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| issue date = 05/31/2009 | | issue date = 05/31/2009 | ||
| title = WCAP-17036-NP, Rev 0, Analysis of Capsule N from the R.E. Ginna Reactor Vessel Radiation Surveillance Program. | | title = WCAP-17036-NP, Rev 0, Analysis of Capsule N from the R.E. Ginna Reactor Vessel Radiation Surveillance Program. | ||
| author name = Burgos B | | author name = Burgos B, Hardin T, Rosier B, Wang S | ||
| author affiliation = ATI Consulting, Westinghouse Electric Co, LLC | | author affiliation = ATI Consulting, Westinghouse Electric Co, LLC | ||
| addressee name = | | addressee name = | ||
| Line 16: | Line 16: | ||
=Text= | =Text= | ||
{{#Wiki_filter:Westinghouse Non-Proprietary Class 3 WCAP-17036-NP May 200!9 Revision 0 Analysis of Capsule | |||
==SUMMARY== | ==SUMMARY== | ||
The purpose of this report is to document the testing results of the surveillance Capsule N from R. E.Ginna. Capsule N was removed at 30.5 EFPY and post-irradiation mechanical tests of the Charpy V-notch and tensile specimens were performed. | |||
A fluence evaluation utilizing the neutron transport and dosimetry cross-section libraries was derived from the ENDF/B-VI database. | The purpose of this report is to document the testing results of the surveillance Capsule N from R. E. | ||
Capsule N received a fluence of 5.80 x 1019 | Ginna. Capsule N was removed at 30.5 EFPY and post-irradiation mechanical tests of the Charpy V-notch and tensile specimens were performed. A fluence evaluation utilizing the neutron transport and dosimetry cross-section libraries was derived from the ENDF/B-VI database. Capsule N received a fluence of 5.80 x 1019 nfcm2 (E > 1.0 MeV) after irradiation to 30.5 EFPY. The peak cladibase metal interface vessel fluence after 30.5 EFPY of plant operation was 3.20 x 1019 n/cm 2 (E > 1.0 MeV). | ||
: 1) The measured percent decrease in upper shelf energy for all surveillance materials contained in R. E. Ginna Capsule N is less than the Regulatory Guide 1.99, Revision 2 [1] prediction. | This evaluation led to the following conclusions: 1) The measured percent decrease in upper shelf energy for all surveillance materials contained in R. E. Ginna Capsule N is less than the Regulatory Guide 1.99, Revision 2 [1] prediction. 2) The R. E. Ginna surveillance data for both forgings (125S255 and 125P666) are judged to be not credible; however the weld data (heat #61782) is judged to be credible. This credibility evaluation can be found in Appendix D. 3) All beltline forging materials exhibit a more than adequate upper shelf energy level for continued safe plant operation and are predicted to maintain an upper shelf energy greater than 50 ft-lb throughout the 53 EFPY as required by 10 CFR 50, Appendix G | ||
[2]. The beltline welds (heat # 61782 and 71249) are predicted to fall below 50 ft-lb; however, an equivalent margin analysis has demonstrated they will remain acceptable through 53 EFPY. The upper shelf energy evaluation is presented in Appendix E. | |||
This credibility evaluation can be found in Appendix D. 3) All beltline forging materials exhibit a more than adequate upper shelf energy level for continued safe plant operation and are predicted to maintain an upper shelf energy greater than 50 ft-lb throughout the 53 EFPY as required by 10 CFR 50, Appendix G[2]. The beltline welds (heat # 61782 and 71249) are predicted to fall below 50 ft-lb; however, an equivalent margin analysis has demonstrated they will remain acceptable through 53 EFPY. The upper shelf energy evaluation is presented in Appendix E.Lastly, a brief summary of the Charpy V-notch testing can be found in Section 1. All Charpy V-notch data was plotted using a symmetric hyperbolic tangent curve fitting program.WCAP-1 7036-NP May 2009 Revision 0 1-1 1 | Lastly, a brief summary of the Charpy V-notch testing can be found in Section 1. All Charpy V-notch data was plotted using a symmetric hyperbolic tangent curve fitting program. | ||
WCAP-1 7036-NP May 2009 Revision 0 | |||
1-1 1 | |||
==SUMMARY== | ==SUMMARY== | ||
OF RESULTS The analysis of the reactor vessel materials contained in surveillance Capsule N, the fifth capsule removed and tested from the R. E. Ginna reactor pressure vessel, led to the following conclusions: | OF RESULTS The analysis of the reactor vessel materials contained in surveillance Capsule N, the fifth capsule removed and tested from the R. E. Ginna reactor pressure vessel, led to the following conclusions: | ||
* Charpy V-notch test data were plotted using a symmetric hyperbolic tangent curve-fitting program.Appendix C presents the CVGRAPH, Version 5.3, Charpy V-notch plots for Capsule N and previous capsules, along with the program input data." Capsule N received an average fast neutron fluence (E > 1.0 MeV) of 5.80 | * Charpy V-notch test data were plotted using a symmetric hyperbolic tangent curve-fitting program. | ||
* Irradiation of the reactor vessel Intermediate Shell Forging 125S255 Charpy specimens, oriented with the longitudinal axis of the specimen parallel to the major working direction (longitudinal orientation), resulted in an irradiated 30 ft-lb transition temperature of 47.5°F and an irradiated 50 ft-lb transition temperature of 102.8°F. This results in a 30 ft-lb transition temperature increase of 76.4°F and a 50 ft-lb transition temperature increase of 100.0°F for the longitudinally oriented specimens." Irradiation of the reactor vessel Lower Shell Forging 125P666 Charpy specimens, oriented with the longitudinal axis of the specimen parallel to the major working direction (longitudinal orientation), resulted in an irradiated 30 ft-lb transition temperature of 44.9°F and an irradiated 50 ft-lb transition temperature of 78.4'F. This results in a 30 ft-lb transition temperature increase of 91. I°F and a 50 ft-lb transition temperature increase of 93.3°F for the longitudinally oriented specimens. | Appendix C presents the CVGRAPH, Version 5.3, Charpy V-notch plots for Capsule N and previous capsules, along with the program input data. | ||
* Irradiation of the Surveillance Program Weld Metal (Heat #61782) Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 182.2°F and an irradiated 50 ft-lb transition temperature of 276.0'F. This results in a 30 ft-lb transition temperature increase of 216.9F and a 50 ft-lb transition temperature increase of 261.0°F.* Irradiation of the Heat-Affected-Zone (HAZ) Material Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 43.0°F and an irradiated 50 ft-lb transition temperature of 58.4°F.This results in a 30 ft-lb transition temperature increase of 107.7°F and a 50 ft-lb transition temperature increase of 74.5°F.* The average upper shelf energy of the Intermediate Shell Forging 125S255 (longitudinal orientation) resulted in an average energy decrease of 5.7 ft-lb after irradiation. | " Capsule N received an average fast neutron fluence (E > 1.0 MeV) of 5.80 x1019 n/cm 2 after 30.5 effective full power years (EFPY) of plant operation. | ||
This results in an irradiated average upper shelf energy of 134.3 ft-lb for the longitudinally oriented specimens. | * Irradiation of the reactor vessel Intermediate Shell Forging 125S255 Charpy specimens, oriented with the longitudinal axis of the specimen parallel to the major working direction (longitudinal orientation), resulted in an irradiated 30 ft-lb transition temperature of 47.5°F and an irradiated 50 ft-lb transition temperature of 102.8°F. This results in a 30 ft-lb transition temperature increase of 76.4°F and a 50 ft-lb transition temperature increase of 100.0°F for the longitudinally oriented specimens. | ||
* The average upper shelf energy of the Lower Shell Forging 125P666 (longitudinal orientation) resulted in an average energy decrease of 32.3 ft-lb after irradiation. | " Irradiation of the reactor vessel Lower Shell Forging 125P666 Charpy specimens, oriented with the longitudinal axis of the specimen parallel to the major working direction (longitudinal orientation), | ||
This results in an irradiated average upper shelf energy of 142.3 ft-lb for the longitudinally oriented specimens. | resulted in an irradiated 30 ft-lb transition temperature of 44.9°F and an irradiated 50 ft-lb transition temperature of 78.4'F. This results in a 30 ft-lb transition temperature increase of 91. I°F and a 50 ft-lb transition temperature increase of 93.3°F for the longitudinally oriented specimens. | ||
* The average upper shelf energy of the Surveillance Program Weld Metal Charpy specimens resulted in an average energy decrease of 27.1 ft-lb after irradiation. | * Irradiation of the Surveillance Program Weld Metal (Heat #61782) Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 182.2°F and an irradiated 50 ft-lb transition temperature of 276.0'F. This results in a 30 ft-lb transition temperature increase of 216.9F and a 50 ft-lb transition temperature increase of 261.0°F. | ||
This results in an irradiated average upper shelf energy of 51.9 ft-lb for the weld metal specimens. | * Irradiation of the Heat-Affected-Zone (HAZ) Material Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 43.0°F and an irradiated 50 ft-lb transition temperature of 58.4°F. | ||
WCAP-17036-NP May 2009 Revision 0 1-2* The average upper shelf energy of the HAZ Material Charpy specimens resulted in an average energy decrease of 1.7 ft-lb after irradiation. | This results in a 30 ft-lb transition temperature increase of 107.7°F and a 50 ft-lb transition temperature increase of 74.5°F. | ||
This results in an irradiated average upper shelf energy of 88.3 ft-lb for the HAZ Material.* A comparison, as presented in Table 5-10, of the R. E. Ginna reactor vessel surveillance material test results with the Regulatory Guide 1.99, Revision 2 predictions led to the following conclusions: | * The average upper shelf energy of the Intermediate Shell Forging 125S255 (longitudinal orientation) resulted in an average energy decrease of 5.7 ft-lb after irradiation. This results in an irradiated average upper shelf energy of 134.3 ft-lb for the longitudinally oriented specimens. | ||
-The measured 30 ft-lb shift in transition temperature values of the Intermediate Shell Forging 125S255 and Lower Shell Forging 125P666 specimens contained in Capsule N are greater than the Regulatory Guide 1.99, Revision 2 predictions. | * The average upper shelf energy of the Lower Shell Forging 125P666 (longitudinal orientation) resulted in an average energy decrease of 32.3 ft-lb after irradiation. This results in an irradiated average upper shelf energy of 142.3 ft-lb for the longitudinally oriented specimens. | ||
-The measured 30 ft-lb shift in transition temperature value of the Surveillance Weld Heat# 61782 specimens contained in Capsule N is less than the Regulatory Guide 1.99, Revision 2 prediction. | * The average upper shelf energy of the Surveillance Program Weld Metal Charpy specimens resulted in an average energy decrease of 27.1 ft-lb after irradiation. This results in an irradiated average upper shelf energy of 51.9 ft-lb for the weld metal specimens. | ||
-The measured percent decrease in upper shelf energy for all forging and weld surveillance materials in Capsule N are less that the Regulatory Guide 1.99, Revision 2 predictions. | WCAP-17036-NP May 2009 Revision 0 | ||
* Based on the credibility evaluation presented in Appendix D, the R. E. Ginna surveillance data for forgings 125S255 and 125P666 are not credible, but the surveillance weld (heat #61782) data are credible. | |||
Sister plant data (from Turkey Point Unit 3) for weld heat #71249 is also credible.* Based on the upper shelf energy evaluation in Appendix E, the beltline forging materials exhibit a more than adequate upper shelf energy level for continued safe plant operation and are predicted to maintain an upper shelf energy greater than 50 ft-lb throughout the end of the current license (53 EFPY) as required by 10 CFR 50, Appendix G [2]." Based on the upper shelf energy evaluation in Appendix E, the beltline welds are predicted to fall below 50 ft-lb by the end of the current extended license (53 EFPY) but an equivalent margin analysis demonstrates acceptability through 53 EFPY.* The calculated 53 EFPY (end-of-license renewal) neutron fluences (E > 1.0 MeV) at the core mid-plane for the R. E. Ginna reactor vessel using the Regulatory Guide 1.99, Revision 2 attenuation formula (i.e., Equation #3 in the guide) are as follows: Calculated (53 EFPY): Vessel inner radius* = 5.56 x 10'9 n/cm 2 (Taken from Table 6-2A)Vessel 1/4 thickness | 1-2 | ||
= 3.76 x 10'9 n/cm 2 Vessel 3/4 thickness | * The average upper shelf energy of the HAZ Material Charpy specimens resulted in an average energy decrease of 1.7 ft-lb after irradiation. This results in an irradiated average upper shelf energy of 88.3 ft-lb for the HAZ Material. | ||
= 1.73 x 1019 n/cm | * A comparison, as presented in Table 5-10, of the R. E. Ginna reactor vessel surveillance material test results with the Regulatory Guide 1.99, Revision 2 predictions led to the following conclusions: | ||
WCAP-17036-NP May 2009 Revision 0 2-1 2 INTRODUCTION This report presents the results of the examination of Capsule N, the fifth capsule removed from the reactor in the continuing surveillance program, which monitors the effects of neutron irradiation on the R.E. Ginna reactor pressure vessel materials under actual operating conditions. | - The measured 30 ft-lb shift in transition temperature values of the Intermediate Shell Forging 125S255 and Lower Shell Forging 125P666 specimens contained in Capsule N are greater than the Regulatory Guide 1.99, Revision 2 predictions. | ||
The surveillance program for the R. E. Ginna reactor pressure vessel materials was designed and recommended by the Westinghouse Electric Corporation. | - The measured 30 ft-lb shift in transition temperature value of the Surveillance Weld Heat | ||
A description of the surveillance program and the pre-irradiation mechanical properties of the reactor vessel materials are presented in WCAP-7254,"Rochester Gas and Electric Robert E. Ginna Unit No. I Reactor Vessel Radiation Surveillance Program"[3]. The surveillance program was planned to cover the 40-year design life of the reactor pressure vessel and was based on ASTM E185-66 [4], "Recommended Practice for Surveillance Tests on Structural Materials in Nuclear Reactors." Capsule N was removed from the reactor after Cycle 33, after 30.5 EFPY of exposure and shipped to the Westinghouse Science and Technology Department Hot Cell Facility, where the post-irradiation mechanical testing of the Charpy V-notch impact and tensile surveillance specimens was performed. | # 61782 specimens contained in Capsule N is less than the Regulatory Guide 1.99, Revision 2 prediction. | ||
This report summarizes the testing of the post-irradiation data obtained from surveillance Capsule N removed from the R. E. Ginna reactor vessel and discusses the analysis of the data.WCAP-17036-NP May 2009 Revision 0 3-1 3 BACKGROUND The ability of the large steel pressure vessel containing the reactor core and its primary coolant to resist fracture constitutes an important factor in ensuring safety in the nuclear industry. | - The measured percent decrease in upper shelf energy for all forging and weld surveillance materials in Capsule N are less that the Regulatory Guide 1.99, Revision 2 predictions. | ||
The beltline region of the reactor pressure vessel is the most critical region of the vessel because it is subjected to significant fast neutron bombardment. | * Based on the credibility evaluation presented in Appendix D, the R. E. Ginna surveillance data for forgings 125S255 and 125P666 are not credible, but the surveillance weld (heat #61782) data are credible. Sister plant data (from Turkey Point Unit 3) for weld heat #71249 is also credible. | ||
The overall effects of fast neutron irradiation on the mechanical properties of low alloy, ferritic pressure vessel steels such as ASTM A508 Class 2 (base material of the R. E. Ginna reactor pressure vessel beltline) are well documented in the literature. | * Based on the upper shelf energy evaluation in Appendix E, the beltline forging materials exhibit a more than adequate upper shelf energy level for continued safe plant operation and are predicted to maintain an upper shelf energy greater than 50 ft-lb throughout the end of the current license (53 EFPY) as required by 10 CFR 50, Appendix G [2]. | ||
Generally, low alloy ferritic materials show an increase in hardness and tensile properties and a decrease in ductility and toughness during high-energy irradiation. | " Based on the upper shelf energy evaluation in Appendix E, the beltline welds are predicted to fall below 50 ft-lb by the end of the current extended license (53 EFPY) but an equivalent margin analysis demonstrates acceptability through 53 EFPY. | ||
A method for ensuring the integrity of reactor pressure vessels has been presented in "Fracture Toughness Criteria for Protection Against Failure," Appendix G to Section XI of the ASME Boiler and Pressure Vessel Code [5]. The method uses fracture mechanics concepts and is based on the reference nil-ductility transition temperature (RTNDT).RTNDT is defined as the greater of either the drop weight nil-ductility transition temperature (NDTT per ASTM E208 [6]) or the temperature 60'F less than the 50 ft-lb (and 35-mil lateral expansion) temperature as determined from Charpy specimens oriented perpendicular (transverse) to the major working direction of the plate. The RTNDT of a given material is used to index that material to a reference stress intensity factor curve ( | * The calculated 53 EFPY (end-of-license renewal) neutron fluences (E > 1.0 MeV) at the core mid-plane for the R. E. Ginna reactor vessel using the Regulatory Guide 1.99, Revision 2 attenuation formula (i.e., Equation #3 in the guide) are as follows: | ||
Allowable operating limits can then be determined using these allowable stress intensity factors.RTNDT and, in turn, the operating limits of nuclear power plants can be adjusted to account for the effects of radiation on the reactor vessel material properties. | Calculated (53 EFPY): Vessel inner radius* = 5.56 x 10'9 n/cm 2 (Taken from Table 6-2A) | ||
The changes in mechanical properties of a given reactor pressure vessel steel, due to irradiation, can be monitored by a reactor vessel surveillance program, such as the R. E. Ginna reactor vessel radiation surveillance program, in which a surveillance capsule is periodically removed from the operating nuclear reactor and the encapsulated specimens are tested. The increase in the average Charpy V-notch 30 ft-lb temperature (ARTNDT) due to irradiation is added to the initial RTNDT, along with a margin (M) to cover uncertainties, to adjust the RTNDT (ART) for radiation embrittlement. | Vessel 1/4 thickness = 3.76 x 10'9 n/cm 2 2 | ||
This ART (RTNDT Initial + M + ARTNDT) is used to index the material to the | Vessel 3/4 thickness = 1.73 x 1019 n/cm | ||
WCAP-17036-NP May 2009 Revision 0 4-1 4 DESCRIPTION OF PROGRAM Six surveillance capsules for monitoring the effects of neutron exposure on the R. E. Ginna reactor pressure vessel core region (beltline) materials were inserted in the reactor vessel prior to initial plant startup. The six capsules were positioned in the reactor vessel between the thermal shield and the vessel wall as shown in Figure 4-1. The vertical center of the capsules is opposite the vertical center of the core.The capsules contain specimens made from the following: | * Clad/base metal interface. | ||
WCAP-17036-NP May 2009 Revision 0 | |||
2-1 2 INTRODUCTION This report presents the results of the examination of Capsule N, the fifth capsule removed from the reactor in the continuing surveillance program, which monitors the effects of neutron irradiation on the R. | |||
E. Ginna reactor pressure vessel materials under actual operating conditions. | |||
The surveillance program for the R. E. Ginna reactor pressure vessel materials was designed and recommended by the Westinghouse Electric Corporation. A description of the surveillance program and the pre-irradiation mechanical properties of the reactor vessel materials are presented in WCAP-7254, "Rochester Gas and Electric Robert E. Ginna Unit No. I Reactor Vessel Radiation Surveillance Program" | |||
[3]. The surveillance program was planned to cover the 40-year design life of the reactor pressure vessel and was based on ASTM E185-66 [4], "Recommended Practice for Surveillance Tests on Structural Materials in Nuclear Reactors." Capsule N was removed from the reactor after Cycle 33, after 30.5 EFPY of exposure and shipped to the Westinghouse Science and Technology Department Hot Cell Facility, where the post-irradiation mechanical testing of the Charpy V-notch impact and tensile surveillance specimens was performed. | |||
This report summarizes the testing of the post-irradiation data obtained from surveillance Capsule N removed from the R. E. Ginna reactor vessel and discusses the analysis of the data. | |||
WCAP-17036-NP May 2009 Revision 0 | |||
3-1 3 BACKGROUND The ability of the large steel pressure vessel containing the reactor core and its primary coolant to resist fracture constitutes an important factor in ensuring safety in the nuclear industry. The beltline region of the reactor pressure vessel is the most critical region of the vessel because it is subjected to significant fast neutron bombardment. The overall effects of fast neutron irradiation on the mechanical properties of low alloy, ferritic pressure vessel steels such as ASTM A508 Class 2 (base material of the R. E. Ginna reactor pressure vessel beltline) are well documented in the literature. Generally, low alloy ferritic materials show an increase in hardness and tensile properties and a decrease in ductility and toughness during high-energy irradiation. | |||
A method for ensuring the integrity of reactor pressure vessels has been presented in "Fracture Toughness Criteria for Protection Against Failure," Appendix G to Section XI of the ASME Boiler and Pressure Vessel Code [5]. The method uses fracture mechanics concepts and is based on the reference nil-ductility transition temperature (RTNDT). | |||
RTNDT is defined as the greater of either the drop weight nil-ductility transition temperature (NDTT per ASTM E208 [6]) or the temperature 60'F less than the 50 ft-lb (and 35-mil lateral expansion) temperature as determined from Charpy specimens oriented perpendicular (transverse) to the major working direction of the plate. The RTNDT of a given material is used to index that material to a reference stress intensity factor curve (K1 c curve) which appears in Appendix G to Section X1 of the ASME Code [5]. The KIc curve is a lower bound of static fracture toughness results obtained from several heats of pressure vessel steel. | |||
When a given material is indexed to the KI, curve, allowable stress intensity factors can be obtained for this material as a function of temperature. Allowable operating limits can then be determined using these allowable stress intensity factors. | |||
RTNDT and, in turn, the operating limits of nuclear power plants can be adjusted to account for the effects of radiation on the reactor vessel material properties. The changes in mechanical properties of a given reactor pressure vessel steel, due to irradiation, can be monitored by a reactor vessel surveillance program, such as the R. E. Ginna reactor vessel radiation surveillance program, in which a surveillance capsule is periodically removed from the operating nuclear reactor and the encapsulated specimens are tested. The increase in the average Charpy V-notch 30 ft-lb temperature (ARTNDT) due to irradiation is added to the initial RTNDT, along with a margin (M) to cover uncertainties, to adjust the RTNDT (ART) for radiation embrittlement. This ART (RTNDT Initial + M + ARTNDT) is used to index the material to the K1 , | |||
curve and, in turn, to set operating limits for the nuclear power plant that take into account the effects of irradiation on the reactor vessel materials. | |||
WCAP-17036-NP May 2009 Revision 0 | |||
4-1 4 DESCRIPTION OF PROGRAM Six surveillance capsules for monitoring the effects of neutron exposure on the R. E. Ginna reactor pressure vessel core region (beltline) materials were inserted in the reactor vessel prior to initial plant startup. The six capsules were positioned in the reactor vessel between the thermal shield and the vessel wall as shown in Figure 4-1. The vertical center of the capsules is opposite the vertical center of the core. | |||
The capsules contain specimens made from the following: | |||
Iintermediate Shell Forging 125S255 (longitudinal orientation) | |||
* Lower Shell Forging 125P666 (longitudinal orientation) | * Lower Shell Forging 125P666 (longitudinal orientation) | ||
* Weld metal, Heat #61782 Linde Type 80 flux, which is the same wire used for the intermediate shell to lower shell girth weld.* Weld heat-affected-zone (HAZ) material of Lower Shell Forging 125P666 Test material obtained from the Intermediate Shell Forging 125S255 and Lower Shell Forging 125P666 (after thermal heat treatment and prior to welding the two shells together) was taken at least one forging thickness from the quenched edges of the forgings. | * Weld metal, Heat #61782 Linde Type 80 flux, which is the same wire used for the intermediate shell to lower shell girth weld. | ||
All test specimens were machined from the '/4 thickness location of the original forging thickness after stress-relieving. | * Weld heat-affected-zone (HAZ) material of Lower Shell Forging 125P666 Test material obtained from the Intermediate Shell Forging 125S255 and Lower Shell Forging 125P666 (after thermal heat treatment and prior to welding the two shells together) was taken at least one forging thickness from the quenched edges of the forgings. All test specimens were machined from the '/4 thickness location of the original forging thickness after stress-relieving. Test specimens from weld metal and heat-affected-zone (HAZ) metal of forging 125P666 were machined from a stress-relieved weldment joining Intermediate Shell Forging 125S255 and Lower Shell Forging 125P666. | ||
Test specimens from weld metal and heat-affected-zone (HAZ) metal of forging 125P666 were machined from a stress-relieved weldment joining Intermediate Shell Forging 125S255 and Lower Shell Forging 125P666.Charpy V-notch impact specimens from Intermediate Shell Forging 125S255 and Lower Shell Forging 125P666 were machined in the "strong" direction (longitudinal). | Charpy V-notch impact specimens from Intermediate Shell Forging 125S255 and Lower Shell Forging 125P666 were machined in the "strong" direction (longitudinal). Specimens from the weld metal were oriented with the longitudinal axis of the specimen transverse to the welding direction. | ||
Specimens from the weld metal were oriented with the longitudinal axis of the specimen transverse to the welding direction. | |||
Tensile specimens were machined with the longitudinal axis of the specimen parallel to the hoop direction of the forging. Tensile specimens from the weld metal were oriented with the longitudinal axis of the specimen parallel to the welding direction. | Tensile specimens were machined with the longitudinal axis of the specimen parallel to the hoop direction of the forging. Tensile specimens from the weld metal were oriented with the longitudinal axis of the specimen parallel to the welding direction. | ||
Wedge Opening Loading (WOL) test specimens from both forgings and the weld were machined with the simulated crack in the specimen perpendicular to the hoop direction and the major surfaces of the forgings. | |||
All six capsules contained dosimeter wires of pure copper, nickel, and aluminum-cobalt wire (cadmium-shielded and unshielded). In addition, cadmium-shielded dosimeters of Neptunium ( 2 37Np) and Uranium (238U) were placed in the capsules to measure the integrated flux at specific neutron energy levels. | |||
The capsules contained thermal monitors made from two low-melting-point eutectic alloys, which were sealed in Pyrex tubes. These thermal monitors were used to define the maximum temperature attained by the test specimens during irradiation. The composition of the two eutectic alloys and their melting points are as follows: | |||
2.5% Ag, 97.5% Pb Melting Point: 579°F (304'C) 1.75% Ag, 0.75% Sn, 97.5% Pb Melting Point: 590'F (310 0 C) | |||
WCAP-17036-NP May 2009 Revision 0 | |||
4-2 The chemical composition and heat treatment of the unirradiated surveillance materials are presented in Tables 4-1 and 4-2, respectively. The data in Table 4-1 was obtained from WCAP-13902 [7], "Analysis of Capsule S from the Rochester Gas and Electric Corporation R. E. Ginna Reactor Vessel Radiation Surveillance Program," with copper and nickel values for the surveillance weld heat #61782 updated as noted. The data in | |||
6-1 6 RADIATION ANALYSIS AND NEUTRON DOSIMETRY | |||
This section describes a discrete ordinates S,, transport analysis performed for the R. E. Ginna reactor to determine the neutron radiation environment within the reactor pressure vessel and surveillance capsules.In this analysis, fast neutron exposure parameters in terms of fast neutron fluence (E > 1.0 MeV) and iron atom displacements (dpa) were established on a plant and fuel cycle specific basis. An evaluation of the most recent dosimetry sensor set from Capsule N, withdrawn at the end of the thirty-third plant operating cycle, is provided. | ==6.1 INTRODUCTION== | ||
In addition, dosimetry results of, the sensor sets from the previously withdrawn capsules (V, R, T, and S) are also presented in Appendix A of this report. Comparisons of the results from these dosimetry evaluations with the analytical predictions served to validate the plant-specific neutron transport calculations. | |||
These validated calculations subsequently formed the basis for providing projections of the neutron exposure of the reactor pressure vessel for operating periods extending to 54 Effective Full Power Years (EFPY).The use of fast neutron fluence (E > 1.0 MeV) to correlate measured material property changes to the neutron exposure of the material has traditionally been accepted for the development of damage trend curves as well as for the implementation of trend curve data to assess the condition of the vessel. In recent years, however, it has been suggested that an exposure model that accounts for differences in neutron energy spectra between surveillance capsule locations and positions within the vessel wall could lead to an improvement in the uncertainties associated with damage trend curves and improved accuracy in the evaluation of damage gradients through the reactor vessel wall.Because of this potential shift away from a threshold fluence toward an energy-dependent damage function for data correlation, ASTM Standard Practice E853-01, "Analysis and Interpretation of Light-Water Reactor Surveillance Results," [22] recommends reporting displacements per iron atom (dpa) along with fluence (E > 1.0 MeV) to provide a database for future reference. | This section describes a discrete ordinates S,, transport analysis performed for the R. E. Ginna reactor to determine the neutron radiation environment within the reactor pressure vessel and surveillance capsules. | ||
The energy-dependent dpa function to be used for this evaluation is specified in ASTM Standard Practice E693-01, "Standard Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements per Atom" [23]. The application of the dpa parameter to the assessment of embrittlement gradients through the thickness of the reactor vessel wall has already been promulgated in Revision 2 to Regulatory Guide 1.99, "Radiation Embrittlement of Reactor Vessel Materials" [1].All of the calculations and dosimetry evaluations described in this section and in Appendix A were based on the latest available nuclear cross-section data derived from ENDF/B-VI and made use of the latest available calculational tools. Furthermore, the neutron' transport and dosimetry evaluation methodologies follow the guidance of Regulatory Guide 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence" [24]. Additionally, the methods used to develop the calculated pressure vessel fluence are consistent with the NRC approved methodology described in WCAP-14040-A, Revision 4, "Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves," May 2004 [25].WCAP-17036-NP May 2009 Revision 0 6-2 6.2 DISCRETE ORDINATES ANALYSIS A plan view of the R. E. Ginna reactor geometry at the core midplane is shown in Figure 4-1. Six irradiation capsules attached to the thermal shield are included in the reactor design that constitutes the reactor vessel surveillance program. The capsules are located at azimuthal angles of 570, 67', 770, 2370, 2470, and 257' as shown in Figure 4-1. These full-core positions correspond to the following octant symmetric locations represented in Figure 6-1: 130 from the core cardinal axes (for the 77' and 257'surveillance capsule holder locations), 23' from the core cardinal axes (for the 670 and 247' surveillance capsule holder locations) and 330 from the core cardinal axes (for the 570 and the 2370 surveillance capsule holder locations). | In this analysis, fast neutron exposure parameters in terms of fast neutron fluence (E > 1.0 MeV) and iron atom displacements (dpa) were established on a plant and fuel cycle specific basis. An evaluation of the most recent dosimetry sensor set from Capsule N, withdrawn at the end of the thirty-third plant operating cycle, is provided. In addition, dosimetry results of, the sensor sets from the previously withdrawn capsules (V, R, T, and S) are also presented in Appendix A of this report. Comparisons of the results from these dosimetry evaluations with the analytical predictions served to validate the plant-specific neutron transport calculations. These validated calculations subsequently formed the basis for providing projections of the neutron exposure of the reactor pressure vessel for operating periods extending to 54 Effective Full Power Years (EFPY). | ||
The six capsules were positioned in the reactor vessel between the thermal shield and the vessel wall as shown in Figure 4-1. The vertical center of the capsule is opposite the vertical center of the core.From a neutronic standpoint, the surveillance capsules and associated support structures are significant. | The use of fast neutron fluence (E > 1.0 MeV) to correlate measured material property changes to the neutron exposure of the material has traditionally been accepted for the development of damage trend curves as well as for the implementation of trend curve data to assess the condition of the vessel. In recent years, however, it has been suggested that an exposure model that accounts for differences in neutron energy spectra between surveillance capsule locations and positions within the vessel wall could lead to an improvement in the uncertainties associated with damage trend curves and improved accuracy in the evaluation of damage gradients through the reactor vessel wall. | ||
The presence of these materials has a marked effect on both the spatial distribution of neutron flux and the neutron energy spectrum in the water annulus between the neutron pads and the reactor vessel. In order to determine the neutron environment at the test specimen location, the capsules themselves must be included in the analytical model.In performing the fast neutron exposure evaluations for the R. E. Ginna reactor vessel and surveillance capsules, a series of fuel cycle specific forward transport calculations were carried out using the following three-dimensional flux synthesis technique: | Because of this potential shift away from a threshold fluence toward an energy-dependent damage function for data correlation, ASTM Standard Practice E853-01, "Analysis and Interpretation of Light-Water Reactor Surveillance Results," [22] recommends reporting displacements per iron atom (dpa) along with fluence (E > 1.0 MeV) to provide a database for future reference. The energy-dependent dpa function to be used for this evaluation is specified in ASTM Standard Practice E693-01, "Standard Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements per Atom" [23]. The application of the dpa parameter to the assessment of embrittlement gradients through the thickness of the reactor vessel wall has already been promulgated in Revision 2 to Regulatory Guide 1.99, "Radiation Embrittlement of Reactor Vessel Materials" [1]. | ||
All of the calculations and dosimetry evaluations described in this section and in Appendix A were based on the latest available nuclear cross-section data derived from ENDF/B-VI and made use of the latest available calculational tools. Furthermore, the neutron' transport and dosimetry evaluation methodologies follow the guidance of Regulatory Guide 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence" [24]. Additionally, the methods used to develop the calculated pressure vessel fluence are consistent with the NRC approved methodology described in WCAP-14040-A, Revision 4, "Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves," May 2004 [25]. | |||
WCAP-17036-NP May 2009 Revision 0 | |||
6-2 6.2 DISCRETE ORDINATES ANALYSIS A plan view of the R. E. Ginna reactor geometry at the core midplane is shown in Figure 4-1. Six irradiation capsules attached to the thermal shield are included in the reactor design that constitutes the reactor vessel surveillance program. The capsules are located at azimuthal angles of 570, 67', 770, 2370, 2470, and 257' as shown in Figure 4-1. These full-core positions correspond to the following octant symmetric locations represented in Figure 6-1: 130 from the core cardinal axes (for the 77' and 257' surveillance capsule holder locations), 23' from the core cardinal axes (for the 670 and 247' surveillance capsule holder locations) and 330 from the core cardinal axes (for the 570 and the 2370 surveillance capsule holder locations). The six capsules were positioned in the reactor vessel between the thermal shield and the vessel wall as shown in Figure 4-1. The vertical center of the capsule is opposite the vertical center of the core. | |||
From a neutronic standpoint, the surveillance capsules and associated support structures are significant. | |||
The presence of these materials has a marked effect on both the spatial distribution of neutron flux and the neutron energy spectrum in the water annulus between the neutron pads and the reactor vessel. In order to determine the neutron environment at the test specimen location, the capsules themselves must be included in the analytical model. | |||
In performing the fast neutron exposure evaluations for the R. E. Ginna reactor vessel and surveillance capsules, a series of fuel cycle specific forward transport calculations were carried out using the following three-dimensional flux synthesis technique: | |||
p(r, 0, z) = p(r, 0) | p(r, 0, z) = p(r, 0) | ||
* p(r, z)T(r)where 4(r,0,z) is the synthesized three-dimensional neutron flux distribution, 4(r,0) is the transport solution in (r,0) geometry, 4(rz) is the two-dimensional solution for a cylindrical reactor model using the actual axial core power distribution, and 4(r) is the one-dimensional solution for a cylindrical reactor model using the same source per unit height as that used in the (r,0) two-dimensional calculation. | * p(r, z) | ||
This synthesis procedure was carried out for each operating cycle at R. E. Ginna.For the R. E. Ginna transport calculations, the (r,0) model depicted in Figure 6-1 was utilized since the reactor is octant symmetric. | T(r) where 4(r,0,z) is the synthesized three-dimensional neutron flux distribution, 4(r,0) is the transport solution in (r,0) geometry, 4(rz) is the two-dimensional solution for a cylindrical reactor model using the actual axial core power distribution, and 4(r) is the one-dimensional solution for a cylindrical reactor model using the same source per unit height as that used in the (r,0) two-dimensional calculation. This synthesis procedure was carried out for each operating cycle at R. E. Ginna. | ||
The (r,0) model includes the core, the reactor internals, the thermal shield -including explicit representations of surveillance capsules at 13', 230 and 330, the pressure vessel cladding and vessel wall, the insulation external to the pressure vessel, and the primary biological shield wall. This model formed the basis for the calculated results and enabled making comparisons to the surveillance capsule dosimetry evaluations. | For the R. E. Ginna transport calculations, the (r,0) model depicted in Figure 6-1 was utilized since the reactor is octant symmetric. The (r,0) model includes the core, the reactor internals, the thermal shield - | ||
In developing these analytical models, nominal design dimensions were employed for the various structural components. | including explicit representations of surveillance capsules at 13', 230 and 330, the pressure vessel cladding and vessel wall, the insulation external to the pressure vessel, and the primary biological shield wall. This model formed the basis for the calculated results and enabled making comparisons to the surveillance capsule dosimetry evaluations. In developing these analytical models, nominal design dimensions were employed for the various structural components. Likewise, water temperatures, and hence, coolant densities in the reactor core and downcomer regions of the reactor were taken to be representative of full power operating conditions. The coolant densities were treated on a fuel cycle specific basis. The reactor core itself was treated as a homogeneous mixture of fuel, cladding, water, and miscellaneous core structures such as fuel assembly grids, guide tubes, et cetera. The geometric mesh description of the (r,0) reactor model consisted of 148 radial by 105 azimuthal intervals. Mesh sizes were chosen to assure that proper convergence of the inner iterations was achieved on a pointwise basis. The pointwise inner iteration flux convergence criterion utilized in the (r,0) calculations was set at a value of 0.001. | ||
Likewise, water temperatures, and hence, coolant densities in the reactor core and downcomer regions of the reactor were taken to be representative of full power operating conditions. | WCAP-17036-NP May 2009 Revision 0 | ||
The coolant densities were treated on a fuel cycle specific basis. The reactor core itself was treated as a homogeneous mixture of fuel, cladding, water, and miscellaneous core structures such as fuel assembly grids, guide tubes, et cetera. The geometric mesh description of the (r,0) reactor model consisted of 148 radial by 105 azimuthal intervals. | |||
Mesh sizes were chosen to assure that proper convergence of the inner iterations was achieved on a pointwise basis. The pointwise inner iteration flux convergence criterion utilized in the (r,0) calculations was set at a value of 0.001.WCAP-17036-NP May 2009 Revision 0 6-3 The (r,z) model used for the R. E. Ginna calculations is shown in Figure 6-2 and extends radially from the centerline of the reactor core out to a location interior to the primary biological shield and over an axial span from an elevation one foot below the active fuel to one foot above the active fuel. As in the case of the (r,0) models, nominal design dimensions and full power coolant densities were employed in the calculations. | 6-3 The (r,z) model used for the R. E. Ginna calculations is shown in Figure 6-2 and extends radially from the centerline of the reactor core out to a location interior to the primary biological shield and over an axial span from an elevation one foot below the active fuel to one foot above the active fuel. As in the case of the (r,0) models, nominal design dimensions and full power coolant densities were employed in the calculations. In this case, the homogenous core region was treated as an equivalent cylinder with a volume equal to that of the active core zone. The stainless steel former plates located between the core baffle and core barrel regions were also explicitly included in the model. The (rz) geometric mesh description of the reactor model consisted of 127 radial by 155 axial intervals. As in the case of the (r,0) calculations, mesh sizes were chosen to assure that proper convergence of the inner iterations was achieved on a pointwise basis. The pointwise inner iteration flux convergence criterion utilized in the (r,z) calculations was also set at a value of 0.001. | ||
In this case, the homogenous core region was treated as an equivalent cylinder with a volume equal to that of the active core zone. The stainless steel former plates located between the core baffle and core barrel regions were also explicitly included in the model. The (rz) geometric mesh description of the reactor model consisted of 127 radial by 155 axial intervals. | The one-dimensional radial (r) model used in the synthesis procedure consisted of the same 127 radial mesh intervals included in the (rz) model. Thus, radial synthesis factors could be determined on a meshwise basis throughout the entire geometry. | ||
As in the case of the (r,0) calculations, mesh sizes were chosen to assure that proper convergence of the inner iterations was achieved on a pointwise basis. The pointwise inner iteration flux convergence criterion utilized in the (r,z) calculations was also set at a value of 0.001.The one-dimensional radial (r) model used in the synthesis procedure consisted of the same 127 radial mesh intervals included in the (rz) model. Thus, radial synthesis factors could be determined on a meshwise basis throughout the entire geometry.The core power distributions used in the plant-specific transport analysis were provided by the Nuclear Fuels Division of Westinghouse for each of the first thirty-three fuel cycles at R. E. Ginna. Specifically, the data utilized included cycle-dependent fuel assembly initial enrichments, burnups, and axial power distributions. | The core power distributions used in the plant-specific transport analysis were provided by the Nuclear Fuels Division of Westinghouse for each of the first thirty-three fuel cycles at R. E. Ginna. Specifically, the data utilized included cycle-dependent fuel assembly initial enrichments, burnups, and axial power distributions. This information was used to develop spatial and energy dependent core source distributions averaged over each individual fuel cycle. Therefore, the results from the neutron transport calculations provided data in terms of fuel cycle averaged neutron flux, which when multiplied by the appropriate fuel cycle length, generated the incremental fast neutron exposure for each fuel cycle. In constructing these core source distributions, the energy distribution of the source was based on an appropriate fission split for uranium and plutonium isotopes based on the initial enrichment and bumup history of individual fuel assemblies. From these assembly-dependent fission splits, composite values of energy release per fission, neutron yield per fission, and fission spectrum were determined. | ||
This information was used to develop spatial and energy dependent core source distributions averaged over each individual fuel cycle. Therefore, the results from the neutron transport calculations provided data in terms of fuel cycle averaged neutron flux, which when multiplied by the appropriate fuel cycle length, generated the incremental fast neutron exposure for each fuel cycle. In constructing these core source distributions, the energy distribution of the source was based on an appropriate fission split for uranium and plutonium isotopes based on the initial enrichment and bumup history of individual fuel assemblies. | All of the transport calculations supporting this analysis were carried out using the DORT discrete ordinates code Version 3.2 [26] and the BUGLE-96 cross-section library [27]. The BUGLE-96 library provides a 67-group coupled neutron-gamma ray cross-section data set produced specifically for light water reactor (LWR) applications. In these analyses, anisotropic scattering was treated with a P 5 legendre expansion and angular discretization was modeled with an S1 6 order of angular quadrature. Energy and space dependent core power distributions, as well as system operating temperatures, were treated on a fuel cycle ýpecific basis. | ||
From these assembly-dependent fission splits, composite values of energy release per fission, neutron yield per fission, and fission spectrum were determined. | Selected results from the neutron transport analyses are provided in Tables 6-1 through 6-6. In Table 6-1, the calculated integrated exposures, expressed in terms of both neutron fluence (E > 1.0 MeV) and dpa, are given at the radial and axial center of the surveillance capsule at each individual azimuthal position, i.e., at 13', 230, and 33'. These results, representative of the axial midplane of the active core, establish the calculated exposure of the surveillance capsules withdrawn to date as well as projected into the future. | ||
All of the transport calculations supporting this analysis were carried out using the DORT discrete ordinates code Version 3.2 [26] and the BUGLE-96 cross-section library [27]. The BUGLE-96 library provides a 67-group coupled neutron-gamma ray cross-section data set produced specifically for light water reactor (LWR) applications. | Similar information is provided in Table 6-2 for the reactor vessel inner radius at four azimuthal locations. | ||
In these analyses, anisotropic scattering was treated with a P 5 legendre expansion and angular discretization was modeled with an | The vessel data given in Table 6-2 were taken at the clad/base metal interface, and thus, represent maximum calculated exposure levels on the vessel. | ||
Energy and space dependent core power distributions, as well as system operating temperatures, were treated on a fuel cycle ýpecific basis.Selected results from the neutron transport analyses are provided in Tables 6-1 through 6-6. In Table 6-1, the calculated integrated exposures, expressed in terms of both neutron fluence (E > 1.0 MeV) and dpa, are given at the radial and axial center of the surveillance capsule at each individual azimuthal position, i.e., at 13', 230, and 33'. These results, representative of the axial midplane of the active core, establish the calculated exposure of the surveillance capsules withdrawn to date as well as projected into the future.Similar information is provided in Table 6-2 for the reactor vessel inner radius at four azimuthal locations. | WCAP-17036-NP May 2009 Revision 0 | ||
The vessel data given in Table 6-2 were taken at the clad/base metal interface, and thus, represent maximum calculated exposure levels on the vessel.WCAP-17036-NP May 2009 Revision 0 6-4 From the data provided in Table 6-2, it is noted that the peak clad/base metal interface vessel fluence (E > 1.0 MeV) at the end of the thirty-third fuel cycle (i.e., after 30.5 EFPY of plant operation) was 3.20x109 n/cm 2.Both calculated fluence (E > 1.0 MeV) and dpa data are provided in Tables 6-1 and 6-2. These data tabulations include both plant and fuel cycle specific calculated neutron exposures at the end of the thirty-third fuel cycle as well as future projections to 31.8, 33.3, 36, 42, 48, 52, 53, and 54 EFPY. The calculations account for an uprate from 1520 MWt to 1775 MWt that occurred at the onset of Cycle 33.Projections for Cycles 35 and beyond were based on the conservative assumption that the core power distribution for Cycle 33 was applicable, along with a power level of 1811 MWt. Similar data applicable to the intermediate shell to nozzle shell circumferential weld are provided in Table 6-3.Radial gradient information applicable to fast (E > 1.0 MeV) neutron fluence and dpa are given in Tables 6-4 and 6-5, respectively. | |||
The data, based on the cumulative integrated exposures from Cycles 1 through 33, are presented on a relative basis for each exposure parameter at several azimuthal locations. | 6-4 From the data provided in Table 6-2, it is noted that the peak clad/base metal interface vessel fluence (E > 1.0 MeV) at the end of the thirty-third fuel cycle (i.e., after 30.5 EFPY of plant operation) was 3.20x109 n/cm 2. | ||
Exposure distributions through the vessel wall maybe obtained by multiplying the calculated exposure at the vessel inner radius by the gradient data listed in Tables 6-4 and 6-5.The calculated fast neutron exposures for the five surveillance capsules withdrawn from R. E. Ginna reactor are provided in Table 6-6. These assigned neutron exposure levels are based on the plant and fuel cycle-specific neutron transport calculations performed for the R. E. Ginna reactor.From the data provided in Table 6-6, Capsule N received a fluence (E > 1.0 MeV) of 5.80x1019 n/cm | Both calculated fluence (E > 1.0 MeV) and dpa data are provided in Tables 6-1 and 6-2. These data tabulations include both plant and fuel cycle specific calculated neutron exposures at the end of the thirty-third fuel cycle as well as future projections to 31.8, 33.3, 36, 42, 48, 52, 53, and 54 EFPY. The calculations account for an uprate from 1520 MWt to 1775 MWt that occurred at the onset of Cycle 33. | ||
Projections for Cycles 35 and beyond were based on the conservative assumption that the core power distribution for Cycle 33 was applicable, along with a power level of 1811 MWt. Similar data applicable to the intermediate shell to nozzle shell circumferential weld are provided in Table 6-3. | |||
Radial gradient information applicable to fast (E > 1.0 MeV) neutron fluence and dpa are given in Tables 6-4 and 6-5, respectively. The data, based on the cumulative integrated exposures from Cycles 1 through 33, are presented on a relative basis for each exposure parameter at several azimuthal locations. | |||
Exposure distributions through the vessel wall maybe obtained by multiplying the calculated exposure at the vessel inner radius by the gradient data listed in Tables 6-4 and 6-5. | |||
The calculated fast neutron exposures for the five surveillance capsules withdrawn from R. E. Ginna reactor are provided in Table 6-6. These assigned neutron exposure levels are based on the plant and fuel cycle-specific neutron transport calculations performed for the R. E. Ginna reactor. | |||
2 From the data provided in Table 6-6, Capsule N received a fluence (E > 1.0 MeV) of 5.80x1019 n/cm after exposure through the end of the thirty-third fuel cycle (i.e., after 30.5 EFPY of plant operation). | |||
Lead factors for the R. E. Ginna surveillance capsules are provided in Table 6-7. The capsule lead factor is defined as the ratio of the calculated fluence (E > 1.0 MeV) at the geometric center of the surveillance capsule to the corresponding maximum calculated fluence at the pressure vessel clad/base metal interface. | Lead factors for the R. E. Ginna surveillance capsules are provided in Table 6-7. The capsule lead factor is defined as the ratio of the calculated fluence (E > 1.0 MeV) at the geometric center of the surveillance capsule to the corresponding maximum calculated fluence at the pressure vessel clad/base metal interface. | ||
In Table 6-7, the lead factors for capsules that have been withdrawn from the reactor (V, R, T, S, and N) were based on the calculated fluence values for the irradiation period corresponding to the time of withdrawal for the individual capsules. | |||
