Westinghouse Non-Proprietary Class 3 · EXECUTIVE SUM M ARY ... Table 5-7 Instrumented Charpy Impact Test Results for the Farley Unit 2 Surveillance Weld Metal Irradiated to a Fluence

Westinghouse Non-Proprietary Class 3

WCAP-16918-NP April 200ORevision 1

Analysis of Capsule V from theSouthern Nuclear OperatingCompany Joseph M. FarleyUnit 2 Reactor VesselRadiation SurveillanceProgram

Westinghouse

3

WESTINGHOUSE NON-PROPRIETARY CLASS 3

WCAP-16918-NP

Revision 1

Analysis of Capsule V from the Southern Nuclear Operating Company Joseph M. FarleyUnit 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*, ManagerPrimary Component Asset Management

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

Westinghouse Electric Company LLCP.O. Box 355

Pittsburgh, PA 15230-0355

© 2008 Westinghouse Electric Company LLCAll 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 andbeyond and the removal time of Capsule V. All the conclusions remained the same as inRevision 0 except for the new service period for Pressure-Temperature Limit Curves.

WCAP- 16918-NPRevision 1

April 2008

iv

TABLE OF CONTENTS

LIST OF TABLES ........................................................................................................................................ v

LIST OF FIGURES .................................................................................................................................... vii

EXECUTIVE SUM M ARY .......................................................................................................................... ix

I SUM M 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 .................................................................................................................... 5-15.2 RESULTS ........................................................................................................................ 5-25.3 TENSILE TEST RESULTS ............................................................................................. 5-45.4 BEND BAR AND COMPACT TENSION SPECIMEN TESTS .................................... 5-5

6 RADIATION ANALYSIS AND NEUTRON DOSIM ETRY ....................................................... 6-16.1 INTRODUCTION ........................................................................................................... 6-16.2 DISCRETE ORDINATES ANALYSIS ........................................................................... 6-26.3 NEUTRON DOSIM ETRY .............................................................................................. 6-4

6.4 CALCULATIONAL UNCERTAINTIES ........................................................................ 6-5

7 SURVEILLANCE CAPSULE REM OVAL SCHEDULE ............................................................ 7-1

8 RE FERE NCES ............................................................................................................................. 8-1

APPENDIX A VALIDATION OF THE RADIATION TRANSPORT MODELS BASEDON NEUTRON DOSIMETRY MEASUREMENTS ................................................. A-i

APPENDIX B LOAD-TIME RECORDS FOR CHARPY SPECIMEN TESTS ............................... B-i

APPENDIX C

APPENDIX D

CHARPY V-NOTCH PLOTS FOR EACH CAPSULE USING SYMMETRIC

HYPERBOLIC TANGENT CURVE-FITTING METHOD ...................................... C-1

JOSEPH M. FARLEY UNIT 2 SURVEILLANCE PROGRAM CREDIBILITYE V A L U A T IO N ............................................................................................................... D -1


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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 SpecimensIrradiated 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 SpecimensIrradiated 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 PlateB7212-1 Specimens Irradiated to a Fluence of 8.73E+ 19 n/cm 2 (E> 1.0 MeV)(L ongitu dinal O rientation) ............................................................................................. 5-10

Table 5-6 Instrumented Charpy Impact Test Results for the Farley Unit 2 Intermediate Shell PlateB7212-1 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/cm2 (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 su le 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

V essel W all ..................................................................................................................... 6 -19


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Table 6-5 Relative Radial Distribution of Iron Atom Displacements (dpa) Within the ReactorV essel W all ..................................................................................................................... 6 -19

Table 6-6 Calculated Fast Neutron Exposure of Surveillance Capsules Withdrawn from FarleyU 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


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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 sim eters ................................................................................................................ 4 -5

Figure 5-1 Charpy V-Notch Impact Energy vs. Temperature for Farley Unit 2 Reactor VesselIntermediate Shell Plate B7212-1 Specimens (Longitudinal Orientation) .................... 5-17

Figure 5-2 Charpy V-Notch Lateral Expansion vs. Temperature for Farley Unit 2 ReactorVessel 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 VesselIntermediate Shell Plate B7212-1 Specimens (Longitudinal Orientation) .................... 5-19

Figure 5-4 Charpy V-Notch Impact Energy vs. Temperature for Farley Unit 2 Reactor VesselIntermediate Shell Plate B7212-1 Specimens (Transverse Orientation) ........................ 5-20

Figure 5-5 Charpy V-Notch Lateral Expansion vs. Temperature for Farley Unit 2 ReactorVessel 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 VesselIntermediate Shell Plate B7212-1 Specimens (Transverse Orientation) ........................ 5-22

Figure 5-7 Charpy V-Notch Impact Energy vs. Temperature for Farley Unit 2 Reactor VesselSurveillance W eld M etal Specim ens .............................................................................. 5-23

Figure 5-8 Charpy V-Notch Lateral Expansion vs. Temperature for Farley Unit 2 ReactorVessel Surveillance W eld M etal Specim ens .................................................................. 5-24

Figure 5-9 Charpy V-Notch Percent Shear vs. Temperature for Farley Unit 2 Reactor VesselSurveillance W eld M etal Specim ens .............................................................................. 5-25

Figure 5-10 Charpy V-Notch Impact Energy vs. Temperature for Farley Unit 2 Reactor VesselH eat-A ffected-Zone Specim ens ..................................................................................... 5-26

Figure 5-11 Charpy V-Notch Lateral Expansion vs. Temperature for Farley Unit 2 ReactorVessel H eat-A ffected-Zone Specim ens .......................................................................... 5-27

Figure 5-12 Charpy V-Notch Percent Shear vs. Temperature for Farley Unit 2 Reactor VesselH eat-A ffected-Zone Specim ens ..................................................................................... 5-28

Figure 5-13 Charpy Impact Specimen Fracture Surfaces for Farley Unit 2 Reactor VesselIntermediate Shell Plate B7212-1 Specimens (Longitudinal Orientation) .................... 5-29

Figure 5-14 Charpy Impact Specimen Fracture Surfaces for Farley Unit 2 Reactor VesselIntermediate Shell Plate B7212-1 Specimens (Transverse Orientation) ........................ 5-30

Figure 5-15 Charpy Impact Specimen Fracture Surfaces for Farley Unit 2 Reactor VesselSurveillance W eld M etal Specim ens .............................................................................. 5-31

Figure 5-16 Charpy Impact Specimen Fracture Surfaces for Farley Unit 2 Reactor VesselH eat-A ffected-Zone Specim ens ..................................................................................... 5-32

WCAP-16918-NPRevision 1

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viii

LIST OF FIGURES (cont.)

Figure 5-17

Figure 5-18

Figure 5-19

Figure 5-20

Figure 5-21

Figure 5-22

Figure 5-23

Figure 5-24

Figure 5-25

Figure 6-1 a

Figure 6-lb

Figure 6-2

Tensile Properties for Farley Unit 2 Reactor Vessel Intermediate Shell PlateB7212-1 Specim ens (Longitudinal Orientation) ............................................................ 5-33

Tensile Properties for Farley Unit 2 Reactor Vessel Intermediate Shell PlateB7212-1 Specim ens (Transverse Orientation) ............................................................... 5-34

Tensile Properties for Farley Unit 2 Reactor Vessel Surveillance Weld MetalS p ecim en s ...................................................................................................................... 5 -3 5

Fractured Tensile Specimens from Farley Unit 2 Reactor Vessel IntermediateShell Plate B7212-1 Specimens (Longitudinal Orientation) .......................................... 5-36

Fractured Tensile Specimens from Farley Unit 2 Reactor Vessel IntermediateShell Plate B7212-1 Specimens (Transverse Orientation) ............................................. 5-37

Fractured Tensile Specimens from Farley Unit 2 Reactor Vessel SurveillanceW eld M etal Specim ens .................................................................................................. 5-38

Engineering Stress-Strain Curves for the Farley Unit 2 Reactor VesselIntermediate Shell Plate B7212-1 Specimens (Longitudinal Orientation) TensileSpecim ens CL-4, CL-5, and CL-6 ................................................................................. 5-39

Engineering Stress-Strain Curves for the Farley Unit 2 Reactor VesselIntermediate Shell Plate B7212-1 Specimens (Transverse Orientation) TensileSpecim ens CT-4, C T-5*, and CT-6 ................................................................................ 5-40

Engineering Stress-Strain Curves for Farley Unit 2 Reactor Vessel SurveillanceWeld Metal Specimens CW4, CW5, and CW6 .............................................................. 5-41

Farley Unit 2 r,0 Reactor Geometry with a 150 Neutron Pad at the Core Midplane ..... 6-21

Farley Unit 2 r,0 Reactor Geometry with a 26' Neutron Pad at the Core Midplane ..... 6-21

Farley Unit 2 r,z Reactor Geometry with Neutron Pad .................................................. 6-22


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EXECUTIVE SUMMARY

The purpose of this report is to document the results of the testing of Surveillance Capsule V from theJoseph 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 CapsuleV 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 weldsurveillance 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 operationand are predicted to maintain an upper shelf energy greater than 50 ft-lb throughout the life of the

vessel (54 EFPY) as required by 1OCFR50, Appendix G.

5. The surveillance weld data was found to be not credible, while the surveillance plate data wasfound 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 33.8EFPY in WCAP-14689, Revision 4, must be reduced to account for the updated neutron fluenceprojections and vessel material chemistry factors calculated as part of the Surveillance Capsule Vanalysis. 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-notchdata was plotted using a symmetric hyperbolic tangent curve fitting program.

WCAP- 16918-NP April 2008Revision 1

1-1

1 SUMMARY OF RESULTS

The analysis of the reactor vessel materials contained in Surveillance Capsule V, the sixth and finalcapsule removed and tested from the Joseph M. Farley Unit 2 reactor pressure vessel, led to the followingconclusions:

Capsule V received an average, fast neutron fluence (E> 1.0 MeV) of 8.73E+19 n/cm 2 after21.82 EFPY of plant operation.

Irradiation of the reactor vessel intermediate shell plate B7212-1 Charpy specimens, oriented withthe longitudinal axis of the specimen parallel to the major working direction (longitudinalorientation), resulted in an irradiated 30 ft-lb transition temperature of 196.0°F and an irradiated50 ft-lb transition temperature of 240.1 F. This results in a 30 ft-lb transition temperatureincrease of 218.3'F and a 50 ft-lb transition temperature increase of 230. 1F for the longitudinalorientation specimens. See Table 5-9.

Irradiation of the reactor vessel intermediate shell plate B7212-1 Charpy specimens, oriented withthe longitudinal axis of the specimen perpendicular to the major working direction (transverseorientation), resulted in an irradiated 30 ft-lb transition temperature of 207.8°F and an irradiated50 ft-lb transition temperature of 234.37F. This results in a 30 ft-lb transition temperatureincrease of 215.3°F and a 50 ft-lb transition temperature increase of 200.7°F for the transverseorientation specimens. See Table 5-9.

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

Irradiation of the weld heat-affected-zone (HAZ) metal Charpy specimens resulted in anirradiated 30 ft-lb transition temperature of 26.2°F and an irradiated 50 ft-lb transitiontemperature of 52.4°F. This results in a 30 ft-lb transition temperature increase of 322.4°F and a50 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 (longitudinalorientation) resulted in an average energy decrease of 44 ft-lb after irradiation. This results in anirradiated 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 (transverseorientation) resulted in an average energy decrease of 26 ft-lb after irradiation. This results in anirradiated 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 energydecrease of 20 ft-lb after irradiation. This results in an irradiated average USE of 124 ft-lb for theweld 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 plateB7212-1 specimens contained inCapsule V (longitudinal and transverse orientations) areless than the Regulatory Guide 1.99, Revision 2E3, predictions.

- The measured 30 ft-lb shift in transition temperature value of the surveillance weld metalspecimens 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 forthe 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:

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

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

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 fluenceprojections 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 individualinstrumented Charpy specimen tests. Appendix C presents the individual Charpy V-notch plotsfor each surveillance capsule and the program input data, which were curve-fit using a symmetrichyperbolic 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 2008Revision 1

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2 INTRODUCTION

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

The surveillance program for the Farley Unit 2 Nuclear Plant reactor pressure vessel materials wasdesigned and recommended by the Westinghouse Electric Corporation. A description of the surveillanceprogram and the pre-irradiation mechanical properties of the reactor vessel materials are presented inWCAP-8956, "Alabama Power Company Joseph M. Farley Nuclear Plant Unit No. 2 Reactor VesselRadiation Surveillance Program''143. The surveillance program was planned to cover the 40-year designlife of the reactor pressure vessel and was based on ASTM E185-73, "Standard Recommended Practicefor Surveillance Tests for Nuclear Reactor Vessels"'51. Capsule V was removed from the reactor after21.82 EFPY of exposure and shipped to the remote metallographic facility (RMF) at the Westinghousescience 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 Vremoved from the Southern Nuclear Operating Company Farley Unit 2 reactor vessel and discusses theanalysis of the data.


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3 BACKGROUND

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

A method for ensuring the integrity of reactor pressure vessels has been presented in "Fracture ToughnessCriteria for Protection Against Failure," Appendix G to Section XI of the ASME Boiler and PressureVessel Code16

3. The method uses fracture mechanics concepts and is based on the reference nil-ductilitytransition temperature (RTNDT).

RTNDT is defined as the greater of either the drop weight nil-ductility transition temperature (NDTT perASTM E208[7') or the temperature 60'F less than the 50 ft-lb (and 35-mil lateral expansion) temperatureas determined from Charpy specimens oriented perpendicular (transverse) to the major working directionof the plate. The RTNDT of a given material is used to index that material to a reference stress intensityfactor curve (Kic curve) which appears in Appendix G to the ASME Code[63. The Klc curve is a lowerbound of static fracture toughness results obtained from several heats of pressure vessel steel. When agiven material is indexed to the K1c curve, allowable stress intensity factors can be obtained for thismaterial as a function of temperature. Allowable operating limits can then be determined using theseallowable stress intensity factors.

RTNDT and, in turn, the operating limits of nuclear power plants can be adjusted to account for the effectsof radiation on the reactor vessel material properties. The changes in mechanical properties of a givenreactor pressure vessel steel, due to irradiation, can be monitored by a reactor vessel surveillanceprogram, such as the Farley Unit 2 reactor vessel radiation surveillance program 4], in which asurveillance capsule is periodically removed from the operating nuclear reactor and the encapsulatedspecimens tested. The increase in the average Charpy V-notch 30 ft-lb temperature (ARTNDT) due toirradiation is added to the initial RTNDT, along with a margin (M) to cover uncertainties, to adjust theRTNDT (ART) for radiation embrittlement. This ART (RTNDT initial + M + ARTNDT) is used to index thematerial to the K1, curve and, in turn, to set operating limits for the nuclear power plant that take intoaccount the effects of irradiation on the reactor vessel materials.


4-1

4 DESCRIPTION OF PROGRAM

Six surveillance capsules for monitoring the effects of neutron exposure on the Farley Unit 2 reactorpressure vessel core region (beltline) materials were inserted in the reactor vessel prior to initial plantstart-up. The six capsules were positioned in the reactor vessel between the neutron pads and the vesselwall 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 plateB7212-1 (Heat #C7466-1) and manual metal arc weld metal identical to intermediate shell longitudinalweld seam 19-923B (Heat #BOLA). In addition, this capsule contained Charpy V-notch specimens fromthe weld heat-affected zone (HAZ) metal of intermediate shell plate B7212-l and pre-cracked bend barspecimens from intermediate shell plate B7212-1.

Test material obtained from intermediate shell plate B7212-1 (after the thermal heat treatment andforming of the plate) was taken at least one plate thickness from the quenched ends of the plate. All testspecimens were machined from the ¼4 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-zonemetal were machined from a stress-relieved weldment joining intermediate shell plate B7212-1 andintermediate 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 thelongitudinal orientation (longitudinal axis of the specimen parallel to the major rolling direction) andtransverse 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 longdimension of each Charpy specimen was perpendicular to the weld direction. The notch of the weldmetal Charpy specimens was machined such that the direction of crack propagation in the specimen wasin the welding direction.

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

Bend bar specimens from plate B7212-1 were machined with the longitudinal axis of specimens orientednormal to the rolling direction of the plate such that the simulated crack would propagate in the rollingdirection 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 andtransverse orientations. Compact tension test specimens from the weld metal were machinedperpendicular to the weld direction with the notch oriented in the direction of the weld. All specimenswere fatigue pre-cracked according to ASTM E3991'1.

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

WCAP-16918-NP April 2008Revision I

4-2

Capsule V contained dosimeter wires of pure copper, iron, nickel, and aluminum-0.15 weight percentcobalt (cadmium-shielded and unshielded). In addition, cadmium-shielded dosimeters of neptunium(Np237) and uranium (U238) 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 inPyrex tubes. These thermal monitors were used to define the maximum temperature attained by the testspecimens during irradiation. The composition of the two eutectic alloys and their melting points are asfollows:

2.5% Ag, 97.5% Pb

1.75% Ag, 0.75% Sn, 97.5% Pb

Melting Point: 579°F (304'C)Melting.Point: 590°F (310°C)

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


April 2008

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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 - -

N 2 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 hours Water-Quenched

B7212-1 Tempered: 1225 ± 25 4 hours Air-Cooled

Stress Relief: 1150 ± 25 18 hours Furnace Cooled to 600'F

Weldment 1150 ± 25 13 hours Furnace Cooled


April 2008

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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


4-5

LEGEND: CL - LOWER SHELL PLATE B7212-1 (LONGITUDINAL)CT - LOWER SHELL PLATE B7212-1 (TRANSVERSE) .-

CW- WELD METALCH - HEAT-AFFECTED-ZONE MATERIAL 579*F 1 Cd

MONITOR

Bend Tensile Compact Compact Charpy Charpy Charpy CompactBar

. CT CW8 CW7 CW6 CW5 C2 H( W6 C26 CW23 CH23 CL8 CL7

L i [[ CW28 ' CH28 [CW25 CH25 CW22 CH22

TOP OF VESSEL • CENTERNp

237

U2 38

Compact Charpy Charpy Dosimeter Tensile Charpy CharpyCW21 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 CT5CT-22 -CL-2-2 - T -9 -T CT16 CL19 CT4

Figure 4-2 Capsule V Diagram Showing the Location of Specimens, Thermal Monitors, and Dosimeters


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 specimenswas performed in the remote metallographic facility (RMF) at the Westinghouse Science and TechnologyCenter.

Upon receipt of the capsule at the laboratory, the capsule was opened per Procedure RMF 8804[003. Thespecimens and spacer blocks were carefully removed, inspected for identification number and checkedagainst 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 theother did not. Based on this examination, the maximum temperature to which the specimens wereexposed 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 ASTMSpecification E 185-821"] and Westinghouse Procedures RMF 8402[121 as detailed by WestinghouseProcedures RMF 8102[131 and RMF 8103[141.

The Charpy impact tests were performed per ASTM Specification E23-06 [1 51 and Procedure RMF 8103[ 41

on a Tinius-Olsen Model 74, 358J machine. The tup (striker) of the Charpy machine is instrumented withan 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 Charpyenergy (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 testconditions, a sharp drop in load indicative of fast fracture was observed. The load at which fast fracturewas initiated is identified as the fast fracture load (PF). If the fast load drop terminates well above zeroload, 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 theload-time record. The energy at maximum load is approximately equivalent to the energy required toinitiate a crack in the specimen. Therefore, the propagation energy for the crack (Ep) is the differencebetween 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 followingexpression[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 thespecimen measured parallel to the notch; W = height of the specimen, measured perpendicularly to thenotch; a = notch depth. The constant C is dependent on the notch flank angle ((P), notch root radius (p),


April 2008

5-2

and the type of loading (i.e., pure bending or three-point bending). In three-point bending, for a Charpyspecimen 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 0 YW (Eq. 5-2)B(W- a)2 1.21 B(W- a) 2

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

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 theyield 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 theCharpy 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 incompliance with ASTM E23-060l"' and A370-071"]I. The lateral expansion was measured using a dialgage 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) perASTM 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 gagelength was 1.00 inch. Elevated test temperatures were obtained with a three-zone electric resistancesplit-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 werecalculated using the original cross-sectional area. The final diameter was determined from post-fracturephotographs. The fracture area used to calculate the fracture stress (true stress at fracture) and percentreduction 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/cm2 (E> 1.0 MeV) in 21.82 EFPY of operation, are presented inTables 5-1 through 5-10 and are compared with unirradiated results shown in Figures 5-1 through 5-12.


April 2008

5-3

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

Irradiation of the reactor vessel intermediate shell plate B7212-1 Charpy specimens, oriented withthe longitudinal axis of the specimen parallel to the major working direction (longitudinalorientation), resulted in an irradiated 30 ft-lb transition temperature of 196.0'F and an irradiated50 ft-lb transition temperature of 240.1 PF. This results in a 30 ft-lb transition temperatureincrease of 218.3°F and a 50 ft-lb transition temperature increase of 230.1 F for the longitudinalorientation specimens. See Table 5-9.

Irradiation of the reactor vessel intermediate shell plate B7212-1 Charpy specimens, oriented withthe longitudinal axis of the specimen perpendicular to the major working direction (transverseorientation), resulted in an irradiated 30 ft-lb transition temperature of 207.8°F and an irradiated50 ft-lb transition temperature of 234.3°F. This results in a 30 ft-lb transition temperatureincrease 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-lbtransition temperature of 22.0°F and an irradiated 50 ft-lb transition temperature of 61.8°F. Thisresults in a 30 ft-lb transition temperature increase of 56.5°F and a 50 ft-lb transition temperatureincrease of 77.2°F. See Table 5-9.

Irradiation of the weld heat-affected-zone (HAZ) metal Charpy specimens resulted in anirradiated 30 ft-lb transition temperature of 26.2°F and an irradiated 50 ft-lb transitiontemperature 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 (longitudinalorientation) resulted in an average energy decrease of 44 ft-lb after irradiation. This results in anirradiated 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 (transverseorientation) resulted in an average energy decrease of 26 ft-lb after irradiation. This results in anirradiated 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 theweld metal specimens. See Table 5-9.

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


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 followingconclusions:

- The measured 30 ft-lb shift in transition temperature values of the intermediate shell plateB7212-1 specimens contained in Capsule V (longitudinal and transverse orientations) areless 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 1OCFR50, Appendix G

The service period of applicability for the Pressure-Temperature Limit Curves labeled for 33.8EFPY 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 Vanalysis. 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 appearancewith 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 surveillancecapsule and the program input data. The credibility evaluation of the Farley Unit 2 surveillance programis presented in Appendix D of this report. The evaluation concluded that the Farley Unit 2 surveillancedata 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> 1.0MeV) 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 ksiincrease in the ultimate tensile strength when compared to unirradiated dataE4 ]. See Figure 5-17.


April 2008

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 ultimatetensile 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 thatirradiation to 8.73E+19 n/cm2 (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. Theengineering 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 and1/2T Compact Tension Specimens were not tested.


April 2008

5-6

Table 5-1 Charpy V-notch Data for the Farley Unit 2 Intermediate Shell Plate B7212-1 SpecimensIrradiated to a Fluence of 8.73E+19 n/cm2 (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


April 2008

5-7

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


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


April 2008

5-8

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


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 100CW18 260 127 125 170 84 2.13 100

Note:1. Data not available.


April 2008

5-9

Table 5-4 Charpy V-notch Data for the Farley Unit 2 HAZ Material Irradiated to a Fluence of8.73E+19 n/cm 2 (E> 1.0 MeV)


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-NPRevision I

April 2008

5-10

Table 5-5 Instrumented Charpy Impact Test Results for the Farley Unit 2 Intermediate Shell Plate B7212-1 Specimens Irradiated to a Fluenceof 8.73E+19 n/cm2 (E> 1.0 MeV) (Longitudinal Orientation)

Normalized Energies GeneralCharpy (ft-lb/in2) Yield Time to

Test Energy Load Yield Max. Time to Fract. Arrest Yield FlowSample 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


April 2008

5-11

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

Normalized Energies GeneralCharpy (ft-lb/in2 ) Yield Time to

Test Energy Load Yield Max. Time to Fract. Arrest Yield FlowSample Temp. ED Total At PM Prop. PGY tGV Load, PM Load, Load, Stress, Stress

No. (0F) (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.


April 2008

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 GeneralCharpy (ft-lb/in2) Yield Time to

Test Energy Load Yield Max. Time to Fract. Arrest Yield FlowSample 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.


April 2008

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 GeneralCharpy (ft-lb/in 2) Yield Time to

Test Energy Load Yield Max. Time to Fract. Arrest Yield FlowSample 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 (1) (1) (1) (1) (1) (1) (a b (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.


April 2008

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 VesselSurveillance 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

IntermediateShell Plate -22.3 196.0 218.3 1.0 224.4 223.4 10.0 240.1 230.1 130 86 -44B7212-1(Longitudinal)

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

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


April 2008

5-15

Table 5-10 Comparison of the Farley Unit 2 Surveillance Material 30 ft-lb Transition TemperatureShifts and Upper Shelf Energy Decreases with Regulatory Guide 1.99, Revision 2,Predictions

30 ft-lb Transition Upper Shelf Energy

Fluence Temperature Shift Decrease

(x 10' 9 n/cm 2, Predicted Measured Predicted MeasuredMaterial Capsule E > 1.0 MeV) (OF)() (OF)(

2) (%)1) (%)(3)

Intermediate Shell U 0.605 128.0 105.5 26 27Plate 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 27Plate 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 8Program

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 - -- 30Zone 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 .


April 2008

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 ReductionSample Temperature Strength Strength Load Stress Strength Elongation Elongation in AreaNumber 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

CT5t 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.


April 2008

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

CurIve1

234567

300-

250

40 200-

0U.

L 150

z

100

50

0 -

-300.0

0 1

Pla itFarley 2Farley 2Farley 2Farley 2Farley 2Farley 2Farley 2

CapsuleUNIRR

UwxzYV

MaterialSA533BISA533BISA533B ISA533B1ISA533B ISA533B!ISA533BI

Or!.LTLTLTLTLTLTLT

Heat #B7212-1B7212-1B7212-1B7212-1B7212-1B7212-1B7212-1

-200.0 -100.0

0 2

0.0 100.0 200.0 300.0 400.0 500.0 600.0

Temperature in Deg FA 4 v 5 0 6 m 7

Results

Curve,

2

4

5

6

7

Fluence LSE USE d-USE T @30 d.T @Y0

2.2 130.0 .0 -22.3 .0

2. 2 94. 4 -35.6 83. 2 105.5

2.2 102.0 -28.0 145.4 167.7

2. 2 96.3 - 33.7 142. 5 164.8

2. 2 93.8 -36.2 177. 8 200. 1

2.2 83.0 -47.0 191.9 214.2

2.2 86.0 -44.0 196.0 218.3

T @50

10.0

141.0

185.4

186.3

208. 8

222. 6

240. 1

d-T @50

.0

131. 0

175.4

176. 3

198. 8

212.6

230. I

Figure 5-1 Charpy V-Notch Impact Energy vs. Temperature for Farley Unit 2 Reactor VesselIntermediate Shell Plate B7212-1 Specimens (Longitudinal Orientation)


April 2008

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

234567

PlantFarley 2Farley 2Farley 2Farley 2Farley 2Farley 2Farley 2

CapsuleUNIRR

UwXzYV

M~aterialSA533B ISA533B ISA533B ISA533B ISA533BISA533B ISA533B I

Ori.LTLTLTLTLTLTLT

Heat #B7212-1B7212-1B7212-1B7212-1B7212-1B7212-1B7212-1

200

150

EC

0 500

04--300.0

0 1

0.0 300.0 600.0

Temperature in Deg F3 A 4 v 5 0 6 m 702

Curv'e1

23

4

5

6

7

Pluence LSE

.0

.0

.0

.0

.0

.0

.0

USE90. 8

85. 2

85. 6

70.4

66. 8

66. 1

75. 4

d-USE

.0

-5.6

-5. 1

-20.4

-24.0

-24. 7

-15.4

Results

T @35

1.0

122.4

167. 9

182. 7

212. I

217. 1

224. 4

d-T @35

.0

121.4

166.9

181.7

211. 1

216. 1

223. 4

Figure 5-2 Charpy V-Notch Lateral Expansion vs. Temperature for Farley Unit 2 Reactor VesselIntermediate Shell Plate B7212-1 Specimens (Longitudinal Orientation)


April 2008

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

1234567

PlantFarley 2Farley 2Farley 2Farley 2Faney 2Farley 2Farley 2

CaipsuleUNTRR

UwxzyV

M~aterialSA533B ISA533B ISA533B ISA533B ISA533B ISA533B ISA533B I

Ori.LTLTLTLTLTLTLT

Heat #B7212-1B7212-1B7212-1B7212-1B7212-1B7212-1B7212-1

125

100

I-

U,

it

75

50

25j

0--300.0

0 1

-200.0 -100.0 0.0 100.0 200.0 300.0 400.0Temperature in Deg F

02 03 A 4 v 5 0 6

500.0 600.0

m 7

Results

Curs-e1

2

4

5

6

Fluence LSE

.0

.0

.0

.0

.0

.0

USE100.0

100.0

100.0

100. 0

100. 0

100. 0

d-USE

.0

.0

.0

.0

.0

.0

T @50 d-T @50

39. 3

150.4

188.4

198.5

209.0

211.0

.0

149. I

159. 2

169.7

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 VesselIntermediate Shell Plate B7212-1 Specimens (Longitudinal Orientation)


April 2008

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

234567

300

250

4 200-

0ILp150

100

50

0-300.0

0 1

PlanltFarley 2Farley 2Farley 2Farley 2Farley 2Farley 2Farley 2

CapsuleUNIRR

UwxzYV

MaterialSA533B !SA533B ISA533BISA533BlSA533BISA533BISA533BI

Ori.TLTLTLTLTLTLTL

Heat #B7212-1B7212-1B7212-1B7212-1B7212-1B7212-1B7212-1

-200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0

Temperature in Deg F02 3 A 4 v 5 6 ,7

Results

Curve

2

3

4

5

6

7

Fluence LSE

2. 2

2. 2

2. 2

2. 2

2. 2

2. 2

2. 2

USE69. 0

69. 0

69. 0

69. 0

69.0

69. 0

69.0

d-USE T @30 d-T @30 T @50

.0 -9.0 .0 28. 1

.0 116.6 125.6 182.0

.0 159.9 168.9 219. 1

.0 192.6 201.6 221.8

.0 188.3 197.3 231.2

.0 229. I 238. I 310.6

.0 207. 8 216. 8 234.3

d-T @50

.0

153. 9

191.0

193. 7

203. I

282. 5

206. 2

Figure 5-4 Charpy V-Notch Impact Energy vs. Temperature for Farley Unit 2 Reactor VesselIntermediate Shell Plate B7212-1 Specimens (Transverse Orientation)


April 2008

5-21


Data Set(s) Plotted

Ciirve1

34567

Plant.Farley 2Farley 2Farley 2Farlev 2Farle•, 2Farlev 2Farle 2

CapsuleUNIRR

UwXzYV

SMatetiaSA5i33B ISA533BISA533B ISA533B ISA533B ISA533B I

Ori.TLTLTLTLTLTLTL

Heat #B7212-1B7212-IB7212-1B7212-1B7212-1B7212-1B7212-1

200

150

EC.2

5100

50

04--300.0

0 1

0.0 300.0

Temperature in Deg F3 "4 v 5

600.0

m 70 2

Cuirve1

2

3

4

5

6

7

Fluenev LSE

.0

.0

.0

.0

.0

.0

.0

USE

72. 7

68.3

69. 1

62. 9

53. 4

44. A

56. 3

d-USE

.0

-4.4

-3.6

-9.8

- 19. 3

-27.9

- 16.4

Results

T @3526. 7

147.0

183. 3

214. 7

226. 0

266. 4

215. 9

d-T @35

.0

120. 3

156.6

188.0

199.3

239.7

189.2

Figure 5-5 Charpy V-Notch Lateral Expansion vs. Temperature for Farley Unit 2 Reactor VesselIntermediate Shell Plate B7212-1 Specimens (Transverse Orientation)


April 2008

5-22


Data Set(s) Plotted

Curve

34567

Plantarley 2arley 2

Farley 2Farley 2Farlev 2Farle6 2Far14 2

CapsuleUNIRR

UwxzYV

MaterialSA533BISA533BISA533BISA533B1ISA533BISA533B 1SA533BI

Ori.TLTLTLTLTLTLTL

Heat #B7212-1B7212-1B7212-1B7212-1B7212-1B7212- 1B7212- 1

125

100

CL

75

50

25

0--300.0

0 1

-200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0

Temperature in Deg F02 3 A 4 7 5 0 6 "7

Results

Curve1

2'3

4

5

6

7

Fluence LSE USE

.0 100.0

.0 100.0

.0 100.0

d-USE T @50 d-T @5(0

.0 49.7 .0

.0 159.8 110. 1

.0 199.8 150. 1

.0

.0

.0

.0

100.0

tOo. 0

too. 0

100. 0

.0

.0

.0

.0

203.0

209.7

234. I

218. 6

153. 3

160.0

184.4

168. 9

Figure 5-6 Charpy V-Notch Percent Shear vs. Temperature for Farley Unit 2 Reactor VesselIntermediate Shell Plate B7212-1 Specimens (Transverse Orientation)


April 2008

5-23

Curve1234567

CVGRAPH 5.3

Plant'arey 2arey 2

Farley 2Farley 2Farley 2Fancy 2Farley 2

SURVEILLANCE WED) METAL

Hyperbolic Tangent Curve Printed on 02/06/2008 04:58 PMData Set(s) Plotted

Capsuule M1IateriaI Ori. Heat #UNIRR SMAW NA BOLA

U SMAW NA BOLAW SMAW NA BOLAX SMAW NA BOLAZ SMAW NA BOLAY SMAW NA BOLAV SMAW NA BOLA

300

250

4 200"

0U.

