Text

Transmittal of Reactor Vessel Surveillance Capsule Report
	ML110910250
Person / Time
Site:	Calvert Cliffs
Issue date:	03/29/2011
From:	John Stanley, Long E, Duo J; Constellation Energy Nuclear Group, Calvert Cliffs 3 Nuclear Project, EDF Group
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
References
	WCAP-17365-NP
	Download: ML110910250 (284)
	v • d • e

Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, Maryland 20657 CENG a joint venture of O Constellation --zef CALVERT CLIFFS NUCLEAR POWER PLANT March 29, 2011 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit No. 1; Docket No. 50-317 Transmittal of Unit 1 Reactor Vessel Surveillance Capsule Report In accordance with 10 CFR Part 50, Appendix H IV.A, Calvert Cliffs hereby submits Westinghouse Report WCAP-17365-NP, "Analysis of Capsule 2840 from the Calvert Cliffs Unit No. 1 Reactor Vessel Radiation Surveillance Program," Revision 0 (Attachment 1). This report presents the analysis of the test results from the Unit 1 2840 capsule. The 2840 capsule test results were used to evaluate reactor vessel material properties following 26.17 effective full power years of plant operation. Based on this analysis, properties of the reactor beltline materials are predicted to remain more than adequate for the continued safe operation of Unit 1 through the end of the renewed license period. There are no changes to the pressure temperature limits associated with the Technical Specifications or to the operating procedures required to meet the limits in this report.

Should you have questions regarding this matter, please contact Mr. Douglas E. Lauver at (410) 495-5219.

Mlana r-Engineering Services JJS/PSF/bjd

Attachment:

(1) WCAP-17365-NP, Analysis of Capsule 2840 from the Calvert Cliffs Unit No. I Reactor Vessel Radiation Surveillance Program 4AJLA

Document Control Desk March 29, 2011 Page 2 cc: (Without Attachment)

D. V. Pickett, NRC Resident Inspector, NRC W. M. Dean, NRC S. Gray, DNR

ATTACHMENT (1)

WCAP-17365-NP, ANALYSIS OF CAPSULE 2840 FROM THE CALVERT CLIFFS UNIT NO. 1 REACTOR VESSEL RADIATION SURVEILLANCE PROGRAM Calvert Cliffs Nuclear Power Plant, LLC March 29, 2011

Westinghouse Non-Proprietary Class 3 WCAP-17365-NP March 2011 Revision 0 Analysis of Capsule 2840 from the Calvert Cliffs Unit No. 1 Reactor Vessel Radiation Surveillance Program Westinghouse

WESTINGHOUSE NON-PROPRIETARY CLASS 3 WCAP-17365-NP Revision 0 Analysis of Capsule 2840 from the Calvert Cliffs Unit No. 1 Reactor Vessel Radiation Surveillance Program E. J. Long*

J. I. Duo*

March 2011 Reviewer: B. A. Rosier*

Aging Management and License Renewal Services Reviewer: J. Chen*

Radiation Engineering and Analysis Acting Manager: A. E. Lloyd*

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

Westinghouse Non-Proprietary Class 3 iii TABLE OF CONTENTS L IST O F TA B L E S ........................................................................................................................................ v L IST O F FIG U R E S ................................................................................................................................... viii EX ECU T IVE SU M MA RY .......................................................................................................................... xi I SU M M A RY O F RESU LTS ......................................................................................................... 1-1 2 IN TR O DU C T ION ......................................................................................................................... 2-1 3 B A C K GR O U N D .......................................................................................................................... 3-1 4 DESCRIPTION OF PROGRAM .................................................................................................. 4-1 5 TESTING OF SPECIMENS FROM CAPSULE 2840 ............................................................. 5-1 5.1 O VE RV IE W .................................................................................................................... 5-1 5.2 CHARPY V-NOTCH IMPACT TEST RESULTS ........................................................... 5-3 5.3 TENSILE TEST RESULTS ............................................................................................. 5-5 6 RADIATION ANALYSIS AND NEUTRON DOSIMETRY ................................................... 6-1 6.1 IN TR OD U C TIO N ........................................................................................................... 6-1 6.2 DISCRETE ORDINATES ANALYSIS ........................................................................... 6-2 6.3 NEUTRON DOSIMETRY .............................................................................................. 6-4 6.4 CALCULATIONAL UNCERTAINTIES ........................................................................ 6-5 7 SURVEILLANCE CAPSULE REMOVAL SCHEDULE ....................................................... 7-1 8 RE FER E N C E S ............................................................................................................................. 8-1 APPENDIX A VALIDATION OF THE RADIATION TRANSPORT MODELS BASED ON NEUTRON DOSIMETRY MEASUREMENTS ............................................................................. A- 1 APPENDIX B LOAD-TIME RECORDS FOR CHARPY SPECIMEN TESTS ................................ B-I APPENDIX C CHARPY V-NOTCH PLOTS FOR EACH CAPSULE USING SYMMETRIC HYPERBOLIC TANGENT CURVE-FITTING METHOD ...................................... C-1 APPENDIX D CALVERT CLIFFS UNIT I SURVEILLANCE PROGRAM CREDIBILITY EVA LU AT ION ............................................................................................................... D -1 APPENDIX E CALVERT CLIFFS UNIT 1 UPPER-SHELF ENERGY EVALUATION ................. E-I APPENDIX F CALVERT CLIFFS UNIT I PRESSURIZED THERMAL SHOCK EVALUATION .... F-I APPENDIX G CALVERT CLIFFS UNIT 1 PRESSURE-TEMPERATURE LIMIT CURVE APPLICABILITY CHECK ....................................................................................... G-1 WCAP- 17365-NP March 2011 Revision 0

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

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

Low er Shell Plates (U nirradiated) ................................................................................... 4-4 Table 4-3 Chemical Composition (wt %) of the Calvert Cliffs Unit 1 Surveillance Test Materials -

Weld and HA Z (U nirradiated) ......................................................................................... 4-5 Table 4-4 Heat Treatment History of the Calvert Cliffs Unit 1 Surveillance Test Materials ........... 4-6 Table 4-5 Arrangement of Encapsulated Test Specimens within Calvert Cliffs Unit 1 Capsule 2840

......................................................................................................................................... 4 -7 Table 5-1 Charpy V-notch Data for the Calvert Cliffs Unit I Intermediate Shell Plate D-7206-3 Irradiated to a Fluence of 2.33 x 1019 n/cm 2 (E > 1.0 MeV) (Longitudinal Orientation) 5-6 Table 5-2 Charpy V-notch Data for the Calvert Cliffs Unit 1 Intermediate Shell Plate D-7206-3 Irradiated to a Fluence of 2.33 x 1019 n/cm 2 (E > 1.0 MeV) (Transverse Orientation) .... 5-7 Table 5-3 Charpy V-notch Data for the Calvert Cliffs Unit 1 Surveillance Weld Metal (Heat # 33A277) Irradiated to a Fluence of 2.33 x 1019 n/cm 2 (E > 1.0 MeV) ................ 5-8 Table 5-4 Charpy V-notch Data for the Calvert Cliffs Unit I Heat-Affected-Zone (HAZ) Material Irradiated to a Fluence of 2.33 x 1019 n/cm 2 (E > 1.0 MeV) ............................................ 5-9 Table 5-5 Instrumented Charpy Impact Test Results for the Calvert Cliffs Unit I Intermediate Shell Plate D-7206-3 Irradiated to a Fluence of 2.33x l019 n/cm 2 (E > 1.0 MeV)

(Longitudinal O rientation) ............................................................................................. 5-10 Table 5-6 Instrumented Charpy Impact Test Results for the Calvert Cliffs Unit 1 Intermediate Shell Plate D-7206-3 Irradiated to a Fluence of 2.33 x 1019 n/cm 2 (E > 1.0 MeV)

(Transverse O rientation) ................................................................................................ 5-11 Table 5-7 Instrumented Charpy Impact Test Results for the Calvert Cliffs Unit 1 Surveillance Weld Metal (Heat # 33A277) Irradiated to a Fluence of 2.33 x 10' 9 n/cm2 (E > 1.0 MeV) .... 5-12 Table 5-8 Instrumented Charpy Impact Test Results for the Calvert Cliffs Unit 1 Heat-Affected-Zone (HAZ) Material Irradiated to a Fluence of 2.33 x 1019 n/cm 2 (E > 1.0 MeV) ...... 5-13 Table 5-9 Effect of Irradiation to 2.33 x 1019 n/cm 2 (E > 1.0 MeV) on the Charpy V-Notch Toughness Properties of the Calvert Cliffs Unit 1 Reactor Vessel Surveillance Capsule 284' M aterials ................................................................................................................ 5-14 Table 5-10 Comparison of the Calvert Cliffs Unit 1 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 I Capsule 2840 Reactor Vessel Surveillance Materials Irradiated to 2.33 x 1019 n/cm 2 (E > 1.0 MeV) .............................................. 5-16 WCAP-17365-NP March 2011 Revision 0

vi Westinghouse Non-Proprietary Class 3 Table 6-1 Calculated Neutron Exposure Rates and Integrated Exposures at the Surveillance C apsule C enter(a) .............................................................................................................. 6-7 Table 6-2 Calculated Azimuthal Variation of Maximum Exposure Rates and Integrated Exposures at the Reactor Vessel Clad/Base M etal Interface ............................................................... 6-11 Table 6-3 Calculated Fast Neutron Exposure of Surveillance Capsules Withdrawn from Calvert C liffs Unit 1 ................................................................................................................... 6-15 Table 6-4 Calculated Surveillance Capsule Lead Factors .............................................................. 6-16 Table 7-1 Surveillance Capsule Withdrawal Schedule .................................................................... 7-1 Table 7-2 Supplemental Surveillance Capsule Withdrawal Schedule ............................................. 7-2 Table A-I Nuclear Parameters Used in the Evaluation of Neutron Sensors ............................. A-10 Table A-2 Monthly Thermal Generation During the First Nineteen Fuel Cycles of the Calvert Cliffs Unit 1 Reactor (Reactor Power of 2560 MWt from 12/27/1974 to 9/8/1977; 2700 MWt from 9/9/1977 to 4/30/2010; and, 2737 MWt from 5/1/2010 to present)

...................................................................................................................................... A -11 Table A-3 Surveillance Capsule Flux for Cj Factors Calculation ................................................... A-16 Table A-4a Measured Sensor Activities and Reaction Rates for Surveillance Capsule 2630 .......... A-18 Table A-4b Measured Sensor Activities and Reaction Rates for Surveillance Capsule 970 ............ A-19 Table A-4c Measured Sensor Activities and Reaction Rates for Surveillance Capsule 2840 .......... A-20 Table A-5 Comparison of Measured, Calculated, and Best-Estimate Reaction Rates at the Surveillance C apsule C enter ......................................................................................... A-21 Table A-6 Comparison of Calculated and Best-Estimate Exposure Rates at the Surveillance C apsule C enter ........................................................................................ A -22 Table A-7 Comparison of Measured/Calculated (MIC) Sensor Reaction Rate Ratios for Fast Neutron Threshold Reactions ..................................................................................................... A-23 Table A-8 Comparison of Best-Estimate/Calculated (BE/C) Exposure Rate Ratios ..................... A-23 Table C-I Upper-Shelf Energy Values (ft-lb) Fixed in CVGRAPH ......................................... C-i Table D- 1 Calculation of Interim Chemistry Factors for the Credibility Evaluation Using Calvert Cliffs Unit 1 Surveillance Capsule Data Only ................................................................ D-4 Table D-2 Best-Fit Evaluation for Calvert Cliffs Unit 1 Surveillance Materials Only .................... D-5 Table D-3 Mean Chemical Composition and Operating Temperature for Calvert Cliffs Unit 1 and Farley U nit 1 ............................................................................................................ D-6 Table D-4 Operating Temperature Adjustments for the Calvert Cliffs Unit 1 and Farley Unit I Surveillance C apsule D ata .............................................................................................. D-7 Table D-5 Calculation of Weld Heat # 33A277 Interim Chemistry Factor for the Credibility Evaluation Using Farley Unit I and Calvert Cliffs Unit 1 Surveillance Capsule Data .. D-8 WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 vii Table D-6 Best-Fit Evaluation for Surveillance Weld Metal Heat # 33A277 Using Calvert Cliffs U nit I and Farley Unit I Data ......................................................................................... D -9 Table D-7 Calculation of Residual vs. Fast Fluence for Calvert Cliffs Unit I .............................. D-10 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 48 EFPY ................... E-4 Table F-I Calculation of the Temperature Adjustments for the Farley Unit I Surveillance Capsule Data Applicable to Calvert Cliffs Unit I ............................................................ F-4 Table F-2 Calculation of Chemistry Factors for Calvert Cliffs Unit 1 Using Surveillance Capsule Data .................................................................................................................................. F -5 Table F-3 RTPTS Calculations for the Calvert Cliffs Unit 1 Surveillance Capsule 2840 Materials at 32 and 48 EFPY ............................................................................................................... F-6 Table G-1 Calculation of the Calvert Cliffs Unit 1 Reactor Vessel Surveillance Capsule Material ART Values at the 1/4T Location for 48 EFPY .............................................................. G-2 Table G-2 Calculation of the Calvert Cliffs Unit 1 Reactor Vessel Surveillance Capsule Material ART Values at the 3/4T Location for 48 EFPY .............................................................. G-3 Table G-3 Comparison of CC-I Surveillance Capsule 2840 Materials Initial Properties to Lower Shell Long. Welds 3-203-A, B, C for P-T Limit Curve Development ............................ G-4 WCAP- 17365-NP March 2011 Revision 0

viii Westinghouse Non-Proprietary Class 3 LIST OF FIGURES Figure 4-1 Arrangement of Surveillance Capsules in the Calvert Cliffs Unit I Reactor Vessel ....... 4-8 Figure 4-2 Original Surveillance Program Capsule in the Calvert Cliffs Unit I Reactor Vessel ...... 4-9 Figure 4-3 Surveillance Capsule Charpy Impact Specimen Compartment Assembly in the Calvert C liffs Unit 1 R eactor Vessel ........................................................................................... 4-10 Figure 4-4 Surveillance Capsule Tensile and Flux-Monitor Compartment Assembly in the Calvert C liffs U nit I Reactor Vessel ........................................................................................... 4-11 Figure 5-1 Charpy V-Notch Impact Energy vs. Temperature for Calvert Cliffs Unit 1 Reactor Vessel Intermediate Shell Plate D-7206-3 (Longitudinal Orientation) ..................................... 5-17 Figure 5-2 Charpy V-Notch Lateral Expansion vs. Temperature for Calvert Cliffs Unit 1 Reactor Vessel Intermediate Shell Plate D-7206-3 (Longitudinal Orientation) .......................... 5-18 Figure 5-3 Charpy V-Notch Percent Shear vs. Temperature for Calvert Cliffs Unit I Reactor Vessel Intermediate Shell Plate D-7206-3 (Longitudinal Orientation) ..................................... 5-19 Figure 5-4 Charpy V-Notch Impact Energy vs. Temperature for Calvert Cliffs Unit 1 Reactor Vessel Intermediate Shell Plate D-7206-3 (Transverse Orientation) ........................................ 5-20 Figure 5-5 Charpy V-Notch Lateral Expansion vs. Temperature for Calvert Cliffs Unit I Reactor Vessel Intermediate Shell Plate D-7206-3 (Transverse Orientation) ............................. 5-21 Figure 5-6 Charpy V-Notch Percent Shear vs. Temperature for Calvert Cliffs Unit I Reactor Vessel Intermediate Shell Plate D-7206-3 (Transverse Orientation) ........................................ 5-22 Figure 5-7 Charpy V-Notch Impact Energy vs. Temperature for the Calvert Cliffs Unit 1 Reactor Vessel Surveillance Program Weld M etal ...................................................................... 5-23 Figure 5-8 Charpy V-Notch Lateral Expansion vs. Temperature for the Calvert Cliffs Unit 1 Reactor Vessel Surveillance Program Weld M etal ...................................................................... 5-24 Figure 5-9 Charpy V-Notch Percent Shear vs. Temperature for the Calvert Cliffs Unit I Reactor Vessel Surveillance Program Weld M etal ...................................................................... 5-25 Figure 5-10 Charpy V-Notch Impact Energy vs. Temperature for the Calvert Cliffs Unit 1 Reactor Vessel Heat-Affected-Zone M aterial ............................................................................. 5-26 Figure 5-11 Charpy V-Notch Lateral Expansion vs. Temperature for the Calvert Cliffs Unit I Reactor Vessel Heat-Affected-Zone M aterial ............................................................................. 5-27 Figure 5-12 Charpy V-Notch Percent Shear vs. Temperature for the Calvert Cliffs Unit 1 Reactor Vessel H eat-Affected-Zone M aterial ............................................................................. 5-28 Figure 5-13 Charpy V-Notch Impact Energy vs. Temperature for the Calvert Cliffs Unit 1 Reactor Vessel Standard Reference M aterial .............................................................................. 5-29 Figure 5-14 Charpy V-Notch Lateral Expansion vs. Temperature for the Calvert Cliffs Unit 1 Reactor Vessel Standard Reference M aterial .............................................................................. 5-30 WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 ix Figure 5-15 Charpy V-Notch Percent Shear vs. Temperature for the Calvert Cliffs Unit I Reactor Vessel Standard Reference M aterial .............................................................................. 5-31 Figure 5-16 Charpy Impact Specimen Fracture Surfaces for Calvert Cliffs Unit I Reactor Vessel Intermediate Shell Plate D-7206-3 (Longitudinal Orientation) ..................................... 5-32 Figure 5-17 Charpy Impact Specimen Fracture Surfaces for Calvert Cliffs Unit 1 Reactor Vessel Intermediate Shell Plate D-7206-3 (Transverse Orientation) ........................................ 5-33 Figure 5-18 Charpy Impact Specimen Fracture Surfaces for the Calvert Cliffs Unit 1 Reactor Vessel Surveillance Program Weld M aterial ............................................................................. 5-34 Figure 5-19 Charpy Impact Specimen Fracture Surfaces for the Calvert Cliffs Unit 1 Reactor Vessel H eat-A ffected-Zone M aterial ......................................................................................... 5-35 Figure 5-20 Tensile Properties for Calvert Cliffs Unit I Reactor Vessel Intermediate Shell Plate D-7206-3 (Longitudinal O rientation) ............................................................................ 5-36 Figure 5-21 Tensile Properties for Calvert Cliffs Unit 1 Reactor Vessel Surveillance Program Weld ........................................................................................... 5-37 Figure 5-22 Tensile Properties for the Calvert Cliffs Unit 1 Reactor Vessel Heat-Affected-Zone M aterial .......................................................................................................................... 5-3 8 Figure 5-23 Fractured Tensile Specimens from Calvert Cliffs Unit I Reactor Vessel Intermediate Shell Plate D-7206-3 (Longitudinal Orientation) ................................................................... 5-39 Figure 5-24 Fractured Tensile Specimens from the Calvert Cliffs Unit 1 Reactor Vessel Surveillance Program Weld M etal ...................................................................................................... 5-40 Figure 5-25 Fractured Tensile Specimens from the Calvert Cliffs Unit 1 Reactor Vessel Heat-A ffected-Zone M aterial ......................................................................................... 5-41 Figure 5-26 Engineering Stress-Strain Curve for Calvert Cliffs Unit 1 Intermediate Shell Plate D-7206-3 Tensile Specimen IK4 Tested at 750 (Longitudinal Orientation) .................. 5-42 Figure 5-27 Engineering Stress-Strain Curve for Calvert Cliffs Unit I Intermediate Shell Plate D-7206-3 Tensile Specimen 1JB Tested at 2250 (Longitudinal Orientation) ................ 5-42 Figure 5-28 Engineering Stress-Strain Curve for Calvert Cliffs Unit I Intermediate Shell Plate D-7206-3 Tensile Specimen IKY Tested at 5500 (Longitudinal Orientation) ............... 5-43 Figure 5-29 Engineering Stress-Strain Curve for Calvert Cliffs Unit 1 Surveillance Program Weld M etal Tensile Specimen 3KT Tested at 750 ................................................................... 5-44 Figure 5-30 Engineering Stress-Strain Curve for Calvert Cliffs Unit I Surveillance Program Weld M etal Tensile Specimen 3L3 Tested at 1500 .................................................................. 5-44 Figure 5-31 Engineering Stress-Strain Curve for Calvert Cliffs Unit 1 Surveillance Program Weld M etal Tensile Specimen 3L1 Tested at 550. .................................................................. 5-45 Figure 5-32 Engineering Stress-Strain Curve for Calvert Cliffs Unit I Heat-Affected-Zone Material Tensile Specim en 4KE Tested at 750 ............................................................................. 5-46 WCAP- 17365-NP March 2011 Revision 0

X Westinghouse Non-Proprietary Class 3 Figure 5-33 Engineering Stress-Strain Curve for Calvert Cliffs Unit I Heat-Affected-Zone Material Tensile Specim en 4KJ Tested at 1750. ........................................................................... 5-46 Figure 5-34 Engineering Stress-Strain Curve for Calvert Cliffs Unit 1 Heat-Affected-Zone Material Tensile Specim en 4KK Tested at 5500 ........................................................................... 5-47 Figure 6-1 Calvert Cliffs Unit I rO Reactor Geometry without Surveillance Capsules ................. 6-17 Figure 6-2 Calvert Cliffs Unit I rO Reactor Geometry with 70 and 14' Surveillance Capsules ..... 6-18 Figure 6-3 Calvert Cliffs Unit I rz Reactor Geometry ................................................................... 6-19 Figure E- 1 Regulatory Guide 1.99, Revision 2 Predicted Decrease in Upper-Shelf Energy as a Function of Copper and Fluence ...................................................................................... E-2 WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 xi EXECUTIVE

SUMMARY

The purpose of this report is to document the testing results of surveillance Capsule 2840 from Calvert Cliffs Unit 1. Capsule 284' was removed at 26.53 Effective Full Power Years, EFPY, (at 2700 MWt, the licensed rated thermal power at the time of capsule removal) or equivalently 26.17 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. A fluence evaluation utilizing the neutron transport and dosimetry cross-section libraries was derived from the ENDF/B-VI database. In this document, EFPYs are expressed in terms of 2737 MWt, the reference power of the analysis, except in the case of exposure cumulative parameters Tables for which EFPY at 2700 MWt for the first nineteen cycles are also included for the purpose of direct comparison with previous documents. Capsule 284' received a fluence of 2.33 x 1019 n/cm2 (E > 1.0 MeV) after irradiation to 26.17 EFPY. The peak clad/base metal interface vessel fluence after 26.17 EFPY of plant operation was 2.32 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 I Capsule 284' are less than the Regulatory Guide 1.99, Revision 2 [Reference 1] predictions. 2) The Calvert Cliffs Unit I 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 (48 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 (48 EFPY) as required by 10 CFR 50.61

[Reference 3]. The PTS evaluation is presented in Appendix F. 5) The Capsule 2840 evaluations, material properties and fluence, did not affect the applicability of the current Calvert Cliffs Unit 1 pressure-temperature (P-T) limit curves. The current Calvert Cliffs Unit 1 P-T limit curves are now applicable through license extension (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.

WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 1-1 1

SUMMARY

OF RESULTS The analysis of the reactor vessel materials contained in surveillance Capsule 2840, the third capsule removed and tested from the Calvert Cliffs Unit I 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 2840. 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 1 capsule reports.

" Capsule 284' received an average fast neutron fluence (E > 1.0 MeV) of 2.33 x 1019 n/cm 2 after 26.17 effective full power years (EFPY) of plant operation.

" Irradiation of the reactor vessel Intermediate Shell Plate D-7206-3 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 104.8°F and an irradiated 50 ft-lb transition temperature of 147.5°F. This results in a 30 ft-lb transition temperature increase of 98.6°F and a 50 ft-lb transition temperature increase of 111.6'F for the longitudinally oriented specimens.

Irradiation of the reactor vessel Intermediate Shell Plate D-7206-3 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 149.6°F and an irradiated 50 ft-lb transition temperature of 182.9'F. This results in a 30 ft-lb transition temperature increase of 127.0'F and a 50 ft-lb transition temperature increase of 128.1°F for the transversely oriented specimens.

Irradiation of the Surveillance Program Weld Metal (Heat # 33A277) Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 16.7°F and an irradiated 50 ft-lb transition temperature of 60.7°F. This results in a 30 ft-lb transition temperature increase of 78.0'F and a 50 ft-lb transition temperature increase of 99.2'F.

Irradiation of the Heat-Affected-Zone (HAZ) Material Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 28.8'F and an irradiated 50 ft-lb transition temperature of 82.3'F.

This results in a 30 ft-lb transition temperature increase of 137.3'F and a 50 ft-lb transition temperature increase of 147.1 °F.

The average upper-shelf energy of Intermediate Shell Plate D-7206-3 (longitudinal orientation) resulted in an average energy decrease of 34.1 ft-lb after irradiation. This results in an irradiated average upper-shelf energy of 103.3 ft-lb for the longitudinally oriented specimens.

WCAP-17365-NP March 2011 Revision 0

1-2 Westinghouse Non-Proprietary Class 3

" The average upper-shelf energy of Intermediate Shell Plate D-7206-3 (transverse orientation) resulted in an average energy decrease of 19.8 ft-lb after irradiation. This results in an irradiated average upper-shelf energy of 87.7 ft-lb for the transversely oriented specimens.

The average upper-shelf energy of the Surveillance Program Weld Metal Charpy specimens resulted in an average energy decrease of 43.8 ft-lb after irradiation. This results in an irradiated average upper-shelf energy of 108.0 ft-lb for the weld metal specimens.

The average upper-shelf energy of the HAZ Material Charpy specimens resulted in an average energy decrease of 14.6 ft-lb after irradiation. This results in an irradiated average upper-shelf energy of 113.7, ft-lb for the HAZ Material.

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

Standard Reference Material (SRM) specimens were not included in the Calvert Cliffs Capsule 2840.

However, the SRM unirradiated and previously withdrawn capsule results were reanalyzed in this report. The SRM was contained in Capsule 263', which was irradiated to a neutron fluence of 5.05 x 1018 n/cm 2 (E > 1.0 MeV). The results of the SRM reanalysis will be included in Table 5-10 and shown in Figures 5-13 through 5-15.

o Irradiation of the Standard Reference Material HSST 01 Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 132.0'F and an irradiated 50 ft-lb transition temperature of 167.0'F. This results in a 30 ft-lb transition temperature increase of 99.8°F and a 50 ft-lb transition temperature increase of 112.1 °F.

o The average upper-shelf energy of the Standard Reference Material HSST 01 Charpy specimens resulted in an average energy decrease of 26.1 ft-lb after irradiation. This results in an irradiated average upper-shelf energy of 109.4 ft-lb for the SRM.

" Based on the credibility evaluation presented in Appendix D, the Calvert Cliffs Unit I 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 (48 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 (48 EFPY).

Based on the Pressure-Temperature (P-T) limit curve applicability check in Appendix G, the Capsule 284' evaluations, material properties and fluence did not affect the applicability of the current Calvert WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 1-3 Cliffs Unit I P-T limit curves. The current Calvert Cliffs Unit 1 P-T limit curves are now applicable through license extension (48 EFPY).

The calculated 48 EFPY (end-of-life-extension) neutron fluence values (E > 1.0 MeV) at the core mid-plane for the Calvert Cliffs Unit 1 reactor vessel using the Regulatory Guide 1.99, Revision 2, attenuation formula (i.e., Equation # 3 in the guide) are as follows:

Calculated (48 EFPY): Vessel inner radius* = 3.86 x 1019 n/cm 2 (Taken from Table 6-2) 9 2 Vessel 1/4 thickness = 2.301 x 101 n/cm 2

Vessel 3/4 thickness = 0.817 x 1019 n/cm

Clad/base metal interface

" All of the calculations and dosimetry evaluations described in this present analysis were based on nuclear cross-section data derived from ENDF/B-VI and made use of the latest available calculational tools. Furthermore, the neutron transport and dosimetry evaluation methodologies follow the guidance of Regulatory Guide 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence" [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].

" With the methodology of the present analysis, the calculated peak neutron fluence (E > 1.0 MeV) at the clad/base metal interface (CBMI) for the Calvert Cliffs Unit I reactor vessel at the End-of-Cycle (EOC) 10 is 1.44 x 1019 n/cm 2 .. The last reported [Reference 22, Table 6-2] calculated peak neutron fluence (E > 1.0 MeV) at the CBMI for the Calvert Cliffs Unit 1 reactor vessel at the EOC 10 was 1.96 x 1019 n/cm 2 . The difference in calculated fluences is attributed to the following:

o The present analysis uses the average of as-built pressure vessel inside radius measurements (86.915 inches) while Reference 22 used the minimum reference inside diameter (ID) (172 inches). In other words, the present analysis positions the CBMI 0.915 inches radially outward compared to the last report [Reference 22, Figure 6-2].

o The present analysis uses the BUGLE 96 [Reference 28] cross section library which is based on ENDF/B-VI while Reference 22 used the CASK (DCL-23F) cross section library which is based on ENDFiB-V. Notice that Regulatory Guide 1.190 indicates in page 2 footnote:

"It should be noted that in many applications the ENDF/B-IV and the first three MODs of the ENDF/B-V iron cross-sections result in as much as -20% underprediction of the vessel inner-wall fluence and -35% underprediction of the cavity fluence (Refs. 5-7). Updated ENDF/B-VI iron cross-section data (Ref. 8) have been demonstrated to provide a more accurate determination of the flux attenuation through iron (Refs. 5, 6) and are strongly recommended.

These new iron data are included in ENDF/B-VI."

WCAP- 17365-NP March 2011 Revision 0

1-4 Westinghouse Non-Proprietary Class 3

For Capsule 970, the present analysis provides a calculated capsule axial-span-average fast neutron fluence (E > 1 MeV) of 1.94 x 1019 n/cm2 . The last report summary, Reference 22, indicated that the capsule received an average fast fluence of 2.64 x 1019 n/cm 2 (E > I MeV). The difference in calculated fluences is attributed to the following:

o The present analysis uses the average as-built pressure vessel inside radius (86.915 inches) while Reference 22 used the minimum reference inner diameter (ID) (172 inches).

o The present analysis uses the average of as-built capsule center radius measurements (85.445 inches) while Reference 22 (Figure 6-2) used the design reference inner diameter (ID) to the center of the capsule (169.362 inches).

o Reference 22 Table 6-2 indicated that 2.64 x 1019 n/cm 2 is the capsules' peak fast neutron fluence (E > 1.0 MeV) and Reference 22 page 6-9 last paragraph indicated the calculation included a 3%

bias factor.

o The present analysis uses the BUGLE 96 [Reference 28] cross section library which is based on ENDFIB-VI while Reference 22 used the CASK [Reference 31] cross section library which is based on ENDF/B-V.

For Capsule 970, the present analysis provides a best-estimate least-squares average fast neutron fluence (E > 1 MeV) of 1.98 x 1019 n/cm 2. The last report [Reference 22 page 6-9 last paragraph],

indicated that the fast neutron flux (E > 1 MeV) interpreted from the measurements were 6.92, 6.45 and 6.50 (x 1010 n/cm 2-s) for the top, middle and bottom compartments (where the seconds are in term of 2700 MWt). Thus, the corresponding fluence values were 2.42, 2.25 and 2.27 (x 10' 9 n/cm 2),

respectively. The difference in calculated fluences is attributed to the following:

o The present analysis uses the Iron, Nickel and Cobalt (bare and Cadmium-shielded) measurements as the input to the least-squares analysis for Capsule 97'. The Titanium and Uranium (Cadmium-shielded) monitors were discarded:

1. The Titanium measurements were found to be +4.5a from a database distribution of six similar plants capsules Titanium monitors measurements. Deviations of less than +/-3a are considered acceptable. Additionally, for Capsule 263', "the titanium results were 20 to 30 percent higher, and were not considered valid due to the condition of the postirradiated wires.

They were very brittle and a copper color which was assumed to be titanium nitride"

[Reference 21 ].

2. The Uranium measurements were found to be -2.3y from a database distribution of four similar plants capsules Uranium cadmium-shielded monitors measurements. However, the Uranium cadmium-shielded monitors tend to melt with the cover providing poor specimens

[Reference 21].

In the last report [Reference 22] the interpretation of measured flux was performed "using four of the fast neutron dosimeters (Iron, Nickel, U-238 and Titanium)." Reference 22 states that "the corrections for the photofission in U-238 are not applied to the "best-estimate" fast neutron fluxes WCAP- 17365-NP March 2011 Revision 0

.Westinghouse Non-Proprietary Class 3 1-5 derived from the U-238 dosimeters because there is little or no measurement data currently available to confirm the gamma ray flux levels calculated at the dosimeter position." In the present analysis, the photofission correction for Capsule 970 is calculated to be 0.8450 which is defined as the neutron fission activity divided by the total activity.

o The present analysis uses SNLRML "Recommended Dosimetry Cross Section Compendium"

[Reference 29] while the last report [Reference 22] used DOSDAM 81-82 "Multigroup Cross Section in SAND II Format for Spectral, Integral, and Damage Analysis" [Reference 30].

o Because the dosimetry cross sections are collapsed with the capsule best-estimate spectrum in the case of the present analysis, and the calculated spectrum in the case of Reference 22, all the reasons that determine the difference in calculated fluxes in Capsule 970 also affect the interpretation of the fluxes from measurements.

WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 2-1 2 INTRODUCTION This report presents the results of the examination of Capsule 2840, 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 1 reactor pressure vessel materials Under actual operating conditions.

The surveillance program for the Calvert Cliffs Unit 1 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 1 and 2 Reactor Vessel Materials Irradiation Surveillance Program Baseline Samples for the Baltimore Gas & Electric Co." and CENPD-34

[Reference 5], "Summary Report on Manufacture of Test Specimens and Assembly of Capsules for Irradiation Surveillance of Calvert Cliffs - Unit I 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], "Recommended Practice Surveillance Tests on Structural Materials in Nuclear Reactors." 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 1.

Capsule 284' was removed from the reactor after 26.17 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 284' removed from the Calvert Cliffs Unit 1 reactor vessel and discusses the analysis of the data.

WCAP- 17365-NP March 2011 Revision 0

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 I 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 60'F less than the 50 ft-lb (and 35-mil lateral expansion) temperature as determined from Charpy specimens oriented perpendicular (transverse) to the major working direction of the plate. The RTNDT of a given material is used to index that material to a reference stress intensity factor curve (K1 , 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 ccurve, 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 1 reactor vessel radiation surveillance program, in which a surveillance capsule is periodically removed from the operating nuclear reactor and the encapsulated specimens are tested. The increase in the average Charpy V-notch 30 ft-lb temperature (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 Ki, curve and, in turn, to set operating limits for the nuclear power plant that take into account the effects of irradiation on the reactor vessel materials.

WCAP- 17365-NP March 2011 Revision 0

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 1 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:

" Intermediate Shell Plate D-7206-3 (longitudinal orientation)

" Intermediate Shell Plate D-7206-3 (transverse orientation)

Weld metal fabricated by a submerged arc process with Mil B-4 weld filler wire, Heat Number 33A277 Linde Type 1092 flux, Lot Number 3922, 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 Intermediate Shell Plates D-7206-1 and D-7206-3

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

Test material obtained from the intermediate shell course plate (after thermal heat treatment and forming of the plate) was taken at least one plate thickness from the quenched edges of the plate. All test specimens were machined from the 11/4 and 3/44 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 Intermediate Shell Plate D-7206-1 and adjacent Intermediate Shell Plate D-7206-2, and Intermediate Shell Plate D-7206-1 and adjacent Intermediate Shell Plate D-7206-3, respectively.

Charpy V-notch impact specimens from Intermediate Shell Plate D-7206-3 were machined in the longitudinal orientation (longitudinal axis of the specimen parallel to the major rolling direction) and also in the transverse orientation (longitudinal axis of the specimen perpendicular to the major rolling direction). The core-region weld Charpy impact specimens were machined from the weldment such that the long dimension of each Charpy specimen was perpendicular (normal) to the weld direction. The notch of the weld metal Charpy specimens was machined such that the direction of crack propagation in the specimen was in the welding direction.

Tensile specimens from Intermediate Shell Plate D-7206-3 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 1 surveillance program 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 1 capsules was obtained from an A533, Grade B Class 1 plate labeled HSST 01. The plate was produced by the Lukens Steel Company and heat treated by Combustion Engineering, Inc.

WCAP- 17365-NP March 2011 Revision 0

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-shielded and 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:

2.5% Ag, 5.0% Sn, 92.5% Pb 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 00C)

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 2840 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 1 test specimens report, CENPD-34 [Reference 5], Tables III, XIX and XX, and the CRVSP, Revision 5 [Reference 7],

Table 3-7.

Capsule 284' was removed after 26.17 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 1 reactor vessel. Capsules 83', 970, 2630 and 2770 are radiologically equivalent to the 70 azimuth, while Capsules 1040 and 2840 are radiologically equivalent to the 140 azimuth.

WCAP-17365-NP March 2011 Revision 0

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

Intermediate Shell Intermediate Shell Plate Intermediate Shell Plate D-7206-1 D-7206-2 Plate D-7206-3(b)

Element Combustion Engineering Analysis(a)

Si 0.21 0.24 0.24 S 0.014 0.014 0.016 P 0.011 0.011 0.011 Mn 1.31 1.28 1.29 C 0.25 0.26 0.26 Cr 0.09 0.08 0.08 Ni 0.55 0.64 0.64 Mo 0.58 0.67 0.69 V 0.002 0.001 0.001 Cb 0.01 0.01 0.01 B 0.0002 0.0003 0.0004 Co 0.010 0.008 0.008 N 0.007 0.008 0.008 Cu 0.11 0.12 0.12 Al 0.027 0.028 0.022 W 0.01 0.01 0.01 Ti 0.01 0.01 0.01 As 0.01 0.01 0.01 Sn 0.002 0.005 0.005 Zr 0.002 0.001 0.001 Notes:

(a) Data obtained from CENPD-34 [Reference 5].

(b) Surveillance program test plate.