6.3 NEUTRON DOSIMETRY The validity of the calculated neutron exposures previously reported in Section 6.2 is demonstrated by a direct comparison against the measured sensor reaction rates and via a least squares evaluation performed for each of the capsule dosimetry sets. However, since the neutron dosimetry measurement data merely serves to validate the calculated results, only the direct comparison of measured-to-calculated results for the most recent surveillance capsule removed from service is provided in this section of the report. For completeness, the assessment of all measured dosimetry removed to date, based on both direct and least squares evaluation comparisons, is documented in Appendix A. | |||
WCAP-17036-NP May 2009 Revision 0 | |||
6-5 The direct comparison of measured versus calculated fast | |||
While the uncertainties associated with the reaction rates were obtained from the measurement procedures and counting benchmarks and the dosimetry cross-section uncertainties were supplied directly with the SNLRML library, the uncertainty matrix for the calculated spectrum was constructed from the following relationship: | While the uncertainties associated with the reaction rates were obtained from the measurement procedures and counting benchmarks and the dosimetry cross-section uncertainties were supplied directly with the SNLRML library, the uncertainty matrix for the calculated spectrum was constructed from the following relationship: | ||
2 *Rg, *P Mgg, = R +R ggn9g9g where R, specifies an overall fractional normalization uncertainty and the fractional uncertainties Rg and Rg, specify additional random groupwise uncertainties that are correlated with a correlation matrix given by: | |||
Pgg, = [1 -O16gg, +- 0 eH where 2 | |||
H - (g_ g,) | |||
2 2y The first term in the correlation matrix equation specifies purely random uncertainties, while the second term describes the short-range correlations over a group range y (0 specifies the strength of the latter term). The value of 5 is 1.0 when g = g', and is 0.0 otherwise. | |||
The set of parameters defining the input covariance matrix for the R. E. Ginna calculated spectra was as follows: | |||
May 2009 WCAP-l 7036- | |||
==References:== | ==References:== | ||
(a) Westinghouse Calculation Note CN-PCAM-07-10, Revision 0, "CVGRAPH Version 5.3 Validation and Verification," December 2007. | |||
(b) WCAP-14370, Revision 0, "Use of the Hyperbolic Tangent Function for Fitting Transition Temperature Toughness Data," T. R. Mager, et al., May 1995. | |||
(c) Westinghouse Letter LTR-PCAM-07-105, "Release of Program CVGraph 5.3 for Production Use," December 19, 2007. | |||
C-2 ASTM E185-82, Standard Practicefor Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, E706 (IF), ASTM, 1982. | |||
May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0 | |||
C-3 Unirradiated Intermediate Shell Forging 125S255 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/08/2009 10:19 PM Page 1 Coefficients of Curve I A=71.1 B=68.9C=85.45 TO=29.82 D= O00RtF00 Equation is A + B * [Tanh((T-ToY(C+DT))] | |||
Upper Shelf Energry=140.0(Fixed) Lower Shelf Energy2.2(Fixed) | |||
Temp@30 ft-lb--28.9 Deg F Temp@50 ft-lb=Z8 Deg F Plant Cinna Material: SA5S08CL2 Heat: 125S255 Orientation: LC Capsule: UNIRR FRuence: r'cnMA2 4~l' ouu 250 | |||
-r 200 IT z | |||
wQ 100 0 | |||
5o 0 0 50 0. | |||
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Teipemretun. Iqnpt CVN Computed CVN Diferentmial | |||
- 80. 00 5. 00 1 .99 -6. 99 | |||
- ,0. O0 11. 50 11.99 -. 49 | |||
- 80. 00 11. 00 11.99 -. 99 | |||
-40. 00 6. 00 24. 70 -18.70 | |||
-40. 00 28. 00 24. 70 3. 30 | |||
-40. 00 19.00 24. 70 -5. 70 | |||
-20. 00 45. 50 | |||
* ITanh((T-ToY(C+DT))] | * ITanh((T-ToY(C+DT))] | ||
Temperature at 50% Shear = 56.7 Plant: Qinna Material: | Temperature at 50% Shear = 56.7 Plant: Qinna Material: SA5O8CL2 Heat: 125P666 Orientation: LC Capsule: T Fluence: n/cm'*2 125 100 0) | ||
SA5O8CL2 Heat: 125P666 Orientation: | Il o,. | ||
LC Capsule: T Fluence: | -300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperuture. Input Percent Shear Computed Percent Shear Diffrential | ||
-50. 00 | -50. 00 2. 00 7.71 - 5. 71 | ||
- 10. 00 26. 00 17. 48 8. 52 | |||
SA508CL2 Heat: 125P666 Orientation: | .00 22. 00 21. 09 .91 | ||
LC Capsule: T Fluenoe: n/cn-ib2 Charpy V-Notch Data Input Percent Shear Computed Percent Shear 100. 00 99. 89 Correlation Coefficient | : 25. 00 18.00 32. 35 -14.35 | ||
=.967 | : 50. 00 47. 00 46. 11 .89 | ||
: 75. 00 74. 00 60. 49 13.51 150. 00 72. 00 89. 76 -17.76 175. 00 10oo 00 94. 01 5. 99 250. 00 1oo. 00 98. 90 1.10 WCAP-17036-NP May 2009 Revision 0 | |||
Temperature at 50% Shear = 38.3 Plant Ginna Material: | |||
SAS08CL2 Heat: 125P666 Orientation: | C-66 Capsule T Lower Shell Forging 125P666 | ||
LC Capsule: S Fluence: rn^mA2 125 100 N.e | . Page 2 | ||
Plant: Ginna Material: SA508CL2 Heat: 125P666 Orientation: LC Capsule: T Fluenoe: n/cn-ib2 Charpy V-Notch Data Temperaturr Input Percent Shear Computed Percent Shear Differential 350. 00 100. 00 99. 89 .1I1 Correlation Coefficient =.967 WCAP-17036-NP May 2009 Revision 0 | |||
SA509CL2 Heat: 125P666 Orientation: | |||
LC Capsule: S Fluence: nlcm^2 Charpy V-Notch Data Tempemrture 225.00 | C-67 Capsule S Lower Shell Forging 12511666 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02(0812009 12:15 PM Page 1 Coefficients of Curve I A=50f B=50. C=63.9 TO= 38.29 D = 0.00E+0O Equation is A + B * [Tanh((T-To)/(C+DT))] | ||
Temperature at 50% Shear = 38.3 Plant Ginna Material: SAS08CL2 Heat: 125P666 Orientation: LC Capsule: S Fluence: rn^mA2 125 100 N. 75 e 50 25 | |||
= .974 WCAP-l 7036-NP | -300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data lnput Percent Shear Computed L-roent Shear Differential | ||
Temperature at 50% Shear= 100.3 Plant: Ginna Material: | -45.00 5. 00 6. 87 - 1. 87 | ||
SA508CL2 Heat: 125P666 Orientation: | .00 10.00 23. 17 - 13. 17 5.00 25. 00 26. 08 -1. 08 15.00 50. 00 32. 54 17. 46 | ||
LC Capsule: N Fluence: nIcmA2 125 100 e 0 | : 25. 00 45. 00 39. 75 5. 25 | ||
-25. 00 | : 50. 00 45. 00 59. 06 -14. 06 | ||
: 75. 00 80. 00 75. 93 4. 07 100. 00 90. 00 87. 34 2. 66 150. 00 95. 00 97. 06 - 2. 06 WCAP-17036-NP May 2009 Revision 0 | |||
SA50CL2 Heat: 125P666 Orientation: | |||
LC Capsule: N Fluence: n/cm12 Charpy V-Notch Data Temperature 350. 00 | C-68 Capsule S Lower Shell Forging 1251P666 Page 2 Plant: Ginna Material: SA509CL2 Heat: 125P666 Orientation: LC Capsule: S Fluence: nlcm^2 Charpy V-Notch Data Tempemrture Input Percent Shear Computed Percent Shear Differential 225.00 100. 00 99. 71 .29 250. 00 100. 00 99. 87 .13 325.00 100. 00 99. 99 . 01 Cormlation Coefficient = .974 May 2009 WCAP-l 7036-NP WCAP-17036-NP May 2009 Revision 0 | ||
=. 989 WCAP-1 7036-NP | C-69 Capsule N Lower Shell Forging 12517666 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0-V0512009 09:16 AM Pag I Coefficients of Curve I A = 50. B = 50. C = 64.75 TO = 100.25 D = 0.OOE+00 Equation is A + B * [Tanh((T-ToY(C+DT))] | ||
Temperature at 50% Shear= 100.3 Plant: Ginna Material: SA508CL2 Heat: 125P666 Orientation: LC Capsule: N Fluence: nIcmA2 125 100 75 IL e | |||
0 50 25 0 i | |||
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data TerimpqrntuI' Input Percent Shear Computed Percnt Shear Differential | |||
- 25. 00 2.00 2. 05 - . 05 | |||
: 20. 00 5. 00 7. 73 -2. 73 | |||
: 30. 00 5.00 10. 25 -5. 25 | |||
: 40. 00 5. 00 13. 46 -8. 46 | |||
: 50. 00 25. 00 17. 48 7. 52 | |||
: 55. 00 20. 00 19.82 go. 00 45. 00 34. 85 10..181 5 | |||
: 90. 00 45. 00 42. 15 2. 85 0oo. 00 40. 00 49. 80 -9.80 May 2009 WCAP-l 7036-NP WCAP-17036-NP May 2009 Revision 0 | |||
C-70 Capsule N Lower Shell Forging 125IP666 Pag 2 Plant: Ginna Material: SA50CL2 Heat: 125P666 Orientation: LC Capsule: N Fluence: n/cm12 Charpy V-Notch Data Temperature hput P*xeent Shear Computed Percent Shear Diffcrential 350. 00 100.00 99. 96 *04 375. 00 100. 00 99. 98 *02 390. 00 100. 00 99. 99 .01 Correlation Coefficient =. 989 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0 | |||
C-71 Unirradiated Weld Heat 61.782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03f10/2009 10:34 PM Page 1 Coefficients of Curve I A=40.6 B=38.4C=93.15 TO=-8.3 D=0.00E+00 Equation is A + B | |||
* ITanh((T-ToY(C+DT))] | * ITanh((T-ToY(C+DT))] | ||
Upper Shelf Energy=79.0(Fixed) | Upper Shelf Energy=79.0(Fixed) Lower Shelf Energ)-y2.2(Fixed) | ||
Lower Shelf Energ)-y2.2(Fixed) | Telmp@ 30 ft-lbs=-34.7 Deg F Temp@50 ft-lbs=15.0 Deg F Plant. Ginna Material: SAW Heat 61782 Orientalion: NA Capsule: UNIRR Fluence: r'cmnA2 300 250 200 0 | ||
Telmp@ 30 ft-lbs=-34.7 Deg F Temp@50 ft-lbs=15.0 Deg F Plant. Ginna Material: | 150 C | ||
SAW Heat 61782 Orientalion: | w z | ||
NA Capsule: UNIRR Fluence: r'cmnA2 300 250 200 0 150 C w z 100 50 0 1- | 100 50 0 't 1- . 1 - - | ||
-90. 00 | -300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Tmlperutuir Input CV N Compubrd CVN Differential | ||
- | -90. 00 7. 50 13. 53 -6.03 | ||
SAW Heat: 61782 Orientation: | -90.00 8. 50 13. 53 - 5. 03 | ||
NA Capsule: UNIRR Fluence: n/cnr"2 Charpy V-Notch Data Temperatur | - 90.00 8. 50 13. 53 -5. 03 | ||
: 10. 00 | -65. 00 26. 00 19. 74 6. 26 | ||
= . | - 65. 00 26. 50 19.74 6. 76 | ||
-65. 00 8. 00 19. 74 -11. 74 | |||
-40. 00 34. 00 28. 02 5. 98 | |||
-40. 00 35. 00 28. 02 6. 98 | |||
-40. 00 35. 00 28. 02 6. 98 WCAP- 17036-NP May 2009 Revision 0 | |||
. | C-72 Unirradiated Weld Heat 61782 Pag 2 Plant: Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: UNIRR Fluence: n/cnr"2 Charpy V-Notch Data Temperatur Input C-VN Computed CVN Differential | ||
SAW Heat: 61782 Orientation: | : 10. 00 51.00 48. 05 2. 95 | ||
NA Capsule: V FRlence: ncmnV2 Charpy V-Notch Data Input CVN Computed C-N | : 10. 00 42. 50 48. 05 -5. 55 | ||
=.992 | : 10. 00 39. 00 48. 05 05 | ||
: 60. 00 54. 00 64. 60 -10. 60 | |||
Upper Shelf Energy=48.9(Fixed) | : 60. 00 66. 50 64. 60 1. 90 | ||
Lower Shelf Energyz2.2(Fixed) | : 60. 00 71. 00 64. 60 6. 40 110. 00 79. 50 73. 39 6. 11 110. 00 70. 50 73. 39 -2. 89 110. 00 76. 50 73. 39 11 160. 00 77. 00 76. 98 02 160. 00 79. 50 76. 98 2. 52 160. 00 76. 50 76. 98 48 210. 00 80. 00 78. 30 1. 70 210. 00 74. 00 78. 30 - 4. 30 210. 00 83. 00 78. 30 4. 70 Corelation Coefficient = .975 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0 | ||
Temp@30 ft-lbs=121.5Deg F Temp@50 ft-lbs= NA Plant: Ginna Material: | |||
SAW Heat 61782 Orientation: | C-73 Capsule V Weld Heat 61.782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/11/2009 08:38 AM Paw I Coefficients of Curve I A = 2&72 B = 26.52 C = 10L65 TO = 107. D = 0.00E+O0 Equation is A + B * [Tanh((T-Toy(C+DT))] | ||
NA Capsule.: | Upper Shelf Energ=55.2 Lower Shelf Energy=2.2(Fixed) | ||
R Fluennce, n/cnA2 300 250-200 0 150 w z 100 50 0-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperamre | Temp@30 ft-lbs1 12.0 Deg F Temp@50 ft-lbs219.4 Deg F Plant Ginna Material: SAW Heat 61782 Orientation: NA Capsule: V Fluence: n/cMA2 | ||
: 17. 00 | 'bA* | ||
aUU 250- | |||
SAW Heat: 6178:2 Orientation: | -r 200 A | ||
NA Capsule: R Fluence: n/cm^2 Charpy V-Notch Data Temperature 350. 00 | 150 0 | ||
= .904 WCAP-17036-NP May 2009 Revision 0 C-77 Capsule T Weld Heat 61782 | 8S 100 501___ | ||
Upper Shelf Energy=52.7(Fixed) | -300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Tempemrtum Input CVN Computed CVN Differnti1al | ||
Lower Shelf Energay2.2(Fixed) | : 10. 00 9. 80 9. 05 .75 | ||
Temp@30 ft-tbs=l 15.0 Deg F Temp@50 ft-lbs=259. | : 40. 00 12.00 13. 40 -1. 40 | ||
IDeg F Plant Ginna Material: | : 75. 00 23. 00 20. 64 2. 36 125.00 29. 50 33. 37 -3.87 125.00 34. 50 33. 37 1. 13 175. 00 47. 00 44. 21 2. 79 175. 00 42. 30 44. 21 -1. 91 210.00 50. 50 49. 06 1.44 300. 00 53. 30 54. 08 -. 78 WCAP-17036-NP May 2009 Revision 0 | ||
SAW Heat: 61782 Orientation: | |||
NA Capsule: T reco Fluenme nk/nP2 | C-74 Capsule V Weld Heat 61782 Page 2 Plant: Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: V FRlence: ncmnV2 Charpy V-Notch Data Temperature Input CVN Computed C-N Differential 500. 00 55. 00 55. 22 -. 22 Cornlation Coefflcient =.992 WCAP-17036-NP May 2009 Revision 0 | ||
.00 | |||
C-75 Capsule R Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/27/2009 09:27 AM Page I Coefficients of Curve I A = 25-55 B = 23.35 C = 81.21 TO = 105.77 D = O.OOE+00 Equation is A + B * [Tanh((T-ToY(C+DT))] | |||
SAW Heat: 61782 Orientation: | Upper Shelf Energy=48.9(Fixed) Lower Shelf Energyz2.2(Fixed) | ||
NA Capsule: T reco Fluence: ncm^2 Charpy V-Notch Data Temperature | Temp@30 ft-lbs=121.5Deg F Temp@50 ft-lbs= NA Plant: Ginna Material: SAW Heat 61782 Orientation: NA Capsule.: R Fluennce, n/cnA2 300 250 | ||
- 200 0 | |||
150 w | |||
Upper Shelf Energr52.2(Fixed) | z 100 50 0 | ||
Lower Shelf Energy=2.2(Fixed) | -300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperamre Input CVN Conputed CVN Differential | ||
Temp@30 ft-lbs=lT77.5 Deg F Temp@50 ft-lbs=346.5 Deg F Plant: Ginna Material: | : 17. 00 21. 00 17.61 3. 39 150.00 35. 00 37. 14 -2.14 150. 00 30, 00 37. 14 -7. 14 199,00 50. 00 44. 63 5. 37 200.00 50. 00 44.72 5. 28 250.00 53. 00 47. 60 5. 40 250.00 47. 00 47. 60 60 300. 00 49. 00 48. 51 49 350. 00 43. 00 48. 79 -5. 79 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0 | ||
SAW Heat 61782 Orientation: | |||
NA Capsule: S Fluen'e: nra^2 0 0n | C-76 Capsule R Weld Heat 61782 Page 2 Plant Ginna Material: SAW Heat: 6178:2 Orientation: NA Capsule: R Fluence: n/cm^2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 350. 00 50. 00 48. 79 1.21 Correlation Coefficient = .904 WCAP-17036-NP May 2009 Revision 0 | ||
.00 | |||
. | C-77 Capsule T Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/27/2009 09:34 AM Page 1 Coefficients of Curve I A = 27.45 B = 25.25 C = 107.87 TO = 104.06 D = 0.OOE+00 Equation is A + B . [Tanh((T-Toy(C+DT))] | ||
SAW Heal: 61792 Orientation: | Upper Shelf Energy=52.7(Fixed) Lower Shelf Energay2.2(Fixed) | ||
NA Capsule: S Fluence: n/km^2 Charpy V-Notch Data Temperature 350. 00 400. 00 | Temp@30 ft-tbs=l 15.0 Deg F Temp@50 ft-lbs=259. IDeg F Plant Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: T reco Fluenme nk/nP2 300 250 200 0 | ||
150 z | |||
= .970 WCAP-1 7036-NP | 100 5o | ||
Upper Shelf Energy=51.9(Fixed) | - -~ -~- - - - -t-0 | ||
Lower Shelf Energy=2.2(Fixed) | -300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differenftial | ||
Temp@30 ft-lbs=182,2 Deg F Temp@50 ft-lbs=276.0 Deg F Plant Ginna Material: | .00 5. 00 8. 60 -3. 60 | ||
SAW Heat: 61782 Orientation: | : 75. 00 22. 00 20. 81 1, 19 125.00 29. 00 32.29 -3. 29 150. 00 35. 50 37.60 -2. 10 210. 00 41. 00 46.49 -5. 49 250.00 46. 50 49. 54 - 3. 04 300. 00 50. 50 51. 40 90 350. 00 52. 50 52. 18 32 425. 00 55. 50 52. 57 2. 93 WCAP-17036-NP May 2009 Revision 0 | ||
NA Capsule: N Fluence: n/cmA2 0 | |||
* 00 150. 00 200-00 | C-78 Capsule T Weld Heat 61782 Page 2 Plant: Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: T reco Fluence: ncm^2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 425. 00 63. 00 52. 57 10. 43 | ||
: 70. 00 22. 00 19. 73 2. 27 150.00 43. 00 37.60 5. 40 210.00 47, 00 46, 49 .51 210. 00 50. 00 46. 49 3.51 300. 00 53. 00 51. 40 1.60 350.00 52. 00 52. 18 -. 18 350. 00 52. 00 52. 18 18 425. 00 49. 00 52. 57 -3. 57 Correlation Coefficient =.966 WCAP-17036-NP May 2009 Revision 0 | |||
C-79 Capsule S Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/27/2009 09:38 AM Page I Coefficients of Curve I A= 27.2 B= 25. C= 118.42 TO- =164.17 )= 0.OOE+00 Equation is A + B * [Tanh((T-Toy(C+DT))] | |||
Upper Shelf Energr52.2(Fixed) Lower Shelf Energy=2.2(Fixed) | |||
Temp@30 ft-lbs=lT77.5 Deg F Temp@50 ft-lbs=346.5 Deg F Plant: Ginna Material: SAW Heat 61782 Orientation: NA Capsule: S Fluen'e: nra^2 300 250 A200 10 0 | |||
150 w | |||
z 100 0 | |||
50 0n 0 | |||
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential | |||
. 00 6. 00 5. 14 .86 | |||
: 50. 00 8. 00 8. 55 55 100. 00 18. 00 14, 84 3. 16 125.00 14.00 19. 22 -5. 22 150. 00 32. 00 24. 22 7. 78 175.00 25. 00 29. 48 -4.48 200. 00 33. 00 34. 54 -1.54 250.00 43. 00 42.70 . 30 300. 00 45. 00 47. 62 -2.62 WCAP- 17036-NP May 2009 Revision 0 | |||
C-80 Capsule S Weld Heat 61782 Page 2 Plant Ginna Material: SAW Heal: 61792 Orientation: NA Capsule: S Fluence: n/km^2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 350. 00 53. 00 50. 12 2. 88 400. 00 57. 00 51. 29 5. 71 450. 00 63. 00 51. 80 11.20 Correlation Coefficient = .970 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0 | |||
C-81 Capsule N Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/27/2009 09:42 AM Page 1 Coefficients of Curve I A =27.05 R = 24.85 C = 62.8 TO = 174.64 D = 0.00E+00 Equation is A + B * [Tanh((T-To/(C+DT))] | |||
Upper Shelf Energy=51.9(Fixed) Lower Shelf Energy=2.2(Fixed) | |||
Temp@30 ft-lbs=182,2 Deg F Temp@50 ft-lbs=276.0 Deg F Plant Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: N Fluence: n/cmA2 300 250 200 0 | |||
w 100 0 | |||
50 I- I-r 0 | |||
0 | |||
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0, 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperamre Input CVN Computed CVN Diflenential | |||
*00 4. 00 2. 39 1.61 150. 00 22. 00 17,77 4. 23 200-00 26. 00 36. 57 - 10, 57 210. 00 37. 00 39. 73 - 2.73 220. 00 46. 00 42,41 3. 59 230. 00 52.00 44. 62 7. 38 240. 00 52. 00 46. 39 5. 61 260. 00 45. 00 48. 82 -3. 82 280.00 51.00 50. 22 .78 WCAP-17036-NP May 2009 Revision 0 | |||
C-82 Capsule N Weld Heat 61782 Page 2 Plant Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: N Fluence: n/cnrA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 350. 00 50. 00 51.71 -1.71 375. 00 64. 00 51 .82 12. 18 400. 00 49. 00 51. 86 -2.86 Correlation Coefficient = .932 WCAP-17036-NP May 2009 Revision 0 | |||
C-83 Unirradiated Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0310/2009 10:36 PM Page 1 Coefficients of Curve I A= 40.35 B=39.35 C=97.25 TO=-8.12 D=0.00E+O0 Equation is A + B | |||
* tTanh((T-To)l(C+DT)y] | * tTanh((T-To)l(C+DT)y] | ||
Upper Shelf L.E,=79.7 (Fixed) Lower Shelf LE= I.0(Fixed) | Upper Shelf L.E,=79.7 (Fixed) Lower Shelf LE= I.0(Fixed) | ||
Temp. A-E 35 rmil,--21.4 Deg F Plant Ginna Mateiial: | Temp. A-E 35 rmil,--21.4 Deg F Plant Ginna Mateiial: SAW Heat: 61782 Ouientalion: NA Capsule: UNIRR Fluence: anCA2 200 ISO E | ||
SAW Heat: 61782 Ouientalion: | a 1oo 50 0 0.0 | ||
NA Capsule: UNIRR Fluence: anCA2 200 ISO E a 1oo 50 0 0.0-300.0 0.0 300.0 Temperature in Deg F | -300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Tempeatum. Input L.E. Computed LE Differential | ||
-90. 00- | -90. 00 10. 00 13. 32 -3.32 | ||
- | - 90. 00 10.00 13. 32 -3.32 | ||
SAW Heat: 61782 Orientation: | -90. 00 10. 00 13. 32 -3. 32 | ||
NA Capsule: UNIRR Flueno: n/cm^2 Charpy V-Notch Data Ternperutuir | - 65. 00 28. 00 19.64 8. 36 | ||
: 10. 00 | -65. 00 12. 00 19.64 -7.64 | ||
- 65. 00 12.00 1 9.64 -7.64 | |||
= .980 WCAP-17036-NP May 2009 Revision 0 C-85 Capsule V Weld Heat 61782 | - 40. 00 33. 00 27. 89 5.11 | ||
Upper Shelf L.E.=55.2 Lower Shelf L.E.=I.0(Fixed) | - 40. 00 37. 00 27. 89 9.1I | ||
Temp.DLF 35 mils=159.6 Deg F Plant Ginna Material: | - 40. 00 35. 00 27. 89 7. 11 WCAP-17036-NP May 2009 Revision 0 | ||
SAW Heat: 61782 Orientation: | |||
NA Capsule: V Fluence: n/cr^2 0 0 | C-84 Unirradiated Weld Heat 61782 Page 2 Plant: Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: UNIRR Flueno: n/cm^2 Charpy V-Notch Data Ternperutuir Input L.E. Computed L.F- Difterential | ||
: 10. 00 | : 10. 00 51. 00 47. 60 3. 40 | ||
: 10. 00 43. 00 47. 60 -4. 60 10.00 39. 00 47. 60 -8. 60 | |||
SAW Heat: 61782 Orientation: | : 60. 00 57. 00 64. 14 -7. 14 | ||
NA Capsile: V FIuence: nniV'2 Charpy V-Notch Data Input L.E. Computed LE 55. 00 55. 09 Correlation Coefficient | : 60. 00 66. 00 64. 14 1. 86 | ||
=.977 | : 60. 00 68. 00 64. 14 3. 86 110. 00 76. 00 73. 33 2. 67 110. 00 74. 00 73. 33 .67 110. 00 78. 00 73. 33 4. 67 160. 00 75. 00 77. 30 -2. 30 160. 00 76. 00 77. 30 -1.30 160. 00 72. 00 77. 30 -5. 30 210. 00 79. 00 78. 82 .18 210. 00 76. 00 78. 82 -2. 82 210. 00 84. 00 78. 82 5. 18 Correlation Coefficient = .980 WCAP-17036-NP May 2009 Revision 0 | ||
C-85 Capsule V Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0N 11/12009 08:41 AM Pare I Coefficients of Curve I A = 28.08 B = 27.08 C = 110.38 TO = 130.69 D =0.OOE+00 Equation is A + B * [Tanh((T-To)(CA-DT))] | |||
Upper Shelf L.E.=55.2 Lower Shelf L.E.=I.0(Fixed) | |||
Temp.DLF 35 mils=159.6 Deg F Plant Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: V Fluence: n/cr^2 200 I SO jo 5l 100 50 0 | |||
0 | |||
-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Ternrmtuar Input LE. Con*puted LE, Diftexnrial | |||
: 10. 00 9. 00 6. 47 2. 53 | |||
: 40. 00 12.00 9. 77 2. 23 | |||
: 75. 00 17. 00 15. 47 1. 53 125. 00 21.00 26. 68 - 5. 68 125. 00 23. 00 26. 68 -3.68 175. 00 38. 00 38. 40 -. 40 175. 00 46. 00 38. 40 7. 60 210. 00 45. 00 44. 76 . 24 300. 00 51.00 52. 75 - 1.75 WCAP-17036-NP May 2009 Revision 0 | |||
C-86 Capsule V Weld Heat 61.782 Page 2 Plant: Ginna Material: SAW Heat: 61782 Orientation: NA Capsile: V FIuence: nniV'2 Charpy V-Notch Data Temperature. Input L.E. Computed LE Differential 500. 00 55. 00 55. 09 -. 09 Correlation Coefficient =.977 WCAP-17036-NP May 2009 Revision 0 | |||
C-87 Capsule R Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0312712009 09W.30 AM Page 1 Coefficients of Curve I A = 26.7 B = 2.7 C = 83.77 TO = 110.68 D = 0.OE+00 Equation is A + B | |||
* ITanh((T-Toy(C+DT))] | * ITanh((T-Toy(C+DT))] | ||
Upper Shelf L.E.--52.4(Fixed) | Upper Shelf L.E.--52.4(Fixed) Lower Shelf LE.=l.0(Fixed) | ||
Lower Shelf LE.=l.0(Fixed) | Temp.@LE 35 mils= 138.8 Deg F Plant Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: R Fluence: nlc/n2 200 150 | ||
Temp.@LE 35 mils= 138.8 Deg F Plant Ginna Material: | .0 5.100 50 0/9 . | ||
SAW Heat: 61782 Orientation: | 0 | ||
NA Capsule: R Fluence: nlc/n2 0/9 .0-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature | -300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input LP Computed LE. Differential | ||
: 77. 00 | : 77. 00 21. 00 16. 89 4. 11 150.00 34. 00 37. 95 3. 95 150.00 32. 00 37. 95 5. 95 199.00 51.00 46. 84 4. 16 200.00 53. 00 46. 95 6. 05 250.00 54.00 50. 62 3, 38 250.00 51, 00 50. 62 38 300.00 54. 00 51. 85 2. 15 350.00 .52. 00 52. 23 - . 23 I | ||
WCAP-17036-NP May 2009 Revision 0 | |||
SAW Heat: 61782 Orientation: | |||
NA Capsule: R Fluence: n/cm^2 Charpy V-Notch Data Temperature | C-88 Capsule R Weld Heat 61782 Page 2 Plant Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: R Fluence: n/cm^2 Charpy V-Notch Data Temperature Input LE Computed LE. DifferentaI 350. 00 52. 00 52. 23 - .23 Correlation Coifficient = .948 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0 | ||
-.23 Correlation Coifficient | |||
= .948 WCAP-1 7036-NP | C-89 Capsule T Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/27/2009 09:36 AM Page I Coefficients of Curve I A = 24.8 B = 23.8 C = 118.13 TO = 117.06 D = 0.OOE+00 Equation is A + B | ||
* iTanh((T-Toy(C+DT))I Upper Shelf L.E.=48.6(Fixed) | * iTanh((T-Toy(C+DT))I Upper Shelf L.E.=48.6(Fixed) Lower Shelf LE.=l.0(Fixed) | ||
Lower Shelf LE.=l.0(Fixed) | Temp.@LE. 35 mils=171.2 Deg F Plant Ginna Material: SAW Heat 61782 Orientation: NA Capsule: T reco Fluence: n/enP2 200 150 E | ||
Temp.@LE. | 100 0i so 50lo 0 8 0 0 0 0 | ||
35 mils=171.2 Deg F Plant Ginna Material: | 0 | ||
SAW Heat 61782 Orientation: | -300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperamre Input L2. Computed LE. Di-24ia | ||
NA Capsule: T reco Fluence: n/enP2 | . 00 4. 30 6. 77 -2. 47 75.00 14. 20 16,67 - 2. 47 125,00 28. 40 26.40 2. 00 150.00 23. 60 31, 27 -7. 67 210,00 35. 00 40. 43 - 5. 43 250. 00 34. 50 44, 06 -9. 56 300.00 44. 50 46, 54 -2.04 350.00 -38, 20 47. 70 -9. 50 425. 00 52. 00 48. 34 3. 66 May 2009 WCAP- 7036-NP WCAP-117036-NP May 2009 Revision 0 | ||
.00 75.00 | |||
SAW Heat: 61782 Orientation: | C-90 Capsule T Weld Heat 61782 Page 2 Plant Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: T mco Fluence: n/cmA^2 Charpy V-Notch Data Temperature Input LE Computed LE. Differmntial 425. 00 56. 30 48. 34 7. 96 | ||
NA Capsule: T mco Fluence: n/cmA^2 Charpy V-Notch Data Temperature 425. 00 70. 00 150. 00 | : 70. 00 17.50 15.79 1.7 1 150. 00 41.50 31. 27 10.23 210. 00 41. 50 40. 43 1. 07 210. 00 44. 50 40. 43 4. 07 300. 00 50. 00 46. 54 3. 46 350. 00 53. 50 47. 70 5. 80 350. 00 55. 00 47. 70 7. 30 425. 00 53. 00 48. 34 4. 66 Correlation Coefficient = .923 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0 | ||
= .923 WCAP-1 7036-NP | C-91 Capsule S Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0312712009 09:39 AM Page I Coefficients of Curve I A = 27.1 B = 26.1 C = 127.22 TO = 161.94 D = O.OOE+00 Equation is A + B * [Tanh((T-Toy(C+DT))] | ||
Upper Shelf L.E.--53.2(Fixed) | Upper Shelf L.E.--53.2(Fixed) Lower Shelf LE.=1.0(Fixed) | ||
Lower Shelf LE.=1.0(Fixed) | Temp.@LE. 35 mils=201.7 Deg F Plant Ginna Material: SAW Heat 61782 Orientation: NA Capsule: S Fluence: Wcm^2 200 150 a100 0 | ||
Temp.@LE. | 5o 0 0 o 0 | ||
35 mils=201.7 Deg F Plant Ginna Material: | 0 | ||
SAW Heat 61782 Orientation: | -300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperacufe lnpM LE Computed LE. Differential 00 6. 00 4. 80 1. 20 | ||
NA Capsule: S Fluence: Wcm^2 0 0 0 o 0 0-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperacufe | : 50. 00 9.00 8. 66 .34 100.00 18. 00 15.31 2. 69 125. 00 16. 00 19.73 -3.73 150.00 31. 00 24. 66 6. 34 175.00 27. 00 29. 77 -2.77 200. 00 30. 00 34. 68 68 250. 00 44. 00 42. 74 1. 26 300. 00 46. 00 47. 85 -1. 85 WCAP-17036-NP May 2009 Revision 0 | ||
SAW Heat: 61782 Orientation: | C-92 Capsule S Weld Heat 61782 Page 2 Plant: Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: S Fluence: n/cm"2 Charpy V-Notch Data Temperature Input LE Computed LE. Diffential 350. 00 47. 00 50. 62 - 3. 62 400. 00 74. 00 51 . 99 22. 01 450. 00 55. 00 52. 64 2. 36 Correlation Coefficient = .938 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0 | ||
NA Capsule: S Fluence: n/cm"2 Charpy V-Notch Data Temperature | |||
C-93 Capsule N Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/27n2009 09:43 AM Page I Coefficients of Curve I A = 25.5 B = 24.5 C = 88.93 TO = 172.11 D = 0.OOE+0O Equation is A + B * [Tanh((r-Toy(C+DT))] | |||
= .938 WCAP-1 7036-NP | Upper Shelf L.E.=50.0(Fixed) Lower Shelf LE.=1.0(Fixed) | ||
Upper Shelf L.E.=50.0(Fixed) | Temp.@LE. 35 mils=208.5 Deg F Plant Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: N Fluence: n/cmA2 200 150 | ||
Lower Shelf LE.=1.0(Fixed) | , 100 0 | ||
Temp.@LE. | 50 0u- o 0 | ||
35 mils=208.5 Deg F Plant Ginna Material: | n j | ||
SAW Heat: 61782 Orientation: | -300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Tempenribre Input LF. Computed LE. Differential 00 7. 00 2.00 5, 00 150.00 23. 00 19. 53 3. 47 200. 00 25. 00 32. 94 -7. 94 210.00 34. 00 35. 35 -1. 35 220. 00 39. 00 37. 55 1. 45" 230.00 44.00 39. 52 4. 48 240.00 43, 00 41. 25 1. 75 260.00 41.00 44.04 -3.04 280. 00 45. 00 46.02 - . 02 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0 | ||
NA Capsule: N Fluence: n/cmA2 200 150 , 100 50 | |||
SAW Heat: 61782 Orientation: | C-94 Capsule N Weld Heat 61782 Page 2 Plant Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: N Fluence: n/cnlA2 Charpy V-Notch Data TemperUtire Input LE Computed L2. Differential 350. 00 46. 00 49. 12 -3.12 373. 00 85. 00 49. 49 35.51 400. 00 46. 00 49.71 -3. 71 Correlation Coefficient = .806 May 2009 WCAP-l 7036-NP WCAP-17036-NP May 2009 Revision 0 | ||
NA Capsule: N Fluence: n/cnlA2 Charpy V-Notch Data TemperUtire 350. 00 373. 00 | |||
C-95 Unirradiated Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03110/2009 10:44 PM Page I Coefficients ofCurve I A = 50L B = 50. C = 93.94 TO = -25.4 D = 0.00E+00 Equation is A + B * [Tanh((T-ToY(C+DT))] | |||
= .806 WCAP-l 7036-NP | Tempemture at 50% Shear = -25.4 Plant Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: UNIRR Fluence: n ,cm^2 125 100 I-75 C) | ||
Tempemture at 50% Shear = -25.4 Plant Ginna Material: | C) 50 a. | ||
SAW Heat: 61782 Orientation: | 25 | ||
NA Capsule: UNIRR Fluence: n ,cm^2 125 100 I-C)C)a. | -300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Tempemrtur. Input Percent Shear Computed Percent Shear Differential | ||
-90. 00 | - 90. 00 15.00 20. 18 -5. 18 | ||
- | - 90. 00 20. 00 20. 18 -. 18 | ||
NA Capsule: UNIRR Fluence: ncn-t2 Charpy V-Notch Data Temperature | - 90. 00 20. 00 20. 18 -. 18 | ||
: 10. 00 | - 65. 00 40. 00 30. 09 9. 91 | ||
= .980 WCAP-17036-NP May 2009 Revision 0 C-97 Capsule R Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03127n2009 09:31 AM Page I Coefficients of Curve I A = 50. B = 50. C = 55.19 TO = 143.78 D = O.OOE+0O Equation is A + B | -65. 00 35. 00 30. 09 4. 91 | ||
- 65. 00 30.00 30. 09 -. 09 | |||
- 40. 00 40. 00 42. 29 - 2. 29 | |||
-40. 00 40. 00 42. 29 - 2. 29 | |||
- 40. 00 40. 00 42. 29 - 2.29 WCAP-17036-NP May 2009 Revision 0 | |||
C-96 Unirradiated Weld Heat 61782 Page 2 Plant: Ginna Mateial: SAW Heat: 61782 Orientation: NA Capsule: UNIRR Fluence: ncn-t2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Diffirential | |||
: 10. 00 75. 00 68. 00 7. 00 | |||
-3 | |||
: 10. 00 65. 00 68. 00 00 | |||
: 10. 00 60. 00 68. 00 00 | |||
: 60. 00 65. 00 86. 04 21. 04 | |||
: 60. 00 95. 00 86. 04 3. 96 | |||
: 60. 00 95. 00 86. 04 8. 96 110. 00 98. 00 94. 70 39. 30 110. 00 100. 00 94. 70 5. 30 110. 00 98. 00 94. 70 30 160. 00 100. 00 98. 11 1. 89 160. 00 100. 00 98. 11 1. 89 160. 00 100. 00 98. 11 1. 89 210.00 100. 00 99. 34 66 210.00 100. 00 99. 34 66 210.00 100. 00 99. 34 66 Corelation Coefficient = .980 WCAP-17036-NP May 2009 Revision 0 | |||
C-97 Capsule R Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03127n2009 09:31 AM Page I Coefficients of Curve I A = 50. B = 50. C = 55.19 TO = 143.78 D = O.OOE+0O Equation is A + B | |||
* ITanh((T-Toy(C+DT))] | * ITanh((T-Toy(C+DT))] | ||
Temperature at 50% Shear= 143.8 Plant: Ginna Material: | Temperature at 50% Shear= 143.8 Plant: Ginna Material: SAW Heat 61782 Orientation: NA Capsule: R Fuence: n/cn-r2 125 100 0 75 50 25 0 - ----- | ||
SAW Heat 61782 Orientation: | -300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Compued Percent Shear Differential 77.00 30. 00 8. 17 21. 83 150.00 50. 00 55. 61 -5. 61 150.00 45. 00 55. 61 10. 61 199.00 100. 00 88. 09 21.91 200.00 99. 00 88. 47 10. 53 250. 00 99. 00 97.92 1. 08 250.00 99. 00 97.92 1.08 300.00 100. 00 99. 65 35 350.00 100. 00 99.94 .06 WCAP-17036-NP May 2009 Revision 0 | ||
NA Capsule: R Fuence: n/cn-r2 125 100 0 75 50 25 0 -------300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature 77.00 | |||
C-98 Capsule R Weld Heat 61782 Page 2 Plant: Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: R Fluence: ncrnm^2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 350. 00 100. 00 99. 94 .06 Correlation Coefficient = .952 WCAP-1 7036-NP May 2009 Revision 0 | |||
SAW Heat: 61782 Orientation: | |||
NA Capsule: R Fluence: ncrnm^2 Charpy V-Notch Data Temperature 350. 00 | C-99 Capsule T Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/27/2009 09:37 AM Page I Coefficients of Curve I A =50. B =50. C= 107.93 TO = 106.47 D = 0.OOE+0O Equation is A + B * [Tanh((T-Toy(C+DT))] | ||
.06 Correlation Coefficient | Temperature at 50% Shear= 106.5 Plant: Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: T reco Fluence: nIcmA2 125 100 (I 75 S | ||
= .952 WCAP-1 7036-NP May 2009 Revision 0 C-99 Capsule T Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/27/2009 09:37 AM Page I Coefficients of Curve I A =50. B =50. C= 107.93 TO = 106.47 D = 0.OOE+0O Equation is A + B * [Tanh((T-Toy(C+DT))] | U, 50 0~ | ||
Temperature at 50% Shear= 106.5 Plant: Ginna Material: | 25 0o- | ||
SAW Heat: 61782 Orientation: | -300.0 0.0 100.0 200.0 300.0 Temperature in Deg F Charpy V-Notch Data Tlmperattie Input Percent Shear Computed Percent Shear Differential 00 13. 00 12. 21 .79 | ||
NA Capsule: T reco Fluence: nIcmA2 (I S U, 0~ | : 75. 00 38. 00 35. 82 2. 18 125. 00 54. 00 58. 50 -4,50 150. 00 73. 00 69. 14 3. 86 210.00 90. 00 87. 20 2. 80 250. 00 98. 00 93. 46 4. 54 300. 00 100. 00 97. 30 2. 70 350. 00 100. 00 98. 91 I. 09 425. 00 100, 00 99. 73 ,27 WCAP-17036-NP May 2009 Revision 0 | ||
. | |||
SAW -lHeat: 61782 Orientation: | C-100 Capsule T Weld Heat 61782 Page. 2 Plant: Ginna Material: SAW -lHeat: | ||
NA Capsule: T reco Fluence: n/cm^2 Charpy V-Notch Data Temperature 425. 00 | 61782 Orientation: NA Capsule: T reco Fluence: n/cm^2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 425. 00 100.00 99. 73 .27 | ||
. | : 70. 00 35. 00 33. 72 1.28 150. 00 65. 00 69. 14 -4. 14 210.00 80. 00 87. 20 -7. 20 210. 00 90. 00 87 20 2. 80 300. 00 100.00 97. 30 2. 70 350.00 100.00 98. 91 1.09 350.00 100. 00 98. 91 1. 09 425. 00 100. 00 99. 73 .27 Correlation Coefficent .994 WCAP-17036-NP May 2009 Revision 0 | ||
.27 | |||
Temperature. | C-101 Capsule S Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/2712009 09:40 AM Page I Coefficients of Curve I A = 50. B = 50. C = 83.42 TO = 154.13 D = 0.OOE+0O Equation is A + B * [Tanh((T-Toy(C+DT))] | ||
at 50% Shear= 154.2 Plant: Ginna Material: | Temperature. at 50% Shear= 154.2 Plant: Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: S Fluence: rtcmA2 125 100 (U 75 U) 50 25 0 -.- -.- 1- | ||
SAW Heat: 61782 Orientation: | -300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential | ||
NA Capsule: S Fluence: rtcmA2 125 100 (U U) | .00 5. 00 2. 42 2. 58 50.00 15.00 7.61 7. 39 100.00 30. 00 21.45 8. 55 125.00 25. 00 33. 22 -8. 22 150.00 50. 00 47.53 2. 47 175.00 45,00 62. 26 -137.26 200.00 90.00 75. 02 14. 98 250.00 95.00 90. 88 4. 12 300.00 S00. 00 97.06 2. 94 WCAP-17036-NP May 2009 Revision 0 | ||
.00 | |||
C-102 Capsule S Weld Heat 61782 Page 2 Plant: Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: S -Yluence: n/cm^2 Charpy VI-Notch Data Temperature Input Percent Shkar Computed Percent Stear Differential 350. 00 t00.00 99.10 .90 400. 00 100. 00 99.73 | |||
SAW Heat: 61782 Orientation: | * 27 450. 00 too. 00 99. 92 .08 Correlation Coefficient =.977 May 2009 WCAP- 17036-NP WCAP-17036-NP May 2009 Revision 0 | ||
NA Capsule: S -Yluence: | |||
n/cm^2 Charpy VI-Notch Data Temperature 350. 00 | C-103 Capsule N Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03127P/009 09:43 AM Page I Coefficients of Curve I A = 50. B = 50. C = 61.4 TO = 171.48 D = 0.00E+00 Equation is A + B *[Tanh((T-ToY(C+DT))j Temperature at 50% Shear= 171.5 Plant: Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: N Fluence: n/cmA2 125 100 (I 75 50 25 0 - i + - - i - | ||
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temprapfeno ntput Percent Shear Computed Pereet Shear Differential | |||
. | .00 5. 00 .37 4. 63 350. 00 40. 00 33. 19 6. 81 200.00 50. 00 71. 69 -21. 69 210.00 80. 00 77. 81 2. 19 220.00 90.00 82. 93 7. 07 230.00 95.00 87. 06 7.94 240.00 95.00 90. 31 4. 69 260. 00 98. 00 94,70 3. 30 280.00 98. 00 97. 17 .83 WCAP-17036-NP May 2009 Revision 0 | ||
SAW Heat: 61782 Orientation: | |||
NA Capsule: N Fluence: n/cmA2 125 100 (I 75 50 25 0 -i + -i - | C-104 Capsule N Weld Heat 61782 Page 2 Plant: Ginna Material: SAW Heat: 61782 Orientation: NA Capsule.: N Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Skiar Computed Percent Shear Differential 350.00 100.00 99. 70 30 375. 00 100. 00 99. 87 .13 400. 00 100. 00 99. 94 06 Correlation Ccefficient = .968 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0 | ||
.00 | |||
C-105 Unirradiated Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03127/2009 09:21 AM Page 1 Coefficients of Curve I A = 46.1 B = 43.9 C = 102.49 TO = -753 D = 0.OOE+0O Equation is A + B * [Tanh((T-Toy(C+DT))] | |||
SAW Heat: 61782 Orientation: | Upper Shelf Energy=90.0(Fixed) Lower Shelf Energy=2.2(Fixed) | ||
NA Capsule.: | Temp@30 ft-lbs=-64.7 Deg F Temp@50 ft-lbs=- 16.1 Deg F Plant GINNA Material: SAW Heat: 125P666 Orientation: NA Capsule: UNIRR Fluence: n/eni2 300 250 200 0 | ||
N Fluence: n/cmA2 Charpy V-Notch Data Temperature 350.00 | 150 z | ||
= .968 WCAP-1 7036-NP | 100 0 50 0 0 0 | ||
Upper Shelf Energy=90.0(Fixed) | -300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temlperature Input CVN Computed CVN Differential | ||
Lower Shelf Energy=2.2(Fixed) | -90. 00 14. 50 21.56 - 7. 06 | ||
Temp@30 ft-lbs=-64.7 Deg F Temp@50 ft-lbs=- 16.1 Deg F Plant GINNA Material: | -90. 00 42. 00 21. 56 20. 44 | ||
SAW Heat: 125P666 Orientation: | -90,00 I1. 50 21.56 - 10.06 | ||
NA Capsule: UNIRR Fluence: n/eni2 0 0 0 0-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 | -65.00 26. 50 29. 90 -3. 40 | ||
-90. 00- | - 65. 00 16. 50 29. 90 -13. 40 | ||
- | -65. 00 20. 00 29. 90 -9. 90 | ||
SAW Heat: 125P666 Orientation: | -40. 00 40. 00 39. 85 .15 | ||
NA Capsule: UNIRR Fluence: nrcm^2 Charpy V-Notch Data Temperature | -40.00 58. 00 39. 85 18. 15 | ||
: 10. 00 | -40.00 51. 50 39. 85 11. 65 WCAP-17036-NP May 2009 Revision 0 | ||
= .826 WCAP-17036-NP May 2009 Revision 0 C-107 Capsule V Heat Affected Zone | C-106 Unirradiated Heat Affected Zone Page 2 Plant: GhNNA Material: SAW Heat: 125P666 Orientation: NA Capsule: UNIRR Fluence: nrcm^2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential | ||
Upper Shelf Energy= 135.0 Lower Shelf Energy=2.2(Fixed) | : 10. 00 90. 00 60. 65 29. 35 10.00 36. 50 60. 65 24. 15 I0. 00 51. 50 60. 65 -9. 15 | ||
Temp@30 ft-lbs=-34.0 Deg F Temp@50ftI-lbs=30.5 DegF Plant: Ginna Material SAW Heat: 1251P666 Orientation: | : 60. 00 56. 00 76.03 20. 03 | ||
NA Capsule: V Fluence: rtcm^2 0 0 0-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Tornpemrtum. | : 60. 00 53. 00 76. 03 - 23. 03 | ||
-50. | : 60. 00 101. 50 76.03 25. 47 110.00 94. 50 84. 15 10. 35 110. 00 98. 00 84. 15 13.85 110. 00 77. 50 84.15 - 6. 65 Correlation Coefficient = .826 WCAP-17036-NP May 2009 Revision 0 | ||
- | |||
SAW Heat 125P666 Orientation: | C-107 Capsule V Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02111/2009 12:40 PM Page I Coefficients of Curve I A= 68.6 B= 66.4 C= 171.32 TO= 79.76 D= O.OOE+00 Equation is A + B * [Tanh((T-ToY(C+-DT))] | ||
NA Capsule: V Fluenoe: a/cmrn2 Charpy V-Notch Data Tcmperatu[e 500. 00 | Upper Shelf Energy= 135.0 Lower Shelf Energy=2.2(Fixed) | ||
-2. 03 Correlation Coefficient | Temp@30 ft-lbs=-34.0 Deg F Temp@50ftI-lbs=30.5 DegF Plant: Ginna Material SAW Heat: 1251P666 Orientation: NA Capsule: V Fluence: rtcm^2 300 250 | ||
=. 915 WCAP-17036-NP May 2009 Revision 0 C-109 Capsule R Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02/11/2009 12:45 PM Page I Coefficients of Curve I A=42.5 B=40.3C=20.12 TO=.29 D=O0.00E+00 Equation is A + B * [Tanlh((T-Toy(C+DT))] | " 200 0 | ||
Upper Shelf Energy=8Z 8(Fixed) Lower Shelf Energ-y2.2(Fixed) | 150 z | ||
Tlmp@30 ft-lbs--6.1 Deg F Temp@5O ft-bs=4.1 Deg F Plant: Ginna Material: | 100 0 | ||
SAW Heat: 125P666 Orientation: | 50 0 | ||
NA Capsule: R Fluence: n/cnrP2 300 | 0 0 | ||
-50. 00.00 | -300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Tornpemrtum. Input CVN Computed CVN Diffrrential | ||
-50. 00 10. 50 26. 13 -1 5. 63 | |||
SAW Heat: 125P666 Orientation: | - 15. 00 33. 00 35. 21 -2. 21 | ||
NA Capsule: R Fluence: nkem^2 Charpy V-Notch Data Input CVN Computed CVN 65. 00 82. 80 Correlation Coefficient | : 10. 00 50. 50 42. 96 7. 54 | ||
=.666 | : 10. 00 61.00 42. 96 18. 04 | ||
: 40. 00 57. 50 53. 46 4. 04 | |||
Upper Shelf Energy= 117.7 (Fixed) Lower Shelf Energy=2.2(Fixed) | : 75. 00 36. 00 66. 76 - 30. 76 | ||
Temp@30 ft-lbs=-23.7 DeI F Temp@50ft-lbs=14.1 DegF Plant: Ginna Material SAW Heat: 125P666 Orientation: | : 75. 00 86. 30 66. 76 19. 54 125. 00 76. 50 85. 74 -9.24 210. 00 1 20. 00 111. 18 8. 82 WCAP-17036-NP May 2009 Revision 0 | ||
NA Capsule: T Fluence: nknvr2 300 250 200 0 F | |||
C-108 Capsule V Heat Affected Zone Pap 2 Plant Ginna Material: SAW Heat 125P666 Orientation: NA Capsule: V Fluenoe: a/cmrn2 Charpy V-Notch Data Tcmperatu[e Input CVN Computed CN Differential 500. 00 132. 00 134. 03 - 2. 03 Correlation Coefficient =. 915 WCAP-17036-NP May 2009 Revision 0 | |||
=.830 WCAP-17036-NP May 2009 Revision 0 C-112 Capsule S Heat Affected Zone | |||
Upper Shelf Energy= 103.5(Fixed) | C-109 Capsule R Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02/11/2009 12:45 PM Page I Coefficients of Curve I A=42.5 B=40.3C=20.12 TO=.29 D=O0.00E+00 Equation is A + B * [Tanlh((T-Toy(C+DT))] | ||
Lower Shelf Energy=2.2 (Fixed)Temp@30 ft-lbs=-25.8 DEq F Ternp@50 ft-lbs=31.4 Deg F Plant: Ginna Material: | Upper Shelf Energy=8Z 8(Fixed) Lower Shelf Energ-y2.2(Fixed) | ||
SAW Heat: 125P666 Orientation: | Tlmp@30 ft-lbs--6.1 Deg F Temp@5O ft-bs=4.1 Deg F Plant: Ginna Material: SAW Heat: 125P666 Orientation: NA Capsule: R Fluence: n/cnrP2 300 200 IT tlS L. 150 | ||
NA Capsule: S Fluence: ,1?cm^2 0 0 0 00 0-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 | ,2 0 | ||
100 0 | |||
SAW Heat: 125P666 Orientation: | 10 so 4 - 4 - 4- - - - - - - 4 - | ||
NA Capsule: S Fluence: nIcnm^2 Charpy V-Notch Data Input CVN Computed CVN 43. 00 87. 46 | -300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Cha-py V-Notch Data Tern-ermtume Input CVN Computed CVN Diffe.rcmiz | ||
=.636 | -50. 00 6.00 2. 74 3. 26 | ||
.00 44. 00 41.91 2. 09 | |||
Upper Shelf Energy=88.3(Fixed) | : 25. 00 55. 50 76. 43 -20. 93 | ||
Lower Shelf EnergD--2.2(Fixed) | : 40. 00 134.00 81. 27 52.73 | ||
Temp@30 ft-lb:s--43.0 Deg F Temp@50 ft-lbs=5 8.4 Deg F Plant: Ginna Material: | : 77. 00 84. 50 82. 76 1.74 110. 00 39. 00 82. 80 -43. 80 150. 00 81. 50 82. 80 - 1. 30 199.00 55. 50 82. 80 -27. 30 250. 00 78. 00 82. 80 -4. 80 WCAP-17036-NP May 2009 Revision 0 | ||
SAW Heat: 125P666 Orientation: | |||
NA Capsule: N Fluence: r'cnV'2 300 250 200 0 50-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Trmpmatunn. | C-110 Capsule R Heat Affected Zone Page 2 Plant: Ginna Material: SAW Heat: 125P666 Orientation: NA Capsule: R Fluence: nkem^2 Charpy V-Notch Data Tempenmturr Input CVN Computed CVN Differential 300. 00 65. 00 82. 80 -17. 80 Correlation Coefficient =.666 WCAP-17036-NP May 2009 Revision 0 | ||
.00 | |||
C-111 Capsule T Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0211/2009 12:51 PM Page 1 Coefficients of Curve 1 A=59.95 B=57.75C.=94.46 T0= 30.53 D= 000E+00 Equation is A + B * [Tanh((T-ToY(C+DT))] | |||
SAW Heat: 125P666 Orientation: | Upper Shelf Energy= 117.7 (Fixed) Lower Shelf Energy=2.2(Fixed) | ||
NA Capsule: N Fluence: nlcmaA2 Charpy V-Notch Data Termpetur 360. 00 | Temp@30 ft-lbs=-23.7 DeI F Temp@50ft-lbs=14.1 DegF Plant: Ginna Material SAW Heat: 125P666 Orientation: NA Capsule: T Fluence: nknvr2 300 250 200 0 | ||
F I1U 0 | |||
=.860 WCAP- 17036-NP | 0 z 0 1000 00 50 0 | ||
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temrnpertum. Input CV N Computed CVN Differential | |||
-1oo 00 4. 00 9. 05 -5. 05 | |||
-60. 00 13. 50 17. 01 -3.51 | |||
-50. 00 66. 00 19.96 46. 04 | |||
.00 24. 50 41. 91 -17.41 | |||
: 50. 00 33. 50 71. 69 -38. 19 | |||
: 75. 00 116. 50 85. 29 31. 21 150. 00 128. 00 109, 17 18. 83 250. 00 139. 00 116. 60 22. 40 350. 00 86. 00 117. 57 -31, 57 Ca*ri aon Ccefficeint =.830 WCAP-17036-NP May 2009 Revision 0 | |||
C-112 Capsule S Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02'16/2009 07:53 AM Page I Coefficients of Curve I A = 52.85 B = 50.65 C = 133.03 T0 = 38.86 i) = O.OOE+00 Equation is A + B * [Tanh((T-ToY(C+DT))] | |||
Upper Shelf Energy= 103.5(Fixed) Lower Shelf Energy=2.2 (Fixed) | |||
Temp@30 ft-lbs=-25.8 DEq F Ternp@50 ft-lbs=31.4 Deg F Plant: Ginna Material: SAW Heat: 125P666 Orientation: NA Capsule: S Fluence: ,1?cm^2 300 250 d 200 0 | |||
LL 150 0 | |||
w z | |||
> 100 o | |||
50 0 | |||
0 00 0 | |||
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Tem ,rnetuur. Input CVN Computed CVN Differential | |||
-50. 00 6. 00 23. 29 -17.29 | |||
-25. 00 7. 00 30. 25 23. 25 | |||
- 25. 00 37. 00 30. 25 6.75 | |||
.00 25. 00 38. 46 -13.46 | |||
: 25. 00 12. 00 47. 59 -35. 59 | |||
: 25. 00 102. 00 47. 59 54. 41 50.00 56. 00 57. 0O -1. 08 | |||
: 50. 00 105. 00 57. 08 47. 92 100. 00 68. 00 74. 62 -6.62 WCAP-17036-NP May 2009 Revision 0 | |||
C-113 Capsule S Heat Affected Zone Page 2 Plant: Ginna Material: SAW Heat: 125P666 Orientation: NA Capsule: S Fluence: nIcnm^2 Charpy V-Notch Data Ternpewrntie Input CVN Computed CVN Differential 150. 00 43. 00 87. 46 -44. 46 200. 00 70. 00 95. 25 - 25. 25 225. 00 137.00 97.68 39. 32 Correlation Coefficient =.636 WCAP-17036-NP May 2009 Revision 0 | |||
C-114 Capsule N Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0-V0612009 09:28 AM Page I Coefficients of Curve I A = 45.22 B = 43.03 C = 32. '0 54.78 D = 0.00E+00 Equation is A + B * [Tanh((T-ToY(C+DT))] | |||
Upper Shelf Energy=88.3(Fixed) Lower Shelf EnergD--2.2(Fixed) | |||
Temp@30 ft-lb:s--43.0 Deg F Temp@50 ft-lbs=5 8.4 Deg F Plant: Ginna Material: SAW Heat: 125P666 Orientation: NA Capsule: N Fluence: r'cnV'2 300 250 200 0 | |||
50 | |||
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Trmpmatunn. Input CVN Computed CVN Differential | |||
.00 8. 00 4. 92 3. 08 | |||
: 35. 00 24. 00 21.57 2.43 | |||
: 40. 00 34. 00 26. 66 7. 34 | |||
: 50. 00 15.00 38. 85 - 23. 85 | |||
: 55. 00 39. 00 45. 52 -7.52 | |||
: 60. 00 80. 00 52. 18 27. 82 | |||
: 80. 00 66. 00 73.51 -7. 51 130. 00 87. 00 87. 48 - . 48 350. 00 1 24. 00 88. 25 35. 75 WCAP-17036-NP May 2009 Revision 0 | |||
C-115 Capsule N Heat Affected Zone PaW 2 Plant: Ginna Material: SAW Heat: 125P666 Orientation: NA Capsule: N Fluence: nlcmaA2 Charpy V-Notch Data Termpetur Input CVN Computed C*YN Diffrntial 360. 00 67.00 88. 25 -21. 25 375. 00 90. 00 88. 25 1.75 390. 00 72.00 88. 25 -16. 25 Conhlation Coefficient =.860 May 2009 WCAP- 17036-NP WCAP- May 2009 Revision 0 | |||
C-116 Unirradiated Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/27P2009 09:23 AM Page I Coefficients of Curve I A = 38.5 B = 37.5 C = 105.67 To = -21.83 1) = O.OOE+00 Equation is A + B | |||
* iTanh((T-ToY(C+DlT))] | * iTanh((T-ToY(C+DlT))] | ||
Upper Shelf L.E.=76.0(Fixed) | Upper Shelf L.E.=76.0(Fixed) Lower Shelf L.E.= 1.0(Fixed) | ||
Lower Shelf L.E.= 1.0(Fixed) | Terp.@L.E. 35 mils=-31.7 Deg F Plant GINNA Material: SAW Heat: 125P666 Orientation: NA Capsule: UNIRR Fluence: nfcm^2 200 150 C | ||
Terp.@L.E. | a100 50 50 0 4- | ||
35 mils=-31.7 Deg F Plant GINNA Material: | -300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Tem1pemre Input LE Computed LE. Diffeiential | ||
SAW Heat: 125P666 Orientation: | -90. 00 10. 00 17. 19 .7. 19 | ||
NA Capsule: UNIRR Fluence: nfcm^2 200 150 C a100 50 50 0 4--300.0 0.0 300.0 Temperature in Deg F Charpy V-Notch Data | -90. 00 34. 00 17. 19 16. 81 | ||
. | -90. 00 12. 00 17. 19 -5.19 | ||
SAW Heat: 125P666 Orientation: | -65. 00 24. 00 23. 98 - 02 | ||
NA Capsule: JNIRR Fluence: nrcm^2 Charpy V-Notch Data Temperature | : 65. 00 14. 00 23. 98 -9.98 | ||
: 10. 00 | : 65. 00 2 1. 00 23, 98 - 2. 98 | ||
= .895 WCAP-1 7036-NP May 2009 Revision 0 C-118 Capsule V Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02 113/2009 t2:41 PM Page I Coefficients ofCurve I A = 45.79 B = 44.79 C =225.29 T0 = 51.04- = 0.00E+00 Equation is A + B | -40.00 33. 00 32, 12 .88 | ||
- 40. 00 43. 00 32. 12 10. 88 | |||
-40. 00 33. 00 32. 12 .88 WCAP-17036-NP May 2009 Revision 0 | |||
C-117 Unirradiated Heat Affected Zone Page 2 Plant: GINNA Material: SAW Heat: 125P666 Orientation: NA Capsule: JNIRR Fluence: nrcm^2 Charpy V-Notch Data Temperature Input L . Computed LF. Differential | |||
: 10. 00 62. 00 49. 47 12.53 10.00 33. 00 49. 47 - 16. 47 | |||
: 10. 00 52. 00 49. 47 2. 53 | |||
: 60. 00 5 1. 00 62. 86 - 11. 86 | |||
: 60. 00 46. 00 62. 86 16.86 | |||
: 60. 00 78. 00 62. 86 15, 14 110. 00 80. 00 70. 29 9. 71 110. 00 78. 00 70. 29 7.71 110. 00 70. 00 70. 29 -. 29 Correlation Coefficient = .895 WCAP-1 7036-NP May 2009 Revision 0 | |||
C-118 Capsule V Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02 113/2009 t2:41 PM Page I Coefficients ofCurve I A = 45.79 B = 44.79 C =225.29 T0 = 51.04- = 0.00E+00 Equation is A + B | |||
* ITanh((T-To)(C+DT))] | * ITanh((T-To)(C+DT))] | ||
Upper Shelf L.E.=90.6 Lower Shelf L.E.=1.O(Fixed) | Upper Shelf L.E.=90.6 Lower Shelf L.E.=1.O(Fixed) | ||
Tenip.@L.E. | Tenip.@L.E. 35 mi1---4.3 Deg F Plant: Ginna Material: SAW Heat 125P666 Orientation: NA Capsule: V Fluence: n1cum^2 200 150 E | ||
35 mi1---4.3 Deg F Plant: Ginna Material: | C 100 50 0 ' | ||
SAW Heat 125P666 Orientation: | -300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Coni*uted LE Difkemntial | ||
NA Capsule: V Fluence: | -50. 00 9. 00 26. 95 -17. 95 | ||
-50. 00 | -15.00 52. 00 33. 02 is. 98 10.00 35. 00 37. 72 -2. 72 | ||
: 10. 00 53. 00 37. 72 1 5. 28 | |||
SAW Heat: 125P666 Orientation: | : 40. 00 46. 00 43. 59 2.41 | ||
NA Capsule: V Fluence: ncnimA2 Charpy V-Notch Data Tempemture. | : 75. 00 27. 00 50. 53 - 23, 53 | ||
: 75. 00 63. 00 50. 53 12. 47 125. 00 40. 00 59. 98 -19. 98 210. 00 92. 00 73. 01 1i . 99 WCAP-17036-NP May 2009 Revision 0 | |||
= .760 WCAP-17036-NP May 2009 Revision 0 C-120 Capsule R Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02f 1112009 12:46 PM Pape I Coefficients ofCurvee I A = 34.1 B = 33. C = 23.99 TO = 3.62 D = 0.00E+00 Equation is A + B * [Tanb((T-To)/(C+DT))] | |||
Upper Shelf L.E.=67.2 (Fixed) Lower Shelf LE.= 1.0(Fixed) | C-119 Capsule V Heat Affected Zone Page 2 Plant: Ginna Material: SAW Heat: 125P666 Orientation: NA Capsule: V Fluence: ncnimA2 Charpy V-Notch Data Tempemture. Input L.E. Computed LE DiffeIrerfinj 500. 00 85. 00 88. 94 3 . 94 Corlation Coefficient = .760 WCAP-17036-NP May 2009 Revision 0 | ||
Teimp. @LE. 35 mils=4.3 Deg F Plant: Ginna Material SAW Heat 125P666 Orientation: | |||
NA Capsule: R Fluence: n/crn2 200 1S0 E C 2.100 5l | C-120 Capsule R Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02f 1112009 12:46 PM Pape I Coefficients ofCurvee I A = 34.1 B = 33. C = 23.99 TO = 3.62 D = 0.00E+00 Equation is A + B * [Tanb((T-To)/(C+DT))] | ||
-50.00.00 25. 00 | Upper Shelf L.E.=67.2 (Fixed) Lower Shelf LE.= 1.0(Fixed) | ||
Teimp. @LE. 35 mils=4.3 Deg F Plant: Ginna Material SAW Heat 125P666 Orientation: NA Capsule: R Fluence: n/crn2 200 1S0 E | |||
SAW Heat: 125P666 Oiientation: | C 2.100 5l 0 0 0 50 Y0 Od0 n1 | ||
NA Capsule: R Fluence: nictr^2 Charpy V-Notch Data Termpemtuie. | -300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Ternpemratuit Input L.E. Computed LE Differential | ||
-50.00 7. 00 1. 75 5. 25 | |||
.00 31. 00 29. 15 1. 85 | |||
= .777 WCAP-1 7036-NP | : 25. 00 45. 00 57.67 -1 2. 67 | ||
Upper Shelf L.E.=61.4(Fixed) | : 40. 00 88. 00 64. 16 23. 84 | ||
Lower Shelf L.E.= I.0(Fixed) | : 77. 00 71.00 67.05 3. 95 110. 00 35. 00 67. 19 -32. 19 150. 00 59. 00 67. 20 -8. 20 199. 00 69. 00 67. 20 1. 80 250. 00 72. 00 67. 20 4. 80 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0 | ||
Temp. OLE. 35 mils=18.2 Deg F Plant: Ginna Material: | |||
SAW Heat: 125P666 Orientation: | C-121 Capsule R Heat Affected Zone Page 2 Plant: Ginna Material: SAW Heat: 125P666 Oiientation: NA Capsule: R Fluence: nictr^2 Charpy V-Notch Data Termpemtuie. Input L.E. Computed LE. Differntial | ||
NA Capsule: T Fluence: nlnrrP2 0 00 | '400. 00 48. 00 67. 20 - 19. 20 Cormlaftion Coefficient = .777 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0 | ||
-100.- | |||
C-122 Capsule 1T Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02111/2009 12:52 PM Page 1 Coefficients ofCurve I A = 31.2 B = 30.2 C = 121.03 TO = 2.82 I = 0.001+00 Equation is A + B * [Tanh((T-To)/(C+DT))] | |||
Upper Shelf L.E.=61.4(Fixed) Lower Shelf L.E.= I.0(Fixed) | |||
Upper Shelf L.E.=64.5(Fixed) | Temp. OLE. 35 mils=18.2 Deg F Plant: Ginna Material: SAW Heat: 125P666 Orientation: NA Capsule: T Fluence: nlnrrP2 200 150 E | ||
Lower Shelf LE= I.0(Fixed) | a 100 so 0 | ||
Temp.@LE. | In 0 | ||
35 mils=17.5 Deg F Plant: Ginna Materiat SAW Heat: 125P666 Orientation: | 00 | ||
NA Capsule: S Fluence: n/cmA2 200 150 E C. | -3 00.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperatur. Input LE. Computed LE Diffemrnial | ||
- | -100. 00 4. 70 10.34 - 5. 64 | ||
-60. 00 6. 30 16.80 -10.50 | |||
-50. 00 41.70 18.80 22. 90 00 28. 00 30. 50 - 2. 50 | |||
: 50. 00 27. 60 42. 41 -14. 81 | |||
: 75. 00 53. 90 47. 34 6. 56 150. 00 62. 20 56. 52 5. 68 250. 00 77. 60 60. 40 17.20 350. 00 44. 50 61. 21 -16. 71 Circlation Coefficient =. 823 WCAP- 17036-NP May 2009 Revision 0 | |||
C-123 Capsule S Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02116(2009 07:54 AM Page I Coefficients of Curve I A=32.75 B=31.75C=61.39 T0 = 13.12 D=0.OOE+00 Equation is A + B * [Tanh((T-To)/(C÷-DT))] | |||
Upper Shelf L.E.=64.5(Fixed) Lower Shelf LE= I.0(Fixed) | |||
Temp.@LE. 35 mils=17.5 Deg F Plant: Ginna Materiat SAW Heat: 125P666 Orientation: NA Capsule: S Fluence: n/cmA2 200 150 ~1 I E | |||
C | |||
_ on | |||
.210 5l 0 0 | |||
0 '6 50 0 | |||
/0 0 0 | |||
0 ni. | |||
-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data T¢mperatum. Input L.E. Computed LE Diftimntial | |||
-50. 00 6. 00 8. 20 - 2. 20 | |||
-25. 00 12.00 15. 23 -3. 23 | |||
- 25. 00 22. 00 15. 23 6. 77 | |||
.00 22. 00 26. 07 -4. 07 | |||
: 25. 00 14.00 38. 82 -24. 82 | |||
: 25. 00 61.00 38. 82 22. 18 | |||
: 50. 00 36. 00 49. 82 -13. 82 | |||
: 50. 00 73. 00 49. 82 23. 18 100. 00 59. 00 60. 96 - 1. 96 WCAP-17036-NP May 2009 Revision 0 | |||
C-124 Capsule S Heat Affected Zone Page 2 Plant: Ginna Material: SAW Heat: 125P666 Orientation: NA Caipulle: S Fluence: n/ccm^2 Charpy V-Notch Data Temperature Input L.E. Computed LE Differential 150. 00 35. 00 63. 77 - 28. 77 200. 00 47. 00 64. 36 -17. 36 225. 00 82. 00 64. 44 17. 56 Correlation Ccefficient = .733 WCAP-1 7036-NP May 2009 Revision 0 | |||
C-125 Capsule N Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03V06/2009 09:29 AM Page 1 Coefficients of Curve I A=30. B =29. C=34.18 TO=50-52 D=0.OOE+00 Equation is A + B | |||
* ITanh((T-To)y(C+DT))] | * ITanh((T-To)y(C+DT))] | ||
Upper Shelf L.E.=59.0(Fixed) Lower Shelf L.E= 1.0(Fixed) | |||
Tbmp. @LE.. 35 mils=56.5 Deg F Plant: Ginna Material: SAW Heat: 125P666 Orientation: NA Capsule: N Fluence: n/ciuA2 200 ISO 0 | |||
50 o In 00 0 | |||
-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Tcrnp'irturr. Input L.E. Computed LE Diffejmntial | |||
.00 8. 00 .3. 87 4. 1 | |||
: 35. 00 19.00 17. 67 1. 33 | |||
: 40. 00 25. 00 21.34 3. 66 50.00 14.00 29. 56 -15. 56 55.00 ,3. 00 33. 78 -. 78 | |||
: 60. 00 51.00 37. 84 13. 16 | |||
: 80. 00 48. 00 50. 23 -2. 23 130. 00 60. 00 58. 45 1. 55 350. 00 64. 00 59. 00 5. 00 WCAP-17036-NP May 2009 Revision 0 | |||
C-126 Capsule N Heat Affected Zone Page 2 Plant: Ginna Material: SAW Heat: 125P666 Orientation: NA Capsule: N Floence: nicnm^2 Charpy V-Notch Data Tempcrmture Input L.E. Computed LF. Differential 360. 00 50. 00 59. 00 -9. 00 375. 00 52. 00 59. 00 -7.00 390. 00 70. 00 59. 00 11.00 Cormlation Co.fficien =. 920 WCAP- 17036-NP May 2009 Revision 0 | |||
C-127 Unirradiated | |||
Latest revision as of 11:52, 12 March 2020
| ML091550271 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/31/2009 |
| From: | Burgos B, Hardin T, Rosier B, Wang S ATI Consulting, Westinghouse |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| WCAP-17036-NP, Rev 0 | |
| Download: ML091550271 (285) | |
Text
Westinghouse Non-Proprietary Class 3 WCAP-17036-NP May 200!9 Revision 0 Analysis of Capsule N from the R. E. Ginna Reactor Vessel Radiation Surveillance Program Westinghouse
WESTINGHOUSE NON-PROPRIETARY CLASS 3 WCAP-17036-NP Revision 0 Analysis of Capsule N from the R. E. Ginna Reactor Vessel Radiation Surveillance Program B. A. Rosier*
T. Hardin, ATI Consulting B. N. Burgos S. S. Wang May 2009 Reviewer: C. C. Heinecke*
Primary Component Asset Management Approved: P. C. Paesano*, Manager Primary Component Asset Management
- Electronically Approved Records Are Authenticated in the Electronic Document Management System.
