ML23075A346

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WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 1 of 7)
ML23075A346
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Site: Prairie Island Xcel Energy icon.png
Issue date: 12/31/2022
From: Benson R, Long M
Northern States Power Company, Minnesota, Westinghouse, Xcel Energy
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Office of Nuclear Reactor Regulation
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L-PI-23-002 WCAP-18795-NP, Rev 0
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      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 WCAP-18795-NP December 2022 Revision 0 Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3

  • Electronically approved records are authenticated in the electronic document management system.

Westinghouse Electric Company LLC 1000 Westinghouse Drive Cranberry Township, PA 16066, USA

© 2022 Westinghouse Electric Company LLC All Rights Reserved WCAP-18795-NP Revision 0 Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program Margaret L. Long*

Reactor Vessel/Containment Vessel (RV/CV)

Design & Analysis Riley I. Benson*

Nuclear Operations December 2022 Reviewers: Donald M. McNutt III*

RV/CV Design & Analysis Eugene T. Hayes*

Radiation Engineering & Analysis Approved: Lynn A. Patterson*, Manager RV/CV Design & Analysis Jesse J Klingensmith*, Manager Radiation Engineering & Analysis

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 ii WCAP-18795-NP December 2022 Revision 0 TABLE OF CONTENTS LIST OF TABLES....................................................................................................................................... iii LIST OF FIGURES..................................................................................................................................... vi EXECUTIVE

SUMMARY

........................................................................................................................ viii 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 N............................................................................ 5-1 5.1 OVERVIEW.................................................................................................................... 5-1 5.2 CHARPY V-NOTCH IMPACT TEST RESULTS........................................................... 5-2 5.3 TENSILE TEST RESULTS............................................................................................. 5-4 6

RADIATION ANALYSIS AND NEUTRON DOSIMETRY.............................................................. 6-1

6.1 INTRODUCTION

........................................................................................................... 6-1 6.2 DISCRETE ORDINATES ANALYSIS........................................................................... 6-1 6.3 NEUTRON DOSIMETRY.............................................................................................. 6-4 6.4 CALCULATIONAL UNCERTAINTIES........................................................................ 6-4 7

SURVEILLANCE CAPSULE REMOVAL SCHEDULE................................................................... 7-1 8

REFERENCES.................................................................................................................................... 8-1 APPENDIX A VALIDATION OF THE RADIATION TRANSPORT MODELS BASED ON NEUTRON DOSIMETRY MEASUREMENTS................................................................................ A-1 APPENDIX B LOAD-TIME RECORDS FOR CHARPY SPECIMEN TESTS FROM CAPSULE N. B-1 APPENDIX C CHARPY V-NOTCH PLOTS FOR EACH CAPSULE INCLUDING BASELINE DATA USING SYMMETRIC HYPERBOLIC TANGENT CURVE-FITTING METHOD..... C-1 APPENDIX D PRAIRIE ISLAND UNIT 2

SURVEILLANCE PROGRAM CREDIBILITY EVALUATION............................................................................................................... D-1

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 iii WCAP-18795-NP December 2022 Revision 0 LIST OF TABLES Table 4-1 Chemical Composition (wt. %) of the Prairie Island Unit 2 Reactor Vessel Surveillance Materials (Unirradiated)................................................................................................... 4-3 Table 4-2 Heat Treatment History of the Prairie Island Unit 2 Reactor Vessel Surveillance Materials

......................................................................................................................................... 4-4 Table 5-1 Charpy V-notch Data for the Prairie Island Unit 2 Capsule N Lower Shell Forging D (Heat # 22642) (Tangential Orientation) Irradiated to a Fluence of 8.41 x 1019 n/cm2 (E > 1.0 MeV).................................................................................................................. 5-5 Table 5-2 Charpy V-notch Data for the Prairie Island Unit 2 Capsule N Lower Shell Forging D (Heat # 22642) (Axial Orientation) Irradiated to a Fluence of 8.41 x 1019 n/cm2 (E > 1.0 MeV).................................................................................................................. 5-6 Table 5-3 Charpy V-notch Data for the Prairie Island Unit 2 Capsule N Surveillance Program Weld Material Irradiated to a Fluence of 8.41 x 1019 n/cm2 (E > 1.0 MeV)............................. 5-7 Table 5-4 Charpy V-notch Data for the Prairie Island Unit 2 Capsule N Heat Affected Zone (HAZ)

Irradiated to a Fluence of 8.41 x 1019 n/cm2 (E > 1.0 MeV)............................................ 5-8 Table 5-5 Charpy V-notch Data for the Prairie Island Unit 2 Capsule N Correlation Monitor Material (CMM) Irradiated to a Fluence of 8.41 x 1019 n/cm2 (E > 1.0 MeV)................ 5-9 Table 5-6 Instrumented Charpy Impact Test Results for the Prairie Island Unit 2 Capsule N Lower Shell Forging D (Heat # 22642) (Tangential Orientation) Irradiated to a Fluence of 8.41 x 1019 n/cm2 (E > 1.0 MeV).............................................................................................. 5-10 Table 5-7 Instrumented Charpy Impact Test Results for the Prairie Island Unit 2 Capsule N Lower Shell Forging D (Heat # 22642) (Axial Orientation) Irradiated to a Fluence of 8.41 x 1019 n/cm2 (E > 1.0 MeV).............................................................................................. 5-11 Table 5-8 Instrumented Charpy Impact Test Results for the Prairie Island Unit 2 Capsule N Surveillance Program Weld Material Irradiated to a Fluence of 8.41 x 1019 n/cm2 (E > 1.0 MeV).............................................................................................................................. 5-12 Table 5-9 Instrumented Charpy Impact Test Results for the Prairie Island Unit 2 Capsule N Heat Affected Zone (HAZ) Irradiated to a Fluence of 8.41 x 1019 n/cm2 (E > 1.0 MeV)...... 5-13 Table 5-10 Instrumented Charpy Impact Test Results for Prairie Island Unit 2 Capsule N Correlation Monitor Material (CMM) Irradiated to a Fluence of 8.41 x 1019 n/cm2 (E >

1.0 MeV)........................................................................................................................ 5-14 Table 5-11 Effect of Irradiation to 8.41 x 1019 n/cm2 (E > 1.0 MeV) on the Charpy V-notch Toughness Properties of the Prairie Island Unit 2 Reactor Vessel Surveillance Capsule N Materials........................................................................................................................ 5-15 Table 5-12 Comparison of the Prairie Island Unit 2 Surveillance Material 30 ft-lb Transition Temperature Shifts and Upper-Shelf Energy Decreases with Regulatory Guide 1.99, Revision 2, Predictions.................................................................................................. 5-16

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 iv WCAP-18795-NP December 2022 Revision 0 Table 5-13 Tensile Test Results of the Prairie Island Unit 2 Capsule N Reactor Vessel Surveillance Materials Irradiated to 8.41 x 1019 n/cm2 (E > 1.0 MeV).............................................. 5-17 Table 6-1 Calculated Maximum Fast (E > 1.0 MeV) Neutron Fluence Rate and Fluence at Surveillance Capsule Locations....................................................................................... 6-7 Table 6-2 Calculated Iron Atom Displacement Rate and Iron Atom Displacements at Surveillance Capsule Locations............................................................................................................ 6-9 Table 6-3 Calculated Surveillance Capsule Lead Factors.............................................................. 6-11 Table 6-4 Calculated Maximum Fast (E > 1.0 MeV) Neutron Fluence Rate at the Pressure Vessel Clad/Base Metal Interface.............................................................................................. 6-12 Table 6-5 Calculated Maximum Fast (E > 1.0 MeV) Neutron Fluence at the Pressure Vessel Clad/Base Metal Interface.............................................................................................. 6-13 Table 6-6 Calculated Maximum Iron Atom Displacement Rate at the Pressure Vessel Clad/Base Metal Interface............................................................................................................... 6-14 Table 6-7 Calculated Maximum Iron Atom Displacements at the Pressure Vessel Clad/Base Metal Interface......................................................................................................................... 6-15 Table 6-8 Calculated Maximum Fast Neutron Fluence (E > 1.0 MeV) at Pressure Vessel Welds and Shells.............................................................................................................................. 6-16 Table 6-9 Calculated Maximum Iron Atom Displacements at Pressure Vessel Welds and Shells. 6-17 Table 6-10 Summary of Reactor Power and RCS Temperatures..................................................... 6-18 Table 7-1 Prairie Island Unit 2 Surveillance Capsule Withdrawal Schedule................................... 7-1 Table A-1 Nuclear Parameters Used in the Evaluation of Neutron Sensors.................................. A-10 Table A-2 Monthly Thermal Generation at Prairie Island Unit 2 Cycles 17 through 31............... A-11 Table A-2 Monthly Thermal Generation at Prairie Island Unit 2 Cycles 17 through 31 (cont.)... A-12 Table A-2 Monthly Thermal Generation at Prairie Island Unit 2 Cycles 17 through 31 (cont.)... A-13 Table A-2 Monthly Thermal Generation at Prairie Island Unit 2 Cycles 17 through 31 (cont.)... A-14 Table A-3 Measured Sensor Activities and Reaction Rates for Surveillance Capsule V.............. A-15 Table A-4 Measured Sensor Activities and Reaction Rates for Surveillance Capsule T............... A-16 Table A-5 Measured Sensor Activities and Reaction Rates for Surveillance Capsule R............... A-17 Table A-6 Measured Sensor Activities and Reaction Rates for Surveillance Capsule P............... A-18 Table A-7 Measured Sensor Activities and Reaction Rates for Surveillance Capsule N.............. A-19 Table A-8 Least-Squares Evaluation of Dosimetry in Surveillance Capsule V (13° Position, Core Midplane, Irradiated During Cycle 1)........................................................................... A-20 Table A-9 Least-Squares Evaluation of Dosimetry in Surveillance Capsule T (23° Position, Core Midplane, Irradiated During Cycles 1 through 4)......................................................... A-21