WCAP- 17365-NP March 2011 Revision 0

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

Lower Shell Lower Shell Lower Shell Plate D-7207-1 Plate D-7207-2 Plate D-7207-3 Element Combustion Engineering Analysis1a)

Si 0.24 0.22 0.22 S 0.016 0.014 0.014 P 0.010 0.009 0.008 Mn 1.29 1.31 1.26 C 0.23 0.25 0.22 Cr 0.11 0.12 0.12 Ni 0.54 0.56 0.53 Mo 0.57 0.55 0.54 V 0.002 0.001 0.001 Cb 0.01 0.01 0.01 B 0.0003 0.0002 0.0002 Co 0.011 0.010 0.010 N 0.008 0.010 0.007 Cu 0.13 0.11 0.11 Al 0.034 0.016 0.020 W 0.01 0.01 0.01 Ti 0.01 0.01 0.01 As 0.01 0.01 0.01 Sn 0.002 0.002 0.001 Zr 0.002 0.002 0.002 Note:

(a) Data obtained from CENPD-34 [Reference 5].

March 2011 WCAP-17365-NP WCAP- 17365-NP March 2011 Revision 0

Westinahouse Non-Proprietary Class 3 4-5 Table 4-3 Chemical Composition (wt %) of the Calvert Cliffs Unit 1 Surveillance Test Materials -Weld and HAZ (Unirradiated)

Intermediate to Lower Shell Girth Weld 9-203 (Heat # HAZ Material 33A277/Linde 1092) [D-7206-1/D-7206-3](c)

Element [D_7206_I/D_7206_2](b)

Combustion Engineering Analysis(a)

Si 0.20 0.18 S 0.013 0.013 P 0.014 0.014 Mn 1.05 1.20 C 0.15 0.15 Cr 0.06 0.06 Ni 0 .1 6 (d) 0.19 Mo 0.55 0.56 V 0.003 0.003 Cb 0.01 0.01 B 0.0001 0.0002 Co 0.003 0.003 N 0.008 0.008 Cu 0.18(d) 0.18 Al 0.002 0.001 W 0.01 0.01 Ti 0.01 0.01 As 0.01 0.01 Sn 0.002 0.002 Zr 0.001 0.001 Notes:

(a) Data obtained from CENPD-34 [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.

WCAP-17365-NP March 2011 Revision 0

4-6 Westinghouse Non-Proprietary Class 3 Table 4-4 Heat Treatment History of the Calvert Cliffs Unit 1 Surveillance Test Materials Materiald') Temperature(a) (OF) Time(a) (hours) Cooling(a)

Austenitized @ 4.00 Water-Quenched 1600 +/- 25 (87 1°C)4.0WtrQecd 0i C l T m r d 125(24 Interm ediate Shell Plates D-7206-1, D-7206-2 and Tempered @ 1225 +/- 25 4.00 Air-Cooled D-7206-3 (663°C)

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

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

Lower Shell Plates D-7207-1, D-7207-2 and Tempered @ 1225 +/- 254.00 Air-Cooled D-7207-3 (663°C)

Stress Relieved @ 40.00 Furnace-Cooled to 600°F 1150 +/- 25 (621°C) (316 0C)

Stress Relieved @ 0.25 See note (b)

Surveillance Weld Metal 1125 + 25 (607°C)

(Heat # 33A277/Linde 1092) Stress Relieved @ 1150 40.00 Furnace-Cooled to 600°F (621°C) (316 0C)

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 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months followed by final stress relief at 1150'F for 40.00 hours0 days 0 hours 0 weeks 0 months . Furnace cooling was performed following the final stress relief.

WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 4-7 Table 4-5 Arrangement of Encapsulated Test Specimens within Calvert Cliffs Unit 1 Capsule 284° Compartment Position(a) Compartment Number (Specimen Type and Material)(a) Specimen Numbers(a) 1 4614 (Tensile HAZ Specimens) 4KJ, 4KK, 4KE 4624 464, 462, 45L, 46C, (Charpy Impact HAZ Specimens) 46D, 463, 46B, 46E, 45U, 45T, 461, 45M 4632 24D, 23Y, 24J, 254, 3 (Charpy Impact Transverse 23U, 252, 242, 241, Plate Specimens) 253, 251, 24E, 24K 4641 4 (Tensile Longitudinal 1K4, 1JB, IKY Plate Specimens) 4651 16A, 16D, 15E, 165, 5 (Charpy Impact Longitudinal 16C, 16B, 16E, 15D, Plate Specimens) 15J, 166, 167, 164 4663 36L, 36P, 35U, 36E, 6 (Charpy Impact4663, Weld Specimens) 36U, 36J, 36M, 371, 36T, 36Y,36D, 36K 7 4673 (Tensile Weld Specimens) 3KT, 3L3, 3L1 Note:

(a) Data obtained from CENPD-34 [Reference 5].

WCAP- 17365-NP March 2011 Revision 0

4-8 Westinghouse Non-Proprietary Class 3 4-8 Westinghouse Non-Proprietary Class 3 zwacwr VC8=z l gSurvebceimc

- -fid

.2W

! I K ~ ~~VeseBal elevdon

_P___View View Figure 4-1 Arrangement of Surveillance Capsules in the Calvert Cliffs Unit 1 Reactor Vessel March 2011 WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 4-9 hInm biwato ar~ ft Wet Cnpft MOMW Fzf=wcuorment, J

kaAuwMoItar Copectm I Figure 4-2 Original Surveillance Program Capsule in the Calvert Cliffs Unit 1 Reactor Vessel WCAP-17365-NP March 2011 Revision 0

4-10 Westinghouse Non-Proprietary Class 3 4-0Wstnhue o-roreay ls coiapben - End u~p CbAW rmpac Sped

. Remingular Tubing

.Wedge Coupling - End Cap Figure 4-3 Surveillance Capsule Charpy Impact Specimen Compartment Assembly in the Calvert Cliffs Unit 1 Reactor Vessel WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 4-11 Wedge Coup&Sn - ft CVp

-Staiales $W~eTubing

- admiuln Sbleld Flux Spectrum Monitor i brmboWd Dowwcr C*dmium Shielded Hlux Monitor Houstng Stainlms Steel Tubing Flux spectum Monitor Thieshold fDeatetr SI- Quartz Thbing:

Tens&l Specimen Split Spaer.

Tensile Specimen Houaing, Rectangular Tubing Wedge Coupling - End Cap Figure 4-4 Surveillance Capsule Tensile and Flux-Monitor Compartment Assembly in the Calvert Cliffs Unit 1 Reactor Vessel WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 5-1 5 TESTING OF SPECIMENS FROM CAPSULE 2840 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 10 CFR 50, Appendices G and H [Reference 2], ASTM Specification E185-82 [Reference 10], and Westinghouse Procedure RMF 8402, Revision 3 [Reference 11], as detailed by Westinghouse RMF Procedures 8102, Revision 3 [Reference 12], and 8103, Revision 2 [Reference 13].

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

[Reference 14]. The specimens and spacer blocks were carefully removed, inspected for identification number, and checked against the master list in CENPD-34 [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 15] and Procedure RMF 8103 on a Tinius-Olsen Model 74, 358J machine. The tup (striker) of the Charpy machine is instrumented with an Instron Impulse instrumentation system, feeding information into a computer. Note that the instrumented Charpy data is for information only. The Instron Impulse system has not been calibrated to ASTM Standard E2298-09 [Reference 16], so the instrumented energy, load, time and stress data are considered for information only. 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 (Fgy), 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 (Wi) 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 (Wt) and the energy at maximum load (Win).

The yield stress (OY) was calculated from the three-point bend formula having the following expression [Reference 17]:

WCAP-17365-NP March 2011 Revision 0

5-2 Westinghouse Non-Proprietary Class 3 B(W - a) 2 C (Eqn. 5-1) where L = distance between the specimen supports in the impact testing machine; B = the width of the specimen measured parallel to the notch; W = height of the specimen, measured perpendicularly to the notch; a = notch depth. The constant C is dependent on the notch flank angle (Tp), 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),

FFr Lr - 3.0 (Eqn. 5-2)

= FL3FGYB(W - a) 2 1.21 B(W-a) 2 For the Charpy specimen, B = 0.394 in., W = 0.394 in., and a = 0.079 in. Equation 5-2 then reduces to:

Ory = 33.3 For (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) = 0.1241 sq. in. (Eqn. 5-4)

Percent shear was determined from post-fracture photographs using the ratio-of-areas methods in compliance with ASTM E23-07a [Reference 15] and A370-09 [Reference 18]. The lateral expansion was measured using a dial gage rig similar to that shown in the same specifications.

Tensile tests were performed on a 20,000-pound Instron, split console test machine (Model 1115) per Procedure RMF 8102 [Reference 12]. 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.

WCAP-17365-NP March 2011 Revision 0

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 2840, which received a fluence of 2.33 x 1019 n/cm 2 (E > 1.0 MeV) in 26.17 EFPY of operation, are presented in Tables 5-1 through 5-8 and are compared with the unirradiated and previously withdrawn capsule results as shown in Figures 5-1 through 5-12. The unirradiated and previously withdrawn capsule results were taken from TR-ESS-001 [Reference 4], BMI-1280 [Reference 21], and BAW-2160

[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 I capsule reports.

The transition temperature increases and changes in upper-shelf energies for the Capsule 2840 materials are summarized in Table 5-9 and led to the following results:

Irradiation of the reactor vessel Intermediate Shell Plate D-7206-3 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 104.8°F and an irradiated 50 ft-lb transition temperature of 147.5°F. This results in a 30 ft-lb transition temperature increase of 98.6°F and a 50 ft-lb transition temperature increase of 111.6°F for the longitudinally oriented specimens.

Irradiation of the reactor vessel Intermediate Shell Plate D-7206-3 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 149.6°F and an irradiated 50 ft-lb transition temperature of 182.9°F. This results in a 30 ft-lb transition temperature increase of 127.0°F and a 50 ft-lb transition temperature increase of 128.1°F for the transversely oriented specimens.

Irradiation of the Surveillance Program Weld Metal (Heat # 33A277) Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 16.7°F and an irradiated 50 ft-lb transition temperature of 60.7°F. This results in a 30 ft-lb transition temperature increase of 78.0°F and a 50 ft-lb transition temperature increase of 99.2°F.

" Irradiation of the Heat-Affected-Zone (HAZ) Material Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 28.8°F and an irradiated 50 ft-lb transition temperature of 82.3'F.

This results in a 30 ft-lb transition temperature increase of 137.3°F and a 50 ft-lb transition temperature increase of 147.1°F.

" The average upper-shelf energy of Intermediate Shell Plate D-7206-3 (longitudinal orientation) resulted in an average energy decrease of 34.1 ft-lb after irradiation. This results in an irradiated average upper-shelf energy of 103.3 ft-lb for the longitudinally oriented specimens.

WCAP- 17365-NP March 2011 Revision 0

5-4 Westinghouse Non-Proprietary Class 3

The average upper-shelf energy of Intermediate Shell Plate D-7206-3 (transverse orientation) resulted in an average energy decrease of 19.8 ft-lb after irradiation. This results in an irradiated average upper-shelf energy of 87.7 ft-lb for the transversely oriented specimens.

The average upper-shelf energy of the Surveillance Program Weld Metal Charpy specimens resulted in an average energy decrease of 43.8 ft-lb after irradiation. This results\ in an irradiated average upper-shelf energy of 108.0 ft-lb for the weld metal specimens.

The average upper-shelf energy of the HAZ Material Charpy specimens resulted in an average energy decrease of 14.6 ft-lb after irradiation. This results in an irradiated average upper-shelf energy of 113.7 ft-lb for the HAZ Material.

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

Standard Reference Material (SRM) specimens were not included in the Calvert Cliffs Capsule 2840. However, the SRM unirradiated and previously withdrawn capsule results were reanalyzed in this report. The SRM was contained in Capsule 2630, which was irradiated to a neutron fluence of 5.05 x 1018 n/cm 2 (E > 1.0 MeV). The results of the SRM reanalysis will be included in Table 5-10 and shown in Figures 5-13 through 5-15.

Irradiation of the Standard Reference Material HSST 01 Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 132.0'F and an irradiated 50 ft-lb transition temperature of 167.0°F. This results in a 30 ft-lb transition temperature increase of 99.8'F and a 50 ft-lb transition temperature increase of 112.1 'F.

The average upper-shelf energy of the Standard Reference Material HSST 01 Charpy specimens resulted in an average energy decrease of 26.1 ft-lb after irradiation. This results in an irradiated average upper-shelf energy of 109.4 ft-lb for the SRM.

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 (48 EFPY) as required by 10 CFR 50, Appendix G

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

WCAP-17365-NP March 2011 Revision 0

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 2840 irradiated to 2.33 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 Intermediate Shell Plate D-7206-3 (longitudinal orientation) indicated that irradiation to 2.33 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 5-20 and Table 5-11.

The results of the tensile tests performed on the surveillance weld metal indicated that irradiation to 2.33 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 2.33 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 Intermediate Shell Plate D-7206-3 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 Intermediate Shell Plate D-7206-3, Figures 5-29 through 5-31 for the surveillance weld metal, and Figures 5-32 through 5-34 for the HAZ material.

WCAP-17365-NP March 2011 Revision 0

5-6 Westinghouse Non-Proprietary Class 3 Table 5-1 Charpy V-notch Data for the Calvert Cliffs Unit 1 Intermediate Shell Plate D-7206-3 Irradiated to a Fluence of 2.33 x 1019 n/cm 2 (E > 1.0 MeV) (Longitudinal Orientation)

Sample Temperature Impact Energy Lateral Expansion Shear Number OF °C ft-lbs Joules mils mm %

164 25 -4 10 14 11 0.28 5 16B 75 24 23 31 22 0.56 10 167 90 32 37 50 31 0.79 15 15D 100 38 33 45 30 0.76 15 16A 125 52 36 49 35 0.89 20 165 150 66 .42 57 40 1.02 40 16D 160 71 50 68 42 1.07 50 16C 175 79 55 75 48 1.22 60 15J 225 107 101 137 83 2.11 98 15E 300 149 106 144 83 2.11 100 16E 325 163 103 140 83 2.11 100 166 350 177 103 140 81 2.06 100 March 2011 WCAP-17365-NP WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 5-7 Table 5-2 Charpy V-notch Data for the Calvert Cliffs Unit 1 Intermediate Shell Plate D-7206-3 Irradiated to a Fluence of 2.33 x 1019 n/cm 2 (E > 1.0 MeV) (Transverse Orientation)

Sample Temperature Impact Energy Lateral Expansion Shear 0

Number OF C ft-lbs Joules mils mm %

241 25 -4 9 12 11 0.28 5 24D 125 52 23 31 22 0.56 15 24K 140 60 30 41 29 0.74 30 24E 150 66 29 39 30 0.76 25 252 160 71 31 42 26 0.66 25 251 175 79 39 53 39 0.99 35 253 185 85 47 64 44 1.12 60 254 195 91 63 85 51 1.30 80 242 200 93 64 87 56 1.42 80 23U 300 149 90 122 74 1.88 100 23Y 325 163 92 125 79 2.01 100 24J 350 177 81 110 68 1.73 100 WCAP-17365-NP March 2011 Revision 0

5-8 Westinghouse Non-Proprietary Class 3 Table 5-3 Charpy V-notch Data for the Calvert Cliffs Unit 1 Surveillance Weld Metal (Heat # 33A277) Irradiated to a Fluence of 2.33 x 1019 n/cm 2 (E > 1.0 MeV)

Sample Temperature Impact Energy Lateral Expansion Shear 0

Number OF C ft-lbs Joules mils mm %

36M -50 -46 8 11 11 0.28 10 36D 0 -18 28 38 27 0.69 20 36E 15 -9 41 56 34 0.86 35 371 25 -4 36 49 29 0.74 25 36J 35 2 36 49 32 0.81 30 35U 50 10 16 22 19 0.48 25 36L 50 10 53 72 47 1.20 40 36K 60 16 51 69 45 1.14 50 36Y 75 24 64 87 49 1.25 70 36U 250 121 111 150 85 2.16 100 36T 275 135 106 144 77 1.96 100 36P 300 149 107 145 85 2.16 100 March 2011 WCAP-17365-NP WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprieta Class 3 5-9 Table 5-4 Charpy V-notch Data for the Calvert Cliffs Unit 1 Heat-Affected-Zone (HAZ)

Material Irradiated to a Fluence of 2.33 x 1019 n/cm2 (E > 1.0 MeV)

Sample Temperature Impact Energy Lateral Expansion Shear Number OF C ft-lbs Joules mils mm %

463 -75 -59 12 16 13 0.33 15 46B 25 -4 28 38 23 0.59 25 45L 30 -1 46 62 37 0.94 35 45U 40 4 54 73 41 1.04 35 46E 50 10 25 34 22 0.56 30 464 60 16 32 43 34 0.86 35 46C 75 24 30 41 27 0.69 40 462 125 52 73 99 52 1.32 85 46D 225 107 88 119 65 1.65 90 461 250 121 116 157 80 2.04 100 45M 275 135 121 164 85 2.16 100 45T 300 149 104 141 76 1.93 100 WCAP-17365-NP March 2011 Revision 0

5-10 Westinghouse Non-Proprietary Class 3 Table 5-5 Instrumented Charpy Impact Test Results for the Calvert Cliffs Unit 1 Intermediate Shell Plate D-7206-3 Irradiated to a Fluence of 2.33x 1019 n/cm 2 (E > 1.0 MeV) (Longitudinal Orientation)

Normalized Energies General Test Charpy (ft-lb/in 2) Yield Time to Max. Time to Fract. Arrest Yield Flow Sample Te Energy, Load, F, Load, Fm Load, Load, Stress Stress No. (0mp. Wt Total At Pm Prop. FR (msec) Fm (lb) (msec) Fbf0b) Fa (lb) (ksi) (ksi)

( F) (ft-lb) Wt/A Wm/A Wp/A (lb) 164 25 12 97 25 72 3500 0.08 3937 0.09 3593 N/A 117 124 16B 75 24 192 123 69 3200 0.07 4113 0.29 4037 N/A 107 122 167 90 36 293 185 108 2800 0.07 4091 0.43 3946 N/A 93 115 15D 100 33 269 229 40 3200 0.08 4119 0.50 4102 N/A 107 122 16A 125 35 282 223 59 2900 0.06 4033 0.50 3982 N/A 97 115 165 150 40 324 218 106 2600 0.06 3947 0.50 3809 500 87 109 16D 160 47 381 277 104 2900 0.07 4082 0.62 3837 1000 97 116 16C 175 52 417 273 144 2600 0.06 3997 0.62 3719 1500 87 110 15J 225 94 755 266 488 2800 0.06 4024 0.60 N/A N/A 93 114 15E 300 97 783 269 513 2600 0.06 3970 0.62 N/A N/A 87 109 16E 325 93 748 260 487 2500 0.07 3890 0.62 N/A N/A 83 106 166 350 94 756 256 500 2500 0.07 3854 0.64 N/A N/A 83 106 WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 5-11 Table 5-6 Instrumented Charpy Impact Test Results for the Calvert Cliffs Unit 1 Intermediate Shell Plate D-7206-3 Irradiated to a Fluence of 2.33 x 1019 n/cm 2 (E > 1.0 MeV) (Transverse Orientation)

Charpy Normalized Energies General Test Energy, (ft-lb/in2) Yield Time to Max. Time to Fract. Arrest Yield Flow Sample No. Temp. W, Load, Fzv Load, F. Load, Load, Stress Stress (OF)Total At PM Prop. Fv (msec) Fm (Ib) (msec) Fbo(lb) Fa (lb) (ksi) (ksi)

(ft-lb) W,/A Wm/A Wp/A (lb) 241 25 9 71 26 46 3200 0.08 3864 0.09 3486 N/A 107 118 24D 125 22 176 125 50 3000 0.07 3779 0.31 3528 N/A 100 113 24K 140 27 221 89 132 3000 0.07 3834 0.26 3782 500 100 114 24E 150 28 222 146 77 2900 0.07 3839 0.35 3674 700 97 112 252 160 30 243 179 64 2800 0.07 3815 0.43 3812 900 93 110 251 175 38 303 200 103 2800 0.07 3811 0.48 3636 1000 93 110 253 185 44 354. 215 139 2800 0.06 3868 0.50 3854 1392 93 111 254 195 58 470 207 262 3000 0.06 3974 0.48 3801 2512 100 116 242 200 59 479 263 216 2800 0.07 3885 0.60 3720 2592 93 111 23U 300 82 657 255 402 2700 0.06 3824 0.60 N/A N/A 90 109 23Y 325 85 685 210 475 2600 0.06 3818 0.50 N/A N/A 87 107 24J 350 72 584 252 331 2300 0.07 3639 0.63 N/A N/A 77 99 WCAP-17365-NP March 2011 Revision 0

5-12 Westinr4house Non-ProDrietarv Class 33 5-12 Westinghouse Non-Proprietary Class Table 5-7 Instrumented Charpy Impact Test Results for the Calvert Cliffs Unit 1 Surveillance Weld Metal (Heat # 33A277) Irradiated to a Fluence of 2.33 x 1019 n/cm 2 (E > 1.0 MeV)

Normalized Energies General Te Charpy (ft-lb/in 2) Yield Time to Max. Time to Fract. Arrest Yield Flow Sample Temp. Load, F, Load, F. Load, Load, Stress Stress No. (OF) Total At PM Prop. F, (msec) Fm (Ib) (msec) Fbf Qb) F. (lb) (ksi) (ksi)

(ft-lb) Wt/A Wm/A We/A (lb) 36M -50 8 61 29 32 3300 0.08 4094 0.10 3977 N/A 110 123 36D 0 27 217 25 193 3400 0.08 4036 0.09 3833 400 113 124 36E 15 40 323 235 89 3400 0.07 4083 0.50 3917 700 113 125 371 25 34 273 227 46 3000 0.07 3922 0.50 3915 900 100 115 36J 35 34 274 26 249 3200 0.07 3909 0.09 3854 1000 107 118 35U 50 16 128 26 102 3300 0.08 3774 0.09 3467 700 110 118 36L 50 50 399 286 113 3200 0.07 4030 0.62 3813 1500 107 120 36K 60 48 384 279 105 3100 0.07 3891 0.62 3788 1600 103 116 36Y 75 59 475 272 203 3100 0.07 3905 0.62 3630 1600 103 117 36U 250 100 803 245 558 2600 0.06 3704 0.60 N/A N/A 87 105 36T 275 94 761 241 520 2500 0.06 3661 0.60 N/A N/A 83 103 36P 300 99 794 243 551 2500 0.06 3683 0.60 N/A N/A 83 103 WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 5-13 Table 5-8 Instrumented Charpy Impact Test Results for the Calvert Cliffs Unit 1 Heat-Affected-Zone (HAZ) Material Irradiated to a Fluence of 2.33 x 1019 n/cm 2 (E > 1.0 MeV)

Normalized Energies General Test Charpy (ft-lb/in2 ) Yield Time to Max. Time to Fract. Arrest Yield Flow Sample T Energy, Load, F, Load, Fm Load, Load, Stress Stress No. emp.OF) Wt Total At PM Prop. (F (msec) F. (lb) (msec) Fbf (lb) Fa (lb) (ksi) (ksi)

( 0 ) (ft-lb) We/A Win/A Wp/A (Ib) 1___ 1_

463 -75 13 103 28 76 3400 0.07 4318 0.09 3947 N/A 113 -

46B 25 25 204 26 178 2800 0.07 4032 0.09 3685 1500 93 114 45L 30 42 339 291 48 3400 0.08 4215 0.61 4190 1700 113 127 45U 40 51 408 290 117 3400 0.07 4188 0.62 3869 2000 113 126

.46E 50 23 189 121 68 3095 0.07 3894 0.29 3867 1500 103 116 464 60 31 252 155 97 3000 0.07 3986 0.35 3951 1100 100 116 46C 75 27 221 122 98 3100 0.07 3965 0.29 3828 2100 103 118 462 125 68 546 283 263 3000 0.07 4118 0.62 3500 2400 100 119 46D 225 80 646 270 376 2700 0.07 4017 0.63 N/A N/A 90 112 461 250 105 845 258 588 2800 0.07 3941 0.60 N/A N/A 93 112 45M 275 110 883 257 625 2700 0.06 3939 0.60 N/A N/A 90 111 45T 300 97 781 44 737 2600 0.06 3950 0.60 N/A N/A 87 WCAP-17365-NP March 2011 Revision 0

5-14 5-14 Westinghouse Non-Pronrietar Class 3 Table 5-9 Effect of Irradiation to 2.33 x 1019 n/cm 2 (E > 1.0 MeV) on the Charpy V-Notch Toughness Properties of the Calvert Cliffs Unit 1 Reactor Vessel Surveillance Capsule 2840 Materials Average 30 ft-lb Transition Average 35 mil Lateral Expansion Average 50 ft-lb Transition Average Energy Absorption at Full Material TemperatureWa) (OF) Temperature(a) (OF) Temperature(a) (OF) Shear(a) (ft-lb)

Unirradiated Irradiated AT Unirradiated Irradiated AT Unirradiated Irradiated AT Unirradiated Irradiated AE Intermediate Shell Plate 6.2 104.8 98.6 18.2 122.5 104.3 35.9 147.5 111.6 137.4 103.3 -34.1 D-7206-3 (LT)

Intermediate Shell Plate 22.6 149.6 127.0 29.4 161.7 132.3 54.8 182.9 128.1 107.5 87.7 -19.8 D-7206-3 (TL)

Surveillance Program MetalWeld -61.3 16.7 78.0 -47.0 39.7 86.7 -38.5 60.7 99.2 151.8 108.0 -43.8 (Heat # 33A277)

HAZ Material -108.5 28.8 137.3 -79.8 66.0 145.8 -64.8 82.3 147.1 128.3 113.7 -14.6 Note:

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

March 2011 WCAP- 7365-NP WCAP-l17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 5-15 Table 5-10 Comparison of the Calvert Cliffs Unit 1 Surveillance Material 30 ft-lb Transition Temperature Shifts and Upper-Shelf Energy Decreases with Regulatory Guide 1.99, Revision 2, Predictions Capsule 30 ft-lb Transition Material Capsule~a) Fluence Temperature Shift (x 10t 9 n/cm 2, Predicted(b) Measured(c) Predicted(b) Measured(c)

E > 1.0 MeV) ( 0F) (0 F) (%) (%)

2630 0.505 67.7 65.8 20.5 16 Intermediate Shell Plate D-7206-3 970 1.94 98.7 111.1 28 26 (Longitudinal) 2840 2.33 102.7 98.6 29 25 Intermediate Shell Plate 970 1.94 98.7 109.5 28 22 D-7206-3 (Transverse) 2840 2.33 102.7 127.0 29 18 2630 0.505 74.3 50.4 29 22 Surveillance Program Weld Metal 970 1.94 108.4 104.5 40 31 (Heat # 33A277) 2840 2.33 112.8 78.0 42 29 2630 0.505 --- 100.2 --- 27 Heat-Affected-Zone 970 1.94 Material 83.9 37 2840 2.33 --- 137.3 --- 11 Standard Reference 2630 0.505 110.2 99.8 --- 19 Material Notes:

(a) Capsule 284° (highlighted) is the latest capsule to be withdrawn and tested from the Calvert Cliffs Unit 1 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-17365-NP March 2011 Revision 0

5-16 Westinghouse Non-Proprietary Class 3 Table 5-11 Tensile Properties of the Calvert Cliffs Unit 1 Capsule 284' Reactor Vessel Surveillance Materials Irradiated to 2.33 x 10' 9 n/cm 2 (E > 1.0 MeV)

Test Ultimate Fracture Fracture Fracture Uniform Total Reduction Material Sample Temp. Yield Strength Load Stress Strength Elongation Elongation in Area Number mp. Strength (ksi) (kip) (ksi) (ksi) (%) (%) (%)

(0F)

Number (ksi) 1K4 125 85 106 3.1 66 207 12.1 23.3 68.1 Intermediate Shell Plate D-7206-3 1JB 225 82 103 3.4 70 178 9.7 20.5 59.8 (Longitudinal) 1KY 550 74 98 3.5 70 176 10.5 22.7 60.0 Surveillance 3KT 75 91 104 3.1 65 228 11.6 27.0 71.6 Program Weld 3L3 150 81 94 3.0 61 155 11.8 26.1 60.6 Metal (Heat # 33A277) 3L1 550 75 94 3.2 64 209 11.2 25.7 69.1 4KE 75 87 103 3.8 79 198 7.8 18.9 59.9 Heat-Affected-Zone 4KJ 175 84 98 2.9 61 205 7.8 23.7 70.4 Material 4KK 550 77 97 3.6 73 231 8.2 16.5 67.7 WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 5-17 Figure 5-1 Charpy V-Notch Impact Energy vs. Temperature for Calvert Cliffs Unit 1 Reactor Vessel Intermediate Shell Plate D-7206-3 (Longitudinal Orientation)

IS PLATE 1-7206-3 (LONGITUDINAL)

CVGRAPH 3. 3 Hyperbolic Tangent Curve Printed en 1/I17/2011 11:19AM Data Setqsi Plotted Curve Plant Capsuk Material 017L Heat #

Calvert Cliffs I UNIRR SA533BI LT C-444 1-1 2 Calvert Cliffs I 263 SA533BI LT C-4441-1 3 Calvert Ciitts I SA533HI LI, C-4441 -1 4 Calvert Cliffs I 284 SA533BI LT C-444 1-1 300_

250-4200-

150 ul z

100 50

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Dog F D1 a 2 03 A4 Resutts Carve Fluenc-t USE UST. d.ISE T VA) d-T 0.30 T (a 5i d-T (P50 12 131.4 .0 6.2 .0 3-N. 9 .0 2 2. 2 115.2 -22.2 72.0 65.8 103. I 09. 2

2. 2 101.8 117. 3 III. I 152.4 3 - 35. b 1 1065 104.8 98. 6 147.5 4 2.2 1031 3 111.0 WCAP- 17365-NP March 2011 Revision 0

5-18 Westinghouse Non-Proprietary Class 3 Figure 5-2 Charpy V-Notch Lateral Expansion vs. Temperature for Calvert Cliffs Unit 1 Reactor Vessel Intermediate Shell Plate D-7206-3 (Longitudinal Orientation)

IS PLATE D-7206-3 4LONCITUDINAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/17t2011 1:23AM Data Setos) Plotted Curve Plant Cap-a.Ie Material Orl. Heat #

Calvedt Cliffs I UNIRR SA533BI LT C-4441-1 2 Calvedl Cliffs I 263 SA533B I LT C-4441- I 3 Calvert Cliffs I 97 SA533BI LT C-4441-1 4 Calvert CifTs 1 284 SA533BI LT C-4441 -1 200 150 E

C 1.100 50

-300.0 0.0 300.0 600.0 Temperature In Deg F c I 02 03 a4 RestaIFs

('urve Fluence [SE USE d-USE T ,35 d-T (V35 1.0 %.5 .0 18.2 .0 2 1.0 93.4 -3.1 82. 3 64.1 3 1.0 86. I -10.4 134. 3 104. I 4 1.0 89.7 -7.8 122.5 104. 3 WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 5-19 Figure 5-3 Charpy V-Notch Percent Shear vs. Temperature for Calvert Cliffs Unit 1 Reactor Vessel Intermediate Shell Plate D-7206-3 (Longitudinal Orientation)

IS PLATE 1)7206-3 (LONGITUDINAL1)

CVGRAPH 5..3 Hyperbolic Tangent Curve Printed on 01/17/2011 11:25 AM Data Set(s) Plotted Curve Plant Capsule Material ODe. Heat #

Calvert Cliffs I UNIRR SA533BI LT C-444 I-1 2 Calvert Cliffs I 263 SA533B I LT C-4441- I 3 Calvert Cliffs I 97 SA533BI LT C-4441-1 4 Calvert Cliffs I 284 SA533BI LT C-444 I-I 125 100 0* 75

-i.

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 og F 0 1 a 2 0 3 A 4 Re*;lts, Curve Fluente USE USE d-USE T @050 d-T 0'50

.0 100.0 59.7 .0 2 .0 100.0 146.5 86.8

.0 3 .0 100.0 152.4 92.7 4 .0 100.0 159.8 100.1 WCAP-17365-NP March 2011 Revision 0

5-20 Westinghouse Non-Proprietary Class 3 Figure 5-4 Charpy V-Notch Impact Energy vs. Temperature for Calvert Cliffs Unit 1 Reactor Vessel Intermediate Shell Plate D-7206-3 (Transverse Orientation)

IS PLATE D-7206-3 (TRANSVERSE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/17/2011 12:08 PM Data Set(s) Plotted Cirve Plant Capulde Material Ori. Heal #

I Calvert Cliffs I UNIRR SA533BI TL C-4441-1 2 Calvert Cliffs I 97 SA533BI TL C-4441-1 3 Calvert Cliffs I 284 SA533B! TL C-444 1-1 300 250 4200 u.

100 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 0 1 a2 0>3 Re1ults Cumv Fluerne ISiE d-IUSE T V30 d-T '.30 T v50 d-T 050

2. 2 107.5 .0 22.6 .0 54. 8 .0 2 2. 2 84.0 132. 1 109.5 174.9 120.1 3 2.2 87.7 -19~. 8 149.6 127.0 182.9 128. 1 WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 5-21 Figure 5-5 Charpy V-Notch Lateral Expansion vs. Temperature for Calvert Cliffs Unit 1 Reactor Vessel Intermediate Shell Plate D-7206-3 (Transverse Orientation)

IS PLATE D-7206-3 (TRANSVERSE)

CVORAPH 5.3 Hypedxlic Tangeni Cnrve Printed on OI/17/2011 12:17 PM Data Set(s) Plotted Curv~e Plant Capsule Material Ori. Heat #*

Calvert Cliffs I UNIRR SA533B31 TL C-4441 -1 Calvert Cliffs I SA533BI Th C-4441.-1 3 Calvert Cliffs I 2N4 SA533BI TL C-'4'1I-1 200 150 is E

C 100 qi 0 .........

0 fl

-340.0 0.0 300.0 600.0 Temperature In Dog F 0 1 a 2 Curve quenre US1E USE d-USE d-1' ,35 1.0 84 3 .0 .0 2 1.0 79.3 145. 0 116.6 3 1, 1 76 t -8.2 161.7 13213 WCAP- 17365-NP March 2011 Revision 0

5-22 Westinghouse Non-Proprietary Class 3 Figure 5-6 Charpy V-Notch Percent Shear vs. Temperature for Calvert Cliffs Unit 1 Reactor Vessel Intermediate Shell Plate D-7206-3 (Transverse Orientation)

IS PLATE D-7206-3 (TRANSVERSE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/17/2011 12:13 PM Data Set(s) Plotted Curve Plant Capsule Material Or. Heat #

1 Calvert Cliffs I UNIRR SA533B I TC C-444 1- I 2 Calvert Cliffs I 97 SA533BI TL C-4441-1 3 Calvert Cliffs I X SA533B I TL C-4441-I I UU I~ I J ~ q U I 75

/4 /

0, 50 25 0/

nI

-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 Sa 2 03 Results Cune Fimence USE USE d-USE T Or50 d-T 050

.0 100.0 .0 76.2 .0 2 .0 100.0 .0 162.0 85.8 3 .0 100.0 .0 175.7 99.5 March 2011 WCAP- 17365-NP WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 5-23 Figure 5-7 Charpy V-Notch Impact Energy vs. Temperature for the Calvert Cliffs Unit 1 Reactor Vessel Surveillance Program Weld Metal SURVEILLANCE WELD METAL CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/I 7/2011 12:20 PM Data Set(s) Plotted Carve Plant Capsule Material Ori. Heat

Calvert Cliffs I UNIRR SAW NA 33A277 2 Calvert Cliffs I 263 SAW NA 33A277 3 Calvert Cliffs I 97 SAW NA 33A277 4 Calvert Cliffs I 284 SAW NA 33A277

-r 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 0 2 03 A4 Reruls (Curve Fluence ILSE USE d-USE T VM'O d-T -. 30 T (r.50 d-T 0150

2. 2 151.8 .0 -61.3 .0 -38. 5 ,0 2 2.2 118. 5 -33.3 -10.9 50. 4 23.0 61.5 3 2.2 10s. 5 -46.3 43. 2 104.5 67. I 105. f 4 2.2 108.0 -43.8 16.7 78.0 60. 7 99. 2 WCAP- 17365-NP March 2011 Revision 0

5-24 Westinghouse Non-Prorietarv Class 3 Figure 5-8 Charpy V-Notch Lateral Expansion vs. Temperature for the Calvert Cliffs Unit 1 Reactor Vessel Surveillance Program Weld Metal SURVEILLANCE WELD METAL CVGRAPPH 5.3 Hyperbolic Tangent Curve Printed on Ol/I7t2011 12.21 PM Data Setts) Plotted Curve Plant Capsiule Material Oil. Heat #

1 Calved Cliffs I UNIRR SAW NA 33A277 2 Calvdt Cliffs I 263 SAW NA 33A277 3 Calvert Cliffs I 97 SAW NA 33A277 4 Calvert Cliffs I 284 SAW NA 33A277 E

c-a S.

0 -- - - - - w - --------- .

