ML16076A209
| ML16076A209 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 12/31/2014 |
| From: | Electric Power Research Institute |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NG-16-0055, TAC MF6617 BWRVIP-135, Rev 3 | |
| Download: ML16076A209 (44) | |
Text
Enclosure 1 to NG-16-0055 Redacted Non-Proprietary BWRVIP-135 Sections 43 pages follow
r._..* r-* li ELECTRIC RESEARCHPOWER INSTITUTE 2014 TECHNICAL REPORT BWRVI P-i135, Revision 3: BWR Vessel and Internals Project Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations E a
~ ~ WARNING: NOTICE: This report contains proprietary information that is the intel ectual property of fW~1J~3~~ Please read the Export Control EPRI.Accordingly, it is availoble only under license from EPRIand may not be reproduced
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Agreement on the bock cover. or disclosed, whol y 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. Carter 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 B0673 -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 T~o Shift Results for Plate Heat B0673-1 Cu Ni Fluence Capsule (wt~%) (wtf%) (1017 nlcm 2, E > 1 MeV) AT3°(°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 S Duane Arnold 108° 26.3 94.3 The results given in Appendix A-3 show a fitted chemistry factor (CF) of (( (E)} }, as compared to a value of 11 1.25°F from the chemistry tables in Reg. Guide 1.99, Rev. 2. The maximum scatter in the fitted data is (( (E)} } which is well within the 1-sigma value of 17°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 DA1 SMAW is contained in the following ISP capsules:
Duane Arnold Capsules SSP Capsule F Specific surveillance data related to weld heat DA1 SMAW are presented in Appendix B-5 and the results are summarized below. Four capsules containing weld heat DA 1 SMAW have been tested. The Charpy V-notch surveillance results are as follows:
Table 2-33 T3oShift Results for Weld Heat DA1 SMAW CpueCu Ni FluenceAT(F Cpue(wt%) (wt%) (10'" n/cm2 , E > 1 MeV) T30(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 1080 26.3 23.8 The results given in Appendix B-5 show a fitted chemistry factor (CF) of (( (E)} }, 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 (( (E)} } 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, 1017 eeec n/cm 2)Reenc Unirradiated Baseline Data Duane Arnold 2880 5.09 References A-3-1 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 11. 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 [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 B0673-l 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 -1 are shown in Table A-3 -3.
The T30 [30 ft-lb Transition Temperature], T5 0 [50 ft-lb Transition Temperature], and T35mi1
[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 (0F) 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>I.0 MeV) on the Notch Toughness Properties of Plate Heat B0673-1
- T 30, 30 ft-lb T50, 50 ft-lb T35mii,35 mil Lateral CVN Upper Shelf Energy Maeil Cpue Transition Temperature Transition Temperature Expansion Temperature (USE)
Identity ID Unirrad Irrad AT3 Unirrad Irrad A~s Unirrad Irrad AT8o Unirrad Irrad Change
(°F) (°F) (0F) (0F) (0F) (0F) (°F) (0F) (0F) (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 DAl 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 SSP 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 -25.1 108° -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 2 Measured Shift1 0FPredicted G19 RG e 1.99 Rev. 2 CapuleIdntiy Mteial(xl01 n/m ) Shift 2 Predicted Capul Idntty atria (l 08 /cm) F F Shift+Margin 2 ,3 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 61.8 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 AT~o.
- 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, f0.2*. 0'o' where f = fluence (1019 n/cm 2, E > 1.0 MeV).
- 3. Margin = 2'l(oj2 + o*o 2
), where a1 = the standard deviation on initial RTNDT (which is taken to be 0°F), and o*Ais the standard deviation on ARTOOT (280F for welds and 170F for base materials, except that uA need not exceed 0.50 times the mean value of ARTNDT). 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.
