Text

Westinghouse, Report LTR-REA-21-1-NP, Revision 1, St. Lucie Units 1 & 2 Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 2021
	ML21285A112
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Site:	Saint Lucie
Issue date:	05/26/2021
From:	; Florida Power & Light Co, Westinghouse
To:	; Office of Nuclear Reactor Regulation
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ML21285A106	List: L-2021-192, Subsequent Licensee Renewal Application, Revision 1, Appendix E, Applicant'S Environmental Report; L-2021-192, Westinghouse, Report LTR-REA-21-1-NP, Revision 1, St. Lucie Units 1 & 2 Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 2021; ML21285A107; ML21285A108; ML21285A109; ML21285A111;
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	L-2021-192
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St. Lucie Nuclear Plant Units 1 and 2 Dockets 50-335 and 50-389 L-2021-192 Enclosure 4 Enclosure 4 Non-proprietary Reference Documents and Redacted Versions of Proprietary Reference Documents (Public Version)

(Revision 1)

(16 Attachments)

(558 Total Pages, including cover sheets)

St. Lucie Nuclear Plant Units 1 and 2 Dockets 50-335 and 50-389 L-2021-192 Enclosure 4 Enclosure 4 Document List - Westinghouse Report LTR-REA-21-1-NP, Revision 1, St. Lucie Units 1 & 2 Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 2021 - Westinghouse Report LTR-REA-21-2-NP, Revision 1, St. Lucie Units 1 & 2 Subsequent License Renewal: Unit 2 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, June 7, 2021 - Westinghouse Report LTR-SDA-21-021-NP, Revision 2, St. Lucie Units 1&2 Subsequent License Renewal: Reactor Pressure Vessel Supports Assessment, September 15, 2021 - Westinghouse Report WCAP-18609-NP, Revision 2, St. Lucie Units 1 & 2 Subsequent License Renewal: Time-Limited Aging Analyses on Reactor Vessel Integrity, July 16, 2021 - Westinghouse Report LTR-SDA-II-20-32-NP, Revision 3, St. Lucie Units 1 & 2 Subsequent License Renewal: 80-Year Projected Transient Cycles, July 15, 2021 - Westinghouse Report LTR-SDA-II-20-31-NP, Rev. 3, St. Lucie Units 1

& 2 Subsequent License Renewal: Primary Equipment and Piping Environmentally Assisted Fatigue Evaluations, September 14, 2021 - BWXT Report MSLEF-SR-01-NP, Revision 0, St. Lucie Unit 1 Replacement Steam Generator Environmentally Assisted Fatigue Report (Non-Proprietary), July 16, 2021 - Framatome Document No. 86-9329647-000, St. Lucie SLR CUFen Evaluations Summary - Non Proprietary, July 15, 2021 - Structural Integrity Report No. 2001262.403, Revision 0, Summary of Fatigue Usage for Charging Nozzle at St. Lucie, Units 1 and 2 for Subsequent License Renewal, June 25, 2021 0 - Westinghouse Report WCAP-18617-NP, Revision 1, St. Lucie Units 1 & 2 Subsequent License Renewal: Technical Justification for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis, June 3, 2021 1 - Westinghouse Report LTR-SDA-20-097-NP, Revision 3, St. Lucie Units 1 & 2 Subsequent License Renewal: Alloy 600 Half Nozzle Repair Flaw Evaluation, September 15, 2021 2 - Westinghouse Report LTR-SDA-20-104-NP, Rev. 3, St. Lucie Units 1&2 Subsequent License Renewal: Evaluation of Time-Limited Aging Analysis of the Reactor Vessel Internals, September 14, 2021 3 - Westinghouse Report LTR-SDA-20-099-NP, Revision 2, St. Lucie Units 1&2 Subsequent License Renewal: Task 9E RCP Casing Code Case N-481 Evaluation, September 14, 2021

St. Lucie Nuclear Plant Units 1 and 2 Dockets 50-335 and 50-389 L-2021-192 Enclosure 4 4 - Structural Integrity Report No. 2001262.402, Revision 1, Flaw Tolerance Evaluation of St. Lucie Units 1 and 2 CASS Components for SLR, July 15, 2021 5 - Framatome Document No. 86-9329648-000, St. Lucie SLR Crack Growth Analysis Summary - Non Proprietary, July 2, 2021 6 - Structural Integrity Report No. 2001262.401, Revision 1, Flaw Tolerance Evaluation of St. Lucie, Units 1 and 2 Surge Line Using ASME Code,Section XI, Appendix L for Subsequent License Renewal, July 15, 2021

St. Lucie Nuclear Plant Units 1 and 2 Dockets 50-335 and 50-389 L-2021-192 Enclosure 4 Enclosure 4 Non-proprietary Reference Documents and Redacted Versions of Proprietary Reference Documents (Public Version)

Attachment 1 Westinghouse Report LTR-REA-21-1-NP, Revision 1, St. Lucie Units 1 & 2 Subsequent License Renewal:

Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 2021 (56 Total Pages, including cover sheets)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 14 of 53 Table 4-1 Fast Neutron (E > 1.0 MeV) Fluence Rate at the RPV Clad/Base Metal Interface Cycle Cumulative Fast Neutron (E > 1.0 MeV) Fluence Rate (n/cm2-s)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 1 1.05 1.05 2.48E+10 1.51E+10 1.46E+10 1.08E+10 1.47E+10 1.48E+10 2.48E+10 2.48E+10 2 0.74 1.79 2.48E+10 1.51E+10 1.46E+10 1.08E+10 1.47E+10 1.48E+10 2.48E+10 2.48E+10 3 0.69 2.48 2.48E+10 1.51E+10 1.46E+10 1.08E+10 1.47E+10 1.48E+10 2.48E+10 2.48E+10 4 1.22 3.70 2.48E+10 1.51E+10 1.46E+10 1.08E+10 1.47E+10 1.48E+10 2.48E+10 2.48E+10 5 1.12 4.82 2.54E+10 1.32E+10 1.11E+10 7.89E+09 1.12E+10 1.29E+10 2.55E+10 2.55E+10 6 1.36 6.18 3.58E+10 2.04E+10 1.70E+10 1.25E+10 1.72E+10 1.98E+10 3.58E+10 3.58E+10 7 1.05 7.22 3.58E+10 2.04E+10 1.70E+10 1.25E+10 1.72E+10 1.98E+10 3.58E+10 3.58E+10 8 1.18 8.41 3.58E+10 2.04E+10 1.70E+10 1.25E+10 1.72E+10 1.98E+10 3.58E+10 3.58E+10 9 1.29 9.70 3.58E+10 2.04E+10 1.70E+10 1.25E+10 1.72E+10 1.98E+10 3.58E+10 3.58E+10 10 1.31 11.01 1.89E+10 1.48E+10 1.72E+10 1.32E+10 1.73E+10 1.44E+10 1.89E+10 1.89E+10 11 1.21 12.22 1.60E+10 1.29E+10 1.83E+10 1.36E+10 1.83E+10 1.26E+10 1.60E+10 1.89E+10 12 1.27 13.48 1.99E+10 1.51E+10 2.01E+10 1.43E+10 2.04E+10 1.49E+10 2.00E+10 2.10E+10 13 1.14 14.62 1.69E+10 1.31E+10 1.73E+10 1.33E+10 1.75E+10 1.29E+10 1.69E+10 1.81E+10 14 1.18 15.80 1.85E+10 1.44E+10 1.73E+10 1.35E+10 1.74E+10 1.41E+10 1.85E+10 1.85E+10 15 1.62 17.42 2.26E+10 1.51E+10 1.26E+10 1.01E+10 1.25E+10 1.46E+10 2.27E+10 2.27E+10 16 1.44 18.86 2.27E+10 1.49E+10 1.47E+10 1.28E+10 1.47E+10 1.45E+10 2.27E+10 2.27E+10 17 1.39 20.26 1.88E+10 1.33E+10 1.22E+10 1.13E+10 1.22E+10 1.29E+10 1.88E+10 1.88E+10 18 1.40 21.66 2.11E+10 1.34E+10 1.28E+10 1.09E+10 1.29E+10 1.30E+10 2.11E+10 2.11E+10 19 1.42 23.08 2.00E+10 1.33E+10 1.25E+10 1.12E+10 1.26E+10 1.29E+10 1.99E+10 2.00E+10 20 1.27 24.35 2.16E+10 1.46E+10 1.23E+10 1.11E+10 1.23E+10 1.41E+10 2.13E+10 2.16E+10 21 1.38 25.73 2.18E+10 1.43E+10 1.13E+10 1.02E+10 1.14E+10 1.37E+10 2.16E+10 2.18E+10 22 1.35 27.08 2.40E+10 1.53E+10 1.14E+10 1.03E+10 1.15E+10 1.47E+10 2.39E+10 2.40E+10 23 1.31 28.39 2.38E+10 1.56E+10 1.31E+10 1.15E+10 1.32E+10 1.51E+10 2.37E+10 2.38E+10 24 1.29 29.67 2.81E+10 1.72E+10 1.57E+10 1.39E+10 1.60E+10 1.66E+10 2.81E+10 2.81E+10 25 1.33 31.00 3.16E+10 1.96E+10 1.58E+10 1.36E+10 1.59E+10 1.91E+10 3.18E+10 3.18E+10 26 1.33 32.33 3.13E+10 1.94E+10 1.68E+10 1.47E+10 1.69E+10 1.88E+10 3.13E+10 3.13E+10

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 15 of 53 Table 4-1 Fast Neutron (E > 1.0 MeV) Fluence Rate at the RPV Clad/Base Metal Interface Cycle Cumulative Fast Neutron (E > 1.0 MeV) Fluence Rate (n/cm2-s)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 27 1.30 33.64 2.96E+10 1.73E+10 1.29E+10 1.05E+10 1.32E+10 1.68E+10 2.97E+10 2.97E+10 28 1.30 34.94 2.59E+10 1.64E+10 1.42E+10 1.27E+10 1.41E+10 1.59E+10 2.59E+10 2.59E+10 29 1.37 36.31 2.89E+10 1.72E+10 1.34E+10 1.19E+10 1.35E+10 1.66E+10 2.90E+10 2.90E+10

[1]

30 1.35 37.66 2.83E+10 1.71E+10 1.41E+10 1.27E+10 1.43E+10 1.66E+10 2.83E+10 2.83E+10 Note(s):

1. Cycle 30 was the current operating cycle at the time the exposures reported in this table were determined. Values listed are based on the projected EFPY for this cycle.

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 16 of 53 Table 4-2 Fast Neutron (E > 1.0 MeV) Fluence at the RPV Clad/Base Metal Interface Cycle Cumulative Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 1 1.05 1.05 8.23E+17 5.01E+17 4.83E+17 3.57E+17 4.87E+17 4.92E+17 8.24E+17 8.24E+17 2 0.74 1.79 1.40E+18 8.53E+17 8.21E+17 6.07E+17 8.29E+17 8.36E+17 1.40E+18 1.40E+18 3 0.69 2.48 1.94E+18 1.18E+18 1.14E+18 8.42E+17 1.15E+18 1.16E+18 1.94E+18 1.94E+18 4 1.22 3.70 2.90E+18 1.77E+18 1.70E+18 1.26E+18 1.72E+18 1.73E+18 2.90E+18 2.90E+18 5 1.12 4.82 3.77E+18 2.22E+18 2.08E+18 1.53E+18 2.10E+18 2.18E+18 3.78E+18 3.78E+18 6 1.36 6.18 5.29E+18 3.08E+18 2.80E+18 2.06E+18 2.83E+18 3.01E+18 5.29E+18 5.29E+18 7 1.05 7.22 6.46E+18 3.75E+18 3.36E+18 2.47E+18 3.39E+18 3.66E+18 6.46E+18 6.46E+18 8 1.18 8.41 7.78E+18 4.50E+18 3.98E+18 2.93E+18 4.02E+18 4.39E+18 7.78E+18 7.78E+18 9 1.29 9.70 9.23E+18 5.32E+18 4.67E+18 3.44E+18 4.72E+18 5.19E+18 9.24E+18 9.24E+18 10 1.31 11.01 1.00E+19 5.93E+18 5.38E+18 3.98E+18 5.43E+18 5.78E+18 1.00E+19 1.00E+19 11 1.21 12.22 1.06E+19 6.42E+18 6.08E+18 4.50E+18 6.13E+18 6.26E+18 1.06E+19 1.06E+19 12 1.27 13.48 1.14E+19 7.01E+18 6.86E+18 5.06E+18 6.93E+18 6.84E+18 1.14E+19 1.14E+19 13 1.14 14.62 1.20E+19 7.49E+18 7.49E+18 5.54E+18 7.56E+18 7.31E+18 1.20E+19 1.20E+19 14 1.18 15.80 1.27E+19 8.02E+18 8.13E+18 6.04E+18 8.20E+18 7.83E+18 1.27E+19 1.27E+19 15 1.62 17.42 1.38E+19 8.80E+18 8.77E+18 6.56E+18 8.84E+18 8.58E+18 1.39E+19 1.39E+19 16 1.44 18.86 1.49E+19 9.47E+18 9.44E+18 7.14E+18 9.51E+18 9.24E+18 1.49E+19 1.49E+19 17 1.39 20.26 1.57E+19 1.01E+19 9.97E+18 7.64E+18 1.01E+19 9.81E+18 1.57E+19 1.57E+19 18 1.40 21.66 1.66E+19 1.07E+19 1.05E+19 8.12E+18 1.06E+19 1.04E+19 1.66E+19 1.66E+19 19 1.42 23.08 1.75E+19 1.12E+19 1.11E+19 8.62E+18 1.12E+19 1.10E+19 1.75E+19 1.75E+19 20 1.27 24.35 1.84E+19 1.18E+19 1.16E+19 9.06E+18 1.17E+19 1.15E+19 1.84E+19 1.84E+19 21 1.38 25.73 1.93E+19 1.25E+19 1.21E+19 9.51E+18 1.22E+19 1.21E+19 1.93E+19 1.93E+19 22 1.35 27.08 2.04E+19 1.31E+19 1.26E+19 9.95E+18 1.27E+19 1.27E+19 2.04E+19 2.04E+19 23 1.31 28.39 2.13E+19 1.37E+19 1.31E+19 1.04E+19 1.32E+19 1.34E+19 2.13E+19 2.13E+19 24 1.29 29.67 2.25E+19 1.44E+19 1.38E+19 1.10E+19 1.39E+19 1.40E+19 2.25E+19 2.25E+19 25 1.33 31.00 2.38E+19 1.53E+19 1.44E+19 1.16E+19 1.45E+19 1.48E+19 2.38E+19 2.38E+19 26 1.33 32.33 2.51E+19 1.61E+19 1.51E+19 1.22E+19 1.52E+19 1.56E+19 2.51E+19 2.51E+19

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 17 of 53 Table 4-2 Fast Neutron (E > 1.0 MeV) Fluence at the RPV Clad/Base Metal Interface Cycle Cumulative Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 27 1.30 33.64 2.63E+19 1.68E+19 1.57E+19 1.26E+19 1.58E+19 1.63E+19 2.63E+19 2.63E+19 28 1.30 34.94 2.74E+19 1.75E+19 1.62E+19 1.31E+19 1.64E+19 1.70E+19 2.74E+19 2.74E+19 29 1.37 36.31 2.87E+19 1.82E+19 1.68E+19 1.36E+19 1.69E+19 1.77E+19 2.87E+19 2.87E+19

[1]

30 1.35 37.66 2.99E+19 1.89E+19 1.74E+19 1.42E+19 1.75E+19 1.84E+19 2.99E+19 2.99E+19 Projections with no bias on the peripheral and re-entrant corner assembly relative powers

[2]

Future -- 42.00 3.38E+19 2.13E+19 1.93E+19 1.58E+19 1.94E+19 2.07E+19 3.38E+19 3.38E+19

[2]

Future -- 48.00 3.93E+19 2.45E+19 2.18E+19 1.81E+19 2.20E+19 2.38E+19 3.93E+19 3.93E+19

[2]

Future -- 54.00 4.48E+19 2.78E+19 2.44E+19 2.03E+19 2.45E+19 2.69E+19 4.48E+19 4.48E+19

[2]

Future -- 60.00 5.03E+19 3.10E+19 2.69E+19 2.25E+19 2.71E+19 3.01E+19 5.03E+19 5.03E+19 Future[2] -- 66.00 5.58E+19 3.43E+19 2.94E+19 2.48E+19 2.96E+19 3.32E+19 5.58E+19 5.58E+19

[2]

Future -- 72.00 6.12E+19 3.75E+19 3.20E+19 2.70E+19 3.22E+19 3.64E+19 6.12E+19 6.12E+19 Projections with a +10% bias on the peripheral and re-entrant corner assembly relative powers

[2]

Future -- 42.00 3.41E+19 2.15E+19 1.94E+19 1.60E+19 1.96E+19 2.09E+19 3.41E+19 3.41E+19

[2]

Future -- 48.00 4.01E+19 2.50E+19 2.22E+19 1.84E+19 2.23E+19 2.43E+19 4.01E+19 4.01E+19

[2]

Future -- 54.00 4.60E+19 2.85E+19 2.50E+19 2.08E+19 2.51E+19 2.76E+19 4.60E+19 4.60E+19

[2]

Future -- 60.00 5.19E+19 3.20E+19 2.77E+19 2.33E+19 2.79E+19 3.10E+19 5.19E+19 5.19E+19

[2]

Future -- 66.00 5.78E+19 3.55E+19 3.05E+19 2.57E+19 3.07E+19 3.44E+19 5.79E+19 5.79E+19

[2]

Future -- 72.00 6.38E+19 3.91E+19 3.33E+19 2.82E+19 3.34E+19 3.78E+19 6.38E+19 6.38E+19 Note(s):

1. Cycle 30 was the current operating cycle at the time the exposures reported in this table were determined. Values listed are based on the projected EFPY for this cycle.

2. Values beyond Cycle 30 are based on the average core power distributions and reactor operating conditions of Cycle 29 and are determined both with and without a 1.1 bias on the peripheral and re-entrant corner assembly relative powers.

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 18 of 53 Table 4-3 Iron Atom Displacement Rate at the RPV Clad/Base Metal Interface Cycle Cumulative Iron Atom Displacement Rate (dpa/s)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 1 1.05 1.05 3.93E-11 2.41E-11 2.30E-11 1.71E-11 2.32E-11 2.39E-11 3.92E-11 3.93E-11 2 0.74 1.79 3.93E-11 2.41E-11 2.30E-11 1.71E-11 2.32E-11 2.39E-11 3.92E-11 3.93E-11 3 0.69 2.48 3.93E-11 2.41E-11 2.30E-11 1.71E-11 2.32E-11 2.39E-11 3.92E-11 3.93E-11 4 1.22 3.70 3.93E-11 2.41E-11 2.30E-11 1.71E-11 2.32E-11 2.39E-11 3.92E-11 3.93E-11 5 1.12 4.82 4.02E-11 2.11E-11 1.75E-11 1.25E-11 1.77E-11 2.09E-11 4.01E-11 4.02E-11 6 1.36 6.18 5.46E-11 3.14E-11 2.60E-11 1.94E-11 2.63E-11 3.06E-11 5.45E-11 5.46E-11 7 1.05 7.22 5.46E-11 3.14E-11 2.60E-11 1.94E-11 2.63E-11 3.06E-11 5.45E-11 5.46E-11 8 1.18 8.41 5.46E-11 3.14E-11 2.60E-11 1.94E-11 2.63E-11 3.06E-11 5.45E-11 5.46E-11 9 1.29 9.70 5.46E-11 3.14E-11 2.60E-11 1.94E-11 2.63E-11 3.06E-11 5.45E-11 5.46E-11 10 1.31 11.01 2.89E-11 2.28E-11 2.63E-11 2.03E-11 2.64E-11 2.22E-11 2.88E-11 2.89E-11 11 1.21 12.22 2.45E-11 1.99E-11 2.79E-11 2.09E-11 2.80E-11 1.96E-11 2.44E-11 2.89E-11 12 1.27 13.48 3.04E-11 2.33E-11 3.07E-11 2.21E-11 3.10E-11 2.30E-11 3.04E-11 3.21E-11 13 1.14 14.62 2.58E-11 2.03E-11 2.65E-11 2.04E-11 2.67E-11 2.00E-11 2.58E-11 2.76E-11 14 1.18 15.80 2.83E-11 2.22E-11 2.64E-11 2.08E-11 2.66E-11 2.19E-11 2.83E-11 2.83E-11 15 1.62 17.42 3.47E-11 2.33E-11 1.93E-11 1.56E-11 1.91E-11 2.26E-11 3.46E-11 3.47E-11 16 1.44 18.86 3.47E-11 2.30E-11 2.24E-11 1.97E-11 2.26E-11 2.24E-11 3.46E-11 3.47E-11 17 1.39 20.26 2.88E-11 2.04E-11 1.86E-11 1.74E-11 1.87E-11 1.99E-11 2.87E-11 2.88E-11 18 1.40 21.66 3.22E-11 2.07E-11 1.96E-11 1.68E-11 1.97E-11 2.01E-11 3.22E-11 3.22E-11 19 1.42 23.08 3.06E-11 2.06E-11 1.91E-11 1.72E-11 1.94E-11 2.00E-11 3.04E-11 3.06E-11 20 1.27 24.35 3.30E-11 2.25E-11 1.89E-11 1.71E-11 1.88E-11 2.17E-11 3.25E-11 3.30E-11 21 1.38 25.73 3.33E-11 2.19E-11 1.74E-11 1.57E-11 1.75E-11 2.13E-11 3.29E-11 3.33E-11 22 1.35 27.08 3.67E-11 2.35E-11 1.75E-11 1.59E-11 1.76E-11 2.28E-11 3.65E-11 3.67E-11 23 1.31 28.39 3.64E-11 2.40E-11 2.01E-11 1.77E-11 2.03E-11 2.33E-11 3.62E-11 3.64E-11 24 1.29 29.67 4.30E-11 2.64E-11 2.40E-11 2.14E-11 2.45E-11 2.58E-11 4.28E-11 4.30E-11 25 1.33 31.00 4.84E-11 3.02E-11 2.42E-11 2.09E-11 2.43E-11 2.95E-11 4.84E-11 4.84E-11 26 1.33 32.33 4.78E-11 2.98E-11 2.57E-11 2.27E-11 2.59E-11 2.90E-11 4.77E-11 4.78E-11

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 19 of 53 Table 4-3 Iron Atom Displacement Rate at the RPV Clad/Base Metal Interface Cycle Cumulative Iron Atom Displacement Rate (dpa/s)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 27 1.30 33.64 4.52E-11 2.66E-11 1.98E-11 1.62E-11 2.02E-11 2.60E-11 4.52E-11 4.52E-11 28 1.30 34.94 3.97E-11 2.53E-11 2.18E-11 1.95E-11 2.16E-11 2.46E-11 3.96E-11 3.97E-11 29 1.37 36.31 4.42E-11 2.64E-11 2.06E-11 1.83E-11 2.07E-11 2.57E-11 4.41E-11 4.42E-11

[1]

30 1.35 37.66 4.32E-11 2.63E-11 2.16E-11 1.96E-11 2.19E-11 2.57E-11 4.31E-11 4.32E-11 Note(s):

1. Cycle 30 was the current operating cycle at the time the exposures reported in this table were determined. Values listed are based on the projected EFPY for this cycle.