Westinghouse Electric Company LLC P.O. Box 355 Pittsburgh, PA 15230-0355
© 2009 Westinghouse Electric Company LLC All Rights Reserved
TABLE OF CONTENTS L IS T OF TA B L ES ....................................................................................................................................... iv L IS T OF F IGU RE S ..................................................................................................................................... vi EX EC U TIV E SU M M A R Y ........................................................................................................................ viii 1 SU M M A RY O F R E SU LT S .......................................................................................................... 1-1 2 IN TR O D U C TIO N ........................................................................................................................ 2-1 3 B A CK G RO U N D .......................................................................................................................... 3-1 4 DESCRIPTIO N O F PRO G RAM .................................................................................................. 4-1 5 TESTING OF SPECIMENS FROM CAPSULE N ...................................................................... 5-1 5 .1 O V ERV IE W .................................................................................................................... 5-1 5.2 CHARPY V-NOTCH IMPACT TEST RESULTS ........................................................... 5-3 5.3 TEN SILE TEST R ESU LTS ............................................................................................. 5-4 5.4 1/2T COMPACT TENSION SPECIMEN TESTS ........................................................... 5-5 6 RADIATION ANALYSIS AND NEUTRON DOSIMETRY ....................................................... 6-1 6.1 IN T R O D U C T IO N ........................................................................................................... 6-1 6.2 DISCRETE ORDINATES ANALYSIS ............. :............................................................. 6-2 6.3 N EU TR ON D O SIM ETRY .............................................................................................. 6-4 6.4 CALCULATIONAL UNCERTAINTIES ........................................................................ 6-5 7 SURVEILLANCE CAPSULE REMOVAL SCHEDULE ............................................................ 7-1 8 REF E REN C E S ............................................................................................................................. 8-1 APPENDIX A VALIDATION OF THE RADIATION TRANSPORT MODELS BASED ON NEUTRON DOSIMETRY MEASUREMENTS ............................................................................. A-1 APPENDIX B LOAD-TIME RECORDS FOR CHARPY SPECIMEN TESTS ................................ B-i APPENDIX C CHARPY V-NOTCH PLOTS FOR EACH CAPSULE USING SYMMETRIC HYPERBOLIC TANGENT CURVE-FITTING METHOD ...................................... C-I APPENDIX D SURVEILLANCE PROGRAM CREDIBILITY EVALUATION ............................. D-1 APPENDIX E UPPER SHELF ENERGY EVALUATION ................................................................ E-1 WCAP-17036-NP May 2009 Revision 0
iv LIST OF TABLES Table 4-1 Chemical Composition (wt%) of the R. E. Ginna Reactor Vessel Surveillance Materials (Unirrad iated)(a) ................................................................................................................ 4 -3 Table 4-2 Heat Treatment History of the R. E. Ginna Reactor Vessel Surveillance Materials(a) ..... 4-3 Table 5-1 Charpy V-notch Data for the R. E. Ginna Intermediate Shell Forging 125S255 Irradiated to a Fluence of 5.80E+19 n/cm 2 (E > 1.0 MeV) (Longitudinal Orientation) ................... 5-6 Table 5-2 Charpy V-notch Data for the R. E. Ginna Lower Shell Forging 125P666 Irradiated to a Fluence of 5.80E+19 n/cm 2 (E > 1.0 MeV) (Longitudinal Orientation) .......................... 5-7 Table 5-3 Charpy V-notch Data for the R. E. Ginna Surveillance Weld Metal Heat #61782 Irradiated to a Fluence of 5.80E+19 n/cm 2 (E > 1.0 MeV) .............................................. 5-8 Table 5-4 Charpy V-notch Data for the R. E. Ginna Heat-Affected-Zone (HAZ) Material Irradiated to a Fluence of 5.80E+19 n/cm 2 (E > 1.0 M eV) .............................................................. 5-9 Table 5-5 Instrumented Charpy Impact Test Results for the R. E. Ginna Intermediate Shell Forging 125S255 Irradiated to a Fluence of 5.80E+19 n/cm 2 (E > 1.0 MeV)
(L ongitudinal Orientation) ............................................................................................. 5-10 Table 5-6 Instrumented Charpy Impact Test Results for the R. E. Ginna Lower Shell Forging 125P666 Irradiated to a Fluence of 5.80E+ 19 n/cm 2 (E > 1.0 MeV) (Longitudinal O rien tatio n ) ................................................ ................................................................... 5 -11 Table 5-7 Instrumented Charpy Impact Test Results for the R. E. Ginna Surveillance Weld Metal Heat #61782 Irradiated to a Fluence of 5.80E+19 n/cm 2 (E > 1.0 MeV) ...................... 5-12 Table 5-8 Instrumented Charpy Impact Test Results for the R. E. Ginna Heat-Affected-Zone (HAZ)
Material Irradiated to a Fluence of 5.80E+19 n/cm 2 (E > 1.0 MeV) ............................. 5-13 Table 5-9 Effect of Irradiation to 5.80E+19 n/cm2 (E > 1.0 MeV) on the Charpy V-Notch Toughness Properties of the R. E. Ginna Reactor Vessel Surveillance Capsule N Materials .......... 5-14 Table 5-10 Comparison of the R. E. Ginna Surveillance Material 30 ft-lb Transition Temperature Shifts and Upper Shelf Energy Decreases with Regulatory Guide 1.99, Revision 2, P red ictio n s ..................................................................................................................... 5-15 Table 5-11 Tensile Properties of the R. E. Ginna Capsule N Reactor Vessel Surveillance Materials Irradiated to 5.80E+19 n/cm 2 (E > 1.0 M eV) ................................................................ 5-16 Table 6-1A Calculated Neutron Fluence - Surveillance Capsule Center ........................................... 6-7 Table 6-2A Calculated Maximum Fluence at the Vessel Clad/Base Metal Interface ......................... 6-9 Table 6-3A Calculated Maximum Fluence at the Pressure Vessel Intermediate Shell Course to Nozzle Shell C ourse Weld .......................................................................................................... 6-11 Table 6-4 Relative Radial Distribution of Fast Neutron Fluence (n/cm 2) Within the Reactor Vessel Wa ll ................................................................................................................................ 6 -13 WCAP-17036-NP May 2009 Revision 0
v Table 6-5 Relative Radial Distribution of iron Atom Displacements (dpa) Within the Reactor Vessel Wall ................................................................................................................................ 6 -14 Table 6-6 Calculated Fast Neutron Exposure of Surveillance Capsules Withdrawn from R.E. Ginna
....................................................................................................................................... 6 -14 Table 6-7 Calculated Surveillance Capsule Lead Factors .............................................................. 6-15 Table 7-1 Recommended Surveillance Capsule Withdrawal Schedule ...................................... 7-1 Table A-I Nuclear Parameters used in the Evaluation of Neutron Sensors ............................... A-10 Table A-2 Calculated Flux at the Surveillance Capsule Center, Core Midplane Elevation ........... A-11 Table A-3 Measured Sensor Activities and Reaction Rates Surveillance Capsule N ................ A-12 Table A-4 Comparison of Measured, Calculated, and Best Estimate Reaction Rates at Center of Surveillance C apsule N ............................................................................................ A -14 Table A-5 Comparison of Measured, Calculated, and Best Estimate Exposure Rates at the Surveillance C apsule C enter ......................................................................................... A-15 Table A-6 Comparison of Measured/Calculated (M/C) Sensor Reaction Rate Ratios Including all Fast Neutron Threshold Reactions ............ ............................................ A -16 Table A-7 Comparison of Best Estimate/Calculated (BE/C) Exposure Rate Ratios ..................... A-17 Table C-I Upper Shelf Energy Values (ft-lb) Fixed in CVGRAPH ........................................... C-1 Table D- 1 Calculation of Chemistry Factors using R. E. Ginna Surveillance Capsule Data ........... D-3 Table D-2 R. E. Ginna Surveillance Capsule Data Scatter about the Best-Fit Line ........................ D-4 Table D-3 Calculation of Chemistry Factor using Turkey Point Unit 3 Surveillance Data for Weld H eat #7 124 9 .................................................................................................................... D -5 Table D-4 Predicted Versus Best-Estimate ARTNDT Values using Turkey Point Unit 3 Surveillance D ata for Weld H eat #71249 ............................................................................................ D -6 Table D-5 Calculated Regulatory Position 2.1 Chemistry Factor for the R. E. Ginna Vessel Heat
- 71249 Using Credible Surveillance Data from Turkey Point Unit 3 ............................ D-7 Table D-6 Calculation of Residual vs. Fast Fluence .................................. D-8 Table E- 1 Predicted Positions 1.2 and 2.2 Upper Shelf Energy Values at 53 EFPY ....................... E-5 WCAP-17036-NP May 2009 Revision 0
vi LIST OF FIGURES Figure 4-1 Arrangement of Surveillance Capsules in the R. E. Ginna Reactor Vessel ..................... 4-4 Figure 4-2 Capsule N Diagram Showing the Location of Specimens, Thermal Monitors, an d D osim eters ................................................................................................................ 4-5 Figure 5-1 Charpy V-Notch Impact Energy vs. Temperature for R. E. Ginna Reactor Vessel Intermediate Shell Forging 125S255 (Longitudinal Orientation) .................................. 5-17 Figure 5-2 Charpy V-Notch Lateral Expansion vs. Temperature for R. E. Ginna Reactor Vessel Intermediate Shell Forging 125S255 (Longitudinal Orientation) .................................. 5-18 Figure 5-3 Charpy V-Notch Percent Shear vs. Temperature for R. E. Ginna Reactor Vessel Intermediate Shell Forging 125S255 (Longitudinal Orientation) .................................. 5-19 Figure 5-4 Charpy V-Notch Impact Energy vs. Temperature for R. E. Ginna Reactor Vessel Lower Shell Forging 125P666 (Longitudinal Orientation) ....................................................... 5-20 Figure 5-5 Charpy V-Notch Lateral Expansion vs. Temperature for R. E. Ginna Reactor Vessel Lower Shell Forging 125P666 (Longitudinal Orientation) ............................................ 5-21 Figure 5-6 Charpy V-Notch Percent Shear vs. Temperature for R. E. Ginna Reactor Vessel Lower Shell Forging 125P666 (Longitudinal Orientation) ....................................................... 5-22 Figure 5-7 Charpy V-Notch Impact Energy vs. Temperature for the R. E. Ginna Reactor Vessel Surveillance Program Weld M etal ................................................................................. 5-23 Figure 5-8 Charpy V-Notch Lateral Expansion vs. Temperature for the R. E. Ginna Reactor Vessel Surveillance Program Weld M etal ................................................................................. 5-24 Figure 5-9 Charpy V-Notch Percent Shear vs. Temperature for the R. E. Ginna Reactor Vessel Surveillance Program Weld M etal ................................................................................. 5-25 Figure 5-10 Charpy V-Notch Impact Energy vs. Temperature for the R. E. Ginna Reactor Vessel H eat-A ffected-Zone M aterial ......................................................................................... 5-26 Figure 5-11 Charpy V-Notch Lateral Expansion vs. Temperature for the R. E. Ginna Reactor Vessel H eat-A ffected-Z one M aterial ......................................................................................... 5-27 Figure 5-12 Charpy V-Notch Percent Shear vs. Temperature for the R. E. Ginna Reactor Vessel H eat-A ffected-Z one M aterial ......................................................................................... 5-28 Figure 5-13 Charpy V-Notch Impact Energy vs. Temperature for the R. E. Ginna Reactor Vessel Correlation M onitor M aterial ..................................................................................... 5-29 Figure 5-14 Charpy V-Notch Lateral Expansion vs. Temperature for the R. E. Ginna Reactor Vessel C orrelation M onitor M aterial ......................................................................................... 5-30 Figure 5-15 Charpy V-Notch Percent Shear vs. Temperature for the R. E. Ginna Reactor Vessel Correlation Monitor Material .......................................... 5-31 Figure 5-16 Charpy Impact Specimen Fracture Surfaces for R. E. Ginna Reactor Vessel Lower Shell Forging 125P666 (Longitudinal Orientation) ................................................................ 5-32 WCAP-17036-NP May 2009 Revision 0
vii Figure 5-17 Charpy Impact Specimen Fracture Surfaces for R. E. Ginna Reactor Vessel Intermediate Shell Forging 125S255 (Longitudinal Orientation) ....................................................... 5-33 Figure 5-18 Charpy Impact Specimen Fracture Surfaces for the R. E. Ginna Reactor Vessel Surveillance Program Weld M etal ................................................................................. 5-34 Figure 5-19 Charpy Impact Specimen Fracture Surfaces for the R. E. Ginna Reactor Vessel H eat-A ffected-Zone M aterial ......................................................................................... 5-35 Figure 5-20 Tensile Properties for R. E. Ginna Reactor Vessel Intermediate Shell Forging 125S255 (L ongitudinal O rientation) ............................................................................................. 5-36 Figure 5-21 Tensile Properties for R. E. Ginna Reactor Vessel Lower Shell Forging 125P666 (L ongitudinal O rientation) ............................................................................................. 5-37 Figure 5-22 Tensile Properties for the R. E. Ginna Reactor Vessel Surveillance Program Weld Metal...
....................................................................................................................................... 5 -3 8 Figure 5-23 Fractured Tensile Specimens from R. E. Ginna Reactor Vessel Lower Shell Forging 125P666 (Longitudinal O rientation) .............................................................................. 5-39 Figure 5-24 Fractured Tensile Specimens from R. E. Ginna Reactor Vessel Intermediate Shell Forging 125S255 (Longitudinal O rientation) .............................................................................. 5-40 Figure 5-25 Fractured Tensile Specimens from the R. E. Ginna Reactor Vessel Surveillance Program Weld M etal H eat #61782 ............................................................................................... 5-4 1 Figure 5-26 Engineering Stress-Strain Curves for R. E. Ginna Lower Shell Forging 125P666 Tensile Specimens P-25 and P-26 (Longitudinal Orientation) ................................................... 5-42 Figure 5-27 Engineering Stress-Strain Curve for R. E. Ginna Lower Shell Forging 125P666 Tensile Specim en P-27 (Longitudinal Orientation) .................................................................... 5-43 Figure 5-28 Engineering Stress-Strain Curves for R. E. Ginna Surveillance Program Intermediate Shell Forging 125S255 Tensile Specimens S-25 and S-26 (Longitudinal Orientation).5-44 Figure 5-29 Engineering Stress-Strain Curve for R. E. Ginna Surveillance Program Intermediate Shell Forging 125S255 Tensile Specim en S-27 ...................................................................... 5-45 Figure 5-30 Engineering Stress-Strain Curves for R. E. Ginna Surveillance Program Weld Metal Heat 61782 Tensile Specim ens W -13 and W -14 .................................................................... 5-46 Figure 5-31 Engineering Stress-Strain Curve for R. E. Ginna Surveillance Program Weld Metal Heat 61782 Tensile Specim en W -15 ....................................................................................... 5-47 Figure 6-1 R.E. Ginna (r,0) Reactor Geometry at the Core Midplane ............................................. 6-16 Figure 6-2 R.E. Ginna (r, z) Reactor Geom etry ............................................................................... 6-17 Figure E- 1 Regulatory Guide 1.99, Revision 2 Predicted Decrease in Upper Shelf Energy as a Function of Copper and Fluence for Lower Shell Forging 125P666 and Weld Heat
- 6 17 8 2 ............................................................................................................................ E -3 Figure E-2 Regulatory Guide 1.99, Revision 2 Predicted Decrease in Upper Shelf Energy as a Function of Copper and Fluence for Intermediate Shell Forging 125S255 .................... E-4 WCAP-17036-NP May 2009 Revision 0
viii EXECUTIVE
SUMMARY
The purpose of this report is to document the testing results of the surveillance Capsule N from R. E.
Ginna. Capsule N was removed at 30.5 EFPY and post-irradiation mechanical tests of the Charpy V-notch and tensile specimens were performed. A fluence evaluation utilizing the neutron transport and dosimetry cross-section libraries was derived from the ENDF/B-VI database. Capsule N received a fluence of 5.80 x 1019 nfcm2 (E > 1.0 MeV) after irradiation to 30.5 EFPY. The peak cladibase metal interface vessel fluence after 30.5 EFPY of plant operation was 3.20 x 1019 n/cm 2 (E > 1.0 MeV).
This evaluation led to the following conclusions: 1) The measured percent decrease in upper shelf energy for all surveillance materials contained in R. E. Ginna Capsule N is less than the Regulatory Guide 1.99, Revision 2 [1] prediction. 2) The R. E. Ginna surveillance data for both forgings (125S255 and 125P666) are judged to be not credible; however the weld data (heat #61782) is judged to be credible. This credibility evaluation can be found in Appendix D. 3) All beltline forging materials exhibit a more than adequate upper shelf energy level for continued safe plant operation and are predicted to maintain an upper shelf energy greater than 50 ft-lb throughout the 53 EFPY as required by 10 CFR 50, Appendix G
[2]. The beltline welds (heat # 61782 and 71249) are predicted to fall below 50 ft-lb; however, an equivalent margin analysis has demonstrated they will remain acceptable through 53 EFPY. The upper shelf energy evaluation is presented in Appendix E.
Lastly, a brief summary of the Charpy V-notch testing can be found in Section 1. All Charpy V-notch data was plotted using a symmetric hyperbolic tangent curve fitting program.
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1-1 1
SUMMARY
OF RESULTS The analysis of the reactor vessel materials contained in surveillance Capsule N, the fifth capsule removed and tested from the R. E. Ginna reactor pressure vessel, led to the following conclusions:
- Charpy V-notch test data were plotted using a symmetric hyperbolic tangent curve-fitting program.
Appendix C presents the CVGRAPH, Version 5.3, Charpy V-notch plots for Capsule N and previous capsules, along with the program input data.
" Capsule N received an average fast neutron fluence (E > 1.0 MeV) of 5.80 x1019 n/cm 2 after 30.5 effective full power years (EFPY) of plant operation.
- Irradiation of the reactor vessel Intermediate Shell Forging 125S255 Charpy specimens, oriented with the longitudinal axis of the specimen parallel to the major working direction (longitudinal orientation), resulted in an irradiated 30 ft-lb transition temperature of 47.5°F and an irradiated 50 ft-lb transition temperature of 102.8°F. This results in a 30 ft-lb transition temperature increase of 76.4°F and a 50 ft-lb transition temperature increase of 100.0°F for the longitudinally oriented specimens.
" Irradiation of the reactor vessel Lower Shell Forging 125P666 Charpy specimens, oriented with the longitudinal axis of the specimen parallel to the major working direction (longitudinal orientation),
resulted in an irradiated 30 ft-lb transition temperature of 44.9°F and an irradiated 50 ft-lb transition temperature of 78.4'F. This results in a 30 ft-lb transition temperature increase of 91. I°F and a 50 ft-lb transition temperature increase of 93.3°F for the longitudinally oriented specimens.
- Irradiation of the Surveillance Program Weld Metal (Heat #61782) Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 182.2°F and an irradiated 50 ft-lb transition temperature of 276.0'F. This results in a 30 ft-lb transition temperature increase of 216.9F and a 50 ft-lb transition temperature increase of 261.0°F.
- Irradiation of the Heat-Affected-Zone (HAZ) Material Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 43.0°F and an irradiated 50 ft-lb transition temperature of 58.4°F.
This results in a 30 ft-lb transition temperature increase of 107.7°F and a 50 ft-lb transition temperature increase of 74.5°F.
- The average upper shelf energy of the Intermediate Shell Forging 125S255 (longitudinal orientation) resulted in an average energy decrease of 5.7 ft-lb after irradiation. This results in an irradiated average upper shelf energy of 134.3 ft-lb for the longitudinally oriented specimens.
- The average upper shelf energy of the Lower Shell Forging 125P666 (longitudinal orientation) resulted in an average energy decrease of 32.3 ft-lb after irradiation. This results in an irradiated average upper shelf energy of 142.3 ft-lb for the longitudinally oriented specimens.
- The average upper shelf energy of the Surveillance Program Weld Metal Charpy specimens resulted in an average energy decrease of 27.1 ft-lb after irradiation. This results in an irradiated average upper shelf energy of 51.9 ft-lb for the weld metal specimens.
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1-2
- The average upper shelf energy of the HAZ Material Charpy specimens resulted in an average energy decrease of 1.7 ft-lb after irradiation. This results in an irradiated average upper shelf energy of 88.3 ft-lb for the HAZ Material.
- A comparison, as presented in Table 5-10, of the R. E. Ginna reactor vessel surveillance material test results with the Regulatory Guide 1.99, Revision 2 predictions led to the following conclusions:
- The measured 30 ft-lb shift in transition temperature values of the Intermediate Shell Forging 125S255 and Lower Shell Forging 125P666 specimens contained in Capsule N are greater than the Regulatory Guide 1.99, Revision 2 predictions.
- The measured 30 ft-lb shift in transition temperature value of the Surveillance Weld Heat
- 61782 specimens contained in Capsule N is less than the Regulatory Guide 1.99, Revision 2 prediction.
- The measured percent decrease in upper shelf energy for all forging and weld surveillance materials in Capsule N are less that the Regulatory Guide 1.99, Revision 2 predictions.
- Based on the credibility evaluation presented in Appendix D, the R. E. Ginna surveillance data for forgings 125S255 and 125P666 are not credible, but the surveillance weld (heat #61782) data are credible. Sister plant data (from Turkey Point Unit 3) for weld heat #71249 is also credible.
- Based on the upper shelf energy evaluation in Appendix E, the beltline forging materials exhibit a more than adequate upper shelf energy level for continued safe plant operation and are predicted to maintain an upper shelf energy greater than 50 ft-lb throughout the end of the current license (53 EFPY) as required by 10 CFR 50, Appendix G [2].
" Based on the upper shelf energy evaluation in Appendix E, the beltline welds are predicted to fall below 50 ft-lb by the end of the current extended license (53 EFPY) but an equivalent margin analysis demonstrates acceptability through 53 EFPY.
- The calculated 53 EFPY (end-of-license renewal) neutron fluences (E > 1.0 MeV) at the core mid-plane for the R. E. Ginna reactor vessel using the Regulatory Guide 1.99, Revision 2 attenuation formula (i.e., Equation #3 in the guide) are as follows:
Calculated (53 EFPY): Vessel inner radius* = 5.56 x 10'9 n/cm 2 (Taken from Table 6-2A)
Vessel 1/4 thickness = 3.76 x 10'9 n/cm 2 2
Vessel 3/4 thickness = 1.73 x 1019 n/cm
- Clad/base metal interface.
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2-1 2 INTRODUCTION This report presents the results of the examination of Capsule N, the fifth capsule removed from the reactor in the continuing surveillance program, which monitors the effects of neutron irradiation on the R.
E. Ginna reactor pressure vessel materials under actual operating conditions.
The surveillance program for the R. E. Ginna reactor pressure vessel materials was designed and recommended by the Westinghouse Electric Corporation. A description of the surveillance program and the pre-irradiation mechanical properties of the reactor vessel materials are presented in WCAP-7254, "Rochester Gas and Electric Robert E. Ginna Unit No. I Reactor Vessel Radiation Surveillance Program"
[3]. The surveillance program was planned to cover the 40-year design life of the reactor pressure vessel and was based on ASTM E185-66 [4], "Recommended Practice for Surveillance Tests on Structural Materials in Nuclear Reactors." Capsule N was removed from the reactor after Cycle 33, after 30.5 EFPY of exposure and shipped to the Westinghouse Science and Technology Department Hot Cell Facility, where the post-irradiation mechanical testing of the Charpy V-notch impact and tensile surveillance specimens was performed.
This report summarizes the testing of the post-irradiation data obtained from surveillance Capsule N removed from the R. E. Ginna reactor vessel and discusses the analysis of the data.
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3-1 3 BACKGROUND The ability of the large steel pressure vessel containing the reactor core and its primary coolant to resist fracture constitutes an important factor in ensuring safety in the nuclear industry. The beltline region of the reactor pressure vessel is the most critical region of the vessel because it is subjected to significant fast neutron bombardment. The overall effects of fast neutron irradiation on the mechanical properties of low alloy, ferritic pressure vessel steels such as ASTM A508 Class 2 (base material of the R. E. Ginna reactor pressure vessel beltline) are well documented in the literature. Generally, low alloy ferritic materials show an increase in hardness and tensile properties and a decrease in ductility and toughness during high-energy irradiation.
A method for ensuring the integrity of reactor pressure vessels has been presented in "Fracture Toughness Criteria for Protection Against Failure," Appendix G to Section XI of the ASME Boiler and Pressure Vessel Code [5]. The method uses fracture mechanics concepts and is based on the reference nil-ductility transition temperature (RTNDT).
RTNDT is defined as the greater of either the drop weight nil-ductility transition temperature (NDTT per ASTM E208 [6]) or the temperature 60'F less than the 50 ft-lb (and 35-mil lateral expansion) temperature as determined from Charpy specimens oriented perpendicular (transverse) to the major working direction of the plate. The RTNDT of a given material is used to index that material to a reference stress intensity factor curve (K1 c curve) which appears in Appendix G to Section X1 of the ASME Code [5]. The KIc curve is a lower bound of static fracture toughness results obtained from several heats of pressure vessel steel.
When a given material is indexed to the KI, curve, allowable stress intensity factors can be obtained for this material as a function of temperature. Allowable operating limits can then be determined using these allowable stress intensity factors.
RTNDT and, in turn, the operating limits of nuclear power plants can be adjusted to account for the effects of radiation on the reactor vessel material properties. The changes in mechanical properties of a given reactor pressure vessel steel, due to irradiation, can be monitored by a reactor vessel surveillance program, such as the R. E. Ginna reactor vessel radiation surveillance program, in which a surveillance capsule is periodically removed from the operating nuclear reactor and the encapsulated specimens are tested. The increase in the average Charpy V-notch 30 ft-lb temperature (ARTNDT) due to irradiation is added to the initial RTNDT, along with a margin (M) to cover uncertainties, to adjust the RTNDT (ART) for radiation embrittlement. This ART (RTNDT Initial + M + ARTNDT) is used to index the material to the K1 ,
curve and, in turn, to set operating limits for the nuclear power plant that take into account the effects of irradiation on the reactor vessel materials.
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4-1 4 DESCRIPTION OF PROGRAM Six surveillance capsules for monitoring the effects of neutron exposure on the R. E. Ginna reactor pressure vessel core region (beltline) materials were inserted in the reactor vessel prior to initial plant startup. The six capsules were positioned in the reactor vessel between the thermal shield and the vessel wall as shown in Figure 4-1. The vertical center of the capsules is opposite the vertical center of the core.
The capsules contain specimens made from the following:
Iintermediate Shell Forging 125S255 (longitudinal orientation)
- Lower Shell Forging 125P666 (longitudinal orientation)
- Weld metal, Heat #61782 Linde Type 80 flux, which is the same wire used for the intermediate shell to lower shell girth weld.
- Weld heat-affected-zone (HAZ) material of Lower Shell Forging 125P666 Test material obtained from the Intermediate Shell Forging 125S255 and Lower Shell Forging 125P666 (after thermal heat treatment and prior to welding the two shells together) was taken at least one forging thickness from the quenched edges of the forgings. All test specimens were machined from the '/4 thickness location of the original forging thickness after stress-relieving. Test specimens from weld metal and heat-affected-zone (HAZ) metal of forging 125P666 were machined from a stress-relieved weldment joining Intermediate Shell Forging 125S255 and Lower Shell Forging 125P666.
Charpy V-notch impact specimens from Intermediate Shell Forging 125S255 and Lower Shell Forging 125P666 were machined in the "strong" direction (longitudinal). Specimens from the weld metal were oriented with the longitudinal axis of the specimen transverse to the welding direction.
Tensile specimens were machined with the longitudinal axis of the specimen parallel to the hoop direction of the forging. Tensile specimens from the weld metal were oriented with the longitudinal axis of the specimen parallel to the welding direction.
Wedge Opening Loading (WOL) test specimens from both forgings and the weld were machined with the simulated crack in the specimen perpendicular to the hoop direction and the major surfaces of the forgings.
All six capsules contained dosimeter wires of pure copper, nickel, and aluminum-cobalt wire (cadmium-shielded and unshielded). In addition, cadmium-shielded dosimeters of Neptunium ( 2 37Np) and Uranium (238U) were placed in the capsules to measure the integrated flux at specific neutron energy levels.
The capsules contained thermal monitors made from two low-melting-point eutectic alloys, which were sealed in Pyrex tubes. These thermal monitors were used to define the maximum temperature attained by the test specimens during irradiation. The composition of the two eutectic alloys and their melting points are as follows:
2.5% Ag, 97.5% Pb Melting Point: 579°F (304'C) 1.75% Ag, 0.75% Sn, 97.5% Pb Melting Point: 590'F (310 0 C)
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4-2 The chemical composition and heat treatment of the unirradiated surveillance materials are presented in Tables 4-1 and 4-2, respectively. The data in Table 4-1 was obtained from WCAP-13902 [7], "Analysis of Capsule S from the Rochester Gas and Electric Corporation R. E. Ginna Reactor Vessel Radiation Surveillance Program," with copper and nickel values for the surveillance weld heat #61782 updated as noted. The data in Table 4-2 was obtained from the unirradiated surveillance program report, WCAP-7254 [3], Appendix A.
Capsule N was removed after 30.5 effective full power years (EFPY) of plant operation. This capsule contained Charpy V-notch, tensile, and WOL specimens, dosimeters, and thermal monitors.
The arrangement of the various mechanical specimens, dosimeters and thermal monitors contained in Capsule N is shown in Figure 4-2.
May 2009 WCAP-1 7036-NP WCAP- 17036-NP May 2009 Revision 0
4-3 Table 4-1 Chemical Composition (wt%) of the R. E. Ginna Reactor Vessel Surveillance Materials (Unirradiated)(a)
Element Forging 125P666 Forging 125S255 Weld Metal 61782 C 0.19 0.18 0.075 Mn 0.67 0.66 1.31 P 0.010 0.010 0.012 S 0.011 0.007 0.016 Si 0.20 0.23 0.59 Ni 0.69 0.69 0.53(')
Cr 0.37 0.33 0.59 Co 0.013 0.015 0.001 Mo 0.57 0.58 0.36 V 0.02 0.02 0.001 Cu 0.05 0.07 0.23(b)
Al 0.004 0.003 0.020 N --- 0.015 Sn 0.01 0.01 - - -
Note:
(a) Data obtained from WCAP-13902 [7].
(b) Updated best estimate Cu / Ni for surveillance weld based on average of twelve unirradiated, Capsule T, and Capsule S specimen measurements.
Table 4-2 Heat Treatment History of the R. E. Ginna Reactor Vessel Surveillance Materials(a)
Material Temperature (IF) Time (hr) Cooling 1550 9 Water-quenched Lower Shell Forging 1220 12 Air-cooled 125P666 1100 11.25 Furnace-cooled 1550 15.5 Water-quenched Intermediate Shell Forging 1220 18 Air-cooled 125S255 1100 11.25 Furnace-cooled Weld Metal (Heat #61782) 1100 11.25 Furnace-cooled Note:
(a) Data obtained from WCAP-7254 [3].
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4-4 2700 R (remove~.
Figure 4-1 Arrangement of Surveillance Capsules in the R. E. Ginna Reactor Vessel WCAP-17036-NP May 2009 Revision 0
4-5 LEGEND: P - LOWER SHELL FORGING 125P666 S - INTERMEDIATE SHELL FORGING 125S255 W - WELD METAL (HEAT # 61782)
H - HEAT AFFECTED ZONE MATERIAL Tensiles WOL WOL WOL Tensiles WOL WOL WOL Tensiles S26 S271 H 1 H P27 S25 15 P25 P26 TOP OF VESSEL CENTER CENTER CENTER CENTER -p-CENTER WOL WOL WOL Tensiles WW13 CENTER BOTTOM OF VESSEL Figure 4-2 Capsule N Diagram Showing the Location of Specimens, Thermal Monitors, and Dosimeters WCAP-17036-NP May 2009 Revision 0
5-1 5 TESTING OF SPECIMENS FROM CAPSULE N 5.1 OVERVIEW Capsule N contained test specimens from the lower shell forging (125P666), intermediate shell forging (125S255), intermediate shell to lower shell girth weld heat #61782, and heat-affected-zone (HAZ) metal from the 125P666 side of the 125P666/125S255 forgings joined by weld heat #61782. Charpy V-notch impact, tensile, and wedge opening loading (WOL) specimens were included. Per the surveillance capsule testing contract with R. E. Ginna, the Charpy V-notch impact and tensile specimens were tested.
Per ASTM E185-82 [8], the testing of WOL specimens is optional. Therefore, the WOL specimens were not tested.
The post-irradiation mechanical testing of the Charpy V-notch impact specimens and tensile specimens was performed at the Westinghouse Science and Technology Department (STD) Remote Metallographic Facility. Testing was performed in accordance with 10 CFR 50, Appendices G and H [2], ASTM Specification E185-82 [8], and Westinghouse Procedure RMF 8402, Revision 3 [9] as detailed by Westinghouse RMF Procedures 8102, Revision 3 [10], and 8103, Revision 2 [11].
The capsule was opened upon receipt at the laboratory per Procedure RMF 8804, Revision 2 [12]. The specimens and spacer blocks were carefully removed, inspected for identification number, and checked against the master list in WCAP-7254 [3]. All items were in their proper locations.
Examination of the thermal monitors indicated that none of the melting point monitors had melted. Based on this examination, the maximum temperature to which the specimens were exposed was less than 579 0 F (304°C).
The Charpy impact tests were performed per ASTM Specification E23-06 [13] and Procedure RMF 8103 on a Tinius-Olsen Model 74, 358J machine. The tup (striker) of the Charpy machine is instrumented with an Instron Impulse instrumentation system, feeding information into a computer. With this system, load-time and energy-time signals can be recorded in addition to the standard measurement of Charpy energy (ED). From the load-time curve, the load of general yielding (PGY), the time to general yielding (TGv), the maximum load (PM), and the time to maximum load (TM) can be determined. Under some test conditions, a sharp drop in load indicative of fast fracture was observed. The load at which fast fracture was initiated is identified as the fast fracture load (PF). If the fast load drop terminates well above zero load, the termination load is identified as the arrest load (PA).
The energy at maximum, load (EM) was determined by comparing the energy-time record and the load-time record. The energy at maximum load is approximately equivalent to the energy required to initiate a crack in the specimen. Therefore, the propagation energy for the crack (EP) is the difference between the total energy to fracture (ED) and the energy at maximum load (EM).
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5-2 The yield stress (cy) was calculated from the three-point bend formula having the following expression [14]:
- PGY 2Y (Eqn. 5-1)
B(W -a) C where L = distance between the specimen supports in the impact testing machine; B = the width of the specimen measured parallel to the notch; W = height of the specimen, measured perpendicularly to the notch; a = notch depth. The constant C is dependent on the notch flank angle (y), notch root radius (p) and the type of loading (i.e., pure bending or three-point bending). In three-point bending, for a Charpy specimen in which y = 450 and p = 0.010 in., Equation 1 is valid with C = 1.21.
Therefore, (for L = 4W),
Y=YPGY B(W-a)2 L 3.305 PGYW (Eqn. 5-2) 1.21 B(W-a) 2 For the Charpy specimen, B = 0.394 in., W = 0.394 in., and a = 0.079 in. Equation 5-2 then reduces to:
G5Y = 3 3 . 3 PGY (Eqn. 5-3) where ay is in units of psi and PGY is in units of lb. The flow stress was calculated from the average of the yield and maximum loads, also using the three-point bend formula.
Symbol A in columns 4, 5, and 6 of Tables 5-5 through 5-8 is the cross-section area under the notch of the Charpy specimens:
A = B(W -a) = 0.1241 sq. in. (Eqn. 5-4)
Percent shear was determined from post-fracture photographs using the ratio-of-areas methods in compliance with ASTM E23-06 [13] and A370-07 [15]. The lateral expansion was measured using a dial gage rig similar to that shown in the same specifications.
Tensile tests were performed on a 20,000 pound Instron, split console test machine (Model 1115) per ASTM Specification E8-04 [16] and E21-05 [17] and Procedure RMF 8102 [10]. Extension measurements were made with a linear variable displacement transducer (LVDT) extensometer. The extensometer gage length was 1.00 inch. Elevated test temperatures were obtained with a three-zone electric resistance split-tube furnace with a 9-inch hot zone. All tests were conducted in air.
The yield load, ultimate load, fracture load, total elongation and uniform elongation were determined directly from the load-extension curve. The yield strength, ultimate strength and fracture strength were calculated using the original cross-sectional area. The final diameter was determined from post-fracture photographs. The fracture area used to calculate the fracture stress (true stress at fracture) and percent reduction in area were computed using the final diameter measurement.
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5-3 5.2 CHARPY V-NOTCH IMPACT TEST RESULTS The results of the Charpy V-notch impact tests performed on the various materials contained in Capsule N, which received a fluence of 5.80 x loll n/cm 2 (E > 1.0 MeV) in 30.5 EFPY of operation, are presented in Tables 5-1 through 5-8 and are compared with the unirradiated and previously withdrawn capsule results as shown in Figures 5-1 through 5-12.
The Charpy V-notch (CVN) test data from the Capsule N specimens were input into a hyperbolic tangent curve-fitting program, CVGraph Version 5.3 which was used to define the 30 ft-lb (41 J), 50 ft-lb (68 J),
and 35 mil (0.89 mm) lateral expansion index temperatures on the transition temperature curve. The baseline (unirradiated) CVN data and the CVN data from all previously-tested capsules (V, R, T, and S) were likewise re-analyzed using CVGraph, to provided consistency of analytical method for all Ginna surveillance data results. The CVGraph data plots are provided in Appendix C. The unirradiated and previous capsule test data were taken from WCAP-7254 [3], FP-RA-1 [18], WCAP-8421 [19],
WCAP-10086 [20], WCAP- 10496 [21] and WCAP-13902 [7].
The transition temperature increases and upper shelf energy decreases for the Capsule N materials are summarized in Table 5-9 and led to the following results for irradiation to 5.80 x l0o9 n/cm 2 (E > 1.0 MeV):
- Irradiation of the reactor vessel Intermediate Shell Forging 125S255 Charpy specimens, oriented with the longitudinal axis of the specimen parallel to the major working direction (longitudinal orientation), resulted in an irradiated 30 ft-lb transition temperature of 47.5°F and an irradiated 50 ft-lb transition temperature of 102.8°F. This results in a 30 ft-lb transition temperature increase of 76.4°F and a 50 ft-lb transition temperature increase of 100.0°F.
- Irradiation of the reactor vessel Lower Shell Forging 125P666 Charpy specimens, oriented with the longitudinal axis of the specimen parallel to the major working direction (longitudinal orientation),
resulted in an irradiated 30 ft-lb transition temperature of 44.9°F and an irradiated 50 ft-lb transition temperature of 78.4°F. This results in a 30 ft-lb transition temperature increase of 91.1 °F and a 50 ft-lb transition temperature increase of 93.3°F.
- irradiation of the weld metal (Heat #61782) Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 182.2 0 F and an irradiated 50 ft-lb transition temperature of 276.0°F. This results in a 30 ft-lb transition temperature increase of 216.9°F and a 50 ft-lb transition temperature increase of 261.0°F.
- Irradiation of the weld Heat-Affected-Zone (HAZ) metal Charpy specimens resulted in an irradiated 30 ft-lb transition temperature of 43.0°F and an irradiated 50 ft-lb transition temperature of 58.4°F.
This results in a 30 ft-lb transition temperature increase of 107.7°F and a 50 ft-lb transition temperature increase of 74.5°F.
- The average upper shelf energy of the Intermediate Shell Forging 125S255 (longitudinal orientation) resulted in an average energy decrease of 5.7 ft-lb. This results in an irradiated average upper shelf energy of 134.3 ft-lb.
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5-4
" The average upper shelf energy of the Lower Shell Forging 125P666 (longitudinal orientation) resulted in an average energy decrease of 32.3 ft-lb. This results in an irradiated average upper shelf energy of 142.3 ft-lb.
- The average upper shelf energy of the weld metal Charpy specimens resulted in an average energy decrease of 27.1 ft-lb. This results in an irradiated average upper shelf energy of 51.9 ft-lb for the weld metal specimens.
" The average upper shelf energy of the weld HAZ metal Charpy specimens resulted in an average energy decrease of 1.7 ft-lb. This results in an irradiated average upper shelf energy of 88.3 ft-lb for the weld HAZ metal.
- Comparisons of the measured 30 ft-lb shift in transition temperature values and upper shelf energy decreases to those predicted by Reg. Guide 1.99, Rev. 2 [1] are presented in Table 5-10. The 30 ft-lb shifts in transition temperature values vary in comparison to the previous R. E. Ginna capsule analyses. This variance is due to the increased accuracy of the hyperbolic tangent methodology contained in CVGRAPH Version 5.3 in comparison with previous methodologies.
The fracture appearance of each irradiated Charpy specimen from the various materials is shown in Figures 5-13 through 5-16. The fractures show an increasingly ductile or tougher appearance with increasing test temperature. Load-time records for the individual instrumented Charpy specimens are contained in Appendix B.
All beltline materials exhibit adequate upper shelf energy levels for continued safe plant operation. This evaluation can be found in Appendix E. Forgings 125S255 and 125P666 are predicted to maintain upper shelf energy values greater than 50 ft-lb throughout the end of the current license (53 EFPY) as required by 10 CFR 50, Appendix G [2]. Weld heat numbers 61782 and 71249 have projected USE values less than the 50 ft-lb screening criteria, but an equivalent margin analysis (EMA) has demonstrated that the weld materials remain acceptable. This is also discussed in Appendix E.
5.3 TENSILE TEST RESULTS The results of the tensile tests performed on the various materials contained in Capsule N irradiated to 5.80E+19 n/cm 2 (E > 1.0 MeV) are presented in Table 5-11 and are compared with unirradiated results as shown in Figures 5-20 through 5-22.
The results of the tensile tests performed on the Intermediate Shell Forging 125S255 (longitudinal orientation) indicated that irradiation to 5.80E+19 n/cm 2 (E > 1.0 MeV) caused approximately a 17.7 ksi increase in the 0.2 percent offset yield strength and approximately a 11.3 ksi increase in the ultimate tensile strength at 550°F when compared to unirradiated data [3]. See Figure 5-20 and Table 5-11.
The results of the tensile tests performed on the Lower Shell Forging 125P666 (longitudinal orientation) indicated that irradiation to 5.80E+19 n/cm 2 (E > 1.0 MeV) caused approximately a 13.1 ksi increase in the 0.2 percent offset yield strength and approximately a 8.3 ksi increase in the ultimate tensile strength when compared to unirradiated data [3]. See Figure 5-21 and Table 5-11.
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5-5 The results of the tensile tests performed on the surveillance weld heat #61782 indicated that irradiation to 5.80E+19 n/cm 2 (E > 1.0 MeV) caused approximately a 31.4 ksi increase in the 0.2 percent offset yield strength and approximately a 24.5 ksi increase in the ultimate tensile strength when compared to unirradiated data [3]. See Figure 5-22 and Table 5-11.
