ML061110180

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Enclosure 1 - Report ORNL/NRC/LTR-05/22, Results of Probabilistic Fracture Mechanics Analyses of Pressurized Thermal Shock Transients for Calvert Cliffs Nuclear Power Plant Using Favor 04.1
ML061110180
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Site: Calvert Cliffs  Constellation icon.png
Issue date: 04/21/2006
From: Dickson T, Matthew Kirk
- No Known Affiliation, NRC/RES/DFERR
To:
Oak Ridge, Office of Nuclear Regulatory Research
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ML061100526 List:
References
DE-AC05-00OR22725, DOE 1886-N665-6Y, Job Code Y6656 ORNL/NRC/LTR-05/22
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ORNL/NRC/LTR-05/22 Contract Program or Heavy-Section Steel Technology (HSST)

Program Project

Title:

Subject of this Document: Results of Probabilistic Fracture Mechanics Analyses of Pressurized Thermal Shock Transients for Calvert Cliffs Nuclear Power Plant using FAVOR 04.1 Type of Document: Letter Report Author(s): T. L. Dickson Date of Document: December 2005 Responsible NRC Individual M. T. EricksonKirk and NRC Office or Division Division of Engineering Technology, U.S. Nuclear Regulatory Commission Prepared for the U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Under Interagency Agreement DOE 1886-N665-6Y NRC JCN No. Y6656 OAK RIDGE NATIONAL LABORATORY Oak Ridge, Tennessee 37831-8056 managed by UT-BATTELLE, LLC.

for the U. S. DEPARTMENT OF ENERGY under Contract No. DE-AC05-00OR22725

ABSTRACT Information Systems Laboratories (ISL) transmitted thermal hydraulic data to Oak Ridge National Laboratory (ORNL) for 104 pressurized thermal shock (PTS) transients postulated for Calvert Cliffs nuclear power plant. The time-dependent thermal hydraulic data for each transient, which summarizes the downcomer conditions for a particular plant condition, were input into the 04.1 version of the FAVOR computer code where it was imposed on the inner wall surface of the reactor pressure vessel (RPV) as a boundary condition. Probabilistic fracture mechanics (PFM) analyses were performed on RPV beltline material models with neutron fluence maps corresponding to 32 and 60 effective full power years (EFPY). This letter report documents the results of these PFM analyses.

Introduction Information Systems Laboratories (ISL) transmitted thermal hydraulic data to Oak Ridge National Laboratory (ORNL) for 104 postulated pressurized thermal shock (PTS) transients for Calvert Cliffs Nuclear Power Plant. The thermal hydraulic data for each transient consist of time history pairs of convective heat transfer coefficient, pressure, and temperature of the coolant in contact with the internal surface of the reactor pressure vessel (RPV) wall. Reference [1] contains the details of the thermal hydraulic modeling considerations.

Based on previous experience, a transient for which the coolant temperature remains above 350 F will have a zero probability of cleavage fracture; therefore, PFM analyses were performed for only 72 of the 104 transients.

As instructed by the NRC staff, ORNL used the 04.1 version of FAVOR [2-3] to generate PFM solutions so as permit comparison with the most recent documented PFM solutions performed for Oconee, Beaver Valley, and Palisades nuclear power plants as part of the PTS re-evaluation program [4].

The PFM analyses were performed for Calvert Cliffs using RPV beltline material models with neutron fluence maps corresponding to 32 and 60 effective full power years (EFPY).

The neutron fluence maps were provided by Brookhaven National Laboratory (BNL).

The modeling and procedures used in generating these neutron fluence maps were based on the guidance provided in the NRC Draft Regulatory Guide DG-1053 [5]. The calculations were performed using the DORT discrete ordinates transport code [6] and the BUGLE-93 [7] forty-seven neutron group ENDF/B-VI nuclear cross sections and fission spectra.

The flaw-characterization data used as input to FAVOR were provided by Pacific Northwest National Laboratory (PNNL). The USNRC has supported research at PNNL that has resulted in the postulation of fabrication flaws based on the non-destructive and destructive examination of actual RPV material. Such measurements [8-10] have been used to characterize the number, size, and location of flaws in various types of weld and base metal used to fabricate vessels, thus providing a technical basis for the flaw data 2

which is critical input data into FAVOR analyses. These measurements have been supplemented by expert elicitation [11].