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 20 of 53 Table 4-4 Iron Atom Displacements at the RPV Clad/Base Metal Interface Cycle Cumulative Iron Atom Displacements (dpa)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 1 1.05 1.05 1.30E-03 7.99E-04 7.63E-04 5.66E-04 7.69E-04 7.93E-04 1.30E-03 1.30E-03 2 0.74 1.79 2.21E-03 1.36E-03 1.30E-03 9.63E-04 1.31E-03 1.35E-03 2.21E-03 2.21E-03 3 0.69 2.48 3.07E-03 1.88E-03 1.80E-03 1.34E-03 1.81E-03 1.87E-03 3.06E-03 3.07E-03 4 1.22 3.70 4.59E-03 2.81E-03 2.68E-03 1.99E-03 2.71E-03 2.79E-03 4.58E-03 4.59E-03 5 1.12 4.82 5.98E-03 3.54E-03 3.29E-03 2.43E-03 3.32E-03 3.51E-03 5.97E-03 5.98E-03 6 1.36 6.18 8.29E-03 4.87E-03 4.39E-03 3.24E-03 4.43E-03 4.81E-03 8.27E-03 8.29E-03 7 1.05 7.22 1.01E-02 5.90E-03 5.24E-03 3.88E-03 5.29E-03 5.81E-03 1.00E-02 1.01E-02 8 1.18 8.41 1.21E-02 7.06E-03 6.20E-03 4.59E-03 6.26E-03 6.94E-03 1.21E-02 1.21E-02 9 1.29 9.70 1.43E-02 8.32E-03 7.25E-03 5.37E-03 7.32E-03 8.18E-03 1.43E-02 1.43E-02 10 1.31 11.01 1.55E-02 9.26E-03 8.34E-03 6.21E-03 8.41E-03 9.09E-03 1.54E-02 1.55E-02 11 1.21 12.22 1.64E-02 1.00E-02 9.40E-03 7.01E-03 9.48E-03 9.84E-03 1.64E-02 1.64E-02 12 1.27 13.48 1.76E-02 1.09E-02 1.06E-02 7.87E-03 1.07E-02 1.07E-02 1.76E-02 1.76E-02 13 1.14 14.62 1.85E-02 1.17E-02 1.16E-02 8.61E-03 1.17E-02 1.15E-02 1.85E-02 1.85E-02 14 1.18 15.80 1.96E-02 1.25E-02 1.25E-02 9.38E-03 1.26E-02 1.23E-02 1.95E-02 1.96E-02 15 1.62 17.42 2.14E-02 1.37E-02 1.35E-02 1.02E-02 1.36E-02 1.34E-02 2.13E-02 2.14E-02 16 1.44 18.86 2.29E-02 1.47E-02 1.45E-02 1.11E-02 1.46E-02 1.45E-02 2.29E-02 2.29E-02 17 1.39 20.26 2.42E-02 1.56E-02 1.54E-02 1.18E-02 1.55E-02 1.53E-02 2.41E-02 2.42E-02 18 1.40 21.66 2.56E-02 1.65E-02 1.62E-02 1.26E-02 1.63E-02 1.62E-02 2.56E-02 2.56E-02 19 1.42 23.08 2.70E-02 1.75E-02 1.71E-02 1.34E-02 1.72E-02 1.71E-02 2.69E-02 2.70E-02 20 1.27 24.35 2.83E-02 1.84E-02 1.78E-02 1.40E-02 1.80E-02 1.80E-02 2.82E-02 2.83E-02 21 1.38 25.73 2.98E-02 1.93E-02 1.86E-02 1.47E-02 1.87E-02 1.89E-02 2.97E-02 2.98E-02 22 1.35 27.08 3.13E-02 2.03E-02 1.93E-02 1.54E-02 1.95E-02 1.99E-02 3.12E-02 3.13E-02 23 1.31 28.39 3.28E-02 2.13E-02 2.02E-02 1.61E-02 2.03E-02 2.08E-02 3.27E-02 3.28E-02 24 1.29 29.67 3.46E-02 2.24E-02 2.11E-02 1.70E-02 2.13E-02 2.19E-02 3.45E-02 3.46E-02 25 1.33 31.00 3.66E-02 2.37E-02 2.22E-02 1.79E-02 2.23E-02 2.31E-02 3.65E-02 3.66E-02 26 1.33 32.33 3.86E-02 2.49E-02 2.32E-02 1.88E-02 2.34E-02 2.43E-02 3.85E-02 3.86E-02

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 21 of 53 Table 4-4 Iron Atom Displacements at the RPV Clad/Base Metal Interface Cycle Cumulative Iron Atom Displacements (dpa)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 27 1.30 33.64 4.05E-02 2.60E-02 2.41E-02 1.95E-02 2.42E-02 2.54E-02 4.03E-02 4.05E-02 28 1.30 34.94 4.21E-02 2.70E-02 2.49E-02 2.03E-02 2.51E-02 2.64E-02 4.20E-02 4.21E-02 29 1.37 36.31 4.40E-02 2.82E-02 2.58E-02 2.11E-02 2.60E-02 2.75E-02 4.39E-02 4.40E-02

[1]

30 1.35 37.66 4.59E-02 2.93E-02 2.68E-02 2.19E-02 2.70E-02 2.86E-02 4.57E-02 4.59E-02 Projections with no bias on the peripheral and re-entrant corner assembly relative powers

[2]

Future -- 42.00 5.19E-02 3.29E-02 2.96E-02 2.44E-02 2.98E-02 3.21E-02 5.18E-02 5.19E-02

[2]

Future -- 48.00 6.03E-02 3.79E-02 3.35E-02 2.79E-02 3.37E-02 3.70E-02 6.01E-02 6.03E-02

[2]

Future -- 54.00 6.87E-02 4.29E-02 3.74E-02 3.14E-02 3.76E-02 4.19E-02 6.85E-02 6.87E-02

[2]

Future -- 60.00 7.71E-02 4.79E-02 4.13E-02 3.48E-02 4.15E-02 4.67E-02 7.68E-02 7.71E-02 Future[2] -- 66.00 8.54E-02 5.30E-02 4.52E-02 3.83E-02 4.55E-02 5.16E-02 8.52E-02 8.54E-02

[2]

Future -- 72.00 9.38E-02 5.80E-02 4.91E-02 4.17E-02 4.94E-02 5.64E-02 9.35E-02 9.38E-02 Projections with a +10% bias on the peripheral and re-entrant corner assembly relative powers

[2]

Future -- 42.00 5.24E-02 3.32E-02 2.98E-02 2.47E-02 3.00E-02 3.24E-02 5.23E-02 5.24E-02

[2]

Future -- 48.00 6.15E-02 3.86E-02 3.41E-02 2.84E-02 3.43E-02 3.77E-02 6.13E-02 6.15E-02

[2]

Future -- 54.00 7.05E-02 4.40E-02 3.83E-02 3.22E-02 3.85E-02 4.29E-02 7.03E-02 7.05E-02

[2]

Future -- 60.00 7.96E-02 4.95E-02 4.26E-02 3.60E-02 4.28E-02 4.82E-02 7.93E-02 7.96E-02

[2]

Future -- 66.00 8.86E-02 5.49E-02 4.68E-02 3.97E-02 4.71E-02 5.34E-02 8.84E-02 8.86E-02

[2]

Future -- 72.00 9.77E-02 6.03E-02 5.11E-02 4.35E-02 5.13E-02 5.87E-02 9.74E-02 9.77E-02 Note(s):

1. Cycle 30 was the current operating cycle at the time the exposures reported in this table were determined. Values listed are based on the projected EFPY for this cycle.

2. Values beyond Cycle 30 are based on the average core power distributions and reactor operating conditions of Cycle 29 and are determined both with and without a 1.1 bias on the peripheral and re-entrant corner assembly relative powers.

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 22 of 53 Table 4-5 Fast Neutron (E > 1.0 MeV) Fluence at the RPV Welds and Shells Projections with no bias on the peripheral and re-entrant corner assembly relative powers Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

Material 37.66 EFPY[1] 42 EFPY 48 EFPY 54 EFPY Inlet-nozzle-to-upper-shell weld (lowest extent) 3.54E+16 3.97E+16 4.57E+16 5.16E+16 Outlet-nozzle-to-upper-shell weld (lowest extent) 3.94E+16 4.48E+16 5.23E+16 5.98E+16 Upper Shell 1.41E+18 1.60E+18 1.86E+18 2.12E+18 Upper-to-Middle-Shell Circumferential Weld 1.77E+18 2.01E+18 2.33E+18 2.66E+18 Middle Shell 2.99E+19 3.38E+19 3.93E+19 4.48E+19 Middle Shell Longitudinal Weld - 15° 1.89E+19 2.13E+19 2.45E+19 2.78E+19 Middle Shell Longitudinal Weld - 135° 1.42E+19 1.58E+19 1.81E+19 2.03E+19 Middle Shell Longitudinal Weld - 255° 1.84E+19 2.07E+19 2.38E+19 2.69E+19 Middle-to-Lower-Shell Circumferential Weld 2.96E+19 3.35E+19 3.89E+19 4.44E+19 Lower Shell 2.97E+19 3.36E+19 3.91E+19 4.45E+19 Lower Shell Longitudinal Weld - 15° 1.88E+19 2.11E+19 2.44E+19 2.76E+19 Lower Shell Longitudinal Weld - 135° 1.41E+19 1.57E+19 1.79E+19 2.02E+19 Lower Shell Longitudinal Weld - 255° 1.82E+19 2.05E+19 2.36E+19 2.68E+19 Lower-Shell-to-Bottom-Head Circumferential Weld 2.18E+16 2.45E+16 2.83E+16 3.21E+16 Projections with no bias on the peripheral and re-entrant corner assembly relative powers Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

Material 60 EFPY 66 EFPY 72 EFPY Inlet-nozzle-to-upper-shell weld (lowest extent) 5.76E+16 6.35E+16 6.95E+16 Outlet-nozzle-to-upper-shell weld (lowest extent) 6.73E+16 7.49E+16 8.24E+16 Upper Shell 2.39E+18 2.65E+18 2.91E+18 Upper-to-Middle-Shell Circumferential Weld 2.99E+18 3.32E+18 3.64E+18 Middle Shell 5.03E+19 5.58E+19 6.12E+19 Middle Shell Longitudinal Weld - 15° 3.10E+19 3.43E+19 3.75E+19 Middle Shell Longitudinal Weld - 135° 2.25E+19 2.48E+19 2.70E+19 Middle Shell Longitudinal Weld - 255° 3.01E+19 3.32E+19 3.64E+19 Middle-to-Lower-Shell Circumferential Weld 4.98E+19 5.52E+19 6.07E+19 Lower Shell 5.00E+19 5.55E+19 6.09E+19 Lower Shell Longitudinal Weld - 15° 3.08E+19 3.41E+19 3.73E+19 Lower Shell Longitudinal Weld - 135° 2.24E+19 2.46E+19 2.69E+19 Lower Shell Longitudinal Weld - 255° 2.99E+19 3.30E+19 3.61E+19 Lower-Shell-to-Bottom-Head Circumferential Weld 3.59E+16 3.97E+16 4.35E+16

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 23 of 53 Table 4-5 Fast Neutron (E > 1.0 MeV) Fluence at the RPV Welds and Shells Projections with a +10% bias on the peripheral and re-entrant corner assembly relative powers Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

Material 37.66 EFPY[1] 42 EFPY 48 EFPY 54 EFPY Inlet-nozzle-to-upper-shell weld (lowest extent) 3.54E+16 4.01E+16 4.66E+16 5.30E+16 Outlet-nozzle-to-upper-shell weld (lowest extent) 3.94E+16 4.51E+16 5.29E+16 6.08E+16 Upper Shell 1.41E+18 1.61E+18 1.89E+18 2.17E+18 Upper-to-Middle-Shell Circumferential Weld 1.77E+18 2.02E+18 2.37E+18 2.72E+18 Middle Shell 2.99E+19 3.41E+19 4.01E+19 4.60E+19 Middle Shell Longitudinal Weld - 15° 1.89E+19 2.15E+19 2.50E+19 2.85E+19 Middle Shell Longitudinal Weld - 135° 1.42E+19 1.60E+19 1.84E+19 2.08E+19 Middle Shell Longitudinal Weld - 255° 1.84E+19 2.09E+19 2.42E+19 2.76E+19 Middle-to-Lower-Shell Circumferential Weld 2.96E+19 3.38E+19 3.97E+19 4.56E+19 Lower Shell 2.97E+19 3.39E+19 3.99E+19 4.58E+19 Lower Shell Longitudinal Weld - 15° 1.88E+19 2.13E+19 2.48E+19 2.83E+19 Lower Shell Longitudinal Weld - 135° 1.41E+19 1.58E+19 1.83E+19 2.07E+19 Lower Shell Longitudinal Weld - 255° 1.82E+19 2.07E+19 2.41E+19 2.75E+19 Lower-Shell-to-Bottom-Head Circumferential Weld 2.18E+16 2.47E+16 2.89E+16 3.30E+16 Projections with a +10% bias on the peripheral and re-entrant corner assembly relative powers Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

Material 60 EFPY 66 EFPY 72 EFPY Inlet-nozzle-to-upper-shell weld (lowest extent) 5.95E+16 6.59E+16 7.24E+16 Outlet-nozzle-to-upper-shell weld (lowest extent) 6.87E+16 7.65E+16 8.44E+16 Upper Shell 2.45E+18 2.73E+18 3.01E+18 Upper-to-Middle-Shell Circumferential Weld 3.07E+18 3.42E+18 3.77E+18 Middle Shell 5.19E+19 5.79E+19 6.38E+19 Middle Shell Longitudinal Weld - 15° 3.20E+19 3.55E+19 3.91E+19 Middle Shell Longitudinal Weld - 135° 2.33E+19 2.57E+19 2.82E+19 Middle Shell Longitudinal Weld - 255° 3.10E+19 3.44E+19 3.78E+19 Middle-to-Lower-Shell Circumferential Weld 5.15E+19 5.73E+19 6.32E+19 Lower Shell 5.17E+19 5.76E+19 6.35E+19 Lower Shell Longitudinal Weld - 15° 3.18E+19 3.53E+19 3.88E+19 Lower Shell Longitudinal Weld - 135° 2.31E+19 2.56E+19 2.80E+19 Lower Shell Longitudinal Weld - 255° 3.08E+19 3.42E+19 3.76E+19 Lower-Shell-to-Bottom-Head Circumferential Weld 3.71E+16 4.12E+16 4.53E+16 Note(s):

1. Value listed is the projected EFPY at the end of Cycle 30.

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 24 of 53 Table 4-6 Iron Atom Displacements at the RPV Welds and Shells Projections with no bias on the peripheral and re-entrant corner assembly relative powers Iron Atom Displacements (dpa)

Material [1]

37.66 EFPY 42 EFPY 48 EFPY 54 EFPY Inlet-nozzle-to-upper-shell weld (lowest extent) 2.94E-04 3.29E-04 3.78E-04 4.26E-04 Outlet-nozzle-to-upper-shell weld (lowest extent) 3.39E-04 3.82E-04 4.42E-04 5.02E-04 Upper Shell 2.35E-03 2.67E-03 3.10E-03 3.54E-03 Upper-to-Middle-Shell Circumferential Weld 2.92E-03 3.31E-03 3.85E-03 4.38E-03 Middle Shell 4.59E-02 5.19E-02 6.03E-02 6.87E-02 Middle Shell Longitudinal Weld - 15° 2.93E-02 3.29E-02 3.79E-02 4.29E-02 Middle Shell Longitudinal Weld - 135° 2.19E-02 2.44E-02 2.79E-02 3.13E-02 Middle Shell Longitudinal Weld - 255° 2.86E-02 3.21E-02 3.70E-02 4.19E-02 Middle-to-Lower-Shell Circumferential Weld 4.55E-02 5.15E-02 5.98E-02 6.81E-02 Lower Shell 4.55E-02 5.16E-02 5.99E-02 6.83E-02 Lower Shell Longitudinal Weld - 15° 2.90E-02 3.26E-02 3.76E-02 4.26E-02 Lower Shell Longitudinal Weld - 135° 2.17E-02 2.42E-02 2.77E-02 3.11E-02 Lower Shell Longitudinal Weld - 255° 2.84E-02 3.19E-02 3.67E-02 4.15E-02 Lower-Shell-to-Bottom-Head Circumferential Weld 1.50E-04 1.69E-04 1.94E-04 2.20E-04 Projections with no bias on the peripheral and re-entrant corner assembly relative powers Iron Atom Displacements (dpa)

Material 60 EFPY 66 EFPY 72 EFPY Inlet-nozzle-to-upper-shell weld (lowest extent) 4.75E-04 5.23E-04 5.72E-04 Outlet-nozzle-to-upper-shell weld (lowest extent) 5.61E-04 6.21E-04 6.80E-04 Upper Shell 3.97E-03 4.41E-03 4.85E-03 Upper-to-Middle-Shell Circumferential Weld 4.92E-03 5.46E-03 6.00E-03 Middle Shell 7.70E-02 8.54E-02 9.38E-02 Middle Shell Longitudinal Weld - 15° 4.79E-02 5.29E-02 5.80E-02 Middle Shell Longitudinal Weld - 135° 3.48E-02 3.83E-02 4.17E-02 Middle Shell Longitudinal Weld - 255° 4.67E-02 5.16E-02 5.64E-02 Middle-to-Lower-Shell Circumferential Weld 7.64E-02 8.48E-02 9.31E-02 Lower Shell 7.66E-02 8.49E-02 9.33E-02 Lower Shell Longitudinal Weld - 15° 4.76E-02 5.26E-02 5.75E-02 Lower Shell Longitudinal Weld - 135° 3.45E-02 3.80E-02 4.14E-02 Lower Shell Longitudinal Weld - 255° 4.64E-02 5.12E-02 5.60E-02 Lower-Shell-to-Bottom-Head Circumferential Weld 2.45E-04 2.71E-04 2.96E-04

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 25 of 53 Table 4-6 Iron Atom Displacements at the RPV Welds and Shells Projections with a +10% bias on the peripheral and re-entrant corner assembly relative powers Iron Atom Displacements (dpa)

Material [1]

37.66 EFPY 42 EFPY 48 EFPY 54 EFPY Inlet-nozzle-to-upper-shell weld (lowest extent) 2.94E-04 3.32E-04 3.85E-04 4.38E-04 Outlet-nozzle-to-upper-shell weld (lowest extent) 3.39E-04 3.86E-04 4.51E-04 5.15E-04 Upper Shell 2.35E-03 2.69E-03 3.15E-03 3.62E-03 Upper-to-Middle-Shell Circumferential Weld 2.92E-03 3.33E-03 3.91E-03 4.49E-03 Middle Shell 4.59E-02 5.24E-02 6.15E-02 7.05E-02 Middle Shell Longitudinal Weld - 15° 2.93E-02 3.32E-02 3.86E-02 4.40E-02 Middle Shell Longitudinal Weld - 135° 2.19E-02 2.47E-02 2.84E-02 3.22E-02 Middle Shell Longitudinal Weld - 255° 2.86E-02 3.24E-02 3.77E-02 4.29E-02 Middle-to-Lower-Shell Circumferential Weld 4.55E-02 5.20E-02 6.10E-02 7.00E-02 Lower Shell 4.55E-02 5.21E-02 6.11E-02 7.01E-02 Lower Shell Longitudinal Weld - 15° 2.90E-02 3.29E-02 3.83E-02 4.37E-02 Lower Shell Longitudinal Weld - 135° 2.17E-02 2.44E-02 2.82E-02 3.19E-02 Lower Shell Longitudinal Weld - 255° 2.84E-02 3.22E-02 3.74E-02 4.26E-02 Lower-Shell-to-Bottom-Head Circumferential Weld 1.50E-04 1.70E-04 1.98E-04 2.26E-04 Projections with a +10% bias on the peripheral and re-entrant corner assembly relative powers Iron Atom Displacements (dpa)

Material 60 EFPY 66 EFPY 72 EFPY Inlet-nozzle-to-upper-shell weld (lowest extent) 4.90E-04 5.43E-04 5.96E-04 Outlet-nozzle-to-upper-shell weld (lowest extent) 5.80E-04 6.44E-04 7.09E-04 Upper Shell 4.08E-03 4.55E-03 5.01E-03 Upper-to-Middle-Shell Circumferential Weld 5.06E-03 5.64E-03 6.21E-03 Middle Shell 7.96E-02 8.86E-02 9.77E-02 Middle Shell Longitudinal Weld - 15° 4.95E-02 5.49E-02 6.03E-02 Middle Shell Longitudinal Weld - 135° 3.60E-02 3.97E-02 4.35E-02 Middle Shell Longitudinal Weld - 255° 4.82E-02 5.34E-02 5.87E-02 Middle-to-Lower-Shell Circumferential Weld 7.89E-02 8.79E-02 9.69E-02 Lower Shell 7.91E-02 8.81E-02 9.72E-02 Lower Shell Longitudinal Weld - 15° 4.91E-02 5.45E-02 5.99E-02 Lower Shell Longitudinal Weld - 135° 3.57E-02 3.95E-02 4.32E-02 Lower Shell Longitudinal Weld - 255° 4.78E-02 5.31E-02 5.83E-02 Lower-Shell-to-Bottom-Head Circumferential Weld 2.53E-04 2.81E-04 3.09E-04 Note(s):

1. Value listed is the projected EFPY at the end of Cycle 30.

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 26 of 53 4.2 Surveillance Capsules Neutron exposure data for the surveillance capsules are provided in Table 4-7 through Table 4-10. In particular, fast neutron (E > 1.0 MeV) fluence rates and fluences determined at the core midplane and geometric center of the surveillance capsules are provided in Table 4-7 and Table 4-8 as a function of irradiation time. Similar data in terms of iron atom displacement rates (dpa/s) and iron atom displacements (dpa) are provided in Table 4-9 and Table 4-10.

Lead factors for the surveillance capsules are provided in Table 4-11. The lead factor is defined as the ratio of the calculated neutron fluence at the geometric center of the surveillance capsule to the maximum fluence at the RPV clad/base metal interface.

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 27 of 53 Table 4-7 Fast Neutron (E > 1.0 MeV) Fluence Rate at the Geometric Center of the Surveillance Capsules Cycle Cumulative Fluence Rate (n/cm2-s)

Cycle Length Operating Time (EFPY) (EFPY) 7° 14° 1 1.05 1.05 3.42E+10 2.32E+10 2 0.74 1.79 3.42E+10 2.32E+10 3 0.69 2.48 3.42E+10 2.32E+10 4 1.22 3.70 3.42E+10 2.32E+10 5 1.12 4.82 3.10E+10 1.94E+10 6 1.36 6.18 4.18E+10 2.80E+10 7 1.05 7.22 4.18E+10 2.80E+10 8 1.18 8.41 4.18E+10 2.80E+10 9 1.29 9.70 4.18E+10 2.80E+10 10 1.31 11.01 2.38E+10 1.94E+10 11 1.21 12.22 1.85E+10 1.59E+10 12 1.27 13.48 2.34E+10 1.92E+10 13 1.14 14.62 1.95E+10 1.64E+10 14 1.18 15.80 2.22E+10 1.85E+10 15 1.62 17.42 2.84E+10 2.08E+10 16 1.44 18.86 2.83E+10 2.05E+10 17 1.39 20.26 2.43E+10 1.83E+10 18 1.40 21.66 2.60E+10 1.85E+10 19 1.42 23.08 2.50E+10 1.83E+10 20 1.27 24.35 2.70E+10 2.00E+10 21 1.38 25.73 2.72E+10 1.97E+10 22 1.35 27.08 2.99E+10 2.12E+10 23 1.31 28.39 2.98E+10 2.16E+10 24 1.29 29.67 3.42E+10 2.37E+10 25 1.33 31.00 3.96E+10 2.76E+10 26 1.33 32.33 3.88E+10 2.70E+10 27 1.30 33.64 3.57E+10 2.41E+10 28 1.30 34.94 3.22E+10 2.27E+10 29 1.37 36.31 3.51E+10 2.38E+10

[1]

30 1.35 37.66 3.46E+10 2.38E+10 Note(s):

1. Cycle 30 was the current operating cycle at the time the exposures reported in this table were determined. Values listed are based on the projected EFPY for this cycle.

