ML061100542
| ML061100542 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 09/30/2004 |
| From: | Conermann J, Ghergurovich J, Hayes E, Laubham T Westinghouse |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| WCAP-16277-NP, Rev 0 | |
| Download: ML061100542 (220) | |
Text
Westinghouse Non-Proprietary Class 3 WCAP-1 6277-NP September 2004 Revision 0 Analysis of Capsule X from the TXU Energy Comanche Peak Unit 2 Reactor Vessel Radiation Surveillance Program
- Westinghouse
WESTINGHOUSE NON-PROPRIETARY CLASS 3 WCAP-16277-NP, Revision 0 Analysis of Capsule X from the TXU Energy Comanche Peak Unit 2 Reactor Vessel Radiation Surveillance Program T.J. Laubham J. Conermann E.T. Hayes September 2004 Approved: i L Ghergurovic Manager Reactor Component Design & Analysis Westinghouse Electric Company LLC Energy Systems P.O. Box 355 Pittsburgh, PA 15230-0355 02004 Westinghouse Electric Company LLC All Rights Reserved
iii TABLE OF CONTENTS LIST OF TABLES ......... iv LIST OF FIGURES.............. ... vi PREFACE .........
viii EXECUTIVE
SUMMARY
.................. ix 1
SUMMARY
OF RESULTS .1-1 2 INTRODUCTION .2-1 3 BACKGROUND .3-1 4 DESCRIPTION OF PROGRAM .4-1 5 TESTING OF SPECIMENS FROM CAPSULE X .. 5-1 5.1 OVERVIEW .; 5-1 5.2 CHARPY V-NOTCH IMPACT TEST RESULTS .5-3 5.3 TENSILE TEST RESULTS .5-5.
5.4 1/2T COMPACT TENSION SPECIMEN TESTS .5-5 6 RADIATION ANALYSIS AND NEUTRON DOSIMETRY . .6-1
6.1 INTRODUCTION
. 6-1 6.2 DISCRETE ORDINATES ANALYSIS .6-2 6.3 NEUTRON DOSIMETRY .6-5 6.4 CALCULATIONALUNCERTAINTIES .6-6 7 SURVEILLANCE CAPSULE REMOVAL SCHEDULE .7-8 REFERENCES ...... -1 8 R F R N E ... .... ... . . ...................................................................................................................... 8-APPENDIX A VALIDATION OF THE RADIATION TRANSPORT MODELS BASED ON NEUTRON DOSIMETRY MEASUREMENTS . A-0 APPENDIX B LOAD-TIME RECORDS FOR CHARPY SPECIMEN TESTS .B-0 APPENDIX C CHARPY V-NOTCH PLOTS FOR CAPSULE X USING SYMMETRIC HYPERBOLIC TANGENT CURVE-FITTING METHOD .C-0 APPENDIX D COMANCHE PEAK UNIT 2 SURVEILLANCE PROGRAM CREDIBILITY EVALUATION .D-0
iv LIST OF TABLES Table 4-1 Chemical Composition (wt %) of the Comanche Peak Unit 2 Reactor Vessel Surveillance Materials (Unirradiated) ........................ 4-3 Table 4-2 Heat Treatment History of the Comanche Peak Unit 2 Reactor Vessel Surveillance Materials . 44 Table 4-3 Chemical Composition (wt%) of the Comanche Peak Unit 2 Reactor Vessel Weld Materials (Unirradiated) .4-5 Table 4-4 Heat Treatment History of the Comanche Peak Unit 2 Reactor Vessel Materials . 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 2.20 x 1l19 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 2.20 x 1 l9 n/cm2 (E>.1.0 MeV)
(Transverse Orientation) ............... 5-7 Table 5-3 Charpy V-notch Data for the Comanche Peak Unit 2 Surveillance Weld Material Irradiated to a Fluence of 2.20 x 10191n/cm 2 (E> 1.0 MeV) ....................................... 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 2.20 x 1O'9 n/cm2 (E> 1.0 MeV) .............................. 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 2.20 x IO"1 n/cm 2 (E> 1.0 MeV) (Longitudinal Orientation) ........................... 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 2.20 x lO'1 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 2.20 x 11i9 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) Metal Irradiated to a Fluence of 2.20 x 1019 n/cm2 (E> 1.0MeV) ....... ; 5-13 Table 5-9 Effect of Irradiation to 2.20 x 10'9 n/cm2 (E> 1.0 MeV) on the Capsule X Notch Toughness Properties of the Comanche Peak Unit 2 Reactor Vessel Surveillance Materials .... 5-14
V LIST OF TABLES (Cont.)
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 X Reactor Vessel Surveillance Materials Irradiated to 2.20 x IO"1 n/cm2 (E> 1.0MeV) ........................... 5 -16 Table 6-1 Calculated Neutron Exposure Rates and Integrated Exposures At The Surveillance Capsule Center ................... 6-8 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 Wall ............ 6-16 Table 64 Relative Radial Distribution Of Iron Atom Displacements (dpa) Within The Reactor Vessel Wall ............. 6-16 Table 6-5 Calculated Fast Neutron Exposure of Surveillance Capsules Withdrawn from Comanche Peak Unit 2 .6-17 Table 6-6 Calculated Surveillance Capsule Lead Factors .6-17 Table 7-1 Recommended Surveillance Capsule Withdrawal Schedule .7-
Ai LIST OF FIGURES Figure 4-1 Arrangement of Surveillance Capsules in the Comanche Peak Unit 2 Reactor Vessel ...4-7 Figure 4-2 Capsule X Diagram Showing the Location of Specimens, Thermal Monitors, and Dosimeters .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 54 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 Comanche Peak Unit 2 Reactor Vessel Weld Metal . 5-23 Figure 5-8 Charpy V-Notch Lateral Expansion vs. Temperature for Comanche Peak Unit 2 Reactor Vessel Weld Metal . 5-24 Figure 5-9 Charpy V-Notch Percent Shear vs. Temperature for Comanche Peak Unit 2 Reactor Vessel Weld Metal........... ...... 5-25 Figure 5-10 Charpy V-Notch Impact Energy vs. Temperature for Comanche Peak Unit 2 Reactor Vessel Heat-Affected-Zone Material ............................. 5-26 Figure 5-11 Charpy V-Notch Lateral Expansion vs. Temperature for Comanche Peak Unit 2 Reactor Vessel Heat-Affected-Zone Material ............................................. 5-27 Figure 5-12 Charpy V-Notch Percent Shear vs. Temperature for Comanche Peak Unit 2 Reactor Vessel Heat-Affected-Zone Material . 5-28 Figure 5-13 Charpy Impact Specimen Fracture Surfaces for Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3 807-2 (Longitudinal Orientation) . 5-29
vii LIST OF FIGURES (Cont.)
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 Comanche Peak Unit 2 Reactor Vessel Weld Metal ........................................................ 5-31 Figure 5-16 Charpy Impact Specimen Fracture Surfaces for Comanche Peak Unit 2 Reactor l Vessel Heat-Affected-Zone Metal ........................................................ 5-32 Figure 5-17 Tensile Properties for Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (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 Comanche Peak Unit 2 Reactor Vessel 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 Comanche Peak Unit 2 Reactor Vessel Weld Metal ........................................................ 5-38 Figure 5-23 Engineering Stress-Strain Curves for Comanche Peak Unit 2 Intermediate Shell Plate R3807-2 Tensile Specimens CL-10, CL-1I and CL-12 (Longitudinal Orientation) ........................................................ 5-39 Figure 5-24 Engineering Stress-Strain Curves for Comanche Peak Unit 2 Intermediate Shell Plate R3807-2 Tensile Specimens CT-10, CT-1I and CT-12 (Transverse Orientation)................................................................................................541 Figure 5-25 Engineering Stress-Strain Curves for Weld Metal Tensile Specimens CW-10, CW-11 and CW-12 ........................................................ 5-43 Figure 6-1 Comanche Peak Unit 2 rO Reactor Geometry ........................................................ 6-18 Figure 6-2 Comanche Peak Unit 2 rz Reactor Geometry ........................................................ 6-21
- viii PREFACE This report has been technically reviewed and verified by:
Reviewer:
Sections 1 through 5, 7, 8, Appendices B, C and D C.M. Burton CtOAZk--
Section 6 and Appendix A GK. Roberts
ix EXECUTIVE
SUMMARY
The purpose of this report is to document the results of the testing of surveillance Capsule X from Comanche Peak Unit 2. Capsule X was removed at 8.83 EFPY and post irradiation mechanical tests of the Charpy V-notch and tensile specimens were performed. A fluence evaluation utilizing the recently released neutron transport and dosimetry cross-section libraries was derived from the ENDF/B-VI data-base. Capsule X received a fluence of 2.20 x IO" n/cm2 (E > 1.0 MeV) after irradiation to 8.83 EFPY.
The peak clad/base metal interface vessel fluence after 8.83 EFPY of plant operation was 5.30 x 1018 n/cm2 (E > 1.0 MeV).
This evaluation lead to the following conclusions: 1) The measured 30 ft-lb shift in transition temperature value of the intermediate shell plate R3807-2 contained in capsule X (Longitudinal) is less than the Regulatory Guide 1.99, Revision 2 1'1, predictions. 2) The measured 30 ft-lb shift in transition temperature value of the intermediate shell plate R3807-2 contained in capsule X (transverse) is greater than the Regulatory Guide 1.99, Revision 2, prediction. However, the shift value is less than the two sigma allowance by Regulatory Guide 1.99, Revision 2. 3) The measured 30 ft-lb shift in transition temperature value of the weld metal contained in capsule X is greater than the Regulatory Guide 1.99, Revision 2, prediction. However, the shift value is less than the two sigma allowance by Regulatory Guide 1.99, Revision 2. 4) The measured percent decrease in upper shelf energy for all the surveillance materials of Capsules X contained in the Comanche Peak Unit 2 surveillance program is less than the Regulatory Guide 1.99, Revision 2 predictions. 5) All beltline materials exhibit a more than adequate upper shelf energy level for continued safe plant operation and are predicted to maintain an upper shelf energy greater than 50 ft-lb throughout the current license (36 EFPY) as required by I OCFR50, Appendix G [2]. 6) The Comanche Peak Unit 2 surveillance plate data was found to be "not-credible," while the surveillance weld data was found to be "credible". The crediblity evaluation can be found in Appendix D.
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.
1-1 1
SUMMARY
OF RESULTS The analysis of the reactor vessel materials contained in surveillance Capsule X, the second capsule removed and tested from the Comanche Peak Unit 2 reactor pressure vessel, led to the following conclusions [Note: The Charpy V-notch datapresented in WCAP-1068413 1 and WCAP-14315 141 were based on hand-fit Charpy curves using engineeringjudgment. However, the resultspresentedin this reportare basedon an updatedplotof all capsule data using CVGRAPH, Version 5.0.2, which is a symmetric hyperbolic tangent curve-fittingprogram. Appendix Cpresents the CVGRAPH, Version 5.0.2, Charpy V-notch plots and the programinput data.]:
- Capsule X specimen testing was performed in accordance with I OCFR50, Appendices G and H[21, ASTM Specification El 85-8217]. The methods used to develop the calculated pressure vessel fluence are consistent with the NRC approved methodology described in WCAP-14040-NP-A, Rev. 41"].
- Capsule X received an average fast neutron fluence (E> 1.0 MeV) of 2.20 x 1019 n/cm2 after 8.83 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-7.81F and an irradiated 50 ft-lb transition temperature of 31.51F. This results in a 30 ft-lb transition temperature increase of 1.61F and a 50 ft-lb transition temperature increase of 3.1 F for the longitudinal 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 40.81F and an irradiated 50 ft-lb transition temperature of 94.61F. This results in a 30 ft-lb transition temperature increase of 52.9 0 F and a 50 ft-lb transition temperature increase of 52.51F for the longitudinal oriented specimens.
- Irradiation of the weld metal (heat number 89833) Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of -1.41F and an irradiated 50 ft-lb transition temperature of 26.30F.
This results in a 30 ft-lb transition temperature increase of 48.20 F and a 50 ft-lb transition temperature increase of 26.70 F.
- Irradiation of the weld Heat-Affected-Zone (HAZ) metal Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of -83.31F and an irradiated 50 ft-lb transition temperature of-57.40 F.
This results in a 30 ft-lb transition temperature increase of 26.21F and a 50 ft-lb transition temperature increase of 18.00 F.
- The average upper shelf energy of the intermediate shell plate R3 807-2 (longitudinal orientation) resulted in no energy decrease after irradiation. This results in an irradiated average upper shelf energy of 115 ft-lb for the longitudinal oriented specimens.
- The average upper shelf energy of the Intermediate Shell Plate R3807-2 (transverse orientation) resulted in no energy decrease after irradiation. This results in an irradiated average upper shelf energy of 84 ft-lb for the longitudinal oriented specimens.
Summary of Results
1-2
- The average upper shelf energy of the weld metal Charpy specimens resulted in no energy decrease after irradiation. This results in an irradiated average upper shelf energy of 94 ft-lb for the weld metal specimens.
- The average upper shelf energy of the weld HAZ metal Charpy specimens resulted in no energy decrease after irradiation. This results in an irradiated average upper shelf energy of 116 ft-lb for the weld HAZ metal.
- A comparison, as presented in Table 5-10, of the Comanche Peak Unit 2 reactor vessel surveillance material test results with the Regulatory Guide 1.99, Revision 2l'J predictions led to the following conclusions:
- The measured 30 ft-lb shift in transition temperature value of the intermediate shell plate R3807-2 contained in capsule X (longitudinal) is less than the Regulatory Guide 1.99, Revision 2, prediction.
- The measured 30 ft-lb shift in transition temperature value of the intermediate shell plate R3807-2 contained in capsule X (transverse) is greater than the Regulatory Guide 1.99, Revision 2, prediction. However, the shift value is less than the two sigma allowance by Regulatory Guide 1.99, Revision 2.
- - The measured 30 ft-lb shift in transition temperature value of the weld metal contained in capsule X is greater than the Regulatory Guide 1.99, Revision 2, prediction. However, the shift value is less than the two sigma allowance by Regulatory Guide 1.99, Revision 2.
- 'The measured percent decrease in upper shelf energy for all the surveillance materials of Capsules X contained in the Comanche Peak Unit 2 surveillance program are less than the
'Regulatory Guide 1.99, Revision 2 predictions.,
- All beltline materials exhibit a more than adequate upper shelf energy level for continued safe plant operation and are predicted to maintain an upper shelf energy greater than 50 ft-lb throughout the end of the current license (36 EFPY) as required by 10CFR5O, Appendix G [2]*
- The calculated end-of-license (36 EFPY) neutron fluence (E> 1.0 MeV) at the core midplane for the Comanche Peak Unit 2 reactor vessel using the Regulatory Guide 1.99, Revision 2 attenuation formula (i.e., Equation #3 in the guide) are as follows:,
Calculated: Vessel inner radius* = 2.29 x 10"9 n/cm2 Vessel 1/4 thickness = 1.36 x IO'n/cm2 Vessel 3/4 thickness = 4.84 x 1018 n/cm 2
- Clad/base metal interface.
Summary of Results
2-1 2 INTRODUCTION This report presents the results of the examination of Capsule X, the second capsule removed from the reactor in the continuing surveillance program which monitors the effects of neutron irradiation on the TXU Energy, Comanche Peak Unit 2 reactor pressure vessel materials under actual operating conditions.
The surveillance program for the TXU Energy 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-1 0684, "Texas Utilities Generating Company Comanche Peak Unit No. 2 Reactor Vessel Radiation Surveillance Program" 131 . The surveillance program was planned to cover the 40-year design life of the reactor pressure vessel and was based on ASTM El 85-82, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels."r7l Capsule X was removed from the reactor after 8.83 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 and the post-irradiation data obtained from surveillance capsule X removed from the TXU Energy Comanche Peak Unit 2 reactor vessel and discusses the analysis of the data.
Introduction
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 6]. 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[ 51) or the temperature 601F less than the 50 ft-lb (and 35-mil lateral expansion) temperature as determined from Charpy specimens oriented perpendicular (transverse) to the major working direction of the plate. The RTNDT of a given material is used to index that material to a reference stress intensity factor curve (K1 , curve) which appears in Appendix G to the ASME Codel6l. The K1, curve is a lower bound of static fracture toughness results obtained from several heats of pressure vessel steel. When a given material is indexed to the K1, curve, allowable stress intensity factors can be obtained for this material as a function of temperature. Allowable operating limits can then be determined using these allowable stress intensity factors.
RTNDT and, in turn, the operating limits of nuclear power plants can be adjusted to account for the effects of radiation on the reactor vessel material properties. The changes in mechanical properties of a given reactor pressure vessel steel, due to irradiation, can be monitored by a reactor vessel surveillance program, such as the Comanche Peak Unit 2 reactor vessel radiation surveillance programt 31, in which a surveillance capsule is periodically removed from the operating nuclear reactor and the encapsulated specimens tested. The increase in the average Charpy V-notch 30 ft-lb temperature (ARTNDT) due to irradiation is added to the initial RTNDT, along with a margin (M) to cover uncertainties, to adjust the RTNDT (ART) for radiation embrittlement. This ART (RTNDT initial + M + ARTNDT) is used to index the material to the Kic curve and, in turn, to set operating limits for the nuclear power plant that take into account the effects of irradiation on the reactor vessel materials.
Background
o.-
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 start-up. The six capsules were positioned in the reactor vessel between the thermal shield 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 intermediate shell plate R3807-2, weld metal fabricated with 3/16-inch Mil B-4 weld filler wire (heat 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. The surveillance weld was fabricated with the same heat of weld wire as all beltline region welds and is therefore representative of all of the reactor vessel beltline region welds.
Capsule X was removed after 8.83 effective full power years (EFPY) of plant operation. This capsule contained Charpy V-notch, tensile, and 1/2T-CT fracture mechanics specimens made from Intermediate Shell Plate R3807-2 and submerged arc weld metal representative of all the reactor vessel beltline region weld seams. In addition, this capsule contained Charpy V-notch specimens from the weld Heat-Affected-Zone (HAZ) metal of 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 1/4 and 3 thickness location of the plate after performing a simulated post-weld stress-relieved treatment on the test material and also 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 the 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 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 with the long dimension of the specimen perpendicular to the weld direction.
Compact tension test specimens from intermediate shell plate R3 807-2 were machined in the longitudinal and transverse orientations. Compact tension test specimens from the weld metal were machined perpendicular to the weld direction with the notch oriented in the direction of welding. All specimens were fatigue pre-cracked according to ASTM E399.
Description of Program
4-2 The chemical composition and heat treatment of the unirradiated vessel and surveillance materials are presented in Tables 4-1 through 4-4, respectively. The data in Tables 4-1 through 4-4 was obtained from the unirradiated surveillance program report, WCAP-10684133, Appendix A.
Capsule X contained dosimeter wires of pure iron, copper, nickel, and aluminum-0.1 5 weight percent cobalt (cadmium-shielded and unshielded). In addition, cadmium shielded dosimeters ofneptunium (NpP 7) and uranium (U2 3 8) were placed in the capsule to measure the integrated flux at specific neutron energy levels.
The capsule contained thermal monitors made from two low-melting-point eutectic alloys and sealed in Pyrex tubes. These thermal monitors were used to define the maximum temperature attained by the test specimens during irradiation. The composition of the two eutectic alloys and their melting points are as follows:
2.5% Ag, 97.5% Pb Melting Point: 579 0 F (304C) -
1.5% Ag, 1.0% Sn, 97.5% Pb Melting Point: 5901F (31 00 C)
The arrangement of the various mechanical specimens, dosimeters and thermal monitors contained in Capsule X is shown in Figure 4-2.
Description of ProgramI
4-3 Table 4-1 Chemical Composition (Wt%) of the Comanche PeakUnit 2 ReactorVessel Intermediate Shell Plates (Unirradiated)(')
Element Intermediate Shell Intermediate Shell Intermediate Shell Intermediate Shell Plate R3807-1(b) Plate R3807-2bc) Plate R3 807 -2(bcd) Plate R3807-3(b C 0.21 0.22 0.22 0.22 Mn 1.42 1.40 1.36 1.30 P 0.006 0.007 0.014 0.007 S 0.015 0.016 0.014 0.009 Si 0.25 0.24 0.25 0.19 Ni 0.64 0.64 0.62 0.60 Mo 0.60 0.59 0.58 0.58 Cr 0.05 0.04 0.056 0.06 Cu 0.06 0.06 0.065 0.05 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[ 3 1 and duplicated herein for completeness.
(b) Chemical Analysis by Combustion Engineering, Inc.
(c) Surveillance program test plate.
(d) Chemical Analysis by Westinghouse.
Description of Program
4-4 Table 4-2 Chemical Composition (wt%) of the Comanche Peak Unit 2 Reactor Vessel Lower Shell Plates (Unirradiated)(' b)
Element Lower Shell Plate Lower Shell Plate Lower Shell Plate R3816-1 R3816-2 R3816-35' C 0.23 0.23 -0.22 Mn 1.48 1.48 1.50 P 0.001 0.002 0.008 S 0.004 -0.012 0.008 Si 0.19 0.21 0.19 Ni 0.59 0.65 0.63 Mo 0.49 0.50 0.52 Cr 0.03 0.03 0.04 Cu 0.05 0.03 0.04 Al 0.026 0.026 0.018 Co 0.02 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 N2 0.028 0.014 0.014 B <0.001 <0.001 <0.001 Notes:
(a) Data obtained from WCAP-106843 1 and duplicated herein for completeness.
(b) Chemical Analysis by Combustion Engineering, Inc.
Description of Program
4-5 Table 4-3 Chemical Composition (wt%) of the Comanche Peak Unit 2 Reactor Vessel Weld Materials(Unirradiated)(a) l Intermediate and Lower Shell Longitudinal Closing Girth Weld Weld Seams Seam Element Wire Flux Test Sample Production Wire Flux Test Surveillance Weldment Weld Sampleb) Weld(bt') Seam No. Weld Sample(b) (Identical to the Closing 101-142A Girth Seam Weld)(d)
C 0.16 0.16 0.088 0.11 Mn 1.32 1.24 1.33 1.37 P 0.005 0.004 0.004 0.011 S 0.011 0.009 0.010 0.014 Si 0.16 0.19 0.51 0.49 Ni 0.05 0.08 0.03 0.072 Mo 0.54 0.59 0.54 0.59 Cr 0.02 0.02 0.03 0.058 Cu 0.07 0.05 0.05 0.030 Al - 0.004 0.006 Co - 0.011 0.008 Pb - <0.001 _ 0.001 W - 0.01 _ <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-10684[ 3 3and duplicated herein for completeness.
(b) Chemical Analysis by Combustion Engineering, Inc.
