ML22067A149

WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Cover Through Section 5

ML22067A149
Person / Time
Site:	Prairie Island
Issue date:	11/30/2021
From:	Benson R, Long M, Mays B Westinghouse, Westinghouse
To:	Office of Nuclear Reactor Regulation
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ML22067A147	List: L-PI-22-005, WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 5 Through Appendix D ML22067A148 ML22067A149 ML22067A150 ML22067A151 ML22067A152 ML22067A153 ML22067A154
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L-PI-22-005 WCAP-18660-NP, Rev 0
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Westinghouse Non-Proprietary Class 3

WCAP-18660-NP November 2021 Revision 0

Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program

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WCAP -18660-NP Revision 0

Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program

Margaret L. Long*

Reactor Vessel/Containment Vessel (RV/CV)

Design & Analysis

Benjamin E. Mays*

License Renewal, Radiation Analysis, and Nuclear Operations

Riley I. Benson*

Nuclear Operations

November 2021

Reviewers: D. Brett Lynch*

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

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

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

© 2021 Westinghouse Electric Company LLC All Rights Reserved

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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 5.4 WEDGE OPENING LOADING SPECIMENS.............................................................. 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 1 SURVEILLANCE PROGRAM CREDIBILITY EVALUATION............................................................................................................... D-1

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LIST OF TABLES Table 4-1 Chemical Composition (wt. %) of the Prairie Island Unit 1 Reactor Vessel Surveillance Materials (Unirradiated)(1)................................................................................................ 4-3

Table 4-2 Heat Treatment History of the Prairie Island Unit 1 Reactor Vessel and Surveillance Materials(1)....................................................................................................................... 4-4

Table 5-1 Charpy V-notch Data for the Prairie Island Unit 1 Capsule N Intermediate Shell Forging C (Tangential Orientation) Irradiated to a Fluence of 8.45 x 1019 n/cm2 (E > 1.0 MeV). 5-5

Table 5-2 Charpy V-notch Data for the Prairie Island Unit 1 Capsule N Intermediate Shell Forging C (Axial Orientation) Irradiated to a Fluence of 8.45 x 1019 n/cm2 (E > 1.0 MeV)......... 5-6

Table 5-3 Charpy V-notch Data for the Prairie Island Unit 1 Capsule N Surveillance Program Weld Material (Heat # 1752) Irradiated to a Fluence of 8.45 x 1019 n/cm2 (E > 1.0 MeV)...... 5-7

Table 5-4 Charpy V-notch Data for the Prairie Island Unit 1 Capsule N Heat Affected Zone (HAZ)

Irradiated to a Fluence of 8.45 x 1019 n/cm2 (E > 1.0 MeV)............................................ 5-8

Table 5-5 Charpy V-notch Data for the Prairie Island Unit 1 Capsule N Correlation Monitor Material (CMM) Irradiated to a Fluence of 8.45 x 1019 n/cm2 (E > 1.0 MeV)................ 5-9

Table 5-6 Instrumented Charpy Impact Test Results for the Prairie Island Unit 1 Capsule N Intermediate Shell Forging C (Tangential Orientation) Irradiated to a Fluence of 8.45 x 1019 n/cm 2 (E > 1.0 MeV).............................................................................................. 5-10

Table 5-7 Instrumented Charpy Impact Test Results for the Prairie Island Unit 1 Capsule N Intermediate Shell Forging C (Axial Orientation) Irradiated to a Fluence of 8.45 x 1019 n/cm 2 (E > 1.0 MeV).............................................................................................. 5-11

Table 5-8 Instrumented Charpy Impact Test Results for the Prairie Island Unit 1 Capsule N Surveillance Program Weld Material (Heat # 1752) Irradiated to a Fluence of 8.45 x 1019 n/cm2 (E > 1.0 MeV).............................................................................................. 5-12

Table 5-9 Instrumented Charpy Impact Test Results for the Prairie Island Unit 1 Capsule N Heat Affected Zone Irradiated to a Fluence of 8.45 x 1019 n/cm2 (E > 1.0 MeV).................. 5-13

Table 5-10 Instrumented Charpy Impact Test Results for Prairie Island Unit 1 Capsule N Correlation Monitor Material Irradiated to a Fluence of 8.45 x 10 19 n/cm2 (E > 1.0 MeV)

....................................................................................................................................... 5-14 Table 5-11 Effect of Irradiation to 8.45 x 10 19 n/cm2 (E > 1.0 MeV) on the Charpy V -notch Toughness Properties of the Prairie Island Unit 1 Reactor Vessel Surveill ance Capsule N Materials........................................................................................................................ 5-15 Table 5-12 Comparison of the Prairie Island Unit 1 Surveillance Material 30 ft -lb Transition Temperature Shifts and Upper -Shelf Energy Decreases with Regulatory Guide 1.99, Revision 2, Predictions.................................................................................................. 5-16 Table 5-13 Tensile Properties of the Prairie Island Unit 1 Capsule N Reactor Vessel Surveillance Materials Irradiated to 8.45 x 10 19 n/cm2 (E > 1.0 MeV).............................................. 5-17

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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 (Full -Power Operations)..................................................... 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 (Full-Power Operations)................................................................................. 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 Surveillance Capsule Withdrawal Schedule.................................................................... 7-1 Table A-1 Nuclear Parameters Used in the Evaluation of Neutron Sensors.................................... A-9 Table A-2 Monthly Thermal Generation at Prairie Island Unit 1 Cycles 18 through 31............... A-10 Table A-2 Monthly Thermal Generation at Prairie Island Unit 1 Cycles 18 through 31 (cont.)... A-11 Table A-2 Monthly Thermal Generation at Prairie Island Unit 1 Cycles 18 through 31 (cont.)... A-12 Table A-2 Monthly Thermal Generation at Prairie Island Unit 1 Cycles 18 through 31 (cont.)... A-13 Table A-3 Measured Sensor Activities and Reaction Rates for Surveillance Capsule V.............. A-14 Table A-4 Measured Sensor Activities and Reaction Rates for Surveillance Capsule P............... A-15 Table A-5 Measured Sensor Activities and Reaction Rates for Surveillance Capsule R............... A-16 Table A-6 Measured Sensor Activities and Reaction Rates for Surveillance Capsule S............... A-17 Table A-7 Measured Sensor Activities and Reaction Rates for Surveillance Capsule N.............. A-18 Table A-8 Least-Squares Evaluation of Dosimetry in Surveillance Capsule V (13° Position, Core Midplane, Irradiated During Cycle 1)........................................................................... A-19 Table A-9 Least-Squares Evaluation of Dosimetry in Surveillance Capsule P (23° Position, Core Midplane, Irradiated During Cycles 1 through 5)......................................................... A-20 Table A-10 Least-Squares Evaluation of Dosimetry in Surveillance Capsule R (13° Position, Core Midplane, Irradiated During Cycles 1 through 9)......................................................... A-21

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Table A-11 Least-Squares Evaluation of Dosimetry in Surveillance Capsule S (33° Position, Core Midplane, Irradiated During Cycles 1 through 17 )....................................................... A-22 Table A-12 Least-Squares Evaluation of Dosimetry in Surveillance Capsule N (33° Position, Core Midplane, Irradiated During Cycles 1 through 31)....................................................... A-23 Table A-13 Measured -to-Calculated (M/C) Reaction Rates - In-Vessel Capsules.......................... A-24 Table A-14 Best -Estimate -to-Calculated (BE/C) Exposure Rates - In-Vessel Capsules................. A-24 Table C-1 Upper-Shelf Energy Values (ft-lb) Fixed in CVGRAPH(1)............................................. C-2

Table D-1 Calculation of Interim Chemistry Factors for the Credibility Evaluation Using Prairie Island Unit 1 Surveillance Data...................................................................................... D-4 Table D-2 Best-Fit Evaluation For Prairie Island Unit 1 Surveillance Materials Only................... D-5 Table D-3 Calculation of Residual vs. Fast Fluence for Prairie Island Unit 1................................. D-7

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LIST OF FIGURES Figure 4-1 Arrangement of Surveillance Capsules in the Prairie Island Unit 1 Reactor Vessel........ 4-5 Figure 4-2 Prairie Island Unit 1 Surveillance Capsule N Specimen Locations................................. 4-6 Figure 5-1 Charpy V-Notch Impact Energy vs. Temperature for Prairie Island Unit 1 Reactor Vessel Surveillance Program Intermediate Shell Forging C (Tangential Orientation).............. 5-18 Figure 5-2 Charpy V-Notch Lateral Expansion vs. Temperature for Prairie Island Unit 1 Reactor Vessel Surveillance Program Intermediate Shell Forging C (Tangential Orientation).. 5-20 Figure 5-3 Charpy V-Notch Percent Shear vs. Temperature for Prairie Island Unit 1 Reactor Vessel Surveillance Program Intermediate Shell Forging C (Tangential Orientation).............. 5-22 Figure 5-4 Charpy V-Notch Impact Energy vs. Temperature for Prairie Island Unit 1 Reactor Vessel Surveillance Program Intermediate Shell Forging C (Axial Orientation)...................... 5-24 Figure 5-5 Charpy V-Notch Lateral Expansion vs. Temperature for Prairie Island Unit 1 Reactor Vessel Surveillance Program Intermediate Shell Forging C (Axial Orientation).......... 5-26 Figure 5-6 Charpy V-Notch Percent Shear vs. Temperature for Prairie Island Unit 1 Reactor Vessel Surveillance Program Intermediate Shell Forging C (Axial Orientation)...................... 5-28 Figure 5-7 Charpy V-Notch Impact Energy vs. Temperature for Prairie Island Unit 1 Reactor Vessel Surveillance Program Weld Material (Heat # 1752)...................................................... 5-30 Figure 5-8 Charpy V-Notch Lateral Expansion vs. Temperature for Prairie Island Unit 1 Reactor Vessel Surveillance Program Weld Material (Heat # 1752)........................................... 5-32 Figure 5-9 Charpy V-Notch Percent Shear vs. Temperature for Prairie Island Unit 1 Reactor Vessel Surveillance Program Weld Material (Heat # 1752)...................................................... 5-34 Figure 5-10 Charpy V-Notch Impact Energy vs. Temperature for Prairie Island Unit 1 Reactor Vessel Heat-Affected Zone Material......................................................................................... 5-36 Figure 5-11 Charpy V-Notch Lateral Expansion vs. Temperature for Prairie Islan d Unit 1 Reactor Vessel Heat -Affected Zone Material.............................................................................. 5-38 Figure 5-12 Charpy V-Notch Percent Shear vs. Temperature for Prairie Island Unit 1 Reactor Vessel Heat-Affec ted Zone Material......................................................................................... 5-40 Figure 5-13 Charpy V-Notch Impact Energy v s. Temperature for Prairie Island Unit 1 Reactor Vessel Correlation Monitor Material......................................................................................... 5-42 Figure 5-14 Charpy V-Notch Lateral Expansion vs. Temperature for Prairie Island Unit 1 Reactor Vessel Correlation Monitor Material............................................................................. 5-44 Figure 5-15 Charpy V-Notch Percent Shear vs. Temperature for Prairie Island Unit 1 Reactor Vessel Correlation Monitor Material......................................................................................... 5-46 Figure 5-16 Charpy Impact Sp ecimen Fracture Surfaces for Prairie Island Unit 1 Capsule N Intermediate Shell Forging C (Tangential Orientation)................................................. 5-48 Figure 5-17 Charpy Impact Specimen Fracture Surfaces for Prairie Island Unit 1 Capsule N Intermediate Shell Forging C (Axial Orientation)......................................................... 5-49 Figure 5-18 Charpy Impact Specimen Fracture Surfaces for the Prairie Island Unit 1 Capsule N Weld Material (Heat # 1752)................................................................................................... 5-50 Figure 5-19 Charpy Impact Specimen Fracture Surfaces for the Prairie Island Unit 1 Capsule N Heat-Affected Zone Material.................................................................................................. 5-51