F 150

ul

z> 100

50

0

-300.0

0 1

-200.0 -100.0 0.0 100.0 200.0 300.0

Temperature in Deg F02 03 A 4 V 5

400.0 500.0 600.0

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 VesselSurveillance Weld Metal Specimens


April 2008

5-24

CVGRAPH 5.3

SURVIILLA NCE WELl) METAL


Curve

234567

PlantFarley 2

arley 2Farley 2Farley 2Farley 2Farley 2Farley 2

CZapsuleUNIRR

UWXzYV

MaterialSMAWSMAWSMAWSMAWSMAWSMAWSMAW

OH.NANANANANANANA

Heat #BOLABOLABOLABOLABOLABOLABOLA

200

150

EC

3.-Ul

10

50

04---300.0

0 1

0.0 300.0

Temperature in Deg F3 A4 v 5

600.0

0 2 0 6 . 7

Curve1

2

3

4

5

6

7

Fluence LSE.0

.0

.0

.0

.0

.0

.0

USE

92. 2

91. 5

85. I

84. I

79. 8

83. 4

86. 4

d-USE.0

-. 7

-7.1

-8.1

-12.4

-8.8

-5.8

Results

T @35

-23. 5

-43. 9

- 18.4

-30.0

-1.4

47. 9

41.3

d-T @35

.0

-20.4

5. 1

-6.5

22. I

71.4

64. 8

Figure 5-8 Charpy V-Notch Lateral Expansion vs. Temperature for Farley Unit 2 Reactor VesselSurveillance Weld Metal Specimens


April 2008

5-25

Curive1234567

CVGRAPH 5.3

NlanlftFarley 2Farlev 2Farley 2Farley 2Farley 2Farley 2Farley 2

SURVEILLANCE WELD METAL


Capsole Material Ori. Heat #UNIRR SMAW NA BOLA

U SMAW NA BOLAW SMAW NA BOLAX SMAW NA BOLAZ SMAW NA BOLAY SMAW NA BOLAV SMAW NA BOLA

125

100

1..'U

U,

a)

a)0.

75

50

'0

Y a

25

00

-300.0

0 1

-200.0 -100.0 0.10 100.0 200.0 300.0Temperature in Deg F

A 4 v 5

400.0 500.0

0 6

600.0

0 2 0 3 a 7

Cure1

2

3

4

5

6

7

Fluence LSE

.0

.0

.0

.0

.0

.0

.0

USE100. 0

100. 0

100. 0

100.0

100. 0

100. 0

100. 0

d-USE

.0

.0

.0

.0

.0

.0

.0

Results

T @50-15. 1

1.9

-8.9

15.2

53. 1

61. 1

d-T @50

.0

4.0

17.0

6. 2

30. 3

68. 2

76. 2

Figure 5-9 Charpy V-Notch Percent Shear vs. Temperature for Farley Unit 2 Reactor VesselSurveillance Weld Metal Specimens


April 2008

5-26

CVGRAPH 5.3

HEAT AFFECTEI) ZONE

Hyperbolic Tangent Curve Printed oil 02/06/2008 05:25 PMData Set(s) Plotted

Ciiive

234567

Plant Caplsule MaterialFarley 2 UNIRR SA533BIFarley 2 U SA533B IFarley 2 W SA533B 1Farlev 2 X SA533B1Farley 2 Z SA533B 1Farley 2 Y SA533B1Farley 2 V SA533Bl!

Orl.NANANANANANANA

Heat #B7212-1B7212- 1B7212-1B7212-IB72 12-1B7212-IB7212-1

300

250

4 200

0U-

150

IL,z> 1000

50-

0-300.0

0 1

-200.0 -100.0 0.0 100.0 200.0 300.0

Temperature in Deg FS2 03 & 4 v 5

400.0 500.0 600.0

0 6 w 7

Results

Curve1

2

3

4

5

6

7

Fluence LSE USE d-USE T @30 d-T @X) T @50

2. 2 158.0 .0 -296. 2 .0 -205.3

2.2 111.0 -47.0 -76.4 219.8 -44.3

2.2 126.0 -32.0 -27.4 268.8 -16.1

2. 2 128.0 -30.0 -65. 7 230.5 -39.9

2.2 126.0 -32.0 -32.4 263.8 -2.9

2.2 102.0 -56.0 -26.6 269.6 -3.8

2.2 118.0 -40.0 26.2 322.4 52.4

d-T @50

.0

161.0

189. 2

165. 4

202. 4

201. 5

257. 7

Figure 5-10 Charpy V-Notch Impact Energy vs. Temperature for Farley Unit 2 Reactor VesselHeat-Affected-Zone Specimens


April 2008

5-27

CVGRAPH 5.3

HEAT AFFECTED) ZONE


Ciiiwe1234567

PlantFarlev 2Farley 2Farley 2Farley 2Farley 2Farley 2Farley 2

CapsuleUNIRR

UwXzYV

MaterialSA533B ISA533BISA533B ISA533B 1SA533B ISA533BISA533BI

Ori.NANANANANANANA

Heat #B7212-1B7212-1B7212-IB7212-1B7212-1B7212-1B7212-1

200

150

a 100

50

0 ý--300.0

0 1

0.0 300.0 600.0

Temperature in Deg F3 A4 v 5 0 6 m 7o 2

Results

Curve

1

23

4

5

6

7

Fluence LSE

.0

.0

.0

.0

.0

.0

.0

U&E

90. 3

88. 1

92. 8

85. 2

86. 1

82. 5

90. 5

d-USE

.0

-1.9

2.5

-5.0

-4.2

-7.8

.2

T @35 d-T @35

-183.6

-58.8

-20. 6

- 37. 0

5. 1

-5. 5

49. 7

.0

124.8

163.0

146.6

188.7

178. I

233. 3

Figure 5-11 Charpy V-Notch Lateral Expansion vs. Temperature for Farley Unit 2 Reactor VesselHeat-Affected-Zone Specimens


April 2008

5-28

HEAT AFFEcTED ZONE

CVGRAPH 5.3 Hyperbolic Tangent Curve Primted on 02/06/2008 05:33 PMData Set(s) Plotted

CurIve1234567

PlantFarley 2

anrev 2Farle5, 2Farney 2Farley 2Farley 2Farley 2

CaipsuleUNIRR

UwxzYV

MiaterialSA533B ISA533B ISA533B ISA533B ISA533BISA533B13SA533B13

Ori.NANANANANANANA

Heat #B7212-IB7212-1B7212-1B7212-1B7212-1B7212-1B7212-I

125

100

I-

a)U,

a)20a.

75

50

25-

0--300.0

0 1

-200.0 -100.0 0.0 100.0 200.0 300.0 400.0

Temperature in Deg F3 2 03 A 4 V 5 6

500.0 600.0

a 7

Results

Curve1

23

4

5

6

7

Fluenme LSE

.0

.0

.0

.0

.0

USE

100.0

100.0

100. 0

100. 0

100. 0

d-USE T @50.0 -116.0

.0 -28.0

.0 -11.3

.0 -14.8

.0 16.2

.0 4.8

.0 56.4

d-T @50

.0

88.0

104. 7

101. 2

132. 2

120. 8

172.4

.0 100.0

.0 100.0

Figure 5-12 Charpy V-Notch Percent Shear vs. Temperature for Farley Unit 2 Reactor VesselHeat-Affected-Zone Specimens


April 2008

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

Figure 5-13

CL26, 315T CL21, 340°F CL20, 370°F CL29, 380°F

Charpy Impact Specimen Fracture Surfaces for Farley Unit 2 Reactor VesselIntermediate Shell Plate B7212-1 Specimens (Longitudinal Orientation)


April 2008

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

Figure 5-14

CT28, 345°F CT30, 375°F CT21, 400°F CT26, 410°F

Charpy Impact Specimen Fracture Surfaces for Farley Unit 2 Reactor VesselIntermediate Shell Plate B7212-1 Specimens (Transverse Orientation)


April 2008

5-31

CW28, -25-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

CW16,2300 F CW23,2500 F CW18, 2600 F

Charpy Impact Specimen Fracture Surfaces for Farley Unit 2 Reactor VesselSurveillance Weld Metal Specimens

CW19,185°F

Figure 5-15


April 2008

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 VesselHeat-Affected-Zone Specimens


April 2008

5-33

din

vn

In

120.0

100.0

80.0

60.0

40.0

20.0

0.0

Ultimate Tensile Strength

~0.2% Yield Strength

0 100 200 300

Temperature (F)

400 500 600

Legend: Aand e and u are unirradiatedA and o and o are irradiated to 8.73E+19 n/cm 2 (E > 1.0 MeV)

80.0

70.0

60.0

50.0

= 40.0U

30.0

20.0

10.0

0.0

Reduction in Area

Total Elongation

U E

Uniform Eogto

0 100 200 300

Temperature (F)

400 500 600

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


April 2008

5-34

U)

Cn

120.0

100.0

80.0

60.0

40.0

20.0

0.0


0.2% Yield Strength

0 100 200 300

Temperature (F)

400 500 600

U

0

70.0

60.0

50.0

40.0

30.0

20.0

10.0

0.0

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

~Reduction in Area

Total Elongation

-0-Uo la

Uniform Elongation

0 100 200 300

Temperature (F)

400 500 600

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


April 2008

5-35

in

inin

100.0

90.0

80.0

70.0

60.0

50.0

40.0

30.0

20.0

10.0

0.0


0% eSn

0.2% Yield Strength

0 100 200 300

Temperature (F)

400 500 600

Legend: A and e and u are unirradiatedA 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

40.0

30.0Total Elongation

20.0

0 0

10.0 - pUniform Elongation

0.0

2

0 100 200 300

Temperature (F)

400 500 600

Figure 5-19 Tensile Properties for Farley Unit 2 Reactor Vessel Surveillance Weld MetalSpecimens


April 2008

5-36

Specimen CL4- Tested at 230'F



Figure 5-20 Fractured Tensile Specimens from Farley Unit 2 Reactor Vessel Intermediate ShellPlate B7212-1 Specimens (Longitudinal Orientation)


5-37

Specimen CT4- Tested at 240'F



Figure 5-21 Fractured Tensile Specimens from Farley Unit 2 Reactor Vessel Intermediate ShellPlate B7212-1 Specimens (Transverse Orientation)


April 2008

5-38

Specimen CW4- Tested at 80'F



Figure 5-22 Fractured Tensile Specimens from Farley Unit 2 Reactor Vessel Surveillance WeldMetal Specimens


April 2008

5-39

FARLEY 2CAPSULE V

120

100

- 80

(6U) 60

40

20

CL4

230°F

0 0.05 0.1 0.15

STRAIN, IN/IN

0.2 0.25 0.3

FARLEY 2CAPSULE V

120

100

- 80

W 60U)

40

20

CL5290=F

0 0.05 0.1 0.15

STRAIN, NIN

0.2 0.25 0.3

FARLEY 2CAPSULE V

120

100

- 80

U)n 60

40

20

CL6550°F

0 0.05 0.1 0.15

STRAIN, IN/IN

0.2 0.25 0.3

Figure 5-23 Engineering Stress-Strain Curves for the Farley Unit 2 Reactor Vessel IntermediateShell Plate B7212-1 Specimens (Longitudinal Orientation) Tensile Specimens CL-4,CL-5 and CL-6


April 2008

5-40

FARLEY 2CAPSULE V

120

100

- 80

) 60

40

20

CT4240°F

0.05 0.1 0.15

STRAIN, IN/IN

0.2 0.25 0.3

FARLEY 2CAPSULE V

120

100-

880

60

40

20

CTS320*F

0

0 0.05 0.1 0.15

STRAIN, IN/IN

FARLEY 2CAPSULE V

0.2 0.25 0.3

120

s080

60

40

20

CT6550=F

0.05 0.1 0.15STRAIN. INIIN

0.2 0.25 0.3

Figure 5-24 Engineering Stress-Strain Curves for the Farley Unit 2 Reactor Vessel IntermediateShell 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.


April 2008

5-41

FARLEY 2CAPSULE V

100

90

80

70

. 60

50

40

30

20

10

0

F7CWý4BOT

a 0.05 0.1 0.15

STRAIN, IN/IN

FARLEY 2

CAPSULE V

0.2 0.25 0.3

100

90

00

70

60

50

40

30

20

10

CW5200*F

0 0.05 0.1 0.15

STRAIN, NIN

FARLEY 2

CAPSULE V

0.2 0.25 0.3

u•

o:

100

90

B0

70

60

50

40

30

20

10

0 0.05 0.1 0.15 0.2 0.25

STRAIN, IN/IN

03

Figure 5-25 Engineering Stress-Strain Curves for Farley Unit 2 Reactor Vessel Surveillance WeldMetal Specimens CW4, CW5, and CW6


April 2008

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 todetermine 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 ironatom displacements (dpa) were established on a plant and fuel cycle specific basis. An evaluation of themost recent dosimetry sensor set from Capsule V, withdrawn at the end of the eighteenth plant operatingcycle, 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 thisreport. Comparisons of the results from these dosimetry evaluations with the analytical predictionsserved to validate the plant specific neutron transport calculations. These validated calculationssubsequently formed the basis for providing projections of the neutron exposure of the reactor pressurevessel 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 theneutron exposure of the material has traditionally been accepted for the development of damage trendcurves as well as for the implementation of trend curve data to assess the condition of the vessel. Inrecent years, however, it has been suggested that an exposure model that accounts for differences inneutron energy spectra between surveillance capsule locations and positions within the vessel wall couldlead to an improvement in the uncertainties associated with damage trend curves and improved accuracyin the evaluation of damage gradients through the reactor vessel wall.

Because of this potential shift away from a threshold fluence toward an energy dependent damagefunction for data correlation, ASTM Standard Practice E853, "Analysis and Interpretation of Light-WaterReactor Surveillance Results,"[20 1 recommends reporting displacements per iron atom (dpa) along withfluence (E > 1.0 MeV) to provide a database for future reference. The energy dependent dpa function tobe used for this evaluation is specified in ASTM Standard Practice E693, "Characterizing NeutronExposures in Iron and Low Alloy Steels in Terms of Displacements per Atom." 2 11 The application of thedpa parameter to the assessment of embrittlement gradients through the thickness of the reactor vesselwall has already been promulgated in Revision 2 to Regulatory Guide 1.99, "Radiation Embrittlement ofReactor Vessel Materials."'1'

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


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. Sixirradiation capsules attached to the neutron pad are included in the reactor design that constitutes thereactor 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 stainlesssteel specimen containers are 1.182-inch by 1-inch and are approximately 56 inches in height. Thecontainers are positioned axially such that the test specimens are centered on the core midplane, thusspanning 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 theneutron energy spectrum in the water annulus between the neutron pads and the reactor vessel. In orderto determine the neutron environment at the test specimen location, the capsules themselves must beincluded in the analytical model.

In performing the fast neutron exposure evaluations for the Farley Unit 2 reactor vessel and surveillancecapsules, a series of fuel cycle specific forward transport calculations were carried out using the followingthree-dimensional flux synthesis technique:

0(r, 0, z) = 4)(r, 0) * 4(r, z)¢(r)

where 0(r,0,z) is the synthesized three-dimensional neutron flux distribution, 0(rO) is the transportsolution in r,0 geometry, 0(r,z) is the two-dimensional solution for a cylindrical reactor model using theactual axial core power distribution, and 0(r) is the one-dimensional solution for a cylindrical reactormodel using the same source per unit height as that used in the r,0 two-dimensional calculation. Thissynthesis 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 aredepicted in Figure 6-1. The first model contained the extended neutron pad (26' span) including thesurveillance capsules, while the second contained the shortened neutron pad (150 span) with nosurveillance capsules. The former model was used to perform surveillance capsule dosimetry evaluationsand subsequent comparisons with calculated results, while the latter model was used to generate themaximum fluence at the pressure vessel wall. In developing these analytical models, nominal designdimensions were employed for the various structural components. Likewise, water temperatures, andhence, coolant densities in the reactor core and downcomer regions of the reactor were taken to berepresentative of full power operating conditions. The coolant densities were treated on a fuel cyclespecific basis. The reactor core itself was treated as a homogeneous mixture of fuel, cladding, water, andmiscellaneous core structures such as fuel assembly grids, guide tubes, et cetera. The geometric meshdescription of the rO reactor models consisted of 185 radial by 92 azimuthal intervals. Mesh sizes werechosen to assure that proper convergence of the inner iterations was achieved on a point-wise basis. Thepoint-wise inner iteration flux convergence criterion utilized in the r,O calculations was set at a value of0.001.


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 inthe 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 avolume equal to that of the active core zone. The stainless steel former plates located between the corebaffle 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 ther,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 ther,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 meshintervals 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 wasused 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 cycleaveraged neutron flux, which when multiplied by the appropriate fuel cycle length, generated theincremental 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 plutoniumisotopes 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 S16 order of angular quadrature. Energy and space

dependent core power distributions, as well as system operating temperatures, were treated on a fuel cyclespecific 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 theactive 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 maximumneutron 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


April 2008

6-4

the vessel inner radius were taken at the clad/base metal interface, and thus, represent the maximumcalculated 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. Thesedata tabulations include both plant and fuel cycle specific calculated neutron exposures at the end of the18th operating fuel cycle as well as future projections to 25, 32, 40, 48, 54, and 60 EFPY The projectionswere based on the assumption that the core power distributions and associated plant operatingcharacteristics from Cycle 19 were representative of future plant operation. The future projections arealso 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 inTables 6-4 and 6-5, respectively. The data, based on the cumulative integrated exposures from Cycles 1through 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 atthe 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 2reactor are provided in Table 6-6. These assigned neutron exposure levels are based on the plant and fuelcycle 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 capsulelead factor is defined as the ratio of the calculated fluence (E > 1.0 MeV) at the geometric center of thesurveillance capsule to the corresponding maximum calculated fluence at the pressure vessel clad/basemetal 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 periodcorresponding 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 adirect comparison against the measured sensor reaction rates and via a least squares evaluation performedfor each of the capsule dosimetry sets. However, since the neutron dosimetry measurement data merelyserves to validate the calculated results, only the direct comparison of measured-to-calculated results forthe most recent surveillance capsule removed from service is provided in this section of the report. Forcompleteness, the assessment of all measured dosimetry removed to date, based on both direct and leastsquares evaluation comparisons, is documented in Appendix A.

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


April 2008

6-5

Reaction Rates (rps/atom)

Reaction Measured Calculated M/C Ratio

63Cu(nQ) 60Co 6.04E- 17 5.96E- 17 1.0154Fe(n,p)54Mn 6.02E- 15 6.94E- 15 0.8758Ni(n,p)58Co 8.51 E- 15 9.82E- 15 0.87

238U(n,p)137Cs (Cd) 3.56E-14 3.89E-14 0.91237Np(n,f) 137Cs (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 from0.87 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 ofcomparisons given in Appendix A for all measured dosimetry removed to date from the Farley Unit 2reactor. 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 capsuleand reactor pressure vessel is based on the recommended approach provided in RegulatoryGuide 1.190.[221 In particular, the qualification of the methodology was carried out in the following fourstages:

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 theH. B. Robinson power reactor benchmark experiment.

3. An analytical sensitivity study addressing the uncertainty components resulting from importantinput parameters applicable to the plant specific transport calculations used in the neutronexposure assessments.

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

The first phase of the methods qualification (PCA comparisons) addressed the adequacy of basic transportcalculation and dosimetry evaluation techniques and associated cross-sections. This phase, however, didnot test the accuracy of commercial core neutron source calculations nor did it address uncertainties inoperational or geometric variables that impact power reactor calculations. The second phase of thequalification (H. B. Robinson comparisons) addressed uncertainties in these additional areas that are

WCAP-16918-NPRevision I

April 2008

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 ofknowledge 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 estimatesassociated 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.


April 2008

6-7

Table 6-1 Calculated Neutron Exposure Rates and Integrated Exposures at the SurveillanceCapsule Center

Neutrons (E > 1.0 MeV)

Cumulative Cumulative Neutron Flux (E > 1.0 MeV)Cycle Irradiation Irradiation (n/cmn-s)

Length Time TimeCycle (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+l 1 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


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)


1

2

3

4

5

6

7

8

9

10

11

12

13

14

15

16

17

18

Future

Future

Future

Future

Future

Future

3.508E+07

2.434E+07

3.436E+07

3.111E+07

3.954E+07

3.837E+07

4.050E+07

3.505E+07

3.992E+07

3.792E+07

4.118E+07

3.982E+07

4.086E+07

3.708E+07

4.192E+07

4.276E+07

4.646E+07

4.219E+07

1.005E+08

2.209E+08

2.525E+08

2.525E+08

1.893E+08

1.893E+08

3.508E+07

5.942E+07

9.378E+07

1.249E+08

1.644E+08

2.028E+08

2.433E+08

2.784E+08

3.183E+08

3.562E+08

3.974E+08

4.372E+08

4.781E+08

5.15 1E+08

5.571E+08

5.998E+08

6.463E+08

6.884E+08

7.889E+08

1.010E+09

1.262E+09

1.515E+09

1.704E+09

1.893E+09

1.11

1.88

2.97

3.96

5.21

6.43

7.71

8.82

10.09

11.29

12.59

13.85

15.15

16.32

17.65

19.01

20.48

21.82

25.00

32.00

40.00

48.00

54.00

60.00

6.05E+18

1.04E+ 19

1.59E+19

2.01E+19

2.52E+19

2.98E+19

3.48E+19

3.90E+19

4.33E+19

4.80E+19

5.23E+19

5.65E+19

6.16E+ 19

6.65E+19

7.18E+19

7.7 1E+19

8.26E+19

8.73E+19

9.9 1E+ 19

1.25E+20

1.55E+20

1.84E+20

2.07E+20

2.29E+20

5.23E+18

9.OOE+18

1.37E+19

1.73E+19

2.17E+ 19

2.57E+19

3.02E+19

3.39E+19

3.77E+19

4.18E+19

4.55E+19

4.92E+19

5.37E+19

5.81E+19

6.29E+19

6.79E+19

7.28E+19

7.70E+19

8.73E+19

1.1OE+20

1.36E+20

1.62E+20

1.81E+20

2.OOE+20


April 2008

6-9


Iron Atom Displacements

Cumulative Cumulative Displacement RateCycle Irradiation Irradiation (dpa/s)


1

2

3

4

5

6

7

8

9

10

11

12

13

14

15

16

17

18

Future

Future

Future

Future

Future

Future

3.508E+07

2.434E+07

3.436E+07

3.11 IE+07

3.954E+07

3.837E+07

4.050E+07

3.505E+07

3.992E+07

3.792E+07

4.118E+07

3.982E+07

4.086E+07

3.708E+07

4.192E+07

4.276E+07

4.646E+07

4.219E+07

1.005E+08

2.209E+08

2.525E+08

2.525E+08

1.893E+08

1.893E+08

3.508E+07

5.942E+07

9.378E+07

1.249E+08

1.644E+08

2.028E+08

2.433E+08

2.784E+08

3.183E+08

3.562E+08

3.974E+08

4.372E+08

4.781E+08

5.151E+08

5.571E+08

5.998E+08

6.463E+08

6.884E+08

7.889E+08

1.010E+09

1.262E+09

1.515E+09

1.704E+09

1.893E+09

1.11

1.88

2.97

3.96

5.21

6.43

7.71

8.82

10.09

11.29

12.59

13.85

15.15

16.32

17.65

19.01

20.48

21.82

25.00

32.00

40.00

48.00

54.00

60.00

3.55E-10

3.71E-10

3.27E-10

2.71E-10

2.65E-10

2.42E-10

2.54E-10

2.41E-10

2.20E-10

2.51E-10

2.13E-10

2.13E-10

2.55E-10

2.65E-10

2.56E-10

2.50E-10

2.40E-10

2.24E-10

2.38E-10

2.38E-10

2.38E-10

2.38E-10

2.38E-10

2.388E-10

3.OOE-10

3.12E-10

2.73E-10

2.30E-10

2.24E-10

2.09E-10

2.22E-10

2.08E-10

1.90E-10

2.16E- 10

1.77E-10

1.85E-10

2.20E-10

2.37E-10

2.25E-10

2.30E-10

2.11E-10

1.96E-10

2.03E-10

2.03E-10

2.03E-10

2.03E-10

2.03E-10

2.03E-10


April 2008

6-10


Iron Atom Displacements

Cumulative Cumulative Displacement RateCycle Irradiation Irradiation (dpa)


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.


