NL-08-0475, WCAP-16918-NP, Rev. 1, Analysis of Capsule V from the Southern Nuclear Operating Company, Joseph M. Farley Unit 2 Reactor Vessel Radiation Surveillance Program.

WCAP-16918-NP, Rev. 1, Analysis of Capsule V from the Southern Nuclear Operating Company, Joseph M. Farley Unit 2 Reactor Vessel Radiation Surveillance Program.

ML081130652
Person / Time
Site:	Farley
Issue date:	04/18/2008
From:	Fischer G, Jurcevich N Westinghouse
To:	Office of Nuclear Reactor Regulation
References
NL-08-0475 WCAP-16918-NP, Rev 1
Download: ML081130652 (316)

Text

Westinghouse Non-Proprietary Class 3 WCAP-16918-NP April 200O3 Revision 1 Analysis of Capsule V from the Southern Nuclear Operating Company Joseph M. Farley Unit 2 Reactor Vessel Radiation Surveillance Program Westinghouse

WESTINGHOUSE NON-PROPRIETARY CLASS 3 WCAP-16918-NP Revision 1 Analysis of Capsule V from the Southern Nuclear Operating Company Joseph M. Farley Unit 2 Reactor Vessel Radiation Surveillance Program N. R. Jurcevich*

G A. Fischer*

April 2008 Reviewer: F. C. Gift, Jr.*

Major Reactor Component Design and Analysis - I Approved: P. C. Paesano*, Manager Primary Component Asset Management

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

Westinghouse Electric Company LLC P.O. Box 355 Pittsburgh, PA 15230-0355

© 2008 Westinghouse Electric Company LLC All Rights Reserved

, iii RECORD OF REVISION Revision 0: Original Issue Revision 1: This revision corrects the cycle lengths for cycles 17 and 18, and projection cycle 19 (CAPs IR 08-107-MOO). These corrections affected the fluence values for cycle 17 and beyond and the removal time of Capsule V. All the conclusions remained the same as in Revision 0 except for the new service period for Pressure-Temperature Limit Curves.

WCAP- 16918-NP April 2008 Revision 1

iv TABLE OF CONTENTS LIST OF TABLES ........................................................................................................................................ v LIST OF FIGURES .................................................................................................................................... vii EXECUTIVE SUMM ARY .......................................................................................................................... ix I SUMM ARY OF RESULTS .......................................................................................................... 1-1 2 INTRODUCTION ........................................................................................................................ 2-1 3 BACKGROUND .......................................................................................................................... 3-1 4 DESCRIPTION OF PROGRAM .................................................................................................. 4-1 5 TESTING OF SPECIM ENS FROM CAPSULE V ...................................................................... 5-1 5.1 OVERVIEW .................................................................................................................... 5-1 5.2 RESULTS ........................................................................................................................ 5-2 5.3 TENSILE TEST RESULTS ............................................................................................. 5-4 5.4 BEND BAR AND COMPACT TENSION SPECIMEN TESTS .................................... 5-5 6 RADIATION ANALYSIS AND NEUTRON DOSIM ETRY ....................................................... 6-1

6.1 INTRODUCTION

........................................................................................................... 6-1 6.2 DISCRETE ORDINATES ANALYSIS ........................................................................... 6-2 6.3 NEUTRON DOSIM ETRY .............................................................................................. 6-4 6.4 CALCULATIONAL UNCERTAINTIES ........................................................................ 6-5 7 SURVEILLANCE CAPSULE REM OVAL SCHEDULE ............................................................ 7-1 8 RE FERENCES ............................................................................................................................. 8-1 APPENDIX A VALIDATION OF THE RADIATION TRANSPORT MODELS BASED ON NEUTRON DOSIMETRY MEASUREMENTS ................................................. A-i 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 JOSEPH M. FARLEY UNIT 2 SURVEILLANCE PROGRAM CREDIBILITY E VA L U AT ION ............................................................................................................... D -1 WCAP- 16918-NP April 2008 Revision 1

v LIST OF TABLES Table 4-1 Chemical Composition (wt %) of the Farley Unit 2 Reactor Vessel Surveillance Materials

......................................................................................................................................... 4 -3 Table 4-2 Heat Treatment of the Farley Unit 2 Reactor Vessel Surveillance Materials ................... 4-3 Table 5-1 Charpy V-notch Data for the Farley Unit 2 Intermediate Shell Plate B7212-1 Specimens Irradiated to a Fluence of 8.73E+19 n/cm 2 (E> 1.0 MeV) (Longitudinal Orientation) ... 5-6 Table 5-2 Charpy V-notch Data for the Farley Unit 2 Intermediate Shell Plate B7212-1 Specimens Irradiated to a Fluence of 8.73E+ 19 n/cm 2 (E> 1.0 MeV) (Transverse Orientation) ....... 5-7 Table 5-3 Charpy V-notch Data for the Farley Unit 2 Surveillance Weld Metal Irradiated to a Fluence of 8.73E+19 n/cm 2 (E> 1.0 M eV ) ...................................................................... 5-8 Table 5-4 Charpy V-notch Data for the Farley Unit 2 HAZ Material Irradiated to a Fluence of 8.73E + 19 n/cm 2 (E > 1.0 M eV) ........................................................................................ 5-9 Table 5-5 Instrumented Charpy Impact Test Results for the Farley Unit 2 Intermediate Shell Plate B7212-1 Specimens Irradiated to a Fluence of 8.73E+ 19 n/cm 2 (E> 1.0 MeV)

(Longitu dinal O rientation) ............................................................................................. 5-10 Table 5-6 Instrumented Charpy Impact Test Results for the Farley Unit 2 Intermediate Shell Plate B7212-1 Specimens Irradiated to a Fluence of 8.73E+19 n/cm 2 (E> 1.0 MeV)

(Transverse O rientation) ................................................................................................ 5-11 Table 5-7 Instrumented Charpy Impact Test Results for the Farley Unit 2 Surveillance Weld Metal Irradiated to a Fluence of 8.73E+19 n/cm 2 (E> 1.0 MeV) ............................................. 5-12 Table 5-8 Instrumented Charpy Impact Test Results for the Farley Unit 2 HAZ Metal Irradiated to a Fluence of 8.73E+19 n/cm 2 (E> 1.0 M eV) .................................................................... 5-13 Table 5-9 Effect of Irradiation to 8.73E+19 n/cm 2 (E> 1.0 MeV) on the Charpy V-Notch Toughness Properties of the Farley Unit 2 Reactor Vessel Surveillance Capsule V Materials ........ 5-14 Table 5-10 Comparison of the Farley Unit 2 Surveillance Material 30 ft-lb Transition Temperature Shifts and Upper Shelf Energy Decreases with Regulatory Guide 1.99, Revision 2, P red ictio n s ..................................................................................................................... 5 -15 Table 5-11 Tensile Properties of the Farley Unit 2 Capsule V Reactor Vessel Surveillance Materials Irradiated to 8.73E+19 n/cm 2 (E> 1.0 M eV) ................................................................. 5-16 Table 6-1 Calculated Neutron Exposure Rates and Integrated Exposures at the Surveillance C ap sule C en ter ................................................................................................................. 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 Azimuthal Variation of Exposure Rates and Integrated Exposures at the Intermediate Shell Course to Nozzle Shell Course Weld ............................................... 6-15 Table 6-4 Relative Radial Distribution of Neutron Fluence (E > 1.0 MeV) Within the Reactor Vessel Wall ..................................................................................................................... 6 -19 WCAP- 16918-NP April 2008 Revision 1

vi Table 6-5 Relative Radial Distribution of Iron Atom Displacements (dpa) Within the Reactor Vessel Wall ..................................................................................................................... 6 -19 Table 6-6 Calculated Fast Neutron Exposure of Surveillance Capsules Withdrawn from Farley U n it 2 ............................................................................................................................. 6 -2 0 Table 6-7 Calculated Surveillance Capsule Lead Factors .............................................................. 6-20 Table 7-1 Farley Unit 2 Surveillance Capsule Withdrawal History ................................................. 7-1 WCAP- 16918-NP April 2008 Revision 1

vii LIST OF FIGURES Figure 4-1 Arrangement of Surveillance Capsules in the Farley Unit 2 Reactor Vessel ................... 4-4 Figure 4-2 Capsule V Diagram Showing the Location of Specimens, Thermal Monitors, an d D o simeters ................................................................................................................ 4-5 Figure 5-1 Charpy V-Notch Impact Energy vs. Temperature for Farley Unit 2 Reactor Vessel Intermediate Shell Plate B7212-1 Specimens (Longitudinal Orientation) .................... 5-17 Figure 5-2 Charpy V-Notch Lateral Expansion vs. Temperature for Farley Unit 2 Reactor Vessel Intermediate Shell Plate B7212-1 Specimens (Longitudinal Orientation) ......... 5-18 Figure 5-3 Charpy V-Notch Percent Shear vs. Temperature for Farley Unit 2 Reactor Vessel Intermediate Shell Plate B7212-1 Specimens (Longitudinal Orientation) .................... 5-19 Figure 5-4 Charpy V-Notch Impact Energy vs. Temperature for Farley Unit 2 Reactor Vessel Intermediate Shell Plate B7212-1 Specimens (Transverse Orientation) ........................ 5-20 Figure 5-5 Charpy V-Notch Lateral Expansion vs. Temperature for Farley Unit 2 Reactor Vessel Intermediate Shell Plate B7212-1 Specimens (Transverse Orientation) ............. 5-21 Figure 5-6 Charpy V-Notch Percent Shear vs. Temperature for Farley Unit 2 Reactor Vessel Intermediate Shell Plate B7212-1 Specimens (Transverse Orientation) ........................ 5-22 Figure 5-7 Charpy V-Notch Impact Energy vs. Temperature for Farley Unit 2 Reactor Vessel Surveillance Weld M etal Specimens .............................................................................. 5-23 Figure 5-8 Charpy V-Notch Lateral Expansion vs. Temperature for Farley Unit 2 Reactor Vessel Surveillance Weld M etal Specim ens .................................................................. 5-24 Figure 5-9 Charpy V-Notch Percent Shear vs. Temperature for Farley Unit 2 Reactor Vessel Surveillance Weld M etal Specim ens .............................................................................. 5-25 Figure 5-10 Charpy V-Notch Impact Energy vs. Temperature for Farley Unit 2 Reactor Vessel H eat-A ffected-Zone Specim ens ..................................................................................... 5-26 Figure 5-11 Charpy V-Notch Lateral Expansion vs. Temperature for Farley Unit 2 Reactor Vessel H eat-A ffected-Zone Specim ens .......................................................................... 5-27 Figure 5-12 Charpy V-Notch Percent Shear vs. Temperature for Farley Unit 2 Reactor Vessel H eat-A ffected-Zone Specim ens ..................................................................................... 5-28 Figure 5-13 Charpy Impact Specimen Fracture Surfaces for Farley Unit 2 Reactor Vessel Intermediate Shell Plate B7212-1 Specimens (Longitudinal Orientation) .................... 5-29 Figure 5-14 Charpy Impact Specimen Fracture Surfaces for Farley Unit 2 Reactor Vessel Intermediate Shell Plate B7212-1 Specimens (Transverse Orientation) ........................ 5-30 Figure 5-15 Charpy Impact Specimen Fracture Surfaces for Farley Unit 2 Reactor Vessel Surveillance Weld M etal Specim ens .............................................................................. 5-31 Figure 5-16 Charpy Impact Specimen Fracture Surfaces for Farley Unit 2 Reactor Vessel H eat-A ffected-Zone Specim ens ..................................................................................... 5-32 WCAP-16918-NP April 2008 Revision 1

viii LIST OF FIGURES (cont.)

Figure 5-17 Tensile Properties for Farley Unit 2 Reactor Vessel Intermediate Shell Plate B7212-1 Specim ens (Longitudinal Orientation) ............................................................ 5-33 Figure 5-18 Tensile Properties for Farley Unit 2 Reactor Vessel Intermediate Shell Plate B7212-1 Specim ens (Transverse Orientation) ............................................................... 5-34 Figure 5-19 Tensile Properties for Farley Unit 2 Reactor Vessel Surveillance Weld Metal S pecim en s ...................................................................................................................... 5 -3 5 Figure 5-20 Fractured Tensile Specimens from Farley Unit 2 Reactor Vessel Intermediate Shell Plate B7212-1 Specimens (Longitudinal Orientation) .......................................... 5-36 Figure 5-21 Fractured Tensile Specimens from Farley Unit 2 Reactor Vessel Intermediate Shell Plate B7212-1 Specimens (Transverse Orientation) ............................................. 5-37 Figure 5-22 Fractured Tensile Specimens from Farley Unit 2 Reactor Vessel Surveillance Weld M etal Specim ens .................................................................................................. 5-38 Figure 5-23 Engineering Stress-Strain Curves for the Farley Unit 2 Reactor Vessel Intermediate Shell Plate B7212-1 Specimens (Longitudinal Orientation) Tensile Specim ens CL-4, CL-5, and CL-6 ................................................................................. 5-39 Figure 5-24 Engineering Stress-Strain Curves for the Farley Unit 2 Reactor Vessel Intermediate Shell Plate B7212-1 Specimens (Transverse Orientation) Tensile Specim ens CT-4, C T-5*, and CT-6 ................................................................................ 5-40 Figure 5-25 Engineering Stress-Strain Curves for Farley Unit 2 Reactor Vessel Surveillance Weld Metal Specimens CW4, CW5, and CW6 .............................................................. 5-41 Figure 6-1 a Farley Unit 2 r,0 Reactor Geometry with a 150 Neutron Pad at the Core Midplane ..... 6-21 Figure 6-lb Farley Unit 2 r,0 Reactor Geometry with a 26' Neutron Pad at the Core Midplane ..... 6-21 Figure 6-2 Farley Unit 2 r,z Reactor Geometry with Neutron Pad .................................................. 6-22 WCAP- 16918-NP April 2008 Revision 1

ix EXECUTIVE

SUMMARY

The purpose of this report is to document the results of the testing of Surveillance Capsule V from the Joseph M. Farley Unit 2 nuclear power plant. Capsule V was removed at the end of cycle (EOC) 18 and post-irradiation mechanical tests of the Charpy V-notch and tensile specimens were performed. A fluence evaluation utilizing the recently released neutron transport and dosimetry cross-section libraries was derived from the ENDF/B-VI data-base. Capsule V received a fluence of 8.73E+19 n/cm 2 after 21.82 Effective Fuel Power Years (EFPY) of plant operation. The peak clad/base metal interface vessel fluence after 21.82 EFPY of plant operation was 2.43E+ 19 n/cm2 .

This evaluation concluded the following:

1. The measured 30 ft-lb shift in transition temperature values of the plate material contained in Capsule V (longitudinal and transverse orientations) is less than the Regulatory Guide 1.99, Revision 2, predictions.

2. The measured 30 ft-lb shift in transition temperature value of the weld metal contained in Capsule V is less than the Regulatory Guide 1.99, Revision 2, prediction.

3. The measured percent decrease in upper shelf energy (USE) for all the plate and weld surveillance materials in Capsule V are less than the Regulatory 1.99, Revision 2, predictions.

4. The beltline materials exhibit a more than adequate USE level for continued safe plant operation and are predicted to maintain an upper shelf energy greater than 50 ft-lb throughout the life of the vessel (54 EFPY) as required by 10CFR50, Appendix G.

5. The surveillance weld data was found to be not credible, while the surveillance plate data was found to be credible. This evaluation can be found in Appendix D.

6. The service period of applicability for the Pressure-Temperature Limit Curves labeled for 33.8 EFPY in WCAP-14689, Revision 4, must be reduced to account for the updated neutron fluence projections and vessel material chemistry factors calculated as part of the Surveillance Capsule V analysis. The new service period for these Pressure-Temperature Limit Curves is 32.8 EFPY.

Lastly, a brief summary of the Charpy V-notch testing can be found in Section 5.0. All Charpy V-notch data was plotted using a symmetric hyperbolic tangent curve fitting program.

WCAP- 16918-NP April 2008 Revision 1

1-1 1

SUMMARY

OF RESULTS The analysis of the reactor vessel materials contained in Surveillance Capsule V, the sixth and final capsule removed and tested from the Joseph M. Farley Unit 2 reactor pressure vessel, led to the following conclusions:

Capsule V received an average, fast neutron fluence (E> 1.0 MeV) of 8.73E+19 n/cm 2 after 21.82 EFPY of plant operation.

Irradiation of the reactor vessel intermediate shell plate B7212-1 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 196.0°F and an irradiated 50 ft-lb transition temperature of 240.1 F. This results in a 30 ft-lb transition temperature increase of 218.3'F and a 50 ft-lb transition temperature increase of 230. 1F for the longitudinal orientation specimens. See Table 5-9.

Irradiation of the reactor vessel intermediate shell plate B7212-1 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 207.8°F and an irradiated 50 ft-lb transition temperature of 234.37F. This results in a 30 ft-lb transition temperature increase of 215.3°F and a 50 ft-lb transition temperature increase of 200.7°F for the transverse orientation specimens. See Table 5-9.

Irradiation of the surveillance weld metal Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 22.0°F and an irradiated 50 ft-lb transition temperature of 61.8°F. This results in a 30 ft-lb transition temperature increase of 56.5°F and a 50 ft-lb transition temperature increase of 77.2°F. See Table 5-9.

Irradiation of the weld heat-affected-zone (HAZ) metal Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 26.2°F and an irradiated 50 ft-lb transition temperature of 52.4°F. This results in a 30 ft-lb transition temperature increase of 322.4°F and a 50 ft-lb transition temperature increase of 257.7°F. See Table 5-9.

The average USE of the intermediate shell plate B7212-1 Charpy specimens (longitudinal orientation) resulted in an average energy decrease of 44 ft-lb after irradiation. This results in an irradiated average USE of 86 ft-lb for the longitudinal orientation specimens. See Table 5-9.

The average USE of the intermediate shell plate B7212-1 Charpy specimens (transverse orientation) resulted in an average energy decrease of 26 ft-lb after irradiation. This results in an irradiated average USE of 69 ft-lb for the transverse orientation specimens. See Table 5-9.

The average USE of the surveillance weld metal Charpy specimens resulted in an average energy decrease of 20 ft-lb after irradiation. This results in an irradiated average USE of 124 ft-lb for the weld metal specimens. See Table 5-9.

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1-2 The average USE of the weld HAZ metal Charpy specimens resulted in an average energy decrease of 40 ft-lb after irradiation. This results in an irradiated average USE of 118 ft-lb for the weld HAZ metal. See Table 5-9.

A comparison, as presented in Table 5-10, of the Farley Unit 2 reactor vessel surveillance material test results with the Regulatory Guide 1.99, Revision 2113 predictions led to the following conclusions:

- The measured 30 ft-lb shift in transition temperature values of the intermediate shell plate B7212-1 specimens contained inCapsule V (longitudinal and transverse orientations) are less than the Regulatory Guide 1.99, Revision 2E3, predictions.

- The measured 30 ft-lb shift in transition temperature value of the surveillance weld metal specimens contained in Capsule V is less than the Regulatory Guide 1.99, Revision 2El3, prediction.

- The measured percent decrease in Upper Shelf Energy (USE) for all the plate and weld surveillance materials in Capsule V are less than the Regulatory 1.99, Revision 2E[l, predictions.

The calculated end-of-license (54 EFPY) neutron fluence (E> 1.0 MeV) at the core midplane for the Joseph M. Farley Unit 2 reactor vessel using the Regulatory Guide 1.99, Revision 2[1I attenuation formula (i.e., Equation #3 in the guide) are as follows:

2 Calculated: Vessel inner radius* =5.76E+19 n/cm 2

Vessel 1/4 thickness = 3.59E+19 n/cm Vessel 3/4 thickness = 1.40E+19 n/cm 2

• Clad/base metal interface (From Table 6-2).

All beltline materials are expected to have an USE greater than 50 ft-lb through end of license (EOL, 54 EFPY) as required by 10CFR50, Appendix G[21.

The service period of applicability for the Pressure-Temperature Limit Curves labeled for 33.8 EFPY in WCAP-14689, Revision 4[3], must be reduced to account for the updated neutron fluence projections and vessel material chemistry factors calculated as part of the Surveillance Capsule V analysis. The new service period for these Pressure-Temperature Limit Curves is 32.8 EFPY.

Appendix A of this report provides the validation of the radiation transport models based on the neutron dosimetry measurements. Appendix B provides the load-time records for individual instrumented Charpy specimen tests. Appendix C presents the individual Charpy V-notch plots for each surveillance capsule and the program input data, which were curve-fit using a symmetric hyperbolic tangent curve-fitting program (CVGRAPH, Version 5.3). Appendix D provides the credibility evaluation of the Farley Unit 2 surveillance program.

WCAP-16918-NP April 2008 Revision 1

2-1 2 INTRODUCTION This report presents the results of the examination of Capsule V, the sixth and final capsule removed from the reactor, as part of Southern Nuclear Operating Company's surveillance program for monitoring the effects of neutron irradiation on the Joseph M. Farley Unit 2 reactor pressure vessel materials under actual operating conditions.

The surveillance program for the Farley Unit 2 Nuclear Plant reactor pressure vessel materials was designed and recommended by the Westinghouse Electric Corporation. A description of the surveillance program and the pre-irradiation mechanical properties of the reactor vessel materials are presented in WCAP-8956, "Alabama Power Company Joseph M. Farley Nuclear Plant Unit No. 2 Reactor Vessel Radiation Surveillance Program143. The surveillance program was planned to cover the 40-year design life of the reactor pressure vessel and was based on ASTM E185-73, "Standard Recommended Practice for Surveillance Tests for Nuclear Reactor Vessels"'51 . Capsule V was removed from the reactor after 21.82 EFPY of exposure and shipped to the remote metallographic facility (RMF) at the Westinghouse science and technology department (STD), where the post-irradiation mechanical testing of the Charpy V-notch impact and tensile surveillance specimens was performed.

This report summarizes the testing of and the post-irradiation data obtained from Surveillance Capsule V removed from the Southern Nuclear Operating Company Farley Unit 2 reactor vessel and discusses the analysis of the data.

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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 Farley Unit 2 reactor pressure vessel beltline) are well documented in the literature. Generally, low alloy ferritic materials show an increase in hardness and tensile properties and a decrease in ductility and toughness during high-energy irradiation.

A method for ensuring the integrity of reactor pressure vessels has been presented in "Fracture Toughness Criteria for Protection Against Failure," Appendix G to Section XI of the ASME Boiler and Pressure Vessel Code16 3. 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[7') 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 (Kic curve) which appears in Appendix G to the ASME Code[63. The Klc 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 K1c curve, allowable stress intensity factors can be obtained for this material as a function of temperature. Allowable operating limits can then be determined using these allowable stress intensity factors.

RTNDT and, in turn, the operating limits of nuclear power plants can be adjusted to account for the effects of radiation on the reactor vessel material properties. The changes in mechanical properties of a given reactor pressure vessel steel, due to irradiation, can be monitored by a reactor vessel surveillance program, such as the Farley Unit 2 reactor vessel radiation surveillance program 4 ], in which a surveillance capsule is periodically removed from the operating nuclear reactor and the encapsulated specimens tested. The increase in the average Charpy V-notch 30 ft-lb temperature (ARTNDT) due to irradiation is added to the initial RTNDT, along with a margin (M) to cover uncertainties, to adjust the RTNDT (ART) for radiation embrittlement. This ART (RTNDT initial + M + ARTNDT) is used to index the material to the K1 , 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- 16918-NP April 2008 Revision 1

4-1 4 DESCRIPTION OF PROGRAM Six surveillance capsules for monitoring the effects of neutron exposure on the Farley Unit 2 reactor pressure vessel core region (beltline) materials were inserted in the reactor vessel prior to initial plant start-up. The six capsules were positioned in the reactor vessel between the neutron pads and the vessel wall as shown in Figure 4-1. The vertical center of the capsules is opposite the vertical center of the core.

Capsule V was removed after 21.82 EFPY of plant operation. This capsule contained Charpy V-notch, tensile, and 1/2T-compact tension (CT) fracture mechanics specimens made from intermediate shell plate B7212-1 (Heat #C7466-1) and manual metal arc weld metal identical to intermediate shell longitudinal weld seam 19-923B (Heat #BOLA). In addition, this capsule contained Charpy V-notch specimens from the weld heat-affected zone (HAZ) metal of intermediate shell plate B7212-l and pre-cracked bend bar specimens from intermediate shell plate B7212-1.

Test material obtained from intermediate shell plate B7212-1 (after the thermal heat treatment and forming of the plate) was taken at least one plate thickness from the quenched ends of the plate. All test specimens were machined from the 1/44 thickness locations of the plate after performing a simulated post-weld stress-relieving treatment on the test material. Specimens from weld metal and heat-affected-zone metal were machined from a stress-relieved weldment joining intermediate shell plate B7212-1 and intermediate shell plate B7203-1. All heat-affected-zone specimens were obtained from the weld heat-affected-zone of intermediate shell plate B7212-1.

Charpy V-notch impact specimens from intermediate shell plate B7212-1 were machined both in the longitudinal orientation (longitudinal axis of the specimen parallel to the major rolling direction) and transverse orientation (longitudinal axis of the specimen perpendicular to the major rolling direction).

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

Tensile specimens from intermediate shell plate B7212-1 were machined in both the longitudinal and transverse orientation. Tensile specimens from the weld metal were oriented with the long dimension of the specimen perpendicular to the weld direction.

Bend bar specimens from plate B7212-1 were machined with the longitudinal axis of specimens oriented normal to the rolling direction of the plate such that the simulated crack would propagate in the rolling direction of the plate. All specimens were fatigue pre-cracked according to ASTM E3991' 1.

Compact tension test specimens from plate B7212-1 were machined in both the longitudinal and transverse orientations. Compact tension test specimens from the weld metal were machined perpendicular to the weld direction with the notch oriented in the direction of the weld. All specimens were fatigue pre-cracked according to ASTM E3991' 1.

The chemical composition measurements and heat treatment of the surveillance material is presented in Tables 4-1 through 4-2. The chemical analysis reported in Table 4-1 was obtained from unirradiated material used in the surveillance program[4] and from irradiated capsule W specimens[ 91.

WCAP-16918-NP April 2008 Revision I

4-2 Capsule V contained dosimeter wires of pure copper, iron, nickel, and aluminum-0.15 weight percent cobalt (cadmium-shielded and unshielded). In addition, cadmium-shielded dosimeters of neptunium (Np237) and uranium (U 238) were placed in the capsule to measure the integrated flux at specific neutron energy levels.

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

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

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

WCAP- 16918-NP April 2008 Revision 1

4-3 Table 4-1 Chemical Composition (wt %) of the Farley Unit 2 Reactor Vessel Surveillance Materials Plate B7212-1 Weld Metal Element Unirradiated Data Capsule W*') Unirradiated Data Capsule W(1 )

C 0.21 0.224 <0.086 0.139 Mn 1.30 1.38 0.95 0.91 P 0.018 0.008 0.004 0.006 S 0.016 0.016 0.014 0.013 Si 0.24 0.208 0.34 0.291 Ni 0.60 0.59 0.90 0.88 Mo 0.49 0.49 0.23 0.243 Cr 0.15(2) 0.153 <0.01 0.027 Cu 0.20 0.186 0.03 0.026 Al 0.04 - - 0.003 - -

Co 0.027 0.005 0.010 0.005 V 0.003(2) <0.002 0.006 0.003 Sn 0.011(2) - - 0.002 - -

N2 0.006(2) - - 0.007 - -

Notes:

1. Chemical analysis by Westinghouse on irradiated Charpy specimens CL-34 and CW-41 removed from Capsule W.

2. Chemical analysis by Westinghouse.

3. This weld was fabricated by CE, Inc. by a manual metal arc process with /4 inch E8018C3 weld filler wire heat number BOLA. This weld is identical to that used for intermediate shell weld seam 19-923B.

Table 4-2 Heat Treatment of the Farley Unit 2 Reactor Vessel Surveillance Materials Material Temperature (IF) Time Coolant Intermediate Shell Plate Austenitizing: 1550/1650 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Water-Quenched B7212-1 Tempered: 1225 +/- 25 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Air-Cooled Stress Relief: 1150 +/- 25 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> Furnace Cooled to 600'F Weldment 1150 +/- 25 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> Furnace Cooled WCAP- 16918-NP April 2008 Revision 1

4-4 0*

REACTOR VESSEL CORE BARREL

\S r-NEUTRON PAD 2700 0 V

w Figure 4-1 Arrangement of Surveillance Capsules in the Farley Unit 2 Reactor Vessel WCAP-16918-NP April 2008 Revision 1

4-5 LEGEND: CL - LOWER SHELL PLATE B7212-1 (LONGITUDINAL)

CT - LOWER SHELL PLATE B7212-1 (TRANSVERSE) .-

CW- WELD METAL CH - HEAT-AFFECTED-ZONE MATERIAL 579*F 1 Cd MONITOR Bend Tensile Compact Compact Charpy Charpy Charpy Compact Bar

. CT CW8 CW7 CW6 CW5 C2 H( W6 C26 CW23 CH23 CL8 CL7 L i (( CW28 ' CH28 [CW25 CH25 CW22 CH22 TOP OF VESSEL

• CENTER 237 Np 2 38 U

Compact Charpy Charpy Dosimeter Tensile Charpy Charpy CW21 CH21 CW18 CH8 / CL6 I[ CT30 tCL30 CT27 C27 CW20 CH20 CW 17 CH17 289 CL5 T29 CL29 CT26 L26 CW19 19 CW 16 CL4 CT28 CL28 CT25 C.

CENTER -0 BOTTOM OF VESSEL Cu -

579*F 1A .Ili (C(d)

"I TORI Charpy Charpy Charpy Compact Compact Tensile TI23 CL23 CT20 CL20 CT8 CT7 CT6 CT5 CT5 CT-22 -CL-2-2 - T -9 -TCT16 CL19 CT4 Figure 4-2 Capsule V Diagram Showing the Location of Specimens, Thermal Monitors, and Dosimeters WCAP- 16918-NP April 2008 Revision 1

5-1 5 TESTING OF SPECIMENS FROM CAPSULE V 5.1 OVERVIEW The post-irradiation mechanical testing of the Charpy V-notch impact specimens and tensile specimens was performed in the remote metallographic facility (RMF) at the Westinghouse Science and Technology Center.

Upon receipt of the capsule at the laboratory, the capsule was opened per Procedure RMF 8804[003. The specimens and spacer blocks were carefully removed, inspected for identification number and checked against the master list in WCAP-8956, Revision 041. All items were in their proper locations.

Examination of the thermal monitors indicated that the 97.5% Pb, 2.5% Ag monitor melted, while the other did not. Based on this examination, the maximum temperature to which the specimens were exposed was greater than 579°F (304'C) and less than 590'F (310°C).

The testing of the Charpy V-notch and tensile specimens was performed in accordance with ASTM Specification E 185-821"] and Westinghouse Procedures RMF 8402[121 as detailed by Westinghouse Procedures RMF 8102[131 and RMF 8103[141.

The Charpy impact tests were performed per ASTM Specification E23-06 [1 51and Procedure RMF 8103[ 41 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. With this system, load-time and energy-time signals can be recorded in addition to the standard measurement of Charpy energy (ED). From the load-time curve, the load of general yielding (PGY), the time to general yielding (Toy), the maximum load (PM), and the time to maximum load (TM) can be determined. Under some test conditions, a sharp drop in load indicative of fast fracture was observed. The load at which fast fracture was initiated is identified as the fast fracture load (PF). If the fast load drop terminates well above zero load, the termination load is identified as the arrest load (PA).

The energy at maximum load (EM) was determined by comparing the energy-time record and the load-time record. The energy at maximum load is approximately equivalent to the energy required to initiate a crack in the specimen. Therefore, the propagation energy for the crack (Ep) is the difference between the total energy to fracture (ED) and the energy at maximum load (EM).

The yield stress (ry) was calculated from the three-point bend formula having the following expression[161:

L

'3Y =PGY 2 (Eq. 5-1)

B(W -a)' C where L = distance between the specimen supports in the impact testing machine; B = the width of the specimen measured parallel to the notch; W = height of the specimen, measured perpendicularly to the notch; a = notch depth. The constant C is dependent on the notch flank angle ((P), notch root radius (p),

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5-2 and the type of loading (i.e., pure bending or three-point bending). In three-point bending, for a Charpy specimen in which y = 450 and p = 0.010 in., Equation 5-1 is valid with C = 1.21.

Therefore, (for L = 4W),

GY =PGY L - 3.305P YW2 (Eq. 5-2)

B(W- a)2 1.21 B(W- 0 a)

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

7y = 33.3 PGy (Eq. 5-3) where uy is in units of psi and PGY 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-section area under the notch of the Charpy specimens:

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

Percent shear was determined from post-fracture photographs using the ratio-of-areas methods in compliance with ASTM E23-060l"' and A370-071"]I. 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 ASTM Specification E8-04[18 ] and E21-05[191 and Procedure RMF 81021"]1. 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 nine-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.

5.2 RESULTS The results of the Charpy V-notch impact tests performed on the various materials contained in Capsule V, which received a fluence of 8.73E+19 n/cm 2 (E> 1.0 MeV) in 21.82 EFPY of operation, are presented in Tables 5-1 through 5-10 and are compared with unirradiated results shown in Figures 5-1 through 5-12.

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5-3 The transition temperature increases and USE decreases for the Capsule V materials are summarized in Table 5-9 and led to the following results:

Irradiation of the reactor vessel intermediate shell plate B7212-1 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 196.0'F and an irradiated 50 ft-lb transition temperature of 240.1PF. This results in a 30 ft-lb transition temperature increase of 218.3°F and a 50 ft-lb transition temperature increase of 230.1 F for the longitudinal orientation specimens. See Table 5-9.

Irradiation of the reactor vessel intermediate shell plate B7212-1 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 207.8°F and an irradiated 50 ft-lb transition temperature of 234.3°F. This results in a 30 ft-lb transition temperature increase of 215.3°F and a 50 ft-lb transition temperature increase of 200.7°F for the transverse orientation specimens. See Table 5-9.

Irradiation of the surveillance weld metal Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 22.0°F and an irradiated 50 ft-lb transition temperature of 61.8°F. This results in a 30 ft-lb transition temperature increase of 56.5°F and a 50 ft-lb transition temperature increase of 77.2°F. See Table 5-9.

Irradiation of the weld heat-affected-zone (HAZ) metal Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 26.2°F and an irradiated 50 ft-lb transition temperature of 52.4°F. This results in a 30 ft-lb transition temperature increase of 322.4°F and a 50 ft-lb transition temperature increase of 257.7°F. See Table 5-9.

The average USE of the intermediate shell plate B7212-1 Charpy specimens (longitudinal orientation) resulted in an average energy decrease of 44 ft-lb after irradiation. This results in an irradiated average USE of 86 ft-lb for the longitudinal orientation specimens. See Table 5-9.

The average USE of the intermediate shell plate B7212-1 Charpy specimens (transverse orientation) resulted in an average energy decrease of 26 ft-lb after irradiation. This results in an irradiated average USE of 69 ft-lb for the transverse orientation specimens. See Table 5-9.

The average USE of the surveillance weld metal Charpy specimens resulted in an average energy decrease of 20 ft-lb after irradiation. This results in an irradiated average USE of 124 ft-lb for the weld metal specimens. See Table 5-9.

The average USE of the weld HAZ metal Charpy specimens resulted in an average energy decrease of 40 ft-lb after irradiation. This results in an irradiated average USE of 118 ft-lb for the weld HAZ metal. See Table 5-9.

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5-4 A comparison, as presented in Table 5-10, of the Farley Unit 2 reactor vessel surveillance material test results with the Regulatory Guide 1.99, Revision 2[1] predictions led to the following conclusions:

- The measured 30 ft-lb shift in transition temperature values of the intermediate shell plate B7212-1 specimens contained in Capsule V (longitudinal and transverse orientations) are less than the Regulatory Guide 1.99, Revision 2, predictions.

- The measured 30 ft-lb shift in transition temperature value of the surveillance weld metal contained in Capsule V is less than the Regulatory Guide 1.99, Revision 2EI), prediction.

- The measured percent decrease in upper shelf energy (USE) for all the plate and weld surveillance materials in Capsule V are less than the Regulatory 1.99, Revision 21",

predictions.

All beltline materials are expected to have an USE greater than 50 ft-lb through end of license (EOL, 54 EFPY) as required by 10CFR50, Appendix G The service period of applicability for the Pressure-Temperature Limit Curves labeled for 33.8 EFPY in WCAP-14689, Revision 4[3], must be reduced to account for the updated neutron fluence projections and vessel material chemistry factors calculated as part of the Surveillance Capsule V analysis. The new service period for these Pressure-Temperature Limit Curves is 32.8 EFPY.

The fracture appearance of each irradiated Charpy specimen from the various surveillance Capsule V materials is shown in Figures 5-13 through 5-16 and shows an increasingly ductile or tougher appearance with increasing test temperature.

The load-time records for individual instrumented Charpy specimen tests are shown in Appendix B.

Appendix C presents the individual CVGRAPH, Version 5.3, Charpy V-notch plots for each surveillance capsule and the program input data. The credibility evaluation of the Farley Unit 2 surveillance program is presented in Appendix D of this report. The evaluation concluded that the Farley Unit 2 surveillance data is deemed not credible for the weld specimens and credible for the plate specimens.

5.3 TENSILE TEST RESULTS The results of the tensile tests performed on the intermediate shell plate specimens (longitudinal and transverse orientations) and weld metal contained in Capsule V irradiated to 8.73E+19 n/cm2 (E> 1.0 MeV) are presented in Table 5-11 and are compared with unirradiated results[43 as shown in Figures 5-17 through 5-19.

The results of the tensile tests performed on the intermediate shell plate B7212-1 (longitudinal orientation) specimens at 550'F indicated that irradiation to 8.73E+19 n/cm 2 (E> 1.0 MeV) caused approximately a 25 ksi increase in the 0.2 percent offset yield strength and approximately a 19 ksi increase in the ultimate tensile strength when compared to unirradiated dataE4 ]. See Figure 5-17.

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5-5 The results of the tensile tests performed on the intermediate shell plate B7212-1 (transverse orientation) specimens at 550'F indicated that irradiation to 8.73E+ 19 n/cm 2 (E> 1.0 MeV) caused approximately a 27 ksi increase in the 0.2 percent offset yield strength and approximately a 21 ksi increase in the ultimate tensile strength when compared to unirradiated data[43. See Figure 5-18.

The results of the tensile tests performed on the surveillance weld metal specimens at 550'F indicated that irradiation to 8.73E+19 n/cm 2 (E> 1.0 MeV) caused approximately a 12 ksi increase in the 0.2 percent offset yield strength and approximately a 7 ksi increase in the ultimate tensile strength when compared to unirradiated data[4 ]. See Figure 5-19.

The fractured tensile specimens for the surveillance plate material are shown in Figures 5-20 and 5-21, while the fractured tensile specimens for the surveillance weld metal are shown in Figure 5-22. The engineering stress-strain curves for the tensile tests are shown in Figures 5-23 through 5-25.

5.4 BEND BAR AND COMPACT TENSION SPECIMEN TESTS Per the surveillance capsule testing contract with Southern Nuclear Operating Company, the bend bar and 1/2T Compact Tension Specimens were not tested.

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5-6 Table 5-1 Charpy V-notch Data for the Farley Unit 2 Intermediate Shell Plate B7212-1 Specimens Irradiated to a Fluence of 8.73E+19 n/cm 2 (E> 1.0 MeV) (Longitudinal Orientation)

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

CL30 50 10 10.5 14 10 0.25 2 CL19 180 82 21 28 20 0.51 20 CL25 210 99 33 45 29 0.74 30 CL17 220 104 32 43 28 0.71 30 CL28 225 107 35 47 29 0.74 40 CL22 230 110 55 75 42 1.07 50 CL18 250 121 64 87 49 1.24 70 CL24 260 127 77 104 58 1.47 90 CL16 265 129 74 100 51 1.30 80 CL27 290 143 35 47 34 0.86 50 CL23 290 143 53 72 55 1.40 75 CL26 315 157 92 125 68 1.73 100 CL21 340 171 80 108 72 1.83 100 CL20 370 188 78 106 66 1.68 100 CL29 380 193 92 125 69 1.75 100 WCAP- 16918-NP April 2008 Revision 1

5-7 Table 5-2 Charpy V-notch Data for the Farley Unit 2 Intermediate Shell Plate B7212-1 Specimens Irradiated to a Fluence of 8.73E+19 n/cm2 (E> 1.0 MeV) (Transverse Orientation)

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

CT25 100 38 9 12 11 0.28 10 CT24 200 93 21 28 22 0.56 20 CT19 205 96 30 41 30 0.76 30 CT27 215 102 36 49 34 0.86 50 CT16 225 107 36 49 36 0.91 60 CT23 230 110 55 75 48 1.22 70 CT17 240 116 55 75 47 1.19 75 CT22 260 127 66 89 58 1.47 90 CT29 275 135 59 80 50 1.27 90 CT20 280 138 69 94 56 1.42 95 CT18 305 152 50 68 46 1.17 80 CT28 345 174 65 88 58 1.47 100 CT30 375 191 70 95 56 1.42 100 CT21 400 204 61 83 60 1.52 100 CT26 410 210 79 107 59 1.50 100 WCAP-16918-NP April 2008 Revision 1

5-8 Table 5-3 Charpy V-notch Data for the Farley Unit 2 Surveillance Weld Metal Irradiated to a Fluence of 8.73E+19 n/cm 2 (E> 1.0 MeV)

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

CW28 -25 -32 6 8 10 0.25 5 CW21 20 -7 26 35 27 0.69 20 CW25 30 -1 54 73 45 1.14 30 CW29 40 4 (1) (1) (1) (1) (1)

CW30 40 4 33 45 31 0.79 30 CW24 50 10 36 49 32 0.81 35 CW27 70 21 69 94 52 1.32 75 CW22 100 38 61 83 48 1.22 75 CW20 125 52 89 121 65 1.65 80 CW26 145 63 88 119 64 1.63 90 CW17 165 74 100 136 81 2.06 90 CW19 185 85 103 140 78 1.98 95 CW16 230 110 137 186 87 2.21 100 CW23 250 121 131 178 76 1.93 100 CW18 260 127 125 170 84 2.13 100 Note:

1. Data not available.

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5-9 Table 5-4 Charpy V-notch Data for the Farley Unit 2 HAZ Material Irradiated to a Fluence of 8.73E+19 n/cm 2 (E> 1.0 MeV)

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

CH23 -80 -62 9 12 22 0.56 2 CH29 -15 -26 17 23 15 0.38 10 CH24 25 -4 24 33 15 0.38 20 CH26 35 2 22.5 31 14 0.36 20 CH22 40 4 54 73 38 0.97 40 CH27 45 7 69 94 51 1.30 60 CH18 50 10 55 75 41 1.04 50 CH17 70 21 13 18 14 0.36 30 CH21 70 21 70 95 47 1.19 70 CH16 90 32 94 127 70 1.78 80 CH19 115 46 107 145 85 2.16 100 CH20 155 68 122 165 89 2.26 100 CH30 200 93 120 163 94 2.39 100 CH28 250 121 134 182 95 2.41 100 CH25 260 127 107 145 72 1.83 100 WCAP- 16918-NP April 2008 Revision I

5-10 Table 5-5 Instrumented Charpy Impact Test Results for the Farley Unit 2 Intermediate Shell Plate B7212-1 Specimens Irradiated to a Fluence of 8.73E+19 n/cm 2 (E> 1.0 MeV) (Longitudinal Orientation)

Normalized Energies General Charpy (ft-lb/in2) Yield Time to Test Energy Load Yield Max. Time to Fract. Arrest Yield Flow Sample Temp. ED Total At PM Prop. PGY tGy Load, PM Load, Load, Stress, Stress No. (OF) (ft-lb) ED/A EM/A Ep/A (Ib) (msec) PM (lb) (msec) PF (ib) PA (lb) av (ksi) (ksi)

CL30 50 10.5 85 48 37 3407 0.13 4117 0.18 4117 0 113 125 CL19 180 21 169 121 48 3047 0.12 4289 0.30 4289 0 101 122 CL25 210 33 266 177 89 3068 0.13 4877 0.39 4866 433 102 132 CL17 220 32 258 185 73 3420 0.13 4801 0.39 4770 330 114 137 CL28 225 35 282 185 97 3414 0.13 4981 0.39 4937 943 114 140 CL22 230 55 443 250 193 3314 0.14 5164 0.50 4906 1386 110 141 CL18 250 64 516 242 274 3126 0.13 4931 0.49 4628 1658 104 134 CL24 260 77 620 234 387 3823 0.14 5175 0.47 4252 2319 127 150 CL16 265 74 596 169 427 3542 0.13 5131 0.38 4394 2274 118 144 CL27 290 35 282 177 105 3258 0.14 4651 0.38 4651 1212 109 132 CL23 290 53 427 209 218 3233 0.12 5009 0.43 4849 1735 108 137 CL26 315 92 741 226 516 2932 0.13 4942 0.47 N/A N/A 98 131 CL21 340 80 645 209 435 3020 0.13 4562 0.46 N/A N/A 101 126 CL20 370 78 628 226 403 2900 0.13 4593 0.48 N/A N/A 97 125 CL29 380 92 741 193 548 3016 0.12 4814 0.42 N/A N/A 100 130 WCAP- 16918-NP April 2008 Revision 1

5-11 Table 5-6 Instrumented Charpy Impact Test Results for the Farley Unit 2 Intermediate Shell Plate B7212-1 Specimens Irradiated to a Fluence of 8.73E+19 n/cm 2 (E> 1.0 MeV) (Transverse Orientation)

Normalized Energies General Charpy (ft-lb/in2 ) Yield Time to Test Energy Load Yield Max. Time to Fract. Arrest Yield Flow Sample Temp. ED Total At PM Prop. PGY tGV Load, PM Load, Load, Stress, Stress No. (0 F) (ft-lb) ED/A EM/A Ep/A (lb) (msec) PM (lb) (msec) PF (Ib) PA (Ib) cr (ksi) (ksi)

CT25 100 9 73 38 35 3285 0.13 3631 0.16 3631 0 109 115 CT24 200 21 169 113 56 2810 0.12 4231 0.28 4223 0 94 117 CT19 205 30 242 161 81 3153 0.13 4646 0.34 4633 661 105 130 CT27 215 (1) (1) (1) (1) (1) (1) (1) (1) (1) (1) (1) (1)

CT16 225 36 290 169 121 2879 0.12 4582 0.36 4561 1304 96 124 CT23 230 55 443 177 266 3073 0.13 4895 0.38 4548 1939 102 133 CT17 240 55 443 177 266 3070 0.14 4871 0.40 4727 1973 102 132 CT22 260 66 532 185 346 3082 0.13 4893 0.40 4593 3132 103 133 CT29 275 59 475 177 298 3281 0.14 4627 0.39 4393 3487 109 132 CT20 280 69 556 226 330 3072 0.13 4856 0.47 3138 2522 102 132 CT18 305 50 403 185 218 3246 0.13 4648 0.41 4494 2598 108 131 CT28 345 65 524 169 355 2953 0.12 4579 0.39 N/A N/A 98 125 CT30 375 70 564 185 379 2959 0.13 4670 0.40 N/A N/A 99 127 CT21 400 61 491 193 298 2843 0.13 4225 0.45 N/A N/A 95 118 CT26 410 (1) (1) (1) (1) (1) (1) (1) (1) (1) (1) (1) (1)

Note:

1. Data not available.

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5-12 Table 5-7 Instrumented Charpy Impact Test Results for the Farley Unit 2 Surveillance Weld Metal Irradiated to a Fluence of 8.73E+19 n/cm2 (E> 1.0 MeV)

Normalized Energies General Charpy (ft-lb/in 2 ) Yield Time to Test Energy Load Yield Max. Time to Fract. Arrest Yield Flow Sample Temp. ED Total At PM Prop. PGY tGY Load, PM Load, Load, Stress, Stress No. (OF) (ft-lb) ED/A EM/A Ep/A (lb) (msec) PM (lb) (msec) PF (lb) PA (lb) gy (ksi) (ksi)

CW28 -25 6 48 24 24 2180 0.10 2323 0.12 2320 0 73 75 CW21 20 26 209 145 64 2876 0.12 4180 0.36 4164 0 96 117 CW25 30 54 435 322 113 3194 0.14 4441 0.68 4187 489 106 127 CW29 40 (1) (1) (1) (1) (1) (1) (1) (1) (1) (1) (1) (1)

CW30 40 33 266 177 89 2762 0.13 4341 0.41 4325 656 92 118 CW24 50 36 290 201 89 3049 0.13 4154 0.47 4146 1176 102 120 CW27 70 69 556 355 201 3280 0.14 4414 0.69 4294 1890 109 128 CW22 100 61 491 226 266 2429 0.12 4160 0.52 4013 1221 81 110 CW20 125 89 717 314 403 2795 0.13 4251 0.68 3704 1605 93 117 CW26 145 88 709 306 403 2605 0.12 4142 0.68 3350 1976 87 112 CW17 165 100 806 306 500 2603 0.12 4194 0.68 N/A N/A 87 113 CW19 185 103 830 298 532 2607 0.13 4111 0.67 N/A N/A 87 112 CW16 230 137 1104 306 798 2862 0.14 4153 0.68 N/A N/A 95 117 CW23 250 131 1056 306 749 2598 0.13 4078 0.68 N/A N/A 87 111 CW18 260 125 1007 298 709 2627 0.12 4080 0.67 N/A N/A 87 112 Note:

I. Data not available.

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5-13 Table 5-8 Instrumented Charpy Impact Test Results for the Farley Unit 2 HAZ Metal Irradiated to a Fluence of 8.73E+19 n/cm 2 (E> 1.0 MeV)

Normalized Energies General Charpy (ft-lb/in 2) Yield Time to Test Energy Load Yield Max. Time to Fract. Arrest Yield Flow Sample Temp. ED Total At PM Prop. PGY tGY Load, PM Load, Load, Stress, Stress No. (OF) (ft-lb) ED/A EM/A Ep/A (ib) (msec) PM (lb) (msec) PF (lb) PA (Ib) GY (ksi) (ksi)

CH23 -80 9 73 47 25 3717 0.15 4049 0.18 4036 0 124 129 CH29 -15 17 137 79 58 3532 0.14 4554 0.23 4554 0 118 135 CH24 25 24 193 137 56 3279 0.13 4726 0.32 4692 0 109 133 CH26 35 22.5 181 129 52 2995 0.13 4472 0.32 4425 0 100 124 CH22 40 54 435 177 258 3388 0.14 5002 0.41 4828 0 113 140 CH27 45 69 556 250 306 3095 0.13 4804 0.52 4302 451 103 132 CH18 50 55 443 215 228 3136 0.13 4761 0.48 4401 0 104 131 CH17 70 13 105 40 64 2208 0.11 2810 0.16 2804 907 74 84 CH21 70 70 564 258 306 4265 0.16 4968 0.49 4552 556 142 154 CH16 90 94 757 355 403 3059 0.13 4909 0.68 3641 789 102 133 CH19 115 107 862 234 628 3213 0.14 4699 0.49 N/A N/A 107 132 CH20 155 122 983 274 709 3168 0.13 4765 0.53 N/A N/A 105 132 CH30 200 120 967 161 806 2703 0.12 4635 0.39 N/A N/A 90 122 CH28 250 b (1) (1) (1) (1) (1) (1) (a (1) (1) (1) (1) (1)

CH25 260 107 862 242 620 3067 10.14 4477 0.51 N/A IN/A 102 126 Note:

I1. Data not available.