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Figure 5-20 Charpy Impact Specimen Fracture Surfaces of the Prairie Island Unit 1 Capsule N Correlation Monitor Material......................................................................................... 5-52 Figure 5-21 Tensile Properties for Prairie Island Unit 1 Reactor Vessel Intermediate Shell Forging C (Tangential Orientation)................................................................................................. 5-53 Figure 5-22 Tensile Properties for Prairie Island Unit 1 Reactor Vessel Intermediate Shell Forging C (Axial Orientation)......................................................................................................... 5-54 Figure 5-23 Tensile Properties for Prairie Island Unit 1 Reactor Vessel Surveillance Program Weld Material (Heat # 1752)................................................................................................... 5-55 Figure 5-24 Fractured Tensile Specimens from Prairie Island Unit 1 Capsule N Intermediate Shell Forging C (Tangential Orientation) [Scale in 1/10th of inch]........................................ 5-56 Figure 5-25 Fractured Tensile Specimens from Prairie Island Unit 1 Capsule N Intermediate Shell Forging C (Axial Orientation) [Scale in 1/10th of inch]................................................ 5-57

Figure 5-26 Fractured Tensile Specimens from Prairie Island Unit 1 Capsule N Intermediate Shell Forging C Weld Metal [Scale in 1/10th of inch]............................................................. 5-58

Figure 5-27 Engineering Stress-Strain Curve for Prairie Island Unit 1 Capsule N Tensile Specimen N13 (Tangential Orientation), Tested at 79°F........................................................................ 5-59 Figure 5-28 Engineering Stress-Strain Curve for Prairie Island Unit 1 Capsule N Tensile Specimen N14 (Tangential Orientation), Tested at 250°F...................................................................... 5-59 Figure 5-29 Engineering Stress-Strain Curve for Prairie Island Unit 1 Capsule N Tensile Specimen N15 (Tangential Orientation), Tested at 550°F...................................................................... 5-59 Figure 5-30 Engineering Stress-Strain Curve for Prairie Island Unit 1 Capsule N Tensile Specimen S13 (Axial Orientation), Tested at 81°F................................................................................ 5-60 Figure 5-31 Engineering Stress-Strain Curve for Prairie Island Unit 1 Capsule N Tensile Specimen S14 (Axial Orientation), Tested at 250°F.............................................................................. 5-60 Figure 5-32 Engineering Stress-Strain Curve for Prairie Island Unit 1 Capsule N Tensile Specimen S15 (Axial Orientation), Tested at 550°F.............................................................................. 5-60 Figure 5-33 Engineering Stress-Strain Curve for Prairie Island Unit 1 Capsule N Tensile Specimen W13 (Weld), Tested at 83°F................................................................................................... 5-61 Figure 5-34 Engineering Stress-Strain Curve for Prairie Island Unit 1 Capsule N Tensile Specimen W14 (Weld), Tested at 250°F................................................................................................. 5-61 Figure 5-35 Engineering Stress-Strain Curve for Prairie Island Unit 1 Capsule N Tensile Specimen W15 (Weld), Tested at 550°F................................................................................................. 5-61 Figure 6-1 Prairie Island Unit 1 Plan View of the Reactor Geometry at the Core Midplane.......... 6-19 Figure 6-2 Prairie Island Unit 1 Plan View of the Reactor Geometry at the Nozzle Centerline..... 6-20 Figure 6-3 Prairie Island Unit 1 Section View of the Reactor Geometry at 0-Degrees................... 6-21 Figure 6-4 Prairie Island Unit 1 Section View of the Reactor Geometry at 33-Degrees................. 6-22

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EXECUTIVE

SUMMARY

The purpose of this report is to document the testing results of surveillance Capsule N from Prairie Island Unit 1. Capsule N was removed at 40.06 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 8.45 x 1019 n/cm2 (E >

1.0 MeV) after irradiation to 40.06 EFPY. The peak clad/base metal interface vessel fluence at 54 EFPY (end-of-license extension) of plant operation is projected to be 5.63 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 (Heat # 1752), and Correlation Monitor Material (CMM) contained in Prairie Island Unit 1 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 Intermediate Shell Forging C (tangential and axial orientations), surveillance weld material (Heat # 1752),

and CMM, are less than the Regulatory Guide 1.99, Rev. 2, Position 1.2 predictions. (3) The Prairie Island Unit 1 surveillance forging and surveillance weld data are deemed to be non-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.

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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 1 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 8.45 x 1019 n/cm2 after 40.06 effective full-power years (EFPY) of plant operation.

• Irradiation of the reactor vessel Intermediate Shell Forging C 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 126.5F. This results in a 30 ft-lb transition temperature increase of 165.5F for the tangentially oriented specimens.

• Irradiation of the reactor vessel Intermediate Shell Forging C 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 116.5F. This results in a 30 ft-lb transition temperature increase of 147.5F for the axially oriented specimens.

• Irradiation of the surveillance program weld material (Heat # 1752, Flux Type UM89, Lot # 1230)

Charpy specimens resulted in an irradiated 30 ft -lb transition temperature of 154F. This results in a 30 ft-lb transition temperature increase of 219F 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 -54.9F. This results in a 30 ft-lb transition temperature increase of 210.1F 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 246.5F. This results in a 30 ft-lb transition temperature increase of 199.5F for the CMM specimens.

• The average upper-shelf energy of Intermediate Shell Forging C (tangential orientation) resulted in an average energy decrease of 20.5 ft-lb after irradiation. This decrease results in an irradiated average upper-shelf energy of 138 ft-lb for the tangentially oriented specimens.

• The average upper-shelf energy of Intermediate Shell Forging C (axial orientation) resulted in an average energy decrease of 23.6 ft-lb after irradiation. This decrease results in an irradiated average upper-shelf energy of 119.5 ft-lb for the axially oriented specimens.

• The average upper-shelf energy of the surveillance program weld material (Heat # 1752) Charpy specimens resulted in an average energy decrease of 3.5 ft-lb after irradiation. This decrease results in

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an irradiated average upper-shelf energy of 79.0 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 105.9 ft-lb after irradiation. This decrease results in an irradiated average upper -shelf energy of 105.2 ft-lb for the HAZ material.

• The average upper-shelf energy of the CMM Charpy specimens resulted in an average energy decrease of 63.6 ft-lb after irradiation. This decrease results in an irradiated average upper-shelf energy of 56.8 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 1 reactor vessel surveillance materials are presented in Table 5-12.

• Based on the credibility evaluation presented in Appendix D, the Prairie Island Unit 1 surveillance plate and surveillance weld material data are deemed non-credible.

• The maximum calculated 54 EFPY (end-of-license extension) neutron fluence (E > 1.0 MeV) for the Prairie Island Unit 1 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* = 5.63 x 1019 n/cm2 Vessel peak quarter-thickness (1/4T) fluence = 3.77 x 1019 n/cm2

Vessel peak three-quarter thickness (3/4T) fluence = 1.69 x 1019 n/cm2

• This fluence value is determined from data in Table 6-5.

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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 1 reactor pressure vessel materials under actual operating conditions.

The surveillance program for the Prairie Island Unit 1 reactor pressure vessel materials was designed and recommended by Westinghouse Electric Company LLC. A detailed description of the surveillance program is contained in WCAP-8086 [2], Northern States Power Co. Prairie Island Unit No. 1 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 40.06 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 1 reactor vessel and presents the analysis of the data.

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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 1 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 resu lts 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 1 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.

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4 DESCRIPTION OF PROGRAM

Six surveillance capsules for monitoring the effects of neutron exposure on the Prairie Island Unit 1 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:

• Intermediate Shell Forging C - Tangential Orientation (Heat # 21918/38566)

• Intermediate Shell Forging C - Axial Orientation (Heat # 21918/38566)

• Surveillance Weld Metal (Heat #1752, Flux Type UM 89, Lot # 1230)

• Heat Affected Zone Material

• Correlation Monitor Material

Test material from Intermediate Shell Forging C 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 Intermediate Shell Forging C. 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 Intermediate Shell Forging C 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. Tensile specimens from the surveillance weld were oriented with the longitudinal axis of the specimens parallel to the welding direction, consistent with WCAP-11006 [8].

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 E399-70T.

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

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 the previous surveillance capsule report WCAP-14779 [16].

Capsule N was removed after 40.06 EFPY of plant operation. The capsule contained Charpy V-notch specimens, tensile specimens, WOL specimens, dosimeters, amd 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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Table 4-1 Chemical Composition (wt. %) of the Prairie Island Unit 1 Reactor Vessel Surveillance Materials (Unirradiated)(1)

Element Intermediate Weld Metal Shell Forging C

C 0.17 0.052 Mn 1.41 1.30 P 0.013 0.017 S 0.005 0.014 Si 0.28 0.36 Mo 0.48 0.51 Ni 0.72 0.11(3)

Cr 0.17 0.015 V <0.002 0.001 Cu 0.06 0.14(3)

Co 0.010 0.001(2)

Al 0.033 0.015 N2 0.006 0.014 Sn 0.007 0.007 Zn 0.001 0.001(2)

Ti 0.001(2) 0.001

Zr 0.001 0.001 As 0.011 0.061 Sb 0.001 0.001 B 0.003(2) 0.003(2)

Notes:

1. The forging and weld data is WCAP-14779 [16], unless otherwise noted.

2. Not detected. The number indicated the minimum limit of detection.

3. The surveillance weld Cu and Ni content was recalculated in WCAP-14779 [16] based on the average of a chemistry data available for the surveillance weld, i.e., chemistry analysis results from the baseline, Capsule R, and Capsule S samples.

