NL-15-2034, E.I. Hatch, Units 1 and 2 - Enclosure 4, Non-Proprietary Version of the Epri/Bwrvip Information Requested in RAI 1

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E.I. Hatch, Units 1 and 2 - Enclosure 4, Non-Proprietary Version of the Epri/Bwrvip Information Requested in RAI 1
ML15322A090
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Site: Hatch  Southern Nuclear icon.png
Issue date: 11/12/2015
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Southern Co, Southern Nuclear Operating Co
To:
Office of Nuclear Reactor Regulation
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NL-15-2034
Download: ML15322A090 (24)


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Edwin I. Hatch Nuclear Plant Response to Request for Additional Information Regarding Application for Amendment to Technical Specifications for Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR) Consistent with TSTF-41 9-A Enclosure 4 Non-Proprietary Version of the EPRI / BWRVIP Information Requested in RAI 1 EPRI I BWRVIP Non-Proprietary Information Plant-Specific Evaluations Hatch I Representative Surveillance Materials The Isp Representative Surveillance Materials for the Hatch 1 vessel target weld and plates are shown in the following table.Table 2-43 Target Vessel Materials and ISP Representative Materials for Hatch 1~Target Vessel Materials ISP Representative Materials Weld 1 P2815 20291 Plate C4114-2 C4114-2 Summary of Available Surveillance Data: Plate The representative plate material C4114-2 is contained in the following ISP capsules: Hatch 1 Capsules Specific surveillance data related to plate heat C41 14-2 are summarized in Appendix A-4. Two capsules containing this plate heat have been tested. The Charpy V-notCh surveillance results are as follows: Table 2-44 T 3 0 Shift Results for Plate Heat C4114-2 Cu Ni FlI~knce Capsule (wt%) (wt%) (10'7 n/cm" ,E > 1MeV) AT 3 0 (0 F)Hatch I 3Q0 2.4 41.8___ __ __ __ __ -0.12 0.70 Hatch 1 120° 4.6 62.5 The results given in Appendix A-4 show a fitted chemistry factor (CE) of {{ }}', as compared to a value of 84.5°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 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 Hatch 1 vessel, and because there are two irradiated data sets for this plate that fall within the 1-sigma scatter band, the ISP surveilrance 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.2-30 EPRI / BWRVIP Non-Proprietary Information Plant-Specific Evaluations In addition, an archival plate heat from the Hatch 1 vessel, Plate Heat C3985-2, was included in the Supplemental Surveillance Program (SSP), and irradiated data from SSP Capsules H and C are provided in Appendix A- 17. The credible surveillance data should be considered when a revised ART is calculated for vessel heat 03985-2.Summary of Available Surveillance Data: Weld The representative weld material 20291 is contained in the following ISP capsules: Cooper Capsules SSP Capsule C Specific surveillance data related to weld heat 20291 are presented in Appendix B-2 and the results are summarized below. Two capsules containing weld heat 20291 have been tested.The Charpy V-notch surveillance results are as follows: Table 2-45 T" 3 o Shift Results for Weld Heat 20291 Cu Ni Fluence Capsule (wt%) (wt%) (10ll n/cm 2 , E > 1MeV) A.T 3 o (CF)Cooper 300 2.4 60.9 Cooper 3000 0.23 0.75 2.8 63.8 SSP C 3.29 73.0 The results given in Appendix B-2 show a fitted chemistry factor (OF) of {{ }}, as compared to a value of 1 94.5°F from the chemistry tables in Reg. Guide 1.99, Rev. 2. The maximum scatter in the fitted data 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 Hatch 1 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.2-31 EPRI / BWRVIP Non-Proprietary information ISP Plate Heat Evaluations A-4 Plate Heat: C41 14-2 Summary of Available Charpy V-Notch Test Data The available Charpy V-notch test data sets for plate heat C41 14-2 are listed in Table A-4-1. The source documents for the data are provided, and the capsule designations and fluence values are also provided for irradiated data sets.Table A-4-1 ISP Capsules Containing Plate Heat C41 14-2 Capsule Fluence (E> 1 MeV, 1017 rlcm 2) Reference Unirradiated Baseline Data --Reference A-4-1 Hatch 1 30° 2.4 Reference A-4-2 Hatch 1 1200 4.6 Reference A-4-3 The CVN test data for each set taken from the references noted above are presented in Tables A-4-7 through A-4-9. 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-4-4] and the plots are provided in Figures A-4-1 through A-4-3.Best Estimate Chemistry Table A-4-2 details the best estimate average chemistry values for plate heat C41 14-2 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-4-2 Best Estimate Chemistry of Available Data Sets for Plate Heat C41 14-2 Cu (wt%) Ni(% P (w%)S(w% Si (wt%) Specimen ID Source 0.11 0.68 --0.21 DEM 0.11 0.57 -- -0.19 D4L 0.12 0.71 -- -0.22 CUBRerncA-3 0.13 0.77 0.015 -0.26 D14 0.13 0.78 0.014 -- 0.26 CUP 0.12 0.68 0.014 -0.19 CUD 0.13 0.7 0.010 0.013 0.28 Baseline CMTR Reference A-4-3 0.12 0.70 0.013 0.013 0.23 ('-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-4-6]1, Table 2 (base metal), is: A-4-1 EPRI I BWRVIP Non-Proprietary Information ISP Plate 1-eat Evaluations CFcc 4 1 1 4.,) -- 84.5°F Effects of Irradiation The radiation induced transition temperature shifts for heat C4 114-2 are shown in Table A-4-3.The [30 ft-lb Transition Temperature], Tho [50 ft-lb Transition Temperature], and T 3 5 mi[35 mil 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 (AT 3 0) is calculated for each irradiated data set using the Reg. Guide 1.99, Rev. 2, Regulatory Position 1.1 method. Table A-4-4 compares the predicted shift with the measured AT 3 0 (°F) taken from Table A-4-3.Comparison of Actual vs. Predicted Decrease in USE Table A-4-5 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-4-3.A-4-2 ISP Plate Heat Evaluations Table A-4-3 Effect of Irradiation (E>1.0 MeV) on the Notch Toughness Properties of Plate Heat C4114-2 T=, 30 ft-lb Two, 50 ft-lb T 3 6 mii, 35 mil Lateral Transition Transition Expansion CVN Upper Shelf Energy Material Capsule Temperature Temperature Temperature (USE)identity ID Unirrad irrad &T~ Unirrad Irrad ATe0 Unirrad Irrad AT 2 5., Unirrad Irrad Change (°F) (0 F) (°F) (0 F) (°F) (°F) (0 F) (°F) (0 F) (it-Ib) (ft-lb) (ft-lb)HlC142 300 -61.5 -19.7 41.8 -28.8 13.8 42.6 -34.7 -9.4 25.3 136.0 135.1 -0.9 1200 -61.5 1.0 62.5 -28.8 25.8 54.6 -34.7 14.1 48.8 136.0 141.1 5.1 Table A-4-4 Comparison of Actual Versus Predicted Embrittlemernt for Plate Heat C41 14-2 Measured RG 1.99 Rev. 2 RG 1.99 Rev. 2 Capsule Identity Material Fx10uence=

