NG-16-0042, BWRVIP-135, Revision 3: BWR Vessel and Internal Project - Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations

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BWRVIP-135, Revision 3: BWR Vessel and Internal Project - Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations
ML16055A127
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Site: Duane Arnold, PROJ0669  NextEra Energy icon.png
Issue date: 12/31/2014
From: Carter E
Electric Power Research Institute
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Office of Nuclear Reactor Regulation
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MF6617, NG-16-0042 BWRVIP-135, Rev 3
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  • 1..121 PLOROWER REERHINSTITUTE 2014 TECHNICAL REPORT BWRVIP-135, Revision 3: BWR Vessel and Internals Project Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations NOTICE: This report contains proprietary information that is the intellectual property of u*'
  • 4*D,*,*WARNING:

Please read the Export Control EPRI. Accordingly, itis available oniy under license from EPRIand may not be reproduced SAI'i \ "90*,/Agreement on the back cover. or disclosed, wholly or in part, by any licensee to any other person or organization.

BWRVIP-1 35, Revision 3: BWR Vessel and Internals Project Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations 3002003144 Technical Report, December 2014 EPRI Project Manager R. Garter Quality Assurance Program apply to this product.

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Plant-Specific Evaluations Duane Arnold Representative Surveillance Materials The ISP Representative Surveillance Materials for the Duane Arnold vessel target weld and plates are shown in the following table.

Table 2-31 Target Vessel Materials and ISP Representative Materials for Duane Arnold Target Vessel Materials ISP Representative Materials Weld 432Z0471 DA1 SMAW Plate B0673-1 B0673-1 Summary of Available Surveillance Data: Plate The representative plate material B0673-l is contained in the following ISP capsules:

Duane Arnold and SSP Capsule F ISpecific surveillance data related to plate heat B 0673-1 are summarized in Appendix A-3. Four capsules containing this plate heat have been tested. The Charpy V-notch surveillance results are as follows:

Table 2-32 "1

30 Shift Results for Plate Heat B0673-1 Capsule Cu (wt%) Ni (wt%) Fluence (1017 n/cm 2, E > 1 MeV) AT30 (°F)

Duane Arnold 2880 5.09 41.8 Duane Arnold 360 11.7 77.0 0.15 0.65 SSP F 18.699 73.4 Duane Arnold 1080 26.3 94.3 The results given in Appendix A-3 show a fitted chemistry factor (CF) of (( } }, as compared to a value of 111 .25°F from the chemistry tables in Reg. Guide 1.99, Rev. 2. The maximum scatter in the fitted data is (( which is well within the 1-sigma value of l17°F for plates as given in Reg. Guide 1.99, Rev. 2. Conclusions and Recommendations Because the representative plate material is the same heat number as the target plate in the Duane Arnold vessel, and because there are four irradiated data sets for this plate that fall within the 1-sigma scatter band, the ISP surveillance data should be used to revise the projected ART value for the target vessel plate with a reduced margin term (Regulatory Position 2.1). Recommended guidelines for use of ISP surveillance data are provided in Section 3 of this Data Source Book. 2-22

Plant-Specific Evaluations Summary of Available Surveillance Data: Weld The representative weld material DAl SMAW is contained in the following ISP capsules: Duane Arnold Capsules SSP Capsule F Specific surveillance data related to weld heat DAl SMAW are presented in Appendix B-5 and the results are summarized below. Four capsules containing weld heat DAl SIMAW have been tested. The Charpy V-notch surveillance results are as follows: Table 2-33 

   *T30Shift Results for Weld Heat DA1 SMAW Capsule             Cu (wt%)        Ni (wt%)               Fluence (1017 n/cm 2, E > 1 MeV)         AT20 (°F)

Duane Arnold 2880 5.09 2.6 Duane Arnold 360 11.7 16.1 0.02 0.94 SSP F 19.336 26.3 Duane Arnold 108° 26.3 23.8 The results given in Appendix B-5 show a fitted chemistry factor (CF) of (( }}, as compared to a value of 27.0°F from the chemistry tables in Reg. Guide 1.99, Rev. 2. The maximum scatter in the fitted data is (( }} which is well within the 1-sigma value of 28°F for welds as given in Reg. Guide 1.99, Rev. 2. Conclusions and Recommendations Because the representative weld material is not the same heat number as the target weld in the Duane Arnold vessel, the utility should use the chemistry factor from the Regulatory Guide 1.99, Rev. 2 tables to determine the projected ART value for the target vessel weld. Recommended guidelines for evaluation of ISP surveillance data are provided in Section 3 of this Data Source Book. 2-23

ISP Plate Heat Evaluations A-3 Plate Heat: B0673-1 Summary of Available Charpy V-Notch Test Data The available Charpy V-notch test data sets for plate heat B0673-1 are listed in Table A-3-1. The source documents for the data are provided, and the capsule designation and fluence values are also provided for irradiated data sets. Table A-3-1 ISP Capsules Containing Plate Heat B0673-1 Capsule Fluence (E> 1 MeV, 1017Rernc n/cm 2)Reene Unirradiated Baseline Data Duane Arnold 2880 5.09 References A-3-i and A-3-2 Duane Arnold 360 11.7 SSP Capsule F 18.699 Reference A-3-3 Duane Arnold 1080 26.3 Reference A-3-2 The CVN test data for each set taken from the references noted above are presented in Tables A-3-7 through A-3-11. The BWRVIP ISP uses the hyperbolic tangent (tanh) function as a statistical curve-fit tool to model the transition temperature toughness data. Tanhi curve plots for each data set have been generated using CVGRAPH, Version 5 [A-3-4] and the plots are provided in Figures A-3-1 through A-3-5. Best Estimate Chemistry Table A-3-2 details the best estimate average chemistry values for plate heat B 0673-1 surveillance material. Chemical compositions are presented in weight percent. If there are multiple measurements on a single specimen, those are first averaged to yield a single value for that specimen, and then the different specimens are averaged to determine the heat best estimate. Table A-3-2 Best Estimate Chemistry of Available Data Sets for Plate Heat B0673-1 Cu (wt%) Ni (wt%) P (wt%) S (wt%) Si (wt%) Specimen ID Source 0.15 0.7 0.006 -- 0.07 ETJ 0.15 0.69 0.006 -- 0.06 ETK 0.14 0.62 0.010 -- 0.01 EB4 Reference A-3-1 0.141 0.62 0.014 -- 0.02 EBA 0.145 0.65 0.010 -- 0.09 EBE 0.15 0.61 0.011 -- 0.18 Baseline CMTR Reference A-3-1 0.15 0.65 0.010 - 0.07 E.Best Estimate Average Calculation of Chemistry Factor (CF): The Chemistry Factor (CF) associated with the best estimate chemistry, as determined from U.S. NRC Regulatory Guide 1.99, Revision 2 [A-3-5], Table 2 (base metal), is: CF(Bo 673 .1) -. 111.25°F A-3-1

ISP Plate Heat Evaluations Effects of Irradiation The radiation induced transition temperature shifts for heat B0673-l are shown in Table A-3-3. The T30 [30 ft-lb Transition Temperature], T5 0 [50 ft-lb Transition Temperature], and T35 m~i [35 mul Lateral Expansion Temperature] have been determined for each Charpy data set, and each irradiated set is compared to the baseline (unirradiated) index temperatures. The change in Upper Shelf Energy (USE) is also shown. The unirradiated and irradiated values are taken from the CVGRAPH fits presented at the back of this sub-appendix (only CVN energy fits are presented). Comparison of Actual vs. Predicted Embrittlement A predicted shift in the 30 ft-lb transition temperature (AT30 ) is calculated for each irradiated data set using the Reg. Guide 1.99, Rev. 2, Regulatory Position 1.1 method. Table A-3-4 compares the predicted shift with the measured AT30 (°F) taken from Table A-3 -3. Comparison of Actual vs. Predicted Decrease in USE Table A-3-5 compares the actual percent decrease in upper shelf energy (USE) to the predicted decrease. The predicted decrease is estimated from USNRC Regulatory Guide 1.99, Rev. 2, Figure 2; the measured percent decrease is calculated from the values presented in Table A-3-3. A-3-2

ISP Plate Heat Evaluations Table A-3-3 Effect of Irradiation (E>1.0 MeV) on the Notch Toughness Properties of Plate Heat B0673-1 T30, 30 ft-lb T50, 50 ft-lb T25 mii,35 mil Lateral CVN Upper Shelf Energy Material Capsule Transition Temperature Transition Temperature Expansion Temperature (USE) Identity ID Unirrad irrad AT~o Unirrad Irrad AT,0 Unirrad Irrad AT3,mii Unirrad Irrad Change _______ (0 F) (0 F) (0 F) (0F) (0F) (°F) (0 F) (0 F) (0 F) (ft-lb) (ft-lb) (ft-lb) 2880 -35.5 6.3 41.8 -7.3 42.4 49.7 -23.6 18.6 42.2 158.1 158.8 0.7 DA1 and 360 -35.5 41.5 77.0 -7.3 70.7 78.0 -23.6 55.7 79.3 158.1 137.0 -21.1 SS P B0673-1 SSP F -35.5 37.9 73.4 -7.3 66.9 74.2 -23.6 57.8 81.4 158.1 133.0 -25.1 1080 -35.5 58.8 94.3 -7.3 91.4 98.7 -23.6 87.1 110.7 158.1 131.3 -26.8 Table A-3-4 Comparison of Actual Versus Predicted Embrittlement for Plate Heat B0673-1 Fluence Measured Shift 1 rGe1i99tev. Shf2 R .9Rv Capsule Identity Material (xl10'8 n/cm2 ) 0 F Prdce hf t Preictedrin' 0 F DA 2880 Plate Heat B0673-1 in Duane Arnold 0.509 41.8 32.9 65.8 DA 360 Plate Heat B0673-1 in Duane Arnold 1.17 77.0 50.0 84.0 SSP F Plate Heat B0673-1 in SSP 1.8699 73.4 61.6 95.6 DA 1080 Plate Heat B0673-1 in Duane Arnold 2.63 94.3 70.8 104.8 Notes:

1. See Table A-3-3 ATe.
2. Predicted shift = CF x FF, where CF is a Chemistry Factor taken from tables from USNRC Reg. Guide 1.99, Rev. 2, based on each material's Cu/Ni content, and FF is Fluence Factor, f02*0.,022I where f =fluence (10=* n/cm2, E > 1.0 May).

0

3. Margin = 2 2+ 2,where 2 =),the standard deviation on initial RT~DT (which is taken to be 0 F), and is the standard deviation on RTDT (28°F for welds and 17°F for base materials, except that need not exceed 0.50 times the mean value of RTNDT). Thus, margin is defined as 34°F for plate materials and 56°F for weld materials, or margin equals shift (whichever is lass), per Rag. Guide 1.99, Rev. 2.

A-3-3

ISP Plate Heat Evaluations Table A-3-5 Comparison of Actual Versus Predicted Percent Decrease in Upper Shelf Energy (USE) for Plate Heat B0673-1 RG 1.99 Rev. 2 MaeilFluence Maeil(xl 018 n/cm 2) Cu (wt%) Content Measured 1 USEDecrease (%) in Predicted 2 in USEDecrease (%) DA 2880 Plate Heat B0673-1 in Duane Arnold 0,509 3 11.9 0.15 DA3°Plate Heat B0673-1 in Duane Arnold 0.519 0.15 13314.9 SSP F Plate Heat B0673-1 in SSP 1.8699 0.15 15.9 16.1 DA 1080 Plate Heat B0673-1 in Duane Arnold 2.63 0.15 17.0 17.5 Notes:

1. See Table A-3-3, (Change in USE)/(Unirradiated USE).
2. Calculated using equations in Regulatory Guide 1.162 [A-3-6] that accurately model the Charpy upper shelf energy decrease curves in Regulatory Guide 1.99, Revision 2.
3. Less than zero.