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Table 4-2 Heat Treatment History of the Prairie Island Unit 1 Reactor Vessel and Surveillance Materials(1)

Material Temperature (F) Time (hrs.) Coolant Heated to 1652/1715 5 Water quenched Tempered at 1175/1238 5 Furnace cooled Intermediate Shell Heated to 1652/1724 5.5 Water quenched Forging C Tempered at 1202/1238 5 Furnace cooled

Stress relieved at 1022 8 Furnace cooled Stress relieved at 1122 14 Furnace cooled Weldment Stress relieved at 1022 5 Furnace cooled Stress relieved at 1122 7 Furnace cooled 1675 +/- 25 4 Air cooled Correlation Monitor 1600 +/- 25 4 Water quenched Material 1125 +/- 25 4 Furnace cooled 1150 +/- 25 40 Furnace cooled to 600ºF

Note:

1. Data obtained from WCAP-14779 [16] and duplicated herein for completeness.

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REACTOR VESSEL

CAPSULE (TYP)

1so*

go*

Figure 4-1 Arrangement of Surveillance Capsules in the Prairie Island Unit 1 Reactor Vessel

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LEGEND: Nxx - INTERMEDIATE SHELL COURSE RING FORGING C (TANGENTIAL)

Sxx - INTERMEDIATE SHELL COURSE RING FORGING C (AXIAL)

Wxx - WELD METAL (HEAT # 1752)

Hxx - HEAT AFFECTED ZONE Rxx - CORRELATION MONITOR MATERIAL

TENSILE WOL WOL WOL TENSILE WOL WOL WOL TENSILE CHARPY W15 W13 S14 S60 W40 W15 W14 W13 S15 S14 S13 W14 S15 S13 S59 W39 BJ BJ BJ@

DOSIMETER CHARPY CHARPY CHARPY BLOCK CHARPY CHARPY CHARPY CHARPY S58 W38 S56 W36 S54 W34 S52 R40 S50 R38 N60 R36 N58 R34 104

@@@ @@@@ S57 W37 S55 W35 S53 W33 S51 R39 S49 R37 N59 R35 N57 R33

CHARPY CHARPY CHARPY CHARPY* WOL WOL WOL TENSILE N56 H40 N54 H38 N52 H36 N50 H34 N49 H33 N14 N15 N14 N13

@l@@ll N55 H39 N53 H37 N51 H35 I I I N15 11D §l N13

TENSILE*

Figure 4-2 Prairie Island Unit 1 Surveillance Capsule N Specimen Locations

• The presentation of these specimens was modified from WCAP-8086 [2], Figure 6 to more closely resemble the arrangement of specimens in Drawing 685J394 [7].

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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-8086

[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 1

Instron0F 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 k N capacity Instron screw driven tensile machine (Model 5985) equipped with Instron Bluehill 3 Software and an Instron 22.48 kip load cel per ASTM E185-82 [10].

1 Instron is a registered trademark of Illinois Tool Works Inc. (ITW). Other product and company names used herein are trademarks or trade names of their respective companies.

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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-8086 [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 gage 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 8.45 x 1019 n/cm2 (E > 1.0 MeV) in 40.06 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-8086 [2].

Results from the previous capsules were obtained from WCAP-14779 [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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• Irradiation of the reactor vessel Intermediate Shell Forging C 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 126.5F and an irradiated 50 ft-lb transition temperature of 149.2°F. This results in a 30 ft-lb transition temperature increase of 165.5F and a 50 ft-lb transition temperature increase of 155.6F for the tangentially oriented specimens.

• Irradiation of the reactor vessel Intermediate Shell Forging C 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 116.5F and an irradiated 50 ft-lb transition temperature of 151.4F. This results in a 30 ft-lb transition temperature increase of 147.5F and a 50 ft-lb transition temperature increase of 147.3F for the axially oriented specimens.

• Irradiation of the surveillance program weld material (Heat # 1752) Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 154.0F and an irradiated 50 ft-lb transition temperature of 193.6F. This results in a 30 ft-lb transition temperature increase of 219.0F and a 50 ft-lb transition temperature increase of 218.4F.

• Irradiation of the Heat Affected Zone (HAZ) material Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of -54.9F and an irradiated 50 ft-lb transition temperature of 43.9F.

This results in a 30 ft-lb transition temperature increase of 210.1F and a 50 ft-lb transition temperature increase of 228.0F.

• Irradiation of the Correlation Monitor Material (CMM) Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 246.5F and an irradiated 50 ft-lb transition temperature of 304.0F.

This results in a 30 ft-lb transition temperature increase of 199.5F and a 50 ft-lb transition temperature increase of 226.0F.

• The average upper-shelf energy of Intermediate Shell Forging C (tangential orientation) resulted in an average energy decrease of 20.5 ft-lb after irradiation. This decrease results in an irradiated average upper-shelf energy of 138.0 ft-lb for the tangentially oriented specimens.

• The average upper-shelf energy of Intermediate Shell Forging C (axial orientation) resulted in an average energy decrease of 23.6 ft-lb after irradiation. This decrease results in an irradiated average upper-shelf energy of 119.5 ft-lb for the axially oriented specimens.

• The average upper-shelf energy of the surveillance program weld material (Heat # 1752) Charpy specimens resulted in an average energy decrease of 3.5 ft-lb after irradiation. This decrease results in an irradiated average upper-shelf energy of 79.0 ft-lb for the weld specimens.

• The average upper-shelf energy of the HAZ material Charpy specimens resulted in an average energy decrease of 105.9 ft-lb after irradiation. This decrease results in an irradiated average upper-shelf energy of 105.2 ft-lb for the HAZ specimens.

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• The average upper-shelf energy of the CMM Charpy specimens resulted in an average energy decrease of 63.6 ft-lb after irradiation. This decrease results in an irradiated average upper-shelf energy of 56.8 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 1 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 8.45 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 Intermediate Shell Forging C (tangential orientation) indicated that irradiation to 8.45 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-8086 [2]. See Figure 5-21.

The results of the tensile tests performed on the Intermediate Shell Forging C (axial orientation) indicated that irradiation to 8.45 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-8086 [2]. See Figure 5-22.

The results of the tensile tests performed on the surveillance program weld material (Heat # 1752) indicated that irradiation to 8.45 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-8086 [2]. See Figure 5-23.

The fractured tensile specimens for the Intermediate Shell Forging C (tangential orientation) material are shown in Figure 5-24; the fractured tensile specimens for the Intermediate Shell Forging C (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.

5.4 WEDGE OPENING LOADING SPECIMENS

The Wedge Opening Loading (WOL) specimens were not tested and are being stored at the Westinghouse Churchill facility.

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Table 5-1 Charpy V-notch Data for the Prairie Island Unit 1 Capsule N Intermediate Shell Forging C (Tangential Orientation) Irradiated to a Fluence of 8.45 x 1019 n/cm2 (E > 1.0 MeV)

Specimen Temperature Impact Energy Lateral Expansion Shear %

ID °F °C ft-lbs Joules mils mm N49 77 25 24.3 32.9 20.0 0.5 10 N54 90 32 9.8 13.2 11.0 0.3 10 N51 110 43 6.5 8.8 9.0 0.2 15 N55 120 49 33.5 45.4 29.5 0.7 20 N60 130 54 55.8 75.6 41.0 1.0 30 N50 140 60 43.0 58.3 36.0 0.9 25 N53 150 66 19.0 25.8 20.0 0.5 30 N58 160 71 68.0 92.2 49.5 1.3 40 N56 180 82 84.0 113.9 64.5 1.6 60 N52 200 93 106.0 143.7 72.5 1.8 75 N57 250 121 138.0 187.1 87.5 2.2 100 N59 300 149 138.0 187.1 97.5 2.5 100

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Table 5-2 Charpy V-notch Data for the Prairie Island Unit 1 Capsule N Intermediate Shell Forging C (Axial Orientation) Irradiated to a Fluence of 8.45 x 1019 n/cm2 (E > 1.0 MeV)

Specimen Temperature Impact Energy Lateral Expansion Shear %

ID °F °C ft-lbs Joules mils mm S60 60 16 17.8 24.1 14.0 0.4 5 S54 77 25 21.5 29.1 20.0 0.5 20 S57 90 32 26.0 35.3 23.0 0.6 15 S55 100 38 13.0 17.6 12.5 0.3 15 S59 110 43 45.5 61.7 37.5 1.0 30 S58 130 54 55.5 75.2 45.0 1.1 30 S49 160 71 35.5 48.1 30.0 0.8 30 S56 170 77 17.5 23.7 17.5 0.4 35 S51 180 82 71.5 96.9 55.5 1.4 45 S53 200 93 110.0 149.1 77.5 2.0 75 S52 250 121 118.5 160.7 80.5 2.0 100 S50 300 149 120.5 163.4 82.0 2.1 100

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Table 5-3 Charpy V-notch Data for the Prairie Island Unit 1 Capsule N Surveillance Program Weld Material (Heat # 1752) Irradiated to a Fluence of 8.45 x 1019 n/cm2 (E > 1.0 MeV)

Specimen Temperature Impact Energy Lateral Expansion Shear %

ID °F °C ft-lbs Joules mils mm W34 110 43 17.8 24.1 15.5 0.4 30 W40 125 52 27.0 36.6 24.0 0.6 25 W36 150 66 24.5 33.2 21.0 0.5 30 W38 175 79 29.5 40.0 24.0 0.6 30 W37 190 88 46.5 63.0 41.5 1.1 50 W39 200 93 58.5 79.3 49.0 1.2 40 W35 250 121 77.0 104.4 68.0 1.7 85 W33 300 149 79.0 107.1 66.0 1.7 100

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Table 5-4 Charpy V-notch Data for the Prairie Island Unit 1 Capsule N Heat Affected Zone (HAZ) Irradiated to a Fluence of 8.45 x 1019 n/cm2 (E > 1.0 MeV)

Specimen Temperature Impact Energy Lateral Expansion Shear %

ID °F °C ft-lbs Joules mils mm H35 -50 -46 65.5 91.5 36.0 0.9 30 H40 -25 -32 27.3 37.0 18.0 0.5 20 H37 10 -12 28.5 38.6 19.0 0.5 30 H33 50 10 59.3 80.3 35.0 0.9 40 H36 120 49 28.0 38.0 21.0 0.5 30 H34 200 93 93.8 127.1 58.0 1.5 70 H38 250 121 94.3 127.8 62.0 1.6 100 H39 300 149 116.0 157.3 74.0 1.9 100

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Table 5-5 Charpy V-notch Data for the Prairie Island Unit 1 Capsule N Correlation Monitor Material (CMM) Irradiated to a Fluence of 8.45 x 1019 n/cm2 (E > 1.0 MeV)

Specimen Temperature Impact Energy Lateral Expansion Shear %

ID °F °C ft-lbs Joules mils mm R33 200 93 13.0 17.6 10 0.3 20 R39 225 107 23.0 31.2 16 0.4 35 R34 250 121 29.8 40.3 24 0.6 35 R40 275 135 38.0 51.5 26 0.7 40 R38 300 149 52.0 70.5 44 1.1 55 R37 325 163 63.0 85.4 50 1.3 100 R35 325 163 42.0 56.9 39 1.0 100 R36 350 177 65.5 88.8 55 1.4 100