Shift 1 Predicted Shift 2 Predicted Shift+Marginz°(xO 0 nc 2 F 0 F °F HA1 300 Plate Heat C41 14-2 in Hatch 1 0.24 41.8 16.2 32.4 HA1 1200 Plate Heat C41 14-2 in Hatch 1 0.46 62.5 23.6 47.2 Notes: 1. See Table A-4-3, ATM.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 FF is Fluence Factor, ' where f = fluence n/cm 2 , E > 1.0 MeV), 3. Margin = 2'J{o, + oa), where a = the standard deviation on initial RT~oT (which is taken to be 0°F), and 0 A is the standard deviation on (28 0 F for welds and 17 0 F for base materials, except that OA need not exceed 0.50 times the mean value of ART~oT). Thus, margin is defined as 34°F for plate mnaterials and 56 0 F for weld materials, or margin equals shift (whichever is less), per Reg. Guide 1.99, Rev. 2.m"-o-;o-o 0--A--4-3 ISP Plate Heat Evaluations Table A-4-5 Comparison of Actual Versus Predicted Percent Decrease in Upper Shelf Energy (USE) for Plate Heat C4114-2 Flec uCnet Measured RG 1.99 Rev. 2 Casuentteiitlene CuCntn Decrease in USE' Predicted Decrease in CasuenMatria (xl 0ls nu/cm 2) (wt%) (%) USE 2 (%)HAl 300 Plate Heat C41 14-2 in Hatch 1 0.24 0.12 0.7 8.7 HA1 1200 Plate Heat C41 14-2 in Hatch 1 0.46 0.12 10.1 Notes: 1. See Table A-4-3, (Change in USE)/(Unirradiated USE).2. Calculated using equations in Regulatory Guide 1.162 [A-4-7] that accurately model the Charpy upper shelf energy decrease curves in Regulatory Guide 1.99, Revision 2.3. Value less than zero.m"-U-o"U 0o ,2 ao o)A-4-4 EPRI / BWRVIP Non-Proprietary Information ISP Plate Heat Evaluations A-5 Plate Heat:C8554 Summary of Available Charpy V-Notch Test Data The available Charpy V-notch test data sets for plate heat C8554 are listed in Table A-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 A-5-1 ISP Capsules Containing Plate Heat C8554 Caps ule Fluence (E > 1MeV, 1017 n/cm 2)) Reference Unirradiated Baseline Data Reference A-5-1 Hatch 2 30° 2.3 The CVN test data for each set taken from the references noted above are presented in Tables A-5-6 and A-5-7. 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 [A-5-2] and the plots are provided in Figures A-5-i and A-5-2.Best Estimate Chemistry Table A-5-2 details the best estimate average chemistry values for plate heat 08554 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-5-2 Best Estimate Chemistry of Available Data Sets for Plate Heat C8554 Cu (wt%) Ni (wt%) P Cwt%) S (wt%) Si (wt%) SpecimenlID Source 0.08 0.63 0.011 -- -- P1-46-A 0.08 0.63 0.009 -- -- P1-46-B Reference A-5-1 0.05 0.63 0.010 -_ Average P1-46-0.57 0.010 0.018 0.22 C8554 Slab,1 Reference A-5-3 S 0.58 0.010 0.018 0.24 C8554 Slab 2{{ }} { {{ }} {{ }} {{ } *--Best Estimate Average A-5-1 EPRI / BWRVIP Non-Proprietary Information ISP Plate Heat Evaluations 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-5-4], Table 2 (base metal), is: CF(Cs 5 5 4) = 51.0°F Effects of Irradiation The radiation induced transition temperature shifts for heat C8554 are shown in Table A-5-3.The T 3 o [30 ft-lb Transition Temperature], T 5 , 2 [50 ft-lb Transition Temperature], and T 3 5 ml[35 rail 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 (AT 3 0) is calculated for each irradiated data set using the Reg. Guide 1.99, Rev. 2, Regulatory Position 1.1 method. Table A-5-4 compares the predicted shift with the measured (°F) taken from Table A-5-3.Comparison of Actual vs. Predicted Decrease in USE Table A-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 A-5-3.A-5-2 ISP Plate Heat Evalua~tions Table A-5-3 Effect of Irradiation (E>1 B MeV) on the Notch Toughness Properties of Plate Heat C8554 TLo, 30 ft-lb T 5 0 , 50 ft-lb T 3 5 , 35 mil Lateral CVN Upper Shelf Energy Transition Transition Material Capsule Temperature Temperature Expansion Temperature (USE)Identity ID IUnirrad Irrad AT 3 0 Unirad Irrad ATso Unirrad Irrad AT 3 5 Unirrad Irrad Change (°F)_______F)F) ( ) (F) (°F) °F) (0 F) (0 F) (F) (ft-lb) (ft-lb) I (ft-lb)HA2 C8554 30" -19.6 -15.6 4.0 62 14.3 8.1 8.2 7.9 -0.3 111.5 112.9 1.4 Table A-5-4 Comparison of Actual Versus Predicted Embrittlement for Plate Heat C8554 Flec esrd RG 1.99 Rev.2 RG 1.99 Rev. 2 Capsule Identity Material Shift' Predicted Shift 2 Predicted Shift+Margin 2'3 HA2 30° Plate Heat C8554 in Hatch 2 0.23 4.0 9.6 19.1 Notes: 1 .See Table A.5 3, AT 3 0 2.Predicted shift = CF x FF, where CF is a Chemistry Factor taken from tables USNRC Reg. Guide 1.99, Rev. 2, based on each material's

3. Cp/Ni content, and FF is Fluence Factor, where f- fluence (10's nfcm 2 , E> 1.0 MeVf).3.Margin = 2.1(o,2 + where 01 = the standard deviation on initial RTNOT- (which is taken to be 0°F), and oA is the standard deviation on &RTNDr (28°F for welds and 1 7'F for base materials, except that oA need not exceed 0.50 times the mean value of ARTF~or).

Thus, margin is defined as 34TF for plate material and for weld materials, or margin equals shift (whichever is less), per Reg. Guide 1.99, Rev. 2.Table A-5-5 Comparison of Actual Versus Predicted Percent Decrease in Upper Shelf Energy (USE) for Plate Heat 08554 Fluence Cu Content Measured Decrease RG 1.99 Rev.2 CapsulelIdentity Material n/Cm)* (wt%) in USE'(%) Predicted Decrease in USE('Co)HA2 300 Plate Heat C8554 in Hatch 2 0.23 {{ } --- 7.0 Notes: 1.See Table A 5 3, (Change in USE)/(Unirradiated USE).2.Calculated using equations in Regulatory-Guide 1 .1 62[A 5]5 that accurately model the Charpy upper shelf energy decrease curves in Regulatory Guide 1 .99, Revision 2.3.Value less than zero."0-o-o,"0 0)A-5-3 EPRi / BWRVIP Non-Proprietary Information ISP Plate Heat Evaluations A-17 Plate Heat: C3985-2 Summary of Available Charpy V-Notch Test Data The available Charpy V-notch test data sets for plate heat C3985-2 are listed in Table A-l 7-1.The source documents for the data are provided, and the capsule designation and fluence values are also provided for irradiated data sets. Plate heat C3985-2 is not the Hatch 1 surveillance plate, but it is a Hatch 1 vessel archival plate included in the Supplemental Surveillance Program (SSP).Table A-17-1 ISP Capsules Containing Plate Heat C3985-2 Capsule Fluence (E> 1 MeV, 1017 n/cm 2) Reference Unirradiated Baseline Data --Reference A-17-1 SSP H 16.240 Reference A-i17-2 SSP C 3.11 Reference A-i17-9 The CVN test data for each set taken from the references noted above are presented in Tables A-17-7 and A-17-9. 