ML061020406

WCAP-16527-NP, Rev. 0, Analysis of Capsule X from Firstenergy Nuclear Operating Company Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program.

ML061020406
Person / Time
Site:	Beaver Valley
Issue date:	03/31/2006
From:	Shaun Anderson, Burgos B, Conermann J Westinghouse
To:	Office of Nuclear Reactor Regulation
References
WCAP-16527-NP, Rev 0
Download: ML061020406 (267)

Text

Westinghouse Non-Proprietary Class 3 WCAIP-16527-NP March 2006 Revision 0 Analysis of Capsule X from FirstEnergy Nuclear Operating Company Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program S) Westinghouse

WESTINGHOUSE NON-PROPRIETARY CLASS 3 WCAP-16527-NP, Revision 0 Analysis of Capsule X from FirstEnergy Nuclear Operating Company Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program B.N. Burgos J. Conermann S.L. Anderson March 2006 Approved: (ElectronicallyAvvroved*)

J.S. Carlson, Manager Primary Component Asset Management

• Electronically Approved Records are Authenticated in the Electronic Document Management System Westinghouse Electric Company LLC Energy Systems P.O. Box 355 Pittsburgh, PA 15230-0355 02006 Westinghouse Electric Company LLC All Rights Reserved

iii TABLE OF CONTENTS LIST OF TABLES ................... iv LIST OF FIGURES ................... vi PREFACE .................. ix EXECUTIVE

SUMMARY

................... x 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 COMPACT TENSION SPECIMEN TESTS .5-5 6 RADIATION ANALYSIS AND NEUTRON DOSIMETRY . . -1

6.1 INTRODUCTION

. 5-1 6.2 DISCRETE ORDINATES ANALYSIS .5-2 6.3 NEUTRON DOSIMETRY .. 64 6.4 CALCULATIONAL UNCERTAINTIES .6-5 7 SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE .7-1 8 REFERENCES .3-1 APPEND:[X A VALIDATION OF THE RADIATION TRANSPORT MODELS BASED ON NEUTRON DOSIMETRY MEASUREMENTS CREDIBILITY APPEND' X B LOAD-TIME RECORDS FOR CHARPY SPECIMEN TESTS APPEND]IX C CHARPY V-NOTCH PLOTS FOR EACH CAPSULE USING SYMMETRIC HYPERBOLIC TANGENT CURVE-FITTING METHOD APPEND]IX D BEAVER VALLEY UNIT 2 SURVEILLANCE PROGRAM CREDIBILITY EVALUATION

iv LIST OF TABLES Table 4-1 Chemical Composition (wt %) of the Beaver Valley Unit 2 Reactor Vessel Surveillance Materials (Unirradiated) ..................................................... 4.-3 Table 4-2 Heat Treatment History of the Beaver Valley Unit 2 Reactor Vessel Surveillance Materials ..... 1-4 Table 5-1 Charpy V-Notch Data for the Beaver Valley Unit 2 Intermediate Shell Plate B9004-2 Irradiated to a Fluence of 5.601 x 1019 n/cm 2 (E > 1.0 MeV)

(Longitudinal Orientation) ................ :5-6 Table 5-2 Charpy V-Notch Data for the Beaver Valley Unit 2 Intermediate Shell Plate B9004-2 Irradiated to a Fluence of 5.601 x 1019 n/cm 2 (E > 1.0 MeV)

(Transverse Orientation) . ............... 5-7 Table 5-3 Charpy V-notch Data for the Beaver Valley Unit 2 Surveillance Weld Material Irradiated to a Fluence of 5.601 x 10'9 n/cm2 (E> 1.0 MeV) ........................................ :5-8 Table 5-4 Charpy V-notch Data for the Beaver Valley Unit 2 Heat Affected Zone Material Irradiated to a Fluence of 5.601 x 10'9 n/cm 2 (E> 1.0 MeV) ................................. 5-9 Table 5-5 Instrumented Charpy Impact Test Results for the Beaver Valley Unit 2 Intermediate Shell Plate B9004-2 Irradiated to a Fluence of 5.601 x 10'9 n/cm2 (E> 1.0 MeV) (Longitudiral Orientation) 5-10 Table 5-6 Instrumented Charpy Impact Test Results for the Beaver Valley Unit 2 Intermediate Shell Plate B9004-2 Irradiated to a Fluence of 5.601 x 10'9 n/cm 2 (E> 1.0 MeV) (Transverse Orientation) 5-11 Table 5-7 Instrumented Charpy Impact Test Results for the Beaver Valley Unit 2 Surveillance Weld Metal Irradiated to a Fluence of 5.601 x 10' 9 n/cm 2 (E> 1.0 MeV) .............................. 5-12 Table 5-8 Instrumented Charpy Impact Test Results for the Beaver Valley Unit 2 Heat Affected Zone Material Irradiated to a Fluence of 5.601 x 10i 9 n/cm2 (E> 1.0MeV) . .................

5-13 Table 5-9 Effect of Irradiation to 5.601 x 10'9 n/cm2 (E> 1.0 MeV) on the Capsule X Toughness Properties of the Beaver Valley Unit 2 Reactor Vessel Surveillance Materials . ............

5-14 Table 5-IC, Comparison of the Beaver Valley Unit 2 Surveillance Material 30 ft-lb Transition Temperature Shifts and Upper Shelf Energy Decreases with Regulatory Guide 1.99, Revision 2, Predictions .................. 5-15

V LIST OF TABLES (Cont.)

Table 5-11 Tensile Properties of the Beaver Valley Unit 2 Capsule X Reactor Vessel Surveillance Materials Irradiated to 5.601 x 1019 n/cm 2 (E> 1.0MeV) .......................... 5-16 Table 6-1 Calculated Neutron Exposure Rates and Integrated Exposures At The Surveillance Capsule Center .................. 6-10 Table 6-2 Calculated Azimuthal Variation of Maximum Exposure Rates and Integrated Exposures at the Reactor Vessel Clad/Base Metal Interface ........................................ 6-14 Table 6-3 Relative Radial Distribution Of Neutron Fluence (E > 1.0 MeV) Within The Reactor Vessel Wall ........... 6-18 Table 6-4 Relative Radial Distribution of Iron Atom Displacements (dpa) Within The Reactor Vessel Wall ........... 6-19 Table 6-5 Calculated Fast Neutron Exposure of Surveillance Capsules Withdrawn from Beaver Valley Unit 2 .6-19 Table 6-6 Calculated Surveillance Capsule Lead Factors .6-19 Table 7-1 Recommended Surveillance Capsule Withdrawal Schedule .7-1

vi LIST OF FIGURES Figure 4-1 Arrangement of Surveillance Capsules in the Beaver Valley Unit 2 Reactor Vessel ........ 4-5 Figure 4-2 Capsule X Diagram Showing the Location of Specimens, Thermal Monitors, and Dosimeters .- 6 Figure 5-1 Charpy V-Notch Impact Energy vs. Temperature for Beaver Valley Unit 2 Reactor Vessel Intermediate Shell Plate B9004-2 (Longitudinal Orientation) . 5-17 Figure 5-2 Charpy V-Notch Lateral Expansion vs. Temperature for Beaver Valley Unit 2 Reactor Vessel Intermediate Shell Plate B9004-2 (Longitudinal Orientation) . 5418 Figure 5-3 Charpy V-Notch Percent Shear vs. Temperature for Beaver Valley Unit 2 Reactor Vessel Intermediate Shell Plate B9004-2 (Longitudinal Orientation) . 5419 Figure 5-4 Charpy V-Notch Impact Energy vs. Temperature for Beaver Valley Unit 2 Reactor Vessel Intermediate Shell Plate B9004-2 (Transverse Orientation) . 5-20 Figure 5-5 Charpy V-Notch Lateral Expansion vs. Temperature for Beaver Valley Unit 2 Reactor Vessel Intermediate Shell Plate B9004-2 (Transverse Orientation) . 5 -21 Figure 5-6 Charpy V-Notch Percent Shear vs. Temperature for Beaver Valley Unit 2 Reactor Vessel Intermediate Shell Plate B9004-2 (Transverse Orientation) . 5--22 Figure 5-7 Charpy V-Notch Impact Energy vs. Temperature for Beaver Valley Unit 2 Reactor Vessel Weld Metal . 5--23 Figure 5-8 Charpy V-Notch Lateral Expansion vs. Temperature for Beaver Valley Unit 2 Reactor Vessel Weld Metal . 5- 24 Figure 5-9 Charpy V-Notch Percent Shear vs. Temperature for Beaver Valley Unit 2 Reactor Vessel Weld Metal . 5-25 Figure 5-1 0 Charpy V-Notch Impact Energy vs. Temperature for Beaver Valley Unit 2 Reactor Vessel Heat Affected Zone Material . 5.-26 Figure 5-1 1 Charpy V-Notch Lateral Expansion vs. Temperature for Beaver Valley Unit 2 Reactor Vessel Heat Affected Zone Material . 5--27 Figure 5-12 Charpy V-Notch Percent Shear vs. Temperature for Beaver Valley Unit 2 Reactor Vessel Heat Affected Zone Material . 5- 28 Figure 5-13 Charpy Impact Specimen Fracture Surfaces for Beaver Valley Unit 2 Reactor Vessel Intermediate Shell Plate B9004-2 (Longitudinal Orientation) . 5-29

vii LIST OF FIGURES (Cont.)

Figure 5-14 Charpy Impact Specimen Fracture Surfaces for Beaver Valley Unit 2 Reactor Vessel Intermediate Shell Plate B9004-2 (Transverse Orientation) ............................... 5-30 Figure 5-15 Charpy Impact Specimen Fracture Surfaces for Beaver Valley Unit 2 Reactor Vessel Weld Metal ............................................................ 5-31 Figure 5-16 Charpy Impact Specimen Fracture Surfaces for Beaver Valley Unit 2 Reactor Vessel Heat Affected Zone Material ............................................................ 5-32 Figure 5-17 Tensile Properties for Beaver Valley Unit 2 Reactor Vessel Intermediate Shell Plate B9004-2 (Longitudinal Orientation) ............................................................ 5-33 Figure 5-18 Tensile Properties for Beaver Valley Unit 2 Reactor Vessel Intermediate Shell Plate B9004-2 (Transverse Orientation) ............................................................ 5-34 Figure 5-19 Tensile Properties for Beaver Valley Unit 2 Reactor Vessel Weld Metal ....................... 5-35 Figure 5-20 Fractured Tensile Specimens from Beaver Valley Unit 2 Reactor Vessel Lower Shell Plate B9004-2 (Longitudinal Orientation) ............................................................ 5-36 Figure 5-21 Fractured Tensile Specimens from Beaver Valley Unit 2 Reactor Vessel Lower Shell Plate B9004-2 (Transverse Orientation) ............................................................ 5-37 Figure 5-22 Fractured Tensile Specimens from Beaver Valley Unit 2 Reactor Vessel Weld Metal ..5-38 Figure 5-23 Engineering Stress-Strain Curves for Lower Shell Plate B9004-2 Tensile Specimens WL-I0 and WL-Il (Longitudinal Orientation) ........................................... 5-39 Figure 5-24 Engineering Stress-Strain Curves for Lower Shell Plate B9004-2 Tensile Specimens WL-12 (Longitudinal Orientation) ............................................................ 5-40 Figure 5-25 Engineering Stress-Strain Curves for Lower Shell Plate B9004-2 Tensile Specimens WT-l0 and WT-1 1 (Transverse Orientation) ............................................... 5-41 Figure 5-26 Engineering Stress-Strain Curves for Lower Shell Plate B9004-2 Tensile Specimens WT-12 (Transverse Orientation) ............................................................ 5-42 Figure 5-27 Engineering Stress-Strain Curves for Weld Metal Tensile Specimens WW-IO and WW-Il ............................................................ 5-43 Figure 5-28 Engineering Stress-Strain Curves for Weld Metal Tensile Specimens WW-12 ............. 5-44

viii LIST OF FIGURES (Cont.)

Figure 6-1 Beaver Valley Unit 2 rO Reactor Geometry at the Core Midplane .................................. 6-7 Figure 6-2 Beaver Valley Unit 2 rz Reactor Geometry with Neutron Pad ........................................ 6-9

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

Reviewer::

All Sections D.M. Chapman (ElectronicallvApproved*)

• Electronically Approved Records are Authenticated in the Electronic Document Management System

x EXECUTIVE

SUMMARY

The purpose of this report is to document the results of the testing of Reactor Vessel Surveillance Capsule X from Beaver Valley Unit 2. Capsule X was removed at 13.94 EFPY and post irradiation mechanical tests of the Charpy V-notch and tensile specimens were performed. A fluence evaluation utilizing the NRC approved neutron transport and dosimetry cross-section libraries was derived from the ENDF/B-VI database. Capsule X received a fluence of 5.601 x 1019 n/cm 2 after irradiation to 13.94 EFPY. The peak clad/base metal interface vessel fluence after 13.94 EFPY of plant operation was 1.521 x 1019 n/cm2 .

This evaluation led to the following conclusions: 1) Five out of the eight measured 30 ft-lb shift in transition temperature values of the intermediate shell plate B9004-2 (longitudinal & transverse) are greater than the Regulatory Guide 1.99, Revision 2 [Ref. 1], predictions. However, the shift values are less than ihe two sigma allowance by Regulatory Guide 1.99, Revision 2. 2) All of the measured 30 ft-lb shifts in transition temperature values of the weld metal are less than the Regulatory Guide 1.99, Revision 2, predictions. 3) The measured percent decrease in upper shelf energy for all the surveillance materials contained in the Beaver Valley Unit 2 surveillance program are less than the Regulatory Guide 1.99, Revision 2 predictions. 4) All beltline materials exhibit a more than adequate upper shelf energy level for continued safe plant operation and are predicted to maintain an upper shelf energy greater than 50 ft-lb throughout the life of the vessel (36 EFPY) as required by IOCFR50, Appendix G [Ref. 2]. 5) The Beaver Valley Unit 2 surveillance data from the intermediate shell plate B9004-2 and the surveillance weld metal were found to be 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 fourth capsule removed and tested from the Beaver Valley Unit 2 reactor pressure vessel, led to the following conclusions:

• The Charpy V-notch data presented in WCAP-9615, Revision I [Ref. 3], WCAP-12406 [Ref. 41, WCAP-14484 [Ref. 5], WCAP-15675 [Ref. 6] and STC Letter Report STD-MCE-05-36 [Ref. T]

were fitted using CVGRAPH, Version 5.0.2, which is a hyperbolic tangent curve-fitting program.

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 5.601 x 10'9 n/cm 2 after 13.94 effective full power years (EFPY) of plant operation.

• Irradiation of the reactor vessel intermediate shelf plate B9004-2 Charpy specimens, oriented with the longitudinal axis of the specimen parallel to the major working direction (longitudinal orientation), resulted in an irradiated 30 ft-lb transition temperature of 133.61F and an irradiated 50 ft-lb transition temperature of 185.3F. This results in a 30 fl-lb transition temperature increase of 98.00 F and a 50 ft-lb transition temperature increase of 105.0 0 F, relative to the unirradiated values, for the longitudinal oriented specimens. See Table 5-9.

• Inradiation of the reactor vessel intermediate shell plate B9004-2 Charpy specimens, oriented with the longitudinal axis of the specimen perpendicular to the major working direction (transverse orientation), resulted in an irradiated 30 ft-lb transition temperature of 143.91F and an irradiated 50 ft-lb transition temperature of 212.77F. This results in a 30 fl-lb transition temperature increase of 104.10 F and a 50 ft-lb transition temperature increase of 121.50 F, relative to the urirradiated values, for the longitudinal oriented specimens. See Table 5-9.

• Inradiation of the weld metal (heat number 83652) Charpy specimens resulted in an irradiated 30 fl-lb transition temperature of-16.90 F and an irradiated 50 ft-lb transition temperature of IC0.0 0 F. This results in a 30 ft-lb transition temperature increase of 22.9 'F and a 50 ft-lb transition temperature increase of 31.7 'F relative to the unirradiated values. See Table 5-9.

• The average upper shelf energy of the intermediate shell plate B9004-2 (longitudinal orientation) resulted in an average energy decrease of 14 ft-lb after irradiation. This results in an irradiated average upper shelf energy of 81 ft-lb for the longitudinal oriented specimens. See Table 5-9.

• The average upper shelf energy of the intermediate shell plate B9004-2 (transverse orientation) resulted in an average energy decrease of 5 ft-lb after irradiation. This results in an irradiated average upper shelf energy of 74 ft-lb for the longitudinal oriented specimens. See Table 5-9.

• The average upper shelf energy of the weld metal Charpy specimens resulted in an average energy decrease of 6 ft-lb after irradiation. This results in an irradiated average upper shelf energy of 133 ft-lb for the weld metal specimens. See Table 5-9.

Summary of Results

1-2

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

- Five out of the eight measured 30 ft-lb shifts in transition temperature values of the intermediate shell plate B9004-2 (longitudinal & transverse) are greater than the Regulatory Guide 1.99, Revision 2, predictions. However, the shift values are less than the two sigma allowance by Regulatory Guide 1.99, Revision 2.

- All of the measured 30 ft-lb shifts in transition temperature value of the weld metal contained in Capsule X are less than the Regulatory Guide 1.99, Revision 2, predictions.

- The measured percent decrease in upper shelf energy for all the surveillance materials contained in the Beaver Valley Unit 2 surveillance program are less than the Regulatory Guide 1.99, Revision 2 predictions.

• All beltline materials exhibit a more than adequate upper shelf energy level for continued safe plant operation and are predicted to maintain an upper shelf energy greater than 50 ft-lb throughout the life of the vessel (36 EFPY) as required by LOCFR50, Appendix G [Ref. 2].

• The calculated end-of-license (36 EFPY) neutron fluence (E> 1.0 MeV) at the core midplane for the Beaver Valley Unit 2 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* = 4.113 x 10' 9 n/cm 2 Vessel 1/4 thickness = 2.572 x 10i 9 n/cm 2 Vessel 3/4 thickness = 1.006 x 1018 n/cm 2

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

• The credibility evaluation of the Beaver Valley Unit 2 surveillance program is presented in Appendix D of this report. The evaluation concluded that the Beaver Valley Unit 2 surveillance results are credible.

Surnmary of Results

.2-1 2 INTRODUCTION This report presents the results of the examination of Capsule X, the fourth capsule removed from the reactor in the continuing surveillance program which monitors the effects of neutron irradiation on the FirstEnergy Nuclear Operating Company (FENOC) Beaver Valley Unit 2 reactor pressure vessel materials under actual operating conditions.

The surveillance program for the FENOC Beaver Valley Unit 2 reactor pressure vessel materials was designed and recommended by the Westinghouse Electric Corporation. A description of the surveillance program and the pre-irradiation mechanical properties of the reactor vessel materials are presented in WCAP-961 5, Revision 1, "Duquesne Light Company Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program" [Ref. 3]. The surveillance program was planned to cover the 40-year design life of the reacto:- pressure vessel and was based on ASTM El 85-73, "Recommended Practice for Surveillance Tests on Structural Materials for Nuclear Reactors" [Ref. 8]. Capsule X was removed from the reactor after 13.94 EFPY of exposure and shipped to the Westinghouse Science and Technology Department Hot Cell Facil ity, where the post-irradiation mechanical testing of the Charpy V-notch impact and tensile surveillance specimens was performed.

This repoit summarizes the testing of and the post-irradiation data obtained from surveillance Capsule X removed from the FENOC Beaver Valley Unit 2 reactor vessel and discusses the analysis of the data.

Introductio::i

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

A method for ensuring the integrity of reactor pressure vessels has been presented in "Fracture Toughness Criteria for Protection Against Failure," Appendix G to Section XI of the ASME Boiler and Pressure Vessel Code [Ref. 9]. The method uses fracture mechanics concepts and is based on the reference nil-ductility transition temperature (RTNDT).

RTNDT is cefined as the greater of either the drop weight nil-ductility transition temperature (NDTT per ASTM E-208 [Ref. 10]) or the temperature 607F less than the 50 ft-lb (and 35-mil lateral expansion) temperature as determined from Charpy specimens oriented perpendicular (transverse) to the major working direction of the plate. The RTNDT of a given material is used to index that material to a reference stress intensity factor curve (K1 , curve) which appears in Appendix G to the ASME Code [Ref. 9]. The K1, curve ils a lower bound of static fracture toughness results obtained from several heats of pressure vessel steel. When a given material is indexed to the Kl, curve, allowable stress intensity factors can be obtained fDr 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 Beaver Valley Unit 2 reactor vessel radiation surveillance program [Ref. 3], 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 Beaver Valley Unit 2 reactor pressure vessel core region (beltline) materials were inserted in the reactor vessel prior to initial plant start-up. The six capsules were positioned in the reactor vessel between the thermal shield 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 13.94 effective full power years (EFPY) of plant operation. This capsule contained Charpy V-notch impact and tensile specimens from Intermediate Shell Plate B9004-2, and weld metal made from sections of B9004-2 and the adjoining Lower Shell Plate B9005-2 (Heat No. C 1408-1).

The weld was fabricated using a submerged arc weld metal with 3/16-inch diameter weld wire type B-4, heat number 83642, with Linde 0091 flux, lot number 3536, and is identical to the wire/flux combination used in the original fabrication of the core region. There were also Charpy V-notch impact specimens for the heat-alfected-zone which obtained from the weld-heat-affected zone. Additionally, bend bar and 1/2T compact tension test specimens were included in the capsule (Figure 4-2).

Test material obtained from the Intermediate Shell Plate B9004-2 (after thermal heat treatment and forming of the plate) were taken at least one plate thickness from the quenched edges of the plate. All test specimens were machined from the 1/414 thickness location of the plate after performing a simulated post-weld stress-relieving treatment on the test material. Specimens were machined from weld metal and the heat-affect ed-zone (HAZ) metal of a stress-relieved weldment joining sections of the intermediate and lower shell plates. All HAZ specimens were obtained from the weld heat-affected-zone of intermediate shell plate B9004-2.

Charpy V-notch impact specimens from the intermediate shell plate B9004-2 were machined in the longitudinal (longitudinal axis of the specimen parallel to the major working direction) and transverse (longitudinal axis of the specimen perpendicular to the major working direction) orientations. 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 plate B9004-2 were machined in both the longitudinal and transverse orientations. Tensile specimens from the weld metal were oriented with the long dimension of the specimen perpendicular to the weld direction.

Capsule X contained a bend bar specimen, machined from intermediate shell plate B9004-2 with the longitudinal axis of the specimen oriented to the working direction of the plate, such that the simulated crack in the specimen would propagate in the major working direction of the plate. All bend bar specimens were fatigue pre-cracked according to ASTM E399 [Ref. 11].

The compact tension specimens from intermediate shell plate B9004-2 were machined in the transverse and longitudinal orientations, to obtain fracture toughness data both normal and parallel to the rolling direction of the plate. Compact tension test specimens from the weld metal were machined normal to the Description of Program

4-2 weld direction with the notch oriented in the direction of the weld. All specimens were fatigue pre-cracked according to ASTM E399 [Ref. 11].

The chemical composition and heat treatment of the unirradiated surveillance materials are presented in Tables 4-1 and 4-2, respectively. The chemical analysis reported in Table 4-1 was obtained from unirradiated material used in the surveillance program [Ref. 3].

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 (NP2 3 7 ) and uranium (U238 ) were placed in the capsule to measure the integrated flux at specific neutron energy levels [Ref. 3].

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

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 Table 4-1 Chemical Composition (wt%) of the Beaver Valley Unit 2 Reactor Vessel Surveillance Materials (Unirradiated)

Element Intermediate Shell Weld Metal('b)

Plate B9004-2()

C 0.24 0.10 Al 0.047 0.001 S 0.016 0.011 N2 0.009 0.028 Co 0.009 0.007 As 0.010 0.005 Cu 0.05 0.08 W 0.01 <0.01 Si 0.24 0.14 Sn 0.008 0.005 Mo 0.59 0.49 Zr 0.002 <0.001 Ni 0.56 0.07 P 0.010 0.008 Mn 1.32 1.17 B 0.0003 <0.00 1 Cr 0.08 0.07 Cb <0.01 <0.01 V 0.003 0.002 Ti <0.01 <0.01 Notes:

a. Analysis conducted by Combustion Engineering, Inc.

b. The surveillance weldment is a submerged arc weld fabricated using 3/16-inch diameter weld wire type B-4, heat number 83642, with a Linde 0091 flux, lot number 3536. This weld wire/flux combination is identical to that used for the intermediate and lower shell vertical seams and the girth weld between the intermediate and lower shell plates.

Description of Program

4-4 Table 4-2 Heat Treatment History of the Beaver Valley Unit 2 Reactor Vessel Surveillance Materials [Ref. 31 Material Temperature ( 0F) Time Coolant Austenitizing: 4 hrs. Water-Quench 1600 +/- 25 Intermediate Shell Plates Tempered: 4 hrs. Air-cooled B9004-2 1225 + 25 Stress Relief: 30 hrs. Furnace Cooled 1140 25 Weldment Stress Relief: 13.5 hrs. Furnace Cooled 1150 +/-25 Description of Program

.4-5 U

REACTOR VESSEL CORE SARREL

\x /NEUTRON PAC otV w

140y Figure 4-1 Arrangement of Surveillance Capsules in the Beaver Valley Unit 2 Reactor Vessel Description of Program

4-6 LEGEND: W'L - INTERMEDIATE SHELL PLATE B9004-2 (LONGITUDINAL)

WT - INTERMEDIATE SHELL PLATE B9004-2 (TANGENTIAL)

WVW- WVELD METAL (HEAT U83652)

WVH - HEAT AFFECTED ZONE METAL Bend Bar Tensile Corn act Cornaat Char yCharp Charp Corn )act

[1 %V 1WW60 IIf WH-60 W5 W4 WS IWTI NWIII W5 WI VI IV1 WW59 WH59 WWVS 5 H56 WWV53 WH53 WL16 WI W N-- 010 WW58 WH58~ L=55 WW5J~y2 WH52 L~

TOP OF VESSEL t CENTER Dosimeter A Corn pact Charp Cha Dosimeter Tensile Charp Charp CharVC p 7 ] -NN-5i7 WH51 WL4WL3~

W50 WH50 FW-W48 WI4WL1'II4I H48 FT]ILI2VT60

[T59 IWL60 I WL59 WVT57 WVT56 WL57 WL56 WVT54 WVT53 WL54 WL3 IWNT51 VTS0 I WL5I IVL50 IWLV49IH I WN46 I WL0 I I WT[8 WDL58 I I %VT52VI L522I I VT9 VL-49 CENTER 0 Dosimeter B Do.-imeterq A anid B j LvTk Tensile WT12J I

Al -. 15% Co (Cd) Wirer Ni Wire-

• 1 ----

I '--

I-----4 I

S

- Al -. 15% Co Wire Fe Wire

~ L3I IILJ0 5790 F (Dosimeter Ar - Cu Wire BOTITOM OF VESSEL 590'F (Dosimeter B)

Dosimeter A 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 OVERVIEW The post-irradiation mechanical testing of the Charpy V-notch impact specimens and tensile specimens was perfoamed in the Remote Metallographic Facility (RMF) at the Westinghouse Science and Technology Department. Testing was performed in accordance with 10CFR50, Appendices G and H

[Ref. 2], ASTM Specification E185-82 [Ref. 12], and Westinghouse Procedure RMF 8402, Revision 2

[Ref. 13] as detailed by Westinghouse RMF Procedures 8102, Revision 3 [Ref. 14], and 8103, Revision 2

[Ref. I 5].

Upon receipt of the capsule at the hot cell laboratory (located at RMF), the specimens and spacer blocks were carefully removed, inspected for identification number, and checked against the master list in WCAP-9615 [Ref. 3]. No discrepancies were found.

Examination of the two low-melting point 579 0 F (3040 C) and 590'F (310 0 C) eutectic alloys indicated no melting of either type of thermal monitor. Based on this examination, the maximum temperature to which the test spe.cimens were exposed was less than 579 0 F (304'C).

The Charpy impact tests were performed per ASTM Specification E23-02a [Ref. 16] and RMF Procedure 8103 [Ref 15] on a Tinius-Olsen Model 74, 358J machine. The tup (striker) of the Charpy impact test machine is instrumented with an Instrom Impulse instrumentation system, feeding information into an IBM compatible computer. With this system, load-time and energy-time signals can be recorded in addition tc 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 (TGy), the maximum load (PM), and the time to maximum load (tM) can be determined. Under some test conditions, a sharp drop in load indicative of fast fracture was observed. The load at which fast fracture was initiated is identified as the fast fracture load (PF), and the load at which fast fracture terminated is identified as the arrest load (PA).

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

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

ay=(PGy*L)/[B *(W-a)2 *C] (1) where: , = distance between the specimen supports in the impact machine 13 = the width of the specimen measured parallel to the notch n = height of the specimen, measured perpendicularly to the notch a = notch depth The constant C is dependent on the notch flank angle (O), 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 4 =

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

Testing of Specimens from Capsule X

5-2 ay= (PGY*L) /[B* ( W_ a)2 *1.21]=(3.305 *PGY*W)/[B *(W-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:

oy= 33.3

• PGY (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 5, 6, and 7 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 E23-02a [Ref. 16] and A370-97a [Ref. 17].. 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 11 15) per ASTM Specification E8-04 [Ref. 18] and E21-03a [Ref. 19], and Procedure RMF 8102 [Ref. 14]. 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 E83-93

[Ref. 20].

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. Chromel-Alumel 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 550'F. During the actual testing, the grip temperatures were used to obtain desired specimen temperatures. Experiments have indicated that this method is accurate to +20 F.

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 result:3 of the Charpy V-notch impact tests performed on the various materials contained in Capsule X, which received a fluence of 5.601 x 10'9 n/cm 2 (E> 1.0 MeV) in 13.94 EFPY of operation, are presented in Tables 5-1 through 5-12 and are compared with unirradiated results [Ref. 3] as shown in Figures 5-1 through 5-12.

The transitiion 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 plate B9004-2 Charpy specimens, oriented with the longitudinal axis of the specimen parallel to the major working direction (longitudinal orientation),

resulted in an irradiated 30 ft-lb transition temperature of 133.60 F and an irradiated 50 ft-lb transition temperature of 185.3 0F. This results in a 30 ft-lb transition temperature increase of 98.00 F and a 50 ft-lb transition Temperature increase of 105.0 0 F, relative to the unirradiated values, for the longitudinal oriented specimens. See Table 5-9.

Irradiation of the reactor vessel intermediate shell plate B9004-2 Charpy specimens, oriented with the longitudinal axis of the specimen perpendicular to the major working direction (transverse orientation),

resulted in an irradiated 30 ft-lb transition temperature of 143.90 F and an irradiated 50 ft-lb transition temperature of 212.70 F. This results in a 30 ft-lb transition temperature increase of 104.10 F and a 50 ft-lb transition temperature increase of 121.5 0 F, relative to the unirradiated values, for the longitudinal oriented specimens. See Table 5-9.

Irradiation of the weld metal (heat number 83652) Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of -16.97F and an irradiated 50 ft-lb transition temperature of 10.00 F. This results in a 30 ft-lb transition temperature increase of 22.90 F and a 50 ft-lb transition temperature increase of 31.70 F, relative to the unirradiated values. See Table 5-9.

Irradiation of the reactor vessel heat affected zone Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of -1.90 F and an irradiated 50 ft-lb transition temperature of 49.81F. This results in a 30 ft-lb transition temperature increase of 85.30 F and a 50 ft-lb transition temperature increase of 91.6 0 F, relative to the unirradiated values, for the HAZ specimens. See Table 5-9.

