ML12055A166

WCAP-17501-NP, Revision 0, Analysis of Capsule 104 from the Calvert Cliffs Unit No. 2 Reactor Vessel Radiation Surveillance Program.

ML12055A166
Person / Time
Site:	Calvert Cliffs
Issue date:	02/22/2012
From:	Duo J, Long E Westinghouse
To:	Office of Nuclear Reactor Regulation
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WCAP-17501-NP, Rev 0
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WCAP-17501-NP, REVISION 0, ANALYSIS OF CAPSULE 1040 FROM THE CALVERT CLIFFS UNIT NO. 2 REACTOR VESSEL RADIATION SURVEILLANCE PROGRAM Calvert Cliffs Nuclear Power Plant, LLC February 22, 2012

Westinghouse Non-Proprietary Class 3 WCAP-17501-NP February 2012 Revision 0 Analysis of Capsule 1040 from the Calvert Cliffs Unit No. 2 Reactor Vessel Radiation Surveillance Program Westinghouse MMw,--,

WESTINGHOUSE NON-PROPRIETARY CLASS 3 WCAP-17501-NP Revision 0 Analysis of Capsule 1040 from the Calvert Cliffs Unit No. 2 Reactor Vessel Radiation Surveillance Program E. J. Long*

J. I. Duo*

February 2012 Reviewer: B. A. Rosier*

Aging Management and License Renewal Services Reviewer: A. D. Iams*

Aging Management and License Renewal Services Reviewer: F. A. Alpan* for J. Chen Radiation Engineering and Analysis Acting Manager: M. G. Semmler*

Aging Management and License Renewal Services

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

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

© 2012 Westinghouse Electric Company LLC All Rights Reserved

Westinghouse Non-Proprietary Class 3 iii TABLE OF CONTENTS L IS T OF TA B L ES ........................................................................................................................................ v L IS T OF F IG U RE S ................................................................................................................................... v iii EX EC U T IV E SU M MA RY .......................................................................................................................... xi I SU M M A RY O F R E SU LT S .......................................................................................................... 1-1 2 IN T R OD U C TIO N ........................................................................................................................ 2-1 3 B A C K G R O UN D .......................................................................................................................... 3-1 4 DESCRIPTION OF PROGRAM .............................................................................................. 4-1 5 TESTING OF SPECIMENS FROM CAPSULE 1040 ............................................................ 5-1 5 .1 O V E R V IE W .................................................................................................................... 5-1 5.2 CHARPY V-NOTCH IMPACT TEST RESULTS ........................................................... 5-3 5.3 TEN SILE TEST RESU LTS ............................................................................................. 5-5 6 RADIATION ANALYSIS AND NEUTRON DOSIMETRY ................................................... 6-1 6.1 INT R O DU C T ION ........................................................................................................... 6-1 6.2 DISCRETE ORDINATES ANALYSIS ........................................................................... 6-2 6.3 N EU TR ON DO SIM ETRY .............................................................................................. 6-4 6.4 CALCULATIONAL UNCERTAINTIES ........................................................................ 6-5 7 SURVEILLANCE CAPSULE REMOVAL SCHEDULE ....................................................... 7-1 8 R E F ER EN C E S ............................................................................................................................. 8-1 APPENDIX A VALIDATION OF THE RADIATION TRANSPORT MODELS BASED ON NEUTRON DOSIMETRY MEASUREMENTS ............................................................................. A-1 APPENDIX B LOAD-TIME RECORDS FOR CHARPY SPECIMEN TESTS .................................... B-I APPENDIX C CHARPY V-NOTCH PLOTS FOR EACH CAPSULE USING SYMMETRIC HYPERBOLIC TANGENT CURVE-FITTING METHOD ...................................... C-1 APPENDIX D CALVERT CLIFFS UNIT 2 SURVEILLANCE PROGRAM CREDIBILITY E VA L U AT IO N ............................................................................................................... D -I APPENDIX E CALVERT CLIFFS UNIT 2 UPPER-SHELF ENERGY EVALUATION ................. E-I APPENDIX F CALVERT CLIFFS UNIT 2 PRESSURIZED THERMAL SHOCK EVALUATION .... F-1 APPENDIX G CALVERT CLIFFS UNIT 2 PRESSURE-TEMPERATURE LIMIT CURVE APPLICABILITY CHECK ....................................................................................... G-1 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 V LIST OF TABLES Table 4-1 Chemical Composition (wt %) of the Calvert Cliffs Unit 2 Surveillance Test Materials -

Interm ediate Shell Plates (U nirradiated) .......................................................................... 4-3 Table 4-2 Chemical Composition (wt %) of the Calvert Cliffs Unit 2 Surveillance Test Materials -

Low er Shell Plates (U nirradiated) ................................................................................... 4-4 Table 4-3 Chemical Composition (wt %) of the Calvert Cliffs Unit 2 Surveillance Test Materials -

Weld and H AZ (U nirradiated) ......................................................................................... 4-5 Table 4-4 Heat Treatment History of the Calvert Cliffs Unit 2 Surveillance Test Materials ........... 4-6 Table 4-5 Arrangement of Encapsulated Test Specimens within Calvert Cliffs Unit 2 Capsule 1040

......................................................................................................................................... 4 -7 Table 5-1 Charpy V-notch Data for the Calvert Cliffs Unit 2 Lower Shell Plate D-8907-2 Irradiated to a Fluence of 2.44 x 10 n/cm 2 (E> 1.0 MeV) (Longitudinal Orientation) ................. 5-6 Table 5-2 Charpy V-notch Data for the Calvert Cliffs Unit 2 Surveillance Weld Metal (Heat # 10137) Irradiated to a Fluence of 2.44 x 10'9 n/cm 2 (E > 1.0 MeV) ................... 5-7 Table 5-3 Charpy V-notch Data for the Calvert Cliffs Unit 2 Heat-Affected-Zone (HAZ) Material Irradiated to a Fluence of 2.44 x 1019 n/cm 2 (E > 1.0 MeV) ............................................ 5-8 Table 5-4 Charpy V-notch Data for the Calvert Cliffs Unit 2 Standard Reference Material (SRM)

HSST 01 Irradiated to a Fluence of 2.44 x 1019 n/cm 2 (E > 1.0 MeV) ............................. 5-9 Table 5-5 Instrumented Charpy Impact Test Results for the Calvert Cliffs Unit 2 Lower Shell Plate D-8907-2 Irradiated to a Fluence of 2.44 x 1019 n/cm 2 (E > 1.0 MeV)

(L ongitudinal Orientation) ............................................................................................. 5-10 Table 5-6 Instrumented Charpy Impact Test Results for the Calvert Cliffs Unit 2 Surveillance Weld Metal (Heat # 10137) Irradiated to a Fluence of 2.44 x 10'9 n/cm 2 (E > 1.0 MeV) ..... 5-11 Table 5-7 Instrumented Charpy Impact Test Results for the Calvert Cliffs Unit 2 Heat-Affected-Zone (HAZ) Material Irradiated to a Fluence of 2.44 x 1019 n/cm 2 (E > 1.0 MeV) ....... 5-12 Table 5-8 Instrumented Charpy Impact Test Results for the Calvert Cliffs Unit 2 Standard Reference Material (SRM) HSST 01 Irradiated to a Fluence of 2.44 x 1019 n/cm 2 (E > 1.0 M e V ) .............................................................................................................................. 5-13 Table 5-9 Effect of Irradiation to 2.44 x 1019 n/cm 2 (E > 1.0 MeV) on the Charpy V-Notch Toughness Properties of the Calvert Cliffs Unit 2 Reactor Vessel Surveillance Capsule 1040 M aterials ................................................................................................................ 5-14 Table 5-10 Comparison of the Calvert Cliffs Unit 2 Surveillance Material 30 ft-lb Transition Temperature Shifts and Upper-Shelf Energy Decreases with Regulatory Guide 1.99, R evision 2, Predictions .................................................................................................. 5-15 Table 5-11 Tensile Properties of the Calvert Cliffs Unit 2 Capsule 104' Reactor Vessel Surveillance M aterials Irradiated to 2.44 x 1019 n/cm 2 (E > 1.0 M eV) .............................................. 5-16 WCAP-17501-NP February 2012 Revision 0

vi Westinghouse Non-Proprietary Class 3 Table 6-1 Calculated Neutron Exposure Rates and Integrated Exposures at the Surveillance C ap su le C enter ................................................................................................................. 6 -7 Table 6-2 Calculated Azimuthal Variation of Maximum Exposure Rates and Integrated Exposures at the Reactor Vessel Clad/Base Metal Interface .......................................................... 6-11 Table 6-3 Calculated Fast Neutron Exposure of Surveillance Capsules Withdrawn from Calvert C liffs U nit 2 ................................................................................................................... 6 -15 Table 6-4 Calculated Surveillance Capsule Lead Factors .............................................................. 6-16 Table 7-1 Surveillance Capsule W ithdrawal Schedule .................................................................... 7-1 Table A-I Nuclear Parameters Used in the Evaluation of Neutron Sensors ............................. A-11 Table A-2 Monthly Thermal Generation During the First Eighteen Fuel Cycles of the Calvert Cliffs Unit 2 Reactor (Reactor Power of 2560 MWt from 12/07/1976 to 10/18/1977; 2700 MWt from 10/19/1977 to 2/22/2009; and, 2737 MWt from 3/17/2009 to present)

...................................................................................................................................... A -12 Table A-3 Surveillance Capsule Flux for C3 Factors Calculation ................................................... A-17 Table A-4a Measured Sensor Activities and Reaction Rates for Surveillance Capsule 263. .......... A-19 Table A-4b Measured Sensor Activities and Reaction Rates for Surveillance Capsule 970 ............ A-20 Table A-4c Measured Sensor Activities and Reaction Rates for Surveillance Capsule 1040 .......... A-21 Table A-5 Comparison of Measured, Calculated, and Best-Estimate Reaction Rates at the Surveillance C apsule C enter ......................................................................................... A -23 Table A-6 Comparison of Calculated and Best-Estimate Exposure Rates at the Surveillance C apsule C enter ........................................................................................ A -24 Table A-7 Comparison of Measured/Calculated (M/C) Sensor Reaction Rate Ratios for Fast Neutron T hreshold R eactions ..................................................................................................... A -25 Table A-8 Comparison of Best-Estimate/Calculated (BE/C) Exposure Rate Ratios ..................... A-25 Table C-I Upper-Shelf Energy Values (ft-lb) Fixed in CVGRAPH ........................................... C-I Table D-I Calculation of Interim Chemistry Factors for the Credibility Evaluation Using Calvert Cliffs U nit 2 Surveillance Capsule D ata ......................................................................... D-4 Table D-2 Best-Fit Evaluation for Calvert Cliffs Unit 2 Surveillance Materials ............................. D-5 Table D-3 Calculation of Residual vs. Fast Fluence for Calvert Cliffs Unit 2 ................................ D-6 Table E-1 Predicted Positions 1.2 and 2.2 Upper-Shelf Energy Values at 32 EFPY ................... E-3 Table E-2 Predicted Positions 1.2 and 2.2 Upper-Shelf Energy Values at 52 EFPY ................... E-4 Table F-I Calculation of the Temperature Adjustments for the Calvert Cliffs Unit I and Farley Unit 1 Surveillance Capsule Data Applicable to Calvert Cliffs Unit 2 .................................... F-4 Table F-2 Calculation of Chemistry Factors for Calvert Cliffs Unit 2 Using CC-2 Surveillance C ap su le D ata .................................................................................................................... F-5 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 Vii Table F-3 Calculation of Chemistry Factors for Calvert Cliffs Unit 2 Using CC-I and Far-I Sister Plant Surveillance C apsule D ata ............................................................. ......................... F-6 Table F-4 RTPTS Calculations for the Calvert Cliffs Unit 2 Surveillance Capsule Materials at 32 and 52 EFP Y ........................................................................................................................... F-7 Table G-1 Calculation of the Calvert Cliffs Unit 2 Reactor Vessel Surveillance Capsule Material ART Values at the 1/4T Location for 52 EFPY .............................................................. G-2 Table G-2 Calculation of the Calvert Cliffs Unit 2 Reactor Vessel Surveillance Capsule Material ART Values at the 3/4T Location for 52 EFPY .............................................................. G-3 Table G-3 Comparison of CC-2 Surveillance Capsule Materials Initial Properties to Intermediate Shell Plate D-8906-1 for P-T Limit Curve Development ............................................... G-4 WCAP-17501-NP February 2012 Revision 0

viii Westinghouse Non-Proprietary Class 3 LIST OF FIGURES Figure 4-1 Arrangement of Surveillance Capsules in the Calvert Cliffs Unit 2 Reactor Vessel ....... 4-8 Figure 4-2 Original Surveillance Program Capsule in the Calvert Cliffs Unit 2 Reactor Vessel ...... 4-9 Figure 4-3 Surveillance Capsule Charpy Impact Specimen Compartment Assembly in the Calvert C liffs U nit 2 R eactor Vessel ........................................................................................... 4-10 Figure 4-4 Surveillance Capsule Tensile and Flux-Monitor Compartment Assembly in the Calvert C liffs U nit 2 R eactor Vessel ........................................................................................... 4-11 Figure 5-1 Charpy V-Notch Impact Energy vs. Temperature for Calvert Cliffs Unit 2 Reactor Vessel Lower Shell Plate D-8907-2 (Longitudinal Orientation) ............................................... 5-17 Figure 5-2 Charpy V-Notch Lateral Expansion vs. Temperature for Calvert Cliffs Unit 2 Reactor Vessel Lower Shell Plate D-8907-2 (Longitudinal Orientation) .................................... 5-18 Figure 5-3 Charpy V-Notch Percent Shear vs. Temperature for Calvert Cliffs Unit 2 Reactor Vessel Lower Shell Plate D-8907-2 (Longitudinal Orientation) ............................................... 5-19 Figure 5-4 Charpy V-Notch Impact Energy vs. Temperature for Calvert Cliffs Unit 2 Reactor Vessel Lower Shell Plate D-8907-2 (Transverse Orientation) .................................................. 5-20 Figure 5-5 Charpy V-Notch Lateral Expansion vs. Temperature for Calvert Cliffs Unit 2 Reactor Vessel Lower Shell Plate D-8907-2 (Transverse Orientation) ....................................... 5-21 Figure 5-6 Charpy V-Notch Percent Shear vs. Temperature for Calvert Cliffs Unit 2 Reactor Vessel Lower Shell Plate D-8907-2 (Transverse Orientation) .................................................. 5-22 Figure 5-7 Charpy V-Notch Impact Energy vs. Temperature for the Calvert Cliffs Unit 2 Reactor Vessel Surveillance Program Weld M etal ...................................................................... 5-23 Figure 5-8 Charpy V-Notch Lateral Expansion vs. Temperature for the Calvert Cliffs Unit 2 Reactor Vessel Surveillance Program Weld M etal ...................................................................... 5-24 Figure 5-9 Charpy V-Notch Percent Shear vs. Temperature for the Calvert Cliffs Unit 2 Reactor Vessel Surveillance Program Weld M etal ...................................................................... 5-25 Figure 5-10 Charpy V-Notch Impact Energy vs. Temperature for the Calvert Cliffs Unit 2 Reactor Vessel H eat-A ffected-Zone M aterial ............................................................................. 5-26 Figure 5-11 Charpy V-Notch Lateral Expansion vs. Temperature for the Calvert Cliffs Unit 2 Reactor Vessel Heat-A ffected-Zone M aterial ............................................................................. 5-27 Figure 5-12 Charpy V-Notch Percent Shear vs. Temperature for the Calvert Cliffs Unit 2 Reactor Vessel H eat-A ffected-Zone M aterial ............................................................................. 5-28 Figure 5-13 Charpy V-Notch Impact Energy vs. Temperature for the Calvert Cliffs Unit 2 Reactor Vessel Standard R eference M aterial .............................................................................. 5-29 Figure 5-14 Charpy V-Notch Lateral Expansion vs. Temperature for the Calvert Cliffs Unit 2 Reactor Standard R eference M aterial .......................................................................................... 5-30 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 ix Figure 5-15 Charpy V-Notch Percent Shear vs. Temperature for the Calvert Cliffs Unit 2 Reactor Vessel Standard Reference Material ................................. 5-31 Figure 5-16 Charpy Impact Specimen Fracture Surfaces for Calvert Cliffs Unit 2 Reactor Vessel Lower Shell Plate D-8907-2 (Longitudinal Orientation) ............................................... 5-32 Figure 5-17 Charpy Impact Specimen Fracture Surfaces for Calvert Cliffs Unit 2 Reactor Vessel Surveillance Program Weld M aterial ............................................................................. 5-33 Figure 5-18 Charpy Impact Specimen Fracture Surfaces for the Calvert Cliffs Unit 2 Reactor Vessel H eat-A ffected-Z one M aterial ......................................................................................... 5-34 Figure 5-19 Charpy Impact Specimen Fracture Surfaces for the Calvert Cliffs Unit 2 Reactor Vessel Standard R eference M aterial .......................................................................................... 5-35 Figure 5-20 Tensile Properties for Calvert Cliffs Unit 2 Reactor Vessel Lower Shell Plate D-8907-2 (L ongitudinal Orientation) ............................................................................................. 5-36 Figure 5-21 Tensile Properties for Calvert Cliffs Unit 2 Reactor Vessel Surveillance Program Weld M aterial .......................................................................................................................... 5-3 7 Figure 5-22 Tensile Properties for the Calvert Cliffs Unit 2 Reactor Vessel Heat-Affected-Zone M aterial .......................................................................................................................... 5 -3 8 Figure 5-23 Fractured Tensile Specimens from Calvert Cliffs Unit 2 Reactor Vessel Lower Shell Plate D -8907-2 (Longitudinal Orientation) ............................................................................ 5-39 Figure 5-24 Fractured Tensile Specimens from the Calvert Cliffs Unit 2 Reactor Vessel Surveillance Program Weld M etal ...................................................................................................... 5-40 Figure 5-25 Fractured Tensile Specimens from the Calvert Cliffs Unit 2 Reactor Vessel H eat-A ffected-Zone M aterial ......................................................................................... 5-41 Figure 5-26 Engineering Stress-Strain Curve for Calvert Cliffs Unit 2 Lower Shell Plate D-8907-2 Tensile Specimen 1KP Tested at 1750 (Longitudinal Orientation) ................................ 5-42 Figure 5-27 Engineering Stress-Strain Curve for Calvert Cliffs Unit 2 Lower Shell Plate D-8907-2 Tensile Specimen IK2 Tested at 2500 (Longitudinal Orientation) ................................ 5-42 Figure 5-28 Engineering Stress-Strain Curve for Calvert Cliffs Unit 2 Lower Shell Plate D-8907-2 Tensile Specimen IKE Tested at 5500 (Longitudinal Orientation) ................................ 5-43 Figure 5-29 Engineering Stress-Strain Curve for Calvert Cliffs Unit 2 Surveillance Program Weld M etal Tensile Specim en 3JP Tested at 750 .................................................................... 5-44 Figure 5-30 Engineering Stress-Strain Curve for Calvert Cliffs Unit 2 Surveillance Program Weld M etal Tensile Specimen 3K4 Tested at 1500 . ................................................................ 5-44 Figure 5-31 Engineering Stress-Strain Curve for Calvert Cliffs Unit 2 Surveillance Program Weld M etal Tensile Specim en 3L4 Tested at 5500 .................................................................. 5-45 Figure 5-32 Engineering Stress-Strain Curve for Calvert Cliffs Unit 2 Heat-Affected-Zone Material Tensile Specim en 4JE Tested at 750 .............................................................................. 5-46 WCAP-17501-NP February 2012 Revision 0

x Westinghouse Non-Proprietary Class 3 Figure 5-33 Engineering Stress-Strain Curve for Calvert Cliffs Unit 2 Heat-Affected-Zone Material Tensile Specim en 4JM Tested at 1500 ........................................................................... 5-46 Figure 5-34 Engineering Stress-Strain Curve for Calvert Cliffs Unit 2 Heat-Affected-Zone Material Tensile Specim en 4K 4 Tested at 550 ............................................................................. 5-47 Figure 6-1 Calvert Cliffs Unit 2 r,0 Reactor Geometry without Surveillance Capsules ................. 6-17 Figure 6-2 Calvert Cliffs Unit 2 r,0 Reactor Geometry with 70 and 14' Surveillance Capsules ..... 6-18 Figure 6-3 Calvert Cliffs Unit 2 rz Reactor Geometry ................................................................... 6-19 Figure E-1 Regulatory Guide 1.99, Revision 2 Predicted Decrease in Upper-Shelf Energy as a Function of C opper and Fluence ..................................................................................... E-2 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 Xi EXECUTIVE

SUMMARY

The purpose of this report is to document the testing results of surveillance Capsule 1040 from Calvert Cliffs Unit 2. Capsule 1040 was removed at 27.13 Effective Full Power Years, EFPY, (at 2737 MWt, the rated thermal power after Appendix K uprate) and post-irradiation mechanical tests of the Charpy V-notch and tensile specimens were performed. All the calculations and dosimetry evaluations described in this report were based on nuclear cross-section data derived from ENDF/B-VI, and made use of the latest available calculational tools. In this document, EFPYs are expressed in terms of 2737 MWt, the reference power of the analysis, except in the case of tables with exposure cumulative parameters for which EFPY at 2700 MWt for the first seventeen cycles are also included for the purpose of direct comparison with previous documents. Capsule 104' received a fluence of 2.44 x 1019 n/cm 2 (E > 1.0 MeV) after irradiation to 27.13 EFPY. The peak clad/base metal interface vessel fluence after 27.13 EFPY of plant operation was 2.53 x 1019 n/cm 2 (E > 1.0 MeV).

This evaluation led to the following conclusions: 1) The measured percent decrease in upper-shelf energy for all the surveillance materials contained in Calvert Cliffs Unit 2 Capsule 104' are less than the Regulatory Guide 1.99, Revision 2 [Reference 1] predictions. 2) The Calvert Cliffs Unit 2 surveillance plate and weld data is judged to be credible. This credibility evaluation can be found in Appendix D.

3) All beltline materials exhibit a more than adequate upper-shelf energy level for continued safe plant operation and are predicted to maintain an upper-shelf energy greater than 50 ft-lb throughout the current license (32 EFPY) and license extension (52 EFPY) as required by 10 CFR 50, Appendix G

[Reference 2]. The upper-shelf energy evaluation is presented in Appendix E. 4) All the surveillance capsule materials are predicted to meet the Pressurized Thermal Shock (PTS) screening criteria throughout the current license (32 EFPY) and license extension (52 EFPY) as required by 10 CFR 50.61

[Reference 3]. The PTS evaluation is presented in Appendix F. 5) The Capsule 1040 evaluations, material properties and fluence, did not affect the applicability of the current Calvert Cliffs Unit 2 pressure-temperature (P-T) limit curves. The current Calvert Cliffs Unit 2 P-T limit curves are now applicable through 48 EFPY. The applicability evaluation is presented in Appendix G.

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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Westinghouse Non-Proprietary Class 3 1-1 1

SUMMARY

OF RESULTS The analysis of the reactor vessel materials contained in surveillance Capsule 104', the third capsule removed and tested from the Calvert Cliffs Unit 2 reactor pressure vessel, led to the following conclusions:

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

Appendix C presents the CVGRAPH, Version 5.3, Charpy V-notch plots for Capsule 1040. The previous capsules, along with the original program unirradiated material input data, were updated using CVGRAPH, Version 5.3, from the hand-drawn plots presented in earlier reports. This accounts for the differences in measured values of 30 ft-lb and 50 ft-lb transition temperature between the results documented in this report and those shown in the previous Calvert Cliffs Unit 2 capsule reports.

• Capsule 1040 received an average fast neutron fluence (E > 1.0 MeV) of 2.44 x 1019 n/cm 2 after 27.13 effective full power years (EFPY) of plant operation.

• Irradiation of the reactor vessel Lower Shell Plate D-8907-2 Charpy specimens, oriented with the longitudinal axis of the specimen parallel to the major working direction (longitudinal orientation),

resulted in an irradiated 30 ft-lb transition temperature of 146.97F and an irradiated 50 ft-lb transition temperature of 179.77F. This results in a 30 ft-lb transition temperature increase of 135.6'F and a 50 ft-lb transition temperature increase of 143.6 0 F for the longitudinally oriented specimens.

" Irradiation of the Surveillance Program Weld Metal (Heat # 10137) Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 16.0'F and an irradiated 50 ft-lb transition temperature of 27.4°F. This results in a 30 ft-lb transition temperature increase of 69.7°F and a 50 ft-lb transition temperature increase of 58.2°F.

• Irradiation of the Heat-Affected-Zone (HAZ) Material Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 40.4'F and an irradiated 50 ft-lb transition temperature of 112.9°F.

This results in a 30 ft-lb transition temperature increase of 105.4'F and a 50 ft-lb transition temperature increase of 123.6°F.

• Irradiation of the Standard Reference Material (SRM) HSST 01 Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 190.5°F and an irradiated 50 ft-lb transition temperature of 217.9°F. This results in a 30 ft-lb transition temperature increase of 165.5°F and a 50 ft-lb transition temperature increase of 163.7°F.

• The average upper-shelf energy of Lower Shell Plate D-8907-2 (longitudinal orientation) resulted in an average energy decrease of 33.9 ft-lb after irradiation. This results in an irradiated average upper-shelf energy of 107.7 ft-lb for the longitudinally oriented specimens.

" The average upper-shelf energy of the Surveillance Program Weld Metal Charpy specimens resulted in an average energy decrease of 28.6 ft-lb after irradiation. This results in an irradiated average upper-shelf energy of 110.3 ft-lb for the weld metal specimens.

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1-2 Westinghouse Non-Proprietary Class 3

• The average upper-shelf energy of the HAZ Material Charpy specimens resulted in an average energy decrease of 33.7 ft-lb after irradiation. This results in an irradiated average upper-shelf energy of 94.0 ft-lb for the HAZ Material.

• The average upper-shelf energy of the SRM HSST 01 Charpy specimens resulted in an average energy decrease of 49.2 ft-lb after irradiation. This results in an irradiated average upper-shelf energy of 92.3 ft-lb for the SRM.

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

Lower Shell Plate D-8907-2 Charpy specimens, oriented with the longitudinal axis of the specimen perpendicular to the major working direction (transverse orientation), were not included in the Calvert Cliffs Capsule 104'. However, the transversely orientated unirradiated and previously withdrawn capsule results for the Lower Shell Plate D-8907-2 Charpy specimens were reanalyzed in this report. The transverse orientation Lower Shell Plate D-8907-2 was contained in Capsule 970, which was irradiated to a neutron fluence of 1.95 x 10 19 n/cm2 (E > 1.0 MeV).

The results of the transverse orientation Lower Shell Plate D-8907-2 reanalysis will be included in Table 5-10 and shown in Figures 5-4 through 5-6.

Irradiation of the Lower Shell Plate D-8907-2 Charpy specimens, oriented with the longitudinal axis of the specimen perpendicular to the major working direction (transverse orientation), resulted in an irradiated 30 ft-lb transition temperature of 137.57F and an irradiated 50 ft-lb transition temperature of 179.07F. This results in a 30 ft-lb transition temperature increase of 102.67F and a 50 ft-lb transition temperature increase of 112.7 0 F.

• The average upper-shelf energy of the Lower Shell Plate D-8907-2 (transverse orientation) Charpy specimens resulted in an average energy decrease of 27.7 ft-lb after irradiation. This results in an irradiated average upper-shelf energy of 86.7 ft-lb for the transversely oriented specimens.

• Based on the credibility evaluation presented in Appendix D, the Calvert Cliffs Unit 2 surveillance plate and weld data is credible.

• Based on the upper-shelf energy evaluation in Appendix E, all beltline materials exhibit a more than adequate upper-shelf energy level for continued safe plant operation and are predicted to maintain an upper-shelf energy greater than 50 ft-lb throughout the end of the current license (32 EFPY) and license extension (52 EFPY) as required by 10 CFR 50, Appendix G [Reference 2].

• Based on the Pressurized Thermal Shock (PTS) evaluation in Appendix F, all the surveillance capsule materials are predicted to meet the 10 CFR 50.61 [Reference 3] screening criteria throughout the current license (32 EFPY) and license extension (52 EFPY).

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Westinghouse Non-Proprietary Class 3 1-3

• Based on the Pressure-Temperature (P-T) limit curve applicability check in Appendix G, the Capsule 1040 evaluations, material properties and fluence did not affect the applicability of the current Calvert Cliffs Unit 2 P-T limit curves. The current Calvert Cliffs Unit 2 P-T limit curves are now applicable through 48 EFPY.

• The calculated 52 EFPY (end-of-life-extension) neutron fluence values (E > 1.0 MeV) at the core mid-plane for the Calvert Cliffs Unit 2 reactor vessel using the Regulatory Guide 1.99, Revision 2, attenuation formula (i.e., Equation # 3 in the guide) are as follows:

2 Calculated (52 EFPY): Vessel inner radius* = 4.28 x 1019 n/cm (Calculated using the fluence data contained in Table 6-2) 2 Vessel 1/4 thickness = 2.551 x 10'9 n/cm 9 2 Vessel 3/4 thickness = 0.906 x 10' n/cm

• Clad/base metal interface

" Because the end of life (EOL) fluence projection of this report is significantly lower than that in CA06959, Revision 0 [Reference 29], a brief explanation for the difference is outlined here.

Reference 29 projected EOL peak clad base metal interface (CBMI) fluence is 6.16 x 1019 n/cm 2 for an estimated a thermal power generation of 51.55 EFPY at 2700 MWt through 8/13/2036. In this analysis, the EOL thermal power generation through August 13, 2036 is estimated to be 52 EFPY at 2737 MWt and the corresponding EOL peak CBMI fluence is 4.28 x 1019 n/cm 2 . The reason for the significant decrease in estimated peak CBMI fluence is that Reference 29 uses cycle 9 flux data to perform the extrapolations while the current analysis considers the low leakage core loading pattern that Calvert Cliffs Unit 2 has implemented since Cycle 10. More specifically, the current analysis uses actual core designed data from cycles I through 18 to perform cycle-specific transport calculations and future fluence projections are estimated with cycle 18 flux data.

" The current report uses slightly overestimated EFPY (and thus, overestimated time integrated exposure parameters). Notice that the cycle-wise exposure rates (flux and dpa/s) are still correct. The integrated exposure parameters are evaluated to be at most 6% overestimated (for Cycle 2) and 3% or less for Cycle 18 and future projections. It is recommended that in future fluence analyses the EFPY (and time integrated exposure) be corrected according to the following table:

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1-4 Westinghouse Non-Proprietary Class 3 WCAP-17501 Design Basis (Correct)

Cycle EFPY Cycle EFPS EFPY Cycle EFPS 1 1.39 43726821 1.35 42485757 2 2.28 28304427 2.16 25718102 3 3.22 29688012 3.10 29608142 4 4.63 44516242 4.47 43254621 5 5.79 36570373 5.58 34876668 6 6.93 36036347 6.69 35097928 7 8.14 38027913 7.83 35999575 8 9.65 47657946 9.32 47065957 9 11.16 47778629 10.81 47165729 10 12.74 49689016 12.39 49575113 11 14.48 54905721 14.12 54692572 12 16.20 54341141 15.84 54265144 13 18.00 56854841 17.63 56679027 14 19.71 54010369 19.35 54000053 15 21.51 56713759 21.14 56582528 16 23.41 59877642 23.04 59921647 17 25.27 58649289 24.89 58414854 18 27.13 58743605 26.74 58556027 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 2-1 2 INTRODUCTION This report presents the results of the examination of Capsule 1040, the third capsule removed and tested in the continuing surveillance program, which monitors the effects of neutron irradiation on the Constellation Energy Calvert Cliffs Unit 2 reactor pressure vessel materials under actual operating conditions.

The surveillance program for the Calvert Cliffs Unit 2 reactor pressure vessel materials was designed and recommended by Combustion Engineering, Inc. A description of the surveillance program and the pre-irradiation mechanical properties of the reactor vessel materials is presented in TR-ESS-001

[Reference 4], "Testing and Evaluation of Calvert Cliffs, Units I and 2 Reactor Vessel Materials Irradiation Surveillance Program Baseline Samples for the Baltimore Gas & Electric Co." and CENPD-48

[Reference 5], "Summary Report on Manufacture of Test Specimens and Assembly of Capsules for Irradiation Surveillance of Calvert Cliffs - Unit 2 Reactor Vessel Materials." The original surveillance program was planned to cover the 40-year design life of the reactor pressure vessel and was based on ASTM E185-70 [Reference 6], "Standard Recommended Practice for Surveillance Tests for Nuclear Reactor Vessels." The Comprehensive Reactor Vessel Surveillance Program (CRVSP), Revision 5

[Reference 7] documents the current surveillance capsule and reactor vessel integrity programs for Calvert Cliffs Unit 2.

Capsule 104' was removed from the reactor after 27.13 EFPY of exposure and shipped to the Westinghouse Research and Technology Unit (RTU) Hot Cell Facility, where the post-irradiation mechanical testing of the Charpy V-notch impact and tensile surveillance specimens was performed.

This report summarizes the testing of the post-irradiation data obtained from surveillance Capsule 104' removed from the Calvert Cliffs Unit 2 reactor vessel and discusses the analysis of the data.

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Westinghouse Non-Proprietary Class 3 3-1 3 BACKGROUND The ability of the large steel pressure vessel containing the reactor core and its primary coolant to resist fracture constitutes an important factor in ensuring safety in the nuclear industry. The beltline region of the reactor pressure vessel is the most critical region of the vessel because it is subjected to significant fast neutron bombardment. The overall effects of fast neutron irradiation on the mechanical properties of low-alloy, ferritic pressure vessel steels such as SA533 Grade B Class 1 (base material of the Calvert Cliffs Unit 2 reactor pressure vessel beltline) are well documented in the literature. Generally, low-alloy ferritic materials show an increase in hardness and tensile properties and a decrease in ductility and toughness during high-energy irradiation.

A method for ensuring the integrity of reactor pressure vessels has been presented in "Fracture Toughness Criteria for Protection Against Failure," Appendix G to Section XI of the ASME Boiler and Pressure Vessel Code [Reference 8]. The method uses fracture mechanics concepts and is based on the reference nil-ductility transition temperature (RTNDT).

RTNDT is defined as the greater of either the drop-weight nil-ductility transition temperature (NDTT per ASTM E208 [Reference 9]) or the temperature 607F less than the 50 ft-lb (and 35-mil lateral expansion) temperature as determined from Charpy specimens oriented perpendicular (transverse) to the major working direction of the plate. The RTNDT of a given material is used to index that material to a reference stress intensity factor curve (KI, curve) which appears in Appendix G to Section XI of the ASME Code

[Reference 8]. The KI curve is a lower bound of static fracture toughness results obtained from several heats of pressure vessel steel. When a given material is indexed to the K1 , curve, allowable stress intensity factors can be obtained for this material as a function of temperature. Allowable operating limits can then be determined using these allowable stress intensity factors.

RTNDT and, in turn, the operating limits of nuclear power plants can be adjusted to account for the effects of radiation on the reactor vessel material properties. The changes in mechanical properties of a given reactor pressure vessel steel, due to irradiation, can be monitored by a reactor vessel surveillance program, such as the Calvert Cliffs Unit 2 reactor vessel radiation surveillance program, in which a surveillance capsule is periodically removed from the operating nuclear reactor and the encapsulated specimens are tested. The increase in the average Charpy V-notch 30 ft-lb temperature (ARTNDT) due to irradiation is added to the initial RTNDT, along with a margin (M) to cover uncertainties, to adjust the RTNDT (ART) for radiation embrittlement. This ART (initial RTNDT + M + ARTNDT) is used to index the material to the K1 ccurve 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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Westinghouse Non-Proprietary Class 3 4-1 4 DESCRIPTION OF PROGRAM Six surveillance capsules for monitoring the effects of neutron exposure on the Calvert Cliffs Unit 2 reactor pressure vessel core region (beltline) materials were inserted in the reactor vessel prior to initial plant startup. The six surveillance capsules were positioned adjacent to the reactor vessel inside wall so that the irradiation conditions are very similar to those of the reactor vessel. The six surveillance capsules are bisected by the core mid-plane and are positioned in capsule holders at azimuthal locations near the regions of maximum neutron flux. The capsules contain specimens made from the following:

• Lower Shell Plate D-8907-2 (longitudinal orientation)

• Lower Shell Plate D-8907-2 (transverse orientation)

• Weld metal fabricated by a submerged arc process with Mil B-4 weld filler wire, Heat Number 10137 Linde Type 0091 flux, Lot Number 3999, which is identical in Heat Number and flux type to that used in the actual fabrication of the intermediate to lower shell circumferential weld seam 9-203

" Weld heat-affected-zone (HAZ) material of Lower Shell Plates D-8907-1 and D-8907-2

• Heavy-Section Steel Technology (HSST) 01 Standard Reference Material (SRM)

Test material obtained from the lower shell course plate (after thermal heat treatment and forming of the plate) was taken at least one plate thickness from the quenched edges of the plate. All test specimens were machined from the '/4 and 3/4 thickness locations of the plate after performing a simulated post-weld stress-relieving treatment on the test material. Test specimens were also removed from weld and heat-affected-zone metal of stress-relieved weldments joining Lower Shell Plate D-8907-1 and adjacent Lower Shell Plate D-8907-3, and Lower Shell Plate D-8907-1 and adjacent Lower Shell Plate D-8907-2, respectively.

Charpy V-notch impact specimens from Lower Shell Plate D-8907-2 were machined in the longitudinal orientation (longitudinal axis of the specimen parallel to the major rolling direction) and also in the transverse orientation (longitudinal axis of the specimen perpendicular to the major rolling direction).

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

Tensile specimens from Lower Shell Plate D-8907-2 were machined in both the longitudinal and transverse orientations. Tensile specimens from the weld metal were oriented perpendicular to the welding direction.

Some of the capsules in the Calvert Cliffs Unit 2 surveillance program, including Capsule 1040, contain Standard Reference Material, which was supplied by the Oak Ridge National Laboratory, from plate material used in the Heavy-Section Steel Technology (HSST) Program. The material for the Calvert Cliffs Unit 2 capsules was obtained from an A533, Grade B Class I plate labeled HSST 01. The plate was produced by the Lukens Steel Company and heat treated by Combustion Engineering, Inc.

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4-2 Westinghouse Non-Proprietary Class 3 All six capsules contained flux monitor assemblies made from sulfur pellets, iron wire, titanium wire, nickel wire (cadmium-shielded), aluminum-cobalt wire (cadmium-shielded and unshielded), copper wire (cadmium-shielded) and uranium foil (cadmium-shieldedand unshielded).

The capsules contained (12 total) thermal monitors made from four low-melting-point eutectic alloys, which were sealed in glass tubes. The thermal monitors were located in three different positions in the capsule. These thermal monitors were used to define the maximum temperature attained by the test specimens during irradiation. The composition of the four eutectic alloys and their melting points are as follows:

80.0% Au, 20.0% Sn Melting Point: 536'F (280'C) 5.0% Ag, 5.0% Sn, 90.0% Pb Melting Point: 558°F (292°C) 2.5% Ag, 97.5% Pb Melting Point: 580'F (304'C) 1.75% Ag, 0.75% Sn, 97.5% Pb Melting Point: 590'F (31 00 C)

The chemical composition and heat treatment of the unirradiated surveillance materials are presented in Tables 4-1 through 4-4. The arrangement of the various mechanical specimens in Capsule 1040 is shown in Table 4-5. The data in Tables 4-1 through 4-5 was obtained from the unirradiated surveillance program report, TR-ESS-001 [Reference 4], Table I, the manufacture of Calvert Cliffs Unit 2 test specimens report, CENPD-48 [Reference 5], Tables III, XIX and XX, and the CRVSP, Revision 5 [Reference 7],

Table 3-8.

Capsule 1040 was removed after 27.13 effective full power years (EFPY) of plant operation. This capsule contained Charpy V-notch and tensile specimens, dosimeters, and thermal monitors. Figures 4-1 through 4-4 detail the arrangement of the surveillance capsules, an example of an original program surveillance capsule, a close-up on the Charpy impact specimen compartment and the tensile and flux-monitor compartment assembly in the Calvert Cliffs Unit 2 reactor vessel. Capsules 830, 970, 2630 and 2770 are radiologically equivalent to the 70 azimuth, while Capsules 1040 and 2840 are radiologically equivalent to the 140 azimuth.

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Westinghouse Non-Proprietary Class 3 4-3 Table 4-1 Chemical Composition (wt %) of the Calvert Cliffs Unit 2 Surveillance Test Materials - Intermediate Shell Plates (Unirradiated)

Element *,l1 Pl..

ta iate She Intermediate Shell Plate IIntermediate Shell1

,PlateD-89061 . D-8906-2 Plate D-8906-3 Combustion Engineering Analysis~a Si 0.21 0.23 0.27 S 0.015 0.018 0.017 P 0.006 0.007 0.005 Mn 1.36 1.39 1.38 C 0.24 0.24 0.22 Cr 0.08 0.09 0.08 Ni 0.56 0.56 0.55 Mo 0.63 0.64 0.63 V 0.004 0.004 0.004 Cb < 0.01 < 0.01 < 0.01 B 0.0003 0.0004 0.0003 Co 0.011 0.011 0.011 N 0.007 0.008 0,007 Cu 0.15 0.11 0.14 Al 0.023 0.021 0.023 W < 0.01 < 0.01 < 0.01 Ti < 0.01 < 0.01 < 0.01 As 0.012 0.012 0.010 Sn 0.019 0.006 0.016 Zr 0.001 0.001 0.001 Note:

(a) Data obtained from CENPD-48 [Reference 5].

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4-4 Westinghouse Non-Proprietary Class 3 Table 4-2 Chemical Composition (wt %) of the Calvert Cliffs Unit 2 Surveillance Test Materials - Lower Shell Plates (Unirradiated)

Loe hllLwrShell Plate D-8907-1 Plate D-8907-2(b)  :

I Lower Shell Plate D-8907-3 Element

Combustion Engineering Analyslsa)

Si 0.17 0.21 0.18 S 0.011 0.010 0.012 P 0.005 0.005 0.006 Mn 1.26 1.22 1.26 C 0.22 0.23 0.24 Cr 0.09 0.11 0.07 Ni 0.60 0.66 0.74 Mo 0.61 0.63 0.63 V 0.004 0.004 0.004 Cb < 0.01 < 0.01 < 0.01 B 0.0003 0.0001 0.0004 Co 0.010 0.011 0.011 N 0.007 0.006 0.010 Cu 0.15 0.14 0.11 Al 0.021 0.022 0.019 W < 0.01 < 0.01 < 0.01 Ti < 0.01 < 0.01 < 0.01 As 0.014 0.012 0.017 Sn 0.007 0.006 0.006 Zr 0.002 0.001 0.001 Notes:

(a) Data obtained from CENPD-48 [Reference 5].

(b) Surveillance program plate material.

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Westinghouse Non-Proprietary Class 3 4-5 Table 4-3 Chemical Composition (wt %) of the Calvert Cliffs Unit 2 Surveillance Test Materials -Weld and HAZ (Unirradiated)

Intermediate to Lower Shell

~Girth Weld 9-203 (Heat # HAZ Material 10137/Linde 0091) I D8907"1i.)8907-21(O Element iD-8907-1ID-80*7*)* j ___ý_________________

Combutstion "EngineeringAnalysisai Si 0.17 0.17 S 0.013 0.010 P 0.016 0.014 Mn 1.11 1.13 C 0.13 0.14 Cr 0.05 0.04 Ni 0 .0 6(d) 0.07 Mo 0.53 0.54 V 0.010 0.004 Cb < 0.01 < 0.01 B 0.0003 0.0002 Co 0.009 0.010 N 0.008 0.008 Cu 0 .2 1(d) 0.22 Al < 0.001 < 0.001 W <0.01 <0.01 Ti < 0.01 < 0.01 As 0.013 0.018 Sn 0.004 0.005 Zr 0.001 0.002 Notes:

(a) Data obtained from CENPD-48 [Reference 5], unless otherwise noted.

