ML25091A297
| ML25091A297 | |
| Person / Time | |
|---|---|
| Site: | Robinson |
| Issue date: | 04/01/2025 |
| From: | Duke Energy Progress |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML25091A290 | List: |
| References | |
| RA-25-0067 WCAP-18909-NP, Rev 2 | |
| Download: ML25091A297 (1) | |
Text
ENCLOSURE 4 H.B. ROBINSON STEAM ELECTRIC PLANT, UNIT NUMBER 2 NON-PROPRIETARY REFERENCE DOCUMENTS AND A REDACTED VERSION OF A PROPRIETARY REFERENCE DOCUMENT (PUBLIC VERSION)
ENCLOSURE 4 ATTACHMENT 1 H.B. ROBINSON STEAM ELECTRIC PLANT, UNIT NUMBER 2 Westinghouse WCAP-18909-NP, Revision 2 Determination of T0 for H.B. Robinson Unit 2 Heat Number W5214, Linde 1092 Weld Metal Based on Unirradiated Data, March 2025
- This record was final approved on 03/06/2025 08:39:24. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 WCAP-18909-NP March 2025 Revision 2 Determination of T0 for H.B. Robinson Unit 2 Heat # W5214, Linde 1092 Weld Metal Based on Unirradiated Data
- This record was final approved on 03/06/2025 08:39:24. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 ii
- Electronically approved records are authenticated in the electronic document management system.
Westinghouse Electric Company LLC 1000 Westinghouse Dr.
Cranberry Township, PA 16066
© 2025 Westinghouse Electric Company LLC All Rights Reserved WCAP-18909-NP Revision 2 Determination of T0 for H.B. Robinson Unit 2 Heat # W5214, Linde 1092 Weld Metal Based on Unirradiated Data D. Brett Lynch*
Advanced Analysis and Methods March 2025 Verifier:
J. Brian Hall*
Materials Innovation Approved: John L. Lyons*
Manager, Materials Innovation
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Westinghouse Non-Proprietary Class 3 iii WCAP-18909-NP March 2025 Revision 2 RECORD OF REVISION Revision 0:
Original Issue (February 2024)
Revision 1:
Corrected the labeling of the Yield and Tensile Strength in Appendix A and updated reference 22. (March 2024)
Revision 2:
Updated the methodology in Section 5. (March 2025)
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Westinghouse Non-Proprietary Class 3 iv WCAP-18909-NP March 2025 Revision 2 TABLE OF CONTENTS LIST OF TABLES........................................................................................................................................ v LIST OF FIGURES..................................................................................................................................... vi 1
INTRODUCTION............................................................................................................................... 1-1 2
FRACTURE TOUGHNESS TESTING AND RESULTS................................................................... 2-1 2.1 SOURCE AND VALIDATION OF SPECIMEN MATERIAL................................................. 2-3 2.2 SPECIMEN GEOMETRY......................................................................................................... 2-9 2.3 TEST PROCEDURE............................................................................................................... 2-11 2.3.1 PRE-CRACKING....................................................................................................... 2-11 2.3.2 ASTM E1921 TESTING............................................................................................ 2-11 3
T0 CALCULATION METHODOLOGY............................................................................................ 3-1 3.1 CALCULATION OF T0............................................................................................................. 3-1 3.2 MEASUREMENT MARGIN ADJUSTMENT......................................................................... 3-3 4
COMPARISON WITH MRP-127....................................................................................................... 4-1 5
IRRADIATION INDUCED SHIFT IN FRACTURE TOUGHNESS AND APPLICABLE MARGINS
............................................................................................................................................. 5-1 5.1 INITIAL REFERENCE TEMPERATURE............................................................................... 5-2 5.2 IRRADIATION INDUCED SHIFT IN FRACTURE TOUGHNESS (RTNDT)....................... 5-2 5.2.1 REGULATORY GUIDE 1.99, REVISION 2, ETC METHODOLOGY..................... 5-2 5.2.2 ETC USE WITH MASTER CURVE DATA................................................................ 5-2 5.2.3 USE OF SURVEILLANCE DATA.............................................................................. 5-3 5.3 APPLICABLE MARGINS........................................................................................................ 5-5 5.3.1 UNCERTAINTY OF INITIAL REFERENCE TEMPERATURE (I)......................... 5-5 5.3.2 UNCERTAINTY OF IRRADIATION-INDUCED SHIFT ()................................... 5-5 6
REFERENCES.................................................................................................................................... 6-1
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Westinghouse Non-Proprietary Class 3 v
WCAP-18909-NP March 2025 Revision 2 APPENDICES
- of Pages Appendix A Unirradiated Weld Heat # W5214 Data................................................................................ 17 LIST OF TABLES Table 2-1 Test Results for Heat # W5214, Linde 1092 Based on ASTM E1921-16 Multiple Temperature Analysis.................................................................................................................................. 2-1 Table 2-2 Calculation of T0 for Unirradiated Weld Heat # W5214, Linde 1092 per ASTM E1921-16
................................................................................................................................................ 2-2 Table 2-3 Chemistry Comparison for Heat # W5214 Specimens........................................................... 2-4 Table 2-4 Post-Weld Heat Treatment Comparison for W5214 Specimens............................................. 2-4 Table 2-5 Summary of CVN Impact Test Results for Block AY Weld W5214 Resulting from ASTM E23-2002a.................................................................................................................. 2-5 Table 3-1 Weighting Factors for Multi-Temperature Analysis............................................................... 3-2 Table 3-2 Sample Size Uncertainty Factor............................................................................................. 3-3 Table 4-1 Weld Heat # W5214 Reference Temperature Results from Palisades Steam Generator (For Informational Purposes Only)................................................................................................ 4-2 Table 4-2 Calculation of T0 for Weld Heat # W5214 from SA-60-1 per ASTM E1921-16 (For Informational Purposes Only)................................................................................................ 4-3 Table 5-1 Regulatory Guide 1.99, Revision 2 and Master Curve Method Comparison......................... 5-1
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Westinghouse Non-Proprietary Class 3 vi WCAP-18909-NP March 2025 Revision 2 LIST OF FIGURES Figure 2-1 Unirradiaded Weld Heat # W5214, Linde 1092 Fracture Toughness Relative to the Master Curves Based on ASTM E1921-16........................................................................................ 2-1 Figure 2-2 Fracture Surfaces of CVN Specimens before Mini-CT Specimen Machining....................... 2-5 Figure 2-3 Pre-Irradiation CVN Impact Energy for Robinson RV Surveillance Weld from WCAP-7373 Compared to Current Tests..................................................................................................... 2-6 Figure 2-4 CVN Impact Energy for Palisades SG Weld from AEA Testing (T-L) Comparison to Current Tests........................................................................................................................................ 2-7 Figure 2-5 CVN Impact Energy for Palisades SG Weld from AEA Testing (L-T) Comparison to Current Tests........................................................................................................................................ 2-8 Figure 2-6 Schematic of Cutting Plan of Specimens............................................................................... 2-9 Figure 2-7 CVN Specimen (dimensions given in inches, [mm])........................................................... 2-10 Figure 2-8 Mini-CT Geometry (dimensions given in inches)................................................................ 2-10 Figure 2-9 Example Mini-CT Removal Location from Broken CVN AY3........................................... 2-11 Figure 4-1 MRP-127 Weld Fracture Toughness Relative to the Master Curves (For Informational Purposes Only)....................................................................................................................................... 4-2 Figure 5-1 Comparison of T0 and RTNDT............................................................................................ 5-3
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Westinghouse Non-Proprietary Class 3 1-1 WCAP-18909-NP March 2025 Revision 2 1
INTRODUCTION The fracture toughness of the reactor pressure vessel (RPV) steel in a nuclear plant provides a key input to calculations that commercial licensees perform to demonstrate the fracture integrity of the vessel during both normal operations and postulated accident conditions (e.g., pressurized thermal shock, or PTS).
Currently, the ASME KIc curve is indexed to Reference Temperature for Nil-Ductility Transition (RTNDT) to describe the fracture toughness of the RPV and its variance with temperature. These curves were adopted in 1972 as a lower bound representation of a set of approximately 173 linear elastic fracture toughness values of RPV steel. The use of RTNDT to normalize temperature was intended to account for the heat-to-heat differences in fracture toughness transition temperature, thereby collapsing the fracture toughness data onto a single curve. However, indexing KIc to RTNDT is not a direct measure of fracture toughness but provides a conservative characterization of fracture toughness. The master curve approach is a true fracture toughness-based method that can be used to definitively determine the transition temperature fracture toughness (T0) with an increased certainty by testing fracture toughness specimens.
The purpose of this report is to report the measured initial (unirradiated) reference temperatures, and associated margins, for the H.B. Robinson Unit 2 (HBR2) Heat # W5214, Linde 1092 weld material using the fracture toughness-based Master Curve method specified in ASTM E1921-16. ASME Section III, NB-2331(a)(5) describes how to use the T0, determined per ASTM E1921, as alternative to Charpy or Drop weight testing to determine the fracture toughness-based reference temperature (RTT0).
The Nuclear Regulatory Commission (NRC) permits the use of RTT0 as an alternative to RTNDT through its approval of the 2019 Edition of ASME Section III and ASME Section XI in 10 CFR 50.55a. Both specify that T0 must be determined using ASTM E1921. ASME Section III, Table NCA-7100-2 establishes the ASTM E1921-16 as the official version for use with Section III. ASME,Section XI, Table IWA-1600-1 establishes the ASTM E1921-17 as the official version for use with Section XI. The methodologies in the 2016 and 2017 editions are equivalent. This report cites the 2016 edition, but the results are equally valid for 2017 edition. 10 CFR 50.55a Section (b)(2)(xliii) requires that T0 and RTT0 values used for ASME Section XI purposes be submitted to the NRC for review and approval. There is no equivalent condition for ASME Section III.
The HBR2 RPV Surveillance Program includes weld 10-273, Heat W5214, within Capsules X, V, and T.
However, all of this material has been irradiated. Therefore, in order to provide unirradiated data for weld Heat # W5214, Linde 1092 material, weld specimens from Palisades Steam Generator A were machined into miniature compact fracture toughness (mini-CT) specimens and tested. Section 2 presents the results of the ASTM E1921-16 transition temperature fracture toughness testing. The data from testing is provided in Appendix A. Section 3 describes the T0 calculation methodology.
In addition, MRP-127 reports the Master Curve testing results of specimens of Heat # W5214, Linde 1092, that were previously tested according to ASTM E1921-97. The results are reevaluated according to the ASTM E1921-16 methodologies in Section 4.