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 28 of 53 Table 4-8 Fast Neutron (E > 1.0 MeV) Fluence at the Geometric Center of the Surveillance Capsules Cycle Cumulative Fluence (n/cm2)

Cycle Length Operating Time (EFPY) (EFPY) 7° 14° 1 1.05 1.05 1.14E+18 7.71E+17 2 0.74 1.79 1.93E+18 1.31E+18 3 0.69 2.48 2.68E+18 1.82E+18 4 1.22 3.70 4.00E+18 2.71E+18

[1]

5 1.12 4.82 5.09E+18 3.40E+18 6 1.36 6.18 6.88E+18 4.60E+18 7 1.05 7.22 8.27E+18 5.52E+18 8 1.18 8.41 9.83E+18 6.56E+18 9 1.29 9.70 1.15E+19 7.70E+18[2]

10 1.31 11.01 1.25E+19 8.50E+18 11 1.21 12.22 1.32E+19 9.11E+18 12 1.27 13.48 1.42E+19 9.88E+18 13 1.14 14.62 1.49E+19 1.05E+19 14 1.18 15.80 1.57E+19 1.12E+19 15 1.62 17.42 1.71E+19 1.22E+19[3]

16 1.44 18.86 1.84E+19 1.32E+19 17 1.39 20.26 1.95E+19 1.40E+19 18 1.40 21.66 2.06E+19 1.48E+19 19 1.42 23.08 2.18E+19 1.56E+19 20 1.27 24.35 2.28E+19 1.64E+19 21 1.38 25.73 2.40E+19 1.73E+19 22 1.35 27.08 2.53E+19 1.82E+19 23 1.31 28.39 2.65E+19 1.90E+19 24 1.29 29.67 2.79E+19 2.00E+19 25 1.33 31.00 2.96E+19 2.12E+19 26 1.33 32.33 3.12E+19 2.23E+19 27 1.30 33.64 3.27E+19 2.33E+19 28 1.30 34.94 3.40E+19 2.42E+19 29 1.37 36.31 3.55E+19 2.53E+19

[4]

30 1.35 37.66 3.70E+19 2.63E+19

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 29 of 53 Table 4-8 Fast Neutron (E > 1.0 MeV) Fluence at the Geometric Center of the Surveillance Capsules No bias on the peripheral and re-entrant corner assembly relative powers Cycle Cumulative Fluence (n/cm2)

Cycle Length Operating Time (EFPY) (EFPY) 7° 14°

[5]

Future -- 42.00 4.18E+19 2.95E+19 Future[5] -- 48.00 4.84E+19 3.41E+19

[5]

Future -- 54.00 5.51E+19 3.86E+19

[5]

Future -- 60.00 6.17E+19 4.31E+19

[5]

Future -- 66.00 6.84E+19 4.76E+19

[5]

Future -- 72.00 7.50E+19 5.21E+19

+10% bias on the peripheral and re-entrant corner assembly relative powers Cycle Cumulative Fluence (n/cm2)

Cycle Length Operating Time (EFPY) (EFPY) 7° 14°

[5]

Future -- 42.00 4.22E+19 2.98E+19 Future[5] -- 48.00 4.94E+19 3.47E+19

[5]

Future -- 54.00 5.66E+19 3.96E+19

[5]

Future -- 60.00 6.38E+19 4.45E+19

[5]

Future -- 66.00 7.10E+19 4.94E+19

[5]

Future -- 72.00 7.81E+19 5.42E+19 Note(s):

1. This value is applicable to Capsule 97.

2. This value is applicable to Capsule 104.

3. This value is applicable to Capsule 284.

4. Cycle 30 was the current operating cycle at the time the exposures reported in this table were determined. Values listed are based on the projected EFPY for this cycle.

5. Values beyond Cycle 30 are based on the average core power distributions and reactor operating conditions of Cycle 29 and are determined both with and without a 1.1 bias on the peripheral and re-entrant corner assembly relative powers.

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 30 of 53 Table 4-9 Iron Atom Displacement Rate at the Geometric Center of the Surveillance Capsules Cycle Cumulative Displacement Rate (dpa/s)

Cycle Length Operating Time (EFPY) (EFPY) 7° 14° 1 1.05 1.05 5.26E-11 3.58E-11 2 0.74 1.79 5.26E-11 3.58E-11 3 0.69 2.48 5.26E-11 3.58E-11 4 1.22 3.70 5.26E-11 3.58E-11 5 1.12 4.82 4.77E-11 3.00E-11 6 1.36 6.18 6.07E-11 4.09E-11 7 1.05 7.22 6.07E-11 4.09E-11 8 1.18 8.41 6.07E-11 4.09E-11 9 1.29 9.70 6.07E-11 4.09E-11 10 1.31 11.01 3.47E-11 2.84E-11 11 1.21 12.22 2.70E-11 2.34E-11 12 1.27 13.48 3.41E-11 2.83E-11 13 1.14 14.62 2.85E-11 2.41E-11 14 1.18 15.80 3.23E-11 2.71E-11 15 1.62 17.42 4.14E-11 3.04E-11 16 1.44 18.86 4.11E-11 3.01E-11 17 1.39 20.26 3.53E-11 2.68E-11 18 1.40 21.66 3.79E-11 2.71E-11 19 1.42 23.08 3.64E-11 2.69E-11 20 1.27 24.35 3.93E-11 2.92E-11 21 1.38 25.73 3.95E-11 2.88E-11 22 1.35 27.08 4.35E-11 3.10E-11 23 1.31 28.39 4.34E-11 3.15E-11 24 1.29 29.67 4.97E-11 3.47E-11 25 1.33 31.00 5.75E-11 4.03E-11 26 1.33 32.33 5.63E-11 3.95E-11 27 1.30 33.64 5.19E-11 3.53E-11 28 1.30 34.94 4.68E-11 3.33E-11 29 1.37 36.31 5.10E-11 3.49E-11

[1]

30 1.35 37.66 5.03E-11 3.48E-11 Note(s):

1. Cycle 30 was the current operating cycle at the time the exposures reported in this table were determined. Values listed are based on the projected EFPY for this cycle.

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 31 of 53 Table 4-10 Iron Atom Displacements at the Geometric Center of the Surveillance Capsules Cycle Cumulative Displacements (dpa)

Cycle Length Operating Time (EFPY) (EFPY) 7° 14° 1 1.05 1.05 1.74E-03 1.19E-03 2 0.74 1.79 2.96E-03 2.02E-03 3 0.69 2.48 4.11E-03 2.80E-03 4 1.22 3.70 6.14E-03 4.18E-03

[1]

5 1.12 4.82 7.82E-03 5.24E-03 6 1.36 6.18 1.04E-02 6.99E-03 7 1.05 7.22 1.24E-02 8.35E-03 8 1.18 8.41 1.47E-02 9.87E-03 9 1.29 9.70 1.72E-02 1.15E-02[2]

10 1.31 11.01 1.86E-02 1.27E-02 11 1.21 12.22 1.96E-02 1.36E-02 12 1.27 13.48 2.10E-02 1.47E-02 13 1.14 14.62 2.20E-02 1.56E-02 14 1.18 15.80 2.32E-02 1.66E-02 15 1.62 17.42 2.53E-02 1.82E-02[3]

16 1.44 18.86 2.72E-02 1.95E-02 17 1.39 20.26 2.88E-02 2.07E-02 18 1.40 21.66 3.04E-02 2.19E-02 19 1.42 23.08 3.21E-02 2.31E-02 20 1.27 24.35 3.37E-02 2.43E-02 21 1.38 25.73 3.54E-02 2.55E-02 22 1.35 27.08 3.72E-02 2.69E-02 23 1.31 28.39 3.90E-02 2.82E-02 24 1.29 29.67 4.10E-02 2.96E-02 25 1.33 31.00 4.34E-02 3.13E-02 26 1.33 32.33 4.58E-02 3.29E-02 27 1.30 33.64 4.79E-02 3.44E-02 28 1.30 34.94 4.99E-02 3.57E-02 29 1.37 36.31 5.21E-02 3.73E-02

[4]

30 1.35 37.66 5.42E-02 3.87E-02

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 32 of 53 Table 4-10 Iron Atom Displacements at the Geometric Center of the Surveillance Capsules No bias on the peripheral and re-entrant corner assembly relative powers Cycle Cumulative Displacements (dpa)

Cycle Length Operating Time (EFPY) (EFPY) 7° 14°

[5]

Future -- 42.00 6.12E-02 4.35E-02 Future[5] -- 48.00 7.09E-02 5.01E-02

[5]

Future -- 54.00 8.05E-02 5.67E-02

[5]

Future -- 60.00 9.02E-02 6.33E-02

[5]

Future -- 66.00 9.98E-02 6.99E-02

[5]

Future -- 72.00 1.09E-01 7.66E-02

+10% bias on the peripheral and re-entrant corner assembly relative powers Cycle Cumulative Displacements (dpa)

Cycle Length Operating Time (EFPY) (EFPY) 7° 14°

[5]

Future -- 42.00 6.18E-02 4.39E-02 Future[5] -- 48.00 7.22E-02 5.11E-02

[5]

Future -- 54.00 8.27E-02 5.82E-02

[5]

Future -- 60.00 9.31E-02 6.54E-02

[5]

Future -- 66.00 1.04E-01 7.25E-02

[5]

Future -- 72.00 1.14E-01 7.97E-02 Note(s):

1. This value is applicable to Capsule 97.

2. This value is applicable to Capsule 104.

3. This value is applicable to Capsule 284.

4. Cycle 30 was the current operating cycle at the time the exposures reported in this table were determined. Values listed are based on the projected EFPY for this cycle.

5. Values beyond Cycle 30 are based on the average core power distributions and reactor operating conditions of Cycle 29 and are determined both with and without a 1.1 bias on the peripheral and re-entrant corner assembly relative powers.

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 33 of 53 Table 4-11 Surveillance Capsule Lead Factors Cycle Cumulative Lead Factor Cycle Length Operating Time (EFPY) (EFPY) 7° 14° 1 1.05 1.05 1.38 0.94 2 0.74 1.79 1.38 0.94 3 0.69 2.48 1.38 0.94 4 1.22 3.70 1.38 0.94

[1]

5 1.12 4.82 1.35 0.90 6 1.36 6.18 1.30 0.87 7 1.05 7.22 1.28 0.85 8 1.18 8.41 1.26 0.84 9 1.29 9.70 1.25 0.83[2]

10 1.31 11.01 1.25 0.85 11 1.21 12.22 1.25 0.86 12 1.27 13.48 1.24 0.87 13 1.14 14.62 1.24 0.87 14 1.18 15.80 1.23 0.88 15 1.62 17.42 1.24 0.88[3]

16 1.44 18.86 1.24 0.88 17 1.39 20.26 1.24 0.89 18 1.40 21.66 1.24 0.89 19 1.42 23.08 1.24 0.89 20 1.27 24.35 1.24 0.89 21 1.38 25.73 1.24 0.89 22 1.35 27.08 1.24 0.89 23 1.31 28.39 1.24 0.89 24 1.29 29.67 1.24 0.89 25 1.33 31.00 1.24 0.89 26 1.33 32.33 1.24 0.89 27 1.30 33.64 1.24 0.88 28 1.30 34.94 1.24 0.88 29 1.37 36.31 1.24 0.88

[4]

30 1.35 37.66 1.24 0.88

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 34 of 53 Table 4-11 Surveillance Capsule Lead Factors No bias on the peripheral and re-entrant corner assembly relative powers Cycle Cumulative Lead Factor Cycle Length Operating Time (EFPY) (EFPY) 7° 14° Future[5] -- 42.00 1.24 0.87 Future[5] -- 48.00 1.23 0.87

[5]

Future -- 54.00 1.23 0.86 Future[5] -- 60.00 1.23 0.86

[5]

Future -- 66.00 1.23 0.85

[5]

Future -- 72.00 1.22 0.85

+10% bias on the peripheral and re-entrant corner assembly relative powers Cycle Cumulative Lead Factor Cycle Length Operating Time (EFPY) (EFPY) 7° 14° Future[5] -- 42.00 1.24 0.87 Future[5] -- 48.00 1.23 0.87 Future[5] -- 54.00 1.23 0.86 Future[5] -- 60.00 1.23 0.86

[5]

Future -- 66.00 1.23 0.85

[5]

Future -- 72.00 1.23 0.85 Note(s):

1. This value is applicable to Capsule 97.

2. This value is applicable to Capsule 104

3. This value is applicable to Capsule 284.

4. Cycle 30 was the current operating cycle at the time the lead factors reported in this table were determined. Values listed are based on the projected EFPY for this cycle.

5. Values beyond Cycle 30 are based on the average core power distributions and reactor operating conditions of Cycle 29 and are determined both with and without a 1.1 bias on the peripheral and re-entrant corner assembly relative powers.

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 35 of 53 4.3 RPV Support Structure Neutron exposure data for the RPV support structure are provided in Table 4-12 through Table 4-20. In particular:

x Table 4-12 provides the maximum neutron exposures, expressed as fast neutron (E > 1.0 MeV and E > 0.1 MeV) fluences and iron atom displacements (all energies and E > 0.1 MeV), at the RPV support structure. Note that each value reported in Table 4-12 was determined at the RPV support structure inner surface, 0° azimuth, and axial elevation where the maximum exposure occurred.

x Table 4-13 and Table 4-14 provide fast neutron (E > 1.0 MeV) fluence projections at the RPV support structure as a function of height. Note that each fluence value reported in Table 4-13 and Table 4-14 was determined at the RPV support structure inner surface, 0° azimuth, and axial elevation indicated.

x Table 4-15 and Table 4-16 provide fast neutron (E > 0.1 MeV) fluence projections at the RPV support structure as a function of height. Note that each fluence value reported in Table 4-15 and Table 4-16 was determined at the RPV support structure inner surface, 0° azimuth, and axial elevation indicated.

x Table 4-17 and Table 4-18 provide iron atom displacement (all energies) projections at the RPV support structure as a function of height. Note that each displacement value reported in Table 4-17 and Table 4-18 was determined at the RPV support structure inner surface, 0° azimuth, and axial elevation indicated.

x Table 4-19 and Table 4-20 provide iron atom displacement (E > 0.1 MeV) projections at the RPV support structure as a function of height. Note that each displacement value reported in Table 4-19 and Table 4-20 was determined at the RPV support structure inner surface, 0° azimuth, and axial elevation indicated.

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 36 of 53 Table 4-12 Maximum Neutron Exposures at the RPV Support Structure Cycle Cumulative Fast Neutron Fluence Iron Atom Displacements Cycle Length Operating Time (n/cm2) (dpa)

(EFPY) (EFPY) E > 1.0 MeV E > 0.1 MeV All Energies E > 0.1 MeV 1 1.05 1.05 3.49E+16 5.00E+17 1.58E-04 1.44E-04 2 0.74 1.79 5.93E+16 8.49E+17 2.68E-04 2.45E-04 3 0.69 2.48 8.22E+16 1.18E+18 3.72E-04 3.39E-04 4 1.22 3.70 1.23E+17 1.76E+18 5.56E-04 5.07E-04 5 1.12 4.82 1.59E+17 2.27E+18 7.19E-04 6.55E-04 6 1.36 6.18 2.21E+17 3.01E+18 9.61E-04 8.78E-04 7 1.05 7.22 2.69E+17 3.58E+18 1.15E-03 1.05E-03 8 1.18 8.41 3.24E+17 4.22E+18 1.36E-03 1.24E-03 9 1.29 9.70 3.83E+17 4.93E+18 1.59E-03 1.46E-03 10 1.31 11.01 4.18E+17 5.35E+18 1.73E-03 1.59E-03 11 1.21 12.22 4.45E+17 5.68E+18 1.84E-03 1.68E-03 12 1.27 13.48 4.77E+17 6.07E+18 1.96E-03 1.80E-03 13 1.14 14.62 5.03E+17 6.38E+18 2.06E-03 1.89E-03 14 1.18 15.80 5.33E+17 6.72E+18 2.17E-03 1.99E-03 15 1.62 17.42 5.83E+17 7.30E+18 2.36E-03 2.17E-03 16 1.44 18.86 6.27E+17 7.83E+18 2.54E-03 2.33E-03 17 1.39 20.26 6.64E+17 8.28E+18 2.68E-03 2.46E-03 18 1.40 21.66 7.04E+17 8.76E+18 2.84E-03 2.61E-03 19 1.42 23.08 7.43E+17 9.24E+18 3.00E-03 2.75E-03 20 1.27 24.35 7.81E+17 9.69E+18 3.15E-03 2.89E-03 21 1.38 25.73 8.22E+17 1.02E+19 3.31E-03 3.04E-03 22 1.35 27.08 8.66E+17 1.07E+19 3.48E-03 3.20E-03 23 1.31 28.39 9.08E+17 1.12E+19 3.65E-03 3.35E-03 24 1.29 29.67 9.57E+17 1.18E+19 3.84E-03 3.53E-03 25 1.33 31.00 1.01E+18 1.25E+19 4.06E-03 3.73E-03 26 1.33 32.33 1.07E+18 1.32E+19 4.28E-03 3.93E-03 27 1.30 33.64 1.12E+18 1.38E+19 4.48E-03 4.12E-03 28 1.30 34.94 1.17E+18 1.43E+19 4.66E-03 4.28E-03 29 1.37 36.31 1.22E+18 1.50E+19 4.87E-03 4.47E-03

[1]

30 1.35 37.66 1.27E+18 1.56E+19 5.07E-03 4.66E-03

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 37 of 53 Table 4-12 Maximum Neutron Exposures at the RPV Support Structure Cycle Cumulative Fast Neutron Fluence Iron Atom Displacements Cycle Length Operating Time (n/cm2) (dpa)

(EFPY) (EFPY) E > 1.0 MeV E > 0.1 MeV All Energies E > 0.1 MeV Projections with no bias on the peripheral and re-entrant corner assembly relative powers

[2]

Future -- 42.00 1.44E+18 1.76E+19 5.72E-03 5.26E-03

[2]

Future -- 48.00 1.67E+18 2.03E+19 6.63E-03 6.09E-03

[2]

Future -- 54.00 1.90E+18 2.31E+19 7.53E-03 6.93E-03 Future[2] -- 60.00 2.13E+18 2.58E+19 8.43E-03 7.76E-03

[2]

Future -- 66.00 2.37E+18 2.86E+19 9.34E-03 8.59E-03

[2]

Future -- 72.00 2.60E+18 3.14E+19 1.02E-02 9.42E-03 Projections with a +10% bias on the peripheral and re-entrant corner assembly relative powers

[2]

Future -- 42.00 1.45E+18 1.77E+19 5.78E-03 5.31E-03

[2]

Future -- 48.00 1.70E+18 2.07E+19 6.76E-03 6.22E-03

[2]

Future -- 54.00 1.95E+18 2.37E+19 7.74E-03 7.12E-03

[2]

Future -- 60.00 2.20E+18 2.67E+19 8.72E-03 8.02E-03

[2]

Future -- 66.00 2.45E+18 2.97E+19 9.70E-03 8.92E-03

[2]

Future -- 72.00 2.71E+18 3.27E+19 1.07E-02 9.83E-03 Note(s):

1. Cycle 30 was the current operating cycle at the time the exposures reported in this table were determined. Values listed are based on the projected EFPY for this cycle.

2. Values beyond Cycle 30 are based on the average core power distributions and reactor operating conditions of Cycle 29 and are determined both with and without a 1.1 bias on the peripheral and re-entrant corner assembly relative powers.

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 38 of 53 Table 4-13 Fast Neutron (E > 1.0 MeV) Fluence at the RPV Support Structure -

No Bias on the Peripheral and Re-Entrant Corner Assembly Relative Powers Elevation[1] Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

(cm) 37.66 EFPY[2] 42 EFPY 48 EFPY 54 EFPY 60 EFPY 66 EFPY 72 EFPY

[3]

218.81 9.90E+16 1.12E+17 1.31E+17 1.49E+17 1.67E+17 1.85E+17 2.04E+17 213.36 1.26E+17 1.43E+17 1.66E+17 1.90E+17 2.13E+17 2.36E+17 2.60E+17 198.12 2.22E+17 2.52E+17 2.94E+17 3.36E+17 3.77E+17 4.19E+17 4.60E+17 182.88 3.52E+17 4.00E+17 4.67E+17 5.34E+17 6.00E+17 6.67E+17 7.33E+17 167.64 5.22E+17 5.94E+17 6.93E+17 7.92E+17 8.91E+17 9.90E+17 1.09E+18 152.40 7.09E+17 8.06E+17 9.40E+17 1.07E+18 1.21E+18 1.34E+18 1.48E+18 137.16 8.83E+17 1.00E+18 1.17E+18 1.34E+18 1.50E+18 1.67E+18 1.83E+18 121.92 1.03E+18 1.17E+18 1.36E+18 1.55E+18 1.74E+18 1.93E+18 2.12E+18 106.68 1.13E+18 1.28E+18 1.49E+18 1.70E+18 1.91E+18 2.12E+18 2.32E+18 91.44 1.20E+18 1.36E+18 1.58E+18 1.80E+18 2.02E+18 2.25E+18 2.47E+18 76.20 1.23E+18 1.39E+18 1.61E+18 1.84E+18 2.06E+18 2.28E+18 2.51E+18 60.96 1.25E+18 1.42E+18 1.65E+18 1.88E+18 2.10E+18 2.33E+18 2.56E+18 45.72 1.26E+18 1.43E+18 1.66E+18 1.89E+18 2.11E+18 2.34E+18 2.57E+18 30.48 1.26E+18 1.43E+18 1.66E+18 1.88E+18 2.11E+18 2.34E+18 2.57E+18 15.24 1.25E+18 1.42E+18 1.65E+18 1.88E+18 2.10E+18 2.33E+18 2.56E+18 0.00 1.26E+18 1.42E+18 1.65E+18 1.88E+18 2.11E+18 2.34E+18 2.57E+18

-15.24 1.26E+18 1.43E+18 1.66E+18 1.89E+18 2.12E+18 2.35E+18 2.58E+18

-30.48 1.27E+18 1.44E+18 1.67E+18 1.90E+18 2.13E+18 2.36E+18 2.60E+18

-45.72 1.27E+18 1.44E+18 1.67E+18 1.90E+18 2.13E+18 2.36E+18 2.59E+18

-60.96 1.26E+18 1.43E+18 1.66E+18 1.89E+18 2.12E+18 2.35E+18 2.58E+18

-76.20 1.24E+18 1.41E+18 1.64E+18 1.86E+18 2.09E+18 2.32E+18 2.55E+18

-91.44 1.21E+18 1.37E+18 1.59E+18 1.82E+18 2.04E+18 2.26E+18 2.48E+18

-106.68 1.15E+18 1.30E+18 1.51E+18 1.72E+18 1.94E+18 2.15E+18 2.36E+18

-121.92 1.05E+18 1.19E+18 1.38E+18 1.58E+18 1.77E+18 1.97E+18 2.16E+18

-137.16 9.10E+17 1.03E+18 1.20E+18 1.37E+18 1.54E+18 1.71E+18 1.89E+18

-152.40 7.40E+17 8.41E+17 9.80E+17 1.12E+18 1.26E+18 1.40E+18 1.54E+18

-167.64 5.51E+17 6.26E+17 7.30E+17 8.35E+17 9.39E+17 1.04E+18 1.15E+18

-182.88 3.74E+17 4.25E+17 4.95E+17 5.66E+17 6.37E+17 7.07E+17 7.78E+17

-198.12 2.33E+17 2.65E+17 3.09E+17 3.53E+17 3.97E+17 4.40E+17 4.84E+17

-213.36 1.39E+17 1.58E+17 1.84E+17 2.10E+17 2.36E+17 2.61E+17 2.87E+17

-228.60 8.41E+16 9.52E+16 1.11E+17 1.26E+17 1.41E+17 1.57E+17 1.72E+17

-243.84 5.37E+16 6.06E+16 7.03E+16 7.99E+16 8.95E+16 9.92E+16 1.09E+17

-259.08 3.75E+16 4.23E+16 4.90E+16 5.56E+16 6.23E+16 6.89E+16 7.56E+16

-274.32 2.82E+16 3.17E+16 3.67E+16 4.17E+16 4.66E+16 5.16E+16 5.66E+16

-289.56 2.26E+16 2.55E+16 2.94E+16 3.34E+16 3.74E+16 4.14E+16 4.53E+16

-304.80 1.82E+16 2.05E+16 2.37E+16 2.69E+16 3.01E+16 3.33E+16 3.65E+16 Note(s):

1. Elevations are given with respect to the midplane of the active fuel.

2. Value listed is the projected EFPY at the end of Cycle 30.

3. This elevation corresponds to the top of the 6-inch-thick horizontal plate at the top-center of the RPV support structure.