(c) Actual Beitline production weld chemistry (Lower Shell Plate Seam No. 101-142A).
(d) Chemical Analysis by Westinghouse of the Surveillance Program Test Weldment (Test Plate "D") supplied by Combustion Engineering, Inc. (Analysis results contain an error band of+/- 10%. Standards are traceable to the National Institute of Standards & Technology and are run with each group of samples.).
Description of Program
4-6 Table 4-4 Heat Treatment History of the Comanche Peak Unit 2 Reactor Vessel Materials(a)
Material Temperature (IF) Time (hours) Cooling Intermediate Shell Plates: Austenitized @ 4 Water-Quench R3807-1 1600 +/-25(871IC)
R3807-2 ' Tempered @ 4 Air-cooled R3807-3 ' 1225 i25 (6630C) ' iX lStress Relieved @ - 19.25() Furnace Cooled 1150 +/-50(621'C)
Lower Shell Plates: Austenitized @ 4 Water-Quench R3816-1 1600 +/-25(871OC)
R3816-2 Tempered @ 4 Air-cooled R3816-3 1225 +/-25 (663C)'
- Stress Relieved @ - 14.5(b) -Furnace Cooled l _ _ __ 1150 +/- 50 (621 0C) -
Intermediate Shell Longitudinal 19.25° Furnace Cooled Seam Welds Stress Relieved @
Lower Shell Longitudinal Seam 1150 +/-50(621 0C) 14.5() Furnace Cooled Welds Intermediate to Lower Shell Local Stress Relieved @ 8.0 Furnace Cooled Girth Seam Weld 1150 +/- 50 (6210 C)
Surveillance Program Test Material Surveillance Program Test Plate - Post Weld Stress Relief 8.5(c) Furnace Cooled "D" (Representative of Closing 1150 +/- 50(621 OC)
Girth Seam)
Notes:
(a) Data obtained from WCAP-10684131 and duplicated herein for completeness. Likens Steel Company, Marrel Freres and Combustion Engineering, Inc. Certification Reports.
(b) Stress Relief includes the intermediate to lower shell closing girth seam post weld heat treatment.
(c) The stress relief heat treatment received by the surveillance test weldment has been simulated.
Description of Program
4-7 0*
-REACTOR VESSEL (301.5*) Z hPSULE U (58.5*)
V (61) 270* - - 90 (241 *) y W (121.50)
(238.5). X REACTOR VESSEL 1800 PLAN VIEW VESSEL WALL CAPSULE
- ASSEMBLY
_ CORE MIOPLANE
-NEUTRON PAD
-CORE BARREL ELEVATION VIEW Figure 4-1 Arrangement of Surveillance Capsules in the Comanche Peak Unit 2 Reactor Vessel Description of Program
4-8 LEGEND: CL - INTERMEDIATE SHELL PLATE R3807-2 (LONGITUDINAL)
CT - INTERMEDIATE SHELL PLATE R3807-2 (TRANSVERSE) cu Al-.151C0 CW - WELD METAL (HEAT # 89833)
CH - HEAT AFFECTED ZONE MATERIAL Fe -
579'F 33 ii!II MR, TOR hgPs. I -l- lSZCQ (Cd)
Large Tensile Compact Compact Charpy Charpy Charpy Compact
[ CW12 7 CW60 j CH60 CW57 CH57 l CW54 CH54
[CWII CW[O CW16
[
CW1 4 CW13 CW59 CW58 CH59 CH58 CW56 CW55 CH56 CH55 CW53 C5l CH53 CH52 CL16CL15 L L_
p TOP OF VESSEL CENTER Np2 7 Compact Charpy Charpy Dosimeter Tensile Charpy Charpy
- CWSI CHIS I f -C-L-12 l l CT60 l l.C6 CT57 l CL57l CL14 CL13 CWS0 CH50 516 CLIU! I. l . I CT56 I CL56
.CW49 CH49 CLIO I CTs8 CL58 CT55 I CL55 CENTER _ BOTTOM OF VESSEL CU .. . Al-152Co MOITR II 1l. -l~.see (Cd) is I Charpy Charpy Charpy Compact Compact Tensile CT54 L4llC5 I I CLS5I1 lCT53 I CL53 lI TS CL50 lCT16 lCT5 CT14 lCT13 l [ J l CT2CL2 1 1 CT4 1I CL49 L~LJ ITLi Figure 4-2 Capsule X Diagram Showing The Location of Specimens, Thermal Monitors, and Dosimeters Description of Program
5-1 5 TESTING OF SPECIMENS FROM CAPSULE X 5.1 OVERVIEW The post-irradiation mechanical testing of the Charpy V-notch impact specimens and tensile specimens was performed in the Remote Metallographic Facility (RMF) at the Westinghouse Science and Technology Department. Testing was performed in accordance with 10CFR50, Appendices G and H[21, ASTM Specification El 85-82w71, and Westinghouse Procedure RMF 8402183, Revision 2 as modified by Westinghouse RMF Procedures 8102191, Revision 1, and 8103(10], Revision 1.
Upon receipt of the capsule at the hot cell laboratory, the specimens and spacer blocks were carefully removed, inspected for identification number, and checked against the master list in WCAP-10684['3. No discrepancies were found.
Examination of the two low-melting point 5791F (3041C) and 5901F (310 0 C) eutectic alloys indicated no melting of either type of thermal monitor. Based on this examination, the maximum temperature to which the test specimens were exposed was less than 5791F (3040 C).
The Charpy impact tests were performed per ASTM Specification E23-02a [12] and RMF Procedure 8103, Rev. 1, on a Tinius-Olsen Model 74, 358J machine. The tup (striker) of the Charpy impact test machine is instrumented with an Instron Dynatup Impulse instrumentation system, feeding information into an IBM compatible computer. With this system, load-time and energy-time signals can be recorded in addition to the standard measurement of Charpy energy (ED). From the load-time curve (Appendix B),
the load of general yielding (PGy), the time to general yielding (try), 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), and the load at which fast fracture terminated 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:
ay= (PGy *L) I[B (W_ a)2 *C] I where: L distance between the specimen supports in the impact 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 (f), 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 + =
450 and p = 0.010 inch, Equation 1 is valid with C = 1.21. Therefore, (for L = 4W),
Testing of Specimens from Capsule X
5-2 ay=(Poy*L)/[B * (W-a) 2
- 1.21]= (3.305 *PGY*.W)/fB.*(W-a)2J (2)
For the Charpy specimen, B = 0.394 inch, W = 0.394 inch and a = 0.079 inch. Equation 2 then reduces to:
= 333 *GY (3) where cry is in units of psi and PGy is in units of lbs. The flow stress was calculated from the average of the yield and maximum loads, also using the three-point bend formula.
The 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. (4)
Percent shear was determined from post-fracture photographs using the ratio-of-areas methods in compliance with ASTM Specification E23-02a~l" and A370-97a' "]. 2 The lateral expansion was measured using a dial gage rig similar to that shown in the same specification.
Tensile tests were performed on a 20,000-pound Instron, split-console test machine (Model 115) per ASTM Specification E8-01 [3" and E21-92 (1998)114J, and Procedure RMF 8102, Rev. 1. All pull rods, grips, and pins were made of Inconel 718. The upper pull rod was connected through a universal joint to improve axiality of loading. The tests were conducted at a constant crosshead speed of 0.05 inches per minute throughout the test.
Extension measurements were made with a linear variable displacement transducer extensometer. The extensometer knife-edges were spring-loaded to the specimen and operated through specimen failure.
The extensometer gage length was 1.00 inch. The extensometer is rated as Class B-2 per ASTM E83-93115]
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. Because of the difficulty in remotely attaching a thermocouple directly to the specimen, the following procedure was used to monitor specimen temperatures. Chromel-Alumel thermocouples were positioned at the center and at each end of the gage section of a dummy specimen and in each tensile machine griper. In the test configuration, with a slight load on the specimen, a plot of specimen temperature versus upper and lower tensile machine griper and controller temperatures was developed over the range from room temperature to 5501F. During the actual testing, the grip temperatures were used to obtain desired specimen temperatures. Experiments have indicated that this method is accurate to +20 F.
The yield load, ultimate load, fracture load, total elongation, and uniform elongation were determined directly from the load-extension curve. The yield strength, ultimate strength, and fracture strength were calculated using the original cross-sectional area. The final diameter and final gage length were determined from post-fracture photographs. The fracture area used to calculate the fracture stress (true stress at fracture) and percent reduction in area was computed using the final diameter measurement.
Testing of Specimens from Capsule X
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 X, which received a fluence of 2.20 x 1019 n/cm2(E> 1.0 MeV) in 8.83 EFPY of operation, are presented in Tables 5-1 through 5-8 and are compared with unirradiated resultsE1 as shown in Figures 5-1 through 5-12.
The transition temperature increases and upper shelf energy decreases for the Capsule X materials are summarized in Table 5-9 and led to the following results:
- Capsule X received an average fast neutron fluence (E> 1.0 MeV) of 2.20 x 1019 n/cm 2 after 8.83 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-7.8IF and an irradiated 50 ft-lb transition temperature of 31.51F. This results in a 30 ft-lb transition temperature increase of l.61F and a 50 ft-lb transition temperature increase of 3.1 IF for the longitudinal 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 40.81F and an irradiated 50 ft-lb transition temperature of 94.61F. This results in a 30 ft-lb transition temperature increase of 52.90 F and a 50 ft-lb transition temperature increase of 52.50 F for the longitudinal oriented specimens.
- Irradiation of the weld metal (heat number 89833) Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of -1.41F and an irradiated 50 ft-lb transition temperature of 26.31F.
This results in a 30 ft-lb transition temperature increase of 48.20 F and a 50 ft-lb transition temperature increase of 26.71F.
- Irradiation of the weld Heat-Affected-Zone (IAZ) metal Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of-83.30 F and an irradiated 50 ft-lb transition temperature of-57.40 F.
This results in a 30 ft-lb transition temperature increase of 26.21F and a 50 ft-lb transition temperature increase of 18.0 0 F.
- The average upper shelf energy of the intermediate shell plate R3807-2 (longitudinal orientation) resulted in no energy decrease after irradiation. This results in an irradiated average upper shelf energy of 115 ft-lb for the longitudinal oriented specimens.
- The average upper shelf energy of the intermediate shell plate R3807-2 (transverse orientation) resulted in no energy decrease after irradiation. This results in an irradiated average upper shelf energy of 84 ft-lb for the longitudinal oriented specimens.
Testing of Specimens from Capsule X
54
- The average upper shelf energy of the weld metal Charpy specimens resulted in no energy decrease after irradiation. This results in an irradiated average upper shelf energy of J 94 ft-lb for the weld metal specimens.
- The average upper shelf energy of the weld HAZ metal Charpy specimens resulted in no energy decrease after irradiation. This results in an irradiated average upper shelf energy of 116 ft-lb for the weld HAZ metal.
- A comparison, as presented in Table 5-10, of the Comanche Peak Unit 2 reactor vessel surveillance material test results with the Regulatory Guide 1.99, Revision 2t1] predictions led to the following conclusions:
- The measured 30 ft-lb shift in transition temperature value of the intermediate shell plate R3807-2 contained in capsule X (longitudinal) is less than the Regulatory Guide 1.99, Revision 2, prediction.
- The measured 30 ft-lb shift in transition temperature value of the intermediate shell plate R3807-2 contained in capsule X (transverse) is greater than the Regulatory Guide 1.99, Revision 2, prediction. However, the shift value is less than the two sigma allowance by Regulatory Guide 1.99, Revision 2.
- The measured 30 ft-lb shift in transition temperature value of the weld metal contained in capsule X is greater than the Regulatory Guide 1.99, Revision 2, prediction. However, the shift value is less than the two sigma allowance by Regulatory Guide 1.99, Revision 2.
- The measured percent decrease in upper shelf energy for all the surveillance materials of Capsules X contained in the Comanche Peak Unit 2 surveillance program are less than the Regulatory Guide 1.99, Revision 2 predictions.
- All beltline materials exhibit a more than adequate upper shelf energy level for continued safe plant operation and are predicted to maintain an upper shelf energy greater than 50 ft-lb throughout the end of the current license (36 EFPY) as required by 10CFR50, Appendix G A2.
- The fracture appearance of each irradiated Charpy specimen from the various surveillance Capsule X materials is shown in Figures 5-13 through 5-16 and shows an increasingly ductile or tougher appearance with increasing test temperature.
- The load-time records for individual instrumented Charpy specimen tests are shown in Appendix B.
- The Charpy V-notch data presented in WCAP-10684P 1 and WCAP-14315 141 were based on hand-fit Charpy curves using engineering judgment. However, the results presented in this report are based on an updated plot of all capsule data using CVGRAPH, Version 5.0.2, which is a symmetric hyperbolic tangent curve-fitting program.' Appendix C presents the CVGRAPH, Version 5.0.2, Charpy V-notch plots and the program input data.
Testing of Specimens from Capsule X
5-5 5.3 TENSILE TEST RESULTS The results of the tensile tests performed on the various materials contained in Capsule X irradiated to 2.20 x 10'9 n/cm2 (E> 1.0 MeV) are presented in Table 5-11 and are compared with unirradiated results14 3 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 2.20 x 1019 n/cm 2 (E> 1.0 MeV) caused approximately a 4 to 8 ksi increase in the 0.2 percent offset yield strength and approximately a 5 to 7 ksi increase in the ultimate tensile strength when compared to unirradiated data14 ]. See Figure 5-17.
The results of the tensile tests performed on the intermediate shell plate R3807-2 (transverse orientation) indicated that irradiation to 2.20 x 10'9 n/cm 2 (E> 1.0 MeV) caused approximately a I to 7 ksi increase in the 0.2 percent offset yield strength and approximately a 4 to 7 ksi increase in the ultimate tensile strength when compared to unirradiated datal4l. See Figure 5-18.
The results of the tensile tests performed on the surveillance weld metal indicated that irradiation to 2.20 x 10'9 n/cm2 (E> 1.0 MeV) caused approximately a 5 to 7 ksi increase in the 0.2 percent offset yield strength and approximately a 4 to 6 ksi increase in the ultimate tensile strength when compared to unirradiated data"4]. See Figure 5-19.
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 Park Hot Cell facility.
Testing of Specimens from Capsule X
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 2.20 x 1019 n/cm 2 (E> 1.0 MeV) (Longitudinal Orientation)
Sample l Temperature Impact Energy Lateral Expansion Shear Number 'IF IC ft-lbs Joules mils mm l CL52 -50 -46 6 8 1 0.03 CL60 -40 -40 . 10 .14: 1 4 0.10 5 CL59 -25 -32 33 45 20 0.51 10 CL57 -25 -32 35 47 .19 0.48 10 CL58 -10 -23 *28 38 16 0.41 10 CL53 25 4 33 45 23 0.58 20 CL46 25 -4. 52 71 32 0.81 25 CL54 40 4 58 79 39 0.99 30 CL47 60 16 69 94 43 1.09 S0 CL51 75 24 82 111 46 1.17 55 CL48 110 43 79 107 56 1.42 60 CL49 150 66 105 142 69 1.75 80 CLS0 175 79 113 153 71 1.80 100 CL56 200 93 121 164 79 2.01 100 CL55 225 107 127 172 74 1.88 100 Testing of Specimens from Capsule X
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 2.20 x 1019 n/cm 2 (E> 1.0 MeV) (Transverse Orientation)
Sample Temperature ImpactEnergy Lateral Expansion Shear Number OF j C ft-lbs Joules mils J mm CT54 -100 -73 3 4 0 0.00 2 CT55 -50 -46 9 12 4 0.10 5 CT60 0 -18 23 31 14 0.36 15 CT47 25 -4 28 38 19 0.48 25 CT53 50 10 35 47 24 0.61 30 CTS1 60 16 37 50 25 0.64 40 CT59 75 24 45 61 32 0.81 45 CT58 100 38 45 61 33 0.84 45 CT49 125 52 57 77 42 1.07 55 CT48 150 66 64 87 50 1.27 80 CT46 175 79 73 99 54 1.37 85 CT52 200 93 88 119 59 1.50 100 CT50 225 107 92 125 68 1.73 100 CT56 250 121 93 126 68 1.73 100 CT57 275 135 90 122 65 1.65 100 Testing of Specimens from Capsule X
5-8 Table 5-3 Charpy V-notch Data for the Comanche Peak Unit 2 Surveillance Weld Metal Irradiated to a Fluence of 2.20 x iO" nlcm 2 (E> 1.0 MeV) Metal _ l Sample Temperature Impact Energy Lateral Expansion Shear Number OF'C ft-lbs Joules mils mm %
CW48 -100 -73 6 8 0 0.00 5 CW47 -50 -46 8 .11 4 0.10 20 CW52 -25 -32 14 .19 10 0.25 20 CW46 0 -18 27 37 22 0.56 30 CW57 25 -4 67 91 -49 1.24 '60 CW49 25 4 41 56 35 0.89 55 CW51 50 10 62 84 47 1.19 65 CW60 75 24 94 127 63 1.60 85 CW53 75 24 69 94 52 1.32 75 CW55 135 57 89 121 64 1.63 90 CW50 175 79 81 110 65 1.65 95 CW54 200 93 83 113 64 1.63 100 CW56 200 93 92 125 68 1.73 100 CW58 225 107 106 144 74 1.88 100 250 121 102 138 73 1.85 100 CW59 Testing of Specimens from Capsule X
5-9 Table 54 Charpy V-notch Data for the Comanche Peak Unit 2 Heat-Affected-Zone (HAZ)
Material Irradiated to a Fluence of 2.20 x 1019 nlcm 2 (E> 1.0 MeV)
Sample Temperature Impact Energy Lateral Expansion Shear Number OC Ft-lbs Joules mils mm CH53 -175 -115 4 5 0 0.00 2 CH58 -130 -90 27 37 10 0.25 10 CH47 -110 -79 28 38 7 0.18 10 CH57 -100 -73 21 28 7 0.18 15 CH60 -75 -59 34 46 18 0.46 40 CH56 -50 -46 55 75 30 0.76 30 CH46 -35 -37 40 54 19 0.48 45 CH49 -25 -32 63 85 39 0.99 35 CH50 -10 -23 137 186 70 1.78 100 CH51 25 -4 107 145 63 1.60 100 CH52 75 24 104 141 58 1.47 100 CH55 100 38 114 155 67 1.70 100 CH48 125 52 129 175 74 1.88 100 CH59 125 52 121 164 68 1.73 100 CH54 150 66 102 138 56 1.42 100 Testing of Specimens from Capsule X
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 2.20 x 1019 n/cm 2 (E>1.0 MeV) (Longitudinal Orientation) _ :
Charpy Normalized Energies Yield Time to Fast Test Energy (ft-lblin2) Load Time to Max. Max. Fract. Arrest Yield Flow Sample Temp. Charpy Max. Prop. PGY Yield tcy Load PM tM Load PF Load PA Stress Stress No. C°]) (ft-lb) ED/A Em/A Ep/A (lb) (mnsec) -(lb) (msec) (lb) , '(lb) cryI(W) (ksi)
CLS2 -50 6 48 29 19 3250 0.15 3250 0.15 3247 0 108 108 CL60 -40 10 81 45 35 4098 0.17 4157 0.18 4149 0 136 137 CL59 -25 33 266 228 38 3727 0.14 4834 0.48 4834 0 124 143 CL57. -25 35 282 249 33 3817 0.15 4912 0.51 4896 0 127 145 CL58 -10 28 226 194 31 3706 0.15 4674 0.43 4674 0 123 140 CL53 25 33 266 203 63 3468 0.16 4597 0.47 4591 401 115 134 CL46 25 52 419 333 86 3608 0.15 4808 0.67 4751 0 120 140 CL54 40 58 467 346 121 3570 0.16 4765 - 0.70 4673 86' -119 139 CL47 60 69 556 337 219 3532 0.15 4725, 0.69 4663 757 118 137 CL51 75 82 661 347 314 3606 0.15 4761 '0.69 4488 914' 120 139 CL48 110 79 637 320 317 3322 0.14 4569 ' 0.67 3984 1369 III 131 CL49 150 105 846 319 527 3225 0.15 4483 0.69 3422 1787 107 128 CL50 175 113 910 302 608 3129 0.14 4394 0.67 n/a. n/a 104 125 CL56 200 121 975 308 667 3162 0.14 4430 0.68 n/a n/a . 105 126 CL55 225 127 1023 309 714 3105 0.14 4504 '0.67 n/a n/a 103 127 Testing of Specimens from Capsule X
5-1I Table 5-6 Instrumented Charpy Impact Test Results for the Comanche Peak Unit 2 Intermediate Shell Plate R3807-2 Irradiated to a Fluence of 2.20 x 1019 n/cm2 (E>1.0 MeV) (Transverse Orientation)
Charpy Normalized Energies Yield Time to Fast Test Energy (rt-lbin2) Load Time to Max. Max. Fract. Arrest Yield Flow Sample Temp. ED Charpy Max. Prop. PGY Yield tCy Load PM tM Load PF Load PA Stress Stress No. (OF) (ft-lb) ED/A EM/A Ep/A (lb) (msec) (lb) (msec) (lb) (lb) ay (ksi) (ksi)
CT54 -100 3 24 8 16 1030 0.08 1211 0.10 1208 0 34 37 CT55 -50 9 73 40 32 3951 0.15 4029 0.16 4021 0 132 133 CT60 0 23 185 67 118 3602 0.14 4452 0.21 4379 0 120 134 CT47 25 28 226 153 73 3571 0.15 4442 0.37 4436 5 119 133 CT53 50 35 282 204 78 3451 0.14 4533 0.46 4533 186 115 133 CT51 60 37 298 198 100 3371 0.14 4486 0.45 4473 627 112 131 CT59 75 45 363 219 144 3594 0.14 4795 0.46 4755 931 120 140 CT58 100 45 363 222 140 3359 0.14 4552 0.49 4475 1511 112 132 CT49 125 57 459 211 248 3325 0.14 4353 0.49 3960 1532 111 128 CT48 150 64 516 210 305 3240 0.16 4295 0.51 4278 2838 108 125 CT46 175 73 588 214 374 3193 0.14 4258 0.50 3752 2148 106 124 CT52 200 88 709 302 407 3135 0.14 4311 0.67 n/a n/a 104 124 CT50 225 92 741 300 441 3047 0.14 4399 0.67 n/a n/a 101 124 CT56 250 93 749 223 526 3122 0.14 4393 0.52 n/a n/a 104 125 CT57 275 90 725 288 437 2998 0.14 4259 0.65 n/a n/a 100 121 Testing of Specimens from Capsule X
I 5-12 5-7 Table Instrumented Charpy I mpac t TestResults for the Com Peak Unit 2 Surveillance Weld Metal anche 2 (E>1.0 MeV) -_-
Irradiated to a Fluence of 2.20 x 10'9 n/cm __
Charpy Normalized Energies Max. Max. Fract. Arrest Yield Flow Test ergy (ft-lb/ En2) Load Time to Max. Prop. PGY Yield tGy Load Pm tM Load PI? Load PA Stress cy Stress Sample Temp. E D Charpy 0 EJ /A Ep/A (lb) (msee) (lb) (msec) (Ibb)((lb (ksi) (ksi)
No. ( F) (ft-lb) 48 24 24 2950 0.14 2950 0.14 2945 0 98 98 CW48 -100 6 21 44 2339 0.11 2476 0.13 2476 145 78 80 CW47 -50 8 64 14 113 54 59 3895 0.15 4330 0.19 4330 0 130 137 CW52 -25 218 67 151 3543 0.14 4325 0.21 4268 574 118 131 CW46 0 27 540 245 294 3606 0.15 4644 0.53 4264 938 120 137 CW57 25 67 330 182 148 3419 0.14 4403 0.42 4374 1416 114 130 CW49 25 41 62 500s 241 258 3461 0.14 4531 0.53 4467 '1979 115 133 CW51 50 757 339 418 3613 0.15 4817 0.67 4094 2373 120 140 CW60 75 94 69 556 234 322 3467 0.14 4513 0.51 4255 2397 115 133 CW53 75 89 717 316 401 3348 0.15 4410 0.68 3315 2302 111 129 CW55 135 653 295 357 3140 0.14 4192 0.66 3371 2529 105 122 CW50 175 81 83 669 295 373 3120 0.14 4216 0.66 n/a n/a 104 122 CWs4 200 92 741 302 440 3179 0.14 4243 0.68 n/a n/a 106 124 CW56 200 106 854 317 537 3289 0.14 4489 0.67 n/a n/a 110 130 CW58 225 CW59 250 102 822 311 511 2910 0.16 4376 0.70 n/a n/a 97 121 Testing of Specimens from Capsule X
5-13 M
Table 58 Instrumented Charpy Impact Test Results for the Comanche Peak Unit 2 Heat-Affected-Zone (HEAZ) Metal Irradiated to a Fluence of 2.20 x 101 n/cmn (E>1.0 MeV)
Charpy Normalized Energies Yield Time to Fast Test Encrgy (*-lb/in) Load Time to MaX. Max. Fract. Arrest Yield Flow Sample Temp. ED Charpy Max. Prop. PcY Yield tcy Load PM tM Load PF Load Stress ay Stress No. (OF) (ft-lb) E0/A EM/A Ep/A (lb) (msec) (lb) (msec) (lb) PA (lb) (ksi) (ksi)
CH53 -175 4 32 18 14 2321 0.12 2321 0.12 2321 0 77 77 CH58 -130 27 218 84 134 4520 0.15 5443 0.22 5249 0 151 166 CH47 -110 28 226 81 145 4523 0.15 5298 0.22 5203 0 151 164 CH57 -100 21 169 76 94 4247 0.15 5079 0.22 4837 0 141 155 CH60 -75 34 274 82 192 4069 0.16 5010 0.23 4848 1411 136 151 CH56 -50 55 443 260 183 3943 0.15 4971 0.52 4809 0 131 148 CH46 -35 40 322 70 253 4239 0.15 4901 0.21 4809 1337 141 152 CH49 -25 63 508 267 241 4026 0.15 5022 0.52 4782 145 134 151 CH50 -10 137 1104 366 737 3949 0.15 5062 0.69 n/a n/a 132 150 CHI51 25 107 862 251 611 3791 0.15 4815 0.52 n/a n/a 126 143 CH52 75 104 838 254 584 3717 0.15 4920 0.52 n/a n/a 124 144 CH55 100 114 919 334 585 3464 0.14 4707 0.68 n/a n/a 115 136 CH48 125 129 1039 337 703 3456 0.14 4716 0.69 n/a n/a 115 136 CH59 125 121 975 327 648 3543 0.15 4614 0.68 n/a n/a 118 136 CH54 150 102 822 315 507 3374 0.14 4549 0.66 n/a n/a 112 132 Testing of Specimens from Capsule X
5-14 Table 5-9 Effect of Irradiation to 2.20 x 1019 n/cm 2 (E>1.0 MeV) on the Capsule X Notch Toughness Properties of the Comanche Peak Unit 2 Reactor Vessel Surveillance Materials Average 30 (ft-lb)(t ) Average 35 mil Lateral(b) Average 50 ft-lbt ) Average Energy Absorption(9)
Material Transition Temperature (IF) Expansion Temperature (0F) Transition Temperature ('IF) at Full Shear (ft-lb)
Unirradiated Irradiated AT Unirradiated Irradiated AT Unirradiated Irradiated AT Unirradiated Irradiated AE Intermediate Shell -9.4 -7.8 1.6 33.4 42.2 8.8 28.4 31.5 3.1 115 120 +5 Plate R3807-2 (Longitudinal)
Intermediate Shell -12.1 40.8 52.9 39.1 95.6 56.5 42.1 94.6 52.5 84 91 s +7 Plate R3807-2 (Transverse)
Weld Metal -49.6 -1.4 48.2 0.7 20.3 19.6 -0.4 26.3 26.7 94 96 +2 (Heat # 89833)
HAZ Metal -109.5 -83.3 26.2 -48.9 -37.8 11.1 -75.4 -57.4 18.0 116 116 0
- a. "Average" is defined as the value read from the curve fit through the data points of the Charpy tests (see Figures 5-1, 54, 5-7 and 5-10).
