Text

Submittal of Second Reactor Vessel Surveillance Capsule Report
	ML030940139
Person / Time
Site:	Waterford
Issue date:	03/28/2003
From:	Peters K; Entergy Nuclear South, Entergy Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	W3F1-2003-0020
	Download: ML030940139 (214)
	v • d • e

Entergy Nuclear South Entergy Operations, Inc 17265 River Road Entergy Killona, LA 70066 Tel 504 739 6440 Fax 504 739 6698 kpeters~entergy corn Ken Peters Director, Nuclear Safety Assurance Waterford 3 W3F1 -2003-0020 March 28, 2003 U.S. Nuclear Regulatory Commission Attn. Document Control Desk Washington, DC 20555

SUBJECT:

Waterford Steam Electric Station, Unit 3 Docket No. 50-382 Submittal of Second Reactor Vessel Surveillance Capsule Report

Dear Sir or Madam:

The reactor vessel material irradiation surveillance specimens inserted in the Waterford Steam Electric Station, Unit 3 (Waterford 3) reactor vessel prior to initial plant startup are required to be removed and examined to determine changes in material properties, in accordance with the surveillance program. The second capsule, 4NV-263, was removed on April 1, 2002, during the eleventh refueling outage after 13.83 effective full power years (EFPY). In accordance with 10 CFR 50 Appendix H, a summary report is required to be submitted within one year of the date of capsule withdrawal Entergy Operations, Inc. (Entergy) hereby submits the attached report summarizing the post irradiation testing and fluence analysis results associated with capsule 41W-263. (All nomenclature or identification denoted as capsule 263- or W-263 in the attached report pertains to capsule 4NW-263.)

Weld metal specimen 3J7, tested at 550 'F, was shown to have failed outside the gauge length resulting in the clip gauge falling off. Therefore the stress-strain curve is incomplete. A review of the fabrication records by Entergy indicates that the failure probably occurred at or very close to the fusion line of the surveillance weld Therefore Entergy believes the data from the test conducted on specimen 3J7 is not representative for the weld metal tensile properties. Hence the tensile data from specimen 3J7 will be thoroughly evaluated prior to being used for historical or correlation purposes.

The current Waterford 3 pressure-temperature limits are valid through 16 EFPY. New pressure-temperature limit curves are currently being developed and Entergy plans to submit a license amendment request in August 2003 to establish pressure-temperature limits for operation beyond 16 EFPY.

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W3Fl-2003-0020 Page 2 of 2 March 28, 2003 The proposed change does not include any new commitments.

If you have any questions or require additional information, please contact D. Bryan Miller at 504-739-6692.

Sincerely, Director, Nuclear Safety Assurance Waterford Steam Electric Station, Unit 3 KJPIDBM/cbh

Attachment:

WCAP-1 6002, Revision 0, Analysis of Capsule 263- from the Entergy Operations Waterford Unit 3 Reactor Vessel Radiation Surveillance Program cc: E.W. Merschoff, NRC Region IV N. Kalyanam, NRC-NRR J. Smith (w/o attachment)

N.S. Reynolds (w/o attachment)

NRC Resident Inspectors Office

Attachment To W3FI -2003-0020 WCAP-1 6002, Revision 0, Analysis of Capsule 263- from the Entergy Operations Waterford Unit 3 Reactor Vessel Radiation Surveillance Program

Westinghouse Non-Proprietary Class 3 WCAP-16002 March, 2003 Revision 0 Analysis of Capsule 2630 from the Entergy Operations Waterford Unit 3 Reactor Vessel Radiation Surveillance Program

Westinghouse

WESTINGHOUSE NON-PROPRIETARY CLASS 3 WCAP-16002 Analysis of Capsule 2630 from the Entergy Operations Waterford Unit 3 Reactor Vessel Radiation Surveillance Program S. T. Byrne T. J. Laubham J. Conermann E.T. Hayes March 2003 Verified by:

C.L. Hoffmanli' Component Integrity Approved by: y 3/4 3 B.M. Hinton, Manager Component Integrity Westinghouse Electric Company LLC P.O. Box 355 Pittsburgh, PA 15230-0355 D 2003 Westinghouse Electric Company LLC All Rights Reserved

TABLE OF CONTENTS LIST OF TABLES ................................................................. 5 LIST OF FIGURES ................................................................. 8 EXECUTIVE

SUMMARY

................................................................ 10 1

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 2630 .5-1 5.1 OVERVIEW .5-1 5.2 CHARPY V-NOTCH IMPACT TEST RESULTS .5-3 5.3 TENSILE TEST RESULTS .5-5 6 RADIATION ANALYSIS AND NEUTRON DOSIMETRY .6-1

6.1 INTRODUCTION

.6-1 6.2 DISCRETE ORDINATES ANALYSIS .6-2 6.3 NEUTRON DOSIMETRY .6-5 6.4 CALCULATIONAL UNCERTAINTIES .6-5 7 SURVEILLANCE CAPSULE REMOVAL SCHEDULE .7-1 8 REFERENCES .8-1 APPENDIX A INSTRUMENTED CHARPY IMPACT TEST CURVES .................................................... A-1 APPENDIX B CHARPY V-NOTCH PLOTS................................................................................................ B-1 APPENDIX C CHARPY V-NOTCH SHIFT RESULTS............................................................................... C-1 APPENDIX D WATERFORD UNIT 3 SURVEILLANCE DATA CREDIBILITY ANALYSIS ................ D-1 APPENDIX E VALIDATION OF THE RADIATION TRNSPORT MODELS BASED ON NEUTRON DOSIMETRY MESUREMENTS..................................................................................................................... E-I

WESTINGHOUSE NON-PROPRIETARY CLASS 3 LIST OF TABLES Table 5-1 Charpy V-notch Data for the Waterford Unit 3 Plate M-1004-2 Irradiated to a Fluence of 1.45 x 1019 n/cm 2 (E> 1.0 MeV), Transverse Orientation ................................... 5-6 Table 5-2 Charpy V-notch Data for the HSST Plate 01MY Correlation Monitor Material Irradiated to a Fluence of 1.45 x 10'9 n/cm 2 (E> 1.0 MeV), Longitudinal Orientation ........ 5-7 Table 5-3 Charpy V-notch Data for the Waterford Unit 3 Surveillance Weld Metal Irradiated to a Fluence of 1.45 x 1019 n/cm 2 (E> 1.0 MeV) ............................................................. 5-8 Table 5-4 Charpy V-notch Data for the Waterford Unit 3 Heat Affected Zone Metal Irradiated to a Fluence of 1.45 x 10'9 n/cm 2 (E> 1.0 MeV) ............................................................. 5-9 Table 5-5 Instrumented Charpy Impact Test Results for the Waterford Unit 3 Plate M-1004-2 ........ 5-10 Table 5-6 Instrumented Charpy Impact Test Results for the HSST Plate 01MY Correlation Monitor Material Irradiated to a Fluence of 1.45 x 1019 n/cm 2 (E> 1.0 MeV),

Longitudinal Orientation ............................................................. 5-11 Table 5-7 Instrumented Charpy Impact Test Results for the Waterford Unit 3 Surveillance Weld Metal ............................................................. 5-12 Table 5-8 Instrumented Charpy Impact Test Results for the Waterford Unit 3 Heat Affected Zone Material ............................................................. 5-13 Table 5-9 Effect of Irradiation to 1.45 x 11i9 n/cm 2 (E>1.0 MeV) on the Notch Toughness Properties of the Waterford Unit 3. 5-14 Table 5-10 Comparison of the Waterford Unit 3 Surveillance Material 30 ft-lb Transition Temperature Shifts and Upper Shelf Energy Decrease with Regulatory Guide 1.99, Revision 2, Predictions . 5-15 Table 5-11 Tensile Specimens From Lower Shell Course Plate M-1004-2, Weld, and Heat Affected Zone Material ........................................................... 5-16 Table 6-1 Calculated Neutron Exposure Rates and Integrated Exposures .......................................... 6-10 Table 6-2 Calculated Neutron Exposure of the Middle Shell to Lower Shell Circumferential Weld (101-171) ........................................................... 6-12 Table 6-3 Calculated Neutron Exposure of the Middle Shell Plates (M-1003-1, M-1003-2, and M-1003-3) . 6-13 Table 6-4 Calculated Neutron Exposure of the Lower Shell Plates (M-1004-1, M-1004-2, and M-1004-3) . 6-14 Westinghouse Electric Company LLC P.O. Box 355 Pittsburgh, PA 15230-0355

Table 6-5 Calculated Neutron Exposure of the Middle Shell Longitudinal Welds ............................. 6-15 Table 6-6 Calculated Neutron Exposure of the Lower Shell Longitudinal Welds .............................. 6-16 Table 6-7 Relative Radial Distribution of Neutron Fluence (E > 1.0 MeV) ....................................... 6-17 Table 6-8 Relative Radial Distribution of Iron Atom Displacements (dpa) ........................................ 6-17 Table 6-9 Calculated Fast Neutron Exposure of Surveillance Capsules ............................................. 6-18 Table 6-10 Calculated Surveillance Capsule Lead Factors . 6-18 Table 7-1 Waterford Unit 3 Reactor Vessel Surveillance Capsule Withdrawal Schedule .................... 7-1 Table B-i Upper Shelf Energy Values Fixed in CVGRAPH ........................................................ B-I Table C-I Changes in Average 30 and 50 ft-lb Temperatures for Lower Shell Plate M-1004-2 (Longitudinal Orientation), CVGRAPH 4.1 .C-2 Table C-2 Changes in Average 35 mil Lateral Expansion Temperatures and Average Energy Absorption at Full Shear for Lower Shell Plate M-1004-2 (Longitudinal Orientation), CVGRAPH 4.1 .C-2 Table C-3 Changes in Average 30 and 50 ft-lb Temperatures for Lower Shell Plate M-1004-2 (Transverse Orientation), CVGRAPH 4.1 ............................................................ C-2 Table C4 Changes in Average 35 mil Lateral Expansion Temperatures for Lower Shell Plate M-1 004-2 (Transverse Orientation), CVGRAPH 4.1 ......................................................... C-2 Table C-5 Changes in Average 30 and 50 ft-lb Temperatures for Surveillance Weld Material, CVGRAPH 4.1 ............................................................ C-3 Table C-6 Changes in Average 35 mil Lateral Expansion Temperatures and Average Energy Absorption at Full Shear for Surveillance Weld Material, CVGRAPH 4.1 ......................... C-3 Table C-7 Changes in Average 30 and 50 ft-lb Temperatures for the Heat-Affected-Zone Material CVGRAPH 4.1 ............................................................ C-3 Table C-8 Changes in Average 35 mil Lateral Expansion Temperatures and Average Energy Absorption at Full Shear for the Heat-Affected-Zone Material, CVGRAPH 4.1 ............... C-3 Table C-9 Changes in Average 30 and 50 ft-lb Temperatures for the Correlation Monitor Material HSST Plate 01, CVGRAPH 4.1 ........................... ................................. C-4 Table C-10 Changes in Average 35 mil Lateral Expansion Temperatures and Average Energy Absorption at Full Shear for the Correlation Monitor Material HSST Plate 01, CVGRAPH 4.1 ............................................................ C-4 Table D-1 Waterford Unit 3 Surveillance Capsule Data ............................................................ D-4 Table D-2 Best Fit Evaluation for Waterford Unit 3 Surveillance Materials .................... .................... D-5 Table D-3 Calculation of Residual vs. Fast Fluence .............................................................. D-6 Table E-1 Nuclear Parameters Used In The Evaluation Of Neutron Sensors ..................................... E-10

WESTINGHOUSE NON-PROPRIETARY CLASS 3 Table E-2 Monthly Thermal Generation During the First Eleven Fuel Cycles of The Waterford Unit 3 Reactor (Reactor Power of 3390 MWt) ............................................................. E-1 1 Table E-3 Calculated Cj Factors at the Surveillance Capsule Center Core Midplane Elevation ........ E-14 Table E4 Measured Sensor Activities And Reaction Rates Surveillance Capsule W-97 .................. E-17 Table E-5 Comparison of Measured, Calculated, and Best Estimate Reaction Rates At The Surveillance Capsule Center ............................................................. E-19 Table E-6 Comparison of Calculated and Best Estimate Exposure Rates At The Surveillance Capsule Center ............................................................. E-20 Table E-7 Comparison of Measured/Calculated (M/C) Sensor Reaction Rate Ratios Including all Fast Neutron Threshold Reactions ............................................................. E-21 Table E-8 Comparison of Best Estimate/Calculated (BE/C) Exposure Rate Ratios ........................... E-21 Westinghouse Electric Company LLC P.O. Box 355 Pittsburgh, PA 15230-0355 C 2003 Westinghouse Electric Company LLC All Rights Reserved

LIST OF FIGURES Figure 4-1 Arrangement of Surveillance Capsules in the Waterford Unit 3 Reactor Vessel .................. 4-3 Figure 4-2 Typical Waterford Unit 3 Arrangement of Surveillance Capsule Assembly ........................ 4-4 Figure 4-3 Typical Waterford Unit 3 Surveillance Capsule Charpy Impact Compartment Assembly ....................................................................... 4-5 Figure 4-4 Typical Waterford Unit 3 Surveillance Capsule Tensile and Flux-Monitor Compartment Assembly ....................................................................... 4-3 Figure 5-1 Charpy V-Notch Impact Energy vs. Temperature for Waterford Unit 3 Reactor Vessel Lower Shell Plate M-1004-2 (Transverse Orientation) ........................................... 5-17 Figure 5-2 Charpy V-Notch Lateral Expansion vs. Temperature for Waterford Unit 3 Reactor Vessel Lower Shell Plate M-1004-2 (Transverse Orientation) ........................................... 5-18 Figure 5-3 Charpy V-Notch Percent Shear vs. Temperature for Waterford Unit 3 Reactor Vessel Lower Shell Plate M- 1004-2 (Transverse Orientation) ........................................... 5-19 Figure 5-4 Charpy V-Notch Impact Energy vs. Temperature for HSST Plate O IMY Correlation Monitor Material (Longitudinal Orientation) ...................................................................... 5-20 Figure 5-5 Charpy V-Notch Lateral Expansion vs. Temperature for HSST Plate O1MY Correlation Monitor Material (Longitudinal Orientation) ................................................... 5-21 Figure 5-6 Charpy V-Notch Percent Shear vs. Temperature for HSST Plate OlMY Correlation Monitor Material (Longitudinal Orientation) ...................................................................... 5-22 Figure 5-7 Charpy V-Notch Impact Energy vs. Temperature for Waterford Unit 3 Reactor Vessel Surveillance Weld Material ....................................................................... 5-23 Figure 5-8 Charpy V-Notch Lateral Expansion vs. Temperature for Waterford Unit 3 Reactor Vessel Surveillance Weld Metal ....................................................................... 5-24 Figure 5-9 Charpy V-Notch Percent Shear vs. Temperature for Waterford Unit 3 Reactor Vessel Surveillance Weld Metal ....................................................................... 5-25 Figure 5-10 Charpy V-Notch Impact Energy vs. Temperature for Waterford Unit 3 Reactor Vessel Heat Affected Zone Material ....................................................................... 5-26 Figure 5-11 Charpy V-Notch Lateral Expansion vs. Temperature for Waterford Unit 3 Reactor Vessel Heat Affected Zone Material ....................................................................... 5-27 Figure 5-12 Charpy V-Notch Percent Shear vs. Temperature for Waterford Unit 3 Reactor Vessel Heat Affected Zone Material ....................................................................... 5-28 Figure 5-13 Charpy Impact Specimen Fracture Surfaces for Waterford Unit 3 Reactor Vessel Lower Shell Plate M-1004-2 (Transverse Orientation) ....................................................... 5-29

WESTINGHOUSE NON-PROPRIETARY CLASS 3 Figure 5-14 Charpy Impact Specimen Fracture Surfaces for HSST Plate OlMY Correlation Monitor Material (Longitudinal Orientation) ............................................................. 5-30 Figure 5-15 Charpy Impact Specimen Fracture Surfaces for Waterford Unit 3 Reactor Vessel Weld Metal Specimens ............................................................. 5-31 Figure 5-16 Charpy Impact Specimen Fracture Surfaces for Waterford Unit 3 Reactor Vessel Heat Affected Zone (HAZ) ............................................................. 5-32 Figure 5-17 Tensile Properties for Waterford Unit 3 Reactor Vessel Lower Shell Plate M-1004-2 (Transverse Orientation) ............................................................. 5-33 Figure 5-18 Tensile Properties for Waterford Unit 3 Reactor Vessel Weld Metal ................................. 5-34 Figure 5-19 Tensile Properties for Waterford Unit 3 Reactor Vessel Heat-Affected-Zone (HAZ) ........ 5-35 Figure 5-20 Fractured Tensile Specimens from Waterford Unit 3 Reactor Vessel Plate M-1 004-2 (Transverse Orientation) ............................................................. 5-36 Figure 5-21 Fractured Tensile Specimens from Waterford Unit 3 Reactor Vessel Weld Metal ............ 5-37 Figure 5-22 Fractured Tensile Specimens from Waterford Unit 3 Reactor Vessel Heat-Affected-Zone (HAZ) ............................................................. 5-38 Figure 5-23 Engineering Stress-Strain Curves for Plate M-1004-2 Tensile Specimens 2J2, 2KK and 2KL (Transverse Orientation) ............................................................. 5-39 Figure 5-24 Engineering Stress-Strain Curves for Weld Metal Tensile Specimens 3K3, 3JD, and 3J7. [Note: Specimen 337 broke outside the gage length.] ............................................... 5-40 Figure 5-25 Engineering Stress-Strain Curves for Heat-Affected-Zone (HAZ) Material Tensile Specimens 4JB,4J 1 and 4KA. [Note: Specimen 4KA broke at the clip gage knife edge.] ............................................................. 5-41 Figure 6-1 Waterford Unit 3 r,0 Reactor Geometry at the Core Midplane ............................................. 6-8 Figure 6-2 Waterford Unit 3 rz Reactor Geometry ............................................................. 6-9 Westinghouse Electric Company LLC P.O. Box 355 Pittsburgh, PA 15230-0355

EXECUTIVE

SUMMARY

The purpose of this report is to document the results of the testing of surveillance capsule 2630 from Waterford Unit 3. Capsule 2630 was removed at 13.83 EFPY and post-irradiation mechanical testing of the Charpy V-notch and tensile specimens was performed. A fluence evaluation was also performed based on methodology and nuclear data including neutron transport and dosimetry cross-section libraries derived from the ENDF/B-VI database. The calculated peak clad base metal vessel fluence after 13.83 EFPY of plant operation was 1.23 x 1019 n/cm 2 and the surveillance Capsule 2630 calculated fluence was 1.45 x 1019 n/cm2 . A brief summary of the Charpy V-notch testing results can be found in Section 1 and the updated capsule removal schedule can be found in Section 7. A credibility evaluation was performed of the Waterford Unit 3 surveillance data in accordance with Regulatory Guide 1.99, Revision 2; it can be found in Appendix D.

WESTINGHOUSE NON-PROPRIETARY CLASS 3 1-I 1-1 WESTiNGHOUSE NON-PROPRIETARY CLASS 3 1

SUMMARY

OF RESULTS The analysis of the reactor vessel materials contained in surveillance capsule 2630, the second capsule to be removed from the Waterford Unit 3 reactor pressure vessel, led to the following conclusions:

The capsule received an average fast neutron calculated fluence (E > 1.0 MeV) of 1.45 x 1019 n/cm 2 after 13.83 effective full power years (EFPY) of plant operation.

The reactor vessel lower shell plate M-1004-2 Charpy specimens in the transverse orientation were irradiated to 1.45 x 1019 n/cm 2 (E> L.OMeV). This resulted in a 30 ft-lb transition temperature decrease of 9.1XF and a 50 ft-lb transition temperature increase of 8.17F, with an irradiated 30 ft-lb transition temperature of -33.67F and an irradiated 50 ft-lb transition temperature of 2.97F for the transversely oriented specimens

The HSST Plate OIMY correlation monitor material Charpy specimens in the longitudinal orientation were irradiated to 1.45 x 109 n/cm 2 (E> 1.0 MeV). This resulted in a 30 ft-lb transition temperature increase of 150.57F and a 50 ft-lb transition temperature increase of 151.37F, with an irradiated 30 ft-lb transition temperature of 184.9 0 F and an irradiated 50 ft-lb transition temperature of 211.47F for the longitudinally oriented specimens.

The weld metal Charpy specimens were irradiated to 1.45 x 10'9 n/cm 2 (E> 1.0 MeV). This resulted in a 30 ft-lb transition temperature increase of 6.90 F and a 50 ft-lb transition temperature increase of 13.80 F, with an irradiated 30 ft-lb transition temperature of-77.70 F and an irradiated 50 ft-lb transition temperature of -51.4 0 F.

The weld heat-affected-zone (HAZ) metal Charpy specimens were irradiated to 1.45 x 1019 n/cm2 (E > 1.0 MeV). This resulted in a 30 ft-lb transition temperature increase of 25.1 0 F and a 50 ft-lb transition temperature increase of 27.90 F. The irradiated 30 ft-lb transition temperature is -92.07F and the irradiated 50 ft-lb transition temperature is -62.17F.

Based on the average values, the upper shelf energy of the lower shell plate M-1004-2 (transverse orientation) decreased 10 ft-lb after irradiation to 1.45 x 10i9 n/cm 2 (E> 1.0 MeV). This resulted in an irradiated average upper shelf energy of 131 ft-lb for the transversely oriented specimens.

Based on the average values, the upper shelf energy of the HSST Plate O1MY correlation monitor material (longitudinal orientation) decreased 20 ft-lb after irradiation to 1.45 x 1019 n/cm2 (E> 1.0 MeV). This results in an irradiated average upper shelf energy of 113 ft-lb for the longitudinally oriented specimens.

Based on the average values, the upper shelf energy of the weld metal Charpy specimens decreased 11 ft-lb after irradiation to 1.45 x 1019 n/cm 2 (E> 1.0 MeV). This results in an irradiated average upper shelf energy of 145 ft-lb for the weld metal specimens.

Based on the average values, the average upper shelf energy of the weld HAZ Charpy specimens decreased 7 ft-lb after irradiation to 1.45 x 1019 n/cm2 (E > 1.0 MeV). This results in an irradiated average upper shelf energy of 163 ft-lb for the weld HAZ.

Summary of Results March 2003 WCAP-16002 Revision 0

1-2 WESTINGHOUSE NON-PROPRIETARY CLASS 3 1-2 WESTINGHOUSE NON-PROPRIETARY CLASS 3

A comparison of the Waterford Unit 3 reactor vessel beitline material test results with the Regulatory Guide 1.99, Revision 211] predictions led to the following conclusions:

- The measured 30 ft-lb shift in transition temperature values for all the surveillance program weld and plate materials from Capsule 2630 is less than or comparable to the Regulatory Guide 1.99, Revision 2 predictions.

- The measured percent decrease in upper shelf energy of the Capsule 2630 surveillance material is less than the Regulatory Guide 1.99, Revision 2 predictions.

The peak end-of-license (32 EFPY) neutron fluence (E> 1.0 MeV) at the core midplane for the Waterford Unit 3 reactor vessel is given below. One value is given corresponding to the clad base metal interface. A second value is given for the vessel inner wetted surface back-calculated from the clad base metal interface fluence through the 1/8 inch clad using the Regulatory Guide 1.99, Revision 2 attenuation formula (i.e., Equation 3 in the Guide; f(depth x) = fsur'face

e (4024x)). Also provided are the calculated fluence at the vessel 1/4 and 3/4 thickness locations including the cladding, where thickness is 8.625 inches calculated using the Regulatory Guide 1.99, Revision 2 attenuation formula.

Vessel Clad Base Metal Interface: 2.48 x 1019 n/cm 2 Vessel Inner Wetted Surface: 2.56 x 1019 n/cm 2 RG 1.99 Attenuated Fluence: Vessel 1/4 thickness = 1.48 x 1019 n/cm 2 Vessel 3/4 thickness = 5.25 x 108 n/cm 2 The preceding values of neutron fluence were based on a 107% RCS flow rate. Projections of neutron fluence beyond cycle 11 were based on a 1.5% uprate (3441 MWt) at the start of Cycle 12 and a 8%

uprate (3716 MWt) at the start of Cycle 14.

A credibility evaluation was performed of the Waterford Unit 3 surveillance materials data in accordance with Regulatory Guide 1.99, Revision 2, and is given in Appendix D of this report. The evaluation demonstrates that the surveillance results are credible for the transverse orientation plate and for the weld metal. Therefore, the Chemistry Factor derived in Appendix D for the surveillance plate and weld metal can be used for predicting shift.

All beltline materials exhibit a more than adequate upper shelf energy level for continued safe plant operation and are expected to maintain an upper shelf energy greater than 50 ft-lb throughout the life of the vessel (32 EFPY) as required by I OCFR50, Appendix G121.

Summary of Results March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 1 2-1 2-I WESTINGHOUSE NON-PROPRIETARY CLASS 3 2 INTRODUCTION This report presents the results of the examination of the Capsule located at 2630, the second capsule to be removed from the reactor in the continuing surveillance program which monitors the effects of neutron irradiation on the Waterford Unit 3 reactor pressure vessel materials under actual operating conditions.

The surveillance program for the Waterford Unit 3 reactor pressure vessel materials was designed by Combustion Engineering. A description of the surveillance program and the pre-irradiation mechanical properties of the reactor vessel materials is presented in Reference 3. The surveillance program was planned to cover the 40-year design life of the reactor pressure vessel and was based on ASTM El 85-73, "Standard Practice for Conducting Surveillance for Light-Water Cooled Nuclear Power Reactor Vessels". Capsule 263° was removed from the reactor after 13.83 EFPY of exposure and shipped to the Westinghouse Science and Technology Center Hot Cell Facility, where the post-irradiation mechanical testing of the Charpy V-notch impact and tensile surveillance specimens was performed.

This report summarizes the testing of and the post-irradiation data obtained from surveillance capsule located at 263°, removed from the Waterford Unit 3 reactor vessel and discusses the analysis of the data.

Introduction March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 3-1 WESTINGHOUSE NON-PROPRIETARY CLASS 3 3-1 3 BACKGROUND The ability of the large steel pressure vessel containing the reactor core and its primary coolant to resist fracture constitutes an important factor in ensuring safety in the nuclear industry. The beltline region of the reactor pressure vessel is the most critical region of the vessel because it is subjected to significant fast neutron bombardment. The overall effects of fast neutron irradiation on the mechanical properties of low alloy, ferritic pressure vessel steels such as A533 Grade B Class I (base material of the Waterford Unit 3 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 Codei4'. The method uses fracture mechanics concepts and is based on the reference nil-ductility transition temperature (RTNDT).

RTNDT is defined as the greater of either the drop weight nil-ductility transition temperature (NDTT per ASTM E-208 151 ) or the temperature 60'F less than the 50 ft-lb (and 35-mil lateral expansion) temperature as determined from Charpy specimens oriented perpendicular (transverse) to the major working direction of the plate. The RTNDT of a given material is used to index that material to a reference stress intensity factor curve (KIR or Kic curve) that appears in Appendix G to the ASME Codel43. The KIR curve is a lower bound of dynamic, crack arrest, and static fracture toughness results obtained from several heats of pressure vessel steel. The Kic curve is a lower bound of crack initiation fracture toughness results obtained from several heats of pressure vessel steel. When a given material is indexed to the KIR or Kic curve, allowable stress intensity factors can be obtained for this material as a function of temperature. Operating limits can then be determined utilizing these allowable stress intensity factors. (Code Case N-640 allows the use of the K1, curve as an alternative to the KIR curve.)

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 surveillance program, such as the Waterford Unit 3 reactor vessel radiation surveillance program 61 , in which a surveillance capsule is periodically removed from the operating nuclear reactor and the encapsulated specimens tested. The increase in the average Charpy V-notch 30 ft-lb temperature (ARTNDT) due to irradiation is added to the initial RTNDT, along with a margin (M) to cover uncertainties, to adjust the RTNDT (ART) for radiation embrittlement. This ART (RTNDT initial + M + ARTNDT) is used to index the material to the Kia 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 March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 4-1 4 DESCRIPTION OF PROGRAM Six surveillance capsules for monitoring the effects of neutron exposure on the Waterford Unit 3 reactor pressure vessel core region (beltline) materials were inserted in the reactor vessel prior to initial plant start-up. The capsules were positioned in the reactor vessel between the core barrel and the vessel wall at locations shown in Figure 4-1. The vertical center of the capsule coincides with the vertical center of the core.

Capsule 2630 was removed after 13.83 effective full power years (EFPY) of plant operation. This capsule contained Charpy V-notch impact and tensile specimens made from reactor vessel lower shell course plate M- 1004-2, submerged arc weld metal identical to the beltline region girth weld seam and heat-affected-zone (HAZ) metal. The surveillance program weld and the reactor vessel girth seam weld were fabricated using weld wire heat 88114 using Linde 0091 fluxl 8 1.Standard Reference Material from HSST-O1MY Plate was included within capsule 2630 in addition to the reactor vessel materials.

Test specimens obtained from lower shell plate M-1004-2 (after the heat treatment and forming of the plate) were taken at least one plate thickness from the quenched ends of the plate. All plate and HAZ test specimens were machined from the 1/4 thickness location of the plate. All specimens were removed after performing a simulated post-weld stress-relieving treatment on the test material. All heat-affected-zone specimens were obtained from the weld heat-affected-zone of plate M-1004-2. (The HAZ metal specimens were obtained adjacent to the weldment joining plates M-1004-1 and M-1004-2. The surveillance program weld specimens were obtained from the weldment joining plates M-1004-1 and M-1004-3.)

Charpy V-notch impact specimens from plate M-1004-2 were machined in two orientations. One set of specimens was machined with the longitudinal axis of the specimen parallel to the major working direction of the plate (longitudinal orientation). The other set of specimens from plate M-1004-2 was machined with the transverse axis of the specimen perpendicular to the major working direction of the plate (transverse orientation). The Charpy V-notch specimens from the weld metal were machined with the longitudinal axis of the specimen transverse to the weld direction with the notch oriented in the direction of the weld.

Tensile specimens from plate M-1004-2 were machined in with the longitudinal axis of the specimen normal to the major working direction of the plate (transverse orientation). Tensile specimens from the weld metal were oriented with the longitudinal axis of the specimen transverse to the weld direction.

Capsule 2630 contained neutron flux monitors of sulfur, iron, titanium, nickel (cadmium-shielded),

aluminum-cobalt (cadmium-shielded and unshielded), copper (cadmium shielded) and uranium (cadmium-shielded and unshielded).

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

80% Au, 20% Sn Melting Point 536 0 F (280GC) 90% Pb, 5% Sn, 5% Ag Melting Point 558'F (2920 C) 2.5% Ag, 97.5% Pb Melting Point 580'F (304'C) 1.75% Ag, 0.75% Sn, 97.5% Pb Melting Point 590'F (31 0C)

Description of Program March 2003 WCAP-16002 Revision 0

4-2 WESTINGHOUSE NON-PROPRIETARY CLASS 3 The arrangement of the various mechanical test specimens, dosimeters and thermal monitors contained in capsule 2630 is shown in Figure 4-2. A typical Waterford Unit 3 surveillance capsule Charpy impact compartment assembly is shown in Figure 4-3. A typical Waterford Unit 3 surveillance capsule tensile and flux-monitor compartment assembly is shown in Figure 4-4.

The heat treatment for the plate material consisted of austenitization at 15751F 4i50'F for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , water quenched, and tempered at 1220 'F +/-251F for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . The surveillance plates received a 40 hour4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months stress relief at 1150'F +251F followed by furnace cooling to 600 'F. The weldment received a final 40 hour4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months and 30 minute stress relief at 1100 to 11751F as documented in Reference 6.

The copper and nickel contents (in weight percent) of the surveillance plate and weld materials and for the correlation monitor material are as follows:

Surveillance Material Copper Content - Nickel Content Data Source Plate M-1004-2 0.03 0.58 Waterford Unit 3 FSAR Weld 0.05 0.16 Waterford Unit 3 FSAR Correlation Monitor Material 0.174 0.665 NUREG/CR-6551 The sources are detailed below:

a) Waterford Unit 3 Final Safety Analysis Report, through Revision 12-A, January 2003.

b) Database in NUREG/CR-6551, Improved Embrittlement Correlations for Reactor Pressure Vessel Steels, November 1998.

Description of Program March 2003 WCAP-16002 Revision 0

CDm 1800 o 3Outlet Nozzle 0>

CD Inlet ,

97

, Vessel Barrel i 0 ( Cor Shrou 83 T,

284 w Reato Vessel Core 2630rpot AVeembl 0° 0 0

Enagd0a~e P Mipln lvto 0CDd CD' (n(

Enlarged Plan Viewa Elevation View

4-4 WESTINGHOUSE NON-PROPRIETARY CLASS 3 4-4 WESTINGHOUSE NON-PROPRIETARY CLASS 3 Lock Assembly Tensile -Monitor.