Figure A1 in Appendix A is a 360 degree rollout of the Calvert Cliffs RPV beltline illustrating that the RPV consists of 13 distinct major regions: 6 axial welds, 1 circumferential weld, and 6 plates.

Table A.1 in Appendix A specifies the major region embrittlement-related parameters.

Each of the 13 major regions are further subdivided into the number of subregions specified in Table A1 so as to accommodate the level of detail provided in the neutron fluence maps provided by BNL. The chemistry data were taken from the RVID database

[12]. The Eason and Wright irradiation shift model, as specified in Equation 84 of reference 2, was used to calculate the irradiation-induced Charpy-transition-temperature shift RTNDT .

Warm prestress was included in the PFM analysis.

PFM Analysis Results During the PTS re-evaluation [4], a post-processing step was executed (with the FAVPOST module) which combined the distributions of CPI and CPF (expressed in cracked RPVs and failed RPVs per transient event, respectively) generated during the PFM analysis for each transient with a distribution of the initiating frequency (expressed in events per reactor operating year) for each transient. The distribution of the initiating frequency for each transient is derived from specific plant system and human interaction considerations. The combined result, when integrated over all transients, is the frequency of crack initiation (FCI), expressed in cracked RPVs per reactor operating year and through wall crack frequency (TWCF), expressed in failed RPVs per reactor operating year. There were no transient initiating frequencies (in events per year) provided for Calvert Cliffs; therefore, the post-processing step discussed above was not possible.

Table 1 contains brief descriptive data of the transients and the results of the PFM analyses. It should be noted that the values of CPI and CPF in Table 1 are the mean values of the probability distributions generated during the Monte Carlo PFM analysis.

Table 2 provides the ranking of the transients sorted according to the magnitudes of the CPI and CPF at 32 and 60 EFPY (from table 1), respectively.

The combined contribution of transient sequence numbers 59, 60, and 78 account for approximately 75 and 99 % of the CPI and CPF, respectively. The precursor for each of these three transients is stuck open pressurizer safety relief valves (SRVs) that reclose late in the transient. The valve re-closing causes a repressurization of the primary pressure circuit to the SRV setpoint.

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References

1. W.C. Arcieri, R.M. Beaton, and C.D. Fletcher, RELAP5 Thermal Hydraulic Analysis to Support PTS Evaluations for the Calvert Cliffs Nuclear Power Plant, Information Systems Laboratory, Rockville, Maryland, July, 2005.
2. Williams, P. T., Dickson, T. L., and Yin, S., Fracture Analysis of Vessels - Oak Ridge, FAVOR, v04.1, Computer Code: Theory and Implementation of Algorithms, Methods, and Correlations, NUREG/CR-6854, ORNL/TM-2004/244, in review by the NRC.
3. Dickson, T. L., Williams, P. T., and Yin, S., Fracture Analysis of Vessels - Oak Ridge, FAVOR, v04.1, Computer Code: Users Guide, NUREG/CR-6855, ORNL/TM-2004/245, October 2004, in review by the NRC.
4. Dickson, T. L, and Yin, S., Electronic Archival of the Results of Pressurized Thermal Shock Analyses for Beaver Valley, Oconee, and Palisades Reactor Pressure vessels Generated with the 04.1 Version of FAVOR, Letter Report ORNL/NRC/LTR-04/18, October, 2004.
5. Office of Nuclear Regulatory Research, Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence, Draft Regulatory Guide DG-1053, U.S.

Nuclear Regulatory Commission, September 1999.

6. DORT, Two-Dimensional Discrete Ordinates Transport Code, RSIC Computer Code Collection, CCC-484, Oak Ridge National Laboratory, 1988.
7. D. T. Ingersoll, J. E. White, R. Q. Wright, H. T. Hunter, C. O. Slater, N. M. Greene, R. E.

MacFarlane, R. W. Roussin, Production and Testing of the VITAMIN-B6 Fine-Group and the BUGLE-93 Broad-Group Neutron/Photon Cross-section Libraries Derived from ENDF/B-VI Nuclear Data, ORNL-6795, NUREG/CR-6214, January 1995.

8. Schuster, G.J., Doctor, S.R., Crawford, S.L., and Pardini, A.F., 1998, Characterization of Flaws in U.S. Reactor Pressure Vessels: Density and Distribution of Flaw Indications in PVRUF, USNRC Report NUREG/CR-6471, Vol. 1, U.S. Nuclear Regulatory Commission, Washington, D.C.
9. Schuster, G.J., Doctor, S.R., and Heasler, P.G., 2000, Characterization of Flaws in U.S.