The average upper shelf energy of the intermediate shell plate B9004-2 (longitudinal orientation) resulted in an average energy decrease of 14 ft-lb after irradiation. This results in an irradiated average upper shelf energy of 81 ft-lb for the longitudinal oriented specimens. See Table 5-9.

The average upper shelf energy of the intermediate shell plate B9004-2 (transverse orientation) resulted :in an average energy decrease of 5 ft-lb after irradiation. This results in an irradiated average upper shelf energy of 74 ft-lb for the longitudinal oriented specimens. See Table 5-9.

The average upper shelf energy of the weld metal Charpy specimens resulted in an average energy decrease of 6 ft-lb after irradiation. This results in an irradiated average upper shelf energy of 133 ft-lb for the weld metal specimens. See Table 5-9.

Testing of Specimens from Capsule X

5-4 The average upper shelf energy of the heat affected zone material resulted in an average energy decrease of 0 ft-lb after irradiation. An irradiated average upper shelf energy of 114 ft-lb for the HAZ specimens was measured. See Table 5-9.

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

- Five out of the eight measured 30 ft-lb shifts in transition temperature values of the intermediate shell plate B9004-2 (longitudinal & transverse), relative to the unirradiated values, are greater than the Regulatory Guide 1.99, Revision 2, predictions. However, each shift value is less than the two sigma allowance by Regulatory Guide 1.99, Revision 2.

- All of the measured 30 ft-lb shifts in transition temperature value of the weld metal contained in Capsule X, relative to the unirradiated values, are less than the Regulatory Guide 1.99, Revision 2, predictions.

- The measured percent decrease in upper shelf energy for all the surveillance materials contained in the Beaver Valley Unit 2 surveillance program, relative to the unirradiated values, are less than the Regulatory Guide 1.99, Revision 2 predictions.

All beltline materials exhibit a more than adequate upper shelf energy level for continued safe plant operation and are predicted to maintain an upper shelf energy greater than 50 ft-lb throughout the extended life of the vessel (36 EFPY) as required by IOCFR50, Appendix G [Ref. 2].

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 Charpy V-notch data presented in WCAP-9615, Revision I [Ref. 3], WCAP-12406 [Ref. 4], WCAP-14484 [Ref. 5], WCAP-15675 [Ref. 6] and STC Letter Report STD-MCE-05-36 [Ref. 7] were fitted using CVGRAPH, Version 5.0.2, which is a hyperbolic tangent curve-fitting program. Appendix C presents the CVGRAPH, Version 5.0.2, Charpy V-notch plots and the program input data.

Testing of Specimens from Capsule X

5-5 5.3 TENSILE TEST RESULTS The results of the tensile tests performed on the various materials contained in Capsule X irradiated to 5.601 x 10'9 n/cm 2 (E> 1.0 MeV) are presented in Table 5-11 and are compared with unirradiated results

[Ref. 3] as shown in Figures 5-17 through 5-19.

The result.3 of the tensile tests performed on the Intermediate Shell Plate B9004-2 (longitudinal orientation) indicated that irradiation to 5.601 x 1019 n/cm2 (E> 1.0 MeV) caused approximately a 8 to 11 ksi increase in the 0.2 percent offset yield strength and approximately a 5 to 9 ksi increase in the ultimate tensile strength when compared to unirradiated data [Ref. 3]. See Figure 5-17.

The results of the tensile tests performed on the Intermediate Shell Plate B9004-2 (transverse orientation) indicated that irradiation to 5.601 x 1019 n/cm 2 (E> 1.0 MeV) caused approximately a 9 to 13 ksi increase in the 0.2 percent offset yield strength and approximately a 6 to 11 ksi increase in the ultimate tensile strength when compared to unirradiated data [Ref. 3]. See Figure 5-18.

The results of the tensile tests performed on the reactor vessel weld metal indicated that irradiation to 5.601 x 10I9 n/cm 2 (E> 1.0 MeV) caused approximately a 3 to 10 ksi increase in the 0.2 percent offset yield strength and approximately a 3 to 10 ksi increase in the ultimate tensile strength when compared to unirradiated data [Ref. 3]. See Figure 5-19.

The fractured tensile specimens for the intermediate shell plate B9004-2 (longitudinal and transverse orientations) and the reactor vessel weld metal are shown in Figures 5-20 through 5-22. The engineering stress-strain curves for the tensile tests are shown in Figures 5-23 through 5-28.

5.4 COMPACT TENSION SPECIMEN TESTS Per the surveillance capsule testing contract, the 1/2T compact tension and bend bar specimens were not tested and are being stored at the Westinghousc Science and Technology Center Hot Cell facility.

Testing of Specimens from Capsule X

5-6 Table 5-1 Charpy V-notch Data for the Beaver Valley Unit 2 Intermediate Shell Plate B9004-2 Irradiated to a Fluence of 5.601 x 10"9 n/cm 2 (E> 1.0 MeV) (Longitudinal Orientation)

Sample Temperature Impact Energy Lateral Expansion Shear Number FC ft-lbs Joules milsmm WL49 -50 -46 3 4 1 0.03 2 WL59 25 -4 11 15 8 0.20 5 WL60 75 24 25 34 17 0.43 10 WL58 100 38 23 31 18 0.46 20 WL47 125 52 27 37 21 0.53 25 WL46 150 66 35 47 26 0.66 35 WL48 175 79 38 52 30 0.76 40 WL5S 200 93 37 50 29 0.74 50 WL56 225 107 75 102 53 1.35 95 WL51 250 121 78 106 58 1.47 100 WL52 275 135 77 104 59 1.50 98 WL57 280 138 73 99 58 1.47 98 WL50 325 163 87 118 60 1.52 100 WL54 350 177 89 121 65 1.65 100 WL53 375 191 86 117 63 1.60 100 Testing of Specimens from Capsule X

5-7 Table 5-2 Charpy V-notch Data for the Beaver Valley Unit 2 Intermediate Shell Plate B9004-2 Irradiated to a Fluence of 5.601 x 10'9 n/cm 2 (E> 1.0 MeV) (Transverse Orientation).

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

WT60 -50 -46 3 4 2 0.05 2 WT57 25 -4 9 12 7 0.18 10 WT56 50 10 9 12 9 0.23 15 WT5O 75 24 19 26 15 0.38 20 WT46 100 38 20 27 16 0.41 25 WT59 125 52 28 38 25 0.64 30 WT54 150 66 32 43 28 0.71 35 WT47 175 79 33 45 28 0.71 45 WT52 200 93 45 61 39 0.99 55 WT55 250 121 55 75 50 1.27 75 WT58 275 135 65 88 53 1.35 90 WT53 300 149 65 88 57 1.45 100 WT48 325 163 77 104 55 1.40 100 WTSI 350 177 78 106 55 1.40 100 WT49 375 191 74 100 51 1.30 100 Testing of Specimens from Capsule X

5-8 Table 5-3 Charpy V-notch Data for the Beaver Valley Unit 2 Surveillance Weld Metal Irradiated to a Fluence of 5.601 x I101 n/CM 2 (E> 1.0 MeV) l Sample Temperature Impact Energy Lateral Expansion Shear Number OF OC ft-lbs Joules mils mm  %

WW51 -75 -59 3 4 2 0.05 2 WW53 -50 -46 9 12 6 0.15 15 WW54 -25 -32 7 9 7 0.18 15 WW52 -25 -32 19 26 15 0.38 25 WW55 -10 -23 6 8 5 0.13 15 WW48 0 -18 56 76 40 1.02 50 WW46 10 -12 88 119 59 1.50 65 WW59 25 -4 97 132 63 1.60 75 WW57 50 10 41 56 37 0.94 45 WW50 50 10 79 107 48 1.22 65 WW58 75 24 113 153 80 2.03 90 WW47 100 38 117 159 82 2.08 95 WW60 150 66 129 175 87 2.21 100 WW56 175 79 130 176 85 2.16 100 WW49 225 107 139 188 80 2.03 100 Testing of Specimens from Capsule X

.5-9 Table 54 Charpy V-notch Data for the Beaver Valley Unit 2 Heat Affected Zone Material Irradiated to a Fluence of 5.601 x 1019 n/cm2 (E> 1.0 MeV) l Sample Temperature Impact Energy Lateral Expansion Shear Number. F C Ft-lbs Joules mils mm  %

WH48 -90 -68 15 20 7 0.18 15 WH55 -50 -46 13 18 7 0.18 15 WH50 -25 -32 25 34 19 0.48 35 WH49 0 -18 43 58 29 0.74 40 WH58 25 -4 45 61 34 0.86 60 WHS3 50 10 58 79 36 0.91 70 WH51 75 24 43 58 29 0.74 40 WH54 100 38 87 118 61 1.55 95 WH47 125 52 63 85 43 1.09 90 WH52 135 57 61 83 36 0.91 90 WH46 150 66 85 115 57 1.45 98 WH59 175 79 87 118 61 1.55 100 WH60 200 93 122 165 88 2.24 100 WH57 225 107 137 186 89 2.26 100 WHS6 250 121 137 186 81 2.06 100 Testing of Specimens from Capsule X

5-10 Table 5-5 Instrumented Charpy Impact Test Results for the Beaver Valley Unit 2 Intermediate Shell Plate B9004-2 Irradiated to a Fluence of 5.601 x 1019 n/cm 2 (E>1.0 MeV) (Longitudinal Orientation)

Normalized Energies Charpy (ft-lb/in 2 ) Yield Time to Time to Fast Test Energy Ch M P Load Yield Max. Max. Fract. Arrest Yield Flow Sample Temp. ED arpy ax. rop. PGY tGy Load t,, Load PF Load PA Stress Stress No. (OF) (ft-lb) ED/A ENI/A Ep/A (lb) (msec) PMI (lb) (msec) (lb) (lb) ay (ksi) (ksi)

WL49 -50 3 24 15 9 1683 0.1 1794 0.12 1789 0 56 58 WL59 25 11 89 50 38 3411 0.14 4054 0.19 4054 0 114 124 WL60 75 25 201 157 45 3579 0.14 4600 0.36 4600 0 119 136 WL58 100 23 185 118 68 2906 0.13 4192 0.33 4189 113 97 118 WL47 125 27 218 139 78 3093 0.14 4280 0.36 4252 538 103 123 WL46 150 35 282 169 113 3088 0.13 4360 0.41 4274 983 103 124 WL48 175 38 306 194 112 3012 0.15 4372 0.47 4343 1306 100 123 WL55 200 37 298 134 164 2724 0.13 4174 0.36 4174 2639 91 115 WL56 225 75 604 239 365 2990 0.13 4601 0.53 3662 2602 100 126 WL51 250 78 628 216 413 2988 0.14 4430 0.50 n/a n/a 99 123 WL52 275 77 620 229 392 2741 0.14 4409 0.53 3620 2282 91 119 WL57 280 73 588 211 377 3051 0.14 4335 0.49 2937 2182 102 123 WL50 325 87 701 251 450 1962 0.12 4337 0.61 n/a n/a 65 105 WL54 350 89 717 276 441 1083 0.07 4383 0.66 n/a n/a 36 91 WL53 375 86 693 216 477 2967 0.15 4247 0.52 n/a n/a 99 120 Testing of Specimens from Capsule X

5-11 Table 5 Instrumented-Charpy.Impact Test Results for the Beaver Valley Unit 2 Intermediate Shell Plate B9004-2 Irradiated to a

_ _o Fuence of_5.601 x 1019 n/cm2 (E>1.0 MeV) (Transverse Orientation)

_== _ _ _____---Normalized Energies ~ ~0v -

-- Charpy S I'7~~~(t-lb/i n 2Yield Time t o Time to Fast

-Test- -Energy- _ _r__ -Load - -- Yield Max. Max. Fract. Arrest Yield Flow Sample -:=Temp. - ED Charpy Max-.

Prop. PGY tcy Load t1 Load PF Load PA Stress Stress No. -(F) - (ft-lb) ED/A - EXj,/A Ep/A (lb) (msec) Prq (lb) (msec) (lb) (lb) ay (ksi) (ksi)

WT60 -50 3 24 12 12 1362 0.09 1499 0.11 1491 0 45 48 WT57 25 9 73 37 36 3213 0.14 3455 0.16 3437 0 107 III WT56 50 9 73 30 42 2680 0.13 3022 0.15 3017 106 89 95 WTSO 75 19 153 87 66 2842 0.13 3978 0.27 3978 289 95 114 WVT46 100 20 161 65 96 3194 0.14 4008 0.22 4003 495 106 120 WT59 125 28 226 146 79 3068 0.14 4297 0.37 4284 770 102 123 WVT54 150 32 258 151 107 2858 0.13 4179 0.39 4161 967 95 117 WT47 175 33 266 137 129 2856 0.14 4214 0.37 4211 1376 95 118 WT52 200 45 363 203 159 2769 0.13 4208 0.49 4131 2004 92 116 WT55 250 55 443 186 257 2964 0.14 4041 0.46 3382 2385 99 117 WT58 275 65 524 204 320 2766 0.14 4198 0.5 3361 2568 92 116 WT53 300 65 524 195 329 2785 0.14 4152 0.49 n/a n/a 93 115 WT48 325 77 620 214 406 2689 0.14 4340 0.51 n/a n/a 90 117 WTSI 350 78 628 224 405 2883 0.14 4270 0.53 n/a n/a 96 119 w'49 375 74 596 208 388 2742 0.14 4198 0.51 n/a n/a 91 116 Testing of Specimens from Capsule X

5-12 Table 5-7 Instrumented Charpy Impact Test Results for the Beaver Valley Unit 2 Surveillance Weld Metal Irradiated to a Fluence of 5.601 x 1019 n/cm 2 (E>1.0 MeV)

Normalized Energies Charpy (ft-lb/in2 ) Yield Time to Time to Fast Test Energy Char Max Pro Load Yield Max. Max. Fract. Arrest Yield Flow Sample Temp. ED PY . Pr PGY tGy Load tN, Load PF Load Stress Stress No. (OF) (ft-lb) ED/A Es,/A EWA (lb) (msec) P,, (lb) (msec) (lb) PA (1b) ay (ksi) (ksi)

WVW51 -75 3 24 13 12 1267 0.09 1516 0.12 1516 0 42 46 WVW53 -50 9 73 27 46 2756 0.13 2870 0.15 2857 126 92 94 WW54 -25 7 56 22 35 2357 0.12 2473 0.14 2470 0 78 80 NVW52 -25 19 153 94 59 2695 0.15 3951 0.32 3917 0 90 III WW55 -10 6 48 15 34 1521 0.1 1624 0.12 1622 126 51 52 WW48 0 56 451 244 207 3522 0.15 4611 0.52 4497 489 117 135 NVWV46 10 88 709 326 383 3154 0.14 4557 0.68 3728 1354 105 128 WW59 25 97 782 325 457 3237 0.14 4461 0.68 3616 1476 108 128 NVW57 50 41 330 165 166 3203 0.14 4305 0.40 4246 1190 107 125 WW50 50 79 637 314 322 3114 0.14 4442 0.68 4290 2097 104 126 WW58 75 113 910 318 593 3053 0.14 4454 0.68 3097 2008 102 125 WW47 100 117 943 305 638 2703 0.13 4331 0.68 2587 1587 90 117 WW60 150 129 1039 302 738 2958 0.13 4291 0.67 n/a n/a 99 121 WW56 175 130 1047 296 752 2707 0.13 4191 0.68 n/a n/a 90 115 WW49 225 139 1120 293 827 2882 0.14 4127 0.68 n/a n/a 96 117 Testing of Specimens from Capsule X

5-13 Table 5-8 Instrumented Charpy Impact Test Results for the Beaver Valley Unit 2 Heat Affected Zone Material Irradiated to a Fluence of 5.601 x 10"9 n/cm 2 (E>1.0 MeV)

- _-_ -:---  : -- Normalized Energies -

Charpy - -- (ft-lb/in2 ) - Yield Time to Time to Fast

- Test--- -Energy- __ - Load Yield Max. Max. Fract. Arrest Yield Flow Sample: Temp.  : ED -CharPY- Max. Prop. PGY tcy Load t6, Load PF Load Stress cy Stress No. (°I) (ft-lb) EM/A Ep/A (b) lED/A (msec) P,, (lb) (msec) (lb) PA (lb) (ksi) (ksi)

WH48 -90 15 121 67 54 2988 0.13 4255 0.22 4247 636 99 121 WH55 -50 13 105 55 49 4003 0.15 4601 0.19 4596 0 133 143 WH50 -25 25 201 72 129 3586 0.14 4590 0.22 4588 1195 119 136 WH49 0 43 346 193 153 3615 0.14 4764 0.42 4741 2157 120 140 WH58 25 45 363 215 147 3345 0.15 4684 0.47 4655 1235 III 134 WH53 50 58 467 171 297 3572 0.14 4547 0.39 4186 1626 119 135 WH51 75 43 346 157 190 2960 0.13 4514 0.39 4414 265 99 124 WH54 100 87 701 244 457 3618 0.15 4621 0.52 4165 1950 120 137 WH47 125 63 508 200 307 3342 0.14 4457 0.46 4261 3009 III 130 WH52 135 61 491 207 284 2967 0.13 4317 0.48 3279 1420 99 121 WH46 150 85 685 212 472 3564 0.14 4447 0.47 2745 1691 119 133 WH59 175 87 701 216 485 2766 0.13 4359 0.51 n/a n/a 92 119 WH60 200 122 983 312 671 3368 0.14 4374 0.67 n/a n/a 112 129 WH57 225 137 1104 324 780 3178 0.14 4576 0.68 n/a n/a 106 129 WH56 250 137 1104 317 787 2947 0.14 4575 0.68 n/a _ 98 125 Testing of Specimens from Capsule X

5-14 Table 5-9 Effect of Irradiation to 5.601 x 1019 n/cm 2 (E>1.0 MeV) on the Capsule X Toughness Properties of the Beaver Valley Unit 2 Reactor Vessel Surveillance Materials Average 30 (ft-lb)(') Average 35 mil Lateral(b) Average 50 ft-lb(') Average Energy Absorption(')

Material Transition Temperature ( 0F) Expansion Temperature ( 0F) Transition Temperature (1F) at Full Shear (ft-lb)

Unirradiated Irradiated AT Unirradiated Irradiated AT Unirradiated Irradiated AT Unirradiated Irradiated AE Intermediate Shell Plate B9004-2 35.6 133.6 98.0 82.9 180.4 97.5 80.3 185.3 105.0 95 81 14 (Long.)

Internediate Shell Plate B9004-2 39.8 143.9 104.1 90.8 179.7 88.9 91.2 212.7 121.5 79 74 5 (Trans.)

Weld Metal -39.8 -16.9 22.9 -19.8 8.4 28.2 -21.7 10.0 31.7 139 133 6 (Heat # 83652)

Heat Affected -87.2 -1.9 85.3 -21.5 65.4 86.9 -41.8 49.8 91.6 91 114 0 Zone

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 derined as the value read from the curve fit through the data points of the Charpy tests (see Figures 5-2, 5-5, 5-8 and 5-1 1).

Testing of Specimens from Capsule X

5-15 Table 5-1.0 Comparison of the Beaver Valley Unit 2 Surveillance Material 30 ft-lb Transition Temperature Shifts and Upper Shelf Energy Decreases with Regulatory Guide 1.99, Revision 2, Predictions 30 ft-lb Transition Upper Shelf Energy Fluence(d) Temperature Shift Decrease Maiterial Capsule (x 1019 n/cm 2, E > 1.0 MeV) Predicted Measured Predicted Measured (OF) ( F8) (b) (%) ( (%)(C)

U 0.6082 31.9 24.0 19 0 Intermediate Shell V 2.629 46.6 56.0 24 11 Plate 119004-2 (Longitudina) W 3.625 49.4 71.0 26 1 X 5.601 52.7 98.0 29 15 U 0.6082 31.9 17.7 19 0 Intermediate Shell V 2.629 46.6 46.1 24 4 Plate E19004-2 (Transverse) w 3.625 49.4 63.4 26 5 X 5.601 52.7 104.1 29 6 U 0.6082 32.7 4.1 19 4 Surveillance V 2.629 47.8 25.7 26 2 Program Weld Metal W 3.625 50.7 6.0 28 2 X 5.601 54.1 22.9 31 4 U 0.6082 O(d) --- 0 V 2.629 -- 41.2 - -- 4 Heat Affected Zone V 2.629 41.2_4 Material W 3.625 51.3 --- 0 X 5.601 85.3 0 Notes:

(a) Based on Regulatory Guide 1.99, Revision 2 [Ref. 1], methodology using the mean weight percent values of copper and nickel of the surveillance material.

(b) Calculated using measured Charpy data plotted using CVGRAPH, Version 5.0.2 (See Appendix C)

(c) Values are based on the definition of upper shelf energy given in ASTM E185-82 [Ref. 12].

(d) The fluence values presented here are the calculated values, not the best estimate values.

Testing of Specimens from Capsule X

5-16 Table 5-11 Tensile Properties of the Beaver Valley Unit 2 Capsule X Reactor Vessel Surveillance Materials Irradiated to 5.601 x 1019 n/cm 2 (E > 1.0 MeV)

Material Sample Test 0.2% Yield Ultimate Fracture Fracture Fracture Uniform Total Reduction Number Temp. Strength Strength Load Stress Strength Elongation Elongation in Area

( 0F) (ksi) (ksi) (kip) (ksi) (ksi) ( (%) (%)

WL1O 175 80.0 99.5 3.24 176.0 66.0 9.4 20.9 62 Intermediate Shell B9004-2 WLI1 275 76.4 96.4 3.08 167.0 62.6 10.1 22.1 62 (Longitudinal)

WL12 550 70.3 98.6 3.26 151.5 66.4 10.1 21.6 56 WTIO 150 80.0 99.8 3.36 156.2 68.4 10.6 22.0 56 Intermediate Shell B9004-2 WTI 1 245 77.8 96.8 3.31 157.6 67.3 9.9 20.3 57 (Transverse)

WT12 550 72.8 99.0 3.69 159.4 75.2 11.9 20.6 53 WW10 70 78.9 93.0 2.73 175.6 55.6 10.5 26.3 68 Surveillance WW 1 125 77.6 90.1 2.53 183.4 51.4 9.8 25.2 72 WW12 550 69.3 89.0 2.77 163.1 56.3 10.1 23.7 65 Testing of Specimens from Capsule X

5-17 INTERMEDIATE SHELL PLATE B9004-2 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/29/2005 03:09 PM Data Set(s) Plotted Cv:rve Plant Capsule Material Ori. Heat #

1. BEAVER VALLEY 2 UNIRR SA533BI LT C0544-2 BEAVER VALLEY 2 U SA533BI LT C0544-2 1! BEAVER VALLEY 2 V SA533BI LT C0544-2 BEAVER VALLEY 2 w SA533BI LT C0544-2

.; BEAVER VALLEY 2 x SA533BI LT C0544-2 300 -

250 4 200 :

a 10050 - _

-300 2010 -100 0 100 200 300 400 500 500 Temperature In Dog F 0 Set I a Set 2 ° Set 3 A Set 4 v Set 5 Results Curve Fluence LSE USE d-USE T 530 d-T 30 T @50 d-T @g50 1 2. 2 95.0 .0 35. 6 .0 80. 3 .0 2 2. 2 105.0 10.0 59. 6 24.0 115.5 35.2 3 2. 2 85.0 -10.0 91.6 56.0 146.6 66.3 4 2. 2 94.0 -1.0 106.6 71.0 158. 9 78. 6 5 2. 2 81.0 -14.0 133.6 98.0 185.3 105.0 Figure 5-1 Charpy V-Notch Impact Energy vs. Temperature for Beaver Valley Unit 2 Reactor Vessel Intermediate Shell Plate B9004-2 (Longitudinal Orientation)

Testing of Specimens from Capsule X

5-18 INTERMEDIATE SHELL PLATE B9004-2 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 10/28/2005 11:27 AM Data Set(s) Plotted Curve Plant Capsule Material OrL Heat #

1 BEAVER VALLEY 2 UNIRR SA533BI LT C0544-2 2 BEAVER VALLEY 2 U SA533BI LT C0544-2 3 BEAVER VALLEY 2 V SA533BI LT C0544-2 4 BEAVER VALLEY 2 w SA533BI LT C0544-2 5 BEAVER VALLEY 2 x SA533BI LT C0544-2 200 150 E

.2 a 100 0

50 o *-

-300 0 300 600 Temperature In Dog F 0 Set I Set 2 0 Set 3 A Set 4 v Set 5 Results Curve Fluence LSE USE d-USE T @35 d-T @35 1.0 77.9 .0 82.9 .0 2 1.0 79. 8 1.9 107.9 25.0 3 1.0 73.7 -4.2 142.0 59. 1 4 1.0 60. 9 -17.0 173.2 90.3 5 1.0 68. 9 -9.0 180.4 97. 5 Figure 5-2 Charpy V-Notch Lateral Expansion vs. Temperature for Beaver Valley Unit 2 Reactor Vessel Intermediate Shell Plate B9004-2 (Longitudinal Orientation)

Testing of Specimens from Capsule X

5-19 INTERMEDIATE SHELL PLATE B9004-2 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/29/2005 03:23 PM Data Set(s) Plotted Curve Plant Capsule Material On. Heat #

I BEAVER VALLEY 2 UNIRR SA533BI LT C0544-2 2 BEAVER VALLEY 2 U SA533BI LT C0544-2 I BEAVER VALLEY 2 V SA533BI LT C0544-2 at BEAVER VALLEY 2 w SA533BI LT C0544-2

'i BEAVER VALLEY 2 x SA533BI LT C0544-2 125 100 75 0

X en1 A! 50 25 0 4-

-300 -200 -100 0 100 200 300 400 500 600 Temperature In Deg F 0 SetI a Set 2

• Set 3 A Set 4  ; Set 5 Results Curve Fluence LSE USE d-USE T @50 d-T 50

.0 100.0 .0 115.4 .0 2 .0 100.0 .0 125. 1 9.7 3 .0 100.0 .0 165.0 49.6 4 .0 100.0 .0 170.2 54. 8 5 .0 100.0 .0 175. 1 59. 7 Figure 5-3 Charpy V-Notch Percent Shear vs. Temperature for Beaver Valley Unit 2 Reactor Vessel Intermediate Shell Plate B9004-2 (Longitudinal Orientation)

Testing of Specimens from Capsule X

5-20

• INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 10/25/2005 11:06 AM Data Set(s) Plotted Curve Plant Capsule Material On. Heat #

I BEAVER VALLEY 2 UNIRR SA533BI TL C0544-2 2 BEAVER VALLEY 2 U SA533BI TL C05442 3 BEAVER VALLEY 2 V SA533BI TL C0544-2 4 BEAVER VALLEY2 w SA533BI TL C0544-2 5 BEAVER VALLEY 2 x SA533BI TL C0544-2 300 250

, 200 0

j;150 z

- 100 50 0 4-

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F 0 Set 1 a Set 2 0 Set 3 A Set 4 v Set 5 Results Curve Fluence LSE USE d-USE T @30 d-T @30 T @50 d-T @C50

2. 2 79. 0 .0 39.8 .0 91.2 .0 2 2. 2 87.0 8.0 57.5 17.7 122.6 31.4 3 2. 2 76.0 -3.0 85.9 46. 1 151.9 60. 7 4 2.2 75.0 -4.0 103.2 63.4 163.6 72.4 5 2. 2 74.0 -5.0 143.9 104. 1 212.7 121.5 Figure 5-4 Charpy V-Notch Impact Energy vs. Temperature for Beaver Valley Unit 2 Reactor Vessel Intermediate Shell Plate B9004-2 (Transverse Orientation)

Testing of Specimens from Capsule X

5-21 INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

CVGRAPH 5.0.2 Hypcrbolic Tangent Curve Printed on 09/01/2005 03:58 PM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat #

BEAVER VALLEY 2 UNIRR SA533BI TL C0544-2 2 BEAVER VALLEY 2 U SA533B1 TL C0S44-2 3 BEAVER VALLEY 2 V SA533BI TL C0544-2 4 BEAVER VALLEY 2 w SA533BI TL C0544-2 5 BEAVER VALLEY 2 x SA533BI TL C0544-2 200 150

.2

.2 ZL 100 I

Lb

-300 0 300 600 Temperature in Deg F o Set1 o Set 2 o Set 3 A Set 4 -' Set 5 Results Curve Fluence [SE USE d-USE T @35 d-T @35 1.0 64. 3 .0 90.8 .0 2 1.0 64.0 -.3 102.3 11.5 3 1.0 72.4 8.1 139.0 48.2 4 1.0 56.8 -7.5 178.9 88. 1 5 1.0 57.4 -6.9 179.7 88.9 Figure 5-5 Charpy V-Notch Lateral Expansion vs. Temperature for Beaver Valley Unit 2 Reactor Vessel Intermediate Shell Plate B9004-2 (Transverse Orientation)

Testing of Specimens from Capsule X

5-22 INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/29/2005 04:06 PM Data Set(s) Plotted Curve Plant Capsule Material Oril. Heat #

3 BEAVER VALLEY 2 UNIRR SA533BI TL C0544-2 2 BEAVER VALLEY 2 U SA533BI TL C0544-2 3 BEAVER VALLEY 2 V SA533BI TL C0544-2 4 BEAVER VALLEY 2 W SA533BI TL C0544-2 5 BEAVER VALLEY 2 X SA533BI TL C0544-2 1251 _

100 - _

m 75 _

LI a 50 _

25 -

0

-300 -2011 -100 0 100 200 300 400 500 600 Temperature In Dog F 0 Set I o Set 2 0 Set 3 a Set 4 v Set 5 Results Curve Fluence LSE USE d-USE T 50 d-T @50

.0 100.0 .0 105.0 .0 2 .0 100.0 .0 122.1 17.1 3 .0 100.0 .0 157.1 52.1 4 .0 100.0 .0 156.3 51.3 5 .0 100.0 .0 175.1 70.1 Figure 5-6 Charpy V-Notch Percent Shear vs. Temperature for Beaver Valley Unit 2 Reactor Vessel Intermediate Shell Plate B9004-2 (Transverse Orientation)

Testing of Specimens from Capsule X

5-23 SURVEILLANCE PROGRAM WELD METAL CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/30/2005 10:20 AM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat #

l BEAVER VALLEY 2 UNIRR SAW NA 83642 2 BEAVER VALLEY 2 U SAW NA 83642 3 BEAVER VALLEY 2 V SAW NA 83642 4 BEAVER VALLEY 2 W SAW NA 83642 5 BEAVER VALLEY 2 x SAW NA 83642 300 250

_ 200 A 150 a

mu

100 50 0 4W

-300 -200 -100 0 100 200 300 400 500 600 Temperature In Dog F 0 SetI a Set 2 0 Set 3 a Set 4 v Set 5 Results Curse Fluence LSE USE d-USE T 030 d-T @30 T @50 d-T @S0 2.2 139.0 .0 -39.8 .0 -21.7 .0 2 2.2 134.0 -5.0 -35.7 4. 1 -10.6 11.1 3 2.2 136.0 -3.0 -14. 1 25.7 7.7 29.4 4 2.2 136. 0 -3.0 -33.8 6. 0 -1.4 20.3 5 2.2 133.0 -6.0 - 16.9 22.9 10.0 31.7 Figure 5-7 Charpy V-Notch Impact Energy vs. Temperature for Beaver Valley Unit 2 Reactor Vessel Weld Metal Testing of Specimens from Capsule X

5-24 SURVEILLANCE PROGRAM WELD METAL CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 09/02/2005 09:27 AM Data Set(s) Plotted Curve Plantt Capsule Material OrL Heat #

t BEA1/ERVALLEY 2 UNIRR SAW NA 831542 2 BENAVER VALLEY 2 U SAW NA 831542 3 BEA1VERVALLEY2 V SAW NA 831542 4 BEA1 VER VALLEY 2 W SAW NA 831542 5 BEA1VERVALLEY2 X SAW NA 831642 200 150

.2 S 100 -

S 50

.300 0 300 600 Temperature In Deg F o Set I a Set 2 o Set 3 a Set 4 ' Set 5 Results Curve Fluence LSE USE d-USE T @35 d-T @3S 1.0 79. 8 .0 -19.8 .0 2 1.0 82.6 2.8 -6.5 13.3 3 1.0 86. 3 6.5 7.9 27.7 4 1.0 77.4 -2.4 9.0 28.8 5 1.0 83.8 4.0 8.4 28.2 Figure 5-8 Charpy V-Notch Lateral Expansion vs. Temperature for Beaver Valley Unit 2 Reactor Vessel Weld Metal Testing of Specimens from Capsule X

5-25 SURVEILLANCE PROGRAM WELD METAL CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/30/2005 10:50 AM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat#

I BEAVER VALLEY 2 UNIRR SAW NA 83642 2 BEAVER VALLEY 2 U SAW NA 83642 3 BEAVER VALLEY 2 V SAW NA 83642 4 BEAVER VALLEY 2 W SAW NA 83642 5 BEAVER VALLEY 2 X SAW NA 83642 125 100 a,

-C 75 C,

a.