} Wedge Coupling Assembly Compartment Charpy Impact Compartments Tensile -Monitor Compartment -

j Charpy Impact Compartments J

Tensile -Monitor-Compartment Figure 4-2 Typical Waterford Unit 3 Surveillance Capsule Assembly Description of Program March 2003 WCAP-1 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 4-5 WESTINGHOUSE NON-PROPRIETARY CLASS 3 4-5 Coupling - End Cap Charpy Impact Specimens Sp, Tubing

-Wedge Coupling - End Cap Figure 4-3 Typical Waterford Unit 3 Surveillance Capsule Charpy Impact Compartment Assembly Description of Program March 2003 WCAP-16002 Revision 0

4-6 WESTINGHOUSE NON-PROPRIETARY CLASS 33 4-6 WESTINGHOUSE NON-PROPRIETARY CLASS Wedge Coupling - End Cap Flux Spectrum Monitor Cadmium Shielded Flux Monitor Housing-Stainless Steel Tubing Stainless Steel Tubing Cadmium Shield Threshold Detector Threshold Detector

--Quartz Tubing Temperature Monitor-Weight Temperature Monitor- Low Melting Alloy Housing Tensile Specimen Split Spacer Tensile Specimen Housing

-Rectangular Tubing

-Wedge Coupling - End Cap Figure 4-4 Typical Waterford Unit 3 Surveillance Capsule Tensile and Flux-Monitor Compartment Assembly Description of Program March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-1 5 TESTING OF SPECIMENS FROM CAPSULE 2630 5.1 OVERVIEW The post-irradiation mechanical testing of the Charpy V-notch impact specimens and tensile specimens was performed in the Remote Metallographic Facility (RMF) at the Westinghouse Science and Technology Center. Testing was performed in accordance with 10CFR50, Appendices G and HE2], ASTM Standard Practice El 85 -82 171,and Westinghouse Procedure RMF 8402, Revision 2 as modified by Westinghouse RMF Procedures 8102, Revision 1, and 8103, Revision 1.

Upon receipt of the capsule at the hot cell laboratory, the specimens and spacer blocks were carefully removed, inspected for identification number, and checked against the master lists in TR-C-MCS-001[3].No discrepancies were found.

Examination of the four low-melting, eutectic alloy thermal monitors indicated that the two lowest melting point monitors melted. Based on this examination, the maximum temperature to which the test specimens were exposed to was between 5590 F and 579 0 F.

The Charpy impact tests were performed per ASTM Standard Test Method E23-9818] and RMF Procedure 8103, Revision 1, on a Tinius-Olsen Model 74, 358J machine. The tup (striker) of the Charpy impact test machine is instrumented with an Instron Dynatup Impulse instrumentation system, feeding information into an IBM compatible computer. With this system, load-time and energy-time signals can be recorded in addition to the standard measurement of Charpy energy (ED). From the load-time curve (Appendix A), the load of general yielding (PGy), the time to general yielding (tcy), 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 (cy) was calculated from the three-point bend formula having the following expression:

ay=(PGY *L) / [B * (W - a)2

C] (1) where: L = distance between the specimen supports in the impact machine B = the width of the specimen measured parallel to the notch W = height of the specimen, measured perpendicularly to the notch a = notch depth Testing of Specimens from Capsule 2630 March 2003 WCAP-16002 Revision 0

5-2 WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-2 WESTINGHOUSE NON-PROPRIETARY CLASS 3 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 1 is valid with C = 1.21. Therefore, (for L 4W),

ay=(PGy*L) /[B*(W-a) 2 *1.21] = (3.33*PGy *W) /[B*(WJ-Ta) 2 ] (2)

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

cy=33.3 *PGy (3) where ay is in units of psi and PGY is in units of lbs. The flow stress was approximated using the average of the yield and maximum loads obtained using the three-point bend formula.

The symbol A in columns 4, 5, and 6 of Tables 5-5 through 5-8 is the cross-section area under the notch of the Charpy specimens:

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

Percent shear was determined from post-fracture photographs using the ratio-of-areas methods in compliance with ASTM Standard Test Method A3 7 0-9 7 1[] . The lateral expansion was measured using a dial gage rig similar to that shown in the same specification.

Tensile tests were performed on a 20,000-pound Instron, split-console test machine (Model 1115) per ASTM Standard Test Methods E8-991'oJ and E21-92(1998)' 11], and RMF Procedure 8102, Revision 1. 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 cross-head speed of 0.05 inches per minute throughout the test.

Extension measurements were made with a linear variable displacement transducer (LVDT) 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 E83-93l'21 .

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 gripper. In the test configuration, with a slight load on the specimen, a plot of specimen temperature versus upper and lower tensile machine gripper 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 +2WF.

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 Testing of Specimens from Capsule 2630 March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-3 5-3 WESTINGHOUSE NON-PROPRIETARY CLASS 3 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.

5.2 CHARPY V-NOTCH IMPACT TEST RESULTS The results of the Charpy V-notch impact tests performed on the various materials contained in capsule 2630, which received a fluence of 1.45 x I 1O9 n/cm 2 (E > 1.0 MeV) in 13.83 EFPY of operation, are presented in Tables 5-1 through 5-8 and are compared with unirradiated results from TR-C-MCS-002-P[ 6 1 as shown in Figures 5-1 through 5-12.

The transition temperature increases and upper shelf energy decreases for the capsule 263° materials are summarized in Table 5-9. These results led to the following observations:

The reactor vessel lower shell plate M-1004-2 Charpy specimens, oriented with the longitudinal axis of the specimen normal to the major working direction of the plate (transverse orientation), was irradiated to 1.45 x 10i 9 n/cm2 (E> 1.OMeV). This resulted in a 30 ft-lb transition temperature decrease of 9.17F and a 50 ft-lb transition temperature increase of 8.1 0 F, with an irradiated 30 ft-lb transition temperature of -33.6 0 F and an irradiated 50 ft-lb transition temperature of I I.0 0 F for the transversely oriented plate specimens. The 30 ft-lb transition temperature change was taken as 00 F rather than assume a negative shift.

The HSST Plate OIMY correlation monitor material Charpy specimens, oriented with the longitudinal axis of the specimen parallel to the major working direction of the plate (longitudinal orientation), was irradiated to 1.45 x 10i9 n/cm 2 (E> 1.0 MeV). This resulted in a 30 ft-lb transition temperature increase of 150.50 F and a 50 ft-lb transition temperature increase of 151.3 0 F, with an irradiated 30 ft-lb transition temperature of 184.9 0 F and an irradiated 50 ft-lb transition temperature of 211.41F for the longitudinally oriented plate specimens.

Irradiation of the weld metal Charpy specimens to 1.45 x 1019 n/cm 2 (E> 1.OMeV) resulted in a 30 ft-lb transition temperature increase of 6.9WF and a 50 ft-lb transition temperature increase of 13.87F.

This results in an irradiated 30 ft-lb transition temperature of-77.70 F and an irradiated 50 ft-lb transition temperature of -51.4 0 F for the surveillance weld material.

Irradiation of the weld Heat-Affected-Zone (HAZ) metal Charpy specimens to 1.45 x 1O'9 n/cm2 (E > 1.0 MeV) resulted in a 30 ft-lb transition temperature increase of 25.1°F and a 50 ft-lb transition temperature increase of 27.9°F. This results in an irradiated 30 ft-lb transition temperature of-92.0°F and an irradiated 50 ft-lb transition temperature of 62.1°F.

Irradiation of the lower shell plate M-1004-2 (transverse orientation) to 1.45 x 1019 n/cm 2 (E> 1.0 MeV) resulted in an average upper shelf energy decrease of 10 ft-lb after irradiation. This gives an irradiated average upper shelf energy of 131 ft-lb for the transversely oriented plate specimens.

Irradiation of the correlation monitor material (longitudinal orientation) to 1.45 x 1019 n/cm 2 (E > 1.0 MeV) resulted in an average upper shelf energy decrease of 20 ft-lb after irradiation. This gives an irradiated average upper shelf energy of 113 ft-lb for the longitudinal oriented plate specimens.

Testing of Specimens from Capsule 2630 March 2003 WCAP-16002 Revision 0

5-4 WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-4 WESTINGHOUSE NON-PROPRIETARY GLASS 3 Irradiation of the weld metal Charpy specimens to 1.45 x 1019 n/cm 2 (E> 1.0 MeV) resulted in an average energy decrease of 11 ft-lb after irradiation. This gives an irradiated average upper shelf energy of 145 ft-lb for the weld metal specimens.

Irradiation of the weld HAZ metal Charpy specimens to 1.45 x 1019 n/cm 2 (E > 1.0 MeV) resulted in an average energy decrease of 7 ft-lb after irradiation. This gives an irradiated average upper shelf energy of 163 ft-lb for the weld HAZ metal.

A comparison is presented in Table 5-10 of the Waterford Unit 3 reactor vessel beltline material test results with the Regulatory Guide 1.99, Revision 2[11 predictions. The following observations are made:

- The measured 30 ft-lb shift in transition temperature values for all the surveillance plate and weld materials from capsule 2630 is less than the Regulatory Guide 1.99, Revision 2, predictions. This is indicative of the excellent controls (both copper content and cleanliness of the plate) that were placed on the Waterford Unit 3 reactor vessel materials.

- The measured 30 ft-lb shift in transition temperature value for the HSST Plate OIMY correlation monitor material was within 50 F of the Regulatory Guide 1.99 prediction. This excellent agreement indicates that the irradiation environment has been accurately defined for both the correlation monitor material and the surveillance materials.

- The measured percent decrease in upper shelf energy of the materials from the 2630 surveillance capsule is less than the Regulatory Guide 1.99, Revision 2 predictions.

- A similar analysis is provided in Table 5-10 for the results of capsule 97°. The measured 30 ft-lb shift in transition temperature values for all the surveillance plate and weld materials from capsule 97° is less or comparable to the Regulatory Guide 1.99, Revision 2 predictions.

- Further comparisons are made in the credibility evaluation presented in Appendix D The fracture appearance of each irradiated Charpy specimen from the various surveillance capsule 2630 materials is shown in Figures 5-13 through 5-16. The fracture surfaces show an increasingly ductile (i.e.,

tougher) appearance with increasing test temperature. The load-time records for individual instrumented Charpy specimen tests are shown in Appendix A.

All beltline materials exhibit a more than adequate upper shelf energy level for continued safe plant operation and are expected to maintain an upper shelf energy of no less than 50 ft-lb throughout the life of the vessel (32 EFPY) as required by IOCFR50, Appendix G.

The Charpy V-notch data presented in this report is based on a plot of all capsule data using CVGRAPH, Version 4.1, which is a hyperbolic tangent curve-fitting program. Appendices B and C contain the CVGRAPH, Version 4.1, Charpy V-notch plots and the program input data, and the Charpy V-notch shift results for each surveillance material from the hyperbolic tangent curve-fitting.

Testing of Specimens from Capsule 2630 March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B 5-5 5-5 WESTINGHOUSE NON-PROPRIETARY CLASS 3 5.3 TENSILE TEST RESULTS The results of the tensile tests performed on the various materials contained in capsule 2630 irradiated to 1.45 x I019 n/cm 2 (E > 1.0 MeV) are presented in Table 5-1 1 and are compared with unirradiated results from TR-C-MCS-002-P[ 6 1 as shown in Figures 5-17 through 5-19.

The results of the room temperature (70 to 75 'F) tensile tests performed on the lower shell plate M-1 004-2 (transverse orientation) indicated that irradiation to 1.45 x 109 n/cm 2 (E> 1.0 MeV) caused an approximate increase of 2 ksi in the 0.2 percent offset yield strength and approximately a 4 ksi increase in the ultimate tensile strength when compared to unirradiated data[ 61 (Figure 5-17).

The results of the room temperature tensile tests performed on the surveillance weld metal indicated that irradiation to 1.45 x 10'9 n/cm 2 (E > 1.0 MeV) caused no significant change in the 0.2 percent offset yield strength and a 4 ksi increase in the ultimate tensile strength when compared to unirradiated data 161 (Figure 5-18).

The results of the tensile tests performed on the surveillance HAZ metal indicated that irradiation to 1.45 x 109 n/cm 2 (E > 1.0 MeV) caused a I ksi increase in the 0.2 percent offset yield strength and 2 ksi increase in the ultimate tensile strength when compared to unirradiated data(6 ] (Figure 5-19).

The fractured tensile specimens for the lower shell plate M-1004-2 material are shown in Figure 5-20. The fractured tensile specimens for the surveillance weld metal and heat-affected-zone material are shown in Figures 5-21 and 5-22, respectively. The engineering stress-strain curves for the tensile tests are shown in Figures 5-23 through 5-25.

Testing of Specimens from Capsule 2630 March 2003 WCAP-1 6002 Revision 0

5-6 WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-6 WESTINGHOUSE NON-PROPRIETARY CLASS 3 Table 5-1 Charpy V-notch Data for the Waterford Unit 3 Plate M-1004-2 Irradiated to a Fluence of 1.45 x 1019 n/cm 2 (E> 1.0 MeV), Transverse Orientation Sample Temperature Impact Energy Lateral Expansion Shear Number F C ft-lbs Joules mils Mm %

25E -40 -40 19 26 14 0.36 10 23D -30 -34 14 19 9 0.23 5 25J -10 -23 55 75 37 0.94 15 246 0 -18 46 62 32 0.81 15 215 25 -4 75 102 50 1.27 45 23E 50 10 74 100 51 1.30 50 24U 75 24 66 89 49 1.24 45 22U 125 52 105 142 70 1.78 75 232 160 71 III 151 73 1.85 80

- 22Y 200 93 128 174 77 1.96 100 243 225 107 135 183 82 2.08 100 24M 350 177 131 178 75 1.91 100 Testing of Specimens from Capsule 263° March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-7 WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-7 Table 5-2 Charpy V-notch Data for the HSST Plate OlMY Correlation Monitor Material Irradiated to a Fluence of 1.45 x 1019 n/cm2 (E> 1.0 MeV), Longitudinal Orientation Sample Temperature Impact Energy Lateral Expansion Shear Number F C Ft-lbs Joules mils mm %

A47 -30 -34 4 5 3 0.08 2 A4E 50 10 9 12 6 0.15 10 A46 125 52 12 16 8 0.20 20 A3L 175 79 23 31 17 0.43 25 A4C 200 93 32 43 25 0.64 30 A3P 240 116 92 125 60 1.52 65 A4A 275 135 77 104 58 1.47 75 A41 320 160 116 157 69 1.75 100 A43 350 177 108 146 69 1.75 100 A4K 375 191 117 159 74 1.88 100 A3E 425 218 114 155 68 1.73 100 A3Y 460 238 108 146 67 1.70 100 Testing of Specimens from Capsule 263° March 2003 WCAP-16002 Revision 0

5-8 WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-8 WESTINGHOUSE NON-PROPRIETARY CLASS 3 Table 5-3 Charpy V-notch Data for the Waterford Unit 3 Surveillance Weld Metal Irradiated to a Fluence of 1.45 x 1019 n/cm2 (E> 1.0 MeV)

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

333 -175 -115 4 5 0 0.00 5 332 -125 -87 7 9 I 0.03 10 363 -75 -59 29 39 16 0.41 20 34B -50 -46 57 77 39 0.99 35 35Y -25 -32 76 103 49 1.24 65 361 0 -18 94 127 61 1.55 75 34K 25 -4 121 164 77 1.96 90 33D 50 10 130 176 82 2.08 90 33U 75 24 134 182 83 2.11 90 365 100 38 143 194 87 2.21 100 37A 150 66 139 188 85 2.16 100 35L 200 93 153 207 83 2.11 100 Testing of Specimens from Capsule 2630 March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-9 5-9 WESTINGHOUSE NON-PROPRIETARY CLASS 3 Table 5-4 Charpy V-notch Data for the Waterford Unit 3 Heat Affected Zone Metal Irradiated to a Fluence of 1.45 x 1019 n/cm2 (E> 1.0 MeV)

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

41P -175 -115 4 5 1 0.03 5 41D -125 -87 29 39 15 0.38 10 43E -75 -59 31 42 23 0.58 45 436 -25 -32 83 113 47 1.19 60 42T 0 -18 114 155 67 1.70 75 41U 25 -4 118 160 75 1.91 90 45B 50 10 144 195 80 2.03 100 471 75 24 152 206 69 1.75 100 46L 110 43 142 193 74 1.88 100 473 150 66 182 247 74 1.88 100 446 225 107 163 221 77 1.96 100 44A 325 163 192 260 69 1.75 100 Testing of Specimens from Capsule 2630 March 2003 WCAP-1 6002 Revision 0

5-10 WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-10 WESTINGHOUSE NON-PROPRIETARY CLASS 3 Table 5-5 Instrumented Charpy Impact Test Results for the Waterford Unit 3 Plate M-1004-2 Normalized Energies (ft-lb/in 2 )

Charpy Yield Time to Time to Fast Test Energy Load Yield tGY Max. Max. Fract. Arrest Yield Flow Sample Temp. ED Charpy Max. Prop. PGY (msec) Load PM Tm Load PF Load PA Stress Sy Stress No. (OF) (ft-lb) ED/A EM/A E/A (lb) (lb) (msec) (lb) (lb) (ksi) (ksi) 25E -40 19 153 67 86 3455 0.15 4199 0.22 4051 0 115 127 23D -30 14 113 60 53 3231 0.14 4097 0.21 4087 0 108 122 25J -10 55 443 325 118 3478 0.15 4477 0.68 4334 0 116 132 246 0 46 371 311 59 3327 0.15 4425 0.67 4369 0 III 129 215 25 75 604 316 289 3269 0.15 4413 0.68 3908 324 109 128 23E 50 74 596 308 288 3185 0.15 4282 0.69 4055 744 106 124 24U 75 105 846 308 538 3220 0.15 4303 0.69 3898 620 107 125 22U 125 66 532 295 237 2943 0.15 4164 0.69 3096 1211 98 118 232 160 111 894 290 605 2913 0.14 4079 0.68 2556 1340 97 116 22Y 200 128 1031 289 742 2900 0.14 4078 0.69 n/a n/a 97 116 243 225 135 1088 292 796 2858 0.14 4116 0.69 n/a n/a 95 116 24M 350 131 1056 265 790 2594 0.14 3732 0.69 n/a n/a 86 105 Testing of Specimens from Capsule 2630 March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-11 WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-Il Table 5-6 Instrumented Charpy Impact Test Results for the HSST Plate 01MY Correlation Monitor Material Irradiated to a Fluence of 1.45 x 1019 n/cm2 (E> 1.0 MeV), Longitudinal Orientation Normalized Energies (ft-lb/in2 )

Charpy Yield Time to Time to Fast Test Energy Load Yield tGY Max. Max. Fract. Arrest Yield Flow Sample Temp. ED Charpy Max. Prop. PGY (msec) Load PM Tm Load PF Load PA Stress Sy Stress No. (OF) (ft-lb) ED/A EM/A EW/A (lb) (lb) (msec) (lb) (lb) (ksi) (ksi)

A47 -30 4 32 16 16 1948 0.13 1948 0.13 1944 0 65 65 A4E 50 9 73 38 34 3504 0.15 3648 0.17 3638 0 117 119 A46 125 12 97 39 58 3318 0.15 3564 0.17 3559 345 110 115 A3L 175 23 185 66 120 3103 0.14 3938 0.22 3889 864 103 117 A4C 200 32 258 144 113 3052 0.14 4073 0.38 4039 1097 102 119 A3P 240 92 741 309 433 3230 0.15 4398 0.67 3540 1304 108 127 A4A 275 77 620 222 398 3079 0.14 4257 0.52 3889 2708 103 122 A41 320 116 935 305 630 3208 0.15 4310 0.68 n/a n/a 107 125 A43 350 108 870 265 605 3057 0.17 4225 0.63 n/a n/a 102 121 A4K 375 117 943 299 644 3083 0.15 4200 0.67 n/a n/a 103 121 A3E 425 114 919 290 629 3024 0.15 4117 0.67 n/a n/a 101 119 A3Y 460 108 870 272 598 2985 0.16 4103 0.64 n/a n/a 99 118 Testing of Specimens from Capsule 263° March 2003 WCAP-16002 Revision 0

5-12 WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-12 WESTINGHOUSE NON-PROPRIETARY CLASS 3 Table 5-7 Instrumented Charpy Impact Test Results for the Waterford Unit 3 Surveillance Weld Metal Normalized Energies (ft-lb/in2 )

Charpy Yield Time to Time to Fast Test Energy Load Yield tGy Max. Max. Fract. Arrest Yield Flow Sample Temp. ED Charpy Max. Prop. PGY (msec) Load PM Tm Load PF Load PA Stress Sy Stress No. (F) (ft-lb) ED/A EM/A E/A (lb) (lb) (msec) (lb) (lb) (ksi) (ksi) 333 -175 4 31 15 16 1915 0.11 1968 0.12 1963 0 64 65 332 -125 8 63 32 30 3578 0.15 3587 0.15 3580 0 119 119 363 -75 29 237 74 163 3766 0.16 4672 0.23 4633 0 125 140 34B -50 56 450 240 210 3923 0.15 4621 0.51 4408 337 131 142 35Y -25 74 596 248 348 3616 0.15 4551 0.53 4212 1240 120 136 361 0 92 739 332 407 3641 0.15 4524 0.68 3673 1513 121 136 34K 25 121 975 326 649 3549 0.15 4460 0.68 3420 2099 118 133 33D 50 125 1006 333 673 3457 0.15 4475 0.70 1915 931 115 132 33U 75 129 1037 330 707 3448 0.15 4479 0.70 2153 1356 115 132 365 100 140 1126 309 816 3317 0.15 4224 0.69 n/a n/a 110 126 37A 150 133 1074 309 765 3226 0.14 4184 0.69 n/a n/a 107 123 35L 200 147 1187 303 884 3065 0.14 4152 0.69 n/a n/a 102 120 Testing of Specimens from Capsule 263° March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-13 WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-13 Table 5-8 Instrumented Charpy Impact Test Results for the Waterford Unit 3 Heat Affected Zone Material Normalized Energies (ft-lb/in')

Charpy Yield Time to Time to Fast Test Energy Load Yield tGY Max. Max. Fract. Arrest Yield Flow Sample Temp. ED Charpy Max. Prop. PGY (msec) Load PM T. Load PF Load PA Stress Sy Stress No. (OF) (ft-lb) ED/A EM/A Ep/A (lb) (lb) (msec) (lb) (lb) (ksi) (ksi) 41P -175 5 39 19 20 2325 0.12 2403 0.13 2396 0 77 79 41D -125 31 248 79 169 4110 0.15 5107 0.22 4953 0 137 153 43E -75 30 244 71 173 3817 0.15 4543 0.22 4461 464 127 139 436 -25 80 647 337 310 3566 0.16 4514 0.71 4034 817 119 135 42T 0 111 895 347 548 3583 0.15 4649 0.71 3859 584 119 137 41U 25 116 934 335 599 3512 0.16 4514 0.71 3585 2542 117 134 45B 50 139 1123 327 796 3448 0.15 4506 0.69 n/a n/a 115 132 471 75 146 1179 334 845 3566 0.15 4609 0.69 n/a n/a 119 136 46L 110 138 1108 322 786 3322 0.15 4465 0.69 n/a n/a 111 130 473 150 175 1410 320 1090 3251 0.14 4423 0.70 n/a n/a 108 128 44A 325 184 1485 310 1175 2805 0.15 4231 0.71 n/a n/a 93 117 Testing of Specimens from Capsule 2630 March 2003 WCAP-16002 Revision 0

5-14 WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-14 WESTINGHOUSE NON-PROPRIETARY CLASS 3 Table 5-9 Effect of Irradiation to 1.45 x 1019 n/cm2 (E>1.0 MeV) on the Notch Toughness Properties of the Waterford Unit 3 Average 30 (ft-lb)(') Average 35 mil Lateral(b) Average 50 ft-lb0) Average Energy Absorption(')

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

Unirradiated Irradiated AT Unirradiated Irradiated AT Unirradiated Irradiated AT Unirradiated Irradiated AE Lower Shell -24.44 -33.57 0 (-9.1) -6.73 9.81 16.5 2.89 11.01 8.1 141 131 -10 Plate M-1004-2 (Transverse) .

Correlation 34.31 184.87 150.5 41.94 208.53 166.6 60.02 211.36 151.3 133 113 -20 Monitor Material (Longitudinal)

Weld Metal -84.58 -77.71 6.9 -68.31 -46.80 21.5 -65.19 -51.38 13.8 156 145 -11 HAZ Metal -117.09 -91.96 25.1 -89.55 -56.57 33.0 -90.08 -62.15 27.9 170 163 -7

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

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

Testing of Specimens from Capsule 2630 March 2003 WCAP 16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-15 WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-15 Table 5-10 Comparison of the Waterford Unit 3 Surveillance Material 30 ft-lb Transition Temperature Shifts and Upper Shelf Energy Decrease with Regulatory Guide 1.99, Revision 2, Predictions Material Capsule Fluence 30 ft-lb Transition Upper Shelf Energy (x 10 19 n/cm 2 ) (a) Temperature Shift Decrease Predicted Measured Predicted Measured (OF) (OF) (%)(b) (%)

Lower Shell Plate 970 0.647 18 6 17 8.9 M-1004-2 (Longitudinal)'

Lower Shell Plate 970 0.647 18 28 17 12 M-1 004-2 M-1004-2 2630 1.45 22 0 (-9) 20.7 7 (Transverse)

Surveillance Program 970 0.647 39 28 17 8 Weld Metal 2630 1.45 49 7 20.7 7 Heat Affected Zone 970 0.647 --- 14 --- 8 Material 2630 1.45 --- 25 --- 4 Correlation Monitor 970 c C C C C Material 2630 1.45 145 150 32 15 Notes:

(a) Calculated Fluences from 970 capsule analysis (BAW-2177) and 2630 capsule analysis (section 6 of this report); results (E > 1.0 MeV)

(b) From Figure 2 of Regulatory Guide 1.99, Revision 2, using the Cu values given in Section 4 and the cited capsule fluence values.

(c) No correlation monitor material specimens in 970 capsule. No longitudinal plate specimens in 2630 capsule.

Testing of Specimens from Capsule 2630 March 2003 WCAP-16002 Revision 0

5-16 WESTINGHOUSE NON-PROPRIETARY CLASS 3 rable 5-11 Tensile Specimens From Lower Shell Course Plate M-1004-2, Weld, and Heat Affected Zone Material Sample Test 0.2% Yield Ultimate Fracture Fracture Fracture Uniform Total Reduction Number Material Temperature Strength Strength Load Stress Strength Elongation Elongation in Area (F) (ksi) (ksi) (kip) (ksi) (ksi) (%) (%) (%)

232 Plate 75 71.3 93.2 2.89 223.0 58.9 12.0 29.3 74 2KK Plate 250 66.2 85.5 2.98 186.9 60.7 10.5 22.9 68 2KL Plate 550 61.1 88.0 3.15 152.8 64.2 9.5 19.9 58 3K3 Weld 75 83.5 96.0 2.83 225.9 57.7 10.5 25.8 74 3.D Weld 250 75.4 88.5 2.66 198.9 54.2 9.0 22.9 73 3J7' Weld 550 71.3 87.7 3.29 166.2 67.0 - - 60 4JB AZ 75 70.3 93.8 2.95 200.4 60.1 7.0 19.0 70 411 HAZ 250 65.7 86.5 4.74 365.5 96 6 6.0 18.1 74 2

4KA HAZ 550 67.2 88.8 3.34 156.0 67.9 - - 56 l) Specimen broke outside of the gage section

2) Specimen broke in knife edge of clip gage Testing of Specimens from Capsule 2630 March 2003 WCAP-1 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 g 5-17 5-17 WESTiNGHOUSE NON-PROPRIETARY CLASS 3

.. SHELL PLATE M-1004-2 (TRANS)

CVGRAPH 4J Hyperbolic Tangent Curve Printed at 1451:35 on 09-302 Resuls Curve Fluence LSE d-lSE USE d-tSE T e 30 d-T o 30 Te 5o d-T o 50 1 0 219 .,0 , 141 0 -24.44 0 289 0 2 0 2.19 0 124 -17 W45 Z7B9 331 302 3 0 Z19 0 131 -10 -33.57 -913 11I0 812 (1

la P-4 S0

.4-

.z 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Curve Legend I°- 20--- 30 Data Set(s) Plotted Curve Plant Cansule

material Ori Heati I In7 UNIRR PLATE SA533B1 TL M-1004-2 2 TM WFIR PLATE SA533BI TL U-1004-2 3 1F3 1-Z63 PLATE SA533BI TL U-ID04-2 Figure 5-1 Charpy V-Notch Impact Energy vs. Temperature for Waterford Unit 3 Reactor Vessel Lower Shell Plate M-1004-2 (Transverse Orientation)

Testing of Specimens from Capsule 2630 March 2003 WCAP-1 6002 Revision 0

5-18 WEST1NGHOUSE NON-PROPRIETARY CLASS 33 5-18 WESTINGHOUSE NON-PROPRIETARY CLASS SHELL PLATE M-1004-2 (TRANS)

CYGRAPH 4.1 Hyperbolic Tangent Curve Printed at 14TO3 on 10-01-2002 Results -i Curve Fluence, USE d-USE T o LE35 d-T oLE35 I 0 90.9 0 -&73 a 2 0 834 -75 1883 2557 3 0 77B6 -1303 9.81 16.55 UO r-4

."4 r..

-P co a)l

-30 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Curve legend I0 20---- 30 Data Sel(s) Plotted Curve Plant Capsule Material 0i. Heatt WF3 UNIRR PLATE SA533BI Th M-10D4-2 2 11T3 W PLATE SA533B1 TL M-1004-2 3 1 1-263. PLATE SA533BI TL 19-1004-2 Figure 5-2 Charpy V-Notch Lateral Expansion vs. Temperature for Waterford Unit 3 Reactor Vessel Lower Shell Plate M-1004-2 (Transverse Orientation)

Testing of Specimens from Capsule 2630 March 2003 WCAP-1 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-19 WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-19

SHELL PLATE M-1004-2 (TRANS)

CYGRAPH 41 Hyperbolic Tangent Curve Printed atl4:4158 on 10-01-2002 Results Curve Fluence T o' 0/ Shear d-T o 50/ Shear I 0 4031 0 \

2 0 4406 3.79 3 0 663 V.)

Cd-0) a)

C)

_H

-300 -200 -100 0 100 200 300 400 500 600 TemDerature in Degrees F Curve Legend ID- 2 0-----

Data Set(s) Plotted Curve Plant Carsule Material '0i Heatf 1 11X UNIRR PLATE SA533H1 TL M1-1004-2 2 TF3J -W PLATE SA533B1 TL M1-1004-2 F3! -263 PLATE SA533B1 TL M-1004-2 Figure 5-3 Charpy V-Notch Percent Shear vs. Temperature for Waterford Unit 3 Reactor Vessel Lower Shell Plate M-1004-2 (Transverse Orientation)

Testing of Specimens from Capsule 2630 March 2003 WCAP-16002 Revision 0

5-20 WESTINGHOUSE NON-PROPRIETARY CLASS 3 .

STANDARD REFERENCE MATERIAL CVGRAPH 41 Hyperbolic Tangent Curve Printed at 162051 on 101-20I02 Results Curve fiiuence ISE d-LSE USE d-USE T o 30 d-T o 30 T7o 50 d-T o 50 1 0 2.19 0 133 0 3431 0 60.02 0 2 0 219 0 113 -20 184 B7 150.55 211.36 15133 30- -

U) 250-la I

,0 200- 4c -

150-z 0_

C) 50-

-300 -2O0 -100 0 100 200 300 400 500 600 Temperature in Degrees F Curve Legend 1°- 20 ---------

Data Set(s) Plotted A.... ,....

IDI-f

.n ..... .

Vd~u:- 1l uftrn4>1 ULUd 2 . _

OrL Heatf I WF3 UNIRE SRH HSM1 LT A1008-1 2 iF3 W-263 SRM SA533MB LT A100W81 Figure 5-4 Charpy V-Notch Impact Energy vs. Temperature for HSST Plate OlMY Correlation Monitor Material (Longitudinal Orientation)

Testing of Specimens from Capsule 2630 March 2003 WCAP-1 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-21 WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-21 STANDARD REFERENCE MATERIAL CVGRAPH 41 Hyperbolic Tangent Curve Printed at 162 M3 on 10-01-2002 Results Curve Fluence USE d-USE T o LE35 d-T o LE35 1 0 9525 0 4194 0 2 0 69.45 -25.79 20a53 16658 cn

1'4 r-:

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Curve legend I - 20 Data Set(s) Plotted tul tc DI-fP Plnt rldll.

~Aa tdPDUIE; 1bIAO roas OriL Heat#

I F3 UNIRR SRM 1i11I LT A1088-I 2 1F3 lr-263 SPl SA533BI LT Al1008 rigure5-: tnarpy v-notcn.Laterai xpansion vs. iemperaturexormn I natevulvix torrelatlon Monitor Material (Longitudinal Orientation)

Testing of Specimens from Capsule 263° March 2003 WCAP-1 6002 Revision 0

5-22 WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-22 WESTINGHOUSE NON-PROPRIETARY CLASS 3 STANDARD REFERENCE MATERIAL C1GRAPH 41 Hyperbolic Tangent Curve Printed at 162554 on 10-01-2002 RMutls Curve Fluence T o WI. Shear d-T o W0z.