(b) Surveillance program weld material.

(c) Surveillance program HAZ material.

(d) Data obtained from CRVSP, Revision 5 [Reference 7]. These best-estimate average values were determined using information from various sources.

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4-6 Westinghouse Non-Proprietary Class 3 Table 4-4 Heat Treatment History of the Calvert Cliffs Unit 2 Surveillance Test Materials Material(A) Temperatre(')(OF) Time(')(hours) /cooling~~'a)

Austenitized @ 4.00 Water-Quenched 1600 +/- 25 (871°C)

Intermediate Shell Plates Tempered @ 1225 +/- 25 D-8906-1, D-8906-2 and (663-C) ___25 4.00 Air-Cooled D-8906-3 Stress Relieved @ 40.00 Furnace-Cooled to 600'F 1150 +/- 25 (621°C) (316°C)

Austenitized @ 4.00 Water-Quenched 1600 +/- 25 (87 1C)

Lower Shell Plates D-8907-1, D-8907-2 and Tempered @ 1225 254.00 Air-Cooled D-8907-3 (6630 C)

Stress Relieved @ 40.00 Furnace-Cooled to 600'F 1150 +/- 25 (621°C) (316°C)

Stress Relieved @ 0.25 See note (b)

Surveillance Weld Metal 1125 +/- 25 (607°C)

(Heat # 10137/Linde 0091) Stress Relieved @ 1150 40.00 Furnace-Cooled to 600'F (621°C) (316°C)

Notes:

(a) Data obtained from TR-ESS-001 [Reference 4].

(b) Interstage stress relief was performed at 1125 +/- 25'F for 0.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> followed by final stress relief at 1150'F for 40.00 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. Furnace cooling was performed following the final stress relief.