50 25 0o4-

-300 -200 .100 0 100 200 300 400 500 600 Temperature in Dog F 0 SetI a Set 2 0 Set 3 a Set 4 - Set 5 Results Curve Fluence LSE USE d-USE T @50 d-T @50

.0 100.0 .0 -8.6 .0 2 .0 100.0 .0 -7.5 1. 1 3 .0 100.0 .0 15.8 24.4 4 .0 100.0 .0 17.7 26.3 5 .0 100.0 .0 15.4 24.0 Figure 5-9 Charpy V-Notch Percent Shear vs. Temperature for Beaver Valley Unit 2 Reactor Vessel Weld Metal Testing of Specimens from Capsule X

5-26 HEAT AFFECTED ZONE CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/30/2005 02:32 PM Data Set(s) Plotted Curve Plant Capsule Material OCr. Heat #

BEAVER VALLEY 2 UNIRR SA533B1 NA C0544-2 2 BEAVER VALLEY 2 U SA533BI NA C0544-2 3 BEAVER VALLEY 2 V SA533BI NA C0544-2 4 BEAVER VALLEY 2 w SA533BI NA C0544-2 S BEAVER VALLEY 2 x SA533B1 NA C0544-2 300 250 jg 200 0

IL A 150 B 100 50

-300 -200 -100 0 100 200 300 400 500 600 Temperature In Deg F 0 Set I a Set 2 0 Set 3 & Set 4 v Set 5 Results Curve Fluence LSE USE d-USE T @30 d-T 30 T @50 d-T @30

2. 2 91.0 .0 -87.2 .0 -41.8 .0 2 2.2 109.0 is.0 -89.2 -2.0 -45.0 -3.2 3 2. 2 87.0 -4.0 -46.0 41.2 -14. 1 27. 7 4 2. 2 104.0 13.0 -35.9 51.3 4.4 46.2 S 2. 2 114.0 23.0 -1.9 85.3 49. 8 91.6 Figure 5-10 Charpy V-Notch Impact Energy vs. Temperature for Beaver Valley Unit 2 Reactor Vessel Heat Affected Zone Material Testing of Specimens from Capsule X

5-27 HEAT AFFECTED ZONE CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 09/01/2005 02:44 PM Data Set(s) Plotted Curve Plant Capsule Material On. Heat #

BEAVER VALLEY 2 UNIRR SA533BI NA C0544-2 BEAVER VALLEY 2 U SA533BI NA C0544-2

5 BEAVER VALLEY 2 V SA533BI NA C0544-2 4 BEAVER VALLEY 2 w SA533BI NA C0544-2 BEAVER VALLEY 2 x SA533BI NA C0544-2 200 M

I 0

a EL 0 , - _ _ _ _ _

-300 0 300 600 Temperature In Deg F 0 Set 1 a Set 2 0 Set 3 a S4et 4 q Set 5 Results Curve Fluence [SE USE d-USE T @35 d-T @35 1.0 60.6 .0 -21.5 .0 2 1.0 64.5 3.9 - 29.0 -7. 5 3 1.0 61.0 .4 -10.0 11.5 4 1.0 68. 1 7.5 28.2 49. 7 5 1.0 143.0 82.3 65.4 86.9 Figure 5-1:1 Charpy V-Notch Lateral Expansion vs. Temperature for Beaver Valley Unit 2 Reactor Vessel Heat Affected Zone Material Testing of Specimens from Capsule X

5-28 HEAT AFECTED ZONE CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/30/2005 02:35 PM Data Set(s) Plotted Curve Plant Capsule Material OrL Heat #

1 BEAVER VALLEY 2 UNIRR SA533BI NA C0544-2 2 BEAVER VALLEY 2 U SA533BI NA C0544-2 3 BEAVER VALLEY 2 V SA533BI NA C0544-2 4 BEAVER VALLEY 2 w SA533BI NA C0544-2 5 BEAVER VALLEY 2 x SA533BI NA C0544-2 125 100 I-75 Is0 U)

V 9

IE 50 25 o 4-

-300 -200 -100 0 100 200 300 400 500 600 Temperature In Dog F o Set 1 a Set 2 0 Set 3 a Set 4 v Set 5 Results Curve fluence LSE USE d-USE T @50 d-T @50

.0 100.0 .0 7. 9 .0 2 .0 100.0 .0 - 26. 1 -34. 0 3 .0 100.0 .0 2.0 -5.9 4 .0 100.0 .0 -2.0 -9.9 5 .0 100.0 .0 19.8 11.9 Figure 5-12 Charpy V-Notch Percent Shear vs. Temperature for Beaver Valley Unit 2 Reactor Vessel Heat Affected Zone Material Testing of Specimens from Capsule X

5-29 WL49, -500 F WL59, 25 0F WL60, 75 0F WL58, 100 0F WL47, 125 0F WL46, 150TF WL48, 175 0F WL55, 200 0F WL56, 225 0F WL51, 250 0F WL52, 275 0F WL57, 280 0F WL50, 325°F WL54, 350 0F WL53, 375 0F Figure 5-13 Charpy Impact Specimen Fracture Surfaces for Beaver Valley Unit 2 Reactor Vessel Intermediate Shell Plate B9004-2 (Longitudinal Orientation)

Testing of Specimens from Capsule X

5-30 WT60, -50F WT57, 25 0F WT56, 50 0F WT50, 75 0F WT46, 100-F WT59, 125-F WT54, 150 0F WT47, 175 0F WT52, 200 0F WT55, 250 0F WT58, 275 0F WT53, 300 0F WT48, 325 0F WT51, 350 0F WT49, 375 0F Figure 5-14 Charpy Impact Specimen Fracture Surfaces for Beaver Valley Unit 2 Reactor Vessel Intermediate Shell Plate B9004-2 (Transverse Orientation)

Testing of Specimens from Capsule X

5-31 WW51, F WW53,-500 F WW54,-250 F WW52,-250 F WW55, -10F WW48, 0F WW46, 100 F WW59, 25 0 F WW57, 50 0 F WW50, 50 0F WW58, 75 0F WW47, 100-F WW60, 150OF WW56, 175-F WW49, 225 0F Figure 5-15 Charpy Impact Specimen Fracture Surfaces for Beaver Valley Unit 2 Reactor Vessel Weld Metal Testing of Specimens from Capsule X

5-32 WH48, -90 0F WH55,-50 0 F WH50, F WH49, 0F WH58, 250 F WH53, 50 0F WH51, 75-F WH54, 100F WH47, 125 0F WH52, 135 0F WH46, 150 0F WH59, 175 0F WH60, 200 0F WH57, 225 0F WH56, 250 0F Figure 5-16 Charpy Impact Specimen Fracture Surfaces for Beaver Valley Unit 2 Reactor Vessel Heat Affected Zone Material Testing of Specimens from Capsule X

5-33 120 ULTIMATE YIELD STRENGTH 100 i,, 80-

'w an 60 l 0.2% YIELD STRENGTH 1240 -

20 -

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

Legend: A and o are Unirradiated Aand

• are Irradiated to 5.601 x IO'9 n/cm2 (E > 1.0 MeV) 80 REDUCTION IN AREA 70 d Ar-

_ 60 -

> 50 -

z40 -

u 30 TOTAL ELONGATION 020 -

10 q UNIFORM UNIFORM 0 -

0 100 200 300 400 500 600 TEMPERATURE ( F)

Figure 5-17 Tensile Properties for Beaver Valley Unit 2 Reactor Vessel Intermediate Shell Plate B9004-2 (Longitudinal Orientation)

C(9)\

Testing of Specimens from Capsule X

I 5-34 120 ULTIMATE YIELD STRENGTH 100 A.

80 Hi 60 0.2% YIELD STRENGTH ct4 w" 40 20 0 I, I I 0 100 200 300 4400 500 600 TEMPERATURE( F)

Legend: A and o are Unirradiated A and

• are Irradiated to 5.601 x 10'9 n/cm 2 (E > 1.0 MeV) 80 REDUCTION INAREA 70 -

60 -

4 A. A 50 -

I-

-j 40 F-Q- 30 TOTAL ELONGATION In 0- ~~ *~

20 - -V 10 - _ - * . 0, 0- UNIFORM UNIFORM 0 100 200 300 400 500 600 TEMPERATURE ( F)

Figure 5-18 Tensile Properties for Beaver Valley Unit 2 Reactor Vessel Intermediate Shell Plate B9004-2 (Transverse Orientation)

C-oZ-Testing of Specimens from Capsule X

w 5-35 120 ULTIMATE TENSILE STRENGTH 100

, 80 aw w 60 0.2% YIELD STRENGTH I.-

"'40 20 0

0 100 200 300 400 500 600 TEMPERATURE( F)

Legend: A and o are Unirradiated Aand

• are Irradiated to 5.601 x 1018 n/cm 2 (E > 1.0 MeV) 80 70 I _I

_60-REDUCTION IN AREA

50

z. 40-I--

S- 30 TOTAL ELONGATION 020 10 UNI FORM ELONGATION 0

0 100 200 300 400 500 600 TEMPERATURE ( F)

Figure 5-19 Tensile Properties for Beaver Valley Unit 2 Reactor Vessel Weld Metal Testing of Specimens from Capsule X

5-36 Specimen WL-1O Tested at 1750 F M1 I 0 1j UL I Specimen WL-1 1 Tested at 2750 F Specimen WL-12 Tested at 550'F Figure 5-20 Fractured Tensile Specimens from Beaver Valley Unit 2 Reactor Vessel Intermediate Shell Plate B9004-2 (Longitudinal Orientation)

Testing of Specimens from Capsule X

I w 5-37 Specimen WT-10 Tested at 150°F u_i!1 I1 I l_>=

fi__ -gd ~ j ~

x 9 bt =-A wk7 u, _- lyl1=_

u~~~~~~~~~O I_;*1 Specimen WT-I 1 Tested at 2450 F Specimen WT-12 Tested at 550'F Figure 5-21 Fractured Tensile Specimen from Beaver Valley Unit 2 Reactor Vessel Intermediate Shell Plate B9004-2 (Transverse Orientation)

Testing of Specimens from Capsule X

5-38 Specimen WW-1O Tested at 700 F Specimen WW-11 Tested at 125 0 F Specimen WW-12 Tested at 5500 F Figure 5-22 Fractured Tensile Specimen from Beaver Valley Unit 2 Reactor Vessel Weld Metal Testing of Specimens from Capsule X

5-39 BEAVER VALLEY #2 WXCAPSULE 100 80

)5

- 60 w

40 WL-10 175 F 20 0

0 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN, INfN BEAVER VALLEY #2 WXCAPSULE 100 80 05 60 40 WL-1 1 275 F 20 0 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN, INIIN Figure 5-2.1 Engineering Stress-Strain Curves for Beaver Valley Unit 2 Intermediate Shell Plate B9004-2 Tensile Specimens WL-10 and WL-11 (Longitudinal Orientation)

Testing of Specimens from Capsule X

5-40 BEAVER VALLEY #2 WXCAPSULE 100 80 6

so ro 0

40 WL-12 550'F 20 0

a 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN. IN/IN Figure 5-24 Engineering Stress-Strain Curve for Beaver Valley Unit 2 Intermediate Shell Plate B9004-2 Tensile Specimen WL-12 (Longitudinal Orientation)

Testing of Specimens from Capsule X

52-1 BEAVER VALLEY #2 WXCAPSULE 100 80 In o6 60 V) ul al:

U) 40 WT-10 150 F 20 0

0 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN. ININ BEAVER VALLEY #2 W CAPSULE 100 80 -

to CO 60 W

lo n5 40 WT-1 1 245 F 20 0

0 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN. IN/IN Figure 5-25 Engineering Stress-Strain Curves for Beaver Valley Unit 2 Intermediate Shell Plate B9004-2 Tensile Specimens WT-10 and WT-11 (Transverse Orientation)

Testing of Specimens from Capsule X

5-42 BEAVER VALLEY #2 WX-CAPSULE 100 80 c803 (n

w 40 -

WT-12 550 F 20 0

0 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN, MIN Figure 5-26 Engineering Stress-Strain Curve for Beaver Valley Unit 2 Intermediate Shell Plate B9004-2 Tensile Specimen WT-12 (Transverse Orientation)

Testing of Specimens from Capsule X

5-13 BEAVER VALLEY #2 WXCAPSULE 100 80 05

,, 60 0,

40 WW.10 70 F 20 0 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN, INIIN BEAVER VALLEY #2 XCAPSULE 100 80 V5 a 60 02 40 WW-1 1 125F 20 0

0 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN, INIIN Figure 5-2 7 Engineering Stress-Strain Curves for Beaver Valley Unit 2 Weld Metal Tensile Specimens WW-10 and WW-11 Testing of Specimens from Capsule X

5-44 BEAVER VALLEY #2 X CAPSULE 100 80 05 ui 60 Vn w1 U,

40 WW-12 550 F 20 0

0 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN, N/IN Figure 5-28 Engineering Stress-Strain Curve for Beaver Valley Unit 2 Weld Metal Tensile Specimen WW-12 Testing of Specimens from Capsule X

6-1 6 RADIATION ANALYSIS AND NEUTRON DOSIMETRY

6.1 INTRODUCTION

(REPLACED ENTIRE SECTION)

This section describes a discrete ordinates S,, transport analysis performed for the Beaver Valley Unit 2 reactor to determine the neutron radiation environment within the reactor pressure vessel and surveillance capsules. In this analysis, fast neutron exposure parameters in terms of fast neutron fluence (E > 1.0 Me'V) and iron atom displacements (dpa) were established on a plant and fuel cycle specific basis. An evaluation of the most recent dosimetry sensor set from Capsule X, withdrawn at the end of the eleventh plant operating cycle, is provided. In addition, to provide an up-to-date database applicable to the Beaver Valley Unit 2 reactor, sensor sets from previously withdrawn capsules (U, V, 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 54 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 year<, however, it has been suggested that an exposure model that accounts for differences in neutron energy spectra between surveillance capsule locations and positions within the vessel wall could lead to an improvement in the uncertainties associated with damage trend curves and improved accuracy in the evaluation of damage gradients through the reactor vessel wall.

Because of this potential shift away from a threshold fluence toward an energy dependent damage function for data correlation, ASTM Standard Practice E853-01, "Analysis and Interpretation of Light-Water Reaclor Surveillance Results,"[Ref. 21] recommends reporting displacements per iron atom (dpa) along with fluence (E > 1.0 MeV) to provide a database for future reference. The energy dependent dpa function to be used for this evaluation is specified in ASTM Standard Practice E693-01, "Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements per Atom." [Ref. 22] 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." [Ref. 1]

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" [Ref. 23]. Additionally, the methods used to develop the calculated pressure vessel fluence follow 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," May 2004 [Ref. 24]. The dosimetry evaluations use the methodology described in WCAP-16083-NP, "Benchmark Testing of the FERRET Code for Least Squares Evaluation of Light Water Reactor Dosimetry," May 2004 [Ref. 25].

Radiation Analysis and Neutron Dosimetry

6-2 6.2 DISCRETE ORDINATES ANALYSIS A plan view of the Beaver Valley Unit 2 reactor geometry at the core midplane 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 107°, 2870, 3430 (170 from the core cardinal axes) and 1100, 2900, 340° (200 from the core cardinal axes). The stainless steel specimen containers are 1.182-inch by I-inch and are approximately 56 inches in height. The containers are positioned axially such that the test specimens are centered on the core midplane, thus spanning the central 5 feet of the 12-foot high reactor core.

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

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

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

0(r,O,z) = 0(r,0)

• 5b(r, z) where 4(rO,z) is the synthesized three-dimensional neutron flux distribution, 4(r,0) is the transport solution in rO geometry, 4(rz) is the two-dimensional solution for a cylindrical reactor model using the actual axial core power distribution, and +(r) is the one-dimensional solution for a cylindrical reactor model using the same source per unit height as that used in the rO two-dimensional calculation. This synthesis procedure was carried out for each operating cycle at Beaver Valley Unit 2.

For the Beaver Valley Unit 2 transport calculations, two octant symmetric r,0 models were developed and are depicted in Figure 6-1. The first model contained the shortened neutron pad (15° span) with no surveillance capsules, while the second contained the extended neutron pad (260 span) including the surveillance capsules. The latter model was used to perform surveillance capsule dosimetry evaluations and subsequent comparisons with calculated results, while the former model was used to generate the maximum fluence at the pressure vessel wall. In developing these analytical models, nominal design dimensions were employed for the various structural components. Likewise, water temperatures, and hence, coolant densities in the reactor core and downcomer regions of the reactor were taken to be representative of full power operating conditions. The coolant densities were treated on a fuel cycle specific basis. The reactor core itself was treated as a homogeneous mixture of fuel, cladding, water, and miscellaneous core structures such as fuel assembly grids, guide tubes, et cetera. The geometric mesh description of the rO reactor models consisted of 185 radial by 92 azimuthal intervals. Mesh sizes were chosen to assure that proper convergence of the inner iterations was achieved on a 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 rz model used for the Beaver Valley Unit 2 calculations is shown in Figure 6-2 and extends radially from the centerline of the reactor core out to a location interior to the primary biological shield and over an axial span from an elevation 1-foot below the active fuel to approximately 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 r,z geometric mesh description of this reactor model consisted of 149 radial by 178 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 rz calculations was also set at a value of 0.001.

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

The core power distributions used in the plant specific transport analysis were taken from the appropriate Beaver Valley Unit 2 fuel cycle design reports. The data extracted from the design reports represented cycle deperndent 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 3.1 [Ref. 26] and the BUGLE-96 cross-section library [Ref. 27]. The BUGLE-96 library provides a 67 group coupled neutron-gamma ray cross-section data set produced specifically for light water reactor (LWR) applications. In these analyses, anisotropic scattering was treated with a Ps 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 (170 and 200). These results, representative of the axial midplane of the active core, establish the calculated exposure of the surveillance capsules withdrawn to date as well as projected into the future. Similar information is provided in Table 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 four azimuthal locations (00, 150, 300, and 450). 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 Tables 6-1 and 6-2. These data tabulations include both plant and fuel cycle specific calculated neutron exposures at the end of the eleventh operating fuel cycle as well as projections to 17, 20, 25, 32, 48, and 54 EFPY. The projections were based on the assumption that the core power distributions and associated plant operating characteristics for cycle 12 were representative of plant operation to 17 effective full power years and that the preliminary cycle 13 core power distribution was applicable beyond 17 effective full power years.

The future projections listed in Tables 6-1 and 6-2 are also based on the assumption of a power uprate to 2900 MWt at 17 effective full power years.

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 I through 11, 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 four surveillance capsules withdrawn from the Beaver Valley Unit 2 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 Beaver Valley Unit 2 reactor.

Updated lead factors for the Beaver Valley Unit 2 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, V,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 capsules remaining in the reactor (Y and Z) the lead factor corresponds to the calculated fluence values at the end of cycle 11, the last completed operating fuel cycle for Beaver Valley Unit 2.

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

The direct comparison of measured versus calculated fast neutron threshold reaction rates for the sensors from Capsule X, that was withdrawn from Beaver Valley Unit 2 at the end of the eleventh fuel cycle, is summarized below.

Radiation Analysis and Neutron Dosimetry

6-5 Reaction Rates (rps/atom) M/C Reaction Measured Calculated Ratio 63 Cu(na)60Co 5.96E- 17 6.02E-17 0.99 54Fe(n,p) 54 Mn 6.21E-15 6.99E-15 0.89 58Ni(n,p) 5 8Co 9.05E1-15 9.88E-15 0.92 237 Np(n,f)137 Cs (Cd) 3.64E-13 4.09E- 13 0.89 Average: 0.92

% Standard Deviation: 5.1 The measured-to-calculated (M/C) reaction rate ratios for the Capsule X threshold reactions range from 0.89 to 0.99, and the average MWC ratio is 0.92 +/- 5.1% (la). 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 Beaver Valley Unit 2 reactor. These comparisons validate the current analytical results described in Section 6.2; therefore, the calculations are deemed applicable for Beaver Valley Unit 2.

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

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

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

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

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

The first phase of the methods qualification (PCA comparisons) addressed the adequacy of basic transport calculation and dosimetry evaluation techniques and associated cross-sections. This phase, however, did Radiation Aralysis and Neutron Dosimetry

6-6 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 Beaver Valley Unit 2 analysis was established from results of these three phases of the methods qualification.

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

The following summarizes the uncertainties developed from the first three phases of the methodology qualification. Additional information pertinent to these evaluations is provided in Reference 3.

l Capsule l Vessel JR l 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% 1 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 Beaver Valley Unit 2.

Radiation Analysis and Neutron Dosimetry

6-7 Figure 6-1 r,O Reactor Geometry with a 150 Neutron Pad at the Core Midplane 50 100 I50 200 250 300 2 Axis (cm)

Radiation Analysis and Neutron Dosimetry

6-8 Figure 6-1 (continued) r,O Reactor Geometry with a 260 Neutron Pad at the Core Midplane 200 -

160 A 120-80-40 1 I 0 50 100 150 200 250 300 Radiation Analysis and Neutron Dosimetry

6--9 Figure 6-2 Beaver Valley Unit 2 rz Reactor Geometry with Neutron Pad 225 175 125 75 2.5 -

P -25

-12!i -

-22!1 0 50 100 150 200 250 300 Lm)

Radiation Analysis and Neutron Dosimetry

6-10 Table 6-1 Calculated Neutron Exposure Rates And Integrated Exposures At The Surveillance Capsule Center Neutrons (E > 1.0 MeV)

Cumulative Cumulative Neutron Flux (E > 1.0 MeV)

Cycle Irradiation Irradiation [n/cm 2 -s]

Length Time Time Cycle [EFPS] [EFPS] [EFPY] 170 200 I 3.92E+07 3.92E+07 1.24 1.55E+l1 1.34E+1l 2 3.20E+07 7.12E+07 2.26 1.26E+l1 1.1IE+l1 3 3.90E+07 1.1 0E+08 3.49 1.41E+l1l 1.27E+l1 4 3.99E+07 1.50E+08 4.76 1.38E+11 1.23E+1 1 5 3.87E+07 1.89E+08 5.98 1.34E+11 1.16E+1l 6 3.88E+07 2.28E+08 7.21 1.25E1+11 1.14E+11 7 3.93E+07 2.67E+08 8.46 1.23E+11 1.09E+1l 8 4.15E+07 3.08E+08 9.77 1.20E+11 1.07E+1l 9 3.86E+07 3.47E+08 11.00 1.111E+11 9.64E+10 10 4.73E+07 3.94E+08 12.49 1.14E+l1 l.OlE+ll 11 4.56E+07 4.40E+08 13.94 1.19E+11 1.03E+11 12(Prj) 9.66E+07 5.37E+08 17.00 1.11E+11 9.57E+10 Future 9.47E+07 6.31E+08 20.00 1.21E+11 1.03E+1l Future 1.58E+08 7.89E+08 25.00 1.21E+11 1.03E+1l Future 2.21E+08 1.01E+09 32.00 1.21E+11 1.03E+ll Future 5.05E+08 1.52E+09 48.00 1.21E+11 1.03E+1l Future 1.89E+08 1.70E+09 54.00 1.211E+11 1.03E+11 Note: Neutron exposure values reported for the surveillance capsules are centered at the core midplane.

Radiation Analysis and Neutron Dosimetry

6-1l Table 6-1 cont'd Calculated Neutron Exposure Rates And Integrated Exposures At The Surveillance Capsule Center Neutrons (E > 1.0 MeV)

Cumulative Cumulative Neutron Fluence (E > 1.0 MeV)

Cycle Irradiation Irradiation [n/crm2 ]

Length Time Time Cycle [EFPS] [EFPS] [EFPY] 170 200 1 3.92E+07 3.92E+07 1.24 6.08E+18 5.26E+18 2 3.20E+07 7.12E+07 2.26 1.OlE+19 8.81E+18 3 3.90E+07 1.1OE+08 3.49 1.56E+19 1.38E+19 4 3.99E+07 1.50E+08 4.76 2.11E+19 1.87E+19 5 3.87E+07 1.89E+08 5.98 2.63E+19 2.31E+19 6 3.88E+07 2.28E+08 7.21 3.11E+19 2.76E+19 7 3.93E+07 2.67E+08 8.46 3.60E+19 3.19E+19 8 4.15E+07 3.08E+08 9.77 4.10E+19 3.63E+19 9 3.86E+07 3.47E+08 11.00 4.52E+19 4.OOE+19 10 4.73E+07 3.94E+08 12.49 5.06E+ 19 4.48E+19 11 4.56E+07 4.40E+08 13.94 5.60E+19 4.95E+19 12(Pr) 9.66E+07 5.37E+08 17.00 6.67E+19 5.87E+19 Future 9.47E+07 6.3 1E+08 20.00 7.81E+19 6.85E+19 Future 1.58E+08 7.89E1+08 25.00 9.72E+ 19 8.47E+ 19 Future 2.211E+08 1.01E+09 32.00 1.24E+20 1.07E+20 Future 5.05E+08 l.52E+09 48.00 1.85E+20 1.59E+20 Future 1.89E+08 1.70E+09 54.00 2.08E+20 1.79E+20 Note: Neutron exposure values reported for the surveillance capsules are centered at the core midplane.

Radiation Analysis and Neutron Dosimetry

6-12 Table 6-1 cont'd Calculated Neutron Exposure Rates And Integrated Exposures At The Surveillance Capsule Center IRON ATOM DISPLACEMENTS Cumulative Cumulative Displacement Rate Cycle Irradiation Irradiation [dpa/s]

Length Time Time Cycle [EFPS] [EFPS] [EFPY] 170 200 1 3.92E+07 3.92E+07 1.24 3.19E- 10 2.70E-10 2 3.20E+07 7.12E+07 2.26 2.54E-10 2.20E-10 3 3.90E+07 1.10E+08 3.49 2.85E-10 2.52E-10 4 3.99E+07 1.50E+08 4.76 2.79E-10 2.43E-10 5 3.87E+07 1.89E+08 5.98 2.73E-10 2.30E-10 6 3.88E+07 2.28E+08 7.21 2.53E-10 2.26E-10 7 3.93E+07 2.67E+08 8.46 2.49E-10 2.17E-10 8 4.15E+07 3.08E+08 9.77 2.43E-10 2.12E-10 9 3.86E+07 3.47E+08 11.00 2.25E-10 1.92E-10 10 4.73E+07 3.94E+08 12.49 2.30E-10 2.OOE-10 11 4.56E+07 4.40E+08 13.94 2.39E-10 2.05E-10 12(PIj) 9.66E+07 5.37E+08 17.00 2.25E-10 1.90E-10 Future 9.47E+07 6.31 E+08 20.00 2.45E-10 2.05E-10 Future 1.58E+08 7.89E+08 25.00 2.45E-10 2.05E-10 Future 2.21E+08 1.01E+09 32.00 2.45E- 10 2.05E-10 Future 5.05E+08 1.52E+09 48.00 2.45E-10 2.05E-10 Future 1.89E+08 1.70E+09 54.00 2.45E-10 2.05E-10 Note: Neutron exposure values reported for the surveillance capsules are centered at the core midplane.

Radiation Analysis and Neutron Dosimetry

6-13 Table 6-1 cont'd Calculated Neutron Exposure Rates And Integrated Exposures At The Surveillance Capsule Center IRON ATOM DISPLACEMENTS Cumulative Cumulative Displacements Cycle Irradiation Irradiation [dpa]

Length Time Time Cycle [EFPS] [EFPS] [EFPY] 170 200 1 3.92E+07 3.92E+07 1.24 1.25E-02 1.06E-02 2 3.20E+07 7.12E+07 2.26 2.06E-02 1.76E-02 3 3.90E+07 1.1OE+08 3.49 3.18E-02 2.74E-02 4 3.99E+07 1.50E+08 4.76 4.29E-02 3.71E-02 5 3.87E1+07 1.89E+08 5.98 5.34E-02 4.60E-02 6 3.88E+07 2.28E+08 7.21 6.32E-02 5.48E-02 7 3.93E+07 2.67E+08 8.46 7.30E-02 6.33E-02 8 4.15E1+07 3.08E+08 9.77 8.31 E-02 7.211E-02 9 3.86E+07 3.47E+08 11.00 9.18E-02 7.95E-02 10 4.73E+07 3.94E+08 12.49 1.03E-01 8.90E-02 11 4.56E+07 4.40E+08 13.94 1.14E-01 9.83E-02 12(Prj) 9.66E+07 5.37E+08 17.00 1.35E-01 1.17E-0 I Future 9.47E+07 6.31 E+08 20.00 1.59E-01 1.36E-01 Future 1.58E+08 7.89E+08 25.00 1.97E-01 1.68E-01 Future 2.21E+08 1.01lE+09 32.00 2.51 E-0 1 2.14E-0 I Future 5.05E+08 1.52E+09 48.00 3.75E-01 3.17E-0 I Future 1.89E+08 1.70E+09 54.00 4.22E-01 3.56E-01 Note: Neutron exposure values reported for the surveillance capsules are centered at the core midplane.

