ML102920160

WCAP-17269-NP, Revision 0, Analysis of Capsule W from the Comanche Peak Unit No. 2 Reactor Vessel Radiation Surveillance Program.

ML102920160
Person / Time
Site:	Comanche Peak
Issue date:	09/30/2010
From:	Chen J, Leicht A Westinghouse
To:	Office of Nuclear Reactor Regulation
References
WCAP-17269-NP, Rev 0
Download: ML102920160 (237)

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Westinghouse Non-Proprietary Class 3 WCAP-17269-NP September 2010 Revision 0 Analysis of Capsule W from the Comanche Peak Unit No. 2 Reactor Vessel Radiation Surveillance Program Westinghouse

WESTINGHOUSE NON-PROPRIETARY CLASS 3 WCAP-17269-NP Revision 0 Analysis of Capsule W from the Comanche Peak Unit No. 2 Reactor Vessel Radiation Surveillance Program A. E. Leicht*

J. Chen*

September 2010 Reviewer: B. A. Rosier*

Aging Management and License Renewal Services Approved: N. A. Palm* for P. C. Paesano, Manager Aging Management and License Renewal Services

• Electronically Approved Records Are Authenticated in the Electronic Document Management System.

Westinghouse Electric Company LLC P.O. Box 355 Pittsburgh, PA 15230-0355

© 2010 Westinghouse Electric Company LLC All Rights Reserved

iii TABLE OF CONTENTS LIS T OF TA B LE S ........................................................................................................................................ v LIST OF FIG UR ES .................................................................................................................... vii EX E CU TIV E SU M M A RY ................................................................................ 7......................................... ix 1 SU MM ARY OF RE SU LT S .......................................................................................................... 1-1 2 INTRODUCTION ............................................................................................ 2-1 3 B A C K GR OU N D .......................................................................................................................... 3-1 4 DESCRIPTION OF PROGRAM ................. ............................. 4-1 5 TESTING OF SPECIMENS FROM CAPSULE W ..................................................................... 5-1 5.1 O VE RV IE W .................................................................................................................... 5-1 5.2 CHARPY V-NOTCH IMPACT TEST RESULTS ........................................................... 5-3 5.3 TEN SILE TEST RE SU LTS ............................................................................................. 5-5 5.4 1/2T COMPACT TENSION SPECIMEN TESTS ........................................................... 5-5 6 RADIATION ANALYSIS AND NEUTRON DOSIMETRY ................................................... 6-1 6.1 IN T R OD U C TIO N .......................................................................................................... 6-1 6.2 DISCRETE ORDINATES ANALYSIS ...... .................................................................... 6-2 6.3 N EU TRON D O SIM ETRY ........................ :..................................................................... 6-5 6.4 CALCULATIONAL UNCERTAINTIES ........................................................................ 6-5 7 SURVEILLANCE CAPSULE REMOVAL SCHEDULE ....................................................... 7-1 8 RE F ER E N C E S ............................................................................................................................. 8-1 APPENDIX A VALIDATION OF THE RADIATION TRANSPORT MODELS BASED ON NEUTRON DOSIMETRY MEASUREMENTS ............................................................................. A-1 APPENDIX B LOAD-TIME RECORDS FOR CHARPY SPECIMEN TESTS ................................ B-1 APPENDIX C CHARPY V-NOTCH PLOTS FOR EACH CAPSULE USING SYMMETRIC HYPERBOLIC TANGENT CURVE-FITTING METHOD .................................... C-1 APPENDIX D COMANCHE PEAK UNIT 2 SURVEILLANCE PROGRAM CREDIBILITY EVAL UATIO N .............................................................................................................. D -1 APPENDIX E COMANCHE PEAK UNIT 2 UPPER SHELF ENERGY EVALUATION ............... E-I WCAP- 17269-NP September 2010 Revision 0

V LIST OF TABLES Table 4-1 Chemical Composition (wt%) of the Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plates (U nirradiated)(a) ....................................................................................... 4-3 Table 4-2 Chemical Composition (wt%) of the Comanche Peak Unit 2 Reactor Vessel Lower Shell Plates (U nirradiated)a .... ... ......................................... ........................................ 4 4 Table 4-3 Chemical Composition (wt%) of the Comanche Peak Unit 2 Reactor Vessel Weld M aterials (U nirradiated)(a) ............................................................................................ 4-5 Table 4-4 Heat Treatment History of the Comanche Peak Unit 2 Reactor Vessel Surveillance M aterials(a) ....................................................................................................................... 4 -6 Table 5-1 Charpy V-notch Data for the Comanche Peak Unit 2 Intermediate Shell Plate R3807-2 Irradiated to a Fluence of 3.38E+19 n/cm 2 (E > 1.0 MeV) (Longitudinal Orientation) ..5-6 Table 5-2 Charpy V-notch Data for the Comanche Peak Unit 2 Intermediate Shell Plate R3807-2 Irradiated to a Fluence of 3.38E+19 n/cm 2 (E > 1.0 MeV) (Transverse Orientation) ...... 5-7 Table 5-3 Charpy V-notch Data for the Comanche Peak Unit 2 Surveillance Weld Metal Irradiated to a Fluence of 3.38E+19 n/cm 2 (E > 1.0 M eV) .............................................................. 5-8 Table 5-4 Charpy V-notch Data for the Comanche Peak Unit 2 Heat-Affected-Zone (HAZ) Material Irradiated to a Fluence of 3.38E+19 n/cm 2 (E > 1.0 M eV) .............................................. 5-9 Table 5-5 Instrumented Charpy Impact Test Results for the Comanche Peak Unit 2 Intermediate Shell Plate R3807-2 Irradiated to a Fluence of 3.38E+19 n/cm 2 (E > 1.0 MeV)

(Longitudinal O rientation) ............................................................................................. 5-10 Table 5-6 Instrumented Charpy Impact Test Results for the Comanche Peak Unit 2 Intermediate Shell Plate R3807-2 Irradiated to a Fluence of 3.38E+19 n/cm 2 (E > 1.0 MeV)

(Transverse Orientation) ..................................................................  :............................. 5-11 Table 5-7 Instrumented Charpy Impact Test Results for the Comanche Peak Unit 2 Surveillance Weld Metal Irradiated to a Fluence of 3.38E+19 n/cm 2 (E > 1.0 MeV) ........................ 5-12 Table 5-8 Instrumented Charpy Impact Test Results for the Comanche Peak Unit 2 Heat-Affected-Zone (HAZ) Material Irradiated to a Fluence of 3.38E+19 n/cm 2 (E > 1.0 MeV) ........ 5-13 table 5-9 Effect of Irradiation to 3.38E+19 n/cm 2 (E > 1.0 MeV) on the Charpy V-Notch Toughness Properties of the Comanche Peak Unit 2 Reactor Vessel Surveillance Capsule W M aterials ........................................................................................................................ 5 -14 Table 5-10 Comparison of the Comanche Peak 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 Table 5-11 Tensile Properties of the Comanche Peak Unit 2 Capsule W Reactor Vessel Surveillance Materials Irradiated to 3.38E+1 9 n/cm 2 (E > 1.0 MeV) ................................................ 5-16 Table 6-1 Calculated Neutron Exposure Rates and Integrated Exposures at the Surveillance C apsule C enter ................................................................................................................. 6-8 WCAP-17269-NP September 2010 Revision 0

vi Table 6-2 Calculated Azimuthal Variation of Maximum Exposure Rates and Integrated Exposures at the Reactor Vessel Clad/Base Metal Interface .............................. 6-12 Table 6-3 Relative Radial Distribution of Neutron Fluence (E > 1.0 MeV) Within the Reactor Vessel W all ....................................................................................................... 6-16 Table 6-4 Relative Radial Distribution of Iron Atom Displacements (dpa) Within the Reactor Vessel W all ....................................................................................................... 6-17 Table' 6-5 Calculated Fast Neutron Exposure of Surveillance Capsules Withdrawn and Analyzed from C om anche Peak U nit 2 ......................................................................................... 6-17 Table 6-6 Calculated Surveillance Capsule Lead Factors .............................................................. 6-18 Table 7-1 Surveillance Capsule W ithdrawal Summ ary .................................................................... 7-1 Table A-I Nuclear Parameters Used in the Evaluation of Neutron Sensors ............................. A-10 Table A-2 Monthly Thermal Generation During the First Eleven Fuel Cycles of the Comanche Peak Unit 2 Reactor (Reactor Power of 3411 MWt from Startup through 10/7/99, 3445 MWt from 10/7/99 thrugh 10/16/01, and 3458 MWt from 10/16/01 through the End of Cycle

11) ................................................................................................................................. A -1 1 Table A-3 Calculated Cj Factors at the Surveillance Capsule Center Core Midplane Elevation...A-13 Table A-4a Measured Sensor Activities and Reaction Rates Surveillance Capsule U .................... A-14 Table A-4b Measured Sensor Activities and Reaction Rates Surveillance Capsule X ............... A-15 Table A-4c Measured Sensor Activities and Reaction Rates Surveillance Capsule W ............... A-16 Table A-5 Comparison of Measured, Calculated, and Best Estimate Reaction Rates at the Surveillance C apsule C enter ......................................................................................... A -17 Table A-6 Comparison of Calculated and Best Estimate Exposure Rates at the Surveillance C apsule C enter .............................................................. . . ............. A -20 Table A-7 Comparison of Measured/Calculated (M/C) Sensor Reaction Rate Ratios Including all Fast Neutron Threshold Reactions ................................................................................ A -21 Table A-8 Comparison of Best Estimate/Calculated (BE/C) Exposure Rate Ratios ..................... A-21 Table C-I Upper Shelf Energy Values (ft-lb) Fixed in CVGRAPH ........................................... C-Table D-1 Calculation of Chemistry Factors using Comanche Peak Unit 2 Surveillance Capsule Data ............................................................................... ........ ....... ... D -3 Table D-2 Comanche Peak Unit 2 Surveillance Capsule Data Scatter about the Best-Fit Line . D-4 Table E-1 Predicted Positions 1.2 and 2.2 Upper Shelf Energy Values at 36 EFPY ............ E-3 Table E-2 Predicted Positions 1.2 and 2.2 Upper Shelf Energy Values at 54 EFPY ................... E-4 WCAP-1 7269-NP September 2010 Revision 0

vii LIST OF FIGURES Figure 4-1 Arrangement of Surveillance Capsules in the Comanche Peak Unit 2 Reactor Vessel ...4-7 Figure 4-2 Capsule W Diagram Showing the Location of Specimens, Thermal Monitors, and D osimeters ................................................................... .................................. 4-8 Figure 5-1 Charpy V-Notch Impact Energy vs. Temperature for Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Longitudinal Orientation) ............................ 5-17 Figure 5-2 Charpy V-Notch Lateral Expansion vs. Temperature for Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Longitudinal Orientation) ............................ 5-18 Figure 5-3 Charpy V-Notch Percent Shear vs. Temperature for Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Longitudinal Orientation) ............................ 5-19 Figure 5-4 Charpy V-Notch Impact Energy vs. Temperature for Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Transverse Orientation) ............................... 5-20 Figure 5-5 Charpy V-Notch Lateral Expansion vs. Temperature for Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Transverse Orientation) ............................... 5-21 Figure 5-6 Charpy V-Notch Percent Shear vs. Temperature for Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Transverse Orientation) ............................... 5-22 Figure 5-7 Charpy V-Notch Impact Energy vs. Temperature for the Comanche Peak Unit 2 Reactor Vessel Surveillance Program W eld M etal ...................................................................... 5-23 Figure 5-8 Charpy V-Notch Lateral Expansion vs. Temperature for the Comanche Peak Unit 2 Reactor Vessel Surveillance Program Weld M etal ......................................................... 5-24 Figure 5-9 Charpy V-Notch Percent Shear vs. Temperature for the Comanche Peak Unit 2 Reactor Vessel Surveillance Program Weld M etal ...................................................................... 5-25 Figure 5-10 Charpy V-Notch Impact Energy vs. Temperature for the Comanche Peak Unit 2 Reactor Vessel H eat-A ffected-Zone M aterial ............................................................................. 5-26 Figure 5-11 Charpy V-Notch Lateral Expansion vs. Temperature for the Comanche Peak Unit 2 Reactor Vessel Heat-Affected-Zone M aterial ................................................................ 5-27 Figure 5-12 Charpy V-Notch Percent Shear vs. Temperature for the Comanche Peak Unit 2 Reactor Vessel Heat-Affected-Zone M aterial ............................................................................. 5-28 Figure 5-13 Charpy Impact Specimen Fracture Surfaces for Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Longitudinal Orientation) ....................................... 5-29 Figure 5-14 Charpy Impact Specimen Fracture Surfaces for Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Transverse Orientation) .......................................... 5-30 Figure 5-15 Charpy Impact Specimen Fracture Surfaces for the Comanche Peak Unit 2 Reactor Vessel Surveillance Program Weld M etal ................................................................................. 5-31 Figure 5-16 Charpy Impact Specimen Fracture Surfaces for the Comanche Peak Unit 2 Reactor Vessel H eat-A ffected-Zone M aterial ........................................................................................ 5-32 WCAP-17269-NP September 2010 Revision 0

viii Figure 5-17 Tensile Properties for Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R 3807-2 (Longitudinal Orientation) .............................................................................. 5-33 Figure 5-18 Tensile Properties for Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Transverse Orientation) ...................................... 5-34 Figure 5-19 Tensile Properties for, the Comanche Peak Unit 2 Reactor Vessel Surveillance Program Weld Metal .................................................................................................................... 5-35 Figure 5-20 Fractured Tensile Specimens from Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Longitudinal Orientation) .......................................................... 5-36 Figure 5-21 Fractured Tensile Specimens from Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Transverse Orientation) ............................................................... 5-37 Figure 5-22 Fractured Tensile Specimens from the Comanche Peak Unit 2 Reactor Vessel Surveillance Program Weld M etal ............................................................................... 5-38 Figure 5-23 Engineering Stress-Strain Curves for Comanche Peak Unit 2 Intermediate Shell Plate R3807-2 Tensile Specimens CL7, CL8 and CL9 (Longitudinal Orientation) ............... 5-39 Figure 5-24 Engineering Stress-Strain Curves for Comanche Peak Unit 2 Intermediate Shell Plate R3807-2 Tensile Specimens CT7, CT8 and CT9 (Transverse Orientation) ................... 5-40 Figure 5-25 Engineering Stress-Strain Curves for, Comanche Peak Unit 2 Surveillance Program Weld M etal Tensile Specimens CW 7, CW 8 and CW 9 .......................................................... 5-41 Figure 6-1 Comanche Peak Unit 2 r,0 Reactor Geometry with a 12.50 Neutron Pad Span at the C ore M idplane ....................................................................................................... 6-19 Figure 6-2 Comanche Peak Unit 2 r,0 Reactor Geometry with a 20.0' Neutron Pad Span at the C ore M idplane ............................................................................................................... 6-20 Figure 6-3 Comanche Peak-Unit 2 r,0 Reactor Geometry with a 22.50 Neutron Pad Span at the C ore M idplane ............................ I.................................................................

................ 6-2 1 Figure 6-4 Comanche Peak Unit 2 rz Reactor Geometry with Neutron Pad .................................. 6-22 Figure E-1 Regulatory Guide 1.99, Revision 2 Predicted Decrease in Upper Shelf Energy as a Function of Copper and Fluence ..................................................................................... E-2 WCAP-17269-NP September 2010 Revision 0

ix EXECUTIVE

SUMMARY

The purpose of this report is to document the testing results of surveillance Capsule W from Comanche Peak Unit 2. Capsule W was removed at 14.51 EFPY and post-irradiation mechanical tests of the Charpy V-notch and tensile specimens were performed. A fluence evaluation utilizing the neutron transport and dosimetry cross-section libraries was derived from the ENDF/B-VI database. Capsule W received a fluence of 3.38 x 1019 n/cm 2 (E > 1.0 MeV) after irradiation to 14.51 EFPY. The peak clad/base metal interface vessel fluence after 14.51 EFPY of plant operation was 8.76 x 1018 n/cm 2 (E > 1.0 MeV).

This evaluation.led to the following conclusions: 1) The measured percent decrease in upper shelf energy for all the surveillance materials contained in Comanche Peak Unit 2 Capsule W are less than the Regulatory Guide 1.99, Revision 2 [Ref. 1] predictions. 2) The Comanche Peak Unit 2 surveillance plate data is judged to be not credible; however, the weld data is judged to be credible. This credibility evaluation can be found in Appendix D. 3) 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 (54 EFPY) as required by 10 CFR 50, Appendix G [Ref. 2]. The upper shelf energy evaluation is presented in Appendix E.

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.

Upon completion of the Comanche Peak Unit 2 Capsule W testing, one of the thermocouples used to monitor the temperature of the Charpy impact specimens in the thermal soak bath was found to have slightly drifted outside of the calibration range. With the exception of I data point, the largest adjustment

,that could be applied to any test temperature is _0.8°F (Heat Affected Zone (HAZ) Charpy impact specimen CH31, tested at -175'F, potentially fell outside the tolerance range by no more than 2°F).

Even though the Charpy impact specimen test data are input to the curves and evaluations documented in this report, it has been determined based on engineering judgment that this issue does not significantly impact the results contained within this report. The margin term applied to calculations of reference temperature shifts compensates for such small variances in Charpy testing.

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1-1 1

SUMMARY

OF RESULTS The analysis of the reactor vessel materials contained in surveillance Capsule W, the third capsule removed and tested from the Comanche Peak Unit 2 reactor pressure vessel, led to the following conclusions:

" Charpy V-notch test data were plotted using a symmetric hyperbolic tangent curve-fitting program.

Appendix C presents the CVGRAPH, Version 5.3, Charpy V-notch plots for Capsule W and previous capsules, along with the program input data.

• Capsule W received an average fast neutron fluence (E > 1.0 MeV) of 3.38 x1019 n/cm 2 after 14.51 effective full power years (EFPY) of plant operation.

" Irradiation of the reactor vessel Intermediate Shell Plate R3807-2 Charpy specimens, oriented with the longitudinal axis of the specimen parallel to the major working direction (longitudinal orientation), resulted in an irradiated 30 ft-lb transition temperature of 13.8°F and an irradiated 50 ft-lb transition temperature of 61.4°F. This results in a 30 ft-lb transition temperature increase of 23.2'F and a 50 ft-lb transition temperature increase of 33.0°F for the longitudinally oriented specimens.

• Irradiation of the reactor vessel Intermediate Shell Plate R3807-2 Charpy specimens, oriented with the longitudinal axis of the specimen perpendicular to the major working direction (transverse orientation), resulted in an irradiated 30 ft-lb transition temperature of 62.3°F and an irradiated 50 ft-lb transition temperature of 123.9°F. This results in a 30 ft-lb transition temperature increase of 74.4°F and a 50 ft-lb transition temperature increase of 81.8°F for the transversely oriented specimens.

• Irradiation of the Surveillance Program Weld Metal (Heat # 89833) Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 34.4°F and an irradiated 50 ft-lb transition temperature of 50.9°F. This results in a 30 ft-lb transition temperature increase of 84.0°F and a 50 ft-lb transition temperature increase of 51.3°F.

• Irradiation of the Heat-Affected-Zone (HAZ) Material Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of -80.3°F and an irradiated 50 ft-lb transition temperature of -56.6°F.

This results in a 30 ft-lb transition temperature increase of 29.2°F and a 50 ft-lb transition temperature increase of 18.8°F.

• The average upper shelf energy of Intermediate Shell Plate R3807-2 (longitudinal orientation) resulted in an average energy increase of 3.4 ft-lb after irradiation. This results in an irradiated average upper shelf energy of 118.4 ft-lb for the longitudinally oriented specimens.

• The average upper shelf energy of Intermediate Shell Plate R3807-2 (transverse orientation) did not change after irradiation. This results in an irradiated average upper shelf energy of 84.0 ft-lb for the transversely oriented specimens.

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1-2

• The average upper shelf energy of the Surveillance Program Weld Metal Charpy specimens resulted in an average energy decrease of 10.5 ft-lb after irradiation. This results in an irradiated average upper shelf energy of 83.5 ft-lb for the weld metal specimens.

" The average upper shelf energy of the HAZ Material Charpy specimens resulted in an average energy decrease of 5 ft-lb after irradiation. This results in an irradiated average upper shelf energy of 111.0 ft-lb for the HAZ Material.

• A comparison of the measured 30 ft-lb shift in transition temperature values for the Comanche Peak Unit 2 reactor vessel surveillance materials is presented in Table 5-10.

• Based on the credibility evaluation presented in Appendix D, the Comanche Peak Unit 2 surveillance plate data is not credible but the surveillance weld data is credible.

• Based on the upper shelf energy evaluation in Appendix E, 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 10 CFR 50, Appendix G [Ref. 2].

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2-1 2 INTRODUCTION This report presents the results of the examination of Capsule W, the third capsule removed and tested in the continuing surveillance program, which monitors the effects of neutron irradiation on the Luminant Comanche Peak Unit 2 reactor pressure vessel materials under actual operating conditions.

The surveillance program for the Comanche Peak Unit 2 reactor pressure vessel materials was designed and recommended by the Westinghouse Electric Corporation. A description of the surveillance program and the pre-irradiation mechanical properties of the reactor vessel materials are presented in WCAP-10684 [Ref. 3], "Texas Utilities Generating Company Comanche Peak Unit No. 2 Reactor Vessel Radiation Surveillance Program." The surveillance program was planned to cover the 40-year design life of the reactor pressure vessel and was based on ASTM E185-82 [Ref. 4], "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels." Capsule W was removed from the reactor after 14.51 EFPY of exposure and shipped to the Westinghouse Science and Technology Department 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 the post-irradiation data obtained from surveillance Capsule W removed from the Comanche Peak Unit 2 reactor vessel and discusses the analysis of the data.

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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 SA533 Grade B Class 1 (base material of the Comanche Peak 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 Code [Ref. 5]. 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 E208 [Ref. 6]) or the temperature 60'F 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 (KIc curve) which appears in Appendix G to Section XI of the ASME Code

[Ref. 5]. 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 KIc curve, allowable stress intensity factois 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 Comanche Peak Unit 2 reactor vessel radiation surveillance program, in which a surveillance capsule is periodically removed from the operating nuclear reactor and the encapsulated specimens are tested. The increase in the average Charpy V-notch 30 ft-lb temperature (ARTNDT) due to irradiation is added to the initial RTNat, along with a margin (M) to cover uncertainties, to adjust the RTNDT (ART) for radiation embrittlement. This ART (initial RTNDT + M + ARTNDT) is used to index the material to the K1 c 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.

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4-1 4 DESCRIPTION OF PROGRAM Six surveillance capsules for monitoring the effects of neutron exposure on the Comanche Peak Unit 2 reactor pressure vessel core region (beltline) materials were inserted in the reactor vessel prior to initial plant startup. 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 the following:

• Intermediate Shell Plate R3807-2 (longitudinal orientation)

• Intermediate Shell Plate R3807-2 (transverse orientation)

• Weld metal fabricated with 3/16-inch Mil B-4 weld filler wire, Heat Number 89833 Linde Type 124 flux, Lot Number 1061, which is identical to that used in the actual fabrication of the intermediate to lower shell circumferential weld seam

• Weld heat-affected-zone (HAZ) material of Intermediate Shell Plate R3807-2 Test material obtained from the intermediate shell course plate (after thermal heat treatment and forming of the plate) was taken at least one plate thickness from the quenched edges of the plate. All test specimens were machined from the '/4 and 3/4 thickness locations of the plate after performing a simulated post-weld stress-relieving treatment on the test material. Test specimens were also removed from weld and heat-affected-zone metal of a stress-relieved weldment joining Intermediate Shell Plate R3807-2 and adjacent Lower Shell Plate R3816-2. All heat-affected-zone specimens were obtained from the weld heat-affected-zone of Intermediate Shell Plate R3807-2.

Charpy V-notch impact specimens from Intermediate Shell Plate R3807-2 were machined in the longitudinal orientation (longitudinal axis of the specimen parallel to the major rolling direction) and also in the 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 (normal) to the weld direction. The notch of the weld metal Charpy specimens was machined such that the direction of crack propagation in the specimen was in the welding direction.

Tensile specimens from Intermediate Shell Plate R3807-2 were machined in both the longitudinal and transverse orientations. Tensile specimens from the weld metal were oriented perpendicular to the welding direction.

Compact Test (CT) specimens from Intermediate Shell Plate R3807-2 were machined in the longitudinal and transverse orientations. CT specimens from the weld metal were machined with the notch oriented in the direction of welding. All specimens were fatigue pre-cracked according to ASTM E399 [Ref. 7].

All six capsules contained dosimeter wires of pure iron, copper, nickel, and aluminum-0.15 weight percent cobalt (cadmium-shielded and unshielded). In addition, cadmium-shielded dosimeters of Neptunium (237Np) and Uranium (238U) were placed in the capsules to measure the' integrated flux at specific neutron energy levels.

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4-2 The capsules contained thermal monitors made from two low-melting-point eutectic alloys, which were 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: 579°F (304'C) 1.5% Ag, 1.0% Sn, 97.5% Pb Melting Point: 590'F (310°C)

The chemical composition and heat treatment of the unirradiated surveillance materials are presented in Tables 4-1 through 4-4. The data in Tables 4-1 through 4-4 was obtained from the unirradiated surveillance program report, WCAP-10684 [Ref. 3], Appendix A.

Capsule W was removed after 14.51 effective full power years (EFPY) of plant operation. This capsule contained Charpy. V-notch, tensile, 1/2T-CT fracture mechanics specimens, dosimeters, and thermal monitors.

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

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4-3 Table 4-1 Chemical Composition (wt%) of the Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plates (Unirradiated)(a)

IntermediateShell Plate R3807-( Intermediate Shell S Plate R380"7-1 " Intermediate Shell R3807-3 Platea Element .. .

CoCmbustin' Combustion . .. Comjibustion '

.WestingAousenAnalysisi Engieekifg Analysis Engineering Analysis 1 sin.... ... Engineering aiyss C 0.210 0.220 0.220 0.220 Mn 1.420 1.400 1.360 1.300 P 0.006 0.007 0.014 0.007 S 0.015 0.016 0.014 0.009 Si 0.250 0.240 0.250 0.190 Ni 0.640 0.640 0.620 0.600 Mo 0.600 0.590 0.580 0.580 Cr 0.050 0.040 0.056 0.060 Cu 0.060 0.060 0.065 0.050 Al 0.020 0.025 0.018 0.023 Co 0.012 0.013 0.014 0.009 Pb <0.001 <0.001 0.002 <0.001 W <0.01 <0.01 <0.01 <0.01 Ti <0.01 <0.01 0.004 <0.01 Zr <0.001 <0.001 <0.002 <0.001 V 0.002 0.003 <0.002 0.002 Sn 0.003 0.004 0.002 0.003 As 0.004 0.005 0.004 0.005 Cb <0.01 <0.01 <0.002 <0.01 N2 0.009 0.010 0.008 0.007 B <0.001 <0.001 <0.001 <0.001 Notes:

(a) Data obtained from WCAP-10684, Rev. 0 [Ref. 3].

(b) Surveillance program test plate.

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4-4 Table 4-2 Chemical Composition (wt%) of the Comanche Peak Unit 2 Reactor Vessel Lower Shell Plates (Unirradiated)(a)

Lower hl PaeLShellhell Plt Lwr'Sh~llPlate

'R3816-1 ~ -R381&1: R8f4

.*::~ ~ , ~ ~~~C ,* .*" omistionirEniriieeriiig Analy~sis*o, *".3 .,

C 0.230 0.230 0.220 Mn 1.480 1.480 1.500 P 0.001 0.002 0.008 S 0.004 0.012 0.008 Si 0.190 0.210 0.190 Ni 0.590 0.650 0.630 Mo 0.490 0.500 0.520 Cr 0.030 0.030 0.040 Cu 0.050 0.030 0.040 Al 0.026 0.026, 0.018 Co 0.020 0.012 0.012 Pb <0.001 <0.001 <0.001 W <0.01 <0.01 <0.01 Ti <0.01 <0.01 <0.01 Zr <0.001 <0.001 <0.001 V 0.003 0.003 0.003 Sn 0.001 0.001 0.002 As 0.009 0.011 0.015 Cb <0.01 <0.01 <0.01 N, 0.028 0.014. 0.014-B <0.001 <0.001 <0.001 Note:

(a) Data obtained from WCAP-10684, Rev. 0 [Ref. 3].'

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4-5 Table 4-3 Chemical Composition (wt%) of the Comanche Peak Unit 2 Reactor Vessel Weld Materials (Unirradiated)(a)

Longituinallosingl IfInterimediate and Lower Shelltmngiu urveillance WeldmentC Weld 'Se-ams' Ci* Seamee* sWeld .... nc e thrcumferential (Identicaltothe e

,~. ~~ ~ ~ ~~~ap

.. ,p _uction rod.. .. ,, " sem  :*: , .Closing Element Wiir Flux Test Weld SamplePr~duction Weld Seam No. Wire Flux Test Weld CircumferentialWeld Sample 1.1_l42A~b Sample Seam).

Combustion Combustion Combustion Engineering Analysis Engineering Analysis Engineering Analysis Westinghouse C 0.160 0.160 0.088 0.110 Mn 1.320 1.240 1.330 1.370 P 0.005 0.004 0.004 0.011 S 0.011 0.009 0.010 0.014 Si 0.160 0.190 0.510 0.490 Ni 0.050 0.080 0.030 0.072 Mo 0.540 0.590 0.540 0.590 Cr 0.020 0.020 0.030 0.058 Cu 0.700 0.050 0.050 0.030 Al - 0.004 - 0.006 Co 0.011 - 0.008 Pb <0.001 - 0.001 W - 0.010 - <0.01 Ti - <0.01 - 0.002 Zr - 0.001 - <0.002 V 0.004 0.005 0.003 <0.002 Sn - 0.003 - 0.003 As - 0.021 - 0.018 Cb - <0.01 - <0.002 N2 - 0.007 - 0.008 B - 0.001 0.001 Notes:

(a) Data obtained from WCAP-1 0684, Rev. 0 [Ref. 31.

(b) Actual beltline production weld chemistry (Lower Shell Plate Seam No. 101-142A).

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4-6 Table 4-4 Heat Treatment History of the Comanche Peak Unit 2 Reactor Vessel Surveillance Materials(a)

Material Temperutfe (07F) Time (hours Cooling, Austenitized @ 1600 4 2(81C)4.00 25 (871-C) Water-Quenched Intermediate Shell Plates R3807-1, R3807-2, and 4.00 Air-Cooled R3807-3 (663-C)

Stress Relieved @ 1150 19.25(b) Furnace-Cooled

+/- 50 (621°C)

Austenitized @ 1600 25(7 0 *

)4.00 Water-Quenched 25 (871°C)

Lower Shell Plates R3816-1, Tempered @ 1225 +/- 25 4.00 Air-Cooled R3816-2, and R3816-3 (663°C)

Stress Relieved @ 1150 14.5(b) Furnace-Cooled

+/- 50 (621-C)

Intermediate Shell Stress Relieved @ 1150 19.25(b) Furnace-Cooled Longitudinal Weld Seams +/- 50 (621°C)

Lower Shell Longitudinal Stress Relieved @ 1150 14.5(b) Furnace-Cooled Weld Seams +/- 50 (621°C)

Intermediate to Lower Shell Local Stress Relieved @ 8.00 Furnace-Cooled Circ. Weld Seam 1150 + 50 (621°C)

.:,,~~ ~ ~ ~ ,*~ S~ela

.:-::.,',, § Uo eoProgi-Am Test Mate iaI,, , *:',- .. > ,

V Srveillan g_

Surveillance Program Test Post Weld Stress Plate."D" (Representative of Relieved @ 1150 +/- 50 8.5(c) Furnace-Cooled Closing Circ. Weld Seam) (621 C)

Notes:

(a) Data obtained from WCAP-10684, Rev. 0 [Ref. 3].

(b) Stress Relief includes the intermediate to lower shell closing circ. seam post weld heat treatment.

(c) The stress relief heat treatment received by the surveillance test weldment has been simulated.