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- 17-3] and the plots are provided in Figures A-17-l through A-17-3.Best Estimate Chemistry Table A-17-2 details the best estimate average chemistry values for plate heat C3985-2 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-i17-2 Best Estimate Chemistry of Available Data Sets for Plate Heat C3985-2 Cu (wt%) Ni (wt%) P (wt%) S (wt%) Si (wt%) Specimen ID Source 0.13 0.58 0.015 0.015 0.27 CMTR Reference A-17-4 0.11 0.66 0.02 0.018 0.27 SSP 0.08 0.59 0.008 -- -- SSP Reference A-17-1 0.095 0.625 0.014 0.018 0,27 SSP Average 0.11 0.60 0.015 0.017 0.27 (-Best Estimate Average A-17-1 EPRI / BWRVIP Non-Proprietary Information ISP Plate Heat Evaluations 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-17-5], Table 2 (base metal), is: CFc9s, = 74.0°F Effects of Irradiation The radiation induced transition temperature shifts for heat C3985-2 are shown in Table A-17-3.The T 3 0 [30 ft-lb Transition Temperature], T 5 0 [50 ft-lb Transition Temperature], and T 3 5 1[35 mil 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 end 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 (AT 3 0) is calculated for each irradiated data set using the Reg. Guide 1.99, Rev. 2, Regulatory Position 1.1 method. Table A-17-4 compares the predicted shift with the measured AT 3 0 (0 F) taken from Table A-17-3.Decrease in USE Table A-17-5 shows the percent decrease in upper shelf energy (USE). The measured percent decrease is calculated from the values presented in Table A-17-3.A- 17-2 ISP Plate Heat Evaluations Table A-17-3 Effect of Irradiation (E>I .0 MeV) on the Notch Toughness Properties of Plate Heat C3985-2 T,,o, 30 ft-lb Tso, 50Oft-lb 5mlLtrl CNUprSefEeg Transition Transition T~, 1 5mtLtrl CNUprSefEeg Material Capsule Temperature Temperature Expansion Temperature (USE)Identity ID __Unirrad Irrad ATmo Unirrad Irrad ATs, Unirrad Irrad A~e Unirrad Irrad Change ("F) ("F) ("F) ("F) (°F) ("F) ("F) ("F) ("F) (ft-lb) (ft-tb) (ft-tb)HAl SSP H -11.7 19.4 31.1 27.0 62.5 35.5 31.1 55.6 24.5 112.8 110.5 -2.3 C3985-2 SSP C -11.7 8.8 20.5 27.0 46.4 19.4 31.1 30.6 -0.5 112.8 115.8 3.0 Table A-17-4 Comparison of Actual Versus Predicted Embrittlement for Plate Heat C3985-2 Material m"13 wo-C z2 03 0 Z0 oD 0="13 0" SSP H Plate Heat C3985-2 from HA1 SSP C _Plate Heat 03985-2 from HA1 Notes: 1. See Table A-17-3, ATo.2. Predicted shilt = CF x FF, where CF is a Chemistry Factor taken from tables from USNRC Rag. Guide 1.99, Rev. 2, based on each material's CuINi content, and FF is Fluence Factor, where I = Iluence (10"° n/cm', E > 1.0 MeV).3. Margin = + an'), where Dr = the standard deviation on initial RT,,, (which is taken to be 0"F), and CiA is the standard deviation on ART,~r (28"F for welds and 17"F for base materials, except that 0 A need not exceed 0.50 times the mean value of ARTNm). 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-17-3 ISP Plate Heat Evaluations Table A-i17-5 Comparison of Actual Versus Predicted Percent Decrease in Upper Shelf Energy (USE) for Plate Heat C3985-2 P~ d RG 1.99 Rev. 2 FMeneeasured Predicted Capsule Identity Material Fxlue1nlce 2 Cu Content (wt%) Decrease in USE 1 erae nUE (%) (%)SSP H 1.6240 0.11 2.0 13.0 Plate Heat 03985-2 from HA1 SSP 0 0.311 0.11 .-a 8.8 Notes: 1. See Table A-17-3, (Change in USE)/(Unirradiated USE).2. Calculated using equations in Regulatory Guide 1.162 [A-17-6] that accurately model the Charpy upper shelf energy decrease curves in Regulatory Guide 1.99, Revision 2.3. Value less than zero.m Zr-c r,=0I o A-17-4 EPRI I BWRVIP Non-Proprietary 1nformation ISP Weld Heat Evaluations B-2 Weld Heat: 20291 Summary of Available Charpy V-Notch Test Data The available Charpy V-notch test data sets for weld heat 20291 are listed in Table B-2-1. The source documents for the data are provided, and the capsule designations and fluence values are also provided for irradiated data sets.Table B-2-1 ISP Capsules Containing Weld Heat 20291 Capsule Fluence (E> 1 MeV, 1017 n/cm 2) Reference Unirradiated Baseline Data --Reference B-2-1 Cooper 3000 2.8 Reference B-2-2 and B-2-3 Cooper 30° SSP Capsule C 3.29 Reference B-2-1 1 1Fluence reported by Reference B-2-3, which revised the capsule fluence reported by Reference B-2-2.The CVN test data for each set taken from the references noted above are presented in Tables B-2-7 through B-2-10. 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 CVGRAPH3, Version 5 IReference B-2-4] and the plots are provided in Figures B-2-1 through B-2-4.Best Estimate Chemistry Table B-2-2 details the best estimate average chemistry values for weld heat 20291 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-2-2 Best Estimate Chemistry of Available Data Sets for Weld Heat 20291 Cu Ni P S " Si (wt%) (wt%) (wt%) (wt%) (wt%) Specimen ID Source 0.23 0.75 0.012 -- -- J74 Reference B-2-2 and B-2-5 0.22 0.74 0.012 -- -- J7D 0.22 0.72 0.016 -- -- J7B Reference 6-2-3 0.23 0.77 0.017 --- J75 0.23 0.75 0.014 -- -- 4.Best Estimate Average B-2-1 EPRI I BWRVIP Non-Proprietary Information 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 Regulatory Guide 1.99, Revision 2 [Reference B-2-6], Table 1 (weld metal), is: C(20291,) = 194.5°F Effects of Irradiation The radiation induced transition temperature shifts for heat 20291 are shown in Table B-2-3.The T 3 0 [30 ft-lb Transition Temperature], T 5 o [50 ft-lb Transition Temperature], and T 3 smt[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 (AT 3 0) is calculated for each irradiated data set using the Reg. Guide 1.99, Rev. 2, Regulatory Position 1.1 method. Table B-2-4 compares the predicted shift with the measured AT 3 0 (0 F) taken from Table B-2-3.Decrease in USE Table B-2-5 shows the percent decrease in upper shelf energy (USE). The measured percent decrease is calculated from the values presented in Table B-2-3.B-2-2 ISP Weld Heat Evaluations Table B-2-3 Effect of irradiation (E>1 .0 MeV) on the Notch Toughness Properties of Weld Heat 2029130 ft-lb T=, 50 ft-lb 35 mil Lateral CVN Upper Shelf Energy Material Transition Temperature Transition Temperature Expansion Temperature(U )Identity Capsule ID ..Unirrad Irrad iAT,, Unirrad Irrad AT,, Unirrad Irrad Unirrad Irrad Change 300 -17.8 43.1 60.9 13.3 92.4 79.1 10.8 38.1 27.3 110.0 81.2 -28.8 CPR 221 3000 -17.8 46.0 63.8 13.3 109.6 96.3 10.8 82.0 71.2 110.0 87.9 -22.1 SSP C -17.8 55.2 73.0 13.3 88.7 75.4 10.8 81.6 70.8 110.0 93.6 -16.4 Table B-2-4 Comparison of Actual Versus Predicted Embrittlement far Weld Heat 20291 RG 1.99 Rev. 2 Capsule MaeilFluence Measured PrGe1.99tev. 2hf Predicted Identity Maeil(xlO' 8 n/cm 2) Shift' °F Prdce hFt Shift+Margin 2" 0 oF CPR 300 Weld Heat 20291 in Cooper 0.24 60.9 37.4 74.8 CPR 3000 Weld Heat 20291 in Cooper 0.28 63.8 41.0 82.0 SSP C Cooper Weld Heat 20291 in SSP C 0.329 73.0 45.1 90.1 Notes: 1. See Table B-2-3, T,,T.2. Predicted shift = CF X FF, where CF is a Chemistry Factor taken from tables tram USNRC Reg. Guide 1.99, Rev. 2, based on each material's Cu/Ni content, and FF is Fluence Factor, t 0,o, where f =fluence (10" n/cm 2 , E > 1.0 MeV).3. Margin = 2 -J(a,2 + cQ), where a, = the standard deviation on initial (which is taken to be 0°F). and 0 ,A is the standard deviation on (28 0 F for welds and 17°F for base materials, except that need not exceed 0.50 times the mean value of oT). Thus, margin Is defined as for plate materials and 56°F for weld materials, or margin equals shift (whichever is less), per Reg. Guide 1.99, Rev. 2.m-U-U 02 o0 B-2-3 ISP Weld Heat Ev'aluations Table B-2-5 Comparison of Actual Versus Predicted Percent Decrease in Upper Shelf Energy (USE) for Weld Heat 20291 RG 1.99 Rev. 2 Fiuence CMesrdPredicted Capsule identity Material (x10'8 n/cm 2) Content Decrease in Decrease in USED (wt%) USE 1 (%) (%)CPR 300 Weld Heat 20291 in Cooper 0.24 0.23 26.2 15.3 CPR 3000 Weld Heat 20291 in Cooper 0.28 0.23 20.1 15.9 SSP C Cooper