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5-14 Table 5-9 Effect of Irradiation to 8.73E+19 n/cm 2 (E> 1.0 MeV) on the Charpy V-Notch Toughness Properties of the Farley Unit 2 Reactor Vessel Surveillance Capsule V Materials Average 30 (ft-lb)(1 ) Average 35 mil Lateral(2) Average 50 ft-lbW) Average Energy Absorptiontl)

Material Transition Temperature (IF) Expansion Temperature (IF) Transition Temperature (IF) at Full Shear (ft-lb)

Unirradiated Irradiated AT Unirradiated Irradiated AT Unirradiated Irradiated AT Unirradiated Irradiated AE Intermediate Shell Plate -22.3 196.0 218.3 1.0 224.4 223.4 10.0 240.1 230.1 130 86 -44 B7212-1 (Longitudinal)

Intermediate Shell Plate -7.5 207.8 215.3 26.7 215.9 189.2 33.6 234.3 200.7 95 69 -26 B7212-1 (Transverse)

Weld (Ht. Metal MOl -34.5 22.0 56.5 -23.5 41.3 64.8 -15.4 (Ht.# BOLA)I 61.8 77.2 144 124 -20 I

HAZ Metal -296.2 26.2 322.4 -183.6 49.7 233.3 -205.3 52.4 257.7 158 118 -40 Notes:

I. "Average" is defined as the value mathematically determined by CVGRAPH from the data points of the Charpy tests (see Figures 5-1, 5-4, 5-7, and 5-10).

2. "Average" is defined as the value mathematically determined by CVGRAPH from the data points of the Charpy tests (see Figures 5-2, 5-5, 5-8, and 5-11).

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5-15 Table 5-10 Comparison of the Farley Unit 2 Surveillance Material 30 ft-lb Transition Temperature Shifts and Upper Shelf Energy Decreases with Regulatory Guide 1.99, Revision 2, Predictions 30 ft-lb Transition Upper Shelf Energy Temperature Shift Decrease Fluence (x 10' 9 n/cm 2, Predicted Measured Predicted Measured 2

Material Capsule E > 1.0 MeV) (OF)() (OF)( ) (%)1) (%)(3)

Intermediate Shell U 0.605 128.0 105.5 26 27 Plate B7212-1 (Longitudinal) W 1.73 171.5 167.7 33 22 X 2.98 192.1 164.8 37 26 Z 4.92 208.5 200.1 42 28 Y 6.79 217.2 214.2 45 36 V 8.73 222.9 218.3 48 34 Intermediate Shell U 0.605 128.0 124.0 26 27 Plate B7212-1 (Transverse) W 1.73 171.5 168.5 33 21 X 2.98 192.1 200.1 37 28 Z 4.92 208.5 195.8 42 29 Y 6.79 217.2 231.0 45 42 V 8.73 222.9 215.3 48 27 Surveillance U 0.605 32.8 -28.4 17 8 Program Weld Metal W 1.73 44.0 7.0 22 0 X 2.98 49.2 -15.6 24 0 Z 4.92 53.4 10.2 27 8 Y 6.79 55.7 69.1 30 5 V 8.73 57.1 56.5 32 14 Heat Affected U 0.605 - - - 219.8 - -- 30 Zone Material W 1.73 - - - 268.8 .... 20 X 2.98 -- - 230.5 --- 19 Z 4.92 - - - 263.8 --- 20 Y 6.79 --- 269.6 35 V 8.73 --- 322.4 25 Notes:

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

2. Calculated using measured Charpy data plotted using CVGRAPH, Version 5.3 (See Appendix C).

3. Values are based on the definition of upper shelf energy given in ASTM El85-82E' 11 .

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5-16 Table 5-11 Tensile Properties of the Farley Unit 2 Capsule V Reactor Vessel Surveillance Materials Irradiated to 8.73E+19 n/cm 2 (E> 1.0 MeV)

Test 0.2% Yield Ultimate Fracture Fracture Fracture Uniform Total Reduction Sample Temperature Strength Strength Load Stress Strength Elongation Elongation in Area Number Material (OF) (ksi) (ksi) (kip) (ksi) (ksi) (%) (%) (%)

CL4 Longitudinal 230 95.2 112.0 4.05 189.4 82.5 8.7 18.2 56 CL5 Longitudinal 290 94.7 109.5 3.83 178.9 77.9 8.9 19.5 56 CL6 Longitudinal 550 87.6 108.0 4.00 187.1 81.5 9.8 20.0 56 CT4 Transverse 240 95.2 111.0 4.25 172.7 86.6 9.5 18.0 50 t

CT5 1) Transverse 320 90.7 108.0 4.35 167.1 88.5 10.4 17.9 47 CT6 Transverse 550 89.1 109.0 4.55 132.6 92.7 10.5 15.9 30 CW4 Weld 80 82.0 92.3 2.70 203.4 55.0 11.3 26.3 73 CW5 Weld 200 77.4 86.6 2.60 195.9 53.0 9.8 22.5 73 CW6 Weld 550 68.8 85.6 2.60 202.1 53.0 9.5 22.2 74 Note:

1. Specimen broke at edge of clip gage. Curve reconstructed from Load vs. Time data.

WCAP- 16918-NP April 2008 Revision 1

5-17 INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02/06/2008 10:34 AM Data Set(s) Plotted CurIve Pla it Capsule Material Or!. Heat #

1 UNIRR Farley 2 SA533BI LT B7212-1 2 Farley Farley 22 U SA533BI LT B7212-1 3 w SA533B I LT B7212-1 4 Farley 2 x SA533B1I LT B7212-1 5 Farley 2 z SA533B I LT B7212-1 6 Farley 2 Y SA533B!I LT B7212-1 7 Farley 2 V SA533BI LT B7212-1 300-250 40 200-0 U.

L 150 z

100 50 0 -

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F 0 1 0 2 A 4 v 5 0 6 m 7 Results Curve, Fluence LSE USE d-USE T @30 d.T @Y0 T @50 d-T @50 2.2 130.0 .0 -22.3 .0 10.0 .0 2 2. 2 94. 4 -35.6 83. 2 105.5 141.0 131. 0 2.2 102.0 -28.0 145.4 167.7 185.4 175.4 4 2. 2 96.3 - 33.7 142. 5 164.8 186.3 176. 3 5 2. 2 93.8 -36.2 177. 8 200. 1 208. 8 198. 8 6 2.2 83.0 -47.0 191.9 214.2 222. 6 212.6 7 2.2 86.0 -44.0 196.0 218.3 240. 1 230. I Figure 5-1 Charpy V-Notch Impact Energy vs. Temperature for Farley Unit 2 Reactor Vessel Intermediate Shell Plate B7212-1 Specimens (Longitudinal Orientation)

WCAP- 16918-NP April 2008 Revision 1

5-18 INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02/06/2008 03:19 PM Data Set(s) Plotted Culllve Plant Capsule M~aterial Ori. Heat #

2 Farley 2 UNIRR SA533B I LT B7212-1 Farley 2 U SA533B I LT B7212-1 3 Farley 2 w SA533B I LT B7212-1 4 Farley 2 X SA533B I LT B7212-1 5 Farley 2 z SA533BI LT B7212-1 6 Farley 2 Y SA533B I LT B7212-1 7 Farley 2 V SA533B I LT B7212-1 200 150 E

C 500 0

04-

-300.0 0.0 300.0 600.0 Temperature in Deg F 0 1 02 3 A 4 v 5 0 6 m 7 Results Curv'e Pluence LSE USE d-USE T @35 d-T @35 1 .0 90. 8 .0 1.0 .0 2 .0 85. 2 -5.6 122.4 121.4 3 .0 85. 6 -5. 1 167. 9 166.9 4 .0 70.4 -20.4 182. 7 181.7 5 .0 66. 8 -24.0 212. I 211. 1 6 .0 66. 1 -24. 7 217. 1 216. 1 7 .0 75. 4 -15.4 224. 4 223. 4 Figure 5-2 Charpy V-Notch Lateral Expansion vs. Temperature for Farley Unit 2 Reactor Vessel Intermediate Shell Plate B7212-1 Specimens (Longitudinal Orientation)

WCAP- 16918-NP April 2008 Revision 1

5-19 INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02/22J2008 11:50 AM Data Set(s) Plotted Plant Caipsule M~aterial Ori. Heat #

1 Farley 2 UNTRR SA533B I LT B7212-1 2 Farley 2 U SA533B I LT B7212-1 3 Farley 2 w SA533B I LT B7212-1 4 Farley 2 x SA533B I LT B7212-1 5 Faney 2 z SA533B I LT B7212-1 6 Farley 2 y SA533B I LT B7212-1 7 Farley 2 V SA533B I LT B7212-1 125 100 I-75 U,

it 50 25j 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 02 03 A 4 v 5 0 6 m 7 Results Curs-e Fluence LSE USE d-USE T @50 d-T @50 1 .0 100.0 .0 39. 3 .0 2 .0 100.0 .0 150.4

.0 100.0 .0 188.4 149. I 4 .0 100. 0 .0 198.5 159. 2 5 .0 100. 0 .0 209.0 169.7 6 .0 100. 0 .0 211.0 171.7

.0 100.0 .0 233.3 194.0 Figure 5-3 Charpy V-Notch Percent Shear vs. Temperature for Farley Unit 2 Reactor Vessel Intermediate Shell Plate B7212-1 Specimens (Longitudinal Orientation)

WCAP- 16918-NP April 2008 Revision I

5-20 INTERMEDIATE SHELL PLATE B7212-1 (TRANSVERSE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02/22/2008 12:34 PM Data Set(s) Plotted Planlt Capsule Material Ori. Heat #

Farley 2 UNIRR SA533B ! TL 2 B7212-1 Farley 2 U SA533B I TL B7212-1 3 Farley 2 w SA533BI TL B7212-1 4 Farley 2 x SA533Bl TL B7212-1 5 Farley 2 z SA533BI TL B7212-1 6 Farley 2 Y SA533BI TL B7212-1 7 Farley 2 V SA533BI TL B7212-1 300 250 4 200-0 IL p150 100 50 0

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F 0 1 02 3 A 4 v 5 6 ,7 Results Curve Fluence LSE USE d-USE T @30 d-T @30 T @50 d-T @50

2. 2 69. 0 .0 -9.0 .0 28. 1 .0 2 2. 2 69. 0 .0 116.6 125.6 182.0 153. 9 3 2. 2 69. 0 .0 159.9 168.9 219. 1 191.0 4 2. 2 69. 0 .0 192.6 201.6 221.8 193. 7 5 2. 2 69.0 .0 188.3 197.3 231.2 203. I 6 2. 2 69. 0 .0 229. I 238. I 310.6 282. 5 7 2. 2 69.0 .0 207. 8 216. 8 234.3 206. 2 Figure 5-4 Charpy V-Notch Impact Energy vs. Temperature for Farley Unit 2 Reactor Vessel Intermediate Shell Plate B7212-1 Specimens (Transverse Orientation)

WCAP-16918-NP April 2008 Revision 1

5-21 INTERMEDIATE SHELL PLATE B7212-1 (TRANSVERSE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02/22/2008 12:36 PM Data Set(s) Plotted Ciirve Plant. Capsule Ori. Heat #

SMatetia 1 Farley 2 UNIRR SA5i33B I TL B7212-1 Farley 2 U SA533BI TL B7212-I 3 Farley 2 w SA533B I TL B7212-1 4 Farlev 2 X SA533B I TL B7212-1 5 Farle*, 2 z SA533B I TL B7212-1 6 Farlev 2 Y SA533B I TL B7212-1 7 Farle 2 V TL B7212-1 200 150 E

C

.2 5100 50 04-

-300.0 0.0 300.0 600.0 Temperature in Deg F 0 1 0 2 3 "4 v 5 m 7 Results Cuirve Fluenev LSE USE d-USE T @35 d-T @35 1 .0 72. 7 .0 26. 7 .0 2 .0 68.3 -4.4 147.0 120. 3 3 .0 69. 1 -3.6 183. 3 156.6 4 .0 62. 9 -9.8 214. 7 188.0 5 .0 53. 4 - 19. 3 226. 0 199.3 6 .0 44. A -27.9 266. 4 239.7 7 .0 56. 3 - 16.4 215. 9 189.2 Figure 5-5 Charpy V-Notch Lateral Expansion vs. Temperature for Farley Unit 2 Reactor Vessel Intermediate Shell Plate B7212-1 Specimens (Transverse Orientation)

WCAP-16918-NP April 2008 Revision 1

5-22 INTERMEDIATE SHELL PLATE B7212-1 (TRANSVERSE)

CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02/22/2008 12:34 PM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat #

arley 2 UNIRR SA533BI TL B7212-1 arley 2 U SA533BI TL B7212-1 3 Farley 2 w SA533BI TL B7212-1 4 Farley 2 x SA533B1I TL B7212-1 5 Farlev 2 z SA533BI TL B7212-1 6 Farle6 2 Y SA533B 1 TL B7212- 1 7 Far14 2 V SA533BI TL B7212- 1 125 100 75 CL 50 25 0-

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F 0 1 02 3 A 4 7 5 0 6 "7 Results Curve Fluence LSE USE d-USE T @50 d-T @5(0 1 .0 100.0 .0 49.7 .0 2 .0 100.0 .0 159.8 110. 1

'3 .0 100.0 .0 199.8 150. 1 4 .0 100.0 .0 203.0 153. 3 5 .0 tOo. 0 .0 209.7 160.0 6 .0 too. 0 .0 234. I 184.4 7 .0 100. 0 .0 218. 6 168. 9 Figure 5-6 Charpy V-Notch Percent Shear vs. Temperature for Farley Unit 2 Reactor Vessel Intermediate Shell Plate B7212-1 Specimens (Transverse Orientation)

WCAP- 16918-NP April 2008 Revision 1

5-23 SURVEILLANCE WED)METAL CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02/06/2008 04:58 PM Data Set(s) Plotted Curve Plant Capsuule M1IateriaI Ori. Heat #

1 'arey 2 UNIRR SMAW NA BOLA 2 arey 2 U SMAW NA BOLA 3 Farley 2 W SMAW NA BOLA 4 Farley 2 X SMAW NA BOLA 5 Farley 2 Z SMAW NA BOLA 6 Fancy 2 Y SMAW NA BOLA 7 Farley 2 V SMAW NA BOLA 300 250 4" 200 0

U.

F 150 ul z

> 100 50 0

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F 0 1 02 03 A 4 V 5 a 7 Results Curve Fluence LSE USE d-USE T @30 d-T @30 T @50 (1-T @50 1 2.2 144.0 .0 -34.5 .0 -15.4 .0 2 2.2 132.0 -12.0 -62.9 -28.4 -26.3 -10.9 3 2.2 144.0 .0 -27.5 7.0 -3.2 12.2 4 2.2 150.0 6.0 -50.1 -15.6 -17.9 -2.5 5 2.2 133.0 -11.0 -24.3 10.2 -2.0 13.4 6 2. 2 137.0 -7.0 34. 6 69. 1 50.2 65.6 7 2.2 124.0 -20.0 22.0 56.5 61.8 77.2 Figure 5-7 Charpy V-Notch Impact Energy vs. Temperature for Farley Unit 2 Reactor Vessel Surveillance Weld Metal Specimens WCAP- 16918-NP April 2008 Revision 1

5-24 SURVIILLA NCE WELl) METAL CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02/06/2008 05:04 PM Data Set(s) Plotted Curve Plant CZapsule Material OH. Heat #

2 Farley 2 UNIRR SMAW NA BOLA arley 2 U SMAW NA BOLA 3 Farley 2 W SMAW NA BOLA 4 Farley 2 X SMAW NA BOLA 5 Farley 2 z SMAW NA BOLA 6 Farley 2 Y SMAW NA BOLA 7 Farley 2 V SMAW NA BOLA 200 150 E

C 3.-

Ul 10 50 04--

-300.0 0.0 300.0 600.0 Temperature in Deg F 0 1 0 2 3 A4 v 5 0 6 . 7 Results Curve Fluence LSE USE d-USE T @35 d-T @35 1 .0 92. 2 .0 -23. 5 .0 2 .0 91. 5 -. 7 -43. 9 -20.4 3 .0 85. I -7.1 - 18.4 5. 1 4 .0 84. I -8.1 -30.0 -6.5 5 .0 79. 8 -12.4 -1.4 22. I 6 .0 83. 4 -8.8 47. 9 71.4 7 .0 86. 4 -5.8 41.3 64. 8 Figure 5-8 Charpy V-Notch Lateral Expansion vs. Temperature for Farley Unit 2 Reactor Vessel Surveillance Weld Metal Specimens WCAP- 16918-NP April 2008 Revision 1

5-25 SURVEILLANCE WELD METAL CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02/06/2008 05:13 PM Data Set(s) Plotted Curive Nlanlft Capsole Material Ori. Heat #

1 Farley 2 UNIRR SMAW NA BOLA 2 Farlev 2 U SMAW NA BOLA 3 Farley 2 W SMAW NA BOLA 4 Farley 2 X SMAW NA BOLA 5 Farley 2 Z SMAW NA BOLA 6 Farley 2 Y SMAW NA BOLA 7 Farley 2 V SMAW NA BOLA 125 100 1..

'U '0 75 U,

a) Ya a) 50 0.

25 0

0

-300.0 -200.0 -100.0 0.10 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F 0 1 0 2 0 3 A 4 v 5 0 6 a 7 Results Cure Fluence LSE USE d-USE T @50 d-T @50 1 .0 100. 0 .0 -15. 1 .0 2 .0 100. 0 .0 4.0 3 .0 100. 0 .0 1.9 17.0 4 .0 100.0 .0 -8.9 6. 2 5 .0 100. 0 .0 15.2 30. 3 6 .0 100. 0 .0 53. 1 68. 2 7 .0 100. 0 .0 61. 1 76. 2 Figure 5-9 Charpy V-Notch Percent Shear vs. Temperature for Farley Unit 2 Reactor Vessel Surveillance Weld Metal Specimens WCAP- 16918-NP April 2008 Revision 1

5-26 HEAT AFFECTEI) ZONE CVGRAPH 5.3 Hyperbolic Tangent Curve Printed oil 02/06/2008 05:25 PM Data Set(s) Plotted Ciiive Plant Caplsule Material Orl. Heat #

2 Farley 2 UNIRR SA533BI NA B7212-1 Farley 2 U SA533B I NA B7212- 1 3 Farley 2 W SA533B 1 NA B7212-1 4 Farlev 2 X SA533B1 NA B7212-I 5 Farley 2 Z SA533B 1 NA B72 12-1 6 Farley 2 Y SA533B1 NA B7212-I 7 Farley 2 V SA533Bl! NA B7212-1 300 250 4 200 0

U-150 IL, z

> 100 0

50-0

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F 0 1 S2 03 & 4 v 5 0 6 w 7 Results Curve Fluence LSE USE d-USE T @30 d-T @X) T @50 d-T @50 1 2. 2 158.0 .0 -296. 2 .0 -205.3 .0 2 2.2 111.0 -47.0 -76.4 219.8 -44.3 161.0 3 2.2 126.0 -32.0 -27.4 268.8 -16.1 189. 2 4 2. 2 128.0 -30.0 -65. 7 230.5 -39.9 165. 4 5 2.2 126.0 -32.0 -32.4 263.8 -2.9 202. 4 6 2.2 102.0 -56.0 -26.6 269.6 -3.8 201. 5 7 2.2 118.0 -40.0 26.2 322.4 52.4 257. 7 Figure 5-10 Charpy V-Notch Impact Energy vs. Temperature for Farley Unit 2 Reactor Vessel Heat-Affected-Zone Specimens WCAP- 16918-NP April 2008 Revision 1

5-27 HEAT AFFECTED)ZONE CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02/06/2008 05:29 PM Data Set(s) Plotted Ciiiwe Plant Capsule Material Ori. Heat #

21 Farlev 2 UNIRR SA533B I NA B7212-1 Farley 2 U SA533BI NA B7212-1 3 Farley 2 w SA533B I NA B7212-I 4 Farley 2 X SA533B 1 NA B7212-1 5 Farley 2 z SA533B I NA B7212-1 6 Farley 2 Y SA533BI NA B7212-1 7 Farley 2 V SA533BI NA B7212-1 200 150 a 100 50 0 ý-

-300.0 0.0 300.0 600.0 Temperature in Deg F 0 1 o 2 3 A4 v 5 0 6 m 7 Results Curve Fluence LSE U&E d-USE T @35 d-T @35 1 .0 90. 3 .0 -183.6 .0 2 .0 88. 1 -1.9 -58.8 124.8 3 .0 92. 8 2.5 -20. 6 163.0 4 .0 85. 2 -5.0 - 37. 0 146.6 5 .0 86. 1 -4.2 5. 1 188.7 6 .0 82. 5 -7.8 -5. 5 178. I 7 .0 90. 5 .2 49. 7 233. 3 Figure 5-11 Charpy V-Notch Lateral Expansion vs. Temperature for Farley Unit 2 Reactor Vessel Heat-Affected-Zone Specimens WCAP- 16918-NP April 2008 Revision 1

5-28 HEAT AFFEcTED ZONE CVGRAPH 5.3 Hyperbolic Tangent Curve Primted on 02/06/2008 05:33 PM Data Set(s) Plotted CurIve Plant Caipsule Miaterial Ori. Heat #

1 Farley 2 UNIRR SA533B I NA B7212-I 2 anrev 2 U SA533B I NA B7212-1 3 Farle5, 2 w SA533B I NA B7212-1 4 Farney 2 x SA533B I NA B7212-1 5 Farley 2 z SA533BI NA B7212-1 6 Farley 2 Y SA533B13 NA B7212-1 7 Farley 2 V SA533B13 NA B7212-I 125 100 I-a) 75 U,

a) 2 0 50 a.

25-0-

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F 0 1 3 2 03 A 4 V 5 6 a 7 Results Curve Fluenme LSE USE d-USE T @50 d-T @50 1 .0 100.0 .0 -116.0 .0 2 .0 100.0 .0 -28.0 88.0 3 .0 100. 0 .0 -11.3 104. 7 4 .0 100. 0 .0 -14.8 101. 2 5 .0 100. 0 .0 16.2 132. 2 6 .0 100.0 .0 4.8 120. 8 7 .0 100.0 .0 56.4 172.4 Figure 5-12 Charpy V-Notch Percent Shear vs. Temperature for Farley Unit 2 Reactor Vessel Heat-Affected-Zone Specimens WCAP- 16918-NP April 2008 Revision 1

5-29 CL30, 50°F CL 19, 180°F CL25, 210°F CL17, 220°F CL28, 225°F CL22, 230°F CL 18, 250°F CL24, 260°F CL16, 265°F CL27, 290°F CL23, 290°F CL26, 315T CL21, 340°F CL20, 370°F CL29, 380°F Figure 5-13 Charpy Impact Specimen Fracture Surfaces for Farley Unit 2 Reactor Vessel Intermediate Shell Plate B7212-1 Specimens (Longitudinal Orientation)

WCAP- 16918-NP April 2008 Revision 1

5-30 CT25, 100°F CT24, 200°F CT19, 205°F CT27, 215°F CT16, 225°F CT23, 230°F CT17,240°F CT22, 260°F CT29, 275°F CT20, 280°F CT18, 305°F CT28, 345°F CT30, 375°F CT21, 400°F CT26, 410°F Figure 5-14 Charpy Impact Specimen Fracture Surfaces for Farley Unit 2 Reactor Vessel Intermediate Shell Plate B7212-1 Specimens (Transverse Orientation)

WCAP- 16918-NP April 2008 Revision 1

5-31 CW28, F CW21, 20°F CW25, 30°F CW30, 40°F CW24, 50°F CW27, 70°F CW22, 100-F CW20, 125-F CW26, 145°F CW17, 165-F CW19,185°F CW16,230 0 F CW23,250 0 F CW18, 2600 F Figure 5-15 Charpy Impact Specimen Fracture Surfaces for Farley Unit 2 Reactor Vessel Surveillance Weld Metal Specimens WCAP-16918-NP April 2008 Revision 1

5-32 CH23, -80°F CH29, -15°F CH24, 25°F CH26, 35°F CH22, 40°F CH27, 45°F CH18, 50°F CH17, 70°F CH21, 70°F CH16, 90QF CH19, l15°F CH20, 155°F CH30,200°F CH28, 250°F CH25, 260°F Figure 5-16 Charpy Impact Specimen Fracture Surfaces for Farley Unit 2 Reactor Vessel Heat-Affected-Zone Specimens WCAP- 16918-NP April 2008 Revision 1

5-33 120.0 Ultimate Tensile Strength 100.0 80.0

~0.2% Yield Strength din vn In 60.0 40.0 20.0 0.0 0 100 200 300 400 500 600 Temperature (F)

Legend: Aand e and u are unirradiated A and o and o are irradiated to 8.73E+19 n/cm 2 (E > 1.0 MeV) 80.0 Reduction in Area 70.0 60.0 50.0

= 40.0 U

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

Figure 5-17 Tensile Properties for Farley Unit 2 Reaaor Vessel Intermediate Shell Plate B7212-1 Specimens (Longitudinal Orientation)

WCAP- 16918-NP April 2008 Revision 1

5-34 120.0 Ultimate Tensile Strength 100.0 80.0 0.2% Yield Strength U) 60.0 Cn 40.0 20.0 0.0 0 100 200 300 400 500 600 Temperature (F)

Legend: Aand e and m are unirradiated A and o and E] are irradiated to 8.73E+19 n/cm2 (E > 1.0 MeV) 70.0

~Reduction in Area 60.0 50.0 40.0 U

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

Figure 5-18 Tensile Properties for Farley Unit 2 Reactor Vessel Intermediate Shell Plate B7212-1 Specimens (Transverse Orientation)

WCAP- 16918-NP April 2008 Revision 1

5-35 100.0 Ultimate Tensile Strength 90.0 0% eSn 80.0 70.0 60.0 in 0.2% Yield Strength in in 50.0 40.0 30.0 20.0 10.0 0.0 0 100 200 300 400 500 600 Temperature (F)

Legend: A and e and u are unirradiated A and o and E] are irradiated to 8.73E+19 n/cm2 (E > 1.0 MeV) 80.0 70.0 Reduction in Area 60.0 50.0 2

40.0 30.0 Total Elongation 20.0 0 0 10.0 - p Uniform Elongation 0.0 0 100 200 300 400 500 600 Temperature (F)

Figure 5-19 Tensile Properties for Farley Unit 2 Reactor Vessel Surveillance Weld Metal Specimens WCAP- 16918-NP April 2008 Revision 1

5-36 Specimen CL4- Tested at 230'F Specimen CL5- Tested at 290'F Specimen CL6- Tested at 550'F Figure 5-20 Fractured Tensile Specimens from Farley Unit 2 Reactor Vessel Intermediate Shell Plate B7212-1 Specimens (Longitudinal Orientation)

WCAP- 16918-NP April 2008 Revision 1

5-37 Specimen CT4- Tested at 240'F Specimen CT5- Tested at 320'F Specimen CT6- Tested at 550'F Figure 5-21 Fractured Tensile Specimens from Farley Unit 2 Reactor Vessel Intermediate Shell Plate B7212-1 Specimens (Transverse Orientation)

WCAP-16918-NP April 2008 Revision 1

5-38 Specimen CW4- Tested at 80'F Specimen CW5- Tested at 200'F Specimen CW6- Tested at 550'F Figure 5-22 Fractured Tensile Specimens from Farley Unit 2 Reactor Vessel Surveillance Weld Metal Specimens WCAP- 16918-NP April 2008 Revision I

5-39 FARLEY 2 CAPSULE V 120 100

- 80 (6

U) 60 40 CL4 230°F 20 0 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN, IN/IN FARLEY 2 CAPSULE V 120 100

- 80 W 60 U) 40 CL5 290=F 20 0 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN, NIN FARLEY 2 CAPSULE V 120 100

- 80 U)n 60 40 CL6 550°F 20 0 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN, IN/IN Figure 5-23 Engineering Stress-Strain Curves for the Farley Unit 2 Reactor Vessel Intermediate Shell Plate B7212-1 Specimens (Longitudinal Orientation) Tensile Specimens CL-4, CL-5 and CL-6 WCAP- 16918-NP April 2008 Revision 1

5-40 FARLEY 2 CAPSULE V 120 100

- 80

) 60 40 CT4 240°F 20 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN, IN/IN FARLEY 2 CAPSULE V 120 100-80 8

60 40 CTS 320*F 20 0

0 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN, IN/IN FARLEY 2 CAPSULE V 120 80s0 60 40 CT6 550=F 20 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN. INIIN Figure 5-24 Engineering Stress-Strain Curves for the Farley Unit 2 Reactor Vessel Intermediate Shell Plate B7212-1 Specimens (Transverse Orientation) Tensile Specimens CT-4, CT-5* and CT-6

• Specimen broke at edge of clip gage. Curve reconstructed from the Load vs. Time data.

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5-41 FARLEY 2 CAPSULE V 100 90 80 70

. 60 50 40 30 F7CWý4 BOT 20 10 0

a 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN, IN/IN FARLEY 2 CAPSULE V 100 90 00 70 60 50 40 30 CW5 200*F 20 10 0 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN, NIN FARLEY 2 CAPSULE V 100 90 B0 70 60 u*

o: 50 40 30 20 10 0 0.05 0.1 0.15 0.2 0.25 03 STRAIN, IN/IN Figure 5-25 Engineering Stress-Strain Curves for Farley Unit 2 Reactor Vessel Surveillance Weld Metal Specimens CW4, CW5, and CW6 WCAP- 16918-NP April 2008 Revision 1

6-1 6 RADIATION ANALYSIS AND NEUTRON DOSIMETRY

6.1 INTRODUCTION

This section describes a discrete ordinates Sn, transport analysis performed for the Farley Unit 2 reactor to determine the neutron radiation environment within the reactor pressure vessel and surveillance capsules.

In this analysis, fast neutron exposure parameters in terms of fast neutron fluence (E > 1.0 MeV) and iron atom displacements (dpa) were established on a plant and fuel cycle specific basis. An evaluation of the most recent dosimetry sensor set from Capsule V, withdrawn at the end of the eighteenth plant operating cycle, is provided. In addition, to provide an up-to-date data base applicable to the Farley Unit 2 reactor, sensor sets from previously withdrawn capsules (U, W, X, Z, and Y) 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).

The use of fast neutron fluence (E > 1.0 MeV) to correlate measured material property changes to the neutron exposure of the material has traditionally been accepted for the development of damage trend curves as well as for the implementation of trend curve data to assess the condition of the vessel. In recent years, however, it has been suggested that an exposure model that accounts for differences in neutron energy spectra between surveillance capsule locations and positions within the vessel wall could lead to an improvement in the uncertainties associated with damage trend curves and improved accuracy in the evaluation of damage gradients through the reactor vessel wall.

Because of this potential shift away from a threshold fluence toward an energy dependent damage function for data correlation, ASTM Standard Practice E853, "Analysis and Interpretation of Light-Water Reactor Surveillance Results,"[20 1recommends reporting displacements per iron atom (dpa) along with fluence (E > 1.0 MeV) to provide a database for future reference. The energy dependent dpa function to be used for this evaluation is specified in ASTM Standard Practice E693, "Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements per Atom." 2 11 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 1

Reactor Vessel Materials."

All of the calculations and dosimetry evaluations described in this section and in Appendix A were based on the latest available nuclear cross-section data derived from ENDF/B-VI and made use of the latest available calculational tools. Furthermore, the neutron transport and dosimetry evaluation methodologies follow the guidance and meet the requirements of Regulatory Guide 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence" 22 . Additionally, the methods used to develop the calculated pressure vessel fluence are consistent with the NRC approved methodology described in WCAP-14040-NP-A, Revision 4 "Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves," May 2004[23].

WCAP-16918-NP April 2008 Revision 1

6-2 6.2 DISCRETE ORDINATES ANALYSIS A plan view of the Farley Unit 2 reactor geometry at the core midplane is shown in Figure 6-1. Six irradiation capsules attached to the neutron pad are included in the reactor design that constitutes the reactor vessel surveillance program. The capsules are located at azimuthal angles of 107', 2870, 3430 (17' from the core cardinal axes) and 1100, 2900, 3400 (200 from the core cardinal axes). The stainless steel specimen containers are 1.182-inch by 1-inch and are approximately 56 inches in height. The containers are positioned axially such that the test specimens are centered on the core midplane, thus spanning the central 5 feet of the 12-foot high reactor core.

From a neutronic standpoint, the surveillance capsules and associated support structures are significant.

The presence of these materials has a marked effect on both the spatial distribution of neutron flux and the neutron energy spectrum in the water annulus between the neutron pads and the reactor vessel. In order to determine the neutron 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 Farley Unit 2 reactor vessel and surveillance capsules, a series of fuel cycle specific forward transport calculations were carried out using the following three-dimensional flux synthesis technique:

0(r, 0, z) = 4)(r, 0)

• 4(r,

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

For the Farley Unit 2 transport calculations, two octant-symmetric rO models were developed and are depicted in Figure 6-1. The first model contained the extended neutron pad (26' span) including the surveillance capsules, while the second contained the shortened neutron pad (150 span) with no surveillance capsules. The former model was used to perform surveillance capsule dosimetry evaluations and subsequent comparisons with calculated results, while the latter model was used to generate the maximum fluence at the pressure vessel wall. In developing these analytical models, nominal design dimensions were employed for the various structural components. Likewise, water temperatures, and hence, coolant densities in the reactor core and downcomer regions of the reactor were taken to be representative of full power operating conditions. The coolant densities were treated on a fuel cycle specific basis. The reactor core itself was treated as a homogeneous mixture of fuel, cladding, water, and miscellaneous core structures such as fuel assembly grids, guide tubes, et cetera. The geometric mesh description of the rO reactor models consisted of 185 radial by 92 azimuthal intervals. Mesh sizes were chosen to assure that proper convergence of the inner iterations was achieved on a point-wise basis. The point-wise inner iteration flux convergence criterion utilized in the r,O calculations was set at a value of 0.001.

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6-3 The r,z model used for the Farley Unit 2 calculations is shown in Figure 6-2 and extends radially from the centerline of the reactor core out to a location interior to the primary biological shield and over an axial span from an elevation 1-foot below the active fuel to approximately one-foot above the active fuel. 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 149 radial by 178 axial intervals. As in the case of the r,0 calculations, mesh sizes were chosen to assure that proper convergence of the inner iterations was achieved on a point-wise basis. The point-wise inner iteration flux convergence criterion utilized in the r,z calculations was also set at a value of 0.001.

The one-dimensional radial models used in the synthesis procedure consisted of the same 149 radial mesh intervals included in the r,z models. Thus, radial synthesis factors could be determined on a mesh-wise basis throughout the entire geometry.

The core power distributions used in the plant specific transport analysis were taken from the appropriate Farley Unit 2 fuel cycle design reports. The data extracted from the design reports represented cycle-dependent fuel assembly enrichments, bum-ups, 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 bum-up 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.

The transport calculations supporting this analysis were carried out using the DORT discrete ordinates code Version 3.2[24] and the BUGLE-96 cross-section library.[25 3 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 S1 6 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 6-7. 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 two azimuthally symmetric surveillance capsule positions (170 and 200). These results, representative of the axial midplane of the active core, establish the calculated exposure of the surveillance capsules withdrawn to date as well as projected into the future. Similar information is provided in Tables 6-2 and 6-3 for the reactor vessel inner radius. The vessel data given in Table 6-2 are representative of the axial location of the maximum neutron exposure at each of the four azimuthal locations, while Table 6-3 provides neutron exposure data for the intermediate shell course to nozzle shell course weld. It is also important to note that the data for WCAP- 16918-NP April 2008 Revision 1

6-4 the vessel inner radius were taken at the clad/base metal interface, and thus, represent the maximum calculated exposure levels of the vessel plates and welds.

Both calculated fluence (E > 1.0 MeV) and dpa data are provided in Table 6-1 through Table 6-3. These data tabulations include both plant and fuel cycle specific calculated neutron exposures at the end of the 18th operating fuel cycle as well as future projections to 25, 32, 40, 48, 54, and 60 EFPY 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 2775 MWt.

Radial gradient information applicable to fast (E > 1.0 MeV) neutron fluence and dpa are given in Tables 6-4 and 6-5, respectively. The data, based on the cumulative integrated exposures from Cycles 1 through 19, are presented on a relative basis for each exposure parameter at several azimuthal locations.

Exposure distributions through the vessel wall may be obtained by multiplying the calculated exposure at the vessel inner radius by the gradient data listed in Tables 6-4 and 6-5.

The calculated fast neutron exposures for the six surveillance capsules withdrawn from the Farley Unit 2 reactor are provided in Table 6-6. These assigned neutron exposure levels are based on the plant and fuel cycle specific neutron transport calculations performed for the Farley Unit 2 reactor.

Updated lead factors for the Farley Unit 2 surveillance capsules are provided in Table 6-7. The capsule lead factor is defined as the ratio of the calculated fluence (E > 1.0 MeV) at the geometric center of the surveillance capsule to the corresponding maximum calculated fluence at the pressure vessel clad/base metal interface. In Table 6-7, the lead factors for capsules that have been withdrawn from the reactor (U, W, X, Z, Y, and V) were based on the calculated fluence values for the irradiation period corresponding to the time of withdrawal for the individual capsules.

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

The direct comparison of measured versus calculated fast neutron threshold reaction rates for the sensors from Capsule V, withdrawn from Farley Unit 2 at the end of the 18th fuel cycle, is summarized below.

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6-5 Reaction Rates (rps/atom)

Reaction Measured Calculated M/C Ratio 63Cu(nQ) 60 Co 6.04E- 17 5.96E- 17 1.01 54Fe(n,p) 54 Mn 6.02E- 15 6.94E- 15 0.87 58Ni(n,p)5 8 Co 8.51 E- 15 9.82E- 15 0.87 238U(n,p)137 Cs (Cd) 3.56E-14 3.89E-14 0.91 237Np(n,f) 37 1 Cs (Cd) 3.63E-13 4.10E-13 0.88 Average: 0.91

% Standard Deviation: 6.5 The measured-to-calculated (M/C) reaction rate ratios for the Capsule V threshold reactions range from 0.87 to 1.01, and the average M/C ratio is 0.91 +/- 6.5 (la). This direct comparison falls well within the

+/- 20% criterion specified in Regulatory Guide 1.190[22]; furthermore, it is consistent with the full set of comparisons given in Appendix A for all measured dosimetry removed to date from the Farley Unit 2 reactor. These comparisons validate the current analytical results described in Section 6.2; therefore, the

,calculations are deemed applicable for Farley Unit 2.

6.4 CALCULATIONAL UNCERTAINTIES The uncertainty associated with the calculated neutron exposure of the Farley Unit 2 surveillance capsule and reactor pressure vessel is based on the recommended approach provided in Regulatory Guide 1.190.[221 In particular, the qualification of the methodology was carried out in the following four stages:

1. Comparison of calculations with benchmark measurements from the pool critical assembly (PCA) simulator at the Oak Ridge National Laboratory (ORNL).

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

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

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

The first phase of the methods qualification (PCA comparisons) addressed the adequacy of basic transport calculation and dosimetry evaluation techniques and associated cross-sections. This phase, however, did not test the accuracy of commercial core neutron source calculations nor did it address uncertainties in operational or geometric variables that impact power reactor calculations. The second phase of the qualification (H. B. Robinson comparisons) addressed uncertainties in these additional areas that are WCAP-16918-NP April 2008 Revision I

6-6 primarily methods related and would tend to apply generically to all fast neutron exposure evaluations.

The third phase of the qualification (analytical sensitivity study) identified the potential uncertainties introduced into the overall evaluation due to calculational methods approximations as well as to a lack of knowledge relative to various plant specific input parameters. The overall calculational uncertainty applicable to the Farley Unit 2 analysis was established from results of these three phases of the methods qualification.

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

The following summarizes the uncertainties developed from the first three phases of the methodology qualification. Additional information pertinent to these evaluations is provided in Reference 22.