- b. "Average" is defined as the value read from the curve fit through the data points of the Charpy tests (see Figures 5-2, 5-5, 5-8 and 5-1 1).
Testing of Specimens from Capsule X
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 i ;
l 30 ft-lb Transition -Upper Shelf Energy Temperature Shift Decrease Material Capsule Fluence 8 *Predicted Measured Predicted Measured (X 1019 n/cm 2, (of() (a) (%F) (% ) (%)(c)
E > 1.O MeV)
Intermediate Shell U 0.315 25.3 1.6 14.5 0 Plate R3807-2 (Longitudinal) X 2.20 44.8 1.6 23 0 Intermediate Shell U 0.315 25.3 23.4 14.5 0 Plate R3807-2 (Transverse) X 2.20 44.8 52.9 23 0 Surveillance Program U 0.315 20.7 3.6 14.5 10 Weld Metal X 2.20 36.7 48.2 23 0 Heat Affected Zone U 0.315 -- _ O.O0 --- 0 Material X 2.20 --- 26.2 --- 0
-Notes:
a) Based on Regulatory Guide 1.99, Revision 2, methodology using the mean weight percent values of copper and nickel of the surveillance material.
b) Calculated using measured Charpy data plotted using CVGRAPH, Version 5.0.2 (See'Appendix C) c) Values are based on the definition of upper shelf energy given in ASTM El 85-82.
d) The fluence values presented here are the calculated values, not the best estimate values.
e) Due to the scatter in the Capsule U HAZ Charpy test results, a true Hyperbolic Tangent Curve fit resulted in AT30 values of-13.2 0F when compared to unirradiated Charpy test data. Physically this should not happen.
Hence, based on engineering judgment a value of 0 0F will be report here.
Testing of Specimens from Capsule X
5-16 Table 5-11 Tensile Properties of the Comanche Peak Unit 2 Capsule X Reactor Vessel Surveillance Materials Irradiated to 2.20 x 1019 n/cm 2 (E> 1.0 MeV)
Material Sample Test 0.2% Ultimate Fracture Fracture Fracture Uniform Total Reduction Number Temp. Yield Strength Load Stress (ksi) Strength Elongation Elongation in Area (f) Strength (ksi) (kip) (ksi) (%) (%) (%)
._ (ksi)
Inter. Shell Plate CL-10 75 74.4 95.2 3.00 184.7 61.1 11.0 25.4 67 R3807-2 CL- 1 300 68.8 88.2 2.80 172.4 57.0 10.3 23.6 67 (Longiludinat)
CL-12 550 64.2 91.1 3.15 166.5 64.1 10.0 21.3 62 Inter. Shell Plate CT-lI 75 68.2 94.7 3.15 149.1 64.2 12.0 24.6 57 R3807-2 CT-10 300 67.7 86.8 2.88 152.4 58.7 11.3 23.5 62 (Transverse)
CT-12 550 63.7 90.1 3.16 127.7 64.4 10.0 20.0 50 Weld Metal CW-12 75 75.4 90.5 2.98 178.0 60.8 10.5 24.7 66 CW-I1 300 67.7 83.4 2.81 157.7 57.2 9.8 22.5 64 CW-10 550 68.8 88.7 3.15 157.4 64.2 9.7 21.6 59 Testing of Specimens from Capsule X
5-17 INTERMEDIATE SHELL PLATE R3807-2 (LONGITUDINAL ORIENTATION)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03117/2004 01:54 PM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat #
1 Comanche Peak 2 UNIRR SAS33B I LT
- C5522-2 2 Comanche Peak 2 U SA533B I LT C5522-2 3 Comanche Peak 2 x SA533B1 LT C5522-2 300 250 8, 200 1
0 0
It El 150 w 0 z
> 100 0
50 0
0 I
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F
° Set 1 1 Set2 ° Set3 Results Curve Fluence LSE USE d-USE T @30 d-T @30 T @50 d-T @50 I 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 Figure 5-1 Charpy V-Notch Impact Energy vs. Temperature for Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Longitudinal Orientation)
Testing of Specimens from Capsule X
5-18
- INTERMEDIATE SHELL PLATE R3807-2 (LONGITUDINAL ORIENTATION)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03117/2004 02:08 PM
- Data Set(s) Plotted Curve Plant Capsule Material Or. Heat #
I1 Comanche Peak 2 UNIRR SA533B 1 LT C5522-2 2 Comanche Peak 2 U. SA533B I LT C5522-2 3 : Comanche Peak 2 'xX SA533B 1 LT C5522-2 200 150 M
E U,
c
-0
. I100 0
0 _-
-300 0 300 600 Temperature in Deg F 0 Set 1 D Set2 0 Set 3 Results Curve Fluence LSE USE d-USE T @35 d-T @35
.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 Figure 5-2 Charpy V-Notch Lateral Expansion vs. Temperature for Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Longitudinal Orientation)
Testing of Specimens from Capsule X
5-19 INTERMEDIATE SHELL PLATE R3807-2 (LONGITUDINAL ORIENTATION)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 02:04 PM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat #
1 Comanche Peak 2 UNIRR SA533BI LT C5522-2 2 Comanche Peak 2 U SA533BI LT C5522-2 3 Comanche Peak 2 x SA533B 1 LT C5522-2 125 100 S-a) 75 (I,
I,=
- 0. 50 25 o 4-
-300 -200 -100 0 100 200 300 400 501lo 600 Temperature in Deg F 0 Si'et I Set 2 0 Set 3 Results Curve Fluence . LSE USE d.USE T @50 d-T @50 l -. 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 Figure 5-3 Charpy V-Notch Percent Shear vs. Temperature for Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Longitudinal Orientation)
Testing of Specimens from Capsule X
5-20 INTERMEDIATE SHELL PLATE R3807-2 (TRANSVERSE ORIENTATION)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed ofi 03/17/2004 03:38 PM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat #
1 Comanche Peak 2 UNIRR SA533B1I TL -C5522-2 2 Comanche Peak 2 U SA533B1 TL C5522-2 3 Comanche Peak 2 SA533B 1 TL i . C5522-2 300
. 250 0 200 Z1 0
E 150 ca Pi z
> 100 50 0
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F 0 Set I c Set 2 I Set 3 Results Curve Fluence LSE USE d-USE T @30 d-T @30 ' T @50 d-T @50 1 2. 2 84.0 .0 -12. 1 .0 42. 1 .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 Figure 5-4 Charpy V-Notch Impact Energy vs. Temperature for Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Transverse Orientation)
Testing of Specimens from Capsule X
5-21 INTERMEDIATE SHELL PLATE R3807-2 (TRANSVERSE ORIENTATION)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 04:16 PM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat #
3 Comanche Peak 2 UNIRR SA533BI TL C5522-2 2 Comanche Peak 2 U SA533B I TL C5522-2 3 Comanche Peak 2 X SA533B1 TL C5522-2 200 150 on 50 U-CJ2100 50 0 f-
-300 0 300 600 Temperature in Deg F o Set I a Set 2 0 Set 3 Results Curve Fluence LSE USE d-USE T @35 d-T @35 l .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 Figure 5-5 Charpy V-Notch Lateral Expansion vs. Temperature for Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Transverse Orientation)
Testing of Specimens from Capsule X
5-22 INTERMEDIATE SHELL PLATE R3807-2 (TRANSVERSE ORIENTATION)
- CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 04:04 PM Data Set(s) Plotted Curve . Plant Capsule Material Oni. Heat #
2 Comanche Peak 2 UTNIRR SA533BI TL C5522-2 2 Comanche Peak 2 U SA533BI Th C5522-2 3 Comanche Peak 2 :X SA533B I TL C5522-2 125 100 co 75 n
~0 V-(U W
IL 50 25 o 4-
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F o Siet 1 a Set 2 ° Set3 Results Curve Fluence LSE 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 Figure 5-6 Charpy V-Notch Percent Shear vs. Temperature for Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Transverse Orientation)
Testing of Specimens from Capsule X
5-23 SURVELLANCE PROGRAM WELD METAL CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03117/2004 04:23 PM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat #
3 Comanche Peak 2 UNIRR SAW NA 89833 2 Comanche Peak 2 U SAW NA 89833 3 Comanche Peak 2 X SAW NA 89833 300 _
250 -
8, 200 -
0 0
U-150 -
w z
8 100-_
50-0
-300 -200 -100 0 100 200 300 400 5iOO 600 Temperature in Deg F 0 Set I o Set 2
- Set 3 Results Curve Fluence LSE USE d-USE T @30 d-T @30 T @50 d-T @50 I 2.2 94.0 .0 -49. 6 .0 -. 4 .0 2 2.2 85.0 -9.0 -46.0 3.6 -1.2 -.8 3 2.2 96. 0 2.0 -1.4 48.2 26. 3 26. 7 Figure 5-7 Charpy V-Notch Impact Energy vs. Temperature for Comanche Peak Unit 2 Reactor Vessel Weld Metal Testing of Specimens from Capsule X
5-24 SURVIELLANCE PROGRAM WELD METAL CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 04:29 PM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat #
1 Comanche Peak 2 UNIRR SAW NA 89833 2: Comanche Peak 2 U SAW NA 89833 3 Comanche Peak 2 'X SAW NA 89833 200 150 In Co a 100 50 o _-
-300 0 300 600 Temperature In Deg F o Set 1 a Set 2 ° Set 3 Results Curve Fluence LSE USE d-USE T @35 d-T @35
.0 76. 0 .0 .7 .0 2 .0 66. 1 -9.9 -16.7 -17.4 3 .0 67.9 -8. 1 20.3 19.6 Figure 5-8 Charpy V-Notch Lateral Expansion vs. Temperature for Comanche Peak Unit 2 Reactor Vessel Weld Metal Testing of Specimens from Capsule X
5-25 SURVIELLANCE PROGRAM WELD METAL CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 04:26 PM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat #
1 Comanche Peak 2 UNIRR SAW NA 89833 2 Comanche Peak 2 U SAW NA 89833 3 Comanche Peak 2 X SAW NA 89833 125 -
100 -
(U 75 -
U)
(U C-50-25 -
0
-300 -201D -100 0 100 200 300 400 500 600 Temperature in Deg F 0 Set 1 3 Set 2
- Set 3 Results Curve Fluence LSE USE d-USE T @50 d-T @50
.0 100.0 .0 -1.2 .0 2 .0 100.0 .0 21.6 22.8 3 .0 100.0 .0 20.8 22.0 Figure 5-9 Charpy V-Notch Percent Shear vs. Temperature for Comanche Peak Unit 2 Reactor Vessel Weld Metal Testing of Specimens from Capsule X
5-26 HEAT AFFECTED ZONE CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 04:36 PM Data Set(s) Plotted Curve Plant Capsule Material On. Heat #
Comanche Peak 2 UNIRR SA533BI NA C5522-2 2 Comanche Peak 2 U SA533B 1 NA . C5522-2 3 Comanche Peak 2 x SA533B1 NA C5522-2 300 -
250 - -
to J 200 -
0-0 U-
@ 150 -.
Lu 2
>100 _
50 -
0 I' 4 ;
-300 -20( -100 0 100 200 300 400 50olo 600 Temperature in Deg F 0 Set 1 a Set 2
- Set 3 Results Curve Fluence LSE USE d-USE T @30 d-T @30 T @50 d-T @50 1 2.2 116.0 .0 -109.5 .0 -75.4 .0 2 2.2 127.0 11.0 - 122.7 -13.2 -70.1 5.3 3 2.2 116.0 .0 - 83.3 26. 2 -57.4 18.0 Figure 5-10 Charpy V-Notch Impact Energy vs. Temperature for Comanche Peak Unit 2 Reactor Vessel Heat-Affected-Zone Material Testing of Specimens from Capsule X
5-27
-HEAT AFFECTED ZONE CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/1712004 05:04 PM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat #
I Comanche Peak 2 UNIRR SA533B I NA C5522-2 2 Comanche Peak 2 U SA533B 1 NA C5522-2 3 Comanche Peak, 2 X SA533BI NA C5522-2 200 150 2
E C
50 0 a=::
-300 0 300 600 Temperature in Deg F o Set I a Set2
- Set 3 Results Curve Fluence LSE USE d-USE T @35 d-T @35
.0 72. 8 .0 -48. 9 .0 2 .0 77.8 5.0 -49.4 -. 5.
3 .0 66. 1 -6.7 -37.8 11.1 Figure 5-11 Charpy V-Notch Lateral Expansion vs. Temperature for Comanche Peak Unit 2 Reactor Vessel Heat-Affected-Zone Material Testing of Specimens from Capsule X
5-28
- HEAT AFFECTED ZONE CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03117/2004 04:39 PM
- Data Set(s) Plotted Curve Plant Capsule Material 01-i. Heat #
1 Comanche Peak 2 UNIRR SA533B I NA C5522-2 2 Comanche Peak 2 U SA533B1 NA .. C5522-2 3 Comanche Peak 2 x SA533B 1 NA C5522-2 125 -
100 -
L..
75 -
a).
50 -
0!
25 -
o ,
-300 -201o -100 0 100 200 300 400 500 600 Temperature in Deg F 0 Set I X Set 2
- Set 3 Results Curve Fluence LSE USE d-USE T @50 d-T @50 3 .0 100.0 .0 -40.3 .0 2 .0 100.0 .0 -31. 1 9.2 3 .0 100.0 .0 -38. 1 2.2 Figure 5-12 Charpy V-Notch Percent Shear vs. Temperature for Comanche Peak Unit 2 Reactor Vessel Heat-Affected-Zone Material ' -- I:
Testing of Specimens from Capsule X
5-29 CL48, 110F CL49, 1500 F CL50, 1750 F CL56, 200 0 F CL55, 2250 F Figure 5-13 Charpy Impact Specimei Fracture Surfaces for Conianclie Peak Unit 2 Reactor Vessel Intermiediate Shell Plate R3807-2 (Longitudinial Orientationi)
Testing of Specimens from Capsule X 1
V4.+
5-30 CT46, 175 0F CT52, 200 0F CT50, 225 0F CT56, 250 0F Figure 5-14 Charpy Impact Specimeni Fracture Surfaces for Comianche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Transverse Orientatioii)
Testing of Specimens from Capsule X
5-31 rUIAZ7 9S°FOT CW53. 750 F CW50,175 0 F CW54, 200 0 F CW56, 2000 F CW58,2250 F CW59,2500 F Figure 5-1I Charpy Impact Specimen Fracture Surfaces for Comancihe Peak Unit 2 Reactor Vessel WVeld Metal Testing of Specimens from Capsule X
5-32 CH55, 1000 F CH48, 125 0F CH59, 125 0F 0F CH52,75OF CH54, 15iO
_ A _ _
Figure 5-16 Charpy himpact Specimene Fracture Surfaces for Comancile Peak Unit 2 Reactor Vessel Heat-Affected-Zone Metal Testing of Specimens from Capsule X
5-33 80
_60-e 0.2% MIELD STRENGTH
, 40-20 -
0 100 200 300 400 500 600 TEMPERATURE( F)
Leaend: A and o are Unirradiated A and
- are Irradiated to 2.20 x I 09 n/cm 2 (E > 1.0 MeV) 80 REDUCTION IN AREA 70 50-60-40
)300 - _ TOTA ELONGATION 020-10
- AA 0- UNIFORM UNIFORM 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)
Testing of Specimens from Capsule X
5-34 100 80 ERTh *T
- ~ 60-se .. 0.2% YIELD STRENGTH a: 40 20.-
0 100 200 300 400 500 600 TEMPERATURE F)
Lc-end: A and 0 are Unirradiated A and
- are Irradiated to 2.20 x IO'9 n/cm2 (E> 1.0 MeV) 70 -
60 -
F 50 REDUCTION INAREA
, 40-30 -TOTAL 3F ELONGATION
~20- ,,,
10- ,-
UNIFORM UNIFORM 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)
Testing of Specimens from Capsule X
5-35 100 ULTIMATE YIELD STRENGTH 80
_?. 60 en 0.2% YIELD STRENGTH LU a: 40 U,
20 0
0 100 200 300 400 500 600 TEMPERATURE( F)
Lcgend: A and o are Unirradiated A and
- are Irradiated to 2.20 x 10'9 li/Cm2 (E > 1.0 McV) 70 -
60 -
So REDUCTION INAREA
.> 20° TOTAL ELONGATION im20 10 UNIFORM UNIFORM 0 I 0 100 200 300 400 500 600 TEMPERATURE ( F)
Fi,,ure 5-19 Tcnsile Properties foor ComancheIleak Unit 2 Reactor Vessel W-Veld N'letal Testing ofSpecimecns from Capsule X
5-36 Specimen CLIO Tested at 750 F Specimen CL1I1 Tested at 300'F Specimen CL12 Tested at 550TF Figure 5-20 Fractured Tensile Specimens from Comanche Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Longitudinal Oricntation)
Testing of Specimens from Capsule X
5-37 Specimen CT11 Tested at 750 F 60-eIw.~-..