4. Linear interpolation between the EFPY values listed in this table may be performed as necessary.

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 39 of 53 Table 4-14 Fast Neutron (E > 1.0 MeV) Fluence at the RPV Support Structure -

+10% Bias on the Peripheral and Re-Entrant Corner Assembly Relative Powers Elevation[1] Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

(cm) 37.66 EFPY[2] 42 EFPY 48 EFPY 54 EFPY 60 EFPY 66 EFPY 72 EFPY

[3]

218.81 9.90E+16 1.13E+17 1.33E+17 1.53E+17 1.72E+17 1.92E+17 2.12E+17 213.36 1.26E+17 1.44E+17 1.70E+17 1.95E+17 2.20E+17 2.45E+17 2.70E+17 198.12 2.22E+17 2.55E+17 3.00E+17 3.45E+17 3.90E+17 4.35E+17 4.80E+17 182.88 3.52E+17 4.04E+17 4.76E+17 5.49E+17 6.21E+17 6.93E+17 7.65E+17 167.64 5.22E+17 6.00E+17 7.07E+17 8.14E+17 9.22E+17 1.03E+18 1.14E+18 152.40 7.09E+17 8.14E+17 9.59E+17 1.10E+18 1.25E+18 1.40E+18 1.54E+18 137.16 8.83E+17 1.01E+18 1.19E+18 1.37E+18 1.55E+18 1.73E+18 1.91E+18 121.92 1.03E+18 1.18E+18 1.38E+18 1.59E+18 1.80E+18 2.01E+18 2.21E+18 106.68 1.13E+18 1.29E+18 1.52E+18 1.75E+18 1.97E+18 2.20E+18 2.43E+18 91.44 1.20E+18 1.38E+18 1.61E+18 1.85E+18 2.09E+18 2.33E+18 2.57E+18 76.20 1.23E+18 1.40E+18 1.64E+18 1.89E+18 2.13E+18 2.37E+18 2.62E+18 60.96 1.25E+18 1.43E+18 1.68E+18 1.93E+18 2.18E+18 2.42E+18 2.67E+18 45.72 1.26E+18 1.44E+18 1.69E+18 1.94E+18 2.19E+18 2.43E+18 2.68E+18 30.48 1.26E+18 1.44E+18 1.69E+18 1.94E+18 2.18E+18 2.43E+18 2.68E+18 15.24 1.25E+18 1.43E+18 1.68E+18 1.93E+18 2.17E+18 2.42E+18 2.67E+18 0.00 1.26E+18 1.43E+18 1.68E+18 1.93E+18 2.18E+18 2.42E+18 2.67E+18

-15.24 1.26E+18 1.44E+18 1.69E+18 1.94E+18 2.19E+18 2.44E+18 2.69E+18

-30.48 1.27E+18 1.45E+18 1.70E+18 1.95E+18 2.20E+18 2.45E+18 2.70E+18

-45.72 1.27E+18 1.45E+18 1.70E+18 1.95E+18 2.20E+18 2.45E+18 2.70E+18

-60.96 1.26E+18 1.44E+18 1.69E+18 1.94E+18 2.19E+18 2.44E+18 2.68E+18

-76.20 1.24E+18 1.42E+18 1.67E+18 1.92E+18 2.16E+18 2.41E+18 2.65E+18

-91.44 1.21E+18 1.39E+18 1.63E+18 1.87E+18 2.11E+18 2.35E+18 2.59E+18

-106.68 1.15E+18 1.31E+18 1.54E+18 1.77E+18 2.00E+18 2.23E+18 2.46E+18

-121.92 1.05E+18 1.20E+18 1.41E+18 1.62E+18 1.83E+18 2.04E+18 2.25E+18

-137.16 9.10E+17 1.04E+18 1.23E+18 1.41E+18 1.60E+18 1.78E+18 1.97E+18

-152.40 7.40E+17 8.49E+17 1.00E+18 1.15E+18 1.30E+18 1.45E+18 1.60E+18

-167.64 5.51E+17 6.32E+17 7.45E+17 8.58E+17 9.71E+17 1.08E+18 1.20E+18

-182.88 3.74E+17 4.29E+17 5.05E+17 5.82E+17 6.58E+17 7.35E+17 8.11E+17

-198.12 2.33E+17 2.68E+17 3.15E+17 3.62E+17 4.10E+17 4.57E+17 5.04E+17

-213.36 1.39E+17 1.60E+17 1.87E+17 2.15E+17 2.43E+17 2.71E+17 2.99E+17

-228.60 8.41E+16 9.61E+16 1.13E+17 1.29E+17 1.46E+17 1.62E+17 1.79E+17

-243.84 5.37E+16 6.12E+16 7.16E+16 8.20E+16 9.24E+16 1.03E+17 1.13E+17

-259.08 3.75E+16 4.27E+16 4.99E+16 5.71E+16 6.43E+16 7.15E+16 7.87E+16

-274.32 2.82E+16 3.20E+16 3.74E+16 4.28E+16 4.82E+16 5.35E+16 5.89E+16

-289.56 2.26E+16 2.57E+16 3.00E+16 3.43E+16 3.86E+16 4.29E+16 4.72E+16

-304.80 1.82E+16 2.07E+16 2.42E+16 2.76E+16 3.11E+16 3.45E+16 3.80E+16 Note(s):

1. Elevations are given with respect to the midplane of the active fuel.

2. Value listed is the projected EFPY at the end of Cycle 30.

3. This elevation corresponds to the top of the 6-inch-thick horizontal plate at the top-center of the RPV support structure.

4. Linear interpolation between the EFPY values listed in this table may be performed as necessary.

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 40 of 53 Table 4-15 Fast Neutron (E > 0.1 MeV) Fluence at the RPV Support Structure -

No Bias on the Peripheral and Re-Entrant Corner Assembly Relative Powers Elevation[1] Fast Neutron (E > 0.1 MeV) Fluence (n/cm2)

(cm) 37.66 EFPY[2] 42 EFPY 48 EFPY 54 EFPY 60 EFPY 66 EFPY 72 EFPY

[3]

218.81 2.56E+18 2.89E+18 3.35E+18 3.80E+18 4.26E+18 4.72E+18 5.18E+18 213.36 2.97E+18 3.35E+18 3.88E+18 4.41E+18 4.94E+18 5.48E+18 6.01E+18 198.12 4.12E+18 4.65E+18 5.39E+18 6.14E+18 6.88E+18 7.62E+18 8.36E+18 182.88 5.41E+18 6.11E+18 7.09E+18 8.07E+18 9.05E+18 1.00E+19 1.10E+19 167.64 7.07E+18 8.00E+18 9.28E+18 1.06E+19 1.18E+19 1.31E+19 1.44E+19 152.40 8.89E+18 1.01E+19 1.17E+19 1.33E+19 1.49E+19 1.65E+19 1.81E+19 137.16 1.06E+19 1.20E+19 1.40E+19 1.59E+19 1.78E+19 1.97E+19 2.16E+19 121.92 1.21E+19 1.37E+19 1.59E+19 1.81E+19 2.03E+19 2.24E+19 2.46E+19 106.68 1.33E+19 1.50E+19 1.74E+19 1.98E+19 2.22E+19 2.46E+19 2.69E+19 91.44 1.43E+19 1.62E+19 1.87E+19 2.13E+19 2.39E+19 2.64E+19 2.90E+19 76.20 1.56E+19 1.76E+19 2.03E+19 2.31E+19 2.58E+19 2.86E+19 3.14E+19 60.96 1.50E+19 1.69E+19 1.95E+19 2.22E+19 2.48E+19 2.74E+19 3.01E+19 45.72 1.48E+19 1.67E+19 1.93E+19 2.20E+19 2.46E+19 2.72E+19 2.98E+19 30.48 1.48E+19 1.66E+19 1.92E+19 2.18E+19 2.44E+19 2.70E+19 2.96E+19 15.24 1.47E+19 1.65E+19 1.91E+19 2.17E+19 2.43E+19 2.69E+19 2.95E+19 0.00 1.46E+19 1.65E+19 1.91E+19 2.16E+19 2.42E+19 2.68E+19 2.94E+19

-15.24 1.46E+19 1.65E+19 1.90E+19 2.16E+19 2.42E+19 2.68E+19 2.93E+19

-30.48 1.46E+19 1.64E+19 1.90E+19 2.15E+19 2.41E+19 2.67E+19 2.93E+19

-45.72 1.44E+19 1.63E+19 1.88E+19 2.14E+19 2.39E+19 2.65E+19 2.90E+19

-60.96 1.43E+19 1.61E+19 1.86E+19 2.11E+19 2.36E+19 2.62E+19 2.87E+19

-76.20 1.39E+19 1.57E+19 1.82E+19 2.07E+19 2.31E+19 2.56E+19 2.81E+19

-91.44 1.35E+19 1.52E+19 1.76E+19 2.00E+19 2.24E+19 2.47E+19 2.71E+19

-106.68 1.27E+19 1.43E+19 1.66E+19 1.89E+19 2.11E+19 2.34E+19 2.56E+19

-121.92 1.16E+19 1.31E+19 1.52E+19 1.73E+19 1.94E+19 2.14E+19 2.35E+19

-137.16 1.02E+19 1.15E+19 1.34E+19 1.52E+19 1.71E+19 1.89E+19 2.07E+19

-152.40 8.54E+18 9.66E+18 1.12E+19 1.27E+19 1.43E+19 1.58E+19 1.74E+19

-167.64 6.75E+18 7.63E+18 8.85E+18 1.01E+19 1.13E+19 1.25E+19 1.37E+19

-182.88 5.05E+18 5.71E+18 6.62E+18 7.53E+18 8.44E+18 9.35E+18 1.03E+19

-198.12 3.63E+18 4.10E+18 4.75E+18 5.40E+18 6.05E+18 6.70E+18 7.35E+18

-213.36 2.57E+18 2.90E+18 3.36E+18 3.81E+18 4.27E+18 4.73E+18 5.18E+18

-228.60 1.84E+18 2.07E+18 2.40E+18 2.72E+18 3.04E+18 3.37E+18 3.69E+18

-243.84 1.35E+18 1.52E+18 1.76E+18 1.99E+18 2.23E+18 2.47E+18 2.70E+18

-259.08 1.02E+18 1.15E+18 1.32E+18 1.50E+18 1.67E+18 1.85E+18 2.03E+18

-274.32 7.84E+17 8.81E+17 1.01E+18 1.15E+18 1.28E+18 1.42E+18 1.55E+18

-289.56 6.28E+17 7.06E+17 8.13E+17 9.20E+17 1.03E+18 1.13E+18 1.24E+18

-304.80 5.14E+17 5.77E+17 6.64E+17 7.51E+17 8.38E+17 9.25E+17 1.01E+18 Note(s):

1. Elevations are given with respect to the midplane of the active fuel.

2. Value listed is the projected EFPY at the end of Cycle 30.

3. This elevation corresponds to the top of the 6-inch-thick horizontal plate at the top-center of the RPV support structure.

4. Linear interpolation between the EFPY values listed in this table may be performed as necessary.

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 41 of 53 Table 4-16 Fast Neutron (E > 0.1 MeV) Fluence at the RPV Support Structure -

+10% Bias on the Peripheral and Re-Entrant Corner Assembly Relative Powers Elevation[1] Fast Neutron (E > 0.1 MeV) Fluence (n/cm2)

(cm) 37.66 EFPY[2] 42 EFPY 48 EFPY 54 EFPY 60 EFPY 66 EFPY 72 EFPY

[3]

218.81 2.56E+18 2.92E+18 3.41E+18 3.91E+18 4.40E+18 4.90E+18 5.39E+18 213.36 2.97E+18 3.38E+18 3.96E+18 4.53E+18 5.11E+18 5.68E+18 6.26E+18 198.12 4.12E+18 4.70E+18 5.50E+18 6.30E+18 7.11E+18 7.91E+18 8.71E+18 182.88 5.41E+18 6.17E+18 7.24E+18 8.30E+18 9.36E+18 1.04E+19 1.15E+19 167.64 7.07E+18 8.07E+18 9.46E+18 1.09E+19 1.22E+19 1.36E+19 1.50E+19 152.40 8.89E+18 1.02E+19 1.19E+19 1.37E+19 1.54E+19 1.71E+19 1.89E+19 137.16 1.06E+19 1.22E+19 1.42E+19 1.63E+19 1.84E+19 2.05E+19 2.26E+19 121.92 1.21E+19 1.39E+19 1.62E+19 1.86E+19 2.10E+19 2.33E+19 2.57E+19 106.68 1.33E+19 1.52E+19 1.78E+19 2.04E+19 2.29E+19 2.55E+19 2.81E+19 91.44 1.43E+19 1.64E+19 1.91E+19 2.19E+19 2.47E+19 2.74E+19 3.02E+19 76.20 1.56E+19 1.77E+19 2.07E+19 2.37E+19 2.67E+19 2.97E+19 3.27E+19 60.96 1.50E+19 1.70E+19 1.99E+19 2.28E+19 2.56E+19 2.85E+19 3.14E+19 45.72 1.48E+19 1.69E+19 1.97E+19 2.26E+19 2.54E+19 2.82E+19 3.11E+19 30.48 1.48E+19 1.68E+19 1.96E+19 2.24E+19 2.52E+19 2.81E+19 3.09E+19 15.24 1.47E+19 1.67E+19 1.95E+19 2.23E+19 2.51E+19 2.79E+19 3.07E+19 0.00 1.46E+19 1.66E+19 1.94E+19 2.22E+19 2.50E+19 2.78E+19 3.06E+19

-15.24 1.46E+19 1.66E+19 1.94E+19 2.22E+19 2.50E+19 2.78E+19 3.05E+19

-30.48 1.46E+19 1.66E+19 1.93E+19 2.21E+19 2.49E+19 2.77E+19 3.05E+19

-45.72 1.44E+19 1.64E+19 1.92E+19 2.20E+19 2.47E+19 2.75E+19 3.02E+19

-60.96 1.43E+19 1.62E+19 1.90E+19 2.17E+19 2.44E+19 2.71E+19 2.99E+19

-76.20 1.39E+19 1.59E+19 1.86E+19 2.12E+19 2.39E+19 2.66E+19 2.93E+19

-91.44 1.35E+19 1.53E+19 1.79E+19 2.05E+19 2.31E+19 2.57E+19 2.83E+19

-106.68 1.27E+19 1.45E+19 1.69E+19 1.94E+19 2.18E+19 2.43E+19 2.67E+19

-121.92 1.16E+19 1.32E+19 1.55E+19 1.78E+19 2.00E+19 2.23E+19 2.45E+19

-137.16 1.02E+19 1.17E+19 1.36E+19 1.56E+19 1.76E+19 1.96E+19 2.16E+19

-152.40 8.54E+18 9.75E+18 1.14E+19 1.31E+19 1.48E+19 1.64E+19 1.81E+19

-167.64 6.75E+18 7.71E+18 9.03E+18 1.04E+19 1.17E+19 1.30E+19 1.43E+19

-182.88 5.05E+18 5.76E+18 6.75E+18 7.73E+18 8.72E+18 9.71E+18 1.07E+19

-198.12 3.63E+18 4.14E+18 4.84E+18 5.54E+18 6.25E+18 6.95E+18 7.66E+18

-213.36 2.57E+18 2.93E+18 3.42E+18 3.92E+18 4.41E+18 4.91E+18 5.40E+18

-228.60 1.84E+18 2.09E+18 2.44E+18 2.79E+18 3.14E+18 3.49E+18 3.84E+18

-243.84 1.35E+18 1.54E+18 1.79E+18 2.05E+18 2.30E+18 2.56E+18 2.81E+18

-259.08 1.02E+18 1.16E+18 1.35E+18 1.54E+18 1.73E+18 1.92E+18 2.11E+18

-274.32 7.84E+17 8.89E+17 1.03E+18 1.18E+18 1.33E+18 1.47E+18 1.62E+18

-289.56 6.28E+17 7.12E+17 8.28E+17 9.44E+17 1.06E+18 1.18E+18 1.29E+18

-304.80 5.14E+17 5.82E+17 6.77E+17 7.71E+17 8.65E+17 9.60E+17 1.05E+18 Note(s):

1. Elevations are given with respect to the midplane of the active fuel.

2. Value listed is the projected EFPY at the end of Cycle 30.

3. This elevation corresponds to the top of the 6-inch-thick horizontal plate at the top-center of the RPV support structure.

4. Linear interpolation between the EFPY values listed in this table may be performed as necessary.

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 42 of 53 Table 4-17 Iron Atom Displacements (All Neutron Energies) at the RPV Support Structure -

No Bias on the Peripheral and Re-Entrant Corner Assembly Relative Powers Elevation[1] Iron Atom Displacements - All Neutron Energies (dpa)

(cm) 37.66 EFPY[2] 42 EFPY 48 EFPY 54 EFPY 60 EFPY 66 EFPY 72 EFPY

[3]

218.81 7.61E-04 8.60E-04 9.96E-04 1.13E-03 1.27E-03 1.40E-03 1.54E-03 213.36 8.89E-04 1.00E-03 1.16E-03 1.32E-03 1.48E-03 1.64E-03 1.80E-03 198.12 1.27E-03 1.43E-03 1.66E-03 1.89E-03 2.12E-03 2.35E-03 2.58E-03 182.88 1.71E-03 1.93E-03 2.24E-03 2.55E-03 2.86E-03 3.17E-03 3.48E-03 167.64 2.27E-03 2.57E-03 2.99E-03 3.40E-03 3.82E-03 4.24E-03 4.65E-03 152.40 2.90E-03 3.28E-03 3.81E-03 4.34E-03 4.86E-03 5.39E-03 5.92E-03 137.16 3.49E-03 3.95E-03 4.58E-03 5.22E-03 5.85E-03 6.49E-03 7.12E-03 121.92 4.00E-03 4.52E-03 5.24E-03 5.96E-03 6.68E-03 7.41E-03 8.13E-03 106.68 4.39E-03 4.96E-03 5.75E-03 6.53E-03 7.32E-03 8.11E-03 8.90E-03 91.44 4.71E-03 5.32E-03 6.16E-03 7.01E-03 7.85E-03 8.69E-03 9.53E-03 76.20 5.05E-03 5.70E-03 6.60E-03 7.50E-03 8.40E-03 9.30E-03 1.02E-02 60.96 4.91E-03 5.54E-03 6.42E-03 7.29E-03 8.16E-03 9.04E-03 9.91E-03 45.72 4.89E-03 5.51E-03 6.38E-03 7.25E-03 8.11E-03 8.98E-03 9.85E-03 30.48 4.86E-03 5.49E-03 6.35E-03 7.21E-03 8.08E-03 8.94E-03 9.80E-03 15.24 4.84E-03 5.46E-03 6.32E-03 7.17E-03 8.03E-03 8.89E-03 9.75E-03 0.00 4.83E-03 5.44E-03 6.30E-03 7.16E-03 8.01E-03 8.87E-03 9.73E-03

-15.24 4.83E-03 5.45E-03 6.30E-03 7.16E-03 8.02E-03 8.87E-03 9.73E-03

-30.48 4.82E-03 5.44E-03 6.29E-03 7.15E-03 8.01E-03 8.86E-03 9.72E-03

-45.72 4.79E-03 5.40E-03 6.25E-03 7.10E-03 7.96E-03 8.81E-03 9.66E-03

-60.96 4.73E-03 5.34E-03 6.18E-03 7.02E-03 7.87E-03 8.71E-03 9.55E-03

-76.20 4.64E-03 5.24E-03 6.06E-03 6.89E-03 7.72E-03 8.54E-03 9.37E-03

-91.44 4.48E-03 5.06E-03 5.86E-03 6.67E-03 7.47E-03 8.27E-03 9.07E-03

-106.68 4.23E-03 4.78E-03 5.54E-03 6.30E-03 7.06E-03 7.83E-03 8.59E-03

-121.92 3.87E-03 4.38E-03 5.08E-03 5.78E-03 6.48E-03 7.18E-03 7.88E-03

-137.16 3.40E-03 3.84E-03 4.46E-03 5.08E-03 5.69E-03 6.31E-03 6.93E-03

-152.40 2.83E-03 3.20E-03 3.72E-03 4.23E-03 4.75E-03 5.26E-03 5.78E-03

-167.64 2.21E-03 2.50E-03 2.91E-03 3.31E-03 3.71E-03 4.12E-03 4.52E-03

-182.88 1.63E-03 1.84E-03 2.14E-03 2.43E-03 2.73E-03 3.02E-03 3.32E-03

-198.12 1.14E-03 1.29E-03 1.50E-03 1.71E-03 1.91E-03 2.12E-03 2.33E-03

-213.36 7.94E-04 8.97E-04 1.04E-03 1.18E-03 1.32E-03 1.46E-03 1.60E-03

-228.60 5.58E-04 6.30E-04 7.28E-04 8.26E-04 9.25E-04 1.02E-03 1.12E-03

-243.84 4.06E-04 4.57E-04 5.28E-04 5.98E-04 6.69E-04 7.40E-04 8.10E-04

-259.08 3.04E-04 3.42E-04 3.95E-04 4.47E-04 5.00E-04 5.52E-04 6.05E-04

-274.32 2.34E-04 2.63E-04 3.03E-04 3.43E-04 3.83E-04 4.24E-04 4.64E-04

-289.56 1.88E-04 2.12E-04 2.44E-04 2.76E-04 3.08E-04 3.40E-04 3.72E-04

-304.80 1.55E-04 1.74E-04 2.00E-04 2.26E-04 2.52E-04 2.78E-04 3.05E-04 Note(s):

1. Elevations are given with respect to the midplane of the active fuel.

2. Value listed is the projected EFPY at the end of Cycle 30.

3. This elevation corresponds to the top of the 6-inch-thick horizontal plate at the top-center of the RPV support structure.