A-3-4

ISP Plate HeatEvaluations Credibility of Surveillance Data The credibility of the surveillance data is determined according to the guidance of Regulatory Guide 1.99, Rev. 2 and 10 CFR 50.61, as supplemented by the NRC staff [A-3-7]. The following evaluation is based on the available surveillance data for irradiated plate heat B0673- 1. The applicability of this evaluation to a particular BWR plant must be confirmed on a plant-by-plant basis to verify there are no plant-specific exceptions to the following evaluation. Per Regulatory Guide 1.99, Revision 2 and 10 CFR 50.61, there are 5 criteria for the credibility assessment. Criterion 1: Materials in the capsules should be those judged most likely to be controlling with regard to radiation embrittlement. In order to satisfy this criterion, the representative surveillance material heat number must match the material in the vessel. Criterion2: 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 this sub-appendix. 1Based on engineering judgment, the scatter in these plots is small enough to permit the determination of the 30 ft-lb temperature and the upper shelf energy. Hence, this criterion is met. Criterion3: 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 17°F for plates. Even if the fluence range is large (two or more orders of magnitude), the scatter should not exceed twice that value. 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 El185-82 [A-3-8]. For plate material B30673-1, there are 4 surveillance capsule data sets currently available. The functional form of the least squares fit method as described in Regulatory Position 2.1 is utilized to determine a best-fit line for this data and to determine if the scatter of these ARTN*DT values about this line is less than 17°F for plates. Figure A-3-6 presents the best-fit line as described in Regulatory Position 2.1 utilizing the shift prediction routine from CVGRAPH, Version 5.0.2. The scatter of ARTNDT values about the functional form of the best-fit line drawn as described in Regulatory Position 2.1 is presented in Table A-3-6. A-3-5

ISP Plate Heat Evaluations Table A-3-6 Best Fit Evaluation for Surveillance Plate Heat B0673-1. Measred<17° F Mesued Best Fit Scatter (Base Metal) Material Fitted CF Casl F ARTNDT ARTNDT of ART NoT <28° F (0F) Casl F (30 ft-lb) (0F) (0F) (Weld (0F) metal) B0673-1 (( }} 288° 0.290 41.8 (( }} ((_ } Yes (( }} 360 0.436 77.0 (( }} (( }} Yes (( }} SSP F 0.553 73.4 (( }} (( }} Yes ((____ }} 1080 0.637 94.3 (( }} (( }} Yes Table A-3-6 indicates that the scatter is within acceptable range for credible surveillance data. Therefore, plate heat B0673-.1 meets this criterion. Criterion4: The irradiation temperature of the Charpy specimens in the capsule should match the vessel wall temperature at the cladding/base metal interface within + ! - 25°F. BWRVIP-78 [A-3-9] established the similarity of BWR plant environments in the BWR fleet. The annulus between the wall and the core shroud in the region of the surveillance capsules contains a mix of water returning from the core and feedwater. Depending on feedwater temperature, this annulus region is between 525°F and 535°F. This location of specimens with respect to the reactor vessel beltline is designed so that the reactor vessel wall and the specimens experience equivalent operating conditions such that the temperature will not differ by more than 25°F. Any plant-specific exceptions to this generic analysis should be evaluated. Criterion5: The surveillance data for the correlation monitor material in the capsule should fall within the scatter band of the database for that material. Few ISP capsules contain correlation monitor material. Generally, this criterion is not applicable. For plate heat B 0673-1, these criteria are satisfied (or not applicable). The surveillance data are nominally credible because the scatter criterion is met. Prior to application of the data, a plant should verify that no plant-specific exceptions to these criteria exist. A-3 6

ISP Plate Heat Evaluations Table A-3-7 Unirradiated Charpy V-Notch Results for Surveillance Plate B0673-1 (LT) Spec ID Temp (°F) CVN (ft-lb) LE (mils) %Shear ED4 -100 6.5 7.0 0 ED1 -80 4.2 5.0 0 ECT -40 9.0 14.0 10 EDK -40 24.0 30.0 5 ED7 -30 38.0 35.0 5 EDT -30 49.0 30.0 5 ED6 -20 47.0 43.0 10 ED5 -10 43.0 43.0 20 ECP 0 56.5 49.0 25 ECM 40 98.5 73.0 40 ECL 120 134.5 73.0 80 ECK 200 158.5 93.0 85 EDY 300 163.5 81.0 90 EDA 400 No Break No Break No Break Table A-3-8 Charpy V-Notch Results for B0673-1 (LT) in Duane Arnold 288 Deg Capsule Spec ID Temp (0F) CVN (ft-tb) LE (mils) %Shear EBU -60 4.0 4.0 0 EBP -20 15.0 19.0 0 EBT 10 15.5 26.0 40 EC1 20 49.5 45.0 40 EBK 40 60.0 49.0 40 EBJ 120 101.5 70.0 70 EBL 200 144.5 95.0 90 EBY 400 160.0 98.0 90 A-3-7

ISP Plate Heat Evaluations Table A-3-9 Charpy V-Notch Results for B0673-1 (LT) in Duane Arnold 36 Deg Capsule Spec ID Temp (0 F) CVN (ft-lb) LE (mils) %Shear EBD -50 5.0 5.0 1 EB1 0 18.5 15.0 41 EB2 13 27.7 24.0 10 EB3 25 13.7 13.0 27 EBC 32 15.4 23.0 24 EB6 40 15.4 16.0 32 EB4 49 59.2 48.0 32 EB5 81 51.5 43.0 44 EBA 120 92.9 69.0 78 EB7 202 127.8 82.0 100 EBE 250 142.8 84.0 100 EBB 400 140.5 94.0 100 Table A-3-10 Charpy V-Notch Results for B0673-1 (LT) in SSP Capsule F Spec ID Temp (0 F) CVN (ft-lb) LE (mils) %Shear EDJ 0 12.5 9.0 0 ECU 30 25.5 22.0 20 EDD. 50 24.5 21.0 20 ECY 50 34.5 26.0 30 ED)M 70 71.5 54.0 45 EDP 150 103.5 78.0 75 EDB 175 113.5 82.0 85 ED2 200 139.0 89.0 100 ECJ 300 134.5 91.0 100 ECE 400 125.5 85.0 100 A-3-8

ISP Plate Heat Evaluations Table A-3-11 Charpy V-Notch Results for B0673-1 (LT) in Duane Arnold 1080 Capsule Spec ID Temp (0F) CVN (ft-lb) LE (mils) %Shear ECB -1.3 4.2 5.0 4.2 EGO 35.8 23.88 17.3 10.4 EC3 69.1 42.06 30.4 17.6 EC7 128.7 63.71 48.5 38.6 ECD 160.5 111.06 76.2 67.2 ECA 191.5 110.36 76.0 84.1 EC4 252.0 129.48 91.0 100.0 EC5 400.8 133.11 92.9 100.0 A-3-9

ISP PlateHeat Evaluations Tanh Curve Fits Of CVN Test Data for Plate Heat 80673-1 PLATE HEAT B0673-1 (DA AND SSP) CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 09/09/2002 08:29 AM Page 1 Coefficients of Curve 1 A = 80.31 B =77.81 C =78.77 TO = 25.02 D = O.00E+00 Equation is A + B * [Tanh((T-To)/(C+DT))] Upper Shelf Energy=1 58.1 Lower Shelf Energy=2.5(Fixed) Temp@30 ft-lbs=-35.5 Deg F Temp@50 ft-lbs*-7.3 Deg F Plant: DUANE ARNOLD AND SSP Material: SA533B1 Heat: B0673-1 Orientation: LT Capsule: UNIRRA Fluence: 0.0 n/emA2 U.I z 1 I o 

                      -300
                                  -i------ -100
                                 -200
                                            --T* ..    ._

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

             -1I00. 00                         6. 50                               8.75                         -2.25
               - 80. 00                        4. 20                              12. 6t                        -8.41
               - 40. 00                         9. 00                            27. 56                       -18.56
               - 40. 00                       24. 00                           27. 56                         -3.56
               -30. 00                        38. 00                           33. 36                           4.64
               -30. 00                        49. 00                           33. 36                         15.64
               - 20. 00                       47. 00                            40. 12                           6. 88
               -10.00                         43. 00                           47. 83                         -4.83
                    .00                       56. 50                            56. 40                             .10
40. 00 98. 50 94. 93 3.57 120. 00 134. 50 145.31 -10.81 Figure A-3-1 Charpy Energy Data for Pfate B0673-1 (LT) Unirradiated A-3-10

ISP Plate Heat Evaluations PLATE HEAT B0673-1 (DA AND SSP) Page 2 Plant: DUANE ARN'OLD AND SSP Material: SA533B1 Heat: B0673-1 Orientation: LT Capsule: UNIRRA Fluence: 0.0 rdcm^2 Charpy V-Notch Data Input CVN Computed CVN Differential Temperature 200. 00 158.50 156. 31 2. 19 300.,00 163.50 157. 97 5,53 Correlation Coeffeient =.988 Figure A-3-1 Charpy Energy Data for Plate 1B0673-1 (LT) Unirradiated (Continued) A-.3-11

ISP Plate Heat Evaluations Irradiated Plate Heat B0673-1 (DA1-288) CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 12/17/2013 01:33 PM Page 1 Coefficients of Curve 1 A = 80.66 B = 78.16 C.= 101.16 TO =84.32 D = 0.O0E+00 Equation is A +IB.*[Tanh((T-To)f(C+DT))] upper Shelf Energy=l 58.8 Lower Shelf Energy=2.5(Fixed) 

                                     *Temp@30 ft-lbs=6.3 Deg F           Temp@50 ft-lbs=42.4 Deg P Plant: DUANE ARNOLD AND SSP Material: SA533B1                   Heat: B 0673-1 Orientation: LT Capsule: DA-288              Fluence*      n/cmA2 300 250
             *200 50 U-100 0

50 0 0 300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data TIemnpeatsure Input CVN Computed CVN Differential 

            -60.00                             4. 00                              11.02                       -7.02
            -20.00                           15. 00                              20. 13                      -5.13 1.o. 00                         15. 50                              31. 74                    - 16.24
20. 00 49. 50 3.6. 73 12. 77
40. 00 60. 00 48.45 11.55 120.00 10"1. 50 107. 13 -5. 63 200. 00 144. 50 144. 40 ,10 400. 00 160. 00 158. 51 1. 49 Correlation Coefficient = .987 Figure A-3-2 Charpy Energy Data for Plate B0673-1 (LT) in Duane Arnold 288° Capsule A-3-12

ISP Plate Heat Evaluations Irradiated Plate Heat B0673-1 (~DA1-36) CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 22/17/20.13 01:34 PM Page 1 Coefficients of Curve 2 A = 69.75 B = 67.25 C = 77.56 TO = 94.1 D = 0.00E+00 Equation is A + B * [T*anh((T-To)/(C+DT))] Upper Shelf Enlergy=137.0(Fixed) Lower Shelf Energy=2.5(Fixed) Temp@30 ft-lbs=41.5 Deg F Temp@50 ft-lbs=70.7 Deg.F Plant: DUANE ARNOLD AND SSP Material: SA533B1 Heat: B0673-1 Oriefitation: LT Ca~psule: DA-36 Fluence: n/cmt'2 300 250 

           .200
       *10 U,-

100 

                                                               /

50 0 

               -300      -200        -100         0        100       200         300     400       500       600 Temperature in Deg F Charpy V-Notch Data Temperature                         InputCVN                       Competed CYN                 Differential
       -50. 00                            :5, 00                              5. 70                     -. 70
             ,00                         18. 50                             13. 42                    5. 08
13. 00 27. 70 17. 29 10. 41
13. 70 21. 88 -8.18
32. 00 15. 40 2*5.07 -9.67"
40. 00 15. 40 29. 21 -13..81
49. 00 59. 20 34. 53 24. 67 81.00 51.50 58. 50 -7.00 120. 00 92. 90 91.41 1. 49 Figure A-3-3 Charpy Energy Data for Plate 60673-1 (LT) in Duane Arnold 360 Capsule I

A-3 -13

ISP Plate Heat Evaluations Irradiated Plate Heat B0673-1 (IDA1-36) Page 2 Plant: DUANE ARNOLD AND SSP Material: SA533B1 Heat: B0673-1 Orientation: LT Capsule: DA-36 Fluence: n/cma2 Charpy V-Notch Data Temperatdite Input CVN Computed CVN Differential 202. 00 127. 80 12,9. 16 -1.36 250. 00 142..80 134. 63 8. 17 400. 00 140. 50 136.95 3. 55 Correlation Coefficent =.980 Figure A-3-3 Charpy Energy Data for Plate B0673-1 (LT) in Duane Arnold 360 Capsule (Continued) A-3-14

ISP Plate Heat Evaluations Irradiated Plate Heat B0673-1 (SSP-F) CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 12/17/2013 01:34 PM Page 1 Coefficients of Curve 3 A = 67.75 B = 65.25 C = 76.12 TO = 88.09 D = O.OO0E+O0 Equation is A + B * [Tanla((T-To)/(C+FDI))] Upper Shelf Energy=133.0(Fixed) Lower Shelf Energy=2.5(Fixed) Temp@30 ft-lbs=37.9 .feg*F Temp@5SO ft-lhs=66.9 Deg F Plant: DUANE ARNOLD AND SSP Material: SA533B1 Heat: B 0673-1 Orientation: LT Capsule: $8P-F Fluence: rtcmA2 a uu 2.50.. 2'00 U- 50 ji C 

                                                                'so DO/

0....--+ 

                            "..r ....   ....           0 !'
              -300      -200       -100         0        100        200       300      400       500         600 Temperature in Deg F Charpy V-Notch Data Temperature                       InputCVN                       Comnputed.CVN                 Differential 12.50                              14. 24                      -1. 74
          $.00
25. 50 25..80 - .30
50. 00 24. 50 $7. 57 - 13. 07
50. 00 34. 50 3.7. 57 -3.07
70. 00 71. 50 52. 53 18.97 150. 00 103. 50 111. 56 - 8.06 175.00 113.50 120. 93 -7.43 200. 00 139. 00 126.45 12. 55 300.00 134. 50 132. 50 2. 00 Figure A-3-4 Charpy Energy Data for Plate B0673-1 (LT) in SSP Capsule F A-3-15

Isp PlateHeat Evaluations Irradiated Plate Heat B0673-1 (SSP-F) Page 2 Plant: DUANE. ARNOLD AND SSP Material: SA533B1 Heat: B0673-1 Orientation: LT Capsule: SSP-F Fluence: n/era^2 Charpy V-Notch Data Temjperature Input CVN Com~puted.CVN Diffferential 400. 00 125.50 132. 96 7. 46 Correlation Coefficient =.981 Figure CharpyA-3-4 Energy Data for Plate B0673-1 (LT) in SSP Capsule F (Continued) f A 16

ISP Plate Heat Evaluations Irradiated Plate Heat B0673-1 (jDA!-108) CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 12/31/2013 09:45 AM Page 1 Coefficients of Curve 1 A = 66.9 B = 64.4 C = 85.21 T0 = 114.29 D = 0.00E+00 Equation is A + B * [Tanh((T-To)/(C+-DT))I Upper Shelf Energy*=131.3(Fixed) Lower Shelf Energy,=2.5(Fixed) Temp@30 ft-lbs=58.8 Deg F Temp@l50 ft-lbs=91.4 Deg F Plant: DUANE ARNOLD AND SSP Material: SA533B1 Heat: B 0673-1 Orientation: LT Capsule: DA-108 Fluencee: rdcm^2 300 250 

         *200 a
         *150 ull                                                         0 .. _
          "100 0