The fractured tensile specimens for Lower Shell Forging 125P666, Intermediate Shell Forging 125S255, and weld metal heat #61782 are shown in Figures 5-23, 5-24, and 5-25, respectively. The engineering stress-strain curves for the tensile tests are shown in Figures 5-26 through 5-31.
5.4 1/2T COMPACT TENSION SPECIMEN TESTS Per ASTM E185-82 [8], the testing of 1/2T Compact Tension Specimens is optional. Therefore, the 1/2T Compact Tension Specimens were not tested and are being stored at the Westinghouse Research and Technology Department Hot Cell Facility.
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5-6 Table 5-1 Charpy V-notch Data for the R. E. Ginna Intermediate Shell Forging 125S255 Irradiated to a Fluence of 5.80E+19 n/cm 2 (E > 1.0 MeV) (Longitudinal Orientation)
Sample Temperature Impact Energy Lateral Expansion Shear 0
Number OF C ft-lbs Joules mils mm %
S43 0 -18 6 8 6 0.15 0 S44 20 -7 32 43 28 0.71 5 S53 35 2 7 9 8 0.20 5 S52 40 4 5 7 6 0.15 5 S46 50 10 71 96 54 1.37 25 S54 60 16 13 18 13 0.33 5 S50 80 27 45 .61 35 0.89 20 S48 90 -32 72 98 51 1.30 30 S47 200 93 73 99 63 1.60 50 S49 350 177 148 201 90 2.29 100 S51 375 191 125 170 77 1.96 100 S45 390 199 130 176 83 2.11 100 May 2009 WCAP-1 7036-NP WCAP-17036-NP May R 009 Revision 0
5-7 Table 5-2 Charpy V-notch Data for the R. E. Ginna Lower Shell Forging 125P666 Irradiated to a Fluence of 5.80E+19 n/cm2 (E > 1.0 MeV) (Longitudinal Orientation)
Sample Temperature Impact Energy Lateral Expansion Shear Number fF fl-bs
-C Joules mils mm %
P47 -25 -32 3 4 6 0.15 2 P50 20 -7 14 19 12 0.30 5 P53 30 -1 5 7 7 0.18 5 P51 40 4 4 5 7 0.18 5 P54 50 10 64 87 48 1.22 25 P44 55 13 49 66 40 1.02 20 P49 80 27 63 85 51 1.30 45 P45 90 32 74 100 56 1.42 45 P52 100 38 36 49 35 0.89 40 P46 350 177 145 197 88 2.24 100 P48 375 191 141 191 84 2.13 100 P43 390 199 141 191 83 2.11 100 WCAP-17036-NP May 2009 Revision 0
5-8 Table 5-3 Charpy V-notch Data for the R. E. Ginna Surveillance Weld Metal Heat #61782 Irradiated to a Fluence of 5.80E+19 n/cm 2 (E > 1.0 MeV)
Sample Temperature Impact Energy Lateral Expansion Shear Number OF °C ft-lbs Joules mils mm %
W54 0 -18 4 5 7 0.18 5 W47 150 66 22 30 23 0.58 40 W48 200 93 26 35 25 0.64 50 W45 210 99 37 50 34 0.86 80 W43 220 104 46 62 39 0.99 90 W53 230 110 52 71 44 1.12 95 W49 240 116 52 71 43 1.09 95 W51 260 127 45 61 41 1.04 98 W50 280 138 51 69 45 1.14 98 W52 350 177 50 68 46 1.17 100 W44 375 191 64 87 85 2.16 100 W46 400 204 49 66 46 1.17 100 WCAP-17036-NP May 2009 Revision 0
5-9 Table 5-4 Charpy V-notch Data for the R. E. Ginna Heat-Affected-Zone (HAZ) Material Irradiated to a Fluence of 5.80E+19 n/cm 2 (E > 1.0 MeV)
Sample Temperature Impact Energy Lateral Expansion Shear Number OF °C Ft-lbs Joules mils mm %
H48 0 -18 8 11 8 0.20 20 H43 35 2 24 33 19 0.48 20 H50 40 4 34 46 25 0.64 20 H46 50 10 15 20 14 0.36 25 H52 55 13 38 52 33 0.84 30 H54 60 16 80 108 51 1.30 50 H53 80 27 66 89 48 1.22 50 H47 130 54 87 118 60 1.52 70 H45 350 177 124 168 64 1.63 100 H49 360 182 67 91 50 1.27 100 H51 375 191 90 122 52 1.32 100 H44 390 199 72 98 70 1.78 100 WCAP-17036-NP May 2009 Revision 0
5-10 Table 5-5 Instrumented Charpy Impact Test Results for the R. E. Ginna Intermediate Shell Forging 125S255 Irradiated to a Fluence of 5.80E+19 n/cm 2 (E > 1.0 MeV) (Longitudinal Orientation)
Test Charpy Normalized Energies General Sapl Energy (ft-lb/in 2 ) Yield Time to Max. Time to Fract. Arrest Yield Flow Temp. E Load PCY Load, PM Load, Load, Stress Stress No. (OF) E, Total At PM Prop. PGY (msec) PM (Ib) (msec) PF (lb) PA (lb) (ksi) (ksi)
ED/A EM/A Ep/A (Ib)
S43 0 6 46 23 23 2708 0.14 2714 0.14 2708 0 90 90 S44 20 32 259 206 53 3423 0.15 4431 0.47 4363 0 114 131 S53 35 7 57 30 27 3069 0.15 3097 0.16 3088 0 102 103 S42 40 5 41 20 21 2438 0.13 2472 0.14 2461 0 81 82 S46 50 69 552 326 226 3406 0.15 4367 0.7 4006 0 113 129 S54 60 12 98 55 43 3107 0.15 3910 0.21 3907 0 103 117 S50 80 44 350 296 54 3157 0.15 4140 0.68 4068 0 105 122 S48 90 67 536 316 220 3262 0.16 4310 0.7 3887 0 109 126 S47 200 66 531 302 228 3065 0.15 4221 0.69 3921 649 102 121 S49 350 137 1102 296 806 3164 0.3 3814 0.8 n/a n/a 105 116 S51 375 115 927 288 640 2905 0.15 4042 0.68 n/a n/a 97 116 S45 390 118 947 284 663 2754 0.15 3958 0.69 n/a n/a 92 112 WCAP-17036-NP May 2009 Revision 0
5-11 Table 5-6 Instrumented Charpy Impact Test Results for the R. E. Ginna Lower Shell Forging 125P666 Irradiated to a Fluence of 5.80E+19 n/cm 2 (E > 1.0 MeV) (Longitudinal Orientation)
Test Charpy Normalized Energies General (ft-lb/in 2) Yield Time to Max. Time to Fract. Arrest Yield Flow Sample Energy No. Temp. E, Load PGY Load, PM Load, Load, Stress Stress (NF) (E-lb) Total At PM Prop. PGY (msec) PM (lb) (msec) PF (lb) PA (lb) (ksi) (ksi)
ED/A EM/A Ep/A (lb) I I P47 -25 3 25 12 13 1526 0.1 1588 0.11 1574 0 51 52 P50 20 13 108 57 51 2995 0.14 3692 0.21 3672 0 100 111 P53 30 5 38 19 20 2211 0.12 2292 0.13 2290 0 74 75 P51 40 4 29 15 15 1800 0.12 1825 0.12 1825 0 60 60 P54 50 62 501 297 203 2973 0.15 4022 0.7 3823 0 99 116 P44 55 47 382 308 74 3178 0.15 4159 0.7 4081 0 106 122 P49 80 59 474 301 173 3006 0.15 4021 0.71 3841 0 100 117 P45 90 68 545 296 249 2996 0.15 4094 0.69 3668 0 100 118 P52 100 31 253 200 53 2828 0.14 3887 0.52 3878 0 94 112 P46 350 132 1061 254 807 2393 0.14 3552 0.69 n/a n/a 80 99 P48 375 129 1043 268 775 2579 0.14 3721 0.69 n/a n/a 86 105 P43 390 129 1038 269 769 2581 0.14 3777 0.68 n/a n/a 86 106 WCAP- 17036-NP May 2009 Revision 0
5-12 Table 5-7 Instrumented Charpy Impact Test Results for the R. E. Ginna Surveillance Weld Metal Heat #61782 Irradiated to a Fluence of 5.80E+19 n/cm 2 (E > 1.0 MeV)
Normalized Energies General Test Charpy (ft-lb/in2 ) Yield Time to Max. Time to Fract. Arrest Yield Flow No. Temp. En Load PGY Load, PM Load, Load, Stress Stress (OF) (ft-lb) Total At PM Prop. PGY (msec) PM (ib) (msee) PF (lb) PA (lb) (ksi) (ksi)
ED/A EM/A Ep/A (lb)
W54 0 4 30 15 15 1865 0.12 1874 0.12 1874 0 62 62 W47 150 21 171 65 106 3057 0.14 3916 0.22 3742 739 102 116 W48 200 25 199 64 135 3099 0.15 3840 0.22 3773 1304 103 116 W45 210 35 282 67 214 3336 0.14 4176 0.22 3020 1002 111, 125 W43 220 44 358 177 181 3329 0.14 4352 0.41 4232 2449 111 128 W53 230 49 392 179 213 3151 0.14 4146 0.43 3314 2367 105 122 W49 240 50 399 171 228 3011 0.14 4214 0.42 3348 2027 100 120 W51 260 43 344 156 188 3139 0.14 4043 0.39 2142 1666 105 120 W50 280 48 389 183 206 3019 0.15 4037 0.46 2941 2044 101 117 W52 350 47 379 159 221 2981 0.14 3838 0.42 n/a n/a 99 114 W44 375 59 479 199 280 3145 0.14 4156 0.48 n/a n/a 105 122 W46 400 46 374 153 221 2925 0.15 3742 0.42 n/a n/a 97 111 WCAP- 17036-NP May 2009 Revision 0
5-13 Table 5-8 Instrumented Charpy Impact Test Results for the R. E. Ginna Heat-Affected-Zone (HAZ) Material Irradiated to a Fluence of 5.80E+19 n/cm 2 (E > 1.0 MeV)
Charpy Normalized Energies General Sample Test Energy (ft-lb/in2 ) Yield Time to Max. Time to Fract. Arrest Yield Flow No.Sam En Load PGY Load, PM Load, Load, Stress Stress (NF) (ft-lb) Total At PM Prop. PGY (msec) PM (lb) (msec) PF (Ib) PA (lb) (ksi) (ksi)
ED/A EM/A Ep/A (Ib)
H48 0 7 53 28 25 2983 0.14 3011 0.15 3002 0 99 100 H43 35 24 192 68 124 3664 0.15 4384 0.22 4334 0 122 134 H50 40 31 253 199 54 3409 0.15 4498 0.45 4478 0 114 132 H46 50 13 105 58 46 3685 0.15 4335 0.2 4329 0 123 134 H52 55 35 285 211 74 3570 0.15 4603 0.47 4601 272 119 136 H54 60 73 591 344 248 3588 0.17 4643 0.7 4122 562 119 137 H53 80 64 515 338 176 3605 0.15 4601 0.69 4357 0 120 137 H47 130 80 648 244 404 3609 0.16 4519 0.53 3332 980 120 135 H45 350 115 925 312 614 2978 0.15 4278 0.71 n/a n/a 99 121 H49 360 63 506 207 299 2978 0.15 4087 0.51 n/a n/a 99 118 H51 375 81 656 307 349 3171 0.15 4324 0.68 n/a n/a 106 125 H44 390 65 524 216 308 3084 0.14 4200 0.51 n/a n/a 103 121 May 2009 WCAP- 17036-NP WCAP- 17036-NP May 2009 Revision 0
5-14 Table 5-9 Effect of Irradiation to 5.80E+19 n/cm2 (E > 1.0 MeV) on the Charpy V-Notch Toughness Properties of the R. E. Ginna Reactor Vessel Surveillance Capsule N Materials Average 30 ft-lb(a) Average 35 mil Lateraltb) Average 50 ft-lb(') Average Energy Absorption(a)
Material Transition Temperature (IF) Expansion Temperature (IF) Transition Temperature (IF) (ft-lb)
Unirradiated Irradiated AT Unirradiated Irradiated AT Unirradiated Irradiated AT Unirradiated Irradiated AE Intermediate Shell Forging -28.9 47.5 76.4 -6.6 79.7 86.3 2.8 102.8 100.0 140.0 134.3 -5.7 125S255 (Longitudinal)
Lower Shell Forging -46.2 44.9 91.1 -28.2 64.4 92.6 -14.9 78.4 93.3 174.6 142.3 -32.3 125P666 (Longitudinal)
Weld Metal -34.7 182.2 216.9 -21.4 208.5 229.9 15.0 276.0 261.0 79.0 51.9 -27.1 (Heat # 61782) 1 HAZ Material -64.7 43.0 107.7 -31.7 56.5 88.2 -16.1 58.4 74.5 90.0 88.3 -1.7 Notes:
(a) "Average" is defined as the value mathematically determined by CVGRAPH from the data points of the Charpy tests (see Figures 5-1, 5-4, 5-7 and 5-10).
(b) "Average" is defined as the value mathematically determined by CVGRAPH from the data points of the Charpy tests (see Figures 5-2, 5-5, 5-8 and 5-11).
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5-15 Table 5-10 Comparison of the R. E. Ginna Surveillance Material 30 ft-lb Transition Temperature Shifts and Upper Shelf Energy Decreases with Regulatory Guide 1.99, Revision 2, Predictions 30 ft-lb Transition Fluence Temperature Shift USE Decrease (x 10' 9n/cm 2, Predicted Measured Predicted Measured Material Capsule E > 1.0 MeV) (OF) (a) (OF) (b) (%) (a) (%)
V 0.587 37.4 0.0(c) 14.5 3.7 Intermediate Shell R 1.02 44.2 20.1 16.5 -1.6 Forging 125S255 (Longitudinal) T 1.69 50.4 0.0(c) 19 -8.8 S 3.64 58.8 76.8 23 0.7 N 5.8 62.9 76.4 26 4.1 V 0.587 26.4 34.7 13 10.1 Lower Shell R 1.02 31.2 57.5 15 15.4 Forging 125P666 T 1.69 35.5 33.6 17 18.4 (Longitudinal) S 3.64 41.4 45.8 21 18.4 N 5.8 44.3 91.1 23 18.5 V 0.587 135.2 146.7 32.5 30.1 R 1.02 159.7 156.2 37 38.1 Weld Metal (Heat # 61782) T 1.69 181.8 149.7 40.5 33.3 S 3.64 212.1 212.2 49 33.9 N 5.8 227.2 216.9 54 34.3 V 0.587 --- 30.7 .- 50.0 R 1.02 --- 58.6 --- 8.0 HAZ Material T 1.69 --- 41.0 ....- 30.8 S 3.64 -- - 38.9 .- 15.0 N 5.8 --- 107.7 --- 1.9 Notes:
(a) Based on Regulatory Guide 1.99, Revision 2, methodology using the mean weight percent values of copper and nickel of the surveillance material.
(b) Calculated by CVGraph Version 5.3 using measured Charpy data (See Appendix C).
(c) Measured ARTNDT value was determined to be negative, but physically a reduction should not occur, therefore a conservative value of zero is used.
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5-16 Table 5-11 Tensile Properties of the R. E. Ginna Capsule N Reactor Vessel Surveillance Materials Irradiated to 5.80E+19 n/cm 2 (E > 1.0 MeV) 0.2%
Test Yield Ultimate Fracture Fracture Fracture Uniform Total Reduction Sample Temp. Strength Strength Load Stress Strength Elongation Elongation in Area Material Number (OF) (ksi) (ksi) (kip) (ksi) (ksi) (%) (%) (%)
S25 125 93.2 109.0 3.75 188.9 76.4 8.4 19.6 60 Intermediate Shell Forging 125S255 S26 300 79.5 94.2 3.00 161.1 61.1 8.3 21.5 62 (Longitudinal) S27 550 86.6 104.9 3.90 223.7 79.5 7.5 18.2 64 P25 150 73.8 91.7 2.75 189.3 56.0 9.6 23.3 70 Lower Shell Forging 125P666 P26 325 69.5 86.1 2.70 177.9 55.0 8.6 21.6 69 (Longitudinal) P27 550 69.8 88.6 3.03 146.8 61.6 7.8 18.6 58 W13 125 102.9 111.0 4.05 184.9 82.5 9.0 21.2 55 Weld Metal W14 260 96.8 104.9 3.90 184.6 79.5 9.0 19.8 57 (Heat #61782)
W15 550 92.7 105.4 4.15 189.5 84.5 8.3 17.3 55 WCAP-17036-NP May 2009 Revision 0
5-17 Intermediate Shell Forging 125S255 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/08/2009 09:31 PM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat #
1 Ginna UNIRR SA508CL2 LC 125S255 2 Ginna V SA508CL2 LC 125S255 3 Ginna R SA508CL2 LC 125S255 4 Ginna T SA508CL2 LC 125S255 5 Ginna S SA508CL2 LC 125S255 6 Ginna N SA508CL2 LC 125S255 300-250-4200-150 In 100 50 0 "-'-"
-300.0 -200..0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 6 00.0 Temperature In Deg F 0 1 0 2 03 A4 v 5 0 6 Results Curve Fluence LSE USE d-USE T @30 d-T @30 T @50 d-T @50 1 2. 2 140.0 .0 -28.9 .0 2. 8 .0 2 2. 2 134.8 -5.2 -48.4 -19.5 -14.5 -17. 3 3 2. 2 142. 2 2. 2 -8.8 20. 1 20.5 17.7 4 2. 2 152.3 12.3 -71.5 -42.6 -6.4 -9.2 5 2. 2 139.0 -1.0 47.9 76. 8 74. 7 71.9 6 2. 2 134. 3 -5.7 47. 5 76.4 102.8 100.0 Figure 5-1 Charpy V-Notch Impact Energy vs. Temperature for R. E. Ginna Reactor Vessel Intermediate Shell Forging 125S255 (Longitudinal Orientation)
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5-18 Intermediate Shell Forging 125S255 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 04/03/2009 08:55 AM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat #
Ginna UNIRR SA508CL2 LC 125S255 2 Ginna V SA508CL2 _C 125S255 3 Ginna R SA508CL2 LC 125S255 4 Ginna T SA508CL2 LC 125S255 5 Ginna S SA508CL2 LC 125S255 6 Ginna N SAS08CL2 LC 125S255 200 150
.2 IL 100 50 0 +-
-300.0 0.0 300.0 600.0 Temperature in Deg F 0 1 a 2 03 64 4 @6 Uwlve EWM 1.SE USE d-USE T 035 d-T 035 1.0 8T, 0 .0 -6.6 .0 2 88. 8 1. 8 -25.7 -19.1I 1.0 3 I.0 93. 7 6.7 3, 5 10.1I 4 75. 5 -11.S -17.9 1It. 3 1.0 5 1.0 88. 5 1. 5 65.7 72. 3 6 I.0 83, 3 -3.7 79.7 86. 3 Figure 5-2 Charpy V-Notch Lateral Expansion vs. Temperature for R. E. Ginna Reactor Vessel Intermediate Shell Forging 125S255 (Longitudinal Orientation)
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5-19 Intermediate Shell Forging 125S255 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 04/03/2009 08:57 AM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat #
1 Ginna UNIRR SA508CL2 LC 125S255 2 Ginna R SA508CL2 LC 125S255 3 Ginna T SAS08CL2 LC 125S255 4 Ginna S SAS08CL2 LC 125S255 5 Ginna N SASNCL2 LC 125S2-55 125 100 75 50 25 0 ....
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F 0 1 a 2 0 34 A4 FIE .LS0 USE i-USE T 050 -T 050 I .0 100.0 .0 60.0 .0
.0 100.0 .0 52.5 -7,5 3 .0 100.0 .0 87.4 27.4 4 .0 100.0 ,0 80. 0 200 5 .0 100. 0 .0 179.4 119.4 Figure 5-3 Charpy V-Notch Percent Shear vs. Temperature for R. E. Ginna Reactor Vessel Intermediate Shell Forging 125S255 (Longitudinal Orientation)
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5-20 Lower Shell Forging 125P666 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/11/2009 09:05 AM Data Set(s) Plotted Curve Plant Capsule Materila oril. Heat #
1 Ginna UNIRR SA5O8CL2 LC 125P666 2 Ginna V SA5O8CL2 LC 125P666 3 Ginna R SA5O8CL2 LC 125P666 4 Ginna T SA5O8CL2 LC 125P666 5 Ginna S SA5O8CL2 LC 125P666 6 Ginna N SA5O8CL2 LC 125P666 300
-r Lu 0 -
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 800.0 Temperature in Deg F 01 2 0 3 A 4 v 5 0 6 Results Curve Fluence LSE USE d-USE T @30 d-T @30 T @50 d-T @50 1 2.2 174.6 .0 -46.2 .0 -14.9 .0 2 22 157.0 -17.6 -11.5 34.7 12.3 27.2 3 2. 2 147.8 -26.8 11.3 57.5 27.1 42.0 4 2.2 142.5 -32. 1 -12.6 33.6 14.0 28.9 5 2. 2 142.5 -32. 1 -. 4 45.8 31.3 46. 2 6 2. 2 142.3 -32.3 44.9 91. 1 78.4 93. 3 Figure 5-4 Charpy V-Notch Impact Energy vs. Temperature for R. E. Ginna Reactor Vessel Lower Shell Forging 125P666 (Longitudinal Orientation)
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5-21 Lower Shell Forging 125P666 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 04/03/2009 08:42 AM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat #
1 Ginna UNIRR SA508CL2 LC 125P666 2 Ginna V SA508CL2 LC 125P666 3 Ginna R SA5ORCL2 LC 125P666 4 Ginna T SA508CL2 LC 12SP666 5 Ginna S SA508CL2 LC 125P666 6 Ginna N SA508CL2 LC 12511666 20W C
E 1.100 I
so 0 +-
-300.0 0.0 300.0 600.0 Temperature in Deg F 0 1 02 03 ^4 46 Vbomm LSF d-USE T 035 d-T 035 1.0 85. 2 .O -28.2 ,0 2 1L0 85. 5 .3 3. 4 31.6 3 1.0 90.0 4,.8 23.6 51,8 4 1.0 82. I I I 29. 3 5 1.0 86. 0 .8 20. 8 49.0 6 85. 0 - .2 64.4 92. 6 1.0 Figure 5-5 Charpy V-Notch Lateral Expansion vs. Temperature for R. E. Ginna Reactor Vessel Lower Shell Forging 125P666 (Longitudinal Orientation)
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5-22 Lower Shell Forging 1115P666 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 04/03/2009 08:49 AM Data Set(s) Plotted Plant Capsule Material Ori. Heat #
Ginna UNIRR SA508CL2 LC 125P666 2 Ginna R SA508CL2 LC 12pP666 3 Ginna T SAS08CL2 LC I25P666 4 Ginna S SA508CL2 LC 125P666 5 Ginna N SAS08CL2 LC 125P666 125 100 It 75 I 50 25 01-
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Dog F 0 1 1 2 03 '4 45 curve FhKUea LS USE 4-USE T @50 d-T "350
.0 100.0 .0 44. 3 .0 2 .0 100.0 .0 50. 5 6.2 3 .0 10.0 .0 56. 7 12.4 4 100.0 .0 38. 3 -6.0
.0 .0 5 100.0 100, 3 56. 0 Figure 5-6 Charpy V-Notch Percent Shear vs. Temperature for R. E. Ginna Reactor Vessel Lower Shell Forging 125P666 (Longitudinal Orientation)
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5-23 Weld Heat #61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 04/03/2009 08:f07 PM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat #
2 Ginna UNIRR SAW NA 61782 Ginna V SAW NA 61782 3 Ginna R SAW NA 61782 4 Ginna T reco SAW NA 61782 5 Ginna S SAW NA 61782 6 Ginna N SAW NA 61782 300 250 U.2 p150 lI
~100-.
50 2 o
-300.0 -200.0 -1001.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F 0 1 0 2 03 A 4 v 6 06 Cwrve Fbsm ~ IS2 USE 4-USE T @30 d-T 030 T 0-M1 -iT 050 2.2 79. 0 .0 -34.7 ,0 15.0 .0 2 2,2 55. 2 -23. 8 1120 146.7 219.4 204.4 3 2.2 48. 9 -30.1 121.5 156. 2 4 2'2 52.7 -26, 3 115.0 149.7 259. i 244. I 5 2.2 52. 2 -26. 8 177.5 212.2 346. 5 331.5 6 122 51.9 -27. I 182.2 216.9 276.0 261.0 Figure 5-7 Charpy V-Notch Impact Energy vs. Temperature for the R. E. Ginna Reactor Vessel Surveillance Program Weld Metal May 2009 WCAP-1 7036-NP WCAP- 17036-NP May 2009 Revision 0
5-24 Weld Heat #61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on (W03/2009 0& 10 PM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat #
Ginna UNIRR SAW NA 61782 2 Ginna V SAW NA 61782 3 Ginna R SAW NA 61782 4 Ginna T reco SAW NA 61782 5 Ginna S SAW NA 61782 6 Ginna N SAW NA 61782 200
.3 150 s
8.2o 50 0
o*
-300.0 0.0 300.0 600.0 Temperature in Dog F 0 1 03 tA 4 V 6 06 Curve Fbaeow LSE G-USN T (035 d-T 035 1.0 79. 7 .0 -21.4 .0 1.0 55.2 -24. 5 159.6 181.0 3 Lo0 52.4 -27. 3 138.8 160,2 4 1.0 48. 6 -31. 1 171. 2 192.6 5 1.0 53.2 -26. 5 201.7 223. I 6 1.0 50. 0 -29. 7 208.5 229.9 Figure 5-8 Charpy V-Notch Lateral Expansion vs. Temperature for the R. E. Ginna Reactor Vessel Surveillance Program Weld Metal WCAP-17036-NP May 2009 Revision 0
5-25 Weld Heat #61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on (W03/2009 08:11 PM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat #
Ginna UNIRR SAW NA 61782 2 Ginna R SAW NA 61782 3 Ginna T reco SAW NA 61782 4 Ginna S SAW NA 61782 5 Ginna N SAW NA 61782 125 100
'I 75
&o 50 25-0.
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F 0 1 02 03 e 4 Cm"vc F1b LSE "w d-USE
.0 .0 -25.4 .0 2 .0 i00, 0 .0 143.8 169. 2 3 .0 I00 0 .0 106.5 131.9 4 .0 100.0 .0 154.2 179.6 5 .0 100.0 .0 171.5 196.9 Figure 5-9 Charpy V-Notch Percent Shear vs. Temperature for the R. E. Ginna Reactor Vessel Surveillance Program Weld Metal WCAP-17036-NP May 2009 Revision 0
5-26 Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 04/03/2009 08:20 AM Data Set(s) Plotted Curve Plant Capsuke Material Ori. Heat #
GINNA UNIRR SAW NA 125P666 2 Ginna V SAW NA 125P666 3 Ginna R SAW NA 125P666 4 Ginna T SAW NA 125P666 5 Ginna S SAW NA 125P666 6 Ginna N SAW NA 125P666 300 250 200 p150 ISO 0
100 0 0 V 50 0
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Dog F 0 1 2 03 " 4 v 5 0 6 Cwve USE d-USE T @36 &-T @30 T @50 44T @50 2.2 90.0 .0 -64.7 S0 -16. 1 .0 2 2.2 135.0 45. 0 -34.0 30,7 30.5 46. 6 3 2.2 12. 8 .7.2 -6.1 58. 6 4. 1 20.2 4 2.2 117.7 27. 7 -23.7 41.0 14. 1 30.2 5 2. 2 103. 5 13.5 -25.8 38.9 31. 4 47.5 6 88. 3 -1. 7 43.0 107.7 58.4 74.5 Figure 5-10 Charpy V-Notch Impact Energy vs. Temperature for the R. E. Ginna Reactor Vessel Heat-Affected-Zone Material May 2009 WCAP- 17036-NP WCAP-17036-NP May 2009 Revision 0
5-27 Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 04/03/2009 08:24 AM Data Set(s) Plotted Curve Plant Capsuke Material Ori. Heat #
1 GINNA UNIRR SAW NA 125P666 2 Ginna V SAW NA 125P666 3 Ginna R SAW NA 125P666 4 Ginna T SAW NA 125P666 5 Ginna S SAW NA 125P666 6 Ginna N SAW NA 125P666 200 150
.9 E
C 100 1.
50 0 4-
-300.0 0.0 300.0 600.0 Temperature in Deg F 0 1 1 2 03 A 4 Flum LME USE 4-USE T @35 d.T @35 1.0 76. 0 .0 -31.7 .0 2 1.0 90.6 14.6 -4.3 27 ý4 3 1.0 67. 2 -8.8 4. 3 36.0 4 1.0 61.4 -14.6 18.2 49. 9 5 1.0 64.5 -11.5 17.5 49. 2 6 1.0 59. 0 -17.0 56.5 88.2 Figure 5-11 Charpy V-Notch Lateral Expansion vs. Temperature for the R. E. Ginna Reactor Vessel Heat-Affected-Zone Material WCAP-17036-NP May 2009 Revision 0
5-28 Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 04/03/2009 08:51 AM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat #
2 GINNA UNIRR SAW NA 125P666 Ginna R SAW NA 125P666 3 Ginna T SAW NA 125P666 4 Ginna S SAW NA 125P666 5 Ginna N SAW NA 125P666 125 100 75-I 50o 25-0
-300.0 -200..0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F 0 1 Do2 0 3 ý 4 v 5 Cw~e Flueue LS USE d-USE T OM d-T 0s5
.0 100.0 .0 -27.7 .0 21 0 100.0 .0 29. 9 57.6 3 .0 100.0 .0 35.3 63.0 4 .0 100.0 .0 21.8 49. 5 5 .0 100.0 .0 86.0 113.7 Figure 5-12 Charpy V-Notch Percent Shear vs. Temperature for the R. E. Ginna Reactor Vessel Heat-Affected-Zone Material May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
5-29 Ginna Correlation Monitor Miaterial CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0N08/2009 09,44 PM Data Set(s) Plotted Curve Plant Capsuke Material Ori. Heat #
Ginna UNIRR SA302B LT A042 I 2 Ginna V SA302B LT A0421 3 Ginna R SA302B LT A0421 4 Ginna T SA302B LT A0421 300 250 p150
~100 so A
0 0
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Dog F 0 1 - 2 03 , 4 Curve fecue LS USE d-USE T 030 &.T030 T Off d-T 05 a
- 2. 2 67. 5 .0 30.2 .0 74. 5 .0 1
12- 68, 6 I. 1 127.2 97.0 1821 7 108.2 3 22 59. 5 -8.0 133.4 103.2 204. 6 130. 1 4 2.2 61. 2 -6. 3 128.0 97. 8 274. 3 199.8 Figure 5-13 Charpy V-Notch Impact Energy vs. Temperature for the R. E. Ginna Reactor Vessel Correlation Monitor Material WCAP-17036-NP May 2009 Revision 0
5-30 Ginna Correlation Monitor Material CVGIRAPH 5.3 Hyperbolic Tangent Curve Printed on 04/0.32009 08:17 PM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat #
1 Ginna UNIRR SA302B LT A0421!
2 Ginna V SA302B LT A0421!
3 Ginna R SA302B LT A0421I 4 Ginna T SA302B LT A0421 200 150 i
.2 IB so 50 0 +--
-300.0 0.0 300.0 600.0 Temperature in Deg F 0 1 2 0 3 4 Fblueu MSE USE i-USE T @35 d-T @35 1.0 60.0 .0 41.0 .0 2 1.0 53. 0 -7. 0 148.2 107. 2 3 Lo 59. 5 -. 5 157. 2 116 2 4 1.0 46. 6 -13.4 214.9 173.9 Figure 5-14 Charpy V-Notch Lateral Expansion vs. Temperature for the R. E. Ginna Reactor Vessel Correlation Monitor Material May 2009 17036-NP WCAP- 17036-NP May 2009 Revision 0
5-31 Ginna Correlation Monitor Material CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 04/03/2009 0& 19 PM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat #
Ginna UNIRR SA302B LT A0421 2 Ginna R SA302B LT A0421 3 Ginna T SA302B LT A0421 125 100 I 75 50 25
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F 0 D 2 Carve Mewm ISE USE 4-USE T @50 d-T 0"4
.0 t00.0 .0 43.2 .0 2 0 to0,0 .0 163. I 1tQ. 9 3 .0 too. 0 .0 164.7 t21. 5 Figure 5-15 Charpy V-Notch Percent Shear vs. Temperature for the R. E. Ginna Reactor Vessel Correlation Monitor Material WCAP-17036-NP May 2009 Revision 0
5-32 r
P47, -25°F P50, 20°F P53, 30°F P51, 40°F P54, 50°F P44,55°F P49,80°F P45, 90°F P52,100 0 F P46,350°F P48, 375°F P43,390°F Figure 5-16 Charpy Impact Specimen Fracture Surfaces for R. E. Ginna Reactor Vessel Lower Shell Forging 125P666 (Longitudinal Orientation)
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5-33 S43, 0°F S44, 20°F S53, 35-F S52, 40°F S46, 50°F S54, 60°F S50, 80°F S48, 90°F S47, 200°F S49, 350°F S51, 375°F S45, 390°F Figure 5-17 Charpy Impact Specimen Fracture Surfaces for R. E. Ginna Reactor Vessel Intermediate Shell Forging 125S255 (Longitudinal Orientation)
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5-34 W54, 0°F W47, 150°F W48, 200°F W45, 210°F W43, 220°F W53,230°F W49, 240°F W51, 260°F W50, 280°F W52, 350°F W44, 375°F W46, 400°F Figure 5-18 Charpy Impact Specimen Fracture Surfaces for the R. E. Ginna Reactor Vessel Surveillance Program Weld Metal WCAP-17036-NP May 2009 Revision 0
5-35 H48, 0°F H43, 35°F H50, 40°F H46, 50°F H52. 550 F
'm H54, 60°F H53, 80°F H47, 130°F H45, 350°F H49, 360°F H51, 375°F H44, 390°F Figure 5-19 Charpy Impact Specimen Fracture Surfaces for the R. E. Ginna Reactor Vessel Heat-Affected-Zone Material WCAP-17036-NP May 2009 Revision 0
5-36 Forging 125S255 120 100 80 --- Unirradiated 0.2% Yield Strength 9,
- 60 -- 11-Unirradiated Ultimate Strength 40 -*-CapsuleN 0.2% Yeld Strength 20 - Capsule N Ultimate Strengtri 0
0 200 400 600 800 Test Temperature, °F Forging 125S255 83 70 60 Unirradiated Total r51)
Elongation, %
43 U-nlralaeditdutln 4.t 40 --I--Unirradiated Reduction in CI I _i i i i !
Area, %
CL 39
-*-Cansule N Total Flongation, 23 13 - Capsule N Reduction in Area, 0
0 200 400 600 800 Test Temperature, 'F Figure 5-20 Tensile Properties for R. E. Ginna Reactor Vessel Intermediate Shell Forging 125S255 (Longitudinal Orientation)
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5-37 Forging 125P666 100 90
-I I_
70
--- Unirradiated 0.2% Yield 60 Strength 50 -U-Unirradiated Ultimate 40 -------------
Strength 30 - Capsule N 0.2% Yield Strength 20
Capsule N Ultimate Strength 10 0
0 200 400 600 800 Test Temperature, F Forging 125P666 80 70 60 4 Unirradiated Total Elongation, 50 C
- 40 --E-Unirradiated Reduction in
- o. 30 30 Area, %
-- *Capsule N Total Elongation, %
20 10 - Capsule N Reduction in Area, 0
0 200 400 600 800 Test Temperature, *F Figure 5-21 Tensile Properties for R. E. Ginna Reactor Vessel Lower Shell Forging 125P666 (Longitudinal Orientation)
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5-38 Weld 61782 120 100 -
!El 80o II II -- o- Unirradiated 0.2% Yield Strength 60 -- Unirradiated Jitinate Strength 40 Capsule N 0.2% Yield Strength 20 k-- - Capsule N Ultimate Strength 0
0 200 400 600 800 Test Temperature, °F Weld 61782 70 60 50
-po-Unirradiated Total
- 40E 40 ' orgation, Yo C-- Unirradiated Reduction ii
- 30 Area, %
C-.-
-- *-Capsule N Total Elongation,%
20 10 -=- --- Capsule N Reductioi in Area, 0 200 400 600 800 Test Temperature, "F Figure 5-22 Tensile Properties for the R. E. Ginna Reactor Vessel Surveillance Program Weld Metal WCAP- 17036-NP May 2009 Revision 0
5-39 Specimen P25- Tested at 150OF Specimen P27- Tested at 550'F Figure 5-23 Fractured Tensile Specimens from R. E. Ginna Reactor Vessel Lower Shell Forging 125P666 (Longitudinal Orientation)
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5-40 Specimen S25- Tested at 125°F Specimen S27- Tested at 550'F Figure 5-24 Fractured Tensile Specimens from R. E. Ginna Reactor Vessel Intermediate Shell Forging 125S255 (Longitudinal Orientation)
May 2009 17036-NP WCAP- 17036-NP May 2009 Revision 0
5-41 Specimen W13- Tested at 125°F Specimen W14- Tested at 260'F Specimen W15- Tested at 550'F Figure 5-25 Fractured Tensile Specimens from the R. E. Ginna Reactor Vessel Surveillance Program Weld Metal Heat #61782 WCAP-17036-NP May 2009 Revision 0
5-42 GINNA CAPSULE N 100 90 80 70 0560
' 50 40 P25 30 150°F 20 10 0
0 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN, IN/IN GINNA CAPSULE N 90 80 70 60 50 40 30 P26 325°F 20 10 0 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN, IN/IN Figure 5-26 Engineering Stress-Strain Curves for R. E. Ginna Lower Shell Forging 125P666 Tensile Specimens P-25 and P-26 (Longitudinal Orientation)
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5-43 GINNA CAPSULE N 100 90 80 70 Fn 60 50 30 40 30 P27 550TF 20 10 0
0 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN, IN/IN Figure 5-27 Engineering Stress-Strain Curve for R. E. Ginna Lower Shell Forging 125P666 Tensile Specimen P-27 (Longitudinal Orientation)
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5-44 GINNA CAPSULE N 120 100 80 w0 6 40 S25 125TF 20 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN, IN/IN GINNA CAPSULE N 100 90 80 70 60 Q
50 I-40 30 S26 300°F 20 10 0 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN, INIIN Figure 5-28 Engineering Stress-Strain Curves for R. E. Ginna Surveillance Program Intermediate Shell Forging 125S255 Tensile Specimens S-25 and S-26 (Longitudinal Orientation)
May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
5-45 GINNA CAPSULE N 120 100 80 60 40 SS277 550*F 20 0
0 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN, IN/IN Figure 5-29 Engineering Stress-Strain Curve for R. E. Ginna Surveillance Program Intermediate Shell Forging 125S255 Tensile Specimen S-27 WCAP-17036-NP May 2009 Revision 0
5-46 GINNA CAPSULE N 120 100 80 60 40 W13 125°F 20 0* 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN, IN/IN GINNA CAPSULE N 120 100 80 60 40 W14 260°F 20 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN, IN/IN Figure 5-30 Engineering Stress-Strain Curves for R. E. Ginna Surveillance Program Weld Metal Heat 61782 Tensile Specimens W-13 and W-14 (Note: A temporary signal loss to the plotter occurred during the course of this test. This loss of data to the plotter had no adverse impact to tensile data analysis for specimen W-14)
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5-47 GINNA CAPSULE N 120 100 80 0 60 40 W15 550°F 20 0 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN, IN/IN Figure 5-31 Engineering Stress-Strain Curve for R. E. Ginna Surveillance Program Weld Metal Heat 61782 Tensile Specimen W-15 WCAP- 17036-NP May 2009 Revision 0
6-1 6 RADIATION ANALYSIS AND NEUTRON DOSIMETRY
6.1 INTRODUCTION
This section describes a discrete ordinates S,, transport analysis performed for the R. E. Ginna reactor to determine the neutron radiation environment within the reactor pressure vessel and surveillance capsules.
In this analysis, fast neutron exposure parameters in terms of fast neutron fluence (E > 1.0 MeV) and iron atom displacements (dpa) were established on a plant and fuel cycle specific basis. An evaluation of the most recent dosimetry sensor set from Capsule N, withdrawn at the end of the thirty-third plant operating cycle, is provided. In addition, dosimetry results of, the sensor sets from the previously withdrawn capsules (V, R, T, and S) are also presented in Appendix A of this report. Comparisons of the results from these dosimetry evaluations with the analytical predictions served to validate the plant-specific neutron transport calculations. These validated calculations subsequently formed the basis for providing projections of the neutron exposure of the reactor pressure vessel for operating periods extending to 54 Effective Full Power Years (EFPY).
The use of fast neutron fluence (E > 1.0 MeV) to correlate measured material property changes to the neutron exposure of the material has traditionally been accepted for the development of damage trend curves as well as for the implementation of trend curve data to assess the condition of the vessel. In recent years, however, it has been suggested that an exposure model that accounts for differences in neutron energy spectra between surveillance capsule locations and positions within the vessel wall could lead to an improvement in the uncertainties associated with damage trend curves and improved accuracy in the evaluation of damage gradients through the reactor vessel wall.
Because of this potential shift away from a threshold fluence toward an energy-dependent damage function for data correlation, ASTM Standard Practice E853-01, "Analysis and Interpretation of Light-Water Reactor Surveillance Results," [22] recommends reporting displacements per iron atom (dpa) along with fluence (E > 1.0 MeV) to provide a database for future reference. The energy-dependent dpa function to be used for this evaluation is specified in ASTM Standard Practice E693-01, "Standard Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements per Atom" [23]. The application of the dpa parameter to the assessment of embrittlement gradients through the thickness of the reactor vessel wall has already been promulgated in Revision 2 to Regulatory Guide 1.99, "Radiation Embrittlement of Reactor Vessel Materials" [1].
All of the calculations and dosimetry evaluations described in this section and in Appendix A were based on the latest available nuclear cross-section data derived from ENDF/B-VI and made use of the latest available calculational tools. Furthermore, the neutron' transport and dosimetry evaluation methodologies follow the guidance of Regulatory Guide 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence" [24]. Additionally, the methods used to develop the calculated pressure vessel fluence are consistent with the NRC approved methodology described in WCAP-14040-A, Revision 4, "Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves," May 2004 [25].
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6-2 6.2 DISCRETE ORDINATES ANALYSIS A plan view of the R. E. Ginna reactor geometry at the core midplane is shown in Figure 4-1. Six irradiation capsules attached to the thermal shield are included in the reactor design that constitutes the reactor vessel surveillance program. The capsules are located at azimuthal angles of 570, 67', 770, 2370, 2470, and 257' as shown in Figure 4-1. These full-core positions correspond to the following octant symmetric locations represented in Figure 6-1: 130 from the core cardinal axes (for the 77' and 257' surveillance capsule holder locations), 23' from the core cardinal axes (for the 670 and 247' surveillance capsule holder locations) and 330 from the core cardinal axes (for the 570 and the 2370 surveillance capsule holder locations). The six capsules were positioned in the reactor vessel between the thermal shield and the vessel wall as shown in Figure 4-1. The vertical center of the capsule is opposite the vertical center of the core.
From a neutronic standpoint, the surveillance capsules and associated support structures are significant.
The presence of these materials has a marked effect on both the spatial distribution of neutron flux and the neutron energy spectrum in the water annulus between the neutron pads and the reactor vessel. In order to determine the neutron environment at the test specimen location, the capsules themselves must be included in the analytical model.
In performing the fast neutron exposure evaluations for the R. E. Ginna reactor vessel and surveillance capsules, a series of fuel cycle specific forward transport calculations were carried out using the following three-dimensional flux synthesis technique:
p(r, 0, z) = p(r, 0)
- p(r, z)
T(r) where 4(r,0,z) is the synthesized three-dimensional neutron flux distribution, 4(r,0) is the transport solution in (r,0) geometry, 4(rz) is the two-dimensional solution for a cylindrical reactor model using the actual axial core power distribution, and 4(r) is the one-dimensional solution for a cylindrical reactor model using the same source per unit height as that used in the (r,0) two-dimensional calculation. This synthesis procedure was carried out for each operating cycle at R. E. Ginna.
For the R. E. Ginna transport calculations, the (r,0) model depicted in Figure 6-1 was utilized since the reactor is octant symmetric. The (r,0) model includes the core, the reactor internals, the thermal shield -
including explicit representations of surveillance capsules at 13', 230 and 330, the pressure vessel cladding and vessel wall, the insulation external to the pressure vessel, and the primary biological shield wall. This model formed the basis for the calculated results and enabled making comparisons to the surveillance capsule dosimetry evaluations. In developing these analytical models, nominal design dimensions were employed for the various structural components. Likewise, water temperatures, and hence, coolant densities in the reactor core and downcomer regions of the reactor were taken to be representative of full power operating conditions. The coolant densities were treated on a fuel cycle specific basis. The reactor core itself was treated as a homogeneous mixture of fuel, cladding, water, and miscellaneous core structures such as fuel assembly grids, guide tubes, et cetera. The geometric mesh description of the (r,0) reactor model consisted of 148 radial by 105 azimuthal intervals. Mesh sizes were chosen to assure that proper convergence of the inner iterations was achieved on a pointwise basis. The pointwise inner iteration flux convergence criterion utilized in the (r,0) calculations was set at a value of 0.001.
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6-3 The (r,z) model used for the R. E. Ginna calculations is shown in Figure 6-2 and extends radially from the centerline of the reactor core out to a location interior to the primary biological shield and over an axial span from an elevation one foot below the active fuel to one foot above the active fuel. As in the case of the (r,0) models, nominal design dimensions and full power coolant densities were employed in the calculations. In this case, the homogenous core region was treated as an equivalent cylinder with a volume equal to that of the active core zone. The stainless steel former plates located between the core baffle and core barrel regions were also explicitly included in the model. The (rz) geometric mesh description of the reactor model consisted of 127 radial by 155 axial intervals. As in the case of the (r,0) calculations, mesh sizes were chosen to assure that proper convergence of the inner iterations was achieved on a pointwise basis. The pointwise inner iteration flux convergence criterion utilized in the (r,z) calculations was also set at a value of 0.001.
The one-dimensional radial (r) model used in the synthesis procedure consisted of the same 127 radial mesh intervals included in the (rz) model. Thus, radial synthesis factors could be determined on a meshwise basis throughout the entire geometry.
The core power distributions used in the plant-specific transport analysis were provided by the Nuclear Fuels Division of Westinghouse for each of the first thirty-three fuel cycles at R. E. Ginna. Specifically, the data utilized included cycle-dependent fuel assembly initial enrichments, burnups, and axial power distributions. This information was used to develop spatial and energy dependent core source distributions averaged over each individual fuel cycle. Therefore, the results from the neutron transport calculations provided data in terms of fuel cycle averaged neutron flux, which when multiplied by the appropriate fuel cycle length, generated the incremental fast neutron exposure for each fuel cycle. In constructing these core source distributions, the energy distribution of the source was based on an appropriate fission split for uranium and plutonium isotopes based on the initial enrichment and bumup history of individual fuel assemblies. From these assembly-dependent fission splits, composite values of energy release per fission, neutron yield per fission, and fission spectrum were determined.
All of the transport calculations supporting this analysis were carried out using the DORT discrete ordinates code Version 3.2 [26] and the BUGLE-96 cross-section library [27]. The BUGLE-96 library provides a 67-group coupled neutron-gamma ray cross-section data set produced specifically for light water reactor (LWR) applications. In these analyses, anisotropic scattering was treated with a P 5 legendre expansion and angular discretization was modeled with an S1 6 order of angular quadrature. Energy and space dependent core power distributions, as well as system operating temperatures, were treated on a fuel cycle ýpecific basis.
Selected results from the neutron transport analyses are provided in Tables 6-1 through 6-6. In Table 6-1, the calculated integrated exposures, expressed in terms of both neutron fluence (E > 1.0 MeV) and dpa, are given at the radial and axial center of the surveillance capsule at each individual azimuthal position, i.e., at 13', 230, and 33'. These results, representative of the axial midplane of the active core, establish the calculated exposure of the surveillance capsules withdrawn to date as well as projected into the future.
Similar information is provided in Table 6-2 for the reactor vessel inner radius at four azimuthal locations.
The vessel data given in Table 6-2 were taken at the clad/base metal interface, and thus, represent maximum calculated exposure levels on the vessel.
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6-4 From the data provided in Table 6-2, it is noted that the peak clad/base metal interface vessel fluence (E > 1.0 MeV) at the end of the thirty-third fuel cycle (i.e., after 30.5 EFPY of plant operation) was 3.20x109 n/cm 2.
Both calculated fluence (E > 1.0 MeV) and dpa data are provided in Tables 6-1 and 6-2. These data tabulations include both plant and fuel cycle specific calculated neutron exposures at the end of the thirty-third fuel cycle as well as future projections to 31.8, 33.3, 36, 42, 48, 52, 53, and 54 EFPY. The calculations account for an uprate from 1520 MWt to 1775 MWt that occurred at the onset of Cycle 33.
Projections for Cycles 35 and beyond were based on the conservative assumption that the core power distribution for Cycle 33 was applicable, along with a power level of 1811 MWt. Similar data applicable to the intermediate shell to nozzle shell circumferential weld are provided in Table 6-3.
Radial gradient information applicable to fast (E > 1.0 MeV) neutron fluence and dpa are given in Tables 6-4 and 6-5, respectively. The data, based on the cumulative integrated exposures from Cycles 1 through 33, are presented on a relative basis for each exposure parameter at several azimuthal locations.
Exposure distributions through the vessel wall maybe obtained by multiplying the calculated exposure at the vessel inner radius by the gradient data listed in Tables 6-4 and 6-5.
The calculated fast neutron exposures for the five surveillance capsules withdrawn from R. E. Ginna reactor are provided in Table 6-6. These assigned neutron exposure levels are based on the plant and fuel cycle-specific neutron transport calculations performed for the R. E. Ginna reactor.
2 From the data provided in Table 6-6, Capsule N received a fluence (E > 1.0 MeV) of 5.80x1019 n/cm after exposure through the end of the thirty-third fuel cycle (i.e., after 30.5 EFPY of plant operation).
Lead factors for the R. E. Ginna surveillance capsules are provided in Table 6-7. The capsule lead factor is defined as the ratio of the calculated fluence (E > 1.0 MeV) at the geometric center of the surveillance capsule to the corresponding maximum calculated fluence at the pressure vessel clad/base metal interface.
In Table 6-7, the lead factors for capsules that have been withdrawn from the reactor (V, R, T, S, and N) were based on the calculated fluence values for the irradiation period corresponding to the time of withdrawal for the individual capsules.
6.3 NEUTRON DOSIMETRY The validity of the calculated neutron exposures previously reported in Section 6.2 is demonstrated by a direct comparison against the measured sensor reaction rates and via a least squares evaluation performed for each of the capsule dosimetry sets. However, since the neutron dosimetry measurement data merely serves to validate the calculated results, only the direct comparison of measured-to-calculated results for the most recent surveillance capsule removed from service is provided in this section of the report. For completeness, the assessment of all measured dosimetry removed to date, based on both direct and least squares evaluation comparisons, is documented in Appendix A.
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6-5 The direct comparison of measured versus calculated fast neutron threshold reaction rates for the sensors from Capsule N, that was withdrawn from R. E. Ginna at the end of the thirty-third fuel cycle, is summarized below.
Reaction Rates (rps/atom)
Reaction Measured Calculated M/C Ratio 63 Cu(n,x)6 °Co 4.06E- 17 3.87E-17 1.05 54 Fe(n,p) 54Mn 3.37E-15 4.19E-15 0.80 58 Ni(n,p) 58 Co 5.07E- 15 5.77E-15 0.88 238 U(n,f)137 Cs (Cd) 2.13E-14 2.08E-14 1.02 237 Np(n,f)137 Cs (Cd) 2.45E-13 1.67E-13 1.47 Average: 1.04
% Standard Deviation: 24.8 The measured-to-calculated (M/C) reaction rate ratios for the Capsule N threshold reactions range from 0.80 to 1.47, and the average M/C ratio is 1.04 +/- 24.8% (la). This direct comparison falls outside the
+/- 20% criterion specified in Regulatory Guide 1.190; however, the overall average of all five extracted capsules is within the +/- 20% criterion specified in the Regulatory Guide. As demonstrated in the full set of comparisons given in Appendix A for all measured dosimetry removed to date from the R. E. Ginna reactor, these comparisons validate the current analytical results described in Section 6.2; therefore, the calculations are deemed applicable for R. E. Ginna.
6.4 CALCULATIONAL UNCERTAINTIES The uncertainty associated with the calculated neutron exposure of the R. E. Ginna surveillance capsule and reactor pressure vessel is based on the recommended approach provided in Regulatory Guide 1.190.
In particular, the qualification of the methodology was carried out in the following four stages:
- 1. Comparison of calculations with benchmark measurements from the Pool Critical Assembly (PCA) simulator at the Oak Ridge National Laboratory (ORNL).
- 2. Comparisons of calculations with surveillance capsule and reactor cavity measurements from the H. B. Robinson power reactor benchmark experiment.
- 3. An analytical sensitivity study addressing the uncertainty components resulting from important input parameters applicable to the plant-specific transport calculations used in the neutron exposure assessments.
- 4. Comparisons of the plant-specific calculations with all available dosimetry results from the R. E. Ginna surveillance program.
WCAP-17036-NP May 2009 Revision 0
6-6 The first phase of the methods qualification (PCA comparisons) addressed the adequacy of basic transport calculation and dosimetry evaluation techniques and associated cross-sections. This phase, however, did not test the accuracy of commercial core neutron source calculations nor did it address uncertainties in operational or geometric variables that impact power reactor calculations. The second phase of the qualification (H. B. Robinson comparisons) addressed uncertainties in these additional areas that are primarily methods related and would tend to apply generically to all fast neutron exposure evaluations.
The third phase of the qualification (analytical sensitivity study) identified the potential uncertainties introduced into the overall evaluation due to calculational methods approximations as well as to a lack of knowledge relative to various plant-specific input parameters.. The overall calculational uncertainty applicable to the R. E. Ginna analysis was established from results of these three phases of the methods qualification.
The fourth phase of the uncertainty assessment (comparisons with R. E. Ginna measurements) was used solely to demonstrate the validity of the transport calculations and to confirm the uncertainty estimates associated with the analytical results. The comparison was used only as a check and was not used in any way to modify the calculated surveillance capsule and pressure vessel neutron exposures previously described in Section 6.2. As such, the validation of the R. E. Ginna analytical model based on the measured plant dosimetry is completely described in Appendix A.
The following summarizes the uncertainties developed from the first three phases of the methodology qualification. Additional information pertinent to these evaluations is provided in [25].
Capsule Vessel IR PCA Comparisons 3% 3%
H. B. Robinson Comparisons 3% 3%
Analytical Sensitivity Studies 10% 11%
Additional Uncertainty for Factors not Explicitly Evaluated 5% 5%
Net Calculational Uncertainty 12% 13%
The net calculational uncertainty was determined by combining the individual components in quadrature.
Therefore, the resultant uncertainty was treated as random and no systematic bias was applied to the analytical results.
The R. E. Girma plant-specific measurement comparisons in Appendix A support these assessments.