Capsule Vessel IR PCA Comparisons 3% 3%

H. B. Robinson Comparisons 3% 3%

Analytical Sensitivity Studies 10% 11%

Additional Uncertainty for Factors not Explicitly Evaluated 5% 5%

Net Calculational Uncertainty 12% 13%

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

Therefore, the resultant uncertainty was 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 Farley Unit 2.

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6-7 Table 6-1 Calculated Neutron Exposure Rates and Integrated Exposures at the Surveillance Capsule Center Neutrons (E > 1.0 MeV)

Cumulative Cumulative Neutron Flux (E > 1.0 MeV)

Cycle Irradiation Irradiation (n/cmn-s)

Length Time Time Cycle (EFPS) (EFPS) (EFPY) 170 200 1 3.508E+07 3.508E+07 1.11 1.73E+11 1.49E+ 11 2 2.434E+07 5.942E+07 1.88 1.80E+ 11 1.55E+ 11 3 3.436E+07 9.378E+07 2.97 1.60E+ 11 1.36E+11 4 3.111E+07 1.249E+08 3.96 1.33E+11 1.16E+ 11 5 3.954E+07 1.644E+08 5.21 1.30E+ 11 1.12E+ 11 6 3.837E+07 2.028E+08 6.43 1.19E+ 1I 1.05E+l 1 7 4.050E+07 2.433E+08 7.71 1.25E+ 11 1.11 E+ 11 8 3.505E+07 2.784E+08 8.82 1.19E+ 11 1.04E+ 11 9 3.992E+07 3.183E+08 10.09 1.09E+ 11 9.57E+10 10 3.792E+07 3.562E+08 11.29 1.24E+ 11 1.09E+ 11 11 4.118E+07 3.974E+08 12.59 1.05E+l1 8.83E+10 12 3.982E+07 4.372E+08 13.85 1.05E+ 11 9.34E+10 13 4.086E+07 4.781E+08 15.15 1.26E+11 1.11E+I 1 14 3.708E+07 5.151E+08 16.32 1.31E+1 1 1.19E+ 11 15 4.192E+07 5.571E+08 17.65 1.26E+ 11 1.14E+ 11 16 4.276E+07 5.998E+08 19.01 1.24E+ 11 1.16E+ 11 17 4.646E+07 6.463E+08 20.48 1.18E+l 1 1.07E+1 1 18 4.219E+07 6.884E+08 21.82 1.11E+ 1I 9.89E+10 Future 1.005E+08 7.889E+08 25.00 1.18E+ 11 1.02E+ 11 Future 2.209E+08 1.010E+09 32.00 1.18E+l 1 1.02E+ 1I Future 2.525E+08 1.262E+09 40.00 1.18E+ 11 1.02E+ 11 Future 2.525E+08 1.515E+09 48.00 1.18E+ 11 1.02E+ 11 Future 1.893E+08 1.704E+09 54.00 1.18E+11 1.02E+ 11 Future 1.893E+08 1.893E+09 60.00 1.18E+l 1 1.02E+ 11 WCAP- 16918-NP April 2008 Revision 1

6-8 Table 6-1 Calculated Neutron Exposure Rates and Integrated Exposures at the Surveillance (cont.) Capsule Center Neutrons (E > 1.0 MeV)

Cumulative Cumulative Neutron Fluence (E > 1.0 MeV)

Cycle Irradiation Irradiation (n/cm 2)

Length Time Time Cycle (EFPS) (EFPS) (EFPY) 170 200 1 3.508E+07 3.508E+07 1.11 6.05E+18 5.23E+18 2 2.434E+07 5.942E+07 1.88 1.04E+ 19 9.OOE+18 3 3.436E+07 9.378E+07 2.97 1.59E+19 1.37E+19 4 3.111E+07 1.249E+08 3.96 2.01E+19 1.73E+19 5 3.954E+07 1.644E+08 5.21 2.52E+19 2.17E+ 19 6 3.837E+07 2.028E+08 6.43 2.98E+19 2.57E+19 7 4.050E+07 2.433E+08 7.71 3.48E+19 3.02E+19 8 3.505E+07 2.784E+08 8.82 3.90E+19 3.39E+19 9 3.992E+07 3.183E+08 10.09 4.33E+19 3.77E+19 10 3.792E+07 3.562E+08 11.29 4.80E+19 4.18E+19 11 4.118E+07 3.974E+08 12.59 5.23E+19 4.55E+19 12 3.982E+07 4.372E+08 13.85 5.65E+19 4.92E+19 13 4.086E+07 4.781E+08 15.15 6.16E+ 19 5.37E+19 14 3.708E+07 5.15 1E+08 16.32 6.65E+19 5.81E+19 15 4.192E+07 5.571E+08 17.65 7.18E+19 6.29E+19 16 4.276E+07 5.998E+08 19.01 7.7 1E+19 6.79E+19 17 4.646E+07 6.463E+08 20.48 8.26E+19 7.28E+19 18 4.219E+07 6.884E+08 21.82 8.73E+19 7.70E+19 Future 1.005E+08 7.889E+08 25.00 9.9 1E+ 19 8.73E+19 Future 2.209E+08 1.010E+09 32.00 1.25E+20 1.1OE+20 Future 2.525E+08 1.262E+09 40.00 1.55E+20 1.36E+20 Future 2.525E+08 1.515E+09 48.00 1.84E+20 1.62E+20 Future 1.893E+08 1.704E+09 54.00 2.07E+20 1.81E+20 Future 1.893E+08 1.893E+09 60.00 2.29E+20 2.OOE+20 WCAP- 16918-NP April 2008 Revision 1

6-9 Table 6-1 Calculated Neutron Exposure Rates and Integrated Exposures at the Surveillance (cont.) Capsule Center Iron Atom Displacements Cumulative Cumulative Displacement Rate Cycle Irradiation Irradiation (dpa/s)

Length Time Time Cycle (EFPS) (EFPS) (EFPY) 170 200 1 3.508E+07 3.508E+07 1.11 3.55E-10 3.OOE-10 2 2.434E+07 5.942E+07 1.88 3.71E-10 3.12E-10 3 3.436E+07 9.378E+07 2.97 3.27E-10 2.73E-10 4 3.11IE+07 1.249E+08 3.96 2.71E-10 2.30E-10 5 3.954E+07 1.644E+08 5.21 2.65E-10 2.24E-10 6 3.837E+07 2.028E+08 6.43 2.42E-10 2.09E-10 7 4.050E+07 2.433E+08 7.71 2.54E-10 2.22E-10 8 3.505E+07 2.784E+08 8.82 2.41E-10 2.08E-10 9 3.992E+07 3.183E+08 10.09 2.20E-10 1.90E-10 10 3.792E+07 3.562E+08 11.29 2.51E-10 2.16E- 10 11 4.118E+07 3.974E+08 12.59 2.13E-10 1.77E-10 12 3.982E+07 4.372E+08 13.85 2.13E-10 1.85E-10 13 4.086E+07 4.781E+08 15.15 2.55E-10 2.20E-10 14 3.708E+07 5.151E+08 16.32 2.65E-10 2.37E-10 15 4.192E+07 5.571E+08 17.65 2.56E-10 2.25E-10 16 4.276E+07 5.998E+08 19.01 2.50E-10 2.30E-10 17 4.646E+07 6.463E+08 20.48 2.40E-10 2.11E-10 18 4.219E+07 6.884E+08 21.82 2.24E-10 1.96E-10 Future 1.005E+08 7.889E+08 25.00 2.38E-10 2.03E-10 Future 2.209E+08 1.010E+09 32.00 2.38E-10 2.03E-10 Future 2.525E+08 1.262E+09 40.00 2.38E-10 2.03E-10 Future 2.525E+08 1.515E+09 48.00 2.38E-10 2.03E-10 Future 1.893E+08 1.704E+09 54.00 2.38E-10 2.03E-10 Future 1.893E+08 1.893E+09 60.00 2.388E-10 2.03E-10 WCAP- 16918-NP April 2008 Revision 1

6-10 Table 6-1 Calculated Neutron Exposure Rates and Integrated Exposures at the Surveillance (cont.) Capsule Center Iron Atom Displacements Cumulative Cumulative Displacement Rate Cycle Irradiation Irradiation (dpa)

Length Time Time Cycle (EFPS) (EFPS) (EFPY) 170 200 1 3.508E+07 3.508E+07 1.11 1.25E-02 1.05E-02 2 2.434E+07 5.942E+07 1.88 2.15E-02 1.81E-02 3 3.436E+07 9.378E+07 2.97 3.27E-02 2.75E-02 4 3.11 IE+07 1.249E+08 3.96 4.12E-02 3.47E-02 5 3.954E+07 1.644E+08 5.21 5.16E-02 4.35E-02 6 3.837E+07 2.028E+08 6.43 6.09E-02 5.15E-02 7 4.050E+07 2.433E+08 7.71 7.12E-02 6.05E-02 8 3.505E+07 2.784E+08 8.82 7.97E-02 6.78E-02 9 3.992E+07 3.183E+08 10.09 8.85E-02 7.54E-02 10 3.792E+07 3.562E+08 11.29 9.80E-02 8.36E-02 11 4.118E+07 3.974E+08 12.59 1.07E-01 9.08E-02 12 3.982E+07 4.372E+08 13.85 1.15E-01 9.82E-02 13 4.086E+07 4.781E+08 15.15 1.26E-01 1.07E-01 14 3.708E+07 5.151E+08 16.32 1.36E-01 1.16E-01 15 4.192E+07 5.571E+08 17.65 1.46E-01 1.25E-01 16 4.276E+07 5.998E+08 19.01 1.57E-01 1.35E-01 17 4.646E+07 6.463E+08 20.48 1.68E-01 1.45E-01 18 4.219E+07 6.884E+08 21.82 1.78E-01 1.53E-01 Future 1.005E+08 7.889E+08 25.00 2.01E-01 1.74E-01 Future 2.209E+08 1.010E+09 32.00 2.54E-01 2.19E-01 Future 2.525E+08 1.262E+09 40.00 3.14E-01 2.70E-01 Future 2.525E+08 1.515E+09 48.00 3.74E-01 3.21E-01 Future 1.893E+08 1.704E+09 54.00 4.19E-01 3.60E-01 Future 1.893E+08 1.893E+09 60.00 4.64E-01 3.98E-01 Note:

Neutron exposure values reported for the surveillance capsules are centered at the core midplane.

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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)

Cycle Irradiation Irradiation (n/cm2-s)

Length Time Time Cycle (EFPS) (EFPS) (EFPY) 00 150 300 450 1 3.508E+07 3.508E+07 1.11 5.30E+10 2.94E+10 2.17E+10 1.48E+10 2 2.434E+07 5.942E+07 1.88 5.43E+10 3.01E+10 2.21E+10 1.50E+10 3 3.436E+07 9.378E+07 2.97 4.91E+10 2.70E+10 1.79E+10 1.10E+10 4 3.111E+07 1.249E+08 3.96 3.93E+10 2.22E+10 1.58E+10 1.12E+10 5 3.954E+07 1.644E+08 5.21 3.71E+10 2.20E+10 1.62E+10 1.16E+10 6 3.837E+07 2.028E+08 6.43 3.24E+10 1.99E+10 1.54E+10 1.06E+10 7 4.050E+07 2.433E+08 7.71 3.53E+10 2.11E+10 1.66E+10 1.11E+10 8 3.505E+07 2.784E+08 8.82 3.22E+10 1.99E+10 1.52E+10 1.08E+10 9 3.992E+07 3.183E+08 10.09 2.99E+10 1.83E+10 1.44E+10 1.04E+10 10 3.792E+07 3.562E+08 11.29 3.70E+10 2.09E+10 1.57E+10 1.09E+10 11 4.118E+07 3.974E+08 12.59 3.79E+10 1.81E+10 1.30E+10 9.99E+09 12 3.982E+07 4.372E+08 13.85 2.60E+10 1.75E+10 1.31E+10 9.23E+09 13 4.086E+07 4.781E+08 15.15 3.56E+10 2.12E+10 1.61E+10 1.12E+10 14 3.708E+07 5.151E+08 16.32 3.38E+10 2.19E+10 1.83E+10 1.28E+10 15 4.192E+07 5.571E+08 17.65 3.18E+10 2.11E+10 1.72E+10 1.18E+10 16 4.276E+07 5.998E+08 19.01 2.84E+10 2.02E+10 1.75E+10 1.14E+10 17 4.646E+07 6.463E+08 20.48 2.95E+10 1.95E+10 1.63E+10 1.20E+10 18 4.219E+07 6.884E+08 21.82 2.84E+10 1.84E+10 1.43E+10 1.01E+10 Future 1.005E+08 7.889E+08 25.00 3.30E+10 1.94E+10 1.44E+10 1.04E+10 Future 2.209E+08 1.010E+09 32.00 3.30E+10 1.94E+10 1.44E+10 1.04E+10 Future 2.525E+08 1.262E+09 40.00 3.30E+10 1.94E+10 1.44E+10 1.04E+10 Future 2.525E+08 1.515E+09 48.00 3.30E+10 1.94E+10 1.44E+10 1.04E+10 Future 1.893E+08 1.704E+09 54.00 3.30E+10 1.94E+10 1.44E+10 1.04E+10 Future 1.893E+08 1.893E+09 60.00 3.30E+10 1.94E+10 1.44E+10 1.04E+10 WCAP-16918-NP April 2008 Revision I

6-12 Table 6-2 Calculated Azimuthal Variation of Maximum Exposure Rates and Integrated Exposures at (cont.) the Reactor Vessel Clad/Base Metal Interface Cumulative Cumulative Neutron Fluence (E > 1.0 MeV)

Cycle Irradiation Irradiation (n/cm 2)

Length Time Time 00 Cycle (EFPS) (EFPS) (EFPY) 00 150 300 450 1 3.508E+07 3.508E+07 1.11 1.86E+18 1.03E+18 7.63E+17 5.21E+17 2 2.434E+07 5.942E+07 1.88 3.18E+18 1.77E+18 1.30E+18 8.85E+17 3 3.436E+07 9.378E+07 2.97 4.87E+18 2.69E+18 1.92E+18 1.26E+18 4 3.111E+07 1.249E+08 3.96 6.09E+ 18 3.38E+18 2.41E+18 1.61E+18 5 3.954E+07 1.644E+08 5.21 7.56E+18 4.25E+18 3.05E+18 2.07E+18 6 31837E+07 2.028E+08 6.43 8.80E+18 5.01E+18 3.63E+18 2.48E+18 7 4.050E+07 2.433E+08 7.71 1.02E+19 5.87E+18 4.31E+18 2.93E+18 8 3.505E+07 2.784E+08 8.82 1.14E+ 19 6.56E+18 4.84E+ 18 3.30E+18 9 3.992E+07 3.183E+08 10.09 1.25E+19 7.28E+18 5.40E+ 18 3.71E+18 10 3.792E+07 3.562E+08 11.29 1.39E+19 8.07E+ 18 6.OOE+ 18 4.12E+ 18 11 4.118E+07 3.974E+08 12.59 1.55E+19 8.81E+18 6.53E+18 4.53E+18 12 3.982E+07 4.372E+08 13.85 1.65E+19 9.51E+18 7.05E+18 4.90E+18 13 4.086E+07 4.781E+08 15.15 1.80E+19 1.04E+19 7.70E+ 18 5.36E+18 14 3.708E+07 5.15 1E+08 16.32 1.92E+19 1.12E+ 19 8.38E+18 5.83E+18 15 4.192E+07 5.571E+08 17.65 2.06E+19 1.21E+19 9.10E+18 6.32E+18 16 4.276E+07 5.998E+08 19.01 2.18E+19 1.29E+19 9.85E+18 6.81E+18 17 4.646E+07 6.463E+08 20.48 2.3 1E+19 1.38E+19 1.06E+19 7.36E+18 18 4.219E+07 6.884E+08 21.82 2.43E+19 1.46E+19 1.12E+19 7.79E+ 18 Future 1.005E+08 7.889E+08 25.00 2.76E+19 1.65E+19 1.26E+19 8.83E+18 Future 2.209E+08 1.0 1OE+09 32.00 3.48E+19 2.08E+19 1.58E+19 1.11 E+19 Future 2.525E+08 1.262E+09 40.00 4.3 1E+19 2.57E+19 1.94E+19 1.37E+19 Future 2.525E+08 1.515E+09 48.00 5.14E+ 19 3.06E+19 2.30E+19 1.63E+19 Future 1.893E+08 1.704E+09 54.00 5.76E+19 3.42E+19 2.57E+19 1.83E+19 Future 1.893E+08 1.893E+09 60.00 6.39E+19 3.79E+19 2.84E+19 2.03E+19 WCAP-16918-NP April 2008 Revision 1

6-13 Table 6-2 Calculated Azimuthal Variation of Maximum Exposure Rates and Integrated Exposures at (cont.) the Reactor Vessel Clad/Base Metal Interface Cumulative Cumulative Iron Atom Displacement Rate Cycle Irradiation Irradiation (dpa/s)

Length Time Time 0 1 Cycle (EFPS) (EFPS) (EFPY) 0 150 300 450 1 3.508E+07 3.508E+07 1.11 8.41E-1 1 4.63E-1 1 3.33E-1 1 2.29E- 11 2 2.434E+07 5.942E+07 1.88 8.62E-11 4.74E-1 1 3.38E-11 2.32E-1 1 3 3.436E+07 9.378E+07 2.97 7.80E-I 1 4.25E-1 1 2.75E-1 1 1.70E-11 4 3.111 E+07 1.249E+08 3.96 6.24E-1 1 3.48E-11 2.42E-1 1 1.73E-11 5 3.954E+07 1.644E+08 5.21 5.89E- 11 3.46E-11 2.49E- 11 1.80E-1 1 6 3.837E+07 2.028E+08 6.43 5.15E-1 1 3.13E- 11 2.36E-1 1 1.64E-1 1 7 4.050E+07 2.433E+08 7.71 5.60E-1 1 3.3 1E-1I 2.54E-1 1 1.72E-11 8 3.505E+07 2.784E+08 8.82 5.12E-1 1 3.12E-11 2.34E-1 1 1.68E-11 9 3.992E+07 3.183E+08 10.09 4.75E-1 1 2.87E-1 1 2.21E-11I 1.60E-1 1 10 3.792E+07 3.562E+08 11.29 5.86E-1 1 3.28E-11 2.40E- 11 1.69E-1 1 11 4.118E+07 3.974E+08 12.59 6.OOE- 11 2.86E-1 1 2.OOE- 11 1.55E-I1 12 3.982E+07 4.372E+08 13.85 4.13E-11 2.74E- 1I 2.01E-11I 1.43E-1 1 13 4.086E+07 4.781E+08 15.15 5.64E- 11 3.33E-1 1 2.47E-1 1 1.73E-1 1 14 3.708E+07 5.15 1E+08 16.32 5.36E- 1I 3.44E- 11 2.81E-11I 1.97E-1 1 15 4.192E+07 5.571E+08 17.65 5.04E- 11 3.3 1E-I1 2.64E-1 1 1.83E-1 1 16 4.276E+07 5.998E+08 19.01 4.50E-1 1 3.16E-1 1 2.69E-1 1 1.76E-1 1 17 4.646E+07 6.463E+08 20.48 4.68E-1 1 3.06E- 11 2.50E-1 1 1.85E-11 18 4.219E+07 6.884E+08 21.82 4.50E- 11 2.88E-1 1 2.20E-1 1 1.56E-11 Future 1.005E+08 7.889E+08 25.00 5.23E-11 3.05E-1 1 2.21E-l 1 1.61E-1 1 Future 2.209E+08 1.010E+09 32.00 5.23E-1 1 3.05E-11 2.21E-1 1 1.61E-11I Future 2.525E+08 1.262E+09 40.00 5.23E-1 1 3.05E-11 2.21E-1 1 1.61E-1I Future 2.525E+08 1.515E+09 48.00 5.23E-1 1 3.05E-11 2.21E-1 1 1.61E-1 1 Future 1.893E+08 1.704E+09 54.00 5.23E-11 3.05E-11 2.21E-11 1.61E-11 Future 1.893E+08 1.893E+09 60.00 5.23E-1 1 3.05E-1 1 2.21E-11I 1.61E-1 1 WCAP- 16918-NP April2008 Revision 1

6-14 Table 6-2 Calculated Azimuthal Variation of Maximum Exposure Rates and Integrated Exposures at (cont.) the Reactor Vessel Clad/Base Metal Interface Cumulative Cumulative Iron Atom Displacement Rate Cycle Irradiation Irradiation (dpa)

Length Time Time Cycle (EFPS) (EFPS) (EFPY) 0 I 150 300 450 1 3.508E+07 3.508E+07 1(11 2.95E-03 1.63E-03 1.17E-03 8.04E-04 2 2.434E+07 5.942E+07 1.88 5.05E-03 2.78E-03 1.99E-03 1.37E-03 3 3.436E+07 9.378E+07 2.97 7.73E-03 4.24E-03 2.94E-03 1.95E-03 4 3.111E+07 1.249E+08 3.96 9.67E-03 5.32E-03 3.69E-03 2.49E-03 5 3.954E+07 1.644E+08 5.21 1.20E-02 6.69E-03 4.67E-03 3.20E-03 6 3.837E+07 2.028E+08 6.43 1.40E-02 7.88E-03 5.58E-03 3.83E-03 7 4.050E+07 2.433E+08 7.71 1.62E-02 9.23E-03 6.61E-03 4.53E-03 8 3.505E+07 2.784E+08 8.82 1.80E-02 1.03E-02 7.42E-03 5.11E-03 9 3.992E+07 3.183E+08 10.09 1.99E-02 1.14E-02 8.29E-03 5.74E-03 10 3.792E+07 3.562E+08 11.29 2.21E-02 1.27E-02 9.20E-03 6.38E-03 11 4.118E+07 3.974E+08 12.59 2.46E-02 1.39E-02 1.OOE-02 7.01E-03 12 3.982E+07 4.372E+08 13.85 2.62E-02 1.49E-02 1.08E-02 7.58E-03 13 4.086E+07 4.781E+08 .15.15 2.85E-02 1.63E-02 1.1 8E-02 8.28E-03 14 3.708E+07 5.15 1E+08 16.32 3.05E-02 1.76E-02 1.29E-02 9.02E-03 15 4.192E+07 5.571E+08 17.65 3.26E-02 1.90E-02 1.40E-02 9.78E-03 16 4.276E+07 5.998E+08 19.01 3.45E-02 2.03E-02 1.5 1E-02 1.05E-02 17 4.646E+07 6.463E+08 20.48 3.67E-02 2.17E-02 1.63E-02 1. 14E-02 18 4.219E+07 6.884E+08 21.82 3.86E-02 2.29E-02 1.72E-02 1.21E-02 Future 1.005E+08 7.889E+08 25.00 4.38E-02 2.60E-02 1.94E-02 1.37E-02 Future 2.209E+08 1.010E+09 32.00 5.53E-02 3.27E-02 2.43E-02 1.72E-02 Future 2.525E+08 1.262E+09 40.00 6.84E-02 4.03E-02 2.98E-02 2.12E-02 Future 2.525E+08 1.515E+09 48.00 8.15E-02 4.80E-02 3.53E-02 2.53E-02 Future 1.893E+08 1.704E+09 54.00 9.14E-02 5.38E-02 3.95E-02 2.83E-02 Future 1.893E+08 1.893E+09 60.00 1.01E-01 5.96E-02 4.37E-02 3.14E-02 WCAP-16918-NP April 2008 Revision 1

6-15 Table 6-3 Calculated Azimuthal Variation of Exposure Rates and Integrated Exposures at the Intermediate Shell Course to Nozzle Shell Course Weld Cumulative Cumulative Neutron Flux (E > 1.0 MeV)

Cycle Irradiation Irradiation (n/cm 2-s)

Length Time Time Cycle (EFPS) (EFPS) (EFPY) 00 150 300 450 1 3.508E+07 3.508E+07 1.11 5.55E+09 3.08E+09 2.28E+09 1.55E+09 2 2.434E+07 5.942E+07 1.88 9.29E+09 5.15E+09 3.78E+09 2.57E+09 3 3.436E+07 9.378E+07 2.97 6.54E+09 3.59E+09 2.39E+09 1.46E+09 4 3.111E+07 1.249E+08 3.96 6.82E+09 3.84E+09 2.73E+09 1.94E+09 5 3.954E+07 1.644E+08 5.21 4.94E+09 2.93E+09 2.15E+09 1.54E+09 6 3.837E+07 2.028E+08 6.43 5.65E+09 3.46E+09 2.68E+09 1.85E+09 7 4.050E+07 2.433E+08 7.71 5.48E+09 3.28E+09 2.58E+09 1.73E+09 8 3.505E+07 2.784E+08 8.82 5.52E+09 3.40E+09 2.6 1E+09 1.86E+09 9 3.992E+07 3.183E+08 10.09 5.17E+09 3.16E+09 2.49E+09 1.79E+09 10 3.792E+07 3.562E+08 11.29 6.3 1E+09 3.56E+09 2.67E+09 1.86E+09 11 4.118E+07 3.974E+08 12.59 7.23E+09 3.46E+09 2.49E+09 1.91E+09 12 3.982E+07 4.372E+08 13.85 4.79E+09 3.2 1E+09 2.4 1E+09 1.70E+09 13 4.086E+07 4.781E+08 15.15 5.94E+09 3.54E+09 2.68E+09 1.86E+09 14 3.708E+07 5.151E+08 16.32 5.45E+09 3.53E+09 2.95E+09 2.06E+09 15 4.192E+07 5.571E+08 17.65 5.07E+09 3.37E+09 2.75E+09 1.89E+09 16 4.276E+07 5.998E+08 19.01 5.22E+09 3.72E+09 3.23E+09 2.09E+09 17 4.646E+07 6.463E+08 20.48 6.OOE+09 3.97E+09 3.3 1E+09 2.44E+09 18 4.219E+07 6.884E+08 21.82 5.17E+09 3.35E+09 2.62E+09 1.84E+09 Future 1.005E+08 7.889E+08 25.00 6.37E+09 3.76E+09 2.77E+09 2.01E+09 Future 2.209E+08 1.010E+09 32.00 6.37E+09 3.76E+09 2.77E+09 2.01E+09 Future 2.525E+08 1.262E+09 40.00 6.37E+09 3.76E+09 2.77E+09 2.0 1E+09 Future 2.525E+08 1.515E+09 48.00 6.37E+09 3.76E+09 2.77E+09 2.0 1E+09 Future 1.893E+08 1.704E+09 54.00 6.37E+09 3.76E+09 2.77E+09 2.01E+09 Future 1.893E+08 1.893E+09 60.00 6.37E+09 3.76E+09 2.77E+09 2.01E+09 WCAP- 16918-NP April 2008 Revision I

6-16 Table 6-3 Calculated Azimuthal Variation of Exposure Rates and Integrated Exposures at the (cont.) Intermediate Shell Course to Nozzle Shell Course Weld Cumulative Cumulative Neutron Fluence (E > 1.0 MeV)

Cycle Irradiation Irradiation (n/cm 2 )

Length Time Time Cycle (EFPS) (EFPS) (EFPY) 00 150 300 450 1 3.508E+07 3.508E+07 1.11 1.95E+17 1.08E+17 7.99E+16 5.45E+16 2 2.434E+07 5.942E+07 1.88 4.21E+17 2.34E+17 1.72E+17 1.17E+17 3 3.436E+07 9.378E+07 2.97 6.45E+17 3.57E+17 2.54E+17 1.67E+17 4 3.111E+07 1.249E+08 3.96 8.57E+17 4.76E+17 3.39E+17 2.28E+17 5 3.954E+07 1.644E+08 5.21 1.05E+18 5.92E+17 4.24E+17 2.89E+17 6 3.837E+07 2.028E+08 6.43 1.27E+18 7.25E+17 5.26E+17 3.59E+17 7 4.050E+07 2.433E+08 7.71 1.49E+18 8.58E+17 6.31E+17 4.29E+17 8 3.505E+07 2.784E+08 8.82 1.68E+18 9.77E+17 7.22E+17 4.94E+17 9 3.992E+07 3.183E+08 10.09 1.89E+18 1.10E+18 8.21E+17 5.66E+17 10 3.792E+07 3.562E+08 11.29 2.13E+18 1.24E+18 9.23E+17 6.36E+17 11 4.118E+07 3.974E+08 12.59 2.43E+18 1.38E+18 1.03E+18 7.15E+17 12 3.982E+07 4.372E+08 13.85 2.62E+18 1.51E+18 1.12E+18 7.83E+17 13 4.086E+07 4.781E+08 15.15 2.86E+18 1.65E+18 1.23E+18 8.59E+17 14 3.708E+07 5.151E+08 16.32 3.06E+18 1.78E+18 1.34E+18 9.35E+17 15 4.192E+07 5.571E+08 17.65 3.28E+18 1.93E+18 1.46E+18 1.01E+18 16 4.276E+07 5.998E+08 19.01 3.50E+18 2.08E+18 1.59E+18 1.10E+18 17 4.646E+07 6.463E+08 20.48 3.78E+18 2.27E+18 1.75E+18 1.22E+18 18 4.219E+07 6.884E+08 21.82 4.OOE+18 2.41E+18 1.86E+18 1.29E+18 Future 1.005E+08 7.889E+08 25.00 4.64E+18 2.79E+18 2.14E+18 1.50E+18 Future 2.209E+08 1.01OE+09 32.00 6.04E+18 3.62E+18 2.75E+18 1.94E+18 Future 2.525E+08 1.262E+09 40.00 7.65E+18 4.57E+18 3.45E+18 2.45E+18 Future 2.525E+08 1.515E+09 48.00 9.26E+18 5.51E+18 4.15E+18 2.96E+18 Future 1.893E+08 1.704E+09 54.00 1.05E+19 6.22E+18 4.68E+18 3.34E+18 Future 1.893E+08 1.893E+09 60.00 1.17E+19 6.94E+18 5.20E+18 3.72E+18 WCAP- 16918-NP April 2008 Revision I

6-17 Table 6-3 Calculated Azimuthal Variation of Exposure Rates and Integrated Exposures at the (cont.) Intermediate Shell Course to Nozzle Shell Course Weld Cumulative Cumulative Iron Atom Displacement Rate Cycle Irradiation Irradiation (dpa/s)

Length Time Time Cycle (EFPS) (EFPS) (EFPY) 00 150 300 450 1 3.508E+07 3.508E+07 1.11 8.64E-12 4.76E-12 3.42E-12 2.35E-12 2 2.434E+07 5.942E+07 1.88 1.44E- 1I 7.92E-12 5.66E-12 3.88E-12 3 3.436E+07 9.378E+07 2.97 1.02E-1 1 5.54E-12 3.59E-12 2.22E-12 4 3.11 1E+07 1.249E+08 3.96 1.06E- 11 5.90E-12 4.10E-12 2.93E-12 5 3.954E+07 1.644E+08 5.21 7.68E-12 4.51E-12 3.24E-12 2.34E-12 6 3.837E+07 2.028E+08 6.43 8.77E-12 5.32E-12 4.01E-12 2.79E-12 7 4.050E+07 2.433E+08 7.71 8.51E-12 5.03E-12 3.86E-12 2.62E-12 8 3.505E+07 2.784E+08 8.82 8.56E-12 5.22E-12 3.92E-12 2.81E-12 9 3.992E+07 3.183E+08 10.09 8.03E-12 4.85E-12 3.74E- 12 2.71E-12 10 3.792E+07 3.562E+08 11.29 9.78E-12 5.48E-12 4.01E-12 2.81E-12 11 4.118E+07 3.974E+08 12.59 1.12E-11 5.33E-12 3.74E-12 2.89E-12 12 3.982E+07 4.372E+08 13.85 7.43E-12 4.92E-12 3.62E-12 2.57E-12 13 4.086E+07 4.781E+08 15.15 9.21E-12 5.43E-12 4.02E-12 2.82E-12 14 3.708E+07 5.15iE+08 16.32 8.46E-12 5.42E-12 4.43E-12 3.11E-12 15 4.192E+07 5.571E+08 17.65 7.90E-12 5.18E-12 4.13E-12 2.86E-12 16 4.276E+07 5.998E+08 19.01 8.10E-12 5.68E-12 4.84E-12 3.17E-12 17 4.646E+07 6.463E+08 20.48 9.29E-12 6.07E- 12 4.96E-12 3.68E-12 18 4.219E+07 6.884E+08 21.82 8.01E-12 5.13E-12 3.93E-12 2.78E-12 Future 1.005E+08 7.889E+08 25.00 9.86E-12 5.76E-12 4.17E-12 3.04E-12 Future 2.209E+08 1.010E+09 32.00 9.86E-12 5.76E-12 4.17E-12 3.04E-12 Future 2.525E+08 1.262E+09 40.00 9.86E-12 5.76E-12 4.17E-12 3.04E-12 Future 2.525E+08 1.515E+09 48.00 9.86E-12 5.76E-12 4.17E-12 3.04E-12 Future 1.893E+08 1.704E+09 54.00 9.86E-12 5.76E-12 4.17E-12 3.04E-12 Future 1.893E+08 1.893E+09 60.00 9.86E-12 5.76E-12 4.17E-12 3.04E-12 WCAP-16918-NP April 2008 Revision 1

6-18 Table 6-3 Calculated Azimuthal Variation of Exposure Rates and Integrated Exposures at the (cont.) Intermediate Shell Course to Nozzle Shell Course Weld Cumulative Cumulative Iron Atom Displacement Rate Cycle Irradiation Irradiation (dpa)

Length Time Time Cycle (EFPS) (EFPS) (EFPY) 00 150 300 450 1 3.508E+07 3.508E+07 1.11 3.03E-04 1.67E-04 1.20E-04 8.26E-05 2 2.434E+07 5.942E+07 1.88 6.54E-04 3.60E-04 2.58E-04 1.77E-04 3 3.436E+07 9.378E+07 2.97 1.OOE-03 5.50E-04 3.81E-04 2.53E-04 4 3.111E+07 1.249E+08 3.96 1.33E-03 7.33E-04 5.09E-04 3.44E-04 5 3.954E+07 1.644E+08 5.21 1.64E-03 9.12E-04 6.37E-04 4.37E-04 6 3.837E+07 2.028E+08 6.43 1.97E-03 1.12E-03 7.9 1E-04 5.44E-04 7 4.050E+07 2.433E+08 7.71 2.32E-03 1.32E-03 9.47E-04 6.50E-04 8 3.505E+07 2.784E+08 8.82 2.62E-03 1.50E-03 1.08E-03 7.48E-04 9 3.992E+07 3.183E+08 10.09 2.94E-03 1.70E-03 1.23E-03 8.56E-04 10 3.792E+07 3.562E+08 11.29 3.3 1E-03 1.90E-03 1.39E-03 9.63E-04 11 4.118E+07 3.974E+08 12.59 3.77E-03 2.12E-03 1.54E-03 1.08E-03 12 3.982E+07 4.372E+08 13.85 4.06E-03 2.32E-03 1.68E-03 1.1 8E-03 13 4.086E+07 4.781E+08 15.15 4.44E-03 2.54E-03 1.85E-03 1.30E-03 14 3.708E+07 5.151E+08 16.32 4.75E-03 2.74E-03 2.01E-03 1.42E-03 15 4.192E+07 5.571E+08 17.65 5.09E-03 2.96E-03 2.19E-03 1.54E-03 16 4.276E+07 5.998E+08 19.01 5.43E-03 3.20E-03 2.39E-03 1.67E-03 17 4.646E+07 6.463E+08 20.48 5.86E-03 3.49E-03 2.62E-03 1.84E-03 18 4.219E+07 6.884E+08 21.82 6.20E-03 3.70E-03 2.79E-03 1.96E-03 Future 1.005E+08 7.889E+08 25.00 7.19E-03 4.28E-03 3.21E-03 2.26E-03 Future 2.209E+08 1.010E+09 32.00 9.37E-03 5.55E-03 4.13E-03 2.94E-03 Future 2.525E+08 1.262E+09 40.00 1.19E-02 7.01E-03 5.18E-03 3.70E-03 Future 2.525E+08 1.515E+09 48.00 1.44E-02 8.46E-03 6.23E-03 4.47E-03 Future 1.893E+08 1.704E+09 54.00 1.62E-02 9.55E-03 7.02E-03 5.05E-03 Future 1.893E+08 1.893E+09 60.00 1.81E-02 1.06E-02 7.81E-03 5.62E-03 WCAP- 16918-NP April 2008 Revision 1

6-19 Table 6-4 Relative Radial Distribution of Neutron Fluence (E > 1.0 MeV) Within the Reactor Vessel Wall Radius Azimuthal Angle (cm) 00 150 300 450 199.79 1.000 1.000 1.000 1.000 204.79 0.586 0.600 0.600 0.603 209.79 0.301 0.316 0.314 0.318 214.79 0.148 0.159 0.158 0.161 219.79 0.068 0.079 0.078 0.082 Note: Base Metal Inner Radius = 199.79 cm Base Metal 1/4T = 204.79 cm Base Metal 1/2T = 209.79 cm Base Metal 3/4T = 214.79 cm Base Metal Outer Radius = 219.79 cm Table 6-5 Relative Radial Distribution of Iron Atom Displacements (dpa) Within the Reactor Vessel Wall RADIUS AZIMUTHAL ANGLE (cm) 00 150 300 450 199.79 1.000 1.000 1.000 1.000 204.79 0.666 0.680 0.665 0.668 209.79 0.416 0.435 0.415 0.420 214.79 0.254 0.273 0.256 0.262 219.79 0.140 0.163 0.153 0.164 Note: Base Metal Inner Radius = 199.79 cm Base Metal 1/4T = 204.79 cm Base Metal 1/2T = 209.79 cm Base Metal 3/4T = 214.79 cm Base Metal Outer Radius = 219.79 cm WCAP-16918-NP April 2008 Revision 1

6-20 Table 6-6 Calculated Fast Neutron Exposure of Surveillance Capsules Withdrawn from Farley Unit 2 Irradiation Time Fluence (E > 1.0 MeV) Iron Displacements Capsule (EFPY) (n/cm 2) (dpa)

U 1.11 6.05E+ 18 1.25E-02 W 3.96 1.73E+19 3.47E-02 X 6.43 2.98E+19 6.09E-02 Z 13.85 4.92E+19 9.82E-02 Y 19.01 6.79E+19 1.35E-01 V 21.82 8.73E+19 1.78E-01 Table 6-7 Calculated Surveillance Capsule Lead Factors Capsule ID And Location Status Lead Factor U (170) Withdrawn EOC 1 3.26 W (200) Withdrawn EOC 4 2.84 X (170) Withdrawn EOC 6 3.38 Z (20°) Withdrawn EOC 12 2.98 Y (20°) Withdrawn EOC 16 3.12 V (170) Withdrawn EOC 18 3.58 WCAP- 16918-NP April 2008 Revision 1

6-21 200-160-1? 120-80 4-0 50 100 150 200 250 300 R Axis (cm)

Figure 6-1a Farley Unit 2 rO Reactor Geometry with a 150 Neutron Pad at the Core Midplane 200 160

? 120 80 40 0 50 100 150 200 250 300 R Axis (cm)

Figure 6-1b Farley Unit 2 r,8 Reactor Geometry with a 260 Neutron Pad at the Core Midplane WCAP- 16918-NP April 2008 Revision 1

6-22 225 175 125 75 25 E

U

.In x

-25

-75

-125

-175

-225 0 50 100 150 200 250 300 R Axis (cm)

Figure 6-2 Farley Unit 2 rz Reactor Geometry with Neutron Pad WCAP-16918-NP April 2008 Revision 1

7-1 7 SURVEILLANCE CAPSULE REMOVAL SCHEDULE The following surveillance capsule removal history meets the requirements of ASTM E185-82'11". The withdrawal schedule for Capsules Y and V was reviewed and approved in NUREG-1825[ 261 , and is consistent with the withdrawal EFPY documented in Table 7-1.

Table 7-1 Farley Unit 2 Surveillance Capsule Withdrawal History Capsule Fluence Capsule Location Lead Factor(l) Withdrawal EFPY(2) (n/cm 2, E > 1.0 MeV)(1)

U 3430 3.26 1.11 6.05E+18 W 1100 2.84 3.96 1.73E+19 X 2870 3.38 6.43 2.98E+19 Z 3400 2.98 13.85 4.92E+19 Y 2900 3.12 19.01 6.79E+19 V 1070 3.58 21.82 8.73E+19 Notes:

1. Updated in Capsule V dosimetry analysis (see Section 6).

2. EFPY from plant startup.

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8-1 8 REFERENCES

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

2. Code of Federal Regulations, 10CFR50, Appendix G, Fracture Toughness Requirements, and Appendix H, Reactor Vessel MaterialSurveillance ProgramRequirements, U.S. Nuclear Regulatory Commission, Washington, D.C.

3. WCAP-14689, Revision 4, "Farley Units 1 and 2 Heatup and Cooldown Limit Curves for Normal Operation and PTLR Support Documentation," April 1998.

4. WCAP-8956, Revision 0, "Alabama Power Company, Joseph M. Farley Nuclear Plant Unit No. 2 Reactor Vessel Radiation Surveillance Program," August 1977.

5. ASTM E185-73, StandardPracticefor ConductingSurveillance Testsfor Light-Water Cooled Nuclear Power Reactor Vessels, American Society for Testing and Materials.

6. Section XI of the ASME Boiler and Pressure Vessel Code, Appendix GQ FractureToughness Criteriafor ProtectionAgainst Failure.

7. ASTM E208, StandardTest Methodfor Conducting Drop-Weight Test to Determine Nil-Ductility Transition Temperature of FerriticSteels, American Society for Testing and Materials.

8. ASTM E399, Test Methodfor Plane-StrainFractureToughness of Metallic Materials,American Society for Testing and Materials.

9. WCAP-11438, "Analysis of Capsule W from the Alabama Power Company Joseph M. Farley Unit 2 Reactor Vessel Radiation Surveillance Program," April 1987.

10. Westinghouse Science and Technology Department Procedure RMF 8804, "Opening of Westinghouse Surveillance Capsules," Revision 2, August 1, 2004.

11. ASTM E185-82, StandardPracticefor ConductingSurveillance Testsfor Light-Water Cooled Nuclear Power Reactor Vessels, E706 (IF), American Society for Testing and Materials.

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

13. Westinghouse Science and Technology Department Procedure RMF 8102, "Tensile Testing,"

Revision 3, March 1, 1999.

14. Westinghouse Science and Technology Department Procedure RMIF 8103, "Charpy Impact Testing," Revision 2, August 1, 1998.

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8-2

15. ASTM E23-06, StandardTest Methodfor Notched Bar Impact Testing of Metallic Materials, American Society for Testing and Materials.

16. W. L. Server, "General Yielding of Charpy V-Notch and Precracked Charpy Specimens," Journal of Engineering Materials and Technology, Vol. 100, April 1978, pp. 183-188.

17. ASTM A370-07, StandardTest Methods and Definitionsfor Mechanical Testing of Steel Products,American Society for Testing and Materials.

18. ASTM E8-04, StandardTest Methodsfor Tension Testing of Metallic Materials,American Society for Testing and Materials.

19. ASTM E21-05, StandardTest Methodsfor Elevated Temperature Tension Tests of Metallic Materials,American Society for Testing and Materials.

20. ASTM E853-0 1, StandardPracticefor Analysis andInterpretationofLight- Water Reactor Surveillance Results, E706(IA), American Society for Testing and Materials.

21. ASTM E693-01, StandardPracticefor CharacterizingNeutron Exposures in Iron and Low Alloy Steels in Terms of DisplacementsPerAtom (DPA), E706(ID), American Society for Testing and Materials.

22. Regulatory Guide 1.190, Calculationaland Dosimetry Methodsfor Determining Pressure Vessel Neutron Fluence, U.S. Nuclear Regulatory Commission, March 2001.

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

24. RSICC Computer Code Collection CCC-650, DOORS 3.2, One-, Two-, and Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code System, April 1998.

25. RSIC Data Library Collection DLC-185, BUGLE-96, Coupled 47 Neutron, 20 Gamma-Ray Group Cross Section LibraryDerivedfrom ENDF/B-Vlfor L WR Shielding and Pressure Vessel Dosimetry Applications, March 1996.

26. NUREG- 1825, Safety EvaluationReport Related to the License Renewal of the Joseph M Farley Nuclear Plant, Units 1 and 2, Docket Nos. 50-348 and 50-364, Southern Nuclear Operating Company, Inc., U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, May 2005.

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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 Farley Unit 2 are described herein. The sensor sets from these capsules have been analyzed in accordance with the current dosimetry evaluation methodology described in Regulatory Guide 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence" [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. This information may also be useful in the future, in particular, as least squares adjustment techniques become accepted in the regulatory environment.

A.1.1 Sensor Reaction Rate Determinations In this section, the results of the evaluations of the six neutron sensor sets withdrawn to date as part of the Farley Unit 2 Reactor Vessel Materials Surveillance Program[A-2] are presented. The capsule designation, location within the reactor, and time of withdrawal of each of these dosimetry sets were as follows:

Capsule ID Azimuthal Location Withdrawal Time Irradiation Time (EFPY)

U 170 End of Cycle 1 1.11 W 200 End of Cycle 4 3.96 X 170 End of Cycle 6 6.43 Z 200 End of Cycle 12 13.85 Y 200 End of Cycle 16 19.01 V 170 End of Cycle 18 21.82 WCAP-16918-NP April 2008 Revision I

A-2 The passive neutron sensors included in the evaluations of Surveillance Capsules U, W, X, Z, Y, and V are summarized as follows.