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 Capsule dentity CpueIettMaeil(x10T aterialFluence 8 n/cm 2) Cu (wt%)
Content MeasuredUSE'Decrease
(%) in PeitdDces Peinte Decreas DA 2880 Plate Heat B0673-1 in Duane Arnold 0.509 0.15 11.9 DA 36° Plate Heat B0673-1 in Duane Arnold 1.17 0.15 13.3 14.4 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
1SP Plate 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 [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. 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 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 E185-82
[A-3-8].
For plate material B0673-l, 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 ARTNDoT 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 Measured<17°F Measred Best Fit Scatter (Base Metal)
Material Fitted CF Casl F ARTNDT ART NOT of ARTNOT <28°F
(°F) Casl F (30 ft-lb) (OF) (OF) (Weld
(°F) metal)
B0673-1 (( (E) 2880 0.290 41.8 (( (E)}} (( (E)}} Yes (( E)}}' 360 0.436 77.0 (( (E)}* (( (E)}} Yes (( (E)}} SSP F 0.553 73.4 (( (E)}1 (( E}} Yes (( (E)}} 1080 0.637 94.3 (( (E)}} (( (E)}} 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 0 F. BWRVIP-78 [IA-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 B0673- 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 (0F) 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-lb) 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 (°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-3-1 0 Charpy V-Notch Results for B0673-1 (LT) in SSP Capsule F Spec ID Temp (°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 EDM 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-3-1 1 Charpy V-Notch Results for B0673-1 (LT) in Duane Arnold 1080 Capsule Spec ID Temp (0 F) CVN (ft-lb) LE (mils) %Shear ECB -1.3 4.2 5.0 4.2 ECC 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 Plate Heat Evaluations Tanh Curve Fits of CVN Test Data for Plate Heat B0673-1 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 = 0.00E+00 Equation is A + B * [Tanh((T-To)/(C+DT))] Upper Shelf Energy=l 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/cm^~2 300 .... 250- 1. t- -i
~200- -I--
i i
~ I_
~1150~*
I.. I 4
~ I w
z . .. _ .
>100-- -
U 50 0 -=
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperaure Input CYN Computed CVN Differential
-100.00 6. 50 8. 75 -2.25
-80. 00 4. 20 12.61 -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 Plate B0673-1 (LT) Unirradiated A-3-10
ISP Plate Heat Evaluations PLATE HEAT B0673-1 (DA AND SSP) Page 2 Plant: DUANE ARNOLD AND SSP Material: SA533BI Heat: B0673-l Orientation: LT Capsule: UNIRRA Fluence: 0.0 n/cm^2 Charpy V-Notch Data Temperature lnput CVN Computed CVN Differential 200. 00 158.50 156.31 2. 19 300. 00 163.50 157. 97 5. 53 Correlation Coefficient =.988 Figure A-3-1 Charpy Energy Data for Plate B0673-1 (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 = 0.00E+O0 Equation is A + B * [Tanh((T-To)/(C+DT))] Upper Shelf Energy=158.8 Lower Shelf Energy=2..5(Fixed) Temp@30 ft-lbs=6.3 Deg F Temp@50 ft-lbs=42.4 Deg F Plant: DUANE ARNOLD AND SSP Material: SA533BI Heat: B0673-1 Orientation: LT Capsule: DA-288 Fluence: n/cm^2 300
*PA 2
a j 200 "___ U. 150 __ 1 100 uJ 1 N -- °" 0
-300 -200 -100 0 100 200 300 400 500 600 TemperaturelIn Dog F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential
-60.00 4.00 11.02 -7.02
-20.00 15. 00 20. 13 -5.13 10.00 15. 50 31.74 -16. 24