Weld Heat 20291 in SSP C 0.329 0.23 14.9 16.5 Notes: 1. See Table B3-2-3, (Change in USE)I(Unirradiated USE).2. Calculated using equations in Regulatory Guide 1.162 [B-2-7] that accurately model the Charpy upper shelf energy decrease curves in Regulatory Guide 1.99, Revision 2.m t0 0, 0, 0-B-2-4 EPRI / BWRVIP Non-Proprietary Information Plant-Specific Evaluations Hatch 2 Representative Surveillance Materials The ISP Representative Surveillance Materials for the Hatch 2 vessel target weld and plates are shown in the following table.Table 2-46 Target Vessel Materials and ISP Representative Materials for Hatch 2 ITarget Vessel Materials ISP Representative Materials Weld 10137 51912 Plate C8579-2 C8554 Summary of Available Surveillance Data: Plate The representative plate material 08554 is contained in the following ISP capsules: Hatch 2 Capsules Specific surveillance data related to plate heat 08554 are summarized in Appendix A-5. One capsule containing this plate heat has been tested. The Charpy V-notch surveillance results are as follows: Table 2-47 T1 3 o Shift Results for Plate Heat C8554 Cu Ni Fluence Capsule (wt%) (wt%) (1017 n/cmn 2 , E > 1MeV), AT 3 0 (0 F)Hatch 2 300 [{ }} {{ )} 2.3 4.0 NO surveillance based chemistry factor will be available until a second capsule is tested (see reference [1] for capsule test schedule). Conclusions and Recommendations Because the representative plate material is not the same heat number as the target plate in the Hatch 2 vessel, the utility should use the chemistry factor from the Regulatory Guide 1 .99, Rev.2 tables (Regulatory Position 1.1) to determine the projected ART value for the target vessel plate. However, 08554 is a plate heat in the Hatch 2 vessel beltline; therefore, the surveillance data reported in Appendix A-S should be considered in the evaluation of that vessel plate. However, there is currently only one irradiated data set available for this plate. Therefore, the utility should use the chemistry factor from the Regulatory Guide 1.99 Rev. 2 tables (Regulatory Position 1 .1)to determine the projected ART value for the 08554 plate until such time as there are two or more credible irradiated data sets available. Recommended guidelines for evaluation of ISP surveillance data are provided in Section 3 of this Data Source Book.2-32 EPRI / BWRVIP Non-Proprietary Information , Plant-Specific Evaluations Summary of Available Surveillance Data: Weld The representative weld material 51912 is contained in the following capsules: Hatch 2 Capsules Specific surveillance data related to weld heat 51912 are presented in Appendix B-6 and the results are summarized below. One capsule containing weld heat 51912 has been tested. The Charpy V-notch surveillance results are as follows: Table 2-48 T 3 8 Shift Resultsfor Weld Heat 51912 ICu Ni Fluence Capsule (wt%) (wt%) (1017 n/cmn 2 , E > 1MeV), AT 3 0 ("F)Hatch2 3O° {{} {{ }) 2.3 1.1 No surveillance based chemistry factor will be available until a second capsule is tested (see reference [1] for capsule test schedule). Conclusions and Recommendations Because the representative weld material is not the same heat number as the target weld in the Hatch 2 vessel, the utility should use the chemisiry 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.2-33 EPRI / BWRVIP Non-Proprietary Information 1SF' held H-eat Lia/uatio,,s B-6 Weld Heat:51912 Summary of Available Charpy V-Notch Test Data The available Charpy V-notch test data sets for weld heat 51912 are listed in Table 8-6-1. The source documents for the data are provided, and the capsule designation and fluence values are also provided for irradiated data sets.Table B-6-1 ISP Capsules Containing Weld Heat 51912 Capsule Fluence (E> 1MeV,10"7 n/cm 2) Reference Unirradiated Baseline Data ----.Reference B-6-1 Hatch 2 3Q0 2.31 The CVN test data for each set taken from the references noted above are presented in Tables B-6-6 and B-6-7. The BWRVlP 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-6-2] and the plots are provided in Figures B-6-1 and B-6-2.Best Estimate Chemistry Table B-6-2 details the best estimate average chemistry values for weld heat 51912 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-6-2 Best Estimate Chemistry of Available Data Sets for Weld Heat 51912 Cu Ni P~ S Si Specimen ID Source (wt%) (wt%) (wt%) (wt%) (wt%) ______0.13 0.12 0.013 -P2-46-A 0.12 0.07 0.014 --P2-46-B Reference B-6-1{{ )J ({ 7) (( 7) -A-verage P2-46 ______({ 7) ({ 7) {{ 7) -,-Best Estimate Average Calculation of Chemistry Factor (C F): The Chemistry Factor (CF) associated with the best estimate chemistry, as determined from U.S.NRC Regulatory Guide 1.99, Revision 2 [Reference B-6-3], Table 1 (weld metal), is: CFs91)= 67.0=F B-6-1 EPRI I BWRVIP Non-Proprietary information ISP Weld Heat Eval uations Effects of Irradiation The radiation induced transition temperature shifts for heat 51912 are shown in Table B-6-3.The T 3 0 [30 ft-lb Transition Temperature], Tho [50 ft-lb Transition Temperature], and T 3 5 ,mi I [35 mai 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 (ATmo) is calculated for each irradiated data set using the Reg. Guide 1.99, Rev. 2, Regulatory Position 1.1 method. Table B-6-4 compares the predicted shift with the measured AT 3 0 (0 F) taken from Table B-6-3.Comparison of Actual vs. Predicted Decrease in USE Table B-6-5 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-6-3.B-6-2 ISP Weld Heat Evaluations Table B-6-3 Effect of Irradiation (E>I.0 MeV) on the Notch Toughness Properties of Weld Heat 51912 T~o, 30 ft-lb T~o 50 ft-lb T 335 mai Lateral CNUprSefEeg Transition Transition Expansion(UE Material Capsule Temperature Temperature Temperature(UE dett D Unirrad Irrad AT= ad Irrad ATwo Unirrad Irrad Unirrad Irrad Change (0 F) (°F) (0 F) (OF) (°F) (0 F) (°F) (0 F) (0 F) (ft-lb) (ft-lb) (ft-lb)HA2 592 300 -21.0 -19.9 1.1 4.0 10.2 6.2 7.3 4.9 -2.4 120.8 119.1 -1.7 Table B-6-4 Comparison of Actual Versus Predicted Embrittlement for Weld Heat 51912 RG 1.99 Rev. 2 Capsule Material Fluence Measured Shift' RG 1.99 Rev. 2 Predicted Identity (XlO" nlcm 2) 0 F Predicted Shift2 0 F Shift+Margin 2'3 oF HA2 300 Weld Heat 51912 in Hatch 2 0.23 1.1 12.6 25.1 Notes: 1. See Table B-6-3, AT 0.2. 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 materalrs Cu/Ni content, and FF is Fluence Factor, where f = fluence (10's ndcm=, E > 1.0 MeV).3. Margin =24/(0,- + where o, = the standard deviation on initial (which is taken to be 0*F), and is the standard deviation on ARTwJz (28°F for welds and 1 7 0 F for base materials, except tht , need not exceed 0.50 times the mean value of ART,,or). 