4. Linear interpolation between the EFPY values listed in this table may be performed as necessary.

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 43 of 53 Table 4-18 Iron Atom Displacements (All Neutron Energies) at the RPV Support Structure -

+10% Bias on the Peripheral and Re-Entrant Corner Assembly Relative Powers Elevation[1] Iron Atom Displacements - All Neutron Energies (dpa)

(cm) 37.66 EFPY[2] 42 EFPY 48 EFPY 54 EFPY 60 EFPY 66 EFPY 72 EFPY

[3]

218.81 7.61E-04 8.68E-04 1.02E-03 1.16E-03 1.31E-03 1.46E-03 1.61E-03 213.36 8.89E-04 1.01E-03 1.19E-03 1.36E-03 1.53E-03 1.71E-03 1.88E-03 198.12 1.27E-03 1.45E-03 1.69E-03 1.94E-03 2.19E-03 2.44E-03 2.69E-03 182.88 1.71E-03 1.95E-03 2.29E-03 2.62E-03 2.96E-03 3.30E-03 3.63E-03 167.64 2.27E-03 2.60E-03 3.05E-03 3.50E-03 3.95E-03 4.40E-03 4.85E-03 152.40 2.90E-03 3.31E-03 3.88E-03 4.46E-03 5.03E-03 5.61E-03 6.18E-03 137.16 3.49E-03 3.99E-03 4.68E-03 5.37E-03 6.05E-03 6.74E-03 7.43E-03 121.92 4.00E-03 4.56E-03 5.35E-03 6.13E-03 6.91E-03 7.70E-03 8.48E-03 106.68 4.39E-03 5.01E-03 5.86E-03 6.72E-03 7.57E-03 8.43E-03 9.28E-03 91.44 4.71E-03 5.37E-03 6.29E-03 7.20E-03 8.12E-03 9.03E-03 9.95E-03 76.20 5.05E-03 5.75E-03 6.73E-03 7.71E-03 8.68E-03 9.66E-03 1.06E-02 60.96 4.91E-03 5.60E-03 6.54E-03 7.49E-03 8.44E-03 9.38E-03 1.03E-02 45.72 4.89E-03 5.57E-03 6.51E-03 7.45E-03 8.39E-03 9.33E-03 1.03E-02 30.48 4.86E-03 5.54E-03 6.48E-03 7.41E-03 8.35E-03 9.28E-03 1.02E-02 15.24 4.84E-03 5.51E-03 6.44E-03 7.37E-03 8.30E-03 9.23E-03 1.02E-02 0.00 4.83E-03 5.50E-03 6.42E-03 7.35E-03 8.28E-03 9.20E-03 1.01E-02

-15.24 4.83E-03 5.50E-03 6.42E-03 7.35E-03 8.28E-03 9.21E-03 1.01E-02

-30.48 4.82E-03 5.49E-03 6.42E-03 7.34E-03 8.27E-03 9.19E-03 1.01E-02

-45.72 4.79E-03 5.45E-03 6.37E-03 7.30E-03 8.22E-03 9.14E-03 1.01E-02

-60.96 4.73E-03 5.39E-03 6.30E-03 7.21E-03 8.12E-03 9.04E-03 9.95E-03

-76.20 4.64E-03 5.29E-03 6.18E-03 7.08E-03 7.97E-03 8.87E-03 9.76E-03

-91.44 4.48E-03 5.11E-03 5.98E-03 6.85E-03 7.72E-03 8.58E-03 9.45E-03

-106.68 4.23E-03 4.83E-03 5.65E-03 6.48E-03 7.30E-03 8.12E-03 8.95E-03

-121.92 3.87E-03 4.42E-03 5.18E-03 5.94E-03 6.69E-03 7.45E-03 8.21E-03

-137.16 3.40E-03 3.88E-03 4.55E-03 5.22E-03 5.88E-03 6.55E-03 7.22E-03

-152.40 2.83E-03 3.23E-03 3.79E-03 4.35E-03 4.91E-03 5.46E-03 6.02E-03

-167.64 2.21E-03 2.53E-03 2.96E-03 3.40E-03 3.84E-03 4.27E-03 4.71E-03

-182.88 1.63E-03 1.86E-03 2.18E-03 2.50E-03 2.82E-03 3.14E-03 3.46E-03

-198.12 1.14E-03 1.31E-03 1.53E-03 1.75E-03 1.98E-03 2.20E-03 2.42E-03

-213.36 7.94E-04 9.05E-04 1.06E-03 1.21E-03 1.36E-03 1.52E-03 1.67E-03

-228.60 5.58E-04 6.35E-04 7.42E-04 8.48E-04 9.55E-04 1.06E-03 1.17E-03

-243.84 4.06E-04 4.61E-04 5.38E-04 6.14E-04 6.91E-04 7.67E-04 8.44E-04

-259.08 3.04E-04 3.46E-04 4.02E-04 4.59E-04 5.16E-04 5.73E-04 6.30E-04

-274.32 2.34E-04 2.66E-04 3.09E-04 3.53E-04 3.96E-04 4.39E-04 4.83E-04

-289.56 1.88E-04 2.14E-04 2.48E-04 2.83E-04 3.18E-04 3.53E-04 3.88E-04

-304.80 1.55E-04 1.75E-04 2.04E-04 2.32E-04 2.60E-04 2.89E-04 3.17E-04 Note(s):

1. Elevations are given with respect to the midplane of the active fuel.

2. Value listed is the projected EFPY at the end of Cycle 30.

3. This elevation corresponds to the top of the 6-inch-thick horizontal plate at the top-center of the RPV support structure.

4. Linear interpolation between the EFPY values listed in this table may be performed as necessary.

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 44 of 53 Table 4-19 Iron Atom Displacements (E > 0.1 MeV) at the RPV Support Structure -

No Bias on the Peripheral and Re-Entrant Corner Assembly Relative Powers Elevation[1] Iron Atom Displacements - Neutron Energies > 0.1 MeV (dpa)

(cm) 37.66 EFPY[2] 42 EFPY 48 EFPY 54 EFPY 60 EFPY 66 EFPY 72 EFPY

[3]

218.81 6.57E-04 7.42E-04 8.60E-04 9.78E-04 1.10E-03 1.21E-03 1.33E-03 213.36 7.73E-04 8.74E-04 1.01E-03 1.15E-03 1.29E-03 1.43E-03 1.57E-03 198.12 1.12E-03 1.27E-03 1.47E-03 1.68E-03 1.88E-03 2.08E-03 2.29E-03 182.88 1.53E-03 1.74E-03 2.02E-03 2.30E-03 2.58E-03 2.86E-03 3.14E-03 167.64 2.06E-03 2.34E-03 2.72E-03 3.10E-03 3.48E-03 3.85E-03 4.23E-03 152.40 2.65E-03 3.00E-03 3.48E-03 3.97E-03 4.45E-03 4.94E-03 5.43E-03 137.16 3.20E-03 3.63E-03 4.21E-03 4.80E-03 5.38E-03 5.96E-03 6.55E-03 121.92 3.68E-03 4.16E-03 4.82E-03 5.49E-03 6.16E-03 6.82E-03 7.49E-03 106.68 4.04E-03 4.56E-03 5.29E-03 6.02E-03 6.75E-03 7.47E-03 8.20E-03 91.44 4.33E-03 4.90E-03 5.68E-03 6.45E-03 7.23E-03 8.01E-03 8.79E-03 76.20 4.63E-03 5.23E-03 6.06E-03 6.89E-03 7.72E-03 8.55E-03 9.37E-03 60.96 4.52E-03 5.10E-03 5.91E-03 6.71E-03 7.52E-03 8.32E-03 9.13E-03 45.72 4.50E-03 5.08E-03 5.88E-03 6.68E-03 7.48E-03 8.28E-03 9.08E-03 30.48 4.48E-03 5.06E-03 5.85E-03 6.65E-03 7.45E-03 8.24E-03 9.04E-03 15.24 4.46E-03 5.03E-03 5.82E-03 6.62E-03 7.41E-03 8.20E-03 8.99E-03 0.00 4.45E-03 5.02E-03 5.81E-03 6.60E-03 7.39E-03 8.18E-03 8.98E-03

-15.24 4.45E-03 5.02E-03 5.82E-03 6.61E-03 7.40E-03 8.19E-03 8.98E-03

-30.48 4.45E-03 5.02E-03 5.81E-03 6.60E-03 7.40E-03 8.19E-03 8.98E-03

-45.72 4.42E-03 4.99E-03 5.78E-03 6.57E-03 7.35E-03 8.14E-03 8.93E-03

-60.96 4.37E-03 4.94E-03 5.72E-03 6.50E-03 7.27E-03 8.05E-03 8.83E-03

-76.20 4.29E-03 4.84E-03 5.61E-03 6.38E-03 7.14E-03 7.91E-03 8.67E-03

-91.44 4.15E-03 4.68E-03 5.43E-03 6.17E-03 6.91E-03 7.66E-03 8.40E-03

-106.68 3.92E-03 4.43E-03 5.13E-03 5.84E-03 6.54E-03 7.25E-03 7.95E-03

-121.92 3.58E-03 4.05E-03 4.70E-03 5.35E-03 6.00E-03 6.64E-03 7.29E-03

-137.16 3.14E-03 3.55E-03 4.12E-03 4.69E-03 5.26E-03 5.83E-03 6.40E-03

-152.40 2.60E-03 2.95E-03 3.42E-03 3.90E-03 4.38E-03 4.85E-03 5.33E-03

-167.64 2.02E-03 2.29E-03 2.66E-03 3.03E-03 3.40E-03 3.77E-03 4.15E-03

-182.88 1.48E-03 1.67E-03 1.94E-03 2.21E-03 2.48E-03 2.75E-03 3.02E-03

-198.12 1.03E-03 1.16E-03 1.35E-03 1.53E-03 1.72E-03 1.91E-03 2.09E-03

-213.36 7.02E-04 7.93E-04 9.18E-04 1.04E-03 1.17E-03 1.30E-03 1.42E-03

-228.60 4.86E-04 5.48E-04 6.34E-04 7.20E-04 8.06E-04 8.92E-04 9.78E-04

-243.84 3.48E-04 3.93E-04 4.53E-04 5.14E-04 5.75E-04 6.36E-04 6.97E-04

-259.08 2.59E-04 2.91E-04 3.36E-04 3.81E-04 4.26E-04 4.71E-04 5.16E-04

-274.32 1.98E-04 2.23E-04 2.57E-04 2.91E-04 3.25E-04 3.59E-04 3.93E-04

-289.56 1.58E-04 1.78E-04 2.05E-04 2.32E-04 2.59E-04 2.86E-04 3.13E-04

-304.80 1.29E-04 1.45E-04 1.67E-04 1.89E-04 2.11E-04 2.33E-04 2.55E-04 Note(s):

1. Elevations are given with respect to the midplane of the active fuel.

2. Value listed is the projected EFPY at the end of Cycle 30.

3. This elevation corresponds to the top of the 6-inch-thick horizontal plate at the top-center of the RPV support structure.

4. Linear interpolation between the EFPY values listed in this table may be performed as necessary.

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 45 of 53 Table 4-20 Iron Atom Displacements (E > 0.1 MeV) at the RPV Support Structure -

+10% Bias on the Peripheral and Re-Entrant Corner Assembly Relative Powers Elevation[1] Iron Atom Displacements - Neutron Energies > 0.1 MeV (dpa)

(cm) 37.66 EFPY[2] 42 EFPY 48 EFPY 54 EFPY 60 EFPY 66 EFPY 72 EFPY

[3]

218.81 6.57E-04 7.49E-04 8.77E-04 1.00E-03 1.13E-03 1.26E-03 1.39E-03 213.36 7.73E-04 8.83E-04 1.03E-03 1.18E-03 1.34E-03 1.49E-03 1.64E-03 198.12 1.12E-03 1.28E-03 1.50E-03 1.72E-03 1.94E-03 2.16E-03 2.38E-03 182.88 1.53E-03 1.75E-03 2.06E-03 2.36E-03 2.66E-03 2.97E-03 3.27E-03 167.64 2.06E-03 2.36E-03 2.77E-03 3.18E-03 3.59E-03 4.01E-03 4.42E-03 152.40 2.65E-03 3.03E-03 3.56E-03 4.08E-03 4.61E-03 5.13E-03 5.66E-03 137.16 3.20E-03 3.66E-03 4.30E-03 4.93E-03 5.56E-03 6.20E-03 6.83E-03 121.92 3.68E-03 4.20E-03 4.92E-03 5.64E-03 6.37E-03 7.09E-03 7.81E-03 106.68 4.04E-03 4.61E-03 5.40E-03 6.19E-03 6.98E-03 7.77E-03 8.56E-03 91.44 4.33E-03 4.95E-03 5.79E-03 6.63E-03 7.48E-03 8.32E-03 9.16E-03 76.20 4.63E-03 5.28E-03 6.18E-03 7.08E-03 7.98E-03 8.88E-03 9.78E-03 60.96 4.52E-03 5.15E-03 6.03E-03 6.90E-03 7.77E-03 8.64E-03 9.52E-03 45.72 4.50E-03 5.13E-03 5.99E-03 6.86E-03 7.73E-03 8.60E-03 9.46E-03 30.48 4.48E-03 5.11E-03 5.97E-03 6.83E-03 7.70E-03 8.56E-03 9.42E-03 15.24 4.46E-03 5.08E-03 5.94E-03 6.79E-03 7.65E-03 8.51E-03 9.37E-03 0.00 4.45E-03 5.07E-03 5.92E-03 6.78E-03 7.64E-03 8.49E-03 9.35E-03

-15.24 4.45E-03 5.07E-03 5.93E-03 6.79E-03 7.64E-03 8.50E-03 9.36E-03

-30.48 4.45E-03 5.07E-03 5.92E-03 6.78E-03 7.64E-03 8.50E-03 9.35E-03

-45.72 4.42E-03 5.04E-03 5.89E-03 6.74E-03 7.59E-03 8.45E-03 9.30E-03

-60.96 4.37E-03 4.98E-03 5.83E-03 6.67E-03 7.51E-03 8.36E-03 9.20E-03

-76.20 4.29E-03 4.89E-03 5.72E-03 6.55E-03 7.38E-03 8.21E-03 9.04E-03

-91.44 4.15E-03 4.73E-03 5.53E-03 6.34E-03 7.14E-03 7.95E-03 8.75E-03

-106.68 3.92E-03 4.47E-03 5.23E-03 6.00E-03 6.76E-03 7.52E-03 8.29E-03

-121.92 3.58E-03 4.09E-03 4.79E-03 5.49E-03 6.20E-03 6.90E-03 7.60E-03

-137.16 3.14E-03 3.58E-03 4.20E-03 4.82E-03 5.44E-03 6.06E-03 6.68E-03

-152.40 2.60E-03 2.98E-03 3.49E-03 4.01E-03 4.52E-03 5.04E-03 5.55E-03

-167.64 2.02E-03 2.31E-03 2.72E-03 3.12E-03 3.52E-03 3.92E-03 4.32E-03

-182.88 1.48E-03 1.69E-03 1.98E-03 2.27E-03 2.56E-03 2.86E-03 3.15E-03

-198.12 1.03E-03 1.17E-03 1.37E-03 1.58E-03 1.78E-03 1.98E-03 2.18E-03

-213.36 7.02E-04 8.00E-04 9.36E-04 1.07E-03 1.21E-03 1.34E-03 1.48E-03

-228.60 4.86E-04 5.53E-04 6.46E-04 7.39E-04 8.32E-04 9.25E-04 1.02E-03

-243.84 3.48E-04 3.96E-04 4.62E-04 5.28E-04 5.94E-04 6.60E-04 7.26E-04

-259.08 2.59E-04 2.94E-04 3.43E-04 3.91E-04 4.40E-04 4.89E-04 5.37E-04

-274.32 1.98E-04 2.25E-04 2.61E-04 2.98E-04 3.35E-04 3.72E-04 4.09E-04

-289.56 1.58E-04 1.80E-04 2.09E-04 2.38E-04 2.68E-04 2.97E-04 3.27E-04

-304.80 1.29E-04 1.46E-04 1.70E-04 1.94E-04 2.18E-04 2.42E-04 2.66E-04 Note(s):

1. Elevations are given with respect to the midplane of the active fuel.

2. Value listed is the projected EFPY at the end of Cycle 30.

3. This elevation corresponds to the top of the 6-inch-thick horizontal plate at the top-center of the RPV support structure.

4. Linear interpolation between the EFPY values listed in this table may be performed as necessary.

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 46 of 53 4.4 Bioshield Concrete Neutron and gamma exposure data for the bioshield concrete are provided in Table 4-21 through Table 4-23.

In particular, fast neutron (E > 1.0 MeV) fluences are provided in Table 4-21 as a function of irradiation time.

Similar data, but for energies greater than 0.1 MeV, are provided in Table 4-22. Calculated gamma doses for the bioshield concrete are provided in Table 4-23. In all cases, the data provided in Table 4-21 through Table 4-23 are the maximum exposures experienced by the bioshield concrete at the azimuthal angles listed and at the azimuthal location providing the maximum exposure relative to the core cardinal axes.

Table 4-23 shows that the concrete gamma dose threshold value for consideration of radiation exposure effects, 1x108 Gy (1x1010 rad), is not projected to be exceeded prior to a cumulative operating time of 72 EFPY.

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 47 of 53 Table 4-21 Fast Neutron (E > 1.0 MeV) Fluence at the Bioshield Concrete Cycle Cumulative Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 1 1.05 1.05 3.87E+15 1.33E+16 1.27E+16 1.19E+16 1.28E+16 1.55E+16 1.80E+16 1.80E+16 2 0.74 1.79 6.57E+15 2.27E+16 2.17E+16 2.02E+16 2.17E+16 2.64E+16 3.07E+16 3.07E+16 3 0.69 2.48 9.11E+15 3.15E+16 3.00E+16 2.80E+16 3.01E+16 3.66E+16 4.25E+16 4.25E+16 4 1.22 3.70 1.36E+16 4.70E+16 4.49E+16 4.18E+16 4.50E+16 5.46E+16 6.35E+16 6.35E+16 5 1.12 4.82 1.74E+16 5.94E+16 5.59E+16 5.16E+16 5.60E+16 6.93E+16 8.13E+16 8.13E+16 6 1.36 6.18 2.43E+16 8.27E+16 7.70E+16 7.04E+16 7.71E+16 9.64E+16 1.13E+17 1.13E+17 7 1.05 7.22 2.97E+16 1.01E+17 9.33E+16 8.49E+16 9.34E+16 1.17E+17 1.38E+17 1.38E+17 8 1.18 8.41 3.57E+16 1.21E+17 1.12E+17 1.01E+17 1.12E+17 1.41E+17 1.66E+17 1.66E+17 9 1.29 9.70 4.23E+16 1.43E+17 1.32E+17 1.19E+17 1.32E+17 1.67E+17 1.96E+17 1.96E+17 10 1.31 11.01 4.67E+16 1.60E+17 1.50E+17 1.37E+17 1.50E+17 1.86E+17 2.16E+17 2.16E+17 11 1.21 12.22 5.04E+16 1.74E+17 1.67E+17 1.54E+17 1.67E+17 2.02E+17 2.32E+17 2.32E+17 12 1.27 13.48 5.48E+16 1.91E+17 1.86E+17 1.72E+17 1.86E+17 2.21E+17 2.51E+17 2.51E+17 13 1.14 14.62 5.83E+16 2.05E+17 2.02E+17 1.87E+17 2.02E+17 2.36E+17 2.66E+17 2.66E+17 14 1.18 15.80 6.21E+16 2.19E+17 2.18E+17 2.02E+17 2.18E+17 2.52E+17 2.82E+17 2.82E+17 15 1.62 17.42 6.78E+16 2.39E+17 2.36E+17 2.19E+17 2.36E+17 2.74E+17 3.08E+17 3.08E+17 16 1.44 18.86 7.31E+16 2.58E+17 2.55E+17 2.38E+17 2.55E+17 2.96E+17 3.32E+17 3.32E+17 17 1.39 20.26 7.75E+16 2.73E+17 2.71E+17 2.53E+17 2.71E+17 3.14E+17 3.52E+17 3.52E+17 18 1.40 21.66 8.22E+16 2.90E+17 2.87E+17 2.68E+17 2.87E+17 3.32E+17 3.74E+17 3.74E+17 19 1.42 23.08 8.68E+16 3.06E+17 3.03E+17 2.84E+17 3.03E+17 3.51E+17 3.94E+17 3.94E+17 20 1.27 24.35 9.12E+16 3.21E+17 3.18E+17 2.98E+17 3.18E+17 3.69E+17 4.14E+17 4.14E+17 21 1.38 25.73 9.60E+16 3.38E+17 3.33E+17 3.12E+17 3.33E+17 3.87E+17 4.36E+17 4.36E+17 22 1.35 27.08 1.01E+17 3.55E+17 3.49E+17 3.26E+17 3.49E+17 4.07E+17 4.59E+17 4.59E+17 23 1.31 28.39 1.06E+17 3.72E+17 3.65E+17 3.42E+17 3.65E+17 4.26E+17 4.82E+17 4.82E+17 24 1.29 29.67 1.11E+17 3.91E+17 3.83E+17 3.59E+17 3.84E+17 4.49E+17 5.07E+17 5.07E+17 25 1.33 31.00 1.18E+17 4.12E+17 4.04E+17 3.78E+17 4.04E+17 4.74E+17 5.37E+17 5.37E+17 26 1.33 32.33 1.24E+17 4.34E+17 4.24E+17 3.98E+17 4.25E+17 4.99E+17 5.66E+17 5.66E+17

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 48 of 53 Table 4-21 Fast Neutron (E > 1.0 MeV) Fluence at the Bioshield Concrete Cycle Cumulative Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 27 1.30 33.64 1.30E+17 4.53E+17 4.41E+17 4.13E+17 4.41E+17 5.21E+17 5.93E+17 5.93E+17 28 1.30 34.94 1.35E+17 4.71E+17 4.58E+17 4.29E+17 4.58E+17 5.42E+17 6.17E+17 6.17E+17 29 1.37 36.31 1.41E+17 4.91E+17 4.76E+17 4.46E+17 4.76E+17 5.65E+17 6.44E+17 6.44E+17

[1]

30 1.35 37.66 1.47E+17 5.11E+17 4.95E+17 4.63E+17 4.95E+17 5.88E+17 6.71E+17 6.71E+17 Projections with no bias on the peripheral and re-entrant corner assembly relative powers

[2]

Future -- 42.00 1.66E+17 5.73E+17 5.52E+17 5.15E+17 5.52E+17 6.60E+17 7.57E+17 7.57E+17

[2]

Future -- 48.00 1.92E+17 6.60E+17 6.31E+17 5.88E+17 6.30E+17 7.61E+17 8.76E+17 8.76E+17

[2]

Future -- 54.00 2.17E+17 7.46E+17 7.10E+17 6.61E+17 7.09E+17 8.61E+17 9.95E+17 9.95E+17

[2]

Future -- 60.00 2.43E+17 8.33E+17 7.89E+17 7.34E+17 7.88E+17 9.62E+17 1.11E+18 1.11E+18 Future[2] -- 66.00 2.69E+17 9.19E+17 8.68E+17 8.07E+17 8.66E+17 1.06E+18 1.23E+18 1.23E+18

[2]

Future -- 72.00 2.95E+17 1.01E+18 9.47E+17 8.79E+17 9.45E+17 1.16E+18 1.35E+18 1.35E+18 Projections with a +10% bias on the peripheral and re-entrant corner assembly relative powers

[2]

Future -- 42.00 1.67E+17 5.79E+17 5.57E+17 5.20E+17 5.57E+17 6.66E+17 7.64E+17 7.64E+17

[2]

Future -- 48.00 1.95E+17 6.72E+17 6.43E+17 5.99E+17 6.42E+17 7.75E+17 8.93E+17 8.93E+17

[2]

Future -- 54.00 2.23E+17 7.66E+17 7.28E+17 6.78E+17 7.28E+17 8.84E+17 1.02E+18 1.02E+18

[2]

Future -- 60.00 2.51E+17 8.60E+17 8.14E+17 7.58E+17 8.13E+17 9.93E+17 1.15E+18 1.15E+18

[2]

Future -- 66.00 2.79E+17 9.54E+17 9.00E+17 8.37E+17 8.99E+17 1.10E+18 1.28E+18 1.28E+18

[2]

Future -- 72.00 3.07E+17 1.05E+18 9.86E+17 9.16E+17 9.84E+17 1.21E+18 1.41E+18 1.41E+18 Note(s):

1. Cycle 30 was the current operating cycle at the time the exposures reported in this table were determined. Values listed are based on the projected EFPY for this cycle.