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Westinghouse Non-Proprietary Class 3 4-7 Table 4-5 Arrangement of Encapsulated Test Specimens within Calvert Cliffs Unit 2 Capsule 1040 Comp artmentPosition(.) Compartment Number () Seie ubr a

~~~ ~~~~ Specimeni Type and Material)t) SemnNubr 5314 (Tensile HAZ Specimens) 4JE, 4J4, 4K4 5324 43D,43B,45D,44B, (Charpy Impact HAZ Specimens) 44T, 42M, 462, 45C, 453, 43C, 44A, 434 5336 67B, 67D, 67M, 67E, 3 (Charpy Impact SRM 66K, 66E, 66B, 66P, Plate Specimens) 67C, 66J, 67J, 66L 5341 4 (Tensile Longitudinal 1KP, 1K2, IKE Plate Specimens) 5351 12M, 123, 162, 15U, 5 (Charpy Impact Longitudinal 122, 13B, 142, 1IY, Plate Specimens) 11K, 15M, 12C, 15P 5363 35L, 343, 313, 32P, (Charpy Impact Weld Specimens) 316, 31K, 31J, 32T, 34D, 31E, 341, 31M 5373 (Tensile Weld Specimens) 3JP, 3K4, 3L4 Note:

(a) Data obtained from CENPD-48 [Reference 5].

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4-8 Westinghouse Non-Proprietary Class 3 4-8 Westinghouse Non-Proprietary Class 3 Elevatdon EnA edý Plan Vjew Vlew Figure 4-1 Arrangement of Surveillance Capsules in the Calvert Cliffs Unit 2 Reactor Vessel WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 4-9 Westinghouse Non-Proprietary Class 3 4-9 I Waegs GIvpf AGOWuY Ftn Multo" Flux Montor COumPM2t-I Figure 4-2 Original Surveillance Program Capsule in the Calvert Cliffs Unit 2 Reactor Vessel WCAP-17501-NP February 2012 Revision 0

4-10 Westinghouse Non-Proprietary Class 3 4-10 Westinghouse Non-Proprietary Class 3 CoaplI~ng- End Cap Chatj bVMpe spwens

. ERuanguar Tubing

.Wedge CouplIng - End Cap Figure 4-3 Surveillance Capsule Charpy Impact Specimen Compartment Assembly in the Calvert Cliffs Unit 2 Reactor Vessel WCAP- 17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 4-11 Westinghouse Non-Proprietary Class 3 4-11

• • Stacsa $PjTubing Cadmium Shield Flux Spectrumn Monitor aw Flux Monitor Housing FIUX SpectrUM Monitor ,---4* - Muesold IXumretn Teperan Monitor Housing 1 )Low Molting Alloy Tensile; Specimen -

sptli spae Temile Specimen Housing 4-Rectangular Tubing

-Wedge Coupling - End Cap Figure 4-4 Surveillance Capsule Tensile and Flux-Monitor Compartment Assembly in the Calvert Cliffs Unit 2 Reactor Vessel WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 5-1 5 TESTING OF SPECIMENS FROM CAPSULE 1040 5.1 OVERVIEW The post-irradiation mechanical testing of the Charpy V-notch impact specimens and tensile specimens was performed at the Hot Cell Facility at the Westinghouse Research and Technology Unit (RTU).

Testing was performed in accordance with ASTM Specification E185-82 [Reference 10] and Westinghouse Procedure RMF 8402, Revision 3 [Reference 11 ].

The capsule was opened upon receipt at the hot cell laboratory per Procedure RTU 5004 [Reference 12].

The specimens and spacer blocks were carefully removed, inspected for identification number, and checked against the master list in CENPD-48 [Reference 5]. All items were in their proper locations.

Examination of the thermal monitors indicated that six of the twelve thermal monitors had melted. Based on this examination, the maximum temperature to which the specimens were exposed was less than 580°F (304'C), but greater than 558°F (292°C).

The Charpy impact tests were performed per ASTM Specification E23-07a [Reference 13] and Procedure RMF 8103, Revision 2 [Reference 14] on a Tinius-Olsen Model 74, 358J machine. The tup (striker) of the Charpy machine is instrumented with an Instron Impulse instrumentation system, feeding information into a computer. The Instron Impulse system has not been calibrated to ASTM Standard E2298-09

[Reference 15], so the instrumented energy, load, time and stress data are considered for information only in Tables 5-5 through 5-8. With this system, load-time and energy-time signals can be recorded in addition to the standard dial measurement of Charpy energy. The load signal data acquisition rate was 819 kHz with data acquired for 10 ms. From the load-time curve, the load of general yielding (F.), the time to general yielding, the maximum load (Fm) and the time to maximum load can be determined.

Under some test conditions, a sharp drop in load indicative of fast fracture was observed. The load at which fast fracture was initiated is identified as brittle fracture load (Fbf). The termination of the fast load drop is identified as the arrest load (Fa). Fgy, Fm, Fbf, and Fa were determined per the guidance in ASTM Standard E2298-09. Note that some of the signals were filtered, which is not recommended by ASTM Standard E2298-09.

The energy at maximum load (Win) was determined by integrating the load-time record to the maximum load point. The energy at maximum load is approximately equivalent to the energy required to initiate a crack in the specimen. Therefore, the propagation energy for the crack (Wp) is the difference between the total energy to fracture (W,) and the energy at maximum load (Wm).

The yield stress (ay) was calculated from the three-point bend formula having the following expression [Reference 16]:

o-r = FGYr L (Eqn. 5-1)

B(W - a)' C WCAP- 17501-NP February 2012 Revision 0

5-2 Westinghouse Non-Proprietary Class 3 where L = distance between the specimen supports in the impact testing machine; B = the width of the specimen measured parallel to the notch; W = height of the specimen, measured perpendicularly to the notch; a = notch depth. The constant C is dependent on the notch flank angle ((p), notch root radius (p) and the type of loading (i.e., pure bending or three-point bending). In three-point bending, for a Charpy specimen in which T) = 450 and p = 0.010 in., Equation 5-1 is valid with C = 1.21.

Therefore, (for L = 4W),

L 3.305 F yW Cry = FGY B(W - a) 2 1.21 = B(W - a) 2 (Eqn. 5-2)

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

oY = 3 3 . 3 FGy (Eqn. 5-3) where ay is in units of psi and FGY is in units of lb. The flow stress was calculated from the average of the yield and maximum loads, also using the three-point bend formula.

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

A = B(W-a) = 0.1241sq. in. (Eqn. 5-4)

Percent shear was determined from post-fracture photographs using the ratio-of-areas methods in compliance with ASTM E23-07a [Reference 13] and A370-09 [Reference 17]. The lateral expansion was measured using a dial gage rig similar to that shown in the same specifications.

Tensile tests were performed on a 250 KN Instron screw driven tensile machine (Model 5985) per Procedure RTU 5016 [Reference 18]. The tensile testing met ASTM Specifications E8-09 [Reference 19]

and E21-09 [Reference 20] except for a minor deviation that does not have any significant effect on the results provided in this report.

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

The extensometer gage length was 1.00 inch. Elevated test temperatures were obtained with a three-zone electric resistance split-tube furnace with a 9-inch hot zone. All tests were conducted in air.

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

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Westinghouse Non-Proprietary Class 3 5-3 5.2 CHARPY V-NOTCH IMPACT TEST RESULTS The results of the Charpy V-notch impact tests performed on the various materials contained in Capsule 104', which received a fluence of 2.44 x 10' 9 n/cm 2 (E > 1.0 MeV) in 27.13 EFPY of operation, are presented in Tables 5-1 through 5-8 and are compared with the unirradiated and previously withdrawn capsule results as shown in Figures 5-1 through 5-3 and 5-7 through 5-15. The unirradiated and previously withdrawn capsule results were taken from TR-ESS-001 [Reference 4], SwRI-06-7524

[Reference 21], and BAW-2199 [Reference 22]. The previous capsules, along with the original program unirradiated material input data, were updated using CVGRAPH, Version 5.3 from the hand-drawn plots presented in these earlier reports. This accounts for the differences in measured values of 30 ft-lb and 50 ft-lb transition temperature between the results documented in this report and those shown in the previous Calvert Cliffs Unit 2 capsule reports.

The transition temperature increases and changes in upper-shelf energies for the Capsule 1040 materials are summarized in Table 5-9 and led to the following results:

• Irradiation of the reactor vessel Lower Shell Plate D-8907-2 Charpy specimens, oriented with the longitudinal axis of the specimen parallel to the major working direction (longitudinal orientation),

resulted in an irradiated 30 ft-lb transition temperature of 146.9'F and an irradiated 50 ft-lb transition temperature of 179.7°F. This results in a 30 ft-lb transition temperature increase of 135.6°F and a 50 ft-lb transition temperature increase of 143.6°F for the longitudinally oriented specimens.

• Irradiation of the Surveillance Program Weld Metal (Heat # 10137) Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 16.0'F and an irradiated 50 ft-lb transition temperature of 27.4'F. This results in a 30 ft-lb transition temperature increase of 69.7°F and a 50 ft-lb transition temperature increase of 58.2'F.

• Irradiation of the Heat-Affected-Zone (HAZ) Material Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 40.40 F and an irradiated 50 ft-lb transition temperature of 112.9'F.

This results in a 30 ft-lb transition temperature increase of 105.4'F and a 50 ft-lb transition temperature increase of 123.6°F.

" Irradiation of the reactor vessel Standard Reference Material (SRM) HSST 01 Charpy specimens, resulted in an irradiated 30 ft-lb transition temperature of 190.5°F and an irradiated 50 ft-lb transition temperature of 217.9°F. This results in a 30 ft-lb transition temperature increase of 165.5°F and a 50 ft-lb transition temperature increase of 163.7'F.

" The average upper-shelf energy of Lower Shell Plate D-8907-2 (longitudinal orientation) resulted in an average energy decrease of 33.9 ft-lb after irradiation. This results in an irradiated average upper-shelf energy of 107.7 ft-lb for the longitudinally oriented specimens.

• The average upper-shelf energy of the Surveillance Program Weld Metal Charpy specimens resulted in an average energy decrease of 28.6 ft-lb after irradiation. This results in an irradiated average upper-shelf energy of 110.3 ft-lb for the weld metal specimens.

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5-4 Westinghouse Non-Proprietary Class 3

• The average upper-shelf energy of the HAZ Material Charpy specimens resulted in an average energy decrease of 33.7 ft-lb after irradiation. This results in an irradiated average upper-shelf energy of 94.0 ft-lb for the HAZ Material.

• The average upper-shelf energy of the SRM HSST 01 Charpy specimens resulted in an average energy decrease of 49.2 ft-lb after irradiation. This results in an irradiated average upper-shelf energy of 92.3 ft-lb.

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

Lower Shell Plate D-8907-2 Charpy specimens, oriented with the longitudinal axis of the specimen perpendicular to the major working direction (transverse orientation), were not included in the Calvert Cliffs Capsule 1040. However, the transversely orientated unirradiated and previously withdrawn capsule results for the Lower Shell Plate D-8907-2 Charpy specimens were reanalyzed in this report. The transverse orientation Lower Shell Plate D-8907-2 was contained in Capsule 970, which was irradiated to a neutron fluence of 1.95 x 1019 n/cm2 (E > 1.0 MeV).

The results of the transverse orientation Lower Shell Plate D-8907-2 reanalysis will be included in Table 5-10 and shown in Figures 5-4 through 5-6.

" Irradiation of the Lower Shell Plate D-8907-2 Charpy specimens, oriented with the longitudinal axis of the specimen perpendicular to the major working direction (transverse orientation), resulted in an irradiated 30 ft-lb transition temperature of 137.57F and an irradiated 50 ft-lb transition temperature of 179.07F. This results in a 30 ft-lb transition temperature increase of 102.6°F and a 50 ft-lb transition temperature increase of 1 12.7°F.

" The average upper-shelf energy of the Lower Shell Plate D-8907-2 (transverse orientation)

Charpy specimens resulted in an average energy decrease of 27.7 ft-lb after irradiation. This results in an irradiated average upper-shelf energy of 86.7 ft-lb for the transversely oriented specimens.

The fracture appearance of each irradiated Charpy specimen from the various materials is shown in Figures 5-16 through 5-19. The fractures show an increasingly ductile or tougher appearance with increasing test temperature. Load-time records for the individual instrumented Charpy specimens are contained in Appendix B.

All beltline materials exhibit a more than adequate upper-shelf energy level for continued safe plant operation and are predicted to maintain an upper-shelf energy greater than 50 ft-lb throughout the end of the current license (32 EFPY) and license extension (52 EFPY) as required by 10 CFR 50, Appendix G

[Reference 2]. This evaluation can be found in Appendix E.

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Westinghouse Non-Proprietary Class 3 5-5 5.3 TENSILE TEST RESULTS The results of the tensile tests performed on the various materials contained in Capsule 1040 irradiated to 2.44 x 1019 n/cm 2 (E > 1.0 MeV) are presented in Table 5-11 and are compared with unirradiated results as shown in Figures 5-20 through 5-22.

The results of the tensile tests performed on the Lower Shell Plate D-8907-2 (longitudinal orientation) indicated that irradiation to 2.44 x 109rn/cm 2 (E > 1.0 MeV) caused increases in the 0.2 percent offset yield strength and the ultimate tensile strength when compared to unirradiated data [Reference 4]. See Figure 5-20 and Table 5-11.

The results of the tensile tests performed on the surveillance weld metal indicated that irradiation to 2.44 x 1019 n/cm 2 (E > 1.0 MeV) caused increases in the 0.2 percent offset yield strength and the ultimate tensile strength when compared to unirradiated data [Reference 4]. See Figure 5-21 and Table 5-11.

The results of the tensile tests performed on the Heat-Affected-Zone material indicated that irradiation to 2.44 x 1019 n/cm 2 (E > 1.0 MeV) caused increases in the 0.2 percent offset yield strength and the ultimate tensile strength when compared to unirradiated data [Reference 4]. See Figure 5-22 and Table 5-11.

The fractured tensile specimens for the Lower Shell Plate D-8907-2 material are shown in Figure 5-23, the fractured tensile specimens for the surveillance weld metal are shown in Figure 5-24 and the fractured tensile specimens for the HAZ material are shown in Figure 5-25. The engineering stress-strain curves for the tensile tests are shown in Figures 5-26 through 5-28 for Lower Shell Plate D-8907-2, Figures 5-29 through 5-31 for the surveillance weld metal, and Figures 5-32 through 5-34 for the HAZ material.

WCAP-1750 1-NP February 2012 Revision 0

5-6 Westinghouse Non-Proprietary Class 3 Table 5-1 Charpy V-Notch Data for the Calvert Cliffs Unit 2 Lower Shell Plate D-8907-2 Irradiated to a Fluence of 2.44 x 1019 n/cm 2 (E > 1.0 MeV) (Longitudinal Orientation)

,SampleTemjerature Impact Energy .LaterailExpansion :Shear Number 'OF ft-lbs Noules mils mm 15P 0 -18 4 5 8 0.20 0 IlY 75 24 22 30 25 0.64 10 13B 125 52 26 35 27 0.69 20 IlK 150 66 28 38 28 0.71 30 12M 155 68 31 42 35 0.89 40 122 165 74 37 50 35 0.89 30 123 175 79 45 61 44 1.12 50 15U 190 88 51 69 47 1.20 55 15M 210 99 82 111 69 1.76 75 142 325 163 92 125 74 1.88 100 12C 340 171 108 146 82 2.09 100 162 350 177 123 167 81 2.06 100 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 5-7 Table 5-2 Charpy V-Notch Data for the Calvert Cliffs Unit 2 Surveillance Weld Metal (Heat # 10137) Irradiated to a Fluence of 2.44 x 10'9 n/cm 2 (E > 1.0 MeV)

SampleTemperature Impact Energy ~ Lateral Expansion . Shear~

0 Number 0C1 ft-lbs. Joules mils m%'

mm 341 0 -18 9 12 15 0.38 15 316 15 -9 11 15 13 0.33 20 313 20 -7 86 117 62 1.58 60 34D 25 -4 42 57 43 1.09 50 32P 30 -1 25 34 27 0.69 50 31K 50 10 105 142 83 2.11 70 32T 60 16 63 85 55 1.40 75 31E 75 24 165 224 96 2.44 90 35L 150 66 91 123 81 2.06 100 343 225 107 97 132 81 2.06 100 31J 250 121 136 184 92 2.34 100 31M 275 135 117 159 93 2.37 100 WCAP-17501-NP February 2012 Revision 0

5-8 Westinghouse Non-Proprietary Class 3 Table 5-3 Charpy V-Notch Data for the Calvert Cliffs Unit 2 Heat-Affected-Zone (HAZ)

Material Irradiated to a Fluence of 2.44 x 1019 n/cm 2 (E > 1.0 MeV)

Sample Temperature Impact Energy Lateral Expansionf Shear Number OF "C ft-lbs Joules mils mm 44T -75 -59 15 20 11 0.28 10 43D -25 -32 12 16 14 0.36 20 45D -15 -26 10 14 8 0.20 25 44A 0 -18 35 47 32 0.81 30 453 20 -7 20 27 21 0.53 30 43B 40 4 17 23 20 0.51 25 45C 50 10 17 23 17 0.43 30 43C 75 24 73 99 59 1.50 70 42M 250 121 61 83 60 1.53 90 462 275 135 70 95 63 1.60 100 434 300 149 85 115 73 1.86 100 44B 325 163 127 172 78 1.98 100 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 5-9 Table 5-4 Charpy V-Notch Data for the Calvert Cliffs Unit 2 Standard Reference Material (SRM) HSST 01 Irradiated to a Fluence of 2.44 x 1019 n/em 2 (E > 1.0 MeV)

SapeTemperature Impact Energy Lateral Expansion Shear Number fo mils mm%

67M 75 24 4.5 6 11 0.28 10 66B 150 66 21 28 24 0.61 20 67D 175 79 28 38 26 0.66 30 67J 190 88 22 30 28 0.71 40 66J 200 93 26 35 27 0.69 40 66L 210 99 47 64 41 1.04 50 67B 220 104 52 71 45 1.14 50 67E 225 107 56 76 48 1.22 60 66E 235 113 67 91 55 1.40 75 66P 325 163 95 129 75 1.91 100 66K 350 177 89 121 70 1.78 100 67C 375 191 93 126 80 2.04 100 WCAP- 17501 -NP February 2012 Revision 0

5-10 Westinghouse Non-Proprietary Class 3 Table 5-5 Instrumented Charpy Impact Test Results for the Calvert Cliffs Unit 2 Lower Shell Plate D-8907-2 Irradiated to a Fluence of 2.44 x 1019 n/cm 2 (E > 1.0 MeV) (Longitudinal Orientation)

Normalized. Energies General:

le Test Tem (ft-lb/in) Yield .Time to Max. Time to Fract. Arrest Yieldl- Flow..

No Temp. Load, F, Load, F. Load, Load, Stress Stress F) ft Total At F,, Prop. Fvy (msec) Fý (lb) (i(s-) F( FI) si)- (ki)

(ftlb W/A Wi/A ~W,/A (Ib) 15P 0 3.9 31 26 6 2310 0.05 3890 0.09 3890 NA 77 103 llY 75 19.4 156 160 -3 3130 0.05 3820 0.38 3820 NA 104 116 13B 125 24.3 196 145 51 2570 0.05 3800 0.35 3500 490 86 106 11K 150 26.0 210 135 74 2540 0.05 3615 0.35 3260 1200 85 102 12M 155 29.2 235 173 62 2640 0.05 3630 0.43 3530 800 88 104 122 165 34.8 280 204 77 2520 0.05 3700 0.50 3500 1210 84 104 123 175 42.3 341 259 82 2760 0.05 3780 0.63 3680 1270 92 109 15U 190 47.0 379 251 127 2670 0.05 3810 0.60 3680 1280 89 108 15M 210 73.3 591 246 345 2540 0.05 3740 0.60 3440 1940 85 105 142 325 83.4 672 240 432 2690 0.05 3650 0.60 NA NA 90 106 12C 340 98.4 793 243 550 2770 0.05 3690 0.60 NA NA 92 108 162 350 111.1 895 245 650 2300 0.05 3770 0.61 NA NA 77 101 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 5-11 Table 5-6 Instrumented Charpy Impact Test Results for the Calvert Cliffs Unit 2 Surveillance Weld Metal (Heat # 10137)

Irradiated to a Fluence of 2.44 x 1019 n/cm 2 (E > 1.0 MeV)

Normalized Energies General S p Test, Charp. (ft-lb/in 2) Yield Time to Max. Time to Fract. Arrest Yield - Flow N. Temp..Ttl A Load,, F, Load, Fni Load,;, Load, Stress Stress (OF) Prp F, (msec) F. (lb) (msie~c) FLb (b)j F,, (b) (Kksi)' (ksi)

(ft-lb) W/A W/A W/ (b)________________

341 0 9.7 78 35 43 3270 0.08 4240 0.12 4240 NA 109 125 316 15 11.7 94 27 68 2500 0.05 3960 0.09 3330 500 83 108 313 20 78.5 633 226 406 2600 0.05 3390 0.60 2910 1660 87 100 34D 25 38.2 308 226 82 3100 0.05 3920 0.50 3650 1120 103 117 32P 30 23.0 185 122 63 2810 0.05 3820 0.29 3770 1100 94 110 31K 50 94.4 761 304 457 2740 0.05 3540 0.77 2570 1700 91 105 32T 60 56.8 458 275 183 3150 0.06 3790 0.62 3470 2060 105 116 31E 75 151.4 1220 322 898 2050 0.05 3700 0.79 NA NA 68 96 35L 150 82.3 663 249 414 2730 0.05 3640 0.60 NA NA 91 106 343 225 87.6 706 245 461 2600 0.05 3630 0.60 NA NA 87 104 31J 250 123.6 996 341 655 2630 0.05 3250 0.95 NA NA 88 98 31M 275 105.7 852 247 604 2200 0.05 3650 0.63 NA NA 73 97 WCAP-1750 1-NP February 2012 Revision 0

5-12 Westinghouse Non-Proprietary Class 3 Table 5-7 Instrumented Charpy Impact Test Results for the Calvert Cliffs Unit 2 Heat-Affected-Zone (HAZ) Material Irradiated to a Fluence of 2.44 x 1019 n/cm 2 (E > 1.0 MeV)

Normalized'Energies: ,General Test Charpy (ft-lb/in)) Yield Time to Max. Time to Fract. Arrest .::.Yield Flow.

-Sample Te Energ, Lod" -Lad

': Stress S Toa AtF3/4(Temp. , Load, F, Load, F Load, Load, Stress 44T -75 13.2 106 26 81 2530 0.05 4350 0.09 3840 NA 84 115 43D -25 11.8 95 24 71 2560 0.05 4070 0.09 3130 450 85 110 45D -15 9.8 79 35 44 1890 0.05 4180 0.11 3280 500 63 101 44A 0 31.9 257 35 222 2970 0.07 4130 0.11 3890 840 99 118 453 20 19.7 159 110 48 2550 0.05 3830 0.26 3660 490 85 106 43B 40 17.2 139 96 43 1900 0.05 3430 0.26 3370 NA 63 89 45C 50 16.0 129 93 36 2620 0.05 3660 0.24 3470 410 87 105 43C 75 64.9 523 259 264 2740 0.05 3900 0.60 3570 2570 91 111 42M 250 54.1 436 184 252 2180 0.05 3410 0.48 NA NA 73 93 462 275 62.7 505 119 386 2300 0.05 3600 0.31 NA NA 77 98 434 300 78.4 632 229 403 2060 0.05 3500 0.61 NA NA 69 93 44B 325 116.8 941 255 686 1740 0.05 3830 0.63 NA NA 58 93 WCAP- 17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 5-13 Table 5-8 Instrumented Charpy Impact Test Results for the Calvert Cliffs Unit 2 Standard Reference Material (SRM)

HSST 01 Irradiated to a Fluence of 2.44 x 1019 n/cm 2 (E > 1.0 MeV)

TesChrpy Normalized Energies, ýGeneral Sample Energy, ____' (ft-lb/in) , Yield Time to Max:. ':' Time to Fract. eArrest Yieldl VFlow No. lTemnp. Total A Load, 'F, Load,' I' F. lLoad, Load, Stress 'Stress $

( F I Total At FM. Prop. F, (msec). Fm (lb)' .(msec)', Fbf (lb F( (ksi) (ksi) j.

W1IAb, :Win/A ~WýA (b)_________

67M 75 4.0 32 12 20 3100 0.05 3450 0.06 3450 NA 103 109 66B 150 20.3 164 115 48 2760 0.05 3560 0.29 3560 250 92 105 67D 175 26.6 214 180 34 2770 0.05 3820 0.43 3740 570 92 110 67J 190 19.0 153 118 35 2300 0.05 3570 0.26 3440 490 77 98 66J 200 23.5 189 140 49 2480 0.05 3700 0.36 3560 950 83 103 66L 210 43.0 346 210 136 2300 0.05 3890 0.50 3700 1930 77 103 67B 220 47.8 385 216 169 3200 0.05 3890 0.50 3660 2170 107 118 67E 225 48.7 392 257 135 2360 0.05 3780 0.48 3720 2000 79 102 66E 235 60.7 489 259 230 2900 0.05 3900 0.60 3530 2580 97 113 66P 325 85.9 692 246 446 3140 0.05 3730 0.60 NA NA 105 114 66K 350 79.8 643 247 396 2200 0.05 3680 0.61 NA NA 73 98 67C 375 84.5 681 251 430 2780 0.05 3750 0.60 NA NA 93 109 WCAP-17501-NP February 2012 Revision 0

5-14 4Westinouse Non-P. rietarv Class 3 Table 5-9 Effect of Irradiation to 2.44 x 1019 n/cm2 (E > 1.0 MeV) on the Charpy V-Notch Toughness Properties of the Calvert Cliffs Unit 2 Reactor Vessel Surveillance Capsule 1040 Materials

.Average30 ft-lb Transitio Average 35 mil Lateral Expansion Average 50 ft-lb Transition Average Energy Absorption at Full Material Tmertre(F Temperature~a (F Temperature(OF) 2Shear") (ft-..

. Unirradiated Irradiated ,'AT* Unirradiated Irradiated AT *Unirradiated Irradiated; iAT Unirradiated& Irradiated AE Lower Late Shell Shell 11.3 146.9 135.6 21.4 148.1 126.7 36.1 179.7 143.6 Plate D-8907-2 141.6 107.7 -33.9 (LT)

Surveillance Program Weld -53.7 16.0 69.7 -41.0 20.7 61.7 -30.8 27.4 58.2 138.9 110.3 -28.6 Metal (Heat # 10137)

HAZ Material -65.0 40.4 105.4 -43.3 59.6 102.9 -10.7 112.9 123.6 127.7 94.0 -33.7 SRM 25.0 190.5 165.5 42.0 197.1 155.1 54.2 217.9 163.7 141.5 92.3 -49.2 Note:

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

I-NP February 2012 WCAP-1750 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 5-15 Table 5-10 Comparison of the Calvert Cliffs Unit 2 Surveillance Material 30 ft-lb Transition Temperature Shifts and Upper-Shelf Energy Decreases with Regulatory Guide 1.99, Revision 2, Predictions

~psu~eluence30 ft-lb TransitionUE Materialsul Fluensule Decrease USE________

YPredicteds <Mea~sured(" rdcedI Masrd~

E>1.0 MeV)  :(OF). (___F)_ (%) ___%)__

2630 0.825 96.0 86.4 23 19 Lower Shell Plate D-8907-2 970 1.95 120.0 111.6 28 24 (Longitudinal) 1040 : 125.9 135 6 3 24 Lower Shell Plate D-8907-2 970 1.95 120.0 102.6 28 24 (Transverse) 2630 0.825 91.6 72.7 38 24 Surveillance Program Weld Metal 970 1.95 14.5 82.9 46 30 (Heat# 10137) ,

S1040 2.44 120.0 69,7 48 21 2630 0.825 --- 130.6 --- 18 Heat-Affected-Zone Material 970 1.95 - - -136 104' .2.44:,. ..

3. 1054 26 2630 0.825 125.6 36 Standard Reference Material 1044

2. 44 4'4 ~4-

"465.5 Notes:

(a) Capsule 1040 (highlighted) is the latest capsule to be withdrawn and tested from the Calvert Cliffs Unit 2 reactor vessel.

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

(c) Calculated by CVGraph Version 5.3 using measured Charpy data (See Appendix C).

WCAP-17501-NP February 2012 Revision 0

5-16 Westinehouse Non-PrODrietarv Class 3 Table 5-11 Tensile Properties of the Calvert Cliffs Unit 2 Capsule 1040 Reactor Vessel Surveillance Materials Irradiated to 2.44 x 1019 n/cm 2 (E > 1.0 MeV)

ý0.2%:

Sa Test Ultimate Fracture Fracture - Fracture Uniform Total>. Reduction Material Tem Yild Strength Load Stress Strength Elongation 'Elongation in Area Nmber Strength (ksi) 1KP 175 79.2 99.2 3.3 68 208 10.3 22 67 Lower Shell Plate D-8907-2 1K2 250 75.2 96.8 3.2 65 207 11.0 23 69 (Longitudinal) IKE 550 73.5 94.3 3.3 66 177 10.9 23 63 Surveillance 3JP 75 87.4 99.5 3.6 73 172 7.4 22(a) 57 Program Weld 3K4 150 81.8 94.4 3.0 60 209 10.8 25 71 Metal (Heat# 10137) 3L4 550 78.5 93.2 3.1 64 172 9.8 24 63 4JE 75 82.7 96.9 3.0 62 197 9.2 22 69 Heat-Affected-Zone 4JM 150 81.1 94.3 3.0 61 204 7.8 26(a) 70 Material 4K4 550 73.8 91.5 3.4 70 104 8.4 20(a) 33 Note:

(a) The extensometer slipped during testing after the ultimate strength was reached, therefore the elongation at fracture could not be taken from extensometer output. The distance between extensometer indentation marks was measured after placing the fracture surfaces together in order to calculate the elongation at fracture.

February 2012 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 5-17 Figure 5-1 Charpy V-Notch Impact Energy vs. Temperature for Calvert Cliffs Unit 2 Reactor Vessel Lower Shell Plate D-8907-2 (Longitudinal Orientation)

LS PLATE D-8907-2 (LONGITUIDINAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on I 1/03/201 107:1 1 AM Data Set(s) Plotted Cm nre Plant Capsule Material Ori. Heat #

Calvert Cliffs 2 UNIRR SA533BI LT C-5286-1 2 Calvert Cliffs 2 263 SA533B I LT C-5286-1 3 Calvert Cliffs 2 97 SA533B1 LT C-5286- I 4 Calvert Cliffs 2 104 SA533B1 LT C-5286- I 300 250 T 200 0

I.

150

'LI 100 50 0

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F 0 1 a 2 4 4>3 Results Cutrve Fluence S-SE USE d-USE, T @30 d-r @30 T @510 d.T @50 2.2 141.6 .0 11.3 .0 36. 1 ,.C 2 2.2 114.7 -26.9 97. 7 86.4 132.7 96. 6.

3 2. 2 108.0 -33.6 122.9 111.6 158. 1 122.0 4 2.2 107. 7 -33.9 146. 9 135.6 179. 7 143.6.

WCAP-17501-NP February 2012 Revision 0

5-18 Westinghouse Non-Proprietary Class 3 Figure 5-2 Charpy V-Notch Lateral Expansion vs. Temperature for Calvert Cliffs Unit 2 Reactor Vessel Lower Shell Plate D-8907-2 (Longitudinal Orientation)

LS PLATE D-8907-2 tL()NG.ITUDINAI..)

CVGRAPH 5,3 Hyperbolic Tangent Curve Printed on I 1/08/2011 07:15 AM Data Set(s) Plotted Curve Plant Capsule kI\'lterial Ori. Heat #

2 Calvert Cliffs 2 UNIRR SA533BI1 LT C-5286-1 Calvert Cliffs 2 263 SA533BI1 LT C-5286-1 3 Calvert Cliffs 2 97 SA533B1 LT C-5286- I 4 Calvert Cliffs 2 104 SA533B I LT C-5286-1 M

C

.2 0r ...

-300.0 0.0 300.0 600.0 Temperature in Deg F 0o1 2 >3 >4 Results Curme Filuence LSE USE d-USE T @35 d-T @35 1.0 92.6 .0 21.4 .0 2 1.0 97.0 4. 3 104. 7 83,3 3 1.0 87. 2 -5.4 137. 6 116.2 4 1.0 86. I -6.5 148. 1 126.7 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 5-19 Figure 5-3 Charpy V-Notch Percent Shear vs. Temperature for Calvert Cliffs Unit 2 Reactor Vessel Lower Shell Plate D-8907-2 (Longitudinal Orientation)

LS PLATE I)-8907-2 (LONGITDI. NAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 11/08/2011 07:50 AM Data Set(s) Plotted Cur-ve Plant Capsule Material Orn. Heat #

1 Calvert Cliffs 2 UNIRR SA533B1 LT C-5286- I 2 Calvert Cliffs 2 263 SA533B I LT C-5286- I 3 Calvert Cliffs 2 97 SA533B 1 LT C-5286-1 4 Calvert Cliffs 2 104 SA533B1 LT C-5286-1 125 100 75 U) 50 25 0 4-

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F 0 1 2 03 4 Res,ults (7iirve 1ti~ence LSE USE dI.USE T C.450 d-'r (A50

.0 100.0 .0 69. I .0

.0 100. 0 .0 169. 1 100.0 3 .0 100.0 .0 170. 0 100.9 4 .0 1W00. ,0 178.8 109. 7 WCAP-17501-NP February 2012 Revision 0

5-20 Westinahouse Non-ProDrietarv Class 3 Figure 5-4 Charpy V-Notch Impact Energy vs. Temperature for Calvert Cliffs Unit 2 Reactor Vessel Lower Shell Plate D-8907-2 (Transverse Orientation)

LS PLATE D-8907-2 (TRANSVERSE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 11/08/2011 07:52 AM Data Set(s) Plotted Curvre Plant Capsule Material Oi. Heat #

2 Calvert Cliffs 2 LINIRR SA533B I TL C-5286-1 Calvert Cliffs 2 97 SA533B I TL C-5286- I 300 250 200 150 LU1 8100

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F 0 1 a 2 Resualts Curve Fluence LSE USE d-USE T @30 d-T @30 T @50 d-T1 @50 1 2. 2 114.4 .0 34.9 .0 66. 3 .0 2 2. 2 86.7 -27.7 137. 5 102.6 179. 0 112.7 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 5-21 Figure 5-5 Charpy V-Notch Lateral Expansion vs. Temperature for Calvert Cliffs Unit 2 Reactor Vessel Lower Shell Plate D-8907-2 (Transverse Orientation)

LS PLATE D-8907-2 (TRANSVERSE)

CVGRAPH 5.3 Hyperbtlic Tangent Curve Printed on 11/08/2011 08:09 AM Data Set(s) Plotted Curve Plant Capsule Material Onl. Heat #

Calvert Cliffs 2 UNIRR SA533B1 Th C-5286-1 2 Calvert Cliffs 2 97 SA533B I TL C-5286-1 200 150 E

C

.2

• .100 50 0 lý

-300.0 0.0 300.0 600.0 Temperature in Deg F 0 1 Resultls Curve Fluente LSE USE d-USE T @35 d-T @35 1.0 90.4 .0 44.7 .0 1.0 79,9 -10.6 147, 6 102. 9 WCAP-17501-NP February 2012 Revision 0

5-22 Westin2house Non-Pronrietarv Class 3 Figure 5-6 Charpy V-Notch Percent Shear vs. Temperature for Calvert Cliffs Unit 2 Reactor Vessel Lower Shell Plate D-8907-2 (Transverse Orientation)

[S PLATE D-8907-2 (TRANSVERSE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 11/08/2011 08:10 AM Data Set(s) Plotted Curve Plant Capsule N-laterhil Or. Heat #

Calvert Cliffis 2 UNIRR SA533B31 TL C-5286-1 Calvert Cliffs 2 97 SA533BI TL C-5286-1 125 100 75 2

a!

50 25 0$

0 0

-300.0 -100.0 0.0 100.0 200.0 300.0 400.0

-200.0 500.0 600.0 Temperature In Deg F 0 1 0 2 Results Curve 1Iluence LSE USE d-USE T 4i@50 fl-I @~~50

.0 100.0 .0 98, 5 .0

.0 100.0 .0 180.8 82. 3 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 5-23 Figure 5-7 Charpy V-Notch Impact Energy vs. Temperature for the Calvert Cliffs Unit 2 Reactor Vessel Surveillance Program Weld Metal SURVEILLANCE WELD METAL CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 11/08/2011 08:13 AM Data Set(s) Plotted Curve Plant Capsule Material Or. Heat #

2 Calvert Cliffs 2 UNIRR SAW NA 10137 Calvert Cliffs 2 263 SAW NA 10.137 3 Calvert Cliffs 2 97 SAW NA 10137 4 Calvert Cliffs 2 104 SAW NA 10137 300 0

LL.

z 8

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F 01 02 03 4 Results Curvt- Fluencie ISE USE I-USE T 1.30 (d-T(@30 T 0, 50 d-T (0>50 2.2 138.9 .0 -53. 7 .0 -30. 8 .0

2. 2 105. 3 -33, 6 19.0 72. 7 39. 9 70. 7 3 2. 2 97. 3 -41.6 29. 2 82.9 60. 6 91.4 4 2. 2 110.3 -28.6 16.0 69.7 27. 4 58.2 WCAP-17501-NP February 2012 Revision 0

5-24 Westin2house Non-Proorietarv Class 3 Figure 5-8 Charpy V-Notch Lateral Expansion vs. Temperature for the Calvert Cliffs Unit 2 Reactor Vessel Surveillance Program Weld Metal SUJRVEILLANCE AVELD METAL CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 11/08/2011 08:16 AM Data Set(s) Plotted Curve Plant . Capsule Material Ori. Heat #

1 Calvert Cliffs 2 UNIRR SAW NA 10137 2 Calvert Cliffs 2 263 SAW NA 10137 3 Calvert Cliffs 2 97 SAW NA 10137 4 Calvert Cliffs 2 104 SAW NA 10137 200 150 E

a 100 so 0 *=

-300.0 0.0 300.0 600.0 Temperature In Deg F 0 1 2 03 4 Results Curve FIuen'e I.SE USE d-USE T 435 d-T (035 1 1.0 93.5 .0 -41.0 .0 2 1.0 89. 2 -4.2 25. 2 66. 2 3 1.0 83.0 -10.5 44. 7 85. 7 4 1.0 87. 8 -5,7 20. 7 61.7 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 5-25 Figure 5-9 Charpy V-Notch Percent Shear vs. Temperature for the Calvert Cliffs Unit 2 Reactor Vessel Surveillance Program Weld Metal SURVEILLANCE WELD METAL CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 11/08/2011 08:18 AM Data Set(s) Plotted Curve Plant Capsule Mvlaterial Ori.

Calvert Cliffs 2 UN]RR SAW NA 10137 2 Calvert Cliffs 2 263 SAW NA 10137 3 Calvert Cliffs 2 97 SAW NA 10137 4 Calvert Cliffs 2 104 SAW NA 10137 125 100 ci,

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F 0 1 02

<3 4 Curve Fluence LSE USE d-USE T Q50 d-T 04,50

.0 100.0 .0 -12.9 ,0 2 .0 100,0 .0 58. 5 71.4 3 .0 100,0 .0 4&8.8 61.7 4 .0 100.0 .0 29. 0 41.9 WCAP-17501-NP February 2012 Revision 0

5-26 Westinahouse Non-Pronrietarv Class 3 Figure 5-10 Charpy V-Notch Impact Energy vs. Temperature for the Calvert Cliffs Unit 2 Reactor Vessel Heat-Affected-Zone Material HEAT AFFECTED ZONE CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 11/08/20111 08:21 AM Data Set(s) Plotted Plant Capsule Material Orl. Heat #

2 Calvert Cliffs 2 UNIRR SA533B1 NA C-5286-1 Calvert Cliffs 2 263 SA533BI NA C-5286-I 3 Calvert Cliffs 2 97 SA533B1 NA C-5286-1 4 Calvert Cliffs 2 104 SA533B1 NA C-5286-1 300-250-

-r 200o

=15 0

U.

150-z 100-50-0

-300.0 -200 .0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F 0 1 a2 03 4 Curve Fluence LSE USE d-USE TQ@30 d-T @30 T @(150 d-T @50 1 2.2 127.7 .0 -65.0 .0 -10.7 .0 2 2. 2 104.5 -23.2 65, 6 130.6 121.2 131.9 3 2.2 81.4 -46. 3 56. 2 121.2 104.3 115.0 4 2- 2 94.0 -33.7 40. 4 105.4 112.9 123.6 WCAP- 17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 5-27 Figure 5-11 Charpy V-Notch Lateral Expansion vs. Temperature for the Calvert Cliffs Unit 2 Reactor Vessel Heat-Affected-Zone Material HEAT AFFECTED ZONE CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 11/08/2011 08:23 AM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat #

1 Calvert Cliffs 2 UNIRR SA533B1 NA C-5286-1 2 Calvert Cliffs 2 263 SA533B 1 NA C-5286-1 3 Calvert Cliffs 2 97 SA533B1 NA C-5286-1 4 Calvert Cliffs 2 104 SA533BI NA C-5286-1 200 150 E

.2 8.100 50 0 J

-300.0 0.0 300.0 600.0 Temperature In Deg F 0 1 02 03 4 Resulls Curve Fluence LSE USE d-USE T @35 d-T @35 1.0 82.8 .0 -43.3 .0 2 1.0 125. I 42.3 87. 8 131. 1 3 1.0 86. 5 3.8 83,0 126. 3 4 1.0 70, 5 -12,3 59. 6 102. 9 WCAP- 17501-NP February 2012 Revision 0

5-28 Westinehouse Non-ProDrietarv Class 3 Figure 5-12 Charpy V-Notch Percent Shear vs. Temperature for the Calvert Cliffs Unit 2 Reactor Vessel Heat-Affected-Zone Material HEAT AFFECTED ZONE CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 11/08/2011 08:24 AM Data Set(s) Plotted Curm Plant Capsule Material Ori. fleat #

2 Calvert Cliffs 2 UNIRR SA533BI NA C-528(i-I Calvert Cliffs 2 263 SA533BI NA C-5286-1 3 Calvert Cliffs 2 97 SA533B1 NA C-5286-1 4 Calvert Cliffs 2 104 SA533B1 NA C-5286-1 125 100 A

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F 0 1 '2 0<3 4 Results Curve Fluence LSE USE d-USE T @50 d-T @50

.0 100.0 .0 18.6 .0 2 .0 100.0 .0 123.8 105.2 3 .0 100.0 .0 74.0 55.4 4 .0 100.0 .0 68.5 49.9 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 5-29 Figure 5-13 Charpy V-Notch Impact Energy vs. Temperature for the Calvert Cliffs Unit 2 Reactor Vessel Standard Reference Material STANDARD REFERENCE MATERIAL CVGRAPH 5 .3 Hyperbolic Tangent Curve Printed on 1,1/08/2011 08:27 AM Data Set(s) Plotted Curve I*lr Plant Capsule Material Ori. Heat # ¢ 3 Calvert Cliffs 2 UNIRR SA533B 1 LT HSST-O1MYt alver IA5UNT:81M1 300 zoU 200 0

LL 150, 1 00 -/- -"-

0 ..

!fl f,,.

50 0

(A P

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F 0 a 2 0>3 Results Curve~ Fluence L+SE USE d-1USE T @ )30 d-T (,,30 T @50 d -T @5 0 2.2 141,5 .0 25.0 .0 54, 2 ,0

2. 2 89W9 -51.6 150,6 I 25. 6 181.0 126,8 3 2.2 92, 3 -49.2 190, 5 165,5 217. 9 163. 7 WCAP-17501-NP February 2012 Revision 0

5-30 Westinizhouse Non-Prot)rietarv Class 3 5-30 Westinghouse Non-Provrietarv Class 3 Figure 5-14 Charpy V-Notch Lateral Expansion vs. Temperature for the Calvert Cliffs Unit 2 Reactor Standard Reference Material STAND)ARD REFERENCE MNATERIAL CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 11/08/2011 08:29 AM Data Set(s) Plotted Plant Capsule M~aterial Ori. [teat #

1 Calvert Cliffs 2 UNIRR SAS33813 LLI' HSS'1-0IMY 2 Calvert Cliffs 2 263 SA533B I LT HSST-OlMY 3 Calvert Cliffs 2 104 SA533131 LT HSST-OIMY E

C 12

-300.0 0.0 300.0 600.0 Temperature in Deg F 01 a 2 Results C~urve Fluence ISE USE d1-USE T 0135 d-T' 0.35 1.0 91.1 .0 42.0 ,0 2 10 79, 9 -11.2 148&8 106, 8 3 1.0 81.3 -9.9 197. 1 155, I WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 5-31 Figure 5-15 Charpy V-Notch Percent Shear vs. Temperature for the Calvert Cliffs Unit 2 Reactor Vessel Standard Reference Material STANDARD REFERENCE MATERIAL CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 11/08/2011 08:30 AM Data Set(s) Plotted Curve Plant Capsule Material Orl. Heat # Y 1 Calvert Cliffs 2 UNIRR SA533B1 LT HSST-01M) 2 Calvert Cliffs 2 263 SA533B1 LT HSST-0IM) 3 Calvert Cliffs 2 t104 SA533B1 LT HSST-0IM) 125 100 0

75 cn

,2 50 25 0 0 0,C 0

-300,0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F 0 1 0 2 0<3 Curve Fluence LSE USE d-USE, T 05O l-Tr @ý50

-0 .0 92.9 .0 2 1'3 0 214.4 121.5 3 .0 I 0.0ý .0 208.6 115.7 WCAP-17501-NP February 2012 Revision 0

5-32 Westinehouse Non-Pronrietarv Nn Class 3 frori tar Cl....

53Wetnhous 15P,00TIY, 75-F 13B, 125-F IlK, 150-F 12M, 155°F 122, 165°F 123, 175°F 15U, 190°F 15M, 210°F 142, 325-F 12C, 340-F 162, 350-F Figure 5-16 Charpy Impact Specimen Fracture Surfaces for Calvert Cliffs Unit 2 Reactor Vessel Lower Shell Plate D-8907-2 (Longitudinal Orientation)

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Westinghouse Non-Proprietary Class 3 5-33 Westinghouse Non-Proprietary Class 3 5-33 341, 0°F 316, 15°F 313, 20-F 34D, 25-F 32P, 30°F 31K, 50-F 32T,600 F 31E, 75 0 F 35L, 150-F 343, 225°F 31J, 250-F 31M, 275°F Figure 5-17 Charpy Impact Specimen Fracture Surfaces for Calvert Cliffs Unit 2 Reactor Vessel Surveillance Program Weld Material WCAP-17501-NP February 2012 Revision 0

5-34 Westinghouse Non-Proprietary Class 3 44T, F 43D, -25°F 45D, F 44A,0OT 453, 20-F 43B, 40°F 45C, 50°F 43C, 75°F 42M, 250°F 462, 275°F 434, 300°F 44B, 325°F Figure 5-18 Charpy Impact Specimen Fracture Surfaces for the Calvert Cliffs Unit 2 Reactor Vessel Heat-Affected-Zone Material WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 5-35 67M, 75°F 66B, 150-F 67D, 175°F 67J, 190°F 66J, 200-F 66L, 210-F 67B, 220-F 67E, 225-F 66E, 235°F 66P, 3250 F 66K, 350°F 67C, 375°F Figure 5-19 Charpy Impact Specimen Fracture Surfaces for the Calvert Cliffs Unit 2 Reactor Vessel Standard Reference Material WCAP-17501-NP February 2012 Revision 0

5-36 Westinghouse Non-Proprietary Class 3 120.0 100.0 80.0 60.0 40.0 20.0 0.0 100 200 300 400 500 600 Temperature (7F)

Legend: Aand 9 and m are unirradiated A and o and o are irradiated to 2.44 x 1019 n/cm 2 (E > 1.0 MeV) 80.0 70.0 Area Reduction 60.0 50.0 40.0 30.0 Total Elongation 20.0 Uniform Elongation 10.0 0.0 0 100 200 300 400 500 600 Temperature (*F)

Figure 5-20 Tensile Properties for Calvert Cliffs Unit 2 Reactor Vessel Lower Shell Plate D-8907-2 (Longitudinal Orientation)

WCAP- 17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 5-37 120.0 100.0 Ultimate Tensile Strength 80.0 0.2% Yield Strength 60.0 40.0 20.0 0.0 0 100 200 300 400 500 600 Temperature (*F)

Legend: Aand 9 and m are unirradiated A and o and c are irradiated to 2.44 x 1019 n/cm 2 (E > 1.0 MeV) 80.0 70.0 Area Reduction 60.0 50.0 a 40.0 30.0 Toral Elongation 20.0 10.0 Uniform Elongation 0.0 0 100 200 300 400 500 600 Temperature (*F)

Figure 5-21 Tensile Properties for Calvert Cliffs Unit 2 Reactor Vessel Surveillance Program Weld Material WCAP- 17501-NP February 2012 Revision 0

5-38 Westinghouse Non-Pronrietarv Class 3 5-38 120.0 100.0 t ,,Ultimate Tensile Strength 80.0

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

Legend: Aand e and u are unirradiated A and o and o] are irradiated to 2.44 x 1019 n/cm 2 (E > 1.0 MeV) 80.0 70.0 60.0 50.0 40.0 30.0 20.0 10.0 0.0 0 100 200 300 400 500 600 Temperature (*F)

Figure 5-22 Tensile Properties for the Calvert Cliffs Unit 2 Reactor Vessel Heat-Affected-Zone Material WCAP-17501-NP February 2012 Revision 0

WestinRhouse Non-Proprietary Class 3 5-39 Wetnhos o-Poretr lss353 Specimen I KP - Tested at 175'F Specimen 1K2 - Tested at 250'F Specimen IKE - Tested at 550°F Figure 5-23 Fractured Tensile Specimens from Calvert Cliffs Unit 2 Reactor Vessel Lower Shell Plate D-8907-2 (Longitudinal Orientation)

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5-40 Westinghouse Non-Proprietary Class 3 Specimen 3JP - Tested at 75"F Specimen 3K4 - Tested at 150'F Specimen 3L4 - Tested at 550'F Figure 5-24 Fractured Tensile Specimens from the Calvert Cliffs Unit 2 Reactor Vessel Surveillance Program Weld Metal WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 5-41 Westinghouse Non-Proprietary Class 3 5-41 Specimen 4JE - Tested at 75*F Specimen 4JM - Tested at 150'F Specimen 4K4 - Tested at 550'F Figure 5-25 Fractured Tensile Specimens from the Calvert Cliffs Unit 2 Reactor Vessel Heat-Affected-Zone Material February 2012 WCAP- 17501 -NP WCAP-17501-NP February 2012 Revision 0