-300.0 0.0 300.0 600.0 Temperature In Deg F C t a 2 03 Results Cura've Ftlutre I IM USE d-USF T w35 dT ("35 1.0 99. 6 .0 -47. 0 .0 2 1.0 90.7 -8.9 7. 2 54. 2 3 1.0 83.7 -16.0 56. 4 103. 4 4 1.0 85.9 -13.7 39. 7 86. 7 WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 5-25 Figure 5-9 Charpy V-Notch Percent Shear vs. Temperature for the Calvert Cliffs Unit 1 Reactor Vessel Surveillance Program Weld Metal CURVEIJLLANCE WELD METAL CVGRAPIl 5.3 Ilyperbolic Tangent Curve Printed on 01/17/2011 12:23 PM Data Set(s) Plotted Curve Plant (ap~iae Material Ori. Reat #

Calvert Cliffs I UNIRR SAW NA 33A277 2 Calvert Cliffs I 263 SAW NA 33A277 3 Calvert Cliffs I 97 SAW NA 33A277 4 Calvert Cliff%I 284 SAW NA 33A277 125 100 I.- 75 50 25

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Dog F 0 1 2 03 Re.quits Curve flwiktn U.SE USi: d-USE T to 0 d-T 050

.0 300.0 .0 -16.6 .0 2 .0 l0ll.0 .0 41.8 ~ 8. 4 3 .0 100.0 .0 68.9 85. 5 4 A0 I00.0 .0 629 79, WCAP-17365-NP March 2011 Revision 0

5-26 Westinghouse Non-Proprietary Class 3 Figure 5-10 Charpy V-Notch Impact Energy vs. Temperature for the Calvert Cliffs Unit 1 Reactor Vessel Heat-Affected-Zone Material HEAT AFFECTED ZONE CVGRAPI I 5.3 I yperbolic Tangent Curve Printed on 01/17/2011 12:24 PM Data Set(si Plotted Curve Plant ('Camtile Martial (ri. Heat 4 1 Calvert Cliffs I UNIRR SA533BI NA C-444 I-I 2 Calvert Cliffs I 263 SA533B1 NA C-444 1-I 3 Calvert Cliffs I 97 SA533B1 NA C-4441-I 4 Calveit Cliffs I 284 SA533BI NA C-4441- I 300 w

z

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In DogIF 0 1 a2 03 Results Curvne Fuemk'e LSE UsE d-USE d-T (30 T W511 d-T 050 2.2 128.3 .0 -108.5 .0 -64. 8 .0

1. 2 93. I -33. 2 -8.3 100. 2 49. 8 114. 6 2.2 81.0 -47.3 -24. 6 83.9 4i, 9 109. 7 2.2 113.7 -14.6 28. 8 137. 3 82. 3 147. I WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 5-27 Figure 5-11 Charpy V-Notch Lateral Expansion vs. Temperature for the Calvert Cliffs Unit 1 Reactor Vessel Heat-Affected-Zone Material HEAT AFFECTED ZONE CVGRAPII 5.3 llyperbolic Tangent Curve Printed on 01/17!2011 12:27 PM Data Set(s) Plotted Plant (apsnule Material 0"i. "eat #

Calvert Cliffs I UNIRR SA533BI NA C-4441-i 2 Calvert Cliffs I 263 SA533B I NA C-444I- I 3 Calvert Cliffs I 97 SA533BI NA C-4441-I 4 Calvert Cliffs I 284 SA533B] NA C-4441-I 200 150 E

C

.2 51 50 0 1

-300.0 0.0 300.0 600.0 Temperature In Dg F 0 1 a 2 03 Resutk Curve~ Flutnre I-St. USE d-USE d-T (d.5 1.0 8-. 4 .0 -79.8 .0 1.0( 80.4 -4. 1 26. 1 106. 3 3 1.0( 79. 3 -5. 1 51.6 131,4 4 L 0 100.3 IS. 9 66. 0 145. 8 March 2011 17365-NP WCAP- 17365-NP March 2011 Revision 0

5-28

. .Westinhouse

.orietarv Non-P Class 3 Figure 5-12 Charpy V-Notch Percent Shear vs. Temperature for the Calvert Cliffs Unit 1 Reactor Vessel Heat-Affected-Zone Material HEAT AFFECTED ZONE CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/17/2011 12:29 PM Data Sct(s) Plotted Curve Plant Capsule Malerial oh. Heat #

Calvert Cliffs I UNIRR SA533B 1 NA C-4441 I-1 2,3 Cahvrt Cliffs I 263 SA533B1 NA C-4441-1 Calvert Cliffs I 97 SA533B I NA C-4441 -1 4 CsalvertClifft I 784 SA533R I NA (-4441- 1 125 100 b

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Dog F 0 1 ' 2 03 a 4 murve FIlen" L%.

1S U00 d-Ulsl, I Or5s d- I WS

~.0 100.0 .0 -27.3 .0 2 .0 100.0 .0 57. 3 94.0 3 .0 100.0 .0 41.8 69. 1 4 .0 I00A0 .0 77.6 104.9 WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 5-29 Figure 5-13 Charpy V-Notch Impact Energy vs. Temperature for the Calvert Cliffs Unit 1 Reactor Vessel Standard Reference Material STANDARD REFERENCE MATERIAL CVGRAPHI 3 Hyperbolic Tangent Curve Printed on 01/17/2011 12:35 PM Data Set(s) Plotted Curve Plant Capsule Material Oil. Heat#

Calven Cliffs I UNIRR SA533BI LT HSST-OIMY 2 Calvert Cliffs I 263 SA533BI LT HSST-OIMY 300 IL

-r t

0'

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Dog F 0 i 132 Results Fluhrnn INV ISV T (w.10 d-T (".M T (ff.1 d-T o'5i1 2.2 135.5 .0 32. 2 .0 54.9 2 2.2 119.4 -26. 1 132., 99.8 167.0 112. 1 WCAP-17365-NP March 2011 Revision 0

5-30 Westin2house Non-Pronrietarv Class 3 5 . ... . . .... ... ... . . .. .. . . . i-... .. . s. 3 C la.

Figure 5-14 Charpy V-Notch Lateral Expansion vs. Temperature for the Calvert Cliffs Unit 1 Reactor Vessel Standard Reference Material STANDARD REFERENCE MATERIAL CVGRAPH15.3 Uypeh.nolic TangentCiirve Print*I nO1/17/I011 I12:16 PM Data Selis) Plotted Curve Plant Capsule Material Orl. Heat #

1 calved~ Cliffs I UNIRR SA533nI LT IISST-O1MY 2 Calveit Cliffs I 263 SA533BI LT HSST-OIMY 200 150 E

50

-300.0 0.0 300.0 600.0 Temperature In Dog F C I Results turve Fluence LtE USE d-USE T *35 d-T @35 I

1.0 97.5 .0 39. 2 .0 2 1.0 89.9 -7.6 143. I 103.9 WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 5-31 Figure 5-15 Charpy V-Notch Percent Shear vs. Temperature for the Calvert Cliffs Unit 1 Reactor Vessel Standard Reference Material STANDARD REFERENCE MATERIAL CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/17/2011 12:37 PM Data Set(s) Plotted Clrne Plant Capsule Material Ori. Heat #

Calvert Cliffs I UNIRR SA533B I LT HSST-O I MY 2 Calvert Cliffs I 263 SA533BI LT HSST-O1MY 125 100 t-

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Dog F 0 1 a 2 Results~

Curve I'luence l.,E USE d- US E T (o50 d-T 0.,50 1 .0 100.0 .0 85.7 .0 2 .0 100.0 A0 193.7 108.0 WCAP- 17365-NP March 2011 Revision 0

5-32 WestinehouseeNo-roIetrvCas Non-Proorietarv Class 3 5-2Wsindh 164,25-F 16B, 75-F 167, 90°F 15D, 100-F 16A, 125-F 165, 150°F 16D, 160°F 16C, 175-F 15J, 225°F 15E, 300-F 16E, 325-F 166, 350°F Figure 5-16 Charpy Impact Specimen Fracture Surfaces for Calvert Cliffs Unit 1 Reactor Vessel Intermediate Shell Plate D-7206-3 (Longitudinal Orientation)

WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 5-33 Westinghouse Non-Proprietary Class 3 5-33 241, 25-F 24D, 125°F 24K, 140°F 24E, 150-F 252, 160-F 251, 175°F 253, 185°F 254, 195-F 242, 200°F 23U, 300°F 23Y, 325-F 24J, 350°F Figure 5-17 Charpy Impact Specimen Fracture Surfaces for Calvert Cliffs Unit 1 Reactor Vessel Intermediate Shell Plate D-7206-3 (Transverse Orientation)

WCAP-17365-NP March 2011 Revision 0

5-34 WestinRhouse Non-Pror)rietarv Class 3 5-34 Westinghouse Non-Proprietary Class 3 36M, -50°F 36D, 0°F 36E, 15-F 371, 25-F 36J, 35°F 35U, 50°F 36L, 50°F 36K, 60°F 36Y, 75-F 36U, 250°F 36T, 275-F 36P, 300°F Figure 5-18 Charpy Impact Specimen Fracture Surfaces for the Calvert Cliffs Unit 1 Reactor Vessel Surveillance Program Weld Material WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 5-35 463,-75°F 46B, 25-F 45L, 30°F 45U, 40°F 46E, 50°F 464, 60°F 46C, 75°F 462, 125°F 46D, 225°F 461, 250°F 45M, 275°F 45T, 300°F Figure 5-19 Charpy Impact Specimen Fracture Surfaces for the Calvert Cliffs Unit 1 Reactor Vessel Heat-Affected-Zone Material WCAP- 17365-NP March 2011 Revision 0

5-36 Westinghouse Non-Proprietary Class 3 120.0 100.0 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 o are irradiated to 2.33 x 1019 n/cm 2 (E > 1.0 MeV) 80.0 70.0 Area Reduction 60.0 50.0 Z

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 1 Reactor Vessel Intermediate Shell Plate D-7206-3 (Longitudinal Orientation)

March 2011 WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 5-37 120.0 100.0 Ultimate Tensile Strength 80.0 0.2% Yield Strength"-

60.0 U) 40.0 20.0 0.0 0 100 200 300 400 500 600 Temperature (F)

Legend: Aand

and mare unirradiated A and o and o are irradiated to 2.33 X 1i0 9 n/cm 2 (E > 1.0 MeV) 80.0 70.0 AraReduction 60.0 50.0 40.0 30.0 Total 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 1 Reactor Vessel Surveillance Program Weld WCAP- 17365-NP March 2011 Revision 0

5-38 5-38 Westinghouse Non-Pronrietarv Clasts 3 120.0 Ultimate Tensile Strength 100.0 80.0

~0.2% Yield Strength C

C C

60.0 40.0 20.0 0.0 0 100 200 300 400 500 600 Temperature (F)

Legend: Aand

and m are unirradiated A and o and o are irradiated to 2.33 x 10' 9 n/cm2 (E > 1.0 MeV) 80.0 70.0 Area Reduction 60.0 50.0 40.0 U

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

Figure 5-22 Tensile Properties for the Calvert Cliffs Unit 1 Reactor Vessel Heat-Affected-Zone Material WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 5-39 Wetngos NnPopitryCas359 Specimen 1K4- Tested at 125 0 F Specimen IJB - Tested at 225°F Specimen 1KY - Tested at 550 0 F Figure 5-23 Fractured Tensile Specimens from Calvert Cliffs Unit 1 Reactor Vessel Intermediate Shell Plate D-7206-3 (Longitudinal Orientation)

WCAP-17365-NP March 2011 Revision 0

5-40 Westinghouse Non-Proprietary Class 3 Specimen 3KT - Tested at 75'F Specimen 3L3 - Tested at 150'F Specimen 3L1 - Tested at 550'F Figure 5-24 Fractured Tensile Specimens from the Calvert Cliffs Unit 1 Reactor Vessel Surveillance Program Weld Metal WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 5-41 Wetnhos o-Poretr lss354 Specimen 4KE - Tested at 75°F Specimen 4KJ - Tested at 175 0 F Specimen 4KK - Tested at 550'F Figure 5-25 Fractured Tensile Specimens from the Calvert Cliffs Unit 1 Reactor Vessel Heat-Affected-Zone Material WCAP-17365-NP March 2011 Revision 0

5-42 Westinghouse Non-Proprietary Class 3 120 100 80 60 U,

40 20 0

0.00 0.05 0.10 0.15 0.20 0.25 0.30 Strain (in/in)

Figure 5-26 Engineering Stress-Strain Curve for Calvert Cliffs Unit 1 Intermediate Shell Plate D-7206-3 Tensile Specimen 1K4 Tested at 750 (Longitudinal Orientation) 120 100 80 60 a

40 20 0 4L-0.00 0.05 0.10 0.15 0.20 0.25 0.30 Strain (in fin)

Figure 5-27 Engineering Stress-Strain Curve for Calvert Cliffs Unit 1 Intermediate Shell Plate D-7206-3 Tensile Specimen 1JB Tested at 2250 (Longitudinal Orientation)

WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 5-43 120 100 80 60 Co 40 2:

0 0.00 0.05 0.10 0.15 0.20 0.25 0.30 Strain(In I In)

Figure 5-28 Engineering Stress-Strain Curve for Calvert Cliffs Unit 1 Intermediate Shell Plate D-7206-3 Tensile Specimen 1KY Tested at 5500 (Longitudinal Orientation)

WCAP-17365-NP March 2011 Revision 0

5-44 Westinghouse Non-Proprietary Class 3 120 100 80 60 C,,

40 20 0

0.00 0.05 0.10 0.15 0.20 0.25 0.30 0.35 Strain (in I In)

Figure 5-29 Engineering Stress-Strain Curve for Calvert Cliffs Unit 1 Surveillance Program Weld Metal Tensile Specimen 3KT Tested at 750 100 90 80 70 60 50 a

a 40 30 20 10 0

0.00 0.05 0.10 0.15 0.20 0.25 0.30 0.35 Strain(in I in)

Figure 5-30 Engineering Stress-Strain Curve for Calvert Cliffs Unit 1 Surveillance Program Weld Metal Tensile Specimen 3L3 Tested at 1500 March 2011 17365-NP WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 5-45 100 90 80 70 60 50 40 30 20 10 0

0.00 0.05 0.10 0.15 0.20 0.25 0.30 0.35 Strain (in I In)

Figure 5-31 Engineering Stress-Strain Curve for Calvert Cliffs Unit 1 Surveillance Program Weld Metal Tensile Specimen 3L1 Tested at 5500 WCAP-17365-NP March 2011 Revision 0

5 -46 Westinghouse Non-Proprietary Class 3 120 100 80 I 60 40 2j 0

0.00 0.01 0.02 0.03 0.04 0.05 0.06 0.07 0.08 0.09 Strain (in I In)

Figure 5-32 Engineering Stress-Strain Curve for Calvert Cliffs Unit 1 Heat-Affected-Zone Material Tensile Specimen 4KE Tested at 750 120 100 80 60 I

In 40 20 0o o.00 0.01 0.02 0.03 0.04 0.05 0.06 0.07 0.06 0.09 Strain (in I in)

Figure 5-33 Engineering Stress-Strain Curve for Calvert Cliffs Unit 1 Heat-Affected-Zone Material Tensile Specimen 4KJ Tested at 1750 NOTE: This curve is incomplete due to slippage of the extensometer.

WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 5-47 120 100 80 60 40 20 0

0.00 0.02 0.04 0.06 0.08 0.10 0.12 0.14 0.16 0.18 0.20 Strain (in I In)

Figure 5-34 Engineering Stress-Strain Curve for Calvert Cliffs Unit 1 Heat-Affected-Zone Material Tensile Specimen 4KK Tested at 5500 WCAP-17365-NP March 2011 Revision 0

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

6.1 INTRODUCTION

This section describes a discrete ordinates S. transport analysis performed for the Calvert Cliffs Unit 1 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 2840, withdrawn at the end of the nineteenth plant operating cycle, is provided. In addition, to provide an up-to-date database applicable to the Calvert Cliffs Unit 1 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 Effective Full Power Years (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. In recent years, however, it has been suggested that an exposure model that accounts for differences in neutron energy spectra between surveillance capsule locations and positions within the vessel wall could lead to an improvement in the uncertainties associated with damage trend curves and improved accuracy in the evaluation of damage gradients through the reactor vessel wall.

Because of this potential shift away from a threshold fluence toward an energy-dependent damage function for data correlation, ASTM Standard Practice E853-01, "Analysis and Interpretation of Light-Water Reactor Surveillance Results," [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 E693-01, "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 made use of the latest available calculational tools. Furthermore, the neutron transport and dosimetry evaluation methodologies follow the guidance of Regulatory Guide 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence" [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].

WCAP-17365-NP March 2011 Revision 0

6-2 Westinghouse Non-Proprietary Class 3 6.2 DISCRETE ORDINATES ANALYSIS The arrangement of the surveillance capsules in the Calvert Cliffs Unit 1 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, 277', and 284' as shown in Figure 4-1. These full-core positions correspond to the following octant symmetric locations represented in Figure 6-2: 70 from the core cardinal axes (for the 830, 970, 2630 and 2770 capsules) and 140 from the core cardinal axes (for the 1040 and 2840 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 apart enough 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 I reactor vessel and surveillance capsules, a series of fuel-cycle-specific forward transport calculations were carried out using the following three-dimensional flux synthesis technique:

(p(r, 0, z) = q,(r, 0) * (r,z) (Eqn. 6-1)

(p(r) where (r,0,z) is the synthesized three-dimensional neutron flux distribution, dX(r,0) is the transport solution in r,0 geometry, 4(rz) is the two-dimensional solution for a cylindrical reactor model using the actual axial core power distribution, and *(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 1.

For the Calvert Cliffs Unit 1 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 assure that proper convergence of the inner iterations was achieved on a pointwise basis. The WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 6-3 pointwise inner iteration flux convergence criterion utilized in the r,0 calculations was set at a value of 0.001.

The rz model used for the Calvert Cliffs Unit I 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 rz 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 assure that proper convergence of the inner iterations was achieved on a pointwise basis. The pointwise inner iteration flux convergence criterion utilized in the r,z calculations was also set at a value of 0.001.

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

The core power distributions used in the plant-specific transport analysis were provided by Constellation Energy for each of the first nineteen fuel cycles at Calvert Cliffs Unit 1. Specifically, the data utilized included cycle-dependent fuel assembly initial enrichments, bumups, and axial power distributions. This information was used to develop spatial- and energy-dependent core source distributions averaged over each individual fuel cycle. Therefore, the results from the neutron transport calculations provided data in terms of fuel-cycle-averaged neutron flux, which when multiplied by the appropriate fuel cycle length, generated the incremental fast neutron exposure for each fuel cycle. In constructing these core source distributions, the energy distribution of the source was based on an appropriate fission split for uranium and plutonium isotopes based on the initial enrichment and burnup history of individual fuel assemblies.

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

All of the transport calculations supporting this analysis were carried out using the DORT discrete ordinates code Version 3.2 [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 P 5 Legendre expansion and angular discretization was modeled with an S 16 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' single 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. Similar information is provided in Table 6-2 for the reactor vessel inner radius at four azimuthal locations. The vessel data given in Table 6-2 were WCAP-17365-NP March 2011 Revision 0

6-4 Westin.house Non-Pronrietarv Class 3 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 nineteenth fuel cycle (i.e., after 26.17 EFPY at 2737 MWt of plant operation) was 2.32 x 1019 n/cm 2 .

Both calculated fluence (E > 1.0 MeV) and dpa data are provided in Tables 6-1 and 6-2. These data tabulations include both plant- and fuel-cycle-specific calculated neutron exposures at the end of the nineteenth 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 2, and from 2700 MWt to 2737 MWt that occurred during the current Cycle 20. The projections were based on the assumption that the core power distributions and associated plant operating characteristics from Cycle 19 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 I 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 1 reactor.

From the data provided in Table 6-3, Capsule 2840 received a fluence (E > 1.0 MeV) of 2.33 x 1019 n/cm2 after exposure through the end of the nineteenth fuel cycle (i.e., after 26.17 EFPY at 2737 MWt of plant operation).

Updated lead factors for the Calvert Cliffs Unit I 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 2840) 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, 104' and 2770), the lead factor corresponds to the calculated fluence values at the end of Cycle 19, the last completed fuel cycle for Calvert Cliffs Unit 1.

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.

WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 6-5 The direct comparison of measured versus calculated fast neutron threshold reaction rates for the sensors from Capsule 2840, that was withdrawn from Calvert Cliffs Unit I at the end of the nineteenth fuel cycle, is summarized below.

Reaction Rates (rps/atom)

Reaction Measured Calculated M/C Ratio 63 Cu(n,(x) 60Co 5.31 E- 17 4.63E-17 1.15 54 Fe(n,p) 54Mn 3.89E- 15 3.96E- 15 0.98 5 58 "Ni(n,p) Co 4.56E-15 5.14E- 15 0.89 Average: 1.01

% Standard Deviation: 13.1 The measured-to-calculated (M/C) reaction rate ratios for the Capsule 2840 threshold reactions range from 0.89 to 1.15, and the average M/C ratio is 1.01 +/- 13.1% (Ia). This direct comparison falls well 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 1.

6.4 CALCULATIONAL UNCERTAINTIES The uncertainty associated with the calculated neutron exposure of the Calvert Cliffs Unit 1 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:

I. 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 I 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.

WCAP-17365-NP March 2011 Revision 0

6-6 Westinghouse Non-Proprietary Class 3 The third phase of the qualification (analytical sensitivity study) identified the potential uncertainties introduced into the overall evaluation due to calculational methods approximations as well as to a lack of knowledge relative to various plant-specific input parameters. The overall calculational uncertainty applicable to the Calvert Cliffs Unit I 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 I 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 I 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 1.

WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 6-7 Table 6-1 Calculated Neutron Exposure Rates and Integrated Exposures at the Surveillance Capsule Center(a)

Cumulative Cumulative Neutron Flux (E > 1.0 MeV)

Cycle Irradiation Irradiation [n/cm 2-s]

Length Time Time Cycle [EFPS(b)I [EFPS(b)] [EFPY(b), 70 Capsule 140 Capsule 1 4.49E+07 4.49E+07 1.42 5.23E+10 3.77E+10 2 2.18E+07 6.66E+07 2.11 6.02E+10 4.39E+10 3 2.39E+07 9.05E+07 2.87 5.84E+10 4.23E+10 4 3.14E+07 1.22E+08 3.86 5.71E+10 4.16E+10 5 3.52E+07 1.57E+08 4.98 5.96E+10 4.29E+10 6 3.45E+07 1.92E+08 6.07 6.16E+10 4.46E+10 7 3.50E+07 2.27E+08 7.18 6.14E+ 10 4.43E+10 8 3.36E+07 2.60E+08 8.25 5.62E+10 4.07E+10 9 2.93E+07 2.90E+08 9.18 6.31E+10 4.50E+10 10 5.46E+07 3.44E+08 10.91 4.42E+10 3.05E+10 11 4.33E+07 3.87E+08 12.28 2.84E+10 2.34E+10 12 5.39E+07 4.41E+08 13.99 1.48E+10 1.55E+10 13 5.01E+07 4.91E+08 15.57 2.47E+10 1.90E+10 14 5.22E+07 5.44E+08 17.23 2.26E+10 1.85E+10 15 5.56E+07 5.99E+08 18.99 2.40E+10 1.91E+10 16 5.49E+07 6.54E+08 20.73 2.44E+10 1.97E+10 17 5.52E+07 7.09E+08 22.48 2.53E+10 2.08E+10 18 5.72E+07 7.66E+08 24.29 2.55E+10 1.85E+10 19 5.94E+07 8.26E+08 26.17 2.93E+ 10 2.16E+ 10 Future 1.84E+08 1.01E+09 32.00 2.93E+10 2.16E+10 Future 1.26E+08 1.14E+09 36.00 2.93E+ 10 2.16E+ 10 Future 1.26E+08 1.26E+09 40.00 2.93E+10 2.16E+10 Future 1.26E+08 1.39E+09 44.00 2.93E+10 2.16E+ 10 Future 1.26E+08 1.51E+09 48.00 2.93E+ 10 2.16E+ 10 Future 1.89E+08 1.70E+09 54.00 2.93E+10 2.16E+10 Future 1.89E+08 1.89E+09 60.00 2.93E+ 10 2.16E+ 10 Note:

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

(b) At 2737 MWt.

WCAP-17365-NP March 2011 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(a)

Cumulative Cumulative Cumulative Neutron Fluence (E > 1.0 MeV) 2 Cycle Irradiation Irradiation Irradiation In/cm I Length Time Time Time Cycle [EFPS(b)] [EFPS(b)I [EFPY(b)] [EFPY(c)] 70 Capsule 140 Capsule I 4.49E+07 4.49E+07 1.42 1.44 2.35E+18 1.69E+18 2 2.18E+07 6.66E+07 2.11 2.14 3.66E+18 2.65E+18 3 2.39E+07 9.05E+07 2.87 2.91 5.05E+18 3.66E+18 4 3.14E+07 1.22E+08 3.86 3.92 6.84E+ 18 4.96E+18 5 3.52E+07 1.57E+08 4.98 5.05 8.94E+18 6.47E+18 6 3.45E+07 1.92E+08 6.07 6.15 1.11E+19 8.01E+18 7 3.50E+07 2.27E+08 7.18 7.28 1.32E+19 9.56E+18 8 3.36E+07 2.60E+08 8.25 8.36 1.51E+19 1.09E+ 19 9 2.93E+07 2.90E+08 9.18 9.30 1.70E+19 1.23E+19 10 5.46E+07 3.44E+08 10.91 11.06 1.94E+19 1.39E+19 11 4.33E+07 3.87E+08 12.28 12.45 2.06E+19 1.49E+19 12 5.39E+07 4.41E+08 13.99 14.18 2.14E+19 1.58E+19 13 5.01E+07 4.91E+08 15.57 15.79 2.26E+19 1.67E+19 14 5.22E+07 5.44E+08 17.23 17.47 2.38E+19 1.77E+19 15 5.56E+07 5.99E+08 18.99 19.25 2.52E+19 1.87E+19 16 5.49E+07 6.54E+08 20.73 21.01 2.65E+19 1.98E+19 17 5.52E+07 7.09E+08 22.48 22.79 2.79E+19 2.10E+19 18 5.72E+07 7.66E+08 24.29 24.62 2.93E+19 2.20E+19 19 5.94E+07 8.26E+08 26.17 26.53 3.11E+19 2.33E+19 Future 1.84E+08 1.01E+09 32.00 -- 3.65E+19 2.73E+19 Future 1.26E+08 1.14E+09 36.00 -- 4.02E+19 3.00E+19 Future 1.26E+08 1.26E+09 40.00 -- 4.39E+19 3.28E+19 Future 1.26E+08 1.39E+09 44.00 -- 4.75E+19 3.55E+19 Future 1.26E+08 1.51E+09 48.00 -- 5.12E+19 3.82E+19 Future 1.89E+08 1.70E+09 54.00 -- 5.68E+19 4.23E+19 Future 1.89E+08 1.89E+09 60.00 -- 6.23E+19 4.64E+19 Note:

(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-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 6-9 Westinghouse Non-Proprietary Class 3 6-9 Table 6-1 (Continued) Calculated Neutron Exposure Rates and Integrated Exposures at the Surveillance Capsule Center(a)

Cumulative Cumulative Iron Atom Displacement Rate Cycle Irradiation Irradiation Idpa/s]

Length Time Time Cycle IEFPS(b)I [EFPS(b)] IEFPY(b)I 70 Capsule 140 Capsule 1 4.49E+07 4.49E+07 1.42 7.56E-11 5.47E-11 2 2.18E+07 6.66E+07 2.11 8.70E-11 6.38E-11 3 2.39E+07 9.05E+07 2.87 8.43E- 11 6.15E-11 4 3.14E+07 1.22E+08 3.86 8.26E-11 6.04E- 11 5 3.52E+07 1.57E+08 4.98 8.61E-11 6.23E-11 6 3.45E+07 1.92E+08 6.07 8.90E-11 6.48E-11 7 3.50E+07 2.27E+08 7.18 8.88E-11 6.44E-11 8 3.36E+07 2.60E+08 8.25 8.13E-11 5.91E-11 9 2.93E+07 2.90E+08 9.18 9.12E-11 6.53E-11 10 5.46E+07 3.44E+08 10.91 6.40E- 11 4.44E-11 11 4.33E+07 3.87E+08 12.28 4.13E-11 3.42E- 11 12 5.39E+07 4.41E+08 13.99 2.16E-11 2.26E-11 13 5.01E+07 4.91E+08 15.57 3.59E-11 2.76E-11 14 5.22E+07 5.44E+08 17.23 3.28E-1 1 2.69E-1 1 15 5.56E+07 5.99E+08 18.99 3.49E- 11 2.78E-11 16 5.49E+07 6.54E+08 20.73 3.55E-11 2.87E-11 17 5.52E+07 7.09E+08 22.48 3.67E- 11 3.03E- 11 18 5.72E+07 7.66E+08 24.29 3.70E-11 2.71E-I1 19 5.94E+07 8.26E+08 26.17 4.25E-11 3.16E-11 Future 1.84E+08 1.01E+09 32.00 4.25E- 11 3.16E-11 Future 1.26E+08 1.14E+09 36.00 4.25E- 11 3.16E- 11 Future 1.26E+08 1.26E+09 40.00 4.25E-11 3.16E- 11 Future 1.26E+08 1.39E+09 44.00 4.25E- I1 3.16E- 11 Future 1.26E+08 1.51E+09 48.00 4.25E- 11 3.16E- 11 Future 1.89E+08 1.70E+09 54.00 4.25E- 1I 3.16E- 11 Future 1.89E+08 1.89E+09 60.00 4.25E- 11 3.16E- 11 Note:

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

(b) At 2737 MWt.

WCAP-17365-NP March 2011 Revision 0

6-10 Westinghouse Non-Pronrietarv Class 3 Table 6-1 (Continued) Calculated Neutron Exposure Rates and Integrated Exposures at the Surveillance Capsule Center(a)

Cumulative Cumulative Cumulative Iron Atom Displacements [dpa]

Cycle Irradiation Irradiation Irradiation Length Time Time Time Cycle [EFPS(b)I [EFPS(b)* [EFPY(b)] [EFPY(c)] 70 Capsule 140 Capsule 1 4.49E+07 4.49E+07 1.42 1.44 3.39E-03 2.46E-03 2 2.18E+07 6.66E+07 2.11 2.14 5.29E-03 3.84E-03 3 2.39E+07 9.05E+07 2.87 2.91 7.30E-03 5.31E-03 4 3.14E+07 1.22E+08 3.86 3.92 9.89E-03 7.21E-03 5 3.52E+07 1.57E+08 4.98 5.05 1.29E-02 9.40E-03 6 3.45E+07 1.92E+08 6.07 6.15 1.60E-02 1.16E-02 7 3.50E+07 2.27E+08 7.18 7.28 1.91E-02 1.39E-02 8 3.36E+07 2.60E+08 8.25 8.36 2.18E-02 1.59E-02 9 2.93E+07 2.90E+08 9.18 9.30 2.45E-02 1.78E-02 10 5.46E+07 3.44E+08 10.91 11.06 2.80E-02 2.02E-02 11 4.33E+07 3.87E+08 12.28 12.45 2.98E-02 2.17E-02 12 5.39E+07 4.41E+08 13.99 14.18 3.10E-02 2.29E-02 13 5.01E+07 4.91E+08 15.57 15.79 3.28E-02 2.43E-02 14 5.22E+07 5.44E+08 17.23 17.47 3.45E-02 2.57E-02 15 5.56E+07 5.99E+08 18.99 19.25 3.64E-02 2.73E-02 16 5.49E+07 6.54E+08 20.73 21.01 3.83E-02 2.88E-02 17 5.52E+07 7.09E+08 22.48 22.79 4.04E-02 3.05E-02 18 5.72E+07 7.66E+08 24.29 24.62 4.25E-02 3.21E-02 19 5.94E+07 8.26E+08 26.17 26.53 4.50E-02 3.39E-02 Future 1.84E+08 1.01E+09 32.00 -- 5.28E-02 3.97E-02 Future 1.26E+08 1.14E+09 36.00 -- 5.82E-02 4.37E-02 Future 1.26E+08 1.26E+09 40.00 -- 6.35E-02 4.77E-02 Future 1.26E+08 1.39E+09 44.00 -- 6.89E-02 5.17E-02 Future 1.26E+08 1.51E+09 48.00 -- 7.43E-02 5.57E-02 Future 1.89E+08 1.70E+09 54.00 -- 8.23E-02 6.17E-02 Future 1.89E+08 1.89E+09 60.00 -- 9.03E-02 6.76E-02 Note:

(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-17365-NP March 2011 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-sl Cycle Irradiation Irradiation Length Time Time Cycle [EFPS(a)] [EFPS(a)] [EFpY(a)] 00 150 300 450 1 4.49E+07 4.49E+07 1.42 3.89E+10 2.50E+10 2.13E+10 1.72E+10 2 2.18E+07 6.66E+07 2.11 4.43E+10 2.91E+10 2.59E+10 2.01E+10 3 2.39E+07 9.05E+07 2.87 4.28E+10 2.79E+10 2.25E+10 1.75E+10 4 3.14E+07 1.22E+08 3.86 4.23E+10 2.77E+10 2.47E+10 1.95E+10 5 3.52E+07 1.57E+08 4.98 4.41E+10 2.84E+10 2.55E+10 1.98E+10 6 3.45E+07 1.92E+08 6.07 4.57E+10 2.96E+10 2.62E+10 2.02E+10 7 3.50E+07 2.27E+08 7.18 4.55E+10 2.94E+10 2.61E+10 2.10E+10 8 3.36E+07 2.60E+08 8.25 4.15E+10 2.69E+10 2.43E+10 1.93E+10 9 2.93E+07 2.90E+08 9.18 4.71E+10 2.98E+10 2.72E+ 10 2.09E+10 10 5.46E+07 3.44E+08 10.91 3.49E+10 2.04E+10 1.67E+10 1.28E+10 11 4.33E+07 3.87E+08 12.28 2.11E+10 1.63E+10 1.68E+10 1.25E+10 12 5.39E+07 4.41E+08 13.99 1.03E+10 1.13E+10 1.26E+10 1.03E+10 13 5.01E+07 4.91E+08 15.57 1.86E+10 1.30E+10 1.14E+10 1.04E+10 14 5.22E+07 5.44E+08 17.23 1.63E+10 1.27E+10 1.16E+10 1.07E+ 10 15 5.56E+07 5.99E+08 18.99 1.83E+10 1.34E+10 1.30E+10 1.01E+10 16 5.49E+07 6.54E+08 20.73 1.86E+10 1.40E+10 1.32E+10 1.02E+10 17 5.52E+07 7.09E+08 22.48 1.93E+10 1.48E+10 1.46E+10 1.11E+10 18 5.72E+07 7.66E+08 24.29 1.97E+10 1.26E+10 1.11E+10 9.75E+09 19 5.94E+07 8.26E+08 26.17 2.23E+10 1.46E+10 1.29E+10 1.07E+10 Future 1.84E+08 1.01E+09 32.00 2.23E+10 1.46E+10 1.29E+10 1.07E+10 Future 1.26E+08 1.14E+09 36.00 2.23E+10 1.46E+10 1.29E+10 1.07E+10 Future 1.26E+08 1.26E+09 40.00 2.23E+10 1.46E+10 1.29E+10 1.07E+10 Future 1.26E+08 1.39E+09 44.00 2.23E+10 1.46E+10 1.29E+10 1.07E+10 Future 1.26E+08 1.51E+09 48.00 2.23E+10 1.46E+10 1.29E+10 1.07E+10 Future 1.89E+08 1.70E+09 54.00 2.23E+10 1.46E+10 1.29E+10 1.07E+10 Future 1.89E+08 1.89E+09 60.00 2.23E+10 1.46E+10 1.29E+10 1.07E+10 Note:

(a) At 2737 MWt.

WCAP-17365-NP March 2011 Revision 0

6-12 ' 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 Neutron Fluence (E > 1.0 MeV) [n/cm 2]

Cycle Irradiation Irradiation Irradiation Length Time Time Time Cycle [EFPSýa)] [EFPS(a)] [EFPYIa)] [EFPy(b)I 00 150 300 450 1 4.49E+07 4.49E+07 1.42 1.44 1.75E+18 1.12E+18 9.58E+17 7.72E+17 2 2.18E+07 6.66E+07 2.11 2.14 2.70E+18 1.75E+18 1.52E+18 1.20E+18 3 2.39E+07 9.05E+07 2.87 2.91 3.72E+18 2.42E+18 2.05E+18 1.62E+18 4 3.14E+07 1.22E+08 3.86 3.92 5.04E+18 3.28E+18 2.83E+18 2.23E+18 5 3.52E+07 1.57E+08 4.98 5.05 6.60E+18 4.28E+18 3.72E+18 2.93E+18 6 3.45E+07 1.92E+08 6.07 6.15 8.17E+18 5.30E+18 4.63E+18 3.63E+18 7 3.50E+07 2.27E+08 7.18 7.28 9.76E+18 6.33E+18 5.54E+18 4.36E+18 8 3.36E+07 2.60E+08 8.25 8.36 1.12E+19 7.23E+18 6.36E+18 5.01E+18 9 2.93E+07 2.90E+08 9.18 9.30 1.25E+19 8.11E+18 7.15E+18 5.62E+18 10 5.46E+07 3.44E+08 10.91 11.06 1.44E+ 19 9.22E+ 18 8.07E+ 18 6.32E+ 18 11 4.33E+07 3.87E+08 12.28 12.45 1.54E+19 9.93E+18 8.79E+18 6.86E+18 12 5.39E+07 4.41E+08 13.99 14.18 1.59E+19 1.05E+19 9.47E+18 7.41E+18 13 5.01E+07 4.91E+08 15.57 15.79 1.68E+19 1.12E+19 1.00E+19 7.93E+18 14 5.22E+07 5.44E+08 17.23 17.47 1.77E+19 1.19E+ 19 1.07E+19 8.49E+ 18 15 5.56E+07 5.99E+08 18.99 19.25 1.87E+19 1.26E+19 1.14E+19 9.06E+18 16 5.49E+07 6.54E+08 20.73 21.01 1.97E+19 1.34E+19 1.21E+19 9.62E+18 17 5.52E+07 7.09E+08 22.48 22.79 2.08E+19 1.42E+19 1.29E+19 1.02E+19 18 5.72E+07 7.66E+08 2429 24.62 2.19E+19 1.49E+19 1.35E+19 1.08E+19 19 5.94E+07 8.26E+08 26.17 26.53 2.32E+19 1.58E+19 1.43E+19 1.14E+19 Future 1.84E+08 1.01E+09 32.00 -- 2.73E+19 1.85E+19 1.67E+19 1.34E+19 Future 1.26E+08 1.14E+09 36.00 -- 3.02E+19 2.03E+19 1.83E+19 1.47E+19 Future 1.26E+08 1.26E+09 40.00 -- 3.30E+19 2.22E+19 1.99E+19 1.61E+19 Future 1.26E+08 1.39E+09 44.00 -- 3.58E+19 2.40E+19 2.15E+19 1.74E+19 Future 1.26E+08 1.51E+09 48.00 -- 3.86E+19 2.59E+19 2.31E+19 1.88E+19 Future 1.89E+08 1.70E+09 54.00 -- 4.28E+19 2.86E+19 2.56E+19 2.08E+19 Future 1.89E+08 1.89E+09 60.00 -- 4.70E+19 3.14E+19 2.80E+19 2.28E+19 Note:

(a) At 2737 MWt.