2. Values beyond Cycle 30 are based on the average core power distributions and reactor operating conditions of Cycle 29 and are determined both with and without a 1.1 bias on the peripheral and re-entrant corner assembly relative powers.

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 49 of 53 Table 4-22 Fast Neutron (E > 0.1 MeV) Fluence at the Bioshield Concrete Cycle Cumulative Fast Neutron (E > 0.1 MeV) Fluence (n/cm2)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 1 1.05 1.05 1.03E+17 1.70E+17 1.57E+17 1.44E+17 1.50E+17 1.76E+17 1.97E+17 1.97E+17 2 0.74 1.79 1.76E+17 2.90E+17 2.67E+17 2.44E+17 2.55E+17 2.99E+17 3.35E+17 3.35E+17 3 0.69 2.48 2.43E+17 4.01E+17 3.70E+17 3.38E+17 3.54E+17 4.14E+17 4.65E+17 4.65E+17 4 1.22 3.70 3.63E+17 6.00E+17 5.53E+17 5.06E+17 5.28E+17 6.18E+17 6.94E+17 6.94E+17 5 1.12 4.82 4.63E+17 7.58E+17 6.92E+17 6.27E+17 6.60E+17 7.83E+17 8.85E+17 8.85E+17 6 1.36 6.18 6.16E+17 1.01E+18 9.11E+17 8.21E+17 8.67E+17 1.04E+18 1.17E+18 1.17E+18 7 1.05 7.22 7.35E+17 1.20E+18 1.08E+18 9.70E+17 1.03E+18 1.23E+18 1.40E+18 1.40E+18 8 1.18 8.41 8.68E+17 1.41E+18 1.27E+18 1.14E+18 1.21E+18 1.45E+18 1.65E+18 1.65E+18 9 1.29 9.70 1.01E+18 1.65E+18 1.48E+18 1.32E+18 1.40E+18 1.69E+18 1.92E+18 1.92E+18 10 1.31 11.01 1.11E+18 1.83E+18 1.66E+18 1.49E+18 1.58E+18 1.87E+18 2.10E+18 2.10E+18 11 1.21 12.22 1.19E+18 1.98E+18 1.82E+18 1.65E+18 1.74E+18 2.02E+18 2.25E+18 2.25E+18 12 1.27 13.48 1.29E+18 2.15E+18 2.01E+18 1.83E+18 1.91E+18 2.20E+18 2.43E+18 2.43E+18 13 1.14 14.62 1.37E+18 2.29E+18 2.16E+18 1.97E+18 2.06E+18 2.34E+18 2.57E+18 2.57E+18 14 1.18 15.80 1.45E+18 2.44E+18 2.31E+18 2.12E+18 2.21E+18 2.49E+18 2.72E+18 2.72E+18 15 1.62 17.42 1.57E+18 2.65E+18 2.50E+18 2.29E+18 2.39E+18 2.70E+18 2.96E+18 2.96E+18 16 1.44 18.86 1.69E+18 2.85E+18 2.69E+18 2.47E+18 2.57E+18 2.90E+18 3.17E+18 3.17E+18 17 1.39 20.26 1.79E+18 3.01E+18 2.85E+18 2.62E+18 2.72E+18 3.07E+18 3.36E+18 3.36E+18 18 1.40 21.66 1.89E+18 3.19E+18 3.01E+18 2.77E+18 2.88E+18 3.24E+18 3.55E+18 3.55E+18 19 1.42 23.08 2.00E+18 3.36E+18 3.18E+18 2.93E+18 3.03E+18 3.42E+18 3.74E+18 3.74E+18 20 1.27 24.35 2.09E+18 3.52E+18 3.33E+18 3.07E+18 3.18E+18 3.58E+18 3.92E+18 3.92E+18 21 1.38 25.73 2.20E+18 3.69E+18 3.49E+18 3.21E+18 3.33E+18 3.76E+18 4.12E+18 4.12E+18 22 1.35 27.08 2.31E+18 3.87E+18 3.65E+18 3.35E+18 3.48E+18 3.94E+18 4.33E+18 4.33E+18 23 1.31 28.39 2.42E+18 4.05E+18 3.81E+18 3.51E+18 3.64E+18 4.13E+18 4.53E+18 4.53E+18 24 1.29 29.67 2.54E+18 4.26E+18 4.00E+18 3.68E+18 3.82E+18 4.33E+18 4.76E+18 4.76E+18 25 1.33 31.00 2.68E+18 4.49E+18 4.21E+18 3.87E+18 4.02E+18 4.57E+18 5.03E+18 5.03E+18 26 1.33 32.33 2.83E+18 4.72E+18 4.43E+18 4.07E+18 4.22E+18 4.81E+18 5.30E+18 5.30E+18

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 50 of 53 Table 4-22 Fast Neutron (E > 0.1 MeV) Fluence at the Bioshield Concrete Cycle Cumulative Fast Neutron (E > 0.1 MeV) Fluence (n/cm2)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 27 1.30 33.64 2.95E+18 4.92E+18 4.60E+18 4.23E+18 4.39E+18 5.02E+18 5.54E+18 5.54E+18 28 1.30 34.94 3.07E+18 5.12E+18 4.78E+18 4.39E+18 4.56E+18 5.21E+18 5.75E+18 5.75E+18 29 1.37 36.31 3.20E+18 5.33E+18 4.97E+18 4.56E+18 4.73E+18 5.43E+18 6.00E+18 6.00E+18

[1]

30 1.35 37.66 3.33E+18 5.54E+18 5.16E+18 4.73E+18 4.91E+18 5.64E+18 6.24E+18 6.24E+18 Projections with no bias on the peripheral and re-entrant corner assembly relative powers

[2]

Future -- 42.00 3.74E+18 6.20E+18 5.75E+18 5.27E+18 5.48E+18 6.32E+18 7.02E+18 7.02E+18

[2]

Future -- 48.00 4.31E+18 7.12E+18 6.58E+18 6.01E+18 6.25E+18 7.26E+18 8.09E+18 8.09E+18

[2]

Future -- 54.00 4.88E+18 8.05E+18 7.40E+18 6.75E+18 7.03E+18 8.20E+18 9.16E+18 9.16E+18

[2]

Future -- 60.00 5.45E+18 8.97E+18 8.22E+18 7.49E+18 7.81E+18 9.14E+18 1.02E+19 1.02E+19 Future[2] -- 66.00 6.02E+18 9.89E+18 9.04E+18 8.23E+18 8.58E+18 1.01E+19 1.13E+19 1.13E+19

[2]

Future -- 72.00 6.60E+18 1.08E+19 9.86E+18 8.97E+18 9.36E+18 1.10E+19 1.24E+19 1.24E+19 Projections with a +10% bias on the peripheral and re-entrant corner assembly relative powers

[2]

Future -- 42.00 3.77E+18 6.26E+18 5.81E+18 5.32E+18 5.52E+18 6.38E+18 7.08E+18 7.08E+18

[2]

Future -- 48.00 4.39E+18 7.26E+18 6.70E+18 6.12E+18 6.37E+18 7.40E+18 8.25E+18 8.25E+18

[2]

Future -- 54.00 5.01E+18 8.26E+18 7.59E+18 6.93E+18 7.21E+18 8.42E+18 9.41E+18 9.41E+18

[2]

Future -- 60.00 5.63E+18 9.26E+18 8.48E+18 7.73E+18 8.06E+18 9.44E+18 1.06E+19 1.06E+19

[2]

Future -- 66.00 6.25E+18 1.03E+19 9.38E+18 8.54E+18 8.90E+18 1.05E+19 1.17E+19 1.17E+19

[2]

Future -- 72.00 6.87E+18 1.13E+19 1.03E+19 9.34E+18 9.74E+18 1.15E+19 1.29E+19 1.29E+19 Note(s):

1. Cycle 30 was the current operating cycle at the time the exposures reported in this table were determined. Values listed are based on the projected EFPY for this cycle.

2. Values beyond Cycle 30 are based on the average core power distributions and reactor operating conditions of Cycle 29 and are determined both with and without a 1.1 bias on the peripheral and re-entrant corner assembly relative powers.

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 51 of 53 Table 4-23 Gamma Dose at the Bioshield Concrete Cycle Cumulative Gamma Dose (Gy)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 1 1.05 1.05 3.05E+05 5.45E+05 5.16E+05 4.99E+05 5.24E+05 5.81E+05 6.37E+05 6.38E+05 2 0.74 1.79 5.18E+05 9.27E+05 8.77E+05 8.49E+05 8.91E+05 9.88E+05 1.08E+06 1.09E+06 3 0.69 2.48 7.18E+05 1.29E+06 1.22E+06 1.18E+06 1.23E+06 1.37E+06 1.50E+06 1.50E+06 4 1.22 3.70 1.07E+06 1.92E+06 1.82E+06 1.76E+06 1.84E+06 2.05E+06 2.24E+06 2.25E+06 5 1.12 4.82 1.36E+06 2.42E+06 2.27E+06 2.18E+06 2.30E+06 2.58E+06 2.85E+06 2.86E+06 6 1.36 6.18 1.81E+06 3.73E+06 3.45E+06 3.26E+06 3.49E+06 3.95E+06 4.34E+06 4.35E+06 7 1.05 7.22 2.16E+06 4.75E+06 4.36E+06 4.10E+06 4.41E+06 5.00E+06 5.49E+06 5.50E+06 8 1.18 8.41 2.56E+06 5.89E+06 5.39E+06 5.04E+06 5.44E+06 6.18E+06 6.79E+06 6.81E+06 9 1.29 9.70 2.99E+06 7.15E+06 6.52E+06 6.07E+06 6.58E+06 7.48E+06 8.21E+06 8.23E+06 10 1.31 11.01 3.30E+06 8.07E+06 7.53E+06 7.05E+06 7.59E+06 8.44E+06 9.13E+06 9.15E+06 11 1.21 12.22 3.56E+06 8.88E+06 8.48E+06 7.99E+06 8.54E+06 9.27E+06 9.87E+06 9.89E+06 12 1.27 13.48 3.87E+06 9.83E+06 9.54E+06 9.01E+06 9.62E+06 1.02E+07 1.08E+07 1.08E+07 13 1.14 14.62 4.12E+06 1.06E+07 1.04E+07 9.85E+06 1.05E+07 1.10E+07 1.15E+07 1.15E+07 14 1.18 15.80 4.38E+06 1.14E+07 1.13E+07 1.07E+07 1.14E+07 1.19E+07 1.23E+07 1.23E+07 15 1.62 17.42 4.76E+06 1.25E+07 1.23E+07 1.17E+07 1.24E+07 1.30E+07 1.34E+07 1.35E+07 16 1.44 18.86 5.12E+06 1.35E+07 1.34E+07 1.27E+07 1.35E+07 1.40E+07 1.45E+07 1.46E+07 17 1.39 20.26 5.42E+06 1.44E+07 1.42E+07 1.36E+07 1.43E+07 1.49E+07 1.55E+07 1.55E+07 18 1.40 21.66 5.74E+06 1.52E+07 1.51E+07 1.45E+07 1.52E+07 1.58E+07 1.64E+07 1.65E+07 19 1.42 23.08 6.06E+06 1.61E+07 1.60E+07 1.53E+07 1.61E+07 1.68E+07 1.74E+07 1.74E+07 20 1.27 24.35 6.36E+06 1.70E+07 1.69E+07 1.61E+07 1.70E+07 1.76E+07 1.83E+07 1.83E+07 21 1.38 25.73 6.68E+06 1.79E+07 1.77E+07 1.69E+07 1.78E+07 1.86E+07 1.93E+07 1.93E+07 22 1.35 27.08 7.01E+06 1.88E+07 1.85E+07 1.77E+07 1.87E+07 1.95E+07 2.03E+07 2.04E+07 23 1.31 28.39 7.34E+06 1.97E+07 1.94E+07 1.86E+07 1.96E+07 2.05E+07 2.13E+07 2.14E+07 24 1.29 29.67 7.71E+06 2.08E+07 2.05E+07 1.96E+07 2.06E+07 2.16E+07 2.25E+07 2.26E+07 25 1.33 31.00 8.15E+06 2.20E+07 2.16E+07 2.07E+07 2.17E+07 2.28E+07 2.39E+07 2.39E+07 26 1.33 32.33 8.58E+06 2.32E+07 2.27E+07 2.18E+07 2.29E+07 2.41E+07 2.52E+07 2.53E+07

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 52 of 53 Table 4-23 Gamma Dose at the Bioshield Concrete Cycle Cumulative Gamma Dose (Gy)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 27 1.30 33.64 8.95E+06 2.42E+07 2.37E+07 2.27E+07 2.38E+07 2.52E+07 2.64E+07 2.65E+07 28 1.30 34.94 9.31E+06 2.52E+07 2.46E+07 2.36E+07 2.48E+07 2.62E+07 2.75E+07 2.76E+07 29 1.37 36.31 9.70E+06 2.63E+07 2.56E+07 2.45E+07 2.58E+07 2.73E+07 2.88E+07 2.88E+07

[1]

30 1.35 37.66 1.01E+07 2.74E+07 2.66E+07 2.55E+07 2.68E+07 2.84E+07 3.00E+07 3.01E+07 Projections with no bias on the peripheral and re-entrant corner assembly relative powers

[2]

Future -- 42.00 1.13E+07 3.08E+07 2.98E+07 2.85E+07 2.99E+07 3.20E+07 3.39E+07 3.40E+07

[2]

Future -- 48.00 1.30E+07 3.55E+07 3.41E+07 3.26E+07 3.43E+07 3.69E+07 3.93E+07 3.94E+07

[2]

Future -- 54.00 1.47E+07 4.03E+07 3.85E+07 3.68E+07 3.87E+07 4.18E+07 4.48E+07 4.49E+07

[2]

Future -- 60.00 1.65E+07 4.50E+07 4.28E+07 4.09E+07 4.30E+07 4.68E+07 5.02E+07 5.03E+07 Future[2] -- 66.00 1.82E+07 4.97E+07 4.72E+07 4.50E+07 4.74E+07 5.17E+07 5.56E+07 5.58E+07

[2]

Future -- 72.00 1.99E+07 5.44E+07 5.15E+07 4.92E+07 5.18E+07 5.66E+07 6.10E+07 6.12E+07 Projections with a +10% bias on the peripheral and re-entrant corner assembly relative powers

[2]

Future -- 42.00 1.14E+07 3.11E+07 3.01E+07 2.88E+07 3.02E+07 3.23E+07 3.42E+07 3.43E+07

[2]

Future -- 48.00 1.33E+07 3.62E+07 3.48E+07 3.33E+07 3.50E+07 3.77E+07 4.01E+07 4.03E+07

[2]

Future -- 54.00 1.51E+07 4.14E+07 3.95E+07 3.78E+07 3.97E+07 4.30E+07 4.60E+07 4.62E+07

[2]

Future -- 60.00 1.70E+07 4.65E+07 4.43E+07 4.23E+07 4.45E+07 4.84E+07 5.19E+07 5.21E+07

[2]

Future -- 66.00 1.89E+07 5.17E+07 4.90E+07 4.68E+07 4.92E+07 5.37E+07 5.78E+07 5.80E+07

[2]

Future -- 72.00 2.07E+07 5.68E+07 5.37E+07 5.13E+07 5.40E+07 5.91E+07 6.37E+07 6.39E+07 Note(s):

1. Cycle 30 was the current operating cycle at the time the exposures reported in this table were determined. Values listed are based on the projected EFPY for this cycle.

2. Values beyond Cycle 30 are based on the average core power distributions and reactor operating conditions of Cycle 29 and are determined both with and without a 1.1 bias on the peripheral and re-entrant corner assembly relative powers.

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-1-NP, Revision 1 May 26, 2021 Page 53 of 53 References

1. USNRC Regulatory Guide 1.190, Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence, Office of Nuclear Regulatory Research, March 2001.

2. Westinghouse Report WCAP-18124-NP-A, Revision 0, Fluence Determination with RAPTOR-M3G and FERRET, July 2018.

3. Westinghouse InfoGram IG-13-2, Fluence Attenuation Profile in Reactor Pressure Vessel Shell and Inlet/Outlet Nozzle Regions, July 2013.

- - This record was final approved on 5/26/2021 1:32:42 PM. (This statement was added by the PRIME system upon its validation)

St. Lucie Nuclear Plant Units 1 and 2 Dockets 50-335 and 50-389 L-2021-192 Enclosure 4 Enclosure 4 Non-proprietary Reference Documents and Redacted Versions of Proprietary Reference Documents (Public Version)

Attachment 2 Westinghouse Report LTR-REA-21-2-NP, Revision 1, St. Lucie Units 1 & 2 Subsequent License Renewal:

Unit 2 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, June 7, 2021 (59 Total Pages, including cover sheets)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 11 of 56 Table 4-1 Fast Neutron (E > 1.0 MeV) Fluence Rate at the RPV Clad/Base Metal Interface Cycle Cumulative Fluence Rate (n/cm2-s)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 1 1.11 1.11 3.19E+10 2.03E+10 1.71E+10 1.26E+10 1.71E+10 1.97E+10 3.19E+10 3.19E+10 2 1.12 2.23 3.36E+10 1.98E+10 1.71E+10 1.28E+10 1.71E+10 1.93E+10 3.37E+10 3.37E+10 3 1.22 3.45 3.01E+10 1.80E+10 1.47E+10 1.07E+10 1.47E+10 1.75E+10 3.02E+10 3.02E+10 4 1.16 4.61 2.05E+10 1.61E+10 1.56E+10 1.18E+10 1.56E+10 1.58E+10 2.05E+10 2.05E+10 5 1.30 5.91 1.99E+10 1.61E+10 1.55E+10 1.13E+10 1.55E+10 1.57E+10 1.99E+10 2.00E+10 6 1.35 7.26 2.14E+10 1.37E+10 1.22E+10 9.79E+09 1.22E+10 1.34E+10 2.14E+10 2.14E+10 7 1.21 8.47 2.31E+10 1.44E+10 1.21E+10 1.02E+10 1.21E+10 1.40E+10 2.32E+10 2.32E+10 8 1.38 9.85 1.40E+10 1.10E+10 1.30E+10 1.01E+10 1.30E+10 1.08E+10 1.41E+10 1.41E+10 9 1.22 11.07 1.92E+10 1.58E+10 1.39E+10 1.00E+10 1.39E+10 1.55E+10 1.92E+10 1.98E+10 10 1.44 12.51 2.05E+10 1.59E+10 1.37E+10 1.06E+10 1.37E+10 1.55E+10 2.05E+10 2.09E+10 11 1.32 13.83 1.92E+10 1.42E+10 1.43E+10 1.16E+10 1.43E+10 1.39E+10 1.92E+10 1.92E+10 12 1.51 15.34 1.94E+10 1.25E+10 1.23E+10 1.07E+10 1.23E+10 1.22E+10 1.94E+10 1.94E+10 13 1.29 16.63 2.14E+10 1.41E+10 1.30E+10 1.14E+10 1.30E+10 1.38E+10 2.14E+10 2.14E+10 14 1.43 18.06 1.87E+10 1.27E+10 1.23E+10 1.06E+10 1.23E+10 1.24E+10 1.87E+10 1.87E+10 15 1.15 19.21 2.18E+10 1.41E+10 1.20E+10 9.78E+09 1.20E+10 1.37E+10 2.19E+10 2.19E+10 16 1.25 20.46 2.22E+10 1.46E+10 1.23E+10 9.93E+09 1.23E+10 1.42E+10 2.22E+10 2.22E+10 17 1.25 21.71 2.08E+10 1.40E+10 1.18E+10 9.70E+09 1.18E+10 1.38E+10 2.16E+10 2.16E+10 18 1.42 23.13 2.00E+10 1.42E+10 1.21E+10 1.00E+10 1.19E+10 1.39E+10 2.01E+10 2.02E+10 19 1.19 24.32 2.54E+10 1.75E+10 1.65E+10 1.29E+10 1.65E+10 1.68E+10 2.52E+10 2.54E+10 20 1.23 25.55 2.99E+10 1.95E+10 1.86E+10 1.54E+10 1.86E+10 1.90E+10 2.99E+10 2.99E+10 21 1.28 26.83 2.85E+10 1.89E+10 1.84E+10 1.50E+10 1.83E+10 1.84E+10 2.85E+10 2.85E+10 22 1.31 28.13 3.30E+10 2.13E+10 1.92E+10 1.68E+10 1.92E+10 2.07E+10 3.31E+10 3.31E+10 23 1.40 29.53 3.30E+10 2.14E+10 2.12E+10 1.70E+10 2.12E+10 2.09E+10 3.30E+10 3.30E+10 24 1.34 30.88 3.01E+10 1.95E+10 1.84E+10 1.46E+10 1.84E+10 1.90E+10 3.02E+10 3.02E+10 25[1] 1.43 32.30 2.88E+10 1.87E+10 1.79E+10 1.38E+10 1.80E+10 1.85E+10 2.92E+10 2.92E+10 Note(s):