May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
6-7 Table 6-1A Calculated Neutron Fluence - Surveillance Capsule Center Table 6-4A Calculated Neutron Fluence - Surveillance Capsule Center (CyEl> 1.0 MeV) (n/cm121 Cycle IEFPY 130 230 33° la 0.7 2.50E+ 18 1.47E+ 18 1.40E+18 lb 1.4 5.87E+ 18 3.3 7E+ 18 3.10E+18 2 1.6 6.83E+ 18 3.93E+18 3.64E+ 18 3 2.6 1.02E+ 19 5.86E+ 18 5.45-E+ 18 4 3.2 1.26E+-19 7.48E+18 7.06E+ 18 5 3.8 1.50E+19 8.89E+18 8.36E+ 18 6 4.6 1.84E+19 1.09E+ 19 1.02E+ 19 7 5.3 2.12E+ 19 1.27E+19 1. 19E+ 19 8 6.0 2.45E+19 1.46E+ 19 1.37E+19 9 6.9 2.81E+19 1.69E+ 19 1.59E+19 10 7.7 3.12E+19 1.89E+19 1.79E+19 11 8.2 3.36E+19 2.02E+ 19 1.91E+19 12 9.0 3.68E+ 19 2.19E+19 2.06E+ 19 13 9.6 3.91 E+ 19 2.34E+19 2.20E+19 14 10.4 4.16E+ 19 2.51 E+ 19 2.36E+ 19 15 11.2 4.39E+19 2.68E+19 2.53E+19 16 12.0 4.65E+19 2.84E+19 2.69E+19 17 12.9 4.95E+19 3.02E+19 2.86E+19 18 13.9 5.22E+ 19 3.21 E+ 19 3.04E+ 19 19 14.6 5.44E+ 19 3.36E+ 19 3.18E1+19 20 15.4 5.69E+ 19 3.52E+ 19 3.33E+19 21 16.2 5.95E+19 3.69E+ 19 3.48E+19 22 17.0 6.21E+19 3.86E+ 19 3.64E+ 19 23 17.8 6.45E+19 4.01E+19 3.79E+19 24 18.6 6.70E+ 19 4.17E+19 3.94E+ 19 25 19.5 6.93E+ 19 4.32E+-19 4.09E+ 19 26 20.7 7.23E+19 4.5 1E+19 4.27E+19 27 22.0 7.54E+ 19 4.70E+ 19 4.44E+19 28 23.4 7.88E+19 4.92E+19 4.65E+19 29 24.8 8.19E+ 19 5.13E+19 4.86E+19 30 26.1 8.51 E+ 19 5.34E+ 19 5.06E+ 19 31 27.5 8.85E+19 5.55E+ 19 5.27E+19 32 29.0 9.3 1E+19 5.82E+19 5.54E+ 19 33 30.5 9.75E+19 6.09E+19 5.80E+19 34 31.8 1.O1E+20 6.34E+19 6.05E+19 35 33.3 1.06E+20 6.62E+19 6.33E+19 future 36 1.14E+20 7.12E+19 6.82E+19 future 42 1.33E+20 8.22E+ 19 7.91 E+19 future 48 1.51E+20 9.33E+19 9.OOE+19 future 52 1.63E+20 1.01E+20 9.73E+19 future 53 1.66E+20 1.03E+20 9.91E+19 future 54 1.69E+20 1.04E+20 1.O1E+20
-' I Data in shaded area are estimates based on projected future operations.
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6-8 Table 6-1 B Calculated Iron Atom Displacement at Surveillance Capsule Center Table 6-lB Calculated Iron Atom Displacement at Surveillance Capsule Center Iron atom displacement (dpa)
Cycle I EFPY 130 230 330 la 0.7 4.56E-03 2.56E-03 2.46E-03 lb 1.4 1.07E-02 5.87E-03 5.44E-03 2 1.6 1.25E-02 6.86E-03 6.39E-03 3 2.6 1.85E-02 1.02E-02 9.58E-03 4 3.2 2.29E-02 1.30E-02 1.24E-02 5 3.8 2.73E-02 1.55E-02 1.47E-02 6 4.6 3.35E-02 1.91 E-02 1.79E-02 7 5.3 3.87E-02 2.22E-02 2.09E-02 8 6.0 4.46E-02 2.55E-02 2.4 1E-02 9 6.9 5.12E-02 2.94E-02 2.80E-02 10 7.7 5.69E-02 3.29E-02 3.15E-02 11 8.2 6.12E-02 3.52E-02 3.36E-02 12 9.0 6.71E-02 3.82E-02 3.62E-02 13 9.6 7.13E-02 4.08E-02 3.86E-02 14 10.4 7.57E-02 4.37E-02 4.15E-02 15 11.2 7.99E-02 4.66E-02 4.44E-02 16 12.0 8.47E-02 4.95E-02 4.73E-02 17 12.9 9.OOE-02 5.26E-02 5.02E-02 18 13.9 9.5 1E-02 5.59E-02 5.33E-02 19 14.6 9.90E-02 5.84E-02 5.58E-02 20 15.4 1.04E-01 6.12E-02 5.84E-02 21 16.2 1.08E-01 6.41E-02 6.11E-02 22 17.0 1.13E-0 I 6.70E-02 6.38E-02 23 17.8 1.17E-01 6.98E-02 6.65E-02 24 18.6 1.22E-01 7.25E-02 6.9 1E-02 25 19.5 1.26E-01 7.5 1E-02 7.17E-02 26 20.7 1.3 1E-01 7.84E-02 7.48E-02 27 22.0 1.37E-01 8.16E-02 7.79E-02 28 23.4 1.43E-01 8.54E-02 8.15E-02 29 24.8 1.49E-01 8.90E-02 8.5 1E-02 30 26.1 1.54E-01 9.26E-02 8.87E-02 31 27.5 1.60E-01 9.63E-02 9.23E-02 32 29.0 1.69E-01 1.01 E-0 I 9.70E-02 33 30.5 1.77E-01 1.06E-01 1.02E-01 34 31.8 1.84E-01 1.1OE-01 1.06E-01 35 33.3 1.92E-01 1.15E-01 1.111E-01 future 36 2.07E-01 1.23E-01 1.19E-0 1 future 42 2.40E-01 1.43E-01 1.38E-01 future 48 2.73E-01 1.62E-01 1.57E-01 future 52 2.95E-01 1.75E-01 1.70E-01 future 53 3.01 E-0 1 1.78E-01 1.73E-01 future 54 3.06E-01 1.811E-01 1.76E-01 Data in shaded area are estimates based on projected future operations.
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6-9 Table 6-2A Calculated Maximum Fluence at the Vessel Clad/Base Metal Interface Table 6-2A Calculated Maximum Fluence at the Vessel Clad/Base Metal Interface Cycle EFPYCyl3FP I -12 (Dl(E > 1.0 MeV) (n/cm2) " 45-la 0.7 8.46E+ 17 5.14E+ 17 3.57E+-17 3.OOE+ 17 lb 1.4 1.99E+ 18 1.20E+ 18 7.97E+ 17 6.64E+ 17 2 1.6 2.3 1E+18 1.40E+ 18 9.34E+17 7.84E+ 17 3 2.6 3.41E+18 2.08E+ 18 1.40E+ 18 1.19E+ 18 4 3.2 4.20E+ 18 2.60E+ 18 1.81E+18 1.55E+ 18 5 3.8 5.01E+18 3.09E+ 18 2.14E+ 18 1.82E+ 18 6 4.6 6.12E+18 3.79E+ 18 2.61E+18 2.19E+-18 7 5.3 7.03E+18 4.38E+18 3.04E+ 18 2.54E+ 18 8 6.0 8.09E+ 18 5.02E+ 18 3.48E+ 18 2.92E+ 18 9 6.9 9.26E+18 5.75E+ 18 4.03 E+ 18 3.40E+ 18 10 7.7 1.03E+19 6.39E+ 18 4.52E+18 3.82E+ 18 11 8.2 1.10E+19 6.86E+18 4.82E+18 4.11E+18 12 9.0 1.2 1E+19 7.50E+ 18 5.20E+ 18 4.46E+ 18 13 9.6 1.29E+ 19 7.98E+ 18 5.54E+ 18 4.75E+-18 14 10.4 1.37E+19 8.49E+ 18 5.95E+ 18 5.14E+ 18 15 11.2 1.44E+ 19 8.98E+ 18 6.36E+18 5.56E+18 16 12.0 1.52E+19 9.52E+18 6.76E+ 18 5.98E+18 17 12.9 1.62E+19 1.01E+19 7.19E+-18 6.37E+18 18 13.9 171E+19 1.07E+19 7.64E+ 18 6.76E+ 18 19 14.6 1.78E+19 1.12E+-19 7.99E+ 18 7.09E+ 18 20 15.4 1.86E+19 1.17E+-19 8.37E+18 7.42E+ 18 21 16.2 1.94E+ 19 1.23E+19 8.77E+ 18 7.77E+18 22 17.0 2.03 E+ 19 1.28E+ 19 9.17E+ 18 8.12E+18 23 17.8 2.11E+19 1.33E+19 9.55E+18 8.48E+ 18 24 18.6 2.19E+ 19 1.38E+19 9.93E+18 8.82E+18 25 19.5 2.26E+ 19 1.43E+ 19 1.03E+19 9.15E+18 26 20.7 2.36E+19 1.49E+19 1.07E+ 19 9.56E+18 27 22.0 2.47E+ 19 1.56E+19 1. 12E+ 19 9.98E+18 28 23.4 2.58E+19 1.63E+19 1. 17E+ 19 1.04E+19 29 24.8 2.68E+ 19 1.69E+ 19 1.22E+19 1.09E+-19 30 26.1 2.78E+ 19 1.76E+19 1.27E+ 19 1.14E+-19 31 27.5 2.89E+19 1.83E+19 1.32E+19 1. 18E+ 19 32 29.0 3.05E+19 1.92E+19 1.39E+19 1.25E+19 33 30.5 3.20E+ 19 2.01E+19 1.45E+19 1.31E+19 34 31.8 3.32E+19 2.09E+19 1.52E+19 1.37E+19 35 33.3 3.48E+ 19 2.18E+19 1.58E+19 1.44E+19 future 36 3.76E+19 2.35E+19 1.70E+ 19 1.56E+19 future 42 4.40E+19 2.73E+19 1.97E+ 19 1.82E+19 future 48 5.03E+19 3.10E+19 2.24E+19 2.08E+19 future 52 5.45E+19 3.35E+19 2.42E+19 2.26E+19 future 53 5.56E+ 19 3.42E+19 2.46E+19 2.30E+19 future 54 5.66E+ 19 3.48E+19 2.51E+19 2.35E+19 Data in shaded area are estimates based on projected future operations.
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6-10 Table 6-2B Calculated Maximum Iron Atom Displacement at Vessel Clad/Base Metal Interface I Table 6-2B Calculated Maximum Iron Atom Displacement at Vessel Clad/Base Metal Interface I I _Iron atom displacement (dpa) 450 Cycle EFPY 1 00 150 300 la 0.7 1.38E-03 8.69E-04 5.87E-04 4.87E-04 lb 1.4 3.24E-03 2.04E-03 1.31E-03 1.08E-03 2 1.6 3.77E-03 2.37E-03 1.54E-03 1.27E-03 3 2.6 5.58E-03 3.52E-03 2.30E-03 1.93E-03 4 3.2 6.86E-03 4.39E-03 2.97E-03 2.51E-03 5 3.8 8.19E-03 5.23E-03 3.52E-03 2.96E-03 6 4.6 1.OOE-02 6.40E-03 4.30E-03 3.55 E-03 7 5.3 1.15E-02 7.39E-03 5.OOE-03 4.12E-03 8 6.0 1.32E-02 8.48E-03 5.73E-03 4.74E-03 9 6.9 1.51E-02 9.72E-03 6.63E-03 5.52E-03 10 7.7 1.68E-02 1.08E-02 7.43E-03 6.21E-03 11 8.2 1.80E-02 1.16E-02 7.94E-03 6.68E-03 12 9.0 1.98E-02 1.27E-02 8.56E-03 7.24E-03 13 9.6 2.11E-02 1.35E-02 9.12E-03 7.71E-03 14 10.4 2.24E-02 1.43E-02 9.79E-03 8.35E-03 15 11.2 2.35E-02 1.52E-02 1.05E-02 9.03E-03 16 12.0 2.48E-02 1.61E-02 1.11E-02 9.71E-03 17 12.9 2.65E-02 1.71E-02 1.18E-02 1.04E-02 18 13.9 2.80E-02 1.81E-02 1.26E-02 1.1OE-02 19 14.6 2.91E-02 1.89E-02 1.32E-02 1.15E-02 20 15.4 3.04E-02 1.98E-02 1.38E-02 1.21E-02 21 16.2 3.17E-02 2.07E-02 1.44E-02 1.26E-02 22 17.0 3.31E-02 2.16E-02 1.51E-02 1.32E-02 23 17.8 3.44E-02 2.25E-02 1.57E-02 1.38E-02 24 18.6 3.57E-02 2.33E-02 1.64E-02 1.43E-02 25 19.5 3.70E-02 2.42E-02 1.70E-02 1.49E-02 26 20.7 3.86E-02 2.52E-02 1.77E-02 1.55E-02 27 22.0 4.03E-02 2.63E-02 1.84E-02 1.62E-02 28 23.4 4.21E-02 2.74E-02 1.92E-02 1.69E-02 29 24.8 4.37E-02 2.85E-02 2.01E-02 1.77E-02 30 26.1 4.54E-02 2.96E-02 2.09E-02 1.84E-02 31 27.5 4.71E-02 3.08E-02 2.17E-02 1.92E-02 32 29.0 4.97E-02 3.23E-02 2.28E-02 2.02E-02 33 30.5 5.22E-02 3.39E-02 2.39E-02 2.13E-02 34 31.8 5.41E-02 3.52E-02 2.49E-02 2.22E-02 35 33.3 5.68E-02 3.68E-02 2.60E-02 2.33E-02 future 36 6.14E-02 3.96E-02 2.80E-02 2.52E-02 future 42 7.17E-02 4.59E-02 3.24E-02 2.95E-02 future 48 8.20E-02 5.23E-02 3.68E-02 3.37E-02 future 52 8.89E-02 5.65E-02 3.98E-02 3.66E-02 future 53 9.06E-02 5.75E-02 4.05E-02 3.73E-02 future 54 9.23E-02 5.86E-02 4.12E-02 3.80E-02 Data in shaded area are estimates based on projected future operations.
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6-11 Table 6-3A Calculated Maximum Fluence at the Pressure Vessel Intermediate Shell Course to Nozzle Shell Course Weld Table 6-3A Calculated Maximum Fluence at the Pressure 1
Vessel Intermediate Shell Course to Nozzle Shell Course Weld EFPY( 0 ~(E > 1.0 MeV) (n/c 450 Cycle I_______ __
EFP_0__1_150 _ 1 300 1_________
la 0.7 3.15E+16 1.92E+16 1.33E+16 1.12E+16 lb 1.4 7.37E+16 4.47E+16 2.96E+ 16 2.47E+ 16 2 1.6 8.57E+16 5.20E+ 16 3.46E+ 16 2.91E+16 3 2.6 1.29E+17 7.84E+-16 5.26E+ 16 4.48E+16 4 3.2 1.69E+17 1.05E+17 7.3 7E+ 16 6.32E+16 5 3.8 2.19E+ 17 1.35E+1 7 9.39E+16 8.01E+16 6 4.6 2.69E+ 17 1.67E+17 1.15E+17 9.67E+16 7 5.3 3.12E+ 17 1.95E+17 1.36E+17 1.13E+ 17 8 6.0 3.55E+17 2.20E+17 1.54E+ 17 1.29E+ 17 9 6.9 4.02E+ 17 2.50E+ 17 1.76E+17 1.48E+ 17 10 7.7 4.43E+17 2.76E+17 1.95E+17 1.65E+17 11 8.2 4.74E+ 17 2.95E+ 17 2.08E+17 1.77E+17 12 9.0 5.18E+17 3.21 E+ 17 2.23E+17 1.91E+17 13 9.6 5.50E+17 3.41E+17 2.37E+17 2.03E+-17 14 10.4 5.81E+17 3.61E+17 2.53E+ 17 2.18E+ 17 15 11.2 6.08E+ 17 3.80E+17 2.69E+ 17 2.35E+17 16 12.0 6.34E+ 17 3.97E+17 2.82E+17 2.48E+17 17 12.9 6.65E+ 17 4.16E+17 2.95E+ 17 2.60E+ 17 18 13.9 6.92E+17 4.33E+17 3.08E+ 17 2.71E+17 19 14.6 7. 15E+ 17 4.49E+ 17 3.20E+ 17 2.82E+17 20 15.4 7.40E+ 17 4.65E+17 3.32E+17 2.93E+17 21 16.2 7.65E+17 4.82E+17 3.44E+ 17 3.04E+ 17 22 17.0 7.91 E+ 17 4.99E+ 17 3.56E+ 17 3.14E+ 17 23 17.8 8.15E+17 5.14E+17 3.68E+17 3.25E+17 24 18.6 8.45E+17 5.33E+17 3.82E+17 3.38E+ 17 25 19.5 8.79E+17 5.55E+17 3.99E+ 17 3.53E+17 26 20.7 9.30E+ 17 5.87E+17 4.21E+17 3.73E+ 17 27 22.0 9.72E+17 6.12E+17 4.39E+ 17 3.90E+ 17 28 23.4 1.02E+18 6.39E+17 4.59E+ 17 4.08E+17 29 24.8 1.05E+ 18 6.64E+ 17 4.78E+17 4.26E+ 17 30 26.1 1.09E+18 6.89E+ 17 4.98E+ 17 4.43E+ 17 31 27.5 1.13E+18 7.16E+17 5.17E+ 17 4.62E+ 17 32 29.0 1.20E+ 18 7.52E+17 5.43 E+ 17 4.87E+17 33 30.5 1.27E+ 18 7.94E+ 17 5.73E+ 17 5.17E+17 34 31.8 1.32E+18 8.32E+17 6.03E+17 5.44E+ 17 35 33.3 1.40E+ 18 8.76E+17 6.34E+ 17 5.76E+17 future 36 1.53E+18 9.54E+17 6.90E+ 17 6.31E+17 future 42 1.83E+18 1.13E+18 8.16E+17 7.54E+ 17 future 48 2.12E+18 1.30E+18 9.41E+17 8.77E+ 17 future 52 2.32E+18 1.42E+18 1.02E+ 18 9.59E+17 future 53 2.37E+18 1.45E+18 1.05E+18 9.79E+17 future 54 2.42E+ 18 1.48E+18 1.07E+18 1.OOE+18
- &- i & i Data in shaded area are estimates based on projected future operations.
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6-12 Table 6-3B Calculated Maximum Iron Atom Displacement at the Pressure Vessel Intermediate Shell Course to Nozzle Shell Course Weld Table 6-3B Calculated Maximum Iron Atom Displacement at the Pressure Vessel Intermediate Shell Course to Nozzle Shell Course Weld II_ Iron atom displacement (dpa)
Cycle EFPV 1 00 150 300 450 la 0.7 5.47E-05 3.44E-05 2.33E-05 1.93E-05 lb 1.4 1.28E-04 8.03E-05 5.17E-05 4.25E-05 2 1.6 1.49E-04 9.34E-05 6.06E-05 5.02E-05 3 2.6 2.23E-04 1.41 E-04 9.21 E-05 7.72E-05 4 3.2 2.93E-04 1.88E-04 1.29E-04 1.09E-04 5 3.8 3.78E-04 2.42E-04 1.64E-04 1.38E-04 6 4.6 4.66E-04 2.99E-04 2.01E-04 1.66E-04 7 5.3 5.41 E-04 3.49E-04 2.37E-04 1.95E-04 8 6.0 6.15 E-04 3.95E-04 2.68E-04 2.22E-04 9 6.9 6.97E-04 4.48E-04 3.06E-04 2.55E-04 10 7.7 7.68E-04 4.95E-04 3.4 1E-04 2.85E-04 11 8.2 8.22E-04 5.30E-04 3.63E-04 3.05E-04 12 9.0 8.99E-04 5.76E-04 3.90E-04 3.29E-04 13 9.6 9.55E-04 6.12E-04 4.15E-04 3.50E-04 14 10.4 1.01E-03 6.47E-04 4.42E-04 3.76E-04 15 11.2 1.06E-03 6.82E-04 4.71 E-04 4.05E-04 16 12.0 1.1OE-03 7.13E-04 4.93E-04 4.28E-04 17 12.9 1.16E-03 7.47E-04 5.16E-04 4.49E-04 18 13.9 1.20E-03 7.79E-04 5.40E-04 4.69E-04 19 14.6 1.24E-03 8.06E-04 5.60E-04 4.87E-04 20 15.4 1.29E-03 8.36E-04 5.8 1E-04 5.06E-04 21 16.2 1.33E-03 8.67E-04 6.04E-04 5.25E-04 22 17.0 1.38E-03 8.96E-04 6.24E-04 5.43E-04 23 17.8 1.42E-03 9.25E-04 6.46E-04 5.62E-04 24 18.6 1.47E-03 9.59E-04 6.70E-04 5.84E-04 25 19.5 1.53E-03 9.99E-04 6.99E-04 6.1OE-04 26 20.7 1.62E-03 1.05E-03 7.38E-04 6.45E-04 27 22.0 1.69E-03 1.1OE-03 7.69E-04 6.74E-04 28 23.4 1.76E-03 1.15 E-03 8.04E-04 7.05E-04 29 24.8 1.83E-03 1. 19E-03 8.38E-04 7.35E-04 30 26.1 1.90E-03 1.24E-03 8.72E-04 7.66E-04 31 27.5 1.97E-03 1.29E-03 9.07E-04 7.98E-04 32 29.0 2.08E-03 1.35E-03 9.52E-04 8.42E-04 33 30.5 2.20E-03 1.43E-03 1.OOE-03 8.92E-04 34 31.8 2.30E-03 1.49E-03 1.06E-03 9.40E-04 35 33.3 2.43E-03 1.57E-03 1.11 E-03 9.94E-04 future 36 2.66E-03 1.71E-03 1.21E-03 1.09E-03 future 42 3.17E-03 2.02E-03 1.43E-03 1.30E-03 future 48 3.68E-03 2.34E-03 1.64E-03 1.51E-03 future 52 4.02E-03 2.54E-03 1.79E-03 1.65E-03 future 53 4.10E-03 2.60E-03 1.83E-03 1.68E-03 future 54 4.19E-03 2.65E-03 1.86E-03 1.72E-03 Data in shaded area are estimates based on projected future operations.
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6-13 Table 6-4 Relative Radial Distribution of Fast Neutron Fluence (n/cm 2) Within the Reactor Vessel Wall Table 6-4 Relative Radial Distribution of Fast Neutron Fluence (n/cm 2)
Within the Reactor Vessel Wall Radius Azimuthal Angle (cm) 00 150 300 450 168.04 1.000 1.000 1.000 1.000 172.25 0.638 0.645 0.635 0.645 176.46 0.364 0.374 0.366 0.372 180.66 0.200 0.210 0.205 0.208 184.87 0.103 0.116 0.114 0.113 Base Metal Inner Radius = 168.04 cm Base Metal 1/4T = 172.25 cm Base Metal 1/2T = 176.46 cm Base Metal 3/4T = 180.66 cm Base Metal Outer Radius = 184.87 cm Relative radial distribution based on the cumulative integrated exposures through plant life WCAP-17036-NP May 2009 Revision 0
6-14 Table 6-5 Relative Radial Distribution of Iron Atom Displacements (dpa) Within the Reactor Vessel Wall Table 6-5 Relative Radial Distribution of Iron Atom Displacements (dpa)
Within the Reactor Vessel Wall Azimuthal Angle Radius (cm) 00 150 300 450 168.04 1.000 1.000 1.000 1.000 172.25 0.708 0.724 0.712 0.715 176.46 0.472 0.497 0.486 0.484 180.66 0.304 0.333 0.326 0.320 184.87 0.179 0.212 0.213 0.204 Base Metal Inner Radius 168.04 cm Base Metal 1/4T = 172.25 cm Base Metal 1/2T = 176.46 cm Base Metal 3/4T = 180.66 cm Base Metal Outer Radius = 184.87 cm Relative radial distribution based on the cumulative integrated exposures through plant life Table 6-6 Calculated Fast Neutron Exposure of Surveillance Capsules Withdrawn from R.E. Ginna Table 6-6 Calculated Fast Neutron Exposure of Surveillance Capsules Withdrawn from R. E.
Ginna Irradiation Time Fluence (E > 1.0 MeV) Iron Displacements Capsule IEFPY] [n/cm 2 Idpal V 1.4 5.87E+18 1.07E-03 R 2.6 1.02E+19 1.85E-02 T 6.9 1.69E+19 2.94E-02 S 17.0 3.64E+19 6.38E-02 N 30.5 5.80E+19 1.02E-01 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
6-15 Table 6-7 Calculated Surveillance Capsule Lead Factors Table 6-7 Calculated Surveillance Capsule Lead Factors Capsule ID And Location Status Lead Factor V (130) Withdrawn EOC 1 2.96 R (13-) Withdrawn EOC 3 2.97 T (23-) Withdrawn EOC 9 1.82 S(33-) Withdrawn EOC 22 1.79 N (33-) Withdrawn EOC 33 1.82 P (23-) In Reactor 1.90 Note: Capsule P lead factor is based on EOC33 fluence distribution.
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6-16 R.E Ginna 2-loop reactor (r-theta model at core midplane)
Meshes: 148R,1058 43.7 87.4 131.1 174J 218.6 26 R Figure 6-1 R.E. Ginna (r,0) Reactor Geometry at the Core Midplane WCAP-17036-NP May 2009 Revision 0
6-17 R.E Ginna 2-loop reactor (r-z Model)
Meshes: 127X,155Y
- , m S.k- w %WMfMW a &W 5f S8Ipp a rMf Aib*
ft SM- .w I1- W NW1.l ;X Figure 6-2 R.E. Ginna (r, z) Reactor Geometry WCAP-1 7036-NP May 2009 Revision 0
7-1 7 SURVEILLANCE CAPSULE REMOVAL SCHEDULE The following surveillance capsule removal schedule meets the requirements of ASTM E185-82 [8] and is recommended for the future capsule to be removed from the R. E. Ginna reactor vessel. This recommended removal schedule is applicable to 53 EFPY of operation.
Table 7-1 Recommended Surveillance Capsule Withdrawal Schedule Not tes:
(a) Updated in Capsule N dosimetry analysis; see Table 6-6.
(b) EFPY from plant startup.
(c) Capsule P should be removed at about 33.9 EFPY to fulfill the commitment of [28] to remove the capsule shortly after it accumulates a fluence equivalent to 80 years of operation.
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8-1 8 REFERENCES
- 1. Regulatory Guide 1.99, Revision 2, Radiation Embrittlement of Reactor Vessel Materials, U.S. Nuclear Regulatory Commission, May, 1988.
- 2. 10 CFR 50, Appendix G, Fracture Toughness Requirements, and Appendix H, Reactor Vessel Material Surveillance Program Requirements, Federal Register, Volume 60, No. 243, December 19, 1995.
- 3. WCAP-7254, Revision 0, Rochester Gas and Electric Robert E. Ginna Unit No. I Reactor Vessel Radiation Surveillance Program, S. E. Yanichko, May 1969.
- 4. ASTM E185-66, Recommended Practicefor Surveillance Tests on StructuralMaterial in Nuclear Reactors, American Society for Testing and Materials, 1966.
- 5.Section XI of the ASME Boiler and Pressure Vessel Code, Appendix G, Fracture Toughness Criteriafor ProtectionAgainst Failure.
- 6. ASTM E208, StandardTest Methodfor Conducting Drop-Weight Test to Determine Nil-Ductility Transition Temperature of FerriticSteels, in ASTM Standards, Section 3, American Society for Testing and Materials, Philadelphia, PA.
- 7. WCAP-13902, Analysis of Capsule S from the Rochester Gas and Electric CorporationR. E.
Ginna Reactor Vessel Radiation Surveillance Program,J. M. Chicots, et. al., December 1993.
- 8. ASTM E185-82, Standard Practicefor Conducting Surveillance Tests for Light-Water Cooled NuclearPower Reactor Vessels, E706 (IF), ASTM 1982.
- 9. Westinghouse Science and Technology Department Procedure RMF 8402, Surveillance Capsule Testing Program, Revision 3, June 6, 2005.
- 10. Westinghouse Science and Technology Department Procedure RMF 8102, Tensile Testing, Revision 3, March 1, 1999.
- 11. Westinghouse Science and Technology Department Procedure RNIF 8103, Charpy Impact Testing, Revision 2, August 1, 1998.
- 12. Westinghouse Science and Technology Department Procedure RMF 8804, Opening of Westinghouse Surveillance Capsules, Revision 2, August 1, 2004.
- 13. ASTM E23-06, Standard Test Method for Notched Bar Impact Testing of Metallic Materials, ASTM, 2006.
- 14. General Yielding of Charpy V-Notch and Precracked Charpy Specimens, Journal of Engineering Materials and Technology, Vol. 100, April 1978, pp. 183-188.
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8-2
- 15. ASTM A370-07, Standard Test Methods and Definitions for Mechanical Testing of Steel Products,ASTM, 2007.
- 17. ASTM E21-05, Standard Test Methods for Elevated Temperature Tension Tests of Metallic Materials,ASTM, 2005.
- 18. FP-RA- 1, Analysis of Capsule V from the Rochester Gas and Electric R. E. Ginna Unit No. 1 Reactor Vessel Surveillance Program,T. R. Mager et al, March 1, 1973.
- 19. WCAP-8421, Analysis of Capsule R from the Rochester Gas & Electric CorporationR. E. Ginna Unit No. 1 Reactor Vessel RadiationSurveillance Program, S. E. Yanichko et al, November 1974.
- 20. WCAP-10086, Analysis of Capsule Tfrom the Rochester Gas and Electric Corporation R. E.
Ginna Nuclear Plant Reactor Vessel Radiation Surveillance Program, Topical Report, EPRI Research Project 1021-3, S. E. Yanichko et al, April 1982.
- 21. WCAP-10496, R. E. Ginna Reactor Vessel Surveillance Capsule T Reconstituted Weld Metal Charpy Impact Tests, S. E. Yanichko and R. P. Shogan, March 1984.
- 22. ASTM E853-01, Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Results, E706 (IA), ASTM, 2001
- 23. ASTM E693-01, StandardPracticefor CharacterizingNeutron Exposures in Iron and Low Alloy Steels in Terms of DisplacementsPer Atom (DPA), E706 (ID), ASTM, 2001.
- 24. Regulatory Guide 1.190, Calculationaland Dosimetry Methods for Determining Pressure Vessel Neutron Fluence, U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, March 2001.
- 25. WCAP-14040-A, Revision 4, Methodology Used to Develop Cold Overpressure Mitigating System Setpoints andRCS Heatup and Cooldown Limit Curves, May 2004.
- 26. RSICC Computer Code Collection CCC-650, DOORS 3.2.: One, Two- and Three Dimensional Discrete OrdinatesNeutron/Photon Transport Code System, April 1998.
- 27. RSICC Data Library Collection DLC-185, BUGLE-96, Coupled 47 Neutron, 20 Gamma-Ray Group Cross Section LibraryDerivedfrom ENDF/B-Vifor L WR Shielding and Pressure Vessel Dosimetry Applications, March 1996.
- 28. Safety Evaluation by the Office of Nuclear Reactor Regulation Related to Amendment No. 97 to Renewed Facility Operating License No. DPR-18 R. E. Ginna Nuclear Power Plant, Docket No.
50-244.
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A-I APPENDIX A VALIDATION OF THE RADIATION TRANSPORT MODELS BASED ON NEUTRON DOSIMETRY MEASUREMENTS A.1 NEUTRON DOSIMETRY Comparisons of measured dosimetry results to both the calculated and least squares adjusted values for all surveillance capsules withdrawn from service to date at R. E. Ginna are described herein. The sensor sets from these capsules have been analyzed in accordance with the current dosimetry evaluation methodology described in Regulatory Guide 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence" (Reference A-I). One of the main purposes for presenting this material is to demonstrate that the overall measurements agree with the calculated and least squares adjusted values to within +/- 20% as specified by Regulatory Guide 1.190, thus serving to validate the calculated neutron exposures previously reported in Section 6.2 of this report.
A.1.1 Sensor Reaction Rate Determinations In this section, the results of the evaluations of the five neutron sensor sets analyzed to date as part of the R. E. Ginna Reactor Vessel Materials Surveillance Program are presented. The capsule designation, location within the reactor, and time of withdrawal of each of these dosimetry sets were as follows:
Capsule ID Azimuthal Location Withdrawal Time Irradiation Time [EFPY]
V 130 End of Cycle 1 1.4 R 130 End of Cycle 3 2.6 T 230 End of Cycle 9 6.9 S 330 End of Cycle 22 17.0 N 330 End of Cycle 33 30.5 The azimuthal locations included in the above tabulation represent the first octant equivalent azimuthal angle of the geometric center of the respective surveillance capsules.
The passive neutron sensors included in the evaluations of Surveillance Capsules V, R, T, S, and N are summarized as follows:
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A-2 Reaction Of Sensor Material Interest Capsule V Capsule R Capsule T Capsule S Capsule N 63 60 Copper Cu(n,a) Co *1 '1 '1 54 Iron+ Fe(n,p) 5 4 Mn 1 58 58 Nickel Ni(n,p) Co '1 23 137 Uranium-238 8U(n,f) Cs ,/
23 7 Neptunium-237 Np(n,f) 137 Cs --
59 6 Cobalt-Aluminum* Co(n,y) °Co '1 V V V
+The iron specimens were obtained from Charpy test material instead of dosimetry sensors.
- The cobalt-aluminum measurements for this plant include both bare wire and cadmium-covered sensors.
Since not all of the dosimetry monitors are located at the radial center of the material test specimen array, radial gradient corrections were made for these reaction rates. Pertinent physical and nuclear characteristics of the passive neutron sensors are listed in Table A- 1.
The use of passive monitors such as those listed above does not yield a direct measure of the energy-dependent neutron flux at the point of interest. Rather, the activation or fission process is a measure of the integrated effect that the time and energy dependent neutron flux has on the target material over the course of the irradiation period. An accurate assessment of the average neutron flux level incident on the various monitors may be derived from the activation measurements only if the irradiation parameters are well known. In particular, the following variables are of interest:
- the measured specific activity of each monitor, 0 the physical characteristics of each monitor, 9 the operating history of the reactor, 0 the energy response of each monitor, and
- the neutron energy spectrum at the monitor location.
Results from the radiometric counting of the neutron sensors from Capsules V, R, T, and S are documented in Reference A-2. The radiometric counting of the sensors from Capsule N was carried out by Pace Analytical Services, Inc. In all cases, the radiometric counting followed established ASTM procedures. Following sample preparation and weighing, the specific activity of each sensor was determined by means of a high-resolution gamma spectrometer. For the copper, iron, nickel, and cobalt-aluminum sensors, these analyses were performed by direct counting of each of the individual samples.
In the case of the uranium and neptunium fission sensors, the analyses were carried out by direct counting preceded by dissolution and chemical separation of cesium from the sensor material.
The irradiation history of the reactor over the irradiation periods experienced by Capsules V, R, T, S, and N was based on the monthly power generation of R. E. Ginna from initial reactor criticality through the end of the dosimetry evaluation period. For the sensor sets utilized in the surveillance capsules, the half-WCAP-17036-NP May 2009 Revision 0
A-3 lives of the product isotopes are long enough that a monthly histogram describing reactor operation has proven to be an adequate representation for use in radioactive decay corrections for the reactions of interest in the exposure evaluations. The irradiation history for Capsule N encompassed thirty-three fuel cycles.
Having the measured specific activities, the physical characteristics of the sensors, and the operating history of the reactor, reaction rates referenced to full-power operation were determined from the following equation:
A No F Y Cj [1- e-QJ [e td]
Prcf where:
R = Reaction rate averaged over the irradiation period and referenced to operation at a core power level of Prcf (rps/nucleus).
A = Measured specific activity (dps/gm).
No = Number of target element atoms per gram of sensor.
F = Atom fraction of the target isotope in the target element.
Y = Number of product atoms produced per reaction.
Pi = Average core power level during irradiation period j (MW).
Pref = Maximum or reference power level of the reactor (MW).
C1 = Calculated ratio of 4(E > 1.0 MeV) during irradiation period j to the time weighted average 4(E > 1.0 MeV) over the entire irradiation period.
k = Decay constant of the product isotope (1/sec).
tj = Length of irradiation period j (sec).
td = Decay time following irradiation period j (sec).
and the summation is carried out over the total number of monthly intervals comprising the irradiation period.
In the equation describing the reaction rate calculation, the ratio [Pj]/[Pref] accounts for month-by-month variation of reactor core power level within any given fuel cycle as well as over multiple fuel cycles. The ratio Cj, which was calculated for each fuel cycle using the transport methodology discussed in Section 6.2, accounts for the change in sensor reaction rates caused by variations in flux level induced by WCAP-17036-NP May 2009 Revision 0
A-4 changes in core spatial power distributions from fuel cycle to fuel cycle. For a single-cycle irradiation, Cj is normally taken to be 1.0. However, for multiple-cycle irradiations, particularly those employing low leakage fuel management, the additional Cj term should be employed. The impact of changing flux levels for constant power operation can be quite significant for sensor sets that have been irradiated for many cycles in a reactor that has transitioned from non-low leakage to low leakage fuel management or for sensor sets contained in surveillance capsules that have been moved from one capsule location to another.
The fuel cycle specific neutron flux values are listed in Table A-2. These flux values represent the cycle dependent results at the radial and azimuthal center of the respective capsules at the axial elevation of the active fuel midplane.
Prior to using the measured reaction rates in the least-squares evaluations of the dosimetry sensor sets, additional corrections were made to the 238U measurements to account for the presence of 235U impurities in the sensors as well as to adjust for the build-in of plutonium isotopes over the course of the irradiation.
Corrections were also made to the 238U and 237Np sensor reaction rates to account for gamma ray induced fission reactions that occurred over the course of the capsule irradiations. The correction factors applied to the R. E. Ginna fission sensor reaction rates are summarized as follows:
Correction Capsule V Capsule R Capsule T Capsule S Capsule N 235U Impurity/Pu 0.861 0.820 0.845 0.755 0.689 Build-in 238 U(,,f) 0.950 0.955 0.950 0.953 0.953 Net 238U Correction 0.818 0.783 0.803 0.720 0.657 237 Np(y,f) 0.983 0.984 0.983 0.983 0.983 These factors were applied in a multiplicative fashion to the decay corrected uranium and neptunium fission sensor reaction rates.
Results of the sensor reaction rate determinations for Capsule N are given in Table A-3; results for Capsules V, R, T, and S are provided in Reference A-2. In Table A-3, the measured specific activities, decay corrected saturated specific activities, and computed reaction rates for each sensor indexed to the radial center of the capsule are listed: The fission sensor reaction rates are listed both with and without the applied corrections for 238U impurities, plutonium build-in, and gamma ray induced fission effects.
A.1.2 Least Squares Evaluation of Sensor Sets Least squares adjustment methods provide the capability of combining the measurement data with the corresponding neutron transport calculations resulting in a Best Estimate neutron energy spectrum with associated uncertainties. Best Estimates for key exposure parameters such as 4(E > 1.0 MeV) or dpa/s along with their uncertainties are then easily obtained from the adjusted spectrum. In general, the least squares methods, as applied to surveillance capsule dosimetry evaluations, act to reconcile the measured sensor reaction rate data, dosimetry reaction cross-sections, and the calculated neutron energy spectrum within their respective uncertainties. For example, WCAP-17036-NP May 2009 J Revision 0
(
A-5 Ri +/-6"i (Cyjg +/- 6', )((Pg +/- 6(p g
relates a set of measured reaction rates, Ri, to a single neutron spectrum, 4 g, through the multigroup dosimeter reaction cross-section, aig, each with an uncertainty 5. The primary objective of the least squares evaluation is to produce unbiased estimates of the neutron exposure parameters at the location of the measurement.
For the least squares evaluation of the R. E. Ginna surveillance capsule dosimetry, the FERRET code (Reference A-4) was employed to combine the results of the plant-specific neutron transport calculations and sensor set reaction rate measurements to determine best-estimate values of exposure parameters (O(E > 1.0 MeV) and dpa) along with associated uncertainties for the five in-vessel capsules analyzed to date.
The application of the least squares methodology requires the following input:
- 1. The calculated neutron energy spectrum and associated uncertainties at the measurement location.
- 2. The measured reaction rates and associated uncertainty for each sensor contained in the multiple foil set.
- 3. The energy dependent dosimetry reaction cross-sections and associated uncertainties for each sensor contained in the multiple foil sensor set.
For the R. E. Ginna application, the calculated neutron spectrum was obtained from the results of plant-specific neutron transport calculations described in Section 6.2 of this report. The sensor reaction rates were derived from the measured specific activities using the procedures described in Section A. 1.1. The dosimetry reaction cross-sections and uncertainties were obtained from the SNLRML dosimetry cross-section library (Reference A-5). The SNLRML library is an evaluated dosimetry reaction cross-section compilation recommended for use in LWR evaluations by ASTM Standard E1018, "Application of ASTM Evaluated Cross-Section Data File, Matrix E 706 (JiB)."
The uncertainties associated with the measured reaction rates, dosimetry cross-sections, and calculated neutron spectrum were input to the least squares procedure in the form of variances and covariances. The assignment of the input uncertainties followed the guidance provided in ASTM Standard E 944, "Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance."
The following provides a summary of the uncertainties associated with the least squares evaluation of the R. E. Ginna surveillance capsule sensor sets.
Reaction Rate Uncertainties The overall uncertainty associated with the measured reaction rates includes components due to the basic measurement process, irradiation history corrections, and corrections for competing reactions. A high level of accuracy in the reaction rate determinations is assured by utilizing laboratory procedures that WCAP-17036-NP May 2009 Revision 0
A-6 conform to the ASTM National Consensus Standards for reaction rate determinations for each sensor type.
After combining all of these uncertainty components, the sensor reaction rates derived from the counting and data evaluation procedures were assigned the following net uncertainties for input to the least squares evaluation:
Reaction Uncertainty 63 Cu(no()60Co 5%
54 Fe(n,p) 54Mn 5%
58 Ni(n,p) 58Co 5%
23 8U(n,f) 137Cs 10%
237 37 Np(n,f) 1 Cs 10%
59 Co(nY)6°Co 5%
These uncertainties are given at the 10c level.
Dosimetry Cross-Section Uncertainties The reaction rate cross-sections used in the least squares evaluations were taken from the SNLRML library. This data library provides reaction cross-sections and associated uncertainties, including covariances, for 66 dosimetry sensors in common use. Both cross-sections and uncertainties are provided in a fine multigroup structure for use in least squares adjustment applications. These cross-sections were compiled from the most recent cross-section evaluations and they have been tested with respect to their accuracy and consistency for least squares evaluations. Further, the library has been empirically tested for use in fission spectra determination as well as in the fluence and energy characterization of 14 MeV neutron sources.
For sensors included in the R. E. Ginna surveillance program, the following uncertainties in the fission spectrum averaged cross-sections are provided in the SNLRML documentation package.
IReaction Uncertainty 63 60 CU(n,(c) Co 4.08-4.16%
54 Fe(n,p) 54Mn 3.05-3.11%
58 Ni(n,p) 58Co 4.49-4.56%
238 37 U(n,f)1 Cs 0.54-0.64%
237 137 Np(n,f) Cs 10.32-10.97%
59 Co(n,7)6°Co 0.79-3.59%
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A-7 These tabulated ranges provide an indication of the dosimetry cross-section uncertainties associated with the sensor sets used in LWR irradiations.
Calculated Neutron Soectrum The neutron spectra input to the least squares adjustment procedure were obtained directly from the results of plant-specific transport calculations for each surveillance capsule irradiation period and location. The spectrum for each capsule was input in an absolute sense (rather than as simply a relative spectral shape). Therefore, within the constraints of the assigned uncertainties, the calculated data were treated equally with the measurements.
While the uncertainties associated with the reaction rates were obtained from the measurement procedures and counting benchmarks and the dosimetry cross-section uncertainties were supplied directly with the SNLRML library, the uncertainty matrix for the calculated spectrum was constructed from the following relationship:
2 *Rg, *P Mgg, = R +R ggn9g9g where R, specifies an overall fractional normalization uncertainty and the fractional uncertainties Rg and Rg, specify additional random groupwise uncertainties that are correlated with a correlation matrix given by:
Pgg, = [1 -O16gg, +- 0 eH where 2
H - (g_ g,)
2 2y The first term in the correlation matrix equation specifies purely random uncertainties, while the second term describes the short-range correlations over a group range y (0 specifies the strength of the latter term). The value of 5 is 1.0 when g = g', and is 0.0 otherwise.
The set of parameters defining the input covariance matrix for the R. E. Ginna calculated spectra was as follows:
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A-8 Flux Normalization Uncertainty (R,) 15%
Flux Group Uncertainties (Rg, Rg,)
(E > 0.0055 MeV) 15%
(0.68 eV < E < 0.0055 MeV) 25%
(E < 0.68 eV) 50%
Short Range Correlation (0)
(E > 0.0055 MeV) 0.9 (0.68 eV < E < 0.0055 MeV) 0.5 (E < 0.68 eV) 0.5 Flux Group Correlation Range (y)
(E > 0.0055 MeV) 6 (0.68 eV < E < 0.0055 MeV) 3 (E < 0.68 eV) 2 A.1.3 Comparisons of Measurements and Calculations Results of the least squares evaluations of the dosimetry from the R. E. Ginna surveillance capsules withdrawn to date are provided in Tables A-4 and A-5. In Table A-4, measured, calculated, and best-estimate values for sensor reaction rates are given for each capsule. Also provided in this tabulation are ratios of the measured reaction rates to both the calculated and least squares adjusted reaction rates.
These ratios of M/C and M/BE illustrate the consistency of the fit of the calculated neutron energy spectra to the measured reaction rates both before and after adjustment. In Table A-5, comparison of the calculated and best estimate values of neutron flux (E > 1.0 MeV) and iron atom displacement rate are tabulated along with the BE/C ratios observed for each of the capsules.
The data comparisons provided in Tables A-4 and A-5 show that the adjustments to the calculated spectra are relatively small and within the assigned uncertainties for the calculated spectra, measured sensor reaction rates, and dosimetry reaction cross-sections. Further, these results indicate that the use of the least squares evaluation results in a reduction in the uncertainties associated with the exposure of the surveillance capsules. From Section 6.4 of this report, it may be noted that the uncertainty associated with the unadjusted calculation of neutron fluence (E > 1.0 MeV) and iron atom displacements at the surveillance capsule locations is specified as 12% at the la level. From Table A-5, it is noted that the corresponding uncertainties associated with the least squares adjusted exposure parameters have been reduced to 6% for neutron flux (E > 1.0 MeV) and 7-8% for iron atom displacement rate. Again, the uncertainties from the least squares evaluation are at the Icy level.
Further comparisons of the measurement results (from Tables A-4 and A-5) with calculations are given in Tables A-6 and A-7. These comparisons are given on two levels. In Table A-6, calculations of individual threshold sensor reaction rates are compared directly with the corresponding measurements. These threshold reaction rate comparisons provide a good evaluation of the accuracy of the fast neutron portion of the calculated energy spectra. In Table A-7, calculations of fast neutron exposure rates in terms of 4(E > 1.0 MeV) and dpa/s are compared with the best estimate results obtained from the least squares evaluation of the capsule dosimetry results. These two levels of comparison yield consistent and similar WCAP-17036-NP May 2009 Revision 0
A-9 results with all measurement-to-calculation comparisons falling well within the 20% limits specified as the acceptance criteria in Regulatory Guide 1.190.
In the case of the direct comparison of measured and calculated sensor reaction rates, the M/C comparisons for fast neutron reactions range from 0.78 to 1.47 for the 24 samples included in the data set.
The overall average M/C ratio for the entire set of R. E. Ginna data is 1.01 with an associated standard deviation of 17.1%.
In the comparisons of best estimate and calculated fast neutron exposure parameters, the corresponding BE/C comparisons for the capsule data sets range from 0.86 to 1.04 for neutron flux (E > 1.0 MeV) and from 0.85 to 1.03 for iron atom displacement rate. The overall average BE/C ratios for neutron flux (E > 1.0 MeV) and iron atom displacement rate are 0.98 with a standard deviation of 7.6% and 0.98 with a standard deviation of 7.6%, respectively.
Based on these comparisons, it is concluded that the calculated fast neutron exposures provided in Section 6.2 of this report are validated for use in the assessment of the condition of the materials comprising the beltline region of the R. E. Ginna reactor pressure vessel.
May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
A-10 Table A-1 Nuclear Parameters Used in the Evaluation of Neutron Sensors Reaction of Target Atom 90% Response Product Fission Yield Monitor Material Interest Fraction Range (MeV) Half-life (%)
63 Copper Cu (n,a) 0.6917 4.9-11.9 5.271 y 54 Iron Fe (n,p) 0.0585 2.1 -8.5 312.1 d 5
Nickel 8Ni (n,p) 0.6808 1.5- 8.3 70.82 d 23 Uranium-238 8U (n,f) 1.0000 1.3 - 6.9 30.07 y 6.02 237 Neptunium-237 Np (n,f) 1.0000 0.3 - 3.8 30.07 y 6.17 Cobalt-Aluminum 59Co (n,,) 0.0015 non-threshold 5.271 y The 90% response range is defined such that, in the neutron spectrum characteristic of the R. E. Ginna surveillance capsules, approximately 90% of the sensor response is due to neutrons in the energy range specified with approximately 5% of the total response due to neutrons with energies below the lower limit and 5% of the total response due to neutrons with energies above the upper limit.
WCAP- 17036-NP May 2009 Revision 0
A-11 Table A-2 Calculated Flux at the Surveillance Capsule Center, Core Midplane Elevation
_1) (E > 1.0 MeV) (n/cm2-s)
Cycle EFPY Capsule V Capsule R Capsule T Capsule S Capsule N la 0.7 1.20E+ 1I 1.20E+1I1 7.04E+ 10 6.70E+ 10 6.70E+ 10 lb 1.4 1.42E+ 1I 1.42E+11I 8.00E+10 7.15E+10 7.15E+10 2 1.6 1.37E+11I 8.08E+10 7.70E+ 10 7.70E+10 3 2.6 1.15E+lI1 6.66E+ 10 6.29E+10 6.29E+10 4 3.2 7.45E+10 7.42E+ 10 7.42E+ 10 5 3.8 7.68E+10 7.06E+10 7.06E+ 10 6 4.6 8.47E+10 7.62E+10 7.62E+10 7 5.3 7.61E+10 7.12E+107.12E+10 7.12E+10 8 6.0 8.58E+10 8.20E+10 8.20E+ 10 9 6.9 8.60E+10 8.48E+10 8.48E+ 10 10 7.7 7.92E+ 10 7.92E+ 10 11 8.2 6.60E+ 10 6.60E+10 12 9.0 6.49E+ 10 6.49E+ 10 13 9.6 6.37E+10 6.37E+10 14 10.4 7.04E+ 10 7.04E+ 10 15 11.2 6.72E+10 6.72E+10 16 12.0 6.08E+10 6.08E+ 10 17 12.9 6.07E+10 6.07E+ 10 18 13.9 5.96E+10 5.96E+10 19 14.6 6.02E+ 10 6.02E+ 10 20 15.4 5.89E+105.89E+10 5.89E+10 21 16.2 6. 1OE+ 10 6.10E+10 22 17.0 6.19E+10 6.19E+10 23 17.8 6.13E+10 24 18.6 5.58E+10 25 19.5 5.33E+10 26 20.7 4.66E+10 27 22.0 4.47E+ 10 28 23.4 4.77E+10 29 24.8 4.64 E+ 10 30 26.1 4.75E+1-0 31 27.5 4.65E+10 32 29.0 5.79E+10 33 30.5 5.69E+10 Average 1.32E+11 1.26E+11 7.79E+10 6.78E+10 6.03E+10 Data for Capsules V, R, T, S are from Reference A-2.
WCAP-17036-NP May 2009 Revision 0
A-12 Table A-3 Measured Sensor Activities And Reaction Rates Surveillance Capsule N Measured Saturated Radially Adjusted Radially Adjusted Activity Activity Saturated Activity Reaction Rate Reaction Location (dps/g) (dps/g) (dps/g) (rps/atom) 63 Cu(n,a) 6°Co (Cd) Top 2.13E+05 2.89E+05 2.75E+05 4.16E-17 TopMid 1.86E+05 2.52E+05 2.41E+05 3.63E-17 BotMid 2.13E+05 2.89E+05 2.75E+05 4.16E-17 Bottom 2.12E+05 2.87E+05 2.74E+05 4.14E-17 Average 4.02E-17 5 5 8Ni(n,p) 8Co Middle 2.68E+06 3.72E+07 3.54E+07 5.OOE-15 23 37 8U(n,f)1 Cs (Cd) Cap 2.26E+06 4.90E+06 4.90E+06 3.24E-14 235 239 Including U, Pu, and y,fission corrections: 2.13E-14 237 37 Np(n,f)1 Cs (Cd) Cap 1.80E+07 3.90E+07 3.90E+07 2.49E-13 235 239 Including U, Pu, and y,fission corrections: 2.45E-13 59 Co(n,y)6 °Co Top 3.55E+07 4.81E+07 4.61E+07 3.01E-12 TopMid 3.11E+07 4.21E+07 4.04E+07 2.63E-12 Middle 3.20E-07 4.34E+07 4.15E+07 2.71E-12 BotMid 3.39E+07 4.59E+07 4.40E+07 2.87E-12 Bottom 3.28E+07 4.45E+07 4.26E+07 2.78E-12 Average 2.80E-12 59 6 Co(n,y) °Co (Cd) Top 1.32E+07 1.79E+07 2.08E+07 1.36E-12 TopMid 1.40E+07 1.90E+07 2.21E+07 1.44E-12 Middle 1.29E+07 1.75E+07 2.03E+07 1.33E-12 BotMid 1.40E+07 1.90E+07 2.21E+07 1.44E-12 Bottom 1.32E+07 1.79E+07 2.08E+07 1.36E-12 Average 1.38E-12
- 1. Measured specific activities are indexed to a counting date of January 23, 2009
- 2. The average 238U(n,f) reaction rate of 2.13E-14 includes a correction factor of 0.689 to account for plutonium build-in and an additional factor of 0.953 to account for photo-fission effects in the sensor.
- 3. The average 237Np(n,f) reaction rate of 2.45E-13 includes a correction factor of 0.983 to account for photo-fission effects in the sensor.
May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
A-13 Table A-3 Measured Sensor Activities And Reaction Rates Surveillance Capsule N (Continued)
Measured Saturated Radially Adjusted Radially Adjusted Activity Activity Saturated Activity Reaction Rate Reaction Location (dps/g) (dps/g) (dps/g) (rps/atom) 4 4 1 Fe(n P) Mn Core side 1.24E+06 2.28E+06 2.16E+06 3.43E-15 Charpy Core side 1.17E+06 2.15E+06 2.04E+06 3.63E-17 Charpy Core side 1.24E+06 2.28E+06 2.16E+06 3.24E- 15 Charpy Vessel side 1.02E+06 1.87E+06 2.17E+06 3.43E-15 Charpy Vessel side 9.67E+05 1.77E+06 2.05E+06 3.25E-15 Charpy Vesselside 1.02E+06 1.87E+06 2.17E+06 3.43E-15 Charpy Average 3.37E-15
- 1. Measured specific activities are indexed to a counting date ot January 23, 2009
- 2. The average 238U(n,f) reaction rate of 2.13E-14 includes a correction factor of 0.689 to account for plutonium build-in and an additional factor of 0.953 to account for photo fission effects in the sensor.
- 3. The average 237Np(n,f) reaction rate of 2.45E-13 includes a correction factor of 0.983 to account for photo fission effects in the sensor.