- 20. 00 49.50 36.73 12. 77 40.,00 60. 00 48. 45 11.55 120. 00 101.50 "107. 13 -5. 63 200. 00 144. 50 144.40 .10 400. 00 160.00 158.51 1. 49 Corrlaion Coefficiet =.987 Figure A-3-2 Charpy Energy Data for Plate B0673-1 (LT) in Duane Arnold 2880 Capsule A-3-12
ISP Plate Heat Evaluations Irradiated Plate Heat B0673-1 (DA1-36) CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 12/17/2013 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 * [Tanh((T-To)/(C+DT))] Upper Shelf Energy=137.0(Fixed) Lower Shelf Energy=2.5(Fixed) Temip@30 ft-lbs=41.5 Deg F Temp@450 ft-lbs=70.7 Deg F Plant: DUANE ARNOLD AND SSP Material: SA533B1 Heat: B0673-1 Orientation: LT Capsule: DA-36 Fluence: n/cma^2 300 250 1 200 S150 100 / 50 a 0
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Compute CVN Differetial
-50. 00 5. 00 5. 70 -. 70
*00 18. 50 13. 42 5. 08 13.o00 27. 70 17. 29 10.41
- 25. 00 13. 70 21. 88 -8. 18 32.,00 15.40 25. 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 B0673-1 (LT) in Duane Arnold 36° Capsule A-3-13
ISP Plate Heat Evaluations Irradiated Plate Heat B0673-1 (DA1-36) Page 2 Plant: DUANE ARNOLD AND SSP Material: SA533B1 Heat: B0673-1 Orientation: LT Capsule: DA-36 Fluence: n/cm^2 Charpy V-Notch Data Temperature Input CVN Compute CVN Differential 202. 00 127. 80 129. 16 -1. 36 250. 00 142. 80 134. 63 8. 17 400. 00 140. 50 136. 95 3. 55 Correlation Coefficient= .980 Figure A-3-3 Charpy Energy Data for Plate B0673-1 (LT) in Duane Arnold 36° Capsule (Continued) A-3-14
ISP Plate Heat Evaluations Irradiated Plate Heat B0673-1 (SSP-F) CVGRAPH 5.0.2 Hyperbolic Tangent Cu~rve Printed on 1211712013 01:34 PM Page 1 Coefficients of Curve 3 A = 67.75 B = 65.25 C = 76.12 TO = 88.09 D = O.00E+00 Equation is A + B * [Tanh((T-To)/(C+DT))] Upper Shelf Energy=133.0(Fixed) Lower Shelf Energy=2.5(Fixed) Temnp@30 ft-Ibs=37.9 Deg F Temp@50 ft-lbs=66.9 Deg F Plant: DUANE ARNOLD AND SSP Material: SA533B1 Heat: B0673-1 Orientation: LT Capsule: SSP-F Fluence: n/cmA2 300 250
--200 150
~ ~ g ~ .
100
/
/
50
-/ OI
. I'o 0
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature lnputCVN Computed CVN Differential
. 00 12.50 14. 24 -1.74
- 30. 00 25. 50 25. 80 -. 30
- 50. 00 24.50 37.57 -307
- 50. 00 34. 50 37. 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/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Difffererttial 400. 0o 125. 50 132. 96- 7. 46 Correlation Coefficient = .981 Figure A-3-4 Charpy Energy Data for Plate B0673-1 (LT) in SSP Capsule F (Continued) A 16
ISP Plate Heat Evaluations Irradiated Plate Heat B0673-1 (DAI-108) CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 1213112013 09:45 AM Page 1 Coefficients of Curve 1 A = 66.9 B = 64.4 C = 85.21 TO = 114.29 D = 0.00E+00 Equation is A + B
- Tanh((T-To)/(C+DT))]
Upper Shelf Energy= 131.3(Fixed) Lower Shelf Energy=2.5(Fixed) Temp@30 ft-lbs=58.8 Deg F Temp@50 ft-lbs=91.4 Deg F Plant: DUANE ARNOLD AND SSP Material: SA533B1 Heat: B0673-1 Orientation: LT Capsule: DA-108 Fluenee: nlcm^2 300 250
-r200 U-150 uJ 100 0
50 0 0
-300 -200 -100 0 100 200 300 400 500 600 Temperature In Deg F Charpy V-Notch Data Temperature InputCVN Compute CVN 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. 50 110.36 113.22 -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 108° Capsule A-3-17
ISP Plate Heat Evaluations (E)}} Figure A-3-6 Filled Surveillance Results for Plate Heat B0673-1 A 18