Reaction of Capsule Sensor Material Interest U W X Z Y V 63 6 Copper Cu(n,(X) °Co 4 4 4 4 4 4 54 Iron Fe(n,p) 54Mn 4 4 4 4 4 4 Nickel 58Ni(n,p)58Co 4 4 4 4 4 4 238 Uranium-238 U(n,f) 13 7Cs 4 4 4 4 4 Neptunium-237 2 37 Np(n,f) 137Cs 4 4 4 4 Cobalt-Aluminum(l) 59 Co(ny)60 Co 4 4 4 4 4 4 Note:

1. The cobalt-aluminum measurements include both bare and cadmium-covered sensors.

Since all the dosimetry monitors were accommodated within the dosimeter block centered at the radial, azimuthal, and axial center of the material test specimen array, gradient corrections were not required for these reaction rates. Pertinent physical and nuclear characteristics of the passive neutron sensors are listed in Table A- 1.

The use of passive monitors such as those listed above do 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 0 The physical characteristics of each monitor

• The operating history of the reactor

• The energy response of each monitor 0 The neutron energy spectrum at the monitor location Results from the radiometric counting of the neutron sensors from Capsules U, W, X, Z, Y, and V are documented in References A-3 through A-7. The radiometric counting of the sensors from Capsule Y and V was carried out by Pace Analytical Services, Inc., located at the Westinghouse Waltz Mill Site. In all cases, the radiometric counting followed established ASTM procedures. Following sample preparation and weighing, the specific activity of each sensor was determined by means of a high-resolution gamma spectrometer. For the copper, iron, nickel, and cobalt-aluminum sensors, analyses were performed by direct counting of each of the individual samples. In the case of the uranium and neptunium fission sensors, the analyses were carried out by direct counting preceded by dissolution and chemical separation of cesium from the sensor material.

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A-3 The irradiation history of the reactor over the irradiation periods experienced by Capsules U, W, X, Z, Y, and V was based on the reported monthly power generation of Farley Unit 2 for Cycles 1 through 18. For the sensor sets utilized in the surveillance capsules, the half-lives of the product isotopes are long enough that a monthly histogram describing reactor operation has proven to be an adequate representation for use in radioactive decay corrections for the reactions of interest in the exposure evaluations. The irradiation history applicable to Capsules U, W, X, Z, Y, and V 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=

NoFYZ-, j Cj[1-e-ItIj][e-I'td]

Pref where:

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

A = Measured specific activity (dps/gm)

No = Number of target element atoms per gram of sensor F = Atom fraction of the target isotope in the target element Y = Number of product atoms produced per reaction Pj = Average core power level during irradiation period j (MWt)

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

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

= Decay constant of the product isotope (1/sec) tj = Length of irradiation period j (sec) td = Decay time following irradiation period j (sec) and the summation is carried out over the total number of monthly intervals comprising the irradiation period.

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A-4 In the equation describing the reaction rate calculation, the ratio [Pj]/[Pref] accounts for month-by-month variation of reactor core power level within any given fuel cycle as well as over multiple fuel cycles. The ratio Cj, which was calculated for each fuel cycle using the transport methodology discussed in Section 6.2, accounts for the change in sensor reaction rates caused by variations in flux level induced by changes in core spatial power distributions from fuel cycle to fuel cycle. For a single-cycle irradiation, Cj is normally taken to be 1.0. However, for multiple-cycle irradiations, particularly those employing low leakage fuel management, the additional Cj term should be employed. The impact of changing flux levels for constant power operation can be quite significant for sensor sets that have been irradiated for many cycles in a reactor that has transitioned from non-low leakage to low leakage fuel management or for sensor sets contained in surveillance capsules that have been moved from one capsule location to another.

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

These flux values represent the cycle dependent results at the radial and azimuthal center of the respective capsules at the axial elevation of the active fuel midplane.

Prior to using the measured reaction rates in the least-squares evaluations of the dosimetry sensor sets, additional corrections were made to the 238U and 237Np 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 238 irradiation. Corrections were also made to the U 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 Farley Unit 2 fission sensor reaction rates for Capsule V are summarized as follows:

Capsule Correction U W X Z Y V 235 U Impurity/Pu Build-in 0.861 0.818 0.777 0.714 0.663 0.618 238 Photo-fission, U(y,f) 0.976 0.978 0.976 0.978 0.978 0.976 Net 238U Correction 0.840 0.800 0.758 0.698 0.648 0.603 Photo-fission, 237 Np(y,f) 0.994 0.994 0.994 0.994 0.994 0.994 These factors were applied in a multiplicative fashion to the decay-corrected uranium fission sensor reaction rates.

Results of the sensor reaction rate determinations for Capsules U, W, X, Z, Y, and V are given in Tables A-4a through A-4f, respectively. The measured specific activities, decay corrected saturated specific activities, and computed reaction rates for each sensor indexed to the radial center of the capsule are listed in these tables. The fission sensor reaction rates are listed both with and without the applied corrections for 238U impurities, plutonium build-in, and gamma ray induced fission effects.

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 O(E > 1.0 MeV) or dpals 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 WCAP-16918-NP April 2008 Revision 1

A-5 reaction rate data, dosimetry reaction cross-sections, and the calculated neutron energy spectrum within their respective uncertainties. For example, Ri +/- Ri = (Gig +/- 8g)O@i g +/- 0g) g relates a set of measured reaction rates, Ri, to a single neutron spectrum, Og, through the multigroup dosimeter reaction cross-section, Gig, 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 Farley Unit 2 surveillance capsule dosimetry, the FERRET code[A-S8 was employed to combine the results of the plant specific neutron transport calculations and sensor set reaction rate measurements to determine best-estimate values of exposure parameters (O(E > 1.0 MeV) and dpa) along with associated uncertainties for the six in-vessel capsules withdrawn to date.

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

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

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

3. The energy dependent dosimetry reaction cross-sections and associated uncertainties for each sensor contained in the multiple foil sensor set For the Farley Unit 2 application, the calculated neutron spectrum was obtained from the results of plant specific neutron transport calculations described in Section 6.2 of this report. The sensor reaction rates were derived from the measured specific activities using the procedures described in Section A. 1.1. The dosimetry reaction cross-sections and uncertainties were obtained from the SNLRML dosimetry cross-section library [A-9]. The SNLRML library is an evaluated dosimetry reaction cross-section compilation recommended for use in LWR evaluations by ASTM Standard El018, "Application of ASTM Evaluated Cross-Section Data File, Matrix E 706 (1IB)."

The uncertainties associated with the measured reaction rates, dosimetry cross-sections, and calculated neutron spectra were input to the least squares procedure in the form of variances and covariances. The assignment of the input uncertainties followed the guidance provided in ASTM Standard E 944, "Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance."

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

Reaction Rate Uncertainties The overall uncertainty associated with the measured reaction rates includes components due to the basic measurement process, irradiation history corrections, and corrections for competing reactions. A high WCAP- 16918-NP April 2008 Revision 1

A-6 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:

These uncertainties are given at the 1 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 multi-group 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 Farley Unit 2 surveillance program, the following uncertainties in the fission spectrum averaged cross-sections are provided in the SNLRML documentation package.

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A-7 These tabulated ranges provide an indication of the dosimetry cross-section uncertainties associated with the sensor sets used in Light Water Reactor (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:

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

Pgg, = [lP - 0gg, + 0 e-H where:

H-= (g -g),)

2y 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.

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

Flux Normalization Uncertainty (Rn) 15%

Flux Group Uncertainties (Rg, Rg,)

(E > 0.0055 MeV) 15%

(0.68 eV < E < 0.0055 MeV) 29%

(E < 0.68 eV) 52%

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A-8 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 Farley Unit 2 surveillance capsules withdrawn to date are provided in Tables A-5 and A-6. In Table A-5, measured, calculated, and best-estimate values for sensor reaction rates are given for each capsule. Also provided in this tabulation are ratios of the measured reaction rates to both the calculated and least squares adjusted reaction rates.

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

A distinction should be made between the Best Estimate/Calculation, or [BE]/[C], ratios and the Measurement/Calculation, or [M]/[C], ratios. In this case, Best Estimate values refer to the combination of calculation and measurement via a least squares adjustment procedure to arrive at the best estimate of the neutron flux (E > 1.0 MeV) with an associated uncertainty. The least squares procedure provides a weighting of calculated and measured input based on the energy response and uncertainty associated with each input parameter. The [BE]/[C] ratios, therefore, represent a comparison of the results of the least squares adjustment with the analytical prediction of the neutron flux (E > 1.0 MeV). The [M]/[C] ratios, on the other hand, provide a direct comparison of actual calculated and measured individual foil reaction rates. Using the [M]/[C] data, a direct comparison of calculated and measured neutron flux (E > 1.0 MeV) can not be made without a suitable weighting of the individual foil results.

The data comparisons provided in Tables A-5 and A-6 show that the adjustments to the calculated spectra are relatively small and well within the assigned uncertainties for the calculated spectra, measured sensor reaction rates, and dosimetry reaction cross-sections. Further, these results indicate that the use of the least squares evaluation results in a reduction in the uncertainties associated with the exposure of the surveillance capsules. From Section 6.4 of this report, it may be noted that the uncertainty associated with the unadjusted calculation of neutron fluence (E > 1.0 MeV) and iron atom displacements at the surveillance capsule locations is specified as 12 percent at the I1a 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 percent to 8 percent for neutron flux (E > 1.0 MeV) and 8 percent to 10 percent for iron atom displacement rate. Again, the uncertainties from the least squares evaluation are at the 1a level.

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A-9 Further comparisons of the measurement results with calculations are given in Tables A-7 and A-8. These comparisons are given on two levels. In Table A-7, calculations of individual threshold sensor reaction rates are compared directly with the corresponding measurements. These threshold reaction rate comparisons provide a good evaluation of the accuracy of the fast neutron portion of the calculated energy spectra. In Table A-8, calculations of fast neutron exposure rates in terms of O(E > 1.0 MeV) and dpa/s are compared with the best estimate results obtained from the least squares evaluation of the capsule dosimetry results. These two levels of comparison yield consistent and similar results with all measurement-to-calculation comparisons falling well within the 20 percent 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 MIC comparisons for fast neutron reactions range from 0.79 to 1.16 for the 27 samples included in the data set.

The overall average M/C ratio for the entire set of Farley Unit 2 data is 0.94 with an associated standard deviation of 9.7 percent.

In the comparisons of best estimate and calculated fast neutron exposure parameters, the corresponding BE/C comparisons for the capsule data sets range from 0.85 to 1.04 for neutron flux (E > 1.0 MeV), and from 0.87 to 1.04 for iron atom displacement rate. The overall average BE/C ratios for neutron flux (E > 1.0 MeV) and iron atom displacement rate are 0.91 with a standard deviation of 7.8 percent and 0.93 with a standard deviation of 6.9 percent, 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 Farley Unit 2 reactor pressure vessel.

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A-10 Table A-i Nuclear Parameters Used in the Evaluation of Neutron Sensors Product Reaction of Target Atom 90% Response Half-life Fission Monitor Material Interest Fraction Range (MeV) (days) Yield (%)

63 Copper Cu (ncx) 0.6917 5.0- 11.9 1925.5 54 Iron Fe (n,p) 0.0585 2.1 - 8.5 312.3 58 Nickel Ni (n,p) 0.6808 1.5 - 8.3 70.82 238 Uranium-238 U (n,f) 1.0000 1.3 - 6.9 10983.3 6.02 237 Neptunium-237 Np (n,f) 1.0000 0.3 - 3.8 10983.3 6.17 59 Cobalt-Aluminum Co (n,y) 0.0015 non-threshold 1925.5 Note:

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

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A-11 Table A-2 Monthly Thermal Generation, Cycles 1 through 4 Cycle 1 Cycle 2 Cycle 3 Cycle 4 Thermal Thermal Thermal Thermal Generation Generation Generation Generation Month (MWt-hrs) Month (MW-hrs) Month (MW-hrs) Month (MW-hrs)

May-81 49210 Nov-82 0 Oct-83 163398 Feb-85 0 Jun-81 369436 Dec-82 1572848 Nov-83 1479567 Mar-85 368968 Jul-81 118595 Jan-83 1967195 Dec-83 1917263 Apr-85 1861582 Aug-81 1830227 Feb-83 1778710 Jan-84 1711893 May-85 1925137 Sep-81 1837261 Mar-83 1969863 Feb-84 1845593 Jun-85 1865725 Oct-81 1948774 Apr-83 1899797 Mar-84 1895910 Jul-85 1769634 Nov-81 1818795 May-83 1970049 Apr-84 1845190 Aug-85 1739953 Dec-81 1912506 Jun-83 1905327 May-84 1950480 Sep-85 1867238 Jan-82 1707819 Jul-83 1960067 Jun-84. 1909440 Oct-85 1943516 Feb-82 10186 Aug-83 1966925 Jul-84 1968023 Nov-85 1874503 Mar-82 1541170 Sep-83 937869 Aug-84 1951599 Dec-85 1962073 Apr-82 1855620 Sep-84 944645 Jan-86 1798238 May-82 1913932 Oct-84 1813687 Feb-86 1755415 Jun-82 1836202 Nov-84 1906767 Mar-86 1945120 Jul-82 1925451 Dec-84 1771677 Apr-86 239320 Aug-82 1963933 Jan-85 239473 WCAP- 16918-NP April 2008 Revision 1

A-12 Table A-2 Monthly Thermal Generation, Cycles 4 through 8 (cont.)

Cycle 5 Cycle 6 Cycle 7 Cycle 8 Thermal Thermal Thermal Thermal Generation Generation Generation Generation Month (MWt-hrs) Month (MW-hrs) Month (MW-hrs) Month (MW-hrs)

May-86 396193 Nov-87 0 Apr-89 0 Nov-90 0 Jun-86 1744613 Dec-87 240584 May-89 172773 Dec-90 0 Jul-86 1625000 Jan-88 1971889 Jun-89 1786822 Jan-91 1459221 Aug-86 1865663 Feb-88 1806542 Jul-89 1864633 Feb-91 1744114 Sep-86 1871967 Mar-88 1973062 Aug-89 1971608 Mar-91 1971550 Oct-86 1966262 Apr-88 1906960 Sep-89 1456223 Apr-91 1237745 Nov-86 1905245 May-88 1973062 Oct-89 1848890 May-91 1965554 Dec-86 1970404 Jun-88 1904396 Nov-89 1815074 Jun-91 1905656 Jan-87 789042 Jul-88 1973019 Dec-89 1971879 Jul-91 1966074 Feb-87 1756640 Aug-88 1973083 Jan-90 1970306 Aug-91 1874009 Mar-87 1839164 Sep-88 1767980 Feb-90 1631313 Sep-91 1901630 Apr-87 1873088 Oct-88 1975740 Mar-90 1971205 Oct-91 1973717 May-87 1972677 Nov-88 1690586 Apr-90 1694856 Nov-91 1784506 Jun-87 1771494 Dec-88 1938045 May-90 1168621 Dec-91 1971598 Jul-87 1970667 Jan-89 1967158 Jun-90 1907902 Jan-92 1853267 Aug-87 1782971 Feb-89 1687171 Jul-90 1970982 Feb-92 1845792 Sep-87 1909196 Mar-89 1516400 Aug-90 1970095 Mar-92 367169 Oct-87 119759 Sep-90 1907101 Oct-90 755300 WCAP- 16918-NP April 2008 Revision I

A-13 Table A-2 Monthly Thermal Generation, Cycles 9 through 12 (cont.)

Cycle 9 Cycle 10 Cycle 11 Cycle 12 Thermal Thermal Thermal Thermal Generation Generation Generation Generation Month (MWt-hrs) Month (MW-hrs) Month (MW-hrs) Month (MW-hrs)

Apr-92 0 Oct-93 0 Apr-95 76112 Nov-96 0 May-92 513304 Nov-93 0 May-95 493007 Dec-96 749110 Jun-92 1783981 Dec-93 1104196 Jun-95 880008 Jan-97 1972929 Jul-92 1877441 Jan-94 1953209 Jul-95 1896021 Feb-97 1688502 Aug-92 1965981 Feb-94 1772701 Aug-95 1865019 Mar-97 1973088 Sep-92 1779781 Mar-94 1962548 Sep-95 1909440 Apr-97 1906788 Oct-92 1742799 Apr-94 1893222 Oct-95 1776999 May-97 1971338 Nov-92 1890054 May-94 1963755 Nov-95 1772332 Jun-97 1909440 Dec-92 1952058 Jun-94 1903898 Dec-95 1939487 Jul-97 1973008 Jan-93 1879525 Jul-94 1973017 Jan-96 1867751 Aug-97 1971815 Feb-93 1114049 Aug-94 1881896 Feb-96 1809698 Sep-97 1909440 Mar-93 1936119 Sep-94 1909440 Mar-96 1832081 Oct-97 1975501 Apr-93 1885890 Oct-94 1975737 Apr-96 1895146 Nov-97 1908804 May-93 1902839 Nov-94 1905343 May-96 1880613 Dec-97 1951236 Jun-93 1889227 Dec-94 1709587 Jun-96 1907027 Jan-98 1972558 Jul-93 1906713 Jan-95 1728025 Jul-96 1973088 Feb-98 1782144 Aug-93 1952573 Feb-95 1742523 Aug-96 1972155 Mar-98 1715128 Sep-93 1433273 Mar-95 555111 Sep-96 1891141 Oct-96 696495 WCAP- 16918-NP April 2008 Revision 1

A-14 Table A-2 Monthly Thermal Generation, Cycles 13 through 16 (cont.)

Cycle 13 Cycle 14 Cycle 15 Cycle 16 Thermal Thermal Thermal Thermal Generation Generation Generation Generation Month (MWt-hrs) Month (MW-hrs) Month (MW-hrs) Month (MW-hrs)

May-98 740426 Nov-99 0 Mar-01 0 Oct-02 117549 Jun-98 1997168 Dec-99 954610 Apr-01 0 Nov-02 1997029 Jul-98 2064600 Jan-00 2064517 May-01 1319568 Dec-02 2064600 Aug-98 2063768 Feb-00 1931400 Jun-01 1785737 Jan-03 2064073 Sep-98 1900736 Mar-00 2060077 Jul-01 2064406 Feb-03 1864800 Oct-98 2067375 Apr-00 1902124 Aug-01 2064600 Mar-03 2064600 Nov-98 1961065 May-00 2064600 Sep-01 1996557 Apr-03 1995225 Dec-98 2064031 Jun-00 1997972 Oct-01 2067375 May-03 2060438 Jan-99 2035712 Jul-00 2056525 Nov-01 1991229 Jun-03 1998000 Feb-99 1864800 Aug-00 2064600 Dec-01 2055914 Jul-03 1961703 Mar-99 1669440 Sep-00 1996280 Jan-02 2033964 Aug-03 2064545 Apr-99 997640 Oct-00 2067375 Feb-02 1864800 Sep-03 1998000 May-99 1820483 Nov-00 1782716 Mar-02 2064600 Oct-03 2066654 Jun-99 1758831 Dec-00 2048450 Apr-02 1995225 Nov-03 1874540 Jul-99 2064228 Jan-01 2064600 May-02 2061520 Dec-03 2064461 Aug-99 2064323 Feb-01 1526944 Jun-02 1997945 Jan-04 2064600 Sep-99 1704166 Jul-02 2063629 Feb-04 1924546 Oct-99 655844 Aug-02 2043899 Mar-04 716672 Sep-02 839216 WCAP- 16918-NP April 2008 Revision 1

A-15 Table A-2 Monthly Thermal Generation, Cycles 17 and 18 (cont.)

Cycle 17 Cycle 18 Thermal Generation Thermal Generation Month (MWt-hrs) Month (MW-hrs)

Apr-04 830891 Nov-05 0 May-04 2064600 Dec-05 1757907 Jun-04 1997445 Jan-06 2058800 Jul-04 2063768 Feb-06 1864800 Aug-04 2064600 Mar-06 2063795 Sep-04 1946302 Apr-06 1995225 Oct-04 2067209 May-06 2064600 Nov-04 1998000 Jun-06 1997584 Dec-04 2063518 Jul-06 2063934 Jan-05 2063795 Aug-06 2060354 Feb-05 1864800 Sep-06 1996807 Mar-05 2062935 Oct-06 2066765 Apr-05 1975356 Nov-06 1998000 May-05 2052224 Dec-06 2064600 Jun-05 1995392 Jan-07 2063573 Jul-05 2064489 Feb-07 1864800 Aug-05 2064600 Mar-07 2053805 Sep-05 1867714 Apr-07 482961 Oct-05 704600 WCAP- 16918-NP April 2008 Revision 1

A-16 Table A-3 Calculated Cj Factors at the Surveillance Capsule Center, Core Midplane Elevation Fuel _D (E > 1.0 MeV) (n/cm 2-s)

Cycle EFPY Capsule U Capsule W Capsule X Capsule Z Capsule Y Capsule V 1 1.11 1.73E+ 11 1.49E+ 11 1.73E+11 1.49E+11 1.49E+ 11 1.73E+11 2 0.77 1.55E+1l 1.80E+11 1.55E+11 1.55E+11 1.80E+ 11 3 1.09 1.36E+11 1.60E+ 11 1.36E+ 11 1.36E+11 1.60E+ 11 4 0.99 1.16E+l 1 1.33E+11 1.16E+11 1.16E+ 1 1.33E+11 5 1.25 1.30E+11 1.12E+I1 1.12E+11 1.30E+11 6 1.22 1.19E+ll 1.05E+11 1.05E+11 1.19E+11 7 1.28 1.11E+l1 1.11E+ll 1.29E+11 8 1.11 1.04E+ 1 1.04E+1 1 1.19E+ 1 9 1.26 9.57E+10 9.57E+10 1.09E+1I 10 1.20 1.09E+1I 1.09E+1I 1.24E+ 11 11 1.30 8.83E+10 8.83E+10 1.05E+1 1 12 1.26 9.34E+10 9.34E+10 1.05E+1 1 13 1.29 1.11E+I1 1.26E+11 14 1.17 1.19E+ll 1.31E+l1 15 1.33 1.14E+ll 1.26E+11 16 1.35 1.16E+ll 1.24E+11 17 1.47 1.18E+l 1 18 1.34 1.11E+ 11 Average 1.73E+11 1.33E+11 1.47E+11 1.04E+I11 1.09E+-iI 1.27E+11 Fuel Cj Cycle EFPY Capsule U Capsule W Capsule X Capsule Z Capsule Y Capsule V 1 1.11 1.000 1.122 1.175 1.431 1.368 1.358 2 0.77 1.164 1.226 1.485 1.419 1.417 3 1.09 1.025 1.089 1.307 1.25 1.258 4 0.99 0.87 0.909 1.109 1.061 1.050 5 1.25 0.883 1.075 1.028 1.020 6 1.22 0.811 1.008 0.963 0.937 7 1.28 1.069 1.022 0.982 8 1.11 1.001 0.957 0.935 9 1.26 0.918 0.878 0.855 10 1.20 1.043 0.997 0.974 11 1.30 0.847 0.81 0.822 12 1.26 0.896 0.857 0.829 13 1.29 1.017 0.989 14 1.17 1.094 1.031 15 1.33 1.041 0.992 16 1.35 1.068 0.977 17 1.47 0.932 18 1.34 0.874 Average 1.000 1.000 1.000 1.000 1.000 1.000 WCAP- 16918-NP April 2008 Revision 1

A-17 Table A-4a Measured Sensor Activities And Reaction Rates Surveillance Capsule U Radially Radially Measured Saturated Adjusted Adjusted Activity Activity Saturated Activity Reaction Rate Reaction Location (dps/g) (dps/g) (dps/g) (rps/atom) 63 60 Cu (ncL) Co (Cd) Top 6.42E+04 5.26E+05 5.26E+05 8.02E-17 Middle 6.47E+04 5.30E+05 5.30E+05 8.08E-17 Bottom 6.79E+04 5.56E+05 5.56E+05 8.48E-17 Average 8.20E-17 54 54 Fe (n,p) Mn Top 1.68E+06 5.43E+06 5.43E+06 8.61E-15 Middle 1.62E+06 5.23E+06 5.23E+06 8.30E-15 Bottom 1.71E+06 5.53E+06 5.53E+06 8.76E-15 Average 8.55E-15 58 5 Ni (n,p) 8Co Top 5.17E+06 8.28E+07 8.28E+07 1.19E-14 Middle 4.84E+06 7.75E+07 7.75E+07 1.11E-14 Bottom 5.29E+06 8.47E+07 8.47E+07 1.21 E-14 Average 1.17E-14 238 137 U (n,f) Cs (Cd) Middle 2.29E+05 9.23E+06 9.23E+06 6.06E-14 2 35 239 Including U, Pu, and yfission corrections: 5.09E-14 237Np (n,f) 137Cs (Cd) Middle 2.15E+06 8.66E+07 T 8.66E+07 5.53E-13 235 239 Including U, Pu, and yfission corrections: 5.49E-13 59 60 Co (n,y) Co Top 1.36E+07 1.11E+08 1.lIE+08 7.27E-12 Middle 1.42E+07 1.16E+08 1.16E+08 7.59E-12 Bottom 1.40E+07 1.15E+08 1.15E+08 7.48E-12 Average 7.44E-12 59 6 Co (n,y) 1Co (Cd) Top 7.76E+05 6.35E+07 6.35E+07 4.15E-12 Middle. 8.09E+06 6.63E+07 6.63E+07 4.32E-12 Bottom 7.82E+06 6.40E+07 6.40E+07 4.18E-12 Average 4.22E-12 Notes:

1. Measured specific activities are indexed to a counting date of July 25, 1983.

2. The average 238U (n,f) reaction rate of 5.09E-14 includes a correction factor of 0.861 to account for plutonium build-in and an additional factor of 0.976 to account for photo-fission effects in the sensor.

3. The average 237 Np (n,f) reaction rate of 5.49E-13 includes a correction factor of 0.994 to account for photo-fission effects in the sensor.

WCAP- 16918-NP April 2008 Revision 1

A-18 Table A-4b Measured Sensor Activities and Reaction Rates Surveillance Capsule W Radially Radially Measured Saturated Adjusted Adjusted Activity Activity Saturated Activity Reaction Rate Reaction Location (dps/g) (dps/g) (dps/g) (rps/atom) 63 Cu (n,a) 6°Co (Cd) Top 1.53E+05 4.15E+05 4.15E+05 6.33E-17 Middle 1.55E+05 4.21E+05 4.21E+05 6.42E-17 Bottom 1.69E+05 4.59E+05 4.59E+05 6.99E-17 Average 6.58E-1 7 4 54 1 Fe (n,p) Mn Top 2.1 1E+06 4.22E+06 4.22E+06 6.70E-15 Middle 2.05E+06 4.1OE+06 4.1OE+06 6.51E-15 Bottom 2.19E+06 4.38E+06 4.38E+06 6.95E-15 Average 6.72E-15 55 5 Ni (n,p) "Co Top 7.28E+06 6.65E+07 6.65E+07 9.51E-15 Middle 6.91E+06 6.31E+07 6.31E+07 9.03E-15 Bottom 8.04E+06 7.34E+07 7.34E+07 1.05E-14 Average 9.68E-15 37 238U (n,f) 1 Cs (Cd) Middle 5.70E+05 6.44E+06 6.44E+06 4.23E-14 Including 235U, 2 39 Pu, and yfission corrections: 3.38E-14 37 237Np (n,f) 1 Cs (Cd) Middle 5.54E+06 6.26E+07 6.26E+07 3.99E-13 Including 235U, 239 Pu, and yfission corrections: 3.97E-13 59 Co (n,y) 60Co Top 2.77E+07 7.5 1E+07 7.5 1E+07 4.90E-12 Middle 2.92E+07 7.92E+07 7.92E+07 5.17E- 12 Bottom 2.78E+07 7.54E+07 7.54E+07 4.92E-12 Average 5.OOE-12 59 60 Co (nY) Co (Cd) Top 1.56E+07 4.33E+07 4.33E+07 2.76E-12 Middle 1.64E+07 4.45E+07 4.45E+07 2.90E-12 Bottom 1.62E+07 4.40E+07 4.40E+07 2.87E-12 Average 2.84E-12 Notes:

1. Measured specific activities are indexed to a counting date of October 28, 1986.

2. The average 238U (n,f) reaction rate of 3.38E-14 includes a correction factor of 0.818 to account for plutonium build-in and an additional factor of 0.978 to account for photo-fission effects in the sensor.

3. The average 237Np (n,f) reaction rate of 3.97E-13 includes a correction factor of 0.994 to account for photo-fission effects in the sensor.

WCAP- 16918-NP April 2008 Revision 1

A-19 Table A-4c Measured Sensor Activities and Reaction Rates Surveillance Capsule X Radially Radially Measured Saturated Adjusted Adjusted Activity Activity Saturated Activity Reaction Rate Reaction Location (dps/g) (dps/g) (dps/g) (rps/atom) 63Cu (n,00 60Co (Cd) Top 2.27E+05 4.52E+05 4.52E+05 6.90E-17 Middle 2.21E+05 4.40E+05 4.40E+05 6.71E-17 Bottom 2.33E+05 4.64E+05 4.64E+05 7.08E-17 Average 6.90E-17 54Fe (n,p) 54Mn Top 2.85E+06 4.33E+06 4.33E+06 6.86E-15 Middle 2.80E+06 4.25E+06 4.25E+06 6.74E-15 Bottom 2.95E+06 4.48E+06 4.48E+06 7.1OE- 15 Average 6.90E-15 58Ni (n,p) 58Co Top 3.24E+07 7.02E+07 7.02E+07 1.OIE-14 Middle 3.07E+07 6.65E+07 6.65E+07 9.52E-15 Bottom 3.34E+07 7.24E+07 7.24E+07 1.04E-14 Average 9.98E-15 59Co (n,y) 60Co Top 4.90E+07 9.76E+07 9.76E+07 6.37E-12 Middle 5.09E+07 1.O1E+08 1.O0E+08 6.61E-12 Bottom 5.06E+07 1.O1E+08 1.01E+08 6.57E-12 Average 6.52E-12 59Co (n,y) 60Co (Cd) Top 2.90E+07 5.77E+07 5.77E+07 3.77E-12 Middle 2.76E+07 5.50E+07 5.50E+07 3.59E-12 Bottom 2.75E+07 5.48E+07 5.48E+07 3.57E-12 Bottom 2.67E+07 5.32E+07 5.32E+07 3.47E-12 Average 3.60E-12 Notes:

1. Measured specific activities are indexed to a counting date of May 17, 1989.

2. There are no fission monitors present in the capsule.

WCAP-16918-NP April 2008 Revision 1

A-20 Table A-4d Measured Sensor Activities and Reaction Rates Surveillance Capsule Z Radially Radially Measured Saturated Adjusted Adjusted Activity Activity Saturated Activity Reaction Rate Reaction Location (dps/g) (dps/g) (dps/g) (rps/atom) 63 6 CU (n,Q) °Co (Cd) Top 2.90E+05 4.25E+05 4.25E+05 6.48E-17 Middle 2.81E+05 4.12E+05 4.12E+05 6.28E-17 Bottom 3.OOE+05 4.40E+05 4.40E+05 6.71E-17 Average 6.49E-17 54 54 Fe (n,p) Mn Top 2.17E+06 4.32E+06 4.32E+06 6.85E-15 Middle 2.06E+06 4.1OE+06 4.10E+06 6.50E-15 Bottom 2.21E+06 4.40E+06 4.40E+06 6.98E-15 Average 6.78E-15 5 5 8Ni (n,p) 8Co Top 7.13E+06 6.83E+07 6.83E+07 9.78E-15 Middle 6.86E+06 6.57E+07 6.57E+07 9.41E-15 Bottom 7.42E+06 7.11E+07 7.11E+07 1.02E-14 Average 9.79E-15 238 37 U (n,f) 1 Cs (Cd) Middle 2.12E+06 7.65E+06 7.65E+06 5.02E-14 2 39 Including 235U, Pu, and yfission corrections: 3.51E-14 37 237Np (n,f) 1 Cs (Cd) Middle 1 1.12E+07 I 4.04E+07 4.04E+07 2.58E-13 235 239 Including U, Pu, and yfission corrections: 2.56E-13 59 60 Co (nY) Co Top 4.37E+07 6.40E+07 6.40E+07 4.18E- 12 Middle 4.49E+07 6.58E+07 6.58E+07 4.29E-12 Bottom 4.30E+07 6.30E+07 6.30E+07 4.1 IE-12 Average 4.19E-12 59 Co (ny) 6 0Co (Cd) Top 2.41E+07 3.53E+07 3.53E+07 2.30E-12 Middle 2.52E+07 3.69E+07 3.69E+07 2.41E-12 Bottom 2.42E+07 3.55E+07 3.55E+07 2.31E-12 Average 2.34E-12 Notes:

1. Measured specific activities are indexed to a counting date of November 1, 1998.

2. The average 238U (n,f) reaction rate of 3.51E-14 includes a correction factor of 0.714 to account for plutonium build-in and an additional factor of 0.978 to account for photo-fission effects in the sensor.

3. The average 237Np (n,f) reaction rate of 2.56E-13 includes a correction factor of 0.994 to account for photo-fission effects in the sensor.

4. The reaction rate for 237Np (n,f) 137Cs (Cd) for Capsule Z was not used in the FERRET least square evaluation due to inconsistency of 237Np (n,f) 137Cs measurement relative to the 3-loop neutron pad data base'.

1. WCAP-14044, Revision 0, "Westinghouse Surveillance Capsule Neutron Fluence Reevaluation," April 1994.

WCAP- 16918-NP April 2008 Revision 1

A-21 Table A-4e Measured Sensor Activities And Reaction Rates Surveillance Capsule Y Radially Radially Measured Saturated Adjusted Adjusted Activity Activity Saturated Activity Reaction Rate Reaction Location (dps/g) (dps/g) (dps/g) (rps/atom) 63 60 Cu (nc() Co (Cd) Top 2.89E+05 3.63E+05 3.63E+05 5.54E-17 Middle 2.80E+05 3.52E+05 3.52E+05 5.37E-17 Bottom 2.84E+05 3.57E+05 3.57E+05 5.45E-17 Average 5.45E-17 54 54 Fe (n,p) Mn Top 2.61E+06 3.56E+06 3.56E+06 5.64E-15 Middle 2.52E+06 3.43E+06 3.43E+06 5.44E-15 Bottom 2.67E+06 3.64E+06 3.64E+06 5.77E-15 Average 5.61E-15 5 58 8Ni (n,p) Co Top 1.36E+07 5.47E+07 5.47E+07 7.83E-15 Middle 1.29E+07 5.19E+07 5.19E+07 7.43E-15 Bottom 1.38E+07 5.55E+07 5.55E+07 7.94E-15 Average 7.73E-15 13 7 238U (n,f) Cs (Cd) Middle 2.61E+06 3.56E+06 3.56E+06 5.64E-15 235 239 Including U, Pu, and yfission corrections: 2.97E-14 237 Np (n,f) 37 1 Cs (Cd) Middle 1.63E+07 ] 4.67E+07 4.67E+07 2.98E-13 235 239 Including U, Pu, and yfission corrections: 2.96E-13 59 Co (ny) 6°Co Top 4.54E+07 5.7 1E+07 5.7 1E+07 3.72E-12 Middle 4.82E+07 6.06E+07 6.06E+07 3.95E-12 Bottom 4.36E+07 5.48E+07 5.48E+07 3.58E-12 Average 3.75E-12 59 60 Co (n,y) CO (Cd) Top 2.52E+07 3.17E+07 3.17E+07 2o07E-12 Middle 2.69E+07 3.38E+07 3.38E+07 2.21E-12 Bottom 2.54E+07 3.19E+07 3.19E+07 2.08E-12 Average 2.12E-12 Notes:

1. Measured specific activities are indexed to a counting date of August 9, 2004.

2. The average 238U (n,f) reaction rate of 2.97E-14 includes a correction factor of 0.663 to account for plutonium build-in and an additional factor of 0.978 to account for photo-fission effects in the sensor.

3. The average 237Np (n,f) reaction rate of 2.96E-13 includes a correction factor of 0.994 to account for photo-fission effects in the sensor.

WCAP- 16918-NP April 2008 Revision 1

A-22 Table A-4f Measured Sensor Activities And Reaction Rates Surveillance Capsule V Radially Radially Measured Saturated Adjusted Adjusted Activity Activity Saturated Activity Reaction Rate Reaction Location (dps/g) (dps/g) (dps/g) (rps/atom) 63 6 Cu (nUc) 0Co (Cd) Top 2.93E+05 3.97E+05 3.97E+05 6.05E-17 Middle 2.84E+05 3.85E+05 3.85E+05 5.87E-17 Bottom 3.OOE+05 4.06E+05 4.06E+05 6.20E-17 Average 6.04E-17 54 54 Fe (n,p) Mn Top 1.90E+06 3.78E+06 3.78E+06 6.OOE-15 Middle 1.89E+06 3.76E+06 3.76E+06 5.97E-15 Bottom 1.93E+06 3.84E+06 3.84E+06 6.09E-15 Average 6.02E-15 5 5 8Ni (n,p) "Co Top 5.22E+06 6.03E+07 6.03E+07 8.63E-15 Middle 4.97E+06 5.74E+07 5.74E+07 8.22E-15 Bottom 5.24E+06 6.05E+07 6.05E+07 8.66E-15 Average 8.51E-15 238 37 U (n,f) 1 Cs (Cd) Middle 3.32E+06 9.OOE+06 9.OOE+06 5.91E-14 235 239 Including U, Pu, and yfission corrections: 3.56E-14 237 37 Np (n,f) 1 Cs (Cd) Middle 2.11 E+07 I 5.72E+07 5.72E+07 3.65E-13 235 2 39 Including U, Pu, and yfission corrections: 3.63E-13 9 60

' Co (nY) CO Top 5.13E+07 6.95E+07 6.95E+07 4.53E-12 Middle 5.42E+07 7.34E+07 7.34E+07 4.79E-12 Bottom 5.22E+07 7.07E+07 7.07E+07 4.61E-12 Average 4.65E-12 59 60 Co (nY) Co (Cd) Top 2.87E+07 3.89E+07 3.89E+07 2.54E-12 Middle 3.04E+07 4.12E+07 4.12E+07 2.69E-12 Bottom 2.88E+07 3.90E+07 3.90E+07 2.55E-12 Bottom 2.89E+07 3.91E+07 3.91E+07 2.55E-12 Average 2.58E-12 Notes:

I. Measured specific activities are indexed to a counting date of November 29, 2007.

2. The average 238U (n,f) reaction rate of 3.56E-14 includes a correction factor of 0.618 to account for plutonium build-in and an additional factor of 0.978 to account for photo-fission effects in the sensor.

3. The average 23 7Np (n,f) reaction rate of 3.63E-13 includes a correction factor of 0.994 to account for photo-fission effects in the sensor.

WCAP-16918-NP April 2008 Revision 1

A-23 Table A-5 Comparison of Measured, Calculated, and Best Estimate Reaction Rates at the Surveillance Capsule Center Reaction Rate (rps/atom)

Reaction Measured Calculated Best Estimate M/C M/BE Capsule U 63 6 Cu(n,(x) °Co 8.19E-17 7.50E-17 7.86E-17 1.09 1.04 54 54 Fe(n,p) Mn 8.55E-15 9.08E-15 8.71E-15 0.94 0.98 58 Ni(n,p) 58Co 1.17E-14 1.29E-14 1.22E-14 0.91 0.96 238U (n,f) 137CS (Cd) 5.09E-14 5.23E-14 4.92E-14 0.97 1.03 237 137 Np (n,f) Cs (Cd) 5.49E-13 5.64E-13 5.42E-13 0.97 1.01 59 60 Co (n,y) Co 7.44E-12 5.56E-12 7.23E-12 1.34 1.03 59 60 Co (n,y) Co (Cd) 4.2 1E-12 4.29E-12 4.30E-12 0.98 0.98 Capsule W 63 6 Cu(n,ct) °Co 6.58E-17 6.64E- 17 6.40E-17 0.99 1.03 54 54 Fe(n,p) Mn 6.72E-15 7.72E-15 6.86E-15 0.87 0.98 58 Ni(n,p) 58 Co 9.68E-15 1.09E-14 9.69E- 15 0.89 1.00 13 7 238U (n,f) Cs (Cd) 3.38E-14 4.28E-14 3.71E-14 0.79 0.91 237 37 Np (n,f) 1 Cs (Cd) 3.97E-13 4.41E-13 3.90E-13 0.90 1.02 59 Co (n,y) 60CO 5.OOE-12 4.03E-12 4.85E-12 1.24 1.03 59 Co (n,y) 60Co (Cd) 2.84E-12 3.13E-12 2.91E-12 0.91 0.98 Capsule X 63 60 Cu(n, .X) Co 6.89E-17 6.61E-17 6.63E-17 1.04 1.04 54 4 Fe(n,p)1 Mn 6.90E- 15 7.86E-15 7.15E-15 0.88 0.97 58 58 Ni(n,p) Co 9.98E-15 1.12E- 14 1.01E-14 0.89 0.99 23 8 37 U (n,f) 1 Cs (Cd) 23 7 Np (n,f) 37 1 Cs (Cd) 59 Co (n,y) 60 Co 6.52E-12 4.65E-12 6.31E-12 1.40 1.03 59 Co (n,y) 60Co (Cd) 3.60E-12 3.59E-12 3.67E-12 1.00 0.98 WCAP- 16918-NP April 2008 Revision 1

A-24 Table A-5 Comparison of Measured, Calculated, and Best Estimate Reaction Rates at the Surveillance (cont.) Capsule Center Reaction Rate (rps/atom)

Reaction Measured Calculated Best Estimate M/C M/BE Capsule Z 63 6 Cu(n,cL) °Co 6.49E-17 5.61E-17 6.40E-17 1.16 1.01 54 54 Fe(n,p) Mn 6.77E-15 6.38E-15 6.82E- 15 1.06 0.99 58 58 Ni(n,p) Co 9.79E-15 8.99E-15 9.59E-15 1.09 1.02 2 38 37 u (n,f) 1 Cs (Cd) 3.51E-14 3.50E-14 3.51E-14 1.00 1.00 237 37 Np (n,f) 1 Cs (Cd) 59 Co (n,y) 6"Co 4.19E-12 3.22E-12 4.07E-12 1.30 1.03 59 60 Co (ny) Co (Cd) 2.34E-12 2.50E-12 2.39E-12 0.94 0.98 Capsule Y 63 60 Cu(n, C) Co 5.45E-17 5.67E- 17 5.33E-17 0.96 1.02 54 4 Fe(n,p)1 Mn 5.61E-15 6.44E- 15 5.66E-15 0.87 0.99 58 Ni(n,p) 58 Co 7.73E-15 9.07E- 15 7.88E-15 0.85 0.98 238 37 U (n,f) 1 Cs (Cd) 2.97E-14 3.52E-14 3.02E-14 0.84 0.98 237 137 Np (n,f) Cs (Cd) 2.96E-13 3.58E-13 3.01E-13 0.83 0.98 59 Co (ny) 60Co 3.75E-12 3.22E- 12 3.65E-12 1.16 1.03 59 Co (ny) 61Co (Cd) 2.12E-12 2.50E-12 2.17E-12 0.85 0.98 Capsule V 63 Cu(noC) 6°Co 6.04E- 17 5.96E- 17 5.82E- 17 1.01 1.04 54 54 Fe(n,p) Mn 6.02E- 15 6.94E- 15 6.20E-15 0.87 0.97 58 58 Ni(n,p) Co 8.51E-15 9.82E-15 8.73E-15 0.87 0.97 238 U (n,f) 137Cs (Cd) 3.56E-14 3.89E-14 3.43E-14 0.91 1.04 237 37 Np (n,f) 1 Cs (Cd) 3.63E-13 4.10E-13 3.64E-13 0.88 1.00 59 Co (ny) 60Co 4.65E-12 3.94E- 12 4.52E-12 1.18 1.03 59 60 Co (n,y) Co (Cd) 2.58E-12 3.04E-12 2.64E-12 0.85 0.98 WCAP-16918-NP April 2008 Revision 1

A-25 Table A-6 Comparison of Calculated and Best Estimate Exposure Rates at the Surveillance Capsule Center 4 (E > 1.0 MeV) (n/cm 2-s)

Uncertainty Capsule ID Calculated Best Estimate (loF) BE/C U 1.74E+11 1.62E+11 6% 0.94 W 1.39E+11 1.20E+1 1 6% 0.86 X 1.48E+11 1.31E+1 1 8% 0.89 Z 1.13E+ 11 1.18E+ 11 7% 1.04 Y 1.14E+Il I 9.66E+10 6% 0.85 V 1.28E+11 1.12E+l 1 6% 0.88 Iron Atom Displacement Rate (dpa/s)

Uncertainty Capsule ID Calculated Best Estimate (lo) BE/C U 3.53E-10 3.40E- 10 8% 0.96 W 2.76E-10 2.45E-10 8% 0.89 X 2.99E-10 2.73E-10 10% 0.92 Z 2.23E-10 2.32E-10 9% 1.04 Y 2.24E-10 1.94E-10 8% 0.87 V 2.57E-10 2.31E-10 8% 0.90 WCAP- 16918-NP April 2008 Revision 1

A-26 Table A-7 Comparison of Measured/Calculated (MIC) Sensor Reaction Rate Ratios Including All Fast Neutron Threshold Reactions M/C Ratio Capsule Cu-63(n,a) Fe-54(n,p) Ni-58(n,p) U-238(nf) Np-237(n,f) Average  % std dev U 1.09 0.94 0.91 0.97 0.97 0.98 7.1 W 0.99 0.87 0.89 0.79 0.9 0.89 8.1 X 1.04 0.88 0.89 N/A N/A 0.94 9.6 Z 1.16 1.06 1.09 1.0 N/A 1.08 6.2 Y 0.96 0.87 0.85 0.84 0.83 0.87 6.0 V 1.01 0.87 0.87 0.91 0.88 0.91 6.5 Average 1.04 0.92 0.92 0.90 0.90 0.94 9.7

% std dev 7.0 8.3 9.5 9.7 6.5 Table A-8 Comparison of Best Estimate/Calculated (BE/C) Exposure Rate Ratios BE/C Ratio Capsule ID (D (E > 1.0 MeV) dpa/s Y 0.94 0.96 W 0.86 0.89 X 0.89 0.92 Z 1.04 1.04 Y 0.85 0.87 V 0.88 0.90 Average 0.91 0.93

% Standard Deviation 7.8 6.9 WCAP- 16918-NP April 2008 Revision 1

A-27 A.2 REFERENCES A-1 Regulatory Guide RG-1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence," U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, March 2001.