Shear I 0 86.38 0 2 0 21984 1346 Q) co C.)

$S4 (t

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Curve Legend I 0 20-- -----

Data Setqs) Plotted Curve Plant Capsule. Material Ori. Heat!

I V?3 UNIRR SNM, wr1 LT A1008-1 2 TF3 W-M SRM SA533BI LT A1008-1 Figure 5-6 Charpy V-Notch Percent Shear vs. Temperature for HSST Plate OlMY Correlation Monitor Material (Longitudinal Orientation)

Testing of Specimens from Capsule 263° March 2003 WCAP-1 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-23 WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-23 SURVEILLANCE PROGRAM WELD METAL CYGRAPH 4.1 Hyperbolic Tangent Curve Printed at 151321 on IO01-20(2 Results Curve Fluence ISE d-ISE USE d-USE T o 30 d-T o 30 T o 50 d-T o 50 I 0 219 0 156 0 -m48 0 -6519 0 2 0 219 0 143 -13 -36 2822 -34.7 3031 3 0 219 0 145 -11 -77.71 6B7 -5138 13.

30F -

250F (a 2cX 0.

z 150- ?,

0 100--X _ ==

_I _ _ _=== __ __

=U - - ---

( I

-300 -200 -100 0 100 200 300 40. 500 600 Temperature in Deg)rees F Curve Legend 10- 20--- 30 Data Set(s) Plotted Curve Plant Capsule Material Or Heat!

I HF3 UNIRR IELD L 124/0091 88114/0145 2 1w W-9 WELD L 124/0091 8114/0145 3 1 -263 WUl L124/0091 M114/0145 Figure 5-7 Charpy V-Notch Impact Energy vs. Temperature for Waterford Unit 3 Reactor Vessel Surveillance Weld Material Testing of Specimens from Capsule 2630 March 2003 WCAP-I 6002 Revision 0

5-24 WESTINGHOUSE NON-PROPRIETARY CLASS 3 SURVEILLANCE PROGRAM WELD METAL CYGRAPH 41 Hyperbolic Tangent Curve Printed at 15;17:12 on 10-01-2002 Resilts Curve Fluence USE d-USE T o LE35 d-T o LE35 I 0 95.49 0 -6E31 O 2 0 87 -6.81 -39.63 2868 3 0 85z5 -1013 -46.8 2151 -

(n r__4

.,_4

$::Li X

Po r__4 CTj

. ;.4 cu

_P Cd J-

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Curve legend I - 20---

Data Set(s) Plotted Curve Plant Capsule Material OrL Heat#. .

I lF~3 UNtRR WELD L 124/0091 O8114/0145 2 Wff3 W-W MELD L 124/0091 8114/0145 3 WF31 t-263 WELD L 124/0091 88114/0145 Figure 5-8 Charpy V-Notch Lateral Expansion vs. Temperature for Waterford Unit 3 Reactor Vessel Surveillance Weld Metal Testing of Specimens from Capsule 2630 March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-25 5-25 WESTINGHOUSE NON-PROPRIETARY CLASS 3 SURVEILLANCE PROGRAM WELD METAL CYGRAPH 41 Hyperbolic Tangent Curve Printed at 15:2123 on 10-01-2002 Remits r.'".~ Fillow"

-- J *b*

T o 50z Shear d-T o 5(a Shear 1 0 -51.09 0 2 0 -30.93 2015 3 0 -36Z7 14.71 CZ) c-)

a,

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Curve Legend 1a 20--- 3<

Data Set(s) Plotted Curve Plant ------...

Cawsule Material= Or Heat!

I Wm UNN IELD L 124/0091 88114/0145 2 WlF3 F FELD L 124/0091 88114/0145 F3 l-263 IELD L 124/0091 88114/0145 Figure 5-9 Charpy V-Notch Percent Shear vs. Temperature for Waterford Unit 3 Reactor Vessel Surveillance Weld Metal Testing of Specimens from Capsule 2630 March 2003 WCAP-16002 Revision 0

5-26 WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-26 WESTiNGHOUSE NON-PROPRIETARY CLASS 3 HEAT AFFECTED ZONE CVGRAPH 41 Hyperbolic Tangent Curve Printed at 15352 on 10-01-2002 Results f~l".11 rlwhn-11 a -.

1.S A-M~.

IJSE d-1USE T o 30 d-T o 30 T o 50 d-T o 50 I O 219 0 170 0 -11709 0 -90.06 C 2 C 2.19 0 156 -14 -103.49 136 -71M83 1825 3 0 219 0 163 -7 -91.96 2513 -15 27.92 (12 PC 0)

Z; Vq

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Curve Legend I - 20----- 3-Data Set(s) Plotted Curve Plant Capsule lMaterial Ori. Heatl I TF3 UNIRR HEAT AFD ZONE SA533BI M-1004-2 2 1TF3 !-97 HEAT AFFD ZONE SA533B1 M-1004-2 3 1 J-263 HEAT AFTD ZONE SA533BI lF3 U1-1004-2 Figure 5-10 Charpy V-Notch Impact Energy vs. Temperature for Waterford Unit 3 Reactor Vessel Heat Affected Zone Material Testing of Specimens from Capsule 263° March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-27 WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-27 HEAT AFFECTED ZONE CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 15:4212 on 10-01-2002 Results -

Curve Fluence USE d-USE To LE5 d-To LE35 I 0 8813 0 -a.55 0 2 0 7806 -1007 -7224 173 3 0 7519 -1294 -657 3298 MI rE

-300 -200 -100 0 100 200 300 400 600 600 Temperature in Degrees F Curve Legend I - 20---- 30 Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat#

I m UNIER HEAT AFFD ZONE SA533BI M-HD4-2 2 1M3 11-T7 HEAT AFFD ZONE SA533BI M-1004-2 3 11 11-63 HEAT AMD ZONE SA533BI M-1004-2 Figure 5-11 Charpy V-Notch Lateral Expansion vs. Temperature for Waterford Unit 3 Reactor Vessel Heat Affected Zone Material Testing of Specimens from Capsule 2630 March 2003 WCAP-16002 Revision 0

5-28 WESTINGHOUSE NON-PROPRIETARY CLASS 3 HEAT AFFECTED ZONE CVGRAPH 41 Hyperbolic Tangent Curve Printed at 15:4752 on 10 01-2W2 Results Curve Fluence T 0 SOX Shear d-T o 50z Shear I 0 -531 0 2 0 -37.5 17.1 3 0 -543 IB7 a)

C,)

5H a,

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Curve Lgend I - 20-----

Data Setqs) Plotted Curve Plant Camsule Material flii "eaO I TM UNIRR HEAT AFFD ZONE SA533BI M-1004-2 2 F TI-97 HEAT AFFID ZONE SA533B1 M-1004-2 3 1M3 *FZ63 HEAT AFFD ZONE SA533BI M-1004-2 Figure 5-12 Charpy V-Notch Percent Shear vs. Temperature for Waterford Unit 3 Reactor Vessel Heat Affected Zone Material Testing of Specimens from Capsule 263° March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-29 WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-29

1. 2. 3. 4. 5.

25E, -40 0 F 23D, -30 0 F 25J, -100 F 246, 00 F 215, 25 0 F

6. 7. 8. 9. 10.

23E, 500 F 24U, 750 F 22U, 1250 F 232, 1600 F 22Y, 2000 F

13. 14. 15.

11. 12.

243, 225 0F 24M, 350 0F Figure 5-13 Charpy Impact Specimen Fracture Surfaces for Waterford Unit 3 Reactor Vessel Lower Shell Plate M-1004-2 (Transverse Orientation)

Testing of Specimens from Capsule 263° March 2003 WCAP-I 6002 Revision 0

5-30 WESTINGHOUSE NON-PROPRIETARY CLASS 3

16. 17. 18. 19. 20.

A47, -30F A4E, 500 F A46, 125 0 F A3L, 1750 F A4C, 2000 F

21. 22. 23. 24. 25.

A3P, 2400 F A4A, 2750 F A41, 3200 F A43, 3500 F A4K, 375-F

28. 29. 30.

26. 27.

A3E, 425-F A3Y, 460 0F Figure 5-14 Charpy Impact Specimen Fracture Surfaces for HSST Plate OlMY Correlation Monitor Material (Longitudinal Orientation)

Testing of Specimens from Capsule 263° March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-31 WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-31

31. 32. 33. 34. 35.

333, -175-F 332, -1250 F 363, -750 F 34B, -50 0 F 35Y, -250 F

36. 37. 38. 39. 40.

361, 0 0F 34K, 25 0 F 33D, 50 0 F 33U, 75 0 F 365, 100 0 F

43. 44. 45.

41. 42.

37A, 150 0F 35L, 200 0F Figure 5-15 Charpy Impact Specimen Fracture Surfaces for Waterford Unit 3 Reactor Vessel Weld Metal Specimens Testing of Specimens from Capsule 263° March 2003 WCAP-1 6002 Revision 0

5-32 WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-32 WESTINGHOUSE NON-PROPRIETARY CLASS 3

46. 47. 48. 49. 50.

41P, -1750 F 41D, -1250 F 43E, -750 F 436, -250 F 42T, 0F

51. 52. 53. 54. 55.

41U, 25 0 F 45B, 50 0 F 471, 750 F 46L, 110F 473, 150 0 F

58. 59. 60.

56. 57. 4 446, 2250 F 44A, 3250 F Figure 5-16 Charpy Impact Specimen Fracture Surfaces for Waterford Unit 3 Reactor Vessel Heat Affected Zone (HAZ)

Testing of Specimens from Capsule 2630 March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-33 WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-33 95 sLD Ultimate Tensile Strength 90-85-

80-0 U)

0) 75 -

to 70 I% Yield Strength 65 -

60 0 100 200 300 400 500 600 Temperature (0F)

UW263 E2 W263 -- UnirradI

- - Unirrad -4W97 e W97 I 80 70 - Reduction in Area 60 -

i 50-p40-

' 30-Total Elongatio a 20-Total Elongation 10 -

0 Ia 100 200 300 400 500 600 Temperature (°F)

-U-W263 - W263 *-Unirrad l A Unirrad -W97 - W97 Figure 5-17 Tensile Properties for Waterford Unit 3 Reactor Vessel Lower Shell Plate M-1004-2 (Transverse Orientation)

Testing of Specimens from Capsule 263° March 2003 WCAP-16002 Revision 0

5-34 WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-34 WESTINGHOUSE NON-PROPRIETARY CLASS 3 100 Ultimate Tensile Strength 95 -

90 -

u) 85 -

(u 80- Yield Strength (a

X 75-70 -

65 -

60 0 100 200 300 400 500 600 0

Temperature ( F)

-- W263 -B W263 Ai-Unirrad l A Unirrad -W97 - W97 80 DReduction inArea 70 -

60 -

Z 50-

. 40-0 30 -

20 20 - Tp Total Elongation 10 -

0 0 100 200 300 400 500 600 Temperature (OF)

-W263 -:1 W263

Unirrad lA Unirrad W97 e W97 Figure 5-18 Tensile Properties for Waterford Unit 3 Reactor Vessel Weld Metal Testing of Specimens from Capsule 2630 March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-35 WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-35 100 Ultimate Tensile Strength 95 -

90 -

° 85-cm 80-

.' 75- 0 2% Yield Strength u,

70 L_ le 65-60 0 100 200 300 400 500 600 0

Temperature ( F)

-W263 -EW263 Ai-Unirrad

-A- Unirrad - W97 - W97 80 -

70 - Reduction in Area 70---

60 -

ZZ! 50 -

_40 -

Total Elongation 20 - A 10 0 100 200 300 400 500 600 Temperature (0 F)

- W263 CB W263 - Unirrad lA Unirrad + W97 -& W97 Figure 5-19 Tensile Properties for Waterford Unit 3 Reactor Vessel Heat-Affected-Zone (HAZ)

Testing of Specimens ftom Capsule 2630 March 2003 WCAP-I 6002 Revision 0

5-36 WESTINGHOUSE NON-PROPRIETARY CLASS 33 5-36 WESTiNGHOUSE NON-PROPRIETARY CLASS J , ..:_,L- L4

- _== I , _4 Specimen 2J2 Tested at 75 0 F

62. r Specimen 2KK Tested at 250'F Specimen 2KL Tested at 550'F Figure 5-20 Fractured Tensile Specimens from Waterford Unit 3 Reactor Vessel Plate M-1004-2 (Transverse Orientation)

Testing of Specimens from Capsule 263° March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-37 WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-37

~

71, Specimen 3K3 Tested at 75 'F

. - -'- - 7 - --

1. %+ I !

Specimen 3JD Tested at 250'F Specimen 3J7 Tested at 5500 F Figure 5-21 Fractured Tensile Specimens from Waterford Unit 3 Reactor Vessel Weld Metal Testing of Specimens from Capsule 2630 March 2003 WCAP-16002 Revision 0

5-38 WESTINGHOUSE NON-PROPRIETARY CLASS 3 Specimen 4JB Tested at 75 0 F en 4J1 Tested at 250WF Specimen 4KA Tested at 550'F Figure 5-22 Fractured Tensile Specimens from Waterford Unit 3 Reactor Vessel Heat-Affected-Zone (HAZ)

Testing of Specimens from Capsule 2630 March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 5-39 STRESS-STRAIN CURVE WATERFORD UNIT 3 CAPSULE 263 100 90 80 70 o5 S 60

('5 w 50 Ff 40 30 2J2 75 F 20 10 0

0 005 01 015 02 025 03 STRAIN, INAN STRESS-STRAIN CURVE WATERFORD UNIT 3 CAPSULE 263 100 90 80 70 2 60 050 40 30 2KK 20 250 F 10 0

0 005 01 015 02 025 03 STRAIN, ININ STRESS-STRAIN CURVE WATERFORD UNIT 3 CAPSULE 263 100 90 80 70 ro 11 60 U) 50 w

Uf 40 30 2KL 550 F 20 10 0

0 05 01 015 02 025 03 STRAIN, IN/IN Figure 5-23 Engineering Stress-Strain Curves for Plate M-1004-2 Tensile Specimens 2J2, 2KK and 2KL (Transverse Orientation)

Testing of Specimens from Capsule 2630 March 2003 WCAP-I 6002 Revision 0

540 WESTINGHOUSE NON-PROPRIETARY CLASS 3 STRESS-STRAIN CURVE WATERFORD UNIT 3 CAPSULE 263 100 90 80

_ 70 ro S 60

°W w 50 400 3K3 30 75 F 20 -

10 -

0 0 0 05 01 015 0.2 025 03 STRAIN, INAN STRESS-STRAIN CURVE WATERFORD UNIT 3 CAPSULE 263 100 90 80 70

< 60 CD 50

40 30 20 10 0

0 005 01 015 02 025 03 STRAIN, INIIN STRESS-STRAIN CURVE WATERFORD UNIT 3 CAPSULE 263 100 90 80 70 60 50 1 40 3J7 30 550 F 20 10 0

005 01 015 02 025 03 STRAIN. INAN Figure 5-24 Engineering Stress-Strain Curves for Weld Metal Tensile Specimens 3K3, 3JD, and 3J7.

[Note: Specimen 3J7 broke outside the gage length.]

Testing of Specimens from Capsule 2630 March 2003 WCAP-1 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 541 STRESS-STRAIN CURVE WATERFORD UNIT 3 CAPSULE 263 100 90 80 70 60 50 40 30 20 10 0

0 005 01 015 02 025 03 STRAIN, INIIN STRESS-STRAIN CURVE WATERFORD UNIT 3 CAPSULE 263 100 90 80 70 CD

=~ 60 cO.

C,, .50 w

40 30 4J1 20 250F 10 0

0 005 01 015 02 025 03 STRAIN, INAN STRESS-STRAIN CURVE WATERFORD UNIT 3 CAPSULE 263 100 90 80

_ 70 2 60 10 oo50 E 40 4KA 30 550 F 20 10 0

0 005 0.1 015 02 0 25 03 STRAIN, INAN Figure 5-25 Engineering Stress-Strain Curves for Heat-Affected-Zone (HAZ) Material Tensile Specimens 4JB, 4J1 and 4KA. [Note: Specimen 4KA broke at the clip gage knife edge.]

Testing of Specimens from Capsule 2630 March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 6-1 6 RADIATION ANALYSIS AND NEUTRON DOSIMETRY

6.1 INTRODUCTION

Knowledge of the neutron environment within the reactor vessel and surveillance capsule geometry is required as an integral part of LWR reactor vessel surveillance programs for two reasons. First, the neutron environment (energy spectrum, flux, fluence) to which the test specimens were exposed must be known to interpret the neutron radiation induced material property changes observed in the test specimens. Second, a relationship must be established between the neutron environment at various positions within the reactor vessel and that experienced by the test specimens to relate the changes observed in the test specimens to the present and future condition of the reactor vessel. The first requirement is normally met by employing a combination of rigorous analytical techniques and measurements obtained with passive neutron flux monitors contained in each of the surveillance capsules. The second requirement is normally met by the derivation of information solely from analysis.

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 development of damage trend curves as well as for the implementation of trend curve data to assess vessel condition. It has also 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 reduce the uncertainties and increase the accuracy associated with damage trend curves when evaluating damage gradients through the reactor vessel wall.

One energy dependent damage function for data correlation is displacements per iron atom (dpa).

In order to provide the dpa values in the data base for future reference, ASTM Standard Practice E8531121 ,

"Analysis and Interpretation of Light-Water Reactor Surveillance Results," recommends reporting both displacements per iron atom (dpa) and neutron fluence (E > 1.0 MeV). The energy dependent dpa function to be used for this evaluation is specified in ASTM Standard Practice E693, "Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements per Atom." The application of the dpa parameter to the assessment of embrittlement gradients through the thickness of the reactor vessel wall is reflected in the through-wall fluence adjustment factor in Regulatory Guide 1.99, Revision 211], "Radiation Embrittlement of Reactor Vessel Materials."

This section describes a discrete ordinates S,, transport analysis performed for the Waterford Unit 3 reactor to determine the neutron radiation environment within the reactor pressure vessel and surveillance capsules.

In this analysis, fast neutron exposure parameters in terms of fast neutron fluence (E > 1.0 MeV) and iron atom displacements (dpa) were established on a plant and fuel cycle specific basis. An evaluation of the most recent dosimetry sensor set from Capsule W-263, withdrawn at the end of the eleventh plant operating cycle, is provided. In addition, to provide an up-to-date data base applicable to the Waterford Unit 3 reactor, the sensor set from the previously withdrawn capsule[131 (W-97) was re-analyzed using the current dosimetry evaluation methodology. These dosimetry updates are presented in Appendix E 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 48 Effective Full Power Years (EFPY).

Radiation Analysis and Neutron Dosimetry March 2003 WCAP-16002 Revision 0

6-2 WESTINGHOUSE NON-PROPRIETARY CLASS 3 All of the calculations and dosimetry evaluations described in this section and in Appendix E 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." 114 1 The specific calculational methods applied are also consistent with those described in WCAP-15557, "Qualification of the Westinghouse Pressure Vessel Neutron Fluence Evaluation Methodology."[ 15 1 6.2 DISCRETE ORDINATES ANALYSIS A plan view of the Waterford Unit 3 reactor geometry at the core midplane is shown in Figure 4-1. Six irradiation capsules attached to the reactor pressure vessel are included in the reactor design that constitutes the reactor vessel surveillance program. The capsules are located at azimuthal angles of 830, 970, 2630, 2770 (70 from the core cardinal axes), and 1040, 2840 (140 from the core cardinal axes) as shown in Figure 4-1. The capsule assemblies are centered on the core midplane, thus spanning the central portion of the active fuel zone.

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 core barrel 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.

The fast neutron exposure evaluations for the Waterford Unit 3 reactor vessel and surveillance capsules were based on a series of fuel cycle specific forward transport calculations that were combined using the following three-dimensional flux synthesis technique:

0(r,0,z) = q(r,0)x0 (rz) 0(r) wheret(r,O,z) is the synthesized three-dimensional neutron flux distribution, 4(rO) is the transport solution in r,0 geometry, 4(r,z) is the two-dimensional solution for a cylindrical reactor model using the actual axial core power distribution, and ¢(r) is the one-dimensional solution for a cylindrical reactor model using the same source per unit height as that used in the r,0 two-dimensional calculation. This synthesis procedure was carried out for each operating cycle at Waterford Unit 3.

For the Waterford Unit 3 transport calculations, the r,0 model depicted in Figure 6-1 was utilized since the reactor is octant symmetric (with the exception of the surveillance capsules). This r,0 model includes the core, the reactor internals and core barrel, explicit representations of the surveillance capsules at 70 and 140, the pressure vessel cladding and vessel wall, the insulation external to the pressure vessel, and the primary biological shield wall. This r,0 model was utilized in the synthesis procedure to perform the surveillance capsule dosimetry evaluations and subsequent comparisons with calculated results, in addition to calculating the maximum neutron exposure levels at the pressure vessel wall. Note that a variation of this model in which the material composition of the surveillance capsules were redefined as water was utilized to determine the neutron exposure of the pressure vessel wall at the 15° degree azimuth. This accounts for the fact that the peak neutron exposure of the vessel at the 15° azimuth occurs in octants of the core that do not have a 140 surveillance capsule. In developing this analytical model, nominal design dimensions were Radiation Analysis and Neutron Dosimetry March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 6-3 WESTINGHOUSE NON-PROPRIETARY CLASS 3 6-3 employed for the various structural components with two exceptions. Specifically, the radius to the center of the surveillance capsule holder as well as the pressure vessel inner radius (PVIR) were taken from the as-built drawings for the Waterford Unit 3 reactor. This was done to account for key differences between the nominal versus as-built dimensions.

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 with a 107% RCS flow rate. The coolant densities were treated on a fuel cycle specific basis. The reactor core itself was treated as a homogeneous mixture of fuel, cladding, water, and miscellaneous core structures such as fuel assembly grids, guide tubes, et cetera. The geometric mesh description of the r,0 reactor model consisted of 153 radial by 82 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 r,0 calculations was set at a value of 0.001.

The r,z model used for the Waterford Unit 3 calculations (see Figure 6-2) extended 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 r,0 model, nominal design dimensions (except for the PVIR as-built dimension) 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 girth ribs located between the core shroud and core barrel regions were also explicitly included in the model. The r,z geometric mesh description of the reactor model consisted of 151 radial by 94 axial intervals. As in the case of the r,0 calculations, mesh sizes were chosen to assure that proper convergence of the inner iterations was achieved on a pointwise basis. The pointwise inner iteration flux convergence criterion utilized in the r,z calculations was also set at a value of 0.001.

The one-dimensional radial model used in the synthesis procedure consisted of the same 151 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 Waterford Unit 3 fuel cycle designs. The data extracted from the design calculations represented cycle dependent fuel assembly enrichments, bumups, axial power distributions and pin-by-pin power distributions for assemblies having a face or part of a face on the periphery of the core. 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 bumup 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[16] and the BUGLE-96 cross-section library.["7 1 The BUGLE-96 library provides a 67 group coupled neutron-gamma ray cross-section data set produced specifically for light water reactor Radiation Analysis and Neutron Dosimetry March 2003 WCAP-16002 Revision 0

6-4 WESTINGHOUSE NON-PROPRIETARY CLASS 3 (LWR) applications. In these analyses, anisotropic scattering was treated with a P5 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 6-10. 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 (70 and 140). 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.

In Table 6-2, cycle specific maximum integrated neutron exposures, expressed in terms of both neutron fluence (E > 1.0 MeV) and dpa, are given at the pressure vessel clad base metal interface at azimuthal angles of 00, 150, 300, and 450 relative to the core major axis for the middle to lower shell circumferential weld located approximately 11.4 inches below the core midplane. Tables 6-3 and 6-4 contain comparable results for the middle shell plates and the lower shell plates, respectively. Due to the symmetry in the reactor geometry, each of the middle and lower shell plates spanning 120° sectors experience neutron exposure levels characteristic of the 0°, 150, 300, and 450 azimuths.

In Tables 6-5 and 6-6, cycle specific maximum integrated neutron exposures, expressed in terms of both neutron fluence (E > 1.0 MeV) and dpa, are given at the pressure vessel clad base metal interface at the azimuthal locations of longitudinal welds located in the middle and lower shell courses, respectively. All of the data provided in Tables 6-2 through 6-6 were taken at the axial location of the maximum exposure experienced by each material based on the results of the three-dimensional synthesized neutron exposure evaluations.

Both calculated fluence (E > 1.0 MeV) and dpa data are provided in Tables 6-1 through 6-6. These data tabulations include both plant and fuel cycle specific calculated neutron exposures at the end of the eleventh operating fuel cycle (reactor power of 3390 MWt) as well as projections for the current operating fuel cycle, i.e., cycle twelve (reactor power of 3441 MWt), cycle thirteen (reactor power of 3441 MWt), and cycle fourteen (reactor power of 3716 MWt) and beyond to 32 and 48 effective full power years (EFPY). The projections were based on the assumption that the reactor power level and spatial power distribution from fuel cycle twelve was representative of cycle thirteen and the assumed cycle lengths were 524 EFPD and 490 EFPD, respectively. Projections for cycle fourteen and beyond were based on the assumption that future operation would continue to make use of low leakage fuel management and that a representative equilibrium spatial power distribution from the ongoing major uprate program would be typical of future operating cycles. Furthermore, to provide a degree of conservatism in the cycle fourteen and beyond projected fluence, a positive bias of 5% was applied to the neutron source in all fuel assemblies located on the core periphery.

Radial gradient information applicable to fast (E > 1.0 MeV) neutron fluence and dpa are given in Tables 6-7 and 6-8, respectively. The data, based on the cumulative integrated exposures from cycles one through twelve, 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 6-7 and 6-8. The calculated fast neutron Radiation Analysis and Neutron Dosimetry March 2003 WCAP-16002 Revision 0

WESTINGHOUSE W.TNGOS NO.RPITR NON-PROPRIETARY CLASS LS 3 6-5 exposures for the two surveillance capsules withdrawn from the Waterford Unit 3 reactor are provided in Table 6-9. These assigned neutron exposure levels are based on the plant and fuel cycle specific neutron transport calculations performed for the Waterford Unit 3 reactor.

Updated lead factors for the Waterford Unit 3 surveillance capsules are provided in Table 6-10. 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 6-10, the lead factors for capsules that have been withdrawn from the reactor (W-97 and W-263) 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 (W-83, W-104, W-277, and W-284), the lead factors correspond to the calculated fluence values at the end of cycle twelve, the current operating fuel cycle for Waterford Unit 3.

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 E.

The direct comparison of measured versus calculated fast neutron threshold reaction rates for the sensors from Capsule W-263, that was withdrawn from Waterford Unit 3 at the end of the eleventh fuel cycle, is summarized below.

Reaction Rat es (rps/atom) M/C Reaction Measured Calculated Ratio 63 Cu(n,a)6 0 Co (Cd) 4.95E-17 4.86E-17 1.02 54 Fe(n,p) 54Mn 4.80E-15 4.33E-15 1.11 58Ni(n,p) 'Co (Cd) 6.65E-15 5.66E-15 1.17 Average: 1.10

% Standard Deviation: 7.1 The measured-to-calculated (MIC) reaction rate ratios for the Capsule W-263 threshold reactions range from 1.02 to 1.17, and the average M/C ratio is 1.10 +/- 7.1% (Ia). This direct comparison falls well within the +/- 20% criterion specified in Regulatory Guide 1.190114'; furthermore, it is consistent with the full set of comparisons given in Appendix E for all measured dosimetry removed to date from the Waterford Unit 3 reactor. As a result, these comparisons validate the current analytical results described in Section 6.2 and are deemed applicable for Waterford Unit 3.

6.4 CALCULATIONAL UNCERTAINTIES The uncertainty associated with the calculated neutron exposure of the Waterford Unit 3 surveillance capsule and reactor pressure vessel is based on the recommended approach provided in Regulatory Radiation Analysis and Neutron Dosimetry March 2003 WCAP-16002 Revision 0

6-6 WESTINGHOUSE NON-PROPRIETARY CLASS 3 6-6 WESTINGHOUSE NON-PROPRIETARY CLASS 3 Guide 1.190(141. 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 Waterford Unit 3 surveillance program.

The first phase of the methods qualification (PCA comparisons) addressed the adequacy of basic transport calculation and dosimetry evaluation techniques and associated cross-sections. This phase, however, did not test the accuracy of commercial core neutron source calculations nor did it address uncertainties in operational or geometric variables that impact power reactor calculations. The second phase of the qualification (H. B. Robinson comparisons) addressed uncertainties in these additional areas that are primarily methods related and would tend to apply generically to all fast neutron exposure evaluations. The third phase of the qualification (analytical sensitivity study) identified the potential uncertainties introduced into the overall evaluation due to calculational methods approximations as well as to a lack of knowledge relative to various plant specific input parameters. The overall calculational uncertainty applicable to the Waterford Unit 3 analysis was established from results of these three phases of the methods qualification.

The fourth phase of the uncertainty assessment (comparisons with Waterford Unit 3 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 Waterford Unit 3 analytical model based on the measured plant dosimetry is completely described in Appendix E.

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 15.

Capsule Vessel IR PCA Comparisons 3% 3%

H. B. Robinson Comparisons 3% 3%

Analytical Sensitivity Studies 10% 11%

Additional Uncertainty for Factors not Explicitly Evaluated 5% 5%

Net Calculational Uncertainty 12% 13%

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

Therefore, the resultant uncertainty was random and no systematic bias was applied to the analytical results.

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 6-7 The plant specific measurement comparisons described in Appendix E support these uncertainty assessments for Waterford Unit 3.

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6-8 WESTINGHOUSE NON-PROPRIETARY CLASS 3 6-8 WESTINGHOUSE NON-PROPRIETARY CLASS 3 200 - 1\

160

?V 120 ix 80 40 I I I i I I I i 0 50 100 150 200 250 300 R AxIs (cm)

Figure 6-1 Waterford Unit 3 r,O Reactor Geometry at the Core Midplane Radiation Analysis and Neutron Dosimetry March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 6-9 WESTINGHOUSE NON-PROPRIETARY CLASS 3 6-9 225 -

175-125 -

75-25-E

£0 r-:

-125-

-175-

_v?5

_-as, I I I I I I I I I 2 I 1 0 50 100 150 200 250 300 R Axis (cm)

Figure 6-2 Waterford Unit 3 rz Reactor Geometry Radiation Analysis and Neutron Dosimetry March 2003 WCAP-16002 Revision 0

6-10 WESTINGHOUSE NON-PROPRIETARY CLASS 3 Table 6-1 Calculated Neutron Exposure Rates and Integrated Exposures Cumulative Cumulative Neutron Flux (E > 1.0 MeV)

Cycle Irradiation Irradiation [n/c -s]

Length Time Time Cycle [EFPS] [EFPS] [EFPY] 70 140 1 3.28E+07 3.28E+07 1.04 5.62E+10 3.9713+10 2 3.18E+07 6.46E+07 2.05 4.37E+10 3.07E+10 3 3.6413+07 1.01E+08 3.20 4.38E+10 2.99E+10 4 3.82E+07 1.39E+08 4.41 3.98E+10 2.79E+10 5 3.93E+07 1.79E+08 5.66 3.98E+10 2.78E+10 6 4.09E+07 2.19E+08 6.95 3.9013+10 2.33E+10 7 4.2613+07 2.62E+08 8.30 2.13E+10 1.70E+10 8 4.27E+07 3.05E+08 9.66 2.60E+10 1.83E+10 9 4.55E+07 3.50E+08 11.10 2.50E+10 1.85E+10 10 4.43E+07 3.95E+08 12.50 2.38E+10 1.80E+10 11 4.19E+07 4.36E+08 13.83 1.88E+10 1.40E+10 12 (Pjt) 4.53E+07 4.8213+08 15.27 2.38E+10 1.72E+10 13 (Pjt) 4.2313+07 5.24E+08 16.61 2.38E+10 1.72E+10 Future 2.21 E+08 1.01 E+09 32.00 2.73E+10 2.04E+10 Future 3.79E+08 1.51E+09 48.00 2.73E+10 2.04E+10 Cumulative Cumulative Neutron Fluence (E > 1.0 MeV)

Cycle Irradiation Irradiation [n/cm r2 Length Time Time Cycle [EFPS] [EFPS] [EFPYJ 70 140 I 3.28E+07 3.2813+07 1.04 1.84E+18 1.30E+18 2 3.18E+07 6.46E+07 2.05 3.231E+18 2.28E+18 3 3.64E+07 1.011E+08 . 3.20 4.83E+18 3.37E+18 4 3.82E+07 1.3913+08 4.41 6.35E+18 4.43E+18 5 3.93E+07 1.79E+08 5.66 7.9113+18 5.52E+ 18 6 4.09E+07 2.19E+08 6.95 9.5113+18 6.48E+18 7 4.26E+07 2.62E+08 8.30 1.04E+19 7.2013+18 8 4.27E+07 3.05E+08 9.66 1.1513+19 7.98E+18 9 4.55E+07 3.50E+08 11.10 1.27E+19 8.8313+18 10 4.43E+07 3.95E+08 12.50 1.37E+19 9.6213+18 11 4.19E+07 4.36E+08 13.83 1.45E+19 1.02E+19 12 (Pjt) 4.53E+07 4.82E+08 15.27 1.56E+19 1.1013+19 13 (Pjt) 4.2313+07 5.24E+08 16.61 1.66E+19 1.17E+19 Future 2.21 E+08 1.011E+09 32.00 2.98E+19 2.16E+19 Future 3.7913+08 1.511E+09 48.00 4.36E+19 3.19E+19 Note: Neutron exposure values reported for the surveillance capsules are centered at the core midplane.