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 v

WCAP-18795-NP December 2022 Revision 0 Table A-10 Least-Squares Evaluation of Dosimetry in Surveillance Capsule R (13° Position, Core Midplane, Irradiated During Cycles 1 through 9)......................................................... A-22 Table A-11 Least-Squares Evaluation of Dosimetry in Surveillance Capsule P (33° Position, Core Midplane, Irradiated During Cycles 1 through 16)....................................................... A-23 Table A-12 Least-Squares Evaluation of Dosimetry in Surveillance Capsule N (33° Position, Core Midplane, Irradiated During Cycles 1 through 31) - Case 1........................................ A-24 Table A-13 Least-Squares Evaluation of Dosimetry in Surveillance Capsule N (33° Position, Core Midplane, Irradiated During Cycles 1 through 31) - Case 2........................................ A-25 Table A-14 Measured-to-Calculated (M/C) Reaction Rates - In-Vessel Capsules.......................... A-26 Table A-15 Best-Estimate-to-Calculated (BE/C) Exposure Rates - In-Vessel Capsules................. A-26 Table C-1 Upper-Shelf Energy Values Fixed in CVGRAPH........................................................... C-2 Table D-1 Calculation of Interim Chemistry Factors for the Credibility Evaluation Using Prairie Island Unit 2 Surveillance Data...................................................................................... D-4 Table D-2 Best-Fit Evaluation For Prairie Island Unit 2 Surveillance Materials Only................... D-5 Table D-3 Calculation of Residual vs. Fast Fluence for Prairie Island Unit 2 Correlation Monitor Material........................................................................................................................... D-7

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 vi WCAP-18795-NP December 2022 Revision 0 LIST OF FIGURES Figure 4-1 Arrangement of Surveillance Capsules in the Prairie Island Unit 2 Reactor Vessel........ 4-5 Figure 4-2 Prairie Island Unit 2 Surveillance Capsule N Specimen Locations per WCAP-8193..... 4-6 Figure 5-1 Charpy V-notch Impact Energy vs. Temperature for Prairie Island Unit 2 Reactor Vessel Surveillance Program Lower Shell Forging D (Heat # 22642) (Tangential Orientation)

....................................................................................................................................... 5-18 Figure 5-2 Charpy V-notch Lateral Expansion vs. Temperature for Prairie Island Unit 2 Reactor Vessel Surveillance Program Lower Shell Forging D (Heat # 22642) (Tangential Orientation)

....................................................................................................................................... 5-20 Figure 5-3 Charpy V-notch Percent Shear vs. Temperature for Prairie Island Unit 2 Reactor Vessel Surveillance Program Lower Shell Forging D (Heat # 22642) (Tangential Orientation)

....................................................................................................................................... 5-22 Figure 5-4 Charpy V-notch Impact Energy vs. Temperature for Prairie Island Unit 2 Reactor Vessel Surveillance Program Lower Shell Forging D (Heat # 22642) (Axial Orientation)...... 5-24 Figure 5-5 Charpy V-notch Lateral Expansion vs. Temperature for Prairie Island Unit 2 Reactor Vessel Surveillance Program Lower Shell Forging D (Heat # 22642) (Axial Orientation)...... 5-26 Figure 5-6 Charpy V-notch Percent Shear vs. Temperature for Prairie Island Unit 2 Reactor Vessel Surveillance Program Lower Shell Forging D (Heat # 22642) (Axial Orientation)...... 5-28 Figure 5-7 Charpy V-notch Impact Energy vs. Temperature for Prairie Island Unit 2 Reactor Vessel Surveillance Program Weld Material............................................................................. 5-30 Figure 5-8 Charpy V-notch Lateral Expansion vs. Temperature for Prairie Island Unit 2 Reactor Vessel Surveillance Program Weld Material............................................................................. 5-32 Figure 5-9 Charpy V-notch Percent Shear vs. Temperature for Prairie Island Unit 2 Reactor Vessel Surveillance Program Weld Material............................................................................. 5-34 Figure 5-10 Charpy V-notch Impact Energy vs. Temperature for Prairie Island Unit 2 Reactor Vessel Heat-Affected Zone Material......................................................................................... 5-36 Figure 5-11 Charpy V-notch Lateral Expansion vs. Temperature for Prairie Island Unit 2 Reactor Vessel Heat-Affected Zone Material......................................................................................... 5-38 Figure 5-12 Charpy V-notch Percent Shear vs. Temperature for Prairie Island Unit 2 Reactor Vessel Heat-Affected Zone Material......................................................................................... 5-40 Figure 5-13 Charpy V-notch Impact Energy vs. Temperature for Prairie Island Unit 2 Reactor Vessel Correlation Monitor Material......................................................................................... 5-42 Figure 5-14 Charpy V-notch Lateral Expansion vs. Temperature for Prairie Island Unit 2 Reactor Vessel Correlation Monitor Material......................................................................................... 5-44 Figure 5-15 Charpy V-notch Percent Shear vs. Temperature for Prairie Island Unit 2 Reactor Vessel Correlation Monitor Material......................................................................................... 5-46 Figure 5-16 Charpy Impact Specimen Fracture Surfaces for Prairie Island Unit 2 Capsule N Lower Shell Forging D (Heat # 22642) (Tangential Orientation)............................................. 5-48 Figure 5-17 Charpy Impact Specimen Fracture Surfaces for Prairie Island Unit 2 Capsule N Lower Shell Forging D (Heat # 22642) (Axial Orientation)..................................................... 5-49

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 vii WCAP-18795-NP December 2022 Revision 0 Figure 5-18 Charpy Impact Specimen Fracture Surfaces for the Prairie Island Unit 2 Capsule N Weld Material.......................................................................................................................... 5-50 Figure 5-19 Charpy Impact Specimen Fracture Surfaces for the Prairie Island Unit 2 Capsule N Heat-Affected Zone (HAZ) Material...................................................................................... 5-51 Figure 5-20 Charpy Impact Specimen Fracture Surfaces of the Prairie Island Unit 2 Capsule N Correlation Monitor Material (CMM)........................................................................... 5-52 Figure 5-21 Tensile Properties for Prairie Island Unit 2 Reactor Vessel Lower Shell Forging D (Heat #

22642) (Tangential Orientation).................................................................................... 5-53 Figure 5-22 Tensile Properties for Prairie Island Unit 2 Reactor Vessel Lower Shell Forging D (Heat #

22642) (Axial Orientation)............................................................................................ 5-54 Figure 5-23 Tensile Properties for Prairie Island Unit 2 Reactor Vessel Surveillance Program Weld Material.......................................................................................................................... 5-55 Figure 5-24 Fractured Tensile Specimens from Prairie Island Unit 2 Capsule N Lower Shell Forging D (Heat # 22642) (Tangential Orientation) [Scale in 1/10th of inch]................................ 5-56 Figure 5-25 Fractured Tensile Specimens from Prairie Island Unit 2 Capsule N Lower Shell Forging D (Heat # 22642) (Axial Orientation) [Scale in 1/10th of inch]........................................ 5-57 Figure 5-26 Fractured Tensile Specimens from Prairie Island Unit 2 Capsule N Weld Metal [Scale in 1/10th of inch]................................................................................................................. 5-58 Figure 5-27 Engineering Stress-Strain Curve for Prairie Island Unit 2, Capsule N, Tensile Specimen NL13 (Tangential Orientation), Tested at 78°F.............................................................. 5-59 Figure 5-28 Engineering Stress-Strain Curve for Prairie Island Unit 2, Capsule N, Tensile Specimen NL14 (Tangential Orientation), Tested at 300°F............................................................ 5-59 Figure 5-29 Engineering Stress-Strain Curve for Prairie Island Unit 2, Capsule N, Tensile Specimen NL15 (Tangential Orientation), Tested at 550°F............................................................ 5-59 Figure 5-30 Engineering Stress-Strain Curve for Prairie Island Unit 2, Capsule N, Tensile Specimen NT13 (Axial Orientation), Tested at 78°F..................................................................... 5-60 Figure 5-31 Engineering Stress-Strain Curve for Prairie Island Unit 2, Capsule N, Tensile Specimen NT14 (Axial Orientation), Tested at 300°F................................................................... 5-60 Figure 5-32 Engineering Stress-Strain Curve for Prairie Island Unit 2, Capsule N, Tensile Specimen NT15 (Axial Orientation), Tested at 550°F................................................................... 5-60 Figure 5-33 Engineering Stress-Strain Curve for Prairie Island Unit 2, Capsule N, Tensile Specimen NW13 (Weld), Tested at 78°F........................................................................................ 5-61 Figure 5-34 Engineering Stress-Strain Curve for Prairie Island Unit 2, Capsule N, Tensile Specimen NW14 (Weld), Tested at 300°F...................................................................................... 5-61 Figure 5-35 Engineering Stress-Strain Curve for Prairie Island Unit 2, Capsule N, Tensile Specimen NW15 (Weld), Tested at 550°F...................................................................................... 5-61 Figure 6-1 Prairie Island Unit 2 Plan View of the Reactor Geometry at the Core Midplane.......... 6-19 Figure 6-2 Prairie Island Unit 2 Plan View of the Reactor Geometry at the Nozzle Centerline..... 6-20 Figure 6-3 Prairie Island Unit 2 Section View of the Reactor Geometry at 0-Degrees................... 6-21 Figure 6-4 Prairie Island Unit 2 Section View of the Reactor Geometry at 33-Degrees................. 6-22

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 viii WCAP-18795-NP December 2022 Revision 0 EXECUTIVE

SUMMARY

The purpose of this report is to document the testing results of surveillance Capsule N from Prairie Island Unit 2. Capsule N was removed at 40.64 effective full-power years (EFPY) and post-irradiation mechanical tests of the Charpy V-notch and tensile specimens were performed. A fluence evaluation utilizing the neutron transport and dosimetry cross-section libraries was derived from the Evaluated Nuclear Data File (ENDF) database (specifically, ENDF/B-VI). Capsule N received a fluence of 8.41 x 1019 n/cm2 (E >

1.0 MeV) after irradiation to 40.64 EFPY. The peak clad/base metal interface vessel fluence at 54 EFPY (end-of-license extension) of plant operation is projected to be 5.66 x 1019 n/cm2 (E > 1.0 MeV).