50 0 

              -300   -200        -100         0          100      200       300       400        500        600 Temperature in Deg F Charpy V-Notch Data Temperature                      nput CVN                       Compute CVNN                    Differential
        -'1. 30                       4. 20                             10. 51                       -6.31
35. 80 23. 88 20. 12 3.76
69. 10 42. 06 35. 63 6.43 128. 70 63.71 77. 69 -13.98 160. 50 111.06 98. 76 12. 30 191. 50 1i0.36 113. '22 -2.86 252. 00 129. 48 126.41 3.07 400. 80 133. 11 131. 15 1.96 Correlation Coefficient = .987 Figure A-3-5 Charpy Energy Data for Plate B0673-1 (LT) in Duane Arnold 1080 Capsule A-3-17

ISP Plate Heat Evaluations Figure A-3-6 Fitted Surveillance Results for Plate Heat B0673-1 A-3-18

ISP Plate Heat Evaluations References A-3-1. GE Nuclear Energy, "Duane Arnold RPV Surveillance Materials Testing and Analysis," GE-NE-B 1100716-01, July 1997. A-3-2. BWRVJP-279NP: BWR Vessel and Internals Project, Testing and Evaluation of the DuaneArnold 1080 Capsule. EPRI, Palo Alto, CA: 2014. 3002003134. A.-3-3. BWRVIP-J11NP, Revision 1:~BWR Vessel and Internals Project, Testing and Evaluation of BWR Supplemental Surveillance ProgramCapsules E, F and I. EPRI, Palo Alto, CA: 2010. 1021554. A-3-4. CVGRAPH, Hyperbolic Tangent Curve Fitting Program, Developed by ATI Consulting, Version 5.0.2, Revision 1, 3/26/02. A-3-5. "Radiation Embrittlement of Reactor Vessel Materials," USNRC Regulatory Guide 1.99, Revision 2, May 1988. A-3-6. "Format and Content of Report for Thermal Annealing of Reactor Pressure Vessels," USNRC Regulatory Guide 1.162, February 1996. A-3-7. K. Wichiman, M. Mitchell, and A. Hiser, USNRC, Generic Letter 92-01 and RPV Integrity Workshop Handouts, NRC/Industry Workshop on RPV Integrity Issues, February 12, 1998. A-3-8. ASTM E-185, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels," American Society for Testing and Materials, July 1982. A-3-9. BWR Vessel and InternalsProject: BWR IntegratedSurveillance ProgramPlan (BWRVIP-78). EPRI, Palo Alto, CA and BWRVIP: 1999. TR-1 14228. A-3-19

ISP Weld Heat Evaluations B-5 Weld Heat: DA1 SMAW Summary of Available Charpy V-Notch Test Data The available Charpy V-notch test data sets for weld heat DA1 SMAW are listed in Table B-5-i. The source documents for the data are provided, and the capsule designation and fluence values are also provided for irradiated data sets. Table 6-5-1 ISP Capsules Containing Weld Heat DA1 SMAW Capsule Fluence (E> 1 MeV, 1017 n/cm 2) Reference Unirradiated Baseline Data References B-5-1 Duane Arnold 1 288° 5.09anB-2 Duane Arnold 1 360 11.7 SSP Capsule F 19.336 Reference B-5-3 Duane Arnold 1 1080 26.3 Reference B-5-2 The CVN test data for each set taken from the references noted above are presented in Tables B-5-7 through B-5-i11. The BWRVIP ISP uses the hyperbolic tangent (tanh) function as a statistical curve-fit tool to model the transition temperature toughness data. Tanh curve plots for each data set have been generated using CVGRAPH, Version 5 [Reference B-5-4] and the plots are provided in Figures B-5-1 through B-5-5. Best Estimate Chemistry Table B-5-2 details the best estimate average chemistry values for weld heat DA1 SMAW surveillance material. Chemical compositions are presented in weight percent. If there are multiple measurements on a single specimen, those are first averaged to yield a single value for that specimen, and then the different specimens are averaged to determine the heat best estimate. Table B-5-2 Best Estimate Chemistry of Available Data Sets for Weld Heat DA1 SMAW Cu Ni Source (wt%) (wt%) (wt%) (wt%) (wt%) Specimen ID Suc 0.02 1.00 0.011 -- 0.32 EU3 irrad 0.02 0.90 0.010 -- 0.33 EU6 irrad 0.025 0.96 0.011 -- 0.02 EJM Reference B-5-1 0.025 0.94 0.008 -- 0.02 EJJ 0.024 0.88 0.010 -- 0.02 EJA 0.02 0.94 0.010 -- 0.14 E-=Best Estimate Average B-5-1

ISP Weld Heat Evaluations Calculation of Chemistry Factor (CF): The Chemistry Factor (CF) associated with the best estimate chemistry, as determined from U.S. NRC Regulatoly' Guide 1.99, Revision 2 [Reference B-5-4], Table 1 (weld metal), is: CF(DAlSNm = 27"0OF Effects of Irradiation The radiation induced transition temperature shifts for heat DAl SMAW are shown in Table B-5-3. The T30 [30 ft-lb Transition Temperature], T1so [50 ft-lb Transition Temperature], and T35mi, I[35 mil Lateral Expansion Temperature] index temperatures have been determined for each Charpy data set, and each irradiated set is compared to the baseline (unirradiated) index temperatures. The change in Upper Shelf Energy (USE) is also shown. The unirradiated and irradiated values are taken from the CVGRAPH fits presented at the back of this sub-appendix (only CVN energy fits are presented). Comparison of Actual vs. Predicted Embrittlement A predicted shift in the 30 ft-lb transition temperature (AT30) is calculated for each irradiated data set using the Reg. Guide 1.99, Rev. 2, Regulatory Position 1.1 method. Table B-5-4 compares the predicted shift with the measured AT30 (0 F) taken from Table B-5-3. Comparison of Actual vs. Predicted Decrease in USE Table B-5-S compares the actual percent decrease in upper shelf energy (USE) to the predicted decrease. The predicted decrease is estimated from USNRC Regulatory Guide 1.99, Rev. 2, Figure 2; the measured percent decrease is calculated from the values presented in Table B-5-3. B-5-2

ISP Weld Heat Evaluations Table B-5-3 Effect of Irradiation (E>1I.0 MeV) on the Notch Toughness Properties of Weld Heat DA1 SMAW T30, 30 ft-lb To, 50 ft-lb T35 m, 1, 35 mil Lateral CVN Upper Shelf Energy Material Capsule Transition Temperature Transition Temperature Expansion Temperature (USE) Iett ID Unirrad Irrad AT3 Unirrad Irrad A~e Unirrad Irrad A30m,, Unirrad Irrad Change (0 F) (0F) (°F) (0 F) (0 F) (°F) (°F) (0F) (0F) (ft-lb) (ft-lb) (ft-lb) Dl 2880 -45.4 -42.8 2.6 -10.2 -14.2 -4.0 -37.3 -37.2 0.1 99.0 101.7 2.7 and 360 -45.4 -29.3 16.1 -10.2 9.1 19.3 -37.3 -5.5 31.8 99.0 95.6 -3.4 SSP DAl SSP F -45.4 -19.1 26.3 -10.2 35.5 45.7 -37.3 14.2 51.5 99.0 99.0 0.0 SMAW_________ __ _ 1080 -45.4 -21.6 23.8 -10.2 9.1 19.3 -37.3 -2.9 34.4 99.0 119.0 20.0 Table B-5-4 Comparison of Actual Versus Predicted Embrittlement for Weld Heat DA1 SMAW Capsule Material Fluence Measured1 Pr 1.99 ceRG Rev. 2sft RGprd Rev. e1.992 Identity (x T /m) Sit° FShift+Margin2 3, DA1 288° Weld Heat D)A1 SMAW in Duane Arnold 0.509 2.6 8.0 16.0 DAl 360 Weld Heat DAl SMAW in Duane Arnold 1.17 16.1 12.1 24.2 SSP Capsule F Weld Heat DA1 SMAW in SSP Capsule F 1.9336 26.3 15.1 30.3 DA1 1080 Weld Heat DA1 SMAW in Duane Arnold 2.63 23.8 17.2 34.4 Notes:

1. See Tabie B-5-3, AT,,o.
2. Predicted shift = CF x FE, where CF is a Chemistry Factor taken from tables from USNRC Reg. Guide 1.99, Rev. 2, based on each material's Cu/Ni content, and FE is Fluence Factor, fo22*.1olo% where f =fluence (10"9 n/cm 2, E > 1.0 MeV).

3.Margin =2'l(o* 2 + oA2), where o, = the standard deviation on initial RT,,,, (which is taken to be 0°F), and OA is the standard deviation on ARTNDT (28°F for welds and 170F for base materials, except that 0 A need not exceed 0.50 times the mean value of ARTNOT). Thus, margin is defined as 34°F for plate materials and 56°F for weld materials, or margin equals shift (whichever is less), per Reg. Guide 1.99, Rev. 2. B-5-3

ISP Weld Heat Evaluations Table B-5-5 Comparison of Actual Versus Predicted Percent Decrease in Upper Shelf Energy (USE) for Weld Heat DA1 SMAW RG 1.99 Rev. 2 Capsule MaeilFluence Cu Content Meceasuedi Predicted Identity Maeil(xl 018 n/cm 2) (wt%) DereSE(%n Decrease in USE 2 USE 1 (%)(%) DA1 2880 Weld Heat DA1 SMAW in Duane Arnold 0.509 0.02 -37.9 DA1 360 Weld Heat DA1 SMAW in Duane Arnold 1.17 0.02 3.4 9.6 SSP Capsule F Weld Heat DA1 SMAW in SSP Capsule F 1.9336 0.02 0 10.8 DA1 1080 Weld Heat DA1 SMAW in Duane Arnold 2.63 0.02 -411.7 Notes:

1. See Table B-5-3, (Change in USE)/(unirradiated usE).
2. Calculated using equations in Regulatory Guide 1.162 [B-5-6] that accurately model the Charpy upper shelf energy decrease curves in Regulatory Guide 1.99, Revision 2.
3. Value less than zero.

B-5-4

ISP Weld Heat Evaluations Credibility of Surveillance Data The credibility of the surveillance data is determined according to the guidance of Regulatory Guide 1.99, Rev. 2 and 10 CFR 50.61, as supplemented by the NRC staff [Reference B-5-7]. The following evaluation is based on the available surveillance data for irradiated weld heat DA1 SMAW. The applicability of this evaluation to a particular BWR plant must be confirmed on a plant-by-plant basis to verify there are no plant-specific exceptions to the following evaluation. Per Regulatory Guide 1.99, Revision 2 and 10 CFR 50.61, there are 5 criteria for the credibility assessment. Criterion 1: Materials in the capsules should be those judged most likely to be controlling with regard to radiation embrittlement. In order to satisfy this criterion, the representative surveillance material heat number must match the material in the vessel. Criterion2: 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 this sub-appendix. Based on engineering judgment, the scatter in these plots is small enough to permit the determination of the 30 ft-lb temperature and the upper shelf energy. Hence, this criterion is met. Criterion3: When there are two or more sets of surveillance data from one reactor, the scatter of values about a best-fit line drawn as described in Regulatory Position 2.1 normally NDRT* should be less than 28°F for welds. Even if the fluence range is large (two or more orders of magnitude), the scatter should not exceed twice that value. 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 El185-82 [Reference B-5-8]. For weld material DA1 SMAW, there are 4 surveillance capsule data sets currently available. The functional form of the least squares fit method as described in Regulatory Position 2.1 is utilized to determine a best-fit line for this data and to determine if the scatter of these AXRTNDT values about this line is less than 28°F for welds. Figure B-5-6 presents the best-fit line as described in Regulatory Position 2.1 utilizing the shift prediction routine from CVGRAPH, Version 5.0.2. The scatter of RT* values about the functional form of the best-fit line drawn as described in Regulatory Position 2.1 is presented in Table B-5-6. B-5-5

ISP Weld Heat Evaluations Table B-5-6 Best Fit Evaluation for Surveillance Plate Heat DA1 SMAW Measured Best Scatter <17 0 F Maeil Fitted ARTND Fit of (Base Metal) CF ( 0F) Casl F (30 ft-lb) ARTNDT ARTN~ <28°F (0F) (0F) (0F) (Weld metal) (( }} DA1 2880 0.296 2.6 (( }} (( }} Yes DA1l { }} DA1 360 0.449 16.1 (( }} (( }} Yes SMAW (( }} SSP F0 0.56 1 26.3 (( }} (( }} Yes (( }} DA1 1080 0.637 23.8 (( }}(( }} Yes Table B-5-6 indicates that the scatter is within acceptable range for credible surveillance data. Therefore, weld heat DAl SMAW meets this criterion. Criterion4: The irradiation temperature of the Charpy specimens in the capsule should match the vessel wall temperature at the cladding/base metal interface within +/ 25°F. BWRVIP-78 [Reference B-5-9] established the similarity of BWR plant environments in the BWR fleet. The annulus between the wall and the core shroud in the region of the surveillance capsules contains a mix of water returning from the core and feedwater. Depending on feedwater temperature, this annulus region is between 525°F and 535°F. This location of specimens with respect to the reactor vessel beltline is designed so that the reactor vessel wall and the specimens experience equivalent operating conditions such that the temperature will not differ by more than 25°F. Any plant-specific exceptions to this generic analysis should be evaluated. 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. Few ISP capsules contain correlation monitor material. Generally, this criterion is not applicable. For weld heat DA1 SMAW, these criteria are satisfied (or not applicable). The surveillance data are nominally credible because the scatter criterion is met. Prior to application of the data, a plant should verify that no plant-specific exceptions to these criteria exist. B-5-6