Reactor Pressure Vessels: Validation of Flaw Density and Distribution in the Weld Metal of the PVRUF Vessel, USNRC Report NUREG/CR-6471, Vol. 2, U.S. Nuclear Regulatory Commission, Washington, D.C.

10. Schuster, G.J., Doctor, S.R., Crawford, S.L., and Pardini, A.F., 1999, Characterization of Flaws in U.S. Reactor Pressure Vessels: Density and Distribution of Flaw Indications in the Shoreham Vessel, USNRC Report NUREG/CR-6471, Vol. 3, U.S. Nuclear Regulatory Commission, Washington, D.C.

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11. Jackson, D.A., and Abramson, L., 1999, Report on the Results of the Expert Judgment Process for the Generalized Flaw Size and Density Distribution for Domestic Reactor Pressure Vessels, U.S. Nuclear Regulatory Commission Office of Research, FY 2000-2001 Operating Milestone 1A1ACE.
12. RVID Reactor Vessel Integrity Database, NUREG-1511, U.S. Nuclear Regulatory Commission, December, 1994, NUREG-1511, Supplement 1, October, 1996; RVID Version 2.0, August, 1997.

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Table 1 Results of PFM analyses for Calvert Cliffs transients received from ISL 07-29-2005 Last Transient Sequence Included Lowest Last Lowest CPImean CPFmean CPImean CPFmean Brief P(t) number number in T(t) F T(t) F P(t) ksi @ 32 @ 32 @ 60 @ 60 Transient ksi analysis EFPY EFPY EFPY EFPY description 1 No 418.1 418.1 0.978 0.984 - - - -

1 2 Yes 281.6 281.6 0.636 0.646 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2 3 Yes 134.8 188.5 0.181 0.283 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.828 primary 3 4 Yes 94.4 101.3 0.138 0.181 2.19E-08 1.18E-10 1.01E-07 2.72E-09 side LOCA 4.00 primary 4 5 Yes 63.8 68.4 0.111 0.175 7.27E-06 1.98E-07 1.95E-05 1.13E-06 side LOCA 5.67 primary 5 6 Yes 60.7 60.7 0.090 0.136 1.39E-06 7.26E-09 4.67E-06 8.70E-08 side LOCA 8.00 primary 6 7 Yes 60.5 61.7 0.077 0.122 1.09E-07 1.42E-10 6.59E-07 2.67E-09 side LOCA 11.314 7 8 Yes 63.1 180.6 0.019 0.029 7.40E-08 2.34E-10 4.75E-07 2.56E-09 primary side LOCA 16.00 8 9 Yes 63.2 172.3 0.017 0.021 1.01E-06 8.20E-10 3.73E-06 7.61E-09 primary side LOCA 6

22.627 9 10 Yes 62.7 172.5 0.017 0.017 9.17E-07 8.91E-10 3.33E-06 7.96E-09 primary side LOCA 10 11 Yes 241.2 249.1 0.218 0.279 0.00E+00 0.00E+00 0.00E+00 0.00E+00 11 12 Yes 102.9 225.9 0.022 0.022 0.00E+00 0.00E+00 0.00E+00 0.00E+00 13 No 355.7 355.7 0.804 0.841 - - - -

14 No 483.4 524.1 0.953 2.228 - - - -

12 15 Yes 252.2 252.2 0.506 0.517 0.00E+00 0.00E+00 0.00E+00 0.00E+00 16 No 501.9 537.2 1.645 2.227 - - - -

17 No 502.3 538.1 1.492 2.304 - - - -

18 No 502.4 537.4 1.486 2.258 - - - -

19 No 495.7 542.2 1.924 2.244 - - - -

20 No 361.9 377.6 1.833 2.269 - - - -

21 No 482.9 542.2 1.924 2.168 - - - -

22 No 527 533.1 1.938 2.247 - - - -

13 23 Yes 245.4 245.4 0.786 0.786 0.00E+00 0.00E+00 0.00E+00 0.00E+00 14 24 Yes 195.9 195.9 0.492 0.513 0.00E+00 0.00E+00 0.00E+00 0.00E+00 25 No 459.3 541.1 1.78 2.424 - - - -

15 26 Yes 298.7 304.3 1.107 2.227 0.00E+00 0.00E+00 0.00E+00 0.00E+00 27 No 518.8 532.9 1.768 2.34 - - - -