Section 5 outlines a method to adjust unirradiated T0 to account for irradiation induced embrittlement for use in 10 CFR 50, Appendix G Pressure-Temperature curves and 10 CFR 50.61, Pressurized Thermal Shock (PTS) evaluations.
- This record was final approved on 03/06/2025 08:39:24. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 2-1 WCAP-18909-NP March 2025 Revision 2 2
FRACTURE TOUGHNESS TESTING AND RESULTS To determine the Master Curve fracture toughness reference temperature, T0, testing was completed in accordance with ASTM E1921-16 [Ref. 1]. This section serves to provide an overview of the testing which was completed. Table 2-1 summarizes the results based on the multi-temperature analysis. The measured fracture toughness data is plotted in Figure 2-1 and the detailed calculation of T0, per the methodology described in Section 3.1, is shown in Table 2-2. The data from testing is provided in Appendix A.
Table 2-1 Test Results for Heat # W5214, Linde 1092 Based on ASTM E1921-16 Multiple Temperature Analysis Material T0(a)
(°F)
RTT0(b)
(without margin)
(°F)
RTT0(b)
(with margin)
(°F) 2 x E1921(c)
(°F)
- of Tests (Uncensored
/ Censored)
Valid per ASTM E1921 Paragraph 10.5 Heat # W5214, Linde 1092 Weld
-167.1
-132.1
-109.5 2 x 11.3 =
22.6 15 (15 / 0)
Yes Note(s):
(a) T0 developed per ASTM E1921.
(b) From ASME Section III, paragraph NB-2331(a)(5), a fracture toughness-based reference temperature, RTT0, may be used in place of RTNDT when twice the margin adjustment from ASTM E1921 is added; thus, RTT0 = T0 + 35°F + 2E1921.
(c) Twice the margin adjustment defined in ASTM E1921 is added to cover the uncertainty associated with the limited number of specimens tested to establish T0. The margin per ASTM E1921 is 11.3°F.
Figure 2-1 Unirradiaded Weld Heat # W5214, Linde 1092 Fracture Toughness Relative to the Master Curves Based on ASTM E1921-16
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Westinghouse Non-Proprietary Class 3 2-2 WCAP-18909-NP March 2025 Revision 2 Table 2-2 Calculation of T0 for Unirradiated Weld Heat # W5214, Linde 1092 per ASTM E1921-16 T0 (°C)(a) =
-110.6 T
Jc KJc KJc (1T)
Limit KJc (1T)
Censored KJc(b) (1T)
T-T0 Kronecker Delta(c)
ASTM E1921-16, Eq. 19(d)
Validity KJc(med)
ID
(°C)
(kN/m)
(MPam)
(MPam)
(MPam)
(MPam)
(C)
()
TERM 1 TERM 2 Weight(e)
(MPam)
AY1-1
-145.6 24.2 75.3 55.1 101.9 55.1
-35 1
0.01017 0.00235 0.143 66.0 AY1-2
-140.0 19.0 66.7 49.6 98.7 49.6
-29 1
0.01039 0.00086 0.143 70.1 AY1-3
-151.1 17.8 64.6 48.2 103.1 48.2
-40 1
0.00993 0.00133 0.125 62.4 AY1-4
-148.3 33.6 109.1 76.4 101.8 76.4
-38 1
0.01005 0.01819 0.125 64.2 AY4-1
-134.4 29.6 83.1 59.9 97.3 59.9
-24 1
0.01060 0.00207 0.143 74.5 AY4-3
-128.9 8.0 43.1 34.7 99.3 34.7
-18 1
0.01080 0.00003 0.143 79.5 AY4-4
-128.9 79.2 135.8 92.8 96.1 92.8
-18 1
0.01080 0.01659 0.143 79.5 AY5-1
-145.6 18.1 65.1 48.6 103.0 48.6
-35 1
0.01017 0.00104 0.143 66.0 AY5-2
-148.3 39.2 95.8 68.0 104.2 68.0
-38 1
0.01005 0.00959 0.125 64.2 AY5-3
-148.3 94.2 148.5 101.1 103.4 101.1
-38 1
0.01005 0.07787 0.125 64.2 AY5-4
-147.8 13.8 56.8 43.3 103.1 43.3
-37 1
0.01007 0.00052 0.125 64.6 AY6-1
-148.3 7.0 40.6 33.1 100.6 33.1
-38 1
0.01005 0.00005 0.125 64.2 AY6-2
-140.0 41.2 98.1 69.1 100.1 69.1
-29 1
0.01039 0.00656 0.143 70.1 AY6-3
-140.0 14.9 59.0 44.8 102.1 44.8
-29 1
0.01039 0.00043 0.143 70.1 AY6-4
-137.2 63.7 122.0 84.7 98.6 84.7
-27 1
0.01050 0.01694 0.143 72.2 Sum 15 0.15441 0.15441 2.036 1031.7 Sum(KJc(med)) / Sum() =
68.8 (f) =
18.8 E1921(g) (°C) =
6.3 Note(s)
(a) T0 is iterated until the summation of Term 1 and Term 2 are equal.
(b) Data is censored according to ASTM E1921-16, Section 10.2.1. If KJc limit (Section 3.1, Eq. 5 of this report) is violated, the KJc limit value shall be used. If crack growth limit (KJca, Section 3.1, Eq. 4 of this report) is violated, then KJca, which is set equal to the highest valid KJc, shall be used. Otherwise, set equal to KJc.
(c) 1.0 if the datum is uncensored, i.e., censored KJc set equal to KJc (1T), or zero if the datum is a censored value per footnote (b).
(d) Term 1 and Term 2 represent the 1st and 2nd terms, respectively, in the summation in ASTM E1921-16, Equation 19, which is reiterated in Section 3.1, Eq. 6 of this report.
(e) Prescribed by Table 3-1 according to (T - T0) range.
(f) Prescribed by Table 3-2 according to Sum(KJc(med)) / Sum() range.
(g) E1921 2 / Sum 4
- This record was final approved on 03/06/2025 08:39:24. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 2-3 WCAP-18909-NP March 2025 Revision 2 2.1 SOURCE AND VALIDATION OF SPECIMEN MATERIAL In order obtain unirradiated Heat # W5214, Linde 1092 specimens, Oak Ridge National Laboratory (ORNL) provided Block AY W5214 Weld Metal previously harvested from the retired Palisades Steam Generator (SG) A. This block was removed as part of Consumers Power Companys efforts to demonstrate compliance with the PTS rule circa 1994. At that time, Consumers Power Company evaluated the applicability of this SG weld material to the Palisades Reactor RPV Heat # W5214 weld material and documented it in correspondence with the NRC [Ref. 3]. The comparison of the SG-A chemistry concluded that the weld would embrittle in the same manner as the RPV weld. The post weld heat treatment was different from the Palisades RPV (Table 2-4) and so the Charpy transition temperature curve was compared to the weld Heat # W5214 taken from Indian Point Unit 2, Indian Point Unit 3, and Robinson Unit 2 welds.
The unirradiated 30 ft-lbs transition temperature of the SG-A weld is about 30°F higher than the RPV welds and therefore the SG transition temperature is conservative with respect to RPV welds. To demonstrate the applicability of the Palisades SG-A specimens to HBR2 RPV welds with Heat # W5214, the chemistry measurements and Charpy V-Notch (CVN) specimens were taken from the same Block AY provided by ORNL.
The chemistry results are shown in Table 2-3 and compared to the HBR2 RPV best estimate values and previous measurements from the Palisades Steam Generator A. The Block AY measurements were taken by atomic emission spectroscopy (AES) on broken CVN specimens AY2 and AY4 near the fracture surface.
These specimens were located at least 1/2 from fusion boundaries, weld roots, and weld surfaces with one specimen from each side of the weld root as shown in Figure 2-6. The Ni value for AY2 was outside expectations compared to AY4, HBR2 RPV, and other Palisades measurements. Additional measurements were taken from the broken CVN specimens using the Churchill bench top X-ray fluorescence spectroscopy (XRF) semi-quantitative technique. XRF analysis was then performed on the other CVN samples showing that both AY2 and AY3 showed lower Ni than expected, while all the other samples were within expectations. It was concluded that these 2 CVN specimens nearest the root may not be representative of the Ni-200 addition W5214 weld (See Figure 2-6). Therefore, mini-CT specimens machined from AY2 and AY3, both of which showed lower Ni, are not used to calculate T0.
The Charpy impact testing was conducted according to ASTM E23-2002a [Ref. 8], Standard Test Methods for Notched Bar Impact Testing of Metallic Materials. The results of the ASTM E23-2002a CVN impact tests for total 6 samples at -40F (0C) and 0 F (-17.8C) are summarized in Table 2-5. The fracture surfaces of broken CVN samples, both sides, were photographed and are presented in Figure 2-2. CVN impact test results are compared to CVN test results from the Robinson reactor vessel surveillance program (RVSP),
WCAP-7373 [Ref. 9], and the Palisades SG-A results reported by AEA [Ref. 10]. Figure 2-3 compares the current test results to the Robinson RVSP baseline testing with reasonable agreement. Figure 2-4 and Figure 2-5 compare the current test results to the AEA for two orientations. Note the two orientations considered by AEA is somewhat redundant, as typically, orientation is not considered critical in CVN testing for welds; thus, it is not considered in WCAP-7373. Both AEA stated orientations agree acceptably with Block AY. The tests support following conclusions:
the block labeled as AY provided by ORNL is from the Palisades SG-A weld, and the mini-CT test results are representative the unirradiated/initial toughness for the HBR2 welds of Heat # W5214, Linde 1092.
- This record was final approved on 03/06/2025 08:39:24. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 2-4 WCAP-18909-NP March 2025 Revision 2 Table 2-3 Chemistry Comparison for Heat # W5214 Specimens Chemistry HBR2 Vessel
[Refs. 4 & 5]
Westinghouse Specimen Measurements Palisades SG Specimens
[Ref. 6]
AY2 AY4 Cu (wt.-%)
0.21 0.36 0.29 0.307 Ni (wt.-%)
1.01 0.43 0.93 1.045 C
(wt.-%)
0.16(a) 0.10 0.10 0.094 Mn (wt.-%)
0.98(a) 1.19 1.24 1.161 Mo (wt.-%)
0.46(a) 0.51 0.49 0.510 Si (wt.-%)
0.34(a) 0.27 0.27 0.252 S
(wt.-%)
0.014 0.014 0.018 0.012 P
(wt.-%)
0.021 0.015 0.017 0.009 Note(s):
(a) Data unavailable from the stated reference so the values were taken from the Capsule X report from the HBR2 RVSP, WCAP-15805 [Ref. 7].