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 6-11 WESTINGHOUSE NON-PROPRIETARY CLASS 3 6-11 Table 6-1 cont'd Calculated Neutron Exposure Rates and Integrated Exposures At the Surveillance Capsule Center Cumulative Cumulative Displacement Rate Cycle Irradiation Irradiation [dpa/s]

Length Time Time Cycle [EFPS] [EFPS] [EFPY] 70 140 3.28E+07 3.28E+07 1.04 8.20E-11 5.82E-1 1 2 3.18E+07 6.46E+07 2.05 6.38E-11 4.51 E-l 1 3 3.64E+07 I.O1E+08 3.20 6.40E-1I 4.39E-1 1 4 3.82E+07 1.39E+08 4.41 5.81E-11 4.10E-I I 5 3.93E+07 1.79E+08 5.66 5.82E-1I 4.09E-1 1 6 4.09E+07 2.19E+08 6.95 5.70E-1 I 3.43E-I I 7 4.26E+07 2.62E+08 8.30 3.12E-11 2.50E-I I 8 4.27E+07 3.05E+08 9.66 3.81E-1I 2.70E-I I 9 4.55E+07 3.50E+08 11.10 3.66E-11 2.72E-I I 10 4.43E+07 3.95E+08 12.50 3.48E-11 2.65E-1 I II 4.19E+07 4.36E+08 13.83 2.77E-11 2.05E-I I 12 (Pjt) 4.53E+07 4.82E+08 15.27 3.48E-11 2.54E-1 l 13 (Pjt) 4.23E+07 5.24E+08 16.61 3.48E-11 2.54E- 11 Future 2.2 1E+08 1.011E+09 32.00 3.99E-11 3.01 E-l l Future 3.79E+08 I.51E+09 48.00 3.99E-1I 3.01E-1l Cumulative Cumulative Displacements Cycle Irradiation Irradiation [d pa Length Time Time Cycle [EFPS] [EFPS] [EFPY] 70 140 1 3.28E+07 3.28E+07 1.04 2.69E-03 1.91 E-03 2 3.18E+07 6.46E+07 2.05 4.72E-03 3.34E-03 3 3.64E+07 1.01 E+08 3.20 7.05E-03 4.94E-03 4 3.82E+07 1.39E+08 4.41 9.27E-03 6.51E-03 5 3.93E+07 1.79E+08 5.66 1.16E-02 8.12E-03 6 4.09E+07 2.19E+08 6.95 1.39E-02 9.52E-03 7 4.26E+07 2.62E+08 8.30 1.52E-02 1.06E-02 8 4.27E+07 3.05E+08 9.66 1.69E-02 1.17E-02 9 4.55E+07 3.50E+08 11.10 1.85E-02 1.30E-02 10 4.43E+07 3.95E+08 12.50 2.01 E-02 1.42E-02 11 4.19E+07 4.36E+08 13.83 2.12E-02 1.50E-02 12 (Pjt) 4.53E+07 4.82E+08 15.27 2.28E-02 1.62E-02 13 (Pjt) 4.23E+07 5.24E+08 16.61 2.43E-02 1.72E-02 Future 2.21E+08 I.01 E+09 32.00 4.37E-02 3.18E-02 Future 3.79E+08 1.51E+09 48.00 6.38E-02 4.70E-02 Note: Neutron exposure values reported for the surveillance capsules are centered at the core midplane.

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6-12 WESTINGHOUSE NON-PROPRIETARY O-RPITR CLASS LS 3 6-12WSIGOS Table 6-2 Calculated Neutron Exposure of the Middle Shell to Lower Shell Circumferential Weld (101-171)

Cumulative Cumulative Neutron Fluence (E > 1.0 MeV)

Cycle Irradiation Irradiation [n/cm 2J Length Time Time Cycle [EFPS] [EFPS] [EFPY] 00 150 300 450 1

2 3.28E+07 3.28E+07 1.04 1.48E+18 9.23E+17 8.05E+17 6.35E+17 3 3.18E+07 6.4613+07 2.05 2.67E+18 1.63E+18 1.47E+18 1.12E+18 4 3.64E+07 1.O1E+08 3.20 4.05E+18 2.42E+18 2.12E+18 1.61E+18 5 3.82E+07 1.39E+08 4.41 5.36E+18 3.211E+18 2.82E+18 2.15E+18 6 3.93E+07 1.79E+08 5.66 6.72E+18 4.01E+18 3.52E+18 2.69E+18 7 4.09E+07 2.19E+08 6.95 8.1413+18 4.68E1+18 4.00E+18 3.14E+18 8 4.26E+07 2.62E+08 8.30 8.87E+18 5.21E+18 4.56E+18 3.58E+18 9 4.27E+07 3.05E+08 9.66 9.80E+18 5.78E+18 5.01E+18 3.99E+18 10 4.5513+07 3.50E+08 11.10 1.07E+19 6.39E+18 5.49E+18 4.36E+18 11 4.43E+07 3.95E+08 12.50 1.16E+19 6.97E+18 6.05E+18 4.84E+18 12 (Pjt) 4.19E+07 4.36E+08 13.83 1.2213+19 7.40E+18 6.45E+18 5.23E+18 4.53E+07 4.82E+08 15.27 1.311E+19 7.96E+18 6.93E+18 5.65E+18 13 (Pjt) 4.23E+07 5.24E+08 16.61 1.40E+19 8.49E+18 7.39E+18 6.03E+ 18 Future 2.2 1E+08 1.0IE+09 32.00 2.47E+19 1.57E+19 1.41E+19 1.17E+19 Future 3.79E+08 1.51 E+09 48.00 3.59E+19 2.32E+19 2.12E+19 1.75E+19 Cumulative Cumulative Iron Atom Displacements Cycle Irradiation Irradiation [dpa]

Length Time Time Cycle [EFPS] [EFPS] [EFPY] 00 150 300 450 1

2 3.2813+07 3.28E+07 1.04 2.25E-03 1.42E-03 1.23E-03 9.77E-04 3 3.1813+07 6.46E+07 2.05 4.06E-03 2.51 E-03 2.24E-03 1.72E-03 4 3.64E+07 1.0113+08 3.20 6.1613-03 3.73E-03 3.24E-03 2.48E-03 5 3.82E+07 1.39E+08 4.41 8.17E-03 4.94E-03 4.32E-03 3.32E-03 6 3.93E+07 1.79E+08 5.66 1.0213-02 6.17E-03 5.38E-03 4.15E-03 7 4.0913+07 2.19E+08 6.95 1.2413-02 7.20E-03 6.12E-03 4.8313-03 8 4.26E+07 2.62E+08 8.30 1.35E-02 8.0313-03 6.97E-03 5.5213-03 9 4.27E+07 3.05E+08 9.66 1.49E-02 8.9013-03 7.68E-03 6.151E-03 10 4.5513+07 3.5013+08 11.10 1.6313-02 9.8413-03 8.411E-03 6.72E-03 11 4.43E+07 3.95E+08 12.50 1.7613-02 1.07E-02 9.26E-03 7.46E-03 12 (Pjt) 4.19E+07 4.36E+08 13.83 1.86E-02 1.14E-02 9.88E-03 8.06E-03 4.53E+07 4.82E+08 15.27 2.00E-02 1.23E-02 1.06E-02 8.70E-03 13 (Pjt) 4.23E+07 5.24E+08 16.61 2.13E-02 1.3113-02 1.13E-02 9.301E-03 Future 2.21 E+08 1.011E+09 32.00 3.77E-02 2.42E-02 2.17E-02 1.80E-02 Future 3.79E+08 1.51 E+09 48.00 5.48E-02 3.58E-02 3.24E-02 2.70E-02 Radiation Analysis and Neutron Dosimetry March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 6-13 6-13 WESTINGHOUSE NON-PROPRIETARY CLASS 3 Table 6-3 Calculated Neutron Exposure of the Middle Shell Plates (M-1003-1, M-1003-2, and M-1003-3)

Cumulative Cumulative Neutron Fluence (E > 1.0 MeV)

Cycle Irradiation Irradiation [n/c m2 _

Length Time Time Cycle [EFPS] [EFPS] [EFPY] 00 150 300 450 1 3.28E+07 3.28E+07 1.04 1.48E,+18 9.25E+17 8.07E+17 6.37E+17 2 3.18E+07 6.46E+07 2.05 2.68E+18 1.64E+18 1.47E+18 1.12E+18 3 3.64E+07 1.OIE+08 3.20 4.06E+18 2.43E+18 2.12E+18 1.611E+18 4 3.82E+07 1.39E+08 4.41 5.38E+18 3.22E+18 2.83E+18 2.16E+18 5 3.93E+07 1.79E+08 5.66 6.75E+18 4.02E+18 3.53E+18 2.70E+18 6 4.09E+07 2.19E+08 6.95 8.19E+18 4.7013+18 4.02E+18 3.15E+18 7 4.26E+07 2.62E+08 8.30 8.92E+18 5.24E+18 4.58E+18 3.60E+18 8 4.27E+07 3.0513+08 9.66 9.85E+18 5.81E+18 5.04E+18 4.011E+18 9 4.55E+07 3.SOE+08 11.10 1.08E+19 6.42E+ 18 5.52E+18 4.38E+18 10 4.43E+07 3.95E+08 12.50 1.16E+19 7.OOE+18 6.08E+18 4.86E+18 1I 4.19E+07 4.36E+08 13.83 1.23E+19 7.43E+18 6.48E+18 5.25E+18 12 (Pjt) 4.53E+07 4.82E+08 15.27 1.32E+19 7.99E1+18 6.96E+18 5.66E+18 13 (Pjt) 4.23E+07 5.24E+08 16.61 1.40E+19 8.52E1+18 7.40E+18 6.05E+18 Future 2.211E+08 1.01 E+09 32.00 2.48E+19 1.588E+19 1.42E+19 1.17E+19 Future 3.79E+08 1.511E+09 48.00 3.60E+19 2.33E+19 2.12E1+19 1.75E+19 Cumulative Cumulative Iron Atom Displacements Cycle Irradiation Irradiation Ldpa_

Length Time Time Cycle [EFPS] [EFPS] [EFPY] 00 150 300 450 1 3.28E+07 3.28E+07 1.04 2.26E-03 1.42E-03 1.23E-03 9.79E-04 2 3.18E+07 6.46E+07 2.05 4.07E-03 2.52E-03 2.25E-03 1.73E-03 3 3.64E+07 1.011E+08 3.20 6.18E-03 3.74E-03 3.25E-03 2.49E-03 4 3.82E+07 1.39E+08 4.41 8.2013-03 4.95E-03 4.33E-03 3.33E-03 5 3.93E+07 1.7913+08 5.66 1.03E-02 6.19E-03 5.4013-03 4.17E-03 6 4.09E+07 2.1913+08 6.95 1.25E-02 7.24E-03 6.151E-03 4.86E-03 7 4.26E+07 2.62E+08 8.30 1.36E-02 8.0713-03 7.01 E-03 5.54E-03 8 4.27E+07 3.05E+08 9.66 1.50E-02 8.94E-03 7.71 E-03 6.18E-03 9 4.551E+07 3.50E+08 11.10 1.64E-02 9.88E-03 8.4413-03 6.75E-03 10 4.4313+07 3.95E+08 12.50 1.77E-02 1.08E-02 9.3 OE-03 7.4913-03 11 4.19E+07 4.36E+08 13.83 1.87E-02 1.1 4E-02 9.92E-03 8.0913-03 12 (Pjt) 4.53E+07 4.82E+08 15.27 2.0113-02 1.23E-02 1.0713-02 8.73E-03 13 (Pjt) 4.231E+07 5.24E+08 16.61 2.13E-02 1.31 E-02 1.131E-02 9.32E-03 Future 2.21 E+08 1.011E+09 32.00 3.78E-02 2.431E-02 2.1713-02 1.8013-02 Future 3.79E+08 1.5 1E+09 48.00 5.50E-02 3.59E-02 3.2513-02 2.701-02 Note: The maximum exposure after cycle one occurs an axial elevation of 8.3 inches below the midplane of the active fuel. The maximum exposure for all other times occurs at an axial elevation 16 8 inches above the midplane of the active fuel.

Radiation Analysis and Neutron Dosimetry March 2003 WCAP-16002 Revision 0

6-14 WESTINGHOUSE NON-PROPRIETARY CLASS 3 6-14 WEST[NGHOUSE NON-PROPRIETARY CLASS 3 Table 6-4 Calculated Neutron Exposure of the Lower Shell Plates (M-1004-1, M-1004-2, and M-1004-3)

Cumulative Cumulative Neutron Fluence (E > 1.0 MeV)

Cycle Irradiation Irradiation [n Length Time Time Cycle [EFPS] [EFPS] [EFPY] 00 150 300 450 I 3.28E+07 3.28E+07 1.04 1.48E+18 9.23E+/-+17 8.05E+17 6.35E+17 2 3.18E+07 6.46E+07 2.05 2.67E+18 1.63E+18 1.47E+18 1.12E+18 3 3.64E+07 1.01E+08 3.20 4.05E+18 2.42E+18 2.12E+18 1.61E+18 4 3.82E+07 1.39E+08 4.41 5.36E+18 3.21E+18 2.82E+18 2.15E+18 5 3.93E+07 1.79E+08 5.66 6.72E+18 4.01E+18 3.52E+18 2.69E+18 6 4.09E+07 2.19E+08 6.95 8.14E+18 4.68E+18 4.OOE+18 3.14E+18 7 4.26E+07 2.62E+08 8.30 8.87E+18 5.21E+18 4.56E+18 3.58E+18 8 4.27E+07 3.05E+08 9.66 9.80E+18 5.78E+18 5.01E+18 3.99E+18 9 4.55E+07 3.50E+08 11.10 1.07E+19 6.39E+18 5.49E+18 4.36E+18 10 4.43E+07 3.95E+08 12.50 1.16E+19 6.97E+18 6.05E+18 4.84E+18 11 4.19E+07 4.36E+08 13.83 1.22E+19 7.40E+18 6.45E+18 5.23E+18 12 (Pjt) 4.53E+07 4.82E+08 15.27 1.311E+19 7.96E+18 6.93E+18 5.65E+18 13 (Pjt) 4.23E+07 5.24E+08 16.61 1.40E+19 8.49E+18 7.39E+18 6.03E+18 Future 2.21E+08 1.01 E+09 32.00 2.47E+19 1.57E+19 1.41E+19 1.17E+19 Future 3.79E+08 1.511E+09 48.00 3.59E+19 2.32E+19 2.12E+19 1.75E+19 Cumulative Cumulative Iron Atom Displacements Cycle Irradiation Irradiation [d a]

Length Time Time Cycle [EFPS] [EFPS] [EFPY] 0O 150 300 450 I 3.28E+07 3.28E+07 1.04 2.25E-03 1.42E-03 1.23E-03 9.77E-04 2 3.18E+07 6.46E+07 2.05 4.06E-03 2.51 E-03 2.24E-03 1.72E-03 3 3.64E+07 1.011E+08 3.20 6.16E-03 3.73E-03 3.24E-03 2.48E-03 4 3.82E+07 1.39E+08 4.41 8.17E-03 4.94E-03 4.32E-03 3.32E-03 5 3.93E+07 1.79E+08 5.66 1.02E-02 6.17E-03 5.38E-03 4.15E-03 6 4.09E+07 2.19E+08 6.95 1.24E-02 7.20E-03 6.12E-03 4.83E-03 7 4.26E+07 2.62E+08 8.30 1.35E-02 8.03E-03 6.97E-03 5.52E-03 8 4.27E+07 3.05E+08 9.66 1.49E-02 8.90E-03 7.68E-03 6.15E-03 9 4.55E+07 3.50E+08 11.10 1.63E-02 9.84E-03 8.41 E-03 6.72E-03 10 4.43E+07 3.95E+08 12.50 1.76E-02 1.07E-02 9.26E-03 7.46E-03 11 4.19E+07 4.36E+08 13.83 1.86E-02 1.14E-02 9.88E-03 8.06E-03 12 (Pjt) 4.53E+07 4.82E+08 15.27 2.OOE-02 1.23E-02 1.06E-02 8.70E-03 13 (Pjt) 4.23E+07 5.24E+08 16.61 2.13E-02 1.31 E-02 1.13E-02 9.30E-03 Future 2.21 E+08 1.01E+09 32.00 3.77E-02 2.42E-02 2.17E-02 1.80E-02 Future 3.79E+08 1.51 E+09 48.00 5.48E-02 3.58E-02 3.24E-02 2.70E-02 Note: The maximum exposure occurs at the axial elevation of the circumferential weld, i.e., 11.4 inches below the midplane of the active fuel.

Radiation Analysis and Neutron Dosimetry March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 6-15 WESTINGHOUSE NON-PROPRIETARY CLASS 3 6-15 Table 6-5 Calculated Neutron Exposure of the Middle Shell Longitudinal Welds Cumulative Cumulative Neutron Fluence (E > 1.0 MeV)

Cycle Irradiation Irradiation [nl/cm 2]

Length Time Time Weld Weld Weld Cycle [EFPS] [EFPS] [EFPY] 101-124A 101-124B 101-124C I 3.28E+07 3.28E+07 1.04 1.48E+18 8.07E+17 8.07E+17 2 3.18E+07 6.46E+07 2.05 2.68E+18 1.47E+18 1.47E+18 3 3.64E+07 1.0113+08 3.20 4.06E+18 2.12E1+18 2.12E+18 4 3.82E+07 1.3913+08 4.41 5.38E+18 2.83E+18 2.83E+18 5 3.93E+07 1.79E+08 5.66 6.7513+18 3.53E+18 3.53E+18 6 4.09E+07 2.19E+08 6.95 8.19E+18 4.02E1+18 4.02E+18 7 4.26E+07 2.62E+08 8.30 8.92E+18 4.58E+18 4.58E+18 8 4.2713+07 3.0513+08 9.66 9.85E+18 5.04E1+18 5.04E+18 9 4.55E+07 3.50E+08 11.10 1.08E+19 5.52E+18 5.52E+18 10 4.43E+07 3.95E+08 12.50 1.16E+19 6.08E+18 6.08E+18 11 4.19E+07 4.36E+08 13.83 1.23E+19 6.48E+18 6.48E+18 12 (Pjt) 4.53E+07 4.82E+08 15.27 1.32E+19 6.96E+18 6.96E+18 13 (Pjt) 4.23E+07 5.24E+08 16.61 1.4013+19 7.40E+18 7.40E+18 Future 2.21 E+08 1.0 IE+09 32.00 2.48E+19 1.42E+19 1.42E+19 Future 3.79E+08 1.5113+09 48.00 3.60E1+19 2.12E+19 2.12E+19 Cumulative Cumulative Iron Atom Displacements Cycle Irradiation Irradiation [dpa]

Length Time Time Weld Weld Weld Cycle [EFPS] [EFPS] [EFPY] 101-124A 101-124B 101-124C 1 3.28E+07 3.28E+07 1.04 2.26E-03 1.23E-03 1.23E-03 2 3.18E+07 6.4613+07 2.05 4.07E-03 2.25E-03 2.25E-03 3 3.64E+07 1.01E+08 3.20 6.18E-03 3.25E-03 3.25E-03 4 3.82E+07 1.39E+08 4.41 8.2013-03 4.33E-03 4.33E-03 5 3.93E+07 1.79E+08 5.66 1.0313-02 5.40E-03 5.40E-03 6 4.09E+07 2.19E+08 6.95 1.25E-02 6.15E-03 6.15E-03 7 4.26E+07 2.6213+08 8.30 1.36E-02 7.011E-03 7.01 E-03 8 4.27E+07 3.0513+08 9.66 1.50E-02 7.71 E-03 7.71 E-03 9 4.55E+07 3.5013+08 11.10 1.64E-02 8.44E-03 8.44E-03 10 4.4313+07 3.9513+08 12.50 1.7713-02 9.30E-03 9.30E-03 11 4.1913+07 4.36E+08 13.83 1.87E-02 9.92E-03 9.92E-03 12 (Pjt) 4.53E+07 4.82E+08 15.27 2.011E-02 1.07E-02 1.07E-02 13 (Pjt) 4.23E+07 5.24E+08 16.61 2.13E-02 1.13E-02 1.13E-02 Future 2.211E+08 1.01 E+09 32.00 3.78E-02 2.17E-02 2.17E-02 Future 3.79E+08 1.5 1E+09 48.00 5.50OE-02 3.25E-02 3.251-02 Note: The maximum exposure after cycle one occurs an axial elevation of 8.3 inches below the midplane of the active fuel. The maximum exposure for all other times occurs at an axial elevation 16 8 inches above the midplane of the active fuel.

Radiation Analysis and Neutron Dosimetry

March 2003 WCAP-16002 Revision 0

6-16 WESTINGHOUSE NON-PROPRIETARY CLASS 3 6-16 WESTINGHOUSE NON-PROPRIETARY CLASS 3 Table 6-6 Calculated Neutron Exposure of the Lower Shell Longitudinal Welds Cumulative Cumulative Neutron Fluence (E > 1.0 MeV)

Cycle Irradiation Irradiation [n/cm2 ]

Length Time Time Weld Weld Weld Cycle [EFPS] [EFPS] [EFPY] 101-142A 101-142B 101-142C I 3.28E+07 3.28E+07 1.04 1.48E+18 8.05E+17 8.05E+17 2 3.18E+07 6.46E+07 2.05 2.67E+18 1.47E+18 1.47E+18 3 3.64E+07 1.01E+08 3.20 4.05E+18 2.12E+18 2.12E+18 4 3.82E+07 1.39E+08 4.41 5.36E+18 2.82E+ 18 2.82E+18 5 3.93E+07 1.79E+08 5.66 6.72E+18 3.52E+18 3.52E+18 6 4.09E+07 2.19E+08 6.95 8.14E+18 4.00E+18 4.00E+18 7 4.26E+07 2.62E+08 8.30 8.87E+18 4.56E+18 4.56E+18 8 4.27E+07 3.05E+08 9.66 9.80E+18 5.01E+18 5.01E+18 9 4.55E+07 3.50E+08 11.10 1.07E+19 5.49E+18 5.49E+18 10 4.43E+07 3.95E+08 12.50 1.16E+19 6.05E+18 6.05E+18 11 4.19E+07 4.36E+08 13.83 1.22E+19 6.45E+18 6.45E+18 12 (Pjt) 4.53E+07 4.82E+08 15.27 1.3 IE+19 6.93E+18 6.93E+18 13 (Pjt) 4.23E+07 5.24E+08 16.61 1.40E+19 7.39E+18 7.39E+18 Future 2.21E+08 1.01E+09 32.00 2.47E+19 1.41E+19 1.41lE+19 Future 3.79E+08 1.51 E+09 48.00 3.59E+19 2.12E+19 2.12E+19 Cumulative Cumulative Iron Atom Displacements Cycle Irradiation Irradiation [dpa]

Length Time Time Weld Weld Weld Cycle [EFPS] [EFPS] [EFPY] 101-142A 101-142B 101-142C I 3.28E+07 3.28E+07 1.04 2.25E-03 1.23E-03 1.23E-03 2 3.18E+07 6.46E+07 2.05 4.06E-03 2.24E-03 2.24E-03 3 3.64E+07 1.01E+08 3.20 6.16E-03 3.24E-03 3.24E-03 4 3.82E+07 1.39E+08 4.41 8.17E-03 4.32E-03 4.32E-03 5 3.93E+07 1.79E+08 5.66 1.02E-02 5.38E-03 5.38E-03 6 4.09E+07 2.19E+08 6.95 1.24E-02 6.12E-03 6.12E-03 7 4.26E+07 2.62E+08 8.30 1.35E-02 6.97E-03 6.97E-03 8 4.27E+07 3.OSE+08 9.66 1.49E-02 7.68E-03 7.68E-03 9 4.55E+07 3.S0E+08 11.10 1.63E-02 8.41 E-03 8.41 E-03 10 4.43E+07 3.95E+08 12.50 1.76E-02 9.26E-03 9.26E-03 11 4.19E+07 4.36E+08 13.83 1.86E-02 9.88E-03 9.88E-03 12 (Pjt) 4.53E+07 4.82E+08 15.27 2.00E-02 1.06E-02 1.06E-02 13 (Pjt) 4.23E+07 5.24E+08 16.61 2.13E-02 1.13E-02 1.13E-02 Future 2.21E+08 1.0 IE+09 32.00 3.77E-02 2.17E-02 2.17E-02 Future 3.79E+08 1.51 E+09 48.00 5.48E-02 3.24E-02 3.24E-02 11-- - A n A-osr _

A-ar _I5 -1 -to - - ---- n:_ ....

Note: mhe maximum exposure occurs at me axiaLI eCevat1on (1 IMe circuL11ier1iiMI welu, Anss n n VtA 4A A ~ ~e I.C.,

tl II.'+

A;oncSlo h^~ll ILIUMb Ut;;;IVW an^ nf UIV 1111UPIalM tL^

%JI tLl%.;;

active fuel.

Radiation Analysis and Neutron Dosimetry March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 6-17 Table 6-7 Relative Radial Distribution of Neutron Fluence (E > 1.0 MeV)

RADIUS AZIMUTHAL ANGLE l (cm) 00 150 300 450 221.36 1.000 1.000 1.000 1.000 226.84 0.557 0.563 0.558 0.562 232.31 0.270 0.280 0.271 0.276 237.79 0.125 0.133 0.126 0.129 243.26 0.052 0.060 0.055 0.058 Note: Base Metal Inner Radius = 221.36 cm Base Metal 1/4T* = 226.84 cm Base Metal 1/2T* = 232.31 cm Base Metal 3/4T* = 237.79 cm Base Metal Outer Radius = 243.26 cm

excludes cladding in thickness dimension Table 6-8 Relative Radial Distribution of Iron Atom Displacements (dpa)

RADIUS AZIMUTHAL ANGLE (cm) 00 150 300 450 221.36 1.000 1.000 1.000 1.000 226.84 0.630 0.640 0.631 0.636 232.31 0.374 0.391 0.377 0.384 237.79 0.217 0.235 0.223 0.230 243.26 0.111 0.130 0.122 0.129 Note: Base Metal Inner Radius = 221.36 cm Base Metal 1/4T* = 226.84 cm Base Metal I/2T* = 232.31 cm Base Metal 3/4T* = 237.79 cm Base Metal Outer Radius = 243.26 cm

excludes cladding in thickness dimension Radiation Analysis and Neutron Dosimetry March 2003 WCAP-1 6002 Revision 0

6-18 WESTINGHOUSE NON-PROPRIETARY CLASS 3 6-18 WESTINGHOUSE NON-PROPRIETARY CLASS 3 Table 6-9 Calculated Fast Neutron Exposure of Surveillance Capsules Table 6-10 Calculated Surveillance Capsule Lead Factors Capsule ID And Location Status Lead Factor W-97 (70) Withdrawn EOC 4 1.18 W-263 (70) Withdrawn EOC 11 1.18 W-83 (70) In Reactor 1.18 W-104 (140) In Reactor 0.83 W-277 (70) In Reactor 1.18 W-284 (14°) In Reactor 0.83 Note: (1) Lead factors for capsules remaining in the reactor are based on cycle specific exposure calculations through the current operating fuel reload, i.e., Cycle 12.

Radiation Analysis and Neutron Dosimetry March 2003 WCAP-I 6002 Revision 0

WESTfNGHOUSE NON-PROPRIETARY CLASS 3 7-1 WESTINGHOUSE NON-PROPRIETARY CLASS 3 7-I 7 SURVEILLANCE CAPSULE REMOVAL SCHEDULE The following surveillance capsule removal schedule meets the intent of ASTM El 85-82 and is recommended for future capsules to be removed from the Waterford Unit 3 reactor vessel. This recommended removal schedule is applicable to 32 EFPY of operation.

Table 7-1 Waterford Unit 3 Reactor Vessel Surveillance Capsule Withdrawal Schedule Removal Time Fluence Capsule Location Lead Factor(a) (EFPY)(1) (n/cm 2 ,

E > 1.0 MeV) 970 970 1.18 4.44(c) 6.47 x 1018 (c) 1040 1040 0.83 Standby 2840 2840 0.83 Standby 2630 2630 1.18 13.83 1.45 x 10' 9 830 830 1.18 26 2.47x 10 "

2770 2770 1.18 Standby Notes:

(a) Updated based on Capsule 2630 dosimetry analysis.

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

(c) From Capsule 970 capsule evaluation report, Reference 13.

(d) Capsule 830 will reach the EOL (32 EFPY) vessel inside surface fluence of 2.47 x 1019 n/cm2 (E > 1.0 MeV) at approximately 26 EFPY.

Surveillance Capsule Removal Schedule March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 8-1 8-1 WESTINGHOUSE NON-PROPRIETARY CLASS 3 8 REFERENCES

1. Regulatory Guide 1.99, Revision 2, RadiationEmbrittlement ofReactor Vessel Materials, U.S.

Nuclear Regulatory Commission, May, 1988.

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

3. TR-C-MCS-001, A.D. Emery, "Summary Report on Manufacture of Test Specimens and Assembly of Capsules For Irradiation Surveillance of Waterford-Unit 3 Reactor Vessel Materials", Combustion Engineering Report, December 15,1977.

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

5. ASTM E208, StandardTest Methodfor Conducting Drop-Weight Test to Determine Nil-Ductility Transition Temperatureof FerriticSteels, in ASTM Standards, Section 3, American Society for Testing and Materials, Philadelphia, PA

6. TR-C-MCS-002, A. Ragl, "Louisiana Power & Light Waterford Steam Electric Station Unit No. 3, Evaluation of Baseline Specimens, Reactor Vessel Materials Irradiation Surveillance Program", Combustion Engineering Report, August 1977.

7. ASTM E185-82, StandardPracticefor Conducting Surveillance Testsfor Light-Water Cooled NuclearPower Reactor Vessels, E706 (IF), in ASTM Standards, Section 3, American Society for Testing and Materials, Philadelphia, PA, 1993.

8. ASTM E23-98, StandardTest Methodfor Notched Bar Impact Testing ofMetallic Materials, in ASTM Standards, Section 3, American Society for Testing and Materials, Philadelphia, PA, 1998.

9. ASTM A370-97a, StandardTest Methods and Definitionsfor Mechanical Testing ofSteel Products, in ASTM Standards, Section 3, American Society for Testing and Materials, Philadelphia, PA, 1997.

10. ASTM E8-99, StandardTest Methodsfor Tension Testing ofMetallic Materials, in ASTM Standards, Section 3, American Society for Testing and Materials, Philadelphia, PA, 1999.

11. ASTM E21-92 (1998), Standard Test Methodsfor Elevated Temperature Tension Tests of Metallic Materials,in ASTM Standards, Section 3, American Society for Testing and Materials, Philadelphia, PA, 1998.

12. ASTM Designation E693-94, StandardPracticefor CharacterizingNeutron Exposures in Iron and Low Alloy Steels in Terms of Displacementsper Atom (dpa), in ASTM Standards, Section 12, American Society for Testing and Materials, Philadelphia, PA, 1999.

13. BAW-2177, "Analysis of Capsule W-97, Entergy Operations, Inc., Waterford Generating Station, Unit No. 3, November 1992.

References March 2003 WCAP-16002 Revision 0

8-2 WESTINGHOUSE NON-PROPRIETARY CLASS 3 8-2 WESTINGHOUSE NON-PROPRIETARY CLASS 3

14. 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.

15. WCAP-15557, Revision 0, "Qualification of the Westinghouse Pressure Vessel Neutron Fluence Evaluation Methodology," August 2000.

16. RSIC Computer Code Collection CCC-650, "DOORS 3.1 One, Two- and Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code System, ", August 1996.

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

18. C-PENG-ER-004, Revision 0, "The Reactor Vessel Group Records Evaluation Program Phase II Final Report for the Waterford 3 Reactor Pressure Vessel Plates, Forgings, Welds and Cladding",

October 1995.

References March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 g A-1 A-i WESTINGHOUSE NON-PROPRIETARY CLASS 3 APPENDIX A INSTRUMENTED CHARPY IMPACT TEST CURVES

Specimen prefix "2" denotes Lower Shell Plate M-A 004-2, Transverse Orientation

Specimen prefix "A" denotes Correlation Monitor Material, Longitudinal Orientation

Specimen prefix "3" denotes Weld Material

Specimen prefix "4" denotes Heat-Affected Zone material Appendix A March 2003 WCAP-16002 Revision 0

A-2 WESTINGHOUSE NON-PROPRIETARY CLASS 3 A-2 WESTINGHOUSE NON-PROPRIETARY CLASS 3 5000 00 4000 00

- 3000 00-0 5000 00- 00 1.00 2 00 3 00 4.00 5 00 6.00 Time-1 (ms) 4000 00- 25E, -40 0 F 0 0000 0

4000 00 2i 2000 00.