ISP Weld Heat Evaluations Table B-5-7 Unirradiated Charpy V-Notch Results for Surveillance Weld DA1 SMAW Spec ID Temp (0F) CVN (ft-lb) *LE (mils) %Shear EET -100 6.5 11.0 10 EEK -80 5.5 10.0 15 EK3 -60 16.8 19.0 40 EK4 -50 21.5 22.0 20 EEE -40 49.0 45.0 20 EK2 -20 58.0 57.0 50 EEL 0 52.5 50.0 30 EEY 40 65.0 61.0 50 EED 120 102.0 88.0 80 EEM 200 94.0 65.0 70 EK5 300 88.2 93.0 60 EK6 400 113.7 96.0 70 Table B-5-8 Charpy V-Notch Results for DA1 SMAW in DA1 288 Deg Capsule Spec ID Temp (°F) CVN (ft-lb) LE (mils) %Shear EJ1 -100 6.5 11.0 0 E J2 -60 15.3 24.0 10 E J4 -40 22.0 26.0 10 EE5 -20 63.5 54.0 40 EE2 40 75.2 69.0 60

  • EE3 120 97.2 86.0 80 EE4 200 109.0 90.0 70 E J3 400 101.0 91.0 100 B-5-7

ISP Weld Heat Evaluations Table B-5-9 Charpy V-Notch Results for DA1 SMAW in DAl 36 Deg Capsule Spec ID Temp (0 F) CVN (ft-lb) LE (mils) %Shear EJP -80 7.2 6.0 25 EJL -50 23.3 19.0 33 EJM -25 28.0 24.0 36 EJK 0 48.9 41.0 49 EJJ 33 62.7 51.0 62 EJE 49 74.7 61.0 73 EJA 103 90.2 78.0 91 EJY 120 77.7 61.0 93 EJ D 163 84:3 76.0 95 EJT 202 93.4 76.0 100 EJU 250 94.6 69.0 100 EJC 400 110.1 94.0 100 Table B-5-10 Charpy V-Notch Results for DA1 SMAW in SSP Capsule F Spec ID Temp (0F) CVN (ft-lb) LE (mils) %Shear EKB -40 10.0 9.0 15 EKJ -40 25.5 17.0 30 EKO -20 29.5 24.0 35 EKT 0 48.5 39.0 50 EEJ 0 40.5 33.0 50 EK1 70 56.5 49.0 70 EKA 150 86.5 78.0 95 EKE 200 90.0 77.0 100 EEC 300 108.5 89.0 100 EKY 400 98.5 84.0 100 B-5-8

ISP Weld Heat Evaluations Table B-5-1 1 Charpy V-Notch Results for DA1 SMAW in DA1 1080 Capsule Spec ID Tremp (°F) CVN (ft-lb) LE (mils) %Shear EEl -125.5 3.33 1.1 4.3 EE6 -59.3 9.6 11.0 15.0 EEA -30.3 20.39 18.7 23.6 EEB -11.4 28.08 24.5 28.4 EE7 -1.7 59.88 48.0 46.0 E J5 69.3 86.4 67.5 84.1 EJ6 201.7 118.43 88.0 100 EJ7 398.7 119.49 92.5 1O00 B-5-9

ISP Weld Heat Evaluations Tanh Curve Fits of CVN Test Data for Weld Heat DA 1 SMA W DA1 SURV WELD HEAT UNK (DA1 AND SSP) CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 09/09/2002 08:25 AM Page 1 Coefficients of Curve 1 A =50.7"7 B = 48.27 C = 79.1 TO =-9. D = 0.00E+O0 Equation is A + B

  • fTanh((T-To)/(C+DT))]

Upper Shelf Energy=99.0 Lower Shelf Energy=2.5(Fixed) Temp@30 ft-lbs=-45.4 Deg F Temnp@50 ft-lbs=-l0.2 Deg F Plant: Duane Arnold AND SSP Material: SMAW Heat: SURV WELD HIE Orientation: NA Capsule: UNIRRA Fluence: 0.0 n/cm^2 0o -- * - - ... . . . .. .. . . .. . 

                       -300       -200      -100         0        100         200        100    400     500 600 Temperature in Deg F Charpy V-Notch Data Temperature                      Input CVN                         Computed CVN                Differential
              -100.00                           6. 50                               11.29                    -4.79
               -80.00                           5.50                                16.25                  - 10. 75
               -60. 00                        16.80                                 23. 35                   -6. 55
               -50.00                         21.50                                 27. 78                   -6.28
               -40.00                         49. 00                                32. 77                    16.23
               -20.00                         58.00                                 44. 10                    13.90
                    .00                       52. 50                                56. 24                   -3.74
40. 00 65. 00 77. 36 - 12. 36 120. 00 102.00 95. 48 6. 52 200. 00 94. 00 98. 56 -4. 56 300. 00 88. 20 99. 00 - 10. 80 Figure B-5-1 Charpy Energy Data for Weld DA1 SMAW Unirradiated B-5-10

ISP Weld Heat Evaluations DA1 SURV WELD HEAT UNK (DA1 AND SSP) Page 2 Plant: Duane Arnold AND SSP Material: SMAW Heat: SURV WELD HE Orientation: NA Capsule: UNIRRA Fluence: 0.0 n/cmnA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 400. 00 113.70 99. 04 14. 66 Correlation Coefficient =.961 Figure B-5-1 Charpy Energy Data for Weld DA1 SMAW Unirradiated (Continued) B-5-11

ISP Weld Heat Evaluations Irradiated Weld Heat DA1 SMAW (DA1-288) CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 12117/2013 04:51 PM Page 1 Coefficients of Curye 3 A = 52.09 B3= 49.59 C = 65.4.8 TO = -11.49 D = 0.00E+00 Equation is A + B3* [Tanh((T-T6)I(C+DT))] Upper Shelf Energy=101,7 Lower Shelf Energy=2.5(Fiaed) Temp@30 ft-Ibs=-42.8 Deg F Temp@50 ft-lbs=-14.2 Deg F Plant: DUANE ARNOLD AND SSP Material: SMAW Heat: DA1 SMAW Orientation: NA Capsule: DA-288* Fluence: r,/cmA'2 

             *200 S150 U,.'

100 

                   -300     -200       -100          0         100     200       300       400       500          600 Temperature in Deg F Charpy V-Notch Data Temperature                       Ifiput CVN                      Computed CVN                 Differential
         - 100. 00                          6. 50                              8.72                      -2. 22
           - 60 O00                       15.30                              20. 86                      -5.56
           - 40.00o                       22. 00                             31. 77                      -9.77
           - 20. 00                      63; 50                             4.5. 68                     17.82
40. 00 75. 20 84. 64 -9. 44 120. 00 97 20 99.9:2 -2.72 200. 00 109. 00 101. 52 7. 48 400. O00 101. 00 101. 68 -. 68 Correlation Coefficientt' .975 Figure B-5-2 Charpy Energy Data for Weld DA1 SMAW in DA1 2880 Capsule B-5-12

ISP Weld Heat Evaluations Irradiated Weld Heat DA1 SMAW (DA1-36) CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 12/17/2013 04:50 PM Page 1 Coefficients of Curve 1 A = 49.05 B = 46.55 C = 84.36 TO = 7.36 D = 0.O0E+00 Equation is A + B * [Tanh((T-T6)/(C+DT))] Upper Shelf En~ergy=95.6(Fixed) Lower Shelf Energy=2.5(Fixed) Temp@30 ft-lbs=-29.3 Deg F Tenmp@5O fr-]bs=9.1 Deg F Plant: DUANE ARNOLD AND SSP Material: SMAW Heat: DAl SMAW Orjentafion:NA Capsule: DA1-36 Fluence: n/era^2 300 250

  • 200
         *150 C"
      >100 t          1          I-        t          2*

_________ t _________ j _________ 0 0 50 ________ 0 -4.-.--- ------ 4----- - --. --- nl 

               -300      -200      -100         0        100        200         300             400          500             600 Temperature in Deg F Charpy V-Notch Data Teiperature                       InputCVN,                      Computed CVN                               Differential
      -  80. 00                          7.20                                1.2.92                                 -5.72 23.,30                                21.52                                      1.78
      -25. 00                          28. 00                                32. 02                                 -4.02 48..90                                45. 00                                    3.90
33. o00 62. 70 62. 78 - . 0.8 4.9.00 74. 70 70. 33 4.37 10.3.00 90. 20 86. 86 3.34 120. 00 77.70 89. 57 - 11. 87 163. 00 84. 30 93.33 -9.03 Figure B-5-3 Charpy Energy Data for Weld DA1 SMAW in DAl 360 Capsule B-5-13

ISP Weld Heat Evaluations Irradiated Weld Heat DA1 SMAW (DA1-36) Page 2 Plant: DUANE ARNOLD AND SSP Material: SMAW Heat: DAl SMAW Orientation: NA Capsule: DA1-36 Fluence: n/cm^A2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 202. 00 93. 40 94. 69 -1.29 250. 00 94. 60 95. 31 -. 71 400. 00 110. 10 95. 59 14. 51 Correlation Coefficient = .977 Figure B-5-3 Charpy Energy Data for Weld DA1 SMAW in DA1 360 Capsule (Continued) B-5-14

ISP Weld Heat Evaluations Irradiated Weld Heat DA1 SMAW (SSP-F) CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 12/17/2013 04:53 PM Page 1 Coefficients of Curve 4 A = 50.75 B = 48.25 C = 122.89 TO.= 37.36 D = 0.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))] Upper Shelf Energy=99,0(Fixed) Lower Shelf Energy=2.5(Fixed) Temnp@30 ft-lbs=-19.1 Deg F Temp@50 ft-lbs=35.5 Deg F Plant:.DUANE ARNOLD AND SSP Material: SMAW Heat: DAl SMAW Orientation: NA Capsule: SSP-F Fluence: n/emA2 300 250 

        *200
        *150 e-100 50 0

O0 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temp~erature InputCV Computed CVN Differential 

      -40. 00                         10.O00                            23. 84                   -  13, 84
      -40. 00                         25. 50                            23. 84                       1. 66
      - 20. 00                        29. 50                            29;  73                       -. 23
            .00                       48. 50                            36. 52                     11. 98
            .00                       40. 50                            36. 52                       3. 98
70. 00 56. 50 63. 27 -6.77 150. 00 86. 50 85. 70 .80 200. 00 90. 00 92. 61 -2, 61 300. 00 108. 50 97. 68 10. 82 Figure B-5-4 Charpy Energy Data for Weld DA1 SMAW in SSP Capsule F B-5-15

ISP Weld Heat Evaluations Irradiated Weld Heat DA1 SMAW (SSP-F) Page 2 Plant: DUANE ARNOLD AND SSP Material: SMAW Heat: DA1 SMAW Orientation: NA Capsule: SSP-F Pluence: r/cmA2 Charpy V-Notch Data Temperatdre Input CVN Computed CVN Diffeerentijal 400. O00 98. 50 98. 74- .24 Correlation Coefficient =.976 Figure B-5-4 Charpy Energy Data for Weld DA1 SMAW in SSP Capsule F (Continued) B-5-16

ISP Weld Heat Evaluations Irradiated Weld Heat DA1 SMAW (DAI-108) CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 01/02/2014 10:04 PM Page .1 Coefficients of Curve .1 A = 60.75 B =58.25 C = 76.69 TO -23.34 D O.00E+00 Equation is A + B *' [Tanh((T-To)](C+DT))I Upper Shelf Energy=1 19. 0(Fixed) Lower Shelf Energy=2. 5(Fixed) Temp@30 ft-lbs=-21.6 Deg F Temp@50 ft-lbs=9.1 Deg F Plant: DUANE ARNOLD AND SSP Material: SMAW Heat: DA1 SMAW Orientation: NA Capsule: DA-108 Fluence: n/erna2 

         *200
       '15-
                                                             /

at ILl 

       >100 fI 50 A N
               -300    -200       -100          0          100      200      300       400        500        600 Temperature in Deg F Chiarpy V-Notch Data Tempeature                        Inpu CVN                        Computed CVN                  Differential
     -  125.,50                         3. 33                              4. 85                      -.1. 52
       -59.30                           9. 60                             14.60                       -5. 00
       -30.30                        20. 39                               25. 57                      -5. 18
       -  11. 40                     28.08                                36.03                       -7.95
         -1.70                       59.88                                42. 38                      17. 50 69.30                        86. 40                              92.01                       -5.61 201.70                       118.43                              117.90                             .53 398. 70                      119.49                              118.99                             .50 Correlation Coefficient = .986 Figure B-5-5 Charpy Energy Data for Weld DA1 SMAW in DA1 1080 Capsule B-5-17

ISP Weld Heat Evaluations { (E)}} Figure B-5-6 Fitted Surveillance Results for Weld Heat DAl SMAW B-5-18

ISP Weld Heat Evaluations References B-5-1i. GE Nuclear Energy, "Duane Arnold RPV Surveillance Materials Testing and Analysis," GE-NE-B1100716-01, July 1997. B-5-2 BWRVIP-279NP:~BWR Vessel and Internals Project, Testing and Evaluation of the Duane Arnold 108° Capsule. EPRI, Palo Alto, CA: 2014. 3002003134. B-5-3. B WR VIP-1l1NP, Revision 1: B WR Vessel and InternalsProject, Testing and Evaluation of BWR Supplemental Surveillance Program Capsules E, F and I. EPRI, Palo Alto, CA: 2010. 1021554. B-5-4. CVGRAPH, Hyperbolic Tangent Curve Fitting Program, Developed by ATI Consulting, Version 5.0.2, Revision 1, 3/26/02. B-5-5. "Radiation Embrittlement of Reactor Vessel Materials," USNRC Regulatory Guide 1.99, Revision 2, May 1988. B-5-6 "Format and Content of Report for Thermal Annealing of Reactor Pressure Vessels," USNRC Regulatory Guide 1.162, February 1996. B-5-7. K. Wichman, M. Mitchell, and A. Hiser, USNRC, Generic Letter 92-01 and RPV Integrity Workshop Handouts, NRC/Industry Workshop on RPV Integrity Issues, February 12, 1998. B-5-8. ASTM E-1 85, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels," American Society for Testing and Materials, July 1982. B-5-9. BWR Vessel and Internals Project: BWR IntegratedSurveillance ProgramPlan (BWRVIP-78). EPRI, Palo Alto, CA and BWRVIP: 1999. TR-1 14228. B-5-19

  • 1..121 PLOROWER REERHINSTITUTE 2014 TECHNICAL REPORT BWRVIP-135, Revision 3: BWR Vessel and Internals Project Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations NOTICE: This report contains proprietary information that is the intellectual property of u*'
  • 4*D,*,*WARNING:

Please read the Export Control EPRI. Accordingly, itis available oniy under license from EPRIand may not be reproduced SAI'i \ "90*,/Agreement on the back cover. or disclosed, wholly or in part, by any licensee to any other person or organization.