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.m-o-o 02*" CD B-6-3 1SP' Weld Heat Evaluations Table B-6.5 Comparison of Actual Versus Predicted Percent Decrease in Upper Shelf Energy (USE) for Weld Heat 51912 Casueudetencatrel 1Cu Content Measured RG 1.99 Rev. 2 CasueIdntt Mtril x 0Mn/cm 2) (wt%) Decrease in USE" 2 {%) Predicted Decrease in_ USE 2 (%)HA2 30+ Weld Heat 51912 in Hatch 2 0.23 { }1,4 11.1 Notes: 1. See Table R-6-3, (Change In USE)/(Unirradiated USE).2. Calculated using equations in Regulatory Guide 1.162 { B-6-4) that accurately model the charpy upper shelf energy decrease curves in Regulatory Guide 1.99, Revision 2.-o z a, a,.C B-6-4 Edwin I. Hatch Nuclear Plant Response to Request for Additional Information Regarding Application for Amendment to Technical Specifications for Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR) Consistent with TSTF-41 9-A Enclosure 4 Non-Proprietary Version of the EPRI / BWRVIP Information Requested in RAI 1 EPRI I BWRVIP Non-Proprietary Information Plant-Specific Evaluations Hatch I Representative Surveillance Materials The Isp Representative Surveillance Materials for the Hatch 1 vessel target weld and plates are shown in the following table.Table 2-43 Target Vessel Materials and ISP Representative Materials for Hatch 1~Target Vessel Materials ISP Representative Materials Weld 1 P2815 20291 Plate C4114-2 C4114-2 Summary of Available Surveillance Data: Plate The representative plate material C4114-2 is contained in the following ISP capsules: Hatch 1 Capsules Specific surveillance data related to plate heat C41 14-2 are summarized in Appendix A-4. Two capsules containing this plate heat have been tested. The Charpy V-notCh surveillance results are as follows: Table 2-44 T 3 0 Shift Results for Plate Heat C4114-2 Cu Ni FlI~knce Capsule (wt%) (wt%) (10'7 n/cm" ,E > 1MeV) AT 3 0 (0 F)Hatch I 3Q0 2.4 41.8___ __ __ __ __ -0.12 0.70 Hatch 1 120° 4.6 62.5 The results given in Appendix A-4 show a fitted chemistry factor (CE) of {{ }}', as compared to a value of 84.5°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 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 Hatch 1 vessel, and because there are two irradiated data sets for this plate that fall within the 1-sigma scatter band, the ISP surveilrance 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.2-30 EPRI / BWRVIP Non-Proprietary Information Plant-Specific Evaluations In addition, an archival plate heat from the Hatch 1 vessel, Plate Heat C3985-2, was included in the Supplemental Surveillance Program (SSP), and irradiated data from SSP Capsules H and C are provided in Appendix A- 17. The credible surveillance data should be considered when a revised ART is calculated for vessel heat 03985-2.Summary of Available Surveillance Data: Weld The representative weld material 20291 is contained in the following ISP capsules: Cooper Capsules SSP Capsule C Specific surveillance data related to weld heat 20291 are presented in Appendix B-2 and the results are summarized below. Two capsules containing weld heat 20291 have been tested.The Charpy V-notch surveillance results are as follows: Table 2-45 T" 3 o Shift Results for Weld Heat 20291 Cu Ni Fluence Capsule (wt%) (wt%) (10ll n/cm 2 , E > 1MeV) A.T 3 o (CF)Cooper 300 2.4 60.9 Cooper 3000 0.23 0.75 2.8 63.8 SSP C 3.29 73.0 The results given in Appendix B-2 show a fitted chemistry factor (OF) of {{ }}, as compared to a value of 1 94.5°F from the chemistry tables in Reg. Guide 1.99, Rev. 2. The maximum scatter in the fitted data 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 Hatch 1 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.2-31 EPRI / BWRVIP Non-Proprietary information ISP Plate Heat Evaluations A-4 Plate Heat: C41 14-2 Summary of Available Charpy V-Notch Test Data The available Charpy V-notch test data sets for plate heat C41 14-2 are listed in Table A-4-1. The source documents for the data are provided, and the capsule designations and fluence values are also provided for irradiated data sets.Table A-4-1 ISP Capsules Containing Plate Heat C41 14-2 Capsule Fluence (E> 1 MeV, 1017 rlcm 2) Reference Unirradiated Baseline Data --Reference A-4-1 Hatch 1 30° 2.4 Reference A-4-2 Hatch 1 1200 4.6 Reference A-4-3 The CVN test data for each set taken from the references noted above are presented in Tables A-4-7 through A-4-9. 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-4-4] and the plots are provided in Figures A-4-1 through A-4-3.Best Estimate Chemistry Table A-4-2 details the best estimate average chemistry values for plate heat C41 14-2 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-4-2 Best Estimate Chemistry of Available Data Sets for Plate Heat C41 14-2 Cu (wt%) Ni(% P (w%)S(w% Si (wt%) Specimen ID Source 0.11 0.68 --0.21 DEM 0.11 0.57 -- -0.19 D4L 0.12 0.71 -- -0.22 CUBRerncA-3 0.13 0.77 0.015 -0.26 D14 0.13 0.78 0.014 -- 0.26 CUP 0.12 0.68 0.014 -0.19 CUD 0.13 0.7 0.010 0.013 0.28 Baseline CMTR Reference A-4-3 0.12 0.70 0.013 0.013 0.23 ('-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-4-6]1, Table 2 (base metal), is: A-4-1 EPRI I BWRVIP Non-Proprietary Information ISP Plate 1-eat Evaluations CFcc 4 1 1 4.,) -- 84.5°F Effects of Irradiation The radiation induced transition temperature shifts for heat C4 114-2 are shown in Table A-4-3.The [30 ft-lb Transition Temperature], Tho [50 ft-lb Transition Temperature], and T 3 5 mi[35 mil 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 (AT 3 0) is calculated for each irradiated data set using the Reg. Guide 1.99, Rev. 2, Regulatory Position 1.1 method. Table A-4-4 compares the predicted shift with the measured AT 3 0 (°F) taken from Table A-4-3.Comparison of Actual vs. Predicted Decrease in USE Table A-4-5 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-4-3.A-4-2 ISP Plate Heat Evaluations Table A-4-3 Effect of Irradiation (E>1.0 MeV) on the Notch Toughness Properties of Plate Heat C4114-2 T=, 30 ft-lb Two, 50 ft-lb T 3 6 mii, 35 mil Lateral Transition Transition Expansion CVN Upper Shelf Energy Material Capsule Temperature Temperature Temperature (USE)identity ID Unirrad irrad &T~ Unirrad Irrad ATe0 Unirrad Irrad AT 2 5., Unirrad Irrad Change (°F) (0 F) (°F) (0 F) (°F) (°F) (0 F) (°F) (0 F) (it-Ib) (ft-lb) (ft-lb)HlC142 300 -61.5 -19.7 41.8 -28.8 13.8 42.6 -34.7 -9.4 25.3 136.0 135.1 -0.9 1200 -61.5 1.0 62.5 -28.8 25.8 54.6 -34.7 14.1 48.8 136.0 141.1 5.1 Table A-4-4 Comparison of Actual Versus Predicted Embrittlemernt for Plate Heat C41 14-2 Measured RG 1.99 Rev. 2 RG 1.99 Rev. 2 Capsule Identity Material Fx10uence= Shift 1 Predicted Shift 2 Predicted Shift+Marginz°(xO 0 nc 2 F 0 F °F HA1 300 Plate Heat C41 14-2 in Hatch 1 0.24 41.8 16.2 32.4 HA1 1200 Plate Heat C41 14-2 in Hatch 1 0.46 62.5 23.6 47.2 Notes: 1. See Table A-4-3, ATM.