ML043000356

to WCAP-16245-NP, Analysis of Capsule X from Tennessee Valley Authority, Watt Bar Unit 1 Reactor Vessel Radiation Surveillance Program.

ML043000356
Person / Time
Site:	Watts Bar
Issue date:	04/30/2004
From:	Conermann J, Doumont C, Laubbam T Westinghouse
To:	Office of Nuclear Reactor Regulation
References
WCAP-16245-NP, Rev 0
Download: ML043000356 (252)

Text

ENCLOSURE 1 WATTS BAR NUCLEAR PLANT UNIT 1 WCAP-16245-NP, REVISION 0 ANALYSIS OF CAPSULE X FROM THE TENNESSEE VALLEY AUTHORITY, WATTS BAR UNIT 1 REACTOR VESSEL RADIATION SURVEILLANCE PROGRAM

Westinghouse Non-Proprietary Class 3 WCAP-16245-NP April 2004 Revision 0 Analysis of Capsule X from the Tennessee Valley Authority Watts Bar Unit 1 Reactor Vessel Radiation Surveillance Program e3 Westinghouse

WESTINGHOUSE NON-PROPRIETARY CLASS 3 WCAP-16245-NP, Revision 0 Analysis of Capsule X from the Tennessee Valley Authority, Watts Bar Unit 1 Reactor Vessel Radiation Surveillance Program T.J. Laubbam J. Conermann C. Doumont April 2004 Approved: vCOKE Ghergurovicbqanager Reactor Component Design & Analysis Westinghouse Electric Company LLC Energy Systems P.O. Box 355 Pittsburgh, PA 15230-0355 02004 Westinghouse Electric Company LLC All Rights Reserved

fiii TABLE OF CONTENTS LIST OF TABLES ................. iv LIST OF FIGURES ................. vi PREFACE ................... vii EXECUTIVE

SUMMARY

I

SUMMARY

OF RESULTS .1-1 2 INTRODUCTION .2-1 3 BACKGROUND. 3-1 4 DESCRIPTION OF PROGRAM .4-1 5 TESTING OF SPECIMENS FROM CAPSULE X .. 5-1 5.1 OVERVIEW ........................................................................................................... 5-1 5.2 CHARPY V-NOTCH IMPACT TEST RESULTS .5-3 5.3 TENSILE TEST RESULTS .5-5 5.4 1/2T COMPACT TENSION SPECIMEN TESTS .5-5 6 RADIATION ANALYSIS AND NEUTRON DOSIMETRY . .6-1

6.1 INTRODUCTION

.6-1 6.2 DISCRETE ORDINATES ANALYSIS .6-2 6.3 NEUTRON DOSIMETRY .6-5 6.4 CALCULATIONAL UNCERTAINTIES .6-6 7 SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE .7-1 8 REFERENCES .8-1 APPENDIX A VALIDATION OF THE RADIATION TRANSPORT MODELS BASED ON NEUTRON DOSIMETRY MEASUREMENTS CREDIBILITY .A-0 APPENDIX B LOAD-TIME RECORDS FOR CHARPY SPECIMEN TESTS .B-0 APPENDIX C CHARPY V-NOTCH PLOTS FOR EACH CAPSULE USING SYMMETRIC HYPERBOLIC TANGENT CURVE-FITTING METHOD .C-0 APPENDIX D WATTS BAR UNIT I SURVEILLANCE PROGRAM CREDIBILITY EVALUATION ............................................................................................... D-0

iv LIST OF TABLES Table 4-1 Chemical Composition (wt %) of the Watts Bar Unit I Reactor Vessel Surveillance Materials (Unirradiated) ..................................................... 4-3 Table 4-2 Heat Treatment History of the Watts Bar Unit I Reactor Vessel Surveillance Materials .... 4-4 Table 5-1 Charpy V-Notch Data for the Watts Bar Unit 1 Intermediate Shell Forging 05 Irradiated to a Fluence of 1.71 x 1019 n/cm 2 (E > 1.0 MeV) (Tangential Orientation).... 5-6 Table 5-2 Charpy V-Notch Data for the Watts Bar Unit I Intermediate Shell Forging 05 Irradiated to a Fluence of 1.71 x 1019 n/cm2 (E > 1.0 MeV) (Axial Orientation) ........... 5-7 Table 5-3 Charpy V-notch Data for the Watts Bar Unit I Surveillance Weld Material Irradiated to a Fluence of 1.71 x 1019 n/cm2 (E> 1.0 MeV) ....................................... 5-8 Table 5-4 Charpy V-notch Data for the Watts Bar Unit 1 Heat-Affected-Zone (HAZ)

Material Irradiated to a Fluence of 1.71 x 1019 n/cm 2 (E> 1.0 MeV) ........................... 5-9 Table 5-5 Instrumented Charpy Impact Test Results for the Watts Bar Unit 1 Intermediate Shell Forging 05 Irradiated to a Fluence of 1.71 x 1019 n/cm 2 (E> 1.0 MeV)

(Tangential Orientation) .............. 5-10 Table 5-6 Instrumented Charpy Impact Test Results for the Watts Bar Unit 1 Intermediate Shell Forging 05 Irradiated to a Fluence of 1.71 x 1019 n/cm 2 (E> 1.0 MeV)

(Axial Orientation) .......... 5-11 Table 5-7 Instrumented Charpy Impact Test Results for the Watts Bar Unit I Surveillance Weld Metal Irradiated to a Fluence of 1.71 x 1019 n/cm2 (E> 1.0 MeV) ..................... 5-12 Table 5-8 Instrumented Charpy Impact Test Results for the Watts Bar Unit 1 Heat-Affected-Zone (HAZ) Irradiated to a Fluence of 1.71 x 1019 n/cm2 (E> 1.0MeV) .................... 5-13 Table 5-9 Effect of Irradiation to 1.71 x 1019 n/cm 2 (E> 1.0 MeV) on the Notch Toughness Properties of the Watts Bar Unit I Reactor Vessel Surveillance Materials .......... ....... 5-14 Table 5-10 Comparison of the Watts Bar Unit I Surveillance Material 30 ft-lb Transition Temperature Shifts and Upper Shelf Energy Decreases with Regulatory Guide 1.99, Revision 2, Predictions ................. 5-15 Table 5-11 Tensile Properties of the Watts Bar Unit 1 Capsule X Reactor Vessel Surveillance Materials Irradiated to 1.71 x 1019 n/cm 2 (E> 1.0MeV) .................................... 5-16

LIST OF TABLES (Cont.)

Table 6-1 Calculated Neutron Exposure Rates and Integrated Exposures At The Surveillance Capsule Center ......................................... 6-12 Table 6-2 Calculated Azimuthal Variation of Maximum Exposure Rates and Integrated Exposures at the Reactor Vessel Clad/Base Metal Interface .................................... 6-16 Table 6-3 Relative Radial Distribution Of Neutron Fluence (E > 1.0 MeV) Within The Reactor Vessel Wall ............ 6-20 Table 6-4 Relative Radial Distribution of Iron Atom Displacements (dpa) Within The Reactor Vessel Wall ............ 6-20 Table 6-5 Calculated Fast Neutron Exposure of Surveillance Capsules Withdrawn from Watts Bar Unit I .6-21 Table 6-6 Calculated Surveillance Capsule Lead Factors .6-21 Table 7-1 Recommended Surveillance Capsule Withdrawal Schedule .7-1

Vi LIST OF FIGURES Figure 4-1 Arrangement of Surveillance Capsules in the Watts Bar Unit 1 Reactor Vessel ........... 4-5 Figure 4-2 Capsule X Diagram Showing the Location of Specimens, Thermal Monitors, and Dosimeters .4-6 Figure 5-1 Charpy V-Notch Impact Energy vs. Temperature for Watts Bar Unit I Reactor Vessel Intermediate Shell Forging 05 (Tangential Orientation) . 5-17 Figure 5-2 Charpy V-Notch Lateral Expansion vs. Temperature for Watts Bar Unit I Reactor Vessel Intermediate Shell Forging 05 (Tangential Orientation) . 5-18 Figure 5-3 Charpy V-Notch Percent Shear vs. Temperature for Watts Bar Unit 1 Reactor VesselIntermediate Shell Forging 05 (Tangential Orientation) . 5-19 Figure 5-4 Charpy V-Notch Impact Energy vs. Temperature for Watts Bar Unit I Reactor Vessel Intermediate Shell Forging 05 (Axial Orientation) . 5-20 Figure 5-5 Charpy V-Notch Lateral Expansion vs. Temperature for Watts Bar Unit 1 Reactor Vessel Intermediate Shell Forging 05 (Axial Orientation) .5-21 Figure 5-6 Charpy V-Notch Percent Shear vs. Temperature for Watts Bar Unit 1 Reactor Vessel Intermediate Shell Forging 05 (Axial Orientation) . 5-22 Figure 5-7 Charpy V-Notch Impact Energy vs. Temperature for Watts Bar Unit 1 Reactor Vessel Weld Metal . 5-23 Figure 5-8 Charpy V-Notch Lateral Expansion vs. Temperature for Watts Bar Unit 1 Reactor Vessel Weld Metal . 5-24 Figure 5-9 Charpy V-Notch Percent Shear vs. Temperature for Watts Bar Unit I Reactor VesselWeld Metal . 5-25 Figure 5-10 Charpy V-Notch Impact Energy vs. Temperature for Watts Bar Unit 1 Reactor Vessel Heat-Affected-Zone Material . 5-26 Figure 5-11 Charpy V-Notch Lateral Expansion vs. Temperature for Watts Bar Unit I Reactor Vessel H eat-Affected-Zone Material . 5-27 Figure 5-12 Charpy V-Notch Percent Shear vs. Temperature for Watts Bar Unit I Reactor Vessel Heat-Affected-Zone Material . 5-28 Figure 5-13 Charpy Impact Specimen Fracture Surfaces for Watts Bar Unit 1 Reactor Vessel Intermediate Shell Forging 05 (Tangential Orientation) . 5-29

vii LIST OF FIGURES (Cont.)

Figure 5-14 Charpy Impact Specimen Fracture Surfaces for Watts Bar Unit 1Reactor Vessel Intermediate Shell Forging 05 (Axial Orientation) ..................................................... 5-30 Figure 5-15 Charpy Impact Specimen Fracture Surfaces for Watts Bar Unit 1Reactor Vessel Weld Metal ..... 5-31 Figure 5-16 Charpy Impact Specimen Fracture Surfaces for Watts Bar Unit I Reactor Vessel Heat-Affected-Zone Metal ................. 5-32 Figure 5-17 Tensile Properties for Watts Bar Unit I Reactor Vessel Intermediate Shell Forging 05 (Tangential Orientation) ...................... 5-33 Figure 5-18 Tensile Properties for Watts Bar Unit 1 Reactor Vessel Intermediate Shell Forging 05 (Axial Orientation) .5-34 Figure 5-19 Tensile Properties for Watts Bar Unit 1 Reactor Vessel Weld Metal .5-35 Figure 5-20 Fractured Tensile Specimens from Watts Bar Unit 1 Reactor Vessel Intermediate Shell Forging 05 (Tangential Orientation) ................................... 5-36 Figure 5-21 Fractured Tensile Specimens from Watts Bar Unit I Reactor Vessel Intermediate Shell Forging 05 (Axial Orientation) .5-37 Figure 5-22 Fractured Tensile Specimens from Watts Bar Unit I Reactor Vessel Weld Metal. 5-38 Figure 5-23 Engineering Stress-Strain Curves for Intermediate Shell Forging 05 Tensile Specimens WL-10, WL-I 1 and WL-12 (Tangential Orientation) ........... ......... 5-39 Figure 5-24 Engineering Stress-Strain Curves for Intermediate Shell Forging 05 Tensile Specimens WT-10, WT-11 and WT-12 (Axial Orientation) ............................ 5-41 Figure 5-25 Engineering Stress-Strain Curves for Weld Metal Tensile Specimens WW-10, WW-1 l and W-12. 5-43 Figure 6-1 Watts Bar Unit 1 r,? Reactor Geometry at the Core Midplane .6-8 Figure 6-2 Watts Bar Unit I r,z Reactor Geometry with Neutron Pad .6-11

viii PREFACE This report has been technically reviewed and verified by:

Reviewer:

Sections 1 through 5, 7, 8,Appendices B, C and D C.M. Burton Section 6 and Appendix A S.L. Anderson kL",J(.,AD

Lx EXECUTIVE

SUMMARY

The purpose of this report is to document the results of the testing of surveillance Capsule X from Watts Bar Unit 1. Capsule X was removed at 6.63 EFPY 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 X received a fluence of 1.71 x 1019 n/cm 2 after irradiation to 6.63 EFPY. The peak clad/base metal interface vessel fluence after 6.63 EFPY of plant operation was 3.39 x los n/cm2 .

This evaluation lead to the following conclusions: 1)The measured 30 ft-lb shift in transition temperature values of the Intermediate Shell Forging 05 contained in capsule X (Tangential & Axial is less than the Regulatory Guide 1.99, Revision 2111, predictions. 2) The measured 30 ft-lb shift in transition temperature values of the weld metal contained in capsule X is less than the Regulatory Guide 1.99, Revision 2, predictions. 3) The measured percent decrease in upper shelf energy for all the surveillance materials of Capsules X contained in the Watts Bar Unit 1surveillance program are less than the Regulatory Guide 1.99, Revision 2 predictions. 4) The lower shell forging and the intermediate shell to lower shell girth weld materials exhibit a more than adequate upper shelf energy level for continued safe plant operation and are predicted to maintain an upper shelf energy greater than 50 ft-lb throughout the life of the vessel (32 EFPY) as required by I OCFR50, Appendix G 121. 5) The intermediate shell forging 05 is predicted to drop below 50 ft-lbs at 32 EFPY, however, it still remains above the 43 ft-lb lower bound as determined in WCAP-13587, Rev. 1(6]. 6) The Watts Bar Unit 1surveillance weld data was found to be credible, while the surveillance forging 05 material was found to be not-credible. This evaluation can be found in Appendix D.

Lastly, a brief summary of the Charpy V-notch testing can be found in Section 1. All Charpy V-notch data was plotted using a symmetric hyperbolic tangent curve fitting program.

1-1 1

SUMMARY

OF RESULTS The analysis of the reactor vessel materials contained in surveillance Capsule X, the third capsule removed and tested from the Watts Bar Unit 1 reactor pressure vessel, led to the following conclusions:

• The Charpy V-notch data presented in BWXT Report dated 9/10/01l31 were based on a re-plot of all capsule data from WCAP-9298, Rev. 314] and WVCAP-15046 151 using CVGRAPH, Version 5.0, which is a symmetric hyperbolic tangent curve-fitting program. The results presented here are also a re-plot from all the capsules because CVGRAPH has been updated to Version 5.0.2.

Appendix C presents the CVGRAPH, Version 5.0.2, Charpy V-notch plots and the program input data.

• Capsule X received an average fast neutron fluence (E> 1.0 MeV) of 1.71 x 1019 n/cm2 after 6.63 effective full power years (EFPY) of plant operation.

• Irradiation of the reactor vessel Intermediate Shell Forging 05 (heat number 527536) Charpy specimens, oriented with the longitudinal axis of the specimen parallel to the major working direction (tangential orientation), resulted in an irradiated 30 ft-lb transition temperature of 37.60 F and an irradiated 50 ft-lb transition temperature of 87.20 F. This results in a 30 ft-lb transition temperature increase of 94.70 F and a 50 ft-lb transition temperature increase of 102.6 0 F for the longitudinal oriented specimens. See Table 5-9.

• Irradiation of the reactor vessel Intermediate Shell Forging 05 (heat number 527536) Charpy specimens, oriented with the longitudinal axis of the specimen perpendicular to the major working direction (axial orientation), resulted in an irradiated 30 ft-lb transition temperature of 161.10 F and an irradiated 50 ft-lb transition temperature of 218.30 F. This results in a 30 ft-lb transition temperature increase of 115.90F and a 50 fl-lb transition temperature increase of 104.10 F for the longitudinal oriented specimens. See Table 5-9.

• Irradiation of the weld metal (heat number 895075) Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of -5.4 0 F and an irradiated 50 ft-lb transition temperature of 37.90 F.

This results in a 30 ft-lb transition temperature increase of 25.81F and a 50 fl-lb transition temperature increase of 43.80 F. See Table 5-9.

• Irradiation of the weld Heat-Affected-Zone (HAZ) metal Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 18.60 F and an irradiated 50 ft-lb transition temperature of 62.50 F. This results in a 30 ft-lb transition temperature increase of 74.80 F and a 50 ft-lb transition temperature increase of 71.1 0F. See Table 5-9.

• The average upper shelf energy of the Intermediate Shell Forging 05 (tangential orientation) resulted in an average energy decrease of 26 fl-lb after irradiation. This results in an irradiated average upper shelf energy of 106 ft-lb for the longitudinal oriented specimens. See Table 5-9.

Summary of Results

1-2

• The average upper shelf energy of the Intermediate Shell Forging 05 (axial orientation) resulted in no energy decrease after irradiation. This results in an irradiated average upper shelf energy of 62 ft-lb for the tangential oriented specimens. See Table 5-9.

• The average upper shelf energy of the weld metal Charpy specimens resulted in no energy decrease after irradiation. This results in an irradiated average upper shelf energy of 131 ft-lb for the weld metal specimens. See Table 5-9.

• The average upper shelf energy of the weld HAZ metal Charpy specimens resulted in an average energy decrease of 9 ft-lb after irradiation. This results in an irradiated average upper shelf energy of 80 ft-lb for the weld HAZ metal. See Table 5-9.

• A comparison, as presented in Table 5-10, of the Watts Bar Unit 1reactor vessel surveillance material test results with the Regulatory Guide 1.99, Revision 2111 predictions led to the following conclusions:

- The measured 30 fl-lb shift in transition temperature values of the Intermediate Shell Forging 05 contained in capsule X (longitudinal & transverse) are less than the Regulatory Guide 1.99, Revision 2, predictions.

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

- The measured percent decrease in upper shelf energy for all the surveillance materials of Capsules X contained in the Watts Bar Unit I surveillance program are less than the Regulatory Guide 1.99, Revision 2 predictions.

• The calculated end-of-license (32 EFPY) neutron fluence (E> 1.0 MeV) at the core midplane for the Watts Bar Unit I reactor vessel using the Regulatory Guide 1.99, Revision 2 attenuation formula (i.e., Equation #3 in the guide) are as follows:

Calculated: Vessel inner radius* = 1.541 x 1019 n/cm2 Vessel 1/4 thickness = 9.27 x 1018 n/cm 2 Vessel 3/4 thickness = 3.36 x 10's n/cm2

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

Summary of Results

1-3 All beltline materials, with exception to the intermediate shell forging 05, are expected to have an upper shelf energy (USE) greater than 50 fl-lb through end of license (EOL, 32 EFPY) as required by 10CFR50, Appendix d21.

In September of 1993, Westinghouse completed an evaluation to demonstrate that all Westinghouse Owners Group (WOG) Plant reactor vessels have a margin of safety, relative to USE, equivalent to that required by Appendix G of the ASME Code. This was accomplished by performing generic bounding evaluations per the proposed ASME Section XI, Appendix X. This evaluation is documented in WCAP-13587, Revision 1[6] , "Reactor Vessel Upper Shelf Energy Bounding Evaluation for Westinghouse Pressurized Water Reactors" and provides the minimum USE for a four loop Westinghouse NSSS plant. The minimum acceptable USE for a 4 loop plant is 43 fl-lb. The projected minimum EOL USE for the Watts Bar Unit I intermediate shell forging 05 is greater than 43 ft-lb. Hence, the bounding WOG evaluation shows that the Watts Bar Unit I intermediate shell forging 05 will maintain an equivalent margin, with respect to USE per the requirements of 10 CFR Part 50, Appendix G,through EOL (i.e. Maintain this margin through EOL). In addition, the results of capsule X testing indicate that the measured EOL USE for the axially oriented Charpy specimens actually increased by approximately 4 ft-lb.

In addition, as part of the Capsule W testing, Framatome performed 1/2T compact tension tests to determine the upper shelf J-R curve for the intermediate shell forging 05. The purpose of this test was to demonstrate that the Watts Bar Unit 1 reactor vessel has margins of safety equivalent to the ASME Code Appendix G. The results were that the low upper shelf for intermediate shell forging 05 had sufficient margin. Lastly, as part of this capsule testing, Westinghouse will be performing a similar test and analysis, with the same purpose as that was previously performed by Framatome. This report will be published following the issuance of this report.

Summary of Results

2-1 2 INTRODUCTION This report presents the results of the examination of Capsule X, the third capsule removed from the reactor in the continuing surveillance program which monitors the effects of neutron irradiation on the Watts Bar Unit I reactor pressure vessel materials under actual operating conditions.

The surveillance program for the Watts Bar Unit 1reactor pressure vessel materials was designed and recommended by the Westinghouse Electric Corporation. A description of the surveillance program and the pre-irradiation mechanical properties of the reactor vessel materials are presented in WCAP-9298, "Tennessee Valley Authority Watts Bar Unit No. I Reactor Vessel Radiation Surveillance Programn' 14 1.

The surveillance program was planned to cover the 40-year design life of the reactor pressure vessel and was based on ASTM El85-73193, "Standard Recommended Practice Surveillance Tests for Nuclear Reactor Vessels." Capsule X was removed from the reactor after 6.63 EFPY of exposure and shipped to the Westinghouse Science and Technology Department Hot Cell Facility, where the post-irradiation mechanical testing of the Charpy V-notch impact and tensile surveillance specimens was performed.

This report summarizes the testing of and the post-irradiation data obtained from surveillance capsule X removed from the Watts Bar Unit 1 reactor vessel and discusses the analysis of the data.

Introduction

3-1 3 BACKGROUND The ability of the large steel pressure vessel containing the reactor core and its primary coolant to resist fracture constitutes an important factor in ensuring safety in the nuclear industry. The beitline region of the reactor pressure vessel is the most critical region of the vessel because it is subjected to significant fast neutron bombardment. The overall effects of fast neutron irradiation on the mechanical properties of low alloy, ferritic pressure vessel steels such as A508 Class 2 Forging (base material of the Watts Bar Unit I reactor pressure vessel beitline) are well documented in the literature. Generally, low alloy ferritic materials show an increase in hardness and tensile properties and a decrease in ductility and toughness during high-energy irradiation.

A method for ensuring the integrity of reactor pressure vessels has been presented in "Fracture Toughness Criteria for Protection Against Failure," Appendix G to Section XI of the ASME Boiler and Pressure Vessel Codel8l. The method uses fracture mechanics concepts and is based on the reference nil-ductility transition temperature (RTNDT)-

RTNDT is defined as the greater of either the drop weight nil-ductility transition temperature (NDTT per ASTM E-208171) or the temperature 60'F less than the 50 ft-lb (and 35-mil lateral expansion) temperature as determined from Charpy specimens oriented perpendicular (transverse) to the major working direction of the plate. The RTNDT of a given material is used to index that material to a reference stress intensity factor curve (Krc curve) which appears in Appendix G to the ASME Code17 . The Ki. curve is a lower bound of static fracture toughness results obtained from several heats of pressure vessel steel. When a given material is indexed to the K1 , curve, allowable stress intensity factors can be obtained for this material as a function of temperature. Allowable operating limits can then be determined using these allowable stress intensity factors.

RTNDT and, in turn, the operating limits of nuclear power plants can be adjusted to account for the effects of radiation on the reactor vessel material properties. The changes in mechanical properties of a given reactor pressure vessel steel, due to irradiation, can be monitored by a reactor vessel surveillance program, such as the Watts Bar Unit 1 reactor vessel radiation surveillance programti, in which a surveillance capsule is periodically removed from the operating nuclear reactor and the encapsulated specimens tested.

The increase in the average Charpy V-notch 30 fl-lb temperature (ARTNDT) due to irradiation is added to the initial RTNDT, along with a margin (M) to cover uncertainties, to adjust the RTNDT (ART) for radiation embrittlement This ART (RTNDT initial + M + ARTNDT) is used to index the material to the K1 , curve and, in turn, to set operating limits for the nuclear power plant that take into account the effects of irradiation on the reactor vessel materials.

Background

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

Capsule X was removed after 6.63 effective full power years (EFPY) of plant operation. This capsule contained Charpy V-notch, tensile, and 1/2T-CT fracture mechanics specimens made from intermediate shell forging 05 (heat number 527536) and submerged arc weld metal identical to the reactor vessel beltline region weld. In addition, this capsule contained Charpy V-notch specimens from the weld Heat-Affected-Zone (HAZ) metal of intermediate shell forging 05.

Test material obtained from the intermediate shell forging 05 (after thermal heat treatment and forming of the plate) was taken at least one plate thickness from the quenched edges of the plate. All test specimens were machined from the 1/4 thickness location of the plate after performing a simulated post-weld stress-relieved weldment joining intermediate shell forging 05 and adjacent lower shell forging 04. All heat-affected-zone specimens were obtained from the weld heat-affected-zone of the intermediate shell forging 05.

Charpy V-notch impact specimens from intermediate shell forging 05 were machined in the tangential orientation (longitudinal axis of the specimen parallel to the major working direction) and also in the axial orientation (longitudinal axis of the specimen perpendicular to the major working direction). The core region weld Charpy impact specimens were machined from the weldment such that the long dimension of each Charpy specimen was perpendicular to the weld direction. The notch of the weld metal Charpy specimens was machined such that the direction of crack propagation in the specimen was in the welding direction.

Tensile specimens from the intermediate shell forging 05 were machined in both the tangentialand axial orientations. Tensile specimens from the weld metal were oriented with the long dimension of the specimen perpendicular to the weld direction.

Bend bar specimens were machined from the intermediate shell forging 05 with the longitudinal axis of the specimen oriented in the rolling direction of the forging such that the simulated crack would propagate in a direction normal to the rolling direction of the forging. All bend bar specimens were fatigue pre-cracked according to ASTM E399.

Compact tension test specimens from intermediate shell forging 05 were machined in the tangentialand axial orientations. Compact tension test specimens from the weld metal were machined perpendicular to the weld direction with the notch oriented in the direction of welding. All specimens were fatigue pre-cracked according to ASTM E399.

Description of Program

4-2 The chemical composition and heat treatment of the unirradiated surveillance materials are presented in Tables 4-1 and 4-2, respectively. The data in Table 4-1 and 4-2 was obtained from the unirradiated surveillance program report, WCAP-9298, Rev. 3, Appendix A.

Capsule X contained dosimeter wires of pure iron, copper, nickel, and aluminum 0.15 weight percent cobalt (cadmium-shielded and unshielded). In addition, cadmium shielded dosimeters of neptunium (Np 3) and uranium (Ues) were placed in the capsule to measure the integrated flux at specific neutron energy levels.

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

2.5% Ag, 97.5% Pb Melting Point: 5790 F (3040 C) 1.75% Ag, 0.75% Sn, 97.5% Pb Melting Point: 5901F (3101C)

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

Description of Program

4-3

• v. . .. - . .. . e . .  ;{-P TabaeJ-1l Chemic 1 CoMposition ('iio)iof the Watt BarUnit 1 Reactorvessel

. *Sai- eillance Mat laia

. ... Intermediat S Fcrgig -.....

C 0.20 0.21 0.080 0.069 S 0.016 0.014 0.007 0.010 N 0.009 --- 0.019 Co <0.01 0.012 0.007 Cu 0.17 0.14 0.031 0.05 Si 0.25 0.25 0.27 0.22 Mo 0.57 0.61 0.54 0.56 Ni 0.80 0.79 0.75 0.70 Mn 0.73 0.68 1.94 1.97 Cr 0.32 0.34 0.023 0.05 V <0.01 <0.02 0.001 P 0.012 0.013 0.015 0.010 Al <0.019 0.049 0.019 Sn 0.010 --- 0.003 Notes (a) All analysis except for N and Sn were conducted by Rotterdam Dockyard Company/Krupp ladle analysis; N and Sn analysis were performed by Westinghouse.

(b) The surveillance weldment is identical to the closing girth seam weldment between forging 04 and 05.

The closing seam used weld wire heat number 895075 with Grau L.O. (LW320) flux, lot P46, except for the 1-inch root pass at the ID of the vessel. This root pass used weld wire heat number 899680 with type Grau L.O. (LW320) flux, lot P23, with as as-deposited copper and phosphorus content of 0.03 and 0.009, respectively. The surveillance weldment specimens were not removed from this root area.

(c) The left column results were obtained from Westinghouse analyses, while the results in the right column results were obtained from analyses conducted by Rotterdam Dockyard Company.

Description of Program

4-4

• T'ble 4-2':Jeat tream.ent i lto blk ar s:the i

~Matc~ii 0*9~~**TnnriueJ Intermediate Shell Forging 05 1675 - 1700 3 I/2 Water-quenched 1230 - 1240 6 Air Cooled 1140 +25 21 Fumace Cooled Weldment 1140 + 25 14 hr., 56 min Fumace Cooled Notes:

(a) This table was taken from WCAP-9298, Rev. 3141.

Description of Program

4.5 REACTOR VESSELq

,,-CORE BARREL

%,.- NEUTRON PAD CAPSULJE (TYP) 270' 90' 50I Figure 4-1 Arrangement of Surveillance Capsules in the Watts BarUnit 1 Reactor Vessel Description of Program

4-6 LEGEND: WI, - INTERMEDIATE SHIELL FORGING 05, IEAT NO. 527638 (TANGENTIAL)

WT - INTERMEDIATE SHELL FORGING 05, HEAT NO. 527638 (AXIAL) Cu  : Al-,lS1to WW - WELD METAL (IIEAT # 895075) Fe g ii WH - IIEAT AFFECTED ZONE MATERIAL 579-Ft Al_ lSto (Cd)

M~ONITOR Ben Tensile Compact Compact Clmrpy Cliarpy Clharpy Compact d

Bar WW60 _ WH60 WW57 lWH57 WW54 lWH54 V4 Wll WW16 VW15 WW4W1 W59 W11591 WW56 WH56 WW3 WH53 W16 WL15 WW58 _W1158 lWW55 _WH55 WW52 WH52 TOP OF VESSEL 4 CENTER Np2 Uz:!

Compact Charpy Clarpy Dosimeter Tnsile Charpy Clharpy lWW5 WH1 lVW48 WH48 1W2 WT6O WL60 WT57 Wl57 WL14 WL13 WW50 llW150 WW47W<>H47 l 2 LI lI T5 WL59 l WT56 l WL56l WW49 lVlW49 WW46 VH46 WLI0 WT58 WL58 WT55 VlW55 CENTER BOTTOM OF VESSEL CU S A.l 5%C MI Al-.-ICo F Fit~

,TOR 1 -eAl_.1%C8 (Cd) S90 -F l .I-SISCo (Cd)

C Charpy arpy Compact Compact Tensile lW1'5` ll54 4I T5 WL51llW4ll WLA8 r WT12ll lWT53l W ll L l 47 l lWTL47 l *VT16 lWT15l WT14 lWT13 NMI T52 l WT49 lWLA9 WT46 WA6 llWTI0Mll Figure 4-2 Capsule X Diagram Showing The Location of Specimens, Thermal Monitors, and Dosimeters Description of Program

5-1 5 TESTING OF SPECIMENS FROM CAPSULE X 5.1 OVERVIEWN' The post-irradiation mechanical testing of the Charpy V-notch impact specimens and tensile specimens was performed in the Remote Metallographic Facility (RMF) at the Westinghouse Science and Technology Center. Testing was performed in accordance with IOCFR50, Appendices G and HI2 I,ASTM Specification El 85-82191, and Westinghouse Procedure RMF 840211[°, Revision 2 as modified by Westinghouse RMF Procedures 8102[i1", Revision l, and 8103["], Revision 1.