1. Cycle 25 was the current operating cycle at the time this summary report was authored.

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 12 of 56 Table 4-2 Fast Neutron (E > 1.0 MeV) Fluence at the RPV Clad/Base Metal Interface Cycle Cumulative Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 1 1.11 1.11 1.12E+18 7.10E+17 5.99E+17 4.41E+17 5.99E+17 6.91E+17 1.12E+18 1.12E+18 2 1.12 2.23 2.30E+18 1.41E+18 1.20E+18 8.92E+17 1.20E+18 1.37E+18 2.30E+18 2.30E+18 3 1.22 3.45 3.46E+18 2.10E+18 1.77E+18 1.30E+18 1.77E+18 2.04E+18 3.46E+18 3.46E+18 4 1.16 4.61 4.20E+18 2.68E+18 2.33E+18 1.73E+18 2.33E+18 2.61E+18 4.20E+18 4.20E+18 5 1.30 5.91 5.00E+18 3.33E+18 2.96E+18 2.19E+18 2.96E+18 3.25E+18 5.00E+18 5.00E+18 6 1.35 7.26 5.90E+18 3.90E+18 3.47E+18 2.60E+18 3.47E+18 3.81E+18 5.91E+18 5.91E+18 7 1.21 8.47 6.78E+18 4.45E+18 3.93E+18 2.99E+18 3.93E+18 4.34E+18 6.79E+18 6.79E+18 8 1.38 9.85 7.37E+18 4.92E+18 4.48E+18 3.42E+18 4.48E+18 4.80E+18 7.38E+18 7.38E+18 9 1.22 11.07 8.11E+18 5.53E+18 5.02E+18 3.80E+18 5.02E+18 5.40E+18 8.13E+18 8.13E+18 10 1.44 12.51 9.05E+18 6.25E+18 5.64E+18 4.29E+18 5.64E+18 6.10E+18 9.06E+18 9.06E+18 11 1.32 13.83 9.84E+18 6.83E+18 6.23E+18 4.76E+18 6.23E+18 6.67E+18 9.85E+18 9.85E+18 12 1.51 15.34 1.08E+19 7.43E+18 6.81E+18 5.27E+18 6.81E+18 7.25E+18 1.08E+19 1.08E+19 13 1.29 16.63 1.16E+19 8.00E+18 7.34E+18 5.73E+18 7.34E+18 7.81E+18 1.16E+19 1.16E+19 14 1.43 18.06 1.25E+19 8.57E+18 7.89E+18 6.21E+18 7.89E+18 8.36E+18 1.25E+19 1.25E+19 15 1.15 19.21 1.32E+19 9.08E+18 8.33E+18 6.56E+18 8.32E+18 8.86E+18 1.33E+19 1.33E+19 16 1.25 20.46 1.41E+19 9.65E+18 8.81E+18 6.95E+18 8.81E+18 9.41E+18 1.41E+19 1.41E+19 17 1.25 21.71 1.49E+19 1.02E+19 9.27E+18 7.33E+18 9.27E+18 9.96E+18 1.50E+19 1.50E+19 18 1.42 23.13 1.58E+19 1.08E+19 9.81E+18 7.78E+18 9.80E+18 1.06E+19 1.59E+19 1.59E+19 19 1.19 24.32 1.68E+19 1.15E+19 1.04E+19 8.26E+18 1.04E+19 1.12E+19 1.68E+19 1.68E+19 20 1.23 25.55 1.79E+19 1.22E+19 1.12E+19 8.86E+18 1.11E+19 1.19E+19 1.80E+19 1.80E+19 21 1.28 26.83 1.91E+19 1.30E+19 1.19E+19 9.46E+18 1.19E+19 1.27E+19 1.91E+19 1.91E+19 22 1.31 28.13 2.04E+19 1.39E+19 1.27E+19 1.02E+19 1.27E+19 1.35E+19 2.05E+19 2.05E+19 23 1.40 29.53 2.19E+19 1.48E+19 1.36E+19 1.09E+19 1.36E+19 1.45E+19 2.19E+19 2.19E+19 24 1.34 30.88 2.32E+19 1.57E+19 1.44E+19 1.15E+19 1.44E+19 1.53E+19 2.32E+19 2.32E+19 25[1] 1.43 32.30 2.45E+19 1.65E+19 1.52E+19 1.21E+19 1.52E+19 1.61E+19 2.45E+19 2.45E+19

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 13 of 56 Table 4-2 Fast Neutron (E > 1.0 MeV) Fluence at the RPV Clad/Base Metal Interface Cycle Cumulative Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum Projections with no bias on the peripheral and re-entrant corner assembly relative powers Future[2] -- 36.00 2.80E+19 1.88E+19 1.74E+19 1.38E+19 1.73E+19 1.83E+19 2.81E+19 2.81E+19 Future[2] -- 42.00 3.37E+19 2.25E+19 2.08E+19 1.66E+19 2.08E+19 2.19E+19 3.38E+19 3.38E+19 Future[2] -- 48.00 3.94E+19 2.62E+19 2.43E+19 1.94E+19 2.43E+19 2.55E+19 3.95E+19 3.95E+19 Future[2] -- 54.00 4.51E+19 2.99E+19 2.78E+19 2.21E+19 2.78E+19 2.91E+19 4.52E+19 4.52E+19 Future[2] -- 60.00 5.08E+19 3.36E+19 3.13E+19 2.49E+19 3.12E+19 3.27E+19 5.09E+19 5.09E+19 Future[2] -- 66.00 5.65E+19 3.73E+19 3.48E+19 2.76E+19 3.47E+19 3.63E+19 5.66E+19 5.66E+19 Future[2] -- 72.00 6.22E+19 4.10E+19 3.82E+19 3.04E+19 3.82E+19 3.99E+19 6.23E+19 6.23E+19 Projections with a +10% bias on the peripheral and re-entrant corner assembly relative powers Future[2] -- 36.00 2.83E+19 1.90E+19 1.76E+19 1.40E+19 1.75E+19 1.85E+19 2.84E+19 2.84E+19 Future[2] -- 42.00 3.45E+19 2.30E+19 2.14E+19 1.70E+19 2.13E+19 2.24E+19 3.46E+19 3.46E+19 Future[2] -- 48.00 4.07E+19 2.70E+19 2.52E+19 2.01E+19 2.51E+19 2.64E+19 4.08E+19 4.08E+19 Future[2] -- 54.00 4.69E+19 3.11E+19 2.90E+19 2.31E+19 2.90E+19 3.03E+19 4.70E+19 4.70E+19 Future[2] -- 60.00 5.31E+19 3.51E+19 3.28E+19 2.61E+19 3.28E+19 3.42E+19 5.32E+19 5.32E+19 Future[2] -- 66.00 5.93E+19 3.91E+19 3.66E+19 2.91E+19 3.66E+19 3.81E+19 5.94E+19 5.94E+19 Future[2] -- 72.00 6.55E+19 4.31E+19 4.04E+19 3.22E+19 4.04E+19 4.21E+19 6.56E+19 6.56E+19 Note(s):

1. Cycle 25 was the current operating cycle at the time this summary report was authored.

2. Values beyond Cycle 25 are based on the average core power distributions and reactor operating conditions of Cycle 24 and are determined both with and without a 1.1 bias on the peripheral and re-entrant corner assembly relative powers.

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 14 of 56 Table 4-3 Iron Atom Displacement Rate at the RPV Clad/Base Metal Interface Cycle Cumulative Iron Atom Displacement Rate (dpa/s)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 1 1.11 1.11 4.86E-11 3.11E-11 2.61E-11 1.94E-11 2.61E-11 3.04E-11 4.86E-11 4.86E-11 2 1.12 2.23 5.13E-11 3.04E-11 2.61E-11 1.97E-11 2.61E-11 2.98E-11 5.12E-11 5.13E-11 3 1.22 3.45 4.59E-11 2.76E-11 2.25E-11 1.65E-11 2.25E-11 2.71E-11 4.58E-11 4.59E-11 4 1.16 4.61 3.13E-11 2.47E-11 2.38E-11 1.81E-11 2.38E-11 2.43E-11 3.13E-11 3.14E-11 5 1.30 5.91 3.05E-11 2.47E-11 2.37E-11 1.75E-11 2.37E-11 2.43E-11 3.04E-11 3.06E-11 6 1.35 7.26 3.27E-11 2.11E-11 1.86E-11 1.51E-11 1.86E-11 2.07E-11 3.26E-11 3.27E-11 7 1.21 8.47 3.53E-11 2.21E-11 1.86E-11 1.57E-11 1.86E-11 2.17E-11 3.53E-11 3.53E-11 8 1.38 9.85 2.15E-11 1.69E-11 1.99E-11 1.56E-11 1.99E-11 1.66E-11 2.14E-11 2.15E-11 9 1.22 11.07 2.94E-11 2.43E-11 2.12E-11 1.54E-11 2.12E-11 2.38E-11 2.93E-11 3.02E-11 10 1.44 12.51 3.14E-11 2.44E-11 2.09E-11 1.63E-11 2.09E-11 2.39E-11 3.13E-11 3.19E-11 11 1.32 13.83 2.94E-11 2.19E-11 2.18E-11 1.78E-11 2.18E-11 2.15E-11 2.93E-11 2.94E-11 12 1.51 15.34 2.97E-11 1.93E-11 1.89E-11 1.65E-11 1.89E-11 1.89E-11 2.96E-11 2.97E-11 13 1.29 16.63 3.27E-11 2.17E-11 2.00E-11 1.75E-11 2.00E-11 2.13E-11 3.26E-11 3.27E-11 14 1.43 18.06 2.86E-11 1.95E-11 1.88E-11 1.63E-11 1.88E-11 1.91E-11 2.85E-11 2.86E-11 15 1.15 19.21 3.34E-11 2.17E-11 1.84E-11 1.51E-11 1.84E-11 2.12E-11 3.33E-11 3.34E-11 16 1.25 20.46 3.40E-11 2.25E-11 1.88E-11 1.53E-11 1.88E-11 2.20E-11 3.39E-11 3.40E-11 17 1.25 21.71 3.19E-11 2.15E-11 1.81E-11 1.49E-11 1.81E-11 2.14E-11 3.29E-11 3.29E-11 18 1.42 23.13 3.06E-11 2.17E-11 1.85E-11 1.55E-11 1.83E-11 2.15E-11 3.08E-11 3.09E-11 19 1.19 24.32 3.89E-11 2.69E-11 2.52E-11 1.98E-11 2.52E-11 2.60E-11 3.84E-11 3.89E-11 20 1.23 25.55 4.57E-11 3.00E-11 2.84E-11 2.36E-11 2.84E-11 2.93E-11 4.56E-11 4.57E-11 21 1.28 26.83 4.36E-11 2.91E-11 2.81E-11 2.31E-11 2.79E-11 2.84E-11 4.35E-11 4.36E-11 22 1.31 28.13 5.05E-11 3.28E-11 2.93E-11 2.58E-11 2.93E-11 3.20E-11 5.04E-11 5.05E-11 23 1.40 29.53 5.04E-11 3.29E-11 3.23E-11 2.61E-11 3.23E-11 3.22E-11 5.03E-11 5.04E-11 24 1.34 30.88 4.60E-11 3.00E-11 2.81E-11 2.24E-11 2.80E-11 2.94E-11 4.60E-11 4.60E-11 25[1] 1.43 32.30 4.41E-11 2.87E-11 2.74E-11 2.12E-11 2.74E-11 2.86E-11 4.44E-11 4.44E-11 Note(s):

1. Cycle 25 was the current operating cycle at the time this summary report was authored.

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 15 of 56 Table 4-4 Iron Atom Displacements at the RPV Clad/Base Metal Interface Cycle Cumulative Iron Atom Displacements (dpa)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 1 1.11 1.11 1.70E-03 1.09E-03 9.14E-04 6.79E-04 9.14E-04 1.07E-03 1.70E-03 1.70E-03 2 1.12 2.23 3.51E-03 2.16E-03 1.83E-03 1.37E-03 1.83E-03 2.11E-03 3.50E-03 3.51E-03 3 1.22 3.45 5.28E-03 3.22E-03 2.70E-03 2.01E-03 2.70E-03 3.15E-03 5.27E-03 5.28E-03 4 1.16 4.61 6.40E-03 4.11E-03 3.56E-03 2.66E-03 3.55E-03 4.03E-03 6.39E-03 6.40E-03 5 1.30 5.91 7.63E-03 5.11E-03 4.52E-03 3.37E-03 4.52E-03 5.02E-03 7.62E-03 7.63E-03 6 1.35 7.26 9.01E-03 6.00E-03 5.30E-03 4.00E-03 5.29E-03 5.88E-03 8.99E-03 9.01E-03 7 1.21 8.47 1.04E-02 6.84E-03 6.00E-03 4.60E-03 6.00E-03 6.71E-03 1.03E-02 1.04E-02 8 1.38 9.85 1.13E-02 7.56E-03 6.84E-03 5.26E-03 6.84E-03 7.41E-03 1.12E-02 1.13E-02 9 1.22 11.07 1.24E-02 8.49E-03 7.66E-03 5.86E-03 7.66E-03 8.33E-03 1.24E-02 1.24E-02 10 1.44 12.51 1.38E-02 9.60E-03 8.61E-03 6.60E-03 8.61E-03 9.42E-03 1.38E-02 1.38E-02 11 1.32 13.83 1.50E-02 1.05E-02 9.52E-03 7.33E-03 9.51E-03 1.03E-02 1.50E-02 1.50E-02 12 1.51 15.34 1.64E-02 1.14E-02 1.04E-02 8.12E-03 1.04E-02 1.12E-02 1.64E-02 1.64E-02 13 1.29 16.63 1.78E-02 1.23E-02 1.12E-02 8.83E-03 1.12E-02 1.21E-02 1.77E-02 1.78E-02 14 1.43 18.06 1.91E-02 1.32E-02 1.21E-02 9.56E-03 1.21E-02 1.29E-02 1.90E-02 1.91E-02 15 1.15 19.21 2.03E-02 1.40E-02 1.27E-02 1.01E-02 1.27E-02 1.37E-02 2.02E-02 2.03E-02 16 1.25 20.46 2.16E-02 1.48E-02 1.35E-02 1.07E-02 1.35E-02 1.45E-02 2.15E-02 2.16E-02 17 1.25 21.71 2.28E-02 1.57E-02 1.42E-02 1.13E-02 1.42E-02 1.54E-02 2.28E-02 2.28E-02 18 1.42 23.13 2.42E-02 1.66E-02 1.50E-02 1.20E-02 1.50E-02 1.63E-02 2.42E-02 2.42E-02 19 1.19 24.32 2.57E-02 1.77E-02 1.59E-02 1.27E-02 1.59E-02 1.73E-02 2.56E-02 2.57E-02 20 1.23 25.55 2.74E-02 1.88E-02 1.70E-02 1.36E-02 1.70E-02 1.85E-02 2.74E-02 2.74E-02 21 1.28 26.83 2.92E-02 2.00E-02 1.82E-02 1.46E-02 1.82E-02 1.96E-02 2.92E-02 2.92E-02 22 1.31 28.13 3.13E-02 2.13E-02 1.94E-02 1.56E-02 1.94E-02 2.09E-02 3.12E-02 3.13E-02 23 1.40 29.53 3.35E-02 2.28E-02 2.08E-02 1.68E-02 2.08E-02 2.23E-02 3.34E-02 3.35E-02 24 1.34 30.88 3.54E-02 2.41E-02 2.20E-02 1.77E-02 2.20E-02 2.36E-02 3.54E-02 3.54E-02 25[1] 1.43 32.30 3.74E-02 2.54E-02 2.32E-02 1.87E-02 2.32E-02 2.49E-02 3.74E-02 3.74E-02

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 16 of 56 Table 4-4 Iron Atom Displacements at the RPV Clad/Base Metal Interface Cycle Cumulative Iron Atom Displacements (dpa)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum Projections with no bias on the peripheral and re-entrant corner assembly relative powers Future[2] -- 36.00 4.28E-02 2.89E-02 2.65E-02 2.13E-02 2.65E-02 2.83E-02 4.28E-02 4.28E-02 Future[2] -- 42.00 5.15E-02 3.45E-02 3.18E-02 2.55E-02 3.18E-02 3.39E-02 5.15E-02 5.15E-02 Future[2] -- 48.00 6.02E-02 4.02E-02 3.71E-02 2.98E-02 3.71E-02 3.94E-02 6.02E-02 6.02E-02 Future[2] -- 54.00 6.89E-02 4.59E-02 4.25E-02 3.40E-02 4.24E-02 4.50E-02 6.89E-02 6.89E-02 Future[2] -- 60.00 7.76E-02 5.16E-02 4.78E-02 3.83E-02 4.77E-02 5.06E-02 7.76E-02 7.76E-02 Future[2] -- 66.00 8.63E-02 5.73E-02 5.31E-02 4.25E-02 5.30E-02 5.61E-02 8.63E-02 8.63E-02 Future[2] -- 72.00 9.51E-02 6.29E-02 5.84E-02 4.68E-02 5.83E-02 6.17E-02 9.50E-02 9.51E-02 Projections with a +10% bias on the peripheral and re-entrant corner assembly relative powers Future[2] -- 36.00 4.32E-02 2.92E-02 2.68E-02 2.16E-02 2.68E-02 2.86E-02 4.32E-02 4.32E-02 Future[2] -- 42.00 5.27E-02 3.54E-02 3.26E-02 2.62E-02 3.26E-02 3.47E-02 5.27E-02 5.27E-02 Future[2] -- 48.00 6.22E-02 4.15E-02 3.85E-02 3.09E-02 3.84E-02 4.07E-02 6.21E-02 6.22E-02 Future[2] -- 54.00 7.17E-02 4.77E-02 4.43E-02 3.55E-02 4.42E-02 4.68E-02 7.16E-02 7.17E-02 Future[2] -- 60.00 8.11E-02 5.39E-02 5.01E-02 4.02E-02 5.00E-02 5.29E-02 8.11E-02 8.11E-02 Future[2] -- 66.00 9.06E-02 6.01E-02 5.59E-02 4.48E-02 5.58E-02 5.89E-02 9.05E-02 9.06E-02 Future[2] -- 72.00 1.00E-01 6.63E-02 6.17E-02 4.95E-02 6.16E-02 6.50E-02 1.00E-01 1.00E-01 Note(s):

1. Cycle 25 was the current operating cycle at the time this summary report was authored.

2. Values beyond Cycle 25 are based on the average core power distributions and reactor operating conditions of Cycle 24 and are determined both with and without a 1.1 bias on the peripheral and re-entrant corner assembly relative powers.

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 17 of 56 Table 4-5 Fast Neutron (E > 1.0 MeV) Fluence at the RPV Welds and Shells Projections with no bias on the peripheral and re-entrant corner assembly relative powers Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

Material 32.30 EFPY[1] 36 EFPY 42 EFPY 48 EFPY Inlet-nozzle-to-upper-shell weld (lowest extent) 2.89E+16 3.29E+16 3.93E+16 4.58E+16 Outlet-nozzle-to-upper-shell weld (lowest extent) 3.97E+16 4.51E+16 5.39E+16 6.27E+16

[2]

Upper Shell 6.47E+17 7.23E+17 8.47E+17 9.70E+17 Upper-to-Intermediate-Shell Circumferential Weld 7.46E+17 8.34E+17 9.77E+17 1.12E+18 Intermediate Shell 2.45E+19 2.81E+19 3.38E+19 3.95E+19 Intermediate Shell Longitudinal Weld - 15° 1.65E+19 1.88E+19 2.25E+19 2.62E+19 Intermediate Shell Longitudinal Weld - 135° 1.21E+19 1.38E+19 1.66E+19 1.94E+19

[3]

Intermediate Shell Longitudinal Weld - 255° 1.65E+19 1.88E+19 2.25E+19 2.62E+19 Intermediate-to-Lower-Shell Circumferential Weld 2.44E+19 2.79E+19 3.35E+19 3.92E+19 Lower Shell 2.44E+19 2.79E+19 3.36E+19 3.93E+19 Lower Shell Longitudinal Weld - 15° 1.64E+19 1.86E+19 2.23E+19 2.60E+19 Lower Shell Longitudinal Weld - 135° 1.21E+19 1.37E+19 1.65E+19 1.92E+19

[3]

Lower Shell Longitudinal Weld - 255° 1.64E+19 1.86E+19 2.23E+19 2.60E+19 Lower-Shell-to-Bottom-Head Circumferential Weld 2.41E+16 2.75E+16 3.29E+16 3.83E+16 Projections with no bias on the peripheral and re-entrant corner assembly relative powers Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

Material 54 EFPY 60 EFPY 66 EFPY 72 EFPY Inlet-nozzle-to-upper-shell weld (lowest extent) 5.22E+16 5.86E+16 6.50E+16 7.15E+16 Outlet-nozzle-to-upper-shell weld (lowest extent) 7.15E+16 8.03E+16 8.91E+16 9.79E+16

[2]

Upper Shell 1.09E+18 1.22E+18 1.34E+18 1.46E+18 Upper-to-Intermediate-Shell Circumferential Weld 1.26E+18 1.41E+18 1.55E+18 1.69E+18 Intermediate Shell 4.52E+19 5.09E+19 5.66E+19 6.23E+19 Intermediate Shell Longitudinal Weld - 15° 2.99E+19 3.36E+19 3.73E+19 4.10E+19 Intermediate Shell Longitudinal Weld - 135° 2.21E+19 2.49E+19 2.76E+19 3.04E+19

[3]

Intermediate Shell Longitudinal Weld - 255° 2.99E+19 3.36E+19 3.73E+19 4.10E+19 Intermediate-to-Lower-Shell Circumferential Weld 4.49E+19 5.06E+19 5.62E+19 6.19E+19 Lower Shell 4.50E+19 5.07E+19 5.64E+19 6.21E+19 Lower Shell Longitudinal Weld - 15° 2.97E+19 3.34E+19 3.70E+19 4.07E+19 Lower Shell Longitudinal Weld - 135° 2.20E+19 2.47E+19 2.75E+19 3.02E+19

[3]

Lower Shell Longitudinal Weld - 255° 2.97E+19 3.34E+19 3.70E+19 4.07E+19 Lower-Shell-to-Bottom-Head Circumferential Weld 4.37E+16 4.92E+16 5.46E+16 6.00E+16

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 18 of 56 Table 4-5 Fast Neutron (E > 1.0 MeV) Fluence at the RPV Welds and Shells Projections with a +10% bias on the peripheral and re-entrant corner assembly relative powers Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

Material 32.30 EFPY[1] 36 EFPY 42 EFPY 48 EFPY Inlet-nozzle-to-upper-shell weld (lowest extent) 2.89E+16 3.33E+16 4.03E+16 4.73E+16 Outlet-nozzle-to-upper-shell weld (lowest extent) 3.97E+16 4.56E+16 5.52E+16 6.48E+16

[2]

Upper Shell 6.47E+17 7.28E+17 8.60E+17 9.92E+17 Upper-to-Intermediate-Shell Circumferential Weld 7.46E+17 8.40E+17 9.92E+17 1.14E+18 Intermediate Shell 2.45E+19 2.84E+19 3.46E+19 4.08E+19 Intermediate Shell Longitudinal Weld - 15° 1.65E+19 1.90E+19 2.30E+19 2.70E+19 Intermediate Shell Longitudinal Weld - 135° 1.21E+19 1.40E+19 1.70E+19 2.01E+19 Intermediate Shell Longitudinal Weld - 255°[3] 1.65E+19 1.90E+19 2.30E+19 2.70E+19 Intermediate-to-Lower-Shell Circumferential Weld 2.44E+19 2.82E+19 3.43E+19 4.05E+19 Lower Shell 2.44E+19 2.82E+19 3.44E+19 4.06E+19 Lower Shell Longitudinal Weld - 15° 1.64E+19 1.88E+19 2.29E+19 2.69E+19 Lower Shell Longitudinal Weld - 135° 1.21E+19 1.39E+19 1.69E+19 1.99E+19

[3]

Lower Shell Longitudinal Weld - 255° 1.64E+19 1.88E+19 2.29E+19 2.69E+19 Lower-Shell-to-Bottom-Head Circumferential Weld 2.41E+16 2.78E+16 3.37E+16 3.96E+16 Projections with a +10% bias on the peripheral and re-entrant corner assembly relative powers Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

Material 54 EFPY 60 EFPY 66 EFPY 72 EFPY Inlet-nozzle-to-upper-shell weld (lowest extent) 5.43E+16 6.13E+16 6.84E+16 7.54E+16 Outlet-nozzle-to-upper-shell weld (lowest extent) 7.44E+16 8.40E+16 9.36E+16 1.03E+17

[2]

Upper Shell 1.12E+18 1.26E+18 1.39E+18 1.52E+18 Upper-to-Intermediate-Shell Circumferential Weld 1.30E+18 1.45E+18 1.60E+18 1.75E+18 Intermediate Shell 4.70E+19 5.32E+19 5.94E+19 6.56E+19 Intermediate Shell Longitudinal Weld - 15° 3.11E+19 3.51E+19 3.91E+19 4.31E+19 Intermediate Shell Longitudinal Weld - 135° 2.31E+19 2.61E+19 2.91E+19 3.22E+19

[3]

Intermediate Shell Longitudinal Weld - 255° 3.11E+19 3.51E+19 3.91E+19 4.31E+19 Intermediate-to-Lower-Shell Circumferential Weld 4.67E+19 5.28E+19 5.90E+19 6.52E+19 Lower Shell 4.68E+19 5.29E+19 5.91E+19 6.53E+19 Lower Shell Longitudinal Weld - 15° 3.09E+19 3.49E+19 3.89E+19 4.29E+19 Lower Shell Longitudinal Weld - 135° 2.29E+19 2.59E+19 2.89E+19 3.20E+19

[3]

Lower Shell Longitudinal Weld - 255° 3.09E+19 3.49E+19 3.89E+19 4.29E+19 Lower-Shell-to-Bottom-Head Circumferential Weld 4.55E+16 5.14E+16 5.73E+16 6.32E+16 Note(s):

1. Value listed is the projected EFPY at the end of Cycle 25.

2. Exposure values for the upper shell longitudinal welds are bounded by the exposure values for the upper shell.

3. Exposure values for the intermediate shell and lower shell 255° longitudinal welds are bounded by the exposure values for the intermediate shell and lower shell 15° longitudinal welds.