April 2008

6-11

Table 6-2 Calculated Azimuthal Variation of Maximum Exposure Rates and Integrated Exposures atthe Reactor Vessel Clad/Base Metal Interface

Cumulative Cumulative Neutron Flux (E > 1.0 MeV)Cycle Irradiation Irradiation (n/cm2-s)

Length Time TimeCycle (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


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 00Cycle (EFPS) (EFPS) (EFPY) 00 150 300 450

1

2

3

4

5

6

7

8

9

10

11

12

13

14

15

16

17

18

Future

Future

Future

Future

Future

Future

3.508E+07

2.434E+07

3.436E+07

3.111E+07

3.954E+07

31837E+07

4.050E+07

3.505E+07

3.992E+07

3.792E+07

4.118E+07

3.982E+07

4.086E+07

3.708E+07

4.192E+07

4.276E+07

4.646E+07

4.219E+07

1.005E+08

2.209E+08

2.525E+08

2.525E+08

1.893E+08

1.893E+08

3.508E+07

5.942E+07

9.378E+07

1.249E+08

1.644E+08

2.028E+08

2.433E+08

2.784E+08

3.183E+08

3.562E+08

3.974E+08

4.372E+08

4.781E+08

5.15 1E+08

5.571E+08

5.998E+08

6.463E+08

6.884E+08

7.889E+08

1.0 1OE+09

1.262E+09

1.515E+09

1.704E+09

1.893E+09

1.11

1.88

2.97

3.96

5.21

6.43

7.71

8.82

10.09

11.29

12.59

13.85

15.15

16.32

17.65

19.01

20.48

21.82

25.00

32.00

40.00

48.00

54.00

60.00

1.86E+18

3.18E+18

4.87E+18

6.09E+ 18

7.56E+18

8.80E+18

1.02E+19

1.14E+ 19

1.25E+19

1.39E+19

1.55E+19

1.65E+19

1.80E+19

1.92E+19

2.06E+19

2.18E+19

2.3 1E+19

2.43E+19

2.76E+19

3.48E+19

4.3 1E+19

5.14E+ 19

5.76E+19

6.39E+19

1.03E+18

1.77E+18

2.69E+18

3.38E+18

4.25E+18

5.01E+18

5.87E+18

6.56E+18

7.28E+18

8.07E+ 18

8.81E+18

9.51E+18

1.04E+19

1.12E+ 19

1.21E+19

1.29E+19

1.38E+19

1.46E+19

1.65E+19

2.08E+19

2.57E+19

3.06E+19

3.42E+19

3.79E+19

7.63E+17

1.30E+18

1.92E+18

2.41E+18

3.05E+18

3.63E+18

4.31E+18

4.84E+ 18

5.40E+ 18

6.OOE+ 18

6.53E+18

7.05E+18

7.70E+ 18

8.38E+18

9.10E+18

9.85E+18

1.06E+19

1.12E+19

1.26E+19

1.58E+19

1.94E+19

2.30E+19

2.57E+19

2.84E+19

5.21E+17

8.85E+17

1.26E+18

1.61E+18

2.07E+18

2.48E+18

2.93E+18

3.30E+18

3.71E+18

4.12E+ 18

4.53E+18

4.90E+18

5.36E+18

5.83E+18

6.32E+18

6.81E+18

7.36E+18

7.79E+ 18

8.83E+18

1.11 E+19

1.37E+19

1.63E+19

1.83E+19

2.03E+19


April 2008

6-13


Cumulative Cumulative Iron Atom Displacement RateCycle Irradiation Irradiation (dpa/s)

Length Time Time 0 1Cycle (EFPS) (EFPS) (EFPY) 0 150 300 450

1

2

3

4

5

6

7

8

9

10

11

12

13

14

15

16

17

18

Future

Future

Future

Future

Future

Future

3.508E+07

2.434E+07

3.436E+07

3.111 E+07

3.954E+07

3.837E+07

4.050E+07

3.505E+07

3.992E+07

3.792E+07

4.118E+07

3.982E+07

4.086E+07

3.708E+07

4.192E+07

4.276E+07

4.646E+07

4.219E+07

1.005E+08

2.209E+08

2.525E+08

2.525E+08

1.893E+08

1.893E+08

3.508E+07

5.942E+07

9.378E+07

1.249E+08

1.644E+08

2.028E+08

2.433E+08

2.784E+08

3.183E+08

3.562E+08

3.974E+08

4.372E+08

4.781E+08

5.15 1E+08

5.571E+08

5.998E+08

6.463E+08

6.884E+08

7.889E+08

1.010E+09

1.262E+09

1.515E+09

1.704E+09

1.893E+09

1.11

1.88

2.97

3.96

5.21

6.43

7.71

8.82

10.09

11.29

12.59

13.85

15.15

16.32

17.65

19.01

20.48

21.82

25.00

32.00

40.00

48.00

54.00

60.00

8.41E-1 1

8.62E-11

7.80E-I 1

6.24E-1 1

5.89E- 11

5.15E-1 1

5.60E-1 1

5.12E-1 1

4.75E-1 1

5.86E-1 1

6.OOE- 11

4.13E-11

5.64E- 11

5.36E- 1I

5.04E- 11

4.50E-1 1

4.68E-1 1

4.50E- 11

5.23E-11

5.23E-1 1

5.23E-1 1

5.23E-1 1

5.23E-11

5.23E-1 1

4.63E-1 1

4.74E-1 1

4.25E-1 1

3.48E-11

3.46E-11

3.13E- 11

3.3 1E-1I

3.12E-11

2.87E-1 1

3.28E-11

2.86E-1 1

2.74E- 1I

3.33E-1 1

3.44E- 11

3.3 1E-I1

3.16E-1 1

3.06E- 11

2.88E-1 1

3.05E-1 1

3.05E-11

3.05E-11

3.05E-11

3.05E-11

3.05E-1 1

3.33E-1 1

3.38E-11

2.75E-1 1

2.42E-1 1

2.49E- 11

2.36E-1 1

2.54E-1 1

2.34E-1 1

2.21E-11I

2.40E- 11

2.OOE- 11

2.01E-11I

2.47E-1 1

2.81E-11I

2.64E-1 1

2.69E-1 1

2.50E-1 1

2.20E-1 1

2.21E-l 1

2.21E-1 1

2.21E-1 1

2.21E-1 1

2.21E-11

2.21E-11I

2.29E- 11

2.32E-1 1

1.70E- 11

1.73E-11

1.80E-1 1

1.64E-1 1

1.72E-11

1.68E-11

1.60E-1 1

1.69E-1 1

1.55E-I1

1.43E-1 1

1.73E-1 1

1.97E-1 1

1.83E-1 1

1.76E-1 1

1.85E-11

1.56E-11

1.61E-1 1

1.61E-11I

1.61E-1I

1.61E-1 1

1.61E-11

1.61E-1 1


April2008

6-14


Cumulative Cumulative Iron Atom Displacement RateCycle Irradiation Irradiation (dpa)

Length Time TimeCycle (EFPS) (EFPS) (EFPY) 0 I 150 300 450

1

2

3

4

5

6

7

8

9

10

11

12

13

14

15

16

17

18

Future

Future

Future

Future

Future

Future

3.508E+07

2.434E+07

3.436E+07

3.111E+07

3.954E+07

3.837E+07

4.050E+07

3.505E+07

3.992E+07

3.792E+07

4.118E+07

3.982E+07

4.086E+07

3.708E+07

4.192E+07

4.276E+07

4.646E+07

4.219E+07

1.005E+08

2.209E+08

2.525E+08

2.525E+08

1.893E+08

1.893E+08

3.508E+07

5.942E+07

9.378E+07

1.249E+08

1.644E+08

2.028E+08

2.433E+08

2.784E+08

3.183E+08

3.562E+08

3.974E+08

4.372E+08

4.781E+08

5.15 1E+08

5.571E+08

5.998E+08

6.463E+08

6.884E+08

7.889E+08

1.010E+09

1.262E+09

1.515E+09

1.704E+09

1.893E+09

1(11

1.88

2.97

3.96

5.21

6.43

7.71

8.82

10.09

11.29

12.59

13.85

.15.15

16.32

17.65

19.01

20.48

21.82

25.00

32.00

40.00

48.00

54.00

60.00

2.95E-03

5.05E-03

7.73E-03

9.67E-03

1.20E-02

1.40E-02

1.62E-02

1.80E-02

1.99E-02

2.21E-02

2.46E-02

2.62E-02

2.85E-02

3.05E-02

3.26E-02

3.45E-02

3.67E-02

3.86E-02

4.38E-02

5.53E-02

6.84E-02

8.15E-02

9.14E-02

1.01E-01

1.63E-03

2.78E-03

4.24E-03

5.32E-03

6.69E-03

7.88E-03

9.23E-03

1.03E-02

1.14E-02

1.27E-02

1.39E-02

1.49E-02

1.63E-02

1.76E-02

1.90E-02

2.03E-02

2.17E-02

2.29E-02

2.60E-02

3.27E-02

4.03E-02

4.80E-02

5.38E-02

5.96E-02

1.17E-03

1.99E-03

2.94E-03

3.69E-03

4.67E-03

5.58E-03

6.61E-03

7.42E-03

8.29E-03

9.20E-03

1.OOE-02

1.08E-02

1.1 8E-02

1.29E-02

1.40E-02

1.5 1E-02

1.63E-02

1.72E-02

1.94E-02

2.43E-02

2.98E-02

3.53E-02

3.95E-02

4.37E-02

8.04E-04

1.37E-03

1.95E-03

2.49E-03

3.20E-03

3.83E-03

4.53E-03

5.11E-03

5.74E-03

6.38E-03

7.01E-03

7.58E-03

8.28E-03

9.02E-03

9.78E-03

1.05E-02

1. 14E-02

1.21E-02

1.37E-02

1.72E-02

2.12E-02

2.53E-02

2.83E-02

3.14E-02


April 2008

6-15

Table 6-3 Calculated Azimuthal Variation of Exposure Rates and Integrated Exposures at theIntermediate Shell Course to Nozzle Shell Course Weld

Cumulative Cumulative Neutron Flux (E > 1.0 MeV)Cycle Irradiation Irradiation (n/cm 2-s)


1

2

3

4

5

6

7

8

9

10

11

12

13

14

15

16

17

18

Future

Future

Future

Future

Future

Future

3.508E+07

2.434E+07

3.436E+07

3.111E+07

3.954E+07

3.837E+07

4.050E+07

3.505E+07

3.992E+07

3.792E+07

4.118E+07

3.982E+07

4.086E+07

3.708E+07

4.192E+07

4.276E+07

4.646E+07

4.219E+07

1.005E+08

2.209E+08

2.525E+08

2.525E+08

1.893E+08

1.893E+08

3.508E+07

5.942E+07

9.378E+07

1.249E+08

1.644E+08

2.028E+08

2.433E+08

2.784E+08

3.183E+08

3.562E+08

3.974E+08

4.372E+08

4.781E+08

5.151E+08

5.571E+08

5.998E+08

6.463E+08

6.884E+08

7.889E+08

1.010E+09

1.262E+09

1.515E+09

1.704E+09

1.893E+09

1.11

1.88

2.97

3.96

5.21

6.43

7.71

8.82

10.09

11.29

12.59

13.85

15.15

16.32

17.65

19.01

20.48

21.82

25.00

32.00

40.00

48.00

54.00

60.00

5.55E+09

9.29E+09

6.54E+09

6.82E+09

4.94E+09

5.65E+09

5.48E+09

5.52E+09

5.17E+09

6.3 1E+09

7.23E+09

4.79E+09

5.94E+09

5.45E+09

5.07E+09

5.22E+09

6.OOE+09

5.17E+09

6.37E+09

6.37E+09

6.37E+09

6.37E+09

6.37E+09

6.37E+09

3.08E+09

5.15E+09

3.59E+09

3.84E+09

2.93E+09

3.46E+09

3.28E+09

3.40E+09

3.16E+09

3.56E+09

3.46E+09

3.2 1E+09

3.54E+09

3.53E+09

3.37E+09

3.72E+09

3.97E+09

3.35E+09

3.76E+09

3.76E+09

3.76E+09

3.76E+09

3.76E+09

3.76E+09

2.28E+09

3.78E+09

2.39E+09

2.73E+09

2.15E+09

2.68E+09

2.58E+09

2.6 1E+09

2.49E+09

2.67E+09

2.49E+09

2.4 1E+09

2.68E+09

2.95E+09

2.75E+09

3.23E+09

3.3 1E+09

2.62E+09

2.77E+09

2.77E+09

2.77E+09

2.77E+09

2.77E+09

2.77E+09

1.55E+09

2.57E+09

1.46E+09

1.94E+09

1.54E+09

1.85E+09

1.73E+09

1.86E+09

1.79E+09

1.86E+09

1.91E+09

1.70E+09

1.86E+09

2.06E+09

1.89E+09

2.09E+09

2.44E+09

1.84E+09

2.01E+09

2.01E+09

2.0 1E+09

2.0 1E+09

2.01E+09

2.01E+09


April 2008

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/cm2 )


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 2008Revision I

6-17


Cumulative Cumulative Iron Atom Displacement RateCycle Irradiation Irradiation (dpa/s)


1

2

3

4

5

6

7

8

9

10

11

12

13

14

15

16

17

18

Future

Future

Future

Future

Future

Future

3.508E+07

2.434E+07

3.436E+07

3.11 1E+07

3.954E+07

3.837E+07

4.050E+07

3.505E+07

3.992E+07

3.792E+07

4.118E+07

3.982E+07

4.086E+07

3.708E+07

4.192E+07

4.276E+07

4.646E+07

4.219E+07

1.005E+08

2.209E+08

2.525E+08

2.525E+08

1.893E+08

1.893E+08

3.508E+07

5.942E+07

9.378E+07

1.249E+08

1.644E+08

2.028E+08

2.433E+08

2.784E+08

3.183E+08

3.562E+08

3.974E+08

4.372E+08

4.781E+08

5.15iE+08

5.571E+08

5.998E+08

6.463E+08

6.884E+08

7.889E+08

1.010E+09

1.262E+09

1.515E+09

1.704E+09

1.893E+09

1.11

1.88

2.97

3.96

5.21

6.43

7.71

8.82

10.09

11.29

12.59

13.85

15.15

16.32

17.65

19.01

20.48

21.82

25.00

32.00

40.00

48.00

54.00

60.00

8.64E-12

1.44E- 1I

1.02E-1 1

1.06E- 11

7.68E-12

8.77E-12

8.51E-12

8.56E-12

8.03E-12

9.78E-12

1.12E-11

7.43E-12

9.21E-12

8.46E-12

7.90E-12

8.10E-12

9.29E-12

8.01E-12

9.86E-12

9.86E-12

9.86E-12

9.86E-12

9.86E-12

9.86E-12

4.76E-12

7.92E-12

5.54E-12

5.90E-12

4.51E-12

5.32E-12

5.03E-12

5.22E-12

4.85E-12

5.48E-12

5.33E-12

4.92E-12

5.43E-12

5.42E-12

5.18E-12

5.68E-12

6.07E- 12

5.13E-12

5.76E-12

5.76E-12

5.76E-12

5.76E-12

5.76E-12

5.76E-12

3.42E-12

5.66E-12

3.59E-12

4.10E-12

3.24E-12

4.01E-12

3.86E-12

3.92E-12

3.74E- 12

4.01E-12

3.74E-12

3.62E-12

4.02E-12

4.43E-12

4.13E-12

4.84E-12

4.96E-12

3.93E-12

4.17E-12

4.17E-12

4.17E-12

4.17E-12

4.17E-12

4.17E-12

2.35E-12

3.88E-12

2.22E-12

2.93E-12

2.34E-12

2.79E-12

2.62E-12

2.81E-12

2.71E-12

2.81E-12

2.89E-12

2.57E-12

2.82E-12

3.11E-12

2.86E-12

3.17E-12

3.68E-12

2.78E-12

3.04E-12

3.04E-12

3.04E-12

3.04E-12

3.04E-12

3.04E-12


April 2008

6-18


Cumulative Cumulative Iron Atom Displacement RateCycle Irradiation Irradiation (dpa)


1

2

3

4

5

6

7

8

9

10

11

12

13

14

15

16

17

18

Future

Future

Future

Future

Future

Future

3.508E+07

2.434E+07

3.436E+07

3.111E+07

3.954E+07

3.837E+07

4.050E+07

3.505E+07

3.992E+07

3.792E+07

4.118E+07

3.982E+07

4.086E+07

3.708E+07

4.192E+07

4.276E+07

4.646E+07

4.219E+07

1.005E+08

2.209E+08

2.525E+08

2.525E+08

1.893E+08

1.893E+08

3.508E+07

5.942E+07

9.378E+07

1.249E+08

1.644E+08

2.028E+08

2.433E+08

2.784E+08

3.183E+08

3.562E+08

3.974E+08

4.372E+08

4.781E+08

5.151E+08

5.571E+08

5.998E+08

6.463E+08

6.884E+08

7.889E+08

1.010E+09

1.262E+09

1.515E+09

1.704E+09

1.893E+09

1.11

1.88

2.97

3.96

5.21

6.43

7.71

8.82

10.09

11.29

12.59

13.85

15.15

16.32

17.65

19.01

20.48

21.82

25.00

32.00

40.00

48.00

54.00

60.00

3.03E-04

6.54E-04

1.OOE-03

1.33E-03

1.64E-03

1.97E-03

2.32E-03

2.62E-03

2.94E-03

3.3 1E-03

3.77E-03

4.06E-03

4.44E-03

4.75E-03

5.09E-03

5.43E-03

5.86E-03

6.20E-03

7.19E-03

9.37E-03

1.19E-02

1.44E-02

1.62E-02

1.81E-02

1.67E-04

3.60E-04

5.50E-04

7.33E-04

9.12E-04

1.12E-03

1.32E-03

1.50E-03

1.70E-03

1.90E-03

2.12E-03

2.32E-03

2.54E-03

2.74E-03

2.96E-03

3.20E-03

3.49E-03

3.70E-03

4.28E-03

5.55E-03

7.01E-03

8.46E-03

9.55E-03

1.06E-02

1.20E-04

2.58E-04

3.81E-04

5.09E-04

6.37E-04

7.9 1E-04

9.47E-04

1.08E-03

1.23E-03

1.39E-03

1.54E-03

1.68E-03

1.85E-03

2.01E-03

2.19E-03

2.39E-03

2.62E-03

2.79E-03

3.21E-03

4.13E-03

5.18E-03

6.23E-03

7.02E-03

7.81E-03

8.26E-05

1.77E-04

2.53E-04

3.44E-04

4.37E-04

5.44E-04

6.50E-04

7.48E-04

8.56E-04

9.63E-04

1.08E-03

1.1 8E-03

1.30E-03

1.42E-03

1.54E-03

1.67E-03

1.84E-03

1.96E-03

2.26E-03

2.94E-03

3.70E-03

4.47E-03

5.05E-03

5.62E-03


April 2008

6-19

Table 6-4 Relative Radial Distribution of Neutron Fluence (E > 1.0 MeV) Within the ReactorVessel Wall

Azimuthal AngleRadius

(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 Outer Radius = 219.79 cm

Table 6-5 Relative Radial Distribution of Iron Atom Displacements (dpa) Within the ReactorVessel 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 Outer Radius = 219.79 cm


April 2008

6-20

Table 6-6 Calculated Fast Neutron Exposure of Surveillance Capsules Withdrawn fromFarley Unit 2

Irradiation Time Fluence (E > 1.0 MeV) Iron DisplacementsCapsule (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


April 2008

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


April 2008

6-22

225

175

125

75

EU

.Inx

25

-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


April 2008

7-1

7 SURVEILLANCE CAPSULE REMOVAL SCHEDULE

The following surveillance capsule removal history meets the requirements of ASTM E185-82'11". Thewithdrawal 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 FluenceCapsule 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.


April 2008

8-1

8 REFERENCES

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

2. Code of Federal Regulations, 10CFR50, Appendix G, Fracture Toughness Requirements, andAppendix H, Reactor Vessel Material Surveillance Program Requirements, U.S. NuclearRegulatory Commission, Washington, D.C.

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

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

5. ASTM E185-73, Standard Practice for Conducting Surveillance Testsfor Light-Water CooledNuclear Power Reactor Vessels, American Society for Testing and Materials.

6. Section XI of the ASME Boiler and Pressure Vessel Code, Appendix GQ Fracture ToughnessCriteria for Protection Against Failure.

7. ASTM E208, Standard Test Method for Conducting Drop- Weight Test to Determine Nil-DuctilityTransition Temperature of Ferritic Steels, American Society for Testing and Materials.

8. ASTM E399, Test Methodfor Plane-Strain Fracture Toughness of Metallic Materials, AmericanSociety for Testing and Materials.

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

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

11. ASTM E185-82, Standard Practice for Conducting Surveillance Testsfor Light-Water CooledNuclear Power Reactor Vessels, E706 (IF), American Society for Testing and Materials.

12. Westinghouse Science and Technology Department Procedure RMF 8402, "Surveillance CapsuleTesting 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 ImpactTesting," Revision 2, August 1, 1998.

WCAP- 16918-NP April 2008Revision I

8-2

15. ASTM E23-06, Standard Test Method for 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," Journalof Engineering Materials and Technology, Vol. 100, April 1978, pp. 183-188.

17. ASTM A370-07, Standard Test Methods and Definitions for Mechanical Testing of SteelProducts, American Society for Testing and Materials.

18. ASTM E8-04, Standard Test Methods for Tension Testing of Metallic Materials, American Societyfor Testing and Materials.

19. ASTM E21-05, Standard Test Methods for Elevated Temperature Tension Tests of MetallicMaterials, American Society for Testing and Materials.

20. ASTM E853-0 1, Standard Practice for Analysis and Interpretation ofLight- Water Reactor

Surveillance Results, E706(IA), American Society for Testing and Materials.

21. ASTM E693-01, Standard Practice for Characterizing Neutron Exposures in Iron and Low Alloy

Steels in Terms of Displacements Per Atom (DPA), E706(ID), American Society for Testing andMaterials.

22. Regulatory Guide 1.190, Calculational and Dosimetry Methods for Determining Pressure VesselNeutron Fluence, U.S. Nuclear Regulatory Commission, March 2001.

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

24. RSICC Computer Code Collection CCC-650, DOORS 3.2, One-, Two-, and Three-DimensionalDiscrete 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 Library Derived from ENDF/B- Vlfor L WR Shielding and Pressure Vessel

Dosimetry Applications, March 1996.

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


April 2008

A-I

APPENDIX AVALIDATION 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 allsurveillance capsules withdrawn from service to date at Farley Unit 2 are described herein. The sensorsets from these capsules have been analyzed in accordance with the current dosimetry evaluationmethodology described in Regulatory Guide 1.190, "Calculational and Dosimetry Methods forDetermining Pressure Vessel Neutron Fluence" [A-I] One of the main purposes for presenting this materialis to demonstrate that the overall measurements agree with the calculated and least squares adjustedvalues to within ± 20% as specified by Regulatory Guide 1.190, thus serving to validate the calculatedneutron exposures previously reported in Section 6.2 of this report. This information may also be usefulin the future, in particular, as least squares adjustment techniques become accepted in the regulatoryenvironment.

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 theFarley 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


April 2008

A-2

The passive neutron sensors included in the evaluations of Surveillance Capsules U, W, X, Z, Y, and V aresummarized as follows.

Reaction of Capsule

Sensor Material Interest U W X Z Y V

Copper 63Cu(n,(X) 6 °Co 4 4 4 4 4 4

Iron 54Fe(n,p)54Mn 4 4 4 4 4 4

Nickel 58Ni(n,p)58Co 4 4 4 4 4 4

Uranium-238 238 U(n,f) 13 7Cs 4 4 4 4 4

Neptunium-237 2 37Np(n,f) 137Cs 4 4 4 4

Cobalt-Aluminum(l) 5 9Co(ny)60Co 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 forthese reaction rates. Pertinent physical and nuclear characteristics of the passive neutron sensors arelisted in Table A- 1.

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

* The measured specific activity of each monitor0 The physical characteristics of each monitor* The operating history of the reactor* The energy response of each monitor0 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 aredocumented in References A-3 through A-7. The radiometric counting of the sensors from Capsule Y andV was carried out by Pace Analytical Services, Inc., located at the Westinghouse Waltz Mill Site. In allcases, the radiometric counting followed established ASTM procedures. Following sample preparationand weighing, the specific activity of each sensor was determined by means of a high-resolution gammaspectrometer. For the copper, iron, nickel, and cobalt-aluminum sensors, analyses were performed bydirect counting of each of the individual samples. In the case of the uranium and neptunium fissionsensors, the analyses were carried out by direct counting preceded by dissolution and chemical separationof cesium from the sensor material.


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 enoughthat a monthly histogram describing reactor operation has proven to be an adequate representation for usein radioactive decay corrections for the reactions of interest in the exposure evaluations. The irradiationhistory 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 thefollowing equation:

R= A

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 corepower 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 weightedaverage 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.


A-4

In the equation describing the reaction rate calculation, the ratio [Pj]/[Pref] accounts for month-by-monthvariation of reactor core power level within any given fuel cycle as well as over multiple fuel cycles. Theratio Cj, which was calculated for each fuel cycle using the transport methodology discussed inSection 6.2, accounts for the change in sensor reaction rates caused by variations in flux level induced bychanges in core spatial power distributions from fuel cycle to fuel cycle. For a single-cycle irradiation, Cjis normally taken to be 1.0. However, for multiple-cycle irradiations, particularly those employing lowleakage fuel management, the additional Cj term should be employed. The impact of changing flux levelsfor constant power operation can be quite significant for sensor sets that have been irradiated for manycycles in a reactor that has transitioned from non-low leakage to low leakage fuel management or forsensor 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 respectivecapsules 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 235Uimpurities in the sensors as well as to adjust for the build-in of plutonium isotopes over the course of theirradiation. Corrections were also made to the 238U sensor reaction rates to account for gamma rayinduced fission reactions that occurred over the course of the capsule irradiations. The correction factorsapplied to the Farley Unit 2 fission sensor reaction rates for Capsule V are summarized as follows:

Capsule

Correction U W X Z Y V235U Impurity/Pu Build-in 0.861 0.818 0.777 0.714 0.663 0.618

Photo-fission, 238 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 sensorreaction rates.

Results of the sensor reaction rate determinations for Capsules U, W, X, Z, Y, and V are given inTables A-4a through A-4f, respectively. The measured specific activities, decay corrected saturatedspecific activities, and computed reaction rates for each sensor indexed to the radial center of the capsuleare listed in these tables. The fission sensor reaction rates are listed both with and without the appliedcorrections 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 thecorresponding neutron transport calculations resulting in a Best Estimate neutron energy spectrum withassociated uncertainties. Best Estimates for key exposure parameters such as O(E > 1.0 MeV) or dpals alongwith their uncertainties are then easily obtained from the adjusted spectrum. In general, the least squaresmethods, as applied to surveillance capsule dosimetry evaluations, act to reconcile the measured sensor


A-5

reaction rate data, dosimetry reaction cross-sections, and the calculated neutron energy spectrum within theirrespective 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 multigroupdosimeter reaction cross-section, Gig, each with an uncertainty 6. The primary objective of the least squaresevaluation is to produce unbiased estimates of the neutron exposure parameters at the location of themeasurement.

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 setreaction 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 multiplefoil set

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

For the Farley Unit 2 application, the calculated neutron spectrum was obtained from the results of plantspecific neutron transport calculations described in Section 6.2 of this report. The sensor reaction rateswere derived from the measured specific activities using the procedures described in Section A. 1.1. Thedosimetry 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 compilationrecommended for use in LWR evaluations by ASTM Standard El018, "Application of ASTM EvaluatedCross-Section Data File, Matrix E 706 (1IB)."

The uncertainties associated with the measured reaction rates, dosimetry cross-sections, and calculatedneutron spectra were input to the least squares procedure in the form of variances and covariances. Theassignment 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 theFarley Unit 2 surveillance capsule sensor sets.

Reaction Rate Uncertainties

The overall uncertainty associated with the measured reaction rates includes components due to the basicmeasurement process, irradiation history corrections, and corrections for competing reactions. A high


A-6

level of accuracy in the reaction rate determinations is assured by utilizing laboratory procedures thatconform 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 countingand data evaluation procedures were assigned the following net uncertainties for input to the least squaresevaluation:

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 SNLRMLlibrary. This data library provides reaction cross-sections and associated uncertainties, includingcovariances, for 66 dosimetry sensors in common use. Both cross-sections and uncertainties are providedin a fine multi-group structure for use in least squares adjustment applications. These cross-sections werecompiled from the most recent cross-section evaluations and they have been tested with respect to theiraccuracy and consistency for least squares evaluations. Further, the library has been empirically tested foruse in fission spectra determination as well as in the fluence and energy characterization of 14 MeVneutron sources.

For sensors included in the Farley Unit 2 surveillance program, the following uncertainties in the fissionspectrum averaged cross-sections are provided in the SNLRML documentation package.


April 2008

A-7

These tabulated ranges provide an indication of the dosimetry cross-section uncertainties associated withthe 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 theresults of plant specific transport calculations for each surveillance capsule irradiation period andlocation. The spectrum for each capsule was input in an absolute sense (rather than as simply a relativespectral shape). Therefore, within the constraints of the assigned uncertainties, the calculated data weretreated equally with the measurements.

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

Mgg, =R 2 +Rg *Rg, *Pgg,

where Rn specifies an overall fractional normalization uncertainty and the fractional uncertainties Rg andRg, specify additional random group-wise uncertainties that are correlated with a correlation matrix givenby:

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 secondterm describes the short-range correlations over a group range y (0 specifies the strength of the latterterm). 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 asfollows:

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%


April 2008

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 capsuleswithdrawn to date are provided in Tables A-5 and A-6. In Table A-5, measured, calculated, andbest-estimate values for sensor reaction rates are given for each capsule. Also provided in this tabulationare 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 spectrato the measured reaction rates both before and after adjustment. In Table A-6, comparison of thecalculated and best estimate values of neutron flux (E > 1.0 MeV) and iron atom displacement rate aretabulated 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 theMeasurement/Calculation, or [M]/[C], ratios. In this case, Best Estimate values refer to the combinationof calculation and measurement via a least squares adjustment procedure to arrive at the best estimate ofthe neutron flux (E > 1.0 MeV) with an associated uncertainty. The least squares procedure provides aweighting of calculated and measured input based on the energy response and uncertainty associated witheach input parameter. The [BE]/[C] ratios, therefore, represent a comparison of the results of the leastsquares 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 reactionrates. 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 spectraare relatively small and well within the assigned uncertainties for the calculated spectra, measured sensorreaction rates, and dosimetry reaction cross-sections. Further, these results indicate that the use of theleast squares evaluation results in a reduction in the uncertainties associated with the exposure of thesurveillance capsules. From Section 6.4 of this report, it may be noted that the uncertainty associatedwith the unadjusted calculation of neutron fluence (E > 1.0 MeV) and iron atom displacements at thesurveillance capsule locations is specified as 12 percent at the I1a level. From Table A-6, it is noted thatthe corresponding uncertainties associated with the least squares adjusted exposure parameters have beenreduced to 6 percent to 8 percent for neutron flux (E > 1.0 MeV) and 8 percent to 10 percent for ironatom displacement rate. Again, the uncertainties from the least squares evaluation are at the 1 a level.


A-9

Further comparisons of the measurement results with calculations are given in Tables A-7 and A-8. Thesecomparisons are given on two levels. In Table A-7, calculations of individual threshold sensor reactionrates are compared directly with the corresponding measurements. These threshold reaction ratecomparisons provide a good evaluation of the accuracy of the fast neutron portion of the calculatedenergy spectra. In Table A-8, calculations of fast neutron exposure rates in terms of O(E > 1.0 MeV) anddpa/s are compared with the best estimate results obtained from the least squares evaluation of the capsuledosimetry 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 theacceptance criteria in Regulatory Guide 1.190.

In the case of the direct comparison of measured and calculated sensor reaction rates, the MICcomparisons 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 correspondingBE/C comparisons for the capsule data sets range from 0.85 to 1.04 for neutron flux (E > 1.0 MeV), andfrom 0.87 to 1.04 for iron atom displacement rate. The overall average BE/C ratios for neutronflux (E > 1.0 MeV) and iron atom displacement rate are 0.91 with a standard deviation of 7.8 percent and0.93 with a standard deviation of 6.9 percent, respectively.

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


April 2008

A-10

Table A-i Nuclear Parameters Used in the Evaluation of Neutron Sensors

ProductReaction of Target Atom 90% Response Half-life Fission

Monitor Material Interest Fraction Range (MeV) (days) Yield (%)

Copper 63Cu (ncx) 0.6917 5.0- 11.9 1925.5

Iron 54Fe (n,p) 0.0585 2.1 - 8.5 312.3

Nickel 58Ni (n,p) 0.6808 1.5 - 8.3 70.82

Uranium-238 238U (n,f) 1.0000 1.3 - 6.9 10983.3 6.02

Neptunium-237 237Np (n,f) 1.0000 0.3 - 3.8 10983.3 6.17

Cobalt-Aluminum 59Co (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 totalresponse due to neutrons with energies below the lower limit and 5% of the total response due to neutrons with energies abovethe upper limit.


April 2008

A-11

Table A-2 Monthly Thermal Generation, Cycles 1 through 4

Cycle 1 Cycle 2 Cycle 3 Cycle 4

Thermal Thermal Thermal ThermalGeneration 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


April 2008

A-12

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




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


April 2008

A-13





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


April 2008

A-14





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


April 2008

A-15

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

Cycle 17 Cycle 18

Thermal Generation Thermal GenerationMonth (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


April 2008

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+115 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+I 1 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+ 11Average 1.73E+11 1.33E+11 1.47E+11 1.04E+I11 1.09E+-iI 1.27E+11

Fuel CjCycle 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 1.3582 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


April 2008

A-17

Table A-4a Measured Sensor Activities And Reaction Rates Surveillance Capsule U

Radially RadiallyMeasured Saturated Adjusted AdjustedActivity Activity Saturated Activity Reaction Rate

Reaction Location (dps/g) (dps/g) (dps/g) (rps/atom)63Cu (ncL) 60Co (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-1754Fe (n,p) 54Mn 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

58Ni (n,p) 58Co 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-142 3 8

U (n,f) 1 3 7Cs (Cd) Middle 2.29E+05 9.23E+06 9.23E+06 6.06E-14

Including 2 35U,

239Pu, 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

Including 235U, 239Pu, and yfission corrections: 5.49E-13

59Co (n,y) 60Co 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-1259Co (n,y) 6

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 effectsin the sensor.