Radiation Analysis and Neutron Dosimetry

6-14 Table 6-2 Calculated Azimuthal Variation Of Maximum Exposure Rates And Integrated Exposures At The Reactor Vessel Clad/Base Metal Interface With Uprate to 2900 MWt at the Start of Cycle 13 Cumulative Cumulative Neutron Flux (E > 1.0 MeV)

Cycle Irradiation Irradiation [n/cm 2 -s]

Length Time Time Cycle [EFPS] [EFPS] [EFPY] 00 150 300 450 I 3.92E+07 3.92E+07 1.24 4.89E+10 2.73E+10 2.02E+10 1.38E+10 2 3.20E+07 7.12E+07 2.26 3.34E+10 2.09E+10 1.56E+l0 1.07E+10 3 3.90E+07 1.1 OE+08 3.49 3.39E+10 2.29E+10 1.80E+10 1.29E+10 4 3.99E+07 1.50E+08 4.76 3.68E+10 2.29E+10 1.67E+10 1.07E+10 5 3.87E+07 1.89E+08 5.98 3.75E+10 2.27E+10 1.56E+10 1.06E+10 6 3.88E+07 2.28E+08 7.21 3.18E+10 2.11E+1O 1.79E+10 1.29E+10 7 3.93E+07 2.67E+08 8.46 3.32E+10 2.08E+10 1.711E+10 1.30E+10 8 4.15E+07 3.08E+08 9.77 3.1IE+10 1.99E+10 1.58E+10 1.15E+10 9 3.86E+07 3.47E+08 11.00 3.311E+10 1.900+10 1.46E+10 1.111E+10 10 4.73E+07 3.94E+08 12.49 2.96E+10 1.89E+10 1.46E+1 0 1.07E+10 11 4.56E+07 4.40E+08 13.94 3.25E+10 1.97E+10 1.43E+10 9.50E+09 12(Pr) 9.66E+07 5.37E+08 17.00 3.12E+10 1.86E+10 1.38E+10 9.98E+09 Future 9.47E+07 6.31 E+08 20.00 3.82E+10 2.04E+10 1.44E+ 10 1.01E+10 Future 1.58E+08 7.89E+08 25.00 3.82E+10 2.04E+10 1.44E+10 1.01E+10 Future 2.21E+08 1.011E+09 32.00 3.82E+10 2.04E+10 1.44E+10 1.011E+10 Future 5.05E+08 1.52E+09 48.00 3.82E+10 2.04E+10 1.44E+10 1.011E+10 Future 1.89E+08 1.70E+09 54.00 3.82E+10 2.04E+10 1.44E+10 1.011E+10 Radiation Analysis and Neutron Dosimetry

6-15 Table 6-2 cont'd Calculated Azimuthal Variation Of Maximum Exposure Rates And Integrated Exposures At The Reactor Vessel Clad/Base Metal Interface With Uprate to 2900 MWt at the Start of Cycle 13 Cumulative Cumulative Neutron Fluence (E > 1.0 MeV)

Cycle Irradiation Irradiation [n/cm 2 ]

Length Time Time Cycle [EFPS] [EFPS] [EFPY] 00 150 300 450 1 3.92E+07 3.92E+07 1.24 1.92E+18 1.07E+18 7.91E+17 5.41 E+17 2 3.20E+07 7.12E+07 2.26 2.98E+18 1.74E+18 1.29E+18 8.82E+17 3 3.90E+07 1.10E+08 3.49 4.31IE+18 2.63E+18 1.99E+18 1.38E+18 4 3.99E+07 I.50E+08 4.76 5.77E+18 3.55E+18 2.66E+18 1.81E+18 5 3.87E+07 1.89E+08 5.98 7.22E+18 4.42E+18 3.26E+18 2.22E+18 6 3.88E+07 2.28E+08 7.21 8.46E+18 5.24E+18 3.96E+18 2.72E+18 7 3.93E+07 2.67E+08 8.46 9.76E+18 6.06E+18 4.63E+18 3.23E+18 8 4.15E+07 3.08E+08 9.77 I.11 E+19 6.88E+18 5.29E+18 3.70E+18 9 3.86E+07 3.47E+08 11.00 1.23E+19 7.62E+18 5.85E+18 4.13E+18 10 4.73E+07 3.94E+08 12.49 1.37E+19 8.511E+18 6.54E+18 4.64E+ 18 11 4.56E+07 4.40E+08 13.94 1.52E+19 9.411E+18 7.20E+18 5.07E+18 12(Prj) 9.66E+07 5.37E+08 17.00 1.82E+19 1.12E+19 8.53E+18 6.04E+ 18 Future 9.47E+07 6.31E+08 20.00 2.18E+19 1.31E+18 9.89E+18 6.99E+18 Future 1.58E+08 7.89E+08 25.00 2.79E+19 1.63E+19 1.22E+19 8.58E+18 Future 2.21 E+08 1.011E+09 32.00 3.63E+19 2.09E+19 1.53E+19 1.08E+19 Future 5.05E+08 1.52E+09 48.00 5.56E+19 3.11 E+19 2.26E+19 1.59E+19 Future 1.89E+08 1.70E+09 54.00 6.29E+19 3.50E+19 2.53E+19 1.78E+19 Radiation Analysis and Neutron Dosimetry

6-16 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 With Uprate to 2900 MWt at the Start of Cycle 13 Cumulative Cumulative Iron Atom Displacement Rate Cycle Irradiation Irradiation [dpa/s]

Length Time Time Cycle [EFPS] [EFPS] [EFPY] 00 150 300 450 I 3.92E+07 3.92E+07 1.24 7.76E- 11 4.29E-11 3.09E- 11 2.13E-I1 2 3.20E+07 7.12E+07 2.26 5.32E-11 3.29E-11 2.41E-11 1.66E-I 3 3.90E+07 1.11OE+08 3.49 5.39E-11 3.60E- 11 2.77E- 11 1.99E- 11 4 3.99E+07 1.50E+08 4.76 5.84E- 11 3.60E- 11 2.57E-11 1.66E-11 5 3.87E+07 1.89E+08 5.98 5.96E-11 3.57E-11 2.40E-11 1.64E-11 6 3.88E+07 2.28E+08 7.21 5.05E-11 3.31E-11 2.75E-11 1.99E-11 7 3.93E+07 2.67E+08 8.46 5.27E-11 3.27E-11 2.63E-11 2.00E-11 8 4.15E+07 3.08E+08 9.77 4.94E-11 3.13E-l1 2.43E-11 1.78E-11 9 3.86E+07 3.47E+08 11.00 5.28E-11 3.00E-11 2.24E-11 1.71E-11 10 4.73E+07 3.94E+08 12.49 4.69E-11 2.96E-11 2.25E-11 1.66E-11 11 4.56E+07 4.40E+08 13.94 5.15E- 11 3.09E- 11 2.22E- 11 1.47E- 11 12(Pri) 9.66E+07 5.37E+08 17.00 4.95E-11 2.92E-11 2.11E-11 1.55E-11 Future 9.47E+07 6.31E+08 20.00 6.07E-11 3.21E-11 2.22E-11 1.56E-11 Future 1.58E+08 7.89E+08 25.00 6.07E-11 3.21E-11 2.22E-11 1.56E-11 Future 2.2 1E+08 1.0 IE+09 32.00 6.07E-11 3.21E-11 2.22E-11 1.56E-11 Future 5.05E+08 1.52E+09 48.00 6.07E-11 3.21E-11 2.22E-11 1.56E-11 Future 1.89E+08 1.70E+09 54.00 6.07E-11 3.21E-11 2.22E-11 1.56E-11 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 With Uprate to 2900 MWt Cumulative Cumulative Iron Atom Displacements Cycle Irradiation Irradiation [dpa]

Length Time Time Cycle [EFPS] [EFPS] [EFPY] 00 150 300 450 1 3.92E+07 3.92E+07 1.24 3.04E-03 1.68E-03 1.21E-03 8.35E-04 2 3.20E+07 7.12E+07 2.26 4.75E-03 2.73E-03 1.98E-03 1.37E-03 3 3.90E+07 1.1OE+08 3.49 6.85E-03 4.14E-03 3.06E-03 2.14E-03 4 3.99E+07 1.50E+08 4.76 9.18E-03 5.57E-03 4.09E-03 2.80E-03 5 3.87E+07 1.89E+08 5.98 1.15E-02 6.95E-03 5.02E-03 3.44E-03 6 3.88E+07 2.28E+08 7.21 1.34E-02 8.24E-03 6.09E-03 4.2 1E-03 7 3.93E+07 2.67E+08 8.46 1.55E-02 9.52E-03 7.12E-03 5.OOE-03 8 4.15E+07 3.08E+08 9.77 1.76E-02 1.08E-02 8.13E-03 5.73E-03 9 3.86E+07 3.47E+08 11.00 1.96E-02 1.20E-02 8.99E-03 6.40E-03 10 4.73E+07 3.94E+08 12.49 2.18E-02 1.34E-02 1.011E-02 7.18E-03 11 4.56E+07 4.40E+08 13.94 2.42E-02 1.48E-02 1.1IE-02 7.85E-03 12(PIj) 9.66E+07 5.37E+08 17.00 2.90E-02 1.76E-02 1.31 E-02 9.35E-03 Future 9.47E+07 6.31 E+08 20.00 3.47E-02 2.07E-02 1.52E-02 1.08E-02 Future 1.58E+08 7.89E+08 25.00 4.43E-02 2.57E-02 1.87E-02 1.33E-02 Future 2.21 E+08 1.01E+09 32.00 5.77E-02 3.28E-02 2.36E-02 1.67E-02 Future 5.05E+08 1.52E+09 48.00 8.83E-02 4.911E-02 3.48E-02 2.46E-02 Future 1.89E+08 1.70E+09 54.00 9.98E-02 5.51 E-02 3.90E-02 2.76E-02 Radiation An lysis and Neutron Dosimetry

6-18 Table 6-3 Relative Radial Distribution Of Neutron Fluence (E > 1.0 MeV)

Within The Reactor Vessel Wall RADIUS AZIMUTHAL ANGLE (cm) 00 150 300 450 199.79 1.000 1.000 1.000 1.000 204.79 0.587 0.601 0.600 0.603 209.79 0.301 0.316 0.314 0.318 214.79 0.148 0.159 0.158 0.161 219.79 0.068 0.078 0.078 0.082 Note: Base Metal Inner Radius = 199.79 cm Base Metal 1/4T = 204.79 cm Base Metal 1/2T = 209.79 cm Base Metal 3/4T = 214.79 cm Base Metal Outer Radius = 219.79 cm Table 64 Relative Radial Distribution Of Iron Atom Displacements (dpa)

Within The Reactor Vessel Wall RADIUS AZIMUTHAL ANGLE (cm) 00 150 300 450 199.79 1.000 1.000 1.000 1.000 204.79 0.666 0.681 0.665 0.668 209.79 0.417 0.436 0.416 0.420 214.79 0.254 0.274 0.256 0.262 219.79 0.140 0.163 0.154 0.164 Note: Base Metal Inner Radius = 199.79 cm Base Metal 1/4T = 204.79 cm Base Metal 1/2T = 209.79 cm Base Metal 3/4T = 214.79 cm Base Metal Outer Radius = 219.79 cm Radiation Analysis and Neutron Dosimetry

6-19 Table 6-5 Calculated Fast Neutron Exposure of Surveillance Capsules Withdrawn from Beaver Valley Unit 2 Irradiation Time Fluence (E > 1.0 MeV) Iron Displacements Capsule [EFPY] [n/cm 2 ] [dpa]

U 1.24 6.08E+18 1.25E-02 V 5.98 2.63E+19 5.34E-02 W 9.77 3.63E+19 7.20E-02 X 13.94 5.60E+19 1.14E-01 Table 6-6 Calculated Surveillance Capsule Lead Factors Capsule ID And Location Status Lead Factor U (170) Withdrawn EOC 1 3.17 V (17°) Withdrawn EOC 5 3.64 W (200) Withdrawn EOC 8 3.29 X (170) Withdrawn EOC 11 3.68 Y (200) In Reactor 3.25 Z (20°) In Reactor 3.25 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 11 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 [Ref. 12]

and is recommended for future capsules to be removed from the Beaver Valley Unit 2 reactor vessel.

Table 7-1 Recommended Surveillance Capsule Withdrawal Schedule Capsule Capsule Location Lead Factor l Withdrawal EFPY(b) Fluence (n/cm 2 ) '

U 3430 3.17 1.24 6.082 x IO8 (c)

V 1070 3.64 5.98 2.629 x 1019 (c)

W 1100 3.29 9.77 3.625 x 1019 (c)

X 2870 3.68 13.94 5.601 x 10'9(c)

Y 2900 3.25 Standby (d) (d)

Z 3400 3.25 Standby (d) (d)

Notes:

(a) Updated in Capsule X dosimetry analysis.

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

(c) Actua! plant evaluation calculated fluence.

(d) These capsules will reach a fluence of approximately 6.29 x 1019 (54 EFPY Peak Fluence) which occurs at 17.33 EFPY.

It is recommended that these standby capsules are withdrawn between 17 and 18 EFPY and placed in storage. Future testing of one of the standby capsules is prudent if license extension for the plant is implemented.

Surveillance Capsule Removal Schedule

8-1 8 RTFERENCES

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

2. Code o f Federal Regulations, IOCFR50, Appendix Q FractureToughness Requirements, and Appendix H, Reactor Vessel MaterialSurveillance ProgramRequirements, U.S. Nuclear Regulatory Commission, Washington, D.C.

3. WCAP-9615, Revision 1, Duquesne Light Company Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program,P.A. Peters, dated June 1995.

4. WCAP -12406, Analysis of Capsule Ufrom the Duquesne Light Company Beaver Valley Unit 2 Reactor Vessel RadiationSurveillance Program, S.E. Yanichko, et. al., September 1989.

5. WCAP-14484, Analysis of Capsule Vfrom the Duquesne Light Company Beaver Valley Unit 2 Reactor Vessel RadiationSurveillance Program, P.A. Grendys, et. al., February 1996.

6. WCAP -15675, Analysis of Capsule Wfrom FirstEnergyNuclear Operating Company Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program,J.H. Ledger, et. al., August 2001.

7. STD Letter Report STD-MCE-05-36, Beaver Valley Unit 2, CapsuleX Test Report, J. Conermann, et al., July 11, 2005.

8. ASTM E 185-73, StandardPracticefor ConductingSurveillance Tests for Light- Water Cooled Nuclear Power Reactor Vessels, American Society for Testing and Materials.

9.Section XI of the ASME Boiler and Pressure Vessel Code, Appendix Q FractureToughness Criteria for Pro,ection Against Failure

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

11. ASTM E399, Test Methodfor Plane-StrainFractureToughness ofMetallic Materials,American Society for Testing and Materials.

12. ASTM El 85-82, StandardPracticefor ConductingSurveillance Tests for Light- Water Cooled NuclearPower Reactor Vessels, American Society for Testing and Materials.

13. Westinghouse Science and Technology Department Procedure RMF 8402, Surveillance Capsule Testing Program,Revision 2, dated 1/6/2005.

14. Westinghouse Science and Technology Procedure RMF 8102, Tensile Testing, Revision 3, dated 3/1/1999.

References

8-2

15. Westinghouse Science and Technology Procedure RMF 8103, Charpy Impact Testing, Revision 2, dated 8/1/1998.

16. ASTM E23-02a, StandardTest Methodfor Notched Bar Impact Testing of Metallic Materials, American Society for Testing and Materials.

17. ASTM A370-97a, StandardTest Methods andDefinitionsfor Mechanical Testing of Steel Products, American Society for Testing and Materials.

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

19. ASTM E21-03 a, StandardTest Methods for Elevated Temperature Tension Tests of Metallic Materials,American Society for Testing and Materials.

20. ASTM E83-93, StandardPracticefor Verification and Classificationof Extensometers, in ASTM Standards, Section 3, American Society for Testing and Materials.

21. ASTM E853-01, StandardPracticefor Analysis and Interpretationof Light Water Reactor Surveillance Results, E706(1A), Volume 12.02, American Society for Testing and Materials.

22. ASTM E693-01, StandardPracticefor CharacterizingNeutron Exposures in Iron andLow Alloy Steels in Terms of Displacements PerAtom (DPA), E706(ID), Volume 12.02, American Society for Testing and Materials.

23. Regulatory Guide RG- 1.190, CalculationalandDosimetry Methodsfor DeterminingPressure Vessel Neutron Fluence, U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, March 2001.

24. WCAP-14040-NP-A, Revision 4, Methodology Used to Develop Cold OverpressureMitigating System Setpoints andRCS Heatup and Cooldown Limit C'urves, May 2004.

25. WCAP-16083-NP, Benchmark Testing of the FERRET Codefor the Least Squares Evaltation ofLight Water Reactor Dosimetry, S.L. Anderson, May 2004.

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

27. RSICC Data Library Collection DLC-1 85, BUGLE-96, Coupled 47 Neutron, 20 Gamma-Ray Group Cross Section LibraryDerivedfrom ENDFIB-VIfor LWR Shielding and PressureVessel Dosimetry Applications,March 1996.

References

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

A-I 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 Beaver Valley Unit 2 are described herein. The sensor sets from these capsules have been analyzed in accordance with the current dosimetry evaluation methodology described in Regulatory Guide 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence."[Ref. A-I] One of the main purposes for presenting this material is to demonstrate that the overall measurements agree with the calculated and least squares adjusted values to within +/- 20% as specified by Regulatory Guide 1.190, thus serving to validate the calculated neutron exposures previously reported in Section 6.2 of this report.

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

Azimuthal Withdrawal Irradiation Capsule ID Location Time Time rEFPY1 U 170 End of Cycle I 1.24 V 170 End of Cycle 5 5.98 W 200 End of Cycle 8 9.77 X 170 End of Cycle 11 13.94 The azimuthal locations included in the above tabulation represent the first octant equivalent azimuthal angle of the geometric center of the respective surveillance capsules. The passive neutron sensors included in the evaluations of Surveillance Capsules U, V,W and X are summarized as follows:

Reaction Sensor Material Of Interest Capsule U Capsule V Capsule W Capsule X Copper 63Cu(n,a)60Co X X X X Iron 14Fe(np)4 Mn X X X X Nickel 58 Ni(n,p)58Co X X X X"

23 8 37 Uranium-238 U(nf) Cs X X X"*

Neptunium-237 237 Np(nf) 13'Cs X X X X Cobalt-Aluminum* 59Co(ny)60 Co X X X X

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

• • The U-238 sensors from these capsules yielded erroneous results and were, therefore, rejected.

Appendix A

A-2 Since all of the dosimetry monitors were accommodated within the dosimeter block centered at the radial center of thi material test specimen array, gradient corrections were not required for these reaction rates.

Pertinent physical and nuclear characteristics of the passive neutron sensors are listed in Table A-1.

The use of passive monitors such as those listed above does not yield a direct measure of the energy dependent rneutron 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, V,W, and X are provided in Table A-4. In all cases, the radiometric counting followed established ASTM procedures. Following sample preparation and weighing, the specific activity of each sensor was determined by means of a high-resolution gamma spectrometer. For the copper, iron, nickel, and cobalt-aluminum sensors, these analyses were performed by direct counting of each of the individual samples. In the case of the uranium 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, V,W, and X was based on the reported monthly power generation of Beaver Valley Unit 2 from initial reactor criticality through the end of the dosimetry evaluation period. For the sensor sets utilized in the surveillance capsules, the half-lives of the product isotopes are long enough that a monthly histogram describing reactor operation has proven to be an adequate representation for use in radioactive decay corrections for the reactions of interest in the exposure evaluations. The irradiation history applicable to Capsules U, V,W, 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:

RA No F Y LX c [1- e-At] [e- td]

Appendix A

A-3 where:

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

A = Measured specific activity (dps/gm).

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

F = 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).

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

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

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

tj = Length of irradiation 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.

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

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

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

Prior to using the measured reaction rates in the least-squares evaluations of the dosimetry sensor sets, additional corrections were made to the 238U measurements to account for the presence of 235U impurities in the sensors as well as to adjust for the build-in of plutonium isotopes over the course of the irradiation.

Corrections were also made to the 238U and 237Np 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 Beaver Valley Unit 2 fission sensor reaction rates are summarized as follows:

Appendix A

A-4 Correction Capsule U Capsule V Capsule W Capsule X

,35U Impurity/Pu Build-in 0.861 0.789 238U(y,f) 0.976 0.976 Net 238U Correction 0.840 0.770 n/a n/a 237NP(Y,f) 0.994 0.994 0.994 0.994 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, V, 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 238U impurities, plutonium build-in, an:l gamma ray induced fission effects.

A.1.2 Least Squares Evaluation of Sensor Sets Least squares adjustment methods provide the capability of combining the measurement data with the corresponding neutron transport calculations resulting in a Best Estimate neutron energy spectrum with associated uncertainties. Best Estimates for key exposure parameters such as $(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, = E( ig +/- Sg )(Og +/- St) relates a set of measured reaction rates, Ri, to a single neutron spectrum, jg, through the multigroup dosimeter reaction cross-section, aig, each with an uncertainty 8. 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 Beaver Valley Unit 2 surveillance capsule dosimetry, the FERRET code [Ref. A-2] 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

(+(E > 1.0 Mv[eV) and dpa) along with associated uncertainties for the four in-vessel capsules withdrawn to date.

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

Appendix A

A-5 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 Beaver Valley Unit 2 application, the calculated neutron spectrum was obtained from the results of plant specific neutron transport calculations described in Section 6.2 of this report. The sensor reaction rates were derived from the measured specific activities using the procedures described in Section A. 1.1.

The dosimetry reaction cross-sections and uncertainties were obtained from the SNLRML dosimetry cross-section library [Ref. A-3]. The SNLRML library is an evaluated dosimetry reaction cross-section compilation recommended for use in LWR evaluations by ASTM Standard El 018, "Application of ASTM Evaluated Cross-Section Data File, Matrix E 706 (IIB)".

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 Beaver Valley Unit 2 surveillance capsule sensor sets.

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

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

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

"Fe(n,p)"Mn 5%

58 Ni(n,p)5"Co 5%

238 U(n,f)' 37Cs 10%

37Np(nf)137cS 10%

"Co(ny) 60Co 5%

These uncertainties are given at the Ic level.

Appendix A

A-6 Dosimetry Gross-Section Uncertainties The reactio:n 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 fo'r use in fission spectra determination as well as in the fluence and energy characterization of 14 MeV neutron sources.

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

Reaction Uncertainty 63 Cu(na)6 0Co 4.08-4.16%

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

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

238U(n,0137Cs 0.54-0.64%

237Np(n,f)l37Cs 10.32-10.97%

59Co(nY)6 0Co 0.79-3.59%

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

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

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

Mgg = R' +Rg *RgI *Pgg Appendix A

A-7 where Rn specifies an overall fractional normalization uncertainty and the fractional uncertainties Rg and Rg9 specify additional random groupwise uncertainties that are correlated with a correlation matrix given by:

Pgg =f[I-J J9 +OeH where H = (g-g') 2 2y2 The first term in the correlation matrix equation specifies purely random uncertainties, while the second term describes the short-range correlations over a group range y (0 specifies the strength of the latter term). The value of 8 is 1.0 when g = g', and is 0.0 otherwise.

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

Flux Normalization Uncertainty (R,) 15%

Flux Group Uncertainties (Rg, Rg.)

(E > 0.0055 MeV) 15%

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

Appendix A

A-8 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 la level. From Table A-6, it is noted that the corresponding uncertainties associated with the least squares adjusted exposure parameters have been reduced to 6%-7% for neutron flux (E > 1.0 MeV) and 8%-9% for iron atom displacement rate. Again, the uncertainties from the least squares evaluation are at the Ic 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 4(E > 1.0 MeV) and dpa/s are compared with the best estimate results obtained from the least squares evaluation of the capsule dosimetry results. These two levels of comparison yield consistent and similar results with all measurement-to-calculation comparisons falling well within the 20% limits specified as the acceptance criteria in Regulatory Guide 1.190.

In the case of the direct comparison of measured and calculated sensor reaction rates, the M/C comparison i for fast neutron reactions range from 0.89-1.11 for the 18 samples included in the data set.

The overall average M/C ratio for the entire set of Beaver Valley Unit 2 data is 0.98 with an associated standard deviation of 7.5%.

In the comparisons of best estimate and calculated fast neutron exposure parameters, the corresponding BE/C comparisons for the capsule data sets range from 0.90-0.98 for neutron flux (E > 1.0 MeV) and from 0.91 to 0.99 for iron atom displacement rate. The overall average BE/C ratios for neutron flux (E > 1.0 MeV) and iron atom displacement rate are 0.95 with a standard deviation of 3.6% and 0.96 with a standard deviation of 3.6%, 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 lthe beltline region of the Beaver Valley Unit 2 reactor pressure vessel.

Appendix A

A-9 Table A-I Nuclear Parameters Used In The Evaluation Of Neutron Sensors Target 90% Response Fission Atom Monitor Reaction of RANGE Product Yield Fraction Half-life (%)0 Material Interest (MEV)

Copper "Cu (na) 0.6917 4.9- 11.8 5.271 y 54 0.0585 2.1 -8.4 312.3 d Iron Fe (n,p)

Nickel 58Ni (n,p) 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 7 1.0000 0.4 - 3.6 30.07 y 6.17

" Np (n,f)

Cobalt-Aluminum 59 0.0015 non-threshold 5.271 y Co (nuy)

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

Appendix A

A-:_

Table A-2 Monthly Thermal Generation During The First Eleven Fuel Cycles Of The Beaver Valley Unit 2 Reactor (Reactor Power of 2652 MWt for Cycles 1 through 9, and 2689MW for Cycles 10 and 11)

Thermal Thermnal Thermal Generation Generation Generation Year Month (MWt-hr) Year Month (MWt-hr) Year Month (MWt-hr) 1987 8 188655 1990 8 1664072 1993 8 1951094 1987 9 309627 1990 9 74406 1993 9 782113 1987 10 1138592 1990 10 0 1993 10 0 1987 11 517531 1990 11 375293 1993 11 0 1987 12 1868106 1990 12 1962999 1993 12 13183-L3 1988 1 1647518 1991 1 1966105 1994 1 195742,7 1988 2 948305 1991 2 1772383 1994 2 1767624 1988 3 1961547 1991 3 1920061 1994 3 19572C'7 1988 4 1816453 1991 4 1899670 1994 4 1895053 1988 5 1963013 1991 5 1959596 1994 5 196014l8 1988 6 1795032 1991 6 1764771 1994 6 1121998 1988 7 1881079 1991 7 1941503 1994 7 1954090 1988 8 1783059 1991 8 1954146 1994 8 1958831 1988 9 1802754 1991 9 1881952 1994 9 1897976 1988 10 1882405 1991 10 1861135 1994 10 1962873 1988 11 1900844 1991 11 1674762 1994 11 1894630 1988 12 1963294 1991 12 1636047 1994 12 1950889 1989 1 1863158 1992 I 1870700 1995 1 1917701 1989 2 1018798 1992 2 1796307 1995 2 1754716 1989 3 612808 1992 3 509755 1995 3 1200818 1989 4 0 1992 4 0 1995 4 0 1989 5 12973 1992 5 1023309 1995 5 1147307 1989 6 1009593 1992 6 1809717 1995 6 1864365 1989 7 1033532 1992 7 1934799 1995 7 1916207 1989 8 1948907 1992 8 1959446 1995 8 1773194 1989 9 1900600 1992 9 1859358 1995 9 1880865 1989 10 1966839 1992 10 1960015 1995 10 1957436 1989 11 1899581 1992 11 1752279 1995 11 1754745 1989 12 1814015 1992 12 1708578 1995 12 18910165 1990 1 1686721 1993 I 1635667 1996 l 181001 4 1990 2 1194673 1993 2 1702839 1996 2 174289')

1990 3 1476919 1993 3 1947152 1996 3 191532')

1990 4 1380856 1993 4 1786447 1996 4 177799) 1990 5 1489609 1993 5 1839535 1996 5 193463'7 1990 6 1431870 1993 6 1888001 1996 6 1857381) 1990 7 1577454 1993 7 1834053 1996 7 1918340)

Appendix A

A-l1 Table A-2 cont'd Monthly Thermal Generation During The First Eleven Fuel Cycles Of The Beaver Valley Unit 2 Reactor (Reactor Power of 2652 MWt for Cycles 1 through 9, and 2689MW for Cycles 10 and 11)

Thermal Thermal Thermal Generation Generation Generation Year Month (MWt-hr) Year Month (MWt-hr) Year Month (MWt-hr) 1996 8 1469931 1999 8 1928918 2002 8 1997895 1996 9 0 1999 9 1874313 2002 9 1823374 1996 10 0 1999 10 1323291 2002 10 2000043 1996 11 0 1999 11 1682987 2002 11 1933715 1996 12 694343 1999 12 1775505 2002 12 1962537 1997 1 1210605 2000 1 1903763 2003 1 1997888 1997 2 1776258 2000 2 1677554 2003 2 1804094 1997 3 1178064 2000 3 1681774 2003 3 1997749 1997 4 1768747 2000 4 1873178 2003 4 1930985 1997 5 1942927 2000 5 1944510 2003 5 1953657 1997 6 1853679 2000 6 1857436 2003 6 1894875 1997 7 1082321 2000 7 1931752 2003 7 1997943 1997 8 1914272 2000 8 1925633 2003 8 1998043 1997 9 1572152 2000 9 1207003 2003 9 733841 1997 10 1944012 2000 10 286752 2003 10 1019110 1997 11 1895487 2000 11 1901991 2003 11 1931584 1997 12 990665 2000 12 1435864 2003 12 1998849 1998 1 0 2001 1 1950715 2004 1 1997347 1998 2 0 2001 2 1778926 2004 2 1869774 1998 3 0 2001 3 1724097 2004 3 1998361 1998 4 0 2001 4 1748718 2004 4 1869427 1998 5 0 2001 5 1944298 2004 5 1949549 1998 6 0 2001 6 1904103 2004 6 1933646 1998 7 0 2001 7 1938365 2004 7 1965028 1998 8 0 2001 8 1928137 2004 8 1997512 1998 9 25385 2001 9 1873345 2004 9 1928322 1998 10 1935467 2001 10 1968825 2004 10 2001362 1998 11 1624078 2001 11 1932741 2004 11 1934478 1998 12 1955838 2001 12 1997249 2004 12 1997979 1999 I 1954784 2002 1 1997170 2005 1 1999031 1999 2 1626617 2002 2 157181 2005 2 1675452 1999 3 0 2002 3 1730020 2005 3 1831750 1999 4 964605 2002 4 1842917 2005 4 154254 1999 5 1943731 2002 5 1816591 1999 6 1859034 2002 6 1932910 1999 7 1226305 2002 7 1997512 Appendix A

A-12 Table A-3 Calculated CJ Factors at the Surveillance Capsule Center Core Midplane Elevation Fuel 7C-ycle Capsule U Capsule V Capsule W Capsule X 1 1.55E+1 I 1.55E+1l 1.34E+1 1 1.55E+11 2 1.26E+1 I 1.11 E+ 11 1.26E+1 I 3 1.41E+1 1 1.27E+11 1.41E+1 1 4 1.38E+11 1.23E+1 I 1.38E+11 5 1.34E+1 I 1.16E+ II 1.34E+1 I 6 1.14E+1 I 1.25E+1 I 7 1.09E+11 1.23E+11 8 1.07E+1 I 1.20E+1 I 9 1.11E+11 10 1.14E+1 I 11 1.18E+11 Average 1.55E+11 1.39E+11 1.18E+11 1.27E+11 Fuel Cycle

_Capsule U lCapsule V Capsule W Capsule X 1 1.000 1.115 1.136 1.220 2 0.906 0.941 0.992 3 1.014 1.076 1.110 4 0.993 1.042 1.087 5 0.964 0.983 1.055 6 0.966 0.984 7 0.924 0.969 8 0.907 0.945 9 0.874 10 0.898 11 0.929 Average 1.000 1.000 1.000 1.000 Appendix A

A-13 Table A-4 Measured Sensor Activities And Reaction Rates Surveillance Capsule U Radially Radially Adjusted Adjusted Measured Saturated Saturated Reaction Activity Activity Activity Rate Reaction Location (dps/g) (dps/g) (dps/g) (rps/atom) 6 3 CU (n,ot) 60Co Top 7.54E+04 S.18E+05 5.18E+05 7.90E-17 Middle 7.17E+04 4.92E+05 4.92E+05 7.51E-17 Bottom 6.70E+04 4.60E+05 4.60E+05 7.02E- 17 Average 7.48E-17 54 Fe (n,p) 54Mn Top 2.77E+06 5.33E+06 5.33E+06 8.44E-15 Middle 2.53E+06 4.87E+06 4.87E+06 7.7 1E-15 Bottom 2.44E+06 4.69E+06 4.69E+06 7.44E-15 Average 7.86E-15 "Ni (n,p) " 8Co 5

Middle 3.49E+07 7.80E+07 7.80E+07 1.12E-14 Bottom 3.37E+07 7.54E+07 7.54E+07 1.08E-14 Average 1.10E-14 238U (nf) 137Cs (Cd) Middle 2.66E+05 9.48E+06 9.48E+06 6.23E-14 238U (nf) 137Cs (Cd) Including 235u, 239pu, and y,fission corrections: 5.23E-14 237 Np (nf) 137CS (Cd) Middle 1.99E+06 7.1OE+07 7.10E+07 4.53E-13 237 Np (nf) 137Cs (Cd) Including yfission correction: 4.50E-13 59 Co (n,y) 6 0Co Top 1.50E+07 1.03E+08 1.03E+08 6.72E-12 Top 1.28E+07 8.79E+07 8.79E+07 5.73E-12 Middle 1.36E+07 9.34E+07 9.34E+07 6.09E-12 Middle 1.58E+07 1.09E+08 1.09E+08 7.08E-12 Bottom 1.43E+07 9.82E+07 9.82E+07 6.411E-12 Average 6.41E-12 "Co (ny) 6 0Co (Cd) 5 Top 8.57E+06 5.88E+07 5.88E+07 3.84E-12 Middle 8.69E+06 5.97E+07 5.97E+07 3.89E-12 Bottom 9.17E+06 6.30E+07 6.30E+07 4.1lE-12 Average 3.95E-12 Notes: 1) Measured specific activities are indexed to a counting date of May 17, 1989.