ISP Plate Heat Evaluations References A-3-1. GE Nuclear Energy, "Duane Arnold RPV Surveillance Materials Testing and Analysis," GE-NE-B 1 1007 16-01, July 1997. A-3-2. BWRVIP-279NP: BWR Vessel and Internals Project, Testing and Evaluation of the Duane Arnold 1080 Capsule. EPRI, Palo Alto, CA: 2014. 3002003134. A-3-3. BWRVIP-111NP, 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-1 85, "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 Program Plan (BWRVIP-78). EPRI, Palo Alto, CA and BWRVIP: 1999. TR-1 14228. A 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 DAl SMAW are listed in Table B-5-1. The source documents for the data are provided, and the capsule designation and fluence values are also provided for irradiated data sets. Table B-5-1 ISP Capsules Containing Weld Heat DAl SMAW Capsule Fluence (E> 1 MeV, 1017 n/cm 2) Reference Unirradiated Baseline Data References B-5-1 Duane Arnold 1 2880 5.09anB52 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-l11. The BWR VIP 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 P S Si Seie DSuc (wt%) (wt%) (wt%) (wt%) (wt%) Seie DSuc 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-i 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 4- Best Estimate Average B-5-1
ISP Weld Heat Evaluations Calculation of Chemistry Factor (CF): The Chemistry Factor (CF) associated with the best estimate chemistr'y, as determined from U.S. NRC Regulatory Guide 1.99, Revision 2 [Reference B-5-4], Table 1 (weld metal), is: CF(DAI SMAW) = 27"0°F Effects of Irradiation The radiation induced transition temperature shifts for heat DA1 SMAW are shown in Table B-5-3. The T30 [30 ft-lb Transition Temperature], T50 [50 ft-lb Transition Temperature], and T3smii I[35 mail 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 (0F) taken from Table B-5-3. Comparison of Actual vs. Predicted Decrease in USE Table B-5-5 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 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 DAl SMAW T30, 30 ft-lb T 0, 50 ft-lb T35 rii, 35 mil Lateral CVN Upper Shelf Energy Material Capsule Transition Temperature Transition Temperature Expansion Temperature (USE) Iett ID Unirrad Irrad AT3 Unirrad Irrad A~s Unirrad Irrad AT5, Unirrad Irrad Change (°F) (°F) (°F) (°F) ( 0F) (°F) (0F) (°F) (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 SS P DA1 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 RG 1.99 Rev. 2 Capsule Material Fluence Measured RG 1.99 Rev. 2 Predicted Shift2 Predicted Identity (xl0'8 n/cm2 ) Shift1 °F oF Shift+Margin 2'3 DA1 2880 Weld Heat DA1 SMAW in Duane Arnold 0.509 2.6 8.0 16.0 DA1 36° Weld Heat DA1 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 Table 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 2
FF is Fluence Factor, fo-.oo, where f = fluence (1019 n/cm , E > 1.0 MeV).
- 3. Margin = 2*/(oi2 + or:), where a, = the standard deviation on initial RTNDoT(which is taken to be 0°F), and OA is the standard deviation on ARTNDT (28°F for welds and 17°F for base materials, except that Ganeed not exceed 0.50 times the mean value of AxRTNDT). 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 MeasuredRG 1.99 Rev. 2 Capsule Material Fluence Cu Content Decrease in Predicted Identity (xl 018 n/cm 2) (wt%) USE 1 (%) Decrease in USE 2 (%) DA1 2880 Weld Heat DA1 SMAW in Duane Arnold 0.509 0.02 -47.9 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 -3 11.7 Notes:
- 1. See Table B-5-3, (Change in USE)/(Unirradiated USE).