A-2 WCAP-88 10, "Southern Alabama Power Company Joseph M. Farley Nuclear Plant Unit No. 1 Reactor Vessel Radiation Surveillance Program," J. A. Davidson, et al., December 1976.

A-3 WCAP-10425, Revision 0, "Analysis of Capsule U from the Alabama Power Company Farley Unit 2 Reactor Vessel Radiation Surveillance Program," October 1983.

A-4 WCAP- 11438, Revision 0, "Analysis of Capsule W from the Alabama Power Company,"

April 1987.

A-5 WCAP-12471, Revision 0, "Analysis of Capsule X from the Alabama Power Company Joseph M. Farley Unit 2 Reactor Vessel Radiation Surveillance Program," December 1989.

A-6 WCAP-15171, Revision 1, "Analysis of Capsule Z from the Alabama Power Company Farley Unit 2 Reactor Vessel Radiation Surveillance Program," February 2000.

A-7 WCAP-1635 1-NP, Revision 0, "Analysis of Capsule Y from Southern Nuclear Operating Company Joseph M. Farley Unit 2 Reactor Vessel Radiation Surveillance Program,"

February 2005.

A-8 A. Schmittroth, FERRETDataAnalysis Core, HEDL-TME 79-40, Hanford Engineering Development Laboratory, Richland, WA, September 1979.

A-9 RSIC Data Library Collection DLC-178, "SNLRML Recommended Dosimetry Cross-Section Compendium," July 1994.

WCAP-16918-NP April 2008 Revision 1

B-1 APPENDIX B LOAD-TIME RECORDS FOR CHARPY SPECIMEN TESTS

• Specimen prefix "CL" denotes Intermediate Shell Plate B7212-1, longitudinal orientation 0 Specimen prefix "CT" denotes Intermediate Shell Plate B7212-1, transverse orientation 0 Specimen prefix "CW" denotes surveillance weld material

• Specimen prefix "CH" denotes heat-affected zone material WCAP- 16918-NP April 2008 Revision 1

B-2 5000.00 .......... . .. .. . .......... ..............

4000.00 n

3000.00 ..........

ca 2000.00 .......... ............

1000.00 ............

n fm +

1.00 2.00 3.00 4.00 5.00 6.00 Time- (ms)

CL30, 50°F 5000.00- ..............

4000.00- ..........

"73000.00- ......................

MOM 2000.00- ................

1000.00-G flfI -

0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)

CL19, 180°F WCAP-16918-NP April 2008 Revision 1

B-3 0.00 1.00 2.00 3.0,0 4.00 5.00 6.00 Time-l (mS)

CL25, 210°F 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)

CL17, 220 0 F WCAP- 16918-NP April 2008 Revision I

B-4 0.00 1.00 2.00 3.00 4.00 S.00 6.00 Time-I (mns)

CL28, 225-F 6.00 Tine-1 (ms)

CL22, 230°F WCAP- 16918-NP April 2008 Revision I

B-5 5 00 0.0 0 . .- -.. . .. . .. .. .. . .. . . .. . .. .. . .. . . .. . .. .. .. .. . .. . . .. .. . .. .. . . .. .. . .. .. .

4000.00 300.0 4 00 0.0 0 3000 00 0....... .... . . . . ...

..........i........i.... . . . . . . . . . . .

0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ins)

CL18, 250°F

$. 00 . . . . . . . . . . . . . . . . : . . . . . . . . . . . .. -. . . . . . . . . . . . . . ,. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .*.. . . . . . . . . . . . . . ..

4 0 00 .00 - .. . . . .. . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . ... . . . . . . . . . . . . . . .

3000.00 ...........

2 0 0G.00 .. . . . . . .. . . . . . . ... .. . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . .. . . . ... . . . . .. . . . . . . .. . . . . . . .. .

0 0 . . . . . .. . . .. .. .. . .. . . .. .. . .. . 3.00 . . .. ... ..

0.0c 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-i (ms)

CL24, 260-F WCAP- 16918-NP April 2008 Revision 1

B-6 n 30 0. .0. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . .

0

-j 2000.00."

1 0 00 .00 .... . . .... . . .. . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . .... . . . . . . . . . . . . . .

0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)

CL16, 265 0 F 50 D0 .00 .. .. . .. .. . .. . .. . .. . . . . . .:... . . . . . ....... . . . .. .. .. . . . . ,. . . . . . . . . . . ... . . . . . . . . . . . . . . . . . .

5:

4000.00 G00 .00 .. . . . . . . . .. . . ....

4000.00 0 .00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (fm)

CL27, 290°F WCAP-16918-NP April 2008 Revision I

B-7 4000.00- ..........

3000.00- . ....... .. . . .............. ............... .............

0

-j 2000.00 .......... ...........

IOG.O- ...................

0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)

CL23, 290-F 300000-0 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)

CL26, 315°F WCAP-16918-NP April 2008 Revision 1

B-8 50 0 0.0 0 . . . . .. .. . .. . . . . . ..... . . . . . . .. . . . . . . .. .. .. . .. .. . .. . . . . . . . . .. . .. .. .. .. .. .

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)

CL21, 340°F 5000.00 4000.00 3000,00

-J 2000.00 1000.00 . ,. ...

0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-i (ms)

CL20, 370°F WCAP- 16918-NP April 2008 Revision 1

B-9 5000.00 ......

4000.00 n

0 3000.00 .. .............. .... . . ............

-J 2000.00 ............

1000.00 ............

flLI 1 i 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ws)

CL29, 380°F 5000.00 .. .. .. .. .. . .. . .. .

4000.00 .......... . . .. .. . .. .. . . .. .. . ..-

n 3000.00 .. . .. . .. . . ... . .. .. ... . .... ..

w 0

-J 2000.00 1000.00 ................

r i l* i =

0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-i (ms)

CT25, 100-F WCAP- 16918-NP April 2008 Revision 1

B-10 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)

CT24, 200°F 00 . . .

5.0 .. . . . . . . . . . =. . ... . . . . . . . . . . . . . . . .. . . . . . .. . . . . . . . . . . . . . . . *..

40 00 .00 . . . . . . . . . . . . ... . . . . . .. .... .... . . . . . . . . . . . .. . .. . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . .

3 000.0 0 .. .. ... ..... .......... .... ..... .....

2 0 00 .0 0 t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . .

10 00 .00 .. .. . . .. . . . . . . . . . . . . . . . . . . . . . . .;... . . . . . . ...... . . . . . . . . . . . . . . . . . . . .

0.00 0.00 1.00 2.00 3.00 4.00 &OD 600 Time..1 (ms)

CT19,0205F WCAP-16918-NP April 2008 Revision I

B-11 SO.0. .O

. 0 . .. . . . . . . . . . . . . . . . . '.. . . . . . . . . . . . . . . . .,. . . . . . . . . . . . . . . . * . .. . . . . . . . . . . * . . . . . . . . . . . . . . .

4000.00 n 3000.00 3000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)

CT16, 225°F 5 0 0. ...... . .. . . . . . .. . . . .. . . . . . . . . . . .

4000.00 3000.00 2000.00 1000.00 0.00 O.00 1.00 2.00 300 4.00 5.00 6.00 Time-1 (ms)

CT23, 230°F WCAP- 16918-NP April 2008 Revision 1

B-12 S 0 00 .00 . . . . . ..... . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . .. . . . . . . . . . .. . . . . . . . . .

0ooooo ........ ............... ..... . ..... ...... .... ..............................

0.00 4000.00 30.0000.

0.00 1.00 2.00 3.00 4.00 5.00 6.00 lime-i (ms)

CT17, 240 0 F 50 0D.00 . . . . . . . . . . .. . . . .* . . . ..... .. . . . . . . . . . . . . . . . . ',. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . *... . . . . . . . . . .

5000.00 3*0 0.00 .. . . .. . . . . . . . .. . . . . .

ca 4000.00 0.00 1.00 2.00 3.00 4.30 5.00 6.00 Time-1 (ms)

CT22, 260-F WCAP-16918-NP April 2008 Revision I

B-13 5000.00- .........

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

0 3000.00- ............ .....

-j 2000.00 ...........

1000.00 .............. . ....... ............. .....

u 00 i 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)

CT29, 275-F 3000.00 0

-J 2000.00-0.00 1.00 2.00 3.00 4.00 5.00 6.00 lime-I (me)

CT20, 280°F WCAP- 16918-NP April 2008 Revision 1

B-14 5000.00- ..............

4000.00- ...........

3000.00-S 2000.00- ............ ............

1000.00- ............. ........... .......

0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)

CT18, 305 0 F 5000.00 a .. .. . .. .. .. . .. .. .. .. . .. . . . . . . . . ... . . . . . . . ..............

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

3000.00 . ......... ....

iu 0

-j 2000.00 ................ .........

1000.00 .............. ........

0.00 0.010 1.00 2.00 3.00 4.00 5.00 6.00 lime-i (ms)

CT28, 345°F WCAP- 16918-NP April 2008 Revision 1

B-15 0

-j Time-i (mns)

CT30, 3750 F n

0

-J 0.00 1.00 2.00 3.00 4.00 500 6.00 Time-1 (ms)

CT21, 400°F WCAP- 16918-NP April 2008 Revision 1

B- 16 5000.00 .............. ....................................

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

n7 3000.00 0

A 2000.00 ........... ........ ......

1000.00 ........................... ......... ............................

0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)

CW28, -25 0 F 5000.00 4000.00 3000.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)

CW21, 20°F WCAP-16918-NP April 2008 Revision 1

B-17 3000.00 .......

o

-a 2 0 00 .00 . . . . .. .. .. . . . . . . . . . . . . . . . ... . . . . . . .... . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . .

10 00 .00 .. .... ... .. ............. .. ...... ..

0.00 i , , , ,

0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-i (ms)

CW25, 30°F 50 00.00 . ... . ...... . .. .. ...

2 0 O0 .00 . .. .. . . .. .. .. . . . .. .. .. . .. .. . . . . . . .=

1 0 0 ..0. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . .. .. ..... . .. . . . .. . . .. .. . .

0.00" 0.00 1.00 2.00 3.00 4.00 5.00 6,00 Tirn*1 (fms)

CW30,340F WCAP-16918-NP April 2008 Revision I

B- 18 0o 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-i (m)

CW24, 50OF F

50,00.00 4000.00 ..........

3000.00 ........... . ... .. ...

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

1000.00 .......... .......... ......

0.00 0.0 0t 1.00 2.00 3.00 4.00 5.00 6.00 Time-i (m)

CW27, 70 0 F WCAP- 16918-NP April 2008 Revision 1

B-19 I000.00 ................ ........I....... ....... ....... ............ . .. . .. .. .................

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

3000.00 .. ... ...... . ...

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

1oo0.00 ... ......... ..... ....... ............

0n4 0.00 1.00

. -C--

2-00 3.00 4.00 5.00 6.00 Time-i (ms)

CW22, 100-F 3000.00-2000.00-0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)

CW20, 125 0 F WCAP-16918-NP April 2008 Revision 1

B-20 B-20 5000.00 1 :.. . . . . . . . . .

4000.00 3000.00 ............ .....

0 2000.00 .............

1000.00 0.00 0.0O0 1.00 2.00 3.00 4.00 5.00 6.00 Time-i (ms)

CW26, 145°F 5000.00 F ................ . .. .. . .

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

n G-S3000.00 .. . .. .. . .. .. . . .. . - .. . .. . . . .... .... ............... .........

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

1000.00 .......... ......... .......... . .... ....... .

0.00 0.0 0o 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)

CW17, 165°F WCAP- 16918-NP April 2008 Revision 1

B-21 4000.00 17 3000.00 2000.00-0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)

CW19, 1850 F n

-J, 0

0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)

CW16, 2300 F WCAP- 16918-NP April 2008 Revision 1

B-22

.0 0

0

-j 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)

CW23, 250OF 3G0O 3000.

0

-j 2000.

0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)

CW18, 260°F WCAP-16918-NP April 2008 Revision 1

B-23 5000.00 4000.00-0"73000.00- ............. ......

0

-j 3000.00-1000.00-0.00D 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (Ms)

CH23, -80°F 5000.00 4000.00 3000.00 .. .........

0, 2000.00 1000.00 ......... - .

0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)

CH29, -15°F WCAP- 16918-NP April 2008 Revision 1

B-24 3000.00 . . . . . . . . . . . . .

0 0 .00 . . . .

2 DO3 . . . . . . . . . . .. . .. . ... .... . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . ... . . . . . . . . . . . . . . ..

2000.00 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)

CH24, 25-F

00. 00 5 DO . . . . . . . .: . . . . . . . . . . . . . . . . . . . . . . . . ,. . . . . . . . . . . . . . . .., . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . .

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)

CH26, 35°F WCAP-16918-NP April 2008 Revision 1

B-25 5000"00-4000.00- ...........

3000.00-0 2000.00 ........... .........

1000.00- . .. .. . .. .. . . . . . . . . ...

r nJ 4 ýP[ I ,

0.00 1 00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)

CH22, 40-F n

'7 3000 00-n 0

-J 3.00 6.00 TIme-1 (Ms)

CH27, 45-F WCAP- 16918-NP April 2008 Revision 1

B-26 "n

0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)

CH18, 50 0 F n

0

-I 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-i (ms)

CH17, 70°F WCAP- 16918-NP April 2008 Revision 1

B-27 5000.00 ................ ..................

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

3000.00 1000.00 0.00 0.0 1.00 5.00 D0 2.00 3.00 4.00 6.00 Time-1 (ms)

CH21, 70°F 4000.00

.*3000.00 2000.00 1000.00 0.00 0.0 1.00 D0 2.00 3.00 4.00 5.00 6.00 Time-i (ms)

CH16, 90 0 F WCAP- 16918-NP April 2008 Revision 1

B-28 5 0 00.0 0 . .. . . . . . . . . .. . .. .. . . .. ... . .. . . . .. . .. . . . . . . . .. . . . . .

4000.00 3000.00 o

2000.00 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-i (ms)

CH19, 115°F 50 0 0.0 0 .. . . . . . . . . . . . .... . . . . . . . . . . . . . . . . . . . . . . . ..

5000.00 4000.00

_.0 3000.00 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 500 6.00 Time-1 (ms)

CH20, 155°F WCAP- 16918-NP April 2008 Revision 1

B-29 nu m7 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-i (am)

CH30, 200-F 4000.00-3000.00 ..................

cc 0

-J 20D0.00- ............ .......

M00.0- ... .... .... . ......... ..

0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-i (ms)

CH25, 260°F WCAP- 16918-NP April 2008 Revision 1

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 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 inASTM E185-82[c-'], 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 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. Hence, the USE values reported in Table C-i, which were used to generate the Charpy V-notch curves, were determined utilizing this methodology.

The lower shelf energy values were fixed at 2.2 ft-lb for all cases.

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

Material Initial U W X Z Y V Int. Shell B7212-1 (LT) 130 94.4 102 96.3 93.8 83.0 86.0 Int. Shell B7212-1 (TL) 95.0 68.9 75.5 68.5 67.8 55;0 69.0 Weld Metal (Heat #BOLA) 144 132 144 150 133 137 124 HAZ Material 158 111 126 128 126 102 118 CVGRAPH v5.3 plots of all surveillance data are provided in this appendix, on the pages following the reference list.

C.1 REFERENCES C-1 ASTM E 185-82, StandardPracticefor ConductingSurveillance Testsfor Light-Water Cooled Nuclear PowerReactor Vessels.

WCAP-16918-NP April 2008 Revision 1

C-2 UNIIRADIATED INTERMEMIATE SHELL PLATE B7212-1 (LONGITUDINAL)

CVGRAPI 5.3 Hyperblic Tangat Carve Printed on 02/06f008 10:15 AM Pap I Coe-ciciitz of CmNe 1 A =66J B =6&9PC=34A6 TO =31.75 D = .OOas4O Epulan is A tBB rrmTb(t-T-IbC+DT))]

Upp= Shelf limnWyI3O.O(1'1ze) Is Shf~ncul =2.2(Plxc Temp@30 ft-lls=-223 Dqg F Tamp@50 fl-Rm=10.0 Deg F FPlatPaey 2 Mateal: SA533B1 ea B7212-I Oduntaln: LT Caqumle: UNIRR Fkcm: nfctn2

-ao 300 I20 IS J5D 400.0 -200.0 -100a0 0.0 100.0 200.0 300.0 400.0 s6.0 600.0 Temperaure In Deg F Charpy V-Notch Data N QMVMndCVN DiflktW

-60.00 12.00 15.27 -3.27

-50.00 15.00 18.32 -3.32

-25.00 19.00 28.64 -9.64

-25.00 34.00 28. 64 5.36

-10.00 47.00 36. 86 10.14

.00 5D. 00 43. 15 6.85 20.00 63.00 57.27 5.73 50.00 72.00 79.70 -7.70 60.00 67.00 86.71 -19.71 WCAP-16918-NP April 2008 Revision 1

C-3

]UNIRRADIATED INTERMICIATE SHELL PLATE B7212-1 (LONGITUDINAL)

Pap 2 Plant Fadcy2 Mari SA533B1 HeatB7212-1 Odnhtaj: LT Capaule UNIRR Flec nkmA2 Charpy V-Notch Data Tevew lp CVN CwapadCVN Dfmu 75.00 103.00 96.23 6.77 100.00 110. 50 108.82 1.68 125.00 123.00 117.35 5.65 150.00 132.00 122. 68 9.32 210.00 134.00 128. 15 5.85 210.00 130.00 128.15 1.85 210.00 132.00 128.15 3.85 Caur im (befficic m.985 WCAP- 16918-NP April 2008 Revision 1

C-4 CAPSULE U INTERMEDIATE SHELL PLATE B7212-i (LONGITUDINAL)

CVYRAPH 5.3 Hyperboalc Tangent Curve Pdnted on 02/0M61008 10:16 AM Page 1 Coefiuieutz of Cure 2 A =-43 B=-46.C= 126.54 TO=-136.29 D =0.O,+00 Eqti is A + B ' [VPrbh -ThAC+DT)]j Uppu S-fhelf 94A(Fizcd Inner Smf Enmc=2.20Fxzm)

Tup=@3O ft-(h93l.2 Deg F TmpOSO f.l4b=141.O Deg F Flat:Fucy2 MeW: SAS33BI Hcat B7212-I Odwali LT Capslac U Plama: nWW2 280 4200 150 100 0o 400.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 60.0 600.0 Temperature In Deg F Chmapy V-Notch Data T¶ruqma CmoedCVYN a

.00 13. 50 11.78 1.72 30.00 23.50 20. 97 2.53 75.00 33.00 27.537 5.43 100.00 40. 50 3..43 3.07 125.00 42. 00 44.20 -2.20 150.00 46. 00 53.28 -7.2U 150.00 34. 00 53. 28 173. 00 53.00 61. 98 18.98 200.00 35.00 69. 73 -1]4.7/3 WCAP-16918-NP April 2008 Revision 1

C-5 CAPSULE U INTERMEDIATE SHELL PLATE ]B7212-1 (LONGITUDINAL)

Pap 2 PlantPFadcy 2 Mutriak SA533B 1 Heat B7212-1 Odmenmto LT Capsule: U Pmhimenc nkr2 Chap V-Notch Data CmuplCYVN 200.00 73.50 69.73 3.77 225.00 38.50 76. 19 12.31 250. 00 90.00 81.29 8.71 300.00 91.50 87.95 3.55 350.00 98.50 91.36 7.14 400.00 97.50 92.99 4.51 Cnbmuk effridm -M65 WCAP- 16918-NP April 2008 Revision I

C-6 CAPSULE W INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

C-GRAPH 53 Hyperolic Tanmt Curve Pdinted on 04&0 10:17 AM Coefficients of Carvc 3 A =5.1 BE-49.9C=92l TO=IS9128 D=0.001400 Equaim is A +B * (mnbfT-ToA)C+tlf)]

Upper ShffEnain*g=I.0(FmI) Lowe UaelfZjY4.2(led)

TempO30 ft-lh4s145A Deg iF Temp*50 ft-bh=1RSA Deg F Flue Fsiey2 Matfial: SA53BI t Bf212-1 Odausio LI Cqmik W Fbo: ntm"2 200 I

ISO

?2 z

100- A 0

0o - 4 - 4 4

-M0.0 -200.0 -100.0 0.0 100.0 200.0 300.0 4m.0 M0.0 ea Temperature In DMM F Charpy V-Notch Data Trmemi ]-n* Cw C YmNd fN

.00 6.00 3.82 2.13 73.00 26.00 9.62 16.33 100.00 34.00 14.78 19.22 125.00 15. 00 22.04 -7.04 150.00 40.00 32.05 7.95 150.00 27.00 32.05 -5.05 175.00 40.00 44.44 -4.44 175.00 31.00 44.44 -6.44 200.00 49.00 57.81 -U.88 WCAP- 16918-NP April 2008 Revision 1

C-7 CAPSULE W INTERMEDIATE SHELL PLATE B7212-1 (LONGrrUDINAL)

Page 2 Plant Farlcy 2 MmuEria SA533B 1 Hcat B7212-1 Odatatien: LT Capsule: W Piuence: nkmA2 Chmrpy V-Notch Data

- wC-N -MVMdCYN 200.00 45.00 57.88 -12.88 225.00 32.00 70.52 11.48 250.00 93.00 80.91 12.09 300.00 103.00 93.71 9.29 350.00 100.00 99.03 .97 400.00 103.00 100.98 2.02 Cmwlima befffdit - .956 WCAP-16918-NP April 2008 Revision 1

C-8 CAPSULE X INITRMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

CVGRAPH 5.3 Hypebolic Tangent Curve Printed on 02106t20W= 1031 AM Page 1 Cofliciits of Cu-vc 4 A =49.25 B =47.oS C =97.3 T1O=184.74 D =0.0E+00 Equtionis At B *Vrbnb'l-T-KlxcDT))]

UppcrM Shmyc9&S*mr*"ucd Low Sfdfnm=212%iz Tcmny30 ft-ilb-142.5 Deg F Tenp@50 fi-b-186.3 Deg F Plaut fPley2 Matedal: SAS3BI Bek 7B212-1 Odmmuou LT Cqlc X FPicnuc: nkmf2 20-15wO -_ _0 ill 50 _

-e.a -200.0 -100ta 0.0 10DLO 200.0 3W0.0 mW.0 io.a eoo0 Temperours In Do F Chmrpy V-Notch Data TmPwmhm -qpmCYN -ulad CYN

.00 2.00 4.26 -2.26 72.00 19.00 10.64 3.36 100.00 21.00 16.23 11.77 125.00 11. 00 23.52 -5.52 125.00 22.00 23.52 -1.52 150.00 33.00 33. 13 -. 13 150.00 37.00 33. 13 3.87 175.00 46.00 44. 56 1.44 200.00 42.00 56.57 -14.57 WCAP- 16918-NP April 2008 Revision 1

C-9 CAPSULE X INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

Pago 2 Plat Fadey 2 Mtcriak SA533B I Heat: B7212,-

Odetoi* LT Casuk, X Plunce* ocm"2 Chmrpy V-Notch Data

- mCN (MWWmdCVN 200.00 47.00 56.57 -9.57 225.00 73.00 67.68 5.32 250.00 92.00 76.80 15.20 350.00 97.00 93. 25 3.75 400.00 102.00 95. 19 6.81 450.00 94. 00 9.5.90 -1.90 Camxztfm benicM m AM1 WCAP-16918-NP April 2008 Revision 1

C-I0 CAPSULE Z INTERMEDIATE SHELL PLATE B7212-I (LONGITUDINAL)

CVGRAPH 53 Hypmbolic Tganmt Cme Plnted on 02100M 10:32 AM Page Coafficita Of Curve 5 A=a U= 45.SC =67J6 TO"=201.76 D=OOE+00 Huivniu is A +.

• Irr0h"-To-TXC4m))1 Uppe SbUVzcl]h9aui93Q Lwa Shel EnHr--2.2Mrmd)

L')

Tcmp30 t--lbs=7"8 Dcg F TcMO@O fl-.-=208.8 DgFP Fla Fw1-y2 Medal: 8A5331B Neat B7212-1 Odualtin LT Capalm Z Fbso nkufta 420

• 150 I

ml Sio o _

-100.0 -200.0 -00.O 0.0 100.0 200.0 300.0 400.0 00.o 600.0 Tempemtur In Doe F Chmapy V-Notch Data T¶rum 1os CW4 c-mvum CN DinflMM

.00 5.00 2.41 2.59 72.00 21.00 3.91 17.09 125.00 17.00 9.81 7.12 150.00 20.00 16.95 3.05 175.00 28.00 28.48 -. 41 190.00 39.00 37.30 1.50 200.00 25.00 44.10 -19.10 210.00 60.00 30.87 9.13 225.00 60. 00 60. 70 -. 70 WCAP-16918-NP April 2008 Revision 1

C-II CAPSUL Z INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

Page 2 Plant Faf* 2 Miat SAS33B1 Heat B7212-1 Odenrflfa LT Capmul Z Flume: nftmA2 Charpy V-Notch Data

'r.llmmu lquliCYN mpubd CVYN 250.00 74.00 74. 33 -. 33 275. aa 94. 00 13. 35 10. 65 300.00 90.00 83. 50 1.50 350.00 91.00 92.54 -1.54 400.00 96.00 93.51 2.49 450.00 98.00 93.73 4.27 Cknsmkwm Om = .974 WCAP-16918-NP April 2008 Revision 1

C- 12 CAPSULE V INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

C-VGRAPH 53 Hypebolc Taanget Camrve Pnted on O2(06#200 10:33 AM Celimcts of Cumve 6 A =4t46 B=4.4C=60A61 TO = 21L37 D =t0.0KX40 Eqution is A +B I rrunh((T-ToA(CtDT]

Uppwe SwefHnac 3.OV(azed Low ShfHnmg=22O(a Temp30 ft4b-s=19I.9 Deg F Temp l50 ft4nz222.6 Deg F Plant Fslcy2 Madal: SA533B1 HesL B7212-1 OIIUIiWE LT Cqsk Y Fluence: nknt2 250 4zo 6'*

ID .S 0

400.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 S00.0 600.0 Temperature In Des P Charpy V-Notch Data 7m3 kSpu CYNT QSmodSCVN 10.00 7.00 2.30 4.70 50.00 3.00 2. 59 5.41 100.00 12.00 4.20 7.80 150.00 22.00 11.62 10.33 175.00 19.00 20. 90 -[.90 180.00 23.00 23.38 -. 38 200.00 28.00 35.11 -7.11 210.00 54.00 41.69 12.31 225.00 48.00 51.53 -3.53 WCAP- 16918-NP April 2008 Revision 1

C-13 CAPSULE Y INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

Page 2 PlantFadry2 maa SA533B1 Heat B7212-1 Odumlent LT Capsule* Y Pluenot n/MA2 Charpy V-Notch Data ThwMsu (*ompnxle C-*

225.00 36. 00 51.53 -15.53 250.00 72. 00 65. 35 6.65 275.00 34. 00 74. 18 9.82 300. 00 31.00 78.88 2.12 325.00 33.00 81. 14 6.86 350.00 77.00 82. 18 -5. 11 CsukJ ' CbeffcmM - .967 WCAP- 16918-NP April 2008 Revision 1

C-14 CAPUE V INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

CVGRAPH 53 Hypebolic Tangmt Cura Praed on WOW= 10:33 AM Page 1 Corifwicnts of Curvc 7 A=44.1 B=-41SC =.73 TO=W27.37 D=.OO0E404i Equation is A + B *1 'mn(T-To)(CT]))j Uppin ShcVEDm'=S6OIFkadIv ~d ncy-20w Tcmpl30 fls=19.0 Dog F Tomp*O5 ftasl2.1 Deg F uet FPly 2 Mmaio: SAS33BI HE aB7212-1 Odnmiako LT Cqmilc V PFbiti: mftg2 3a 2M0 1150 a

so

-Mo.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 SO0.o 6t0 Temperaure In Dog F Chwr V-Notch Data T¶mq alpu CVN 50.00 10. 50 3. 78 6.72 180.00 21.00 23. 13 -2.83 210.00 33.00 36.09 -3.09 220.00 32.00 40.67 -1.67 225.00 35.00 42.99 -7.99 230.00 55.00 45.33 9.67 250.00 64.00 54.45 9.55 260.00 77.00 58. 70 18.30 265.00 74.00 60. 71 13.29 WCAP- 16918-NP April 2008 Revision 1

C-15 CAPSUE V INTERMEDIATE SHELL PLATE 17212-1 (LONGITUDINAL)

Pag 2 Pint Pkaft2 MamiaL SA533B1 Heat: B7212-1 Odnt'm LT Capaue, V Plucnce nkA2 Charpy V-Notch Data Tam-mm3 1npmCYN -u CYN 290.00 35.00 69.37 -34.37 290.00 53.00 69.37 -16.37 315.00 92.00 75.59 16.41 340.00 80.-00 79.70 .30 370.00 78.00 32.65 -4.65 380.00 92.00 13.30 1.70 Cmnttiom tiasdmt - a=

WCAP- 16918-NP April 2008 Revision 1

C-16 UNIRRADIATED INTMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

CvGRAH £.3 Hyperoic Tangmnt Curve P*d*tl on 0206C 03:14 PM Pape 1 CoeFflicta of Cowv I A =4 .3 B =4&.VC=ULf73 TI=21.1B D=O.OFM Equtimis A + B 0rraT ((T-ToA(CtDT))1 Upper Shelf L.R--90. Lower Shelf LR=. d)

Tamp.@LAE, 35 mzil=1.0 Dg F lnFsiy2 MWd: SAS33B Heat B7212-1 m

Odelacti: LT Cqxualo: UNIRR Fumces: nkmt2 ISO a

U 100 50 0 0 I 4M0.0 0.0 300.0 600.0 Temperature In Dog F Chmrlp V-Notch Data "lpS CLmEd arfim"

-60.00 9.00 12. 10 -3.10

-50.00 11.00 14.73 -3.73

-25.00 16.00 23.27 -7.27

-25.00 26. ao 23.27 2.73

- 10.00 35. ao 29.74 5.26 00 40. 00 34.32 5.48

20. 00 49.00 44.77 4.23 50.00 60. 00 39. 94 .06 60.00 53.00 64.43 -11.45 WCAP- 16918-NP April 2008 Revision 1

C-17 UNIRRADIATED INTFRMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

Pap 2 Plan.tFadey 2 Matcriak SA533B1 I-Hat B7212-1 Odmadin: LT Capat UNIRR EPue= nAcmA2 Chap V-Noth Data

- LB 75.00 71.00 70.42 . 538 100.00 30.00 78. 10 1.90 125.00 34.00 83. 19 .81 150.00 91.00 86.35 4.65 210.00 37.00 89. 63 -2.63 210.00 90.00 89. 63 .37 210.00 39-00 89. 63 -. 63 Comudm Cfbeffic -, -

WCAP- 16918-NP April 2008 Revision 1

C-18 CAPSULE U INTERMEDIATE SHELL PHATE B7212-1 (LONGITUDINAL)

CvCIAPH 5.3 Hypufic Iaqgmt Curve Prmit on 02106a= 03:15 PM Papi1 Coeffficints of Con 2 A=4 .42 BI=42S C==l3 TV= 14&39 D=OAIOE_00 Equatim is A t B 0 rrmbTl-To-)CtDTr]

Upper ShelfLJL=352 Lowa Shelf LJL=.0(Phed)

Tamp, 0L.R 35 mila=122.4 Deg F Fist fP 7 2 MEial; SA.3BI eWB 7212-1 Orifhati LT CwwlC U ucMe: nftm"2 20 A

1100 IO 400.0 0.0 300.0 600.0 Temperalum In Dog F Chmarp V-Netch Data T'rMMUM .I. QuudwL.

.00 1.00 8. 57 -. 57 50.00 21.00 16.21 4.72 75.00 27.00 21.78 5.22 100.00 33. 50 28.37 5.13 125.00 30.50 35.83 -5.33 150. 00 37.50 43.73 -6.23 150.00 40.00 43.73 -3.73 175.00 40.00 51.56 -11.56 200.00 63.00 58.80 4.20 WCAP- 16918-NP April 2008 Revision I

C-19 CAPSULE U INTERMEDIATE SHELL PLATE BW7212-1 (LONGITUDINAL)

Pap 2 Plant.Fadcy2 MacriakSA533Bl Heat B7212-1 Odmnafoc. LT CapsukeU luen nkMn2 Charpy V-Notch Data 7ampe-s o W& MR" 200.00 59.00 58.80 .20 225.00 31.00 65.09 15.91 250.00 71.50 70.26 1.24 300. 00 76.00 77.40 -1.40 350.00 30.00 81.31 -1.31 400.00 30.00 83.30 -3.30 Caklcmi Cfetiat- .965 WCAP- 16918-NP April 2008 Revision 1

C-20 CAPSULE W JNTERMEIATE SHELL PLATE 1B7212-1 (LONGITDINAL)

CYVCRAPH 5.3 Hyp Ticbngt Curve Printed on 02/06t2CO 03:15 PM Papl CoefdMints of Cone 3 A-=42tI B= 41222 C=*156*6 TO =196L62 D=UOs0ta0 Equtiimis A + B' rrWm(T-ToA(CtDT))J Upper Shelf L*8.5.A L[anr Shelf ]=.R00Fzed)

Tamp.lR. 35 mdlh=167.9 Deg F Flt FwPecy2 Mated1: SA533BI Heat B7212-1 Odllt LT Capsue W B  : nftur2 200 15D A

E so 04-

-00.0 0.0 300.0 600.0 Temperature In Dog F Chap V-Notch Data

¶wmwan Cw0u3.L.B

.00 6.50 6.37 .13 73.00 19.00 14.57 4.43 100.00 29. 50 19.24 10.26 125.00 18.00 24. 44 -6.44 150.00 34.50 30. 39 4.11 150.00 23.00 30.39 -7.39 175.00 34.50 36.92 -2.42 175.00 34.50 36.92 -2.42 200.00 39.00 43.74 -4.74 WCAP- 16918-NP April 2008 Revision 1

C-21 CAPSULE W INTERMEDIATE SHEUL PLATE B7212-1 (LONGITUDINAL)

Pap 2 Plant Fadcy2 Maeiak SA533B 1 Hcat B7212-1 Odemiatln: LT Capsule: W luence: /cnt&2 Chamrp V-Notch Data OmpIdL.

200.00 37.50 43.74 -6.24 225.00 60. 00 50.52 9.48 250.00 63.00 56.92 6.03 300.00 70. 00 67.66 2.34 350.00 71.00 75. 12 -4.12 400.00 79.50 79. 75 -. 25 Camdwunxf baffciM,- .966 WCAP-16918-NP April 2008 Revision 1

C-22 CAPSULE X INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

CYGRAPH 5.3 Hyperbolic Tangn Curvm Prit on MAW= 03:16 PM Page 1 Codeiits of Com' 4 A=3M.21 I=33.C=107.31 'O = 1MM, D=OMiE00 Equtin is A SB

• funb((T-To)CC+-fl)]

Uppe ShaVLJL-=70. Loe Shelf L1L=A0u20d)

TamupL.R. 35 mils=1R&V Deg F Plant Fweiy2 Mtcdal: SASS3B1 Hca Bfl212-1 Ofrnhtio LT Caeic K PlXgMe: nftt2 w

15D) a IE U 100 0 A 0---

400.0 0.0 300.0 600.0 Temperature In Dog F Charpy V-Notch Data T¶mwan -LEK Qupn~dLIL

.00 2.00 2.24 -. 24 72.00 13.00 7.86 5. 14 I00. 00 21.00 12.31 1.69 125.00 13.00 17.77 -4.77 125.00 13.00 17.77 -4.77 150.00 27.00 24.63 2.37 150.00 27. 00 24. 63 2.37 175.00 31.00 32.50 -1.50 200.00 34.00 40.66 -6.66 WCAP- 16918-NP April 2008 Revision 1

C-23 CAPSUE X IfNTEMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

Page 2 Plant. FPafd2 Maa SA533BI Hat B7212-1 Odmalt PLT C.aulk X Muen nkm^2 Chap V-Notch Data DC-23 200.00 33.00 40.66 -7.66 225.00 55.00 48.25 6.75 250.00 63.00 54.66 H.34 350.00 65.00 67.41 -2.41 400.00 73.00 69.20 3.80 450.00 65.00 69.93 -4.93 Csrulaifm Cbrffi* m-971 WCAP- 16918-NP April 2008 Revision 1

C-24 CAPSUZ INTERMmATE SHELL PLATE B7212-I (LONGITUDINAL)

CVGRAPH 53 Hypeolic Tag= Cmrve Pdmma on 021t6t20 03:17 PM Page I Coefficients Of Cmrve 5 A=33A B=33A4C=6&.02 TO=2091 D=O.00K400 Equikuxib A + B' R'amh((T-To)MC+Dlm)]

Upper S EIr=66.K Low. ShalfLL.,.=.0(Ftizd)

Taup.SL, 35 mils=212.1 De F PFml FmEiy2 Mahtmi: SA533BI Eat B7212-1 Odmusiorn LT COMaI Z Mucn ntt2 200 ISD 10 5D 04-400.0 0.0 300.0 600.0 Temperature In Dig F Charpy V-Notch Data T7uVOmuM lcpi La CompQard LEL

.00 00 .11 -. 11 72.00 11.00 .93 10.02 125.00 5.00 4.70 .30 150.00 12. 00 9. 3 2.62 175.00 1. 00 17. 41 .59 190.00 27. 00 23. 95 3.05 200.00 16. 00 28. 85 -12.85 210.00 40. G0 33. 96 6.04 225.00 41.00 41.50 -. 50 WCAP- 16918-NP April 2008 Revision 1

C-25 CAPSUL Z INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

Pap 2 Plant, Fadey2 Matedal SA.S3B1 Heat B7212-1 OdeltaLT CapulmZ Fina: nkmt2 Cbarpy V-Notch Data

¶rmqau D-mt~dLB.

250.00 52.00 52.09 -. 09 275. 00 64. 00 59. 07 4.93 300.'00 63-00 62.98 .02 350.00 64.00 65.95 -1.95 400.00 67.00 66.62 .38 450.00 65.00 66.77 -1.77 Cmmkhui caab = M.98 WCAP-16918-NP April 2008 Revision 1

C-26 CAPSULE Y INTERMEDIATE SHELL PLATE F7212-I (LONGITUDINAL)

C RAH 5.3 Hypatolt Tangnt Curve PrNte on 02106a008 03:17 PM Page 1 Coc*fiients of Cm-vc 6 A =33.4 B= 33M04C=T7.73 TO=212A D=0A09+- 3 Equtiamis A +e

• rrmb((*rr-TlbCmDI)3]

Upper Shelf L.ILE=66.1 Low" Shelf IR=.D0zcd)

TempALE.R 35 milhs17.1 Dog F Flue Fwluy2 Mtedal: SAS3YB1 Hea B7212-1 Oiicukoi LT Cqskc Y FPmrne aC:tn2 a 1W IL 0 50 0300.0

-800.0 0.0 S00.0 600.0 Temperature In Dog F Charpy V-Notch Data TMwflmu ]ipoLa.& -ampdked LIL 10.00 5.00 .21 4.79 50.00 7.00 .65 6.35 100.00 6.00 2. 61 3.39 150. 00 17.00 9. 55 7.45 175.00 14. 00 16.86 -2.86 180.00 18.00 18.70 -. 70 200.00 19. 00 27. a; -.. 09 210. 00 37. 00 31.69 5.31 225.00 44. 00 38. 65 5.35 WCAP- 16918-NP April 2008 Revision 1

C-27 CAPSUE V INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

Page 2 PlanutfPly2 Macria SA533B1 Heat B7212-1 OdammilLT Capsule:Y Puence- nkM42 Charpy V-Notch Data T"mhwamm -LE 225.00 31.00 38. 65 -7.65 250.00 49.00 48.95 .05 275.00 61.00 56.36 4.64 300.00 63.00 60.90 2.10 325.00 68.00 63.42 4.58 350.00 56.00 64.75 -3.75 Cnudkncnbaefim -372 WCAP-16918-NP April 2008 Revision I

C-28 CAPSULE V INTERMEDIATE SOELL PLATE B7212-i (LONGITUDINAL)

CVGRAPH .3 Hypfoic TaIn Curve Print on 02102M 03:18 PM Page 1 Cocffwicnts of Curve 7 A=37A9 B=37SC=113.73 TO=2f.53 D=S.fE+00 Equtiwi is A + B 0 rrmh((T-ToX)CtfT))]

Upper Shelf LJL=73A Shelf LJL=.OW.Mh)

Temap.@L1- 35 mgifr'AA4 DogEF HatftPly2 Mtal: SA.33BI Hea BflI2-1 Oxnideni. LT Cipadc V Flucu: nicun2 2OO I 150 E0 0a-400.0 0.0 m00.0 o00.0 Temperaure In Dog F Chmapy V-Notch Data Tpmvum UpEdLa -*nmMLIl 50.00 £0.00 2.92 7.09 180. n 20.00 21.42 -1.42 210.00 29. 00 30.32 -1.32 220.00 28. O0 33.56 -5.56 225.00 29. O0 35.20 -6.20 230.00 42. 00 36.86 5.14 230.00 49. 00 43.44 5.56 260.00 55.00 46.62 11.31 265.00 SI. 00 48. 17 2.83 WCAP- 16918-NP April 2008 Revision 1

C-29 CASUE V INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

Page 2 Pimt P*aty 2 MaUdat SA533B1 HIat B7212-I Odenaim r LT Capsul& V Puence- nkt*A Chamrpy V-Notl Data 2nv0.0 ai 290.00 34. 00 55.27 -21.27 290.00 55.00 55.27 -. 27 315.00 68.00 61.07 6.93 340. 00 72. 00 65.49 6.51 370.00 66. 00 69.22 -3.22 380.00 69. 00 70. 14 -1.14 Caonzk OoCdfciml 16 WCAP- 16918-NP April 2008 Revision 1

C-30 UNIRFADIATED INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

CYVCRAPH 5.3 Hypernoc Tang*t Curve Prited on 02Mtf108 11:42 AM Pape Coofficnt9 Of Curve 1 A=S& B m.SL CE= 376 TO=39.23 D=LOO Equuaikais A +B Cfrmn((T-To*ACtfTl)j Tempra-tum at 50% Sher = 393 lant FIrcy2 Mhmial: SA33BI Heat B7212-1 Odcutiwi: LT Cqpeb: UNIRR Flouan: kmftr 125 1w 75 V 0 If 5D

/0 25 0 - J- 4 - - - - 4 4 - - -

0

-MO.0 -200.0 -100.0 0.0 100.0 200.0 300.a 400. 500.0 600.0 Temperture In Dog F Charpy V-Notch Data Tnmpemm

-60.00 3.00 8.55 -. 55

-50.00 12.00 10.62 1.33

-25.00 22.00 17.75 4.25

-25.00 18.00 17.75 .25

-10.00 25.00 23. 59 1.41

.00 30.00 28.16 1.84 20.00 40.00 38.72 1.28 50.00 60.00 56.40 3.60 60.00 43.00 62.15 -14.15 WCAP- 16918-NP April 2008 Revision 1

C-31 UNIRtADIATED InTRME4IATE SHELL PLATE B7212-1 (LONGITUDINAL)

Pag 2 Plmat Farley 2 Murdalk SA533B 1 Heat B7212-1 Ofilawlan: LT Capsue UNIRR Fluenc nm=A2 Charwy V-Notch Data TeMP-StB rP=*qn ran .. QmumrdPanmUSbew 75.00 63.00 70.14 -7.14 100.00 85.00 31.02 9.98 125.00 100.00 88.58 11.42 150.00 100.00 93.37 6.63 210.00 100.00 98.33 1.67 210.00 100.00 98.33 1.67 210.00 100.00 98.33 1.67 Crinuldi Ckbmt- -W WCAP-16918-NP April 2008 Revision 1

C-32 CAPSUE U INTERNMIATE SHELL PLATE B7212-1 (LONGITUDINAL)

CVGRAPH 53 Hypmbol Tangmt Curve Pdnted on 02Wn0 11:42 AM

.Pape 1 Coeffl*acsi of Cmunc 2 A=-S& B=aS. C=10M04 T11=1503 D=0.0OK+00 Equatim is A + B'0fl1(Y-ToAfCtJUf))j Tcmplmx'u al 50% Shr= 150A Wanl Fatky2 Mnfminl: SA533BI Heat B7212-Oamai*o LT Cqms c U Plenc: nzmf2

'IU

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 5u.0 600.0 Temperture In Deg F Charpy V-NMlch Data T¶rmqn. CampowdPoma mws

.00 2.00 4.79 -2.79 50.00 17.00 11.97 5.03 75.00 25. 00 11.27 6.73 100.00 31.00 26. 88 4.12 125.00 38.00 37.68 .32 150.00 44.00 49.85 -5.85 150.00 49.00 49.85 -. 85 175.00 56.00 62.04 -6.04 200.00 58.00 72.88 -14.88 WCAP- 16918-NP April 2008 Revision 1

C-33 CAPSULE U INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

Pap 2 Pint Fley 2 MamtiaL-SA533B1 I-Ht B7212-1 Odenta*d LT Capsuler U Pmuenc alcm2 Charpy V-Notch Data CmrmPMMs 200.00 73.00 72.88 .12 225.00 96.00 81.55 14.45 250.00 100.00 87.90 12.10 300. 00 100.00 95.16 4.84 350.00 100.00 98. 15 1.85 400.00 100.00 99.31 .69 Cowftaliw coffim - -M77 WCAP- 16918-NP April 2008 Revision I

C-34 CAPSULE W INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

CYGRAPHI 53 Hypeablic Tanmgt Crve Pdrnted on 02/222008 11:43 AM Page CoeffKicis of Curve 3 A-a. B =5&C=-74SB TO=-lISA D =-.O0O*E.