0I, 3000 00-2000 00, 1 000 00.

u uu_

000 1.00 200 300 4.00 5 00 600 Time-1 (Ms) 23D. -300 F 00 500 0. . . . . -

400 A a000 . .

cs 300 0

200 0.00 100 0 00 . . .. .. .. . .

nnn 00o 1 00 200 300 400 500 6 .00 Time-1 (ms) 25J, -10°F Appendix A March 2003 WCAP-I 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 3 A-3 WESTINGHOUSE NON-PROPRIETARY CLASS 3 A-3 5000 00 4000 00 7 3000 00 0

2000 00 1 000 0 000 1 00 2.00 3.00 4 00 500 600 Time-1 (ms) 246, 00 F 500000 4000 00

,,, 3000 00 0

-J 2000 00 1000 00

_, _ _. _ _, .Sv , , , ,

000 , , , ,

0CS0 1.00 2 0C3 300 4 00 Sf0 600 Time-1 (ms) 215, 250 F 5000 00 4000.00

.0 13000.00 0

0

-j 2000 00 1000.00 I I l l l l l rob , _

000 600 10 1 00 200 3 00 4 00 5.00 Time-1 (ms) 23E, 500 F Appendix A March 2003 WCAP-16002 Revision 0

A4 WESTINGHOUSE NON-PROPRIETARY CLASS 3 5000O00 4000.00 2.

.7 3000 00 a

-J 2000 00-1000 00-0 00 I I 000 1 00 2 00 3.00 4.00 5.00 6.00 Time-1 (ms) 24U, 750 F C

0

-J 0 00 1.00 2.00 3 00 4 00 5.00 6.00 Time-1 Cms) 22U, 1250 F 5000 4000 In 3000

.7

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 A-5 3000.00;- if . . .. . \ . . . . .. . .. . . .

.0 0

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A-6 WESTINGHOUSE NON-PROPRIETARY CLASS 33 A-6 WESTINGHOUSE NON-PROPRIETARY CLASS 5000 0o 4000 00 B_-

2000 00 . : .:

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 A-7 5000 4000

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A-8 WESTINGHOUSE NON-PROPRIETARY CLASS 3 5000 00 4000 00 no

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 A-9 5000 Do 4000 00 Q

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A-10 WESTINGHOUSE NON-PROPRIETARY CLASS 3 A-b WESTINGHOUSE NON-PROPRIETARY CLASS 3 5000 0o0 4000 00O

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 A-1 I WESTINGHOUSE NON-PROPRIETARY CLASS 3 A-li 5000 00 4000 00 D0 D 3000 00 C

2000 00 1000 00 on

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-J 2000 00 1000 00 0 00' 000 1 00 200 300 400 500 600 Time-1 (ins) 35Y, -25 0F 0 00 1.00 2.00 3 00 4 00 5 00 600 Time-1 (ms) 361, 0F Appendix A March 2003 WCAP-16002 Revision 0

A-12 WESTINGHOUSE NON-PROPRIETARY CLASS 3 rt. - _ _ _ _ _ _ _ _ _ _ _

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 A-13 5000 00 4000 00

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-D

,0 3000 ca 2000 1000 0

0.00 1 00 2 00 3 00 4 00 5 00 6 00 Time-1 (ins) 35L, 200 0 F Appendix A March 2003 WCAP-16002 Revision 0

A-14 WESTINGHOUSE NON-PROPRIETARY CLASS 3 5000 00 4000 00

- 3000 00 A

2000 00 1000 00 0 00 1.00 2.00 300 4.00 500 6.00 Time-1 (ms) 41P, -175 0 F 5000 00_

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ll\_

000 1 00 2 00 3.00 400 5 00 6 00 Time-1 (ms) 43E, -750 F Appendix A March 2003 WCAP-1 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 A-15

£2 0

0 00 1 00 2 00 3 00 4 00 5 00 600 rie-1 (ms)

£2 V6 0

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-j 0 00 1.00 2 00 3.00 4 00 5 00 600 Time-1 (ms) 41U, 25 0F Appendix A March 2UUJ WCAP-16002 Revision 0

A-16 WESTINGHOUSE NON-PROPRIETARY CLASS 3 0

-J 0 00 100 2 00 3 00 400 5 00 600 Time-I (ms) 45B, 50WF 5000 00 4000 00

0 3000 00 03 Cj 2000 00 1000 00 I, I I 0 00 ,~~~~~ , i 00 1 00 2.00 3.00 400 50o 600 Time-I (ins) 471, 75-F 4000 a

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2000

'0 3 00 6 00 Time-1 (ms) 46L, 1100 F Appendix A March 2UU3 WCAP-1 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 A-17

.0 V7 C

C

-j 0.00 1.00 2 00 3 00 4 00 5 00 600 Time-1 (ms) 473, 1500 F

a 0

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WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-1 B-I WESTINGHOUSE NON-PROPRIETARY CLASS 3 APPENDIX B Charpy V-Notch Plots for Each Capsule Charpy V-notch plots for each capsule are given in the following pages. They were determined using the Hyperbolic Tangent Curve-Fitting Method. Contained in Table B-I are the upper shelf energy values used as input for the generation of the Charpy V-notch plots using CVGRAPH, Version 4.1. Lower shelf energy values were fixed at 2.2 fi-lb. The unirradiated and irradiated upper shelf energy values were calculated per the ASTM El 85-82 definition of upper shelf energy.

Table B-1 Upper Shelf Energy Values Fixed in CVGRAPH Material Unirradiated Capsule 970 Capsule 2630 Lower Shell Plate M- 170 ft-lb 155 ft-lb 1004-2 (Longitudinal Orientation)

Lower Shell Plate M- 141 ft-lb 124 ft-lb 131 ft-lb 1004-2 (Transverse Orientation)

Weld Metal 156 ft-lb 143 ft-lb 145 ft-lb (Heat # 88114)

HAZ Material 170 ft-lb 156 ft-lb 163 ft-lb Correlation Monitor 133 ft-lb --- 113 ft-lb Material (HSST Plate 01 MY)

Appendix B March 2003 WCAP-1 6002 Revision 0

B-2 WESTINGHOUSE NON-PROPRIETARY CLASS 33 B-2 WESTINGHOUSE NON-PROPRIETARY CLASS UNIRRADIATED PLATE M-1004-2 (LONGITUDINAL)

CYGRAPH 4.1 Hyperbolic Tangent Curve Printed at 1565315 on 09-30-2002 Page I Coefficients of Curve I IA =8 9 P = 839 C = 7221 1D = 44.99 Equation is CYN = A + B

I tanh((T - TO)/C) I Upper Shelf Energy: 170 Fixed Temp. at 30 fl-lbs -13.3 Temp. at 50 ft-lbs 11.7 Lower Shelf Energy- 219 Fixed Material: PLATE SA533BI Heat Number. M-1004-2 Orientation: LT Capsule UNIRR Total Fluence 300 - -

rI) 250F 20~

10 z__ 0 0

100-5(f 0- -

-30 0 -200 -100 0 100 200 300 400 r500 600 Temperature in Degrees F Data Set(s) Plotted Plant WM Cap: UNIRR Material PLATE SA533BI Ori: LT Heat t: M-1004-2 Charpy V-Notch Data Temperature Input CVN Energy Computed CYN Energy Differential

-80 7 73 -3

-40 115 16.75 -52

-40 12 165 -4.75 0 485 3968 asl 0 145 39.8 2518 40 105 803 24.69 40 86 803 6.69 80 130 15 614 80 107 IM5 -16B5 I" Data continued on next page **

Appendix B March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 g B-3 B-3 WESTINGHOUSE NON-PROPRIETARY CLASS 3 UNIRRADIATED PLATE M-1004-2 (LONGITUDINAL)

Page 2 Material F'LATE SA533BI Heat Number. M-1004-2 Orientation: LT Capsule: UNIRR Total Fluence.

Charpy V-Notch Data (Continued)

Temperature Input CVN Energy Computed CVN Energy Differential 120 147 151.31 -4.31 120 131 151.31 -20.31 140 158 15872 -.72 160 1775 163.33 1416 160 169.5 16333 616 M0 175 1682? 6.72 210 168.5 16827 ' 22 SUM of RRSSIDUAIS = -5.08 Appendix B March 2003 WCAP-16002 Revision 0

B4 WESTINGHOUSE NON-PROPRIETARY CLASS 3 BA WESTINGHOUSE NON-PROPRIETARY CLASS 3 UNIRRADIATED PLATE M-1004-2 (LONGITUDINAL)

CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 145&42 on 09-30-2002 Page I Coefficients of Curve I A = 46.13 B = 4513 C = 449 TO = 16.4 Equation is: LE = A + B I I tanh((T - T0)/C) I Upper Shelf LE 9127 Temperaturee al LE 35: 5 Lower Shelf L.E I Fixed Material PLATE SA533BI Helat Number. M-ll 04-2 Orientation: LT Capsule UNIRR Total Fluence:

U1 r-.4

. rj X

W r__4 0

_4 cu

_P Cd

_4

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant 1IF3 Cap: UNIRR Material: PLATE SA533BI Or: LT Heat 1: M-1004-2 Charpy V-Notch Data Temperature Input Lateral Expansion Computed LE Differential

-0 3 222 .77

-40 10 7.8 219

-40 10 78 219 0 41 30.37 10.62 0 14 30.37 -16.37 40 78 67B5 1014 40 65 67.85 -285 50 90 8623 376 80 72 Om2 -1423 Data continued on next page I March 2003 Appendix B March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-5 B-5 WESTINGHOUSE NON-PROPRIETARY CLASS 3 UNIRRADIATED PLATE M-1004-2 (LONGITUDINAL)

Page 2 Materia 1 PLATE SA533B1 Heat Number M-1004-2 Orientation: LT Capsule: UNIRR Total Fluence Charpy V-Notch Data (Continued)

TemperaLure Input Lateral Expansion Computed LE Differential 120 92 9038 1.61 120 89 9038 -138 140 160 91 909I 160 94 91J2 287 160 90 91.12 -1.12 210 95 9126 3.73 210 90 9126 -126 SUM of RESIDUAIS = .78 Appendix B March 2003 WCAP-1 6002 Revision 0

B-6 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-6 WESTINGHOUSE NON-PROPRIETARY CLASS 3 UNIRRADIATED PLATE M-1004-2 (LONGITUDINAL)

CVGRAPH 41 Hyperbolic Tangent Curve Printed at 142559 on 10-01-2002 Page I Coefficients of Curve I I A = 50 B = 50 C = 63I5 TO = 4078 Equation is Shear/ = A + B ' I tanh((T - T0)/C) I Temperature at 5WI Shear 40.7 Material PLATE SA533BI Heat Number H-1004-2 Orientation: LT Capsule UNIRR Total Fluence CI)

$.4-a) 10 Co p-4

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plantz IFn3 Cap: UNIRR Material. PATE SA533B1 Ori: LT Heat #: M-1004-2 Charpy V-Notch Data Temperature Input Percent Shear Compuled Percent Shear Differential

-0 0 213 -213

-40 10 7J8 281

-40 10 718 2.81 0 20 21.56 -L%5 0 15 2L56 -656 65 4938 15.61 40 -9.3 40 40 4939 80 80 775B 241 80 75 7758 -258

- Data continued on next page -1 March 2003 Appendix B March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-7 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-7 UNIRRADIATED PLATE M-1004-2 (LONGITUDINAL)

Page 2 Material' PLATE SA533BI Heat Number. M-1004-2 Oriental ion: LT Capsule UNIRR Total Fluence Charpy V-Notch Data (Continued)

Temperature Input Percent Shear Computed Percent Shear Differential 20 90 9Z47 -Z47 120 &5 9Z47 -7.47 140 100 95.85 414 160 100 97.75 224 160 1O0 97.75 224 210 100 99.53 A6 210 100 9953 .46 SUW4 of RESIDUALS = 103 Appendix B March 2003 WCAP-16002 Revision 0

B-8 WESTfNGHOUSE NON-PROPRIETARY CLASS 3 B-8 WESTINGHOUSE NON-PROPRIETARY CLASS 3 CAPSULE 97 PLATE M-1004-2 (LONGITUDINAL)

CVGRAPH 41 Hyperbolic Tangent Curve Printed at 1409 on 09-30-2002 Page I Coefficients of Curve 2 I- A = 7859 L = 76.4 C = 76.75 TO = 50.62 Equation is CVN = A + B I tanh((T - T0)/C) I Upper Shelf Energy: 155 Fixed Temp. at 30 ft-lbs -7 Temp. at 50 ft-lbs 204 Lower Shelf Energy: 219 Fixed Material: PLATE SA533BI Heat Number M-1004-2 Orientation: LT W-g7 Total Fluence:

Ef S-4 154 0L) 10 V 5

-30 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s Plotted PlantL fF3 Cap: 1T-97 Material: PLATI SA533BI Ori LT Heat f: M1-1004-2 Charpy V-Notch Data Temper ature Input CYN Energy Computed CVN Energy Differential 75 12.54 -5D4

-253 24 20.89 31

.225 34.43 -11.93 36 49.63 -13.6 3J 84S 58.54 2595 3 76 6325 12.74 O 72.5 77.97 7( 90 97.48 -7.48

"" Data continued on next page ""

Appendix B March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-9 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-9 CAPSULE 97 PLATE M-1004-2 (LONGITUDINAL)

Page 2 Matenal PLATE SA533B1 Heat Number. M-1004-2 Orientation LT Capsule: W-197 Total Fluencw Charpy V-Notch Data (Continued)

Temperature Input CVN Energy Computed CVN Energy Differential 100 113 12193 -893 150 156 14433 1L6 200 152 151.94 .05 550 157 15499 2 JM1 of RESIDUAIS = 301 Appendix B March 2003 WCAP-1 6002 Revision 0

B-10 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-b WESTINGHOUSE NON-PROPRIETARY CLASS 3 CAPSULE 97 PLATE M-1004-2 (LONGITUDINAL)

CVGRAPH 41 Hyperbolic Tangent Curve Printed at 1458:42 on 09-30-2002 Page I Coefficients of Curve 2 =

A = 44.9 B = 43.9 C = 66.46 TO = 2578 Equation is LE = A + B II tanh((T - T0)/C) I Upper Shelf LE: 88.81 Temperature at LE 35: 105 Lower Shelf LE: I Fixed Material: PLATE SA533BI Beat Number M-1004-2 Orientation- LT Capsule: !-97 Total Fluence:

(I)

. 154 a-4 X 0

?1 0r*

300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant lTF3 Cap: !-97 Material: PLATE SA533B1 Ori: LT Heat f: M-1004-2 Charpy V-Notch Data ature Input Lateral Expansion Computed LE Differential 0 6 914 -a14 21 1.65 4.34 25 28.68 -3.68 20 32 41.09 -. 09 61 47.68 1331 5 i54 50.95 3.04 s0 57 6023 -323 69 70.45 -L45

' Data continued on next page "

Appendix B March 2003 WCAP-1 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-I I B-Il WESTINGHOUSE NON-PROPRIETARY CLASS 3 CAPSULE 97 PLATE M-1004-2 (LONGITUDINAL)

Page 2 Materia 1.PLATE SA533BI Heat Number. M-1004-2 Oriientation: LT Capsule W-97 Total Fluence Charpy V-Notch Data (Continued)

Temperature Input Lateral Expansion Computed LF. Differential 100 75 8031 -5.31 150 93 86.77 622 200 93 8835 4f4 550 82 8.1 -115 SUM of RESIDUAIS = -uJ5 Appendix B March 2003 WCAP-1 6002 Revision 0

B-12 WESTINGHOUSE NON-PROPRIETARY CLASS 3 13-12 WESTINGHOUSE NON-PROPRIETARY CLASS 3 CAPSULE 97 PLATE M-1004-2 (LONGITUDINAL)

CYGRAPH 41 Hyperbolic Tangent Curve Printed at 1425i9 on 1041-2002 Page I Coefficients of Curve 2 A = 50 B = 50 C = 5L69 T = 52D3 Equation is: Shear/ = A + B I I lanh((T - TO)/C) I Temperature at SWz Shear 52 Material PLAITESA53381 Heat Number: M-1004-2 a rienlation: LT Capsule: N-7 Total Fluence IJ C) 61 I

4 41 ql) 3 -

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Setks) Plotted Flant llJ3 Cap: 1T1-7 Material: PLAT SA533BI Ori- LT Heat I: M-1004-2 Charpy V-Notch Data Temperaature Input Percent Shear Computed Percent Shear Differential

-50 O L89 -189

-25 0 403 4.3 0 10 IL78 -1.78 20 10 2245 -1a45 30 40 29B9 101 35 40 34.09 5.9 50 40 48.03 403 70 BO 66.71 132.

Data continued on next page Appendix B March 2003 WCAP-I 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-13 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-13 CAPSULE 97 PLATE M-1004-2 (LONGITUDINAL)

Page 2 Material PLATE SA533B1 Heat Number. M-1004-2 Orientat ior: LT Capsule f-P7 Total Fluence:

Charpy V-Notch Data (Continued)

Temperature Input Percent Shear Computed Percent Shear Differential 100 70 86.48 -1648 150 100 97.79 22 200 100 99.67 32 550 100 100 Sul;IUof RESIDUALS = -1365 Appendix B March 2003 WCAP-16002 Revision 0

B-14 WESTINGHOUSE NON-PROPRIETARY CLASS 33 B-14 WESTINGHOUSE NON-PROPRIETARY CLASS UNIRRADIATED PLATE M-1004-2 (TRANSVERSE)

CVGRAPH 41 Hyperbolic Tangent Curve Printed at 145135 on 09-30-20(1X Page I Coefficients of Curve I I A = 71.59 B = 69.4 C = 73a T1= 26L66 Equation is CVN = A + B I I tanh((T - T0)/C) I Upper Shelf Energy: 141 Fixed Temp. at 30 ft-lbs -24.4 Temp. at 50 ft-lbs ZB Lower Shelf Energy: 219 Fixed Material PLATE SA533BI Heat Number. M-1004-2 Orientation: Th Capsule: UNIRR Total Fluence:

U) 25 U T

07 S_4 15 a) 10

?" 10 Q

5

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted PlantL TF3 Cap: UNIRR Material: PLATE SA533BI Ori: TL Heat f. M-1004-2 Charpy V-Notch Data Tempen ature Input CYN Energy Computed CYN Energy Differential

-0CI 9 9.51 -fi1

-BC I 10 143 .43

-4( 285 2176 6.71

-4(I 205 2L78 -128 0 65.5 47.57 17.92 0 44 47.57 -3.57 4C 73 84 -11 4C I 685 84 -155 8C I 130 114.2 15.47

,* Data continued on next page --

Appendix B March 2003 WCAP-1 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-15 UNIRRADIATED PLATE M-1004-2 (TRANSVERSE)

Page 2 Material: IPLATE SA533UI Heat Number. M-1004-2 Orientation: TL Capsule UNIRR Total Fluence Charpy V-Notch Data (Continued)

Temperature Input CVN Energy Computed CVN Energy Differential 60 116 114.52 3.47 120 141 130.74 1025 120 1235 130.74 -724 160 136 13725 -1.35 160 138.5 13735 114 210 145 140.4 495 210 143.5 140.04 3.45 SUM of REESlDUAIS = 1862 Appendix B March 2003 WCAP-1 6002 Revision 0

B-16 WESTINGHOUSE NON-PROPRIETARY CLASS 3 13-16 WESTINGHOUSE NON-PROPRIETARY CLASS 3 UNIRRADIATED PLATE M-1004-2 '(TRANSVERSE)

CVGRAPH 41 Hyperbolic Tangent Curve Printed at 143703 on 10-01-002 Page 1 Coefficients of Curve I A = 45.95 B 44.95 C = 78 T0 = 1a65 Equation is: LE = A+ B* I tanh((T -10)/C) I Upper Shelf LE. 90.9 Temperature at LE 35 -6.7 Lower Shelf L.E. I Fixed Material: PLATE SA533BI Heat Number M-1004-2 Orientation: TL Capsule UNIRR Total Fluence I

9:

U2 r_..4

. r.4 I L500 lag X

Pq 10-o__

r__4 co

_4 0

4.)

tZ P.

-30 0 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant. WF3 Cap: UNIRR Material PLATE SA533B1 Ori TL Ileat I: M-1004-2 Charpy V-Notch Data Temperature Input Lateral Expansion Computed 1I Differential

-80 7 8.64 -164 60 6 -707

-0 23 195 3.49

-40 18 19.5 -15 0 50 3872 1127 0 37 3872 -1.72 40 67 6LO9 -09 40 55 6.09 OD 77 77.22 -.32

- Data continued on next page .

Appendix B March 2003 WCAP-1 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-17 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-17 UNIRRADIATED PLATE M-1004-2 (TRANSVERSE)

Page 2 Material PLATE SA53381 Heat Number I-1004-2 Orientation TL Capsule UNIRR Total Fluence Charpy V-Notch Data (Continued)

Temperature Input Lateral Expansion Computed LE Differential 80 82 7732 4.67 120 90 8551 4.48 160 81 8551 -451 160 88 MD89 -.89 160 92 8.89 31 210 90 90.33 -3 210 88 9033 -233 SUM of RESIDUALS = -3.53 Appendix B March 2003 WCAP-1 6002 Revision 0

B-18 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-iS WESTINGHOUSE NON-PROPRIETARY CLASS 3 UNIRRADIATED PLATE M-1004-2 (TRANSVERSE)

CVGRAPH 41 Hyperbolic Tangent Curve Printed at 14:4158 on 10-01-2002 Page 1 Coefficients of Curve I I A = 50 B = 50 C = 6403 T0 = 40.31 Equation is Shear/ = A + B

I tanh((T - T0)/C) I Temperature at 50;. Shear 403 Material PLATE SA533BI Heat Number. M-1004-2 0Orientation- TL Capsule UN]IR Total Fluence:

Ut' Cl) 6tf-a1)

C)

P-11

-30 OI -200 -100 0 100 200 300 400 F00 600 Temperature in Degrees F Data Set s) Plotted Plant WMF3Cap. UNIRR Material: PLATE SA533BI Ori: TL Heat M-1004-2 M:

Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 0 0 228 -228 0 0 417 -417

-40 10 7.52 2.47 0 10 7.52 2.47 a 2522.11 2B8 20 22.11 -21 80 40 6B 49.75 1024 40 40 49.75 -9.75 75 7754 -254 Data continued on next page Appendix B March 2003 WCAP-1 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 I B-19 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-19 UNIRRADIATED PLATE M-1004-2 (TRANSVERSE)

Page 2 Material: PLATE SA533BI Heat Number: M-1004-2 Orientation TL Capsule UNIRR Total Fluence:

Charpy V-Notch Data (Continued)

Temperature Input Percent Shear Computed Percent Shear Differential 80 75 7754 -2.54 120 100 92M 7.66 90 9233 -233 160 100 9767 232 160 100 9767 2.32 210 100 995 .49 210 100 995 A9 SUM of RESIDUAIS = 5.62 Appendix B March 2003 WCAP-1 6002 Revision 0

B-20 WESTINGHOUSE NON-PROPRIETARY CLASS 3 CAPSULE 97 PLATE M-1004-2 (TRANSVERSE)

CYGRAPH 41 Hyperbolic Tangent Curve Printed at 1451:35 on 09-30-2002 Page I Coefficients of Curve 2 A= 6309 B = 609 C = 75B9 T0 = __I 49.

Equation is CYN = A+ B ' tanh((T - T0)/C) I Upper Shelf Energy. 124 Fixed Temp at 30 ft-lbs 3.4 Temp. at 50 ft-lbs 331 Lower Shelf Energy: 2I9 Fixed Material: PLATE SA533B1 Heat Number. M-1004-2 Orientation: TL Capsule 11-97 Total Fluence 30F - -

02 254F N200 10

-300 -200 -100 0 100 200 300 400 50 60 Temperature in Degrees F Data Sel~s) Plotted Plant. WF3 Cap: W-97 Material PLATE SA533P1 Or Ti: Heat : M-1004-2 Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy Differential

-0 7 10.41 -3.41

-25 11 1713 -613 0 15 28.09 -13.09 10 36 387 2L2 20 53 40.42 12.57 35 54 51.45 254 50 73 63.35 9.64 70 71.5 79.02 -752 0' Data continued on next page Appendix B March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-21 B-21 WESTINGHOUSE NON-PROPRIETARY CLASS 3 CAPSULE 97 PLATE M-1004-2 (TRANSVERSE)

Page 2 Material. PLATE SA533B1 Heat Number. M-1004-2 Orientation: 'L Capsule 1-97 Total Fluence Charpy V-Notch Data (Continued)

Temperature Input CVN Energy Computed CVN Energy Differential 100 659&43 -9.93 150 1215 11521 558 200 125 12L72 327 550 124 12399 0 SUM of REIDUAIS =-4.34 Appendix B March 2003 WCAP-16002 Revision 0

B-22 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-22 WESTINGHOUSE NON-PROPRIETARY GLASS 3 CAPSULE 97 PLATE M-1004-2 (TRANSVERSE)

CVGRAPH 41 Hyperbolic Tangent Curve Printed at 14:3703 on 10-01-2002 Page I Coefficients of Curve 2 A = 422 B = 41.2 C = 65.77 TO = 30.45 Equation is LE = A + B I tanh((T - T0)/C) I Upper Shelf LE. 834 Temperature at I.E. 35: 18 Lower Shelf LE I Fixed MateriaL PLATE SA533BI Heat Number1M-1004-2 Orientation: TL Capsule: W-97 Total Fluence 2507 0) 1000 00

-3[X O -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant2 WF3 Cap: W-w7 Material: PLATY SA533BI Ori: TL Heat M-1004-2 M.

Charpy V-Notch Data Temperature Input Lateral Expansion Computed LE Differential

-0 6 756 -156

-25 11 1387 -2B7 0 17 24.37 -737 10 31 29.78 121 20 44 35.7 829 35 47 45.04 ,195 50 57 54.09 29 70 57 64.36 -736

- Data continued on next page

Appendix B March 2003 WCAP-I 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-23 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-23 CAPSULE 97 PLATE M-1004-2 (TRANSVERSE)

Page 2 Material: PLATE SA53311 Heat Number. M-1004-2 Orientation: TL Capsule 11-97 Total Fluence:

Charpy V-Notch Data (Continued)

Temperature Input Lateral Expansion Computed LE Differential 100 70 7452 -452 150 86 8128 4.71 200 86 8a29 a07 550 81 834 -a4 SUM of RESIDUAIS =-.96 Appendix B March 2003 WCAP-1 6002 Revision 0

B-24 WESTINGHOUSE NON-PROPRIETARY CLASS 33 B-24 WESTINGHOUSE NON-PROPRIETARY CLASS CAPSULE 97 PLATE M-1004-2 (TRANSVERSE)

CYGRAPH 41 Hyperbolic Tangent Curve Printed at 14:4158 on 10-01-2002 Page I Coefficients of Curve 2 A=50 B=50 C=33.47 T0= 4406 Equation is Shear/ = A + S II tanh((T - T0)/C)

Temperature at 50W. Shear. 44 Material PLAI1ESA53311 Heat Number. M-1004-2 0rientation: TL Capsule lT-T7 Total Fluence Ce co 10 0

C.)

a)

-30 -200 -100 0 100 200 300 410 500 600 Temperature in Degrees F Data Set(s) Plotted Plant WIFM Cap.: W-97 Material PLATE SA33B1 Ori: TI Heat I: M-1004-2 Charpy V-Notch Data Tempen ature Input Percent Shear Computed Percent Shear Differential

-50 0 36 -.36

-25 S L58 a41 0 5 6.7 -17 10 10 1155 -155 2G 20 109 .8 35 40 3678 321 50 10 5&77 -a17 70 100 8Z48 17.51

-' Data continued on next page I Appendix B March 2003 WCAP-1 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-25 CAPSULE 97 PLATE M-1004-2 (TRANSVERSE)

Page 2 Material: PLATE SA533BI Heat Number. M-1004-2 Orientation: TL Capsule 1-97 Total fluence:

Charpy V-Notch Data (Continued)

Temperature Input Percent Shear Computed Percent Shear Differential 100 70 9658 -2658 150 100 9962 17 200 100 99.99 0 100 100 0 550 SIDUAIS =-13.95 SUM of RE March 2003 Appendix B March 2003 WCAP-1 6002 Revision 0

B-26 WESTINGHOUSE NON-PROPRIETARY CLASS 33 B-26 WESTINGHOUSE NON-PROPRIETARY CLASS CAPSULE 263 PLATE M-1004-2 (TRANSVERSE)

CYGRAPH 41 Hyperbolic Tangent Curve Printed at 145135 on 09-30-2002 Page I

'Coefficients of Curve 3 A = 6659 B = 64.4 C = 11R94 ID = 41B5 Equation is CYN = A + B t tanh((T - T0)/C) I Upper Shelf Energy 131 Fixed Temp. at 30 fL-lbs -335 Temp. at 50 ft-lbs 11 Lower Shelf Energy 2.19 Fixed Material' PLATE SA533BI Heat Number. 11-1004-2 Orientation- T1 Capsule: W-263 Total Fluence 300yA En 2,50' P.-

200

~. 1507 1007

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant- !F3 Cap: W-263 Material: PLATE SA533B1 Ori TL Heat #:M-1004-2 Charpy V-Notch Data Temperature Input CYN Energy Computed CVN Energy Differential

-40 19 Z767 -&67

-30 14 3135 -1735

-10 55 3977 1522 0 46 44.4B 151 25 75 57.37 1762 50 74 7107 292 75 66 8437 -IB37 125 105 10516 -.96

' Data continued oni next page 'J" Appendix B March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-27 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-27 CAPSULE 263 PLATE M-1004-2 (TRANSVERSE)

Page 2 Matenal IPLATE SA533BI Heat Number1M-1004-2 Orientz ition: TL Capsule 1T-263 Total Fluence:

Charpy V-Notch Data (Continued)

Temperature Input CVN Energy Computed CVN Energy Differential 160 111 115.92 -4.92 200 128 12292 507 225 135 125.61 938 350 131 130.34 .65 Si)Mof RESIDUAIS = 2)9 Appendix B March 2003 WCAP-16002 Revision 0

B-?R WRSTING1401 SE NON-PROPRIETARY CLASS 3 R-9R WFSTIN(ThIOI JSF NON-PROPRIETARY CLASS 3 CAPSULE 263 PLATE M-1004-2 (TRANSVERSE)

CVGRAPI1 41 Hyperbolic Tangent Curve Printed at 1437:03 on 10-01-2002 Page I Coefficients of Curve 3 I A = 39.43 B = 3843 C = 9557 T0 = 20.88 Equation is LE = A + B I I tanh((T - T0)/C) I Upper Shelf LE 77.86 Temperature at LE 35 9.8 Lovier Shelf LE. I Fixed Material PLATE SA533BI Heat Number. M-ID04-2 Orientation: TL Capsule: 1-263 Total Fluence U) .1 .4- 4 + * -f t

.,- 150 X

I-W 100--. I I IIIII r_4 co _ I ,, i cu 4W H

5rT V_

i I U-'

-30 0 -200 -100 0 100 200 300 400 300 600 Temperature in Degrees F Data Set(s) Plotted Plant 1F3 Cap: W-263 Material PLATE SA533B1 Ori TL Heat f: M-1004-2 Charpy V-Notch Data Temperature Input Lateral Expansion Computed LE Differential

-40 14 17.79 -a79

-30 9 207 -117

-10 37 27.42 9.57 0 32 31.16 83 25 50 4108 891 50 51 50.79 2 75 49 5913 -1013 125 70 70.05 -.05 Data continued on next page -

Appendix B March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-29 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-29 CAPSULE 263 PLATE M-1004-2 (TRANSVERSE)

Page 2 Material. PLATE SA533131 hleat Number M-1004-2 Orientation: TL Capsule 1-263 Total Fluence:

Charpy V-Notch Data (Continued)

Temperature Input Lateral Expansion Computed LF Differential 160 73 739 -.9 200 77 76.09 .9 225 82 76.01 518 350 75 77.79 -S79 SUM of RESIDUALS = -376 March 20030 Revision Appendix BB March 2003 WCAP-I 6002 WCAP-16002 Revision 0

B-30 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-30 WESTINGHOUSE NON-PROPRIETARY CLASS 3 CAPSULE 263 PLATE M-1004-2 (TRANSVERSE)

CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 144158 on 10-01-2002 Page I Coefficients of Curve 3 l A = 50 B = 50 C = 99.72 TO = 663 Equation is: Shear/ = A + B II tanh((T - TO)/C I Temperature at 50z. Shear 663 Material PLATE SA533BI Heat Number. M-1004-2 Orientation: TL Capsule: W-263 Total Fluence a) a-)

-300 -200 -100 0 100 200 300 400 F500 600 Temperature in Degrees F Data Set(s) Plotted Plant: WF3 Cap: W-263 Material: PLATE SA533B1 Ori TL Heat #: M-1004-2 Charpy V-Notch Data Temper, ature Input Percent Shear Computed Percent Shear Differential

-40 10 10.6 -.6

-30 5 1265 -7.65

-10 15 17.79 -Z79 0 15 20.91 -5.91 25 45 3039 14.6 50 50 41.89 .1 75 45 5434 -934 IZ5 75 7644 -144

' Data continued on next page -

Appendix B March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-31 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-3 1 CAPSULE 263 PLATE M-1004-2 (TRANSVERSE)

Page 2 Material: PLATE SA533BI Heat Number M-1004-2 Orientation: TL Capsule: 1-263 Total Fluence:

Charpy V-Notch Data (Continued)

Temperature Input Percent Shear Computed Percent Shear Differential 160 80 -6.75 200 100 93.59 6.4 225 100 96.01 a98 350 100 99.66 33 SUM of RESIDUALS = -109 Appendix B March 2003 WCAP-16002 Revision 0

B-32 WESTINGHOUSE NON-PROPRIETARY CLASS 3 .