S 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 ART NDT values about a best-fit line drawn as described in Regulatory Position 2.1 normally 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 E185-82 [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 ARTT values about this line is less than 280 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 ART NDT 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°F Fitted ARTND Fit of (Base Metal) Material CapulTF CF (°F) Ca sl F (30 ft-lb) ART NOT ART NOT <28°F (°F) (°F) (°F) (Weld metal) (( (E)}} DA1 2880 0.296 2.6 (( (E)}] (( (E)}} Yes DA1 (( (E)}} DA1 360 0.449 16.1 (( (E)} (( (E)}} Yes SMAW (( (E)}} SSP F° 0.561 26.3 { (E)} (( (E)}} Yes (( (E)}} DA1 1080 0.637 23.8 (( (E)}] (( (E)}} Yes Table B-5-6 indicates that the scatter is within acceptable range for credible surveillance data. Therefore, weld heat DA1 SMAW meets this criterion. Criterion 4: The irradiation temperature of the Charpy specimens in the capsule should match the vessel wall temperature at the cladding/base metal interface within +/- 25°F. 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. 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 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 DAl SMAW Spec ID Temp (CF) 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 DAl 288 Deg Capsule Spec ID Temp (°F) CVN (ft-lb) LE (mils) %Shear EJ1 -100 6.5 11.0 0 EJ2 -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 DA1 36 Deg Capsule 0 Spec ID Temp ( 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 EJD 163 84.3 76.0 95 EJT 202 93.4 76.0 100 EJU 250 94.6 69.0 100 E JC 400 110.1 94.0 100 Table B-5-1 0 Charpy V-Notch Results for DA1 SMAW in SSP Capsule F Spec ID Temp (°F) 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 108° Capsule Spec ID Temp (0F) CVN (ft-lb) ILE (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 EJ5 69.3 86.4 67.5 84.1 EJ6 201.7 118.43 88.0 100 EJ7 398.7 119.49 92.5 100 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 = 50.77 B =48.27 C = 79.1 TO -- -9. D = 0.00E+00 Equation is A + B * [Tanh((T-To)/(C+DT))] Upper Shelf Energy=99.0 Lower Shelf Energy=2.5(Fixed) Temp@30 ft-lbs=-45.4 Deg F Temp@50 ft-Ibs=-lO.2 Deg F Plant: Duane Arnold AND SSP Material: SMAW Heat: SURV WELD HE Orientation: NA Capsule: UNIRRA Fluence: 0.0 n/cm^2 300 4--. . ... I ....... I I I
÷i i -
2 5I!. . . ...
° I 15 -- . .....
0e---- -
-30 -20 -1
)0 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Tempeatre Input CVN Comnputed 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/cm^2 Charpy V-Notch Data Input CVN Computed CVN Temperatlture 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 Curve 3 A = 52.09 B = 49.59 C = 65.48 TO = -11.49 D = .O.E+O0 Equation is A + B * [Tanh((T-To)/(C+DT))] Upper Shelf Energy= 101.7 Lower Shelf Energy=2,5(Fixed) Temp@30 ft-lbs=-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: n/cm^2 300 250
-200
*10 150
/
/
0
-300 -200 -100 0 100 200 300 400 500 600 Temperature In Dog F Charpy V-Notch Data Temperatur Input CVN Computed CVN Differential
- 100. 00 6. 50 8.72 -2. 22
-60.00 15.30 20. 86 -5. 56
-40. 00 22. 00 31.77 -9.77
-20. 00 63. 50 45. 68 17.82 40.,00 75.20 84. 64 -9.44 120.00 97. 20 99. 92 -2.,72 200. 00 109. 00 101.52 7. 48 400. 00 101.00 101.68 - .68 Correlation Coefficient = .975 Figure B-5-2 Charpy Energy Data for Weld DA1 SMAW in DA1 288° Capsule B-5-12