Table 2-4 Post-Weld Heat Treatment Comparison for W5214 Specimens HBR2 Capsule X
[Ref. 7]
Palisades Capsule SA-60-1
[Ref. 6]
1150° +/- 25°F, 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; Furnace Cooled to 600°F(a)
Post weld heat treatment: >1100°F for 25 hrs, cooled at 8°F/hr for 24 hrs.(b)
Re-post weld heat treatment: 1150°F for 2 hrs, with 100°F/hr heating/cooling rates (above 500°F)(c)
Note(s):
(a) Simulates the stress relieving treatment received by the reactor vessel.
(b) Original post weld heat treatment.
(c) Post weld heat treatment performed on retired steam generator material to ensure that the material would be as close as possible to the original start-of-life condition.
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Westinghouse Non-Proprietary Class 3 2-5 WCAP-18909-NP March 2025 Revision 2 Table 2-5 Summary of CVN Impact Test Results for Block AY Weld W5214 Resulting from ASTM E23-2002a CVN Sample ID Temperature Absorbed Energy Lateral Expansion Shear Fracture (F)
(C)
(ft-lb)
(J)
(mils)
(mm)
(%)
AY1 0
-17.8 68 92.2 52 1.3 60 AY3 0
-17.8 57 77.3 43 1.1 20 AY6 0
-17.8 24 32.5 19 0.5 30 AY2
-40
-40.0 65 88.1 54 1.4 50 AY4
-40
-40.0 39 52.9 32 0.8 10 AY5
-40
-40.0 31 42.0 24 0.6 20 Figure 2-2 Fracture Surfaces of CVN Specimens before Mini-CT Specimen Machining
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Westinghouse Non-Proprietary Class 3 2-6 WCAP-18909-NP March 2025 Revision 2 Figure 2-3 Pre-Irradiation CVN Impact Energy for Robinson RV Surveillance Weld from WCAP-7373 Compared to Current Tests Note:
Green & Red datapoints identify the data from this testing campaign as identified in Figure 2-3.
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Westinghouse Non-Proprietary Class 3 2-7 WCAP-18909-NP March 2025 Revision 2 Figure 2-4 CVN Impact Energy for Palisades SG Weld from AEA Testing (T-L)
Comparison to Current Tests Note:
Green & Red datapoints identify the data from this testing campaign as identified in Figure 2-3.
- This record was final approved on 03/06/2025 08:39:24. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 2-8 WCAP-18909-NP March 2025 Revision 2 Figure 2-5 CVN Impact Energy for Palisades SG Weld from AEA Testing (L-T)
Comparison to Current Tests Note:
Green & Red datapoints identify the data from this testing campaign as identified in Figure 2-3.
- This record was final approved on 03/06/2025 08:39:24. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 2-9 WCAP-18909-NP March 2025 Revision 2 2.2 SPECIMEN GEOMETRY Six CVN specimens were machined from Block AY as shown in Figure 2-6. The weld CVN specimens were machined in order to be oriented with crack growth parallel to the weld groove and perpendicular to the etched machined surface with the test volume farthest away from the cut surface, which appeared to be flame cut. Specimens were 1/2 or more from the weld top and bottom surfaces and root according to ASTM E185-82 [Ref. 11]. Schematic of the CVN samples is shown in Figure 2-7.
The miniature compact tension (mini-CT) specimens were machined from tested/broken CVN samples, four specimens per CVN specimen (two specimens from each half of each CVN sample). The schematic of the mini-CT specimens is shown in Figure 2-8. This resulted in twenty-four mini-CT specimens from the six broken CVN samples as shown in Figure 2-6. Mini-CT specimens were machined with orientation with crack growth parallel to the fracture surface and perpendicular to the length of the tested Charpy samples consistent with the CVN notches. The mini-CT specimens were removed from the weld metal with a reasonable distance from the fracture surfaces and plastic deformation of the notch tip during Charpy test.
An example of mini-CT specimens machined from a CVN is shown in Figure 2-9.
Figure 2-6 Schematic of Cutting Plan of Specimens
- This record was final approved on 03/06/2025 08:39:24. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 2-10 WCAP-18909-NP March 2025 Revision 2 Figure 2-7 CVN Specimen (dimensions given in inches, [mm])
Figure 2-8 Mini-CT Geometry (dimensions given in inches)
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Westinghouse Non-Proprietary Class 3 2-11 WCAP-18909-NP March 2025 Revision 2 Figure 2-9 Example Mini-CT Removal Location from Broken CVN AY3 2.3 TEST PROCEDURE 2.3.1 Pre-Cracking All pre-cracking was performed at room temperature. The pre-cracks were monitored to ensure a straight crack was produced. After the ASTM E1921 testing, the pre-crack final crack length was determined using a photo system at various locations on the crack front. The maximum Kmax value is calculated using the actual initial and final maximum pre-crack load. The maximum pre-crack load being 292 lbs to start with 124 lbs at the end.
ASTM E1921-16, Section 7.8.2, limits the initial Kmax to 25 MPam, and limits the final Kmax from pre-cracking to 20 MPam for tests conducted at or above the pre-cracking temperature and 15 MPam for tests conducted below pre-cracking temperature. The Kmax for each test met these requirements within 1 MPam except for specimen AY4-2 which had a Kmax of 18 MPam, therefore this specimen was excluded from the T0 calculation. All of the other 15 tests meet all the acceptance criteria.
2.3.2 ASTM E1921 Testing Fracture toughness testing was performed according to ASTM E1921-16. Time, applied load, and clip gage displacement were recorded during testing. The fracture surfaces were photographed, and post-test measurements of the pre-crack length and ductile crack extension (if applicable) were recorded. This data is provided in Appendix A.
Nine crack size measurements were taken according to ASTM E1921-16, Section 8.8.1, and the pre-crack straightness was checked according to E1921-16, Section 8.9.1. The pre-crack depth checks were conducted according to E1921-16, Section 7.8.2. The average crack size (depth) was calculated according to E1921-16, Section 8.8.1. The crack aspect ratio, a/W, was checked for each specimen and all were 0.45
< a/W < 0.55 consistent with E1921-16, Section 4.1. The stress intensity (K) rate was calculated for the linear portion and to failure (total). The linear K rate is to be between 0.1 and 2 MPam/s according to E1921-16, Section 8.7.1. All tests met this K rate requirement.
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Westinghouse Non-Proprietary Class 3 2-12 WCAP-18909-NP March 2025 Revision 2 Test data is analyzed to determine the J-integral (Jc) at the onset of cleavage fracture based on the sum of the elastic and plastic components. KJc was calculated per Equation 1.
(1)
Where Jc is the J-integral at onset of cleavage fracture calculated per Equation 2; E is Youngs Modulus and is Poissons Ratio (0.3).
J J J (2)
Where:
Je = to the elastic component of the J-integral as measured from test data Jp = to the plastic component of the J-integral as measured from test data Depending on the Jc result of the first test(s), the temperature was changed with subsequent tests so that a valid T0 could be produced. For mini-CT tests, testing at about 30°C (54°F) below T0 is ideal. The allowable test window is T0 +/- 50°C, but with the small specimens, testing near the lower allowable temperature is desired to reduce the number of KJclimit violations.
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Westinghouse Non-Proprietary Class 3 3-1 WCAP-18909-NP March 2025 Revision 2 3
T0 CALCULATION METHODOLOGY As described previously, ASTM E1921-16 is utilized for T0 (and RTT0) as determined herein, since 10 CFR 50.55a [Ref. 12] approves the 2019 Edition of the ASME Code Sections III and XI [Ref. 13], which cites ASTM E1921-16 [Ref. 1] and -17 [Ref. 2], respectively. The 2016 and 2017 versions of the ASTM standard are equivalent with respect to this methodology.
3.1 CALCULATION OF T0 The K data from the testing is used to calculate T0 as described herein. ASTM E1921 is based on 1TC(T) specimens; therefore, the 0.16TC(T) test results are size adjusted to 1TC(T) results per ASTM E1921-16, Section 10.2.2. This is done using Equation 3 below.
20 20
/
(3)
Where:
KJc(x) = KJc for a specimen size Bx KJc(o) = KJc for a specimen size Bo Bo = gross thickness of test specimens (side grooves ignored), and Bx = gross thickness of prediction (side grooves ignored).
The data are checked for censoring per ASTM E1921-16, Section 10.2.1 by determining if either crack growth limit (Equation 4) or KJc limit (Equation 5) are exceeded. KJc limit equation assumes a standard specimen size and must be adjusted for size using Equation 3.
a < min [0.05W-a0, 1 mm]
(4)
(5)
Where:
b0 = remaining ligament = W - a0 W = specimen width a0 = initial crack size.
= Poissons ratio = 0.3
= yield strength When KJ or KJc values are censored, these data contain statistically useable information that are applied as censored data. If KJc limit is violated, the KJc limit value shall be used for censoring purposes. If KJca is violated, then KJca, which is set equal to the highest valid KJc, shall be used for censoring purposes. If both KJc limit and KJca are violated, the lower value of the two shall prevail for data censoring purposes.
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Westinghouse Non-Proprietary Class 3 3-2 WCAP-18909-NP March 2025 Revision 2 If tests are conducted at multiple temperatures (Ti), then, per ASTM E1921-16, Section 10.2.3, T0Q is iterated on until Equation 6 below is satisfied. At that point, T0 = T0Q.
0 (6)
Where:
N = number of specimens tested within 50ºC of T0Q Ti = test temperature corresponding to KJc(i),
KJc(i) = either an uncensored KJc datum or a datum replaced with a censoring value. This is the 1T equivalent KJc value.
i = 1.0 if the datum is uncensored or zero if the datum is a censored value.
T0Q = T0 when the equation is satisfied.
T0 is checked for validity per ASTM E1921-16, Section 10.3, by summing the weighting factors from Table 3-1 for each test and confirming the result is greater than or equal to 1.0.
1 (7)
Where:
ri = the number of uncensored data within the i-th temperature range, (TT0) in Table 3-1, ni = the specimen weighting factor for the same temperature range as shown in Table 3-1.
Table 3-1 Weighting Factors for Multi-Temperature Analysis (T - T0) Range
(°C) 1T KJc(med) Range(a)
(MPam)
Weighting Factor ni 50 to -14 212 to 84 1/6
-15 to -35 83 to 66 1/7
-36 to -50 65 to 58 1/8 Note(s):
(a) Rounded off to the closest integer.