2) The average 23 8U(n,f) reaction rate of 5.23E-14 includes a correction factor of 0.861 to account for plutonium build-in and an additional factor of 0.976 to account for photo-fission effects in the sensor.

3) The average 237Np (n,f) reaction rate of 4.50E-13 includes a correction factor of 0.994 to account for photo-fission effects in the sensor.

Appendix A

A-:14 Table A-4 cont'd Measured Sensor Activities And Reaction Rates Surveillance Capsule V Radially Radially Adjusted Adjusted Measured Saturated Saturated Reaction Activity Activity Activity Rate Reaction Location (dps/g) (dps/g) (dps/a) (rps/atoln) 63Cu (n,c) 6 0Co Top 2.41 E+05 4.99E+05 4.99E+05 7.56E- 17 Middle 2.27E+05 4.67E+05 4.67E+05 7.13E-17 Bottom 2.16E+05 4.44E+05 4.44E+05 6.78E-17 Average 7.16E-1 7 14Fe (n,p) `Mn Top 3.25E+06 4.80E+06 4.80E+06 7.611E-15 Middle 3.08E+06 4.55E+06 4.55E+06 7.21E-15 Bottom 2.94E+06 4.34E+06 4.34E+06 6.88E-15 Average 7.23E-15 "Ni (n,p) "Co Top 2.56E+07 7.45E+07 7.45E+07 1.071E-14 Middle 2.41E+07 7.0 IE+07 7.01E+07 L.OOE-14 Bottom 2.34E+07 6.81 E+07 6.81E+07 9.751E- 15 Average 1.02E-14 23 8U (nf) 137 Cs (Cd) Middle 1.13E+06 8.971E+06 8.97E+06 5.89E-14 238U (nf) 137 Cs (Cd) Including 23 5U, 239pu, and y,fission corrections: 4.53E-14 2 37Np (nf) 137Cs (Cd) Middle 8.83E+06 7.01E+07 7.01E+07 4.47E-1 3 237Np (nf) 137CS (Cd) Including y,fission correction: 4.45E-13 59 Co (n,-') 6 0 Co Top 4.07E+07 8.37E+07 8.37E+07 5.46E-12 Top 3.63E+07 7.47E+07 7.47E+07 4.87E- 12 Middle 3.67E+07 7.55E+07 7.55E+07 4.93E-112 Middle 4.36E+07 8.97E+07 8.97E+07 5.85E-12 Bottom 3.71 E+07 7.63E+07 7.63E+07 4.98E- 12 Bottom 4.40E+07 9.05E+07 9.05E+07 5.9 1E-1:2 Average 5.33E-12 59 Co (n,y) 6 3Co (Cd) Top 2.411E+07 4.96E+07 4.96E+07 3.24E- 12 Middle 2.481E+07 5.1 OE+07 5.1 OE+07 3.33E- 12 Bottom 2.511E+07 5.16E+07 5.16E+07 3.37E-12 Average 3.31E-12 Notes: 1)Measured specific activities are indexed to a counting date of June 30, 1995.

2) The average 238U (n,f) reaction rate of 4.53E-14 includes a correction factor of 0.789 to account for plutonium build-in and an additional factor of 0.976 to account for photo-fission effects in the sensor.

3) The average 237Np (n,f) reaction rate of 4.45E-13 includes a correction factor of 0.994 to account.

for photo-fission effects in the sensor.

Appendix A

A-15 Table A-4 cont'd Measured Sensor Activities And Reaction Rates Surveillance Capsule W Radially Radially Adjusted Adjusted Measured Saturated Saturated Reaction Activity Activity Activity Rate Reaction Location (dps/g) (dps/g) (dps/g) (Ms/atom) 63 CU (n,ca) 60 Co Top 2.39E+05 4.11E+05 4.11 E+05 6.27E-1 7 Middle 2.17E+05 3.73E+05 3.73E+05 5.69E-17 Bottom 2.11 E+05 3.63E+05 3.63E+05 5.54E-17 Average 5.83E-17 S

4 Fe (n,p) 5 4Mn Top 2.91E+06 4.29E+06 4.29E+06 6.80E-15 Middle 2.65E+06 3.90E+06 3.90E+06 6.19E-15 Bottom 2.44E+06 3.60E+06 3.60E+06 5.70E- 15 Average 6.23E-15 58Ni (n,p) 5 8Co Top 4.39E+06 6.88E+07 6.88E+07 9.85E-15 Middle 3.94E+06 6.17E+07 6.17E+07 8.84E-15 Bottom 3.85E+06 6.03E+07 6.03E+07 8.631E-15 Average 9.11E-15 237Np (nf) 137Cs (Cd) Middle 1.06E+07 5.50E+07 5.50E+07 3.511E-13 237 Np (nf) 137Cs (Cd) Including y,fission correction: 3.49E-13 59 60Co Top Co (n,y) 3.24E+07 5.57E+07 5.57E+07 3.64E-12 Top 3.73E+07 6.42E+07 6.42E+07 4.19E- 12 Middle 3.33E+07 5.73E+07 5.73E+07 3.74E-12 Middle 3.98E+07 6.85E+07 6.85E+07 4.47E-12 Bottom 3.40E+07 5.85E+07 5.85E+07 3.82E-12 Bottom 3.89E+07 6.69E+07 6.69E+07 4.37E-12 Average 4.03E-12 60 Top "Co (n,y) Co (Cd) 2.22E+07 3.82E+07 3.82E+07 2.49E-12 Middle 2.27E+07 3.90E+07 3.90E+07 2.55E- 12 Bottom 2.3 1E+07 3.97E+07 3.97E+07 2.59E-12 Average 2.54E-12 Notes: 1) Measured specific activities are indexed to a counting date of October 20, 2000.

2) The average 23 7Np (n,f) reaction rate of 4.97E-13 includes a correction factor of 0.994 to account for photo-fission effects in the sensor.

Appendix A

A-15 Table A-4 cont'd Measured Sensor Activities And Reaction Rates Surveillance Capsule X Radially Radially Adjusted Adjusted Measured Saturated Saturated Reaction Activity Activity Activity Rate Reacl:ion Location (dps/g) (dps/g) (dps/g) (rps/atomi) 63 CU (n, t) 60 Co Top 2.971E+05 4.09E+05 4.091E+05 6.24E- 1'7 Middle 2.831E+05 3.90E+05 3.90E+05 5.94E-17 Bottom 2.7 1E+05 3.73E+05 3.73E+05 5.69E- 1'7 Average 5.96E-1'7 54 Fe (n,p) 14Mn Top 3.331E+06 4.08E+06 4.08E+06 6.46E-1:5 Bottom 3.07E+06 3.761E+06 3.76E+06 5.96E-1:5 Average 6.21E-1:5 58Ni (n,p) 5 8 Co Top 3.59E+07 6.54E+07 6.54E+07 9.36E-15 Top 3.58E+07 6.52E+07 6.52E+07 9.33E-1:5 Middle 3.40E+06 6.19E+07 6.19E+07 8.86E-1:5 Bottom 3.3 IE+06 6.03E+07 6.03E+07 8.63E-1:5 Average 9.05E-15 237Np (nf) 137CS (Cd) Middle 1.54E+07 5.74E+07 5.74E+07 3.66E- 1:3 2 37 Np (nf) 137CS (Cd) Including y,fission correction: 3.64E-I';

59 60 Co (n,y) Co Top 4.73E+07 6.5 1E+07 6.51 E+07 4.25E-12 Top 5.19E+07 7.15E+07 7.15E+07 4.66E-12 Middle 5.54E+07 7.63E+07 7.63E+07 4.98E-12 Middle 4.58E+07 6.3 1E+07 6.31 E+07 4.1 1E-l,2 Bottom 5.37E+07 7.39E+07 7.39E+07 4.82E-12 Bottom 4.66E+07 6.42E+07 6.42E+07 4.19E-12I Average 4.50E-1:!

59 Co (nY) 6OCo (Cd) Top 3.04E+07 4.19E+07 4.19E+07 2.73E-12 Middle 2.97E+07 5.74E+07 5.74E+07 2.67E-12 Average 2.70E-12 Notes: 1) Measured specific activities are indexed to a counting date of May 27, 2005.

2) The average 237 Np (n,f) reaction rate of 3.64E-13 includes a correction factor of 0.994 to account for photo-fission effects in the sensor.

Appendix A

A-17 Table A-5 Comparison of Measured, Calculated, and Best Estimate Reaction Rates At The Surveillance Capsule Center Capsule U Reaction Rate frps/atom]

Best Reaction Measured Calculated Estimate M/C M/BE 63 Cu(n,a)6 0Co 7.47E-17 6.82E-17 7.22E-17 1.10 0.97 54 Fe(n,p) 54 Mn 7.86E-15 8.22E-15 8.09E-15 0.96 1.03 s8Ni(np) 58 Co 1.1 OE- 14 1.17E- 14 1.14E- 14 0.94 1.04 n 38U(nf)' 37 Cs (Cd) 5.23E-14 4.71E-14 4.59E-14 1.11 0.88 237 Np(n,f)137Cs (Cd) 4.50E-13 5.05E-13 4.71E-13 0.89 1.05 59Co(n,y) 6 0Co 6.41E-12 4.92E-12 6.24E-12 1.30 0.97 59Co(n,y)60Co (Cd) 3.95E-12 3.77E-12 4.02E-12 1.05 1.02 Capsule V Reaction Rate [ s/atom]

Best Reaction Measured Calculated Estimate M/C M/BE 63 Cu(na) 6 0Co 7.16E-17 6.47E- 17 6.88E-17 1.11 0.96 54 Fe(n,p) 54 Mn 7.23E-15 7.59E-15 7.47E-15 0.95 1.03 58Ni(np)5 8Co 1.01E-14 1.07E- 14 1.05E-14 0.94 1.03 2 38U(nf)3 7 Cs (Cd) 4.53E-14 4.27E-14 4.18E-14 1.06 0.92 237 Np(n,f)137 Cs (Cd) 4.44E-13 4.49E- 13 4.43E- 13 0.99 1.00 59 Co(ny)60Co 5.33E-12 4.26E-12 5.20E-12 1.25 0.98 59 Co(n,y) 6 0Co (Cd) 3.31E-12 3.27E-12 3.37E-12 1.01 1.02 Capsule W React ion Rate [rps/ atom]

Best Reaction Measured Calculated Estimate M/C M/BE 63 Cu(na)60Co 5.83E-17 5.90E-17 5.78E-17 0.99 0.99 54 Fe(n,p) 5 4 Mn 6.23E-15 6.70E- 15 6.37E-15 0.93 1.02 58 Ni(n,p) 5 8Co 9.1OE- 15 9.44E- 15 9.04E- 15 0.96 0.99 237 Np(n,f)137 Cs (Cd) 3.49E-13 3.70E-13 3.52E- 13 0.94 1.01 59 Co(n,y) 6 0Co 4.03E-12 3.28E-12 3.93E- 12 1.23 1.02 59Co(n,y)60Co (Cd) 2.54E- 12 2.53E-12 2.59E-12 1.00 1.00 Appendix A

A-18 Table A-5 cont'd Comparison of Measured, Calculated, and Best Estimate Reaction Rates At The Surveillance Capsule Center Capsule X Re-action Ratep __frn./atnm1l

[ ___ ___ ___ __ -_- -

Best Reaction Measured Calculated Estimate M/C M/BE 63 Cu(n,a) 6 0Co 5.96E-17 6.02E- 17 5.83E-17 0.99 1.02 54 Fe(n,p)54 Mn 6.21E-15 6.99E-15 6.38E-15 0.89 0.97 58.Ni(n,p) 58Co 9.05E-15 9.88E-15 9.05E-15 0.92 1.00 237NIp(,f)137CS (Cd) 3.64E-13 4.09E-13 3.68E-13 0.89 0.99 59Co(n,y)60Co 4.50E-12 3.87E-12 4.39E-12 1.16 1.03 59Co (n,,y)60Co (Cd) 2.70E- 12 2.97E-12 2.75E-12 0.91 0.98 Appendix A

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

• (E > 1.0 MeV) [n/cm2 -s]

Best Uncertainty Capsule ID Calculated Estimate (1ic) BE/C U 1.55E+1l 1.51 E+1 1 6% 0.972 V 1.39E+lI 1.37E+l1 6% 0.981 W 1.18E+11 1.12E+11 7% 0.954 x 1.27E+l1 1.15E+11 7% 0.903 Note: Calculated results are based on the synthesized transport calculations taken at the core midplane following the completion of each respective capsules irradiation period.

Iron Atom Displacement Rate [dpa/sl Best Uncertainty Capsule ID Calculated Estimate (lo) BE/C U 3.19E-10 3.10E-10 8% 0.971 V 2.83E-10 2.80E-10 8% 0.988 W 2.34E-I0 2.23E-10 8% 0.956 x 2.58E-10 2.35E-10 9% 0.909 Note: Calculated results are based on the synthesized transport calculations taken at the core midplane following the completion of each respective capsules irradiation period.

Appendix A

A-23 Table A-7 Comparison of Measured/Calculated (M/C) Sensor Reaction Rate Ratios Including all Fast Neutron Threshold Reactions Reaction Capsule U Capsule V Capsule W Capsule X 63 Cu(n,a)6 0Co 1.10 1.11 0.99 0.99 54 Fe(n,p) 54 Mn 0.96 0.95 0.93 0.89 58 Ni(n,p) 5 8Co 0.94 0.94 0.96 0.92 238U(np)l37 Cs (Cd) 1.11 1.06 237Np(nf)13 Cs (Cd) 0.89 0.99 0.94 0.89 Average 1.00 1.01 0.96 0.92

_% Standard Deviation 9.9 7.2 2.8 5.1 Note: The overall average M/C ratio for the set of 18 sensor measurements is 0.98 with an associated standard deviation of 7.5%.

Table A-Z Comparison of Best Estimate/Calculated (BEIC) Exposure Rate Ratios BE/C Ratio Capsule ID +(E > 1.0 MeV) dpa/s U 0.97 0.97 V 0.98 0.99 W 0.95 0.96 X 0.90 0.91 Average 0.95 0.96

%Standard Deviation 3.6 3.6 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. A. Schmittroth, FERRET DataAnalysis Core, HEDL-TME 79-40, Hanford Engineering Development Laboratory, Richland, WA, September 1979.

A-3. RSIC Data Library Collection DLC-178, "SNLRML Recommended Dosimetry Cross-Section Compendium", July 1994.

Appendix A

B-D APPENDIX B LOAD-TIME RECORDS FOR CHARPY SPECIMEN TESTS INSTRUMENTED CHARPY IMPACT TEST CURVES

• Specimen prefix "WL" denotes Intermediate Plate, Longitudinal Orientation

• Specimen prefix "WT" denotes Intermediate Plate, Transverse Orientation

• Specimen prefix "WW" denotes Weld Material

• Specimen prefix "WH" denotes Heat-Affected Zone material Appendix C

I B-1 500.00-4000.00

• 300000 2000.00 iooo.oo

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

L49, -50 0 F 5000.00 4000 .00 -

a 3000.00-2000.00-i0oo.00.

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

WL59, 25 0F Appendix C

I B-2 5 0 .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 Thme-1 (ms)

WL60, 75 0F 50o0.00 4000.00 3000.00 2000.00 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (mn)

WL58, 100 0F Appendix C

B-3 S00.00 4000.00-a 3owoo~o

-J i3000.00 200.00-1000.00-l nn, n

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

WL47, 125 0 F 0.00 1.00 2.00 3.00 4.00 6.00 6.00 rmne-1 (ms)

WL46, 150 0F CGUC Appendix C

I B4 5M.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 Tine-1 (ms)

WL48, 175 0 F 5000.00-4000.00 a

3000

.00-2000.00' 1000.00-

.00 3.00 6.00 Tine-1 (ffs)

WL55, 2000 F Appendix C

B-5 500.00 4000.00 a3000.00 2000.00 1000.00 1.00 2.00 3.00 4.00 5.00 6.00 Tiro-I (ms)

WL56, 225 0 F 5000.00 4000.00

" 3000.00 2000.00 1000.00 0.00 i iA i i ,

0.00 1.00 IW.o 3.00 4.00 5.00 6.00 Tine-I (mns)

WL51, 250 0 F Appendix C

B-6 5000.00 4000.00 0

3000.00 0.00 1.00 2.00 3.00 4.00 5.00 Thme-1 (ms)

WL52, 275 0 F 5000.00-400000-3000.00-2000.00-1000.00-

.00 3.00 6.00 Mrnm-1 (mS)

WL57, 2800 F Appendix C

B-7 5000.00 4000.00

- 3000.00 g

2000.0 1000.00 0.00

0. 00 1.00 2.00 3.00 4.00 5.00 6.00 Tike-I (m)

WL50, 3250 F 5000S00 4000.00

'A 3000.00 0

-ft 2000.00 1000.00 2.00 3.00 6.00 rne-1 (ms)

WL54, 3500 F Appendix C

B-8 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Thme-1 (ms)

WL53, 375 0 F 5000.00-4000.00-30W.00 2000.0 1000.00 Mill_--

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

WT60, -500 F Appendix C

B-9 3000.00 2w O.w0 1000.00 0.00 O.(30 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)

WT57, 25 0 F 5000.00.

4000.00-

- 30M000 2000.00 1000 .00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-i (ims)

WT56, 50 0F Appendix C

B-10 5000.00.

4000.00 2000.00 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Tirra-1 (ins)

WT50, 750 F 5000.00 40.00

~3000.00 2000.00 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time- (ms)

WT46, 100 0 F 0.00-Appendix C

B-l1 4000.00-

- 3000.00 2000.00-1000 00.

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

WT59, 125 0F 5000.00 4000.00

- 3000.00-2000.00-1000.00-0.00 1.00 2.00 3.00 4.00 5.00 6.00 rwne-1 (Ms)

WT54, 150 0F CQ3 Appendix C

B-12 4000D/0 200.00 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 The-1 (ma)

WT47, 175 0 F 5000.00 4000.00 s3000.00S 2000.00 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 rlme-1 (Ms)

WT52, 200 0 F Appendix C  :)(r

B-13 I 3000.00 2000.00 I WW.W0- .

100.00I 0.0.0 1.00 2.00 3.00 4.00 5.00 6.00 Tmne-1 (ms)

WT55, 250 0F 5000.00 4000.00 A

X7 30W.00 2000.00 1000.00 0.00 1.00 2.00 3.00 4.00 S.00 6.00 rrne-1 (ms)

WT58, 275 0F Appendix C

B-14 8

I 3000.00 2000.00 1000.001 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Thlme-1 (ms)

WT53,3000 F 0.00 1.00 2.00 3.00 4.00 5.00 6.00 rme-i (ms)

WT48, 325WF Appendix C

B-15 5000.00 4000.00 A

- 3000.00 0

2000.00 1000.00 A . . . . .

n nno. ,

0.00 1.00 2.00 3.00 4.00 5.00 6.00 Tine- (ms)

WT51, 350°F 5000.00 4000.00 n 3000.00 8

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

WT49, 3750 F Appendix C

K-B-16 00.00 4000.00 g

X 3000.00 2000.00 1000.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 and-i (ms)

WW51, -750 F 5000.00 4000.00 a

- 3000.00-2000.001 1000.00' 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Tme-1 (mas)

WW53, -50 0F Appendix C

B-17 4000.00 X 3000.00 2000.00 1000.00 -

0.00 0.00 1.W 2.00 3.W 4.00 5.00 6.00 Time-1 (ins)

WWV54, -25 0 F s00.00 4W0.00 -

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)

WW52, F C\1 Appendix C

B-18 S500.00 4000.00 30wo00 2000.00 1000.00 0.00 1.00 2.0 3.00 4.00 5.00 6.00 Thkc-1 (ms)

WW55, -10F 5000.00 4000.00 3000.O0 2000.00 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ins)

WW48, 0F cl%

Appendix C

B-i9 4000.00*

3000.00W-2000.00 1000.00 0.00 i 4--------

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

WW46, 10 0 F 5000.00.

4000.00 -

3000.00/t 2000.00 1000.00 2.00 3.00 6.00 Time-1 (ms)

WW59, 250 F Appendix C

mmm -

B-20 5000.00.

4000.00-30.00 0

.00 3.00 4.00 5.00 6.00 Tine-1 (ms)

WW57, 500 F

.00 3.00 4.00 5.00 6.00 Tffne-i (ms)

WW50, 50 0 F Appendix C

B-21 5000.00 4000.00

- 3000.001 2000.00 1000.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Tkro-1 (ms)

WW58, 750 F 5000.00-4000.00-a- 3000.00-2000.00-1000.00

, , , l l l , -P A_ B l .

l ,

nnn.

0.00 1.00 2.00 3.00 4.00 5.00 6.00 nrne-1 (Ms)

WW47, 1000 F rc Appendix C

B-22 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Tim-1 (Ms)

WW60, 150WF 5000.00 4000.00 i 30W.00 2000.00-1000.00' nrhl , , , ,

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

WW56, 175WF Appendix C

I B-23 5000.00 -

4000.00 3000.00-.

2000.00 1000.00 0.00

0. 10 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)

WW49, 225 0F 5000.00 4000.00 as 3000.00 2000.00 1000.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)

WH48, -90 0F Appendix C

-I f

B-24 0.00 1.00 2.00 3.00 4.00 5.00 6.00 TOMe-1 (ms)

WH55, -500 F 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Thr-I (ims)

WH50, F Appendix C

B-25 3000.00 2000.00 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Tine-1 (ins)

WH49, 0F 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 Tikm-1 (ms)

WH58, 250 F C2P Appendix C

B-26 5000.00 4000.00 I- 300.00-2000.00 1000.00 0.00 00 1.00 2.00 3.00 4.00 5.00 6.00 Tmwe-1 (ms)

WH53, 500 F a

0.00 1.00 2.00 3.00 4.00 5.00 6.00 Tme*1 (Ms)

WHS1, 75 0F Appendix C rC-?

B-27 1.00 2.00 3.00 4.00 5.00 6.00 Time-i (ms)

WH54, lOOTF 5000.00 4000.00-300000-2000.00-1000.00-0.00n. , , ,

6.00 0.00 1.00 i2.00 3.00 4.0 5.00 Time-1 (ms)

WH47, 125 0F C2C9 Appendix C

B-28 soon 4000.00O Ii i3000.00-2000.00 1000.00 0.00 0.1 .00 3.00 6.00 rW5e-1 (Ms)

WH52, 135°F 5000.00 4000.00

- 3000.00 2000.00 1000.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 rne-1 (Ms)

WH46, 150 0 F Appendix C L1

B-29 500 0 4000.00 t 3000.00 0

2000.00 100O0.

0.00 01 00 1.00 2.00 3.00 4.00 5.00 6.00 Tine-1 (ms)

H59, 1750 F 5000.00 4000.00 9 3000.00 g

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

W160, 2000 F Appendix C

B-3D W.o 3.00 6.00 TW7-1 (2n2)

WH57, 225°F 0.00 1.00 2.00 3.00 4.00 S.0 6.00 Tkmn-1 (Ens)

WH56, 2500 F Appendix C

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

C-l 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 E185-82, Section 4.18, and reads as follows:

"tupper 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."

Westinghouse typically reports the average of all Charpy data 2 95% shear as the USE. In some instances, there may be data deemed 'out of family' and are removed from the determination of the USE based on engineering judgement. The USE values reported in Table C-I 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.

Table C-1 Upper Shelf Energy Values Fixed in CVGraph Material Unirradiated Capsule U Capsule V Capsule W Capsule X Intermediate Shell Plate 95 ft-lbs 105 ft-lbs 85 ft-lbs 94 ft-lbs 81 ft-lbs B9004-2 (Long.)

Intermediate Shell Plate 79 ft-lbs 87 ft-lbs 76 ft-lbs 75 ft-lbs 74 ft-lbs B9004-2 (Trans.)

Weld Metal 139 ft-lbs 134 ft-lbs 136 ft-lbs 136 ft-lbs 133 ft-lbs (Heat # 83652)

Heat Affected 91 ft-lbs 109 ft-lbs 87 ft-lbs 104 ft-lbs 114 ft-lbs Zone Material Appendix C

C-2 UNIRILADIATED INTERMEDIATE SHELL PLATE B9004-2 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/29/2005 03:05 PM Page I Coefficients of Curve I A = 48.6 B =46A C = 98.21 T0 = 77.3 D =O.OOE+00 Equation is A + B * (Tanh((T-To)I(C+DT))]

Upper Shelf Energy=95.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 fl-lbs=35.6 Deg F Temp@50 ft-lbs=80.3 Deg F Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: LT Capsule: UNIRR Fluence: t/cmA2 300 250

, 200 0

IL-g 150 8 100 0/-

50 0 0 I00 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

-75. 00 6.0 0 6.19 -. 19

-50.00 7.00 8.66 -1.66

-10. 00 22. 00 1 5. 6 2 6. 3 8

-I 0. 00 30.00 15. 6 2 14.38

10. 00 26. 00 20.99 5.01

10. 00 23. 00 20.99 2. 0 1 3 0. 00 3 1. 00 27.83 3.17

30. 00 21.00 27.83 - 6. 8 3

75. 00 45. 00 4 7. 5 1 - 2. 5 1 Appendix C

C-3 UNIRRADIATED INTERMEDIATE SHELL PLATE B9004-2 (LONGITUDINAL)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: LT Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

75. 00 34.00 47.51 - 13.51 100.00 69. 00 5 9. 14 9.8 6 100. 00 55. 00 59. 14 -4. 14 100.00 4 5. 0 0 5 9. 14 - 14. 14 150.00 85.00 77.80 7.20 150.00 85.00 77.80 7. 20 210.00 94. 0 0 8 9. 1 7 4.83 210.00 9 6. 00 8 9. 1 7 6. 83 210.00 94. 0 0 8 9. 17 4.83 Correlation Coefficient - .970 Appendix C

C-4 CAPSULE U INTERMEDIATE SHELL PLATE B9004-2 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/29/2005 03:05 PM Page 1 Coefficients of Curve 2 A = 53.6 B = 51.4 C = 131.08 TO - 124.63 D = O.OOE+00 Equation is A + B * [Tanh((r-To)/(C+DT))]

Upper Shelf Energy=I05.0(Fixed) Lower Shelf Energy 2.2(Fixed)

Tenmp30 R-lbs=59.6 Deg F Temp@50 R-lbs=1 15.5 Deg F Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: LT Capsule: U Fluence: n/cMnA2 300 250 aJ 200 P 150 z

100

. _ 7T 50

-1 a 0

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

- 60. 00 4.00 8.00 -4. 00

- 30. 00 18. 00 11.07 6. 93

25. 00 25.00 20.65 4. 35

25. 00 33.00 20.65 12.35

50. 00 24. 00 27. 13 -3. 13

50. 00 29. 00 27. 13 1.87

74. 00 35.00 34.68 .32

75. 00 33.00 35.02 -2. 02 100. 00 48.00 44.05 3.95 Appendix C

C-s CAPSULE U INTERMEDIATE SHELL PLATE B9004-2 (LONGITUDINAL)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: LT Capsule: U Fluence: n/cmr2 Charpy V-Notch Data Texnperature Input CVN Computed CVN Differential 125. 00 37. 00 53.74 - 16. 74 125. 00 53. 00 53.74 -. 74 150. 00 55.00 63. 42 -8.42 200. 00 94.00 80.28 13. 72 300. 00 1 09. 00 98.38 10. 62 400. 00 1 1 1. 00 103.48 7. 52 Correlation Coefficient = .970 Appendix C

C-6 CAPSULE V INTERMEDIATE SHELL PLATE 9004-2 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/29/2005 03:06 PM Coefficients of Curve 3 A = 43.6 B = 41.4 C = 110.82 TO = 129.32 D = O.0OE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=85.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Ternp@30 ft-lbs=91.6 Deg F Temp@50 ft-lbs=146.6 Deg F Plant: BEAVER VALLEY 2 Material: SA533B I Heat: C0544-2 Orientation: LT Capsule: V Fluence: nkcre2 300 250 a-200 0

P 150 Lu 8 100 0 4 0...

50 1.40I 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 6.00 5.33 . 67

.00 10.00 9.52 .48

25. 00 18.00 13.14 4. 86

50. 00 16.00 18.17 -2.17

65. 00 25.00 21.95 3.05

75. 00 32.00 24.79 7.21 85.00 24.00 27.87 -3.87 100.00 32.00 32.90 .90 150.00 42.00 51.24 - 9.24 Appendix C

C-7 CAPSULE V INTERMEDIATE SHELL PLATE 9004-2 (LONGITUDINAL)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: LT Capsule: V Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Comput ed CVN Differential 200. 00 67.00 66 . 92 .08 250. 00 77.00 76 .57 .43 275. 00 90.00 79 .43 10.57 300. 00 82.00 81 .36 .64 325.00 92.00 82 .65 9.35 Correlation Coefficient =.986 Appendix C

C-8 CAPSULE W INTERMEDIATE SHELL PLATE 9004-2 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/29/2005 03:06 PM Page I Coefficients of Curve 4 A = 48.1 B - 45.9 C = 114.14 TO = 154.1 D = O.OOE+OO Equation is A + B * [Tanh((r-To)Y(C+DT))]

Upper Shelf Energy-94.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 fl-lbs=l 06.6 Deg F Temp@50 ft-lbs=158.9 Deg F Plant: BEAVER VALLEY 2 Material: SA533B I Heat: C0544-2 Orientation: LT Capsule: W Fluencc: n/cm\2 300 250

, 200 Is 0

U-P 150 0

Lu

100 50 0 +.