This evaluation led to the following conclusions: (1) The measured shifts in the 30 ft-lb transition temperature of all the surveillance materials, i.e., the surveillance forging (tangential and axial orientations),

the surveillance weld material, and Correlation Monitor Material (CMM) contained in Prairie Island Unit 2 Capsule N are higher than the Regulatory Guide 1.99, Revision 2 [1], Position 1.1 predictions. (2) The measured percent decreases in upper-shelf energy of all the surveillance materials, i.e., the Lower Shell Forging D (Heat # 22642) (tangential and axial orientations), surveillance weld material (Heat # 2721), and CMM, are less than the Regulatory Guide 1.99, Rev. 2, Position 1.2 predictions. (3) The Prairie Island Unit 2 surveillance forging data is deemed non-credible, while the surveillance weld data is deemed to be credible. This credibility 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.

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 1-1 WCAP-18795-NP December 2022 Revision 0 1

SUMMARY

OF RESULTS The analysis of the reactor vessel materials contained in surveillance Capsule N, the fifth capsule removed and tested from the Prairie Island Unit 2 reactor pressure vessel, led to the following conclusions:

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

Appendix C presents the CVGRAPH, Version 6.02, Charpy V-notch plots for Capsule N, along with data from the program baseline and previous capsules.

Capsule N received an average fast neutron fluence (E > 1.0 MeV) of 8.41 x 1019 n/cm2 after 40.64 effective full-power years (EFPY) of plant operation.

Irradiation of the reactor vessel Lower Shell Forging D (Heat # 22642) Charpy specimens, oriented with the longitudinal axis of the specimen parallel to the major working direction (tangential orientation), resulted in an irradiated 30 ft-lb transition temperature of 148.2F. This results in a 30 ft-lb transition temperature increase of 176.5F for the tangentially oriented specimens.

Irradiation of the reactor vessel Lower Shell Forging D (Heat # 22642) Charpy specimens, oriented with the longitudinal axis of the specimen perpendicular to the major working direction (axial orientation), resulted in an irradiated 30 ft-lb transition temperature of 152.9F. This results in a 30 ft-lb transition temperature increase of 154.1F for the axially oriented specimens.

Irradiation of the surveillance program weld material (Heat # 2721, Flux Type UM89, Lot # 1263)

Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 59.5F. This results in a 30 ft-lb transition temperature increase of 135.6F for the surveillance program weld material specimens.

Irradiation of the reactor vessel heat-affected zone (HAZ) material Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 10.9F. This results in a 30 ft-lb transition temperature increase of 145.5F for the HAZ material specimens.

Irradiation of the reactor vessel Correlation Monitor Material (CMM) Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 259.9F. This results in a 30 ft-lb transition temperature increase of 212.9F for the CMM specimens.

The average upper-shelf energy of Lower Shell Forging D (Heat # 22642) (tangential orientation) resulted in an average energy decrease of 22.7 ft-lb after irradiation. This decrease results in an irradiated average upper-shelf energy of 125 ft-lb for the tangentially oriented specimens.

The average upper-shelf energy of Lower Shell Forging D (Heat # 22642) (axial orientation) resulted in an average energy decrease of 17.2 ft-lb after irradiation. This decrease results in an irradiated average upper-shelf energy of 89 ft-lb for the axially oriented specimens.

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 1-2 WCAP-18795-NP December 2022 Revision 0 The average upper-shelf energy of the surveillance program weld material (Heat # 2721) Charpy specimens resulted in an average energy decrease of 8.3 ft-lb after irradiation. This decrease results in an irradiated average upper-shelf energy of 95 ft-lb for the surveillance program weld material specimens.

The average upper-shelf energy of the HAZ material Charpy specimens resulted in an average energy decrease of 32 ft-lb after irradiation. This decrease results in an irradiated average upper-shelf energy of 82 ft-lb for the HAZ material.

The average upper-shelf energy of the CMM Charpy specimens resulted in an average energy decrease of 41.4 ft-lb after irradiation. This decrease results in an irradiated average upper-shelf energy of 79 ft-lb for the CMM specimens.

Comparisons of the measured 30 ft-lb shift in transition temperature values and upper-shelf energy decreases to those predicted by Regulatory Guide 1.99, Rev. 2 [1] for the Prairie Island Unit 2 reactor vessel surveillance materials are presented in Table 5-12.

Based on the credibility evaluation presented in Appendix D, the Prairie Island Unit 2 surveillance plate data is deemed non-credible, while the surveillance weld material data is deemed credible.

The maximum calculated 54 EFPY (end-of-license extension) neutron fluence (E > 1.0 MeV) for the Prairie Island Unit 2 reactor vessel beltline using the Regulatory Guide 1.99, Rev. 2 [1] attenuation formula (i.e., Equation # 3 in the Guide) and a vessel thickness of 6.692 inches are as follows:

Calculated (54 EFPY):

Vessel peak clad/base metal interface fluence* = 5.66 x 1019 n/cm2 Vessel peak quarter-thickness (1/4T) fluence = 3.79 x 1019 n/cm2 Vessel peak three-quarter thickness (3/4T) fluence = 1.70 x 1019 n/cm2

  • This fluence value is determined from data in Table 6-5.
      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 2-1 WCAP-18795-NP December 2022 Revision 0 2

INTRODUCTION This report presents the results of the examination of Capsule N, the fifth capsule removed and tested in the continuing surveillance program, which monitors the effects of neutron irradiation on the Xcel Energy Prairie Island Unit 2 reactor pressure vessel materials under actual operating conditions.

The surveillance program for the Prairie Island Unit 2 reactor pressure vessel materials was designed and recommended by Westinghouse Electric Company LLC. A detailed description of the surveillance program is contained in WCAP-8193 [2], Northern States Power Co. Prairie Island Unit No. 2 Reactor Vessel Radiation Surveillance Program. The surveillance program was originally planned to cover the 40-year design life of the reactor pressure vessel and was based on ASTM E185-70 [3], Standard Recommended Practice for Surveillance Tests for Nuclear Reactor Vessels. Capsule N was removed from the reactor at 40.64 effective full-power years (EFPY) of exposure and shipped to the Westinghouse Churchill Laboratory, where the post-irradiation mechanical testing of the Charpy V-notch impact and tensile surveillance specimens was performed.

This report summarizes the testing and post-irradiation data obtained from surveillance Capsule N removed from the Prairie Island Unit 2 reactor vessel and presents the analysis of the data.

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 3-1 WCAP-18795-NP December 2022 Revision 0 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 A508 Class 3 (base material of the Prairie Island 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 [4]. 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 American Society of Testing and Materials (ASTM) E208 [5] or the temperature 60F less than the 50 ft-lb (and 35-mil lateral expansion) temperature as determined from Charpy specimens oriented perpendicular (axial) to the major working direction of the plate. The RTNDT of a given material is used to index that material to a reference stress intensity factor curve (KIc curve) which appears in Appendix G to Section XI of the ASME Code [4]. The KIc curve is a lower bound of static fracture toughness results obtained from several heats of pressure vessel steel. When a given material is indexed to the KIc curve, allowable stress intensity 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, are 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, are monitored by a reactor vessel surveillance program, such as the Prairie Island Unit 2 reactor vessel radiation surveillance program, in which a surveillance capsule is periodically removed from the operating nuclear reactor and the encapsulated specimens are tested. The increase in the average Charpy V-notch 30 ft-lb temperature (RTNDT) 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 (initial RTNDT + M + RTNDT) 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.

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 4-1 WCAP-18795-NP December 2022 Revision 0 4

DESCRIPTION OF PROGRAM Six surveillance capsules for monitoring the effects of neutron exposure on the Prairie Island Unit 2 reactor pressure vessel core region (beltline) materials were inserted in the reactor vessel prior to initial plant startup. The six capsules were positioned in the reactor vessel between the thermal shield and the vessel wall as shown in Figure 4-1. The test capsules are in baskets attached to the thermal shield. The vertical center of the capsules is opposite the vertical center of the core. The capsules contain specimens made from the following:

Lower Shell Forging D (Heat # 22642) - Tangential Orientation Lower Shell Forging D (Heat # 22642) - Axial Orientation Surveillance Weld Metal (Weld Wire Type UM40, Heat # 2721, Flux Type UM89, Lot # 1263)

Heat Affected Zone material of Lower Shell Forging D (Heat # 22642)

Correlation Monitor Material Test material from Lower Shell Forging D (Heat # 22642) was heat-treated with the shell. All test specimens were machined from the 1/4 thickness location of the forging after performing a simulated post-weld stress-relieving treatment on the test material. Test material was taken at least one forging thickness (6.692 inches) from the quenched edges of the forging. Test specimens were also machined from weld metal and the heat affected zone metal of stress-relieved weldment joining sections of the Intermediate and Lower Shell forgings. All heat-affected zone specimens were obtained from the weld heat-affected zone of Lower Shell Forging D (Heat # 22642). The A533 Grade B Class 1 material (HSST Plate 02) for the CMM test specimens was supplied by the Oak Ridge Laboratory from a 12-inch thick plate.