April 2008

A-18

Table A-4b Measured Sensor Activities and Reaction Rates Surveillance Capsule W


Reaction Location (dps/g) (dps/g) (dps/g) (rps/atom)

6 3Cu (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

14Fe (n,p) 54Mn 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-1555Ni (n,p) 5"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

238U (n,f) 137

Cs (Cd) Middle 5.70E+05 6.44E+06 6.44E+06 4.23E-14


237Np (n,f) 137Cs (Cd) Middle 5.54E+06 6.26E+07 6.26E+07 3.99E-13


59Co (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-1259Co (nY) 60Co (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.


April 2008

A-19

Table A-4c Measured Sensor Activities and Reaction Rates Surveillance Capsule X

Radially RadiallyMeasured Saturated Adjusted Adjusted

Activity Activity Saturated Activity Reaction RateReaction 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.


April 2008

A-20

Table A-4d Measured Sensor Activities and Reaction Rates Surveillance Capsule Z


Reaction Location (dps/g) (dps/g) (dps/g) (rps/atom)6 3

CU (n,Q) 6°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


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-1558Ni (n,p) 58Co 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-15238U (n,f) 137Cs (Cd) Middle 2.12E+06 7.65E+06 7.65E+06 5.02E-14

Including 235U, 239 Pu, and yfission corrections: 3.51E-14

237Np (n,f) 137

Cs (Cd) Middle 1 1.12E+07 I 4.04E+07 4.04E+07 2.58E-13

Including 235U, 239Pu, and yfission corrections: 2.56E-1359Co (nY) 60Co 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

59Co (ny) 60Co (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 2

37Np (n,f) reaction rate of 2.56E-13 includes a correction factor of 0.994 to account for photo-fission effects inthe 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.


April 2008

A-21

Table A-4e Measured Sensor Activities And Reaction Rates Surveillance Capsule Y


Reaction Location (dps/g) (dps/g) (dps/g) (rps/atom)

6 3Cu (nc() 6 0Co (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


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-1558Ni (n,p) 58Co 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

238U (n,f) 13 7Cs (Cd) Middle 2.61E+06 3.56E+06 3.56E+06 5.64E-15

Including 235U, 239Pu, and yfission corrections: 2.97E-14237Np (n,f) 1

37Cs (Cd) Middle 1.63E+07 ] 4.67E+07 4.67E+07 2.98E-13


59Co (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

59Co (n,y) 60CO (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.


April 2008

A-22

Table A-4f Measured Sensor Activities And Reaction Rates Surveillance Capsule V


Reaction Location (dps/g) (dps/g) (dps/g) (rps/atom)6 3

Cu (nUc) 60Co (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-1754Fe (n,p) 54Mn 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-1558Ni (n,p) 5"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-152 3 8

U (n,f) 13 7

Cs (Cd) Middle 3.32E+06 9.OOE+06 9.OOE+06 5.91E-14

Including 235U, 239Pu, and yfission corrections: 3.56E-14237Np (n,f) 137Cs (Cd) Middle 2.11 E+07 I 5.72E+07 5.72E+07 3.65E-13


'9Co (nY) 60CO 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

59Co (nY) 60Co (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.2.

3.

Measured specific activities are indexed to a counting date of November 29, 2007.The average 238U (n,f) reaction rate of 3.56E-14 includes a correction factor of 0.618 to account for plutonium build-inand an additional factor of 0.978 to account for photo-fission effects in the sensor.The average 237Np (n,f) reaction rate of 3.63E-13 includes a correction factor of 0.994 to account for photo-fission effectsin the sensor.


April 2008

A-23

Table A-5 Comparison of Measured, Calculated, and Best Estimate Reaction Rates at the SurveillanceCapsule Center

Reaction Rate (rps/atom)

Reaction Measured Calculated Best Estimate M/C M/BE

Capsule U63Cu(n,(x)6°Co 8.19E-17 7.50E-17 7.86E-17 1.09 1.0454Fe(n,p)54Mn 8.55E-15 9.08E-15 8.71E-15 0.94 0.98

58Ni(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

237Np (n,f) 1 3 7Cs (Cd) 5.49E-13 5.64E-13 5.42E-13 0.97 1.01

59Co (n,y) 60Co 7.44E-12 5.56E-12 7.23E-12 1.34 1.03

59Co (n,y) 60Co (Cd) 4.2 1E-12 4.29E-12 4.30E-12 0.98 0.98

Capsule W63Cu(n,ct)6°Co 6.58E-17 6.64E- 17 6.40E-17 0.99 1.0354Fe(n,p)5 4Mn 6.72E-15 7.72E-15 6.86E-15 0.87 0.98

58Ni(n,p)58Co 9.68E-15 1.09E-14 9.69E- 15 0.89 1.00

238U (n,f) 13 7Cs (Cd) 3.38E-14 4.28E-14 3.71E-14 0.79 0.91

237Np (n,f) 137Cs (Cd) 3.97E-13 4.41E-13 3.90E-13 0.90 1.02

59Co (n,y) 60CO 5.OOE-12 4.03E-12 4.85E-12 1.24 1.03

59Co (n,y) 60Co (Cd) 2.84E-12 3.13E-12 2.91E-12 0.91 0.98

Capsule X63Cu(n, .X)60Co 6.89E-17 6.61E-17 6.63E-17 1.04 1.0454Fe(n,p)14Mn 6.90E- 15 7.86E-15 7.15E-15 0.88 0.97

58Ni(n,p)58Co 9.98E-15 1.12E- 14 1.01E-14 0.89 0.992 3 8

U (n,f) 13 7Cs (Cd)

23 7Np (n,f) 137Cs (Cd)

59Co (n,y) 60Co 6.52E-12 4.65E-12 6.31E-12 1.40 1.03

59Co (n,y) 60Co (Cd) 3.60E-12 3.59E-12 3.67E-12 1.00 0.98


April 2008

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 Z6 3Cu(n,cL) 6°Co 6.49E-17 5.61E-17 6.40E-17 1.16 1.0154Fe(n,p) 54Mn 6.77E-15 6.38E-15 6.82E- 15 1.06 0.9958Ni(n,p) 58Co 9.79E-15 8.99E-15 9.59E-15 1.09 1.02

2 3 8u (n,f) 1

3 7Cs (Cd) 3.51E-14 3.50E-14 3.51E-14 1.00 1.00

237Np (n,f) 137Cs (Cd)

59Co (n,y) 6"Co 4.19E-12 3.22E-12 4.07E-12 1.30 1.0359Co (ny) 60Co (Cd) 2.34E-12 2.50E-12 2.39E-12 0.94 0.98

Capsule Y63Cu(n, C)60 Co 5.45E-17 5.67E- 17 5.33E-17 0.96 1.0254Fe(n,p)14Mn 5.61E-15 6.44E- 15 5.66E-15 0.87 0.99

58Ni(n,p)58Co 7.73E-15 9.07E- 15 7.88E-15 0.85 0.98238U (n,f) 137Cs (Cd) 2.97E-14 3.52E-14 3.02E-14 0.84 0.98

237Np (n,f) 137Cs (Cd) 2.96E-13 3.58E-13 3.01E-13 0.83 0.98

59Co (ny) 60Co 3.75E-12 3.22E- 12 3.65E-12 1.16 1.03

59Co (ny) 61Co (Cd) 2.12E-12 2.50E-12 2.17E-12 0.85 0.98

Capsule V

63Cu(noC)6°Co 6.04E- 17 5.96E- 17 5.82E- 17 1.01 1.0454Fe(n,p)54Mn 6.02E- 15 6.94E- 15 6.20E-15 0.87 0.9758Ni(n,p) 58Co 8.51E-15 9.82E-15 8.73E-15 0.87 0.97

238U (n,f) 137Cs (Cd) 3.56E-14 3.89E-14 3.43E-14 0.91 1.04237Np (n,f) 137Cs (Cd) 3.63E-13 4.10E-13 3.64E-13 0.88 1.00

59Co (ny) 60Co 4.65E-12 3.94E- 12 4.52E-12 1.18 1.0359Co (n,y) 60Co (Cd) 2.58E-12 3.04E-12 2.64E-12 0.85 0.98


April 2008

A-25

Table A-6 Comparison of Calculated and Best Estimate Exposure Rates at the SurveillanceCapsule Center

4 (E > 1.0 MeV) (n/cm 2-s)

UncertaintyCapsule 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)

UncertaintyCapsule 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


April 2008

A-26

Table A-7 Comparison of Measured/Calculated (MIC) Sensor Reaction Rate Ratios Including AllFast 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


April 2008

A-27

A.2 REFERENCES

A-1 Regulatory Guide RG-1.190, "Calculational and Dosimetry Methods for Determining PressureVessel Neutron Fluence," U. S. Nuclear Regulatory Commission, Office of Nuclear RegulatoryResearch, March 2001.

A-2 WCAP-88 10, "Southern Alabama Power Company Joseph M. Farley Nuclear Plant Unit No. 1Reactor 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 CompanyFarley 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 CompanyJoseph 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 CompanyFarley Unit 2 Reactor Vessel Radiation Surveillance Program," February 2000.

A-7 WCAP-1635 1-NP, Revision 0, "Analysis of Capsule Y from Southern Nuclear OperatingCompany Joseph M. Farley Unit 2 Reactor Vessel Radiation Surveillance Program,"February 2005.

A-8 A. Schmittroth, FERRETData Analysis Core, HEDL-TME 79-40, Hanford EngineeringDevelopment Laboratory, Richland, WA, September 1979.

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


April 2008

B-1

APPENDIX BLOAD-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


April 2008

B-2

n

ca

5000.00

4000.00

3000.00

2000.00

1000.00

n fm

.......... . .. .. .

............

.......... ..............

..........

.......... ............

+

1.00 2.00 3.00

Time- (ms)

CL30, 50°F

4.00 5.00 6.00

5000.00-

4000.00-

"73000.00-

MOM

2000.00-

1000.00-

..............

..........

......................

................

G flfI -

0.00 1.00 2.00 3.00

Time-I (ms)

CL19, 180°F

4.00 5.00 6.00


April 2008

B-3

0.00 1.00 2.00 3.0,0 4.00 5.00

Time-l (mS)

CL25, 210°F

6.00

0.00 1.00 2.00 3.00 4.00 5.00

Time-1 (ms)

CL17, 220 0 F

6.00


April 2008

B-4

0.00 1.00 2.00 3.00 4.00 S.00

Time-I (mns)

CL28, 225-F

6.00

6.00

Tine-1 (ms)

CL22, 230°F


April 2008

B-5

5 0 0 0 .0 0 . .- -. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

4000.00

4 0 0 0 .0 0 . . . . ... .... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . .... . . . . . . . . . . . . . . . .3 0 0 0 .0 0 .... ... ..... ................. .........................i ...............i ... ..3000 00

0.00 1.00 2.00 3.00 4.00 5.00 6.00

Time-1 (ins)

CL18, 250°F

$ 0 . 0 . . . . . . . . . . . . . . . . : . . . . . . . . . . . .. - . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .•. . . . . . . . . . . . . . . ..

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

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

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

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


B-6

3 0 0 .0 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . .n

0-j

2000.00."

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

0.00

0.00 1.00 2.00 3.00 4.00 5.00 6.00

Time-I (ms)

CL16, 2650F

5 0 D 0 .0 0 . . . . . . . . . . . . . . . . . . . :.. . . . . . . . . . . . ..... . . . . . . . . . . . . . . . . . . . . . ., . . . . . ... . . . . . .. . . . . . . . . . . .

4 G 0 0 .0 0 . . . . . . . . . .... . . . . . .. . . . . . . . . . . . .. " . . . . . . . . . . . . .. . . . . . . . . . . .. . . . .. ". . . . . . . . . .5: 000.00

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

0-j

4000.00-

3000.00-

2000.00

IOG.O-

..........

. ....... .. . . ..............

...................

..........

............... .............

.......... ...........

0.00 1.00 2.00 3.00

Time-1 (ms)

CL23, 290-F

4.00 5.00 6.00

300000-0

0.00 1.00 2.00 3.00 4.00 5.00

Time-I (ms)

CL26, 315°F

6.00


April 2008

B-8

5 0 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 . ,. ...

0.000.00 1.00 2.00 3.00 4.00 5.00 6.00

Time-i (ms)

CL20, 370°F


B-9

n

0-J

5000.00

4000.00

3000.00

2000.00

1000.00

.. .............. .... . .

............

...........

............

......................flLI 1 i

0.00 1.00 2.00 3.00

Time-I (ws)

CL29, 380°F

4.00 5.00 6.00

n

w0

-J

5000.00

4000.00

3000.00

2000.00

1000.00

..........

.. .. .. .. .. . .. . .. .

.. . .. . .. . . ... . .. ..

................

. . .. .. . .. .. . . .. .. . .. -

... . .... ..

r i l• i =

0.00 1.00 2.00 3.00

Time-i (ms)

CT25, 100-F

4.00 5.00 6.00


April 2008

B-10

5000.00

4000.00

3000.00

2000.00 . . .

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

0.000.00 1.00 2.00 3.00 4.00 5.00 6.00

Time-1 (ms)

CT24, 200°F

5 0 0 .0 0 . . . .. . . . . . . . . . = . . .. . . . . . . . . . . . . . . . . .. . . . . .. . . . . . . . . . . . . . . . •.. . . . . . . . . . . . . . . . •. . . . . . . . . . . .

4 0 0 0 .0 0 . . . . . . . . . . . . . . . . . . .... .. .... .. . . . . . . . . . . . .. . .. . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . .

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

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

1 0 0 0 .0 0 . . . . . . .. . . . . . . . . . . . . . . . ;.. . . . . . . . . . . . . . . . .... . . . . . . . . . . . . . . . . . . . . . . . .

0.000.00 1.00 2.00 3.00 4.00 &OD 600

Time..1 (ms)

CT19,0205F


B-11

S O 0 .O 0 . .. . . . . . . . . . . . . . . . . . . . . '. . . . . . . . . . . . . . . . . .,. . . . . . . . . . . . . . . . • . .. . . . . . . . . . . • . . . . . . . . . . . . . . .

4000.00

3000.00n

3000.00

0.000.00 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

0.00O.00 1.00 2.00 300 4.00 5.00 6.00

Time-1 (ms)

CT23, 230°F


B-12

S 0 0 0 .0 0 . . . . . .... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . .

0o o o o o ....... . .. ............ . .. . . . . . . .... ...... .. . . ............................ . .0.004000.00

30.00 00.

0.00 1.00 2.00 3.00 4.00 5.00 6.00

lime-i (ms)

CT17, 2400 F

5 0 0 D .0 0 . . . . . . . . . . .. . . . .• . . . ... . . . . . . . . . . . . . . . . . . . . ',. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . •.. . . . . . . . . . . .

5000.00

3•0 0.00 .. . . .. . . . . . . . .. . . . . .

4000.00ca

0.00 1.00 2.00 3.00 4.30 5.00 6.00

Time-1 (ms)

CT22, 260-F


Revision I

B-13

5000.00-

4000.00

3000.00-

0-j

2000.00

1000.00

..............

.............. . .......

...........

... .. . ....

............

.............

..........

..........

............................

u 00 i0.00 1.00 2.00 3.00

Time-I (ms)

CT29, 275-F

4.00 5.00 6.00

3000.000-J

2000.00-

0.00 1.00 2.00 3.00 4.00 5.00

lime-I (me)

CT20, 280°F

6.00


April 2008

B-14

5000.00-

4000.00-

3000.00-S

2000.00-

1000.00-

...........

............

.............

..............

....................... .......

0.00 1.00 2.00 3.00

Time-I (ms)

CT18, 3050F

4.00 5.00 6.00

5000.00

4000.00

3000.00iu0-j

2000.00

1000.00

0.000.0

a .. .. . .. .. .. . .. .. .. .. . .. . . .. .. .. .. . . .. .. ..

.... ... . ...... ....... ........ .........

. ......... ....

................ .........

.............. ........

........................

10 1.00 2.00 3.00

lime-i (ms)

CT28, 345°F

4.00 5.00 6.00


April 2008

B-15

0-j

Time-i (mns)

CT30, 3750 F

n

0-J

0.00 1.00 2.00 3.00 4.00 500

Time-1 (ms)

CT21, 400°F

6.00


April 2008

B- 16

n7

0

5000.00

4000.00

3000.00

2000.00

1000.00A

..............

..........................................................................

..................................... ..... .... ... ....

........... ........ ......

............................

0.00 1.00 2.00 3.00

Time-1 (ms)

CW28, -25 0 F

4.00 5.00 6.00

5000.00

4000.00

3000.00

0.00 1.00 2.00 3.00 4.00 5.00

Time-1 (ms)

CW21, 20°F

6.00


April 2008

B-17

3000.00 .......o-a

2 0 0 0 .0 0 . . . . . . . . . . . . . . . . . . . . . . . . . ... . . . . . . .... . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . .

10 00 .0 0 .. .... ... .. ............. .. ...... ..

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 O 0 .0 0 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... . . . . . . . . . . . .= . . . . . . . . ... . . . . .

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


Revision I

B- 18

0o

0.00 1.00 2.00 3.00 4.00 5.00

Time-i (m)

CW24, 50OF

6.00

50,00.00

4000.00

3000.00

2000.00

1000.00

0.000.0

F

........... . ... .. ...

.... ......

.......... .......... ......

.......................

...........

0t 1.00 2.00 3.00

Time-i (m)

CW27, 700 F

4.00 5.00 6.00


April 2008

B-19

I000.00

4000.00

3000.00

2000.00

1oo0.00

................ ........I ....... ....... .......

.......... ...........

.. ... ...... . ...

.............

... .............. .......

...........

............ . .. . .. ..

...............

.................

.....................

............

0n4 . -C--

0.00 1.00 2-00 3.00

Time-i (ms)

CW22, 100-F

4.00 5.00 6.00

3000.00-

2000.00-

0.00 1.00 2.00 3.00 4.00 5.00

Time-1 (ms)

CW20, 1250 F

6.00


April 2008

B-20

0

5000.00

4000.00

3000.00

2000.00

1000.00

0.000.0

B-20

............ ....... ........

.............

.... .... ..

1 : .. . .. .. . .. . .. . .. ... . .. - . .. .. .. .

O0 1.00 2.00 3.00

Time-i (ms)

CW26, 145°F

4.00 5.00 6.00

5000.00

4000.00

n G-S3000.00

2000.00

1000.00

0.000.0

F................ . .. .. . .

....................

.. . .. .. . .. .. . . .. . - .. . .. . . . .... ....

............

.......... ......... ..........

............... ...........

. .... ....... .

0o 1.00 2.00 3.00

Time-1 (ms)

CW17, 165°F

4.00 5.00 6.00


April 2008

B-21

4000.00

17 3000.00

2000.00-

0.00 1.00 2.00 3.00 4.00 5.00

Time-I (ms)

CW19, 1850F

6.00

n

0

-J,

0.00 1.00 2.00 3.00 4.00 5.00

Time-1 (ms)

CW16, 2300F

6.00


April 2008

B-22

.0

00-j

0.00 1.00 2.00 3.00 4.00 5.00

Time-I (ms)

CW23, 250OF

6.00

3G0O3000.

0-j

2000.

0.00 1.00 2.00 3.00 4.00 5.00

Time-I (ms)

CW18, 260°F

6.00


April 2008

B-23

. .. .. . .. .. . ..:

5000.00

0"7 3000.00-4000.00-

3000.00-

0-j

1000.00-

0.00D

....... ...... ......

0.00 1.00 2.00 3.00

Time-I (Ms)

CH23, -80°F

4.00 5.00 6.00

0,

5000.00

4000.00

3000.00

2000.00

1000.00

0.000.00

. . . . . . . . . . . . . . . . . . . . . . .

.........-.

.. .........

1.00 2.00 3.00

Time-I (ms)

CH29, -15°F

4.00 5.00 6.00


April 2008

B-24

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

2 DO3 0 0 .0 0 . . . . . . . . . . . . . . . .... . . . . . . .. . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . ... . . . . . . . . . . . . . . ..

2000.00

1000.00

0.000.00 1.00 2.00 3.00 4.00 5.00 6.00

Time-I (ms)

CH24, 25-F

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

4000.00 . .... ...

"7 3000.00

2000.00

1000.00

0.00

0.00 1,00 2.00 3.00 4.00 5.00 6.00

time-1 (ms)

CH26, 35°F


B-25

5000"00-

4000.00-

3000.00-

0

2000.00

1000.00-

...........

.... . .. ...... . ..

........... .........

.. , .... .... .-

. .. .. . .. .. . .. . .. .. .. .

rnJ 4 ýP[ I ,

0.00 1 00 2.00 3.00

Time-1 (ms)

CH22, 40-F

4.00 5.00 6.00

6.00

n

'7 3000 00-n0-J

3.00

TIme-1 (Ms)

CH27, 45-F


April 2008

B-26

"n

0.00 1.00 2.00 3.00 4.00 5.00

Time-I (ms)

CH18, 50 0 F

6.00

n

0-I

0.00 1.00 2.00 3.00 4.00 5.00

Time-i (ms)

CH17, 70°F

6.00


April 2008

B-27

5000.00

4000.00

3000.00

1000.00

0.000.0

................

...........

..................

D0 1.00 2.00 3.00

Time-1 (ms)

CH21, 70°F

4.00 5.00 6.00

4000.00

.•3000.00

2000.00

1000.00

0.000.0

..

....... ... ..................

............

.................. ...........

D0 1.00 2.00 3.00

Time-i (ms)

CH16, 90 0F

4.00 5.00 6.00


April 2008

B-28

5 0 00 .0 0 . .. . . . . . . . . .. . .. .. . . .. ... . .. . . . .. . .. . . . . . . . .. . . . . .

4000.00

3000.00o

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

5 0 0 0 .0 0 .. . . . . . . . . . . . .... . . . . . . . . . . . . . . .. . . . . . . . . . . . . .. .. . . . . . . . . . .. . , . . . . . . . . . . .. .. . . . . . . . .

5000.00

4000.00

_.0 3000.00

1000.00

0.000.00 1.00 2.00 3.00 4.00 500 6.00

Time-1 (ms)

CH20, 155°F


B-29

nu

m7

0.00 1.00 2.00 3.00 4.00 5.00

Time-i (am)

CH30, 200-F

6.00

4000.00-

3000.00cc0-J

20D0.00-

M00.0-

. .. . .. .. .. . .. . . .. .. . . .. .. . .

..................

... .... .... . ......... ..

. . .. .. . .. .. .. . .. ... .. . .. . .. -

........................

............ .......

0.00 1.00 2.00 3.00

Time-i (ms)

CH25, 260°F

4.00 5.00 6.00


April 2008

C-1

APPENDIX CCHARPY 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, andreads 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 thehighest average energy as the USE (usually unirradiated material). If the specimens were not tested insets of three at each temperature, Westinghouse reports the average of all Charpy data (> 95% shear) asthe USE. Hence, the USE values reported in Table C-i, which were used to generate the Charpy V-notchcurves, 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 thereference list.

C.1 REFERENCES

C-1 ASTM E 185-82, Standard Practice for Conducting Surveillance Testsfor Light- Water Cooled

Nuclear Power Reactor Vessels.


April 2008

C-2

UNIIRADIATED INTERMEMIATE SHELL PLATE B7212-1 (LONGITUDINAL)

CVGRAPI 5.3 Hyperblic Tangat Carve Printed on 02/06f008 10:15 AMPap I

Coe-ciciitz of CmNe 1A =66J B =6&9PC=34A6 TO =31.75 D = .OOas4O

Epulan is A tB B 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 FFPlatPaey 2 Mateal: SA533B1 ea B7212-I

Oduntaln: LT Caqumle: UNIRR Fkcm: nfctn2

-ao300

I20

IS

J5D

400.0 -200.0 -100a0 0.0 100.0 200.0 300.0 400.0 s6.0 600.0Temperaure In Deg F

Charpy V-Notch Data

N QMVMndCVN

-60.00-50.00-25.00-25.00-10.00

.0020.0050.0060.00

12.0015.0019.0034.0047.005D. 0063.0072.0067.00

15.2718.3228.6428. 6436. 8643. 1557.2779.7086.71

DiflktW

-3.27-3.32-9.64

5.3610.146.855.73

-7.70-19.71


April 2008

C-3

]UNIRRADIATED INTERMICIATE SHELL PLATE B7212-1 (LONGITUDINAL)

Pap 2Plant Fadcy2 Mari SA533B1 HeatB7212-1

Odnhtaj: LT Capaule UNIRR Flec nkmA2

Charpy V-Notch Data

Tevew lp CVN CwapadCVN Dfmu

75.00100.00125.00150.00210.00210.00210.00

103.00110. 50123.00132.00134.00130.00132.00

96.23108.82117.35122. 68128. 15128.15128.15

6.771.685.659.325.851.853.85

Caur im (befficic m .985


April 2008

C-4

CAPSULE U INTERMEDIATE SHELL PLATE B7212-i (LONGITUDINAL)

CVYRAPH 5.3 Hyperboalc Tangent Curve Pdnted on 02/0M61008 10:16 AMPage 1

Coefiuieutz of Cure 2A =-43 B=-46.C= 126.54 TO=-136.29 D =0.O,+00

Eqti is A + B ' [VPrbh -ThAC+DT)]jUppu S-fhelf 94A(Fizcd Inner Smf Enmc=2.20Fxzm)

Tup=@3O ft-(h93l.2 Deg F TmpOSO f.l4b=141.O Deg FFlat: Fucy2 MeW: SAS33BI Hcat B7212-I

Odwali LT Capslac U Plama: nWW2

280

4200

150

100

0o400.0 -200.0 -100.0 0.0 100.0 200.0 30

Temperature In Deg F0.0 400.0 60.0 600.0

Chmapy V-Notch Data

T¶ruqma

.0030.0075.00

100.00125.00150.00150.00173. 00200.00

13. 5023.5033.0040. 5042. 0046. 0034. 0053.0035.00

CmoedCVYN

11.7820. 9727.5373..4344.2053.2853. 2861. 9869. 73

a

1.722.535.433.07

-2.20-7.2U

18.98-1]4.7/3


April 2008

C-5

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

Pap 2PlantP Fadcy 2 Mutriak SA533B 1 Heat B7212-1

Odmenmto LT Capsule: U Pmhimenc nkr2

Chap V-Notch Data

200.00225.00250. 00300.00350.00400.00

CmuplCYVN

73.5038.5090.0091.5098.5097.50

69.7376. 1981.2987.9591.3692.99

3.7712.31

8.713.557.144.51

Cnbmuk effridm -M65


April 2008

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 3A =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 FFlue Fsiey2 Matfial: SA53BI t Bf212-1

Odausio LI Cqmik W Fbo: ntm"2

200

ISO

100- A

0

0o - 4 - 4 4

I

z?2

-M0.0 -200.0 -100.0 0.0 100.0 200.0 300.0 4m.0 M0.0 eaTemperature In DMM F

Trmemi

.0073.00

100.00125.00150.00150.00175.00175.00200.00

Charpy V-Notch Data

]-n• Cw C YmNd fN

6.00 3.8226.00 9.6234.00 14.7815. 00 22.0440.00 32.0527.00 32.0540.00 44.4431.00 44.4449.00 57.81

2.1316.3319.22-7.047.95

-5.05-4.44-6.44-U.88


April 2008

C-7

CAPSULE W INTERMEDIATE SHELL PLATE B7212-1 (LONGrrUDINAL)

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

Chmrpy V-Notch Data

200.00225.00250.00300.00350.00400.00

-wC-N

45.0032.0093.00

103.00100.00103.00

-MVMd CYN

57.8870.5280.9193.7199.03

100.98

-12.8811.4812.099.29

.972.02

Cmwlima befffdit - .956


April 2008

C-8

CAPSULE X INITRMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

CVGRAPH 5.3 Hypebolic Tangent Curve Printed on 02106t20W= 1031 AMPage 1

Cofliciits of Cu-vc 4A =49.25 B =47.oS C =97.3 T1O=184.74 D =0.0E+00

Equtionis At B * V rbnb'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 FPlaut 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 eoo0Temperours In Do F

Chmrpy V-Notch Data

TmPwmhm

.0072.00

100.00125.00125.00150.00150.00175.00200.00

-qpm CYN

2.0019.0021.0011. 0022.0033.0037.0046.0042.00

-ulad CYN

4.2610.6416.2323.5223.5233. 1333. 1344. 5656.57

-2.263.36

11.77-5.52-1.52

-. 133.871.44

-14.57


April 2008

C-9

CAPSULE X INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

Pago 2Plat Fadey 2 Mtcriak SA533B I Heat: B7212,-Odetoi• LT Casuk, X Plunce• ocm"2

Chmrpy V-Notch Data

200.00225.00250.00350.00400.00450.00

-mCN

47.0073.0092.0097.00

102.0094. 00

(MWWmdCVN

56.5767.6876.8093. 2595. 199.5.90

-9.575.32

15.203.756.81

-1.90

Camxztfm benicM m AM1


April 2008

C-I0

CAPSULE Z INTERMEDIATE SHELL PLATE B7212-I (LONGITUDINAL)

CVGRAPH 53 Hypmbolic Tganmt Cme Plnted on 02100M 10:32 AMPage

Coafficita Of Curve 5A=a U= 45.SC =67J6 TO"=201.76 D=OOE+00

Huivniu is A +. * Irr0h"-To-TXC4m))1Uppe SbUVzcl]h9aui93Q L') Lwa Shel EnHr--2.2Mrmd)

Tcmp30 t--lbs=7"8 Dcg F TcMO@O fl-.-=208.8 DgF PFla Fw1-y2 Medal: 8A5331B Neat B7212-1

Odualtin LT Capalm Z Fbso nkufta

420

*150Iml

Sio

o _-100.0 -200.0 -00.O 0.0 100.0 200.0 300.0 400.0

Tempemtur In Doe F00.o 600.0

T¶rum

.0072.00

125.00150.00175.00190.00200.00210.00225.00

Chmapy V-Notch Data

1os CW4 c-mvum CN

5.00 2.4121.00 3.9117.00 9.8120.00 16.9528.00 28.4839.00 37.3025.00 44.1060.00 30.8760. 00 60. 70