(b) At 2700 MWt.

WCAP- 17365-NP March 2011 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)] [EFPS(a)] [EFPY(a)] 00 150 300 450 1 4.49E+07 4.49E+07 1.42 5.91E-11 3.83E-11 3.25E-11 2.64E-11 2 2.18E+07 6.66E+07 2.11 6.72E-11 4.45E-I1 3.95E- 11 3.08E-11 3 2.39E+07 9.05E+07 2.87 6.50E-11 4.27E-11 3.43E- 11 2.69E- 11 4 3.14E+07 1.22E+08 3.86 6.42E-11 4.23E-11 3.77E- 11 3.00E-11 5 3.52E+07 1.57E+08 4.98 6.70E-11 4.34E-11 3.88E-11 3.05E- 11 6 3.45E+07 1.92E+08 6.07 6.93E-11 4.53E-11 3.99E- 11 3.10E-11 7 3.50E+07 2.27E+08 7.18 6.90E-11 4.49E-11 3.97E- 11 3.22E- 11 8 3.36E+07 2.60E+08 8.25 6.30E-11 4.11E-1I 3.70E- 11 2.96E-11 9 2.93E+07 2.90E+08 9.18 7.14E-11 4.56E-11 4.13E-11 3.21E-11 10 5.46E+07 3.44E+08 10.91 5.28E-11 3.13E-I 1 2.55E-1I 1.97E-11 11 4.33E+07 3.87E+08 12.28 3.22E-11 2.50E-11 2.55E-11 1.92E-11 12 5.39E+07 4.41E+08 13.99 1.58E-11 1.74E-11 1.93E-11 1.58E-11 13 5.01E+07 4.91E+08 15.57 2.84E-11 1.99E-11 1.74E- 11 1.59E-11 14 5.22E+07 5.44E+08 17.23 2.49E- 11 1.95E-II 1.78E- 11 1.65E-11 15 5.56E+07 5.99E+08 18.99 2.79E-11 2.05E-11 1.99E- 11 1.56E- 11 16 5.49E+07 6.54E+08 20.73 2.84E-11 2.14E-11 2.01E-11 1.57E-11 17 5.52E+07 7.09E+08 22.48 2.94E-11 2.28E-11 2.22E- 11 1.71E-11 18 5.72E+07 7.66E+08 24.29 3.OOE- 11 1.94E- 11 1.69E- 11 1.50E-11 19 5.94E+07 8.26E+08 26.17 3.39E-11 2.25E- 11 1.97E- 11 1.64E- 11 Future 1.84E+08 1.01E+09 32.00 3.39E-11 2.25E- 11 1.97E- 11 1.64E- 11 Future 1.26E+08 1.14E+09 36.00 3.39E-11 2.25E- 11 1.97E- 11 1.64E- 11 Future 1.26E+08 1.26E+09 40.00 3.39E- 11 2.25E- Il 1.97E-11 1.64E- 11 Future 1.26E+08 1.39E+09 44.00 3.39E- 11 2.25E- II 1.97E-11 1.64E- 11 Future 1.26E+08 1.51E+09 48.00 3.39E-11 2.25E-11 1.97E-11 1.64E-11 Future 1.89E+08 1.70E+09 54.00 3.39E-11 2.25E- II 1.97E-11 1.64E- 11 Future 1.89E+08 1.89E+09 60.00 3.39E-11 2.25E- 11 1.97E-11 1.64E-11 Note:

(a) At 2737 MWt.

WCAP-17365-NP March 2011 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 [dpa]

Cycle Irradiation Irradiation Irradiation Length Time Time Time Cycle [EFPS(J)] [EFPS(a)] IEFPY(2a* [EFPY(b)] 00 150 300 450 1 4.49E+07 4.49E+07 1.42 1.44 2.65E-03 1.72E-03 1.46E-03 1.19E-03 2 2.18E+07 6.66E+07 2.11 2.14 4.10E-03 2.68E-03 2.31E-03 1.85E-03 3 2.39E+07 9.05E+07 2.87 2.91 5.65E-03 3.70E-03 3.13E-03 2.49E-03 4 3.14E+07 1.22E+08 3.86 3.92 7.66E-03 5.02E-03 4.31E-03 3.43E-03 5 3.52E+07 1.57E+08 4.98 5.05 1.OOE-02 6.54E-03 5.67E-03 4.50E-03 6 3.45E+07 1.92E+08 6.07 6.15 1.24E-02 8.11E-03 7.05E-03 5.57E-03 7 3.50E+07 2.27E+08 7.18 7.28 1.48E-02 9.68E-03 8.43E-03 6.70E-03 8 3.36E+07 2.60E+08 8.25 8.36 1.69E-02 1.1 IE-02 9.68E-03 7.69E-03 9 2.93E+07 2.90E+08 9.18 9.30 1.90E-02 1.24E-02 1.09E-02 8.63E-03 10 5.46E+07 3.44E+08 10.91 11.06 2.19E-02 1.41E-02 1.23E-02 9.71E-03 11 4.33E+07 3.87E+08 12.28 12.45 2.33E-02 1.52E-02 1.34E-02 1.05E-02 12 5.39E+07 4.41E+08 13.99 14.18 2.42E-02 1.61E-02 1.44E-02 1.14E-02 13 5.01E+07 4.91E+08 15.57 15.79 2.56E-02 1.71E-02 1.53E-02 1.22E-02 14 5.22E+07 5.44E+08 17.23 17.47 2.69E-02 1.82E-02 1.62E-02 1.31E-02 15 5.56E+07 5.99E+08 18.99 19.25 2.84E-02 1.93E-02 1.73E-02 1.39E-02 16 5.49E+07 6.54E+08 20.73 21.01 3.OOE-02 2.05E-02 1.84E-02 1.48E-02 17 5.52E+07 7.09E+08 22.48 22.79 3.16E-02 2.17E-02 1.97E-02 1.57E-02 18 5.72E+07 7.66E+08 24.29 24.62 3.33E-02 2.28E-02 2.06E-02 1.66E-02 19 5.94E+07 8.26E+08 26.17 26.53 3.53E-02 2.42E-02 2.18E-02 1.75E-02 Future 1.84E+08 1.01E+09 32.00 -- 4.16E-02 2.83E-02 2.54E-02 2.06E-02 Future 1.26E+08 1.14E+09 36.00 -- 4.58E-02 3.11E-02 2.79E-02 2.26E-02 Future 1.26E+08 1.26E+09 40.00 -- 5.01E-02 3.40E-02 3.04E-02 2.47E-02 Future 1.26E+08 1.39E+09 44.00 -- 5.44E-02 3.68E-02 3.28E-02 2.68E-02 Future 1.26E+08 1.51E+09 48.00 -- 5.87E-02 3.96E-02 3.53E-02 2.89E-02 Future 1.89E+08 1.70E+09 54.00 -- 6.51E-02 4.39E-02 3.91E-02 3.20E-02 Future 1.89E+08 1.89E+09 60.00 -- 7.15E-02 4.81E-02 4.28E-02 3.51E-02 Note:

(a) At 2737 MWt.

(b) At 2700 MWt.

WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 6-15 Table 6-3 Calculated Fast Neutron Exposure of Surveillance Capsules Withdrawn from Calvert Cliffs Unit 1 Irradiation Time Irradiation Time Fluence (E > 1.0 Iron Displacements Capsule [EFPY(a)] [EFPY(b)] MeV) [n/cm 2] Idpal 2630 2.87 2.91 5.05E+18 7.30E-3 970 10.91 11.06 1.94E+ 19 2.80E-2 2840 26.17 26.53 2.33E+19 3.39E-2 Note:

(a) At 2737 MWt.

(b) At 2700 MWt.

WCAP-17365-NP March 2011 Revision 0

6-16 Westinehouse Non-Pronrietarv Class 3 Table 6-4 Calculated Surveillance Capsule Lead Factors Capsule Location Status Lead Factor 2630 Withdrawn EOC 3 1.36 970 Withdrawn EOC 10 1.34 2840 Withdrawn EOC 19 1.00 830 In Reactor(a) 1.34 1040 In Reactor(a) 1.00 277 0 In Reactor(a) 1.34 Note:

(a) Lead factors are based on the cumulative integrated exposures from Cycles 1 through 19.

WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 6-17 Westinghouse Non-Proprietary Class 3 6-17 R-T Calvert Cliffs Jnit 1 - NO Capsules Meshes: 114R, 628

('4

,/ //

U 00 a

R 4- OE0 3.886E+02 cm 3.89E+)2 Figure 6-1 Calvert Cliffs Unit 1 rO Reactor Geometry without Surveillance Capsules WCAP- 17365-NP March 2011 Revision 0

6-18 Westin2house Non-Pronrietarv Class 3 6-1........ ..... s No . -P.. onie r.... Cla..s. 3 R-T Calvert Cliffs Unit 1 - With Capsules Meshes: 114R, 628

.4-E 0

04 L.J 3.886E+02 cm 0 OOE+00 3.89F+02 Figure 6-2 Calvert Cliffs Unit 1 rO Reactor Geometry with 70 and 140 Surveillance Capsules WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 6-19 Westinghouse Non-Proprietary Class 3 6-19 R-Z Calvert Cliffs Unit 1 -

Meshes: 103R,137Z zF E

0 C4 C>

3.886E+02 cm 0O.OE+00 3,89E+02 Figure 6-3 Calvert Cliffs Unit 1 rz Reactor Geometry WCAP-17365-NP March 2011 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 1 reactor vessel. Table 7-2 documents the withdrawal schedule for the supplemental surveillance capsules (SI and S2) which are also contained in the Calvert Cliffs Unit 1 reactor vessel. The two supplemental surveillance capsules are not part of the Calvert Cliffs Unit 1 10 CFR 50, Appendix H [Reference 2]

program; therefore, the withdrawal year, EFPY, end-of-cycle and capsule fluence projections shown in Table 7-2 are subject to change.

Table 7-1 Surveillance Capsule Withdrawal Schedule 2

Capsule Location Lead Factor(a) Withdrawal EFPY(b) Fluence (n/cm )(c) 2630 1.36 2.87 5.05 x 1018 970 1.34 10.91 1.94 x 10' 9 2840 1.00 26.17 2.33 x 1019 830 1.34 See Note (d) ---

2770 1.34 See Note (e) - --

1040 1.00 Standby(f) -- -

Notes:

(a) Updated in Capsule 2840 dosimetry analysis; see Table 6-4.

(b) EFPY from plant startup.

(c) Updated in Capsule 2840 dosimetry analysis; see Table 6-3.

(d) Capsule 830 should be withdrawn at approximately 34.1 EFPY of plant operation, which is when the fluence on the capsule would equal the projected 48 EFPY peak vessel fluence.

(e) Capsule 2770 should be withdrawn after 34.1 EFPY but before 75.1 EFPY, which is when the fluence on the capsule would equal twice the projected 48 EFPY peak vessel fluence. Since the late withdrawal date is past the current end-of-life-extension for Calvert Cliffs Unit 1, Capsule 2770 should be withdrawn before 48 EFPY. However, this capsule could be withdrawn and tested at a time when the metallurgical data will be most beneficial to Calvert Cliffs Unit 1 in support of a potential second license extension (40-year extension to 80-year end-of-life).

(f) Capsule 104' is currently unable to be removed from the Calvert Cliffs Unit 1 reactor vessel. Thus, no recommendations for its withdrawal are given.

WCAP-17365-NP March 2011 Revision 0

7-2 Westinahouse Non-Pronrietarv Class 3 Table 7-2 Supplemental Surveillance Capsule Withdrawal Schedule Withdrawal Withdrawal End-of-Cycle Projected Capsule ID Capsule Location EFPY Year(a) (EOC) Capsule Fluence (n/cm 2)

S1 2630 33.4 2018 23 2.10 x 10 9 S2 2630 51.4 2038 33 3.80 x 1019 Note:

(a) The withdrawal years were selected to coincide with the next two reactor vessel inservice inspections at Calvert Cliffs Unit 1. The withdrawal EFPY, EOC and projected capsule fluence values were calculated assuming that Capsules S I and S2 would be withdrawn in 2018 and 2038, respectively. Since the two supplemental capsules are not part of the 10 CFR 50 Appendix H program at Calvert Cliffs Unit 1, the withdrawal years shown are subject to change for either capsule.

WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 8-1 8 REFERENCES

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

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

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

4. 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.

5. CENPD-34, Summary Report on Manufacture of Test Specimens and Assembly of Capsulesfor IrradiationSurveillance of Calvert Cliffs - Unit 1 Reactor Vessel Materials,February 1972.

6. ASTM E185-70, Recommended Practicefor Surveillance Tests for Nuclear Reactor Vessels, American Society for Testing and Materials, 1970.

7. Comprehensive Reactor Vessel SurveillanceProgram, 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, in ASTM Standards, Section 3, American Society for Testing and Materials, Philadelphia, PA.

10. ASTM El185-82, Standard Practicefor Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, E706 (IF), ASTM, 1982.

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

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

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

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

WCAP-17365-NP March 2011 Revision 0

8-2 Westinghouse Non-Proprietary Class 3

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

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

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

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

19. ASTM E8-09, Standard Test 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. BMI-1280, Final Report on Calvert Cliffs Unit No. 1 Nuclear Plant Reactor Pressure Vessel Surveillance Program: Capsule 263, December 1980.

22. BAW-2160, Analysis of Capsule 970 Baltimore Gas & Electric Company Calvert Cliffs Nuclear Power Plant Unit No. 1, June 1993.

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

24. ASTM E693-01 (Reapproved 2007), StandardPracticefor CharacterizingNeutron Exposures in Iron and Low Alloy Steels in Terms ofDisplacements PerAtom (DPA), E706 (ID), ASTM, 2010.

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/PhotonTransport Code 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. RSICC Data Library Collection DLC-178, SNLRML: Recommended Dosimetry Cross-Section Compendium, July 1994.

WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 8-3

30. RSICC Data Library Collection DLC-97, DOSDAM 81-82: Multigroup Cross Sections in SAND-II Formatfor Spectral, Integral,and DamageAnalyses, May 1985.

31. RSICC Data Library Collection DLC-23F, CASK: 22 Neutron, 18 Gamma-Ray Group, P3, Cross Sectionsfor Shipping Cask Analysis, June 1987.

WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 A-I APPENDIX A VALIDATION OF THE RADIATION TRANSPORT MODELS BASED ON NEUTRON DOSIMETRY MEASUREMENTS A.1 NEUTRON DOSIMETRY Comparisons of measured dosimetry results to both the calculated and least-squares adjusted values for all surveillance capsules withdrawn from service to date at Calvert Cliffs Unit I 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 1 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(a)]

2630 End of Cycle 3 2.87 970 End of Cycle 10 10.91 2840 End of Cycle 19 26.17 Note:

(a) At 2737 MWt.

The passive neutron sensors included in the evaluations of Surveillance Capsules 263', 970, and 284' are summarized as follows:

WCAP-17365-NP March 2011 Revision 0

A-2 Westinehouse Non-Pronrietarv Class 3 A2WtinroueaonProIeta Clas 3 Reaction Of Capsule Capsule Capsule Sensor Material Interest 2630 970 2840 63 60 Copper (Cd) Cu(ncX) Co X X X 54 Iron Fe(n,p) 4aMn X X X 58 58 Nickel (Cd) Ni(n,p) Co X X X 46 46 Titanium Ti(n,p) Sc X X X 238 Uranium-238* U(n,f) 137Cs 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, 0 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 97'are documented in References A-2 and A-3, respectively. The radiometric counting of the sensors from Capsule 2840 was carried out by Pace Analytical Services, Inc. In all cases, the radiometric counting followed established ASTM procedures. Following sample preparation and weighing, the specific activity of each sensor was determined by means of a high-resolution gamma spectrometer. For the copper, iron, nickel, and cobalt-aluminum sensors, these analyses were performed by direct counting of each of the individual samples.

In the case of the uranium fission sensors, the analyses were carried out by direct counting preceded by dissolution and chemical separation of cerium or cesium from the sensor material.

The irradiation history of the reactor over the irradiation periods experienced by Capsules 2630, 970, and 2840 was based on the monthly power generation of Calvert Cliffs Unit I 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 WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 A-3 the reactions of interest in the exposure evaluations. The irradiation history applicable to Capsules 2630, 970, and 2840 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

t No F Y , Pj Cj [1 - e-&'j] [e"-dJ]

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.

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

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

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

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

tj = Length of irradiation period j (sec).

tdj = Decay time following irradiation period j (sec).

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

In the equation describing the reaction rate calculation, the ratio [Pj]/[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 WCAP-17365-NP March 2011 Revision 0

A-4 A-4 Westinighouse Non-Pronrietarv Class 3 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. 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.

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 applied to the Calvert Cliffs Unit 1 fission sensor reaction rates are summarized as follows:

Correction Capsule 2630 Capsule 970 Capsule 2840 235 U Impurity/Pu Build-in 0.8645 0.8107 0.7979 238 U(Y,f) 0.8442 0.8450 0.8347 238 Net U Correction 0.7298 0.6850 0.6660 These factors were applied in a multiplicative fashion to the decay-corrected cadmium-covered uranium fission sensor reaction rates.

Results of the sensor reaction rate determinations for Capsules 263', 970, and 2840 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.

It is noticed that the bottom compartment Cobalt monitors' measurements of Capsules 97', and 2840 are consistently low compared to those in the middle and top compartments. Reference A-3, Capsule 970 analysis, states that "The primary cause of this result is believed to be 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." Reference A-3 also states that for Capsule 970 "The equivalent 'U-235 fission contamination in the U-238 dosimeters show a similar pattern [to Cobalt]." This report, however, has not attempted to determine the absolute level of 231U fission contamination due to large uncertainties in 235U impurities and thermal flux at the monitor locations.

WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 A-5 A.1.2 Least-Squares Evaluation of Sensor Sets Least-squares adjustment methods provide the capability of combining the measurement data with the corresponding neutron transport calculations resulting in a Best-Estimate neutron energy spectrum with associated uncertainties. Best Estimates for key exposure parameters such as 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, Rj +/-6R = 3(Ujg +/-65cg )((Pg +/- 6 9pg g

relates a set of measured reaction rates, Ri, to a single neutron spectrum, *g, through the multigroup dosimeter reaction cross section, Oig, 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 I 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:

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

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

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

For the Calvert Cliffs Unit I 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 (1iB)" [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].

WCAP-17365-NP March 2011 Revision 0

A-6 Westinghouse Non-Proprietary Class 3 The following provides a summary of the uncertainties associated with the least-squares evaluation of the Calvert Cliffs Unit I surveillance capsule sensor sets.

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

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

Reaction Uncertainty 63 Cu(ncX 60 Co 5%

54 54 Fe(n,p) Mn 5%

58 8 Ni(n,p)1 Co 5%

46 46 Ti(n,p) Sc 5%

238 U(n,f)FP 10%

59 Co(n,y) 6°Co 5%

These uncertainties are given at the Ia level.

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

For sensors included in the Calvert Cliffs Unit 1 surveillance program, the following uncertainties in the fission spectrum averaged cross sections are provided in the SNLRML documentation package.

WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 A-7 Westinghouse Non-Proprietary Class 3 A-7 Reaction Uncertainty 63 Cu(n,a)60Co 4.08-4.16%

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

5 "Ni(n,p)1 8 Co 4.49-4.56%

46 Ti(n,p) 46Sc 4.50-4.87%

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

59 60 Co(nY) 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 input to the least-squares adjustment procedure were obtained directly from the results of plant-specific transport calculations for each surveillance capsule irradiation period and location. The spectrum for each capsule was input in an absolute sense (rather than as simply a relative spectral shape). Therefore, within the constraints of the assigned uncertainties, the calculated data were treated equally with the measurements.

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

Mgg, = R2 +Rg *Rg *Pgg where Rn specifies an overall fractional normalization uncertainty and the fractional uncertainties R. and Rg, specify additional random groupwise uncertainties that are correlated with a correlation matrix given by:

Pgg=[1-O gg, +Oe-H where 2

H- (g - g,)

27,2 The first term in the correlation matrix equation specifies purely random uncertainties, while the second term describes the short-range correlations over a group range y (0 specifies the strength of the latter term). The value of 8 is 1.0 when g = g', and is 0.0 otherwise.

WCAP-1 7365-NP March 2011 Revision 0

A-8 Westin2house Non-Pror)rietarv Class 3 The set of parameters defining the input covariance matrix for the Calvert Cliffs Unit I calculated spectra was as follows:

Flux Normalization Uncertainty (R,) 15%

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

The data comparisons provided in Tables A-5 and A-6 show that the adjustments to the calculated spectra are relatively small and well within the assigned uncertainties for the calculated spectra, measured sensor reaction rates, and dosimetry reaction cross sections. Further, these results indicate that the use of the least-squares evaluation results in a reduction in the uncertainties associated with the exposure of the surveillance capsules. From Section 6.4 of this report, it may be noted that the uncertainty associated with the unadjusted calculation of neutron fluence (E > 1.0 MeV) and iron atom displacements at the surveillance capsule locations is specified as 13% at the la level. From Table A-6, it is noted that the corresponding uncertainties associated with the least-squares adjusted exposure parameters have been reduced to 6-7% for neutron flux (E > 1.0 MeV) and 6% for iron atom displacement rate. Again, the uncertainties from the least-squares evaluation are at the 1C 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 WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 A-9 of the calculated energy spectra. In Table A-8, calculations of fast neutron exposure rates in terms of 4(E > 1.0 MeV) and dpals are compared with the best-estimate results obtained from the least-squares evaluation of the capsule dosimetry results. These two levels of comparison yield consistent and similar results with all measurement-to-calculation comparisons falling well within the 20% limits specified as the acceptance criteria in Regulatory Guide 1.190.

In the case of the direct comparison of measured and calculated sensor reaction rates, the M/C comparisons for fast neutron reactions range from 0.89 to 1.30 for the 24 samples included in the data set.

The overall average M/C ratio for the entire set of Calvert Cliffs Unit I data is 1.07 with an associated standard deviation of 12.0%.

In the comparisons of best-estimate and calculated fast neutron exposure parameters, the corresponding BE/C comparisons for the capsule data sets range from 0.92 to 1.08 for neutron flux (E > 1.0 MeV) and from 0.94 to 1.09 for iron atom displacement rate. The overall average BE/C ratios for neutron flux (E > 1.0 MeV) and iron atom displacement rate are 1.00 with a standard deviation of 8.0% and 1.01 with a standard deviation of 7.4%, 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 I reactor pressure vessel.

Note that for Capsule 2630, the Titanium and cadmium-covered Uranium monitors have not been included in the least-squares analysis. The Titanium monitor has been discarded because of the oxidized state of the sampled when counted [Reference A-2] and because the counting is 6.6a high with respect to similar plants' measurements. The cadmium-covered Uranium monitor was discarded because of the poor condition of the specimens as indicated in Reference A-2.

Note that for Capsule 970, the Titanium, Uranium and Copper monitors have not been included in the least-squares analysis. The Titanium and Copper monitors are not included because their countings are 4.5ca and 11.2ca high with respect to similar plants' measurements. The cadmium-covered Uranium monitor was discarded because these monitors tent to melt with the cover.

Note that for Capsule 284', the Titanium and Uranium monitors are not included in the least-squares analysis. The Titanium monitor has been discarded because the counting is -3.7cr low with respect to similar plants' measurements. The cadmium-covered Uranium monitor was discarded because these monitors tend to melt with the cover.

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

WCAP-17365-NP March 2011 Revision 0

A-10 A-.10 Westinahouse Non-Pronrietarv Class 3 Table A-1 Nuclear Parameters Used in the Evaluation of Neutron Sensors Reaction of Target Atom 90% Response Product Fission Yield Monitor Material Interest Fraction Range(a) (MeV) Half-life (%)

63 Copper Cu (n,a) 0.6917 5.0- 12.0 5.272 y 54 Iron Fe (n,p) 0.0585 2.4-8.8 312.1 d 58 Nickel Ni (n,p) 0.6808 2.1 -8.8 70.82 d 46 Titanium Ti(n,p) 0.0825 4.1 - 10.4 83.79 d Uranium-238 (Cd) 2 38 U (n,f)137Cs 1.0000 1.5-8.1 30.07 y 6.02 238 44 Uranium-238 (Cd) U (n,f)1 ce 1.0000 1.5 -8.1 284.89 d 4.55 59 Cobalt-Aluminum Co (ny) 0.0017 non-threshold 5.272 y Note:

(a) The 90% response range is defined such that, in the neutron spectrum characteristic of the Calvert Cliffs Unit I 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.

WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 A-11 Table A-2 Monthly Thermal Generation during the First Nineteen Fuel Cycles of the Calvert Cliffs Unit 1 Reactor (Reactor Power of 2560 MWt from 12/27/1974 to 9/8/1977; 2700 MWt from 9/9/1977 to 4/30/2010; and, 2737 MWt from 5/1/2010 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)

Dec-74 0 Feb-77 0 Apr-79 1294700 Jun-81 1582420 Jan-75 339490 Mar-77 0 May-79 0 Jul-81 867800 Feb-75 553390 Apr-77 1312200 Jun-79 0 Aug-81 1848100 Mar-75 865790 May-77 1494550 Jul-79 747270 Sep-81 1839020 Apr-75 798980 Jun-77 1683500 Aug-79 1763730 Oct-81 1456380 May-75 1153050 Jul-77 1854120 Sep-79 1846800 Nov-81 1714610 Jun-75 1331640 Aug-77 1862160 Oct-79 1807920 Dec-81 1992730 Jul-75 1625120 Sep-77 1887620 Nov-79 1226660 Jan-82 1918400 Aug-75 823610 Oct-77 1719530 Dec-79 1151040 Feb-82 1803510 Sep-75 1360800 Nov-77 1862350 Jan-80 946140 Mar-82 1984690 Oct-75 1856130 Dec-77 1747660 Feb-80 777990 Apr-82 1607690 Nov-75 1664060 Jan-78 1130950 Mar-80 1795870 May-82 0 Dec-75 1819970 Feb-78 0 Apr-80 1650460 Jun-82 0 Jan-76 1773770 Mar-78 0 May-80 1647220 Jul-82 1448340 Feb-76 1638660 Apr-78 1133350 Jun-80 1837080 Aug-82 1512630 Mar-76 1852110 May-78 1255500 Jul-80 1928450 Sep-82 1279150 Apr-76 1010880 Jun-78 1745710 Aug-80 1928450 Oct-82 1988710 May-76 1874210 Jul-78 1757700 Sep-80 1870130 Nov-82 1875960 Jun-76 1782650 Aug-78 1807920 Oct-80 930070 Dec-82 1860150 Jul-76 1850100 Sep-78 1765150 Nov-80 0 Jan-83 1878230 Aug-76 1866180 Oct-78 1826000 Dec-80 0 Feb-83 1607560 Sep-76 1675730 Nov-78 301320 Jan-81 1086760 Mar-83 1956570 Oct-76 1817960 Dec-78 974270 Feb-81 1785370 Apr-83 1562980 Nov-76 1539650 Jan-79 676970 Mar-81 1936480 May-83 1964610 Dec-76 1233400 Feb-79 1707350 Apr-81 1524100 Jun-83 1769040 Jan-77 0 Mar-79 1916400 May-81 1797880 Jul-83 1978670 WCAP-17365-NP March 2011 Revision 0

A-12 Westinghouse Non-Pronrietarv Class 3 Table A-2 (Continued) Monthly Thermal Generation during the First Nineteen Fuel Cycles of the Calvert Cliffs Unit 1 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)

Aug-83 1830020 Oct-85 1536730 Dec-87 2008800 Feb-90 0 Sep-83 1734050 Nov-85 1907060 Jan-88 1908360 Mar-90 0 Oct-83 0 Dec-85 1968620 Feb-88 1766450 Apr-90 268270 Nov-83 0 Jan-86 1846090 Mar-88 1948540 May-90 0 Dec-83 1070690 Feb-86 1783560 Apr-88 447120 Jun-90 0 Jan-84 1902330 Mar-86 1526690 May-88 0 Jul-90 0 Feb-84 1800270 Apr-86 1899290 Jun-88 0 Aug-90 0 Mar-84 1609050 May-86 1950540 Jul-88 1440310 Sep-90 0 Apr-84 1938170 Jun-86 1852630 Aug-88 1836040 Oct-90 1484500 May-84 355560 Jul-86 1823990 Sep-88 1914840 Nov-90 1920670 Jun-84 1910950 Aug-86 1934470 Oct-88 1703460 Dec-90 666920 Jul-84 1994740 Sep-86 1926500 Nov-88 1180010 Jan-91 1813950 Aug-84 1775780 Oct-86 1398120 Dec-88 1990720 Feb-91 680400 Sep-84 1934280 Nov-86 0 Jan-89 1500570 Mar-91 1984690 Oct-84 1938490 Dec-86 0 Feb-89 1745450 Apr-91 1823470 Nov-84 1524100 Jan-87 1044580 Mar-89 152670 May-91 1092790 Dec-84 1008420 Feb-87 1723680 Apr-89 515160 Jun-91 0 Jan-85 1783810 Mar-87 1807920 May-89 301320 Jul-91 847710 Feb-85 1756340 Apr-87 0 Jun-89 0 Aug-91 1986700 Mar-85 1992730 May-87 220970 Jul-89 0 Sep-91 1920670 Apr-85 293540 Jun-87 1924560 Aug-89 0 Oct-91 1801890 May-85 0 Jul-87 682990 Sep-89 0 Nov-91 1928450 Jun-85 0 Aug-87 1707480 Oct-89 0 Dec-91 1988710 Jul-85 0 Sep-87 1885680 Nov-89 0 Jan-92 1994740 Aug-85 447960 Oct-87 2008800 Dec-89 0 Feb-92 1860410 Sep-85 1778760 Nov-87 1224720 Jan-90 0 Mar-92 1185710 WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 A-13 Table A-2 (Continued) Monthly Thermal Generation during the First Nineteen Fuel Cycles of the Calvert Cliffs Unit 1 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)

Apr-92 0 Jun-94 1363260 Aug-96 1735600 Oct-98 2006490 May-92 0 Jul-94 1423990 Sep-96 1942350 Nov-98 1941880 Jun-92 0 Aug-94 2007000 Oct-96 1993580 Dec-98 1988500 Jul-92 0 Sep-94 1942330 Nov-96 1941990 Jan-99 2006690 Aug-92 355050 Oct-94 1994740 Dec-96 1941900 Feb-99 1812390 Sep-92 1876060 Nov-94 1941690 Jan-97 1999400 Mar-99 2005000 Oct-92 1897920 Dec-94 2007260 Feb-97 1682190 Apr-99 1944420 Nov-92 1767660 Jan-95 2007420 Mar-97 2006610 May-99 1477310 Dec-92 2006550 Feb-95 1812900 Apr-97 1941910 Jun-99 1941890 Jan-93 2008810 Mar-95 2007240 May-97 1868050 Jul-99 1520710 Feb-93 1811680 Apr-95 1936400 Jun-97 1810170 Aug-99 1796060 Mar-93 2006630 May-95 1996970 Jul-97 1989650 Sep-99 1779540 Apr-93 1926390 Jun-95 1585130 Aug-97 1999430 Oct-99 1835020 May-93 2006740 Jul-95 2007240 Sep-97 1358830 Nov-99 1941260 Jun-93 1485720 Aug-95 1912320 Oct-97 1926790 Dec-99 2003450 Jul-93 1998390 Sep-95 1906720 Nov-97 1941960 Jan-00 1874910 Aug-93 2001110 Oct-95 1994710 Dec-97 2006300 Feb-00 1811830 Sep-93 1931540 Nov-95 1296120 Jan-98 2002850 Mar-00 703810 Oct-93 2002460 Dec-95 1930850 Feb-98 1812460 Apr-00 131910 Nov-93 1921980 Jan-96 2007100 Mar-98 2006190 May-00 2004460 Dec-93 1987230 Feb-96 1812790 Apr-98 194170 Jun-00 1934570 Jan-94 1515840 Mar-96 1836790 May-98 0 Jul-00 2005960 Feb-94 391760 Apr-96 0 Jun-98 1373300 Aug-00 2005560 Mar-94 0 May-96 0 Jul-98 2006550 Sep-00 1825960 Apr-94 0 Jun-96 0 Aug-98 2006480 Oct-00 2006400 May-94 254110 Jul-96 0 Sep-98 1934450 Nov-00 1941390 WCAP- 17365-NP March 2011 Revision 0

A-14 Westin2house Non-Pronrietarv Class 3 Table A-2 (Continued) Monthly Thermal Generation during the First Nineteen Fuel Cycles of the Calvert Cliffs Unit 1 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)

Dec-00 2004340 Feb-03 1810390 Apr-05 1932960 Jun-07 1943240 Jan-01 2006190 Mar-03 2006160 May-05 2005250 Jul-07 2007170 Feb-01 1812520 Apr-03 1941540 Jun-05 1933580 Aug-07 2000430 Mar-01 2003350 May-03 2005150 Jul-05 2005290 Sep-07 1937670 Apr-01 1941450 Jun-03 1941020 Aug-05 2005270 Oct-07 1959970 May-01 1892160 Jul-03 2005720 Sep-05 1942660 Nov-07 1943100 Jun-01 1941890 Aug-03 2004790 Oct-05 2008030 Dec-07 2007810 Jul-01 2003260 Sep-03 1937450 Nov-05 1943180 Jan-08 2005550 Aug-01 2005570 Oct-03 2005400 Dec-05 2006950 Feb-08 1407840 Sep-01 1936430 Nov-03 1925610 Jan-06 2007840 Mar-08 958510 Oct-01 2006590 Dec-03 2005940 Feb-06 1247040 Apr-08 1938520 Nov-01 1941610 Jan'04 1993480 Mar-06 0 May-08 2007640 Dec-01 2004560 Feb-04 1812190 Apr-06 1191680 Jun-08 1942020 Jan-02 2001200 Mar-04 1896620 May-06 2008080 Jul-08 1984820 Feb-02 882600 Apr-04 631050 Jun-06 1942350 Aug-08 1986510 Mar-02 0 May-04 1340310 Jul-06 2001500 Sep-08 1941430 Apr-02 0 Jun-04 1941550 Aug-06 2005550 Oct-08 1998920 May-02 0 Jul-04 2006770 Sep-06 1943120 Nov-08 1942510 Jun-02 714170 Aug-04 2006670 Oct-06 2007980 Dec-08 2006020 Jul-02 1672020 Sep-04 1938780 Nov-06 1943170 Jan-09 2007190 Aug-02 2006220 Oct-04 2006220 Dec-06 1513600 Feb-09 1812970 Sep- 02 1941150 Nov-04 1943230 Jan-07 1960360 Mar-09 2005720 2

Oct-0 2005610 Dec-04 2007300 Feb-07 1773730 Apr-09 1942600 Nov-02 1433010 Jan-05 2008040 Mar-07 2004290 May-09 2007390 Dec-02 2006070 Feb-05 1813130 Apr-07 1942780 Jun-09 1939870 Jan-03 2005790 Mar-05 1905640 May-07 2007010 Jul-09 1705370 WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 A-15 Table A-2 (Continued) Monthly Thermal Generation during the First Nineteen Fuel Cycles of the Calvert Cliffs Unit 1 Reactor Thermal Month- Generation Year (MWt-hr)

Aug-09 2007320 Sep-09 1941550 Oct-09 2001300 Nov-09 1942660 Dec-09 2007410 Jan-10 2007190 Feb-10 1124630 Mar-10 498670 WCAP-17365-NP March 2011 Revision 0

A-16 Westinehouse Non-Pronrietarv Class 3 A- 16 Westinchouse Non-Pronrietarv Class 3 Table A-3 Surveillance Capsule Flux for Cj Factors Calculation p(E > 1.0 MeV) In/cm 2-sI Cycle Capsule 2630 Capsule 970 Capsule 2840 Length Fuel Cycle [EFPS(a)] z(b) = -7.90 cm z(b) = _11.0 cm z(b) = _11.0 cm 1 4.49E+07 5.26E+ 10 5.32E+10 3.83E+10 2 2.18E+07 5.96E+ 10 6.02E+ 10 4.40E+ 10 3 2.39E+07 5.85E+10 5.91E+10 4.29E+10 4 3.14E+07 5.76E+10 4.20E+10 5 3.52E+07 6.03E+10 4.34E+10 6 3.45E+07 6.20E+10 4.49E+10 7 3.50E+07 6.18E+10 4.46E+10 8 3.36E+07 5.68E+10 4.11E+10 9 2.93E+07 6.35E+10 4.53E+10 10 5.46E+07 4.47E+10 3.08E+10 11 4.33E+07 2.36E+10 12 5.39E+07 1.53E+10 13 5.01E+07 1.90E+10 14 5.22E+07 1.84E+10 15 5.56E+07 1.91E+10 16 5.49E+07 1.97E+10 17 5.52E+07 2.08E+10 18 5.72E+07 1.86E+ 10 19 5.94E+07 2.18E+ 10 Average --- 5.58E+10 5.68E+10 2.84E+10 Note:

(a) At 2737 MWt.

(b) Elevation from core midplane.