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Table 5-6 Instrumented Charpy Impact Test Results for the Prairie Island Unit 1 Capsule N Intermediate Shell Forging C (Tangential Orientation) Irradiated to a Fluence of 8.45 x 1019 n/cm2 (E > 1.0 MeV)

Total Dial Total Difference, Energy to Max Maximum General Yield Brittle Arrest Specimen Test Temp Energy, KV Instrumented (KV-W t)/KV Load, W m Load, Fm Time to Fm Load, Fgy Fracture Load, Fa ID (°F) (ft-lb) Energy, W t (%) (ft-lb) (lb) (msec) (lb) Load, Fbf (lb)

(ft-lb) (lb)

N49 77 24 22 8 20.7 4364 0.36 3404 4364 None N54 90 10 7 25(1) 3.4 3809 0.09 3283 3429 None N51 110 7 4 38(1) 0.3 2118 0.02 1360 1824 783 N55 120 34 31 8 28.7 4165 0.51 3187 4053 None N60 130 56 53 5 35.0 4326 0.61 3296 4235 None N50 140 43 39 9 35 4312 0.61 3120 4206 None N53 150 19 14 26(1) 3.2 3660 0.09 3052 3497 1021 N58 160 68 60 12 34 4233 0.60 3116 4142 725 N56 180 84 77 8 34.1 4158 0.61 3001 3614 2351 N52 200 106 99 6 34.1 4194 0.62 3006 3394 2459 N57 250 138 131 5 34.5 4259 0.61 2989 0 None N59 300 138 130 6 32.9 4076 0.61 2883 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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Table 5-7 Instrumented Charpy Impact Test Results for the Prairie Island Unit 1 Capsule N Intermediate Shell Forging C (Axial Orientation) Irradiated to a Fluence of 8.45 x 1019 n/cm2 (E > 1.0 MeV)

Total Dial Total Difference, Energy to Max Maximum General Yield Brittle Arrest Specimen Test Temp Energy, KV Instrumented (KV-W t)/KV Load, W m Load, Fm Time to Fm Load, Fgy Fracture Load, Fa ID (°F) (ft-lb) Energy, W t (%) (ft-lb) (lb) (msec) (lb) Load, Fbf (lb)

(ft-lb) (lb)

S60 60 18 17 7 15.2 4042 0.29 3264 4016 None S54 77 22 19 11 16.1 4339 0.29 3367 4255 None S57 90 26 25 5 19.3 4137 0.36 3222 4133 None S55 100 13 10 23(1) 3.3 3832 0.09 3244 3756 None S59 110 46 42 8 35.8 4399 0.61 3183 4194 None S58 130 56 52 6 35.0 4320 0.60 3188 4014 None S49 160 36 29 17(1) 27 4141 0.48 3130 4141 None S56 170 18 16 11 3.2 2714 0.09 3145 3392 1283 S51 180 72 65 10 35 4289 0.60 3081 3847 2030 S53 200 110 104 5 34.2 4189 0.61 3047 2942 1897 S52 250 119 114 3 35.0 4273 0.61 3042 0 None S50 300 121 115 4 33.5 4139 0.61 2834 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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Table 5-8 Instrumented Charpy Impact Test Results for the Prairie Island Unit 1 Capsule N Surveillance Program Weld Material (Heat # 1752) Irradiated to a Fluence of 8.45 x 1019 n/cm2 (E > 1.0 MeV)

Total Dial Total Difference, Energy to Max Maximum General Yield Brittle Arrest Specimen Test Temp Energy, KV Instrumented (KV-W t)/KV Load, W m Load, Fm Time to Fm Load, Fgy Fracture Load, Fa ID (°F) (ft-lb) Energy, W t (%) (ft-lb) (lb) (msec) (lb) Load, Fbf (lb)

(ft-lb) (lb)

W34 110 18 16 11 3 3805 0.09 3187 3543 869 W40 125 27 24 11 23 3900 0.43 3065 3889 518 W36 150 25 20 20(1) 4 4122 0.12 3198 3874 935 W38 175 30 27 7 18 3800 0.36 3039 3570 1046 W37 190 47 43 7 27 3906 0.51 3025 3747 2205 W39 200 59 56 4 34 4032 0.60 3014 3672 2481 W35 250 77 72 7 32 3892 0.63 2663 2899 2428 W33 300 79 76 4 31 3752 0.61 2775 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.

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• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-13

Table 5-9 Instrumented Charpy Impact Test Results for the Prairie Island Unit 1 Capsule N Heat Affected Zone Irradiated to a Fluence of 8.45 x 1019 n/cm2 (E > 1.0 MeV)

Total Dial Total Difference, Energy to Max Maximum General Yield Brittle Arrest Specimen Test Temp Energy, KV Instrumented (KV-W t)/KV Load, W m Load, Fm Time to Fm Load, Fgy Fracture Load, Fa ID (°F) (ft-lb) Energy, W t (%) (ft-lb) (lb) (msec) (lb) Load, Fbf (lb)

(ft-lb) (lb)

H35 -50 66 64 5 40 4815 0.61 3983 4503 None H40 -25 27 25 8 22 4573 0.36 3574 4343 None H37 10 29 23 19(1) 21 4349 0.36 3547 4345 None H33 50 59 58 3 39 4743 0.61 3561 4506 None H36 120 28 26 8 20 4117 0.36 3275 3939 908 H34 200 94 88 6 50 4794 0.80 3558 4153 2293 H38 250 94 87 8 46 4379 0.77 3137 0 None H39 300 116 111 4 60 4393 0.99 3060 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.

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Westinghouse Non-Proprietary Class 3 5-14

Table 5-10 Instrumented Charpy Impact Test Results for Prairie Island Unit 1 Capsule N Correlation Monitor Material Irradiated to a Fluence of 8.45 x 1019 n/cm2 (E > 1.0 MeV)

Total Dial Total Difference, Energy to Max Maximum Time to General Yield Brittle Arrest Specimen Test Temp Energy, KV Instrumented (KV-W t)/KV Load, W m Load, Fm Fm Load, Fgy Fracture Load, Fa ID (°F) (ft-lb) Energy, W t (%) (ft-lb) (lb) (msec) (lb) Load, Fbf (lb)

(ft-lb) (lb)

R33 200 13 12 10 10.2 4307 0.19 3580 4182 None R39 225 23 22 5 15.7 4257 0.29 3310 3831 980 R34 250 30 27 10 15.6 4209 0.29 3270 4078 1184 R40 275 38 35 8 24.6 4497 0.44 3463 4274 1559 R38 300 52 49 6 27.2 4142 0.48 3054 3934 3068 R37 325 63 59 6 35.0 4127 0.62 2964 0 None R35 325 42 39 8 15.6 4148 0.29 3320 4035 3525 R36 350 66 62 6 27.0 4098 0.48 3056 0 None

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Westinghouse Non-Proprietary Class 3 5-15

Table 5-11 Effect of Irradiation to 8.45 x 1019 n/cm2 (E > 1.0 MeV) on the Charpy V-notch Toughness Properties of the Prairie Island Unit 1 Reactor Vessel Surveillance Capsule N Materials

Average 30 ft-lb Average 35 mil Lateral Expansion Average 50 ft-lb Average Energy Absorption Transition Temperature(1) Temperature(1) Transition Temperature(1) > 95% Shear (2)

Material (°F) (°F) (°F) (ft-lb)

Unirradiated Irradiated T Unirradiated Irradiated T Unirradiated Irradiated T Unirradiated Irradiated E Intermediate Shell Forging C -39.0 126.5 165.5 -23.9 140.9 164.8 -6.4 149.2 155.6 158.5 138.0 -20.5 (Tangential Orientation)

Intermediate Shell Forging C -31.0 116.5 147.5 -12.9 138.9 151.8 4.1 151.4 147.3 143.1 119.5 -23.6 (Axial Orientation)

Surveillance Weld Material -65.0 154.0 219.0 -50.9 176.2 227.1 -24.8 193.6 218.4 82.5 79.0 -3.5 (Heat # 1752)

Heat-Affected Zone (HAZ) -265.0(3) -54.9 210.1 -180.4(3) 72.5 252.9 -184.1(3) 43.9 228.0 211.1 105.2 -105.9 Material

Correlation Monitor Material 47.0 246.5 199.5 59.1 289.7 230.6 78.0 304.0 226.0 120.4 56.8 -63.6 (CMM)

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.

3. The unirradiated HAZ data was refitted using hyperbolic tangent curve fitting causing the unirradiated data to differ from previous surveillance reports.

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Westinghouse Non-Proprietary Class 3 5-16

Table 5-12 Comparison of the Prairie Island Unit 1 Surveillance Material 30 ft-lb Transition Temperature Shifts and Upper-Shelf Energy Decreases with Regulatory Guide 1.99, Revision 2, Predictions

Capsule 30 ft-lb Transition Upper-Shelf Energy Fluence Temperature Shift Decrease Irradiation Material Capsule 19 2 Temperature(4)

(x 10 n/cm, Predicted(1) Measured(2) Predicted(1) Measured(2) (°F)

E > 1.0 MeV) (°F) (°F) (%) (%)

V 0.609 37.9 31.9 17 2 536 Intermediate Shell P 1.31 47.3 23.2 21 10 536 Forging C R 4.02 59.7 96.0 26 9 536 (Tangential S 4.39 60.5 101.6 27 10 536 Orientation) 65.6 165.5 32 13 534 N 8.45 V 0.609 37.9 48.8 17 0(3) 536 Intermediate Shell P 1.31 47.3 33.9 21 5 536 Forging C R 4.02 59.7 84.0 26 10 536 (Axial Orientation) S 4.39 60.5 74.0 27 6 536 N 8.45 65.6 147.5 32 16 534 V 0.609 61.1 35.2 26 0(3) 536 Surveillance Weld P 1.31 76.2 45.6 30 0(3) 536 Material R 4.02 96.2 123.0 39 9 536 (Heat # 1752) S 4.39 97.6 161.0 40 0(3) 536 N 8.45 105.7 219.0 47 4 534 V 0.609 110.2 101.9 24 24 536 Correlation P 1.31 137.6 160.9 28 30 536 Monitor Material R 4.02 173.7 192.5 37 33 536 (CMM) S 4.39 176.1 165.5 38 31 536 N 8.45 190.9 199.5 44 53 534 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.

4. The irradiation temperature is the time-weighted average reactor vessel inlet temperature during the period of irradiation.

All temperatures are within the applicability range of 525°F to 590°F per Regulatory Guide 1.99 Revision 2 [1].