28 No 491 509.2 1.116 1.304 - - - -

29 No 380.4 529.9 1.26 2.218 - - - -

16 30 Yes 244.3 244.3 0.451 0.47 0.00E+00 0.00E+00 0.00E+00 0.00E+00 17 31 Yes 106.9 115.6 0.152 0.19 0.00E+00 0.00E+00 0.00E+00 0.00E+00 32 No 410.7 523.8 0.655 2.264 - - - -

18 33 Yes 288.2 520.4 0.727 1.807 0.00E+00 0.00E+00 0.00E+00 0.00E+00 34 No 506.2 520.6 1.16 1.184 - - - -

35 No 491.1 525.7 1.176 1.185 - - - -

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19 36 Yes 357.5 357.5 0.832 0.843 0.00E+00 0.00E+00 0.00E+00 0.00E+00 20 37 Yes 266.3 266.3 0.48 0.516 0.00E+00 0.00E+00 0.00E+00 0.00E+00 21 38 Yes 217.8 218.2 0.458 0.494 0.00E+00 0.00E+00 0.00E+00 0.00E+00 39 No 356.6 531.2 0.573 2.328 - - - -

2 stuck open pressurizer 164.6 516.4 0.268 2.369 4.76E-07 4.71E-07 1.27E-06 1.25E-06 SRVs that 22 40 Yes reclose at 6000 seconds 41 No 421.9 421.9 1.924 2.269 - - - -

42 No 423.3 423.3 1.924 2.254 - - - -

23 43 Yes 247.1 247.1 0.778 0.834 0.00E+00 0.00E+00 0.00E+00 0.00E+00 24 44 Yes 188.6 188.6 0.492 0.516 0.00E+00 0.00E+00 0.00E+00 0.00E+00 45 No 363.3 367.3 1.793 2.248 - - - -

25 46 Yes 224.7 232 1.167 1.528 0.00E+00 0.00E+00 0.00E+00 0.00E+00 26 47 Yes 198.8 198.8 0.441 0.517 0.00E+00 0.00E+00 0.00E+00 0.00E+00 48 No 423.3 423.3 1.924 2.254 - - - -

27 49 Yes 177.9 177.9 0.487 0.51 0.00E+00 0.00E+00 0.00E+00 0.00E+00 28 50 Yes 70.1 70.1 0.385 0.636 0.00E+00 0.00E+00 0.00E+00 0.00E+00 29 51 Yes 65.3 65.3 0.169 0.279 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.828 primary 30 52 Yes 62.2 62.2 0.124 0.18 6.27E-07 4.78E-09 2.03E-06 5.76E-08 side LOCA from HZP 31 53 Yes 127.8 127.8 0.208 0.315 0.00E+00 0.00E+00 0.00E+00 0.00E+00 32 54 Yes 97.6 97.6 0.815 0.828 0.00E+00 0.00E+00 0.00E+00 0.00E+00 33 55 Yes 67.9 67.9 0.257 0.507 0.00E+00 0.00E+00 0.00E+00 0.00E+00 56 No 442.5 530.9 0.8 2.421 - - - -

34 57 Yes 67.4 67.4 0.184 0.458 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8

35 58 Yes 66.4 66.4 0.139 0.212 0.00E+00 0.00E+00 0.00E+00 0.00E+00 one stuck open pressurizer SRV that 134.7 307.6 0.257 2.372 8.28E-06 8.24E-06 1.73E-05 1.72E-05 36 59 Yes reclose at 6000 seconds from HZP 2 stuck open pressurizer SRVs that 91.1 270.7 0.139 2.341 3.02E-05 3.01E-05 5.43E-05 5.42E-05 reclose at 6000 37 60 Yes seconds from HZP 61 No 381.2 386.6 2.064 2.327 - - - -

62 No 381.2 386.6 2.064 2.327 - - - -

38 63 Yes 134.6 134.6 0.773 0.828 0.00E+00 0.00E+00 0.00E+00 0.00E+00 39 64 Yes 69.1 69.1 0.437 0.506 0.00E+00 0.00E+00 0.00E+00 0.00E+00 40 65 Yes 319.3 333 1.774 2.344 0.00E+00 0.00E+00 0.00E+00 0.00E+00 41 66 Yes 224.4 227.7 0.792 2.21 0.00E+00 0.00E+00 0.00E+00 0.00E+00 42 67 Yes 81.2 81.2 0.408 0.507 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.0 primary 43 68 Yes 60.5 60.9 0.096 0.174 7.17E-07 3.08E-09 2.41E-06 4.55E-08 side LOCA from HZP 5.657 primary 44 69 Yes 60.3 60.3 0.087 0.136 1.40E-06 1.55E-08 4.34E-06 8.05E-08 side LOCA from HZP 9