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4-7 (3OV5") Z *CAPSULE U 468.S-6)

-V jis, o 270.- -1 904 (241 '1 Y W 1121-5 1236,5*) . X FIEACTOR wE59 140" PLAN VIEW ELEVA1"ON MIEW Figure 4-1 Arrangement of Surveillance Capsules in the Comanche Peak Unit 2 Reactor Vessel WCAP-17269-NP September 2010 Revision 0

4-8 LEGEND: CL - INTERMEDIATE SHELL PLATE R3807-2 (LONGITUDINAL)

CT - INTERMEDIATE SHELL PLATE R3807-2 (TRANSVERSE)

CW - WELD METAL (HEAT # 89833)

CH - HEAT AFFECTED ZONE MATERIAL Large Spacer Tensiles Compacts Compacts Charpys Charpys Charpys CW424 CW39 CH39 CW38 CH38 CW37 CH37 TOP OF VESSEL CENTER Compacts CL12 CL11 CENTER CENTER CENTER BOTTOM OF VESSEL Figure 4-2 Capsule W Diagram Showing the Location of Specimens, Thermal Monitors, and Dosimeters WCAP- 17269-NP September 2010 Revision 0

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 at the Remote Metallographic Facility at the Westinghouse Research and Technology Department (RTU). Testing was performed in accordance with 10 CFR 50, Appendices G and H [Ref. 2],

ASTM Specification E185-82 [Ref. 4], and Westinghouse Procedure RMF 8402, Revision 3 [Ref. 8] as detailed by Westinghouse RMF Procedures 8102, Revision 3 [Ref. 9], and 8103, Revision 2 [Ref. 10].

The capsule was opened upon receipt at the hot cell laboratory per Procedure RMF 8804, Revision 3

[Ref. I I]. The specimens and spacer blocks were carefully removed, inspected for identification number, and checked against the master list in WCAP-10684 [Ref. 3]. All items were in their proper locations.

Examination of the thermal monitors indicated that none of the melting point monitors had melted. Based on this examination, the .maximum temperature to which the specimens were exposed was less than 579°F (304°C).

The Charpy impact tests were performed per ASTM Specification E23-07a [Ref. 12] and Procedure RMF 8103 on a Tinius-Olsen Model 74, 358J machine. The tup (striker) of the Charpy machine is instrumented with an Instron Impulse instrumentation system, feeding information into a 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 (TM) 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 (EM) 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 (ay) was calculated from the three-point bend formula having the following expression [Ref. 13]:

yY = PGY B(W--a)22 C (Eqn. 5-1) 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 p = 450 and p = 0.010 in., Equation 5-1 is valid with C = 1.21.

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

L 3.305 PGYW ayPGY B(W-a)22 1.21 B(W- a) 2 (Eqn. 5-2)

For the Charpy specimen, B = 0.394 in., W = 0.394 in., and a = 0.079 in. Equation 5-2 then reduces to:

CrY = 3 3 .3 PGY (Eqn. 5-3) where c5y is in units of psi and PGY is in units of lb. 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(W - a) = 0.1241 sq. in. (Eqn. 5-4)

Percent shear was determined from post-fracture photographs using the ratio-of-areas methods in compliance with ASTM E23-07a [Ref. 12] and A370-09 [Ref. 14]. 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 (Model 1115) per ASTM Specifications E8-09 [Ref. 15] and E21-09 [Ref. 16] and Procedure RMF 8102 [Ref. 9].

Extension measurements were made with a linear variable displacement transducer (LVDT) 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 was 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.

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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 3.38 x 10"9 n/cm2 (E > 1.0 MeV) in 14.51 EFPY of operation, are presented in Tables 5-1 through 5-8 and are compared with the unirradiated and previously withdrawn capsule results as shown in Figures 5-1 through 5-12. The unirradiated and previously withdrawn capsule results were taken from WCAP-10684 [Ref. 3], WCAP-14315 [Ref. 17], and WCAP-16277-NP [Ref. 18].

The transition temperature increases and changes in upper shelf energies for the Capsule W materials are summarized in Table 5-9 and led to the following results:

" Irradiation of the reactor Vessel Intermediate Shell Plate R3807-2 Charpy specimens, oriented with the longitudinal axis of the specimen parallel to the major working direction (longitudinal orientation), resulted in an irradiated 30 ft-lb transition temperature of 13.8°F and an irradiated 50 ft-lb transition temperature of 61.4°F. This results in a 30 ft-lb transition temperature increase of 23.2°F and a 50 ft-lb transition temperature increase of 33.0°F for the longitudinally oriented specimens.

• Irradiation of the reactor vessel Intermediate Shell Plate R3807-2 Charpy specimens, oriented with the longitudinal axis of the specimen perpendicular to the major working direction (transverse orientation), resulted in an irradiated 30 ft-lb transition temperature of 62.3°F and an irradiated 50 ft-lb transition temperature of 123.9°F. This results in a 30 ft-lb transition temperature increase of 74.4°F and a 50 ft-lb transition temperature increase of 81.8 0 F for the transversely oriented specimens.

• Irradiation of the Surveillance Program Weld Metal (Heat # 89833) Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 34.4°F and an irradiated 50 ft-lb transition temperature of 50.9°F. This results in a 30 ft-lb transition temperature increase of 84.0°F and a 50 ft-lb transition temperature increase of 51.3°F.

" Irradiation of the Heat-Affected-Zone (HAZ) Material Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of -80.3°F and an irradiated 50 ft-lb transition temperature of -56.6°F.

This results in a 30 ft-lb transition temperature increase of 29.2°F and a 50 ft-lb transition temperature increase of 18.8°F.

• The average upper shelf energy of the Intermediate Shell Plate R3807-2 (longitudinal orientation) resulted in an average energy increase of 3.4 ft-lb after irradiation to 3.38 x 1019 n/cm 2 (E > 1.0 MeV). This results in an irradiated average upper shelf energy of 118.4 ft-lb for the longitudinally oriented specimens.

" The average upper shelf energy of the Intermediate Shell Plate R3807-2 (transverse orientation) did not change after irradiation to 3.38 x 1019 n/cm2 (E > 1.0 MeV). This results in an irradiated average upper shelf energy of 84.0 ft-lb for the transversely oriented specimens.

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5-4

" The average upper shelf energy of the weld metal Charpy specimens resulted in an average energy decrease of 10.5 ft-lb after irradiation to 3.38 x 1019 n/cm 2 (E > 1.0 MeV). This results in an irradiated average upper shelf energy of 83.5 ft-lb for the weld metal specimens.

" The average upper shelf energy of the HAZ Material Charpy specimens resulted in an average energy decrease of 5 ft-lb after irradiation to 3.38 x 1019 n/cm 2 (E > 1.0 MeV). This results in an irradiated average upper shelf energy of 111.0 ft-lb for the HAZ Material.

• Comparisons of the measured 30 ft-lb shift in transition temperature values and upper shelf energy decreases to those predicted by Regulatory Guide 1.99, Revision 2 [Ref. 1] for the Comanche Peak Unit 2 reactor vessel surveillance materials are presented in Table 5-10.

The fracture appearance of each irradiated Charpy specimen from the various materials is shown in Figures 5-13 through 5-16. The fractures show an increasingly ductile or tougher appearance with increasing test temperature. Load-time records for the individual instrumented Charpy specimens are contained in Appendix B.

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 10 CFR 50, Appendix G [Ref, 2]. This evaluation can be found in Appendix E.

September 2010 WCAP- 17269-NP September 2010 Revision 0

5-5 5.3 TENSILE TEST RESULTS The results of the tensile tests performed on the various materials contained in Capsule W irradiated to 3.38E+19 n/cm 2 (E > 1.0 MeV) are presented in Table 5-11 and are compared with unirradiated results as shown in Figures 5-17 through 5-19.

The results of the tensile tests performed on the Intermediate Shell Plate R3807-2 (longitudinal orientation) indicated that irradiation to 3.38E+19 n/cm 2 (E > 1.0 MeV) caused approximately an 8 ksi increase in the 0.2 percent offset yield strength and approximately a 6 to 7 ksi increase in the ultimate tensile strength when compared to unirradiated data [Ref. 3]. See Figure 5-17 and Table 5-11.

The results of the tensile tests performed on the intermediate Shell Plate R3807-2 (transverse orientation) indicated that irradiation to 3.38E+19 n/cm 2 (E > 1.0 MeV) caused approximately a 9 to 10 ksi increase in the 0.2 percent offset yield strength and approximately a 6 to 8 ksi increase in the ultimate tensile strength when compared to unirradiated data [Ref. 3]. See Figure 5-18 and Table 5-11.

The results of the tensile tests performed on the surveillance weld metal indicated that irradiation to 3.38E+19 n/cm2 (E > 1.0 MeV) caused approximately a 7 to 8 ksi increase in the 0.2 percent offset yield strength and approximately a 5 to 6 ksi increase in the ultimate tensile strength when compared to unirradiated data [Ref. 3]. See Figure 5-19 and Table 5-11.

The fractured tensile specimens for the Intermediate Shell Plate R3807-2 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 Research and Technology Department.

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5-6 Table 5-1 Charpy V-notch Data for the Comanche Peak Unit 2 Intermediate Shell Plate R3807-2 Irradiated to a Fluence of 3.38E+19 n/cm 2 (E > 1.0 MeV) (Longitudinal Orientation)

Sample Temperature Imp Energy Lateral Expansion Shear:

Number FC ft-lbs Joules mils, mm  %

CL36 -50 -46 7 9 5 0.13 5 CL38 -20 -29 19 26 15 0.38 10 CL44 -15 -26 14 19 12 0.30 10 CL33 -10 -23 38 51 29 0.74 20 CL39 0 -18 32 43 27 0.69 15 CL41 25 -4 34 46 27 0.69 15 CL42 40 4 44 60 34 0.86 25 CL45 60 16 43 58 34 0.86 25 CL34 80 27 56 76 45 1.14 40 CL31 125 52 75 102 61 1.55 60 CL35 200 93 110 149 84 2.13 100 CL43 275 135 117 159 83 2.11 100 CL40 300 149 118 160 80 2.03 100 CL32 325 163 123 167 85 2.16 100 CL37 350 177 124 168 77 1.96 100 WCAP-1 7269-NP September 2010 Revision 0

5-7 Table 5-2 Charpy V-notch Data for the Comanche Peak Unit 2 Intermediate Shell Plate R3807-2 Irradiated to a Fluence of 3.38E+19 n/cm 2 (E > 1.0 MeV) (Transverse Orientation)

Sample , Temperature , , Impact Energy Lateral Expainsion, , Shear Number F C ft-lbs Joules mils mm.  %

CT43 -90 -68 7 9 5 0.13 2 CT39 30 -1 18 24 17 0.43 15 CT31 50 10 31 42 28 0.71 25 CT34 55 13 23 31 21 0.53 20 CT41 65 18 34 46 31 0.79 25 CT44 75 24 46 62 35 0.89 25 CT38 100 38 42 57 38 0.97 45 CT33 125 52 43 58 44 1.12 40 CT42 130 54 50 68 47 1.19 40 CT45 140 60 46 62 44 1.12 40 CT32 150 66 58 79 48 1.22 75 CT36 200 93 75 102 60 1.52 95 CT35 275 135 85 115 62 1.57 100 CT40 300 149 88 119 66 1.68 100 CT37 325 163 88 119 68 1.73 100 WCAP-17269-NP September 2010 Revision 0

5-8 Table 5-3 Charpy V-notch Data for the Comanche Peak Unit 2 Surveillance Weld Metal Irradiated to a Fluence of 3.38E+19 n/cm 2 (E > 1.0 MeV)

Sample Temperature Impact Energy, Lateral Expansion Sliear%

0 Number 'OF C ft-lbs Joules Rmils mm 6/6, CW38 -90 -68 5 7 5 0.13 5 CW40 25 -4 21 28 24 0.61 50 CW45 30 -1 17 23 18 0.46 40 CW33 30 -1 25 34 29 0.74 50 CW43 35 2 31 42 30 0.76 55 CW42 40 4 32 43 29 0.74 55 CW35 45 7 44 60 43 1.09 60 CW31 45 7 59 80 52 1.32 65 CW32 50 10 60 81 50 1.27 70 CW41 50 10 35 47 41 1.04 55 CW36 75 24 65 88 55 1.40 80 CW44 175 79 74 100 67 1.70 98 CW37 275 135 86 117 78 1.98 100 CW39 300 149 87 118 76 1.93 100 CW34 325 163 87 118 69 1.75 100 WCAP-17269-NP September 2010 Revision 0

5-9 Table 5-4 Charpy V-notch Data for the Comanche Peak Unit 2 Heat-Affected-Zone (HAZ)

Material Irradiated to a Fluence of 3.38E+19 n/cm 2 (E > 1.0 MeV)

Sample Temperature 'Impact Energy Lateral Expansion Shear Number 0 oC ft-lbs Joules mils mm W CH31 -175 -115 5 6 3 0.08 2 CH39 -90 -68 18 24 11 0.28 15 CH44 -80 -62 18 24 10 0.25 20 CH33 -75 -59 41 56 25 0.64 30 CH42 -75 -59 60 81 36 0.91 60 CH37 -70 -57 16 22 12 0.30 15 CH43 -65 -54 62 84 38 0.97 60 CH41 -60 -51 74 100 40 1.02 50 CH34 -60 -'51 27 37 19 0.48 45 CH36 -60 -51 25 34 18 0.46 25 CH38 -50 -46 57 77 36 0.91 45 CH32 -25 -32 79 107 45 1.14 70 CH45 200 93 93 126 64 1.63 98 CH40 225 107 147 199 80 2.03 100 CH35 275 135 93 126 62 1.57 100 WCAP-17269-NP September 2010 Revision 0

5-10 Table 5-5 Instrumented Charpy Impact Test Results for the Comanche Peak Unit 2 Intermediate Shell Plate R3807-2 Irradiated to a Fluence of 3.38E+19 n/cm 2 (E > 1.0 MeV) (Longitudinal Orientation)

Test"Charpy Normalize 2nergies General .

STe Ergy, (ft-lb/in ) Yield Time to Max. Time to Fract. Arrest Yield Flow Nl Temp. E , Load, PGI Load, , PM Load, Load, Stress Stress (OF) . El Total At PM -Prop. _ p (rnsec) -PM (b),J' (msec) PF (lb) PA,(lb) (ksi) (ksi)

(ft-ib) ED/A EM/A Ep/A (lb)

CL36 -50 7 57 26 32 2260 0.01 4016 0.09 3333 0 75 104 CL38 -20 17 140 120 20 1432 0.01 3902 0.29 3868 0 48 89 CL44 -15 12 97 27 70 572 0.00 3843 0.09 3502 0 19 74 CL33 -10 35 280 227 52 2187 0.01 4068 0.50 4019 0 73 104 CL39 0 28 229 211 18 2181 0.01 3996 0.47 3993 0 73 103 CL41 25 29 231 223 9 2169 0.01 4016 0.50 3971 0 72 103 CL42 40 37 298 273 25 2075 0.01 4002 0.62 3872 0 69 101 CL45 60 34 275 261 14 2163 0.01 3926 0.60 3909 0 72 101 CL34 80 48 383 263 120 1976 0.02 3918 0.61 3732 895 66 98 CL31 125 68 551 253 298 2179 0.01 3851 0.60 3364 1855 73 100 CL35 200 100 810 253 557 2033 0.01 3725 0.62 n/a n/a 68 96 CL43 275 106 858 311 547 2080 0.02 3633 0.77 n/a n/a 69 95 CL40 300 108 869 314 554 1931 0.05 3771 0.80 n/a n/a 64 95 CL32 325 113 909 242 667 2046 0.01 3704 0.60 n/a n/a 68 96 CL37 350 112 902 243 659 3412 0.44 3640 0.63 n/a n/a 114 117 September 2010 WCAP- 17269-NP September 2010 Revision 0

5-11 Table 5-6 Instrumented Charpy Impact Test Results for the Comanche Peak Unit 2 Intermediate Shell Plate R3807-2 Irradiated to a Fluence of 3.38E+19 n/cm 2 (E > 1.0 MeV) (Transverse Orientation)

Test Charpy' Normalized-Energies General .

Ene ry, (ft-lb/in 2.) Yield Time to Max. Time to Fract.. Arrest Yield- Flow Sample Temp. Energy,, Load, PGY Load, PM" Load; Load, Stress Stress No.

em) ED Total At PM PrOP. PGY (msec), PM (lb) (msec) PF (lb) PA (lb) (ksi) (ksi)ý

. -(ft-lb) ED/A EEM/A Ep/A (ib).

CT43 -90 7 57 34 23 928 0.01 4311 0.11 4307 0 31 87 CT39 30 14 113 26 87 923 0.01 3789 0.09 3665 0 31 78 CT31 50 23 187 146 Al 1722 0.01 3778 0.36 3757 0 57 92 CT34 55 16 126 114 12 1463 0.01 3732 0.29 3732 0 49 87 CT41 65 26 207 196 11 2165 0.01 3814 0.46 3814 0 72 100 CT44 75 40 320 222 97 2074 0.01 4037 0.50 4023 221 69 102 CT38 100 35 281 199 82 2038 0.01 3750 0.48 3712 146 68 96 CT33 125 36 288 173 115 2033 0.01 3621 0.43 3521 960 68 94 CT42 130 44 353 193 160 2096 0.01 3698 0.47 3416 1530 70 96 CT45 140 41 331 193 138 2138 0.01 3676 0.47 3331 1417 71 97 CT32 150 49 393 193 200 1882 0.01 3637 0.48 3564 1810 63 92 CT36 200 68 548 246 302 2023 0.01 3694 0.60 3290 2748 67 95" CT35 275 78 632 183 448 1925 0.01 3554 0.48 n/a n/a 64 91 CT40 300 81 653 186 467 1735 0.01 3592 0.48 n/a n/a 58 89 CT37 325 81 649 231 418 1695 0.01 3486 0.60 n/a n/a 56 86 WCAP-17269-NP September 2010 Revision 0

5-12 Table 5-7 Instrumented Charpy Impact Test Results for the Comanche Peak Unit 2 Surveillance Weld Metal Irradiated to a Fluence of 3.38E+19 n/cm 2 (E > 1.0 MeV)

Normalized Energies General Test Energy, (ft-lb/in 2 ) Yield Time to Max, Time to Fract. Arrest Yield Flow Sample Temp. ne-ED , Load, PGY Load, PM .. Load,, Load, -Stress,, Stress No. E (OF) (ft-lb). Total At PM -Prop. Pcy (msec) PM-Qb).- (msec) PF(0b) 'PA(lb) (ksi) (ksi)

ED/A Em/A Ep/A (lb)

CW38 -90 5 41 29 13 2161 0.02 4118 0.09 4053 0 72 105 CW40 25 16 127 24 102 2240 0.01 3675 0.09 3149 391 75 98 CW45 30 10 78 26 52 2219 0.02 3728 0.09 3530 0 74 99 CW33 30 22 176 26 150 2135 0.02 3657 0.09 3412 716 71 96 CW43 35 24 196 26 171 2177 0.01 3668 0.09 3609 238 72 97 CW42 40 25 204 26 178 2160 0.01 3721 0.09 3638 423 72 98 CW35 45 37 297 200 97 2099 0.01 3687 0.48 3673 1457 70 96 CW31 45 53 423 258 165 2192 0.02 3806 0.60 3617 1903 73 100 CW32 50 53 429 269 160 2019 0.02 3875 0.62 3591 1006 67 98 CW41 50 31 248 113 136 2141 0.02 3620 0.29 3452 1019 71 96 CW36 75 60 480 200 280 2309 0.02 3750 0.47 3230 2064 77 101 CW44 175 68 549 238 311 2235 0.02 3523 0.60 2570 2197 74 96 CW37 275 80 643 233 410 2220 0.02 3540 0.60 n/a n/a 74 96 CW39 300 80 644 235 409 2152 0.02 3531 0.61 n/a n/a 72 95 CW34 325 81 649 233 416 2133 0.02 3488 0.60 n Ia n/a 71 94 September 2010 WCAP- 17269-NP WCAP-17269-NP September 2010 Revision 0

5-13 Table 5-8 Instrumented Charpy Impact Test Results for the Comanche Peak Unit 2 Heat-Affected-Zone (HAZ) Material Irradiated to a Fluence of 3.38E+19 n/cm2 (E > 1.0 MeV)

Te. t CNormalized Energies General 2

Sample S Test Temp.I ry(ft-lb/in Energy, ) Yield Time to Max.: Time to Fract. Arrest Yield Flow Temp., ED'DNo. Load, PGY .. Load, " PM Load, Load, -Stress Stress (OF) (ft-lb) Total At PM Prop. PGY (msec) PM (lb)_ (msec) PF (lb) PA (lb) (ksi) (ksi)

ED/A EM/A Ep/A (lb)

CH31 -175 5 39 32 7 2284 0.02 4912 0.09 4676 0 76 120 CH39 -90 17 138 30 109 2284 0.01 4392 0.09 4178 0 76 111 CH44 -80 14 112 30 83 2266 0.00 4442 0.09 3893 124 75 112 CH33 -75 34 275 29 246 2152 0.01 4428 0.09 4317 0 72 110 CH42 -75 51 414 29 386 2143 0.01 4409 0.09 4082 1090 71 109 CH37 -70 13 106 28 78 2040 0.01 4277 0.09 3835 0 68 105 CH43 -65 53 427 30 398 2169 0.01 4311 0.09 3404 1293 72 108 CH41 -60 67 536 303 233 2045 0.01 4466 0.62 3882 1095 68 108 CH34 -60 23 182 29 153 2137 0.01 4326 0.09 3398 1268 71 108 CH36 -60 21 168 27 141 2275 0.01 4359 0.09 3986 0 76 110 CH38 -50 51 413 298 115 2287 0.02 4351 0.62 4202 297 76 111 CH32 -25 71 572 299 273 2274 0.01 4368 0.61 4046 1952 76 111 CH45 200 84 678 249 428 2250 0.02 3752 0.60 n/a n/a 75 100 CH40 225 136 1093 415 678 2170 0.01 3908 0.94 n/a n/a 72 101 CH35 275 86 697 263 433 2015 0.01 3812 0.62 n/a n/a 67 97 WCAP- 17269-NP September 2010 Revision 0

5-14 Table 5-9 Effect of Irradiation to 3.38E+19 n/cm 2 (E > 1.0 MeV) on the Charpy V-Notch Toughness Properties of the Comanche Peak Unit 2 Reactor Vessel Surveillance Capsule W Materials Average 30 ft-lb Transition Average 35 mil Lateral Expansion, Average 50 ft-lb Transition Average Energy Absorptionat Material - Temperature(a)_ (OF) Temperature(a) (OF) -Temperature(a) (oF) Full Shear(a) .(ft-lb)

.Unirradiated Irradiated AT Unirradiated Irradiated' AT Unirradiated Irradiated AT Unirradiated Irradiated AE Intermediate Shell Plate -9.4 13.8 23.2 33.4 45.8 12.4 28.4 61.4 33 115 118.4 3.4 R3807-2 (LT),

Intermediate Shell Plate -12.1 62.3 74.4 39.1 89.6 50.5 42.1 123.9 81.8 84 84 0 R3807-2 (TL)

Surveillance Program -49.6 34.4 84 0.7 39.3 38.6 -0.4 50.9 51.3 94 83.5 -10.5 Weld Metal (Heat #89833)

HAZ Material -109.5 -80.3 29.2 -48.9 -47.5 1.4 -75.4 -56.6 18.8 116 111 -5 Note:

(a) Average value is determined by CVGraph (see Appendix C).

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5-15 Table 5-10 Comparison of the Comanche Peak Unit 2 Surveillance Material 30 ft-lb Transition Temperature Shifts and Upper Shelf Energy Decreases with Regulatory Guide 1.99, Revision 2, Predictions Capsule 30 ft-lb Transition

'tempera re U USE Decrease Fluence Temperature Shift i C (x 10!9 n/cm 2, Predicted Measured Predicted Measured "E 1.0MeV) , (9F) (a) (0F) (b) (06) (a) (%)(b)

Intermediate Shell Plate U 0.317 25.3 1.6 15 -- -

R3807-2 X 2.16 44.7 1.6 23 - - -

(Longitudinal) W 3.38 48.8 23.2 26 1 Intermediate Shell Plate U 0.317 25.3 23.4 15 R3807-2 X 2.16 44.7 52.9 23 (Transverse) W 3.38 48.8 74.4 26 0 U 0.317 20.7 3.6 15 10 Surveillance Program Weld Metal X 2.16 36.6 48.2 23 -- -

W 3.38 40.0 84.0 26 11 U 0.317 --- 0.0(c) --- ---

Heat Affected Zone Material X 2.16 --- 26.2 -- - 0 W 3.38 29.2 --- 4 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 by CVGraph Version 5.3 using measured Charpy data (See Appendix C).

(c) Measured ARTNDT value was determined to be negative, but physically a reduction should not occur; therefore, a conservative value of zero is used.

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5-16 Table 5-11 Tensile Properties of the Comanche Peak Unit 2 Capsule W Reactor Vessel Surveillance Materials Irradiated to 3.38E+19 n/cm 2 (E > 1.0 MeV) 02%

Test Yield Ultimate Fracture Fracture Fracture Uniform Total Reduction Maeral Material Sample Numbe Til Temp. Strength Strength Load Stress Strength Elongation Elongation -in Area (9F) (ksi) (ksi).-- (kip) - (ksi) (ksi) (%) .  %

CL7 100 75.3 95.2 3.13 195.7 63.7 10.4 23.1 67 Intermediate Shell Plate R3807-2 CL8 200 72.0 90.7 3.00 168.0 61.1 9.3 21.6 64 (Longitudinal) CL9 550 68.1 91.7 3.30 162.7 67.2 1.8 18.0 59 CT7 100 75.9 95.7 3.30 169.6 67.2 10.5 23.9 60 Intermediate Shell Plate R3807-2 CT8 200 72.2 91.2 3.10 162.8 63.2 8.9 21.0 61 (Transverse) CT9 550 69.3 92.2 3.45 157.1 70.3 8.9 18.6 55 CW7 100 75.6 90.1 2.93 187.6 59.6 9.9 23.6 68 Weld Metal CW8 200 73.2 87.1 2.85 182.8 58.1 9.2 22.7 68 (Heat # 89833)

CW9 550 69.6 89.1 3.18 177.7 64.7 9.6 20.2 64 September 2010 WCAP- 17269-NP September 2010 Revision 0

5-17 IS PLATE R3807-2 (LONGITUDINAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 05/21/2010 03:21 PM Data Set(s) Plotted CulNe Plant Capsule Material Ori. Real #*

Comanche Peak 2 UNIRR SA533BI LT C5522-2 Comranche Me~c U SA5 33BI manche Y SA533B I 4 Comanche Peak 2 W SA533BI LT C55 2-2 300 250 4 200 150

~100 so

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F 01 02 03 4 Results Fleene [SE USE d&USE T @30 d-T @30 T @50 d-T @50 1 2.2 115.0 .0 -9.4 .0 28. 4 .0 2 2.2 118.0 3.0 -7.8 1.6 26. 9 -1.5 3 2.2 120.0 5.0 -7.8 1.6 31.5 3.1 4 2.2 118.4 3.4 13.8 23.2 61.4 33.0 Figure 5-1 Charpy V-Notch Impact Energy vs. Temperature for Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Longitudinal Orientation)

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5-18 IS PLATE R3807-2 (LONGITUDINAL)

CVGRAPH 5.3 H)perbolic Tangent Curve Printed on 05/21/2010 03:24 PM Data Set(s) Plotted Cu4ve Plant Capsule Material Ori.

Comanche Peak 2 UNIRR SA533BI LT Heat

1. 2 Comancnf jSA533BI C5522-2 4 Comanche Peak 2 W SA533B1 LT 200 150 3100 Is 5O 0o-

-300.0 0.0 300.0 600.0 Temperature in Deg F 0 1 a2 03 4 Resaft Curve Flueace LSE USE d-USE T @35 a1-T 035

.0 82. 8 .0 33.4 .0 2 .0 82. 5 -. 4 19.4 -14.0 3 .0 78. 3 -4.5 42.2 8.8 4 .0 83. 8 .9 45.8 12.4 Figure 5-2 Charpy V-Notch Lateral Expansion vs. Temperature for Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Longitudinal Orientation)

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5-19 IS PLATE R3807-2 (LONGITUDINAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 05/21/2010 03:23 PM Data Set(s) Plotted Curve Plant Capsule Material On.

I Comanche Peak 2 UNIRR SA533Bi LT C55 22 aSA53jBl 4 Comalcne Pe1 y SA IB1 LT Comanche Peak 2 W SA533B! C5522-2 1256 100.

75-IJ a,

s50o 25 0o

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Dog F 0 1 "2 0 3 Result Curve Fluence ISE USE d-USE T @50 d-T @00

.0 100.0 .0 56.0 .0 2 .0 100.0 .0 85.0 29. 0 3 .0 100.0 .0 73.6 17.6 4 .0 100.0 .0 97.6 41.6 Figure 5-3 Charpy V-Notch Percent Shear vs. Temperature for Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Longitudinal Orientation)

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5-20 IS PLATE R3W0-2 (TRANSVERSE)

CVGRAPH 5.3 Hj)Terbolic Tangent Curve Printed on 05/21/2010 03:29 PM Data Set(s) Plotted Curve Plant Capsule miaterial Od.

CHeat-2 Comanche Peak 2 UNIRR SA533HI TL Comnc1 Pj4 Fomanch Pa U

X SA;3jBI SA . IB C5522-2 4 Comanche Peak2 W SA53391 TL 300 250 4 200 p15 w

~100 so 0 lp

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Dog F 0 1 02 *3 4 Curie Fluence ISE USE tiUSE T@30 dtT @30 T 0S0 d-T @50 2.2 84. 0 .0 -12.1 .0 42. I .0 2 2.2 88.0 4.0 11.3 23.4 63. 2 21.1 3 2.2 91.0 7.0 40.8 52.9 94. 6 52.5 4 2.2 84. 0 .0 62.3 74. 4 123.9 81.8 Figure 5-4 Charpy V-Notch Impact Energy vs. Temperature for Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Transverse Orientation)

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5-21 IS PLATE R3W0-2 (TRANSVERSE)

CVGRAPH 5.3 Hy)Tcrbolic Tangent Curve Printed on 05/21/2010 03:30 PM Data Set(s) Plotted Curve Plant Capsule Material OrT.

Heat2-*

Comanche Peak 2 UNIRR SA533BI TL SA533B 1 C5522-2 Comanche Peak 2 W SA53H I TfL 4 Comanche Peak 2 W SA533BI 200 C 100 50 0o-

-300.0 0.0 300.0 600.0 Temperature in Dog F 0 1 12 03 A 4 Resulls Flumm LSE USE d-USE T @35 d-T @35

.0 65. 6 .0 39.1 .0 2 .0 71.6 6.0 43.1 4.0 3 .0 72. 9 7.3 95.6 56.5 4 .0 68. 2 2.6 89.6 50.5 Figure 5-5 Charpy V-Notch Lateral Expansion vs. Temperature for Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Transverse Orientation)

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5-22 IS PL4TE R3807-2 (TRANSVERSE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 05/21/2010 03:29 PM Data Set(s) Plotted Curve Plant Capsule Material 1il.