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 FF is Fluence Factor, ' where f = fluence n/cm 2 , E > 1.0 MeV), 3. Margin = 2'J{o, + oa), where a = the standard deviation on initial RT~oT (which is taken to be 0°F), and 0 A is the standard deviation on (28 0 F for welds and 17 0 F for base materials, except that OA need not exceed 0.50 times the mean value of ART~oT). Thus, margin is defined as 34°F for plate mnaterials and 56 0 F for weld materials, or margin equals shift (whichever is less), per Reg. Guide 1.99, Rev. 2.m"-o-;o-o 0--A--4-3 ISP Plate Heat Evaluations Table A-4-5 Comparison of Actual Versus Predicted Percent Decrease in Upper Shelf Energy (USE) for Plate Heat C4114-2 Flec uCnet Measured RG 1.99 Rev. 2 Casuentteiitlene CuCntn Decrease in USE' Predicted Decrease in CasuenMatria (xl 0ls nu/cm 2) (wt%) (%) USE 2 (%)HAl 300 Plate Heat C41 14-2 in Hatch 1 0.24 0.12 0.7 8.7 HA1 1200 Plate Heat C41 14-2 in Hatch 1 0.46 0.12 10.1 Notes: 1. See Table A-4-3, (Change in USE)/(Unirradiated USE).2. Calculated using equations in Regulatory Guide 1.162 [A-4-7] that accurately model the Charpy upper shelf energy decrease curves in Regulatory Guide 1.99, Revision 2.3. Value less than zero.m"-U-o"U 0o ,2 ao o)A-4-4 EPRI / BWRVIP Non-Proprietary Information ISP Plate Heat Evaluations A-5 Plate Heat:C8554 Summary of Available Charpy V-Notch Test Data The available Charpy V-notch test data sets for plate heat C8554 are listed in Table A-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 A-5-1 ISP Capsules Containing Plate Heat C8554 Caps ule Fluence (E > 1MeV, 1017 n/cm 2)) Reference Unirradiated Baseline Data Reference A-5-1 Hatch 2 30° 2.3 The CVN test data for each set taken from the references noted above are presented in Tables A-5-6 and A-5-7. 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 [A-5-2] and the plots are provided in Figures A-5-i and A-5-2.Best Estimate Chemistry Table A-5-2 details the best estimate average chemistry values for plate heat 08554 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-5-2 Best Estimate Chemistry of Available Data Sets for Plate Heat C8554 Cu (wt%) Ni (wt%) P Cwt%) S (wt%) Si (wt%) SpecimenlID Source 0.08 0.63 0.011 -- -- P1-46-A 0.08 0.63 0.009 -- -- P1-46-B Reference A-5-1 0.05 0.63 0.010 -_ Average P1-46-0.57 0.010 0.018 0.22 C8554 Slab,1 Reference A-5-3 S 0.58 0.010 0.018 0.24 C8554 Slab 2{{ }} { }} {{ }} {{ }} {{ } *--Best Estimate Average A-5-1 EPRI / BWRVIP Non-Proprietary Information ISP Plate Heat Evaluations 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-5-4], Table 2 (base metal), is: CF(Cs 5 5 4) = 51.0°F Effects of Irradiation The radiation induced transition temperature shifts for heat C8554 are shown in Table A-5-3.The T 3 o [30 ft-lb Transition Temperature], T 5 , 2 [50 ft-lb Transition Temperature], and T 3 5 ml[35 rail 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 (AT 3 0) is calculated for each irradiated data set using the Reg. Guide 1.99, Rev. 2, Regulatory Position 1.1 method. Table A-5-4 compares the predicted shift with the measured (°F) taken from Table A-5-3.Comparison of Actual vs. Predicted Decrease in USE Table A-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 A-5-3.A-5-2 ISP Plate Heat Evalua~tions Table A-5-3 Effect of Irradiation (E>1 B MeV) on the Notch Toughness Properties of Plate Heat C8554 TLo, 30 ft-lb T 5 0 , 50 ft-lb T 3 5 , 35 mil Lateral CVN Upper Shelf Energy Transition Transition Material Capsule Temperature Temperature Expansion Temperature (USE)Identity ID IUnirrad Irrad AT 3 0 Unirad Irrad ATso Unirrad Irrad AT 3 5 Unirrad Irrad Change (°F)_______F)F) ( ) (F) (°F) °F) (0 F) (0 F) (F) (ft-lb) (ft-lb) I (ft-lb)HA2 C8554 30" -19.6 -15.6 4.0 62 14.3 8.1 8.2 7.9 -0.3 111.5 112.9 1.4 Table A-5-4 Comparison of Actual Versus Predicted Embrittlement for Plate Heat C8554 Flec esrd RG 1.99 Rev.2 RG 1.99 Rev. 2 Capsule Identity Material Shift' Predicted Shift 2 Predicted Shift+Margin 2'3 HA2 30° Plate Heat C8554 in Hatch 2 0.23 4.0 9.6 19.1 Notes: 1 .See Table A.5 3, AT 3 0 2.Predicted shift = CF x FF, where CF is a Chemistry Factor taken from tables USNRC Reg. Guide 1.99, Rev. 2, based on each material's

3. Cp/Ni content, and FF is Fluence Factor, where f- fluence (10's nfcm 2 , E> 1.0 MeVf).3.Margin = 2.1(o,2 + where 01 = the standard deviation on initial RTNOT- (which is taken to be 0°F), and oA is the standard deviation on &RTNDr (28°F for welds and 1 7'F for base materials, except that oA need not exceed 0.50 times the mean value of ARTF~or).

Thus, margin is defined as 34TF for plate material and for weld materials, or margin equals shift (whichever is less), per Reg. Guide 1.99, Rev. 2.Table A-5-5 Comparison of Actual Versus Predicted Percent Decrease in Upper Shelf Energy (USE) for Plate Heat 08554 Fluence Cu Content Measured Decrease RG 1.99 Rev.2 CapsulelIdentity Material n/Cm)* (wt%) in USE'(%) Predicted Decrease in USE('Co)HA2 300 Plate Heat C8554 in Hatch 2 0.23 {{ } --- 7.0 Notes: 1.See Table A 5 3, (Change in USE)/(Unirradiated USE).2.Calculated using equations in Regulatory-Guide 1 .1 62[A 5]5 that accurately model the Charpy upper shelf energy decrease curves in Regulatory Guide 1 .99, Revision 2.3.Value less than zero."0-o-o,"0 0)A-5-3 EPRi / BWRVIP Non-Proprietary Information ISP Plate Heat Evaluations A-17 Plate Heat: C3985-2 Summary of Available Charpy V-Notch Test Data The available Charpy V-notch test data sets for plate heat C3985-2 are listed in Table A-l 7-1.The source documents for the data are provided, and the capsule designation and fluence values are also provided for irradiated data sets. Plate heat C3985-2 is not the Hatch 1 surveillance plate, but it is a Hatch 1 vessel archival plate included in the Supplemental Surveillance Program (SSP).Table A-17-1 ISP Capsules Containing Plate Heat C3985-2 Capsule Fluence (E> 1 MeV, 1017 n/cm 2) Reference Unirradiated Baseline Data --Reference A-17-1 SSP H 16.240 Reference A-i17-2 SSP C 3.11 Reference A-i17-9 The CVN test data for each set taken from the references noted above are presented in Tables A-17-7 and A-17-9. 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- 17-3] and the plots are provided in Figures A-17-l through A-17-3.Best Estimate Chemistry Table A-17-2 details the best estimate average chemistry values for plate heat C3985-2 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-i17-2 Best Estimate Chemistry of Available Data Sets for Plate Heat C3985-2 Cu (wt%) Ni (wt%) P (wt%) S (wt%) Si (wt%) Specimen ID Source 0.13 0.58 0.015 0.015 0.27 CMTR Reference A-17-4 0.11 0.66 0.02 0.018 0.27 SSP 0.08 0.59 0.008 -- -- SSP Reference A-17-1 0.095 0.625 0.014 0.018 0,27 SSP Average 0.11 0.60 0.015 0.017 0.27 (-Best Estimate Average A-17-1 EPRI / BWRVIP Non-Proprietary Information ISP Plate Heat Evaluations 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-17-5], Table 2 (base metal), is: CFc9s, = 74.0°F Effects of Irradiation The radiation induced transition temperature shifts for heat C3985-2 are shown in Table A-17-3.The T 3 0 [30 ft-lb Transition Temperature], T 5 0 [50 ft-lb Transition Temperature], and T 3 5 1[35 mil 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 end 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 (AT 3 0) is calculated for each irradiated data set using the Reg. Guide 1.99, Rev. 2, Regulatory Position 1.1 method. Table A-17-4 compares the predicted