DinflMM

2.5917.097.123.05-. 411.50

-19.109.13-. 70


April 2008

C-II

CAPSUL Z INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

Page 2Plant Faf• 2 Miat SAS33B1 Heat B7212-1Odenrflfa LT Capmul Z Flume: nftmA2

Charpy V-Notch Data

'r.llmmu

250.00275. aa300.00350.00400.00450.00

lquliCYN

74.0094. 0090.0091.0096.0098.00

mpubd CVYN

74. 3313. 3583. 5092.5493.5193.73

-. 3310. 65

1.50-1.542.494.27

Cknsmkwm Om = .974


April 2008

C- 12

CAPSULE V INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

250

4zo

ID

C-VGRAPH 53 Hypebolc Taanget Camrve Pnted on O2(06#200 10:33 AM

Celimcts of Cumve 6A =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 FPlant Fslcy2 Madal: SA533B1 HesL B7212-1

OIIUIiWE LT Cqsk Y Fluence: nknt2

6'*

.S

0400.0 -200.0 -100.0 0.0 100.0 200.0 300.0

Temperature In Des P400.0 S00.0 600.0

Charpy V-Notch Data

7m3

10.0050.00

100.00150.00175.00180.00200.00210.00225.00

kSpu CYNT

7.003.00

12.0022.0019.0023.0028.0054.0048.00

QSmodSCVN

2.302. 594.20

11.6220. 9023.3835.1141.6951.53

4.705.417.80

10.33-[.90

-. 38-7.1112.31-3.53


April 2008

C-13

CAPSULE Y INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

Page 2PlantFadry2 maa SA533B1 Heat B7212-1

Odumlent LT Capsule• Y Pluenot n/MA2

Charpy V-Notch Data

ThwMsu

225.00250.00275.00300. 00325.00350.00

36. 0072. 0034. 0031.0033.0077.00

(•ompnxle C-•

51.5365. 3574. 1878.8881. 1482. 18

-15.536.659.822.126.86

-5. 11

CsukJ ' CbeffcmM - .967


April 2008

C-14

CAPUE V INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

CVGRAPH 53 Hypebolic Tangmt Cura Praed on WOW= 10:33 AMPage 1

Corifwicnts of Curvc 7A=44.1 B=-41S C =.73 TO=W27.37 D=.OO0E404i

Equation is A + B •1 'mn(T-To)(CT]))jUppin ShcVEDm'=S6OIFkadIv ~d ncy-20w

Tcmpl30 fls=19.0 Dog F Tomp*O5 ftasl2.1 Deg Fuet FPly 2 Mmaio: SAS33BI HE aB7212-1

Odnmiako LT Cqmilc V PFbiti: mftg23a

2M0

1150

a

so

-Mo.0 -200.0 -100.0 0.0 100.0 200.0 300.0Temperaure In Dog F

400.0 SO0.o 6t0

Chwr V-Notch Data

T¶mq

50.00180.00210.00220.00225.00230.00250.00260.00265.00

alpu CVN

10. 5021.0033.0032.0035.0055.0064.0077.0074.00

3. 7823. 1336.0940.6742.9945.3354.4558. 7060. 71

6.72-2.83-3.09-1.67-7.999.679.55

18.3013.29


April 2008

C-15

CAPSUE V INTERMEDIATE SHELL PLATE 17212-1 (LONGITUDINAL)

Pag 2Pint Pkaft2 MamiaL SA533B1 Heat: B7212-1Odnt'm LT Capaue, V Plucnce nkA2

Charpy V-Notch Data

Tam-mm3

290.00290.00315.00340.00370.00380.00

1n pmCYN

35.0053.0092.0080.-0078.0092.00

-u CYN

69.3769.3775.5979.7032.6513.30

-34.37-16.37

16.41.30

-4.651.70

Cmnttiom tiasdmt - a=


April 2008

C-16

UNIRRADIATED INTMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

CvGRAH £.3 Hyperoic Tangmnt Curve P•d•tl on 0206C 03:14 PMPape 1

CoeFflicta of Cowv IA =4 .3 B =4&.VC=ULf73 TI=21.1B D=O.OFM

Equtimis A + B 0 rraT ((T-ToA(CtDT))1Upper Shelf L.R--90. Lower Shelf LR=. d)

Tamp.@LAE, 35 mzil=1.0 Dg FlnFsiy2 MWd: SAS33B Heat B7212-1

Odelacti: LT Cqxualo: UNIRR Fumces: nkmt2m

aU

ISO

100

50 0

0 I

4M0.0 0.0 300.0 600.0Temperature In Dog F

Chmrlp V-Notch Data

"lpS CLmEd

-60.00-50.00-25.00-25.00- 10.00

0020. 0050.0060.00

9.0011.0016.0026. ao35. ao40. 0049.0060. 0053.00

12. 1014.7323.2723.2729.7434.3244.7739. 9464.43

arfim"

-3.10-3.73-7.27

2.735.265.484.23

.06-11.45


April 2008

C-17

UNIRRADIATED INTFRMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

Pap 2Plan.tFadey 2 Matcriak SA533B1 I-Hat B7212-1

Odmadin: LT Capat UNIRR EPue= nAcmA2

Chap V-Noth Data

75.00100.00125.00150.00210.00210.00210.00

- LB

71.0030.0034.0091.0037.0090.0039-00

70.4278. 1083. 1986.3589. 6389. 6389. 63

. 5381.90

.814.65

-2.63.37

-. 63

Comudm Cfbeffic -, -


April 2008

C-18

CAPSULE U INTERMEDIATE SHELL PHATE B7212-1 (LONGITUDINAL)

CvCIAPH 5.3 Hypufic Iaqgmt Curve Prmit on 02106a= 03:15 PMPapi1

Coeffficints of Con 2

A=4 .42 BI=42S C==l3 TV= 14&39 D=OAIOE_00Equatim 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 7212-1Orifhati LT CwwlC U ucMe: nftm"2

20

A

1100

IO

400.0 0.0 300.0Temperalum In Dog F

Chmarp V-Netch Data

.I. QuudwL.

600.0

T'rMMUM

.0050.0075.00

100.00125.00150. 00150.00175.00200.00

1.0021.0027.0033. 5030.5037.5040.0040.0063.00

8. 5716.2121.7828.3735.8343.7343.7351.5658.80

-. 574.725.225.13

-5.33-6.23-3.73

-11.564.20


April 2008

C-19

CAPSULE U INTERMEDIATE SHELL PLATE BW7212-1 (LONGITUDINAL)

Pap 2Plant.Fadcy2 MacriakSA533Bl Heat B7212-1Odmnafoc. LT CapsukeU luen nkMn2

Charpy V-Notch Data

7ampe-s

200.00225.00250.00300. 00350.00400.00

59.0031.0071.5076.0030.0030.00

o W&

58.8065.0970.2677.4081.3183.30

MR"

.2015.911.24

-1.40-1.31-3.30

Caklcmi Cfetiat- .965


April 2008

C-20

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

CYVCRAPH 5.3 Hyp Ticbngt Curve Printed on 02/06t2CO 03:15 PMPapl

CoefdMints of Cone 3A-=42tI B= 41222 C=•156•6 TO =196L62 D=UOs0ta0

Equtiimis A + B' rrWm(T-ToA(CtDT))JUpper Shelf L•8.5.A L[anr Shelf ]=.R00Fzed)

Tamp.lR. 35 mdlh=167.9 Deg FFlt FwPecy2 Mated1: SA533BI Heat B7212-1

Odllt LT Capsue W B : nftur2200

15DAE

so

04--00.0 0.0 300.0

Temperature In Dog F

Chap V-Notch Data

600.0

¶wmwan

.0073.00

100.00125.00150.00150.00175.00175.00200.00

6.5019.0029. 5018.0034.5023.0034.5034.5039.00

Cw0u3.L.B

6.3714.5719.2424. 4430. 3930.3936.9236.9243.74

.134.43

10.26-6.44

4.11-7.39-2.42-2.42-4.74


April 2008

C-21

CAPSULE W INTERMEDIATE SHEUL PLATE B7212-1 (LONGITUDINAL)

Pap 2Plant Fadcy2 Maeiak SA533B 1 Hcat B7212-1

Odemiatln: LT Capsule: W luence: /cnt&2

Chamrp V-Notch Data

200.00225.00250.00300.00350.00400.00

37.5060. 0063.0070. 0071.0079.50

OmpIdL.

43.7450.5256.9267.6675. 1279. 75

-6.249.486.032.34

-4.12-. 25

Camdwunxf baffciM, - .966


April 2008

C-22

CAPSULE X INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

CYGRAPH 5.3 Hyperbolic Tangn Curvm Prit on MAW= 03:16 PMPage 1

Codeiits of Com' 4A=3M.21 I=3 3.C=107.31 'O = 1MM, D=OMiE00

Equtin is A S B • funb((T-To)CC+-fl)]Uppe ShaVLJL-=70. Loe Shelf L1L=A0u20d)

TamupL.R. 35 mils=1R&V Deg FPlant Fweiy2 Mtcdal: SASS3B1 Hca Bfl212-1

Ofrnhtio LT Caeic K PlXgMe: nftt2

aEIU

w

15D)

100

0 A0 ---

400.0 0.0 300.0 600.0

T¶mwan

.0072.00

I00. 00125.00125.00150.00150.00175.00200.00


Charpy V-Notch Data

-LEK Qupn~dLIL

2.00 2.2413.00 7.8621.00 12.3113.00 17.7713.00 17.7727.00 24.6327. 00 24. 6331.00 32.5034.00 40.66

-. 245. 141.69

-4.77-4.77

2.372.37

-1.50-6.66


April 2008

C-23

CAPSUE X IfNTEMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

Page 2Plant. FPafd2 Maa SA533BI Hat B7212-1Odmalt PLT C.aulk X Muen nkm^2

Chap V-Notch Data

DC-23

200.00225.00250.00350.00400.00450.00

33.0055.0063.0065.0073.0065.00

40.6648.2554.6667.4169.2069.93

-7.666.75H.34

-2.413.80

-4.93

Csrulaifm Cbrffi• m -971


April 2008

C-24

CAPSUZ INTERMmATE SHELL PLATE B7212-I (LONGITUDINAL)

CVGRAPH 53 Hypeolic Tag= Cmrve Pdmma on 021t6t20 03:17 PMPage I

Coefficients Of Cmrve 5A=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 FPFml FmEiy2 Mahtmi: SA533BI Eat B7212-1

Odmusiorn LT COMaI Z Mucn ntt2200

ISD

10

5D

04-400.0 0.0 300.0 600.0

Temperature In Dig F

Charpy V-Notch Data

T7uVOmuM

.0072.00

125.00150.00175.00190.00200.00210.00225.00

lcpi La

0011.005.00

12. 001. 0027. 0016. 0040. G041.00

CompQard LEL

.11.93

4.709. 3

17. 4123. 9528. 8533. 9641.50

-. 1110.02

.302.62

.593.05

-12.856.04-. 50


April 2008

C-25

CAPSUL Z INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

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

Cbarpy V-Notch Data

¶rmqau

250.00275. 00300.'00350.00400.00450.00

D-mt~dLB.

52.0064. 0063-0064.0067.0065.00

52.0959. 0762.9865.9566.6266.77

-. 094.93

.02-1.95

.38-1.77

Cmmkhui caab = M.98


April 2008

C-26

CAPSULE Y INTERMEDIATE SHELL PLATE F7212-I (LONGITUDINAL)

C RAH 5.3 Hypatolt Tangnt Curve PrNte on 02106a008 03:17 PMPage 1

Coc•fiients of Cm-vc 6A =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 FFlue Fwluy2 Mtedal: SAS3YB1 Hea B7212-1

Oiicukoi LT Cqskc Y FPmrne aC:tn2

1Wa

IL 0

50

0300.0-800.0 0.0 S00.0


Charpy V-Notch Data

600.0

TMwflmu

10.0050.00

100.00150. 00175.00180.00200.00210. 00225.00

]ipoLa.&

5.007.006.00

17.0014. 0018.0019. 0037. 0044. 00

-ampdked LIL

.21

.652. 619. 55

16.8618.7027. a;31.6938. 65

4.796.353.397.45

-2.86-. 70

-.. 095.315.35


April 2008

C-27

CAPSUE V INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

Page 2PlanutfPly2 Macria SA533B1 Heat B7212-1OdammilLT Capsule:Y Puence- nkM42

Charpy V-Notch Data

T"mhwamm

225.00250.00275.00300.00325.00350.00

31.0049.0061.0063.0068.0056.00

-LE

38. 6548.9556.3660.9063.4264.75

-7.65.05

4.642.104.58

-3.75

Cnudkncnbaefim -372


April 2008

C-28

CAPSULE V INTERMEDIATE SOELL PLATE B7212-i (LONGITUDINAL)

CVGRAPH .3 Hypfoic TaIn Curve Print on 02102M 03:18 PMPage 1

Cocffwicnts of Curve 7A=37A9 B=37SC=113.73 TO=2f.53 D=S.fE+00

Equtiwi is A + B 0 rrmh((T-ToX)CtfT))]Upper Shelf LJL=73 A Shelf LJL=.OW.Mh)

Temap.@L1- 35 mgifr'AA4 DogEFHatftPly2 Mtal: SA.33BI Hea BflI2-1

Oxnideni. LT Cipadc V Flucu: nicun22OO

150I

E0

0a-400.0 0.0 m00.0 o00.0

Temperaure In Dog F

Chmapy V-Notch Data

Tpmvum

50.00180. n210.00220.00225.00230.00230.00260.00265.00

UpEdLa

£0.0020.0029. 0028. O029. O042. 0049. 0055.00SI. 00

-•nmMLIl

2.9221.4230.3233.5635.2036.8643.4446.6248. 17

7.09

-1.42-1.32-5.56-6.205.145.56

11.312.83


April 2008

C-29

CASUE V INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

Page 2Pimt P•aty 2 MaUdat SA533B1 HIat B7212-I

Odenaim r LT Capsul& V Puence- nkt•A

Chamrpy V-Notl Data

2nv0.0

290.00290.00315.00340. 00370.00380.00

34. 0055.0068.0072. 0066. 0069. 00

55.2755.2761.0765.4969.2270. 14

ai

-21.27-. 276.936.51

-3.22-1.14

Caonzk OoCdfciml -3 -16


April 2008

C-30

UNIRFADIATED INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

CYVCRAPH 5.3 Hypernoc Tang•t Curve Prited on 02Mtf108 11:42 AMPape

Coofficnt9 Of Curve 1A=S& B m.SL CE= 376 TO=39.23 D= LOO

Equuaikais A +B C frmn((T-To•ACtfTl)jTempra-tum at 50% Sher = 393

lant FIrcy2 Mhmial: SA33BI Heat B7212-1Odcutiwi: LT Cqpeb: UNIRR Flouan: kmftr

VIf

125

1w

75

5D

25

0

0

/0

- 4 -J- - - - 4 4 - - -

0-MO.0 -200.0 -100.0 0.0 100.0 200.0 300.a 400.

Temperture In Dog F500.0 600.0

Charpy V-Notch Data

Tnmpemm

-60.00-50.00-25.00-25.00-10.00

.0020.0050.0060.00

3.0012.0022.0018.0025.0030.0040.0060.0043.00

8.5510.6217.7517.7523. 5928.1638.7256.4062.15

-. 551.334.25

.251.411.841.283.60

-14.15


April 2008

C-31

UNIRtADIATED InTRME4IATE SHELL PLATE B7212-1 (LONGITUDINAL)

Pag 2Plmat Farley 2 Murdalk SA533B 1 Heat B7212-1

Ofilawlan: LT Capsue UNIRR Fluenc nm=A2

Charwy V-Notch Data

TeMP-StB

75.00100.00125.00150.00210.00210.00210.00

rP=•qn ran ..

63.0085.00

100.00100.00100.00100.00100.00

QmumrdPanmUSbew

70.1431.0288.5893.3798.3398.3398.33

-7.149.98

11.426.631.671.671.67

Crinuldi Ckbmt- -W


April 2008

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 2A=-S& B=aS. C=10M04 T11=1503 D=0.0OK+00

Equatim is A + B'0 fl1(Y-ToAfCtJUf))jTcmplmx'u al 50% Shr= 150A

Wanl Fatky2 Mnfminl: SA533BI Heat B7212-Oamai•o LT Cqms c U Plenc: nzmf2

I'U

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0

Temperture In Deg F

Charpy V-NMlch Data

5u.0 600.0

T¶rmqn.

.0050.0075.00

100.00125.00150.00150.00175.00200.00

2.0017.0025. 0031.0038.0044.0049.0056.0058.00

CampowdPoma mws

4.7911.9711.2726. 8837.6849.8549.8562.0472.88

-2.795.036.734.12

.32-5.85

-. 85-6.04

-14.88


April 2008

C-33

CAPSULE U INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

Pap 2Pint Fley 2 MamtiaL- SA533B1 I-Ht B7212-1Odenta•d LT Capsuler U Pmuenc alcm2

Charpy V-Notch Data

200.00225.00250.00300. 00350.00400.00

73.0096.00

100.00100.00100.00100.00

Cowftaliw coffim - -M77

CmrmPMMs

72.8881.5587.9095.1698. 1599.31

.1214.4512.104.841.85.69


April 2008

C-34

CAPSULE W INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

CYGRAPHI 53 Hypeablic Tanmgt Crve Pdrnted on 02/222008 11:43 AMPage

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= 188AWant F•ty2 Mami: SA33BI HeaLt B7212-1

Ofiwtow LT Cqctk W Fhl: ftr2

12s

100

I16

It1

75

UO

25

o i -i + - -1 - I--1 -4- -4- 1 -'-1 -

-300.0 -20.0 -100.0 0.0 100.0 200.0 ioa 400.0 SOo.OTemperatmre In Dog F

600.0

clap V-Nidch Data

S caumwpfm mmrTa"rmma

.0073.00

100.00125.00150.00150.00175. 00175. 00200.00

2.007.00

13.0024. 0029. 0026. 0037. 0037. 00SO. 00

.644.351.57

13. 4826.3426.3441. 1341. 1357. 71

1.362.659.433.522.66-. 34

-4.13-4.13-7.71


April 2008

C-35

CAPSULE W INTERMEDIATE SHEOL PLATE il212-1 (LONGITUDINAL)

Pagp 2Plnt: larie2 MatdcriSA533Bl HatB72lZ-I

Odentazion: LT Capsule: W Rhmc=: n/cmA2

Charp V-Notfh Data

TMP'MUe ftWPmtpSar CamPmpem sho me S u

200.00225.00250.00300.00350.00400.00

49.0032. 0095.00

100.00100.00100.00

57. 7172. 7133.8895.2198.7099.66

-8.719.29

11.124.791.30

.34

Cinxltbn Cfciwabm -M.3


April 2008

C-36

CAPSULE X INTERMIEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

CVGRAPH 5.3 Hyperbotl Tang=t Cmve PdntMd on 0222U2( 11:43 AMPap I

Cocffidat of Cum-c 4A=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-IOdno LT Cqiwlc X luxenec: afmtf

I1fl

It

125

100

75

w

25A

0480.0 -200.0 -100.0 0.0 100.0 200.0 300.0


Charp V-Notch Data

400. 500.0 600.0

Tmqnm

.0072.00

100.00125.00125.00150.00150.00175.00200.00

mplaw Pam -

2.0015.0020. 0O20.0020.0025.0025.0030. 0035. 00

.864.628.64

14.6914.6923.8623. 8636.3150.92

1.1410.3011.365.315.311.141.14

-6.31-15.92


April 2008

C-37

CAPSULE X IZTEMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

Pagp 2Pint: Faly2 Maicat SA533B1 Hcat B7212-IOdenmilaLLT CapuleX Pmuence, nm

Chap V-Notch Data

200.00225.00250.00350.00400.00450.00

40.0070.00

100.00100.00100.00100.00

(0MlmdIFcM'eem

50.9265.3777.4597.4199.2099.76

-10.924.63

22.552.59

.80

.24

Cmclamt Ctdmism - .963


April 2008

C-38

CAPSULE Z INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

CYGIRAM 5.3 Hyperolic Tangmt Cmvd intd on O2 11:44AMPapg

Coefficimt of Cumve 5A= SE B=.SMLC=63.2 11T=2L5 D=M..+i0

qutizm is A + B 0 rlih(T-ToC+tm'DJTTempmma at 50% 8r= 29.0

amnt: Fm 7 2 Matml: SA533BI HatL B7212-1OdlWion: LT Cop=]= Z MME akcu'

125

100

75

50

I

25

-400.0 -200.0 -100.0 0.0 100.0 200.0 300.0

Temperature In Dog F400.0 o0.o 60.

Chmpy V-Notch Data

.0072.00

125.00130.00175. 00190. 00200. 00210.00225.00

hftPMn U-

2.005.00

10.0020.0025.0035.0030.0060.0060.00

.131.306.37

13.4325.4835. 4542.9750.8362.42

1.873.703.436.57-. 49-. 45

-12.979.17

-2.42


April 2008

C-39

CAPSU Z INTERMEDIATE SHELL PLATE B7212-1 (LONGITUDINAL)

Pap 2Plant :adly2 MazdilL SA533B I Heat B7212-1Odenafdw LT Capsule: Z Flu=e: n/cm'2

Charpy V-Notch Data

250.00275.00300.00350.00400.00450.00

80.0090.00

100.00100.00100.00100.00

om m Slwr

78.5588.9894.6898.8699.7699.95

1.45L. 025.321.14.24.05

Caftcbtm Cvdimt - -


April 2008

C-40


CVGRAPH 5.3 Hypebolic Tanget Curve Pinfed on 0212n2fl0 11:44 AMPape 1

Couffcirnts of Curve 6A=-S. B=SLC="SOZ T=210.91 D=-0.EiW

p4uiamib A + B 0 rr[n(T-ToA)C+t'))]Tempfal .-0- SM = 211.0

Hat Fuiey 2 Matmiul: SA533B1 Hea B7212-1Ozlsicatioz LT Capwle Y Piucuec: nkm"2

125

1i0

I'U75

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

10.0050.00

100.00150.00175.00180.00200. 00210.00225.00

2.005.00

15.0020.0020.0020.0030.0060.0065.00

.03

.171.208.15

19.3422.6339.3249.1063.66

1.974.83

13.8011.85

.66-2.63

-9.3210.90

1.34


April 2008

C-41


Page 2PLnt FPat 2 Mntcrial SA533B1 Hcat B7212-1Odm=OL LT CapmuIe Y Munce nkle2

Charp V-Noth Data

225.00250.00275.00300.00325.00350.00

mwrpM Show

50.0090.00

100.00100.00100.00100.00

0OWMAPM Shew

63.6682.5692.7597.1998.9499.61

-19.667.447.252.811.06

.39

Cauatium coarid -.. M


April 2008

C-42

CAPSULE V INTERMEDIATE SHELL PLATE R7212-i (LONGITUDINAL)

CYGRAUL 5.3 Hypfbolic Tangt Cue Prind on GWZO 11:50 AMPage 1

Cocfficta of Cnrme 7A=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

i'K

125

100

75

5D

25

U

U

- - I I I -4- -4-0-40.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0

Temperatre In Dog F00.O 600.0

Tmwam

50.00180.00210.00220.00225.00230.00250.00260.00265.00

Charpy V-Notch Data

a penm Stam CaupnmPuvmnaw S

2.00 .4820.00 17.4930.00 33.6130.00 40.4540.00 44.0050.00 47.6170.00 61.9390.00 68.3230.00 71.57

1.522.51

-3.63-10.45-4.002.398.07

21.488.43


April 2008

C-43

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

Pag 2Plint: Pady 2 MiaL SA533B1 Heat B7212-1OdentaimtLT CapaulPeV Puicm ncmA2

Chap V-Noth Data

T290.0

290.00290. 00315.00340.00370.00380.00

-l put~cnges

50. 0075.00

100.00100.00100.00100.00

83.9083.9091.5295.7298. 1798. 62

-33.90-8.90

3.484.231.831.38

cab.aab Cot mt - .930


April 2008

C-44

UNIRRADIATED INTERMEDIATE SHELL PLATE B7212-1 (TRANSVERSE)

CVGRAP 5.3 Hyp•etooic Tangent Curve Prd on 026OM 03:56 PMPage 1

CoDeiciztz Of CurO 1

A = 4L6 B =f46A4C=9L3•.S T073ILM6 D =00G0E400pugicnis A +B B VVrmh(r-To)C+DT))]

Upper SbcHfEM-95.OVUcd0 Low slfEumm=22(ftedTemp @30 ftf&-l-7.5 Deg F TemapO5 ft4-=33.6 Deg F

Flent: Fty2 Meial: SA533B 1 Bela Bfl2-1Odut•o: TL CqudC: UNIR Flbcem: nn2

300

290

4r2

Io

U,z

SOD9D

0.-60.0 -200.0 -100.0 0.0 100.0 200.0 300.0

Temperature In D0g F400.0 500.0 600.0

Charpy V-Netch Data

hptcVm cCmYNTmiMmum

-50.00- 50. 00- 30. 00

.00

.00

.00

30. 0030. 0030. 00

18.5015.5019.0035. 0034.5030. 0043.0048.0052.00

15.4715.4715.44733.,3433. 3433. 3448. 1648. 1648. 16

3.03.03

3.531.661.16

-3.34-5.16

-. 163.84


April 2008

C-45

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

Pap 2Plant-Padcy2 MaMtiak SA533B1 HcatB7212-I

Odamtafi:TL CapaLUNIER Ph== nkat2

Ch"rpy V-Notch Data

Thu*Cn=

100.00100.00100. 00150.00150.00150.00210.00210.00210.00

kIw CYzN

76.5074.0070.0095.0098.00

106.0019-0094.00

38.00

78. 4978. 4978.4988. 8188. 8188. 8193. 2793.2793. 27

-1.99-4.49-8.49

6.199.19

17.19-4.27

.73-5.27

Cumzum Qbcmu•S, .980


April 2008

C-46

CAPSULE U INTERMEDIATE SHELL PLATE F7212-1 (TRANSVERSE)

CVYIAP 5.3 Hypubolc Tkgn Curve P=nd on 02AO6I2OO 03:57 PMPage, 1

Cofficients of Carv 2A=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 [email protected] ft-.hs=l81.9 D1 g FF@PaIFu'ly2 Maie: SA33BI HEa Bf2-1

OdmaadonwTL Cqumc U Pluanc: nitnt2a

300

420

1w

SD

-00.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 50.O 600.0Temperture In Dog F

Chmrpy V-Notch Data

Tmwensu

50.0075.00

100.00110.00125.00150. 00175.00175.00200.00

1low Cw

15.0022.5021.5032.5033. 5037.0046.0042. 5049.50

CbmpaudCVN

13.2118. 3925. 0127.9932.7040.7048.1448.1454.36

1.794.11

-3.514.51

.80-3.70-2.14-5.64-4.86


April 2008

C-47

CAPSULE U INTERMEDIATE SHELL PLATE B7212-1 (TRANSVERSE)

Pap 2Plant PFadey 2 Material SA533B1 Hat B7212-1Odimn.iornTL Capsulk: U Rucume: ncm'c2

Charpy V-Notch Data

225.00250.00275.00300.00350.00400.00

1MOnCYN

69.0067.5068.0067.0069.0073.00

€-Mpa• CYN

59. 1262.5064.8066.3167.8968.51

9.885.003.20

.691.114.49

CmOzhImUMi eirgi - .977


April 2008

C-48

CAPSULE W INTERMEDIATE SHELL PLATE B7212-I (TRANSVERSE)

2W0

~20

0150

100

W

CVGRAPH 5.3 Hypubc Tangent Curve nd on 020628 03:8 PM

Coefficicuix of Curve 3A =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 FPlait PFdey2 bMtr: SAS33B1 Bea 7B7212-1

Odmisi , IL Cqumak W F c:n: m2

04110.0 -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

25.0076.00

125.00150.00150.00175.00175.00200.00200.00

- CvN

6.0016.0029.0030.0030.0037. 0027.0030.0033.00

5.119.78

19. 1926. 3926.3934.8834.8843.8343.83

.826.229.113.613.612.12

-7.83-13.83-10.83


April 2008

C-49

CAPSULE W INTERMEDIATE SHELL PLATE B7212-1 (TRANSVERSE)

Pag 2PanFtadey 2 M ia SA533B1 Hat B7212-1

Oderaziou: TL Capsule: W Rluen=: nkmA2

Charpy V-Notch Data

210.00225.00250.00300.00350. 00400.00

-np CYN

a5. o068.0072.0078.0068.0034. 00

Comitd CYN

47.3052.2059.2368. 4272.6874.41

-12.3015.8012.779.58

-4.689-59

CWiM, efci -=.920


April 2008

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 4A=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 FFlue •mFcy2 MOWW:,SAS33BI HLt B7212-1

Or"m TL C4ApC X Plucme: ntnA2

IS

so

-M00.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0Tempersurs In Dog F

Ch"rpy V-Notch Data

Tmwan

.0072.00

150.00175.00175.00190. 00200.00200.00210.00

upW CYN

3.0019.0024. 0018.0023.0030.0023.0026.0038.00

D=muedCVN

2.212.458.93

18.8618.8628.2133.3235.3242.43

.7916.5515.07

-. 864.141.79

-12.32-9.32-4.43


April 2008

C-5 1

CAPSULE X 1 PlATE SHELL PLATE BW7212-1 (rlANSVERSE)

Pap 2Plat Fadcy 2 Maeak SA533B I Heat B7212-1OditatonIL Caplsule: X Men n/km2

Charpy V-Notch Data

210.00225.00225.00250. 00350.00450.00

45.0055.0063.0069.0067.0075.00

-•qp wlCVN

42.4351.7951.7961.7568.4068.50

2.573.21

11.217.25

-1.406.50

CaOMMIla Cbeffti - AM3


April 2008

C-52

CAPSULE Z UITERJMEDIATE SHELL PLATE B7212-1 (TRANSVERSE)

CVGRAPH 5.3 Hyperolic T¶bgt Cve PMd on 02106IO 04:01 PMPageI

Coefficients of CUMv SA=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#z4TcmnO3Oft-l-b=113 DcgF TempOSO fi-Ihs=)232 Deg F

Flun Fwl"y2 Mateia: SAW3B1 EaL B212-1OdmumIo :TL Cqsut Z Pbnea nklm2

4

ma

4100.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0Temperfture In Deo F

Charp V-Notch Data

TOnqESm

.0072.00

125.00150.00175.00190.00200.00200. 00210. 00

omqpmUCVN

6.004.00

17.0022.0028.0031.0018. 0025.0044. 00

2.363.628. 66

14.5623. 8130. 8635.7935.7940.67

3.64.33

8.347.444.12

.14-17.79-10.79

3.33


April 2008

C-53

CAPSULE Z INTFERMOIATE SHELL PLATE B7212-1 (TRANSVERSE)

Page 2Plant Parly 2 Matriak SA533B1 Hmt B7212-1OdemailoTL -Cape: Z Financ: Wkm'2

Charm V-Notch Data

Tempenme

225.00250.00275.00300.00350.00400.00

]nl-CYN

61.0056.0064.0076.0069.0062.00

SowwmCVN

47.4956.3761.8864.8767. 1367. 65

13.51-. 372.12

11.131.87

-5.65

Csuktam ,,ffic .9a2


April 2008

C-54

CAPSULE Y INTERMEDIATE SHELL PLATE B7212-1 (TRANSVERSE)

CVGRAP 5.3 Hyperbolic Tangemt Curve Prieda on 02A3/20 04:01 PMPape1

CoeFfcmts of Corve 6A = 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 FFlune Plpy2 MaeW: SA533B1 HEat B7212-I

Odnzwukm TL Cpwlc T MiwOM: uhftr2V00

8100

so

0 r

-•30.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 5w.0 eo0Temperatue In Deg F

Chrpy V-Notch Data

FN caupodeCN

.00100.00150.00150.00175.00200. 00200.00220.00250.00

2.005.00

21.0017.0015.0017.0010.0023.0044.00

2. 454.95

10.4710.4715.6522.5822.5828.9038.11

-. 45.05

10.536.53-. 65

-3.53-12.58

-. 905.89


April 2008

C-55

CAPSULE Y INTERMEDIATE SHElL PLATE B7212-1 (TRANSVERSE)

Page 2Plant Parly2 M a SA53D1 H]atB7212-1Odmwin.TL CapsulreY Puence n/mA2

Charpy V-Noatch Data

Thqmapm

260.00275.00300.00310.00350.00375.00

44. 0054. 0033.0050. 0051.0053.00

Comp*6CVYN

40. 7844. 2548. 5649.8152.9253.15

3.229.75

-10.56.19

-L.924.15

Camukn (a•tft . A8


April 2008

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 7A = 3- 6 B=33AC=42M0 TO=214f3 D=tMOOE.t0

Eustion is A t B' rln((T-ToA(CtDT))jUppc Self~nmgy9O=S.(md) Lo~w SMff umu=2.2(Fzmm)

Tmlp3O ftDm=2071. Dcg F Tomp@50 ft-lbs.=2.3 Deg Fla: Pu•ly 2 Mat: SAS3SBI Heat Bfll2-1

OdenUoa: TL Csqzlc V FlucM: usf2

A,IT

Uan

o 1400.0 -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

100.00200.00205.00215.00225.00230.00240.00260.00275.00

9.0021.0030.0036.0036.0055.0055.0066.0059.00

-CampowdCYN

2. 4124.2927.9335.7343.5247.1453.4962.0163.38

6.52-3.292.07

.27-7.52

7.861.313.99

-6.31


April 2008

C-57

CAPSULE V INTERMEIATE SHELL PILATE B7212-1 (TRANSVERSE)

Page 2Plant 1:t! 2 MoaraL- SA533B 1 Heat 7212-1Odenai•or. ILCapsule. V mum= nkem2'

Charpy V-Notch Data

280.00305.00345.00375.00400.00410.00

69.0050.0065.0070.0061.0079.00

(-mpubd CYN

66.1168.0968.8668.9768.9968.99

Difrma1i

2.89-18.09

-3.861.03

-7.9910.01

Cskonfwmi rcisS m M37


April 2008

C-58

UNIRRADIATED INTERMDATE SEM PLATE 17212-1 (TRANSVERSE)

CVYCAH 5.3 Hypebolic Tanget Cuwe l•P d on WOW= 04:15 PMPap 1

Coeffici•ets of OMNC 1A=36M B=36.C=10037 "0=30.36 D=0OOAOO

Equadi is A t B' rrbma(T-ToAC÷tI)jIUpper Shr.] L.JL=72.7 Lnw Shlaf I.B.=.O(rcd)

Temp.OL.- 35 mk=(Z.7 Deg FPlane F'loy2 MaMtil: SA533BI HeaL B7212-1

Oduatto: TL Cycea: UNIRR FluMec: nftr200

I1

I

5D

0 4--00.0 0.0 3o0.o

Temperature In Deog F

Chrmy V-Notch Data

600.0

TmmnMM

-50.00-50.00-50.00

.00

.00

.0030. 0030.0030.00

1les LI.