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• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-17

Table 5-13 Tensile Properties of the Prairie Island Unit 1 Capsule N Reactor Vessel Surveillance Materials Irradiated to 8.45 x 1019 n/cm2 (E > 1.0 MeV)

Specimen Test 0.2% Yield Ultimate Fracture Fracture Fracture Uniform Total Reduction Material ID Temp Strength Strength Load Strength True Stress Elongation Elongation in Area

(°F) (ksi) (ksi) (kip) (ksi) (ksi) (%) (%) (%)

Intermediate Shell N13 79 89.5 104.8 3.4 68.4 195 10.3 24.7 65.0 Forging C N14 250 83.6 98.3 3.0 62.0 190 9.0 23.3 67.3 (Tangential) N15 550 77.5 95.8 3.2 66.1 155 8.5 20.8 57.5 Intermediate Shell S13 81 87.3 103.7 3.4 69.4 159 10.3 22.4 56.4 Forging C S14 250 82.2 97.2 3.1 64.2 165 7.0 19.1 61.1 (Axial) S15 550 79.7 94.8 3.4 68.7 149 6.2 17.8 53.8 Surveillance Weld W13 83 86.1 99.0 3.6 73.4 177 11.6 24 58.5 (Heat # 1752) W14 250 78.3 89.5 3.0 60.8 174 ---(1) ---(1) 65.0 W15 550 70.2 91.8 3.1 62.9 155 8.8 21.7 59.6

Note:

1. The extensometer slipped, therefore this value could not be obtained.

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-18

In te rmediate S hell Forg in g C (Tangential)

CVGraph 6.02 : Hyperbo lic Tangent Curve Printed on 7/ 26/ 2021 12 :18 PM

Curve P lant Capsu le Material O ri. Heat #

1 Prair ie Island 1 Unirrad SA508CL3 Ta ngent ial 2 19 18/38566 2 Prairie I slan d 1 V SA508CL3 Tangent ial 21918 / 38566 3 Prai r ie Islan d 1 p SA508CL3 Tange ntial 219 J 8/ 38566

4 Pra i rie I sland 1 R SA508CL3 Ta ngentia l 219 18/38566 5 Pra irie I slan d 1 s SA508CL3 Tangentia l 219 18/38566

6 Prairie I slan d 1 N SA508CL3 Tangentia l 21918 / 38566 180 ___..,.... ______.....,. ______..,.... ______.....,. _____ _

160 --o-1

~A-2 rr-r-r ~ ~==l~ =+==+===l 140 -- -3

-e$-4

-A--5 120 --+o--6 1-1------1-- -/-, t,-J '--- --hll-#- --+-----1---+--- -1

o l=:i:=~~ ~:c:: +/-:::::..._c----L..---1..----'-_J----'-L.1....-L~

-300 -200 -100 0 100 200 300 400 500 600 Temperature {° F)

Figure 5-1 Charpy V-notch Impact Energy vs. Temperature for Prairie Island Unit 1 Reactor Vessel Surveillance Program Intermediate Shell Forging C (Tangential Orientation)

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-19

Intermediate Shell Forging C (Tangential)

CVGraph 6.02 : Hyperbolic Tangent Curve Printed on 7/ 26 /2021 12:18 PM Curve Fluence LSE USE d-USE T@30 d-T @ 30 T @ 50 d-T @50 1 0.00E +000 2.2 15 8.5 0 -3 9 0 -6.4 0 2 6.09E +0l8 2.2 155.1 -3.40 -7. 1 31.9 20.1 26. 5

3 l.31E +019 2.2 142.2 -1 6.3 -15.8 23.2 17.1 23.5 4 4.02E +0l9 2.2 145 -13.5 57 96 94.9 101.3 5 4.39E+0l9 2.2 142.5 -1 6 62.6 10 1. 6 98.8 105.2 6 8.45 E+019 2.2 138 -20.5 12 6.5 165.5 149.2 155.6

Figure 5-1 Charpy V-notch Impact Energy vs. Temperature for Prairie Island Unit 1 Reactor Vessel Surveillance Program Intermediate Shell Forging C (Tangential Orientation)

(cont.)

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-20

Intermediate Shell Forging C (Tangential)

CVGraph 6.02 : Hyperbolic Tangent Curve Printed on 7/ 26/ 2021 12 :23 PM

Curve Plant Capsule Material Ori. Heat #

1 Prairie Island 1 Unirrad SA508CL3 Tan gential 21918/38566 2 Prairie I sland 1 V SA508CL3 Tangential 21918 / 38566 3 Prairie Island 1 p SA508CL3 Tangential 219 J 8/ 38566

4 Prairie Island 1 R SA508CL3 Tangential 21918/38566 5 Prairie Island 1 s SA508CL3 Tangential 21918/38566

6 Prairie Island 1 N SA508CL3 Tangential 21918 / 38566

120 e 1 6 2 100 B 3

$ 4

-r;IJ 6 5

-6 80 e 6

... = 0

r;IJ

= ~ 60 Q.,

~ ><

-~

...... -~ 40

~

~

20

o '====='==~ ~~=:::t~ _L.1...-.L....1.......L----L..---1----1._L.J.......l

-300 -100 0 100 200 300 400 500 600 Temperature {° F)

Figure 5-2 Charpy V-notch Lateral Expansion vs. Temperature for Prairie Island Unit 1 Reactor Vessel Surveillance Program Intermediate Shell Forging C (Tangential Orientation)

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-21

Intermediate Shell Forging C (Tangential)

CVGrap h 6.02 : Hyperb o li c Tan gent Curve Print ed on 7/ 26 /202 1 12:23 PM Curve Fluence LSE USE d-USE T @3 5 d-T @ 35 1 0.00E +000 1 9 5.36 0 -23.9 0 2 6.09E +0 18 1 80.04 -1 5.32 19 42.9

3 l.31E +019 1 88.04 -7.32 9.5 33.4 4 4.02E +019 1 79.29 -1 6.0 7 8 1 104.9 5 4.39E+0l9 1 91.86 -3. 5 88.3 11 2.2 6 8.4 5E+019 1 100.69 5.33 140.9 164.8

Figure 5-2 Charpy V-notch Lateral Expansion vs. Temperature for Prairie Island Unit 1 Reactor Vessel Surveillance Program Intermediate Shell Forging C (Tangential Orientation)

(cont.)

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-22

In te rmediate S hell Forg in g C (Tangential)

CVGraph 6.02 : Hyperbo lic Tangent Curve Printed on 7/ 26/ 2021 12 :21 PM

Curve P lant Capsu le Material Ori. Heat #

1 Prair ie I slan d 1 Unirrad SA508CL3 Ta ngent ial 2 19 18/38566 2 Prairie I sland 1 V SA508CL3 Tangential 21918 / 38566 3 Prai r ie Island 1 p SA508CL3 Tange ntial 219 18/ 38566

4 Pra i rie I sland 1 R SA508CL3 Ta ngentia l 219 18/38566 5 Pra irie I slan d 1 s SA508CL3 Tangentia l 219 18/38566

6 Prairie I sland 1 N SA508CL3 Tangentia l 21918 / 38566

90 O 1 l-+---+-----+~,,_,_-+--+-------+----+-----+-- ----1 A 2 80 3 f-+-----+--~...-1-_,_, _ ___,__--+----+----+-- ----I

• 4 70 A 5 ~--~- - - - ~ --~--~----- ~

O 6 l-,

~ 60 t-- --+----+-----+- ""1-t-- -+-.&+----+-----+---t--- ---t Qj

-=

00

,.... = 50 - ---------- - - - - - --------------+--- -I Qj

~

~ 40 1-----+----+-----+- -l- -l~l'lc-H-~ H--+----+-----+---+--- ---I

~

0 L......i.- 111111111Mlliiiiiiiii;;:;;;;;.il==:::::!i ~ :te:'::::::i........l.-L..--..L.....L.____JL-..1........L___,JL..--..J...........1..._J

-300 -200 -100 0 100 200 300 400 500 600 Temperature (° F)

Figure 5-3 Charpy V-notch Percent Shear vs. Temperature for Prairie Island Unit 1 Reactor Vessel Surveillance Program Intermediate Shell Forging C (Tangential Orientation)

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-23

Intermediate Shell Forging C (Tangential)

CVGraph 6.02 : Hyperbolic Tangent Curve Printed on 7/ 26 /2021 12 :2 1 PM Curve Fluence LSE USE d-USE T @ 50 d-T @ SO 1 0.00E +000 0 100 0 35.9 0 2 6.0 9E +018 0 100 0 76 40.1

3 l.31E +019 0 100 0 74.2 38.3 4 4.02E +019 0 100 0 131.4 95.5 5 4.39 E+0l9 0 100 0 161.2 125.3 6 8.4 5E+019 0 100 0 168.2 132.3

Figure 5-3 Charpy V-notch Percent Shear vs. Temperature for Prairie Island Unit 1 Reactor Vessel Surveillance Program Intermediate Shell Forging C (Tangential Orientation)

(cont.)

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-24

Intermediate Shell Forging C (Axial)

CVGraph 6.02 : Hyperbolic Tangent Curve Printed on 7/ 26/2021 12 :26 PM

Curve Plant Capsule Material Ori. Heat #

1 Prairie I sland 1 Unirrad SA508CL3 Axial 21918/38566 2 Prairie I sland 1 V SA508CL3 Axial 21918 / 38566 3 Prairie Island 1 p SA508CL3 Axial 21918 / 38566

4 Prairie Island 1 R SA508CL3 Axial 21918/38566 5 Prairie Island 1 s SA508CL3 Axial 21918/38566

6 Prairie Island 1 N SA508CL3 Axia l 21918 / 38566

160 e 1 140 6 2 B 3 120 $ 4

,_ 6 5 f'1 e 6

,Q

- 100 I

~

OJ)

,_ 80

~

~ =

~ 60 u

40

0 l=~~ ~~:::::t:....i._J----1.._J_----L._J_----l...._J_----L..._l_---l..._J

-300 -100 0 100 200 300 400 500 600 Temperature {° F)

Figure 5-4 Charpy V-notch Impact Energy vs. Temperature for Prairie Island Unit 1 Reactor Vessel Surveillance Program Intermediate Shell Forging C (Axial Orientation)

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-25

Intermediate Shell Forging C (Axial)

CVGrap h 6.02 : Hyperbolic Tan gent Curv e Printed on 7/ 26 /2021 12 :26 PM

Curve Fluence LSE USE d-USE T@30 d-T @ 30 T @ 50 d-T @50

1 0.00E +000 2.2 143.1 0 -31 0 4. 1 0 2 6.09E +0l8 2.2 143.3 0.20 17.8 48.8 44.6 40.5 3 l.31E +019 2.2 136.3 -6.80 2.9 33.9 54.5 50.4 4 4.02E +0l9 2.2 128.7 -14.4 53 84 99.6 95.5 5 4.39E+0l9 2.2 135 -8.10 43 74 80.8 76.7 6 8.45E+019 2.2 11 9.5 -23.6 116.5 147.5 151.4 147.3

Figure 5-4 Charpy V-notch Impact Energy vs. Temperature for Prairie Island Unit 1 Reactor Vessel Surveillance Program Intermediate Shell Forging C (Axial Orientation) (cont.)