Upon receipt of the capsule at the hot cell laboratory, the specimens and spacer blocks were carefully removed, inspected for identification number, and checked against the master list in WCAP-9298, Rev.

3141. No discrepancies were found.

Examination of the two low-melting point 5790 F (304'C) and 590'F (310'C) eutectic alloys indicated no melting of either type of thermal monitor. Based on this examination, the maximum temperature to which the test specimens were exposed was less than 5791F (3040C).

The Charpy impact tests were performed per ASTM Specification E23-02aE13 J and RMF Procedure 8103 on a Tinius-Olsen Model 74, 358J machine. The tup (striker) of the Charpy impact test machine is instrumented with a GRC 930-1 instrumentation system, feeding information into an IBM compatible computer. With this system, load-time and energy-time signals can be recorded in addition to the standard measurement of Charpy energy (ED). From the load-time curve (Appendix B), the load of general yielding (PGY), the time to general yielding (toy), the maximum load (PM), and the time to maximum load (to1) can be determined. Under some test conditions, a sharp drop in load indicative of fast fracture was observed.

The load at which fast fracture was initiated is identified as the fast fracture load (PF), and the load at which fast fracture terminated is identified as the arrest load (PA).

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

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

ar = (PGy

• L) /[B * (- a)2

• C] (1) where: L distance between the specimen supports in the impact machine B = the width of the specimen measured parallel to the notch W = height of the specimen, measured perpendicularly to the notch a notch depth The constant C is dependent on the notch flank angle (4), notch root radius (p) and the type of loading (i.e., pure bending or three-point bending). In three-point bending, for a Charpy specimen in which t =

450 and p = 0.010 inch, Equation 1 is valid with C = 1.21. Therefore, (for L = 4W),

Testing of Specimens from Capsule X

5-2 a,=(PGy*L)/[B *(V a)2

• 1.21]= (3.305 *PGy* IY) /[B *( JV_ a)2 ] (2)

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

ay 33.3

• Pr (3) where cry is in units of psi and PGy is in units of lbs. The flow stress was calculated from the average of the yield and maximum loads, also using the three-point bend formula The symbol A in columns 4, 5, and 6 of Tables 5-5 through 5-8 is the cross-section area under the notch of the Charpy specimens:

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

Percent shear was determined from post-fracture photographs using the ratio-of-areas methods in compliance with ASTM Specification E23-98 and A370-97a1 l41 . The lateral expansion was measured using a dial gage rig similar to that shown in the same specification.

Tensile tests were performed on a 20,000-pound Instron, split-console test machine (Model 1115) per ASTM Specification E8-01 115 l and E21-92 (1998)(161, and Procedure RMF 8102. All pull rods, grips, and pins were made of Inconel 718. The upper pull rod was connected through a universal joint to improve axiality of loading. The tests were conducted at a constant crosshead speed of 0.05 inches per minute throughout the test.

Extension measurements were made with a linear variable displacement transducer extensometer. The extensometer knife-edges were spring-loaded to the specimen and operated through specimen failure.

The extensometer gage length was 1.00 inch. The extensometer is rated as Class B-2 per ASTM E83-93117.

Elevated test temperatures were obtained with a three-zone electric resistance split-tube furnace with a 9-inch hot zone. All tests were conducted in air. Because of the difficulty in remotely attaching a thermocouple directly to the specimen, the following procedure was used to monitor specimen temperatures. ChromelAlumel thermocouples were positioned at the center and at each end of the gage section of a dummy specimen and in each tensile machine griper. In the test configuration, with a slight load on the specimen, a plot of specimen temperature versus upper and lower tensile machine griper and controller temperatures was developed over the range from room temperature to 550TF. During the actual testing, the grip temperatures were used to obtain desired specimen temperatures. Experiments have indicated that this method is accurate to +20F.

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

Testing of Specimens from Capsule X

5-3 5.2 CHARPY V-NOTCH IMPACT TEST RESULTS The results of the Charpy V-notch impact tests performed on the various materials contained in Capsule X, which received a fluence of 1.71 x 1019 n/cm2 (E> 1.0 MeV) in 6.63 EFPY of operation, are presented in Tables 5-1 through 5-11 and are compared with unirradiated results[4 1 as shown in Figures 5-1 through 5-12.

The transition temperature increases and upper shelf energy decreases for the Capsule X materials are summarized in Table 5-9 and led to the following results:

Irradiation of the reactor vessel Intermediate Shell Forging 05 (heat number 527536) Charpy specimens, oriented with the longitudinal axis of the specimen parallel to the major working direction (tangential orientation), resulted in an irradiated 30 ft-lb transition temperature of 37.69F and an irradiated 50 fl-lb transition temperature of 87.20F. This results in a 30 fl-lb transition temperature increase of 94.7'F and a 50 ft-lb transition temperature increase of 102.60 F for the longitudinal oriented specimens.

Irradiation of the reactor vessel Intermediate Shell Forging 05 (heat number 527536) Charpy specimens, oriented with the longitudinal axis of the specimen perpendicular to the major wcrking direction (axial orientation), resulted in an irradiated 30 ft-lb transition temperature of 161.1 0F and an irradiated 50 ft-lb transition temperature of 218.30 F. This results in a 30 ft-lb transition temperature increase of 115.9 0 F and a 50 ft-lb transition temperature increase of 104.10 F for the longitudinal oriented specimens.

Irradiation of the weld metal (heat number 895075) Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of -5.40 F and an irradiated 50 ft-lb transition temperature of 37.90 F. This results in a 30 ft-lb transition temperature increase of 25.80 F and a 50 ft-lb transition temperature increase of 43.80F.

Irradiation of the weld Heat-Affected-Zone (HAZ) metal Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 18.6 0 F and an irradiated 50 ft-lb transition temperature of 62.50 F. This results in a 30 ft-lb transition temperature increase of 74.8WF and a 50 ft-lb transition temperature increase of 71.1WF.

The average upper shelf energy of the Intermediate Shell Forging 05 (tangential orientation) resulted in an average energy decrease of 26 ftl-lb after irradiation. This results in an irradiated average upper shelf energy of 106 ft-lb for the longitudinal oriented specimens.

The average upper shelf energy of the Intermediate Shell Forging 05 (axial orientation) resulted in no energy decrease after irradiation. This results in an irradiated average upper shelf energy of 62 ft-lb for the tangential oriented specimens.

The average upper shelf energy of the weld metal Charpy specimens resulted in no energy decrease after irradiation. This results in an irradiated average upper shelf energy of 131 ft-lb for the weld metal specimens.

Testing of Specimens from Capsule X

5-4 The average upper shelf energy of the weld HAZ metal Charpy specimens resulted in an average energy decrease of 9 ft-lb after irradiation. This results in an irradiated average upper shelf energy of 80 ft-lb for the weld HAZ metal.

A comparison, as presented in Table 5-10, of the Watts Bar Unit I reactor vessel surveillance material test results with the Regulatory Guide 1.99, Revision 2r11 predictions led to the following conclusions:

- The measured 30 ft-lb shift in transition temperature values of the intermediate shell forging 05 contained in capsule X (longitudinal & transverse) are less than the Regulatory Guide 1.99, Revision 2, predictions.

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

- The measured percent decrease in upper shelf energy for all the surveillance materials of Capsules X contained in the Watts Bar Unit I surveillance program are less than the Regulatory Guide 1.99, Revision 2 predictions.

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

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

The results presented in this report are a re-plot of all past capsule data and the new capsule X data based on using CVGRAPH, Version 5.0.2. Appendix C presents the individual CVGRAPH, Version 5.0.2, Charpy V-notch plots and the program input data.

All beltline materials, with exception to the intermediate shell forging 05, are expected to have an upper shelf energy (USE) greater than 50 ft-lb through end of license (EOL, 32 EFPY) as required by 10CFR50, Appendix G121.

In September of 1993, Westinghouse completed an evaluation to demonstrate that all Westinghouse Owners Group (WOG) Plant reactor vessels have a margin of safety, relative to USE, equivalent to that required by Appendix G of the ASME Code. This was accomplished by performing generic bounding evaluations per the proposed ASME Section XI, Appendix X. This evaluation is documented in WCAP-13587, Revision 161], "Reactor Vessel Upper Shelf Energy Bounding Evaluation for Westinghouse Pressurized Water Reactors" and provides the minimum USE for a four loop Westinghouse NSSS plant.

The minimum acceptable USE for a 4 loop plant is 43 ft-lb. The projected minimum EOL USE for the Watts Bar Unit 1 intermediate shell forging 05 is greater than 43 ft-lb. Hence, the bounding WOG evaluation shows that the Watts Bar Unit 1 intermediate shell forging 05 will maintain an equivalent margin, with respect to USE per the requirements of 10 CFR Part 50, Appendix G, through EOL (ie.

Maintain this margin through EOL). In addition, the results of capsule X testing indicate that the measured EOL USE for the axially oriented Charpy specimens actually increased by approximately 4 ft-lb.

Testing of Specimens from Capsule X

5-5 In addition, as part of the Capsule W testing, Framatome performed 1/2T compact tension tests to determine the upper shelf J-R curve for the intermediate shell forging 05. The purpose of this test was to demonstrate that the Watts Bar Unit I reactor vessel has margins of safety equivalent to the ASME Code Appendix G. The results were that the low upper shelf for intermediate shell forging 05 had sufficient margin. Lastly, as part of this capsule testing, Westinghouse will be performing a similar test and analysis, with the same purpose as that was previously performed by Framatome. This report will be published following the issuance of this report.

5.3 TENSILE TEST RESULTS The results of the tensile tests performed on the various materials contained in Capsule X irradiated to 1.71 x 1019 n/cm 2 (E> 1.0 MeV) are presented in Table 5-11 and are compared with unirradiated results41 as shown in Figures 5-17 and 5-19.

The results of the tensile tests performed on the Intermediate Shell Forging 05 (tangential orientation) indicated that irradiation to 1.71 x 1019 n/cm 2 (E> 1.0 MeV) caused approximately a 6 to 10 ksi increase in the 0.2 percent offset yield strength and approximately a 6 to 10 ksi increase in the ultimate tensile strength when compared to unirradiated data141. See Figure 5-17.

The results of the tensile tests performed on the Intermediate Shell Forging 05 (axial orientation) indicated that irradiation to 1.71 x 1019 n/cm? (E> 1.0 MeV) caused approximately a 8 to 12 ksi increase in the 0.2 percent offset yield strength and approximately a 9 to 12 ksi increase in the ultimate tensile strength when compared to unirradiated data141. See Figure 5-18.

The results of the tensile tests performed on the surveillance weld metal indicated that irradiation to 1.71 x 1019 n/cm2 (E> 1.0 MeV) caused approximately a 5 to 9 ksi increase in the 0.2 percent offset yield strength and approximately a 4 to 6 ksi increase in the ultimate tensile strength when compared to unirradiated datal4l. See Figure 5-19.

The fractured tensile specimens for the Intermediate Shell Forging 05 material are shown in Figures 5-20 and 5-21, while the fractured tensile specimens for the surveillance weld metal are shown in Figure 5-22.

The engineering stress-strain curves for the tensile tests are shown in Figures 5-23 through 5-25.

5.4 1/2T COMPACT TENSION SPECIMEN TESTS Per the surveillance capsule testing contract, the 1/2T Compact Tension Specimens are to be tested. The test results and corresponding evaluations will be presented in a separate report published after the issuance of this report.

Testing of Specimens from Capsule X

5-6 Table.5- Chary

.. . ..notchData fo'rITe Watts Dar.Unit I Jntermediate Shell Forging 05 I ;i;............ ;.i.

. v;ii.

......... .... ....;. ;i..; ....... . T":n e a; . if;..

Sample -:.. Temperature .><z>-<ImpattEncrgy < Latera i panslon ii Shear

i. ..: .i.;.:.::;

.. .......... . .i:... .j .j . .........  :: i i............. ... .

.. : i:i :....... .............

WL55 -75 -59 10 14 4 0.10 2 WL60 -50 -46 8 11 0 0.00 2 WL54 -25 -32 22 30 14 0.36 5 WL50 0 -18 25 34 13 0.33 5 WL47 25 -4 22 30 11 0.28 10 WL52 40 4 29 39 16 0.41 10 WL57 50 10 42 57 25 0.64 20 WVL51 75 24 31 42 19 0.48 20 WL58 100 38 63 85 40 1.02 40 WL53 125 52 64 87 44 1.12 60 WL56 160 71 75 102 48 1.22 75 WL59 180 82 79 107 51 1.30 75 NWL49 225 107 107 145 72 1.83 100 WL46 250 121 101 137 69 1.75 100 WL48 250 121 111 151 71 1.80 100 Testing of Specimens from Capsule X

5-7 ITable 5 Ca2 tc. a o e Bai tenne ia l

.Irradiated

"- ;r la .;t to

,;t aFlueneeof

.F,16'bf

L7fx , /1........................