11.0011.0011.0027.0027.0027.0035.0036.0039.00

1M2,.29

12.2912.2912.2925. 7225. 7223. 7236.2036.2036.20

DMaM

-1.29-1.29-1.29

1.231.281.28

-1.20-. 202.80


April 2008

C-59

UNIt]RADIATED INTERNM IATE SELL PLATE 17212-1 (TANSVERSE)

Page 2Plant"Paey2 Matcial SA53_B1 tat B7212-I

Odiflaicn:TL CaplzkUNIRR Pi== Wnt2

Chwar V-Notch Data

100.00100.00100.00150.00150.00150.00210.00210.00210.00

10pul L.R.

55.0056. 0054. 0067.0068.0076. 0068.0070. 0069. 00

CO58. 4I.

58.0458. 0456. 0466. 4466. 4466. 4470-6470- 6470.64

-3.04-2.04-4.04

.561.569.56

-2.64-. 64

-1.64

cbuchamscbefims0 - 991


April 2008

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 PMPap 1

Coc-ikiEnta of Cam 2A= 3U4 B=34.14C =ENL95 T0=144.=1 D = OM•b00

qut•uim is A +B r m((T-To)•C+DTD)IUpIr ShaltLJL.=6B3 Lnwe Shelf 1.=.&00430d)

TanptL.R 35 mils=147.0 DegFPlant: Fey•2 Mafteda: SASS3B1 He B7212-1

Owujtmklo iL CqWlC U FleAnc: nibnt 2

150

I

UISOSIw50

o0~-400.0 0.0 300.0Tempeature In Deg F

Charpy V-Notch Data

600.0

TmwMpMu

50.0075.00

100.00110.00125.00150.00175.00175.00200.00

]rqpmlL.a

10.5015.5020.0026.5030.0030.0040.0039. 5050.00

IQUlM LIR

9.1213.7120.0322.9427.6736.0444. 1944. 1951.26

1.39

1.72-. 033.562.33

-6.04-4.19-4.69-1.26


April 2008

C-61

CAPSULE U NERbMDIATE SHELL PLATE B7212-1 (TRANSVERSE)

Pagp 2Plant Fmdcy2 M=r SA533B1 Heat B7212-1OdenmmcaTL Capsule: U Flunm nlcnm2

Char•y V-Notch Data

225.00250.00275.00300.00350.00400.00

69.5062.5067.0063.5060.0068.50

56. 7960.7963.5165.3067.1567.86

12.711.713.49

-1.80-7. 15

.64

cQuika oCdwiaec, -.372


April 2008

C-62


CVGRIAPH 1.3 Hypefbli Tangent Cumvo Pdmud on 02/0612008 04:17 PM

Coeffiximts of Curve 3A =i343 B = 341.53C=144.7 TO=I1IM33 D = 0.00E40

Equatio is At +B p '•f(T-ToDACtDThIrUppc Shalt LJ=69.1 LMw Shelf L.=.0=,Ozcd)

Tamp.OL 35 mils=3.3 Dog FFlanct:icy2 Medml: i 1SA BI Ea B1212-1

Odwmnaio TL CqepsA W PiMw: nkr2

12W

100

D II

IJElI

040.03, 0.0 300.0 600.0Temperature In Deg F

Chmrpy V-Notch Data

25.0076.00

125.00150.00150.00175. 00175.00200.00200.00

-no LE]

7.0015.0025.0030.0027.0038.0027.5030. 5030.50

co-lmJL

7. 1413.0621.7327.1727. 1733.0233.0238.9638.96

nMn

-. 141.943.272.83-. 174.98

-5.32-1.46-8.46


April 2008

C-63


PagB 2Plant-Padey2 Mtia SA533B1 Hcat• B7212-1

Odemtafia: TL Capsule: W PlFu: nt2

Charpy V-Notch Data

Tempeamu

210.00225.00250.00300.00350.00400.00

lzptdL.

36.5053.5058.5060.0061.0064.00

COmwulad LJL

41.2944.6549.7957.8562.9565.86

-4.791.851.712. 15

-1.95-1.86

Camw Cimxm9.rffic Mm


April 2008

C-64

CAPSULE X INTERMEDIATE SHELL PLATE B7212-1 (TRANSVERSE)

20D

15DIa

aI100

5D

CVGR"H 5.3 Hyperolc Tangent Curve Pritd on 02A060008 04:17 PM

Coeficients of Cne 4A=3LA3 B =31A3A C = 124B4 TI=2a2,42 D =O.00_,

Egqnum is A +aB I Dnh((T-ToAC+-]DJUpper Shelf Ljl.62.9 Lower Shelf L.R=A0(mad)

[email protected]. 35 mils-a14.7 Deg F]Plan Fuosy 2 MacENl: SA3rBI Hea B57212-1

OdnMMon' T Cwwlc X Flumes: njbxt2

AA

0-M0.0 0.0 300.0 600.

Temperature In Deog F

Chmrp V-Notch Data

TmflMa

.0072.00

150.00175.00175.00190.00200.00200.00210.00

jap I.1K

4.0012.0023.0023.0021.0036.0023.0027.0023.00

2.447.12

19.3125. 1225. 1228. I131.3231.3233.84

1.564.833.62

-2.12-4.127.19

-1.32-4.32-5.84


April 2008

C-65

CAPSULE X INTERMEDIATE SHDELL PLATE B7212-1 (TRANSVERSE)

Page 2Plant. PFmy2 Macriat SA533B1 Hcat B7212-1OtmtunTL CaulerX mPlnen nk/m2

Charpy V-Notch Data

210.00225. 00225.00250.00350.00450.00

10taLK.

30.0040. O044. 0053.0054.0062.00

33.8437.5437.5443. 2957. 6161.72

-3.842.466.469.71

-3.61.28

ccawhjioao C3icm - 944


April 2008

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 5A =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 FFitn P1 7 2 Materl: SA533BI eaC B7212-1

Odmalk TL Capuel Z PlAu nkft'22W

ISOA

IL 100

so

0 4-400.0 0.0 300.0

Temperatur In Dog F

Chorpy V-Notch Data

600.0

Trayspm.

.0072.00

125.00150.00175.00190.00200.00200.00210.00

lapd t.&

2.00.00

7.0015.0022.0022.0014. 0019.0030.00

.191.3335.52

10.0216.8922.0225.6823.6829.37

1.81- 1. 31

1.414.935. 11-. 02

-11.61-6.61

-63


April 2008

C-67

CAPSULE Z INTERMEDIATE SHELL PLATE B7212-1 (TRANSVERSE)

Page 2Plant PFadcy 2 Maeriak SA533B1 Heat B7212-1Odemori-T, Capsuar Z luence: nkcmn2

Chary V-Notc Data

Tepeem• IQW• E. CLmad L.E.

225.00250.00275.00300.00350. 00400.00

44.0045.0043.0055.0052.0050.00

34.6942.0647.0650.0252.5053.16

9.312.94

-4.064.9.-. 50

-3.16

Cawk1m cbeffici•-.g61


April 2008

C-68

CAPSULE V INTERMEDIATE SHEML PLATE B7212-1 (TRANSVERSE)

CVGRAPH .3 Hype Tangent Cmrve Pdn on 210fi 04:18 FMPANe 1

Coe•fcekmts of Carvc 6A= 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 FFPlan-ltcy2 MateOW: SA533BI Ha B212-1

OdeItSUon: TL Cquwkc Y Furnce: sft220

I.100

s

,I

0 -o.0-0.0 300.0

Temperature In 0Dg F

Chap V-Nutch Data

600.0

76pmOSNn

.00100.00150.00150.00175.00200.00200.00220.00250.00

IPlt LK.

4.004.00

14.0012.0010.0015.0013.0022.0036. 00

.252.677.877.87

12. 5918.7018. 7024.0931.64

3.751.336.134.13

-2.59-3.70-5.70

-2.094.36


April 2008

C-69


Pag5 2Plant. aty 2 MatIcak SA533B1 Hct B7212-1OdemattoilTL CaPOuIeY Phuence n/mr2

Charpy V-Notch Data

260.00275.00300.00310.00350.00375.00

37.0042.0034.0041.0043.0043.00

- LaB

33.7836.5139.8640.8243. 1943.90

Di S

3.225.49

-5.86.18

-. 19-. 90

Ca s CQemicdM - -%7


April 2008

C-70

CAPSULE V IN TAEREIATE SDELL PLATE B7212-1 (TRANSVERSE)

ISO

IL 100

D

5O

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.•0R0Equatkis 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 IB7212-1Odnilot TL Cqmwlc V Finme: uibn"2

W I0,M0.0 0.0 300.0

Temperture In Deog F

Charpy V-Notch Data

600.0

TRmwa

100.00200.00205.00215.00225.00230.00240.00260.00275.00

IMmOUeL.R

11.0022.0030.0034.0036.0048.0047. 0058.0050.00

.3224. 3227. 7234.4740.5343.1447.4252.5754.43

a-

10.68-2.322.23-. 47

-4.534.86-. 425.43

-4.43


April 2008

C-71

CAPSULE V INTERMEDIATE SnHELL PLATE B7212-1 (TRANSVERSE)

Pag5 2Plant FPIey2 Mawlai SA533B1 Hat B7212-1Odenm T Capsule V Pluen cet

Charp V-Notch Data

280.00305.00345.00375.00400.00410.00

56.0046.0058.0056.0060.0059.00

CompudLa-

54.8255.8456.2256.2756.2856.28

1.18-9.84

1.73-. 273.722.72

Ca]ukfism Cdfl Mt - -955


April 2008

C-72

UNIRlIADIATED) INTERNMIATE SHIELL PLATE P7212-i (TRANSVERSE)

CVYGAP 5.3 Hypebolic Tangent Cum Prdi on 0210W602 04:07 'PM

Cocficients Of CaNe 1A= 0& B =S&.C=3L26 TO=-49M9 D =M01)0E,

Eq aizn is At B* P'snb((T-ToA)CDTl)]Tempfnmc ma 50% Shem = 49.7

Plnt Fas. 7y 2 Mahna: SAS33BI Heal B7212-1Odeadion: TL Cqxul: UNIRR Flues.: nk~cm'

I'U

100---

75

25-_ _ __ _0 4 - 4 4 - - -- - 4 4 4 -

4100.0 -200.0 -100.0 0.0 100.0 200.0 366.0 400.0Temperature In Dog F

in0.0 600.0

Charpy V-Notch Data

-50.00-50.00-50.00

.00

.00

.0030.0030.0030.00

12.0012. 0012. 0027.0025.0025.0032.0035.0043.00

8.801.808.80

23.7723.7723.7738.6638. 6638.66

-fndd

3.203.203.203.231.231.23

-6.66-3.664.34


April 2008

C-73

UNItRADIATED INTERMEDIATE SHELL PLATE B7212-I (TRANSVERSE)

Pap 2Planti Fafy2 MatrUiakSA533Bl H1at B7212-1

Odaratom: It CapauleUNIRR Pluene nAMA2

Charpy V-Notch Data

"]oweamu Impa Pam= Shm c-mpmd Psufm Shm m"nnu

100.00100.00100. 00150.00150.00150.00210.00210.00210.00

73.0073.0069.00

100. 00100.00100.00100.00100.00100.00

76.5076.5076.5091.3291.3291.3297. 7397. 7397. 73

-3.50-3.50-7.50

8.681.681.682-272.272.27

CMMIAfM cberk- .99


April 2008

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 2A=SE. B=S0 C=95.113 fl=19.L72 D =MOEO.+O.

Equ•t•i is A + B * ITI'mnw-TDAC+DT))jTcmpflmi at 50% S,= 159.8

Plant: Finly2 Matmial: .SA53BI Hte B7212-1Odcuzmtow It Cqwde U Plane: nknt2

i

-300.0 -200.0 -100.0 0.0 160.0 200.0 300.0 4m.0 uo.O 600.9Temperfture In Dog F

Chmrpy V-Noch Data

TrnM

50.0075.00

100.00i10.00125.00150. 0017s. 00175.00200.00

1mpn Plare Smr

16.0023.0027.0031.0037.0037.0046. 0048.0057.00

amqpum•mP-c -mr

9.0614.4222.1726.0132.5244.9157.9657.9669.99

6.94A.Se4.834.994.43

-7.91-11.96

-9.96-12.99


April 2008

C-75

CAPSULE U INTERMEDIATE SHELL PLATE B7212-1 (TRANSVERSE)

Page 2PlantF-Parly2 MaEria 3SA533B1 Hcat B7212-1Odamtrn.TL Capsule:U P nk/cmA2

Chamrpy V-Notch Data

225.00250.00275.00300.00350.00400.00

Cmplu•u Pcm Sbew

100.00100.00100.00100.00100.00100.00

79.7886. 9791.8695. 0298. 2099. 36

20.2213.033.144.931.80.64

Camult CmfsFcim -, .961


April 2008

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 3A=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 B7212-1OdoWuowi TL Cqpm•m W Flon nfkcr2

I'U

125-__

100

75 /

25

000

400.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 S0.O 600.0Temperature In DM F

Chmrpy V-Notch Data

Teunmamw

25.0076.00

125.00150.00150.00175.00175.00200.00200.00

2.0011. ao20. 0027.0024. 0032.0028.0034. 0036. 00

(amlmlell lPMM Smt

.311.66

7. 8216.2116.2130.6330.6350. 1130. 18

fl-a

1.699.34

12.1810.797.791.37

-2.63-16.18-14.18


April 2008

C-77

CAPSULE W NERMEDIATE SELL PLATE B7212-I (TRANSVERSE)

Page 2Plant Fadey2 Matldak SA533B1 Heat B7212-1Odentauion: TL Capsule: W Pluecce: n/nA2

Charpy V-Notch Data

210.00225.00250.00300.00350.00400.00

49.0090.00

100.00100.00100.00100.00

58.3569.6883. 9896. 4799. 3099.86

ina

-9.3520.3216.023.53

.70

.14

Coaukilm a ewxiM -358


April 2008

C-78

CAPSULE X INTERMEDIATE SHEll, PLATE B7212-1 (TRANSVERSE)

CVGRAPH 5.3 Hypebolic Tangnt Curve Pried on 02100 04:09 PMPape 1

CoefFmicits of Carve 4A=SL. Bn=aSLC = TO =2s D = At}0S0

Nut'sw is At +B B [T3(T-TiAC÷DT))1]Tcmpmnmx at.0 SbVr= 203.0

PlantFlc'y2 Mat•a•i.SA533B1 Heam B7212-1Oilimbdo It Cqmlc X Fbuenv, akftm2

125

100

I*1£a

75

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

.0072.00

150.00175.00175.00190.00200.00200.00210.00

2.0010.0020.0025. 0030. 0035.0035.0040. 0045.00

.00

.064.65

16.8916.8932.3743.8743.8760. 00

UflhuSS

2.009.94

15.35a. it

13.112.63

-10.87-5.87

-15.00


April 2008

C-79

CAPSULE X TERNMDIATE SHELL PLATE B7212-1 (TRANSVERSE)

Page 2Plant PFly 2 Matelat SA533B IHet B7212-1

Odmiaon TL Capsule- X Puacae ntm'2

Champy V-Notch Data

210.00225.00225.00250.00350.00450.00

puFe rnm Shm

45.0095.00

100.00100.00100.00100.00

compedra mtms

60.0077. 9477.9493.6499.98

100.00

-15.0017.0622.06

6.36.02.00

Caukila c efficic -350


April 2008

C-80

CAPSULE Z INTERM]EDIATE SHELL PLATE B7212-1 (TRANSVERSE)

CVGRAPH 5.3 Hypebolic ng Curve Pdrn on02tD6t2008 04:10 PMPageCocfficicit Of Qnvc 5

Af=fS& Br=S& C=46.47 T=2209M1 D =0MOEU0OEquadw is A +B 1 0 rraabT-Tl)bCtDr))J

Tcmpzmu at 80 Sw% = 209.7PlantFwlcy 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.0 600.0Temperaure In Dog F

Charpy V-Netch Data

Ta-mu

.0072.00

125.00150.00175.00190.00200.00200.00210.00

bps Panfl mS

2.0010.0010. 00[5.0020.0035.0030.0035.0045.00

.Ol

.272.557.14

11. 3930. 0639.8039.8050.41

1.999.737.457.16[.614.94

-9.10-4.80-5.41


April 2008

C-81

CAPSULE Z INTIERMEDIATE SHELL PLATE B7212-1 (TRANSVERSE)

Page 2Plant. Fadey2 Macrisk SA533B1 Heat: B7212-1Orentaor"ITL Capaule: Z P•ue=e: n/cm&2

Charwy V-Notich Data

225.00250.00275.00300.00350.00400.00

1W rOeSM

30.0030. 00

1O0. 001OO. 001O0. 00100.00

campmaed enacmSbes

65.9885. 0594.3498.0099.7699.97

14.02-5.05

5.662.00

.24

.03

Cswblmkxen m ,i, - -986


April 2008

C-82

CAPSULE Y INTERMEIDATE SHELL PLATE B7212-1 (TRANSVERSE)

CVCIRAPH .3 Hyperboli Tangent Cun rPvensedon 02/106t 04:10 FMPap 1

Ccdfts of Curm 6A= SL B=ESL C-=64.93 ¶1=234LO D =a.0E+00

Equiam is A + B' rrmnb(Or-To)ACYDT]TcmpmfMx It 50% Smr =234.1

Plant: Fuey 2 Matedl: "A533B1 Heal B7212-1Odaudoa TL Cqwlc Y Finn: ujb'2

I'Uaa

125

100

75

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


Charpy V-Notch Data

.00100.00i50.00150.00175.00200.00200.00220.00250. 00

ptan Sm

2.005.00

10. 0015.00[5. 0020.0025.0040. 0060. (0

ca~mlM P lr Show

.071.586.996.99

13.9623. 9523. 9539.3562.04

f-iguefal

1.933.423.011.011.04

-.. 95-. 95

.65-2.04


April 2008

C-83

CAPSULE Y INTERMEDIATE SHELL PLATE B7212-1 (TRANSVERSE)

Pagp 2Plant. PFacy2 Ma -aSAM33B1 Heat B7212-1Odmawir TL Capsult-Y PNuence. n/cmA2

Charpy V-Notch Data

DiMM

260.00275.00300.00310.00350.00375.00

65.0090.0030.0095.00

100.00100.00

68.9977.9388.4191.2191.2798.72

-3.9912.07-8.413.192.131.23

CsukOhmi beff: - .991


April 2008

C-84


CVYGCAPH 1.3 Hyputolic Tangent Curve PrnS on 02OrOO 04:11 PMPage 1

Coffimnts of Curmv 7Af=S0L B= =SLC= X46 TO =218.5 D =O.M0E+00

Hquta~mis At+ B'* Erun(C-ToAKCDTIYFDTempzat -.V0% Sbcr= 218.6

Plait: Faley 2 Material: SAS33BI Hat B7212-1Odnhlot IT CAWkC V Flsnace: uftm"2

I'U

400.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 600.0 600.0Temperaure In Dog F

Charpy V-Notch Data

100.00200.00205.00215.00225.00230.00240.00260.00275.00

Iva WCMma

10.0020.0030.0050.0060. 0070.0075.0090.0090.00

campow• Fwc= Showr

.1526.6032. 2145. 2138.8265.2676.4890.6995.69

9.85-6.60-2.234.791.184.74

-1.48-. 69

-5.69


April 2008

C-85

CAPSULE V INTERMEDIATE SHELL PLATE B'7212-1 (TRANSVERSE)

Page 2Plant:Parlcy2 MaiadaltSA53311 Heat B7212-1Odweumtoln•Th Capsuk V Pluenr f/MA2

Chary V-Notch Data

Tasmm

280.00305.00345.00375.00400.00410.00

95.0030. 00

100.00100.00100.00100.00

comPmt SPao=m

96.6999. 1499.9099. 98

100.00100.00

DiUffeEauS

-1.69-19.14

.10

.02

.00-.00

Caonms (befcicnt , .a82


April 2008

C-86

UNEDATED (WELD)

250

120

~16

1 100

CVGRAPH S.3 Hyp ic TanM Curve Pinted on 0206t20 04:55 PM

Codefleicm of Carve 1A=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=-34.5 Dog F Temp@_S0 ft.ibas-S.4 Deg FPlnt: Fadby2 Matrial: SMAW Heat: BOLA

Od=atm NA CWWC UINIERR Flmo nfcm"2

oro

40

o# ;'r0

0°

04100.0 -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

-100.00-50.00-25.00-10.00

10.0025.0040.0050.0075.00

1.0016. 0042.0050.00

109.0068.00

124.00133.00144.00

4. 9311.9939.0956.8283.74

102.42117.21124.60135. 91

3.07-2.992.91

-6.8225.26

-34.426.799.409.09


April 2008

C-87

UNIRRADIATED (WELD)

Pagp 2Plant FPaicy 2 Manial: SMAW Heat BOLA

Oreitadon: NA Capmue: UNEIR Flumcc nlMcn2

Chap V-Notch Data

Thmpemc

100.00150.00150.00175.00210.00210.00210.00

npd CYN

132.00131.00150.00154.50154.00153.00137.00

Comp•bdCVN

140.80143.52143.52143.82143.95143.95143.95

-1.80-12.52

6.4310.6310.059.05

-6.95

Cwnklamm Coeficiu -m SM


April 2008

C-88

CAPSULE U WELD METAL

CVGRAPH 5.3 Hyperbo:ic TgM Cuve Prmemd on 0210W=t0O 04:55 PMPap 1

Coefmiiemts of Cmurv 2A=-67.1 B= 64.9C=96.1 TO =-.47 D=0.Oi)_40

Egumign is A + B r [I'mnr-To(C+tDT)JUpper Sheff lml = 132.0(Flwza) LawUe Sbhefa ,-p=Q2

Temp@30 ft-lw-2.9 Deg F TempOSO ft-la-2&L3 Deg FPlant Fmady 2 Maedal: SMAW Heat BOLA

Odmtnimo NA Caauk: U Flubcu uftml2

2W

p150£

9100

Rico

o0 ~ -4- i- -'--- - i-I--- i - - - 4--400.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0

Temperature In Deg F500. 600.0

Charp V-Notch Data

- 50.00-25. 00

.00

.0025.0050. 0050.0075. 00

100. 00

13.0079. 0095.0036. 50B9. 5035. 0096.00

112. 50108.00

comulodCVN

36.3350. 1167.4267.4283. 9198. 3698.36

109.66117.73

D])i1mm

-23.3323.1227.53

-30.925.59

-13.36-2.362.84

-9.73


April 2008

C-89


Plant Fade 2Oriemion: NA

Pago 2Mat'ial: SMAW Heat BOLACapsule: U Fluence: nlat2

ChaMrpy V-Notch Data

125.00150.00175.00200.00250.00300.00

1kEtCVN

140.00132.50122.00114. 00154.50127.50

OwmwatCVN

123. 12126.57128.72130.03131.30131. 75

16.885.93

-6.72- 16.0323.20-4.25

Cmanmsvr CDecim ,, n-W


April 2008

C-90

CAPSULE W WELD METAL

CVCY APH 5.3 Hyperolic Tangwt Cunme Pried on 02A120 04:56 PM

Coeffici•ts of CDime 3A =•73.1 B U=.7.9cC= .=6LTO = 19.0S DM O.E4S,

Equatfiis A + B r [rmn(rT-o)bC+t~))jUppa Shelf Ikaxj144.0(Flzd) Isa ShffBaerg42(PaS)D

Taep@30 Af-h1=-27.5 Deg F Tenp@OS ft-la-3.2 Deg FPlant FmUly 2 MtmrIl: SMA.W Heat: BOLA.