Comanche Peak 2 UNIRR SA533B1 C5522-2 Fomanc N e 2 SAS33BI TL Comalc Ve SA533B I 4 Comanche Peak 2 W SA533BI C5522-2 125 100 S- 75 50 25:1 0-

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Dog F 0 1 02

• 3 A4 Results Cuqrve Fhuelke ISE USE d-USE T @50 d-T @50

.0 100. 0 .0 62.7 .0 2 .0 100.0 .0 116.2 53. 5 3 .0 100.0 .0 91.3 28. 6 4 .0 I00. 0 .0 126. 7 64.0 Figure 5-6 Charpy V-Notch Percent Shear vs. Temperature for Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Transverse Orientation)

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5-23 SURVEILLANCE PROGRAM WELD CVGRAPH 5.3 H)jerbolic Tangent Curve Printed on 05121/2010 03:38 PM Data Set(s) Plotted Cu4ve Plant Capsule Matedal Ori. Heat #

Comanche Peak 2 UNIRR SAW NA 89833 Comalrcl- SAW NA 89833 4 SAW 898.1 Comanche Peak 2 W SAW 89833 300 250 4 200 i ~150 lo z

100 50 0 *f

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Dog F 0 1 S2 3 *4 Resofts Curve Flueem MSE USE d-USE T@30 d-T @30 T @56 &-T @50

94. 0 .0 -49.6 .0 -. 4 .0 2 2.2 85.0 -9.0 -46.0 3.6 -1.2 -. 8 3 96. 0 2.0 -1.4 48. 2 26. 3 26.7 4 83. 5 -10.5 34.4 84. 0 50. 9 51.3 Figure 5-7 Charpy V-Notch Impact Energy vs. Temperature for the Comanche Peak Unit 2 Reactor Vessel Surveillance Program Weld Metal WCAP-17269-NP September 2010 Revision 0

5-24 SURVEILLANCE PROG RAM WELD CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 05/21/2010 03:45 PM Data Set(s) Plotted Curve Plant Capsule Material ON. Heat #

Comanche Comanche Peak Pe422 UNIRR U SAW NA 89833 SAW NA 89833 4 Fomanc- ea SAW 898&3 Comanche Peak 2 W SAW 89833 200 150 E

1100 5o 04

-300.0 0.0 300.0 600.0 Temperature in Dog F 01 2 03 4 Resuf curve Flueoee LSE USE d-USE T 035 4-T @35

.0 76. 0 .0 .7 .0

.0 66. I -9.9 -16.7 -17.4

-3 .0 67.9 -8. 1 20. 3 19.6 4 .0 71.9 -4.2 39. 3 38.6 Figure 5-8 Charpy V-Notch Lateral Expansion vs. Temperature for the Comanche Peak Unit 2 Reactor Vessel Surveillance Program Weld Metal WCAP-17269-NP September 2010 Revision 0

5-25 SURVEILLANCE PROGRAMI WELD CVGRAPH 5.3 Hypxrbolic Tangent Curve Printed on 0/512112010 03:44 PM Data Set(s) Plotted Curve Plant Capsule Material ONA neat#

Comanche Peak 2 UNIRR SAW NA 89833 Comanch NA 89833 SAW SAW 4 Comanche Peak 2 W 89833 125 100 I

~0 75 50 25 0+-

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Dog F 0 1 1 2 0>3 64 Results Curve Fbaenwe ISE USE d.-USE T @30 d-T 050

.0 o00.0 .0 -1.2 .0 2 .0 100.0 .0 21.6 22. 8 3 .0 o00.0 .0 20. 8 22. 0 4 .0 100.0 .0 31.2 32. 4 Figure 5-9 Charpy V-Notch Percent Shear vs. Temperature for the Comanche Peak Unit 2 Reactor Vessel Surveillance Program Weld Metal WCAP-1 7269-NP September 2010 Revision 0

5-26 HEAT AFFECTED ZONE CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 05/21/2010 03:47 PM Data Set(s) Plotted Cu4ve Plant Capsule Material Oni.

Comanche Peak 2 UNIRR SA533B1 NA Heal#-

Comanche 2 U SA53 B0 NA C5522-2 4 Comanch P SA533B I Comanche Peak W SA533BI 300-250-4200--

15O Lu 100 50-0 -

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F 0 1 02 *3 Results Carve Flnence LSE USE d-USE T@30 d-T (30 T 050 d-T @$0 2.2 116.0 .0 - 109.5 .0 -75.4 .0 2 2.2 127.0 11.0 -122.7 -13.2 -70. I 5.3 3 2.2 116.0 .0 -83.3 26. 2 -57.4 18.0 4 2.2 111.0 -5.0 -80.3 29.2 -56.6 18.8 Figure 5-10 Charpy V-Notch Impact Energy vs. Temperature for the Comanche Peak Unit 2 Reactor Vessel Heat-Affected-Zone Material WCAP- 17269-NP September 2010 Revision 0

5-27 HEAT AFFECTED ZONE CVGRAPH 5.3 Hy)erbolic Tangent Curve Printed on 05/21/2010 03:49 PM Data Set(s) Plotted Cur4e Plant Capsule Material ONi. Heat*-

Comanche Peak 2 UNIRR SA333B I NA vU NA C5522-2 4 Comanche Peak 2 W SA533H]

200 150 E

.2 100 Is 50 04

-300.0 0.0 300.0 600.0 Temperature in Dog F 01 a 2 0 3 4 Results curve Hluence [SE USE d-USE T @35 d-T 035

.0 72. 8 .0 -48.9 .0 2 .0 77.8 5.0 -49.4 -. 5 3 .0 66. I -6.7 -37.8 11. 1 4 .0 68. 6 -4.2 -47.5 1.4 Figure 5-11 Charpy V-Notch Lateral Expansion vs. Temperature for the Comanche Peak Unit 2 Reactor Vessel Heat-Affected-Zone Material WCAP-17269-NP September 2010 Revision 0

5-28 HEAT AFFECTED ZONE CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 05/21/2010 03:48 PM Data Set(s) Plotted Curve Plant Capsule Orl Comanche Peak 2 UNIRR MaterBia Heat

1. 2 NA SA533B I NA C5522-2 4 Comanche Peak 2 W 125 100 I

U, 75 50 25 I

0+-

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Dog F 0 1 a2 03 4 Fluem L.SE USE d-USE T @30 d-T 050

.0 100.0 .0 -40. 3 .0

.0 100.0 .0 -31.1 9.2

.0 100.0 .0 -38. I 2.2 4 .0 100.0 .0 -50. 6 -10.3 Figure 5-12 Charpy V-Notch Percent Shear vs. Temperature for the Comanche Peak Unit 2 Reactor Vessel Heat-Affected-Zone Material WCAP-17269-NP September 2010 Revision 0

5-29 CL36, -50°F CL38, -20°F CL44, -15°F CL33, -10°F CL39, 0°F CL41, 25°F CL42, 40°F CL45, 60°F CL34, 80°F CL31, 125°F CL35, 200-F CL43, 275°F CL40, 300-F CL32, 325°F CL37, 350°F Figure 5-13 Charpy Impact Specimen Fracture Surfaces for Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Longitudinal Orientation)

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5-30 CT43, -90°F CT39, 30°F CT31, 50°F CT34, 55-F CT41, 65°F CT44, 75°F CT38, 100°F CT33, 125-F CT42, 130°F CT45, 140°F CT32, 150°F CT36,200°F CT35, 275°F CT40, 300-F CT37,3250 F Figure 5-14 Charpy Impact Specimen Fracture Surfaces for Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Transverse Orientation)

September 2010 WCAP-WCAP- 17269-NP September 2010 Revision 0

5-31 CW38, -90°F CW40, 25-F CW45, 30°F CW33,30°F CW43, 35°F j.1fj* - AMC - f1 -.

CW42, 400 F CW31, 45°F CW35,45°F CW41, 50-F CW32, 50°F CW36, 75°F CW44, 175°F CW37, 275°F CW39, 300°F CW34,325°F Figure 5-15 Charpy Impact Specimen Fracture Surfaces for the Comanche Peak Unit 2 Reactor Vessel Surveillance Program Weld Metal WCAP-17269-NP September 2010 Revision 0

5-32 I

CH31, -175-F CH39, -90 0 F CH44, F CH33, F CH42, -75°F CH37, -70°F CH43, F CH34, -60°F CH36, F CH41, -60°F CH38, -50 0F CH32, -25°F CH45, 200°F CH40,225°F CH35, 275°F Figure 5-16 Charpy Impact Specimen Fracture Surfaces for the Comanche Peak Unit 2 Reactor Vessel Heat-Affected-Zone Material WCAP-17269-NP September 2010 Revision 0

5-33 120.0 100.0 1 Ultimate Tensile Strength 80.0 0.2%/ Yield Strength 0 60.0 40.0 20.0 0.0 0 100 200 300 400 500 600 Temperature (F)

Legend: A and e and n are unirradiated A and o and o are irradiated to 3.38E+19 n/cm 2 (E > 1.0 MeV) 80.0 70.0 !

Area Reduction 60.0 50.0 40.0 C3 30.0 0- Total Elongation 20.0 10.0 Uniform Elongation 0.0 0 100 200 300 400 500 600 Temperature (°F)

Figure 5-17 Tensile Properties for Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Longitudinal Orientation)

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5-34 1200 1n00.0

-UimateTensile Strength 80.0 100.0

'-..-..0.2% Yield Strength 60.0 40.0 20.0 0.0 0 100 200 300 400 500 600 Temperature (*F)

Legend: A and e and n are unirradiated A and o and o are irradiated to 3.38E+19 n/cm 2 (E > 1.0 MeV) 80.0 70.0 Area Reduction 60.0 50.0

= 40.0 30.0 Total Elongation 20.0 Uniform Elongation 10.0 ~A 0.0 0 100 200 300 400 500 600 Temperature (°F)

Figure 5-18 Tensile Properties for Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Transverse Orientation)

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5-35 120.0 100.0 p

-.----- - Ultimate Tensile Strength 80.0

,.ik d i..~t ii. 60.0 1 40.0 4 20.0 1 0 100 200 300 400 500 600 Temperature (*F)

Legend: A and

• and m are unirradiated A and o and o are irradiated to 3.38E+19 n/cm 2 (E > 1.0 MeV) 80.0 70.0 Area Reduction 60.0 50.0

= 40.0 a

30.0 Total Elongation 20.0 10.0 Uniform Elongation 0.0 0 100 200 300 400 500 600 Temperature (°F)

Figure 5-19 Tensile Properties for the Comanche Peak Unit 2 Reactor Vessel Surveillance Program Weld Metal WCAP-17269-NP September 2010 Revision 0

5-36 Specimen CL7- Tested at 100'F Specimen CL8- Tested at 200'F Specimen CL9- Tested at 550'F Figure 5-20 Fractured Tensile Specimens from Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Longitudinal Orientation)

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5-37 Specimen CT7- Tested at 100°F Specimen CT8- Tested at 200'F Specimen CT9- Tested at 550'F Figure 5-21 Fractured Tensile Specimens from Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Transverse Orientation)

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5-38 Specimen CW7- Tested at 100'F Specimen CW8- Tested at 200'F Specimen CW9- Tested at 550'F Figure 5-22 Fractured Tensile Specimens from the Comanche Peak Unit 2 Reactor Vessel Surveillance Program Weld Metal WCAP-17269-NP September 2010 Revision 0

5-39 COMMANCHE PEAK 2W CL7 100*F lo S-N. -

o'15 o ý 5-39 COMMANCHE PEAK 2W 100 -

90 80 70 60 U)

LU 50 Cf 40 30 CL8 200*F 20 10 0

0 0.05 0.1 0.15 0.2 0.25 STRAIN, IN/IN COMMANCHE PEAK 2W 70 CL9 550°F o's .2 Figure 5-23 Engineering Stress-Strain Curves for Comanche Peak Unit 2 Intermediate Shell Plate R3807-2 Tensile Specimens CL7, CL8 and CL9 (Longitudinal Orientation)

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5-40 COMMANCHEPEAK2W 12 CT7 100*F COMMANCHE PEAK 2W ice so 70

ýo CT8 200F 1.

c 015 0.2 025 COMMANCHE PEAK 2W 1.

6o In CT9 550°F c2 025 00500. KAN1 Figure 5-24 Engineering Stress-Strain Curves for Comanche Peak Unit 2 Intermediate Shell Plate R3807-2 Tensile Specimens CT7, CT8 and CT9 (Transverse Orientation)

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5-41 COMMANCHE PEAK 2W 30 CW7 100T 10 COMMANCHE PEAK 2W IN N

M

ýO CW8 200TF 10 0

cos a, 015 0ý 025 STRAN. INAiN COMMANCHE PEAK 2W 100 CW9 3o 550°F 1.

112

.T-1., NIN Figure 5-25 Engineering Stress-Strain Curves for Comanche Peak Unit 2 Surveillance Program Weld Metal Tensile Specimens CW7, CW8 and CW9 WCAP-17269-NP September 2010 Revision 0

6-1 6 RADIATION ANALYSIS AND NEUTRON DOSIMETRY

6.1 INTRODUCTION

This section describes a discrete ordinates Sn transport analysis performed for the Comanche Peak 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 eleventh plant operating cycle, is provided. In addition, to provide an up-to-date database applicable to the Comanche Peak Unit 2 reactor, the sensor sets from the previously withdrawn and analyzed capsules (U and X) were re-analyzed using the current dosimetry evaluation methodology. Capsules V and Y have been removed from the reactor vessel at the end of Cycle 7, Capsule Z has been removed from the reactor vessel at the end of Cycle 11, but all these three capsules have been stored in the spent fuel pool and have never been analyzed; therefore, their sensor sets were not analyzed in this analysis either. The updated dosimetry analysis results 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 60 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 E853-01, "Analysis and Interpretation of Light-Water Reactor Surveillance Results" [Ref. 19], 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 E693-01, "Standard Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements per Atom" [Ref. 20]. 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 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 of Regulatory Guide .1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence" [Ref. 21]. Additionally, the methods used to develop the calculated pressure vessel fluence are consistent with the NRC-approved methodology described in WCAP-14040-WCAP- 17269-NP September 2010 Revision 0

6-2 A, Revision 4, "Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves," May 2004 [Ref. 22].

6.2 DISCRETE ORDINATES ANALYSIS A plan view of the Comanche Peak Unit 2 reactor geometry at the core midplane is shown 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, 610, 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 Figures 6-1 through 6-3: 290 from the core cardinal axes (for the 610 and 2410 dual surveillance capsule holder locations found in octants with a 22.50 neutron pad segment) and 31.50 from the core cardinal axes (for the 121.50 and 301.50 single surveillance capsule holder locations found in octants with a 20.00 neutron pad segment, and for the 58.50 and the 238.50 dual surveillance capsule holder locations found in octants with a 22.50 neutron pad segment). The stainless steel specimen containers are 1.182-inch by 1-inch and are approximately 56 inches in height. The containers are positioned axially such' that the test specimens are centered on the core midplane, thus spanning the central 5 feet of the 12-foot high reactor core.

From a neutronic 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 be included in the analytical model.

In performing the fast neutron exposure evaluations for the Comanche Peak 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:

(p(r, 0, z) = p(r, 0)

• cp(r)

ý(r,z) (Eqn. 6-1) where 4b(r,0,z) is the synthesized three-dimensional neutron flux distribution, 4(r,0) is the transport solution in r,0 geometry, 4(rz) is the two-dimensional solution for a cylindrical reactor model using the actual axial core power distribution, and 4(r) is the one-dimensional solution for a cylindrical reactor model using the same source per unit height as that used in the r,0 two-dimensional calculation. This synthesis procedure was carried out for each operating cycle at Comanche Peak Unit 2.

For the Comanche Peak Unit 2 transport calculations, the r,0 models depicted in Figures 6-1 through 6-3 were utilized since, with the exception of the neutron pads, the reactor is octant symmetric. These r,0 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 WCAP-17269-NP September 2010 Revision 0

6-3 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 r,0 reactor models consisted of 183 radial by 99 azimuthal intervals.

Mesh sizes were chosen to assure that proper convergence of the inner iterations was achieved 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 rz model used for the Comanche Peak Unit 2 calculations is shown in Figure 6-4 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 r,0 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 rz 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 pointwise basis. The pointwise inner iteration flux convergence criterion utilized in the r,z calculations was also set at a value of 0.001.

The one-dimensional radial model used in the synthesis procedure consisted of the same 153 radial mesh intervals included in the rz model. 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 for Cycle 1 through Cycle 7 were provided by TXU, and Cycle 8 through Cycle 11 data were obtained from the Nuclear Fuels Division of Westinghouse. Specifically, the data utilized included cycle-dependent fuel assembly initial enrichments, bumups, 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, 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 burnup 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 3.2 [Ref. 23] and the BUGLE-96 cross-section library [Ref. 24]. 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 P 5 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.

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6-4 Selected results from the neutron transport analyses are provided in Tables 6-1 through 6-6. Cumulative irradiation times contained within these tables are expressed in terms of EFPY as well as Effective Full Power Seconds (EFPS). 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 31.5' single capsule. These results, representative of the axial midplane of the active core, establish the calculated exposure of the 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 five azimuthal locations and the overall maximum fluence (azimuthally and axially). The vessel data given in Table 6-2 were taken at the clad/base metal interface, and thus, represent maximum calculated exposure levels on the vessel.

From the data provided in Table 6-2 it is noted that the peak clad/base metal interface vessel fluence (E > 1.0 MeV) at the end of the eleventh fuel cycle (i.e., after 14.51 EFPY of plant operation) was 8.76x 1018 n/cm 2.

Both calculated fluence (E > 1.0 MeV) and dpa data are provided in Tables 6-1 and 6-2. These data tabulations include both plant- and fuel-cycle-specific calculated neutron exposures at the end of the eleventh fuel cycle as well as future projections to 15.92, 20, 24, 30, 36, 42, 48, 54, and 60 EFPY. The calculations account for uprates from 3411 MWt to 3445 MWt that occurred during Cycle 5, and from 3445 MWt to 3458 MWt that occurred during Cycle 6. The projections were based on the assumption that the core power distributions and associated plant operating characteristics from Cycle 12 were representative of future plant operation. The future projections are also based on the current reactor power level of 3612 MWt.

Radial gradient information applicable to fast (E > 1.0 MeV) neutron fluence and dpa are given in Tables 6-3 and 6-4, respectively. The data, based on the cumulative integrated exposures from Cycles 1 through 11, 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 three surveillance capsules withdrawn and analyzed from Comanche Peak 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 Comanche Peak Unit 2 reactor.

2 From the data provided in Table 6-5, Capsule W received a fluence (E > 1.0 MeV) of 3.38x1019 n/cm after exposure through the end of the eleventh fuel cycle (i.e., after 14.51 EFPY of plant operation).

Updated lead factors for the Comanche Peak 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, V, W, X, Y, and Z) were based on the calculated fluence values for the irradiation period corresponding to the time of withdrawal for the individual capsules.

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6-5 6.3 NEUTRON DOSIMETRY 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 are documented in Appendix A.

The direct comparison of measured versus calculated fast neutron threshold reaction rates for the sensors from Capsule W, which was withdrawn from Comanche Peak Unit 2 at the end of the fourteenth fuel cycle, is summarized below.

Reaction Rates (rps/atom)

Reaction Measured Calculated M/C Ratio1 63 Cu(n, 0)60 Co 4.70E-17 4.OOE-17 1.18 54 54 Fe(n,p) Mn 4.76E-15 4.38E-15 1.09 58Ni(n,p)58Co 7.04E-15 6.13E-15 1.15 238 137 U(n,f) Cs (Cd) 2.94E-14 2.33E-14 1.26 237 Np(n,f) 137 Cs (Cd) 2.48E-13 2.28E-13 1.09 Average: 1.15

% Standard Deviation: 6.1 The measured-to-calculated (M/C) reaction rate ratios for the Capsule W threshold reactions range from 1.09 to 1.26, and the average M/C ratio is 1.15 +/- 6.1% (la). 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 Comanche Peak Unit 2 reactor. These comparisons validate the current analytical results described in Section 6.2; therefore, the calculations are deemed applicable for Comanche Peak Unit 2.

6.4 CALCULATIONAL UNCERTAINTIES The uncertainty associated with the calculated neutron exposure of the Comanche Peak 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:

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

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6-6

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 Comanche Peak Unit 2 surveillance program.

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 Comanche Peak Unit 2 analysis was established from results of these three phases of the methods qualification.

The fourth phase of the uncertainty assessment (comparisons with Comanche Peak 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 Comanche Peak 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 24.

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.

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6-7 The plant-specific measurement comparisons described in Appendix A support these uncertainty assessments for Comanche Peak Unit 2.

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6-8 Table 6-1 Calculated Neutron Exposure Rates and Integrated Exposures at the Surveillance Capsule Center Cumulative CumulativeC Neutron Flux (E > 1.0 MeV)[n/cm 2 -Ms]

Cycle Irradiation ' Irradiation,

'Length Time Time, Cycle lEFPSl IE4eSI EFPYJ _ :E- Dual 290 Dual 31.50 .

1 2.87E+07 2.87E+07 0.91 1.01E+I1I 1.11E+11 1.09E+1 1 2 3.73E+07 6.60E+07 2.09 6.48E+10 7.16E+10 7.10E+10 3 4.42E+07 1.10E+08 3.49 7.47E+10 7.85E+10 7.76E+10 4 3.84E+07 1.49E+08 4.71 6.78E+10 7.20E+10 7.13E+10 5 4.52E+07 1.94E+08 6.14 6.68E+10 7.12E+10 7.05E+10 6 4.37E+07 2.37E+08 7.52 6.83E+10 7.15E+10 7.07E+10 7 4.12E+07 2.79E+08 8.83 7.12E+10 7.78E+10 7.70E+10 8 4.35E+07 3.22E+08 10.21 6.92E+10 7.32E+10 7.24E+10 9 4.52E+07 3.67E+08 11.64 6.99E+10 7.49E+10 7.41E+/-10 10 4.44E+07 4.12E+08 13.05 6.67E+10 7.OOE+10 6.92E+10 11 4.60E+07 4.58E+08 14.51 5.69E+10 6.13E+10 6.07E+10 Future 4.64E+07 5.04E+08 15.92 6.63E+10 7.25E+10 7.18E+10 Future 1.27E+08 6.31E+08 20.00 6.63E+10 7.25E+10 7.18E+10 Future 1.26E+08 7.57E+08 24.00 6.63E+10 7.25E+10 7.18E+10 Future 1.89E+08 9.47E+08 30.00 6.63E+10 7.25E+10 7.18E+10 Future 1.89E+08 1.14E+09 36.00 6.63E+10 7.25E+10 7.18E+10 Future 1.89E+08 1.33E+09 42.00 6.63E+10 7.25E+10 7.18E+10 Future 1.89E+08 1.51E+09 48.00 6.63E+10 7.25E+10 7.18E+10 Future 1.89E+08 1.70E+09 54.00 6.63E+10 7.25E+10 7.18E+10 Future 1.89E+08 1.89E+09 60.00 6.63E+10 7.25E+10 7.18E+10 Note: Neutron exposure values reported for the surveillance capsules are centered at the core midplane.

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6-9 Table 6-1 (Continued) Calculated Neutron Exposure Rates and Integrated Exposures at the Surveillance Capsule Center Cumulative Cumulative i Neutron Fluence (E.>I'.O MeV).n/cm2]

Cycle Irradiation Irradiation' Length Time Tiime Cycle [EFPS] [EFPS] [EFPY] Dual,290 Dual 31'.50

• Single31,59 1 2.87E+07 2.87E+07 0.91 2.90E+18 3.17E+18 3.14E+18 2 3.73E+07 6.60E+07 2.09 5.31E+18 5.84E+18 5.79E+18 3 4.42E+07 1.10E+08 3.49 8.61E+18 9.31E+18 9.22E+18 4 3.84E+07 1.49E+08 4.71 1.12E+19 1.21E+19 1.20E+19 5 4.52E+07 1.94E+08 6.14 1.42E+19 1.53E+19 1.51E+19 6 4.37E+07 2.37E+08 7.52 1.72E+19 1.84E+19 1.82E+19 7 4.12E+07 2.79E+08 8.83 2.02E+19 2.16E+19 2.14E+19 8 4.35E+07 3.22E+08 10.21 2.32E+19 2.48E+19 2.46E+19 9 4.52E+07 3.67E+08 11.64 2.63E+19 2.82E+19 2.79E+19 10 4.44E+07 4.12E+08 13.05 2.93E+19 3.13E+19 3.10E+19 11 4.60E+07 4.58E+08 14.51 3.19E+19 3.41E+19 3.38E+19 Future 4.64E+07 5.04E+08 15.92 3.49E+19 3.73E+19 3.70E+19 Future 1.27E+08 6.3 1E+08 20.00 4.34E+19 4.67E+19 4.62E+19 Future 1.26E+08 7.57E+08 24.00 5.18E+19 5.58E+19 5.53E+19 Future 1.89E+08 9.47E+08 30.00 6.43E+19 6.95E+19 6.89E+19 Future 1.89E+08 1.14E+09 36.00 7.69E+19 8.33E+19 8.25E+19 Future 1.89E+08 1.33E+09 42.00 8.94E+19 9.70E+19 9.61E+19 Future 1.89E+08 1.51E+09 48.00 1.02E+20 1.11E+20 1.1OE+20 Future 1.89E+08 1.70E+09 54.00 1.15E+20 1.24E+20 1.23E+20 Future 1.89E+08 1.89E+09 60:00 1.27E+20 1.38E+20 1.37E+20 Note: Neutron exposure values reported for the surveillance capsules are centered at the core midplane.

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6-10 Table 6-1 (Continued) Calculated Neutron Exposure Rates and Integrated Exposures at the Surveillance Capsule Center Cumulative Cumulative Iron Atom Displacement Rate [dpa/s]

Cycle Irradiation Irradiation*

Length Time Time Cycle [EFPS] [EFPS] [EFPY] Dual 290 Dual 31.50 Single-31.50 1 2.87E+07 2.87E+07 0.91 1.99E-10 2.18E-10 2.15E-10 2 3.73E+07 6.60E+07 2.09 1.26E-10 1.40E-10 1.38E-10 3 4.42E+07 1.1OE+08 3.49 1.46E-10 1.53E-10 1.51E-10 4 3.84E+07 1.49E+08 4.71 1.32E-10 1.40E-10 1.39E-10 5 4.52E+07 1.94E+08 6.14 1.30E-10 -1.39E-10 1.37E-10 6 4.37E+07 2.37E+08 7.52 1.33E-10 1.39E-10 1.38E-10 7 4.12E+07 2.79E+08 8.83 1.39E-10 1.52E-10 1.51E-10 8 4.35E+07 3.22E+08 10.21 1.35E-10 1.43E-10 1.41E-10 9 4.52E+07 3.67E+08 11.64 1.37E-10 1.46E-10 1.45E-10 10 4.44E+07 4.12E+08 13.05 1.30E-10 1.36E-10 1.35E-10 11 4.60E+07 4.58E+08 14.51 1.11E-10 1.19E-10 1.18E-10 Future 4.64E+07 5.04E+08 15.92 1.30E-10 1.42E-10 1.40E-10 Future 1.27E+08 6.31E+08 20.00 1.30E-10 1.42E-10 1.40E-10 Future 1.26E+08 7.57E+08 24.00 1.30E-10 1.42E-10 1.40E-10 Future 1.89E+08 9.47E+08 30.00 1.30E-10 1.42E-10 1.40E-10 Future 1.89E+08 1.14E+09 36.00 1.30E-10 1.42E-10 1.40E-10 Future 1.89E+08 1.33E+09 42.00 1.30E-10 1.42E-10 1.40E-10 Future 1.89E+08 1.51E+09 48.00 1.30E-10 1.42E-10 1.40E-10 Future 1.89E+08 1.70E+09 54.00 1.30E-10 1.42E-10 1.40E-10 Future 1.89E+08 1.89E+09 60.00 1.30E-10 1.42E-10 1.40E-10 Note: Neutron exposure values reported for the surveillance capsules are centered at the core midplane.

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6-11 Table 6-1 (Continued) Calculated Neutron Exposure Rates and Integrated Exposures at the Surveillance Capsule Center Cumulative Cumulative Iron Atom Displacement [dpaJ Cycle Irradiation Irradiation Length Time Time Cycle [EFPS] [EFPS] IEFPy] Dual,29° Dual31.50 Single31.50 1 2.87E+07 2.87E+07 0.91 5.70E-03 6.25E-03 6.19E-03 2 3.73E+07 6.60E+07 2.09 1.04E-02 "1.14E-02 1.13E-02 3 4.42E+07 1.1OE+08 3.49 1.69E-02 1.82E-02 1.80E-02 4 3.84E+07 1.49E+08 4.71 2.20E-02 2.36E-02 2.34E-02 5 4.52E+07 1.94E+08 6.14 2.78E-02 2.99E-02 2.96E-02 6 4.37E+07 2.37E+08 7.52 3.36E-02 3.60E-02 3.56E-02 7 4.12E+07 2.79E+08 8.83 3.94E-02 4.23E-02 4.18E-02 8 4.35E+07 3.22E+08 10.21 4.53E-02 4.85E-02 4.79E-02 9 4.52E+07 3.67E+08 11.64 5.15E-02 5.51E-02 5.45E-02 10 4.44E+07 4.12E+08 13.05 5.73E-02 6.11E-02 6.05E-02 11 4.60E+07 4.58E+08 14.51 6.24E-02 6.66E-02 6.59E-02 Future 4.64E+07 5.04E+08 15.92 6.81E-02 7.29E-02 7.21E-02 Future 1.27E+08 6.31E+08 20.00 8.48E-02 9.12E-02 9.02E-02 Future 1.26E+08 7.57E+08 24.00 1.OIE-01 1.09E-01 1.08E-01 Future 1.89E+08 9.47E+08 30.00 1.26E-01 1.36E-01 1.34E-01 Future 1.89E+08 1.14E+09 36.00 1.50E-01 1.63E-01 1.61E-01 Future 1.89E+08 1.33E+09 42.00 1.75E-01 1.89E-01 1.87E-01 Future 1.89E+08 1.51E+09 48.00 1.99E-01 2.16E-01 2.14E-01 Future 1.89E+08 1.70E+09 54.00 2.24E-01 2.43E-01 2.41E-01 Future 1.89E+08 1.89E+09 60.00 2.48E-01 2.70E-01 2.67E-01 Note: Neutron exposure values reported for the surveillance capsules are centered at the core midplane.

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6-12 Table 6-2 Calculated Azimuthal Variation of Maximum Exposure Rates and Integrated Exposures at the Reactor Vessel Clad/Base Metal Interface Cumulative Cumulative Neutron Flux (E> 1.0 MeV) [n/cm 2,s]

Cycle Irradiation Irradiation .

Length -Time Time .

Cycle [EFPSI [EFPS] [EFPY] 09 '150 210 300 450 Max, I 2.87E+07 2.87E+07 0.91 1.46E+10 2.16E+10 2.55E+10 2.54E+10 2.79E+10 2.79E+10 2 3.73E+07 6.60E+07 2.09 1.14E+10 1.41E+10 1.59E+10 1.66E+10 1.74E+10 1.74E+10 3 4.42E+07 1.1OE+08 3.49 1.44E+10 2.09E+10 2.21E-10 1.91E+10 1.86E+10 2.22E+10 4 3.84E+07 1.49E+08 4.71 1.25E+10 1.85E+10 1.97E+10 1.76E+10 1.70E+10 1.97E+10 5 4.52E+07 1.94E+08 6.14 1.13E+10 1.64E+10 1.83E+10 1.71E+10 1.65E+10 1.83E+10 6 4.37E+07 2.37E+08 7.52 1.27E+10 1.77E+10 1.94E+10 1.73E+10 1.56E+10 1.94E+10 7 4.12E+07 2.79E+08 8.83 1.36E+10 1.81E+10 1.95E+10 1.82E+10 1.96E+10 1.96E+10 8 4.35E+07 3.22E+08 10.21 1.31E+10 1.85E+10 1.99E+10 1.78E+10 1.72E+10 1.99E+10 9 4.52E+07 3.67E+08 11.64 1.28E+10 1.82E+10 1.95E+10 1.78E+10 1.77E+10 1.95E+10 10 4.44E+07 4.12E+08 13.05 1.22E+10 1.74E+10 1.91E+10 1.71E+10 1.63E+10 1.91E+10 11 4.60E+07 4.58E+08 14.51 1.07E+10 1.42E+10 1.57E+10 1.53E+10 1.50E+10 1.58E+10 Future 4.64E+07 5.04E+08 15.92 9.38E+09 1.41E+10 1.67E+10 1.71E+10 1.82E+10 1.82E+10 Future 1,27E+08 6.31E+08 20.00 9.38E+09 1.41E+10 1.67E+10 1.71E+10 1.82E+10 1.82E+10 Future 1.26E+08 7.57E+08 24.00 9.38E+09 1.41E+10 1.67E+10 1.71E+10 1.82E+10 1.82E+10 Future 1.89E+08 9.47E+08 30.00 9.38E+09 1.41E+10 1.67E+10 1.71E+10 1.82E+10 1.82E+10 Future 1.89E+08 1.14E+09 36.00 9.38E+09 1.41E+10 1.67E+10 1.71E+10 1.82E+10 1.82E+10 Future 1.89E+08 1.33E+09 42.00 9.38E+09 1.41E+10 1.67E+10 1.71E+10 1.82E+10 1.82E+10 Future 1.89E+08 1.51E+09 48.00 9.38E+09 1.41E+10 1.67E+10 1.71E+10 1.82E+10 1.82E+10 Future 1.89E+08 1.70E+09 54.00 9.38E+09 1.41E+10 1.67E+10 1.71E+10 1.82E+10 1.82E+10 Future 1.89E+08 1.89E+09 60.00 9.38E+09 1.41E+10 1.67E+10 1.71E+10 1.82E+10 1.82E+10 WCAP-17269-NP September 2010 Revision 0

6-13 Table 6-2 (Continued) Calculated Azimuthal Variation of Maximum Exposure Rates and Integrated Exposures at the Reactor Vessel Clad/Base Metal Interface

~Cuniplative Cycle CYlee Cumuliatiie Slradiation Irrdain Irradiation.