meV) (Axial

.t Orientatio) fi.,

Sample -Temperature  ;-Impat tEnergy L ateral Expansion; Shear

~~~~~~~~~~~~~~~~~~~~~~~. . . . ... . . . .......

s........s.;.

Number. .F -C ft lbs Jouics'. mils.- mm/

WT60 0 -18 4 5 0 0.00 2 WT47 50 10 12 16 7 0.18 5 NVT57 100 38 13 18 13 0.33 15 NN'T54 125 52 28 38 22 0.56 20 WT49 125 52 16 22 14 0.36 20 WT56 150 66 27 37 24 0.61 25 WT58 175 79 30 41 26 0.66 40 WT59 200 93 36 49 30 0.76 40 NVT46 210 99 38 52 33 0.84 60 WVT50 225 107 52 71 44 1.12 80 WT51 250 121 66 89 50 1.27 100 WT53 250 121 64 87 52 1.32 100 WT48 275 135 73 99 53 1.35 100 WT52 275 135 63 85 49 1.24 100 NVT55 300 149 64 87 55 1.40 100 Testing of Specimens from Capsule X

5-8

.. . .. .. .... . ... . ...  ; . i ,  ; , i Table~~~~C( hap>-nocl--t .......

::::. i:. .::.:.Y ri.:: :: i:::: .:.; 5:.::orteW *::: i .:tsBrUnt- i::::: :..: ; >i i:; :.:urV-nc>W l ~tl

.tr ............-vv n:

' .: .'::i:-s';~fi rzt tzn V^: -. t:7 ' : i.:'.e .. '.........................................,:j n :'.J...................................

-' :j.:- > ...::

t '. v o N  :::::::-i:::::::>..........::::;:>::.:%::::

9 ' ' - i; -: .9 :',:9, 99:9 Sample

......... ..  : ,:.;Te s,,...........

pe.i tur.........r I .; .. iA ct E fie-r-g.; rL...........ato

'v is i,, ii i  ; . Shear Number.. .. ftbs ules i. ..- .ils WW55 -100 -73 5 7 0.03 10 W W7 -75 -59 14 19 9 0.23 15 NW 46 -50 -46 23 31 13 0.33 15 WW48 -25 -32 21 28 14 0.36 25 WW52 10 -12 51 69 37 0.94 20 NVWY59 25 -4 26 35 18 0.46 30 WWNY57 50 10 49 66 37 0.94 25 WW49 75 24 91 123 60 1.52 65 WWV53 100 38 78 106 55 1.40 60 NVV5O 125 52 94 127 68 1.73 75 NVW60 175 79 100 136 71 1.80 70 WW56 200 93 125 170 85 2.16 100 WWV58 225 107 138 187 78 1.98 95 WW54 225 107 130 176 80 2.03 100 WW51 275 135 143 194 86 2.18 100 Testing of Specimens from Capsule X

5-9

.Table 5-4:. Ch'p V iocIDat t' Wtt 'o Uii 1'ai etAfce-oeB Aj ae

........ . ...  ; . -i... - . ..ra..e.oa

-. e...ceo.......

i.... .; . ; .. ...... - ...

. . .  ; ; .

v t iTee pp..tre

+ 0 j.............. Mu.................r::...

.,,......  ;........... rl Enrg ..... .Thm .. ....... Exason:Sea ....... .

WH54 -75 -59 8 11 0 0.00 5 WH51 -50 -46 16 22 4 0.10 10 WH50 0 -18 22 30 10 0.25 25 WH56 25 -4 29 39 18 0.46 30 WH46 50 10 42 57 29 0.74 50 WH47 75 24 59 80 36 0.91 45 WH55 100 38 75 102 54 1.37 90 WH49 125 52 58 79 34 0.86 70 WH52 150 66 58 79 42 1.07 60 WH48 200 93 87 118 66 1.68 95 WH58 200 93 97 132 58 1.47 90 WH53 225 107 96 130 70 1.78 90 WH59 250 121 92 125 65 1.65 100 WH60 275 135 69 94 41 1.04 100 WH57 300 149 79 107 47 1.19 100 Testing of Specimens from Capsule X

5-10

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

. -. . s }i.;.i.....

Rnrg _ ( .T .'

Ch/j ,,, Yeld T.e. . F..

Ma^, . .. ..a Ae Y Flow ia..::i::: :..:

ii:';

'..i  ; : 6f iiii.........:.-i::

::::..Io.......:::-. : -:N::.i

..::B.

;...................;.,.:i'

NB

;:

S.mpl.

• rlb-...-.-.....

Temp. .h.p.... . .....

2 .. ..L.d Lo... 5.. Y....t.

b ..

o

......... ;(

WL55 -75 10 81 51 30 4490 0.16 4695 0.18 4695 0 150 153 WL60 -50 8 64 37 27 3835 0.15 3907 0.16 3907 0 128 129 WLS4 -25 22 177 84 93 4410 0.18 4878 0.24 4770 0 147 155 WLS0 0 25 201 74 127 3993 0.15 4791 0.22 4778 0 133 146 WL47 25 22 177 70 107 3760 0.14 4576 0.21 4528 0 125 139 WLS2 40 29 234 191 43 3817 0.14 4839 0.41 4837 0 127 144

= - - . - - - =- - aSiP ....

WLS7 50 42 338 260 79 3905 0.15 4969 0.52 4912 0 130 148 WL5 1 75 31 250 192 58 3762 0.14 4904 0.41 4901 0 125 144 WLS8 100 63 508 341 166 3671 0.14 4830 0.67 4504 0 122 142 WL53 125 64 516 254 262 3672 0.14 4818 0.52 4466 683 122 141 WL56 160 75 604 281 323 3104 0.17 4737 0.62 4453 1395 103 131 WL59 180 79 637 322 314 3424 0.14 4575 0.67 3815 1441 114 133 WL49 225 107 862 246 616 3246 0.14 4779 0.53 n/a n/a 108 134 WL46 250 101 814 328 486 3472 0.14 4699 0.67 n/a n/a 116 136 WL48 250 11 894 323 571 3336 0.15 4661 0.67 n/a n/a _1 133 Testing of Specimens from Capsule X

5-11

.. . . . . . .. .. i............ W62i6iiiw;w2:........

Table 66In nd IImpact T.it.o...B.U.itlICharpy Results r t1Ie daehell iTet Forging:

oriWas  : ;.: .

-.-n s ru e ie

.... ,. !i;;:'*':..

........ ...Ifi.iii.

r. (rt-ThIn) _ _ _ e ..... .. ........... .1 t .... l ....... lo .r..

e... (...ft.)...lA ;T. 1 1/ E/ .ib. (.e) .. sc)... .. .. )

..... J ki) . .

........ (k l Sampl p..  ;  ;* i .....

.. . .. . , o . t ..

WTr6O 0 4 32 17 15 2098 0.11 2143 0.12 2143 0 70 71 WTr47 50 12 97 52 44 3627 0.15 4173 0.19 4159 0 121 130 WT57 100 13 105 38 66 3406 0.15 3637 0.17 3637 624 113 117 WTrS4 125 28 226 150 75 3274 0.13 4212 0.37 4203 490 109 125 WTr49 125 16 129 51 78 3387 0.14 3905 0.19 3897 579 113 121 WT5r6 150 m 27a 218 -

66= 152 ,-

3222 0.13 4045 a 0.22 3893 1224 107.... 121-.

WfT58 175 30 242 62 180 3155 0.14 3957 0.21 3854 1967 105 118 WT5r9 200 36 290 158 132 3061 0.13 4106 0.40 4082 1707 102 119 WTr46 210 38 306 158 149 3071 0.13 4047 0.40 4009 1665 102 119 WT5RO 225 52 _419 190 229 3138 0.14 4083 0.47 3799 2306 104 120 WT5I1 250 66 532 217 315 3161 0.14 4240 0.51 n/a n/a 105 123 WTrS3 250 64 516 201 315 3104 0.14 4119 0.49 n/a n/a 103 120 WT48 275 73 588 215 373 3181 0.14 4321 0.50 n/a n/a 106 125 WT52 275 63 508 171 336 3101 0.14 4154 0.43 n/a nla 103 121 WTrs5 300 64 516 203 313 2986 0.14 4082 0.50 n/a n/a 99118 Testing of Specimens from Capsule X

5-12

. . . .. . .... .. . . .... , n. . ..... . . .. ............ ........ .......

I  :; :a  ; ;:::t..-.:...:.:..:. nl nn....:M p:  :.: . ...... ..............

... a....N..rm...zed nerg es, T.me.t .....s

....Te..

i a;...

E. .. ...

i:.. .-.......

.e . i. e . .......... ..... . Yed N. (F) (-b) E/ 1I ........l Ib me) (b (b 6me) kl kl WW55 -100 5 40 19 21 2374 0.12 2407 0.13 2399 0 79 80 WW47 -75 14_ 113 48 65 3882 0.17 4049 0.19 4028 492 129 132 WW46 -50 23 185 63 122 3744 0.15 4385 0.21 4283 0 125 135 WW48 -25 21 169 60 109 3298 0.14 4067 0.21 4024 1667 110 123 WW52 10 51 411 321 90 3460 0.14 4499 0.67 4370 220 115 133 WW59 25 26 209 48 161 3488 0.14 3956 0.18 3953 2364 116 124 WW57 S0 49 395 294 100 3405 0.14 4472 0.63 4464 1433 113 131 WWY49 75 91 733 328 406 3383 0.14 4570 0.69 3724 1488 113 132 WW53 100 78 628 314 314 3188 0.14 4422 0.68 4050 1381 106 127 WWS0 125 94 757 308 449 3243 0.15 4309 0.69 3316 1155 108 126 WW60 175 100 806 313 493 3261 0.15 4356 0.69 2300 753 109 127 WW56 200 125 1007 296 711 3032 0.14 4235 0.68 n/a n/a 101 121 WW58 225 138 1112 313 799 3265 0.14 4425 0.68 2643 1829 109 128 WW54 225 130 1047 301 747 3028 0.14 4188 0.69 n/a R/a 101 120 WWS1I 275 143 1152 300 853 3098 0.14 4272 0.67 n/a n/a 103 123 Testing of Specimens from Capsule X

5-13 I",.;

...... o Pe ....... of L71

... x tO ...... c.. ., ... ..  :.................. ..

Tr s.......

.........fl 9& a e 0%A'V. u......n .....

e,o 1., ,i Time t. .. M .r...A a.

.................. re t Yil f

..i.o A-......

i.-N e p.r . r. do .... . ..... d d...e

.... .... t.

...... . . ...re WI-54 -75 8 64 39 25 3922 0.14 4181 0.16 4181 0 131 135 W1151 -50 16 129 74 55 4162 0.15 4969 0.21 4969 0 139 152 WH50 0 22 177 66 112 3957 0.15 4653 0.20 4650 1484 132 143 WHS6 25 29 234 67 166 3850 0.14 4588 0.21 4558 892 128 140 W1146 50 42 338 69 269 3781 0.14 4630 0.21 4388 965 126 140 WH47 75 59 475 196 279 3720 0.14 4707 0.42 4586 1922 124 140

- - a.............- = .. -. .........

W1155 100 75 604 223 381 3599 0.14 4507 0.49 660 251 120 135 WH49 125 58 467 218 250 3525 0.14 4592 0.47 4481 2645 117 135 WHS2 150 58 467 162 305 3318 0.13 4270 0.38 3851 317 110 l 126 WH4S 200 87 701 234 467 3462 0.14 4389 0.52 3838 3051 115 131 WVHS8 200 97 782 318 464 3320 0.14 4473 0.67 3141 2639 111 130 WH53 225 96 774 237 537 3462 0.14 4564 0.52 3922 2376 115 134 WH59 250 92 741 218 523 3345 0.14 4448 0.49 n/a n/a 111 130 W1160 275 69 556 200 356 3274 0.14 4299 0.47 n/a n/a 109 126 WHS7 300 79 637 284 352 3119 0.16 4417 0.64 n/a /da 104 125 Testing of Specimens from Capsule X

5-14 Taln99EetoIaito .::i-

.;i t . ::: B 1x.0i~m%10.e  ;:: : -  :'i'"'i

.... :o: te.

i::. apsul ....

'' 6 b -Toug Noch ... nes .Poprt...f.he..f.B...

......  ; V; , ,, ,,i > .  : :l ... ...... .....

l eeor: esse l 6 -e:ate~It i ::I lla~ ....... .. ...... ...... :......

. . .. . i ii ... . ............. ...... ... ..j . . ... '; ........

' *.:.j,.............B.....':'..i'....'l "B-

.-ji:.'

0 tEi)': ....... era'35mlHTherarage ... ~:

'-i.-..: : .......... ..... i:::

i.'-- '::::::.:i

':: '  :,:: ; j .;.

neirgy- Mhorpiit~n,::

ateria. .M *. TransitionTemperatF ¢; IExpanson cmper t r Trnsition emperatuf(.). .)

T...... r , ... ...... . .... ... . ........ ... ..

a......... e .. ..... ra r .... ...... .

Intermediate Shell -57.1 37.6 94.7 -9.4 106.6 116.0 --15.4 87.2 102.6 132 106 -26 Forging 05 (f ang,) _____

Intermediate Shell 45.2 161.1 115.9 84.6 201.6 117.0 114.2 218.3 104.1 62 66 +4 Forging 05 (AxiaDl Weld Metal -31.2 -5.4 25.8 -9.9 35.9 45.8 -5.9 37.9 43.8 131 134 +3 (Heat # 895075)

HAZ Metal -56.2 18.6 74.8 -0.6 72.6 73.2 -8.6 62.5 71.1 89 80 .9

a. "Average" is defined as the value read from the curve fit through the data points of the Charpy tests (see Figures 5-1, 5-4,5-7 and 5-10).

b. "Average" is defined as the value read from the curve fit through the data points ofthe Charpy tests (see Figures 5-2,5-5,5-8 and 5-11).

Testing of Specimens from Capsule X

5-15 Table 540 Comparison of the Wtts'BarU AfUfit nable l Surveilance Materal 30 ft-lb Transition

...... Temperature Shifts and Upper Shelf Enery Decreases ith Regulatory Guide I,,.. ..... :. R e v ionn 22... ~red  ; et oni... i i gi%................ . ....... ... a%.............. A.., ..... ... .........

. ... . . . . . . .. *:'.,:.:: .,; ...inv i: iP. i:: i:: ;:: ;::i:

• ~.  ;. ...........

. . . ......... , %t.... ..... ...=.. ~30:

i,..., ft-lb...Trantido

.s.- . .... ;i n i: i ....

Uppr.ShelfEner

....... , ... ........ .: .. Temperturc Shift  ;.i% Decreasc.e -

I. {  :.......... .%. . .. o. . ... v;l:ll:  :.; ; .... I::

...... .. .... ,..*... /

...... .......... MeAlasured .> .1i ec -i. ............

.............. ....... -. .1~ k.."..-,,

) ,

..-..... i....... .

.. . . .. . . , .. ...-. ,..... ..Preicted.

.;.(,.......... s

,.,. ).. ..... . .

Intermediate Shell U 0.447 95.4 98.3 21 19 Forging 05 W 1.08 125.5 111.4 26 26 (Tangential) X 1.71 141.5 94.7 29 20 Intermediate Shell U 0.447 95.4 28.7 21 0 Forging 05 W 1.08 125.5 79.0 26 3 (Axial) X 1.71 141.5 115.9 29 0 Surveillance U 0.447 31.8 0.0) 16 0 Program W 1.08 41.8 30.5 19 15 Weld Metal X 1.71 47.2 25.8 22 0 Heat Affected U 0.447 --- 50.9 --- 11 Zone Material W 1.08 48.8 13 X 1.71 74.8 10 Notes:

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

(b) Calculated using measured Charpy data plotted using CVGRAPHJ, Version 4.1 (See Appendix C)

(c) Values are based on the definition of upper shelf energy given in ASTM El 85-82.

(d) The fluence values presented here are the "calculated" values.

(e) Due to the scatter in the Capsule U Weld Charpy test results, a true Hyperbolic Tangent Curve fit resulted in AT3 0 values of-6.4°F when compared to unirradiated Charpy test data. Physically this should not happen.

Hence, based on engineering judgement a value of 0°F will be used in RTNr calculations.

Testing of Specimens from Capsule X

5-16 apijl. XWktot:V

-S" lftfti.INI

.................- .. .............th............ -Da r,.. -n .I.. ... ....  : . .. ........... ......... .. ........................................ ....... . ............. ...............

....... ....-. .;.. Z....... ..... . ....- ... ...... ..... .. . .. .... ;;;;;.

Ct-i.- i  ; --

t -- - * . . .  ;

6 fie . ......me ....

t>..... F

..... g. 3 to i . . .; ... . . ..... .. .. . .. . . .. .. . ...

lntermnediatc Shell WL-10 75 86.6 106.3 3.61 200.0 73.5 10.5 23.3 63 Forging 05 WL-l l 300 78.9 98.7 3.30 150.7 67.2 9.0 20.3 55 (agrfa)WL- 12 550 76.5 100.2 3.45 185.4 70.2 10.5 21.8 62 Intermediate Shell WT-l10 75 86.8 106.5 4.12 187.9 83.8 11.3 21.8 55 Forging 05 (Axial) WT-11 300 77.6 99.0 3.90 156.7 79.5 9.8 17.9 49 WT-12 550 78.2 100.0 4.11 157.3 83.7 9.0 16.4 47 Weld Metal WW-10 75 77.8 89.8 2.55 199.3 51.8 13.5 30.8 74 sWW- 30 70.8 81.7 2.37 173.1 48.2 11.3 26.3 72

__ WW-12 550 68.6 84.0 2.57 175.8 52.3 10.5__23.4 70 Testing of Specimens from Capsule X

5-17 INTERMEDIATE SHELL 05 (TANGENTIAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/06/2004 11:20 AM Data Set(s) Plotted Curve Plant Capsule Material Orl. Heat #

I Watts Bar I UNIRR SA50BCL2 LT 527536 2 Watts Bar I U SA508CL2 LT 527536 3 Watts Bar I w SA508CL2 LT 527536 4 Watls Bar 1 x SA508CL2 LT 527536 300

-I 250 I I I I _ _ _ _

4- 200 0

0 0I

150

_II IU 0 z

e 100 i0 I0 50

- I - - I -

0

-300 -200 -100 0 100 200 300 400 500 600 Temperature In Deg F 0 Set 1 a Set2 0 Set3 A Set4 Results Curve Fluence LSE USE d.USE T @30 d-T @30 T @50 d.T @50 1 0.0 2. 2 132.0 .0 -57. 1 .0 -15.4 .0 2 0.0 2.2 J07. 0 -25.0 41.2 98.3 86.4 1 1.8 3 2.2 98.0 -34.0 54.3 111.4 95.0 110.4 4 2.2 106.0 .26.0 37. 6 94.7 87.2 102. 6 Figure 5-1 Charpy VnNetec Impact Energy vs. Temperature forWiT)Bar Unit I Reactor Vessel Intermediate Shell Forging 05 (Tangential Orientation)

Testing of Specimens from Capsule X

5-18 INTERMEDIATE SHELL 05 (TANGENTIAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/0612004 02:09 PM Data Set(s) Plolled Curve Plant Capsule Material Ori. Ileat #

Watts Bar I UNIRR SA50SCL2 LT 527536 2 Watts Bar I U SA508CL2 LT 527536 3 Watts Bar I w SA508CL2 LT 527536 4 Watts Bar I x SA508CL2 LT 527536 200 150 E

a 100

.9 50 0 I-

-300 0 300 600 Temperature in Deg F 0 SetI a Set 2 0 Set 3 A Set 4 Results Curve Fluence LSE USE d-USE T '35 d-T @35

0. 0 .0 80.5 .0 -9.4 .0 2 0.0 .0 76.9 -3.6 91.0 100.4 3 .0 82.6 2.1 84. 3 93.7 4 .0 83.1 2.6 106. 6 116.0

.2 Figure 5-2 UhArY-V@NDo;ffL;ateral kipansion vs. lemperature for Watts ar Unk{lCtor Vessel Intermediate Shell Forging 05 (Tangential Orientation)

Testing of Specimens from Capsule X

5-19

.INTERMEDIATE SHELL 05 (TANGENTIAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/06/2004 02:01 PM Data Set(s) PlOtted Curve Plant Capsule Material Or. Ileat #

I Watts Bar I UNIRR SA508CL2 LT 527536 2 Watts Bar 1 U SA508CL2 LT 527536 3 Watts Bar 1 W SA508CL2 LT 527536 4 Watts Bar I x SA508CL2 LT 527536 125 100 L-

'U 75 U) ci 0.

50 2:11

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F 0 Set 1 Set2 o Set3 a Set 4 Results Curve Fluence LSE USE d-USE T 050 d.T @50 1 0.0 .0 [00.0 .0 34.8 .0 2 0.0 .0 100.0 .0 126.6 91.8 3 .0 100.0 .0 102.3 67.5 4 .0 100.0 .0 116. 6 81.8 figure 5-s Charpy V-NNOllIe rercent lnear vs. Iemperature fr waits Liar I.1DU Mieaunor vessel Intermediate Shell Forging 05 (Tangential Orientation)

Testing of Specimens from Capsule X

5-20 INTERMEDIATE SHELL 05 (AXIAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 0210912004 09:59 AM Data Set(s) Plotted Curve Plant Capsule Material Ori. Ileat #

1 Watts Bar I UNIRR SA508CL2 1L 527536 2 Watts Bar I U SA508CL2 TL 527536 3 Watts Bar I W SA5OSCL2 TL 527536 4 Watts Bar I X SA508CL2 TL 527536 300 250

,2 200 46..a 0

0 LL 150 0

C j1 00 50 0 =-

-300 -200 -100 0 100 200 300 400 500 600 Temperature In Deg F 0 Set1 o Set2 0 Set3 c Set4 Resulk Curve Fluence LSE USE d-USE T @30 d-T 30 T @50 d-T? 50 0.0 2.2 62. 0 .0 45.2 .0 114.2 .0 2 0.0 2.2 72. 0 10.0 73. 9 28.7 148. 7 34.5 3 2.2 60. 0 -2.0 124.2 79. 0 206.2 92. 0 4 2.2 66. 0 4.0 161.1 115.9 218. 3 104.1 Intermediate Shell Forging 05 (Axial Orientation)

Testing of Specimens from Capsule X

5-21 INTERMEDIATE SHELL 05 (AXIAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/0912004 10:45 AM Data Set(s) Plotted Curve Plant Capsule Material Ori. Ileat #

Watts Bar I UNIRR SA508CL2 TL 527536 2 Watts Bar I U SA508CL2 TL 527536 3 Watts Bar I W SA508CL2 TL 527536 4 Watts Bar I X SA508CI-2 TL 527536 200 150

.M E

C

.2 io 50 o 4--

-300 0 300 600 Temperature In Deg F o Setl D Set 2 0 Set 3 A Set 4 Results Curve Fluence LSE USE d-USE T @35 d-T t35

.0 58.3 .0 84.6 .0 2 .0 57.3 -1.0 113.4 28. 8 3 .0 61.8 3.5 138. 1 53.5 4 .0 68.1 9.8 201.6 117.0 Figure 5- VCharpy V-Notec ateShl Expansion vs. Temperatureior)

Vessel Intermediate Shell Forging 05 (Axial Orientation)

Testing of Specimens from Capsule X

5-22 INTERMEDIATE SHELL 05 CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/0912004 10:29 AM Data Set(s) Plotted Curve Plant Capsule Material Or;. Heat #

I Watts Bar I UNIRR SA508CL2 TL 527536 2 Watts Bar ] U SA508CL2 TL 527536 3 Watts Bar I W SA508CL2 TL 527536 4 Watts Bar I X SA508CL'2 TL 527536 125 100 L-75 0

I-C, 50 25:

-300 -200 -100 0 100 200 300 400 500 600 Temperature In Deg F 0 Set 1 I Set 2 o Set 3 4 Set4 Results Curve Fluence LSE USE d.USE T E5O d-T @50 1 .0 100.0 .0 54.9 .0 2 .0 100.0 .0 144.3 89.4 3 .0 100.0 .0 149. 1 94. 2 4 .0 100.0 .0 187.3 132.4 Figure 5-6 Charpy V-Notch Percent Shear vs. Operaature fornWatts BarUnit IReactor Vessel Intermediate Shell Forging 05 (Axial Orientation)

Testing of Specimens from Capsule X

5-23 SURVIELLANCE PROGRAM WELD CVGRAPH 5.02 Hyperbolic Tangent Curve Pnnted on 02/09/2004 01:41 PM Data Set(s) Plotted Curve Plant Capsule Material Ori. Hleat f I Watts Bar I UNIRR N/A NA 895075 FLUX Watts Bar I U NIA NA 895075 3 Watts Bar I W NA 895075 4 Watts Bar I X NIA NA 895075 300 -

250 -_

, 200-0 0

U-p 150'-

0 5D-

-300 -200 -100 0 100 200 300 400 500 600 Temperature In Deg F o Set1 n Set 2 o Set 3 b Set 4 Results Curve Fluence LSE USE d-VSE T 030 d-T @30 T 050 d-T CSO 1 2.2 131.0 .0 -31.2 .0 -S.9 .0 2 2. 2 143.0 12.0 -37. 6 -6.4 6. 3 12. 2 3 2. 2 112.0 -19.0 -. 7 30.5 39.4 45.3 4 2.2 134. 0 3.0 -5.4 25. 8 37.9 43. 8 Figure 5-7 £1i~i Mt VW-Notch mpactEnergayvsl.TemperatureforWatts BarUnit-IReactorVesse7V Weld Metal Testing of Specimens from Capsule X

5-24 SURVIELLANCE PROGRAM WELD CVGRAP}H 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 02:11 PM Data Set(s) Plotted Curve Plant Capsule Material On. Heat #

Watts Bar 1 UNIRR N/A NA 895075 FLUX 2 Watts Bar 1 U N/A NA 895075 3 Watts Bar I W NIA NA 895075 4 Watts Bar 1 X N/A NA 895075 200 150 E

.2 2

. 100 lb

-0 50 0 4-

-300 0 300 600 Temperature In Deg F 0 Set1 a Set 2 o Set 3 & Set 4 Results Curve Fluence LSE USE d-USE T @35 d-T @35

.0 87.8 .0 -9.9 .0 2 .0 76.9 10.9 7. 4 17.3 3 .0 89.2 1.4 21.9 31.8 4 .0 85.0 -2.8 35.9 45. 8 Figure UharpyV-Notc i LateralExpansionxsep ro r Vessel Weld Metal Testing of Specimens from Capsule X

5-25 SURVIELLANCE PROGRAM WVELD CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 02:00 PMI Data Set(s) Plotted Curve Plant Capsule Material OrL. Ient #

I Watts Bar I UNIRR N/A NA 895075 FLUX 2 Watts Bar I U NIA NA 895075 3 Watts Bar 1 W NIA NA 895075 4 Watts Bar I x N/A NA 895075 125 100 S-75 0.

50 25 _

0- _

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F 0 Set 1 I Set 2 o Set 3 & Set 4 Results Curve Fluence LSE USE d.USE T @50 d.T @50

.0 100.0 .0 .1.2 .0 2 .0 100.0 .0 9. 6 ID. S 3 .0 100.0 .0 19.9 21. 1 4 .0 100. 0 .o0 70.9 72.1 Figure 5-9 Charpy V-Notch Percent Shear vs. Temperature forfWatts Bar Unit 1 Reactor Vessel Weld Metal Testing of Specimens from Capsule X

5-26 HEAT AFFECTED ZONE CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02109/2004 03:26 PM Data Set(s) Plotted Curve Plant Capsulc Mnterial On. Jleat #

1 Watts Bar I UNIRR SA508CL2 NA 527536 2 Watts Bar I U SA508CL2 NA 527536 3 Watts Bar I W SA508CL2 NA 527536 4 Watts Bar I x SA508CL2 NA 527536 300 --

250 -

-2 200 -

0 Za 150 -

z -

> 100 -I 50 --

0-

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F 0 Set I a Set 2 0 Set 3 A Set4 Results Curve fluence ISE USE d.USE T @30 d-T @30 T @50 d.T @50

2. 2 89.0 .0 -56.2 .0 -8. 6 .0 2 2.2 79. 0 -10.0 -5.3 50.9 43. 7 52.3 3 2.2 77.0 -12.0 -7.4 48. 8 53. 6 62.2 4 2.2 80. 0 -9.0 18.6 74. 8 62. 5 71. 1 Figure 5-10 Charpy V-Notch Impact Energy v_-lennperature for Watts Barnit.U-ceoaV eSSel Heat-Affected-Zone Material Testing of Specimens from Capsule X

5-27 HEAT AFFECTED ZONE CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 03:41 PM Data Set(s) Plotted Curve Plant Capsule Material Ori Heat #

1 Watts Bar I UNIRR SA508CL2 NA 527536 2 Watts Bar I U SA508CL2 NA 527536 3 Watts Bar ] w SA508CL2 NA 527536 4 Watts Bar]I x SA508CL2 NA 527536 200 150 E

.2 C

in E 100 4-5E 50 0 _-

-300 0 300 600 Temperature in Deg F 0 SetI D Set 2 0 Set 3 A Set 4 Results Curve Fluence ISE USE d.USE T @35 d.T @35 1 .0 66. 3 .0 -. 6 .0 2 .0 54.4 *11.9 51.2 51. g 3 .0 63.6 .2.7 48.0 48. 6 4 .0 56. 3 -10.0 72.6 73. 2 Figure 5-11 _Charpy V-tcWL-iteraI Lipanion vs. lemperature for Watts bar Unit I Keactor Vessel Heat-Affected-Zone Material Testing of Specimens from Capsule X

5-28 HEAT AFFECTED ZONE CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02t0912004 03:34 PM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat #

Watts Bar I UNIRR SA508CL2 NA 527536 2 Watts Bar I U SA508CL2 NA 527536 3 Watts Bar I W SA508CL2 NA 527536 4 Watts Bar I x SAS08CL2 NA 527536 125 100 I..

'I 75 ci U,

0 2!

ci 50 9L 25 1-0 ~

-300 -20D -100 0 100 200 300 400 500 600 Temperature In Deg F o SetI a Set 2 0 Set 3 & Set4 Results Curve Muence LSE USE d-USE T t50 d-T ESO

.0 100.0 .0 -22.2 .0 2 .0 100.0 .0 88. 1 110.3 3 .0 100.0 .0 39. 6 61.8 4 .0 100.0 .0 64.7 86. 9 Figure 5-12 Charpy V-Notch Percent Shear vs. Temperature forWatts BarUnit i Reactor Vessel Heat-Affected-Zone Material Testing of Specimens from Capsule X

5-29 WT55 -75 0 F WTA54. -. 5pF WL.5 (lOF WL57- 50 0F WL51. 75OF WL58, 100 0F WL53.125 0F WL56,160 0F WL59, 180-F WL49,225 0F WL46,250 0F WL48,250 0F Figure 5-13 Charpy Impact Specimen Fracture Surfaces for Watts Bar Unit 1 Reactor Vessel Intermediate Shell Forging (Tangential Orientation)

Testing of Specimens from Capsule X

5-30 WT56. 150 0F WI59. 20UUF WT51, 250 0F WT53, 2507F WT48, 275 0F WT52,275 0F WT55, 300 0F Figure 5-14 Charpy Impact Specimen Fracture Surfaces for Watts Bar Unit 1 Reactor Vessel Intermediate Shell Forging 05 (Axial Orientation)

Testing of Specimens from Capsule X

5-31

--narc --no -11 FAt Io -n --llrsf IrOT' r

-nnr-m nor^

WW57S50F WW60, 175 0 F WW56,2000 F WW58,225 0 F WW54,225 0 F WW51,275 0 F Figure 5-15 Charpy Impact Specimen Fracture Surfaces for Watts Bar Unit 1 Reactor Vessel Weld Metal Testing of Specimens from Capsule X

5-32 0

VW1;4 -75Fp WH5 1 -f lF XV-144A ;fop

• ?~  ;

WVH58, 200 0F WH53, 225 0F WH59,250 0 F WH57, 300 0F Figure 5-16 Charpy Impact Specimen Fracture Surfaces for Watts Bar Unit 1 Reactor Vessel Heat-Affected-Zone Metal Testing of Specimens from Capsule X

5-33 120 - ULTIMATE YIELD STRENGTH 100-

-,80-X 60 - 0.2% YIELD STRENGTH t40 20 -

0 100 200 300 400 500 600 TEMPERATURE( F)

Legend:  ? and ? are Unirradiated

? and ? are Irradiated to 1.71 x IO9 nr/cm 2 (E> 1.0 MeV) 80 REDUCTION INAREA 70 A 60 50 I--

40 0 30 TOTAL ELONGATION 20 p 3 10

. UNIFORM UNIFORM 0 i I I 0 100 200 300 400 500 600 TEMPERATURE ( F)

Figure 5-17 Tensile Properties for Watts Bar Unit 1 Reactor Vessel Intermediate Shell Forging 05 (Tangential Orientation)

Testing of Specimens from Capsule X

5-34 120 - ULTIMATE YIELD STRENGTH 100 &

,-, 80-Un]60 - 0.2% YIELD STRENGTH 20 -

0 . , I I I 0 100 200 300 400 500 600 TEMPERATURE( F)

Legend:  ? and 7 are Unirradiated 7 and? are Irradiated to 1.71 x l0~ln/cm2 (E> 1.0 MeV) 70 -

REDUCTION INAREA 60 - b

- 50- IL

` 40-

-j 30 a, 20 -TOTAL ELONGATION 0 20 -__

10, -

UNIFORM UNIFORM 0 100 200 300 400 500 600 TEMPERATURE (F)

Figure 5-18 Tensile Properties for Watts Bar Unit 1 Reactor Vessel Intermediate Shell Forging 05 (Axial Orientation)

Testing of Specimens from Capsule X

5-35 100 -

ULTIMATE YIELD STRENGTH 80 -

60 -

Cn 0.2% YIELD STRENGTH w

40-20 -

0 - _

_- . . . l 0 100 200 300 400 500 600 TEMPERATURE( F)

Legend:  ? and ? are Unirradiated

? and ? are Irradiated to 1.71 x 10'9 ncm

/ 2 (E> 1.0 MeV) 80 70 -I 60 - REDUCTION INAREA 60-

,- 50-F-

Q 40 - TOTAL ELONGATION C)30-120 -

10 UNIFORM UNIFORM 0 i I II 0 100 200 300 400 500 600 TEMPERATURE ( F)

Figure 5-19 Tensile Properties for Watts Bar Unit 1 Reactor Vessel WVeld Metal Testing of Specimens from Capsule X

5-36 Specimen WL-1 0 Tested at 750 F Specimen NVL- 11 Tested at 3000 F Specimen WL-12 Tested at 550'F Figure 5-20 Fractured Tensile Specimens from Watts Bar Unit 1 Reactor Vessel Intermediate Shell Forging 05 (Tangential Orientation)

Testing of Specimens from Capsule X

5-37 Specimen WT-10 Tested at 75 0 F Specimen WT-.I Tested at 3000 F Specimen WT-12 Tested at 5500 F Figure 5-21 Fractured Tensile Specimens from Watts Bar Unit 1 Reactor Vessel Intermediate Shell Forging 05 (Axial Orientation)

Testing of Specimens from Capsule X

5-38 Specimen WW- 10 Tested at 75 0 F Specimen WW-11 Tested at 3000 F Specimen WW-12 Tested at 5500 F Figure 5-22 Fractured Tensile Specimens from Watts Bar Unit 1 Reactor Vessel Weld Metal Testing of Specimens from Capsule X

5-39 WATTS BAR UNIT I 'X' CAP 120 100 anO o

e) 40 WL-10 75 F 20 0

0 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN, INAN WATTS BAR UNIT 1 *X. CAP 120 100 so V5 co 6 a 40 WL-1 1 300 F 20 0.05 0.1 0.15 02 0.25 0.3 STRAIN, INRMN Figure 5-23 Engineering Stress-Strain Curves for Watts Bar Unit 1 Intermediate Shell Forging 05 Tensile Specimens WLV10, NVL11 and NL-12 (Tangential Orientation)

Testing of Specimens from Capsule X

5-40 WATTS BAR UNIT I v CAP 120 100 80 40 C';

CO60 40 WL-12 550 F 20 0

0 0.05 0.1 0.15 0.2 025 0.3 STRAIN. INIIN Figure 5 Continued Testing of Specimens from Capsule X

5-41 WATTS BAR UNIT I X CAP 120

_ 80 t 60 so 0

40 WT-10 75 F 20 0

0.05 0.1 0.15 02 0.25 0.3 STRAIN. INnN WATTS BAR UNIT I X' CAP 120 100 sf 40 WT.11 300 F 20 0

0 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN, INnN Figure 5-24 Engineering Stress-Strain Curves for WVatts Bar Unit 1 Intermediate Shell Forging 05 Tensile Specimens NIT-10, NVT-11 and VIT-12 (Axial Orientation)

Testing of Specimens from Capsule X

5-42 WATTS BAR UNIT I X CAP 120 100 0o CO

° 60 40 WT-12 550 F 20 0

0 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN, IN/IN Figure 5 Continued Testing of Specimens from CapsuleX

5-43 WATTS BAR UNIT 1 WXCAP 100 -

go 80 60 U) so-V) 40 30-WW-10 75F 20-10 0

C 0.05 0.1 0.15 0.2 0.25 0.3 0.35 STRAIN, INAN WATTS BAR UNIT I X" CAP 100' 90 80' 70

~2 60 g35o Lia) 50 C 40 WW-11 30' 300 F 20' 10 0

0 0.05 0.1 0.15 0.2 025 0.3 STRAIN, IN/IN Figure 5-25 Engineering Stress-Strain Curves for Weld Metal Tensile Specimens WW.V-10, W4V-11 and WVWN-12 Testing of Specimens from Capsule X

5-44 100 .WATTS BAR UNIT 1 90 -X CAP 80 70 600

° 50 It-e 40 WW-12 30 550 F 20 10 0

0 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN, INIIN Figure 5 Continued Testing of Specimens from Capsule X

6-1 6 RADIATIONANALYSISAND NEUTRON DOSIMETRY

6.1 INTRODUCTION

This section describes a discrete ordinates S, transport analysis performed for the Watts Bar Unit 1 reactor to determine the neutron radiation environment within the reactor pressure vessel and surveillance capsules. In this analysis, fast neutron exposure parameters in terms of fast neutron fluence (E > 1.0 MeV) and iron atom displacements (dpa) were established on a plant and fuel cycle specific basis. An evaluation of the most recent dosimetty sensor set from Capsule X, withdrawn at the end of the fifth plant operating cycle, is provided. In addition, to provide an up-to-date data base applicable to the Watts Bar Unit 1 reactor, sensor sets from previously withdrawn capsules (U, and W) were re-analyzed using the current dosimetry evaluation methodology. These dosimetry updates are presented in Appendix A of this report. Comparisons of the results from these dosimetry evaluations with the analytical predictions served to validate the plant specific neutron transport calculations. These validated calculations subsequently formed the basis for providing projections of the neutron exposure of the reactor pressure vessel for operating periods extending to 60 Effective Full Power Years (EFPY).