Eqptn ii A +B 0 r[ab((T-To)ACtDlJJ Tcnmpnim al.50 SlVr= 188A Want F*ty2 Mami: SA33BI HeaLt B7212-1 Ofiwtow LT Cqctk W Fhl: ftr2 12s 100 II 16 75 t1 UO 25 o i -i + - -1 - I--1 1 -'-1 -

-300.0 -20.0 -100.0 0.0 100.0 200.0 ioa 400.0 SOo.O 600.0 Temperatmre In Dog F clap V-Nidch Data Ta"rmma S caumwpfm mmr

.00 2.00 .64 1.36 73.00 7.00 4.35 2.65 100.00 13.00 1.57 9.43 125.00 24. 00 13. 48 3.52 150.00 29. 00 26.34 2.66 150.00 26. 00 26.34 -. 34 175. 00 37. 00 41. 13 -4.13 175. 00 37. 00 41. 13 -4.13 200.00 SO. 00 57. 71 -7.71 WCAP-16918-NP April 2008 Revision 1

C-35 CAPSULE W INTERMEDIATE SHEOL PLATE il212-1 (LONGITUDINAL)

Pagp 2 Plnt: larie2 MatdcriSA533Bl HatB72lZ-I Odentazion: LT Capsule: W Rhmc=: n/cmA2 Charp V-Notfh Data TMP'MUe ftWPmtpSar CamPmpem me u S sho 200.00 49.00 57. 71 -8.71 225.00 32. 00 72. 71 9.29 250.00 95.00 33.88 11.12 300.00 100.00 95.21 4.79 350.00 100.00 98.70 1.30 400.00 100.00 99.66 .34 Cinxltbn Cfciwabm-M.3 WCAP- 16918-NP April 2008 Revision 1

C-36 CAPSULE X INTERMIEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

CVGRAPH 5.3 Hyperbotl Tang=t Cmve PdntMd on 0222U2( 11:43 AM Pap I Cocffidat of Cum-c 4 A=SI B=SLC=83.52 11=199M7 D=0OE+60 Equtim is A + B rm(*CIT-T)KC+MTm]

Tenp-aMM It 50%Sher= 1983.

Hant Ftlay2 Matedal SA533B1 Hcat B7212-I Odno LT Cqiwlc X luxenec: afmtf 125 100 I

1fl 75 I w t

25 A

0 480.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400. 500.0 600.0 Temperature In Dog F Charp V-Notch Data Tmqnm mplaw Pam -

.00 2.00 .86 1.14 72.00 15.00 4.62 10.30 100.00 20. 0O 8.64 11.36 125.00 20.00 14.69 5.31 125.00 20.00 14.69 5.31 150.00 25.00 23.86 1.14 150.00 25.00 23. 86 1.14 175.00 30. 00 36.31 -6.31 200.00 35. 00 50.92 -15.92 WCAP-16918-NP April 2008 Revision 1

C-37 CAPSULE X IZTEMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

Pagp 2 Pint: Faly2 Maicat SA533B1 Hcat B7212-I OdenmilaLLT CapuleX Pmuence, nm Chap V-Notch Data (0MlmdIFcM'eem 200.00 40.00 50.92 -10.92 225.00 70.00 65.37 4.63 250.00 100.00 77.45 22.55 350.00 100.00 97.41 2.59 400.00 100.00 99.20 .80 450.00 100.00 99.76 .24 Cmclamt Ctdmism - .963 WCAP- 16918-NP April 2008 Revision 1

C-38 CAPSULE Z INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

CYGIRAM 5.3 Hyperolic Tangmt Cmvdintd on O2 11:44AM Papg Coefficimt of Cumve 5 A=SE B=.SMLC=63.2 11T=2L5 D=M..+i0 qutizm is A + B 0 rlih(T-ToC+tm'DJT Tempmma at 50% 8r= 29.0 amnt:

Fm 7 2 Matml: SA533BI HatL B7212-1 OdlWion: LT Cop=]= Z MME akcu' 125 100 75 I

50 25

-400.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 o0.o 60.

Temperature In Dog F Chmpy V-Notch Data hftPMn U-

.00 2.00 .13 1.87 72.00 5.00 1.30 3.70 125.00 10.00 6.37 3.43 130.00 20.00 13.43 6.57 175. 00 25.00 25.48 -. 49 190. 00 35.00 35. 45 -. 45 200. 00 30.00 42.97 -12.97 210.00 60.00 50.83 9.17 225.00 60.00 62.42 -2.42 WCAP- 16918-NP April 2008 Revision 1

C-39 CAPSU Z INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

Pap 2 Plant:adly2 MazdilL SA533B I Heat B7212-1 Odenafdw LT Capsule: Z Flu=e: n/cm'2 Charpy V-Notch Data om m Slwr 250.00 80.00 78.55 1.45 275.00 90.00 88.98 L. 02 300.00 100.00 94.68 5.32 350.00 100.00 98.86 1.14 400.00 100.00 99.76 .24 450.00 100.00 99.95 .05 Caftcbtm Cvdimt - -

WCAP- 16918-NP April 2008 Revision 1

C-40 CAPSULE Y INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

CVGRAPH 5.3 Hypebolic Tanget Curve Pinfed on 0212n2fl0 11:44 AM Pape 1 Couffcirnts of Curve 6 A=-S. B=SLC="SOZ T=210.91 D=-0.EiW p4uiamib A + B 0 rr[n(T-ToA)C+t'))]

Tempfal . SM = 211.0 Hat Fuiey 2 Matmiul: SA533B1 Hea B7212-1 Ozlsicatioz LT Capwle Y Piucuec: nkm"2 125 1i0

'IU 75 5a 25 0o -

-M00.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 SO0.O u.o Temperafture In Do9 F Charpy V-Notch Data TlmuMM 10.00 2.00 .03 1.97 50.00 5.00 .17 4.83 100.00 15.00 1.20 13.80 150.00 20.00 8.15 11.85 175.00 20.00 19.34 .66 180.00 20.00 22.63 -2.63 200. 00 30.00 39.32 -9.32 210.00 60.00 49.10 10.90 225.00 65.00 63.66 1.34 WCAP- 16918-NP April 2008 Revision 1

C-41 CAPSULE Y INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

Page 2 PLnt FPat 2 Mntcrial SA533B1 Hcat B7212-1 Odm=OL LT CapmuIe Y Munce nkle2 Charp V-Noth Data mwrpM Show 0OWMAPM Shew 225.00 50.00 63.66 -19.66 250.00 90.00 82.56 7.44 275.00 100.00 92.75 7.25 300.00 100.00 97.19 2.81 325.00 100.00 98.94 1.06 350.00 100.00 99.61 .39 Cauatium coarid -.. M WCAP- 16918-NP April 2008 Revision I

C-42 CAPSULE V INTERMEDIATE SHELL PLATE R7212-i (LONGITUDINAL)

CYGRAUL 5.3 Hypfbolic Tangt Cue Prind on GWZO 11:50 AM Page 1 Cocfficta of Cnrme 7 A=SO. B=So.C=68.n u-=2 Dn-osE+m Equatio is At+B' rrsnb(r-ToAKCtmD])

Tempmon 110%Sh = 233.3 latFP-.y12 Mahtil: SA533BI Et !B7212-1 Otntiwz LT Cqawla V Pbnce;: ukftn2 125 100 U

U i'K 75 5D 25 0 - - I I I -40.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 00.O 600.0 Temperatre In Dog F Charpy V-Notch Data Tmwam a penm Stam CaupnmPuvmnaw S 50.00 2.00 .48 1.52 180.00 20.00 17.49 2.51 210.00 30.00 33.61 -3.63 220.00 30.00 40.45 -10.45 225.00 40.00 44.00 -4.00 230.00 50.00 47.61 2.39 250.00 70.00 61.93 8.07 260.00 90.00 68.32 21.48 265.00 30.00 71.57 8.43 WCAP- 16918-NP April 2008 Revision 1

C-43 CAPUE V INTERMEDIATE SHELL PLATE 1W7212-1 (LONGITUDINAL)

Pag 2 Plint: Pady 2 MiaL SA533B1 Heat B7212-1 OdentaimtLT CapaulPeV Puicm ncmA2 Chap V-Noth Data T290.0 -l put~cnges 290.00 50. 00 83.90 -33.90 290. 00 75.00 83.90 -8.90 315.00 100.00 91.52 3.48 340.00 100.00 95.72 4.23 370.00 100.00 98. 17 1.83 380.00 100.00 98. 62 1.38 cab.aab Cot mt - .930 WCAP- 16918-NP April 2008 Revision 1

C-44 UNIRRADIATED INTERMEDIATE SHELL PLATE B7212-1 (TRANSVERSE)

CVGRAP 5.3 Hyp*etooic Tangent Curve Prd on 026OM 03:56 PM Page 1 CoDeiciztz Of CurO 1 A = 4L6 B =f46A4C=9L3*.S T073ILM6 D =00G0E400 pugicnis A +BB VVrmh(r-To)C+DT))]

Upper SbcHfEM-95.OVUcd0 Low slfEumm=22(fted Temp @30 ftf&-l-7.5 Deg F TemapO5 ft4-=33.6 Deg F Flent: Fty2 Meial: SA533B 1 Bela Bfl2-1 Odut*o: TL CqudC: UNIR Flbcem: nn2 300 290 4r2 Io zU, 9D SOD 0.

-60.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In D0g F Charpy V-Netch Data TmiMmum hptcVm cCmYN

-50.00 18.50 15.47 3.03

- 50. 00 15.50 15.47 .03

- 30. 00 19.00 15.447 3.53

.00 35. 00 33.,34 1.66

.00 34.50 33. 34 1.16

.00 30. 00 33. 34 -3.34

30. 00 43.00 48. 16 -5.16

30. 00 48.00 48. 16 -. 16

30. 00 52.00 48. 16 3.84 WCAP- 16918-NP April 2008 Revision 1

C-45 UNIR1ADIATED INTERNMIATE SlHELL PLATE 1'7212,-I (TRANSVERSE)

Pap 2 Plant-Padcy2 MaMtiak SA533B1 HcatB7212-I Odamtafi:TL CapaLUNIER Ph== nkat2 Ch"rpy V-Notch Data Thu*Cn= kIw CYzN 100.00 76.50 78. 49 -1.99 100.00 74.00 78. 49 -4.49 100. 00 70.00 78.49 -8.49 150.00 95.00 88. 81 6.19 150.00 98.00 88. 81 9.19 150.00 106.00 88. 81 17.19 210.00 19-00 93. 27 -4.27 210.00 94.00 93.27 .73 210.00 38.00 93. 27 -5.27 Cumzum Qbcmu*S, .980 WCAP-16918-NP April 2008 Revision 1

C-46 CAPSULE U INTERMEDIATE SHELL PLATE F7212-1 (TRANSVERSE)

CVYIAP 5.3 Hypubolc Tkgn Curve P=nd on 02AO6I2OO 03:57 PM Page, 1 Cofficients of Carv 2 A=355*5 B 3SCcIm031 TIV-133A7 DcO0OMiI00 Bqutizmis A + B I0mab((T-To)C+tIl))]

Upper sa*elVfn =6L917mad1 ItM SdflHmn =2.2(24za4 TnpO3Oft--lb=1l6.5 DIcgF TepO@.5 ft-.hs=l81.9 D1g F F@PaIFu'ly2 Maie: SA33BI HEa Bf2-1 OdmaadonwTL Cqumc U Pluanc: nitnt2 a

300 420 1w SD

-00.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 50.O 600.0 Temperture In Dog F Chmrpy V-Notch Data Tmwensu 1low Cw CbmpaudCVN 50.00 15.00 13.21 1.79 75.00 22.50 18. 39 4.11 100.00 21.50 25. 01 -3.51 110.00 32.50 27.99 4.51 125.00 33. 50 32.70 .80 150. 00 37.00 40.70 -3.70 175.00 46.00 48.14 -2.14 175.00 42. 50 48.14 -5.64 200.00 49.50 54.36 -4.86 WCAP- 16918-NP April 2008 Revision 1

C-47 CAPSULE U INTERMEDIATE SHELL PLATE B7212-1 (TRANSVERSE)

Pap 2 Plant PFadey 2 Material SA533B1 Hat B7212-1 Odimn.iornTL Capsulk: U Rucume: ncm'c2 Charpy V-Notch Data 1MOnCYN -Mpa* CYN 225.00 69.00 59. 12 9.88 250.00 67.50 62.50 5.00 275.00 68.00 64.80 3.20 300.00 67.00 66.31 .69 350.00 69.00 67.89 1.11 400.00 73.00 68.51 4.49 CmOzhImUMi eirgi - .977 WCAP- 16918-NP April 2008 Revision 1

C-48 CAPSULE W INTERMEDIATE SHELL PLATE B7212-I (TRANSVERSE)

CVGRAPH 5.3 Hypubc Tangent Curve nd on 020628 03:8 PM Coefficicuix of Curve 3 A =35 BI 36ASC=101.92 T=IM86M D=O010Z00 Baniuo is A + B ' r'nb*f-To)KC+DT))]

Upper Shelf lng=75-W..xd) Lower Sheff Eraj=22#(x4 TcmpO3O ft-lha=161.0 Deg F Teap@50 f-Ibs=218.1 Deg F Plait PFdey2 bMtr: SAS33B1 Bea 7B7212-1 Odmisi IL , Cqumak W F c:n: m2 2W0

~20 0150 100 W

0 4110.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 50.0 600.0 Temperature In Del F Charpy V-Notch Data T¶mwpfMM - CvN 25.00 6.00 5.11 .82 76.00 16.00 9.78 6.22 125.00 29.00 19. 19 9.11 150.00 30.00 26. 39 3.61 150.00 30.00 26.39 3.61 175.00 37. 00 34.88 2.12 175.00 27.00 34.88 -7.83 200.00 30.00 43.83 -13.83 200.00 33.00 43.83 -10.83 WCAP- 16918-NP April 2008 Revision 1

C-49 CAPSULE W INTERMEDIATE SHELL PLATE B7212-1 (TRANSVERSE)

Pag 2 PanFtadey 2 M ia SA533B1 Hat B7212-1 Oderaziou: TL Capsule: W Rluen=: nkmA2 Charpy V-Notch Data

-np CYN Comitd CYN 210.00 a5. o0 47.30 -12.30 225.00 68.00 52.20 15.80 250.00 72.00 59.23 12.77 300.00 78.00 68. 42 9.58 350. 00 68.00 72.68 -4.68 400.00 34. 00 74.41 9-59 CWiM, efci -=.920 WCAP- 16918-NP April 2008 Revision 1

C-50 CAPSULE X iNTERMEDIATE SHELL PIATE B7212.1 (TRANSVERSE)

CVGRALH 5.3 HyperboIk Tangwt Curve Pdrnt on O2MO. 03:58 PM Cocffcets of Co.mn 4 A=3&35 B=m33615C=45S T9 =200M D=IOAO*D)0 Bqutizmis A +B 0 'mb(CT-rTo),(CDTr))]

TmpO30 ft-Ih=192.6 Deg F TempOSO ftibs=2219 Dcg F Flue *mFcy2 MOWW:,SAS33BI HLt B7212-1 Or"m TL C4ApC X Plucme: ntnA2 IS so

-M00.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Tempersurs In Dog F Ch"rpy V-Notch Data Tmwan upW CYN D=muedCVN

.00 3.00 2.21 .79 72.00 19.00 2.45 16.55 150.00 24. 00 8.93 15.07 175.00 18.00 18.86 -. 86 175.00 23.00 18.86 4.14 190. 00 30.00 28.21 1.79 200.00 23.00 33.32 -12.32 200.00 26.00 35.32 -9.32 210.00 38.00 42.43 -4.43 WCAP- 16918-NP April 2008 Revision 1

C-5 1 CAPSULE X 1 PlATE SHELL PLATE BW7212-1 (rlANSVERSE)

Pap 2 Plat Fadcy 2 Maeak SA533B I Heat B7212-1 OditatonIL Caplsule: X Men n/km2 Charpy V-Notch Data

-*qpwlCVN 210.00 45.00 42.43 2.57 225.00 55.00 51.79 3.21 225.00 63.00 51.79 11.21 250. 00 69.00 61.75 7.25 350.00 67.00 68.40 -1.40 450.00 75.00 68.50 6.50 CaOMMIla Cbeffti - AM3 WCAP- 16918-NP April 2008 Revision 1

C-52 CAPSULE Z UITERJMEDIATE SHELL PLATE B7212-1 (TRANSVERSE)

CVGRAPH 5.3 Hyperolic T¶bgt Cve PMd on 02106IO 04:01 PM PageI Coefficients of CUMv S A=35. B=S328C=6631 TO.= 1941 D =O.0E4+0 I Equtim is At B'*r'm(rT-ToCtJDT))J Uppcy M"EfmBnr7.BUxd Low, SwMdfHmw=22#z4 TcmnO3Oft-l-b=113 DcgF TempOSO fi-Ihs=)232 Deg F Flun Fwl"y2 Mateia: SAW3B1 EaL B212-1 OdmumIo :TL Cqsut Z Pbnea nklm2 4

ma 4100.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperfture In Deo F Charp V-Notch Data TOnqESm omqpmUCVN

.00 6.00 2.36 3.64 72.00 4.00 3.62 .33 125.00 17.00 8. 66 8.34 150.00 22.00 14.56 7.44 175.00 28.00 23. 81 4.12 190.00 31.00 30. 86 .14 200.00 18. 00 35.79 -17.79 200. 00 25.00 35.79 -10.79 210. 00 44. 00 40.67 3.33 WCAP- 16918-NP April 2008 Revision 1

C-53 CAPSULE Z INTFERMOIATE SHELL PLATE B7212-1 (TRANSVERSE)

Page 2 Plant Parly 2 Matriak SA533B1 Hmt B7212-1 OdemailoTL -Cape:Z Financ: Wkm'2 Charm V-Notch Data Tempenme ]nl-CYN SowwmCVN 225.00 61.00 47.49 13.51 250.00 56.00 56.37 -. 37 275.00 64.00 61.88 2.12 300.00 76.00 64.87 11.13 350.00 69.00 67. 13 1.87 400.00 62.00 67. 65 -5.65 Csuktam ,,ffic

.9a2 WCAP- 16918-NP April 2008 Revision 1

C-54 CAPSULE Y INTERMEDIATE SHELL PLATE B7212-1 (TRANSVERSE)

CVGRAP 5.3 Hyperbolic Tangemt Curve Prieda on 02A3/20 04:01 PM Pape1 CoeFfcmts of Corve 6 A = 2L6 B=26AC=82.04 TO=219.0 D=0.OOL+00 Equfia is At+B 0rranb(cr-iAC+t)1r]

upper Shef Enmqg-y=55J.imd) low ShfHnmj=220(x4 TomO30 ft-lh=223.5 DeI F Tcmip@5 Rft-1311.7 Deg F Flune Plpy2 MaeW: SA533B1 HEat B7212-I Odnzwukm TL Cpwlc T MiwOM: uhftr2 V00 8100 so 0 r

-*30.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 5w.0 eo0 Temperatue In Deg F Chrpy V-Notch Data FN caupodeCN

.00 2.00 2. 45 -. 45 100.00 5.00 4.95 .05 150.00 21.00 10.47 10.53 150.00 17.00 10.47 6.53 175.00 15.00 15.65 -. 65 200. 00 17.00 22.58 -3.53 200.00 10.00 22.58 -12.58 220.00 23.00 28.90 -. 90 250.00 44.00 38.11 5.89 WCAP-16918-NP April 2008 Revision 1

C-55 CAPSULE Y INTERMEDIATE SHElL PLATE B7212-1 (TRANSVERSE)

Page 2 Plant Parly2 M a SA53D1 H]atB7212-1 Odmwin.TL CapsulreY Puence n/mA2 Charpy V-Noatch Data Thqmapm Comp*6CVYN 260.00 44. 00 40. 78 3.22 275.00 54. 00 44. 25 9.75 300.00 33.00 48. 56 -10.56 310.00 50. 00 49.81 .19 350.00 51.00 52.92 -L.92 375.00 53.00 53.15 4.15 Camukn (a*tft . A8 WCAP- 16918-NP April 2008 Revision 1

C-56 CAPSULE V INTERMEDIATE SHELL PLATE B7212-1 (TRANSVERSE)

CYGRAPH 5.3 Hyprtolic Tangnt Curm PrntSd on 026008 04:02 FM Cocfficiemts of Conre 7 A = 3- 6 B=33AC=42M0 TO=214f3 D=tMOOE.t0 Eustion is A t B' rln((T-ToA(CtDT))j Uppc Self~nmgy9O=S.(md) Lo~w SMff umu=2.2(Fzmm)

Tmlp3O ftDm=2071. Dcg F Tomp@50 ft-lbs.=2.3 Deg F la: Pu*ly 2 Mat: SAS3SBI Heat Bfll2-1 OdenUoa: TL Csqzlc V FlucM: usf2 IT A,

U an o 1 400.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 SO0.0 600.0 Temperture In Dog F Chmp V-Notch Data TmpnmuM -CampowdCYN 100.00 9.00 2. 41 6.52 200.00 21.00 24.29 -3.29 205.00 30.00 27.93 2.07 215.00 36.00 35.73 .27 225.00 36.00 43.52 -7.52 230.00 55.00 47.14 7.86 240.00 55.00 53.49 1.31 260.00 66.00 62.01 3.99 275.00 59.00 63.38 -6.31 WCAP- 16918-NP April 2008 Revision 1

C-57 CAPSULE V INTERMEIATE SHELL PILATE B7212-1 (TRANSVERSE)

Page 2 Plant 1:t! 2 MoaraL- SA533B 1 Heat 7212-1 Odenai*or. ILCapsule. V mum= nkem2' Charpy V-Notch Data

(-mpubd CYN Difrma1i 280.00 69.00 66.11 2.89 305.00 50.00 68.09 -18.09 345.00 65.00 68.86 -3.86 375.00 70.00 68.97 1.03 400.00 61.00 68.99 -7.99 410.00 79.00 68.99 10.01 CskonfwmircisS m M37 WCAP- 16918-NP April 2008 Revision I

C-58 UNIRRADIATED INTERMDATE SEM PLATE 17212-1 (TRANSVERSE)

CVYCAH 5.3 Hypebolic Tanget Cuwe l*P d on WOW= 04:15 PM Pap 1 Coeffici*ets of OMNC 1 A=36M B=36.C=10037 "0=30.36 D=0OOAOO Equadi is A t B' rrbma(T-ToAC÷tI)jI Upper Shr.] L.JL=72.7 Lnw Shlaf I.B.=.O(rcd)

Temp.OL.- 35 mk=(Z.7 Deg F Plane F'loy2 MaMtil: SA533BI HeaL B7212-1 Oduatto: TL Cycea: UNIRR FluMec: nftr 200 I1 I

5D 0 4-

-00.0 0.0 3o0.o 600.0 Temperature In Deog F Chrmy V-Notch Data TmmnMM 1les LI. 1M2,.29 DMaM

-50.00 11.00 12.29 -1.29

-50.00 11.00 12.29 -1.29

-50.00 11.00 12.29 -1.29

.00 27.00 25. 72 1.23

.00 27.00 25. 72 1.28

.00 27.00 23. 72 1.28

30. 00 35.00 36.20 -1.20 30.00 36.00 36.20 -. 20 30.00 39.00 36.20 2.80 WCAP-16918-NP April 2008 Revision 1

C-59 UNIt]RADIATED INTERNM IATE SELL PLATE 17212-1 (TANSVERSE)

Page 2 Plant"Paey2 Matcial SA53_B1 tat B7212-I Odiflaicn:TL CaplzkUNIRR Pi== Wnt2 Chwar V-Notch Data 10pul L.R. CO58. 4I.

100.00 55.00 58.04 -3.04 100.00 56. 00 58. 04 -2.04 100.00 54. 00 56. 04 -4.04 150.00 67.00 66. 44 .56 150.00 68.00 66. 44 1.56 150.00 76. 00 66. 44 9.56 210.00 68.00 70-64 -2.64 210.00 70. 00 70- 64 -. 64 210.00 69. 00 70.64 -1.64 cbuchamscbefims0 - 991 WCAP-16918-NP April 2008 Revision 1

C-60 CAPSULE U INTERMIATE SEMLL PLATE B7212-1 (TRANSVERSE)

C-VY H 5.3 Hypue ic Tlngmt Curve Prined on 0210W=2OO 04:16 PM Pap 1 Coc-ikiEnta of Cam 2 A=3U4 B=34.14C =ENL95 T0=144.=1 D = OM*b00 qut*uim is A +B r m((T-To)*C+DTD)I UpIr ShaltLJL.=6B3 Lnwe Shelf 1.=.&00430d)

TanptL.R 35 mils=147.0 DegF Plant: Fey*2 Mafteda: SASS3B1 He B7212-1 Owujtmklo iL CqWlC U FleAnc: nibnt 2 150 I

U SIw ISO 50 o0~

-400.0 0.0 300.0 600.0 Tempeature In Deg F Charpy V-Notch Data TmwMpMu ]rqpmlL.a IQUlM LIR 50.00 10.50 9.12 1.39 75.00 15.50 13.71 1.72 100.00 20.00 20.03 -. 03 110.00 26.50 22.94 3.56 125.00 30.00 27.67 2.33 150.00 30.00 36.04 -6.04 175.00 40.00 44. 19 -4.19 175.00 39. 50 44. 19 -4.69 200.00 50.00 51.26 -1.26 WCAP- 16918-NP April 2008 Revision 1

C-61 CAPSULE U NERbMDIATE SHELL PLATE B7212-1 (TRANSVERSE)

Pagp 2 Plant Fmdcy2 M=r SA533B1 Heat B7212-1 OdenmmcaTL Capsule: U Flunm nlcnm2 Char*y V-Notch Data 225.00 69.50 56. 79 12.71 250.00 62.50 60.79 1.71 275.00 67.00 63.51 3.49 300.00 63.50 65.30 -1.80 350.00 60.00 67.15 -7. 15 400.00 68.50 67.86 .64 cQuika oCdwiaec,-.372 WCAP-16918-NP April 2008 Revision 1

C-62 CAPSULE W INTERMEDIATE SHELL PLATE B7212-1 (TRANSVERSE)

CVGRIAPH 1.3 Hypefbli Tangent Cumvo Pdmud on 02/0612008 04:17 PM Coeffiximts of Curve 3 A =i343 B = 341.53C=144.7 TO=I1IM33 D = 0.00E40 Equatio is At+B p '*f(T-ToDACtDThIr Uppc Shalt LJ=69.1 LMw Shelf L.=.0=,Ozcd)

Tamp.OL 35 mils=3.3 Dog F Flanct:icy2 Medml: i BI1SAEa B1212-1 Odwmnaio TL CqepsA W PiMw: nkr2 12W IJ IEl 100 D II 0

40.03, 0.0 300.0 600.0 Temperature In Deg F Chmrpy V-Notch Data

-noLE] co-lmJL nMn 25.00 7.00 7. 14 -. 14 76.00 15.00 13.06 1.94 125.00 25.00 21.73 3.27 150.00 30.00 27.17 2.83 150.00 27.00 27. 17 -. 17 175. 00 38.00 33.02 4.98 175.00 27.50 33.02 -5.32 200.00 30. 50 38.96 -1.46 200.00 30.50 38.96 -8.46 WCAP- 16918-NP April 2008 Revision 1

C-63 CAPSULE W INTERMEDIATE SHELL PLATE B7212-1 (TRANSVERSE)

PagB 2 Plant-Padey2 Mtia SA533B1 Hcat* B7212-1 Odemtafia: TL Capsule: W PlFu: nt2 Charpy V-Notch Data Tempeamu lzptdL. COmwulad LJL 210.00 36.50 41.29 -4.79 225.00 53.50 44.65 1.85 250.00 58.50 49.79 1.71 300.00 60.00 57.85 2. 15 350.00 61.00 62.95 -1.95 400.00 64.00 65.86 -1.86 Camw Cimxm9.rffic Mm WCAP- 16918-NP April 2008 Revision 1

C-64 CAPSULE X INTERMEDIATE SHELL PLATE B7212-1 (TRANSVERSE)

CVGR"H 5.3 Hyperolc Tangent Curve Pritd on 02A060008 04:17 PM Coeficients of Cne 4 A=3LA3 B=31A3A C= 124B4 TI=2a2,42 D =O.00_,

Egqnum is A +aB IDnh((T-ToAC+-]DJ Upper Shelf Ljl.62.9 Lower Shelf L.R=A0(mad)

Temp.@L.R. 35 mils-a14.7 Deg F

]Plan Fuosy 2 MacENl: SA3rBI Hea B57212-1 OdnMMon' T Cwwlc X Flumes: njbxt2 20D Ia15D a

I100 5D AA 0

-M0.0 0.0 300.0 600.

Temperature In Deog F Chmrp V-Notch Data TmflMa jap I.1K

.00 4.00 2.44 1.56 72.00 12.00 7.12 4.83 150.00 23.00 19.31 3.62 175.00 23.00 25. 12 -2.12 175.00 21.00 25. 12 -4.12 190.00 36.00 28. I1 7.19 200.00 23.00 31.32 -1.32 200.00 27.00 31.32 -4.32 210.00 23.00 33.84 -5.84 WCAP-16918-NP April 2008 Revision 1

C-65 CAPSULE X INTERMEDIATE SHDELL PLATE B7212-1 (TRANSVERSE)

Page 2 Plant. PFmy2 Macriat SA533B1 Hcat B7212-1 OtmtunTL CaulerX mPlnen nk/m2 Charpy V-Notch Data 10taLK.

210.00 30.00 33.84 -3.84 225. 00 40. O0 37.54 2.46 225.00 44. 00 37.54 6.46 250.00 53.00 43. 29 9.71 350.00 54.00 57. 61 -3.61 450.00 62.00 61.72 .28 ccawhjioao C3icm - 944 WCAP- 16918-NP April 2008 Revision 1

C-66 CAPSIUE Z INTERMEDIATE SHELL PLATE B7212-1 (TRANSVERSE)

CVGRAPH 5.3 Hypai nt Curve PdnS on 02 O 04:18 PM Cocflicat g Corve 5 A =X26A9 B =,26A C=.71.S9 T=f2O.73 D0=G.E+00 Eqation is A + B

• rl*f(fr-ToACtDl'))]

Uppcr ghcLJi=53A La Shelf LR=.O(cd)

TapmpLA 3S milr=f&0 Dog F Fitn P1 7 2 Materl: SA533BI eaC B7212-1 Odmalk TL Capuel Z PlAu nkft'2 2W AISO IL100 so 0 4-400.0 0.0 300.0 600.0 Temperatur In Dog F Chorpy V-Notch Data Trayspm. lapdt.&

.00 2.00 .19 1.81 72.00 .00 1.33 - 1. 31 125.00 7.00 35.52 1.41 150.00 15.00 10.02 4.93 175.00 22.00 16.89 5. 11 190.00 22.00 22.02 -. 02 200.00 14. 00 25.68 -11.61 200.00 19.00 23.68 -6.61 210.00 30.00 29.37 -63 WCAP-16918-NP April 2008 Revision 1

C-67 CAPSULE Z INTERMEDIATE SHELL PLATE B7212-1 (TRANSVERSE)

Page 2 Plant PFadcy 2 Maeriak SA533B1 Heat B7212-1 Odemori-T, Capsuar Z luence: nkcmn2 Chary V-Notc Data Tepeem* IQW* E. CLmad L.E.

225.00 44.00 34.69 9.31 250.00 45.00 42.06 2.94 275.00 43.00 47.06 -4.06 300.00 55.00 50.02 4.9.

350. 00 52.00 52.50 -. 50 400.00 50.00 53.16 -3.16 Cawk1m cbeffici*-.g61 WCAP- 16918-NP April 2008 Revision 1

C-68 CAPSULE V INTERMEDIATE SHEML PLATE B7212-1 (TRANSVERSE)

CVGRAPH .3 Hype Tangent Cmrve Pdn on 210fi 04:18 FM PANe 1 Coe*fcekmts of Carvc 6 A= 23B B 22SC==W.S ¶1=213.74 D =0.Oi)E0.

Equl*i*is A + B

• rrTb(Tr-TlbC+mD))]

Upper ShelfX ,44.8 Lower Self IB=.R(I 1 Ied)

Tamql @LR. 35 mik=*26&4 Deg F FPlan-ltcy2 MateOW: SA533BI Ha B212-1 OdeItSUon: TL Cquwkc Y Furnce: sft2 20 I.100 s

,I 0 -

o.0-0.0 300.0 600.0 Temperature In 0Dg F Chap V-Nutch Data 76pmOSNn IPlt LK.

.00 4.00 .25 3.75 100.00 4.00 2.67 1.33 150.00 14.00 7.87 6.13 150.00 12.00 7.87 4.13 175.00 10.00 12. 59 -2.59 200.00 15.00 18.70 -3.70 200.00 13.00 18. 70 -5.70 220.00 22.00 24.09 -2.09 250.00 36. 00 31.64 4.36 WCAP- 16918-NP April 2008 Revision 1

C-69 CAPSULE V INTERMEDIATE SHELL PLATE B7212-1 (TRANSVERSE)

Pag5 2 Plant. aty 2 MatIcak SA533B1 Hct B7212-1 OdemattoilTL CaPOuIeY Phuence n/mr2 Charpy V-Notch Data

- LaB Di S 260.00 37.00 33.78 3.22 275.00 42.00 36.51 5.49 300.00 34.00 39.86 -5.86 310.00 41.00 40.82 .18 350.00 43.00 43. 19 -. 19 375.00 43.00 43.90 -. 90 Ca s CQemicdM - -%7 WCAP-16918-NP April 2008 Revision 1

C-70 CAPSULE V INTAEREIATE SDELL PLATE B7212-1 (TRANSVERSE)

CVGRAPH .3 Hypatbi Twgu Crvc

• Prind on 02100M 04:19 PM Coai*eats of Curm 7 A = 21.14 B=21.14C = 41.A2 TO=20.AI D =SLO.*0R0 Equatkis A ÷B 0 rrmn(T-TXCtDIT)].

Upper Sherf LXL=3 Lnw* SblB.=:.D*Fmi)

Tamp.L.K 35 nid=215S9 Deg F Plant: Fdty 2 Mutedal: SA533B1 Hea IB7212-1 Odnilot TL Cqmwlc V Finme: uibn"2 ISO IL100 D

5O W I 0

,M0.0 0.0 300.0 600.0 Temperture In Deog F Charpy V-Notch Data TRmwa IMmOUeL.R a-100.00 11.00 .32 10.68 200.00 22.00 24. 32 -2.32 205.00 30.00 27. 72 2.23 215.00 34.00 34.47 -. 47 225.00 36.00 40.53 -4.53 230.00 48.00 43.14 4.86 240.00 47. 00 47.42 -. 42 260.00 58.00 52.57 5.43 275.00 50.00 54.43 -4.43 WCAP-16918-NP April 2008 Revision 1

C-71 CAPSULE V INTERMEDIATE SnHELL PLATE B7212-1 (TRANSVERSE)

Pag5 2 Plant FPIey2 Mawlai SA533B1 Hat B7212-1 Odenm T Capsule V Pluen cet Charp V-Notch Data CompudLa-280.00 56.00 54.82 1.18 305.00 46.00 55.84 -9.84 345.00 58.00 56.22 1.73 375.00 56.00 56.27 -. 27 400.00 60.00 56.28 3.72 410.00 59.00 56.28 2.72 Ca]ukfism Cdfl Mt - -955 WCAP- 16918-NP April 2008 Revision 1

C-72 UNIRlIADIATED) INTERNMIATE SHIELL PLATE P7212-i (TRANSVERSE)

CVYGAP 5.3 Hypebolic Tangent Cum Prdi on 0210W602 04:07'PM Cocficients Of CaNe 1 A= 0&B =S&.C=3L26 TO=-49M9 D =M01)0E, Eq aizn is At B* P'snb((T-ToA)CDTl)]

Tempfnmc ma50% Shem = 49.7 Plnt Fas. 7y 2 Mahna: SAS33BI Heal B7212-1 Odeadion: TL Cqxul: UNIRR Flues.: nk~cm' 100---

I'U 75 25-_

0 4- 4 4- - -- - 4 4 4-4100.0 -200.0 -100.0 0.0 100.0 200.0 366.0 400.0 in0.0 600.0 Temperature In Dog F Charpy V-Notch Data

-fndd

-50.00 12.00 8.80 3.20

-50.00 12. 00 1.80 3.20

-50.00 12. 00 8.80 3.20

.00 27.00 23.77 3.23

.00 25.00 23.77 1.23

.00 25.00 23.77 1.23 30.00 32.00 38.66 -6.66 30.00 35.00 38. 66 -3.66 30.00 43.00 38.66 4.34 WCAP- 16918-NP April 2008 Revision 1

C-73 UNItRADIATED INTERMEDIATE SHELL PLATE B7212-I (TRANSVERSE)

Pap 2 PlantiFafy2 MatrUiakSA533Bl H1at B7212-1 Odaratom: It CapauleUNIRR Pluene nAMA2 Charpy V-Notch Data

"]oweamu Impa Pam= Shm c-mpmd Psufm Shm m"nnu 100.00 73.00 76.50 -3.50 100.00 73.00 76.50 -3.50 100. 00 69.00 76.50 -7.50 150.00 100. 00 91.32 8.68 150.00 100.00 91.32 1.68 150.00 100.00 91.32 1.68 210.00 100.00 97. 73 2-27 210.00 100.00 97. 73 2.27 210.00 100.00 97. 73 2.27 CMMIAfM cberk- .99 WCAP- 16918-NP April 2008 Revision 1

C-74 CAPSULE U INERMEDIATE SHELL PLATE B7212-1 (TRANSVERSE)

CVCRAPH 5.3 Hyperbolic Tange Crve Pdrint on 02IU6fl0O 04:08 PrM CoEFfiiets of Curve 2 A=SE. B=S0 C=95.113 fl=19.L72 D =MOEO.+O.

Equ*t*i is A + B

• ITI'mnw-TDAC+DT))j Tcmpflmi at 50% S,= 159.8 Plant: Finly2 Matmial:.SA53BI Hte B7212-1 Odcuzmtow It Cqwde U Plane: nknt2 i

-300.0 -200.0 -100.0 0.0 160.0 200.0 300.0 4m.0 uo.O 600.9 Temperfture In Dog F Chmrpy V-Noch Data TrnM 1mpn Plare Smr amqpum*mP-c -mr 50.00 16.00 9.06 6.94 75.00 23.00 14.42 A.Se 100.00 27.00 22.17 4.83 i10.00 31.00 26.01 4.99 125.00 37.00 32.52 4.43 150. 00 37.00 44.91 -7.91 17s. 00 46. 00 57.96 -11.96 175.00 48.00 57.96 -9.96 200.00 57.00 69.99 -12.99 WCAP- 16918-NP April 2008 Revision 1

C-75 CAPSULE U INTERMEDIATE SHELL PLATE B7212-1 (TRANSVERSE)

Page 2 PlantF-Parly2 MaEria 3SA533B1 Hcat B7212-1 Odamtrn.TL Capsule:U P nk/cmA2 Chamrpy V-Notch Data Cmplu*u Pcm Sbew 225.00 100.00 79.78 20.22 250.00 100.00 86. 97 13.03 275.00 100.00 91.86 3.14 300.00 100.00 95. 02 4.93 350.00 100.00 98. 20 1.80 400.00 100.00 99. 36 .64 Camult CmfsFcim -,.961 WCAP- 16918-NP April 2008 Revision 1

C-76 CAPSULE W INTERMEDIATE SHELL PLATE B7212-I (TRANSVERSE)

CCIAPH 5.3 Hypueroi Tangmt Curv Printd on 06208ia 04:09 PM CociciMets of Cmrve 3 A=S&. B= S. C=6.n = ][I0=199.73 D= .ME..00 Equzmis At B 0 rrb(CT-ToA)C+Dl))]

Tanmpontum a0% 8-= 199.8 Plant Flady2 Matmial: SA5,33B Hat B7212-1 OdoWuowi TL Cqpm*mW Flon nfkcr2 125-__

100

'IU 75 /

25 0

00 400.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 S0.O 600.0 Temperature In DM F Chmrpy V-Notch Data Teunmamw (amlmlell lPMM Smt fl-a 25.00 2.00 .31 1.69 76.00 11. ao 1.66 9.34 125.00 20. 00 7. 82 12.18 150.00 27.00 16.21 10.79 150.00 24. 00 16.21 7.79 175.00 32.00 30.63 1.37 175.00 28.00 30.63 -2.63 200.00 34. 00 50. 11 -16.18 200.00 36. 00 30. 18 -14.18 WCAP- 16918-NP April 2008 Revision I

C-77 CAPSULE W NERMEDIATE SELL PLATE B7212-I (TRANSVERSE)

Page 2 Plant Fadey2 Matldak SA533B1 Heat B7212-1 Odentauion: TL Capsule: W Pluecce: n/nA2 Charpy V-Notch Data ina 210.00 49.00 58.35 -9.35 225.00 90.00 69.68 20.32 250.00 100.00 83. 98 16.02 300.00 100.00 96. 47 3.53 350.00 100.00 99. 30 .70 400.00 100.00 99.86 .14 Coaukilm a ewxiM-358 WCAP- 16918-NP April 2008 Revision 1

C-78 CAPSULE X INTERMEDIATE SHEll, PLATE B7212-1 (TRANSVERSE)

CVGRAPH 5.3 Hypebolic Tangnt Curve Pried on 02100 04:09 PM Pape 1 CoefFmicits of Carve 4 A=SL. Bn=aSLC = TO =2s D = At}0S0 Nut'sw is At+BB [T3(T-TiAC÷DT))1]

Tcmpmnmx at.0 SbVr= 203.0 PlantFlc'y2 Mat*a*i.SA533B1 Heam B7212-1 Oilimbdo It Cqmlc X Fbuenv, akftm2 125 100 I*1 75

£a a

25 0o - --

-00.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 e00.0 Temperaure In Dog F Chrpy V-Notch Data "mzNmWM cum.o acm Shir UflhuSS

.00 2.00 .00 2.00 72.00 10.00 .06 9.94 150.00 20.00 4.65 15.35 175.00 25. 00 16.89 a. it 175.00 30. 00 16.89 13.11 190.00 35.00 32.37 2.63 200.00 35.00 43.87 -10.87 200.00 40. 00 43.87 -5.87 210.00 45.00 60. 00 -15.00 WCAP- 16918-NP April 2008 Revision 1

C-79 CAPSULE X TERNMDIATE SHELL PLATE B7212-1 (TRANSVERSE)

Page 2 Plant PFly 2 Matelat SA533B IHet B7212-1 Odmiaon TL Capsule- X Puacae ntm'2 Champy V-Notch Data puFe rnm Shm compedra mtms 210.00 45.00 60.00 -15.00 225.00 95.00 77. 94 17.06 225.00 100.00 77.94 22.06 250.00 100.00 93.64 6.36 350.00 100.00 99.98 .02 450.00 100.00 100.00 .00 Caukila c efficic -350 WCAP- 16918-NP April 2008 Revision 1

C-80 CAPSULE Z INTERM]EDIATE SHELL PLATE B7212-1 (TRANSVERSE)

CVGRAPH 5.3 Hypebolic ng Curve Pdrn on02tD6t2008 04:10 PM Page Cocfficicit Of Qnvc 5 Af=fS& Br=S& C=46.47 T=2209M1 D =0MOEU0O Equadw is A +B1 0 rraabT-Tl)bCtDr))J Tcmpzmu at 80 Sw%= 209.7 PlantFwlcy 2 Mathmial: SA533B1 Heat: B1212-1 OdcTWan2 IL Cqzwk Z AXE Wan"2 I

400.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 5o.0 600.0 Temperaure In Dog F Charpy V-Netch Data Ta-mu bps PanflmS

.00 2.00 .Ol 1.99 72.00 10.00 .27 9.73 125.00 10. 00 2.55 7.45 150.00 [5.00 7.14 7.16 175.00 20.00 11. 39 [.61 190.00 35.00 30. 06 4.94 200.00 30.00 39.80 -9.10 200.00 35.00 39.80 -4.80 210.00 45.00 50.41 -5.41 WCAP- 16918-NP April 2008 Revision 1

C-81 CAPSULE Z INTIERMEDIATE SHELL PLATE B7212-1 (TRANSVERSE)

Page 2 Plant. Fadey2 Macrisk SA533B1 Heat: B7212-1 Orentaor"ITL Capaule: Z P*ue=e: n/cm&2 Charwy V-Notich Data 1W rOeSM campmaed enacmSbes 225.00 30.00 65.98 14.02 250.00 30. 00 85. 05 -5.05 275.00 1O0. 00 94.34 5.66 300.00 1OO. 00 98.00 2.00 350.00 1O0. 00 99.76 .24 400.00 100.00 99.97 .03 Cswblmkxen m - -986

,i, WCAP-16918-NP April 2008 Revision 1

C-82 CAPSULE Y INTERMEIDATE SHELL PLATE B7212-1 (TRANSVERSE)

CVCIRAPH .3 Hyperboli Tangent Cun rPvensedon 02/106t 04:10 FM Pap 1 Ccdfts of Curm 6 A= SL B=ESL C-=64.93 ¶1=234LO D =a.0E+00 Equiam is A + B' rrmnb(Or-To)ACYDT]