Charpy V-notch impact specimens from Lower Shell Forging D (Heat # 22642) were machined in both the tangential orientation (the longitudinal axis of the specimen parallel to the major working direction) and also in the axial orientation (the longitudinal axis of the specimen perpendicular to the major working direction). The weld specimens were machined from the weldment such that the long dimension of the Charpy was normal to the weld direction where the notch was machined such that the direction of crack propagation was in the weld direction.

Tensile test specimens from the surveillance forging were machined with the longitudinal axis of the specimen in the hoop direction (tangential) and also normal to the hoop direction (axial) of the shell ring forging.

Wedge Opening Loading (WOL) test specimens were machined in a tangential direction so that the loading of the specimen would be in the major working direction of the forging with the simulated crack propagating in the axial direction. In addition, axial specimens were machined so that the loading of the specimens would be in the axial direction of the forging with the simulated crack propagating in the major working direction. All specimens were fatigue pre-cracked per ASTM E399 [6].

Capsule N contained dosimeters of pure iron, copper, nickel, and aluminum-0.15 weight percent cobalt wire (cadmium-shielded and unshielded). In addition, cadmium-shielded dosimeters of neptunium (237Np)

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Westinghouse Non-Proprietary Class 3 4-2 WCAP-18795-NP December 2022 Revision 0 and uranium (238U) were placed in the capsules to measure the integrated flux at specific neutron energy levels.

Thermal monitors comprised of low melting-point eutectic alloy specimens sealed in Pyrex tubes were also included in the capsule. These thermal monitors were used to define the maximum temperature attained by the test specimens during irradiation. The composition of the two eutectic alloys and their melting points are as follows:

2.5% Ag, 97.5% Pb Melting point: 579°F (304°C) 1.75% Ag, 0.75% Sn, 97.5% Pb Melting point: 590°F (310°C)

The chemical composition and the heat treatment of the various mechanical specimens in Capsule N are presented in Table 4-1 and Table 4-2, respectively. The data in the tables was obtained from surveillance capsule report WCAP-14613 [16].

Capsule N was removed after 40.64 EFPY of plant operation. The capsule contained Charpy V-notch specimens, tensile specimens, WOL specimens, dosimeters, and thermal monitors.

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

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Westinghouse Non-Proprietary Class 3 4-3 WCAP-18795-NP December 2022 Revision 0 Table 4-1 Chemical Composition (wt. %) of the Prairie Island Unit 2 Reactor Vessel Surveillance Materials (Unirradiated)(1)

Element(2)

Lower Shell Forging D (Heat # 22642)

Weld Metal (Heat # 2721)

Correlation Monitor Material C

0.175 0.045 0.22 Mn 1.22 1.37 1.48 P

0.011 0.019 0.012 S

0.013 0.014 0.018 Si 0.47 0.25 Mo 0.445 0.51 0.52 Ni 0.70 0.072 0.68 Cr 0.14 0.020 V

<0.008 0.001 Cu 0.085 0.082 0.14 Co 0.026 0.013 Al 0.036 0.007 N2 0.017 0.026 Sn 0.011 0.002 Notes:

1.

Data obtained from WCAP-14613 [16] and duplicated herein for completeness.

2.

A qualitative spectrographic analysis was made for elements greater than 0.010 weight percent.

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Westinghouse Non-Proprietary Class 3 4-4 WCAP-18795-NP December 2022 Revision 0 Table 4-2 Heat Treatment History of the Prairie Island Unit 2 Reactor Vessel Surveillance Materials(1)

Material Temperature (F)

Time (hrs.)

Coolant Lower Shell Forging D (Heat # 22642)

Heated to 1652/1715 5

Water quenched Tempered at 1175/1238 5

Furnace cooled Heated to 1652/1724 5.5 Water quenched Tempered at 1202/1238 5

Furnace cooled Stress relieved at 1022 11.5 Furnace cooled Stress relieved at 1112 7

Furnace cooled Weldment Stress relieved at 1022 5

Furnace cooled Stress relieved at 1112 7

Furnace cooled Correlation Monitor Material 1675 +/- 25 4

Air cooled 1600 +/- 25 4

Water quenched 1125 +/- 25 4

Furnace cooled 1150 +/- 25 40 Furnace cooled to 600ºF Note:

1.

Data obtained from WCAP-14613 [16] and duplicated herein for completeness.

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Westinghouse Non-Proprietary Class 3 4-5 WCAP-18795-NP December 2022 Revision 0 Figure 4-1 Arrangement of Surveillance Capsules in the Prairie Island Unit 2 Reactor Vessel

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Westinghouse Non-Proprietary Class 3 4-6 WCAP-18795-NP December 2022 Revision 0 LEGEND:

NLxx - LOWER SHELL COURSE RING FORGING D (Heat # 22642) (TANGENTIAL)

NTxx - LOWER SHELL COURSE RING FORGING D (Heat # 22642) (AXIAL)

NWxx - WELD METAL NHxx - HEAT AFFECTED ZONE Rxx - CORRELATION MONITOR MATERIAL TENSILE WOL WOL WOL TENSILE WOL WOL WOL TENSILE CHARPY NW15 NW15 NW14 NW13 NW13 NT15 NT14 NT13 NT14 NT60 NW40 NW14 NT15 NT13 NT59 NW39 CHARPY CHARPY CHARPY DOSIMETER BLOCK CHARPY CHARPY CHARPY CHARPY NT58 NW38 NT56 NW36 NT54 NW34 163 NT52 R40 NT50 R38 NL60 R36 N58 R34 NT57 NW37 NT55 NW35 NT53 NW33 NT51 R39 NT49 R37 NL59 R35 N57 R33 CHARPY CHARPY CHARPY CHARPY*

WOL WOL WOL TENSILE NL56 NH40 NL54 NH38 NL52 NH36 NL50 NH34 NL49 NH33 NL15 NL14 NL13 NL14 NL55 NH39 NL53 NH37 NL51 NH35 NL15 NL13 TENSILE Figure 4-2 Prairie Island Unit 2 Surveillance Capsule N Specimen Locations per WCAP-8193 [2]

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Westinghouse Non-Proprietary Class 3 5-1 WCAP-18795-NP December 2022 Revision 0 5

TESTING OF SPECIMENS FROM CAPSULE N 5.1 OVERVIEW The post-irradiation mechanical testing of the Charpy V-notch impact specimens and tensile specimens was performed at the Westinghouse Churchill Hot Cell Facility. Testing was performed in accordance with 10 CFR 50, Appendix H [9] and ASTM Specification E185-82 [10].

Capsule N was opened upon receipt 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-8193

[2] and shown in Figure 4-2. All of the items were in their proper locations.

The temperature monitors were removed from the capsule compartments and were photographed and visually examined for evidence of melting. Visual examination revealed no definitive evidence indicating that the capsule experienced temperatures in excess of 579°F.

Charpy V-notch testing was performed per ASTM E185-82 [10] and ASTM E23-18 [11] on a Tinius-Olsen Model 74, with 358J capacity impact test machine. The Charpy machine striker was instrumented with an Instron0F1 Impulse system. Instrumented testing and calibration were performed to ASTM E2298-18 [12].

The instrumented striker load signal data acquisition rate was 819 kHz with data acquired for 10 ms. From the load-time curve, the load of general yield load (Fgy), the maximum load (Fm) and the time to maximum load were 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 load at brittle fracture initiation/load at initiation of unstable crack propagation (Fbf). The termination load after the fast load drop is identified as the arrest load/load at end of unstable crack propagation (Fa). Fgy, Fm, Fbf, and Fa were determined per the guidance in ASTM Standard E2298-18 [12].

The maximum load energy (Wm) was determined by integrating the load-time record to the maximum load point via the instrumented Charpy software. The maximum load energy is approximately equivalent to the energy required to initiate a crack in the specimen. The integrated total impact energy (Wt) is compared to the absorbed energy measured from the dial energy (KV).

Percent shear was determined from post-fracture photographs using the ratio-of-areas method in compliance with ASTM E23-18 [11] and A370-18 [13]. The lateral expansion was measured using a dial gage rig similar to that shown in the same ASTM Standards.

Tensile tests were performed on a 250 kN capacity Instron screw driven tensile machine (Model 5985) equipped with Instron Bluehill 3 Software and an Instron 22.48 kip load cell per ASTM E185-82 [10].

1 Instron is a registered trademark of Instron Corporation. Other product and company names used herein are trademarks or trade names of their respective companies.

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Westinghouse Non-Proprietary Class 3 5-2 WCAP-18795-NP December 2022 Revision 0 Testing met ASTM Specifications E8/E8M-16a [14] for room temperature or E21-17 [15] for elevated temperatures.

The tensile specimens were, nominally, 4.2 inches long with a 1.00 inch gauge section and a reduced section of 1.25 inches long by 0.250 inches in diameter, as noted in WCAP-8193 [2]. Strain measurements were made using an extensometer (equipped with a Columbia Research Labs LVDT), which was attached to the 1.00 inch gauge section of the tensile specimen. The strain rate (crosshead speed controlled) obtained met the requirements of ASTM E8/E8M-16a [14] and ASTM E21-17 [15].

Elevated test temperatures were obtained with a three-zone electric resistance split-tube Instron SF-16 furnace with an 11-inch hot zone with an Instron TCS 3203 temperature controller. For the elevated temperature tests, two Type-N thermocouples were placed in contact with the specimens on both ends of the gauge-length section of the specimen per ASTM E21-17 [15]. Tensile specimens were soaked at temperature (+/- 5ºF) for a minimum of 20 minutes before testing. All testing was conducted in air.

The yield load, ultimate load, fracture load, uniform elongation, and elongation at fracture were determined directly from the load-extension curve. The yield strength (0.2% offset method), ultimate tensile strength, and fracture strength were calculated using the original cross-sectional area. Yield point elongation (YPE) was calculated as the difference in strain between the upper yield strength and the onset of uniform strain hardening using the methodology described in ASTM E8/E8M-16a [14]. The final diameter and final gauge length were determined from post-fracture photographs. This final diameter measurement was used to calculate the fracture stress (fracture true stress) and the percent reduction in area. The reported total elongation is the elongation at fracture.