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

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

All of the calculations and dosimetry evaluations described in this section and in Appendix A were based on the latest available nuclear cross-section data derived from ENDF/B-VI and made use of the latest available calculational tools. Furthermore, the neutron transport and dosimetry evaluation methodologies follow the guidance and meet the requirements of Regulatory Guide 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence,"119 ].Additionally, the methods used to develop the calculated pressure vessel fluence are consistent with the NRC approved methodology described in WCAP-14040-NP-A, "Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves," January 19961201. The specific calculational methods applied are also consistent with those described in WCAP-15557, "Qualification of the Westinghouse Pressure Vessel Neutron Fluence Evaluation Methodology." 1201 Radiation Analysis and Neutron Dosimetry

6-2 6.2 DISCRETE ORDINATE S ANALYSIS Aplan view of the Watts Bar Unit 1 reactor geometry at the core ridplane is shown in Figure 4-1. Six irradiation capsules attached to the neutron pad are included in the reactor design that constitutes the reactor vessel surveillance program. The capsules are located at azimuthal angles of 560 and 2360 (dual capsule holder - 340 from the core cardinal axes), 58.50 and 238.50 (dual capsule holder - 31.5° from the core cardinal axes) and 1240 and 3040 (single capsule holder - 34° from the core cardinal axes). The stainless steel specimen containers are 1.182-inch by 1-inch and are approximately 56 inches in height.

The containers are positioned axially such that the test specimens are centered on the core midplane, thus spanning the central 5 feet of the 12-foot high reactor core.

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

The presence of these materials has a marked effect on both the spatial distribution of neutron flux and the neutron energy spectrum in the water annulus between the neutron pads and the reactor vessel. In order to determine the neutron environment at the test specimen location, the capsules themselves must be included in the analytical model.

In performing the fast neutron exposure evaluations for the Watts Bar Unit 1 reactor vessel and surveillance capsules, a series of fuel cycle specific forward transport calculations were carried out using the following three-dimensional flux synthesis technique:

i(r, 0, z) = fS(r,0)

• q5(r, z) where O(r,O,z) is the synthesized three-dimensional neutron flux distribution, O(r,O) is the transport solution in rO geometry, O(r,z) is the two-dimensional solution for a cylindrical reactor model using the actual axial core power distribution, and ¢(r) is the one-dimensional solution for a cylindrical reactor model using the same source per unit height as that used in the r.O two-dimensional calculation. This synthesis procedure was carried out for each operating cycle at Watts Bar Unit 1.

For the Watts Bar Unit 1 transport calculations, three octant symmetric r,O models were developed and are depicted in Figure 6-1. The first model contained the shortened neutron pad (15° span) with no surveillance capsules. The second model contained the medium neutron pad (I 7.5° span) including the single holder surveillance capsules. The third model contained the extended neutron pad (200 span) including the dual holder surveillance capsules. The first model was used to generate the maximum fluence at the pressure vessel wall. The two other models were to perform surveillance capsule dosimetry evaluations and subsequent comparisons with calculated results. In developing these analytical models, nominal design dimensions were employed for the various structural components. Likewise, water temperatures, and hence, coolant densities in the reactor core and downcomer regions of the reactor were taken to be representative of full power operating conditions. The coolant densities were treated on a fuel cycle specific basis. The reactor core itself was treated as a homogeneous mixture of fuel, cladding, water, and miscellaneous core structures such as fuel assembly grids, guide tubes, etc. The geometric mesh description of the rO reactor models consisted of 170 radial by 98 azimuthal intervals. Mesh sizes were chosen to assure that proper convergence of the inner iterations was achieved on a pointwise basis. The pointwise inner iteration flux convergence criterion utilized in the rO calculations was set at a value of 0.001.

Radiation Analysis and Neutron Dosimetry

6-3 The r,z model used for the Watts Bar Unit 1 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 1-foot above the active fuel. As in the case of the rO models, nominal design dimensions and full power coolant densities were employed in the calculations. In this case, the homogenous core region was treated as an equivalent cylinder with a volume equal to that of the active core zone. The stainless steel former plates located between the core baffle and core barrel regions were also explicitly included in the model. The rz geometric mesh description of these reactor models consisted of 153 radial by 90 axial intervals. As in the case of the rO calculations, mesh sizes were chosen to assure that proper convergence of the inner iterations was achieved on a pointwise basis. The pointwise inner iteration flux convergence criterion utilized in the r,z calculations was also set at a value of 0.001.

The one-dimensional radial models used in the synthesis procedure consisted of the same 153 radial mesh intervals included in the rz models. Thus, radial synthesis factors could be determined on a meshwise basis throughout the entire geometry.

The core power distributions used in the plant specific transport analysis were taken from the appropriate Watts Bar Unit I fuel cycle design reports. The data extracted from the design reports represented cycle dependent fuel assembly enrichments, burnups, and axial power distributions. This information was used to develop spatial and energy dependent core source distributions averaged over each individual fuel cycle.

Therefore, the results from the neutron transport calculations provided data in terms of fuel cycle averaged neutron flux, which when multiplied by the appropriate fuel cycle length, generated the incremental fast neutron exposure for each fuel cycle. In constructing these core source distributions, the energy distribution of the source was based on an appropriate fission split for uranium and plutonium isotopes based on the initial enrichment and burnup history of individual fuel assemblies. From these assembly dependent fission splits, composite values of energy release per fission, neutron yield per fission, and fission spectrum were determined.

All of the transport calculations supporting this analysis were carried out using the DORT discrete ordinates code Version 3. 11221 and the BUGLE-96 cross-section library. 1231 The BUGLE-96 library provides a 67 group coupled neutron-gamma ray cross-section data set produced specifically for light water reactor (LWVR) 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 cycle specific basis.

Selected results from the neutron transport analyses are provided in Tables 6-1 through 6-6. 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 (31.50 and 340). These results, representative of the axial midplane of the active core, establish the calculated exposure of the surveillance capsules withdrawn to date as well as projected into the future. Similar information is provided in Tables 6-2 for the reactor vessel inner radius.

The vessel data given in Table 6-2 are representative of the axial location of the maximum neutron exposure at each of the four azimuthal locations. It is also important to note that the data for the vessel inner radius were taken at the clad/base metal interface, and thus, represent the maximum calculated exposure levels of the vessel plates and welds.

Radiation Analysis and Neutron Dosimetry

6-4 Both calculated fluence (E > 1.0 MeV) and dpa data are provided in Table 6-1 through Table 6-3. These data tabulations include both plant and fuel cycle specific calculated neutron exposures at the end of the fifth operating fuel cycle as well as projections for the current operating fuel cycle, i.e., Cycle 6, and future projections to 15, 25, 32, 36, 40, 48, 54 and 60 EFPY The projections were based on the assumption that the core power distributions and associated plant operating characteristics from Cycle 6 were representative of future plant operation. The fuiture projections are also based on the current reactor power level of 3459 MWt.

Radial gradient information applicable to fast (E > 1.0 MeV) neutron fluence and dpa are given in Tables 6-3 and 6-4, respectively. The data, based on the cumulative integrated exposures from Cycles 1 through 6, are presented on a relative basis for each exposure parameter at several azimuthal locations.

Exposure distributions through the vessel wall may be obtained by multiplying the calculated exposure at the vessel inner radius by the gradient data listed in Tables 6-3 and 6-4.

The calculated fast neutron exposures for the three surveillance capsules withdrawn from the Watts Bar Unit I reactor are provided in Table 6-5. These assigned neutron exposure levels are based on the plant and fuel cycle specific neutron transport calculations performed for the Watts Bar Unit 1 reactor.

Updated lead factors for the Watts Bar Unit 1 surveillance capsules are provided in Table 6-6. The capsule lead factor is defined as the ratio of the calculated fluence (E > 1.0 MeV) at the geometric center of the surveillance capsule to the corresponding maximum calculated fluence at the pressure vessel clad/base metal interface. In Table 6-6, the lead factors for capsules that have been withdrawn from the reactor (U, W, and X) were based on the calculated fluence values for the irradiation period corresponding to the time of withdrawal for the individual capsules. For the capsule remaining in the reactor (Y.V, and Z), the lead factor corresponds to the calculated fluence values at the end of Cycle 6, the current operating fuel cycle for Watts Bar Unit 1.

Radiation Analysis and Neutron Dosimetry

6-5 6.3 NEUTRON DOSIMETRY The validity of the calculated neutron exposures previously reported in Section 6.2 is demonstrated by a direct comparison against the measured sensor reaction rates and via a least squares evaluation performed for each of the capsule dosimetry sets. However, since the neutron dosimetry measurement data merely serves to validate the calculated results, only the direct comparison of measured-to-calculated results for the most recent surveillance capsule removed from service is provided in this section of the report. For completeness, the assessment of all measured dosimetry removed to date, based on direct, best estimate, and least squares evaluation comparisons, is documented in Appendix A.

The direct comparison of measured versus calculated fast neutron threshold reaction rates for the sensors from Capsule X that was withdrawn from Watts Bar Unit I at the end of the twelfth fuel cycle, is summarized below.

i.:

l '..- '..-.:

ke~a'R.-: :: 'M : : ': ..........

.: :U;Rat......7 ..-..:: .(s.

.atiom

-.. '.. :R :.' , '. c ::':'

.dReaction Med ' C te Riatio .

CU(na) Co 4.48E-17 4.07E-17 1.10 54Fe(n,p)4 Mn 4.46E-15 4.65E-15 0.96 5 8Ni(n,p) 5 8Co 6.69E-15 6.65E-15 1.02 231U(n p)137Cs (Cd) 2.47E-14 2.57E-14 0.96 237Np(nf)1 37Cs (Cd) 2.65E-13 2.59E-13 1.02 Average: 1.01 The measured-to-calculated (M/C) reaction rate ratios for the Capsule X threshold reactions range from 0.96 to 1.10, and the average M/C ratio is 1.01 +/- 5.8% (I6). This direct comparison falls well within the

+/- 20% criterion specified in Regulatory Guide 1.190; furthermore, it is consistent with the full set of comparisons given in Appendix A for all measured dosimetry removed to date from the Watts Bar Unit 1 reactor. These comparisons validate the current analytical results described in Section 6.2; therefore, the calculations are deemed applicable for Watts Bar Unit 1.

Radiation Analysis and Neutron Dosimetry

6-6 6.4 CALCULATIONAI, UNCERTAINTIES The uncertainty associated wvith the calculated neutron exposure of the Watts Bar Unit 1 surveillance capsule and reactor pressure vessel is based on the recommended approach provided in Regulatory Guide 1.190. In particular, the qualification of the methodology was carried out in the following four stages:

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

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

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

4 - Comparisons of the plant specific calculations with all available dosimetry results from the Watts Bar Unit I surveillance program.

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

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

The fourth phase of the uncertainty assessment (comparisons with Watts Bar Unit 1 measurements) was used solely to demonstrate the validity of the transport calculations and to confirm the uncertainty estimates associated with the analytical results. The comparison was used only as a check and was not used in any way to modify the calculated surveillance capsule and pressure vessel neutron exposures previously described in Section 6.2. As such, the validation of the Watts Bar Unit 1 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 infornmation pertinent to these evaluations is provided in Reference 21.

Radiation Analysis and Neutron Dosimetry

6-7 If .. ::. .: :: . -- :::5 t. .'::  :- : :: fCapsule Ves:.::sel .::

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 treated as random and no systematic bias was applied to the analytical results.

The plant specific measurement comparisons described in Appendix A support these uncertainty assessments for Watts Bar Unit 1.

Radiation Analysis and Neutron Dosimetry

6-8 Figure 6-1 IWatts Bar Unit 1 r,0 Reactor Geometry with a 150 Neutron Pad at the Core Midplane 240 180 E

U In 120 60 0

0 75 150 225 300 R Axis (cm)

Radiation Analysis and Neutron Dosimetry

6-9 Figure 6-1 (continued)

Watts Bar Unit I rO Reactor Geometry with a 17.50 Neutron Pad at the Core Midplane 240 180 E

C', 1 20 60 0

0 75 150 225 300 R Axis (cm)

Radiation Analysis and Neutron Dosimetry

6-10 Figure 6-1 (continued)

Watts Bar Unit I rO Reactor Geometry with a 200 Neutron Pad at the Core Midplane 240 180 x

1 20 60 0

0 75 150 225 300 R Axis (cm)

Radiation Analysis and Neutron Dosimetry

6-11 Figure 6-2 NVatts Bar Unit I rz Reactor Geometry with Neutron Pad 22P%-

Or Is FYYTYI 175 -

125 -

75 -

25-U

-C x

-25

-75

-125 -

-175 ..

-225 I I I I I I I I I I 0 75 150 225 300 375 R Axis (cm)

Radiation Analysis and Neutron Dosimetry

6-12 Table 6-1 Calculated Neutron Exposure Rates And Integrated Exposures at the Surveillance Capsule Center Neutrons Flux (E > 1.0 MeV)

,-,'- - 'Cumulative Cu'mulative ' N""t-'eutronFlux (E>'1.0 MeV)-' ' -

Lngth Time Time.:.,'......Du Cyl EFS EFPS! [EFPY 4. ........

1 3.800E+07 3.800E+07 1.20 9.968E+10 1.176E+11 1.194E+1l 2 4.073E+07 7.873E+07 2.49 6.404E+10 7.339E+10 7.444E+10 3 4.359E+07 1.223E+08 3.88 6.343E+10 7.284E+10 7.389E+10 4 4.217E+07 1.645E+08 5.21 7.275E+10 8.363E+10 8.483E+10 5 4.459E1+07 2.091 E+08 6.63 5.634E+10 6.520E+10 6.614E+10 6 4.593E+07 2.550E+08 8.08 6.198E+10 7.278E+10 7.385E+10 Future 2.183E-08 4.734E+08 15 6.198E+10 7.278E+10 7.385E+10 Future 3.156E+08 7.889E+08 25 6.198E+10 7.278E+10 7.385E+10 Future 2.209E+08 l.O1lOE+09 32 6.198E+10 7.278E+10 7.385E+10 Future 1.262E+08 1.136E+09 36 6.198E+10 7.278E+10 7.385E+10 Future 1.262E+08 1.262E+09 40 6.198E+10 7.278E+10 7.385E+10 Future 2.525E+08 1.515E+09 48 6.198E+10 7.278E+10 7.385E+10 Future 1.893E+08 1.70413+09 54 6.198E+10 7.27813+10 7.385E+10 Future 1.893E+08 1.893E+09 60 6.198E+10 7.278E+10 7.385E+10 Note: Neutron exposure values reported for the surveillance capsules are centered at the core inidplane.

Radiation Analysis and Neutron Dosimetry

6-13 Table 6-1 cont'd Calculated Neutron Exposure Rates And Integrated Exposures at the Surveillance Capsule Center Cumulative Neutrons Fluence (E > 1.0 MeV)

CumutiulatiVe :Cuulatie Neutron Fluence" E:> 1.0Me'"

Cycle. :Irradiation:. :::Ir adiation [ncm-s:

-ength ' Time T"ime, -iI Dual. S-Cycle" [EFPS] EFPS] ] 34.34 .... .... ..

I 3.800E+07 3.800E+07 1.20 3.788E+18 4.469E+18 4.536E+18 2 4.073E+07 7.873E+07 2.49 6.396E+18 7.459E+18 7.568E+18 3 4.359E+07 1.223E+08 3.88 9.161E+18 1.063E+19 1.079E+19 4 4.217E+07 1.645E+08 5.21 1.223E+19 1.416E+19 1.437E+19 5 4.459E+07 2.091IE+08 6.63 1.474E+19 1.707E+19 1.731E+19 6 4.593E+07 2.550E+08 8.08 1.759E+19 2.041E+19 2.071E+19 Future 2.183E-08 4.734E+08 15 3.112E+19 3.630E+19 3.683E+19 Future 3.156E+08 7.889E+08 25 5.068E+19 5.927E+19 6.014E+19 Future 2.209E+08 1.01OE+09 32 6.437E+19 7.535E+19 7.645E+19 Future 1.262E+08 1.136E+09 36 7.220E+19 8.453E+19 8.577E+19 Future 1.262E+08 1.262E+09 40 8.002E+19 9.372E+19 9.509E+19 Future 2.525E+08 1.515E+09 48 9.567E+19 1.121E+20 1.137E+20 Future 1.893E+08 1.704E+09 54 1.074E+20 1.259E+20 1.277E+20 Future 1.893E+08 1.893E+09 60 1.191E+20 1.397E+20 1.417E+20 Note: Neutron exposure values reported for the surveillance capsules are centered at the core midplanc.

Radiation Analysis and Neutron Dosimetry

6-14 Table 6-1 cont'd Calculated Neutron Exposure Rates And Integrated Exposures at the Surveillance Capsule Center Iron Atom Displacement Rates

'IronDisplacent Cumulative Culative a ., Rates (E> 1.0MeV)

,, . Cycle ' rradiation 'r diati. j: ;. '[ dp'a:-

s-lB Lengh Time Ti' Dual -' Dual Single Cycle [EFS1' [EFPS] [E,,: 31 5 ' 340 ' 340 I 3.800E+07 3.800E+07 1.20 1.964E-10 2.355E-10 2.438E-10 2 4.073E+07 7.873E+07 2.49 1.248E-10 1.453E-10 1.504E-10 3 4.359E+07 1.223E+08 3.88 1.234E-10 1.440E-10 1.489E-10 4 4.217E+07 1.645E+08 5.21 1.417E-10 1.654E-10 1.711E-10 5 4.459E+07 2.0911E+08 6.63 1.096E-10 1.289E-10 1.334E-10 6 4.593E+07 2.550E+08 8.08 1.210E-10 1.443E-10 1.494E-10 Future 2.183E-O8 4.734E+08 15 1.210E-10 1.443E-10 1.494E-10 Future 3.156E+08 7.889E+08 25 1.210E-10 1.443E-10 1.494E-10 Future 2.209E+08 l.OlOE+09 32 1.21OE-10 1.443E-10 1.494E-10 Future 1.262E+08 1.136E+09 36 1.210E-I0 1.443E-10 1.494E-10 Future 1.262E+08 1.262E+09 40 1.210E-10 1.443E-10 1.494E-10 Future 2.525E+08 1.515E+09 48 1.210E-10 1.443E-10 1.494E-10 Future 1.893E+08 1.704E+09 54 1.210E-10 1.443E-10 1.494E-10 Future 1.893E+08 1.893E+09 60 1.210E-10 1.443E-10 1.494E-10 Note: Neutron exposure values reported for the surveillance capsules are centered at the core midplane.

Radiation Analysis and Neutron Dosimetry

6-15 Table 6-1 cont'd Calculated Neutron Exposure Rates And Integrated Exposures at the Surveillance Capsule Center Cumulative Iron Atom Displacements Cumulativie Cu;ulati "ron 'Ato'm Displac-emn ents '>'1.0 MeV)

, LenthCycl ': ....

....i

,"Tim'e."' [........on~:<>....~.

T'im' tD a; 'iDual'ISii1I~

Cyclec'S [EFPS1 . 49.

340 1 3.800E+07 3.800E+07 1.20 7.464E-03 8.949E-03 9.264E-03 2 4.073E+07 7.873E+07 2.49 1.255E-02 1.487E-02 1.539E-02 3 4.359E+07 1.223E+08 3.88 1.793E-02 2.114E-02 2.188E-02 4 4.217E-07 1.645E1+08 5.21 2.390E-02 2.812E-02 2.910E-02 5 4.459E1+07 2.091E+08 6.63 2.879E-02 3.387E-02 3.505E-02 6 4.593E+07 2.550E+08 8.08 3.434E-02 4.050E-02 4.191E-02 Future 2.183E-08 4.734E+08 15 6.075E-02 7.201E-02 7.451lE-02 Future 3.156E+08 7.889E+08 25 9.892E-02 1.176E-01 1.217E-0O Future 2.209E+08 1.O1OE1+09 32 1.256E-01 1.494E-01 1.547E-01 Future 1.262E+08 1.136E+09 36 1.409E-01 1.677E-01 1.735E-0l Future 1.262E1+08 1.262E+09 40 1.562E-01 1.859E-01 1.924E-O1 Future 2.525E+08 1.515E+09 48 1.867E-01 2.223E-01 2.301E-01 Future 1.893E+08 1.704E+09 54 2.096E-01 1.497E-01 2.584E-01 Future 1.893E+08 1.893E+09 60 2.325E-01 2.770E-01 2.866E-01 Note: Neutron exposure values reported for the surveillance capsules are centered at the core rnidplane.

Radiation Analysis and Neutron Dosimetry

6-16 Table 6-2 Calculated Azimuthal Variation of Maximum Exposure Rates And Integrated Exposures at the Reactor Vessel Clad/Base Metal Interface Cumulativ'e -'Cumulat'iv'e ' ":'":" :Neut on Flux (E 0 Me

Cycle.Irradiation Irradiation': 2

/ ,

n __j___'_'_

Lene-h Tim ime

-Cyc'le- [EFS [FPS] ,[EFPY: 0 ' 15 30 , 450 1 3.800E+07 3.800E+07 1.20 1.260E+10 1.916E+10 1.903E+10 2.353E+10 2 4.073E+07 7.873E+07 2.49 8.1711E+09 1.270E+10 1.318E+10 1.522E+10 3 4.359E+07 1.223E+08 3.88 9.097E+09 1.253E+10 1.278E+10 1.494E+10 4 4.217E+07 1.645E+08 5.21 8.537E+09 1.263E+10 1.386E+10 1.625E+10 5 4.459E+07 2.091E+08 6.63 7.942E1+09 1.062E1+10 1.086E+10 1.320E+10 6 4.593E+07 2.550E+08 8.08 7.885E+09 1.137E+10 l.190E+10 1.5013E+10 Future 2.183E-08 4.734E+08 15 7.885E+09 1.137E+10 1.190E+10 l.501E+10 Future 3.156E+08 7.889E+08 25 7.885E+09 1.137E+10 1.190E+10 1.501E+10 Future 2.209E+08 1.01OE+09 32 7.885E+09 1.137E+10 1.190E+10 1.501SE+10 Future 1.262E+08 1.136E+09 36 7.885E+09 1.137E+10 1.190E+10 l.501E+10 Future 1.262E+08 1.262E+09 40 7.885E+09 1.137E+10 1.190E+10 l.501SE+10 Future 2.525E+08 1.515E+09 48 7.885E+09 1.137E+1O0 1.190E+10 1.501SE+10 Future 1.893E+08 1.704E+09 54 7.885E+09 1.137E+10 1.190E+10 l.501SE+10 Future 1.893E+08 1.893E+09 60 7.885E+09 1.137E+10 1.190E+10 l.501E+10 Radiation Analysis and Neutron Dosimetry

6-17 Table 6-2 cont'd Calculated Azimuthal Variation of Maximum Exposure Rates And Integrated Exposures at the Reactor Vessel Clad/Base Metal Interface Cumuative '

,' ' Cumulative ""-Neut Fluen'ce 'l10Me ':

'Cycle' 'Irr'di'tio" Iradiat a ion,: ' r

,:, 'Length Time Tim yc [EFPS1 PS] '-FFS. [E;']' "3 00 150' 45' I 3.800E+07 3.800E+07 1.20 4.786E+17 7.280E+17 7.299E+17 8.942E+17 2 4.073E+07 7.873E+07 2.49 7.962E+17 1.222E+18 1.237E+18 1.486E+18 3 4.359E+07 1.223E+08 3.88 1.192E+18 1.767E+18 1.792E+18 2.135E+18 4 4.217E+07 1.645E+08 5.21 1.546E+18 2.291E+18 2.368E+18 2.810E+18 5 4.459E+07 2.091E+08 6.63 1.896E+18 2.760E+18 2.847E+18 3.392E+18 6 4.593E+07 2.550E+08 8.08 2.259E+18 3.282E+18 3.394E+18 4.081E1+18 Future 2.183E-08 4.734E+08 15 3.980E+18 5.763E+18 5.992E+18 7.357E+18 Future 3.156E+08 7.889E+08 25 6.468E+18 9.350E+18 9.748E+18 1.209E+19 Future 2.209E+08 1.01OE+09 32 8.21 OE+18 1.186E+19 1.238E+19 1.541E+19 Future 1.262E+08 1.136E+09 36 9.205E+18 1.330E+19 1.388E+19 1.730E+19 Future 1.262E+08 1.262E+09 40 1.020E+19 1.473E+19 1.538E+19 1.919E+19 Future 2.525E+08 1.515E+09 48 1.219E+19 1.760E+19 1.839E+19 2.298E+19 Future 1.893E+08 1.704E+09 54 1.368E+19 1.975E+19 2.064E+19 2.582E+19 Future 1.893E+08 1.893E+09 60 1.518E+19 2.190E+19 2.289E+19 2.866E+19 Radiation Analysis and Neutron Dosimetry

6-18 Table 6-2 cont'd Calculated Azimuthal Variation of Fast Neutron Exposure Rates And Iron Atom Displacement Rates at the Reactor Vessel Clad/Base Metal Interface

-. Cmlatives .  : .i Irn Atom Displacemen Rate.

son-Cumulative

- - i  ::.  :  ::iC.:.:':.:.-':..::'.:::.:

. .: .:.'.:.:O ad rration oation> [dna/si - _::;

-- Lengt-hi> Tim Tiie Cycle [EFPS] EEPS]. [EFPYJ 00 150; 0 - 450 1 3.800E+07 3.800E+07 1.20 1.954E-11 2.945E-l1 2.968E-11 3.729E-11 2 4.073E+07 7.873E+07 2.49 1.270E-11 1.955E-1I 2.054E-11 2.409E-1 I 3 4.359E+07 1.223E+08 3.88 1.412E-11 I .930E-11 1.992E-11 2.364E-11 4 4.217E+07 1.645E+08 5.21 1.327E-11 1.948E-11 2.161E-11 2.573E-1 I 5 4.459E+07 2.091E+08 6.63 1.233E-11 1.638E-11 1.695E-11 2.089E-1l 6 4.593E+07 2.550E+08 8.08 1.225E-11 1.751E-11 1.857E-11 2.374E-1I Future 2.183E-08 4.734E+08 15 1.225E-11 1.751E-ll 1.857E-11 2.374E-ll Future 3.156E+08 7.889E+08 25 1.225E-11 1.751E-11 1.857E-11 2.374E-ll Future 2.209E+08 I.OIOE+09 32 1.225E-11 1.751E-11 1.857E-11 2.374E-1 I Future 1.262E+08 1.136E+09 36 1.225E-l1 1.751E-11 1.857E-11 2.374E-ll Future 1.262E+08 1.262E+09 40 1.225E-11 1.751E-11 1.857E-11 2.374E- lI Future 2.525E+08 1.515E+09 48 1.225E-11 1.751E-11 1.857E-11 2.374E- lI Future 1.893E+08 1.704E+09 54 1.225E-11 1.751E-11 l1.857E-11 2.374E- 11 Future 1.893E+08 1.893E+09 60 1.225E- 11 1.751E-11 l1.857E-11 2.374E-11 Radiation Analysis and Neutron Dosimetry

6-19 Table 6-2 cont'd Calculated Azimuthal Variation of Maximum Exposure Rates And Integrated Exposures at the Reactor Vessel Clad/Base Metal Interface

' ' ' Cumulative' Cumulative '-Ir. onAtom Dis 'l emenits.

ycie 'Irradiation

. - . . ~~~.. ... ....... ..

'Irration :

'- ' al ' .:

Le'th Time Time Cycle [EFPS] " -[EFPS] ' EF '150 .30 450 1 3.800E+07 3.800E+07 1.20 7.426E-04 1.119E-03 1.128E-03 1.417E-03 2 4.073E+07 7.873E+07 2.49 1.236E-03 1.879E-03 1.928E-03 2.353E-03 3 4.359E+07 1.223E+08 3.88 1.850E-03 2.718E-03 2.794E-03 3.380E-03 4 4.217E+07 1.645E+08 5.21 2.400E-03 3.526E-03 3.690E-03 4.448E-03 5 4.459E+07 2.091E+08 6.63 2.944E-03 4.249E-03 4.437E-03 5.369E-03 6 4.593E+07 2.550E+08 8.08 3.506E-03 5.053E-03 5.290E-03 6.459E-03 Future 2.183E-08 4.734E+08 15 6.180E-03 8.876E-03 9.344E-03 1.164E-02 Future 3.156E+08 7.889E+08 25 1.005E-02 1.440E-02 1.521E-02 1.913E-02 Future 2.209E+0S 1.O1OE+09 32 1.275E-02 1.827E-02 1.931E-02 2.438E-02 Future 1.262E+08 1.136E+09 36 1.430E-02 2.048E-02 2.165E-02 2.737E-02 Future 1.262E+08 1.262E+09 40 1.584E-02 2.269E-02 2.400E-02 3.037E-02 Future 2.525E+08 1.515E+09 48 1.894E-02 2.711 E-02 2.868E-02 3.636E-02 Future 1.893E+08 1.704E+09 54 2.126E-02 3.043E-02 3.220E-02 4.086E-02 Future 1.893E+08 1.893E+09 60 2.358E-02 3.375E-02 3.572E-02 4.535E-02 Radiation Analysis and Neutron Dosimetry

6-20 Table 6-3 Relative Radial Distribution of Maximum Neutron Fluence (E > 1.0 MeV)

Within The Reactor Vessel Wall RADIUS:::-: - X__IMUTHAAGLE ___:_-_

(cm) 0I 15 ° 30 450 220.35 1.000 1.000 1.000 1.000 225.87 0.560 0.557 0.559 0.548 231.39 0.275 0.271 0.273 0.261 236.90 0.128 0.126 0.128 0.119 242.42 0.058 0.057 0.058 0.051 Note: Base Metal Inner Radius = 220.35 cm Base Metal l/4T = 225.87 cm Base Metal 1/2T = 231.39 cm Base Metal 3/4T = 236.90 cm Base Metal Outer Radius = 242.42 cm Note: Values for EOC 6 Table 64 Relative Radial Distribution of Maximum Iron Atom Displacerments (dpa)

Within The Reactor Vessel Wall RADIUS.-:` AZIMUTH AGE 0: J 0 . .cm) -:;300: 45 220.35 1.000 1.000 1.000 1.000 225.87 0.633 0.630 0.642 0.636 231.39 0.380 0.377 0.393 0.383 236.90 0.225 0.224 0.238 0.224 242.42 0.126 0.125 0.135 0.117 Note: Base Metal Inner Radius = 220.35 cm Base Metal 1/4T = 225.87 cm Base Metal 1/2T = 231.39 cm Base Metal 3/4T = 236.90 cm Base Metal Outer Radius = 242.42 cm Note: Values for EOC 6 Radiation Analysis and Neutron Dosimetry

6-21 Table 6-5 Calculated Fast Neutron Exposure of Surveillance Capsules Withdrawn from Watts Bar Unit I Irradiation Time Fluence (E> 1.0 MeV) Iron isplacements Capsule:: [ 'E

P >]; [nIc 2 ] [dp

.:::::;-aj U 1.20 4.47E+18 8.95E-03 W 3.88 1.08E+19 2.19E-02 X 6.63 1.71E+19 3.39E-02 Table 6-6 Calculated Surveillance Capsule Lead Factors

Caps'ule ID :"::::-,: .> -'; i A.nd Location .::..-  :...:' i: ......

. i..::: Lead Factor:'