WELD METAL (UNIRRADIATED)

CVGRAPH 41 Hyperbolic Tangent Curve Printed at 1J13.21 on 1001-2002 Page I Coefficients of Curve I A =7909 B = 76.9 C = 5425 T0 = -43.59 Equation is CYN = A + B tI tanh((T - TO)/C) I Upper Shelf Energy. 156 Fixed Temp. at 30 ft-lbs -845 Temp. at 50 ft-lbs -61 Lower Shelf Energy. 2.19 Fixed Material: WELD L 124/0091 Heat Number. 88114/0145 Orientation:

Capsule UNIRR Total Fluence:

1) ;5b g, 200 -_

- 150-_

r_ =

z 100 --_

0

-3(N0 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant: WF3 Cap. UNIRR Material WELD L 124/0091 Ori Hea t f: 88114/0145 Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy Differential

-180 35 32 29

-150 5.5 518 31

-120 8 10.88

-80 135 34.06 -20.56

-80 45.5 34.06 1143

-40 83S 8418 -AB

-40 965 8418 1231 0 1305 13021 18 0 1225 13031 -7.1

" Data continued on next page '*

Appendix B March 2003 WCAP-1 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-33 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-33 WELD METAL (UNIRRADIATED)

Page 2 Material WELD L 124/0091 Heat Number 88114/0145 Orientation:

Capsule UNIRR Total Fluence:

Charpy V-Notch Data (Continued)

Temperature Input CVN Energy Computed CVN Energy Differential 40 149 14925 -25 40 - 142 14925 -725 80 146 1544 -8.4 80 158 154.4 359 120 1555 155.63 -13 120 162.5 15563 6.86 160 171 155.91 15.08 160 148.5 155.91 -7.41 SUM of RESIDUALS = -527 Appendix B March 2003 WCAP-1 6002 Revision 0

B-34 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-34 WE---T-N-GHOUSE NO-PRORITAY LAS WELD METAL (UNIRRADIATED)

CVGRAPH 41 Hyperbolic Tangent Curve Printed at 151712 on 10-01-2002 Page I Coefficients of Curve I A = 4824 B = 4724 C = 43.52 TO = -557 Equation is: LE. = A + B ' I tanh((T - To)/C) I Upper Shelf LE: 9549 Temperature at LE 35 -68.3 Lower Shelf LE I Fixed MateriaL WELD L 124/0091 Heat Number 68114/0145 Orientation:

Capsule UNIRR Total Fluence Cn r_.

-30 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant: VF3 Cap: UNIRR Material: WELD L 124/0091 Ori: HIlat 1: 88114/0145 Charpy V-Notch Data Temper; iture Input Lateral Expansion Computed L.E Differential

-180 4 131 268

-150 3 222 .77

-120 6 569 3

-80 12 24.37 _Vz

-80 IL62 36 24Z7

-0 61 64f6 -3.66

-40

-40 69 64.66 4.33 D 95 6&73 626 0 80 8&73 473

- Data continued on next page March 2003 Appendix B March 2003 WCAP-1 6002 Revision O

WETNGOS NO-RORETR CLS g B-35 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-35 WELD METAL (UNIRRADIATED)

Page 2 Material WEDW L 124/0091 Heat Number 88114/0145 Orientation:

Capsule: UNIRR Total Fluence:

Charpy V-Notch Data (Continued)

Temperature Input Lateral Expansion Computed LE Differential 40 97 94.34 265 40 95 9434 .65 80 94 953 -13 80 96 953 .69 120 96 9546 53 120 97 95.46 1.53 160 94 9548 -148 160 94 9548 -148 SUM of RESIDUAIS = 302 Appendix B March 2003 WCAP-16002 Revision 0

B-36 WESTINGHOUSE NON-PROPRIETARY CLASS 3 WELD METAL (UNIRRADIATED)

CVGRAPH 41 Hyperbolic Tangent Curve Printed at 152123 on 10-01-2002

,Page I Coefficients of Curve I A = 50 B = 50 C = 57.69 TO = -51.09 l Equation is Shear/ = A + B I tanh((T - T0)/C)I Temperature at 50N. Shear. -51 Material: WVELD L 124/0091 Heat Number. 88114/0145 Orientation:

Capsule: UNIRR Total Fluence:

V) 6(F -

10 C-)

2O _

0 _

-304o -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant: WF3 Cap. UNIRE Material: WELD L 124/0091 Ori: Heat $ 88114/0145 Charpy V-Notch Data Temperature

-40i Input Percent Shear Computed Percent Shear Differential

-180 0 1.3 -113

-150 0 314 -314

-120 10 84 1.59 Teprtr

-80 26B5 85 20 0

-18 30 Z6B5 314 0 50 5949 -9.49 75 59.49 15.5 85 8546 -.46 00 85.46 --&46 Data continued on next page Appendix B March 2003 WCAP-1 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-37 WESTINGHOUSE NON-PROPRIETARY CLASS 3 13-37 WELD METAL (UNIRRADIATED)

Page 2 Material W(ELD L 124/0091 Heat Number 08114/0145 Orientation:

Capsule UNIRR Total Fluence:

Charpy V-Notch Data (Continued)

Temperature Input Percent Shear Computed Percent Shear Differential 40 100 95.92 41)7 40 90 95.92 -5.92 00 100 93.94 105 80 100 9894 1.05 120 100 99.73 26 120 100 9973 26 160 100 9993 .06 160 100 99.93 106 SUM of RESIDUAIS = -538 March 20030 Revision Appendix B Appendix B March 2003 WCAP-16002 WCAP-16002 Revision 0

B-38 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-38 WESTINGHOUSE NON-PROPRIETARY GLASS 3 WELD METAL (UNIRRADIATED)

CYGRAPH 4.1 Hyperbolic Tangent Curve Printed at 152123 on 10-01-2002 Page 1 Coefficients of Curve I A= 50 B = 50 C 57.9 TO = -51.09 Equation is Shear/. = A + B II tanh((T - TO)/C) I Temperature at 50:. Shear. -51 Materiatl WELD L 124/0091 HeaL Number. 88114/0145 Orientation Capsule UNIRR Total Fluence U)

C-)

a)

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees iF Data Set(s) Plotted Plant: WF3 Cap.: UNIRR Material. WELD L 124/0091 Ori: Heat t: 88114/0145 Charpy V-Notch Data Tempera ature Input Percent Shear Computed Percent Shear Differential

-180 0 113 -113

-150 0 314 -3.14

-120 10 8.4 1.59

-80 20 261}5 -B5

-80 30 2585 314

-40 50 59.49 -9.49

-40 75 59.49 155 0 85 85.46 -.46 0 80 8546 -6.46 Data continued on next p -

Appendix B March 2003 WCAP-1 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-39 WELD METAL (UNIRRADIATED)

Page 2 Material. WELD L 124/0091 Heat Number 88114/0145 Orientation-Capsule UNIRR Total Fluence:

Charpy V-Notch Data (Continued)

Temperature Input Percent Shear Computed Percent Shear Differential 40 100 9592 407 40 90 95.92 -5.92 80 100 98.94 -11)5 80 100 98.94 1.05 120 100 9973 26 120 100 9973 26 160 100 9993 106 160 100 99.93 106 SUM of RESIDUAIS -538 Appendix B March 2003 WCAP-16002 Revision 0

B40 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-40 WESTINGHOUSE NON-PROPRIETARY CLASS 3 WELD METAL (CAPSULE 97)

CVGRAPH 41 Hyperbolic Tangent Curve Printed at 151321 on 10-01-2002 Page I Coefficients of Curve 2 A = 7259 B = 70.4 C = 5832 T0 = -1a46 Equation is CVN = A + B 'I tanh((T - T0)/C) ]

Upper Shelf Energy. 143 Fixed Temp. at 30 ft-lbs -56.3 Temp. at 50 ft-lbs -34.8 Lower Shelf Energy: 219 Fixed MateriaL WELD L 124/0091 Heat Number. 88114/0145 Orientation:

Capsule 11-97 Total Fluence:

rn CIn P0 z

P-

a4 V1

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant. WF3 Cap. 11-T7 Material WELD L 124/0091 Ori: Heat 1$88114/0145 Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy Differential

-0 145 3519 -20.69

-40 395 44.62 -5.12

-35 67 4986 1713

-20 93 6714 25.85

-15 645 7316 -8.8 0 78 90B4 -12384 20 108 110.81 -Z81 50 131 12951 1.48

'*

Data continued on next page --

Appendix B March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B41 WESTINGHOUSE NON-PROPRIETARY CLASS 3 BA 1 WELD METAL (CAPSULE 97)

Page 2 Material: WELD L 124/0091 Heat Number 88114/0145 Onentation:

Capsule: W-97 Total Fluence:

Charpy V-Notch Data (Continued)

Temperature Input CYN Energy Computed CVN Energy Differential 70 134.5 13586 -1.36 100 147 140.36 6.63 200 139 142.91 -3.91 550 1765 143 335 SUM of REI1DUALS = 2919 Appendix B March 2003 WCAP-16002 Revision 0

B42 WESTINGHOUSE NON-PROPRIETARY CLASS 3 WELD METAL (CAPSULE 97)

CYGRAPH 41 Hyperbolic Tangent Curve Printed at 15:1712 on 10-01-2002 Page I Coefficients of Curve 2 A = 4433 B = 43B3 C = 4628 TO = -29.06 t Equation is LE = A + B

I tanh((T - T0)/C) I Upper Shelf LE: 88.67 Temperature at LE 35: -39.6 Lower Shelf L.E I Fixed Material: MELD L 124/0091 Heat Number 88114/0145 Orientation:

Capsule: I-97 Total Fluence C,)

frq X

CZ CD 4.

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant: WF3 Cap: W-97 Material: WELD L 124/0091 Ori: Heat f: 88114/0145 Charpy V-Notch Data Temperature Input Lateral Expansion Computed LE Differential

-50 15 2625 -1125

-40 33 34.66 -1.66

-35 50 3924 10.75

-20 68 53.1 14N68

-15 51 57.76 -. 76 0 60 6924 -924 20 7B 7928 -123 60 85 85B9 -.89 Data conUnued on next page * :

Appendix B March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B43 WELD METAL (CAPSULE 97)

Page 2 Materi al: WiELD L 124/0091 Heat Number 88114/0145 Orientation:

Capsule: W-97 Total Fluence Charpy V-Notch Data (Continued)

Temperature Input Lateral Expansion Computed LE Differential 70 91 87.48 351 100 93 M834 465 200 94 8867 532 550 79 88.67 -967 SUM of RFESIDUALS = -14 Appendix B March 2003 WCAP-16002 Revision 0

B-44 WESTINGHOUSE NON-PROPRIETARY CLASS 3 WELD METAL (CAPSULE 97)

CVGRAPH 41 Hyperbolic Tangent Curve Printed at 15f2123 on 10-01-2002 Page I Coefficients of Curve 2 A = 50 3 = 50 C = 8534 T0 = -3093 Equation is Shear/. = A + P I I tanh((T - T0)/C3 I Temperature at 5WI Shear: -30.9 Material. WTELDL 124/0091 Heat Number 88114/0145 Orientation Capsule R-97 Total Fluence cu 0)

C.)

- 4(F _

0~

-30 0 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant: 1!F3 Cap: W-97 Material WELD L 124/0091 Ori: Heat #: 881114/0145 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

-50 40 39.01

-40 45 44.71 2B

-35 50 4762 237

-20 65 56.37 8.62

-15 50 5922 -922 0 67.36 -7.36 20 80 76.73 326 50 9Q 86.95 3.04

- Data continued on next page "

Appendix B March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B45 WELD METAL (CAPSULE 97)

Page 2 Material IWELD L 124/0091 Heat Number 88114/0145 Orientation:

Capsule H-97 Total Fluence Charpy V-Notch Data (Continued)

Temperature Input Percent Shear Computed Percent Shear Differential 70 90 9141 -141 100 100 95.55 444 200 100 99.55 A4 550 100 9999 0 M of RESIDUAlS = 546 March 20030 Revision Appendix BB March 2003 WCAP-1 6002 WCAP-1 6002 Revision 0

B46 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-46 WESTINGHOUSE NON-PROPRIETARY CLASS 3 WELD METAL (CAPSULE 263)

CVGRAPH 41 Hyperbolic Tangent Curve Printed' at 151321 on 10-01-2002 Page I Coefficients of Curve 3 A = 73.59 P = 71A . C = 71.83 TO -26.71 Equation is CVN = A + B I I tanh((T - TO)/C) I Upper Shelf Energy: 145 Fixed Temp. at 30 ft-lbs -77.7 Temp. at 50 ft-lbs -513 Lower Shelf Energy. 219 Fixed Material WfELD L 124/0091 Heat Number. 88114/0145 Orientation:

Capsule, W-263 Total Fluence 300 co 250 150 P.,

Vl 100-5 P

-3C10 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set~s) Plotted Plant. WF3 Cap: W-M63 Material: WEI L 124/0091 Ori: Hea t ff 88114/0145 Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy Differential

-175 4 4.46 -.46

-125 7 189 -3B9

-75 29 3173 -2.73

-50 57 5123 5.76

-25 76 753 .69 0 94 9899 -499 25 121 117fi4 3.35 50 130 129.91 8

"** Data continued on Siext page '*

Appendix B March 2003 WCAP-1 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B47 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B WELD METAL (CAPSULE 263)

Page 2 Material WELD L 124/0091 Heal Number 88114/0145 Orie ntation:

Capsule W-263 Total Fluence Charpy V-Notch Data (Continued)

Temperature Input CYN Energy Computed CVN Energy IDfferential 75 134 137.05 -3.05 100 143 1409 ao7 150 139 143.96 -4.96 200 153 144 74 825 SiiMof RESIDUAIS = 11 Appendix B March 2003 WCAP-16002 Revision 0

B-48 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-48 WESTINGHOUSE NON-PROPRIETARY CLASS 3 WELD METAL (CAPSULE 263)

CYGRAPH 4.1 Hyperbolic Tangent Curve Printed at 1517:12 on 10-01-2002 Page I Coefficients of Curve 3 l A = 43.17 B = 42.7 C - 59.76 TO = -35.06 Equation is LE = A + B

I tanh((T - T0)/C) I Upper Shelf LE. 8525 Temperature at LE 35: -46.B Lower Shelf L: I Fixed Material- WELD L 124/0091 Heat Number. 88114/0145 Orientation:

Capsule: 1-263 Total Fluence C) r_41507-01 0-a) co

~_ (

-300 -20 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant: lWF3 Cap: 11-263 Material: WfDD L 124/0091 Ori Heat I: 88114/0145 Charpy V-Notch Data Temper, ature Input Lateral Expansion Computed LE Differential

-175 0 177 477

-125 I 4.96 -3.96

-75 16 15855 -255

-50 39 32.8 614

-25 49 5021 -121 U 61 6542 -4.42 25 77 7529 1.6 50 82 80.72 1X2 Data continued on next page "

Appendix B March 2003 WCAP-1 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B49 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-49 WELD METAL (CAPSULE 263)

Page 2 Material: WELD L 124/0091 Heat Number. 88114/0145 Orientation:

Capsu]e W-263 Total Fluence Charpy V-Notch Data (Continued)

Temperature Input Lateral Expansion Computed LE Differential 75 83 8328 -28 100 87 84.44 2.5 150 85 8518 -18 200 83 8532 -232 SUM of RESIDUALS = -5.15 Appendix B March 2003 WCAP-1 6002 Revision 0

B-50 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-50 WESTINGHOUSE NON-PROPRIETARY CLASS 3 WELD METAL (CAPSULE 263)

CVGRAPH 41 HyperbQlic Tangent Curve Printed 4t 152123 on 10-01-2002 Page I Coefficients of Curve 3 A = 50 B = 50 C = 6417 TO = -36.3; Equation is Shear' = A + B' I tanh((T - TO)/C) I Temperature at 50z Shear -363 Ilaterial WELD L 124/0091 Heat Number 88114/0145 Orientation:

Capsule: 1-263 Total Fluence:

$-4 LK CI) 4- TF-2[

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant 1WF3 Cap: W-263 Material WELD L 124/0091 Ori: Heat #: 88114/0145 Charpy V-Notch Data Tempera ature Input Percent Shear Computed Percent Shear IDfferential

-17W 5 1.31 3.68 10 594 4.05

-75 20 2a08 -3.08

-50 35 39M -454

-25 65 5877 6-M 0 75 7564 -.64 25 9a 8713 2a6 50 90 9365 -3.65

-* Data continued on next page *'"

Appendix B March 2003 WCAP-1 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 ; B-51 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-5 I WELD METAL (CAPSULE 263)

Page 2 Matenal WELD L 124/0091 Heat Number. 88114/0145 Orientation:

Capsule: Tf-263 Total Fluence:

Charpy V-Notch Data (Continued)

Temperature Input Percent Shear Computed Perceht Shear Differential 75 90 969 -698 100 100 9&59 14 150 100 997 29 200 100 99.93 .06 SUM of RESIDUAIS = -3 Appendix B March 2003 WCAP-16002 Revision 0

B-52 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-52 WESTINGHOUSE NON-PROPRIETARY CLASS 3 HEAT AFFECTED ZONE UNIRRADIATED CYGRAPH 41 Hyperbolic Tangent Curve Printed at 153522 on 10-01-2002 Page I Coefficients of Curve I I A = 8609 B = U9 C =7759 T0 = -54Z37 Equation is CYN = A + B I tanh((T - T0)/C) I Upper Shelf Energy: 170 Fixed Temp. at 30 ft-lbs -117 Temp, at 50 ft-lbs -90 Lower Shelf Energy 2.19 Fixed Material: HEAT AFFD ZONE SA533BI Heat Number. M-1004-2 Orientation:

Capsule: UNIRR Total Fluence:

30F -

rn 25F -

200-P.-

-4 CD150 U

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant: WF3 Cap: UNIRR? Material HEAT AFFD ZONE SA533BI Ori_ Heat j: M-1004-2 Charpy V-Notch Data Tempera ature Input CVN Energy Computed CYN Energy Differential

-150 65 15.34 -. 84

-135 105 20.86 -1036

-120 215 283 -6B

-80 765 59.35 1714

-60 445 59.35 -1485

-40 1135 10L46 IZ03

-40 1165 101.46 15D3 0 llB 13684 -18B4 0 13B 136.84 115

'* Data continued on next page *'"

Appendix B March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-53 B-53 WESTINGHOUSE NON-PROPRIETARY CLASS 3 HEAT AFFECTED ZONE UNIRRADIATED Page 2 Material. HEAT AFFD ZONE SA533B] Heat Number M-1004-2 Orientation:

Capsule: UNIRR Total Fluence:

Charpy V-Notch Data (Continued)

Temperature Input CVN Energy Computed CVN Energy Differential 40 126 15645 -3045 40 162 156.45 5.54 80 177 164.9 1209 80 163.5 164.9 -IA 120 1525 16.14 -15.64 120 183.5 16814 15.35 160 1645 169.33 -4.3 160 183.5 169.33 1416 SUM of RESIDUALS =-19.54 Appendix B March 2003 WCAP-16002 Revision 0

B-54 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-54 WESTINGHOUSE NON-PROPRIETARY CLASS 3 HEAT AFFECTED ZONE UNIRRADIATED CYGRAPH 41 Hyperbolic Tangent Curve Printed at 154212 on 10-01-2002 Page I Coefficients of Curve I i A= 44.56 B = 4356 C - 5048 TO = -7828 Equation is LE. = A + 8 ' I lanh((T - TO)/C) I Upper Shelf LE: 8813 Temperature at LE 35 -895 Lorer Shelf LE. I Fixed Material HEAT AFFD ZONE SA533BI Heat Number. M-1004-2 Orientation:

Capsule UNIRR Total Fluence:

U)

.- 4 Ct ct

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant: WFF3 Cap UNIRR Material: HEAT AtFD ZONE SA533BI Or: Heat fi: M-1004-2 Charpy V-Notch Data Temperal Lure Input Lateral Expansion Computed LE. Dfferential

-150 9 5.8 319

-135 8 9.33 -1.33

-120 17 15 L99

--0 50 43DM 691

-80 33 438 -1008

-40 73 7245 .54

-40 77 7245 454 0 77 8438 -738 0 88 8438 3.81

$- Data continued on next page *'

Appendix B March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 1 B-55 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-55 HEAT AFFECTED ZONE UNIRRADIATED Page 2 Matenal HEAT AFFD ZONE SA533BI Heat Number M-1004-2 Orientation Capsule UNIRR Total Fluence:

Charpy V-Notch Data (Continued)

Temperature Input Lateral Expansion Computed LE. Differential 40 84 87.34 -334 40 88 87.34 L5 80 84 87.97 -3.97 80 91 8727 a02 120 90 881 1.89 120 89 881 B9 160 87 8813 -113 160 89 8.13 B6 SUM of RESIDUAIS = .91 Appendix B March 2003 WCAP-16002 Revision 0

B-56 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-56 WESTiNGHOUSE NON-PROPRIETARY CLASS 3 HEAT AFFECTED ZONE UNIRRADIATED CYGRAPH 41 Hyperbolic Tangent Curve Printed at 154752 on 1-01-2002 Page I Coefficients of Curve I A = 50 B = 50 C = 7235 T0 = -531 Equation is: Shear/ = A + B' I tanh((T - T0)/C) I Temperature at 50z Shear -553 Material HEAT AFFD ZONE SA533BI Heat Number. M-1004-2 Orientation:

Capsule. UNIRR Total Fluence a)

Cr) a-)

-300 -200 -100 0 100 200 300 400 600 600 Temperature in Degrees 3F Data Set(s) Plotted Plant 11F3 Cap: UNIRR Material HEAT AFfD ZONE SA533BI Ori: Heat #: M-1004-2 Charpy V-Notch Data Tempera ature Input Percent Shear Computed Percent Shear Differential

-150 0 6.8 -8

-135 0 9.94 -9.94

-20 10 1432 -432 80 45 3357 1142 80 30 3357 -357

-40 70 60.42 957

-40 60 6042 -.42 0 75 82J8 -718 0 80 818 -Z18 Data continued on next page *-

Appendix B March 2003 WCAP-1 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-57 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-57 HEAT AFFECTED ZONE UNIRRADIATED Page 2 Material HEAT AFFD ZONE SA533BI Heat Number M-1004-2 Orientation:

Capsule: UNIRR Total Fluence Charpy V-Notch Data (Continued)

Temperature Input Percent Shear Computed Percent Shear Differential 40 75 933 -163 40 100 933 6.69 80 100 97. 2831 80 100 97.68 231 120 160 9922 .71 120 100 9922 .77 160 100 9974 25 160 100 9974 25 SUM of RESIDUAIS =-1634 Appendix B March 2003 WCAP-1 6002 Revision 0

B-58 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-58 WESTINGHOUSE NON-PROPRIETARY CLASS 3 HEAT AFFECTED ZONE 'CAPSULE 97 CVGRAPH 41 Hyperbolic Tangent Curve Printed at 153522 on 10-01-2002 Page I Coefficients of Curve 2 A = 7909 B = 76.9 C = 3&57 T0 = -36.56 Equation is CYN = A + B

I tanh((T - 1)/C) I Upper Shelf Energy: 156 Fixed Temp at 30 ft-lbs -1034 Temp. at 50 ft-lbs -71.8 Lower Shelf Energy: 219 Fixed Material: HEAT AFFD ZONE SA533HI Heat Number1M-1004-2 Orientation:

Capsule bf-97 Total Fluence:

.,n~,

, , , i.EI Juu Un 250F In

".L4 20Tf 0 _ _ __ 0 ___ __

15f D

'0 z

V 5(F U I I I I I I

-300 -20 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant1WF3 Cap: W-T7 Material: HEAT AFFD ZONE SA533BI Ori: Heat fi: M-1004-2 Charpy V-Notch Data Temper ature Input CVN Energy Computed CVN Energy Differential

-IC3 21 31B4 -10.84 35 40.79 -5.79

--a5 53.5 5522 -1.72 D

-5 i 90 67.52 22.47 1155 10915 634 1 101 11617 -1517 21 121 122.46 -146 5O 1195 136.91 -17.41

"* Data continued on next page *'

Appendix B March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-59 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-59 HEAT AFFECTED ZONE CAPSULE 97 Page 2 Material. HEAT AFFD ZONE SA533H1 Heat Number M-1004-2 Orientation:

Capsule W-97 Total Fluence:

Charpy V-Notch Data (ContinUed)

Temperature Input CVN Energy Computed CVN Energy Differential 70 155 143ZV 1172 100 14926 1423 150 150 153.75 -375 SUM of RF5IDUAIS = -1.39 Appendix B March 2003 WCAP-16002 Revision 0

B-60 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-60 WESTINGHOUSE NON-PROPRIETARY CLASS 3 HEAT AFFECTED ZONE CAPSULE 97 CVGRAPH 4J Hyperbolic Tangent Curve Prinied at 15-412 on 10-01-2002 Page I Coefficients of Curve 2 -

I A-=3953 P = 3.53 C = 4811 TO = -66.56 Equation is LE = A + B I I tanh((T - TO)/C) I Upper Shef LE. 78.06 Temperature at L.E 35: -722 Lower Shelf LE I Fixed Material: HEAT AFFD ZONE SA533BI Heat Number M-1004-2 Orientation:

Capsule: W-97 Total Fluence:

U)

. X W

Ct_

co

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant- TF3 Cap: 1Y-97 Material: HEAT AFFD ZONE SA533BI Ori Heat D M-1004-2 Charpy V-Notch Data Temper;ature Input Lateral Expansion Computed LE Dif 'erential

-100 14 16.36 -236 26 25.44 .55 36 40.78 -4.78 60 5229 7.7 0 71 735 -ZS IC 67 7499 -799

21) 73 76 -3 77 77.45 -.45 Data continued on next page ~

Appendix B March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-61 B-6 I WESTINGHOUSE NON-PROPRIETARY CLASS 3 HEAT AFFECTED- ZONE CAPSULE 97 Page 2 Material: HEAT AFFD ZONE SA533B1 Heat Number. M-1004-2 Orientation:

Capsule Y-97 Total Fluence:

Charpy V-Notch Data (Continued)

Temperature Input Lateral Expansion Computed LE Differential 70 83 7779 52 100 90 77.9 1201 150 71 7605 -705 SUM of RESIDUALS =-2.68 Appendix B March 2003 WCAP-16002 Revision 0

B-62 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-62 WESTINGHOUSE NON-PROPRIETARY CLASS 3 HEAT AFFECTED ZONE CAPSULE 97 CVGRAPH 41 Hyperbolic Tangent Curve Printed at J54752 on 10-01-2002 Page I Coefficients of Curve 2 A 50 B = 50 C= 67.96 TO = -375 Equation is: Shear/ = A + B ' I tanh((T - TO)/C)

Temperature at 50% Shear. -375 Material: HEAT AFFD ZONE SA533BI Heat Number. M-1004-2 Orientation Capsule: W-97 Total Fluence Ct a)

U) a, C-)

a)

-:300 -200 -100 0 100 200 300 400 5500 600 Temperature in Degrees F Data Set(s) Plotted Plant TM Cap:jl-97 Material HEAT AFFD ZONE SA533BI OrL Heat J7 M-10041-2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

-100 5 13.71 471

-65 25 19.81 518

-65 15 30.8 -152

-0 60 40.9 19.09 0 Bo 7.09 49 10 70 BOIS -101a 20 805 84.45 .54 50 85 9292 -7.92

"' Data continued on next page March 20030 Revision Appendix B B March 2003 WCAP-16002 Revision 0

WESTINfGHOUSE NON-PROPRIETARY CLASS 3 B-63 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-63 HEAT AFFECTED ZONE CAPSULE 97 Page 2 Material HEAT AFFD ZONE SA533BI Heat Number M-1004-2 Orientation:

Capsule 1!-97 Total Fluence:

Charpy V-Notch Data (Continued)

Temperature Input Percent Shear Computed Percent Shear Differential 70 100 95.94 4.05 100 100 9828 171 150 100 996 .39 SUM of RESIDUAIS = -671 f

Appendix B March 2003 WCAP-16002 Revision 0

B-64 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-64 WESTINGHOUSE NON-PROPRIETARY CLASS 3 HEAT AFFECTED ZONE CAPSULE 263 CYGRAPH 41 Hyperbolic Tangent Curve Printed at 15.3522 on 10-01-2002 Page I Coefficients of Curve 3 l A = 8Z59 B = 804 C = 8455 TO = -2578 Equation is CYN = A + B

I tanh((T - 10)/C) I Upper Shelf Energy. 163 Fixed Temp. at 30 ft-lbs -919 Temp. at 50 ft-lbs -61 Lower Shelf Energy: 219 Fixed Material. HEAT AFFD ZONE SA533BI Heat Number. M-1004-2 Orientation:

Capsule: W-263 Total Fluence 300_

U) 25W_

la 20W S..

C-)

150 .

V 100-5(F 0r

-30 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant WF3 Cap: 1'-263 Material HEAT AFFD ZONE SA533BI Or: Heat #: M-1004-2 Charpy V-Notch Data Temperal ture Input CVN Energy Computed CVN Energy Differential

-175 4 678 -Z78

-125 29 1624 1275

-75 31 40.45 -945

-25 83 8334 -34 0 114 10638 7.61 25 118 125.81 -7.B1 50 144 14004 395 75 152 149.42 2.57

"' Data-continued on next page "'

Appendix B March 2003 WCAP-I 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 , B-65 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-65 HEAT AFFECTED ZONE CAPSULE 263 Page 2 Material: HEAT AFFD ZONE SA533B1 Heat Number. M-1004-2 Orientation:

Capsule: T!-263 Total Fluence Charpy V-Notch Data (Continued)

Temperature Input CVN Energy Computed CVN Energy Differential 110 142 15&77 -1477 150 182 160.52 21.47 225 163 16257 A2 325 192 16.95 29.04 SUM of RESIDUAIS = 4Z69 Appendix B March 2003 WCAP-1 6002 Revision 0

B-66 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-66 WESTINGHOUSE NON-PROPRIETARY CLASS 3 HEAT AFFECTED ZONE CAPSULE 263 CVGRAPH 4J Hyperbolic Tangent Curve Printed at 154Z2I on 10-01-2002 Page I Coefficients of Curve 3 l A = 38.09 B = 37.09 C = 6L59 TO = -51.41 Equation is LE = A + B

I tanh((T - T0)/C) I Upper Shelf LE 7519 Temp'erature at LK 35 -565 Lower Shelf LE:E I Fixed Material: HEAT AFFD ZONE SA533BI Heat Numbern M-1004-2 Orientation:

Capsule: 1-263 Total Fluence zuu U2 r--q

.P-1 1507-5 PQX 1

P--4 M e

-4 Q) i co 5T LiIj I I I I

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant: WMI Cap: 1-263 Material HEAT AFFD ZONE SA533B1 Ori Heat 5: M-1004-2 Charpy V-Notch Data Tempera iture Input Lateral Expansion Computed LK Differential

-17,9 51 2.31 -131

-125 15 723 7.76

-75 23 2454 -[54

-25 47 53J 0 67 63.43 3.56 25 75 69.47 552 50 80 7253 7.46 75 69 73.9 -4.99 Data continued on next page

Appendix B March 2003 WCAP-I 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-67 HEAT AFFECTED ZONE CAPSULE 263 Page 2 Material HEAT AFF'D ZONE SA533B1 Heat Number. M-1004-2 Orientation:

Capsule: W-263 Total Fluence Charpy V-Notch Data (Continued)

Temperature Input Lateral Expansion Computed LR Differential 110 74 748 -X 150 74 7518 -108 225 77 75.18 JB1 325 69 7519 -619 SUM of RESIDUAIS = 408 Appendix B March 2003 WCAP-1 6002 Revision 0

B-68 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-68 WESTINGHOUSE NON-PROPRIETARY CLASS 3 HEAT AFFECTED ZONE CAPSULE 263 CVGRAPH 41 Hyperbolic Tangent Curve Printed at 15.47f52 on 10-01-2002 Page I Coefficients of Curve 3 A = 50 B = 50 C = 79A6 TI = -5343 Equation is Shear/ = A + B

I tanh((T - T0)/C) I Temperature at 5%/ Shear. -53.4.