ISP Weld Heat Evaluations Irradiated Weld Heat DA1 SMAW (DA1-36) CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 12117/2013 04:50 PM Page 1 Coefficients of Curve 1 A = 49.05 B =46.55 C =84.36 TO = 7.36 D = 0.00E+00 Equation is A + B
- ITanh((T-TO)/(C+DT))]
Upper Shelf Energy=95.6(Fixed) Lower Shelf Energy=2.5(Fixed) Tenmp@30 ft-lbs=-29.3 Deg F Temp@50 ft-lbs=9.1 Deg F Plant: DUANE ARNOLD AND)SSP Material: SMAW Heat: DA1 SMAW Orientation: NA Capsule: DAI-36 Fluence: n/era^2 300 250 1 200 150 100 50 0
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature InputCVN Compute CYN Differential
- 80. 00 7.,20 12.92 -5.72
- 50. 00 23. 30 21.52 1.78
- 25. 00 28. 00 32. 02 -4.02
.00 48. 90 45. 00 3. 90
- 33. 00 62.70 62. 78 - .08
- 49. 00 74. 70 70. 33 4. 37 103. 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 DAl SMAW in DA1 360 Capsule B 13
ISP Weld Heat Evaluations Irradiated Weld Heat DA1 SMAW (DA1-36) Page 2 Plant: DUANE ARNOLD AND SSP Malerial: SMAW Heat: DA1 SMAW Orientation: NA Capsule: DA1-36 Fluence: n/cm^2 Charpy V-Notch Data Temperatur 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 ICharpy 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 12117/2013 04:53 PM Page~1 Coefficients of Curve 4 A = 50.75 B = 48.25 C = 122.89 TO = 37.36 D = 0.O0E+00 Equation is A + B * [Tanh((T-To)/(C+DT))] Upper Shelf Energy=99.0(Fixed) Lower Shelf Energy=2.5(Fixed) Temp@30 ft-lbs=-19.1 Deg F Temp@~50 ft-lbs=35.5 Deg F Plant: DUANE ARNOLD AND SSP Material: SMAW Heat: DA1 SMAW Orientation: NA Capsule: SSP-F Fluence: n/cm^2 300 250 4 200 10 ILl S100 7 " & "' " . ..-- .. l.. . ,. . --. . 50 A f 03 300 -200 -100 0 100 200 300 400 500 600 Temperature In Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential
- 40.O00 10. 00 23. 84 -13. 84
- 40.O00 25.50 23. 84 1. 66
- 20. O00 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 DAI SMAW (SSP-F) Page 2 Plant: DUANE ARNOLD AND SSP Material: SMAW Heat: DA1 SMAW Orientation: NA Capsule: SSP-F Fluence: n/cm^2 Charpy V-Notch Data Temperatre Input CVN Computed CVN Differential 400. 00 98. 50 98. 74 - .24 Correlation Coefficient = .976 Figure B-5-4 ICharpy 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 01/02t2014 10:04 PM Page 1 Coefficients of Curve 1 A = 60.75 B = 58.25 C = 76.69 TO = 23.34 D = 0.00E+00 Equation is A + B * (Tanh((T-To)/(C+DT))] Upper Shelf Energy=1 19.0(Fixed) Lower Shelf Energy=2.5(Fixed) Temip@30 ft-lbs=-21.6 Deg F Temnp@50 ft-lbs--9.1 Deg F Plant: DUANE ARNOLD AND SSP Material: SMAW Heat: DA1 SMAW Orientation: NA Capsule: DA-108 Fluence: n/era^2 300 250 A 200
*150 C
100 0 50 0
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVNN 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 Figure B-5-6 Fitted Surveillance Results for Weld Heat DA1 SMAW B 18
ISP Weld Heat Evaluations References B-5-1. GE Nuclear Energy, "Duane Arnold RPV Surveillance Materials Testing and Analysis," GE-NE-B 11007 16-01, 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. BWRVIP-111NP, Revision 1: BWR Vessel and InternalsProject, Testing and Evaluation of BWR Supplemental Surveillance ProgramCapsules 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- 185, "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 Integrated Surveillance ProgramPlan (BWRVIP-78). EPRI, Palo Alto, CA and BWRVIP: 1999. TR-1 14228. B-5-19}}