March 2011 WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 A-17 Westinghouse Non-Proprietary Class 3 A- 17 Table A-3 (Continued) Surveillance Capsule Cj Factors Cycle Cj Length Fuel Cycle [EFPSýa)] Capsule 2630 Capsule 970 Capsule 2840 1 4.49E+07 0.942 0.936 1.348 2 2.18E+07 1.067 1.060 1.547 3 2.39E+07 1.047 1.040 1.508 4 3.14E+07 1.014 1.476 5 3.52E+07 1.061 1.527 6 3.45E+07 1.091 1.581 7 3.50E+07 1.088 1.570 8 3.36E+07 0.999 1.445 9 2.931E+07 1.118 1.594 10 5.46E+07 0.787 1.084 11 4.33E+07 0.830 12 5.39E+07 0.540 13 5.01E+07 0.670 14 5.22E+07 0.648 15 5.56E+07 0.673 16 5.49E+07 0.694 17 5.52E+07 0.733 18 5.72E+07 0.654 19 5.94E+07 0.768 Average --- 1.000 1.000 1.000 Note:

(a) At 2737 MWt.

WCAP-17365-NP March 2011 Revision 0

A-18 Westinghouse Non-P. nrietarv Class 3 A..18 Table A-4a Measured(a) Sensor Activities and Reaction Rates for Surveillance Capsule 2630 Measured Activity(b) Saturated Activity Reaction Rate(c)

Reaction Location (dps/g) (dps/g) (rps/atom) 63 60 Cu (n a) CO Top 1.96E+05 6.72E+05 1.03E-16 Middle 1.96E+05 6.72E+05 1.03E-16 Bottom 2.13E+05 7.30E+05 1.11E-16 Average 1.06E-16 54 Fe (n,p) 54Mn Top 3.66E+06 5.34E+06 8.47E-15 Middle 3.45E+06 5.03E+06 7.99E- 15 Bottom 3.57E+06 5.21E+06 8.26E- 15 Average 8.24E-15 58 58 Ni (n,p) Co Top 6.02E+07 7.60E+07 1.09E-14 Middle 5.46E+07 6.90E+07 9.87E-15 Bottom 6.09E+07 7.69E+07 1.1OE- 14 Average 1.06E-14 46Ti(n,p) 46Sc Top 1.47E+06 1.90E+06 1.83E-15 Middle 1.29E+06 1.66E+06 1.60E- 15 Bottom 1.36E+06 1.75E+06 1.69E-15 Average 1.71E-15 23 8 U (n,f) 144Ce (Cd) Top 3.61E+05 5.20E+05 4.52E-15 Middle 3.52E+05 5.07E+05 4.41E-15 Bottom 3.96E+05 5.70E+05 4.96E- 15 Average 4.63E-15 239 Corrected Average Including 235U, Pu, and -, fission corrections(d) 3.38E-15 Not es:

23 8 (a) Cobalt monitors were also measured but are not reported in this document. Bare U monitors' measurements were not reported in Reference A-2.

(b) Measured specific activities are indexed to a counting date of April 20, 1979.

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

(d) See Section A. 1.1.

WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 A-19 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 6 Cu (naC) 0Co Top No Sample Middle 6.44E+05 1.26E+06 1.92E-16 Bottom No Sample Average 1.92E-16 54 54 Fe (n,p) Mn Top 2.80E+06 5.58E+06 8.85E-15 Middle 2.43E+06 4.85E+06 7.69E- 15 Bottom 2.54E+06 5.07E+06 8.04E- 15 Average 8.20E-15 58Ni (n,p) 58Co Top 4.97E+07 6.91E+07 9.89E- 15 Middle 4.29E+07 5.96E+07 8.54E-15 Bottom 4.75E+07 6.61E+07 9.46E- 15 Average 9.30E-15 46Ti(n,p) 46 Sc Top 1.19E+06 1.70E+06 1.64E- 15 Middle 1.18E+06 1.68E+06 1.62E-15 Bottom 1.19E+06 1.69E+06 1.63E-15 Average 1.63E-15 238 U (n,f) 1 3 7 Cs Top 2.01E+06 9.84E+06 6.46E-14 Middle 2.01E+06 9.85E+06 6.47E- 14 Bottom 1.46E+06 7.16E+06 4.70E-14 Average 5.88E-14 238 137 U (n,f) Cs (Cd) Top 9.61E+05 4.70E+06 3.09E-14 Middle 9.07E+05 4.43E+06 2.91 E- 14 Bottom 8.49E+05 4.15E+06 2.73E- 14 Average 2.91E-14 235 239 Corrected Average Including U, pu, and y fission corrections(c) 1.99E-14 59 6 Co (nY) 0Co Top 3.50E+07 6.83E+07 3.93E-12 Middle 3.49E+07 6.81E+07 3.92E-12 Bottom 2.35E+07 4.59E+07 2.64E- 12 Average 3.50E-12 9 6

' Co (nY) 0Co (Cd) Top 4.78E+06 9.33E+06 5.37E-13 Middle 4.47E+06 8.73E+06 5.02E- 13 Bottom 4.33E+06 8.46E+06 4.87E-13 Average 5.09E-13 Notes:

(a) Measured specific activities are indexed to a counting date of March 19, 1992.

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

(c) See Section A.1.1 WCAP-17365-NP March 2011 Revision 0

A-20 Westinghouse Non-Proprietary Class 3 Table A-4c Measured Sensor Activities and Reaction Rates for Surveillance Capsule 2840 Measured Activity(a) Saturated Activity Reaction Rate(b)

Reaction Location (dps/g) (dps/g) (rps/atom) 63 Cu (na) 60Co Top 2.06E+05 3.52E+05 5.38E-17 Middle 2.01E+05 3.44E+05 5.25E-17 Bottom 2.03E+05 3.47E+05 5.30E- 17 Average 5.31E-17 54 54 Fe (n,p) Mn Top 1.04E+06 2.55E+06 4.04E-15 Middle 1.01E+06 2.47E+06 3.92E- 15 Bottom 9.55E+05 2.34E+06 3.71 E- 15 Average 3.89E-15 58 58 Ni (n,p) Co Top 2.15E+06 3.45E+07 4.94E- 15 Middle 1.91E+06 3.07E+07 4.39E-15 Bottom 1.89E+06 3.03E+07 4.34E- 15 Average 4.56E-15 46 Ti(n,p) 46 Sc Top 6.41E+04 7.01E+05 6.75E- 16 Middle 5.76E+04 6.30E+05 6.07E- 16 Bottom 6.00E+04 6.56E+05 6.32E- 16 Average 6.38E-16 238 137 U (n,f) Cs Top 1.56E+06 4.01E+06 2.63E-14 Middle 1.85E+06 4.76E+06 3.12E- 14 Bottom 1.51E+06 3.88E+06 2.55E-14 Average 2.77E-14 23 8 1 37 U (n,f) Cs (Cd) Top 2.04E+05 5.25E+05 3.45E-15 Middle 2.14E+05 5.50E+05 3.61 E- 15 Bottom 2.00E+05 5.14E+05 3.38E-15 Average 3.48E-15 Corrected Average Including 235U, 239Pu, and -, fission corrections(c) 2.32E-15 59 Co (n,y) 6°Co Top 1.48E+07 2.53E+07 1.46E-12 Middle 1.76E+07 3.01E+07 1.73E-12 Bottom 1.24E+07 2.12E+07 1.22E-12 Average 1.47E-12 59 60 Co (n,y) Co (Cd) Top 2.27E+06 3.88E+06 2.24E- 13 Middle 2.43E+06 4.16E+06 2.39E- 13 Bottom 2.13E+06 3.64E+06 2.10E- 13 Average 2.24E-13 Notes:

(a) Measured specific activities are indexed to a counting date of October 30, 2010.

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

(c) See SectionA.1.1 WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 A-21 Table A-5 Comparison of Measured, Calculated, and Best-Estimate Reaction Rates at the Surveillance Capsule Center Capsule 2630 Reaction Rate [rps/atoml Reaction Measured Calculated Best Estimate M/C BE/M 63 Cu(n,a) 60 Co 1.06E- 16 8.09E-17 1.OOE- 16 1.30 0.95 54 54 Fe(nP) Mn 8.24E- 15 7.40E- 15 8.40E- 15 1.11 1.02 58 Ni(n,p) 58Co 1.06E- 14 9.64E-15 1.09E-14 1.10 1.03 Capsule 970 Reaction Rate Irps/atoml Reaction Measured Calculated Best Estimate M/C BE/M 54 54 Fe(np) Mn 8.20E- 15 7.53E-15 7.79E- 15 1.09 0.95 58 58 Ni(n,p) Co 9.30E-15 9.82E- 15 9.81E-15 0.95 1.05 59 60 Co(n,y) Co 3.50E-12 2.67E-12 3.48E-12 1.31 1.00 59 Co(n,y)6 °Co (Cd) 5.09E- 13 5.22E-13 5.10E-13 0.97 1.00 Capsule 2840 Reaction Rate [rps/atom]

Reaction Measured Calculated Best Estimate M/C BE/M 63 60 Cu(na) Co 5.31E-17 4.63E-17 5.OOE- 17 1.15 0.94 54 54 Fe(n,p) Mn 3.89E- 15 3.96E-15 3.87E-15 0.98 0.99 58 58 Ni(n,p) Co 4.56E-15 5.14E-15 4.88E-15 0.89 1.07 59 60 Co(n,y) Co 1.47E- 12 1.28E-12 1.47E- 12 1.15 1.00 59 Co(n,y)f'°Co (Cd) 2.24E-13 2.53E-13 2.25E-13 0.89 1.01 Note:

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

WCAP- 17365-NP March 2011 Revision 0

A-22 Westinghouse Non-Proprietary Class 3 Table A-6 Comparison of Calculated and Best Estimate Exposure Rates at the Surveillance Capsule Center 2

(p(E > 1.0 MeV) In/cm -s]

Capsule ID Calculated Best Estimate Uncertainty (lc) BE/C 2630 5.57E+10 6.05E+10 6% 1.08 970 5.67E+10 5.76E+10 7% 1.01 2840 2.84E+10 2.63E+10 6% 0.92 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 Best-Estimate (BE) exposure rates.

Iron Atom Displacement Rate Idpa/s]

Capsule ID Calculated Best Estimate Uncertainty (Ic) BE/C 2630 7.96E- 11 8.70E- 11 6% 1.09 970 8.1OE-11 8.25E-11 6% 1.01 2840 4.08E-11 3.84E-11 6% 0.94 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 Best'Estimate (BE) exposure rates.

WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 A-23 Table A-7 Comparison of Measured/Calculated (MIC) Sensor Reaction Rate Ratios for Fast Neutron Threshold Reactions M/C Ratio Reaction Capsule 2630 Capsule 970 Capsule 2840 63 Cu(n,a) 60 Co 1.30 Rejected 1.15 54 54 Fe(n,p) Mn 1.11 1.09 0.98 58 58 Ni(n,p) Co 1.10 0.95 0.89 Average 1.17 1.02 1.01

% Standard Deviation 9.6 9.7 13.1 Note:

The overall average M/C ratio for the set of 24 sensor measurements is 1.07 with an associated standard deviation of 12.0%.

Table A-8 Comparison of Best-Estimate/Calculated (BE/C) Exposure Rate Ratios BE/C Ratio Capsule Location *(E > 1.0 MeV) dpa/s 2630 1.08 1.09 970 1.01 1.01 2840 0.92 0.94 Average 1.00 1.01

% Standard Deviation 8.0 7.4 WCAP- 17365-NP March 2011 Revision 0

A-24 Westinghouse Non-Proprietary 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 BMI-1280, Calvert Cliffs Unit No.1 Nuclear Plant Reactor Pressure Vessel Surveillance Program:Capsule 263', J. S. Perrin et al., December 1980.

A-3 BAW-2160, Analysis of the Calvert Cliffs Unit No.1 Reactor Vessel Surveillance Capsule Withdrawnfrom the 970 Location, A. L. Lowe et al., June 1993.

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 E 1018-09, 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-17365-NP March 2011 Revision 0

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

" "IXX" denotes Intermediate Shell Course Plate D-7206-3, Longitudinal Orientation

"2XX" denotes Intermediate Shell Course Plate D-7206-3, Transverse Orientation

"3XX" denotes Weld Material

"4XX" denotes Heat-Affected-Zone material Note that the instrumented Charpy data is for information only. The instrumented tup (striker) was not calibrated per ASTM E2298-09.

WCAP- 17365-NP March 2011 Revision 0

B-2 Westinghouse Non-Pronrietarv Class 33 Westinghouse Non-Pronrietarv Class 5000.00 4000.00 3000.00 2000.00 1000.00 A 0() 1. kfiký

&AA, PM& Il ALtaAM AXU-A& ghA krl..PjA-.A 0 -&AALp, ANnA. j, 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-i (ms) 164, 25 0 F 5000.00 4000.00

'7 3000.00 2000.00 1000.00 n nn - 1111fl S E9 Ik'j I~ IL *IIILJ JJ&t&..*A..LI.~t t M..*&.M fl-. '-..J' A~ 0404k.. .5% .7. A p a.. ~A. ,.. A 0.00 1 .00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms) 16B, 75 0 F WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 B-3 5000.00 4000.00

' 3000.00 2000.00 1000.00 k A ..........

0.0 0

'7.. [If Ii [ a r iA .A*L .. AAAw rI A, A MA., ft A -A

f. - 4 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms) 167, 90 0 F 5000.00 4000.00 a6 3000.00 2000.00 1000.00 n nf 0.00 l yA Ib h 1.00 Md40M4Aml AMP-2.00 m.rtAfaA, m.A.,,A.-J4~ AiAaA.,&n.. & A.MA ^.p 3.00 4.00 5.00 Aý La-L %A 6.00 Time-1 (ms) 15D, 100OF WCAP-17365-NP March 2011 Revision 0

B-4 Westinghouse Non-Pronrietarv Class 33 Westin2house Non-Pronrieta Class 5000.00+

4000.00 3000.00 o

2000.00 100 0.00.

n nn . I Ak4MhMLM&& A*pi- -a A,,..- - A--,A& A.AA 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-i (ms) 16A, 125 0 F

.la

_9 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms) 165, 150 0 F WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 B-5 4000.00 3000.00-2000.00-1000.00-KýAAMMA,.&uA .- & -,. -. ~*, ., A 0.00 1.00 2.00 3.00 4.00 500 6.0(

Time-1 (ms) 16D, 160 0 F 5000.00 4000.00 S 3000.00-2000.00 1000.00 nnn .F . .........

A~~~

L.qq.

0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms) 16C, 175°F WCAP-17365-NP March 2011 Revision 0

B-6 Westinghouse Non-Proprietary Class 3 4000.1 30001 6.00 Time-i (ms) 15J, 225 0 F 5000.00 4000.00 3000.00 2000.00 1000.00 0.00 ... ' * - -: - * -

0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms) 15E, 300OF WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 B-7 5000.00 4000.00

'7 3000.00 2000.00 1000.00 0.00. .. - -- " - - . .

0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms) 16E, 325°F 5000.00 4000.00 3000.00 2000.00 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms) 166, 350 0 F WCAP-17365-NP March 2011 Revision 0

A,,%

A.

A B-8 Westinghouse Non-ProprietaryA Class 3 mA_

JL L

5000.00- kýAA 4000.00 AAAk.h A-,

3000.00 6 2000.00 LAII 1000.00 10 II Illl nnn I

~tLh~i Lk~gAL.A.~...M LA.. AAA~A.I k -,

, a A IL~ .A. .A N-- ~k-.A.

A . A 1 .00 2.00 3.00 4.00 5.00 6.00 0.00 IILý Time-1 (ms) 241, 25°F 50030.00 40000.00 30030.00 20000.00 100 0.00 0A aokA-.p - , %L R AAxA - f. LAr4,^_A- A*A;.I 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms) 24D, 125°F WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 B-9

.Q 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms) 24K, 140OF 5000.00, 4000.00

.7 3000.00-2000.00 100 0.00~-JA1 - 3 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms) 24E, 150OF WCAP-17365-NP March 2011 Revision 0

B-10 Westinghouse Non-Proprietary Class 3 5000.00 4000.00 3000.00 2000.00 1000.004.AA4-A..LdAA,

. &mr . ,

0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ins) 252, 160 0 F 5000.00 4000.00 3000.00 2000.00 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms) 251, 1750 F WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 B-l1

'" 3000.00 2000.00 1000.00 0.00 ý h A &! 1A AAAmLA, - N4 A..&A 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms) 253, 185°F 5000.00 4000.00

'7 3000.00 2000.00 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms) 254, 195°F WCAP-17365-NP March 2011 Revision 0

B-12 Westinghouse Non-Pronrietarv Class 3 Westinghouse Non-Pronrietarv Class 3 5000.00 4000.00

. 3000.00" 2000.00" 1000.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms) 242, 200 0 F 5000.00-4000.00 3000.00 2000.00 1000.00 0.00 1.00 2.00 3.00 . 4.00 5.00 6.00 Time-1 (ms) 23U, 3000 F WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 B-13 3000 00 2000.00 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms) 23Y, 325 0 F 5000.00 4000.00 3000.00 2000.00 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-i (ms) 24J, 350 0 F WCAP-17365-NP March 2011 Revision 0

B- 14 Westinghouse Non-Proprietary Class 3 5000.00 4000.00" 3000.00-

-J 2000.00 1000.00"

,,JI IIJM4 4 LUfI. A A, Alit ,t(a.Lf4h.A.W..A At..&A,%,& A n..- A A-&, -. Ai 4L.L-- A. A 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms) 36M, -50F a

0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ins) 36D, 00F WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 B-15 Soo 0.00 400 0.00 300 0.00 400 0.00 100 0.00 Snnn ..IA/1 ,A/.A,, *thmmai Am=*Am ,

m*- . -A -

j - AL At* k* * =-*-**--*,

0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-i (ms) 36E, 150 F W'

00.00 3.00 6.00 Time-1 (ins) 371, 25 0 F WCAP-17365-NP March 2011 Revision 0

B- 16 Westinchouse Non-Pronrietarv Class 3 5O0

,n nnl 400 300 000 200 000 100 0.00 00 Anr~-.A-M .mm m .&*, .Aýe -0 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms) 36J, 35 0 F 5000.00 4000.00 3000.00 2000.00 1000.00 0.00 0.00 1.00 2.00 3.00 4,00 5.00 6.00 Time-1 (ms) 35U, 50WF March 2011 WCAP-17365-NP WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 B-17 Wetnhos onPoritr Cas3--1 so:.O:

4000.001

'7 3000.00 2000.00 1000.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms) 36L, 50°F 5000,00 4000.00-3O300000-3.00 6.OO Time-I (ms) 36K, 60 0 F WCAP-17365-NP March 2011 Revision 0

B-18 Westinghouse Non-Pronrietarv Class 3 5000.00 4000.00 3000.00-2000.00" 1000.00*

3.00 6.00 Time-i (ms) 36Y, 75 0 F 5000.00-4000.00

'7 3000,00" 2000,00-1000,00"

ý nn I 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms) 36U, 2500 F WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 B-19 Westinghouse Non-Proprietary Class 3 B- 19 5000.00-4000.00-

'73000.00-n 2000.00-1000.00 nnnl.

0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms) 36T, 2750 F 1

0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms) 36P, 300°F WCAP- 17365-NP March 2011 Revision 0

B-20 Westinghouse Non-Proprietary Class 3 5000.00 40030.00 30030.00 20030.00 10030.00

-o #.A A Al.A IJIA.A A& .. .. MA 0.00 1.00 2.00 3.00 4.00 5.00 8.00 Time-1 (ms) 463, -75°F 50030.00 400jUU.UU 30000.00 20000.00 10000.00 000-0.CO 1.00 A

2.00 3.00 4.00 5.00 6.00 Time-1 (ms) 46B, 250 F March 2011 WCAP-17365-NP WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 B-21 3000.00 200.00 1000 o00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms) 45L, 30 0 F 5000.00 4000.00

' 3000.00 2000.00 1000.00 o~oo . . .

4.

&.4,,z. L,, m A.... . j. .... .,.. . ,&A 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-i (ms) 45U, 400 F WCAP-17365-NP March 2011 Revision 0

B-22 Westinghouse Non-Pronrietarv Class 3 Westinahouse Non-Pronrietarv Class 3 5000.00-4000.00-3000,00-2000.00-1000.00-0.00 A ~. i i~i~A.

1 .00 Aft.

M..nAn.A A K.

A m-w. A2.00tt A.,-

x- - - .1 3.00 4.00 5.00 6.00 Time-1 (ms) 46E, 50°F 5000.00 4000.00 T 3000.00 2000.00 1000.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms) 464, 60°F WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 B-23 5000.00 4000.00 3000.00 2000.00 1000.00

^^^

n 4- , .. .1* ......

ALIALL A=.bA* * * *L*A * ..........

0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms) 46C, 75 0 F

.o 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms) 462, 125 0 F March 2011 WCAP-17365-NP March 2011 Revision 0

B-24 Westinghouse Non-Proprietary Class 3 5000.00-4000.00 3000.00-2000.00-1000.00-

.L * ....................

0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-i (ms) 46D, 2250 F G"

3 3.00 6.00 Time-i (ms) 461, 2500 F WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 B-25 5000.00 4000.00 3000.00 2000.00 1000.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms) 45M, 2750 F a

0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms) 45T, 300-F WCAP-17365-NP March 2011 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 2840 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 263' and 970 were also determined by applying this methodology to the Charpy Impact data reported in References C-2 through 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-1 Upper-Shelf Energy Values (ft-lb) Fixed in CVGRAPH Capsule Material Unirradiated 2630 970 2840 Intermediate Shell Plate D-7206-3 137.4 115.2 101.8 103.3 Longitudinal Orientation Intermediate Shell Plate D-7206-3 107.5 -- 84.0 87.7 Transverse Orientation Surveillance Program Weld Metal 151.8 118.5 105.5 108.0 (Heat # 33A277)

HAZ Material 128.3 93.1 81.0 113.7 SRM 135.5 109.4 ......

WCAP-17365-NP March 2011 Revision 0

C-2 Westinahouse Non-Pronrietarv 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 97', in References C-2 through C-4, were updated to CVGRAPH Version 5.3 in this analysis for consistency with the Capsule 2840 results.

C.1 REFERENCES C-1 ASTM El185-82, 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 BMI-1280, Final Report on Calvert Cliffs Unit No. 1 Nuclear Plant Reactor Pressure Vessel Surveillance Program: Capsule 263, December 1980.

C-4 BAW-2160, Analysis of Capsule 970 Baltimore Gas & Electric Company Calvert Cliffs Nuclear Power Plant Unit No. 1, June 1993.

WCAP- 17365-NP March 2011 Revision 0

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

WCAP-17365-NP March 2011 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 08/04/2010 08:25 AM Page I Coefficients of Curve I A = 69.8 B = 67.6 C = 79.45 TI = 59.85 D = O.OOE+00 Equation is A + B

ITanh((T-ToY(C+DT))l Upper Shelf Energy=- 37.4(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-Is=6.2 Deg F Temp@50 ft-Ibs=35.9 Deg F Plant: Calvert Cliffs I Material SA533BI Heat: C-4441 -1 Orientation: LT Capsule: UNIRR Fluence: n/cmA2 300 250 4'I200 150 0

ul z 00 -

100 50 0

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

-80. 00 6. 80 6. 09 .71

-40.00 12. 00 12. 33 33

-40.00 15.40 12. 33 3.07 00 22. 40 26. 73 -4. 33 00 28. 40 26. 73 1. 67

40. 00 50. 50 53. 26 -2.76

40. 00 75. 60 53. 26 22. 34

70. 00 59. 50 78. 39 - 18.89

70. 00 70. 50 78. 39 -7. 89 March 2011 WCAP-17365-NP March 2011 Revision 0

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

Page 2 Plant: Calvert Cliffs I Material: SA533BI Heat: C-4441-1 Orientation: LT Capsule: UNIRR Fluence: n/cm^2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

70. 00 89. 00 78. 39 10. 61

80. 00 67. 30 86. 59 - 19. 29

80. 00 96. 30 86. 59 9.71 120. 00 110. 00 123. 02 -3. 02 120. 00 118. 50 113. 02 5.48 160. 00 130. 75 127. 34 3.41 160. 00 142. 50 127. 34 15. 16 210. 00 137. 50 234. 38 3. 12 210. 00 139. 00 134. 38 4.62 Correlation Coefficient= .976 WCAP-17365-NP March 2011 Revision 0

C-6 Westinghouse Non-Proprietary Class 3 UNIRRADIATED (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 08/0412010 08:31 AM Page I Coefficients of Curve I A = 48.75 B = 47.75 C = 94.52 TO = 46.2 I) = &.00E+I11 Equation is A + B

ITanh((T-Toy(C+DT))l Upper Shelf L.E=96.S Lower Shelf LE= I.0(Fixed)

Temp.@LE. 35 mils=18.2 Deg F Plant: Calvert Cliffs I Material: SA533BI Beat C-4441-1 Orientation: LT Capsule: UNIRR Fluence: n/cmA2 200 150 E

C

.2 1.

100 50 0 , --

-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input LE. Computed LE D~fiffeential

-80. 00 5. 00 7.18 -2. 18

-40.00 13.00 14.27 -I.27

-40.00 16.00 14.27 1.73

.00 22. 00 27. 11 -5.11

.00 28. 00 27. 11 89

40. 00 46. 00 45. 63 37

40. 00 60. 00 45. 63 14. 37

70. 00 50. 00 60. 53 10. 53

70. 00 56. 00 60. 53 -4.53 March 2011 WCAP- 17365-NP WCAP-17365-NP March 2011 Revision 0

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

Page 2 Plant: Calvert Cliffs I Material: SA533B I Heal: C-4441- I Orientation: LT Capsule: UNIRR Fluence: n/cm^2 Charpy V-Notch Data Temperature Input L.E. Computed LE. Differential

70. 00 68. 00 60. 53 7. 47

80. 00 52. 00 65. 14 13. 14

80. 00 70. 00 65. 14 4. 86

- I.95 120. 00 78. 00 79. 95 120. OO 84. 00 79. 95 4. 05 160. O0 90.00 88. 62 1.38 160. 00 97. 00 88. 62 8. 38 210. 00 90. 00 93. 62 -3. 62 210. 00 91. 00 93. 62 -2.62 Conrelation Coetflcient= .975 WCAP-17365-NP March 2011 Revision 0

C-8 Westinghouse Non-Proprietary Class 3 UNIRRADIATED (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 08/04/2010 08:34 AM Page I Coefficients of Curve I A=50. B-=-5. C=78.67 TO=59.69 D-=-.00E+00 Equation is A t B

ITanh((T-ToY(C+DT))l Temperature at 50%Shear = 59.7 Plant: Calvert Cliffs I Material: SA533BI Heat: C-4441-I Orientation: LT Capsule: UNIRR Fluence: n/cmA2 I

(4

-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 Percent Shear Computed Percent Shear Differential

-80. 00 .00 2. 79 -2.79

-40. 00 10.00 7. 35 2.65

-40. 00 10. 00 7. 35 2.65

. 00 20. 00 17. 98 2.02

.00 20. 00 17. 98 2.02

40. 00 35. 00 37. 74 -2.'74 40, 00 40. 00 37. 74 2. 26

70. 00 50. 00 56. 51 -6.51

70. 00 55.00 56. 51 -I.51 WCAP-17365-NP March 2011 Revision 0

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

Page 2 Plant: Calvert Cliffs I Material: SA533B I Heat: C-4441-1 Orientation: LT Capsule: UNIRR Fluence: n/cm^2 Charpy V-Notch Data Temperatue Input Percent Shear Computed Percent Shear Differential

70. 00 60. 00 56. 51 3. 49

80. 00 55. 00 62. 63 -7. 63

80. 00 70. 00 62. 63 7. 37 120.00 80. 00 82. 25 -2.25 120. 00 80. 00 82. 25 -2. 25 160.00 100. 00 92. 76 7. 24 160. 00 200. 00 92. 76 7. 24 210.00 100.00 97. 86 2. 14 210.00 300.00 97. 86 2. 14 Correlation Coelficient = .992 WCAP-17365-NP March 2011 Revision 0

C-10 Westinghouse Non-Proprietary Class 3 UNIRRADIATED (TRANSVERSE ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 08/04/2010 09:13 AM Page 1 Coefficients of Curve I A = 54X85 B = 52.65 C = 76.64 TO = 61.81 = 0.QI0E+4N1 Equation is A + B

lTanh((T-ToY(C+DT))l Upper Shelf Energy=107.5(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs-226 Deg 1 TempS50 ft-lbs-54.8 Deg r Plant: Calvert Cliffs I Malerial: SA533BI Heat C-4441-1 Orientation: TL Capsule: UNIRR Fluence: n/cLA2 250 ___ ___ ___ __ __

2100 0

150 n'

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

-80. 00 3. 30 4. 74 -I.44

-40. 00 6. 75 9. 11 -2.36

-40. 00 II. 00 9. 11 1. 89

.00 19. 00 19. 70 -. 70

.00 24. 00 19. 70 4. 30 40.00 37. 30 40. 26 -2.96

40. 00 39. 00 40. 26 - I. 26

70. 00 58. 30 60. 46 -2. 16

70. 00 60. 00 60. 46 -. 46 March 2011 WCAP- 17365-NP 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-11 UNIRRADIATED (TRANSVERSE ORIENTATION)

Page 2 Plant: Calvert Cliffs I Material: SA533B I Heat: C-444 I- I Orientation: TL Capsule: UNIRR Fluence: n/cm^2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

70. 00 68. 50 60. 46 8. 04

80. 00 63. 00 67. 12 -4. 12

80. 00 70.00 67. 12 2. 88 120. 00 83. 50 88. 58 -5. 08

88. 58 - .18 120.00 88. 40

- 2. 96 160. 00 97. 00 99. 96 160.00 102. 50 99. 96 2.54 210. 00 107. 20 105.34 1. 86 210.00 118. 30 105. 34 12.96 Correlation Coe Ificient = .993 March 2011 WCAP- 17365-NP March 2011 Revision 0

C-12 Westinghouse Non-Proxietarv Class Class 33 C-I 2 Westinghouse Non-Proprietary UNIRRADIATED (TRANSVERSE ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 08A04/2010 09:15 AM Page I Coefficients of Curve I A =42.67 B=41.67C=95.65 TO=47.18 D=.OOE+00 Equation is A + B

lTanh((T-Toy(C+DT))l Upper Shelf L.E.=84.3 Lower Shelf LE= I.O(Fixed)

Temp.@L.E. 35 mils=29.4 Deg F Plant: Calvert Cliffs I Material: SA533B I Heat: C-4441 -1 Orientation: TL Capsule: UNIRR Fluence: n/cnA2 200 150

.2 1100 50 0 +-

-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed Lti Diiffe ntial

- 80. 00 6. 00 6. 45 -. 45

-40. 00 II. 00 12.59 -1.59

-40. 00 13. 00 12.59 .41

.00 25. 00 23. 63 1 37

.00 24. 00 23. 63 37

40. 00 42. 00 39. 55 2.45

40. 00 36. 00 39. 55 -3. 55

70. 00 51. 00 52. 43 -1.43

70. 00 52. 00 52. 43 .43 March 2011 I 7365-NP WCAP- 17365-NP March 2011 Revision 0

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

Page 2 Plant: Calvert Cliffs I Material: SA533BI Heat: C-4441-1 Orientation: TL Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed LE. Differential

70. 00 57. 00 52. 43 4. 57

80. 00 5 1. 00 56. 43 -5.43

80. 00 59. 00 56. 43 2. 57 120. 00 68. 00 69. 41 -I.41 120. 00 72. 00 69. 41 2. 59 160. 00 79. 00 77. 14 1. 86 160. 00 74. 00 77. 14 -3. 14 210. 00 80. 00 81. 66 - I. 66 210. 00 84. 00 81. 66 2. 34 Correlation Coefficient .995 WCAP-17365-NP March 2011 Revision 0

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

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 08/04/2010 09:17 AM Page I Coefficients of Curve I A =50. B=5(. C=80.39 T0=76.12 D=0.OE+O0 Equation is A + B

ITanh(T-To)y(C+DT))I Temperature at 50% Shear = 76.2 Plant: Calvert Cliffs I Material: SA533Bl Heat: C-4441-1 Orientation: T. Capsule: UNIRR Fluence: n/cmW2 125 1uuI __

I t:3

.qfl I _____________

25i _________________

0 PIh _____________ I

-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 Percent Shear Computed Percent Shear Differential

- 80. 00 .00 2. 02 -2.02

-40. 00 10.00 5. 27 4.73

-40. 00 10 00 5. 27 4.73

.00 20. 00 13.08 6.92

.00 15.00 13.08 1 92

40. 00 30. 00 28. 93 I. 07

70. 00 40. 00 46. 20 -6.20

70. 00 40. 00 46. 20 -6.20 WCAP- 17365-NP March 2011 Revision 0

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

Page 2 Plant: Calvert Cliffs I Material: SA533B I Heat: C-4441-1 Orientation: TL Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

70. 00 50. 00 46.20 3. 80

80. 00 50. 00 52. 41 -2. 41

80. 00 50. 00 52. 41 -2. 41 120. 00 75. 00 74. 87 13 120. 00 75. 00 74. 87 13 160. 00 100. 00 88. 96 II. 04 160. 00 90. 00 88. 96 I 04 210.00 100. 00 96.55 3 45 210. 00 100. 00 96. 55 3. 45 Conelation Coefficient = .992 WCAP-17365-NP March 2011 Revision 0

C- 16 Westinghouse Non-Pronrietarv Class 3 UNIRRADIATED (SURVEILLANCE WELD METAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 08/10/2010 02-55 PM Page I Coefficients of Curve I A = 77. B = 74.8 C = .03 TO = -14.78 D = O.OOE+00 Equation is A + B

ITanh((T-To)Y(C+DT))l Upper Shelf Energy= I51.8(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lb.---61.3 Deg F Temp@50 ft-lbs--38.5 Deg F Plant: Calven Cliffs I Material: SAW Heat: 33A277 Orientation: NA Capsule: UNIRR Fluence: nkinc2 300 250

150 w

200 150

-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

- 120. 00 4. 20 7. 32 -3. 12

-80. 00 to. 00 18.97 -8. 97

- 80. 00 15.30 18. 97 -3. 67

40. 00 38. 60 48. 57 9. 97

-40. 00 44. 50 48. 57 -4 07

-20. 00 74. 00 70.81 3. 19

-20. 00 91.80 70.81 20. 99

- 20. 00 100. 70 70.81 29. 89

.00 62. 00 94. 22 -32.22 WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-17 Westinghouse Non-Proprietary Class 3 C-i 7 UNIRRADIATED (SURVEILLANCE WELD METAL)

Page 2 Plant: Calvert Cliffs I Material: SAW Heat: 33A277 Orientation: NA Capsule: UNIRR Ruence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

. 00 85. 00 94. 22 -9. 22

40. 00 132. 80 129. 43 3. 37

40. 00 133.00 129. 43 3. 57

80. 00 140. 00 144. 76 -4.76

80. 00 142. 00 144.76 -2.76 120. 00 153. 90 149.75 4. 15 120. 00 156. 00 149.75 6. 25 160. 00 158. 40 151. 22 7. 18 160. 00 160. 60 151.22 9.38 Correlation Coefficient = .972 WCAP-1 7365-NP March 2011 Revision 0

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

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 08/10/2010 02:56 PM Page I Coeflicients of Curve I A = 50.32 B = 49.32 C = 60.89 TO = -27.5 D = O.OOE+00 Equation is A + B

ITanh((T-To)Y(C+DT))i Upper Shelf L.E.=99.6 Lower Shelf L E= I.0(Fixed)

Temp.@LE. 35 mils--47.0 Deg F Plant: Calvert Cliffs I Material: SAW Heat: 33A277 Orientation: NA Capsule: UNIRR Fluence: n/crmA2 200 150

.2q I 8o 50 L :

0

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

- 120. 00 8. 00 5. 51 2. 49

-80. 00 12. 00 15. 92 -3. 92

-80. 00 15.00 15.92 92

-40. 00 35. 00 40. 33 -5. 33

-40. 00 38. 00 40. 33 -2 33

-20. 00 60. 00 56. 36 3. 64

-20. 00 67. 00 56. 36 10. 64

- 20. 00 7 1. 00 56. 36 14. 64

.00 52. 00 71. 19 19. 19 March 2011 WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C- 19 Wetnhos onPoritr Cas3 -

UNIRRADIATED (SURVEILLANCE WELD METAL)

Page 2 Plant: Calvert Cliffs I Material: SAW Heat: 33A277 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperalue Input L.E. Computed Li. Differential

.00 63. 00 71. 19 -8. 19

40. 00 90. 00 89. 94 .06

40. 00 1to. O0 89. 94 10.06

80. 00 95. 00 96. 83 - I. 83

80. 00 97. 00 96. 83 .17 120. 00 98. 00 98. 86 86 120. 00 100. 00 98. 86 1.14 160. 00 101. 00 99. 43 1. 57 160. 00 97. 00 99. 43 -2.43 Cormlation Coefficient = .974 WCAP- 17365-NP March 2011 Revision 0

C-20 Westinehouse Non-Pronrietarv Class 3 UNIRRADIATED (SURVEILLANCE WELD METAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 08/I0/2010 02:58 PM Page I Coefficients of Curve I A = 50. B = 50. C = 61-S9 Tn -=-16.65 D = 0.00E+014 Equation is A + B

ITanh((T-To)(C+DT))I Temperature at 50% Shear = -16.6 Plant: Calvert Cliffs I Material: SAW Heat: 33A277 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 125 100 I

U) 75 50 25 0 - --1=4 iai -- -- {----

-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 Tempendure Input Pcrcent Shear Computed Percent Shear Mciflemntial

- 120I 00 .00 3. 37 -3.37

- 80. 00 10. 00 11. 33 - I.33 80M 00 10. 00 11.33 1.33

-40. 00 30. 00 31, 90 -I 90

-40. 00 35. 00 31. 90 3. 10

- 20 00 40. 00 47. 28 -7.28

- 20. 00 50. 00 47. 28 2.72

-20. 00 65. 00 47. 28 17.72

.00 60. 00 63. 19 -3. 19 WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-21 Westinghouse Non-Proprietary Class 3 C-2 1 UNIRRADIATED (SURVEILLANCE WELD METAL)

Page 2 Plant: Calvert Cliffs I Material: SAW Heat: 33A277 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

,00 50.00 63. 19 -13. 19

40. 00 85. 00 86. 29 - I. 29 40, 00 90. 00 86. 29 3.71

80. 0 100. 00 95. 84 4. 16 80, 00 100.00 95. 84 4. 16 120, 00 100.00 98. 83 1. 17 120. 00 100.00 98. 83 1. 17 160. 00 100. 00 99. 68 32 160. O0 100. 00 99. 68 32 Correlation Coefficient= .986 WCAP-17365-NP March 2011 Revision 0

C-22 Westinehouse Non-ProDrietarv Class 3 C-22 Westinghouse Non-Provrietarv Class 3 UNIRRADIATED (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 10/2712010 09:12 AM Page I Coefficients of Curve I A = 65.25 B = 63.05 C = 113.6 TO = -36.83 D = 0.OOE+

Eqution Ls A + B * [Tantl(T-ToY(C+DT))I Upper Sheif Energy= 128.3(Fixed) Lower Shelf Energy=2.2(Fixed)

Tcmp@30 fl-lbt--10&5 Deg F Temp@50 fi-lbs--64.8 Deg F Plant Calvct Cliffs I Material: SA533BI Heat: C-444 I-]

Onentatio NA Capsule: UNIRR Funce: Wcm'W2 250

- 200 __

12OO_ 0 0o0 I 0 0

~100 0 0

7Z0 50 0

O4 0

-300.0 .200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Tomperature In Dog F Charpy V-Notch Data Temperature input CVN Computed CVN Differenntial

- 15l 00 6 50 17 31 -10 Ri

- 120. 00 ,8. 20 25. 88 22. 32

- 80. 00 23. 00 42. 38 - 19. 38

-It0 00 50 n0 47 3I 7 67

-40. 00 36. 50 63. 49 - 26. 99

-40. 00 84. 00 63. 49 20. 51 00 92 50 85 01 -4 f)1 00 92. 50 85. 01 7. 49

40. 00 120. 00 102. 40 17. 50 March 2011 WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-23 Westinghouse Non-Proprietary Class 3 C-23 UNIRRADIATED (HEAT AFFECTED ZONE)

Page 2 Plant: Calvert Cliffs I Material: SA533BI Heat: C-4441-I Orientation: NA Capsule: UNIRR Fluence: n/cm^2 Charpy V-Notch Data Temperat*e Input CVN Computed CVN Differential

40. 00 130.00 102. 40 27. 60

60. 00 64. 00 108. 90 -44. 90

60. 00 66. 70 108. 90 -42. 20

60. 00 135.00 108. 90 26. 10

80. 00 91.00 114.01 -23. 01

80. 00 145. 50 114. 01 3 1. 49 120. 00 131.50 120. 80 10.70 120.00 133. 50 120.80 12.70 160.00 107. 50 124. 48 - 16. 98 160.00 125.30 124.48 .82 Correlation Coefficient =.829 WCAP-17365-NP March 2011 Revision 0

C-24 Westinhouse Non-Proprietarv Class 3 UNIRRA DIATED, (HEAT AFFECTED ZONE)

CVGRAPH 53 Hyperbolic Tangent Curve Printed on 08/03(2010 W0:.29 AM Pagc I Coefficienti of Curve I A=42471 B=4171 C= 115,11 TI=-4J532 D- OM@E+q0 Equation is A + B

lTanh(,T-ToY(C+IDr))

Upper Shelf LE.=84.4 Lower Shelf l..=l.OW~xed)

Temp.0Ii.F 35 mils=-79.8 Deg F Plant CavinCliffs I Marlial: SA333BI Haer C-4441-1 Orientation: NA Capsule: UNIRR Fluence: WcmA2 200

.1 E

100 0

@0 0

U' 0

0

-300.0 0.0 300.0 600.0 Temperature M Deg F Charpy V-Notch Data Twe~raluie Inpit I-P- Coimpued I I, Differenfial

- IS0. 03 9. 00 13. 09 - .09

- 120.03 31. 00 22. 28 8.72

'1 nO 34 04 II 04

- t0. 03) 40. 00 34. 94 5. 06

- 40. 03 46. 00 49. 29 - 3. 29

-40. W) 16. 00 49. 29 0. 7 1

.0) 64. 00 62. 20 1. 80 60 no 6,7 In.