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-26

Intermediate Shell Forging C (A x ial)

CVGraph 6.02 : Hyperbolic Tangent Curve Printed on 7/ 26/2021 12 :33 PM

Curve P lant Capsu le Material Ori. Heat #

1 Prairie I slan d 1 Unirrad SA508CL3 Axia l 2 19 18/38566 2 Prairie I sland 1 V SA508CL3 Axia l 21918 / 38566 3 Prairie Island 1 p SA508CL3 Axia l 21918 / 38566

4 Prairie Island 1 R SA508CL3 Axia l 219 18/38566 5 Prairie I sland 1 s SA508CL3 Axia l 219 18/38566

6 Prairie I sland 1 N SA508CL3 Axial 21918 / 38566 110 ___..,.... ______.....,. ______..,.... ______.....,. _____ _

--o-1 i---r-----t------t------t-- ---.1;;;:-------t ----=::;;;;;;;~---,

_,....A-2 90 --+ --3 t-,-----;--- -t7" ~--1-'. ~ - -t- -r----;----t--- --i

-et-4 80 -A--5 70........... -----,---..J-t-----+-- ~--t-# - _,_ _,_,_ --o-6 _ __ ----:----+----+--- -1

o 6=~~!!!!: ::t:::~ Ll........1...._J_---1----1..----1.-1----1_L.1....-L~

-300 -200 -100 0 100 200 300 400 500 600 Temperature {° F)

Figure 5-5 Charpy V-notch Lateral Expansion vs. Temperature for Prairie Island Unit 1 Reactor Vessel Surveillance Program Intermediate Shell Forging C (Axial Orientation)

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-27

Intermediate Shell Forging C (A x ial)

CVGrap h 6.02 : Hyperb o li c Tan gent Curve Print ed on 7/ 26 /202 1 12:33 PM Curve Fluence L SE USE d-USE T @3 5 d-T @ 35

1 0.00E +000 1 9 5.67 0 -12.9 0 2 6.09E +0 18 1 86.47 -9.2 4 8 60.9 3 l.31E +019 1 61.97 -33. 7 18.3 31.2 4 4. 02E +0 19 1 85.3 - 10.37 85.3 98.2 5 4.39 E+0l9 1 81.04 -14.63 7 5 87.9 6 8.4 5E+019 1 100. 16 4.4 9 138.9 15 1. 8

Figure 5-5 Charpy V-notch Lateral Expansion vs. Temperature for Prairie Island Unit 1 Reactor

Vessel Surveillance Program Intermediate Shell Forging C (Axial Orientation) (cont.)

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-28

Intermediate Shell Forging C (Axial)

CVGraph 6.02 : Hyperbolic Tangent Curve Printed on 7/ 26/2021 12 :28 PM

Curve Plant Capsule Material Ori. Heat #

1 Prairie I sland 1 Unirrad SA508CL3 Axial 21918/38566 2 Prairie I sland 1 V SA508CL3 Axial 21918 / 38566 3 Prairie Island 1 p SA508CL3 Axial 21918 / 38566

4 Prairie Island 1 R SA508CL3 Axial 21918/38566 5 Prairie Island 1 s SA508CL3 Axial 21918/38566

6 Prairie Island 1 N SA508CL3 Axia l 21918 / 38566

90 O 1 1-+---+-----+-- - - -,,-,- --+---+-----+-- ----I A 2 80 3 ~---+----1---, f-4 ~ +-1-,J-~----+-----+--- ~

• 4 70 A 5 ~--~--~ - ~ - -~--~----- ~

O 6 1-,

~ 60..__--+---+----+-- -F-:z+l'N--ff- --l+-----+-------if----+-- ----1 Qj

-=

00

...,. = 50 - ----------- - - - ---- -----------+--- -I Qj

~

~ 40 ~ ---+---+-----+ -l~'J-- H-~ ~ f--+---+-----+---+--- --1

~

0 L-... liliiiiiii... ~ =iii'ii~ :t:.......1.......l...----L._j_.1....-.l..,_....i.........L----1._L_..i.........J

-300 -200 -100 0 100 200 300 400 500 600 Temperature (° F)

Figure 5-6 Charpy V-notch Percent Shear vs. Temperature for Prairie Island Unit 1 Reactor Vessel Surveillance Program Intermediate Shell Forging C (Axial Orientation)

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-29

Intermediate Shell Forging C (Axial)

CVGraph 6.02 : Hyperbolic Tangent Curve Printed on 7/ 26 /2021 12:28 PM

Curve Fluence LSE USE d-USE T @ 50 d-T @ SO 1 0.00E +000 0 100 0 48 0 2 6.09E +018 0 100 0 90.8 42.8 3 l.31E +019 0 100 0 103.3 55.3 4 4.02 E +019 0 100 0 140.1 92. 1 5 4.39E+0l9 0 100 0 134.5 86.5 6 8.4 5E+019 0 100 0 174.3 12 6.3

Figure 5-6 Charpy V-notch Percent Shear vs. Temperature for Prairie Island Unit 1 Reactor

Vessel Surveillance Program Intermediate Shell Forging C (Axial) (cont.)

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-30

Weld Me tal CVGraph 6.02 : Hyperbolic Tangent Curve Printed on 7/ 5/2021 12:10 PM

Curve P lant Capsu l e Material Ori. Heat#

1 Prair i e I sl an d 1 Unirrad Weld NA 1752

2 Prairie I sland 1 V Weld NA 1752

3 Prai r ie Island 1 p We l d NA 1752

4 Prairie I sl and 1 R Weld NA 1752

5 Pra ir i e I s land 1 s Weld NA 1752

6 Prairie I sland 1 N We l d NA 1752

120 e 1 6 2 100 B 3

$ 4 0 6 5 r,:, 80 e 6

.c

-I

~

OJ)

,_ 60

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~ =

~ 40 u

0........... _...... _...__..._.....,_....__...__..._...... _...... _...__..._...... _...... _...... _...____. _ _.

-300 -200 -100 0 100 200 300 400 500 600 Temperature {° F)

Figure 5-7 Charpy V-notch Impact Energy vs. Temperature for Prairie Island Unit 1 Reactor Vessel Surveillance Program Weld Material (Heat # 1752)

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-31

Weld Metal

CVGraph 6.02: Hyperbolic Tangent Curve Printed on 7/ 5/2021 12 : 10 PM

Curve Fluence LSE USE d-USE T@30 d-T @ 30 T @ 50 d-T @50 1 0.00E +000 2.2 82.5 0 -6 5 0 -24.8 0 2 6.09E +0l8 2.2 90 7.5 -29.8 35.2 20 44.8 3 l.31E +019 2.2 83.2 0.70 -19.4 45.6 45.3 70.1 4 4.02E +0l9 2.2 75 -7.5 58 123 135.2 160 5 4.39E+0l9 2.2 84.5 2 96 161 144 168.8 6 8.45E+019 2.2 79 -3.5 154 219 193.6 218.4

Figure 5-7 Charpy V-notch Impact Energy vs. Temperature for Prairie Island Unit 1 Reactor Vessel Surveillance Program Weld Material (Heat # 1752) (cont.)

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-32

Weld Metal CVGraph 6.02 : Hyperbolic Tangent Curve Printed on 7/ 5/2021 12 : 14 PM

Curve P lant Capsu l e Material Ori. Heat #

1 Prairie l sland 1 Unirrad Weld NA 1752

2 Prairie I sland 1 V Weld NA 1752

3 Prairie Island 1 p Weld NA 1752

4 Prairie Island 1 R Weld NA 1752

5 Prairie I s land 1 s Weld NA 1752

6 Prairie I sland 1 N Weld NA 1752 100 ___..,.... ______.....,. ______..,.... ______.....,. _____ _

90 O 1 0 1-+---+----+----+---+-----+--------,1--- ----1 A 2 80 3 H-------t~ ~o~ ------i~ ::=::.i:i--==F~~.:=-=t

$ 4 0

A 5 H----t=--- v--t~ =/7 ~.-:: cr-J~ c__-+---+-- ----1 O 6

o l!!!!!!!!~~ d===:i::!:f:~ _..l----1.._J_----L._J__;____L----L..._l_---'-_J

-300 -200 -100 0 100 200 300 400 500 600 Temperature {° F)

Figure 5-8 Charpy V-notch Lateral Expansion vs. Temperature for Prairie Island Unit 1 Reactor Vessel Surveillance Program Weld Material (Heat # 1752)

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-33

Weld Metal

CVGraph 6.02: Hyperbolic Tangent Curve Printed on 7/ 5/ 2021 12 : 14 PM

Curve Fluence LSE USE d-USE T @3 5 d-T @ 35 1 0.00E +000 1 76.24 0 -50.9 0 2 6.09E +018 1 79.72 3.48 22.3 73.2 3 l.31E +019 1 80.8 4.56 25.4 76.3 4 4.02 E +019 1 81.48 5.24 11 6.9 167.8 5 4.39E+0l9 1 75. 69 -0.55 132.7 183.6 6 8.4 5E+019 1 75.28 -0.96 176.2 227.1

Figure 5-8 Charpy V-notch Lateral Expansion vs. Temperature for Prairie Island Unit 1 Reactor Vessel Surveillance Program Weld Material (Heat # 1752) (cont.)

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-34

Weld Metal CVGraph 6.02 : Hyperbolic Tangent Curve Printed on 7/ 5/2021 12 :11 PM

Curve P lant Capsu le Material Ori. Heat #

1 Prairie Island 1 Unirrad Weld NA 1752 2 Prairie I slan d 1 V Weld NA 1752

3 Prairie Island 1 p Weld NA 1752

4 Prair ie Island 1 R Weld NA 1752 5 Prairie I s land 1 s Weld NA 1752

6 Prairie I sland 1 N Weld NA 1752

90 O 1 l--+---+-- ----ziH- -b"A-+-~~-jc...._--+-----+-- ----1 A 2 80 3 r-+- ---+- -/- - ---tff---ft ----, f- -----l----t----,------+---+--- ;

$ 4 70 A 5 r-+---~ ~ ~ ~ - ~ ~ ~ ----t----+---+--- ;

O 6 1-,

~ 60 _ ________ ___...,._,,_ _,__,_ ____ __ -+----+-----+----1---- --1 Qj

.c 00

...,. = 50 1-----+----+--- -l'"""1/4--IA+-, f'lcl-t-1---ic.- ---+-----+----t--- -l Qj

~

~ 40 1-----+----+--- l---"l1/4---+---1r.)l-+--- -+-m---t----t--~-t--- -1

~

0 i..lllllEl;:;i.m=c::;;..i.;;;;~ ::::::::c.........,__....L_L..--..L.....L.____JL---..1........L___,JL..--..J...........L.._J

-300 -200 -100 0 100 200 300 400 500 600 Temperature (° F)

Figure 5-9 Charpy V-notch Percent Shear vs. Temperature for Prairie Island Unit 1 Reactor Vessel Surveillance Program Weld Material (Heat # 1752)

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-35

Weld Metal

CVGraph 6.02: Hyp erbolic Tan gent Curve Printed on 7/ 5/ 202 1 12 : 11 PM Curve Fluence LSE USE d-USE T @ 50 d-T @ SO

1 0.00E +000 0 100 0 -22.1 0 2 6.09E +018 0 100 0 49.8 71.9 3 l.31E +019 0 100 0 20.4 42. 5 4 4.02 E +019 0 100 0 113.3 135.4 5 4.39 E+0l9 0 100 0 89.1 111.2 6 8.4 5E+019 0 100 0 193. 5 215.6

Figure 5-9 Charpy V-notch Percent Shear vs. Temperature for Prairie Island Unit 1 Reactor Vessel Surveillance Program Weld Material (Heat # 1752) (cont.)