5-42 Westin2house Non-Proprietarv Class 3 5-2 esinhoseNo-PonietriCas 120, 100, 80 60 ............ ............... ...... -------

40-20 O) I I I I I I I I I I I I i I I I 1 0.00 0.02 0.04 0.06 0.08 0.10 0.12 0.14 0.16 0.18 0.20 0.22 0.24 0.26 0.28 0.30 Strain in/ [in]

Figure 5-26 Engineering Stress-Strain Curve for Calvert Cliffs Unit 2 Lower Shell Plate D-8907-2 Tensile Specimen 1KP Tested at 1750 (Longitudinal Orientation) 120" 100, 1..0 . . . . :. .. .;.. . . .. .............. I ,

.. . . . ; . . .i.......... . * . . ......... ..... ... . .

r-~BO 0 i II'* iI i i i Ii I I ! II..

60-0.00 0.02 0.04 0.06 0.08 0.10 0.12 0.14 0.16 0.18 0.20 0.22 0.24 0.26 0.28 0.30 Strain in/ [in]

Figure 5-27 Engineering Stress-Strain Curve for Calvert Cliffs Unit 2 Lower Shell Plate D-8907-2 Tensile Specimen 1K2 Tested at 2500 (Longitudinal Orientation)

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Westinghouse Non-Proprietary Class 3 5-43 Westinghouse Non-Proprietary Class 3 5-43 120 100

. .. .. i  ! i * ,.

U) Q t.........................

840 20 0.00 0.02 0.04 0.C6 0.08 D.10 0.12 0.14 0.16 0.18 0.20 0.22 0.24 0.26 0.23 0.30 Strain in/ [in]

Figure 5-28 Engineering Stress-Strain Curve for Calvert Cliffs Unit 2 Lower Shell Plate D-8907-2 Tensile Specimen 1KE Tested at 5500 (Longitudinal Orientation)

WCAP-1750 1-NP February 2012 Revision 0

5-44 Westinghouse Non-Proprietary Class 3 120 100

• .7*.  : Extensoineter r~80'

.................. sIjippp*.................. .....

ACL 60 40 20 C 14- I I I I I I I I I I I I I I I I I I I I I I 0.00 0.02 0.04 0.06 0.08 0.10 0.12 0.14 0.16 0.18 0.20 0,22 0.24 0.26 0.28 0.30 Strain in/ [in]

Figure 5-29 Engineering Stress-Strain Curve for Calvert Cliffs Unit 2 Surveillance Program Weld Metal Tensile Specimen 3JP Tested at 750 120" 00 ............................... ...............................

60 ... ... ..

40 .... I---- ....... . . . . . . . . .--

60 - ------- . ........ ........................ . . . . . . .

• ,................ . . . . . . \,

20 0.00 0.02 0.04 0.06 0.08 0.10 0.12 0.14 0.16 0.18 0.20 0.22 0.24 0.26 0.28 0.30 Strain in/ [in]

Figure 5-30 Engineering Stress-Strain Curve for Calvert Cliffs Unit 2 Surveillance Program Weld Metal Tensile Specimen 3K4 Tested at 1500 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 5-45 100-80-u 60 40 20-V i i I I i I . I .  ; . i i ; i i I I 0.00)022 0.04 0.0 O.08 0.10 0.12 O.14 0.16 0.18 0.20 0,22 0.24 O.26 0.28 O.30 Strain in/ [in]

Figure 5-31 Engineering Stress-Strain Curve for Calvert Cliffs Unit 2 Surveillance Program Weld Metal Tensile Specimen 3L4 Tested at 550' WCAP-17501 -NP February 2012 Revision 0

5-46 Westinghouse Non-Proprietary Class 3 120" 100 80 .i u

()

L.,,

60

.............................. ................................. ....... \ ................

40 20-A..........................I I 0.00 0.02 0.04 0.06 0.08 0.10 0.12 0.14 0.16 0.18 0.20 0.22 0.24 0.26 0.28 0.30 Strain in/ [in]

Figure 5-32 Engineering Stress-Strain Curve for Calvert Cliffs Unit 2 Heat-Affected-Zone Material Tensile Specimen 4JE Tested at 750 120 slipe 60 ' ............

20 1--..- --.. . ........................ ... .... -

0 I I I I I I IIII I II I I l i III i I I II I I I I I 0.00 0.02 0.04 0.06 0,08 0.10 0,12 0.14 0.16 0.18 0.20 0.22 0.24 0.26 0.28 0.30 Strain in/ [in]

Figure 5-33 Engineering Stress-Strain Curve for Calvert Cliffs Unit 2 Heat-Affected-Zone Material Tensile Specimen 4JM Tested at 1500 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 5-47 120 100, Extensometer i,80 .- -

-.. .-.. ... ........ ......... slibped ..................... ......

Lj 60 40-20 r%-

0V00 i i ;060.0 0 .0 0 I 0.1 I, 0. 8 I0 0., ,.., 0 .2 0 0.00 0.02 0,04 O.06 0,0:8 0.10 0.12 0.14 0,165 0.18 0.20 0.22 0.24 0.2:6 0.28 0.30 Strain in/ [in]

Figure 5-34 Engineering Stress-Strain Curve for Calvert Cliffs Unit 2 Heat-Affected-Zone Material Tensile Specimen 4K4 Tested at 5500 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 6-1 6 RADIATION ANALYSIS AND NEUTRON DOSIMETRY

6.1 INTRODUCTION

This section describes a discrete ordinates Sn transport analysis performed for the Calvert Cliffs Unit 2 reactor to determine the neutron radiation environment within the reactor pressure vessel and surveillance capsules. In this analysis, fast neutron exposure parameters in terms of fast neutron fluence (E > 1.0 MeV) and iron atom displacements (dpa) were established on a plant- and fuel-cycle-specific basis. An evaluation of the most recent dosimetry sensor set from Capsule 1040, withdrawn at the end of the eighteenth plant operating cycle, is provided. In addition, to provide an up-to-date database applicable to the Calvert Cliffs Unit 2 reactor, the sensor sets from the previously withdrawn capsules (2630 and 970) are presented in Appendix A of this report. Comparisons of the results from these dosimetry evaluations with the analytical predictions served to validate the plant-specific neutron transport calculations. These validated calculations subsequently formed the basis for providing projections of the neutron exposure of the reactor pressure vessel for operating periods extending to 60 EFPY at 2737 MWt.

The use of fast neutron fluence (E > 1.0 MeV) to correlate measured material property changes to the neutron exposure of the material has traditionally been accepted for the development of damage trend curves as well as for the implementation of trend curve data to assess the condition of the vessel.

However, in recent years, it has been suggested that an exposure model that accounts for differences in neutron energy spectra between surveillance capsule locations and positions within the vessel wall could lead to an improvement in the uncertainties associated with damage trend curves and improved accuracy in the evaluation of damage gradients through the reactor vessel wall.

Because of this potential shift away from a threshold fluence toward an energy-dependent damage function for data correlation, ASTM Standard Practice E853-01, "Analysis and Interpretation of Light-Water Reactor Surveillance Results," [Reference 23] recommends reporting displacements per iron atom (dpa) along with fluence (E > 1.0 MeV) to provide a database for future reference. The energy-dependent dpa function to be used for this evaluation is specified in ASTM Standard Practice E693-94, "Standard Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements per Atom" [Reference 24]. The application of the dpa parameter to the assessment of embrittlement gradients through the thickness of the reactor vessel wall has already been promulgated in Revision 2 to Regulatory Guide 1.99, "Radiation Embrittlement of Reactor Vessel Materials" [Reference 1].

All of the calculations and dosimetry evaluations described in this section and in Appendix A were based on nuclear cross-section data derived from ENDF/B-VI and using the latest available calculational tools.

Furthermore, the neutron transport and dosimetry evaluation methodologies follow the guidance of Regulatory Guide 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence" [Reference 25]. Additionally, the methods used to develop the calculated pressure vessel fluence are consistent with the NRC-approved methodology described in WCAP-14040-A, Revision 4, "Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves," May 2004 [Reference 26].

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6-2 6-2 Westin.house Non-Pro.rietar. Class 3 6.2 DISCRETE ORDINATES ANALYSIS The arrangement of the surveillance capsules in the Calvert Cliffs Unit 2 reactor vessel is shown in Figure 4-1. Six irradiation capsules attached to the pressure Vessel inside wall are included in the reactor design that constitutes the reactor vessel surveillance program. The capsules are located at azimuthal angles of 830, 970, 1040, 2630, 2770, and 2840 as shown in Figure 4-1. These full-core positions correspond to the following octant symmetric locations represented in Figure 6-2: 7' from the core cardinal axes (for the 830, 970, 2630 and 2770 capsules) and 140 from the core cardinal axes (for the 1040 and 284' capsules).

The stainless steel specimen containers are 1.5-inch by 0.75-inch and are approximately 97 inches in height. The containers are positioned axially such that the test specimens are centered on the core midplane, thus spanning the approximate central 5 feet of the 11.4-foot-high reactor core.

From a neutronic standpoint, the surveillance capsules and capsule holders are significant. The presence of these materials has a significant effect on both the spatial distribution of neutron flux and the neutron spectrum in the vicinity of the capsules. However, the capsules are far enough apart that they do not interfere with one another. In order to determine the neutron environment at the test specimen location, the capsules themselves must be included in the analytical model.

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

y(r,0, z) = tp(r,0)

• q0(r)

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

For the Calvert Cliffs Unit 2 transport calculations, the r,0 models depicted in Figure 6-1 and Figure 6-2 were utilized since, with the exception of the capsules, the reactor is octant symmetric. These r,0 models include the core, the reactor internals, the surveillance capsules, the pressure vessel cladding and vessel wall, the insulation external to the pressure vessel, and the primary biological shield wall. These models formed the basis for the calculated results and enabled making comparisons to the surveillance capsule dosimetry evaluations. In developing these analytical models, nominal design dimensions were employed for the various structural components. For the reactor pressure vessel, however, the average of the as-built inner radius and the minimum pressure vessel thickness were used. Likewise, water temperatures, and hence, coolant densities in the reactor core and downcomer regions of the reactor were taken to be representative of full-power operating conditions. The coolant densities were treated on a fuel-cycle-specific basis. The reactor core itself was treated as a homogeneous mixture of fuel, cladding, water, and miscellaneous core structures such as fuel assembly grids, guide tubes, et cetera. The geometric mesh description of the r,0 reactor models consisted of 114 radial by 62 azimuthal intervals. Mesh sizes were chosen to ensure that proper convergence of the inner iterations was achieved on a pointwise basis. The WCAP- 17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 6-3 pointwise inner iteration flux convergence criterion utilized in the r,O calculations was set at a value of 0.001.

The r,z model used for the Calvert Cliffs Unit 2 calculations is shown in Figure 6-3 and extends radially from the centerline of the reactor core out to a location interior to the primary biological shield and over an axial span from an elevation below the lower core plate to above the upper core plate. As in the case of the r,0 models, nominal design dimensions and full-power coolant densities were employed in the calculations. In this case, the homogenous core region was treated as an equivalent cylinder with a volume equal to that of the active core zone. The stainless steel former plates located between the core baffle and core barrel regions were also explicitly included in the model. The r,z geometric mesh description of these reactor models consisted of 103 radial by 137 axial intervals. As in the case of the r,0 calculations, mesh sizes were chosen to ensure that proper convergence of the inner iterations was achieved on a pointwise basis. The pointwise inner iteration flux convergence criterion utilized in the r,z calculations was also set at a value of 0.001.

The one-dimensional radial model used in the synthesis procedure consisted of the same 103 radial mesh intervals included in the r,z model. Thus, radial synthesis factors could be determined on a meshwise basis throughout the entire geometry.

The core power distributions used in the plant-specific transport analysis were provided by Constellation Energy for each of the first 18 fuel cycles at Calvert Cliffs Unit 2. Specifically, the data utilized included cycle-dependent fuel assembly initial enrichments, burnups, and axial power distributions. This information was used to develop spatial- and energy-dependent core source distributions averaged over each individual fuel cycle. Therefore, the results from the neutron transport calculations provided data in terms of fuel-cycle-averaged neutron flux, which when multiplied by the appropriate fuel cycle length, generated the incremental fast neutron exposure for each fuel cycle. In constructing these core source distributions, the energy distribution of the source was based on an appropriate fission split for uranium and plutonium isotopes based on the initial enrichment and burnup history of individual fuel assemblies.

From these assembly-dependent fission splits, composite values of energy release per fission, neutron yield per fission, and fission spectrum were determined.

All of the transport calculations supporting this analysis were carried out using the DORT discrete ordinates code Version 3.2 [Reference 27] and the BUGLE-96 cross-section library [Reference 28]. The BUGLE-96 library provides a 67-group coupled neutron, gamma-ray cross-section data set produced specifically for light-water reactor (LWR) applications. In these analyses, anisotropic scattering was treated with a P5 Legendre expansion, and angular discretization was modeled with an S16 order of angular quadrature. Energy- and space-dependent core power distributions, as well as system operating temperatures, were treated on a fuel-cycle-specific basis.

Selected results from the neutron transport analyses are provided in Tables 6-1 through 6-4. In Table 6-1, the calculated exposure rates and integrated exposures, expressed in terms of both neutron fluence (E > 1.0 MeV) and dpa, are given at the radial and azimuthal center of the octant symmetric surveillance capsule positions, i.e., for the 7' capsule and 14' capsule. These results, representative of the average axial exposure of the material specimens, establish the calculated exposure of the surveillance capsules withdrawn to date as well as projected into the future.

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6-4 Westinghouse Non-Proprietary Class 3 Similar information, in terms of both calculated fluence (E > 1.0 MeV) and dpa data are provided in Table 6-2, for the reactor vessel inner radius at four azimuthal locations. The vessel data given in Table 6-2 were taken at the clad/base metal interface and thus represent maximum calculated exposure levels on the vessel. From the data provided in Table 6-2, it is noted that the peak clad/base metal interface vessel fluence (E > 1.0 MeV) at the end of the eighteenth fuel cycle (i.e., after 27.13 EFPY at 2737 MWt of plant operation) was 2.53 x 10' 9 n/cm 2 .

These data tabulations include both plant- and fuel-cycle-specific calculated neutron exposures at the end of the eighteenth fuel cycle, as well as future projections to 32, 36, 40, 44, 48, 54 and 60 EFPY at 2737 MWt. The calculations account for uprates from 2560 MWt to 2700 MWt that occurred during Cycle 1, and from 2700 MWt to 2737 MWt that occurred during Cycle 18. The projections were based on the assumption that the core power distributions and associated plant operating characteristics from Cycle 18 were representative of future plant operation. The future projections are also based on the current reactor power level of 2737 MWt.

The calculated fast neutron exposures for the three surveillance capsules withdrawn from the Calvert Cliffs Unit 2 reactor are provided in Table 6-3. These assigned neutron exposure levels are based on the plant- and fuel-cycle-specific neutron transport calculations performed for the Calvert Cliffs Unit 2 reactor. From the data provided in Table 6-3, Capsule 1040 received a fluence (E > 1.0 MeV) of 2.44 x 10'9 n/cm 2 after exposure through the end of the eighteenth fuel cycle (i.e., after 27.13 EFPY at 2737 MWt of plant operation).

Updated lead factors for the Calvert Cliffs Unit 2 surveillance capsules are provided in Table 6-4. The capsule lead factor is defined as the ratio of the calculated axial average fluence (E > 1.0 MeV) at the geometric radial and azimuthal center of the surveillance capsule to the corresponding maximum calculated fluence at the pressure vessel clad/base metal interface. In Table 6-4, the lead factors for capsules that have been withdrawn from the reactor (2630, 970, and 1040) were based on the calculated fluence values for the irradiation period corresponding to the time of withdrawal for the individual capsules. For the capsule remaining in the reactor (830, 2840 and 2770), the lead factor corresponds to the calculated fluence values at the end of Cycle 18, the last completed fuel cycle for Calvert Cliffs Unit 2.

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

The direct comparison of measured versus calculated fast neutron threshold reaction rates for the sensors from Capsule 1040, which was withdrawn from Calvert Cliffs Unit 2 at the end of the eighteenth fuel cycle, is summarized below.

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Westinghouse Non-Proprietary Class 3 6-5 Reaction Rates (rps/atom)

Reaction Measured Calculated M/C Ratio 63 60 Cu(nX) Co 4.22E- 17 4.67E-17 0.90 54 Fe(n,p)54 Mn 3.77E- 15 3.98E- 15 0.95 "Ni(n,p) 58 Co 5

5.21E-15 5.17E-15 1.01 238 U(Cd)(n,f) FP 9.0 8E- 15 1.31 E- 14 0.69 Average: 0.89

% Standard Deviation: 16 The measured-to-calculated (M/C) reaction rate ratios for the Capsule 104' threshold reactions range from 0.69 to 1.01, and the average M/C ratio is 0.89 +/- 16% (la). This direct comparison falls within the

+/- 20% criterion specified in Regulatory Guide 1.190. These comparisons validate the current analytical results described in Section 6.2; therefore, the calculations are deemed applicable for Calvert Cliffs Unit 2.

6.4 CALCULATIONAL UNCERTAINTIES The uncertainty associated with the calculated neutron exposure of the Calvert Cliffs Unit2 surveillance capsule and reactor pressure vessel is based on the recommended approach provided in Regulatory Guide 1.190. In particular, the qualification of the methodology was carried out in the following four stages:

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

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

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

4. Comparisons of the plant-specific calculations with all available dosimetry results from the Calvert Cliffs Unit 2 surveillance program.

The first phase of the methods qualification (PCA comparisons) addressed the adequacy of basic transport calculation and dosimetry evaluation techniques and associated cross sections. This phase, however, did not test the accuracy of commercial core neutron source calculations nor did it address uncertainties in operational or geometric variables that impact power reactor calculations. The second phase of the qualification (H. B. Robinson comparisons) addressed uncertainties in these additional areas that are primarily methods-related and would tend to apply generically to all fast neutron exposure evaluations.

The third phase of the qualification (analytical sensitivity study) identified the potential uncertainties introduced into the overall evaluation due to calculational methods approximations, as well as to a lack of knowledge relative to various plant-specific input parameters. The overall calculational uncertainty WCAP-17501-NP February 2012 Revision 0

6-6 Westinghouse Non-Proprietary Class 3 applicable to the Calvert Cliffs Unit 2 analysis was established from results of these three phases of the methods qualification.

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

The following summarizes the uncertainties developed from the first three phases of the methodology qualification. Additional information pertinent to these evaluations is provided in Reference 26.

Capsule and Vessel IR PCA Comparisons 3%

H. B. Robinson Comparisons 3%

Analytical Sensitivity Studies 11%

Additional Uncertainty for Factors not Explicitly Evaluated 5%

Net Calculational Uncertainty 13%

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

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

The plant-specific measurement comparisons described in Appendix A support these uncertainty assessments for Calvert Cliffs Unit 2.

WCAP-1750 1-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 6-7 Table 6-1 Calculated Neutron Exposure Rates and Integrated Exposures at the Surveillance Capsule Center Cumulative Cumulative Neutron Flux (E > 1.0 MeV)

Cycle Irradiation Irradiation In/cm 2-s] "'*

Length Time Time Cycle IEFPS(b)I IEFPS(b)] [EFPY(b)] 70 Capsule 14° Capsule 1 4.37E+07 4.37E+07 1.39 5.35E+10 3.86E+10 2 2.83E+07 7.20E+07 2.28 5.53E+10 3.99E+10 3 2.97E+07 1.02E+08 3.22 6.OOE+10 4.43E+10 4 4.45E+07 1.46E+08 4.63 5.77E+10 4.14E+ 10 5 3.66E+07 1.83E+08 5.79 5.95E+10 4.40E+ 10 6 3.60E+07 2.19E+08 6.93 6.40E+10 4.63E+10 7 3.80E+07 2.57E+08 8.14 6.16E+10 4.42E+10 8 4.77E+07 3.05E+08 9.65 4.73E+10 3.21E+10 9 4.78E+07 3.52E+08 11.16 4.55E+10 3.03E+10 10 4.97E+07 4.02E+08 12.74 2.82E+10 2.29E+10 11 5.49E+07 4.57E+08 14.48 2.58E+10 1.93E+10 12 5.43E+07 5.11E+08 16.20 2.57E+10 2.14E+ 10 13 5.69E+07 5.68E+08 18.00 2.42E+10 2.05E+10 14 5.40E+07 6.22E+08 19.71 2.67E+10 2.17E+10 15 5.67E+07 6.79E+08 21.51 2.76E+10 2.19E+10 16 5.99E+07 7.39E+08 23.41 2.53E+10 1.94E+10 17 5.86E+07 7.97E+08 25.27 2.80E+10 2.03E+10 18 5.87E+07 8.56E+08 27.13 2.87E+10 2.12E+10 Future 1.54E+08 1.01E+09 32.00 2.87E+10 2.12E+10 Future 1.26E+08 1.14E+09 36.00 2.87E+10 2.12E+10 Future 1.26E+08 1.26E+09 40.00 2.87E+10 2.12E+ 10 Future 1.26E+08 1.39E+09 44.00 2.87E+10 2,12E+10 Future 1.26E+08 1.51E+09 48.00 2.87E+10 2.12E+10 Future 1.26E+08 1.64E+09 52.00 2.87E+10 2.12E+ 10 Future 6.31E+07 1.70E+09 54.00 2.87E+ 10 2.12E+ 0 Future 1.89E+08 1.89E+09 60.00 2.87E+10 2.12E+10 Notes:

(a) Neutron exposure values reported for the surveillance capsules are axial averages over the capsules' axial span.

(b) At 2737 MWt WCAP-17501-NP February 2012 Revision 0

6-8 Westinghouse Non-Proprietary Class 3 Table 6-1 (Continued) Calculated Neutron Exposure Rates and Integrated Exposures at the Surveillance Capsule Center Cumulative Cumulative Cumulative Neutron Fluence (E > 1.0 MeV)

Cycle Irradiation Irradiation Irradiation in/cm 2 ] (a)

Length Time Time Time Cycle [EFPS(b)] [EFPS(b)I [EFPY(b)I [EFPY(c)] 70 Capsule 140 Capsule I 4.37E+07 4.37E+07 1.39 1.40 2.34E+18 1.69E+18 2 2.83E+07 7.20E+07 2.28 2.31 3.90E+18 2.82E+18 3 2.97E+07 1.02E+08 3.22 3.27 5.69E+18 4.13E+18 4 4.45E+07 1.46E+08 4.63 4.70 8.25E+ 18 5.98E+18 5 3.66E+07 1.83E+08 5.79 5.87 1.04E+19 7.58E+18 6 3.60E+07 2.19E+08 6.93 7.03 1.27E+19 9.25E+18 7 3.80E+07 2.57E+08 8.14 8.25 1.51E+19 1.09E+19 8 4.77E+07 3.05E+08 9.65 9.78 1.73E+19 1.25E+19 9 4.78E+07 3.52E+08 11.16 11.32 1.95E+19 1.39E+19 10 4.97E+07 4.02E+08 12.74 12.91 2.09E+19 1.51E+19 11 5.49E+07 4.57E+08 14.48 14.68 2.23E+19 1.61E+19 12 5.43E+07 5.11E+08 16.20 16.42 2.37E+19 1.73E+19 13 5.69E+07 5.68E+08 18.00 18.25 2.51 E+ 19 1.84E+19 14 5.40E+07 6.22E+08 19.71 19.98 2.65E+19 1.96E+19 15 5.67E+07 6.79E+08 21.51 21.81 2.81E+19 2.08E+19 16 5.99E+07 7.39E+08 23.41 23.73 2.96E+19 2.20E+19 17 5.86E+07 7.97E+08 25.27 25.61 3.13E+19 2.32E+19 18 5.87E+07 8.56E+08 27.13 -- 3.30E+19 2.44E+19 Future 1.54E+08 1.01E+09 32.00 -- 3.82E+19 2.83E+19 Future 1.26E+08 1.14E+09 36.00 -- 4.19E+19 3.10E+19 Future 1.26E+08 1.26E+09 40.00 -- 4.55E+19 3.37E+19 Future 1.26E+08 1.39E+09 44.00 -- 4.91E+19 3.64E+ 19 Future 1.26E+08 1.51E+09 48.00 -- 5.27E+19 3.91E+19 Future 1.26E+08 1.64E+09 52.00 -- 5.64E+ 19 4.17E+19 Future 6.31E+07 1.70E+09 54.00 -- 5.82E+19 4.31E+19 Future 1.89E+08 1.89E+09 60.00 -- 6.36E+19 4.71E+19 Notes:

(a) Neutron exposure values reported for the surveillance capsules are axial averages over the capsules' axial span.

(b) At 2737 MWt (c) At 2700 MWt WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 6-9 6-9 Westinghouse Non-Proprietary Class 3 Table 6-1 (Continued) Calculated Neutron Exposure Rates and Integrated Exposures at the Surveillance Capsule Center Cumulative Cumulative Iron Atom Displacement Rate Cycle Irradiation Irradiation Idpa/sI (a)

Length Time Time Cycle [EFPS(b)I [EFPSM(b) [EFPY(b)l 70 Capsule 140 Capsule 1 4.37E+07 4.37E+07 1.39 7.74E-11 5.62E-11 2 2.83E+07 7.20E+07 2.28 8.02E-11 5.81E-11 3 2.97E+07 1.02E+08 3.22 8.69E- 11 6.44E- 11 4 4.45E+07 1.46E+08 4.63 8.35E-11 6.03E-11 5 3.66E+07 1.83E+08 5.79 8.62E-11 6.39E-11 6 3.60E+07 2.19E+08 6.93 9.27E-11 6.74E-11 7 3.80E+07 2.57E+08 8.14 8.93E-I1 6.44E- 11 8 4.77E+07 3.05E+08 9.65 6.86E- I1 4.69E- 1I 9 4.78E+07 3.52E+08 11.16 6.59E-11 4.43E-11 10 4.97E+07 4.02E+08 12.74 4.1OE-11 3.35E-11 11 5.49E+07 4.57E+08 14.48 3.75E- 11 2.82E-11 12 5.43E+07 5.11E+08 16.20 3.75E-11 3.13E-11 13 5.69E+07 5.68E+08 18.00 3.53E-11 3.00E-11 14 5.40E+07 6.22E+08 19.71 3.88E-11 3.17E- 11 15 5.67E+07 6.79E+08 21.51 4.02E- 11 3.20E-11 16 5.99E+07 7.39E+08 23.41 3.69E-11 2.84E-11 17 5.86E+07 7.97E+08 25.27 4.07E-11 2.97E-11 18 5.87E+07 8.56E+08 27.13 4.18E-11 3.1OE-11 Future 1.54E+08 1.01E+09 32.00 4.18E-11 3.1OE-11 Future 1.26E+08 1.14E+09 36.00 4.18E-11 3.10E-11 Future 1.26E+08 1.26E+09 40.00 4.18E- 11 3.10E-11 Future 1.26E+08 1.39E+09 44.00 4.18E- 11 3.10E-11 Future 1.26E+08 1.51E+09 48.00 4.18E-11 3.10E-11 Future 1.26E+08 1.64E+09 52.00 4.18E-11 3.10E-11 Future 6.31E+07 1.70E+09 54.00 4.18E-11 3.1OE-11 Future 1.89E+08 1.89E+09 60.00 4.18E-11 3.1OE- 11 Notes:

(a) Neutron exposure values reported for the surveillance capsules are axial averages over the capsules' axial span.

(b) At 2737 MWt WCAP- 17501-NP February 2012 Revision 0

6-10 Westinghouse Non-Proprietary Class 3 Table 6-1 (Continued) Calculated Neutron Exposure Rates and Integrated Exposures at the Surveillance Capsule Center Cumulative Cumulative Cumulative Iron Atom Displacements Idpal (a)

Cycle Irradiation Irradiation Irradiation Length Time Time Time Cycle [EFPS(b)] IEFPStb)] [EFPY(b)I IEFPY(c)] 70 Capsule 140 Capsule 1 4.37E+07 4.37E+07 1.39 1.40 3.39E-03 2.46E-03 2 2.83E+07 7.20E+07 2.28 2.31 5.66E-03 4.10E-03 3 2,97E+07 1.02E+08 3.22 3.27 8.24E-03 6.01E-03 4 4.45E+07 1.46E+08 4.63 4.70 1.20E-02 8.70E-03 5 3.66E+07 1.83E+08 5.79 5.87 1.51E-02 1.1OE-02 6 3.60E+07 2.19E+08 6.93 7.03 1.84E-02 1.35E-02 7 3.80E+07 2.57E+08 8.14 8.25 2.18E-02 1.59E-02 8 4.77E+07 3.05E+08 9.65 9.78 2.5 1E-02 1.82E-02 9 4.78E+07 3.52E+08 11.16 11.32 2.83E-02 2.03E-02 10 4.97E+07 4.02E+08 12.74 12.91 3.03E-02 2.19E-02 11 5.49E+07 4.57E+08 14.48 14.68 3.24E-02 2.35E-02 12 5.43E+07 5.11EE+08 16.20 16.42 3.44E-02 2.52E-02 13 5.69E+07 5.68E+08 18.00 18.25 3.64E-02 2.69E-02 14 5.40E+07 6.22E+08 19.71 19.98 3.85E-02 2.86E-02 15 5.67E+07 6.79E+08 21.51 21.81 4.08E-02 3.04E-02 16 5.99E+07 7.39E+08 23.41 23.73 4.30E-02 3.21E-02 17 5.86E+07 7.97E+08 25.27 25.61 4.54E-02 3.38E-02 18 5.87E+07 8.56E+08 27.13 -- 4.78E-02 3.57E-02 Future 1.54E+08 1.01E+09 32.00 -- 5.55E-02 4.14E-02 Future 1.26E+08 1.14E+09 36.00 -- 6.08E-02 4.53E-02 Future 1.26E+08 1.26E+09 40.00 -- 6.61E-02 4.92E-02 Future 1.26E+08 1.39E+09 44.00 -- 7.13E-02 5.31E-02 Future 1.26E+08 1.51E+09 48.00 -- 7.66E-02 5.70E-02 Future 1.26E+08 1.64E+09 52.00 -- 8.19E-02 6.09E-02 Future 6.3 1E+07 1.70E+09 54.00 -- 8.45E-02 6.29E-02 Future 1.89E+08 1.89E+09 60.00 -- 9.24E-02 6.88E-02 Notes:

(a) Neutron exposure values reported for the surveillance capsules are axial averages over the capsules' axial span.

(b) At 2737 MWt (c) At 2700 MWt WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 6-11 Table 6-2 Calculated Azimuthal Variation of Maximum Exposure Rates and Integrated Exposures at the Reactor Vessel Clad/Base Metal Interface Cumulative Cumulative Neutron Flux (E > 1.0 MeV) In/cm 2-s]

Cycle Irradiation Irradiation Length Time Time Cycle [EFPS(a)] [EFPS(a)] [EFPY(a)I 00 150 300 450 1 4.37E+07 4.37E+07 1.39 4.20E+10 2.70E+10 2.30E+10 1.85E+10 2 2.83E+07 7.20E+07 2.28 4.28E+10 2.74E+10 2.54E+10 2.06E+10 3 2.97E+07 1.02E+08 3.22 4.48E+10 2.99E+10 2.69E+10 2.10E+10 4 4.45E+07 1.46E+08 4.63 4.37E+10 2.79E+10 2.50E+10 1.97E+10 5 3.66E+07 1.83E+08 5.79 4.42E+10 2.96E+10 2.66E+10 2.11E+10 6 3.60E+07 2.19E+08 6.93 4.84E+10 3.12E+10 2.79E+10 2.17E+10 7 3.80E+07 2.57E+08 8.14 4.68E+10 2.99E+10 2.78E+10 2.12E+10 8 4.77E+07 3.05E+08 9.65 3,84E+10 2.19E+10 1,78E+10 1.34E+10 9 4.78E+07 3.52E+08 11.16 3.74E+10 2.08E+10 1.61E+10 1.17E+10 10 4.97E+07 4.02E+08 12.74 2.12E+10 1.60E+10 1.47E+10 1.09E+10 11 5.49E+07 4.57E+08 14.48 2,01E+10 1.34E+10 1.20E+10 1.09E+10 12 5.43E+07 5.11E+08 16.20 1.94E+10 1.52E+10 1,43E+10 1.17E+10 13 5.69E+07 5.68E+08 18.00 1.81E+10 1.45E+10 1.42E+10 1.15E+10 14 5.40E+07 6.22E+08 19.71 2.0113+10 1.52E+10 1.35E+10 1.05E+10 15 5.67E+07 6.79E+08 21.51 2.13E+10 1.54E+10 1.45E+10 1.13E+10 16 5.99E+07 7.39E+08 23.41 2.0013+10 1.39E+10 1.32E+10 1.15E+10 17 5.86E+07 7.97E+08 25.27 2.20E+10 1.39E+10 1.26E+10 1.111E+10 18 5.87E+07 8.56E+08 27.13 2.24E+10 1.46E+10 1.28E+10 1.04E+10 Future 1.5413+08 1.01E+09 32.00 2.24E+10 1.46E+10 1.28E+10 1.04E+10 Future 1.26E+08 1.14E+09 36.00 2.24E+10 1.46E+10 1.28E+10 1.04E+10 Future 1.26E+08 1.26E+09 40.00 2.24E+10 1.46E+10 1.28E+10 1.04E+10 Future 1.26E+08 1.39E+09 44.00 2.24E+10 1.46E+10 1.28E+10 1.04E+10 Future 1.26E+08 1.51E+09 48.00 2.24E+10 1.46E+10 1.28E+10 1.04E+10 Future 1.26E+08 1.64E+09 52.00 2.24E+10 1.46E+10 1.28E+10 1.04E+10 Future 6.31E+07 1.70E+09 54.00 2.24E+10 1.46E+10 1.28E+10 1.04E+10 Future 1.89E+08 1.89E+09 60.00 2.24E+I0 1.46E+10 1.28E+10 1.04E+10 Note:

(a) At 2737 MWt WCAP-17501-NP February 2012 Revision 0

6-12 Westinghouse Non-Proprietarv Class 3 Table 6-2 (Continued) Calculated Azimuthal Variation of Maximum Exposure Rates and Integrated Exposures at the Reactor Vessel Clad/Base Metal Interface Cumulative Cumulative Cumulative Neutron Fluence (E > 1.0 MeV) In/cm 21 Cycle Irradiation Irradiation Irradiation Length Time Time Time Cycle [EFPS('a)I EFPS(a)I IEFPY(O)i [EFPY(b)] 00 150 300 450 1 4.37E+07 4.37E+07 1.39 1.40 1.83E+18 1.18E+18 1.01E+18 8.10E+17 2 2.83E+07 7.20E+07 2.28 2.31 3.05E+18 1.96E+18 1.73E+18 1.39E+18 3 2.97E+07 1.02E+08 3.22 3.27 4.38E+18 2.84E+18 2.52E+18 2.02E+18 4 4.45E+07 1.46E+08 4.63 4.70 6.32E+18 4.08E+18 3.64E+18 2.89E+18 5 3.66E+07 1.83E+08 5.79 5.87 7.93E+18 5.16E+18 4.60E+18 3.66E+18 6 3.60E+07 2.19E+08 6.93 7.03 9.64E+18 6.27E+18 5.59E+18 4.43E+18 7 3.80E+07 2.57E+08 8.14 8.25 1.14E+19 7.38E+18 6.63E+18 5.22E+18 8 4.77E+07 3.05E+08 9.65 9.78 1.32E+19 8.43E+18 7.48E+18 5.86E+18 9 4.78E+07 3.52E+08 11.16 11.32 1.50E+19 9.39E+18 8.22E+18 6.41E+18 10 4.97E+07 4.02E+08 12.74 12.91 1.60E+19 1.02E+19 8.95E+18 6.95E+18 11 5.49E+07 4.57E+08 14.48 14.68 1.71E+19 1.09E+19 9.61E+18 7.54E+18 12 5.43E+07 5.11E+08 16.20 16.42 1.82E+19 1.17E+19 1.04E+19 8.18E+18 13 5.69E+07 5.68E+08 18.00 18.25 1.92E+19 1.26E+19 1.12E+19 8.83E+18 14 5.40E+07 6.22E+08 19.71 19.98 2.03E+19 1.34E+19 1.19E+19 9.40E+18 15 5.67E+07 6.79E+08 21.51 21.81 2.15E+19 1.43E+19 1.27E+ 19 1.00E+19 16 5.99E+07 7.39E+08 23.41 23.73 2.27E+19 1.51E+19 1.35E+19 1.07E+19 17 5.86E+07 7.97E+08 25.27 25.61 2.40E+19 1.59E+19 1.43E+19 1.14E+19 18 5.87E+07 8.56E+08 27.13 -- 2.53E+19 1.68E+19 1.50E+19 1.20E+19 Future 1.54E+08 1.01E+09 32.00 -- 2.87E+19 1.90E+19 1.70E+19 1.36E+19 Future 1.26E+08 1.14E+09 36.00 -- 3.15E+19 2.08E+19 1.86E+19 1.49E+19 Future 1.26E+08 1.26E+09 40.00 -- 3.43E+19 2.26E+19 2.02E+19 1.62E+19 Future 1.26E+08 1.39E+09 44.00 -- 3.71E+19 2.45E+19 2.18E+19 1.75E+19 Future 1.26E+08 1.51E+09 48.00 -- 4.OOE+19 2.63E+19 2.34E+19 1.88E+19 Future 1.26E+08 1.64E+09 52.00 -- 4.28E+19 2.81E+19 2.50E+19 2.01E+19 Future 6.31E+07 1.70E+09 54.00 -- 4.42E+-19 2.90E+ 19 2.58E+19 2.08E+19 Future 1.89E+08 1.89E+09 60.00 -- 4.84E+19 3.18E+19 2.82E+19 2.27E+19 Notes:

(a) At 2737 MWt (b) At 2700 MWt WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 6-13 Table 6-2 (Continued) Calculated Azimuthal Variation of Maximum Exposure Rates and Integrated Exposures at the Reactor Vessel Clad/Base Metal Interface Cumulative Cumulative Iron Atom Displacement Rate Idpa/sI Cycle Irradiation Irradiation Length Time Time Cycle [EFPS(a)I [EFPS(a)I fEFPY(a)I 00 150 300 450 1 4.37E+07 4.37E+07 1.39 6.37E- 11 4.13E-11 3.50E-11 2.84E- 11 2 2.83E+07 7.20E+07 2.28 6.50E-11 4.20E-11 3.87E-11 3.16E-11 3 2.97E+07 1.02E+08 3.22 6.80E-11 4.57E-I1 4.09E-11 3.23E-11 4 4.45E+07 1.46E+08 4.63 6.63E-11 4.27E- 11 3.81E-11 3.02E-11 5 3.66E+07 1.83E+08 5.79 6.71E-11 4.52E-11 4.05E-11 3.23E-11 6 3.60E+07 2.19E+08 6.93 7.34E-11 4.78E-11 4.24E- 11 3.33E-11 7 3.80E+07 2.57E+08 8.14 7.11E-11 4.57E-11 4.23E-11 3.27E-11 8 4.77E+07 3.05E+08 9.65 5.81E-11 3.35E-11 2.72E-11 2.07E-11 9 4.78E+07 3.52E+08 11.16 5.67E-11 3.19E-11 2.46E- 11 1.81E-11 10 4.97E+07 4.02E+08 12.74 3.23E-11 2.46E-11 2.25E-11 1.68E-11 11 5.49E+07 4.57E+08 14.48 3.06E-11 2.05E-11 1.84E-11 1.68E-11 12 5.43E+07 5.1 IE+08 16.20 2.96E- I1 2.33E- I1 2.19E-1 1 1.80E-1 1 13 5.69E+07 5.68E+08 18.00 2.75E-11 2.22E-11 2.17E-11 1.76E-11 14 5.40E+07 6.22E+08 19.71 3.06E-11 2.33E-11 2.06E-11 1.62E-11 15 5.67E+07 6.79E+08 21.51 3.24E-11 2.37E-11 2.21E-11 1.74E-11 16 5.99E+07 7.39E+08 23.41 3.05E-11 2.13E-11 2.02E-11 1.77E-11 17 5.86E+07 7.97E+08 25.27 3.35E-11 2.14E-11 1.92E- 11 1.70E- 11 18 5.87E+07 8.56E+08 27.13 3.41E-11 2.24E- 11 1.95E-11 1.60E-11 Future 1.54E+08 1.01E+09 32.00 3,41E-1I 2.24E-11 1.95E-11 1,60E-I I Future 1.26E+08 1.14E+09 36.00 3.41E-11 2.24E- 11 1.95E- 11 1.60E- 11 Future 1.26E+08 1.26E+09 40.00 3.41E-11 2.24E- 11 1.95E- 11 1.60E-11 Future 1.26E+08 1.39E+09 44.00 3.41E-11 2.24E- 11 1.95E-11 1.60E- 11 Future 1.26E+08 1.51E+09 48.00 3.41E-11 2.24E-11 1.95E-11 .1.60E-11 Future 1.26E+08 1.64E+09 52.00 3.41E-11 2.24E-11 1.95E- 11 1.60E- 11 Future 6.31E+07 1.70E+09 54.00 3.41E-11 2.24E- I1 1.95E-11 1.60E-11 Future 1.89E+08 1,89E+09 60.00 3.41E-11 2.24E-11 1.95E-11 1.60E-11 Note:

(a) At 2737 MWt.

WCAP-17501-NP February 2012 Revision 0

6-14 Westinghouse Non-Proprietary Class 3 Table 6-2 (Continued) Calculated Azimuthal Variation of Maximum Exposure Rates and Integrated Exposures at the Reactor Vessel Clad/Base Metal Interface Cumulative Cumulative Cumulative Iron Atom Displacements Idpal Cycle Irradiation Irradiation Irradiation Length Time Time Time Cycle IEFPS(a)] [EFPS(a)] [EFPY(a)] [EFPY(b)] 00 150 300 450 1 4.37E+07 4.37E+07 1.39 1.40 2.78E-03 1.80E-03 1.53E-03 1.24E-03 2 2.83E+07 7.20E+07 2.28 2.31 4.62E-03 2.99E-03 2.63E-03 2.14E-03 3 2.97E+07 1.02E+08 3.22 3.27 6.64E-03 4.35E-03 3.84E-03 3.1OE-03 4 4.45E+07 1.46E+08 4.63 4.70 9.59E-03 6.25E-03 5.54E-03 4.44E-03 5 3.66E+07 1.83E+08 5.79 5.87 1.20E-02 7.90E-03 7.01E-03 5.62E-03 6 3.60E+07 2.19E+08 6.93 7.03 1.46E-02 9.59E-03 8.51E-03 6.80E-03 7 3.80E+07 2.57E+08 8.14 8.25 1.73E-02 1.13E-02 1.O1E-02 8.02E-03 8 4.77E+07 3.05E+08 9.65 9.78 2.01E-02 1.29E-02 1.14E-02 9.01E-03 9 4.78E+07 3.52Et08 11.16 11.32 2.27E-02 1.44E-02 1.25E-02 9.84E-03 10 4.97E+07 4.02E+08 12.74 12.91 2.43E-02 1.56E-02 1.36E-02 1.07E-02 11 5.49E+07 4.57E+08 14.48 14.68 2.60E-02 1.67E-02 1.46E-02 1.16E-02 12 5.43E+07 5.11E+08 16.20 16.42 2.76E-02 1.80E-02 1.58E-02 1.26E-02 13 5.69E+07 5.68E+08 18.00 18.25 2.91E-02 1.92E-02 1.71E-02 1.36E-02 14 5.40E+07 6.22E+08 19.71 19.98 3.08E-02 2.05E-02 1.82E-02 1.45E-02 15 5.67E+07 6.79E+08 21.51 21.81 3.26E-02 2.18E-02 1.94E-02 1.54E-02 16 5.99E+07 7.39E+08 23.41 23.73 3.44E-02 2.3 1E-02 2.06E-02 1.65E-02 17 5.86E+07 7.97E+08 25.27 25.61 3.64E-02 2.44E-02 2.18E-02 1.75E-02 18 5.87E+07 8.56E+08 27.13 -- 3.84E-02 2.57E-02 2.29E-02 1.84E-02 Future 1.54E+08 1.01E+09 32.00 -- 4.36E-02 2.91E-02 2.59E-02 2.09E-02 Future 1.26E+08 1.14E+09 36.00 -- 4.79E-02 3.19E-02 2.83E-02 2.29E-02 Future 1.26E+08 1.26E+09 40.00 -- 5.22E-02 3.47E-02 3.08E-02 2.49E-02 Future 1.26E+08 1.39E+09 44.00 -- 5.64E-02 3.75E-02 3.32E-02 2.69E-02 Future 1.26E+08 1.51E+09 48.00 -- 6.07E-02 4.03E-02 3.57E-02 2.89E-02 Future 1.26E+08 1.64E+09 52.00 -- 6.50E-02 4.32E-02 3.81E-02 3.1OE-02 Future 6.31E+07 1.70E+09 54.00 -- 6.71E-02 4.45E-02 3.94E-02 3.20E-02 Future 1.89E+08 1.89E+09 60.00 -- 7.36E-02 4.88E-02 4.30E-02 3.50E-02 Notes:

(a) At 2737 MWt (b) At 2700 MWt WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 6-15 Table 6-3 Calculated Fast Neutron Exposure of Surveillance Capsules Withdrawn from Calvert Cliffs Unit 2 Irradiation Time Irradiation Time Fluence (E > 1.0 Iron Displacements Capsule IEFPY'a)] IEFPY(b)] MeV) [n/cm2J Idpal 2630 4.63 4.70 8.25E+18 1.20E-02 970 11.16 11.32 1.95E+19 2.83E-02 1040 27.13 -- 2.44E+ 19 3.57E-02 Notes:

(a) At 2737 MWt (b) At 2700 MWt WCAP-1750 1-NP February 2012 Revision 0

6-16 Westini!house Non-Pronrietarv Class 3 Table 6-4 Calculated Surveillance Capsule Lead Factors Capsule Location Status Lead Factor 2630 Withdrawn EOC 4 1.31 970 Withdrawn EOC 9 1.30 1040 Withdrawn EOC 18 0.97 830 In Reactor(a) 1.30 2840 In Reactor(a) 0.97 2770 In Reactor(a) 1.30 Note:

(a) Lead factors are based on the cumulative exposures from Cycles 1 through 18.

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Westinghouse Non-Proprietary Class 3 6-17 R-T Calvert Cliffs Unit 2 - NO Capsules Meshes: 114R, 628

+

,,f E

IA (0

/

00 OR t

3.886E+02 cm w-0.0E0 3.89E-02 Figure 6-1 Calvert Cliffs Unit 2 re Reactor Geometry without Surveillance Capsules WCAP-17501-NP February 2012 Revision 0

6-18 6-18 Westin.house Non-P

. nrietarv Class 3 R-T Calvert Cliffs Unit 2 - WITH Capsules Meshes: 114R, 628 0

E C.,

00 aq 3.886E+02 cm 0.OOE4+00 3.89E+02 Figure 6-2 Calvert Cliffs Unit 2 rO Reactor Geometry with 70 and 140 Surveillance Capsules WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 6-19 6-19 Westinghouse Non-Proprietary Class 3 R-Z Calvert Cliffs Unit 2 -

Meshes: 103R,137Z z

E C."

o

+

-~

IN 3.886E+02 cm 0 OOE+00 3.89E+02 Figure 6-3 Calvert Cliffs Unit 2 rz Reactor Geometry WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 7-1 7 SURVEILLANCE CAPSULE REMOVAL SCHEDULE The following surveillance capsule removal schedule (Table 7-1) meets the requirements of ASTM E185-82 [Reference 10] and is recommended for future capsules to be removed from the Calvert Cliffs Unit 2 reactor vessel.

Table 7-1 Surveillance Capsule Withdrawal Schedule 4.63 8.25E+18 11.16 1.95E+19 27.13 2.44E+19 See Note (d) ---

See Note (e) -- -

Standby(f ---

Notes:

(a) Updated in Capsule 104' dosimetry analysis; see Table 6-4.

(b) EFPY from plant startup.

(c) Updated in Capsule 1040 dosimetry analysis; see Table 6-3.

(d) Capsule 830 should be withdrawn at the next refueling outage after approximately 37 EFPY of plant operation, which is when the fluence on the capsule would equal the projected 60-year (52 EFPY) peak vessel fluence.

(e) Capsule 277' should be withdrawn at a fluence not less than once or greater than twice the peak end of extended life vessel fluence at the vessel inner wall (4.28 x 1019 < fluence in n/cm 2 < 8.56 x 1019). Note that this capsule also satisfies the requirement in the safety evaluation report for Calvert Cliffs License Renewal, that one capsule containing dosimetry is to be removed during the final five years of the extended license. Withdrawal of this capsule at the next refueling outage after approximately 51 EFPY of plant operation would be within the specified fluence range and would equal the projected 80-year (70 EFPY) peak vessel fluence.

(f) Capsule 284' currently has a lead factor less than one. If additional metallurgical data is needed for Calvert Cliffs Unit 2, relocation of this capsule to a higher lead factor location should be considered. However, this can be revisited at a later time; therefore, no recommendations for its withdrawal are given.

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Westinghouse Non-Proprietary Class 3 8-1 8 REFERENCES I. U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Regulatory Guide 1.99, Revision 2, RadiationEmbrittlement of Reactor Vessel Materials, May 1988.

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

3. 10 CFR 50.61, Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events, Federal Register, Volume 60, No. 243, December 19, 1995, effective January 18, 1996.

4. TR-ESS-00 1, Testing and Evaluation of Calvert Cliffs, Units I and 2 Reactor Vessel Materials Irradiation Surveillance Program Baseline Samples for the Baltimore Gas & Electric Co.,

January 1975.

5. CENPD-48, Summary Report on Manufacture of Test Specimens and Assembly of Capsulesfor IrradiationSurveillance of Calvert Cliffs - Unit 2 Reactor Vessel Materials,August 1972.

6. ASTM El185-70, Standard Recommended Practicefor Surveillance Tests for Nuclear Reactor Vessels, American Society for Testing and Materials, 1970.

7. Comprehensive Reactor Vessel Surveillance Program,Revision 5, W. A. Pavinich, July 2009.

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