TcmpmfMx It50% Smr =234.1 Plant: Fuey 2 Matedl: "A533B1 Heal B7212-1 Odaudoa TL Cqwlc Y Finn: ujb'2 125 100 I

'U 75 a

a so 25 0o 1 -1

-400.0 -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 ptan Sm ca~mlM P lr Show f-iguefal

.00 2.00 .07 1.93 100.00 5.00 1.58 3.42 i50.00 10. 00 6.99 3.01 150.00 15.00 6.99 1.01 175.00 [5. 00 13.96 1.04 200.00 20.00 23. 95 -.. 95 200.00 25.00 23. 95 -. 95 220.00 40. 00 39.35 .65 250. 00 60. (0 62.04 -2.04 WCAP-16918-NP April 2008 Revision 1

C-83 CAPSULE Y INTERMEDIATE SHELL PLATE B7212-1 (TRANSVERSE)

Pagp 2 Plant. PFacy2 Ma -aSAM33B1 Heat B7212-1 Odmawir TL Capsult-Y PNuence. n/cmA2 Charpy V-Notch Data DiMM 260.00 65.00 68.99 -3.99 275.00 90.00 77.93 12.07 300.00 30.00 88.41 -8.41 310.00 95.00 91.21 3.19 350.00 100.00 91.27 2.13 375.00 100.00 98.72 1.23 CsukOhmi beff: - .991 WCAP-16918-NP April 2008 Revision 1

C-84 CAPSULE V INTERMEDIATE SHELL PLATE B7212-1 (TRANSVERSE)

CVYGCAPH 1.3 Hyputolic Tangent Curve PrnS on 02OrOO 04:11 PM Page 1 Coffimnts of Curmv 7 Af=S0L B==SLC= X46 TO =218.5 D =O.M0E+00 Hquta~mis At+B'*Erun(C-ToAKCDTIYFD Tempzat -.V0%Sbcr= 218.6 Plait: Faley 2 Material: SAS33BI Hat B7212-1 Odnhlot IT CAWkC V Flsnace: uftm"2

'IU 400.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 600.0 600.0 Temperaure In Dog F Charpy V-Notch Data IvaWCMma campow* Fwc= Showr 100.00 10.00 .15 9.85 200.00 20.00 26.60 -6.60 205.00 30.00 32. 21 -2.23 215.00 50.00 45. 21 4.79 225.00 60. 00 38.82 1.18 230.00 70.00 65.26 4.74 240.00 75.00 76.48 -1.48 260.00 90.00 90.69 -. 69 275.00 90.00 95.69 -5.69 WCAP- 16918-NP April 2008 Revision I

C-85 CAPSULE V INTERMEDIATE SHELL PLATE B'7212-1 (TRANSVERSE)

Page 2 Plant:Parlcy2 MaiadaltSA53311 Heat B7212-1 Odweumtoln*Th Capsuk V Pluenr f/MA2 Chary V-Notch Data Tasmm comPmt SPao=m DiUffeEauS 280.00 95.00 96.69 -1.69 305.00 30. 00 99. 14 -19.14 345.00 100.00 99.90 .10 375.00 100.00 99. 98 .02 400.00 100.00 100.00 .00 410.00 100.00 100.00 -.00 Caonms (befcicnt , .a82 WCAP-16918-NP April 2008 Revision 1

C-86 UNEDATED (WELD)

CVGRAPH S.3 Hyp ic TanM Curve Pinted on 0206t20 04:55 PM Codefleicm of Carve 1 A=73.1 B = 7O9 C=S31.5 T=-2.IS D= .OOE+tU Equaticris A + B *Yb((T-Tq)KC+DTm))]

LUppSheff EumWy=144.0flixed) Lawwur ff~najg=22Vbxa Ternp30 -flm=-34.5Dog F Temp@_S0 ft.ibas-S.4 Deg F Plnt: Fadby2 Matrial: SMAW Heat: BOLA Od=atm NA CWWC UINIERR Flmo nfcm"2 250 120 oro

~16 o#  ;'r0 40 1 100 0° 0

4100.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 S00. 600.0 Temperature In Deg F Charpy V-Netkh Data mare bpi CvN Compmared CYim

-100.00 1.00 4. 93 3.07

-50.00 16. 00 11.99 -2.99

-25.00 42.00 39.09 2.91

-10.00 50.00 56.82 -6.82 10.00 109.00 83.74 25.26 25.00 68.00 102.42 -34.42 40.00 124.00 117.21 6.79 50.00 133.00 124.60 9.40 75.00 144.00 135. 91 9.09 WCAP- 16918-NP April 2008 Revision 1

C-87 UNIRRADIATED (WELD)

Pagp 2 Plant FPaicy 2 Manial: SMAW Heat BOLA Oreitadon: NA Capmue: UNEIR Flumcc nlMcn2 Chap V-Notch Data Thmpemc npd CYN Comp*bdCVN 100.00 132.00 140.80 -1.80 150.00 131.00 143.52 -12.52 150.00 150.00 143.52 6.43 175.00 154.50 143.82 10.63 210.00 154.00 143.95 10.05 210.00 153.00 143.95 9.05 210.00 137.00 143.95 -6.95 Cwnklamm Coeficiu -mSM WCAP-16918-NP April 2008 Revision 1

C-88 CAPSULE U WELD METAL CVGRAPH 5.3 Hyperbo:ic TgM Cuve Prmemd on 0210W=t0O 04:55 PM Pap 1 Coefmiiemts of Cmurv 2 A=-67.1 B= 64.9C=96.1 TO =-.47 D=0.Oi)_40 Egumign is A + B r[I'mnr-To(C+tDT)J Upper Sheff lml = 132.0(Flwza) LawUe Sbhefa ,-p=Q2 Temp@30 ft-lw-2.9 Deg F TempOSO ft-la-2&L3 Deg F Plant Fmady 2 Maedal: SMAW Heat BOLA Odmtnimo NA Caauk: U Flubcu uftml2 2W p150

£ 9100 Rico o0 ~ i- -'--- - i-I--- i- - -

400.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500. 600.0 Temperature In Deg F Charp V-Notch Data comulodCVN D])i1mm

- 50.00 13.00 36.33 -23.33

-25. 00 79. 00 50. 11 23.12

.00 95.00 67.42 27.53

.00 36. 50 67.42 -30.92 25.00 B9. 50 83. 91 5.59

50. 00 35. 00 98. 36 -13.36 50.00 96.00 98.36 -2.36

75. 00 112. 50 109.66 2.84 100. 00 108.00 117.73 -9.73 WCAP- 16918-NP April 2008 Revision 1

C-89 CAPSULE U WELD METAL Pago 2 Plant Fade 2 Mat'ial: SMAW Heat BOLA Oriemion: NA Capsule: U Fluence: nlat2 ChaMrpy V-Notch Data 1kEtCVN OwmwatCVN 125.00 140.00 123. 12 16.88 150.00 132.50 126.57 5.93 175.00 122.00 128.72 -6.72 200.00 114. 00 130.03 - 16.03 250.00 154.50 131.30 23.20 300.00 127.50 131. 75 -4.25 Cmanmsvr CDecimn-W WCAP- 16918-NP April 2008 Revision 1

C-90 CAPSULE W WELD METAL CVCYAPH 5.3 Hyperolic Tangwt Cunme Pried on 02A120 04:56 PM Coeffici*ts of CDime 3 A =*73.1 BU=.7.9cC= =6LTO . = 19.0S DMO.E4S, Equatfiis A + B r[rmn(rT-o)bC+t~))j Uppa Shelf Ikaxj144.0(Flzd) Isa ShffBaerg42(PaS)D Taep@30 Af-h1=-27.5 Deg F Tenp@OS ft-la-3.2 Deg F Plant FmUly 2 MtmrIl: SMA.W Heat: BOLA.

Odutemion: rA Cwmuk W Fh* scrt'2 43O I 150

£ sio 400.0 -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

-C40 CYN (CmladCVK a

-100.00 5.00 5.95 - .95

- 50. 00 14.00 17.78 -3.71

-50.00 33.00 17. 71 15.22

-25.00 47.00 31.76 15.24

.00 28.00 53. 21 -25.21 25.00 72.00 79.50 -7.50 25.00 91.00 79. 50 11.50 50.00 108.00 104. 13 3.87 76.00 132.00 122.58 9.42 WCAP-16918-NP April 2008 Revision 1

C-91 CAPSULE W WELD METAL Page 2 Plmt Fadiy 2 Macnial: SMAW Heat BOLA Otemtim: NA Capsule W Mlueo: n/cmA2 Charp V-Notch Data Thmwam CoVm~md LVN n 125.00 123.00 138.51 -15.51 200.00 127.00 143.41 -16.41 250.00 155.00 143.87 11.13 350.00 154.00 143. 99 10.01 350.00 159.00 143.99 15.01

.00 45.00 53.21 -1.21 Cnomiuhm Cwmcia m.96-WCAP- 16918-NP April 2008 Revision 1

C-92 CAPSULE X WELD METAL CVCIRAPH 5.3 Hyputollc Tanlwt Curve Plard on 02/M = 04:56 PIM Pape 1 Coeffcimta of Cmuve 4 A =76.1 B= -7339C=S1*W ¶ 1= 14.1 D=0 A0E4 Equatimis A +B rrm*b'r-ToCtm'D))]

UppwSheff uEamu=I5tCOWhmx Isw UcffEhj44IVxOd TeMp0O3 ft-fli*-S.1 DegF Tempsu*p ftbs-l7-S79DgF Plutz FPl72 Meaal: SMAW Heat: BOLA Odamiont NA Capmul::x Fbxn* nCMA2 42W A

DI "a

s5o 0

400.0 -f0.0 -100.0 0.0 100.0 200.0 S.0 460.0 Soo.0 eoo.o Tempesturs In DqNF Charpy V-Notch Data 0pa CYN Cmvmdc'VN

- 100. 00 4.00 12.59 -8.59

-50.00 40.00 30. 08 9.92

-50.00 25.00 30. 01 -5.03

-40.00 25.00 35.53 -10.53

-25.00 51.00 45.02 12.91

-25.00 43. 00 45.02 -2.02

.00 74.00 63.83 10.17

.00 62.00 63.83 -1.83

25. 00 69.00 84.45 -15.45 WCAP- 16918-NP April 2008 Revision 1

C-93 CAPSU X WELD METAL Page 2 Plant Fa*-cy 2 Manl: SMAW Heat BOLA Ouemaaio: NA Caple: X Pume=: ncmA2 Chmrmp V-Notch Data M CYN C-n wdCYN 50.00 107.00 103.82 3..13 100.00 138.00 130.98 7.02 200.00 123.00 147.73 -19.73 350.00 131.00 149.92 31.08 450.00 153.00 149.99 3.01 CwmnohmxQufficiu - .971 WCAP- 16918-NP April 2008 Revision 1

C-94 CAPSULE Z WELD METAL CVGRAPH 5.3 Hypeollic Tangwet Curve PFwed on 02A062O 04:57 PM Pap 1 CoefiýcMt of COwe 5 A=67A B=.=6AC=*W7 7 =IU14.14 D=-.AOOR0*

Equdim is A t B' rrwmn(T-To)*Tc)m ]

lUppc 8hefH ara= -133. 0(WWxedQ Lww ShIf Hnrajy=Q22lxdD TanpO30 t-lbsu-24.3 Deg F TempOSD ft-Tha-2.-l Deg F Plant Faiy 2 Msuiu: SKAW Heat: BOLA OducSndow NA Cqaw Z TiaLc nftimn 3O 2M I

406

• 150 io 50

-300.0 -200. -100. 0.0 10o0. 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F Charpy V-Notch Data 0VUwSdCVN

- 100.00 4.00 4.84 -. 84

- 60. o0 7.00 11.91 -4.91

-30.00 10.00 26. 02 - 16.02

-6.00 13.00 46. 03 -33.03

.00 72.00 52. 16 19.84 5.00 B6. 00 57. 51 21.49 15.00 57.00 68.56 -11.56

15. 00 77. 00 68.56 1.44

25. 00 36. 00 79.55 6.45 WCAP-16918-NP April 2008 Revision 1

C-95 CAPSULE Z WELD METAL Page 2 Plant FPady 2 MNatel: SMAW Heatr BOLA Odentado: NA Capsek Z Plume: n/cmf2 Charpy V-Notch Data T"MUMjNm ipM CVN C-mPodCYN 30.00 91.00 84.83 6.17 50.00 88.00 103.19 -15.19 100.00 105.00 126.32 -21.32 150.00 123.00 131.73 -8.73 195.00 151.00 132.72 13.28 259.00 124.00 132.96 -3.96 Ca*w Q3mcSt ,, .A32 WCAP-16918-NP April 2008 Revision 1

C-96 CAPSULE Y WELD METAL CVGRAPH 5.3 Hyperboic Tangn Cmvw PdatSd on 02/060M 04:57 PM Pape 1 CocfFmicets of CwOe 6 A =69A B 67.4Cc=41.74 TON=E" D=-.SOA4M4 Equptmis At B (1rmb((T-Th)ACtDTh[]

1Wpa S helfN Eamau=137.OWm xriQ L"awf Mtoff HnCZY=2.2(Fxe Tamp@30 fi-MI4.6 Dog F Tamp@S0 ft-lls=5OI Deg F Plant Paly 2 Medal: SMAW Heat: BOLA Odtmifim: KA Capsule:Y "No nkft2

.3(I a

so

'O

-6W.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Tlmpsaturs In Dog F Charpy V-Notch Data TmfMMu 1rpM CVN OumledCYN

-50.00 7.00 2. 21 4.19

.00 20.00 9.58 11.42 25.00 12.00 21.25 -9.25 40.00 16.00 36.23 -20.23 40.00 33.00 36.23 -3.23 50.00 53.00 49.77 3.23

60. 00 74.00 63.32 8.63 75.00 104.00 88. 97 15.03 100.00 106.00 117.70 -11.70 WCAP- 16918-NP April 2008 Revision 1

C-97 CAPSULE Y WELD METAL Pae 2 Plant 2 Matnial: SMAW Heat BOLA NAIdy Orienmtaio: NA Capsule Y Flumn:m: n/km2 Charpy V-Nolch Data FN oomuadcvN 125.00 110.00 130. 53 -20.53 150.00 130.00 134.98 -4.98 200.00 122.00 136. 81 -14.81 275.00 133.00 136.99 16.01 275.00 134.00 136.99 -2.99 300.00 125.00 137. 00 -12.00 coaula Qmfficm - .m72 WCAP- 16918-NP April 2008 Revision 1

C-98 CAMLE V WELD METAL CVGRAPH 5.3 Hyperboli Tangent Curve Printd on 02/6OQ 04:58 PM Pae 1 Coc*icuts of Curve 7 A=63.1 B=*-OC=1OMS U=84A3 D=8OI.WeO Equaizm is At B' rranb(T-ToA)C+DT))]

Uppu Bheff~aargy=124.0(Flxd) LowrshcfEnwfB42.2( xod Temp @30 fl- i --2.0 Dog F Tcap@S0 f-fl=6L1.8 Dog F PIant FPasy 2 MVMeit: SKAW Hatd: BOLA OflealoK NA Cap :V Y Flanwm ucm"*

I I

U 06 4100.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperture In Dog F Ehmp V-Netch Data T'Mu -mmloCYN rniae

-25.00 6.00 15. 02 -9.02 20.00 26.00 29.18 -3.13 30.00 54.00 33.52 20.43 40.00 33.00 38.30 -5.30 50.00 36.00 43.48 -7.4,

70. 00 69.00 54.76 14.24 100.00 61.00 72.37 -11.57 125.00 39.00 36.33 2.65 145.00 18.00 95.74 -7.74 WCAP- 16918-NP April 2008 Revision 1

C-99 CAPSULE V WELD METAL Page 2 PIamt Paley 2 Matril SMAW Ekat. BOLA Orientatio: NA Capsulem V Pneuce: n/cmA2 Charpy V-Notch Data Iom CVY1 C-mlimdCYN 165.00 100.00 103.36 -3.36 185.00 103.00 109.25 -6.25 230.00 137.00 117.44 19.56 250.00 131.00 119.49 11.51 260.00 125.00 120.27 4.73 Conalatm Cofcim , .966 WCAP- 16918-NP April 2008 Revision 1

C-100 UNIRRADIATED (WELD)

CvGRAPH 1 H*yPebli Tan1gt Crve Pdutd on 02106t2008 05:00 PM H.3-.

Coeffixita ofOf Cri 1 A -=9MB = 4LO C a=SATO-=-lOS D =LOOE40 Eqution is At B÷ frr Tnl-Tm)'C+DT))]

Upper Shelf LL--92. Loe Shelf Ll-K=b0Fd)

Temp.@L.H. 3.5 mifi-235 DegF Plait Fmky 2 MaWmimi: SMAW Hat: BoLA NA CqWak INIRR Icfta FIn mInA2 150 I

IL1 0 9 0

5D 0

400.0 0.0 300.0 600.0 Tempoeture In Du9 F Chap V-Notch Data Tar~mu aps LJB C(*medL,.1

-100.00 7.00 3.06 3.94

-50.00 15.00 16.99 - 1.99

-25.00 35.00 33. 83 1.17

-10.00 44. 00 46. 56 -2.56 10.00 73. 00 63.09 9.91 25.00 60. 00 73.05 -13.05 40.00 90. 00 80.24 -. 24 50.00 39.00 83.64 5.36 75.00 92.00 83. 65 3.35 WCAP-16918-NP April 2008 Revision 1

C-101 UNIRRADIATED (WELD)

Page 2 PIat Fafdy 2 Mamal: SMAW Hea BOLA Orkud: NA Capzlc UNJER FMn= nkMA2 Charpy V-Notch Data 100.00 91.00 90. 77 .23 150.00 92.00 91.96 .04 150.00 91.00 91.96 -. 96 175.00 90.00 92.09 -2.09 210.00 91.00 92. 15 -1.15 210.00 93.00 92. 15 .85 210.00 92.00 92. 15 -- .15 CamdOw Cbeffifim - 987 WCAP-16918-NP April 2008 Revision 1

C-102 CAPSULE U WELD METAL CVCGALH 5.3 Hyperboa Tanent Curve PdnW on 02060=200 0+/-:00 PM Coeflicients of Curve 2 A =41L75 B-45757C=S4.7 TO=--23S D =.0.001.00 Equtimflis At+B'0 Mnh(CT-ToDAC+tn))j Upper Shelf L.B.--915 Lower Shelf LB.-R=M0( d)

Temp.@LE.L 35 mi!--43.9 DegF Plant FPdy 2 mtala]: SMAW Heat: BOLA Odnudmlo NA Calem : U Plxnw nkA2 201 IOU

.3 E

I U

U.100 a

I rn]

a nli. + I I 4 I

00. 0.0 300.0 600.0 Temlperture In Dog F Charp V-Notch Data Difflienfi

- 50.00 16. 00 31. 98 -15.99

-25.00 68. a0 45.04 22.96

.00 77.00 58. 23 18.77

.00 31.50 58. 23 -26.73 25.00 74. 00 69. 50 4.50

50. 00 70. 00 77.84 -7.84 50.00 78.00 77. 84 .16

75. 00 34.30 83.40 1.10 100. 00 30. 50 86. 83 -6.33 WCAP-16918-NP April 2008 Revision 1

C-103 CAPSULE U WELD METAL Page 2 Plant FPity2 Malmial: SMAW Heat. BOLA Orienaion: NA Capsu U iueme: nflan 4 '2 Charpy V-Notch Data Dinmfl 125.00 91.50 88. 85 2.65 150.00 92.00 90.02 1.98 175.00 91.00 90. 68 .32 200.00 90.50 91.05 -. 55 250.00 90.00 91.37 - L.37 300.00 96.00 91.46 4.54 Cammbdm (befficic - -852 WCAP- 16918-NP April 2008 Revision I

C-104 CAPSULE W WELD METAL CVGRAPH 5.3 Hypaolic Tangent Curve Pined on (02O02008 05:01PM Page 1 Cocffkjizta of Conm 3 A =42t55 B=42.A5C=67.82 TO-=-31 D=0S104E00 Equaion is A + B rru('r-TI)AC+Dt))j Upper Shal LJL85.t [an Shclf L.=.0E.F tad)

Tcmp.@LSL 35 mi!-18.4 DegF Plant Fley 2 Material: SMAW Heat: BOLA Odiendon: NA Cupelc W Fhlus Anlcnt2 2M

[L100 so o 4-0 4W0.0 0.0 300.0 600.0 Temperature In Deg F Charpy V-Notch Dabt

]riLa

- 100.00 5.00 5. 05 -. 05

-50.00 14. 50 18. 39 -3.89

-50.00 23. 50 18.39 10.11

-25.00 41.00 31. 11 9.89

.00 28.50 46.49 -17.99

25. 00 55.00 60.90 -3.90 25.00 71.00 60.90 10. 10

50. 00 31.00 71.30 9.30

76. 00 79.00 78. 19 .81 WCAP- 16918-NP April 2008 Revision 1

C-105 CAPSULE W WELD METAL Page 2 Plant FPrly 2 Matrial: SMAW Heat BOLA Otenmtlma NA Capsule. W Hf ce'. nlcM2 Charp V-Notch Data Tempeumm 125.00 91.50 83. 35 8. 15 200.00 32.50 84.90 -2.40 250.00 92.50 85.05 7.45 350.00 70.50 85.09 -14.59 350.00 32.50 85.09 -2.59

.00 41.50 46. 49 -4. 99 CsMukMtc QCifTit m-951 WCAP- 16918-NP April 2008 Revision 1

C-106 CAPSULE X WELD METAL CVGRAPH*5.3 Hyp*rbaoicTng Cumr Printd on 02f 0 05:01PM Cci:cimt of CmQve 4 A =.42.04 B =42.04C = 72.M TO= -17JS D -LNF_,.,

Hqutizmis A t B r01rnnT-To)ACDTm)]

Upper Shelf L.E=84.1 Law Shebcf*-R=Sotd)

Tcm@L.OL 35 nil=-30.0 DegF Plnt FPdv2 Mal"a]: StAW Heat: BOLA Odat NA Capul: X Plinw Sknt2 2o J15D E

.3f 11610 3100 5D 00.0 400.0 0.0 3O0.O 600.0 Temperature In Deg P Chmrpy V-Notch Data "d L.Ia

- £00.00 4.00 7.80 -3.80

-50.00 33.00 24.43

-30. 00 24. 00 24. 43 -. 43

- 40. 00 22. 00 29. 51 -7.3£

-25. 00 43. 00 37. 88 5.12

-25.00 40. 00 37. 88 2.12

.00 52.00 52.24 -. 24

.00 50. 00 52.24 -2.24 25.00 53.00 64.45 -11.45 WCAP- 16918-NP April 2008 Revision I

C-107 CAPSULE X WELD METAL Pape 2 Plant Fad-y2 Matmil: SMAW Heat BOLA Oientmain: NA Cpsule: X Pluence: n/cm'2 Charpy V-Notch Data ibmmuIedLaL 50.00 80.00 72.97 7.03 100.00 92.00 81. 00 11.00 200.00 85.00 83. 87 1.13 350.00 30. 00 84. 07 -4.07 450.00 78.00 84.07 -6.07 Comhncbcm Cbdcie m.-971 WCAP-16918-NP April 2008 Revision 1

C-108 CAISULE Z WELD METAL CVGIAPH 5.3 Hyperboric Tangent Cuve Printed on 021060 05:02 FM Coefcients of Cawic 5 A =3-91 BD =f39.91 Cc=a7.63 TO1= 3 D =0.001M0 Equatin is A +B 0Imn=(C-TbACtDThJ Upper Shelf L.IL=79.R Lower ShelffIL-R.Mzed)

Trn.@OL.. 35 miln=-IA Deg F Plat F'adcy2 Mct]u: SMAW Heat: BOLA Odeanthiom NA CqMfw Z Fbu bk

/cmnt2 200 150 mu I 5 5D 00.0 400.0 0.0 300.0 600.0 Temperaturs In Dq F Chmrpy V-Notch Data DikES

- 100.00 .00 .33 -. 33

-60.00 1.00 2. 68 -1.63

-30.00 7.00 11.66 -4.66

-6.00 10.00 30. 31 -20.31

.00 52.00 36.49 15.51 5.00 58.00 41.79 16.21 15.00 42.00 52. 00 -10.00 15.00 55.00 52. 00 3.00 25.00 62.00 60.73 1.27 WCAP- 16918-NP April 2008 Revision 1

C-109 CAPSULE Z WELD METAL Pap 2 Plant Padey 2 Maenrial: SMAW Heat BOLA OdCintad*: NA Capsule- Z Pluenc: n/fmA2 Charpy V-Notch Data

-tmLE. LCEp3SL 30.00 63.00 64.32 -1.32 50.00 61.00 73. 68 -12.68 100.00 78. 00 79.35 -1.35 150.00 34. 00 79.78 4.22 195.00 31.00 79.81 1.19 250.00 35.00 79.82 5. 13 CaulfINO Quyciil m .951 WCAP- 16918-NP April 2008 Revision 1

C-110 CAPSULE Y WELD METAL CVYCITAPH 5.3 Hyperboic 'lfge Curm PdnSd on 02060M 05:03 PM Pape 1 Coefficits of Curve 6 A =41.69 B = 41.69tC =33. TOIV=.5114 D =.0.OE00 Equtdi is A + B ' [r1'bfT-To*A DT]

Upper ShaltL.E--3A Lamw Shelf L.R=A0a4cd)

Teuiip.OLA 35 m-&=47.9 DogF P=tnFadcy2 Medal: SMAW Hat: BOLA Oduamofm NA Capan:Y Pxacr ncnk"2 2O A

'100 I so 5O 4100.0 0.0 300.0 600.0 Temperature In Dog F Chap V-Notek Data

¶rmwOMu L CampuwdL..

-50.00 6.00 .1s 5.85

.00 15.00 3.10 11.90 25.00 13.00 12.64 .36 40.00 15.00 25.77 - 10.77 40.00 25.00 25.77 -. 77 50.00 43.00 37.69 5.31 60.00 52.00 50.31 1.69 7s. 00 70.00 66.04 3.96 100. 00 73.00 78.89 -5.89 WCAP- 16918-NP April 2008 Revision 1

C-Ill CAPSULE Y WELD METAL Pap 2 Plant Fadey 2 Matuzial: SMAW HEt BOLA Odentmain: NA Capsule Y Piucnce. nlA2 Charpy V-Notch Data kILpd L.E CompdL..

125.00 74. 00 82.36 -8.36 150.00 37. 00 83. 15 3.85 200.00 88.00 83.37 4.63 275.00 93. O0 83. 38 -. 38 275.00 36. 00 83. 38 2.62 300.00 33. 00 A3. 38 -. 33 Caion -. 984

,befficimt WCAP- 16918-NP April 2008 Revision I

C-1l2 CAPSULE V WELD METAL CVC*1IPH 5.3 Hyp-bolic Tanget Curve Printed on 02A60 05:03 PM Pag 1 Coefficdmts of Curme 7 A =4119 B=43.19 C= 116M TO=63.57 D =0.00E40 EquaUi is A +B rrnbTUT-To)KCtn)T)]

Upper SheVL.RL=8S4 Laww Shelf L--.E..(Fzd)

Ten@,@OL 35 mils=41.3 Deg F Plant FIwle'2 Meial: SKAW t: BOLA Odmilno NA Capsmu: V Fhrnw unt2 A

IE U

U.

400.0 0.0 300.a 600.0 Temperaure In Dug F Charpy V-Notch Data Tmn CnmpumduL.I DiMO

-25.00 10. 00 15.43 -5.43 20.00 27.00 27.70 -. 70 30.00 45.00 31.04 13.96 40.00 31.00 34.54 -3.54 30.00 32.00 38.16 -6.16 70.00 52. 00 45.58 6.42 100. 00 48. 00 56.32 -3.32 125.00 65. 00 64.13 .87 145.00 64.00 69.33 .5.33 WCAP- 16918-NP April 2008 Revision 1

C-113 CAPSULE V WELD METAL Pagp 2 Plantf Parlcy2 Manhikl SMAW HEat BOLA Orentatio: NA Capsulm V Rue=nce: nkMA2 Chap V-Ntkh Data "m'qas% Coa-umi LL 165.00 31.00 73.56 7.44 185.00 73.00 76.89 1.11 230.00 37.00 31.73 5.27 250.00 76. 00 83.03 -7.03 260.00 34. 00 33.55 .45 Cosnulkicm Coffimt - .64 WCAP- 16918-NP April 2008 Revision 1

C-114 UNIRRADIATED (WELD)

CVGRAPH 5.3 Hypedaoc Tangent Curve Prned on 02/060M 05:09 PM Page1 Cneflkicnts of cOve 1 A =50. B= S0.C=62.17 TO'=-1&16 D =0.ACEiI Equtdi is A + B' rrTb(T-Toq(C+Dtm'J Tnpaufm 5M Sheu= -15.1 5a0t PlantFPdaey 2 Maid: SMAW Hes: BOLA OdcOmDS MA Cqamk U14il F=l=aain ub 125 100 I

'U 75

£ a 5s 0-/

4 .0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F Chapy V-Notch Data TManptmm

-100.00 12.00 6. 13 5.87

-50.00 30. 00 24. 59 5.41

-25.00 40. 00 42. 16 -2.16

- 10. 00 43.00 54. 14 11.14 i0. O0 30. 00 69.20 10.80 25.00 72. 00 78.45 -6.45 40.00 35.00 85.50 -. 50 50.00 94. 00 89. 05 4.95 75.00 100.00 94.79 5.21 WCAP- 16918-NP April 2008 Revision 1

C-115 UNIRRADIATED (WELD)

Pagp 2 Plant Friay 2 MatmaI: A*,W Heat BOLA Ornado: NA Capnlc.: UNJIR Pluence nkMA2 Chap V-Notch Data Tempentm b1pa Pecela Ur -Om Pe sm 100.00 100. 00 97.60 2.40 150.00 100. 00 99.51 .49 150. 00 100.00 99.51 . 49 175. 00 100.00 99. 78 .22 210.00 100.00 99.93 . 07 210. 00 100.00 99. 93 .07 210. 00 100.00 99. 93 - 07 Conwhids (befficieci -M8 WCAP- 16918-NP April 2008 Revision 1

C-116 CAPSLE U WELD METAL CVGRAPH 5.3 Hypebolic ¶angmt C-mve P&Wd on 02/060M 05:10 FM Coefficients of Caum 2 A =O. B=S&C -76& TO=--1.17 D =0*.OOR.0 Equidw is A + BFarr(T-T1AC+DTJ)j b

Taer~m at *50% Shear = -11.1 Plant Falay 2 Me~ahl: SMAW Heat BOLA Odwsiow NA Caonu: U Phxace: uan"2 125 tao

'IU 75 5D 25 0 -. 0 -las 41300.0 -200.0 -400.0 0.0 100.0 200.0 300.0 0s o0.0 600.0 Tempemture In Deg F Charpy V-Nelch Data Diifemad

-50.00 24. 00 26.'6d8 -2.68

-25. 00 53. 00 41. 09 11.91

.00 64. 00 57.22 6.73

.00 42.00 57.22 -15.22

25. 00 67.00 71.94 -4.94 50.00 73.00 83. 10 -10.10 50.00 91.00 83. 10 7.90 75.00 99.00 90. 41 8.59 100.00 98.00 94.76 3.24 WCAP- 16918-NP April 2008 Revision 1

C-117 CAPSULE U WELD METAL Pap 2 Plant FPady 2 Matncial: SMAW Heat BOLA Orienatin: NA Capsule: U Pluence: nauA2 Charpy V-Notch Data Teoweemm Composle MGM Saer nan 125. 00 100. Go 97. 19 2.81 150.00 100.00 98.52 1.48 175.00 100.00 99.22 .78 200.00 100. 00 99. 59 .41 250.00 1O0. 00 99. 89 .11 300.00 1O0. ao 9;. 97 -03 CaroskS Qiefficind -36=

WCAP- 16918-NP April 2008 Revision 1

C-118 CAPSULE W WELD METAL CVCRAPH E5.3 Hypaol ngmt Cmrve Prh onO2A62M 05:10 PM CodfiF-imta of C(rve 3 A=S& RB=50.C=f52.99 TO¶=1.2 D= 0.0_,iI Epsir is A +B 0 rTC*r-To)(C+Dt))i ThnmtW= a 50t( Shmr = 1.9 Plst FPday 2 MdiaS: SMAW Het: BOLA OdcWom: MA Cqpwu W Fhwz . z/ca"2 125 i0o I'K 75 so 25

-Mo.0 -200.0 -100.0 0.0 100.0 200.0 o00.0 400.0 500.0 OM.0 Temperature In Dog F Charpy V-Notch Data

¶rEwain Opmp Pm Emhw DfflfmnM

-100.00 6.00 2.10 3.90

-50. a0 13.00 12.39 .61 21.00 12.39 1.61

- 25.O00 28.00 26. 65 1.35

.00

-25.00 37. 00 48. 21 -11.21

25. 00 55. 00 70.57 -15.57

25. 00 37.00 70.57 16.43

50. 00 94. 00 86.03 7.97 76.00 97.00 94.26 2.74 WCAP- 16918-NP April 2008 Revision 1

C-119 CAPSULE W WELD METAL Page 2 Plant Fity 2 Matmial: SMAW Hear BOLA Oen:af: NA Capsule, W Placme: n/CuA2 Chmpy V-Netch Data ypSPf Ucnmlr Gm*aPMd Fa= Shr 125.00 100.00 99. 05 .95 200.00 100.00 99.94 .06 250.00 100.00 99. 99 .0L 350.00 100.00 100.00 . 00 350.00 100.00 100.00 . 00

.00 49.00 48.28 .72 Csnmrm EOefficic m-979 WCAP-16918-NP April 2008 Revision 1

C-120 CAPSULE X WELD METAL CYGRAPH 5.3 Hypflolic Tangen Gino Puinted on 02106fl00 05:11 PM Past 1 Co*--icimta of Curve 4 A =. B=50.C=6443 IM =496 D0=.0E40 Bqutizmis At B 0 rrwh(T-To-)iC+DT))j Tensaphunt a 50%Shuar= -. 9 Plat PFley 2 Mdzial: SMAW Heat: BOLA Odesuiwc NA Cumau: X Pnuwn nkm 125 100 IU75 UO 25

-00.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperaure In Dog F Charpy V-Nolch Data TWAyflrn Iva Peucon shear cmpsd pun= sher

- tOO. 00 4.00 5.62 -1.62

- 50.00 30. 00 21.89 H. it

-50.00 20.00 21.89 - . 89

- 40.00 25.00 27.65 -2.65

-25.00 45.00 37.82 7.11

-25.00 30. 00 37.82 -7.82

.00 65.00 56.90 1.10

.00 50. 00 56.90 .6.90 25.00 65. O0 74. 13 -9.13 WCAP- 16918-NP April 2008 Revision 1

C-121 CAPSULE X WELD METAL Pae 2 Plant Faduy 2 Manital: SMAW Heat BOLA Orentaton: NA Capule X Placte: nkMA2 Charpy V-Notch Data 50.00 95.00 86.15 8.85 100.00 100.00 96.70 3.30 200.00 100.00 99.85 .iLS 350.00 100.00 100.00 .00 450.00 100. 00 100.00 00 Qnhtonfc Cofidn - .985 WCAP- 16918-NP April 2008 Revision 1

C-122 CAPSULE Z WELD METAL CVGLAPH 5.3 Hyprbonc Tanget Curve Pdntd on 02A06I2() 05:11 PM Page 1 Coelicicuta of Conc 5 A=SL. B =S&LC=441.93 TO= IS.9 D =00ME.00 Equmia is Au+B

. rrma((T-ToACtDTJ))]

Tmp*'flhn 8 5f% Sber = 15.2 PlntP Fdaey 2 Mabia: SMAW Hea: BOLA Odeattios NA Cqmw&- Z Fliumc*cWI 125 100 I'U 75 w

25 400.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Dog F Chmrpy V-Notch Data

¶rViau Iupat PrMa Sbo c=add Pao= SMr -a

- 100.00 5.00 .41 4.59

-60. o0 10.00 2.70 7.30

-30.00 15.00 10.31 4.62

.6.00 20.00 26.68 -6.68

.00 30.00 32. 64 -2.64 5.00 40.00 38. 08 1.92 15.00 50. 00 49. 77 .23 15.00 45. 00 49.77 -4.77 25.00 65.00 61.49 3.51 WCAP- 16918-NP April 2008 Revision 1

C-123 CAPSULE Z WELD METAL Pag 2 PmantFadey2 MatntalSMAW HEatBOLA Oakmadca: NA Capule. Z Flue: n/cmf2 Chamrpy V-Notch Data Te .U0 30.00 75.00 66.96 8.04 50.00 30.00 84.03 -4.03 100.00 90.00 98.28 -1.23 150. 00 100.00 99.84 .16 195. 00 100.00 99.98 .02 250. 00 100.00 100.00

• 00 Cuwkmim ,beciaM

.991 WCAP- 16918-NP April 2008 Revision 1

C-124 CAPSULE Y WELD METAL CVG1RAPH 5.3 Hypeboc Tant Curve Ftl o 0210on 05:12 PM Pap I Coeffciets of Cant 6 A=S. B=S.C=3LS4 TO=53.05 D=BM-.001 Epwa is A + B' I[sWm(-Tq)C+C.J))i TPeipd um atmi 50% Shea r= 53.1 Plant Pafle 2 Mahzd: 514kW Had: BOLIA OdnWlmow NA Capsul: YV Fuuzc nkn"

'IU

-00.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 SO0.O 600.0 Temperature In Dog P Charpy V-Notch Data

-50.00 5.00 . 47 4.53

.00 15.00 5. 99 9.01 25.00 20.00 18. 91 [.09 40.00 30.00 33.6M -3.63 40.00 30.00 33.61 -3.61 30.00 40.00 46.05 -6.05

60. 00 65.00 38.91 6.09 75.00 835.00 73.75 9.25 100. a0 35.00 91.95 -6.95 WCAP-16918-NP April 2008 Revision 1

C-125 CAPMLE Y WELD METAL Page 2 Plant Fafd 2 fmai: SMAW HEat BOLA Orientation: NA Capsulm Y Pluence: nfmr2 Chmap V-Notch Data IpW Pao=*mar compma ram Shea 125.00 90.00 97.66 -7.66 150.00 95.00 99.35 -4.35 200.00 95.00 99.95 -4.95 275.00 100.00 100. 00 . 00 275.00 100.00 100. 00 . 00 300.00 100.00 100. 00 - 00 ConrJmmiw (baM - .M WCAP- 16918-NP April 2008 Revision 1

C-126 CAPSULE V WELD METAL CV APH 5.3 Hyperbolic Tangent Curve Pintud on 02826/20{M 05:12 PM Pop 1 Coefficints of Curve 7 A-=a B =a&C=67.16 TO =61Md D =SOA090 Equdim is A + B 0 rruW(T-TlbCtKrr))]

Tcmuerzynm a.50% Shar= 61.1 Plant Fadry 2 M iatW- SMAW Hrat: BOLA Odoztsimo NA Cp:Y V Ehxac nkumt2 125 100 I

'U 75 I

a aD 25

-s.0. -200.0 -100.0 0.0 100.0 200.0 m00.0 400.0 500.0 6eo.o Temperture In Dog F Charpy V-Notch Data Tm¶ffm bnmpt Shemr compuedPmmSEn

-25.00 5.00 7.16 -2.16 20.00 20. 00 22.75 -2.75 30.00 30. 00 28.40 1.60 40.00 30.00 34.82 -4.82 50.00 35.00 41.84 -6.84 70.00 75.00 56. 62 18.3B 100. 00 75.00 76. 13 -1. 13 125.00 30.00 37. 04 -7.04 145.00 90.00 92. 41 -2.41 WCAP- 16918-NP April 2008 Revision 1

C-127 CAPSULE V WELD METAL Page 2 Plant: Parly 2 MacnaL SMAW Heat BOLA Orienmfion: NA Capule V Fhuem: ntnA2 ChaMrpy V-Nakh Data Tanpanm*

165.00 90.00 95.67 -5.67 185.00 95. 00 97.57 -2. 57 230.00 100.00 99.35 .65 250.00 100. 00 99.64 . 36 260.00 100.00 99.73 .27 CAiduaitm Ct mi m "

WCAP- 16918-NP April 2008 Revision 1

C-128 UNIRRADIATED (HEAT AFFECFE ZONE)

CVGRAPH 1.3 Hypeato*c Tant Curve Pinte on 02/0f0 0+/-.22 PM Page 1 CoEFfiits of Cmurv 1 A =80.I Bn=sc=2 n=9CoaTO D=-101..3 D-OJOe+0 quw imis A +B IrmnbaW(-Tq)ACt+DJ)]

UppurShelf Enmw=15tOWlzad Loama Uzalf~ueraj=2.2(Pmxa Tmhp@30 ft-lhb=-296.2 Deg F Tamp@50 ft-Jhs=-205.3 Deg F Plant Fsy2 Mael: SAS33BI Hat B7212-1 Oc*OiC NA Cec UNIRR Flbaw: n/cmn2 4200

• 15 C0 C

06

, C 0

4-0.0 -200.0 -100.0 0.0 100.0 200.0( O0.0 400.0 500.O 600.0 Temperature In Dog F Charp V-Notch Data

]wpm CN flmpzadCVN Dflid

-200.00 11.00 51.40 -40.40

-150.00 159.00 65.42 93.58

-100.00 91.00 80..50 17.50

-100.00 40.00 80.50 -40.50

-50.00 98.00 95. 54 2.46

-50.00 71.00 95.354 -24.54 20.00 44. 00 114.55 -70.55 25.00 113. 30 113.77 -2.27 50.00 136.00 121.32 14.41 WCAP- 16918-NP April 2008 Revision 1

C-129 UNMRADIAT (HEAT AFFECFE ZONE Pae 2 Plant Farlty 2 MateriBk SA533B 1 Heat B7212-1 Ozienadci: NA Capsule UNJIR uen= nkMA2 Charpy V-Notch Data 1mpd CYN 75.00 123.00 126.71 -3.71 100.00 191.00 131.32 59.68 150. 00 159.00 138.91 20.09 210.00 151.00 145.49 5.51 210.00 36.00 145.49 -59.49 210.00 139.00 145.49 43.51 Canmmtr C(beffride ..581 WCAP- 16918-NP April 2008 Revision 1

C-130 CAPSULE U (HEAT AFFECTED ZONE)

CVGRAPH 5.3 HyEfaoli Tanggnt Curve Prlnted on 02/2 05.22 FM Pape 1 Coff-icicuts of Corm 2 A=56. B =-U4.4C=77.3 TO =-34SS D=0.040 Equation is A + B ' rrmnb(C-To)ACtmT))J UpperShelffEnaay I 1.D(nxd) LawwUmff~HwrGY2XV~xc Temp@30 ft-Ts-76.4 Dcg P TempOSO ft4-=44.3 Deg F Flnt: FPry2 MAEa: SA533B1 BE 7212-1 OdwISton NA Capsun:U Pxlua n/CM",2 300 250 IS mals

• 155D aO

-300.0 -200.0 -100.0 0.0 100.0 200.0 a00.0 400.0 s00.0 600.0 Temperature In Dog F Charpy V-Notch Data "rmnjmDm JcPa CwN COmladCVN Diflimal

- 100. 00 21.00 19.38 1.62

-50.00 29.50 46. 14 - 16.64

-25.00 75.50 63. 45 12.05

.00 68.00 79. 45 -11.45

.00 102.00 79.45 22..55 50.00 98.00 99.95 -1.95 50.00 103. 50 99.95 3.55 75.00 57. 50 104.90 -47.40 75.00 119.00 104.90 14. 10 WCAP- 16918-NP April 2008 Revision 1

C-131 CAPSL U (HEAT AFFECTED ZONE)

Page 2 Plant Fadey2 M iaL SA533B1 Hcat B7212-1 Oriezion: NA Capsule U Plume=: n/MA2 Charp V-Notch Data kpa CYN (*amplu-dVN DMaUtsl 100.00 105.50 107.70 -2.20 125.00 124.50 109.24 15.26 175.00O 107.50 110.51 -3.01 200.00 113.50 110.74 2.76.