U (340 - dual) Withdrawn EOC 1 5.00 W (340 - single) Withdrawn EOC 3 5.05 X (340 - dual) WMithdrawn EOC 5 5.03 V (31.50 - dual) In Reactor 4.31 Y (31.5° - dual) In Reactor 4.31 Z (340 - single) In Reactor 5.07 Note: Lead factors for capsules remaining in the reactor are based on cycle specific exposure calculations through the current operating fuel reload, i.e., Cycle 6.

Radiation Analysis and Neutron Dosimetry

7-1 7 SURVEILLANCE CAPSULE REMOVAL SCHEDULE The following surveillance capsule removal schedule meets the requirements of ASTM E185-82 and is recommended for future capsules to be removed from the Watts Bar Unit 1 reactor vessel. This recommended removal schedule is applicable to 32 EFPY of operation.

T~able7-1 ,Recommnded Surveill cCapsul N'Vithda Shdic>

Casl .,..Capsue -Location . cad Factor la WithdrawFluenc.(cm)

U 560 5.0 1.20 4.47 x 1018 (c)

X 1240 5.05 3.88 1.08 x 1019 (c)

X 2360 5.03 6.63 1.71 x 1019 (c)

Z 304 0 5.07 9.25 (d)

V 58.50 4.31 Standby (e)

Y 238.50 4.31 Standby (e)

Notes:

(a) Updated in Capsule X dosimetry analysis.

(b) Effective Full Power Years (EFPY) from plant startup.

(c) Plant specific evaluation.

(d) Capsule Z will have a fluence greater than one-times and less than two-times the peak EOL (32 EFPY vessel fluence (1.541 x 1019 n/cm2 ). If Capsule Z is removed @ 9.25 EFPY it will also satisfy the last Capsule Removal for an EOL of 48 EFPY (e)Section XI.M3 1, "Reactor Vessel Surveillance," of NUREG-1 801 states that any surveillance capsules that are left in the reactor vessel should provide meaningful metallurgical data. The NRC specifically states that anything beyond 60 years of exposure is not meaningful metallurgical data. Hence, it is recommended that Capsules "V" and "Y" be removed at the closest outage on or after 10.7 EFPY (Equivalent to 1 times the 48 EFPY Peak Vessel Fluence of 2.298 x 1019 n/cm2 ) and placed in storage.

Surveillance Capsule Removal Schedule

8-1 8 REFERENCES

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

2. Code of Federal Regulations, I OCFR50, Appendix G, FractureToughness Requirements,and Appendix H, Reactor Vessel MaterialSurveillance Program Requirements, U.S. Nuclear Regulatory Commission, Washington, D.C.

3. BWXT Report, Analysis of Capsule Wfrom the Tennessee ValleyAuthority Watts Bar Unit 1 Reactor Vessel Radiation Surveillance Program,W.A. Pavinich, dated 9/10/01.

4. WCAP-9298, Rev. 3, Tennessee Valley Authority Watts Bar Unit I Reactor Vessel Radiation Surveillance Programn PA. Peter, August 1995.

5. WCAP-15046, Analysis of Capsule Ufrom the Tennessee Valley.Authority Watts Bar Unit I Reactor Vessel Radiation Surveillance Program,TJ. Laubham, et. al., June 1998.

6. WCAP-13587, Revision 1,Reactor Vessel Upper Shelf Energy Bounding Evaluation For Westinghouse PressurizedWater Reactors, S. Tandon, et. al., September 1993.

7. ASTM E208, Standard Test Methodfor ConductingDrop-Weight Test to Determine Nil-Ductility Transition Temperature ofFerriticSteels, in ASTM Standards, Section 3, American Society for Testing and Materials, Philadelphia, PA.

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

9. ASTM E185-82, StandardPracticefor Conducting Surveillance Testsfor LighJ-T-ater Cooled Nuclear Power Reactor Vessels. [Sub-

Reference:

ASTME185-73, 1973 Version]

10. Procedure RMF 8402, Surveillance Capsule Testing Program,Revision 2.

11. Procedure RMF 8102, Tensile Testing, Revision 1.

12. Procedure RMF 8103, Charpy Impact Testing, Revision 1.

13. ASTM E23-02a, StandardTest Methodfor Notched Bar Impact Testing of MetallicMaterials, ASTM, 2002.

14. ASTM A370-97a, Standard Test Methods and Definitionsfor Mechanical Testing of Steel Products,ASTM, 1997.

15. ASTM E8-01, StandardTest Methodsfor Tension Testing ofMetallic Materials,ASTM, 2001.

References

8-2

16. ASTM E21-92 (1998), StandardTest Methodsfor Elevated Temperature Tension Tests of Metallic Materials,ASTM, 1998.

17. ASTM E83-93, StandardPracticefor Verification and Classification ofExtensonmeters, in ASTM Standards, Section 3, American Society for Testing and Materials, Philadelphia, PA, 1993.

18. WCAP-14370, Use of the Hyperbolic Tangent Functionfor Fitting Transition Temperature Toughness Data, T. R. Mager, et al, May 1995.

19. Regulatory Guide RG-I .190, Calculationaland Dosimetry Methodsfor DeterminingPressure Vessel Neutron Fluence, U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, March 2001.

20. WCAP-14040-NP-A, Revision 2, Methodology Used to Develop Cold OverpressureMitigating System Setpoints and RCS Heatup and Cooldown Limit Curves, January 1996.

21. WCAP-15557, Revision 0, Qualificationof the Westinghouse Pressure Vessel Neutron Fluence Evaluation Methodology, August 2000.

22. RSICC Computer Code Collection CCC-650, DOORS 3.1, One, Two- and Three-Dimensional Discrete OrdinatesNeutron/Photon Transport Code System, August 1996.

23. RSIC Data Library Collection DLC-1 85, "BUGLE-96, Coupled 47 Neutron, 20 Gamma-Ray Group Cross Section Library Derived from ENDF/B-VI for LWR Shielding and Pressure Vessel Dosimetry Applications," March 1996.

References

A-O APPENDIX A VALIDATION OF THE RADIATION TRANSPORT MODELS BASED ON NEUTRON DOSIMETRY MEASUREMENTS Appendix A

A-1 A.1 Neutron Dosimetry Comparisons of measured dosimetry results to both the calculated and least squares adjusted values for all surveillance capsules withdrawn from service to date at Watts Bar Unit I are described herein. The sensor sets from these capsules have been analyzed in accordance with the current dosimetry evaluation methodology described in Regulatory Guide 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence."EA-l] One of the main purposes for presenting this material is to demonstrate that the overall measurements agree with the calculated and least squares adjusted values to within +/- 20% as specified by Regulatory Guide 1.190, thus serving to validate the calculated neutron exposures previously reported in Section 6.2 of this report. This information may also be useful in the future, in particular, as least squares adjustment techniques become accepted in the regulatory environment.

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

.. . ..-..... ..- i i.  ;.- . i......... .:. ---

. . .., J....

,..; M CapleIDI Azimuthal Wit.d.awal .r a.ia.ion I.i:.-i.i

.i.;;............... .............

n.. ... :

....c...tio........  : ......

,;--J TieTm EFfY]"~

U 340 End of Cycle 1 1.20 W 340 End of Cycle 3 3.88 X 340 End of Cycle 5 6.63 The azimuthal locations included in the above tabulation represent the first octant equivalent azimuthal angle of the geometric center of the respective surveillance capsules.

Appendix A

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

Sensor Material Reaction Of Capsule U CapsIue C

>  : -  ; ; v Interest; __;____;_i

_ _ _ _ _:_;____* g Copper ' 3 Cu(n4 0Co X X X Iron 54Fe(np)pMn X X X 3 58 Nickel "Ni(np) Co X X X Uranium-238 238U(nf)137Cs X X X 237 Neptunium-237 Np(n,f) 37cS X X X Cobalt-Aluminum* " 9Co(nk)6Co X X X

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

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

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

• The measured specific activity of each monitor,

• the physical characteristics of each monitor,

• the operating history of the reactor,

• the energy response of each monitor, and

• the neutron energy spectrum at the monitor location.

Results from the radiometric counting of the neutron sensors from Capsules U, W and X are documented in References A-2 through A4, respectively. The radiometric counting of the sensors from Capsule X was carried out by Pace Analytical Services, Inc., located at the Westinghouse Waltz Mill Site. In all cases, the radiometric counting followed established ASTM procedures. Following sample preparation and Appendix A

A-3 weighing, the specific activity of each sensor was determined by means of a high-resolution gamma spectrometer. For the copper, iron, nickel, and cobalt-aluminum sensors, these analyses were performed by direct counting of each of the individual samples. In the case of the uranium and neptunium fission sensors, the analyses were carried out by direct counting preceded by dissolution and chemical separation of cesium from the sensor material.

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

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

A R= Pj No F Y S - Cj [1- e-l"] [e-AI]

Pref where:

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

A = Measured specific activity (dps/gm).

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

F = Weight fraction of the target isotope in the sensor material.

Y = Number of product atoms produced per reaction.

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

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

C1 = Calculated ratio of 4 (E > 1.0 MeV) during irradiation periodj to the time weighted average O(E > 1.0 MeV) over the entire irradiation period.

X. = 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.

Appendix A

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

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

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

Prior to using the measured reaction rates in the least-squares evaluations of the dosimetry sensor sets, additional corrections were made to the 238U measurements to account for the presence of 23sU impurities in the sensors as well as to adjust for the build-in of plutonium isotopes over the course of the irradiation.

Corrections were also made to the 23sU and 737Np sensor reaction rates to account for gamma ray induced fission reactions that occurred over the course of the capsule irradiations. The correction factors applied to the Watts Bar Unit 1 fission sensor reaction rates are summarized as follows:

l C{n{orreMtitile: i%; aps1U s -X XV C sue X 235U Impurity/Pu Build-in 0.867 0.843 0.819 238U(y,f) 0.964 0.964 0.964 Net 238 U Correction 0.836 0.813 0.789 7

Np(yf) 0.990 0.990 0.990 These factors were applied in a multiplicative fashion to the decay corrected uranium and neptunium fission sensor reaction rates.

Results of the sensor reaction rate determinations for Capsules U, W, and X are given in Table A-4. In Table A-4, the measured specific activities, decay corrected saturated specific activities, and computed reaction rates for each sensor indexed to the radial center of the capsule are listed. The fission sensor reaction rates are listed both with and without the applied corrections for 23U impurities, plutonium build-in, and gamma ray induced fission effects.

Appendix A

A-5 A.1.2 Least Snuares Evaluation of Sensor Sets Least squares adjustment methods provide the capability of combining the measurement data with the corresponding neutron transport calculations resulting in a Best Estimate neutron energy spectrum with associated uncertainties. Best Estimates for key exposure parameters such as 4(E > 1.0 MeV) or dpa/s along with their uncertainties are then easily obtained from the adjusted spectrum. In general, the least squares methods, as applied to surveillance capsule dosimetry evaluations, act to reconcile the measured sensor reaction rate data, dosimetry reaction cross-sections, and the calculated neutron energy spectrum within their respective uncertainties. For example,

=

Ri + SR, I (ig+/-6 )(Og +/-6¢,)

8 relates a set of measured reaction rates, Ri, to a single neutron spectrum, 4 ., through the multigroup dosimeter reaction cross-section, ai,, each with an uncertainty B. The primary objective of the least squares evaluation is to produce unbiased estimates of the neutron exposure parameters at the location of the measurement.

For the least squares evaluation of the Watts Bar Unit I surveillance capsule dosimetry, the FERRET codeA-41 was employed to combine the results of the plant specific neutron transport calculations and sensor set reaction rate measurements to determine best-estimate values of exposure parameters (O(E > 1.0 MeV) and dpa) along with associated uncertainties for the five in-vessel capsules withdrawn to date.

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

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

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

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

For the Watts Bar Unit 1 application, the calculated neutron spectrum was obtained from the results of plant specific neutron transport calculations described in Section 6.2 of this report. The sensor reaction rates were derived from the measured specific activities using the procedures described in Section A.l .1.

The dosimetry reaction cross-sections and uncertainties were obtained from the SNLRML dosimetry cross-section library[A 51 . The SNLRML library is an evaluated dosimetry reaction cross-section compilation recommended for use in LWR evaluations by ASTM Standard ElOI 8, "Application of ASTM Evaluated Cross-Section Data File, Matrix E 706 (IIB)".

Appendix A

A-6 The uncertainties associated with the measured reaction rates, dosimetry cross-sections, and calculated neutron spectrum were input to the least squares procedure in the form of variances and covariances.

The assignment of the input uncertainties followed the guidance provided in ASTM Standard E 944, "Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance."

The following provides a summary of the uncertainties associated with the least squares evaluation of the Watts Bar Unit 1 surveillance capsule sensor sets.

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

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

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

5Fe(n,p) Mn 5%

5Ni(np) 58Co 5%

238 U(nf)137Cs 10%

23Np(nf)13 7 CS 10%0/

59Co(n,y) 60Co 5%

These uncertainties are given at the 1c; level.

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

Appendix A

A-7 For sensors included in the Farley Unit 1 surveillance program, the following uncertainties in the fission spectrum averaged cross-sections are provided in the SNLRML documentation package.

v ..* Reacti..n;..i:g:. .t Unetint 3Cu(na) 0Co 4.08-4.16%

14Fe(n,p) Mn 3.05-3.11%

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

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

237Np(nf)137Cs 10.32-10.97%

59Co(n,y) 60Co 0.79-3.59%

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

Calculated Neutron Snectrum The neutron spectra input to the least squares adjustment procedure were obtained directly from the results of plant specific transport calculations for each surveillance capsule irradiation period and location.

The spectrum for each capsule was input in an absolute sense (rather than as simply a relative spectral shape). Therefore, within the constraints of the assigned uncertainties, the calculated data were treated equally with the measurements.

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

Mg.=R2 +R

• R8 Pgg.

where Rn specifies an overall fractional normalization uncertainty and the fractional uncertainties Rg and Rg. specify additional random groupwise uncertainties that are correlated with a correlation matrix given by:

Igg= [l-ej8g + e H where 2

(g g')

2y 2 Appendix A

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

The set of parameters defining the input covariance matrix for the Farley Unit 1 calculated spectra was as follows:

Flux Normalization Uncertainty (R.) 15%

Flux Group Uncertainties (Rg, Rg-)

(E > 0.0055 MeV) 15%

(0.68 eV < E < 0.0055 MeV) 29%

(E < 0.68 eV) 52%

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 Appendix A

A-9 A.1.3 Comparisons of Measurements and Calculations Results of the least squares evaluations of the dosimetry from the Watts Bar Unit I surveillance capsules withdrawn to date are provided in Tables A-5 and A-6. In Table A-5, measured, calculated, and best-estimate values for sensor reaction rates are given for each capsule. Also provided in this tabulation are ratios of the measured reaction rates to both the calculated and least squares adjusted reaction rates.

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

The data comparisons provided in Tables A-5 and A-6 show that the adjustments to the calculated spectra are relatively small and well within the assigned uncertainties for the calculated spectra, measured sensor reaction rates, and dosimetry reaction cross-sections. Further, these results indicate that the use of the least squares evaluation results in a reduction in the uncertainties associated with the exposure of the surveillance capsules. From Section 6.4 of this report, it may be noted that the uncertainty associated with the unadjusted calculation of neutron fluence (E > 1.0 MeV) and iron atom displacements at the surveillance capsule locations is specified as 12% at the Ia level. From Table A-6, it is noted that the corresponding uncertainties associated with the least squares adjusted exposure parameters have been reduced to 7% for neutron flux (E > 1.0 MeV) and 11% for iron atom displacement rate. Again, the uncertainties from the least squares evaluation are at the Is level.

Further comparisons of the measurement results with calculations are given in Tables A-7 and A-8.

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

In the case of the direct comparison of measured and calculated sensor reaction rates, the M/C comparisons for fast neutron reactions range from 0.92-1.29 for the 15 samples included in the data set.

The overall average M/C ratio for the entire set of Watts Bar Unit I data is 1.08 with an associated standard deviation of 5.8%.

Appendix A

A-10 In the comparisons of best estimate and calculated fast neutron exposure parameters, the corresponding BE/C comparisons for the capsule data sets range from 0.98-1.15 forneutron flux (E > 1.0 MeV) and from 1.00 to 1.18 for iron atom displacement rate. The overall average BE/C ratios for neutron flux (E > 1.0 MeV) and iron atom displacement rate are 1.06 with a standard deviation of 8.2% and 1.09 with a standard deviation of 9.1%, respectively.

Based on these comparisons, it is concluded that the calculated fast neutron exposures provided in Section 6.2 of this report are validated for use in the assessment of the condition of the materials comprising the beltline region of the Watts Bar Unit 1 reactor pressure vessel.

Appendix A

A-li TableA-I Nuclear Parameters Used In The Evaluation Of Neutron Sensors Target 90% Response Fission Monitor Reaction of Atom Range Product Yield Material Interest Fraction (%eV) Half-life (%)

Copper 63Cu (n,a) 0.6917 4.9- 11.8 5.271 y Iron 4Fe (np) 0.0585 2.1 - 8.4 312.1 d Nickel "Ni (np) 0.6808 1.5 - 8.2 70.82 d 23 8 Uranium-238 U (nf) 1.0000 1.2 - 6.8 30.07 y 6.02 Neptunium-237 23 7Np (n,f) 1.0000 0.4 - 3.6 30.07 y 6.17 59 Cobalt-Aluminum Co (ny) 0.0015 non-threshold 5.271 y Note: The 90% response range is defined such that, in the neutron spectrum characteristic of the Watts Bar Unit I surveillance capsules, approximately 90% of the sensor response is due to neutrons in the energy range specified with approximately 5% of the total response due to neutrons with energies below the lower limit and 5% of the total response due to neutrons with energies above the upper limit.

Appendix A

A-12 TableA-2 Monthly Thermal Generation During The First Five Fuel Cycles Of The Watts Bar Unit 1 Reactor (Reactor PoNver of 3411 MWt for Cycles 1 through middle of Cycle 4, and 3459MW for subsequent cycles)

Cycle I Cycle 2 Cycle 3 Thermal Thermal Thermal Generation Generation Generation Month [MW-Hr] Month [MW-Hr] Month [MW-Hr]

Jan-96 9519 Oct-97 709914 Apr-99 1068631 Feb-96 49773 Nov-97 2449654 May-99 2454763 Mar-96 475248 Dec-97 2527971 Jun-99 2454685 Apr-96 999029 Jan-98 2523492 Jul-99 2536887 May-96 1713718 Feb-98 2142012 Aug-99 2526645 Jun-96 2348718 Mar-98 2180599 Sep-99 2455157 Jul-96 2523691 Apr-98 2370444 Oct-99 2540350 Aug-96 2525629 May-98 2535488 Nov-99 2454874 Sep-96 2184725 Jun-98 2445551 Dec-99 2536956 Oct-96 1114619 Jul-98 2531951 Jan-00 2536601 Nov-96 2202224 Aug-98 2486237 Feb-00 2373327 Dec-96 2523130 Sep-98 2429447 Mar-00 2536915 Jan-97 1956638 Oct-98 2470835 Apr-00 2451520 Feb-97 2147746 Nov-98 2452741 May-00 2536436 Mar-97 1645462 Dec-98 2535907 Jun-00 2455171 Apr-97 2236507 Jan-99 2280206 Jul-00 2534880 May-97 2519097 Feb-99 1519605 Aug-00 2279989 Jun-97 2237128 Mar-99 0 Sep-00 570521 Jul-97 2399891 Aug-97 1934439 Sep-97 262258 Total 36009189 Total 38592054 Total 41304308

[EFPS] 3.800E+07 [EFPS] 4.073E+07 [EFPS] 4.359E+07

[EFPY] 1.204 [EFPY] 1.291 [EFPY] 1.381 To Date To Date To Date

[EFPS] 3.800E+07 [EFPS] 7.873E+07 [EFPS] 1.223E+08

[EFPY] 1.204 [EFPY1 2.495 [EFPY1 3.876 Appendix A

A-13 Table A-2 (continued)

Monthly Thermal Generation During The First Five Fuel Cycles Of The Watts Bar Unit 1 Reactor (Reactor Power of 3411 MWt for Cycles 1 through middle of Cycle 4, and 3459MW for subsequent cycles)

Cycle 4 Cycle 5 Thermal Thermal Generation Generation Month [MW-Hr] Month [MW-Hr]

Oct-00 1906668 Mar-02 759955 Nov-00 2455222 Apr-02 2486032 Dec-00 2536907 May-02 2041632 Jan-01 2539043 Jun-02 2489640 Feb-01 2323719 Jul-02 2440231 Mar-01 2571100 Aug-02 2572406 Apr-01 2486145 Sep-02 2489113 May-01 2572676 Oct-02 2573865 Jun-01 2384162 Nov-02 2489493 Jul-01 1723109 Dec-02 2547822 Aug-01 2572727 Jan-03 2572408 Sep-01 2298210 Feb-03 2322599 Oct-01 2576028 Mar-03 2052502 Nov-01 2489629 Apr-03 2485939 Dec-01 2423020 May-03 2572277 Jan-02 2572218 Jun-03 2487655 Feb-02 1970262 Jul-03 2570050 Aug-03 2409124 Sep-03 485359 Total 40400845 Total 42848102

[EFPS] 4.217E+07 [EFPS] 4.459E+07

[EFPY] 1.336 [EFPY] 1.413 To Date To Date

[EFPS] 1.645E+08 [EFPS] 2.091 E+08

[EFPY] 5.213 [EFPY] 6.626 Appendix A

A-14 TableA-3 Calculated qCFactors at the Surveillance Capsule Center Core Midplane Elevation l.F.uel g.,'..::{g :..,. .MeY)lO 1XZ i

'ikh9 Cycle> CP

-i apsule X9 1 1.176E+11 1.194E+11 1.176E+1 1 2 7.444E+10 7.339E+10 3 7.389E+10 7.284E+10 4 8.363E+10 5 6.520E+10 Average 1.176E+11 8.821E+10 8.163E+10 Appendix A

A-15 Table A-4 Measured Sensor Activities And Reaction Rates Watts Bar Unit I - Surveillance Capsule U Corrected Averaged Averaged Measured Saturated Reaction Reaction Reaction Target Product Actitivy Actitivy Rate Rate Rate Location Isotope Isotope (dpslg) (dpsfg) (rpslatom) (rpslatom) (rpsfatom)

Top Cu-63 Co-60 5.05E+04 3.684E+05 5.620E-1 7 Middle Cu-63 Co-60 5.34E+04 3.895E+05 5.942E-1 7 Bottom Cu-63 Co-60 5.25E+04 3.829E+05 5.842E-1 7 5.801 E-17 5.801 E-17 Top Fe-54 Mn-54 1.62E+06 3.855E+06 6.111E-15 Middle Fe-54 Mn-54 1.71 E+06 4.069E+06 6.450E-1 5 Bottom Fe-54 Mn-54 1.71E+06 4.069E+06 6.450E-1 5 6.337E-15 6.337E-15 Top Ni-58 Co-58 1.20E+07 5.968E+07 8.544E-15 Middle Ni-58 Co-58 1.25E+07 6.217E+07 8.900E-1 5 Bottom Ni-58 Co-58 1.26E+07 6.267E+07 8.971 E-15 8.805E-15 8.805E-15 Top Co-59 Co-60 1.55E+07 1.1 31 E+08 7.376E-1 2 Top Co-59 Co-60 1.28E+07 9.337E+07 6.091 E-1 2 Middle Co-59 Co-60 1.43E+07 1.043E+08 6.805E-12 Middle Co-59 Co-60 1.1 9E+07 8.680E+07 5.663E-1 2 Bottom Co-59 Co-60 1.41 E+07 1.028E+08 6.71 OE-1 2 Bottom Co-59 Co-60 1.22E+07 8.899E+07 5.806E-12 6.409E-12 6.409E-12 Top Co-59 Cd Co-60 7.59E+06 5.536E+07 3.612E-12 Middle Co-59 Cd Co-60 7.06E+06 5.150E+07 3.360E-1 2 Bottom Co-59 Cd Co-60 7.1 OE+06 5.179E+07 3.379E-12 3.450E-12 3.450E-12 U-238 Cs-137 2.34E+05 8.647E+06 5.678E-14 5.678E-14 4.744E-14 Np-237 Cs-1 37 1.94E+06 7.169E+07 4.574E-13 4.574E-1 3 4.528E-13 Notes: 1) Measured specific activities are indexed to a counting date of January 30, 1998.

2) The average 238U (n,f) reaction rate of 4.744E-14 includes a correction factor of 0.867 to account for plutonium build-in and an additional factor of 0.964 to account for photo-fission effects in the sensor.

3) The average 23 7Np (n,f) reaction rate of 4.528E-13 includes a correction factor of 0.990 to account for photo-fission effects in the sensor.

Appendix A

A-16 Table A-4 cont'd Measured Sensor Activities And Reaction Rates Watts Bar Unit 1 - Surveillance Capsule W Corrected Averaged Averaged Measured Measured Saturated Reaction Reaction Reaction Target Product Actitivy Actitivy Actitivy Rate Rate Rate Location Isotope Isotope (micro-CI/g] (dpslg) (dps/g) (rpslatom) (rps/atom) (rps/atom)

Top Cu-63 Co-60 4.975 1.84E+05 4.874E+05 5.143E-1 7 Middle Cu-63 Co-60 5.265 1.95E+05 5.1 66E+05 5.451 E-1 7 Bottom Cu-63 Co-60 5.232 1.94E+05 5.139E+05 5.423E-1 7 5.339E-17 5.339E-17 Top Fe-54 Mn-54 1251 4.63E+07 5.950E+07 5.51 9E-1 5 Middle Fe-54 Mn-54 1308 4.84E+07 6.220E+07 5.769E-1 5 Bottom Fe-54 Mn-54 1269 4.70E+07 6.040E+07 5.602E-15 5.630E-15 5.630E-15 Top Ni-58 Co-58 1664 6.16E+07 7.787E+07 7.592E-1 5 Middle Ni-58 Co-58 1713 6.34E+07 8.015E+07 7.814E-15 Bottom Ni-58 Co-58 1665 6.16E+07 7.787E+07 7.592E-15 7.666E-15 7.666E-15 Top Co-59 Co-G0 5.483E+05 2.03E+10 5.378E+10 5.262E-1 2 Top Co-59 Co-60 4.803E+05 1.78E+10 4.715E+1 0 4.614E-1 2 Middle Co-59 Co-60 5.070E+05 1.88E+10 4.980E+10 4.874E-12 Middle Co-59 Co-60 4.191E+05 1.55E+10 4.106E+10 4.018E-1 2 Bottom Co-59 Co-60 5.247E+05 1.94E+10 5.1 39E+1 0 5.029E-1 2 Bottom Co-59 Co-60 4.432E+05 1.64E+10 4.344E+1 0 4.251 E-1 2 4.675E-1 2 4.675E-1 2 Top Co-59 Cd Co-60 2.740E+05 1.0IE+10 2.676E+10 2.618E-1 2 Middle Co-59 Cd Co-60 2.616E+05 9.68E+09 2.564E+1 0 2.509E-1 2 Bottom Co-59 Cd Co-60 2.690E+05 9.95E+09 2.636E+10 2.579E-12 2.569E-1 2 2.569E-1 2 U-238 Cs-137 9.13 3.97E+05 4.694E+06 3.082E-14 3.082E-14 2.504E-1 4 Np-237 Cs-1 37 124.8 4.62E+06 5.462E+07 3.485E-1 3 3.485E-1 3 3.450E-1 3 Notes: 1) Measured specific activities are indexed to a counting date of September 10, 2000.

2) The average 23'U (n,f) reaction rate of 2.504E-14 includes a correction factor of 0.843 to account for plutonium build-in and an additional factor of 0.964 to account for photo-fission effects in the sensor.

3) The average 237Np (nf) reaction rate of 3.450E-13 includes a correction factor of 0.990 to account for photo-fission effects in the sensor.

Appendix A

A-17 Table A-4 cont'd Measured Sensor Activities And Reaction Rates Watts Bar Unit 1 - Surveillance Capsule X Corrected Averaged Averaged Measured Saturated Reaction Reaction Reaction Target Product Actitivy Actitivy Rate Rate Rate Location Isotope Isotope (dpslg) (dps/g) (rpslatom) (rpslatom) (rpslatom)

Top Cu-63 Co-60 1.52E+05 2.889E+05 4.408E-17 Middle Cu-63 Co-60 1.55E+05 2.946E+05 4.495E-17 Bottom Cu-63 Co-60 1.56E+05 2.965E+05 4.524E-17 4.476E-17 4.476E-17 Top Fe-54 Mn-54 1.84E+06 2.723E+06 4.316E-15 Middle Fe-54 Mn-54 1.96E+06 2.900E+06 4.597E-15 Bottom Fe-54 Mn-54 1.90E+06 2.811 E+06 4.456E-1 5 4.456E-15 4.456E-15 Top Ni-58 Co-58 1.59E+07 4.495E+07 6.436E-1 5 Middle Ni-58 Co-58 1.68E+07 4.750E+07 6.800E-1 5 Bottom Ni-58 Co-58 1.69E+07 4.778E+07 6.840E-1 5 6.692E-15 6.692E-15 Top Co-59 Co-60 3.13E+07 5.950E+07 3.882E-12 Top Co-59 Co-60 3.54E+07 6.729E+07 4.390E-12 Middle Co-59 Co-60 3.35E+07 6.748E+07 4.403E-12 Middle Co-59 Co-60 2.75E+07 5.228E+07 3.411E-12 Bottom Co-59 Co-60 2.93E+07 5.570E+07 3.634E-1 2 Bottom Co-59 Co-60 3.41E+07 6.482E+07 4.229E-12 3.991 E-12 3.991E-12 Top Co-59 Cd Co-60 1.87E+07 3.555E+07 2.319E-1 2 Middle Co-59 Cd Co-60 1.79E+07 3.403E+07 2.220E-12 2.270E-12 2.270E-12 Bottom Co-59 Cd Co-60 U-238 Cs-137 6.61E+05 4.759E+06 3.125E-14 3.125E-14 2.467E-14 Np-237 Cs-1 37 5.82E+06 4.190E+07 2.673E-13 2.673E-13 2.646E-13 Notes: 1)Measured specific activities are indexed to a counting date of November 26, 2003.

2) The average 238U (n,f) reaction rate of 2.467E-14 includes a correction factor of 0.819 to account for plutonium build-in and an additional factor of 0.964 to account for photo-fission effects in the sensor.