BWRVIP-1 35, Revision 3: BWR Vessel and Internals Project Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations 3002003144 Technical Report, December 2014 EPRI Project Manager R. Garter Quality Assurance Program apply to this product. ELECTRIC POWER RESEARCH INSTITUTE 3420 Hillview Avenlue, Palo Alto, California 94304-1338

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Plant-Specific Evaluations Duane Arnold Representative Surveillance Materials The ISP Representative Surveillance Materials for the Duane Arnold vessel target weld and plates are shown in the following table. Table 2-31 Target Vessel Materials and ISP Representative Materials for Duane Arnold Target Vessel Materials ISP Representative Materials Weld 432Z0471 DA1 SMAW Plate B0673-1 B0673-1 Summary of Available Surveillance Data: Plate The representative plate material B0673-l is contained in the following ISP capsules: Duane Arnold and SSP Capsule F ISpecific surveillance data related to plate heat B 0673-1 are summarized in Appendix A-3. Four capsules containing this plate heat have been tested. The Charpy V-notch surveillance results are as follows: Table 2-32 "1 30 Shift Results for Plate Heat B0673-1 Capsule Cu (wt%) Ni (wt%) Fluence (1017 n/cm 2, E > 1 MeV) AT30 (°F) Duane Arnold 2880 5.09 41.8 Duane Arnold 360 11.7 77.0 0.15 0.65 SSP F 18.699 73.4 Duane Arnold 1080 26.3 94.3 The results given in Appendix A-3 show a fitted chemistry factor (CF) of (( } }, as compared to a value of 111 .25°F from the chemistry tables in Reg. Guide 1.99, Rev. 2. The maximum scatter in the fitted data is (( }} which is well within the 1-sigma value of l17°F for plates as given in Reg. Guide 1.99, Rev. 2. Conclusions and Recommendations Because the representative plate material is the same heat number as the target plate in the Duane Arnold vessel, and because there are four irradiated data sets for this plate that fall within the 1-sigma scatter band, the ISP surveillance data should be used to revise the projected ART value for the target vessel plate with a reduced margin term (Regulatory Position 2.1). Recommended guidelines for use of ISP surveillance data are provided in Section 3 of this Data Source Book. 2-22

Plant-Specific Evaluations Summary of Available Surveillance Data: Weld The representative weld material DAl SMAW is contained in the following ISP capsules: Duane Arnold Capsules SSP Capsule F Specific surveillance data related to weld heat DAl SMAW are presented in Appendix B-5 and the results are summarized below. Four capsules containing weld heat DAl SIMAW have been tested. The Charpy V-notch surveillance results are as follows: Table 2-33 

   *T30Shift Results for Weld Heat DA1 SMAW Capsule             Cu (wt%)        Ni (wt%)               Fluence (1017 n/cm 2, E > 1 MeV)         AT20 (°F)

Duane Arnold 2880 5.09 2.6 Duane Arnold 360 11.7 16.1 0.02 0.94 SSP F 19.336 26.3 Duane Arnold 108° 26.3 23.8 The results given in Appendix B-5 show a fitted chemistry factor (CF) of (( }}, as compared to a value of 27.0°F from the chemistry tables in Reg. Guide 1.99, Rev. 2. The maximum scatter in the fitted data is (( }} which is well within the 1-sigma value of 28°F for welds as given in Reg. Guide 1.99, Rev. 2. Conclusions and Recommendations Because the representative weld material is not the same heat number as the target weld in the Duane Arnold vessel, the utility should use the chemistry factor from the Regulatory Guide 1.99, Rev. 2 tables to determine the projected ART value for the target vessel weld. Recommended guidelines for evaluation of ISP surveillance data are provided in Section 3 of this Data Source Book. 2-23

ISP Plate Heat Evaluations A-3 Plate Heat: B0673-1 Summary of Available Charpy V-Notch Test Data The available Charpy V-notch test data sets for plate heat B0673-1 are listed in Table A-3-1. The source documents for the data are provided, and the capsule designation and fluence values are also provided for irradiated data sets. Table A-3-1 ISP Capsules Containing Plate Heat B0673-1 Capsule Fluence (E> 1 MeV, 1017Rernc n/cm 2)Reene Unirradiated Baseline Data Duane Arnold 2880 5.09 References A-3-i and A-3-2 Duane Arnold 360 11.7 SSP Capsule F 18.699 Reference A-3-3 Duane Arnold 1080 26.3 Reference A-3-2 The CVN test data for each set taken from the references noted above are presented in Tables A-3-7 through A-3-11. The BWRVIP ISP uses the hyperbolic tangent (tanh) function as a statistical curve-fit tool to model the transition temperature toughness data. Tanhi curve plots for each data set have been generated using CVGRAPH, Version 5 [A-3-4] and the plots are provided in Figures A-3-1 through A-3-5. Best Estimate Chemistry Table A-3-2 details the best estimate average chemistry values for plate heat B 0673-1 surveillance material. Chemical compositions are presented in weight percent. If there are multiple measurements on a single specimen, those are first averaged to yield a single value for that specimen, and then the different specimens are averaged to determine the heat best estimate. Table A-3-2 Best Estimate Chemistry of Available Data Sets for Plate Heat B0673-1 Cu (wt%) Ni (wt%) P (wt%) S (wt%) Si (wt%) Specimen ID Source 0.15 0.7 0.006 -- 0.07 ETJ 0.15 0.69 0.006 -- 0.06 ETK 0.14 0.62 0.010 -- 0.01 EB4 Reference A-3-1 0.141 0.62 0.014 -- 0.02 EBA 0.145 0.65 0.010 -- 0.09 EBE 0.15 0.61 0.011 -- 0.18 Baseline CMTR Reference A-3-1 0.15 0.65 0.010 - 0.07 E.Best Estimate Average Calculation of Chemistry Factor (CF): The Chemistry Factor (CF) associated with the best estimate chemistry, as determined from U.S. NRC Regulatory Guide 1.99, Revision 2 [A-3-5], Table 2 (base metal), is: CF(Bo 673 .1) -. 111.25°F A-3-1

ISP Plate Heat Evaluations Effects of Irradiation The radiation induced transition temperature shifts for heat B0673-l are shown in Table A-3-3. The T30 [30 ft-lb Transition Temperature], T5 0 [50 ft-lb Transition Temperature], and T35 m~i [35 mul Lateral Expansion Temperature] have been determined for each Charpy data set, and each irradiated set is compared to the baseline (unirradiated) index temperatures. The change in Upper Shelf Energy (USE) is also shown. The unirradiated and irradiated values are taken from the CVGRAPH fits presented at the back of this sub-appendix (only CVN energy fits are presented). Comparison of Actual vs. Predicted Embrittlement A predicted shift in the 30 ft-lb transition temperature (AT30 ) is calculated for each irradiated data set using the Reg. Guide 1.99, Rev. 2, Regulatory Position 1.1 method. Table A-3-4 compares the predicted shift with the measured AT30 (°F) taken from Table A-3 -3. Comparison of Actual vs. Predicted Decrease in USE Table A-3-5 compares the actual percent decrease in upper shelf energy (USE) to the predicted decrease. The predicted decrease is estimated from USNRC Regulatory Guide 1.99, Rev. 2, Figure 2; the measured percent decrease is calculated from the values presented in Table A-3-3. A-3-2

ISP Plate Heat Evaluations Table A-3-3 Effect of Irradiation (E>1.0 MeV) on the Notch Toughness Properties of Plate Heat B0673-1 T30, 30 ft-lb T50, 50 ft-lb T25 mii,35 mil Lateral CVN Upper Shelf Energy Material Capsule Transition Temperature Transition Temperature Expansion Temperature (USE) Identity ID Unirrad irrad AT~o Unirrad Irrad AT,0 Unirrad Irrad AT3,mii Unirrad Irrad Change _______ (0 F) (0 F) (0 F) (0F) (0F) (°F) (0 F) (0 F) (0 F) (ft-lb) (ft-lb) (ft-lb) 2880 -35.5 6.3 41.8 -7.3 42.4 49.7 -23.6 18.6 42.2 158.1 158.8 0.7 DA1 and 360 -35.5 41.5 77.0 -7.3 70.7 78.0 -23.6 55.7 79.3 158.1 137.0 -21.1 SS P B0673-1 SSP F -35.5 37.9 73.4 -7.3 66.9 74.2 -23.6 57.8 81.4 158.1 133.0 -25.1 1080 -35.5 58.8 94.3 -7.3 91.4 98.7 -23.6 87.1 110.7 158.1 131.3 -26.8 Table A-3-4 Comparison of Actual Versus Predicted Embrittlement for Plate Heat B0673-1 Fluence Measured Shift 1 rGe1i99tev. Shf2 R .9Rv Capsule Identity Material (xl10'8 n/cm2 ) 0 F Prdce hf t Preictedrin' 0 F DA 2880 Plate Heat B0673-1 in Duane Arnold 0.509 41.8 32.9 65.8 DA 360 Plate Heat B0673-1 in Duane Arnold 1.17 77.0 50.0 84.0 SSP F Plate Heat B0673-1 in SSP 1.8699 73.4 61.6 95.6 DA 1080 Plate Heat B0673-1 in Duane Arnold 2.63 94.3 70.8 104.8 Notes:

1. See Table A-3-3 ATe.
2. Predicted shift = CF x FF, where CF is a Chemistry Factor taken from tables from USNRC Reg. Guide 1.99, Rev. 2, based on each material's Cu/Ni content, and FF is Fluence Factor, f02*0.,022I where f =fluence (10=* n/cm2, E > 1.0 May).

0

3. Margin = 2 2+ 2,where 2 =),the standard deviation on initial RT~DT (which is taken to be 0 F), and is the standard deviation on RTDT (28°F for welds and 17°F for base materials, except that need not exceed 0.50 times the mean value of RTNDT). Thus, margin is defined as 34°F for plate materials and 56°F for weld materials, or margin equals shift (whichever is lass), per Rag. Guide 1.99, Rev. 2.

A-3-3

ISP Plate Heat Evaluations Table A-3-5 Comparison of Actual Versus Predicted Percent Decrease in Upper Shelf Energy (USE) for Plate Heat B0673-1 RG 1.99 Rev. 2 MaeilFluence Maeil(xl 018 n/cm 2) Cu (wt%) Content Measured 1 USEDecrease (%) in Predicted 2 in USEDecrease (%) DA 2880 Plate Heat B0673-1 in Duane Arnold 0,509 3 11.9 0.15 DA3°Plate Heat B0673-1 in Duane Arnold 0.519 0.15 13314.9 SSP F Plate Heat B0673-1 in SSP 1.8699 0.15 15.9 16.1 DA 1080 Plate Heat B0673-1 in Duane Arnold 2.63 0.15 17.0 17.5 Notes:

1. See Table A-3-3, (Change in USE)/(Unirradiated USE).
2. Calculated using equations in Regulatory Guide 1.162 [A-3-6] that accurately model the Charpy upper shelf energy decrease curves in Regulatory Guide 1.99, Revision 2.
3. Less than zero.

A-3-4

ISP Plate HeatEvaluations Credibility of Surveillance Data The credibility of the surveillance data is determined according to the guidance of Regulatory Guide 1.99, Rev. 2 and 10 CFR 50.61, as supplemented by the NRC staff [A-3-7]. The following evaluation is based on the available surveillance data for irradiated plate heat B0673- 1. The applicability of this evaluation to a particular BWR plant must be confirmed on a plant-by-plant basis to verify there are no plant-specific exceptions to the following evaluation. Per Regulatory Guide 1.99, Revision 2 and 10 CFR 50.61, there are 5 criteria for the credibility assessment. Criterion 1: Materials in the capsules should be those judged most likely to be controlling with regard to radiation embrittlement. In order to satisfy this criterion, the representative surveillance material heat number must match the material in the vessel. Criterion2: 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 this sub-appendix. 1Based on engineering judgment, the scatter in these plots is small enough to permit the determination of the 30 ft-lb temperature and the upper shelf energy. Hence, this criterion is met. Criterion3: 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 17°F for plates. Even if the fluence range is large (two or more orders of magnitude), the scatter should not exceed twice that value. 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 El185-82 [A-3-8]. For plate material B30673-1, there are 4 surveillance capsule data sets currently available. The functional form of the least squares fit method as described in Regulatory Position 2.1 is utilized to determine a best-fit line for this data and to determine if the scatter of these ARTN*DT values about this line is less than 17°F for plates. Figure A-3-6 presents the best-fit line as described in Regulatory Position 2.1 utilizing the shift prediction routine from CVGRAPH, Version 5.0.2. The scatter of ARTNDT values about the functional form of the best-fit line drawn as described in Regulatory Position 2.1 is presented in Table A-3-6. A-3-5