Material- HEAT AFFD ZONE SA533131 Heat Number M-1004-2 Orientation:

Capsule 11-263 Total Fluence

4 a) 1)

C-)

a)

C)

-300 -200 -100 0 100 200 300 400 500 600 TemDerature in Degrees F Data Set(s) Plotted Plant: WF3 Cap: 1-263 Material HEAT AFFD ZONE SA533B1 OrL Heat I: M-1004-2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

-175 5 448 .51

-125 10 1417 -417

-75 45 36.75 824

-25 60 6716 -716 0 75 7933 -433 25 90 87. 219 50 100 931 6.89 75 100 962 3.79 Ad Data continued on next page "-

Appendix B March 2003 WCAP-l 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-69 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-69 HEAT AFFECTED ZONE CAPSULE 263 Page 2 Material HEAT AFFD ZONE SA533BI Heal Number M-1004-2 Orientation Capsule f-263 Total Fluence:

Charpy V-Notch Data (Continued)

Temperature Input Percent Shear Computed Percent Shear Differential 110 100 939 16 150 100 994 59 225 100 99.9 09 325 100 9999 0 SUM of RESIDUAIS = 827 Appendix B March 2003 WCAP-I 6002 Revision 0

B-70 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-70 WESTINGHOUSE NON-PROPRIETARY CLASS 3 STANDARD REFERENCE MATERIAL UNIRRADIATED CVGRAPH 41 Hyperbolic Tangent Curve Printed at 16251 on 10-01-2002 Page I Coefficients of Curve 1 I A = 67.59 B = 65.4 C = 6715 TO = 78.75 Equation is CVN = A + B ' I tanh((T - T0)/C) I Upper Shelf Energy" 133 Fixed Temp at 30 ft-lbs 343 Temp. at 50 fl-lbs 60 lkwer Shelf Energy: 2.19 Fixed Material SRM H!l'0I Heat Number. A1008 I Orientation: LT Capsule: UNIRR Total Fluence U) 1 .0 aJ_

I VL

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant 103 Cap: UNIRR Material- SRM HM1. Ori: LT Heat I: A1008-1 Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy Differential

-a0 145 3.4 1109

-40 7 6.03 .96

-40 8 6.03 1.96 0 185 13B9 4.6 0 18 13.9 41 40 395 33.4 5.65 40 35.5 33.84 165 80 68 68B _-

BO 55 682 -138 Data continued on next page -

Appendix B March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 3 B-71 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-71 STANDARD REFERENCE MATERIAL UNIRRADIATED Page 2 Material SRM ILMITI Heat Number A1008-1 Orientati on LT Capsule UNIRR Total Fluence:

Charpy V-Notch Data (Continued)

Temperature Input CVN Energy Computed CVN Energy Differential 120 -609 975 103.09 12 105.5 ioaog 4 160 130 12207 7.92 160 141 12207 1892 210 131 13032 £7 210 130 130.32 -.32 StIMof RESIDUAIS = 3898 Appendix B March 2003 WCAP-16002 Revision 0

B-72 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-72 WESTINGHOUSE NON-PROPRIETARY CLASS 3 STANDARD REFERENCE MATERIAL UNIRRADIATED CVGRAPH 41 Hyperbolic Tangent Curve Printed at 16Z323 on 10-01-2002 Page I Coefficients of Curve I A = 4812 B = 4712 C = 9208 T0 = 6829 Equation is LE = A + B I tanh((T - T0)/C) ]

Upper Shelf LE_ 9525 Temperature at LE 35. 419 Lower Shelf LE: I Fixed Material. SRM HSST0I Heat Number A1008-1 Orientation: LT Capsule: UNIRR Total Fluence:

200 U) 15f

.P.

X 10f 0P5°0 W

r__ I0 5

U II I

[l

/,- 0 I0

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Dala Sel(s) Plotted Plant FF3 Cap: UNIRR Material: SRM H$10 Ori: LT, Heat $ A1008-I Charpy V-Notch Da Lta Temperature Input Lateral Expansion Computed LE Differential

-80 3 4.61 -1.61

-40 8 919 -119

-40 8 9.19 _U9 0 20 18.43 156 0 20 18.43 156 40 39 3408 491 40 32 341)8 -2.08 80 55 54J08 -91 80 47 54.0 -7.08

"* Data continued on next page ""

Appendix B March 2003 WCAP-1 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-73 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-73 STANDARD REFERENCE MATERIAL UNIRRADIATED Page 2 Material: SRM HSST0I Heat Number. A1008-1 Orientation: LT Capsule UNIRR Total Fluence Charpy V-Notch Data (Continued)

Temperature Input Lateral Expansion Computed LE Differential 120 67 7212 -512 120 75 7212 2.7 160 90 M93 606 160 89 83.93 506 210 84 911 -71 210 92 9I1 .89 SUM of RESIDUAIL =-1.54 Appendix B March 2003 WCAP-16002 Revision 0

B-74 WESTINGHOUSE NON-PROPRIETARY CLASS 3 8-74 WESTINGHOUSE NON-PROPRIETARY CLASS 3 STANDARD REFERENCE MATERIAL UNIRRADIATED CYGRAPH 4.1 Hyperbolic Tangent Curve Printed at 1&2554 on 1001-2002 Page I Coefficients of Curve I A = 50 B = 50 C = 7044 TO = 8638 Equation is Shear/. = A + B I tanh((T - T0)/C) ]

Temperature at 50. Shear. 8&3 Material SRMHST01 Heat Number. A100-1 Orirentation: LT Capsule: UNIRR Total Fluence:

Q) 4-C.)

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant: WFF3 Cap: UNIRR Material SRM HMI Ori LT Heat 5: A1008-1 Charpy V-Notch Data Temper, iture Input Percent Shear Computed Percent Shear Differential

-80 0 8 -.s8

-40 0 269 -2.69

-40 10 269 73 0 15 7.92 7.07 0 15 7.92 7.07 40 25 2113 3.86 40 25 2113 3.86 80 40 4548 -SAS 80 35 45.48 -10.4B Data continued on next page *'

Appendix B March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-75 WESTINGHOUSE NON-PROPRIETARY GLASS 3 B-75 STANDARD REFERENCE MATERIAL UNIRRADIATED Page 2 Materia L SRM H3T0J Heat Number A1008-1 Orientationy LT Capsule UNIRR Total Fhuence Charpy V-Notch Data (Continued)

Temperature Input Percent Shear Computed Percent Shear Differential 120 65 72.2 -72 120 75 722 279 160 100 11 160 10a 8.99 210 100 97.09 Z9 210 100 97.09 2.9 SUM of IRESIDUALS = 3306 Appendix B March 2003 WCAP-1 6002 Revision 0

B-76 WESTINGHOUSE NON-PROPRIETARY CLASS 3 STANDARD REFERENCE MATERIAL CAPSULE 263 CVGRAPH 41 Hyperbolic Tangent Curve Printed at 16201 on 10-01-2002 Page I Coefficients of Curve 2 A = 5759 B = 55.4 C = 64.79 T0 = 0.31 I rb

- . _ *_ . _ .ew n-. , I- rw

_%t{

)rn EquaUon is UN = A t B I tann[ - llU)/L) I Upper Shelf Energy: 113 Fixed Temp. at 30 ft-lbk 184.8 Temp. at 50 ft-lbs 2113 Lower Shelf Energy: 219 Fixed Material: SRM SA533BI Heat Number A1008-1 Orientation: LT Capsule lf-263 Total Fluence 300 U] 250 la

-_4-200

)

150 V

100- 0 50F (F Q~/° n 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant WF3 Cap: W-263 Material: SRM SA533BI Ori: LT Heat j: A1008-1 Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy Differential

-30 4 224 175 50 9 277 622 125 12 7.75 424 175 23 2414 -114 200 32 40.7 -8.78 240 92 7a93 18.06 Z75 77 9S87 -18.7 320 116 10811 78

Data continued on next page "-

Appendix B March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 g B-77 B-77 WESTiNGHOUSE NON-PROPRIETARY CLASS 3 STANDARD REFERENCE MATERIAL CAPSULE 263 Page 2 Material: SRM SA533B1 Heat Number A1008-1 Orientation- LT Capsule: W-263 Total Fluence.

Charpy V-Notch Data (Continued)

Temperature Input CVN Energy Computed CVN Energy Differential 350 106 11101 -3.01 375 117 1IZ07 492 425 114 112.8 119 460 108 112.93 -493 SUM of RESIDUALS = 7.72 Appendix B March 2003 WCAP-1 6002 Revision 0

B-78 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-78 WESTINGHOUSE NON-PROPRIETARY CLASS 3 STANDARD REFERENCE MATERIAL CAPSULE 263 CVGRAPH 41 Hyperbolic Tangent Curve Printed at 1623;23 on 10-01-2002 Page 1 Coefficients of Curve 2 A = 3522 B = 3422 C = M53 T =2088 Equation is IS = A + B ' I tanh((T - T0)/C) I Upper Shelf L. 69.45 Temperature at LE 35c 2085 La1wer Shelf LE.: I Fixed Material: SRM SA533P1 Heat Number. A1008-1 0rientation: LT Capsule: W-263 Total Fluence 200-

.E

.- 4 100-co 0 0 0 - I

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant 11F3 Cap: 11-263 MateriaL SRM SA533B On:

r LT Heat 1: A1008-1 Charpy V-Notch Data Temperature Input Lateral Expansion Computed LE Differential

-30 3 I 199 50 6 117 4.82 125 8 3.82 417 175 17 16 .99 200 25 29.57 -457 240 s0 5319 6B Z75 58 6416 -616 320 69 68.41 58 Data continued on next page -

Appendix B March 2003 WCAP-I 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 , B-79 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-79 STANDARD REFERENCE MATERIAL CAPSULE 263 Page 2 Material SR11 SAM33BI Heat Number. A1008-1 Orientation. LT Capsule: 1f-263 Total Fluence Charpy V-Notch Data (Continued)

Temperature Input Lateral Expansion Computed LE Differential 350 69 6911 -11 375 74 69.32 4.67 425 68 69.43 -143 460 67 69.45 -Z45 SUM of RESIDUALS = 9.31 Appendix B March 2003 WCAP-16002 Revision 0

B-80 WESTINGHOUSE NON-PROPRIETARY CLASS 33 B-80 WESTINGHOUSE NON-PROPRIETARY CLASS STANDARD REFERENCE MATERIAL CAPSULE 263 CYGRAPH 41 Hyperbolic Tangent Curve Printed at 1625i4 on 10-01-2002 Page 1 Coefficients of Curve 2 =

l A = 50 B = 50 C = 874 TO = 2194 Equation is Shear/ = A + B t I tanh((T - T0)/C) I Temperature at 5Y/C Shear. 219B Material SRM SA533W1 Heat Number. A0061 Orientationr LT Capsule W-263 Total Fluence:

.4-a)

Cf) a-)

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant lF3 Cap: 11-263 Material: SRM SA533BI Ori: LT Heat I: A1003-1 Charpy V-Notch Data Temper, iture Input Percent Shear Computed Percent Shear Differential

-30 2 23 176 50 10 1.62 a37 125 20 917 102 175 25 2527 -27 200 30 3823 823 240 65 6L94 3.05 275 75 7913 -4J3 320 100 91114 815

- - Data continued on next page --

Appendix B March 2003 WCAP-l 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 B B-81 WESTINGHOUSE NON-PROPRIETARY CLASS 3 B-8 I STANDARD REFERENCE MATERIAL CAPSULE 263 Page 2 Materia 1:SRM SA533H1 Heat Number. A1008-1 Orientatiion- LT Capsule: W-263 Total Fluence Charpy V-Notch Data (Continued)

Temperature Input Percent Shear Computed Percent Shear Differential 350 100 9587 4J2 375 100 97.7 229 425 100 993 460 100 99.69 .3ft Su 1M of RESIDUALS = 26.95 Appendix B March 2003 WCAP-1 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 C-l WESTINGHOUSE NON-PROPRIETARY CLASS 3 C-I APPENDIX C Charpy V-Notch Shift Results for Each Capsule On the following pages are the Charpy V-notch shift results for each capsule based on using the Hyperbolic Tangent Curve-Fitting Method (CVGRAPH, Version 4.1).

Appendix C March 2003 WCAP-1 6002 Revision 0

C-2 WESTINGHOUSE NON-PROPRIETARY CLASS 3 Table C-1 Changes in Average 30 and 50 ft-lb Temperatures for Lower Shell Plate M-1004-2 (Longitudinal Orientation), CVGRAPH 4.1 Capsule Unirradiated CVGRAPH AT30 Unirradiated CVGRAPH Fit AT 5o T30 Fit T30 Tso T5o 970 -13.37°F -7.06°F 6.30F 11.76°F 20.42°F 8.70F 2630 - - - -- - -

Table C-2 Changes in Average 35 mil Lateral Expansion Temperatures and Average Energy Absorption at Full Shear for Lower Shell Plate M-1004-2 (Longitudinal Orientation),

CVGRAPH 4.1 Capsule Unirradiated T35 CVGRAPH AT35 Unirradiated CVGRAPH Fit AE Fit T35 Upper Shelf Upper Shelf Energy Energy 970 5.07°F 10.52°F 5.40F 170 ft-lb 155 ft-lb -15 ft-lb 263 -- -- I --

Table C-3 Changes in Average 30 and 50 ft-lb Temperatures for Lower Shell Plate M-1004-2 (Transverse Orientation), CVGRAPPH 4.1 Capsule Unirradiated T3 l CVGRAPH AT30 Unirradiated T5o CVGRAPH Fit ATso Fit T30o 970 -24.44°F 3.45°F 27.9 0F 2.89°F 33.1 0°F 30.20F 2630 -24.44°F -33.57°F -9.10F 2.89°F 11.01°F 8.1 OF Table C-4 Changes in Average 35 mil Lateral Expansion Temperatures for Lower Shell Plate M-1004-2 (Transverse Orientation), CVGRAPH 4.1 Capsule Unirradiated T35 CVGRAPH AT3s Unirradiated CVGRAPH Fit AE Fit T35 Upper Shelf Upper Shelf Energy Energy 970 -6.73°F 18.83°F 25.6 0F 141 ft-lb 124 ft-lb -17 ft-lb 2630 -6.73°F 9.81°F 16.5°F 141 ft-lb 131 ft-lb -10 ft-lb Appendix C March 2003 WCAP-I 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 C-3 C-3 WESTINGHOUSE NON-PROPRIETARY CLASS 3 Table C-5 Changes in Average 30 and 50 ft-lb Temperatures for Surveillance Weld Material, CVGRAPH 4.1 Capsule Unirradiated T~o CVGRAPH AT0 Unirradiated T~o CVGRAPH Fit AT50 Fit T3o T5o 970 -84.58 0 F -56.360 F 28.2 0 F -65.19 0 F -34.870 F 30.3 0F 2630 -84.58 0 F -77.71 OF 6.90F -65.19 0 F -51.380 F 13.8 0F Table C-6 Changes in Average 35 mil Lateral Expansion Temperatures and Average Energy Absorption at Full Shear for Surveillance Weld Material, CVGRAPH 4.1 Capsule Unirradiated T35 CVGRAPH AT35 Unirradiated CVGRAPH Fit AE Fit T35 Upper Shelf Upper Shelf

_____ __ __ __ ____ __ __ __ __ __ __ _ _ __ __ __ __E nergy E nergy _ _ _ _ _ _ _ _

970 -68.31 0F -39.630 F 28.70F 156 ft-lb 143 ft-lb -13 ft-lb 2630 -68.31 OF -46 800F 21.5 0F 156 ft-lb 145 ft-lb -11I ft-lb Table C-7 Changes in Average 30and 50ft-lb Temperatures for the Heat-Affected-Zone Material CVGRAPH 4.1 Capsule Unirradiated T~o CVGRAPH AT3o Unirradiated T5o CVGRAPH Fit ATso Fit T3o T5o 970 -1 17.090 F -103.49 0F 13.6 0F -90.080 F -71.83 0 F 18.2 0F 2630 -117.090 F -91.960 F 25.1 OF -90.080 F -62.15 0 F 27.9 0F Table C-8 Changes in Average 35 mil Lateral Expansion Temperatures and Average Energy Absorption at Full Shear for the Heat-Affected-Zone Material, CVGRAPH 4.1 Capsule Unirradiated T35 CVGRAPH AT 35 Unirradiated CVGRAPH Fit AE Fit T35 Upper Shelf Upper Shelf

___ __ __ ____ ____ __ __ __ __ __ __ _ _ __ __ __ __E nergy E nergy _ _ _ _ _ _ _ _

970 -89.55 0F -72.240 F 17.3 0F 170 ft-lb 156 ft-lb -14 ft-lb 2630 -89.55 0F -56.570 F 33.00F 170 ft-lb 163 ft-lb -7ft-lb Appendix C March 2003 WCAP-1 6002 Revision 0

C-4 WESTINGHOUSE NON-PROPRIETARY CLASS CLASS 33 CA WESTINGHOUSE NON-PROPRIETARY Table C-9 Changes in Average 30 and 50 ft-lb Temperatures for the Correlation Monitor Material HSST Plate 01, CVGRAPH 4.1 Capsule Unirradiated T30 CVGRAPH AT30 Unirradiated T50 CVGRAPH Fit AT5o Fit T30 Tso 970 -----

2630 34.31OF 184.87 0F 150.5 0F 60.02OF 211.360F 151.3 0F Table C-10 Changes in Average 35 mil Lateral Expansion Temperatures and Average Energy Absorption at Full Shear for the Correlation Monitor Material HSST Plate 01, CVGRAPH 4.1 Capsule Unirradiated T35 CVGRAPH AT3s Unirradiated CVGRAPH Fit AE Fit T35 Upper Shelf Upper Shelf Energy Energy 970 -_ _ -

2630 41.940 F 208.53 0F 166.6 0F 133 ft-lb 113 ft-lb -20 ft-lb Appendix C March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 D-l WESTINGHOUSE NON-PROPRIETARY CLASS 3 D- 1 APPENDIX D Waterford Unit 3 Surveillance Data Credibility Analysis Appendix D March 2003 WCAP-1 6002 Revision 0

D-2 WESTINGHOUSE NON-PROPRIETARY CLASS 3 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 two surveillance capsules removed from the Waterford Unit 3 reactor vessel. To use these surveillance data sets, they must be shown to be credible. In accordance with the discussion of Regulatory Guide 1.99, Revision 2, there are five requirements that must be met for the surveillance data to be judged credible.

The purpose of this evaluation is to apply the credibility requirements of Regulatory Guide 1.99, Revision 2, to the Waterford Unit 3 reactor vessel surveillance data and determine if the Waterford Unit 3 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, and plates or forgings) that directly surrounds the effective height of the active core and adjacent regions of the reactor vessel that are predicted to experience sufficient neutron radiation damage to be considered in the selection of the most limiting material with regard to radiation damage."

The Waterford Unit 3 reactor vessel consists of the following beltline region materials:

- Intermediate Shell Plates M-1003-1,2 and 3,

- Lower Shell Plates M-1004-1, 2 and 3,

- Intermediate-to-lower shell circumferential weld seam 101-171 (Heat 88114, Linde 0091)

- Intermediate shell plate longitudinal weld seams 101-124 A, B & C (Heat BOLA and HODA).

- Lower shell longitudinal weld seams 101-142A, B & C (Heat 83653, Linde 0091).

Per TR-C-MCS-001, "Summary Report on Manufacture of Test Specimens and Assembly of Capsules for Irradiation Surveillance of Waterford-Unit 3 Reactor Vessel Materials", the surveillance materials in the Appendix D March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 D-3 D-3 WESTINGHOUSE NON-PROPRIETARY CLASS 3 surveillance program are those judged most limiting. This is further demonstrated in the Nuclear Regulatory Commission's (NRC) Reactor Vessel Integrity Database (RVID), Version 2.01, in which the surveillance plate and weld are predicted to be the most limiting in terms of having the highest adjusted reference temperature after exposure to a neutron fluence of 3.68x1019 n/cm 2 .

Hence, Criterion I is met for the Waterford Unit 3 reactor vessel surveillance program materials.

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.

Plots of Charpy energy versus temperature for the unirradiated and irradiated condition are presented in Appendix B of this report. Based on engineering judgment, the scatter in the data presented in these plots is small enough to permit the determination of the 30 ft-lb temperature and the upper shelf energy of the Waterford Unit 3 surveillance materials unambiguously. Hence, the Waterford Unit 3 surveillance data meet this criterion.

Criterion 3: When there are two or more sets of surveillance data from one reactor, the scatter of ARTNDT values about a best-fit line drawn as described in Regulatory Position 2.1 normally should be less than 280 F for welds and 17'F for base metal. Even if the fluence range is large (two or more orders of magnitude), the scatter should not exceed twice those values.

Even if the data fail this criterion for use in shift calculations, they may be credible for determining decrease in upper shelf energy if the upper shelf can be clearly determined, following the definition given in ASTM El 85-82.

The functional form of the least squares method as described in Regulatory Position 2.1 will be utilized to determine a best-fit line for this data and to determine if the scatter of these ARTNDT values about this line is less than 280 F for the weld and less than 17'F for the plate.

Following is the calculation of the best fit line as described in Regulatory Position 2.1 of Regulatory Guide 1.99, Revision 2.

Appendix D March 2003 WCAP-1 6002 Revision 0

D-4 WESTINGHOUSE NON-PROPRIETARY CLASS 3 Table D-1 Waterford Unit 3 Surveillance Capsule Data Material Capsule Capsule f(a) FF(b) ARTNDT(c) FF*ARTNDT FF2 Lower Shell Plate 970 0.647 0.878 6 5.3 0.771 M-1004-2(a)

(Longitudinal)

SUM: 5.3 0.771 CFPlateRW = H(FF

RTNDT) . ( FF2 ) = (5.3) (0.771) = 6.9 'F Lower Shell 970 0.647 0.878 28 24.6 0.771 Plate M-1004-2 2630 1.45 1.103 0 ( 9d) 0 1.217 (Transverse)

SUM: 24.6 1.988 CFplateWR = (FF

RTNDT)

Z( FF2 ) = (24.6) * (1.988) = 12.4 0 F Surveillance Weld 970 0.647 0.878 28 24.6 .771 Material 2630 1.45 1.103 7 7.7 1.217 SUM: 32.3 1.988 CF Weld = Y(FF

RTNDT) .- ( FF 2 ) = (32.3 0 F) + (1.988) = 16.2 0 F Notes:

(a) f = calculated fluence from capsule 970 and 2630 analysis results, (x 1019 n/cm2 , E > 1.0 MeV).

(b) FF = fluence factor = P0 28 -0 llogf)

(c) ARTNDT values are the measured 30 ft-lb shift values taken from Table 5-10.

(d) Assume 00 F shift for negative measured value.

(e) No longitudinal base metal plate M-1004-2 specimens are in capsule 2630.

Appendix D March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 D-5 The scatter of ARTNDT values about the functional WESTINGHOUSE form of a best-fit NON-PROPRIETARY CLASSline 3drawn as described in RegulatoryD-5 The scatter of ARTNDT values about the functional form of a best-fit line drawn as described in Regulatory Position 2.1 is presented in Table D-2.

Table D-2 Best Fit Evaluation for Waterford Unit 3 Surveillance Materials Base Material CF FF Measured Best Fit' Scatter of < 171F (Base Metals)

(OF) ARTNDT ARTNDT ARTNDT < 280 F (Weld Metal)

(30 ft-lb) (`F) (OF)

(OF)

Lower Shell Plate 6.9 0.878 6 6 0 Not Applicable M-1004-2 (single measurementb)

(Longitudinal)

Lower Shell 12.4 0.878 28 11 17 Yes Plate M-1004-2 12.4 1.103 0C 14 14 Yes (Transverse)

Surveillance Weld 16.2 0.878 28 14 14 Yes Metal 16.2 1.103 7 18 11 Yes NOTES:

(a) Best Fit Line Per Equation 2 of Reg. Guide 1.99 Rev. 2 Position 1.1.

(b) Only one set of longitudinal orientation Charpy specimens from Capsule 97°.

(c) The measured Charpy 30 ft-lb shift was negative (-9 0F) which is a non-physical characteristic.

The scatter of the Charpy data in the lower shelf region (around 30 ft-lb) for the data set was about 25% to 30% of the measurement value, which could have contributed to the negative shift.

Additional analysis of two other indices (50 ft-lb and 35 mils LE) show the scatter was well within the permitted scatter of 17'F. Therefore, the measured Charpy 30 ft-lb shift of 0 0F is used for the analysis.

Table D-2 demonstrates that the measured shift values for the transverse orientation plate and for the weld are within the Ic scatter band (17'F for the plate and 28 0F for the weld). Therefore, the Waterford Unit 3 surveillance plate (transverse orientation) and 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 +1- 25 0F.

The capsule specimens are located in the reactor between the thermal shield and the vessel wall and are positioned opposite the center of the core. The test capsules are in baskets attached to the reactor vessel.

Appendix D March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 D-6 WESTINGHOUSE NON-PROPRIETARY CLASS 3 D-6 The location of the specimens with respect to the reactor vessel beltline provides assurance that the reactor vessel wall and the specimens experience equivalent operating conditions such that the temperatures vill not differ by more than 250 F. This is supported by the fact that the 5580 temperature monitors in the surveillance capsule melted but the 5790 temperature monitors did not. 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 Waterford Unit 3 surveillance program has correlation monitor material from HSST Plate OlMY.

NUREG/CR-6413 (ORNL/TM-13133) contains a plot of residual vs. fast neutron fluence for the correlation monitor materials from the HSST Program (Figure 11 in the NUREG report). This figure shows a 2o uncertainty of 50'F. The data used for this plot is contained in Table 14 (in the NUREG Report). The data from the Waterford Unit 3 Capsule 2630 are compared to the NUREG data trend in Table D-3.

Table D-3 Calculation of Residual vs. Fast Fluence Capsule Fluence Fluence Measured Shift RG 1.99 Shift Residual (x 1019 n/cm2 ) Factor (FF) (CF*FF)(a) (Meas.- RG Shift) 2630 1.45 J 1.103 150 145 5 (a) Per N URE(/CR-6413, URNLfIM-13133, the Cu and Ni values for the Correlation Monitor Material is 0.18 Cu and 0.66 Ni. This equates to a Chemistry Factor of 136.1 0 F from Reg. Guide 1.99 Rev. 2.

Table D-3 shows a difference of only 50 F. That is much less than the 2c uncertainty of 500 F, the allowable scatter in NUREG/CR-6413, ORNL/TM-13133. Hence, this criterion is met.

CONCLUSION:

Based on the preceding responses to all five criteria of Regulatory Guide 1.99, Revision 2, Section B and 10 CFR 50.61, the Waterford Unit 3 surveillance data meet credibility requirements 1,2, 3, 4 and 5 of Regulatory Guide 1.99, Revision 2. Meeting these five criteria permits the use of the derived Chemistry Factors of 12.4°F for the transverse orientation plate and 16.2°F for the weld, and permits the use of half the normal value of crA for predicting shift.

Appendix D March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 E-l WESTINGHOUSE NON-PROPRIETARY CLASS 3 E- 1 APPENDIX E VALIDATION OF THE RADIATION TRANSPORT MODELS BASED ON NEUTRON DOSIMETRY MEASUREMENTS Appendix E March 2003 WCAP-16002 Revision 0

E-2 WESTINGHOUSE NON-PROPRIETARY CLASS 3 E. 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 Waterford Unit 3 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."'[E-1 One of the main purposes for presenting this material is to demonstrate that the overall measurements agree with the calculated and least squares adjusted values to within +/- 20% as specified by Regulatory Guide 1.190, thus serving to validate the calculated neutron exposures previously reported in Section 6.2 of this report. This information may also be useful in the future, in particular, as least squares adjustment techniques become accepted in the regulatory environment.

E.1.1 Sensor Reaction Rate Determinations In this section, the results of the evaluations of the two neutron sensor sets withdrawn to date as a part of the Waterford Unit 3 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:

Equivalent Withdrawal Irradiation Capsule ID Azimuthal Time Time [EFPY]

Location W-97 70 End of Cycle 4 4.41 W-263 70 End of Cycle 11 13.83 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 W-97 and W-263 are summarized as follows:

Reaction Sensor Material Of Interest Capsule W-97 Capsule W-263 63 Copper Cu(nxa) 6 Co X X Iron 54 Fe(np)4 Mn X X Nickel "Ni(n,p)"Co X X Titanium 6 46 Ti(np) Sc X X Uranium-238* 238U(nf)137 Cs X X Cobalt-Aluminum* "Co(n,y)Co X X

These measurements include both bare and cadmium-covered sensors.

With regard to the neutron sensors listed above, it should be recognized that both of these capsules also contained sulfur sensors as well. The reaction of interest in these sensors is 3 2S(np)3 2 P; however, due to the short half-life of 32p (14.28 days), this reaction was not measured for Capsule W-263 as part of the present evaluation, nor for Capsule W-97 as reported in Reference E-2. Further note that the bare uranium sensor measurements for Capsules W-97 and W-263 were excluded from this assessment. The Appendix E March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 E-3 WESTINGHOUSE NON-PROPRIETARY CLASS 3 E-3 bare 23 8 U(n,f) measurement is dominated by contributions from thermal neutron reactions in 235U impurities. These thermal contributions add significant uncertainty to the determination of the 2 3 8 U(n,f) reaction rate. The cadmium-covered 238U sensor provides greater accuracy for the measurement of this fast neutron reaction.

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

the measured specific activity of each monitor,

the physical characteristics of each monitor,

the operating history of the reactor,

the energy response of each monitor, and

the neutron energy spectrum at the monitor location.

The radiometric counting of the neutron sensors from Capsule W-97 was carried out by Babcock &

Wilcox (B&W).[E-2] The radiometric counting of the sensors from Capsule W-263 was completed at the Pace Analytical Services Laboratory located at the Westinghouse Waltz Mill Site. In all cases, the radiometric counting followed established ASTM procedures. Following sample preparation and weighing, the specific activity of each sensor was determined by means of a high-resolution gamma spectrometer. For the copper, iron, nickel, titanium, and cobalt-aluminum sensors, these analyses were performed by direct counting of each of the individual samples. In the case of the uranium fission sensors, the analyses were carried out by direct counting preceded by dissolution and chemical separation of cesium from the sensor material.

The irradiation history of the reactor over the irradiation periods experienced by Capsules W-97 and W-263 was based on the reported monthly power generation of Waterford Unit 3 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 W-97 and W-263 is given in Table E-2.

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

A R=

No F Y X p Cj [I - e-h'] [e-Atd Pref Appendix E March 2003 WCAP-16002 Revision 0

E-4 WESTINGHOUSE NON-PROPRIETARY CLASS 3 E-4 WESTINGHOUSE NON-PROPRIETARY CLASS 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.

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

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

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

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

t = Length of irradiation period j (sec).

td = Decay time following irradiation periodj (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 C,, 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, C, is normally taken to be 1.0. However, for multiple-cycle irradiations, particularly those employing low leakage fuel management, the additional C, 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 E-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.

Preliminary calculations for the reactions whose products have short half-lives indicated that C, factors based on cycle average flux values were not appropriate due to a substantial increase in peripheral power from beginning to end of the fuel cycle. The effect of this power change was accounted for by subdividing the cycles immediately preceding the capsule withdrawal (4 and 11) into thirds. This approach better defines the irradiation conditions for the sensors with short half-life reaction products.

Prior to using the measured reaction rates in the least-squares evaluations of the dosimetry sensor sets, 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 sensor reaction rates to account for gamma ray induced fission Appendix E March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 E-5 WESTINGHOUSE NON-PROPRIETARY CLASS 3 E-5 reactions that occurred over the course of the capsule irradiations. The correction factors applied to the Waterford Unit 3 fission sensor reaction rates are summarized as follows:

Correction Capsule W-97 Capsule W-263 23 5U Impurity/Pu Build-in 0.860 0.827 238 U(y,f) 0.872 0.875 Net 238U Correction 0.750 0.724 These factors were applied in a multiplicative fashion to the decay corrected uranium fission sensor reaction rates.

Results of the sensor reaction rate determinations for Capsules W-97 and W-263 are given in Table E-4.

In Table E-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, and gamma ray induced fission effects.

Examination of the Table E-4 results revealed that the average cadmium covered uranium fission monitor reaction rate for Capsule W-263 was more than 500% lower than Capsule W-97. Due to the fact that these two capsules were irradiated in symmetrically equivalent locations and the half-life of cesium-137 is 30.07 years, the measured reaction rate for the fission monitors in Capsule W-263 should be greater than Capsule W-97. Based on this observation, the cadmium-covered uranium measurements for Capsule W-263 was rejected; i.e., it was not utilized in the least squares adjustment calculation for these capsules.

E.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, R. ++/-5R,=+/-E+/-ig+/-ug)(8bg+/-g )

g relates a set of measured reaction rates, R., to a single neutron spectrum, fg, through the multigroup dosimeter reaction cross-section, crg, each with an uncertainty 6. The primary objective of the least squares evaluation is to produce unbiased estimates of the neutron exposure parameters at the location of the measurement.