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-36

Heat A ffected Zone CVGraph 6.02 : Hyperbolic Tangent C urve Printed on 6/ 18/ 2021 9 :35 AM

C urve P lant Capsu le Material Ori. Heat #

I Prairie Island 1 Unirrad SA508CL3 NA 2 l 9 18/ 38566 2 Prairie Island l v* SA508CL3 N A 21918 / 38566 3 Prairie Island l p SA508CL3 N A 21918 /38566

4 Prair ie Island 1 R SA508CL3 NA 219 18/ 38566 5 Prair ie Island I s SA508CL3 NA 21918 / 38566

6 Prairie Island I N SA508CL3 NA 21 9 18/ 38566

250

0 1 A 2 0 200 3

$ 4 6 5

-<IJ 0 6

.c

-I

¢:: 150 bJl

Q,)

~ = OA z 100

> 0 u

so

0

0

-300 -200 -100 0 100 200 300 400 500 600 Temperature (° F)

Figure 5-10 Charpy V-notch Impact Energy vs. Temperature for Prairie Island Unit 1 Reactor Vessel Heat-Affected Zone Material

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-37

Heat Affected Zone

CVGraph 6.02: Hyperbolic Tangent Curve Printed on 6/ 18/2021 9:35 AM

Curve Fluence LSE USE d-USE T @ 30 d-T @ 30 T @ 50 d-T @ 50 1 0.00E+000 2.2 211.1 0 -265 0 -1 84.1 0 2 6.09E +018 2.2 < 211.1** 0 <-200 0 <-125 0 3 l.31E +019 2.2 143.3 -67.8 -125.5 139.5 - 88.8 95.3 4 4.02E +0l9 2.2 97.3 -113.8 -50.3 214.7 -21 163.1 5 4.39E+0l9 2.2 136 -75. 1 -62. 1 202.9 -26.3 157.8 6 8.45E+0l9 2.2 105.2 -105.9 -54.9 210. 1 43.9 228

• Capsule V data not fit with a hyperbolic-tangent function because the fit did not provide a smooth S-shaped curve or realistic results. See Figure "Capsule V Heat Affected Z one" for T@ 30 and T @ 50 values.

• • Per WCAP-8916, upper shelf impact energy is not obtainable due to excessive toughness.

Figure 5-10 Charpy V-notch Impact Energy vs. Temperature for Prairie Island Unit 1 Reactor Vessel Heat-Affected Zone Material (cont.)

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-38

Heat Affected Zone CVGraph 6.02 : Hyperbolic Tangent Curve Printed on 7/ 6/2021 10 :31 AM

Curve P lant Capsu le Material Ori. Heat #

1 Prairie I sland 1 Unirrad SA508CL3 NA 2 19 18/ 38566 2 Prairie I sland 1 V SA508CL3 NA 21918 / 38566 3 Prairie Island 1 p SA508CL3 NA 21918 / 38566

4 Prair ie Island 1 R SA508CL3 NA 219 18/38566 5 Prairie I sland 1 s SA508CL3 NA 219 18/38566

6 Prairie I sland 1 N SA508CL3 NA 21918 / 38566 100 ___..,.... ______.....,. ______..,.... ______.....,. _____ _

0 90

80

o 1==~3::: ~ --1----1_L...,__...L---L.---1-.1....-.L...J.........L----1._L..i........J

-300 -200 -100 0 100 200 300 400 500 600 Temperature {° F)

Figure 5-11 Charpy V-notch Lateral Expansion vs. Temperature for Prairie Island Unit 1 Reactor Vessel Heat -Affected Zone Material

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-39

Heat Affected Zone

CVGrap h 6.02 : Hyperbo li c Tang ent C urve Printed on 7/6 /2021 10 :31 AM Curve Fluence LSE USE d-USE T @3 5 d-T @ 35

1 0.00E +000 1 86.93 0 -1 80.4 0 2 6.09E +018 1 90 3.07 -213.7 -33.3 3 l.31E +019 1 80.66 -6.27 -50.7 129.7 4 4.02 E +019 1 62.04 -24.89 -1 1.5 168.9 5 4.39 E+0l9 1 79.89 -7.04 -7. 6 172.8 6 8.45 E+019 1 68 -1 8.93 72.5 252.9

Figure 5-11 Charpy V-notch Lateral Expansion vs. Temperature for Prairie Island Unit 1 Reactor Vessel Heat -Affected Zone Material (cont.)

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-40

Heat A ffected Zone CVGraph 6.02 : Hyperbolic Tangent Curve Printed on 7/ 6/2021 10 :25 AM

Curve P lant Capsule Material Ori. Heat #

1 Prair i e I sl an d 1 Unirrad SA508CL3 NA 2 19 18/38566

2 Prairie I sland 1 V SA508CL3 NA 21918 / 38566 3 Prai r ie Island I p SA508CL3 NA 21918 / 38566

4 Prair ie Island 1 R SA508CL3 NA 219 18/ 38566

5 Pra ir i e I s land 1 s SA508CL3 NA 219 18/38566

6 Prairie I sland I N SA508CL3 NA 21918 / 38566

90 0 A

80

70 A 0

1-,

~ 60 t-- --+- --l'!r- -+----, f'f-, ~ - +-J ~ t-- -+--+----+-----+---t--- ---t Qj

-=

00

...,. = 50 1-----+- ----hl'>H---t- -hA-- '#----t----+----+----+--- -I Qj

~

~ 40 ------+- ____,,,._..,__, ___ _ _,_ _________________ --t

~

o ~ ~ ia::::::5:!L..._L.J.......l...----1._L...1.......L----1._L.J.......l...----1._L...1.......J

-300 -200 -100 0 100 200 300 400 500 600 Temperature (° F)

Figure 5-12 Charpy V-notch Percent Shear vs. Temperature for Prairie Island Unit 1 Reactor Vessel Heat-Affected Zone Material

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-41

Heat Affected Zone

CVGrap h 6.02 : Hyperbo li c Tan gent C urve Printed on 7 /6 /2021 10 :25 AM Curve Flu en ce LSE USE d -USE T @ 50 d-T @ SO

1 0.00E +000 0 100 0 -72.9 0 2 6.09E +018 0 100 0 -85.9 - 13 3 l.31E +019 0 100 0 -60.9 12 4 4.02E +019 0 100 0 28.2 10 1.1 5 4.39E+0l9 0 100 0 42.1 11 5 6 8.45E +019 0 100 0 103.2 176. 1

Figure 5-12 Charpy V-notch Percent Shear vs. Temperature for Prairie Island Unit 1 Reactor

Vessel Heat-Affected Zone Material (cont.)

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-42

Correlation Monitor Material CVGraph 6.02 : Hyperbolic Tangent Curve Printed on 8/ 5/2021 12:07 PM

Curve P lant Capsu le Material Ori. Heat #

1 Prair ie Island 1 Unirrad A533B 1 NA HSST 02 2 Prairie I sland 1 V A533Bl NA HSST 02 3 Prairie Island 1 p A533Bl NA HSST 02

4 Pra i rie I sland 1 R A533B 1 NA HSST 02 5 Prairie I s land 1 s A533B1 NA HSST 02

6 Prairie I slan d 1 N A533B1 NA HSST 02

140 e 1 120 6 2 3

$ 4

,_ 100 6 5 f'1 e 6

,.Q

-I

~ 80 OJ)

~

~ = 60

~

u 40

o l:::::=:c::::+/-=:::i=~~::E: ::::::i=:::=t:~---1..----'-_.l----'-L.1....-L~

-300 -200 -100 0 100 200 300 400 500 600 Temperature {° F)

Figure 5-13 Charpy V-notch Impact Energy vs. Temperature for Prairie Island Unit 1 Reactor Vessel Correlation Monitor Material

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-43

Correlation Monitor Material

CVGraph 6.02: Hyperbolic Tangent Curve Printed on 8/ 5/2021 12 :07 PM

Curve Fluence LSE USE d-USE T@30 d-T @ 30 T @ 50 d-T @50

1 0.00E +000 2.2 120.4 0 47 0 78 0 2 6.09E +0l8 2.2 91.3 -29.1 148.9 101.9 194.7 116.7 3 l.31E +019 2.2 84.8 -35.6 207.9 160.9 228.3 150.3 4 4.02E +0l9 2.2 80.7 -3 9.7 239.5 192.5 277 199 5 4.39E+0l9 2.2 82.5 -37.9 212.5 16 5.5 238.2 160.2 6 8.45 E+019 2.2 56.8 -63.6 246.5 199.5 304 226

Figure 5-13 Charpy V-notch Impact Energy vs. Temperature for Prairie Island Unit 1 Reactor Vessel Correlation Monitor Material (cont.)

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-44

Correlation M onitor Material CVGraph 6.02 : Hyperbolic Tangent C urve Printed on 7/ 6/2021 10:44 AM

Curve P lan t Capsu le Material Ori. Heat #

1 Pra i rie I slan d 1 Unirrad A533 B l NA HSST 02

2 Prai r ie I sland 1 V A533B1 NA HSST 02 3 Prai r ie Islan d 1 p A533B1 NA HSST 02 4 Pra i rie I sland 1 R A53381 NA HSST 02 5 P rair ie I slan d 1 s A533Bl NA HSST 02

6 Prairie I slan d I N A533B1 NA HSST 02

80 -Mo-1

-"""A,----2 1-r-----r-----r -,-rr r---r--~-----= :::;;;;;;;;;.at,-- -;

70 -- -3

-et-4 i-r-----r------r ---,r"T ----t----i -r- -n- -----1~--"7 "-:= i;;;::-- -I

-A--5

-o-6 H---t-- 3/4 --+ --;:~ +--'=~~~~~~

-~ = 0 50 ~ ---+---+-----+-- ~ 4-------f-H---#--+- E=Y---1---,1------+--- --I

= ~

Q,.