ISP Plate Heat Evaluations Table A-3-6 Best Fit Evaluation for Surveillance Plate Heat B0673-1. Measred<17° F Mesued Best Fit Scatter (Base Metal) Material Fitted CF Casl F ARTNDT ARTNDT of ART NoT <28° F (0F) Casl F (30 ft-lb) (0F) (0F) (Weld (0F) metal) B0673-1 (( }} 288° 0.290 41.8 (( }} ((_ } Yes (( }} 360 0.436 77.0 (( }} (( }} Yes (( }} SSP F 0.553 73.4 (( }} (( }} Yes ((____ }} 1080 0.637 94.3 (( }} (( }} Yes Table A-3-6 indicates that the scatter is within acceptable range for credible surveillance data. Therefore, plate heat B0673-.1 meets this criterion. Criterion4: The irradiation temperature of the Charpy specimens in the capsule should match the vessel wall temperature at the cladding/base metal interface within + ! - 25°F. BWRVIP-78 [A-3-9] established the similarity of BWR plant environments in the BWR fleet. The annulus between the wall and the core shroud in the region of the surveillance capsules contains a mix of water returning from the core and feedwater. Depending on feedwater temperature, this annulus region is between 525°F and 535°F. This location of specimens with respect to the reactor vessel beltline is designed so that the reactor vessel wall and the specimens experience equivalent operating conditions such that the temperature will not differ by more than 25°F. Any plant-specific exceptions to this generic analysis should be evaluated. Criterion5: The surveillance data for the correlation monitor material in the capsule should fall within the scatter band of the database for that material. Few ISP capsules contain correlation monitor material. Generally, this criterion is not applicable. For plate heat B 0673-1, these criteria are satisfied (or not applicable). The surveillance data are nominally credible because the scatter criterion is met. Prior to application of the data, a plant should verify that no plant-specific exceptions to these criteria exist. A-3 6

ISP Plate Heat Evaluations Table A-3-7 Unirradiated Charpy V-Notch Results for Surveillance Plate B0673-1 (LT) Spec ID Temp (°F) CVN (ft-lb) LE (mils) %Shear ED4 -100 6.5 7.0 0 ED1 -80 4.2 5.0 0 ECT -40 9.0 14.0 10 EDK -40 24.0 30.0 5 ED7 -30 38.0 35.0 5 EDT -30 49.0 30.0 5 ED6 -20 47.0 43.0 10 ED5 -10 43.0 43.0 20 ECP 0 56.5 49.0 25 ECM 40 98.5 73.0 40 ECL 120 134.5 73.0 80 ECK 200 158.5 93.0 85 EDY 300 163.5 81.0 90 EDA 400 No Break No Break No Break Table A-3-8 Charpy V-Notch Results for B0673-1 (LT) in Duane Arnold 288 Deg Capsule Spec ID Temp (0F) CVN (ft-tb) LE (mils) %Shear EBU -60 4.0 4.0 0 EBP -20 15.0 19.0 0 EBT 10 15.5 26.0 40 EC1 20 49.5 45.0 40 EBK 40 60.0 49.0 40 EBJ 120 101.5 70.0 70 EBL 200 144.5 95.0 90 EBY 400 160.0 98.0 90 A-3-7

ISP Plate Heat Evaluations Table A-3-9 Charpy V-Notch Results for B0673-1 (LT) in Duane Arnold 36 Deg Capsule Spec ID Temp (0 F) CVN (ft-lb) LE (mils) %Shear EBD -50 5.0 5.0 1 EB1 0 18.5 15.0 41 EB2 13 27.7 24.0 10 EB3 25 13.7 13.0 27 EBC 32 15.4 23.0 24 EB6 40 15.4 16.0 32 EB4 49 59.2 48.0 32 EB5 81 51.5 43.0 44 EBA 120 92.9 69.0 78 EB7 202 127.8 82.0 100 EBE 250 142.8 84.0 100 EBB 400 140.5 94.0 100 Table A-3-10 Charpy V-Notch Results for B0673-1 (LT) in SSP Capsule F Spec ID Temp (0 F) CVN (ft-lb) LE (mils) %Shear EDJ 0 12.5 9.0 0 ECU 30 25.5 22.0 20 EDD. 50 24.5 21.0 20 ECY 50 34.5 26.0 30 ED)M 70 71.5 54.0 45 EDP 150 103.5 78.0 75 EDB 175 113.5 82.0 85 ED2 200 139.0 89.0 100 ECJ 300 134.5 91.0 100 ECE 400 125.5 85.0 100 A-3-8

ISP Plate Heat Evaluations Table A-3-11 Charpy V-Notch Results for B0673-1 (LT) in Duane Arnold 1080 Capsule Spec ID Temp (0F) CVN (ft-lb) LE (mils) %Shear ECB -1.3 4.2 5.0 4.2 EGO 35.8 23.88 17.3 10.4 EC3 69.1 42.06 30.4 17.6 EC7 128.7 63.71 48.5 38.6 ECD 160.5 111.06 76.2 67.2 ECA 191.5 110.36 76.0 84.1 EC4 252.0 129.48 91.0 100.0 EC5 400.8 133.11 92.9 100.0 A-3-9

ISP PlateHeat Evaluations Tanh Curve Fits Of CVN Test Data for Plate Heat 80673-1 PLATE HEAT B0673-1 (DA AND SSP) CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 09/09/2002 08:29 AM Page 1 Coefficients of Curve 1 A = 80.31 B =77.81 C =78.77 TO = 25.02 D = O.00E+00 Equation is A + B * [Tanh((T-To)/(C+DT))] Upper Shelf Energy=1 58.1 Lower Shelf Energy=2.5(Fixed) Temp@30 ft-lbs=-35.5 Deg F Temp@50 ft-lbs*-7.3 Deg F Plant: DUANE ARNOLD AND SSP Material: SA533B1 Heat: B0673-1 Orientation: LT Capsule: UNIRRA Fluence: 0.0 n/emA2 U.I z 1 I o 

                      -300
                                  -i------ -100
                                 -200
                                            --T* ..    ._

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

             -1I00. 00                         6. 50                               8.75                         -2.25
               - 80. 00                        4. 20                              12. 6t                        -8.41
               - 40. 00                         9. 00                            27. 56                       -18.56
               - 40. 00                       24. 00                           27. 56                         -3.56
               -30. 00                        38. 00                           33. 36                           4.64
               -30. 00                        49. 00                           33. 36                         15.64
               - 20. 00                       47. 00                            40. 12                           6. 88
               -10.00                         43. 00                           47. 83                         -4.83
                    .00                       56. 50                            56. 40                             .10
40. 00 98. 50 94. 93 3.57 120. 00 134. 50 145.31 -10.81 Figure A-3-1 Charpy Energy Data for Pfate B0673-1 (LT) Unirradiated A-3-10

ISP Plate Heat Evaluations PLATE HEAT B0673-1 (DA AND SSP) Page 2 Plant: DUANE ARN'OLD AND SSP Material: SA533B1 Heat: B0673-1 Orientation: LT Capsule: UNIRRA Fluence: 0.0 rdcm^2 Charpy V-Notch Data Input CVN Computed CVN Differential Temperature 200. 00 158.50 156. 31 2. 19 300.,00 163.50 157. 97 5,53 Correlation Coeffeient =.988 Figure A-3-1 Charpy Energy Data for Plate 1B0673-1 (LT) Unirradiated (Continued) A-.3-11

ISP Plate Heat Evaluations Irradiated Plate Heat B0673-1 (DA1-288) CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 12/17/2013 01:33 PM Page 1 Coefficients of Curve 1 A = 80.66 B = 78.16 C.= 101.16 TO =84.32 D = 0.O0E+00 Equation is A +IB.*[Tanh((T-To)f(C+DT))] upper Shelf Energy=l 58.8 Lower Shelf Energy=2.5(Fixed) 

                                     *Temp@30 ft-lbs=6.3 Deg F           Temp@50 ft-lbs=42.4 Deg P Plant: DUANE ARNOLD AND SSP Material: SA533B1                   Heat: B 0673-1 Orientation: LT Capsule: DA-288              Fluence*      n/cmA2 300 250
             *200 50 U-100 0

50 0 0 300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data TIemnpeatsure Input CVN Computed CVN Differential 

            -60.00                             4. 00                              11.02                       -7.02
            -20.00                           15. 00                              20. 13                      -5.13 1.o. 00                         15. 50                              31. 74                    - 16.24
20. 00 49. 50 3.6. 73 12. 77
40. 00 60. 00 48.45 11.55 120.00 10"1. 50 107. 13 -5. 63 200. 00 144. 50 144. 40 ,10 400. 00 160. 00 158. 51 1. 49 Correlation Coefficient = .987 Figure A-3-2 Charpy Energy Data for Plate B0673-1 (LT) in Duane Arnold 288° Capsule A-3-12

ISP Plate Heat Evaluations Irradiated Plate Heat B0673-1 (~DA1-36) CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 22/17/20.13 01:34 PM Page 1 Coefficients of Curve 2 A = 69.75 B = 67.25 C = 77.56 TO = 94.1 D = 0.00E+00 Equation is A + B * [T*anh((T-To)/(C+DT))] Upper Shelf Enlergy=137.0(Fixed) Lower Shelf Energy=2.5(Fixed) Temp@30 ft-lbs=41.5 Deg F Temp@50 ft-lbs=70.7 Deg.F Plant: DUANE ARNOLD AND SSP Material: SA533B1 Heat: B0673-1 Oriefitation: LT Ca~psule: DA-36 Fluence: n/cmt'2 300 250 

           .200
       *10 U,-

100 

                                                               /

50 0 

               -300      -200        -100         0        100       200         300     400       500       600 Temperature in Deg F Charpy V-Notch Data Temperature                         InputCVN                       Competed CYN                 Differential
       -50. 00                            :5, 00                              5. 70                     -. 70
             ,00                         18. 50                             13. 42                    5. 08
13. 00 27. 70 17. 29 10. 41
13. 70 21. 88 -8.18
32. 00 15. 40 2*5.07 -9.67"
40. 00 15. 40 29. 21 -13..81
49. 00 59. 20 34. 53 24. 67 81.00 51.50 58. 50 -7.00 120. 00 92. 90 91.41 1. 49 Figure A-3-3 Charpy Energy Data for Plate 60673-1 (LT) in Duane Arnold 360 Capsule I

A-3 -13

ISP Plate Heat Evaluations Irradiated Plate Heat B0673-1 (IDA1-36) Page 2 Plant: DUANE ARNOLD AND SSP Material: SA533B1 Heat: B0673-1 Orientation: LT Capsule: DA-36 Fluence: n/cma2 Charpy V-Notch Data Temperatdite Input CVN Computed CVN Differential 202. 00 127. 80 12,9. 16 -1.36 250. 00 142..80 134. 63 8. 17 400. 00 140. 50 136.95 3. 55 Correlation Coefficent =.980 Figure A-3-3 Charpy Energy Data for Plate B0673-1 (LT) in Duane Arnold 360 Capsule (Continued) A-3-14

ISP Plate Heat Evaluations Irradiated Plate Heat B0673-1 (SSP-F) CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 12/17/2013 01:34 PM Page 1 Coefficients of Curve 3 A = 67.75 B = 65.25 C = 76.12 TO = 88.09 D = O.OO0E+O0 Equation is A + B * [Tanla((T-To)/(C+FDI))] Upper Shelf Energy=133.0(Fixed) Lower Shelf Energy=2.5(Fixed) Temp@30 ft-lbs=37.9 .feg*F Temp@5SO ft-lhs=66.9 Deg F Plant: DUANE ARNOLD AND SSP Material: SA533B1 Heat: B 0673-1 Orientation: LT Capsule: $8P-F Fluence: rtcmA2 a uu 2.50.. 2'00 U- 50 ji C 

                                                                'so DO/

0....--+ 

                            "..r ....   ....           0 !'
              -300      -200       -100         0        100        200       300      400       500         600 Temperature in Deg F Charpy V-Notch Data Temperature                       InputCVN                       Comnputed.CVN                 Differential 12.50                              14. 24                      -1. 74
          $.00
25. 50 25..80 - .30
50. 00 24. 50 $7. 57 - 13. 07
50. 00 34. 50 3.7. 57 -3.07
70. 00 71. 50 52. 53 18.97 150. 00 103. 50 111. 56 - 8.06 175.00 113.50 120. 93 -7.43 200. 00 139. 00 126.45 12. 55 300.00 134. 50 132. 50 2. 00 Figure A-3-4 Charpy Energy Data for Plate B0673-1 (LT) in SSP Capsule F A-3-15

Isp PlateHeat Evaluations Irradiated Plate Heat B0673-1 (SSP-F) Page 2 Plant: DUANE. ARNOLD AND SSP Material: SA533B1 Heat: B0673-1 Orientation: LT Capsule: SSP-F Fluence: n/era^2 Charpy V-Notch Data Temjperature Input CVN Com~puted.CVN Diffferential 400. 00 125.50 132. 96 7. 46 Correlation Coefficient =.981 Figure CharpyA-3-4 Energy Data for Plate B0673-1 (LT) in SSP Capsule F (Continued) f A 16

ISP Plate Heat Evaluations Irradiated Plate Heat B0673-1 (jDA!-108) CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 12/31/2013 09:45 AM Page 1 Coefficients of Curve 1 A = 66.9 B = 64.4 C = 85.21 T0 = 114.29 D = 0.00E+00 Equation is A + B * [Tanh((T-To)/(C+-DT))I Upper Shelf Energy*=131.3(Fixed) Lower Shelf Energy,=2.5(Fixed) Temp@30 ft-lbs=58.8 Deg F Temp@l50 ft-lbs=91.4 Deg F Plant: DUANE ARNOLD AND SSP Material: SA533B1 Heat: B 0673-1 Orientation: LT Capsule: DA-108 Fluencee: rdcm^2 300 250 

         *200 a
         *150 ull                                                         0 .. _
          "100 0

50 0 

              -300   -200        -100         0          100      200       300       400        500        600 Temperature in Deg F Charpy V-Notch Data Temperature                      nput CVN                       Compute CVNN                    Differential
        -'1. 30                       4. 20                             10. 51                       -6.31
35. 80 23. 88 20. 12 3.76
69. 10 42. 06 35. 63 6.43 128. 70 63.71 77. 69 -13.98 160. 50 111.06 98. 76 12. 30 191. 50 1i0.36 113. '22 -2.86 252. 00 129. 48 126.41 3.07 400. 80 133. 11 131. 15 1.96 Correlation Coefficient = .987 Figure A-3-5 Charpy Energy Data for Plate B0673-1 (LT) in Duane Arnold 1080 Capsule A-3-17