shift with the measured AT 3 0 (0 F) taken from Table A-17-3.Decrease in USE Table A-17-5 shows the percent decrease in upper shelf energy (USE). The measured percent decrease is calculated from the values presented in Table A-17-3.A- 17-2 ISP Plate Heat Evaluations Table A-17-3 Effect of Irradiation (E>I .0 MeV) on the Notch Toughness Properties of Plate Heat C3985-2 T,,o, 30 ft-lb Tso, 50Oft-lb 5mlLtrl CNUprSefEeg Transition Transition T~, 1 5mtLtrl CNUprSefEeg Material Capsule Temperature Temperature Expansion Temperature (USE)Identity ID __Unirrad Irrad ATmo Unirrad Irrad ATs, Unirrad Irrad A~e Unirrad Irrad Change ("F) ("F) ("F) ("F) (°F) ("F) ("F) ("F) ("F) (ft-lb) (ft-tb) (ft-tb)HAl SSP H -11.7 19.4 31.1 27.0 62.5 35.5 31.1 55.6 24.5 112.8 110.5 -2.3 C3985-2 SSP C -11.7 8.8 20.5 27.0 46.4 19.4 31.1 30.6 -0.5 112.8 115.8 3.0 Table A-17-4 Comparison of Actual Versus Predicted Embrittlement for Plate Heat C3985-2 Material m"13 wo-C z2 03 0 Z0 oD 0="13 0" SSP H Plate Heat C3985-2 from HA1 SSP C _Plate Heat 03985-2 from HA1 Notes: 1. See Table A-17-3, ATo.2. Predicted shilt = CF x FF, where CF is a Chemistry Factor taken from tables from USNRC Rag. Guide 1.99, Rev. 2, based on each material's CuINi content, and FF is Fluence Factor, where I = Iluence (10"° n/cm', E > 1.0 MeV).3. Margin = + an'), where Dr = the standard deviation on initial RT,,, (which is taken to be 0"F), and CiA is the standard deviation on ART,~r (28"F for welds and 17"F for base materials, except that 0 A need not exceed 0.50 times the mean value of ARTNm). 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-17-3 ISP Plate Heat Evaluations Table A-i17-5 Comparison of Actual Versus Predicted Percent Decrease in Upper Shelf Energy (USE) for Plate Heat C3985-2 P~ d RG 1.99 Rev. 2 FMeneeasured Predicted Capsule Identity Material Fxlue1nlce 2 Cu Content (wt%) Decrease in USE 1 erae nUE (%) (%)SSP H 1.6240 0.11 2.0 13.0 Plate Heat 03985-2 from HA1 SSP 0 0.311 0.11 .-a 8.8 Notes: 1. See Table A-17-3, (Change in USE)/(Unirradiated USE).2. Calculated using equations in Regulatory Guide 1.162 [A-17-6] that accurately model the Charpy upper shelf energy decrease curves in Regulatory Guide 1.99, Revision 2.3. Value less than zero.m Zr-c r,=0I o A-17-4 EPRI I BWRVIP Non-Proprietary 1nformation ISP Weld Heat Evaluations B-2 Weld Heat: 20291 Summary of Available Charpy V-Notch Test Data The available Charpy V-notch test data sets for weld heat 20291 are listed in Table B-2-1. The source documents for the data are provided, and the capsule designations and fluence values are also provided for irradiated data sets.Table B-2-1 ISP Capsules Containing Weld Heat 20291 Capsule Fluence (E> 1 MeV, 1017 n/cm 2) Reference Unirradiated Baseline Data --Reference B-2-1 Cooper 3000 2.8 Reference B-2-2 and B-2-3 Cooper 30° SSP Capsule C 3.29 Reference B-2-1 1 1Fluence reported by Reference B-2-3, which revised the capsule fluence reported by Reference B-2-2.The CVN test data for each set taken from the references noted above are presented in Tables B-2-7 through B-2-10. 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 CVGRAPH3, Version 5 IReference B-2-4] and the plots are provided in Figures B-2-1 through B-2-4.Best Estimate Chemistry Table B-2-2 details the best estimate average chemistry values for weld heat 20291 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-2-2 Best Estimate Chemistry of Available Data Sets for Weld Heat 20291 Cu Ni P S " Si (wt%) (wt%) (wt%) (wt%) (wt%) Specimen ID Source 0.23 0.75 0.012 -- -- J74 Reference B-2-2 and B-2-5 0.22 0.74 0.012 -- -- J7D 0.22 0.72 0.016 -- -- J7B Reference 6-2-3 0.23 0.77 0.017 --- J75 0.23 0.75 0.014 -- -- 4.Best Estimate Average B-2-1 EPRI I BWRVIP Non-Proprietary Information 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 Regulatory Guide 1.99, Revision 2 [Reference B-2-6], Table 1 (weld metal), is: C(20291,) = 194.5°F Effects of Irradiation The radiation induced transition temperature shifts for heat 20291 are shown in Table B-2-3.The T 3 0 [30 ft-lb Transition Temperature], T 5 o [50 ft-lb Transition Temperature], and T 3 smt[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 (AT 3 0) is calculated for each irradiated data set using the Reg. Guide 1.99, Rev. 2, Regulatory Position 1.1 method. Table B-2-4 compares the predicted shift with the measured AT 3 0 (0 F) taken from Table B-2-3.Decrease in USE Table B-2-5 shows the percent decrease in upper shelf energy (USE). The measured percent decrease is calculated from the values presented in Table B-2-3.B-2-2 ISP Weld Heat Evaluations Table B-2-3 Effect of irradiation (E>1 .0 MeV) on the Notch Toughness Properties of Weld Heat 2029130 ft-lb T=, 50 ft-lb 35 mil Lateral CVN Upper Shelf Energy Material Transition Temperature Transition Temperature Expansion Temperature(U )Identity Capsule ID ..Unirrad Irrad iAT,, Unirrad Irrad AT,, Unirrad Irrad Unirrad Irrad Change 300 -17.8 43.1 60.9 13.3 92.4 79.1 10.8 38.1 27.3 110.0 81.2 -28.8 CPR 221 3000 -17.8 46.0 63.8 13.3 109.6 96.3 10.8 82.0 71.2 110.0 87.9 -22.1 SSP C -17.8 55.2 73.0 13.3 88.7 75.4 10.8 81.6 70.8 110.0 93.6 -16.4 Table B-2-4 Comparison of Actual Versus Predicted Embrittlement far Weld Heat 20291 RG 1.99 Rev. 2 Capsule MaeilFluence Measured PrGe1.99tev. 2hf Predicted Identity Maeil(xlO' 8 n/cm 2) Shift' °F Prdce hFt Shift+Margin 2" 0 oF CPR 300 Weld Heat 20291 in Cooper 0.24 60.9 37.4 74.8 CPR 3000 Weld Heat 20291 in Cooper 0.28 63.8 41.0 82.0 SSP C Cooper Weld Heat 20291 in SSP C 0.329 73.0 45.1 90.1 Notes: 1. See Table B-2-3, T,,T.2. Predicted shift = CF X FF, where CF is a Chemistry Factor taken from tables tram USNRC Reg. Guide 1.99, Rev. 2, based on each material's Cu/Ni content, and FF is Fluence Factor, t 0,o, where f =fluence (10" n/cm 2 , E > 1.0 MeV).3. Margin = 2 -J(a,2 + cQ), where a, = the standard deviation on initial (which is taken to be 0°F). and 0 ,A is the standard deviation on (28 0 F for welds and 17°F for base materials, except that need not exceed 0.50 times the mean value of oT). Thus, margin Is defined as for plate materials and 56°F for weld materials, or margin equals shift (whichever is less), per Reg. Guide 1.99, Rev. 2.m-U-U 02 o0 B-2-3 ISP Weld Heat Ev'aluations Table B-2-5 Comparison of Actual Versus Predicted Percent Decrease in Upper Shelf Energy (USE) for Weld Heat 20291 RG 1.99 Rev. 2 Fiuence CMesrdPredicted Capsule identity Material (x10'8 n/cm 2) Content Decrease in Decrease in USED (wt%) USE 1 (%) (%)CPR 300 Weld Heat 20291 in Cooper 0.24 0.23 26.2 15.3 CPR 3000 Weld Heat 20291 in Cooper 0.28 0.23 20.1 15.9 SSP C Cooper Weld Heat 20291 in SSP C 0.329 0.23 14.9 16.5 Notes: 1. See Table B3-2-3, (Change in USE)I(Unirradiated USE).2. Calculated using equations in Regulatory Guide 1.162 [B-2-7] that accurately model the Charpy upper shelf energy decrease curves in Regulatory Guide 1.99, Revision 2.m t0 0, 0, 0-B-2-4 EPRI / BWRVIP Non-Proprietary Information Plant-Specific