For the least squares evaluation of the Waterford Unit 3 surveillance capsule dosimetry, the FERRET code[E-3] 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 MeV) and dpa) along with associated uncertainties for the two in-vessel capsules withdrawn to date.

Appendix E March 2003 WCAP-16002 Revision 0

E-6 WESTINGHOUSE NON-PROPRIETARY CLASS 3 The application of the least squares methodology requires the following input:

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

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

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

For the Waterford Unit 3 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 E. 1.1.

The dosimetry reaction cross-sections and uncertainties were obtained from the Sandia National Laboratory Radiation Metrology Laboratory (SNLRML) dosimeter cross-section library[EA4J. The SNLRML library is an evaluated dosimetry reaction cross-section compilation recommended for use in LWR evaluations byASTM Standard E1018, "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 Waterford Unit 3 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 6 3 Cu(n,a) 60 Co 5%

54 Fe(n,p)54Mn 5%

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

46 Ti(n,p)46Sc 5%

23U(n,f) 37 Cs 10%

5 9Co(n,y)60Co 5%

These uncertainties are given at the Ic level.

Dosimetry Cross-Section Uncertainties The reaction rate cross-sections used in the least squares evaluations were taken from the SNLRML library. This data library provides reaction cross-sections and associated uncertainties, including Appendix E March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 E-7 WESTINGHOUSE NON-PROPRIETARY CLASS 3 E-7 covariances, for 66 dosimetry sensors in common use. Both cross-sections and uncertainties are provided in a fine multigroup structure for use in least squares adjustment applications. These cross-sections were compiled from the most recent cross-section evaluations and they have been tested with respect to their accuracy and consistency for least squares evaluations. Further, the library has been empirically tested for use in fission spectra determination as well as in the fluence and energy characterization of 14 MeV neutron sources.

For sensors included in the Waterford Unit 3 surveillance program, the following uncertainties in the fission spectrum averaged cross-sections are provided in the SNLRML documentation package.

Reaction Uncertainty "Cu(n,a)"Co 4.084.16%

14Fe(np)4 Mn 3.05-3.1 1%

"Ni(n,p)"Co 4.494.56%

16 Ti(np)4 6 Sc 4.514.87%

238 U(n,f)13 7 Cs 0.54-0.64%

5 9Co(n,y) 60Co 0.79-3.59%

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

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

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

Mgg. = R'g g

Pgg.

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

P =[1- , + Oe H where H= (g-g')

2y 2 The first term in the correlation matrix equation specifies purely random uncertainties, while the second term describes the short-range correlations over a group range y (0 specifies the strength of the latter term). The value of 5 is 1.0 when g = g', and is 0.0 otherwise.

Appendix E March 2003 WCAP-16002 Revision 0

E-E WESTINGHOUSE NON-PROPRIETARY CLASS 3 The set of parameters defining the input covariance matrix for the Waterford Unit 3 calculated spectra was as follows:

Flux Normalization Uncertainty (Re,) 15%

Flux Group Uncertainties (R., 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<0.68eV) 2 E.1.3 Comparisons of Measurements and Calculations Results of the least squares evaluations of the dosimetry from the Waterford Unit 3 surveillance capsules withdrawn to date are provided in Tables E-5 and E-6. In Table E-5, measured, calculated, and best-estimate values for sensor reaction rates are given for each capsule. Also provided in this tabulation are ratios of the measured reaction rates to both the calculated and least squares adjusted reaction rates.

These ratios of M/C and M/BE illustrate the consistency of the fit of the calculated neutron energy spectra to the measured reaction rates both before and after adjustment. In Table E-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 E-5 and E-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 I cr level. From Table E-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 5-6% for iron atom displacement rate. Again, the uncertainties from the least squares evaluation are at the Ia level.

Further comparisons of the measurement results with calculations are given in Tables E-7 and E-8. These comparisons are given on two levels. In Table E-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 Appendix E March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 E-9 energy spectra. In Table E-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.

It should be noted that although comparisons between the measured and calculated values for the 46 Ti sensors are included in Table E-7, they were not used in determining the average measurement to calculation (MIC) ratio since a bias exists in the SNLRML cross section for the 4 6 Ti(n,p) reaction. This bias may be observed in the data contained in ASTM Standard Practice E26 1, "Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques." Specifically, Table 3 of ASTM E261 indicates that the sum in quadrature of the experimental uncertainty and the calculated uncertainty for 4 6 Ti(np) 4 6Sc in the 235U thermal fission field is 6.86%. Also indicated in the same table is the ratio of the calculated cross-section to the experimentally measured cross section (C/E) that is given as 0.899. Since the difference between the calculated and measured cross-section is greater than the uncertainties involved supports the hypothesis that the calculated cross-section is biased low.

In the case of the direct comparison of measured and calculated sensor reaction rates, the M/C comparisons for fast neutron reactions range from 0.76-1.23 for the 7 samples included in the data set.

The overall average M/C ratio for the entire set of Waterford Unit 3 data is 1.04 with an associated standard deviation of 14.7%.

In the comparisons of best estimate and calculated fast neutron exposure parameters, the corresponding BE/C comparisons for the capsule data sets range from 0.93-1.14 for neutron flux (E > 1.0 MeV) and from 0.95 to 1.12 for iron atom displacement rate. The overall average BE/C ratios for neutron flux (E > 1.0 MeV) and iron atom displacement rate are 1.04 with a standard deviation of 14.4% and 1.04 with a standard deviation of 12.0%, respectively.

Based on these comparisons, it is concluded that the calculated fast neutron exposures provided in Section 6.2 of this report are validated for use in the assessment of the condition of the materials comprising the beltline region of the Waterford Unit 3 reactor pressure vessel.

Appendix E References E-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.

E-2. BAW-2177, "Analysis of Capsule W-97, Entergy Operations, Inc., Waterford Generating Station, Unit No. 3," A. L. Lowe Jr., et al., November 1992.

E-3. A. Schmittroth, FERRET Data Analysis Core, HEDL-TME 79-40, Hanford Engineering Development Laboratory, Richland, WA, September 1979.

E-4. RSIC Data Library Collection DLC-178, "SNLRML Recommended Dosimetry Cross-Section Compendium", July 1994.

Appendix E March 2003 WCAP-16002 Revision 0

E-10 WESTINGHOUSE NON-PROPRIETARY CLASS 3 Table E-1 Nuclear Parameters Used In The Evaluation Of Neutron Sensors Target 90% Response Fission Monitor Reaction of Atom Range (MeV) Product Yield Material Interest Fraction Half-life (%)

Copper 63 Cu (no) 0.6917 5.0- 12.0 5.271 y Iron 54 Fe (n,p) 0.0585 2.4-8.8 312.3 d Nickel "Ni (n,p) 0.6808 2.1 -8.8 70.82 d 46 Titanium Ti (n,p) 0.0825 4.1 - 10.5 8.379 d 238U (n,f)

Uranium-238 1.0000 1.5 - 7.9 30.07 y 6.02 Cobalt-Aluminum "Co (n,y) 0.0017 non-threshold 5.271 y Notes: The 90% response range is defined such that, in the neutron spectrum characteristic of the Waterford Unit 3 surveillance capsules located at 70 from the core cardinal axes, 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.

The counting results identified by B&W for the Capsule W-97 reactions were reported in Reference E-2 based on the weight of the target material in the sample rather than the total weight of the dosimeter material. As a result, the target atom fraction used in the analysis of the Capsule W-97 sensors was unity.

Appendix E March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 g E-11 E- 11 WESTINGHOUSE NON-PROPRIETARY CLASS 3 Table E-2 Monthly Thermal Generation During the First Eleven Fuel Cycles of The Waterford Unit 3 Reactor (Reactor Power of 3390 MWt)

Thermal Thermal Thermal Generation Generation Generation Year Month (MWt-hr) Year Month (MWt-hr) Year Month (MWt-hr) 1985 3 42830 1988 1 2143917 1991 I 2515171 1985 4 613673 1988 2 2339100 1991 2 2211690 1985 S 809488 1988 3 2298501 1991 3 1196293 1985 6 198642 1988 4 76267 1991 4 0 1985 7 846176 1988 S 3254 1991 5 163566 1985 8 0 1988 6 1934985 1991 6 2275493 1985 9 317589 1988 7 2304929 1991 7 2453834 1985 10 1581557 1988 8 2509305 1991 8 2389958 1985 11 2319818 1988 9 2107712 1991 9 2435284 1985 12 1423475 1988 10 1509724 1991 10 2522290 1986 1 2313146 1988 11 1052050 1991 11 2256967 1986 2 2236098 1988 12 2282880 1991 12 2500136 1986 3 551214 1989 1 2231876 1992 1 2517213 1986 4 2380512 1989 2 2264143 1992 2 1649550 1986 5 2337147 1989 3 2458113 1992 3 2284044 1986 6 2345202 1989 4 2418581 1992 4 2429922 1986 7 1646157 1989 5 2509484 1992 5 2418613 1986 8 2497833 1989 6 2390707 1992 6 2436179 1986 9 2198347 1989 7 2292538 1992 7 2400380 1986 10 2206239 1989 8 2249799 1992 8 2476631 1986 11 2009429 1989 9 1783533 1992 9 1417812 1986 12 0 1989 10 0 1992 10 0 1987 1 0 1989 11 640027 1992 11 1581907 1987 2 1379459 1989 12 2444128 1992 12 2505327 1987 3 2149043 1990 I 1787064 1993 I 2514707 1987 4 2257170 1990 2 1612051 1993 2 2271376 1987 5 2278405 1990 3 2271449 1993 3 2373995 1987 6 2426725 1990 4 2433315 1993 4 2433762 1987 7 2489860 1990 S 2499444 1993 5 2518857 1987 8 2332754 1990 6 2434503 1993 6 2310136 1987 9 1406064 1990 7 2508532 1993 7 2513308 1987 10 1734107 1990 8 2333299 1993 8 2517897 1987 11 2418833 1990 9 2363915 1993 9 2431720 1987 12 2224789 1990 10 1728843 1993 10 2519890 1990 11 2433754 1993 11 2437790 1990 12 2516099 1993 12 2517986 Appendix E March 2003 WCAP-1 6002 Revision 0

E-12 WESTINGHOUSE NON-PROPRIETARY CLASS 3 E-12 WESTINGHOUSE NON-PROPRIETARY CLASS 3 Table E-2 (cont'd)

Monthly Thermal Generation During the First Eleven Fuel Cycles of The Waterford Unit 3 Reactor (Reactor Power of 3390 MWt)

Thermal Thermal Thermal Generation Generation Generation Year Month (MWt-hr) Year Month (MWt-hr) Year Month (MWt-hr) 1994 1 2517230 1997 1 2520469 2000 1 2513887 1994 2 2273776 1997 2 2273932 2000 2 2358614 1994 3 318321 1997 3 2520600 2000 3 2346459 1994 4 433275 1997 4 886717 2000 4 2436564 1994 5 2515334 1997 5 0 2000 5 2521322 1994 6 2306353 1997 6 0 2000 6 1873406 1994 7 2518426 1997 7 99594 2000 7 2521097 1994 8 2514659 1997 8 2505653 2000 8 2521192 1994 9 2430858 1997 9 2439155 2000 9 2436861 1994 10 2518011 1997 10 2523657 2000 10 1051538 1994 11 2439425 1997 11 2433511 2000 11 1030289 1994 12 2515464 1997 12 2433511 2000 12 2517757 1995 1 2517937 1998 1 2513765 2001 1 2521026 1995 2 2273361 1998 2 2276816 2001 2 2121310 1995 3 2516977 1998 3 2520985 2001 3 2520656 1995 4 2436285 1998 4 2436390 2001 4 2436332 1995 5 2518637 1998 5 2503708 2001 5 2518333 1995 6 839448 1998 6 2439738 2001 6 2367725 1995 7 2521005 1998 7 2283997 2001 7 2521008 1995 8 2521249 1998 8 2521163 2001 8 2521122 1995 9 1774478 1998 9 1029804 2001 9 2434974 1995 10 0 1998 10 2456652 2001 10 2520999 1995 11 1929688 1998 11 1396144 2001 11 2439796 1995 12 2517767 1998 12 2262325 2001 12 2520997 1996 1 2517086 1999 1 2486638 2002 1 2518017 1996 2 2357937 1999 2 1291559 2002 2 2277045 1996 3 2516925 1999 3 0 2002 3 1704398 1996 4 2436647 1999 4 2183602 1996 5 2326692 1999 S 2513051 1996 6 2440018 1999 6 2244073 1996 7 1247706 1999 7 2521175 1996 8 2105079 1999 8 1808465 1996 9 2396700 1999 9 880564 1996 10 2471709 1999 10 2524076 1996 11 2295324 1999 11 2080135 1996 12 2449101 1999 12 2370546 Appendix E March 2003 WCAP-16002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 E-13 WESTINGHOUSE NON-PROPRIETARY GLASS 3 El 3 Table E-2 (cont'd)

Monthly Thermal Generation During the First Eleven Fuel Cycles of The Waterford Unit 3 Reactor (Reactor Power of 3390 MWt)

Thermal Thermal Thermal Generation Generation Generation Year Month (MWt-hr) Year Month (MWt-hr) Year Month (MWt-hr) 1994 I 2517230 1997 l 2520469 2000 1 2513887 1994 2 2273776 1997 2 2273932 2000 2 2358614 1994 3 318321 1997 3 2520600 2000 3 2346459 1994 4 433275 1997 4 886717 2000 4 2436564 1994 5 2515334 1997 5 0 2000 5 2521322 1994 6 2306353 1997 6 0 2000 6 1873406 1994 7 2518426 1997 7 99594 2000 7 2521097 1994 8 2514659 1997 8 2505653 2000 8 2521192 1994 9 2430858 1997 9 2439155 2000 9 2436861 1994 10 2518011 1997 10 2523657 2000 10 1051538 1994 11 2439425 1997 11 2433511 2000 11 1030289 1994 12 2515464 1997 12 2433511 2000 12 2517757 1995 1 2517937 1998 1 2513765 2001 I 2521026 1995 2 2273361 1998 2 2276816 2001 2 2121310 1995 3 2516977 1998 3 2520985 2001 3 2520656 1995 4 2436285 1998 4 2436390 2001 4 2436332 1995 5 2518637 1998 5 2503708 2001 5 2518333 1995 6 839448 1998 6 2439738 2001 6 2367725 1995 7 2521005 1998 7 2283997 2001 7 2521008 1995 8 2521249 1998 8 2521163 2001 8 2521122 1995 9 1774478 1998 9 1029804 2001 9 2434974 1995 10 0 1998 10 2456652 2001 10 2520999 1995 11 1929688 1998 11 1396144 2001 11 2439796 1995 12 2517767 1998 12 2262325 2001 12 2520997 1996 I 2517086 1999 I 2486638 2002 I 2518017 1996 2 2357937 1999 2 1291559 2002 2 2277045 1996 3 2516925 1999 3 0 2002 3 1704398 1996 4 2436647 1999 4 2183602 1996 S 2326692 1999 5 2513051 1996 6 2440018 1999 6 2244073 1996 7 1247706 1999 7 2521175 1996 8 2105079 1999 8 1808465 1996 9 2396700 1999 9 880564 1996 10 2471709 1999 10 2524076 1996 11 2295324 1999 1 2080135 1996 12 2449101 1999 12 2370546 Appendix E March 2003 WCAP-1 6002 Revision 0

E-14 WESTINGHOUSE NON-PROPRIETARY CLASS 3 E-1 4 WESTINGHOUSE NON-PROPRIETARY CLASS 3 Table E-3 Calculated Cj Factors at the Surveillance Capsule Center Core Midplane Elevation 4(E > 1.0 MeV) [n/cm2 s] l Fuel Capsule Capsule Capsule Capsule Cycle W-97 W-263 W-97 W-263 I 5.62E+10 5.62E+10 1.233 1.691 2 4.37E+10 4.37E+I0 0.958 1.313 3 4.38E+10 4.38E+10 0.961 1.318 4 BOL 3.80E+10 3.80E+10 0.834 1.144 4 MOL 3.88E+10 3.88E+10 0.852 1.168 4 EOL 4.23E+10 4.23E+10 0.927 1.271 5 3.98E+10 1.198 6 3.90E+l0 1.173 7 2.13E+I0 0.640 8 2.60E+I0 0.783 9 2.50E+10 0.752 10 2.38E+10 0.715 11 BOL 1.74E+10 0.524 11 MOL 1.83E+10 0.549 11 EOL 2.09E+10 0.629 Average 4.56E+10 3.32E+10 1.000 1.000

Note: Cj factors based on the ratio of the cycle specific fast (E > 1.0 MeV) neutron flux divided by the average flux over the total irradiation period were deemed unsuitable for Capsule W-263 since individual reaction rates did not vary proportionally with the fast flux. As a result of this observation, the Cj terms that were utilized in the final analyses for both Capsules W-97 and W-263 were based on the individual reaction rates determined from the synthesized transport calculations. The final Cj terms, which are based on individual reaction rates, are reported on the following pages of this table.

Appendix E March 2003 WCAP-I 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 E-15 WESTINGHOUSE NON-PROPRIETARY CLASS 3 13-15 Table E-3 cont'd Calculated Cj Factors at the Surveillance Capsule Center Core Midplane Elevation (Capsule W-97)

Fuel CapsuleW-97 Reaction Rates rps/atomL 6 3Cu Cycle (n,a) 54Fe (n,p) Ni (np) 46 Ti (n,p) 'ZiU (n,f) 59 Co (n, y) l 59 Co (n,,y) Cd 1 7.74E-17 7.15E-15 9.34E-15 1.31E-15 2.49E-14 3.10E-12 6.20E-13 2 6.21E-17 5.63E-15 7.35E-15 1.04E-15 1.94E-14 2.3613-12 4.76E-13 3 6.24E-17 5.65E-15 7.38E-15 1.05E-15 1.95E-14 2.37E-12 4.77E-13 4 BOL 5.43E-17 4.91E-15 6.41E-15 9.11E-16 1.69E-14 2.06E-12 4.15E-13 4 MOL 5.56E-17 5.02E-15 6.55E-15 9.33E-16 1.73E-14 2.10E-12 4.23E-13 4 EOL 6.0613-17 5.47E-15 7.13E-15 1.02E-15 1.88E-14 2.28E-12 4.6013-13 Avg 6.43E-17 5.86E-15 7.65E1-15 1.08E-15 2.02E-14 2.48E-12 4.99E-13 Fuel Capsule W-97 Cj Cycle 6 3Cu (n,ca) 54 Fe (n,p) 5Ni (n,p) 46Ti (n,p) 238U (nf) 5 9Co (n,y) 59Co (n,y) Cd 1 1.202 1.220 1.221 1.210 1.229 1.251 1.244 2 0.965 0.961 0.961 0.963 0.959 0.953 0.955 3 0.969 0.965 0.964 0.968 0.962 0.955 0.957 4 BOL 0.843 0.837 0.837 0.841 0.835 0.830 0.832 4 MOL 0.864 0.856 0.856 0.860 0.853 0.845 0.848 4 EOL 0.942 0.933 0.932 0.937 0.929 0.919 0.922 Avg. 1.000 1.000 1.000 1.000 1.000 1.000 1.000 Appendix E March 2003 WCAP-I 6002 Revision 0

E-16 WESTINGHOUSE NON-PROPRIETARY CLASS 3 Table E-3 (cont'd)

Calculated Cj Factors at the Surveillance Capsule Center Core Midplane Elevation (Capsule W-263)

Fuel Capsule W-263 Reaction Rates [rps/atomI Cycle 63 Cu (n,a) 54Fe (n,p) 58Ni (n,p) 4 6Ti (n,p) 2 38U (nf) 59Co (ny) ' 9Co (ny) Cd I 7.74E-17 7.15E-15 9.34E-15 1.31E-15 2.49E-14 3.10E-12 6.20E-13 2 6.21E-17 5.63E-15 7.35E-15 1.04E-15 1.94E- 14 2.36E-12 4.76E-13 3 6.24E-17 5.65E-15 7.38E-15 1.OSE-15 1.95E-14 2.37E-12 4.77E-13 4 BOL 5.43E-17 4.91E-15 6.41E-15 9.11E-16 1.69E-14 2.06E-12 4.15E-13 4 MOL 5.56E-17 5.02E-15 6.55E-15 9.33E-16 1.73E-14 2.1OE-12 4.23E-13 4 EOL 6.06E-17 5.47E-15 7.13E- 15 1.02E-15 1.88E-14 2.28E-12 4.60E-13 S 5.70E-17 5.15E-15 6.72E-15 9.56E-16 1.77E-14 2.15E-12 4.34E-13 6 5.62E-17 5.07E-15 6.61 E-15 9.43E-16 1.74E-14 2.08E-12 4.20E-13 7 3.26E-17 2.83E-15 3.69E-15 5.38E-16 9.54E-15 1.1OE-12 2.25E-13 8 3.94E-17 3.45E-15 4.49E-15 6.53E-16 1.17E-14 1.35E-12 2.76E-13 9 3.83E-17 3.33E-15 4.34E-15 6.33E-16 1.12E-14 1.30E-12 2.64E-13 10 3.64E-17 3.16E-15 4.11E-15 6.01E-16 1.07E-14 1.23E-12 2.53E-13 11 BOL 2.71E-17 2.34E-15 3.04E-15 4.46E-16 7.83E-IS 8.96E-13 1.83E-13 11 MOL 2.83E-17 2.44E-15 3.18E-15 4.66E-16 8.20E-I5 9.42E-13 1.92E-13 11 EOL 3.22E-17 2.79E-15 3.63E-15 5.31 E-16 9.39E-I S 1.08E-12 2.21E-13 Avg 4.85E-17 4.33E-15 5.65E-15 8.1OE-16 1.48E-14 1.77E-12 3.59E-13 Fuel Casule W-26_ C Cycle 63 Cu (n,a) 54Fe (n,p) 58Ni (n,p) 46Ti (n,p) 238U (nf) 5 9Co (n,y) ' 9 Co (n,y) Cd 1 1.596 1.651 1.654 1.619 1.679 1.749 1.729 2 1.282 1.300 1.301 1.289 1.309 1.333 1.327 3 1.288 1.305 1.306 1.295 1.314 1.336 1.331 4 BOL 1.120 1.133 1.134 1.125 1.141 1.160 1.157 4 MOL 1.147 1.159 1.159 1.152 1.165 1.182 1.179 4 EOL 1.251 1.262 1.263 1.255 1.268 1.285 1.282 5 1.176 1.189 1.189 1.181 1.195 1.212 1.209 6 1.160 1.169 1.170 1.164 1.172 1.172 1.171 7 0.672 0.653 0.652 0.664 0.644 0.622 0.627 8 0.813 0.796 0.795 0.806 0.787 0.764 0.768 9 0.790 0.768 0.767 0.781 0.757 0.731 0.736 10 0.751 0.729 0.728 0.742 0.719 0.693 0.704 11 BOL 0.559 0.539 0.538 0.551 0.529 0.506 0.510 11 MOL 0.584 0.564 0.563 0.576 0.554 0.531 0.536 11 EOL 0.665 0.644 0.642 0.656 0.633 0.611 0.615 Avg. 1.000 1.000 1.000 1.000 1.000 1.000 1.000 Appendix E March 2003 WCAP-1 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 E-17 E-17 WESTINGHOUSE NON-PROPRIETARY CLASS 3 Table E-4 Measured Sensor Activities And Reaction Rates Surveillance Capsule W-97 Measured Saturated Reaction Activity Activity Rate Reaction Location (dps/k) (dps/g) (rps/atom)

"Cu (n,a) 60Co (Cd) Top 3.15E+05 7.72E+05 8.07E-17 Middle 2.93E+05 7.18E+05 7.51E-17 Bottom 3.22E+05 7.89E+05 8.25E-17 Average 7.94E-17 14Fe (n,p) 14Mn Top 5.41 E+07 6.931E+07 6.21E-15 Middle 5.08E+07 6.501E+07 5.83E-15 Bottom 5.35E+07 6.85E+07 6.14E-15 Average 6.06E-15 Ni (n,p) "Co (Cd) Top 6.69E+07 7.64E+07 7.35E-15 Middle 6.54E+07 7.47E+07 7.18E-15 Bottom 7.14E+07 8.15E+07 7.84E-15 Average 7.46E-15 46Ti (np) 46Sc Top 1.23E+07 1.41 E+07 1.08E-15 Middle 1.31 E+07 1.51 E+07 1.15E-15 Bottom 1.52E+07 1.75E+07 1.33E-15 Average 1.19E-15 238U (nf) 137 Cs (Cd) Top 2.94E+05 3.09E+06 2.03E-14 Middle 2.94E+05 3.09E+06 2.03E-14 Bottom 3.12E+05 3.28E+06 2.15E-14 Average 2.07E-14 238U (nf) 137 CS (Cd) Including 235 u, 239pu, and y, fission corrections. 1.55E-14 "Co (n,y) 60Co Top 1.61E+10 3.97E+10 3.88E-12 Middle 1.81 E+I 0 4.46E+ 10 4.36E-12 Bottom 1.44E+10 3.55E+10 3.47E-12 Average 3.90E-12 59Co (n,,y) 60Co (Cd) Top 1.91 E+09 4.70E+09 4.60E-13 Middle 1.64E+09 4.04E+09 3.95E-13 Bottom 1.84E+09 4.53E+09 4.43E-13 Average 4.33E-13 Notes: 1) Measured specific activities are indexed to a counting date of March 15, 1991.

2) The average 238U (n,f) reaction rate of 6.44E-14 includes a correction factor of 0.860 to account for plutonium build-in and an additional factor of 0.872 to account for photo-fission effects in the sensor.

Appendix E March 2003 WCAP-1 6002 Revision 0

E-18 WESTINGHOUSE NON-PROPRIETARY CLASS 3 13-18 WESTINGHOUSE NON-PROPRIETARY CLASS 3 Table E-4 cont'd Measured Sensor Activities And Reaction Rates Surveillance Capsule W-263 Measured Saturat(ted Reaction Activity Activit ty Rate Reaction Location (dps/g) (dps/z (rps/atom) 63 Cu (n,ax) "Co (Cd) Top 2.36E+05 3.8 1E+(-05 5.82E-17 Middle 1.69E+05 2.73E+(-05 4.1713-17 Bottom 1.98E+05 3.20E+(-05 4.88E-17 Average 4.96E-17 54 Fe (n,p) 54Mn Top 1.42E+06 3.14E+(-06 4.98E-15 Middle 1.36E+06 3.01E+(-06 4.77E-1 5 Bottom 1.33E+06 2.94E+(-06 4.67E-15 Average 4.81E-15 58 Ni (np) 5"Co (Cd) Top 8.83E+06 4.85E+(-07 6.94E-15 Middle 8.27E+06 4.54E+(-07 6.50E-15 Bottom 8.31 E+06 4.56E+(*07 6.53E-15 Average 6.66E-15 46Ti (np) 46Sc Top 2.22E+05 9.94E+(05 9.57E-16 Middle 2.12E+05 9.49E+(05 9.14E-16 Bottom 2.06E+05 9.22E+(05 8.8813-16 Average 9.20E-16 238U (n,f) '3Cs (Cd) Top 2.45E+05 9.58E+05 6.29E- 15 Middle 6.76E+04 2.64E+05 1.74E- 15 Bottom 1.28E+05 5.01E+05 3.29E-15 Average 3.77E-15 238U (nf) '37Cs (Cd) Including 2 35u, 239pu, and y, fission corrections. 2.73E-15 59Co (n,y) 6 0Co Top 2.45E+07 4.1 013+07 2.36E-12 Middle 2.4113+07 4.04E+07 2.32E-12 Bottom 1.96E+07 3.28E+07 1.89E-12 Average 2.19E-12 "Co (n,,y) 6 0Co (Cd) 3.04E+06 5.07E+06 2.9213-13 Top Middle 3.1 1lE+06 5.1913+06 2.9913-13 Bottom 3.04E+06 5.07E+06 2.9213-13 Average 2.94E-13 Notes: 1) Measured specific activities are indexed to a counting date of July 25, 2002.

2) The average 238U (n,f) reaction rate of 6.4413-14 includes a correction factor of 0.827 to account for plutonium build-in and an additional factor of 0.875 to account for photo-fission effects in the sensor.

Appendix E March 2003 WCAP-1 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 E-19 WESTINGHOUSE NON-PROPRIETARY CLASS 3 E-1 9 Table E-5 Comparison of Measured, Calculated, and Best Estimate Reaction Rates At The Surveillance Capsule Center Capsule W-97 Reaction Rate [ros/atoml Best Reaction Measured Calculated Estimate M/C M/BE 63 Cu(n,a) 60Co (Cd) 7.94E-17 6.45E-17 7.58E-17 1.23 1.05 54 Fe(n,) 5 4 Mn 6.06E-15 5.86E-15 6.05E-15 1.03 1.00 "Ni(n,p) Co (Cd) 7.46E-15 7.66E-15 7.74E-15 0.97 0.96 46 4Ti(np) Sc 1.19E-15 1.02E-15 1.14E-15 1.17 1.04 2 38 U(nf)' 7 Cs (Cd) 1.55E-14 2.03E-14 1.95E-14 0.76 0.79

' 9Co(ny)60Co 3.90E-12 2.46E-12 3.88E-12 1.59 1.01 "Co(n,y) 6 Co (Cd) 4.33E-13 4.75E-13 4.35E-13 0.91 1.00 Notes:

1. The Capsule W-97 calculated results reported above for the individual reaction rates were taken from the synthesized transport calculations at the core midplane after the fourth fuel cycle.

Capsule W-263 Reaction Rate [rps om]

Best Reaction Measured Calculated Estimate M/C M/BE 63 Cu(na)60 Co (Cd) 4.95E-17 4.86E-17 5.22E-17 1.02 0.95 5 Fe(n'p) 54 Mn 4.80E-15 4.33E-15 4.90E-15 1.11 0.98 "Ni(n,p) 8Co (Cd) 6.65E-15 5.66E-15 6.49E-15 1.17 1.02 46 Ti(np)46 Sc 9.20E- 16 7.61E-16 8.73E-16 1.21 1.05 2 38 U(nf) 1 7 Cs (Cd) Rejected 1.48E-14 N/A N/A N/A "Co(n,y) 60Co 2.19E-12 1.76E-12 2.18E-12 1.24 1.00 59Co(ny) 60Co (Cd) 2.94E-13 3.42E-13 2.97E-13 0.86 0.99 Notes:

1. Measured reaction rate for the cadmium covered uranium fission monitor was rejected since it was significantly lower than that of Capsule W-97. Due to the fact that these two capsules were irradiated in symmetrically equivalent locations and the half-life of cesium-137 is 30.07 years, the measured reaction rate for the fission monitors in Capsule W-263 should have been greater than the Capsule W-97 measurement results.

2. The Capsule W-263 calculated results reported above for the individual reaction rates were taken from the synthesized transport calculations at the core midplane after the eleventh fuel cycle.

Appendix E March 2003 WCAP-16002 Revision 0

E-20 WESTINGHOUSE NON-PROPRIETARY CLASS 3 E-20 WESTINGHOUSE NON-PROPRIETARY CLASS 3 Table E,6 Comparison of Calculated and Best Estimate Exposure Rates At The Surveillance Capsule Center (E > 1.0 Me V) [n/cm 2 -sl I Best Uncertainty Capsule ID Calculated Estimate (I a) BE/C W-97 4.56E+10 4.24E+10 6% 0.93 W-263 3.32E1+10 7% 1.14 3.79E+10 Notes:

1. Calculated results are based on the synthesized transport calculations taken at the core midplane following the completion of each respective capsules irradiation period.

Notes:

1. Calculated results are based on the synthesized transport calculations taken at the core midplane following the completion of each respective capsules irradiation period.

Appendix E March 2003 WCAP-I 6002 Revision 0

WESTINGHOUSE NON-PROPRIETARY CLASS 3 E-21 WESTINGHOUSE NON-PROPRIETARY CLASS 3 E-2 1 Table E-7 Comparison of Measured/Calculated (NI/C) Sensor Reaction Rate Ratios Including all Fast Neutron Threshold Reactions Notes:

1. The M/C values for the 46Ti sensors are listed but not used in the average M/C ratio due to a bias present in the SNLRML cross-section data as discussed in Section E.1.3. For additional information, these calculations were repeated using the 46Ti dosimetry cross-section from the BUGLE-96 data library set. The results of these calculations were MIC ratios of 1.10 and 1.14 for Capsules W-97 and W-263, respectively.

2. The cadmium-covered uranium measurement from Capsule W-263 was rejected.

3. The overall average M/C ratio for the set of 7 sensor measurements is 1.04 with an associated standard deviation of 14.7%.

Table E-8 Comparison of Best Estimate/Calculated (BE/C) Exposure Rate Ratios BE/C Ratio Capsule ID ¢(E > 1.0 MeV) dpa/s W-97 0.93 0.95 W-263 1.14 1.12 Average 1.04 1.04

% Standard Deviation 14.4 12.0 Appendix E March 2003 WCAP-16002 Revision 0

WCAP-16002, Rev. 0 0

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

W3F1-2003-0020, Submittal of Second Reactor Vessel Surveillance Capsule Report

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W3F1-2003-0020, Submittal of Second Reactor Vessel Surveillance Capsule Report

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