40. 03 82. 00 7 1. 62 10. 38 March 2011 WCAP-1 7365-NP WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-25 UNIRRADIATED (HEAT AFFECTED ZONE)

Page 2 Plant: alnvetrw (-Iifr- I Mareril_ .A533R I I-lent: G-44.41- I Orientation: NA Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data fl"mpcrmnazrc Input LU. Computed L.E. Differential 40.00 84. 00 7 1. 62 12. 38 60.00 I 9. o0o 74 95 25. 95 60.00 54. 00 74. 95 20. 95 60.00 90. 00 74 95 15. 05 80.00 69. 77. 50 -S. 50 80.00 85. 00 77. 50 7. 50 120.00 86. oct 80. 81 5. 19 120.00 86. GO 80. 81 5. 19 160.00 79. Ob 82. 58 - 3. 58 160.00 86. DO 82. 58 3. 42 Correlal ion Coefficient = .892 WCAP- 17365-NP March 2011 Revision 0

C-26 Westinghouse Non-Proprietary Class 3 UNIRRADIATED (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 08/0312010 10:31 AM Page I Coefficients of Curve I A =50. B=50. C= 113.44 T0=-27-46 D=0.OOE+00 Equation is A + B * [Tanh((T-ToY(C+DT))j Temperature at 50% Shear = -27.3 Plant: Calvert Cliffs I Material: SA533BI Heat: C-4441-1 Orientation: NA Capsule: UNIRR Fluence: n/cniA2 125 100 0

75 V 0z 0

0 50 0

25 00 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 Percent Shear Computed PercentShear Differential

-150. 00 .00 10. 32 -10. 32

-120. 00 20. 00 16.34 3. 66

-80. 00 20. 00 28. 33 -8.33

-80. 00 50. 00 28.333 21. 67

-40. 00 35. 00 44. 45 -9.45

-40. 00 40. 00 44. 45 -4.45

.00 75. 00 61.83 13. 17

. 00 50. 00 61.83 -1 1. 83

40. 00 95. 00 76. 63 18. 37 WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-27 UNIRRADIATED (HEAT AFFECTED ZONE)

Page 2 Plant: Calve'rt C~iirr I Nlnu~ri,-:l: A533R1 Ili:

HeI A44.4- I Orientation: NA Capsule: UNIRR Rluecrw: I1/cmnA2 Charpy V-Notch Data Tempemkmre Input Perett Shear Cnmputed P*ment Shear Differ*ntial

40. 00 90. 01) 76. 63 13. 3-'

60. 00 55. 00 82. 35 -27. 35 6O. 00 60. 0O) 97, 35 - 22. 15

60. 00 98. 00 82. 35 15. 65

80. 00 65. 00 86. 91 -21. 91

80. 00 t00. 00 86.91 13. 09 120. 00 I00. 00 93.07 6. 93 120. 00 300. 00 93.07 6. 93 160. 00 100. 00 96.45 3. 55 160. 00 t00. 0') 96. 45 3. 55 Correlahon Coefficielnt = .b94 WCAP-17365-NP March 2011 Revision 0

C-28 Westinghouse Non-Pronrietarv Class Class 33 C-28 Westinghouse Non-Pronrietarv UNIRRADIATED (STANDARD REFERENCE MATERIAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 08104/2010 09:55 AM Page I Coefficients of Curve I A=W6& BR=66.65C=60.29 TV0=72.37 D=0.00EO+0O Equation is A + B

lTanh((T-To)(C+DT))l Upper Shelf Energy=I 35.5(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs-=32.2 Deg F Temp@50 ft-lbs=54.9 Deg F Plant: Calvert Cliffs I Material: SA533BI Heat: HSST-OIMY Orientation: LT Capsule: UNIRR Fluence: n/cmA2 300 250 200 150 w

z 100 so

-- --/

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 CYN Computed CVN Differential

-80. 00 3. 40 3. 05 35

-40. 00 5. 90 5. 33 57 00 8 00 13. 28 -5. 28 00 12.50 13. 28 -. 78

20. 00 36. 30 22. 15 14. 15

40. 00 31. 00 36. 15 -5. 15

40. 00 44. 80 36. 15 8. 65

60. 00 43. 00 55. 37 - 12.37

60. 00 47. 00 55. 37 -8. 37 WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-29 UNIRRADIATED (STANDARD REFERENCE MATERIAL)

Page 2 Plant: Calvert Cliffs I Material: SA533BI Heat: HSST-OIMY Orientation: LT Capsule: UNIRR Fluence: nJcmA2 Charpy V-Notch Data Tenipemtre Input CVN Computed CVN Di fferential

80. G0 80. 90 77. 25 3. 65

80. G0 86. 00 77.25 8.75 120. 00 112. 00 1 12.74 .74 120. 00 112. 20 12.74 -54 160. 00 130. 00 I28. 59 1 41 210. 00 135.550 134. 13 1. 37 Conelation Coefficient = .989 WCAP-17365-NP March 2011 Revision 0

C-30 Westinghouse Non-Proprietary Class 3 UNIRRADIATED (STANDARD REFERENCE MATERIAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 08/0W2010 09:57 AM Page I Coefficients of Curve I A =49.27 B=4&27C=72.48 TOt=61.22 D=O.OOE+O0 Equation is A + B

lTanh((r-To)1(C+DT))l Upper Shelf LE.=97.5 Lower Shelf LE= I.0(Fixed)

Temp.&LE. 35 mils=39.2 Deg F Plant: Calvert Cliffs I Material: SA533BI Heat: HSST-OIMY Orientation: LT Capsule: UNIRR Fluence: n/criA2 A3 E

.2 0 , 1-

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

- 80. 00 6. 00 2. 92 3. 08

-40. 00 6. 00 6. 57 -. 57 00 12. 00 16. 05 -4.05 00 20. 00 16. 05 3. 95

20. 00 32. 00 24. 44 7. 56

40. 00 31. 00 35. 53 -4.53

40. 00 40. 00 35. 53 4. 47

60. 00 40. 00 48. 46 -8.46

60. 00 43. 00 48. 46 -5. 46 March 2011 17365-NP WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-31 UNIRRADIATED (STANDARD REFERENCE MATERIAL)

Page 2 Plant: Calvert Cliff.q I Material- SA533B I Heai: HSST-0IMY Orientation: LT Capsule: UNIRR Fluence: n/cm^2 Charpy V-Notch Data Temperature Input L.E. Computed LE. Differential

80. 00 64. 00 61.51 2.49

80. 00 66. 00 61.51 4.49 120. 00 80. 00 81.62 - I. 62 120. 00 86. 00 81.62 4.38 160. 00 94. 00 91.61 2. 39 210. 00 92. 00 95. 98 -3.98 Correlation Coefficient = .988 WCAP-17365-NP March 2011 Revision 0

C-32 Westinghouse Non-Proprietary Class 3 UNIRRADIATED (STANDARD REFERENCE MATERIAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 08/OW2010 09:59 AM Page I Coefficients of Curve I A =50. B=5O. C=75.71 TO= 85.66 D=0.OOE+00 Equation is A + B

ITanh((T-ToY(C+DT))l Temperature at 50% Shear = 85.7 Plant: Calvert Cliffs I Matrial: SA533BI Heat: HSST-OIMY Orientation: LT Capsule: UNIRR Fluence: n/cmA2 12I or, . ___

75- -__

U) oI 25 nJ

]~Ioo Li0

-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 Pervent Shear Computed Percent Shear Differential

-80. 00 ,00 1. 24 - I. 24

-40. 00 10.00 3. 49 6. 51

00 15. 00 9. 43 5. 57

.00 15. 00 9. 43 5. 57

20. 00 20. 00 15.00 5.00

40. 00 20. 00 23. 04 -3.04

40. 00 25. 00 23. 04 1. 96

60. 00 30. 00 33. 67 -3. 67

60. 00 30. 00 33. 67 - 3. 67 WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-33 UNIRRADIATED (STANDARD REFERENCE MATERIAL)

Page 2 Plant: Calvert Cliffs I Material: SA533B I Heat: HSST-0O MY Orientation: LT Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

80. 00 45. 00 46. 27 - I. 27

80. 00 40. 00 46. 27 -6. 27 120. 00 75. 00 71. 24 3.76 120.00 75. 00 71. 24 3.76 160. 00 90. 00 87. 69 2.31 210. 00 I00. 00 96. 39 3.61 Correlation Coefficient = .991 WCAP-1 7365-NP March 2011 Revision 0

C-34 Westinghouse Non-Proprietary Class 3 CAPSULE 263- (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 08/04/2010 10:27 AM Page I Coefficients of Curve I A=58&7 B=56.5 C= 81.97 TO= 117.81 D=0.OOE+O0 Equation is A + B

ITanh((T-Toy(C+DT))l Upper Shelf Energy- I 15.2(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@030 ft-lbs=72.0 Deg F Temp@50 ft-lbs=105. I Deg F Plant: Calvert Cliffs I Material: SA5338 I Heal: C-4441 -1 Orientation: LT Capsule: 263 Fluence: n/cnVW2 300 250 4 200 150 w

z 100 so 0 v I- T - - 1 -

-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

. 00 8. 00 8. 24 -. 24

40. 00 20. 30 16.92 3. 38

60. 00 28. 70 24. 36 4. 34 78.00 33. 70 33. 23 .47 t00. 00 46. 00 46. 61 -. 61 I15. 00 50. 20 56. 76 -6.56 130. 00 69. 80 67.04 2.76 160. 00 78. 00 85.45 -7.45 185. 00 104. 00 96. 83 7. 17 WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-35 CAPSULE 2630 (LONGITUDINAL ORIENTATION)

Page 2 Plant: Calvert Cliffs I Material: SA533B I Heat: C-444 1-1 Orientation: LT Capsule: 263 Fluence: n/cm^2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 242. 00 120.50 109. 99 10, 51 300. 00 113. 00 113. 89 -. 89 300. 00 112. 00 113. 89 - I. 89 Correlation Coefficient= .992 March 2011 17365-NP WCAP- 17365-NP March 2011 Revision 0

C-36 Westin2house Non-Prot)rietarv Class 3 C-6WsingoueNo-roritryCas CAPSULE 2630 (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Prinled on 08A04/2010 10:30 AM Page I Coefficients of Curve I A = 47.22 B = 46.22 C = 99.01 TO = 109.05 D = 0.00E+00 Equation is A + B

ITanh((T-To)/(C+DT))I Upper Shelf L.E=93.4 Lower Shelf LE.=I.O(Fixed)

Temp.@LE. 35 mils=82.3 Deg F Plant: Calvert Cliffs I Material: SA533BI Heat: C-4441-1 Orientation: LT Capsule: 263 Fluence: nlcm"2 E

.9 a

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

.00 10. 40 10. 20 .20

40. 00 20. 80 19.36 1. 44

60. 00 29. 20 26. 03 3. 17

78. 00 30. 80 33. 19 -2. 39 100. 00 43. 00 43.01 -. 01 1 15.00 44. 80 50. 00 5. 20 130. 00 61. 80 56. 86 4.94 160. 00 63. 80 69. 1 1 -5.31 185. 00 8 1. 40 77. 05 4. 35 March 2011 WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-37 CAPSULE 2630 (LONGITUDINAL ORIENTATION)

Page 2 Plant: Calvert Cliffs I Material: SA533BI Heat: C-4441-1 Orientation: LT Capsule: 263 Fluence: n/cm^2 Charpy V-Notch Data Temperature Input L.E. Computed L. Differential 242. 00 92. 20 87. 55 4. 65 300. 00 92. 40 91.53 . 87 300. 00 86. 00 91.53 -5.53 Cortelation Coefficient = .991 March 2011 WCAP-1 7365-NP WCAP- 17365-NP March 2011 Revision 0

C-38 Westinghouse Non-Pronrietarv Class 3 WestinLyhouse Non-Pronrietarv Class 3 CAPSULE 263° (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 08/04/2010 10:32 AM Page I Coefficients of Curve I A =50. B=50. C=74.53 TO= 146.48 D=O.JOE+00 Equation is A + B *ITanh((T-ToY(C+DT))I Temperature at 50% Shear= 146.5 Plant: Calvert Cliffs I Material: SA533BI Heat: C-4441 -I Orientation: LT Capsule: 263 Fluence: /cnmA2 125 100 75 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 Dog F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

.00 5.00 I. 93 3. 07

40. 00 10.00 5.43 4. 57

60. 00 15. 00 8. 94 6.06

78. 00 10.00 13.73 -3. 73 100. 00 30. 00 22. 32 7. 68 115. 00 30. 00 30.05 05 130. 00 35. 00 39. 12 -4. 12 160. 00 45. 00 58.97 13. 97 185. 00 85. 00 73. 76 11 . 24 WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-39 Westinghouse Non-Proprietary Class 3 C-39 CAPSULE 2630 (LONGITUDINAL ORIENTATION)

Page 2 Plant: Calvert Cliffs I Material: SA533 BI Heat: C-444 I-1 Orientation: LT Capsule: 263 Fluence: n/cmn^2 Charpy V-Notch Data Temperature tnput Percent Shear Computed Percent Shear Differential 242. 00 IOO. 00 92. 85 7. 15 300. 00 I00. 00' 98. 40 1.60 300. 00 100. 00 98. 40 1.60 Correlation Coefficient = .994 March 2011 WCAP- 7365-NP WCAP- 117365-NP March 2011 Revision 0

C-40 Westinghouse Non-Pronrietarv Class 3 CAPSULE 2630 (SURVEILLANCE WELD METAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 10/27/2010 11:20AM Page I Coefficients of Curve I A= 0.S B= 58.15(C= 54.81 T41=3&18 D=0.01E-111 Equation is A + B

ITanh((T-ToY(C÷DT))I Upper Shelf F£argay= I ! 85(Fixed) Lower Shelf EnerVy=2.2(Fixed)

Temp,30 ft-!bs=- IOL9 Deg F Tcmp@.0 ft-lbs=23.O Deg F Plant: Calvert Cliffs I Material: SAW Heat 33A277 Orientation: NA Capsule: 263 Flunce: WcnmA2 300 250 42W 150 w 0 t 100 0

-No P.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 Te~peraume Input CVN Computed CVN Differeatial

-40. 00 22. 50 18.09 4. 41 S00 24. 40 35.81 - 11.41 10.00 56. 00 41.71 14. 29

20. 00 38. 20 48. 07 -9. 87

30. 00 60. 00 54.76 5. 24 30, 00 50. 00 54. 76 -4. 76

40. 00 68. 50 61.60 6. 90

78. 00 78. 80 85. 81 -7.01 115.00 105. 50 102. 17 3. 33 WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-41 Westinghouse Non-Proprietary Class 3 C-4 1 CAPSULE 263- (SURVEILLANCE WELD METAL)

Page 2 Plant: Calvert Cliffs I Material: SAW Heat: 33A277 Orientation: NA Capsule: 263 Fluence: nlcjmA2 Charpy V-Notch Data Temperature Input C.VN Computed CVN Diifferential 18S. 0o 120. 00 114. 96 5. 04 240. 00 117.80 117.51 29 300. 00 117.70 118.26 -. 56 Correlation Coefficient =.978 WCAP-17365-NP March 2011 Revision 0

C-42 C-42 Westinghouse Non-Pronrietarv Class 3 CAPSULE 2630 (SURVEILLANCE WELD METAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 10/27/2010 11:30 AM Page I Coefficients of Curve I A=45.86 B=44.86C=91.93 TO1=29.87 D=O.OOE+00 Equation is A + B * [Tanh((T-Toy(C+DT))I Upper Shelf LE.=90.7 Lower Shelf L E.=I .O(Fixed)

Temp.@LE. 35 mils=7.2 Deg F Plant: Calvert Cliffs I Material: SAW Heal: 33A277 Orientation: NA Capsule: 263 Fluence: ncrma2 200 E

.2 100 n i

-300.0 0.0 300.0 600.0 Temperature In Deg F Charpy V-Notch Data Temperature Input LE. Computed LE. Differeraial

-40. 00 18. 00 17. 10 - 90

.00 24. 40 31.77 -7.37

10. 00 47. 60 36.31 11. 29

20. 00 34. 20 41. 06 -6. 86

30. 00 47. 20 45. 92 1. 28 30.00 43. 60 45. 92 -2. 32

40. 00 56. 60 50. 78 5. 82

78. 00 62. 70 67.41 -4. 71 115.00 80. 20 78. 55 1. 65 WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-43 CAPSULE 263U (SURVEILLANCE WELD METAL)

Page 2 Plant: Calvert Cliffs I Material: SAW Heat: 33A277 Orientation: NA Capsule: 263 Fluence: n/cri02 Chalpy V-Notch Data Temperature Input LE. Computed LE. Differential 185. 00 90. 20 87. 74 2. 46 240 00 88. 60 89. 79 -1.19 300. 00 89. 60 90. 46 .86 Correlation Coeffici2nt =.979 WCAP- 17365-NP March 2011 Revision 0

C-44 Westinghouse Non-Pronrietarv Class 3 C-44 Westinghouse Non-Pronrietarv Class 3 CAPSULE 2630 (SURVEILLANCE WELD METAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 10/27/2010 11:31 AM Page I Coefficients of Curve I A = 50. B = 50. C = 76.67 TO = 41.74 D = 0.00E+00 Equation is A + B

ITanh((T-ToY(C+DT))I Temperature at 50% Shear = 41.8 Plant: Calvert Cliffs I Material: SAW Heat: 33A277 Orientation: NA Capsule: 263 Fluence: n/cniA2 125 100 L. 75 50 25 0 1 1 -=nq F- 4 -

-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 Temperatue Input Percent Shear Computed Percent Shear Differential

-40. 00 10. 00 10.60 -. 60

.00 25. 00 25. 18 .18

10. 00 40. 00 30.41 9. 59

20. 00 35. 00 36. 19 -1.19

30. 00 35. 00 42. 40 -7. 40

40. 00 55. 00 48. 86 6. 14

78. 00 75. 00 72. 03 2. 97 115. 00 85. 00 87. 11 -2. II WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-45 Westinghouse Non-Proprietary Class 3 C-45 CAPSULE 2630 (SURVEILLANCE WELD METAL)

Page 2 Plant: Calvert Cliffs I Material: SAW Heat: 33A277 Orientation: NA Capsule: 263 Fluence: n/cm^2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 185. 00 100. 00 97. 67 2. 33 240. 00 100.00 99. 44 56 300. 00 100.00 99. 88 .12 Correlation Coefficient = .989 WCAP-17365-NP March 2011 Revision 0

C-46 C-46 Westingyhouse Non-Pronrietarv Class 3 CAPSULE 2630 (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 08A)4W2010 11:03 AM Page I Coefficients of Curve I A=47.65 B-=45.45 C= 126. TO=-43.26 D= .LOOE+00 Equation is A + B * [Tanh((T-Toy(C+DT))l Upper Shelf Energy=93. I(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=-8.3 Deg F Temp@50 ft-Ibs=49.8 Deg F Plant: Calvert Cliffs I Material: SA533B I Heat: C-4441 -I Orientation: NA Capsule: 263 Fluence: nlcmA2 i0

~20 I0 ___ ____ ___ .4- 4 -I-pis 100 I

0 nC

-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 Comnputed CVN Differential

-40. 00 16.50 21.34 -4.84

.00 53. 00 32. 63 20. 37

20. 00 25. 80 39. 35 -13.55

30. 00 79. 00 42. 88 36. 12

30. 00 24. 00 42. 88 - 18. 88

40. 00 38. 00 46. 47 -8. 47

60. 00 45. 20 53. 65 -8.45

78. 00 53. 20 59, 87 -6. 67 116.00 68. 70 71.31 -2.61 WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-47 CAPSULE 263- (HEAT AFFECTED ZONE)

Page 2 Plant: Calvert Cliffs I Material: SA533BI Heat: C-444 I- I Orientation: NA Capsule: 263 Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 185. 00 98. 50 84. 43 14. 07 245. 00 99. 20 89. 55 9. 65 300. 00 87. 00 91. 58 -4. 58 Correlation Coefficient = .837 March 2011 WCAP-17365-NP WCAP-17365-NP March 2011 Revision 0

C-48 Westin2house Non-ProDrietarv Class 3 C-48 Westinghouse Non-Proorietarv Class 3 CAPSULE 2630 (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 08/04/2010 11:05 AM Page I Coefficients of Curve I A = 40.68 B = 39.68 C = 166.31 TO = 50.62 D = 0.NE+N00 Equation is A + B

ITanh((T-Toy(C+DT))l Upper Shelf L.E.=80.4 Lower Shelf LE.= I.O(Fixed)

Temp.@ILE 35 mils=267 Deg F Plant: Calved Cliffs I Material: SA533B I Hea: C-4441-1 Orientatiom: NA Capsule: 263 Fluence: rfcmn2 Al150

.2 3.100 50 0 r*

-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Trmpet:.tnr InPll I F Cnmpnted I F Dlifferntial

-40. 00 17.20 20. 97 -3.77

. 00 39. 40 28. 96 10. 44

20. 00 23. 40 33. 45 - 10. 05

30. 00 57. 80 35. 78 22. 02

30. 00 26. 00 35. 78 -9.78

40. 00 30. 40 38. 15 -7.75

60. 00 42. 20 42.91 -. 71

78. 00 45. 00 47. 15 -2. 15 116. 00 56. 00 55. 52 .48 WCAP-17365-NP March 2011 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 Cliffs I Material: SA533BI Heat: C-444 I- I Orientation: NA Capsule: 263 Fluence: n/cm^2 Charpy V-Notch Data Temperature Input L.E. Computed LF. Differential 185. 00 69. 00 67. 20 1. 80 245. 00 74. 60 73. 36 1. 24 300. 00 74. 80 76. 58 -1.78 Correlation Coefficient = .896 WCAP-17365-NP March 2011 Revision 0

C-50 WestinLyhouse Non-P. . . nrietarv

... ... . . .... r... ...

Class C l.....

3.

C. ......

st CAPSULE 263O (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 08/04/2010 11:12 AM Page I Coefficients of Curve I A = 50. B = 50. C = 133.69 TO = 57.2 D = 0.00E+00 Equation is A + B

ITanh((T-To)Y(C+DT))l Temperature at 50% Shear = 57.3 Plant: Calvert Cliffs I Material: SA533BI HeaL: C-4441 -1 Orientation: NA Capsule: 263 Fluence: n/cmi'2 1

100--

0 U) 75o 50 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 Percent Shear Comput Percent Shear Differential

-40. 00 20. 00 18.94 I 06

. 00 30. 00 29. 82 18

20. 00 40. 00 36. 43 3. 57

30. 00 50. 00 39. 96 10.04

30. 00 30. 00 39. 96 -9. 96

40. 00 40. 00 43. 60 -3. 60

60. 00 55. 00 5 1 . 05 3. 95

78. 00 55. 00 57. 72 -2.72 116. 00 65. 00 70. 67 -5. 67 March 2011 WCAP- 17365-NP WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-51 Westinghouse Non-Proprietary Class 3 C-5 1 CAPSULE 2630 (HEAT AFFECTED ZONE)

Page 2 Plant: Calvert Cliffs I Material: SA533BI Heal: C-4441-1 Orientation: NA Capsule: 263 Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 185. 00 90. 00 87. 12 2. 88 245. 00 100.00 94. 32 5. 68 300. 00 I00. 00 97. 42 2.58 Correlation Coefficient = .981 WCAP- 17365-NP March 2011 Revision 0

C-52 Westin2house Non-PrODrietarv Class 3 C-2Wsinroue onPrliear Cas CAPSULE 263- (STANDARD REFERENCE MATERIAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 08/04/2010 11:15 AM Page I Coefficients of Curve I A=55.8 B=53.6C=84.13 TO= 176.09 D= 0.O0E+00 Equation is A + B

ITanh((T-To)/(C+DT))I Upper Shelf Energy= 109.4(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs= 132.0 Deg F Temp@50 fl-lbs= 167.0 Deg F Plant: Calvert Cliffs I Material: SA533B I Heat: HSST-0I MY Orientation: LT Capsule: 263 Fluence: ncmnA2 300 250 200 150 w

z6100

-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 Nifferential

40. 00 6. 00 6. 26 26

78. 00 11.70 11. 69 01 118. 00 27. 10 23. 73 3 37 130. 00 32. 00 29. 06 2. 94 150. 00 40. 20 39. 69 . 51 170. 00 50. 20 51. 93 I .73 185. 00 59. 20 61. 46 -2. 26 210. 00 69. 10 76.31 -7. 21 245. 00 98. 70 91.96 6. 74 March 2011 17365-NP WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-53 Westinghouse Non-Proprietary Class 3 C-53 CAPSULE 2630 (STANDARD REFERENCE MATERIAL)

Page 2 Plant: Calvert Cliffs I Material: SA533BI Heat: HSST-01MY Orientation: LT Capsule: 263 Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 300. 00 112.90 104. 05 8. 85 366. 00 108.40 108. 24 . 16 366. 00 107.00 108. 24 -1. 24 Correlation Coeffcient =.994 WCAP- 17365-NP March 2011 Revision 0

C-54 WestinLyhouse Non-ProDrietarv Class 3 C-54 Westinehouse Non-Proorietarv Class 3 CAPSULE 2630 (STANDARD REFERENCE MATERIAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 08/04/2010 11:17 AM Page I Coefficients of Curve I A = 45.47 B = 44.47 C = 97.44 TO = 166.43 D =0.0E+O0 Equation is A + B

ITanh((T-Toy(C+DT))I Upper Shelf LE.=89.9 Lower Shelf LE=l.0(Fixed)

Temp.@LE. 35 mils.=143.1 Deg F Plant: Calvert Cliffs I Material: SA533B I Heat: HSST-01 MY Orientation: LT Capsule: 263 Fluence: n/cmA2 200 150 E

C I 100 50 i Q 0

0

-3001.0 0.0 300.0 600.0 Temperature in Dog F Charpy V-Notch Data Temperature Input L.E. Computed LE Diffeiential

40. 00 6. 20 7. 18 -. 98

78. 00 12. 60 13. 45 -. 85 118. 00 25. 80 25. 02 .78 130. 00 33. 00 29. 58 3.42 150. 00 38. 00 38. 04 -. 04 170. 00 46. 40 47. 10 -. 70 185. 00 51. 20 53. 84 2. 64 210. 00 62. 40 64. 12 -1.72 245. 00 76. 20 75.15 1. 05 WCAP- 17365-NP March 2011 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 I Material: SA533BI Heat: HSST-01MY Orientation: LT Capsule: 263 Fluence: n/cm^ 2 Charpy V-Notch Data Temperature Input L.E. Computed LE Differential 300. 00 91.20 84. 55 6. 65 366. 00 86. 00 88. 48 -2.48 366. 00 85. 80 88. 48 -2.68 Correlation Coefficient= .996 WCAP-17365-NP March 2011 Revision 0

C-56 Westinghouse Non-Proprietary Class 3 CAPSULE 2630 (STANDARD REFERENCE MATERIAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Prinled on 08/04/2010 11:18 AM Page I Coefficients of Curve I A = 50. B = 50. C = 8&93 TO = 193.64 D = O.00E+00 Equation is A + B * [Tanh((T-To)/(C+DT))I Temperature at 50% Shear-= 193.7 Plant: Calvert Cliffs I MateriaL SA533BI Heat HSST-OIMY Orientation: LT Capsule: 263 Fluence: n/cmA2 U) 0 -.- i -1=41 - + -

-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 Percent Shear Computed Percent Shear Differential

40. 00 5. 00 3. 06 1. 94

78. 00 5. 00 6.91 -1.91 118. 00 25. 00 15.43 9. 57 130. 00 20. 00 19. 29 .7 1 150. 00 35. 00 27. 26 7.74 170. 00 35. 00 37. 01 -2.01 185. 00 35. 00 45. 16 - 10. 16 210. 00 50. 00 59. 09 -9.09 245. 00 85. 00 76. 04 8. 96 WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-57 Westinghouse Non-Proprietary Class 3 C-57 CAPSULE 263- (STANDARD REFERENCE MATERIAL)

Page 2 Plant: Calvert Cliffs I Material: SA533BI Heal: HSST-01MY Orientation: LT Capsule: 263 Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 300. 00 100.00 91.62 8.38 366. 00 100.00 97. 97 2.03 366. 00 100. 00 97. 97 2.03 Correltion Coefficient= .984 WCAP-17365-NP March 2011 Revision 0

C-58 Westinehouse Non-Pronrietarv Class 3 CAPSULE 97- (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 08/04/2010 12:56 PM Page I Coefficients of Curve I A = 52. B = 49.8 C = 80.8 TO = 155.61 D = O.O0E+00 Equation is A + B

lTanh((T-To)y(C+DT))I Upper Shelf Energy=lOI.8(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs= 117.3 Deg F Temp@50 ft-lbs=152.4 Deg F Plant: Calvert Cliffs I Material: SA533BI Heat: C-4441 -1 Orientation: LT Capsule: 97 Fluence: icmW2 300 250 I200 p15 z

~100

______ 0 _____

50-I!

-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 CV N Computed CVN Differential

70. 00 13.50 12.88 .62

90. 00 12.50 18.60 -6. 10 100. 00 26. 50 22. 28 4.22 110. 00 22. 50 26. 54 -4.04 120. 00 34. 50 31. 37 3.13 130. 00 44. 00 36. 72 7. 28 150. 00 52. 00 48. 55 3.45 170. 00 51. 00 60. 78 -9. 78 200. 00 71.50 76. 90 -5. 40 March 2011 17365-NP WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-59 CAPSULE 970 (LONGITUDINAL ORIENTATION)

Page 2 Plant: Calvert Cliffs I Material: SA533BI Heal: C-4441-1 Orientation: LT Capsule: 97 Fluence: n/cmA2 Charpy V-Notch Data Temperature InputCVN Computed CVN Differential 240. 00 98. 50 90. 83 7. 67 280. 00 105.00 97. 42 7.58 550. 00 99. 00 101.79 -2.79 Correlation Coefficient= .984 WCAP-17365-NP March 2011 Revision 0

C-60 Westin2house Non-ProDrietarv Class 3 C-60 WestinEhouse Non-Proprietary Class 3 CAPSULE 970 (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/04/2010 01: 10 PM Page I Coefficients of Curve I A = 43.54 B = 42.54 C = 94.63 TO = 153.48 D = 0,OOE+00 Equation is A + B

lTanh((T-To)1(C+DT))l Upper Shelf LE.=86. I Lower Shelf LE= I.O(Fixed)

Temp.@LE. 35 mils=134.3 Deg F Plant: Calvert Cliffs I Material: SA533BI Heat: C-4441- I Orientation: LT Capsule: 97 Fluence: n/cmi2 200 150 E

.2 R ioo 0 0o,-

10 50 0

0

-300.0 0.0 300.0 600.0 Temperature in Dog F Charpy V-Notch Data Tempcratun! Input L.E. Compuwd Li Diffeential

70. 00 16.00 13. 44 2. 56

90. 00 12. 00 18. 63 -6. 63 100. 00 26. 00 21.76 4. 24 110. 00 23. 00 25. 26 -2. 26 120. 00 31. 00 29. 08 1.92 130. 00 39. 00 33. 19 5.81 150. 00 42. 00 41. 97 .03 170. 00 46. 00 50. 89 -4 89 200. 00 57. 00 62. 91 -5. 91 March 2011 WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-61 Westinghouse Non-Proprietary Class 3 C-6 1 CAPSULE 970 (LONGITUDINAL ORIENTATION)

Page 2 Plant: Calvert Cliffs I Material: SA533B 1 Heat: C-444 1-I Orientation: LT Capsule: 97 Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed LK Differential 240. 00 80. 00 74. 30 5.70 280. 00 86. 00 80. 58 5.442 550. 00 81. 00 86. 05 -5.05 Correlation Coefficient =.982 March 2011 WCAP-1 7365-NP WCAP-17365-NP March 2011 Revision 0

C-62 Westinghouse Non-Pronrietarv Class 3 CAPSULE 97- (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 08/04/2010 01:14 PM Page I Coefficients of Curve I A = 50. B = 50. C = 7&75 TO = 152.34 D =0.OOE+00 Equation is A + B

lTanh((T-Toy(C+DT))I Temperature at 50% Shear = 152.4 Plant: Calvert Cliffs I Material: SA533BI Heal: C-4441-1 Orientation: LT Capsule: 97 Fluence: n/crW2 125 100 75 U) 50 25 o0-

-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 Comnputed Percent Shear Differential

70. 00 0.00 II. 00 - I. 00 90, 00 15. 00 17. 03 -2. 03

20. 00 20. 93 93 100. 00 1O0. 00 20. 00 25. 44 -5 44 120. 00 40. 00 30. 55 9. 45 130 00 40. 00 36. 18 3. 82 150. 00 so. 00 48.51 I. 49 170. 00 55. 00 61. 03 -6. 03 200. 00 70. 00 77. 04 -7. 04 March 2011 WCAP- 17365-NP 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-63 Westinghouse Non-Proprietary Class 3 C-63 CAPSULE 970 (LONGITUDINAL ORIENTATION)

Page 2 Plant: Calvert Cliffs I Material: SA533B I Heat: C-4441-1 Orientation: LT Capsule: 97 Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Pen*nt Shear Computed Percent Shear Differential 240. 00 too. 00 90. 26 9.74 280. 00 100. 00 96. 24 3.76 550. 00 100. 00 100.00 .00 Correlation Coe ficient = .987 WCAP-17365-NP March 2011 Revision 0

C-64 Westinghouse Non-Pronrietarv Class 3 C-64Wes ingho... . .nPronr.... Cl......