Specimen CTIO Tested at 300NF Specimen CT12 Tested at 550 0 F Figure 5-21 Fractured Tcnsile Specimens from Comancle Peak Unit 2 Reactor Vessel Intermediate Shell Plate R3807-2 (Transverse Orientation)
Testing of Specimens from Capsule X
5-38 Specimen CW12 Tested at 75 0 F Specimen CW1 1 Tested at 300OF Specimen CWIO Tested at 550'F Figure 5-22 Fractured Tensile Specimeens from Comancle Peak Unit 2 Reactor Vessel Veld Metal Testing of Specimens from Capsule X
5-39 COMANCHE PEAK UNIT 2 X' CAPSULE 100 90 80 70 F5 60 C6 50 U) 40 CL-10 30 75 F 20 10 0 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN. INIIN COMANCHE PEAK UNIT 2 X' CAPSULE 100 90 80 70 0 60 I- 5 U) 40 30 CL-1l 300 F 20 10 0
0 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN. INWIN Figure 5-23 Engineering Stress-Strain Curves for Comanche Peak Unit 2 Intermediate Shell Plate R3807-2 Tensile Specimens CL-10, CL-11 and CL-12 (Longitudinal Orientation)
Testing of Specimens from Capsule X
5-40 COMANCHE PEAK UNIT 2 X CAPSULE 100-90-80-70 C 60-C,;
Us 50-I-
to 40-CL-12 30 550 F 20 101 to 0 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN. INAIN Figure 5-23 - Continued Testing of Specimens from Capsule X
541 COMANCHE PEAK UNIT 2 X- CAPSULE 100 90 80 70 an 60 so 0 40 30 CT-il 20 75F 10 0
0 0.05 0.1 0.15 02 0.25 0.3 STRAIN. INAN COMANCHE PEAK UNIT 2 X CAPSULE 100 90 80 70 so 0 60 C6 so a:
w oo 40 30 cr-10 20 30OF 10 0
0.05 0.1 0.15 0.2 0.25 0.3 STRAIN. INAN Figure 5-24 'Engineering Stress-Strain Curves for Comanche Peak Unit 2 Intermediate Shell Plate R3807-2 Tensile Specimens CT-10, CT-11 and CT-12 (Transverse Orientation)
Testing of Specimens from Capsule X
42 COMANCHE PEAK UNIT 2 X' CAPSULE 100 90 80 70 60 v;
50 I-ti 40 CT-12 30 550 F 20 10 0
0 0.05 0.1 0.15 . 0.2 - 0.25 0.3 STRAIN. INIIN Figure
~. I .. 5.24 I
- Continued
. IT of S . . .C....
Testing of Specimens from Capsule X
5-43 COMANCHE PEAK UNIT 2 v CAPSULE 100 90 83 70 60 to U(
50 o:
40 CW-12 30 75F 20 10 0
0 0.05 0.1 0.15 0.2 0.25 03 STRAIN, INAN COMANCHE PEAK UNIT 2 X CAPSULE 100 90 80 70 60 rn
'U s0 c:
o 40 CW-11 30 300 F 20 10 0 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN. ININ Figure 5-25 Engineering Stress-Strain Curves for Weld Metal Tensile Specimens CW-10, CW-11 and CW-12 Testing of Specimens from Capsule X
5-44 COMANCHE PEAK UNIT 2 X CAPSULE 100 90 so 70 U) 60 V)
I-to 40 CW-10 30 20 550F 10 0
0 0.05 0.1 0.15 - . 0.2 . 0.25 0.3 STRAIN. ININ Figure 5 Continued Testing of Specimens from Capsule X
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 X, withdrawn at the end of the seventh plant operating cycle, is provided. In addition, to provide an up-to-date data base applicable to the Comanche Peak Unit 2 reactor, the sensor set from the previously withdrawn capsule (U) was re-analyzed using the current dosimetry evaluation methodology. These dosimetry updates are presented in Appendix A of this report. Comparisons of the results from these dosimetry evaluations with the analytical predictions served to validate the plant specific neutron transport calculations. These validated calculations subsequently formed the basis for providing projections of the neutron exposure of the reactor pressure vessel for operating periods extending to 54 Effective Full Power Years (EFPY).
The use of fast neutron fluence (E > 1.0 MeV) to correlate measured material property changes to the neutron exposure of the material has traditionally been accepted for the development of damage trend curves as well as for the implementation of trend curve data to assess the condition of the vessel. In recent years, however, it has been suggested that an exposure model that accounts for differences in neutron energy spectra between surveillance capsule locations and positions within the vessel wall could lead to an improvement in the uncertainties associated with damage trend curves and improved accuracy in the evaluation of damage gradients through the reactor vessel wall.
Because of this potential shift away from a threshold fluence toward an energy dependent damage function for data correlation, ASTM Standard Practice E853, "Analysis and Interpretation of Light-Water Reactor Surveillance Results," recommends reporting displacements per iron atom (dpa) along with fluence (E > 1.0 MeV) to provide a database for future reference. The energy dependent dpa function to be used for this evaluation is specified in ASTM Standard Practice E693, "Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements per Atom." The application of the dpa parameter to the assessment of embrittlement gradients through the thickness of the reactor vessel wall has already been promulgated in Revision 2 to Regulatory Guide 1.99, "Radiation Embrittlement of Reactor Vessel Materials."
All of the calculations and dosimetry evaluations described in this section and in Appendix A were based on the latest available nuclear cross-section data derived from ENDF/B-VI and made use of the latest available calculational tools. Furthermore, the neutron transport and dosimetry evaluation methodologies follow the guidance of Regulatory Guide 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence."[7 1 Additionally, the methods used to develop the calculated pressure vessel fluence are consistent with the NRC approved methodology described in WCAP-14040-NP-A, "Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves," May 2004.1I8]
Radiation Analysis and Neutron Dosimetry
6-2 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.S5, 238.50, 241°, and 301.50 as shown in Figure 4-1. Thesefull core positions correspond to the following octant symmetric locations represented in Figure 6-1: 290 from the core cardinal axes (for the 610 and
'2410 dual surveillance capsule holder locations 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 areapproximately 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 environmentat 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) = q,(r,0)* p(r,z) p)(r) where¢(r,%,z) is the synthesized three-dimensional neutron flux distribution,+(rO) is the transport solution in re geometry,+(rz) is the two-dimensional solution for a cylindrical reactor model using the actual axial core power distribution, and+(r) is the one-dimensional solution for a cylindrical reactor model using'the same source per unit height as that used in the r,O two-dimensional calculation. This synthesis procedure was carried out for each operating cycle at Comanche Peak Unit 2. -
For the Comanche Peak Unit 2 transport calculations, the rO models depicted in Figure 6-1 were utilized since, with the exception of the neutron pads, the reactor is octant symmetric. These rO models include the core, the reactor internals, the neutron pads - including explicit representations of octants not containing surveillance capsules and octants with surveillance capsules at 29° and 31.5°, the pressure -
vessel cladding and vessel wall, the insulation external to the pressure vessel, and the primary biological shield wall. These models formed the basis for the calculated results and enabled making comparisons to the surveillance capsule dosimetry evaluations. In developing these analytical models, nominal design dimensions were employed for the various structural components. Likewise, water temperatures, and hence, coolant densities in the reactor core and downcomer regions of the reactor were taken to be representative of full power operating conditions. The coolant densities were treated on a fuel cycle specific basis. The reactor core itself was treated as a homogeneous mixture of fuel, cladding, water, and Radiation Analysis and Neutron Dosimetry - I
6-3 miscellaneous core structures such as fuel assembly grids, guide tubes, et cetera. The geometric mesh description of the rO reactor models consisted of 183 radial by 99 azimuthal intervals. Mesh sizes were chosen to assure that proper convergence of the inner iterations was achieved on a point-wise basis. The point-wise inner iteration flux convergence criterion utilized in the rO calculations was set at a value of 0.001.
The rz model used for the Comanche Peak Unit 2 calculations is shown in Figure 6-2 and extends radially from the centerline of the reactor core out to a location interior to the primary biological shield and over an axial span from an elevation below the lower core plate to above the upper core plate. As in the case of the rO models, nominal design dimensions and full power coolant densities were employed in the calculations. In this case, the homogenous core region was treated as an equivalent cylinder with a volume equal to that of the active core zone. The stainless steel former plates located between the core baffle and core barrel regions were also explicitly included in the model. The 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 point-wise basis. The point-wise inner iteration flux convergence criterion utilized in the r,z calculations was also set at a value of 0.001.
The one-dimensional radial 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 mesh-wise basis throughout the entire geometry.
The core power distributions used in the plant specific transport analysis were provided by TXU Electric for each of the first seven fuel cycles at Comanche Peak Unit 2.[21] Specifically, the data utilized included cycle dependent fuel assembly initial enrichments, burnups, 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.I'91 and the BUGLE-96 cross-section library. 0 ] The BUGLE-96 library provides a 67 group coupled neutron-gamma ray cross-section data set produced specifically for light water reactor (LWR) applications. In these analyses, anisotropic scattering was treated with a P5 legendre expansion and angular discretization was modeled with an S16 order of angular quadrature.
Energy and space dependent core power distributions, as well as system operating temperatures, were treated on a fuel cycle specific basis.
Selected results from the neutron transport analyses are provided in Tables 6-1 through 6-6. In Table 6-1, the calculated exposure rates and integrated exposures, expressed in terms of both neutron fluence (E > 1.0 MeV) and dpa, are given at the radial and azimuthal center of the octant symmetric surveillance capsule positions, i.e., for the 29° dual capsule, 31.50 dual capsule, and 31.50 single capsule. These Radiation Analysis and Neutron Dosimetry
6-4 results, representative of the axial midplane of the active core, establish the calculated exposure of the 7 surveillance capsules withdrawn to date as well as projected into the future. Similar information is provided in Table 6-2 for the reactor vessel inner radius at four azimuthal locations. The vessel data given in Table 6-2 were taken at the 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 seventh fuel 'cycle (i.e., after 8.83 EFPY of plant operation) was 5.30x 1o09 n/cm 2 .'-
Both calculated fluence (E > 1.0 MeV) and dpa data are provided in Table 6-1 and Table 6-2. These data tabulations include both plant and fuel cycle specific calculated neutron exposures at the end of the seventh fuel cycle as well as future projections to 10, 15, 20,25,32,36, 48, and 54 EFPY. The calculations for Cycle 5 account for an uprate from 3411 MWt to 3445 MWt that occurred at a cycle burnup of 7,121 MWD/MTU. Similarly, the calculations for Cycle 6 account for an uprate from 3445 MWt to 3458 MWt that occurred at a cycle burnup of 14,878 MWD/MTU. The projections were based on the assumption that the core power distributions and associated plant operating characteristics from Cycle 7 were representative of future plant operation. The future projections are also based on the current reactor power level of 3458 MWt.'
Radial gradient information applicable to fast (E > 1.0 MeV) neutron fluence and dpa are given in Tables 6-3 and 64, respectively. The data, based on the cumulative integrated exposures from Cycles I through 7, 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 two surveillance capsules withdrawn from the Comanche Peak Unit 2 reactor are provided in Table 6-5 (also shown in Table 6-1 under the "Dual 31.5°" Column).
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.
From the data provided in Table 6-5 it is noted that Capsule X received a fluence (E > 1.0 MeV) of 2.20x 1019 n/cm 2 after exposure through the end of the seventh fuel cycle (i.e., after 8.83 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 and X) were based on the calculated fluence values' for the irradiation period corresponding to the time of withdrawal for the individual capsules. For the capsules remaining in the reactor (V, W, Y, and Z), the lead factor corresponds to the calculated fluence values at the end of Cycle 7, the last completed fuel cycle for Comanche Peak Unit 2.'
Radiation Analysis and Neutron Dosimetry
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, is documented in Appendix A.
The direct comparison of measured versus calculated fast neutron threshold reaction rates for the sensors from Capsule X, that was withdrawn from Comanche Peak Unit 2 at the end of the seventh fuel cycle, is summarized below.
Reaction Rates (rps/atom) M/C Reaction Measured Calculated Ratio 63 Cu(n,f) 60Co 4.29E-17 4.30E-17 1.00 14Fe(np) Mn 4.57E-15 4.74E-15 0.96 5 Ni(n,p)"Co 6.32E-15 6.63E-15 0.95 23sU(np)13 7Cs (Cd) 2.70E-14 2.53E-14 1.07
- 2 37 Np(nf)' 37 Cs (Cd) 2.49E-13
- 2.46E-13 1.01 Average: 1.00
% Standard Deviation: 4.5 The measured-to-calculated (MWC) reaction rate ratios for the Capsule X threshold reactions range from 0.95 to 1.07, and the average M/C ratio is 1.00 +/- 4.5% (Ia). This direct comparison falls well within the i 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.
Radiation Analysis and Neutron Dosimetry
6-6 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).
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 18.
Radiation Analysis and Neutron Dosimetry
6-7 Capsule Vessel IR l PCA Comparisons 3% 3%
H. B. Robinson Comparisons 3% 3%
Analytical Sensitivity Studies 10% 11%
Additional Uncertainty for Factors not Explicitly Evaluated 5% 5%
Net Calculational Uncertainty 12% 13%
The net calculational uncertainty was determined by combining the individual components in quadrature.
Therefore, the resultant uncertainty was treated as random and no systematic bias was applied to the analytical results.
The plant specific measurement comparisons described in Appendix A support these uncertainty assessments for Comanche Peak Unit 2.
Radiation Analysis and Neutron Dosimetry
6-8 Table 6-1 Calculated Neutron Exposure Rates And Integrated Exposures At The Surveillance Capsule Center Cumulative Cumulative Neutron Flux (E > 1.0 MeV)
Cycle Irradiation Irradiation [n/cm2 -s]
Length Time Time Cycle [EFPS] [EFPSJ [EFPY : -
Dual Dual Single 290 31.50 31.50 1 2.87E+07 2.87E+07 0.91 l.OOE+l l 1.1OE+1l 1.09E+1l 2 3.73E+07 6.60E+07 2.09 6.46E+10 7.i3E+10 7.06E+10 3 4.42E+07 1.1OE+08 3.49 7.72E+10 8.1lE+10 8.02E+10 4 3.84E+07 1.49E+08 4.71 6.97E+10 7.40E+10 7.33E+10 5 4.52E+07 1.94E+08 6.14 6.84E+10 7.28E+10 7.21E+10 6 4.36E+07 2.37E+08 7.52 7.OOE+10 7.32E+10 7.25E+10 7 4.12E+07 2.79E+08 8.83 7.34E+10 8.01E+10 7.93E+10 Future 3.71E+07 3.16E+08 10.00 7.34E+10 8.01E+10 7.93E+10 Future 1.58E+08 4.73E+08 15.00 7.34E+10 8.01E+10 7.93E+10 Future 1.58E+08 6.31E+08 20.00 7.34E+10 8.01E+10 7.93E+l 0 Future 1.58E+08 7.89E+08 25.00 7.34E+10 8.01E+10 7.93E+10 Future 2.21E+08 1.01E+09 32.00 7.34E+10 8.01E+10 7.93E+10 Future 1.26E+08 1.14E+09 36.00 7.34E+10 8.01E+10 7.93E+10 Future 3.79E+08 1.51E+09 48.00 7.34E+10 8.01E+10 7.93E+10 Future 1.89E+08 1.70E+09 54.00 7.34E+10 8.01E+10 7.93E+10 Note: Neutron exposure values reported for the surveillance capsules are centered at the core midplane.
Radiation Analysis and Neutron Dosimetry
6-9 Table 6-1 cont'd Calculated Neutron Exposure Rates And Integrated Exposures At The Surveillance Capsule Center Cumulative Cumulative Neutron Fluence (E > 1.0 MeV)
Cycle Irradiation Irradiation [n/cm2 I Length Time Time Cycle [EFPS] [EFPS] JEFPY]
Dual Dual Single 290 31.50 31.50 1 2.87E+07 2.87E+07 0.91 2.88E+18 3.15E+18 3.12E+18 2 3.73E+07 6.60E+07 2.09 5.28E+18 5.81E+18 5.75E+18 3 4.42E+07 1.lOE+08 3.49 8.69E+18 9.39E+18 9.30E+18 4 3.84E+07 1.49E+08 4.71 1.14E+19 1.22E+19 1.21E+19 5 4.52E+07 1.94E+08 6.14 1.45E+19 1.55E+19 1.54E+19 6 4.36E+07 2.37E+08 7.52 1.75E+19 1.87E+19 1.85E+19 7 4.12E+07 2.79E+08 8.83 2.05E+19 2.20E+19 2.18E+19 Future 3.71 E+07 3.16E+08 10.00 2.33E+19 2.50E+19 2.47E+19 Future 1.58E+08 4.73E+08 15.00 3.48E+19 3.76E+19 3.73E+19 Future 1.58E+08 6.31 E+08 20.00 4.64E+19 5.03E+19 4.98E+19 Future 1.58E+08 7.89E+08 25.00 5.80E+19 6.29E+19 6.23E+19 Future 2.21E+08 1.O1E+09 32.00 7.42E+19 8.06E+19 7.98E+19 Future 1.26E+08 1.14E+09 36.00 8.35E+19 9.07E+19 8.98E+19 Future 3.79E+08 1.51E+09 48.00 1.11E+20 1.21E+20 1.20E+20 Future 1.89E+08 1.70E+09 54.00 1.25E+20 1.36E+20 1.35E+20 Note: Neutron exposure values reported for the surveillance capsules are centered at the core midplane.
Radiation Analysis and Neutron Dosimetry
6-10 Table 6-1 cont'd Calculated Neutron Exposure Rates An'd Integrated Exposures At The Surveillance Capsule Center Cumulative Cumulative Iron Atom Displacement Rate Cycle Irradiation Irradiation Idpa/sl Length Time :.Time Dual Dual Single Cycle [EFPS] IEFPS] [EFPYJ 290 31.50 31.50 I 2.87E+07 2.87E+07 0.91 1.96E-10 2.15E-10 2.13E-10 2 3.73E+07 6.60E+07 2.09 1.25E-10 1.38E-10 1.37E-10 3 4.42E+07 I.IOE+08 3.49 I.50E-I0 1.58E-10 1.56E-10 4 3.84E+07 1.49E+08 4.71 1.35E-10 1.44E-10 1.42E-10 5 -4.52E+07 1.94E+08 6.14 1.33E-10 1.41E-10 1.40E-10 6 4.36E+07 2.37E+08 7.52 1.36E-10 1.42E-10 1.41E-10 7 4.12E+07 2.79E1+08 8.83 1.43E-10 1.56E-10 1.55E-10 Future 3.71E+07 3.16E+08 10.00 1.43E-10 1.56E-10 1.55E-10 Future 1.58E+08 4.73E+08 15.00 1.43E-I0 1.56E-10 1.55E-10 Future 1.58E+08 6.31E+08 , 20.00 1.43E-10 '1.56E-10 1.55E-10 Future 1.58E+08 7.89E+08 25.00 1.43E-10 1.56E-10 1.55E-10 Future 2.21E+08 I.OIE+09 32.00 1.43E-10 1.56E-10 1.55E-10 Future 1.26E+08 1.14E+09 36.00 1.43E-10 1.56E-10 l.55E-10 Future 3.79E+08 1.51E+09 48.00 1.43E-10 1.56E-10 I.551E-10 Future 1.89E+08 ' 1.70E+09 54.00 1.43E-10 1.56E-10 I.55E-I0 Note: -Neutron exposure values reported for the surveillance capsules are centered at the core midplane.
Radiation Analysis and Neutron Dosimetry
6-1l f.... Table 6-1 cont'd .
Calculated Neutron Exposure Rates And Integrated Exposures At The Surveillance Capsule Center Cumulative Cumulative Iron Atom Displacements Cycle Irradiation Irradiation [dpal Length Time - Time Dual Dual Single Cycle [EFPSJ [EFPSJ [EFPYJ 290 31.50 31.50 1 2.87E+07 2.87E+07 0.91 5.64E-03 6.18E-03 6.12E-03 2 3.73E+07 6.60E+07 2.09 1.03E-02 1.13E-02 1.12E-02 3 4.42E+07 1.IOE+08 3.49 1.70E-02 1.83E-02 1.81E-02 4 3.84E+07 1.49E+08 4.71 2.22E-02 2.38E-02 2.36E-02 5 4.52E+07 1.94E+08 6.14 2.82E-02 3.02E-02 2.99E-02 6 4.36E+07 2.37E+08 7.52 3.41E-02 3.64E-02 3.60E-02 7 4.12E+07 2.79E+08 8.83 4.OOE-02 4.28E-02 4.24E-02 Future 3.71E+07 3.16E+08 10.00 4.53E-02 4.86E-02 4.81E-02 Future 1.58E+08 4.73E+08 15.00 6.79E-02 7.33E-02 7.25E-02 Future 1.58E+08 6.31E+08 20.00 9.04E-02 9.79E-02 9.69E-02 Future 1.58E+08 7.89E+08 25.00 1.13E-01 1.23E-01 1.21E-01 Future 2.21E+08 l.O1E+09 32.00 1.45E-01 1.57E-01 l.55E-01 Future 1.26E+08 1.14E+09 36.00 1.63E-01 1.77E-01 1.75E-01 Future 3.79E+08 1.51E+09 48.00 2.17E-01 2.36E-01 2.33E-01 Future 1.89E+08 1.70E+09 54.00 2.44E-01 2.65E-01 2.63E-Ol Note: Neutron exposure values reported for the surveillance capsules are centered at the core midplane.