3) The average 237Np (n,f) reaction rate of 2.646E-13 includes a correction factor of 0.990 to account for photo-fission effects in the sensor.

Appendix A

A-18 Table A-5 Comparison of Measured, Calculated, and Best Estimate Reaction Rates At The Surveillance Capsule Center Capsule U

-'ReactionRate' a '

.u.LN. ' ' ..........

Reaction:K Meaured, C walclte~d Estimate M/CMIB 6 3 Cu(t4a)60Co 5.80E-17 5.45E-17 5.65E-17 1.06 1.03 5Fe(n,p) 5sMn 6.34E-15 6.48E-15 6.50E-15 0.98 0.97 58Ni(n,p)58 Co 8.81E-15 9.18E-15 9.24E-15 0.96 0.95 23U(n,f)1Cs (Cd) 4.74E-14 3.66E-14 3.99E-14 1.29 1.19 2 37Np(nf)"37Cs (Cd) 4.53E-13 3.76E-13 4.49E-13 1.20 1.01 59Co(n,y)Co 6.41E-12 5.58E-12 6.38E-12 1.15 1.00 5 9Co(n,'y)6Co (Cd) 3.45E-12 3.90E-12 3.47E-12 0.89 1.00 Capsule W

-'; '"'2 . 2 RcactkioRat' "[' Jatom ': ;-

Reaction' Me'"sured Calcated IS Estimte " C  : E  ::

63Cu(n,a)W0Co 5.34E-17 4.20E-17 5.28E-17 1.27 1.01 s Fe(n,p)5sMn 5.63E-15 4.86E-15 5.54E-15 1.16 1.02 58Ni(n,p)"Co 7.67E-15 6.88E-15 7.70E-15 1.12 1.00 23sU(ni)O37Cs (Cd) 2.50E-14 2.73E-14 2.90E-14 0.92 0.86 2 37 Np(nj)O37Cs (Cd) 3.45E-13 2.85E-13 3.24E-13 1.21 1.06 59Co(ny)'Co 4.67E-12 3.80E-12 4.65E-12 1.23 1.01 59 Co(4,y)60Co (Cd) 2.57E-12 2.75E-12 2.58E-12 0.93 0.99 Capsule X

-__ .__ -_-____'""_ :R eaction R ate [rpsfatom l __ _ __ _ _____:" _';- _

.:.::: .. .. B st

'cio'n M:ieasured alcuate C

6 3Cu(n,a) 60Co 4.48E-07 4.07E-17 4.4lE-17 1.10 1.02 4Fe(n,p)5Mn 4.46E-15 4.65E-15 4.61 E-15 0.96 0.97 58 Ni(np)58Co 6.69E-15 6.55E-15 6.58E-15 1.02 1.02 238 U(n,) 1 37Cs (Cd) 1.47E-14 2.57E-14 2.50E-14 0.96 0.99 23 7Np(nj) 37 Cs (Cd) 2.65E-13 2.59E-13 2.60E-13 1.02 1.02

' 9Co(ny)6 0Co 3.99E-12 2.72E-12 3.98E-12 1.06 1.00 59Co(n,y)60Co (Cd) 2.27E-12 2.63E-12 2.28E-12 0.86 1.00 Appendix A

A-19 Table A-6 Comparison of Calculated and Best Estimate Exposure Rates at the Surveillance Capsule Center

- --. ; '4 (E> 1.0 MeY) [ncm sl :_. _:

Capsule D ,e, .. Uert Calculated Estirmat t) _________

U 1.075E+11 1.35e+11 7 1.15 W 8.821E+10 9.35E+10 7 1.06 X 8.164E+10 8.02E+10 7 0.98 Note: Calculated results are based on the synthesized transport calculations taken at the core rnidplane following the completion of each respective capsules irradiation period.

- In Ato Di'

- - _____________ ce nt R.te [dpa/sl :_; _;

.est I crtay Capsle ID Calclate Estmat (I 6) BE/

U 2.35E-10 2.78E-10 11 1.18 W 1.79E-10 1.96E-10 11 1.10 X 1.62E-10 1.62E-10 11 1.00 Note: Calculated results are based on the synthesized transport calculations taken at the core rnidplane following the completion of each respective capsules irradiation period.

Appendix A

A-20 Table A-7 Comparison of Measured/Calculated (MJC) Sensor Reaction Rate Ratios Including all Fast Neutron Threshold Reactions

.- -: - -: - -  :; C tio_ _ _

Reaction - pu U C s aX Casic X 6 3Cu(n,a)6 0 Co 1.06 1.27 1.10 54 Fe(np)5 4Mn 0.98 1.16 0.96 5BNi(n,p)58Co 0.96 1.12 1.02 238 U(np) 137CS (Cd) 1.29 0.92 0.92 23 7 Np(nrj 137Cs (Cd) 1.20 1.21 1.02 Average 1.10 1.14 1.01

% Standard Deviation 14 13 6 Note: The overall average MIC ratio for the set of 15 sensor measurements is 1.08 with an associated standard deviation of 11%.

Table A-8 Comparison of Best Estimnate/Calculated (BE/C) Exposure Rate Ratios C--apsule ID  ; E .  :> . i-s ............

U 1.13 1.15 W 1.05 1.06 X 0.97 0.98 Average 1.05 1.06

% Standard Deviation 8.1 8.2 Appendix A

A-21 Appendix A References A-1. Regulatory Guide RG-1. 190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence," U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, March 2001.

A-2. "Dosimetry Characterization; Purchase Order No. WGYP-7500 - Watts Bar Dosimetry; WATTS BAR; Energy Center Antech Ltd. Project No. 98-0027W", Antech Ltd., February 10, 1998.

A-3. "Analysis of Capsule W from the Tennessee Valley Authority Watts Bar Unit 1 Reactor Vessel Material Surveillance Program", BWXT Services, Inc., September 10, 2001.

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

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

Appendix A

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

• Specimen prefix 'WI:' denotes Lower Plate, Longitudinal Orientation

• Specimen prefix 'wT" denotes Lower Plate, Transverse Orientation

• Specimen prefix "WW" denotes Weld Material

• Specimen prefix "'VH" denotes Heat-Affected Zone material

• Load (I) is in units of lbs

• Time (1) is in units of mili seconds Appendix B

B-I 5000.00 4000.00 n 3000.00 as

-j 2000.00 1000.00-0.00 0.0o 1.00 2.00 3.00 4.00 6.00 6.00 rime-i (ms)

WL55, -750 F 5000.00 4000.00 Ad 3000.00' 0

2000.00 1000.00' oflo 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)

WL60, -500 F Appendix B

B-2 5000.00.I--

4000.00, i 3000.00.

-j 2000.00 1000 00' 0.00 0.00 1.00 2.00 3.00 4.00 6.00 6.00 Time-1 (ms)

WL54, -250 F 6000.001 ,

swooooo +:

4000.00'-

4-J 2000.00 :

1000.00t n0r' I r . --

1.00 2.00 3.00 5.00 6.00 Time-i (Ms)

WL50, 0F Appendix B

B.-3 5000.00.

4000.00 i n 3000.001l 2000.00 1000.00 '

0.00 000 1.00 2.00 3.00 4.00 5.00 6.00 rume-I (ms)

WL47, 250 F 5000.00 4000.00 X 3000.00 2000.00 1000.00 0.00 O0.0 1.00 2.00 3.00 4.00 5.00 6.00 lime-i (Ns WL52, 40 0 F Appendix B

B4 5000.00 4000 00 I 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)

WL57, 500 F 5000.00 4000.00-:

i 300000, 2000.00 i 1 000° t 0.00 . A-4 ^

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

WL51, 750 F Appendix B

3-5 5000.00i 4000.00

. 300000 0

-j 2000.00 1 000.00 t:

0.00.

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

WLS8, 1000 F 5000.004 4000.00 3000.00 t 2000.00 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Tme-I (ms)

WL53,1250 F Appendix B

B-6 5000.0O -

4000.00 f s 300000_

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

WL56, 1600 F 5000.00 +

4000.00

• 7 3000.00*

2000.00 1000.00 000 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)

WL59, 1800 F Appendix B

B-7 5000.00W 4000.00

. 300000 2000.00 100000V 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Thne-1 (ms)

WL49, 2250 F 5000.00 4 4000.00\

i 3000.00-2000.00\

1000.00 000 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)

WL46, 2500 F Appendix B

B-8 5000.00 4000.00

• 73000.00

-A 2000.00 1000.00 0.00

0. 00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 rms]

WL48, 250 0 F 5000.00 4000.00 i 3000.00 8

2000.00-1000.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 ime-i (ins)

WT60, 0F Appendix B

B-9 5000.0) 4000.00 3000.00 0

-J 2000.00 1000.00 0.00

a. 00 1.00 2.00 3.00 4.00 5.00 6.00 Tme-I (ms)

WT47, 50 0F 5000.00 4000.00

.7 3000.00 0

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

WT57, 1000 F Appendix B

B-10 5000.00 400000 i 3000.00 2000.00, 1000.00 000 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Tme-I (ms)

WT54,1250 F 5000.00 t 4000.00 3000.00 t 2000.00.

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

WT49, 1250 F Appendix B

B-11 5000.00 4000.001 1

' 300.000 2000.00 \

1000 001 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)

WT56, 1500 F 5000.00 +

.4.

400000 i7 Tf 3000.00t1 1.00 2.00 3.00 4.00 5.00 6.00 Tone-I (m)

WT58, 1750 F Appendix B

B-12 5000.00' 4000.00 30 .

2 000.00 0

0.00 1.0 2.00 3.00 4.00 5.00 6.00 Tine-1 (ms)

WNT59, 2000 F 5000.00.

4000 00 i 3000001 l 2000.00 1000.00 000

. -- - - l 0.00 1.00 2.00 3.00 4.00 5.00 6.00 WT4e6(ms)

WT46, 210°F Appendix B

B-13 5000.00 -

4000.00i

' 3000.00 \

2000.00 \

1000.001.

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

WT50, 2250 F 5000.00 +

4000.00+ ar

• 300000 tk

-j 2000.00.

1000W00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)

IAT51, 250 0F Appendix B

B-14 5000.00 -

4000.00 200000 1000.00' 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Thme-I (ms)

WT53, 2500 F 5000.00 4000.00 i 3U000.00+I 2000.00, 1(00000 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Tme-I (ms)

WT48, 2750 F Appendix B

B-15 500.OOji 4000.00 *t i 3000.00' 2000.00-1000_00 000 0 00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)

WT52, 2750 F 5000.00/

4000.00 6 3000.00 0

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

WT55, 3000 F Appendix B

B-16 5000.00 4000.00

. 3000.00 2000.00 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5 00 6.00 Time-I (ms)

WW55, -100F 5000.00-4000.00 t j 300000.

2000.00 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Tfme-I (s)

WW47, -750 F Appendix B

B-17 3000.001

-JWOWl I 2000.001 1000.001 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)

WW46, -500 F 5000.00 4000.00 3000.00~

-J2000.00{

1000.00 \

0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 rime-I (Ns)

WW48, -250 F Appendix B

B-18 5000.00 4000.00.

'3 3000.00' a

-J 2000.00 1000.00.

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

WW52, 10 0 F 5000,001 4000.00 in -

i 3000.00 i 2000.00-0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (Ms)

WW59, 250 F Appendix B

B-19 5000.00 4000.00 n 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)

IAW57, 50 0 F I

5000.00 4000.00 3000.00 2000.00-1000.00.

0.00 000 100 2.00 3.00 4.00 5.00 6.00 Time-I (Ns WW49, 750 F Appendix B

-. 1B-20 5000.001 4000.00 a 3000.00, 2000.00-1000.00 000 I 000 1.00 2.00 3.00 4.00 SflO 6.00 Time-1 (ms)

WW53, 100lF 5000.00 t

.0 4000.00 3000.00, \:

2000.00, 1000.00 '

0.00 0D00 1.00 2.00 3.00 4.00 5.00 6.00 rime-I (Ms)

WW750, 1250 F Appendix B

B-21

.01

-j 0.00 1.00 2.00 3.00 4.00 5O0 6.00 Tine-I (ms)

WT60, 1750 F a

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

WW56, 2000 F Appendix B

B-22 5000.00 4000.00 n 300000 0.00 Onlo 1.00 2.00 3.00 4.D0 5.00 6.00O lime-i (ins)

WW58, 2250 F 5000.00 l 4000.00-3000.00~

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

WW54, 2250 F Appendix B

-- . B-23 5000.001 4000.00 3000.00 2000.00 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 s.00 6.00 Time-I (ms)

"W51, 275°F 4000.00i

'7 3000.00*

2000.00-0.'°LAi ,'i^ ,

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

WH54, -750 F Appendix B

B-24 5000.00.

4000.00.

300000 2000.00 1000.00'L> l~ r t 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 rune-I (ms)

WH51, -50F 5000.00.

4000.00-i 3000.00 2000.00' 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 lme-I (as)

WH50, 0F Appendix B

B-25 5000.00i 4000.00'.G g 3000.00 2000.00 .

1000.00-0.00 '

O.A DO 1.00 2.00 3.00 4.00 5.00 6.00 Time- (ms)

WH56, 250 F 5000.00, 400000-

' 3000.00-9 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)

WH46, 50 0F Appendix B

B-26 5000.00 .

4000.004

'R 3000.00 2000.00 f 1000.00

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

WH47, 750 F 5000.00 -

4000.00-

3000.00\

2000.00 1000.00 000 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Tome-1 (ms)

WH55, 1000 F Appendix B

B-27 5000.00 4000.00 3000.00 2000. 00 1000.00 000 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I ems)

WH49, 125 0 F 5000.00

. c 4000.00 7 3000.00 0

2000.00 1000.00 0.00 000 1.00 2.0O 3.00 4.00 5.00 6.00 Time-1 (ms)

WH52, 1500 F Appendix B

B-28 5000.00 4000.00

{a3000.00 .

2000.00 X 1000.00 000 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)

WH48, 2000 F 5000.00 i 4000.00 a* 3000.00, 2000.00+

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

WH58, 2000 F Appendix B

B-29 5000.00j 4000.00 4 3000.00 2000.00 1000.00 0.00 0.00 1 no 2.00 3.00 4.00 5.00 6.00 lime-i (rm)

WH53, 2257F 5000.00 4000.00'f 7 30.00)00 2000.00 .

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

WH59, 250 0F Appendix B

B-30 5000.00..

4000.00' i n

3000 00+1\

2j 2000.00i 1000.00+1 0.00* a r- I - I l I I 0.00 1.00 2.00 3.00 4.00 SJO0 Time-1 (ms)

WH60, 2750 F 5000,00 .

4000.00+/-

e 3000.00 III 2000.00 ir 1tb0.0000 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)

WH57, 3000 F Appendix B

c-o APPENDIX C CHARPY V-NOTCH PLOTS FOR EACH CAPSULE USING SYMMETRIC HYPERBOLIC TANGENT CURVE-FITTING METHOD Appendix C

C-1 Contained in Table C-I are the upper shelf energy values used as input for the generation of the Charpy V-notch plots using CVGRAPH, Version 5.0.2. The definition for Upper Shelf Energy (USE) is given in ASTM El 85-82, Section 4.18, and reads as follows:

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

If there are specimens tested in set of three at each temperature Westinghouse reports the set having the highest average energy as the USE (usually unirradiated material). If the specimens were not tested in sets of three at each temperature Westinghouse reports the average of all 100% shear Charpy data as the USE. Hence, the USE values reported in Table C-1 and used to generate the Charpy V-notch curves were determined utilizing this methodology.

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

.... . ..... .;v.. ,.....................................

.Table C-iUpperv.;;......;v [Sf fEeg ausFxdi VRP M>Aaterial -Unirradiatedv Capsul asl asl Intermediate Shell 132 107 98 106 Forging 05 (Tangential)

Intermediate Shell 62 72 60 66 Forging 05 (Axial)

Weld Metal 131 143 112 134 (heat # 895075)

HAZ Material 89 79 77 80 Appendix C

UNIRRADIATED INTERMEDIATE SHELL 05 (TANGENTIAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/06/2004 11:07 AM Page 1 Coefficients of Curve 1 A = 67.1 B = 64.9 C = 109.84 TO = 14.2 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=132.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=-57.1 Deg F Temp @50 ft-lbs=-]5.4 Deg F Plant: WAITS BAR 1 Material: SA508CL2 Heat: 527536 Orientation: LT Capsule: UNIRR Fluence: 0.0 nlcm^2 300 250 In

.0

-. 200 9

0 0

U.

~ 150 z

> 100 50 0 4--

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 125.00 1.50 1I. 74 - 10.24

- 60. 00 41. 00 28.90 12. 10

- 60. 00 17.00 28. 90 - I1. 90

- 20. 00 46.00 47. 52 -. 52

-20. 00 61. 50 47.52 13.98

.00 46. 00 58.75 - 12. 75 15.00 7 1. 00 67.57 3.43

32. 00 73.00 77.52 - 4. 5 2

32. 00 96.00 77. 52 18.48 c-2

UNIRRADIATED INTERMEDIATE SHELL 05 (TANGENTIAL)

Page 2 Plant: WATTS BAR I Material: SA508CL2 Heat: 527536 Orientation: LT Capsule: UNERR Fluence: 0.0 n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 68.00 93.50 96.57 - 3.07

68. 00 90. 00 96. 57 - 6.57

95. 00 120.00 107.76 12.24

95. 00 79. 00 107.76 -28.76 95.00 92. 00 107.76 - 15.76 125.00 123.00 116.76 6. 24 125.00 144. 00 116.76 27.24 210.00 130.00 128.43 1.57 210.00 129.00 128.43 .57 Correlation Coefficient = .941 c-3

UNIRRADIATED INTE RMEDIATE SHELL 05 (TANGENTIAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/06/2004 02:08 PM Page 1 Coefficients of Curve I A = 40.26 B = 40.26 C = 87.82 TO = 2.05 D = O.OOE+O0 Equation is A + B * [Tanh((T-To)I(C+DT))j Upper Shelf L.E.=80.5 Lower Shelf L.E.=.0(Fixed)

Temp.@L.E. 35 rnils=-9.4 Deg F Plant: Watts Bar I Material: SA508CL,2 Heat: 527536 Orientation: LT Capsule: UNIRR Fluence: 0.0 n/cMA2 200 150 U,

50 E 00

-300 0 300 600 Temperature In Deg F Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential

- 125. 00 *00 4 .2 3 - 4.2 3

- 60. 00 2 5. 00 15.7 6 9. 24

- 60. 00 4 .00 1 5.7 6 1 1.7 6

- 20. 00 28. 00 3 0. 3 5 - 2.3 5

- 20. 00 40. 00 3 0. 3 5 9 .65

.00 3 6. 00 3 9. 3 1 - 3.3 1

15. 00 4 4. 00 4 6. 1 5 - 2. 1 5 3 2. 00 5 0. 00 5 3.4 7 - 3.4 7 3 2. 00 61. 00 5 3.4 7 7 .5 3 C-4

UNIRRADIATED INTERMEDIATE SHELL 05 (TANGENTIAL)

Page 2 Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: LT Capsule: UNIRR Fluence: 0.0 n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differcntial

68. 00 65.00 65. 85 - . 85 68.00 66.00 65. 85 .15 95.00 78.00 71.86 6. 14

95. 00 54.00 71.86 - 17. 86 95.00 69.00 71.86 -2. 86 125.00 80. 00 75. 89 4. I1 125.00 88.00 75. 89 12.11 210.00 77.00 79. 81 -2. 81 210. 00 79. 00 79. 81 - . 81 Correlation Coefficient = .958 C-5

UNIRRADIATED INTERMEDIATE SHELL 05 (TANGENTIAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/06/2004 02:00 PM Page 1 Coefficients of Curve I A = 50. B = 50. C = 94.86 TO = 34.78 D = O.OOE+00 Equation is A + B

• ITanh((T-To)f(C+DT))]

Temperature at 50% Shear = 34.8 Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: LT Capsule: UNIRR Fluence: 0.0 n/cmA2 125 100 --

0 75 CO oO 0

aU- 50 0

25 01 0 -

0

-300 -200 -100 0 100 200 300 400 500 600 Temperature In Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

- 1 2 5. 00 .00 3.33 -3. 33

- 60. 00 37.00 11. 94 25. 06

- 60. 00 9.00 11.94 -2. 94

-20. 00 20.00 23.96 -3. 96

- 20. 00 25.00 23.96 1.04

.00 14.00 32.45 - 18. 45

15. 00 38.00 3 9. 7 2 -1. 72

32. 00 56.00 48.53 7.47

32. 00 59.00 48.53 10.47 C-6

UNIRRADIATED INTERMEDIATE SHELL 05 (TANGENTIAL)

Page 2 Plant: Watts Bar 1 Material: SA508CL2 Heat: 527536 Orientation: LT Capsule: UNIRR Fluence: 0.0 n/cmk 2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 68.00 61. 00 66. 83 -5. 83

68. 00 66. 00 66. 83 - . 83 95.00 77. 00 78.07 -1. 07 95.00 70. 00 78. 07 - 8.07

95. 00 68.00 78.07 - 10.07 125. 00 100. 00 87.01 12.99 125.00 1 00. 00 87.01 12.99 210.00 100. 00 97.57 2.43 210.00 1 00. 00 97.57 2.43 Correlation Coefficient = .953 c-7

CAPSULE U INTERMEDIATE SHELL 05 (TANGENTIAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/06/2004 11:07 AM Page 1 Coefficients of Curve 2 A = 54.6 B = 52.4 C = 107.38 TO = 95.83 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT)))

Upper Shelf Energy=107.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=41.2 Deg F Temp,@50 ft-lbs=86.4 Deg F Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: LT Capsule: U Fluence: 0.0 n/cmA2 300 250 1-200

.0-a 0

0 LL 150 z

8 100 50 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 105. 00 8. 00 4. 63 3.37

- 25. 00 9. 00 12. 19 - 3. 19

.00 25. 00 17.26 7. 74 10.00 32.00 19.83 12. 17 25.00 28.00 24.31 3.69

50. 00 47. 00 33.50 13.50 70.00 38.00 42. 23 - 4. 2 3 75.00 13. 00 44.56 - 31.56 100. 00 60. 00 56. 64 3.36 C-8

CAPSULE U INTERMEDIATE SHELL 05 (TANGENTIAL)

Page 2 Plant: Watts Bar 1 Material: SA508CL2 Heat: 527536 Orientation: LT Capsule: U Fluence: 0.0 n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 1 25. 00 66. 00 68.50 -2. 50 150.00 85. 00 79.00 6. 00 200.00 101.00 93. 83 7. 17 250.00 111.00 101.38 9.62 I

300.00 102.00 104.71 -2. 71 350.00 112. 00 106. 09 5.91 Correlation Coefficient = .959 C-9

CAPSULE U INTERMEDIATE SHELL 05 (TANGENTIAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/06/2004 02:08 PM Page 1 Coefficients of Curve 2 A = 38.44 B = 38.44 C = 103.11 TO = 100.22 D = O.OOE+OO Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=76.9 Lower Shelf L.E.=.O(Fixed)

Temp. @L.E. 35 inils=9 1.0 Deg F Plant: Watts Bar I Material: SA508CL2 Heal: 527536 Orientation: LT Capsule: U Fluence: 0.0 ncmnA2 200 150

.__7 _-____

100 5

50 0 00 13/

0)

,c, 1 '.

01 1

-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input LE. Computed LE. Differential

- 105. 00 2.00 1.41 .59

-25. 00 4.00 6.2 3 -2. 23

.00 15.00 9.63 5.37 10.00 17.00 11.38 5.62

25. 00 19.00 14.50 4.5 0

50. 00 29.00 21. 07 7.93

70. 00 25. 00 27.49 -2. 4 9 75.00 6. 00 29. 22 - 23. 22 1 00. 00 44. 00 38.36 5.64 C.1 0

CAPSULE U INTERMEDIATE SHELL 05 (TANGENTIAL)

Page 2 Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: LT Capsule: U Fluence: 0.0 n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential 125. 00 49. 00 47.50 1.50 150. 00 57. 00 55.68 1. 32 200. 00 72. 00 67. 18 4. 82 250.00 76. 00 72. 89 3. 11 300. 00 73.00 75.31 -2.31 350.00 72. 00 76.28 -4.28 Correlation Coefficient = .962 C-11

CAPSULE U INTERMEDIATE SHELL 05 (TANGENTIAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on O0/0612004 02:00 PM Page I Coefficients of Curve 2 A = 50. B = 50. C = 63.23 TO = 126.56 D = 0.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = 126.6 Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: LT Capsule: U Fluence: 0.0 n/cm^2 125 100 75 C0 a,

Q LE a' 50 0.

25 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature In Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

- 105. 00 2.00 .07 I .9 3

- 25. 00 5.00 .82 4. 18

.00 10. 00 1.79 8.21 10.00 15.00 2.44 12.56

25. 00 15.00 3. 87 11.13

50. 00 20.00 8. 15 11.85 70.00 20. 00 14.32 5.68

75. 00 5.00 16. 37 -11. 37 1 00. 00 25. 00 30. 15 -5. 15 C-12

CAPSULE U INTERMEDIATE SHELL 05 (TANGENTIAL)

Page 2 Plant: Watts Bar 1 Material: SA508CL2 Heat: 527536 Orientation: LT Capsule: U Fluence: 0.0 n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 125. 00 40.00 48.77 -8. 77 150.00 75. 00 67. 73 7.27 200. 00 100. 00 91. 08 8.92 250. 00 100. 00 98.02 1.98 300. 00 100. 00 99. 59 .41 350. 00 100. 00 99. 91 .09 Correlation Coefficient = .984 C-13

CAPSULE W INTERMEDIATE SHELL 05 (TANGENTIAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/06/2004 11:07 AM Page 1 Coefficients of Curve 3 A = 50.1 B = 47.9 C = 91.41 TO = 95.16 D = O.OOE+0O Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=98.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=54.3 Deg F Temp@50 ft-lbs=95.0 Deg F Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: LT Capsule: W Fluence: n/cmA2 300 250 0

• - 200 0

0 L

t 150 0

z 8 100 ........ .... ...,.............° ......................

50 A

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

40. 00 15.00 24. 26 -9.26 50.00 22. 00 28. 19 -6. 19

60. 00 37. 50 32.53 4.97

60. 00 49. 50 32.53 16.97

70. 00 39.50 37.24 2.26 1 00. 00 47.50 52. 63 -5. 13 125.00 57.00 65. 20 - 8.20 140. 00 70.50 71. 88 -1. 38 150. 00 76.50 75. 82 .68 C-14

CAPSULE W INTERMEDIATE SHELL 05 (TANGENTIAL)

Page 2 Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: LT Capsule: W Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 200. 00 97.00 89.22 7.78 250. 00 102.50 94. 87 7. 6 3 350. 00 93.50 97.64 -4. 14 Correlation Cocefficient = .964 C-15

CAPSULE W INTERMEDIATE SHELL 05 (TANGENTIAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/06/2004 02:08 PM Page 1 Coefficients of Curve 3 A = 41.32 B = 41.32 C = 99.72 TO = 99.66 D = O.OOE+OO Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=82.6 Lower Shelf L.E.=.O(Fixed)

Temp. @L.E. 35 mils=84.3 Deg F Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: LT Capsule: W Fluence: n/cmA2 200 150

.2 8 100 a)

V-50 0 4-

-300 0 300 600 Temperature In Deg F Charpy V-Notch Data Temperature Input L.E. Computed L.E Differential 40.00 13. 00 19. 18 -6. 18

50. 00 17. 00 22.29 -5. 29

60. 00 30. 00 25. 70 4.30

60. 00 37.00 25.70 1 1.30

70. 00 32. 00 29. 38 2.62 1 00. 00 36. 00 41.46 -5. 46 125. 00 48. 00 51. 60 -3. 60 140. 00 53.00 57. 18 -4. 18 150. 00 65. 00 60. 58 4.42 C-16

CAPSULE W INTERMEDIATE SHELL 05 (TANGENTIAL)

Page 2 Plant: Watts Bar 1 Material: SA508CL2 Heat: 527536 Orientation: LT Capsule: W Fluence: n/cmr2 Charpy V-Notch Data Temperature Input LE. Computed LE. Differential 200. 00 76. 00 72. 90 3. 10 250. 00 82.00 78.78 3.22 350. 00 78. 00 82. 11 -4. 11 Correlation Coefficient = .972 C-17

CAPSULE W INTERMEDIATE SHELL 05 (TANGENTIAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Pnnted on 02/06/2004 02:01 PM Page I Coefficients of Curve 3 A = 50. B = 50. C = 75.89 TO = 102.25 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = 102.3 Plant: Watts Bar I Material: SA508CL2 Heat: 527536 III Orientation: LT Capsule: W Fluence: n/cm^2 125

. Q >

100 IU 75 CO) 0~ 50 25 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature In Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

40. 00 10. 00 1 6. 24 - 6.24 50.00 20. 00 20. 15 - . 15

60. 00 25. 00 24. 73 .27

60. 00 40.00 24. 73 15. 27

70. 00 3 0. 00 29. 95 .05 100. 00 40. 00 48.52 - 8.52 125.00 60. 00 64.56 -4. 56 140.00 70.00 73.01 - 3.01 150.00 85. 00 77. 88 7. 12 C-18

CAPSULE W INTERMEDIATE SHELL 05 (TANGENTIAL)

Page 2 Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: LT Capsule: W Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 200. 00 100. 00 92. 93 7. 07 250. 00 1 00. 00 98. 00 2. 00 350. 00 1 00. 00 99. 85 .15 Correlation Coefficient = .981 C-19

CAPSULE X INTERMEDIATE SHELL 05 (TANGENTIAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/06/2004 11:07 AM Page 1 Coefficients of Curve 4 A = 54.1 B = 51.9 C = 117.15 TO = 96.42 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=1 06.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@?30 fh-lbs=37.6 Deg F Temp@50 ft-lbs=87.2 Deg F Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: LT Capsule: X Fluence: n/cmA2 300 250 aA200 0

0 IL 150 0

C z

> 100 s0 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature In Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

-75. 00 10. 00 7.48 2.52

-50. 00 8.00 10. 08 -2. 08

-25. 00 22.00 13. 80 8.20

.00 25.00 18.98 6. 02

25. 00 22. 00 25. 87 -3. 87 40.00 29. 00 30. 87 - 1. 87

50. 00 42. 00 34.55 7.45 75.00 3 1. 00 44.71 - 13.71 1 00. 00 63. 00 55.69 7. 31 C-20

CAPSULE X INTERMEDIATE SHELL 05 (TANGENTIAL)

Page 2 Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: LT Capsule: X Fluence: nIcmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 125. 00 64. 00 66.52 - 2.52 160. 00 75. 00 79.79 -4. 79 1 80. 00 79. 00 85.91 -6. 91 225. 00 1 07. 00 95.60 I 1. 40 250. 00 101. 00 98. 97 2. 03 250. 00 11 1. 00 98. 97 12. 03 Correlation Coefficient = .979 C-21

CAPSULE X INTERMEDIATE SHELL 05 (TANGENTIAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/06/2004 02:08 PM Page 1 Coefficients of Curve 4 A = 41.57 B = 41.57 C = 138.42 TO = 128.58 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=83.1 Lower Shelf L.E.=.0(Fixed)

Temp. @L.E. 35 mils=106.6 Deg F Plant: Watts Bar 1 Material: SA508CL2 Heat: 527536 Orientation: LT Capsule: X Fluence: n/cmA2 200 150 E

e

.0 c

E 100 . .....

.4.aa 50 z or @w 4 25 Al*S

^A

_,<,-~~ .-d^ . . ~_

0

-300 0 300 600 Temperature In Deg F Charpy V-Notch Data Temperature Input LE. Computed L.E. Differential

-75. 00 4.00 4. 17 - . 17

-50. 00 .00 5.85 -5. 85

- 25. 00 14. 00 8. 15 5. 85

.00 13. 00 1 1. 22 1.78

25. 00 11. 00 15.21 - 4. 2 1

40. 00 16.00 18.09 -2. 09

50. 00 25. 00 20.22 4. 78 75.00 19. 00 26.24 - 7. 24 100. 00 40. 00 33. 10 6.90 C-22

CAPSULE X INTERMEDIATE SHELL 05 (TANGENTIAL)

Page 2 Plant: Watts Bar 1 Material: SA508CL2 Heat: 527536 Orientation: LT Capsule: X Fluence: n/cm'^2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential 125. 00 44.00 40.49 3.51 160. 00 48.00 50. 84 -2. 84 180.00 5 1. 00 56.33 -5. 33 225. 00 72. 00 66. 60 5. 4 0 250.00 69. 00 70. 87 - 1. 8 7 250.00 71.00 70. 87 .13 Correlation Coefficient = .983 C-23

CAPSULE X INTERMEDIATE SHELL 05 (TANGENTIAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/06/2004 02:01 PM Page 1 Coefficients of Curve 4 A = 50. B = 50. C = 78.4 TO = 116.58 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))l Temperature at 50% Shear = 116.6 Plant: Watts Bar 1 Material: SA508CL2 Heat: 527536 Orientation: LT Capsule: X Fluence: n/cmA2 125 100 L-s 75 co IV Q1)

C, a- 50 25 o 4-

-300 -200 -100 0 100 200 300 400 500 600 Temperature In Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

-75. 00 2.00 .75 1. 25

-50. 00 2.00 1.41 .59

-25. 00 5. 00 2. 63 2.37

.00 5. 00 4. 86 .14

25. 00 10.00 8. 82 1. 18 40.00 10. 00 12,. 42 -2. 42

50. 00 20. 00 15.47 4. 5 3 75.00 20.00 25. 72 -5. 72 100. 00 40. 00 39. 58 .42 C-24

CAPSULE X INTERMEDIATE SHELL 05 (TANGENTIAL)

Page 2 Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: LT Capsule: X Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 125. 00 60. 00 55.35 4. 65 160. 00 75.00 75. 17 -. 17 180.00 75.00 83.45 -8.45 225. 00 1 00. 00 94. 08 5.92 250. 00 100.00 96.78 3.22 250.00 100.00 96.78 3.22 Correlation Coefficient = .995 C-25