22.627 primary side 45 70 Yes 62.9 154.6 0.017 0.017 3.24E-07 1.00E-09 1.26E-06 4.18E-09 LOCA from HZP 46 71 Yes 70.1 70.1 0.385 0.636 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.00 primary 47 72 Yes 61 65 0.083 0.125 1.43E-07 1.50E-09 6.73E-07 7.20E-09 side LOCA from HZP 11.314 primary side 48 73 Yes 63 154.6 0.017 0.018 2.39E-06 1.82E-08 7.35E-06 1.09E-07 LOCA from HZP 16.00 primary 49 74 Yes 63.5 154.1 0.015 0.017 1.20E-06 5.40E-09 3.71E-06 3.77E-08 side LOCA from HZP 50 75 Yes 177.5 366.3 0.255 0.385 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2 stuck open pressurizer SRVs that 51 76 Yes 95.5 240.7 0.156 0.183 1.63E-07 2.79E-08 4.90E-07 1.38E-07 reclose at 6000 seconds from HZP 52 77 Yes 167.8 341.2 0.239 0.291 0.00E+00 0.00E+00 0.00E+00 0.00E+00 10

2 stuck open pressurizer 53 78 Yes 95.5 234.5 0.156 0.183 3.66E-05 3.66E-05 6.61E-05 6.60E-05 SRVs that reclose at 6000 seconds 54 79 Yes 133.8 253.8 0.182 0.182 0.00E+00 0.00E+00 0.00E+00 0.00E+00 55 80 Yes 133.8 260.7 0.182 0.182 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.828 primary 56 81 Yes 93.9 99.9 0.139 0.181 1.41E-09 8.78E-13 1.56E-08 1.49E-10 side LOCA 2.828 primary 57 82 Yes 86.7 86.7 0.152 0.181 3.38E-08 6.94E-10 1.35E-07 6.62E-09 side LOCA 3.347 primary 58 83 Yes 67.8 79.6 0.127 0.179 3.24E-06 2.00E-07 8.74E-06 1.14E-06 side LOCA 59 84 Yes 82.8 113.7 0.144 0.182 0.00E+00 0.00E+00 0.00E+00 0.00E+00 60 85 Yes 151.4 175.6 0.157 0.206 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.347 primary 61 87 Yes 81.1 81.1 0.121 0.179 4.22E-07 5.11E-09 1.40E-06 3.88E-08 side LOCA from HZP 2.366 primary 62 88 Yes 76.2 78.4 0.142 0.181 3.15E-10 1.79E-13 7.19E-09 1.76E-11 side LOCA from HZP 63 89 Yes 86.4 98.5 0.165 0.205 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.00 primary 64 91 Yes 60.5 61.8 0.078 0.116 1.06E-06 1.26E-08 3.52E-06 8.56E-08 side LOCA 3.347 primary 65 93 Yes 66.40 66.50 0.111 0.179 1.19E-07 1.54E-09 5.48E-07 3.30E-08 side LOCA 11

8.00 primary 66 94 Yes 43.00 43.20 0.088 0.129 7.51E-07 3.45E-09 2.63E-06 2.42E-08 side LOCA from HZP 3.347 primary 67 96 Yes 61.20 61.20 0.102 0.177 7.97E-07 1.12E-08 2.64E-06 1.01E-07 side LOCA from HZP 68 97 Yes 307.50 310.50 0.602 0.635 0.00E+00 0.00E+00 0.00E+00 0.00E+00 69 98 Yes 305.70 310.60 0.595 0.665 0.00E+00 0.00E+00 0.00E+00 0.00E+00 99 No 439.70 525.80 0.714 2.249 - - - -

100 No 353.40 353.40 0.336 0.337 - - - -

101 No 351.50 351.50 0.327 0.327 - - - -

70 102 Yes 287.50 313.40 0.668 0.781 0.00E+00 0.00E+00 0.00E+00 0.00E+00 71 103 Yes 287.50 316.80 0.668 0.747 0.00E+00 0.00E+00 0.00E+00 0.00E+00 72 104 Yes 282.50 533.50 0.670 2.397 0.00E+00 0.00E+00 0.00E+00 0.00E+00 12