9. ASTM E208, Standard Test Method for Conducting Drop-Weight Test to Determine Nil-Ductility Transition Temperature of FerriticSteels, American Society for Testing and Materials.

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

H1. Westinghouse Science and Technology Department Procedure RMF 8402, Surveillance Capsule Testing Program, Revision 3.

12. Westinghouse Science and Technology Department Procedure RTU 5004, Opening of CE Surveillance Capsules, Revision 0.

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

14. Westinghouse Science and Technology Department Procedure RMF 8103, Charpy Impact Testing, Revision 2.

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8-2 Westinghouse Non-Proprietary Class 3

15. ASTM E2298-09, Standard Test Method for Instrumented Impact Testing of Metallic Materials, ASTM, 2009.

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

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

18. Westinghouse Science and Technology Department Procedure RTU 5016, Surveillance Capsule Hot Cell Tensile Testing, Revision 0.

19. ASTM E8-09, StandardTest Methods for Tension Testing ofMetallic Materials,ASTM, 2009.

20. ASTM E21-09, Standard Test Methods for Elevated Temperature Tension Tests of Metallic Materials,ASTM, 2009.

21. SwRI-06-7524, Reactor Vessel Material Surveillance Programfor Calvert Cliffs Unit 2 Analysis of 2630 Capsule, September 1985.

22. BAW-2199, Analysis of Capsule 970 Baltimore Gas & Electric Company Calvert Cliffs Nuclear Power Plant Unit No. 2, February 1994.

23. ASTM E853-01 (Reapproved 2008), StandardPracticefor Analysis and Interpretationof Light-Water Reactor Surveillance Results, E706 (IA), ASTM, 2010.

24. ASTM E693-94 (Superseded), Standard Practicefor CharacterizingNeutron Exposures in Iron and Low Alloy Steels in Terms ofDisplacements PerAtom (DPA), E706 (ID), ASTM, 2000.

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

26. WCAP-14040-A, Revision 4, Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves, May 2004.

27. RSICC Computer Code Collection CCC-650, DOORS 3.2. One, Two- and Three Dimensional Discrete OrdinatesNeutron/Photon TransportCode System, April 1998.

28. RSICC Data Library Collection DLC-185, BUGLE-96, Coupled 47 Neutron, 20 Gamma-Ray Group Cross Section Library Derivedfrom ENDF/B-VI for LWR Shielding and Pressure Vessel Dosimetry Applications, March 1996.

29. CA06959, Revision 0, "Reactor Vessel Surveillance Capsule Withdrawal Schedule," G. E.

Gryczkowski, August 2008.

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Westinghouse Non-Proprietary Class 3 A-1 APPENDIX A VALIDATION OF THE RADIATION TRANSPORT MODELS BASED ON NEUTRON DOSIMETRY MEASUREMENTS A.1 NEUTRON DOSIMETRY Comparisons of measured dosimetry results to both the calculated and least-squares adjusted values for all surveillance capsules withdrawn from service to date at Calvert Cliffs Unit 2 are described herein. The sensor sets from these capsules have been analyzed in accordance with the current dosimetry evaluation methodology described in Regulatory Guide 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence" [Reference A-I]. One of the main purposes for presenting this material is to demonstrate that the overall measurements agree with the calculated and least-squares adjusted values to within +/- 20% as specified by Regulatory Guide 1.190, thus serving to validate the calculated neutron exposures previously reported in Section 6.2 of this report.

A.1.1 Sensor Reaction Rate Determinations In this section, the results of the evaluations of the three surveillance capsules analyzed to date as part of the Calvert Cliffs Unit 2 Reactor Vessel Materials Surveillance Program are presented. The capsule designation, location within the reactor, and time of withdrawal of each of these dosimetry sets were as follows:

Capsule Azimuthal Withdrawal Time Irradiation Time Location [ EFPY(8)]

2630 End of Cycle 4 4.63 970 End of Cycle 9 11.16 1040 End of Cycle 18 27.13 Note:

(a) At 2737 MWt.'

The passive neutron sensors included in the evaluations of Surveillance Capsules 263', 970, and 1040 are summarized as follows:

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A-2 Westinghouse Non-Proprietary Class 3 Reaction Of Capsule Capsule Capsule Sensor Material Interest 2630 970 1040 63 60 Copper (Cd) Cu(n,(X) Co X X X 54 54 Iron Fe(n,p) Mn X X X Nickel (Cd) "Ni(n,p)S8Co 5

X X X 46 46 Titanium Ti(n,p) Sc X X X 23 8 Uranium-238* U(n,f)FP X X X 59 60 Cobalt-Aluminum* Co(n,y) Co X X X Note:

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

The capsules also contained sulfur monitors, which were not analyzed because of the short half life of the activation product isotope (32p, 14.3 days). Pertinent physical and nuclear characteristics of the passive neutron sensors analyzed are listed in Table A-1.

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

• the measured specific activity of each monitor,

• the physical characteristics of each monitor,

• the operating history of the reactor,

• the energy response of each monitor, and

• the neutron energy spectrum at the monitor location.

Results from the radiometric counting of the neutron sensors from Capsules 2630 and 970 are documented in References A-2 and A-3, respectively. The radiometric counting of the sensors from Capsule 1040 was carried out by PACE Analytical Services, Inc. In all cases, the radiometric counting followed established ASTM procedures.

In the case of PACE analysis of Capsule 1040, following sample preparation and weighing, the specific activity of each sensor was determined by means of a high-resolution gamma spectrometer. For the iron, nickel, and cobalt-aluminum sensors, these analyses were performed by direct counting of each of the individual samples. In the case of the uranium fission sensors, the analyses were carried out by direct counting preceded by dissolution and chemical separation of cesium, zirconium and ruthenium from the sensor material. PACE reports that the cadmium covered uranium dosimetry samples were a powder mixture of uranium oxide and cadmium oxide. The mixture was weighed, counted, dissolved and the solution was then analyzed by Inductively Coupled Plasma (ICP) to determine the cadmium weight. The cadmium weight was then subtracted from the gross weight to obtain a uranium oxide weight. The titanium wire samples in this project had individually broken into multiple pieces. For each titanium WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 A-3 sample, between 2 and 14 individual pieces were retrieved and used to compose the sample for counting.

For the cadmium covered copper wire dosimetry, PACE was unable to retrieve the copper wire, which had totally amalgamated into the cadmium. For each cadmium covered copper wire, a representative sample portion was weighed, counted, dissolved and the solution was analyzed by ICP to obtain the measurement weight of copper wire.

The irradiation history of the reactor over the irradiation periods experienced by Capsules 2630, 970, and 1040 was based on the monthly power generation of Calvert Cliffs Unit 2 from initial reactor criticality through the end of the dosimetry evaluation period. For the sensor sets utilized in the surveillance capsules, the half-lives of the product isotopes are long enough that a monthly histogram describing reactor operation has proven to be an adequate representation for use in radioactive decay corrections for the reactions of interest in the exposure evaluations. The irradiation history applicable to Capsules 2630, 970, and 1040 is given in Table A-2.

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

A R=

No F Y P Cj[1. - e-tj ] [e"td, ]

Pref where:

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

A = Measured specific activity (dps/g).

No = Number of target element atoms per gram of sensor.

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

Y = Number of product atoms produced per reaction.

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

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

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

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

tj = Length of irradiation periodj (sec).

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A-4 Westinehouse Non-PrODrietary Class 3 tdj = Decay time following irradiation periodj (sec).

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

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

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

These flux values represent the capsule- and cycle-dependent results at the radial and azimuthal center of the respective capsules at the closest axial elevation where the accumulated fluence is equivalent to the axial average fluence over the capsules axial span at the time of withdrawal. The core midplane elevation, which is usually used for the Cj determination, was not used because the back-to-back 1.5-inch baffle horizontal formers at core midplane elevation depress the flux at this axial location. Therefore, the midplane core elevation would provide an underestimated normalization for the calculated capsules' spectrum, which is used in the least-squares analysis. Notice that the flux values in Table A-3 are point evaluations at specific axial elevations and thus differ from flux values in Table 6-1, which are axial span averages. The point flux evaluation is accurate for the computation of Cj.

Prior to using the measured reaction rates in the least-squares evaluations of the dosimetry sensor sets, additional corrections were made to the 23 8U cadmium-covered measurements to account for the presence of 235U impurities in the sensors, as well as to adjust for the build-in of plutonium isotopes over the course of the irradiation. Corrections were also made to the 238U sensor reaction rates to account for gamma-ray-induced fission reactions that occurred over the course of the capsule irradiations. The correction factors corresponding to the Calvert Cliffs Unit 2 fission sensor reaction rates are summarized as follows:

Correction Capsule 2630 Capsule 970 Capsule 1040 235 U Impurity/Pu Build-in 0.8530 0.8107 0.7945 238 U(y,f) 0.8461 0.8461 0.8357 Net 238U Correction 0.7217 0.6859 0.6640 The factors for Capsules 263' and 104' were applied in a multiplicative fashion to the decay-corrected cadmium-covered uranium fission sensor reaction rates. The factors for Capsule 97" were not applied. By comparing calculated activities (which by previous experience should agree to within 15%), it has been deduced that Reference A-3 reports cadmium cover uranium measurements with corrections factors applied. In that sense, the current analysis uses the correction factors from Reference A-3, which explicitly states the use of a photo-fission correction factor. In this regard, Reference A-3 indicates that Nuclear Environmental Services Incorporated (NESI) was asked to perform alpha spectrometry WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 A-5 measurements, which revealed that the CC2-97 0 , I 5G Sh 2 38U dosimeter contains 5277 ppm +/-35% 2 35 U impurity. Reference A-3 does not explicitly mention, however, the specific correction factor that may have been applied to account for the impurity and/or the plutonium build in.

Results of the sensor reaction rate determinations for Capsules 2630, 970, and 104' are given in Table A-4.

In Table A-4, the measured specific activities, decay-corrected saturated specific activities, and computed reaction rates for each sensor are listed. The cadmium-covered fission sensor reaction rates are listed both with and without the applied corrections for 235U impurities, plutonium build-in, and gamma-ray-induced fission effects in the cases of Capsule 263' and 1040.

The bottom compartment bare Uranium and Cobalt monitors' measurements of Capsules 2630, 970, and 1040 are consistently low compared to those in the middle and top compartments. The behavior is attributed to a 0.95-centimeter-thick bracket of Inconel that surrounds the bottom set of dosimeters. The bracket is part of the fixture that attaches the surveillance capsule assembly to the reactor vessel.

A.1.2 Least-Squares Evaluation of Sensor Sets Least-squares adjustment methods provide the capability of combining the measurement data with the corresponding neutron transport calculations resulting in a best-estimate neutron energy spectrum with associated uncertainties. Best-estimates for key exposure parameters such as 4(E > 1.0 MeV) or dpa/s along with their uncertainties are then easily obtained from the adjusted spectrum. In general, the least-squares methods, as applied to surveillance capsule dosimetry evaluations, act to reconcile the measured sensor reaction rate data, dosimetry reaction cross sections, and the calculated neutron energy spectrum within their respective uncertainties. For example, R i+/- 6R = 1(ag+/-5 )@Pg +6 relates a set of measured reaction rates, Ri, to a single neutron spectrum, 4., through the multigroup dosimeter reaction cross sections, ag, each with an uncertainty 6. The primary objective of the least-squares evaluation is to produce unbiased estimates of the neutron exposure parameters at the location of the measurement.

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

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

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

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

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A-6 Westinghouse Non-Proprietary Class 3

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

For the Calvert Cliffs Unit 2 application, the calculated neutron spectrum was obtained from the results of plant-specific neutron transport calculations described in Section 6.2 of this report. The sensor reaction rates were derived from the measured specific activities using the procedures described in Section A. 1.1.

The dosimetry reaction cross sections and uncertainties were obtained from the SNLRML dosimetry cross-section library [Reference A-5]. The SNLRML library is an evaluated dosimetry reaction cross-section compilation recommended for use in LWR evaluations by ASTM Standard E1018, "Application of ASTM Evaluated Cross-Section Data File, Matrix E706 (IIB)" [Reference A-6].

The uncertainties associated with the measured reaction rates, dosimetry cross sections, and calculated neutron spectrum were input to the least-squares procedure in the form of variances and covariances. The assignment of the input uncertainties followed the guidance provided in ASTM Standard E944, "Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance" [Reference A-7].

The following provides a summary of the uncertainties associated with the least-squares evaluation of the Calvert Cliffs Unit 2 surveillance capsule sensor sets.

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

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

Reaction Uncertainty 63 60 Cu(n,a) Co 5%

54 Fe(n,p) 4nMn 5%

58 58 Ni(n,p) Co 5%

46 46 Ti(n,p) Sc 5%

238 U(n,f)FP 10%

59 60 Co(ny) Co 5%

These uncertainties are given at the 1a level.

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Westinghouse Non-Proprietary Class 3 A-7 Dosimetry Cross-Section Uncertainties The reaction rate cross sections used in the least-squares evaluations were taken from the SNLRML library. This data library provides reaction cross sections and associated uncertainties, including covariances, for 66 dosimetry sensors in common use. Both cross sections and uncertainties are provided in a fine multigroup structure for use in least-squares adjustment applications. These cross sections were compiled from recent cross-section evaluations, and they have been tested for accuracy and consistency for least-squares evaluations. Further, the library has been empirically tested for use in fission spectra determination, as well as in the fluence and energy characterization of 14 MeV neutron sources.

For sensors included in the Calvert Cliffs Unit 2 surveillance program, the following uncertainties in the fission spectrum averaged cross sections are provided in the SNLRML documentation package.

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

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

58 Ni(n,p)55Co 4.49-4.56%

46 Ti(n,p) 46Sc 4,51-4.87%

238 U(n,f)' 3 7Cs 0.54-0.64%

59 Co(n,y) 6°Co 0.79-3.59%

These tabulated ranges provide an indication of the dosimetry cross-section uncertainties associated with the sensor sets used in LWR irradiations.

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

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

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

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A-8 Westinghouse Non-Proprietary Class 3 Pgg, = [P- 0]6 gg, + 0 eH where H -(g_-g),)

2 2y The first term in the correlation matrix equation specifies purely random uncertainties, while the second term describes the short-range correlations over a group range y (0 specifies the strength of the latter term). The value of 5 is 1.0 when g = g', and is 0.0 otherwise.

The set of parameters defining the input covariance matrix for the Calvert Cliffs Unit 2 calculated spectra was as follows:

Flux Normalization Uncertainty (R,) 15%

Flux Group Uncertainties (Rg, Rg,)

(E > 0.0055 MeV) 15%

(0.68 eV < E < 0.0055 MeV) 25%

(E < 0.68 eV) 50%

Short Range Correlation (0)

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

(E > 0.0055 MeV) 6 (0.68 eV < E < 0.0055 MeV) 3 (E < 0.68 eV) 2 A.1.3 Comparisons of Measurements and Calculations Results of the least-squares evaluations of the dosimetry from the Calvert Cliffs Unit 2 surveillance capsules withdrawn to date are provided in Tables A-5 and A-6. In Table A-5, measured, calculated, and best-estimate values for sensor reaction rates are given for each capsule. Also provided in this tabulation are ratios of the measured reaction rates to both the calculated and least-squares adjusted reaction rates.

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

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Westinghouse Non-Proprietary Class 3 A-9 The data comparisons provided in Tables A-5 and A-6 show that the adjustments to the calculated spectra are relatively small and well within the assigned uncertainties for the calculated spectra, measured sensor reaction rates, and dosimetry reaction cross sections. Further, these results indicate that the use of the least-squares evaluation results in a reduction in the uncertainties associated with the exposure of the surveillance capsules. From Section 6.4 of this report, it may be noted that the uncertainty associated with the unadjusted calculation of neutron fluence (E > 1.0 MeV) and iron atom displacements at the surveillance capsule locations is specified as 13% at the 1c level. From Table A-8, it is noted that the corresponding uncertainties associated with the least-squares adjusted exposure parameters have been reduced to 4.0% for neutron flux (E > 1.0 MeV) and 3.1% for iron atom displacement rate. Again, the uncertainties from the least-squares evaluation are at the I a level.

Further comparisons of the measurement results (from Tables A-5 and A-6) with calculations are given in Tables A-7 and A-8. These comparisons are given on two levels. In Table A-7, calculations of individual threshold sensor reaction rates are compared directly with the corresponding measurements. These threshold reaction rate comparisons provide a good evaluation of the accuracy of the fast neutron portion of the calculated energy spectra. In Table A-8, calculations of fast neutron exposure rates in terms of 4(E > 1.0 MeV) and dpa/s are compared with the best-estimate results obtained from the least-squares evaluation of the capsule dosimetry results. These two levels of comparison yield consistent and similar results with all measurement-to-calculation comparisons falling well within the 20% limits specified as the acceptance criteria in Regulatory Guide 1.190.

In the case of the direct comparison of measured and calculated sensor reaction rates, for the individual threshold foils considered in the least-squares analysis, the average M/C comparisons for fast neutron reactions range from 0.69 to 1.19 for the 31 samples included in the data set. The overall average M/C ratio for the entire set of Calvert Cliffs Unit 2 data is 0.94 with an associated standard deviation of 9.9%.

In the comparisons of best-estimate and calculated fast neutron exposure parameters, the corresponding BE/C comparisons for the capsule data sets range from 0.88 to 0.95 for neutron flux (E > 1.0 MeV) and from 0.90 to 0.95 for iron atom displacement rate. The overall average BE/C ratios for neutron flux (E > 1.0 MeV) and iron atom displacement rate are 0.91 with a standard deviation of 4.0% and 0.92 with a standard deviation of 3.1%, respectively.

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

Note that for Capsule 2630, two of the three cadmium-covered Uranium monitors have not been included in the least-squares analysis. Two cadmium-covered Uranium monitors were discarded because of the poor condition of the specimens as indicated in Reference A-2 (monitors were contaminated with cadmium and the cadmium cover disintegrated at some unknown time during irradiation). For remaining cadmium-covered Uranium monitor, for which the cadmium cover also disintegrated at some unknown time during irradiation, Combustion Engineeering, Inc. made an atomic absorption determination that was included in the analysis.

Note that for Capsule 970, the Copper, Titanium and cadmium-covered Cobalt monitors have not been included in the least-squares analysis. The Copper, Titanium and Cobalt monitors are not included WCAP-17501-NP February 2012 Revision 0

A-10 Westinahouse Non-Pronrietarv Class 3 because their countings are 4.1a, 5a and 5.1cr high with respect to similar plants' measurements, respectively. No bare Cobalt monitors results were reported in Reference A-3.

Note that for Capsule 104', the Titanium and bare Uranium monitors are not included in the least-squares analysis. The Titanium monitor has been discarded because the counting is 6c high with respect to similar plants' measurements. The cadmium-covered Uranium monitor was not discarded because these monitors were -2.3o with respect to similar plants' measurements. However, the original uranium metal foil oxidized and forms a powder mixed with cadmium oxide powder. In the analysis, uranium dioxide, U0 2, has been assumed for the oxidation state of the oxide.

In all capsules, the bare Uranium monitors are not included because the U-235 impurity content and the thermal flux on the capsule are not known with enough accuracy to correct the measurement readings.

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Westinghouse Non-Proprietary Class 3 A-11 Table A-I Nuclear Parameters Used in the Evaluation of Neutron Sensors Notes:

(a) The 90% response range is defined such that, in the neutron spectrum characteristic of the Calvert Cliffs Unit 2 surveillance capsules, approximately 90% of the sensor response is due to neutrons in the energy range specified with approximately 5% of the total response due to neutrons with energies below the lower limit and 5% of the total response due to neutrons with energies above the upper limit.

(b) For Capsule 1040, the Uranium measurements were reported per unit mass of Uranium oxide. Thus, the analysis assumes U0 2, or an equivalent target atom fraction of 0.881572.

(c) For Capsule 2630 and 970, the Cobalt measurement are reported per gram of Cobalt. For Capsule 1040, the measurements are reported per gram of Cobalt-Aluminum and a Cobalt content of 0.17 a/o is assumed.

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A-12 Westinahouse Non-Proorietarv Class 3 Table A-2 Monthly Thermal Generation during the First Eighteen Fuel Cycles of the Calvert Cliffs Unit 2 Reactor (Reactor Power of 2560 MWt from 12/07/1976 to 10/18/1977; 2700 MWt from 10/19/1977 to 2/22/2009; and, 2737 MWt from 3/17/2009 to present)

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

Nov-76 18432 Dec-78 1883736 Jan-81 589032 Feb-83 1608146 Dec-76 491459 Jan-79 1314144 Feb-81 0 Mar-83 1890043 Jan-77 1355305 Feb-79 1711886 Mar-81 1551092 Apr-83 1933074 Feb-77 1501901 Mar-79 1891642 Apr-81 1421105 May-83 1930482 Mar-77 1800499 Apr-79 1933762 May-81 1994396 Jun-83 1933215 Apr-77 1763451 May-79 1866305 Jun-81 1854536 Jul-83 1989315 May-77 816108 Jun-79 1758672 Jul-81 1739847 Aug-83 1545196 Jun-77 1604751 Jul-79 1735992 Aug-81 1743011 Sep-83 1586667 Jul-77 1824276 Aug-79 1700352 Sep-81 1335765 Oct-83 1296083 Aug-77 1450906 Sep-79 1417824 Oct-81 1961940 Nov-83 1568846 Sep-77 1785016 Oct-79 1879902 Nov-81 1803944 Dec-83 1822497 Oct-77 1283701 Nov-79 0 Dec-81 1972804 Jan-84 1996767 Nov-77 1913998 Dec-79 1422360 Jan-52 1959795 Feb-84 1782217 Dec-77 1910347 Jan-80 1359504 Feb-82 905239 Mar-84 1998385 Jan-78 1876867 Feb-80 1779408 Mar-82 1974241 Apr-84 1626228 Feb-78 1703138 Mar-80 1929096 Apr-82 1881782 May-84 0 Mar-78 1856585 Apr-80 1863000 May-82 1976927 Jun-84 0 Apr-78 1262304 May-80 1922616 Jun-82 1852073 Jul-84 1211910 May-78 1260295 Jun-80 1876608 Jul-82 1927212 Aug-84 1659447 Jun-78 1365725 Jul-80 1723032 Aug-82 1367000 Sep-84 1469994 Jul-78 1079827 Aug-80 1820880 Sep-82 1717000 Oct-84 1866319 Aug-78 1804226 Sep-80 1529928 Oct-82 905000 Nov-84 1874178 Sep-78 1515413 Oct-80 1711368 Nov-82 0 Dec-84 1998678 Oct-78 863784 Nov-80 1694520 Dec-82 0 Jan-85 1950430 Nov-78 1561226 Dec-80 1349784 Jan-83 1296481 Feb-85 1801273 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 A-13 Table A-2 (Continued) Monthly Thermal Generation during the First Eighteen Fuel Cycles of the Calvert Cliffs Unit 2 Reactor Thermal Thermal Thermal Thermal Month- Generation Month- Generation Month- Generation Month- Generation Year (MWt-hr) Year (MWt-hr) Year (MWt-hr) Year (MWt-hr)

Mar-85 1989882 Apr-87 0 May-89 0 Jun-91 1086403 Apr-85 1577934 May-87 0 Jun-89 0 Jul-91 2000576 May-85 1257574 Jun-87 0 Jul-89 0 Aug-91 2006340 Jun-85 1934720 Jul-87 1435223 Aug-89 0 Sep-91 1920654 Jul-85 1485446 Aug-87 1997667 Sep-89 0 Oct-91 1162312 Aug-85 1634150 Sep-87 1895948 Oct-89 0 Nov-91 415426 Sep-85 1929517 Oct-87 1813391 Nov-89 0 Dec-91 2005781 Oct-85 1756180 Nov-87 1804125 Dec-89 0 Jan-92 1843271 Nov-85 0 Dec-87 1848160 Jan-90 0 Feb-92 1872867 Dec-85 1550132 Jan-88 1952162 Feb-90 0 Mar-92 1187755 Jan-86 1984432 Feb-88 1654239 Mar-90 0 Apr-92 1707340 Feb-86 1678177 Mar-88 0 Apr-90 0 May-92 1995905 Mar-86 1907013 Apr-88 1643667 May-90 0 Jun-92 1498563 Apr-86 1937020 May-88 1863681 Jun-90 0 Jul-92 1557529 May-86 1690501 Jun-88 1938335 Jul-90 0 Aug-92 1757061 Jun-86 1782055 Jul-88 2001391 Aug-90 0 Sep-92 1832651 Jul-86 1582756 Aug-88 1945508 Sep-90 0 Oct-92 1784321 Aug-86 1926214 Sep-88 1921417 Oct-90 0 Nov-92 1937690 Sep-86 1553646 Oct-88 1941005 Nov-90 0 Dec-92 1995474 Oct-86 1991848 Nov-88 1931845 Dec-90 0 Jan-93 1999836 Nov-86 1932914 Dec-88 2002776 Jan-91 0 Feb-93 1610920 Dec-86 2002060 Jan-89 1806093 Feb-91 0 Mar-93 0 Jan-87 1979543 Feb-89 1802081 Mar-91 0 Apr-93 0 Feb-87 1795300 Mar-89 1034562 Apr-91 0 May-93 0 Mar-87 1618167 Apr-89 0 May-91 1146357 Jun-93 802275 WCAP-17501-NP February 2012 Revision 0

A-14 Westinahouse Non-ProDrietarv Class 3 Table A-2 (Continued) Monthly Thermal Generation during the First Eighteen Fuel Cycles of the Calvert Cliffs Unit 2 Reactor Thermal Thermal Thermal Thermal Month- Generation Month- Generation Month- Generation Month- Generation Year (MWt-hr) Year (MWt-hr) Year (MWt-hr) Year (MWt-hr)

Jul-93 1899709 Aug-95 1991189 Sep-97 1919600 Oct-99 2006511 Aug-93 1997329 Sep-95 1871749 Oct-97 1989880 Nov-99 1939312 Sep-93 1942142 Oct-95 1995146 Nov-97 1937688 Dec-99 2003142 Oct-93 1944012 Nov-95 1942200 Dec-97 2006499 Jan-00 2006535 Nov-93 1931211 Dec-95 2006715 Jan-98 2006272 Feb-00 1374862 Dec-93 2002102 Jan-96 2003930 Feb-98 1812439 Mar-00 2006283 Jan-94 1513287 Feb-96 1730265 Mar-98 2003831 Apr-00 1938535 Feb-94 1799244 Mar-96 1683467 Apr-98 1941748 May-00 2006644 Mar-94 2005485 Apr-96 1929940 May-98 2006778 Jun-00 1936548 Apr-94 1941686 May-96 2002384 Jun-98 1931416 Jul-00 2000175 May-94 1508185 Jun-96 1933449 Jul-98 1476731 Aug-00 2001498 Jun-94 1941922 Jul-96 2000334 Aug-98 1504278 Sep-00 1933488 Jul-94 1823026 Aug-96 1982088 Sep-98 1925485 Oct-00 2006051 Aug-94 1435535 Sep-96 1922791 Oct-98 2007018 Nov-00 1941425 Sep-94 1410192 Oct-96 1987401 Nov-98 1940513 Dec-00 2003330 Oct-94 1748712 Nov-96 1739522 Dec-98 2006797 Jan-01 2006171 Nov-94 1585574 Dec-96 1985257 Jan-99 2006668 Feb-01 1811473 Dec-94 2004274 Jan-97 1980479 Feb-99 1810695 Mar-01 995350 Jan-95 1650542 Feb-97 1762417 Mar-99 743157 Apr-01 0 Feb-95 1786954 Mar-97 780849 Apr-99 0 May-01 1049668 Mar-95 1104057 Apr-97 0 May-99 1427240 Jun-01 1863146 Apr-95 0 May-97 459069 Jun-99 1941987 Jul-01 2006856 May-95 648873 Jun-97 1918099 Jul-99 2006611 Aug-01 1942074 Jun-95 1936904 Jul-97 1985028 Aug-99 1998445 Sep-01 1937954 Jul-95 1926252 Aug-97 1974675 Sep-99 1933855 Oct-01 1833455 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 A-15 Table A-2 (Continued) Monthly Thermal Generation during the First Eighteen Fuel Cycles of the Calvert Cliffs Unit 2 Reactor Thermal Thermal Thermal Thermal Month- Generation Month- Generation Month- Generation Month- Generation Year (MWt-hr) Year (MWt-hr) Year (MWt-hr) Year (MWt-hr)

Nov-01 1934884 Dec-03 1999078 Jan-06 1960274 Feb-08 1878107 Dec-01 2003230 Jan-04 1841771 Feb-06 1813540 Mar-08 2003908 Jan-02 2003631 Feb-04 1877495 Mar-06 2007945 Apr-08 1942948 Feb-02 1808078 Mar-04 2002627 Apr-06 1943236 May-08 2000270 Mar-02 2005211 Apr-04 1942145 May-06 2006377 Jun-08 1942170 Apr-02 1933062 May-04 2003942 Jun-06 1943243 Jul-08 1996364 May-02 2002801 Jun-04 1935074 Jul-06 2007395 Aug-08 1988356 Jun-02 1941315 Jul-04 2007078 Aug-06 2007889 Sep-08 1929826 Jul-02 2002929 Aug-04 2003650 Sep-06 1942947 Oct-08 2001860 Aug-02 2001072 Sep-04 1930069 Oct-06 1981674 Nov-08 1941097 Sep-02 1935979 Oct-04 2005176 Nov-06 1606071 Dec-08 2003359 Oct-02 2006415 Nov-04 1938881 Dec-06 1966267 Jan-09 2006642 Nov-02 1940365 Dec-04 2008135 Jan-07 2007880 Feb-09 1412135 Dec-02 2004611 Jan-05 2008083 Feb-07 1559723 Mar-09 879474 Jan-03 2004240 Feb-05 1388707 Mar-07 0 Apr-09 1942544 Feb-03 901908 Mar-05 978244 Apr-07 1683654 May-09 2006957 Mar-03 0 Apr-05 1943343 May-07 2007759 Jun-09 1937407 Apr-03 491785 May-05 2008062 Jun-07 1939994 Jul-09 2003084 May-03 1912832 Jun-05 1939850 Jul-07 2006588 Aug-09 2007882 Jun-03 1941153 Jul-05 2001291 Aug-07 1999215 Sep-09 1958165 Jul-03 2003747 Aug-05 2000495 Sep-07 1943055 Oct-09 2024085 Aug-03 2000819 Sep-05 1941968 Oct-07 2007775 Nov-09 1960413 Sep-03 1934305 Oct-05 2007848 Nov-07 1943136 Dec-09 2025522 Oct-03 2002912 Nov-05 1943291 Dec-07 2004041 Jan-10 2025517 Nov-03 1938746 Dec-05 2004789 Jan-08 2007492 Feb-10 1176589 WCAP-17501-NP February 2012 Revision 0

A-16 Westinghouse Non-Proprietary Class 3 Table A-2 (Continued) Monthly Thermal Generation during the First Eighteen Fuel Cycles of the Calvert Cliffs Unit 2 Reactor Thermal Month- Generation Year (MWt-hr)

Mar-10 2023060 Apr-10 1959776 May-10 2013775 Jun-10 1922715 Jul-10 1983103 Aug-10 2004861 Sep-10 1956753 Oct-10 2010481 Nov-10 1952412 Dec-10 2017691 Jan-11 2025729 Feb-11 843462 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 A-17 Table A-3 Surveillance Capsule Flux for Cj Factors Calculation 2

(p(E > 1.0 MeV) In/cru-sj Cycle Capsule 2630 Capsule 970 Capsule 1041 Length Fuel Cycle [EFPSHa)I z(b) - 14.737 cm z(b) - 15.671cm z(b) = - 16.202 cm 1 4.37E+07 5.38E+10 5.39E+10 3.90E+10 2 2.83E+07 5.48E+10 5.50E+10 3.97E+10 3 2.97E+07 6.03E+10 6.05E+10 4.47E+10 4 4.45E+07 5.80E+10 5.81E+10 4.18E+10 5 3.66E+07 5.92E+10 4.38E+10 6 3.60E+07 6.43E+10 4.65E+10 7 3.80E+07 6.13E+10 4.40E+10 8 4.77E+07 4.75E+10 3.23E+10 9 4.78E+07 4.57E+ 10 3.05E+10 10 4.97E+07 2.29E+10 11 5.49E+07 1.94E+ 10 12 5.43E+07 2.13E+10 13 5.69E+07 2.03E+10 14 5.40E+07 2.16E+ 10 15 5.67E+07 2.17E+ 10 16 5.99E+07 1.95E+10 17 5.86E+07 2.05E+ 10 18 5.87E+07 2.14E+ 10 Average --- 5.66E+10 5.55E+10 2.86E+10 Notes:

(a) At 2737 MWt.

(b) Elevation from core midplane.

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A-18 Westinizhouse Non-Proorietarv Class 3 A- 18 Westinchouse Non-Proorietarv Class 3 Table A-3 (Continued) Surveillance Capsule Cj Factors Cycle Cj Length Fuel Cycle IEFPS(a)] Capsule 2630 Capsule 970 Capsule 1040 1 4.37E+07 0.950 0.972 1.362 2 2.83E+07 0.969 0.990 1.388 3 2.97E+07 1.066 1.090 1.561 4 4.45E+07 1.024 1.047 1.461 5 3.66E+07 1.067 1.530 6 3.60E+07 1.158 1.626 7 3.80E+07 1.105 1.538 8 4.77E+07 0.855 1.128 9 4.78E+07 0.823 1.066 10 4.97E+07 0.799 11 5.49E+07 0.678 12 5.43E+07 0.744 13 5.69E+07 0.710 14 5.40E+07 0.755 15 5.67E+07 0.759 16 5.99E+07 0.680 17 5.86E+07 0.715 18 5.87E+07 0.747 Average --- 1.000 1.000 1.000 Note:

(a) At 2737 MWt.

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Westinghouse Non-Proprietary Class 3 A-19 Table A-4a Measured Sensor Activities and Reaction Rates for Surveillance Capsule 2630 Measured Activity(a) Saturated Activity Reaction Rate(b)

Reaction Location (dps/g) (dps/g) (rps/atom) 63 60 Cu (n,c ) Co Top 2.69E+05 6.24E+05 9.51E-17 Middle 2.68E+05 6.21E+05 9.48E-17 Bottom 2.87E+05 6.65E+05 1.OIE-16 Average 9.71E-17 54 54 Fe (n,p) Mn Top 4.OOE+06 4.74E+06 7.51 E-15 Middle 3.76E+06 4.45E+06 7.07E-15 Bottom 3.85E+06 4.56E+06 7.24E- 15 Average 7.27E-15 58 58 Ni (n,p) Co Top 5.35E+07 6.08E+07 8.71E-15 Middle 5.1OE+07 5.79E+07 8.29E- 15 Bottom 5.69E+07 6.47E+07 9.26E-15 Average 8.75E-15 46 Ti(n,p) 46 Sc Top 1.03E+06 1.17E+06 1.12E- 15 Middle 1.07E+06 1.22E+06 1.17E- 15 Bottom 9.16E+05 1.04E+06 L.OOE- 15 Average 1.1OE-15 23 8 U (n,f) 137Cs Top 6.59E+05 6.58E+06 4.91E-14 Middle 6.94E+05 6.93E+06 5.17E- 14 Bottom 5.71E+05 5.70E+06 4.25E-14 Average 4.78E-14 238 U (n,f) 13Cs (Cd) Top 1.76E+05 1.75E+06 1.31E-14 Middle 3.78E+05 3.77E+06 2.82E-14 Bottom 1.16E+05 1.1 5E+06 8.62E- 15 Middle('c) 2.82E-14 235 2 9 Corrected Middle Including U, " Pu, and y fission corrections(c) 2.03E-14 59 6 Co (n,,)O Co Top 1.48E+10 3.42E+10 3.35E-12 Middle 1.53E+10 3.55E+l0 3.48E-12 Bottom 1.08E+10 2.51E+10 2.46E- 12 Average 3.09E-12 59 60 Co (nY) Co (Cd) Top 1.83E+09 4.24E+09 4.15E- 13 Middle 1.60E+09 3.70E+09 3.62E-13 Bottom 1.77E+09 4.09E+09 4.01E-13 Average 3.92E-13 Notes:

(a) Measured specific activities are indexed to a counting date of 10/16/1982.

(b) Reaction rates referenced to Rated Reactor Power of 2737 MWt.

(c) Middle monitor weight was determined by atomic absorption. See also Section A.1.1 WCAP-1750 1-NP February 2012 Revision 0

A-20 Westinghouse Non-Provrietarv Class 3 Table A-4b Measured Sensor Activities and Reaction Rates for Surveillance Capsule 970 Measured Activity(a) Saturated Activity Reaction Rate(b)

Reaction Location (dps/g) (dps/g) (rps/atom) 63 Cu (ne() 60CO Top 4.87E+05 9.14E+05 1.40E- 16 Middle 4.03E+05 7.57E+05 1.15E-16 Bottom 4.05E+05 7.60E+05 1.16E-16 Average 1.24E-16 54 54 Fe (n,p) Mn Top 2.98E+06 5.08E+06 8.08E-15 Middle 2.70E+06 4.60E+06 7.33E-15 Bottom 2.65E+06 4.51E+06 7.17E- 15 Average 7.53E-15 58 58 Ni (n,p) Co Top 4.3 1E+07 5.33E+07 7.64E-15 Middle 4.81E+07 5.95E+07 8.52E-15 Bottom 4.98E+07 6.16E+07 8.82E- 15 Average 8.33E-15 46 Ti(n,p) 46Sc Top 1.36E+06 1.71 E+06 1.65E-15 Middle 1.14E+06 1.44E+06 1.39E- 15 Bottom 1.23E+06 1.55E+06 1.49E- 15 Average 1.51E-15 238 37 U (n,f) 1 Cs Top 1.83E+06 8.72E+06 5.73E-14 Middle 1.62E+06 7.72E+06 5.07E- 14 Bottom 1.27E+06 6.02E+06 3.95E-14 Average 4.92E-14 238 U (n,f)137Cs (Cd) (c) Top 7.87E+05 3.74E+06 2.46E-14 Middle 7.72E+05 3.67E+06 2.41E-14 Bottom 7.98E+05 3.80E+06 2.49E- 14 Average _ 2.45E-14 235 239 Corrected Average Including U, pu, and y fission corrections 2.45E-14 9 60

' Co (n,y) Co Top NA NA NA Middle NA NA NA Bottom NA NA NA Average NA 59 60 Co (n,y) Co (Cd) Top 1.75E+10 3.28E+10 3.21E-12 Middle 1.61E+10 3.02E+ 10 2.95E-12 Bottom 1.15E+10 2.16E+10 2.11E-12 Average 2.76E-12 Notes:

(a) Measured specific activities are indexed to a counting date of 02/20/1993.

(b) Reaction rates referenced to Rated Reactor Power of 2737 MWt.

(c) See Section A. 1.1. It has been assumed that the measurements were reported in Reference 22 with corrections.

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Westinghouse Non-Proprietary Class 3 A-21 Table A-4c Measured Sensor Activities and Reaction Rates for Surveillance Capsule 1040 Measured Activity(a) Saturated Activity Reaction Rate(b)

Reaction Location (dps/g) (dps/g) (rps/atom) 63 6 Cu (n,ct) "Co Top 1.86E+05 2.95E+05 4.50E-17 Middle 1.69E+05 2.68E+05 4.09E- 17 Bottom 1.69E+05 2.68E+05 4.09E- 17 Average 4.22E-17 4 54 1 Fe (n,p) Mn Top 1.21E+06 2.59E+06 4.12E- 15 Middle 1.06E+06 2.27E+06 3.61E-15 Bottom 1.05E+06 2.25E+06 3.58E-15 Average 3.77E-15 58 Ni (n,p) "8Co Top 4.61E+06 4.01E+07 5.75E- 15 Middle 3.85E+06 3.35E+07 4.80E-15 Bottom 4.07E+06 3.54E+07 5.07E-15 Average 5.21E-15 46 Ti(n,p) 46 Sc Top 1.37E+05 8.96E+05 8.63E-16 Middle 1.15E+05 7.52E+05 7.25E- 16 Bottom 1.16E+05 7.59E+05 7.31E-16 Average 7.73E-16 238 U (n,f) 137 Cs Top 1.81E+06 4.43E+06 3.30E-14 Middle 1.55E+06 3.80E+06 2.83E-14 Bottom 1.09E+06 2.67E+06 1.99E- 14 Average 2.71E-14 23 8 03 U (n,f) 1 Ru Top 1.83E+05 7.08E+06 5.07E-14 Middle 1.56E+05 6.03E+06 4.32E-14 Bottom 1.13E+05 4.37E+06 3.13E- 14 Average 4.17E-14 238 U (n,f) 95Zr Top 5.70E+05 6.04E+06 5.26E- 14 Middle 4.66E+05 4.94E+06 4.30E-14 Bottom 3.17E+05 3.36E+06 2.93E-14 Average 4.16E-14 38 37 Z U (n,f) Cs (Cd) Top 6.92E+05 1.69E+06 1.26E-14 Middle 6.05E+05 1.48E+06 1.IOE-14 Bottom 5.34E+05 1.31E+06 9.74E-15 Average 1.I1 E-14 23 5 239 Corrected Average Including U, pu, and y fission corrections(c) 7.39E-15 WCAP-17501-NP February 2012 Revision 0

A-22 Westinehouse Non-Prot)rietarv Class 3 Table A-4c(Continued) Measured Sensor Activities and Reaction Rates for Surveillance Capsule 1040 23 03 8U (n,f) 1 Ru (Cd) Top 5.19E+04 2.01E+06 1.44E- 14 Middle 5.31E+04 2.05E+06 1.47E- 14 Bottom 5. 13E+04 1.98E+06 1.42E- 14 Average 1.44E-14 235 239 Corrected Average Including U, Pu, and y fission corrections(c) 9.58E-15 238 U (n,f) 95Zr (Cd) Top 1.87E+05 1.98E+06 1.73E-14 Middle 1.59E+05 1.69E+06 1.47E- 14 Bottom 1.57E+05 1.66E+06 1.45E-14 Average 1.55E-14 235 239 Corrected Average Including U, pu, and y fission corrections(c) 1.03E-14 59 60 Co (n,y) Co Top 1.40E+07 2.22E+07 1.28E-12 Middle 1.33E+07 2.11 E+07 1.21E-12 Bottom 9.75E+06 1.55E+07 8.89E- 13 Average 1.13E-12 59 60 Co (n,y) Co (Cd) Top 2.06E+06 3.26E+06 1.88E-13 Middle 2.02E+06 3.20E+06 1.84E-13 Bottom 1.84E+06 2.92E+06 1.68E-13 Average 1.80E-13 Notee$:

(a) Measured specific activities are indexed to a counting date of 08/22/2011. Uranium measurements are reported per gram of Uranium Oxide while Cobalt measurements are reported per gram of Cobalt-Aluminum.

(b) Reaction rates referenced to Rated Reactor Power of 2737 MWt.

(c) See Section A. 1.1 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 A-23 Table A-5 Comparison of Measured, Calculated, and Best-Estimate Reaction Rates at the Surveillance Capsule Center Capsule 2630 Reaction Rate Irps/atom]

Reaction Measured Calculated Best Estimate M/C MIBE 63 Cu(n,a) 6°Co 9.71E-17 8.15E-17 9.03E-17 1.19 1.08 54 Fe(n,p) 54 Mn 7,27E- 15 7.47E- 15 7.23E- 15 0.97 1.01 58 5t Ni(n,p) Co 8.75E-15 9.74E- 15 9.18E-15 0.90 0.95 59 Co (n,y) 6°Co 3.09E-12 3.01E-12 3.09E- 12 1.03 1.00 59 60 Co(Cd)(n,y) Co 3.92E- 13 5.26E-13 3.97E- 13 0.75 0.99 238 U(Cd)(n,f) 137Cs 2.03E-14 2.54E-14 2.31E-14 0.80 0.88 Capsule 970 Reaction Rate Irps/atom]

Reaction Measured Calculated Best Estimate M/C M/BE 54 Fe(n,p)14Mn 7.53E-15 7.34E-15 7.12E- 15 1.02 1.05 58 58Ni(n,p) Co 8.33E-15 9.58E-15 8.92E-15 0.87 0.93 238 37 U(Cd)(n,f) 1 Cs 2.45E-14 2.50E-14 2.39E-14 0.98 1.03 Capsule 1040 Reaction Rate Irps/atoml Reaction Measured Calculated Best Estimate M/C MIBE 63 60 Cu(n, .) Co 4.22E-17 4.67E-17 4.31E-17 0.90 0.98 54 54 Fe(n,p) Mn 3.77E- 15 3.98E- 15 3.71 E- 15 0.95 1.02 58 58 Ni(n,p) Co 5.211E-15 5.17E- 15 4.90E- 15 1.01 1.06 59 Co(n,y)6°Co 1.13E-12 1.46E-12 1.13E-12 0.77 1.00 59 6 Co(n,y) °Co (Cd) 1.80E-13 2.57E-13 1.82E-13 0.70 0.99 238 U(Cd)(n,f) FP 9.08E-15 1.31E-14 1.19E-14 0.69 0.76 Note:

See Section A. 1.2 for details describing the best-estimate (BE) reaction rates.

WCAP-17501-NP February 2012 Revision 0

A-24 Westinghouse Non-Proprietary Class 3 Table A-6 Comparison of Calculated and Best Estimate Exposure Rates at the Surveillance Capsule Center q_(E > 1.0 MeV) [n/cm 2-s]

Capsule ID Calculated Best Estimate Uncertainty (la) BE/C 2630 5.65E+10 5.00E+10 6 0.88 970 5.54E+10 5.31E+10 6 0.95 1040 2.86E+10 2.58E+10 6 0.90 Note:

Calculated results are based on the synthesized transport calculations following the completion of each respective capsule's irradiation period and are the average neutron exposure rate over the irradiation period for each capsule at a reference thermal power level of 2737 MWt. See Section A. 1.2 for details describing the BE exposure rates.

Iron Atom Displacement Rate [dpa/s]

Capsule ID Calculated Best Estimate Uncertainty (1a) BE/C 2630 8.09E- 11 7.27E- 11 5 0.90 970 7.94E- 11 7.61E-11 6 0.95 1040 4.12E-11 3.72E-11 5 0.90 Note:

Calculated results are based on the synthesized transport calculations following the completion of each respective capsule's irradiation period and are the average neutron exposure rate over the irradiation period for each capsule at a reference thermal power level of 2737 MWt. See Section A.1.2 for details describing the BE exposure rates.

WCAP-1750 1-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 A-25 Table A-7 Comparison of Measured/Calculated (M/C) Sensor Reaction Rate Ratios for Fast Neutron Threshold Reactions M/C Ratio Reaction Capsule 2630 Capsule 970 Capsule 1040 63 6 Cu(n, () °Co 1.19 Rejected 0.90 54 54 Fe(n,p) Mn 0.97 1.02 0,95 58 Ni(n,p)58Co 0.90 0.87 1.01 238 U(Cd)(n,f) FP 0.80 0.98 0.69 Average 0.97 0.96 0.89

% Standard Deviation 17 8.1 16 Note:

The overall average MIC ratio for the set of 31 sensor measurements is 0.94 with an associated standard deviation of 9.9%.

Table A-8 Comparison of Best-Estimate/Calculated (BE/C) Exposure Rate Ratios BE/C Ratio Capsule Location 4(E > 1.0 MeV) dpa/s 2630 0.88 0.90 970 0.95 0.95 1040 0.90 0.90 Average 0.91 0.92

% Standard Deviation 4.0 3.1 WCAP- 17501-NP February 2012 Revision 0

A-26 Westinghouse Non-Proprietarv Class 3 A.2 REFERENCES A-i Regulatory Guide RG- 1.190, Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence, U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, March 2001.

A-2 SWRI-06-7524, Reactor Vessel MaterialSurveillance Programfor Calvert Cliffs Unit 2 Analysis of 263' Capsule, E. B. Norris, September 1985.

A-3 BAW-2199, Analysis of the Calvert Cliffs Unit No. 2 Reactor Vessel Surveillance Capsule Withdrawnfrom the 970 Location of the Beltline Region, A. L. Lowe et al., February 1994.

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

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

A-6 ASTM Standard E1018-09, Application of ASTM Evaluated Cross-Section Data File, Matrix E706 (JIB), 2010.

A-7 ASTM Standard E944-08, Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, 2010.

WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 B-1 APPENDIX B LOAD-TIME RECORDS FOR CHARPY SPECIMEN TESTS

• "IXX" denotes Lower Shell Course Plate D-8907-2, Longitudinal Orientation

• "3XX" denotes Weld Material

• "4XX" denotes Heat-Affected-Zone Material

" "6XX" denotes Standard Reference Material (SRM)

Note that the instrumented Charpy data is for information only. The instrumented tup (striker) was not calibrated per ASTM E2298-09.

WCAP-17501-NP February 2012 Revision 0

B-2 Westinahouse Non-Proprietary Class 3 0000.00 4000.00 t, 2000.00 2000.00 1000.00 C,

j kLtA6 6 6,, kPAtALAA A%-MW .. %A;AA

.&6A A.k A4&AA.&k hA4-A A. .4. NAM AAt A N ..

0,G 2.00 1.00 3.00 4.00 5.00 E.00 Time-i (ms) 15P, 00 F

.cad-I 244.59 Ib Time-1 -0 7E is 5000.00 4000.00 00000 2000.00 1000.00 0.00 1.00 2.00 3.00 4.00 5 00 P.00 T7me-1Ifms*

liY, 75°F WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 B-3 5000.

2000.

2000.

0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-i (msi 13B, 1250F z*b

..a 0.00 1.00 2.00 3.00 4.00 6.00 Time-1 (ms)

IlK, 150-F WCAP-17501-NP February 2012 Revision 0

B-4 Westinghouse Non-Proprietary Class 3 g"6 J

Time-I (nm; 12M, 155 0 F g

.o 6,00 Time-I (ms) 122, 165-F WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 B-5 2.00 ..00 Time-'1 (mel 123, 175-F Load-I 414.76 lb Time-i .0.75,mn OUUU.ul; v 5000.00 7 3000 CC 2000.00 100 6,6fA IP11AS;A ~LM. -

0.00 1.00 2.00 3.00 -.00 5.00 6.00 Time1i (!mTS 15U, 190-F February 2012 WCAP-1750 1-NP WCAP- 17501-NP February 2012 Revision 0

B-6 Westinghouse Non-Proprietary Class 3 n

0.00 1.00 2.00 3.00 4.00 5.00 S00 Time-1 (m3; 15M, 210OF 0S 0.00 100 2.00 3.00 400 5.00 E.00 Time-1 (ms) 142, 325°F WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 B-7 Load-1 3.44 rb Time- 1 -0.72 m%

• 0000.00*

4000. 00-3000.00-2000.00-1000.00.

c,00 1.00 2.00 3.00 4.00 S.00 6.00 Time-'I (ms) 12C, 340-F 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Tim-i (mcs 162, 350 0 F WCAP-17501-NP February 2012 Revision 0

B-8 Westinehouse Non-Proorietarv Class 3 Lcadl 62.04 lb Time-1 -1.71 ms 5000.00 4000.00

-7 M000.00 o,

2000.00 1000.00

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'00. . . . . .. .. .. . . . . . . .. . . . .

100 0.00l 1 A. .ftJ As AM Aw AAAA f . A., -~A sA 1.00 2.00 3.00 4.00 I.00 600 Time-1 (m13 316, 150 F WCAP- 17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 B-9 Load-1 55.12 ro Time-1 -G.75 ms

.00 Time-i (ms) 313, 20-F

~GGG.c~c~

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1000.00-3.00 6.00 Time-i ýms) 34D, 25OF WCAP-17501-NP February 2012 Revision 0

B-10 Westinhouse Non-Proprietarv Class 3 2

O.0Q 1.00 2.00 3.00 4.00 E.00 Time-i (ms) 32P, 30°F

.Lad-1 1717 lb Time-1 00.* em b000.00*

4000.00 3000.00" ............

2000.00 .......... ...... .. ....... .... ...

I000.00-0000 1.00 2.00 3.00 4 00 5.00 Soo Time-i (ms, 31K, 50°F WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 B-11 5.000.00L60 d-1 51.44 lb Time-I -0..7 me

. .00 0. .0 .. .. .. . . .. .. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

" .0 0.0 0. 0... . . . . . .. . . . .. . . . . . . . . . ... . ... ... ... ... . .. . . .. .. . . .. . . . . . . . . . . .

• 000.00 2000.00 P 0.00 1.00 2.00 G00 -. 00 5.00 C.00 Time-1 (mse 32T, 60°F Load-1 5.ag lb Time-I -0.72 me.

o~o ............ ......................... .................. !......... ........

2000.00 4000.00 1000.00d. . . .. . . .

0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time- I (ms) 31E, 75 0 F WCAP-17501-NP February 2012 Revision 0

B- 12 Westinghouse Non-Proprietary Class 3 Load-1 27.0 6b TRne-l -0.7$ ms

£000.00 0.00 0.00 1.00 2.00 3,00 4.00 5.00 .00 T

ime-1 (ms) 35L, 150°F Load-i 65.29 lb Time-1 -0.73 ms SOOD0.0 0 .. . . . . . . . . . . . . . .. . . . . . . .... .... . ... . .... . .. . . . . .. . . . . . . .

4000.00 .... ...... .....

4000.00 0.00 1.00 2.00 1-00 4.00 6.00 60 o Time-I (mni 343, 225WF WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 B-13 3

0.00 1M00 2.00 3.00 4.00 5.00 6.00 Time-I (ms) 31J, 250-F

.7 ~00o V -

0.00 1.00 2.00 3.00 4.00 5.00 600 Tim'e- (mns) 31M, 275-F WCAP-17501-NP February 2012 Revision 0

B-14 Westinghouse Non-Pronrietarv Class 3 Lc8d-f 37.,4 lb Time-1 ,',

ma6 5000.00 4000.00

-,'b_'

2000.00 2000.00 1000.00 0.00 A& AýhLýl A.,. A A -A A. A A A A A ý A ý A 0.00 1.00 2.00 11.00 4.M0 5,00O E.00 Time-l (rs' 44T, -75 0 F

.oad-I 61.92 lb Time-I -0.75.m

$000.00-4000.00]

.S N00 2

0.00 . . . . . . . . .. .. . .... .. .. .. .. .. .. .. .. ..... ... . .. ... .. .. . .. . . .... .. ... ..

200 100 GtGG 0.00 1.00 2.00 5.00 3.00 4.00 600 Time-1 (msa 43D, -25°F WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 B-15 Load-i 37.95Eb Time-i -0.72 ma 5000.00C .  : .. ... ...

4000.00 S3000.00 2000.00.

0.00 1.00 20 3.00 4.00 5.00 6.00 Time-i (ma) 45D, -15 0 F Load-I 61.92 lb Time.- -0.75 ms

...... .00 400 0 .0 0 . .... . .. . . .. .... . ... . .. . . ... .... ...

2000.00' c00 1.00 200 300 4.00 500600 Tim4-i, (ma 44A, 00 F WCAP-17501-NP February 2012 Revision 0

B-16 Westinghouse Non-Proprietary Class 3 Led-.1 17.23 1b Time-1 .0.7 nis 5000.00 4000.00 2000.00-2000.00 1300.00 JkLJ~~.

JA A....A.Ai .I .,.A. .k. ~ .~

C.00 1.00 2.00 3.00 4.00 e.00 Time-I (rre) 453, 20°F

.o0d- I 4.9 lb Time-1 -0.73 rme E000.00 4000.00 .. . . . . . . .

3 17 3000.00 . . . . . . . . . . . .

ip 2000.00 p

1000M 0.0 1.00 2.00 3.00 4.00 .0C 600 Tim-e-I 00)i 43B, 40-F WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 B-17

-6

..J 0.00 1.00 2.00 3.00 4.00 5.00 E.00 Time-1 (msý 45C, 50-F Lo*ad-1 41 2R it, Time-1 -0.7S me 0000.c0 5300.00 2300.00 2000.00

.d 2000.00 1000.00 AA A, 0.00 1 0.000 1.00 2.00 3.00 4.00 5.00 Time-i (msi 43C, 75-F WCAP-17501-NP February 2012 Revision 0

B-18 Westin2house Non-Proorietarv Class 3 B- 18 Westinghouse Non-Proprietary Class 3

-3 8

..J 0.00 1.00 2.00 0.00 4.00 1.00 Time-i (Omsl 42M, 250-F "7

3.00 r00 Time- I (m;*

462, 275-F WCAP- 17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 B-19 Lead-I 0.00 lb Time-1 -0.75 ins 5000.00 4000.00 0 .00G . .. . . . . . . .. . . . . . .

0.00 1.00 2.00 M00 4.00 5.00 O00 Time-I (ms) 434, 300°F 0Lad-1 44.76 1b Time-1 -0.75 ms 0 00.0 0 . . . .. . .. .. . . . . .. .. . . . . . .. ..

'7 0 ..... .. .. .0O '. . . . .. .

00 I.DO 2.O 3.0 4oo 4.00 5.0c 600 Time, I (ma; 44B, 325 0 F WCAP-17501-NP February 2012 Revision 0

B-20 Westinghouse Non-Pronrietarv Class 3 Lcad-I 0.00 IL Time-1 0.71 mn S0000.00 .. .. .. ..

400 00.00 200

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AAp AA R AmAx 1 A.A~A f &

0.00 1.00 2.00 3.00 4.00 I,00 Time-I (ms) 67M, 75 0 F nal.-1 41 48 lb Time-I -0.74 mS

$000.00 400 0.00 * . . . . .i. . . . . . . . . . . . . . . .. . . . . . . . . ... . . ... . .. .

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66B, 150 0 F WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 B-21 LCO,-I -.052lb Time-1 -0.6- ms 0000.00-4000.00-

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._l 2000.00-1000.00-MIA A.-A m A. M A- IL OktýA 0.0 -i.O0 1.00 2.00 0.00 S.00 E.00 Time-I (ns)-

67D, 175-F Load-1 41.221b Time.1 -0.73 ms

$000.00 4000.00 2000.00 2000. 00 1000.00 rl A A A.Ap 0.00 1.00 2.00  ?.00 4.00 ý,0c r 00 Time- I (mcs 67J, 190-F February 2012 17501-NP WCAP- 17501 -NP February 2012 Revision 0

B-22 B-22 Westinahouse Non-Pronrietarv Class 3

-3 7.

P.00 Time-I (ms, 66J, 2000 F Load-I 30.99 Ib Time-I -0.75 ms SO00,O0 5000.00 4"000.00 p

2000.00 1000.00 0.00 1.00 2.00 3.00 4.00 5.00 600 Time- I (me) 66L, 210OF WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 B-23

-4 0.00 1.00 2.00 3.00 5.00 E.00 Time-1 (ms) 67B, 220 0 F Loat-i 5i tO lb Time-1 -0.75 me oad-I 5160 Ib Time.1 -0 75 ms S000.00 4000.00 3000.00-J 2000.00" 1000.00-A it.. a .~. a.

0.00 1.00 6000 2.00 3.00 4 00 Time-I fims 67E, 225 0 F WCAP-17501-NP February 2012 Revision 0

B-24 Westingrhouse Non-Proprietarv Class 3

-4 3.0G Time-l (ms) 66E, 235-F

.Lad-1 10.21 lb Time-1 -0.75 ms 5000.00 4000.00-

"7 1000.00 2000.001 1000.00 ....... .... .... .. ....... . .. ........ .

G1ccL I4-0.00 1.00 2.00 Ž.00 4.00 600 Time-1 (i*)

66P, 325°F WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 B-25 Westinghouse Non-Proprietary Class 3 B-25

-3 6.00 Time-1 (ms) 66K, 350-F 2i" Time-1 (ms; 67C, 375 0 F WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-1 APPENDIX C CHARPY V-NOTCH PLOTS FOR EACH CAPSULE USING SYMMETRIC HYPERBOLIC TANGENT CURVE-FITTING METHOD Contained in Table C-I are the upper-shelf energy (USE) values used as input for the generation of the Charpy V-Notch plots using CVGRAPH, Version 5.3. The definition for USE is given in ASTM E185-82

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

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

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

shear) as the USE, excluding any values that are deemed outliers using engineering judgment. Hence, the Capsule 104' USE values reported in Table C-I were determined by applying this methodology to the Charpy data tabulated in Tables 5-1 through 5-4 of this report. USE values documented in Table C-I for the unirradiated material, as well as Capsules 2630 and 970 were also determined by applying this methodology to the Charpy Impact data reported in TR-ESS-001 [Reference C-2], SwRI-06-7524

[Reference C-3] and BAW-2199 [Reference C-4]. The USE values reported in Table C-I were used in generation of the Charpy V-Notch curves.

The lower shelf energy values were fixed at 2.2 ft-lb for all cases. The lower shelf Lateral Expansion values were fixed at 1.0 mils in all cases.

Table C-i Upper-Shelf Energy Values (ft-lb) Fixed in CVGRAPH Capsule

Ž,MteilUnirradiated 2630, 970 1040 Lower Shell Plate D-8907-2 141.6 114.7 108.0 107.7 Longitudinal Orientation Lower Shell Plate D-8907-2 114.4 - - - 86.7 - - -

Transverse Orientation Surveillance Program Weld Metal 138.9 105.3 97.3 110.3 (Heat# 10137)

HAZ Material 127.7 104.5 81.4 94.0 SRM 141.5 89.9 - -- 92.3 WCAP-17501-NP February 2012 Revision 0

C-2 Westinahouse Non-Pronrietary Class 3 CVGRAPH Version 5.3 plots of all surveillance data are provided in this appendix, on the pages following the reference list. Note that the hand drawn plots of the unirradiated material, as well as Capsules 2630 and 970, in References C-2 through C-4, were updated to CVGRAPH Version 5.3 in this analysis for consistency with the Capsule 104' results.

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

C-2 TR-ESS-001, Testing and Evaluation of Calvert Cliffs, Units 1 and 2 Reactor Vessel Materials Irradiation Surveillance Program Baseline Samples for the Baltimore Gas & Electric Co.,

January 1975.

C-3 SwRI-06-7524, Reactor Vessel MaterialSurveillance Programfor Calvert Cliffs Unit 2 Analysis of 263' Capsule, September 1985.

C-4 BAW-2199, Analysis of Capsule 97' Baltimore Gas & Electric Company Calvert Cliffs Nuclear Power Plant Unit No. 2, February 1994.

WCAP- 17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-3 C-3 Westinghouse Non-Proprietary Class 3 This page is intentionally blank.

WCAP- 17501-NP February 2012 Revision 0

C-4 Westinghouse Non-Proprietary Class 3 C.2 CVGRAPH VERSION 5.3 INDIVIDUAL PLOTS UNIRRADIATED (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 05/23/201. 1 12:35 PM Page 1 Coefficients of Curve I A = 71.9 B = 69.7 C = 67.15 TO = 57.93 D = 0.OOE+00 Equation is A + 1 * [Tanh((T-ToY(C+DT))]

Upper Shelf Energy= 141.6(FLxed) Lower Shelf Energy=-2.2(Fixed)

Temp@ 30 ft-lbs= 11.3 Deg F Tenip@50 ft-lbs-36.1 Deg F Plant: Calvert Cliffs 2 Material: SA533B1 Heat: C-5286-1 Orientation: [.:' Capsule: UNIRR l11uence: n/cm^12 300-250-200 0

U-150 z so go100 t-3 50 0

-30 0.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 80. 00 5. 00 4.45 I55

-40. 00 8. 20 9. 36 -I. 16

-40. 00 t 1. 00 9. 36 1. 64

. 00 16. 00 23. 27 - 7. 27

. 00 21. 50 23. 27 -I .77

40. 00 49. 50 53.72 -4. 22

40. 00 59. GO 53.72 5. 28

70. 00 90. GO 84. 30 5. 70

70. (10 93. 50 84. 3(1 9 20 WCAP-1750 1-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-5 UNIRRADIATED (LONGITUDINAL ORIENTATION)

Page 2 Plant: Calvert Cliff's 2 Material: SA533B1 Heat: C-5286-1 Orientation: LT Capsule: UNIRR Fluence: n/cmA2 Charpy V.Notch Data Temperature Input CVN Computed CVN Differentiat

70. 00 101. 00 84. 30 16.70

80. 00 65. 50 94. 02 - 28. 52 80.()0 0 94. 50 94. 02 .48

20. 00 1 12. 00 22. 64 -10.64 120. 00 127. 50 122. 64 4. 86 1 60. 00 130. 00 13.5. 24 -5. 24 160. 00 142. 00 135. 24 6,76 210. 00 141. 50 140. II 1. 39 2M0. 00 153. 00 140. 12.89 Correlation Coefficient Al98 WCAP-17501-NP February 2012 Revision 0

C-6 Westinehouse Non-Prot)rietarv Class 3 C-6 Westinghouse Non-Proprietary Class 3 UNIRRADIATEI) (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 05/23/2011 12:41 PM Page I Coefficients of Curve I A = 46.82 B = 45.82 C = 66.88 TO = 38.97 D = O.OOE+00 Equation is A + B A ['I'anh((T-TYo)(C+DIT)))J Upper Shelf L.E.=92.6 Lower Shelf L E.=1.0(Fixed)

Tenp.@L,E. 35 mits=21.4 Deg F Plant: Calvert Cliffs 2 Material: SA533BI Heat: C-5286- I Orientatirn: LT Capsule: UNIRR Fluence: n/rcmA2 200 150 * +

t-0 100 I. ,-.

-I.

0 0

so 0

13

-300.0 0.0 300.0 600.0 Temporature In Dog F Charpy V-Notch Data Temperature Input LE. Computed LEI. Differential

80. 00 7. 00 3. 54 3.46

- 40. 00 I . 00 8. 89 2. 11

- 40. 00 13. 00 8. 89 4. 11 00 17. 00 22, 78 -5.78

.00 23. 00 22. 78 .22

40. 00 42. 00 47. 52 -5.52

40. 00 51.00 47. 52 3.4-8 70, 0(1 72. 00 66, 67 5. 13

70. 00 73. 00 67 6. 33 66.

WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-7 UNIRRADIATED (LONGITUDINAL ORIENTATION)

Page 2 Plant: Calvert Cliffs 2 Material: SA533BI Heat: C-5286-1 Orientation: LT Capsule: UNIRR Fluence: n/cmnA2 Charpy V.Notch Data Temperature Input LE. Computed L.E. Differential

70. 00 74. 00 66. 67 7.33

80. 00 54. 00 71.86 -17.86 8(0. 00 72. 00 71.86 .14 120. 00 82. 00 85, 17 -3. 17 120. 00 89. 00 85. 17 3. 83 160.00 89. 00 90. 24 - 1. 24 160. 00 98. 00 90, 24 7.76 210. 00 88. 00 92. 08 -4. 08 210. 00 91.00 92. 08 - I. 08 Correlation Coefficient =.981 WCAP-17501-NP February 2012 Revision 0

C-8 Westinahouse esighue Non-Promietarv o lPoritIvCas Class 3 C-UNIRRADIATED (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on, 05/23/2011 12:47 PM Page I Coefficients of Curve I A = 50. B = 50. C = 75.07 TO = 69.05 D = O.OOE+00 Equation is A + B * [Tanh((r-To)/(C+DT))]

Temperature at. 50% Shear = 69. I Plant: Calven Cliffs 2 Material: SA533BI Heat: C-5286-I Orientation: LT Capsule: UNIRR Fluence: n/crnA2 125 100 75 M

50 25

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

- 80. 00 -.00 I.85 -I 85 O0 5. 00 5.19 19

-40. 00 10. 00 5.19 4.81

• 00 15.00 13,7 1 1 29

.00 20. 00 13.71 6. 29

40. 00 30. 00 31,56 -1 56 40, 00 30.00 31 , 56 -1 56

70. 00 50.00 50. 63 63

70. 00 50.00 50. 63 63 February 2012 WCAP- 7501-NP WCAP-117501 -NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-9 UNIRRADIATED (LONGITUDINAL ORIENTATION)

Page 2 Plant: Calvert Cliffs 2 Material: SA533BI Heat: C-5286-1 Orientation: LT Capsule: UN1RR Fluence: n/cm^2 Charpy V-Notch Data Temperature Input Percent Shear Compuied Percent Shear Differemnial

70. 00 60 00 50. 63 9, 37

80. 00 40. 00 57. 24 - 17. 24

80. 00 60. 00 57. 24 2.76 120. 00 75. 00 79. 53 -4.53 120. 00 85. 00 79. 53 5.47 160. 00 95. 00 91.86 3. 14 160, 00 100. 00 91.86 8. 14 2 10. 00 100. 00 97. 71 2. 29 210. 00 100. 00 97. 71 2. 29 Correlation Coefficient =.986 WCAP-17501-NP February 2012 Revision 0

C-iO Westinghouse Non-Proorietarv Class 3 UNIRRADIATED (TRANSVERSE ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 05/23/2011 12:52 PM Page 1 Coefficients of Curve I A - 58.3 B = 56.1 C = 77.45 TO = 77.83 1) = O.OOE+O0 Equation is A + B r [lTIh((T-ToY(C+DT))J Upper Shelf Energy=l 14.4(Fixed) Lower Shelf Energy--2,2(Fixed)

TempQ1S30 ft-lbs=34.9 Deg F Temp@50 ft-lbs=66.3 Deg F Plant: Calvert Cliffs 2 Material: SA5331]1 Heat: C-5286-1 Orientation: TI, Capsule: UNIRR Fluence: n/enIA2 300 250 S200 U.4 i 150 LU

§0 100 50 A-0

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

- 80. 00 4. 50 4. 07 443

- 80. 00 4. 80 4. 07 73

-40. 00 5. 50 7.31 -1.81

- 40. 00 6, 60 7.31 771 00 15. 00 15.46 46 00 15. 50 15. 46 04

40. 00 35, 00 32. 89 2. I1

40. 00 48, 00 15. 1

70. 00 47. 50 52. 65 -5. 15 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-I11 Westinghouse Non-Proprietary Class 3 C-Il UNIRRADIATED (TRANSVERSE ORIENTATION)

Page 2 Plant: Calvert Cliffs 2 Material: SA533BI Heat: C-5286- I Orientation: TL Capsule: UNIRR Fluence: n/cm^2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

80. 00 56. 00 59. '87 -3,87

-2. 87

80. 00 57. 00 59. 87

80. 00 58. 50 59, 87 -1.37 I 20. 00 78. 00 86, 15 -8. 15 1 20. 00 81. 50 86. 15 -4. 6.5 1 60. 00 12. 50 .102. 40 10. 10 160. 00 115. 00 102. 40 12.60 210.00 110. 50 110. 82 - .32 210.00 1 19. 50 110, 82 8.68 Correlation Coefficient = ,988 WCAP-17501-NP February 2012 Revision 0

C-12 Westinahouse Non-Proorietarv Class 3 UNIRRADIATED (TRANSVERSE ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 05/23/2011 12:55 PM Page 1 Coefficients of Curve I A = 45.71 B = 44,71 C = 96.75 TO = 68.33 D = O.OOE+00 Equation is A + B * [Tanh((T-Toy(C+DT))]

Upper Shelf LE.=90.4 Lower Shelf L.E.= .O(Fixed)

Temp.@L.E. 35 mils=44.7 Deg F Plant: Calvert Cliffs 2 Material: SA533B3I Heat: C-5286-1 Orientation: 1. Capsule: UNIRR Fluence: n/c,,A2 200 150 C

.2 a.ioo 0

50 0

A

-300.0 0

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

- 80. 00 4. 00 4. 98 -. 98

- 80. 00 4. 00 4. 98 -. 98

- 40. 00 9. 00 9.61 .61

- 40. 00 8. 00 9.61 -1.61 00 16.00 18. 51 -2. 5 1 00 20. 00 18. 51 1.49

40. 00 32. (10 32. 98 -. 98

40. 00 42. 00 32. 98 9. 02

70. 00 44. 00 46. 49 -2.49 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-13 UNIRRAD1ATED (TRANSVERSE ORIENTATION)

Page 2 Plant: Calvert Cliffs 2 Material: SA533BI Heat: C-5286-1 Orientation: TL Capsule: UNIRR Fluence: n/cm^2 Charpy V-Notch Data Temperature Input L.E. Computed hE. Differential

80. 00 51. 00 51.08 - .08

80. 00 50. 00 5 1. 08 -I .08

80. 00 49. 00 5I. 08 -2. 08 120, 00 64. 00 67. 56 -3 56 1 20. 00 68. 00 67. 56 .44 160.00 81.00 78. 74 2. 26 160, 00 83, 00 78,74 4 26 2 10. 00 81. 00 85. 89 -4 89 210.00 88. 00 85. 89 2.11 CotTelation Cm-fficient = ,994 WCAP-17501-NP February 2012 Revision 0

C-14 Westinghouse Non-Protnrietarv Class 3 Westinghouse Non-Pronrietarv Class 3 UNIRRADIATED (TRANSVERSE ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 05/231201.1 12:57 PM Page 1 Coefficients of Curve I A = 50. B = 50. C = 64.9 TO = 98.42 D = 0.00E+00)

Pijuation is A + B * [Tanh((T-'I'Y(C+DT))]

Temperature at 50% Shear= 98.5 Plant- Calvert Cliffs 2 Material: SA5330 I Heat: C-5286- 1 Orientation: TL Capsule: UNIRR Fluence: n/ernA2 125 100 0

b.

0. 75 50 0o 25 0

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

-80. 00 00 .41 - 41

-80. 00 00 .41 - .41

-40. 00 5. 00 I 39

-40 00 5. 00 1.39 3.61 00 10.00 4. 60 5.40 00 10.00 4. 60 5.40

40. 00 20. 00 14. 18 5.82 40, 00 20. 00 14. 18 5 82

70. 00 30. 00 29. 41 .59 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-15 UNIRRADIATED (TRANSVERSE ORIENTATION)

Page 2 Plant: Calvert Cliffs 2 Material: SA533BI Heat: C-5286-1 Orientation: TL Capsule: UNIRR Fluence: n/cm^2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

-I.18

80. 00 35. 00 36. 18

80. 00 30. 00 36. 18 -6.18

80. 00 35, 00 36. 18 -1,18 120. 00 50. 00 66. 04 - 16. 04 120. 00 70. 00 66. 04 3. 96 160. 00 95. 00 86. 96 8.04 160. 00 100. )0 86. 96 13. 04 210. 00 100. 00 96. 89 3. 11 210. 00 100. 00 96. 89 3. 11 Correlation Coefficient =.986 WCAP-17501-NP February 2012 Revision 0

C-16 Westinghouse Non-Proprietary Class 3 UNIRR*ADIATED (SURVEILLANCE WELD METAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 05/23/2011 01:00 PM Page I Coefficients of Curve I A = 70.55 B = 68.35 C = 61.38 TO = -11.84 D = O.O0E+0O Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Ernergy=1 38.9(Pixed) Lo)wer Shelf Ernergy=2.2(Fixcd)

Tcnp@30 ft-lbs-53.7 Deg F Temp@50 ft-lb--30.8 D8g F Plant: Calvert Cliffs 2 Material: SAW He at: 10137 Orientation: NA Capsule: UNIRR Fluence: n/cm^2 300 250

" 200 0

0 0

uJ 0 0 100 0

5o 0

/0 n

0

-300.0 -200.0 -100.0 0.(0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Ditferential

- 120. 00 4. 30 6. 11 -1.81

- 80. 00 8. 00 15. 58 -7. 58

- 80. 00 8. 50 15. 58 -7. 08

-40. 00 28. 00 41. 22 -t3.22

-40. 00 39. 50 41 22 - I .72

-40. 00 76. 50 41 22 35. 28

.0C 70. 50 83. 57 -13. 07

.00 78. 50 83. 57 - 5. 07

-00 89. 50 83. 57 5. 93 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-17 UNIRRADIATED (SURVEILLANCE WELD METAL)

Page 2 Plant: Calvert Cliffs 2 Material: SAW Heat: 10137 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 Charpy V.Notch Data Temperature Input CVN Computed CVN Differential

40. 00 101. 50 1 17. 59 - 16. 09

40. 00 125. 00 117. 59 7 41

80. 00 124, 00 132. 37 -8 37

80. 00 128. 50 132. 37 -3. 87

80. 00 172. 50 132. 37 40 13 12n. 00 134. 50 137, 06 -2 56 i 20. 00 142. 50 137, 06 5 44 160. 00 128. 50 138. 40 -9. 90 160. 00 141. 50 38. 40 3. 10 Correlation Coefficient = .958 WCAP- 17501-NP February 2012 Revision 0

C-18 Westinghouse Non-Proprietary Class 3 UNIRRADIATED (SURVEILLANCE WELD METAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 05/2312011 01:03 PM Page I Coefficients of Curve I A = 47.23 B = 46.23 C = 60.51 TO = -24.68 D = 0.OOE+00 Equation is A + B * [Tanh((IT-ToA(C+DT))j Upper Shelf LE.=93.5 Lower Shelf L.E.=1.0(Fixed)

Temp. @ILE. 35 mil=-41.0 Deg F Plant: Calvert Cliffs 2 Material: SAW Heat: 10137 Orientation: NA Capsule: UNIRR Fluenee: n/cm^2 200 150 E

._o 0

50 0 4

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

- 120. 00 3. 00 4.80 -I .80

-80. 00 7. 00 13. 80 -6. 80

- 80. 00 9. 00 13, 80 -4, 80

-40. 00 26. 00 35,77 -9. 77

- 40. 00 33.00 35. 7 7 -2. 77

-40. 00 60. 00 35.77 24. 23 00 63, 00 65, 10 - 2. 10

.00 62. 00 65. 10 -3. 10

.00 66. 00 65. 10 .90 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-19 UNIRRADIATED (SURVEILLANCE WELD METAL)

Page 2 Plant: Calvert Cliffs 2 Material: SAW Heat: 10137 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input LE. Computed LE Differential

40. 00 76. 00 83. 70 -7. 70

40. 00 86. 00 83.70 2. 30

80. 00 92. 00 90. 63 1.37 80, 00 93. 00 90. 63 2. 37

80. 00 91. 00 90. 63 37 120. 00 93. 00 92. 68 32 120. 00 94. 00 92 68 1.32 160. 00 91 . 00 93. 25 -2. 25 160. 00 95. 00 93. 25 1.75 Correlation Coefficient =.977 WCAP-1750 1-NP February 2012 Revision 0

C-20 Westinahouse Non-Proorietarv Class 3 UNIRRADIATED (SURVEILLANCE WELD METAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 05/23/2011 01: 10 PM Page I Coefficients of Curve 1.

A = 50. B = 50. C = 73.94 TO = -13. D = O.O0E+O0 Equation is A + 9 [*'Tanh(('"-FTo-(C+DT))j Temperature at 50% Shear = -12.9 Plant: Calvert Cliffs 2 Material: SAW Heat: 10137 Orientation: NA Capsule: UNIRR FuencEC: n/cnA2 125 100 C, 75 50 25 4-200.

-000 -100.0 0.0

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

- 120. 00 5. 00 5. 24 24

-8M. 00 15.00 14.04 96

-80. 00 15,00 14.04 96

-40. 00 30, 00 32.5 1 2. 51

-40. 00 35. 00 32.51 2. 49

-40. 00 35. 00 32. 51 2 49 00 60. 00 58. 70 1 30 00 50, 00 58.70 8. 70 00 65. 00 58.70 6. 30 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-21 UNIRRADIATED (SURVEILLANCE WELD METAL)

Page 2 Plant: Calvert Cliffls 2 Material: SAW Heat: 10137 Orientation: NA Capsule: UNIRR Fluence: n/cn^A2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

40. 00 70, 00 80. 74 - 10, 74 40, 00 80. 00 80, 74 - .74

80. 00 99. 00 92. 52 6. 48

80. 00 95. 00 92. 52 2. 48

80. 00 100. 00 92. 52 7.48 120. 00 100. 00 97. 33 2. 67 120. 00 100. 00 97. 33 2. 67 160. 00 100. 00 99. 08 92 160. 00 100, 00 99. 08 .92 Correlation Coefficient =.991 WCAP-17501-NP February 2012 Revision 0

C-22 Westin2house Non-ProDrietarv Class 3 C-22 Westinehouse Non-Pronrietarv Class 3 UNIRRADIATED (HEAT AFFECTED ZONE)

CVGRAP:H 5.3 Hyperbolic Tangent Curve Printed on 05/2-3/201I 01:14 PM Page I Coefficients of Curve I A = 64.95 B = 62.75 C = 14(1.93 TO = 23.48 D = 0.OOE+O0 Equation is A + B * [Tanh(CT-To/(C+DTr))]

Upper Shelf Energy= I127.7(Fixed) Lower Shelf Energy=2.2 (Fixed)

Temp@30 ft-lbs=-65.0 Deg F Temp @50 ft-lb,=-10.7 Deg F Plant: Calvert Cliffs 2 Material: SA533B 1 Heat: C-5286-1 Orientation: NA Capsule: UNIRR Fluence: n/cma^2 300 250 200 150 UL z

0> 100 50

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

- 120. 00 9. 80 1 6. 69 -6. 89

-80. 00 7. 00 25. 69 -18 69

-g0. 00 21.50 25. 69 -4. L9

- 40, 00 45. 00 38. 45 6. 55

- 40. 00 56. 50 38. 45 18. 05 00 40. 00 54. 59 - 14. 59 00 80. 00 54. 59 25. 4 1 40, 00 84, 00 72. 27 11 73

40. 00 85. 00 72. 27 12. 73 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-23 UNIRRADIATED (HEAT AFFECTED ZONE)

Page 2 Plant: Calvert Cliffs 2 Material: SA533BI Heat: C-5286-1 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

70. 00 02. 00 84. 94 -22. 94

70. 00 71- 00 84. 94 -13. 94

70. 00 71. 50 84. 94 -13. 44 s0. 00 80. 00 88. 85 -8. 85

80. 00 90. 00 88. 85 1 .15 1 20, 00 74. 50 102. 27 27. 77 120. 00 134. 00 102. 27 31 .73 160. 00 120. 00 11 1. 90 8 10 160. 00 129. 00 11 1. 90 17. 1(

Correlation Coefficient = .883 February 2012 WCAP-1750 1-NP WCAP-17501-NP February 2012 Revision 0

C-24 Westin2house Non-ProDrietarv Class Class 33 C-24 Westinghouse Non-Proorietarv UNIRRADIATED (HEAT AFFECTED ZONE)

CVGRAPIH 5.3 Hyperbolic Tangent Curve Printed on 05/23/2011 01:16 PM Page I Coefficients of Curve I A = 41.89 B = 40.89 C = 109.56 TO = -24.66 D = 0,O0E+O0 Equation is A + B * [Tanh((T-To)/(C+DT))j Upper Shelf L.E.=82.8 Lower Shelf LE.=I.0(Fixed)

Temp.@L.E. 35 mils=-43.3 Deg F Plant: Calvert Cliffs 2 Material: SA533B1 Heat: C-5286-1 Orientat~ion: NA Capsule: UNIRR Fluence: ntcrn^2 200 150 E.

.2

~.100 0

0o so 0 n

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

- 120. 00 10. 00 13,21 -3. 21

- 80. 00 7. 00 22. 83 .15.83

- 80. 00 22. 00 22. 83 - . 83

-40. 00 38.00 36. 20 1. 80

-40. 00 54. 00 36. 20 17.80 00 39. 00 50, 94 - I1. 94 00 61,00 50. 94 10.06

40. 00 82. 00 63. 56 18. 44

40. 00 65. 00 63. 56 1.44 WCAP-1 7501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-25 UNIRRADIATED (HEAT AFFECTED ZONE)

Page 2 Plant: Calvert Cliffs 2 Material: SA533B I Heat: C-5286.l.

Orientation: NA Capsule: UNIRR Fluence: n/cm12 Charpy V-Notch Data Tvmptraturc Input: i*E Computed LE, Diffewntial

70. 00 53. 00 70. 45 -17, 45

70. 00 59. 00 70. 45 - I 1.45

70. 00 67. 00 70. 45 3. 45

80. 00 72, 00 72. 24 -, 24 80, 00 67. 00 72. 24 -5. 24 120. 00 69. 00 77. 34 8. 34 120. 00 86. 00 77. 34 8, 66 160.00 88. 00 80. 07 7. 93 160. 00 87. 00 80. 07 6. 93 Correlation Coefficient = .907 WCAP- 17501 -NP February 2012 Revision 0

C-26 Westin2house Non-Provrietarv Class 3 C-26 Westinghouse Non-Proprietary Class 3 UNIRRADIATED (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 05/23/2011 01:18 PM Page I Coefficients of Curve I A = 50. B = 50. C = 108.57 T0 = 18*59 1) = 0.OOE+00 Equation is A + B

• ITanh(0T-ToY(C+DT))]

Temperature at 50% Shear = 18.6 Plant: Caivert CliflT 2 Material: SA533BI Heat: C-5286-1 Orientation: NA Capsule: UNIRR Rucnce: n/cm^2 125 100 0

75 C,,

0 50 /0 00 25 0

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F Charpy V-Notch D)ata Temperature Input Percent Shear Computed Percent Shear Diff*rential

- 120. 00 .00 7. 22 -7. 22

- 80. 00 .00 13.99 -13. 99

- 80. 00 10. 00 13.99 -3. 99

- 40. 00 40. 00 25. 37 14. 63

- 40. 00 50. 00 25. 37 24. 63 00 40. 00 41. 52 -I .5 2 00 30. 00 41. 52 - I .52

40. 00 70. 00 59,73 10.27

40. 00 50. 00 59,73 -9.73 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-27 UNIRR4*DIATED (HEAT AFFECTED ZONE)

Page 2 Plant: Calvert Cliffs 2 Material: SA533BI Heat: C-5286-1 Orientation: NA Capsule: UNIRR Fluence: n/cm^2 Charpy V.Notch Data Tenp*r'l tre, Ilput Percent Siwar Computed Percent Shear Differntial

70. 00 60. 00 72. 03 - 12.03

70. 00 60. 00 72. 05 -12. 05

70. 00 70. 00 72. 05 -2. 05

80. 00 75. 00 75, 61 -. 6i

80. 00 80. 00 75. 61 4. 39 120. 00 90. 00 86. 62 3. 38 120. 00 1oo, 00 86, 62 13.38 160. 00 100. 00 93. 12 6. 88 160. 00 100. 00 93. 12 6.88 Correlation Coe, ficient =943 WCAP-17501-NP February 2012 Revision 0

C-28 Westinghouse Non-Proprietary Class 3 UNIRRADIATED (STANDARD REFERENCE MATERIAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 05/23/2011 01:20 PM Page I Coefficiettts of Curve I A = 71.85 B = 69.65 C = 78.89 TO = 79.73 D = O.OOE+00 Equation is A + B * [Tanh((T-ToY(C+DT))]

Upper ShIlf Energy= 14.1.5(Fixed) Lower Sheilf Encrgy--2.2 (Fixcd)

Temp@30 ft-lbs.25.0 Deg F Temp @50 ft-lbs=54.2 Deg F Plant: Calvert Cliff, 2 Material: SAS33BI Heat: HSST-O0MY Orientation: LT Capsule: UNIRR Pluence: n/cm^2 300 250

=T" 200 0

LI-S150 uJ /3 100 0

5o 0

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

- 80. 00 4. 50 4. 59 - . 09

-40. 00 6. 20 8. 59 -2. 39

.00 15. 00 18. 49 -3.49

.00 18. 50 18.49 .01

40. 00 32. 50 39. 46 -6.96

40. 00 40. 50 39. 46 1. 04

60. 00 56. 00 54. 78 1,22

60. 00 72. 50 54. 78 17. 72 80, 00 66. 50 72. 09 -5.59 WCAP- 17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-29 UNIRRADIATED (STANDARD REFERENCE MATERIAL)

Page 2 Plant: Calvert Cliffs 2 Material: SA533BI Heat HSST-01 MY Orientation: LT Capsule: UNIRR Fluence: nicn^A2 Charpy V.Notch Data Temperature Input CVN Computed CVN Differential 80, 00 70. 00 72. 09 -2. 09 1 20. 00 100. 50 104.60 4. 10 120.00 101.50 104. 60 -3. 10 1 60 00 127.00 125. 40 1I60 2 10. 00 134.50 136.56 -2. 06 210. 00 148.50 136. 56 11. 94 Correlation Coefficient = .991 WCAP-17501-NP February 2012 Revision 0

C-30 Westinahouse Non-Pronrietarv Class 3 C-30 Westin2house Non-Pronrietarv Class 3 UNIRRADIATED (STANDARD REFERENCE MIATERIAL)

CVGRAPH4 5.3 Hyperbolic Tangent Curve Printed on 05/23/2011 01:36 PM Page I Coefficients of Curve I A = 46.06 B = 45.06 C = 78.28 To = 61.55 D = 0.00E+40 Equation is A + B * [Tanh((T-TorY(C+DT))]

Upper Shelf LE.=9 . I Lower Shelf L l.=l .0(Pixed)

Temp.,@LE. 35 mils=42.0 Deg F Plant: Calvert Cliffs 2 Material: SA533BI Heat ISST-01MY Orienutation: LT Capsule: UNIRR Fluenee: n/era^2 200 1500 50 so 0 *ý

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

- 80. 00 2. 00 3.36 - 1.36

-40. 00 5. 00 7. 26 -2. 26

.00 14, 00 16.49 -2. 49

.00 17.00 16.49 .51

40. 00 30. 00 33. 96 -3. 96

40. 00 34. 00 33. 96 .04

60. 00 48. 00 45. 17 2. 83

60. 00 55. 00 45.17 9. 83

80. 00 53. 00 56. 49 3. 49 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-31 UNIRRADIATED (STANDARD REFERENCE MATERIAL)

Page 2 Plant: Calvert Cliffs 2 Material: SA533BI Heat: HSST-OIMY Orientation: LT Capsule: UNIRR Fluence: n/cm^2 Charpy V-Notch I)ata Temperature Input LE. Computed L E. Differential

80. 00 56. 00 56. 49 -. 49 120. 00 69. 00 74. 60 -5, 60 120. 00 72.00 74. 60 -2. 60 160. 00 90. 00) 84. 39 5,61 210. 00 86. 00 89. 14 -3, 14 210, 00 92. 00 89. 14 2,86 Correlation Coefficient = .991 WCAP- 17501-NP February 2012 Revision 0

C-32 Westinahouse Non-Pronrietarv Class 3 C-32 Westinehouse Non-Pronrietarv Class 3 UNIRRADIATED (STANDARD REFERENCE MATERIAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 05/2312011 01:41 PM Page I Coefficients of Curve I A = 50. B =50. C = 82.68 TO = 92.87 D = 0.00E+00 Equation is A + B IslTanh((T-Toy(C+DT))]

Temperature at 50% Shear= 92.9 Plant: Calvert Cliffs 2 Material: SA533B1 Heat: 1-ISST-OINMY Orientation: LT Capsule: UNIRR Fluence: n/cIA2 125 100 L.) 75 50

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

- 80. 00 .00 -I1.50 1.50

-40. 00 10.00 3. 86 6. 14

. 00 15,00 9. 56 5. 44

,00 15, 00 9. 56 5 44

40. 00 20. 00 21. 77 -1.77

40. 00 20. 00 21.77 -1.77

60. 00 30. 00 31. 1 0 1 1.0

60. 00 35. 00 31. 10 3.90

80. 00 40. 00 42,28 -2.28 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-33 UNIRRADIATED (STANDARD REFERENCE MATERIAL)

Page 2 Plant: Calvert Cliffs 2 Material: SA533B1 Heat: HSST-01MY Orientation: LT Capsule: UNIRR Fluence: n/cmnA2 Charpy V.Notch Data Temperatute Input Percent Shear Computed Percent 9hear Differential

80. 00 40. 00 42. 28 -2.28 120. 00 60. 00 65. 84 -5.84 120. 00 65, (t 65. 84 -. 84 160. 00 90. 00 93. 53 6.47 210. 00 100, 00 94. 44 5.56 210. 00 1I W. 00 94. 44 5. 56 Correlation Coefficient = .992 WCAP-17501-NP February 2012 Revision 0

C-34 Westin2house Non-Pronrietarv Class 3 C-34 Westinehouse Non-Proorietarv Class 3 CAPSULE 263Y (LONGITUDINAL ORIENTATION)

CVGRAPH 5,3 Hyperbolic Tangent Curve Printed on 06128/201I 10:26 AM Page I Coefficients of Curve I A = 58.45 B = 56.25 C = 86.37 TO = 145.74 D = 0.OOE+00 Equation is A + B * [Tanh((T-ToY/(C+DT))]

Upper Shelf Energy=1.14.7(Fixed) Lower Shelf £*nrgy=2.2(Fixed)

Temp@30 ft-lln=97.7 Deg F Ternpd 50 ft-lbft32.7 Deg F Plant Calvert Cliffis 2 Material: SA533Bl Heat: C-5286-1 Orientation: LT Capsule: 263 Fluenec: n/crnA2 300 250 200 0

LM150 w 0 -

0

> 100 50 0

A I

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In D[eg F Charpy V-Notch Data Temperatlure Input CVN Computed CVN Differential

25. 00 8. 50 8.67 - 17

50. 00 7. 50 13.25 - 5. 75

75. 00 24. 00 20. 5 1 3. 49

75. 00 33. 50 20. 51 12, 99 100. 00 34. 00 31. 17 2. 83 120. 00 46. 50 42. 17 4. 33 140. 00 49, 50 54,72 -5, 22 160. 00 52 00 67. 66 - 15. 66 ISO. OO 75, 50 79. 66 -4. 16 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-35 CAPSULE 2630 (LONGITUDINAL ORIENTATION)

Page 2 Plant: Calvert Cliffs 2 Material: SA533BI Heat: C-5286-1 Orientation: LT Capsule: 263 Fluence: njcmA2 Charpy V.Notch Data Temperature Input CVN Computed CVN Differential 210. 00 104. 50 93. 98 10. 52 250. 00 1 17. 00 105. 47 11.53 300W 00 122. 50 111.63 10. 87 Correlation Coefficient = .977 WCAP-17501-NP February 2012 Revision 0

C-36 Westinahouse Non-Pronrietarv Class 3 C -36 es .n.. N . n- ron

. --- r Class...

CAPSULE 2630 (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 06128/2011 10:31 AM Page I Coefficients of Curve I A = 48.99 B = 47.99 C = 111.9 TO = 138.22 D = 0.04E+00 Equation is A + 13* ['anh((r-ToY(C+DT))j Upper Shelf L L,=97.0 Lower Shelf L E.=1.0(Fixed)

Temnp. @L. E. 35 rnils= 104.7 Deg F Plant: CalvertCCliffs2 Material: SA533B1 Heat: C-5286-I Orientation: LT Capsule: 263 Fluenc: n/cmn^2 200 150 E

100 50 00.0

-300.0 0.0 300.0 600.0 Temperature In Deg F Charpy V-Notch D~ata Temperature Input LE. Computed LE. Differential

25. 00 I L100 12.2 1 I . 21

50. 00 10,00 17.44 -7. 44 75.00 25, 00 24. 44 ,56 75.00 34. 00 24. 44 9. 56 100. 00 34. 00 33. 2 1 .79 120. 00 43. 00 41. 24 1 76 1 40, 00 49. 00 49. 75 75 I60. 00 52, 00 5X. 221 -6 21 W80.00 61. 00 66. 12 -5. 12 WCAP-17501 -NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-37 CAPSULE 263" (LONGITUDINAL ORIENTATION)

Page 2 Plant: Calvert Cliffs 2 Material: SA533BI Heat C-5286-1 Orientation: LT Capsule: 263 Fluencc: alcm^2 Charpy V-Notch Data TemperatLure Input LE. Computed LE,. Differential 2710. 00 84. 00 76. 14 7. 86 250. 00 89. 00 85. 51 3.49 300, 00 88. 00 91.93 .3.93 Correlation Coefficient = .982 WCAP-17501-NP February 2012 Revision 0

C-38 Westinahouse Non-Pror)rietarv Class 3 C-8WsindoseNn roIetrvCas CAPSULE 2630 (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 06/28/2011 10:43 AM Page I Coefficients of Curve I A = 50. B = 54. C = 19.51 TO = 169.08 D = O.OOE+00 Equation is A + B

• fTanh((T-ToY(C+DT))j Temperature at 50% Shear= 169.1 Plant: Calvert Cliffs 2 Material: SA533BI Heat: C-5286-1 Orientation: LT Capsule: 263 Ftuence: n/cm^2 0!

0 - -

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

25. 00 )00 00 .00

50. 00 2 00 00 2. 00

75. 00 10.00 01 9. 99

75. 00 5. 00 01 4, 99 100. 00 10. 00 08 9. 92 120. 00 15.00 65 14. 35 140. 00 20. 00 4. 83 15. 17 160. 00 20. 00 28. 28 -8.28 180. 00 80. 00 75. 38 4. 62 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-39 CAPSULE 2630 (LONGITUDINAL ORIENTATION)

Page 2 Plant: Calvert Cliffs 2 Material: SA533BI Heat: C-5286-1 Orientation: LT Capsule: 263 Fluence: t/cm^2 Charpy V.Notch Data Temperatur Inpul Percent Slanr Computed lrcent Shear Differenlial 98.51 1.49 210.00 100.00 250.00 100. 00 99. 97 03 300. 00 100.,00 100. 00 00 Correlation Coefficient = ,A90 WCAP-17501-NP February 2012 Revision 0

C-40 Westinghouse Non-Proprietary Class 3 CAPSULE 263- (SURVEILLANCE WELD METAL)

CVGRAPH 5.3 Hyyperbolic Tangent Curve Printed on 06(28/201,1 10:46 AM Page I Coefficients of Curve I A = 53.75 It = 51.55 C = 49.16 TO = 43.48 D = OAOE+(XI Exquation is A + B * [1anh((T-ToYt(C+lI-)T))]

Upper Shelf Energy= 105.3(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs= 19.0 Deg F Tenip@50 ft-lbs=39.9 Deg F Plant: Calvert Cliffs 2 Material: SAW Heat: 10137 Orientnfion: NA Capsule: 263 Fluence: n/cnm2 300 0

LL wU z

0

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

- 50, 00 5ý 00 4. 45 55

- 25. 00 19. 00 8. 19 10.81

.00 14. 00 17. 22 -3.22 10.00 23. 50 23. 22 . 28

20. 00 25. 00 30. 84 5,84

25. 00 38. 00 35. 24 2.76

40. 00 57. 00 50. .11 6. 89

50. 00 50. 00 60. 55 - 10. 55 75.00 90. 50 82.91 7. 59 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-41 CAPSULE 263° (SURVEILLANCE WELD METAL)

Page 2 Plant: Calvert Cliffs 2 Material: SAW Heat: 10137 Orientation: NA Capsule: 263 Fluence: n/cr^A2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 140. 00 98. 50 103. 31 -4. 81 210,00 105. 00 105. 18 -. 18 250. 00 112, 50 105. 29 7. 22 Correlation Coefficient =,986 WCAP-17501-NP February 2012 Revision 0

C-42 Westin2house Non-ProDrietarv NnPrpitayCls Class 3 C-2Wetngos CAPSULE 263- (SURVEILLANCE WELD METAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 06/28/201.1 10:49 AM Page I Coefficients of Curve I A = 45.12 B = 44.12 C = 61.06 TO = 39.43 D = 0.OOE+0*I

-ltl.4iton is A + B * [Tanh((T-ToY(C+D-)))]

Upper Shelf L.E.=89.2 Lower Shelf L.E.=-1.0(Fixed)

Temp.@L.E. 35 mils=25.2 Deg F Plant: Calvert Cliffs2 Material: SAW Heat: 10l137 Orientation: NA Capsule: 263 Fluence: n/cnrnA2 200 150

_1 E

a 100 01

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

- 50, 00 6. 00 5, 48 52

- 25. 00 19.00 10.54 8. 46

,00 16. 00 20. 02 -4. 02

10. 00 25. 00 25. 36 -. 36 20, 00 27. 00 31.54 -4. 54

25. 00 36. 00 34, 88 1. 12

40. 00 51. 00 45. 53 5, 47 50, 00 46. 00 52. 69 -16, 69

75. 00 74. 00 68, 27 5.73 WCAP- 17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-43 CAPSULE 263- (SURVEILLANCE WELD METAL)

Page 2 Plant: Calvert Cliffs 2 Material: SAW Heat: 10137 Orientation: NA Capsule: 263 Fluence: n/cin-2 Charpy V.Notch Data Temperature Input L E. Computed LE. Differential 140. 00 83. 00 86. 09 -3. 09 210.00 88. 00 88. 9 1 91 250. 00 91. 00 89.15 1.85 Correlation Coefficient = .989 WCAP-17501-NP February 2012 Revision 0

C-44 Westin2house Non-Pronrietarv Class 3 C-4Wetngos NnPrtitavCls CAPSULE 263- (SURVEILLANCE WELD METAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 06/28/2011 10:51 AM Page I Coefficients of Curve I A = 50. B = 50. C = 46.36 TO = 58.42 D = 0.OOE+00 Equation is A + B * [Tanh((T-ToY(C+DT))]

"l'emperature at 50% Shear = 58.5 Plant: Calvert Cliffs 2 Material: SAW Heat: 10137 Orientation: NA Capsule: 263 luence: n/cm'2 12s 100 1-75 a) 50 25 0

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

- 50. 00 00 92 -92

- 25, 00 10. 00 2.66 7. 34 00 5. 00 7. 45 -2. 45

10. 00 15. 00 1t.02 3. 98

20. 00 20. 00 16. 01 3.99