All testing equipment was calibrated per Westinghouse procedures and in accordance with the ASTM standards cited herein. Records of calibration are available at Westinghouse.

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 N, which received a fluence of 8.41 x 1019 n/cm2 (E > 1.0 MeV) in 40.64 EFPY of operation, are presented in Tables 5-1 through 5-10 and are compared with the unirradiated and previously withdrawn capsule results as shown in Figures 5-1 through 5-15. The unirradiated capsule results were taken from WCAP-8193 [2].

Results from the previous capsules were obtained from WCAP-14613 [16] and confirmed to be applicable or updated as appropriate. The previous capsules, along with the original program unirradiated material input data, were updated using CVGRAPH, Version 6.02.

The transition temperature increases and decreases in upper-shelf energies for the Capsule N materials are summarized in Table 5-11 and led to the following results:

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Westinghouse Non-Proprietary Class 3 5-3 WCAP-18795-NP December 2022 Revision 0 Irradiation of the reactor vessel Lower Shell Forging D (Heat # 22642) Charpy specimens, oriented with the longitudinal axis of the specimen parallel to the major working direction (tangential orientation), resulted in an irradiated 30 ft-lb transition temperature of 148.2F and an irradiated 50 ft-lb transition temperature of 170.7°F. This results in a 30 ft-lb transition temperature increase of 176.5F and a 50 ft-lb transition temperature increase of 177.5F for the tangentially oriented specimens.

Irradiation of the reactor vessel Lower Shell Forging D (Heat # 22642) Charpy specimens, oriented with the longitudinal axis of the specimen perpendicular to the major working direction (axial orientation), resulted in an irradiated 30 ft-lb transition temperature of 152.9F and an irradiated 50 ft-lb transition temperature of 184.7F. This results in a 30 ft-lb transition temperature increase of 154.1F and a 50 ft-lb transition temperature increase of 150.1F for the axially oriented specimens.

Irradiation of the surveillance program weld material (Heat # 2721) Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 59.5F and an irradiated 50 ft-lb transition temperature of 112F. This results in a 30 ft-lb transition temperature increase of 135.6F and a 50 ft-lb transition temperature increase of 154.1F.

Irradiation of the Heat Affected Zone (HAZ) material Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 10.9F and an irradiated 50 ft-lb transition temperature of 50.4F.

This results in a 30 ft-lb transition temperature increase of 145.5F and a 50 ft-lb transition temperature increase of 148.4F.

Irradiation of the Correlation Monitor Material (CMM) Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 259.9F and an irradiated 50 ft-lb transition temperature of 310.3F.

This results in a 30 ft-lb transition temperature increase of 212.9F and a 50 ft-lb transition temperature increase of 232.3F.

The average upper-shelf energy of Lower Shell Forging D (Heat # 22642) (tangential orientation) resulted in an average energy decrease of 22.7 ft-lb after irradiation. This decrease results in an irradiated average upper-shelf energy of 125.0 ft-lb for the tangentially oriented specimens.

The average upper-shelf energy of Lower Shell Forging D (Heat # 22642) (axial orientation) resulted in an average energy decrease of 17.2 ft-lb after irradiation. This decrease results in an irradiated average upper-shelf energy of 89.0 ft-lb for the axially oriented specimens.

The average upper-shelf energy of the surveillance program weld material (Heat # 2721) Charpy specimens resulted in an average energy decrease of 8.3 ft-lb after irradiation. This decrease results in an irradiated average upper-shelf energy of 95.0 ft-lb for the weld specimens.

The average upper-shelf energy of the HAZ material Charpy specimens resulted in an average energy decrease of 32.0 ft-lb after irradiation. This decrease results in an irradiated average upper-shelf energy of 82.0 ft-lb for the HAZ specimens.

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Westinghouse Non-Proprietary Class 3 5-4 WCAP-18795-NP December 2022 Revision 0 The average upper-shelf energy of the CMM Charpy specimens resulted in an average energy decrease of 41.4 ft-lb after irradiation. This decrease results in an irradiated average upper-shelf energy of 79.0 ft-lb for the CMM specimens.

Comparisons of the measured 30 ft-lb shift in transition temperature values and upper-shelf energy decreases to those predicted by Regulatory Guide 1.99, Rev. 2 [1] for the Prairie Island Unit 2 reactor vessel surveillance materials are presented in Table 5-12.

The fracture appearance of each irradiated Charpy specimen from the various materials is shown in Figure 5-16 through Figure 5-20. The fractures show an increasingly ductile or tougher appearance with increasing test temperature. Load-time records for the individual instrumented Charpy specimens are contained in Appendix B.

5.3 TENSILE TEST RESULTS The results of the tensile tests performed on the various materials contained in Capsule N irradiated to 8.41 x 1019 n/cm2 (E > 1.0 MeV) are presented in Table 5-13 and are compared with unirradiated results as shown in Figure 5-21 through Figure 5-23.

The results of the tensile tests performed on the Lower Shell Forging D (Heat # 22642) (tangential orientation) indicated that irradiation to 8.41 x 1019 n/cm2 (E > 1.0 MeV) caused increases in the 0.2 percent offset yield strength and the ultimate tensile strength when compared to unirradiated data in WCAP-8193

[2]. See Figure 5-21.

The results of the tensile tests performed on the Lower Shell Forging D (Heat # 22642) (axial orientation) indicated that irradiation to 8.41 x 1019 n/cm2 (E > 1.0 MeV) caused increases in the 0.2 percent offset yield strength and the ultimate tensile strength when compared to unirradiated data in WCAP-8193 [2]. See Figure 5-22.

The results of the tensile tests performed on the surveillance program weld material (Heat # 2721) indicated that irradiation to 8.41 x 1019 n/cm2 (E > 1.0 MeV) caused increases in the 0.2 percent offset yield strength and the ultimate tensile strength when compared to unirradiated data in WCAP-8193 [2]. See Figure 5-23.

The fractured tensile specimens for the Lower Shell Forging D (Heat # 22642) (tangential orientation) material are shown in Figure 5-24; the fractured tensile specimens for the Lower Shell Forging D (Heat #

22642) (axial orientation) are shown in Figure 5-25; and the fracture tensile specimens for the surveillance program weld material are shown in Figure 5-26. The engineering stress-strain curves for the tensile tests are shown in Figure 5-27 through Figure 5-35.

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Westinghouse Non-Proprietary Class 3 5-5 WCAP-18795-NP December 2022 Revision 0 Table 5-1 Charpy V-notch Data for the Prairie Island Unit 2 Capsule N Lower Shell Forging D (Heat # 22642) (Tangential Orientation) Irradiated to a Fluence of 8.41 x 1019 n/cm2 (E > 1.0 MeV)

Specimen ID Temperature Impact Energy Lateral Expansion Shear %

°F

°C*

ft-lbs Joules*

mils mm*

NL59 73 23 20 27 13 0.3 5

NL56 120 49 11 15 11 0.3 10 NL53 130 54 14 19 13 0.3 15 NL57 140 60 36 49 27 0.7 15 NL51 155 68 20 27 20 0.5 10 NL49 165 74 45 61 34 0.9 20 NL58 175 79 57 77 42 1.1 30 NL55 200 93 97 132 57 1.4 60 NL60 225 107 77 104 54 1.4 55 NL52 250 121 126 171 78 2.0 100 NL54 300 149 127 172 85 2.2 100 NL50 325 163 122 165 79 2.0 100

  • Calculated conversion values.
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Westinghouse Non-Proprietary Class 3 5-6 WCAP-18795-NP December 2022 Revision 0 Table 5-2 Charpy V-notch Data for the Prairie Island Unit 2 Capsule N Lower Shell Forging D (Heat # 22642) (Axial Orientation) Irradiated to a Fluence of 8.41 x 1019 n/cm2 (E > 1.0 MeV)

Specimen ID Temperature Impact Energy Lateral Expansion Shear %

°F

°C*

ft-lbs Joules*

mils mm*

NT54 100 38 19 26 16 0.4 5

NT56 120 49 24 33 20 0.5 10 NT49 140 60 27 37 19 0.5 10 NT59 155 68 20 27 18 0.5 15 NT58 165 74 31 42 24 0.6 20 NT53 170 77 31 42 26 0.7 20 NT60 175 79 57 77 38 1.0 30 NT57 200 93 56 76 42 1.1 35 NT55 225 107 78 106 56 1.4 65 NT51 275 135 93 126 63 1.6 100 NT50 300 149 84 114 66 1.7 100 NT52 325 163 90 122 61 1.5 100

  • Calculated conversion values.
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Westinghouse Non-Proprietary Class 3 5-7 WCAP-18795-NP December 2022 Revision 0 Table 5-3 Charpy V-notch Data for the Prairie Island Unit 2 Capsule N Surveillance Program Weld Material Irradiated to a Fluence of 8.41 x 1019 n/cm2 (E > 1.0 MeV)

Specimen ID Temperature Impact Energy Lateral Expansion Shear %

°F

°C*

ft-lbs Joules*

mils mm*

NW36 30

-1 22 30 17 0.4 15 NW39 50 10 29 39 21 0.5 20 NW38 73 23 51 69 34 0.9 30 NW40 100 38 26 35 17 0.4 25 NW37 175 79 69 94 44 1.1 55 NW35 225 107 91 123 73 1.9 95 NW33 275 135 95 129 69 1.8 100 NW34 300 149 99 134 83 2.1 100

  • Calculated conversion values.
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Westinghouse Non-Proprietary Class 3 5-8 WCAP-18795-NP December 2022 Revision 0 Table 5-4 Charpy V-notch Data for the Prairie Island Unit 2 Capsule N Heat Affected Zone (HAZ) Irradiated to a Fluence of 8.41 x 1019 n/cm2 (E > 1.0 MeV)