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Westinghouse Non-Proprietary Class 3 3-3 WCAP-18909-NP March 2025 Revision 2 3.2 MEASUREMENT MARGIN ADJUSTMENT The ASTM E1921-16, Section 10.9 margin adjustment associated with the T0 and RTT0 can be calculated using Equation 8:
(8)
Where:
= sample size uncertainty factor defined in Table 3-2.
r= total number of uncensored specimens used to establish the value T0, and exp = contribution of experimental uncertainties.
Since standard calibration practices were followed, exp = 4°C is used.
Table 3-2 Sample Size Uncertainty Factor
1T Equivalent(a)
(MPam)
(°C)
> 83 18 83 to 66 18.8 65 to 58 20.1 Note(s):
(a) Rounded off to nearest whole number.
Where:
KJc(med) eq
=
1 r
30 + 70 exp(0.019Ti-T0) r i=1 MPam (9)
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Westinghouse Non-Proprietary Class 3 4-1 WCAP-18909-NP March 2025 Revision 2 4
COMPARISON WITH MRP-127 MRP-127 [Ref. 14] reported the results from previous Master Curve testing of unirradiated Weld Heat #
W5214, Linde 1092, specimens. These tests were conducted in accordance with ASTM E1921-97, with some modification per ASTM E1921-02 to account for specimen size and number of specimens. The source of Weld Heat # W5214 for the specimens in the MRP-127 also came from the Palisades SG-A. The applicability of this material is discussed in Section 2.1 of this report. The available test results are reevaluated here according to ASTM E1921-16. Due to the uncertainty associated with testing for MRP-127 compliance with ASTM E1921-16, specifically the loading rates which are discussed below, these results are intended for informational and comparative purposes only and should not be used to establish the materials reference temperature.
Significant differences between the MRP-127 calculation and the methods used herein (ASTM E1921-16) include:
MRP-127 states that as the fatigue crack length increased, the stress intensity range was decreased to approximately 15.9 MPam at the final stage of pre-cracking. According to E1921-16, Table 1, Kfinal should be less than 15 MPam when the test temperature < pre-cracking temperature. The tests were conducted at -200°F while pre-cracking was most likely conducted at room temperature. Therefore, the pre-cracking Kmax slightly violates E1921-16. This is not a significant violation and likely would not affect the results.
Since the 1997 edition, the Poissons ratio was added to the conversion from Je to KJc. If the test is purely elastic (small Jp), then the 1-2 terms in the Je and KJc equations cancel out and there is no effect.
If the test has large plasticity (large Jp relative to Je) then the E1921-16 would provide a higher KJc value than the E1921-97 version. Therefore, the E1921-97 calculated KJc values are conservative and are used as is herein.
ASTM E1921-16 adds an 18°F (10°C) bias to the Charpy size three-point bend (3PB) test temperature, while it is not discussed in E1921-97. MRP-127 clearly states that Charpy size 3PB (also called pre-cracked Charpy V-notch) specimens were tested. Therefore, the 18°F (10°C) bias will be added to the test temperature to calculate the T0 with the 3PB bias.
Crack front straightness in ASTM E1921-97 was defined as no points differ by more than 7% from average a0, while ASTM E1921-16 requires that none may differ more than 5% of B from the average or 0.5 mm, whichever is larger. The a0/W was about 0.5 making a0 = 0.197 inch and B = 0.394 inch (B
= W). This results in the ASTM E1921-97 crack front straightness being more restrictive for this specimen geometry than ASTM E1921-16, therefore the cracks passing E1921-97 requirements are acceptable to E1921-16.
The loading rate limits differ between ASTM E1921-97 and ASTM E1921-16. ASTM E1921-97 limits loading specimens at a rate such that the time of loading taken to reach load PM lies between 0.1 and 10 min. ASTM E1921-16 states that specimens are to be loaded at a rate such that Krate during the initial elastic portion is between 0.1 and 2 MPam/s. The maximum load time of 10 min results in a loading rate less than that allowed by ASTM E1921-16. Due to the unreported loading rate and the tighter limits in loading rate for ASTM E1921-16, the T0 is increased by 25°F to ensure a conservative result. This adjustment is based on Equation 4-2 from BAW-2308, Rev. 1-A [Ref. 15].
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Westinghouse Non-Proprietary Class 3 4-2 WCAP-18909-NP March 2025 Revision 2 The results of the ASTM E1921-16 T0 calculations are shown in Table 4-1 based on the calculation in Table 4-2 and the measured fracture toughness data is plotted in Figure 4-1. The KJc values shown in Table 4-2 are different from those in MRP-127 due to the use of (1-2) in Equation 15 of E1921-16. Other than this difference and the 3PB bias, the results are consistent with Table 3-3 of MRP-127. The data relative to the 5% and 95% tolerance bounds are shown in Figure 4-1. The data is fully bounded by the 5%
tolerance bound and the 5% tolerance bound curve with 2 added. The result determined herein agree well with the reevaluated MRP-127 data; thus, providing assurance that an accurate and conservative fracture toughness-based reference temperature has been generated.
Table 4-1 Weld Heat # W5214 Reference Temperature Results from Palisades Steam Generator (For Informational Purposes Only)
MRP-127 Reported Results Revised MRP-127 Results Results from Section 2 T0 from MRP-127
(ºF)
-192.8
-180.6 to -156.0
-167.1 Test E1921 (ºF) 9.8 11.8 to 16 11.3
- of Valid Specimens (Uncensored/Censored) 12 (12 / 0) 12 (12 / 0) 15 (15 / 0)
Valid Yes Yes Yes Figure 4-1 MRP-127 Weld Fracture Toughness Relative to the Master Curves (For Informational Purposes Only)
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Westinghouse Non-Proprietary Class 3 4-3 WCAP-18909-NP March 2025 Revision 2 Table 4-2 Calculation of T0 for Weld Heat # W5214 from SA-60-1 per ASTM E1921-16 (For Informational Purposes Only)
T0 (°C)(a) =
-118.1 T(b)
Jc KJc KJc (1T)
Limit KJc (1T)
Censored KJc(c) (1T)
T-T0 Kronecker Delta(d)
ASTM E1921-16, Eq. 19(e)
Validity KJc(med)
ID
(°C)
(kN/m)
(MPam)
(MPam)
(MPam)
(MPam)
(C)
()
TERM 1 TERM 2 Weight(f)
(MPam)
AA-11
-118.9 43.1 100.3 83.6 129.2 83.6
-1 1
0.01134 0.00329 0.167 99.0 AA-12
-118.9 74.3 131.6 108.4 129.2 108.4
-1 1
0.01134 0.01232 0.167 99.0 AA-01
-118.9 78.4 135.2 111.3 129.2 111.3
-1 1
0.01134 0.01398 0.167 99.0 AA-10
-118.9 76.9 133.9 110.2 129.2 110.2
-1 1
0.01134 0.01336 0.167 99.0 AA-07
-118.9 89.3 144.2 118.4 129.2 118.4
-1 1
0.01134 0.01890 0.167 99.0 AA-02
-118.9 77.9 134.7 110.9 129.2 110.9
-1 1
0.01134 0.01375 0.167 99.0 AA-04
-118.9 74.0 131.3 108.2 129.2 108.2
-1 1
0.01134 0.01218 0.167 99.0 AA-06
-118.9 81.2 137.6 113.1 129.2 113.1
-1 1
0.01134 0.01516 0.167 99.0 AA-03
-118.9 85.6 141.2 116.0 129.2 116.0
-1 1
0.01134 0.01715 0.167 99.0 AA-08
-118.9 72.5 130.0 107.1 129.2 107.1
-1 1
0.01134 0.01162 0.167 99.0 AA-09
-118.9 35.7 91.2 76.4 129.2 76.4
-1 1
0.01134 0.00204 0.167 99.0 AA-05
-118.9 37.5 93.5 78.2 129.2 78.2
-1 1
0.01134 0.00232 0.167 99.0 Sum 12 0.13605 0.13605 2.000 1188.0 Sum(KJc(med)) / Sum() =
99.0 (g) =
18 E1921(h) (°C) =
6.6 Note(s)
(a) T0 is iterated until the summation of Term 1 and Term 2 are equal.
(b) 10ºC is added to the listed temperature in MRP-127 to bias the Charpy-size 3PB test result as required per ASTM E1921-16.
(c) Data is censored according to ASTM E1921-16, Section 10.2.1. If KJc limit (Section 3.1, Eq. 5 of this report) is violated, the KJc limit value shall be used. If crack growth limit (KJca, Section 3.1, Eq. 4 of this report) is violated, then KJca, which is set equal to the highest valid KJc, shall be used. Otherwise, set equal to KJc.
(d) 1.0 if the datum is uncensored, i.e., censored KJc set equal to KJc (1T), or zero if the datum is a censored value per footnote (c).
(e) Term 1 and Term 2 represent the 1st and 2nd terms, respectively, in the summation in ASTM E1921-16, Equation 19, which is reiterated in Section 3.1, Eq. 6 of this report.
(f) Prescribed by Table 3-1 according to (T - T0) range.
(g) Prescribed by Table 3-2 according to Sum(KJc(med)) / Sum() range.
(h) E1921 2 / Sum 4
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Westinghouse Non-Proprietary Class 3 5-1 WCAP-18909-NP March 2025 Revision 2 5
IRRADIATION INDUCED SHIFT IN FRACTURE TOUGHNESS AND APPLICABLE MARGINS To use T0 for reactor vessel integrity analyses, i.e., P-T limit curves (10 CFR 50, Appendix G) and PTS (10 CFR 50.61), it must be adjusted to the irradiated condition of the vessel. This is done by adjusting the data along an Embrittlement Trend Curve (ETC). No ETC is specified in 10 CFR 50, Appendix G [Ref. 16] for P-T limit curves; however, the NRC has provided guidance in Regulatory Guide 1.99, Revision 2 (RG 1.99)
[Ref. 17]. 10 CFR 50.61 [Ref. 18] does provide an ETC that is equivalent to RG 1.99. The RG 1.99 ETC is based on the shift in the 30 ft-lbs transition temperate (T30). There is no industry accepted ETC based on T0; therefore, the currently approved T30 ETC from RG 1.99 will be maintained. The validity of the approached is addressed in Section 5.2.2 of this report.
RG 1.99 determines the effect of irradiation on ferritic reactor vessel material by calculating an adjusted Reference Temperature for Nil-Ductility Transition (RTNDT). This equation is also consistent with 10 CFR 50.61.
Adjusted RTNDT = Initial RTNDT + RTNDT + Margin (10)
Table 5-1 provides a comparison of the inputs to Equation 10 based on the method chosen. Each portion of Equation 10 is addressed in the below subsections.