25. 00 15.00 19. 13 -4.13

40. 00 45. 00 31. 12 13.88 50, 00 20, 00 41.02 -21,02

75. 00 75. 00 67. 16 7. 84 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-45 CAPSULE 263° (SURVEILLANCE WELD METAL)

Page 2 Plant: Calvert Cliffs 2 Material: SAW Heat: 10137 Orieniation: NA Capsule: 263 Fluence: n/c^nA2 Charpy V.Notch Data Tmperatur Input Percent Shear Computed Pvrcent Shear Differential 140.00 00., 00 97. 12 2. 88 210. 00 100. 00 99. 86 .14 250. 00 100. 00 99. 97 03 Correlation Coefidient = ,977 WCAP- 17501 -NP February 2012 Revision 0

C-46 Westin2house Non-Proorietarv Class 3 C-6Wsinghue o-PoritryCas CAPSULE 2630 (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 06/28/2011 10:54 AM Page I Coefficients of Curve I A = 53.35 B = 51.15 C = 130.22 T0 = 129.71 I)= 10.00E+00 Equation is A + B

• lTanh((T-ToA(C+DT))I Upper Shelf I*nergy= 104.5(Fixed) L)wer Shelf Energy--2.2(Fixed)

Temp@30 ft-lbs=65.6 Deg F Temp@50 ft-lbs= 121.2 Deg F Plant: Calvert Cliflf 2 Material: SA533B I Heat: C-5286- I Orientation: NA Capsule: 263 Fluence: n/em^2 300 250 S200 0

LL.

150

'U z

100 0 50 0

0 0

-300,0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 50. 00 I1. 00 8. 29 2 71

- 25. 00 18.00 10.90 7. 10

.00 23. 00 14.48 8. 52

25. 00 28. 00 19.27 8. 73

50. 00 20. 50 25. 44 -4. 94

60. 00 25. 00 28. 32 -3. 32

75. 00 36. 50 33. 04 3. 46 140. 00 50. 50 57. 38 -6. 88 180. 00 49, 00 72. 18 -23. 18 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-47 CAPSULE 263° (HEAT AFFECTED ZONE)

Page 2 Plant: Calvert Cliffs 2 Material: SA533BI Heat: C-5286-1 Orientation: NA Capsule: 263 Fluence: n/cm"2 Charpy V-Notch Data Temperawur Input CVN Computed CVN Differential 210.00 92. 00 81.42 10.58 250. 00 103. 50 90. 57 12. 93 300. 00 1 18, 00 97, 53 20. 47 Correlalion Co.fficiern = .951 WCAP-17501-NP February 2012 Revision 0

C-48 Westin2house Non-Proorietarv NnProitayCls Class 3 C-8Wetngos CAPSULE 2630 (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 06128/2011 10:58 AM Page I Coefficients of Curve I A = 63.O5 B = 62.05 C = 209.64 TO = 189.93 D = 0.00E+0O Equation is A + B * [Tanh((T'-ToY(C+DT))j Upper Shelf LE.= 125.1 Lower Shelf L E.= 1.0( Fixed)

Tehnp.@LE. 35 rnils,=87.8 Deg F Plant: Calvert Cliffs 2 Material: SA533B I Heat: C-5286- I Orientation: NA Capsule: 263 Fluence: n/kim2 200

.2 2

a 10, 0 . 0

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

- 50. 00 13. 00 12.42 58

- 25. 00 17. 00 15.1t5 1.85

.00 23. 00 18.42 4.58

25. 00 27. 00 22. 3 1 4.69

50. 00 20. 00 26. 83 6.685

60. 00 24. 00 28. 86 -4. 86

75. 00 34. 00 32. 07 1 93 140, 00 48, 00 48. 54 - .54 I 80. 00 53. 00 6(0. 11 -7. 11 WCAP-1 7501 -NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-49 Westinghouse Non-Proprietary Class 3 C-49 CAPSULE 2630 (HEAT AFFECTED ZONE)

Page 2 Plant: Calvert Cliff' 2 Material: SA533B1 Heat: C-52861 Orientation: NA Capsule: 263 Fluence: n/cnm^2 Charpy V-Notch Data Temperature Input LE. Computed LE. Differential 2 10. 00 76. 0(0 68. 97 7. 03 250. 00 85. O0 80. 35 4. 65 300, 00 89, 00 92, 92 -3, 92 Correlation Coefficient = .984 WCAP-17501-NP February 2012 Revision 0

C-50 C....Westin.house Non-Pronrietarv Class 3 CAPSULE 263° (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 06128/2011 11:00 AM Page I Coefficients of Curve I A = 50. B = 50. C = 71.01 TO = 123.77 D = O.OOE+00 Equation is A + B * [Tanh((T-ToY(C+DT))]

Temperature at 50% Shear= 123.8 Plant: Calvert Cliffs 2 Material: SA533B I Heat: C-5286-1 Orientation: NA Capsule: 263 Fluence: n/cmA2 125 100 L., 75 2 50 it 25 0 1 0

0

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

-50. 00 .00 .74 74

- 25. 00 10.00 1.49 8. 51

25. 00 10.00 2. 97 7. 03 00 5. 00 5. 83 83

50. 00 10.00 11. 13 13

60. 00 20. 00 14. 23 5. 77

75. 00 15. 0(0 20. 20 - 5. 20 140, 00 60. 00 61.23 - 1. 23 180. 00 80. 00 82. 97 97 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-51 CAPSULE 2630 (HEAT AFFECTED ZONE)

Page 2 Plant: Calvert Cliffs 2 Material: SA533BI Heat: C-5286-1 Orientation: NA Capsule: 263 Fluence: n/crn^2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Sher Differential

91. 90 210.00 100. 00 8. 10 250. 00 100. 00 97. '22 2. 7 8 300. 00 100, 00 99. 31 .69 Correlalion Cwefficiew =.994 WCAP-17501-NP February 2012 Revision 0

C-52 Westin2house Non-ProDrietarv Class 3 C-52 Westinghouse Non-Proprietary Class 3 CAPSULE 2630 (STANDARD REFERENCE MATERIAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 06128/201 l :16 AM Page I Coefficients of Curve I A = 46.05 B = 43.85 C = 64.05 TO = 175.15 1) = O.OE+00l Equation is A + B * [fanh((T-'I'oY(C+DlT))]

Upper Shelf Energy=89.9(,Fixed) Lower Shelf Energy=2.2(Fixed)

"etnp@30 ft-lb--l50.6 Deg F Temp@50 f-lbs-= 181.0 Deg F Plant: Catven Cliffs 2 Material: SA533B1 Heat: HSST-01MY Orientation: LT Capsule: 263 Fluence: n/cmn2 300 250

, 200 0

LL i*10 L-100 0

50 0

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

50. 00 9. 00 3. 93 5. 07 75,00 9. 00 5. 88 3. 12 100.00 11. 00 9. 86 1. 14 120.00 17, 50 15.49 2. 01 140.00 31.00 24. 14 6. 86 160.00 31. 50 35. 86 -4.36 180.00 42. 00 49. 36 -7. 36 210. 00 65. 00 67. 80 2, 80 230. 00 84. 00 76. 50 7. 50 WCAP- 17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-53 CAPSULE 263- (STANDARD REFERENCE MATERIAL)

Page 2 Plant: Calvert Cliffs 2 Material: SA533B1 Heat: HSST-O IMY Orientation: LT Capsule: 263 Fluence: nt/cmA2 Cliarpy V-Notch Data Temperaluic Input CVN Computed CVN Differential 250, 00 87. 50 82. 17 5.33 300, 00 94. 00 88. 16 5. 84 350, 00 94. 00 89. 53 4.47 Correlation Cc~fficient=.991 WCAP-17501-NP February 2012 Revision 0

C-54 C-4WsingoseNn-rpietryCas Westin2house Non-Prol)rietarv Class 3 CAPSULE 263° (STANDARD REFERENCE MATERIAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 06/28/2011 1 t1:18 AM Page I Coecikients of Curve I A = 40.47 B = 39.47 C= 70.86 TO = 158.62 D = 0. OOE+00 Equation is A + B * [Tanh(Cb-I'oy(C+DT))i Upper Shelf LE.=79.9 Lower Shelf L.E.=1 .0(Fixed)

Temp.@L.E. 35 rnils=148.8 Deg F Plant: Calvert Cliffs 2 Material: SA53311 Heat: HSST-0IMY Orientation: LT Capsule: 263 Ftuence: n/em"2 200 150 E

a 100 50 0 t=

-300.0 0.0 300.0 600.0 Temperature In Deg F Charpy V.Notch Data Tenlperatum, Input L.E. Computed LiE. Differential

50. 00 1 1. 00 4.52 6. 48

75. 00 ItI. 00 7.81 3. 19 300. 00 13. 00 13. 67 67 120. 00 20. 00 20. 86 86 140. 00 30. 00 30.33 -. 33 160. 00 30. 00 41. 24 24 180. 00 67, 00 52. 03 14, 97 210. 00 57. 00 64. 95 7. 95 230. 00 74. 00 70. 66 3. 34 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-55 Westinghouse Non-Proprietary Class 3 C-55 CAPSULE 2630 (STANDARD REFERENCE MATERIAL)

Page 2 Plant: Calvert Cliffs 2 Material: SA533B1 Heat: HSST-OIMY OrientatiOn: LT Capsule: 263 Flueuce: I/cin^2 Charpy V-Notch Data Temperature Input ILE. Computed L.E Differential 250. 00 75, 00 74.38 .62 300. 00 81 00 78. 52 2.48 350. 00 76, 00 79. 60 - .60 Correlation Coefficient= .973 WCAP-17501I-NP February 2012 Revision 0

C-56 Westinghouse Non-Proprietary Class 3 CAPSULE 263' (STANDARD REFERENCE MATERIAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 06/28/2011 11:19 AM Page 1 Coefficents of Curve I A = 50. B = 50. C = 7.43 TO.= 214.35 D = O.OOE+00 Equation is A + B

• ITanh((T-ToY(C+DT))]

Temperaturc at 50% Shear = 214.4 Plant: Calvert Cliffs 2 Material: SA533BI Heat HSST-01 MY Orientation: LT Capsule: 263 Fluence: nlcm^2 125 100 6-75

'a M

so 25 0 !I -F 1

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F Charpy V-Notch Data Temperatur Input Percent Shear Computed Percent Shear 50, 00 00 00 00 75.00 5. 00 00 5. 00 t00. 00 5. 00 00 00 120.00 10. 00 00 I0. 00 140.00 10. 00 00 10. 00 160 (00 20. 00 00 00 180,00 25. 00 01 24. 99 2 10. 00 25. 00 23 65 35 230 00 S00. 00 98. 54 46 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-57 CAPSULE 2630 (STANDARD REFERENCE MATERIAL)

Page 2 Plant: Calvert Cliffs 2 Material: SA533BI Heat HSST-OIMY Orientation: LT Capsule: 263 Fluence: ncrn^2 Charpy V-Notch Data Temperature Input, percent Shear Computed Percent Shear Differential 250, 00 100.00 99. 99 01 300. 00 100. 00 100. 00 00 350. 00 100. 00 100. 00 00 Correlation Cuefficient = .988 WCAP-17501-NP February 2012 Revision 0

C-58 Westin2house Non-Promietarv, Class Cls 33 C-8Wsineoue onProretr CAPSULE 97° (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 05/23/2011 01:52 PM Page I Coefficients of Curve I A = 55.1 B = 52.9 C = 83.97 TO = 166.16 D = 0.00E+00 Equation is A + B [Tanh((T-ToY(C+DT))]

Upper Shelf Energy= 108.0(Fixed) Lower Shelf lnergy=2.2(Fixed)

Temp( 30 ft-lbs=122.9 Deg F Tempt@50 ft-lIb,=158.1 De'g F Plant: Calvert Cliffs 2 Material: SA5331I Heat: C-5286-1 Orientation: LT Capsule: 97 Fluence: n/cnmA2 300 250 S200 150 w

z 0 - -

100 so 0

-300.0 0

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

70. 00 12. 00 M 1..3 93 07 100. 00 28. 11.

50 20. 33 . 1.7 100. 00 20. 50 20. 33 17 120. 00 30. 00 28. 63 t 37 120. 00 34. 00 28. 63 5.37 140. 00 32. 50 39, 13 -6. 63

60. 00 46. 50 51.23 .4 73 180. 00 59. 50 63. 74 -4.24 220. 00 87. 50 85. 03 2.47 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-59 CAPSULE 970 (LONGITUDINAL ORIENTATION)

Page 2 Plant: Calvert Cliffs 2 Material: SA533B1 Heat: C-5286-1 Orientation: LT Capsule: 97 IFluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN I)iftrential 260.00 107.00 97. 78 9. 22 340. 00 109.00 106.34 2. 66 550. 00 95. 50 107.99 -12. 49 Correlation Cxefficient = 984 WCAP-17501-NP' February 2012 Revision 0

C-60 Westinizhouse Non-Pronrietarv Class 3 C-60 Westinehouse Non-Pronrietarv Class 3 CAPSULE 970 (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperblolic Tangent Curve Printed on 05/231201 I 01:54 PM Page I Coefficients of Curve I A = 44.12 B = 43.12 C = 97.13 TO = 158.43 D = O.O0E+00-r Equation is A + B [Tanh((1-TohY(C+DT))I Upper Shelf L.E.=87.2 Lower Shelf L.E.=1 ,O(Fixed)

Temp.@L.E. 35 nails= 137.6 Deg F Plant: Calvert Cliffs 2 Material: SA533BI Heat: C-5286-1 Orientation: LT Capsule: 97 Fluence: n/crnd2 200 150 2

Ul 50 0 +=

-300.0 0.0 300.0 600.0 Temperature In Deg F Charpy V-Notch Data Temperature Input LE. Computed LE.. Differential 70 00 12. 00 13.02 -I.02 1 00. 00 27. 00 2.0. 92 6. 08 oo. 00 22. 00 20. 92 t.08 120. 00 28. 00 27. 90 10 120. 00 33. 00 27. 90 5. 10 140. 00 29. 00 36. 04 -7. 04 1 60. 00 42. 00 44. 82 -2. 82 180. 00 50. 00 53. 55 -3 55 220. 00 70. 00 68. 30 1 70)

WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-61 CAPSULE 970 (LONGITUDINAL ORIENTATION)

Page 2 Plant: Calvert Cliffs 2 Material: SA533BI Heat: C-5286-1 Orientation: LT Capsule: 97 Fluence: ncrnm^2 Charpy V-Notch Data Temperature Input L.E. Computed LE. Differential 26(). 00 84, 00 77. 77 6. 23 340. 00 89. 00 85. 24 3. 76 550. 00 80. 00 87. 22 - 7. 22 Correlation Coefficient = .985 WCAP- 17501 -NP February 2012 Revision 0

C-62 Westinehouse Non-Pronrietarv Class 3 C-2Wsineoue onProIetrvCas CAPSULE 970 (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 05/23/2011. 01:58 PM Page 1 Coefficients of Curve I A = 50. B = 50. C= 73.1 TO = 169.96 D = 0.OOE+00 Equation is A + B * [Tanh((T-ToV(C+DT))]

Temperature at 50% Shear = 170.0 Plant: Calvert Cliffs 2 Material: SA533B I Heat: C-5286-1 Orientation: LT Capsule: 97 Fluence: n/cmn^2 125 100 75 cn 2 50 25 0

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

70. 00 10.00 6. 10 3. 90 100. 00 25. 00 12. 85 12. 15 100. 00 10. 00 12.85 -2 85 120. 00 20. 00 20. 31 331 120. 00 20. 00 20. 3 1 331 141). 00 30. (0 30. 58 58 160. 00 40. 00 43. 23 -3. 23 180. 00 50. 00 56. 82 -6. 82 220. 00 85. 00 79.72 5. 28 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-63 CAPSULE 97° (LONGITUDINAL ORIENTATION)

Page 2 Plant: Calvert Cliffs 2 Material: SA533B1 Heat: C-5286-1 Orientation: LT Capsule: 97 Fluence: n/cm,2 Charpy V.Notch Data Temperature Input Percent Shtar Computed Percent Shear Differential 260. 00 100. 00 92. 15 7,85 340.00 100. 00 99. 05 .95 550.00 too, 00 .100. 00 00 Correlation Coefficient =.990 WCAP-17501-NP February 2012 Revision 0

C-64 Westinghouse Non-Provrietarv Class 3 C-4Wsingos NnPopitry ls CAPSULE 97- (TRANSVERSE ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Prined, on 05/23/2011 02:04 PM Page I Coefficients of Curve I A = 44.45 B = 42.25 C = 84.92 TO = 167,71 D = 0.O0E+0O Equation is A + B * [Tanh(CT-To)/(C+DT))]

Upper Shelf Encrgy=86.7(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=137.5 Deg F Tenip@50 ft-lbhz179.0 Deg F Plant: Calvert Cliffs 2 Material: SA533BI Heat: C-5286-1 Orientation: TL, Capsule: 97 Fluence: n/crn'2 300 250

'200 0

u,.

S150 100 0 L0 0

50 0

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

70. 00 21. 50 9. 89 11.61 t00. 00 18. 50 16. 46 2. 04 120. 00 23.50 22. 93 .57 140, 00 27. 50 31 13 -3. 63 160. 00 36. 50 40. 63 -4. 13 180. 00 50. 50 50. 52 -. 02 200, 00 56. 50 59. 78 -3. 28 220. 00 68. 50 67. 61 . 89 260. 00 88. 00 78. 07 9. 93 WCAP- 17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-65 CAPSULE 97° (TRANSVERSE ORIENTATION)

Page 2 Plant: Calvert Cliffs 2 Material: SA533BI Heat: C-5286-1 Orientation: TL Capsule: 97 Fluence: nlcmrA2 Clharpy V-Notch Data Temperattte Input CVN Compuled CVN l)iffmermit 300. 00 86. 50 83. 11 3. 39 340. 00 85. 50 85. 26 24 550. 00 81,50 86. 69 -5.19 Correlation Coefficient = .982 WCAP-1750 1-NP February 2012 Revision 0

C-66 Westin2house Non-ProDrietarv Class 3 C-66 Westinghouse Non-Proprietary Class 3 CAPSULE 970 (TRANSVERSE ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 05/23/2011 02:06 PM Page I Coefficients of Curve 1 A = 40.44 B = 39.44 C = 99.06 TO = 161.27 D = O.OOE+00 Equation is A + B * [T'anh(tT-ToY(C+DT))]

Upper Shelf LE.=79.9 Lower Shelf L E.=l.O(Fixed)

Temp. @LE. 35 mils=147.6 Deg F Plant: Calvert Cli-, 2 Material: SA5331 I Heat: C-5286- I Orientation: TL Capsule: 97 Fluence: n/en02 200 150 (C

8.100 I5 50 0 0 0

0 0

-300.0 0.0 300.0 600.0 Temperature In Deg F Charpy VNotch Data Temperature Input LE. Computed LE. Differential

70. 00 21. 00 11. 78 9. 22 1.00. 00 20. 00 18. 74 1 26 120. 00 24. 00 24. 90 90 140. 00 29. 00 32. 10 -3 10 160. 00 33. 00 39. 93 -6. 93 180. 00 51. 00 47, 81 3. 19 200. 00 53. 00 55, 12 .2 12 220. 00 63. 00 61 42 1 58 260. 00 78. 00 70. 42 7.58 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-67 CAPSULE 97- (TRANSVERSE ORIENTATION)

Page 2 Plant: Calvert Cliffs 2 Material: SA533B I Heat: C-5286- I Orientation: TL Capsule: 97 Fluence: rn'cm^2 Charpy V-Notch Data Temperature Input LE. Compure.d I-E. Differential 300. 00 74. 00 75. 36 - I. 36 340. 00 79. 00 77. 80 1.20 550. 00 75.00 79.85 -4.85 Correlation Cofficient = .981 WCAP-17501-NP February 2012 Revision 0

C-68 Westinehouse Non-Proprietary Class 3 C-68 Westin2house Non-Proorietarv Class 3 CAPSULE 97° (TRANSVERSE ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 05/231/2011 02:08 PM Page 1 Coefficients of Curve I A = 50. B = 50. C = 72.01 TO = 180.73 D = O.OOE+OO Equation is A + B t[Tanh((T-ToY(C+DTI))j Temperature at 50% Shear = 180.8 Plant Calvert Cliffs 2 Material: SA53311 I Heal: C-5286-t Orientation: T., Capsule: 97 Fluence: n/cm^2 125 100 J0 75 0

0. so 25

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

'70. 00 , 00 4. 41 -4. 41 I oo, 00 9. 60 40 120. 00 15. 00 15.62 62 140, 00 30, 00 24. 39 5. 61 160. 00 40. 00 35, 99 4. 01 180. 00 45. 00 49. 49 -4. 49 200. 00 60. 00 63.07 -3. 07 220. 00 70. 00 74, 85 -4 85 260. 00 100. 00 90. 04 9. 96 WCAP- 17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-69 CAPSULE 917 (TRANSVERSE ORIENTATION)

Page 2 Plant: Calvert Cliffs 2 Material: SA533B1I Heat: C-5286-1 Orientation: TL Capsule: 97 Fluence: n/cM^2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 300 00 100. 00 96. 49 3.51 340. 00 100. 00 98.81 . 119 550. 00 100. 00 100. 00 .00 Correlation Coefficient = .993 WCAP-17501-NP February 2012 Revision 0

C-70 Westinehouse Non-Pronrietarv Non-Pronrietarv Class C-70 Westinehouse Class 33 CAPSULE 97° (SURVEILLANCE WELD METAL)

CVGRA PH 5.3 Hyperbolic Tangent Curve Printed on 05/23/2011 02:19 PM Page I Coefficients of Curve I A=49.75 B =47.5SC=70.19 TO=60.18 D= 0.OOE+00 IEquation is A + B

• rranh(l'H'o)/(C+DTf))

Upper Shelf Energy=97.3(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 fi-lbs=29.2 Deg F Temnp@50 ft-lb.60.6 Deg F Plant Calvert Cliffs 2 Material: SAW Heat: 10137 Orientation; NA Capsule: 97 Fluence: nlcfi^2 300 250

'2 200 IL 150 w

0

> 100 0 50

/0 0

0

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN I)ifferentiat

.00 25. 00 16.71 8. 29

20. 00 11 00 25. 16 S14. 16

30. 00 5 1. 50 30.48 21.02

40. 00 26. 00 36z 44 -10.44

55. 00 50. O0 46. 25 3. 75

70. 00 46. 00 56, 36 - 10. 36 I00. 00 77, 00 74. 16 2. 84 140. 00 95. 50 88. 43 7. 07 180. 00 92. 50 94.27 - I .77 WCAP- 17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-71 CAPSULE 97- (SURVEILLANCE WELD METAL)

Page 2 Plant: Calvert Cliffs 2 Material: SAW Heat: 10137 Orientation: NA Capsule: 97 Fluence: n/cm^2 Charpy V-Notch Data Temperature Input CYN Computed CYN Differential 220. 00 104, 50 96. 31 8.19 260. 00 95. 00 96. 98 - I. 98 Correlation Coefficient = 950 WCAP-17501-NP February 2012 Revision 0

C-72 Westinahouse Non-Pronrietarv Class 3 C-2Wetngos NnProitavCls CAPSULE 970 (SURVEILLANCE WELD METAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 05/23/2011 02:25 PM Page 1 Coefficients of Curve I A = 41.98 B = 40.98 C = 83.94 TO = 59.11 D = O.OOE+00 Equation is A + B * [Tanh((T-ToY(C+DT))]

Upper Shelf LE.=83.0 Lower Shelf LE.=l.O(Fixed)

Temnp.@L.E. 35 mils=44.7 Deg F Plant: Calvert Cliffs 2 Material; SAW Heat: 10137 Orientation: NA Capsule: 97 Flucncm: n/crnm2 200 ISO a100 50 0 *

-300.0 0.0 300.0 600.0 Temperature In Deg F Charpy V-Notch Data Tcmnperature Input LE. Computed LE. Differential

.00 23. 00 17. 10 5. 90

20. 00 13. 00 24, 15 15

30. 00 42. 00 28.31 13. 69

40. 00 26. 00 32. 80 80

55. 00 40. 00 39. 97 -. " 03

70. 00 45. 00 47. 26 26

!00. 00 61. 00 60. 49 51 14-0. 00 76. 00 72, 54 3. 46 I80. 00 78. 00 78. 60 60 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-73 CAPSULE 970 (SURVEILLANCE WELD METAL)

Page 2 Plant; Calvert Cliffs 2 Material: SAW Heat: 10137 Orientation: NA Capsule: 97 Fluence: n/cm"2 Charpy V-Notch Data Temperature Input LE. Computed LE. Differential 220. 00 82. 00 81. 22 ..78 260. 00 80. 00 82. 27 -2. 27 Correlation Coefficient = .967 WCAP- 17501-NP February 2012 Revision 0

C-74 Westinp-house Non-Promietarv Class 3 C7Wetinhus onPolitayClsd CAPSULE 97' (SURVEILLANCE WELD METAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 05/23/2011 02:28 PM Page I Coefficients of Curve 1 A = 50. B = 50. C = 71.57 TO = 48.7 D = 0.00E+O0 Equation is A + B

• jTunh([T-ToY(C+DT))I Temperature at 50% Shear= 48.8 Plant. Calvert Cliffs 2 Material: SAW Heat: 101.37 Orientation: NA Capsule: 97 Fluence: ncnA"2 125 100 75 (0

0)

C) 50 25 0

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

'00 30. 00 20. 41 9. 59

20. 00 10, 00 30. 96 - 20. 96 30, 00 50. 00 37. 22 12.78

40. 00 45. 00 43. 95 1. 05

55. 00 55. 00 54. 39 61

70. 00 60. 00 64. 45 -4. 45 100. 00 85. 00 80. 7 4 4. 26 140. 00 90. 00 92. 77 -2.77 180. 00 100. 00 97.51 2. 49 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-75 CAPSULE 97" (SURVEILLANCE WELD METAL)

Page 2 Plan*: Calvert Cliffs 2 Material: SAW Heat: 10137 Orientation: NA Capsule: 97 Fluc:nce: ncin^2 Charpy V-Notch Data TenperatuI Input Percent Shar Computed Percent Shear 1)ifferemuial 220. 00 100. 00 99. 17 83 260. 00 100. 00 99. 73 .27 Correlation Coefficienl = .961 WCAP-17501-NP February 2012 Revision 0

C-76 Westinghouse Non-Proprietarv Class 3 C-6Wsingos o-rpietry ls CAPSULE 97° (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 05/23/2011 02:31 PM Page I Coefficients of Curve I A = 41.8 B = 39.6 C = 93.04 TO = 84.74 D = 0.OOE+00 Equation is A + B

• ITanh((T-ToY(C+DT))j Upper Shelf Energy=81,4(Fixed) L.ower Shelf Energy=2.2(Fixed)

Ternp@30 ft-lbs=56.2 Deg F Temp@50 ft-lb.l104.3 Deg F Plant: Calvert Cliffs 2 Material: SA533B I Heat: C-5286-1 Orientation: NA Capsule: 97 Fluence: n/cm^2 300 250 200 0

150 nU 0

z

> 100 0 0 0 50 0 0

00 0

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

30. 00 44. 50 20. 86 23. 64

70. 00 23. 50 35. 58 -12. 08

85. 00 25. 50 41.91 -16. 41 100. 00 31.50 48. 24 -16,74 110.00 82. 00 52. 29 29. 71 120. 00 53. 50 56. 13 -2. 63 140. 00 54. 00 62. 90 - 8. 90 160. 0( 84. 50 68, 29 16.21 18(1. 00 67. 50 72. 35 -4. 85 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-77 CAPSULE 97- (HEAT AFFECTED ZONE)

Page 2 Plant: Calvert Cliffs 2 Material: SA533BI Heat: C-5286-1 Orientation: NA Capsule: 97 Fluence: n/cm^2 Charpy V.Notch Data Temperature Input CVN Computed CVN Differential 220. 00 78. 00 77. 30 .70 260. 00 95, 00 79. 6 1 15. 39 550. 00 116, 50 81,40 35. 10 Correlation Coettficilfi = .793 WCAP-17501-NP February 2012 Revision 0

C-78 Westinghouse Non-Pronrietarv Class 3 CAPSULE 970 (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 05/23/201 1 02:35 PM Page I Coefficients of Curve I A = 43.77 B = 42.77 C = 144.66 T0 = 113.04 D = 0.0OE+00 Equation is A + B " [Twih((T-ToY(C+DT))1 Upper Shelf L.E.=86.5 Lower Shelf L.E.= .O(Fixed)

Tewp.@LE, 35 ruils=83.0 Deg F Plant; Calvert Cliffs 2 Materiai SA533Bl Heat: C-5286-1 Orientation: NA Capsule: 97 Fluence: n/cmni2 200 150 C

.2 S100 so 50 0 4=

-300.0 0.0 300.0 600.0 Temperature In Deg F Charpy V-Notch Data Temperature Input LE. Computed LE. D)ifferential

30. 00 36. 00 2 1. 60 14. 40

70. 00 23, 00 31. 41 -8. 41

85. 00 25. 00 35, 58 - 10. 58 I 00ý 00 26, 00 39. 93 -13. 93 110. 00 60. 00 42. 87 17. 13 120. 00 47. 00 45. 83 1 .17 140. 00 48, 00 5 1, 65 - 3. 65 160. 00 70. 00 57. 19 12. 81 180. 00 57. 00 62. 27 -5. 27 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-79 CAPSULE 970 (HEAT AFFECTED ZONE)

Page 2 Plant: Calvert Cliffs 2 Material: SA533BI Heat.: C-5286-1 Orientation: NA Capsule: 97 Flue:nce: n/cm^2 Charpy V.Notch Data Temporatum, Input LE. Computed LE. Differential 220. 00 67. 00 70, 67 -3.67 260. 00 80, 00 76. 63 3.37 550. 00 85. 00 86. 34 -I .34 Correlation Cfficient =.S84 WCAP-1750 1-NP February 2012 Revision 0

C-80 Westinahouse Non-ProDrietarv Class 3 C-0WsingoueNo-roritrvCas CAPSULE 97° (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 05/23/2011 02:38 PM Page 1 Coefficients of Curve I A = 50. B = 50. C = 97.51 TO = 73.97 D = O.OOE+00 Equation is A + B

• Tflnh((T-ToY(C+DT))I Temperature at 50% Shear= 74.0 Plant: Calvert Cliffs.2 Material: SA5331I1 Heat: C-5286-1 Orientation: NA Capsule: 97 Flhcnce: n/cnA2 125 100 0 o L-CO 75 50 A

25 J0 0

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

30. 00 65. 00 28. 87 36. 13

70. 00 25. 00 47. 96 22. 96

85. 00 30. 00 55. 63 - 25. 63 100. 00 50, 00 63. 04 -13.04 I 0. 00 95. 00 67. 68 7 32 120 00 65. 00 71.99 -6. 99 140. 00 80. 00 79. 48 .52 160. 00 100. 00 85. 38 14. 62 180. 00 too. 00 89. 79 10. 21 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-81 Wetnhos onPoritr Cas3_-

CAPSULE 970 (HEAT AFFECTED ZONE)

Page 2 Plant: Calvert Cliffs 2 Material: SA533B1 Heat: C-5286-1 Orientation: NA Capsule: 97 Fluence: n/cmW'2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 220. 00 100. o00 95. 23 4. 77 260. 00 100. 00 97. 84 2. 16 550. 00 100. 00 99. 99 . 01 Correlation Coefficient =.761 WCAP-17501-NP February 2012 Revision 0

C-82 C-82 Westinizhouse Non-Pronrietarv Class 3 CAPSULE 104° (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 11/02/2011 03:01. PM Page 1 Coefficients of Curve I A = 54.95 B = 52.75 C = 78.24 TO = 187.01 D = O.OOE+00 Equation is A + B * [Tanh((T-ToY(C+DT))I Upper Shelf Energy=107.7(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs= 146.9 Deg F Temp@50 ft-lbs-179.7 Deg F Plant: Calvert Cliffs 2 Material: SA5338 I Heat: C-5286-1 Orientation! tLT Capsule: 104 Fluence: u/c^nA2 300 250 S200 0

i 150 z

100 50 0 , I

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential I 00 4. 00 3. 08 .92

75. 00 22. 00 7, 90 14. 10 125. 00 26. 00 20, 14 5. 86 150. 00 28. 00 31.71 3 71 155. 00 31. 00 34. 50 3. 50 165. 00 37. 00 40. 49 -3. 49 175. 00 45. 00 46. 92 -I. 92 190. 00 51. 00 56. 96 -5. 96 210. 00 82. 00 70. 02 I1. 98 WCAP- 17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-83 CAPSULE 1040 (LONGITUDINAL ORIENTATION)

Page 2 Plant: Calvert Cliffs 2 Material: SA533BI Heat: C-5286-1 Orientation: LT Capsule: 104 Fluence: n/cnV^2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 325. 00 92. 00 104,69 - 12ý 69 340. 00 108. 00 105.63 2, 37 350. 00 123. 00 106.09 16. 91 Correlation Coeflicient = .972 WCAP- 17501-NP February 2012 Revision 0

C-84 Westinehouse Non-ProDrietarv Class 3 C-4WsingoseNn-rnietrvCas CAPSULE 104" (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 11/02/2011 02:51 PM Page I Coefficients of Curve I A = 43.57 B = 42.57 C = 128.03 TO = 174.23 D = 0.OOE+O0 Equation is A + B1 [Tanh((T-ToY(C+DT))]

Upper Shelf LE.=86.1 Lower Shelf LE,=I .O(Fixed)

Temp. @L.2. 35 mils=148. I Deg F Plant: Calvert Cliffs 2 Material: SA533BI Heat: C-5286-1 Orientation: LT Capsule: 104 Fluenee: n/cmk2 200 150 E

C a100 15 50 0 ]m

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

'00 8. 00 6. 25 I.75

75. 00 25. 00 15.91 9. 09 125. 00 27. 00 27. 96 -. 96 1.50. 00 28. 00 35. 61 -7,61 155.00 35. 00 3'7. 22 -2.22 165. 00 35. 00 40.51 -5.51 175, 00 44. 00 43. 83 .17 190. 00 47. 00 48. 79 -I .79 210.00 69, 00 55. 17 13 83 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-85 CAPSULE 1040 (LONGITUDINAL ORIENTATION)

Page 2 Plant: Calvert Cliffs 2 Material: SA533BI Heat: C-5286- I Orientation: LT Capsule: 104 Fluence: n/cm^2 Charpy V-Notch Dtat Temperatue Input LE,. Computed LE. Differential 325. 00 74. 00 78. 77 -4.77 340. 00 82. 00 80. 20 1 80 350. 00 8t. 00 81.01 -. 01 Correlation Coefficient = .970 WCAP-17501-NP February 2012 Revision 0

C-86 Westin2house Non-ProDrietarv onPrpietryCas Class 3 C-6Wsingoue CAPSULE 104° (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 11102f2011 02:57 PM Page I Coefficients of Curve I A = 50. B = 50. C = 72. TO = 178.73 D = 0.00E+00 Equation is A + B * [Tanh((T-ToY(C+DT))I Temperature at 50% Shear= 178.8 Plant: Calvert Cliffs 2 Material: SA533B I Heat: C-5286-1 Orientation: LT Capsde: 104 Fluence: n/clnY2 125 100 0 75 In 0

2 50 0

0.

25

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

,00 '00 69 -. 69 75.00 10.'00 5.31 4. 69 125. 00 20. 00 18.35 1. 65 ISO, 00 30. 00 31.04 - I. 04 155. 00 40. 00 34. 09 5. 91 165. 00 30. 00 40. 58 - 10. 58 175, 00 50, 00 47, 41 2, 59 190. 00 55.00 57. 76 - 2. 76 210. 00 75. 00 70. 44 4. 56 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-87 Westinghouse Non-Proprietary Class 3 C-87 CAPSULE 104" (LONGITUDINAL ORIENTATION)

Page 2 Plant: Calvert Cliffs 2 Material: SA533BI Heat: C-5286-1 Orientation: LT Capsule: 104 Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 325. 00 100. 00 98.31 1.69 340. 00 100. 00 98. 88 1.12 350. 00 100,.00 99. 15 85 Correlation Coefficient = .993 WCAP-17501 -NP February 2012 Revision 0

C-88 WestinRhouse Non-Provrietarv Class 3 C-88 Westinghouse Non-Proprietary Class 3 CAPSULE 104- (SURVEILLANCE WELD METAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on I L/04/2011 08:26 AM Page I Coefficients of CurNe I A = 56.25 It = 54.05 C = 27.49 TO = 30.54 1) = 0.0I1-1+O)

Equation is A + B * [Tanh((T-ToY)(C+DT))]

Upper Shelf Energy=l 10.3(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=16,0 Deg F Tcmp@50 ft-lbsi=27,4 Deg F Plant: Calvert Cliffs 2 Material: SAW Heat: 10137 Orientation: NA Capsule: 104 Fluence: nkenA2 300 250 S200 0

ILl 1100 s0 0 I'

-300.0 -200.0 -100.0 0.0 100.0 200.0 3N00.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Tlemperature Input CVN Computed CVN Differential 100 9. 00 12. 77 -3. 77

15. 00 1t . 00 28. 59 -IT. 59

20. 00 S6, 00 36. 49 49. 51 25.00 42. 00 45. 51 - 3. 51

30. 00 25. 00 55. 20 -30. 20

50. 00 105. 00 89. 19 15. 81

60. 00 63. 00 98. 96 35. 96 75.00 165.00 106. 21 58. 79 150. 00 91. 00 110. 28 -19. 28 WCAP- 17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-89 Westinghouse Non-Proprietary Class 3 C-89 CAPSULE 1040 (SURVEILLANCE WELD METAL)

Page 2 Plant: Calvert Cliffs 2 Material: SAW Heat: 10137 Orientation. NA Capsule: [,04 Fluence: n/cm^2 Charpy V-Notch Data Temrnjral urn Input CVN Computed CYN Diffetrtiat 225. 00 97. 00 I10.30 - 13.30 250. 00 136.00 110.30 25.70 275.00 117.00 110.30 6, 70 Correlation Coeflicient = .801 WCAP-17501-NP February 2012 Revision 0

C-90 Westinehouse Non-Proorietarv Class 3 C0WstingoseNn-rnIetrvCas CAPSULE 104° (SURVEILLANCE WELD METAL)

CVGRAPLH 5.3 Hyperbolic Tangent Curve Printed on 11/04/2011 08:28 AM Page I Coefficients of Curve I A = 44.39 B = 43.39 C = 35.33 TO = 28.44 D = .OO.E+00 Equation is A + B * [ranh((T-To)/(C+DT))I Upper Shelf LE.=87. 8 Lower Shelf L.E. = I.0(Fixed)

Tenip.@10,E. 35 mils=20.7 Deg F Plant: Calvert Cliffs 2 Materinl: SAW Heat: 10137 Orientation: NA Capsule: 104 Fluence: n/cnA2 200 a

r._

0/

0 {

-300.0 0.0 300.0 600.0 Temperature In Deg F Charpy V-Notch Data Temperature Input LE. Computed LE. Diffe~rential

.00 15. 00 15,46 -46 15 00 13. (0 28, 63 -15. 63

20. 00 62. 00 34,21 27 79

25. 00 43, 00 4,0. 18 2. 82 30, 00 27. 00 46. 30 -19 30

50. 00 83, 00 68. 00 15 00

60. 00 55. 00 75. 33 20 33 75.00 96. 00 81.98 14. 02 150. 00 8 1. 00 87. 69 - 6. 69 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-91 CAPSULE 1040 (SURVEILLANCE WELD METAL)

Page 2 Plant: Calvert Cliffs 2 Material: SAW Heat: 10137 Orientation: NA Capsule: 104 Fluence: n/cm^%2 Charpy V-Notch Data Tempcraturc Input L E. Computed LE. Differential 225.00 8 1. 00 87,78 - 6. 78 250. 00 92. 00 87.7 8 4. 22 275.00 93. 00 87,78 5. 22 Correlation Coe fficient = .879 WCAP-17501-NP February 2012 Revision 0

C-92 Westinahouse Non-Pronrietarv Class 3 C-92 Westinghouse Non-Proprietary Class 3 CAPSULE 104° (SURVEILLANCE WELD METAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 1 1/04/2011 08:30 AM Page I Coefficients of Curve I A = 50. B = 50. C = 44.28 TO = 28.91 1) = 0.OOE+00 Equation is A + B * [Tanh((T-ToV(C+DT))j Te nperatu-e at 50% Shear= 29.0 Plant: Calvert Cliffs 2 Material: SAW Heat: 10137 Oriental ion: NA Capsule: 104 Fluence: nfcni2 125 100 L.

75 U) 4.,

0 50 25 0 -

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

.00 15. 00 2 1. 31

15. 00 20. 00 34. 78 -14.78

20. 00 60. 00 40. 07 19.93 25, 00 50. 00 45. 59 4.,41

30. 00 50. 00 51.23 I,23

50. 00 70. 00 72. 16 2. 16 60, 00 75. 00 80M 28 -5. 28 75.00 90. 00 88. 91 1. 09 150. 00 100. 00 99. 58 .42 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-93 CAPSULE 104' (SURVEILLANCE WELD METAL)

Page 2 Plant: Calvert Cliffs 2 Material: SAW Heat: 10137 Orientation: NA Capsule: 104 Fluence: n/cmA2 Charpy V.Notch Data Temperature Input Pecent Shear Cornputed Percenl Shear Differenlial 22 5 - 00 1 00. 00 99. 99 .01 250. 00 100, 00 0OO.00 S00 275- 00 100. 00 100.00 .00 Correlation Coefficient .966 WCAP-17501-NP February 2012 Revision 0

C-94 Westinghouse Non-Proprietary Class 3 C-4Wstnhue1o-roreay ls CAPSULE 104° (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 11/02/2011 013:55 PM Page I Coefficients of Curve I A = 48.1. B = 45.9 C = 158.19 To = 106.3 D = 0.OOE+00 Equation is A + B ITanh((T-ToY(C+DT))]

Upper Shelyf Energy=94.0(Fix cd) Lower Shelf Energy=2.2(Fixed)

Tcrnp@30 ft-lbk40.4 Deg F Tempp@50 ft-lbs 112.9 Deg F Plant: Calvert Cliffs 2 Material: SA533BI Heat: C-5286-I Orientation: NA Capsule: 104 Fluenee: nfcmA2 300 250 1 200 150 0U 150 100 0

so 0

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

-75. 00 15. 00 10. 62 4. 38

. 25. 00 1.2. 00 16. 87 -4 .87

-15.00 1.0. 00 18. 49 -8. 49 100 35, 00 21. 19 13. 81 20.00 20. 00 25, 28 -5 28

40. 00 17. 00 29, 92 12 92

50. 00 t7, 00 32, 42 -15. 42 75.00 73. 00 39. 14 33. 86 250. 00 61. 00 81. 17 -20. 17 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-95 CAPSULE 104° (HEAT AFFECTED ZONE)

Page 2 Plant: Calvert Cliffs 2 Material: SA533BI Heat: C-5286-1 Orientation: NA Capsule: 104 Fluence: n/crnA2 Charpy V-Notch Data Temperattrf Input CVN Computed CVN Differential 275. 00 70. 00 84. 27 14. 27 300. 00 85, 00 86. 70 - i.70 325.00 127.00 88. 56 38.44 Correlation Coefficient = .863 WCAP-17501-NP February 2012 Revision 0

C-96 Westinahouse Non-ProDrietarv Class 3 C-96 Westin2house Non-Proorietarv Class 3 CAPSULE 1040 (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 11/02/2011 04:101 PM Page I Coefficients of Curve I A = 35.73 B = 34.73 C = 11:1.76 TO= 61.96 D = 0.00E+00 E~quation is A + B * [Tanh((T-To)Y(C+/-DT))i Upper Shelf L.E.=70.5 Lower Shelf L.E.-.10(Fixed)

Tcmp.@L.,E. 35 mils59.6 Deg F Plant: Calvert Cliffs 2 Material: SA533BI Heat: C-5286-1 Orientation: NA Capsule: 104 Fluence: n/cm^2 200 150 ISO E

a100 Ulo i5 50 0 4 -- "" 1 - 1 -

-300.0 0.0 300.0 600.0 Temperature In Deg F Charpy V.Notch Data Temperature Input LiE. Computed LI.E Differential

-75. 00 00 6.51 4 49 tI.

-25. 00 14 00 13. 10 90

-15.00 8. 00 14, 99 -6. 99

.00 32. 00 18,23 13. 77

20. 00 2 1. 00 23. 27 - 2. 27

40. 00 20. 00 28. 99 -8. 99

50. 00 17. 00 32. 03 5. 03 75, 00 59. (00 39. 7 7 19. 23 250. 00 60. 00 68. 15 -8. 15 WCAP- 17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-97 CAPSULE 1040 (HEAT AFFECTED ZONE)

Page 2 Plant. Calvert Cliffs 2 Material: SA533B1 Heat: C-5286-1 Orientation: NA Capsule: 104 Fluence: n/cmA2 Charpy V-Notch Data Temperature Input LE. Computed LE. Diffemretial 275. 00 63. 00 68. 97 -5. 97 300. 00 73. 00 69. 50 3. 50 325. 00 78. 00 69. 85 8. 15 Correlation Coefficient =.924 WCAP-17501-NP February 2012 Revision 0

C-98 Westin2house Non-Proorietarv Class 3 C-98 Westinghouse Non-Proorietarv Class 3 CAPSULE 104' (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 11/02/201 I. 04:03 PM Page 1 Coefficients of Curve I A = 50. B = 50. C = 121.65 TO = 68.46 D = 0.)0E+O0 Equation is A + B " [Tanh((T-ToY(C-i-DT))j Temperature at 50% Shear = 68.5 Plant: Calvert Cliffs 2 Material: SA533BI Heat: C.5286-1 Orientation: NA Capsule: 104 Fluence: nrcm^n2 125 100 75

a. 50 25

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

-75. 00 10. 00 8. 64 1.36

-25. 00 20. 0(0 17. 70 2. 30

-15. 00 25. 00 20. 23 4. 77

,00 30. 00 24C 50 5. 50

'20. 00 30. 00 31.07 - 107

40. 00 25. 00 38,. 51 -13ý 51

50. 00 30 00 42. 47 -12 47 75.00 70. 00 52. 69 17. 31 250. 00 90 00 95. 19 -5, 19 WCAP-1750 1-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-99 Westinghouse Non-Proprietary Class 3 C-99 CAPSULE 1040 (HEAT AFFECTED ZONE)

Page 2 Plant: Calvert Cliffs 2 Material: SA533B1 Heat: C-5286-1 Orientation: NA Capsule: 104 Rluence: n/cm^2 Charpy V-Notch Data Temperature Input Percent Shear Computcd Percent Shear Differential 275. 00 I 00. 00 96. 76 3ý 24 300. 00 100. 00 97. 83 2. 17 325. 01)0 I 00. 00 98. 55 1.45 Correlation Coefficient = .97 4 WCAP-17501-NP February 2012 Revision 0

C-100 Westinghouse Non-Prot~rietarv Class 3 CAPSULE 1040 (STANDARD REFERENCE MATERIAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 11/04/2011 08: W)AM Page I Coefficients of Curve I A = 47.25 B = 45.05 C = 58.89 TO = 214.25 D = 0.01OF,+00 Equation is A + B * [Tanh((r-To)/(C+DT))j Upper Shelf Energy=92.3(Fxixed) Lower Shelf Energy-2.2(Fixed)

Temp@30 fl-lbs=190.5 Deg F Tenip@50 ft.-lbs217.9 Deg F Plant: Calvert Cliffs 2 Material: SA53381 Heat: HSST-01MY Orientation: LT Capsule: 104 Fluence: n/cmrn2 300 250 A200 1150 100 00 50 ~~-o-. -* -o 0

0

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

75. 00 4, 50 2, 99 1.51 150. 00 21.00 tI1 33 9. 67 175. 00 28. 00 21 00 7. 00 190.00 22. 00 29. 68 - 7, 68 200. 00 26. 00 36. 55 -10.55 210. 00 47, 00 44. 00 3. 00 220. 00 52. 08 51 63 37 225. 00 56. 00 55 38 62 235. 00 67. 00 62 50 4 50 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-101 CAPSULE 104° (STANDARD REFERENCE MATERIAL)

Page 2 Plant: Calvert Cliffs 2 Material: SA533B1 Heat HSST-OIMY Orientation: LT Capsule: 104 Phuence n/em^2 Charpy V-Notch Data Temperature Input CVN Computed CNN Differentital 325. 00 95. 00 90. 25 4.75 350. 00 89. 00 91.41 -2.41 375, 0 93. 00 91 . 92 1. 08 Correlation Coefficient = .983 WCAP-17501-NP February 2012 Revision 0

C-102 Westinghouse Non-Proprietarv Class 3 CAPSULE 1040 (STANDARD REFERENCE MATERIAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on I 1/04/2011 08:03 AM Page I Coeflicients of Cure 1 A = 41,13 B = 40,13 C = 104.92 TO = 213.16 D = 0,OOE+O0 Equation is A + B

• ITanh((T-ToY(C+DT))]

Upper Shelf L.E.=81.3 Lower Shelf L.E.=I.O(Fixed)

Temp. @L.E. 35 mils=197.1 Dkg F Plant: Calvert Cliffs 2 Material: SA533BI Heat: HSST-01 IMY Oricntalion: LT Capsule: 104 Fluentc: n/cmA2 200 U, 150 E

a0 ioo 50 0 1=

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

75. 00 I1 . 00 6.38 4.62 150. 00 24. 00 19.52 4.48 175.00 26. 00 27. 14 -1.14 190. 00 28. 00 32.41 -4.41 200, 00 27. 00 36. 12 -9. 12 210.00 41. 00 39. 92 1. 08 220, 00 45. 00 43. 74 1.26 225.00 48. 00 45.63 2.37 235.00 55. 00 49. 36 5. 64 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-103 CAPSULE 104' (STANDARD REFERENCE MATERIAL)

Page 2 Plant: Calvert Cliffs 2 Material: SA53381 Heat: I-SST-0IMY Orientation: LT Capsule: 104 Fluence: n/cmA2 Charpy V-Notch Data Teniplraltlu I11ut L.E. Computed LE. Differential 325. 00 75. 00 72. 74 2. 26 350. 00 70. 00 75. 74 -5.74 375. 00 80. 00 77. 74 2. 26 Correlation Coefficient = .979 WCAP-17501-NP February 2012 Revision 0

C-104 Westin2house Non-Prot)rietarv Class 3 C-104 Westinghouse Non-Proprietary Class 3 CAPSULE 104- (STANDARD REFERENCE MATERIAL)

CVGRAPI-l 5.3 Hyperbolic Tangent Curve Printed on 11/04/2011 08:05 AM Page I Coefficients of Curve I A = 50. B = 50. C = 75.33 TO = 208.6 D = O.OOE+00 Equation is A + B * [Tanh(('l-Toy(C+DT))j Temperature at 50% Shear = 208.6 Plant: Calvcrt Cliffs 2 Material: SA533BI Heat: HSST-01MY Orientation: LT Capsule: 104 Fluence: n/cm"2 1,

00 - -

U, 0,

0~

50

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

75. 00 10. 00 2. 80 7.20 1 50. 00 20. 00 17.43 2.57 175.00 30. 00 29. 07 .93

' 90. 00 40, 00 37, 90 2, 10 200, 00 40. 00 44, 32 -4.32 210. 00 50. 00 50. 93 - . 93 220. 00 50. 00 57. 51 -7.51 225, 00 60. 00 60. 7 2 -. 72 235, 00 75. 00 66. 84 8.16 WCAP- 17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 C-105 Westinghouse Non-Proprietary Class 3 C-105 CAPSULE 1040 (STANDARD REFERENCE MATERIAL)

Page 2 Plant: Calvert Cliffs 2 Material: SA533B1 Heat: HSST-01MY Orientation: LT Capsule: 104 Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 325. 00 100. 00 95. 65 4. 35 350. 00 100.00 97. 7 1 2. 29 375.00 100. 00 98.81 1.19 Correlation Coefficient =.990 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 D-1 APPENDIX D CALVERT CLIFFS UNIT 2 SURVEILLANCE PROGRAM CREDIBILITY EVALUATION D.1 INTRODUCTION Regulatory Guide 1.99, Revision 2 [Reference D-I], describes general procedures acceptable to the NRC staff for calculating the effects of neutron radiation embrittlement of the low-alloy steels currently used for light-water-cooled reactor vessels. Position C.2 of Regulatory Guide 1.99, Revision 2, describes the method for calculating the adjusted reference temperature and Charpy upper-shelf energy of reactor vessel beltline materials using surveillance capsule data. The methods of Position C.2 can only be applied when two or more credible surveillance data sets become available from the reactor in question.

To date there have been three surveillance capsules removed from the Calvert Cliffs Unit 2 reactor vessel. To use these surveillance data sets, they must be shown to be credible. In accordance with Regulatory Guide 1.99, Revision 2, the credibility of the surveillance data will be judged based on five criteria.

The purpose of this evaluation is to apply the credibility requirements of Regulatory Guide 1.99, Revision 2, to the Calvert Cliffs Unit 2 reactor vessel surveillance data and determine whether that surveillance data is credible.

D.2 EVALUATION Criterion 1: Materials in the capsules should be those judged most likely to be controlling with regardto radiationembrittlement.

The beltline region of the reactor vessel is defined in Appendix G to 10 CFR Part 50, "Fracture Toughness Requirements" [Reference D-2], as follows:

"the region of the reactor vessel (shell material including welds, heat affected zones, and plates orforgings) that directly surrounds the effective height of the active core and adjacent regions of the reactor vessel that are predicted to experience sufficient neutron radiation damage to be considered in the selection of the most limiting material with regard to radiationdamage. "

The Calvert Cliffs Unit 2 reactor vessel consists of the following beltline region materials:

• Intermediate Shell Plates D-8906-1, 2 and 3 (Heat # A-4463-1, B-9427-2 and A-4463-2)

" Lower Shell Plates D-8907-1, 2 and 3 (Heat # C-5804-1, C-5286-1, C-5803-3)

" Intermediate to Lower Shell Circumferential Weld Seam 9-203 (Heat # 10137)

" Intermediate Shell Longitudinal Weld Seams 2-203-A, B, C (Heat # A8746)

• Lower Shell Longitudinal Weld Seams 3-203-A, B, C (Heat # 33A277)

WCAP- 17501-NP February 2012 Revision 0

D-2 Westinghouse Non-Proprietary Class 3 Per the CRVSP, Revision 5 [Reference D-3] for Calvert Cliffs, ASTM E185-70 [Reference D-4]

recommended the surveillance program material be representative of the reactor vessel beltline materials.