Evaluations Hatch 2 Representative Surveillance Materials The ISP Representative Surveillance Materials for the Hatch 2 vessel target weld and plates are shown in the following table.Table 2-46 Target Vessel Materials and ISP Representative Materials for Hatch 2 ITarget Vessel Materials ISP Representative Materials Weld 10137 51912 Plate C8579-2 C8554 Summary of Available Surveillance Data: Plate The representative plate material 08554 is contained in the following ISP capsules: Hatch 2 Capsules Specific surveillance data related to plate heat 08554 are summarized in Appendix A-5. One capsule containing this plate heat has been tested. The Charpy V-notch surveillance results are as follows: Table 2-47 T1 3 o Shift Results for Plate Heat C8554 Cu Ni Fluence Capsule (wt%) (wt%) (1017 n/cmn 2 , E > 1MeV), AT 3 0 (0 F)Hatch 2 300 [{ }} {{ )} 2.3 4.0 NO surveillance based chemistry factor will be available until a second capsule is tested (see reference [1] for capsule test schedule). Conclusions and Recommendations Because the representative plate material is not the same heat number as the target plate in the Hatch 2 vessel, the utility should use the chemistry factor from the Regulatory Guide 1 .99, Rev.2 tables (Regulatory Position 1.1) to determine the projected ART value for the target vessel plate. However, 08554 is a plate heat in the Hatch 2 vessel beltline; therefore, the surveillance data reported in Appendix A-S should be considered in the evaluation of that vessel plate. However, there is currently only one irradiated data set available for this plate. Therefore, the utility should use the chemistry factor from the Regulatory Guide 1.99 Rev. 2 tables (Regulatory Position 1 .1)to determine the projected ART value for the 08554 plate until such time as there are two or more credible irradiated data sets available. Recommended guidelines for evaluation of ISP surveillance data are provided in Section 3 of this Data Source Book.2-32 EPRI / BWRVIP Non-Proprietary Information , Plant-Specific Evaluations Summary of Available Surveillance Data: Weld The representative weld material 51912 is contained in the following capsules: Hatch 2 Capsules Specific surveillance data related to weld heat 51912 are presented in Appendix B-6 and the results are summarized below. One capsule containing weld heat 51912 has been tested. The Charpy V-notch surveillance results are as follows: Table 2-48 T 3 8 Shift Resultsfor Weld Heat 51912 ICu Ni Fluence Capsule (wt%) (wt%) (1017 n/cmn 2 , E > 1MeV), AT 3 0 ("F)Hatch2 3O° {{} {{ }) 2.3 1.1 No surveillance based chemistry factor will be available until a second capsule is tested (see reference [1] for capsule test schedule). Conclusions and Recommendations Because the representative weld material is not the same heat number as the target weld in the Hatch 2 vessel, the utility should use the chemisiry 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.2-33 EPRI / BWRVIP Non-Proprietary Information 1SF' held H-eat Lia/uatio,,s B-6 Weld Heat:51912 Summary of Available Charpy V-Notch Test Data The available Charpy V-notch test data sets for weld heat 51912 are listed in Table 8-6-1. The source documents for the data are provided, and the capsule designation and fluence values are also provided for irradiated data sets.Table B-6-1 ISP Capsules Containing Weld Heat 51912 Capsule Fluence (E> 1MeV,10"7 n/cm 2) Reference Unirradiated Baseline Data ----.Reference B-6-1 Hatch 2 3Q0 2.31 The CVN test data for each set taken from the references noted above are presented in Tables B-6-6 and B-6-7. The BWRVlP 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-6-2] and the plots are provided in Figures B-6-1 and B-6-2.Best Estimate Chemistry Table B-6-2 details the best estimate average chemistry values for weld heat 51912 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-6-2 Best Estimate Chemistry of Available Data Sets for Weld Heat 51912 Cu Ni P~ S Si Specimen ID Source (wt%) (wt%) (wt%) (wt%) (wt%) ______0.13 0.12 0.013 -P2-46-A 0.12 0.07 0.014 --P2-46-B Reference B-6-1{{ )J ({ 7) (( 7) -A-verage P2-46 ______({ 7) ({ 7) {{ 7) -,-Best Estimate Average Calculation of Chemistry Factor (C F): The Chemistry Factor (CF) associated with the best estimate chemistry, as determined from U.S.NRC Regulatory Guide 1.99, Revision 2 [Reference B-6-3], Table 1 (weld metal), is: CFs91)= 67.0=F B-6-1 EPRI I BWRVIP Non-Proprietary information ISP Weld Heat Eval uations Effects of Irradiation The radiation induced transition temperature shifts for heat 51912 are shown in Table B-6-3.The T 3 0 [30 ft-lb Transition Temperature], Tho [50 ft-lb Transition Temperature], and T 3 5 ,mi I [35 mai 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 (ATmo) is calculated for each irradiated data set using the Reg. Guide 1.99, Rev. 2, Regulatory Position 1.1 method. Table B-6-4 compares the predicted shift with the measured AT 3 0 (0 F) taken from Table B-6-3.Comparison of Actual vs. Predicted Decrease in USE Table B-6-5 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-6-3.B-6-2 ISP Weld Heat Evaluations Table B-6-3 Effect of Irradiation (E>I.0 MeV) on the Notch Toughness Properties of Weld Heat 51912 T~o, 30 ft-lb T~o 50 ft-lb T 335 mai Lateral CNUprSefEeg Transition Transition Expansion(UE Material Capsule Temperature Temperature Temperature(UE dett D Unirrad Irrad AT= ad Irrad ATwo Unirrad Irrad Unirrad Irrad Change (0 F) (°F) (0 F) (OF) (°F) (0 F) (°F) (0 F) (0 F) (ft-lb) (ft-lb) (ft-lb)HA2 592 300 -21.0 -19.9 1.1 4.0 10.2 6.2 7.3 4.9 -2.4 120.8 119.1 -1.7 Table B-6-4 Comparison of Actual Versus Predicted Embrittlement for Weld Heat 51912 RG 1.99 Rev. 2 Capsule Material Fluence Measured Shift' RG 1.99 Rev. 2 Predicted Identity (XlO" nlcm 2) 0 F Predicted Shift2 0 F Shift+Margin 2'3 oF HA2 300 Weld Heat 51912 in Hatch 2 0.23 1.1 12.6 25.1 Notes: 1. See Table B-6-3, AT 0.2. 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 materalrs Cu/Ni content, and FF is Fluence Factor, where f = fluence (10's ndcm=, E > 1.0 MeV).3. Margin =24/(0,- + where o, = the standard deviation on initial (which is taken to be 0*F), and is the standard deviation on ARTwJz (28°F for welds and 1 7 0 F for base materials, except tht , need not exceed 0.50 times the mean value of ART,,or). 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.m-o-o 02*" CD B-6-3 1SP' Weld Heat Evaluations Table B-6.5 Comparison of Actual Versus Predicted Percent Decrease in Upper Shelf Energy (USE) for Weld Heat 51912 Casueudetencatrel 1Cu Content Measured RG 1.99 Rev. 2 CasueIdntt Mtril x 0Mn/cm 2) (wt%) Decrease in USE" 2 {%) Predicted Decrease in_ USE 2 (%)HA2 30+ Weld Heat 51912 in Hatch 2 0.23 { }1,4 11.1 Notes: 1. See Table R-6-3, (Change In USE)/(Unirradiated USE).2. Calculated using equations in Regulatory Guide 1.162 { B-6-4) that accurately model the charpy upper shelf energy decrease curves in Regulatory Guide 1.99, Revision 2.-o z a, a,.C B-6-4}}