Table 5-1 Regulatory Guide 1.99, Revision 2 and Master Curve Method Comparison RG 1.99 With Master Curve Data Comments Initial Ref.
Temp.
Determined per ASME Code Section III Determined per ASTM E1921 + 2 + 35°F Calculated Shift (RTNDT)
CF x FF Welds = 1.0 x RTNDT_RG1.99 Plates / Forgings = 1.1 x RTNDT_RG1.99 For Heat # W5214, RG 1.99 Position 2.1 should not be used.
Margin 2
I 0°F (Based on Measured RTNDT) 0°F (Based on Measured RTNDT)
= 17°F for plates/forgings
= 28°F for welds
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Westinghouse Non-Proprietary Class 3 5-2 WCAP-18909-NP March 2025 Revision 2 5.1 INITIAL REFERENCE TEMPERATURE ASME III NB-2300 & XI, Appendix G, does provide a method to convert T0 to an alternate RTNDT resulting in a fracture toughness-based reference temperature (RTT0).
The initial RTNDT based on T0 is addressed by ASME Section III and Section XI, Appendix G [Ref. 13]
(formerly in Code Case N-629). The Code requires an adjustment to T0 for it to be used with the KIc curve.
Per ASME Section III, paragraph NB-2331(a)(5) and ASME Section XI, Sub-article G-2110, fracture toughness-based reference temperature, RTT0, is determined using a valid T0 calculated per ASTM E1921 using Equation 11.
RTT0 = T0 + 35°F (11)
In addition, NB-2331(a)(5) requires twice the margin adjustment defined in ASTM E1921 to be added to account for the uncertainty associated with the limited number of specimens tested to establish T0. This margin adjustment (E1921) is presented in Section 3.2, Equation 8.
These adjustments are required for the use of T0 with 10 CFR 50.61, PTS.
5.2 IRRADIATION INDUCED SHIFT IN FRACTURE TOUGHNESS (RTNDT) 5.2.1 Regulatory Guide 1.99, Revision 2, ETC Methodology RG 1.99 calculates the shift term (RTNDT) as:
RTNDT = CF x f (0.28 - 0.10 log f)
(12)
Where:
CF =
the chemistry factor based on the Cu and Ni content and RG 1.99, Table 1 for weld or Table 2 for base metal f =
the fluence at the desired location in the reactor vessel material, i.e., surface, 1/4T, or 3/4T.
This is sometimes referred to as the fluence factor (FF).
5.2.2 ETC Use with Master Curve Data Equation 12 is based on the difference between the unirradiated and irradiated Charpy V-notch 30 ft-lb transition temperatures. Replacement of the initial RTNDT with an appropriate alternative initial reference temperature, specifically RTT0, does not necessitate a change to the shift term in RG 1.99 for welds. This assertion has been studied and, in some cases, there is a measured difference between T30 and T0. Since the ETC model used is based on T30, this difference is considered. ORNL/TM-2012/567 [Ref. 19],
compared these two shifts and, on average, the ratio of T0 to T30 for welds is 0.99 and 1.1 for plates as shown Figure 5-1. Due to a lack of forging shift data, a value of 1.1 has previously been used for forgings, matching the plate value as shown in NUREG-1807 [Ref. 20]. For simplicity and conservatism, the ETC
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Westinghouse Non-Proprietary Class 3 5-3 WCAP-18909-NP March 2025 Revision 2 from RG 1.99 [Ref. 17] may be multiplied by a factor of 1.0 for welds and 1.1 for plates/forgings. These factors are consistent with a more recent evaluation [Ref. 21].
Figure 5-1 Comparison of T0 and RTNDT 5.2.3 Use of Surveillance Data 10 CFR 50.61 and RG 1.99 requires that surveillance data to be considered; however, the surveillance data requirement applies to data generated under the 10 CFR 50, Appendix H, Reactor Vessel Surveillance program. The only fracture toughness tests required by these Reactor Vessel Surveillance programs are Charpy V-Notch tests, which are not sufficient to make T0 determinations. In addition, there currently exists no NRC approved method to incorporate measured T0 results into T0 projections. Therefore, T0 measurements are only for ETC confirmation at this time.
WCAP-18933-NP [Ref. 22] evaluated the irradiated T0 for Heat # W5214, Linde 1092 at two exposures according to ASTM E1921-16. The first samples were from the Palisades steam generator, which were irradiated to 1.5E+19 n/cm2 in Palisades capsule SA-60-1. The results were first reported in BAW-2389 according to ASTM E1921-97 but were reevaluated to the ASTM E1921-16 in WCAP-18933-NP. The ASTM E1921-16 evaluation resulted in an irradiated T0 = 137.8°F, which results in a measured T0 =
137.8°F - (-167.1°F) = 304.9°F. This is compared to the RG 1.99, Position 1.1 predicted T30 = 296.4°F, based on chemistry content of Cu = 0.307 wt-% and Ni = 1.045 wt-% (CF = 266.5°F) and fluence of 1.5E+19 n/cm2 (FF = 1.112) for the Palisades SG-A chemistry. This results in a measured to predicted T0/30 difference of 8.5°F (304.9°F - 296.4°F), which is within a standard deviation of the RG 1.99 ETC
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Westinghouse Non-Proprietary Class 3 5-4 WCAP-18909-NP March 2025 Revision 2
(+/-) for welds, 28°F and within the measurement margin adjustment. This is the RG 1.99 credibility acceptance criteria.
The second samples were from the HBR2 Capsule X, which were irradiated to 4.43E+19 n/cm2. The ASTM E1921-16 evaluation resulted in an irradiated T0 = 131.2°F, which results in a measured T0 = 131.2°F -
(-167.1°F) = 298.3°F. This is compared to the RG 1.99, Position 1.1 predicted T30 = 300°F, based on chemistry content of Cu = 0.34 wt-% and Ni = 0.66 wt-% as reported in WCAP-15805 [Ref. 7] for the surveillance weld (CF = 217.7°F) and fluence of 4.43E+19 n/cm2 (FF = 1.378). This results in a measured to predicted T0/30 difference of -1.7°F (298.3°F - 300°F), which is within a standard deviation of the RG 1.99 ETC (+/-) for welds, 28°F and within the measurement margin adjustment.
It is noted that the lower irradiation resulted in greater measured shift. This is not unexpected. In addition to the worst chemistry, which is reflected in the predicted T30, the SA-60-1 specimens were also irradiated at a lower temperature (535°F vs 546°F).
RG 1.99 also allows for the use of credible material-specific T30 surveillance data, i.e., Position 2.1 CF.
In the case of Heat # W5214 material, the surveillance data for this material are deemed not fully credible in SIA Report 0901132.401 [Ref. 23], which allowed the use of the Position 2.1 CF but requires the use of a full margin term (see Section 5.3). Position 2.1 results in a CF of 227.7°F. This CF is based on the surveillance data from multiple plants with an averaged operating temperature of 535°F and a Position 1.1 CF of 230.7°F based on the averaged chemistry of the specimens from those surveillance programs. These differences (temperature and chemistry) can be approximated by multiplying the Position 2.1 CF of 227.7°F by the ratio of Position 1.1 CF, and adding the temperature difference. For the temperature difference, it should be applied so that a colder operating temperature results in more embrittlement.
If the Position 2.1 CF is used to evaluate the SA-60-1 data, then the T30 would be 253.3°F (227.7°F x 1.112) and results in measured to predicted T0/30 difference of 51.6°F (304.9°F - 253.3°F), which is greater than +/-, 28°F, but within +/-2 for welds, 2
- 28°F = 56°F. Since the operating temperature of Palisades is approximately equal to the average temperature of all specimens, only the chemistry difference needs to be accounted for. This can be approximated as CF = 227.7°F x 266.5°F / 230.7°F = 263.0°F. This results in a T30 ~292.5°F (263.0°F x 1.112), and a measured to predicted T0/30 difference of ~12.4°F (304.9°F -
292.5°F), which is within +/- for welds, 28°F.
If this Position 2.1 CF is used to evaluate the Capsule X data, then the T30 would be 313.7°F (227.7°F x 1.378) and result in measured to predicted T0/30 difference of -15.5°F (298.3°F - 313.7°F), which is within
+/- for welds, 28°F. However, this does not account for the chemistry and temperature differences between the Position 2.1 CF calculation (CF=230.7°F, Temp.=535°F) and the HBR2 specimens (CF=217.7°F, Temp.=546°F). This affect can be approximated as CF = 227.7°F x 217.7°F / 230.7°F - 11°F = 203.9°F.
This results in a T30 ~280.9°F (203.9°F x 1.378), and a measured to predicted T0/30 difference of ~17.4°F (298.3°F - 280.9°F), which is within +/- for welds, 28°F.
Because the RG 1.99 Position 2.1 CF based 10 CFR 50, Appendix H surveillance data was not intended for T0 projections and it is less conservative than the measured T0, the Heat # W5214 embrittlement predictions should be based on RG 1.99, Position 1.1, when the initial RTNDT is based on master curve data.
However, the surveillance data demonstrates that the RG 1.99 ETC provides conservative embrittlement projections for the initial T0 of the W5214 weld material in HBR2.
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Westinghouse Non-Proprietary Class 3 5-5 WCAP-18909-NP March 2025 Revision 2 5.3 APPLICABLE MARGINS In Equation 10, the Initial RTNDT and shift term (RTNDT) have independent measures of uncertainty, which are captured in Equation 13.
Margin 2
2 2
I (13)
Where:
I = uncertainty in the initial RTNDT
= uncertainty in RTNDT 5.3.1 Uncertainty of Initial Reference Temperature (I)
This term is the uncertainty associated with the methods used to measure the initial RTNDT. Typically, for example in WCAP-14040-A [Ref. 24], the I term is set equal to zero (0) when measured data is used.
ASTM E1921-16 provides a method to determine a measurement margin adjustment for T0 based on the number of tests and normal experimental uncertainties. However, in order to align with NB-2331(a)(5),
this adjustment has already been applied as shown in Section 5.1. Therefore, the I term can continue to be set to zero (0) when the initial reference temperature is based on RTT0.
5.3.2 Uncertainty of Irradiation-Induced Shift ()
This term is the uncertainty associated with the ETC used. RG 1.99 recommends that be set equal to specific values depending upon the product form ( = 17°F for plates/forgings and = 28°F for welds) but limited to half of the magnitude of the predicted shift. If credible surveillance data is used, this value is halved. Since RTNDT is still based on the ETC in RG 1.99, the values remain appropriate for welds.