WCAP-17036-NP May 2009 Revision 0
A-14 Table A-4 Comparison of Measured, Calculated, and Best Estimate Reaction Rates at Center of Surveillance Capsule N Reaction Rate (rps/atom)
Reaction Measured Calculated Best Estimate M/C M/BE 63 Cu(n,a) 6 °Co 4.06E- 17 3.87E-17 3.79E- 17 1.05 1.08 54 54 Fe(n,p) Mn 3.3 7E- 15 4.19E- 15 3.73E-15 0.80 0.90 58 58 Ni(n,p) Co 5.07E- 15 5.77E-15 5.25E- 15 0.88 0.97 238 U(nf)137Cs (Cd) 2.13E-14 2.08E-14 1.97E-14 1.02 1.08 237 37 Np(n,f)1 Cs (Cd) 2.45E-13 1.67E-13 2.04E- 13 1.47 1.20 59 Co(nY) 6°Co 2.80E-12 3.85E-12 2.84E-12 0.73 0.99 59 60 Co(nY) Co (Cd) 1.38E-12 1.50E-12 1.38E-12 0.92 1.00 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
A-15 Table A-5 Comparison of Calculated and Best Estimate Exposure Rates at the Surveillance Capsule Center (p(E > 1.0 MeV) [n/cm 2-s]
Capsule ID Calculated Best Estimate Uncertainty (Icy) I BE/C V 1.32E+11 1.13E+1 1 6% 0.86 R 1.26E+11 1.30E+1 1 6% 1.03 T 7.79E+10 8.12E+10 6% 1.04 S 6.79E+10 6.62E+10 6% 0.98 N 6.03E+10 5.92E+10 6% 0.98 Calculated results are based on the synthesized transport calculations taken at the core midplane following the completion of each respective capsule's irradiation period and are the average neutron exposure over the irradiation period for each capsule.
See Section A. 1.2 for details describing the Best Estimate (BE) exposure rates.
Iron Atom Displacement Rate [dpa/sJ Capsule ID Calculated Best Estimate Uncertainty (Ia) BE/C V 2.40E- 10 2.05E-10 8% 0.85 R 2.30E-10 2.36E-10 7% 1.03 T 1.36E-10 1.40E- 10 8% 1.03 S 1.19E-10 1.16E-10 7% 0.97 N 9.93E- 11 1.06E-10 7% 1.01 Calculated results are based on the synthesized transport calculations taken at the core midplane following the completion of each respective capsule's irradiation period and are the average neutron exposure over the irradiation period for each capsule.
See Section A. 1.2 for details describing the Best Estimate (BE) exposure rates.
WCAP-17036-NP May 2009 Revision 0
A-16 Table A-6 Comparison of Measured/Calculated (M/C) Sensor Reaction Rate Ratios Including all Fast Neutron Threshold Reactions M/C Ratio
% Standard Reaction Capsule V Capsule R Capsule T Capsule S Capsule N Average Deviation 63Cu(na) 6Co 1.02 1.01 1.00 1.02 1.05 1.02 1.8 54Fe(np) 54Mn 0.93 1.01 1.01 0.95 0.80 0.94 9.2 58Ni(n'P)58Co 0.78 0.93 0.95 0.90 0.88 0.89 7.4 23 8 U(n,f)13 7 CS (Cd) 0.89 0.98 1.01 0.94 1.02 0.97 5.5 237Np(n,f)137Cs (Cd) -- 1.32 1.29 1.22 1.47 1.33 8.0 The overall average M/C ratio for the set of 24 sensor measurements is 1.01 with an associated standard deviation of 17.1%.
May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
A-17 Table A-7 Comparison of Best Estimate/Calculated (BE/C) Exposure Rate Ratios BE/C Ratio Capsule ID *(E > 1.0 MeV) dpa/s V 0.86 0.85 R 1.03 1.03 T 1.04 1.03 S 0.98 0.97 N 0.98 1.01 Average 0.98 0.98
% Standard Deviation 7.6 7.6 WCAP-17036-NP May 2009 Revision 0
A-I 8 A.2 REFERENCES A-1. Regulatory Guide RG-1.190, Calculationaland Dosimetry Methods for DeterminingPressure Vessel Neutron Fluence, U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, March 2001.
A-2. WCAP- 15885, R. E. Ginna Heatup and Cooldown Curvesfor Normal Operation, Revision 0, July 2002.
A-3 WCAP-7254, Rochester Gas and Electric Robert E. Ginna Unit No. I Reactor Vessel Radiation Surveillance Program,May 1969.
A-4. A. Schmittroth, FERRETDataAnalysis Core, HEDL-TME 79-40, Hanford Engineering Development Laboratory, Richland, WA, September 1979.
A-5. RSICC Data Library Collection DLC-178, SNLRML Recommended Dosimetry Cross-Section Compendium, July 1994.
May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
B-1 APPENDIX B LOAD-TIME RECORDS FOR CHARPY SPECIMEN TESTS S Specimen prefix "P" denotes Forging 125P666, Longitudinal (Tangential) Orientation S Specimen prefix "S" denotes Forging 125S255, Longitudinal (Tangential) Orientation S Specimen prefix "W" denotes Surveillance Program Weld Metal Specimen prefix "H" denotes Heat-Affected Zone Material May 2009 WCAP-1 7036-Np WCAP-17036-NP May 2009 Revision 0
B-2 ma .c 10 1 TS*1 Irm)
P47, 25F MISL Zm&t IN.
0 P5. 0 P53, 30-F WCAP-1 7036-NP May 2009 Revision 0
B-3 tcNoo " ..
P51, 40 F
+
/........-.
++ t I'm Liiii3i P44. ..0F WCAP-17036-NP May 2009 Revision 0
B-4 P49, 80 0 F I
P45, 90-F all Pt52, 100 0F WCAP-17036-NP May 2009 Revision 0
B-5 F",
WOO .........................
LJ*
50OF
ýý, (-I P43, 390F WCAP-17036-NP May 2009 Revision 0
B-6
- - . ..~~~~~~~~~.................
"............ . . .. .i .................... i......... . .. . . .i........ . . . . . . .! ..........
S43, OOF
.Mm - ..-c.-.-... .... ....-......
........ .... If........ ............ ...
$44, 20 0 F
$53, 35*1F WCAP-1 7036-NP May 2009 Revision 0
B-7
... i ..... ...
. .i.
S52, 40 0F S46, 5o 0F j
0.11 WCAP-1 7036-NP May 2009 Revision 0
B-8 1
S50, 80-F MCI ............
ý19 I 3=12 ........
=M21 .. ........ .......
f0mir all iH 4,"
i Th0-F j S48, 9D0OF S47, 200OT WCAP-17036-NP May 2009 Revision 0
B-9 rn"A 0-)
S49, 350OF
~TV 0%)
SS 1, 3 7 ;-F 1's Thie1Om S4,5, 3-90'T WCAP-17036-NP May 2009 Revision 0
B-10 H
l~fl ...................................
211 213l W-54, OOF ThiM 01 AW47. 150OF 113 WAS, 200-F WCAP-17036-NP May 2009 Revision 0
B-11 oW W43, 220 0 F W53, 2300 "
WCAP- 17036-NP May 2009 Revision 0
B-12 Tne-I 0" N%49, 240-F W151, 26 0-F W-0, 8T May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
B-13 W52, 3501F W44~, 37 F Im 29 it Al 5 XV 4006 1 WCAP- 17036-NP Mav 2009 Revision 0
B-14 H48, 09F WI4 urnrn i 0"1E H43, 35F H~ro, 40O'F WCAP- 17036-NP May 2009 Revision 0
B-15 H46,5SO0F TftO.lI")
H52, 5S-0rF tIm.
s0]
M3 R54. 6001 WCAP-1 7036-NP May 2009 Revision 0
B-16
,to4' . . . . . . . . . . . . . . . .....
- nA .. . . ........ . . . . .
0 H 80O 93, 4F x*. .l... .... ... ... .... : ...... ...... ......... *......-................ J . . ........
lto 11 t4l,11 I0o It I4', 23300 roI qsj H47,1309OF WCAP-1 7036-NP May 2009 Revision 0
B-17 rn1~ ým H49, 360OF
-*l...
... i.........
- i............ ......
H51, 37,50 F
.055 1.1 ZEN1 311 ACV am.11 H44, 390-F WCAP-17036-NP May 2009 Revision 0
C-1 APPENDIX C CHARPY V-NOTCH PLOTS FOR EACH CAPSULE USING SYMMETRIC HYPERBOLIC TANGENT CURVE-FITTING METHOD Contained in Table C-I are the upper shelf energy (USE) values used as input for the generation of the Charpy V-notch plots using CVGRAPH, Version 5.3 [C-l]. Per Reference C-1, CVGRAPH, Version 5.3 meets the Westinghouse QA program requirements. The use of CVGARPH 5.3 to fit the Charpy V-notch impact energy data for all capsules and baseline testing is the most accurate and consistent methodology available. Previous capsules relied upon manual free hand fits that are still valid today, but not necessarily the most consistent approach when comparing all of the capsule test data. Therefore, all previous testing and analyses are valid, but the new CVGARPH 5.3 results presented in this report, coupled with the updated fluence values for each capsule, provide the best representation of the total surveillance results for the R. E. Ginna surveillance program.
The definition for USE is given in ASTM E185-82 [C-2], Section 4.18, and reads as follows:
"upper shelf energy level - the average energy value for all Charpy specimens (normally three) whose test temperature is above the upper end of the transition region. For specimens tested in sets of three at each test temperature, the set having the highest average may be regarded as defining the upper shelf energy."
If there are specimens tested in sets of three at each temperature, Westinghouse reports the set having the highest average energy as the USE (usually unirradiated material). If the specimens were not tested in sets of three at each temperature, Westinghouse reports the average of all Charpy data (> 95% shear) as the USE, excluding any values that are deemed outliers using engineering judgment. Hence, the USE values reported in Table C-i, which were used to generate the Charpy V-notch curves, were determined utilizing this methodology.
The lower shelf energy values were fixed at 2.2 ft-lb for all cases.
Table C-1 Upper Shelf Energy Values (ft-lb) Fixed in CVGRAPH Capsule Material Unirradiated V R T S N Lower Shell Forging 125P666 174.6 (a) 147.8 142.5 142.5 142.3 (L-C)
Intermediate Shell Forging 140.0 (a) 142.2 152.3 139.0 134.3 125S255_(L-C)
Weld Metal (Heat # 61782) 79.0 (a) 48.9 52.7 52.2 51.9 HAZ Material 90.0 (a) 82.8 117.7 103.5 88.3 Note:
(a) No shear data was reported for Capsule V; therefore, the upper shelf was left free for CVGRAPH to determine from the tanh fit of the data.
CVGRAPH Version 5.3 plots of all surveillance data are provided in this appendix, on the pages following the reference list.
WCAP-17036-NP May 2009 Revision 0
C-2 C.1 REFERENCES C-1 CVGRAPH, Hyperbolic Tangent Curve-Fitting Program, Version 5.3, developed by ATI Consulting, December 2007. Sub-
References:
(a) Westinghouse Calculation Note CN-PCAM-07-10, Revision 0, "CVGRAPH Version 5.3 Validation and Verification," December 2007.
(b) WCAP-14370, Revision 0, "Use of the Hyperbolic Tangent Function for Fitting Transition Temperature Toughness Data," T. R. Mager, et al., May 1995.
(c) Westinghouse Letter LTR-PCAM-07-105, "Release of Program CVGraph 5.3 for Production Use," December 19, 2007.
C-2 ASTM E185-82, Standard Practicefor Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, E706 (IF), ASTM, 1982.
May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
C-3 Unirradiated Intermediate Shell Forging 125S255 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/08/2009 10:19 PM Page 1 Coefficients of Curve I A=71.1 B=68.9C=85.45 TO=29.82 D= O00RtF00 Equation is A + B * [Tanh((T-ToY(C+DT))]
Upper Shelf Energry=140.0(Fixed) Lower Shelf Energy2.2(Fixed)
Temp@30 ft-lb--28.9 Deg F Temp@50 ft-lb=Z8 Deg F Plant Cinna Material: SA5S08CL2 Heat: 125S255 Orientation: LC Capsule: UNIRR FRuence: r'cnMA2 4~l' ouu 250
-r 200 IT z
wQ 100 0
5o 0 0 50 0.
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Teipemretun. Iqnpt CVN Computed CVN Diferentmial
- 80. 00 5. 00 1 .99 -6. 99
- ,0. O0 11. 50 11.99 -. 49
- 80. 00 11. 00 11.99 -. 99
-40. 00 6. 00 24. 70 -18.70
-40. 00 28. 00 24. 70 3. 30
-40. 00 19.00 24. 70 -5. 70
-20. 00 45. 50 34. 94 10. 56
-20. 00 67. 50 34. 94 32. 56
-20. 00 22. 50 34. 94 -12. 44 WCAP-17036-NP May 2009 Revision 0
C-4 Unirradiated Intermediate Shell Forging 125S255 Pap 2 Plant: Ginna Material: SA50CL2 Heat: 125S255 Orientation: LC Capsule: UNIRR Fluence: n/cm^2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential
- 10. 00 47. 50 55. 40 -7. 90
- 10. 00 79. 50 55. 40 24. 10 10.00 45. 50 55. 40 -9.90
- 60. 00 107. 00 94. 47 12.53
- 60. 00 54. 00 94. 47 -40. 47
- 60. 00 93. 00 94. 47 -1. 47 110. 00 158. 00 121. 71 36. 29 110. 00 151.50 121. 71 29. 79 110. 00 80. 00 121. 71 -41.71 210.00 151. 00 138. O0 13. 00 210. 00 1 20. 00 138. 00 -18. 00 210. 00 149. 00 138. 00 11. 00 Correlation Coefficient = .917 May2009 WCAP- 7036-NP WCAP-l17036-NP May 2009 Revision 0
C-5 Capsule V Intermediate Shell Forging 125S255 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0210912009 08:12 AM Paw 1 Coefficients of Curve I A = 6&49 B = 66.29 C = 90.07 TO = 11.28 ) = O.OOE+00 Equation is A + B * [Tanh((T-To)y(C+DT))]
Upper Shelf Energy=1 34.8 Lower Shelf Energy=2.2(Fixed)
Temp@30 ft-lbs=-48.4 Deg F Temp@50 ft-lbs-14.5 Deg F Plant: Qinna Material: SA508CL2 Heat: 1255255 Orientation: LC Capsule: V Fluence: n/crnA2 300 250
- 200 150 z 00 0/
100 50 0
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temrpertuir Input CVN Computed CVN Diiffcrendal
-50. 00 3. 80 29. 26 -25.46
-25. 00 74. 50 43. 14 31.36
-10. 00 51. 30 53. 11 -1. 81 10.00 66. 50 67. 55 -1. 05
- 40. 00 80. 50 88. 94 -8. 44
- 75. 00 107. 00 108. 86 -1. 86 140. 00 1 29. 00 127. 58 1.42 175. 00 140. 50 131. 37 9. 13 210. 00 136. 00 133. 19 2. 81 WCAP-17036-NP May 2009 Revision 0
C-6 Capsule V Intermediate Shell Forging 125S255 Page 2 Plant: Ginna Material: SA50CL2 Heat: 125S255 Orientation: LC Capsule: V Fluence: n/cm^2 Charpy V-Notch Data Tempertutre. Input CV N Computed CVN Differcndal 500. 00 125. 50 134. 77 - 9. 27 Correlation Coefficient = .945 WCAP-1 7036-NP May 2009 Revision 0
C-7 Capsule R Intermediate Shell Forging 125S255 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02/09/2009 08:17 AM Pawe I Coefficients of Curve I A =722 B =70. C=79.49 TO= 46-59 D= 0.OOE+00 Equation is A + B * [Tanh((T-Toy(C+DT))]
Upper Shelf Energr=142.2(Fixed) Lower Shelf Energy=2.2(Fixed)
Temp@30 ft-lbs--8.8 Deg F Temp@50 ft-lbs=20.5 Deg F Plant Ginna Material: SA5S08CL2 Heat: 125S255 Orientation. LC Capsule: R Fluence: aucmA2 300 250
- 200 0
12 150 0 - -
IMl 100 50 0/
0
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temnperature Input CVN Computed CVN Differential
-40. 00 29. 00 16. 44 12. 56
.00 56. 00 35. 31 20. 69
- 00 37. 50 35. 31 2. 19
- 40. 00 57. 50 66. 41 -8.91
- 40. 00 34. 50 66. 41 - 31. 91
- 77. 00 109. 00 97. 75 11.25
- 77. 00 104. 50 97. 75 6.75 150. 00 144. 50 132. 54 11.96 i 99. 00 149.00 139. 24 9. 76 WCAP-17036-NP May 2009 Revision 0
C-8 Capsule R Intermediate Shell Forging 125S255 Page 2 Plnt: Ginna Material: SA509CL2 Heat: 125S255 Orientation: LC Capsule: R Fluence: n/cm^2 Charpy V-Notch Data Ternperture. Input CVN Computed CVN Differ-en.al 3M0 00 133. 00 141. 96 - S.9 6 Corteintion Coefficient = .947 WCAP-1 7036-NP May 2009 Revision 0
C-9 Capsule T Intermediate Shell Forging 125S255 CVGRAPH 5.3 Hyperbolic Tangent Curve Prnted on 02/09/2009 08:52 PM Paw- 1 Coefficients of Curve I A=77.22 B=75.03C= 180.72 TO=62.3 D=f000E+00 Equation is A + B * [Tanh((T-To)/(C+DT))]
Upper Shelf Energy=152.3(Fixed) Lower Shelf Energy=2.2(Fixed)
Temp @30 ft-lbs-7 1.5 Dog F Teup @50 ft-lt*=-6.4 Deg F Plant Cinna Material: SA508CL2 Heat: 125S255 Orientation: LC Capsule: T Fluence: nknt2 300 250 A 200 t0 S150 C
w 100 so 0' 0 0
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperuturr. Input CVN Computed CVN Diffrcntial
- 100. 00 2. 50 23. 56 -21. 06
-50. 00 27. 00 35. 80 -8.80
,00 68. 00 52. 34 15. 66
- 00 78. 00 52. 34 25. 66
- 25. 00 70. 50 61. 96 8. 54
- 75. 00 56. 00 82. 49 - 26. 49 150. 00 103. 00 III. 02 -8.02 175. 00 1 13.00 118. 76 -5. 76 250. 00 155. 00 135. 55 19. 45 May 2009 WCAP-1 7036-NP WCAP- 17036-NP May 2009 Revision 0
c-i1o Capsule T Intermediate Shell Forging 125S255 Pag 2 Plant: Ginna Material: SA508CL2 Heat: 125S255 Orientation: LC Capsule: T Fluence: n/cnmA2 Charpy V-Notch Data Tempcmtute Input CVN Computed CVN DifferentLial 350. 00 149.50 146. 28 3. 22 Cormtlation Coefficient =.937 WCAP-17036-NP May 2009 Revision 0
C-11 Capsule S Intermediate Shell Forging 125S255 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0210912009 08:57 PM Page 1 Coefficients of Curve I A =70.6 B=68.4C=71.81 TO=96.92 D=0.00E4+00 Equation is A + B * [Tanh((T-To)Y(C+DT))]
Upper Shelf Energy= 139.O(Fixed) Lower Shelf Energy=2.2 (Fixed)
Temp@30 ft-lbs=47.9 Deo F Temp@50 ft-lbs::74.7 Deg F Plant CGinna Material: SA508CL2 Heat: 129SS255 Orientation: LC Capsule: S Fluence: n/cmA2 300 250 200 150 0 0 z
100 5o = 4 4-~ - 4 -
0
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperture Input CVN Computed CVN Differential
- 25, 00 3.00 6. 64 -3. 64 00 6. 00 10. 82 - 4. 82
- 15. 00 38. 00 14.88 23. 12
- 25. 00 33. 00 18. 46 14. 54
- 50. 00 30. 00 31.34 - 1. 34
- 75. 00 54. 00 50. 35 3. 65 100. 00 42. 00 73. 53 - 31. 53 140. 00 119.00 107. 33 11. 67 175. 00 146. 00 125. 04 20. 96 WCAP- 17036-NP May 2009 Revision 0
C-12 Capsule S Intermediate Shell Forging 125S255 Pap 2 Plant: Ginna Material: SA509CL2 Heat: 125S255 Orientation: LC Capsule: S Fluence: n/cmA2 Chai-py V-Notch Data Tempcrututm. Input CVN Computed CVN Di rental 225. 00 1 50. 00 135. 24 14.76 250. 00 123.00 137. 10 -14. 10 300. 00 137.00 138. 52 -1. 52 Corre lation Coefficient =. 961 WCAP-17036-NP May 2009 Revision 0
C-13 Capsule N Intermediate Shell Forging 125S255 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0N05/2009 09:18 AM Page I Coefficients of Curve I A =6&25 B= 66.05 C= 146.43 TO= 144L29 D= 0.00E+00 Equation is A + B * [Tanh((T-To)/(C+DT))]
Upper Shelf Energy- 134.3(Fixed) Lower Shelf Energy2.2 (Fixed)
Temp030 ft-lbs47.5 Deg F Tempp@50 ft-lbs= 102.8 Deg F Plant: Crinna Material: SA508CL2 Heat: 125S255 Oiientation: LC Capsule: N Fluence: nicmnA2 300 250 r 200 150 z
100 so 0- - --
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V.Notch Data Tenuperatur. Input CVN Computed CVN Differential 00 6. 00 18.36 -12. 36
- 20. 00 32. 00 22. 65 9. 35
- 35. 00 7. 00 26. 44 -19. 44
- 40. 00 5. 00 27. 82 - 22. 82
- 50. 00 71. 00 30. 76 40. 24
- 60. 00 13. 00 33. 94 - 20. 94
- 80. 00 45. 00 40. 98 4. 02
- 90. 00 72. 00 44. 83 27. 17 200. 00 73. 00 92. 23 -19. 23 WCAP-17036-NP May 2009 Revision 0
C-I14 Capsule N Intermediate Shell Forging 125S255 Pap 2 Plant: Ginna Material: SA50CL2 Heat: 125S255 Orientation: LC Capsule: N Fluence: n/cm^2 Charpy V-Notch Data Temperntum. Input CVN Computed CYN Diffrntia 350. 00 148. 00 126. 80 21. 20 375. 00 125. 00 128.88 - 3. 88 39.0. 00 130. 00 129. 85 .15 Corrlation Coefficient = .915 WCAP-17036-NP May 2009 Revision 0
C-15 Unirradiated Intermediate Shell Forging 125S255 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03108/2009 10:20 PM Page 1 Coefficients of Curve I A = 441 B = 43. C = 79.95 TO = 10.36 D = 0.O0E+0O Equation is A + B * [Tanh((T-To)/(C+DT))]
Upper Shelf L.E.=87.0(Fixed) Lower Shelf LF_= I.0(Fixed)
Temp.@LE. 35 mfils=-6.6 Deg F Plant (3inna Material: SA508CL2 Heat: 125S255 Orientation: LC Capsule: UNIRR Fhuence: UVcmA,2 200 150 E
.2Soo "1
50 0 +-
-300.0 0.0 300.0 600.0 Temperature in Dog F Charpy V-Notch Data Ternpemtum. Input L.E. Computed LE Diffe=iniuI
- go. 00 4. 00 9. 12 - 5. 12
- 80. 00 7. 00 9. 12 -2. 12
- 80. 00 8. 00 9. 12 -18. 12
-40. 00 2. 00 20. 01 01
-40. 00 20. 00 20. 01 01
-40. 00 15. 00 20. 01 S5. 01
-20.00 37. 00 28. 41 8. 59
-20. 00 57. 00 28. 41 28. 59
-20. 00 18.00 28. 41 -10. 41 WCAP-17036-NP May 2009 Revision 0
C-16 Unirradiated Intermediate Shell Forging 125S255 Pap 2 Plant: Ginna Material: SA509CL2 Heat: 125S255 Orientation: LC Capsule: UNIRR Fluence: nkmnA2 Charpy V-Notch Data Tempemture Input L.E. Computed L. Differential 10.00 34. 00 43.81 -9. 81 10.00 64. 00 43.81 20. 19 10.00 36. 00 43.81 - 7. 81
- 60. 00 79. 00 67. 72 11. 28
- 60. 00 42. 00 67. 72 -25. 72
- 60. 00 72. 00 67. 72 4. 28 110. 00 89. 00 80. 43 8. 57 110. 00 90. 00 80. 43 9. 57.
110.00 62. 00 80. 43 -18. 43, 210.00 91.00 86. 42 4. 58 210.00 82. 00 86. 42 - 4. 42 210.00 88. 00 86. 42 1. 58 Corelation Ccefficirnt =.917 WCAP-17036-NP May 2009 Revision 0
C-17 Capsule V Intermediate Shell Forging 125S255 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0210912009 08:12 AM pawe I Coefficients of Curve 1 A = 44.92 B = 43.92 C = 68.36 TO= -10.08 D = 0.OOE+00 Equation is A + B * [Tanb((T-Toy(C+DT))]
Upper Shelf L.E.=88.8 Lower Shelf L.E.=l.0(Fixed)
Temp.@1LE. 35 mils=25.7 Deg F Plant CGnna Material: SA508CL2 Heat: 125S255 Orientation: LC Capsule: V Fluence: IcVCM2 200 150 E
E 100 00 00 00 50 0 0 __ _ _ _ _
-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Tenmpertuir linpt L.E. Computrd LE Diffkential
-50. 00 3. 00 21.84 -18. 84
- 25. 00 56. 00 35. 48 20. 52
-10.00 41.00 44. 97 -3. 97
- 10. 00 64. 00 57. 47 6. 53
- 40. 00 58. 00 72. 36 -14. 36
- 75. 00 85. 00 82. 12 2. 88 140. 00 88. 00 87. 77 ,23 175. 00 86. 00 88. 46 - 2. 46 210. 00 91. 00 88.71 2. 29 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
C-18 Capsule V Intermediate Shell Forging 125S255 Page 2 Plant: Ginna Material: SA5S0CL2 Heat: 125S255 Orientation: LC Capsule: V Fluence: nrcn^2 Charpy V-Notch Data Te mpemratur Input L.E. Computed LE Difrmntial 500. 00 92. 00 88. 85 3.15 Correlation Coefficient = .925 WCAP-17036-NP May 2009 Revision 0
C-19 Capsule R Intermediate Shell Forging 125S255 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02/09/2009 08:18 AM Paw I Coefficients of Curve I A = 47.35 B = 46.35 C = 97.33 TO = 30.06 D = 0.00E+00 Equation is A + B * [Tanh((T-To)/(C+DT))]
Upper Shetf L.E.=93.7 (Fixed) Lower Shelf LE= I.0(Fixed)
Temp. @LE. 35 miils=3.5 Deg F Plant: Ginna Material: SA508CL2 Heat: 125S255 Orientation: LC Capsule: R Fluence: n/crn2 200 150 2
0r-O 5
ioo I 00 I 50 0) 0 fl~
-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Tnmp'mtuir Input L.E. Computed LE Differifnad1
- 40. 00 31. 00 18. 76 12. 24
.00 44. 00 33. 47 10, 53
.00 29. 00 33. 47 -4. 47
- 40. 00 49. 00 52. 07 -3. 07
- 40. 00 24. 00 52. 07 - 28. 07
- 77. 00 79. 00 68. 12 10. 88
- 77. 00 77. 00 68. 12 8. 88 150. 00 9 . 00 86. 43 4. 57 199. 00 96. 00 90. 91 5. 09 WCAP-17036-NP May 2009 Revision 0
C-20 Capsule R Intermediate Shell Forging 125S255 Page 2 Plant: Ginna Material: SA0S0CL2 Heat: 125S255 Orientation: LC Capsule: R Fluence: n/cm^2 Charpy V.Notch Data Temperature Input L.E. Computed LE. Diffterential 300. 00 94. 00 93. 34 .66 Correlation Coefficient =.910 WCAP-17036-NP May 2009 Revision 0
C-21 Capslde T Intermediate Shell Forging 125S255 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02/09/2009 08:54 PM Page 1 Coefficients of Curve I A = 38,-5 B = 37.25 C = 10-.65 TO=-&84 D = 0.00E+O0 Equation is A + B * [Tanh((T-ToY(C+DT))]
Upper Shelf L.E.=75.5(Fixed) Lower Shelf LE.= t.0(Fixed)
Temp.@LE 35 mils=- 17.9 Deg F Plant: Oinna Material: SA508CL2 Heat: 125S255 Orientation: LC Capsule: T Fluence: n/ckrnr2 200 150 E
C
.o a ISO 100 5l 0 0 so
/0 0
-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Ten'pe*tum. Input LE. Computed LE Ditf~nntia1
- 100. 00 2. 80 11. 94 -9.14
-50. 00 16.90 24. 19 -7. 29
.00 50. 80 41. 42 9. 38
.00 53. 20 41. 42 11. 78
- 25. 00 50. 80 50. 00 .80
- 75. 00 43. 30 63. 17 -19. 87 150. 00 68. 50 72. 18 - 3. 68 175. 00 79. 00 73. 41 5. 59 250. 00 79. 00 75, 00 4. 00 WCAP-17036-NP May 2009 Revision 0
C-22 Capsule T Intermediate Shell Forging 125S255 Pae 2 Plant: Ginna Material: SA50CL2 Heat: 125S255 Orientation: LC Capsule: T Fluence: n/crnm2 Charpy V-Notch Data Ternperuture Input L.E. Computed LE. Differenti-4 350. 00 72. 00 75. 43 -3. 43 Correlation Ccefficient =.928 WCAP-17036-NP May 2009 Revision 0
C-23 Capsule S Intermediate Shell Forging 125S255 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02f09/2009 08:57 PM Page 1 Coefficients of Curve I A=44.75 B=43.75C=77.23 TO=83.14 D=0.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]
Upper Shelf L.E.=88.5(Fixed) Lower Shelf LF.= i.0(Fixed)
Temp.@LE. 35 miLs=65.7 Deg F Plant Qinna Material: SA508CL2 Heat: 125S255 Orientation: LC Capsule: S Fluence: ncm^A2 200 150 E
C 2
a 100 50 0 4-
-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperatue. Input LE. Computed LR Differential
- 25. 00 3. 00 6. 01 -3.01 00 6. 00 10. 10 -4. 10
- 15. 00 28. 00 13. 79 14. 21
- 25. 00 26. 00 16.89 9. 11
- 50. 00 22. 00 27. 05 - 5. 05
- 75. 00 41.00 40. 16 .84 100. 00 35. 00 54. 15 19. 15 140. 00 85. 00 72. 18 12.82 175. 00 92. 00 81.08 10. 92 WCAP- 17036-NP May 2009 Revision 0
C-24 Capsule S Intermediate Shell Forging 125S255 Page 2 Plant: Ginna Material: SA508CL2 Heat: 125S255 Orientation: LC Capsule: S Fluenoe: nlcm^2 Charpy V-Notch Data Tempemme Input L.E. Computed LE Differential 225. 00 88. 00 86. 33 1. 67 250. 00 88. 00 87. 35 .65 300. 00 86. 00 88. 1B -2. 18 Correlation Coefficient = .963 WCAP-17036-NP May 2009 Revision 0
C-25 Capsule N Intermediate Shell Forging 125S255 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on O-_-05/2009 09:19 AM Page I Coefficients of Curve I A = 42-15 B= 41.15 C= 112.11 TO= 99.29 D = O.0OE+OO Equation is A + B * [Tanh((T-Toy(C,+DT))]
Upper Shelf L.E.=83.3(Fixed) Lower Shelf L E.= 1.0(Fixed)
Temp. @LE 35 mils=79.7 Deg F Plant: Ginna Material: SA508CL2 Heat: 125S255 Orientation: LC Capsule: N Fluence: nfcmA2 200 150 E
C 0 _
-300.0 0.0 300.0 600.0
- Temperature in Deg F Charpy V-Notch Data Termperatuir Input LE. Computed LE. Dif&rntial 00 6. 00 12.96 -6. 96
- 20. 00 28. 00 17. 09 10. 91
- 35. 00 8. 00 20. 84 -1 2. 84
- 40. 00 6. 00 22. 21 -16. 21
- 50. 00 54. 00 25. 14 28. 86
- 60. 00 13.00 28. 29 -15. 29
- 80. 00 35. 00 35. 14 14
- 90. 00 51. 00 38. 75 1 2. 25 200. 00 63. 00 71. 59 -8. 59 WCAP-17036-NP May 2009 Revision 0
C-26 Capsule N Intermediate Shell Forging 125S255 Page 2 Plant: Ginna Material: SA50CL2 Heat: 125S255 Orientation: LC Capsule: N Fluence: n/cm^2 Charpy V-Notch Data Temperatuit Input L.E. Computed LE. Differential 350. 00 90. 00 82. 37 7. 63 375. 00 77. 00 82. 70 - 5. 70 390. 00 83. 00 82. 84 .16 Correlation Coefficient =. 903 WCAP-17036-NP May 2009 Revision 0
C-27 Unirradiated Intermediate Shell Forging 125S255 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/2712009 09:07 AM Page I Coefficients of Curve I A = 50. B = 50. C = 69.54 TO = 59.9 D = 0.OOE+00 Equation is A + B * [Tanh((T-Toy(C+DT))]
Temperature. at 50% Shear = 60.0 Plant: Girna Material: SASOSCL2 Heat 125S255 Orientation: LC Capsule: UNIRR Fluence: n/cmA2 125 100
( 75 a.
50 25 0 , ¢i
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Tempera-ure Input Percet Shear Computed Percent Shear Differential
-80. 00 1. 00 . 76 -. 76
-80.00 1. 00 1.76 -. 76
- 80. 00 1.00 I .76 -. 76
-40. 00 1.00 5. 35 -4.35
-40.00 5. 00 5. 35 -. 35
-40.00 5. 00 3. 35 -. 35
-20. 00 15. 00 9. 13 5. 87
-20. 00 20. 00 9. 13 to, 87
- 20.00 10.00 9.13 .87 WCAP-17036-NP May 2009 Revision 0
C-28 Unirradiated Intermediate Shell Forging 125S255 Page 2 Plant: Ginna Material: SA508CL2 Heat: 125S255 Orientation: LC Capsule: UN1RR Fluence: n/cla"2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 10.00 25. 00 19.23 5.77 10.00 30. 00 19.23 10, 77 10.00 10.00 19.23 -9. 23
- 60. 00 60. 00 50, 07 9. 93
- 60. 00 25. 00 50. 07 25. 07
- 60. 00 45. 00 50. 07 -5. 07 110. 00 100. 00 80. 86 19. 14 110. 00 100. 00 80. 86 19. 14 110.00 60. 00 80. 86 20. 86 210. 00 100. 00 98. 68 1.32 210. 00 100. 00 98. 68 1. 32 210.00 100. 00 98. 68 1. 32 Correlation Coefficient = .962 WCAP-17036-NP May 2009 Revision 0
C-29 Capsule R Intermediate Shell Forging 125S255 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02109/2009 08: 18 AM Pape I Coefficients of Curve I A=50. B=50. C=95.37 TO=52.44 1)=O.OOE+-00 Equation is A + B * [Tanh((T-Toy(C+DT))]
Temperature at 50% Shear = 52.5 Plant Ginna Material: SA508CL2 Heat: 125S255 Orientation: LC Capsule: R Fluence: n/cm'12 125 100 75 e)
CI 50 25
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Tcrnperatuzm Input Pe*o*t Shear Computed 1ercnt Shear Differential
-40. 00 15.00 12. 58 2. 42
.00 35. 00 24. 98 10. 02
.00 30. 00 24. 98 5. 02
- 40. 00 40. 00 43. 52 -3. 52
- 40. 00 30. 00 43. 52 - 13. 52
- 77. 00 65. 00 62. 60 2. 40
- 77. 00 60. 00 62.60 - 2. 60 150ý 00 98, 00 88. 55 9.45 199. 00 100.00 95. 58 4.42 WCAP-17036-NP May 2009 Revision 0
C-30 Capsule R Intermediate Shell Forging 125S255 Pag 2 Plant: Ginna Material: SA508CL2 Heat: 125S255 Orientation: LC Capsule: R Fluence: ncm^n2 Charpy V.Notch Data Tempe*nturr Input Perocnt Shear Computed Percent Sltar Differentir1 300. 00 100. 00 99. 45 .55 Correlation Coefficient = .977 WCAP-17036-NP May 2009 Revision 0
C-31 Capsule T Intermediate Shell Forging 125S255 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02(09/2009 08:54 PM Pape I Coefficients of Curve I A=50. B=50. C= 156.06 TO=87.32 D=0.OOE+00 Equation is A + B * [Tanh((T-To)Y(C+DT))]
Temperature at 50% Shear = 87.4 Plant: Ginna Material: SAS0CL2 Heat: 125S255 Orientation: LC Capsule: T Fluence: n/cm'12 125 100 75 L3
- a. 50 25
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature. Input Percent Shear Computed Peroent Shear Differential
-100.00 2. 00 8. 31 -6. 31
-50. 00 9. 00 14.68 - 5. 68
.00 31. 00 24. 62 6. 38
.00 38. 00 24. 62 13.38
- 25. 00 34. 00 31. 03 2. 97
- 75. 00 32. 00 46. 06 -14. 06 150. 00 70. 00 69. 07 . 93 175. 00 70. 00 75. 47 - 5.47 250. 00 100. 00 88, 94 11. 06 WCAP-17036-NP May 2009 Revision 0
C-32 Capsule T Intermediate Shell Forging 125S255 Pag 2 Platt: Ginna Material: SA509CL2 Heat" 125S255 Orientation: LC Capsule: T Fluenoe: n/cn-i2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Diikrentini 350. 00 100.00 96. 66 3. 34 Correlation Coefficient =.970 WCAP-17036-NP May 2009 Revision 0
C-33 Capsule S Intermediate Shell Forging 125S255 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02109/2009 08:58 PM Pagg I Coefficients of Curve I A=50. B =50. C=85.92 TO=79.99 I)=O.O00E+00 Equation is A + B * [Tanh((T-To)1(C4+DT))]
Temperature at 50% Shear = 80.0 Plant Ginna Material: SA508CL2 Heat: 125S255 Orientation: LC Capsule: S Fluence: n/cmA2 125 100 ---- -
75 L. 0 CL 0e 50 0
25 0
0
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temrperatur. Input Pe, ent Shear Computed Percent Shear Differential
- 25. 00 2. 00 7.99 -5. 99 00 5. 00 13.45 -8.45
- 15. 00 35, 00 18.05 16. 95
- 25. 00 30. 00 21. 75 8. 25
- 50. 00 30. 00 33. 22 -3. 22
- 75. 00 50. 00 47. 10 2. 90 100. 00 40. 00 61. 44 -21.44 140. 00 90. 00 80. 17 9. 83 175. 00 100. 00 90. 13 9. 87 WCAP-17036-NP May 2009 Revision 0
C-34 Capsule S Intermediate Shell Forging 125S255 Page 2 Plant: Ginna Material: SA509CL2 Heat: 125S255 Orientation: LC Capsule: S Fluenee: n/cmnA2 Charpy V-Notch Data Tempertuem Input Percent Shear Computed Percent Shear Differential 225. 00 100. 00 96. 69 3. 31 250. 00 100.00 98. 13 1. 87 300. 00 100. 00 99.41 .59 Correlation Coefficient =. 966 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
C-35 Capsule N Intermediate Shell Forging 125S255 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0N0512009 09:20 AM Page 1 Coefficients of Curve 1 A = 50. B = 50. C = 125.47 TO = 179.32 ) = 0.00E+00 Equation is A + B * [Tanh((T-To)I(C,+DT))]
Temperature at 50% Shear= 179.4 Plant Cinna Material: SA508CL2 Heat: 125S255 Orientation: LC Capsule: N Fluence: n/cm^2 12 0
10(0o 7!5
/ o ._._-_._
a.
01.
0 2!
0-- -_
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 600.0 600.0 Temperature in Deg F Charpy V-Notch Data Te mtperatutr Input Percent Shear Computed Neruent Shear Differential
.00 .00 5. 42 -5. 42
- 20. 00 5.00 7.31 - 2. 31
- 35. 00 5.00 9. 11 -4. 11
- 40. 00 5. 00 9. 79 -4. 79
- 50. 00 25. 00 11.29 13.71
- 60. 00 5. 00 12.99 -7. 99
- 80. 00 20. 00 17. 03 2. 97
- 90. 00 30. 00 19. 41 10.59 200. 00 50. 00 58. 17 -8.17 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
C-36 Capsule N Intermediate Shell Forging 125S255 Page 2 Plant: Ginna Material: SA508CL2 Heat: 125S255 Orientation: LC Capsule: N Ruenee: nrcmA^2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Sthar Differential 350. 00 100. 00 93. 82 6. 18 375. 00 100.00 95. 77 4. 23 390. 00 100. 00 96. 64 3. 36 Correlation Coefficient =. 985 WCAP-17036-NP May 2009 Revision 0
C-37 Unirradiated Lower Shell Forging 125P666 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/27/2009 09:10 AM Page 1 Coefficients of Curve. I A =88.4 B = 86.2 C = 90.59 TO = 2&44 D = 0.OOE+00 Equation is A + B * [Tanh((T-ToY(C+DT))]
Upper Shelf Energy= 174,6(Fixed) Lower Shelf Energy=2.2(Fixed)
Ternp@30 ft-lbs=-46.2 Deg F Temp@50 ft-lbs=-14.9 Deg F Plant: Ginna Material: SA508CL2 Heat 125P666 Orientation: LC Capsule: UNIRR Fluence: n1cn^A2 300 250 200 0
U.
S150 z
100 50 0 -
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential
- 80. 00 7. 50 16.62 -9. 12
- go. 00 4. 00 16. 62 -12.62
- 0.O00 5.00 16.62 -11. 62
-60, 00 23. 00 23 62 - 62
-60. 00 4, 00 23. 62 -19. 62
-60.00 17. 50 23. 62 -6. 12
- 40. 00 20. 00 33. 37 -13. 37
-40. 00 52. 00 33. 37 18. 63
-40. 00 72. 00 33. 37 38. 63 WCAP-17036-NP May 2009 Revision 0
C-38 Unirradiated Lower Shell Forging 125P666 Page 2 Plant: Ginna Material: SA508CL2 Heat: 125P666 Orientation: LC Capsule: UNIRR Fluence: n/crnA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 10.00 61.50 71. 09 -9. 59 10.00 81. 00 7t1. 09 9. 91 1 0. 00 78. 00 7 1. 09 6.91
- 60. 00 128. 00 117. 27 10. 73
- 60. 00 90. 50 117. 27 -26.77
- 60. 00 124. 00 117. 27 6.73 110. 00 12 1.'00 150. 16 .29. 16 110. 00 174. 00 150, 16 23. 84 110.00 143. 50 150. 16 -6. 66 210. 00 190. 00 171.53 18.47 210. 00 164. 50 171. 53 -7. 03 210. 00 201. 00 171. 53 29. 47 Correlation Coefficient = .962 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
C-39 Capsule V Lower Shell Forging 125P666 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02J08/2009 11:56 AM Pare I Coefficients of Curve I A = 79.61 B = 77.41 C = 66.66 TO = 39.09 D = O.00E+00 Equation is A + B * [Tanh((T-To)/(C.+DT))]
Upper Shelf Energy= 157.0 Lower Shelf Energy=2.2(Fixed)
Temp@30 ft-bs=-1 1.5 1eg F Temp@50 ft-lbs=lZ3 Deg F Plant: Giana Material: SA508CL2 Heat: 125P666 Orientation: LC Capsule: V Fluence: n/cmA^2 300
- "killhI'*
'UU 150 -0 C
z t 100 0 so -t_
n ____L__90
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Tcmptratu= Input CVN Computed CVN Differential
-50. 00 5.80 12,20 -6. 40
-10. 00 32. 50 31. 07 1. 43
- 10. 00 41.30 47. 82 -6.52
- 40. 00 84. 50 80. 66 3. 84
- 40. 00 94. 30' 80. 66 13, 64
- 75. 00 99. 50 117. 69 - 18. 19 140. 00 165. 00 149. 86 15. 14 210. 00 146. 00 156. 10 - 10. 10 210.00 155. 50 156. 10 -. 60 WCAP-17036-NP May 2009 Revision 0
C-40 Capsule V Lower Shell Forging 125P666 Pap 2 Plant: Ginna Material: SA50CL2 Heat: 125P666 Orientation: LC Capsule: V Fluence: nfcm^2 Charpy V-Notch Data Tcnmperture Input CVN Computed CVN Differential 500. 00 160. 00 157. 02 2. 98 Cornlation Coefficient =.984 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
C-41 Capsule R Lower Shell Forging 125P666 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02108/2009 12:06 PM Page 1 Coefficients of Curve I A =75. B= 72.8 C= 43.38 TO= 42.54 D= 0.00E+00 Equation is A + B * [Tanh((T-To)Y(C+DT))]
Upper Shelf Energy=-I47.8(Fixed) Lower Shelf Energy)2.2 (Fixed)
Temp@30 ft-lbs-l 1.3 Deg F Temnp@50 ft-lbs=27.1 Deg F Plant: Ginna Material: SA508CL2 Heat: 125P666 Orientation: LC Capsule: R Fluence: n/cnd2 300 I
250
.* 200 S150 CIS uJ 100 50 0
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Tenientue, Input CVN Computed CVN Differential
.00 5. 00 20. 16 -1 5. 16
- 25. 00 63. 00 47. 07 15. 93
- 25. 00 20. 50 47. 07 -26. 57
- 40. 00 79. 00 70. 74 8. 26
- 40. 00 90, 50 70. 74 19. 76
- 77. 00 105.00 123. 11 - 18.
11
- 77. 00 118. 00 123. 11 -5. 11 150. 00 176.00 146. 78 29. 22 199.00 140.00 147. 69' -7. 69 WCAP-17036-NP May 2009 Revision 0
C-42 Capsule R Lower Shell Forging 125P666 Page 2 Plantt: Ginna Material: SA50&CL2 Heat: 125P666 Orientation: LC Capsule: R Fluence: n/cm^2 Charpy V-Notch Data Temperatur Input C'N ComputedCVN Differential 300. 00 127. 50 147. 80 -20. 30 Correation Coefficient =.932 WCAP-1 7036-NP May 2009 Revision 0
C-43 Capsule T Lower Shell Forging 1251P666 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02108/2009 12:09 PM Page 1 Coefficients of Curve I A = 72.35 B =70.15 C=72.13 TO= 37.8 D= 0.00E+00 Equation is A + B * [Tanh((T-To)/(C+DT))]
Upper Shelf Energy= 142.5(Fixed) Lower Shelf Eneurg2.2(Fixed)
Temp@30 ft-lbs-12.6 Deg F Temp@ 50 ft-lbs 14.0 Deg F Plant: Qinna Material: SAS08CL2 Heat: 125P666 Orientation: LC Capsule: T Fluence: nkcnmV2 300 250 t 200 t2 S150 U.
z 100 50 o .
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Ternpenttnr Input CVN Computed CVN Differendal
- 50. 00 12.00 13. 51 -1.51
-10. 00 38. 50 31. 65 6. 85
.00 42. 00 38. 62 3. 38
- 25. 00 36. 00 60. 03 - 24. 03
- 50. 00 94. 50 84. 10 10.40
- 75. 00 121. 00 105. 63 15.37 150. 00 98. 00 136. 51 -38. 51 175. 00 150. 00 139. 44 10. 56 250. 00 140. 00 142. 11 - 2. 11 WCAP-1 7036-NP May 2009 Revision 0
C-44 CapsuleI1 Lower Shell Forging 125IP666 Par, 2 Plant: Ginna Material: SA50SCL2 Heat: 125P666 Orientation: LC Capsule: T Fluence: n/cmnP2 Charpy V-Notch Data Temperatuem. Input CV N Computed CVN Differential 350. 00 137.50 142.48 - 4. 98 Correlation Coefficient = .945 WCAP-17036-NP May 2009 Revision 0
C-45 Capsule S Lower Shell Forging 125P666 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02/08/2009 12:13 PM Page I Coefficients of Curve I A=72.35 B=70.15C=85.77 TO=59.55 D=0.OOE+00 Equation is A + B * [Tanh((T-To)/(C4+DT))]
Upper S helf Energy= 142 5(Fixed) Lower Shelf Energ=-2.2(Fixed)
Temp@30 ft-lb--.4 Deg F Temp@50 ft-lbr=31.3 Deg F Plant: Ginna Material: SAS08CL2 Heat: 125-P666 Orientation: LC Capsule: S Fluence: nlcra2 300 250 200 0
- 150 w
z 100 50 0
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Tenmpcmtum. Input CVN Computed CVN
-45. 00 5.00 13. 47 -8. 47
.00 14.00 30. 21 -16. 21
- 5. 00 32. 00 32. 92 - . 92 15.00 68. 00 38. 87 29. 13 25.00 44. 00 45. 53 -1. 53
- 50. 00 53.00 64. 57 -11. 57
- 75. 00 98. 00 84. 85 13. 15 100.00 92. 00 103. 18 -11, 18 150. 00 125. 00 127. 32 -2. 32 WCAP-17036-NP May 2009 Revision 0
C-46 Capsule S Lower Shell Forging 1251P666 Pag 2 Plant: Ginna Material: SA50CL2 Heat: 125P666 Orientation: LC Capsule: S Fluence: n/cm^2 Charpy V-Notch Data Tempenture. Input CVN Computed CVN Differential 225. 00 134.00 1 39. 60 - 5. 60 250. 00 171. 00 140. 87 30. 13 325. 00 140. 00 142.21 - 2. 21 Corinlation Coefficirnt = .960 WCAP-17036-NP May 2009 Revision 0
C-47 Capsule N Lower Shell Forging 1251P666 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0 11/2.009 09:09 AM Page I Coefficients of Curve I A = 72.25 B = 70.05 C = 90.S8 TO = 108.24 D = 0.OOE+00 Equation is A + B * (Tanh((T-To)/(C+DT))]
Upper Shelf Energy= 142.3(Fixed) Lower Shelf Energy=2.2(Fixed)
Temp@30 ft-lbs-44.9 Deg F Temp@50 ft-lbr=78.4 Deg F Plant Ginna Material: SA5S08CL2 Heat: 125P666 Orientation: LC Capsule: N Fluence: jnA2 300 250 200 0
150 w
100 5o
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperatuir Input CVN Computed CVN Diffrrential
- 25. 00 3. 00 9. 29 -6. 29
- 20. 00 14. 00 19. 77 -5.77
- 30. D0 5. 00 23. 44 -18.44
- 40. 00 4. 00 27. 72 -23. 72
- 50. 00 64. 00 32. 64 31.36
- 55. 00 49. 00 35. 34 13. 66
- 80. 00 63. 00 51. 16 11. 84
- 90. 00 74. 00 58. 37 1 5. 63 100. 00 36. 00 65. 91 -29. 91 WCAP- 17036-NP May 2009 Revision 0
C-48 Capsule N Lower Shell Forging 125IP666 Page 2 Plant: Ginna Material: SA50SCL2 Het: 125P666 Orientation: LC Capsule: N Fluence: nlcm^2 Charpy V-Notch Data Temperatur Input C2VN Computed CVN Differential 350. 00 145.00 141. 62 3. 38 375. 00 141.00 141.91 -. 91 390. 00 141.00 142. 02 -1. 02 Corlation Coefticient = .946 WCAP-17036-NP May 2009 Revision 0
C-49 Unirradiated Lower Shell Forging 125P666 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03127/2009 09: 12 AM Page 1 Coefficients of Curve I A = 43.1 B = 42.1 C = 63.27 TO = -15.97 D = 0.OOE+00 Equation is A + B * [Tanh((T-ToY(C+DT))I Upper Shelf L.E.=85.2(Fixed) Lower Shelf L.E.= I.O(Fixed)
Temp.@LE. 35 mils=-28.2 Deg F Plant: Ginna Material: SA508CL2 Heat: 125P666 Orientation: LC Capsule: UNIRR Fluence: nDcm^A2 200 150 m
100 50 0 +-
-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Tempetx" Input LB. Computed LE. Differenlial
- 80. 00 9. 00 10. 83 -I. 83
- S0. 00 3. 00 10. 83 -7.83
- 80. 00 3. 00 10..83 -7. 83
-60. 00 19. 00 17. 7 7 1.23
-60. 00 3. 00 17. 77 - 14. 77
-60. 00 15. 00 17.77 -2. 77
-40. 00 14. 00 27. 84 -13. 84
-40. 00 42. 00 27. 84 14. 16
-40. 00 56. 00 27. 84 28. 16 WCAP-17036-NP May 2009 Revision 0
C-50 Unirradiated Lower Shell Forging 125P666 Page. 2 Plant: Ginna Material: SA508CL2 Heat: 125P666 Orientation: LC Capsule: UNIRR Fluence: n/cWn'2 Charpy V-Notch Data Temperature Input LE" Computed LE. Differential
- 10. 00 50. 00 59. 47 -9.47
- 10. 00 62. 00 59. 47 2. 53 10.00 61 00 59. 47 1.53 60.00 81. 00 78,21 2. 79
- 60. 00 66. 00 78. 21 12. 21
- 60. 00 80. 00 78. 21 1.79 110.00 75. 00 83. 66 -8. 66 110.00 86. 00 83. 66 2. 34 II0.00 87. 00 83. 66 3, 34 210.00 88. 00 85, 13 2. 87 210.00 82. 00 85. 13 -3.13 210.00 83. 00 85. 13, -2. 13 Correlation Coefficient = .954 WCAP-17036-NP May 2009 Revision 0
C-51 Capsule V Lower Shell Forging 125P666 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02/08/2009 12:01 PM Page I Coefficients of Curve I A=43.24 B=42.24C=44.25 TO= 12.09 D= 0.0E+O0 Equation is A + B * [Tanb((T-To)/(C+DT))]
Upper Shetf L.E.=85.5 Lower Shelf L.E.=1.0(Fixed)
TeImp.@L.E. 35 mils=3.4 Deg F Plant: Ginna Material: SA508CL2 Heat: 125P666 Orienltation: LC Capsule: V Fluence: nfcn*2 200 150 2
C
&100 0 0 5l 0
50 0
-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Trmpermtuir Input L.E. Computed LE Diffretntial
-50. 00 4. 00 5.81 -1. 81
- 10. 00 27. 00 23. 75 3. 25
- 10. 00 36. 00 41. 25 -5. 25
- 40. 00 69. 00 66. 84 2. 16
- 40. 00 72. 00 66. 84 5. 16
- 75. 00 71. 00 80. 84 -9. 84 140. 00 92. 00 85. 23 6. 77 210. 00 70. 00 85. 47 -15. 47 210. 00 90. 00 85. 47 4. 53 WCAP-17036-NP May 2009 Revision 0
C-52 Capsule V Lower Shell Forging 1251P666 Page 2 Plant: Ginna Material: SA509CL2 Heat: 125P666 Orientation: LC Capsule: V Fluen: n/cnm^2 Charpy V-Notch Data Tempernture Input L.E. Computed L.E Differential 500. 00 95. 00 85. 49 9. 5 1 Correlation Coefficient = .965 WCAP-17036-NP May 2009 Revision 0
C-53 Capsule R Lower Shell Forging 125P666 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02108/2009 12:07 PM Page 1 Coefficients of Curve I A = 45.5 B = 44.5 C = 22.93 TO = 29.06 D = 0.00E+00 Equation is A + B * [Tanh((T-Toy(C+DT))]
Upper Shelf L.E.=90.0(Fixed) Lower Shelf LE= I.0(Fixed)
Temp. @LE 35 mils=23.6 Deg F Plant Ginna Material: SA508CL2 Heat: 125P666 Orientation: LC Capsule: R Fluence: n/cmA2 200 150 E
1.