250.00 96.50 110.93 -14.43 300.00 108.00 110.98 -2.95 CawhmiracCffis m.948 WCAP- 16918-NP April 2008 Revision 1

C-132 CAPSULE W (HEAT AFFECTED ZONE)

C-YRAPH 5.3 Hyprolic Tangnmt Curve PrintS on MUM 05.23 PM pape 1 Codeficnts of Curve 3 A=64.1 B =6139C=28231 TO =-9.34 D =.0 E*40 Equdi isA +AtB' rrmh(rTTo-bC+Tl))]

Uppw 9hdeffHnam -126.0(13 msd Lawef UrcffBaqy=CZ2(FmxcD TempSO0 ft4r.-27A De gF Temp@5O) ftlbs-16.1 Deg F FPlat:Palsy 2 Mtea*: SA**3B1 ka Bfll2-1 Ouculdo: NA Cqpslk W Fbzmr,: Dta i

-4o0,- -uo.-1000.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temprature In Dog F Chap V-Notch Data M muMdCYN *flamtia

-100.00 20.00 2.45 17.55

-liOu. ao 29.00 2.45 26.55

-50.00 5.00 9.47 -4.47

-50.00 13.00 9.47 3.53

-25.00 9.00 33.84 -24.94

-25.00 79.00 33.84 45.16

-20.00 19.00 42.52 -23.52

.00 53.00 83. 18 -30.18

.00 119.00 83. 18 35.82 WCAP- 16918-NP April 2008 Revision 1

C-133 CAPSULE W (HEAT AFFECT ZONE)

Page 2 Plant Falcy 2 Macriak SA533B 1 Heat B7212-1 ldentmtiai: NA CapeuW W Plluexe: nh:mA2 Chamrpy V-Notch Data 10pul CYN 50.00 122. 00 123. 88 -1.88 76.00 132. 00 125.64 6.36 125.00 120. 00 125.99 -5.99 250.00 sq. no 126.00 -37.00 250.00 139. 00 126.00 13.00 350.00 155. 00 126.00 29.00 Cma CleffciM m.92 WCAP-16918-NP April 2008 Revision 1

C-134 CAPSULE X (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbaoc Tangent Curve Prined on 02/M= 05.23 PM Pap 1 Co-cificnts of Carve 4 A=6.1 B=6L9PC=67.01 TO=-23.6 D=OBS= .O0 Bquatia is A +B rranb(r-Tq)KC+DT))]

Uppw Sheff Eann=l23.0(Fbxsd) Lawu Uiulfflnmaj=a2(FxOd Tcmp@30 ft-b--65.7 Dog F Temp@.5 ft-ba--39.9 Dg F Plant Palcy 2 Medal: $SAS3B1 Heat B7212-1 OdaiwNA Casl:X K Flac nfmt2 3SO 5a Rioo aO

-M00.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F Chupy V-Nesh Data T¶MPMmuM -pa CYN cwVU1edcVN

-100.00 13.00 13. 86 -. 86

-70. 00 3.00 27.37 -19.37

-50.00 66. 00 41.50 24.50

-50.00 38. 00 41.50 -3.50

-40.00 59.00 49.97 9.03

-20.00 36.00 68.44 -32.44

.00 110.00 86.35 23.65

.00 135.00 86.35 40.65

.00 27.00 86.35 -59.35 WCAP- 16918-NP April 2008 Revision 1

C-135 CAPSULE X (HEAT AFFECTED ZONE)

Pago 2 Plantrarly2 MatIea SA53_B1 Heat B7212-1 Oienmauion: NA Capsuqe X luence: n/cm"2 Charpy V-Notch Data T20.0 20.00 127.00 101.06 25.94

50. 0a 91.00 115.40 -24.40 125.00 92.00 126.53 -34.53 200.00 118.00 127.84 -9.84 250.00 126.00 127.96 -1.96 350.00 140.00 128.00 12.00 Conulktm tbaffiit - .797 WCAP- 16918-NP April 2008 Revision 1

C-136 CAPSULE Z (HEAT AFFECTED ZONE)

CL"RAPH 5.3 Hyputblc Tangent Cur Panted on 02W2 05-23 PM Pap 1 Cacffidans of COrve S A =641 B=6L9C=76.1 7 1T= 14.7 D =,00E+00 Equsisi i. A + 1H' rrnnhu(T-TbAC+Dm))1 IUIn= Shelfr nmcI --126.0(PWamd) lowe Uzclf lupi=22(Had).

Tcmp@30 ft-lba-32A Det F TcmpO@!A-Ib=--2.9 Dog F Pln FwrEy2 Mamida: 5A3B1 Hcat B/212-1 Odmntfm NA Caaft Z FiemC 3OW 200 206 Im Rioo sa 5O

-sOa.a -20O.0 -i00.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperalum In Di9 F Charw V-Notch Data Tmownu ft" CVN COmluSdCVN

-100.00 1.00 7.99 .01

-60.00 16.00 17.44 -1.44

-30.00 20.00 31.42 -11.42

-20.00 61. 00 37.68 30.32

-15.00 68.00 41.10 26.90

-10.00 8.00 44.69 -36.69

-10.00 42.00 44.69 -2.69

.00 44.00 52.29 -8.29

.00 70. 00 32.29 17.71 WCAP- 16918-NP April 2008 Revision 1

C-137 CAPSULE Z (HEAT AFFECTED ZONE)

Page 2 Plant F*al 2 Matera SA53B31 Heat B7212-1 Orieldn: NA Capsnue Z luenc: n/MA2 Cluff V-Notch Data TmIqti c-mpalI*"VN 10.00 7.00 60.28 -53.28

25. 00 130.00 72.43 57.57 100.00 122. 00 114.11 7.39 150.00 115.00 122.56 -7.56 195.00 140. 00 124.93 15.07 50.00 68.00 90.91 -22.91 amoaa Ocm3 = .Al WCAP- 16918-NP April 2008 Revision 1

C-138 CAPSULE Y (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hypaoic Tangmt Curve Pried on 0)6Nf050.2A FM Pape 1 Codficet of Cmrve 6 A=S2.1 B = 49.3C = S242 TfO=-4A9 D =0.OEi0i Equtoais A t B 0 Ifmnb(T-TDACtDIh]

UpperShelffllar=-1E0(1'hm) Is cStclfBnzUa=220ixc0 Temp@30 ft-rh=-2&X6 Ifg F TcmpV.Sl ft-lha=-31 Deg F Finley 2 Maial: SA BI HEat B7212-1 Odummtow NA Capms:Y Fluxn ucn2 I

~100 aD o0.F

-M00.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature In Deg F Chap V-Notch Data

¶reapmunn c-Md CYN

- 75.00 8.00 7. 94 .06

-50.00 19.00 15.84 3.16

-25.00 73.00 31.27 41.73

-25.00 9.00 31.27 -22.27

.00 91.00 53.71 37.29

.00 ii. a0 53.71 -42.71 10.00 36.00 63.05 -27.05 2s. 00 71.00 75.52 -4.52 50.00 131.00 89.81 41.19 WCAP- 16918-NP April 2008 Revision 1

C-139 CAPSULE Y (BEAT AFFECTED ZONE)

Page 2 Plan. Parley 2 MateUa SA533B 1 Heat B7212-1 Orientmain: NA CauiM Y Pluoe: n/"ft2 Charp V-Notch Data CWmpmYdCVN 50.00 92.00 89.81 2.19 75.00 77.00 96.92 -19.92

90. 00 127. 00 99.07 27.93 125.00 62.00 101.21 -39.21 125. 00 111.00 101.21 9.79 150.00 107.00 101-. 5.31 Calmank Cbafficia - .764 WCAP- 16918-NP April 2008 Revision 1

C-140 CAPSULE V (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hypebolic Tangent Cmve Prineld on 02109M 0524 PM Page 1 Cacfcicnta of Curve 7 A=UM1 B=S7.9C=656 T0=61M D=0OE4+O0 Equtim is A + B

• rrs* ('r-To)CUTM']

UpperShcfflagy- 13.0(Fhed) LowerShoff aErrzfl22Vmo Temp@30 ft-lb=262 Dag F T=up@S0 ft-Zlh=52A Deg F lant Feld-y2 MeAal: SAS33BI Heat Bf212-OdmitiwE NA Capuc: Pxl nlcnr2 S

ISO U

8100 U

U U, so 0

400.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Tempermure In Deg F Charpy V-Notch Data hpw CYN -omutd CNVW

- 80.00 9.00 3.62 5.38

-15.00 17. 00 11.77 5.23 25.00 24.00 29.27 -5.27

35. 00 22.50 36.09 -13.59 40.00 54.00 39.86 14.14 45.00 69.00 43.83 25. 17 50.00 $5.00 47.98 7.02 70.00 13.00 65.43 -52.43 70.00 70.00 65.43 4.57 WCAP-16918-NP April 2008 Revision 1

C-141 CAPSUE V OMEAT AFFECTED ZONE)

Pagp 2 Piant: Pud2 Maca SA53BI Hat B7212-I Oriemain: NA Capsule V Flumc:

u:A2 Chamy V-Notch Data kpil CYN -ompumd CYN 90.00 94.00 31.96 12.04 115.00 107.00 97. 83 9.17 155.00 122.00 111.21 10.79 200.00 120.00 116.20 3.80 250.00 134.00 117.60 16.40 260.00 107.00 117.71 -10.71 Cbmgtm. CokenM .912 WCAP-16918-NP April 2008 Revision 1

C-142 UNIRRADA¶TE (HEAT AFFEC[E ZONE)

CVGRAPH 5.3 HypUerbc 'Tnt Curve Prmd on 0206O 05.26 FM pap I Cocf-kicnts of Curve I A =4&13 B =413C=19Sf3 TO=-13t9 D=0.AMOR Equatim is A + B I rl'nbT-To)KCtD'))j Up~r She LJ._--90.3 Lauf Shelf L.=JI(FmVMd)

TumpSLA.. 35 mil-t.3.6 DegF PlantfPsly2 Muldal: SA3B1 eaL B7fl2-1 OdcOMk nA CWk LNUI Fham: nfcmr2 200 1w so E0 0 aCa o

0 04O.0 0.0 300.0 600.0 Temperture In Deg F Charpy V-Notch Data fimummft nPSL*E. Dnb

-200.00 5.00 31.49 -26.49

-150.00 95.00 42.51 52.42

-100.00 57.00 53.98 3.02

-100.00 33.00 53.98 -20.93

-50.00 60.00 64.32 -4.32

-30.00 46.00 64.32 -11.32 20.00 73.00 75.38 -2.31 25.00 79.00 76. 01 2.99 50.00 91.00 78.81 12.19 WCAP- 16918-NP April 2008 Revision 1

C-143 UNIRRlADATED (HEAT AFFECTE ZONE)

Pag 2 Plant PFafly2 Matriak SA533B1 Heat: B7212-1 Orientation: NA Capsutl UNIRR fiuen= ncmA2 Charpy V-Notch Data hnlL L.H.

75.00 37.00 81.13 5.87 100.00 31.00 83.02 -2.02 150.00 95.00 85.77 9.23 210.00 91.00 87.77 3.23 210.00 73.00 87.77 -14.77 210.-0 37.0 0 87. 77 -. 77 Cbmkimi Obeffic - -701 WCAP-16918-NP April 2008 Revision 1

C-144 CAPSUE U (EAT AFFECTED ZONE)

CVGRAPH 5.3 Hypetoli Tangent Curv Pdtzd on 02A62= 05:26 FM Cocfficiets of CDi 2 A =44.16 B=44.16C=99125 TO=-39A6 D =0O.00_E0 Equwiamis A + B' rrmLb(cT-Tb)ACtDT1)]

upper Shbel .. =3.,3 Lowr SheIf L.E=.(0"U4d)

Temp@LE. 35 mils=-59.8 Deg F FlMFs-cy2 Matidal: SAS3BI HE Bl7212-1 OdamMui NA Cpalem:U mu AuWA2 I

U U.

'U

-00.0 0.0 300.0 600.0 Temperature In Deg F Chaupy V-Notch Data OL, low

[6.50 18.59 -2.09

-50. 00 28.50 39. 18 -10.63

-25.00 63.00 51. 20 1lt. so

. 0a 57.50 62. 23 -4.73

. 00 75.00 62. 23 12.77

50. 00 70. 00 77. 47 -7.47

50. 00 32. 50 77. 47 5.03 75s. 0 S0. 00 81. 70 -31.70

75. 00 39.00 81. 70 7.30 WCAP-16918-NP April 2008 Revision 1

C-145 CAPSULE U (HEAT AFFECTED ZONE)

Pap 2 Plan* Fafdy 2 MatcrIak SA533B1 Heat B7212-I lentatmion: NA Capsule: U Pluence: nAMA2 Charpy V-Notch Data L tm.utLZ.

100.00 39.00 84.37 4.63 125.00 92. 50 86. 00 6.50 175.00 39. 00 87.53 1.47 200.00 90. 00 87.86 2.14 250.00 37.50 88. 17 -. 67 300.00 92.00 88. 27 3-73 Carmatdm' Qfficut m.- 92 WCAP- 16918-NP April 2008 Revision I

C-146 CAPSULE W (HEIAT AFFECTED ZONE)

CVGRAPLH 5.3 Hypert0c Tangent Curve Prhild on 020. 005:27 PM Pape Cocfficnts of Camve 3 A =46.3 B=46.39C=45A TO=-9-2 D =mAO.

Hqumizu is A + Br 'Tw(t'T-To)ACD-s))]

Upper ShlfLB--M92. Lowa Sbhlf .LE=.(ftud)

TempA@LJL 35 ml--20.6 Deg F Flemat Py2 Aitedal:

• WBfl12-1 A533B1 Ht Ocnhitsion: NA Cquukc W Elects: s/ca" 2OO iso I

2 1100 SD 00.0

-M0.0 0.0 300.0 600.0 Tempsrature In Deog F Chap V-Notch Data fto L. ch*RndL.

-100.00 15.00 1.67 13.33

-100.00 16.50 1.67 14.13

-50.00 9.50 13.21 -3.71

-50.00 23.00 13.21 9.79

-25.00 10.00 30.90 -20.90

-25.00 57.00 30.90 26.10

-20.00 14. 50 35.59 -21.09

.00 41.00 55.69 -14.69

.00 30.00 55.69 24.31 WCAP-16918-NP April 2008 Revision 1

C-147 CAPSULE W (HEAT AFFECTED ZONE)

Pape 2 Plan Pmaley 2 Mutc*ank SA533B 1 Heat: B7212-1 Ofientmai: NA Capsule, W Place: nkemAl Charpy V-Notch Data TanpOMM qpu LK. -m L.

50.00 90.00 86.43 3.57 76.00 92.50 90.66 1.84 125.00 97.50 92.54 4.96 250.00 70.50 92.79 -22.29 250.00 97.50 92.79 4.71 350. 00 99.50 92.79 6.71 Comwelnfa be~ciaS - "9 WCAP- 16918-NP April 2008 Revision 1

C-148 CAPSULE X (HEAT AFFECTED ZONE)

CVGRAPH 5.3 HypetOBiC ¶bnw Curve Printe o 0210612008 05:7 PM Ppag 1 CoeXficients of Cman 4 A = 4261 B =42A.1C = 61.23 V =-25.29 D = tO._.0 Equtiom is At+B rrmnb((T-To)KC+T))]

Upper Shelf LA-35(2 Lower ShefL.&= alrzcd)

Temp.@LJI. 35 mflz-37.0 Deg F FlueFsa2 Mgedia: SAS33BI Hue B212-1 OdatiWoENA Caonl:x Flusc nkA2 200 A

Im 31100 5D 0I-

-0M.0 0.0 300.0 600.0 Temperature In Deg F Charpy V-Notch Data DUiMMM

-100.00 9.00 6.97 2.03

-70.00 7.00 16.35 -9.35

-50.00 40. 00 26. 70 13.30

-50.00 23.00 26. 70 -3.70

-40.00 40. 00 33. 02 6.91

-20.00 32.00 46. 76 -14.76

.00 68.00 59. 68 8.32

.00 91.00 59. 68 31.32

.00 I5. 00 59. 68 -44.63 WCAP- 16918-NP April 2008 Revision 1

C-149 CAPSUE X (HEAT AFFECTED ZONE)

Pag 2 PlHaw Fadcy2 Maeriak SA533B1 IHcat B7212-1 Orientation: NA Capsutl X Pluence: n/cmA2 Charpy V-Notch Data Dic 20.00 92. 00 69.69 22.31 50.00 65.00 78.64 13.64 125.00 76. 00 84.60 -3.60 200.00 32.00 85. 16 -3.16 250.00 90. 00 85.20 4.80 350.00 94. 00 85.21 '.79 Cmukm Cbeffid.m -. 37 WCAP- 16918-NP April 2008 Revision 1

c-i o CAPSULE Z (HEAT AFFECTED ZONE)

C *RAPH 53 Hypuerbc langent Curve Pdned an 02W06n= 05-27 PM Page 1 Coefficiats Of Curve 5 A =43.04 B =43.04C=70X5 IV= 18,M D =0,00E+00 Equtkui is A +-B rrfbh(Cr-To)MC4lf))1 Upper SM L.E.=16.1 Lws Shelf L.B.=.0(FPIxd)

Tcnp.@LE. 35 mila.1 DelF rPlan F"1y 2 Matedal: SA.3SBI Neat B7212-1 OdLSOe NA Cqpadc Z Fluze tkmf2 a

"S d

IN E

I I 100 V _________

V V

0] V 40-.0 0.0 300.0 600.0 Temperature In Deg F ChapV-NotcBData T¶memMuM faOVaMd &LE

-100.00 2.00 2.85 _-. 15

-60.00 5.00 1.34 -3.34

-30.00 9.00 17.34 -1.34

-20.00 46.00 21.62 24.31

-15.00 40.00 24. 01 15.99

-10.00 4.00 26.56 -22.56

-10.00 26.00 26.56 -. 56

.00 25.00 32.05 -7.05

.00 43.00 32. 05 10.95 WCAP- 16918-NP April 2008 Revision 1

C-151 CAPSULE Z (HEAT AFFECTED ZONE)

Pap 2 Pluat Pare 2 Maiti SA533B1 Heat B7212-I Orifltinn: NA CaqsunI. Z Phumn: n/cmA2 Charpy V-Notch Data

¶NxempMun -ampuladl.K 10.00 1.00 37.97 -36.97 25.00 90. 00 47. 13 42.37

£00.00 87.00 73.45 8. 55 150.00 3S9 00 84. 12 3. 88 195.00 79. 00 85.53 -6.53 50.00 40. 00 61.26 -21.26 comnhjamr0cc = .W06 WCAP-16918-NP April 2008 Revision 1

C-152 CAPSULE Y (HIEAT AFFECTED ZONE)

CVGRP 5.3 Hypatic Tanget Curve Prinmed on 02/0.0 05.28 PM Pape 1 Cocffimcnt of Cm.v 6 A =4125 BN=4L25C=6L96 T0=3.9 D =O.OO*4 Swquatizis A + 8 rru*n(cr-To)KC+tl)]

Upper Shelf L..=82.S Lower Sbelf LJL=.0(Fzaid)

Tcnmp.@L.R 35 mis=-55 Deg F Plant Palsy 2 Medl;SA*S* 1 Hea B7fl2-1 Otwnioa- NA Capsm: Y FIum nlMcr2 130 IS IL 100 so N I I I I 40M.0 0.0 300.0 600.0 Temperature In Deog F Champy V-Notch Data Inpu LL.

-?75.00 3.00 5.99 -2.99

- 50.00 15.00 12.32 2.63

-25.00 53.00 23.29 29.71

-25.00 10.00 23.29 -13.29

.00 70.00 38.65 31.35

.00 6.00 38.65 -32.65 10.00 21.00 45.29 -24.29 25.00 51.00 54.77 -3.77

50. 00 37.00 67. 30 19.70 WCAP- 16918-NP April 2008 Revision I

C-153 CAPSULE Y (HEAT AFFECTED ZONE)

Page 2 PiatParly FM 2 MaeriaL SA533B1 Hat: B7212-1 Orienmazo: NA Capsu Y Punce: n/MA2 Chap V-Notch Data hmpm L& Oaupad L.

50.00 77.00 67.30 9.70 75.00 61.00 74.94 -13.94 90.00 91.00 77.67 13.33 125.00 65.00 80.87 -15.87 125.00 81.00 80. 87 .13 150.00 35. 00 81.76 3.24 CautmAio cIc - .516 WCAP- 16918-NP April 2008 Revision 1

C-154 CAPSULE V (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyprbolic ¶bnm Cuve PinaSd on 02100M 0528 PM PageB 1 Cocffi*dmts of Cmrve 7 A =a4n.M B =45.23C = 67.71 TO =65.26 B =0.O0E+i0 P4stiamis At B

• frur(r-To)C+-Tm))j

[Jpper ShelfLE=95 Lauwc Shelf LBE-.=h(xzc)

TemniLA 35 nm*i=9.7 Dq F 0fet fIocy2 Moxd: SASS3BI Set 572121 Odimniow NA Canuil: Fhmuw AknYQ2 2o Ia A

10

• U U

dl U ID 50 U U

U U n 1 400.0 0.0 300.0 600.0 Temperature In Dog F Chrpy V-Notch Data DUMEmdd

- 80.00 22.00 1.22 20. 78

-15.00 [5. 00 7.73 7.27 25.00 15. 00 21. 12 -6.12 35.00 14. 00 26.27 -12.27 40.00 38.00 29. 10 8.90 45.00 51.00 32.09 11.91 50.00 41.00 33.21 3.79 70.00 14. 00 48.40 -34.40

70. 00 47.00 48.40 - 1.40 WCAP- 16918-NP April 2008 Revision 1

C-155 CAPSULE V (HEAT AFFECTED ZONE)

Pap 2 Plait 1aft 2 Matedat SA533B1 Heat: B7212-1 Ouemazion: NA Capsule V Pluence: nlcr2 Charpy V-Notch Data T7MP~m' f*PtwL.IL -OMptdl.I 90.00 70. 00 61.06 8.94 115.00 85.00 73.55 11.45 155.00 39.00 34.50 4.50 200.00 94.00 88.81 5.19 250.00 95.00 90.08 4.92 260.00 72.00 90.18 -13.13 Cmxttm Caeffid - A92 WCAP- 16918-NP April 2008 Revision 1

C-156 UNIRRADIATD EAT AFFECTZONF CVYGIAPH 5.3 Hypertbc lbagM Curvme Prnt on 021060O 05:30 PM PapI Coeffiigmts of Care 1 A=S0S B=50.C==18.06 TO=-11i6.09 B=m -BE400 qutiwan is A B' ITmnw((T-T)AC*t÷lT))j TSUpMmCtM at 50% Shear = -116.0 Plant Fley 2 Mateial: SA533BI Heat B7212-1 Odenubm NA Cqwkl IJNIR Fiama: acn'Qr I

lfl aa

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 4m.0 50.O 600.0 Temperture In Deo F Charpy V-Netch Data TmeMOM camp PMfm SSer DIMnMl

-200.00 3.00 28. 86 -20.86

-150.00 100.00 40.99 59.01

-100. o0 45.00 54.31 -9.31

-100.00 42.00 54. 31 -12.31

-50.00 60. 00 67.05 -7.05

-50.00 34. 00 67.05 -33.05 20.00 32. 00 81.20 .80 25.00 33.00 82.00 1.00 50.00 100.00 85. 64 14.36 WCAP-16918-NP April 2008 Revision 1

C-i157 UNtRRADIATED (HEAT AFFECTED ZONE)

Pap 2 Plan. Padcy 2 Mmctri SA533BI H-eat B7212-1 Ozitlom: NA Capmsle, UNIR Raum nlcnt2 Charpy V-Notch Data D!a 75.00 100.00 88.64 11.36 100.00 100.00 91.07 8.93 150.00 100.00 94. 58 5.42 210.00 100.00 97.08 2.92 210.00 93.00 97.08 -4.03 210.00 100.00 97.08 2.92 Cozd -bfi

-751 WCAP- 16918-NP April 2008 Revision 1

C-158 CAPSUu (H AT AFFECTED ZONE)

CVGRAPH 5.3 Hyperblic Tangent Curve Punted on 021020 05:30 PM Pap 1 CocfiMcnt of Come 2 A=S. B=SL.C=76fl TOa.-2fM D = O01R+OO Equtionis A +B 0 Tua(CF-To)hC+tDT)j Tunpmertrn at5 Shin= -2.0 Plant Fulcy2 Menial: SA533BI Heat fB7212-1 Ofiwttion;A Csmuc:U Pluc nkm*2 125 100 I

U 75

£ a so 25 0 , I - I- - fi - i M -- I

-00.0 -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 COMlmS Pan=m flr

- 100.00 5.00 13. 16 -1.16

-50.00 - 1.01 35.00 36. 01

-25.00 52.00 52.02 -. 02

.00 62.00 67.63 -5.63

.00 37.00 67.63 19.37 50.00 34.00 88.58 -4.58 30.00 32.00 88.58 -6.58 75.00 73.00 93.73 -20.73

75. 00 100.00 93.73 6.27 WCAP- 16918-NP April 2008 Revision I

C-159 CAPSULE U (HEAT AFFECTED ZONE)

Pap 2 Plant. Farley 2 Material SA533B1 Heat B7212-1 Orentaion: NA Capsule U Pluence: n/m"2 Charpy V-Notch Data "reavemm - ShePao=

a*e 100.00 100.00 96. 65 3.35 125.00 100.00 98. 23 1.77 175. o 100.00 99..52 .48 200.00 100.00 99.75 .25 250.00 100.00 99.93 . 07 300.00 100.00 99.98 - 02 Csunbsm Cbefficia - M56 WCAP-16918-NP April 2008 Revision 1

C-160 CAPSULE W (BEAT AFFECTED ZONE)

CVGRAPH1 5.3 Hypeolic TngMt Curve Plted on 021060M 05:31 FM Pape 1 Coeffici--ti of cmuve 3 A=5IL B-50.C=275 T0I--1I3S D=cO.OO+O Equtkinis A +BBirmn((T-To)C+tDTD]

Tcapau at .SO Shle = -11.3 Fadnt P..2 Maadia: SA533B1 BHat B7212-1 Odmoaton:NA Cqu W Ebma¶ ulaa"1 126 100 75 V

so 25 01 1 400.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 o0.O 600.0 Temperturf In Dog F Charpy V-Notch Data rmpmmuo comtaked PrrMM ffel"

-100.00 9.00 .15 8.85

-100.00 10. a0 9.85

-50.00 9. 00 5.61 3.39

-50.00 13. 00 5.61 7.39

-25.00 16. 00 26.99 -10.99

-25.00 31. C0 26. 99 4.01

-20.00 35.00 34. 77 .23

.00 49.00 69.70 -20.70

.00 94. 00 69.70 24.30 WCAP- 16918-NP April 2008 Revision 1

C-161 CAPStUL W (HEAT A1'FECrE ZONE)

Pagp 2 Plant* l*ry2 Macri-SA533B1 H tB7212-I Ofienic: NA Capsule: W Flue: njcmA2 Charp V-Notch Data c- Nd Shern 50.00 96.00 98.89 -2.89 76.00 97. 00 99.83 -2.83 125.00 100. 00 100.00 . 00 250.00 95. 00 100.00 -5.00 250.00 100. 00 100. 00 . 00 350.00 100. 0o 100.00 . 00 Canmuiaw Cbeffi4 .-- 72 WCAP-16918-NP April 2008 Revision 1

C-162 CAPSLE X O(AT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic ThI Cunrv Prmted on 02160 05:31 PM Co--mts of Curm 4 A =S0. B Cn5".CcS TO =l-14A D=.063E00 Bqutim is A t B 0rrm((T--T¶)IbCDT))]

Talpamnin at 50%Shcs= -14.8 Plant: FPb 2 Matmial: SA53BI HeatL B7212-1 Odwimiow NA Cupm=l: X n~unz nftm"

'IU

-it.0 -200.0 -100A 0.0 100.0 200.0 300.0 400 .0 600.0 Temperature In Dog F Chm-p V-Notch Data Tmjmn IRM Pmnm show

-100.00 5.00 6.26 -1.26

-70.00 5.00 14.77 -9.77

-50.00 35.00 24.64 10.36

-50.00 20.00 24.64 -4.64

-40.00 35.00 31.00 4.00

-20.00 35.00 45.88 -10.88

.00 65.00 61.54 3.46

.00 95.00 61.54 33.46

.00 25.00 61.54 -36.54 WCAP-16918-NP April 2008 Revision 1

C-163 CAPSULE X O(AT AFFECTED ZONE)

Page 2 Plant Pary 2 MatlntzU SA533B 1 Heat B7212-1 Orlemauion: NA Caslm X Puence: n/fmA2 Charpy V-Notch Data IDpuPflrOMt 20.00 100.00 75. 12 24.88

50. 00 65.00 88.67 -23.67 125.00 75.00 98.83 -23.83 200. 00 100.00 99.89 .11 250.00 100. 00 99.98 .02 350.00 100.00 100.00 .00 CwrznhM fbeffic , .572 WCAP- 16918-NP April 2008 Revision 1

C-164 CAPSULE Z (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyprbolic Tangent Curve PrntS on 02AWO 05:32 FM Pap I Coefrfiiets of CaNrv 5 Af=fSL B =5I&C=7M34 TO=16.15 D =S00E40 Equtismis A +SB rT*rm(T-ToC+tmT)J Tempcnbzzc a 50% SMr = 16.2 Plant F.Iey2 Matidal: SAS33BI Heat B7212-l OdenicE 1A Cqwjc Z Pbxuzcce an'Q 125 I'U 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 Iupn PMnm c(mkd n 5-=

- tOO. 00 5.00 3.65 1.35

-60. 00 20. 00 10.46 9.54

-30. 00 15.00 21.40 -6.40

--20.00

15. Oa

-15.00

40. 00 26.52 13.43 45.00 29. 36 15.64

-10.00 25.00 32. 36 -7.36

- 10. 00 20.00 32. 36 -12.36

• O0 25.00 38.81 -13.81

.00 S0. 00 38.81 11.19 WCAP- 16918-NP April 2008 Revision 1

C-165 CAPSULE Z (HEAT AFFECTED ZONK)

Pap 2 Plantra&y2 M i A53- 1I HeatB7212-1 Odentatlon: NA Capsule.Z Phueace: nkmA2 Cha*r V-Notch Data cmm Pao=Sh naiad 10.00 10.00 45.68 -35.68 25.00 100.00 56.21 43.79 LO0. 00 100.00 91.40 8.60 150.00 100.00 97.75 2.25 195.00 100.00 99.36 .64 50.00 55.00 72.20 -17.20 Canfw bed~cieS m.861 WCAP- 16918-NP April 2008 Revision 1

C-166 CAPSULE Y MAT AFFECTED ZONE)

CVCRAPH 5.3 Hyperbuoc Tangent Curve Pnuted on 0210600 05:32 PM Pape 1 Coefficzits of Curve 6 A=-5IL I=- S C=67.51 TO1=43 D =.0.00E44 EPsunis is A + IW rr=W(T-ToAC+il)']

¶bnpm t 50%Shcar= 4,L Plant FP-by2 Maftal: **33BI Heat f7212-I Odwutsiow.NA. Cipal: Y Mlug nkm"t2 I

'U U

a 400.0 -200.0 -100.0 0.0 100.0 200.0 3m0.0 400.0 m.0 600.0 Tempenrsure In Dog F Chap V-Notch Data TupmrMm m Paem Sme OMPme PrM ffr

-75.00 10. 00 8. 59 1.41

-50. o0 10. ao 16.47 -6.47

-25.00 45. 00 29. 26 15.74

-25.00 25.00 29. 26 -4.26

.00 90. 00 46. 45 43.55

.00 20.00 46. 45 -26.45 10.00 25.00 53. 85 -23.85

25. 00 55.00 64. 53 -9.53

50. 00 100.00 79. 24 20.76 WCAP-16918-NP April 2008 Revision I

C-167 CAPSUL Y (HEAT AFFECTED ZONE)

Pagre 2 Plant Padey 2 Matcrink SA533B1 Hat B7212-1 Oriention: NA Capule Y Rluence: nMA2 CharMp V-Notch Data 50.00 90.00 79.24 10.76 75.00 65.00 88. 89 -23.89 90.00 100.00 92. 58 7.42 125.00 100.00 97. 24 2.76 125.00 100.00 97. 24 2.76 150.00 100.00 gm. 66 1-34 Cormisd CbdFfcimft - -M5 WCAP-16918-NP April 2008 Revision 1

C-168 CAPSUME V (HEAT AFFECTED ZONE)

CVCRAPH 1.3 Hypuoc Tangwt Curve Pdnted on 02 O0W05:32 PM Page 1 Cccffiiuts of Cmuv 7 AS L B =S&Cc=5S& T0=56.34 D =S. OMIS Equtia mis A +B [1b(UT-T)AC+l'D))]

I Tcmpumyma 50% Sher = 56A lamnt FEcI 2 Matmial: SA533B1 HRe B7212-1 Oziisow NA Cqma -:V i avutm"2 125 100 2 75 a

25 4100.0 -200.0 -100.0 0.0 100.0 200.0 uO0.0 400.0 500. 600.0 Temnperamre In Dog F Chmrp V-Notch Data C pmamd= uMsr

- 80.00 2.00

• 76 1.24

-15.00 10.00 7.24 2.76 25.00 20.00 24. 59 -4.59 35.00 20.00 31.80 -11.80 40.00 40. 00 35. 79 4.21 45.00 60. 00 40. 00 20.00 30.00 S0. 00 44. 35 5.65 70.00 30. 00 61.97 -31.97 70.00 70. 00 61.97 1.03 WCAP- 16918-NP April 2008 Revision 1

C-169 CAPSULE V (HEAT AFFECTED ZONE)

Pagp 2 Pint FPeiy 2 MaLc SA533B1 Hcat B721Z-Odenudiom : NA CapuIE V Pluhnce: nMfa2 Charpy V-Nolth Data compmPaen t sbcw 90.00 30.00 76.91 3.09 115.00 100.00 39.06 10.94 155.00 100.00 97.14 2.86 200.00 100.00 99.42 .58 250.00 100.00 99.90 .10 260.00 100.00 99. 93 *07 castiium canit - -M95 WCAP- 16918-NP April 2008 Revision I

D-1 APPENDIX D JOSEPH M. FARLEY UNIT 2 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. Positions 2.1 and 2.2 of Regulatory Guide 1.99, Revision 2, describe the method for calculating the adjusted reference temperature and Charpy USE of reactor vessel beltline materials using surveillance capsule data. The methods of Positions 2.1 and 2.2 can only be applied when two or more credible surveillance data sets become available from the reactor in question.

To date there have been six surveillance capsules removed from the Farley Unit 2 reactor vessel. To use these surveillance data sets without additional margin, they must be shown to be credible. In accordance with the discussion of Regulatory Guide 1.99, Revision 2, there are five requirements that, must be met for the surveillance data to be judged credible.

The purpose of this evaluation is to apply the credibility requirements of Regulatory Guide 1.99, Revision 2, to the Farley Unit 2 reactor vessel surveillance data and determine if that surveillance data is credible.

D.2 EVALUATION Criterion 1 Materials in the capsules should be those judged most likely to be controlling with regard to radiation embrittlement.

The beltline region of the reactor vessel is defined in Appendix G to 10 CFR Part 50, "Fracture Toughness Requirements,'[D-2] as follows:

"the reactor vessel (shellmaterial including welds, heat affected zones, andplates orforgings) that directly surrounds the effective height of the active core and adjacentregions of the reactor vessel that are predictedto experience sufficient neutron radiationdamage to be consideredin the selection of the most limiting materialwith regardto radiationdamage."

The Farley Unit 2 reactor vessel consists of the following beltline region materials:

• Intermediate Shell Plates B7203-1 and B7212-1

• Lower Shell Plates B7210-1 and B7210-2

• Intermediate to Lower Shell Circumferential Weld Seam 11-923 (Heat #5P5622)

• Intermediate Shell Axial Weld Seams 19-923A (Heat #HODA) and 19-923B (Heat #BOLA) 0 Lower Shell Axial Weld Seams 20-923A and 20-923B (both Heat #83640)

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D-2 The Farley Unit 2 surveillance program utilizes longitudinal and transverse test specimens from intermediate shell plate B7212-1. The surveillance weld metal was fabricated with weld wire heat #

BOLA.

Per Reference D-3, the Farley Unit 2 surveillance program was based on ASTM E 185-73, "Standard Recommended Practice for Surveillance Tests for Nuclear Reactor Vessels" [Ref. D-4]. Per Section 4.1 of ASTM E 185-73, "The base metal and weld metal to be included in the program should represent the material that may limit the operation of the reactor during its lifetime. The test material should be selected on the basis of initial transition temperature, upper shelf energy level and estimated increase in transition temperature considering chemical composition (copper (Cu) and phosphorus (P)) and neutron fluence." At the time when the Farley Unit 2 surveillance program material was developed, intermediate shell plate B7212-1 was judged to be the most limiting and was therefore utilized in the surveillance program.

The Farley Unit 2 surveillance program weld was fabricated using the shielded metal arc welding process and E8018 stick electrodes, in a manner similar to that used to fabricate middle shell axial seams 19-923A (heat HODA) and 19-923B (heat BOLA). These electrodes were not copper-coated and do not exhibit the chemical variability found in copper-coated submerged arc weld wire. Although the surveillance weld material does not represent the limiting reactor vessel beltline weld, the results of mechanical property tests performed on the surveillance weld are considered to be representative of the property changes expected in the reactor vessel beltline seams. The NRC explicitly approved the selection of the Farley Unit 2 surveillance weld material on the basis that the limiting beltline material (i.e., intermediate plate B7212-1) was included in the surveillance program and conservative methods of analysis contained in Regulatory Guide 1.99 were available to predict the radiation characteristics of the limiting beltline weld.

The NRC incorporated an exemption to the requirements of Appendix H to 10CFR50 in the Farley Unit 2 Operating License, thereby approving the selected surveillance weld material based on the NRC evaluation.

Although the Farley Unit 2 surveillance weld material does not meet the requirements of Criterion 1, conservative methods of analysis are available to predict the radiation characteristics of the limiting beltline weld. The limiting beltline material is intermediate plate B7212-1 which is more limiting than any of the reactor vessel beltline welds and is included in the reactor vessel material surveillance program. Therefore, the Farley Unit 2 reactor vessel material surveillance program provides assurance that the radiation damage to the vessel can be adequately determined and the integrity of the Farley Unit 2 reactor vessel will be ensured during normal plant operations and anticipated operational occurrences.

Therefore, the Farley Unit 2 surveillance program meets this criterion.

Criterion 2 Scatter in the plots of Charpy energy versus temperature for the irradiated and unirradiated conditions should be small enough to permit the determination of the 30 ft-lb temperature and USE unambiguously.

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D-3 All of the Farley Unit 2 Charpy energy versus temperature surveillance program data can be found in Appendix C, including data for the unirradiated material. Charpy V-Notch test data for the Farley Unit 2 Surveillance Capsule V specimens is tabulated in Tables 5-1 through 5-4, with scatter that falls within the expected variance of test results for these materials. 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 USE of the Farley Unit 2 surveillance materials unambiguously. Hence, the Farley Unit 2 surveillance program meets this criterion.

Criterion 3 When there are two or more sets of surveillance data from one reactor, the scatter of ARTNDT values about a best-fit line drawn as described in Regulatory Position 2.1 normally should be less than 28°F for welds and 17'F for base metal. Even if the fluence range is large (two or more orders of magnitude), the scatter should not exceed twice those values. Even if the data fail this criterion for use in shift calculations, they may be credible for determining decrease in USE if the upper shelf can be clearly determined, following the definition given in ASTM E1 8 5 - 8 2 ID-4.

The functional form of the least squares method as described in Regulatory Position 2.1 is 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 welds and less than 177F for the plate.

The Farley Unit 2 plate and weld specimens are both evaluated for credibility. The weld is made from weld wire heat #BOLA; no other plant has this weld wire heat in their surveillance program and, thus, this assessment does not utilize data from other surveillance programs.

Credibility Assessment Since all surveillance data is from one vessel (Farley Unit 2), the measured ARTNDT and fluence factor (FF) should be used to calculate the chemistry factor to determine if the surveillance material test results are credible.

The chemistry factors for the Farley Unit 2 surveillance plate and weld material contained in the surveillance program were calculated per Regulatory Guide 1.99, Revision 2, Position 2.1, including the negative shifts in RTNDT as determined from the curve fit data. These chemistry factor calculations, used to calculate ARTNDT scatter between the measured and predicted values, are provided in Table D- 1. The credibility calculations are presented in Table D-2.

Plate Evaluation Table D-2 indicates that two of the measured ARTNDT values are slightly below the lower bound of lI (171F) by less than 57F. This indicates that the best fit line would slightly over-predict these measured ARTNDT values. Table D-2 also indicates that one of the measured ARTNDT values is slightly above the upper bound of 1lT (17°F) by approximately 37F.

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D-4 Table D-1 Farley Unit 2 Surveillance Data Chemistry Factor Calculation for Credibility Material Capsule Caps. f FF ARTNDT FF*ARTNDT FF 2 Intermediate Shell U 0.605 0.859 105.5 90.7 0.738 Plate B7212-l (lotudinal)1 W 1.73 1.151 167.7 (Longitudinal) 193.0 1.324 X 2.98 1.289 164.8 212.4 1.662 Z 4.92 1.399 200.1 280.0 1.958 Y 6.79 1.458 214.2 312.3 2.125 V 8.73 1.496 218.3 326.6 2.238 Intermediate Shell U 0.605 0.859 124.0 106.5 0.738 Plate B7212-l (Tansverse)-W 1.73 1.151 168.5 (Transverse) 193.9 1.324 X 2.98 1.289 200.1 258.0 1:662 Z 4.92 1.399 195.8 274.0 1.958 Y 6.79 1.458 231.0 336.8 2.125 V 8.73 1.496 215.3 322.1 2.238 SUM: 2906.13 20.091 CFB7212-1= X(FF

• RTNDT) + Y(FF 2 ) = (2906.13) + (20.091) = 144.6 0 F Surveillance Weld U 0.605 0.859 -28.4 -24.4 0.738 Material W 1.73 1.151 7.0 8.1 1.324 X 2.98 1.289 -15.6 -20.1 1.662 Z 4.92 1.399 10.2 14.3 1.958 Y 6.79 1.458 69.1 100.7 2.125 V 8.73 1.496 56.5 84.5 2.238 SUM: 163.08 10.046 CF Surv. Weld = YX(FF

• RTNDT) -+-Y(FF 2 ) = (163.08) + (10.046) = 16.2 0F WCAP- 16918-NP April 2008 Revision 1

D-5 Table D-2 Farley Unit 2 Surveillance Capsule Data Scatter about the Best-Fit Line Measured Predicted Scatter CF ARTNDT ARTNDT ARTNDT <17F0)

Material Caps. (SIOpebest f1t) FF (OF) (OF) (OF) <280F(2 )

Intermediate U 144.6 0.8593 105.5 124.3 18.8 NO Shell Plate W 144.6 1.1508 167.7 166.4 1.3 YES B7212-1 (Longitudinal) X 144.6 1.2891 164.8 186.4 21.6 NO Z 144.6 1.3992 200.1 202.3 2.2 YES Y 144.6 1.4579 214.2 210.8 3.4 YES V 144.6 1.4960 218.3 216.3 2.0 YES Intermediate U 144.6 0.8593 124.0 124.3 0.3 YES Shell Plate B7212-1 W 144.6 1.1508 168.5 166.4 2.1 YES (Transverse) X 144.6 1.2891 200.1 186.4 13.7 YES Z 144.6 1.3992 195.8 202.3 6.5 YES Y 144.6 1.4579 231.0 210.8 20.2 NO V 144.6 1.4960 215.3 216.3 1.0 YES Surveillance U 16.2 0.8593 -28.4 13.9 42.3 NO Weld Metal W 16.2 1.1508. 7.0 18.6 11.6 YES X 16.2 1.2891 -15.6 20.9 36.5 NO Z 16.2 1.3992 10.2 22.7 12.5 YES Y 16.2 1.4579 69.1 23.6 45.5 NO V 16.2 1.4960 56.5 24.2 32.3 NO Notes:

1. <17°F applies to the plate specimens and a "Yes" indicates it is credible.

2. <28TF applies to the surveillance weld specimens and a "Yes" indicates it is credible.

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D-6 From a statistical point of view, +/- ly (171F) would be expected to encompass 75 percent of the data. It is still statistically acceptable to have 3 of 12 points fall outside the +/- 1Ii bound. The fact that 3 measured ARTNDT values are slightly outside the bound of 17°F can be attributed to several factors, such as: 1) the inherent uncertainty in the Charpy test data, 2) the use of symmetric hyperbolic tangent Charpy curve fitting program versus an asymmetric hyperbolic tangent Charpy curve fitting program or a hand drawn curve using engineering judgment, and/or 3) rounding errors.

Looking at the data given in Table D-2, eight of the measured ARTNDT values are within 7°F of the predicted values for the plates. Hence, based on the arguments above, the plate data meets the intent of this criterion. (Note that this approach is consistent with the previous evaluation of the Capsule Y data.)

Weld Evaluation Table D-2 indicates that four of the six surveillance data points are outside the +/- I a of 28°F scatter band for the surveillance weld material; therefore, the surveillance weld data is deemed "not credible" per the third criterion.

Criterion 4 The irradiation temperature of the Charpy specimens in the capsule should match the vessel wall temperature at the cladding/base metal interface within +/- 25°F.

The capsule specimens are located in the reactor between the neutron pad and the vessel wall and are positioned opposite the center of the core. The test capsules are in baskets attached to the neutron pad.

The location of the specimens with respect to the reactor vessel beltline provides assurance that the reactor vessel wall and the specimens experience equivalent operating conditions such that the temperatures will not differ by more than 25°F. Hence, this criterion is met.

Criterion 5 The surveillance data for the correlation monitor material in the capsule should fall within the scatter band of the database for that material.

The Farley Unit 2 surveillance program does not contain correlation monitor material. Therefore, this criterion is not applicable to the Farley Unit 2 surveillance program.

D.3 CONCLUSION Based on the preceding responses to all five criteria of Regulatory Guide 1.99, Revision 2, Section B, the Farley Unit 2 surveillance data is deemed credible for the plate specimens and non-credible for the weld specimens. Credibility of surveillance data is used to determine the appropriate margin term for calculation of adjusted reference temperature in accordance with Reference D-1. Credible plate surveillance data may utilize a reduced oT.term of 8.5°F, while the non-credible weld surveillance data must utilize the full (T.term of 28TF, in calculation of the margin term for determining the respective vessel materials' Position 2.1 adjusted reference temperatures.

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D-7 D.4 REFERENCES D-1 Regulatory Guide 1.99, Revision 2, RadiationEmbrittlement of Reactor Vessel Materials, U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, May 1998.

D-2 Code of Federal Regulations, 10CFR50, Appendix Q FractureToughness Requirements, and Appendix H, Reactor Vessel MaterialSurveillance ProgramRequirements, U.S. Nuclear Regulatory Commission, Washington, D.C.

D-3 WCAP-8956, Revision 0, "Alabama Power Company, Joseph M. Farley Nuclear Plant Unit No. 2 Reactor Vessel Radiation Surveillance Program," August 1977.

D-4 ASTM E185-82, StandardPracticefor Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, American Society for Testing and Materials.

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