.EFVI 7 0 I UnI

.E.PS 5 Neutron Fluence ( > iO8W)lfei1

. 21 .30 ... *45 Max' I 2.87E+07 2.87E+07 0.91 4.18E+17 6.20E+17 7.33E+17 7.29E+17 8.01E+17 8.01E+17 2 3.73E+07 6.60E+07 2.09 8.40E+17 1.14E+18 1.32E+18 1.34E+18 1,44E+18 1.44E+18 3 4.42E+07 1.1OE+08 3.49 1.48E+18 2.07E+18 2.30E+18 2.18E+18 2.26E+18 2.30E+18 4 3.84E+07 1.49E+08 4.71 1.95E+/-18 2.76E+18 3.03E+18 2.84E+18 2.90E+18 3.03E+18

.5 4.52E+07 1.94E+08 6.14 2.45E+18 3.50E+18 3.86E+18 3.61E+18 3.64E+18 3.86E+18 6 4.37E+07 2.37E+08 7.52 3.01E+18 4.27E+18 4.70E+18 4.36E+18 4.32E+18 4.70E+18 7 4.12E+07 2.79E+08 8.83 3.57E+18 5.02E+18 5.51E+18 5.12E+18 5.14E+18 5.51E+18 8 4.35E+07 3.22E+08 10.21 4.13E+18 5.81E+18 6.36E+18 5.88E+18 5.87E+18 6.36E+18 9 4.52E+07 3.67E+08 11.64 4.70E+18 6.62E+18 7.23E+18 6.67E+18 6.66E+18 7.23E+18 10 4.44E+07 4:12E+08 13.05 5.23E+18 7.39E+18 8.07E+18 7.42E+18 7.37E+18 8.07E+18 11 4.60E+07 4.58E+08 14.51 5.70E+18 8.01E+18 8.76E+18 8.10E+18 8.03E+18 8.76E+18 Future 4.64E+07 5.04E+08 15.92 6.11E+18 8.63E+18 9.49E+18 8.84E+18 8.83E+18 9.49E+18 Future 1.27E+08 6.31E+08 20.00 7.32E+18 1.04E+19 1,16E+19 1.10E+19 1.12E+19 1.18E+19 Future 1.26E+08 7.57E+08 24.00 8.51E+18 1.22E+19 1.38E+19 1.32E+19 1.35E+19 1.41E+19 Future 1.89E+08 9.47E+08 30.00 1.03E+19 1.49E+19 1.69E+19 1.64E+19 1.69E+19 1.76E+19 Future 1.89E+08 1.14E+09 36.00 1.21E+19 1.75E+19 2.01E+19 1.97E+19 2.04E+19 2.10E+19 Future 1.89E+08 1.33E+09 42.00 1.38E+19 2.02E+19 2.32E+19 2.29E+19 2.38E+19 2.45E+19 Future 1.89E+08 1.51E+09 48.00 1.56E+19 2.29E+19 2.64E+19 2.61E+19 2.73E+19 2.79E+19 Future 1.89E+08 1.70E+09 54.00 1.74E+19 2.55E+19 2.96E+19 2.94E+19 3.07E+19 3.14E+19 Future 1.89E+08 1.89E+09 60.00 1.92E+19 2.82E+19 3.27E+19 3.26E+19 3.42E+19 3.48E+19 WCAP-17269-NP September 2010 Revision 0

6-14 Table 6-2 (Continued) Calculated Azimuthal Variation of Maximum Exposure Rates and Integrated Exposures at the Reactor Vessel Clad/Base Metal Interface Cumulative Cumulative Iron Atom Displacement Rate Idpa/s]

C riradiation Irradiation Length Time Time Cycle [EFPS] [EFPS] [EFPY] 00 150 210 300 459 Max 1 2.87E+07 2.87E+07 0.91 2.26E-11 3.31E-11 3.91E-11 3.91E-11 4.41E-11 4.41E-11 2 3.73E+07 6.60E+07 2.09 1.77E-11 2.18E-11 2.44E-11 2.56E-11 2.74E-11 2.74E-11 3 4.42E+07 1.1OE+08 3.49 2.23E-11 3.21E-11 3.39E-11 2.94E-11 2.94E-11 3.39E-11 4 3.84E+07 1.49E+08 4.71 1.94E-11 2.85E-11 3.02E-11 2.72E-11 2.69E-11 3.02E-11 5 4.52E+07 1.94E+08 6.14 1.75E-11 2.52E-11 2.81E-11 2.63E-11 2.61E-11 2.81E-11 6 4.37E+07 2.37E+08 7.52 1.96E-11 2.72E- 1 2.97E-11 2.67E-11 2.47E-11 2.97E-11 7 4.12E+07 2.79E+08 8.83 2.11E-11 2.79E-11 2.99E-11 2.82E-11 3.10E-11 3.10E-11 8 4.35E+07 3.22E+08 10.21 2.04E-11 2.85E-11 3.05E-11 2.74E-11 2.71E-11 3.05E-11 9 4.52E+07 3.67E+08 11.64 1.98E-11 2.80E-11 2.99E-11 2.75E-11 2.80E-11 2.99E-11 10 4.44E+07 4.12E+08 13.05 1.88E-11 2.67E-11 2.93E-11 2.64E-11 2.57E-11 2.93E-11 11 4.60E+07 4.58E+08 14.51 1.65E-11 2.18E-11 2.41E-11 2.37E-11 2.36E-11 2.43E-11 Future 4.64E+07 5.04E+08 15.92 1.46E-11 2.16E-11 2.56E-11 2.64E-11 2.88E-11 2.88E-11 Future 1.27E+08 6.31E+08 20.00 1.46E-11 2.16E-11 2.56E-11 2.64E-11 2.88E-11 2.88E-11 Future 1.26E+08 7.57E+08 24.00 1.46E-11 2.16E-11 2.56E-11 2.64E-11 2.88E-11 2.88E-11 Future 1.89E+08 9.47E+08 30.00 1.46E-11 2.16E-11 2.56E-11 2.64E-11 2.88E-11 2.88E-11 Future 1.89E+08 1.14E+09 36.00 1.46E-11 2.16E-11 2.56E-11 2.64E-11 2.88E-11 2.88E-11 Future 1.89E+08 1.33E+09 42.00 1.46E-11 2.16E-11 2.56E-11 2.64E-11 2.88E-11 2.88E-11 Future 1.89E+08 1.51E+09 48.00 1.46E-11 2.16E-11 2.56E-11 2.64E-11 2.88E-11 2.88E-11 Future 1.89E+08 1.70E+09 54.00 1.46E-11 2.16E-11 2.56E-11 2.64E-11 2.88E-11 2.88E-11 Future 1.89E+08 1.89E+09 60.00 1.46E-11 2.16E-11 2.56E-11 2.64E-1 2.88E-11 .2.88E-11 WCAP-17269-NP September 2010 Revision 0

6-15 Table 6-2 (Continued) Calculated Azimuthal Variation of Maximum Exposure Rates and Integrated Exposures at the Reactor Vessel'Clad/Base Metal Interface Cumulative Cuu...latie.*" Iron Atom Disp!facemient dpal -

.Cycle, Irradiation' Irradiation,

-'Leith Tm 'in K7 0

yelp IEFPSJ 04 "21 0EFPY1'  : ax, I 2.87E+07 2.87E+07 0.91 6.48E-04, 9.52E-04 1.12E-03 1.12E-03 1.27E-03 1.27E-03 2 3.73E+07 6.60E+07 2.09 1.30E-03 1.75E-03 2.02E-03 2.07E-03 2.28E-03 2.28E-03 3 4.42E+07 1.10E+08 3.49 2.29E-03 3.17E-03 3.52E-03 3.37E-03 3.57E-03 3.57E-03 4 3.84E+07 1.49E+08 4.71 3.01E-03 4.24E-03. 4.65E-03 4.38E-03 4.58E-03 4.65E-03 5 4.52E+07 1.94E+08 6.14 3.81E-03 5.38E-03 5.91E-03 5.57E-03 5.76E-03 5.92E-03 6 4.37E+07 2.37E+08 7.52 4.66E-03 6.56E-03 7.21E-03 6.73E-03 6.83E-03 7.21E-03 7 4.12E+07 2.79E+08 8.83 5.53E-03 7.71E-03 8.45E-03 7.90E-03 8.12E-03 8.44E-03 8 4.35E+07 3.22E+08 10.21 6.40E-03 8.92E-03 9.74E-03 9.07E-03 9.27E-03 9.74E-03 9 4.52E+07 3.67E+08 11.64 7.29E-03 1.02E-02 1.11E-02 1.03E-02 1.05E-02 1.11E-02 10 4.44E+07 4.12E+08 13.05 8.11E-03. 1.13 E-02 1.24E-02 1.15E-02 1.17E-02 1.24E-02 11 4.60E+07 4.58E+08 14.51 8.84E-03 1.23E-02 1.34E-02 1.25E-02 1.27E-02 1.34E-02 Future 4.64E+07 5.04E+08 15.92 9.48E-03 1.33E-02 1.46E-02 1.37E-02 1.40E-02 1.46E-02 Future 1.27E+08 6.31E+08 20.00 1.14E-02 1.60E-02 1.79E-02 1.70E-02 1.77E-02 1.83E-02 Future 1.26E+08 7.57E+08 24.00 1.32E-02 1.88E-02 2.11E-02 2.04E-02 2.13E-02 2.19E-02 Future 1.89E+08 9.47E+08 30.00 1.60E-02 2.29E-02 2.59E-02 2.54E-02 2.68E-02 2.73E-02 Future 1.89E+08 1.14E+09 36.00 1.87E-02 2.70E-02 3.08E-02 3.04E-02 3.22E-02 3.28E-02 Future 1.89E+08 1.33E+09 42.00 2.15E-02 3.11E-02 3.56E-02 3.53E-02 3.77E-02' 3.83E-02 Future 1.89E+08 1.51E+09 48.00 2.42E-02 3.52E-02 4.05E-02 4.03E-02 4.31E-02 4.37E-02 Future 1.89E+08 1.70E+09 54.00 2.70E-02 3.93E-02 4.53E-02 4.53E-02 4.86E-02 4.92E-02 Future 1.89E+08 1.89E+09 60.00 2.97E-02 4.34E-02 5.02E-02 5.03E-02 5.40E-02 5.46E-02 WCAP-17269-NP September 2010 Revision 0

6-16 Table 6-3 Relative Radial Distribution of Neutron Fluence (E > 1.0 MeV) Within the Reactor Vessel Wall

-~~ Azimut 220.11 1.000 1.000 1.000 1.000 1.000 225.59 0.571 0.566 0.564 0.562 0.557 231.06 0.281 0.276 0.274 0.273 0.268 236.54 0.132 0.129 0.128 0.128 0.123 242.01 0.061 0.059 0.058 0.059 0.054 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 Note:

Relative radial distribution data are based on the cumulative integrated exposures from Cycles 1 through 11.

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6-17 Table 6-4 Relative Radial Distribution of Iron Atom Displacements (dpa) Within the Reactor Vessel Wall R a~dius,, R..

. ...... .. , . . Azimuthal o .. . Angle.-,.

(cm) 00 " 15.0 21,0 300 45.0-220.11 1.000 1.000 1.000 1.000 1.000 225.59 0.641 0.636 0.635 0.638 0.643 231.06 0.385 0.381 0.379 0.385 0.389 236.54 0.228 0.227 0.225 0.231 0.229 242.01 0.129 0.128 0.126 0.132 0.122 Base Metal Inner Radius = 220.11 cm Base Metal I/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 Note:

Relative radial distribution data are based on the cumulative integrated exposures from Cycles I through 11.

Table 6-5 Calculated Fast Neutron Exposure of Surveillance Capsules Withdrawn and Analyzed from Comanche Peak Unit 2 Irradiation Time Fluence (E > 1.0 MeV), Iron.Displacements Capsule [EFPYJ., [n/cm,1Idpa]

U 0.91 3.17E+18 6.25E-03 X 8.83 2.16E+19 4.23E-02 W 14.51 3.38E+19 6.59E-02 September 2010 WCAP- 17269-NP September 2010 Revision 0

6-18 Table 6-6 Calculated Surveillance Capsule Lead Factors ID And Location "Lapsule Status Lead Factor U (31.50 Dual) Withdrawn EOC 1 3.96 X (31.5' Dual) Withdrawn EOC 7 3.92 W (31.5' Single) Withdrawn EOC 11 3.86 V (29.00 Dual) Stored in Spent Fuel Pool 3.66 (Withdrawn EOC 7)

Y (29.0' Dual) Stored in Spent Fuel Pool 3.66 (Withdrawn EOC 7)

Z (31.5' Single) Stored in Spent Fuel Pool 3.86 (Withdrawn EOC 11)

Note:

Lead factors for capsules stored in the spent fuel pool are based on cycle-specific exposure calculations through their last completed fuel cycle, i.e., Cycle 7 for Capsules V and Y, Cycle 11 for Capsule Z.

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6-19 Comanche Peak 2 Reactor R,T Model 12.5 DEGREE NEUTRON PAD Meshes: 183R, 998 MCwi hukMWbk ab am

-Mu Iii SAiM Ud 0

t-C&

C014 a"& emuI VW. WZLU N". SIO SI0 1. 0 .0m 30 ;R Ionil Figure 6-1 Comanche Peak Unit 2 rO Reactor Geometry with a 12.50 Neutron Pad Span at the Core Midplane WCAP- 17269-NP September 2010 Revision 0

6-20 Comanche Peak 2 Reactor R,T Model 20.0 DEGREE NEUTRON PAD Meshes: 183R, 998 man madmaw

-w humuson

'It.

0 13LO 155.0 19a. 2A0O n.4. 26~.0 &AT.

ImJ¶l Figure 6-2 Comanche Peak Unit 2 r,0 Reactor Geometry with a 20.00 Neutron Pad Span at the Core Midplane WCAP-17269-NP September 2010 Revision 0

6-21 Comanche Peak 2 Reactor R,T Model 22.5 DEGREE NEUTRON PAD Meshes: 183R, 998

-cm =I - No Mh-0 l I,,IM Imba. -u M U~mld 0!

A' a

WZLU RO.u 01 1O 24WL 16~.0 i~

femi Figure 6-3 Comanche Peak Unit 2 rO Reactor Geometry with a 22.5' Neutron Pad Span at the Core Midplane WCAP-17269-NP September 2010 Revision 0

6-22 2'

[cFcr Figure 6-4 Comanche Peak Unit 2 r,z Reactor Geometry with Neutron Pad WCAP-17269-NP September 2010 Revision 0

7-1 7 SURVEILLANCE CAPSULE REMOVAL SCHEDULE The following table summarizes the removal of the six surveillance capsules from the Comanche Peak Unit 2 reactor vessel, meeting the requirements of ASTM E185-82 [Ref. 4].

Table 7-1 Surveillance Capsule Withdrawal Summary capsule Capsule Location Lead Factor(a) Withdrawal EFPy(b) Fluence (n/cm2)(c)

U 58.50 3.96 0.91 0.317 x 1019 X 238.50 3.92 8.83 2.16 x 10'9 W 121.50 3.86 14.51 3.38 x 10" Z(d) 301.50 3.86 14.51 3.38 x 1019 V(d) 61.00 3.66 8 .8 3 (d) 2.02 x 1019 19 y(d) 241.00 3.66 8.83 () 2.02 x 10 Notes:

(a) Updated in Capsule W dosimetry analysis; see Table 6-6.

(b) EFPY from plant startup.

(c) Updated in Capsule W dosimetry analysis; see Table 6-5.

(d) Standby Capsules Z, V, and Y were removed and placed in the spent fuel pool. No testing or analysis has been performed on these capsules. Reinsertion of one or more of these capsules may be considered in the future, especially if Comanche Peak Unit 2 plans to pursue a 40-year license renewal (72 EFPY or 80 years). However, since the current regulations may change between now and then, it is recommended that the schedule for reinsertion and subsequent withdrawal of an 80-year license capsule be revisited at a later time.

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8-1 8 REFERENCES

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

2. 10 CFR 50, Appendix G, Fracture Toughness Requirements, and Appendix H, Reactor Vessel Material Surveillance Program Requirements, Federal Register, Volume 60, No. 243, December 19, 1995.

3. WCAP-10684, Revision 0, Texas Utilities Generating Company Comanche Peak Unit No. 2 Reactor Vessel RadiationSurveillance Program, L. R. Singer, October 1984.

4. ASTM E 185-82, Standard Practicefor Conducting Surveillance Tests for Light-Water Cooled Nuclear PowerReactor Vessels, E706 (IF), ASTM, 1982.

5.Section XI of the ASME Boiler and Pressure Vessel Code, Appendix Q Fracture Toughness Criteriafor ProtectionAgainst Failure.

6. ASTM E208, Standard Test Method for ConductingDrop-Weight Test to Determine Nil-Ductility Transition Temperature of FerriticSteels, in ASTM Standards, Section 3, American Society for Testing and Materials, Philadelphia, PA.

7. ASTM E399, Test Method for Plane-StrainFracture Toughness of Metallic Materials, American Society for Testing Materials.

8. Westinghouse Science and Technology Department Procedure RMF 8402, Surveillance Capsule Testing Program,Revision 3, June 6, 2005.

9. Westinghouse Science and Technology Department Procedure RMF 8102, Tensile Testing, Revision 3, March 1, 1999.

10. Westinghouse Science and Technology Department Procedure RMF 8103, Charpy Impact Testing, Revision 2, August 1, 1998.

11. Westinghouse Science and Technology Department Procedure RMF 8804, Opening of Westinghouse Surveillance Capsules, Revision 3.

12. ASTM E23-07a, Standard Test Method for Notched Bar Impact Testing of Metallic Materials, ASTM, 2007.

13. General Yielding of Charpy V-Notch and Precracked Charpy Specimens, Journal of Engineering Materials and Technology, Vol. 100, April 1978, pp. 183-188.

14. ASTM A370-09, Standard Test Methods and Definitions for Mechanical Testing of Steel Products,ASTM, 2009.

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8-2

15. ASTM E8-09, StandardTest Methodsfor Tension Testing of Metallic Materials,ASTM, 2009.

16. ASTM E2 1-09, Standard Test Methods for Elevated Temperature Tension Tests of Metallic Materials,ASTM, 2009.

17. WCAP-14315, Revision 0, Analysis of Capsule U from the Texas Utilities Electric Company Comanche Peak Steam Electric Station Unit No; 2 Reactor Vessel Radiation Surveillance Program, R. Auerswald et al., July 1995.

18. WCAP- 16277-NP, Revision 0, Analysis of Capsule Xfrom the TXU Energy Comanche Peak Unit 2 Reactor Vessel RadiationSurveillance Program,T. J. Laubham et al., September 2004.

19. ASTM E853-01, Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Results, E706 (IA), ASTM, 2001

20. ASTM E693-01, StandardPracticefor CharacterizingNeutron Exposures in Iron and Low Alloy Steels in Terms ofDisplacements,PerAtom (DPA), E706 (ID), ASTM, 2001.

21. Regulatory Guide 1.190, Calculationaland Dosimetry Methods for Determining Pressure Vessel Neutron Fluence, U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, March 2001.

22. WCAP-14040-A, Revision 4, Methodology Used to Develop Cold Overpressure Mitigating Sysiem Setpoints andRCS Heatup and Cooldown Limit Curves, May 2004.

23. RSICC Computer Code Collection CCC-650, DOORS 3.2: One, Two- and Three Dimensional Discrete OrdinatesNeutron/PhotonTransport Code System, April 1998.

24. RSICC Data Library Collection DLC-185, BUGLE-96, Coupled 47 Neutron, 20 Gamma-Ray

-Group Cross Section Library Derivedfrom ENDF/B-Vlfor LWR Shielding and Pressure Vessel Dosimetry Applications, March 1996.

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A-i APPENDIX A VALIDATION OF THE RADIATION TRANSPORT MODELS BASED ON NEUTRON DOSIMETRY MEASUREMENTS 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 and analyzed to date at Comanche Peak 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 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence" [Ref. 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.

A.1.1 Sensor Reaction Rate Determinations In this section, the results of the evaluations of the three neutron sensor sets analyzed to date as part of the Comanche Peak 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:

Capsule ID Azimuthal Location Withdrawal Time Irradiation Time [EFPY]

U 31.5' Dual End of Cycle 1 0.91 X 31.5' Dual End of Cycle 7 8.83 W 31.5' Single End of Cycle 11 14.51 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, X, and W are summarized as follows:

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A-2 Reaction Of Capsule Capsule Capsule Sensor Material Interest U X W 63 60 Copper Cu(n,a) Co X X X 54 Iron Fe(np) 4nMn X X X 58 58 Nickel Ni(n,p) Co X X X 238 Uranium-238 U(n,f) 137 Cs X X X 237 37 Neptunium-237 Np(n,f) 1 Cs X X X 59 60 Cobalt-Aluminum* Co(n,Y) Co X X X

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

Since all of the dosimetry monitors were located at the radial center of the material test specimen array, radial 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, 0 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 Capsules U and X are documented in References A-2 through A-3, respectively. The radiometric counting of the sensors from Capsule W was carried out by Pace Analytical Services, Inc. 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, X, and W was based on the monthly power generation of Comanche Peak 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 WCAP-17269-NP September 2010 Revision 0

A-3 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, 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:

A R

NOFYZ Pi Cj[1- e-ti][e- t d],j Pref where:

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

A = Measured specific activity (dps/g).

No

• Number of target element atoms per gram of sensor.

F - Atom fraction of the target isotope in the target element.

Y = Number of product atoms produced per reaction.

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

Pref - Maximum or reference power level of the reactor (MW).

- Calculated ratio of 4(E > 1.0 MeV) during irradiation periodj to the time weighted average O(E > 1.0 MeV) over the entire irradiation period.

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

tj - Length of irradiation period j (sec).

td, j = 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]/[Prof] 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 WCAP-17269-NP September 2010 Revision 0

A-4 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, Cj 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 235U 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 237Np 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 Comanche Peak Unit 2 fission sensor reaction rates are summarized as follows:

Correction Capsule U Capsule X Capsule W 2 35 U Impurity/Pu Build-in 0.872 0.804 0.764 23 8 U(y,f) 0.966 0.967 0.969 238 Net U Correction 0.842 0.777 0.740 237 Np(7,f) 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, X, and W are given in Table A-4. In Table A-4, 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 238U 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 O(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, WCAP-17269-NP September 2010 Revision 0

A-5 Ri ++/-SR=I (COg +/-+k )((g +/-5%)

g relates a set of measured reaction rates, Ri, to a single neutron spectrum, Og, through the multigroup dosimeter reaction cross-section, caig, 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 Comanche Peak Unit 2 surveillance capsule dosimetry, the FERRET code [Ref. A-4] 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 (O(E > 1.0 MeV) and dpa) along with associated uncertainties for the three in-vessel capsules analyzed to date.

The application of the least squares methodology requires the following input:

1. 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 Comanche Peak 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 (Reference A-5). The SNLRML library is an evaluated dosimetry reaction cross-section compilation recommended for use in LWR evaluations by ASTM Standard E 1018, "Application of ASTM Evaluated Cross-Section Data File, Matrix E 706 (JIB)" [Ref. A-6].

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" [Ref. A-7].

The following provides a summary of the uncertainties associated with the least squares evaluation of the Comanche Peak 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 WCAP-17269-NP September 2010 Revision 0

A-6 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 Uncertainty 63 60 Cu(n,a) Co 5%

54 54 Fe(n,p) Mn 5%

58 Ni(n,p) 58Co 5%

238 U(n,f)137 Cs 10%

237 Np(n,f) 137 Cs 10%

59 60 Co(nY) Co 5%

These uncertainties are given at the 1a level.

Dosimetrv 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 commonuse. Both cross-sections and uncertaihties 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 Comanche Peak Unit 2 surveillance program, the following uncertainties in the fission spectrum averaged cross-sections are provided in the SNLRML documentation package.

Reaction Uncertainty 63 Cu(n,a) 60Co 4.08-4.16%

"4Fe(n,p) 54Mn 3.05-3.11%

58 Ni(n,p) 58Co 4.49-4.56%

238 U(n,f) 137Cs 0.54-0.64%

237 37 Np(n,f)1 Cs 10.32-10.97%

59 Co(nY) 60 Co 0.79-3.59%

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A-7 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:

Mgg =R +Rg *R *P where R, specifies an overall fractional normalization uncertainty and the fractional uncertainties Rg and Rg, specify additional random groupwise uncertainties that are correlated with a correlation matrix given by:

Pgg, [1 -0*]gg, + 0 e-H where 2

H - (g -2 g')

2 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 6 is 1.0 when g = g', and is 0.0 otherwise.

The set of parameters defining the input covariance -matrix for the Comanche Peak Unit 2 calculated spectra was as follows:

Flux Normalization Uncertainty (Rn) 15%

Flux Group Uncertainties (Rg, Rg')

(E > 0.0055 MeV) 15%

(0.68 eV < E < 0.0055 MeV) 25%

(E < 0.68 eV) 50%

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A-8 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 A.1.3 Comparisons of Measurements and Calculations Results of the least squares evaluations of the dosimetry from the Comanche Peak Unit 2 surveillance capsules withdrawn and analyzed 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 la 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 7-8% for iron atom displacement rate. Again, the uncertainties from the least squares evaluation are at the Ia level.

Further comparisons of the measurement results (from Tables A-5 and A-6) 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 0.92 to 1.26 for the 15 samples included in the data set.

The overall average MI/C ratio for the entire set of Comanche Peak Unit 2 data is 1.08 with an associated standard deviation of 8.2%.

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A-9 In the comparisons of best-estimate and calculated fast neutron exposure parameters, the corresponding BE/C comparisons for the capsule data sets range from 0.98 to 1.14 for neutron flux (E > 1.0 MeV) and from 1.01 to 1.13 for iron atom displacement rate. The overall average BE/C ratios for neutron flux (E > 1.0 MeV) and iron atom displacement rate are 1.05 with a standard deviation of 7.8% and 1.06 with a standard deviation of 6.1%, 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 Comanche Peak Unit 2 reactor pressure vessel.

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A-I0 Table A-I Nuclear Parameters Used in the Evaluation of Neutron Sensors Reaction of Target Atom 900% Response Product Fission Yield Monitor Material Interest Fraction Range (MeV) ,Half-life . (%)

63 Copper Cu (n,aX) 0.6917 4.9-11.9 5.271 y 54 Iron Fe (n,p) 0.0585 2.1 -8.5 312.1 d 5

Nickel 8Ni (n,p) 0.6808 1.5 - 8.3 70.82 d 238 Uranium-238 U (n,f) 1.0000 1.3 - 6.9 30.07 y 6.02 237 Neptunium-237 Np (n,f) 1.0000 0.3 -3.8 30.07 y 6.17 59 Cobalt-Aluminum Co (n,y) 0.0015 non-threshold 5.271 y Note:

The 90% response range is defined such that, in the neutron spectrum characteristic of the Comanche Peak 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.

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A-11 Table A-2 Monthly Thermal Generation During the First Eleven Fuel Cycles of the Comanche Peak Unit 2 Reactor (Reactor Power of 3411 MWt from Startup through 10/7/99, 3445 MWt from 10/7/99 through 10/16/01, and 3458 MWt from 10/16/01 through the End of Cycle 11)

Thermal Thermal Thermal Thermal Month- Generation Month- Generation Month- Generation Month- Generation Year (MWt-hr) Year (MWt-hr) 'Year (MWt-hr) Year (MWt-,hr)

Mar-93 5239 Mar-95 2496279 Mar-97 2536640 Mar-99 1548126 Apr-93 665227 Apr-95 2291046 Apr-97 2450049 Apr-99 473690 May-93 499862 May-95 1551323 May-97 2144436 May-99 2536163 Jun-93 0 Jun-95 2414907 Jun-97 2368587 Jun-99 2446800 Jul-93 1398237 Jul-95 2537455 Jul-97 2530139 Jul-99 2533421 Aug-93 2506266 Aug-95 2533692 Aug-97 2536238 Aug-99 2535877 Sep-93 1317192 Sep-95 2451091 Sep-97 2451498 Sep-99 2454020 Oct-93 2397305 Oct-95 2537946 Oct-97 1958440 Oct-99 2547941 Nov-93 2066821 Nov-95 2447406 Nov-97 0 Nov-99 2478920 Dec-93 2512243 Dec-95 2116020 Dec-97 1470859 Dec-99 2561649 Jan-94 2471392 Jan-96 2528370 Jan-98 2532970 Jan-00 2558037 Feb-94 1545102 Feb-96 1731998 Feb-98 2227110 Feb-00 2396090 Mar-94 1165989 Mar-96 0 Mar-98 2428176 Mar-00 2559136 Apr-94 1225995 Apr-96 0 Apr-98 2450649 Apr-00 2476416 May-94 0 May-96 1738972 May-98 2533092 May-00 2561079 Jun-94 608905 Jun-96 2329301 Jun-98 2454480 Jun-00 2472280 Jul-94 2417607 Jul-96 2530637 Jul-98 2285176 Jul-00 2558036 Aug-94 1728640 Aug-96 2532626 Aug-98 2048721 Aug-00 2561286 Sep-94 2323301 Sep-96 2011808 Sep-98 2281630 Sep-00 2383888 Oct-94 342436 Oct-96 2353951 Oct-98 2532717 Oct-00 0 Nov-94 317387 Nov-96 2449903 Nov-98 2450886 Nov-00 1926717 Dec-94 2534919 Dec-96 2515648 Dec-98 2535523 Dec-00 2560103 Jan-95 2527469 Jan-97 2118763 Jan-99 2312036 Jan-01 2560732 Feb-95 2280649 Feb-97 2281115 Feb-99 2285274 Feb-01 2308856 WCAP-17269-NP September 2010 Revision 0

A-12 Table A-2 (Continued) Monthly Thermal Generation During the First Eleven Fuel Cycles of the Comanche Peak Unit 2 Reactor (Reactor Power of 3411 MWt from Startupthrough 10/7/99, 3445 MWt from 10/7/99 through 10/16/01, and 3458 MWt from 10/16/01 through the End of Cycle 11)

Thermal Thermal Thermal Thermal Month- Generation Month- Generation Month- Generation Month- Generation" Year (MWt-hr) 'Year .(MWt~hr) Year (MWt-hr) Year (MWt-hr)

Mar-01 2551290 May-03 1320086 Jul-05 2565762 Sep-07 2488899 Apr-01 2478855 Jun-03 2465264 Aug-05 2567525 Oct-07 2570046 May-01 2561154 Jul-03 111801 Sep-05 2487748 Nov-07 2492064 Jun-01 2474728 Aug-03 2547906 Oct-05 2564267 Dec-07 2571882 Jul-01 2431971 Sep-03 2473497 Nov-05 2488298 Jan-08 2569185 Aug-01 2560721 Oct-03 384321 Dec-05 2571074 Feb-08 2405943 Sep-01 2478056 Nov-03 2417397 Jan-06 2566082 Mar-08 2125790 Oct-01 2565724 Dec-03 2178790 Feb-06 2322771 Apr-08 932174 Nov-01 2486883 Jan-04 2548556 Mar-06 2567895 May-08 2567597 Dec-01 2569796 Feb-04 2385232 Apr-06 2485431 Jun-08 2486976 Jan-02 2563715 Mar-04 2544441 May-06 2571435 Jul-08 2571426 Feb-02 2320836 Apr-04 2479308 Jun-06 2488956 Aug-08 2571837 Mar-02 2419437 May-04 2565864 Jul-06 2567925 Sep-08 2488910 Apr-02 0 Jun-04 2476634 Aug-06 2571915 Oct-08 2571737 May-02 1996301 Jul-04 2567252 Sep-06 2478864 Nov-08 2482583 Jun-02 2333719 Aug-04 2569751 Oct-06 643723 Dec-08 2571908

• Jul-02 2509555 Sep-04 2483501 Nov-06 2486122 Jan-09 2571027 Aug-02 2542003 oct-04 2563599 Dec-06 2572531 Feb-09 2322983 Sep-02 2468447 Nov-04 2478648 Jan-07 2572442 Mar-09 2568015 Oct-02 2553421 Dec-04 2570238 Feb-07 2321329 Apr-09 2489118 Nov-02 2473948 Jan-05 2567214 Mar-07 2568423 May-09 2431026 Dec-02 2563144 Feb-05 2284203 Apr-07 2487473 Jun-09 2488797 Jan-03 2560486 Mar-05 2007877 May-07 2572745 Jul-09 2570769 Feb-03 2315079 Apr-05 148984 Jun-07 2489726 Aug-09 2571684 Mar-03 2567033 May-05 2537525 Jul-07 2568944 Sep-09 2488098 Apr-03 2475564 Jun-05 2488337 Aug-07 2571861

• Oct-09 448292 WCAP-17269-NP September2010 Revision 0

A-13 Table A-3 Calculated Cj Factors at the Surveillance Capsule Center Core Midplane Elevation Cycle p)(E > 1.0 MeV) [n/cm 2 -sJ Length Fuel Cycle [EFPS], 1Capsule U. Capsul e X. Capsule W I 2.87E+07 1.11E+11 1.11E+11 1.09E+1I 2 3.73E+07 7.16E+10 7.10E+10 3 4.42E+07 7.85E+10 7.76E+10 4 3.84E+07 7.20E+10 7.13E+10 5 4.52E+07 7.12E+ 10 7.05E+10 6 4.37E+07 7.15E+10 7.07E+10 7 4.12E+07 7.78E+10 7.70E+10 8 4.35E+07 7.24E+10 9 4.52E+07 7.41E+ 10 10 4.44E+07 6.92E+10 11 4.60E+07 6.07E+10 Average 1.11E+11 7.76E+10 7.38E+10 Cycle Cj Length Fuel Cycle [EFPS] Capsule U Capsule X Capsule W I 2.87E+07 1.000 1.424 1.484 2 3.73E+07 0.923 0.962 3 4.42E+07 1.011 1.052 4 3.84E+07 0.928 0.966 5 4.52E+07 0.918 0.955 6 4.37E+07 0.921 0.958 7 4.1'2E+07 1.002 1.044 8 4.35E+07 0.982 9 4.52E+07 1.005 10 4.44E+07 0.939 11 4.60E+07 0.823 Average 1.000 1.000 1.000 WCAP-17269-NP September 2010 Revision 0

A-14 Table A-4a Measured Sensor Activities and Reaction Rates Surveillance Capsule U

'Measured Activity -Saturated Activity Adjusted Reaction 1Reaction Location (dps/g) '(dps/g) Rate (rps/atom) 63 60 CU (nC) Co Top 4.78E+04 4.56E+05 6.96E-17 Middle 4.28E+04 4.09E+05 6.24E- 17 Bottom 4.29E+04 4.1OE+05 6.25E-17 Average 6.48E-17 54 Fe (np) 54Mn Top 1.39E+06 4.09E+06 6.49E-15 Middle 1.27E+06 3.73E+06 5.93E-15 Bottom 1.27E+06 3.73E+06 5.93E-15 Average 6.11E-15 5 5 SNi (np) 8Co Top 1.30E+07 6.06E+07 8.68E-15 Middle 1.21E+07 5.64E+07 8.08E-15 Bottom 1.21E+07 5.64E+07 8.08E-15 Average 8.28E-15 238 U (n,f) 137Cs (Cd) Middle 1.37E+05 6.69E+06 4.39E-14 235 239 Including U, Pu, and 7 fission corrections: 3.70E-14 237 Np (n,f) 137 Cs (Cd) Middle [ 1.21E+06 5.91E+07 3.77E-13 Including y fission corrections: 3.73E-13 59 6 Co (nY) 0Co Top 9.83E+06 9.39E+07 6.12E-12 Middle 1.03E+07 9.84E+07 6.42E-12 Bottom 1.03E+07 9.84E+07 6.42E-12 Average 6.32E-12 59 6 Co (ny) °Co (Cd) Top 5.29E+06 5.05E+07 3.30E-12 Middle 5.65E+06 5.40E+07 3.52E-12 Bottom 5.55E+06 5.30E+07 3.46E-12 Average 3.43E-12 Notes:

1. Measured specific activities are indexed to a counting date of February 1, 1995.

238

2. The average U (n,f) reaction rate of 3.70E-14 includes a correction factor of 0.872 to account for plutonium build-in and an additional factor of 0.966 to account for photo-fission effects in the sensor.