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

-50. 00 6. 00 4. 7 0 I.30

.00 9. 00 7. 9 8 1.02 50.00 24. 00 14. 9 6 9. 04 100.00 28. 00 27. 84 .16 115. 00 30. 00 32.96 -2. 96 125.00 36.00 36. 65 -. 65 140. 00 42. 00 42.46 - . 46 ISO. OO 54. 00 46. 45 7. 55 150. 00 35. 00 46.45 -I 1. 45

-1 Appendix C

C-9 CAPSULE W INTERMEDIATE SHELL PLATE 9004-2 (LONGITUDINAL)

Page 2 Plant: BEAVERVALLEY 2 Material: SA533B1 Heat: C0544-2 Orientation: LT Capsule: W Fluence: n/cm\2 Charpy V-Notch Data Teiiperature Input CVN Computed CVN Differential 160. 00 46. 00 50.47 .4. 47 175.00 64. 00 56.41 7.5 9 200. 00 62. 00 65.62 -3. 62 250.00 82.00 79. 5 8 2.42 300.00 92. 00 87.39 4.6 1 350. 00 95. 00 91. 13 3.87 Correlation Coefficient -. 981 Appendix C

C-li)

CAPSULE X INTERMEDIATE SHELL PLATE B9004-2 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/29/2005 03:06 PM Page 1 Coefficients of Curve 5 A = 41.6 B = 39.4 C = 99.55 TO = 163.71 D =0.OOE+00 Equation is A + B * [Tanh((T-Toy(C+DT))]

Upper Shelf Energy=8 I.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ftl-bs=133.6 Deg F Temp@50 ft-lbs=185.3 Deg F Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: LT Capsule: X Fluence: n/cmA2 300 250

, 200

a 150 z

8 100 R

¶,r 50 0

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

-50. 00 3. 00 3. 2 6 -. 26

25. 00 I1. 00 6. 77 4. 23 75.00 25.00 13. 5 5 1 1. 45 100. 00 23. 00 19.34 3. 66 125.00 27. 00 27. 01 - .0 1 150.00 35.00 3 6. 2 1 - 1.21 175. 00 38. 00 46. 05 - 8. 05 200. 00 3 7. 00 55.36 - 18.36 225. 00 75. 00 63. 2 0 1 1. 80

_ I Appendix C

C-lI CAPSULE X INTERMEDIATE SHELL PLATE B9004-2 (LONGITUDINAL)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533B1 Heat: C0544-2 Orientation: LT Capsule: X Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 250. 00 7 8. 0 0 69. 1 7 8. 83 275. 00 77.00 73.39 3. 6 1 280. 00 73.00 74.05 -I . 0 5 32S. 00 87.00 78.03 8. 9 7 350.00 89. 00 7 9. 1 8 9. 8 2 375. 00 86.00 79.89 6. 11 Correlation Coefficient -. 965 Appendix C

C-1:2 UNIRFADIATED INTERMEDIATE SHELL PLATE B9004-2 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 10/28/2005 11:41 AM Page I Coefficients of Curve I A = 39.45 B = 38.45 C = 94.75 TO =93.9 D = O.OOE+O0 Equation is A + B * [Tanh((T-ToY(C+DT))]

Upper Shelf L.E.=77.9 Lower Shelf LE.=I.O(Fixed)

Tenp.@L.E. 35 mils=82.9 Deg F Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: LT Capsule: UNIRR Fluence: n/cm^2 200 150 E

C

.2 B. 100 C

50 o 4-

-300 0 300 600 Temperature In Deg F Charpy V-Notch Data Temperature Input LE. Confuted LE. Differntial

-75. 00 .00 3. 12 -3. 12

-50. 00 .00 4. 52 -4. 52

-10. 00 1 1. 0 0 8. 7 2 2.2 8

-0. 00 13.50 8.72 4.78 I 0. 00 14. 00 12. 18 1.82 10.00 13. 00 12. 18 .82 30.00 20. 00 16.84 3. 16 30.00 13. 00 16. 84 -3. 84 75.00 3 2. 00 3 1. 8 8 .12 Appendix C

C-i13 UNIRRADIATED INTERMEDIATE SHELL PLATE B9004-2 (LONGITUDINAL)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533B1 Heat: C0544-2 Orientation: LT Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Ternperature Input L.E. Computed L.E. Differential

75. 00 28.50 31.88 -3.38 1 00. 00 45.50 41. 92 3.58 100.00 37. 00 41. 92 -4.92 1 00. 00 41. 00 41. 92 -. 92 150. 00 62. 50 59. 88 2. 62 150.00 62. 50 59. 88 2.62 210.00 69. 00 71.79 -2. 79 210. 00 73. 00 71.79 1.21 210.00 71.00 71.79 - .79 Correlation Coefficient =.993 Appendix C

C-14 CAPSULE U INTERMEDIATE SHELL PLATE B9004-2 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 10/28/2005 11:17 AM Page I Coefficients of Curve 2 A 40.38 B = 39.38 C = 143.58 TO = 127.55 D = 0.0OE+OO Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf LE.=79.8 Lower Shelf L.E.=I.0(Fixed)

Temp.@LsE. 35 mils=107.9 Deg F Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: LT Capsule: U Fluence: n/cm^2 200 150 E

I

.2 a 100

<D 0

50 0 +-._

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

-60. 00 5.00 6. 38 -1. 38

-30. 00 1 0. 00 8.89 1.11

25. 00 1 9. 0 0 1 6. 23 2.7 7

25. 00 22.00 1 6. 23 5.7 7

50. 00 20. 00 20. 96 -. 96

50. 00 20. 00 20. 96 -. 96 74.00 24. 00 26.34 -2. 34

75. 00 24. 00 26.58 -2. 58 100. 00 37. 00 3 2. 9 1 4.09 Appendix C

C-15 CAPSULE U INTERMEDIATE SHELL PLATE B9004-2 (LONGITUDINAL)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: LT Capsule: U Fluence: n/cmA2 Charpy V-Notch Data Temperature Input LE. Computed LE. Differential 125.00 33.00 39. 68 -6. 68 125. 00 39.00 39.68 -. 68 150.00 45. 00 46.48 - 1. 4 S 200. 00 66.00 58. 72 7. 28 300. 00 72. 00 73. 22 - 1.22 400. 00 77. 00 78. 02 - 1. 02 Correlation Coefficient -. 987 Appendix C

C-16 CAPSULE V INTERMEDIATE SHELL PLATE B9004-2 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 10/28/2005 11:17 AM Page I Coefficients of Curve 3 A = 37.35 B = 36.35 C = 130.93 TO = 150.4 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=73.7 Lower Shelf L.E.=l.O(Fixed)

Ternp.@LE. 35 mils= 142.0 Deg F Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: LT Capsule: V Fluence: n/cmA2 200 150 a-2 El 100 C

50 o -

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

-50. 00 6. 00 4.25 I .7 5

. 00 6. 0 0 7. 64 - 1. 64

25. 00 1 1. 0 0 1 0. 3 3 .67 50.00 10.00 13. 90 -3. 90 65.00 19. 00 1 6. 5 2 2. 48

75. 00 20. 00 1 8. 4 6 1. 54 85.00 22.00 20.57 1.43 1 00. 0 0 24. 00 24. 01 - .01 150.00 34. 00 37.24 -3. 24

-- - 0 w Appendix C

C-17 CAPSULE V INTERMEDIATE SHELL PLATE B9004-2 (LONGITUDINAL)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533B1 Heat: C0544-2 Orientation: LT Capsule: V Fluence: n/cmA2 Charpy V-Notch Data Temperature Input LE. Computed LE. Differential 200. 00 52.00 50.50 1.50 250.00 60. 00 60. 67 - . 67 275.00 67. 00 64. 27 2. 73 300. 00 66. 00 66. 99 - . 99 325. 00 68. 00 68.98 -. 98 Correlation Coefficient - .996 E

Appendix C

C-18 CAPSULE W INTERMEDIATE SHELL PLATE B9004-2 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 10/28/2005 11:17 AM Page I Coefficients of Curve 4 A = 30.95 B = 29.95 C = 105.74 TO = 158.73 D = 0.OOE+00 Equation is A + B * [Tanh((T-Toy(C+DT))]

Upper Shelf L.E.=60.9 Lower Shelf L.E.=l.O(Fixed)

Ternp.@L.E. 35 mils=173.2 Deg F Plant: BEAVERVALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: LT Capsule: W Fluence: ncmrA2 200 150

.a T

.2 a 100 50 o 4-'

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

-50. 00 .00 2. 13 -2. 13

.00 2. 00 3. 83 -I .8 3

50. 00 II . 00 7. 7 9 3. 2 1 1 00. 00 16. 00 15. 84 .16 115.00 21.00 1 9. 2 2 1. 78 1 25. 00 2 3. 00 21.71 1. 29 140. 00 25. 00 25. 70 -. 70 150.00 3 1. 00 28.48 2. 5 2 150. 00 21. 00 28.48 -7. 48 Appendix C

C-19 CAPSULE W INTERMEDIATE SHELL PLATE B9004-2 (LONGITUDINAL)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: LT Capsule: W Fluence: n/CMA2 Charpy V-Notch Data Temperature Input LE. Computed LE. Differential 160.00 27. 00 31.31 -4. 31 175.00 42. 00 35.52 6. 48 200. 00 42. 00 42.08 - . 08 250. 00 5 1. 00 51. 85 - . 85 300. 00 60. 00 5 7. 02 2. 98 350. 00 57. 00 59. 33 -2. 33 Correlation Coefficient -. 983 Appendix C

C-20 CAPSULE X INTERMEDIATE SHELL PLATE B9004-2 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 10/28/2005 11:17 AM Page I Coefficients of Curve 5 A = 34.96 B = 33.96 C = 127.68 TO = 180.18 D = O.OOE+00 Equation is A + B * [Tanh((T-ToY(C+DT))]

Upper Shelf L.E.=68.9 Lower Shelf L.E.=l.O(Fixed)

Tenp.@L.E. 35 mnls=1 80.4 Deg F Plant: BEAVER VALLEY 2 Material: SA533B1 Heat: C0544-2 Orientation: LT Capsule: X Fluencc: n/cmA2 200 I

150 I_ _ _ _ _

0 ca

. 100 2

• 50 a _,-_I ____*o_'

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

-50. 00 1.00 2. 80 -1. 80

25. 00 8. 00 6. 49 1.51 75.00 17. 00 11.96 5.04 1 00. 00 1 S. 00 16.05 1.95 125. 00 21. 00 21.13 -. 13 150.00 26. 00 27.08 - 1.08 175.00 30. 00 33.58 -3. 58 200. 00 29. 00 40. 19 - 1. 19 225. 00 53.00 46.41 6.59 Appendix C

C-21 CAPSULE X INTERMEDIATE SHELL PLATE B9004-2 (LONGITUDINAL)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: LT Capsule: X Fluence: n/cmr2 Charpy V-Notch Data Temperature Input L.E. Computed LE. Differential 250. 00 58. 00 51.87 6. 13 275. 00 59. 00 56.37 2. 63 280..00 58.00 57. 15 .85 325.00 60. 00 62. 55 -2.55 350. 00 65.00 64. 47 .53 3 75. 00 63.00 65. 85 -2. 85 Correlation Coefficient = .980 Appendix C

C-22 UNIRRADIATED INTERMEDIATE SHELL PLATE B9004-2 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/29/2005 03:22 PM Coefficients of Curve I A = 50. B = 50. C = 81.15 TO = 115.34 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = 115.4 Plant: BEAVER VALLEY 2 Matcrial: SA533BI Heat: C0544-2 Orientation: LT Capsule: UNIRR Fluence: n/cmnA2 125 100 0 75 In 0?

50 25 0 _-

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

-75. 00 . 00 .9 1 -. 91

-50. 00 . 00 1 . 67 - 1. 67

-10. 00 . 00 4.36 -4. 36

- 10.00 . 00 4. 3 6 -4. 36 10.00 . 00 6. 94 -6. 94 1 0. 0 0 .0 0 6. 94 -6. 94

30. 00 10. 00 10. 88 -. 88

30. 00 I 0. 00 10. 88 -. 88

75. 00 27. 00 27. 01 -. 01 Appendix C

C-23 UNIRRADIATED INTERMEDIATE SHELL PLATE B9004-2 (LONGITUDINAL)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533B1 Heat: C0544-2 Orientation: LT Capsule: UNIRR Fluence: r/CMnA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

75. 00 32. 00 27. 01 4. 99 100. 00 61.00 40. 66 20. 34 100. 00 47. 00 40. 66 6. 34 100. 00 36. 00 40. 66 -4. 66 150. 00 50. 00 70. 14 -20. 14 150. 00 57. 00 70. 14 - 13. 14 210. 00 100.00 91. 16 8. 84 210. 00 100.00 91. 16 8. 84 210.00 100.00 91.16 8.84 Correlation Coefficient = .969 Appendix C

C-24 CAPSULE U INTERMEDIATE SHELL PLATE B9004-2 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/29/2005 03:22 PM Page I Coefficients of Curve 2 A=50. B=50.C=104.13 TO=125.04 D=O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50%/o Shear = 125.1 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544.2 Orientation: LT Capsule: U Fluence: n/cmA2 125 100

/P ao 75 0

I, 0

a. 50 /a aL 0 I/ ,

25 i ci-rr

=r_

i i 0

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

- 60. 00 5. 00 2.7 8 2. 2 2

-30. 00 5. 0 0 4.84 .16 25.00 15. 00 12.77 2. 2 3

25. 00 15. 00 1 2. 77 2. 2 3 50.00 20.00 19. 14 .86 50.00 20. 00 19. 14 .86

74. 00 30.00 27.28 2. 7 2 75.00 30. 00 27. 67 2. 3 3 1 00. 00 45.00 38. 21 6.79 6

Appendix C

C-25 CAPSULE U INTERMEDIATE SHELL PLATE B9004-2 (LONGITUDINAL)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: LT Capsule: U Fluence: n/cm12 Charpy V-Notch Data Termperature Input Percent Shear Cornputed Percent Shear Differential 125.00 40. 00 49.98 -9. 98 125.00 4 5. 00 49.98 - 4. 9 8 150.00 50. 00 6 1. 76 - 1. 76 200. 00 100. 00 80. 84 19. 16 300.00 100.00 96. 64 3. 3 6 400. 00 100. 00 99. 49 .51 Correlation Coefficient = .978 Appendix C

C-26 CAPSULE V INTERMEDIATE SHELL PLATE B9004-2 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/29/2005 03:22 PM Page I Coefficients of Curve 3 A = 50. B = 50. C = 102.55 TO = 164.92 D = O.OOE+OO Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = 165.0 Plant: BEAVER VALLEY 2 Material: SA533B I Heat: C0544-2 Orientation: LT Capsule: V Fluence: n/cm^2 125 100 CS. 75 to 50 I I_ _ __ _

/I i1 25 a

-300 -200 -100 0

0 100

-0

/

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

-50. 00 .00 1.49 -1.49

.00 5.00 3. 86 1. 14 25.00 10. 00 6. 13 3. 87

50. 00 15. 00 9. 61 5. 39 65.00 20. 00 12.47 7.53 75.00 20. 00 14.76 5.24 85.00 20.00 17. 38 2. 62 100.00 25. 00 21.99 3. 01 150.00 30. 00 42. 78 - 12.78

-__ I Appendix C

C-27 CAPSULE V INTERMEDIATE SHELL PLATE B9004-2 (LONGITUDINAL)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: LT Capsule: V Fluence: n/cmA2 Charpy V-Notch Data Tempcrature Input Percent Shear Computed Percent Shear Differential 200. 00 50. 00 66.47 - 16.47 250. 00 1 00. 00 84. 02 15. 98 275. 00 100. 00 89.54 10.46 300. 00 1 00. 00 93.31 6.69 325.00 100.00 95. 78 4. 22 Correlation Coefficient = .978 Appendix C

C-28 CAPSULE W INTERMEDIATE SHELL PLATE B9004-2 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/29/2005 03:22 PM Page I Coefficients of Curve 4 A 50. B - 50. C = 68.4 TO = 170.19 D - 0.00E+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = 170.2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: LT Capsule: W Fluence: n/crnA2 125 100 a, 75 a-50 25 O +-

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

-50. 00 2. 00 .16 1.84

.00 5.00 . 69 4.31 5 0. 00 1 0. 00 2.89 7.11 100.00 1 5.0 0 11.38 3. 62 1 15. 00 20. 00 16.61 3.39 125. 00 20. 00 21. 06 - 1. 06 140. 00 25. 00 29.26 -4. 26 150.00 35.00 35. 65 -. 65 ISO. 00 30. 00 35. 65 -5. 65 Appendix C

C-29 CAPSULE W INTERMEDIATE SHELL PLATE B9004-2 (LONGITUDINAL)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: LT Capsule: W Fluence: n/cMA2 Charpy V-Notch Data Temperature Input Percent Shear Conputed Percent Shear Differential 160.00 40.00 42.60 -2. 60 175.00 65.00 5 3. 5 1 1 1. 49 200. 00 65.00 70. 50 -5. 50 250. 00 95. 00 91.16 3. 84 300. 00 100.00 97.80 2.20 350. 00 100.00 99. 48 .52 Correlation Coefficient = .991 Appendix C

C -3.;0 CAPSULE X INTERMEDIATE SHELL PLATE B9004-2 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/29/2005 03:22 PM Page I Coefficients of Curve 5 A = 50. B = 50. C = 71.78 TO = 175.02 D = O.OOE+00 Equation is A + B * [Tanh((r-ToY(C+DT))]

Temperature at 50% Shear = 175.1 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: LT Capsule: X Fluence: n/cmA2 125 100 0

U)

I&D IL 0 I , I , y -. I -1 -

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

-50. 00 2. 00 .19 1.81 25.00 5.00 1 .5 1 3. 4 9

75. 00 10.00 5.80 4.20 100. 00 20. 00 1 1.01 8. 99 125.00 25.00 19.88 5. 12 150. 00 35.00 33.25 1. 7 5 175.00 40.00 49. 99 -9. 99 200. 00 5 0. 00 6 6. 73 - 1 6. 73 225. 00 95. 00 80. 10 1 4. 90 Appendix C

C-3 1 CAPSULE X INTERMEDIATE SHELL PLATE B9004-2 (LONGITUDINAL)

Page 2 Plant: BEAVER VALLEY 2 Material:SA533BI Heat: C0544-2 Orientation: LT Capsule: X Fluence: n/cm12 Charpy V-Notch Data Terrperature Input Percent Shear Computed Percent Shear Differential 250. 00 100.00 88.98 11. 02 275.00 98.00 94. 19 3.81 280.00 98.00 94.91 3. 09 325.00 1 00. 00 98.49 1.51 350.00 100.00 99. 24 .76 375. 00 100. 00 99. 62 . 38 Correlation Coefficient - .982

-0 1 Appendix C

C-$ 2 UNIRRADIATED INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/29/2005 03:50 PM Coefficients of Curve I A = 40.6 B = 38.4 C = 96.46 TO = 67.07 D - 0.O0E+00 Equation is A + B * [Tanh((T-Toy(C+DT))]

Upper Shelf Energy=79.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Ternp@30 fl-lbs=39.8 Deg F Temp@50 ft-lbs=91.2 Deg F Plant: BEAVER VALLEY 2 Material: SA533B I Heat: C0544-2 Orientation: TL Capsule: UNIRR Fluence: n/ctn^2 300 250

, 200

150 w

z 8 100 50 0+

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

-40. 00 6. 00 9. 72 -3. 72

-40. 00 S.00 9. 72 -4. 72

-15. 00 20. 00 14. 05 5. 95

10. 00 25.00 20.21 4. 79

20. 00 26. 00 23.22 2. 78

50. 00 39. 00 33.87 5. 13

50. 00 28. 00 33. 87 -5. 87

50. 00 33.00 33.87 - . 87 100. 00 5 0. 00 53. 22 -3. 22 Appendix C

C-33 UNIRRADIATED INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: TL Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 100. 00 47. 00 53.22 -6. 22 125.00 61. 00 61.24 -. 24 150. 00 68. 00 67. 33 .67 150. 00 71.00 67. 33 3.67 210.00 77. 00 75. 23 1.77 210. 00 80. 00 75. 23 4.77 210.00 80. 00 75. 23 4.77 300.00 82. 00 78.39 3.61 300. 00 76. 00 78.39 - 2.39 Correlation Coefficient -. 988 Appendix C

C-34 CAPSULE U INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/29/2005 03:51 PM Page I Coefficients of Curve 2 A = 44.6 B = 42.4 C =133.76 TO 105.42 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy-87.0(Fixed) Lower Shelf Energy2.2(Fixed)

Ternp@30 ft-lbs=57.5 Deg F Ternp@50 ft-lbs=122.6 Deg F Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: TL Capsule: U Fluence: n/cm^2 300 I

250

, 200 06

15 T

P150 z

100 50 1,... z I 0

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

-30. 00 13. 00 12. 09 .9 1

25. 00 19. 00 21.79 -2. 79

40. 00 23. 00 25. 37 -2.37

60. 00 37. 00 30.73 6. 27

60. 00 40. 00 30. 73 9.27

74. 00 34. 00 34. 82 - . 82 75.00 33. 00 35. 12 -2. 12 1 00. 00 43.00 42. 88 .12 1 00. 00 39. 00 42. 88 -3. 88 Appendix C

C-35 CAPSULE U INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: TL Capsule: U Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 125. 00 45.00 50.76 -5. 76 Is0. 00 58.00 58.23 - .23 200. 00 67. 00 70.41 -3.41 250.00 89.00 78.24 10.76 350.00 87.00 84. 87 2. 13 450. 00 85.00 86.51 - 1.51 Correlation Coefficient .981 Appendix C

CAPSULE V INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/29/2005 03:51 PM Page 1 Coefficients of Curve 3 A = 39.1 B = 36.9 C = 118.74 TO = 115.7 D = O.OOE+0O Equation is A + B * [Tanh((T-To)I(C+DT))]

Upper Shelf Energy=76.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Ternp@30 fl-lbs=85.9 Deg F Temp@50 ft-lbs=151.9 Deg F Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: TL Capsule: V Fluence: n/cmA2 300 250 J 200 a

P150 z

100

--K-....

50 0

r

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

-50. 00 7. 00 6. 47 .53

-25. 00 12. 00 8.51 3.49

. 00 14.00 11.40 2.60 25.00 15. 00 15.36 - .36 50.00 28.00 20. 54 7. 46 75.00 28. 00 26. 92 1.08

85. 00 27. 00 29. 77 -2. 77 100.00 33. 00 34.25 - 1.25 125. 00 38.00 41.98 -3.98 Appendix C

C-37 CAPSULE V INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533B1 Heat: C0544-2 Orientation: TL Capsule: V Fluence: n/cm'2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 150.00 43.00 49.47 -6.47 200. 00 56. 00 61.63 -5. 63 225. 00 73.00 65.89 7.11 250. 00 80. 00 69. 04 10. 96 275. 00 74.00 71.28 2.72 300. 00 78.00 72.83 5. 17 Correlation Coefficient = .981 Appendix C

C-38 CAPSULE W INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/29/2005 03:51 PM Page I Coefficients of Curve 4 A = 38.6 B = 36.4 C =106.94 TO = 128.94 D = O.OOE+00 Equation is A + B * (Tanh((T-Toy(C+DT))]

Upper Shelf Energy=75.0(Fixed) Lower Shelf Energy-2.2(Fixed)

Ternp130 R-lbs=103.2 Deg F Tcmp@50 fl-lbs=163.6 Deg F Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: TL Capsule: W Fluence: n/cmA2 300 250

], 200 a

2 P 150 C

W 8 100 Aff 50 A - -- ,~----- --.----

A-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

- 50. 00 II. 0 0 4.68 6.32

. 00 12. 00 8. 19 3.8 1 5 0. 00 18. 00 15. 74 2.2 6

85. 00 24. 00 24.43 -. 43 100. 00 31.00 28.98 2.02 I 1 5. 00 32. 00 33. 88 -1.88 125. 00 36.00 37. 26 - 1.26 150.00 4 1. 0 0 45. 68 -4. 6 8 1 65.00 5 2. 00 50.43 1 .5 7 Appendix C

C-39 CAPSULE W INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533B I Heat: C0544-2 Orientation: TL Capsule: W Fluence: nrcmA2 Charpy V-Notch Data Temperature Input CVN Comrputed CVN Differential 175.00 52. 00 53.37 - 1.37 200. 00 55.00 59. 76 - 4.76 225.00 67. 00 64. 64 2.36 250. 00 77. 00 68. 15 8. 85 300. 00 81.00 72. 15 8. 85 350.00 76. 00 73.85 2. 15 Correlation Coefficient e .984 Appendix C

CGAO CAPSULE X INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/29/2005 03:51 PM Page I Coefficients of Curve 5 A=38.1 B=35.9C=119.72 TO=171.36 D=O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=74.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Ternp@30 R-lbs=143.9 Deg F Temp@50 R-lbs=212.7 Deg F Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: TL Capsule: X Fluence: n/cMA2 300 1I 250 I.I a4200 12 g 150 II I I

100 50 ~~ .. , _v-t ~

I II 0 =_=W: i5_O, v-

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

- 50. oo 3. 00 3. 94 -. 94

25. 00 9.00 7. 93 1.07 50.00 9. 00 10.55 -1.55

75. 00 19. 00 14. 16 4.84 100. 00 20. 00 18.92 1. 08 125. 00 28.00 24. 85 3. 15 150. 00 32.00 31. 76 .24 175. 00 33.00 39. 19 -6. 19 200. 00 45. 00 46.53 - 1.53 Appendix C

C-41 CAPSULE X INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533B I Heat: C0544-2 Orientation: TL Capsule: X Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 250. 00 55.00 58.79 -3.79 275. 00 65.00 63. 20 1.8 0 300. 00 65. 00 66.50 - 1.5 0 325. 00 77.00 68. 88 8.12 350.00 78.00 70. 54 7.46 375. 00 74. 00 71.69 2.31 Correlation Coefficient - .990 Appendix C

C Z2 UNIRRADIATED INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 09/01/2005 03:56 PM Page 1 Coefficients of Curve I A = 32.63 B = 31.63 C = 91.03 TO = 83.96 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.-64.3 Lower Shelf L.E.I .O(Fixed)

Ternp.@L.E. 35 mils=90.8 Deg F Plant: BEAVER VALLEY 2 Material: SA533B1 Heat: C0544-2 Orientation: TL Capsule: UNIRR Fluence: n/cnA2 200 150 i

C EL 100 t1_

I5 50 0

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

-40. 00 .0 0 4.90 -4. 90

-40. 00 .00 4. 9 0 -4. 90

-15. 00 1 0. 0 0 7.46 2. 5 4 I 0. 00 14. 00 11. 4 1 2.5 9

20. 00 15. 00 13.46 1.54 50.00 2 5. 00 21.35 3.6 5 5 0. 00 20. 00 21. 3 5 - 1.35

50. 00 2 1. 00 21. 3 5 -. 35 100. 00 38. 00 38. 14 -. 14 i

i Appendix C

C43 UNIRRADIATED INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: TL Capsule: UNIRR Fluence: n/cmr2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential 100. 00 36. 00 38. 14 -2. 14 125. 00 43.00 45. 99 -2.99 150. 00 54.00 52.25 1.75 150.00 52. 00 52.25 -. 25 210. 00 60. 50 60. 52 -. 02 210.00 66. 00 60.52 5.48 210. 00 60. 00 60.52 -. 52 300. 00 66. 00 63.71 2.29 300. 00 58. 00 63. 71 -5.71 Correlation Coefficient -. 991 Appendix C

C-14 CAPSULE U INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 09/01/2005 03:57 PM Page 1 Coefficients of Curve 2 A = 32.48 B = 31A8 C = 130.65 TO = 91.78 D - O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=64.0 Lower Shelf L.E.=l.O(Fixed)

Tenp.@L.E. 35 miils= 102.3 Deg F Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: TL Capsule: U Fluence: n/cmA2 200 150 T

.2 C

0 100 5

50 O +._

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

-30. 00 8. 00 9. 45 - 1.45

25. 00 14. 00 17. 66 -3. 66

40. 00 23. 00 20. 62 2. 3 8

60. 00 27. 00 24. 97 2. 03

60. 00 33. 00 24. 97 8. 03

74. 00 23.00 28.23 -5. 23

75. 00 26. 00 28.46 -2. 4 6 100. 00 3 7. 00 34.46 2. 54 1 00. 00 34. 00 34.46 -. 46 Appendix C

C-45 CAPSULE U INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: TL Capsule: U Fluence: n/cmA2 Charpy V-Notch Data Temperature Input LE. Computed L.E. Differential 125.00 38.00 40. 32 -2.32 150.00 46. 00 45. 65 .35 200. 00 49. 00 53. 88 -4. 88 250. 00 65. 00 58. 84 6. 16 350. 00 66. 00 62. 78 3.22 450.00 59. 00 63. 71 -4.71 Correlation Coefficient = .973 Appendix C

C-46 CAPSULE V INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 09/01/2005 03:57 PM Page 1 Coefficients of Curve 3 A = 36.69 B = 35.69 C = 147.86 TO = 146.02 D = O.OOE+00 Equation is A + B I [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=72.4 Lower Shelf L.E.=I.O(Fixed)

Temp.@L.E. 35 rnils=139.0 Deg F Plant: BEAVER VALLEY 2 Material: SA533B I Heat: C0544-2 Orientation: TL Capsule: V Fluence: n/crm2 200 150 I

A

.2 C

.2 IL100 50 a I ......... ...... .__ __._.

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

-50. 00 6. 00 5.70 .30

- 25. 00 1 1. 00 7.43 3. 57

.00 8. 00 9.70 -1. 70

25. 00 10. 00 12.63 -2. 63

50. 00 20. 00 16.30 3. 70

75. 00 21.00 20. 76 . 24 8 5. 00 22. 00 22.75 - .75 100. 00 27. 00 25. 93 1. 07 125. 00 31.00 3 1. 65 -. 65 Appendix C

C-47 CAPSULE V INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: TL Capsule: V Fluence: rLcrn^2 Charpy V-Notch Data Temperature Input L.E. Computed LE. Differential 150.00 34.00 37. 65 -3. 65 200. 00 47. 00 49. 18 -2. 18 225. 00 56. 00 54. 13 1.87 250. 00 65. 00 58. 34 6.66 275. 00 63. 00 61.77 1.23 300. 00 59. 00 64.48 -5.48 Correlation Coefficient =.989 Appendix C

C-48 CAPSULE W INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 09/01/2005 03:57 PM Page I Coefficients of Curve 4 A = 28.88 B = 27.88 C = 92.25 TO = 158.27 D = O.OOE+00 Equation is A + B * [Tanh((T-Toy(C+DT))]

Upper Shelf L.E.=56.8 Lower Shelf L.E.=1.0(Fixed)

Ternp.@L.E. 35 mils=178.9 Deg F Plant: BEAVERVALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: TL Capsule: W Fluence: n/cMA2 200 150 e

.2 a 100 50 ,A-.

i f o -

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

-50. 00 7. 00 I . 60 5. 40

.00 2. 00 2.75 -. 75

50. 00 9. 00 5. 87 3. 13 85.00 15.00 10.46 4.54 100. 00 15. 00 13.29 1 . 71 115.00 24. 00 16. 68 7. 32 125. 00 .00 19.24 - 19.24 150.00 29. 00 26. 38 2. 62 165.00 37. 00 30. 91 6. 09 Appendix C

C-49 CAPSULE W INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: TL Capsule: W Fluence: n/CMA2 Charpy V-Notch Data Tempcrature Input L.E. Computed L.E. Differential 175. 00 31.00 33.88 -2.88 200. 00 38. 00 40. 69 -2. 69 225. 00 47.00 46. 13 . 87 250.00 54.00 50. 04 3. 96 300. 00 5 S. 00 54.29 3.71 350.00 5 0. 00 55.89 -5.89 Correlation Coefficient = .941 0 - - -

Appendix C

CAPSULE X INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 09/01/2005 03:57 PM Page I Coefficients of Curve 5 A = 29.2 B =28.2 C = 118.13 TO = 154.97 D =O.OOE+00 Equation is A + B * [Tanh((T-ToY(C+DT))]

Upper Shelf L.E.57.4 Lower Shelf L.E.=l.O(Fixed)

Temp.@L.E. 35 mils=179.7 Deg F Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: TL Capsule: X Fluence: nfcmA2 200 150 a

I

.2 a 100 I

50 I--_- -,- . X ._-v----------------- ---

a_

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

-50. 00 2. 00 2.70 -. 70

25. 00 7. 00 6.62 .38 50.00 9. 00 9. 16 - . 16 75.00 15. 00 12.58 2.42 100.00 16. 00 16.95 -. 95 125.00 25. 00 22.20 2.80 150. 00 28.00 28. 01 -. 01 175.00 28.00 33.94 -5.94 200. 00 39. 00 39.46 - .46 E

Appendix C

C-51 CAPSULE X INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: TL Capsule: X Fluence: n/cMA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential 250. 00 50.00 48.00 2. 00 275. 00 53.00 50.87 2. 13 300.00 57. 00 52. 94 4.06 325.00 55. 00 54.40 . 60 350.00 55.00 55.40 -. 40 375. 00 51. 00 56.08 -5. 08 Correlation Coefficient -. 991 Appendix C

UNIRRADIATED INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/29/2005 04:02 PM Page 1 Coefficients of Curve I A =50. B = 50. C =53.26 TO = 104.9 D = 0.00E+00 Equation is A + B * [Tanh((T-ToY(C+DT))]

Temperature at 50% Shear = 105.0 Plant:BEAVERVALLEY2 Material:SA533BI Heat:C0544-2 Orientation: TL Capsule: UNIRR Fluence: n/cmA2 125 100 I- 75 0.