ISP Plate Heat Evaluations Figure A-3-6 Fitted Surveillance Results for Plate Heat B0673-1 A-3-18

ISP Plate Heat Evaluations References A-3-1. GE Nuclear Energy, "Duane Arnold RPV Surveillance Materials Testing and Analysis," GE-NE-B 1100716-01, July 1997. A-3-2. BWRVJP-279NP: BWR Vessel and Internals Project, Testing and Evaluation of the DuaneArnold 1080 Capsule. EPRI, Palo Alto, CA: 2014. 3002003134. A.-3-3. BWRVIP-J11NP, Revision 1:~BWR Vessel and Internals Project, Testing and Evaluation of BWR Supplemental Surveillance ProgramCapsules E, F and I. EPRI, Palo Alto, CA: 2010. 1021554. A-3-4. CVGRAPH, Hyperbolic Tangent Curve Fitting Program, Developed by ATI Consulting, Version 5.0.2, Revision 1, 3/26/02. A-3-5. "Radiation Embrittlement of Reactor Vessel Materials," USNRC Regulatory Guide 1.99, Revision 2, May 1988. A-3-6. "Format and Content of Report for Thermal Annealing of Reactor Pressure Vessels," USNRC Regulatory Guide 1.162, February 1996. A-3-7. K. Wichiman, M. Mitchell, and A. Hiser, USNRC, Generic Letter 92-01 and RPV Integrity Workshop Handouts, NRC/Industry Workshop on RPV Integrity Issues, February 12, 1998. A-3-8. ASTM E-185, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels," American Society for Testing and Materials, July 1982. A-3-9. BWR Vessel and InternalsProject: BWR IntegratedSurveillance ProgramPlan (BWRVIP-78). EPRI, Palo Alto, CA and BWRVIP: 1999. TR-1 14228. A-3-19

ISP Weld Heat Evaluations B-5 Weld Heat: DA1 SMAW Summary of Available Charpy V-Notch Test Data The available Charpy V-notch test data sets for weld heat DA1 SMAW are listed in Table B-5-i. The source documents for the data are provided, and the capsule designation and fluence values are also provided for irradiated data sets. Table 6-5-1 ISP Capsules Containing Weld Heat DA1 SMAW Capsule Fluence (E> 1 MeV, 1017 n/cm 2) Reference Unirradiated Baseline Data References B-5-1 Duane Arnold 1 288° 5.09anB-2 Duane Arnold 1 360 11.7 SSP Capsule F 19.336 Reference B-5-3 Duane Arnold 1 1080 26.3 Reference B-5-2 The CVN test data for each set taken from the references noted above are presented in Tables B-5-7 through B-5-i11. The BWRVIP ISP uses the hyperbolic tangent (tanh) function as a statistical curve-fit tool to model the transition temperature toughness data. Tanh curve plots for each data set have been generated using CVGRAPH, Version 5 [Reference B-5-4] and the plots are provided in Figures B-5-1 through B-5-5. Best Estimate Chemistry Table B-5-2 details the best estimate average chemistry values for weld heat DA1 SMAW surveillance material. Chemical compositions are presented in weight percent. If there are multiple measurements on a single specimen, those are first averaged to yield a single value for that specimen, and then the different specimens are averaged to determine the heat best estimate. Table B-5-2 Best Estimate Chemistry of Available Data Sets for Weld Heat DA1 SMAW Cu Ni Source (wt%) (wt%) (wt%) (wt%) (wt%) Specimen ID Suc 0.02 1.00 0.011 -- 0.32 EU3 irrad 0.02 0.90 0.010 -- 0.33 EU6 irrad 0.025 0.96 0.011 -- 0.02 EJM Reference B-5-1 0.025 0.94 0.008 -- 0.02 EJJ 0.024 0.88 0.010 -- 0.02 EJA 0.02 0.94 0.010 -- 0.14 E-=Best Estimate Average B-5-1

ISP Weld Heat Evaluations Calculation of Chemistry Factor (CF): The Chemistry Factor (CF) associated with the best estimate chemistry, as determined from U.S. NRC Regulatoly' Guide 1.99, Revision 2 [Reference B-5-4], Table 1 (weld metal), is: CF(DAlSNm = 27"0OF Effects of Irradiation The radiation induced transition temperature shifts for heat DAl SMAW are shown in Table B-5-3. The T30 [30 ft-lb Transition Temperature], T1so [50 ft-lb Transition Temperature], and T35mi, I[35 mil Lateral Expansion Temperature] index temperatures have been determined for each Charpy data set, and each irradiated set is compared to the baseline (unirradiated) index temperatures. The change in Upper Shelf Energy (USE) is also shown. The unirradiated and irradiated values are taken from the CVGRAPH fits presented at the back of this sub-appendix (only CVN energy fits are presented). Comparison of Actual vs. Predicted Embrittlement A predicted shift in the 30 ft-lb transition temperature (AT30) is calculated for each irradiated data set using the Reg. Guide 1.99, Rev. 2, Regulatory Position 1.1 method. Table B-5-4 compares the predicted shift with the measured AT30 (0 F) taken from Table B-5-3. Comparison of Actual vs. Predicted Decrease in USE Table B-5-S compares the actual percent decrease in upper shelf energy (USE) to the predicted decrease. The predicted decrease is estimated from USNRC Regulatory Guide 1.99, Rev. 2, Figure 2; the measured percent decrease is calculated from the values presented in Table B-5-3. B-5-2

ISP Weld Heat Evaluations Table B-5-3 Effect of Irradiation (E>1I.0 MeV) on the Notch Toughness Properties of Weld Heat DA1 SMAW T30, 30 ft-lb To, 50 ft-lb T35 m, 1, 35 mil Lateral CVN Upper Shelf Energy Material Capsule Transition Temperature Transition Temperature Expansion Temperature (USE) Iett ID Unirrad Irrad AT3 Unirrad Irrad A~e Unirrad Irrad A30m,, Unirrad Irrad Change (0 F) (0F) (°F) (0 F) (0 F) (°F) (°F) (0F) (0F) (ft-lb) (ft-lb) (ft-lb) Dl 2880 -45.4 -42.8 2.6 -10.2 -14.2 -4.0 -37.3 -37.2 0.1 99.0 101.7 2.7 and 360 -45.4 -29.3 16.1 -10.2 9.1 19.3 -37.3 -5.5 31.8 99.0 95.6 -3.4 SSP DAl SSP F -45.4 -19.1 26.3 -10.2 35.5 45.7 -37.3 14.2 51.5 99.0 99.0 0.0 SMAW_________ __ _ 1080 -45.4 -21.6 23.8 -10.2 9.1 19.3 -37.3 -2.9 34.4 99.0 119.0 20.0 Table B-5-4 Comparison of Actual Versus Predicted Embrittlement for Weld Heat DA1 SMAW Capsule Material Fluence Measured1 Pr 1.99 ceRG Rev. 2sft RGprd Rev. e1.992 Identity (x T /m) Sit° FShift+Margin2 3, DA1 288° Weld Heat D)A1 SMAW in Duane Arnold 0.509 2.6 8.0 16.0 DAl 360 Weld Heat DAl SMAW in Duane Arnold 1.17 16.1 12.1 24.2 SSP Capsule F Weld Heat DA1 SMAW in SSP Capsule F 1.9336 26.3 15.1 30.3 DA1 1080 Weld Heat DA1 SMAW in Duane Arnold 2.63 23.8 17.2 34.4 Notes:

1. See Tabie B-5-3, AT,,o.
2. Predicted shift = CF x FE, where CF is a Chemistry Factor taken from tables from USNRC Reg. Guide 1.99, Rev. 2, based on each material's Cu/Ni content, and FE is Fluence Factor, fo22*.1olo% where f =fluence (10"9 n/cm 2, E > 1.0 MeV).

3.Margin =2'l(o* 2 + oA2), where o, = the standard deviation on initial RT,,,, (which is taken to be 0°F), and OA is the standard deviation on ARTNDT (28°F for welds and 170F for base materials, except that 0 A need not exceed 0.50 times the mean value of ARTNOT). Thus, margin is defined as 34°F for plate materials and 56°F for weld materials, or margin equals shift (whichever is less), per Reg. Guide 1.99, Rev. 2. B-5-3

ISP Weld Heat Evaluations Table B-5-5 Comparison of Actual Versus Predicted Percent Decrease in Upper Shelf Energy (USE) for Weld Heat DA1 SMAW RG 1.99 Rev. 2 Capsule MaeilFluence Cu Content Meceasuedi Predicted Identity Maeil(xl 018 n/cm 2) (wt%) DereSE(%n Decrease in USE 2 USE 1 (%)(%) DA1 2880 Weld Heat DA1 SMAW in Duane Arnold 0.509 0.02 -37.9 DA1 360 Weld Heat DA1 SMAW in Duane Arnold 1.17 0.02 3.4 9.6 SSP Capsule F Weld Heat DA1 SMAW in SSP Capsule F 1.9336 0.02 0 10.8 DA1 1080 Weld Heat DA1 SMAW in Duane Arnold 2.63 0.02 -411.7 Notes:

1. See Table B-5-3, (Change in USE)/(unirradiated usE).
2. Calculated using equations in Regulatory Guide 1.162 [B-5-6] that accurately model the Charpy upper shelf energy decrease curves in Regulatory Guide 1.99, Revision 2.
3. Value less than zero.

B-5-4

ISP Weld Heat Evaluations Credibility of Surveillance Data The credibility of the surveillance data is determined according to the guidance of Regulatory Guide 1.99, Rev. 2 and 10 CFR 50.61, as supplemented by the NRC staff [Reference B-5-7]. The following evaluation is based on the available surveillance data for irradiated weld heat DA1 SMAW. The applicability of this evaluation to a particular BWR plant must be confirmed on a plant-by-plant basis to verify there are no plant-specific exceptions to the following evaluation. Per Regulatory Guide 1.99, Revision 2 and 10 CFR 50.61, there are 5 criteria for the credibility assessment. Criterion 1: Materials in the capsules should be those judged most likely to be controlling with regard to radiation embrittlement. In order to satisfy this criterion, the representative surveillance material heat number must match the material in the vessel. Criterion2: 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 this sub-appendix. Based on engineering judgment, the scatter in these plots is small enough to permit the determination of the 30 ft-lb temperature and the upper shelf energy. Hence, this criterion is met. Criterion3: When there are two or more sets of surveillance data from one reactor, the scatter of values about a best-fit line drawn as described in Regulatory Position 2.1 normally NDRT* should be less than 28°F for welds. Even if the fluence range is large (two or more orders of magnitude), the scatter should not exceed twice that value. 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 El185-82 [Reference B-5-8]. For weld material DA1 SMAW, there are 4 surveillance capsule data sets currently available. The functional form of the least squares fit method as described in Regulatory Position 2.1 is utilized to determine a best-fit line for this data and to determine if the scatter of these AXRTNDT values about this line is less than 28°F for welds. Figure B-5-6 presents the best-fit line as described in Regulatory Position 2.1 utilizing the shift prediction routine from CVGRAPH, Version 5.0.2. The scatter of RT* values about the functional form of the best-fit line drawn as described in Regulatory Position 2.1 is presented in Table B-5-6. B-5-5

ISP Weld Heat Evaluations Table B-5-6 Best Fit Evaluation for Surveillance Plate Heat DA1 SMAW Measured Best Scatter <17 0 F Maeil Fitted ARTND Fit of (Base Metal) CF ( 0F) Casl F (30 ft-lb) ARTNDT ARTN~ <28°F (0F) (0F) (0F) (Weld metal) (( }} DA1 2880 0.296 2.6 (( }} (( }} Yes DA1l { }} DA1 360 0.449 16.1 (( }} (( }} Yes SMAW (( }} SSP F0 0.56 1 26.3 (( }} (( }} Yes (( }} DA1 1080 0.637 23.8 (( }}(( }} Yes Table B-5-6 indicates that the scatter is within acceptable range for credible surveillance data. Therefore, weld heat DAl SMAW meets this criterion. Criterion4: The irradiation temperature of the Charpy specimens in the capsule should match the vessel wall temperature at the cladding/base metal interface within +/ 25°F. BWRVIP-78 [Reference B-5-9] established the similarity of BWR plant environments in the BWR fleet. The annulus between the wall and the core shroud in the region of the surveillance capsules contains a mix of water returning from the core and feedwater. Depending on feedwater temperature, this annulus region is between 525°F and 535°F. This location of specimens with respect to the reactor vessel beltline is designed so that the reactor vessel wall and the specimens experience equivalent operating conditions such that the temperature will not differ by more than 25°F. Any plant-specific exceptions to this generic analysis should be evaluated. 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. Few ISP capsules contain correlation monitor material. Generally, this criterion is not applicable. For weld heat DA1 SMAW, these criteria are satisfied (or not applicable). The surveillance data are nominally credible because the scatter criterion is met. Prior to application of the data, a plant should verify that no plant-specific exceptions to these criteria exist. B-5-6

ISP Weld Heat Evaluations Table B-5-7 Unirradiated Charpy V-Notch Results for Surveillance Weld DA1 SMAW Spec ID Temp (0F) CVN (ft-lb) *LE (mils) %Shear EET -100 6.5 11.0 10 EEK -80 5.5 10.0 15 EK3 -60 16.8 19.0 40 EK4 -50 21.5 22.0 20 EEE -40 49.0 45.0 20 EK2 -20 58.0 57.0 50 EEL 0 52.5 50.0 30 EEY 40 65.0 61.0 50 EED 120 102.0 88.0 80 EEM 200 94.0 65.0 70 EK5 300 88.2 93.0 60 EK6 400 113.7 96.0 70 Table B-5-8 Charpy V-Notch Results for DA1 SMAW in DA1 288 Deg Capsule Spec ID Temp (°F) CVN (ft-lb) LE (mils) %Shear EJ1 -100 6.5 11.0 0 E J2 -60 15.3 24.0 10 E J4 -40 22.0 26.0 10 EE5 -20 63.5 54.0 40 EE2 40 75.2 69.0 60