CAPSULE 97- (TRANSVERSE ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 08/04/2010 01:17 PM Page I Coefficients of Curve I A = 43.1 B = 40.9 C = 85.11 TO = 160.32 D = 0.NE+00 Equation is A + B * [Tanh((T-Toy(C+DT))]

Upper Shelf Energy=84.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-Ibs= 132.1 Deg F Temp@50 ft-lbs= 174.9 Deg F Plant: Calvert Cliffs I Material: SA533BI Heal: C-4441-1 Orientation: TL Capsule: 97 Fluence: Wncm^2 300 250 4200 150 Lu z

100 0 0 0 50 --- - -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 Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

70. 00 16.50 10. 95 5. 55 100. 00 23. 00 18. 16 4. 84 130. 00 26. 50 29. 12 -2.62 140. 00 33. 50 33. 52 - . 02 150. 00 37. 00 38. 16 I. 16 160. 00 43. 00 42. 95 .05 180. 00 47. 50 52. 39 -4.89 200. 00 58. 00 60. 90 -2. 90 220. 00 67. 00 67. 85 -. 85 WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-65 CAPSULE 970 (TRANSVERSE ORIENTATION)

Page 2 Plant: Calvert Cliffs I Material: SA533BI Heat: C-4441-1 Orientation: TL Capsule: 97 Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 240. 00 83. 00 73. 10 9. 90 280. 00 85. 00 79. 37 5. 63 550. 00 90. 00 83. 99 6.01 Correlation Coefficient =.985 WCAP-17365-NP March 2011 Revision 0

C-66 UWestinghouse Non-Proprietary Class 3 CAPSULE 970 (TRANSVERSE ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 08/04/2010 01:19 PM Page I Coefficients of Curve I A =40.13 Bf=39.13C= 109.61 IV = 160.37 D = .OOE+00 Equation is A + B *lTanh((T-To)/(C+DT))I Upper Shelf LE=79.3 Lower Shelf LE= I.0(Fixed)

Temp.@LE. 35 mils=146.0 Deg F Plant: Calvert Cliffs I Material: SA533B I Heat: C-444 I-1 Orientation: TL Capsule: 97 Fluence: n/cm"2 200 150 f0 E

.9

&100 0o 0

-300.0 0.0 300.0 600.0 Temperature in Dog F Charpy V-Notch Data Tempenaure Input L.E. Computed LE. Diffewrntial

70. 00 16.00 13.62 2.38 100. 00 23. O0 20. 52 2.48

30. 00 28. 00 29. 56 - I 56

40. 00 32. 00 32. 94 94 150.00 36. 00 36. 44 44 160.00 41.00 40. 00 1.00

80. 00 45. 00 47. 06 -2.06 200. 00 49. 00 53. 69 -4. 69 220. 00 61. 00 59. 54 1. 46 March 2011 17365-NP WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-67 CAPSULE 970 (TRANSVERSE ORIENTATION)

Page 2 Plant: Calvert Cliffs I Material: SA533BI Heat: C-444 I- I Orientation: TL Capsule: 97 Fluence: n/cm^2 Charpy V-Notch Data TeMpCeiture Input L.E. Computed LE Differential 240. 00 70. 00 64. 43 5. 57 280. 00 72. 00 71.33 .67 550. 00 77. 00 79. 20 -2.20 CornLation Coefficient= .991 WCAP- 17365-NP March 2011 Revision 0

C-68 Westinghouse Non-Proprietary Class 3 CAPSULE 970 (TRANSVERSE ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 08/04/2010 01:21 PM Page I Coefficients of Curve I A-=50. B=50. C=90.39 TO-=161.94 D=O.00JE+J00 Equation is A + B

ITanh((T-ToY(C+DT))I Temperature at 50% Shear = 162.0 Plant: Calvert Cliffs I Material: SA533BI Heat: C-4441-1 Orientation: TL Capsule: 97 Fluence: n/cmnA2 125 100 In 75 50 25

-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 Percent Shear Computed Percent Shear Dif*erential

70. 00 10.00 11.57 - I. 57 100. 00 20. 00 20. 26 26 130. 00 40. 00 33. 04 6. 96 140. 00 40. 00 38. 10 1.90 150. 00 45. 00 43. 44 1. 56 160.00 50. 00 48. 93 1.07 180. 00 50. 00 59. 86 -9.86 200. 00 60. 00 69. 89 -9. 89 220. 00 80. 00 78. 32 1. 68 WCAP- 17365-NP March 2011 Revision 0

Westinhouse Non-Proprietary Class 3 C-69 Westinghouse Non-Proprietary Class 3 C-69 CAPSULE 970 (TRANSVERSE ORIENTATION)

Page 2 Plant: Calvert Cliffs I Material: SA533B I Heat: C-444 I-I Orientation: TL Capsule: 97 Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 240. 00 95. 00 84.91 10.09 280. 00 100. 00 93. 16 6. 84 550. 00 100. 00 99. 98 .02 Correlation Coefficient = .980 WCAP- 17365-NP March 2011 Revision 0

C-70 Westinehouse Non-Pronrietarv Class tin g ... .... . .... . . . rI et.....

.. ...... C l... s..

3 CAPSULE 970 (SURVEILLANCE WELD METAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 08/1012010 03:07 PM Page I Coefficients of Curve I A =5R5 B=51.65C=56.35 T0=71.28 D=O.OOE+00 Equation is A + B

ITanh((T-Toy(C+DT))I Upper Shelf Energy= 105.5(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-l-s=43.2 Deg F Temp@50 ft-lbs=67.I Deg F Plant: Calvert Cliffs I Material: SAW Heat: 33A277 Orientatim: NA Capsule: 97 huence: n/cmA2 300 250 200 150 z 0 100 0O 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 Dog F Charpy V-Notch Data Temperature Input CVN Computed CV N Differential

' 00 8. 00 9. 82 - I. 82

20. 00 24. 00 16. 60 7. 40

40. 00 28. 00 27. 80 . 20

50. 00 23. 50 35. 22 II .72

60. 00 37. 00 43. 64 -6. 64

70. 00 65. 50 52. 67 12. 83 100. 00 82. 50 78. 11 4. 39 I 30. 00 91.50 94. 07 -2. 57 160. 00 89. ou 101. 2 -12. 2.

WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-71 CAPSULE 970 (SURVEILLANCE WELD METAL)

Page 2 Plant: Calvert Cliffs I Material: SAW Heat: 33A277 Orientaticn: NA Capsule: 97 Fluence: n/cm^A2 Charpy V-Notch Data Tempcmture Input CVN Computed CVN Differential 200. 00 104. 00 104.44 -. 44 200. 00 107. 00 104.44 2.56 550. 00 1 13. 00 105. 50 7. 50 Correlation Coefficient = .980 WCAP-17365-NP March 2011 Revision 0

C-72 Westinghouse Non-Proprietary Class 3 CAPSULE 97- (SURVEILLANCE WELD METAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 08110/2010 03:08 PM Page I Coefficients of Curve I A = 42.33 B = 41.33 C = 61.31 TV = 67.33 D = 0.OOE+00 Equation is A + B

ITanh((T-To)1(C+DT))I Upper Shelf L.E.=83.7 Lower Shelf L.E= I.0(Fixed)

Temp.@LE. 35 mils=56.4 Deg F Plant: Calvert Cliffs I Material: SAW Heat: 33A277 Orientation: NA Capsule: 97 Fluence: n/crnA2 200 150 E

.2 8.100 50 0 . i i

-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperatue Input LE. Computed LK hifferential

. 00 5. 00 9. 27 -4.27

20. 00 23. 00 15. 54 7. 46

40. 00 25. 00 25. 04 - .04

50. 00 24. 00 30. 95 -6.95

60. 00 34. 00 37.41 -3.41

70. 00 51. 00 44. 13 6. 87 100. 00 64. 00 62. 48 1.52 130. 00 74. 00 74. 18 .18 160. 00 75. 00 79. 82 -4.82 WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-73 C-73 Westinghouse Non-Proprietary Class 3 CAPSULE 970 (SURVEILLANCE WELD METAL)

Page 2 Plant: Calvert Cliffs I Material: SAW Heat: 33A277 Orientation: NA Capsule: 97 Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed LK Differential 200. 00 82. 00 82. 58 .58 200. 00 82. 00 82. 58 .58 550. 00 88. 00 83. 66 4. 34 Correltion Coefficient =.988 WCAP-17365-NP March 2011 Revision 0

C-74 Westinghouse Non-Proprietary Class 3 CAPSULE 97- (SURVEILLANCE WELD METAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 08/10/2010 03:09 PM Page I Coefficients of Curve I A=50. B=50.C=71.15 TO=6&81 D=O.00E+00 Equation is A + B

ITanh((T-ToY(C+DT))I Temperature at 50% Shear = 68.9 Plant: Calvert Cliffs I Material: SAW Heat: 33A277 Orientation: NA Capsule: 97 Fluence: nfcmA2 125 100 I, 75

'I) 50 25 0

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

. 00 5.00 12.63 -7.63

20. 00 30. 00 20. 23 9.77

40. 00 30. 00 30. 79 .- 79

50. 00 35. 00 37. 08 -2. 08

60. 00 40. 00 43. 84 -3. 84

70. 00 55. 00 50. 84 4. 16 100.00 70. 00 70. 61 .61 130.00 85. 00 84.81 19 160. 00 90. 00 92. 85 -2.85 WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-75 Westinghouse Non-Proprietary Class 3 C-75 CAPSULE 970 (SURVEILLANCE WELD METAL)

Page 2 Plant: Calvert Cliffs I Material: SAW Heat: 33A277 Orientation: NA Capsule: 97 Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 200. 00 .100. 00 97. 56 2. 44 200. 00 100. O0 97. 56 2. 44 550. 00 100. 00 100. 00 .00 Correlation Coefficient = .991 WCAP-17365-NP March 2011 Revision 0

C-76 Westinghouse Non-Pronrietarv Class 3 Westinghouse Non-Pronrietarv Class 3 CAPSULE 970 (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 08/04/2010 01:31 PM Page I Coefficients of Curve I A = 41.6 B = 39.4 C = 133.71 TO = 15.92 D = O.OOE+00 Equation is A + B

ITanh((T-To)/(C+DT))l Upper Shelf Energy=81.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=-24.6 Deg F TempO50 ft-lbs=44.9 Deg F Plant: Calvert Cliffs I Material: SA533BI Heat: C-4441-1 Orientation: NA Capsule: 97 Fluence: Wcmn2 300 250 4200

,15 w 0 z

100 0 0 0

0 0

0

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 50-0 60.0 Temperature in Deg F Charpy V-Notch Data Temperature Inpt CVN Computed CVN DINferential

-40. 00 23. 00 26. 02 -3. 02

-20. 00 23. 00 31.26 -8. 26 00 51. 00 36. 93 14.07

20. 00 43. 50 42. 80 70

40. (oo 00 61.50 48. 62 12.88

70. 00 43. 50 56. 72 -13.22

80. 00 56. 00 59. 16 -3. 16 I00. 0000 42. 00 63. 56 -21. 56 130. 82. 00 68. 89 13.11 WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-77 Westinghouse Non-Proprietary Class 3 C-77 CAPSULE 970 (HEAT AFFECTED ZONE)

Page 2 Plant: Calvert Cliffs I Material: SA533BI Heat: C-4441-1 Orientation: NA Capsule: 97 Fluence: n/cmA2 Charpy V-Notch Data Temperture Input CVN Computed CVN Differential 160. 00 87. 00 72. 82 14.18 200. 00 75. 00 76. 28 - 1. 28 550. 00 129.50 80. 97 48. 53 Coalation Coefficient =.832 WCAP-17365-NP March 2011 Revision 0

C-78 CU Westinghouse Non-ProFrietarE Class 3 CAPSULE 970 (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 08/04/2010 01:33 PM Page I Coefficients of Curve I A = 40.17 B = 39.17 C = 192.9 TO = 77.15 D = O.OOE+00 Equation is A + B

ITanh((T-ToY(C+DT))I Upper Shelf L.E=79.3 Lower Shelf LE.= I.O(Fixed)

Temp.@LE. 35 mils=51.6 Deg F Plant: Calvert Cliffs I Material: SA533B!I Heat: C-4441-1 Orientation: NA Capsule: 97 Fluence: IWcmA2 2W0 150 in E

.2 3100 dl 50 00.0

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

-40. 00 16.00 18.93 -2. 93

-20. 00 16.00 21.96 -5. 96

.00 33. 00 25. 29 7.71

20. 00 32. 00 28. 89 3. II

40. 00 36. 00 32. 72 3. 28

70. 00 33. 00 38. 72 -5. 72

80. 00 41.00 40. 75 . 25 100. 00 34. 00 44. 79 - 10. 79 130.00 60.00 50. 64 9. 36 March 2011 WCAP-1 7365-NP WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-79 Westinghouse Non-Proprietary Class 3 C-79 CAPSULE 970 (HEAT AFFECTED ZONE)

Page 2 Plant: Calvert Cliffs I Material: SA533BI Heat: C-4441-1 Orientation: NA Capsule: 97 Fluence: n/cmA2 Charpy V-Notch Data Tempemture Input LE. Computed LE Differential 160. 00 67. 00 56. 03 10. 97 200. 00 51. 00 62. 21 - 11.2 1 550. 00 80. 00 78. 76 1. 24 Correlation Coefficient = .925 WCAP- 17365-NP March 2011 Revision 0

C-80 Westinghouse Non-Proprietary Class 3 CAPSULE 970 (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 08104/2010 01:36 PM Page I Coefficients of Curve I A=50J. 3=50. C= 151.14 TO=41.78 D=O.OOE+O Equation is A + B

lTanh((T-To)1(C+DT))I Temperature at 50% Shear = 41.8 Plant: Calvert Cliffs I Material: SA533BI iteat C-4441-1 Orientation: NA Capsule: 97 Fluence: n/cmA2 125 100 L.

to 75 0

0 0 50 0

25 0

00

-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

- 40. 00 20. 00 25.31 -5.31

-20. 00 30. 00 30. 63 63

.00 40. 00 36. 52 3.48 20.00 50. 00 42. 84 7. 16

40. 00 65. 00 49. 41 15.59

70. 00 40. 00 59. 23 -19.23

80. 00 70. 00 62. 38 7. 62 100.00 50. 00 68. 36 -18.36 130. 00 65. 00 76. 27 - I . 27 WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-81 Westinghouse Non-Proprietary Class 3 C-8 1 CAPSULE 970 (HEAT AFFECTED ZONE)

Page 2 Plant: Calvert Cliffs I Material: SA533B I Heat: C-4441 -1 Orientation: NA Capsule: 97 Fluence: n/cmA2 Charpy V-Notch Data Tempemiun: Input Percent Shear Computed Percent Shear Ditterential 160. 00 100. 00 82. 70 17.30 200. 00 tOO. 00 89. 03 10. 97 550. 00 100. 00 99. 88 .12 Correlation Coefficient= .898 March 2011 I 7365-NP WCAP- 17365-NP March 2011 Revision 0

(".R9 lea KTnn..Drnnriston, C'I ~ 2 r-R2 W..*;. F2h-.. XT-.-P- L Am =Z ri- 11 CAPSULE 2840 (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/17/2011 0751 AM Page 1 Coefficients of Curve I A = 52.75 B = 50,56 U = 99.35 TIl = 152189 D = O,00E+-1)

Equation is A + B *ITanh((T-ToY(C+DT))]

Upper Shelf Energy= 103.3(Fixed) Lower Shelf Encrgy-=2.2(Fixed)

Temp@30 ft-lbs=104.8 Deg F Tenm, 50 ft-lbs 147.5 Deg F Plant Calvert Cliffs I Material: SA533BI Heat: C-4441-1 Orientation: LT Capsule: 284 Fluenoe: n/cmA2 300 250 4200 150 100 so 0 n

-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 Differeatial

25. 00 I0. 00 9. 36 .64 75.00 23. 00 19. 64 3. 36 90.00 37. 00 21. 43 12.57 100.00 33. 00 28. 12 4. 88 125.00 36. 00 38. 92 -2. 92 150.00 12. 00 51. 28 9. 28 160. 00 50. 00 56. 36 -6.36 175.00 55. 00 63. 82 -8.82 225. 00 101. 00 84. 11 16. 89 March2011 WCAP- 17365-NP WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-83 CAPSULE 2840 (LONGITUDINAL ORIENTATION)

Page 2 Plant: Calven Cliffs I Material: SA533B I Heat: C-4441- I Orientation: LT Capsule: 284 Fluence: n/cm^2 Charpy V-Notch Data Temperature Input CVM Computed CVN Differential 300 .0 0 106, no0 9. 33 7, 67 325.00 103.00 100.23 2. 77 350,00 103.00 101.42 1.58 Correlation Coefficient =.974 WCAP-17365-NP March 2011 Revision 0

C-84 Westinghouse Non-Proprietarv Class 3 CAPSULE 284- (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0V 17/2011 07:55 AM Page I Coefficients of Curve I A=44.&5 B=43.85C= 121.84 TO=150.31 D=0O.OOE400 Equation is A + B * [Tanht(T-Toy(C+DT))I Upper Shclf LE.=88.7 Lower Shclf LE=l .=(Fixcd)

Temnp.@L.E. 35 ,uils,-122.5 Deg F Plant: Calvert Cliffs I Material: SA533BI teat: C-4441-1 Orientation: LT Capsule: 284 Humnce: Wci"2 200 150 E

J I

so 0 J-

-300.0 0.0 300.0 600.0 Temperature In Deg F Charpy V-Notch Data Temperauwe Input LE. Computed LE. Dfifferential 25.00 11.00 10. 94 .06

75. 00 22. 00 20. 74 1.26

90. 00 31. 00 24. 76 6. 24 I00. 00 30. 00 27. 71 2.29 125. 00 35. 00 35. 87 87

50. 00 40. 00 44. 74 -4. 74 160. 00 42. 00 48. 33 -6. 33 175. 00 48. 00 53. 62 - 5. 62 225. 00 83. 00 68. 80 14. 20 WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-85 Westinghouse Non-Proprietary Class 3 C-85 CAPSULE 2840 (LONGITUDINAL ORIENTATION)

Page 2 Plant: Calvert Cliffs I Material: SA533BI Heal: C-4441 I-Orientation: LT Capsule: 284 Fluence: n/cmn^2 Charpy V-Notch Data Temperalure Input LE. Computed LE Differential 300. 00 83. 00 81.78 1. 22 325.00 83. 00 83. 98 -. 98 350.00 81.00 85.51 -4.51 Correlation Coefficient = .976 WCAP-17365-NP March 2011 Revision 0

C-86 C-86 Westinghouse Non-P Westinghouse Non-Pronrietarv Class 33 nrietarv Class CAPSULE 284u (LONGITUDINAL ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/17/2011 017:58 AM Page I Coefficients of Curve I A = R B = 50. C = 6081 TO = 159.75 D =O.0OE+O0 FrIpalion i% A + R

ITanh((T-Toy(f"+DT))l Tempcrature at 50% Shear = 159.8 Plant: Calvert Cliffs I Material: SA533B I Peat: C 4441 1 Orientation: LT Capsule: 284 Fluence: nlcn"2 125 100 I

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 Temerature Input Percent Shear Computed Percent Shear Difftrential

25. 00 5. 00 I. 18 3. 82

75. 00 10. 00 5. 80 4. 20

90. 00 is. 00 9. 16 5. 84 100.00 15. 00 12.29 2. 71 125.00 20. 00 24. 18 -4. 18 150.00 40. 00 42. 05 -2. 05 160.00 50. 00 50.21 -. 21 175. 00 60. 00 62. 29 -2. 29 225. 00 98. 00 89. 53 8. 47 WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-87 Westinghouse Non-Proprietary Class 3 C-87 CAPSULE 2840 (LONGITUDINAL ORIENTATION)

Page 2 Plant: Calvert Cliffs I Material: SA533B I Heat: C-444 I-I Orientation: LT Capsule: 284 Fluence: nicrnA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 300. 00 00. 00 99. 02 .98 325.00 100. 00 99. 57 .43 350. 00 100. 00 99 91 .19 Correlation Coefficient = .996 WCAP-17365-NP March 2011 Revision 0

C-88 Westinjahouse Non-Prot)rietarv Class 3 C-88 Westinghouse Non-Prorrietarv Class 3 CAPSULE 284- (TRANSVERSE ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/1712011 08:11 AM Page I Coefficients of Curve I A - 44.95 B - 42.75 C - 6&72 TO = 174." D - O.00E+40 Equation is A + B * [lanh((T-Toy(C+DT))j Upper Selt Energy=8l./(Ftxed) Lower Shelf Energy=2.2(Ftxed)

Temp@30 ft-lbs= 149.6 Deg F Temp@50 ft-lbs=182.9 Deg F Plant: Calvert Cliffs I Material: SA533B1 Heal: C-4441-1 Orictitfioo: TL Capsule; 284 FRuam=: iWCki12 300 250 4 200 IL 150 100 0-50 0O 00 0

-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 Temperatur Inpul CVN Cemputed CVN Differential

25. 00 9. 00 3 28 5.72 125.00 23. 00 18.51 4.49 140.00 30. 00 25. 05 4.95 1.50. 00 29. 00 30. 24 -1.24 160. 00 31. 00 35, 97 -4.97 175.00 39. 00 45. 16 -6. 16 185. 00 47. 00 51.33 -4.33 195.00 63,00 57, 25 5.75 200.00 04.00 60. 04 3.90 March 2011 WCAP- 17365-NP 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-89 Westinghouse Non-Proprietary Class 3 C-89 CAPSULE 2840 (TRANSVERSE ORIENTATION)

Page 2 Plant: Calvert Cliffs I Material: SA533B I Heat: C-4441-1 Orientation: TL Capsule: 284 Fluence: n/cmA2 Charpy V-Notch Data Temiperature Input CVN Computed CVN Differential 300. 00 90. 00 85. 53 4. 47 325. 00 92. 00 86. 64 5. 36 350. 00 81. 00 87. 18 -6. 18 Correlation Coefficient =.983 WCAP-17365-NP March 2011 Revision 0

C-90 Westin2house Non-Pronrietarv Class 3 C-90 Westinghouse Non-Pronrietarv Class 3 CAPSULE 2840 (TRANSVERSE ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/17/2011 08:13 AM Page I Coefficients of Curve I A = 38.57 K = 37.57 C = 86.47 '11) = 169.92 D = 0.00E+PU Equdtion i3 A + B

ITanh((T-ToY(C+DTi0 Upper Shelf LF.-76. I Lower Shelf L-- I .O4Fixed)

Temp.@LE. 35 nils=161.7 Deg F Plant: Calvert Cliffs I Martial: SA533B1 Heat: C-4441-1 Orientation: TL Capsule: 284 Fluence: n/ct?2 200 150 E

C

.9 1100 o

0 v

5o 0

Co 0

01

-3IX .0 0.0 300.0 600.0 Tamperature In Dog F Charpy V-Notch Data Temperature Input I.E. Computed LE. Differential

25. 00 II. 00 3. 54 7. 46 125. 00 22. 00 20. 63 1.37 140.00 29. 00 26.06 2. 94 150. 00 30. 00 30. 06 -. 06 160.00 26. 00 34. 27 8. 27 75.00 39. 00 M0,77 1.77 85.00 44. 00 45. 05 I.05 195.00 51.00 49. 16 1. 84 200. 00 56. 00 51. 13 1. 87 WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-91 CAPSULE 2840 (TRANSVERSE ORIENTATION)

Page 2 Plani- Calvert Cliffs I Material- A533R1 Heat- C-4441-I Orientation: TL Capsule: 284 Fluence: n/cn^A2 Charpy V-Notch Data Temperature Input LE. Computed LE. Differential 300, 00 74. 00 72. 60 1. 40 325. 00 79. 00 74. 11 4. 89 350. O0 68. 00 74. 98 - 6. 98 Correlation Coefficient =.9/9 WCAP-17365-NP March 2011 Revision 0

C-92 Westinghouse Non-Proprietary Class 3 CAPSULE 284- (TRANSVERSE ORIENTATION)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/17/2011 08:15 AM Page I Coefficient%of Curve I A=50. B=50. C=44.93 TV= 175.63 D=0.OOE+00 Equation is A + B

ITanh%('-ToY'(C+DT))l Tempcraktfu at 50% Shear = 175.7 Plant: Calvert Cliffs I Mateial: SA533BI Heat: C-444I-I Orientation: TL Cap"le: 284 Fltuenc: n/cmn^2 125 100 I

(0) 75

0. 50 25 0 l- - 4 -

-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 Percent Shear Computed Percent Shear Differential

25. 00 5. 00 .12 4. 88 125. 00 15.00 9. 50 5. 50 140. 00 30. 00 16.99 13.01 150. 00 25. 00 24.21 .79 160. 00 25. 00 33. 27 - 8. 27 175.00 35. 00 49. 30 - 14. 30 185. 00 60. 00 60. 28 -. 28 195. 00 80. 00 70.31 9. 69 200. 00 80. 00 74. 74 5. 26 March 2011 WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-93 CAPSULE 284- (TRANSVERSE ORIENTATION)

Page 2 Plant: Calvert Cliffs I Material: SA533B I Heat: C-4441-1 Orientation: TL Capsule: 284 Fluence: nlcm^2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 300.00 100.00 99.61 .39 325.00 100. 00 99. 87 .13 350.00 100. 00 99. 96 .04 Correlation Coefficient =.979 WCAP-17365-NP March 2011 Revision 0

C-94 Westin2house Non-Pronrietarv Class 3 CAPSULE 2840 (SURVEILLANCE WELD METAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/17/20110 8:19 AM Page I Coefficients of Curve I A = 55.1 B = 52.9 C = 14.9 11 = 7U.79 D =U.WOE+-1 Equation is A + B + [Trah((T-Toy(C-DT))l Upper Shelf Emergy= 108.0(Fixed) Lower Shelf Evergy=2.2(Fixed)

Teary@30 fi-lbs= 16.7 Deg F Tenp@50 ft-1br--W.7 Deg F Plant: Calvert Cliffs I Material: SAW Heat 33A277 Orientation: NA Capsule: 284 Fluence: nkmA2 300 4 200 150 wu z 1 -- -__

0 so n

n0

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

-50. 00 8. 00 11.83 -3. 93

.00 28. 00 24.01 3. 99

15. 00 i1. 00 29. 37 11. 63 25.00 36. 00 33. 39 2.61

35. 00 36. 00 37.73 -I.73

50. 00 16. 00 14.76 29. 76 50.00 53. 00 44. 76 8. 24

60. 00 5 1. 00 49. 68 1. 32

75. 00 64. 00 57. 22 6.78 WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-95 Westinghouse Non-Proprietary Class 3 C-95 CAPSULE 2840 (SURVEILLANCE WELD METAL)

Page 2 Plant: Calvert Cliffs I Material: SAW Heal: 33A277 Orientation: NA Capsule: 284 Fluence: ricm"n2 Charpy V-Notch Data Temperature Inut CVN Computed CVN Differential 2507 00 III. 00 1 04. 63 6. 37 275. 00 106.00 105. 38 12 300. 00 107.00 106.67 33 Correlation Coefficient =.9:8 WCAP-17365-NP March 2011 Revision 0

C-96 Westin2house Non-Pronrietarv Class 3 C-96 Westint~house Non-Proorietarv Class 3 CAPSULE 2840 (SURVEILLANCE WELD METAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01117/2011 08:21 AM Page I Coefficients of Curve I A = 43.45 B = 42.45 C = 132.17 TO= 66.32 D =0.0OE+410 Equation is A + B * [Tanh(&T-Toy(C+DT))l Upper Shelf L E=85.9 Lower Shelf LE.=I .O(Fixed)

Temp.@LE. 35 mils--39.7 Deg F Plant: Calvert Cliffs I Material: SAW Heal: 33A277 MA Orientation: NA Capsule: 284 Fluence: n/cmA2 150 E

C

.2 100 0

0 JCft ____I__________

7 0 0 "i -. + I 0

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

- 50. 00 II. 00 13. 46 -2. 46

00 27. 00 23. 77 3. 23 15.00 34. 00 27. 75 6. 25

25. 00 29. 00 30. 59 -1.59

35. 00 32. 00 33. 57 -I.57

50. 00 19. 00 38. 23 - 19. 23

50. 00 47. 00 38. 23 8. 77

60. 00 45. 00 41.42 3. 58

75. 00 49. 00 46. 23 2. 77 WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-97 Westinghouse Non-Proprietary Class 3 C-97 CAPSULE 2840 (SURVEILLANCE WELD METAL)

Page 2 Plant: Calvert Cliffs I Material: SAW Heat: 33A277 Orientation: NA Capsule: 284 Fluence: n/cmA2 Charpy V-Notch Data TemperatUre Input LE. Computed LE. Differential 250. 00 85. 00 80. 93 4. 07 275. 10 77. 00 82. 43 -5.43 300. 00 85. 00 83. 49 I.5I CulldatiuJi Ctxfficielit =.958 WCAP-17365-NP March 2011 Revision 0

C-98 Westinghouse Non-Proprietary Class 3 CAPSULE 284- (SURVEILLANCE WELD METAL)

CVGRAPII 5.3 Hyperbolic Tangent Curve Printed on 01/17/2011 08:22 AM Page I Coefficients of Curve I A =50. B=50.C=81-,3 10=62.84 D= 0.W0E-lNP Equation is A + B

ITanM(T-ToY(C+Err))l Temperature at 50% Shear- 62.9 Plant: Calvert Cliffs I Material: SAW Heat: 33A277 Orientation: NA Capsule 284 Ruenw: n/cr2 125 100 U 75 0

I 50 25 01-

-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 Temperatwe Input Percenl Shear Compited Percent Shear Differential

- 50. 00 10. 00 5. 87 4.13

, 00 20. 00 17. 58 2. 42 ls 00 A5. 00 23. 57 1 1, 43

25. 00 25. 00 28. 28 -3. 28

35. 00 30. 00 33. 52 -3. 52

50. 00 25. 00 42. 17 - 17. 17

50. 00 40. 00 42. 17 -2. 17

60. 00 50. 00 48. 25 1. 75

75. 00 70. 00 57. 42 12.58 WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-99 CAPSULE 284- (SURVEILLANCE WELD METAL)

Page 2 PLint: Calvert Cliftf I Material' RAW Heat- 33A277 Orientation: NA Capsule: 284 Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percem Shear Computed Percent Shear Differential

99. 01 99 250 00 10ll). 0 275. 00 100. 00 99. 46 .54 300. 00 o00.00 99.71 .29 Correlation Cooefficient =.S1/4 WCAP-17365-NP March 2011 Revision 0

C-1O00 0Westinghouse Non-Proprietary Class 3 CAPSULE 284- (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0/ 17/2011 08:25 AM Page I Coefficients of Curve I A = 57.95 B = 55.75 C = 131.23 TV = 101.06 D= 0.OOE+00 Equation is A + B * [Tanh(lT-To)Y(C+DT))j Uppe Shelf ElCEi = I13.7(Fixud) Luowe Slwlf &aigy=2.2(Fixvd)

Tcmp@30 fl-lbs=28.8 Dcg F Tcmp@50 ft-lbs=82.3 Deg F Plant: Calvert Cliffs I Material: SA5338 Heat: C-4441-I Orientation: NA Capsule: 284 Fluence: rlcnmA2 300 250 4200 150 w 0 0 z

~100 0

0o 50 000 n

vi

-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 Tempergure Input CVN Computed CVN Differential

-75. 00 12. 00 9. 33 2 67

25. 00 28. 00 28. 83 83 30.00 16. 00 30. 40 I5. 60

40. 00 54. 00 33. 73 20. 27

50. 00 25. 00 37, 29 12 29 60.00 32. 00 41. 05 - 9. 05 75.00 30. 00 47. 02 17. 02 125.00 73. 00 68.01 4, 99 225. 00 88. 00 99. 05 -II 05 WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-101 CAPSULE 284- (HEAT AFFECTED ZONE)

Page 2 Plant: Calvert Cliffs I Material: SA533BI Heat: C-4441-1 Orientation: NA Capsule: 284 Fluence: n/cma^2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 250. 00 I16.00 103.26 12. 74 275. 00 121.00 106. 35 14.65 300. 00 104.00 108.57 -4. 57 Coitelatiuin CuefficieIt = .946 WCAP-17365-NP March 2011 Revision 0

C- 102 LWestinghouse Non-ProprietarE Class 3 CAPSULE 2840 (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 01/17/1)11 08:27 AM Page I Coefficients of Curve I A=S5L65 B=49.65C=215.65 TO= 13&34 D=S.OOE--OO Equation is A . B * [Tanh((T-Toy(C D137)l Upper Shelf L.E.= 100.3 Lower Shelf LE=l .0(Fixed)

Temp.@L.E. 35 mils=66,0 Dog F Plant: Calvert Cliffs I Material: SA533B I Heat: C444 1-1 OInctataon: NA Capsule: 284 Hucnco: n/cmn^2 20W 150 E

C

.0 8.100 5o

-300.0 0.0 300.0 600.0 Temperature In Deg F Charpy V-Notch Data Temperatue Inpul LE. Comrpted LE. Dilknrtial

-75. 00 13. 00 13. 26 -. 26 2>. 00 23. o0 21. 0u -4. 018

30. 00 37. 00 27. 98 9. 02

40. 00 41.00 29. 84 It. 16

50. 00 22. 00 31.77 -9.77

60. 00 34. 00 33.77 . 23 75.00 27. 00 36. 90 -9. 90 125. 00 12. 00 48.04 3. 96 225. 00 65. 00 69. 9Q -4. 99 March 2011 WCAP- 17365-NP WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-103 CAPSULE 2840 (HEAT AFFECTED ZONE)

Page 2 Plant: Calvert Cliffs I Material: SA533B I Heat: C-4441-1 Orientation: NA Capsule: 284 Fluence: n/cmA2 Charpy V-Notch Data Temperature Input LE. Computed LE. Differential 250. 00 80. 00 74. 64 5. 36 275. 00 85. 00 78. 80 6. 20 300. 00 76. 00 82. 45 -6. 45 Correlation Coefficient = .957 WCAP-17365-NP March 2011 Revision 0

C-104 Westinghouse Non-Pronrietary Class 3 Westinghouse Non-P nrietarv Class 3 CAPSULE 24O (HEAT AFFECTED ZONE)

CVGRAPII 5.3 Hyperbolic Tangent Curve Printed on 01/17/2011 08:29 AM Page I Coefficients of Curve I A = 50. B = 50. C = 96. TI = 77.52 D =O.O(E+00 Equation is A + B * [Tanh((T-To)Y(C+DT))l Temperature at .50%Shear= 77.6 Plant: Calvert Cliffs I Material: SA533B I Heat: C-4441- I Orientation: NA Capsule: 284 Fluence: n/cmt2 0

I 0 -

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

-75.00 15. 00 4. 00 I. 00

25. 00 25. 00 25. 08 08

30. 00 35. 00 27. 09 7.91

40. 00 35. 00 31. 39 3.61

50. 00 30. 00 36. 04 -6. 04

60. 00 35. 00 40. 97 -5. 97

75. 00 40. 00 48. 69 -8. 69 125. 00 85. 00 72. 89 12. II 225. 00 90. 00 95. 57 -5. 57 WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 C-105 Westinghouse Non-Proprietary Class 3 C-i 05 CAPSULE 2840 (HEAT AFFECTED ZONE)

Page 2 Plant: Calvert Cliff- I Malerial: SA533RI Heat: C-4441-1 Orientation: NA Capsule: 284 Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed percent Shear Differential 25). ('0 iOn. OQ 97. 32 2. 69 275. 00 I00. 00 98. 39 1. 61 300. 00 100.00 99. 04 . 96 Correlation Coefficient =.980 WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 D-1 APPENDIX D CALVERT CLIFFS UNIT 1 SURVEILLANCE PROGRAM CREDIBILITY EVALUATION D.1 INTRODUCTION Regulatory Guide 1.99, Revision 2 [Reference D-1], describes general procedures acceptable to the NRC staff for calculating the effects of neutron radiation embrittlement of the low-alloy steels currently used for light-water-cooled reactor vessels. 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 1 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 1 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 radiation embrittlement.

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 1 reactor vessel consists of the following beltline region materials:

" Intermediate Shell Plates D-7206-1, 2 and 3 (Heat # C-4351-2, C-4441-2, and C-4441-1)

Lower Shell Plates D-7207-1, 2 and 3 (Heat # C-4420-1, B-8489-2, and B-8489-1)

Intermediate to Lower Shell Circumferential Weld Seam 9-203 (Heat # 33A277)

Intermediate Shell Longitudinal Weld Seams 2-203-A, B, C (Heat # 12008/20291)

Lower Shell Longitudinal Weld Seams 3-203-A, B, C (Heat # 21935)

WCAP-17365-NP March 2011 Revision 0

D-2 Westinehouse Non-Pronrietarv 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 I plates (D-7207-1 and D-7206-3) had a 0

TNDT of 0 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, Intermediate Shell Plate D-7206-3 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 33A277/1092 for Calvert Cliffs Unit 1. 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 1 surveillance program (Heat # 33A277) had the 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 I 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 temperatureand 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 I surveillance materials unambiguously. Hence, the Calvert Cliffs Unit I surveillance program meets this criterion.

Hence, Criterion 2 is met for the Calvert Cliffs Unit 1 surveillance program.

Criterion 3: When there are two or more sets of surveillance datafrom 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°Ffor welds and 17°Ffor 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-17365-NP March 2011 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 I surveillance plate material. The Calvert Cliffs Unit 1 surveillance weld will be evaluated for credibility using the guidance from the appropriate case as explained in Reference D-6.

Each surveillance material and its respective evaluation method are described below:

1. IS Plate D-7206-3 (Case 1) - This plate material will be evaluated using the NRC Case I guidelines as described above.

2. Heat # 33A277 (Case 4) - This weld heat pertains to IS to LS Circumferential Weld 9-203 in the Calvert Cliffs Unit 1 reactor vessel. This weld heat is contained in the Calvert Cliffs Unit 1 surveillance program as well as the Farley Unit 1 surveillance program. NRC Case 4 per Reference D-6 is entitled "Surveillance Data from Plant and Other Sources" and most closely represents the situation for Calvert Cliffs Unit I weld Heat # 33A277.

WCAP- 17365-NP March 2011 Revision 0

D-4 Westinghouse Non-Proprietary Class 3 Case 1: IS Plate D-7206-3 and Case 4: Weld Heat # 33A277 (Calvert Cliffs Unit 1 data only)

Following the NRC Case 1 and Case 4 guidelines, the Calvert Cliffs Unit 1 surveillance plate and weld metal (Heat # 33A277) will be evaluated using Calvert Cliffs Unit 1 data only. This evaluation is contained in Table D-1.