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

-40. 00 .00 . 43 -. 43

-40. 00 .00 .43 -. 43

-15. 00 .00 1. 10 - 1. 10 I 0. 0 0 .00 2.7 6 -2. 76 20.00 .00 3.96 -3. 96

50. 00 10. 00 1 1. 2 9 -1. 29

50. 00 10. 00 1 1. 2 9 - 1.29

50. 00 1 0. 00 1 1. 2 9 - 1.29 1 00. 00 58. 00 45.41 12.59 Appendix C

C-53 UNIRRADIATED INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: TL Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 1 00. 00 47. 00 45.41 I .5 9 125. 00 5 0. 00 68.02 - 18.02 150.00 9 5. 00 84.47 10. 53 150. 00 8 1. 00 84. 47 .3. 4 7 210.00 100.00 98. 10 1 .9 0 210.00 100.00 98. 10 1 .9 0 210.00 100. 00 98. 10 1.90 300. 00 100.00 99. 93 .07 300. 00 100. 0 0 99. 93 .07 Correlation Coefficient e.990 Appendix C

C-54 CAPSULE U INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/29/2005 04:02 PM Page I Coefficients of Curve 2 A = 50. B = 50. C = 100.52 TO = 122.03 D = O.OOE+00 Equation is A + B * [Tanh((T-ToY(C+DT))]

Temperature at 50% Shear = 122.1 Plant: BEAVER VALLEY 2 Material: SAS33BI Heat: C0544-2 Orientation: TL Capsule: U Fluence: n/cm^2 125 100 _ _ _ I --- - - _

75 I/

0. 50 a

25 0

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

-30. 00 5. 00 4. 63 .37

25. 00 1 0. 00 1 2. 67 -2. 67 40.00 1 5. 00 1 6. 3 5 -1.35

60. 00 20. 00 22. 54 -2. 54

60. 00 35. 00 22.54 12.46

74. 00 3 0. 00 27.78 2. 22

75. 00 30.00 28. 18 1 .8 2 100. 00 4 0. 00 3 9. 2 1 .79 1 00. 00 40.00 3 9. 2 1 .79

- _ _ _ _ i Appendix C

C-55 CAPSULE U INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: TL Capsule: U Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 125.00 45. 00 51. 48 - 6. 48 150.00 50. 00 63.57 -13. 57 200. 00 95.00 8 2. 5 1 12.49 250.00 100. 00 92.73 7. 2 7 350. 00 I 00. 00 98.94 1.06 450.00 100. 00 99. 85 .15 Correlation Coefficient -. 982 Appendix C

C-56 CAPSULE V INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/29/2005 04:02 PM Page I Coefficients of Curve 3 A = 50. B = 50. C =81.08 TO = 157.09 D = 0.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = 157.1 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: TL Capsule: V Fluence: n/crna2 125 100 -.- 4O-.- .......

I-aw 75

/I I_ ___I _ _ _ _ _ _ _ _ _ _ _ _ _ _ I__

50 /

.. I 25 0

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

-50. 00 .0 0 . 60 -. 60

- 25. 00 5. 00 1.11 3. 89

.0 0 1 0. 00 2.03 7.97 25.00 10.00 3. 70 6. 3 0

50. 00 15. 00 6. 65 8.35 75.00 20. 00 11. 6 6 8. 3 4

85. 00 20. 00 14.45 5. 5 5 100. 00 20. 00 19.65 .35 125. 00 25. 00 31. 19 -6. 19 Appendix C

C-57 CAPSULE V INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: TL Capsule: V Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 150. 00 35.00 45.64 - 10. 64 200. 00 65. 00 74. 24 -9. 24 225. 00 1 00. 00 84. 23 15.77 250. 00 100. 00 90. 82 9.18 275. 00 100.00 94. 8 3 5.17 300. 00 1 00. 00 97. 14 2. 86 Correlation Coefficient .983 Appendix C

C-58 CAPSULE W INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/29/2005 04:03 PM Page I Coefficients of Curve 4 A = 50. B = 50. C =57.99 T0 156.22 D = O.O0E+00 Equation is A + B * (Tanh((T-Toy(C+DT))]

Temperature at 50% Shear - 156.3 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: TL Capsule: W Fluence: n/cre2 125 100 Io 75 0

P- 50 25 0 4-

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

-50.00 2. 00 .08 1.92

.00 5.00 .4 6 4.54 50.00 15.00 2.50 12.50 85.00 20. 00 7. 90 12. 10 100.00 20. 00 12.58 7. 42 115.00 25.00 19.44 5.56 125. 00 5. 00 25.41 20.41 150.00 45. 00 44. 66 .34 165.00 55.00 57.52 -2.52 Appendix C

C-59 CAPSULE W INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

Page 2 Plant: BEAVERVALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: TL Capsule: W Fluence: n/crnA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 175.00 70. 00 65.65 4.35 200. 00 8 0. 00 81.91 - 1.91 225. 00 100. 00 91.47 8.53 250. 00 100. 00 96. 21 3. 79 300.00 100. 00 99.30 .70 350. 00 100. 00 99.88 .12 Correlation Coefficient = .980 Appendix C

C-6iO CAPSULE X INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/29/2005 04:03 PM Page I Coefficients of Curve 5 A = 50. B = 50. C = 113.12 TO = 175.03 D = O.OOE+00 Equation is A + B * [Tanh((T-Toy(C+DT))]

Temperature at 50% Shear = 175.1 Plant: BEAVER VALLEY 2 Material: SA533B I Heat: C0544-2 Orientation: TL Capsule: X Fluence: n/cmA2 125 100 75 co 0

a. 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

-50. 00 2.00 1. 84 .16

25. 00 10.00 6. 58 3.42

50. 00 15. 00 9. 88 5. 12 75.00 20. 00 14.57 5. 43 1 00. 00 25. 00 20. 97 4. 03 125. 00 30. 00 29.22 .78 150. 00 35.00 39.11 - 4.11 175.00 45. 00 49. 99 -4. 99 200. 00 55.00 60. 86 -5. 86 Appendix C

C-61 CAPSULE X INTERMEDIATE SHELL PLATE B9004-2 (TRANSVERSE)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: TL Capsule: X Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 250. 00 75.00 79. 01 -4. 01 275. 00 90. 00 85. 42 4.5 8 300.00 100.00 90. 11 9.89 325.00 100. 00 93.41 6. 59 350.00 100. 00 95. 66 4. 34 375.00 100. 00 97. 17 2.83 Correlation Coefficient = .992 Appendix C

- ] aI C-62 UNIRRADIATED (WELD METAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/30/2005 10:18 AM Page I Coefficients of Curve I A = 70.6 B = 68.4 C = 48.66 TO = -6.58 D = 0.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=139.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 fl-lbs-39.8 Deg F Ternp@50 ft-lbs-21.7 Deg F Plant: BEAVER VALLEY 2 Material: SAW Heat: 83642 Orientation: NA Capsule: UNIRR Fluence: nlcm^2 300 250

, 200 4-2 Bi150 z

6 100 50 o _

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

- 60. 00 0O.00 15.90 -5. 90

- 60. 00 15. 00 15. 90 -. 90

- 25.00 17. 00 45. 88 -28.88

- 25.00 15. 00 45. 88 -30. 88

- 25. 00 71.00 45. 8 8 25. 12

- 10. 00 101.00 65.81 35. 19

.00 46. 00 79. 80 - 33. 80

.00 106. 00 79. 80 26. 20

.00 100.00 79. 80 20. 20 6 - I -

Appendix C

C-63 UNIRRADIATED (WELD METAL)

Page 2 Plant: BEAVER VALLEY 2 Material: SAW Heat: 83642 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 30.00 114.00 114.12 -. 12

30. 00 117. 00 114.12 2.88 30.00 89. 00 114.12 -25.12 100. 00 135.00 137.31 -2. 31 100. 00 109.00 137.31 -28.31 150.00 137. 00 138.78 -1.78 210.00 135.00 138.98 -3. 98 210.00 139. 00 138.98 . 02 210. 00 144.00 138.98 5. 02 Correlation Coefficient - .902 Appendix C

C-64 2

CAPSULE U (WELD METAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/30/2005 10:18 AM Page I Coefficients of Curve 2 A = 68.1 B -65.9 C = 66.44 T0 = 8.08 D = O.OOE+00 Equation is A + B * [Tanh((T-ToY(C+DT))]

Upper Shelf Energy=1 34.0(Fixed) Lower Shelf Energy2.2(Fixed)

Temp@30 ft-lbs-35.7 Deg F Ternp@50 ft-lbs-10.6 Deg F Plant: BEAVER VALLEY 2 Material: SAW Heat: 83642 Orientation: NA Capsule: U Fluence: n/cm^2 300 250 I I

- 200 a .I

_ _ _ I_ I P 150 1 f~~~~1 /- . --

100

. a 50

- 11 a n

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

- 50. 00 I I. 00 21.74 - 10. 74

- 25. 00 17.00 37. 76 - 20. 76

-20. 00 28. 00 41. 80 -13. 80

- 10.00 115. 0 0 50. 60 64.40

. 00 23.00 60. 12 -37. 12

. 00 89. 00 60. 12 28. 88 1 0. 0 0 56. 00 70. 00 -14. 00

25. 00 108.00 84.53 23.47

25. 00 63. 00 84. 53 -21. 53 Appendix C

C-65 CAPSULE U (WELD METAL)

Page 2 Plant: BEAVERVALLEY 2 Material: SAW Heat: 83642 Orientation: NA Capsule: U Fluence: n/cmrn2 Charpy V-Notch Data Temperature Input CVN Cornputed CVN Differential

88. 00 104. 92 -16. 92

50. 00 15.51

75. 00 134.00 118. 49 121.00 130. 21 -9. 2 1 125.00 2. 41 200.00 136. 00 133.59 145.00 133. 98 1 1. 02 300. 00 30. 00 400. 00 164. 00 134.00 Correlation Coefficient -. 856

- 1 Appendix C

C-66 CAPSULE V (WELD METAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/30/2005 10:18 AM Page 1 Coefficients of Curve 3 A = 69.1 B = 66.9 C = 58.12 TO = 24.76 D =O.OOE+00 Equation is A + B * (Tanh((T-To)/(C+DT))]

Upper Shelf Energy-l 36.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Ternp30 fl-lbs=-14.1 Deg F Temp@50 fl-lbs=7.7 Deg F Plant: BEAVER VALLEY 2 Material: SAW Heat: 83642 Orientation: NA Capsule: V Fluence: n/cmA2 300 250

-S 200 _I V

150 l~' e.... ..

w z

i; 100 I

50 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

- 50.00 27.( 10 11.69 15.31

-25.00 10.t )0 22.65 -12.65

- 10.00 12. ( 00 33.26 -21.26

.00 19.( 00 42.20 -23.20 10.00 72. t00 52.46 19.54 15.00 105.( 00 57.97 47.03 25.00 44. C10 69.38 .25.38 50.00 107.C10 96.46 10.54 72.00 9S. (00 114.00 .16.00 Appendix C

C-67 CAPSULE V (WELD METAL)

Page 2 Plant: BEAVER VALLEY 2 Material: SAW Heat: 83642 Orientation: NA Capsule: V Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 100. 00 122. 00 126. 66 -4. 66 1 2 5. 00 129. 00 131.88 -2. 88 150.00 129. 00 134.23 - 5.23 175.00 148.00 135.24 12. 76 200. 00 133. 00 135.68 -2. 68 225.00 142. 00 135.86 6. 14 Correlation Coefficient = .925 Appendix C

C-68 CAPSULE W (WELD METAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/30/2005 10:18 AM Page 1 Coefficients of Curve 4 A 69.1 B = 66.9 C = 86.05 TO = 23.78 D = 0.O0E+00 Equation is A + B * [Tanh((T-ToY(C+DT))]

Upper Shelf Energy=136.0(Fixed) Lower Shelf Energy--2.2(Fixed)

Ternp@30 ft-lbs--33.8 Deg F Tcmp@50 fl-lbs=-l A Deg F Plant: BEAVERVALLEY 2 Material: SAW Heat: 83642 Orientation: NA Capsule: W Fluence: n/crnA2 300 I

250 a- 200 0

L6

150 I

z A *,' __________

100 A ,' A 50 i

'A A

.5.

0

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

-75. 00 6. 00 14. 44 -8. 44

-50. 00 9.00 22. 61 - 13. 61

-25. 00 28. 00 34.78 -6. 78

- 20. 00 9.0 0 37. 73 -28. 73

-15. 00 87.00 40. 84 46. 16

.0 0 47. 00 51.07 -4. 07

15. 00 107. 00 62.30 44.70 20.00 78. 00 66. 16 11. 84

25. 00 28.00 70. 05 -42. 05 Appendix C

C-69 CAPSULE W (WELD METAL)

Page 2 Plant: BEAVER VALLEY 2 Material: SAW Heat: 83642 Orientation: NA Capsule: W Fluence: n/cmA2 Charpy V-Notch Data Ternperature Input CVN Computed CVN Differential 50.00 71.00 88. 88 -17. 88

75. 00 114.00 104. 80 9.20 115. 00 116.00 121.66 -5.66 150. 00 134.00 129.24 4.76 200. 00 134.00 133. 8I .19 275. 00 141.00 135.61 5.39 Correlation Coefficient = .882 Appendix C

C-70 CAPSULE X (WELD METAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/30/2005 10:18 AM Page I Coefficients of Curve 5 A = 67.6 B = 65A C = 71.02 TO = 29.58 D = O.OOE+O0 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=133.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=-16.9 Deg F Temp@50 R-lbs=10.0 Deg F Plant: BEAVER VALLEY 2 Material: SAW Heat: 83642 Orientation: NA Capsule: X Fluence: n/cmA2 300 250

- 200 0

I- 150 L-____-

i;100 I 7 WI 'V 50

., ?Vv

, *i*

0

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

-75. 00 3.' 00 8.74 -5.74

-50.00 9-. 00 14. 78 -5. 78

- 25. 00 7. ' DO 25.35 -18.35

-25. 00 19.' D0 25.35 -6.35

-10. 00 6-. DO 34.51 -28.51

.00 56.4 DO 41.84 14.16 10.00 88.( DO 50. 02 37. 98 25.00 97.4 DO 63.39 33.61 50.00 41.( DO 8 5. 91 -44. 91 Appendix C

C-71 CAPSULE X (WELD METAL)

Page 2 Plant: BEAVER VALLEY 2 Material: SAW Heat: 83642 Orientation: NA Capsule: X Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 5 0. 00 79.00 S. 9 1 -6. 91

75. 00 113. 00 104. 53 8. 47 100. 00 117.00 117.18 -. 18 150.00 129.00 128.74 .26 175.00 130.00 130.86 -. 86 225. 00 139.00 132.47 6. 5 3 Correlation Coefficient - .913 I

Appendix C

C-72 UNIRRADIATED (WELD)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 09/02/2005 09:25 AM Page 1 Coefficients of Curve I A = 40.41 B = 39.41 C = 32.36 TO = -15.4 D = O.OOE+00 Equation is A + B * [Tanh((T-ToY(C+DT))]

Upper Shelf L.E.=79.8 Lower Shelf L.E.=l.O(Fixed)

Temp.@L.E. 35 mnils-19.8 Deg F Plant: BEAVER VALLEY 2 Material: SAW Heat: 83642 Orientation: NA Capsule: UNIRR Fluence: n/cm'2 200 150 M

C

.2 8 100 0 0 i0 oS so 50 Js0

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

- 60.00 6. 00 i 5.71 .29

- 60. 00 7-. 00 5.71 1.29

-25. 00 12. 1DO 29.06 -17.06

-25.00 10.I DO 29.06 -19.06

-25. 00 51.I Do 29. 06 21. 94

- 10.00 66. 4 D0 46.93 19.07

.00 31.4 DO 57.87 -26. 87

.00 72. ( 0O 57.87 14. 13

.00 68.4 oO 57. 87 10. 13 Appendix C

C-73 UNIRRADIATED (WELD)

Page 2 Plant: BEAVER VALLEY 2 Material: SAW Heat: 83642 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential 30.00 73.50 75. 33 - 1.83

30. 00 75.00 75. 33 - .33

30. 00 60. 00 75.33 -15.33 100.00 78.00 79.76 - 1. 76 100. 00 65.00 79. 76 - 14. 76 150.00 86.50 79. 82 6. 68 210.00 87. 50 79. 82 7. 68 210.00 86. 00 79.82 6. 18 210.00 88. 00 79. 82 8. 18 Correlation Coefficient -. 889 Appendix C

C-74 CAPSULE U (WELD)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 09/02/2005 09:25 AM Page 1 Coefficients of Curve 2 A = 41.82 B = 40.82 C = 53.47 TO = 2.46 D = 0.O0E+OO Equation is A + B * [Tanh((T-ToY(C+DT))]

Upper Shelf L.E.82.6 Lower Shelf L.E.-1.0(Fixed)

Temp.@L.E. 35 mils=-6.5 Deg F Plant: BEAVER VALLEY 2 Material: SAW Heat: 83642 Orientation: NA Capsule: U Fluence: n/cMnA2 200 150 M

T

.2 a 100 o7 a s0 D _0.______ ______________

0

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

- 50. 00 12. 00 I I. 0 6 .9 4

- 25.00 12. 0 0 22.53 - IO0. 5 3

- 20. 00 22.00 25. 62 -3. 62

- 10.00 47. 00 32.48 14. 5 2

. 00 19. 00 39.95 -20. 95

. 00 62. 00 39.95 22.05 10.00 4 5. 00 47. 55 -2. 55 25.00 74. 00 58.08 1 5. 92

25. 00 44. 00 58.08 - 14.08

_I Appendix C

C-75 CAPSULE U (WELD)

Page 2 Plant: BEAVER VALLEY 2 Material: SAW Heat: 83642 Orientation: NA Capsule: U Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential

50. 00 62. 00 70. 85 -8. 85

75. 00 83. 00 77. 5 7 5. 43 125. 00 83. 00 8 1.82 1.18 200. 00 76. 00 82.60 -6. 60 300. 00 79.00 82.65 -3. 65 400. 00 92. 00 82. 65 9. 35 Correlation Coefficient =.904 Appendix C

C-76 CAPSULE V (WELD)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 09/02/2005 09:25 AM Page 1 Coefficients of Curve 3 A = 43.65 B = 42.65 C = 55.22 TO = 19.19 D = O.OOE+00 Equation is A + B r[Tanh((T-Toy(C+DT))l Upper Shelf L.E.=86.3 Lower Shelf L.E.=l.O(Fixed)

Ternp.@L.E. 35 mils=7.9 Deg F Plant: BEAVER VALLEY 2 Material: SAW Heat: 83642 Orientation: NA Capsule: V Fluence: nrcmA2 200 I

150 C

0 2

a 100 e 50 f l ..- ---/.:

n

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

-50. 00 17.00 7.44 9. 56

- 25.00 12.00 15.32 -3.32

- 10. 00 12. 00 23. 00 -1 1. 00

.0 0 16. 00 29. 40 -13. 40

10. 00 50. 00 36. 62 13. 3 8 15.00 61. 00 40. 42 20.58

25. 00 33. 00 48. 12 - 15. 12

50. 00 73. 00 65.25 7. 75 72.00 66. 00 75.33 -9. 33 I

Appendix C

C-77 CAPSULE V (WELD)

Page 2 Plant: BEAVER VALLEY 2 Material: SAW Heat: 83642 Orientation: NA Capsule: V Fluence: n/cmA2 Charpy V-Notch Data Temperature Input LE. Computed LE. Differential 1 00. 00 77. 00 81.97 -4. 97 125.00 88.00 84.50 3.50 150. 00 87. 00 85.57 1.43 175.00 88.00 86. 01 1 .9 9 200. 00 86. 00 86. 18 -. 18 225. 00 87. 00 86. 26 .74 Correlation Coefficient = .945 Appendix C

C-78 lw CAPSULE W (WELD)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 09/02/2005 09:26 AM Page I Coefficients of Curve 4 A=39.22 B=38.22C=75.19 TO=17.27 D=O.OOE+O0 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=77.4 Lower Shelf L.E.=l.O(Fixed)

Ternp.@L.E. 35 mils=9.0 Deg F Plant: BEAVER VALLEY 2 Material: SAW Heat: 83642 Orientation: NA Capsule: W Fluence: n/cMs2 200 150

.2 E

a 100 .

E I

Aj~~

50 4,;,

. ~~~~I,,*

a

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

-75. 00 .0 0 7. 05 -7. 05

-50.00 2.00 11. 94 -9.94

-25. 00 17.00 19.75 -2.75

-20. 00 2. 00 21. 69 - 19.69

-15. 00 51.00 23.76 27. 24

.00 30.00 30.59 -. 59

15. 00 67. 00 38. 07 28.93

20. 00 46. 00 40.61 5.39

25. 00 19.00 43. 14 - 24. 14 N

Appendix C

C-79 CAPSULE W (WELD)

Page 2 Plant: BEAVER VALLEY 2 Material: SAW Heat: 83642 Orientation: NA Capsule: W Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential 50.00 42. 00 54. 88 - 12.88 75.00 70. 00 63.90 6.10 115.00 67.00 72. 15 -5. 15 150. 00 7S. 00 75. 26 2. 74 200. 00 79. 00 76. 85 2. 15 275. 00 78. 00 77.36 .64 Correlation Coefficient - .872

-m m Appendix C

C-,30 CAPSULE X (WELD)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 09/02/2005 09:26 AM Page I Coefficients of Curve 5 A = 42.39 B = 41.39 C = 61.65 TO = 19.49 D = O.OOE+O0 Equation is A + B * [Tanh((T-Toy(C+DT))]

Upper Shelf L.E.=83.8 Lower Shelf L.E.- .O(Fixed)

Temp.@LE. 35 mils=8.4 Deg F Plant: BEAVER VALLEY 2 Material: SAW Heat: 83642 Orientation: NA Capsule: X Fluence: n/cmA2 200 150 EL 100 E

0 12#S 50 vI rv

- S----

n 4

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

-75. 00 2. 00 4. 69 -2. 69

- 50. 00 6. 00 8. 86 -2. 86

- 25. 00 7. 00 16. 81 -9. 81

- 25. 00 15.00 16.81 -1 . 81

- 10.00 5. 00 23.98 -18.98

.00 40.00 29. 72 10.28 1 0. 00 59.00 36. 07 22.93 25.00 63. 00 46. 08 16. 92 50.00 37. 00 61. 35 -24.35 Appendix C

C-81 CAPSULE X (WELD)

Page 2 Plant: BEAVER VALLEY 2 Material: SAW Heat: 83642 Orientation: NA Capsule: X Fluence: n/cm12 Charpy V-Notch Data Temperature Input L.E. Computed LE. Differential 50.00 48. 00 61.35 - 13.35

75. 00 80. 00 72. 04 7. 96 100. 00 82. 00 78. 12 3. 88 150. 00 87. 00 82. 59 4.41 175. 00 85. 00 83.25 1.75 225.00 80. 00 83. 67 - 3. 67 Correlation Coefficient =.922 Appendix C

C-32 UNIRRADIATED (WELD METAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/30/2005 10:28 AM Page I Coefficients of Curve I A=50. B=50.C=4255 TO=-8.64 D=0.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = -8.6 Plant: BEAVER VALLEY 2 Material: SAW Heat: 83642 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 125 100 L. 75 E

50 25 O 4-

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

- 60. 00 .00 8.21 -S.21

- 60. 00 . 00 8.2 1 -8.21

- 25. 00 10. 00 31. 67 -21. 67

- 25. 00 10. 00 31. 67 -21. 67

- 25.00 48. 00 31. 67 16.33

- 10.00 75. 00 48.40 26.60

.00 50. 00 60. 02 - 10.02

. 00 81. 00 60. 02 20. 98

. 00 71. 00 60.02 10.98 Appendix C

C-83 UNIRRADIATED (WELD METAL)

Page 2 Plant: BEAVER VALLEY 2 Material: SAW Heat: 83642 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

30. 00 77. 00 86. 01 -9. 01

30. 00 8 1. 00 86.01 -5. 01

30. 00 61.00 86. 01 -25. 01 100. 00 90. 00 99. 40 -9. 40 100. 00 87.00 99.40 -12. 40 150. 00 1 00. 00 99. 94 . 06 210.00 9 8. 00 100. 00 -2. 00 210.00 9 8. 00 100.00 -2. 00 210.00 98.00 100. 00 -2. 00 Correlation Coefficient .915 Appendix C

C-34 CAPSULE U (WELD METAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/30/2005 10:29 AM Page I Coefficients of Curve 2 A = 50. B = 50. C = 44.29 TO = -7.55 D = 0.00E+00 Equation is A + B I[Tanh((T-Toy(C+DT))]

Temperature at 50% Shear = -7.5 Plant: BEAVER VALLEY 2 Material: SAW Heat: 83642 Orientation: NA Capsule: U Fluence: nfcm'A2 125 100 _ _ C T0 .- _ _ - ,

02 75 12 C 50 II 25 I I I. -~* I-I - I 0

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

-50. 00 10. 00 12. 82 -2.82

- 25.00 10. 00 31.26 -21.26

- 20. 00 25. 00 36. 31 -11.31

-0. 00 100. 00 47. 24 52.76

.00 20. 00 58.45 -38.45

. 00 85.00 58.45 26.55 I 0. 00 60. 00 68. 84 -8.84

25. 00 100. 00 81.31 18. 69

25. 00 60. 00 81. 31 -21.31 Appendix C

C-85 CAPSULE U (WELD METAL)

Page 2 Plant: BEAVER VALLEY 2 Material: SAW Heat: 83642 Orientation: NA Capsule: U Fluence: rn/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

50. 00 85. 00 93. 08 - S. 08 75.00 100.00 97.65 2. 35 125.00 100. 00 99.75 .25 200. 00 100.00 99.99 .01 300. 00 1 00. 00 100.00 . 00 400. 00 100. 00 100. 00 . 00 Correlation Coefficient - .808 Appendix C

C-36 CAPSULE V (WELD METAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/30/2005 10:29 AM Page 1 Coefficients of Curve 3 A = 50. B = 50. C = 53.49 TO =15.76 D = O.O0E+O0 Equation is A + B * [Tanh((T-Toy(C+DT))]

Temperature at 50% Shear= 15.8 Plant: BEAVER VALLEY 2 Material: SAW Heat: 83642 Orientation: NA Capsule: V Fluence: n/cm`A2 125 100 I

L. 75 It co n9

a. II 50 25

.1..-.I 0

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

- 50.00 10. 00 7. 88 2. 12

-25. 00 1S. 00 17.89 - 2. 9

-10. 00 20. 00 27. 62 -7. 62

.00 40. 00 35.68 4.32

10. 00 50. 00 44. 64 5. 36 15.00 70. 00 49. 29 20. 7 1

25. 00 30.00 58.55 -2S. 55 50.00 85. 00 78.25 6. 75

72. 00 90. 00 89. 12 .88 W

Appendix C

C-87 CAPSULE V (WELD METAL)

Page 2 Plant: BEAVER VALLEY 2 Material: SAW Heat: 83642 Orientation: NA Capsule: V Fluence: nkcmA2 Charpy V-Notch Data Temperature Input Percent Shear Conputed Percent Shear Differential 100. 00 95. 00 95. 89 -. 8 9 125. 00 100.00 9S. 35 1 .6 5 150.00 100. 00 99. 34 .6 6 175.00 100. 00 99.74 . 26 200. 00 100. 00 99. 90 .10 225. 00 100. 00 99. 96 .04 Correlation Coefficient = .959 Appendix C

c-} 8 CAPSULE W (WELD METAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/30/2005 10:29 AM Page 1 Coefficients of Curve 4 A = 50. B = 50. C = 78.42 TO = 17.67 D = O.OOE+00 Equation is A + B * [Tanh((T-Toy(C+DT))]

Temperature at 50% Shear = 17.7 Plant: BEAVER VALLEY 2 Material: SAW Heat: 83642 Orientation: NA Capsule: W Fluence: n/cmA2 125 100 (L. 75 LJa z 0.

50 25 0

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

- 7 5. 00 5. 00 8. 60 -3.60

- 50. 00 10.00 15. 11 -5.11

- 25. 00 15. 00 25. 19 -10.19

- 20. 00 10.00 27. 67 -17. 67

-15. 00 60. 00 30.29 29.71

.00 25. 00 38. 92 -13.92 15.00 85. 00 48.30 36. 70

20. 00 65. 00 51. 48 13.52

25. 00 30. 00 54. 66 -24. 66 Appendix C

C-89 CAPSULE W (WELD METAL)

Page 2 Plant: BEAVER VALLEY 2 Material: SAW Heat: 83642 Orientation: NA Capsule: W Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 5 0. 00 50. 00 69.52 - 19.52

75. 00 90. 00 81. 19 8. 8 1 I 15. 00 90. 00 92.29 -2. 29 1 5 0. 00 95.00 96. 69 - 1.69 200. 00 100. 00 99. 05 . 95 275. 00 100.00 99. 8 6 .14 Correlation Coefficient -. 884 Appendix C

C-90 CAPSULE X (WELD METAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/30/2005 10:29 AM Page 1 Coefficients of Curve 5 A=50. B=50.C=71.09 TO 15.33 D=0.00E+00 Equation is A + B * [Tanh((T-Toy(C+DT))]

Temperature at 50% Shear 15.4 Plant: BEAVER VALLEY 2 Material: SAW Hcat: 83642 Orientation: NA Capsule: X Fluence: n/crnA2 125 100 75 0.