The continued use of = 28°F is supported by the evaluation of available measured T0 data presented in Section 5.2.3, which demonstrated the predictions are within +/-. This is also consistent with previously approved uses of Master Curve data for vessel integrity in BAW-2308 [Ref. 15].
- This record was final approved on 03/06/2025 08:39:24. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 6-1 WCAP-18909-NP March 2025 Revision 2 6
REFERENCES
- 1. ASTM E1921-16, Standard Test Method for Determination of Reference Temperature, T0, for Ferritic Steels in the Transition Range, August 2016.
- 2. ASTM E1921-17, Standard Test Method for Determination of Reference Temperature, T0, for Ferritic Steels in the Transition Range, May 2017.
- 3. Consumers Power Letter, Palisades Compliance with Pressurized Thermal Shock Screening Criteria, November 30, 1994. [ADAMS Accession No. ML18064A487]
- 4. Westinghouse Report, WCAP-18215-NP, Revision 0, H.B. Robinson Unit 2 End-of-License Extension Reactor Vessel Integrity Evaluations and Feasibility Study, March 2017. [Agencywide Documents Access and Management System (ADAMS) Accession No. ML18038B289]
- 5. CP&L Letter RNP-RA/95-0205, H.B. Robinson Steam Electric Plant, Unit No. 2 Docket No.
50-261/License No. DPR-23; Response to Generic Letter 92-01, Revision 1, Supplement 1, Reactor Vessel Structural Integrity, November 20, 1995. [ADAMS Accession No. ML14178A896]
- 6. BAW-2341, Revision 2, Test Results of Capsule SA-60-1, Consumers Energy, Palisades Nuclear Plant
- Reactor Vessel Material Surveillance Program, May 2001. [ADAMS Accession No. ML11145A180]
- 7. WCAP-15805, Revision 0, Analysis of Capsule X from the Carolina Power & Light Company H.B.
Robinson Unit 2 Reactor Vessel Radiation Surveillance Program, March 2002.
- 8. ASTM E23-2002a, Standard Test Methods for Notched Bar Impact Testing of Metallic Materials, ASTM International, 2002.
- 9. WCAP-7373, Revision 0, Carolina Power and Light Co. H. B. Robinson Unit No. 2 Reactor Vessel Radiation Surveillance Program, January 1970.
- 10. AEA Technology Report AEA-TSD-0774, Evaluation of Weldmetals from Retired Palisades Steam Generators, November 1995.
- 11. ASTM E185-82, Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, E 706, 1982.
- 12. Code of Federal Regulations, 10 CFR 50.55a, Codes and Standards, dated October 27, 2022.
- 13. ASME Boiler and Pressure Vessel (B&PV) Code,Section III, Division 1, Rules for Construction of Nuclear Facility Components, and XI, Division 1, Rules for Inservice Inspection of Nuclear Power Plant Components, 2019 Edition.
- 14. Westinghouse LTR-CI-04-49, Revision 0, Materials Reliability Program: Fracture Toughness Evaluation of Unirradiated and Irradiated RPV Weld Metals (MRP-127), EPRI Report 1011112, Technical Update, August 2004 Final Report, August 2004 December 2004.
- 15. AREVA Document BAW-2308, Revision 1-A and 2-A, Initial RTNDT of Linde 80 Weld Materials, August 2005 [ADAMS Accession Number ML052070408] and March 2008 [ADAMS Accession Number ML081270388].
- 16. Code of Federal Regulations 10 CFR 50, Appendix G, Fracture Toughness Requirements, U.S.
Nuclear Regulatory Commission, Federal Register, dated November 29, 2019.
- This record was final approved on 03/06/2025 08:39:24. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 6-2 WCAP-18909-NP March 2025 Revision 2
- 17. U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Regulatory Guide 1.99, Revision 2, Radiation Embrittlement of Reactor Vessel Materials, May 1988. [ADAMS Accession Number ML003740284]
- 18. Code of Federal Regulations, 10 CFR 50.61, Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events, dated November 29, 2019.
- 19. Oak Ridge National Laboratory Report ORNL/TM-2012/567, Fracture Analysis of Vessels - Oak Ridge FAVOR, v12.1, Computer Code: Theory and Implementation of Algorithms, Methods, and Correlations, November 2012. [ADAMS Accession Number ML13008A015]
- 20. U.S Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, NUREG-1807, Probabilistic Fracture Mechanics - Models, Parameters, and Uncertainty Treatment Used in FAVOR Version 04.1, June 2007. [ADAMS Accession Number ML072010411]
- 21. Methods to Address the Effects of Irradiation Embrittlement in Section XI of the ASME Code (MRP-462): Estimation of an Irradiated Reference Temperature Using Either Traditional Charpy Approaches or Master Curve Data. EPRI, Palo Alto, CA: 2021. 3002020911.
- 22. WCAP-18933-NP, Revision 1, Determination of T0 for H.B. Robinson Unit 2 Heat # W5214 Weld Metal and Upper Shell Plate W10201-1 Based on Available Irradiated Data, March 2025.
- 23. Structural Integrity Associates (SIA), Inc. Report 0901132.401, Revision 0, Evaluation of Surveillance Data for Weld Heat No. W5214 for Application to Palisades PTS Analysis, April 2010. [ADAMS Accession Number ML110060693]
- 24. Westinghouse Report WCAP-14040-A, Revision 4, Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves, May 2004. [ADAMS Accession No. ML050120209]
- This record was final approved on 03/06/2025 08:39:24. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 A-1 WCAP-18909-NP March 2025 Revision 2 APPENDIX A UNIRRADIATED WELD HEAT # W5214 DATA L = 0.394 in Notch thickness (h) = 0.010 in Yield Modulus = 64.15 ksi @ 75°F per WCAP-7373 Tensile Strength = 79.8 ksi @ 75°F per WCAP-7373 Block AY Mini CT Specimen ID 1-1 1-2 1-3 1-4 4-1 4-2(b) 4-3 4-4 5-1 5-2 5-3 5-4 6-1 6-2 6-3 6-4 a1 (in) 0.0218 0.0223 0.0189 0.0278 0.0240 0.0289 0.0242 0.0264 0.0226 0.0208 0.0212 0.0226 0.0246 0.0208 0.0212 0.0226 a2 (in) 0.0280 0.0336 0.0297 0.0335 0.0333 0.0357 0.0284 0.0335 0.0311 0.0288 0.0292 0.0325 0.0332 0.0311 0.0259 0.0316 a3 (in) 0.0303 0.0384 0.0321 0.0344 0.0389 0.0410 0.0303 0.0382 0.0349 0.0325 0.0335 0.0368 0.0393 0.0373 0.0288 0.0363 a4 (in) 0.0327 0.0403 0.0335 0.0358 0.0394 0.0439 0.0318 0.0401 0.0358 0.0349 0.0344 0.0373 0.0445 0.0354 0.0321 0.0387 a5 (in) 0.0351 0.0431 0.0344 0.0363 0.0403 0.0443 0.0327 0.0425 0.0358 0.0354 0.0325 0.0368 0.0450 0.0358 0.0321 0.0410 a6 (in) 0.0341 0.0431 0.0335 0.0358 0.0389 0.0429 0.0351 0.0434 0.0354 0.0349 0.0325 0.0358 0.0431 0.0354 0.0330 0.0429 a7 (in) 0.0322 0.0408 0.0325 0.0321 0.0357 0.0390 0.0336 0.0420 0.0335 0.0325 0.0307 0.0344 0.0398 0.0335 0.0302 0.0406 a8 (in) 0.0303 0.0384 0.0278 0.0292 0.0314 0.0328 0.0299 0.0377 0.0297 0.0278 0.0278 0.0321 0.0336 0.0292 0.0288 0.0330 a9 (in) 0.0237 0.0294 0.0208 0.0217 0.0249 0.0246 0.0251 0.0264 0.0231 0.0236 0.0226 0.0236 0.0256 0.0222 0.0231 0.0241 Average(a)
(in) 0.0307 0.0379 0.0304 0.0328 0.0353 0.0383 0.0308 0.0380 0.0324 0.0311 0.0303 0.0336 0.0380 0.0324 0.0291 0.0359 Cycles 56843 64690 59230 53581 55173 53786 42699 49371 45462 68015 59127 50081 52804 55843 54088 63154 Initial Max Load (lbs) 292 290 288 290 287 286 288 285 284 287 285 287 290 288 290 287 Final Max Load (lbs) 128 128 127 125 125 126 127 126 125 127 125 128 126 124 128 128 B (in) 0.163 0.161 0.160 0.160 0.160 0.155 0.164 0.156 0.162 0.161 0.158 0.162 0.162 0.156 0.163 0.162 W (in) 0.325 0.330 0.329 0.327 0.326 0.326 0.328 0.327 0.331 0.334 0.330 0.333 0.328 0.328 0.330 0.326 notch (in) 0.132 0.136 0.136 0.134 0.135 0.140 0.131 0.132 0.133 0.135 0.134 0.135 0.135 0.133 0.134 0.133 Temperature
(°F)
-230
-220
-240
-235
-210
-210
-200
-200
-230
-235
-235
-234
-235
-220
-220
-215 Note(s):
(a) The average crack size (depth) is calculated according to E1921 Section 8.8.1. Average the two near-surface measurements and then combine with the remaining seven crack measurements.
(b) Results from this specimen are not used in the T0 determination because the final pre-crack kmax value exceeded 15 MPam.
- This record was final approved on 03/06/2025 08:39:24. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 A-2 WCAP-18909-NP March 2025 Revision 2 A.1 Specimen AY1-1 Test Date Date: 12/1/2023 Laboratory Westinghouse Specimen ID AY1-1 Material Type Weld Metal #W5214 Clip gauge type Outboard (Load-line)
Test Temperature - T -146 (C)
Elastic Modulus - E at T 213 (GPa)
Yield Strength - YS at T 692 (MPa)
Tensile Strength - UTS at T 800 (MPa)
Specimen Width - W 8.25 (mm)
Specimen Thickness - B 4.13 (mm)
Specimen Height - 2H 10.0 (mm)
Net Thickness - BN 4.13 (mm)
Final Crack Length - a0 4.14 (mm) a0/W 0.502 Fatigue Pre-cracking Final Kmax 14.7(MPa-m)
Number of fatigue cycles 56843 Loading Speed 0.15 (mm/min)
(Max a - Min a)/B 8%
Je 16.6 (kN/m)
Jp 7.6 (kN/m)
Jc 24.2 (kN/m)
KJc 75.3 (MPa-m)
KJc (1T eq) 102.6 (MPa-m)
KJc (limit) 128 (MPa-m)
KJc (limit) (1T eq) 88.6 (MPa-m)
Ductile Crack Growth 0
(mm)
Valid Test?