237

3. The average Np (n,f) reaction rate of 3.73E-13 includes a correction factor of 0.990 to account for photo-fission effects in the sensor.

4. Reaction rates referenced to the Cycle I Rated Reactor Power of 3411 MWt.

September 2010 WCAP-I 7269-NP WCAP-17269-NP September 2010 Revision 0

A-15 Table A-4b Measured Sensor Activities and Reaction Rates Surveillance Capsule X MeasuredActivity. Saturated Activity Adjusted Reaction

Reaction Location (dps/g) (dps/g) Rate (rps/atom) 63 Cu (na) 60 CO Top 1.91E+05 3.06E+05 4.66E-17 Middle 1.71E+05 2.74E+05 4.18E-17 Bottom 1.68E+05 2.69E+05 4.10E-17 Average 4.31E-17 54 54 Fe (n,p) Mn Top 2.44E+06 3.13E+06 4.97E-15 Middle 2.23E+06 2.86E+06 4.54E-15 Bottom 2.18E+06 2.80E+06 4.44E-15 Average 4.65E-15 58 58 Ni (np) Co Top 2.48E+07 4.78E+07 6.84E-15 Middle 2.29E+07 4.41 E+07 6.31E-15 Bottom 2.25E+07 4.33E+07 6.20E-15 Average 6.45E-15 238 U (n,f) 137Cs (Cd) Middle 9.58E+05 5.3 1E+06 3.49E-14 Including 231U, 239Pu, andy fission corrections: 2.71E-14 237 37 Np (n,f) 1 Cs (Cd) Middle 1 7.11E+06 3.94E+07 2.51E-13 Including y fission corrections: 2.49E-13 59 Co (n,y) 6PCo Top 3.84E+07 6.15E+07 4.01E-12 Middle 3.91E+07 6.26E+07 4.08E-12 Bottom 4.03E+07 6.45E+07 4.21 E- 12 Average 4.10E-12 "Co (nY) 60Co (Cd) Top 2.1OE+07 3.36E+07 2.19E-12 Middle 2.14E+07 3.43E+07 2.23E-12 Bottom 2.20E+07 3.52E+07 2.30E-12 Average 2.24E-12 Notes:

1. Measured specific activities are indexed to a counting date of November 26, 2003.

23

2. The average 8U (n,f) reaction rate of 2.71E-14 includes a correction factor of 0.804 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 237Np (n,f) reaction rate of 2.49E-13 includes a correction factor of 0.990 to account for photo-fission effects in the sensor.'

4. Reaction rates referenced to the Cycles 1-7 Average Rated Reactor Power of 3428 MWt.

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A-16 Table A-4c Measured Sensor Activities and Reaction Rates Surveillance CapsuleW Measured Activity Saturated Activity Adjusted Reaction Reactionj Location (dps/g) ,(dps/g) Rate (rps/atomr) 63 60 CU (n,ct) Co Top 2.15E+05 2.93E+05 4.47E-17 Middle 2.17E+05 2.95E+05 4.51E-17 Bottom 2.47E+05 3.36E+05 5.13E- 17 Average 4.70E-17 54 54 Fe (n,p) Mn Top 1.67E+06 2.89E+06 4.59E-15 Middle 1.67E+06 2.89E+06 4.59E-15 Bottom 1.86E+06 3.22E+06 5.11 E-15 Average 4.76E-15 5

8Ni (n,p) 58Co Top 7.53E+06 4.74E+07 6.79E-15 Middle 7.57E+06 4.77E+07 6.83E-15 Bottom 8.32E+06 5.24E+07 7.50E- 15 Average 7.04E-15 23 137 8U (n,f) Cs (Cd) Middle 1.67E+06 6.06E+06 3.98E-14 U, 239 Pu, and y fission corrections:

23 5 Including 2.94E-14 237 37 Np (n,f) 1 Cs (Cd) Middle I 1.08E+07 3.92E+07 2.50E-13 Including y fission corrections: 2.48E-13 59 Co (ny) 6°Co Top 4.69E+07 6.39E+07 4.17E-12 Middle 4.79E+07 6.52E+07 4.25E-12 Bottom 4.69E+07 6.39E+07 4.17E-12 Average 4.19E-12 59 Co (nY) 6°Co (Cd) Top 2.52E+07 3.43E+07 2.24E-12 Middle 2.51E+07 3.42E+07 2.23E-12 Bottom 2.45E+07 3.34E+07 2.18E-12 Average 2.21E-12 Notes:

1. Measured specific activities are indexed to a counting date of March 22, 2010.

2. The average 238U (n,f) reaction rate of 2.94E-14 includes a correction factor of 0.764 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 237 Np (n,f) reaction rate of 2.48E-13 includes a correction factor of 0.991 to account for photo-fission effects in the sensor.

4. Reaction rates referenced to the Cycles 1-11 Average Rated Reactor Power of 3440 MWt.

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A-17 Table A-5 Comparison of Measured, Calculated, and Best Estimate Reaction Rates at the Surveillance Capsule Center Capsule U Reaction Rate [rps/atom]

Reaction Measured Calculated Best Estimate M/C M/BE' 63 Cu(n,a) 6 °Co 6.48E-17 5.59E-17 6.13E-17 1.16 1.05 54 54 Fe(n,p) Mn 6.11 E-15 6.38E-15 6.32E-15 0.96 0.97 5 5 8Ni(n,p) 8Co 8.28E-15 8.97E-15 8.75E-15 0.92 0.94 23 37 8U(n,f)1 Cs (Cd) 3.70E-14 3.48E-14 3.42E-14 1.06 1.09 237 137 Np(n,f) Cs (Cd) 3.73E-13 3.44E-13 3.58E-13 1.08 1.04 59 Co(nY) 60Co 6.32E-12 4.95E-12 6.20E-12 1.28 1.02 59 Co(nY) 60Co (Cd) 3.42E-12 3.44E-12 3.47E-12 0.99 0.99 Note:

See Section A. 1.2 for details describing the Best-Estimate (BE) reaction rates.

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A-18 Table A-5 (Continued) Comparison of Measured, Calculated, and Best Estimate Reaction Rates at the Surveillance Capsule Center

• , . .. Caps*. X Reaction Rate [rps/atoni]

Reaction Measured Calculated Best Estimate M/C M/BE 63 60 Cu(n, a) Co 4.31E-17 4.19E-17 4.28E-17 1.03 1.01 54 54 Fe(n,p) Mn 4.65E-15 4.61E-15 4.69E415 1.01 0.99 "Ni(n,p) 5t Co 5

6.45E-15 6.46E-15 6.55E-15 1.00 0.98 23 137 8U(n,f) Cs (Cd) 2.71E-14 2.46E-14 2.53E-14 1.10 1.06 237 37 Np(n,f)1 Cs (Cd) 2.49E-13 2.40E-13 2.49E-13 1.04 1.00 59o(n,7)60Co 4.10E-12 3.39E-12 4.03E-12 1.21 1.02 59 Co(nY) 60Co (Cd) 2.24E-12 2.36E-12 2.27E-12 0.95 0.99 Note:

See Section A. 1.2 for details describing the Best-Estimate (BE) reaction rates.

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A-19 Table A-5 (Continued) Comparison of Measured, Calculated, and Best Estimate Reaction Rates at the Surveillance Capsule Center Capsule W Reaction Rate [rps/atomJ*

Reaction Measured Calculated :Best Estimate :MIc' M/BE 63 60 Cu(nQ) Co 4.70E-17 4.00E-17 4.62E-17 1.18 1.02 54 54 Fe(n,p) Mn 4.76E- 15 4.38E-15 4.94E- 15 1.09 0.96 5

58Ni(n,p) 8Co 7.04E- 15 6.13E-15 7.01E-15 1.15 1.00 23 137 8U(n,f) Cs (Cd) 2.94E-14 2.33E-14 2.67E- 14 1.26 1.10 237 Np(n,f)137Cs (Cd) 2.48E-13 2.28E-13 2.54E-13 1.09 0.98 59 Co(nY) 6°Co 4.19E- 12 2.92E-12 4.10E-12 1.43 1.02 59 60 Co(nY) Co (Cd) 2.21E-12 2.07E-12 2.25E-12 1.07 0.99 Note:

See Section A. 1.2 for details describing the Best-Estimate (BE) reaction rates.

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'Revision 0

A-20 Table A-6 Comparison of Calculated and Best Estimate Exposure Rates at the Surveillance Capsule Center

_________________.... ..

• p qi(E > 4I0M eV) [n/cm2*s] ______ ..... ..

Capsuie I Calculated ' i Best' Estimate Uncertainty (1) BE/C U 1.1IE+1I1 1.09E+l 1 6% 0.98 X 7.77E+10 8.03E+10 6% 1.03 W 7.39E+10 8.42E+10 6% 1.14 Note:

Calculated results are based on the synthesized transport calculations taken at the core midplane following the completion of each respective capsules irradiation period and are the average neutron exposure over the irradiation period for each capsule.

See Section A. 1.2 for details describing the Best-Estimate (BE) exposure rates.

- . ~~Iron Atom DIsplacem~eni Rate-idp a/sI .

CasueID .. Calculaited  ; Bb~t'Estimat y(l) cU~etit -BE/C U 2.14E-10 2.17E-10 8% 1.01 X 1.49E-10 1.55E-10 8% 1.03 W 1.42E-10 1.61E-10 7% 1.13 Note:

Calculated results are based on the synthesized transport calculations taken at the core midplane following the completion of each respective capsules irradiation period and are the average neutron exposure over the irradiation period for each capsule.

See Section A. 1.2 for details describing the Best-Estimate (BE) exposure rates.

WCAP- 17269-NP September 2010 Revision 0

A-21 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, CapsuleX 'Capsule W 63 0 Cu(n,')" Co 1.16 1.03 1.18 54 Fe(n'p) 54 Mn 0.96 1.01 1.09 58 Ni(np)58Co 0.92 1.00 1.15 238 U(n,f) 13 7Cs (Cd) 1.06 1.10 1.26 237 Np(n,f) 137 Cs (Cd) 1.08 1.04 1.09 Average 1.04 1.04 1.15

% Standard Deviation 9.3 3.8 6.1 Note:

The overall average M/C ratio for the set of 15 sensor measurements is 1.08 with an associated standard deviation of 8.2%.

Table A-8 Comparison of Best-Estimate/Calculated (BE/C) Exposure Rate Ratios BE/C Ratio Capsule'lD *(E > 1.0 MeV) dpa/s U 0.98 1.01 X 1.03 1.03 W 1.14 1.13 Average 1.05 1.06

% Standard Deviation 7.8 6.1 WCAP-17269-NP September 2010 Revision 0

A-22 A.2 REFERENCES A-1 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 2001.

A-2 WCAP-14315, "Analysis of Capsule U from the Texas Utilities Electric Company Comanche Peak Steam Electric Station Unit No. 2 Reactor Vessel Radiation Surveillance Program,"

July 1995.

A-3 WCAP-16277-NP, "Analysis of Capsule X from the TXU Energy Comanche Peak Unit 2 Reactor Vessel Radiation Surveillance Program," September 2004.

A-4 A. Schmittroth, FERRETData Analysis Core, HEDL-TME 79-40, Hanford Engineering Development Laboratory, Richland, WA, September 1979.

A-5 RSICC Data Library Collection DLC-178, "SNLRML Recommended Dosimetry Cross-Section Compendium," July 1994.

A-6 ASTM Standard E l 018, Application ofASTM EvaluatedCross-Section DataFile, Matrix E706 (1IB).

A-7 ASTM Standard E944, Application ofNeutron Spectrum Adjustment Methods in Reactor Surveillance.

September 2010 WCAP-1 7269-NP WCAP- 17269-NP September 2010 Revision 0

B-1 APPENDIX B LOAD-TIME RECORDS FOR CHARPY SPECIMEN TESTS

• Specimen prefix "CL" denotes Intermediate Shell Plate R3807-2, Longitudinal Orientation

" Specimen prefix "CT" denotes Intermediate Shell Plate R3807-2, Transverse Orientation

• Specimen prefix "CW" denotes Surveillance Program Weld Metal

• Specimen prefix "CH" denotes Heat-Affected Zone Material WCAP- 17269-NP September 2010 Revision 0

B-2 BC-C 2 i

.- C*I ....

A*1 A~a,* f ýWMýAA A A& ký A. AL,& 0 CL36, F

!- 1ý ...

1C.14 cc .....

AM, A AkA AAkA A A j-NM A I MA A AO- Aý P CL38, -20 0F 0 co

]1IlIAmLý,ItCO AkAA A 0 u~AI

&A A Iý.

A . A A o.A -. CM 4 00

. -bAA-o~o~

- A-c -.

CL44, F WCAP- 17269-NP September 2010 Revision 0

B-3 cccc . . . . . . . .........

It ............

V0 tt tt ...........................

ttt ....................... . ............ . ........................

IN A ýA i#L.ýt& m ým A w.e. A iN L\ m Aý m-A---j lt tt It CL33, F it CO V ...............................

toco ............

It ........ ..... .. .. . .. ....... -

AM;:.hýA &INA-A.A-ýAAM-lh, M 0to 20. to Cc U. I

-1 -1 CL39, 00 F CL41, 25-F WCAP-17269-NP September 2010 Revision 0

B-4 cc ........ ...... ........ ..

tcn CL42, 40 0 F CL45, 60°F OCO Iý- 2*C . 1. Mc I ýO CL34, 80°F September 2010 WCAP-1 WCAP-1 7269-NP September 2010 Revision 0

B-5 j

CL31, 125 0 F I

T*t i*)

CL35, 200-F H .c c: ............. . ............... a ..

cc cc ...........

cc ........... ...... ...

cc11 ..........

iccccc -- 4 I cc 2 cc Icc ec 0 cc CL43, 275-F WCAP-17269-NP September 2010 Revision 0

B-6 CL40, 300-F 20 ....................... ....... ..................

11 ..........

CL32, 325°F

+/-V~3 CL37, 350°F WCAP-17269-NP September 2010 Revision 0

B-7 Mc c ... .. . . .... . ........ ....

a Ic* .....

cccccc cc uIA mLIM A j.A ic.

As Nm AAA A... A &A cc A. AA CT43, F

ýc .....

ýc* ..

A, A A -N A jL CT39,30-F sc ......................

V0 cc,.

. cc ,cc 2CO . cc ScO CT31, 50-F WCAP-17269-NP September 2010 Revision 0

B-8 CO 1co A, A.. A AM- A 2*Q A A A -N A.m 4C0

! .C Il CT34, 55°F CT41, 65-F CT44, 75-F September 2010 WCAP- 7269-NP WCAP-117269-NP September 2010 Revision 0

B-9 a¢CC co ....... ........ . ..o.. ... .. .. . ....

CT38, 100°F

- '0001 CT33, 125°F

11. 1¢0 2*g 4 gl Iýý CO2me-tl)

CT42, 130°F WCAP-17269-NP September 2010 Revision 0

B-10 a

Ico fýl II CT45, 140°F CT32, 150°F

- 00'00 1~

CT36, 200°F September 2010 WCAP- 7269-NP WCAP-1I17269-NP September 2010 Revision 0

B-11 CT35, 275-F CT40, 3000 F CT37, 325°F WCAP-17269-NP September 2010 Revision 0

B-12 ANA AaAA M IM AA, 1&',A -A ýAA A- A A.

SO CW38, -90 0 F

]

Iýl CW40, 25 0 F z

]

-1l '.)

CW45, 30 0 F September 2010 WCAP- 7269-NP WCAP-117269-NP September 2010 Revision 0

B-13 i

CW33, 30 0 F

.e*.. :. ... .... .. .. . .. .. ......................... .. ... . . . . . . . .. . . . . . ..... .......... .. . ......... .. . . ....................... . . . . . . . ..................... .. ..

CW43, 35°F

• e *... ..... . .. ... ... ...

... . .............. ............ ......... ................... . . . . . . . . ..... . . ...... ....... ..... i ..... ............ ............... ...................... ...... ......

.*z.c.c.... . .............. .. . .. .. . .. .. .. . .. .. . . . .. . .. .. .. . .. .. . . . . . . .. .. . . . .. .. . .. .. . .. . .. .. ....

............. ... . .. ...::... ... ... ... ............... .:................ ..... . ............... . .. . .... . . ... .. . . . . . . . . . . . . . . . ..i . . . . . . . . . . . . . . . .

G©O 2 *. I ý.

CW42, 40 0 F WCAP-17269-NP September 2010 Revision 0

B-14

-I I-ANX.AA AA It, oto I to, ýoGl I0 CW31, 45°F 3C*

W*,.! ,*1 CW35, 45°F

!tooco ot I

"otoo tooto

... .A.. ..

A I& M -,A too I CO -NAAIýM 2Qg f%,,M 3CC -. 00 .ol v*l t*)

CW41, 50-F WCAP- 17269-NP September 2010 Revision 0

B-15

£ B-15 CW32, 50-F i

• C0 CW36, 75 0 F CW44, 1750 F WCAP- 17269-NP September 2010 Revision 0

B-16 1-11, C C0 *GO 2U QO CW37, 275°F 2C0 CW39, 3000 F CW34, 325 0 F WCAP- 17269-NP September 2010 Revision 0

B-17 WOco ...............................

S U2.

1-40 ................. .. ..............