Specimen ID Temperature Impact Energy Lateral Expansion Shear %

°F

°C*

ft-lbs Joules*

mils mm*

NH39

-25

-32 26 35 15 0.4 20 NH33 25

-4 33 45 19 0.5 25 NH36 30

-1 28 38 19 0.4 30 NH40 60 16 64 87 40 1.0 60 NH37 90 32 72 98 49 1.2 70 NH34 120 49 67 91 42 1.1 55 NH35 175 79 85 115 62 1.6 98 NH38 275 135 79 107 49 1.2 100

  • Calculated conversion values.
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Westinghouse Non-Proprietary Class 3 5-9 WCAP-18795-NP December 2022 Revision 0 Table 5-5 Charpy V-notch Data for the Prairie Island Unit 2 Capsule N Correlation Monitor Material (CMM) Irradiated to a Fluence of 8.41 x 1019 n/cm2 (E > 1.0 MeV)

Specimen ID Temperature Impact Energy Lateral Expansion Shear %

°F

°C*

ft-lbs Joules*

mils mm*

R37 200 93 16 22 10 0.3 15 R35 225 107 27 37 16 0.4 20 R34 240 116 12 16 10 0.3 18 R33 275 135 37 50 28 0.7 35 R36 320 160 54 73 39 1.0 50 R38 375 191 66 89 39 1.0 65 R39 425 218 84 114 51 1.3 100 R40 450 232 74 100 63 1.6 100

  • Calculated conversion values.
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Westinghouse Non-Proprietary Class 3 5-10 WCAP-18795-NP December 2022 Revision 0 Table 5-6 Instrumented Charpy Impact Test Results for the Prairie Island Unit 2 Capsule N Lower Shell Forging D (Heat # 22642)

(Tangential Orientation) Irradiated to a Fluence of 8.41 x 1019 n/cm2 (E > 1.0 MeV)

Specimen ID Test Temp

(°F)

Total Dial Energy, KV (ft-lb)

Total Instrumented Energy, Wt (ft-lb)

Difference, (KV-Wt)/KV

(%)

Energy to Max Load, Wm (ft-lb)

Maximum Load, Fm (lb)

Time to Fm (msec)

General Yield Load, Fgy (lb)

Brittle Fracture Load, Fbf (lb)

Arrest Load, Fa (lb)

NL59 73 20 19 4

15.9 4265 0.29 3413 4015 None NL56 120 11 8

26(1) 3.2 3767 0.09 2193 3256 None NL53 130 14 9

33(1) 3.3 3727 0.09 3289 3443 None NL57 140 36 30 16(1) 28.6 4102 0.51 3118 4039 None NL51 155 20 15 27(1) 11.7 3723 0.24 3104 3540 None NL49 165 45 37 18(1) 34.1 4130 0.60 3103 4050 None NL58 175 57 52 9

34.9 4188 0.61 3120 3956 1391 NL55 200 97 90 7

34.6 4184 0.60 3050 3557 2031 NL60 225 77 67 13 33.2 4055 0.60 2919 3788 1790 NL52 250 126 118 7

34.4 4156 0.60 2962 0

None NL54 300 127 118 7

33.3 4018 0.61 2938 0

None NL50 325 122 114 7

33.9 4040 0.61 2993 0

None Note:

1. The difference between instrumented Charpy and Dial values was greater than 15%. The values were not adjusted as required by ASTM E2298-18 [12] since this data is not required, but is presented for informational purposes only.
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Westinghouse Non-Proprietary Class 3 5-11 WCAP-18795-NP December 2022 Revision 0 Table 5-7 Instrumented Charpy Impact Test Results for the Prairie Island Unit 2 Capsule N Lower Shell Forging D (Heat # 22642)

(Axial Orientation) Irradiated to a Fluence of 8.41 x 1019 n/cm2 (E > 1.0 MeV)

Specimen ID Test Temp

(°F)

Total Dial Energy, KV (ft-lb)

Total Instrumented Energy, Wt (ft-lb)

Difference, (KV-Wt)/KV

(%)

Energy to Max Load, Wm (ft-lb)

Maximum Load, Fm (lb)

Time to Fm (msec)

General Yield Load, Fgy (lb)

Brittle Fracture Load, Fbf (lb)

Arrest Load, Fa (lb)

NT54 100 19 17 12 15.3 4015 0.29 3142 3934 None NT56 120 24 22 10 18.9 4004 0.36 3234 3810 None NT49 140 27 23 14 19.0 4013 0.36 3084 3971 None NT59 155 20 16 19(1) 14.8 3879 0.29 3116 3770 None NT58 165 31 25 21(1) 18.5 3914 0.36 3047 3840 451 NT53 170 31 26 17(1) 3.6 4111 0.11 3039 3981 415 NT60 175 57 51 11 35.8 4253 0.61 3146 4078 1526 NT57 200 56 47 15 26.9 4079 0.48 3154 3964 1766 NT55 225 78 71 9

34.3 4074 0.61 3055 3656 2506 NT51 275 93 87 6

33.7 4011 0.60 2966 0

None NT50 300 84 77 9

26.6 3823 0.51 2883 0

None NT52 325 90 84 7

33.2 3932 0.60 2905 0

None Note:

1. The difference between instrumented Charpy and Dial values was greater than 15%. The values were not adjusted as required by ASTM E2298-18 [12] since this data is not required, but is presented for informational purposes only.
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Westinghouse Non-Proprietary Class 3 5-12 WCAP-18795-NP December 2022 Revision 0 Table 5-8 Instrumented Charpy Impact Test Results for the Prairie Island Unit 2 Capsule N Surveillance Program Weld Material Irradiated to a Fluence of 8.41 x 1019 n/cm2 (E > 1.0 MeV)

Specimen ID Test Temp

(°F)

Total Dial Energy, KV (ft-lb)

Total Instrumented Energy, Wt (ft-lb)

Difference, (KV-Wt)/KV

(%)

Energy to Max Load, Wm (ft-lb)

Maximum Load, Fm (lb)

Time to Fm (msec)

General Yield Load, Fgy (lb)

Brittle Fracture Load, Fbf (lb)

Arrest Load, Fa (lb)

NW36 30 22 19 15 3.4 3973 0.09 3346 3564 461 NW39 50 29 26 10 18.5 3807 0.36 3143 3730 1097 NW38 73 51 47 8

34.7 4083 0.60 3332 3829 952 NW40 100 26 22 15 18.8 3883 0.36 3256 3763 761 NW37 175 69 61 11 33.2 3884 0.60 2957 3319 1563 NW35 225 91 83 8

31.3 3764 0.60 2870 2790 2124 NW33 275 95 87 8

32.1 3819 0.60 2870 0

None NW34 300 99 91 9

31.4 3761 0.60 2780 0

None

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-13 WCAP-18795-NP December 2022 Revision 0 Table 5-9 Instrumented Charpy Impact Test Results for the Prairie Island Unit 2 Capsule N Heat Affected Zone (HAZ) Irradiated to a Fluence of 8.41 x 1019 n/cm2 (E > 1.0 MeV)

Specimen ID Test Temp

(°F)

Total Dial Energy, KV (ft-lb)

Total Instrumented Energy, Wt (ft-lb)

Difference, (KV-Wt)/KV

(%)

Energy to Max Load, Wm (ft-lb)

Maximum Load, Fm (lb)

Time to Fm (msec)

General Yield Load, Fgy (lb)

Brittle Fracture Load, Fbf (lb)

Arrest Load, Fa (lb)

NH39

-25 26 23 10 21.5 4512 0.36 3524 4361 None NH33 25 33 30 10 20.9 4338 0.36 3647 4148 1529 NH36 30 28 21 24(1) 16.6 4342 0.29 3529 4180 591 NH40 60 64 58 10 36.7 4339 0.60 3426 4034 2612 NH37 90 72 67 7

37.0 4357 0.61 3360 3216 2043 NH34 120 67 62 7

20.0 4228 0.36 3408 2091 1190 NH35 175 85 78 8

24.0 4358 0.44 3304 2553 2091 NH38 275 79 74 7

24.0 4312 0.44 3333 0

None Note:

1. The difference between instrumented Charpy and Dial values was greater than 15%. The value was not adjusted as required by ASTM E2298-18 [12] since this data is not required, but is presented for informational purposes only.
      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-14 WCAP-18795-NP December 2022 Revision 0 Table 5-10 Instrumented Charpy Impact Test Results for Prairie Island Unit 2 Capsule N Correlation Monitor Material (CMM)

Irradiated to a Fluence of 8.41 x 1019 n/cm2 (E > 1.0 MeV)

Specimen ID Test Temp

(°F)

Total Dial Energy, KV (ft-lb)

Total Instrumented Energy, Wt (ft-lb)

Difference, (KV-Wt)/KV

(%)

Energy to Max Load, Wm (ft-lb)

Maximum Load, Fm (lb)

Time to Fm (msec)

General Yield Load, Fgy (lb)

Brittle Fracture Load, Fbf (lb)

Arrest Load, Fa (lb)

R37 200 16 15 8

9.8 4212 0.19 3638 4086 None R35 225 27 23 15 15.8 4253 0.29 3365 4155 730 R34 240 12 10 16(1) 9.3 3928 0.19 3324 3809 365 R33 275 37 33 12 15.5 4287 0.30 3353 4062 2158 R36 320 54 49 9

27.4 4158 0.48 3132 3972 2587 R38 375 66 62 7

20.5 4311 0.38 3232 3671 2220 R39 425 84 77 8

24.0 4253 0.44 3280 0

None R40 450 74 70 6

14.9 4065 0.29 3081 0

None Note:

1. The difference between instrumented Charpy and Dial values was greater than 15%. The value was not adjusted as required by ASTM E2298-18 [12] since this data is not required, but is presented for informational purposes only.
      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-15 WCAP-18795-NP December 2022 Revision 0 Table 5-11 Effect of Irradiation to 8.41 x 1019 n/cm2 (E > 1.0 MeV) on the Charpy V-notch Toughness Properties of the Prairie Island Unit 2 Reactor Vessel Surveillance Capsule N Materials Material Average 30 ft-lb Transition Temperature(1)

(°F)

Average 35 mil Lateral Expansion Temperature(1)

(°F)

Average 50 ft-lb Transition Temperature(1)

(°F)

Average Energy Absorption

> 95% Shear(2)

(ft-lb)

Unirradiated Irradiated T

Unirradiated Irradiated T

Unirradiated Irradiated T

Unirradiated Irradiated E

Lower Shell Forging D (Heat # 22642)

(Tangential Orientation)

-28.3 148.2 176.5

-10.0 169.2 179.2

-6.8 170.7 177.5 147.7 125.0

-22.7 Lower Shell Forging D (Heat # 22642)

(Axial Orientation)

-1.2 152.9 154.1 23.0 181.3 158.3 34.6 184.7 150.1 106.2 89.0

-17.2 Surveillance Weld Material (Heat # 2721)

-76.1 59.5 135.6

-47.6 124.8 172.4

-42.1 112.0 154.1 103.3 95.0

-8.3 Heat-Affected Zone (HAZ) Material

-134.6 10.9 145.5

-86.2 58.7 144.9

-98.0 50.4 148.4 114.0 82.0

-32.0 Correlation Monitor Material (CMM) 47.0 259.9 212.9 59.1 330.6 271.5 78.0 310.3 232.3 120.4 79.0

-41.4 Notes:

1.

Average value is determined by CVGRAPH (see Appendix C).

2.

USE values are a calculated average from unirradiated and Capsule N Charpy test results for specimens that achieved greater than or equal to 95% shear.

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-16 WCAP-18795-NP December 2022 Revision 0 Table 5-12 Comparison of the Prairie Island Unit 2 Surveillance Material 30 ft-lb Transition Temperature Shifts and Upper-Shelf Energy Decreases with Regulatory Guide 1.99, Revision 2, Predictions Material Capsule Capsule Fluence (x 1019 n/cm2, E > 1.0 MeV) 30 ft-lb Transition Temperature Shift Upper-Shelf Energy Decrease Predicted(1)

(°F)

Measured(2)

(°F)

Predicted(1)

(%)

Measured(2)

(%)

Lower Shell Forging D (Heat # 22642)

(Tangential Orientation)

V 0.598 43.7 33.8 17 0(3)

T 1.10 52.4 54.4 20 10 R

4.11 69.5 89.6 26 14 P

4.27 69.9 99.6 27 13 N

8.41 76.0 176.5 32 15 Lower Shell Forging D (Heat # 22642)

(Axial Orientation)

V 0.598 43.7 35.0 17 0(3)

T 1.10 52.4 27.9 20 13 R

4.11 69.5 84.3 26 7

P 4.27 69.9 103.5 27 11 N

8.41 76.0 154.1 32 16 Surveillance Weld Material (Heat # 2721)

V 0.598 44.2 69.3 20 6

T 1.10 53.0 57.7 23 8

R 4.11 70.3 100.3 31 12 P

4.27 70.7 96.2 32 5

N 8.41 76.9 135.6 37 8

Heat Affected Zone (HAZ)

V 0.598 42.9 0(3)

T 1.10 48.9 13 R

4.11 127.6 23 P

4.27 81.2 16 N

8.41 145.5 28 Correlation Monitor Material (CMM)

V 0.598 109.6 123.5 20 15 T

1.10 131.1 158.0 23 27 R

4.11 174.3 183.2 32 36 P

4.27 175.4 196.8 33 20 N

8.41 190.8 212.9 38 34 Notes:

1.

Based on Regulatory Guide 1.99, Revision 2 [1], methodology using the capsule fluence and best-estimate weight percent values of copper and nickel of the surveillance material. For the predicted USE decrease determinations, the Cu weight percentages were conservatively rounded up to the lowest line (Cu weight % of 0.10 for base metal and 0.05 for weld metal) in Regulatory Guide 1.99, Revision 2, Figure 2. Also note that for Capsule N, the fluence value is slightly beyond the scale in Figure 2; therefore, the predicted USE was extrapolated from the available data in the figure.

2.

Calculated using measured Charpy data (See Appendix C).

3.

Physically, an increase in USE should not occur after irradiation. Therefore, a conservative 0% decrease value is shown here instead of the measured increase.

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-17 WCAP-18795-NP December 2022 Revision 0 Table 5-13 Tensile Test Properties of the Prairie Island Unit 2 Capsule N Reactor Vessel Surveillance Materials Irradiated to 8.41 x 1019 n/cm2 (E > 1.0 MeV)

Material Specimen ID Test Temp

(°F) 0.2% Yield Strength (ksi)

Ultimate Strength (ksi)

Fracture Load (kip)

Fracture Strength (ksi)

Fracture True Stress (ksi)

Uniform Elongation

(%)

Total Elongation

(%)

Reduction in Area

(%)

Lower Shell Forging D (Heat # 22642)

(Tangential)

NL13 78 91.1 106.5 3.5 71.3 210 10.4 22.7 66.1 NL14 300 82.1 98.2 3.3 67.2 195 10.1 21.6 65.6 NL15 550 76.9 98.3 3.4 70.3 178 7.9 18.5 60.4 Lower Shell Forging D (Heat # 22642)

(Axial)

NT13 78 93.0 108.2 3.7 77.4 202 9.6 20.7 61.6 NT 14 300 78.7 98.2 3.6 73.9 173 6.9 14.9(1) 57.1 NT 15 550 82.5 101.7 3.8 78.5 170 7.8 16.7 53.7 Surveillance Weld (Heat # 2721)

NW13 78 100.2 109.3 4.0 82.7 205 8.3 19.0 59.7 NW14 300 80.7 92.4 2.9 60.9 204 5.9 18.6 70.1 NW15 550 77.2 94.0 3.4 70.1 179 8.8 19.0 60.9 Note:

1. Elongation at fracture value is low compared to the elongation after fracture for that specimen. May be an indication of the specimen gauge slipping.
      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-18 WCAP-18795-NP December 2022 Revision 0 Figure 5-1 Charpy V-notch Impact Energy vs. Temperature for Prairie Island Unit 2 Reactor Vessel Surveillance Program Lower Shell Forging D (Heat # 22642) (Tangential Orientation)

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-19 WCAP-18795-NP December 2022 Revision 0 Figure 5-1 Charpy V-notch Impact Energy vs. Temperature for Prairie Island Unit 2 Reactor Vessel Surveillance Program Lower Shell Forging D (Heat # 22642) (Tangential Orientation) (cont.)

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-20 WCAP-18795-NP December 2022 Revision 0 Figure 5-2 Charpy V-notch Lateral Expansion vs. Temperature for Prairie Island Unit 2 Reactor Vessel Surveillance Program Lower Shell Forging D (Heat # 22642) (Tangential Orientation)

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-21 WCAP-18795-NP December 2022 Revision 0 Figure 5-2 Charpy V-notch Lateral Expansion vs. Temperature for Prairie Island Unit 2 Reactor Vessel Surveillance Program Lower Shell Forging D (Heat # 22642) (Tangential Orientation) (cont.)

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-22 WCAP-18795-NP December 2022 Revision 0 Figure 5-3 Charpy V-notch Percent Shear vs. Temperature for Prairie Island Unit 2 Reactor Vessel Surveillance Program Lower Shell Forging D (Heat # 22642) (Tangential Orientation)

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-23 WCAP-18795-NP December 2022 Revision 0 Figure 5-3 Charpy V-notch Percent Shear vs. Temperature for Prairie Island Unit 2 Reactor Vessel Surveillance Program Lower Shell Forging D (Heat # 22642) (Tangential Orientation) (cont.)

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-24 WCAP-18795-NP December 2022 Revision 0 Figure 5-4 Charpy V-notch Impact Energy vs. Temperature for Prairie Island Unit 2 Reactor Vessel Surveillance Program Lower Shell Forging D (Heat # 22642) (Axial Orientation)

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-25 WCAP-18795-NP December 2022 Revision 0 Figure 5-4 Charpy V-notch Impact Energy vs. Temperature for Prairie Island Unit 2 Reactor Vessel Surveillance Program Lower Shell Forging D (Heat # 22642) (Axial Orientation) (cont.)

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-26 WCAP-18795-NP December 2022 Revision 0 Figure 5-5 Charpy V-notch Lateral Expansion vs. Temperature for Prairie Island Unit 2 Reactor Vessel Surveillance Program Lower Shell Forging D (Heat # 22642) (Axial Orientation)

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-27 WCAP-18795-NP December 2022 Revision 0 Figure 5-5 Charpy V-notch Lateral Expansion vs. Temperature for Prairie Island Unit 2 Reactor Vessel Surveillance Program Lower Shell Forging D (Heat # 22642) (Axial Orientation) (cont.)

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-28 WCAP-18795-NP December 2022 Revision 0 Figure 5-6 Charpy V-notch Percent Shear vs. Temperature for Prairie Island Unit 2 Reactor Vessel Surveillance Program Lower Shell Forging D (Heat # 22642) (Axial Orientation)

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-29 WCAP-18795-NP December 2022 Revision 0 Figure 5-6 Charpy V-notch Percent Shear vs. Temperature for Prairie Island Unit 2 Reactor Vessel Surveillance Program Lower Shell Forging D (Heat # 22642) (Axial Orientation) (cont.)