Yes
- This record was final approved on 03/06/2025 08:39:24. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 A-3 WCAP-18909-NP March 2025 Revision 2 A.2 Specimen AY1-2 Test Date Date: 12/2/2023 Laboratory Westinghouse Specimen ID AY1-2 Material Type Weld Metal #W5214 Clip gauge type Outboard (Load-line)
Test Temperature - T
-140 (C)
Elastic Modulus - E at T 213 (GPa)
Yield Strength - YS at T 673 (MPa)
Tensile Strength - UTS at T 781(MPa)
Specimen Width - W 8.37 (mm)
Specimen Thickness - B 4.08 (mm)
Specimen Height - 2H 10.0 (mm)
Net Thickness - BN 4.08 (mm)
Final Crack Length - a0 4.41 (mm) a0/W 0.526 Fatigue Pre-cracking Final Kmax 16.0(MPa-m)
Number of fatigue cycles 64690 Loading Speed 0.15 (mm/min)
(Max a - Min a)/B 13%
Je 14.4 (kN/m)
Jp 4.7 (kN/m)
Jc 19.1 (kN/m)
KJC 66.7 (MPa-m)
KJC (1T eq) 49.6 (MPa-m)
KJc (limit) 144 (MPa-m)
KJc (limit) (1T eq) 98.7 (MPa-m)
Ductile Crack Growth 0
(mm)
Valid Test?
Yes
- This record was final approved on 03/06/2025 08:39:24. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 A-4 WCAP-18909-NP March 2025 Revision 2 A.3 Specimen AY1-3 Test Date Date: 12/2/2023 Laboratory Westinghouse Specimen ID AY1-3 Material Type Weld Metal #W5214 Clip gauge type Outboard (Load-line)
Test Temperature - T
-151 (C)
Elastic Modulus - E at T 213 (GPa)
Yield Strength - YS at T 712 (MPa)
Tensile Strength - UTS at T 820(MPa)
Specimen Width - W 8.35 (mm)
Specimen Thickness - B 4.07 (mm)
Specimen Height - 2H 10.0 (mm)
Net Thickness - BN 4.07 (mm)
Final Crack Length - a0 4.23 (mm) a0/W 0.507 Fatigue Pre-cracking Final Kmax 15.0(MPa-m)
Number of fatigue cycles 59230 Loading Speed 0.15 (mm/min)
(Max a - Min a)/B 10%
Je 14.3 (kN/m)
Jp 3.6 (kN/m)
Jc 17.9 (kN/m)
KJc 64.6 (MPa-m)
KJc (1T eq) 48.2 (MPa-m)
KJc (limit) 151 (MPa-m)
KJc (limit) (1T eq) 103.1 (MPa-m)
Ductile Crack Growth 0
(mm)
Valid Test?
Yes
- This record was final approved on 03/06/2025 08:39:24. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 A-5 WCAP-18909-NP March 2025 Revision 2 A.4 Specimen AY1-4 Test Date Date: 12/2/2023 Laboratory Westinghouse Specimen ID AY1-4 Material Type Weld Metal #W5214 Clip gauge type Outboard (Load-line)
Test Temperature - T
-148 (C)
Elastic Modulus - E at T 213 (GPa)
Yield Strength - YS at T 701 (MPa)
Tensile Strength - UTS at T 809(MPa)
Specimen Width - W 8.30 (mm)
Specimen Thickness - B 4.07 (mm)
Specimen Height - 2H 10.0 (mm)
Net Thickness - BN 4.07 (mm)
Final Crack Length - a0 4.24 (mm) a0/W 0.510 Fatigue Pre-cracking Final Kmax 14.9(MPa-m)
Number of fatigue cycles 53581 Loading Speed 0.15 (mm/min)
(Max a - Min a)/B 9%
Je 19.0 (kN/m)
Jp 14.6 (kN/m)
Jc 33.6 (kN/m)
KJc 109.1 (MPa-m)
KJc (1T eq) 76.4 (MPa-m)
KJc (limit) 149 (MPa-m)
KJc (limit) (1T eq) 101.8 (MPa-m)
Ductile Crack Growth 0
(mm)
Valid Test?
Yes
- This record was final approved on 03/06/2025 08:39:24. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 A-6 WCAP-18909-NP March 2025 Revision 2 A.5 Specimen AY4-1 Test Date Date: 12/2/2023 Laboratory Westinghouse Specimen ID AY4-1 Material Type Weld Metal #W5214 Clip gauge type Outboard (Load-line)
Test Temperature - T
-134 (C)
Elastic Modulus - E at T 212 (GPa)
Yield Strength - YS at T 657 (MPa)
Tensile Strength - UTS at T 765(MPa)
Specimen Width - W 8.28 (mm)
Specimen Thickness - B 4.06 (mm)
Specimen Height - 2H 10.0 (mm)
Net Thickness - BN 4.06 (mm)
Final Crack Length - a0 4.32 (mm) a0/W 0.522 Fatigue Pre-cracking Final Kmax 15.6(MPa-m)
Number of fatigue cycles 55173 Loading Speed 0.3 (mm/min)
(Max a - Min a)/B 10%
Je 16.1 (kN/m)
Jp 13.5 (kN/m)
Jc 29.6 (kN/m)
KJc 83.1 (MPa-m)
KJc (1T eq) 59.9 (MPa-m)
KJc (limit) 142 (MPa-m)
KJc (limit) (1T eq) 97.3 (MPa-m)
Ductile Crack Growth 0
(mm)
Valid Test?
Yes
- This record was final approved on 03/06/2025 08:39:24. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 A-7 WCAP-18909-NP March 2025 Revision 2 A.6 Specimen AY4-2 Results from AY4-2 are not used in the T0 determination because the final pre-crack kmax value exceeded 15 MPam.
Test Date Date: 12/4/2023 Laboratory Westinghouse Specimen ID AY4-2 Material Type Weld Metal #W5214 Clip gauge type Outboard (Load-line)
Test Temperature - T
-134 (C)
Elastic Modulus - E at T 212 (GPa)
Yield Strength - YS at T 657 (MPa)
Tensile Strength - UTS at T 765(MPa)
Specimen Width - W 8.29 (mm)
Specimen Thickness - B 3.93 (mm)
Specimen Height - 2H 10.0 (mm)
Net Thickness - BN 3.93 (mm)
Final Crack Length - a0 4.54 (mm) a0/W 0.547 Fatigue Pre-cracking Final Kmax 17.6(MPa-m)
Number of fatigue cycles 53786 Loading Speed 0.3 (mm/min)
(Max a - Min a)/B 13%
Je 18.3 (kN/m)
Jp 14.8 (kN/m)
Jc 33.1 (kN/m)
KJc 87.9 (MPa-m)
KJc (1T eq) 62.6 (MPa-m)
KJc (limit) 138 (MPa-m)
KJc (limit) (1T eq) 94.3 (MPa-m)
Ductile Crack Growth 0
(mm)
Valid Test?
No high pre-crack Kmax
- This record was final approved on 03/06/2025 08:39:24. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 A-8 WCAP-18909-NP March 2025 Revision 2 A.7 Specimen AY4-3 Test Date Date: 12/4/2023 Laboratory Westinghouse Specimen ID AY4-3 Material Type Weld Metal #W5214 Clip gauge type Outboard (Load-line)
Test Temperature - T
-129 (C)
Elastic Modulus - E at T 212 (GPa)
Yield Strength - YS at T 641 (MPa)
Tensile Strength - UTS at T 749(MPa)
Specimen Width - W 8.33 (mm)
Specimen Thickness - B 4.15 (mm)
Specimen Height - 2H 10.0 (mm)
Net Thickness - BN 4.15 (mm)
Final Crack Length - a0 4.12 (mm) a0/W 0.495 Fatigue Pre-cracking Final Kmax 14.2(MPa-m)
Number of fatigue cycles 42699 Loading Speed 0.3 (mm/min)
(Max a - Min a)/B 7%
Je 7.0 (kN/m)
Jp 1.0 (kN/m)
Jc 8.0 (kN/m)
KJc 43.1 (MPa-m)
KJc (1T eq) 34.7 (MPa-m)
KJc (limit) 145 (MPa-m)
KJc (limit) (1T eq) 99.3 (MPa-m)
Ductile Crack Growth 0
(mm)
Valid Test?
Yes
- This record was final approved on 03/06/2025 08:39:24. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 A-9 WCAP-18909-NP March 2025 Revision 2 A.8 Specimen AY4-4 Test Date Date: 12/4/2023 Laboratory Westinghouse Specimen ID AY4-4 Material Type Weld Metal #W5214 Clip gauge type Outboard (Load-line)
Test Temperature - T
-129 (C)
Elastic Modulus - E at T 212 (GPa)
Yield Strength - YS at T 641 (MPa)
Tensile Strength - UTS at T 749(MPa)
Specimen Width - W 8.30 (mm)
Specimen Thickness - B 3.97 (mm)
Specimen Height - 2H 10.0 (mm)
Net Thickness - BN 3.97 (mm)
Final Crack Length - a0 4.30 (mm) a0/W 0.519 Fatigue Pre-cracking Final Kmax 15.9(MPa-m)
Number of fatigue cycles 49371 Loading Speed 0.3 (mm/min)
(Max a - Min a)/B 11%
Je 20.5 (kN/m)
Jp 58.6 (kN/m)
Jc 79.2 (kN/m)
KJc 135.8 (MPa-m)
KJc (1T eq) 92.8 (MPa-m)
KJc (limit) 141 (MPa-m)
KJc (limit) (1T eq) 96.1 (MPa-m)
Ductile Crack Growth 0.1 (mm)
Valid Test?
Yes
- This record was final approved on 03/06/2025 08:39:24. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 A-10 WCAP-18909-NP March 2025 Revision 2 A.9 Specimen AY5-1 Test Date Date: 12/2/2023 Laboratory Westinghouse Specimen ID AY5-1 Material Type Weld Metal #W5214 Clip gauge type Outboard (Load-line)
Test Temperature - T
-146 (C)
Elastic Modulus - E at T 213 (GPa)
Yield Strength - YS at T 692 (MPa)
Tensile Strength - UTS at T 800(MPa)
Specimen Width - W 8.41 (mm)
Specimen Thickness - B 4.12 (mm)
Specimen Height - 2H 10.0 (mm)
Net Thickness - BN 4.12 (mm)
Final Crack Length - a0 4.20 (mm) a0/W 0.500 Fatigue Pre-cracking Final Kmax 14.2(MPa-m)
Number of fatigue cycles 45462 Loading Speed 0.3 (mm/min)
(Max a - Min a)/B 8%
Je 13.9 (kN/m)
Jp 4.2 (kN/m)
Jc 18.1 (kN/m)
KJc 65.1 (MPa-m)
KJc (1T eq) 48.6 (MPa-m)
KJc (limit) 151.0 (MPa-m)
KJc (limit) (1T eq) 103.0 (MPa-m)
Ductile Crack Growth 0
(mm)
Valid Test?