100 50 0 -
-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Termnprtutr Input LE. Co nputed LE. Differwntial 00 5. 00 7. 54 - 2. 54
- 25. 00 55. 00 37. 70 17. 30
- 25. 00 20. 00 37. 70 -17.70
- 40. 00 62. 00 65. 26 -3. 26
- 40. 00 71.00 65. 26 5. 74
- 77. 00 81. 00 88. 66 -7. 66
- 77. 00 81.00 88. 66 -7. 66 150. 00 89. 00 90. 00 - 1. 00 199. 00 90. 00 90. 00 .00 WCAP-17036-NP May 2009 Revision 0
C-54 Capsule R Lower Shell Forging 1251P666 Paw. 2 Phult: Ginna Material: SA50CL2 Heat: 125P666 Orientation: LC Capsule: R Fluence: n/cmA^2 Charpy V-Notch Data Tempnmtut Input L.E. Computed LE. Differential 300. 00 91. 00 90. 00 1. 00 Correlaition Coefficient = .953 WCAP-1 7036-NP May 2009 Revision 0
C-55 Capsule T Lower Shell Forging 1251P666 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02/08/2009 12:10 PM Page I Coefficients of Curve I A = 41.55 B = 40.55 C = 76.65 TO = 13.59 D = .OOEE+00 Equation is A + B * [Tanh((T-ToY(C+.DT))]
Upper Shelf L.E.=82. I (Fixed) Lower Shelf L.E.= I .0(Fixed)
Temp.@LE. 35 mils=1. 1 Deg F Plant Ginna Material: SA508CL2 Heat: 125P666 Orientation: LC Capsule: T Fluence: nlcra"2 200 150 E
C a 100 so o-30
-300.0 0.0 300.0 600.0 Temperature in Deg F Chmrpy V-Notch Data Temper.tuir Input L.E. Computed LE Difl~m*nfial
-50. 00 7. 10 13. 97 -6. 87
-10. 00 44. 50 29. 45 15.05
.00 31. 50 34. 43 - 2. 93
- 25. 00 35. 80 47. 54 11.74
- 50. 00 59. 10 59. 48 -. 38
- 75. 00 79. 10 68. 50 10. 60 150. 00 65. 80 79. 86 14. 06 175. 00 84. 30 80. 92 3. 38 250. 00 84. 50 81. 93 2. 57 WCAP- 17036-NP May 2009 Revision 0
C-56 Capsule T Lower Shell Forging 1251P666 Page 2 Plant: Ginna Material: SA509CL2 Heat: 125P666 Orientation: LC Capsule: T Fluence: nlcnm2 Charpy V-Notch Data Temperaturm Input L.E. Computed L.F. Diftrential 350. 00 77, 50 82. 09 -4. 59 Correlation Coefficient =. 937 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
C-57 Capsule S Lower Shell Forging 12511666 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/1112009 08:33 AM Page I Coefficients of Curve I A = 43.5 B = 42.5 C = 69.3 TO = 3483 D = 0.OOE+00 Equation is A + B * [Tanh((T-ToY(C+DT))]
Upper Shelf L.E.=86.0(Fixed) Lower Shelf L E.= I.0(Fixed)
Termp. @LE. 35 mils=20.8 Deg F Plant: Ginna Material: SA508CL2 Heat: 12-5P666 Orientation: LC Capsule: S Fluence: nr/CuA2 200 ISO E
a100 A ----- 4 0
50 0
0 01
-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Tmp.rnturr Input L.E. Coutputed LE Diftfemntial
- 45. 00 4. 00 8. 72 -4. 72
.00 12.00 23. 77 -11.77 5.00 26. 00 26. 26 -. 26 15.00 52. 00 31. 66 20. 34
- 25. 00 36. 00 37. 51 -1.51
- 50. 00 43. 00 52. 66 -9.66
- 75. 00 74. 00 65. 70 8. 30 1oo, 00 68. 00 74. 76 -6.76 150. 00 83. 00 83. 05 - . 05 WCAP-17036-NP May 2009 Revision 0
C-58 Capsule S Lower Shell Forging 1251P666 Paw 2 Plant: Ginna Material: SA508CL2 Heat: 125P666 Orientation: LC Capsule: S Fluence: ncneA2 Charpy V-Notch Data Temperntur Input LE. Computed L.E Differential 225.00 87. 00 85. 65 1.35 250. 00 86. 00 85. 83 17 325. 00 88. 00 85. 98 2. 02 Correlation Coefficient =.961 WCAP-17036-NP May 2009 Revision 0
C-59 Capsule N Lower Shell Forging 1251)666 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0305/2009 09:16 AM Paw I Coefficients of Curve I A=4k B=42.C=75.92 TO=78.99 D=O.OOE+00 Equation is A + B * [Tanh((T-ToY(C,+DT))]
Upper Shelf L.E.=85.0(Fixed) Lower Shelf L E= I.0(Fixed)
Temp. @LE 35 mils=64.4 Deg F Plant: Girna Material: SA508CL2 Heat: 125P666 Orientation: LC Capsule: N Fluence: IcVnv2 200 150 ISO C
.2 EL100 0
0 50 0
0
-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data aTmeratum Input L.E. Coiputed LE. Diffemntial
- 25. 00 6. 00 6. 10 -. 10
- 20. 00 12. 00 15. 66 -3.66
- 30. 00 7. 00 19. 12 -1 2. 1 2
- 40. 00 7. 00 23. 14 -16. 14
- 50. 00 48. 00 27. 70 20. 30
- 55. 00 40. 00 30. 15 9. 85
- 80. 00 51. 00 43. 56 7. 44
- 90. 00 56. 00 49. 05 6. 95 1oo. 00 35. 00 54. 33 -19. 33 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
C-60 Capsule N Lower Shell Forging 1251P666 Pap 2 Plant: Ginna Material: SA50SCL2 Heat: 125P666 Orientation: LC Capsule: N Fluence: n/cniA2 Charpy V-Notch Data Tenperatum Input L.E. Computed LE Differntial 350. 00 88. 00 84. 93 3. 07 375. 00 84. 00 84. 97 -. 97 390. 00 83. 00 84. 98 -1.98 Cormlation Coefficient =. 930 WCAP-17036-NP May 2009 Revision 0
C-61 Unirradiated Lower Shell Forging 125P666 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/27/2009 09:13 AM Page I Coefficients of Curve I A = 50. B =50. C = 75.69 TO = 44.23 D = 0.OOE+00 Equation is A + B * [Tanh((T-Toy(C+DT))]
Temperature at 50% Shear = 44.3 Plant: Ginna Material: SA508CL2 Heat 125P666 Orientation: LC Capsule: UNIRR Fluence: n/cm"2 125 100 CD 75-U-
0 25 0
0 00
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input Perent Shear Computed Percent Shear Differential
-80. 00 1.00 3. 62 -2. 62
-80.00 1.00 3. 62 -2. 62
-80.00 1. 00 3.62 -2. 62
- 60. 00 10 00 5. 98 4. 02
-60.00 5. 00 5.98 -. 98
-60,00 10.00 5.98 4. 02
-40.00 5. 00 9.75 -4.75
-40.00 15.00 9.75 5. 25
-40.00 25. 00 9.75 15.25 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
C-62 Unirradiated Lower Shell Forging 125P666 Page 2 Plant: Ginna Material: SA508CL2 Heat: 115P666 Orientation: LC Capsule: UNIRR Fluence: n/cmn2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 10.00 25. 00 28. 81 -3. 81 10.00 30. 00 28. 81 1.19
- 10. 00 30. 00 28. 81 1.19
- 60. 00 60. 00 60. 27 -. 27
- 60. 00 45. 00 60. 27 15.27
- 60. 00 60. 00 60. 27 -. 27 11I0. 00 75. 00 85. 04 10.04 110.00 100. 00 85. 04 14. 96 110.00 100.00 85. 04 14.96 210.00 100.00 98. 76 1.24 210.00 100.00 98. 76 1.24 210.00 100.00 98. 76 1.24 Correlation Coefficient= .981 May 2009 WCAP-l 7036-NP WCAP-17036-NP May 2009 Revision 0
C-63 Capsule R Lower Shell Forging 125P666 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02/08/2009 12:08 PM Page 1 Coefficients of Curve I A=50. B =50. C=47.48 TO=50.41 D=0.O0E+00 Equation is A + B * [Tanh((T-ToY(C+DT))]
Temperature at 50% Shear = 50.5 Plant Ginna Material: SAS08CL2 Heat: 125P666 Orientation: LC Capsule: R Fluence: tVcm'12 125 100 75 e,
CI PI a- 50 25 0
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Tempe-ratumr Input Perent Shear Computed PNroent Shear Diffeiretial
.00 5. 00 10.68 - 5. 68
- 25. 00 30. 00 25. 53 4. 47
- 25. 00 15. 00 25. 53 -10. 53
- 40. 00 40. 00 39. 21 .79
- 40. 00 50. 00 39. 21 10.79
- 77. 00 70. 00 75. 40 - 5. 40
- 77. 00 75. 00 75. 40 -. 40 150. 00 99. 00 98. 52 48 199. 00 100. 00 99. 81 19 WCAP-17036-NP May 2009 Revision 0
C-64 Capsule R Lower Shell Forging 125P666 Page 2 Plant: Ginna Material: SA508CL2 Heat: 125P666 Orientation: LC Capsule: R Fluence: n/cra^2 Charpy V-Notch Data Temperature Input Perce.nt Shear Computed Percent Shear Differential 300. 00 99.00 100.00 - 1. 00 Correlation Coefficient =.987 WCAP-17036-NP May 2009 Revision 0
C-65 Capsule T Lower Shell Forging 1251P666 CVIGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0210812009 12:11 PM Page 1 Coefficients of Curve I A=50. B=50. C=85.95 TO=56.7 D=0OO0E+00 Equation is A + B
- ITanh((T-ToY(C+DT))]
Temperature at 50% Shear = 56.7 Plant: Qinna Material: SA5O8CL2 Heat: 125P666 Orientation: LC Capsule: T Fluence: n/cm'*2 125 100 0)
Il o,.
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperuture. Input Percent Shear Computed Percent Shear Diffrential
-50. 00 2. 00 7.71 - 5. 71
- 10. 00 26. 00 17. 48 8. 52
.00 22. 00 21. 09 .91
- 25. 00 18.00 32. 35 -14.35
- 50. 00 47. 00 46. 11 .89
- 75. 00 74. 00 60. 49 13.51 150. 00 72. 00 89. 76 -17.76 175. 00 10oo 00 94. 01 5. 99 250. 00 1oo. 00 98. 90 1.10 WCAP-17036-NP May 2009 Revision 0
C-66 Capsule T Lower Shell Forging 125P666
. Page 2
Plant: Ginna Material: SA508CL2 Heat: 125P666 Orientation: LC Capsule: T Fluenoe: n/cn-ib2 Charpy V-Notch Data Temperaturr Input Percent Shear Computed Percent Shear Differential 350. 00 100. 00 99. 89 .1I1 Correlation Coefficient =.967 WCAP-17036-NP May 2009 Revision 0
C-67 Capsule S Lower Shell Forging 12511666 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02(0812009 12:15 PM Page 1 Coefficients of Curve I A=50f B=50. C=63.9 TO= 38.29 D = 0.00E+0O Equation is A + B * [Tanh((T-To)/(C+DT))]
Temperature at 50% Shear = 38.3 Plant Ginna Material: SAS08CL2 Heat: 125P666 Orientation: LC Capsule: S Fluence: rn^mA2 125 100 N. 75 e 50 25
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data lnput Percent Shear Computed L-roent Shear Differential
-45.00 5. 00 6. 87 - 1. 87
.00 10.00 23. 17 - 13. 17 5.00 25. 00 26. 08 -1. 08 15.00 50. 00 32. 54 17. 46
- 25. 00 45. 00 39. 75 5. 25
- 50. 00 45. 00 59. 06 -14. 06
- 75. 00 80. 00 75. 93 4. 07 100. 00 90. 00 87. 34 2. 66 150. 00 95. 00 97. 06 - 2. 06 WCAP-17036-NP May 2009 Revision 0
C-68 Capsule S Lower Shell Forging 1251P666 Page 2 Plant: Ginna Material: SA509CL2 Heat: 125P666 Orientation: LC Capsule: S Fluence: nlcm^2 Charpy V-Notch Data Tempemrture Input Percent Shear Computed Percent Shear Differential 225.00 100. 00 99. 71 .29 250. 00 100. 00 99. 87 .13 325.00 100. 00 99. 99 . 01 Cormlation Coefficient = .974 May 2009 WCAP-l 7036-NP WCAP-17036-NP May 2009 Revision 0
C-69 Capsule N Lower Shell Forging 12517666 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0-V0512009 09:16 AM Pag I Coefficients of Curve I A = 50. B = 50. C = 64.75 TO = 100.25 D = 0.OOE+00 Equation is A + B * [Tanh((T-ToY(C+DT))]
Temperature at 50% Shear= 100.3 Plant: Ginna Material: SA508CL2 Heat: 125P666 Orientation: LC Capsule: N Fluence: nIcmA2 125 100 75 IL e
0 50 25 0 i
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data TerimpqrntuI' Input Percent Shear Computed Percnt Shear Differential
- 25. 00 2.00 2. 05 - . 05
- 20. 00 5. 00 7. 73 -2. 73
- 30. 00 5.00 10. 25 -5. 25
- 40. 00 5. 00 13. 46 -8. 46
- 50. 00 25. 00 17. 48 7. 52
- 55. 00 20. 00 19.82 go. 00 45. 00 34. 85 10..181 5
- 90. 00 45. 00 42. 15 2. 85 0oo. 00 40. 00 49. 80 -9.80 May 2009 WCAP-l 7036-NP WCAP-17036-NP May 2009 Revision 0
C-70 Capsule N Lower Shell Forging 125IP666 Pag 2 Plant: Ginna Material: SA50CL2 Heat: 125P666 Orientation: LC Capsule: N Fluence: n/cm12 Charpy V-Notch Data Temperature hput P*xeent Shear Computed Percent Shear Diffcrential 350. 00 100.00 99. 96 *04 375. 00 100. 00 99. 98 *02 390. 00 100. 00 99. 99 .01 Correlation Coefficient =. 989 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
C-71 Unirradiated Weld Heat 61.782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03f10/2009 10:34 PM Page 1 Coefficients of Curve I A=40.6 B=38.4C=93.15 TO=-8.3 D=0.00E+00 Equation is A + B
- ITanh((T-ToY(C+DT))]
Upper Shelf Energy=79.0(Fixed) Lower Shelf Energ)-y2.2(Fixed)
Telmp@ 30 ft-lbs=-34.7 Deg F Temp@50 ft-lbs=15.0 Deg F Plant. Ginna Material: SAW Heat 61782 Orientalion: NA Capsule: UNIRR Fluence: r'cmnA2 300 250 200 0
150 C
w z
100 50 0 't 1- . 1 - -
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Tmlperutuir Input CV N Compubrd CVN Differential
-90. 00 7. 50 13. 53 -6.03
-90.00 8. 50 13. 53 - 5. 03
- 90.00 8. 50 13. 53 -5. 03
-65. 00 26. 00 19. 74 6. 26
- 65. 00 26. 50 19.74 6. 76
-65. 00 8. 00 19. 74 -11. 74
-40. 00 34. 00 28. 02 5. 98
-40. 00 35. 00 28. 02 6. 98
-40. 00 35. 00 28. 02 6. 98 WCAP- 17036-NP May 2009 Revision 0
C-72 Unirradiated Weld Heat 61782 Pag 2 Plant: Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: UNIRR Fluence: n/cnr"2 Charpy V-Notch Data Temperatur Input C-VN Computed CVN Differential
- 10. 00 51.00 48. 05 2. 95
- 10. 00 42. 50 48. 05 -5. 55
- 10. 00 39. 00 48. 05 05
- 60. 00 54. 00 64. 60 -10. 60
- 60. 00 66. 50 64. 60 1. 90
- 60. 00 71. 00 64. 60 6. 40 110. 00 79. 50 73. 39 6. 11 110. 00 70. 50 73. 39 -2. 89 110. 00 76. 50 73. 39 11 160. 00 77. 00 76. 98 02 160. 00 79. 50 76. 98 2. 52 160. 00 76. 50 76. 98 48 210. 00 80. 00 78. 30 1. 70 210. 00 74. 00 78. 30 - 4. 30 210. 00 83. 00 78. 30 4. 70 Corelation Coefficient = .975 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
C-73 Capsule V Weld Heat 61.782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/11/2009 08:38 AM Paw I Coefficients of Curve I A = 2&72 B = 26.52 C = 10L65 TO = 107. D = 0.00E+O0 Equation is A + B * [Tanh((T-Toy(C+DT))]
Upper Shelf Energ=55.2 Lower Shelf Energy=2.2(Fixed)
Temp@30 ft-lbs1 12.0 Deg F Temp@50 ft-lbs219.4 Deg F Plant Ginna Material: SAW Heat 61782 Orientation: NA Capsule: V Fluence: n/cMA2
'bA*
aUU 250-
-r 200 A
150 0
8S 100 501___
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Tempemrtum Input CVN Computed CVN Differnti1al
- 10. 00 9. 80 9. 05 .75
- 40. 00 12.00 13. 40 -1. 40
- 75. 00 23. 00 20. 64 2. 36 125.00 29. 50 33. 37 -3.87 125.00 34. 50 33. 37 1. 13 175. 00 47. 00 44. 21 2. 79 175. 00 42. 30 44. 21 -1. 91 210.00 50. 50 49. 06 1.44 300. 00 53. 30 54. 08 -. 78 WCAP-17036-NP May 2009 Revision 0
C-74 Capsule V Weld Heat 61782 Page 2 Plant: Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: V FRlence: ncmnV2 Charpy V-Notch Data Temperature Input CVN Computed C-N Differential 500. 00 55. 00 55. 22 -. 22 Cornlation Coefflcient =.992 WCAP-17036-NP May 2009 Revision 0
C-75 Capsule R Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/27/2009 09:27 AM Page I Coefficients of Curve I A = 25-55 B = 23.35 C = 81.21 TO = 105.77 D = O.OOE+00 Equation is A + B * [Tanh((T-ToY(C+DT))]
Upper Shelf Energy=48.9(Fixed) Lower Shelf Energyz2.2(Fixed)
Temp@30 ft-lbs=121.5Deg F Temp@50 ft-lbs= NA Plant: Ginna Material: SAW Heat 61782 Orientation: NA Capsule.: R Fluennce, n/cnA2 300 250
- 200 0
150 w
z 100 50 0
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperamre Input CVN Conputed CVN Differential
- 17. 00 21. 00 17.61 3. 39 150.00 35. 00 37. 14 -2.14 150. 00 30, 00 37. 14 -7. 14 199,00 50. 00 44. 63 5. 37 200.00 50. 00 44.72 5. 28 250.00 53. 00 47. 60 5. 40 250.00 47. 00 47. 60 60 300. 00 49. 00 48. 51 49 350. 00 43. 00 48. 79 -5. 79 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
C-76 Capsule R Weld Heat 61782 Page 2 Plant Ginna Material: SAW Heat: 6178:2 Orientation: NA Capsule: R Fluence: n/cm^2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 350. 00 50. 00 48. 79 1.21 Correlation Coefficient = .904 WCAP-17036-NP May 2009 Revision 0
C-77 Capsule T Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/27/2009 09:34 AM Page 1 Coefficients of Curve I A = 27.45 B = 25.25 C = 107.87 TO = 104.06 D = 0.OOE+00 Equation is A + B . [Tanh((T-Toy(C+DT))]
Upper Shelf Energy=52.7(Fixed) Lower Shelf Energay2.2(Fixed)
Temp@30 ft-tbs=l 15.0 Deg F Temp@50 ft-lbs=259. IDeg F Plant Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: T reco Fluenme nk/nP2 300 250 200 0
150 z
100 5o
- -~ -~- - - - -t-0
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differenftial
.00 5. 00 8. 60 -3. 60
- 75. 00 22. 00 20. 81 1, 19 125.00 29. 00 32.29 -3. 29 150. 00 35. 50 37.60 -2. 10 210. 00 41. 00 46.49 -5. 49 250.00 46. 50 49. 54 - 3. 04 300. 00 50. 50 51. 40 90 350. 00 52. 50 52. 18 32 425. 00 55. 50 52. 57 2. 93 WCAP-17036-NP May 2009 Revision 0
C-78 Capsule T Weld Heat 61782 Page 2 Plant: Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: T reco Fluence: ncm^2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 425. 00 63. 00 52. 57 10. 43
- 70. 00 22. 00 19. 73 2. 27 150.00 43. 00 37.60 5. 40 210.00 47, 00 46, 49 .51 210. 00 50. 00 46. 49 3.51 300. 00 53. 00 51. 40 1.60 350.00 52. 00 52. 18 -. 18 350. 00 52. 00 52. 18 18 425. 00 49. 00 52. 57 -3. 57 Correlation Coefficient =.966 WCAP-17036-NP May 2009 Revision 0
C-79 Capsule S Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/27/2009 09:38 AM Page I Coefficients of Curve I A= 27.2 B= 25. C= 118.42 TO- =164.17 )= 0.OOE+00 Equation is A + B * [Tanh((T-Toy(C+DT))]
Upper Shelf Energr52.2(Fixed) Lower Shelf Energy=2.2(Fixed)
Temp@30 ft-lbs=lT77.5 Deg F Temp@50 ft-lbs=346.5 Deg F Plant: Ginna Material: SAW Heat 61782 Orientation: NA Capsule: S Fluen'e: nra^2 300 250 A200 10 0
150 w
z 100 0
50 0n 0
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential
. 00 6. 00 5. 14 .86
- 50. 00 8. 00 8. 55 55 100. 00 18. 00 14, 84 3. 16 125.00 14.00 19. 22 -5. 22 150. 00 32. 00 24. 22 7. 78 175.00 25. 00 29. 48 -4.48 200. 00 33. 00 34. 54 -1.54 250.00 43. 00 42.70 . 30 300. 00 45. 00 47. 62 -2.62 WCAP- 17036-NP May 2009 Revision 0
C-80 Capsule S Weld Heat 61782 Page 2 Plant Ginna Material: SAW Heal: 61792 Orientation: NA Capsule: S Fluence: n/km^2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 350. 00 53. 00 50. 12 2. 88 400. 00 57. 00 51. 29 5. 71 450. 00 63. 00 51. 80 11.20 Correlation Coefficient = .970 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
C-81 Capsule N Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/27/2009 09:42 AM Page 1 Coefficients of Curve I A =27.05 R = 24.85 C = 62.8 TO = 174.64 D = 0.00E+00 Equation is A + B * [Tanh((T-To/(C+DT))]
Upper Shelf Energy=51.9(Fixed) Lower Shelf Energy=2.2(Fixed)
Temp@30 ft-lbs=182,2 Deg F Temp@50 ft-lbs=276.0 Deg F Plant Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: N Fluence: n/cmA2 300 250 200 0
w 100 0
50 I- I-r 0
0
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0, 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperamre Input CVN Computed CVN Diflenential
- 00 4. 00 2. 39 1.61 150. 00 22. 00 17,77 4. 23 200-00 26. 00 36. 57 - 10, 57 210. 00 37. 00 39. 73 - 2.73 220. 00 46. 00 42,41 3. 59 230. 00 52.00 44. 62 7. 38 240. 00 52. 00 46. 39 5. 61 260. 00 45. 00 48. 82 -3. 82 280.00 51.00 50. 22 .78 WCAP-17036-NP May 2009 Revision 0
C-82 Capsule N Weld Heat 61782 Page 2 Plant Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: N Fluence: n/cnrA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 350. 00 50. 00 51.71 -1.71 375. 00 64. 00 51 .82 12. 18 400. 00 49. 00 51. 86 -2.86 Correlation Coefficient = .932 WCAP-17036-NP May 2009 Revision 0
C-83 Unirradiated Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0310/2009 10:36 PM Page 1 Coefficients of Curve I A= 40.35 B=39.35 C=97.25 TO=-8.12 D=0.00E+O0 Equation is A + B
- tTanh((T-To)l(C+DT)y]
Upper Shelf L.E,=79.7 (Fixed) Lower Shelf LE= I.0(Fixed)
Temp. A-E 35 rmil,--21.4 Deg F Plant Ginna Mateiial: SAW Heat: 61782 Ouientalion: NA Capsule: UNIRR Fluence: anCA2 200 ISO E
a 1oo 50 0 0.0
-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Tempeatum. Input L.E. Computed LE Differential
-90. 00 10. 00 13. 32 -3.32
- 90. 00 10.00 13. 32 -3.32
-90. 00 10. 00 13. 32 -3. 32
- 65. 00 28. 00 19.64 8. 36
-65. 00 12. 00 19.64 -7.64
- 65. 00 12.00 1 9.64 -7.64
- 40. 00 33. 00 27. 89 5.11
- 40. 00 37. 00 27. 89 9.1I
- 40. 00 35. 00 27. 89 7. 11 WCAP-17036-NP May 2009 Revision 0
C-84 Unirradiated Weld Heat 61782 Page 2 Plant: Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: UNIRR Flueno: n/cm^2 Charpy V-Notch Data Ternperutuir Input L.E. Computed L.F- Difterential
- 10. 00 51. 00 47. 60 3. 40
- 10. 00 43. 00 47. 60 -4. 60 10.00 39. 00 47. 60 -8. 60
- 60. 00 57. 00 64. 14 -7. 14
- 60. 00 66. 00 64. 14 1. 86
- 60. 00 68. 00 64. 14 3. 86 110. 00 76. 00 73. 33 2. 67 110. 00 74. 00 73. 33 .67 110. 00 78. 00 73. 33 4. 67 160. 00 75. 00 77. 30 -2. 30 160. 00 76. 00 77. 30 -1.30 160. 00 72. 00 77. 30 -5. 30 210. 00 79. 00 78. 82 .18 210. 00 76. 00 78. 82 -2. 82 210. 00 84. 00 78. 82 5. 18 Correlation Coefficient = .980 WCAP-17036-NP May 2009 Revision 0
C-85 Capsule V Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0N 11/12009 08:41 AM Pare I Coefficients of Curve I A = 28.08 B = 27.08 C = 110.38 TO = 130.69 D =0.OOE+00 Equation is A + B * [Tanh((T-To)(CA-DT))]
Upper Shelf L.E.=55.2 Lower Shelf L.E.=I.0(Fixed)
Temp.DLF 35 mils=159.6 Deg F Plant Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: V Fluence: n/cr^2 200 I SO jo 5l 100 50 0
0
-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Ternrmtuar Input LE. Con*puted LE, Diftexnrial
- 10. 00 9. 00 6. 47 2. 53
- 40. 00 12.00 9. 77 2. 23
- 75. 00 17. 00 15. 47 1. 53 125. 00 21.00 26. 68 - 5. 68 125. 00 23. 00 26. 68 -3.68 175. 00 38. 00 38. 40 -. 40 175. 00 46. 00 38. 40 7. 60 210. 00 45. 00 44. 76 . 24 300. 00 51.00 52. 75 - 1.75 WCAP-17036-NP May 2009 Revision 0
C-86 Capsule V Weld Heat 61.782 Page 2 Plant: Ginna Material: SAW Heat: 61782 Orientation: NA Capsile: V FIuence: nniV'2 Charpy V-Notch Data Temperature. Input L.E. Computed LE Differential 500. 00 55. 00 55. 09 -. 09 Correlation Coefficient =.977 WCAP-17036-NP May 2009 Revision 0
C-87 Capsule R Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0312712009 09W.30 AM Page 1 Coefficients of Curve I A = 26.7 B = 2.7 C = 83.77 TO = 110.68 D = 0.OE+00 Equation is A + B
- ITanh((T-Toy(C+DT))]
Upper Shelf L.E.--52.4(Fixed) Lower Shelf LE.=l.0(Fixed)
Temp.@LE 35 mils= 138.8 Deg F Plant Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: R Fluence: nlc/n2 200 150
.0 5.100 50 0/9 .
0
-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input LP Computed LE. Differential
- 77. 00 21. 00 16. 89 4. 11 150.00 34. 00 37. 95 3. 95 150.00 32. 00 37. 95 5. 95 199.00 51.00 46. 84 4. 16 200.00 53. 00 46. 95 6. 05 250.00 54.00 50. 62 3, 38 250.00 51, 00 50. 62 38 300.00 54. 00 51. 85 2. 15 350.00 .52. 00 52. 23 - . 23 I
WCAP-17036-NP May 2009 Revision 0
C-88 Capsule R Weld Heat 61782 Page 2 Plant Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: R Fluence: n/cm^2 Charpy V-Notch Data Temperature Input LE Computed LE. DifferentaI 350. 00 52. 00 52. 23 - .23 Correlation Coifficient = .948 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
C-89 Capsule T Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/27/2009 09:36 AM Page I Coefficients of Curve I A = 24.8 B = 23.8 C = 118.13 TO = 117.06 D = 0.OOE+00 Equation is A + B
- iTanh((T-Toy(C+DT))I Upper Shelf L.E.=48.6(Fixed) Lower Shelf LE.=l.0(Fixed)
Temp.@LE. 35 mils=171.2 Deg F Plant Ginna Material: SAW Heat 61782 Orientation: NA Capsule: T reco Fluence: n/enP2 200 150 E
100 0i so 50lo 0 8 0 0 0 0
0
-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperamre Input L2. Computed LE. Di-24ia
. 00 4. 30 6. 77 -2. 47 75.00 14. 20 16,67 - 2. 47 125,00 28. 40 26.40 2. 00 150.00 23. 60 31, 27 -7. 67 210,00 35. 00 40. 43 - 5. 43 250. 00 34. 50 44, 06 -9. 56 300.00 44. 50 46, 54 -2.04 350.00 -38, 20 47. 70 -9. 50 425. 00 52. 00 48. 34 3. 66 May 2009 WCAP- 7036-NP WCAP-117036-NP May 2009 Revision 0
C-90 Capsule T Weld Heat 61782 Page 2 Plant Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: T mco Fluence: n/cmA^2 Charpy V-Notch Data Temperature Input LE Computed LE. Differmntial 425. 00 56. 30 48. 34 7. 96
- 70. 00 17.50 15.79 1.7 1 150. 00 41.50 31. 27 10.23 210. 00 41. 50 40. 43 1. 07 210. 00 44. 50 40. 43 4. 07 300. 00 50. 00 46. 54 3. 46 350. 00 53. 50 47. 70 5. 80 350. 00 55. 00 47. 70 7. 30 425. 00 53. 00 48. 34 4. 66 Correlation Coefficient = .923 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
C-91 Capsule S Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0312712009 09:39 AM Page I Coefficients of Curve I A = 27.1 B = 26.1 C = 127.22 TO = 161.94 D = O.OOE+00 Equation is A + B * [Tanh((T-Toy(C+DT))]
Upper Shelf L.E.--53.2(Fixed) Lower Shelf LE.=1.0(Fixed)
Temp.@LE. 35 mils=201.7 Deg F Plant Ginna Material: SAW Heat 61782 Orientation: NA Capsule: S Fluence: Wcm^2 200 150 a100 0
5o 0 0 o 0
0
-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperacufe lnpM LE Computed LE. Differential 00 6. 00 4. 80 1. 20
- 50. 00 9.00 8. 66 .34 100.00 18. 00 15.31 2. 69 125. 00 16. 00 19.73 -3.73 150.00 31. 00 24. 66 6. 34 175.00 27. 00 29. 77 -2.77 200. 00 30. 00 34. 68 68 250. 00 44. 00 42. 74 1. 26 300. 00 46. 00 47. 85 -1. 85 WCAP-17036-NP May 2009 Revision 0
C-92 Capsule S Weld Heat 61782 Page 2 Plant: Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: S Fluence: n/cm"2 Charpy V-Notch Data Temperature Input LE Computed LE. Diffential 350. 00 47. 00 50. 62 - 3. 62 400. 00 74. 00 51 . 99 22. 01 450. 00 55. 00 52. 64 2. 36 Correlation Coefficient = .938 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
C-93 Capsule N Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/27n2009 09:43 AM Page I Coefficients of Curve I A = 25.5 B = 24.5 C = 88.93 TO = 172.11 D = 0.OOE+0O Equation is A + B * [Tanh((r-Toy(C+DT))]
Upper Shelf L.E.=50.0(Fixed) Lower Shelf LE.=1.0(Fixed)
Temp.@LE. 35 mils=208.5 Deg F Plant Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: N Fluence: n/cmA2 200 150
, 100 0
50 0u- o 0
n j
-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Tempenribre Input LF. Computed LE. Differential 00 7. 00 2.00 5, 00 150.00 23. 00 19. 53 3. 47 200. 00 25. 00 32. 94 -7. 94 210.00 34. 00 35. 35 -1. 35 220. 00 39. 00 37. 55 1. 45" 230.00 44.00 39. 52 4. 48 240.00 43, 00 41. 25 1. 75 260.00 41.00 44.04 -3.04 280. 00 45. 00 46.02 - . 02 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
C-94 Capsule N Weld Heat 61782 Page 2 Plant Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: N Fluence: n/cnlA2 Charpy V-Notch Data TemperUtire Input LE Computed L2. Differential 350. 00 46. 00 49. 12 -3.12 373. 00 85. 00 49. 49 35.51 400. 00 46. 00 49.71 -3. 71 Correlation Coefficient = .806 May 2009 WCAP-l 7036-NP WCAP-17036-NP May 2009 Revision 0
C-95 Unirradiated Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03110/2009 10:44 PM Page I Coefficients ofCurve I A = 50L B = 50. C = 93.94 TO = -25.4 D = 0.00E+00 Equation is A + B * [Tanh((T-ToY(C+DT))]
Tempemture at 50% Shear = -25.4 Plant Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: UNIRR Fluence: n ,cm^2 125 100 I-75 C)
C) 50 a.
25
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Tempemrtur. Input Percent Shear Computed Percent Shear Differential
- 90. 00 15.00 20. 18 -5. 18
- 90. 00 20. 00 20. 18 -. 18
- 90. 00 20. 00 20. 18 -. 18
- 65. 00 40. 00 30. 09 9. 91
-65. 00 35. 00 30. 09 4. 91
- 65. 00 30.00 30. 09 -. 09
- 40. 00 40. 00 42. 29 - 2. 29
-40. 00 40. 00 42. 29 - 2. 29
- 40. 00 40. 00 42. 29 - 2.29 WCAP-17036-NP May 2009 Revision 0
C-96 Unirradiated Weld Heat 61782 Page 2 Plant: Ginna Mateial: SAW Heat: 61782 Orientation: NA Capsule: UNIRR Fluence: ncn-t2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Diffirential
- 10. 00 75. 00 68. 00 7. 00
-3
- 10. 00 65. 00 68. 00 00
- 10. 00 60. 00 68. 00 00
- 60. 00 65. 00 86. 04 21. 04
- 60. 00 95. 00 86. 04 3. 96
- 60. 00 95. 00 86. 04 8. 96 110. 00 98. 00 94. 70 39. 30 110. 00 100. 00 94. 70 5. 30 110. 00 98. 00 94. 70 30 160. 00 100. 00 98. 11 1. 89 160. 00 100. 00 98. 11 1. 89 160. 00 100. 00 98. 11 1. 89 210.00 100. 00 99. 34 66 210.00 100. 00 99. 34 66 210.00 100. 00 99. 34 66 Corelation Coefficient = .980 WCAP-17036-NP May 2009 Revision 0
C-97 Capsule R Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03127n2009 09:31 AM Page I Coefficients of Curve I A = 50. B = 50. C = 55.19 TO = 143.78 D = O.OOE+0O Equation is A + B
- ITanh((T-Toy(C+DT))]
Temperature at 50% Shear= 143.8 Plant: Ginna Material: SAW Heat 61782 Orientation: NA Capsule: R Fuence: n/cn-r2 125 100 0 75 50 25 0 - -----
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Compued Percent Shear Differential 77.00 30. 00 8. 17 21. 83 150.00 50. 00 55. 61 -5. 61 150.00 45. 00 55. 61 10. 61 199.00 100. 00 88. 09 21.91 200.00 99. 00 88. 47 10. 53 250. 00 99. 00 97.92 1. 08 250.00 99. 00 97.92 1.08 300.00 100. 00 99. 65 35 350.00 100. 00 99.94 .06 WCAP-17036-NP May 2009 Revision 0
C-98 Capsule R Weld Heat 61782 Page 2 Plant: Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: R Fluence: ncrnm^2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 350. 00 100. 00 99. 94 .06 Correlation Coefficient = .952 WCAP-1 7036-NP May 2009 Revision 0
C-99 Capsule T Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/27/2009 09:37 AM Page I Coefficients of Curve I A =50. B =50. C= 107.93 TO = 106.47 D = 0.OOE+0O Equation is A + B * [Tanh((T-Toy(C+DT))]
Temperature at 50% Shear= 106.5 Plant: Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: T reco Fluence: nIcmA2 125 100 (I 75 S
U, 50 0~
25 0o-
-300.0 0.0 100.0 200.0 300.0 Temperature in Deg F Charpy V-Notch Data Tlmperattie Input Percent Shear Computed Percent Shear Differential 00 13. 00 12. 21 .79
- 75. 00 38. 00 35. 82 2. 18 125. 00 54. 00 58. 50 -4,50 150. 00 73. 00 69. 14 3. 86 210.00 90. 00 87. 20 2. 80 250. 00 98. 00 93. 46 4. 54 300. 00 100. 00 97. 30 2. 70 350. 00 100. 00 98. 91 I. 09 425. 00 100, 00 99. 73 ,27 WCAP-17036-NP May 2009 Revision 0
C-100 Capsule T Weld Heat 61782 Page. 2 Plant: Ginna Material: SAW -lHeat:
61782 Orientation: NA Capsule: T reco Fluence: n/cm^2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 425. 00 100.00 99. 73 .27
- 70. 00 35. 00 33. 72 1.28 150. 00 65. 00 69. 14 -4. 14 210.00 80. 00 87. 20 -7. 20 210. 00 90. 00 87 20 2. 80 300. 00 100.00 97. 30 2. 70 350.00 100.00 98. 91 1.09 350.00 100. 00 98. 91 1. 09 425. 00 100. 00 99. 73 .27 Correlation Coefficent .994 WCAP-17036-NP May 2009 Revision 0
C-101 Capsule S Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/2712009 09:40 AM Page I Coefficients of Curve I A = 50. B = 50. C = 83.42 TO = 154.13 D = 0.OOE+0O Equation is A + B * [Tanh((T-Toy(C+DT))]
Temperature. at 50% Shear= 154.2 Plant: Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: S Fluence: rtcmA2 125 100 (U 75 U) 50 25 0 -.- -.- 1-
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential
.00 5. 00 2. 42 2. 58 50.00 15.00 7.61 7. 39 100.00 30. 00 21.45 8. 55 125.00 25. 00 33. 22 -8. 22 150.00 50. 00 47.53 2. 47 175.00 45,00 62. 26 -137.26 200.00 90.00 75. 02 14. 98 250.00 95.00 90. 88 4. 12 300.00 S00. 00 97.06 2. 94 WCAP-17036-NP May 2009 Revision 0
C-102 Capsule S Weld Heat 61782 Page 2 Plant: Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: S -Yluence: n/cm^2 Charpy VI-Notch Data Temperature Input Percent Shkar Computed Percent Stear Differential 350. 00 t00.00 99.10 .90 400. 00 100. 00 99.73
- 27 450. 00 too. 00 99. 92 .08 Correlation Coefficient =.977 May 2009 WCAP- 17036-NP WCAP-17036-NP May 2009 Revision 0
C-103 Capsule N Weld Heat 61782 CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03127P/009 09:43 AM Page I Coefficients of Curve I A = 50. B = 50. C = 61.4 TO = 171.48 D = 0.00E+00 Equation is A + B *[Tanh((T-ToY(C+DT))j Temperature at 50% Shear= 171.5 Plant: Ginna Material: SAW Heat: 61782 Orientation: NA Capsule: N Fluence: n/cmA2 125 100 (I 75 50 25 0 - i + - - i -
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temprapfeno ntput Percent Shear Computed Pereet Shear Differential
.00 5. 00 .37 4. 63 350. 00 40. 00 33. 19 6. 81 200.00 50. 00 71. 69 -21. 69 210.00 80. 00 77. 81 2. 19 220.00 90.00 82. 93 7. 07 230.00 95.00 87. 06 7.94 240.00 95.00 90. 31 4. 69 260. 00 98. 00 94,70 3. 30 280.00 98. 00 97. 17 .83 WCAP-17036-NP May 2009 Revision 0
C-104 Capsule N Weld Heat 61782 Page 2 Plant: Ginna Material: SAW Heat: 61782 Orientation: NA Capsule.: N Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Skiar Computed Percent Shear Differential 350.00 100.00 99. 70 30 375. 00 100. 00 99. 87 .13 400. 00 100. 00 99. 94 06 Correlation Ccefficient = .968 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
C-105 Unirradiated Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03127/2009 09:21 AM Page 1 Coefficients of Curve I A = 46.1 B = 43.9 C = 102.49 TO = -753 D = 0.OOE+0O Equation is A + B * [Tanh((T-Toy(C+DT))]
Upper Shelf Energy=90.0(Fixed) Lower Shelf Energy=2.2(Fixed)
Temp@30 ft-lbs=-64.7 Deg F Temp@50 ft-lbs=- 16.1 Deg F Plant GINNA Material: SAW Heat: 125P666 Orientation: NA Capsule: UNIRR Fluence: n/eni2 300 250 200 0
150 z
100 0 50 0 0 0
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temlperature Input CVN Computed CVN Differential
-90. 00 14. 50 21.56 - 7. 06
-90. 00 42. 00 21. 56 20. 44
-90,00 I1. 50 21.56 - 10.06
-65.00 26. 50 29. 90 -3. 40
- 65. 00 16. 50 29. 90 -13. 40
-65. 00 20. 00 29. 90 -9. 90
-40. 00 40. 00 39. 85 .15
-40.00 58. 00 39. 85 18. 15
-40.00 51. 50 39. 85 11. 65 WCAP-17036-NP May 2009 Revision 0
C-106 Unirradiated Heat Affected Zone Page 2 Plant: GhNNA Material: SAW Heat: 125P666 Orientation: NA Capsule: UNIRR Fluence: nrcm^2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential
- 10. 00 90. 00 60. 65 29. 35 10.00 36. 50 60. 65 24. 15 I0. 00 51. 50 60. 65 -9. 15
- 60. 00 56. 00 76.03 20. 03
- 60. 00 53. 00 76. 03 - 23. 03
- 60. 00 101. 50 76.03 25. 47 110.00 94. 50 84. 15 10. 35 110. 00 98. 00 84. 15 13.85 110. 00 77. 50 84.15 - 6. 65 Correlation Coefficient = .826 WCAP-17036-NP May 2009 Revision 0
C-107 Capsule V Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02111/2009 12:40 PM Page I Coefficients of Curve I A= 68.6 B= 66.4 C= 171.32 TO= 79.76 D= O.OOE+00 Equation is A + B * [Tanh((T-ToY(C+-DT))]
Upper Shelf Energy= 135.0 Lower Shelf Energy=2.2(Fixed)
Temp@30 ft-lbs=-34.0 Deg F Temp@50ftI-lbs=30.5 DegF Plant: Ginna Material SAW Heat: 1251P666 Orientation: NA Capsule: V Fluence: rtcm^2 300 250
" 200 0
150 z
100 0
50 0
0 0
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Tornpemrtum. Input CVN Computed CVN Diffrrential
-50. 00 10. 50 26. 13 -1 5. 63
- 15. 00 33. 00 35. 21 -2. 21
- 10. 00 50. 50 42. 96 7. 54
- 10. 00 61.00 42. 96 18. 04
- 40. 00 57. 50 53. 46 4. 04
- 75. 00 36. 00 66. 76 - 30. 76
- 75. 00 86. 30 66. 76 19. 54 125. 00 76. 50 85. 74 -9.24 210. 00 1 20. 00 111. 18 8. 82 WCAP-17036-NP May 2009 Revision 0
C-108 Capsule V Heat Affected Zone Pap 2 Plant Ginna Material: SAW Heat 125P666 Orientation: NA Capsule: V Fluenoe: a/cmrn2 Charpy V-Notch Data Tcmperatu[e Input CVN Computed CN Differential 500. 00 132. 00 134. 03 - 2. 03 Correlation Coefficient =. 915 WCAP-17036-NP May 2009 Revision 0
C-109 Capsule R Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02/11/2009 12:45 PM Page I Coefficients of Curve I A=42.5 B=40.3C=20.12 TO=.29 D=O0.00E+00 Equation is A + B * [Tanlh((T-Toy(C+DT))]
Upper Shelf Energy=8Z 8(Fixed) Lower Shelf Energ-y2.2(Fixed)
Tlmp@30 ft-lbs--6.1 Deg F Temp@5O ft-bs=4.1 Deg F Plant: Ginna Material: SAW Heat: 125P666 Orientation: NA Capsule: R Fluence: n/cnrP2 300 200 IT tlS L. 150
,2 0
100 0
10 so 4 - 4 - 4- - - - - - - 4 -
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Cha-py V-Notch Data Tern-ermtume Input CVN Computed CVN Diffe.rcmiz
-50. 00 6.00 2. 74 3. 26
.00 44. 00 41.91 2. 09
- 25. 00 55. 50 76. 43 -20. 93
- 40. 00 134.00 81. 27 52.73
- 77. 00 84. 50 82. 76 1.74 110. 00 39. 00 82. 80 -43. 80 150. 00 81. 50 82. 80 - 1. 30 199.00 55. 50 82. 80 -27. 30 250. 00 78. 00 82. 80 -4. 80 WCAP-17036-NP May 2009 Revision 0
C-110 Capsule R Heat Affected Zone Page 2 Plant: Ginna Material: SAW Heat: 125P666 Orientation: NA Capsule: R Fluence: nkem^2 Charpy V-Notch Data Tempenmturr Input CVN Computed CVN Differential 300. 00 65. 00 82. 80 -17. 80 Correlation Coefficient =.666 WCAP-17036-NP May 2009 Revision 0
C-111 Capsule T Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0211/2009 12:51 PM Page 1 Coefficients of Curve 1 A=59.95 B=57.75C.=94.46 T0= 30.53 D= 000E+00 Equation is A + B * [Tanh((T-ToY(C+DT))]
Upper Shelf Energy= 117.7 (Fixed) Lower Shelf Energy=2.2(Fixed)
Temp@30 ft-lbs=-23.7 DeI F Temp@50ft-lbs=14.1 DegF Plant: Ginna Material SAW Heat: 125P666 Orientation: NA Capsule: T Fluence: nknvr2 300 250 200 0
F I1U 0
0 z 0 1000 00 50 0
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temrnpertum. Input CV N Computed CVN Differential
-1oo 00 4. 00 9. 05 -5. 05
-60. 00 13. 50 17. 01 -3.51
-50. 00 66. 00 19.96 46. 04
.00 24. 50 41. 91 -17.41
- 50. 00 33. 50 71. 69 -38. 19
- 75. 00 116. 50 85. 29 31. 21 150. 00 128. 00 109, 17 18. 83 250. 00 139. 00 116. 60 22. 40 350. 00 86. 00 117. 57 -31, 57 Ca*ri aon Ccefficeint =.830 WCAP-17036-NP May 2009 Revision 0
C-112 Capsule S Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02'16/2009 07:53 AM Page I Coefficients of Curve I A = 52.85 B = 50.65 C = 133.03 T0 = 38.86 i) = O.OOE+00 Equation is A + B * [Tanh((T-ToY(C+DT))]
Upper Shelf Energy= 103.5(Fixed) Lower Shelf Energy=2.2 (Fixed)
Temp@30 ft-lbs=-25.8 DEq F Ternp@50 ft-lbs=31.4 Deg F Plant: Ginna Material: SAW Heat: 125P666 Orientation: NA Capsule: S Fluence: ,1?cm^2 300 250 d 200 0
LL 150 0
w z
> 100 o
50 0
0 00 0
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Tem ,rnetuur. Input CVN Computed CVN Differential
-50. 00 6. 00 23. 29 -17.29
-25. 00 7. 00 30. 25 23. 25
- 25. 00 37. 00 30. 25 6.75
.00 25. 00 38. 46 -13.46
- 25. 00 12. 00 47. 59 -35. 59
- 25. 00 102. 00 47. 59 54. 41 50.00 56. 00 57. 0O -1. 08
- 50. 00 105. 00 57. 08 47. 92 100. 00 68. 00 74. 62 -6.62 WCAP-17036-NP May 2009 Revision 0
C-113 Capsule S Heat Affected Zone Page 2 Plant: Ginna Material: SAW Heat: 125P666 Orientation: NA Capsule: S Fluence: nIcnm^2 Charpy V-Notch Data Ternpewrntie Input CVN Computed CVN Differential 150. 00 43. 00 87. 46 -44. 46 200. 00 70. 00 95. 25 - 25. 25 225. 00 137.00 97.68 39. 32 Correlation Coefficient =.636 WCAP-17036-NP May 2009 Revision 0
C-114 Capsule N Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 0-V0612009 09:28 AM Page I Coefficients of Curve I A = 45.22 B = 43.03 C = 32. '0 54.78 D = 0.00E+00 Equation is A + B * [Tanh((T-ToY(C+DT))]
Upper Shelf Energy=88.3(Fixed) Lower Shelf EnergD--2.2(Fixed)
Temp@30 ft-lb:s--43.0 Deg F Temp@50 ft-lbs=5 8.4 Deg F Plant: Ginna Material: SAW Heat: 125P666 Orientation: NA Capsule: N Fluence: r'cnV'2 300 250 200 0
50
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Trmpmatunn. Input CVN Computed CVN Differential
.00 8. 00 4. 92 3. 08
- 35. 00 24. 00 21.57 2.43
- 40. 00 34. 00 26. 66 7. 34
- 50. 00 15.00 38. 85 - 23. 85
- 55. 00 39. 00 45. 52 -7.52
- 60. 00 80. 00 52. 18 27. 82
- 80. 00 66. 00 73.51 -7. 51 130. 00 87. 00 87. 48 - . 48 350. 00 1 24. 00 88. 25 35. 75 WCAP-17036-NP May 2009 Revision 0
C-115 Capsule N Heat Affected Zone PaW 2 Plant: Ginna Material: SAW Heat: 125P666 Orientation: NA Capsule: N Fluence: nlcmaA2 Charpy V-Notch Data Termpetur Input CVN Computed C*YN Diffrntial 360. 00 67.00 88. 25 -21. 25 375. 00 90. 00 88. 25 1.75 390. 00 72.00 88. 25 -16. 25 Conhlation Coefficient =.860 May 2009 WCAP- 17036-NP WCAP- May 2009 Revision 0
C-116 Unirradiated Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/27P2009 09:23 AM Page I Coefficients of Curve I A = 38.5 B = 37.5 C = 105.67 To = -21.83 1) = O.OOE+00 Equation is A + B
- iTanh((T-ToY(C+DlT))]
Upper Shelf L.E.=76.0(Fixed) Lower Shelf L.E.= 1.0(Fixed)
Terp.@L.E. 35 mils=-31.7 Deg F Plant GINNA Material: SAW Heat: 125P666 Orientation: NA Capsule: UNIRR Fluence: nfcm^2 200 150 C
a100 50 50 0 4-
-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Tem1pemre Input LE Computed LE. Diffeiential
-90. 00 10. 00 17. 19 .7. 19
-90. 00 34. 00 17. 19 16. 81
-90. 00 12. 00 17. 19 -5.19
-65. 00 24. 00 23. 98 - 02
- 65. 00 14. 00 23. 98 -9.98
- 65. 00 2 1. 00 23, 98 - 2. 98
-40.00 33. 00 32, 12 .88
- 40. 00 43. 00 32. 12 10. 88
-40. 00 33. 00 32. 12 .88 WCAP-17036-NP May 2009 Revision 0
C-117 Unirradiated Heat Affected Zone Page 2 Plant: GINNA Material: SAW Heat: 125P666 Orientation: NA Capsule: JNIRR Fluence: nrcm^2 Charpy V-Notch Data Temperature Input L . Computed LF. Differential
- 10. 00 62. 00 49. 47 12.53 10.00 33. 00 49. 47 - 16. 47
- 10. 00 52. 00 49. 47 2. 53
- 60. 00 5 1. 00 62. 86 - 11. 86
- 60. 00 46. 00 62. 86 16.86
- 60. 00 78. 00 62. 86 15, 14 110. 00 80. 00 70. 29 9. 71 110. 00 78. 00 70. 29 7.71 110. 00 70. 00 70. 29 -. 29 Correlation Coefficient = .895 WCAP-1 7036-NP May 2009 Revision 0
C-118 Capsule V Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02 113/2009 t2:41 PM Page I Coefficients ofCurve I A = 45.79 B = 44.79 C =225.29 T0 = 51.04- = 0.00E+00 Equation is A + B
- ITanh((T-To)(C+DT))]
Upper Shelf L.E.=90.6 Lower Shelf L.E.=1.O(Fixed)
Tenip.@L.E. 35 mi1---4.3 Deg F Plant: Ginna Material: SAW Heat 125P666 Orientation: NA Capsule: V Fluence: n1cum^2 200 150 E
C 100 50 0 '
-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Coni*uted LE Difkemntial
-50. 00 9. 00 26. 95 -17. 95
-15.00 52. 00 33. 02 is. 98 10.00 35. 00 37. 72 -2. 72
- 10. 00 53. 00 37. 72 1 5. 28
- 40. 00 46. 00 43. 59 2.41
- 75. 00 27. 00 50. 53 - 23, 53
- 75. 00 63. 00 50. 53 12. 47 125. 00 40. 00 59. 98 -19. 98 210. 00 92. 00 73. 01 1i . 99 WCAP-17036-NP May 2009 Revision 0
C-119 Capsule V Heat Affected Zone Page 2 Plant: Ginna Material: SAW Heat: 125P666 Orientation: NA Capsule: V Fluence: ncnimA2 Charpy V-Notch Data Tempemture. Input L.E. Computed LE DiffeIrerfinj 500. 00 85. 00 88. 94 3 . 94 Corlation Coefficient = .760 WCAP-17036-NP May 2009 Revision 0
C-120 Capsule R Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02f 1112009 12:46 PM Pape I Coefficients ofCurvee I A = 34.1 B = 33. C = 23.99 TO = 3.62 D = 0.00E+00 Equation is A + B * [Tanb((T-To)/(C+DT))]
Upper Shelf L.E.=67.2 (Fixed) Lower Shelf LE.= 1.0(Fixed)
Teimp. @LE. 35 mils=4.3 Deg F Plant: Ginna Material SAW Heat 125P666 Orientation: NA Capsule: R Fluence: n/crn2 200 1S0 E
C 2.100 5l 0 0 0 50 Y0 Od0 n1
-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Ternpemratuit Input L.E. Computed LE Differential
-50.00 7. 00 1. 75 5. 25
.00 31. 00 29. 15 1. 85
- 25. 00 45. 00 57.67 -1 2. 67
- 40. 00 88. 00 64. 16 23. 84
- 77. 00 71.00 67.05 3. 95 110. 00 35. 00 67. 19 -32. 19 150. 00 59. 00 67. 20 -8. 20 199. 00 69. 00 67. 20 1. 80 250. 00 72. 00 67. 20 4. 80 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
C-121 Capsule R Heat Affected Zone Page 2 Plant: Ginna Material: SAW Heat: 125P666 Oiientation: NA Capsule: R Fluence: nictr^2 Charpy V-Notch Data Termpemtuie. Input L.E. Computed LE. Differntial
'400. 00 48. 00 67. 20 - 19. 20 Cormlaftion Coefficient = .777 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
C-122 Capsule 1T Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02111/2009 12:52 PM Page 1 Coefficients ofCurve I A = 31.2 B = 30.2 C = 121.03 TO = 2.82 I = 0.001+00 Equation is A + B * [Tanh((T-To)/(C+DT))]
Upper Shelf L.E.=61.4(Fixed) Lower Shelf L.E.= I.0(Fixed)
Temp. OLE. 35 mils=18.2 Deg F Plant: Ginna Material: SAW Heat: 125P666 Orientation: NA Capsule: T Fluence: nlnrrP2 200 150 E
a 100 so 0
In 0
00
-3 00.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperatur. Input LE. Computed LE Diffemrnial
-100. 00 4. 70 10.34 - 5. 64
-60. 00 6. 30 16.80 -10.50
-50. 00 41.70 18.80 22. 90 00 28. 00 30. 50 - 2. 50
- 50. 00 27. 60 42. 41 -14. 81
- 75. 00 53. 90 47. 34 6. 56 150. 00 62. 20 56. 52 5. 68 250. 00 77. 60 60. 40 17.20 350. 00 44. 50 61. 21 -16. 71 Circlation Coefficient =. 823 WCAP- 17036-NP May 2009 Revision 0
C-123 Capsule S Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02116(2009 07:54 AM Page I Coefficients of Curve I A=32.75 B=31.75C=61.39 T0 = 13.12 D=0.OOE+00 Equation is A + B * [Tanh((T-To)/(C÷-DT))]
Upper Shelf L.E.=64.5(Fixed) Lower Shelf LE= I.0(Fixed)
Temp.@LE. 35 mils=17.5 Deg F Plant: Ginna Materiat SAW Heat: 125P666 Orientation: NA Capsule: S Fluence: n/cmA2 200 150 ~1 I E
C
_ on
.210 5l 0 0
0 '6 50 0
/0 0 0
0 ni.