50 I _I 25 C.... i II 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Ternperature Input Percent Shear Cornputed Percent Shear Differential

- 75. 00 2. 0 0 7. 3 0 -5. 30

-50. 00 1 5. 00 13.73 1. 27

- 25. 00 15.00 24. 3 3 -9. 33

- 25. 00 25.00 24. 33 . 67

- 10.00 1 5. 00 32.90 17. 90

.00 5 0. 00 3 9. 3 8 1 0. 62 I 0. 00 65.00 46.26 1 8. 74 25.00 75. 00 56. 76 18.24

50. 00 45.00 72. 62 -27. 62 Appendix C

C-9 1 CAPSULE X (WELD METAL)

Page 2 Plant: BEAVER VALLEY 2 Material: SAW Heat: 83642 Orientation: NA Capsule: X Fluence: n/crnA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

50. 00 65. 00 72. 62 -7. 62

75. 00 90. 00 84.27 5.7 3 100.00 95.00 9 1. 5 5 3.4 5 150. 00 100. 00 97. 79 2.2 1 175. 00 1 00. 00 98. 89 1.11 225. 00 100.00 99.73 .2 7 Correlation Coefficient - .940 Appendix C

C-92 UNIRRADIATED (HAZ)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/30/2005 02:30 PM Page 1 Coefficients of Curve I A=46.6 B=44.4C=96.61 TO=-49.3 D=O.OOE+00 Equation is A + B * [Tanh((T-Toy(C+DT))]

Upper Shelf Energy'91.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=87.2 Deg F Temp@50 fR-lbs=-41.8 Deg F Plant: BEAVER VALLEY 2 Material: SA533B I Heat: C0544-2 Orientation: NA Capsule: UNIRR Fluence: n/cmn^2 300 250 J 200 P 150 Lu i; 100 50 0 e

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

-150.00 41.00 12.02 28.98

- 150.00 20. 00 12. 02 7. 98

- 100. 00 19. 00 25.23 -6. 23

-I 00. 00 19. 00 25.23 -6. 23

- 60. 00 45. 00 41.70 3.30

- 60. 00 39. 00 41.70 - 2.70

- 50. 00 38.00 46. 28 - 8.28

-50. 00 49. 00 46.28 2. 72

- 20. 00 49. 00 59. 67 -0. 67

-I Appendix C

C-93 UNIRRADIATED (HAZ)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: NA Capsule: UNIRR Fluence: n/cm^2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 20. 00 50. 00 59.67 -9. 67

-20. 00 66. 00 59. 67 6.33

40. 00 93.00 78.92 14.08 40.00 83. 00 78.92 4.08 100.00 109. 00 87. 14 21.86 100.00 93. 00 87. 14 5.86 210. 00 77. 00 90.59 -13. 59 210.00 80. 00 90.59 10. 59 210. 00 95. 00 90. 59 4.41 Correlation Coefficient -. 914 Appendix C

C-94 CAPSULE U (HAZ)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/30/2005 02:30 PM Page 1 Coefficients of Curve 2 A - 55.6 B = 53.4 C = 106.03 TO = -33.89 D = O.OOE+00 Equation is A + B * [Tanh((T-Toy(C+DT))]

Upper Shelf Energy=l09.0(Fixed) Lower Shelf Energy2.2(Fixed)

Temp@30 ft-lbs-89.2 Deg F Tenip@50 ft-lbs=-45.0 Deg F Plant: BEAVER VALLEY 2 Material: SA533B I Heat: C0544-2 Orientation: NA Capsule: U Fluence: n/crn^2 300 250

]A200 0

P10 IL

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

- 150. 00 16. 00 12. 95 3. 05

-100.00 25. 00 26. 04 - 1.04

-1 00. 00 27. 00 26. 04 .96

- 80. 00 22. 00 33.74 11.74

-75. 00 39.00 35.87 3. 13

-75.00 48.00 35.87 12. 13

-50. 00 47. 00 47.55 -. 55

- 25. 00 77. 00 60. 07 1 6. 93

- 25.00 44.00 60. 07 - 16.07 Appendix C

C-95 CAPSULE U (HAZ)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: NA Capsule: U Fluence: ri/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

. 00 5 9. 00 72. 11 - 13. 11

25. 00 92.00 82.54 9. 46 75.00 89. 00 96. 8 6 -7. 86 1 25. 00 120. 00 103.92 1 6. 08 200. 00 I 1 3. 00 107.72 5. 28 300.00 I 1 3. 0 0 108. 80 4. 20 Correlation Coefficient - .960 Appendix C

C..:?6 CAPSULE V (HAZ)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08130/2005 02:30 PM Page I Coefficients of Curve 3 A = 44.6 B = 42.4 C = 65.54 TO = -22.51 D = 0.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=87.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Ternp@30 fl-lbs=-46.0 Deg F Temp@50 ftllbs-14.1 Deg F Plant: BEAVER VALLEY 2 Material: SA533B I Heat: C0544-2 Orientation: NA Capsule: V Fluence: n/cmA2 300 250

__ I __wr a, 200 12 IL;150 lu z

100 50 0

--- T-.-.. -- F, I I

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

• 1 2 5. 00 17. 00 5.7 6 It. 24 I00.

0 00 17. 00 9. 4 8 7.5 2

- 75. 00 16. 00 16. 42 -. 42

- 65. 00 23. 00 20.41 2.5 9

-50. 00 34. 00 27. 79 6.2 1

-40. 00 2 6. 00 33. 54 -7. 54

- 25. 00 34.00 42.99 - 8. 9 9

.00 59. 00 5 8. 6 1 .3 9

25. 00 68.00 70. 88 -2. 88 Appendix C

C-97 CAPSULE V (HAZ)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: NA Capsule: V Fluence: n/cmA2 Charpy V-Notch Data Tenperature Input CVN Computed CVN Differential

50. 00 92.00 78.64 13.36

85. 00 102.00 83.93 18. 07 125.00 73.00 86.07 -13. 07 150.00 72.00 86.56 -14.56 200. 00 106.00 86.90 19. 10 225. 00 97.00 86.96 10. 04 Correlation Coefficient = .948 Appendix C

C-98 CAPSULE W (HAZ)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/30/2005 02:30 PM Page I Coefficients of Curve 4 A = 53.1 B = 50.9 C = 94.17 T0 = 10.14 D =0.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=104.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temnp@30 fl-lbs--35.9 Deg F Temp@50 fl-lbs--4.4 Deg F Plant: BEAVER VALLEY 2 Material: SA533B I Heat: C0544-2 Orientation: NA Capsule: W Fluence: n/cMA2 300 250 a, 200 a

U.

P 150 0

C

100 A

AA 50 0

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

-150. 00 13.00 5.48 7.52

-75. 00 14.00 16.54 -2. 54

-50. 00 2 6. 00 24. 3 9 1.61

-30. 00 58.00 32.63 25.37

- 25. 00 3 2. 0 0 3 4. 9 4 -2. 94

-5. 00 44.00 44.99 -. 99

.0 0 51.00 47.64 3.3 6 1 5. 00 64.00 55.72 8.2 8 50.00 76.00 73.44 2.5 6 M

Appendix C

C-99 CAPSULE W (HAZ)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533B1 Heat: C0544-2 Orientation: NA Capsule: W Fluence: n/cmA2 Charpy V-Notch Data Tenperature Input CVN Computed CVN Differential 100.00 78. 00 90. 85 - 12. 8 5 125.00 82. 00 95. 83 -13. 83 150.00 129. 00 99.03 29.97 200.00 133.00 102.23 30. 77 275. 00 9 7. 00 103.63 -6. 63

- 10.00 lI. 00 42.38 -31.38 Correlation Coefficient -. 905 Appendix C

C-i 00 CAPSULE X (HAZ)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/30/2005 02:30 PM Page 1 Coefficients of Curve 5 A = 58.1 B = 55.9 C = 127.18 TO = 68.35 D = O.OOE+0O Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=l 14.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temnp@30 fi-lbs-1.9 Deg F Tcmp@50 ft-lbs=49.8 Deg F Plant: BEAVER VALLEY 2 Material: SA533BI Hcat: C0544-2 Orientation: NA Capsule: X Fluence: n/cmA2 300 250 A,200 a

150

100 50

- - I , -

0

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

-90. 00 15.00 10. 76 4. 24

- 50. 00 13.00 17.24 4. 24

-25. 00 25.00 23. 13 1. 8 7

. 00 43. 00 30.65 t2. 35

25. 00 45. 00 39.75 5. 2 5

50. 00 58.00 50. 09 7. 9 1

75. 00 43.00 61.02 - 18. 02 100. 00 87.00 71.73 15.27 125. 00 63.00 81.47 -18. 47 Appendix C

C-101 CAPSULE X (HAZ)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: NA Capsule: X Fluence: ijcmA2 Charpy V-Notch Data Tenperature Input CVN Computed CVN Differential 135.00 61.00 84.98 -23.98 150.00 85.00 89.75 -4.75 175.00 87.00 96.39 -9.39 200.00 122. 00 101.48 20. 52 225.00 137.00 105.23 31.77 250.00 137.00 107. 92 29. 08 Correlation Coefficient -. 913 Appendix C

C-102 UNIRRADIATED (HAZ)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 09/01/2005 02:33 PM Page I Coefficients of Curve I A = 30.82 B = 29.82 C = 86.37 TO = -33.74 D = O.OOE+00 Equation is A + B * [Tanh((T-ToY(C+DT))]

Upper Shelf L.E.=60.6 Lower Shelf L.E.=1.O(Fixed)

Ternp.@L.E. 35 rnils-2 1.5 Deg F Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: NA Capsule: UNIRR Fluence: nfcmr2 200 150 a100 a

50 0 o

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

-150. 00 9.00 4. 7 8 4. 2 2

-150. 00 22. 00 4.78 1 7. 2 2

- 100. 00 8. 00 I 1. 5 8 -3. 58

-I 00. 00 1 0. 00 11.58 - I .5 8

- 60. 00 25.00 22.02 2. 9 8

- 60. 00 19. 00 2 2. 02 -3. 02

- 5 0. 00 23. 00 25. 27 -2. 27

-50. 00 29. 00 25.27 3. 73

- 20.00 27. 00 35.53 - 8. 53 Appendix C

C-103 UNIRRADIATED (IAZ)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: NA Capsule: UNIRR Fluence: n/cm\2 Charpy V-Notch Data Temperature Input LE. Computed LE. Differential

- 20. 00 28. 00 3 5. 53 -7. 53

- 20. 00 4 1. 00 35.53 5. 4 7

40. 00 5 6. 00 5 1. 49 4. 5 1

40. 00 58. 00 5 1. 49 6. 5 1 1 00. 00 6 6. 00 5 8. 06 7. 94 100. 00 5S8. 00 58.06 -. 06 210.00 54. 00 60. 43 - 6. 4 3 210.00 55.50 60. 43 -4. 93 210.00 60. 00 60. 43 -. 43 Correlation Coefficient = .949 Appendix C

C-104 CAPSULE U (HAZ)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 09/01/2005 02:34 PM Page I Coefficients of Curve 2 A = 32.77 B = 31.77 C = 107.99 TO = -36.62 D = 0.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.64.5 Lower Shelf LE.E1 .0(Fixed)

Ternp.@L.E. 35 mnils-29.0 Deg F Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: NA Capsule: U Fluence: nlcmr2 200 150 A

a 100 I

50 0 *-=-

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

..1 50. 00 8. 00 7. 93 .07

.- I 00. 00 19. 00 16.01 2.99

-100. 00 14.00 16.01 -2. 01

- 80. 00 17.00 20. 65 -3. 65

-75. 00 21.00 21.93 - .93

- 75. 00 24. 00 21.93 2.07

-50.00 30. 00 28.85 1.15

- 25. 00 45.00 36. 17 8.83

- 25. 00 29. 00 36. 17 -7. 17 Appendix C

C-105 CAPSULE U (HAZ)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: NA Capsule: U Fluence: n/cmA2 Charpy V-Notch Data Ternperature Input L.E. Computed L.E. Differential

.00 42. 00 43. 15 - 1. 15

25. 00 5 1. 00 49. 15 1 .85

75. 00 48. 00 57.40 -9. 40 125.00 73. 00 61.50 11.50 200. 00 63.00 63.75 - . 75 300. 00 61. 00 64.41 -3. 41 Correlation Coefficient - .964 Appendix C

C-1l)6 CAPSULE V (HAZ)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 09/01/2005 02:34 PM Page 1 Coefficients of Curve 3 A = 31.02 B = 30.02 C = 66.87 TO = -18.96 D = 0.OOE+0O Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=61.0 Lower Shelf L.E.=1.0(Fixed)

Temp.@L.E. 35 mils=-l0.0 Deg F Plant: BEAVER VALLEY 2 Material: SA533B I Heat: C0544-2 Orientation: NA Capsule: V Fluence: n/cMA2 200 150

.1 I

.2

. 100 5

50 OO

. .............. ..... .. ..r <> *~~ @ - -

0

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

- 125.00 9. 00 3.42 5.58

-100. 00 8.00 5.89 2. 11

-75. 00 1 1. 0 0 10.46 .54

- 65. 00 12.00 13. 10 - 1. 10

-50. 00 24. 00 18.00 6. 00

-40. 00 19.00 21. 87 -2.87

- 25. 00 22. 00 28.31 -6. 31

.00 41. 00 39. 31 1. 69 25.00 44. 00 48.33 -4.33 N

Appendix C

C-107 CAPSULE V (HAZ)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: NA Capsule: V Fluence: n/cmA2 Charpy V-Notch Data Temperature Input LE. Computed LE. Differential

50. 00 63.00 54. 26 8.74 85.00 68. 00 58.47 9.53 125.00 50.00 60. 24 - 10. 24 ISO. 00 48.00 60. 66 - 12.66 200.00 67. 00 60. 95 6.05 225. 00 65. 00 61. 00 4. 00 Correlation Coefficient = .957 Appendix C

C-108 CAPSULE W (HAZ)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 09/01/2005 02:34 PM Page I Coefficients of Curve 4 A 34.56 B = 33.56 C = 104.86 TO = 26.75 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=68.1 Lower Shelf L.E.= I.O(Fixed)

Temp.@L.E. 35 mils=28.2 Deg F Plant: BEAVER VALLEY 2 Material: SA533B I Heat: C0544-2 Orientation: NA Capsule: W Fluence: n/crnA2 200 150 A

E C

.2 a 100 50

.4 0

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

. 1 50. 0 0 1.00 3. 2 3 -2. 23

-75. 00 3. 00 9.43 -6. 43

-50. 00 10. 00 13.61 -3. 61

30. 00 34.00 17. 98 16. 02

-25. 00 18.00 1 9. 2 2 - 1.22

-5. 00 21. 00 24.70 -3. 70

.00 30.00 26. 18 3.82 1 5. 00 4 2. 00 30. 82 11.18

50. 00 40. 00 41.88 -1. 88 Appendix C

C-109 CAPSULE W (HAZ)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: NA Capsule: W Fluence: n/cmAn2 Charpy V-Notch Data Temperature Input L.E. Compute d LE. Differential 100. 00 45.00 54. .81 -9. 81 125. 00 52. 00 59. . 19 -7. 19 150.00 74. 00 62, ! 28 11. 72 200. 00 79.00 65. . 74 13. 26 275.00 56. 00 67. . 54 -I I. 54

- 10. 00 11. 00 23. . .26 - 12.26 Correlation Coefficient .923 Appendix C

C-ito CAPSULE X (HAZ)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 09/01/2005 02:34 PM Page 1 Coefficients of Curve S A = 71.99 B = 70.99 C = 223.65 TO = 194.57 D = 0.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=143.0 Lower Shelf L.E.sl.0(Fixed)

Temp.@L.E. 35 niils=65A Deg F Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: NA Capsule: X Fluence: n/cm^2 200 150 E

.2 R 100 50

. ~-~~~ ~ ~ -_

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

-90. 00 7. 00 11. 33 -4.33

-50. 00 7. 00 15.33 -8.33

- 25. 00 1 9. 00 18.48 .52

. 00 29. 00 22. 20 6. 80

25. 00 34. 00 26. 56 7. 44 50.00 36. 00 31.58 4.42

75. 00 29. 00 37.28 -8. 28 100.00 61.00 43. 64 17.36 125. 00 43.00 50.59 -7.59 M

Appendix C

C-111 CAPSULE X (HAZ)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: NA Capsule: X Fluence: n/cmr2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential 135.00 36. 00 53.52 .17.52 150. 00 57. 00 5S. 03 - 1.03 175.00 61. 00 65.79 - 4.79 200. 00 88. 00 73.71 14.29 225.00 89. 00 81.5 9 7.41 250.00 81.00 89.23 -8.23 Correlation Coefficient .934 Appendix C

C-1 12 UNIRRADIATED (HAZ)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/30/2005 03:10 PM Page 1 Coefficients of Curve I A = 50. B = 50. C = 38.32 TO = 7.81 D =0.OOE+00 Equation is A + B * [Tanh((T-Toy(C+DT))]

Temperature at 50% Shear = 7.9 Plant: BEAVER VALLEY 2 Material: SA533B I Heat: C0544-2 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 125 100 75 U,

n.E 0 00 50 25 0 t 0

100

-200 -100 0 100 i 200

_I _

300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

- 150.00 10. 00 .0 3 9. 97

- 150.00 1 0. 00 .03 9. 97

- 100.00 10. 00 .3 6 9. 64

- I 0. 00 13.00 .3 6 1 2. 64

- 60. 00 3 0. 00 2. 8 2 27. 18

- 60. 00 I 0. 00 2. 82 7. 18

- 50. 00 20. 00 4. 6 6 1 5. 34

-50. 00 2 5. 00 4.66 20. 34

- 20. 00 I 0. 0 0 18. 9 7 -8. 97 Appendix C

C-1 13 UNIRRADIATED (HAZ)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

- 20. 00 I 0. 00 1 8. 9 7 -S. 97

- 20. 00 10. 00 1 8. 9 7 -8. 97

40. 00 9 0. 00 84.29 5.71 40.00 90. 00 84. 2 9 5. 71 100. 00 100. 00 99. 19 .81 100. 00 100. 00 99. 19 .81 210.00 1 00. 00 100. 00 .00 210.00 100.00 100. 00 .00 210.00 100. 00 100. 00 .00 Correlation Coefficient -. 977 Appendix C

C-114 CAPSULE U (HAZ)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/30/2005 02:34 PM Page I Coefficients of Curve 2 A=50. B=50.C=83.7 TO=-26.16 D=O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+Dl))]

Temperature at 50% Shear= -26.1 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: NA Capsule: U Fluence: n/cm^2 125 100 75 L.

50 25 0 4-

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

'renOmpeture Input Percent Shear Computed Percent Shear Differential

.150. 00 5.00 4.93 . 07

• .100. 00 15. 00 14.62 .38

• -100. 00 20. 00 14. 62 5.38

- 80. 00 15. 00 21.64 -6. 64

-75.00 20. 00 23. 74 -3. 74

- 75. 00 35. 00 23. 74 11. 26

-50. 00 40. 00 36. 13 3. 87

- 25. 00 55.00 50. 69 4. 31

- 25. 00 40. 00 50. 69 -10. 69 Appendix C

C-i 15 CAPSULE U (HAZ)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: NA Capsule: U Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

.00 55.00 65. 13 -10. 13

25. 00 8 5.00 77.25 7.7 5 75.00 100.00 91.81 8.19 125. 00 100.00 97.37 2. 63 200. 00 100.00 9 9. 5 5 .4 5 300. 00 100. 00 99. 9 6 . 04 Correlation Coefficient .984

, Appendix C

/7

C-116 CAPSULE V (HAZ)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/30/2005 02:34 PM Page I Coefficients of Curve 3 A=50. B=50.C=71.81 TO=1.98 D=0.OOE+00 Equation is A + B * [Tanh((T-Toy(C+DT))]

Temperature at 50% Shear = 2.0 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: NA Capsule: V Fluence: n/cMA2 125 100 75 II I- II 50 II I-I I 25 0

-300 -200 .100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data 7emperature Input Percent Shear Computed Percent Shear Differential

. 1 2 5. 0 0 5. 00 2. 8 3 2. 17

• 100. 00 1 0. 00 5. 5 2 4.48

-75. 00 10.00 1 0. 4 9 .49

- 65. 00 1 5. 0 0 13.41 1 .5 9

-50. 00 25. 00 19. 03 5.9 7

-40. 00 20. 00 23.70 .3. 70

- 25. 00 40. 00 3 2. 05 7. 9 5

.00 35.00 48.62 - 13. 62

25. 00 60. 00 65. 5 0 -5. 50 Appendix C

C-1 17 CAPSULE V (HAZ)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: NA Capsule: V Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

50. 00 90. 00 79.21 10. 79 85.00 95.00 90. 99 4. 01 1 2 5.00 100.00 96. 85 3. 15 150.00 100. 00 9 8. 4 1 1. 59 200. 00 100. 00 99. 60 . 40 225.00 100.00 99. 80 . 20 Correlation Coefficient -. 989 Appendix C

C-118 CAPSULE W (HAZ)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/30/2005 02:34 PM Page 1 Coefficients of Curve 4 A = 50. B = 50. C =74.91 T0 = -2.01 D -0.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = -2.0 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: NA Capsule: W Fluence: n/cmr2 125 100 I

co 75 le 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 Cornputed Percent Shear Differential

-50. 00 5. 00 I . 89 3.11

-75. 00 10. 00 12.47 -2. 47

-50. 00 25.00 2 1. 73 3. 2 7

-30. 00 60.00 32. 14 27. 86

- 25. 00 40. 00 35. 12 4. 8 8

- 5. 00 25. 00 48.00 -23. 00

.00 60. 00 51.34 8. 66

15. 00 70. 00 61. 16 8. 84

50. 00 8 5. 00 80.04 4. 9 6 Appendix C

C-1 19 CAPSULE W (HAZ)

Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: NA Capsule: W Fluence: n/cm12 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 100. 00 100. 00 93.84 6. 16 125. 00 100. 00 96.74 3.26 150.00 100. 00 98.30 1. 7 0 200. 00 100. 00 99.55 .45 275. 00 1 00. 00 99. 94 . 06

-10. 00 15.00 44. 69 -29. 69 Correlation Coefficient - .934 Appendix C

C-120 CAPSULE X CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 08/30/2005 02:34 PM Page 1 Coefficients of Curve 5 A = 50. B = 50. C = 106.78 TO = 19.76 D =D.OOE+0O Equation is A + B * [Tanh((T-Toy(C+DT))]

Temperature at 50% Shear = 19.8 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: NA Capsule: X Fluence: n/cmAn2 125 100 (6 75 0

to 2

50 a.

25 O4

-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

-90. 00 15. 00 11.35 3. 65

-50. 00 15. 00 21.31 -6. 31

- 25. 00 35. 00 30. 19 4. 8 I

.00 40. 00 40. 85 - . 85

25. 00 60. 00 52.45 7. 55

50. 00 70. 00 63.79 6.21

75. 00 40. 00 73. 78 -33. 78 100. 00 95. 00 81.80 13. 20 125. 00 90. 00 87. 77 2.23 Appendix C

C-121 CAPSULE X Page 2 Plant: BEAVER VALLEY 2 Material: SA533BI Heat: C0544-2 Orientation: NA Capsule: X Fluence: n/cMA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 135.00 90. 00 89. 65 . 35 150. 00 9 8. 00 9 1. 9 8 6.02 1 75. 00 100. 00 94. 82 5. 18 200. 00 1 00. 00 96. 69 3. 3 1 225. 00 100. 00 97. 90 2. 10 250. 00 1 00. 00 98.68 1.32 Correlation Coefficient = .947 Appendix C

D-O APPENDIX D BEAVER VALLEY UNIT 2 SURVEILLANCE PROGRAM CREDIBILITY EVALUATION Appendix D

D-1 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 four surveillance capsules removed from the Beaver Valley Unit 2 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. Each of these five requirements is presented, along with an evaluation of each, in the following section.

The purpose of this evaluation is to apply the credibility requirements of Regulatory Guide 1.99, Revision 2 to the Beaver Valley Unit 2 reactor vessel surveillance data and determine if the Beaver Valley Unit 2 surveillance data are credible.

EVALUATION:

Criterion 1: Materials in the capsules should be those judged most likely to be controlling with regard to radiation embrittlement.

The beltline region of the reactor vessel is defined in Appendix G to 10 CFR Part 50, "Fracture Toughness Requirements," as follows:

...the reactor vessel (shell material including welds, heat affected zones, andplates orforgings) that directly surrounds the effective height of the active core andadjacent regions of the reactor vessel that are predictedto experience sz fficient neutron radiationdamage to be consideredin the selection of the most limiting materialwith regardto radiationdamage.

The Beaver Valley Unit 2 reactor vessel consists of the following beltline region materials:

• Intermediate shell plates B9004-1 and -2

• Lower shell plates B9005-1 and -2

• Intermediate shell longitudinal (axial) weld seams 101-142 A & B

• Lower shell longitudinal (axial) weld seams 10 1-142 A & B

• Intermediate to lower shell circumferential (girth) weld seam 101-171 From WCAP-9615, Revision 1,selection of the surveillance material was based on an evaluation of initial toughness (characterized by the reference temperature, RTNDT and C, upper shelf energies), and the predicted effect of chemical composition (residual copper and phosphorus) and neutron fluence on the toughness (RTNDT shift) during reactor operation. Lower shell plate numbered B9004-2 (Heat C0544-1) was selected as the surveillance base metal since it had the highest adjusted EOL RTNDT of the four beltline region plates. Weld Heat 83642 was selected because it is the same heat used in fabrication of all of the axial and circumferential welds.

Based on this discussion, Criterion I is met for the Beaver Valley Unit 2 reactor vessel.

Appendix D

D-2 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 USE of the Beaver Valley Unit 2 surveillance materials unambiguously. Hence, the Beaver Valley Unit 2 surveillance program meets this criterion.

Criterion l: When there are two or more sets of surveillance data from one reactor, the scatter of ARTNDT values about a best-fit line drawn as described in Regulatory Position 2.1 normally should be less than 280 F for welds and 17IF for base metal. Even if the fluence range is large (two or more orders of magnitude), the scatter should not exceed twice those values. Even if the data fail this criterion for use in shift calculations, they may be credible for determining decrease in upper shelf energy if the upper shelf can be clearly determined, following the definition given in ASTM 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 these data and to determine if the scatter of ARTNDT values about this line is less than 28'F for welds and less than 17'F for the plate.

The Beaver Valley Unit 2 lower shell plate B9004-2 and surveillance weld will be evaluated for credibility. The surveillance weld is made from weld wire Heat 83642. Since there are now four data points available that are specific to the Beaver Valley surveillance program, only that data will be evaluated to determine credibility. Note that there are two magnitudes of fluence, therefore a wider scatter band is permitted if needed.

Table D-1 contains the calculation of chemistry factors for the Beaver Valley Unit 2 reactor vessel beltline materials contained in the surveillance program. These chemistry factors are calculated per Regulatory Guide 1.99, Rcvision 2, Position 2.1.

Appendix D

D-3 Table D-1 Calculation of Chemistry Factors using Beaver Valley Unit 2 Surveillance Capsule Data Material Capsule Capsule a) FF(b) ARTNDT(c) FF*ARTNDT FF2 U 0.6082 0.861 24.0 20.66 0.741 Intermediate Shell Plate B9004-2 V 2.629 1.259 56.0 70.50 1.585 (Longitudinal) W 3.625 1.335 71.0 94.79 1.782 X 5.601 1.424 98.0 139.55 2.028 U 0.6082 0.861 17.7 15.24 0.741 Intermediate Shell V 2.629 1.259 46.1 58.04 1.585 Plate B9004-2__ _ _ _ __ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _

(Transverse) W 3.625 1.335 63.4 84.64 1.782 X 5.601 1.424 104.1 148.24 2.028 SUM: 631.66 12.272 CF - X(FF

• RTNDT)

• Z(TFF2 ) = (631.66) -(12.272) - 51.5 0 F U 0.6082 0.861 4.1 3.53 0.741 Beaver Valley V 2.629 1.259 25.7 32.36 1.585 Surveillance Weld Metal 83642 W 3.625 1.335 6.0 8.01 1.782 X 5.601 1.424 22.9 32.61 2.028 SUM: 76.51 6.136 CF =X(FF

• RTNDT) + Y( FF2 ) = (76.51) . (6.136) = 12.51F Notes:

(a) f = Calculated fluence from the Beaver Valley Unit 2 capsule X dosimetry analysis results, (x n/CM2 , E > 1.0 MeV).

o1019 (b) FF = fluence factor = f0.28 - fog 0)

(c) ARTNDT values are the measured 30 ft-lb. shift values for Beaver Valley Unit 2 taken from Appendix C.

The scatter of ARTNDT values about the functional form of a best-fit line drawn as described in Regulatory Position 2.1 is presented in Table D-2.

Appendix D

D-4 Table D-2 Beaver Valley Unit 2 Surveillance Capsule Data Scatter about the Best-Fit Line for Surveillance Materials

<17 0 F Material Capsule CF FF Measured Predicted Scatter (Base Metals)

(Slopeb.1 fit) ARTNDT ARTNDT ARTNDT <280 F (Weld)

U 51.5 0F 0.861 24.0F 44.30 F -20.3 0 F No (a)

Intermediate Shell V 51.5 0F 1.259 56.0F 64.80 F -8.8 0 F Yes Plate B9004-2 W 51.5 0F 1.335 71.00 F 68.8 0 F 2.2 0F Yes (Longitudinal)

X 51.5 0 F 1.424 98.0F 73.3 0F 24.70 F No(a)

U 51.5 0 F 0.861 17.7 0 F 44.30F -26.60 F No (a)

Intermediate Shell V 51.5 0F 1.259 46.1 OF 64.8 0F -18.7 0F No (a)

Plate B9004-2 W 51.5 0 F 1.335 63.4 0F 68.8°F -5.4 0F Yes (Transverse)

X 51.5 0F 1.424 104.1°F 73.3 0F 30.8 0F No (a)

U 12.5°F 0.861 4.1°F 10.8 0F -6.7°F Yes Surveillance WeldV 12.5 0 F 1.259 25.7°F 15.70 F 10.0°F Yes Material (Heat # 83642) W 12.5°F 1.335 6.0°F 16.7 0F -10.7 0 F Yes X 12.5 0 F 1.424 22.9 0 F 17.8°F 5.1 0F Yes Note:

(a) Based on guidelines from Regulatory guide 1.99, Revision 2, and guidance from 10 CFR 50.61, if there are two or more orders of magnitude of the fluence, you are permitted to double the scatter acceptability criteria. In this case, there are two magnitudes of fluence, therefore, these data scat:er can be considered acceptable.

Table D-2 irdicates that 5 out of the 8 data points fall outside the 4 Ic of 17°F scatter band for the lower shell plate B9004-2 surveillance data. Per guidelines provided in Regulatory Guide 1.99 and 10 CFR 50.61, if there are two or more magnitudes in fluence, the scatter bands are allowed to be doubled. For Beaver Valley Unit 2, there are two orders of magnitude for the fluence. Therefore, the plate data meet this criterion since the scatter is < 34°F for all of the plate materials. No weld data points fall outside the

+/- I c of 28°F scatter band for the surveillance weld data; therefore, the weld data meet this criterion.

Criterion 4: The irradiation temperature of the Charpy specimens in the capsule should match the vessel wall temperature at the cladding/base metal interface within +/- 25°F.

The capsule specimens are located in the reactor between the fuel and the vessel wall opposite the center of the core. The test capsules are in baskets attached to the vessel wall. The location of the specimens with respect to the reactor vessel beltline provides assurance that the reactor vessel wall and the Appendix D

D-5 specimens are subjected to equivalent operating conditions such that the temperatures will not differ by more than 250 F. Hence, this criterion is met.

Criterion 5: The surveillance data for the correlation monitor material in the capsule should fall within the scatter band of the database for that material.

The Beaver Valley Unit 2 surveillance program does not contain correlation monitor material. Therefore, this criterion is not applicable to the Beaver Valley Unit 2 surveillance program and exemption to its requirements is implemented.

CONCLUSION:

Based on the preceding responses to all five criteria of Regulatory Guide 1.99, Revision 2 and guidance from 10 CFR 50.61, the Beaver Valley Unit 2 surveillance plate and weld data are deemed credible. For future evaluations of ART and RTpTs values, reduced margin terms for the plate and weld material is permitted per Regulatory Guide 1.99, Revision 2.

Appendix D