Radiation Analysis and Neutron Dosimetry
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)
. Cycle Irradiation Irradiation _n/cm_-sl Length Time Time Cycle JEFPSJ -EFPSj IEFPYJ - 150 300 450 I 2.87E+07 2.87E+07 0.91 1.46E+10 2.16E+10 2.54E+10 2.79E+10 2 3.73E+07 6.60E+07 2.09 1.15E+10 1.42E+10 1.66E+10 1.74E+10 3 4.42E+07 1.10E+08 3.49 1.52E+10 2.21E+10 2.01E+10 1.96E+10 4 3.84E+07 1.49E+08 4.71 1.29E+10 1.91E+10 1.81E+10 1.75E+10 5 4.52E+07 1.94E+08 6.14 1.18E+10 1.71E+10 1.78E+10 1.72E+10 6 4.36E+07 2.37E+08 7.52 1.32E+10 1;85E+10 1.81E+10 1.63E+10 7 4.12E+07 2.79E+08 8.83 1.43E+10 1.90E+10 1.91E+10 2.06E+10 Future 3.71E+07 3.16E+08 10.00 1.43E+10 1.90E+10 1.91E+10 2.06E+10 Future '1.58E+08 4.73E+08 15.00 1.43E+10 1.90E+10 1.91E+10 2.06E+10 Future 1.58E+08 6.3 1E+08 20.00 1.43E+10 1.90E+10 1.91E+10 2.06E+10 Future 1.58E+08 7.89E+08 25.00 1.43E+10 1.90E+10 1.91E+10 2.06E+10 Future 2.21E+08 1.OlE+09 32.00 1.43E+10 1.90E+10 1.91E+10 2.06E+10 Future 1.26E+08 1.14E+09 36.00 1.43E+10 1.90E+10 l.91E+10 2.06E+10 Future 3.79E+08 1.51E+09 48.00 1.43E+10 1.90E+10 1.91E+10 2.06E+10 Future 1.89E+08 1.70E+09 54.00 1.43E+10 1.90E+10 l.91E+10 2.06E+10 Radiation Analysis and Neutron Dosimetry - ; X
6-13 Table 6-2 cont'd Calculated Azimuthal Variation Of Maximum Exposure Rates And Integrated Exposures At The Reactor Vessel Clad/Base Metal Interface Cumulative Cumulative Neutron Fluence (E > 1.0 MeV)
Cycle Irradiation Irradiation InIcm 2 Length Time Time Cycle IEFPSJ IEFPS] [EFPYJ 00 150 300 450 1 2.87E+07 2.87E+07 0.91 4.19E+17 6.21E+17 7.30E+17 8.02E+17 2 3.73E+07 6.60E+07 2.09 8.42E+17 1.14E+18 1.34E+18 1.44E+18 3 4.42E+07 1.IOE+08 3.49 1.51E+18 2.12E+18 2.23E+18 2.31E+18 4 3.84E+07 1.49E+08 4.71 2.00E+18 2.84E+18 2.92E+18 2.97E+18 5 4.52E+07 1.94E+08 6.14 2.53E+18 3.61E+18 3.72E+18 3.75E+18 6 4.36E+07 2.37E+08 7.52 3.1lE+18 4.42E+18 4.51E+18 4.46E+18 7 4.12E+07 2.79E+08 8.83 3.70E+18 5.21E+18 5.30E+18 5.30E+18 Future 3.71E+07 3.16E+08 10.00 4.23E+18 5.91E+18 6.00E+18 6.07E+18 Future 1.58E+08 4.73E+08 15.00 6.49E+18 8.92E+18 9.02E+18 9.31E+18 Future 1.58E+08 6.31E+08 20.00 8.74E+18 1.19E+19 1.20E+19 1.26E+19 Future 1.58E+08 7.89E+08 25.00 1.1OE+19 1.49E+19 1.511E+19 1.58E+19 Future 2.21E+08. 1.OlE+09 32.00 1.42E+19 1.91E+19 1.93E+19 2.03E+19 Future 1.26E+08 1.14E+09 36.00 1.60E+19 2.15E+19 2.17E+19 2.29E+19 Future 3.79E+08 1.511E+09 48.00 2.14E+19 2.88E+19 2.89E+19 3.07E+19 Future 1.89E+08 1.70E+09 54.00 2.41E+19 3.24E+19 3.26E+19 3.46E+19 Radiation Analysis and Neutron Dosimetry
6-14 Table 6-2 cont'd Calculated Azimuthal Variation Of Fast Neutron Exposure Rates And Iron Atom Displacement Rates At The Reactor Vessel Clad/Base Metal Interface Cumulative Cumulative Iron Atom Displacement Rate Cycle Irradiation Irradiation Ida/s_
Length Time Time Cycle IEFPSJ IEFPSl IEFPY] 00 150 300 450 1 2.87E+07 2.87E+07 0.91 2.27E-11 3.32E-11 3.92E-11 4.42E-11 2 3.73E+07 6.60E+07 2.09 1.78E-11 2.19E-11 2.57E-11 2.75E-11 3 4.42E+07 1.1OE+08 3.49 2.36E-11 3.39E-11 3.1OE-1 1 3.1OE-1 1 4 3.84E+07 1.49E+08 4.71 2.01E-11 2.94E-11 2.80E-11 2.77E-11 5 4.52E+07 1.94E+08 6.14 1.83E-11 2.63E-11 2.74E-11 2.71E-11 6 4.36E+07 2.37E+08 7.52 2.05E-1 1 2.84E-1 I 2.79E-1 1 2.58E-1 I 7 4.12E+07 2.79E+08 8.83 2.22E-11 2.93E-11 2.96E-11 3.25E-11 Future 3.71E+07 3.16E+08 10.00 2.22E-11 2.93E-11 2.96E-11 3.25E-11 Future 1.58E+08 4.73E+08 15.00 2.22E-11 2.93E-11 2.96E-11 3.25E-11 Future 1;58E+08 6.31E+08 20.00 2.22E-11 2.93E-1I 2.96E-11 3.25E-11 Future 1.58E+08 7.89E+08 25.00 2.22E-11 2.93E-11 2.96E-11 3.25E-11 Future 2.21E+08 1.OlE+09 32.00 2.22E-11 2.93E-11 2.96E-11 3.25E-11 Future 1.26E+08 1.14E+09 36.00 2.22E-11 2.93E-11 2.96E-11 3.25E-1 I Future 3.79E+08 1.51E+09 48.00 2.22E-11 2.93E-11 2.96E-11 3.25E-11 Future 1.89E+08 1.70E+09 54.00 2.22E-1 1 2.93E-1 1 2.96E-11 3.25E-11 Radiation Analysis and Neutron Dosimetry
6-15 Table 6-2 cont'd Calculated Azimuthal Variation Of Maximum Exposure Rates And Integrated Exposures At The Reactor Vessel Clad/Base Metal Interface Cumulative Cumulative Iron Atom Displacements Cycle Irradiation Irradiation [dpa_
Length Time Time Cycle IEFPS] IEFPSJ tEFPY] 00 150 300 450 1 2.87E+07 2.87E+07 0.91 6.50E-04 9.54E-04 1.13E-03 1.27E-03 2 3.73E+07 6.60E+07 2.09 1.31E-03 1.76E-03 2.07E-03 2.28E-03 3 4.42E+07 1.10E+08 3.49 2.35E-03 3.26E-03 3.44E-03 3.65E-03 4 3.84E+07 1.49E+08 4.71 3.11 E-03 4.37E-03 4.50E-03 4.70E-03 5 4.52E+07 1.94E+08 6.14 3.93E-03 5.55E-03 5.74E-03 5.92E-03 6 4.36E+07 2.37E+08 7.52 4.83E-03 6.79E-03 6.96E-03 7.05E-03 7 4.12E+07 2.79E+08 8.83 5.74E-03 8.OOE-03 8.17E-03 8.39E-03 Future 3.71E+07 3.16E+08 10.00 6.57E-03 9.08E-03 9.27E-03 9.59E-03 Future 1.58E+08 4.73E+08 15.00 l.OlE-02 1.37E-02 1.39E-02 1.47E-02 Future 1.58E+08 6.3 1E+08 20.00 1.36E-02 1.83E-02 1.86E-02 1.99E-02 Future 1.58E+08 7.89E+08 25.00 1.71E-02 2.29E-02 2.33E-02 2.50E-02 Future 2.21E+08 1.01E+09 32.00 2.20E-02 2.94E-02 2.98E-02 3.22E-02 Future 1.26E+08 1.14E+09 36.00 2.48E-02 3.3 1E-02 3.35E-02 3.63E-02 Future 3.79E+08 1.51E+09 48.00 3.32E-02 4.42E-02 4.47E-02 4.86E-02 Future 1.89E+08 1.70E+09 54.00 3.74E-02 4.97E-02 5.03E-02 5.47E-02 Radiation Analysis and Neutron Dosimetry
6-16 Table 6-3 Relative Radial Distribution Of Neutron Fluence (E > 1.0 MeV)
Within The Reactor Vessel Wall '
RADIUS AZIMUTHALANGLE l (cm) 00 150 300 450 220.11 1.000 1.000 1.000 1.000 225.59 0.570 0.565 0.562 0.557 231.06 0.281 0.276 0.273 0.269 236.54 0.134 0.129 0.128 0.125 242.01 0.064 0.059 0.059 0.057 Note: Base Metal Inner Radius = 220.11 cm Base Metal 1/4T = 225.59 cm Base Metal 1/2T = 231.06 cm Base Metal 3/4T = 236.54 cm Base Metal Outer Radius = 242.01 cm Note: Relative radial distribution data are based on the cumulative integrated exposures from Cycles 1 through 7.
Table 64 Relative Radial Distribution Of Iron Atom Displacements (dpa)
Within The Reactor Vessel Wall RADIUS AZIMUTHAL ANGLE (cm) 00 150 300 450 220.11 1.000 1.000 1.000 1.000 225.59 0.642 0.636 0.638 0.646 231.06 0.390 0.381 0.385 0.394 236.54 0.237 0.227 0.231 0.238 242.01 0.142 0.128 0.133 0.135 Note: Base Metal Inner Radius = 220.11 cm Base Metal 1/4T = 225.59 cm Base Metal 1/2T = 231.06 cm Base Metal 3/4T = 236.54 cm Base Metal Outer Radius = 242.01 cm Note: Relative radial distribution data are based on the cumulative integrated exposures from Cycles 1 through 7.
Radiation Analysis and Neutron Dosimetry I -
6-17 Table 6-5 Calculated Fast Neutron Exposure of Surveillance Capsules Withdrawn from Comanche Peak Unit 2 Irradiation Time Fluence (E > 1.0 MeV) Iron Displacements Capsule [EFPY] Inlcm2 l [dpal U 0.91 3.15E+18 6.18E-03 X 8.83 2.20E+19 4.28E-02 Table 6-6 Calculated Surveillance Capsule Lead Factors Capsule ID And Location Status Lead Factor U (31.50 Dual) Withdrawn EOC 1 3.93 X (31.5° Dual) Withdrawn EOC 7 4.15 V (29.0° Dual) In Reactor 3.87 W (31.50 Single) In Reactor 4.11 Y (29.00 Dual) In Reactor 3.87 Z (31.5 0 Single) In Reactor 4.11 Note: Lead factors for capsules remaining in the reactor are based on cycle specific exposure calculations through the last completed fuel cycle, i.e., Cycle 7.
Radiation Analysis and Neutron Dosimetry
6-18 Figure 6-1 Comanche Peak Unit 2 rO Reactor Geometry with a 12.50 Neutron Pad Span at the Core Midplane 240 180 C.!
vX xC 120 60 0
0 75 150 225 300 R Axis (cm)
Radiation Analysis and Neutron Dosimetry
6-19 Figure 6-1 (continued)
Comanche Peak Unit 2 r,0 Reactor Geometry with a 20.00 Neutron Pad Span at the Core Midplane 240 180 E
cn 120 60 0
0 75 150 . 225 300 R Axis (cm)
Radiation Analysis and Neutron Dosimetry
6-20 Figure 6-1 (continued)
Comanche Peak Unit 2 rO Reactor Geometry with a 22.50 Neutron Pad Span at the Core Midplane 240 -
1 80 -
E
.~120-60 0 75 1 50 225 300 R Axis (cm)
Radiation Analysis and Neutron Dosimetry
6-21 Figure 6-2 Comanche Peak Unit 2 rz Reactor Geometry with Neutron Pad
- 7r7V7 300-
-, A A dU V -
- L--
100-E L) 0-
.L n
X
-100-f=
-200-
-300-
-400 I I I I I I I I I I I 0 75 150 225 300 R Axis (cm)
Radiation Analysis and Neutron Dosimetry
7-1 7 SURVEILLANCE CAPSULE REMOVAL SCHEDULE The following surveillance capsule removal schedule meets the requirements of ASTM El 85-82 and is recommended for future capsules to be removed from the Comanche Peak Unit 2 reactor vessel. This recommended removal schedule is applicable to 36 EFPY of operation.
Table 7-1 Recommended Surveillance Capsule Withdrawal Schedule Capsule Capsule Location Lead Factor (a) Withdrawal EFPY (b) Fluence (n/cm2 ) (a)
U 58.50 (31.5'Dual) 3.93 0.91 3.15 x 10i"(c)
X 238.5° (31.5'Dual) 4.15 8.83 2.20 x 10'9 (c)
W 121.5° (31.5° Single) 4.11 11.7 2.94 x 10'9 (d)
Z 301.5° (31.5'Single) 4.11 Standby (e) (e)
V 61.00 (29. 0°Dual) 3.87 Standby (f) (f)
Y 241.00 (29. 0°Dual) 3.87 Standby (f) (f)
Notes:
(a) Updated in Capsule X dosimetry analysis.
(b) Effective Full Power Years (EFPY) from plant startup.
(c) Plant specific evaluation.
(d) This fluence is greater than one-times and less than two-times the peak EOL (@ 36 EFPY) vessel fluence.
(e) If license renewal is obtained this capsule should be withdrawn anytime after 13.6 EFPY, which is when the capsule fluence would exceed one-times the peak EOLR (54 EFPY) vessel fluence, not to exceed 26.6 EFPY, which is when the fluence on the capsule would exceed two-times the EOLR (54 EFPY) vessel fluence. If license renewal is never obtained, then this capsule should still be removed prior to 26.6 EFPY and placed in storage. See Note "f'.
(f) These capsules should be withdrawn at least one outage prior to 28.2 EFPY, which is when the fluence on these capsules would exceed two-times the EOLR (54 EFPY) vessel fluence. Once all capsules are removed alternative fluence measuring capabilities must be in place.
Surveillance Capsule Removal Schedule
8-1 8 REFERENCES
- 1. Regulatory Guide 1.99, Revision 2, RadiationEmbrittlement ofReactor Vessel Materials, U.S. Nuclear Regulatory Commission, May, 1988.
- 2. Code of Federal Regulations, 10CFR5O, Appendix G FractureToughness Requirements, and Appendix H, Reactor Vessel MaterialSurveillance ProgramRequirements, U.S. Nuclear Regulatory Commission, Washington, D.C.
- 3. WCAP-10684, Texas Utilities GeneratingCompany Comanche Peak Unit No. 2 Reactor Vessel RadiationSurveillanceProgram, L.R. Singer, dated October 1984.
- 4. WCAP-14315,Analysis of Capsule Ufrom the Texas Utilities GeneratingCompany Comanche Peak Steam ElectricStation Unit No. 2 Reactor Vessel RadiationSurveillance Program,R. Auerswald, et.
al., dated July 1995.
- 5. ASTM E208, StandardTest Methodfor ConductingDrop-Weight Test to Determine Nil-Ductility Transition Temperature of FerriticSteels, in ASTM Standards, Section 3, American Society for Testing and Materials, Philadelphia, PA.
- 6.Section XI of the ASME Boiler and Pressure Vessel Code, Appendix G.FractureToughness Criteria for ProtectionAgainst Failure
- 7. ASTM E1 85-82, StandardPracticefor ConductingSurveillance Testsfor Light-Water Cooled NuclearPower Reactor Vessels, in ASTM Standards, Section 3, American Society for Testing and Materials, Philadelphia, PA.
- 8. Procedure RMF 8402, Surveillance Capsule Testing Program,Revision 2.
- 9. Procedure RMF 8102, Tensile Testing, Revision 1.
- 10. Procedure RMF 8103, Charpy Impact Testing, Revision 1.
- 11. ASTM E23-02a, StandardTest Methodfor Notched Bar Impact Testing ofMetallic Materials, in ASTM Standards, Section 3, American Society for Testing and Materials, Philadelphia, PA, 2002.
- 12. ASTM A370-97a, StandardTest Methods and Definitionsfor Mechanical Testing of Steel Products, in ASTM Standards, Section 3, American Society for Testing and Materials, Philadelphia, PA, 1997.
- 13. ASTM E8-01, StandardTest Methods for Tension Testing of Metallic Materials, in ASTM Standards, Section 3, American Society for Testing and Materials, Philadelphia, PA, 2001.
- 14. ASTM E21-92 (1998), StandardTest Methods for Elevated Temperature Tension Tests ofMetallic Materials, in ASTM Standards, Section 3, American Society for Testing and Materials, Philadelphia, PA, 1998.
References
8-2
- 15. ASTM E83-93, StandardPracticefor Verification and ClassificationofExtensometers, in ASTM Standards, Section 3, American Society for Testing and Materials, Philadelphia, PA, 1993.
- 16. WCAP-14370, Use ofthe Hyperbolic Tangent FunctionforFittingTransition Temperature Toughness Data,T. R. Mager, et al, May 1995.
- 17. Regulatory Guide RG-1.190, Calculationaland DosimetryMethodsfor DeterminingPressureVessel NeutronFluence, U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, March 2001.
- 18. WCAP-14040-NP-A, Revision 4, Methodology Used to Develop Cold OverpressureMitigating System Setpoints andRCS Heatup and Cooldown Limit Curves, May 2004.
- 19. RSICC Computer Code Collection CCC-650, DOORS 3.1, One, Two- and Three-Dimensional Discrete OrdinatesNeutron/PhotonTransport Code System, August 1996.
- 20. RSIC Data Library Collection DLC-1 85, "BUGLE-96, Coupled 47 Neutron, 20 Gamma-Ray Group Cross Section Library Derived from ENDFIB-VI for LWR Shielding and Pressure Vessel Dosimetry Applications," March 1996.
- 21. CPSES-200401979, "Transmittal of Design Information for Unit 2 Fluence Analysis," August 2004.
References
A-O APPENDIX A VALIDATION OF THE RADIATION TRANSPORT MODELS BASED ON NEUTRON DOSIMETRY MEASUREMENTS Appendix A
A-I A.1 Neutron Dosimetry Comparisons of measured dosimetry results to both the calculated and least squares adjusted values for all surveillance capsules withdrawn from service to date at 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."EA"l] One of the main purposes for presenting this material is to demonstrate that the overall measurements agree with the calculated and least squares adjusted values to within +/- 20% as specified by Regulatory Guide 1.190, thus serving to validate the calculated neutron exposures previously reported in Section 6.2 of this report. This information may also be useful in the future, in particular, as least squares adjustment techniques become accepted in the regulatory environment.
A. 1.1 Sensor Reaction Rate Determinations In this section, the results of the evaluations of the two neutron sensor sets withdrawn 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:
Azimuthal Withdrawal Irradiation Location Time Time [EFPY1 Capsule ID U 31.50 Dual End of Cycle I 0.91 X 31.5° Dual End of Cycle 7 8.83 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 and X are summarized as follows:
Reaction Capsule U Capsule X Sensor Material Of Interest Appendix A
A-2 Copper 63Cu(n,a)6oCo X X lIon 5Fe(np)-4Mn X X Nickel 58Ni(n,p) 58Co X X Uranium-238 238U(n 37 Cs X X137 2 7 Neptunium-237 3 Np(n, 13Cs X X Cobalt-Aluminum* 59Co(n,y)6oCo X X
- The cobalt-aluminum measurements for this plant include both bare wire and cadmium-covered sensors.
Since all of the dosimetry monitors were accommodated within the dosimeter block centered at the radial, azimuthal, and axial center of the material test specimen array, gradient corrections were not required for these reaction rates. Pertinent physical and nuclear characteristics of the passive neutron sensors are listed in Table A-1.
The use of passive monitors such as those listed above does not yield a direct measure of the energy dependent neutron flux at the point of interest. Rather, the activation or fission process is a measure of the integrated effect that the time and energy dependent neutron flux has on the target material over the course of the irradiation period. An accurate assessment of the average neutron flux level incident on the various monitors may be derived from the activation measurements only if the irradiation parameters are well known. In particular, the following variables are of interest:
- the measured specific activity of each monitor,
- the physical characteristics of each monitor,
- the operating history of the reactor,
- the energy response of each monitor, and
- the neutron energy spectrum at the monitor location.
Results from the radiometric counting of the neutron sensors from Capsule U are documented in Reference A-2. The radiometric counting of the sensors from Capsule X was carried out by Pace Analytical Services, Inc., located at the Westinghouse Waltz Mill Site. In all cases, the radiometric counting followed established ASTM procedures. Following sample preparation and weighing, the specific activity of each sensor was determined by means of a high-resolution gamma spectrometer. For the copper, iron, nickel, and cobalt-aluminum sensors, these analyses were performed by direct counting of each ofthe individual samples. In the case of the uranium and neptunium fission sensors, the analyses Appendix A
A-3 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 and X 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 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 and X is given in Table A-2.
Having the measured specific activities, the physical characteristics of the sensors, and the operating history of the reactor, reaction rates referenced to full-power operation were determined from the following equation:
R= A No F Y P Cj [1P- etj] [e-'t']
Pref where:
R = Reaction rate averaged over the irradiation period and referenced to operation at a core power level of Prf (rps/nucleus).
A Measured specific.activity (dps/gm).
No = Number of target element atoms per gram of sensor.
F = Atom fraction of the target isotope in the target element.
Y = Number of product atoms produced per reaction.
Pj Average core power level during irradiation period j (MW).
Prcf = Maximum or reference power level of the reactor (MW).
Cj = Calculated ratio of 4(E > 1.0 MeV) during irradiation period j to the time weighted average 4(E > 1.0 MeV) over the entire irradiation period.
X = Decay constant of the product isotope (1/sec).
tj = Length of irradiation period j (sec).
td = Decay time following irradiation period j (sec).
and the summation is carried out over'the total number of monthly intervals comprising the irradiation period.
In the equation describing the reaction rate calculation, the ratio [Pj]/[Pmd accounts for month-by-month variation of reactor core power level within any given fuel cycle as well as over multiple fuel cycles. The ratio Cj, which was calculated for each fuel cycle using the transport methodology discussed in Section 6.2, accounts for the change in sensor reaction rates caused by variations in flux level induced by Appendix A
A-4 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 "U 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 235U Impurity/Pu Build-in 0.872 0.803 8 U(yf)
-23 0.966 0.966 Net 238 U Correction 0.842 0.776 3'Np(y,f) 0.990 0.990 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 and X 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 238 U impurities, plutonium build-in, and gamma ray induced fission effects.
Appendix A
A-5 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 ¢(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, Ri + jb =E(Uig +/- 8oI )((Pg + 8) g relates a set of measured reaction rates, R4, to a single neutron spectrum, f, through the multigroup dosimeter reaction cross-section, sig, each with an uncertainty B. 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 codeEA- 3] 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 two in-vessel capsules withdrawn to date.
The application of the least squares methodology requires the following input:
I - The calculated neutron energy spectrum and associated uncertainties at the measurement location.
2 - The measured reaction rates and associated uncertainty for each sensor contained in the multiple foil set.
3 - The energy dependent dosimetry reaction cross-sections and associated uncertainties for each sensor contained in the multiple foil sensor set.
For the 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 Appendix A
A-6 dosimetry cross-section librarylA4]. The SNLRML library is an evaluated dosimetry reaction cross-section compilation recommended for use in LWR` evaluations by ASTM Standard E101 8, "Application of ASTM Evaluated Cross-Section Data File, Matrix E 706 (fIB)".