-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data T¢mperatum. Input L.E. Computed LE Diftimntial
-50. 00 6. 00 8. 20 - 2. 20
-25. 00 12.00 15. 23 -3. 23
- 25. 00 22. 00 15. 23 6. 77
.00 22. 00 26. 07 -4. 07
- 25. 00 14.00 38. 82 -24. 82
- 25. 00 61.00 38. 82 22. 18
- 50. 00 36. 00 49. 82 -13. 82
- 50. 00 73. 00 49. 82 23. 18 100. 00 59. 00 60. 96 - 1. 96 WCAP-17036-NP May 2009 Revision 0
C-124 Capsule S Heat Affected Zone Page 2 Plant: Ginna Material: SAW Heat: 125P666 Orientation: NA Caipulle: S Fluence: n/ccm^2 Charpy V-Notch Data Temperature Input L.E. Computed LE Differential 150. 00 35. 00 63. 77 - 28. 77 200. 00 47. 00 64. 36 -17. 36 225. 00 82. 00 64. 44 17. 56 Correlation Ccefficient = .733 WCAP-1 7036-NP May 2009 Revision 0
C-125 Capsule N Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03V06/2009 09:29 AM Page 1 Coefficients of Curve I A=30. B =29. C=34.18 TO=50-52 D=0.OOE+00 Equation is A + B
- ITanh((T-To)y(C+DT))]
Upper Shelf L.E.=59.0(Fixed) Lower Shelf L.E= 1.0(Fixed)
Tbmp. @LE.. 35 mils=56.5 Deg F Plant: Ginna Material: SAW Heat: 125P666 Orientation: NA Capsule: N Fluence: n/ciuA2 200 ISO 0
50 o In 00 0
-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Tcrnp'irturr. Input L.E. Computed LE Diffejmntial
.00 8. 00 .3. 87 4. 1
- 35. 00 19.00 17. 67 1. 33
- 40. 00 25. 00 21.34 3. 66 50.00 14.00 29. 56 -15. 56 55.00 ,3. 00 33. 78 -. 78
- 60. 00 51.00 37. 84 13. 16
- 80. 00 48. 00 50. 23 -2. 23 130. 00 60. 00 58. 45 1. 55 350. 00 64. 00 59. 00 5. 00 WCAP-17036-NP May 2009 Revision 0
C-126 Capsule N Heat Affected Zone Page 2 Plant: Ginna Material: SAW Heat: 125P666 Orientation: NA Capsule: N Floence: nicnm^2 Charpy V-Notch Data Tempcrmture Input L.E. Computed LF. Differential 360. 00 50. 00 59. 00 -9. 00 375. 00 52. 00 59. 00 -7.00 390. 00 70. 00 59. 00 11.00 Cormlation Co.fficien =. 920 WCAP- 17036-NP May 2009 Revision 0
C-127 Unirradiated Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/27P-009 09:23 AM Page I Coefficients of Curve I A = 50. B = 50. C = 111.53 TO = -27.79 D = 0.00E+00 Equation is A + B * [Tanh((r-Toy(C+DT))]
Temperature at 50% Shear= -27.7 Plant GINNA Material: SAW Heat 125P666 Orientation: NA Capsule: UNIRR Fluence: nlcm^2 125 100 75
- a. 50 25 0 " '-- '- - - - . F-i - -
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Stear computed Percent Shear Differemnial
-90.00 20. 00 24. 68 -4. 68
-90. 00 35. 00 24. 68 10. 32
-90. 00 25. 00 24. 68 .32
-65.00 40. 00 33. 91 6. 09
-65. 00 35. 00 33.91 1.09
- 65. 00 35. 00 33. 91 1. 09
-40.00 45. 00 44. 55 45
-40. 00 45. 00 44. 55 45
- 40.00 35. 00 44. 55 - . 55 WCAP-17036-NP May 2009 Revision 0
C-128 .. 4° Unirradiated Heat Affected Zone Page. 2 Plant: GINNA Material: SAW Heat: 125P666 Orientation: NA Capsule: UNIRR Fluence: n/cm^2 Charpy V-Notch Data Temperature Input PeRcent Slhar Computed Percent Stear Differential 10.00 70, 00 66. 32 3. 68 10.00 50. 00 66. 32 -16. 32 10.00 70. 00 66. 32 3. 68
- 60. 00 75. 00 82. 84 -7. 84
- 60. 00 70. 00 82. 84 -12.84
- 60. 00 100. 00 82. 84 17. 16 110. 00 300. 00 92. 21 7. 79 110.00 100. 00 92.21 7, 79 Ito. 00 tOO. 00 92. 21 7.79 Correlation Coefficient =.952 WCAP-17036-NP May 2009 Revision 0
C-129 Capsule R Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02111/2009 12:47 PM Page. I Coefficients of Curve I A=50. B=50. C=98.74 TO=29.86 D=0.OOE+00 Equation is A + B * [Tanb((T-To)/(C+DT))]
Temperature at 50% Shear= 29.9 Plant: Cinna Material: SAW Heat 125P666 Orientation: NA Capsule: R Fluence: n/cm,2 125 100 u)
IL a.
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Tempemrturi Input Pcwrnt Shear Computed Percent Sheiar Differential
-50. 00 5. 00 16. 55 -11.55
.00 25. 00 35. 32 -10. 32 25, 00 40. 00 47. 54 -7.54
- 40. 00 95. 00 55, 12 39. 88
- 77. 00 75. 00 72. 21 2. 79 110. 00 45. 00 83. 52 - 38. 52 150. 00 100. 00 91. 93 8. 07 199. 00 100. 00 96. 85 3. 1 5 250. 00 100. 00 98. 86 1.14 WCAP-17036-NP May 2009 Revision 0
C-130 Capsule R Heat Affected Zone Page 2 Plant: Ginna Material: SAW Heat: 125P666 Orientation: NA Capsule: R Fluent: nfcm"2 Charpy V-Notch Data Tencpecrtum. Input Percent Shear Computed Percent Shear Di4ferential 300. 00 100. 00 99. 58 . 42 Conrlation Coefficient = .845 WCAP-17036-NP May 2009 Revision 0
C-131 Capsule T Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02f1112009 12:53 PM Page i Coefficients ofCurve I A=50. B=50.C=94.I9 ro=35.2 D=0.00E+00 Equation is A + B * [Tanu((T-ToY(C+-DT))]
Temperature at 50% Shear = 35.3 Plant: Ginna Material: SAW Heat 125P666 Orientation: NA Capsule: T Fluence: n/cnrn2 125 100 0) 75
~0 0 C)
I:!
C) 0.
50 - ~
0
--/-- -- -- 4 25 0
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Cha-py V-Notch Data Termperatute Input Pe*ernt Shear Computed Percent Shear Diff&rntia1
- 1oo. 00 2. 00 5. 36 -3.36
- 60. 00 10.00 11. 70 - 1.70
- 50. 00 31. 00 14. 07 16. 93
.00 27. 00 32. 14 -5. 14 50, 00 46. 00 57. 79 11. 79
- 75. 00 78. 00 69. 95 8. 05 150. 00 100. 00 91. 97 8. 03 250. 00 100. 00 98. 97 1. 03 350. 00 100. 00 99. 88 .1 12 Corilati on Coefficient = .977 May 2009 WCAP- 7036-NP WCAP-117036-NP May 2009 Revision 0
C-132 Capsule S Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 02116/2009 07:55 AM Page I Coefficients of Curve I A=50. B=50. C=66.92 TO=21.71 1)=O.OOE+00 Equation is A + B * !Tanh((T-To)/(C+DT))]
Temperature at 50% Shear= 2 1.8 Plant: Ginna Material: SAW Heat: 125P666 Orientation: NA Capsule: S Fluence: n/cm^2 125 100 75 C)
IL 0~ 50 25
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperntum. Input P*,r*,nt Shear Computed Pircent Shear Differetmial
-50. 00 5. 00 10. 50 - 5. 50
- 25. 00 10, 00 19. 85 -9.85
- 25. 00 30. 00 19. 85 10. 15
.00 30. 00 34. 33 -4.33
- 25. 00 20. 00 52. 46 - 32. 46
- 25. 00 90. 00 52. 46 37. 54
- 50. 00 55. 00 69. 96 - 14. 96
- 50. 00 90. 00 69. 96 20. 04 100. 00 85. 00 91. 21 -6. 21 WCAP- 17036-NP May 2009 Revision 0
C-133 Capsule S Heat Affected Zone Pap 2 Plant: Ginna Material: SAW Heat: 125P666 Orientation: NA Capsule: S Fluence: n/cm^2 Charpy V-Notch Data Terrperatua. Input Poe.nt Shear Computed Percent Shear Differential 150. 00 so. 00 97. 88 -17. 88 200. 00 95. 00 99. 52 -4.52 225. 00 100. 00 99. 77 . 21 Corrlation Coefficient =.867 May 2009 WCAP-l 7036-NP WCAP-17036-NP May 2009 Revision 0
C-134 Capsule N Heat Affected Zone CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 03/06/2009 09:30 AM Paw I Coefficients ofCurve I A=50. B =50. C=90.97 TO=85.94 D=0.OEtE+00 Equation is A + B * [Tanh((T-Toy(C+-DT))]
Temperature at 50% Shear = 86.0 Plant: Ginna Material: SAW Heat: 125P666 Orientation: NA Capsule: N Fluence: n~cmA2 CI 0 -- '-
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temiperture Input Pkernt Sherr Computed Per*e.nt Shear Differential
.00 20. 00 13. 13 6. 87
- 35. 00 20. 00 24. 60 -4. 60
- 40. 00 20. 00 26. 70 -6. 70
- 50. 00 25. 00 31. 21 -6. 21
- 55. 00 30. 00 33. 62 -3.62
- 60. 00 50. 00 36. 12 13. 88
- 80. 00 50. 00 46. 74 3. 26 130. 00 70. 00 72. 48 - 2. 48 350. 00 100. 00 99. 70 .30 WCAP-17036-NP May 2009 Revision 0
C-135 Capsule N Heat Affected Zone Pag 2 Plant: Ginna Material: SAW Heat: 125P666 Orientation: NA Capsule: N Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 360. 00 100. 00 99.76 .24 375. 00 100. 00 99.83 .17 390. 00 100. 00 99.88 .12 Conrlation Coefficient = .986 WCAP-1 7036-NP May 2009 Revision 0
C-136 Unirradiated Correlation Monitor Material CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 04/15/2009 10:46 AM Page I Coefficients of Curve I A = 34.85 B = 32.65 C = 67.92 TO = 40.28 D = 0.OOE+00 Equation is A + B * [Tanh((T-ToY(C+DT))]
Upper Shelf Energy,=67.5(Fixed) Lower Shelf Energy=2.2(Fixed)
Temp@30 ft-lbs=30.2 Deg F Temp@50 ft-lbs=74.5 Deg F Plant: Ginna Material: SA302B Heal: A0421 Orientation: LT Capsule: UNIRR Fluence: n/crnA2 300 250 4 200 0
U.
o ISO
'U 100 0
50 0
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN CornpuW CVN Differential
- 80. 00 4. 00 4. 04 - 04
-80, 00 4. 00 4.04 -. 04
- 60. 00 8. 00 5. 44 2. 56
-60. 00 6.00 5.44 ,56
- 40 00 12.00 7. 81 4. 19
-40. 00 10.00 '7.81 2. 19
-40. 00 6. 00 '7. 81 1.81
- 20. 00 14.00 It. 66 2. 34
-20. 00 13.00 It. 66 1. 34 WCAP- 17036-NP May 2009 Revision 0
C-137 Unirradiated Correlation Monitor Material Page 2 Plant: Ginna Material: SA3O2B Heat: A0421 Orientation: LT Capsule: UNIRR Fluence: n/cm^2 Charpy V-Notch Data Tempemture Input CVN Computed CVN Differential
- 00 22. 00 17.48 4. 52
- 00 18. 00 17. 48 .52
- 20. 00 29. 00 25. 38 3. 62
- 20. 00 23. 00 25. 38 -2.38
- 40. 00 36. 00 34. 72 i. 28
- 40. 00 26. 00 34. 72 -8. 72
- 60. 00 36. 00 44. 07 -8. 07
- 60. 00 33. 00 44. 07 -11.07
- 80. 00 67. 00 52. 03 14, 97 80.00 50. 00 52. 03 - 2. 03 100. 00 68. 00 57. 90 10. 10 100. 00 62. 00 57. 90 4. 10 Correlation Coefficient = .960 WCAP-17036-NP May 2009 Revision 0
C-138 Capsule V Correlation Monitor Material CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 04115/2009 10:52 AM Page I Coefficients of Curve I A = 35.4 B = 33.2 C = 87.23 TO = 141.45 D = 0.OOE+00 Equation is A + B * [Tanh((l-Toy(C+DT))]
Upper Shelf Energy=68.6 Lower Shelf Energy=2.2(Fixed)
Temp@30 ft-lbs=1 77.2 Deg F Temp@50 ft-lbs= 182.7 Deg F Plant: Ginna Material: SA302B Heat: A0421 Orientation: LT Capsule: V Fluence: n/ernA2 300 250 200 0
150 w
z 100 50
- - - -- 1 - - - -
0
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperatre Input CVN Computed CVN Differential
- 50. 00 10. 30 9. 46 184
- 75. 00 It. 00 14.08 -3. 08 125.00 34. 00 29.21 4. 79 150.00 38. 00 38. 64 -,64 175. 00 45. 00 47. 57 -2.57 175.00 44. 50 47. 57 -3. 07 210.00 61. 50 57. 18 4. 32 300. 00 66. 0 66. 89 -. 89 Correlaion Coefftient =.9m WCAP-17036-NP May 2009 Revision 0
C-139 Capsule R Correlation Monitor Material CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 04/15/2009 10:44 AM Page I Coefficients of Curve I A = 30.85 B = 28.65 C = 84.99 TO = 135.85 D = 0.OOE+00 Equation is A + B * [Tanh((T-Toy(C+DT))]
Upper Shelf Energy=59.5(Fixed) Lower Shelf Energy=2.2(Fixed)
Temp@30 ft-lbs=1 33.4 Deg F Temp@50 ft-lbs=204.6 Deg F Plant: Ginna Material: SA3021B Heat: A0421 Orientation: LT Capsule: R Fluence: nIcrnA2 300 250
- 200
- 150 ISO z
100 50 <
0
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Tempenilure Input CVN Cnmptlzed CVN Differential 77, 00 18.00 13. 67 4. 33 110. 00 20. 00 22.40 -2.40 150. 00 38. 50 35. 58 2. 92 150. 00 30, 00 35. 58 -5. 58 199.00 55. 50 48.93 6. 57 200. 00 45. 50 49. 13 - 3. 63 300. 00 59. 00 58. 32 .68 300. 00 60. 00 58. 32 !. 68 Cmrelalion Coeffrcieft= .969 WCAP-17036-NP May 2009 Revision 0
C-140 Capsule T Correlation Monitor Material CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 04/15/2009 10:51 AM Page 1 Coefficients or Cutrve 1 A = 31.7 B = 295 C = 186.75 TO = 138.74 D = O.OOE+00 Equation is A + B * [Tanh((T-Toy(C+DT))]
Upper Shelf EnerVy=61.2(Fixed) Lower Shelf Energry2.2(Fixed)
Ternp@30 ft-lbs=128.0 Deg F Temp@50 ft-lbs=274.3 Deg F Plant: Ginna Material: SA302B Heal: A0421 Orientation: LT Capsule: T Fluence: n/IcmA2 300 250 200 LL S150 z
? 100 0 0 50 000_.. <
0 0
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperat'e Input CVN Computd CVN Differential
- 75. 00 40ý 00 22.00 18.00 100.00 19. 00 25. 67 -6. 67 150.00 26. 00 33. 48 -7.48 175, 00 30. 00 37, 36 -7,36 210.00 33. 50 42. 44 - 8. 94 250. 00 61. 50 47. 45 14. 05 350. 00 63ý 00 55. 64 7. 36 425. 00 59, 00 58. 57 .43 Comelauion Coefficient := .789 WCAP-17036-NP May 2009 Revision 0
C-141 Unirradiated Correlation Monitor Material CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 04/15/2009 01:59 PM Page I Coefficients of Curve I A =30.5 B=29.5C=71.82 TO= 29.87 D=0.OOE+00 Equation is A + B * [Tanh((T-ToY(C+DT))I Upper Shelf L.E.--60.0(Fixed) Lower Shelf L.E.=l.0(Fixed)
Temp.@LE. 35 mits41.0 Deg F Plant: Ginna Material: SA302B Heat: A0421 Orientation: LT Capsule: UNIRR Fluence: n/cnA2 200 150 2a 100 5o
.J00 0
-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperabtre Input LE Computed LEý Diffential
- s0. O0 6. 00 2. 36
- 80. 00 3. 64
-60. 00 6.00 3. 64 2. 36
-60. 00 6. 00 5.46 54
- 6. 00 5.46 54
-640.00
-40. 00 14.00 8.38 5. 62
-40.00 10. 00 8. 38 1. 62
- 7. 00 8. 38 -1.38
-20.00 14.00 12. '78 1. 22
- 20.00 14.00 12.78 1. 22 WCAP-17036-NP May 2009 Revision 0
C-142 Unirradiated Correlation Monitor Material Page 2 Plant Ginna Material: SA302B Heat: A0421 Orientation: LT Capsule: UNIRR Fluence: n/cm"2 Charpy V-Notch Data Temperature Input LE. Computed LE. Differential
.00 22. 00 Is. 89 3. 11
.00 18. 00 18.89 -,89 20, 00 28. 00 26, 47 1.53 20.00 23. 00 26. 47 -3. 47
- 40. 00 33. 00 34. 63 - . 63
- 40. 00 26. 00 34. 63 -8. 63
- 60. 00 40. 00 42. 20 -2. 20
- 60. 00 35. 00 42. 20 -7. 20
- 80. 00 60. 00 48. 29 1I . 71 Ho. 00 48. 00 48. 29 -. 29 100. 00 60. 00 52. 67 7. 33 100. O0 58. 00 52. 67 5. 33 Correlation Coefficient = .970 WCAP-17036-NP May 2009 Revision 0
C-143 Capsule V Correlation Monitor Material CVGRAPPH 5.3 Hyperbolic Tangent Curve Printed on 04/15/2009 02:01 PM Page 1 Coefficients of Curve I A = 27.02 B = 26.02 C = 79.33 TO = 122.99 D = 0.OOE+00 Equation is A + B * [Tanh((T-ToY(C+DT))]
Upper Shelf LE.=53.0 Lower Shelf L.E= I.0(Fixed)
Temp.@LE. 35 mits= 148.2 Deg F Plant: Ginna Material: SA302B Heat: A0421 Orientation: LT Capsule: V Fluhnce: nkmA2 200 150 0
i,-
8.Co 50 0 -
-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Thmerature Input LE Computed LE, Differntial 50.00 10. 00 8. 13 1. 87
- 75. 00 I 1. 00 12.95 -1.95 125.00 30. 00 27. 67 2, 33 150.00 33. 00 35.54 2. 54 175. 00' 42. 00 41.98 -. 0?
175. 00 41. 00 41.98 98 210. 00 51. 00 471 81 3. 19 300. 00 51.00 52. 44 1. 44 CeffelaIionCoefficitc=t .991 WCAP-1 7036-NP May 2009 Revision 0
C-144 Capsule R Correlation Monitor Material CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 04/15/2009 02.100 PM Page I Coefficients of Curve I A = 30.25 B = 29.25 C = 100.63 TO = 140.66 D = 0.OOE+00 Equation is A + B * [Tanh((T-Toy(C+DT))]
Upper Shelf L.E.--59.5(Fixed) Lower Shelf L.E.=].0(Fixed)
Te:mp.@L: 35 mils=IS7,2 Deg F Plant: Ginna. Material: SA302B Heat: A0421 Orientation: LT Capsule: R Fluence: n/rac^2 200 150 S
100 so 50 0
0
-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature Input LF. Computed LB. Differential
- 77. 00 17,00 13.87 3. 13 110.00 121. 00 21. 60 -, 60 150. 00 36. 00 32. 96 3, 04 150. 00 27. 00 32.96 5. 96 199.00 50. 00 43. 53 4. 47 200. 00 42. 00 45. 74 3. 74 300. 00 61.00 57. 13 3. 87 300. 00 58. 00 57. 13 ,87 Corielation Coefficient = .974 May 2009 WCAP-I 7036-NP WCAP-17036-NP May 2009 Revision 0
C-145 Capsule T Correlation Monitor Material CVGRAPI- 5.3 Hyperbolic Tangent Curve Printed on 04/15/2009 02-01 PM Page I Coefficients of Curve I A=23.8 B =22.8C=161.67 TO= 127.94 DI=O.OOE+00 Equation is A + B * [Tanh((T-Toy(C+DT))]
Upper Shelf L.E.=46.6(Fixed) Lower Shelf LE.=].0(Fixed)
Temp.@LE. 35 mils=214.9 Deg F Plant: Ginna Material: SA302B Heat: A0421 Orientation: LT Capsule: T Fluenme Win/eaA2 200 150 0
1 loo 50 0 0 0
0
-300.0 0.0 300.0 600.0 Temperature in Deg F Charpy V-Notch Data Tremaperure Input LP. Computd LE Difereential 75.00 24. 80 16. 59 8. 21 100.00 13. 40 19.90 -6. 50 150.00 28.70 26. 89 I1.81 175.00 28. 00 30. 25 -2. 25 210.00 25. 20 34. 47 -9. 27 250.00 47. 60 38. 35 9. 25 350.00 49. 20 43. 85 5. 35 425.00 43.00 45.47 -2. 47 Correlztion Coerfiewimt = .846 May 2009 WCAP- 7036-NP WCAP-l17036-NP May 2009 Revision 0
C-146 Unirradiated Correlation Monitor Material CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 04/15/2009 03:09 PM Page 1 Coefficients of Curve I A = 50. B = 50. C = 65.95 TO = 43.1 D = 0.OOE+00 Equation is A + B * [Tanh((T-Toy(C+DT))I Temperaure at 50% Shear = 43.2 Plant: Ginna Material: SA302-B Heat: A042 I Orientation: LT Capsule: UJNIRR Fluence: n/rnA2 125 100 I
U, 75 50 a-25 0 1---i - --- *-
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature tipul Percent Sbear Cnonred Percern Strar Differential
-80.00 2.00 2. 34 -. 34
- 80.00 2. 00 2. 34 -. 34
-60. 00 3.00 4. 20 I. 20
- 60. 00 3. 00 4. 20 -1.20
-40.00 I0. 00 7.45 2. 55
-40. 00 5. 00 7. 45 -2. 45
-40, 00 5. 00 7.45 -2. 45
-20. 00 15. 00 12. 86 2, 14
-20. 00 15.00 12.86 2. 14 May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
C-147 Unirradiated Correlation Monitor Material Pa.ge 2 Plant: Ginna Material: SA3O2B Heat: A0421 Orientation: LT Capsule: UNIRR Fluence: n/cm^2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential
. 00 30. 00 21. 30 8. 70
.00 25. 00 21. 30 3. 70
- 20. 00 35. 00 33. 17 1, 83
- 20. 00 35. 00 33. 17 1.83 40, 00 45. 00 47. 65 - 2. 65
- 40. 00 45. 00 47, 65 -2. 65
- 60. 00 50. 00 62. 54 -12. 54
- 60. 00 45. 00 62. 54 -17. 54
- 80. 00 100. o0 75. 38 24. 62
- 80. 00 70. 00 75. 38 -5. 38 100. 00 98. 00 84. 88 13. 12 100. O0 85. 00 84. 88 .12 Correlation Coefficient = .965 WCAP-17036-NP May 2009 Revision 0
C-148 Capsule R Correlation Monitor Material CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 04/15/2009 10:40 AM Page I Coefficients of Curve i A = 50. B = 50. C = 77.59 TO = 163.09 D = 0.OOE+00 Equation is A + B * [Tanh((F-Toy(C+DT))]
Temperature at 50% Shear= 163.1 Plant: Ginna Material: SA302B Heat: A0421 Orientation: LT Capsule: R Fluence: ndcmA2 125 100 (0 75 50 25 0 -. - - -
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temapnature Input Percent Shear Computed Percent Shear Differential
- 77. 00 15. 00 9. 81 5. 19 110,00 20. 00 20. 29 29 150.00 40. 00 41. 65 - I. 65 150.00 40. 00 41.,65 65 199.00 75. 00 71. 62 3. 38 200. 00 70. 00 72, 14 2. 14 300. 00 99. 00 97. 15 1. 85 300. 00 100. 00 97. 15 2. 85 Correlation Coefiwient = .997 WCAP-17036-NP May 2009 Revision 0
C-149 Capsule T Correlation Monitor Material CVGRAPH 5.3 Hyperbolic Tangent Curve Printed on 04/15/2009 10:51 AM Page I Coefficients of Curve I A = 50. B = 50. C = 145.59 TO = 164.7 D = O.OOE+00 Equation is A + B * [Tanh((r-Toy(C+DT))]
Temperature at 50% Shear= 164.7 Plant: Ginna Material: SA302B Heat: A0421 Orientation: LT Capsule: T Fluence: n/cmA2 125 100 75 0 .. .. _ _
U. 0 50 0 0
25 n
-300.0 -200.0 -100.0 0.0 100.0 200.0 300.0 400.0 500.0 600.0 Temperature in Deg F Charpy V-Notch Data Temperature InpdlPertent Slbea Cmputed Percent Shear Differential 75.00 53. 00 22. 58 30. 42 100.00 15. 00 29, 14 -14. 14 150.00 41. 00 44. 97 -3. 97 175.00 44. 00 53. 53 -9. 53 210.00 48. 00 65. 07 -17. 07 250.00 too. 00 76. 35 23. 65 350.00 100. 00 92. 73 7. 27 425.00 too. 00 97.28 2.72 Curreltion Coeffr*=en.=1 I WCAP-17036-NP May 2009 Revision 0
D-1 APPENDIX D SURVEILLANCE PROGRAM CREDIBILITY EVALUATION D.1 INTRODUCTION Regulatory Guide 1.99, Revision 2 [D-l] describes general procedures acceptable to the NRC staff for calculating the effects of neutron radiation embrittlement of the low-alloy steels currently used for light-water-cooled reactor vessels. Regulatory Positions 2.1 and 2.2 of Regulatory Guide 1.99, Revision 2, describe the methods for calculating the adjusted reference temperature (ART) and Charpy upper shelf energy (USE) of reactor vessel beltline materials using surveillance capsule data.
To date there have been five surveillance capsules removed from the R. E. Ginna reactor vessel. To use these surveillance data sets to reduce the margin term (cYA)that is used to calculate ART according to Position 2.1, or to obtain the projected decrease in USE per Position 2.2, the data must be shown to be credible. However, even if the data is not shown to be credible, the projected decrease in USE per Position 2.2 may still be obtained if the upper shelf can be clearly determined, following the definition given in ASTM E185-82 [D-2]. In accordance with Regulatory Guide 1.99, Revision 2, the credibility of the surveillance data will be judged based on five criteria.
The purpose of this evaluation is to apply the credibility requirements of Regulatory Guide 1.99, Revision 2, to the R. E. Ginna reactor vessel surveillance data and determine if that surveillance data is credible.
D.2 EVALUATION Criterion 1: Materials in the capsules should be those judged most likely to be controlling with regard to radiation embrittlement.
The beltline region of the reactor vessel is defined in Appendix G to 10 CFR Part 50, "Fracture Toughness Requirements" [D-3], as follows:
"the reactor vessel (shell material including welds, heat affected zones, and plates or forgings) that directly surrounds the effective height of the active core and adjacent regions of the reactor vessel that are predictedto experience sufficient neutron radiationdamage to be consideredin the selection of the most limiting materialwith regardto radiationdamage. "
The R. E. Ginna reactor vessel consists of the following beltline region materials:
" Nozzle shell forging 123P118
" Intermediate shell forging 125S255
" Lower shell forging 125P666
" Nozzle to Intermediate shell girth weld seam (heat # 71249)
" Intermediate to lower shell girth weld seam (heat # 61782)
WCAP-17036-NP May 2009 Revision 0
D-2 Per WCAP-7254, the R. E. Ginna surveillance program was based on ASTM E185-66 [D-4],
"Recommended Practice for Surveillance Tests on Structural Materials in Nuclear Reactors". Per Section 3.1 of ASTM E185-66, "Samples shall represent one heat of the base metal and one butt weld if a weld occurs in the irradiated region." R. E. Ginna included the intermediate and lower shell forging materials as well as the intermediate to lower shell girth weld metal in the surveillance program. At the time the surveillance program was developed, the nozzle area (weld and forging) was thought to be outside the beltline region; thus, it was left out of the surveillance program. All beltline region materials were included. Hence, Criterion 1 is met for the R. E. Ginna reactor vessel.
Criterion 2: Scatter in the plots of Charpy energy versus temperature for the irradiated and unirradiated conditions should be small enough to permit the determination of the 30 ft-lb temperature and USE unambiguously.
Based on engineering judgment, the scatter in the data presented in these plots is small enough to permit the determination of the 30 ft-lb temperature and the USE of the R. E. Ginna surveillance materials unambiguously. Hence, the R. E. Ginna surveillance program meets this criterion.
Criterion 3: When there are two or more sets of surveillance data from one reactor, the scatter of ARTNDT values about a best-fit line drawn as described in Regulatory Position 2.1 normally should be less than 28'F for welds and 170 F for base metal. Even if the fluence range is large (two or more orders of magnitude), the scatter should not exceed twice those values. Even if the data fail this criterion for use in shift calculations, they may be credible for determining decrease in USE if the upper shelf can be clearly determined, following the definition given in ASTM E185-82 [D-2].
The functional form of the least squares method as described in Regulator ' Position 2.1 will be utilized to determine a best-fit line for this data and to determine if the scatter of these ARTNDT values about this line is less than 28°F for surveillance welds and less than 17'F for surveillance forgings.
Following is the calculation of the best fit line as described in Regulatory Position 2.1 of Regulatory Guide 1.99, Revision 2. There are three cases to be evaluated for this criterion, and they are:
Charpy specimens of weld heat #61782 are contained in the R. E. Ginna surveillance capsule program and will be evaluated for the R. E. Ginna reactor vessel.
This weld is not included in the R. E. Ginna surveillance program but surveillance data are available from Turkey Point Units 3 and 4 and Davis-Besse.
- Case C: Surveillance forging data from the Intermediate and Lower Shell forgings. Data for these forgings are contained only in the R. E. Ginna surveillance program.
WCAP-17036-NP May 2009 Revision 0
D-3 The recommended NRC methods for determining credibility will be followed. The NRC methods were presented to industry at a meeting held by the NRC on February 12 and 13, 1998 [D-5]. At this meeting the NRC presented five cases. Of the five cases, NRC Case I most closely represents R. E. Ginna Cases A and C. NRC Case 1 is "Surveillance Data Available From Plant But No Other Source". This is identical to the credibility calculation of Regulatory Guide 1.99, Revision 2. R. E. Ginna Case B corresponds to NRC Case 5, "Surveillance Data from Other Plants Only".
Credibility Assessment (Cases A and C):
The chemistry factors for the R. E. Ginna surveillance forging and weld material contained in the surveillance program were calculated in accordance with Regulatory Guide 1.99, Revision 2, Position 2.1 and are presented in Table D-1. The scatter of ARTNDT values about the functional form of a best-fit line drawn as described in Regulatory Position 2.1 is presented in Table D-2.
Table D-1 Calculation of Chemistry Factors using R. E. Ginna Surveillance Capsule Data Material Capsule Capsule f (a) FF(b) ARTNnT(c) FF*ARTNDT FF2 V 0.587 0.851 0 (od) 0 0.724 Intermediate R 1.02 1.006 20.1 20.2 1.011 Shell Forging T 1.69 1.144 0 (d) 0 1.310 125S255 S 3.64 1.335 76.8 102.6 1.783 (L-C) N 5.8 1.430 76.4 109.3 2.046 SUM: 232.1 6.875 CF1 25s 2 55 =ý (FF
- ARTNDT) + Y(FF 2 ) =(232.1)+ (6.875)= 33.8'F V 0.587 0.851 34.7 29.5 0.724 Lower Shell R 1.02 1.006 57.5 57.8 1.011 Forging T 1.69 1.144 33.6 38.5 1.310 125P666 S 3.64 58 1.335 45.8 61.2 1.783 N
N- _ 5.8_- 1.430 91.1 130.3 2.046 (L-C) SUM: 317.3 6.875 CF1 25 p666 = Y(FF
- ARTNDT) + E(FF2 ) = (317.3) + (6.875) = 46.20 F V 0.587 0.851 146.7 124.8 0.724 R 1.02 1.006 156.2 157.1 1.011 Surveillance T 1.69 1.144 149.7 171.3 1.310 Weld Material S 3.64 1.335 212.2 283.4 1.783 Heat # 61782 N 5.8 1.430 216.9 310.3 2.046 SUM: 1046.9 6.875 2 0 CF I1t.#61782 = Y(FF
- ARTNoT) + X(FF ) = (1046.9)+ (6.875)= 152.3 F Notes:
(a) f= fluence (x 101 9 n/cm 2, E > 1.0 MeV). See Section 6.
(b) FF = fluence factor = fO.28 - o.1I-og (f)).
(c) ARTNDT ('F) values are the measured 30 ft-lb shift values taken from Section 5.
(d) Measured ARTNDT value was determined to be negative, but physically a reduction should not occur. Therefore, a conservative value of zero is used.
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D-4 Table D-2 R. E. Ginna Surveillance Capsule Data Scatter about the Best-Fit Line CF Measured Predicted Scatter <17 0 F (Slopebest fit) Capsule f ARTNDT ARTNDT ARTNDT (Base Metal) 19 2 Material Capsule (OF) (x10 n/cm ) FF (OF) (OF) (OF) <28 0 F (Weld)
Intermediate V 33.8 0.587 0.851 0 28.7 28.7 No Shell Forging R 33.8 1.02 1.006 20.1 33.9 13.8 Yes 125S255 T 33.8 1.69 1.144 0 38.6 38.6 No (Longitudinal) 33.8 3.64 1.335 76.8 45.1 -31.7 No N 33.8 5.8 1.430 76.4 48.3 -28.1 No Lower Shell V 46.2 0.587 0.851 34.7 39.3 4.6 Yes Forging R 46.2 1.02 1.006 57.5 46.4 -11.1 Yes 125P666 T 46.2 1.69 1.144 33.6 52.8 19.2 No (Longitudinal) S 46.2 3.64 1.335 45.8 61.6 15.8 Yes N 46.2 5.8 1.430 91.1 66.0 -25.1 No V 152.3 0.587 0.851 146.7 129.57 -17.1 Yes Surveillance R 152.3 1.02 1.006 156.2 153.12 -3.1 Yes Weld Material T 152.3 1.69 1.144 149.7 174.28 24.6 Yes Heat # 61782 S 152.3 3.64 1.335 212.2' 203.36 -8.8 Yes N 152.3 5.8 1.430 216.9 217.83 0.9 Yes Conclusions (Cases A and C)
" R. E. Ginna Intermediate Shell Forging 125S255 has 4 of 5 data points outside the 17'F scatter band and is therefore deemed NOT CREDIBLE;
" R. E. Ginna Lower Shell Forging 125P666 has 2 of 5 data points outside the 17'F scatter band and is therefore deemed NOT CREDIBLE;
- R. E. Ginna Surveillance Weld Heat # 61782 has 5 of 5 data points within the 28°F scatter band and is credible if the other Criteria are satisfied.
It should be noted that the CF calculated for Heat #61782 in Table D-1 is applicable only to the surveillance weld; to apply the R. E. Ginna surveillance data for weld heat #61782 to the R. E. Ginna vessel heat #61782 (e.g., to calculate a regulatory Position 2.1 CF for vessel heat #61782), the shift data must be adjusted for chemical composition differences between the surveillance weld and the vessel weld of that same heat. This evaluation is not contained in this Appendix.
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D-5 Credibility Assessment (Case B)
Surveillance weld Heat #71249 is contained in the Turkey Point Units 3 and 4 (TP3, TP4) surveillance programs. It was also contained in a supplemental surveillance capsule irradiated in the Davis Besse reactor vessel.
In order to adapt sister plant surveillance data to a particular plant, the data must be adjusted for (1) differences in irradiation temperature and (2) differences between the surveillance material chemistry and the target plant vessel material chemistry. The adjustment is described later in this Appendix.
Like R. E. Ginna, Turkey Point is a Westinghouse plant (NSSS vendor). Davis Besse is a B&W plant.
The irradiation environment of Turkey Point Unit 3 is judged closer to R. E. Ginna than that of Davis Besse, so Turkey Point Unit 3 will be evaluated first.
Three capsules containing weld heat #71249 have been tested at Turkey Point Unit 3. A fitted chemistry factor considering only the Turkey Point Unit 3 data is calculated in the table below. For this case, no adjustment of ARTNDT is required.
Table D-3 Calculation of Chemistry Factor using Turkey Point Unit 3 Surveillance Data for Weld Heat #71249 Material Capsule Capsule f a) FF(b) ARTNDT~c) FF*ARTNDT FF 2 T (TP3) 0.599 0.856 163.87 140.4 0.734 Surveillance V (TP3) 1.223 1.056 180.77 190.9 1.115 Weld Heat X (TP3) 2.897 1.282 191.06 245.0 1.644
- 71249 SUM: 576.3 3.493 CF__It. # 71249 = Y(FF
- ARTNDT) + Y(FF 2) = (576.3) + (3.493) = 165.00F Notes:
(a) f= fluence (x 101 9 n/cm 2, E > 1.0 MeV).
(b) FF = fluence factor = f0.25-o.Iiog f)
(c) ARTNDT (0 F) values are the measured 30 ft-lb shift values taken from [D-6].
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D-6 The fitted CF calculated in Table D-3 is used to calculate a predicted shift, which is then compared to the measured shift. If the scatter is less than 28°F (the scatter criteria for welds), then the data are considered to be credible.
Table D-4 Predicted Versus Best-Estimate ARTNDT Values using Turkey Point Unit 3 Surveillance Data for Weld Heat #71249 Best Estimate Measured Scatter in ARTNDT ARTNDT (°F) ARTNDT (°F) (B. E. - Measured)
T (TP3) 0.856 141.3 163.87 -22.58 Surveillance Weld V (TP3) 165.0°F 1.056 174.2 180.77 -6.55 Heat # 71249 X (TP3) 1.282 211.5 191.06 20.48 The scatter for all capsules is less than 28°F. Therefore, the surveillance data for weld heat #71249 from Turkey Point Unit 3 are credible.
When the Turkey Point Unit 3 data are considered with the Turkey Point Unit 4 data and the Davis Besse data, the scatter exceeds 28°F for two of the data points; therefore that data is not credible. Only the Turkey Point Unit 3 data should be used for R. E. Ginna.
The next step is to apply the credible Turkey Point Unit 3 data to the R. E. Ginna vessel weld Heat
- 71249 in order to calculate a Position 2.1 CF for the R. E. Ginna vessel weld. For this calculation, the surveillance data must be adjusted for the irradiation temperature and vessel weld chemistry. These adjustments are shown below:
Adjusted ARTNDT = ((Measured Shift * [CFvw / CFsw]) + [Tcapsule - Tplant])
where, CFvw / CFsw is the ratio of the Regulatory Guide 1.99, Revision 2 Table chemistry factors (vessel weld CF to surveillance weld CF)
Tcapsule - TPlant is the adjustment for irradiation temperature.
For the application of the Turkey Point Unit 3 data to the R. E. Ginna vessel weld Heat # 71249:
CFvw = 167.6°F CFsw = 194.1 OF CFvw / CFsw = 167.6°F / 194. 10F 0.863 0
Tcapsulc - Tplant = 6 F May 2009 WCAP-1 7036-NP WCAP-17036-NP May 2009 Revision 0
D-7 Table D-5 Calculated Regulatory Position 2.1 Chemistry Factor for the R. E. Ginna Vessel Heat
- 71249 Using Credible Surveillance Data from Turkey Point Unit 3 Material Capsule Capsule f (a) FF(b)A RTNDT (C) ARTNDT(d)
Adjusted FF RTD FF*ARTNDT FF FF T (TP3) 0.599 0.856 163.87 147.5 126.3 0.734 Surveillance V (TP3) 1.223 1.056 180.77 162.09 171.2 1.115 WeldHeat X (TP3) 2.897 1.282 191.06 170.98 219.2 1.644
- 71249 SUM: 516.8 3.493 C1711,.# 71249 Y(FF
- ARTNDT) + X(FF 2) = (516.8) + (3.493) 147.9'F Notes:
(a) f= fluence (x 101 9 n/cm 2, E > 1.0 MeV).
(b) FF = fluence factor = *O.2 8 -0.1og(f).
(c) ARTNDT (TF) values are the measured 30 ft-lb shift values taken from [D-6].
(d) Adjusted for irradiation temperature and chemical composition differences.
Conclusion (Case B)
Per Table D-5, the Regulatory Position 2.1 Chemistry Factor for R. E. Ginna vessel weld Heat #71249 is 147.9°F, based on credible Turkey Point Unit 3 surveillance data.
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D-8 Criterion 4: The irradiation temperature of the Charpy specimens in the capsule should match the vessel wall temperature at the cladding/base metal interface within +/- 25°F.
The capsule specimens are located in the reactor between the neutron pad and the vessel wall and are positioned opposite the center of the core. The test capsules are in baskets attached to the neutron pad.
The location of the specimens with respect to the reactor vessel beltline provides assurance that the reactor vessel wall and the specimens experience equivalent operating conditions such that the temperatures will not differ by more than 25°F. Hence, this criterion is met.
Criterion 5: The surveillance data for the correlation monitor material in the capsule should fall within the scatter band of the database for that material.
The R. E. Ginna surveillance program does have Correlation Monitor Material. NUREG/CR-6413, ORNL/TM-13133 [D-7] contains a plot of residual vs. Fast Fluence for the SRM (Figure 10 in the NUREG report) and shows a 2(y uncertainty of 50'F. The data used for the plot is contained in Table 15 (in the NUREG Report). However, the data in the NUREG Report has not been considered for the recalculated fluences as documented herein. Thus, Table D-6 contains an updated calculation of Residual vs. Fast fluence.
Table D-6 Calculation of Residual vs. Fast Fluence Fluence Fluence Measured RG 1.99 Rev. 2 Residual Capsule (x 1019 n/cm 2) Factor (FF) ARTNDT(a) Shift (CF*FF)(b) (Measured -RG Shift)
V 0.587 0.851 97.0 85.1 11.9 R 1.02 1.006 103.2 100.6 2.6 T 1.69 1.144 97.8 114.4 -16.6 Notes:
(a) ARTNDT ('F) values are the measured 30 ft-lb shift values obtained from Section 5.
(b) Per NUREG/CR-6413, ORNL/TM-13133, the Cu and Ni values for the Correlation Monitor Material are 0.20 Cu and 0.18 Ni. This equates to a Chemistry Factor of I 00°F from Reg. Guide 1.99 Rev. 2.
Table D-6 shows a 2a uncertainty of less than 50*F, which is the allowable scatter in NUREG/CR-6413, ORNL/TM- 13133 [D-7]. Hence, this criterion is met.
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D-9 D.3 CONCLUSION Based on the preceding responses to all five criteria of Regulatory Guide 1.99, Revision 2, Section B and 10 CFR 50.61 [D-8], the R. E. Ginna surveillance weld (heat # 61782) data meet the credibility criteria of Regulatory Guide 1.99, Revision 2 and are deemed CREDIBLE. The surveillance forging data for the lower shell and intermediate shell forgings do not meet Criterion #3 and are deemed NOT CREDIBLE for use in the shift calculations of Regulatory Position 2.1; however, the upper shelf energy levels of the forgings can be clearly determined, and thus the data are credible for use in determining decrease in USE per Regulatory Position 2.2.
The weld data of heat # 71249 from Turkey Point Unit 3 is credible and results in an adjusted Regulatory Position 2.1 Chemistry Factor for R. E. Ginna beltline weld heat # 71249 of 147.9°F.
D.4 REFERENCES D-1 Regulatory Guide 1.99, Revision 2, Radiation Embrittlement of Reactor Vessel Materials, U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, May 1998.
D-2 ASTM E185-82, Standard Practicefor Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, American Society for Testing and Materials.
D-3 10 CFR 50, Appendix G, Fracture Toughness Requirements, Federal Register, Volume 60, No. 243, December 19, 1995.
D-4 ASTM E 185-66, Recommended Practicefor Surveillance Tests on Structural Materialin Nuclear Reactors, American Society for Testing and Materials, 1966 D-5 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.
D-6 WCAP- 15916, Revision 0, Analysis of Capsule Xfrom FloridaPower and Light Company Turkey Point Unit 3 Reactor Vessel Radiation Surveillance Program, J. H.. Ledger et. al., September 2002.
D-7 ORNL/TM-13133; NUREG/CR-6413, Analysis of the IrradiationData for A302B and A533B Correlation Monitor Materials, J. A. Wang, Oak Ridge National Laboratory, Oak Ridge, TN, April 1996.
D-8 10 CFR Part 50.61, Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events, Federal Register, Volume 60, No. 143, dated December 19, 1995, as amended at 61 FR 39300, July 29, 1996; 72 FR 49500, Aug. 28, 2007; 73 FR 5722, Jan. 31, 2008.
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E-1 APPENDIX E UPPER SHELF ENERGY EVALUATION Per Regulatory Guide 1.99, Revision 2 [E-l], the Charpy upper shelf energy (USE) is assumed to decrease as a function of fluence and copper content as indicated in Figure 2 of the Guide (Figure E- 1 of this appendix) when surveillance data is not used. Linear interpolation is permitted. In addition, if surveillance data is to be used, the decrease in upper shelf energy may be obtained by plotting the reduced plant surveillance data on Figure 2 of the Guide (Figure E-1 of this appendix) and fitting the data with a line drawn parallel to the existing lines as the upper bound of all the data. This line should be used in preference to the existing graph. Even if the surveillance data are not credible for use in the shift calculations per Regulatory Position 2.1, they may be credible for determining decrease in USE per Regulatory Position 2.2 if the upper shelf can be clearly determined, following the definition given in ASTM E185-82 [E-2].
The 53 EFPY (end-of-license renewal) upper shelf energy of the vessel materials can be predicted using the corresponding 1/4T fluence projection, the copper content of the beltline materials and/or the results of the capsules tested to date using Figure 2 in Regulatory Guide 1.99, Revision 2. The maximum vessel clad/base metal interface fluence value was used to determine the corresponding 1/4T fluence value at 53 EFPY.
The R. E. Ginna reactor vessel beltline region minimum thickness is 6.50 inches. Calculation of the 1/4T vessel fluence values at 53 EFPY for the intermediate shell and lower shell forgings and the intermediate shell to lower shell girth weld is shown as follows:
Maximum Vessel Fluence @ 53 EFPY = 5.56 x 1019 n/cm 2 (E > 1.0 MeV) 1/4T Fluence @ 53 EFPY = (5.56 x 1019 n/cm 2 )
- e(-°24. (6.50/4))
- 3.76 x 1019 n/cm 2 (E > 1.0 MeV)
Calculation of the 1/4T vessel fluence values at 53 EFPY for the nozzle shell forging and the nozzle to intermediate shell girth weld:
Maximum Vessel Fluence @ 53 EFPY = 2.37 x 1018 n/cm 2 (E > 1.0 MeV) 1/4T Fluence @ 53 EFPY = (2.37 x 1018 n/cm 2)
- e(-0.24 * (6.50/4))
- 1.60 x l01l n/cm 2 (E > 1.0 MeV)
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E-2 However, based on the conservative approach that the NRC requested R. E. Ginna to take in DA-ME-2003-024 [E-3], the fluence for the Nozzle Shell Area materials will be doubled:
Max. Vessel Fluence @ 53 EFPY
- 2 - 4.74 x 1018 n/cm 2 (E > 1.0 MeV) 2 24 (4.74 x 1018 n/cm )
- e(-0. (6.50/4))
1/4T Fluence @ 53 EFPY -
= 3.2 x 10s n/cm 2 (E > 1.0 MeV)
The following pages present the R. E. Ginna upper shelf energy evaluation. Figure E-I, as indicated above, as well as Figure E-2, are used in making predictions in accordance with Regulatory Guide 1.99, Revision 2. Note that in Figure E-2, only two red data points are displayed, pertaining to Capsules V and N. Capsules R, T, and S have measured USE decreases of less than one percent. Therefore, the data points pertaining to these capsules do not appear on Figure E-2. Table E-1 provides the predicted upper shelf energy values for 53 EFPY (end-of-license renewal).
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E-3
- Surveillance Material: Lower Shell Forging 125P666
- Surveillance Material: Intermediate Shell to Lower Shell Girth Weld 61782 100.0 uJ or) 0.
I..
o 10.0 Q
tU L-0 53 EFPY 1/4T fluence 3.76 x 1019 n/cm2 1.0 1.OOE+17 1.00E+18 1.OOE+19 1.OOE+20 Neutron Fluence, n/cm2 (E > 1 MeV)
Figure E-1 Regulatory Guide 1.99, Revision 2 Predicted Decrease in Upper Shelf Energy as a Function of Copper and Fluence for Lower Shell Forging 125P666 and Weld Heat # 61782 May 2009 WCAP- 17036-NP WCAP-17036-NP May 2009 Revision 0
E-4 E Surveillance Material: Intermediate Shell Forging 125S255 100.0
.u 0
L.
3 10.0 0.
53 EFPY 1/4T fluence 3.76 x 10' n/cm2 1.0 1 1.00E+17 1.OOE+18 1.OOE+19 1.OOE+20 2
Neutron Fluence, n/cm (E > I MeV)
Figure E-2 Regulatory Guide 1.99, Revision 2 Predicted Decrease in Upper Shelf Energy as a Function of Copper and Fluence for Intermediate Shell Forging 125S255 WCAP-17036-NP May 2009 Revision 0
E-5 Table E-1 Predicted Positions 1.2 and 2.2 Upper Shelf Energy Values at 53 EFPY 1/4T EOLE Projected Fluence Unirradiated Projected EOLE Weight (x 10' 9 n/cm 2, USE USE Decrease USE Material % of Cu E > 1.0 MeV) (ft-lb) (%) (ft-lb)
Position 1.2 Nozzle Shell Forging 123P1 18 0.17 0 .32('b) 117 21 92 Intermediate Shell Forging 125S255 0.07 3.76 91 23 70 Lower Shell Forging 125P666 0.05 3.76 114 21 90 Nozzle to Intermediate Shell Girth 0.23 0 3. 2(b) 65 29 46 Weld (Heat # 71249) 1 1 1 1 Intermediate Shell to Lower Shell 0.25 3.76 80 52 38 Girth Weld (Heat # 61782)
Position 2.2(a)
Intermediate Shell Forging 125S255 0.07 3.76 91 6 85.5 Lower Shell Forging 125P666 0.05 3.76 114 23 88 Intermediate Shell to Lower Shell 0 3 Girth Weld (Heat # 61782) 0 3 Notes:
(a) Calculated using surveillance capsule measured percent decrease in USE from Table 5-10 and Regulatory Guide 1.99, Revision 2, Position 2.2; see Figures E-I and E-2.
(b) Based on the conservative approach that the NRC requested R. E. Ginna to take in DA-ME-2003-024 [E-3], the fluence values for the Nozzle Shell Area materials have been doubled.
The projected EOLE USE value for the Intermediate Shell to Lower Shell Girth Weld (Heat #61782) is 39 ft-lbs. This is below the acceptable level of 50 ft-lbs. The projected EOLE USE value for the Nozzle to Intermediate Shell Girth Weld (Heat #71249) is 46 ft-lbs. This too is below the acceptable level of 50 ft-lbs.
An equivalent margin analysis was performed in BAW-2425, Revision 1 [E-4] which showed weld heat.
- 61782 is acceptable even with a USE value below 50 ft-lbs. However, this analysis was performed for an EOLE (53 EFPY) inside surface fluence of 5.01 x 1019 n/cm 2 . Thus, the calculation was checked for a revised EOLE (53 EFPY) fluence of 5.56 x l019 n/cm 2.
In BAW-2425, Revision 1, the applied J-integral was compared to the J-integral resistance to determine the acceptable margin for USE. The applied J-integral, which is not a function of fluence, must be lower than the J-integral resistance, which is a function of fluence. Thus, J-integral resistance was calculated and confirmed to be greater than the applied J-integral for an EOLE inside surface fluence of 5.56 x 10'9 n/cm 2.* For Service Levels A, B, C and D, the Intermediate to Lower Shell Girth Weld and the Nozzle to Intermediate Shell Girth Weld show more than sufficient margin for USE.
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E-6 E.1 REFERENCES E-l U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Regulatory Guide 1.99, Revision 2, RadiationEmbrittlement ofReactor Vessel Materials,May 1988.
E-2 ASTM E185-82, Standard Practicefor Conducting Surveillance Tests for Light-Water Cooled Nuclear PowerReactor Vessels, American Society for Testing and Materials.
E-3 Safety Evaluation by the Office of Nuclear Reactor Regulation Related to Amendment No. 97 to Renewed Facility Operating License No. DPR- 18 R. E. Ginna Nuclear Power Plant, Docket No.
50-244.
E-4 Framatome ANP Report BAW-2425, Rev. 1, Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessel of R. E. Ginna for Extended Life through 54 Effective Full Power Years, H. P. Gunawardane, June 2002.
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ATTACHMENT 2 List of Regulatory Commitments
ATTACHMENT 2 List of Regulatory Commitments The following table identifies those actions committed to by Ginna LLC in this document. Any other statements made in this licensing submittal are provided for informational purposes only and are not to be considered regulatory commitments. Please direct any questions you have in this matter to Mr. Thomas Harding at (585)771-5219.
COMMITMENT COMPLETION DATE An updated Pressure Temperature Limits Report February 19, 2010 (PTLR) incorporating the Capsule "N" test results will be submitted.