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-30 WCAP-18795-NP December 2022 Revision 0 Figure 5-7 Charpy V-notch Impact Energy vs. Temperature for Prairie Island Unit 2 Reactor Vessel Surveillance Program Weld Material

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-31 WCAP-18795-NP December 2022 Revision 0 Figure 5-7 Charpy V-notch Impact Energy vs. Temperature for Prairie Island Unit 2 Reactor Vessel Surveillance Program Weld Material (cont.)

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-32 WCAP-18795-NP December 2022 Revision 0 Figure 5-8 Charpy V-notch Lateral Expansion vs. Temperature for Prairie Island Unit 2 Reactor Vessel Surveillance Program Weld Material

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-33 WCAP-18795-NP December 2022 Revision 0 Figure 5-8 Charpy V-notch Lateral Expansion vs. Temperature for Prairie Island Unit 2 Reactor Vessel Surveillance Program Weld Material (cont.)

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-34 WCAP-18795-NP December 2022 Revision 0 Figure 5-9 Charpy V-notch Percent Shear vs. Temperature for Prairie Island Unit 2 Reactor Vessel Surveillance Program Weld Material

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-35 WCAP-18795-NP December 2022 Revision 0 Figure 5-9 Charpy V-notch Percent Shear vs. Temperature for Prairie Island Unit 2 Reactor Vessel Surveillance Program Weld Material (cont.)

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-36 WCAP-18795-NP December 2022 Revision 0 Figure 5-10 Charpy V-notch Impact Energy vs. Temperature for Prairie Island Unit 2 Reactor Vessel Heat-Affected Zone Material

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-37 WCAP-18795-NP December 2022 Revision 0 Figure 5-10 Charpy V-notch Impact Energy vs. Temperature for Prairie Island Unit 2 Reactor Vessel Heat-Affected Zone Material (cont.)

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-38 WCAP-18795-NP December 2022 Revision 0 Figure 5-11 Charpy V-notch Lateral Expansion vs. Temperature for Prairie Island Unit 2 Reactor Vessel Heat-Affected Zone Material

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-39 WCAP-18795-NP December 2022 Revision 0 Figure 5-11 Charpy V-notch Lateral Expansion vs. Temperature for Prairie Island Unit 2 Reactor Vessel Heat-Affected Zone Material (cont.)

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-40 WCAP-18795-NP December 2022 Revision 0 Figure 5-12 Charpy V-notch Percent Shear vs. Temperature for Prairie Island Unit 2 Reactor Vessel Heat-Affected Zone Material

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-41 WCAP-18795-NP December 2022 Revision 0 Figure 5-12 Charpy V-notch Percent Shear vs. Temperature for Prairie Island Unit 2 Reactor Vessel Heat-Affected Zone Material (cont.)

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-42 WCAP-18795-NP December 2022 Revision 0 Figure 5-13 Charpy V-notch Impact Energy vs. Temperature for Prairie Island Unit 2 Reactor Vessel Correlation Monitor Material

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-43 WCAP-18795-NP December 2022 Revision 0 Figure 5-13 Charpy V-notch Impact Energy vs. Temperature for Prairie Island Unit 2 Reactor Vessel Correlation Monitor Material (cont.)

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-44 WCAP-18795-NP December 2022 Revision 0 Figure 5-14 Charpy V-notch Lateral Expansion vs. Temperature for Prairie Island Unit 2 Reactor Vessel Correlation Monitor Material

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-45 WCAP-18795-NP December 2022 Revision 0 Figure 5-14 Charpy V-notch Lateral Expansion vs. Temperature for Prairie Island Unit 2 Reactor Vessel Correlation Monitor Material (cont.)

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-46 WCAP-18795-NP December 2022 Revision 0 Figure 5-15 Charpy V-notch Percent Shear vs. Temperature for Prairie Island Unit 2 Reactor Vessel Correlation Monitor Material

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-47 WCAP-18795-NP December 2022 Revision 0 Figure 5-15 Charpy V-notch Percent Shear vs. Temperature for Prairie Island Unit 2 Reactor Vessel Correlation Monitor Material (cont.)

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-48 WCAP-18795-NP December 2022 Revision 0 Figure 5-16 Charpy Impact Specimen Fracture Surfaces for Prairie Island Unit 2 Capsule N Lower Shell Forging D (Heat # 22642) (Tangential Orientation)

NL59, 73°F NL56, 120°F NL53, 130°F NL57, 140°F NL51, 155°F NL49, 165°F NL58, 175°F NL55, 200°F NL60, 225°F NL52, 250°F NL54, 300°F NL50, 325°F

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-49 WCAP-18795-NP December 2022 Revision 0 Figure 5-17 Charpy Impact Specimen Fracture Surfaces for Prairie Island Unit 2 Capsule N Lower Shell Forging D (Heat # 22642) (Axial Orientation)

NT54, 100°F NT56, 120°F NT49, 140°F NT59 155°F NT58, 165°F NT53, 170°F NT60, 175°F NT57, 200°F NT55, 225°F NT51, 275°F NT50, 300°F NT52, 325°F

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-50 WCAP-18795-NP December 2022 Revision 0 Figure 5-18 Charpy Impact Specimen Fracture Surfaces for the Prairie Island Unit 2 Capsule N Weld Material NW36, 30°F NW39, 50°F NW38, 73°F NW40, 100°F NW37, 175°F NW35, 225°F NW33, 275°F NW34, 300°F

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-51 WCAP-18795-NP December 2022 Revision 0 Figure 5-19 Charpy Impact Specimen Fracture Surfaces for the Prairie Island Unit 2 Capsule N Heat-Affected Zone (HAZ) Material NH39, -25°F NH33, 25°F NH36, 30°F NH40, 60°F NH37, 90°F NH34, 120°F NH35, 175°F NH38, 275°F

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-52 WCAP-18795-NP December 2022 Revision 0 Figure 5-20 Charpy Impact Specimen Fracture Surfaces of the Prairie Island Unit 2 Capsule N Correlation Monitor Material (CMM)

R37, 200°F R35, 225°F R34, 240°F R33, 275°F R36, 320°F R38, 375°F R39, 425°F R40, 450°F

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-53 WCAP-18795-NP December 2022 Revision 0 Legend:,, and are unirradiated

,, and are irradiated to 8.41 x 1019 n/cm2 (E > 1.0 MeV)

Figure 5-21 Tensile Properties for Prairie Island Unit 2 Reactor Vessel Lower Shell Forging D (Heat # 22642) (Tangential Orientation)

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-54 WCAP-18795-NP December 2022 Revision 0 Legend:,, and are unirradiated

,, and are irradiated to 8.41 x 1019 n/cm2 (E > 1.0 MeV)

Figure 5-22 Tensile Properties for Prairie Island Unit 2 Reactor Vessel Lower Shell Forging D (Heat # 22642) (Axial Orientation)

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-55 WCAP-18795-NP December 2022 Revision 0 Legend:,, and are unirradiated

,, and are irradiated to 8.41 x 1019 n/cm2 (E > 1.0 MeV)

Figure 5-23 Tensile Properties for Prairie Island Unit 2 Reactor Vessel Surveillance Program Weld Material

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-56 WCAP-18795-NP December 2022 Revision 0 NL13 tested at 78°F.

NL14 tested at 300°F.

NL15 tested at 550°F.

Figure 5-24 Fractured Tensile Specimens from Prairie Island Unit 2 Capsule N Lower Shell Forging D (Heat # 22642) (Tangential Orientation) [Scale in 1/10th of inch]

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-57 WCAP-18795-NP December 2022 Revision 0 NT13 tested at 78°F.

NT14 tested at 300°F.

NT15 tested at 550°F.

Figure 5-25 Fractured Tensile Specimens from Prairie Island Unit 2 Capsule N Lower Shell Forging D (Heat # 22642) (Axial Orientation) [Scale in 1/10th of inch]

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-58 WCAP-18795-NP December 2022 Revision 0 NW13 tested at 78°F.

NW14 tested at 300°F.

NW15 tested at 550°F.

Figure 5-26 Fractured Tensile Specimens from Prairie Island Unit 2 Capsule N Weld Metal [Scale in 1/10th of inch]

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-59 WCAP-18795-NP December 2022 Revision 0 Figure 5-27 Engineering Stress-Strain Curve for Prairie Island Unit 2, Capsule N, Tensile Specimen NL13 (Tangential Orientation), Tested at 78°F Figure 5-28 Engineering Stress-Strain Curve for Prairie Island Unit 2, Capsule N, Tensile Specimen NL14 (Tangential Orientation), Tested at 300°F Figure 5-29 Engineering Stress-Strain Curve for Prairie Island Unit 2, Capsule N, Tensile Specimen NL15 (Tangential Orientation), Tested at 550°F

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-60 WCAP-18795-NP December 2022 Revision 0 Figure 5-30 Engineering Stress-Strain Curve for Prairie Island Unit 2, Capsule N, Tensile Specimen NT13 (Axial Orientation), Tested at 78°F Figure 5-31 Engineering Stress-Strain Curve for Prairie Island Unit 2, Capsule N, Tensile Specimen NT14 (Axial Orientation), Tested at 300°F Figure 5-32 Engineering Stress-Strain Curve for Prairie Island Unit 2, Capsule N, Tensile Specimen NT15 (Axial Orientation), Tested at 550°F

      • This record was final approved on 12/14/2022, 8:08:16 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-61 WCAP-18795-NP December 2022 Revision 0 Figure 5-33 Engineering Stress-Strain Curve for Prairie Island Unit 2, Capsule N, Tensile Specimen NW13 (Weld), Tested at 78°F Figure 5-34 Engineering Stress-Strain Curve for Prairie Island Unit 2, Capsule N, Tensile Specimen NW14 (Weld), Tested at 300°F Figure 5-35 Engineering Stress-Strain Curve for Prairie Island Unit 2, Capsule N, Tensile Specimen NW15 (Weld), Tested at 550°F

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