UNIRRADIATED INTERMEDIATE SHELL 05 (AXIAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 09:56 AM Page I Coefficients of Curve I A = 32.1 B = 29.9 C = 90.57 TO = 51.57 D = 0.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=62.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=45.2 Deg F Temp@50 ft-lbs=1 14.2 Deg F Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: TL Capsule: UNIRR Fluence: 0.0 n/cmA2 300 -_

250 -_

, 200 -_

8 0

0 U-

150 -

z t 100 -_

50 ._

0-_

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 100.00 5.5 0 4.23 1. 2 7 100.00 5.00 4.23 .7 7 100. 00 6.50 4.23 2. 27

-35. 00 13.00 9. 90 3. 10

. 00 17.00 16. 70 . 30

.00 17.00 16. 70 .30 38.00 24. 50 27.65 -3. 15

38. 00 30.00 27. 65 2.35 38.00 24. 00 27. 65 -3. 65 C-26

UNIRRADIATED INTERMEDIATE SHELL 05 (AXIAL)

Page 2 Plant: Watts Bar 1 Material: SA508CL2 Heat: 527536 Orientation: TL Capsule: UNIRR Fluence: 0.0 n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

60. 00 41.00 34. 88 6. 12

60. 00 33. 00 34. 88 -1.88 75.00 34. 00 39. 67 -5. 67 125.00 57. 00 52. 13 4.87 210.00 62.00 60.24 1.76 210.00 62.00 60. 24 1.76 210.00 60. 00 60. 24 - .24 300.00 60. 00 61.75 -1.75 300.00 64. 00 61.75 2.25 Correlation Coefficient = .991 c-27

UNIRRADIATED INTERMEDIATE SHELL 05 (AXIAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 10:42 AM Page 1 Coefficients of Curve 1 A = 29.17 B = 29.17 C = 101.37 TO = 63.98 D = O.OOE+0O Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=58.3 Lower Shelf L.E.=.0(Fixed)

Temp.@L.E. 35 mils=84.6 Deg F Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: TL Capsule: UNIRR Fluence: n/cmA2 200 150 E

0 100

• 50

-300 0 300 600 Temperature In Deg F Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential

- 100. 00 2. 00 2.21 - .21

- 100. 00 1. 00 2.21 - 1. 2 1

-100. 00 3.00 2.21 .79

- 35. 00 13. 00 7.25 5.75

.00 11. 00 12. 87 - I . 87

.00 10.00 12. 87 -2. 87 38.00 21.00 21. 85 -. 85

38. 00 21. 00 21. 85 -. 85 38.00 20. 00 21.85 - 1. 85 C-28

UNIRRADIATED INTERMEDIATE SHELL 05 (AXIAL)

Page 2 Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: TL Capsule: UNIRR Fluence: nlcmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential

60. 00 40.00 28. 03 11. 97

60. 00 30.00 28. 03 1.97

75. 00 22.00 32. 33 - 10. 33 125. 00 44. 00 44. 88 - .88 210.00 58.00 55. 24 2.76 210. 00 59.00 55.24 3.76 210.00 55. 00 55.24 -. 24 300. 00 55.00 57. 79 -2.79 300.00 56.00 57.79 - 1. 79 Correlation Coefficient = .977 c-29

UNIRRADIATED INTERMEDIATE SHELL PLATE 05 (AXIAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 10:26 AM Page 1 Coefficients of Curve 1 A = 50. B = 50. C = 95.2 TO = 54.88 D =0.0E+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = 54.9 Plant: Watts Bar I Material: SA50CL2 Heat: 527536 Orientation: TL Capsule: UNIRR Fluence: n/cmin2 125 100 I-(U a) 75 to, 4.'

0~

50 25 0 +-

-300 -200 -100 0 100 200 300 400 500 600 Temperature In Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

- 100.00 2.00 3.72 -1. 72

- 100. 00 2. 00 3.72 -1.72

- 100. 00 2.00 3.72 - 1. 72

-35. 00 15.00 13. 14 1. 86

.00 30.00 23. 99 6.01

.00 2B. 00 23.99 4. 01 38.00 45. 00 41. 22 3. 7 8 38.00 43. 00 41.22 1.78

38. 00 40. 00 41. 22 - 1. 22 C-30

UNIRRADIATED INTERMEDIATE SHELL PLATE 05 (AXIAL)

Page 2 Plant: Watts Bar 1 Material: SA508CL2 Heat: 527536 Orientation: TL Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

60. 00 50.00 52. 68 -2. 68

60. 00 43.00 52.68 -9. 68

75. 00 54. 00 60. 41 - 6. 4 1 125.00 90. 00 81.35 8. 65 210. 00 100.00 96.30 3. 70 210.00 1 00. 00 96. 30 3.70 210.00 100. 00 96.30 3.70 300. 00 100. 00 99.42 . 58 300. 00 1 00. 00 99.42 .58 Correlation Coefficient = .993 C-31

CAPSULE U INTERMEDIATE SHELL 05 (AXIAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 09:56 AM Page 1 Coefficients of Curve 2 A = 37.1 B = 34.9 C = 125.83 TO = 99.81 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=72.0(Fixed) Lower Shelf Encrgy=2.2(Fixed)

Temp@30 ft-lbs=73.9 Deg F Temp@50 ft-lbs=148.7 Deg F Plant: Watts Bar 1 Material: SA508CL2 Heat: 527536 Orientation: TL Capsule: U Fluence: 0.0 n/cmA2 300 250 u) a 200 0

0 lU 50 C) 8 100 z

> 100.

50 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature In Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 100. 00 4. 00 5.00 -1. 00

- 20. 00 8.00 11. 25 -3. 25 10.00 9.00 15.71 -6. 71

50. 00 23.00 23. 96 -. 96

75. 00 33.00 30. 31 2.69 75.00 56.00 30.31 25.69 1 00. 00 30. 00 37. 15 -7. 15 125. 00 38. 00 43. 99 -5. 99 150.00 38. 00 50. 33 - 12.33 C-32

CAPSULE U INTERMEDIATE SHELL 05 (AXIAL)

Page 2 Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: TL Capsule: U Fluence: 0.0 n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 175.00 47.00 55.78 - 8. 7 8 225. 00 80.00 63.60 16. 40 250.00 71. 00 66. 13 4.87 300.00 73. 00 69.22 3.78 350.00 76.00 70.72 5.28 400. 00 61.00 71.41 -O. 41 Correlation Coefficient = .917 C-33

CAPSULE U INTERMEDIATE SHELL 05 (AXIAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 10:43 AM Page 1 Coefficients of Curve 2 A = 28.65 B = 28.65 C = 111.9 TO = 88.09 D = 0.OOE+00 Equation is A + B

• ITanh((T-To)/(C+DT))]

Upper Shelf L.E.=57.3 Lower Shelf L.E.=.0(Fixed)

Temp.@L.E. 35 mils=1 13.4 Deg P Plant: Watts Bar 1 Material: SA508CL2 Heat: 527536 Orientation: TL Capsule: U Fluence: n/cmA2 200 150

._2 100 a,

50 0 o-

-300 0 300 600 Temperature In Deg F Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential

- 100. 00 2.00 1.92 . 08

- 20. 00 2.00 7. 25 -5. 25

10. 00 4.00 1 1. 3 7 - 7. 3 7

50. 00 18.00 19.26 - 1.26 75.00 25.00 25. 32 - .32 75.00 49. 00 25. 32 23.68 1 00. 00 26. 00 31. 69 - 5.69 1 25. 00 33.00 37.77 -4. 77 150.00 34. 00 43.06 -9. 06 c-34

CAPSULE U INTERMEDIATE SHELL 05 (AXIAL)

Page 2 Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: TL Capsule: U Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential 175.00 4 6. 00 47.30 - 1.30 225.00 60. 00 52.74 7.26 250.00 56.00 54. 30 1 .7 0 300. 00 56. 00 56.03 -. 03 350. 00 60. 00 56. 78 3.22 400. 00 52. 00 57.09 -5. 09 Correlation Coefficient = .929 C-35

CAPSULE U INTERMEDIATE SHELL 05 (AXIAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 10:26 AM Page 1 Coefficients of Curve 2 A = 50. B = 50. C = 108.6 TO = 144.29 D = O.OOE+00 Equation is A + B * (Tanh((T-To)/(C+DT))l Temperature at 50% Shear = 144.3 Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: TL Capsule: U Fluence: n/cmA2 125 100 c-75 15

0. 50 25 0 I-

-300 -200 -100 0 100 200 300 400 500 600 Temperature In Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

- 100.00 2.00 1. 10 .90

- 20. 00 5.00 4. 63 .37

10. 00 10.00 7.78 2.22

50. 00 20. 00 14.98 5.02

75. 00 20.00 21. 82 - 1.82

75. 00 60. 00 21. 82 38. 18 100.00 20. 00 30. 67 - 10.67 125. 00 30.00 41.21 - I 1.21 150. 00 30.00 52. 63 - 22. 63 C-36

CAPSULE U INTERMEDIATE SHELL 05 (AXIAL)

Page 2 Plant: Watts Bar 1 Material: SA508CL2 Heat: 527536 Orientation: TL Capsule: U Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 175. 00 60. 00 63.77 -3. 77 225. 00 1 00. 00 81. 55 18.45 250. 00 100. 00 87. 51 12.49 300. 00 1 00. 00 94. 62 5.38 350. 00 1 00. 00 97.79 2.21 400. 00 100. 00 99. 11 .89 Correlation Coefficient = .937 C-37

CAPSULE X INTERMEDIATE SHELL 05 (AXIAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 09:56 AM Page 1 Coefficients of Curve 4 A = 34.1 B = 31.9 C = 84.5 TO = 172. D = 0.OOE+00 Equation is A + B * [Tanh((T-1o)/(C+DT))]

Upper Shelf Energy=66.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=161.1 Deg F Temp@50 ft-lbs=218.3 Deg F Plant: Watts Bar 1 Material: SA508CL2 Heat: 527536 Orientation: TL Capsule: X Fluence: n/cm^2 300 250 u,

Q 200 1

0 0

IL 150 aD 0

z

>0 100 50 O k- -r- I-- - - ----- - --- - l l

-300 -200 -1 00 0 100 200 300 400 500 600 Temperature In Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

. 00 4.00 3.27 .73

50. 00 12.00 5.57 6.43 1 00. 00 13.00 12. 02 .98 125.00 28.00 17.99 10.01 125. 00 16.00 17.99 -1. 99 150. 00 27. 00 25.98 1.02 175.00 30. 00 35.23 - 5.23 200. 00 36. 00 44.30 -8. 30 210.00 38.00 47. 55 - 9.55 C-38

CAPSULE X INTERMEDIATE SHELL 05 (AXIAL)

Page 2 Plant: Watts Bar 1 Material: SA508CL2 Heat: 527536 Orientation: TL Capsule: X Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 225.00 52. 00 51.84 .16 250. 00 66. 00 57.30 8.70 250.00 64.00 57.30 6. 70 275.00 73. 00 60. 87 12. 13 275. 00 63. 00 60. 87 2. 13 300. 00 64. 00 63.06 .94 Correlation Coefficient = .961 c-39

CAPSULE X INTERMEDIATE 05 (AXIAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 10:43 AM Page I Coefficients of Curve 4 A = 34.07 B = 34.07 C = 129.63 TO = 197.99 D = O.OOE+0O Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=68.1 Lower Shelf L.E.=.0(Fixed)

Temp.@L.E. 35 mils=201.6 Deg F Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: TL Capsule: X Fluence: n/cmA2 200 150 --- 4-n to 0

2 100 _ ..

0 50 Ae I

4.1A, gi A ,

0

-300 0 300 600 Temperature In Deg F Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential

. 00 . 00 3. 07 -3. 07 50.00 7.00 6. 30 .70 100. 00 13.00 12.31 .69 125. 00 22. 00 16. 69 5.31 125. 00 14.00 16. 69 -2. 69 150. 00 24.00 22. 00 2.00 17 5. 00 26. 00 28.09 -2. 09 200. 00 30.00 34.60 -4. 60 210. 00 33.00 37.22 -4. 22 C-40

CAPSULE X INTERMEDIATE 05 (AXIAL)

Page 2 Plant: Watts Bar 1 Material: SA508CL2 Heat: 527536 Orientation: TL Capsule: X Fluence: nLcmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential 225. 00 44.00 41. 07 2.93 250.00 SO. 00 47. 05 2.95 250.00 52. 00 47.05 4. 95 275. 00 53. 00 52.22 .78 275. 00 49. 00 52.22 -3.22 300. 00 55. 00 56.44 -1. 44 Correlation Coefficient = .984 C-41

CAPSULE W INTERMEDIATE SHELL 05 (AXIAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 10:26 AM Page 1 Coefficients of Curve 3 A = 50. B = 50. C = 66.93 TO = 149.07 D = O.OOE+00 Equation is A + B

• ITanh((T-To)/(C+DT))]

Temperature at 50% Shear = 149.1 Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: TL Capsule: W Fluence: n/cmr2 125 100 I..

C) 75 CO) ' .' 0_ _

2 50 0.

25 _, ., A, C 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature In Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 40.00 . 00 3.70 -3. 70 70.00 15. 00 8.60 6.40

70. 00 15. 00 8.60 6.40 100.00 25. 00 18.75 6.25 125.00 35.00 32.75 2.25 150. 00 40. 00 50.69 - 10.69 1 65. 00 55.00 61. 68 - 6. 6 8 175.00 55. 00 68. 45 - 13.45 1 85. 00 85. 00 74.53 10. 47 C-42

CAPSULE W INTERMEDIATE SHELL 05 (AXIAL)

Page 2 Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: TL Capsule: W Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 200. 00 I 00. 00 82.08 17. 92 250.00 100. 00 95.33 4. 67 350. 00 100.00 99.75 .25 Correlation Coefficient = .969 c-43

CAPSULE W INTERMEDIATE SHELL 05 CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 09:56 AM Page 1 Coefficients of Curve 3 A = 31.1 B = 28.9 C = 99.98 TO = 127.92 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=60.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=124.2 Deg F Temp@50 ft-lbs=206.2 Deg F Plant: Watts Bar I Material: SA508CL2 Hcat: 527536 Orientation: TL Capsule: W Fluence: n/cmA2 300 250

, 200 0

0 L-150 LUJ z

> 100 50 o +-

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computcd CVN Differential

40. 00 10.00 10. 69 - . 69

70. 00 18.50 16.01 2. 49 70.00 20.50 16.01 4.49 100. 00 23.50 23.23 .27 125. 00 30.50 30.26 .24 150.00 29.50 37. 38 7. 88 165.00 39.00 41.35 2. 35 175.00 39.50 43.78 4. 28 185. 00 48.50 46.01 2.49 C-44

CAPSULE W INTERMEDIATE SHELL 05 Page 2 Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: TL Capsule: W Fluence: n/CMA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 200. 00 54.50 48. 95 5. 55 250. 00 63. 50 55.37 8. 13 350. 00 62.50 59. 33 3. 17 Correlation Coefficient = .969 C-45

CAPSULE W INTERMEDIATE SHELL 05 (AXIAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 10:43 AM Page I Coefficients of Curve 3 A = 30.92 B = 30.92 C = 108.86 TO = 123.59 D = O.OOE+0O Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=61.8 Lower Shelf L.E.=.0(Fixed)

Temp. @L.E. 35 mnils=13 8.1 Deg F Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: TL Capsule: W Fluence: n/cmA2 200 150

.2 a 100 c .. ...........

50 1010,Y" P.,".0 n I4 ... V - -- 4 --*---.-----------*-- i . . .

-300 0 300 600 Temperature In Deg F Charpy V-Notch Data Tcmperature Input L.E. Computed L.E. Differential 40.00 10.00 10.96 -. 96 70.00 70.00 1 00. 00

20. 00 19.00 25.00

16. 82

16. 82

24. 32

-.6968 2.18 8

125.00 30.00 31.32 1.32 150.00 32. 00 38.28 -6.2 8 165. 00 41.00 42. 15 175.00 42. 00 44. 53 -2.53 185.00 49. 00 46.72 2.28 C-46

CAPSULE W INTERMEDIATE SHELL 05 (AXIAL)

Page 2 Plant: Watts Bar 1 Material: SA508CL2 Heat: 527536 Orientation: TL Capsule: W Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential 200. 00 53. 00 49. 65 3.35 250.00 64.00 56.32 7.68 350.00 55.00 60. 89 -5. 89 Correlation Coefficient = .971 C-47

CAPSULE X INTERMEDIATE SHELL 05 (AXIAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 10:26 AM Page I Coefficients of Curve 4 A = 50. B = 50. C = 63.84 TO = 187.25 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = 187.3 Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: TL Capsule: X Fluence: n/cmA2 125 100 75 M

L.

E 1-150 CO 25 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature In Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Perccnt Shear Differential

. 00 2.00 .28 1.72

50. 00 5.00 1.34 3.66 100.00 15.00 6. 10 8.90 125. 00 20. 00 12.45 7.55 125.00 20. 00 12. 45 7. 55 150.00 25. 00 23.74 1.26 175. 00 40. 00 40.52 - .52 200. 00 40. 00 59. 86 - 19. 86 210.00 60. 00 67. 10 -7. 10 C-48

CAPSULE X INTERMEDIATE SHELL 05 (AXIAL)

Page 2 Plant: Watts Bar 1 Material: SA5S08CL2 Heat: 527536 Orientation: TL Capsule: X Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 225. 00 80.00 76.54 3.46 250.00 1 00. 00 87. 72 12.28 250. 00 I 00. 00 87. 72 12.28 275. 00 100.00 93.99 6. 01 275. 00 100. 00 93.99 6. 01 300. 00 1 00. 00 97. 16 2. 84 Correlation Coefficient = .979 C-49

UNIRRADIATED SURVEILLANCE PROGRAM WELD CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 01:38 PM Page I Coefficients of Curve I A = 66.6 B = 64.4 C = 66.29 TO = 11.54 D = O.O0E+0O Equation is A + B * (Tanh((T-To)/(C+DT))]

Upper Shelf Energy=l 31 .0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=-31.2 Deg F Temnp@50 ft-lbs=-5.9 Deg F Plant: Watts ar I Material: N/A Heat: 895075 FLUX Orientation: NA Capsule: UNIRR Fluence: n/cmA2 300 250 In

, 200 0

0 LL L150 a) 0 0 c______

w z 0191

> 100 50 0

0

-3100 -200 -1 00 0 100 200 300 400 500 600 Temperature In Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 125. 00 6.00 4.26 1.74

- 125.00 5.00 4.26

-75.00 9.50 1 1. 0 1 - 1.51

-40. 00 20.00 24. 66 -4.66

-40.00 43.00 24.66 18. 34

-20. 00 30. 00 38.08 - 8.08

-7.00 50. 00 49. 04 .96

-7. 00 54.00 49.04 4.96

-7.00 55.00 49. 04 5.96 C-SO

UNIRRADIATED SURVEILLANCE PROGRAM WELD Page 2 Plant: Watts Bar 1 Material: N/A Heat: 895075 FLUX Orientation: NA Capsule: UNJIR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

32. 00 7 1. 00 85. 87 -14. 87 32.00 62.00 85. 87 - 23.87

50. 00 117. 00 100.26 16.74 68.00 I 1 7.00 111. 16 5.84 73.00 13 1. 00 113.56 17.44 I I 0. 00 123.50 124. 72 - 1. 22 210.00 130.00 130. 68 - . 68 210.00 127.00 130.68 -3. 68 275. 00 142.00 130.95 11. 05 Correlation Coefficient = .975 C-51

UNIRRADIATED SURVIELLANCE PROGRAM WELD CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 02:09 PM Page 1 Coefficients of Curve 1 A = 43.89 1B = 43.89 C = 65.14 TO = 3.4 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=87.8 Lower Shelf L.E.=.0(Fixed)

Temp.@L.E. 35 mils-9.9 Deg F Plant: Watts Bar 1 Material: N/A Heat: 895075 FLUX Orientation: NA Capsule: UNIRR Fluence: n/cMA2 200 150 0

100 50 0

-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input LE. Computed LE. Differential

- 1 25. 00 1.00 1.67 -. 67

- 125.00 1.00 1.67 -. 67

-75. 00 4.00 7. 25 -3. 25

-40. 00 13.00 18.32 -5. 32

-40. 00 32. 00 18.32 13.68

-20. 00 26.00 28. 77 -2. 77

-7. 00 37. 00 36. 94 . 06

-7. 00 37.00 36.94 .06

-7. 00 41.00 36. 94 4. 06 C-52

UNIRRADIATED SURVIELLANCE PROGRAM WELD Page 2 Plant: Watts Bar I Material: N/A Heat: 895075 FLUX Orientation: NA Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential 32.00 53. 00 62.01 - 9. 0 1

32. 00 48.00 62. 01 - 14. 01 50.00 84.00 70. 84 13. 16 68.00 80. 00 77. 16 2.84 73.00 90. 00 78. 52 11.48 110. 00 80. 00 84.58 -4.58 210.00 89.00 87.63 1.37 210. 00 77. 00 87. 63 -o. 63 275. 00 92. 00 87.76 4.24 Correlation Coefficient = .972 C-53 .

UNIRRADIATED SURVIELLANCE PROGRAM WELD CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 01:53 PM Page 1 Coefficients of Curve I A = 50. B = 50. C = 91.87 TO = -1.28 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = -1.2 Plant: Watts Bar I Material: N/A Heat: 895075 FLUX Orientation: NA Capsule: UNIRR Fluence: n/cmA2 125 100 L-75 w

L.

0~ 50 25 0 4-

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

- 125.00 5.00 6. 34 - 1. 34

-125.00 5.00 6. 34 - 1. 34

-75. 00 20. 00 16. 73 3.27

-40. 00 30.00 30. 09 -. 09

-40. 00 41.00 30.09 10.91

• - 20.00 41.00 39. 95 1. 05

-7.00 46.00 46. 89 -. 89

-7. 00 40. 00 46. 89 -6. 89

-7.00 46. 00 46. 89 -. 89 C-54

UNIRRADIATED SURVIELLANCE PROGRAM WELD Page 2 Plant: Watts Bar I Material: N/A Heat: 895075 FLUX Orientation: NA Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

32. 00 61. 00 67. 36 - 6. 36

32. 00 57. 00 67.36 -o. 36

50. 00 78. 00 75.33 2. 67 68.00 82.00 81.88 .12 73.00 1 00. 00 83.44 1 6. 5 6 1 10.00 95.00 91. 85 3. 15 210.00 1 00. 00 99.00 1.00 210.00 95. 00 99. 00 -4. 00 275. 00 1 00. 00 99.76 .24 Correlation Coefficient = .982 C-55

CAPSULE U SURVEILLANCE PROGRAM WELD CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02109/2004 01:38 PM Page 1 Coefficients of Curve 2 A = 72.6 B = 70.4 C = 119.21 TO = 45.94 D = O.0OE+OO Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=143.0(Fixed) Lower Shelf Energy-2.2(Fixed)

Temp@30 ft-lbs=-37.6 Deg F Temp@50 ft-lbs=6.3 Deg F Plant: Watts Bar 1 Material: N/A Heat: 895075 Orientation: NA Capsule: U Fluence: n1cm^'2 300 250 Y,

I 200 0

0 IL

150 _.__- -_--------------------

)

0 z

100 5

I, a

50. 7'--'-

0 - 2--0

---

-1 0

• 300 -200 -10oo I0 100 200 300 400 500 600 Temperature In Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 100. 00 7.00 13. 40 - 6.40

-50.00 17. 00 25. 66 -8. 66

- 25. 00 25.00 35. 04 - O. 04

.00 36. 00 46. 74 - 10. 74

20. 00 65. 00 57.52 7.48

35. 00 75.00 66. 16 8.84

50. 00 76.00 75.00 1.00

75. 00 127.00 89.43 37.57

75. 00 91.00 89. 43 1.57 C-56

CAPSULE U SURVEILLANCE PROGRAM WELD Page 2 Plant: Watts Bar I Material: N/A Heat: 895075 Orientation: NA Capsule: U Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 100. 00 95.00 102. 50 -7. 50 125. 00 93. 00 113.47 - 20.47 150. 00 99. 00 122.08 - 23.08 250. 00 145. 00 138. 56 6.44 300. 00 138.00 141.04 -3. 04 350. 00 147.00 142. 15 4. 85 Correlation Coefrlcicnt = .949 C-57

CAPSULE U SURVIELLANCE PROGRAM WELD CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 02:10 PM Page I Coefficients of Curve 2 A = 38.43 B = 38.43 C = 65.63 TO = 13.24 D = O.OOE+0O Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=76.9 Lower Shelf L.E.=.0(Fixed)

Temp.@L.fB. 35 mils=7.4 Deg F Plant: Watts Bar 1 Material: N/A Heat: 895075 Orientation: NA Capsule: U Fluence: nIcmA2 200 150

.2 100 50 0

C I/LI 0

-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Tempcrature Input L.E. Computed LE. Differential

- 100. 00 3. 00 2.36 .64

-50. 00 1 1. 00 9.77 1.23

- 25. 00 19.00 18.27 .73

.00 25. 00 30. 78 - 5.78

20. 00 50.00 42. 38 7.62

35. 00 49. 00 50. 73 - 1. 73 50.00 51. 00 57.96 - 6. 9 6

75. 00 87. 00 66.71 20.29

75. 00 58. 00 66.71 -8. 71 C-58

CAPSULE U SURVIELLANCE PROGRAM WELD Page 2 Plant: Watts Bar 1 Material: N/A Heat: 895075 Orientation: NA Capsule: U Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential 100. 00 67.00 71.76 -4. 76 125. 00 71. 00 74.39 -3. 39 150. 00 73. 00 75. 69 -2. 69 250. 00 84. 00 76. 81 7. 19 300. 00 84. 00 76. 85 7. 15 350. 00 67.00 76. 86 -9. 86 Correlation Coefficient =.957 C-59

CAPSULE U SURVIELLANCE PROGRAM WELD CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 01:53 PM Page 1 Coefficients of Curve 2 A = 50. B = 50. C = 52.19 TO = 9.58 D = O.OOE+00 Equation is A + B

• tTanh((T-To)/(C+DT))]

Temperature at 50% Shear = 9.6 Plant: Watts Bar I Material: N/A Heat: 895075 Orientation: NA Capsule: U Fluence: n/cmA2 125 100 75 I-.

0.

50 25 o +-

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 100. 00 5.00 1.48 3.52

-50. 00 10. 00 9.25 .75

-25. 00 25.00 20. 99 4.01

.00 25.00 40. 92 - 1 5. 9 2

20. 00 70. 00 59. 85 10. 15 35.00 80. 00 72. 59 7.41 50.00 80. 00 82. 47 - 2.47 75.00 95.00 92.46 2.54 75.00 90. 00 92.46 - 2. 4 6 C-60

CAPSULE U SURVIELLANCE PROGRAM WELD Page 2 Plant: Watts Bar 1 Material: N/A Hcat: 895075 Orientation: NA Capsule: U Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 1 00. 00 90. 00 96.97 - 6. 9 7 125. 00 80. 00 98. 81 - 18.81 150. 00 85. 00 99.54 -14. 54 250. 00 1 00. 00 99. 99 .01 300. 00 100.00 100. 00 . 00 350. 00 1 00. 00 100. 00 .00 Correlation Coefficicnt = .972 C-61

CAPSULE W SURVEILLANCE PROGRAM WELD CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02109/2004 01:39 PM Page 1 Coefficients of Curve 3 A = 57.1 B = 54.9 C = 97.49 TO = 52.01 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=1 12.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=-.7 Deg F Temp@50 ft-lbs=39.4 Deg F Plant: Watts Bar I Material: N/A Heat: 895075 Orientation: NA Capsule: W Fluence: n/cmA2 300 250 (A

n, 200 0

0 U-10 z

> 100 50 0 4-

-300 -200 -1 00 0 100 200 300 400 500 600 Temperature In Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 5 0. 00 13.00 14.26 - 1.26

- 20. 00 20. 00 22. 61 -2. 61 10.00 32. 00 34. 81 -2. 81 25.00 41.50 42.27 - . 77 40.00 56. 00 50.37 5.63

55. 00 61. 50 58. 79 2.71

70. 00 71.50 67. 12 4. 38 100. 00 7 5. 00 82. 14 - 7. 14 125. 00 87.50 91.93 -4. 43 C-62

CAPSULE W SURVEILLANCE PROGRAM WELD Page 2 Plant: Watts Bar I Material: N/A Heat: 895075 Orientation: NA Capsule: W Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 150. 00 98. 50 99. 03 - . 53 200. 00 1 13. 00 1 0 6. 9 7 6.03 350. 00 123. 50 111.76 1 1.74 Correlation Coefficient = .990 C-63

CAPSULE W SURVIELLANCE PROGRAM WELD CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 02:10 PM Page 1 Coefficients of Curve 3 A = 44.58 B = 44.58 C = 95.29 TO = 42.68 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=89.2 Lower Shelf L.E.=.O(Fixed)

Temp.@L.E. 35 mils=21.9 Deg F Plant: Watts Bar 1 Material: N/A Heat: 895075 Orientation: NA Capsule: W Fluence: n/cmA2 200 150 0

E C . .

100 500

• a I c0,,,o,,,,,.............

50 0

-300 0 300 600 Temperature In Deg F Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential

-50. 0O 10.00 11. 15 - 1. 15

- 20. 00 19. 00 18. 86 .14 10.00 27.00 29.86 -2. 86 25.00 35. 00 36.40 - 1.40 40.00 49. 00 43. 32 5.68

55. 00 54.00 50.31 3.69 70.00 5 5. 00 57.02 - 2. 02 1 00. 00 64.00 68. 57 -4. 57 125.00 74.00 75.70 - 1.70 C-64

CAPSULE W SURVIELLANCE PROGRAM WELD Page 2 Plant: Watts Bar 1 Material: N/A Heat: 895075 Orientation: NA Capsule: W Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential 150. 00 82. 00 80. 67 1. 33 200. 00 90. 00 85. 99 4.01 350. 00 87. 00 89.01 -2. 01 Correlation Coefficient = .993 C-65

CAPSULE W SURVIELLANCE PROGRAM WELD CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 01:53 PM Page I Coefficients of Curve 3 A = 50. B = 50. C= 88.62 TO = 19.8 D =O.00E+O0 Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = 19.9 Plant: Watts Bar 1 Material: N/A Heat: 895075 Orientation: NA Capsule: W Fluence: n/cmA2 125 100 0 75 a,

50 25 -_

0 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature In Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

-50. 00 . 00 17. 15 -17. 15

- 20. 00 30.00 28.94 1.06

10. 00 55.00 44. 49 10.51

25. 00 60. 00 52. 93 7.07

40. 00 65. 00 61.20 3. 80

55. 00 65. 00 68. 88 -3. 88

70. 00 70. 00 75. 64 -5. 64 I 00. 00 75.00 85.94 - 10. 94 125.00 90. 00 91.48 -1. 48 c-66

CAPSULE W SURVIELLANCE PROGRAM WELD Page 2 Plant: Watts Bar 1 Material: N/A Heat: 895075 Orientation: NA Capsule: W Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 150. 00 I 00. 00 94.97 5.03 200. 00 100. 00 98. 32 1. 68 350.00 1 00. 00 99.94 .06 Correlation Coefficient = .967 C-67

CAPSULE X SURVEILLANCE PROGRAM WELD CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 01:39 PM Page I Coefficients of Curve 4 A = 68.1 B = 65.9 C = 114.7 TO = 70.21 D = O.OOE+O0 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy= I34.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=-5.4 Deg F Temp@50 ft-lbs=37.9 Deg F Plant: Watts Bar I Material: N/A Heat: 895075 Orientation: NA Capsule: X Fluence: n/cmA2 300 250 n

-. 200 0a 0

U-C w

z

> 100 50 0 - ;- T-I....

-300 -200 -100 0 100 200 300 400 500 600 Temperature In Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 100. 00 5. 00 8. 64 .3. 64

-75. 00 14. 00 1 1. 91 2.09

-50. 00 23. 00 16. 63 6.37

- 25. 00 21. 00 23. 25 - 2.25

10. 00 51. 00 36.37 14. 6 3

25. 00 26. 00 43.39 -17.39 50.00 49. 00 56. 61 -7. 61

75. 00 91.00 70. 85 20. 15 100. 00 78.00 84. 84 -6. 84 C-68

CAPSULE X SURVEILLANCE PROGRAM WELD Page 2 Plant: Watts Bar 1 Material: N/A Heat: 895075 Orientation: NA Capsule: X Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 125. 00 94. 00 97.39 -3. 39 175.00 1 00. 00 115.74 - 15. 74 200. 00 125. 00 121.58 3.42 225. 00 138. 00 125.69 12.31 225. 00 130. 00 1 25. 69 4.31 275. 00 143. 00 130. 39 12.61 Correlation Coefficient = .975 C-69

CAPSULE X SURVIELLANCE PROGRAM WELD CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 02:10 PM Page I Coefficients of Curve 4 A = 42.49 B = 42.49 C = 109.65 TO = 55.42 D = O.OOE+00 Equation is A + B * (Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=85.0 Lower Shelf L.E.=.O(Fixed)

Temp.@L.E. 35 mils=35.9 Deg F Plant: Watts Bar 1 Material: N/A Heat: 895075 Orientation: NA Capsule: X Fluence: n/ClMA2 200 150 100 50 A --- - - - - - - - - - - - - - - - - - - - -

0 .~ ..... _ . A--a' E

A

0 A.,,I t,,- ---

-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperaturc Input L.E. Computed L.E. Differential

- 100. 00 I. 00 4.71 -3. 71

- 7 5. 00 9. 00 7.21 1.79

-50. 00 13. 00 10. 84 2. 16

-25. 00 14. 00 15.93 -1. 93

10. 00 37.00 25. 83 11. 17

25. 00 18.00 31. 00 -13. 00

50. 00 37. 00 40. 39 -3. 39

75. 00 60. 00 50. 00 10.00 1 00. 00 55. 00 58. 87 -3. 87 C-70

CAPSULE X SURVIELLANCE PROGRAM WELD Page 2 Plant: Watts Bar I Material: N/A Heat: 895075 Orientation: NA Capsule: X Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential 125.00 68.00 66.34 1.66 175.00 71. 00 76. 36 -5. 36 200. 00 85. 00 79. 31 5. 69 225.00 78.00 81.29 - 3.29 225. 00 80. 00 81.29 - 1.29 275.00 86. 00 83.46 2.54 Correlation Coefficient = .980

• . C-71

CAPSULE X SURVIELLANCE PROGRAM WELD CVGRAPH 5.0.2 Hyperbolic Tangent Curve Pnnted on 02/09/2004 01:53 PM Page 1 Coefficients of Curve 4 A = 50. B = S0. C = 120.09 TO = 70.86 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = 70.9 Plant: Watts Bar I Material: N/A

• Heat: 895075 Orientation: NA Capsule: X Fluence: n/cm^2 125 100 S. 75 s

ux co C,

0) 0, 50 25 0 b-

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperaturc Input Percent Shear Computed Percent Shear Differential

- 100. 00 10. 00 5.49 4.51

-75. 00 15. 00 8. 10 6. 90

- O0.0 0 15. 00 1 1.79 3.21

-25. 00 25. 00 16. 85 8. 15

10. 00 20. 00 26.63 -6. 63

25. 00 30. 00 31.78 -1. 78

50. 00 25.00 41.40 - 16.40

75. 00 65. 00 51.72 13.28 1 00. 00 60. 00 61.90 - I. 90 C-72