11 AA k A I 0 I isoo ioAo Lla ...

&] A+/-+/- din~

, En. .. Al

.oLi.faý -.. aAA. .AN A CH31, -175-F 1000cc

................. ~~~~~......

~~~~~~~~~~

00-1--

0000 00A 0Lr AL0000 r+/-011.~2 fOLf...................................A Ma ýl ýýA I A A 0.C0 000 U En ^j 200 N

.0 wCH39, 000

-9 0F A0 u0k 000 A 3A - 0.00 w 0 0

CH39, -90 0 F ooL I1ý I1O 2,0.

A L.A oN. .00, AA 0, A A.

AA IPIA ýA 0001010 A X L M A IL 1

CH44, -80 0 F WCAP-17269-NP September 2010 Revision 0

B-I8 CH42, -75°F

~Ot Am .Am& A A A

ý CH33,-75°F CH37, -70 0 F WCAP- 17269-NP September 2010 Revison 0

B-19 CH43, F AM J& A J,. ./AA

-- c *C0 I. I CH34, -60°F CH36, F WCAP- 17269-NP September 2010 Revision 0

B-20 33rm.1*)

CH41, -60 0 F a:*c ~ ~ ~ Le A t\ ,k .o c ,.o+o CH38, -50 0 F CH32, -25 0 F WCAP-17269-NP September 2010 Revision 0

B-21 F

CH45, 200-F I..,C CH40, 225-F CH35, 2750 F WCAP-17269-NP September 2010 Revision 0

C-1 APPENDIX C CHARPY V-NOTCH PLOTS FOR EACH CAPSULE USING SYMMETRIC HYPERBOLIC TANGENT CURVE-FITTING METHOD Contained in Table C-I are the upper shelf energy (USE) values used as input for the generation of the Charpy V-notch plots using CVGRAPH, Version 5.3. The definition for USE is given in ASTM E185-82

[Ref. C-I], Section 4.18, and reads as follows:

"upper shelf energy level - the average energy value for all Charpy specimens (normally three) whose test temperature is above the upper end of the transition region. For specimens tested in sets of three at each test temperature, the set having the highest average may be regarded as defining the upper shelf energy."

If there are specimens tested in sets of three at each temperature, Westinghouse typically reports the set having the highest average energy as the USE (usually unirradiated material). If the specimens were not tested in sets of three at each temperature, Westinghouse reports the average of all Charpy data (> 95%

shear) as the USE, excluding any values that are deemed outliers using engineering judgment. Hence, the Capsule W USE values reported in Table C-1 were determined by applying this methodology to the Charpy data tabulated in Tables 5-1 through 5-4 of this report. USE values documented in Table C-1 for the unirradiated material, as well as Capsules U and X, were imported directly from Reference C-2. The USE values reported in Table C-I were used in generation of the Charpy V-notch curves.

The lower shelf energy values were fixed at 2.2 ft-lb for all cases. The lower shelf Lateral Expansion values were fixed at 0.0 mils in order to be consistent with the previous capsule analysis [Ref. C-2].

Table C-1 Upper Shelf Energy Values (ft-lb) Fixed in CVGRAPH Capsule Material Unirradiated U . X W Intermediate Shell Plate R3807-2 Longitudinal Orientation 115 118 120 118.4 Intermediate Shell Plate R3807-2 84 88 91 84.0 Transverse Orientation Surveillance Program Weld Metal 94 85 96 83.5 (Heat # 89833)

HAZ Material 116 127 116 111.0 CVGRAPH Version 5.3 plots of all surveillance data are provided in this appendix, on the pages following the reference list.

September 2010 WCAP-l 7269-NP WCAP-17269-NP September 2010 Revision 0

C-2 C.1 REFERENCES C-1 ASTM E185-82, Standard Practicefor Conducting Surveillance Tests for Light-Water Cooled NuclearPower Reactor Vessels, E706(IF), ASTM, 1982.

C-2 WCAP-16277-NP, Revision 0, Analysis of CapsuleXfrom the TXU Energy Comanche Peak Unit 2 Reactor Vessel Radiation Surveillance Program, September 2004.

September 2010 WCAP- 17269-NP WCAP-17269-NP September 2010 Revision 0

C-3 C.2 CVGRAPH VERSION 5.3 INDIVIDUAL PLOTS UNIRRADIATED (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/29/2010 11:16 AM Page I Coefficients of Curve I A = 58.6 B = 56.4 C = 93.38 TO = 42.7 D = O.OOE+O0 Equation is A + B

• lTanh((T-To)/(C+DT))l Upper Shelf Energy= I15.0(Fixed) Lower Shelf Energy-2.2(Fixed)

Temp@30 ft-lbs=-9.4 Deg F Temp@50 ft-lbs=28.4 Deg F Plant: Comanche Peak 2 Material: SA533B I Heat: C5522-2 Orientation: LT Capsule: UNIRR Fluence: n/cmA2 300 250 *I. 4 4 4- 4 4 200 U.

150 C

I.1J 00 z

> 100 U

00 50 080 n3

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

-80. 00 II. 00 9. 80 I . 20

-60. 00 6. 00 13.45 -7. 45

-60. 00 12. 00 13.45 - . 45

-30. 00 19. 00 21.83 -2.83

- 30. 00 22. 00 21. 83 .17

-30. 00 35. 00 21.83 13. 17

.00 33. 00 34. 47 - I. 47

• 00 33. 00 34. 47 - I. 47

-00 35. 00 34. 47 .53 WCAP-17269-NP September 2010 Revision 0

C-4 UNIRRADIATED (LONGITUDINAL ORIENTATION)

Page 2 Plant: Comanche Peak 2 Material: SA533BI Heat: C5522-2 Orientation: LT Capsule: UNIRR Fluence: n/cm^2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

• 00 68. 00 34. 47 33. 53

40. 00 35. 00 56. 97 -21. 97

40. 00 41.00 56. 97 -15.97

40. 00 81. 00 56. 97 24. 03

60. 00 55. 00 68. 93 -13.93

60. 00 60. 00 68. 93 -8.93

60. 00 77. 00 68. 93 8. 07

80. 00 64. 00 80. 00 -16.00

80. 00 65. 00 80. 00 -15.00

80. 00 76. 00 80. 00 -4.00 120. 00 107. 00 96. 91 10. 09 120. 00 108. 00 96. 91 11. 09 120. 00 118. 00 96. 91 21.09 160. 00 114. 00 106. 54 7.46 160. 00 115 00 106. 54 8. 46 160. 00 115. 00 106. 54 8. 46 260. 00 I 1. 00 113.94 -2.94 260. 00 114. 00 113.94 .06 260. 00 118. 00 113.94 4.06 320. 00 I 1. 00 114. 70 -3.70 320. 00 118. 00 114.70 3. 30 Correlation Coefficient = .950 September 2010 WCAP-1 7269-NP September 2010 Revision 0

C-5 UNIRRADIATED (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/29/2010 11:19 AM Page 1 Coefficients of Curve I A = 41.42 B = 41.42 C = 89.07 TO = 47.28 D = O.OOE+OO Equation is A + B

• lTanh((T-Toy(C+DT))I Upper Shelf L.E.=82.8 Lower Shelf LE.=.O(Fixed)

Temp.@LE. 35 mils=33.4 Deg F Plant: Comanche Peak 2 Material: SA533B I Heat: C5522-2 Orientation: LT Capsule: UNIRR Fluence: n/cmA2 200 150 E

.o 100 50 0o-

-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed LE. Differential

-80. 00 I. 00 .4. 510 -3.50

-60. 00 2.00 6. 83 -4.83

-60. 00 2.00 6. 83 -4. 8,3

-30. 00 10. 00 12. 42 -2. 42

- 30. 00 12. 00 12. 42 - . 42

- 30. 00 22. 00 12.42 9.58 00 21. 00 21.29 - . 29

• 00 24. 00 21. 29- 2.71

.00 20. 00 21.29 - I. 29 WCAP-17269-NP September 2010 Revision 0

C-6 UNIRRADIATED (LONGITUDINAL ORIENTATION)

Page 2 Plant: Comanche Peak 2 Material: SA533BI Heat: C5522-2 Orientation: LT Capsule: UNIRR Fluence: n/cm^2 Charpy V-Notch Data Temperature Input L.E. Computed LE Differential

. 00 41. 00 21. 29 19.71

40. 00 19.00 38. 04 -19.04

40. 00 27. 00 38. 04 -1 1. 04

40. 00 49. 00 38. 04 10.96

60. 00 48. 00 47. 30 .70

60. 00 44. 00 47. 30 -3. 30

60. 00 58. 00 47. 30 10.70

80. 00 49. 00 55. 99 -6. 99

80. 00 42. 00 55. 99 -13. 99

80. 00 58. 00 55. 99 2.0O 120. 00 76. 00 69. 30 6. 70 120. 00 7 1. 00 69. 30 1 .70 120. 00 79. 00 69. 30 9. 70 160. 00 81. 00 76. 74 4. 26 160. 00 79. 00 76. 74 2. 26 160. 00 79.00 76. 74 2. 26 260. 00 76. 00 82. 15 -6. 15 260. 00 80. 00 82. 15 -2. 15 260. 00 81. 00 82. 15 -I .15 320. 00 79. 00 82. 66 -3. 66 320. 00 84. 00 82. 66 I. 34 Correlation Coefficient = .962 WCAP- 17269-NP September 2010 Revision 0

C-7 UNIRRADIATED (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 04/27/2010 02:03 PM Page 1 Coefficients of Curve I A = 50. B = 50. C = 82.77 TO = 55.95 D = O.OOE+O0 Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear= 56.0 Plant: Comanche Peak 2 Material: SA533B I Heat C5522-2 Orientation: LT Capsule: UNIRR Fluence: n/cmA2 125 100

'U 75 0

Co 0

20 50 a-25 0 4-41 --- =[=ZF- 4.-I -1 - 4. 4 1- -s--

& 4

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

-80. 00 9. 00 3.61 5. 39

-60. 00 2. 00 5. 72 -3. 72

-60. 00 2. 00 5.72 -3.72

30. 00 25. 00 11.14 13.86

-30. 00 11. 00 11. 14 -. 14

-30. 00 25. 00 11.14 13.86

.00 29. 00 20. 55 8. 45

.00 17. 00 20. 55 -3. 55

.00 16. 00 20. 55 -4. 55 WCAP- 17269-NP September 2010 Revision 0

C-8 UNIRRADIATED (LONGITUDINAL ORIENTATION)

Page 2 Plant: Comanche Peak 2 Material: SA533BI Heat: C5522-2 Orientation: LT Capsule: UNIRR Fluence: n/cm^2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

.00 30. 00 20. 55 9. 45

40. 00 2 1. 00 40. 48 -19.48

40. 00 30. 00 40. 48 - 10. 48

40. 00 60. 00 40. 48 19.52

60. 00 60. 00 52. 44 7. 56

60. 00 48. 00 52. 44 - 4. 44

60. 00 43. 00 52. 44 - 9. 44

80. 00 48. 00 64. 13 - 16. 13

80. 00 59. 00 64. 13 -5. 13

80. 00 63. 00 64. 13 -1. 13 120. 00, 90. 00 82. 46 7. 54 120.00 82. 00 82. 46 - . 46 120.00 100. 00 82. 46 17. 54 160. 00 100. 00 92.51 7. 49 160.00 100. 00 92.51 7. 49 160.00 100. 00 92.51 7. 49 260. 00 100. 00 99. 28 72 260. 00 00 99. 28 72 260. 00 100. 00 99. 28 72 320.00 100. 00 99. 83 17 320. 00 100. 00 99. 83 17 Correlation Coefficient - .968 WCAP-1 7269-NP September 2010 Revision 0

C-9 UNIRRADIATED (TRANSVERSE ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 04/30/2010 04:03 PM Page 1 Coefficients of Curve I A = 43.1 B = 40.9 C = 107.72 TO = 23.65 D = O.OOE+00 Equation is A + B

• ITanh((T-To)/(C+DT))I Upper Shelf Energy=84.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=-12.1 Deg F Temp@50 ft-lbs=42.1 Deg F Plant: Comanche Peak 2 Material: SA533B I Heat: C5522-2 Orientation: TL Capsule: UNIRR Fluence: n/cmA2 300 250 200 150 C

w z

U> 100 50 0 i i

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 120. 00 9. 00 7. 51 I. 49

- 120. 00 10.00 7.51 2. 49

-80. 00 13. 00 12.62 .38

-80. 00 18.00 12.62 5. 38

-60. 00 15. 00 16.48 -I .48

-60. 00 21. 00 16.48 4. 52

-60. 00 22. 00 16. 48 5. 52

-30. 00 27. 00 24. 26 2.74

-30. 00 32. 00 24. 26 7. 74 WCAP- 17269-NP September 2010 Revision 0

C-IO UNIRRADIATED (TRANSVERSE ORIENTATION)

Page 2 Plant: Comanche Peak 2 Material: SA533BI Heat: C5522-2 Orientation: TL Capsule: UNIRR Fluence: n/cm^2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

-30. 00 34. 00 24. 26 9.74

.00 28. 00 34. 26 -6. 26

.00 30. 00 34. 26 -4.26

.00 30. 00 34.26 -4.26

40. 00 33. 00 49. 26 -16. 26

40. 00 40. 00 49. 26 -9.26

40. 00 52. 00 49. 26 2.74

80. 00 54. 00 62.73 -8.73

80. 00 57. 00 62. 73 -5.73

80. 00 66. 00 62. 73 3. 27 120.00 75. 00 72.28 2.72 120. 00 84. 00 72. 28 11.72 120. 00 88. 00 72.28 15.72 160. 00 79. 00 77.97 1. 03 160. 00 81. 00 77. 97 3.03 160.00 96. 00 77. 97 18. 03 260. 0.0 80. 00 83. 00 -3. 00 260. 00 82. 00 83. 00 - I. 00 260. 00 84. 00 83. 00 I. 00 320. 00 78. 00 83. 67 -5. 67 320. 00 84. 00 83. 67 .33 Correlation Coefficient = .967 WCAP-17269-NP September 2010 Revision 0

C-11 UNIRRADIATED (TRANSVERSE ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 04/30/2010 04:04 PM Page I Coefficients of Curve I A = 32.79 B = 32.79 C = 92.46 TO = 32.86 D = O.OOE+OO Equation is A + B

• ITanh((T-To)/(C+DT))I Upper Shelf L.E.=65.6 Lower Shelf L.E=.0(Fixed)

Temp.@L.E. 35 mils=39. I Deg F Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: TL Capsule: UNIRR Fluence: n/cmA2 200 150 E

E 100 550 0 _0_

80 OK 0

0

-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed LE. Differential

- 120. 00 2. 00 2. 32 -. 32

-120. 00 1.00 2. 32 -I 32

-80. 00 3. 00 5. 25 -2. 25

-80. 00 1.00 5. 25 -4. 25

-60. 00 7. 00 7. 76 76

-60. 00 7. 00 7. 76 76

-60. 00 4. 00 7. 76 -3. 76

-30. 00 21. 00 13. 40 7. 60

-30. 00 20.00 13. 40 6. 60 WCAP-1 7269-NP September 2010 Revision 0

C-12 UNIRRADIATED (TRANSVERSE ORIENTATION)

Page 2 Plant: Comanche Peak 2 Material: SA533BI Heat: C5522-2 Orientation: TL Capsule: UNIRR Fluence: n/cm^2 Charpy V-Notch Data Temperature Input L.E. Computed LE Differential

- 30. 00 22. 00 13.40 8. 60

.00 21. 00 21.61 -. 61

.00 19.00 21.61 -2.61

.00 20. 00 21.61 -I.61

40. 00 28. 00 35. 32 -7.32

40. 00 30. 00 35. 32 -5.32

40. 00 38. 00 35. 32 2.68

80. 00 43. 00 48. 20 -5.20

80. 00 47. 00 48. 20 - I. 20

80. 00 52. 00 48. 20 3. 80 120. 00 55. 00 56. 94 - I. 94 120. 00 62. 00 56. 94 5. 06 120. 00 65. 00 56. 94 8.06 160. 00 57. 00 61 64 -4.64 160. 00 62. 00 61. 64 .36 160. 00 69. 00 61.64 7. 36 260. 00 65. 00 65. 11 - . 11 260. 00 62. 00 65. 11 -3.11 260. 00 65. 00 65. 11 - . 11 320. 00 61. 00 65. 45 -4.45 320. 00 66. 00 65. 45 .55 Correlation Coefficient = .984 WCAP- 17269-NP September 2010 Revision 0

C-13 UNIRRADIATED (TRANSVERSE ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0412712010 02:06 PM Page 1 Coefficients of Curve I A = 50. B = 50. C = 76.68 TO = 62.67 I) = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))i Temperature at 50% Shear= 62.7 Plant: Comanche Peak 2 Material: SA533B I Heat: C5522-2 Orientation: TL Capsule: UNIRR Fluence: n/cm^2 125 100

'U 75 0j 50 25 0 i i -

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear D)ifferentia

- 120. 00 5. 00 .85 4.15

- 120. 00 .00 .85 - . 85

- 80. 00 5. 00 2. 36 2. 64

-80. 00 9. 00 2. 36 6. 64

- 60. 00 3. 00 3. 92 - . 92

-60. 00 9. 00 3. 92 5. 08

-60. 00 3. 00 3. 92 - . 92

- 30. 00 22. 00 8. 19 13.81

- 30. 00 18.00 8. 19 9.81 WCAP-17269-NP September 2010 Revision 0

C-14 UNIRRADIATED (TRANSVERSE ORIENTATION)

Page 2 Plant Comanche Peak 2 Material: SA533B I Heat: C5522-2 Orientation: TL Capsule: UNIRR Fluence: n/cm^2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differenfial

- 30. 00 25. 00 8. 19 16.81

.00 13.00 16.32 -3. 32

.00 20. 00 16.32 3. 68

.00 16. 00 16.32 -. 32

40. 00 38. 00 35. 63 2. 37

40. 00 25. 00 35. 63 -10.63

40. 00 30. 00 35. 63 -5. 63

80. 00 48. 00 61. 11 - 13. 11

80. 00 54. 00 61. 11 -7.11

80. 00 59. 00 61. II -2. 11 120. 00 79. 00 81. 69 -2.69 120.00 90. 00 81. 69 8.31 120.00 100.00 81. 69 18.31 160.00 100. 00 92. 68 7. 32 160. 00 100. 00 92. 68 7. 32 160. 00 100. 00 92. 68 7. 32 260.00 100. 00 99. 42 58 260. 00 100. 00 99. 42 58 260.00 100. 00 99. 42 58 320.00 100. 00 99. 88 .12 320. 00 100. 00 99. 88 .12 Corelation Coefficient .984 WCAP-17269-NP September 2010 Revision 0

C-15 UNIRRADIATED (WELD)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/29/2010 02:55 PM Page I Coefficients of Curve I A = 48.1 B = 45.9 C = 107.15 TO = -4.93 D = O.OOE+00 Equation is A + B

• ITanh((T-To)/(C+DT))l Upper Shelf Energy=94.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=-49.6 Deg F Temp@50 ft-lbs=-.4 Deg F Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 300 250

• 200 0

150 100 0

50 o0 0

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 120. 00 10. 00 11. 80 -I 80

- 120. 00 13. 00 11. 80 I 20

-90. 00 16. 00 17. 78 - 78

-90. 00 18. 00 17. 78 22

-90. 00 29. 00 17. 78 II 22

-60. 00 21. 00 26. 39 -5 39

-60. 00 22. 00 26. 39 -4.39

-60. 00 26. 00 26. 39 - . 39

-30. 00 26. 00 37. 55 -11.55 WCAP-17269-NP September 2010 Revision 0

C-16 UNIRRADIATED (WELD)

Page 2 Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: UNIRR Fluence: n/cm^2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 30. 00 41. 00 37. 55 3.45

-30. 00 47. 00 37. 55 9. 45

.00 47. 00 50. 21 -3.21

.00 47. 00 50. 21 -3.21

.00 60. 00 50. 21 9.79

40. 00 60. 00 66. 29 -6. 29

40. 00 64. 00 66. 29 -2.29

40. 00 75. 00 66. 29 8.71

80. 00 74. 00 78. 39 -4.39

80. 00 76. 00 78. 39 -2.39

80. 00 76. 00 78. 39 -2.39 120. 00 80. 00 85. 87 -5.87 120. 00 89. 00 85. 87 3. 13 120. 00 95. 00 85. 87 9. 13 160. 00 91. 00 89. 96 1. 04 160. 00 94. 00 89. 96 4. 04 260. 00 93. 00 93. 35 -. 35 260. 00 94. 00 93. 35 65 260. 00 98. 00 93. 35 4.65 320. 00 95. 00 93. 79 1.2 1 320. 00 99. 00 93. 79 5.21 Correlation Coefficient = .984 WCAP-17269-NP September 2010 Revision 0

C-17 UNIRRADIATED (WELD)

CVGRAPH 5.3 Hyperbolic Tangent Curve :Printed on 01/29/2010 02:56 PM Page I Coefficients of Curve I A = 38.02 B = 38.02 C = 91.24 TO = 7.89 D = O.OOE+00 Equation is A + B

• tTanh((T-To)I(C+DT))I Upper Shelf L.E.=76.0 Lower Shelf LE=.O(Fixed)

Temp.@L.E. 35 mils=.7 Deg F Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 200 150 E

0 100 50 0o-

-300.0 0.0 300.0 600.0 Temperature in Deg F D

Charpy V-Notch Data Temperature Input L.E. Computed LEF Differential

-120. 00 .00 4. 34 -4. 34

-120. 00 I. 00 4. 34 -3. 34

-90. 00 8. 00 7. 96 .04

-90. 00 7. 00 7.96 96

-90. 00 13. 00 7. 96 5. 04

-60. 00 4.00 14.00 -10. 00

-60. 00 1. 00 14.00 -13. 00

-60. 00 11. 00 14.00 -3. 00

- 30. 00 20. 00 23.08 -3. 08 WCAP-17269-NP September 2010 Revision 0

C-18 UNIRRADIATED (WELD)

Page 2 Plant: Comanche Peak 2 Material: SAW Heal: 89833 Orientation: NA Capsule: UNIRR Ruence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed LE Differential

-30. 00 28. 00 23. 08 4. 92

-30. 00 35. 00 23. 08 11. 92

.00 34. 00 34. 74 - .74

.00 36. 00 34. 74 1. 26

.00 47. 00 34. 74 12.26

40. 00 46. 00 50. 87 -4.87

40. 00 48. 00 50. 87 -2. 87

40. 00 58. 00 50. 87 7. 13

80. 00 58. 00 63. 06 -5.06

80. 00 57. 00 63. 06 -6.06

80. 00 60. 00 63. 06 -3.06 120. 00 63. 00 70. 04 -7. 04 120. 00 67. 00 70. 04 -3.04 120. 00 79. 00 70. 04 8.96 160. 00 74. 00 73. 42 .58 160. 00 75. 00 73. 42 1.58 260. 00 75. 00 75. 73 -. 73 260. 00 74. 00 75. 73 -I.73 260. 00 78. 00 75. 73 2.27 320. 00 80. 00 75. 96 4. 04 320. 00 78. 00 75. 96 2. 04 Correlation Coefficient = .979 WCAP- 17269-NP September 2010 Revision 0

C-19 UNIRRADIATED (WELD)

CVGRAPH 5.3 Hp)erbolic Tangent Curve Printed on 04/27/2010 02:10 PM Page I Coefficients of Curve 1 A = 50. B = 50. C = 93.39 TO = -1.21 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))1 Temperature at 50% Shear= -1.2 Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: UNIRR Fluence: n/cm^2 125 100

(-

V. 75 Co 0t. 50 25

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 .600.0 Temperature In Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

- 120.00 5. 00 7. 28 -2. 28

- 120.00 2. 00 7. 28 - 5. 28

-90. 00 18. 00 12.99 5. 01

-90. 00 18.00 12.99 5. 01

-90. 00 25. 00 12.99 12. 01

-60. 00 9. 00 22. 11 -13. I1

-60. 00 5. 00 22. 11 -17. I1

-60. 00 30. 00 22. 11 7. 89

-30. 00 34. 00 35. 06 - 1. 06 WCAP-17269-NP September 2010 Revision 0

C-20 UNIRRADIATED (WELD)

Page 2 Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: UNIRR Fluence: n/cmn2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

-30. 00 40. 00 35. 06 4. 94

-30. 00 45. 00 35. 06 9. 94

.00 45. 00 50. 65 - 5. 65

.00 45. 00 50. 65 -5. 65

.00 61.00 50. 65 10. 35

40. 00 59. 00 70. 73 11. 73

40. 00 66.00 70. 73 -4. 73

40. 00 81.00 70. 73 10. 27

80. 00 82. 00 85. 06 - 3. 06

80. 00 86. 00 85. 06 .94

80. 00 79. 00 85. 06 -6.06 120.00 96. 00 93. 06 2. 94 120.00 100. 00 93. 06 6. 94 120.00 100. 00 93. 06 6. 94 160.00 100. 00 96. 93 3. 07 160.00 100. 00 96. 93 3. 07 260. 00 100. 00 99. 63 37 260. 00 100. 00 99. 63 37 260. 00 100. 00 99. 63 37 320. 00 100. 00 99. 90 10 320. 00 100. 00 99. 90 10 Correlation Coefficient = .980 WCAP-17269-NP September 2010 Revision 0

C-21 UNIRRADIATED (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/29/2010 02:58 PM Page I Coefficients of Curve I A = 59.1 B = 56.9 C = 84.54 TO = .61.79 D = O.OOE+OO Equation is A + B

• ITanh((T-To)/(C+DT))I Upper Shelf Energy=l 16.0(Fixed) Lower Shelf Energ,-=2.2(Fixed)

Temp@30 ft-lbs=- 109.5 Deg F Temp@50 ft-lbs=-75.4 Deg F Plant: Comanche Peak 2 Material: SA533B I Heat: C5522-2 Orientation: NA Capsule: UNIRR Fluence: n/cm^2 300 250 200 0

0 IJL 150 z 0

> 100 0

50 0

@ 0 0 Z 0 0

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature tnput CVN Computed CVN Differential

-220. 00 13. 00 4. 83 8. 17

-220. 00 15.00 4. 83 10. 17

- 160. 00 II. 00 12. 35 - I. 35 160. 00 20. 00 12. 35 7. 65 160. 00 22. 00 12.35 9. 65 120. 00 13. 00 25. 13 12. 13 120. 00 14.00 25. 13 -11. 13 120. 00 29. 00 25. 13 3. 87

-90. 00 39. 00 40. 79 -I .79 WCAP-1 7269-NP September 2010 Revision 0

C-22 UNIRRADIATED (HEAT AFFECTED ZONE)

Page 2 Plant: Comanche Peak 2 Material: SA533BI Heat: C5522-2 Orientation: NA Capsule: UNIRR Fluence: n/cm^2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

-90. 00 45. 00 40. 79 4.21

-90. 00 96. 00 40. 79 55. 21

-60. 00 33. 00 60. 31 -27. 31

-60. 00 50. 00 60. 31 -10. 31

-60. 00 51. 00 60. 31 -9. 31

- 30. 00 53. 00 79. 54 -26. 54

- 30. 00 60. 00 79. 54 - 19. 54

.00 101. 00 94. 59 6.41

.00 II. 00 94. 59 16. 41

.00 130. 00 94. 59 35. 41

40. 00 104.00 106.61 -2. 61

40. 00 112. 00 106.61 5. 39

40. 00 115. 00 106.61 8. 39 100. 00 124. 00 113. 58 10.42 100. 00 128. 00 113.58" 14. 42 140. 00 106. 00 115.05 -9.05 140. 00 120. 00 115.05 4.95 140. 00 124. 00 115.05 8. 95 180. 00 100. 00 115. 63 - 15. 63 Correlation Coefficient= .921 WCAP-17269-NP September 2010 Revision 0

C-23 UNIRRADIATED (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/29/2010 02:59 PM Page I Coefficients of Curve I A = 36.41 B = 36.41 C = 76.16 TO = -46.04 D = 0.O0E+0O Equation is A + B

• ITanh((T-To)/(C+DT))]

Upper Shelf L.E.=72.8 Lower Shelf LE.=.O(Fixed)

Temp.@LE. 35 mils=-48.9 Deg F Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: NA Capsule: UNIRR Fluence: n/cnm2 200 150 E

a 10 10 Q

0 50 0

0

-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed LE. Differential

-220.00 I. 00, .75 .25

-220.00 I. 00 .75 25

- 160. 00 6. 00 3.48 2.52

-160. 00 7. 00 3.48 3.52

-160. 00 5. 00 3.48 1.52

-120. 00 6. 00 9. 13 -3. 13

-120. 00 4. 00 9. 13 -5. 13

-120. 00 12. 00 9.. 13 2.87

-90.00 18.00 17.45 .55 WCAP-17269-NP September 2010 Revision 0

C-24 UNIRRADIATED (HEAT AFFECTED ZONE)

Page 2 Plant: Comanche Peak 2 Material: SA533BI Heat: C5522-2 Orientation: NA Capsule: UNIRR Fluence: n/cm^2 Charpy V-Notch Data Temperature Input L.E. Computed LE Differential

-90. 00 22. 00 17. 45 4.55

-90. 00 48. 00 17.45 30. 55

-60. 00 9. 00 29. 81 -20. 81

-60. 00 29. 00 29. 81 -. 81

-60. 00 21. 00 29. 81 -8. 81

-30. 00 33. 00 43. 97 - 10.97

-30. 00 35. 00 43. 97 -8. 97

. 00 61. 00 56. 08 4. 92

.00 67.00 56.08 10.92

. 00 75. 00 56. 08 18. 92

40. 00 56. 00 65. 94 -9. 94

40. 00 68. 00 65. 94 2. 06

40. 00 7 1. 00 65. 94 5. 06 o00. 00 69. 00 71.28 -2. 28 000- 0 71. 00 71. 28 - . 28 140. 00 68. 00 72. 27 -4. 27 140. 00 79. 00 72. 27 6. 73 140. 00 75. 00 72. 27 2. 73 180. 00 62. 00 72. 63 - 10. 63 Correlation Coefficient = .941 WCAP-17269-NP September 2010 Revision 0

C-25 UNIRRADIATED (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 04/2712010 02:12 PM Page I Coefficients of Curve I A = 50. B = 50. C = 69.21 TO = -40.34 D = O.OOE+00 Equation is A + B

• ITanh((T-To)/(C+DT))I Temperature at 50% Shear = -40.3 Plant: Comanche Peak 2 Material: SA533B1 Heat C5522-2 Orientation: NA Capsule: UNIRR Fluence: n/cm^2 125 100 75 21

.1 50 25

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

-220. 00 2. 00 .55 1. 45

-220.00 2.00 .55 1.45

- 160.00 . 00 3.05 -3. 05

- 160. 00 9. 00 3. 05 5. 95

-160.00 1l. 00 3.05 7. 95

- 120.00 . 00 9. 10 -9. 10

- 120.00 13.00 9. 10 3. 90

- 120.00 9. 00 9. 10 -. 10

-90. 00 28. 00 19. 23 8. 77 September 2010 WCAP-1 7269-NP WCAP-17269-NP September 2010 Revision 0

C-26 UNIRRADIATED (HEAT AFFECTED ZONE)

Page 2 Plant: Comanche Peak 2 Material: SA533BI Heat: C5522-2 Orientation: NA Capsule: UNIRR Fluence: n/cm^2 Charpy V-Notch Data Temperature, Input Percent Shear Computed Percent Shear Differential

-90. 00 23.00 19. 23 3. 77

-90. 00 36.00 19.23 16.77

-60. 00 18. 00 36. 17 -18. 17

-60. 00 57. 00 36. 17 20. 83

-60. 00 20. 00 36. 17 -16. 17

-30. 00 50. 00 57.41 -7.41

-30. 00 47.00 57. 41 -10.41

.00 54.00 76. 24 -22. 24

.00 79. 00 76. 24 2.76

.00 200. 00 76. 24 23.76

40. 00 200. 00 91. 06 8. 94

40. 00 200. 00 91. 06 8. 94

40. 00 200.00 91. 06 8. 94 200. 00 200.00 98. 30 1. 70 IO0. 00 200. 00 98. 30 1. 70 140.00 100. 00 99. 46 54 140. 00. 200. 00 99. 46 54 140. 00 200. 00 99. 46 54 180.00 200. 00 99. 83 17 Correlation Coefficient - .966 September 2010 WCAP-1 7269-NP WCAP-17269-NP September 2010 Revision 0

C-27 CAPSULE U (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/29/2010 03:00.PM Page I Coefficients of Curve I A = 60.1 B = 57.9 C = 86.68 TO = 42.11 D = 0.OOE+00 Equation is A + B

• ITanh((T-To)/(C+DT))1 Upper Shelf Energy=l 18.0(Fixed) Lower Shelf Energy=-2.2(Fixed)

Temp@30 ft-lbs=-7.8 Deg F Temp@50 ft-lbs=26.9 Deg F Plant: Comanche Peak 2 Material: SA533B I Heat: C5522-2 Orientation: LT Capsule: U Fluence: n/cnA2 300 250 oA

-- 200 150 U.I 0

100 or 50 n4~

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

-75. 00 8. 00 9. 48 - I. 48

-50. 00 11. 00 14. 55 -3. 55

-25. 00 20. 00 22. 50 -2. 50

- 10. 00 36. 00 28. 96 7. 04

. 00 41.00 34. 00, 7. 00

10. 00 42. 00 39. 58 2. 42

25. 00 42. 00 48. 82 -6. 82

50. 00 58. 00 65. 36 -7. 36

72. 00 85. 00 79.31 5. 69 WCAP- 17269-NP September 2010 Revision 0

C-28 CAPSULE U (LONGITUDINAL ORIENTATION)

Page 2 Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: LT. Capsule: U Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 100. 00 88. 00 93. 89 -5. 89 125. 00 106.00 103. 10 2.90 150. 00 I 15.00 109. 13 5.87 200. 00 116. 00 115.05 .95 250. 00 1 16.00 117.05 - I. 05 300. 00 127.00 117. 70 9.30 Correlation Coefficient = .992 WCAP-17269-NP September 2010 1Revision 0

C-29 CAPSULE U (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/29/2010 03:01 PM

. Page 1 Coefficients of Curve I A = 41.23 B = 41.23 C = 93.56 TO = 33.6 D = O.OOE+0O Equation is A + B

• ITanh((T-To)/(C+DT))I Upper Shelf L.E.=82.5 Lower Shelf L.E=.0(Fixed)

Temp.@LE. 35 mils=19.4 Deg F Plant: Comanche Peak 2 Material: SA533B I Heat: C5522-2 Orientation: LT Capsule: U Fluence: n/cnm2 200 150 E

100 50 04-

-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed LE Differential

-75. 00 8. 00 7. 37 .63

-50. 00 10. 00 11. 83 -1 83

-25. 00 17.00 18.32 -1 32

-10.00 27. 00 23. 29 3.71

.00 30. 00 27. 03 2. 97 10.00 32. 00 31. 04 .596

25. 00 32. 00 37. 45 -5. 45

50. 00 46. 00 48. 38 -2. 38

72. 00 61. 00 57. 26 3.74 WCAP-17269-NP September 2010 Revision 0

C-30 CAPSULE U (LONGITUDINAL ORIENTATION)

Page 2 Plant: Comanche Peak 2 Material: SA533BI Heat: C5522-2 Orientation: LT Capsule: U Fluence: n/cm^2 Charpy V-Notch Data Temperature Input L.E. Computed LE Differential 100. 00 65. 00 66. 40 - I.40 125. 00 7 1. 00 72. 22 1 .22 150. 00 80. 00 76. 13 3. 87 200. 00 81. 00 80. 17 83 250. 00 77. 00 81.65 -4.65 300. 00 84. 00 82. 18 1. 82 Correlation Coefficient = .994 September 2010 WCAP-1 7269-NP WCAP-17269-NP September 2010 Revision 0

C-31 CAPSULE U (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0412712010 02:04 PM Page 1 Coefficients of Curve I A = 50. B = 50. C = 92.29 TO = 84.98 I) = O.OOE+OO Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear= 85.0 Plant Comanche Peak 2 Material: SA533BI Heat C5522-2 Orientation: LT Capsule: U Fluence: n/cm^2 125 100

'U 0 75 C")

0 C) 50 0.

25

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

-75.00 2. 00 3.03 - 1. 03

-50. 00 5.00 5.09 -. 09

- 25. 00 10. 00 8. 45 1. 55

- 10. 00 15.00 11.32 3. 68 15.00 13.69 1.31

• 00 10.00 20. 00 16.45 3. 55

25. 00 25.00 2 1. 42 3. 58

50. 00 35. 00 31.91 3. 09

72. 00 40. 00 4.3.01 -3. 01 WCAP-17269-NP September 2010 Revision 0

C-32 CAPSULE U (LONGITUDINAL ORIENTATION)

Page 2 Plant: Comanche Peak 2 Material: SA533B I Heat: C5522-2 Orientation: LT Capsule: U Fluence: n/cm^2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 100.00 45. 00 58. 07 -13. 07 125.00 60. 00 70. 42 -10. 42 150.00 100. 00 80. 36 19. 64 200. 00 100. 00 92. 36 7. 64 250. 00 100. 00 97. 28 2. 72 300. 00 100. 00 99. 06 .94 Correlation Coefficient= .981 WCAP-17269-NP September 2010 Revision 0

C-33 CAPSULE U (TRANSVERSE ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/29/2010 03:03 PM Page I Coefficients of Curve I A = 45.1 B = 42.9 C = 107.61 TO = 50.81 D = 0.OOE+00 Equation is A + B

• ITanh((T-To)/(C+DT))l Upper Shelf Energy=88.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=l 1.3 Deg F Temp@50 ft-lbs=63.2 Deg F Plant: Comanche Peak 2 Material: SA533B I Heat: C5522-2 Orientation: TL Capsule: U Fluence: n/cnmA2 300 250

- 200 150 LC z

) 100 0-0 50 o 0 0

0

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 125. 00 6. 00 5.35

- 65

- 95. 00 4. 00 7.55 3 55

-50. 00 20. 00 13.62 6. 38

-25. 00 22. 00 19. 05 2. 95

- 10. 00 29. 00 23. 14 5. 86

.00 24. 00 26. 22 -2. 22

10. 00 26. 00 29. 57 -3. 57

50. 00 35.00 44. 78 -9. 78

72. 00 66. 00 53. 44 12. 56 September 2010 WCAP- 17269-NP September 2010 1Revision 0

C-34 CAPSULE U (TRANSVERSE ORIENTATION)