The uncertainties associated with the measured reaction rates, dosimetry cross-sections, and calculated neutron spectrum were input to the least squares procedure in the form of variances and covariances.
The assignment of the input uncertainties followed the guidance provided in ASTM Standard E 944, "Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance."
The following provides a summary of the uncertainties associated with the least squares evaluation of the 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 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 CU(n,a)6OCo 5%
54 Fe(n,p)54 Mn 5%
58Ni(n,p)sSCo 5%
238U(nf)l3 7Cs 10%
237 Np(n,f)137 Cs 10%
59Co(n,y)6Co 5%
These uncertainties are given at the la level.
Dosimetry Cross-Section Uncertainties The reaction rate cross-sections used in the least squares evaluations were taken from the SNLRML library. This data library provides reaction cross-sections and associated uncertainties, including covariances, for 66 dosimetry sensors in common use. Both cross-sections and uncertainties are provided in a fine multigroup structure for use in least squares adjustment applications. These cross-sections were compiled from the most recent cross-section evaluations and they have been tested with respect to their accuracy and consistency for least squares evaluations. Further, the library has been empirically tested for use in fission Appendix A
A-7 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 63Cu(n,a)6OCo 4.08-4.16%
54 Fe(n,p)5 4 Mn 3.05-3.11%
u8 Ni(n,p) 58 Co 4.49-4.56%
238U(nf)137CS 0.54-0.64%
237 Np(n,f)137 Cs 10.32-10.97%
59 Co(n,y)6OCo 0.79-3.59%
These tabulated ranges provide an indication of the dosimetry cross-section uncertainties associated with the sensor sets used in LWR irradiations.
Calculated Neutron Snectrum 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 =R2+Rg *Rg. *Pgg.
where Rn specifies an overall fractional normalization uncertainty and the fractional uncertainties R. and Rg, specify additional random groupwise uncertainties that are correlated with a correlation matrix given by:
Pgg =[I-O]ogg8 +Oe H Appendix A
A-8 where (g g') 2 29 The first term in the correlation matrix equation specifies purely random uncertainties, while the second term describes the short-range correlations over a group range y (0 specifies the strength of the latter term). The value of 8 is 1.0 when g g', and is 0.0 otherwise.
The set of parameters defining the input covariance matrix for the Comanche Peak Unit 2 calculated spectra was as follows:
Flux Normalization Uncertainty (R.) 15%
Flux Group Uncertainties (Rg, Rg')
(E > 0.0055 MeV) 15%
(0.68 eV < E < 0.0055 MeV)29%
(E < 0.68 eV) 52%
Short Range Correlation (0)
(E > 0.0055 MeV)0.9 (0.68 eV < E < 0.0055 MeV)0.5 (E < 0.68 eV) 0.5 Flux Group Correlation Range (y)
(E> 0.0055 MeV)6 Appendix A
A-9 (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 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 8% for iron atom displacement rate. Again, the uncertainties from the least squares evaluation are at the la level.
Further comparisons of the measurement results (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 (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 1.16 for the 10 samples included in the data set. The overall average M/C ratio for the entire set of Comanche Peak Unit 2 data is 1.02 with an associated standard deviation of 7.2%.
In the comparisons of best estimate and calculated fast neutron exposure parameters, the corresponding BE/C comparisons for the capsule data sets range from 0.99 to 1.01 for neutron Appendix A
A-10 flux (E > 1.0 MeV) and from 1.00 to 1.01 for iron atom displacement rate. The overall average BE/C ratios for neutron flux (E > 1.0 MeV) and iron atom displacement rate are 1.00 with a standard deviation of 1.3% and 1.00 with a standard deviation of 0.2%, 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.
Appendix A
A-1l Table A-1 Nuclear Parameters Used In The Evaluation Of Neutron Sensors Target 90% Response Fission Monitor Reaction of Atom Range Product Yield Material Interest Fraction (MeV) Half-life (%)
63 Copper Cu (n,a) 0.6917 4.9-11.9 5.271 y Iron 54Fe (np) 0.0585 2.1 -8.5 312.1 d 58 Nickel Ni (np) 0.6808 1.5 - 8.3 70.82 d Uranium-238 2U (n,f) 1.0000 1.3 -6.9 30.07 y 6.02 Neptunium-237 23 7Np (n,f) 1.0000 0.3 -3.8 30.07 y 6.17 Cobalt-Aluminum 59 Co (ny) 0.0015 non-threshold 5.271 y Note: The 90% response range is defined such that, in the neutron spectrum characteristic of the 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.
Appendix A
A-12 Table A-2 Monthly Thermal Generation During The First Seven 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 10/15/01, and 3458 MWt from 10/16/01 through the End of Cycle 7)
- Thermal Thermal Thermal
- Generation Generation Generation Year Month (MWt-hr) Year Month (MWt-hr) Year Month (MWt-hr) 1993 3 5239 1996 3 0 1999 .3 1548126 1993 4 . 665227 ; 1996 4. 0 1999 4 473690 1993 5 499862 1996 5 1738972 1999 5 2536163 1993 6 0 I 1996 6. 2329301 1999 6 2446800 1993 -7 1398237 1996- 7 2530637 1999 7 2533421 1993 8 2506266 1996. 8 2532626 1999 8 2535877 1993 9 1317192 1996 .9 2011808 1999 .9 2454020 1993' 10 2397305 1996 10 2353951 1999 10 2547941 1993 '11 2066821 1996 11 2449903 1999 11 2478920 1993 12 2512243 1996 12 2515648 1999 12 2561649 1994 1 2471392 1997 1 2118763 2000 1 2558037 1994 2 1545102 1997 2 2281115 2000 2 2396090 1994 3 1165989 1997 3 2536640 2000 3 2559136 1994 4 1225995 1997 4 2450049 2000 4 2476416 1994 5 0 1997 5 2144436 2000 5 2561079 1994 6 608905 1997 6 2368587 2000 6 2472280 1994 7 2417607 1997 7 2530139 2000 7 2558036 1994 8 1728640 1997 8 2536238 2000 8 2561286 1994 9 2323301 1997 9 2451498 2000 9 2383888 1994 10 342436 1997 10 1958440 2000 10 O0 1994 11 317387 1997 11 0 2000 11 1926717 1994 12 2534919 1997 12 1470859 2000 12 2560103 1995 1 2527469 1998 1 2532970 2001 1 2560732 1995 2 2280649 1998 2 2227110 2001 2 2308856 1995 3 2496279 1998 .3 2428176 2001 3 2551290 1995 4 2291046 1998 4 2450649 2001 4 2478855 1995 S 1551323 1998 5 2533092 2001 5 2561154 1995 6 2414907 1998 6 2454480 2001 6 2474728 1995 7 2537455 1998 7 2285176 2001 7 2431971 1995 8 2533692 1998 8 2048721 2001 8 2560721 1995 9 2451091 1998 9 2281630 2001 9 2478056 1995 10 2537946 1998 10 2532717 2001 10 2565724 1995 11 2447406 1998 11 2450886 2001 11 2486883 1995 12 2116020 1998 12 2535523 .2001 12 2569796 1996 1 2528370 1999 1 2312036 2002 1 2563715 1996 2 1731998 1999 2 2285274 2002 2 2320836 Appendix A . .
A-13 Table A-2 cont'd Monthly Thermal Generation During The First Seven 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 10115101, and 3458 MWt from 10116/01 through the End of Cycle 7)
Thermal Generation Year Month (MWt-hr) 2002 3 2419437 2002 4 0 2002 5 1996301 2002 6 2333719 2002 7 2509555 2002 8 2542003 2002 9 2468447 2002 10 2553421 2002 11 2473948 2002 12 2563144 2003 1 2560486 2003 2 2315079 2003 3 2567033 2003 4 2475564 2003 5 1320086 2003 6 2465264 2003 7 1118001 2003 8 2547906 2003 9 2473497 2003 10 281172 Appendix A
A-14 Table A-3 Calculated Cj Factors at the Surveillance Capsule Center Core Midplane Elevation Fuel Cycle Length *(E> 1.0 MeV) [n/cm2-s]
Cycle [EFPS] Capsule U Capsule X 1 2.87E+07 1.1OE+11 1.1OE+11 2 3.73E+07 7.13E+10 3 4.42E+07 8.1IE+10 4 3.84E+07 7.40E+1 0 5 4.52E+07 7.28E+10 6 4.36E+07 - 7.32E+10 7 4.12E+07 8.01E+10 Average 1.1OE+11 7.90E+10 Fuel Cycle Length C_ _ l Cycle [EFPS] Capsule U Capsule X 1 2.87E+07 1.000 1.389 2 3.73E+07 0.902 3 4.42E+07 1.026 4 3.84E+07 0.937 5 4.52E+07 0.921 6 4.36E+07 0.927 7 4.12E+07 1.013 Average 1.000 1.000 Appendix A
A-15 Table A-4 Measured Sensor Activities And Reaction Rates Surveillance Capsule U Radially Radially Adjusted Adjusted Measured Saturated Saturated Reaction Activity Activity Activity Rate Reaction Location (dps/g) (dps/g) (dps/g) (rps/atom) 6 3Cu (n,cz) 60Co Top 4.78E+04 4.56E+05 4.56E+05 6.96E-17 Middle 4.28E+04 4.09E+05 4.09E+05 6.24E-1 7 Bottom 4.29E+04 4.10E+05 4.10E+05 6.25E-17 Average 6.48E-17 4Fe (n,p) 54Mn Top 1.39E+06 4.09E+06 4.09E+06 6.48E-15 Middle 1.27E+06 3.73E+06 3.73E+06 5.92E-15 Bottom 1.27E+06 3.73E+06 3.73E+06 5.92E-15 Average 6.11E-15 58Ni 5 (n,p) "Co Top 1.30E+07 6.06E+07 6.06E+07 8.68E-15 Middle 1.21E+07 5.64E+07 5.64E+07 8.08E-15 Bottom 1.21E+07 5.64E+07 5.64E+07 8.08E-15 Average 8.28E-15 238u (nf) 137CS (Cd) Middle 1.37E+05 6.69E+06 6.69E+06 4.39E-14
'3sU (nf) 13Cs (Cd) 5 239 Including 23U, Pu, and y,fission corrections: 3.70E-14 237 Np (nf) 137CS (Cd) Middle 1.21E+06 5.91E+07 5.91E+07 3.77E-13 237Np (n,f) 137CS (Cd) Including y,fission correction: 3.73E-13 5 9Co (ny) 6 Co Top . 9.83E+06 9.39E+07 9.39E+07 6.12E-12 Middle 1.03E+07 9.84E+07 9.84E+07 6.42E-12 Bottom 1.03E+07 9.84E+07 9.84E+07 6.42E-12 Average 6.32E-12 "Co (n,y) '0 Co (Cd) Top 5.29E+06 5.05E+07 5.05E+07 3.30E-12 Middle 5.65E+06 5.40E+07 5.40E+07 3.52E-12 Bottom '5.55E+06 5.30E+07 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.
- 2) The average 238U (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.
- 3) The average 237Np (nf) 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.
Appendix A
A-16 Table A-4 cont'd Measured Sensor Activities And Reaction Rates Surveillance Capsule X Radially Radially Adjusted Adjusted Measured Saturated Saturated Reaction Activity Activity Activity Rate Reaction Location (dps/g) (dps/g) (dps/g) (rps/atom) 63 Cu (n,a) 'OCo 'Top 1.91E+05 3.04E+05 3.04E+05 4.64E-17 Middle 1.71E+05 2.72E+05 2.72E+05 4.15E-17 Bottom 1.68E+05 2.67E+05 2.67E+05 4.08E-17 Average 4.29E-17 54Fe (n,p) 5Mn Top 2.44E+06 3.08E+06 3.08E+06 .4.88E-15 Middle 2.23E+06 2.82E+06 2.82E+06 4.46E-15 Bottom 2.18E+06 2.75E+06 2.75E+06 4.36E-15 Average 4.57E-15 "Ni (np) 58Co Top 2.48E+07 4.68E+07 4.68E+07 6.70E-15 Middle 2.29E+07 4.32E+07 4.32E+07 6.19E-15 Bottom 2.25E+07 4.25E+07 4.25E+07 6.08E-15 Average 6.32E-15 23'U (nf) '17Cs (Cd) Middle 9.58E+05 5.30E+06 5.30E+06 3.48E-14 23sU (nf) 137Cs (Cd) Including 23U, 239pu, and y,fission corrections: 2.70E-14 237Np (n,f) 13'Cs (Cd) Middle' 7.11E+06 3.94E+07 3.94E+07 2.51E-13 237Np (nf) 137CS (Cd) Including yfission correction: 2.49E-13
"'Co (ny) 60Co Top 3.84E+07 6.11E+07 6.1 1E+07 3.99E-12 Middle 3.91E+07 6.22E+07 6.22E+07 4.06E-12 Bottom 4.03E+07 6.41E+07 6.41E+07 4.18E-12 Average 4.08E-12 "Co (ny) 60Co (Cd) Top 2.10E+07 3.34E+07 3.34E+07 2.18E-12 Middle 2.14E+07 3.41E+07 3.41E+07 2.22E-12 Bottom :2.20E+07 3.50E+07 3.50E+07 2.28E-12 Average 2.23E-12 Notes: 1) Measured specific activities are indexed to a counting date of November 26, 2003.
- 2) The average 238U (n,f) reaction rate of 2.70E-14 includes a correction factor of 0.803 to account for plutonium build-in and an additional factor of 0.966 to account for photo-fission effects in the sensor.
- 3) The average 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.
Appendix A
A-17 Table A-5 Comparison of Measured, Calculated, and Best Estimate Reaction Rates At The Surveillance Capsule Center Capsule U Reacn Rate rps/atoml Best Reaction Measured Calculated Estimate M/C M/BE 6"Cu(n,af)Co 6.48E-17 5.60E-17 6.13E-17 1.16 1.06 4Fe(n,p)4Mn 6.11E-15 6.39E-15 6.31E-15 0.96 0.97 58Ni(n,p)"Co 8.28E-15 8.99E-15 8.74E-15 0.92 0.95 238U(n f)137 CS (Cd) 3.67E-14 3.48E-14 3.41E-14 1.05 1.08 237 Np(nf)13 7Cs (Cd) 3.73E-13 3.45E-13 3.57E-13 1.08 1.04
' 9Co(n,y)6Co 6.32E-12 4.96E-12 6.20E-12 1.27 1.02 5 Co(n,y)oCo (Cd) 3.42E-12 3.45E-12 3.47E-12 0.99 0.99 Note: See Section A.1.2 for details describing the Best Estimate (BE) reaction rates.
Capsule X Reaction Rate rPs/atoml Best Reaction Measured Calculated Estimate M/C M/BE 63Cu(n,() 60 Co 4.29E-17 4.30E-17 4.25E-17 1.00 1.01 54Fe(n,p) 54Mn 4.57E-15 4.74E-15 4.62E-15 0.96 0.99 58Ni(n,p)5"Co 6.32E-15 6.63E-15 6.46E-15 0.95 0.98 23 8 U(nf)137Cs (Cd) 2.70E-14 2.53E-14 2.50E-14 1.07 1.08 37Np(n,f)'3 7 Cs (Cd) 2.49E-13 2.46E-13 2.48E-13 1.01 1.00 59Co(n,y) Co 4.08E-12 3.49E-12 4.01E-12 1.17 1.02 59 Co(ny)60Co (Cd) 2.23E-12 2.43E-12 2.26E-12 0.92 0.99 Note: See Section A. 1.2 for details describing the Best Estimate (BE) reaction rates.
Appendix A
A-18 Table A-6 Comparison of Calculated and Best Estimate Exposure Rates At The Surveillance Capsule Center 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 Displacement Rate [dpalsl Best Uncertainty Capsule ID Calculated Estimate (1a) BE/C U 2.15E-10 2.16E-10 8% 1.01 X 1.54E-10 1.54E-10 ; 8% 1.00 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.
Appendix A
A-19 Table A-7 Comparison of Measured/Calculated (M/C) Sensor Reaction Rate Ratios Including all Fast Neutron Threshold Reactions Note: The overall average MWC ratio for the set of 10 sensor measurements is 1.02 with an associated standard deviation of 7.2%.
Table A-8 Comparison of Best Estimate/Calculated (BE/C) Exposure Rate Ratios BE/C Ratio Capsule ID *(E > 1.0 MeV) dpals U 0.99 1.01 X 1.01 1.00 Average 1.00 1.00
% Standard Deviation 1.3 0.2 Appendix A
A-20 Appendix A 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-143 15, "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. A. Schmittroth, FERRETDataAnalysis Core, HEDL-TME 79-40, Hanford Engineering Development Laboratory, Richland, WA, September 1979.
A-4. RSIC Data Library Collection DLC-1 78, "SNLRML Recommended Dosimetry Cross-Section Compendium", July 1994.
Appendix A
B-0 APPENDIX B LOAD-TIME RECORDS FOR CHARPY SPECIMEN TESTS
- Specimen prefix "CL" denotes Intermediate Shell Plate, Longitudinal Orientation
- Specimen prefix "Cr' denotes Intermediate Shell Plate, Transverse Orientation
- Specimen prefix "CW" denotes Weld Material
- Specimen prefix "CH"'denotes Heat-Affected Zone material
- Load (1) is in units of lbs
- Time (I) is in units of milli seconds Appendix B
B- I 5000.00j1 4000.00.
D..
i' 3000.00 2000.00 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)
CL52, -500 F I
5000.00.
4000.00].
3000.0 2000.00.
1000.00 0.00 OfOm 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)
CL60, -400 F Appendix B
B-2 SO50.00 4000.00 s
6- 3000.00 0
-J 2000.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time.1 (ms)
I CL59, -25TF
.0 0
-J 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (=s)
CL57, -250 F Appendix B
B-3 20
-J 03 O
Time-1 (ms)
-J CL58, -10F Q
17 Cs 0.00 1.00 2.00 3.00 4.00 5.00 6.00 0
Time-2 ( s)
.CL53, 25°F Appendix B
B4 n 3000.00
- 11 i 2000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 5.00 Time-1 (ITns)
CL46, 25 0F 5000.001 4000.00{
n 3000.00 2000.001T 1000.000T, , ^_,
0.00-0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)
CL54, 40TF Appendix B
B-5 5000.00.
4000.00 6 3000.001 0
.-- 1 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)
CL47, 60TF 0
.4 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-i (ms)
CL51, 750 F Appendix B
B-6 XI I0
-j 2.00 3.00 6.00 Time-i (ms)
. CL48, 110 0 F 0
-J 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)
CL49, 1500 F Appendix B
B-7 5000.00 4000.00 a
.i 3000.00-0
-J 2000.00-Time-1 (ws)
CLSO, 1750 F G
0
-j 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)
CL56, 2000 F Appendix B
B-8
- 5000.00 4000.00 s 3000.00 0
2000.00 l 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (is)
CL55, 2250 F 5000.00~
4000.00
.03000.00-0
-J.
2000.00.
1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)
CT54, -1000 F Appendix B
B-9 5000.00 4000.00
.0
=53000.00l 2000.00 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)
CT55, -500 F 5000.001 4000.00-3 3000.00 i 2000.001 1000.00 0.00 0.00 1.00 2.00 3.00 4.0O 5.00 6.00 Time-I (ms)
CT60, 0F Appendix B
B-10 5000.00.
4000.00
- 3000.00l 2000.00 j 1000.00].
0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)
- CT47, 250 F 4000.001 0 3000.00+
2000.00.
0.00 Time-1 (MS)
CT53, 500 F Appendix B
B-1l 5000.00 4000.00-
-0
. 3000.00 0
2000.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (Ms)
CTI51, 60 0F i
4000.00.j 4 000.00 00.00 2000.00 1 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I ins)
CT59, 75TF Appendix B
B-12
.0
-0
-J 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)
CT58, 1000 F 0
0
-J 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)
CT49, 125°F Appendix B
B-13 5000.00 4000.00
_3000 l a0
-j 2000.00 looonoo 0.00, ,
0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)
CT48, 150TF 5000.00 4000.00.f 3000.00V 20 0 0 .0 0l o o7 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)
CT46, 175 0F Appendix B
B-14 4000.001
- 3000.00 2000.00 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-i (is)
CT52, 2000 F 5000.00 4000.001
's 3000.001 2000.00 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-i (is)
CT50, 2250 F Appendix B
B-15
.0 r-0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-i (ms)
.0 0
-j CT56, 250TF 0.00 1.00 2.00 3.00 4.00 500 6.00 Time-I (ms)
CM57, 275TF Appendix B
B-16 5000.00f 4000.00-i 3000.00 0 1 2000.00 1000.00!
1 +l l WO.O s
^ . _ ^
- 0. 0 DM 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)
-CW48, -100WF I
I 4000.001 m 3000.001
-° 2000.00 1000.00V L n I D a 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)
CW47, -500 F Appendix B
B-17 9
,6 300.00, as 2000.00
.00 3.00 6.00 Time-I (ms)
CW52, -250 F 5000.00+
4000.001
.0 3000.00
-J 2000.00
- 1 l
.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ins)
CW46, 0F Appendix B
B-18
.0
-j 0.00 1.00 2.00 3.00 4.00 5.00 6.00
- . Time-1 (ms)
- CW57, 250 F 0
-J 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)
CW49, 250 F Appendix B
B- 19 5000.00 4000.00
.s 3000.00 2000.00 1000.00 /
0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)
CW51, 500 F 5000.00' T r 4000.001
.E 3000.00-2M2000.0.f 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Tine-1 (ins)
CW60 750 F Appendix B
B-20 0 3000.00 2000.00 \
1000.001 0.00; 0.00 1.00 2.00 3 .00 4.00 5.00 6.00 Tme.I1 (Ms)
CW53, 755°F 4000.001 r 3000.00-2000.001 1000.001 0.00 i i l 0.00 1.00 2.00 3 .00 4.00 5.00 6.00 Time-1 (ms)
CW55, 135 0F Appendix B
B-21 5000.O0j 4000.001 3WO. <E 22000.00j 1000.00\
0.00-0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)
CW50, 175-F 5000 .00 4000.00
.0 2000.00-1000.00k 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)
- CW54, 200'F Appendix B
B-22 5000.001 4000.00 3000.00 1 2000.00 1000.00:
0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-i (ms)
CW56, 2000 F 000.00.
4000.00 5 3000.001 2000.00 \
1000.00k 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)
CW58, 2250 F Appendix B
B-23 6- 3000.001 0 1
' I 2000.001 1 000.00V 0.00 i 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)
CW59, 250TF 5000.00 4000.001 6- 3000.00f 2000.00 1 1000.00.