Table 2 Ranking of transients by magnitude of CPI and CPF Transient sequence numbers CPI CPI CPF CPF Brief description of transient Rank Rank at Rank at 60 Rank at 32 Rank at 60 provided by ISL 32 EFPY EFPY EFPY EFPY 1 78 78 78 78 Sequence 78: two stuck open pressurizer SRVs that reclose at 6000 seconds 2 60 60 60 60 Sequence 60: two stuck open pressurizer SRVs that reclose at 6000 seconds from HZP Sequence 59: one stuck open pressurizer SRV that reclose at 6000 seconds from HZP 3 59 5 59 59 Sequence 5: 4.00 primary side LOCA Sequence 5: 4.00 primary side LOCA Sequence 59: one stuck open pressurizer SRV that reclose at 6000 seconds from HZP 4 5 59 40 40 Sequence 40: two stuck open pressurizer SRVs that reclose at 6000 seconds 5 83 83 83 83 Sequence 83: 3.347 primary side LOCA Sequence 73: 11.314 primary side LOCA from HZP 6 73 73 5 5 Sequence 5: 4.00 primary side LOCA Sequence 69: 5.657 primary side LOCA from HZP Sequence 6: 5.67 primary side LOCA 7 69 6 76 76 Sequence 76: two stuck open pressurizer SRVs that reclose at 6000 seconds from HZP Sequence 6: 5.67 primary side LOCA Sequence 69: 5.657 primary side LOCA from HZP 8 6 69 73 73 Sequence 73: 11.314 primary side LOCA from HZP Sequence 74: 16.00 primary side LOCA from HZP Sequence 9: 16.00 primary side LOCA Sequence 69: 5.657 primary side LOCA from HZP 9 74 9 69 96 Sequence 96: 3.347 primary side LOCA from HZP Sequence 91: 8.00 primary side LOCA Sequence 74: 16.00 primary side LOCA from HZP 10 91 74 91 6 Sequence 6: 5.67 primary side LOCA 13

Appendix A Figure A.1 - Calvert Cliffs Reactor Beltline 14

Table A.1 - Calvert Cliffs Beltline Major Region Embrittlement-Related Parameters max max neutron max neutron max Number of copper nickel phos RTNDT(u) fluence RTNDT fluence RTNDT Major Description Heat ID subregions @32 @ 32 @60 @ 60 Region EFPY(1) EFPY(2) EFPY(1) EFPY(2) 1019 n / 1019 n /

wt % wt % wt % (°F) cm2 (°F)

(°F) cm2 1 AXIAL WELD 3 - 203 A 55 0.18 0.72 0.015 -56 3.065 134.7 4.90 148.1 2 AXIAL WELD 3 - 203 B 55 0.18 0.72 0.015 -56 1.82 121.3 2.96 134.0 3 AXIAL WELD 3 - 203 C 55 0.18 0.72 0.015 -56 1.83 121.4 2.97 134.1 4 AXIAL WELD 2 - 203 A 86 0.22 0.83 0.010 -50 1.81 168.4 2.95 180.5 5 AXIAL WELD 2 - 203 B 86 0.22 0.83 0.010 -50 1.82 168.6 2.96 180.6 6 AXIAL WELD 2 - 203 C 86 0.22 0.83 0.010 -50 3.04 181.0 4.88 192.7 7 CIRC WELD 9 - 203 632 0.24 0.16 0.014 -80 3.20 62.0 5.13 74.5 8 Plate D7207 - 1 4345 0.13 0.54 0.010 10 3.22 139.8 5.15 154.1 9 Plate D7207 - 3 4345 0.11 0.53 0.008 -20 3.22 87.7 5.15 100.3 10 Plate D7207 - 2 5885 0.11 0.56 0.009 -10 3.22 102.4 5.15 115.8 11 Plate D7206 - 2 9288 0.12 0.64 0.011 -30 3.20 102.1 5.13 117.1 12 Plate D7206 - 3 6794 0.12 0.64 0.011 10 3.20 142.1 5.13 157.1 13 Plate D7206 - 1 6794 0.11 0.55 0.011 20 3.20 137.4 5.13 152.3 (1) maximum neutron fluence among all subregions in this major region (2) maximum RTNDT among all subregions in this major region - no margin term 15

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