CAPSULE X SURVIELLANCE PROGRAM WELD Page 2 Plant: Watts Bar 1 Material: N/A Heat: 895075 Orientation: NA Capsule: X Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 125. 00 75. 00 71. 13 3.87 175.00 70. 00 85.00 - 15.00 200.00 100. 00 89. 57 10.43 225. 00 95.00 92. 87 2.13 225.00 100. 00 92. 87 7.13 275.00 100. 00 96. 77 3.23 Correlation Coefficient = .970 C-73

UNIRRADIATED HEAT AFFECTED ZONE CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 03:18 PM Coefficients of Curve 1 A = 45.6 B = 43.4 C = 99.65 TO = -18.8 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=89.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=-56.2 Deg F Temp@50 ft-lbs=-8.6 Deg F Plant: Watts Bar 1 Matcrial: SA508CL2 Heat: 527536 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 300 250

, 200 9

0 LL 0

I-; 150 ai z

8 100 50 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 225.00 3.00 3.56 -. 56

- 225. 00 3.00 3.56 -. 56

- 150. 00 7.00 8.02 - 1.02

-1 00. 00 30.00 16.42 13.58

- 67.00 17.00 26. 10 -9. 10

-67. 00 23.50 26. 10 -2.60

-40. 00 37.50 36.50 1.00

-20. 00 36. 00 45. 08 -9. 08

- 7. 00 71. 00 50.71 20.29 c-74

UNIRRADIATED HEAT AFFECTED ZONE Page 2 Plant: Watts Bar 1 Material: SA508CL2 Heat: 527536 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

-7. 00 45.50 50.71 -5. 21

- 7. 00 60. 00 50. 71 9.29

20. 00 43.00 61.69

• 1 8. 69

20. 00 59. 50 61.69 -2. 19

40. 00 73.00 68. 60 4.40

68. 00 73.50 76. 06 - 2. 5 6 100. 00 80.00 81. 68 - 1. 68 150.00 108.00 86. 16 21.84 210. 00 94. 00 88. 13 5.87 Correlation Coefficient = .948 C-75

UNIRRADIATED HEAT AFFECTED ZONE CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 03:40 PM Page 1 Coefficients of Curve I A = 33.16 B = 33.16 C = 114.43 TO = -7. D = 0.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=66.3 Lower Shelf LE.=.O(Fixed)

Temp.@L.E. 35 nils=-.6 Deg F Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: NA Capsule: UNIRR Fluence: nlcmA2 200 150 r-

.o C

8 100 6

50.

50 0 -

-300 0 300 600 Temperature In Deg F Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential

- 225. 00 1. 00 1. 44 - . 44

- 225. 00 1.00 1. 44 - . 44

- 150. 00 4.00 5.03 - 1.03

- 100. 00 18.00 10.91 7.09

- 67. 00 10.00 17.21 -7. 21

- 67. 00 13.00 17.21 -4. 21

-40. 00 28.00 23. 85 4. 15

- 20. 00 25. 00 29.41 -4. 41

-7. 00 41.00 33. 16 7. 84 C-76

UNIRRADIATED HEAT AFFECTED ZONE Page 2 Plant: Watts Bar 1 Material: SA508CL2 Heat: 527536 Orientation: NA Capsule: UNLRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential

-7.00 31.00 33. 16 -2. 16

-7.00 40. 00 33. 16 6. 84

20. 00 33.00 40. 84 -7.84

20. 00 41.00 40. 84 .16

40. 00 49. 00 46. 06 2.94

68. 00 50. 00 52. 24 - 2.24 1 00. 00 51. 00 57. 46 - 6.46 150.00 76. 00 62. 31 13. 69 210. 00 58. 00 64. 86 -6.86 Correlation Coefficient = .958 c-77

UNIRRADIATED HEAT AffJEJCTED ZONE CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 03:33 PM Page 1 Coefficients of Curve I A = 50. B = 50. C = 94.74 TO = -22.26 D = O.OOE+00 Equation is A + B * [Tanh((T-l'o)/(C+DT))]

Temperature at 50% Shear = -22.2 Plant: Watts Bar 1 Material: SA508CL2 Heat: 527536 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 125 100 I-M 75 -

(n 1U, D

a, (L 50 _ _

25-I O - - . .

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

- 225. 00 .00 1.37 - 1.37

- 225. 00 . 00 1.-37 - 1.37

- 150.00 .00 6. 32 - 6. 32

- 100. 00 20. 00 16.23 3.77

-67. 00 18.00 28.00 - 10.00

- 67. 00 33. 00 28. 00 5. 00

- 40. 00 35. 00 40. 75 -5. 75

- 20. 00 55. 00 51. 19 3.81

-7. 00 79. 00 57.99 21.01 c-78

UNIRRADIATED HEAT AFFECTED ZONE Page 2 Plant: Watts Bar 1 Material: SA508CL2 Heat: 527536 Orientation: NA Capsule: UNIR Fluence: n/cmA2 Charpy V-Notch Data Temperature Jnput Percent Shear Computed Percent Shear Differential

-7. 00 56.00 57.99 - 1.99

.7. 00 74.00 57. 99 16.01 20.00 50. 00 70.93 - 20. 93

20. 00 46.00 70. 93 - 24. 93

40. 00 84. 00 78. 82 5. 18 6 8. 00 100. 00 87. 05 12.95 100.00 91. 00 92.96 -1.96 150. 00 1 00. 00 97.43 2.57 210.00 100.00 99.26 .74 Correlation Coefficient = .948 c-79

CAPSULE U HEAT AFFECTED ZONE.

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 03:18 PM Page 1 Coefficients of Curve 2 A = 40.6 B = 38.4 C = 91.79 TO = 20.68 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=79.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=-5.3 Deg F Temp@50 ft-lbs=43.7 Deg F Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: NA Capsule: U Fluence: n/cmA2 300 250

, 200 U

46..

0 0

U.

~ 150 z

> 100 50 _. -. ----------

r-------

03 n

-300 -200 -100 0 100 200 300 400 500 600 Temperature In Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 175.00 3.00 3.27 -. 27

- 100. 00 8. 00 7. 37 .63

-25.00 26.00 22. 93 3.07

.00 37.00 32. 09 4.91

25. 00 55.00 42. 41 12.59

40. 00 36.00 48.56 12.56

50. 00 39. 00 52.46 13.46

60. 00 36. 00 56. 11 20. 11

70. 00 79. 00 59.45 19.55 C-80

CAPSULE U HEAT AFFECTED ZONE Page 2 Plant: Watts Bar 1 Material: SA508CL2 Heat: 527536 Orientation: NA Capsule: U Fluence: n/cmA2 Charpy V-Notch Data Temperaturc Input CVN Computed CVN Differential 75.00 95. 00 61. 00 34. 00 75.00 15. 00 61. 00 -46. 00 100. 00 99. 00 67.42 31.58 150. 00 68. 00 74.67 -6. 67 250. 00 86. 00 78.48 7.52 300. 00 83. 00 78. 83 4. 17 Correlation Coefficient = .780 C-81

CAPSULE U HEAT AFFECTED ZONE CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 03:40 PM Page 1 Coefficients of Curve 2 A = 27.21 B = 27.21 C = 80.96 TO = 27.31 D = O.OOE+00 Equation is A + B

• JTanh((T-To)/(C+DT))]

Upper Shelf L.E.=54.4 Lower Shelf L.E.-.0(Fixed)

Temp.@L.E. 35 mils=51.2 Deg F Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: NA Capsule: U Fluence: n/cmA2 200 150 1- 4

a. 100 C

lb ------- r-- ------------- :--:--

50 11'0n "Ir

,, :;2-,

m , ,_ ,I 0

-300 0 300 600 Temperature In Deg F Charpy V-Notch Data Temperature Input LE. Computed L.E. Differential

- 175. 00 2.00 .37 1. 63

- 100.00 1. 00 2.25 - 1.25

- 25. 00 10.00 11.73 - 1.73

.00 21.00 18.37 2. 63

25. 00 40. 00 26.44 13.56

40. 00 25. 00 31. 44 - 6.44

50. 00 27. 00 34. 65 -7. 65

60. 00 27. 00 37.64 -1O. 64

70. 00 58. 00 40. 37 17.63 C-82

CAPSULE U HEAT AFFECTED ZONE Page 2 Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: NA Capsule: U Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential

75. 00 56. 00 41.62 14.38

75. 00 5.00 4 1. 62 36. 62 1 00. 00 68. 00 46. 68 21.32 150.00 52. 00 51.92 . 08 250. 00 50. 00 54.21 - 4.21 300. 00 53.00 54. 36 - 1. 36 Corrclation Coefficient = .782 C-83

CAPSULE U HEAT AFFECTED ZONE CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 03:33 PM Page 1 Coefficients of Curve 2 A = 50. B = 50. C = 37.41 TO = 88.1 D =O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))J Temperature at 50% Shear = 88.1 Plant: Watts Bar 1 Material: SA508CL2 Heat: 527536 Orientation: NA Capsule: U Fluence: n/cmA2 125 100 to-0 75 (n

0 P

0 50 fI-II1 25 73 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature In Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

- 175. 00 . 00 .00 .00

- 100. 00 5.00 . 00 5.00

-25. 00 10. 00 . 24 9.76

.00 15.00 . 89 14. 11

25. 00 15. 00 3.31 1 1. 69

40. 00 20. 00 7. 10 12.90

50. 00 20. 00 11. 54 8.46

60. 00 20. 00 18.21 1.79

70. 00 5.00 27.54 - 22. 54 C-84

CAPSULE U HEAT AFFECTED ZONE Page 2 Plant: Watts Bar 1 Material: SA508CL2 Heat: 527536 Orientation: NA Capsule: U Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

75. 00 25. 00 33. 18 -8. 18 75.00 4 0. 00 33. 18 6. 82 100. 00 75. 00 65. 39 9. 61 150.00 100. 00 96.48 3.52 250.00 1 00. 00 99.98 .02 300. 00 1 00. 00 100. 00 . 00 Correlation Coefficient = .970 c-85

CAPSULE W HEAT AFFECTED ZONE CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 03:18 PM Page 1 Coefficients of Curve 3 A = 39.6 B = 37.4 C = 111.37 TO = 21.74 D = O.OOE+00 Equation is A + B

• ITanh((T-To)/(C+DT))]

Upper Shelf Energy=77.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=-7.4 Deg F Temp@50 ft-lbs=53.6 Deg F Plant: Watts Bar 1 Material: SA508CL2 Heat: 527536 Orientation: NA Capsule: W Fluencc: n/cm^2 300 250 to

,. 200 0

0 v150 LL z

U> 100 50 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature In Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 50. 00 15. 00 18. 37 -3.37

-30.00 37.50 23. 38 14. 12

-20.00 26.50 26. 20 .30

10. 00 33. 00 35.67 -2.67 40.00 37. 00 45.68 - 8.68

70. 00 57. 00 54. 86 2. 14 85.00 44.50 58. 82 14.32

00. 0 0 69. 00 62.27 6.73 150.00 86. 50 70.20 16. 30 C-86

CAPSULE W HEAT AIJTJ ECTED ZONE Page 2 Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: NA Capsule: W Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 200. 00 79. 50 74.07 5.43 300.00 81. 00 76.50 4.50 350.00 60. 50 76.79 - 1 6. 2 9 Correlation Coefficient = .902 C-87

CAPSULE W HEAT AFFECTED ZONE CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 03:40 PM Page 1 Coefficients of Curve 3 A = 31.8 B = 31.8 C = 108.76 TO = 36.94 D = O.OOE+OO Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=63.6 Lower Shelf L.E.=.0(Fixed)

Temp.@L.E. 35 mils=48.0 Deg F Plant: Watts Bar 1 Material: SA508CL2 Heat: 527536 Orientation: NA Capsule: W Fluence: nIcmr2 200 150 E

.o a 100 50 0 4-

-300 0 300 600 Temperature In Deg F Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential

-50. 00 9. 00 10. 70 -1.70

-30. 00 22.00 14.37 7.63

- 20. 00 17.00 16.52 .48

10. 00 25.00 24. 08 . 92

40. 00 29.00 32.70 3.70

70. 00 40. 00 41.18 -1. 18 85.00 34.00 45. 00 -I I . 00 1 00. 00 52.00 48. 42 3.58 150. 00 70. 00 56. 53 13.47 C-88

CAPSULE W HEAT AFFECTED ZONE Page 2 Plant: Watts Bar 1 Material: SA508CL2 Heat: 527536 Orientation: NA Capsule: W Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computcd LE. Differential 200. 00 63. 00 60.58 2.42 300. 00 63. 00 63. 10 -. 10 350. 00 55.00 63.40 - 8.40 Correlation Coefficient = .947 c-89

CAPSULE W HEAT AFFECTED ZONE CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 03:33 PM Page 1 Coefficients of Curve 3 A = 50. B = 50. C = 99.03 TO = 39.58 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = 39.6 Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: NA Capsule: W Fluence: nlcmA2 125 100 - _ --_. '- _ .....-..- -

I-75 C,)

IL 50 25 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature In Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

-50. 00 .00. 14.07 -14. 07

-30. 00 25. 00 19. 70 5.30

-20. 00 30. 00 23. 09 6. 91

10. 00 45. 00 35.49 9.51

40. 00 50. 00 50.21 - .21

70. 00 50. 00 64. 89 - 14. 89

85. 00 60. 00 71. 45 -I I . 4 5 1 00. 00 90.00 77.21 12.79 150. 00 100. 00 90.29 9.71 C-90

CAPSULE W HEAT AFFECTED ZONE Page 2 Plant: Watts Bar 1 Material: SA508CL2 Heat: 527536 Orientation: NA Capsule: W Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 200. 00 100. 00 96.23 3.77 300. 00 100. 00 99.48 . 52 350. 00 100. 00 99. 81 .19 Correlation Coefficient = .963 C-91

CAPSULE X HEAT AFFECTED ZONE CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 03:18 PM Page I Coefficients of Curve 4 A = 41.1 B = 38.9 C = 83.53 TO = 43.04 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=80.0(Pixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=18.6 Deg F Temp@50 ft-lbs=62.5 Deg F Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: NA Capsule: X Fluence: n/cmnA2 300 250 u,

, 200 1

0 0

IL

150 C)

W...

z

>; 100 50 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature In Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

-75. 00 8. 00 6. 55 1.45

-50. 00 16. 00 9.77 6. 23

. 00 22. 00 22. 66 -. 66

25. 00 29. 00 32. 83 -3. 83 5 0. 00 42. 00 44. 33 -2. 33

75. 00 59. 00 55.30 3. 70 100. 00 75. 00 64. 16 10.84 1 25. 00 58.00 70.41 - 12.41 150. 00 58. 00 74.42 - 16. 42 c-92

CAPSULE X HEAT AFFECTED ZONE Page 2 Plant: Watts Bar 1 Material: SA508CL2 Heat: 527536 Orientation: NA Capsule: X Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 200. 00 87. 00 78.23 8.77 200. 00 97.00 78.23 18.77 225. 00 96. 00 79. 02 16.98 250. 00 92.00 79.46 12.54 275. 00 69. 00 79.70 - 10.70 300.00 79.00 79. 83 - . 83 Correlation Coefficient = .937 C-93

CAPSULE X HEAT AFFECTED ZONE CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 03:40 PM Page 1 Coefficients of Curve 4 A = 28.15 B = 28.15 C = 79.27 TO = 52.89 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=56.3 Lower Shelf L.E.=.0(Fixed)

Temp. @L.E. 35 mils=72.6 Deg F Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: NA Capsule: X Fluence: n/cmA2 200 150 W

C 0 .A 5

100 C)

E I.

50

_ A _-

0

-300 0 300 600 Temperature In Deg F Charpy V-Notch Data Tcmperature Input LE. Computed L.F. Differential

- 75. 00 . 00 2. 15 - 2. 15

-50. 00 4.00 3.91 .09

.00 10. 00 1 1.74 1. 74

25. 00 18.00 18.64 - . 64

50. 00 29. 00 27. 13 1.87

75. 00 36. 00 35.81 .19 1 00. 00 54.00 43. 16 10. 84 1 25. 00 34. 00 48. 45 -14. 45 150. 00 42. 00 51. 83 -9. 83 C-94

CAPSULE X HEAT AFFECTED ZONE Page 2 Plant: Watts Bar I Material: SA508CL2 Heat: 527536 Orientation: NA Capsule: X Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential 200. 00 66. 00 54.96 11. 04 200. 00 58. 00 54. 96 3.04 225. 00 70. 00 55. 58 14.42 250. 00 65. 00 55.92 9. 08 275. 00 41. 00 56. 10 - 15. 10 300. 00 47.00 56. 19 - 9. 19 Correlation Coefficient = .915 C-95

CAPSULE X HEAT AFFECTED ZONE CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 02/09/2004 03:34 PM Page 1 Coefficients of Curve 4 A = 50. B = 50. C = 117.85 TO = 64.64 D = O.OOE+00 Equation is A + B * (Tanh((T-To)/(C+DT)))

Temperature at 50% Shear = 64.7 Plant: Watts Bar 1. Material: SA508CL2 Heat: 527536 Orientation: NA Capsule: X Fluence: n/cmA2 125 100 L.

0 75 -

0 U

0 50 0L 25 -

o -. -.- -_

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shcar Differential

-75.00 5.00 8.55 -3.55

-50. 00 10.00 12. 50 -2.50

.00 25.00 25.03 -. 03 25.00 30. 00 33.79 -3. 79 50.00 50.00 43. 82 6. 18

75. 00 45. 00 54.38 -9.38 1 00. 0 0 90. 00 64. 5 7 25.43 125. 00 70. 00 73.58 -3.58 150. 00 60. 00 80.98 -20.98 C-96

CAPSULE X HEAT AFFECTED ZONE Page 2 Plant: Watts Bar 1 Material: SA508CL2 Heat: 527536 Orientation: NA Capsule: X Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 200. 00 95.00 90. 86 4. 14 200. 00 90. 00 90. 86 - . 86 225. 00 90. 00 93. 83 -3. 83 250.00 1 00. 00 95. 87 4.13 275. 00 1 00. 00 97.26 2.74 300. 00 I 00. 00 98. 19 1.81 Correlation Coefficient = .960 C-97

D-o APPENDIX D WATTS BAR UNIT 1 SURVEILLANCE PROGRAM CREDIBILITY EVALUATION Appendix D

D-l INTRODUCTION:

Regulatory Guide 1.99, Revision 2, describes general procedures acceptable to the NRC staff for calculating the effects of neutron radiation embrittlement of the low-alloy steels currently used for light-water-cooled reactor vessels. Position C.2 of Regulatory Guide 1.99, Revision 2, describes the method for calculating the adjusted reference temperature and Charpy upper-shelf energy of reactor vessel beltline materials using surveillance capsule data. The methods of Position C.2 can only be applied when two or more credible surveillance data sets become available from the reactor in question.

To date there have been three surveillance capsules removed from the Watts Bar Unit I reactor vessel.

To use these surveillance data sets, they must be shown to be credible. In accordance with the discussion of Regulatory Guide 1.99, Revision 2, there are five requirements that must be met for the surveillance data to be judged credible.

The purpose of this evaluation is to apply the credibility requirements of Regulatory Guide 1.99, Revision 2, to the Watts Bar Unit I reactor vessel surveillance data and determine if the Watts Bar Unit I surveillance data is credible.

EVALUATION:

Criterion 1: Materials in the capsules should be those judged most likely to be controlling vith regard to radiation embrittlement.

The beitline region of the reactor vessel is defined in Appendix G to 10 CFR Part 50, "Fracture Toughness Requirements", as follows:

"the reactor vessel (shell material including welds, heat affected zones, and plates or forgings) that directly surrounds the effective height of the active core and adjacent regions of the reactor vessel that are predicted to experience sufficient neutron radiation damage to be considered in the selection of the most limiting material with regard to radiation damage."

The Watts Bar Unit I reactor vessel consists of the following beltline region materials:

• Intermediate Shell Forging 05

• Lower Shell Forging 04

• Intermediate to Lower Shell Circumferential Weld Seam (Heat # 895075).

Appendix D

D-2 At the time when the Watts Bar Unit 1 surveillance program material was selected it was believed that copper and phosphorus were the elements most important to embrittlement of the reactor vessel steels.

However, the intermediate shell forging had the lowest initial USE of the vessel beltline materials and it was below the required 75 fl-lbs limit from IOCFR5O Appendix G. Thus it -was selected as the surveillance base metal.

The weld material in the Watts Bar Unit 1 surveillance program was made of the same wire as the reactor vessel beitline weld, thus it was chosen as the surveillance weld material.

Hence, Criterion I is met for the Watts Bar Unit 1 reactor vessel.

Criterion 2: Scatter in the plots of Charpy energy versus temperature for the irradiated and unirradiated conditions should be small enough to permit the determination of the 30 ft-lb temperature and upper shelf energy unambiguously.

Based on engineering judgment, the scatter in the data presented in these plots is small enough to permit the determination of the 30 fl-lb temperature and the upper shelf energy of the Watts Bar Unit 1 surveillance materials unambiguously. Hence, the Watts Bar Unit 1 surveillance program meets this criterion.

Appendix D

D-3 Criterion 3: When there are two or more sets of surveillance data from one reactor, the scatter of ARTN-ur values about a best-fit line drawn as described in Regulatory Position 2.1 normally should be less than 280 F for welds and 17 0 F for base metal. Even if the fluence range is large (two or more orders of magnitude), the scatter should not exceed tvice those values. Even if the data fail this criterion for use in shift calculations, they may be credible for determining decrease in upper shelf energy if the upper shelf can be clearly determined, following the definition given in ASTAI E185-82.

The functional form of the least squares method as described in Regulatory Position 2.1 will be utilized to determine a best-fit line for this data and to determine if the scatter of these ARTIDT values about this line is less than 280F for welds and less than 171F for the plate.

The Watts Bar intermediate to lower circumferential weld will be evaluated for credibility. This weld is made from weld wire heat 895075. This weld metal is also contained in the Catawba Unit 1 and McGuire Unit 2 surveillance programs. Since the welds in question utilize data from other surveillance programs, the recommended NRC methods for determining credibility will be followed. The NRC methods were presented to industry at a meeting held by the NRC on February 12 and 13, 1998. At this meeting the NRC presented five cases. Of the five cases, Case 4 most closely represents the situation listed above for Watts Bar surveillance weld metal. Note, for the plate materials, the straight forvard method of Regulatory Guide 1.99, Revision 2 will be followed. Note, for the forging material, the straight forvard method of Regulatory Guide 1.99, Revision 2 will be followed.

Appendix D

D-4 First, NRC Case 4 will be evaluated for the Watts Bar surveillance weld metal, "Surveillance Data Available from Plant and Other Sources".

TABLE D-1 Surveillance Data - Normalization for Credibility Determination (when all data is being used)

Capsule:: Zessel .. Su -radaton -Fluencc .atio . luenc M.easured Temperature .

C' Material Tcmp. - 10) Factor' -- RT T AdJustd  :£hemistry C

{D: .. .I.. ..C  ;..

(5usted A .

WBI - U 54.0 41.0 560°F 0.447 0.776 O.0(c)OF 0.0°F 0.0°F WBI -W 54.0 41.0 560°F 1.08 1.02 30.50F 30.50F 40.26°F WBI - X 54.0 41.0 560°F 1.71 1.15 25.80F 25.80F 34.06°F Cat.1 - Z 54.0 68.0 553°F 02993 0.670 1.91°F 0.0(d)OF 0.000 F Cat.1 - Y 54.0 68.0 553°F 1318 1.077 17.79°F 10.79°F 8.52°F Cat.1 - V 54.0 68.0 553°F 2334 1.229 26.5 0F 19.5 0F 15.41°F MG2 - V 54.0 54.0 5540F 0.323 0.689 38.51°F 32.51°F 32.51°F MG2 - X 54.0 54.0 554°F 1.47 1.11 35.93°F 29.93°F 29.93°F MG2 - U 54.0 54.0 554°F 2.04 1.19 23.81 OF 17.81 OF 17.81°F MG2 - W 54.0 54.0 554°F 3.07 130 43.76°F 37.76°F 37.76°F Notes:

(a) Ratios equal 1.32 (Watts Bar), 0.79 (Catawba 1), and 1.0 (McGuire 2).

(b) Normalized to an average operating temperature 560°F (The Watts Bar Reactor Vessel).

(c) Actual value -6.4°F. For conservatism zero wvill be used.

(d) Afler the temperature adjustment, the Adjusted ?RTNr is less than zero. For conservatism zero will be used.

Credibility assessment - Watts Bar Data Only:

Assume the following for Watts Bar, the plant being assessed:

• Weld Heat # 895075 is in the surveillance program and in the vessel. The cold inlet temperature is equal to 5600F.

• The Best Estimate chemistry for heat # 895075 is:Cu = 0.04%, Ni = 0.73%

This equates to a Chemistry Factor of: CF = 54.0°F Appendix D

D-5 The data most representative for Watts Bar is that from Watts Bar since the irradiation environment of the surveillance capsules and the vessel are the same. The data requires the least adjustments. Watts Bar data should be examined independently to determine credibility.

Since all data is from one source (Watts Bar), then plot the measure ?RTNDT versus FF and determine the best fit line.

TABLE D-2 Determnination of Surveillance Weld CF Watts Bar Unit 1 Data Only

-nMaterial C . , - . . . ND Watts Bar WBI - U 0.447 0.776 0.00) 0.00 0.602 Surveillance WBI -W 1.08 1.02 305 l 31.11 1.04 Weld Material WBI -X 1.71 1.15 25.8 29.67 132 SUM: 60.78 2.962 CFs.wdd=W(FF*RTNMr) + - ( FF2 )=(60.78 0F)- (2.962)=20.59F (a) Units are n/cm 2 (E > 1.0 MeV).

(b) Actual value is -6.4, but for conservatism(i.e. a higher CF) a value of zero is used.

Slope of best fit line = 20.51F Appendix D

D-6 The Scatter above the best fit line is given in Table D-3:

TABLE D-3 Watts Bar Surveillance Capsule Data Only Capsule C: Irradiatoi ,i: luencet^) Fluencc Measuredt WBI - U 20.5 5600 F 0.447 0.776 0.0()' 15.90 F -15.90 F WBI - W 20.5 5600 F 1.08 1.02 30.5 20.90F 9.60F WBI - X 20.5 5600F 1.71 1.15 25.8 23.60F 2.2OF (a) Units are nfcrn' (E > 1.0 MeV).

(b) Where predicted ARTNr - (Slopeb¢, f,) * (Fluence Factor)

(c) Actual value is -6.4, but for conservatism(i.e. a higher CF) a value of zero is used.

Data is credible since the scatter is less than 280 F for all three surveillance specimens.

Credibility Assessment - All Weld Data:

The data from all sources should also be considered Since data are from multiple sources the data must be adjusted for chemical composition and irradiation environment differences and then determine the "ratio and temperature" adjusted slope of the best fit line.

For credibility determination, data are normalized to the mean chemical composition and temperature of the Watts Bar surveillance specimens.

Appendix D

D-7 TABLE D-4 All Surveillance Capsule Weld Data p . .r Ratio .. ure'..

.,..............-,, Cepsue .

Mate-ial .

CaAdjusted ARAditistW Surv. Weld WBI - U 0.447 0.776 0.0 0.00 0.602 Material WBI -W 1.08 1.02 4026 41.07 1.04 WBI -X 1.71 1.15 34.06 39.17 132 Cat.l - Z 0.2993 0.670 0.0 0.000 0.449 Cat.1 -Y 1318 1.077 8.52 9.176 1.160 Cat.1 - V 2334 1229 15.41 18.927 1.510 MG2 - V 0323 0.689 32.51 22399 0.475 MG2 - X 1.47 1.11 29.93 3322 123 MG2 - U 2.04 1.19 17.81 21.19 1.42 MG2 -XW 3.07 130 37.76 49.09 1.69 SUM: 234242 10.896 CF sun.wdd = X(FF

• RTNDT) + X( FF2) = (234242) + (10.896) = 21.5IF Notes (a) Calculated fluence in units ofn/cm2 (E > 1.0 MeV).

(b) FF = fluence factor =

• OPlog 0 (c) From Table D-1; [IF].

The slope of the best fit line = 21.5°F Appendix D

D-8 TABLE D-5 Best Fit of all Weld Metal Surveillance Data Available Ca.psul CF-: Irradiation Fluenne cFiuencc 'Rto ' rdce~)easured a

.(X1 '. Factor, Temperature ji:.

(E).. Adjutted BtFit Ln Rri WBI -U 21.5 560°F 0.447 0.776 O.0°F 16.68°F -16.70F WBI -W 215 560°F 1.08 1.02 40.26°F 21.93°F 18.3 0F WBI -X 21.5 560°F 1.71 1.15 34.06°F 24.73°F 9.3 0F Cat.1 - Z 21.5 553°F 0.2993 0.670 O.0°F 14.41°F -14.40F Cat.1 - Y 21.5 553°F 1318 1.077 8.52°F 23.16°F -14.60F Cat.1 - V 21.5 553°F 2334 1.229 15.41°F 26.42°F -11 .0F MG2- V 21.5 554°F 0323 0.689 32.51°F 14.81°F 17.70F MG2-X 21.5 554°F 1.47 1.11 29.930F 23.87°F 6.1°F MG2-U 21.5 554°F 2.04 1.19 17.81 OF 25.59°F -7.80F MG2 - W 21.5 554°F 3.07 130 37.76°F 27.95°F 9.80F (a) Units are n/cm2 (E > 1.0 MeV).

(b) Where predicted ARTNDT = (Slopeb,,fi) * (Fluence Factor)

Data is credible since the scatter is less than 28°F for all surveillance specimens.

In summary, the measured weld data is within acceptable range regardless of whether Watts Bar data is evaluated stand-alone or with the surveillance data from Catawba 1 and McGuire 2. Therefore, weld data meets this criteria, and the surveillance program weld metal CF to be used in calculations is 21.5°F and is based on all available surveillance data.

Appendix D

D-9 Credibilitv Assessment - Foreini Material:

Now that the Weld Metal has been evaluated for credibility, the surveillance Forging material must be evaluated. From Table D-6 the calculated CF values from surveillance data for the intermediate shell forging 05 is 90.30 F.

TABLE D-6 Calculation of Chemistry Factors using Watts Bar Unit 1 Surveillance Capsule Data Muateri a apl Cp ef F RT F AR C H .....

Inter. Shell U 0.447 0.776 98.3 76.281 0.602 Forging 05 W 1.08 1.02 111.4 113.63 1.04 (Tangential) X 1.71 1.15 94.7 108.91 1.32 Inter. Shell U 0.447 0.776 28.7 22.271 0.602 Forging 05 W 1.08 1.02 79.0 80.58 1.04 (Axial) X 1.71 1.15 115.9 133.29 1.32 SUM: 534.962 5.924 CFo5 = (FF

• RTNDT) +- ( FF2 ) = (534.962) * (5.924) = 90.31F (a) Calculated fluence in units of n/cm2 (E > 1.0 MeV).

(b) FF = fluence factor = 1 o28s

• O.1]og D (c) From Appendix C; [TF].

Appendix D

D-10 TABLE D-7 Predicted Versus Best-Estimate ARTNDT Values for the Watts Bar Unit 1 Surveillance Forging Data M.ta Cs C it sehngen ARrv I ~~~~~~~~R >...........

..I Intermediate Shell U 903 0F 0.776 70.1 983 -28.2 0

Forging 05 W 903 F 1.02 92.1 111.4 -19.3 (Tangential) X 903 0F 1.15 103.8 94.7 9.1 Intermediate Shell U 903 0F 0.776 70.1 28.7 41.4 0

Forging 05 W 903 F 1.02 92.1 79.0 13.1 (Axial) X 903 0F 1.15 103.8 115.9 -12.1 From Table D-7 above, 3 out of 6 data points exceeds the +/- 17'F scatter-band and is therefore deemed not-credible.

Appendix D

D-11 Criterion 4: The irradiation temperature of the Charpy specimens in the capsule should match the vessel wall temperature at the cladding/base metal interface siithin +/- 25 0F.

The capsule specimens are located in the reactor between the neutron pad and the vessel wall and are positioned opposite the center of the core. The test capsules are in baskets attached to the neutron pad.

The location of the specimens with respect to the reactor vessel beltline provides assurance that the reactor vessel wall and the specimens experience equivalent operating conditions such that the temperatures will not differ by more than 250F. 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 Watts Bar Unit 1surveillance program does not contain correlation monitor material. Therefore, this criterion is not applicable to the Watts Bar Unit 1 surveillance program.

CONCLUSION:

Based on the preceding responses to all five criteria of Regulatory Guide 1.99, Revision 2, Section B and 10 CFR 50.61, the Watts Bar Unit 1 surveillance plate and weld data is credible.

Appendix D