Page 2 Plant: Comanche Peak 2 Material: SA533BI Heat: C5522-2 Orientation: TL Capsule: U Fluence: n/cm^2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 0OO.00 48. 00 63.45 - 15.45 125. 00 73. 00 70. 74 2.26 150. 00 85. 00 76. 28 8.72 200. 00 87. 00 82.95 4. 05 250. 00 86. 00 85.93 .07 300. 00 96. 00 87. 17 8.83 Correlation Coefficient = .974 WCAP- 17269-NP September 2010 Revision 0

C-35 CAPSULE U (TRANSVERSE ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/29/2010 03:04 PM Page I Coefficients of Curve I A = 35.8 B = 35.8 C = 117.55 TO = 45.7 D = 0.OOE+O0 Equation is A + B

• I.Tanh((T-To)I(C+DT))1 Upper Shelf L.E.=71.6 Lower Shelf LE=.0(Fixed)

Temp.@LE. 35 mils-43. I Deg F Plant: Comanche Peak 2 Material: SA533B I Heat: C5522-2 Orientation: TL Capsule: U Fluence: n/cnW2 200 150 E

Ea 100 0

50 50 0

0

-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed LE. Differential

- 125. 00 6.00 3. 72 2. 28

- 95. 00 5.00 5. 99 - . 99

-50. 00 14.00 11.75 2. 25

- 25. 00 16. 00. 16.54 - .54

-10.00 24. 00 20. 00 4. 00

.00 22. 00 22. 55 - .55 10.00 20. 00 25. 25 - 5.'25

50. 00. 35. 00 37. 11 -2. I1

72. 00 50. 00 43. 68 6. 32 WCAP-17269-NP September 2010 Revision 0

C-36 CAPSULE U (TRANSVERSE ORIENTATION)

Page 2 Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: TL Capsule: U Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed LE. Differential 100. 00 46. 00 51. 26 -5. 26 125. 00 54. 00 56. 86 -2.86 150. 00 67. 00 61.23 5.77 200. 00 70. 00 66. 77 3.23 250. 00 67. 00 69. 46 -2. 46 300. 00 69. 00 70. 68 - I. 68 Correlation Coefficient = .988 WCAP-1 7269-NP September 2010 Revision 0

C-37 CAPSULE U (TRANSVERSE ORIENTATION)

CVGRAPH 5.3 H)perbolic Tangent Curve Printed on 0412712010 02:08 PM Page I Coefficients of Curve I A = 50. B = 50. C = 72.02 TO = 116.15 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))1 Temperature at 50% Shear= 116.2 Plant: Comanche Peak 2 Material: SA533B I Heat: C5522-2 Orientation: TL Capsule: U Fluence: n/cm^2 125 100 75 L,

00*

a. 50 25 0 --

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

- 125. 00 00 .12 -. 12

- 95. 00 00 28 - .28

- 50. 00 5. 00 98 4. 02

- 25. 00 10.00 1.95 8. 05

- 10. 00 10.00 2. 92 7. 08

.00 15. 00 3. 82 11. 18 10.00 15.00 4. 98 10. 02

50. 00 20. 00 13.74 6. 26 72.00 30. 00 22. 69 7. 31 WCAP-17269-NP September 2010 Revision 0

C-38 CAPSULE U (TRANSVERSE ORIENTATION)

Page 2 Plant: Comanche Peak 2 Material: SA533B I Heat: C5522-2 Orientation: TL Capsule: U Fluence: n/cm^l2 Charpy V-Notch Data Temperature tnput Percent Shear Computed Percent Shear Differential 100.00 25. 00 38. 97 -13.97 125.00 30. 00 56. 11 -26.11 150.00 100.00 71.91 28.09 200. 00 100. 00 91. 12 8. 88 250. 00 100. 00 97. 63 2. 37 300. 00 100. 00 99. 40 .60 Correlation Coefficient = .955 WCAP-17269-NP September 2010 Revision 0

C-39 CAPSULE U (WELD)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/29/2010 03:06 PM Page I Coefficients of Curve I A = 43.6 B = 41.4 C = 90.09 TO= -15.27 D = 0.OOE+00 Equation is A + B

• ITanh((T-To)/(C+DT))l Upper Shelf Energy=85.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=-46.0 Deg F Temp@50 ft-lbs=-1.2 Deg F Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: U Fluence: n/cmA2 300 250 T 200 0

U-150 0

z 100 50 0

0

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 125. 00 3. 00 8. 86 -5. 86

-95. 00 II. 00 14. 25 -3. 25

-75. 00 7. 00 19. 57 -12. 57

-60. 00 32. 00 24. 58 7. 42

- 50. 00 38. 00 28. 39 9.61

-25. 00 40. 00 39. 15 85

- 10. 00 48. 00 46. 02 I. 98

.00 48. 00 50. 55 -2. 55

50. 00 66. 00 69. 25 -3. 25 WCAP- 17269-NP September 2010 Revision 0

C-40 CAPSULE U (WELD)

Page 2 Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: U Fluence: n/cm^2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

72. 00 75. 00 74. 57 .,43 100. 00 76. 00 79. 05 -3.05 150. 00 80. 00 82. 94 -2.94 200. 00 87. 00 84. .31 2.69 250. 00 86. 00 84. 77 1. 23 300. 00 86. 00 84. 92 1. 08 Correlation Coefficient = .984 WCAP- 17269-NP September 2010 Revision 0

C-41 CAPSULE U (WELD)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/29/2010 03:06 PM Page I Coefficients of Curve I A = 33.05 B = 33.05 C = 92. TO= -22.16 D = 0.OOE+00 Equation is A +B

• ITanh((T-To)/(C+DT))l Upper Shelf L.E.=66.1 Lower Shelf LE.=.0(Fixed)

. Temp.@LE. 35 mils=- 16.7 Deg F Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: U Fluence: n/cmA2 200 150 0

a 100 50*

50 04-

-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed LE. Differential

- 125. 00 8. 00 6. 39 1.61

-95. 00 9.00 11. 26 -2.26

-75. 00 9. 00 15.91 -6.91

-60. 00 24. 00 20. 17 3. 83

-50. 00 29. 00 23. 34 5. 66

-25. 00 31. 00 32. 03 -1.03

-10.00 38. 00 37. 39 .61

.00 39. 00 40. 86 -1.86

50. 00 52. 00 54. 71 -2.71 WCAP- 17269-NP September 2010 Revision 0

C-42 CAPSULE U (WELD)

Page 2 Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: U Fluence: n/cm^2 Charpy V-Notch Data Temperature Input L.E. Computed LE. Differential

72. 00 61.00 58. 54 2. 46 100. 00 62. 00 61.76 24 150. 00 65. 00 64. 57 .43 200. 00 67. 00 65. 58 1. 42 250. 00 60. 00 65. 92 -5.92 300. 00 70. 00 66. 04 3. 96 Correlation Coefficient = .988 September 2010 WCAP- 17269-NP September 2010 Revision 0

C-43 CAPSULE U (WELD)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0412712010 05:35 PM Page I Coefficients of Curve I A = 50. B = 50. C = 67.17 TO = 21.32 D =O.00E+00 Equation is A + B

• jTanh((T-To)/(C+DT))]

Temperature at 50% Shear= 21.6 Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: U Fluence: n/cm^2 125 100 1~

(U C) 75 Co C)

C) 50 a-25 0 i i 1 . d 1

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

- 125. 00 5. 00 I. 26 3. 74

- 95. 00 5. 00 3. 02 1.98

-75. 00 10.00 5. 35 4. 65

- 60. 00 10.00 8. II 1. 89

-50. 00 15.00 10. 63 4. 37

- 25. 00 15.00 20. 02 5. 02

- 10.00 25. 00 28. 12 -3. 12

.00 35. 00 34. 51 49

50. 00 70. 00 70. 01 -. 01 WCAP-17269-NP September 2010 Revision 0

C-44 CAPSULE U (WELD)

Page 2 Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: U Fluence: n/cm^2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

72. 00 85. 00 81.80 3. 20 100.00 90. 00 91.19 -I. 19 150.00 100. 00 97. 87 2. 13 200. 00 100. 00 99.51 .49 250. 00 100. 00 99. 89 .11 300. 00 100. 00 99. 97 03 Correlation Coefficient - .998 WCAP- 17269-NP September 2010 Revision 0

C-45 CAPSULE U (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/29/2010 03:07 PM Page I Coefficients of Curve I A = 64.6 B = 62.4 C = 136.19 TO = .37.65 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))1 Upper Shelf Energy=127.0(Fixed) Lower Shelf Energy=-2.2(Fixed)

Temp@30 ft-lbs=- 122.7 Deg F Temp@50 ft-lbs=-70.l Deg F Plant: Comanche Peak 2 Material: SA533BI Heat: C5522-2 Orientation: NA Capsule: U Fluence: n/cmA2 300 250 4- + 4 4 4 4 4 200 0

150 IL1 0

100 00 0 0 0

50 fl

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

-225. 00 7. 00 9. 69 -2.69

- 175. 00 16.00 16. 86 -. 86

- 150. 00 20. 00 22. 31 -2.31

- 125. 00 40. 00 29. 29 10.71

- 100. 00 23. 00 37. 88 -14. 88

-75. 00 90. 00 47.91 42. 09

-60. 00 59. 00 54. 45 4.55

-50. 00 35. 00 58. 96 -23. 96

-25. 00 52. 00 70. 38 -18.38 WCAP- 17269-NP September 2010 Revision 0

C-46 CAPSULE U (HEAT AFFECTED ZONE)

Page 2 Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: NA Capsule: U Fluence: n/cm^2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

. 00 78. 00 81.43 -3.43

25. 00 90. 00 91. 44 -I. 44

72. 00 124. 00 106.22 17.78 150. 00 104. 00 119.54 - 15.54 200. 00 154.00 123.31 30. 69 Correlation Coefficient = .909 WCAP- 17269-NP September 2010 Revision 0

C-47 CAPSULE U (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/29/2010 03:07 PM Page I Coefficients of Curve 1 A = 38.9 B = 38.9 C = 126.43 TO = -36.72 D -=,O.OOE+00 Equation is A + B

• ITanh((T-To)/(C+DT))I Upper Shelf L.E.=77.8 Lower Shelf LE.=.0(Fixed)

Temp.@LE. 35 mils=-49.4 Deg F Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: NA Capsule: U Fluence: n/cmA2 200 150 a100

_1 0

50 0 #_

-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed LE Differential

-225. 00 2. 00 3. 77 1.77

- 175. 00 8. 00 7. 85 .15

-150. 00 9.00 I I. I*1 -2.11

- 125. 00 21. 00 15. 43 5.57

- 100. 00 13. 00 20. 91 -7.91

-75. 00 44. 00 27. 47 16. 53

-60. 00 37. 00 31.82 5. 18

-50. 00 26. 00 34. 83 -8.83

- 25. 00 29. 00 42. 50 -13.50 WCAP-17269-NP September 2010 Revision 0

C-48 CAPSULE U (HEAT AFFECTED ZONE)

Page 2 Plant: Comanche Peak 2 Material: SA533BI Heat: C5522-2 Orientation: NA Capsule: U Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed LE. Differential

' 00 50. 00 49. 89 . 11

25. 00 59. 00 56. 5 1 2. 49

72. 00 75. 00 65. 98 9.02 150. 00 71. 00 73. 95 -2. 95 200. 00 74. 00 76. 00 -2. 00 Correlation Coefficient = .954 WCAP-1 7269-NP September 2010 Revision 0

C-49 CAPSULE U (HEAT AFFECTED ZONE)

CVGRAPH 5.3 H)Perbolic Tangent Curve Printed on 04/27/2010 02:13 PM Page 1 Coefficients of Curve I A = 50. B = 50. C = 99.81 TO = -31.2 1)= 0.00E+0O Equation is A + B

• FTanh((T-To)/(C+DT))]

Temperature at 50% Shear = -3 1.1 Plant Comanche Peak 2 Material: SA533B I Heat C5522-2 Orientation: NA Capsule: U Fluence: nfcm^2 125 100 1~

CI 75 cn CI CI 50 a.

25 0 = !.- --- 4.

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

-225. 00 5. 00 2. 02 2. 98

-175.00 5.00 5.31 31

-150.00 10.00 8. 47 1. 53

-125.00 15.00 13.24 1. 76

-100.00 10. 00 20. 12 - 10. 12

-75. 00 50.00 29. 37 20. 63

-60. 00 30. 00 35. 96 - 5. 96

-50. 00 30. 00 40. 69 -10. 69

-25.00 60. 00 53. 10 6. 9O WCAP-17269-NP September 2010 Revision 0

C-50 CAPSULE U (HEAT AFFECTED ZONE)

Page 2 Plant: Comanche Peak 2 Material: SA533BI Heat: C5522-2 Orientation: NA Capsule: U Fluence: n/cm^2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

. 00 65.00 65. 14 -. 14

25. 00 65.00 75.51 -10.51

72. 00 100.00 88. 77 1. 23 150.00 100. 00 97. 42 2..58 200. 00 100.00 99. 04 .96 Correlation Coefficient= .971 September 2010 WCAP- 17269-NP September 2010 Revision 0

C-51 CAPSULE X (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/29/2010 03:09 PM Page 1 Coefficients of Curve I A = 61.1 B = 58.9 C = 98.97 TO 50.28 D = O.OOE+00 Equation is A + B

• ITanh((T-To)y(C+DT))i Upper Shelf Energy=] 20.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=-7.8 Deg F Temp@50 ft-lbs=31.5 Deg F Plant: Comanche Peak 2 Material: SA533BI Heat: C5522-2 Orientation: LT Capsule: X Fluence: nIcmA2 300 250 200 0

150 0

100 50

§ o 0

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 50. 00 6. 00 15.92 -9.92

-40. 00 10. 00 18. 56 -8.56

- 25. 00 33. 00 23. 32 9. 68

-25. 00 35. 00 23. 32 11.68

-10.00 28. 00 29. 09 - I. 09

25. 00 33. 00 46. 37 - 13.37

25. 00 52. 00 46. 37 5.63

40. 00 58. 00 55. 00 3. 00

60. 00 69. 00 66. 86 2. 14 WCAP-17269-NP September 2010 Revision 0

C-52 CAPSULE X (LONGITUDINAL ORIENTATION)

Page 2 Plant: Comanche Peak 2 Material: SA533BI Heat: C5522-2 Orientation: LT Capsule: X Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

75. 00 82. 00 75. 51 6. 49 I10. 00 79. 00 92. 87 -13.87 150. 00 105. 00 106. 14 -1.14 175. 00 113.00 111.23 1.77 200. 00 121. 00 114. 55 6. 45 225. 00 127. 00 116.65 10. 35 Correlation Coefficient = .978 WCAP- 17269-NP September 2010 Revision 0

C-53 CAPSULE X (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/29/2010 03:10 PM Page 1 Coefficients of Curve I A = 39.15 B = 39.15 C = 99.41 TO= 52.76 D = 0.OOE+00 Equation is A + B

• ITanh((T-To)/(C+DT))l Upper Shelf L.E.=78.3 Lower Shelf LE.=.0(Fixed)

Temp.@LE. 35 mils=42.2 Deg F Plant: Comanche Peak 2 Material: SA533BI Heat: C5522-2 Orientation: LT Capsule: X Fluence: n/cnA2 200 150 E,,

a 100 50 0

0 n4 0

-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed LE. Differential

-50. 00 1.00 8.79 -7.79

-40. 00 4. 00 10. 49 -6. 49

-25. 00 20. 00 13.55 6. 45'

-25. 00 19.00 13. 55 5. 45

-10.00 16. 00 17. 26 - I. 26

25. 00 23.00 28. 49 -5. 49

25. 00 32. 00 28. 49 3.51

40. 00 39. 00 34. 15 4. 85

60. 00 43. 00 42. 00 *1. 00 WCAP-1 7269-NP September 2010 Revision 0

C-54 CAPSULE X (LONGITUDINAL ORIENTATION)

Page 2 Plant: Comanche Peak 2 Material: SA533BI Heat: C5522-2 Orientation: LT Capsule: X Fluence: n/cm^2 Charpy V-Notch Data Temperature Input L.E. Computed LE Differential

75. 00 46. 00 47. 76 -I.76

10. 00 56. 00 59. 49 -3.49 150. 00 69. 00 68. 60 . 40 175. 00 71. 00 72. 13 1 13 200. 00 79. 00 74. 45 4.55 225. 00 74. 00 75. 93 -1 .93 Correlation Coefficient = .985 September 2010 WCAP-1 7269-NP WCAP-17269-NP September 2010 Revision 0

C-55 CAPSULE X (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 04/27/2010 02:05 PM Page l Coefficients of Curve I A = 50. B = 50. C = 84.87 TO = 73.51 D = 0.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear= 73.6 Plant Comanche Peak 2 MateriaL SA533B I Heat: C5522-2 Orientation: LT Capsule: X Fluence: n/cm^2 125 100 75 L-Q!

50 25 0 1 = -

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

-50. 00 5. 00 5. 16 -. 16

-40. 00 5. 00 6. 45 1 .45

-25. 00 I0. 00 8.93 I. 07

- 25. 00 10. 00 8. 93 I. 07

-0. 00 10. 00 12. 26 -2. 26

25. 00 20. 00 24. 17 -4. 17

25. 00 25. 00 24. 17 .83

40. 00 30. 00 31.22 - . 22

60. 00 50. 00 42. 10 7.90 WCAP-17269-NP September 2010 Revision 0

C-56 CAPSULE X (LONGITUDINAL ORIENTATION)

Page 2 Plant: Comanche Peak 2 Material: SA533BI Heat: C5522-2 Orientation: LT Capsule: X Fluence: n/cm^2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

75. 00 55. 00 50. 88 4. 12 110.00 60. 00 70. 26 - 10. 26 150.00 80. 00 85. 85 - 5. 85 175.00 00. 00 91.62 8. 38 200. 00 100. 00 95.17 4. 83 225. 00 100.00 97. 26 2. 74 Correlation Coefficient = .991 WCAP-17269-NP September 2010 Revision 0

C-57 CAPSULE X (TRANSVERSE ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/29/2010 03:12 PM Page I Coefficients of Curve I A = 46.6 B = 44.4 C = 114.54 TO = 85.75 I) = 0.OOE+O0 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=9 I.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=40.8 Deg F Temp@50 ft-lbs=94.6 Deg F Plant: Comanche Peak 2 Material: SA533BI Heat C5522-2 Orientation: TL Capsule: X Fluence: nfcm^2 300 250 + 4 + + + +~ I

- 200 150 LU z

0> 100 00 5o n",

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 7 100. 00 3. 00 5. 54 -2. 54

- 50. 00 9. 00 9.79 -. 79

.00 23. 00. 18. 44 4. 56

25. 00 28. 00 25. 04 2.96

50. 00 35. 00 33. 18 1.82

60. 00 37. 00 36. 78 .22 75.00 45. 00 42: 45 2. 55 100.00 45. 00 52. 30 -7.10 125. 00 57. 00 61.25 -4.25 WCAP-17269-NP September 2010 Revision 0

C-58 CAPSULE X (TRANSVERSE ORIENTATION)

Page 2 Plant: Comanche Peak 2 Material: SA533B! Heat: C5522-2 Orientation: TL Capsule: X Ruence: n/cm^2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 150. 00 64. 00 69. 19 -5. 19 175.00 73. 00 75. 56 -2. 56 200. 00 88. 00 80. 37 7.63 225. 00 92. 00 83. 82 8. 18 250. 00 93. 00 86. 23 6. 77 275. 00 90. 00 87. 85 2. 15 Correlation Coefficient = .989 WCAP-17269-NP September 2010 Revision 0

C-59 CAPSULE X (TRANSVERSE ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/2912010 03:12 PM Page 1 Coefficients of Curve I A = 36.44 B = 36.44 C = 129.38 TO = 100.68 1) = 0.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))I Upper Shelf L.E.=7 2.9 Lower Shelf L.E.=.0(Fixed)

Temp.@LE. 35 mils95.6 Deg F Plant: Comanche Peak 2 Material: SA533B I Heat: C5522-2 Orientation: TL Capsule: X Fluence: n/cm^2 200 150 E

.o 2100 50 5O 0

-300.0 0.0 300.0 600.0 Temperature In Deg F Charpy V-Notch Data Temperature Input L.E. Computed LE Differential

- 100.00 00 3. 14 -3. 14

- 50. 00 4. 00 6. 47 *2. 47

.00 14. 00 12.69 1.31

25. 00 19. 00 17. 26 1. 74

50. 00 24. 00 22. 86 1.14

60. q0 25. 00 25. 35 -. 35 75.00 32. 00 29. 30 2. 70 100.00 33. 00 36. 25 -3.25 125. 00 42. 00 43.21 I. 2 1 WCAP- 17269-NP September 2010 Revision 0

C-60 CAPSULE X (TRANSVERSE ORIENTATION)

Page 2 Plant: Comanche Peak 2 Material: SA533BI Heat: C5522-2 Orientation: TL Capsule: X Fluence: n/cm^2 Charpy V-Notch Data Temperature Input L.E. Computed LE Ditferential 150.00 50. 00 49. 70 130 175.00 54. 00 55. 34 -I34 200. 00 59. 00 59. 97 -. 97 225.00 68. 00 63. 58 4.42 250. 00 68. 00 66. 29 1.71 275. 00 65. 00 68. 27 -3.27 Correlation Coefficient = .995 WCAP-17269-NP September 2010 Revision 0

C-61 CAPSULE X (TRANSVERSE ORIENTATION)

CVGRAPH 5.3 Hy)perbolic Tangent Curve Printed on 04/2712010 02:09 PM Page 1 Coefficients of Curve I A = 50. B = 50. C = 98.48 TO = 91.27 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear= 91.3 Plant Comanche Peak 2 Material: SA533B I Heat C5522-2 Orientation: TL Capsule: X Fluence: nWcm^2 125 100 (U

0 75 U) 0 0 50 a.

25 0 i - - . =-1!r- 1- i -

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

-oo. 00 2. 00 2.01 -. 01

- 50. 00 5. 00 5. 37 -. 37 15.00 13.54 1.46

25. '00 00 25. 00 20. 65 4. 35

50. 00 30. 00 30. 19 -. 19

60. 00 40. 00 34. 63 5. 37

75. 00 45. 00 41. 81 3. 19 100. 00 45. 00 54. 42 -9.42 125. 00 55. 00 66. 48 -11. 48 WCAP-17269-NP September 2010 Revision 0

C-62 CAPSULE X (TRANSVERSE ORIENTATION)

Page 2 Plant: Comanche Peak 2 Material: SA533BI Heat: C5522-2 Orientation: TL Capsule: X Fluence: n/cm^2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 150. 00 80. 00 76. 72 3. 28 175.00 85. 00 84. 56 .44 200. 00 100. 00 90. 10 9. 90 225.00 100. 00 93. 80 6. 20 250. 00 100.00 96. 17 3. 83 275. 00 100. 00 97. 66 2. 34 Correlation Coefficient = .989 WCAP-17269-NP September 2010 Revision 0

C-63 CAPSULE X (WELD)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/29/2010 03:13 PM Page I Coefficients of Curve I A = 49.1 B = 46.9 C = 61.35 TO = 25.12 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=96.0(Fixed) Lower Shelf Eneqgy=2.2(Fixed)

Temp@30 ft-lbs=-1.4 Deg F Temp@50 ft-lbs=26.3 Deg F Plant: Comanche Peak 2 Material: SAW Heat 89833 Orientation: NA Capsule: X Fluence: n/cm^2 300 200 ILL 150 100- 0 0

0/0 50- -

n

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 100.00 6. 00 3.76 2.24

-50. 00 8.00 9. 66 -I . 66

-25.00 14. 00 17. 52 -3.52

.00 27. 00 30. 90 -3.90 25.00 67. 00 49.01 17.99 25.00 41.00 49.01 -8.01

50. 00 62. 00 67. 14 -5. 14

75. 00 94. 00 80. 58 13.42 75.00 69. 00 80. 58 -11.58 WCAP-17269-NP September 2010 Revision 0

C-64 CAPSULE X (WELD)

Page 2 Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: X Fluence: nrcm^2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 135.00 89. 00 93. 46 - 4. 46 175. 00 81. 00 95. 30 -14.30 200. 00 83.00 95. 69 -12. 69 200. 00 92.00 95. 69 -3.69 225.00 106. 00 95. 86 10. 14 250. 00 102.00 95. 94 6. 06 Correlation Coefficient =.962 WCAP- 17269-NP September 2010 Revision 0

C-65 CAPSULE X (WELD)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/29/2010 03:13 PM Page 1 Coefficients of Curve I A = 33.97 B = 33.97 C = 58.82 TO = 18.45 D = O.OOE+00 Equation is A +B

• ITanh((T-Toy(C+DT))I Upper Shelf L.E.--67.9 Lower Shelf L.E.=.O(Fixed)

Temp.@LE. 35 mils=20.3 Deg F Plant: Comanche Peak 2 Material: SAW Heat 89833 Orientation: NA Capsule: X Fluence: n/cm^2 200 150 E

0 100 00 0

50 0

-300.0 0.0 300.0 600.0 Temperature In Deg F Charpy V-Notch Data Temperature Input L.E. Computed L.FE Differential

- 100.00 .00 1. 19 -1.19

-2.04

- 50. 00 4. 00 6. 04

-25. 00 10. 00 12.62 - 2. 62

.00 22. 00 23. 65

25. 00 49. 00 37. 74 11.26

25. 00 35. 00 37. 74 -2.74

50. 00 47. 00 50.63 -3. 63 75.00 63. 00 59..28 3. 72

75. 00 52. 00 59. 28 -7.28 WCAP- 17269-NP September 2010 Revision 0

C-66 CAPSULE X (WELD)

Page 2 Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: X Fluence: n/cm^2 Charpy V-Notch Data Temperature Input L.E. Computed L.11 Differential 135. 00 64. 00 66. 68 -2.68 175.00 65. 00 67. 62 - 2. 62 200. 00 64. 00 67.81 -3.8 1 200. 00 68. 00 67.81 .19 225. 00 74. 00 67. 89 6. 11 250. 00 73. 00 67. 92 5. 08 Correlation Coefficient = .983 WCAP-17269-NP September 2010 Revision 0

C-67 CAPSULE X (WELD)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0412712010 05:36 PM Page 1 Coefficients of Curve I A = 50. B = 50. C = 80.55 TO = 20.76 D = O.OOE+O0 Equation is A + B * [Tanh((T-Toy(C+DT))]

Temperature at 50% Shear= 20.8 Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: X Fluence: n/cm^2 125 1-

'U 0

0 - I ,

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

- 100. 00 5. 00 4. 75 .25

- 50. 00 20. 00 14.72 5. 28

- 25. 00 20. 00 24. 30 -4.30

.00 30. 00 37. 39 -7.39

25. 00 60. 00 52. 63 7. 37

25. 00 55. 00 52. 63 2. 37

50. 00 65. 00 67. 40 -2. 40

75. 00 85. 00 79. 36 5. 64

75. 00 75. 00 79. 36 -4. 36 WCAP-17269-NP September 2010 Revision 0

C-68 CAPSULE X (WELD)

Page 2 Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: X Fluence: n/cm^2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 135. 00 90. 00 94. 46 -4. 46 175.00 95. 00 97. 87 -2. 87 200. 00 100. 00 98. 85 1. 15 200. 00 100. 00 98. 85 1.15 225. 00 100. 00 99. 38 62 250. 00 100. 00 99. 66 34 Correlation Coefficient = .992 WCAP-17269-NP September 2010 Revision 0

C-69 CAPSULE X (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02J0412010 04:53 PM Page I Coefficients of Curve I A = 59.1 B = 56.9 C = 64.25 TO = -47.07 1) = O.OOE+OO Equation is A + B

• ITanh((T-To)1(C+DT))I Upper Shelf Energy=l 16.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=-83.3 Deg F Temp@50 ft-lbs=-57.4 Deg F Plant: Comanche Peak 2 Material: SA533B I Heat: C5522-2 Orientation: NA Capsule: X Fluence: n/cmA2 300 250 200 150 w

z 100 50 0 -*-

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 175.00 4. 00 4. 28 - .28

- 130. 00 27. 00 10. 20 16.80

-110.00 28. 00 16. 26 II .174

- 100.00 21. 00 20. 57 .43

-75.00 34. 00 35.81 - I.81

-50. 00 55. 00 56. 51 -1.51

- 35. 00 40. 00 69. 67 -29. 67

25. 00 63. 00 77.91 - 14. 91

10. 00 137. 00 88. 72 48. 28 WCAP-17269-NP September 2010 Revision 0

C-70 CAPSULE X (HEAT AFFECTED ZONE)

Page 2 Plant: Comanche Peak 2 Material: SA533BI Heat: C5522-2 Orientation: NA Capsule: X Fluence: n/cm^2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differenfia]

25. 00 107. 00 105. 09 I .91

75. 00 104. 00 113.51 9. 51 1 00.00 114. 00 114. 84 - . 84 125. 00 129. 00 115. 47 13. 53 125. 00 121. 00 115. 47 5. 53 150. 00 102. 00 1,15. 75 -13. 75 Correlation Coefficient -. 923 September 2010 WCAP-1 7269-NP WCAP-17269-NP September 2010 Revision 0

C-71 CAPSULE X (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02104/2010 04:54 PM Page I Coefficients of Curve I A = 33.07 B = 33.07 C = 51.65 TO = -40.87 1) = O.OOE+00 Equation is A + B

• ITanh((T-To)/(C+DT))I Upper Shelf L.E.=66. I Lower Shelf L.E.=.0(Fixed)

Temp. @LE. 35 mil:-37.8 Deg F Plant: Comanche Peak 2 Material: SA533B I Heat:C5522-2 Orientation: NA Capsule: X Fluence: n/cm^2 200 150 E

21 100 00 50 0

A a.

-300.0 0.0 300.0 600.0 Temperature In Deg F Charpy V-Notch Data Temperature Input L.E. Computed L.E Differential

- 175. 00 . 00 . 37 - .37

- 130.00 10. 00 2.03 7.97

-110. 00 7.00o4.26 2. 74

- 100.00 7. 00 6.08 .92

-75. 00 18. 00 13.93 4. 07

-50. 0,0 30. 00 27. 28 2.72

- 35. 00 19. 00 36.81 - 17. 81

- 25. 00 39. 00 42. 92 -3.92

-10. 00 70. 00 50.77 19.23 WCAP- 17269-NP September 2010 Revision 0

C-72 CAPSULE X (HEAT AFFECTED ZONE)

Page 2 Plant: Comanche Peak 2 Material: SA533B I Heat: C5522-2 Orientation: NA Capsule: X Fluence: n/cin^2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential

25. 00 63. 00 61. 35 I. 65

75. 00 58. 00 65. 40 -7.40 100.00 67. 00 65. 85 1.15 125.00 74. 00 66. 03 7. 97 125.00 68. 00 66. 03 1.97 150. 00 56. 00 66. 09 - 10.09 Correlation Coefficient - .950 WCAP-17269-NP September 2010 Revision 0

C-73 CAPSULE X (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hgperbolic Tangent Curve Printed on 0412712010 02:13 PM Page 1 Coefficients of Curve I A = 50. B = 50. C = 59.24 TO = -38.14 D = O.OOE+00 Equation is A + B

• ITanh((T-To)/(C+DT))]

Temperature at 50% Shear = -38.1 Plant Comanche Peak 2 Material: SA533Bl Heat C5522-2 Orientation: NA Capsule: X Fluence: n/cm^2 125 100 6-10 75 I..

a. 50 0/

0 25 0

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

-175.00 2. 00 .98 1. 02

-130. 00 10. 00 4.31 5. 69

-I10. 00 10. 00 8. 12 1. 88

-100. 00 15.00 11.02 3. 98

-75. 00 40. 00 22. 37 17. 63

-50. 00 30. 00 40. 12 -10. 12

-35. 00 45. 00 52. 65 -7. 65

-25. 00 35. 00 60. 91 -25.91

- 10. 00 100.00 72. 11 27. 89 WCAP-17269-NP September 2010 Revision 0

C-74 CAPSULE X (HEAT AFFECTED ZONE)

Page 2 Plant: Comanche Peak 2 Material: SA533BI Heat: C5522-2 Orientation: NA Capsule: X Fluence: n/cm^2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Diferential

25. 00 100. 00 89. 39 10. 61

75. 00 100.00 97. 85 2. 15 100. 00 100.00 99. 07 93 125. 00 100.00 99. 60 40 125. 00 100.00 99. 60 40 150.00 100.00 99. 83 17 Correlation Coefficient= .956 WCAP- 17269-NP September 2010 Revision 0

C-75 CAPSULE W (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0412712010 09:17 AM Page I Coefficients of Curve I A = 60.3 B = 58.1 C = 119.24 TO = 82.71 D = 0.OOE+00 Equation is A + B

• ITanh((T-To)/(C+DT))I Upper Shelf Energy=l 18.4(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs= 13.8 Deg F Temp@50 ft-lbs=61.4 Deg F Plant: Comanche Peak 2 Material: SA533B I Heat: C5522-2 Orientation: LT Capsule: W Fluence: n/cmA2 300 250 200 0

IL 150 0

z

> 100

_41ý...*

00 O 50 0

0

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

-50. 00 7. 00 13.52 -6.52

-20. 00 19.00 19.81 -. 81

-15.00 14.00 21. 10 -7.10

- 10. 00 38. 00 22. 46 15.54

.00 32. 00 25. 42 6.58

25. 00 34. 00 34. 19 -. 19

40. 00 44. 00 40. 34 3. 66

60. 00 43. 00 49. 37 -6.37

80. 00 56. 00 58. 98 -2.98 September 2010 WCAP-1 7269-NP WCAP- 17269-NP September 2010 Revision 0

C-76 CAPSULE W (LONGITUDINAL ORIENTATION)

Page 2 Plant: Comanche Peak 2 Material: SA533B I Heat: C5522-2 Orientation: LT Capsule: W Fluence: n/cm^2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 125. 00 75. 00 80. 08 -5. 08 200. 00 110.00 104. 14 5.86 275. 00 117.00 113.96 3. 04 300. 00 118.00 115.44 2.56 325. 00 123. 00 116. 44 6.56 350. 00 124. 00 117. 10 6.90 Correlation Coefficient = .990 WCAP-17269-NP September 2010 Revision 0

C-77 CAPSULE W (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 04127/2010 09:23 AM Page I Coefficients of Curve I A = 41.89 B = 41.89 C = 116.94 TO = 65.19 D = 0.OOE+00 Equation is A + B

• lTanh((T-To)/(C+DT))I Upper Shelf L.E.=83.8 Lower Shelf LE=.0(Fixed)

Temp.@L.E. 35 mils=45.8 Deg F Plant: Comanche Peak 2 Material: SA533B I Heat: C5522-2 Orientation: LT Capsule: W Fluence: n/cnW2 200 150 C

5 100 0O 0

50 C6 0.

0

-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed LE. Differential

-50. 00 5. 00 10.25 -5. 25

-20. 00 15. 00 15.83 - .83

-15.00 12.00 16.95 -4.95

- 10'. 00 29. 00 18. 14 10.86

.00 27. 00 20. 69 6.31

25. 00 27. 00 28. 03 -I.03

40. 00 34. 00 33. 00 I. 00

60. 00 34. 00 40. 03 -6.03

80. 00 45. 00 47. 16 m2. 16 September 2010 WCAP- 7269-NP WCAP-117269-NP September 2010 Revision 0

C-78 CAPSULE W (LONGITUDINAL ORIENTATION)

Page 2 Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: LT Capsule: W Fluence: n/cm"2 Charpy V-Notch Data Temperature Input L.E. Computed LE Differential 125. 00 61. 00 61.62 - . 62 200. 00 84. 00 76. 18 7. 82 275. 00 83. 00 81.52 1.48 300. 00 80'. 00 82. 29 -2. 29 325. 00 85. 00 82. 80 2. 20 350. 00 77. 00 83. 13 -6. 13 Correlation Coefficient = .984 September 2010 WCAP- 7269-NP WCAP-117269-NP September 2010 Revision 0

C-79 CAPSULE W (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 04/27/2010 09:20 AM Page I Coefficients of Curve I A = 50. B = 50. C = 95.99 TO = 97.59 D = 0.00E+00 Equation is A + B

• ITanh((T-To)(C+DT))l Temperature at 50% Shear = 97.6 Plant: Comanche Peak 2 Material: SA533B I Heat: C5522-2 Orientation: LT Capsule: W Fluence: n/cnP2 125 100 1..

75 U) 50 25 0

0

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

-50. 00 5.00 4.41 .59

-20. 00 10. 00 7. 94 2. 06

-15. 00 to. 00 8. 74 1. 26

- 10. 00 20. 00 9.61 10. 39

.00 15.00 11. 57 3.43

25. 00 15.00 18.06 -3. 06

40. 00 25. 00 23. 15 1. 85

60. 00 25. 00 31.36 -6.36

80. 00 40. 00 40. 94 -. 94 September 2010 WCAP-1 7269-NP WCAP-17269-NP September 2010 Revision 0

C-80 CAPSULE W (LONGITUDINAL ORIENTATION)