ASTM E185-70 suggested using the plate with the highest TNDT, as determined by the drop-weight test, as the source for base metal and HAZ materials. Two of the Unit 2 plates (D-8906-2 and D-8907-2) had a TNDT of 10'F. Therefore, the surveillance plate was chosen based on a second selection criterion: the plate with the highest temperature at the 30 ft-lb CVN energy level. Based on this criterion, Lower Shell Plate D-8907-2 was selected.

The surveillance weld metal was selected as the same weld wire heat/flux type combination used in Intermediate to Lower Shell Circumferential Weld 9-203. The weld wire heat/flux type combination used for surveillance welds was 10137/0091 for Calvert Cliffs Unit 2. The selection of these weld materials was the general practice for Combustion Engineering surveillance programs because it was considered representative material. Additionally, the surveillance weld metal in the Calvert Cliffs Unit 2 surveillance program (Heat # 10137) had the second highest Cu Wt. % of all the reactor vessel beltline welds. Thus, it was chosen as the surveillance weld metal.

Hence, Criterion I is met for the Calvert Cliffs Unit 2 surveillance program.

Criterion 2: Scatter in the plots of Charpy energy versus temperature for the irradiated and unirradiatedconditions should be small enough to permit the determination of the 30 ft-lb temperature and upper-shelfenergy unambiguously.

Based on engineering judgment, the scatter in the data presented in these plots is small enough to permit the determination of the 30 ft-lb temperature and the upper-shelf energy of the Calvert Cliffs Unit 2 surveillance materials unambiguously. Hence, the Calvert Cliffs Unit 2 surveillance program meets this criterion.

Hence, Criterion 2 is met for the Calvert Cliffs Unit 2 surveillance program.

Criterion 3: When there are two or more sets of surveillance data from one reactor,the scatter of ARTNDT values about a best-fit line drawn as described in Regulatory Position 2.1 normally should be less than 28 0 F for welds and 170F for base metal. Even if the fluence range is large (two or more orders of magnitude), the scatter should not exceed twice those values. Even if the datafail this criterionfor use in shift calculations, they may be crediblefor determining decrease in upper-shelf energy if the upper shelf can be clearly determined,following the definition given in ASTM E185-82 [Reference D-5].

The functional form of the least-squares method as described in Regulatory Position 2.1 will be utilized to determine a best-fit line for this data and to determine if the scatter of these ARTNDT values about this line is less than 28°F for the weld and less than 17'F for the plate.

WCAP-1 7501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 D-3 Following is the calculation of the best-fit line as described in Regulatory Position 2.1 of Regulatory Guide 1.99, Revision 2. In addition, the recommended NRC methods for determining credibility will be followed. The NRC methods were presented to the industry at a meeting held by the NRC on February 12 and 13, 1998 [Reference D-6]. At this meeting the NRC presented five cases. Of the five cases, Case I ("Surveillance data available from plant but no other source") most closely represents the situation for the Calvert Cliffs Unit 2 surveillance material.

WCAP-17501-NP February 2012 Revision 0

D-4 Westinjahouse Non-Pror)rietarv Class 3 Following the NRC Case 1, the Calvert Cliffs Unit 2 surveillance plate and weld metal (Heat # 10137) will be evaluated using Calvert Cliffs Unit 2 data. This evaluation is contained in Table D-1.

Table D-1 Calculation of Interim Chemistry Factors for the Credibility Evaluation Using Calvert Cliffs Unit 2 Surveillance Capsule Data Material

- .:DT FF*ARTNDT

,*Materia.j CCapsule Cps9ue "FF b RNTC FF2

_" _ (xlO6 n/fcm 2,,E>;1.0 MeV) ':(F) (0F).___(OF)_:_

2630 0.825 0.946 86.4 81.74 0.895 Lower Shell Plate D-8907-2 97° 1.95 1.182 111.6 131.97 1.398 (Longitudinal) 104 0 2.44 1.240 135.6 168.16 1.538 Lower Shell Plate D-8907-2 97' 1.95 1.182 102.6 121.32 1.398 (Transverse) I I SUM: 503.19 5.229 CFD-8907 -2 = 1(FF

• ARTNDT) + Z(FF 2) = (503.19) + (5.229) - 96.2*F 2630 Calvert Cliffs_______________ 0.825 0.946 72.7 68.78 0.895 Unit 2 Weld Metal 970 1.95 1.182 82.9 98.03 1.398 (Heat 10137) 1040 2.44 1.240 69.7 86.44 1.538 SUM: 253.24 3.831 CFHeat # 10137 = 1(FF

• ARTNDT) - X(FF 2 ) = (253.24) - (3.831) = 66.1-F Notes:

(a) f= capsule fluence taken from Table 7-1 of this report.

(b) FF = fluence factor = (O.28-0.10*log f)

(c) ARTNDT values are the measured 30 ft-lb shift values taken from Section 5 of this report. The measured ARTNDT values for the surveillance weld metal do not include the adjustment ratio procedure of Reg. Guide 1.99, Revision 2, Position 2.1 since this calculation is based on the actual surveillance weld metal measured shift values. In addition, only Calvert Cliffs Unit 2 data is being considered; therefore, no temperature adjustment is required.

WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 D-5 The scatter of ARTNDT values about the functional form of a best-fit line drawn as described in Regulatory Position 2.1 is presented in Table D-2.

Table D-2 Best-Fit Evaluation for Calvert Cliffs Unit 2 Surveillance Materials CF CapsuleLMeasured Predicted SResidual <

~Material' Capsule. (SlOPeb,,,f-,) Fluence FF ART,,,(A ARTKN(b) ARITc (Base Metal)

Lower Shell Plate 2630 96.2 0.825 0.946 86.4 91.0 4.6 Yes D-8907-2 970 96.2 1.95 1.182 111.6 113.8 2.2 Yes (Longitudinal) 1040 96.2 2.44 1.240 135.6 119.3 16.3 Yes Lower Shell Plate D-8907-2 97* 96.2 1.95 1.182 102.6 113.8 11.2 Yes (Transverse)

Calvert Cliffs 263' 66.1 0.825 0.946 72.7 62.5 10.2 Yes Unit 2 Weld Metal 97' 66.1 1.95 1.182 82.9 78.2 4.7 Yes (Heat # 10137) 104 1 66.1 2.44 1.240 69.7 82.0 12.3 Yes Notes:

(a) Measured ARTNDT values are taken from Table D-1.

(b) Predicted ARTNDT = CFbS,.fit

• FF.

(c) Residual ARTNOT = Absolute Value [Predicted ARTNDT- Measured ARTrNT].

The scatter of ARTNDT values about the best-fit line, drawn as described in Regulatory Guide 1.99, Revision 2, Position 2.1, should be less than 17'F for base metal. Table D-2 indicates that all four surveillance data points fall within the +/- I of 17'F scatter band for surveillance base metals; therefore, the Lower Shell Plate D-8907-2 data is deemed "credible" per the third criterion.

The scatter of ARTNDT values about the best-fit line, drawn as described in Regulatory Guide 1.99, Revision 2, Position 2.1, should be less than 28°F for weld metal. Table D-2 indicates that all three surveillance data points fall within the +/- la of 28°F scatter band for surveillance weld materials; therefore, the weld material (Heat # 10137) is deemed "credible" per the third criterion.

Hence. Criterion 3 is met for the Calvert Cliffs Unit 2 surveillance olate and weld metal.

WCAP- 17501-NP February 2012 Revision 0

D-6 Westinghouse Non-Proprietarv Class 3 Criterion 4: The irradiationtemperature of the Charpy specimens in the capsule should match the vessel wall temperature at the cladding/basemetal interface within +/- 25°F The surveillance materials are contained in capsules positioned near the reactor vessel inside wall so that the irradiation conditions (fluence, flux spectrum, temperature) of the test specimens resemble, as closely as possible, the irradiation conditions of the reactor vessel. The capsules are bisected by the midplane of the core and are placed in capsule holders positioned circumferentially about the core at locations near the regions of maximum flux. The location of the specimens with respect to the reactor vessel beitline provides assurance that the reactor vessel wall and the specimens experience equivalent operating conditions such that the temperatures will not differ by more than 25°F.

Hence, Criterion 4 is met for the Calvert Cliffs Unit 2 surveillance program.

Criterion 5: The surveillance data for the correlation monitor material in the capsule should fall within the scatter band of the databasefor that material.

The Calvert Cliffs Unit 2 surveillance program does contain Standard Reference Material (SRM). The material was obtained from an A533 Grade B, Class 1 plate (HSST Plate 01). NUREG/CR-6413, ORNL/TM- 13133 [Reference D-7] contains a plot of residual vs. Fast Fluence for the SRM (Figure 11 in the report). This Figure shows a 2a uncertainty of 50'F. The data used for this plot is contained in Table 14 in the report. However, the NUREG Report does not consider the recalculated fluence and ARTNDT values for Capsule 2630, nor does it consider the surveillance data from Capsule 1040. Thus, Table D-3 contains an updated calculation of Residual vs. Fast fluence, considering the recalculated capsule fluence and ARTNDT values for Capsule 2630 and the surveillance data from Capsule 1040.

Table D-3 Calculation of Residual vs. Fast Fluence for Calvert Cliffs Unit 2 CGapsule ::'*

C.psule 1

• Capsi"le

"'::.*:f  : F :

• FF. Measured. . RG 1.99, Rev. 21 Residuallc),

__________" _~ (xl0" n/cm 2 , E >1.0 MeV) Shift(a, (F) Shiftb:, (TF) ('F) 2630 0.825 0.946 125.6 128.76 -3.2 1040 2.44 1.240 165.5 168.78 -3.3 Notes:

(a) Measured AT 30 values for the SRM were taken from Section 5 of this report.

(b) Per NUREG/CR-6413, ORNL/TM-13133, the Cu and Ni values for the SRM (HSST Plate 01) are 0.18 and 0.66, respectively. This equates to a chemistry factor value of 136.10F based on Regulatory Guide 1.99, Revision 2, Position 1.1. The calculated shift is thus equal to CF

• FF.

(c) Residual = Measured Shift - RG 1.99 Shift.

Table D-3 shows a 2y uncertainty of less than 50'F, which is the allowable scatter in NUREG/CR-6413, ORNL/TM-13133.

Hence, Criterion 5 is met for the Calvert Cliffs Unit 2 surveillance program.

WCAP- 17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 D-7 D.3 CONCLUSION Based on the preceding responses to all five criteria of Regulatory Guide 1.99, Revision 2, Section B, the Calvert Cliffs Unit 2 surveillance data for both the surveillance plate and weld specimens are deemed credible.

D.4 REFERENCES D-1 U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Regulatory Guide 1.99, Revision 2, Radiation Embrittlement of Reactor Vessel Materials, May 1988.

D-2 10 CFR 50, Appendix G, Fracture Toughness Requirements, Federal Register, Volume 60, No.

243, December 19, 1995.

D-3 Comprehensive Reactor Vessel Surveillance Program,Revision 5, W. A. Pavinich, July 2009.

D-4 ASTM El 85-70, Standard Recommended Practicefor Surveillance Tests for Nuclear Reactor Vessels, American Society for Testing and Materials, Philadelphia, PA, 1970.

D-5 ASTM E185-82, Annual Book of ASTM Standards, Section 12, Volume 12.02, StandardPractice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels.

D-6 K. Wichman, M. Mitchell, and A. Hiser, USNRC, Generic Letter 92-01 and RPV Integrity Assessment Workshop Handouts, NRC/Industry Workshop on RPV Integrity Issues, February 12, 1998.

D- 7 NUREG/CR-6413; ORNL/TM-13133, Analysis of the IrradiationData for A302B and A533B Correlation Monitor Materials, J. A. Wang, Oak Ridge National Laboratory, Oak Ridge, TN, April 1996, WCAP-17501 -NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 E-I APPENDIX E CALVERT CLIFFS UNIT 2 UPPER-SHELF ENERGY EVALUATION Per Regulatory Guide 1.99, Revision 2 [Reference E-I ], the Charpy upper-shelf energy (USE) is assumed to decrease as a function of fluence and copper content as indicated in Figure 2 of the Guide (Figure E-1 of this Appendix) when surveillance data is not used. Linear interpolation is permitted. In addition, if surveillance data is to be used, the decrease in upper-shelf energy may be obtained by plotting the reduced plant surveillance data on Figure 2 of the Guide (Figure E-I of this Appendix) and fitting the data with a line drawn parallel to the existing lines as the upper bound of all the data. This line should be used in preference to the existing graph.

The 32 EFPY (end-of-life) and 52 EFPY (end-of-life-extension) upper-shelf energy of the vessel materials can be predicted using the corresponding 1/4T fluence projection, the copper content of the beltline materials and/or the results of the capsules tested to date using Figure 2 in Regulatory Guide 1.99, Revision 2. The maximum vessel clad/base metal interface fluence value was used to determine the corresponding 1/4T fluence value at 32 and 52 EFPY.

The Calvert Cliffs Unit 2 reactor vessel beltline region minimum thickness is 8.625 inches. Calculation of the I/4T vessel surface fluence values at 32 and 52 EFPY for the beltline materials is shown as follows:

Maximum Vessel Fluence @ 32 EFPY - 2.87 x 1019 n/cm 2 (E > 1.0 MeV) 2 24 (8.625/4))

1/4T Fluence @ 32 EFPY (2.87 x 1019 n/cm )

• e(-' *

= 1.711 x 1019 n/cm 2 (E > 1.0 MeV) 2 Maximum Vessel Fluence @ 52 EFPY = 4.28 x 1019 n/cm (E > 1.0 MeV) 1/4T Fluence @ 52 EFPY = (4.28 x loll n/cm )

2

• e( 0 24 * (8,625/4))

2

= 2.551 X 1019 n/cm (E > 1.0 MeV)

The following pages present the Calvert Cliffs Unit 2 upper-shelf energy evaluation. Figure E-1, as indicated above, is used in making predictions in accordance with Regulatory Guide 1.99, Revision 2.

Table E-I provides the predicted upper-shelf energy values for 32 EFPY (end-of-life (EOL)). Table E-2 provides the predicted upper-shelf energy values for 52 EFPY (end-of-life-extension (EOLE)).

WCAP- 17501-NP February 2012 Revision 0

E-2 Westinghouse Non-Proprietary Class 3 100.0 (I) 0.

0 tm 10.0 (0

• Surveillance Material: LS Plate D-8907-2

• Surveillance Material: Weld Heat# 10137 1.0 I1 1.00E+I 7 1.OOE+18 1.OOE+19 1.OOE+20 Neutron Fluence, n/cm 2 (E > I MeV)

Figure E-1 Regulatory Guide 1.99, Revision 2 Predicted Decrease in Upper-Shelf Energy as a Function of Copper and Fluence WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 E-3 Table E-1 Predicted Positions 1.2 and 2.2 Upper-Shelf Energy Values at 32 EFPY

...  : T: 1T E Unirradiate'd Projected I Projected Materal PUSE IWeight Fluencet~ UateSel

%OfCu 9 (XI01 ii/CM2,j Decrease. EOL USE

_______________________ ______ E> .0MC) (ft-lb) (ftdb)Y, Position 1 .2 (b)

Intermediate Shell Plate D-8906-1 0.15 1.711 77 27 56.2 Intermediate Shell Plate D-8906-2 0.11 1.711 74 27 54.0 Intermediate Shell Plate D-8906-3 0.14 1.711 75 27 54.8 Lower Shell Plate D-8907-1 0.15 1.711 83 27 60.6 Lower Shell Plate D-8907-2 0.14 1.711 115 27 84.0 Lower Shell Plate D-8907-3 0.11 1.711 85 27 62.1 Intermediate Shell Long. Welds 0.16 1.711 84 345(c) 2-203-A, B, C Intermediate to Lower Shell 0.21 1.711 140 44 78.4 Circ. Weld 9-203 Lower Shell Long. Welds 3-203-A,323ABC0.24 B, C 1.711 160 44 89.6 Position 2 .2 (d)

Lower Shell Plate D-8907-2(e) 0.14 1.711 115 23 88.6 Intermediate to Lower Shell 0 1 Circ. Weld 9-203(P) 0.21 1.711 140 29 99.4 Notes:

(a) The fluence values listed pertain to the maximum vessel fluence value at 32 EFPY, though the longitudinal welds vary in location.

(b) Percent USE decrease values were calculated using Figure 2 of Regulatory Guide 1.99, and the fluence and Cu wt. % values for each material. The Cu wt. % values were conservatively rounded up to the next highest line for each plate and weld material, unless otherwise noted. The percent USE drop of the plates was calculated based on the 0.15 Cu wt. % base metal line. The percent USE drop of the Intermediate to Lower Shell Circ. Weld and the Lower Shell Long. Welds was calculated based on the 0.25 Cu wt. % weld line.

(c) The Intermediate Shell Long. Welds' projected USE value at EOL is close to the 10 CFR 50, Appendix G screening criteria.

Therefore, the percent USE decrease value that corresponded to the specific Cu wt. % (0.16) for this material was determined using interpolation between the existing weld lines on Figure 2 of Regulatory Guide 1.99, Revision 2.

(d) Calculated using surveillance capsule measured percent decrease in USE from Table 5-10 and Regulatory Guide 1.99, Revision 2, Position 2.2; see Figure E-1.

(e) The most limiting surveillance data point for Lower Shell Plate D-8907-2 is a measured decrease of 24% at a fluence of 1.95 x 1019 n/cm 2 pertaining to Capsule 970 (see Table 5-10). The most limiting surveillance data point for the Intermediate to Lower Shell Circumferential Weld 9-203 is a measured decrease of 30% at a fluence of 1.95 x 10'9 n/cm 2 pertaining to Capsule 970 (see Table 5-10).

WCAP-17501-NP February 2012 Revision 0

E-4 Westinahouse Non-Proorietarv Class 3 Table E-2 Predicted Positions 1.2 and 2.2 Upper-Shelf Energy Values at 52 EFPY

.... ... Unirradiated

.. Projected Projectd t ~ l.

.~~~~1

• l Material , ,,:i*.. .Weight .. Wei~kUSE - : 2..

Fluence(:) USE . . .EOLE "

%of Cu -(xlO 9 n/lcm 2, UE Decrease

_...._._.. s 1 . ..... (ft-!b):: ,* U SE (ftýlb)

Position 1 .2(b)

Intermediate Shell Plate D-8906-1 0.15 2.551 77 30 53.9 Intermediate Shell Plate D-8906-2 0.11 2.551 74 30 51.8 Intermediate Shell Plate D-8906-3 0.14 2.551 75 30 52.5 Lower Shell Plate D-8907-1 0.15 2.551 83 30 58.1 Lower Shell Plate D-8907-2 0.14 2.551 115 30 80.5 Lower Shell Plate D-8907-3 0.11 2.551 85 30 59.5 Intermediate Shell Long. Welds 0.16 2.551 84 37.5(C 52.5 2-203-A, B, C Intermediate to Lower Shell Circ._Weld_9-203 0.21 2.551 140 48 72.8 Lower Shell Longitudinal Welds 0.24 2.551 160 48 83.2 3-203-A, B, C I I I Position 2 .2(d)

Lower Shell Plate D-8907-2(e) 0.14 2.551 115 25.5 85.7 Intermediate to Lower Shell 0 Circ. Weld 9-203Pe) 0.21 2.551 140 32 95.2 Notes:

(a) The fluence values listed pertain to the maximum vessel fluence value at 52 EFPY, though the longitudinal welds vary in location.

(b) Percent USE decrease values were calculated using Figure 2 of Regulatory Guide 1.99, and the fluence and Cu wt. %

values for each material. The Cu wt. % values were conservatively rounded up to the next highest line for each plate and weld material, unless otherwise noted. The percent USE drop of the plates was calculated based on the 0.15 Cu wt. % base metal line. The percent USE drop of the Intermediate to Lower Shell Circ. Weld and the Lower Shell Long. Welds was calculated based on the 0.25 Cu wt. % weld line.

(c) The Intermediate Shell Long. Welds' projected USE value at EOLE is close to the 10 CFR 50, Appendix G screening criteria. Therefore, the percent USE decrease value that corresponded to the specific Cu wt. % (0.16) for this material was determined using interpolation between the existing weld lines on Figure 2 of Regulatory Guide 1.99, Revision 2.

(d) Calculated using surveillance capsule measured percent decrease in USE from Table 5-10 and Regulatory Guide 1.99, Revision 2, Position 2.2; see Figure E-1.

(e) The most limiting surveillance data point for Lower Shell Plate D-8907-2 is a measured decrease of 24% at a fluence of 1.95 x 1019 n/cm 2 pertaining to Capsule 970 (see Table 5-10). The most limiting surveillance data point for the 2

Intermediate to Lower Shell Circumferential Weld 9-203 is a measured decrease of 30% at a fluence of 1.95 x 1019 n/cm pertaining to Capsule 97' (see Table 5-10).

USE Conclusion All of the beltline materials in the Calvert Cliffs Unit 2 reactor vessel are projected to remain above the USE screening criterion value of 50 ft-lb (per 10 CFR 50, Appendix G) at 32 and 52 EFPY.

WCAP- 17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 E-5 E.1 REFERENCES E-1 U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Regulatory Guide 1.99, Revision 2, Radiation Embrittlement of Reactor Vessel Materials,May 1988.

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Westinghouse Non-Proprietary Class 3 F-I APPENDIX F CALVERT CLIFFS UNIT 2 PRESSURIZED THERMAL SHOCK EVALUATION A limiting condition on reactor vessel integrity known as Pressurized Thermal Shock (PTS) may occur during a severe system transient such as a loss-of-coolant accident (LOCA) or steam line break. Such transients may challenge the integrity of the reactor vessel under the following conditions: severe overcooling of the inside surface of the vessel wall followed by high repressurization; significant degradation of vessel material toughness caused by radiation embrittlement; and the presence of a critical-size defect anywhere within the vessel wall.

In 1985, the U.S. NRC issued a formal ruling (10 CFR 50.61) on PTS [Reference F-I] that established screening criteria on reactor vessel embrittlement, as measured by the maximum reference nil-ductility transition temperature in the limiting beltline component at the end-of-life, termed RTPTS. RTPTS screening values were set by the U.S. NRC for beltline axial welds, forgings or plates, and for beltline circumferential weld seams for plant operation to the end of plant license. All domestic PWR vessels have been required to evaluate vessel embrittlement in accordance with the criteria through the end-of-life. The U.S. NRC revised 10 CFR 50.61 in 1991 and 1995 to change the procedure for calculating radiation embrittlement. These revisions make the procedure for calculating the reference temperature for pressurized thermal shock (RTPTs) values consistent with the methods given in Regulatory Guide 1.99, Revision 2 [Reference F-2].

These accepted methods were used with the surface fluence of Section 6, the material properties (Initial RTNDT, Position 1.1 Chemistry Factor values) from the CRVSP, Revision 5 [Reference F-3], and the results of this report with regards to the Position 2.1 chemistry factor values (See Table F-2) and credibility evaluation to calculate the following RTPTS values for the Calvert Cliffs Unit 2 surveillance Capsule 104' materials at 32 EFPY (EOL) and 52 EFPY (EOLE).

Also, Calvert Cliffs Unit 2 has sister plant surveillance data from Calvert Cliffs Unit I and Farley Unit 1 for weld Heat # 33A277. Data from WCAP-17365-NP, Revision 0 [Reference F-4] was used to determine the Position 2.1 chemistry factor value for this material applicable to Calvert Cliffs Unit 2 (See Table F-3). Weld Heat # 33A277 has been deemed credible per WCAP-17365-NP, Revision 0.

The EOL and EOLE RTPTS calculations are summarized in Table F-4.

WCAP-17501-NP February 2012 Revision 0

F-2 Westinghouse Non-Proprietary Class 3 F.1 CALCULATION OF POSITION 2.1 CHEMISTRY FACTORS Ratio Procedure The Calvert Cliffs Unit 2 (CC-2) Position 1.1 surveillance program weld chemistry factor (96.87F) is identical to the vessel weld chemistry factor for the Intermediate to Lower Shell Circumferential Weld 9-203 (96.87F) per Reference F-3. Thus, in Table F-2, the ratio procedure of Regulatory Guide 1.99, Revision 2, Position 2.1 [Reference F-2] is not used for the CC-2 surveillance weld metal (Heat # 10137) because the ratio is equal to one.

Credible sister plant data for Weld Heat # 33A277 is available from the Calvert Cliffs Unit 1 (CC-1) and Farley Unit I (Far-1) surveillance programs.

The CC-1 Position 1.1 surveillance program weld chemistry factor (91.87F) is not identical to the Calvert Cliffs Unit 2 vessel weld chemistry factor for the Lower Shell Longitudinal Welds 3-203-A, B, C (1 17.8°F) per Reference F-3. Thus, the ratio procedure of Regulatory Guide 1.99, Revision 2, Position 2.1 [Reference F-2] is applied to the surveillance data from the Calvert Cliffs Unit I surveillance weld (see calculation below).

CFcc.I Surv Weld = 91.87F [Reference F-4]

CFcc.2 Betline Weld = 11 7.8°F [Reference F-4]

Ratio 117.8 91.8 Ratio = 1.28 The Far-1 Position 1.1 surveillance program weld chemistry factor (78.17F) is also not identical to the vessel weld chemistry factor for the Lower Shell Longitudinal Welds 3-203-A, B, C (117.8°F). Thus, the ratio procedure of Regulatory Guide 1.99, Revision 2, Position 2.1 is applied to the surveillance data from the Far-1 surveillance weld (see calculation below).

CFFar-I Surv. Weld = 78.1 °F [Reference F-4]

CFcc- 2 Beitline Weld = 11 7.87F [Reference F-4]

Ratio = 117.8 78.1 Ratio = 1.51 Therefore, in Table F-3, the measured ARTNDT values for weld Heat # 33A277 from the CC-1 surveillance program will be multiplied by the ratio of 1.28 and the measured ARTNDT values from the Far-I surveillance program will be multiplied by the ratio of 1.51.

WCAP- 17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 F-3 Temperature Adjustments Calvert Cliffs Unit 2 utilizes surveillance data from two sister plants (Calvert Cliffs Unit I and Farley Unit 1). Therefore, temperature adjustments are required. From NRC Industry Meetings on November 12, 1997 and February 12 and 13, 1998, procedural guidelines were presented to adjust the ARTNDT for temperature differences when using surveillance data from one reactor vessel applied to another reactor vessel. The following is taken from the handout [Reference F-5] given by the NRC at these industry meetings:

Studies have shown that for temperatures near 550°F, a 1 WF decrease in irradiation temperaturewill result in approximately a I °F increase in ARTN7)T.

Thus, for plants that use surveillance data from other reactor vessels that operate at different temperatures or when the capsule is at a different temperature than the plant, this difference must be considered.

The temperature adjustment is as follows:

Temp. Adjusted ARTNDT = ARTNDT, Measured + (Tcapsule - Tplant)

The CC-1 and Far-1 capsule irradiation temperatures (Tcapsuie) and measured ARTNDT values are taken from Reference F-4. The irradiation temperature of the CC-2 reactor vessel is 548'F (Tpl1 t). Table F-1 gives a summary of the temperature adjustments of the CC-I and Far-1 surveillance data that will be used in Table F-3 to calculate the Position 2.1 chemistry factor value for weld Heat # 33A277. A sample calculation of adjusted ARTNDT (for chemistry and temperature) for Far-I Capsule Y is shown below:

Temperature Adjustment Procedure Tcapsule = 5440 F Tplant = 548 0F ARTNDT, Measured = 66.9 0 F Temp. Adjusted ARTNDT = 66.9 0 F + (544 0 F - 548 0 F)

= 62.9 0 F Ratio Procedure Temp. Adjusted ARTNDT = 62.90 F Ratio = 1.51 Chemistry-Adjusted ARTNDT = 1.51

• 62.9 0 F

= 95.0 0 F The remaining Far-I and CC-1 measured ARTNDT values were adjusted in the same fashion and are shown in Table F-3 (unadjusted ARTNDT values are included in parentheses). No temperature adjustments were required for the CC-I data because the CC-I capsules were irradiated at the same temperature as CC-2.

February 2012 WCAP-1750 WCAP-17501-NP1-NP February 2012 Revision 0

F-4 Westinghouse Non-Proprietary Class 3 Table F-1 Calculation of the Temperature Adjustments for the Calvert Cliffs Unit 1 and Farley Unit 1 Surveillance Capsule Data Applicable to Calvert Cliffs Unit 2

'Calvert.Cliffs Mate ':,.:,>*::fria

!::,*:,* .. .. Inlet:.:,Temperature

,-u:  :,:during Unit 2 Inlet

*::,*, I:*::::,unitI2,Inlet::*: Temperature i ,*Tem perature : =:

MaeilCapsule Period of IrradialtionAdutet(F TemperatureAedjustment(-F)-

2630 548.00 0.00 Weld Metal Heat # 33A277 970 548.00 0.00 (Calvert Cliffs Unit 1 data) 2840 548.00 0.00 y 544.00 -4.00 U 540.25 548 -7.75 Weld Metal Heat # 33A277 X 540.86 -7.14 (Farley Unit 1 data) W 541.75 -6.25 V 541.72 -6.28 z 541.43 -6.57 WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 F-5 Table F-2 Calculation of Chemistry Factors for Calvert Cliffs Unit 2 using CC-2 Surveillance Capsule Data Capsule Fluence ) ARaT Material Capsule' '( 101 FFt ~, ATD~~~FA D FF2

.(x1O i/em',  ;:. ( O..(F) (OF) . A Lower Shell 263* 0.825 0.946 86.4 81.74 0.895 Plate 1.95 1.182 111.6 131.97 1.398 D-8907-2 97' (Longitudinal) 104' 2.44 1.240 135.6 168.16 1.538 Lower Shell Plate 97* 1.95 1.182 102.6 121.32 1.398 D-8907-2 (Transverse)

SUM: 503.19 5.229 CFD-8907- 2 = YX(FF

• ARTNDT) + I(FF2 ) = (503.19) + (5.229) = 96.20 F CC-2 263' 0.825 0.946 72.7 68.78 0.895 Surveillance 970 1.95 1.182 82.9 98.03 1.398 Program Weld (Heat # 10137) 1040 2.44 1.240 69.7 86.44 1.538 SUM: 253.24 3.831 CF Heat 10137 = Z(FF

• ARTNDT) + Z(FF 2) = (253.24) + (3.831) = 66.1-F Notes:

(a) The Calvert Cliffs Unit 2 calculated capsule fluence values are taken from Table 7-1 of this report.

(b) FF = fluence factor = fo28-o.*o*1og(O).

(c) ARTNDT values are the measured 30 ft-lb shift values taken from Section 5 of this report for Calvert Cliffs Unit 2. No temperature or ratio adjustments were applied to the Calvert Cliffs Unit 2 surveillance data because the capsules were irradiated at the same temperature as the plant and the ratio was equal to one, respectively.

WCAP- 17501-NP February 2012 Revision 0

F-6 Westinghouse Non-Proprietary Class 3 Table F-3 Calculation of Chemistry Factors for Calvert Cliffs Unit 2 using CC-i and Far-i Sister Plant Surveillance Capsule Data Cajpsule' Material 2 Capsule FX109ue Cnce'a FFb RTTFFFA T IFF

" .O (x i1 n/cm 2 , (OF) (0F)

______ ~~

E>1.OMeV') _ _ _ _ __ _ _ _ _

CC-I 2630 0.505 0.809 64.5 (50.4) 52.21 0.655 Surveillance Program ce 970 1.94 1.181 133.8 (104.5) 157.99 Program Weld 1.395 (Heat # 33A277) 284° 2.33 1.228 99.8 (78.0) 122.65 1.509 Y 0.612 0.862 95.0 (66.9) 81.92 0.744 Far-i U 1.73 1.151 101.7 (75.1) 117.03 1.324 Surveillance X 3.06 1.295 121.2 (87.4) 156.99 1.678 Program Weld W 4.75 1.392 139.0 (98.3) 193.50 1.938 (Heat # 33A277) V 7.14 1.466 167.9 (117.5) 246.22 2.149 Z 8.47 1.492 161.5 (113.5) 240.87 2.225 SUM: 1369.38 13.618 CFHeat# 33A2 77 XY(FF

• ARTNoT) + X(FF) =(1369.38)-+ (13.618)= 100.6*F Notes:

(a) The Calvert Cliffs Unit I and Farley Unit I calculated capsule fluence values are taken from Reference F-4.

(b) FF = fluence factor = f0o28-o.1o*logff).

(c) The Calvert Cliffs Unit 1 and Farley Unit I ARTNDT values are the measured 30 ft-lb shift values and were taken from Reference F-4. The Farley Unit I ARTNDT values for the surveillance weld data are adjusted first by the difference in operating temperature. Then, both the Calvert Cliffs Unit I and Farley Unit I values are further adjusted using the ratio procedure to account for differences in the surveillance weld chemistry and the beltline weld chemistry (pre-adjusted values are listed in parentheses). The temperature adjustments and ratios applied are as follows:

Calvert Cliffs Unit 1 - Ratio = 1.28, Temperature adjustments per Table F-I (adjustments are equal to zero)

Farley Unit I - Ratio = 1.51, Temperature adjustments per Table F-I (on a capsule-by-capsule basis)

WCAP-17501-NP February 2012 Revision 0

Westinghouse Non-Proprieta Class 3 F-7 F.2 RTPTS CALCULATIONS Table F-4 RTPTS Calculations for the Calvert Cliffs Unit 2 Surveillance Capsule Materials at 32 and 52 EFPY SR.G. 1.99, C*a). Fluence~b) IRTrnT()' ARTNDT "tit I ( Mri RTPTS Reactor Vessel Material Rev. 2 .-

Position __

'(OF)-:

I (ficm2,E.>.1.0 2

(nlcm ,E .0MeV).

MeV j

, FF

()

(

i]. . O)*:(017) 0 (F("( ' in .- (

32 EFPY 1.1 101.5 2.870 x 10'9 1.2801 20 129.9 0 17 34.0 184 Lower Shell Plate D-8907-2 9

2.1 96.2 2.870 x 10" 1.2801 20 123.1 0 8 .5(d) 17.0 160 Intermediate Shell to Lower Shell 1.1 96.8 2.870 x 10'9 1.2801 -60 123.9 0 28 56.0 120 Circ. Weld 9-203 2.1 66.1 2.870 x 10'9 1.2801 -60 84.6 0 14 (d) 28.0 53 Lower Shell Longitudinal Weld 3-203- 1.1 117.8 2.870 x 10'9 1.2801 -80 150.8 0 28 56.0 127 9

A, B, C 2.1 100.6 2.870 x 10' 1.2801 -80 128.8 0 14 (d) 28.0 77 52 EFPY 1.1 101.5 4.280 x 10'9 1.3707 20 139.1 0 17 34.0 193 Lower Shell Plate D-8907-2 2.1 96.2 4.280 x 10'9 1.3707 20 131.9 0 8 .5(d) 17.0 169 9

Intermediate Shell to Lower Shell 1.1 96.8 4.280 X 101 1.3707 -60 132.7 0 28 56.0 129 Circ. Weld 9-203 2.1 66.1 4.280 x 10'9 1.3707 -60 90.6 0 14 (d) 28.0 59 Lower Shell Longitudinal Welds 1.1 117.8 4.280 x 1019 1.3707 -80 161.5 0 28 56.0 137 3-203-A, B, C 2.1 100.6 4.280 x 10'9 1.3707 -80 137.9 0 14 (d) 28.0 86 Notes:

(a) Position 1.1 Chemistry Factor values were calculated per Reference F- I and Position 2.1 Chemistry Factor values taken from Tables F-2 and F-3.

(b) Maximum end-of-life and end-of-life-extension fluence values taken from Table 6-2 of this report.

(c) Initial RTNDT values are measured and are taken from Reference F-3.

(d) A reduced 0 a term is used since the surveillance data is deemed credible per Appendix D and Reference F-4.

WCAP-17501-NP February 2012 Revision 0

F-8 Westinghouse Non-Proprietary Class 3 PTS Conclusion All of the surveillance Capsule 104 0 materials for Calvert Cliffs Unit 2 are projected to remain below the PTS screening criterion value of 270'F for plates and longitudinal welds and 300'F for circumferential welds (per 10 CFR 50.61) at 32 and 52 EFPY.

F.3 REFERENCES F-1 10 CFR 50.61, Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events, Federal Register, Volume 60, No. 243, dated December 19, 1995, effective January 18, 1996.

F-2 U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Regulatory Guide 1.99, Revision 2, RadiationEmbrittlement of Reactor Vessel Materials, May 1988.

F-3 Comprehensive Reactor Vessel Surveillance Program,Revision 5, W. A. Pavinich, July 2009.

F-4 WCAP- 17365-NP, Revision 0, Analysis of Capsule 2840 from the Calvert Cliffs Unit No. I Reactor Vessel Radiation Surveillance Program,E. J. Long and J. I. Duo, March 2011.

F-5 K. Wichman, M. Mitchell, and A. Hiser, USNRC, Generic Letter 92-01 and RPV Integrity Assessment Workshop Handouts, NRC/Industry Workshop on RPV Integrity Issues, February 12, 1998.

WCAP- 17501-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 G-1 APPENDIX G CALVERT CLIFFS UNIT 2 PRESSURE-TEMPERATURE LIMIT CURVE APPLICABILITY CHECK G.1 CALCULATION OF ART VALUES FOR CAPSULE MATERIALS The adjusted reference temperature (ART) values are calculated for Calvert Cliffs Unit 2 at 52 EFPY for each reactor vessel surveillance capsule material (Lower Shell Plate D-8907-2, Intermediate to Lower Shell Circ. Weld 9-203 and Lower Shell Axial Welds 3-203-A, B, C) at the 1/4T and 3/4T locations.

These values, along with these materials' initial properties, are used to perform an applicability check on the current heatup and cooldown pressure-temperature (P-T) limit curves. The ART values are calculated per Regulatory Guide 1.99, Revision 2, Positions 1.1 and 2.1 [Reference G-1]. The initial properties for the Capsule 104' materials are documented in the CRVSP, Revision 5 [Reference G-2].

The Calvert Cliffs Unit 2 (CC-2) Lower Shell Plate D-8907-2 surveillance data has been deemed credible per Appendix D of this report. Therefore, when using the Lower Shell Plate D-8907-2 surveillance data, a reduced 0 Avalue can be used. The CC-2 Intermediate Shell to Lower Shell Circ. Weld 9-203 surveillance data has been deemed credible per Appendix D of this report. Therefore, when using the Intermediate to Lower Shell Circ. Weld 9-203 surveillance data, a reduced oA value can be used. Finally, the CC-1 and Far-I surveillance weld data (Heat # 33A277), which is applicable to the CC-2 Lower Shell Axial Welds 3-203-A, B, C, has been deemed credible per WCAP-17365-NP, Revision 0 [Reference G-3]. Therefore, when using the Lower Shell Longitudinal Welds 3-203-A, B, C surveillance data, a reduced oa value can be used.

The Calvert Cliffs Unit 2 reactor vessel beltline region minimum thickness is 8.625 inches. Calculation of the 1/4T and 3/4T vessel fluence values at 52 EFPY for the beltline materials is shown as follows:

Maximum Vessel Fluence @ 52 EFPY = 4.28 x 1019 n/cm 2 (E > 1.0 MeV) 1/4T Fluence @ 52 EFPY = (4.28 x 10 9 n/cm 2)

• e(424 *(8,625/4))

= 2.551 x 10' 9 n/cm2 (E > 1.0 MeV)

Maximum Vessel Fluence @ 52 EFPY = 4.28 x 1019 n/cm 2 (E > 1.0 MeV) 3/4T Fluence @ 52 EFPY = (4.28 x 101 9

n/cm 2)

• e(424* (3.625/4))

= 0.906 x 1019 n/cm 2 (E > 1.0 MeV)

Tables G-1 and G-2 contain the calculations for 1/4T and 3/4T ART values for the CC-2 reactor vessel surveillance Capsule 1040 materials, as well as for the CC-I and Far-I surveillance materials that apply to the CC-2 reactor vessel.

WCAP-17501-NP February 2012 Revision 0

G-2 Westinghouse Non-Proprieta Class 3 Table G-1 Calculation of the Calvert Cliffs Unit 2 Reactor Vessel Surveillance Capsule Material ART Values at the 1/4T Location for 52 EFPY CO 1"/4TFluence IRTIT (b) ARTNDT 1(b) G. Margin ART 0 0 0 Reactor Vessel Material Rev. 2 M 1. MeV FF (F ) (F ) (F '

Position>___________

1.1 101.5 2.551 x 10' 9 1.2512 20 127.0 0 17 34.0 181 Lower Shell Plate D-8907-2 2.1 96.2 2.551 x 10'9 1.2512 20 120.4 0 8.5(c) 17.0 157 Intermediate Shell to Lower Shell 1.1 96.8 2.551 X 10"9 1.2512 -60 121.1 0 28 56.0 117 Circ. Weld 9-203 2.1 66.1 2.551 x 1019 4.2512 -60 82.7 0 14(c) 28.0 51 Lower Shell Longitudinal Weld 3-203- 1.1 117.8 2.551 x I019 1.2512 -80 147.4 0 28 56.0 123 A, B, C 2.1 100.6 2.551 x 10'9 1.2512 -80 125.9 0 14'c) 28.0 74 Notes:

(a) Position 1.1Chemistry Factor values were calculated per Reference G-I and Position 2.1 Chemistry Factor values taken from Appendix F.

(b) Initial RT, Dvalues are measured and are taken from Reference G-2.

(c) A reduced aj term is used since the surveillance data is deemed credible per Appendix D and Reference G-3.

February 2012 WCAP-1750 WCAP- 1-NP 17501I-NP February 2012 Revision 0

Westinghouse Non-Proprietary Class 3 G-3 Table G-2 Calculation of the Calvert Cliffs Unit 2 Reactor Vessel Surveillance Capsule Material ART Values at the 3/4T Location for 52 EFPY R.G. 1.99,(b()

Reactor Vessel Materl Rev. 2 314T PCF*a) EFlucace F. AR* AR)T 2I)E1> 1"Margin IRTNaT 0 F) T (OF) IL0 MeV) ((O(n/cm (OF) (OF) (OF). (OF) ('F) 1.1 101.5 0.906 x 1019 0.9724 20 98.7 0 17 34.0 153 Lower Shell Plate D-8907-2 2.1 96.2 0.906 x 10'9 0.9724 20 93.5 0 8.5(c) 17.0 131 Intermediate Shell to Lower Shell 1.1 96.8 0.906 x 10'9 0.9724 -60 94.1 0 28 56.0 90 Circ. Weld 9-203 2.1 66.1 0.906 x 10' 9 0.9724 -60 64.3 0 14(c) 28.0 32 Lower Shell Longitudinal Weld 3-203- 1.1 117.8 0.906 X 1019 0.9724 -80 114.5 0 28 56.0 91 A, B, C 2.1 100.6 0.906 x 1019 0.9724 -80 97.8 0 14(c) 28.0 46 Notes:

(a) Position 1.1 Chemistry Factor values were calculated per Reference G-I and Position 2.1 Chemistry Factor values taken from Appendix F.

(b) Initial RTNDT values are measured and are taken from Reference G-2.

(c) A reduced aA term is used since the surveillance data is deemed credible per Appendix D and Reference G-3.

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G-4 Westinghouse Non-Proprietary Class 3 G.2 P-T LIMIT CURVE APPLICABILITY The current P-T limit curves for CC-2 are based on Intermediate Shell Plate D-8906-1 [Reference G-2].

It must be ensured that the current surveillance capsule results from Capsule 104%, and the updated surveillance capsule results for weld Heat # 33A277, do not invalidate the current P-T limit curves for Calvert Cliffs Unit 2. Table G-3 compares Capsule 1040 materials' initial properties to the Intermediate Shell Plate D-8906-1 material properties. Reference G-2 confirms that all CC-2 reactor vessel beltline materials use the same fluence value. It can be determined from the properties in Table G-3 that plate D-8906-1 has more limiting material properties than the Capsule 1040 materials and weld Heat # 33A277 at any fluence, as long as the fluence on each material is the same.

Table G-3 Comparison of CC-2 Surveillance Capsule Materials Initial Properties to Intermediate Shell Plate D-8906-1 for P-T Limit Curve Development Reactor Vessel Material>

Material Intermediate-Shell to. Lower Shell Lower Shell Intermediate Shell Platerty Plate D-8907-21 D .. .' Shell' Circ.

807i() Lower *' * ..... **:

Longitudinal " Weld a:  ::Plate D4906-4~b

_____ _ ,______ _____,__Wed_9 , _03_

_ ... 3-203-A,_B,_C( _

Initial RTNDTQ(F) 20 -60 -80 10 Margin (°F) 17.0 28.0 28.0 34 Chemistry Factor 96.2 66.1 100.6 108

(*F)

Notes:

(a) Values are summarized in Tables G-I and G-2 of this report.

(b) Values taken from CRVSP, Revision 5 [Reference G-2].

Furthermore, the fluence value used in the current P-T limit curve analysis of record [Reference G-4] is 4.00 x 1019 n/cm2 (E > 1.0 MeV). The applicability term (EFPY) corresponding to 4.00 x 1019n/cm 2 (E >

1.0 MeV), was taken directly from Table 6-2 and is equal to 48 EFPY. Therefore, the current P-T limit curves are valid to 48 EFPY.

P-T Limit Curve Annlicabilitv Conclusion It is concluded that Intermediate Shell Plate D-8906-1 will continue to be more limiting for use in the development of the P-T limit curves. The surveillance Capsule 1040 analysis does not invalidate the current P-T limit curves. Additionally, based on the comparison of the fluence value used in the analysis of record for Calvert Cliffs Unit 2 and the peak fluence values from Table 6-2, the P-T limit curves for CC-2 are predicted to remain applicable to 48 EFPY.

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Westinghouse Non-Proprietary Class 3 G-5 G.3 REFERENCES G-1 U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Regulatory Guide 1.99, Revision 2, RadiationEmbrittlement of Reactor Vessel Materials, May 1988.

G-2 Comprehensive Reactor Vessel Surveillance Program,Revision 5, W. A. Pavinich, July 2009.

G-3 WCAP-17365-NP, Revision 0, Analysis of Capsule 284' from the Calvert Cliffs Unit No. 1 Reactor Vessel RadiationSurveillance Program,E. J. Long and J. I. Duo, March 2011.

G-4 Constellation Energy Group, LLC, Letter to US NRC, Calvert Cliffs Nuclear Power Plant Unit Nos. I & 2; Docket Nos. 50-317 & 50-318, License Amendment Request: Revision to Technical Specification P-T Curves, Peter E. Katz, May 28, 2003.

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