~ >'1 40 J-- ---+----+-------if--- +-+--- -+l---l-',.._ ~ ~ -.,..- +-----+--- ---1

-~

~ 30 - ---+-----+------+- ------- -........,__----+------,__ _____ ____

~

~

o b::i:=::6~ ~ !!!!!!!3::~ !:E~ --1-1....--L..1....-.L...1...-...L....1.-_J

-300 -200 -100 0 100 200 300 400 500 600 Temperature {° F)

Figure 5-14 Charpy V-notch Lateral Expansion vs. Temperature for Prairie Island Unit 1 Reactor Vessel Correlation Monitor Material

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-45

Correlation Monitor Material

CVGrap h 6.02 : Hyperbolic Tangent Curve Printed on 7/6 /2021 10 :44 AM

Curve Fluence LSE USE d-USE T@35 d-T @ 35 1 0.00E +000 1 86.42 0 59.1 0 2 6.0 9E +018 1 80.07 -6.35 192.7 133.6 3 l.31E +019 1 60.72 -25.7 217.4 158.3 4 4.02E +019 1 79.05 -7.37 299.8 240.7 5 4.39E+0l9 1 59.42 -27 238.4 179.3 6 8.45E +019 1 70.15 -1 6.27 289.7 230.6

Figure 5-14 Charpy V-notch Lateral Expansion vs. Temperature for Prairie Island Unit 1 Reactor Vessel Correlation Monitor Material (cont.)

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-46

Correlation M onitor Material CVGraph 6.02 : Hyperbolic Tangent C urve Printed on 7/ 6/2021 10:43 AM

Curve P lant Capsu le Material Ori. Heat #

1 Prair ie I sl an d 1 Unirrad A533 B l NA HSST 02

2 Prairie I slan d 1 V A533B1 NA HSST 02 3 Pra irie Islan d 1 p A533B1 N A HSST 02

4 Prair ie Island 1 R A533Bl NA HSST 02 5 Pra ir ie I s lan d 1 s A533Bl NA HSST 02

6 Prairie I slan d I N A533B1 NA HSST 02

90 O 1 l---+---+-----+--- ~ ---l+-l~'I-J,__+-__ --+ __ ----1 A 2 80 3 r+----+---+- ---,. -+- ----J'-----f;I~ ---+---+--- ;

• 4 70 A 5 H----+--- ~ --+- tt-LJH1----+---t-- ~

O 6 1-,

~ 60 t-- --+----+-----+--- tr- ---+-:: -=1----t----i,.... ----+---t--- ---t Qj

-=

00

.,._. = 50 1-----+----t----+--- -+-t--- -+I W--l,H,__t----+----t--- -l Qj

~

~ ~ 40 ------+-----+---+-- ------------ +-+--+-----+----+---- -

0 L-..........l. 111111111::i::::;J....,....==::t:::;.111111;;~~ L..--..L.....L.____JL-.J.........L___,JL..--..J...........1..._J

-300 -200 -100 0 100 200 300 400 500 600 Temperature (° F)

Figure 5-15 Charpy V-notch Percent Shear vs. Temperature for Prairie Island Unit 1 Reactor Vessel Correlation Monitor Material

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-47

Correlation Monitor Material

CVGraph 6.02 : Hyp erbolic Tangent Curve Printed on 7 /6 /2021 10:43 AM

Curve Fluence LSE USE d-USE T @ 50 d-T @ SO 1 0.00E +000 0 100 0 85.7 0 2 6.09E +018 0 100 0 217.2 131.5 3 l.31E +019 0 100 0 221.4 135.7 4 4.02 E +019 0 100 0 266.8 181.1 5 4.39 E+0l9 0 100 0 249.9 16 4.2 6 8.4 5E+019 0 100 0 2 67.8 182.1

Figure 5-15 Charpy V-notch Percent Shear vs. Temperature for Prairie Island Unit 1 Reactor Vessel Correlation Monitor Material (cont.)

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-48

N49, 77°F N54, 90°F N51, 110°F N55, 120°F N60, 130°F

N50, 140°F N53, 150°F N58, 160°F N56, 180°F N52, 200°F

N57, 250°F N59, 300°F Figure 5-16 Charpy Impact Specimen Fracture Surfaces for Prairie Island Unit 1 Capsule N Intermediate Shell Forging C (Tangential Orientation)

Note: Specimen N51 shows areas of intergranular fracture. Since the Charpy testing results for this specimen are lower than results from other specimens for this material, inclusion of this specimen in the analysis of the tangential orientation forging is considered appropriate and conservative. The effect on the overall Charpy curve fit is small.

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-49

S60, 60°F S54, 77°F S57, 90°F S55 100°F S59, 110°F

S58, 130°F S49, 160°F S56, 170°F S51, 180°F S53, 200°F

S52, 250°F S50, 300°F

Figure 5-17 Charpy Impact Specimen Fracture Surfaces for Prairie Island Unit 1 Capsule N Intermediate Shell Forging C (Axial Orientation)

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-50

W34, 110°F W40, 125°F W36, 150°F W38, 175°F W37, 190°F

W39, 200°F W35, 250°F W33, 300°F

Figure 5-18 Charpy Impact Specimen Fracture Surfaces for the Prairie Island Unit 1 Capsule N Weld Material (Heat # 1752)

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-51

H35, -50°F H40, -25°F H37, 10°F H33, 50°F H36, 120°F

H34, 200°F H38, 250°F H39, 300°F

Figure 5-19 Charpy Impact Specimen Fracture Surfaces for the Prairie Island Unit 1 Capsule N Heat-Affected Zone Material

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-52

R33, 200°F R39, 225°F R34, 250°F R40, 275°F R38, 300°F

R37, 325°F R35, 325°F R36, 350°F

Figure 5-20 Charpy Impact Specimen Fracture Surfaces of the Prairie Island Unit 1 Capsule N Correlation Monitor Material

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-53

120.0 100.0 -----

Ultimate Tensile Strength I

~

80.0

~

• A-- 0.2 % Yield Strength

~

If> 60.0 ~

Ill i

40.0

20.0

0.0 0 100 200 300 400 500 600 700

Temperature (°F)

Legend:,, and are unirradiated

,, and are irradiated to 8.45 x 1019 n/cm2 (E > 1.0 MeV)

80

70 -

~

~ Reduction

60 -

50

~

~ 40 u

0 30 -

- Total Elongation

20 Uniform Elongation 10 --

0 0 100 200 300 400 500 600 700

Temperature (°F)

Figure 5-21 Tensile Properties for Prairie Island Unit 1 Reactor Vessel Intermediate Shell Forging C (Tangential Orientation)

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-54

120.0

100.0 a-___

---

/ -

,__ U ltimate Tensile strength.....,..

80.0 -

- /

.; ~ 0.2 % Y ield Strength -

=-,,, 60.0 II)

~

~

40.0

20.0

0.0 0 100 200 300 400 500 600 700

Temperature ("Fl

Legend:,, and are unirradiated

,, and are irradiated to 8.45 x 1019 n/cm2 (E > 1.0 MeV)

80

70 -

~

Area Redu ction

~ -----------

60

50

~

~ 40 i; '-'

C 30 20 -------- Total Elongation

10 Uniform Elongation

0 0 100 200 300 400 500 600 700

Temperature. ("F)

Figure 5-22 Tensile Properties for Prairie Island Unit 1 Reactor Vessel Intermediate Shell Forging C (Axial Orientation)

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-55

120. 0 ~ ----------------------------------------------~

100. 0 +---------------------------------------------------<

---

Ultim *ate Tensile Strength

~ 60.0 +--------------------------------------------------,

'40.0 +---------------------------------------------------<

20. 0 +---------------------------------------------------<

0.0 +-------~-----~------~------~------~-----~~---------<

100 200 300 400 500 600 700

Temperature rFl

Legend:,, and are unirradiated

,, and are irradiated to 8.45 x 1019 n/cm2 (E > 1.0 MeV)

70

.Ar9a, R:e,dllCUOn

ro --

s:,

~ Tolar EloagstJoa.

U!iU:ORII EJooge;bofl

10

100 "'" son 500 GOO,

Figure 5-23 Tensile Properties for Prairie Island Unit 1 Reactor Vessel Surveillance Program Weld Material (Heat # 1752)

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-56

N13 tested at 79°F.

N14 tested at 250°F.

N15 tested at 550°F.

Figure 5-24 Fractured Tensile Specimens from Prairie Island Unit 1 Capsule N Intermediate Shell Forging C (Tangential Orientation) [Scale in 1/10th of inch]

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-57

S13 tested at 81°F.

S14 tested at 250°F.

S15 tested at 550°F.

Figure 5-25 Fractured Tensile Specimens from Prairie Island Unit 1 Capsule N Intermediate Shell Forging C (Axial Orientation) [Scale in 1/10th of inch]

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-58

W13 tested at 83°F.

W14 tested at 250°F.

W15 tested at 550°F.

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

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-59

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Figure 5-27 Engineering Stress-Strain Curve for Prairie Island Unit 1 Capsule N Tensile Specimen N13 (Tangential Orientation), Tested at 79°F

100................................... :.................................... :....................................

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Figure 5-28 Engineering Stress-Strain Curve for Prairie Island Unit 1 Capsule N Tensile Specimen N14 (Tangential Orientation), Tested at 250°F

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Figure 5-29 Engineering Stress-Strain Curve for Prairie Island Unit 1 Capsule N Tensile Specimen N15 (Tangential Orientation), Tested at 550°F

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-60

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Figure 5-30 Engineering Stress-Strain Curve for Prairie Island Unit 1 Capsule N Tensile Specimen S13 (Axial Orientation), Tested at 81°F

100.....................................................................................................

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Figure 5-31 Engineering Stress-Strain Curve for Prairie Island Unit 1 Capsule N Tensile Specimen S14 (Axial Orientation), Tested at 250°F

100...................................,..................................,...................................

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Figure 5-32 Engineering Stress-Strain Curve for Prairie Island Unit 1 Capsule N Tensile Specimen S15 (Axial Orientation), Tested at 550°F

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 5-61

100...................................................................... ********** ***** ** *- ** **- *- ** * ******

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Figure 5-33 Engineering Stress-Strain Curve for Prairie Island Unit 1 Capsule N Tensile Specimen W13 (Weld), Tested at 83°F

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Note: The extensometer slipped, therefore this graph may not be representative.

Figure 5-34 Engineering Stress-Strain Curve for Prairie Island Unit 1 Capsule N Tensile Specimen W14 (Weld), Tested at 250°F

100 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *.. ~ * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * ~ * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

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Figure 5-35 Engineering Stress-Strain Curve for Prairie Island Unit 1 Capsule N Tensile Specimen W15 (Weld), Tested at 550°F

WCAP-18660-NP November 2021 Revision 0

• • • This record was final approved on 12/1/2021 8:24:23 AM. (This statement was added by the PRIME system upon its validation)