0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)
CH53, -1750 F Appendix B
B-24 5000.00' 4000.001 7 3000.001 2000.00 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Tie-I (ins)
CH58, -1300 F 5000.00 4000.00X a 3000.001 2000.001 1000.00-0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-i (ms)
CH47, -110 0 F Appendix B
B-25 Q
-J 00 ' ' -e -,
0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)
CH57, -100-F 0
-J 0.00 1.00 2.00 3.00 4.00 S.00 6.00 Time-I (ms)
CH60, -750 F Appendix B
B-26 5000.001 4000.001 c 3000.00T 2000.00 1 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-i (ms)
CH56,-500 F 5000.00 4000.00 1 x 3000.00 2000.001 1000.00X 0.00 l 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ins)
CH46, -350 F Appendix B
B-27 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)
CH49, -250 F 20 0r
-J 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)
CH5O, -100 F Appendix B
B-28 5000.00 4000.00
.0 6- 3000.00 0
-J 2000.00-1000.00-0.00 -
0 j .0 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)
CH51, 250 F so0oo.oo.
4000.00 .
I 3000.00.
0
-jI 0.00 1.00. 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)
CH52, 75TF Appendix B
B-29
-J 2, 3000.00 r;
2000.00 1000.00 0.00 0 .00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (is)
CH55, 100-F 5000.00 4000.00 a, 3000.00 r;
0
-J 2000.00 1000.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)
CH48, 1250 F Appendix B
B-30 5000.001 4000.00 2000.00 1000.00I 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 T:me-1 (ms)
CH59, 1250 F 5000.001 4000.00
= 3000.00 \
-J2000.00-1000.001 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)
CH54, 1500 F Appendix B
C-o APPENDIX C CHARPY V-NOTCH PLOTS FOR CAPSULE X USING SYMMETRIC HYPERBOLIC TANGENT CURVE-FITTING METHOD Contained in Table C- I are the upper shelf energy values used as input for the generation of the Charpy V-notch plots using CVGRAPH, Version 5.0.2. The definition for Upper Shelf Energy (USE) is given in ASTM E185-82, 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 set of three at each temperature Westinghouse 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 100% shear Charpy data as the USE. Hence, the USE values reported in Table C- I and used to generate the Charpy V-notch curves were determined utilizing this methodology.
The lower shelf energy values were fixed at 2.2 ft-lb for all cases.
Table C-i Upper Shelf Energy Values Fixed in CVGRAPH [ft-lb]
Material Unirradiated Capsule U Capsule X (ft-lbs) (ft-lbs) (ft-lbs)
Intermediate Shell Plate 115 118 120 R3807-2 (Longitudinal)
Intermediate Shell Plate 84 88 91 R3807-2 (Transverse)
Weld Metal 94 85 96 (Heat # 89833)
HAZ Material 116 127 116 Appendix C
UNIRRADIATED (LONGITUDINAL ORIENTATION)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 01:51 PM Page 1 Coefficients of Curve 1 A = 58.6 B = 56.4 C = 93.38 TO = 42.7 D = O.OOE+OO Equation is A + B * [Tanh((T-To)/(C+DT))]
Upper Shelf Energy=l 15.0(Fixed) Lower Shelf Energy=2.2(Fixed)
Temnp@30 ft-lbs=-9.4 Deg F Temp@50 ft-lbs=28.4 Deg F Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: LT Capsule: UNIRR Fluence: n/cm^A2 300
.250 tn
- 200 0
0 U-E 150 LU 0
z
> 100 50 o 4l=
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential
-80. 00 11. 00 9. 80 1.20
- 60. 00 6. 00 13.45 - 7.45
- 60. 00 12. 00 13.45 - 1. 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 - 1. 47
.00 33. 00 34.47 - 1. 47
.00 35. 00 34.47 .53 C-1
UNIRRADIATED (LONGITUDINAL ORIENTATION)
I :~Page 2 Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: LT Capsule: UNIRR Fluence: n/cmA2 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 i 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 1 15.00 106. 54 8; 46 260. 00 11 1. 00 113.94 -2. 94 260.00 114.00 113.94 .06 260. 00 118.00 113.94 4.06 320. 00 1 1 1. 00 114. 70 -3.70 320. 00 118.00 114.70 3.30 Correlation Coefficient = .950 C-2'
UNIRRADIATED (LONGITUDINAL ORIENTATION)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 02:06 PM Page 1 Coefficients of Curve 1 A = 41.42 B = 41.42 C = 89.07 TO = 47.28 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]
Upper Shelf L.E.=82.8 Lower Shelf L.E.=.0(Fixed)
Temp. @L.E. 35 mils=33.4 Deg F Plant: Comanche Peak 2 Material: SA533B 1 Heat: C5522-2 Orientation: LT Capsule: UNIRR Fluence: n/cmA2 200 150 a,
0 100 I- 50 0 50
~0 0t i n-3 sJ
-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential
- 80.00 1.00 4.50 -3. 50
- 60. 00 2.00 6.83 -4. 83
- 60. 00 2.00 6.83 -4. 83
-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 - 1. 29 C-3
UNIRRADIATED (LONGITUDINAL ORIENTATION)
Page 2 Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: LT Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input LE.: Computed L.E. Differential
.00 41.00 21.29 19.71 40.00 19.00 38.04 -19.04 40.00 27. 00 38.04 -11.04 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 o80.00 58.00 55.99 2.01 120.00 76.00 69.30 6.70 120.00 71.00 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 -1. 15 320. 00 79.00 82. 66 - 3.66 320.00 84.00 82.66 1.34 Correlation Coefficient = .962 C-4
UNIRRADIATED (LONGITUDINAL ORIENTATION)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 02:01 PM Page 1 Coefficients of Curve 1 A = 50. B = 50. C = 82.77 TO = 55.95 D = O.OOE+OO Equation is A + B * [Tanh((T-To)/(C+DT))]
Temperature at 50% Shear = 56.0 Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: LT Capsule: UNIRR Fluence: n/cmA2 125 100 to 75 1w Co
--a. 50 25 0 +-
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential
- 80. 00 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 1 1. 00 11.14 -. 14
-30. 00 25.00 11.14 13.86
.00 29. 00 20. 5 5 8.45
.00 17. 00 20. 55 -3. 55
.00 16. 00 20. 55 -4. 55 C-5
UNIRRADIATED (LONGITUDINAL ORIENTATION)
-> : Page 2 Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: LT Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential
.00 30.00 20. 55 9.45 40.00 21.00 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 I100.00 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 .72 260.00 100.00 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 C-6
UNIRRADIATED (TRANSVERSE ORIENTATION)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 03:35 PM Page 1 Coefficients of Curve 1 A = 43.1 B = 40.9 C = 107.72 TO = 23.65 D = O.OOE+OO Equation is A + B * [Tanh((T-To)/(C+DT))]
Upper Shelf Energy=84.0(Fixed) Lower Shelf Energy=2.2(Fixed)
Temp@30 ft-lbs=-12.1 Deg F Temp@50 ft-lbs=42.1 Deg F Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: TL Capsule: UNIRR Fluence: n/cmA2 300 250 (n
- 200 9
0 0
U-E 150 a) z 8 100 50 o0 4=
-300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential
-120.00 9. 00 7.51 1.49
- 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 - 1.48
- 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 C-7
UNIRRADIATED (TRANSVERSE ORIENTATION)
Page 2 Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: TL Capsule: UNIRR . Fluence: n/cmA2 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 18.03 260.00 80. 00 83. 00 -3. 00
_260. 00 82. 00 83. 00 - 1. 00 260. 00 84.00 83. 00 1.00 320. 00 78. 00 83. 67 -5.67 320.00 84. 00 83. 67 .33 Correlation Coefficient = .967 C-8
UNIRRADIATED (TRANSVERSE ORIENTATION)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 04:14 PM Page 1 Coefficients of Curve 1 A = 32.79 B = 32.79 C = 92.46 TO = 32.86 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]
Upper Shelf L.E.=65.6 Lower Shelf L.E.=.0(Fixed)
Temp. @L.E. 35 mils=39.1 Deg F Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: TL Capsule: UNIRR Fluence: nIcmA2 200 150 (0
E 0
rn R 100 50 0
-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential
-120.00 2.00 2.32 -. 32
-120.00 1. 00 2.32 - 1. 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 7.7 6 -3. 76
-30. 00 21. 00 13.40 7. 60
-30. 00 20. 00 13.40 6. 60 C-9 I I
- UNIRRADIATED (TRANSVERSE ORIENTATION)
Page 2 Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: TL Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. 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 -1.61 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 -1.20 I
80.00 52.00 48.20 3.80 120.00 55. 00 56.94 -1.94 120.00 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 C-10
UNIRRADIATED (TRANSVERSE ORIENTATION)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 04:11 PM Page 1 Coefficients of Curve 1 A = 50. B = 50. C = 76.68 TO = 62.67 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]
Temperature at 50% Shear = 62.7 Plant: Comanche Peak 2 Material: SA533B I Heat: C5522-2 Orientation: TL Capsule: UNIRR Fluence: n/cmA2 125 100 I-75 r-1..
0~ 50 25 0 I-
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential
-1 20. 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 C-11
UNIRRADIATED (TRANSVERSE ORIENTATION)
Page 2 Plant: Cornanche Peak 2 Material: SA53BI Heat: C5522-2 Orientation: Th ~Capsule: UNIRR Fluence: n/cMA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential
- 3 0. 00 25.0 0 8. 1 9 1 6. 81
. 00 1 3.0 0 1 6.3 2 .-3. 32
. 00 20. 00 1 6.3 2 3. 68
. 00 1 6. 0 0 1 6.3 2 - . 32 4 0. 00 38S.0 0 3 5.6 3 2. 37
- 40. 00 25. 00 3 5. 6 3 -1I0. 63
- 40. 00 3 0.0 0 3 5. 6 3 - 5.63 8 0. 0.0 4 8. 0 0 6 1.I11 - 13. 11I
- 80. 00 54. 00 6 1. I11 - 7. 11 8 0. 00 5 9. 0 0 6 1.I11 - 2. 11 120. 00 7 9. 0 0 8 1.6 9 - 2.69 120. 00 90. 00 .8 1.6 9 8. 3 1 12 0. 00 100. 00 8 1. 69 1 8.3 1 160. 00 1 00. 00 9 2.6 8 7. 32 160. 00 100. 00 9 2.6 8 7. 32 160. 00 1 00. 00 9 2. 6 8 7. 32 2 60. 00 100. 00 9 9.4 2 . 58 -
2 60. 00 100. 00 9 9.4 2 2 60. 00 1 00. 00 9 9.4 2 3 20. 00 1 00. 00 9 9. 8 8 12 3 20. 00 1 00. 00 9 9. 8 8 12 Correlation Coefficient = .984 C-1 2-
- .- . - - -- - .- . - - - . -- - - - - . ----- -.. ----- ---. . - - - . 1 1
UNIRRADIATED (WELD)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 04:20 PM Page 1 Coefficients of Curve 1 A = 48.1 B = 45.9 C = 107.15 TO = -4.93 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]
Upper Shelf Energy=94.0(Fixed) Lower Shelf Energy=2.2(Fixed)
Temp@30 ft-lbs=-49.6 Deg F Ternp@50 ft-lbs=-.4 Deg F Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 300 250 u7
- 200 8
0 0
U-150 a) z
> 100 50 o 4--
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential
- 120.00 10. 00 11. 80 - 1. 80
- 120.00 13.00 11. 80 1.20
-90. 00 16.00 17.78 - 1.78
- 90. 00 18.00 17.78 .22
-90. 00 29. 00 17.78 1 1. 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 C-13
UNIRRADIATED (WELD)
Page 2 Plant: Comanche Peak 2 . Material: SAW Heat: 89833 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 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 1.21 320. 00 99. 00 93.79 5.21 Correlation Coefficient = .984 C-14
UNIRRADIATED (WELD)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 04:28 PM Page 1 Coefficients of Curve 1 A = 38.02 B = 38.02 C = 91.24 TO = 7.89 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]
Upper Shelf L.E.=76.0 Lower Shelf L.E.=.0(Fixed)
Temp. @L.E. 35 mils=.7 Deg F Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: UNTRR Fluence: n/cmA2 200 150 In Co a 100 00 a) 50 n
-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential
- 120. 00 . 00 4.34 -4. 34
- 120. 00 1.00 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 - 1 3. 00
- 60. 00 11. 00 14. 00 -3. 00
-30. 00 20. 00 23. 08 -3. 08 C
UNIRRADIATED (WELD)
Page 2 Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. 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 - 1.73 260. 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 C-16
UNIRRADIATED (WELD)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 04:25 PM
- Page 1 Coefficients of Curve I A = 50. B = 50. C = 93.39 TO = -1.21 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]
Temperature at 50% Shear = -1.2 Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 125 100 5-co 75 C'
2.
4a, 50 0L 25 -_
0
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential
- 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. 11
- 60. 00 5. 00 22. 11 - 17. 11
- 60.00 30.00 22. 11 7.89
-30. 00 34. 00 35. 06 - 1. 06 C-17
UNIRRADIATED (WELD)
Page 2 Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 3 5.0
-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 00. 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 1 00. 00 99. 90 .10 Correlation Coefficient = .980 C-18
UNIRRADIATED (HEAT AFFECTED ZONE)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 04:33 PM Page 1 Coefficients of Curve 1 A = 59.1 B = 56.9 C = 84.54 TO = -61.79 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]
Upper Shelf Energy=l 16.0(Fixed) Lower Shelf Energy=2.2(Fixed)
Temp@30 ft-lbs=-109.5 Deg F Temp@50 ft-lbs=-75.4 Deg F Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 300 -_
250 -
, I 200 -
0 0
UL.
a150 -
4) z
> 100 -
50 -
o0
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential
- 220. 00 13.00 4. 83 8. 17
- 220. 00 15. 00 4. 83 10. 17
- 160. 00 11. 00 12. 35 -1. 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 -1 . 13
- 120. 00 29. 00 25. 13 3. 87
-90. 00 39.00 40. 79 -1. 79 C-19
UNIRRADIATED (HEAT AFFECTED ZONE)
Page 2 Plant: Comanche Peak 2 Material: SA533B 1 Heat: C5522-2 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 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.- 5 4 - 19. 54
.00 101.00 94. 59 6. 41
.00 11 1. 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 1 00. 00 128.00 I1 3. 5 8 14. 42 140. 00 106. 00 115.05 - 9.:05 140. 00 120. 00 I 15. 05 4. 95
- 140.00 124. 00 115.05 8.95 1 80. 00 100. 00 115.63 - 15. 63 Correlation Coefficient = .921 c-20
UNIRRADIATED (HEAT AFFECTED ZONE)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 05:02 PM Page 1 Coefficients of Curve 1 A = 36.41 B = 36.41 C = 76.16 TO = -46.04 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]
Upper Shelf L.E.=72.8 Lower Shelf L.E.=.0(Fixed)
Temp. @L.E. 35 mils=-48.9 Deg F Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: NA Capsule: UNIRR Fluence: nlcmA2 200 150 0
C
- 2. 100 Z0 50 0
-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential
- 220. 00 1. 00 .75 25
- 220. 00 1.00 .75 25
- 1 60. 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
- 1 2 0. 00 4.00 9.13 -5. 13
- 120.00 12. 00 9.13 2. 87
-90. 00 18.00 17.45 . 55 C-21
UNIRRADIATED (HEAT AFFECTED ZONE)
Page 2 Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. -. Computed L.E. 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 71. 00 65.94 5.06 1 00. 00 69. 00 71.28 -2.28
.100. 00 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 C-22
UNIRRADIATED (HEAT AFFECTED ZONE)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 04:38 PM Page 1 Coefficients of Curve 1 A = 50. B = 50. C = 69.21 TO = -40.34 D = O.OOE+OO Equation is A + B * [Tanh((T-To)/(C+DT))]
Temperature at 50% Shear = -40.3 Plant: Comanche Peak 2 Material: SA533B 1 Heat: C5522-2 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 125 100 I1 _ _ _ __
I-
'U a, 75 co) r- 0 0 50 0.
0
.0 25 8
X I8 0 -i . 1 . , i
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential
- 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
- 1 60. 00 1 1. 00 3.05 7. 95
- 120. 00 .00 9. 10 -9. 10
- 120. 00 13.00 9. 10 3.90
- 1 2 0. 00 9.00 9. 10 -. 10
-90. 00 28.00 19. 23 8.77 C-23
UNIRRADIATED (HEAT AFFECTED ZONE)
Page 2 Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 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
.00 100.00 76.24 23.76
- 40. 00 .100. 00 91. 06 8.94
- 40. 00 1 00. 00 91. 06 8.94
- 40. 00 1 00. 00 91.06 8.94 100. 00 1 00. 00 98. 30 1.70 100. 00 1 00. 00 98.30 1.70 140. 00 1 00. 00 99. 46 .54 140. 00 1 00. 00 99.46 .54 140. 00 1 00. 00 99. 46 .54 180.00 100. 00 99. 83 .17 Correlation Coefficient = .966 C-24
CAPSULE U (LONGITUDINAL ORIENTATION)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed o03/17/2004 01:51 PM Page 1 Coefficients of Curve 2 A = 60.1 B = 57.9 C = 86.68 TO = 42.11 D = O.OOE+O0 Equation is A + B * [Tanh((T-To)/(C+DT))]
Upper Shelf Energy=1 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: SA533B1 Heat: C5522-2 Orientation: LT Capsule: U Fluence: n/cmA2 300 250
, a 200 46..
0 0
U.
El 150 a) z
> 100 00 0
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential
-75. 00 8.00 9.48 - 1. 48
-50. 00 II. 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 C-25
CAPSULE U (LONGITUDINAL ORIENTATION)
- IPage 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 9 3.8 9 -5. 89 125. 00 106.00 103. 10 2. 90
- 150. 00 115.00 109. 13 5.87
- 200. 00 116.00 115.05 .95 250. 00 116.00 1 1'7. 05 - I1.05 300.00 127.00 117.70 9.330 Correlation Coefficient = .992 C
CAPSULE U (LONGITUDINAL ORIENTATION)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 02:06 PM Page 1 Coefficients of Curve 2 A = 41.23 B = 41.23 C = 93.56 TO = 33.6 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]
Upper Shelf L.E.=82.5 Lower Shelf L.E.=.0(Fixed)
Temp.@L.E. 35 mils=19.4 Deg F Plant: Comanche Peak 2 Material: SA533B 1 Heat: C5522-2 Orientation: LT Capsule: U Fluence: n/cm^2 200 150 2
iC 0
o I.
(Z 100 r-9 -
- 0 50 013 0
-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential
-75. 00 8.00 7.37 .63
-350. 00 10.00 11.83 - 1. 83
- 25. 00 17.00 18. 32 - 1. 32
- I0. 00 27.00 23. 29 3.71
.00 30. 00 27. 03 2. 97 10.00 32. 00 31. 04 .96
- 25. 00 32.00 37. 45 -5. 45
- 50. 00 46. 00 48. 38 - 2.38
- 72. 00 61.00 57. 26 3.74 C-27
CAPSULE U (LONGITUDINAL ORIENTATION)
- I - Page 2 Plant: Comanche Peak 2 Material: SA533B 1 Heat: C5522-2 Orientation: LT Capsule: U Fluence: n/cmA2 Charpy V-Notch Data Temperature Input LE. Computed LE. Differential 100. 00 65.00 66. 40 - 1. 40 125. 00 71. 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 C-28
CAPSULE U (LONGITUDINAL ORIENTATION)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 02:01 PM Page 1 Coefficients of Curve 2 A = 50. B = 50. C = 92.29 TO = 84.98 D = O.OOE+00 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/cmA2 125 100 co 0i 75 C,
0)
U a, 50 (L
25 0 I-
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential
-75. 00 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
.00 15.00 13. 69 1.31
- 10. 00 20. 00 16. 45 3. 55
- 25. 00 25. 00 21. 42 3. 58
- 50. 00 35.00 31.91 3. 09
- 72. 00 40. 00 43.01 -3. 01 C-29
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 Percent Shear Computed Percent Shear Differential 5 S.0 100.00 45. 00 58.07 - 1 3. 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 C-30
CAPSULE U (TRANSVERSE ORIENTATION)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 03:35 PM Page 1 Coefficients of Curve 2 A = 45.1 B = 42.9 C = 107.61 TO = 50.81 D = O.0OE+0O Equation is A + B * [Tanh((T-To)/(C+DT))]
Upper Shelf Energy=88.0(Fixed) Lower Shelf Energy=2.2(Fixed)
Temp@30 ft-lbs=11.3 Deg F Temp@50 ft-lbs=63.2 Deg F Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: TL Capsule: U Fluence: n/cmA2 300 250 (h
-. 200 8
0 0
LL M 150 C,
w
-z 8 100 0 --- ~-------------------
50
_ .P o -------------- 4--
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential
- 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 C-31
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 CVN Computed CVN Differential 100. 00 48. 00 63.45 - 15.45 125. 00 73. 00 70.7 4 2. 26 150.bo 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 C-32
CAPSULE U (TRANSVERSE ORIENTATION)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 04:14 PM Page 1 Coefficients of Curve 2 A = 35.8 B = 35.8 C = 117.55 TO = 45.7 D = O.O0E+0O Equation is A + B * [Tanh((T-To)/(C+DT))]
Upper Shelf L.E.=71.6 Lower Shelf L.E.=.0(Fixed)
Temp. @L.E. 35 mrils=43.1 Deg F Plant: Comanche Peak 2 Material: SA533B 1 Heat: C5522-2 Orientation: TL Capsule: U Fluence: n/cmA2 200 150 0E 100 3 ---
50
-- I 9- 9.1v 4 0
-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed L.E. 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. 11
- 72. 00 50.00 43. 68 6. 32 C-33
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 L.E. Differential 100.00 46. 00 51.26 -5. 26 125.00 54.00 56. 86 -2. 86 150. 00 67.00 61.23 i 5.77 200. 00 70. 00 66.77 3.23 250. 00 67. 00 69.46 -2. 46 300. 00 69.00 70. 68 - 1.68 Correlation Coefficient = .988 C-34
CAPSULE U (TRANSVERSE ORIENTATION)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/1712004 04:02 PM Page 1 Coefficients of Curve 2 A = 50. B = 50. C = 72.02 TO = 116.15 D = O.OOE+OO Equation is A + B * [Tanh((T-To)/(C+DT))J Temperature at 50% Shear = 116.2 Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: TL Capsule: U Fluence: n/cmA2 125 100 L..