Odutemion: rA Cwmuk W Fh• scrt'2

43O

I150

£

sio

400.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0


Charpy V-Notch Data

-100.00- 50. 00-50.00-25.00

.0025.0025.0050.0076.00

-C40 CYN

5.0014.0033.0047.0028.0072.0091.00

108.00132.00

(Cmlad CVK

5.9517.7817. 7131.7653. 2179.5079. 50

104. 13122.58

a

- .95-3.7115.2215.24

-25.21-7.5011.503.879.42


April 2008

C-91


Page 2Plmt Fadiy 2 Macnial: SMAW Heat BOLA

Otemtim: NA Capsule W Mlueo: n/cmA2

Charp V-Notch Data

Thmwam

125.00200.00250.00350.00350.00

.00

123.00127.00155.00154.00159.0045.00

CoVm~md LVN

138.51143.41143.87143. 99143.9953.21

n

-15.51-16.41

11.1310.0115.01-1.21

Cnomiuhm Cwmcia m .96-


April 2008

C-92

CAPSULE X WELD METAL

42W

DI"a

s5o

0

CVCIRAPH 5.3 Hyputollc Tanlwt Curve Plard on 02/M = 04:56 PIMPape 1

Coeffcimta of Cmuve 4A =76.1 B= -7339C=S1•W ¶ 1= 14.1 D=0 A0E4

Equatimis A +B r rm•b'r-ToCtm'D))]UppwSheff uEamu=I5tCOWhmx Isw Ucff Ehj44IVxOd

TeMp0O3 ft-fli•-S.1 DegF Tempsu•p ftbs-l7-S79DgFPlutz FPl72 Meaal: SMAW Heat: BOLA

Odamiont NA Capmul::x Fbxn• nCMA2

A

400.0 -f0.0 -100.0 0.0 100.0 200.0 S.0 460.0 Soo.0 eoo.oTempesturs In DqN F

Charpy V-Notch Data

- 100. 00-50.00-50.00-40.00-25.00-25.00

.00

.0025. 00

0pa CYN

4.0040.0025.0025.0051.0043. 0074.0062.0069.00

Cmvmdc'VN

12.5930. 0830. 0135.5345.0245.0263.8363.8384.45

-8.599.92

-5.03-10.53

12.91-2.0210.17-1.83

-15.45


April 2008

C-93

CAPSU X WELD METAL

Page 2Plant Fa•-cy 2 Manl: SMAW Heat BOLA

Ouemaaio: NA Caple: X Pume=: ncmA2

Chmrmp V-Notch Data

50.00100.00200.00350.00450.00

M CYN

107.00138.00123.00131.00153.00

C-n wdCYN

103.82130.98147.73149.92149.99

3..137.02

-19.7331.083.01

Cwmnohm xQufficiu - .971


April 2008

C-94

CAPSULE Z WELD METAL

CVGRAPH 5.3 Hypeollic Tangwet Curve PFwed on 02A062O 04:57 PMPap 1

CoefiýcMt of COwe 5A=67A B= .=6AC=•W7 7 =IU14.14 D =-.AOOR0*

Equdim is A t B' rrwmn(T-To)•Tc)m ]lUpp c 8h efH ara= -13 3. 0(WWxedQ Lww ShIf Hnrajy=Q22lxdD

TanpO30 t-lbsu-24.3 Deg F TempOSD ft-Tha-2.-l Deg FPlant Faiy 2 Msuiu: SKAW Heat: BOLA

OducSndow NA Cqaw Z TiaLc nftimn3O

2M

406

I

*150

io50

-300.0 -200. -100. 0.0 10o0. 200.0 300.0 400.0Temperature In Deg F

500.0 600.0

Charpy V-Notch Data

- 100.00- 60. o0-30.00-6.00

.005.00

15.0015. 0025. 00

0VUwSdCVN

4.007.00

10.0013.0072.00B6. 0057.0077. 0036. 00

4.8411.9126. 0246. 0352. 1657. 5168.5668.5679.55

-. 84-4.91

- 16.02-33.03

19.8421.49

-11.561.446.45


April 2008

C-95


Plant FPady 2Odentado: NA

Page 2MNatel: SMAW Heatr BOLACapsek Z Plume: n/cmf2

Charpy V-Notch Data

T"MUMjNm

30.0050.00

100.00150.00195.00259.00

ipM CVN

91.0088.00

105.00123.00151.00124.00

C-mPodCYN

84.83103.19126.32131.73132.72132.96

6.17-15.19-21.32

-8.7313.28-3.96

Ca•w Q3m cSt ,, .A32


April 2008

C-96

CAPSULE Y WELD METAL

CVGRAPH 5.3 Hyperboic Tangn Cmvw PdatSd on 02/060M 04:57 PMPape 1

CocfFmicets of CwOe 6A =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 FPlant Paly 2 Medal: SMAW Heat: BOLA

Odtmifim: KA Capsule:Y "No nkft2.3(I

a

so

'O

-6W.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0Tlmpsaturs In Dog F

Charpy V-Notch Data

TmfMMu

-50.00

.0025.0040.0040.0050.0060. 0075.00

100.00

1rpM CVN

7.0020.0012.0016.0033.0053.0074.00

104.00106.00

OumledCYN

2. 219.58

21.2536.2336.2349.7763.3288. 97

117.70

4.1911.42-9.25

-20.23-3.23

3.238.63

15.03-11.70


April 2008

C-97


Plant NAIdy 2Orienmtaio: NA

Pae 2Matnial: SMAW Heat BOLACapsule Y Flumn:m: n/km2

Charpy V-Nolch Data

FN oomuadcvN

125.00150.00200.00275.00275.00300.00

110.00130.00122.00133.00134.00125.00

130. 53134.98136. 81136.99136.99137. 00

-20.53-4.98

-14.8116.01-2.99

-12.00

coaula Qmfficm - .m72


April 2008

C-98

CAMLE V WELD METAL

CVGRAPH 5.3 Hyperboli Tangent Curve Printd on 02/6OQ 04:58 PMPae 1

Coc•icuts of Curve 7A=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 FPIant FPasy 2 MVMeit: SKAW Hatd: BOLA

OflealoK NA Cap :V Y Flanwm ucm"•

IIU06

4100.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0Temperture In Dog F

Ehmp V-Netch Data

T'Mu

-25.0020.0030.0040.0050.0070. 00

100.00125.00145.00

6.0026.0054.0033.0036.0069.0061.0039.0018.00

-mmlo CYN

15. 0229.1833.5238.3043.4854.7672.3736.3395.74

rniae

-9.02-3.1320.43-5.30-7.4,14.24

-11.572.65

-7.74


April 2008

C-99

CAPSULE V WELD METAL

PIamt Paley 2Orientatio: NA

Page 2Matril SMAW Ekat. BOLACapsulem V Pneuce: n/cmA2

Charpy V-Notch Data

165.00185.00230.00250.00260.00

Iom CVY1

100.00103.00137.00131.00125.00

C-mlimdCYN

103.36109.25117.44119.49120.27

-3.36-6.2519.5611.514.73

Conalatm Cofcim , .966


April 2008

C-100

UNIRRADIATED (WELD)

150I

IL1

5D

CvGRAPH 1 H.3-. H•yPebli Tan1gt Crve Pdutd on 02106t2008 05:00 PM

Coeffixita ofOf Cri 1A -=9M B = 4LO C a=SA TO-=-lOS D =LOOE40

Eqution is At B÷ frr Tnl-Tm)'C+DT))]Upper Shelf LL--92. Loe Shelf Ll-K=b0Fd)

[email protected]. 3.5 mifi-235 DegFPlait Fmky 2 MaWmimi: SMAW Hat: BoLA

Icfta NA CqWak INIRR FIn mInA2

0 9

0

0400.0 0.0 300.0

Tempoeture In Du9 F

Chap V-Notch Data

aps LJB C(•medL,.1

600.0

Tar~mu

-100.00-50.00-25.00-10.00

10.0025.0040.0050.0075.00

7.0015.0035.0044. 0073. 0060. 0090. 0039.0092.00

3.0616.9933. 8346. 5663.0973.0580.2483.6483. 65

3.94- 1.99

1.17-2.569.91

-13.05-. 245.363.35


April 2008

C-101

UNIRRADIATED (WELD)

Page 2PIat Fafdy 2 Mamal: SMAW Hea BOLA

Orkud: NA Capzlc UNJER FMn= nkMA2

Charpy V-Notch Data

100.00150.00150.00

175.00210.00210.00210.00

91.0092.0091.0090.0091.0093.0092.00

90. 7791.9691.9692.0992. 1592. 1592. 15

.23

.04-. 96

-2.09-1.15

.85-- .15

CamdOw C beffifim - 987


April 2008

C-102


CVCGALH 5.3 Hyperboa Tanent Curve PdnW on 02060=200 0±:00 PM

Coeflicients of Curve 2A =41L75 B-45757C=S4.7 TO=--23S D =.0.001.00

Equtimflis At+ B'0 Mnh(CT-ToDAC+tn))jUpper Shelf L.B.--915 Lower Shelf LB.-R=M0( d)

[email protected] 35 mi!--43.9 DegFPlant FPdy 2 mtala]: SMAW Heat: BOLA

Odnudmlo NA Calem : U Plxnw nkA2201

.3EIUU.

aI

IOU

100

rn]

a

nli. + I I 4 I00. 0.0 300.0 600.0

Temlperture In Dog F

Charp V-Notch Data

- 50.00-25.00

.00

.0025.0050. 0050.0075. 00

100. 00

16. 0068. a077.0031.5074. 0070. 0078.0034.3030. 50

31. 9845.0458. 2358. 2369. 5077.8477. 8483.4086. 83

Difflienfi

-15.9922.9618.77

-26.734.50

-7.84.16

1.10-6.33


April 2008

C-103


Page 2Plant FPity2 Malmial: SMAW Heat. BOLA

Orienaion: NA Capsu U iueme: nflan 4'2

Charpy V-Notch Data

125.00150.00175.00200.00250.00300.00

91.5092.0091.0090.5090.0096.00

88. 8590.0290. 6891.0591.3791.46

Dinmfl

2.651.98

.32-. 55

- L.374.54

Cammbdm (befficic - -852


April 2008

C-104


CVGRAPH 5.3 Hypaolic Tangent Curve Pined on (02O02008 05:01PMPage 1

Cocffkjizta of Conm 3A =42t55 B=42.A5C=67.82 TO-=-31 D=0S104E00

Equaion is A + B rru('r-TI)AC+Dt))jUpper Shal LJL85.t [an Shclf L.=.0E.F tad)

Tcmp.@LSL 35 mi!-18.4 DegFPlant Fley 2 Material: SMAW Heat: BOLA

Odiendon: NA Cupelc W Fhlus Anlcnt22M

[L100

so

o 4-04W0.0 0.0 300.0


Charpy V-Notch Dabt

600.0

- 100.00-50.00-50.00-25.00

.0025. 0025.0050. 0076. 00

]riLa

5.0014. 5023. 5041.0028.5055.0071.0031.0079.00

5. 0518. 3918.3931. 1146.4960.9060.9071.3078. 19

-. 05-3.8910.119.89

-17.99-3.9010. 109.30

.81


April 2008

C-105


Plant FPrly 2Otenmtlma NA

Page 2Matrial: SMAW Heat BOLACapsule. W Hf ce'. nlcM2

Charp V-Notch Data

Tempeumm

125.00200.00250.00350.00350.00

.00

91.5032.5092.5070.5032.5041.50

83. 3584.9085.0585.0985.0946. 49

8. 15-2.407.45

-14.59-2.59-4. 99

CsMukMtc QCifTit m -951


April 2008

C-106


CVGRAPH•5.3 Hyp•rbaoicTng Cumr Printd on 02f 0 05:01PM

Cci:cimt of CmQve 4A =.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)

[email protected] 35 nil=-30.0 DegFPlnt FPdv2 Mal"a]: StAW Heat: BOLA

Odat NA Capul: X Plinw Sknt22o

J15D.3fE

310011610

5D

00.0400.0 0.0 3O0.O

Temperature In Deg P

Chmrpy V-Notch Data

600.0

- £00.00-50.00-30. 00- 40. 00-25. 00-25.00

.00.00

25.00

"d L.Ia

4.0033.0024. 0022. 0043. 0040. 0052.0050. 0053.00

7.8024.4324. 4329. 5137. 8837. 8852.2452.2464.45

-3.80

-. 43-7.3£

5.122.12-. 24

-2.24-11.45


April 2008

C-107


Pape 2Plant Fad-y2 Matmil: SMAW Heat BOLA

Oientmain: NA Cpsule: X Pluence: n/cm'2

Charpy V-Notch Data

50.00100.00200.00350.00450.00

80.0092.0085.0030. 0078.00

ibmmuIed LaL

72.9781. 0083. 8784. 0784.07

7.0311.00

1.13-4.07-6.07

Comhncbcm Cbdcie m .-971


April 2008

C-108

CAISULE Z WELD METAL

CVGIAPH 5.3 Hyperboric Tangent Cuve Printed on 021060 05:02 FM

Coefcients of Cawic 5A =3-91 BD =f39.91 Cc=a7.63 TO 1= 3 D =0.001M0

Equatin is A +B 0 Imn=(C-TbACtDThJUpper Shelf L.IL=79.R Lower Shelf fIL-R.Mzed)

Trn.@OL.. 35 miln=-IA Deg FPlat F'adcy2 Mct]u: SMAW Heat: BOLA

Odeanthiom NA CqMfw Z Fbu bk /cmnt2200

150

mu

I 55D

00.0400.0 0.0 300.0

Temperaturs In Dq F

Chmrpy V-Notch Data

600.0

- 100.00-60.00-30.00-6.00

.005.00

15.0015.0025.00

DikES

.001.007.00

10.0052.0058.0042.0055.0062.00

.332. 68

11.6630. 3136.4941.7952. 0052. 0060.73

-. 33-1.63-4.66

-20.3115.5116.21

-10.003.001.27


April 2008

C-109


Pap 2Plant Padey 2 Maenrial: SMAW Heat BOLA

OdCintad•: NA Capsule- Z Pluenc: n/fmA2

Charpy V-Notch Data

-tm LE. LCEp3SL

30.0050.00

100.00150.00195.00250.00

63.0061.0078. 0034. 0031.0035.00

64.3273. 6879.3579.7879.8179.82

-1.32-12.68-1.35

4.221.195. 13

CaulfINO Quyciil m .951


April 2008

C-110


CVYCITAPH 5.3 Hyperboic 'lfge Curm PdnSd on 02060M 05:03 PMPape 1

Coefficits of Curve 6A =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 DogFP=tnFadcy2 Medal: SMAW Hat: BOLA

Oduamofm NA Capan:Y Pxacr ncnk"22O

A

'100soI5O

4100.0 0.0 300.0 600.0Temperature In Dog F

Chap V-Notek Data

L CampuwdL..¶rmwOMu-50.00

.0025.0040.0040.0050.0060.007s. 00

100. 00

6.0015.0013.0015.0025.0043.0052.0070.0073.00

.1s3.10

12.6425.7725.7737.6950.3166.0478.89

5.8511.90

.36- 10.77

-. 775.311.693.96

-5.89


April 2008

C-Ill


Pap 2Plant Fadey 2 Matuzial: SMAW HEt BOLA

Odentmain: NA Capsule Y Piucnce. nlA2

Charpy V-Notch Data

125.00150.00

200.00275.00275.00300.00

kILpd L.E

74. 0037. 0088.0093. O0

36. 0033. 00

CompdL..

82.3683. 1583.3783. 3883. 38A3. 38

-8.363.854.63-. 382.62-. 33

Caion ,befficimt -. 984


April 2008

C-1l2


CVC*1IPH 5.3 Hyp-bolic Tanget Curve Printed on 02A60 05:03 PMPag 1

Coefficdmts of Curme 7A =4119 B=43.19 C= 116M TO=63.57 D =0.00E40

EquaUi is A +B r rnbTUT-To)KCtn)T)]Upper SheVL.RL=8S4 Laww Shelf L--.E..(Fzd)

Ten@,@OL 35 mils=41.3 Deg FPlant FIwle'2 Meial: SKAW t: BOLA

Odmilno NA Capsmu: V Fhrnw unt2

AEIUU.

400.0 0.0 300.aTemperaure In Dug F

Charpy V-Notch Data

600.0

Tmn

-25.0020.0030.0040.0030.0070.00

100. 00125.00145.00

10. 0027.0045.0031.0032.0052. 0048. 0065. 0064.00

CnmpumduL.I

15.4327.7031.0434.5438.1645.5856.3264.1369.33

DiMO

-5.43-. 70

13.96-3.54-6.166.42

-3.32.87

.5.33


April 2008

C-113


Pagp 2Plantf Parlcy2 Manhikl SMAW HEat BOLA

Orentatio: NA Capsulm V Rue=nce: nkMA2

Chap V-Ntkh Data

"m'qas%

165.00185.00230.00250.00260.00

Coa-umi LL

31.0073.0037.0076. 0034. 00

73.5676.8931.7383.0333.55

7.441.115.27

-7.03.45

Cosnulkicm Coffimt - .64


April 2008

C-114

UNIRRADIATED (WELD)

CVGRAPH 5.3 Hypedaoc Tangent Curve Prned on 02/060M 05:09 PMPage1

Cneflkicnts of cOve 1A =50. B= S0.C=62.17 TO'=-1&16 D =0.ACEiI

Equtdi is A + B' rrTb(T-Toq(C+Dtm'JTnpaufm 5a0t 5M Sheu= -15.1

PlantF Pdaey 2 Maid: SMAW Hes: BOLAOdcOmDS MA Cqamk U14il F=l=aain ub

125

100

I'U£a

75

5s

0-/4 .0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0


Chapy V-Notch Data

TManptmm

-100.00-50.00-25.00- 10. 00

i0. O0

25.0040.0050.0075.00

12.0030. 0040. 0043.0030. 0072. 0035.0094. 00

100.00

6. 1324. 5942. 1654. 1469.2078.4585.5089. 0594.79

5.875.41

-2.1611.1410.80-6.45

-. 504.955.21


April 2008

C-115

UNIRRADIATED (WELD)

Pagp 2Plant Friay 2 MatmaI: A•,W Heat BOLA

Ornado: NA Capnlc.: UNJIR Pluence nkMA 2

Chap V-Notch Data

Tempentm

100.00150.00150. 00175. 00210.00210. 00210. 00

b1pa Pecela Ur

100. 00100. 00100.00100.00100.00100.00100.00

-Om Pe sm

97.6099.5199.5199. 7899.9399. 9399. 93

2.40.49. 49.22. 07.07- 07

Conwhids (befficieci -M8


April 2008

C-116

CAPSLE U WELD METAL

CVGRAPH 5.3 Hypebolic ¶angmt C-mve P&Wd on 02/060M 05:10 FM

Coefficients of Caum 2A =O. B=S&C -76& TO=--1.17 D =0•.OOR.0

Equidw is A + BFa b rr(T-T1AC+DTJ)jTaer~m at *50% Shear = -11.1

Plant Falay 2 Me~ahl: SMAW Heat BOLAOdwsiow NA Caonu: U Phxace: uan"2

125

tao

I'U75

5D

25

0 -. 0 -las41300.0 -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

-50.00-25. 00

.00

.0025. 0050.0050.0075.00

100.00

24. 0053. 0064. 0042.0067.0073.0091.0099.0098.00

26.'6d841. 0957.2257.2271.9483. 1083. 1090. 4194.76

-2.6811.916.73

-15.22-4.94

-10.107.908.593.24


April 2008

C-117


Plant FPady 2Orienatin: NA

Pap 2Matncial: SMAW Heat BOLACapsule: U Pluence: nauA2

Charpy V-Notch Data

Teoweemm

125. 00150.00175.00200.00250.00300.00

100. Go100.00100.00100. 001O0. 001O0. ao

Composle MGM Saer

97. 1998.5299.2299. 5999. 899;. 97

nan

2.811.48

.78

.41

.11-03

CaroskS Qiefficind -36=


April 2008

C-118


CVCRAPH E5.3 Hypaol ngmt Cmrve Prh onO2A62M 05:10 PM

CodfiF-imta of C(rve 3A=S& RB=50.C=f52.99 TO¶=1.2 D= 0.0_,iI

Epsir is A +B 0 rTC•r-To)(C+Dt))iThnmtW= a 50t( Shmr = 1.9

Plst FPday 2 MdiaS: SMAW Het: BOLAOdcWom: MA Cqpwu W Fhwz . z/ca"2

125

i0o

I'K75

so

25

-Mo.0 -200.0 -100.0 0.0 100.0 200.0 o00.0 400.0 500.0 OM.0


Charpy V-Notch Data

¶rEwain

-100.00-50. a0

- 25.O00.00

-25.0025. 0025. 00

50. 0076.00

6.0013.0021.0028.0037. 0055. 0037.0094. 0097.00

Opmp Pm Emhw

2.1012.3912.3926. 6548. 2170.5770.5786.0394.26

DfflfmnM

3.90.61

1.611.35

-11.21-15.57

16.437.972.74


April 2008

C-119


Page 2Plant Fity 2 Matmial: SMAW Hear BOLA

Oen:af: NA Capsule, W Placme: n/CuA2

Chmpy V-Netch Data

ypSPf Ucnmlr Gm•aPMd Fa= Shr

125.00200.00250.00350.00350.00

.00

100.00100.00100.00100.00100.0049.00

99. 0599.9499. 99

100.00100.0048.28

.95

.06

.0L

. 00

. 00

.72

Csnmrm EOefficic m -979


April 2008

C-120


CYGRAPH 5.3 Hypflolic Tangen Gino Puinted on 02106fl00 05:11 PMPast 1

Co•--icimta of Curve 4A =. B=50.C=6443 IM =496 D0=.0E40

Bqutizmis At B 0 rrwh(T-To-)iC+DT))jTensaphunt a 50% Shuar= -. 9

Plat PFley 2 Mdzial: SMAW Heat: BOLAOdesuiwc NA Cumau: X Pnuwn nkm

125

100

IU75

UO

25

-00.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0Temperaure In Dog F

Charpy V-Nolch Data

TWAyflrn

- tOO. 00- 50.00-50.00- 40.00-25.00-25.00

.00.00

25.00

Iva Peucon shear

4.0030. 0020.0025.0045.0030. 0065.0050. 0065. O0

cmpsd pun= sher

5.6221.8921.8927.6537.8237.8256.9056.9074. 13

-1.62H. it

- . 89-2.65

7.11-7.82

1.10.6.90-9.13


April 2008

C-121


Pae 2Plant Faduy 2 Manital: SMAW Heat BOLA

Orentaton: NA Capule X Placte: nkMA2

Charpy V-Notch Data

50.00100.00200.00350.00450.00

95.00100.00100.00100.00100. 00

86.1596.7099.85

100.00100.00

8.853.30

.iLS

.0000

Qnhtonfc Cofidn - .985


April 2008

C-122


CVGLAPH 5.3 Hyprbonc Tanget Curve Pdntd on 02A06I2() 05:11 PMPage 1

Coelicicuta of Conc 5A=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: BOLAOdeattios NA Cqmw&- Z Fliumc•cWI

125

100

I'U75

w

25

400.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0


Chmrpy V-Notch Data

¶rViau

- 100.00-60. o0-30.00.6.00

.005.00

15.0015.0025.00

Iupat PrMa Sbo

5.0010.0015.0020.0030.0040.0050. 0045. 0065.00

c=add Pao= SMr

.412.70

10.3126.6832. 6438. 0849. 7749.7761.49

-a

4.597.304.62

-6.68-2.64

1.92.23

-4.773.51


April 2008

C-123


Pag 2PmantFadey2 MatntalSMAW HEatBOLA

Oakmadca: NA Capule. Z Flue: n/cmf2


Te .U0

30.0050.00

100.00150. 00195. 00250. 00

75.0030.0090.00

100.00100.00100.00

66.9684.0398.2899.8499.98

100.00

8.04-4.03-1.23

.16

.02* 00

Cuwkmim ,beciaM .991


April 2008

C-124


CVG1RAPH 5.3 Hypeboc Tant Curve Ftl o 0210on 05:12 PMPap I

Coeffciets of Cant 6A=S. B=S.C=3LS4 TO=53.05 D=BM-.001

Epwa is A + B' I[sWm(-Tq)C+C.J))iTPeipd um atmi 50% Shea r= 53.1

Plant Pafle 2 Mahzd: 514kW Had: BOLIAOdnWlmow NA Capsul: YV Fuuzc nkn"

I'U

-00.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 SO0.O 600.0Temperature In Dog P

Charpy V-Notch Data

-50.00.00

25.0040.0040.0030.0060. 00

75.00100. a0

5.0015.0020.0030.0030.0040.0065.00835.0035.00

. 475. 99

18. 9133.6M33.6146.0538.9173.7591.95

4.539.01[.09

-3.63-3.61-6.056.099.25

-6.95


April 2008

C-125

CAPMLE Y WELD METAL

Page 2Plant Fafd 2 fmai: SMAW HEat BOLA

Orientation: NA Capsulm Y Pluence: nfmr2

Chmap V-Notch Data

125.00150.00200.00275.00275.00300.00

IpW Pao=•mar

90.0095.0095.00

100.00100.00100.00

compma ram Shea

97.6699.3599.95

100. 00100. 00100. 00

-7.66-4.35-4.95

. 00

. 00- 00

ConrJmmiw (baM - .M


April 2008

C-126


CV APH 5.3 Hyperbolic Tangent Curve Pintud on 02826/20{M 05:12 PMPop 1

Coefficints of Curve 7A-=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: BOLAOdoztsimo NA Cp:Y V Ehxac nkumt2

125

100

I'UIa

75

aD

25

-s.0. -200.0 -100.0 0.0 100.0 200.0 m00.0 400.0 500.0 6eo.oTemperture In Dog F

Charpy V-Notch Data

Tm¶ffm

-25.0020.0030.0040.0050.0070.00

100. 00125.00145.00

bnmpt Shemr

5.0020. 0030. 0030.0035.0075.0075.0030.0090.00

compuedPmmSEn

7.1622.7528.4034.8241.8456. 6276. 1337. 0492. 41

-2.16-2.75

1.60-4.82-6.8418.3B-1. 13-7.04-2.41


April 2008

C-127


Plant: Parly 2Orienmfion: NA

Page 2MacnaL SMAW Heat BOLACapule V Fhuem: ntnA2

ChaMrpy V-Nakh Data

Tanpanm•

165.00185.00230.00250.00260.00

90.0095. 00

100.00100. 00100.00

95.6797.5799.3599.6499.73

-5.67-2. 57

.65

. 36

.27

CAiduaitm Ct mi m "


April 2008

C-128

4200

*15

06

UNIRRADIATED (HEAT AFFECFE ZONE)

CVGRAPH 1.3 Hypeato•c Tant Curve Pinte on 02/0f0 0±.22 PMPage 1

CoEFfiits of Cmurv 1A =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 FPlant Fsy2 Mael: SAS33BI Hat B7212-1

Oc•OiC NA Cec UNIRR Flbaw: n/cmn2

C0

C

, C

04-0.0 -200.0 -100.0 0.0 100.0 200.0 ( O0.0 400.0 500.O 600.0

-200.00-150.00-100.00-100.00-50.00-50.00

20.0025.0050.00

]wpm CN

11.00159.0091.0040.0098.0071.0044. 00

113. 30136.00


Charp V-Notch Data

flmpzadCVN

51.4065.4280..5080.5095. 5495.354

114.55113.77121.32

Dflid

-40.4093.5817.50

-40.502.46

-24.54-70.55-2.2714.41


April 2008

C-129

UNMRADIAT (HEAT AFFECFE ZONE

Pae 2Plant Farlty 2 MateriBk SA533B 1 Heat B7212-1

Ozienadci: NA Capsule UNJIR uen= nkMA2

Charpy V-Notch Data

75.00100.00150. 00210.00210.00210.00

1mpd CYN

123.00191.00159.00151.0036.00

139.00

126.71131.32138.91145.49145.49145.49

-3.7159.6820.09

5.51-59.4943.51

Canmmtr C(beffride ..581


April 2008

C-130

CAPSULE U (HEAT AFFECTED ZONE)

CVGRAPH 5.3 HyEfaoli Tanggnt Curve Prlnted on 02/2 05.22 FMPape 1

Coff-icicuts of Corm 2A=56. B =-U4.4C=77.3 TO =-34SS D=0.040

Equation is A + B ' rrmnb(C-To)ACtmT))JUpperShelffEnaay I 1.D(nxd) LawwUmff~HwrGY2XV~xc

Temp@30 ft-Ts-76.4 Dcg P TempOSO ft4-=44.3 Deg FFlnt: FPry2 MAEa: SA533B1 BE 7212-1

OdwISton NA Capsun:U Pxlua n/CM",2300

250

IS*155Dmals

a O

-300.0 -200.0 -100.0 0.0 100.0 200.0 a00.0 400.0 s00.0 600.0Temperature In Dog F

Charpy V-Notch Data

"rmnjmDm

- 100. 00-50.00-25.00

.00

.0050.0050.0075.0075.00

JcPa CwN

21.0029.5075.5068.00

102.0098.00

103. 5057. 50

119.00

COmladCVN

19.3846. 1463. 4579. 4579.4599.9599.95

104.90104.90

Diflimal

1.62- 16.64

12.05-11.4522..55-1.953.55

-47.4014. 10


April 2008

C-131

CAPSL U (HEAT AFFECTED ZONE)

Page 2Plant Fadey2 M iaL SA533B1 Hcat B7212-1Oriezion: NA Capsule U Plume=: n/MA2

Charp V-Notch Data

100.00125.00175.00O

200.00250.00300.00

kpa CYN

105.50124.50107.50113.5096.50

108.00

(•amplu-dVN

107.70109.24110.51110.74110.93110.98

DMaUtsl

-2.2015.26-3.012.76.

-14.43-2.95

Cawhmirac Cffis m .948


April 2008

C-132

CAPSULE W (HEAT AFFECTED ZONE)

C-YRAPH 5.3 Hyprolic Tangnmt Curve PrintS on MUM 05.23 PMpape 1

Codeficnts of Curve 3A=64.1 B =6139C=28231 TO =-9.34 D =.0 E•40

Equdi isA +At B' 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 FFPlat:Palsy 2 Mtea•: SA••3B1 ka Bfll2-1

Ouculdo: NA Cqpslk W Fbzmr,: Dta

-4o0,- -uo.-1000.0

i

0.0 100.0 200.0 300.0 400.0 500.0 600.0Temprature In Dog F

Chap V-Notch Data

M muMdCYN •flamtia

-100.00-liOu. ao-50.00-50.00-25.00-25.00-20.00

.00

.00

20.0029.005.00

13.009.00

79.0019.0053.00

119.00

2.452.459.479.47

33.8433.8442.5283. 1883. 18

17.5526.55-4.473.53

-24.9445.16

-23.52-30.18

35.82


April 2008

C-133

CAPSULE W (HEAT AFFECT ZONE)

Page 2Plant Falcy 2 Macriak SA533B 1 Heat B7212-1ldentmtiai: NA CapeuW W Plluexe: nh:mA2


50.0076.00

125.00250.00250.00350.00

10pul CYN

122. 00132. 00120. 00sq. no

139. 00155. 00

123. 88125.64125.99126.00126.00126.00

-1.886.36

-5.99-37.00

13.0029.00

Cma CleffciM m .92


April 2008

C-134

CAPSULE X (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbaoc Tangent Curve Prined on 02/M= 05.23 PMPap 1

Co-cificnts of Carve 4A=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 [email protected] ft-ba--39.9 Dg FPlant Palcy 2 Medal: $SAS3B1 Heat B7212-1

OdaiwNA Casl:X K Flac nfmt2

3SO

5aRioo

aO

-M00.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0


Chupy V-Nesh Data

T¶MPMmuM

-100.00-70. 00-50.00-50.00-40.00-20.00

.00

.00

.00

-pa CYN

13.003.00

66. 0038. 0059.0036.00

110.00135.0027.00

cwVU1edcVN

13. 8627.3741.5041.5049.9768.4486.3586.3586.35

-. 86-19.3724.50-3.509.03

-32.4423.6540.65

-59.35


April 2008

C-135


Pago 2Plantrarly2 MatIea SA53_B1 Heat B7212-1

Oienmauion: NA Capsuq e X luence: n/cm"2

Charpy V-Notch Data

T20.0

20.0050. 0a

125.00200.00250.00350.00

127.0091.0092.00

118.00126.00140.00

101.06115.40126.53127.84127.96128.00

25.94-24.40-34.53-9.84-1.9612.00

Conulktm tbaffiit - .797


April 2008

C-136

CAPSULE Z (HEAT AFFECTED ZONE)

CL"RAPH 5.3 Hyputblc Tangent Cur Panted on 02W2 05-23 PMPap 1

Cacffidans of COrve SA =641 B=6L9C=76.1 7 1T= 14.7 D =,00E+00

Equsisi i. A + 1H' rrnnhu(T-TbAC+Dm))1IUIn= Shelfr nmcI --12 6.0(PWamd) lowe Uzclf lupi=22(Had).