Yes
- This record was final approved on 03/06/2025 08:39:24. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 A-11 WCAP-18909-NP March 2025 Revision 2 A.10 Specimen AY5-2 Test Date Date: 12/2/2023 Laboratory Westinghouse Specimen ID AY5-2 Material Type Weld Metal #W5214 Clip gauge type Outboard (Load-line)
Test Temperature - T
-148 (C)
Elastic Modulus - E at T 213 (GPa)
Yield Strength - YS at T 701 (MPa)
Tensile Strength - UTS at T 809(MPa)
Specimen Width - W 8.50 (mm)
Specimen Thickness - B 4.10 (mm)
Specimen Height - 2H 10.0 (mm)
Net Thickness - BN 4.10 (mm)
Final Crack Length - a0 4.23 (mm) a0/W 0.498 Fatigue Pre-cracking Final Kmax 14.4(MPa-m)
Number of fatigue cycles 68015 Loading Speed 0.3 (mm/min)
(Max a - Min a)/B 9%
Je 19.1 (kN/m)
Jp 20.1 (kN/m)
Jc 39.2 (kN/m)
KJc 95.8 (MPa-m)
KJc (1T eq) 68.0 (MPa-m)
KJc (limit) 153 (MPa-m)
KJc (limit) (1T eq) 104.2 (MPa-m)
Ductile Crack Growth 0
(mm)
Valid Test?
Yes
- This record was final approved on 03/06/2025 08:39:24. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 A-12 WCAP-18909-NP March 2025 Revision 2 A.11 Specimen AY5-3 Test Date Date: 12/2/2023 Laboratory Westinghouse Specimen ID AY5-3 Material Type Weld Metal #W5214 Clip gauge type Outboard (Load-line)
Test Temperature - T
-148 (C)
Elastic Modulus - E at T 213 (GPa)
Yield Strength - YS at T 701 (MPa)
Tensile Strength - UTS at T 809(MPa)
Specimen Width - W 8.39 (mm)
Specimen Thickness - B 4.03 (mm)
Specimen Height - 2H 10.0 (mm)
Net Thickness - BN 4.03 (mm)
Final Crack Length - a0 4.16 (mm) a0/W 0.496 Fatigue Pre-cracking Final Kmax 14.4(MPa-m)
Number of fatigue cycles 59127 Loading Speed 0.3 (mm/min)
(Max a - Min a)/B 8%
Je 21.6 (kN/m)
Jp 72.6 (kN/m)
Jc 94.2 (kN/m)
KJc 148.5 (MPa-m)
KJc (1T eq) 101.1 (MPa-m)
KJc (limit) 152 (MPa-m)
KJc (limit) (1T eq) 103.4 (MPa-m)
Ductile Crack Growth 0.12 (mm)
Valid Test?
Yes
- This record was final approved on 03/06/2025 08:39:24. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 A-13 WCAP-18909-NP March 2025 Revision 2 A.12 Specimen AY5-4 Test Date Date: 12/2/2023 Laboratory Westinghouse Specimen ID AY5-4 Material Type Weld Metal #W5214 Clip gauge type Outboard (Load-line)
Test Temperature - T
-148 (C)
Elastic Modulus - E at T 213 (GPa)
Yield Strength - YS at T 699 (MPa)
Tensile Strength - UTS at T 807(MPa)
Specimen Width - W 8.47 (mm)
Specimen Thickness - B 4.11 (mm)
Specimen Height - 2H 10.0 (mm)
Net Thickness - BN 4.11 (mm)
Final Crack Length - a0 4.29 (mm) a0/W 0.507 Fatigue Pre-cracking Final Kmax 14.8(MPa-m)
Number of fatigue cycles 50081 Loading Speed 0.3 (mm/min)
(Max a - Min a)/B 9%
Je 11.5 (kN/m)
Jp 2.3 (kN/m)
Jc 13.8 (kN/m)
KJc 56.8 (MPa-m)
KJc (1T eq) 43.3 (MPa-m)
KJc (limit) 151 (MPa-m)
KJc (limit) (1T eq) 103.1 (MPa-m)
Ductile Crack Growth 0
(mm)
Valid Test?
Yes
- This record was final approved on 03/06/2025 08:39:24. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 A-14 WCAP-18909-NP March 2025 Revision 2 A.13 Specimen AY6-1 Test Date Date: 12/2/2023 Laboratory Westinghouse Specimen ID AY6-1 Material Type Weld Metal #W5214 Clip gauge type Outboard (Load-line)
Test Temperature - T
-148 (C)
Elastic Modulus - E at T 213 (GPa)
Yield Strength - YS at T 701 (MPa)
Tensile Strength - UTS at T 809(MPa)
Specimen Width - W 8.33 (mm)
Specimen Thickness - B 4.10 (mm)
Specimen Height - 2H 10.0 (mm)
Net Thickness - BN 4.10 (mm)
Final Crack Length - a0 4.38 (mm) a0/W 0.526 Fatigue Pre-cracking Final Kmax 15.7(MPa-m)
Number of fatigue cycles 52804 Loading Speed 0.3 (mm/min)
(Max a - Min a)/B 13%
Je 6.7 (kN/m)
Jp 0.3 (kN/m)
Jc 7.0 (kN/m)
KJc 40.6 (MPa-m)
KJc (1T eq) 33.1 (MPa-m)
KJc (limit) 147 (MPa-m)
KJc (limit) (1T eq) 100.6 (MPa-m)
Ductile Crack Growth 0
(mm)
Valid Test?
Yes
- This record was final approved on 03/06/2025 08:39:24. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 A-15 WCAP-18909-NP March 2025 Revision 2 A.14 Specimen AY6-2 Test Date Date: 12/2/2023 Laboratory Westinghouse Specimen ID AY6-2 Material Type Weld Metal #W5214 Clip gauge type Outboard (Load-line)
Test Temperature - T
-140 (C)
Elastic Modulus - E at T 213 (GPa)
Yield Strength - YS at T 673 (MPa)
Tensile Strength - UTS at T 781(MPa)
Specimen Width - W 8.34 (mm)
Specimen Thickness - B 3.95 (mm)
Specimen Height - 2H 10.0 (mm)
Net Thickness - BN 3.95 (mm)
Final Crack Length - a0 4.19 (mm) a0/W 0.502 Fatigue Pre-cracking Final Kmax 14.9(MPa-m)
Number of fatigue cycles 55843 Loading Speed 0.3 (mm/min)
(Max a - Min a)/B 11%
Je 19.1 (kN/m)
Jp 22.1 (kN/m)
Jc 41.2 (kN/m)
KJc 98.1 (MPa-m)
KJc (1T eq) 69.1 (MPa-m)
KJc (limit) 148 (MPa-m)
KJc (limit) (1T eq) 100.1 (MPa-m)
Ductile Crack Growth 0
(mm)
Valid Test?
Yes
- This record was final approved on 03/06/2025 08:39:24. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 A-16 WCAP-18909-NP March 2025 Revision 2 A.15 Specimen AY6-3 Test Date Date: 12/2/2023 Laboratory Westinghouse Specimen ID AY6-3 Material Type Weld Metal #W5214 Clip gauge type Outboard (Load-line)
Test Temperature - T
-140 (C)
Elastic Modulus - E at T 213 (GPa)
Yield Strength - YS at T 673 (MPa)
Tensile Strength - UTS at T 781(MPa)
Specimen Width - W 8.39 (mm)
Specimen Thickness - B 4.15 (mm)
Specimen Height - 2H 10.0 (mm)
Net Thickness - BN 4.15 (mm)
Final Crack Length - a0 4.14 (mm) a0/W 0.494 Fatigue Pre-cracking Final Kmax 14.2(MPa-m)
Number of fatigue cycles 54088 Loading Speed 0.3 (mm/min)
(Max a - Min a)/B 7%
Je 11.3 (kN/m)
Jp 3.7 (kN/m)
Jc 14.9 (kN/m)
KJc 59.0 (MPa-m)
KJc (1T eq) 44.8 (MPa-m)
KJc (limit) 149 (MPa-m)
KJc (limit) (1T eq) 102.1 (MPa-m)
Ductile Crack Growth 0
(mm)
Valid Test?
Yes
- This record was final approved on 03/06/2025 08:39:24. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 A-17 WCAP-18909-NP March 2025 Revision 2 A.16 Specimen AY6-4 Test Date Date: 12/2/2023 Laboratory Westinghouse Specimen ID AY6-4 Material Type Weld Metal #W5214 Clip gauge type Outboard (Load-line)
Test Temperature - T
-137 (C)
Elastic Modulus - E at T 213 (GPa)
Yield Strength - YS at T 665 (MPa)
Tensile Strength - UTS at T 773(MPa)
Specimen Width - W 8.29 (mm)
Specimen Thickness - B 4.12 (mm)
Specimen Height - 2H 10.0 (mm)
Net Thickness - BN 4.12 (mm)
Final Crack Length - a0 4.29 (mm) a0/W 0.518 Fatigue Pre-cracking Final Kmax 15.5(MPa-m)
Number of fatigue cycles 63154 Loading Speed 0.3 (mm/min)
(Max a - Min a)/B 13%
Je 21.3 (kN/m)
Jp 42.4 (kN/m)
Jc 63.7 (kN/m)
KJc 122.0 (MPa-m)
KJc (1T eq) 84.7 (MPa-m)
KJc (limit) 144 (MPa-m)
KJc (limit) (1T eq) 98.6 (MPa-m)
Ductile Crack Growth 0
(mm)
Valid Test?
Yes
- This record was final approved on 03/06/2025 08:39:24. (This statement was added by the PRIME system upon its validation)
WCAP-18909-NP Revision 2 Non-Proprietary Class 3
- This page was added to the quality record by the PRIME system upon its validation and shall not be considered in the page numbering of this document.**
Approval Information Author Approval Lynch Donald Mar-04-2025 11:35:37 Verifier Approval Hall J Brian Mar-05-2025 11:28:19 Approver Approval Lyons John L Mar-05-2025 16:03:02 Hold to Release Approval Lynch Donald Mar-06-2025 08:39:24 Files approved on Mar-06-2025