  • EE3 120 97.2 86.0 80 EE4 200 109.0 90.0 70 E J3 400 101.0 91.0 100 B-5-7

ISP Weld Heat Evaluations Table B-5-9 Charpy V-Notch Results for DA1 SMAW in DAl 36 Deg Capsule Spec ID Temp (0 F) CVN (ft-lb) LE (mils) %Shear EJP -80 7.2 6.0 25 EJL -50 23.3 19.0 33 EJM -25 28.0 24.0 36 EJK 0 48.9 41.0 49 EJJ 33 62.7 51.0 62 EJE 49 74.7 61.0 73 EJA 103 90.2 78.0 91 EJY 120 77.7 61.0 93 EJ D 163 84:3 76.0 95 EJT 202 93.4 76.0 100 EJU 250 94.6 69.0 100 EJC 400 110.1 94.0 100 Table B-5-10 Charpy V-Notch Results for DA1 SMAW in SSP Capsule F Spec ID Temp (0F) CVN (ft-lb) LE (mils) %Shear EKB -40 10.0 9.0 15 EKJ -40 25.5 17.0 30 EKO -20 29.5 24.0 35 EKT 0 48.5 39.0 50 EEJ 0 40.5 33.0 50 EK1 70 56.5 49.0 70 EKA 150 86.5 78.0 95 EKE 200 90.0 77.0 100 EEC 300 108.5 89.0 100 EKY 400 98.5 84.0 100 B-5-8

ISP Weld Heat Evaluations Table B-5-1 1 Charpy V-Notch Results for DA1 SMAW in DA1 1080 Capsule Spec ID Tremp (°F) CVN (ft-lb) LE (mils) %Shear EEl -125.5 3.33 1.1 4.3 EE6 -59.3 9.6 11.0 15.0 EEA -30.3 20.39 18.7 23.6 EEB -11.4 28.08 24.5 28.4 EE7 -1.7 59.88 48.0 46.0 E J5 69.3 86.4 67.5 84.1 EJ6 201.7 118.43 88.0 100 EJ7 398.7 119.49 92.5 1O00 B-5-9

ISP Weld Heat Evaluations Tanh Curve Fits of CVN Test Data for Weld Heat DA 1 SMA W DA1 SURV WELD HEAT UNK (DA1 AND SSP) CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 09/09/2002 08:25 AM Page 1 Coefficients of Curve 1 A =50.7"7 B = 48.27 C = 79.1 TO =-9. D = 0.00E+O0 Equation is A + B

  • fTanh((T-To)/(C+DT))]

Upper Shelf Energy=99.0 Lower Shelf Energy=2.5(Fixed) Temp@30 ft-lbs=-45.4 Deg F Temnp@50 ft-lbs=-l0.2 Deg F Plant: Duane Arnold AND SSP Material: SMAW Heat: SURV WELD HIE Orientation: NA Capsule: UNIRRA Fluence: 0.0 n/cm^2 0o -- * - - ... . . . .. .. . . .. . 

                       -300       -200      -100         0        100         200        100    400     500 600 Temperature in Deg F Charpy V-Notch Data Temperature                      Input CVN                         Computed CVN                Differential
              -100.00                           6. 50                               11.29                    -4.79
               -80.00                           5.50                                16.25                  - 10. 75
               -60. 00                        16.80                                 23. 35                   -6. 55
               -50.00                         21.50                                 27. 78                   -6.28
               -40.00                         49. 00                                32. 77                    16.23
               -20.00                         58.00                                 44. 10                    13.90
                    .00                       52. 50                                56. 24                   -3.74
40. 00 65. 00 77. 36 - 12. 36 120. 00 102.00 95. 48 6. 52 200. 00 94. 00 98. 56 -4. 56 300. 00 88. 20 99. 00 - 10. 80 Figure B-5-1 Charpy Energy Data for Weld DA1 SMAW Unirradiated B-5-10

ISP Weld Heat Evaluations DA1 SURV WELD HEAT UNK (DA1 AND SSP) Page 2 Plant: Duane Arnold AND SSP Material: SMAW Heat: SURV WELD HE Orientation: NA Capsule: UNIRRA Fluence: 0.0 n/cmnA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 400. 00 113.70 99. 04 14. 66 Correlation Coefficient =.961 Figure B-5-1 Charpy Energy Data for Weld DA1 SMAW Unirradiated (Continued) B-5-11

ISP Weld Heat Evaluations Irradiated Weld Heat DA1 SMAW (DA1-288) CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 12117/2013 04:51 PM Page 1 Coefficients of Curye 3 A = 52.09 B3= 49.59 C = 65.4.8 TO = -11.49 D = 0.00E+00 Equation is A + B3* [Tanh((T-T6)I(C+DT))] Upper Shelf Energy=101,7 Lower Shelf Energy=2.5(Fiaed) Temp@30 ft-Ibs=-42.8 Deg F Temp@50 ft-lbs=-14.2 Deg F Plant: DUANE ARNOLD AND SSP Material: SMAW Heat: DA1 SMAW Orientation: NA Capsule: DA-288* Fluence: r,/cmA'2 

             *200 S150 U,.'

100 

                   -300     -200       -100          0         100     200       300       400       500          600 Temperature in Deg F Charpy V-Notch Data Temperature                       Ifiput CVN                      Computed CVN                 Differential
         - 100. 00                          6. 50                              8.72                      -2. 22
           - 60 O00                       15.30                              20. 86                      -5.56
           - 40.00o                       22. 00                             31. 77                      -9.77
           - 20. 00                      63; 50                             4.5. 68                     17.82
40. 00 75. 20 84. 64 -9. 44 120. 00 97 20 99.9:2 -2.72 200. 00 109. 00 101. 52 7. 48 400. O00 101. 00 101. 68 -. 68 Correlation Coefficientt' .975 Figure B-5-2 Charpy Energy Data for Weld DA1 SMAW in DA1 2880 Capsule B-5-12

ISP Weld Heat Evaluations Irradiated Weld Heat DA1 SMAW (DA1-36) CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 12/17/2013 04:50 PM Page 1 Coefficients of Curve 1 A = 49.05 B = 46.55 C = 84.36 TO = 7.36 D = 0.O0E+00 Equation is A + B * [Tanh((T-T6)/(C+DT))] Upper Shelf En~ergy=95.6(Fixed) Lower Shelf Energy=2.5(Fixed) Temp@30 ft-lbs=-29.3 Deg F Tenmp@5O fr-]bs=9.1 Deg F Plant: DUANE ARNOLD AND SSP Material: SMAW Heat: DAl SMAW Orjentafion:NA Capsule: DA1-36 Fluence: n/era^2 300 250

  • 200
         *150 C"
      >100 t          1          I-        t          2*

_________ t _________ j _________ 0 0 50 ________ 0 -4.-.--- ------ 4----- - --. --- nl 

               -300      -200      -100         0        100        200         300             400          500             600 Temperature in Deg F Charpy V-Notch Data Teiperature                       InputCVN,                      Computed CVN                               Differential
      -  80. 00                          7.20                                1.2.92                                 -5.72 23.,30                                21.52                                      1.78
      -25. 00                          28. 00                                32. 02                                 -4.02 48..90                                45. 00                                    3.90
33. o00 62. 70 62. 78 - . 0.8 4.9.00 74. 70 70. 33 4.37 10.3.00 90. 20 86. 86 3.34 120. 00 77.70 89. 57 - 11. 87 163. 00 84. 30 93.33 -9.03 Figure B-5-3 Charpy Energy Data for Weld DA1 SMAW in DAl 360 Capsule B-5-13

ISP Weld Heat Evaluations Irradiated Weld Heat DA1 SMAW (DA1-36) Page 2 Plant: DUANE ARNOLD AND SSP Material: SMAW Heat: DAl SMAW Orientation: NA Capsule: DA1-36 Fluence: n/cm^A2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 202. 00 93. 40 94. 69 -1.29 250. 00 94. 60 95. 31 -. 71 400. 00 110. 10 95. 59 14. 51 Correlation Coefficient = .977 Figure B-5-3 Charpy Energy Data for Weld DA1 SMAW in DA1 360 Capsule (Continued) B-5-14

ISP Weld Heat Evaluations Irradiated Weld Heat DA1 SMAW (SSP-F) CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 12/17/2013 04:53 PM Page 1 Coefficients of Curve 4 A = 50.75 B = 48.25 C = 122.89 TO.= 37.36 D = 0.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))] Upper Shelf Energy=99,0(Fixed) Lower Shelf Energy=2.5(Fixed) Temnp@30 ft-lbs=-19.1 Deg F Temp@50 ft-lbs=35.5 Deg F Plant:.DUANE ARNOLD AND SSP Material: SMAW Heat: DAl SMAW Orientation: NA Capsule: SSP-F Fluence: n/emA2 300 250 

        *200
        *150 e-100 50 0

O0 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temp~erature InputCV Computed CVN Differential 

      -40. 00                         10.O00                            23. 84                   -  13, 84
      -40. 00                         25. 50                            23. 84                       1. 66
      - 20. 00                        29. 50                            29;  73                       -. 23
            .00                       48. 50                            36. 52                     11. 98
            .00                       40. 50                            36. 52                       3. 98
70. 00 56. 50 63. 27 -6.77 150. 00 86. 50 85. 70 .80 200. 00 90. 00 92. 61 -2, 61 300. 00 108. 50 97. 68 10. 82 Figure B-5-4 Charpy Energy Data for Weld DA1 SMAW in SSP Capsule F B-5-15

ISP Weld Heat Evaluations Irradiated Weld Heat DA1 SMAW (SSP-F) Page 2 Plant: DUANE ARNOLD AND SSP Material: SMAW Heat: DA1 SMAW Orientation: NA Capsule: SSP-F Pluence: r/cmA2 Charpy V-Notch Data Temperatdre Input CVN Computed CVN Diffeerentijal 400. O00 98. 50 98. 74- .24 Correlation Coefficient =.976 Figure B-5-4 Charpy Energy Data for Weld DA1 SMAW in SSP Capsule F (Continued) B-5-16

ISP Weld Heat Evaluations Irradiated Weld Heat DA1 SMAW (DAI-108) CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 01/02/2014 10:04 PM Page .1 Coefficients of Curve .1 A = 60.75 B =58.25 C = 76.69 TO -23.34 D O.00E+00 Equation is A + B *' [Tanh((T-To)](C+DT))I Upper Shelf Energy=1 19. 0(Fixed) Lower Shelf Energy=2. 5(Fixed) Temp@30 ft-lbs=-21.6 Deg F Temp@50 ft-lbs=9.1 Deg F Plant: DUANE ARNOLD AND SSP Material: SMAW Heat: DA1 SMAW Orientation: NA Capsule: DA-108 Fluence: n/erna2 

         *200
       '15-
                                                             /

at ILl 

       >100 fI 50 A N
               -300    -200       -100          0          100      200      300       400        500        600 Temperature in Deg F Chiarpy V-Notch Data Tempeature                        Inpu CVN                        Computed CVN                  Differential
     -  125.,50                         3. 33                              4. 85                      -.1. 52
       -59.30                           9. 60                             14.60                       -5. 00
       -30.30                        20. 39                               25. 57                      -5. 18
       -  11. 40                     28.08                                36.03                       -7.95
         -1.70                       59.88                                42. 38                      17. 50 69.30                        86. 40                              92.01                       -5.61 201.70                       118.43                              117.90                             .53 398. 70                      119.49                              118.99                             .50 Correlation Coefficient = .986 Figure B-5-5 Charpy Energy Data for Weld DA1 SMAW in DA1 1080 Capsule B-5-17

ISP Weld Heat Evaluations { (E)}} Figure B-5-6 Fitted Surveillance Results for Weld Heat DAl SMAW B-5-18

ISP Weld Heat Evaluations References B-5-1i. GE Nuclear Energy, "Duane Arnold RPV Surveillance Materials Testing and Analysis," GE-NE-B1100716-01, July 1997. B-5-2 BWRVIP-279NP:~BWR Vessel and Internals Project, Testing and Evaluation of the Duane Arnold 108° Capsule. EPRI, Palo Alto, CA: 2014. 3002003134. B-5-3. B WR VIP-1l1NP, Revision 1: B WR Vessel and InternalsProject, Testing and Evaluation of BWR Supplemental Surveillance Program Capsules E, F and I. EPRI, Palo Alto, CA: 2010. 1021554. B-5-4. CVGRAPH, Hyperbolic Tangent Curve Fitting Program, Developed by ATI Consulting, Version 5.0.2, Revision 1, 3/26/02. B-5-5. "Radiation Embrittlement of Reactor Vessel Materials," USNRC Regulatory Guide 1.99, Revision 2, May 1988. B-5-6 "Format and Content of Report for Thermal Annealing of Reactor Pressure Vessels," USNRC Regulatory Guide 1.162, February 1996. B-5-7. K. Wichman, M. Mitchell, and A. Hiser, USNRC, Generic Letter 92-01 and RPV Integrity Workshop Handouts, NRC/Industry Workshop on RPV Integrity Issues, February 12, 1998. B-5-8. ASTM E-1 85, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels," American Society for Testing and Materials, July 1982. B-5-9. BWR Vessel and Internals Project: BWR IntegratedSurveillance ProgramPlan (BWRVIP-78). EPRI, Palo Alto, CA and BWRVIP: 1999. TR-1 14228. B-5-19}}

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