Tcmp@30 ft-lba-32A Det F TcmpO@!A-Ib=--2.9 Dog FPln FwrEy2 Mamida: 5A3B1 Hcat B/212-1

Odmntfm NA Caaft Z FiemC3OW

200

206

Imsa

Rioo

5O

-sOa.a -20O.0 -i00.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0Temperalum In Di9 F

Charw V-Notch Data

Tmownu

-100.00-60.00-30.00-20.00-15.00-10.00-10.00

.00

.00

ft" CVN

1.0016.0020.0061. 0068.008.00

42.0044.0070. 00

COmluSdCVN

7.9917.4431.4237.6841.1044.6944.6952.2932.29

.01-1.44

-11.4230.3226.90

-36.69-2.69-8.2917.71


April 2008

C-137


Plant F•al 2Orieldn: NA

Page 2Matera SA53B31 Heat B7212-1

Capsnue Z luenc: n/MA2

Cluff V-Notch Data

TmIqti

10.00

25. 00100.00150.00195.0050.00

7.00130.00122. 00115.00140. 0068.00

c-mpalI•"VN

60.2872.43

114.11122.56124.9390.91

-53.2857.577.39

-7.5615.07

-22.91

amoaa Ocm3 = .Al


April 2008

C-138

CAPSULE Y (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hypaoic Tangmt Curve Pried on 0)6Nf050.2A FMPape 1

Codficet of Cmrve 6A=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 FFinley 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


Chap V-Notch Data

¶reapmunn

- 75.00-50.00-25.00-25.00

.00

.0010.002s. 0050.00

c-Md CYN

8.0019.0073.00

9.0091.00ii. a036.0071.00

131.00

7. 9415.8431.2731.2753.7153.7163.0575.5289.81

.063.16

41.73-22.27

37.29-42.71-27.05

-4.5241.19


April 2008

C-139

CAPSULE Y (BEAT AFFECTED ZONE)

Plan. Parley 2Orientmain: NA

Page 2MateUa SA533B 1 Heat B7212-1

CauiM Y Pluoe: n/"ft2

Charp V-Notch Data

50.0075.0090. 00

125.00125. 00150.00

92.0077.00

127. 0062.00

111.00107.00

CWmpmYdCVN

89.8196.9299.07

101.21101.21101-.

2.19-19.9227.93

-39.219.795.31

Calmank Cbafficia - .764


April 2008

C-140

S

CAPSULE V (HEAT AFFECTED ZONE)

CVGRAPH 5.3 Hypebolic Tangent Cmve Prineld on 02109M 0524 PMPage 1

Cacfcicnta of Curve 7A=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 Flant Feld-y2 MeAal: SAS33BI Heat Bf212-

OdmitiwE NA Capuc: Pxl nlcnr2

U

U

U U,

ISO

8100

so

0400.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0

Tempermure In Deg F

Charpy V-Notch Data

500.0 600.0

- 80.00-15.0025.0035. 0040.0045.0050.0070.0070.00

hpw CYN

9.0017. 0024.0022.5054.0069.00$5.0013.0070.00

-omutd CNVW

3.6211.7729.2736.0939.8643.8347.9865.4365.43

5.385.23

-5.27-13.59

14.1425. 177.02

-52.434.57


April 2008

C-141

CAPSUE V OMEAT AFFECTED ZONE)

Pagp 2Piant: Pud2 Maca SA53BI Hat B7212-I

Oriemain: NA Capsule V Flumc: u:A2

Chamy V-Notch Data

90.00115.00155.00200.00250.00260.00

kpil CYN

94.00107.00122.00120.00134.00107.00

-ompumd CYN

31.9697. 83

111.21116.20117.60117.71

12.049.17

10.793.80

16.40-10.71

Cbmgtm. Coken M .912


April 2008

C-142

UNIRRADA¶TE (HEAT AFFEC[E ZONE)

200

1wso

E0

CVGRAPH 5.3 HypUerbc 'Tnt Curve Prmd on 0206O 05.26 FMpap I

Cocf-kicnts of Curve IA =4&13 B =413C=19Sf3 TO=-13t9 D=0.AMOR

Equatim is A + B I rl'nbT-To)KCtD'))jUp~r She LJ._--90.3 Lauf Shelf L.=JI(FmVMd)

TumpSLA.. 35 mil-t.3.6 DegFPlantf Psly2 Muldal: SA3B1 eaL B7fl2-1

OdcOMk nA CWk LNUI Fham: nfcmr2

0 aCa

o

004O.0 0.0 300.0 600.0

Temperture In Deg F

Charpy V-Notch Data

fimummft

-200.00-150.00-100.00-100.00

-50.00-30.0020.0025.0050.00

nPSL•E.

5.0095.0057.0033.0060.0046.0073.0079.0091.00

31.4942.5153.9853.9864.3264.3275.3876. 0178.81

Dnb

-26.4952.423.02

-20.93-4.32

-11.32-2.31

2.9912.19


April 2008

C-143

UNIRRlADATED (HEAT AFFECTE ZONE)

Pag 2Plant PFafly2 Matriak SA533B1 Heat: B7212-1

Orientation: NA Capsutl UNIRR fiuen= ncmA2

Charpy V-Notch Data

75.00100.00150.00210.00210.00210.-0

hnlL L.H.

37.0031.0095.0091.0073.0037.0 0

81.1383.0285.7787.7787.7787. 77

5.87-2.02

9.233.23

-14.77-. 77

Cbmkimi Obeffic - -701


April 2008

C-144

CAPSUE U (EAT AFFECTED ZONE)

CVGRAPH 5.3 Hypetoli Tangent Curv Pdtzd on 02A62= 05:26 FM

Cocfficiets of CDi 2A =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 FFlMFs-cy2 Matidal: SAS3BI HE Bl7212-1

OdamMui NA Cpalem:U mu AuWA2

IUU.'U

-00.0 0.0 300.0Temperature In Deg F

Chaupy V-Notch Data

600.0

-50. 00-25.00

. 0a

. 00

50. 0050. 0075s. 075. 00

low OL,

[6.5028.5063.0057.5075.0070. 0032. 50S0. 0039.00

18.5939. 1851. 2062. 2362. 2377. 4777. 4781. 7081. 70

-2.09-10.63

1lt. so-4.7312.77-7.47

5.03-31.70

7.30


April 2008

C-145


Plan• Fafdy 2lentatmion: NA

Pap 2MatcrIak SA533B1 Heat B7212-I

Capsule: U Pluence: nAMA2

Charpy V-Notch Data

L tm.utLZ.

100.00125.00175.00200.00250.00300.00

39.0092. 5039. 0090. 0037.5092.00

84.3786. 0087.5387.8688. 1788. 27

4.636.501.472.14-. 673-73

Carmatdm' Qfficut m .- 92


April 2008

C-146

CAPSULE W (HEIAT AFFECTED ZONE)

CVGRAPLH 5.3 Hypert0c Tangent Curve Prhild on 020. 005:27 PMPape

Cocfficnts of Camve 3A =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 FFlemat Py2 Aitedal: A533B1 Ht •WBfl12-1

Ocnhitsion: NA Cquukc W Elects: s/ca"2OO

iso

I2

1100

SD

00.0-M0.0 0.0 300.0

Tempsrature In Deog F

Chap V-Notch Data

fto L. ch•RndL.

600.0

-100.00-100.00-50.00-50.00-25.00-25.00-20.00

.00

.00

15.0016.509.50

23.0010.0057.0014. 5041.0030.00

1.671.67

13.2113.2130.9030.9035.5955.6955.69

13.3314.13-3.719.79

-20.9026.10

-21.09-14.6924.31


April 2008

C-147

CAPSULE W (HEAT AFFECTED ZONE)

Plan Pmaley 2Ofientmai: NA

Pape 2Mutc•ank SA533B 1 Heat: B7212-1

Capsule, W Place: nkemAl

Charpy V-Notch Data

TanpOMM

50.0076.00

125.00250.00250.00350. 00

qpu LK.

90.0092.5097.5070.5097.5099.50

-m L.

86.4390.6692.5492.7992.7992.79

3.571.844.96

-22.294.716.71

Comwelnfa be~ciaS - "9


April 2008

C-148


CVGRAPH 5.3 HypetOBiC ¶bnw Curve Printe o 0210612008 05:7 PMPpag 1

CoeXficients of Cman 4A = 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 FFlue Fsa2 Mgedia: SAS33BI Hue B212-1

OdatiWoE NA Caonl:x Flusc nkA2200

ImA

31100

5D

0I--0M.0 0.0 300.0


Charpy V-Notch Data

600.0

-100.00-70.00-50.00-50.00-40.00-20.00

.00

.00

.00

9.007.00

40. 0023.0040. 0032.0068.0091.00I5. 00

6.9716.3526. 7026. 7033. 0246. 7659. 6859. 6859. 68

DUiMMM

2.03-9.3513.30-3.706.91

-14.768.32

31.32-44.63


April 2008

C-149

CAPSUE X (HEAT AFFECTED ZONE)

Pag 2PlHaw Fadcy2 Maeriak SA533B1 IHcat B7212-1Orientation: NA Capsutl X Pluence: n/cmA2

Charpy V-Notch Data

20.0050.00

125.00200.00250.00350.00

92. 0065.0076. 0032.0090. 0094. 00

Dic

69.6978.6484.6085. 1685.2085.21

22.3113.64-3.60-3.164.80'.79

Cmukm Cbeffid.m -. 37


April 2008

c-i o


C •RAPH 53 Hypuerbc langent Curve Pdned an 02W06n= 05-27 PMPage 1

Coefficiats Of Curve 5A =43.04 B =43.04C=70X5 IV= 18,M D =0,00E+00

Equtkui is A +- B rrfbh(Cr-To)MC4lf))1Upper SM L.E.=16.1 Lws Shelf L.B.=.0(FPIxd)

Tcnp.@LE. 35 mila.1 DelFrPlan F"1y 2 Matedal: SA.3SBI Neat B7212-1

OdLSOe NA Cqpadc Z Fluze tkmf2ad

IEI

"S

IN

100V _________

V

VV0]

40-.0 0.0 300.0 600.0Temperature In Deg F

ChapV-NotcB Data

T¶memMuM

-100.00-60.00-30.00-20.00-15.00-10.00-10.00

.00

.00

2.005.009.00

46.0040.004.00

26.0025.0043.00

faOVaMd &LE

2.851.34

17.3421.6224. 0126.5626.5632.0532. 05

_-. 15-3.34-1.3424.3115.99

-22.56-. 56

-7.0510.95


April 2008

C-151


Pap 2Pluat Pare 2 Maiti SA533B1 Heat B7212-IOrifltinn: NA CaqsunI. Z Phumn: n/cmA2

Charpy V-Notch Data

¶NxempMun

10.00

25.00£00.00150.00195.0050.00

1.0090. 0087.003S9 0079. 0040. 00

-ampuladl.K

37.9747. 1373.4584. 1285.5361.26

-36.9742.37

8. 553. 88

-6.53-21.26

comnhjam r0cc = .W06


April 2008

C-152

CAPSULE Y (HIEAT AFFECTED ZONE)

CVGRP 5.3 Hypatic Tanget Curve Prinmed on 02/0.0 05.28 PMPape 1

Cocffimcnt of Cm.v 6A =4125 BN=4L25C=6L96 T 0=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)

[email protected] 35 mis=-55 Deg FPlant Palsy 2 Medl;SA•S• 1 Hea B7fl2-1

Otwnioa- NA Capsm: Y FIum nlMcr2

130

IS

IL 100

so

I I I IN

40M.0 0.0 300.0Temperature In Deog F

Champy V-Notch Data

600.0

-?75.00- 50.00-25.00-25.00

.00

.0010.0025.0050. 00

Inpu LL.

3.0015.0053.0010.0070.00

6.0021.0051.0037.00

5.9912.3223.2923.2938.6538.6545.2954.7767. 30

-2.992.63

29.71-13.29

31.35-32.65-24.29

-3.7719.70


April 2008

C-153

CAPSULE Y (HEAT AFFECTED ZONE)

Page 2PiatParly FM 2 MaeriaL SA533B1 Hat: B7212-1Orienmazo: NA Capsu Y Punce: n/MA2

Chap V-Notch Data

hmpm L& Oaupad L.

50.0075.0090.00

125.00125.00150.00

77.0061.0091.0065.0081.0035. 00

67.3074.9477.6780.8780. 8781.76

9.70-13.94

13.33-15.87

.133.24

CautmAio cIc - .516


April 2008

C-154


CVGRAPH 5.3 Hyprbolic ¶bnm Cuve PinaSd on 02100M 0528 PMPageB 1

Cocffi•dmts of Cmrve 7A =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 F0fet fIocy2 Moxd: SASS3BI Set 572121

Odimniow NA Canuil: Fhmuw AknYQ2

2o

IaA

10dl

ID50

* UU

U

U

UU U

n 1400.0 0.0 300.0

Temperature In Dog F600.0

Chrpy V-Notch Data

- 80.00-15.0025.0035.0040.0045.0050.0070.0070. 00

22.00[5. 0015. 0014. 0038.0051.0041.0014. 0047.00

1.227.73

21. 1226.2729. 1032.0933.2148.4048.40

DUMEmdd

20. 787.27

-6.12-12.27

8.9011.913.79

-34.40- 1.40


April 2008

C-155


Pap 2Plait 1aft 2 Matedat SA533B1 Heat: B7212-1

Ouemazion: NA Capsule V Pluence: nlcr2

Charpy V-Notch Data

T7MP~m'

90.00115.00155.00200.00250.00260.00

f•PtwL.IL

70. 0085.0039.0094.0095.0072.00

-OMptdl.I

61.0673.5534.5088.8190.0890.18

8.9411.454.505.194.92

-13.13

Cmxttm Caeffid - A92


April 2008

C-156

UNIRRADIATD EAT AFFECTZONF

CVYGIAPH 5.3 Hypertbc lbagM Curvme Prnt on 021060O 05:30 PMPapI

Coeffiigmts of Care 1A=S0S B=50.C==18.06 TO=-11i6.09 B=m -BE400

qutiwan is A B' ITmnw((T-T)AC•t÷lT))jTSUpMmCtM at 50% Shear = -116.0

Plant Fley 2 Mateial: SA533BI Heat B7212-1Odenubm NA Cqwkl IJNIR Fiama: acn'Qr

Ilfl

aa

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 4m.0 50.O 600.0Temperture In Deo F

Charpy V-Netch Data

TmeMOM

-200.00-150.00-100. o0-100.00-50.00-50.00

20.0025.0050.00

3.00100.0045.0042.0060. 0034. 0032. 0033.00

100.00

camp PMfm SSer

28. 8640.9954.3154. 3167.0567.0581.2082.0085. 64

DIMnMl

-20.8659.01-9.31

-12.31-7.05

-33.05.80

1.0014.36


April 2008

C-i157

UNtRRADIATED (HEAT AFFECTED ZONE)

Plan. Padcy 2Ozitlom: NA

Pap 2Mmctri SA533BI H-eat B7212-1

Capmsle, UNIR Raum nlcnt2

Charpy V-Notch Data

D!a

75.00100.00150.00210.00210.00210.00

100.00100.00100.00100.0093.00

100.00

88.6491.0794. 5897.0897.0897.08

11.368.935.422.92

-4.032.92

Cozd -bfi -751


April 2008

C-158

CAPSUu (H AT AFFECTED ZONE)

CVGRAPH 5.3 Hyperblic Tangent Curve Punted on 021020 05:30 PMPap 1

CocfiMcnt of Come 2A=S. B=SL.C=76fl TOa.-2fM D = O01R+OO

Equtionis A +B 0 Tua(CF-To)hC+tDT)jTunpmertrn at 5 Shin= -2.0

Plant Fulcy2 Menial: SA533BI Heat fB7212-1Ofiwttion;A Csmuc:U Pluc nkm*2

125

100

IU£a

75

so

25

0 , I - I - - i i f - M -- I

-00.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0Temperature In Dog F

Charpy V-Notch Data

- 100.00-50.00-25.00

.00

.0050.0030.0075.0075. 00

5.0035.0052.0062.0037.0034.0032.0073.00

100.00

COMlmS Pan=m flr

13. 1636. 0152.0267.6367.6388.5888.5893.7393.73

-1.16- 1.01

-. 02-5.6319.37-4.58-6.58

-20.736.27


April 2008

C-159


Plant. Farley 2Orentaion: NA

Pap 2Material SA533B1 Heat B7212-1

Capsule U Pluence: n/m"2

Charpy V-Notch Data

"reavemm

100.00125.00175. o200.00250.00300.00

100.00100.00100.00100.00100.00100.00

- ShePao= a•e

96. 6598. 2399..5299.7599.9399.98

3.351.77

.48

.25

. 07- 02

Csunbsm Cbefficia - M56


April 2008

C-160

CAPSULE W (BEAT AFFECTED ZONE)

CVGRAPH1 5.3 Hypeolic TngMt Curve Plted on 021060M 05:31 FMPape 1

Coeffici--ti of cmuve 3A=5IL B-50.C=275 T0I--1I3S D=cO.OO+O

Equtkinis A +B B irmn((T-To)C+tDTD]Tcapau at .SO Shle = -11.3

Fadnt P..2 Maadia: SA533B1 BHat B7212-1Odmoaton:NA Cqu W Ebma¶ ulaa"1

126

100

V75

so

25

01 1400.0 -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

-100.00-100.00-50.00-50.00-25.00-25.00-20.00

.00

.00

9.0010. a0

9. 0013. 0016. 0031. C035.0049.0094. 00

comtaked PrrMM ffel"

.15

5.615.61

26.9926. 9934. 7769.7069.70

8.859.853.397.39

-10.994.01

.23-20.7024.30


April 2008

C-161

CAPStUL W (HEAT A1'FECrE ZONE)

Pagp 2Plant• l•ry2 Macri-SA533B1 H tB7212-I

Ofienic: NA Capsule: W Flue: njcmA2

Charp V-Notch Data

50.0076.00

125.00250.00250.00350.00

96.0097. 00

100. 0095. 00

100. 00100. 0o

c- Nd Shern

98.8999.83

100.00100.00100. 00100.00

-2.89-2.83

. 00-5.00

. 00

. 00

Canmuiaw Cbeffi4 .-- 72


April 2008

C-162

CAPSLE X O(AT AFFECTED ZONE)

CVGRAPH 5.3 Hyperbolic ThI Cunrv Prmted on 02160 05:31 PM

Co--mts of Curm 4A =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 B7212-1Odwimiow NA Cupm=l: X n~unz nftm"

I'U

-it.0 -200.0 -100A 0.0 100.0 200.0 300.0 400 .0 600.0Temperature In Dog F

Chm-p V-Notch Data

Tmjmn

-100.00-70.00-50.00-50.00-40.00-20.00

.00

.00

.00

IRM Pmnm show

5.005.00

35.0020.0035.0035.0065.0095.0025.00

6.2614.7724.6424.6431.0045.8861.5461.5461.54

-1.26-9.7710.36-4.644.00

-10.883.46

33.46-36.54


April 2008

C-163

CAPSULE X O(AT AFFECTED ZONE)

Plant Pary 2Orlemauion: NA

Page 2MatlntzU SA533B 1 Heat B7212-1

Caslm X Puence: n/fmA2

Charpy V-Notch Data

20.0050. 00

125.00200. 00250.00350.00

IDpuPflrOMt

100.0065.0075.00

100.00100. 00100.00

75. 1288.6798.8399.8999.98

100.00

24.88-23.67-23.83

.11

.02

.00

CwrznhM fbeffic , .572


April 2008

C-164


CVGRAPH 5.3 Hyprbolic Tangent Curve PrntS on 02AWO 05:32 FMPap I

Coefrfiiets of CaNrv 5Af=fSL B =5I&C=7M34 TO=16.15 D =S00E40

Equtismis A +SB rT•rm(T-ToC+tmT)JTempcnbzzc a 50% SMr = 16.2

Plant F.Iey2 Matidal: SAS33BI Heat B7212-lOdenicE 1A Cqwjc Z Pbxuzcc e an'Q

125

I'U

0

-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0Temperature In Dog F

Charpy V-Notch Data

- tOO. 00-60. 00-30. 00-20.00- 15. Oa-15.00

-10.00- 10. 00

* O0.00

Iupn PMnm

5.0020. 0015.0040. 0045.0025.0020.0025.00S0. 00

c(mkd n 5-=

3.6510.4621.4026.5229. 3632. 3632. 3638.8138.81

1.359.54

-6.4013.4315.64-7.36

-12.36-13.81

11.19


April 2008

C-165

CAPSULE Z (HEAT AFFECTED ZONK)

Pap 2Plantra&y2 M i A53- 1 I HeatB7212-1Odentatlon: NA Capsule.Z Phueace: nkmA2

Cha•r V-Notch Data

cmm Pao=Sh

10.0025.00

LO0. 00150.00195.0050.00

10.00100.00100.00100.00100.00

55.00

45.6856.2191.4097.7599.3672.20

naiad

-35.6843.79

8.602.25

.64-17.20

Canfw bed~cieS m .861


April 2008

C-166

CAPSULE Y MAT AFFECTED ZONE)

CVCRAPH 5.3 Hyperbuoc Tangent Curve Pnuted on 0210600 05:32 PMPape 1

Coefficzits of Curve 6A=-5IL I=- S C =67.51 TO1=43 D =.0.00E44

EPsunis is A + I W rr=W(T-ToAC+il)']¶bnpm t 50% Shcar= 4,L

Plant FP-by2 Maftal: ••33BI Heat f7212-IOdwutsiow.NA. Cipal: Y Mlug nkm"t2

I'UUa

400.0 -200.0 -100.0 0.0 100.0 200.0 3m0.0 400.0 m.0 600.0Tempenrsure In Dog F

Chap V-Notch Data

TupmrMm

-75.00-50. o0-25.00-25.00

.00

.0010.0025. 0050. 00

m Paem Sme

10. 0010. ao45. 0025.0090. 0020.0025.0055.00

100.00

OMPme PrM ffr

8. 5916.4729. 2629. 2646. 4546. 4553. 8564. 5379. 24

1.41-6.4715.74-4.2643.55

-26.45-23.85

-9.5320.76


April 2008

C-167

CAPSUL Y (HEAT AFFECTED ZONE)

Plant Padey 2Oriention: NA

Pagre 2Matcrink SA533B1 Hat B7212-1

Capule Y Rluence: nMA2

CharMp V-Notch Data

50.0075.0090.00

125.00125.00150.00

90.0065.00

100.00100.00100.00100.00

79.2488. 8992. 5897. 2497. 24gm. 66

10.76-23.89

7.422.762.761-34

Cormisd CbdFfcimft - -M5


April 2008

C-168

CAPSUME V (HEAT AFFECTED ZONE)

CVCRAPH 1.3 Hypuoc Tangwt Curve Pdnted on 02 O0W 05:32 PMPage 1

Cccffiiuts of Cmuv 7AS L B =S&Cc=5S& T0=56.34 D =S. OMIS

Equtia mis A +B I [1b(UT-T)AC+l'D))]Tcmpumy ma 50% Sher = 56A

lamnt FEcI 2 Matmial: SA533B1 HRe B7212-1Oziisow NA Cqma -: V i avutm"2

2

125

100

75

a

25

4100.0 -200.0 -100.0 0.0 100.0 200.0 uO0.0 400.0Temnperamre In Dog F

500. 600.0

Chmrp V-Notch Data

- 80.00-15.00

25.0035.0040.0045.0030.0070.0070.00

C pmamd= uMsr

2.0010.0020.0020.0040. 0060. 00S0. 0030. 0070. 00

* 767.24

24. 5931.8035. 7940. 0044. 3561.9761.97

1.242.76

-4.59-11.80

4.2120.00

5.65-31.97

1.03


April 2008

C-169


Pint FPeiy 2Odenudiom : NA

Pagp 2MaLc SA533B1 Hcat B721Z-

CapuIE V Pluhnce: nMfa2

Charpy V-Nolth Data

90.00115.00155.00200.00250.00260.00

30.00100.00100.00100.00100.00100.00

compmPaen t sbcw

76.9139.0697.1499.4299.9099. 93

3.0910.942.86

.58

.10*07

castiium canit - -M95


April 2008

D-1

APPENDIX DJOSEPH 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 NRCstaff for calculating the effects of neutron radiation embrittlement of the low-alloy steels currently usedfor 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 vesselbeltline materials using surveillance capsule data. The methods of Positions 2.1 and 2.2 can only beapplied 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 usethese surveillance data sets without additional margin, they must be shown to be credible. In accordancewith the discussion of Regulatory Guide 1.99, Revision 2, there are five requirements that, must be met forthe 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 iscredible.

D.2 EVALUATION

Criterion 1

Materials in the capsules should be those judged most likely to be controlling with regard toradiation embrittlement.

The beltline region of the reactor vessel is defined in Appendix G to 10 CFR Part 50, "Fracture ToughnessRequirements,'[D-2] as follows:

"the reactor vessel (shell material including welds, heat affected zones, and plates orforgings)that directly surrounds the effective height of the active core and adjacent regions of the reactorvessel that are predicted to experience sufficient neutron radiation damage to be considered in theselection of the most limiting material with regard to radiation damage."

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)


April 2008

D-2

The Farley Unit 2 surveillance program utilizes longitudinal and transverse test specimens fromintermediate 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, "StandardRecommended Practice for Surveillance Tests for Nuclear Reactor Vessels" [Ref. D-4]. Per Section 4.1of ASTM E 185-73, "The base metal and weld metal to be included in the program should represent thematerial that may limit the operation of the reactor during its lifetime. The test material should beselected on the basis of initial transition temperature, upper shelf energy level and estimated increase intransition temperature considering chemical composition (copper (Cu) and phosphorus (P)) and neutronfluence." At the time when the Farley Unit 2 surveillance program material was developed, intermediateshell plate B7212-1 was judged to be the most limiting and was therefore utilized in the surveillanceprogram.

The Farley Unit 2 surveillance program weld was fabricated using the shielded metal arc welding processand 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 thechemical variability found in copper-coated submerged arc weld wire. Although the surveillance weldmaterial does not represent the limiting reactor vessel beltline weld, the results of mechanical propertytests performed on the surveillance weld are considered to be representative of the property changesexpected in the reactor vessel beltline seams. The NRC explicitly approved the selection of the FarleyUnit 2 surveillance weld material on the basis that the limiting beltline material (i.e., intermediate plateB7212-1) was included in the surveillance program and conservative methods of analysis contained inRegulatory 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 1OCFR50 in the Farley Unit 2Operating License, thereby approving the selected surveillance weld material based on the NRCevaluation.

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 limitingbeltline weld. The limiting beltline material is intermediate plate B7212-1 which is more limiting thanany of the reactor vessel beltline welds and is included in the reactor vessel material surveillanceprogram. Therefore, the Farley Unit 2 reactor vessel material surveillance program provides assurancethat the radiation damage to the vessel can be adequately determined and the integrity of the Farley Unit 2reactor 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 unirradiatedconditions should be small enough to permit the determination of the 30 ft-lb temperature and USEunambiguously.


April 2008

D-3

All of the Farley Unit 2 Charpy energy versus temperature surveillance program data can be found inAppendix 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 theexpected variance of test results for these materials. Based on engineering judgment, the scatter in thedata presented in these plots is small enough to permit the determination of the 30 ft-lb temperature andthe USE of the Farley Unit 2 surveillance materials unambiguously. Hence, the Farley Unit 2 surveillanceprogram 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 than28°F for welds and 17'F for base metal. Even if the fluence range is large (two or more orders ofmagnitude), the scatter should not exceed twice those values. Even if the data fail this criterion foruse in shift calculations, they may be credible for determining decrease in USE if the upper shelfcan be clearly determined, following the definition given in ASTM E18 5 -8 2 ID-4.

The functional form of the least squares method as described in Regulatory Position 2.1 is utilized todetermine a best-fit line for this data and to determine if the scatter of these ARTNDT values about this lineis 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 fromweld 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 thenegative shifts in RTNDT as determined from the curve fit data. These chemistry factor calculations, usedto calculate ARTNDT scatter between the measured and predicted values, are provided in Table D- 1. Thecredibility 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 measuredARTNDT 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.


April 2008

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 0.738Plate B7212-l(lotudinal)1 W 1.73 1.151 167.7 193.0 1.324(Longitudinal)

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 0.738Plate B7212-l(Tansverse)-W 1.73 1.151 168.5 193.9 1.324(Transverse)

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(FF2 ) = (2906.13) + (20.091) = 144.6 0 F

Surveillance Weld U 0.605 0.859 -28.4 -24.4 0.738Material 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


April 2008

D-5

Table D-2 Farley Unit 2 Surveillance Capsule Data Scatter about the Best-Fit Line

Measured Predicted ScatterCF 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 YESB7212-1

(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 PlateB7212-1 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 NOWeld 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.


April 2008

D-6

From a statistical point of view, +/- ly (171F) would be expected to encompass 75 percent of the data. Itis still statistically acceptable to have 3 of 12 points fall outside the +/- 1Ii bound. The fact that 3measured ARTNDT values are slightly outside the bound of 17°F can be attributed to several factors, suchas: 1) the inherent uncertainty in the Charpy test data, 2) the use of symmetric hyperbolic tangent Charpycurve fitting program versus an asymmetric hyperbolic tangent Charpy curve fitting program or a handdrawn 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 thepredicted values for the plates. Hence, based on the arguments above, the plate data meets the intent ofthis 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 bandfor the surveillance weld material; therefore, the surveillance weld data is deemed "not credible" per thethird criterion.

Criterion 4

The irradiation temperature of the Charpy specimens in the capsule should match the vessel walltemperature 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 arepositioned 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 thereactor vessel wall and the specimens experience equivalent operating conditions such that thetemperatures 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, thiscriterion 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, theFarley Unit 2 surveillance data is deemed credible for the plate specimens and non-credible for the weldspecimens. Credibility of surveillance data is used to determine the appropriate margin term forcalculation of adjusted reference temperature in accordance with Reference D-1. Credible platesurveillance data may utilize a reduced oT. term of 8.5°F, while the non-credible weld surveillance datamust utilize the full (T. term of 28TF, in calculation of the margin term for determining the respectivevessel materials' Position 2.1 adjusted reference temperatures.


April 2008

D-7

D.4 REFERENCES

D-1 Regulatory Guide 1.99, Revision 2, Radiation Embrittlement of Reactor Vessel Materials,U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, May 1998.

D-2 Code of Federal Regulations, 1OCFR50, Appendix Q Fracture Toughness Requirements, andAppendix H, Reactor Vessel Material Surveillance Program Requirements, U.S. NuclearRegulatory Commission, Washington, D.C.

D-3 WCAP-8956, Revision 0, "Alabama Power Company, Joseph M. Farley Nuclear Plant Unit No. 2Reactor Vessel Radiation Surveillance Program," August 1977.

D-4 ASTM E185-82, Standard Practice for Conducting Surveillance Tests for Light-Water CooledNuclear Power Reactor Vessels, American Society for Testing and Materials.


April 2008

Documents

Westinghouse Non-Proprietary Class 3 · EXECUTIVE SUM M ARY ... Table 5-7 Instrumented Charpy Impact Test Results for the Farley Unit 2 Surveillance Weld Metal Irradiated to a Fluence