Page 2 Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: LT Capsule: W Fluence: n/cm,^2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 125. 00 60. 00 63. 90 - 3. 90 200. 00 100.00 89.41 10. 59 275. 00 0OO.00 97. 58 2.42 300. 00 100.00 98.55 1. 45 325. 00 100. 00 99. 13 87 350. 00 100.00 99. 48 .52 Correlation Coefficient = .994 WCAP- 17269-NP September 2010 Revision 0

C-81 CAPSULE W (TRANSVERSE ORIENTATION)

CVGRAPH 5.3 H)yerbolic Tangent Curve Printed on 04/27/2010 09:28 AM Page 1 Coefficients of Curve I A = 43.1 B = 40.9 C = 122.5 TO = 102.96 D = O.OOE+00 Equation is A + B * [Tanh((T-Toy(C+DT))]

Upper Shelf Energy=84.0(Fixed) Lower Shelf Enercyg2.2(Fixed)

Tcmp@30 ft-lbs=62.3 Deg F Tcmp@50 ft-lbs=123.9 Deg F Plant: Comanche Pcak 2 Material: SA533BI Heal: C5522-2 Orientation: TL Capsule: W Fluence: n/cm^2 300 250 200 IL 0

150 w

z 100 0

-3010.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Tempera*ure *Input CVN Computed CVN Differential

- 90. 00 7. 00 5. 56 S.44

30. 00 18.00 21. 26 - 3. 26

50. 00 31. 00 26. 44 4. 56 55.00 23. 00 27. 86 -4. 86

65. 00 34. 00 30. 82 3. 18 75.00 46. 00 33. 92 12. 08 100. 00 42. 00 42. 11 -. 11 125.00 43. 00 50. 38 -7. 38 130.00 50. 00 5 1. 99 -I 99 WCAP-17269-NP September 2010 Revision 0

C-82 CAPSULE W (TRANSVERSE ORIENTATION)

Page 2 Plant: Comanche Peak 2 Material: SA533BI Heat: C5522-2 Orientation: TL Capsule: W Fluence: n/cm^2 Charpy V-Notch Data Temperatuie Input CVN Computed CVN Differential 140. 00 46. 00 55. to -9. 10 150. 00 58. 00 58. 08 -. 08 200. 00 75. 00 70. 08 4.92 275. 00 85. 00 79. 35 5.65 300. 00 88. 00 80. 85 7. 15 325. 00 88. 00 81.88 6. 12 Correlation Coefficient = .975 WCAP-17269-NP September 2010 Revision 0

C-83 CAPSULE W (TRANSVERSE ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0412712010 09:29 AM Page I Coefficients of Curve I A = 34.08 B = 34.08 C = 130.86 TO = 85.99 D = O.OOE+00 Equation is A + B

• ITanh((T-To)/(C+DT))l Upper Shelf L.E.=68.2 Lower Shelf LE=.O(Fixed)

Temp.@L.F 35 mils=89.6 Deg F Plant: Comanche Peak 2 Material: SA533B I Heat: C5522-2 Orientation: TL Capsule: W Fluence: n/cnm2 200 150 + +

E

.o 50 0

nJ.

-300.0 0.0 0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed LE. Differential

-90. 00 5. 00 4. 33 .67

30. 00 17.00 20. 33 -3.33

50. 00 28. 00 24. 93 3.07

55. 00 2 1. 00 26. 16 -5. 16

65. 00 31. 00 28. 66 2..34

75. 00 35. 00 31.22 3.78 100. 00 38. 00 37. 71 .29 125. 00 44. 00 43. 95 05 130. 00 47. 00 45. 13 1.87 WCAP-17269-NP September 2010 Revision 0

C-84 CAPSULE W (TRANSVERSE ORIENTATION)

Page 2 Plant: Comanche Peak 2 Material: SA533B I Heat: C5522-2 Orientation: TL Capsule: W Fluence: n/cm^2 Charpy V-Notch Data Temperature Input L.E. Computed LE. Differential 140. 00 44. 00 47. 39 -3.39 150. 00 48. 00 49. 53 - I.53 200. 00 60. 00 58. 00 2.00 275. 00 62. 00 64. 56 -2. 56 300. 00 66. O0 65. 66 .34 325. 00 68. 00 66. 43 1. 57 Correlation Coefficient = .990 WCAP-17269-NP September 2010 Revision 0

C-85 CAPSULE W (TRANSVERSE ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 04/27/2010 09:28 AM Page I Coefficients of Curve I A = 50. B = 50. C = 97.7 TO = 126.68 D = O.OOE+O0 Equation is A + B

• ITanh((T-To)I(C+DT))]

Temperature at 50% Shear= 126.7 Plant: Comanche Peak 2 Material: SA533B I Heat: C5522-2 Orientation: TL Capsule: W Fluence: n/cmA2 125 100 I-75 OU)

Ix 50 25 0 i - - -- - 1'

-300.0 -200.0 -100.0 0.0 100.0 200.0 3()0.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

-90. 00 2. 00 1.17 .83

30. 00 15.00 12. 14 2. 86

50. 00 25. 00 17.23 7.77

55. 00 20. 00 18.73 1. 27

65. 00 25. 00 22. 05 2. 95

75. 00 25. 00 25. 77 - .77 100. 00 45. 00 36. 68 8. 32 125. 00 40. 00 49. 14 -9. 14 130. 00 40. 00 51. 70 -11.70 September 2010 WCAP-1 7269-NP WCAP- 17269-NP September 2010 Revision 0

C-86 CAPSULE W (TRANSVERSE ORIENTATION)

Page 2 Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: TL Capsule: W Fluence: n/cm^2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 1 40. 00 40. 00 56. 78 -16.78 150. 00 75. 00 61. 71 13.29 200. 00 95. 00 81.77 13.23 275. 00 100. 00 95. 42 4.58 300. 00 100. 00 97. 20 2. 80 325. 00 100. 00 98. 30 1.70 Correlation Coefficient= .970 WCAP- 17269-NP September 2010 Revision 0

C-87 CAPSULE W (WELD)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 04/27/2010 09:37 AM Page 1 Coefficients of Curve I A = 42.85 B = 40.65 C = 32.64 TO = 45.05 D = O.OOE+O0 Equation is A + B

• ITanh((T-Toy(C+DT))I Upper Shelf Energy=83.5(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=34.4 Deg F Temp@50 ft-lbs=50.9 Deg F Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: W Fluence: nIcmA2 300 250 200 0

150 0

Lu z

>. 100 Q

50 0

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

-90. 00 5. 00 2. 22 2. 78

25. 00 2 1. 00 20. 62 38

30. 00 17.00 25. 34 -8. 34

30. 00 25. 00 25. 34 34 35.00 3 1. 00 30. 72 28

40. 00 32.00 36. 62 -4. 62

45. 00 44. 00 42. 79 1 .21

45. 00 59. 00 42. 79 16. 21

50. 00 60. 00 48. 97 II. 03 WCAP- 17269-NP September 2010 Revision 0

C-88 CAPSULE W (WELD)

Page 2 Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: W Fluence: n/cm^2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

50. 00 35. 00 48. 97 -13.97

75. 00 65. 00 72. 31 -7.31 175. 00 74.00 83.47 -9.47 275. 00 86. 00 83. 50 2.50 300. 00 87. 00 83. 50 3. 50 325. 00 87. 00 83. 50 3. 50 Correlation Coefficient = .959 WCAP-17269-NP September 2010 Revision 0

C-89 CAPSULE W (WELD)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0412712010 09:35 AM Page I Coefficients of Curve I A = 35.93 B = 35.93 C = 38.16 TO = 40.25 D = O.OOE+00 Equation is A + B

• ITanh((T-To)/(C+DT))]

Upper Shelf L.E.=71.9 Lower Shelf LE.=.0(Fixed)

Temp.@L.E. 35 mils=39.3 Deg F

• Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: W Fluence: n/cmA2 200 150 E

.o 100 50 0 ! 4-

-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed LE. Differential

-90. 00 5.00 08 4.92

25. 00 24. 00 22. 29 1.7 1

30. 00 18.00 26. 51 -8.5 1

30. 00 29. 00 26. 51 2.49

35. 00 30. 00 31. 02 - I. 02

40. 00 29. 00 35. 70 -6.70

45. 00 43. 00 40. 38 2. 62

45. 00 52. 00 40. 38 11. 62

50. 00 50. 00 44. 92 5.08 WCAP-17269-NP September 2010 Revision 0

C-90 CAPSULE W (WELD)

Page 2 Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: W Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed LE. Differential

50. 00 41. 00 44. 92 -3.92

75. 00 55. 00 61. 85 -6. 85 175. 00 67. 00 71. 80 -4.80 275. 00 78. 00 71. 86 6. 14 300. 00 76. 00 71. 86 4. 14 325. 00 69. 00 71. 86 -2. 86 Correlation Coefficient = .965 WCAP-17269-NP September 2010 Revision 0

C-91 CAPSULE W (WELD)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 04/27/2010 09:37 AM Page 1 Coefficients of Curve I A = 50. B = 50. C = 67.19 TO = 31.11 D =0.OEE+00 Equation is A + B

• ITanh((T-To)/(C+DT))l Temperature at 50% Shear = 31.2 Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: W. Fluence: n/cm^2 125 100 75-t..

50-25 -

0o

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

-90.00 5. 00 2. 65 2. 35

25. 00 50. 00 45. 46 4. 54

30. 00 40. 00 49. 17 -9. 17

30. 00 50. 00 49. 17 83 35.00 55. 00 52. 89 2. II

40. 00 55. 00 56. 58 -I.

58

45. 00 60. 00 60. 19 19

45. 00 65. 00 60. 19 4. 81

50. 00 70. 00 63. 70 6. 30 WCAP-17269-NP September 2010 Revision 0

C-92 CAPSULE W (WELD)

Page 2 Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: W Fluence: nfcm^2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

50. 00 55. 00 63. 70 -8.70

75. 00 80. 00 78. 69 1.31 175. 00 98. 00 98. 64 .. 64 275. 00 100. 00 99. 93 07 300. 00 100. 00 99. 97 .03 325. 00 100. 00 99. 98 02 Correlation Coefficient = .987 WCAP-1 7269-NP September 2010 Revision 0

C-93 CAPSULE W (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 04/27/2010 09:38 AM Page I Coefficients of Curve I A = 56.6 B = 54.4 C = 57.45 TO = -49.64 D = O.0OE+00 Equation is A + B

• ITanh((T-To)/(C+DT))]

Upper Shelf Energy=l I 1.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=-80.3 Deg F Temp@50 ft-lbs=-56.6 Deg F Plant: Comanche Peak 2 Material: SA533B I Heat: C5522-2 Orientation: NA Capsule: W Fluence: n/cmA2 300 250

@1

• 200 150 0

Lu 100 50

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 175. 00 5. 00 3. 57 1.43

-90. 00 18.00 23. 63 -5.63

-80. 00 18. 00 30. 26 -12.26

-75. 00 41. 00 34. 03 6. 97

-75. 00 60. 00 34. 03 25. 97

-70. 00 16. 00 38. 09 -22. 09

-65. 00 62. 00 42. 39 19.61

-60. 00 74. 00 46. 89 27. 11

-60. 00 27. 00 46. 89 - 19. 89 WCAP-17269-NP September 2010 Revision 0

C-94 CAPSULE W (HEAT AFFECTED ZONE)

Page 2 Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: NA Capsule: W Fluence: n/cm,^2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

-60. 00 25. 00 46. 89 -21. 89

-50. 00 57. 00 56. 26 .74

-25. 00 79. 00 78. 60 40 200. 00 93. 00 110. 98 -17.98 225. 00 147. 00 110. 99 36. 01 275. 00 93. 00 III. 00 -18. 00 Correlation Coefficient = .864 WCAP- 17269-NP September 2010 Revision 0

C-95 CAPSULE W (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 04/27/2010 09:33 AM Page I Coefficients of Curve I A = 34.3 B = 34.3 C = 64.75 TO = -48.88 D = O.O0E+OO Equation is A + B

• ITanh((T-Toy(C+DT))I Upper Shelf L.E.=68.6 Lower Shelf LE.=.0(Fixed)

Temp.@LE. 35 mils=-47.5 Deg F Plant: Comanche Peak 2 Material: SA533BI Heat: C5522-2 Orientation: NA Capsule: W. Fluence: n/cmA2 200 150 E

la 100 0

0 0 50 n4 0

-300.0 6( 00.0 0.0 300.0 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed LE. Differential

- 175. 00 3.00 1.37 1.63

-90. 00 11. 00 15.04 -4.04

-80. 00 10. 00 18.98 -8. 98

-75. 00 25. 00 21. 17 3.83

-75. 00 36. 00 21. 17 14. 83

-70. 00 12. 00 23. 49 - 11 . 49

-65. 00 38.00 25. 93 12.07

-60. 00 40. 00 28. 47 11.53

-60. 00 19. 00 28. 47 -9. 47 WCAP- 17269-NP September 2010 Revision 0

C-96 CAPSULE W (HEAT AFFECTED ZONE)

Page 2 Plant: Comanche Peak 2 Material: SA533BI Heat: C5522-2 Orientation: NA Capsule: W Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed LE Differential

-60. 00 18. 00 28. 47 - 10.47

-50. 00 36. 00 33. 71 2. 29

-25. 00 45. 00 46. 40 - I. 40 200. 00 64. 00 68. 56 '4.56 225. 00 80. 00 68. 58 11. 42 275. 00 62. 00 68. 59 -6.59 Correlation Coefficient = .916 WCAP-17269-NP September 2010 Revision 0

C-97 CAPSULE W (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0412712010 09:39 AM Page I Coefficients of Curve I A = 50. B = 50. C = 63-51 TO = -50.63 D =O.O0E+O0 Equation is A + B

• ITanh((T-To)I(C+DT))I Temperature at 50% Shear = -50.6 Plant: Comanche Peak 2 Material: SA533BI Heat: C5522-2 Orientation: NA Capsule: W Fluence: n/cmA2 125 100 CD 75 U)

C) a1. 50 25 0 f- .=----+-------- 1-----

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

- 175. 00 2. 00 1.95 05

-90. 00 15. 00 22. 45 -7. 45

-80. 00 20. 00 28. 40 -8. 40

-75. 00 30. 00 31. 71 -I 71

-75. 00 60. 00 31. 71 28. 29

-70. 00 15. 00 35. 21 20. 2 1

-65. 00 60. 00 38. 88 21. 12

-60. 00 50. 00 42. 68 7. 32

-60. 00 45. 00 42. 68 2. 32 WCAP-1 7269-NP September 2010 Revision 0

C-98 CAPSULE W (HEAT AFFECTED ZONE)

Page 2 Plant: Comanche Peak2 Material: SA533BI Heat: C5522-2 Orientation: NA Capsule: W Fluence: nf/cm^2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

-60. 00 25. 00 42. 68 - 17. 68

-50. 00 45. 00 50. 50 -5.50

-25. 00 70. 00 69. 15 . 85 200. 00 98. 00 99. 96 - i. 96 225. 00 t00. 00 99. 98 02 275. 00 t00. 00 t00. 00 00 Correlation Coefficient = .922 WCAP-1 7269-NP September 2010 Revision 0

D-1 APPENDIX D COMANCHE PEAK UNIT 2 SURVEILLANCE PROGRAM CREDIBILITY EVALUATION D.1 INTRODUCTION Regulatory Guide 1.99, Revision 2 [Ref. D-1] 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. Positions 2.1 and 2.2 of Regulatory Guide 1.99, Revision 2, describe 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 Positions 2.1 and 2.2 can only be applied when two or more credible surveillance data sets become available from the reactor in question.

To date there have been three surveillance capsules removed from the Comanche Peak Unit 2 reactor vessel and tested. To use these surveillance data sets, they must be shown to be credible. in accordance with Regulatory Guide 1.99, Revision 2, the credibility of the surveillance data will be judged based on five criteria.

The purpose of this evaluation is to apply the credibility requirements of Regulatory Guide 1.99, Revision 2, to the Comanche Peak Unit 2 reactor vessel surveillance data and determine if that surveillance data is credible.

D.2 EVALUATION Criterion 1: Materials in the capsules should be those judged most likely to be controlling with regard to radiation embrittlement.

The beltline region of the reactor vessel is defined in Appendix G to 10 CFR Part 50, "Fracture Toughness Requirements" [Ref. D-2], as follows:

"the region of the reactor vessel (shell material including welds, heat affected zones, and plates orforgings) 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 consideredin the selection of the most limiting materialwith regardto radiationdamage."

The Comanche Peak Unit 2 reactor vessel consists of the following beltline region materials:

• Intermediate Shell Plates R3807-1, 2, and 3 (Heat # C5522-1, C5522-2, and B9566-1)

" Lower Shell Plates R3816-1, 2, and 3 (Heat # NR64435-1, NR64439-1, and NR64443-1)

" Intermediate to Lower Shell Circumferential Weld Seam (Heat # 89833)

• Intermediate & Lower Shell Longitudinal Weld Seams (Heat # 89833)

At the time when the Comanche Peak Unit 2 surveillance program material was selected it was believed that copper and phosphorus were the elements most important to embrittlement of the reactor vessel WCAP-17269-NP September 2010 Revision 0

D-2 steels. Since all the plates had essentially the same weight percent copper, the choice for the surveillance plate was based on the plate that had the lowest initial USE, which was Intermediate Shell Plate R3807-2 (initial USE = 101 ft-lbs). In addition, this material also has the highest initial RTNDT (initial RTNDT =

10F) of all the plates in the beltline region. Therefore, based on the highest initial RTNDT and the lowest initial USE, Intermediate Shell Plate R3807-2 was chosen for the surveillance program.

The weld material in the Comanche Peak Unit 2 surveillance program was made of the same weld wire (Heat # 89833) as all the reactor vessel beltline welds. Thus, it was chosen as the surveillance weld material.

Hence, Criterion 1 is met for the Comanche Peak Unit 2 surveillance program.

Criterion 2: Scatter in the plots of Charpy energy versus temperature for the irradiated and unirradiated conditions should be small enough to permit the determination of the 30 ft-lb temperature and USE unambiguously.

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 USE of the Comanche Peak Unit 2 surveillance materials unambiguously. Hence, the Comanche Peak Unit 2 surveillance program meets this criterion.

Criterion 3: When there are two or more sets of surveillance data from one reactor, the scatter of ARTNDT values about a best-fit line drawn as described in Regulatory Position 2.1 should normally be less than 28°F for welds and 17'F for base. metal. Even if the fluence range is large (two or more orders of magnitude), the scatter should not exceed twice those values. Even if the data fail this criterion for use in shift calculations, they may be credible for determining decrease in USE if the upper shelf can be clearly determined, following the definition given in ASTM E185-82 [Ref. D-3].

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 28°F for welds and less than 17'F for the plate.

The Comanche Peak Unit 2 Intermediate Shell Plate R3807-2 and surveillance weld material will be evaluated for credibility. The weld is made from weld wire Heat # 89833; Comanche Peak Unit 2 does not have a sister plant that shares the same weld wire heat and thus, does not utilize data from other surveillance programs. Therefore, the method of Regulatory Guide, 1.99, Revision 2 will be followed for determining credibility of the weld as well as the plate material.

Credibility Assessment:

Since all surveillance data is from one vessel (Comanche Peak Unit 2), the measured ARTNDT and fluence factor (FF) should be used to calculate the chemistry factors to determine if the Comanche Peak Unit 2 surveillance material test results are credible.

The chemistry factors for the Comanche Peak Unit 2 surveillance plate and weld material contained in the surveillance program were calculated in accordance with Regulatory Guide 1.99, Revision 2, Position 2.1 WCAP-17269-NP September 2010 Revision 0

D-3 and are presented in Table D-1. 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-1 Calculation of Chemistry Factors using Comanche Peak Unit 2 Surveillance Capsule Data Materialf Capsule Cpu FF (x10"9 n/cm2) (OF) (OF)'

U 0.317 0.685 1.6 1.10 0.469 Intermediate Shell Plate R3807-2 (Longitudinal) X 2.16 1.209 1.6 1.93 1.462 W 3.38 1.319 23.2 30.59 1.739 U 0.317 0.685 23.4 16.02 0.469 Intermediate Shell Plate x 2.16 1.209 52.9 63.96 1.462 R3807-2 (Transverse)

W 3.38 1.319 74.4 98.11 1.739 SUM: 211.71 7.339 CFR3807-2 =X(FF

• ARTNDT) Y-( FF 2) = (211.71) + (7.339) = 28.8°F U 0.317 0.685 3.6 2.46 0.469 Surveillance Weld X 2.16 1.209 48.2 58.28 1.462 Material W 3.38 1.319 84.0 110.76 1.739 SUM: 171.51 3.669 CF sumv. Wed = Y(FF

• ARTNDT) + Y( FF 2) = (171.51) + (3.669)= 46.7°F WCAP-17269-NP September 2010 Revision 0

D-4 Table D-2 Comanche Peak Unit 2 Surveillance Capsule Data Scatter about the Best-Fit Line CF -Measured Predicted Scatter 7TF Material CaPsule (SlOpebesti Capsulef FF ARTNDr ARTNDT . ARTNDT, (Base Metal)

- !' (xlO' 9 n/cm 2) F..M.. ) f*. .d

%_____ (0 F . (0F) F ) 9F)

Intermediate U 28.8 0.317 0.685 1.6 19.7 18.1 No Shell Plate X 28.8 2.16 1.209 1.6 34.8 33.2 No R3807-2 (Longitudinal) W 28.8 3.38 1.319 23.2 38.0 14.8 Yes Intermediate U 28.8 0.317 0.685 23.4 19.7 3.7 Yes Shell Plate X 28.8 2.16 1.209 52.9 34.8 18.1 No R3807-2 2826 2 594.1 (Transverse) W 28.8 3.38 1.319 74.4 38.0 36.4 No U 46.7 0.317 0.685 3.6 32.0 28.4 No Surveillance Welate X 46.7 2.16 1.209 48.2 56.5 8.3 Yes Weld Material W 46.7 3.38 1.319 84.0 61.6 22.4 Yes From a statistical point of view, +/- 1c would be expected to encompass 68% of the data. Table D-2 indicates that four of the six surveillance data points fall outside the +/- la of 17°F scatter band for surveillance base metals; therefore, the plate data is deemed "not credible" per the third criterion.

Table D-2 indicates that one of the three surveillance data points falls outside the +/- 1c of 28°F scatter band for surveillance weld materials. The Comanche Peak Unit 2 surveillance weld material only has three data points. In order for the weld material to fully satisfy this requirement literally, all three data points would have to fall within the +/- I a scatter band. Since 66.7% (two-thirds) of the weld data fall within the +/- Ic scatter band, it is concluded that this is approximately 68% and meets the intent of the requirement. Also note that the surveillance weld data point (Capsule U) that falls outside the scatter band is only slightly outside the criteria by approximately 0.4°F. Therefore, the surveillance weld data is deemed "credible" per the third criterion.

Note that although Intermediate Shell Plate R3807-2 did not meet Criterion 3, both materials (Intermediate Shell Plate R3807-2 and the surveillance weld material) may still be used in determining the upper shelf energy decrease in accordance with Regulatory Guide 1.99, Revision 2, Position 2.2.

Criterion 4: The irradiation temperature of the Charpy specimens in the capsule should match the vessel wall temperature at the cladding/base metal interface within +/- 25°F.

The capsule specimens are located in the reactor between the neutron pad and the vessel wall and are positioned opposite the center of the core. The test capsules are in baskets attached to the neutron pad.

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 temperatures will not differ by more than 25°E Hence, this criterion is met.

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D-5 Criterion 5: The surveillance data for the correlation monitor material in the capsule should fall within the scatter band of the database for that material.

The Comanche Peak Unit 2 surveillance program does not contain correlation monitor material.

Therefore, this criterion is not applicable to the Comanche Peak Unit 2 surveillance program.

D.3 CONCLUSION Based on the preceding responses to all five criteria of Regulatory Guide 1.99, Revision 2, Section B, the Comanche Peak Unit 2 surveillance data is deemed credible for the weld specimens and non-credible for the plate specimens.

D.4 REFERENCES D-1 Regulatory Guide 1.99, Revision 2, Radiation Embrittlement of Reactor Vessel Materials, U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, May 1998..

D-2 10 CFR 50, Appendix G, Fracture Toughness Requirements, Federal Register, Volume 60, No. 243, December 19, 1995.

D-3 ASTM E185-82, Standard Practicefor Conducting Surveillance Tests for Light-Water Cooled Nuclear PowerReactor Vessels, E706(IF), ASTM, 1982.

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E-1 APPENDIX E COMANCHE PEAK UNIT 2 UPPER SHELF ENERGY EVALUATION Per Regulatory Guide 1.99, Revision 2 [Ref. E-1], the Charpy upper shelf energy (USE) is assumed to decrease as a function of fluence and copper content as indicated in Figure 2 of the Guide (Figure E-I of this appendix) when surveillance data is not used. Linear interpolation is permitted. In addition, if surveillance data is to be used, the decrease in upper shelf energy may be obtained by plotting the reduced plant surveillance data on Figure 2 of the Guide (Figure E-1 of this appendix) and fitting the data with a line drawn parallel to the existing lines as the upper bound of all the data. This line should be used in preference to the existing graph.

The 36 EFPY (end-of-license) and 54 EFPY (end-of-license renewal) upper shelf energy of the vessel materials can be predicted using the corresponding I/4T fluence projection, the copper content of the beltline materials and/or the results of the capsules tested to date using Figure 2 in Regulatory Guide 1.99, Revision 2. The maximum vessel clad/base metal interface fluence value was used to determine the corresponding 1/4T fluence value at 36 and 54 EFPY.

The Comanche Peak Unit 2 reactor vessel beitline region minimum thickness is 8.63 inches. Calculation of the 1/4T vessel surface fluence values at 36 and 54 EFPY for the beitline materials is shown as follows:

Maximum Vessel Fluence @ 36 EFPY = 2.10 x 10' 9 n/cm 2 (E > 1.0 MeV) 2 0 24 1/4T Fluence @ 36 EFPY = (2.10 x 1019 n/cm )

• e(- . *(8.63/4))

1.251 x 10' 9 n/cm 2 (E > 1.0 MeV)

Maximum Vessel Fluence @ 54 EFPY = 3.14 x 1019 n/cm 2 (E > 1.0 MeV) 2 1/4T Fluence @ 54 EFPY = (3.14 x 10 1 n/cm )

• e(-024 * (8.63 /4))

= 1.871 x 10"9 n/cm 2 (E > 1.0 MeV)

The following pages present the Comanche Peak Unit 2 upper shelf energy evaluation. Figure E-i, as indicated above, is used in making predictions in accordance with Regulatory Guide 1.99, Revision 2.

Table E-1 provides the predicted upper shelf energy values for 36 EFPY (end-of-license). Table E-2 provides the predicted upper shelf energy values for 54 EFPY (end-of-license renewal).

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E-2 100.0 **  ; !-*** * */* ** .. ........

• • *,* **:7: *Surveillance Material:

• i* ................. W eld Heat 89833

% Copper ý=I Base Metal Weld S0.35:*0.30 0.30Wel 0.25 S0.25 0.20 CL* 0.20 0.15 0 0.15 0.10 o 10.0 0.10 0.05 0)

I...;' * * ....,

• * *,,,i

• 3 6 E F P Y 1/4T . ...... 54 E F P Y 1 /4T

• ,:*fluence fluence

~1.251 x 1019 n/cm2 .. 1.871 x 109 in/m 1.0 1.OOE+17 1.OOE+18 1.OOE+19 1.OOE+20 Neutron Fluence, n/cm2 (E > 1 MeV)

Figure E-1 Regulatory Guide 1.99, Revision 2 Predicted Decrease in Upper Shelf Energy as a Function of Copper and Fluence WCAP- 17269-NP September 2010 Revision 0

E-3 Table E-1 Predicted Positions 1.2 and 2.2 Upper Shelf Energy Values at 36 EFPY 11/4T

,I EL L,w * ..Unirradiated

. Projected:

Wegt Fluenice " , , .= . Projected Material Wei.t..uei:SE USE DecreaseI EOL USE

% of'Cu (xl-? n/cm-, USE , ____...__

_______________________________ ______ _ E >1. M ) (ft-lb) . . . (%)M (ft-lb) ..

Position 1.2, Intermediate Shell Plate R3807-1 0.06 1.251 108 20 86.4 Intermediate Shell Plate R3807-2 0.06 1.251 101 20 80.8 Intermediate Shell Plate R3807-3 0.05 1.251 105 20 84 Lower Shell Plate R3816-1 0.05 1.251 107 20 85.6 Lower Shell Plate R3816-2 0.03 1.251 106 20 84.8 Lower Shell Plate R3816-3 0.04 1.251 108 20 86.4 Intermediate & Lower Shell 0.046 1.251(a) 172 20 137.6 Longitudinal Welds (Heat # 89833)

Intermediate to Lower Shell 0.046 1.251 96 20 76.8 Circumferential Weld (Heat # 89833) 1 Position 2 .2(b)

Intermediate Shell Plate R3807-2 0.06 1.251 101 2(c) 99.0 Intermediate & Lower Shell 0.046 1.251(a 172 14 147.9 Longitudinal Welds (Heat # 89833)

Intermediate to Lower Shell 0.046 1.251 96 14 82.6 Circumferential Weld (Heat # 89833)

Notes:

(a) The fluence values listed for the intermediate and lower shell longitudinal welds conservatively pertain to the maximum vessel fluence value, though the welds vary in location.

(b) Calculated using surveillance capsule measured percent decrease in USE from Table 5-10 and Regulatory Guide 1.99, Revision 2, Position 2.2; see Figure E-1.

(c) The most limiting surveillance data point for Intermediate Shell Plate R3807-2 is a measured decrease of 0% at a fluence of 3.38 x 1019 n/cm 2 pertaining to Capsule W. A parallel line cannot be drawn in accordance with the guidelines of Position 2.2 of Regulatory Guide 1.99, Revision 2 using this limiting data point. Therefore, a Position 2.2 projected USE decrease of 2% is conservatively used.

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E-4 Table E-2 Predicted Positions 1.2 and 2.2 Upper Shelf Energy Values at 54 EFPY 1/4-T EOLR I Weigh F~i~n~e 9

UnirrAdiated I Pojec-ted UE Projected,,

Materiil' i~ 2 ,-xOUSE D ~~ EOLR"

• _________J (t-b), USEQtfitl)

Position 1.2 Intermediate Shell Plate R3807-1 0.06 1.871 108 22 84.2 Intermediate Shell Plate R3807-2 0.06 1.871 101 22 78.8 Intermediate Shell Plate R3807-3 0.05 1.871 105 22 81.9 Lower Shell Plate R3816-1 0.05 1.871 107 22 83.5 Lower Shell Plate R3816-2 0.03 1.871 106 22 82.7 Lower Shell Plate R3816-3 0.04 1.871 108 22 84.2 Intermediate & Lower*Shell Itrdat&Lo rhel 0.046 1.871(a) 172 22 134.2 Welds (Heat # 89833)

Longitudinal Intermediate to Lower Shell 0.046 1.871 96 22 74.9 046.7927.

Circumferential Weld (Heat # 89833)

Position 2 .2(b)

Intermediate Shell Plate R3807-2 0.06 1.871 101 2(c) 99.0 Intermediate & Lower Shell 0.046 1.871(a) 172 16 144.5 Longitudinal Welds (Heat # 89833)

Intermediate to Lower Shell 0.046 1.871 96 16 80.6 Circumferential Weld (Heat # 89833) 1 _ _1 Notes:

(a) The fluence values listed for the intermediate and lower shell longitudinal welds conservatively peitain to the maximum vessel fluence value, though the welds vary in location.

(b) Calculated using surveillance capsule measured percent decrease in USE from Table 5-10 and Regulatory Guide 1.99, Revision 2, Position 2.2; see Figure E-1.

(c) The most limiting surveillance data point for Intermediate Shell Plate R3807-2 is a measured decrease of 0% at a fluence of 3.38 x 1019 n/cm 2 pertaining to Capsule W. A parallel line cannot be drawn in accordance with the guidelines of Position 2.2 of Regulatory Guide 1.99, Revision 2 using this limiting data point. Therefore, a Position 2.2 projected USE decrease of 2% is conservatively used.

USE Conclusion All of the beltline materials in the Comanche Peak Unit 2 reactor vessel are projected to remain above the USE screening criterion value of 50 ft-lb (per 10 CFR 50, Appendix G) at 36 and 54 EFPY September 2010 WCAP-1 7269-NP WCAP-17269-NP September 2010 Revision 0

E-5 E.1 REFERENCES E-1 U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Regulatory Guide 1.99, Revision 2, RadiationEmbrittlement ofReactor Vessel Materials,May 1988.

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