Table D-1 Calculation of Interim Chemistry Factors for the Credibility Evaluation Using Calvert Cliffs Unit 1 Surveillance Capsule Data Only Material Capsule Capsule f (a) (b) ARTNDT(c) FF*ARTNDT FF2 Material_ _ Capsule (x 10'9 n/cm 2, E > 1.0 MeV) FFb) (OF) (OF) FF2 Intermediate Shell 2630 0.505 0.809 65.8 53.25 0.655 Plate 97° 1.94 1.181 111.1 131.22 1.395 D-7206-3 (Longitudinal) 2840 2.33 1.228 98.6 121.13 1.509 Intermediate Shell 970 1.94 1.181 109.5 129.33 1.395 Plate D-7206-3 2840 2.33 1.228 127.0 156.02 1.509 (Transverse)

SUM: 590.96 6.463 CFD-7 206 _3= 1(FF

ARTNDT) + Y(FF 2 ) = (590.96) + (6.463) = 91.4°F 2630 0.505 0.809 50.4 40.79 0.655 Calvert Cliffs Unit 1 Weld Metal 97' 1.94 1.181 104.5 123.43 1.395 (Heat # 33A277) 284' 2.33 1.228 78.0 95.82 1.509 SUM: 260.04 3.559 CFHeat A 33A277.= 1(FF

ARTNDT) + 12(FF 2) =(260.04) + (3.559) =73.1°F Notes:

(a) f= capsule fluence taken from Table 7-1 of this report.

(b) FF = fluence factor = f0 28 -O.lOlog 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 I data is being considered; therefore, no temperature adjustment is required.

WCAP- 17365-NP March 2011 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 1 Surveillance Materials Only CF Capsule Measured Predicted Residual <17 0F Material Capsule (Slopebtnit) Fluence FF ARTNDT(a) ARTNDT(b) ARTNDT(c) (Base Metal)

(OF) (x10 19 2 n/cm ) _ (F) (OF) (OF) <28 0 F (Weld)

Intermediate Shell 263* 91.4 0.505 0.809 65.8 74.0 8.2 Yes Plate 97' 91.4 1.94 1.181 111.1 108.0 3.1 Yes D-7206-3 (Longitudinal) 2840 91.4 2.33 1.228 98.6 112.3 13.7 Yes Intermediate Shell 97* 91.4 1.94 1.181 109.5 108.0 1.5 Yes Plate D-7206-3 284* 91.4 2.33 1.228 127.0 112.3 14.7 Yes (Transverse) I Calvert Cliffs 2630 73.1 0.505 0.809 50.4 59.1 8.7 Yes Unit 1 Weld Metal 97* 73.1 1.94 1.181 104.5 86.3 18.2 Yes (Heat #33A277) 2840 73.1 2.33 1.228 78.0 89.8 1 1.8 Yes Notes:

(a) Measured ARTNDT values are taken from Table D-1.

(b) Predicted ARTNDT CFbest-fit

FF.

(c) Residual ARTNDT Absolute Value [Predicted ARTNDT - Measured ARTNDT].

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 170F for base metal. Table D-2. indicates that all five surveillance data points fall within the +/- 1 of 17'F scatter band for surveillance base metals; therefore, the IS Plate D-7206-3 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 +/- Icr of 287F scatter band for surveillance weld materials; therefore, the weld material (Heat # 33A277) is deemed "credible" per the third criterion when only the Calvert Cliffs Unit I data is considered.

Hence, Criterion 3 is met for the Calvert Cliffs Unit 1 surveillance plate material. Criterion 3 is also met for the surveillance weld metal when only Calvert Cliffs Unit 1 data is considered. In accordance with Case 4 of the NRC Credibility Guidelines, the surveillance weld metal will now also be evaluated including the Farley Unit 1 surveillance data to determine if it remains credible when considering all available data.

WCAP-17365-NP March 2011 Revision 0

D-6 Westinghouse Non-Proprietary Class 3 Case 4: Weld Heat # 33A277 (All data)

In accordance with the NRC Case 4 guidelines, the data from Calvert Cliffs Unit I and Farley Unit 1 will now be analyzed together. Data is adjusted to the mean chemical composition and operating temperature of the surveillance capsules. This is performed in Table D-3 below:

Table D-3 Mean Chemical Composition and Operating Temperature for Calvert Cliffs Unit 1 and Farley Unit 1 Inlet Temperature during Cu Ni Material Capsule Period of Irradiation Wt. % Wt. %

2630 0.18 0.16 548.00 Weld Metal Heat # 33A277 970 0.18 0.16 548.00 (Calvert Cliffs Unit 1 data) 2840 0.18 0.16 548.00 Y 0.14 0.19 544.00 U 0.14 0.19 540.25 Weld Metal Heat # 33A277 X 0.14 0.19 540.86 (Farley Unit 1 data) W 0.14 0.19 541.75 V 0.14 0.19 541.72 Z 0.14 0.19 541.43 MEAN 0.15 0.18 543.78 Therefore, the Calvert Cliffs Unit I and Farley Unit I surveillance capsule data will be adjusted to the mean chemical composition and operating temperature calculated in Table D-3.

Calvert Cliffs Unit 1 data CFMean = 82°2F (calculated per Table I of Regulatory Guide 1.99, Revision 2 using Cu Wt. % = 0.15 and Ni Wt. % = 0.18 per Table D-3)

CFsurv. Weld (Calvert Cliffs Unit 1) 91.8 0 F (calculated per Table 1 of Regulatory Guide 1.99, Revision 2 using Cu Wt. % = 0.18 and Ni Wt. % = 0.16 per Reference D-3)

Ratio = 82.2 ÷ 91.8 = 0.90 (apr lied to Calvert Cliffs Unit I surveillance data for wel d Heat # 33A277 in the credibility evaluation)

WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 D-7 Westinghouse Non-Proprietary Class 3 D-7 Farley Unit I data CFMean = 82.2 0 F CFsurv. Weld (Farley Unit 1) 78.1°F (calculated per Table 1 of Regulatory Guide 1.99, Revision 2 using Cu Wt. % = 0.14 and Ni Wt. % = 0.19 per Reference D-8)

Ratio = 82.2 + 78.1 = 1.05 (applied to Farley Unit 1 surveillance data for weld Heat # 33A277 in the credibility evaluation)

The capsule-specific temperature adjustments are as shown in Table D-4 below:

Table D-4 Operating Temperature Adjustments for the Calvert Cliffs Unit 1 and Farley Unit 1 Surveillance Capsule Data Inlet Temperature during Mean Operating Temperature Material Capsule Period of Irradiation Temperature Adjustment (OF) (OF) (OF) 2630 548.00 543.78 +4.22 Weld Metal Heat # 33A277 (Calvert Cliffs Unit 1 data) 970 548.00 543.78 +4.22 2840 548.00 543.78 +4.22 y 544.00 543.78 +0.22 U 540.25 543.78 -3.53 Weld Metal Heat # 33A277 X 540.86 543.78 -2.92 (Farley Unit 1 data) W 541.75 543.78 -2.03 V 541.72 543.78 -2.06 z 541.43 543.78 -2.35 WCAP-17365-NP March 2011 Revision 0

D-8 Westinehouse Non-ProDrietarv Class 3 Using the chemical composition and operating temperature adjustments described and calculated above, an interim chemistry factor is calculated for weld Heat # 33A277 using the Calvert Cliffs Unit 1 and Farley Unit 1 data. This calculation is shown in Table D-5 below.

Table D-5 Calculation of Weld Heat # 33A277 Interim Chemistry Factor for the Credibility Evaluation Using Farley Unit 1 and Calvert Cliffs Unit 1 Surveillance Capsule Data Material Capsule Capsule f~a) FF(b) ARTNDT(C) FF*ARTNDT FF2 Material _ Capsule (xlO' 9 n/cm 2, E > 1.0 MeV) FFb_ (OF) (OF) FF_

2630 0.505 0.809 49.2 (50.4) 39.78 0.655 Weld Metal Heat#33A277 970 1.94 1.181 97.8 (104.5) 115.57 1.395 (Calvert Cliffs Unit 1 data) 2840 2.33 1.228 74.0 (78.0) 90.90 1.509 Y 0.612 0.862 70.5 (66.9) 60.78 0.744 U 1.73 1.151 75.1 (75.1) 86.48 1.324 Weld Metal X 3.06 1.295 88.7 (87.4) 114.91 1.678 Heat # 33A277 (Farley Unit 1 data) W 4.75 1.392 101.1 (98.3) 140.72 1.938 V 7.14 1.466 121.2 (117.5) 177.71 2.149 Z 8.47 1.492 116.7 (113.5) 174.10 2.225 SUM: 1000.96 13.62 CFHeat # 33A277 = E(FF

ARTNDT) - E(FF 2) =(1000.96) + (13.62) = 73.5°F Notes:

(a) f= capsule fluence taken from Table 7-1 and Reference D-8 for Calvert Cliffs Unit I and Farley Unit 1, respectively.

(b) FF = fluence factor = 1(028 -.0o*og f.

(c) ARTNDT values are the measured 30 ft-lb shift values. Pre-adjusted values are taken from Section 5 of this report and Reference D-3 for Calvert Cliffs Unit 1 and Farley Unit 1, respectively. ARTNDT values for the surveillance weld data are adjusted first by the difference in operating temperature then by using the ratio procedure to account for differences in the surveillance weld chemistry and the mean chemical composition (pre-adjusted values are listed in parentheses). The temperature adjustments are shown in Table D-4 of this report. The ratios applied are 0.90 and 1.05 for Calvert Cliffs Unit 1 and Farley Unit 1, respectively.

WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 D-9 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-6.

Table D-6 Best-Fit Evaluation for Surveillance Weld Metal Heat # 33A277 Using Calvert Cliffs Unit 1 and Farley Unit 1 Data CF Capsule f Measured Predicted Residual 19 Material Capsule (Slopebst-fit) (xl0 2

n/cm , FF ARTNDT(s) ARTNDT(b) ARTNDT(C) <28°F (Weld)

(OF) E > 1.0 MeV) (OF) (OF) (OF) 2630 73.5 0.505 0.809 49.2 59.5 10.3 Yes Weld Metal Heat Heat # 33A277 li3A77 970 73.5 1.94 1.181 97.8 86.8 11.0 (Calvert Cliffs Yes Unit 1 data) 2840 73.5 2.33 1.228 74.0 90.3 16.3 Yes Y 73.5 0.612 0.862 70.5 63.4 7.1 Yes U 73.5 1.73 1.151 75.1 84.6 9.4 Yes Weld Metal Heat # 33A277 X 73.5 3.06 1.295 88.7 95.2 6.5 Yes (Farley Unit 1 W 73.5 4.75 1.392 101.1 102.3 1.2 Yes data) V 73.5 7.14 1.466 121.2 107.8 13.5 Yes Z 73.5 8.47 1.492 116.7 109.6 7.1 Yes Notes:

(a) ARTNDT values are the adjusted values taken from Table D-5.

(b) Predicted ARTNT CFbest.fit

FF.

(c) Residual ARTDT = Absolute Value [Predicted ARTNDT - Measured ARTNDT].

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-6 indicates that 100% (nine out of nine) of the surveillance data points fall within the +/- 1a of 28'F scatter band for surveillance weld materials. Therefore, the surveillance weld material (Heat # 33A277) is deemed "credible" per the third criterion when all available data is considered.

In conclusion, the combined surveillance data from Calvert Cliffs Unit I and Farley Unit I for weld Heat # 33A277 may be applied to the Calvert Cliffs Unit 1 reactor vessel weld. The chemistry factor calculation as applicable to the Calvert Cliffs Unit 1 reactor vessel weld is contained in Appendix F of this report.

WCAP-17365-NP March 2011 Revision 0

D-10 Westinahouse Non-Proorietarv 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 +/- 250 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 beltline provides assurance that the reactor vessel wall and the specimens experience equivalent operating conditions such that the temperatures will not differ by more than 25°F.

Hence, Criterion 4 is met for the Calvert Cliffs Unit I surveillance program.

Criterion 5: The surveillance datafor the correlation monitor material in the capsule should fall within the scatterband of the databasefor that material.

The Calvert Cliffs Unit I surveillance program does contain Standard Reference Material (SRM). The material was obtained from an A533 Grade B, Class I 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 value for Capsule 263' as documented herein, nor does it consider the updated ARTNDT as determined by CVGraph.

Thus, Table D-7 contains an updated calculation of Residual vs. Fast fluence, considering the recalculated capsule fluence and ARTNDT value for Capsule 2630.

Table D-7 Calculation of Residual vs. Fast Fluence for Calvert Cliffs Unit 1 Capsule f Measured RG 1.99, Rev. 2 Residual(')

Capsule (xW01 9 n/cm 2, E > 1.0 MeV) FF Shift(a) (*F) Shift(b) (*F) (OF) 2630 0.505 0..809 99.8 110.15 -10.3 Notes:

(a) Measured AT30 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 136.1*F 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-7 shows a 2(y uncertainty of less than 50F, which is the allowable scatter in NUREG/CR-6413, ORNL/TM-13133.

Hence, Criterion 5 is met for the Calvert Cliffs Unit I surveillance program.

WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 D-11 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 I surveillance data is deemed credible for both the surveillance plate and weld specimens.

D.4 REFERENCES D-1 U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Regulatory Guide 1.99, Revision 2, Radiation Embrittlement ofReactor 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 E185-70, Recommended Practicefor Surveillance Tests for Nuclear Reactor Vessels, American Society of Testing and Materials, Philadelphia, PA, 1970.

D-5 ASTM E 185-82, Annual Book of ASTM Standards, Section 12, Volume 12.02, StandardPractice for ConductingSurveillance Testsfor 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 RP V Integrity Issues, February 12, 1998.

D-7 NUREG/CR-6413; ORNL/TM-13133, Analysis of the Irradiation Datafor A302B and A533B CorrelationMonitor Materials, J. A. Wang, Oak Ridge National Laboratory, Oak Ridge, TN, April 1996.

D-8 WCAP-16964-NP, Revision 0, Analysis of Capsule Z from the Southern Nuclear Operating Company Joseph M Farley Unit I Reactor Vessel Radiation Surveillance Program, J. M.

Conermann and M. A. Hunter, October 2008.

WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 E-1 APPENDIX E CALVERT CLIFFS UNIT 1 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-I of this Appendix) when surveillance data is not used. Linear interpolation is permitted. In addition, if surveillance data is to be used, the decrease in upper-shelf energy may be obtained by plotting the reduced plant surveillance data on Figure 2 of the Guide (Figure E-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 48 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 48 EFPY.

The Calvert Cliffs Unit I reactor vessel beltline region minimum thickness is 8.625 inches. Calculation of the 1/4T vessel surface fluence values at 32 and 48 EFPY for the beltline materials is shown as follows:

Maximum Vessel Fluence @ 32 EFPY 2.73 x 1019 n/cm 2 (E > 1.0 MeV) 2 e('°'2 4 I/4T Fluence @ 32 EFPY = (2.73 X i019 n/cm ) * * (8.625/4))

11.627 x 1019 n/cm 2 (E > 1.0 MeV)

Maximum Vessel Fluence @ 48 EFPY = 3.86 x 1019 n/cm 2 (E > 1.0 MeV) 2 24 1/4T Fluence @ 48 EFPY (3.86 x 1019 n/cm )

e(-° *(8.625/4))

= 2.301 x 1019 n/cm2 (E > 1.0 MeV).

The following pages present the Calvert Cliffs Unit I upper-shelf energy evaluation. Figure E-I, as indicated above, is used in making predictions in accordance with Regulatory Guide 1.99, Revision 2.

Table E-l provides the predicted upper-shelf energy values for 32 EFPY (end-of-life). Table E-2 provides the predicted upper-shelf energy values for 48 EFPY (end-of-life-extension).

WCAP-17365-NP March 2011 Revision 0

E-2 Westinghouse Non-Proprietary Class 3 100.0-100.0 ~%Metal Base Copper......

Weld Weld Heat # 33A277 0.35 0.30 1 1 1 w!

0.30 0.25 Upper Limit ?

0.25 U) ~ 02 0.15t D726 I..

o 10.0 0

0, 32 EFPY' 1/4 T Fluence = 1.627 x 1011g n/crn=

0 Surveillance M aterial: IS P late D-7206-3

Surveillance M aterial: Weld 48:P( 1/4T Fluence 2.301 x 1V~ n/c? Heat# 33A277 1.0 1.00E+17 1.00E+18 I.00E+19 1.00E+20 2

Neutron Fluence, nlcm (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- 17365-NP March 2011 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 Material Position 1 .2(b)

Intermediate Shell Plate D-7206-1 0.11 1.627 90 27 65.7 Intermediate Shell Plate D-7206-2 0.12 1.627 81 27 59.1 Intermediate Shell Plate D-7206-3 0.12 1.627 112 27 81.8 Lower Shell Plate D-7207-1 0.13 1.627 77 27 56.2 Lower Shell Plate D-7207-2 0.12 1.627 90 27 65.7 Lower Shell Plate D-7207-3 0.11 1.627 81 27 59.1 Intermediate Shell Long. Welds 0.22 1.627 110 44 61.6 2-203-A, B, C Intermediate to Lower Shell 0.24 1.627 160 44 89.6 Circ. Weld 9-203 Lower Shell Long. Welds 0.18 1.627 109 38.5 67.0 3-203-A, B, C Position 2.2(c)

Intermediate Shell Plate D-7206-3(d) 0.12 1.627 112 25 84.0 Intermediate to Lower Shell 0.24 1.627 160 29.5 112.8 Circ. Weld 9 -2 0 3 (d)

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, respectively. The percent USE drop of the plates was calculated on the 0.15 Cu wt. % base metal line. The percent USE drop of the Intermediate Shell Longitudinal Welds and the Intermediate to Lower Shell Circ. Weld was calculated on the 0.25 Cu wt. % weld line. The percent USE drop of the Lower Shell Longitudinal Welds was calculated on the 0.20 Cu wt. %

weld line.

(c) 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.

(d) The most limiting surveillance data point for Intermediate Shell Plate D-7206-3 is a measured decrease of 26% at a fluence of 1.94 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 31% at a fluence of 1.94 x 1019 n/cm 2 pertaining to Capsule 970 (see Table 5-10).

WCAP-17365-NP March 2011 Revision 0

E-4 Westinehouse Non-Pronrietarv Class 3 Table E-2 Predicted Positions 1.2 and 2.2 Upper-Shelf Energy Values at 48 EFPY 1/4T EOLE i Projected Material Weight Fluence(a) Unirradiated E Projected

% of Cu (X1019 n/cm 2, UE DecreaseUSE EOLE E > 1.0 MeV) (%)

Position 1 .2(b)

Intermediate Shell Plate D-7206-1 0.11 2.301 90 29.5 63.5 Intermediate Shell Plate D-7206-2 0.12 2.301 81 29.5 57.1 Intermediate Shell Plate D-7206-3 0.12 2.301 112 29.5 79.0 Lower Shell Plate D-7207-1 0.13 2.301 77 29.5 54.3 Lower Shell Plate D-7207-2 0.12 2.301 90 29.5 63.5 Lower Shell Plate D-7207-3 0.11 2.301 81 29.5 57.1 Intermediate Shell Long. Welds 0.22 2.301 110 48 57.2 2-203-A, B, C Intermediate to Lower Shell Circ. Weld 9-203 0.24 2.301 160 48 83.2 Lower Shell Longitudinal Welds 0.18 2.301 109 42 63.2 3-203-A, B, C I Position 2.2(c)

Intermediate Shell Plate D-7206-3(d) 0.12 2.301 112 27 81.8 Intermediate to Lower Shell 0.24 2.301 160 32.5 108.0 Circ. Weld 9 -2 0 3(d)

Notes:

(a) The fluence values listed pertain to the maximum vessel fluence value at 48 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, respectively. The percent USE drop of the plates was calculated on the 0.15 Cu wt. % base metal line. The percent USE drop of the Intermediate Shell Longitudinal Welds and the Intermediate to Lower Shell Circ. Weld was calculated on the 0.25 Cu wt. % weld line. The percent USE drop of the Lower Shell Longitudinal Welds was calculated on the 0.20 Cu wt. % weld line.

(c) 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.

(d) The most limiting surveillance data point for Intermediate Shell Plate D-7206-3 is a measured decrease of 26% at a fluence of 1.94 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 31% at a fluence of 1.94 x 1019 n/cm pertaining to Capsule 970 (See Table 5-10).

USE Conclusion All of the beltline materials in the Calvert Cliffs Unit 1 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 48 EFPY.

WCAP- 17365-NP March 2011 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 ofReactor Vessel Materials,May 1988.

WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 F-1 APPENDIX F CALVERT CLIFFS UNIT 1 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 1 surveillance Capsule 2840 materials at 32 EFPY (EOL) and 48 EFPY (ECLE). The EOL and EOLE RTPTS calculations are summarized in Table F-3.

WCAP-17365-NP March 2011 Revision 0

F-2 Westinghouse Non-Proprietary Class 3 F.1 CALCULATION OF POSITION 2.1 CHEMISTRY FACTORS Ratio Procedure The Calvert Cliffs Unit I (CC-1) Position 1.1 surveillance program weld chemistry factor (91.8°F) is not identical to the vessel weld chemistry factor for the Intermediate to Lower Shell Circumferential Weld 9-203 (117.8'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 1 surveillance weld (see calculation below).

CFcc-I Surv Weld = 91.8'F [See Appendix D]

CFcc-I Beltline Weld = 117.8'F [Reference F-3]

117.8 Ratio 91.8 Ratio 1.28 The Farley Unit 1 (Far-I) Position 1.1 surveillance program weld chemistry factor (78.1°F) is also not identical to the vessel weld chemistry factor for the Intermediate to Lower Shell Circumferential Weld 9-203 (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 (See Appendix D)

CFcc-1 Beltline Weld = 11 7.8°F [Reference F-3]

117.8 Ratio 78.1 Ratio = 1.51 Therefore, in Table F-2, the measured ARTNDT values for weld Heat # 33A277 from the CC-I surveillance program will be multiplied by the ratio of 1.28 and the measured ARTNDT from the Far-l surveillance program will be multiplied by the ratio of 1.51.

Temperature Adjustments Calvert Cliffs Unit 1 utilizes surveillance data from a sister plant (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-4] given by the NRC at these industry meetings:

March 2011 WCAP- 17365-NP WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 F-3 Studies have shown that for temperatures near 550 F, a I 'F decrease in irradiation temperaturewill result in approximately a 1 "F increase in ARTNDT.

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 Far-i capsule irradiation temperatures (Tcapsule) and measured ARTNDT values are taken from Reference F-3 (see also Appendix D). The CC-I capsules were irradiated to 548°F (Tplan). Table F-I gives a summary of the temperature adjustments of the Far-I surveillance data that will be used in Table F-2 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 will be shown here.

Temperature Adiustment Procedure Tcapsule = 5440 F Tplant = 548 0 F 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

= 95.0OF The remaining Far-i measured ARTNDT values were adjusted in the same fashion and are shown in Table F-2 (unadjusted ARTNDT values are included in parentheses). No temperature adjustments were required for the CC-I data because the capsules were irradiated at the same temperature as the plant.

WCAP- 17365-NP March 2011 Revision 0

F-4 Westinghouse Non-Proprietary Class 3 Table F-1 Calculation of the Temperature Adjustments for the Farley Unit 1 Surveillance Capsule Data Applicable to Calvert Cliffs Unit I Calvert Cliffs Unit1lem rt Inlet Temperature during Material Capsule Period of Irradiation Temperature Adjustment (IF)

(TcauIe)(*F)

(Tp _(Tpjt) (IF) _

y 544.00 -4.00 U 540.25 -7.75 Weld Metal Heat # 33A277 X 540.86 548 -7.14 (Farley Unit 1 data) W 541.75 -6.25 V 541.72 -6.28 z 541.43 -6.57 WCAP- 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 F-5 Table F-2 Calculation of Chemistry Factors for Calvert Cliffs Unit 1 using Surveillance Capsule Data Capsule Fluence (a) ARTNDT(c) FF*ART*T FF2 Material Capsule (X 1019 n/cm2 FF(b) (OF (F)

E > 1.0 MeV)

Intermediate 263° 0.505 0.809 65.8 53.25 0.655 Shell Plate 970 1.94 1.181 111.1 131.22 1.395 D-7206-3 (Longitudinal) 2840 2.33 1.228 98.6 121.13 1.509 Intermediate 97* 1.94 1.181 109.5 129.33 1.395 Shell Plate D-7206-3 284' 2.33 1.228 127.0 156.02 1.509 (Transverse)

SUM: 590.96 6.463 2

CFD-7206 . 3 = (FF

ARTNDT) + (FF ) = (590.96) (6.463) = 91.4"F cc- 263* 0.505 0.809 64.5 (50.4) 52.21 0.655 Surveillance 97 1.94 1.181 133.8 (104.5) 157.99 1.395 Program Weld (Heat # 33A277) 2840 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 2 0 CFsurv Weld = Y(FF

ARTNDT) + Y2(FF ) = (1369.38)+ (13.618) = 100.6 F Notes:

(a) The Calvert Cliffs Unit I calculated capsule fluence values are taken from Table 7-1 of this report. The Farley Unit I calculated capsule fluence values are taken from Reference F-3.

(b) FF = fluence factor = fo.28-0. lOlog(0).

(c) ARTNDT values are the measured 30 ft-lb shift values taken from Section 5 of this report for Calvert Cliffs Unit 1 and Reference F-3 for Farley Unit 1. The Farley Unit 1 ARTanT 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 1 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 I - Ratio = 1.28 Farley Unit 1 - Ratio = 1.51, Temperature adjustments per Table F-1 (on a capsule-by-capsule basis)

WCAP- 17365-NP March 2011 Revision 0

F-6 Westinghouse Non-Proprietary Class 3 F.2 RTprs CALCULATIONS Table F-3 RTPTS Calculations for the Calvert Cliffs Unit 1 Surveillance Capsule 2840 Materials at 32 and 48 EFPY R.G. 1.99, CF(a) Fluence(b) IRTNDT(c) ARTNDT u(c) I a Margin RTTs Reactor Vessel Material Rev. 2 ( FF IT.DT (O) (OF) (OF) (Mn)

Position (IF) (n/cm2, E> 1.0 MeV) (0 F) (0F) (0F) 0

(°F) ( F) (0F) 32 EFPY Intermediate Shell Plate D- 7 20 6 -2(d) 1.1 83.6 2.730 x 1019 1.2679 -30 106.0 0 17 34.0 110 2.1 91.4 2.730 x 1019 1.2679 -30 115.9 0 8.5(e) 17.0 103 1.1 83.6 2.730 x 1019 1.2679 10 106.0 0 17 34.0 150 Intermediate Shell Plate D-7206-3 2.1 91.4 2.730 x 1019 1.2679 10 115.9 0 8.5(e) 17.0 143 Intermediate Shell to Lower Shell 1.1 117.8 2.730 x 1019 1.2679 -80 149.4 0 28 56.0 125 Circ. Weld 9-203 2.1 100.6 2.730 x 1019 1.2679 -80 127.5 0 14(e) 28.0 75 48 EFPY 1.1 83.6 3.860 x 1019 1.3485 -30 112.7 0 17 34.0 117 Intermediate Shell Plate D-7206-2(d) 2.1 91.4 3.860 x 1019 1.3485 -30 123.3 0 8.5(e) 17.0 110 1.1 83.6 3.860 x 1019 1.3485 10 112.7 0 17 34.0 157 Intermediate Shell Plate D-7206-3 2.1 91.4 3.860 x 1019 1.3485 10 123.3 0 8.5(e) 17.0 150 Intermediate Shell to Lower Shell 1.1 117.8 3.860 X 1019 1.3485 -80 158.8 0 28 56.0 135 Circ. Weld 9-203 2.1 100.6 3.860X 1019 1.3485 -80 135.6 0 14(') 28.0 84 Notes:

(a) Position 1.1 Chemistry Factor values taken from Reference F-3 and Position 2.1 Chemistry Factor values taken from Table F-2.

(b) Maximum end-of-life and end-of-life-extension fluence values taken from Table 6-2 of this report.

(c) Initial RIOT values are measured and are taken from Reference F-3.

(d) Intermediate Shell Plate D-7206-2 is the same heat of material as the surveillance capsule plate material Intermediate Shell Plate D-7206-3 [Reference F-3].

(e) A reduced oA term is used since the surveillance data is deemed credible per Appendix D.

WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 F-7 PTS Conclusion All of the surveillance Capsule 2840 materials for Calvert Cliffs Unit 1 are projected to remain below the PTS screening criterion value of 270'F for plates and 300'F for circumferential welds (per 10 CFR 50.61) at 32 and 48 EFPY.

F.3 REFERENCES F-i 10 CFR 50.61, Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events, Federal Register, Volume 60, No. 243, December 19, 1995.

F-2 U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Regulatory Guide 1.99, Revision 2, Radiation Embrittlement of Reactor Vessel Materials,May 1988.

F-3 Comprehensive Reactor Vessel SurveillanceProgram, Revision 5, W. A. Pavinich, July 2009.

F-4 K. Wichman, M. Mitchell, and A. Hiser, USNRC, Generic Letter 92-01 and RPV Integrity Assessment Workshop Handouts, NRC/Industry Workshop on RP V Integrity Issues, February 12, 1998.

WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 G-1 APPENDIX G CALVERT CLIFFS UNIT 1 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 1 at 48 EFPY for each reactor vessel surveillance capsule material (Intermediate Shell Plate D-7206-3 and Intermediate to Lower Shell Circ. Weld 9-203) 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 2840 materials are documented in the CRVSP, Revision 5 [Reference G-2].

The Calvert Cliffs Unit 1 (CC-1) Intermediate Shell Plate D-7206-3 surveillance data has been deemed credible per Appendix D of this report. Therefore, when using the Intermediate Shell Plate D-7206-3 surveillance data, a reduced 0 A value can be used. The CC-I 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 ca value can be used.

The Calvert Cliffs Unit 1 reactor vessel beltline region minimum thickness is 8.625 inches. Calculation of the 1/4T and 3/4T vessel fluence values at 48 EFPY for the beltline materials is shown as follows:

Maximum Vessel Fluence @ 48 EFPY - 3.86 x 10' 9 n/cm 2 (E > 1.0 MeV) 2 e(4024 1/4T Fluence @ 48 EFPY = (3.86 x 1019 n/cm ) * * (8.625 /4))

= 2.301 X 1019 n/cm 2 (E > 1.0 MeV)

Maximum Vessel Fluence @ 48 EFPY = 3.86 x 1019 n/cm 2 (E > 1.0 MeV) 2 24 3/4T Fluence @ 48 EFPY (3.86 x 1019 n/cm )

e(4° * (3*8"625 /4))

= 0.817 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-I reactor vessel surveillance Capsule 2840 materials.

WCAP-17365-NP March 2011 Revision 0

G-2 Westinghouse Non-Proprietary Class 3 Table G-1 Calculation of the Calvert Cliffs Unit 1 Reactor Vessel Surveillance Capsule Material ART Values at the 1/4T Location for 48 EFPY R.G. 1.99, CF(a) 1/4T Fluence IRTNDT (b) ARTNDT aI(b) GA Margin ART Reactor Vessel Material Rev. 2 FF (OF) (n/cm 2, E > 1.0 MeV) (OF) (OF) (OF) (OF) (OF) (OF)

Position 1.1 83.6 2.301 x 10"9 1.2252 -30 102.4 0 17 34.0 106 Intermediate Shell Plate D-7206-2(c) 9 2.1 91.4 2.301 x 10' 1.2252 -30 112.0 0 8 .5(d) 17.0 99 Intermediate Shell Plate D-7206-3 1.1 83.6 2.301 x 10' 9 1.2252 10 102.4 0 17 34.0 146 2.1 91.4 2.301 x 10'9 1.2252 10 112.0 0 8 .5(d) 17.0 139 Intermediate Shell to Lower Shell 1.1 117.8 2.301 x 1019 1.2252 -80 144.3 0 28 56.0 120 Circ. Weld 9-203 2.1 100.6 2.301 x 1019 1.2252 -80 123.2 0 14(d) 28.0 71 Notes:

(a) Position 1.1 Chemistry Factor values taken from Reference G-2 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) Intermediate Shell Plate D-7206-2 is the same heat of material as the surveillance capsule plate material Intermediate Shell Plate D-7206-3 [Reference G-2].

(d) A reduced aAterm is used since the surveillance data is deemed credible per Appendix D.

March 2011 WCAP-WCAP- 17365-NP 17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 G-3 Table G-2 Calculation of the Calvert Cliffs Unit 1 Reactor Vessel Surveillance Capsule Material ART Values at the 3/4T Location for 48 EFPY R.G. 1.99, CF(a) 3/4T Fluence IRThnT (b) ARTNDT 0l(b) CA Margin ART Reactor Vessel Material Rev. 2 FF (OF) (OF) (OF) (OF) (OF)

Position ( 0F) (n/cm 2 , E > 1.0 MeV) (OF)

Intermediate Shell Plate D-7206-2(c) 1.1 83.6 0.817 x 10' 9 0.9434 -30 78.9 0 17 34.0 83 2.1 91.4 0.817 x 1019 0.9434 -30 86.3 0 8 .5 (d) 17.0 73 1.1 83.6 0.817 x 10'9 0.9434 10 78.9 0 17 34.0 123 Intermediate Shell Plate D-7206-3 2.1 91.4 0.817 x 1019 0.9434 10 86.3 0 8 .5(d) 17.0 113 Intermediate Shell to Lower Shell 1.1 117.8 0.817 x 1019 0.9434 -80 111.1 0 28 56.0 87 Circ. Weld 9-203 2.1 100.6 0.817 x 1019 0.9434 -80 94.9 0 14(d) 28.0 43 Notes:

(a) Position 1.1 Chemistry Factor values taken from Reference G-2 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) Intermediate Shell Plate D-7206-2 is the same heat of material as the surveillance capsule plate material Intermediate Shell Plate D-7206-3 [Reference G-2].

(d) A reduced aA term is used since the surveillance data is deemed credible per Appendix D.

WCAP-17365-NP March 2011 Revision 0

G-4 Westinghouse Non-Proprietary Class 3 G.2 P-T LIMIT CURVE APPLICABILITY The current P-T limit curves for CC-i are based on Lower Shell Longitudinal Welds 3-203-A, B, C

[Reference G-3]. It must be ensured that the current surveillance capsule results from Capsule 2840 do not invalidate the current P-T limit curves for Calvert Cliffs Unit 1. Table G-3 compares Capsule 2840 materials' initial properties to the Lower Shell Longitudinal Welds 3-203-A, B, C material properties.

Reference G-2 confirms that all CC-i reactor vessel beltline materials use the same fluence value. It can be determined from the properties in Table G-3 that welds 3-203-A, B, C have more limiting material properties than the Capsule 2840 materials at any fluence, as long as the fluence on each material is the same.

Table G-3 Comparison of CC-i Surveillance Capsule 2840 Materials Initial Properties to Lower Shell Long. Welds 3-203-A, B, C for P-T Limit Curve Development Reactor Vessel Material Intermediate Shell to Lower Material Property Intermediate Shell Lower Shell Long. Weld Shell Circ.

Plate D-7206-3(a) Weld 9-2031a) 3-203-A, B, Ct ")

Initial RTNDT( 0 F) 10 -80 -56 Margin (*F) 17 28 66 Chemistry Factor (°F) 91.4 100.6 174 Notes:

(a) Values are summarized in Tables G-1 and G-2 of this report.

(b) Values taken from WCAP-17014-NP, Revision 0 [Reference G-3].

Furthermore, the fluence value used in the current P-T limit curve analysis of record [Reference G-4] is 4.49 x 1019 n/cm 2 (E > 1.0 MeV). Using the updated fluence values contained in Table 6-2, the EFPY applicability term can be calculated. Using linear interpolation, the peak vessel fluence value is not projected to reach 4.49 x 1019 n/cm 2 (E > 1.0 MeV) until about 57 EFPY. Since the revised EFPY term for Calvert Cliffs Unit I is past end-of-life-extension (48 EFPY), the current P-T limit curves are projected to remain valid throughout the period of extended operation.

P-T Limit Curve Applicability Conclusion It is concluded that Lower Shell Longitudinal Welds 3-203-A, B, C will continue to be more limiting for use in the development of the P-T limit curves. The surveillance Capsule 284' analysis does not invalidate the current P-T limit curves. Additionally, based on the fluence value used in the analysis of record for Calvert Cliffs Unit 1 and interpolation of the peak fluence values from Table 6-2, the P-T limit curves for CC-I are predicted to remain applicable through end-of-life-extension (48 EFPY).

WCAP-17365-NP March 2011 Revision 0

Westinghouse Non-Proprietary Class 3 G-5 4'

G.3 REFERENCES G-1 U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Regulatory Guide 1.99, Revision 2, Radiation Embrittlement ofReactor Vessel Materials,May 1988.

G-2 Comprehensive Reactor Vessel Surveillance Program,Revision 5, W. A. Pavinich, July 2009.

G-3 WCAP-17014-NP, Revision 0, Analysis of Capsule Wfrom the McGuire Unit No. 1 Reactor Vessel Radiation Surveillance Programfor the Calvert Cliffs Unit 1 Vessel Weld Metal, C. C.

Heinecke and M. A. Hunter, December 2008.

G-4 Constellation Energy Group, LLC, Letter to US NRC, Calvert Cliffs Nuclear Power Plant Unit Nos. 1 & 2; Docket Nos. 50-317 & 50-318, License Amendment Request: Revision to Technical Specification P-T Curves, Peter E. Katz, May 28, 2003.

WCAP- 17365-NP March 2011 Revision 0

ML110910250

Contents

Text

SUBJECT:

Attachment:

SUMMARY

SUMMARY

6.1 INTRODUCTION

Navigation menu

ML110910250

Text

SUBJECT:

Attachment:

SUMMARY

SUMMARY

6.1 INTRODUCTION

Navigation menu

Search