75 C)
H 0~ 50 25 0 4-
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 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 I1. 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 C-35
CAPSULE U (TRANSVERSE ORIENTATION) i I Page 2 Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: TL Capsule: U 'Fluence:
- n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear 7
- Computed Percent Shear Differential 100.00 25.00 38.97 -13. 97
. 125.00 - 3 0. 00 56.11 - 26. 1 1 150.00 100.00 71.91 2 8. 09 200. 00 100.00 91. 12 8.88 250.00 100.00 97. 63 2. 37 300.00 1 00. 00 99.40 .60 Correlation Coefficient = .955 C-36
CAPSULE U (WELD)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 04:20 PM Page 1 Coefficients of Curve 2 A = 43.6 B = 41.4 C = 90.09 TO = -15.27 D = 0.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]
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 0,
, 200 0
0 U. _ _ _,.
2' 150 a)
_ _ _ __0 z
8 100
-- ~-0-------------- - .--------
C3. - - -
50 13 A
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential
- 125. 00 3.00 8. 86 -5. 86
-95. 00 11. 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 1.98
.00 48. 00 50.55 -2.55
- 50. 00 66. 00 69.25 - 3. 25 C-37
CAPSULE U (WELD)
Page 2 Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: U Fluence: n/cmA2 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 C-38
CAPSULE U (WELD)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 04:28 PM Page 1 Coefficients of Curve 2 A = 33.05 B = 33.05 C = 92. TO = -22.16 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]
Upper Shelf L.E.=66.1 Lower Shelf L.E.=.0(Fixed)
Temp.@L.E. 35 mils=-16.7 Deg F Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: U Fluence: n/cmA2 200 150 0
cn E100 L.
50 50 0 I-
-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential
- 125. 00 8.00 6.39 1.61
.9 5. 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
- C-39
II CAPSULE U (WELD)
Page 2 Plant: Comanche Peak 2 : Material: SAW Heat: 89833 Orientation: NA Capsule: U Fluence: n/cmA2 Charpy V-Notch Data t
Temperature Input L.E. Computed L.E. Differential I
- 72. 00 61.00 58.54 2.46 1 00. 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 C-40
CAPSULE U (WELD)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 04:25 PM Page 1 Coefficients of Curve 2 A = 50. B = 50. C = 67.17 TO = 21.52 D = O.OOE+O0 Equation is A + B * [Tanh((T-To)/(C+DT))]
Temperature at 50% Shear = 21.6 Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: U Fluence: n/cmA2 125 100 a
,1 014 Irr L- 11 co 75 II a) 4 co I1 10 z 11 11 11
- a. 50 II III III III 25 P IIII "D
I131, a 1?f 0
0 I
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential
- 1 25. 00 5.00 1.26 3. 74
-95. 00 5.00 3. 02 1.98
-75. 00 10. 00 5. 35 4. 65
- 60. 00 10. 00 8. 11 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 C-41
CAPSULE U (WELD)
Page 2 Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: U Fluence: nrcmA2 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 .1. 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 C-42
CAPSULE U (HEAT AFFECTED ZONE)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Pnnted on 03/17/2004 04:34 PM Page 1 Coefficients of Curve 2 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))]
Upper Shelf Energy=127.0(Fixed) Lower Shelf Energy=2.2(Fixed)
Temp@30 ft-lbs=-122.7 Deg F Temp@50 ft-lbs=-70.1 Deg F Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: NA Capsule: U Fluence: n/cmA2 300 250 (A
8, 200 09 0
U.
cm 150 CD w
> 100 50 50
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 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 1 00. 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 C-43
CAPSULE U (HEAT AFFECTED ZONE Page 2 FKlant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: NA Capsule: U Fluence: nkcmA2
- Charpy V-Notch Data Temperature Input CVN Computed CVN Differential
.00 78.00 81.43 -3. 43 25.00 90.00 91.44 - 1.44
- 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 C-44
- I
CAPSULE U (HEAT AFFECTED ZONE)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 05:02 PM Page 1 Coefficients of Curve 2 A = 38.9 B = 38.9 C = 126.43 TO = -36.72 D = O.00E+OO Equation is A + B * [Tanh((T-To)/(C+DT))]
Upper Shelf L.E.=77.8 Lower Shelf L.E.=.0(Fixed)
Temp. @L.E. 35 mils=-49.4 Deg F Plant: Comanche Peak 2 Material: SA533B I Heat: C5522-2 Orientation: NA Capsule: U Fluence: n/cmA2 200 150 (n
0 E
100 50 0 -
C5 C,,o
.3 0-3 t T_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
0 300
-;11: 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential
- 225. 00 2.00 3.77 - 1. 77
- 175.00 8.00 7. 85 .15
- 150. 00 9.00 11. 11 -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 C-45 I
CAPSULE U (HEAT AFFECTED ZONE)
Page 2-Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: NA Capsule: U -.Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential
. 00 50.00 49. 89 .11
- 25. 00 59.00 56.51 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 C-46
CAPSULE U (HEAT AFFECTED ZONE)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 04:39 PM Page 1 Coefficients of Curve 2 A = 50. B = 50. C = 99.81 TO = -31.2 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]
Temperature at 50% Shear = -31.1 Plant: Comanche Peak 2 Material: SA533B 1 Heat: C5522-2 Orientation: NA Capsule: U Fluence: n/cmA2 125 100 I,
M 75 U,
Cn CL 50 25 o 4==-
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential
-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
- 1 00. 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 6.90 C-47
CAPSULE U (HEAT AFFECTED ZONE)
Page 2 Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: NA Capsule: U Fluence: n/cmA2 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 11. 23 150.00 100. 00 97.42 2.58 200. 00 100.00 99.04 .96 Correlation Coefficient = .971 C-48
CAPSULE X (LONGITUDINAL ORIENTATION)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 63/17/2004 01:51 PM Page 1 Coefficients of Curve 3 A = 61.1 B = 58.9 C = 98.97 TO = 50.28 D = O.O0E+0O Equation is A + B * [Tanh((T-To)/(C+DT))]
Upper Shelf Energy=120.0(Fixed) Lower Shelf Energy=2.2(Fixed)
Temp@30 ft-lbs=-7.8 Deg F Temnp@50 ft-lbs=31.5 Deg F Plant: Comanche Peak 2 Material: SA533B I Heat: C5522-2 Orientation: LT Capsule: X Fluence: n/crm2 300 250
- 200 6
0 0
LL M 150 U-z
> 100 50
-. . - ... ----- -'° 0
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential
-50. 00 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 -1. 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 C-49
CAPSULE X (LONGITUDINAL ORIENTATION)
Page 2 Plant: Comanche Peak 2 Material: SA533B1 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. 49 110.00 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 C-50O
CAPSULE X (LONGITUDINAL ORIENTATION)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 02:07 PM
. Page 1 Coefficients of Curve 3 A = 39.15 B = 39.15 C = 99.41 TO = 52.76 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]
Upper Shelf L.E.=78.3 Lower Shelf L.E.=.0(Fixed)
Temp. @L.E. 35 mils=42.2 Deg F Plant: Comanche Peak 2 Material: SA533B 1 Heat: C5522-2 Orientation: LT Capsule: X Fluence: n/cmA2 200 150 U) 0 100 (U
50 0 4-
-300 0 . 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed L.E. 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
-2 5. 00 19.00 13.55 5. 45
-Io. 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 C-51
CAPSULE X (LONGITUDINAL ORIENTATION)
Page 2, I Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: LT Capsule: X Fluence: n/cmA2 Charpy V-Notch Data Temperature Input LE. Computed L.E. Differential
- 75. 00 46.00 47.76 -1. 76 1 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 C-52
CAPSULE X (LONGITUDINAL ORIENTATION)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 02:01 PM Page 1 Coefficients of Curve 3 A = 50. B = 50. C = 84.87 TO = 73.51 D = O.OOE+OO Equation is A + B * [Tanh((T-To)/(C+DT))]
Temperature at 50% Shear = 73.6 Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: LT Capsule: X Fluence: n/cmA2 125 100 I-
- 0) 75 U,..
a-a, 50 0) 25 0 4-
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential
-50.00 5.00 5. .16 . 16
-40. 00 5.00 6.45 - 1. 4 5
-25.00 10. 00 8.93 1. 07
-25. 00 10. 00 8. 93 1. 07
- 10. 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 - 1.22
- 60. 00 50. 00 42. 10 7.90 C-53
CAPSULE X (LONGITUDINAL ORIENTATION)
- IPage 2 Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: LT Capsule: X Fluence: n/cmA2 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 1 00. 00 91.62 8.38 200. 00 1 00. 00 95. 17 4.83 225.00 100.00 97.26 2. 74 Correlation Coefficient = .991 C-54
CAPSULE X (TRANSVERSE ORIENTATION)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 03:35 PM Page 1 Coefficients of Curve 3 A = 46.6 B = 44.4 C = 114.54 TO = 85.75 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]
Upper Shelf Energy=9 1.0(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: SA533B 1 Heat: C5522-2 Orientation: TL Capsule: X Fluence: n/cmA2 300-250-
-200 0
0 LL
- 150 z
> 100 . 1 4 o ....-....
50 -
0 37.00
.. 7 .2
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential
-100.00 34.00 5. 54 - 2. 54
-50. 00 95.00 96.79 - . 79
. 00 2 3. 00 18. 44 4 . 56 2 5. 00 28S. 00 25. 04 2 .9 6 5 0. 00 3 5.0 0 3 3. 18 1 . 82 6 0. 00 3 7. 00 3 6. 78 .2 2 7 5. 00 45. 00 4 2. 45 2 .5 5 100. 0 0 4 5. 00 5 2. 1 0 - 7. 1 0 12 5. 00 5 7. 00 6 1. 25 - 4.2 5 C-55
CAPSULE X (TRANSVERSE ORIENTATION)
- : -- Page 2 Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: TL Capsule: X Fluence: n/cmA2 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 C-56 1-.
CAPSULE X (TRANSVERSE ORIENTATION)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 04:14 PM Page 1 Coefficients of Curve 3 A = 36.44 B = 36.44 C = 129.38 TO = 100.68 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]
Upper Shelf L.E.=72.9 Lower Shelf L.E.=.0(Fixed)
Temp.@L.E. 35 mils=95.6 Deg F Plant: Comanche Peak 2 Material: SA533B 1 Heat: C5522-2 Orientation: TL Capsule: X Fluence: n/cmA2 200 U) 150 W
C 0
ar- 100 15
. 0. ................. .......................
50 0 . . . . . --..--.. . . ...-...-.. -- Zz '
-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential
- 100.00 00 33.14 - 3. 14
-50. 00 4. 00 66. 47 - 2. 47
- 14. (
14.1 )0
.00 12. 69 1.31 25.00 19. () 0 17.26 1.74 50.00 24. t00 22. 86 1.14 60.00 25. (00 25. 3 5 -. 35 75.00 32. (0 0 2 9. 3 0 2.70 I 00. 00 33. (00 3 6. 2 5 -3. 25 125.00 42. t00 443.21 - 1.21 C
CAPSULE X (TRANSVERSE ORIENTATION)
Page 2 Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: TL Capsule: X Fluence: n/cmh2 Charpy V-Notch Data Temperature Input LE. Computed L.E. Differential 150.00 50. 00 49. 70 .30 175.00 54. 00 55.34 -1. 34 200. 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 C-58 I
CAPSULE X (TRANSVERSE ORIENTATION)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 04:02 PM Page 1 Coefficients of Curve 3 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: n/cmA2 125 100 I-a) 75 CL 0
0~ 50 25 0 I-
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential
- 100. 00 2.00 2. 01 -. 01
-50. 00 5.00 5.37 -. 37
.00 15.00 13.54 1.46
- 25. 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 - 1.48 C-59
CAPSULE X (TRANSVERSE ORIENTATION)
Page 2 :
Plant: Comanche Peak 2 Material: SA533B 1 Heat: C5522-2 Orientation: TL Capsule: X Fluence: n/cmA2 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 C-60
CAPSULE X (WELD)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 04:20 PM Page 1 Coefficients of Curve 3 A = 49.1 B = 46.9 C = 61.35 TO = 25.12 D = O.OOE+O0 Equation is A + B * [Tanh((T-To)/(C+DT))]
Upper Shelf Energy=96.0(Fixed) Lower Shelf Energy=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/cmA2 300 250 In 8, 200 a
0 0
L-E 150 a,
C z
8 100 50
........ .......... ........... ......... ........=
.°eO X
0
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential
- 100.00 6.00 3. 76 2.24
-50. 00 8.00 9.66 - 1. 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 C-61
CAPSULE X (WELD)
Page 2 -.1 Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: X Fluence: n/cmA2 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 I
C-62
CAPSULE X (WELD)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 04:28 PM Page 1 Coefficients of Curve 3 A = 33.97 B = 33.97 C = 58.82 TO = 18.45 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]
Upper Shelf L.E.=67.9 Lower Shelf LE.=.0(Fixed)
Temp.@L.E. 35 mils=20.3 Deg F Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: X Fluence: n/cmA2 200 150 E
U)
C 0
2 100 (U
a5 50 0
-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential
- 100. 00 .00 1.19 - 1. 19
-50. 00 4.00 6. 04 -2. 04
- 25. 00 10. 00 12. 62 -2. 62
.00 22. 00 23. 65 - 1. 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 C-63
CAPSULE X (WELD)
Page 2 Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: X Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential 135.00 64. 00 66. 68 -2. 68 175. 00 65.00 67. 62 -2. 62 200. 00 64. 00 67. 81 - 3. 81 200. 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 C-64
CAPSULE X (WELD)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 04:25 PM Page I Coefficients of Curve 3 A = 50. B = 50. C = 80.55 TO = 20.76 D = O.00E+00 Equation is A + B * [Tanh((T-To)/(C+DT))]
Temperature at 50% Shear = 20.8 Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: X Fluence: nlcmA2 125 100 1..
Lu a) 75 (0
4-a 0
2 a) 50 - - - -- - - - -.
C.
25 0
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential
- 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 C
CAPSULE X (WELD)
Page 2 Plant: Comanche Peak 2 Material: SAW Heat: 89833 Orientation: NA Capsule: X Fluence: n/cmA2 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 C-66
CAPSULE X (HEAT AFFECTED ZONE)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 04:34 PM Page 1 Coefficients of Curve 3 A = 59.1 B = 56.9 C = 64.25 TO = -47.07 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]
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: SA533B1 Heat: C5522-2 Orientation: NA Capsule: X Fluence: n/cmA2 300 250 UI
-.8 200 0
0 IL 2' 150 C)
________ 0 z
100 .00 50 4t0 00.
0
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential
- 175. 00 4.00 4.28 - . 28
- 130.00 27.00 10.20 16. 80
- I1 0. 00 28.00 16.26 11. 74
-I 00. 00 21.00 20. 57 .43
-75. 00 34. 00 35.81 - 1. 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 C-67
CAPSULE X (HEAT AFFECTED ZONE)
Page 2 Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: NA Capsule: X - Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 25.00 107. 00 105. 09 1.91 75.00 104. 00 113.51 -9. 51 100.00 114. 00 114.84 -. 84 125. 00 129. 00 115. 47 13.53 125.00 121.00 115. 47 5.53 150. 00 102. 00 115.75 - 13.75 Correlation Coefficient = .923 C-68
CAPSULE X (HEAT AFFECTED ZONE)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 05:03 PM Page 1 Coefficients of Curve 3 A = 33.07 B = 33.07 C = 51.65 TO = -40.87 D = 0.O0E+0O Equation is A + B * [Tanh((T-To)/(C+DT))]
Upper Shelf L.E.=66. 1 Lower Shelf L.E.=.0(Fixed)
Temp. @L.E. 35 mils=-37.8 Deg F Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: NA Capsule: X Fluence: n/cmA2 200 150 2
I 0
2.100 50 .........
-300 0 300 600 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 1 0.00 7.00 4.26 2.74 100. 00 7.00 6.08 .92
-75. 00 18.00 13.93 4. 07
-50. 00 30. 00 27. 28 2.72
-35. 00 19.00 36. 81 - 17. 81
-25. 00 39.00 42. 92 -3. 92
-Io. 00 70. 00 50. 77 19.23 c-69
CAPSULE X (HEAT AFFECTED ZONE)
Page 2 Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: NA Capsule: X- Fluence: n/cmA2 Charpy V-Notch Data Temperature Input LE. Computed L.E. Differential
- 25. 00 63. 00. 61..35 1.65 75.00 58. 00 65.40 -7. 40 1 00. 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 C-70
CAPSULE X (HEAT AFFECTED ZONE)
CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 03/17/2004 04:39 PM Page 1 Coefficients of Curve 3 A = 50. B = 50. C = 59.24 TO = -38.14 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]
Temperature at 50% Shear= -38.1 Plant: Comanche Peak 2 Material: SA533B 1 Heat: C5522-2 Orientation: NA Capsule: X Fluence: n/cmA2 125 100 L-75 Cn
- -0 C) 0.
50 25 0 4-
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 175. 00 2.00 .98 1. 02 130. 00 10.00 4.31 5.69 110. 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 C-71
CAPSULE X (HEAT AFFECTED ZONE)
-Page-2 Plant: Comanche Peak 2 Material: SA533B1 Heat: C5522-2 Orientation: NA Capsule: X -Fluence: n/cmA2 Charpy V-Notch Data Temperature -Input Percent Shear Computed Percent Shear . Differential
- 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 C-72
D-O APPENDIX D COMANCHE PEAK UNIT 2 SURVEILLANCE PROGRAM CREDIBILITY EVALUATION Appendix D
D-1 INTRODUCTION:
Regulatory Guide 1.99, Revision 2, describes general procedures acceptable to the NRC staff for calculating the effects of neutron radiation embrittlement of the low-alloy steels currently used for light-water-cooled reactor vessels. Position C.2 of Regulatory Guide 1.99, Revision 2, describes the method for calculating the adjusted reference temperature and Charpy upper-shelf energy of reactor vessel beltline materials using surveillance capsule data. The methods of Position C.2 can only be applied when two or more credible surveillance data sets become available from the reactor in question.
To date there has been two surveillance capsules removed from the Comanche Peak Unit 2 reactor vessel.
To use these surveillance data sets, they must be shown to be credible. In accordance with the discussion of Regulatory Guide 1.99, Revision 2, there are five requirements that must be met for the surveillance data to be judged credible.
The purpose of this evaluation is to apply the credibility requirements of Regulatory Guide 1.99, Revision 2, to the Comanche Peak Unit 2 reactor vessel surveillance data and determine if the surveillance data is credible.
EVALUATION:
Criterion 1: Materials in the capsules should be those judged most likely to be controlling with regard to radiation embrittlement.
The Comanche Peak Unit 2 reactor vessel consists of the following beltline region materials:
- Intermediate Shell Plates R3807-1, 2, 3
- Lower Shell Plates R3816-1, 2, 3 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 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 Intermediated Shell Plate R3807-2 (Initial USE = 101 ft-lbs).
The weld material in the Comanche Peak Unit 2 surveillance program was made of the same wire as all the reactor vessel beltline weld, thus it was chosen as the surveillance weld material.
Hence, Criterion 1 is met for the Comanche Peak Unit 2 reactor vessel.
Appendix D
D-2 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 upper shelf energy 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 upper shelf energy 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 normally should be less than 28IF for welds and 17 0 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 upper shelf energy if the upper shelf can be clearly determined, following the definition given in ASTM E185-82.
The functional form of the least squares method as described in Regulatory Position 2.1 will be utilized to determine a best-fit line for this data and to determine if the scatter of these ARTNDT values about this line is less than 28IF for welds and less than 171F for the plate.
The Comanche Peak Unit 2 intermediate shell plate R3807-2 and surveillance weld will be evaluated for credibility. The weld is made from weld wire heat 89833. This weld metal is not in any other plant surveillance program.
The NRC methods for credibility determination were presented to industry at a meeting held by the NRC on February 12 and 13, 1998. At these meetings the NRC presented five cases. Of the five cases, Case 1 (the "straightforwardRG Method") most closely represents the situation listed above for Comanche Peak Unit 2 surveillance weld metal. Note, for the plate material, the straightforward method of Regulatory Guide 1.99, Revision 2 will also be followed.
Appendix D
D-3 TABLE D-I Calculation of Chemistry Factors using Comanche Peak Unit 2 Surveillance Capsule Data Material Capsule Capsule e(a) 1TWb) ARTNDT(C) FF*ARTNDT FF2 Inter. Shell U 0.315 0.683 1.6 1.093 0.466 Plate R3807-2 2.20 1.21 1.6 1.94 1.46 (Longitudinal)
Inter. Shell U 0.315 0.683 23.4 15.982 0.466 Plate R3807-2 X 2.20 1.21 52.9 64.01 1.46 (Transverse) SUM: 83.025 3.852 CFR3 807.2 = X(FF
- RTNDT) dX( FE2) = (83.025) _ (3.852) = 21.60 F Surv. Weld U 0.315 0.683 3.6 2.459 0.466 Material X 2.20 1.21 48.2 58.32 1.46 (Heat #89833) SUM: 60.779 1.926 CF sum. whd = Z(FF
- RTNDT) - ( FE2) = (60.779) - (1.926) = 31.6°F Notes:
(a) f = fluence. Units are x 1019 n/cm2 (E > 1.0 MeV).
(b) FF= fluence factor = f(O.2S-O.1'of)
(c) ARTNDT values are the measured 30 ft-lb shift values. See Appendix C herein, Units are [0F].
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.
Appendix D
D-4 TABLE D-2 Comanche Peak Unit 2 Surveillance Capsule Data Scatter about the Best-Fit Line for Surveillance Forging Materials.
Scatter -<17 F CF ' Measured Predicted (Base Metals)
Maternal Capsule ( e FF ARTNDT ATNT RTNT (OF) <280 F (Weld)
Inter. Shell Plate U 21.6 0.683 1.6 14.8 -13.2 Yes R3 807-2 (Longitudinal) X 21.6 1.21 1.6 26.1 -24.5 NO Inter. Shell Plate U 21.6 0.683 23.4 14.8 8.6 Yes R3807-2 (Transverse) X 21.6 1.21 52.9 26.1 26.8 NO Surveillance Weld U 31.6 0.683 3.6 21.6 -18 Yes Material X 31.6 1.21 48.2 38.2 10 Yes Table D-2 indicates that 2 of 4 data points fall outside the +/- lIa of 171F scatter band for the intermediate shell plate R3707-2 surveillance data. Therefore the plate surveillance data is deemed "Not-Credible." No weld data points fall outside the +/- lI of 281F scatter band for the surveillance weld data, therefore the weld data is deemed "credible" per the third criterion.
- Appendix D
D-5 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 0 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 0F. Hence, this criterion is met.
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.
CONCLUSION:
Based on the preceding responses to all five criteria of Regulatory Guide 1.99, Revision 2, Section B and 10 CFR 50.61, the Comanche Peak Unit 2 surveillance plate data is deemed "not-credible," while the surveillance weld data is "credible."
Appendix D