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 19 of 56 Table 4-6 Iron Atom Displacements at the RPV Welds and Shells Projections with no bias on the peripheral and re-entrant corner assembly relative powers Iron Atom Displacements (dpa)

Material [1]

32.30 EFPY 36 EFPY 42 EFPY 48 EFPY Inlet-nozzle-to-upper-shell weld (lowest extent) 2.42E-04 2.75E-04 3.29E-04 3.84E-04 Outlet-nozzle-to-upper-shell weld (lowest extent) 3.16E-04 3.59E-04 4.29E-04 5.00E-04

[2]

Upper Shell 1.11E-03 1.25E-03 1.46E-03 1.68E-03 Upper-to-Intermediate-Shell Circumferential Weld 1.27E-03 1.43E-03 1.67E-03 1.92E-03 Intermediate Shell 3.74E-02 4.28E-02 5.15E-02 6.02E-02 Intermediate Shell Longitudinal Weld - 15° 2.54E-02 2.89E-02 3.45E-02 4.02E-02 Intermediate Shell Longitudinal Weld - 135° 1.87E-02 2.13E-02 2.55E-02 2.98E-02

[3]

Intermediate Shell Longitudinal Weld - 255° 2.54E-02 2.89E-02 3.45E-02 4.02E-02 Intermediate-to-Lower-Shell Circumferential Weld 3.72E-02 4.25E-02 5.12E-02 5.98E-02 Lower Shell 3.72E-02 4.25E-02 5.12E-02 5.99E-02 Lower Shell Longitudinal Weld - 15° 2.52E-02 2.86E-02 3.43E-02 3.99E-02 Lower Shell Longitudinal Weld - 135° 1.85E-02 2.11E-02 2.53E-02 2.96E-02

[3]

Lower Shell Longitudinal Weld - 255° 2.52E-02 2.86E-02 3.43E-02 3.99E-02 Lower-Shell-to-Bottom-Head Circumferential Weld 1.58E-04 1.80E-04 2.16E-04 2.52E-04 Projections with no bias on the peripheral and re-entrant corner assembly relative powers Iron Atom Displacements (dpa)

Material 54 EFPY 60 EFPY 66 EFPY 72 EFPY Inlet-nozzle-to-upper-shell weld (lowest extent) 4.38E-04 4.92E-04 5.46E-04 6.00E-04 Outlet-nozzle-to-upper-shell weld (lowest extent) 5.70E-04 6.41E-04 7.11E-04 7.81E-04

[2]

Upper Shell 1.89E-03 2.11E-03 2.33E-03 2.54E-03 Upper-to-Intermediate-Shell Circumferential Weld 2.17E-03 2.41E-03 2.66E-03 2.91E-03 Intermediate Shell 6.89E-02 7.76E-02 8.63E-02 9.51E-02 Intermediate Shell Longitudinal Weld - 15° 4.59E-02 5.16E-02 5.73E-02 6.30E-02 Intermediate Shell Longitudinal Weld - 135° 3.40E-02 3.83E-02 4.25E-02 4.68E-02

[3]

Intermediate Shell Longitudinal Weld - 255° 4.59E-02 5.16E-02 5.73E-02 6.30E-02 Intermediate-to-Lower-Shell Circumferential Weld 6.85E-02 7.71E-02 8.58E-02 9.44E-02 Lower Shell 6.85E-02 7.72E-02 8.59E-02 9.46E-02 Lower Shell Longitudinal Weld - 15° 4.56E-02 5.12E-02 5.69E-02 6.25E-02 Lower Shell Longitudinal Weld - 135° 3.38E-02 3.80E-02 4.22E-02 4.64E-02

[3]

Lower Shell Longitudinal Weld - 255° 4.56E-02 5.12E-02 5.69E-02 6.25E-02 Lower-Shell-to-Bottom-Head Circumferential Weld 2.87E-04 3.23E-04 3.59E-04 3.95E-04

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 20 of 56 Table 4-6 Iron Atom Displacements at the RPV Welds and Shells Projections with a +10% bias on the peripheral and re-entrant corner assembly relative powers Iron Atom Displacements (dpa)

Material [1]

32.30 EFPY 36 EFPY 42 EFPY 48 EFPY Inlet-nozzle-to-upper-shell weld (lowest extent) 2.42E-04 2.79E-04 3.38E-04 3.97E-04 Outlet-nozzle-to-upper-shell weld (lowest extent) 3.16E-04 3.63E-04 4.40E-04 5.17E-04

[2]

Upper Shell 1.11E-03 1.26E-03 1.49E-03 1.72E-03 Upper-to-Intermediate-Shell Circumferential Weld 1.27E-03 1.44E-03 1.70E-03 1.96E-03 Intermediate Shell 3.74E-02 4.32E-02 5.27E-02 6.22E-02 Intermediate Shell Longitudinal Weld - 15° 2.54E-02 2.92E-02 3.54E-02 4.16E-02 Intermediate Shell Longitudinal Weld - 135° 1.87E-02 2.16E-02 2.62E-02 3.09E-02 Intermediate Shell Longitudinal Weld - 255°[3] 2.54E-02 2.92E-02 3.54E-02 4.16E-02 Intermediate-to-Lower-Shell Circumferential Weld 3.72E-02 4.30E-02 5.24E-02 6.18E-02 Lower Shell 3.72E-02 4.30E-02 5.24E-02 6.18E-02 Lower Shell Longitudinal Weld - 15° 2.52E-02 2.89E-02 3.51E-02 4.12E-02 Lower Shell Longitudinal Weld - 135° 1.85E-02 2.14E-02 2.60E-02 3.06E-02

[3]

Lower Shell Longitudinal Weld - 255° 2.52E-02 2.89E-02 3.51E-02 4.12E-02 Lower-Shell-to-Bottom-Head Circumferential Weld 1.58E-04 1.82E-04 2.21E-04 2.60E-04 Projections with a +10% bias on the peripheral and re-entrant corner assembly relative powers Iron Atom Displacements (dpa)

Material 54 EFPY 60 EFPY 66 EFPY 72 EFPY Inlet-nozzle-to-upper-shell weld (lowest extent) 4.56E-04 5.15E-04 5.74E-04 6.33E-04 Outlet-nozzle-to-upper-shell weld (lowest extent) 5.93E-04 6.70E-04 7.47E-04 8.24E-04

[2]

Upper Shell 1.95E-03 2.18E-03 2.41E-03 2.64E-03 Upper-to-Intermediate-Shell Circumferential Weld 2.23E-03 2.49E-03 2.76E-03 3.02E-03 Intermediate Shell 7.17E-02 8.11E-02 9.06E-02 1.00E-01 Intermediate Shell Longitudinal Weld - 15° 4.77E-02 5.39E-02 6.01E-02 6.63E-02 Intermediate Shell Longitudinal Weld - 135° 3.55E-02 4.02E-02 4.48E-02 4.95E-02

[3]

Intermediate Shell Longitudinal Weld - 255° 4.77E-02 5.39E-02 6.01E-02 6.63E-02 Intermediate-to-Lower-Shell Circumferential Weld 7.12E-02 8.06E-02 9.00E-02 9.94E-02 Lower Shell 7.12E-02 8.07E-02 9.01E-02 9.95E-02 Lower Shell Longitudinal Weld - 15° 4.74E-02 5.35E-02 5.97E-02 6.58E-02 Lower Shell Longitudinal Weld - 135° 3.52E-02 3.99E-02 4.45E-02 4.91E-02

[3]

Lower Shell Longitudinal Weld - 255° 4.74E-02 5.35E-02 5.97E-02 6.58E-02 Lower-Shell-to-Bottom-Head Circumferential Weld 2.99E-04 3.38E-04 3.77E-04 4.16E-04 Note(s):

1. Value listed is the projected EFPY at the end of Cycle 25.

2. Exposure values for the upper shell longitudinal welds are bounded by the exposure values for the upper shell.

3. Exposure values for the intermediate shell and lower shell 255° longitudinal welds are bounded by the exposure values for the intermediate shell and lower shell 15° longitudinal welds.

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 21 of 56 4.2 Surveillance Capsules Neutron exposure data for the surveillance capsules are provided in Table 4-7 through Table 4-10. In particular, fast neutron (E > 1.0 MeV) fluence rates and fluences determined at the core midplane and geometric center of the surveillance capsules are provided in Table 4-7 and Table 4-8 as a function of irradiation time. Similar data in terms of iron atom displacement rate and iron atom displacements are provided in Table 4-9 and Table 4-10.

Lead factors for the surveillance capsules are provided in Table 4-11. The lead factor is defined as the ratio of the calculated neutron fluence at the geometric center of the surveillance capsule to the maximum fluence at the RPV clad/base metal interface.

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 22 of 56 Table 4-7 Fast Neutron (E > 1.0 MeV) Fluence Rate at the Geometric Center of the Surveillance Capsules Cycle Cumulative Fluence Rate (n/cm2-s)

Cycle Length Operating Time (EFPY) (EFPY) 7° 14° 1 1.11 1.11 4.06E+10 2.86E+10 2 1.12 2.23 4.01E+10 2.72E+10 3 1.22 3.45 3.62E+10 2.49E+10 4 1.16 4.61 2.66E+10 2.16E+10 5 1.30 5.91 2.62E+10 2.17E+10 6 1.35 7.26 2.58E+10 1.86E+10 7 1.21 8.47 2.79E+10 1.96E+10 8 1.38 9.85 1.72E+10 1.40E+10 9 1.22 11.07 2.62E+10 2.16E+10 10 1.44 12.51 2.78E+10 2.21E+10 11 1.32 13.83 2.49E+10 1.95E+10 12 1.51 15.34 2.42E+10 1.74E+10 13 1.29 16.63 2.70E+10 1.97E+10 14 1.43 18.06 2.37E+10 1.76E+10 15 1.15 19.21 2.77E+10 1.98E+10 16 1.25 20.46 2.85E+10 2.06E+10 17 1.25 21.71 2.78E+10 2.01E+10 18 1.42 23.13 2.66E+10 2.01E+10 19 1.19 24.32 3.26E+10 2.41E+10 20 1.23 25.55 3.78E+10 2.72E+10 21 1.28 26.83 3.63E+10 2.64E+10 22 1.31 28.13 4.25E+10 3.03E+10 23 1.40 29.53 4.18E+10 3.00E+10 24 1.34 30.88 3.81E+10 2.73E+10

[1]

25 1.43 32.30 3.69E+10 2.66E+10 Note(s):

1. Cycle 25 was the current operating cycle at the time this summary report was authored.

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 23 of 56 Table 4-8 Fast Neutron (E > 1.0 MeV) Fluence at the Geometric Center of the Surveillance Capsules Cycle Cumulative Fluence (n/cm2)

Cycle Length Operating Time (EFPY) (EFPY) 7° 14° 1 1.11 1.11 1.42E+18[1] 1.00E+18 2 1.12 2.23 2.84E+18 1.97E+18 3 1.22 3.45 4.23E+18 2.92E+18 4 1.16 4.61 5.20E+18 3.72E+18 5 1.30 5.91 6.28E+18 4.60E+18 6 1.35 7.26 7.38E+18 5.39E+18 7 1.21 8.47 8.44E+18 6.14E+18 8 1.38 9.85 9.19E+18 6.75E+18

[2]

9 1.22 11.07 1.02E+19 7.59E+18 10 1.44 12.51 1.15E+19 8.59E+18 11 1.32 13.83 1.25E+19 9.40E+18 12 1.51 15.34 1.37E+19 1.02E+19 13 1.29 16.63 1.48E+19 1.10E+19 14 1.43 18.06 1.58E+19 1.18E+19 15 1.15 19.21 1.68E+19 1.25E+19 16 1.25 20.46 1.80E+19 1.34E+19 17 1.25 21.71 1.91E+19 1.42E+19 18 1.42 23.13 2.02E+19 1.51E+19 19 1.19 24.32 2.15E+19 1.60E+19

[3]

20 1.23 25.55 2.29E+19 1.70E+19 21 1.28 26.83 2.44E+19 1.81E+19 22 1.31 28.13 2.61E+19 1.93E+19 23 1.40 29.53 2.80E+19 2.06E+19 24 1.34 30.88 2.96E+19 2.18E+19

[4]

25 1.43 32.30 3.13E+19 2.30E+19

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 24 of 56 Table 4-8 Fast Neutron (E > 1.0 MeV) Fluence at the Geometric Center of the Surveillance Capsules No bias on the peripheral and re-entrant corner assembly relative powers Cycle Cumulative Fluence (n/cm2)

Cycle Length Operating Time (EFPY) (EFPY) 7° 14°

[5]

Future -- 36.00 3.57E+19 2.62E+19 Future[5] -- 42.00 4.29E+19 3.14E+19

[5]

Future -- 48.00 5.01E+19 3.65E+19

[5]

Future -- 54.00 5.74E+19 4.17E+19

[5]

Future -- 60.00 6.46E+19 4.69E+19

[5]

Future -- 66.00 7.18E+19 5.21E+19

[5]

Future -- 72.00 7.90E+19 5.72E+19

+10% bias on the peripheral and re-entrant corner assembly relative powers Cycle Cumulative Fluence (n/cm2)

Cycle Length Operating Time (EFPY) (EFPY) 7° 14°

[5]

Future -- 36.00 3.61E+19 2.65E+19 Future[5] -- 42.00 4.40E+19 3.21E+19

[5]

Future -- 48.00 5.18E+19 3.78E+19

[5]

Future -- 54.00 5.97E+19 4.34E+19

[5]

Future -- 60.00 6.75E+19 4.90E+19

[5]

Future -- 66.00 7.54E+19 5.47E+19 Future[5] -- 72.00 8.33E+19 6.03E+19 Note(s):

1. This value is applicable to Capsule 83°.

2. This value is applicable to Capsule 263°.

3. This value is applicable to Capsule 97°.

4. Cycle 25 was the current operating cycle at the time this summary report was authored.

5. Values beyond Cycle 25 are based on the average core power distributions and reactor operating conditions of Cycle 24 and are determined both with and without a 1.1 bias on the peripheral and re-entrant corner assembly relative powers.

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 25 of 56 Table 4-9 Iron Atom Displacement Rate at the Geometric Center of the Surveillance Capsules Cycle Cumulative Displacement Rate (dpa/s)

Cycle Length Operating Time (EFPY) (EFPY) 7° 14° 1 1.11 1.11 5.91E-11 4.19E-11 2 1.12 2.23 5.84E-11 3.99E-11 3 1.22 3.45 5.27E-11 3.64E-11 4 1.16 4.61 3.88E-11 3.17E-11 5 1.30 5.91 3.82E-11 3.18E-11 6 1.35 7.26 3.76E-11 2.72E-11 7 1.21 8.47 4.07E-11 2.88E-11 8 1.38 9.85 2.51E-11 2.06E-11 9 1.22 11.07 3.82E-11 3.16E-11 10 1.44 12.51 4.05E-11 3.24E-11 11 1.32 13.83 3.63E-11 2.86E-11 12 1.51 15.34 3.53E-11 2.55E-11 13 1.29 16.63 3.94E-11 2.89E-11 14 1.43 18.06 3.46E-11 2.58E-11 15 1.15 19.21 4.04E-11 2.90E-11 16 1.25 20.46 4.16E-11 3.02E-11 17 1.25 21.71 4.06E-11 2.94E-11 18 1.42 23.13 3.87E-11 2.94E-11 19 1.19 24.32 4.75E-11 3.53E-11 20 1.23 25.55 5.51E-11 3.99E-11 21 1.28 26.83 5.28E-11 3.86E-11 22 1.31 28.13 6.19E-11 4.43E-11 23 1.40 29.53 6.08E-11 4.39E-11 24 1.34 30.88 5.55E-11 4.00E-11

[1]

25 1.43 32.30 5.38E-11 3.89E-11 Note(s):

1. Cycle 25 was the current operating cycle at the time this summary report was authored.

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 26 of 56 Table 4-10 Iron Atom Displacements at the Geometric Center of the Surveillance Capsules Cycle Cumulative Displacements (dpa)

Cycle Length Operating Time (EFPY) (EFPY) 7° 14° 1 1.11 1.11 2.07E-03[1] 1.47E-03 2 1.12 2.23 4.13E-03 2.88E-03 3 1.22 3.45 6.16E-03 4.28E-03 4 1.16 4.61 7.58E-03 5.44E-03 5 1.30 5.91 9.15E-03 6.74E-03 6 1.35 7.26 1.08E-02 7.90E-03 7 1.21 8.47 1.23E-02 9.00E-03 8 1.38 9.85 1.34E-02 9.90E-03

[2]

9 1.22 11.07 1.49E-02 1.11E-02 10 1.44 12.51 1.67E-02 1.26E-02 11 1.32 13.83 1.82E-02 1.38E-02 12 1.51 15.34 1.99E-02 1.50E-02 13 1.29 16.63 2.15E-02 1.62E-02 14 1.43 18.06 2.31E-02 1.73E-02 15 1.15 19.21 2.45E-02 1.84E-02 16 1.25 20.46 2.62E-02 1.96E-02 17 1.25 21.71 2.78E-02 2.07E-02 18 1.42 23.13 2.95E-02 2.21E-02 19 1.19 24.32 3.13E-02 2.34E-02

[3]

20 1.23 25.55 3.34E-02 2.49E-02 21 1.28 26.83 3.56E-02 2.65E-02 22 1.31 28.13 3.81E-02 2.83E-02 23 1.40 29.53 4.08E-02 3.02E-02 24 1.34 30.88 4.32E-02 3.19E-02

[4]

25 1.43 32.30 4.56E-02 3.37E-02

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 27 of 56 Table 4-10 Iron Atom Displacements at the Geometric Center of the Surveillance Capsules No bias on the peripheral and re-entrant corner assembly relative powers Cycle Cumulative Displacements (dpa)

Cycle Length Operating Time (EFPY) (EFPY) 7° 14°

[5]

Future -- 36.00 5.21E-02 3.84E-02 Future[5] -- 42.00 6.26E-02 4.59E-02

[5]

Future -- 48.00 7.31E-02 5.35E-02

[5]

Future -- 54.00 8.36E-02 6.11E-02

[5]

Future -- 60.00 9.41E-02 6.87E-02

[5]

Future -- 66.00 1.05E-01 7.62E-02

[5]

Future -- 72.00 1.15E-01 8.38E-02

+10% bias on the peripheral and re-entrant corner assembly relative powers Cycle Cumulative Displacements (dpa)

Cycle Length Operating Time (EFPY) (EFPY) 7° 14°

[5]

Future -- 36.00 5.26E-02 3.88E-02 Future[5] -- 42.00 6.41E-02 4.70E-02

[5]

Future -- 48.00 7.55E-02 5.53E-02

[5]

Future -- 54.00 8.70E-02 6.36E-02

[5]

Future -- 60.00 9.84E-02 7.18E-02

[5]

Future -- 66.00 1.10E-01 8.01E-02 Future[5] -- 72.00 1.21E-01 8.83E-02 Note(s):

1. This value is applicable to Capsule 83°.

2. This value is applicable to Capsule 263°.

3. This value is applicable to Capsule 97°.

4. Cycle 25 was the current operating cycle at the time this summary report was authored.

5. Values beyond Cycle 25 are based on the average core power distributions and reactor operating conditions of Cycle 24 and are determined both with and without a 1.1 bias on the peripheral and re-entrant corner assembly relative powers.

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 28 of 56 Table 4-11 Surveillance Capsule Lead Factors Cycle Cumulative Lead Factor Cycle Length Operating Time (EFPY) (EFPY) 7° 14°

[1]

1 1.11 1.11 1.27 0.90 2 1.12 2.23 1.23 0.85 3 1.22 3.45 1.22 0.84 4 1.16 4.61 1.24 0.88 5 1.30 5.91 1.25 0.92 6 1.35 7.26 1.25 0.91 7 1.21 8.47 1.24 0.90 8 1.38 9.85 1.24 0.91

[2]

9 1.22 11.07 1.26 0.93 10 1.44 12.51 1.27 0.95 11 1.32 13.83 1.27 0.95 12 1.51 15.34 1.27 0.95 13 1.29 16.63 1.27 0.95 14 1.43 18.06 1.27 0.95 15 1.15 19.21 1.27 0.95 16 1.25 20.46 1.27 0.95 17 1.25 21.71 1.27 0.94 18 1.42 23.13 1.28 0.95 19 1.19 24.32 1.28 0.95

[3]

20 1.23 25.55 1.28 0.95 21 1.28 26.83 1.28 0.95 22 1.31 28.13 1.28 0.94 23 1.40 29.53 1.28 0.94 24 1.34 30.88 1.27 0.94

[4]

25 1.43 32.30 1.27 0.94

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 29 of 56 Table 4-11 Surveillance Capsule Lead Factors No bias on the peripheral and re-entrant corner assembly relative powers Cycle Cumulative Lead Factor Cycle Length Operating Time (EFPY) (EFPY) 7° 14° Future[5] -- 36.00 1.27 0.93 Future[5] -- 42.00 1.27 0.93

[5]

Future -- 48.00 1.27 0.93 Future[5] -- 54.00 1.27 0.92

[5]

Future -- 60.00 1.27 0.92

[5]

Future -- 66.00 1.27 0.92

[5]

Future -- 72.00 1.27 0.92

+10% bias on the peripheral and re-entrant corner assembly relative powers Cycle Cumulative Lead Factor Cycle Length Operating Time (EFPY) (EFPY) 7° 14° Future[5] -- 36.00 1.27 0.93 Future[5] -- 42.00 1.27 0.93 Future[5] -- 48.00 1.27 0.93

[5]

Future -- 54.00 1.27 0.92

[5]

Future -- 60.00 1.27 0.92

[5]

Future -- 66.00 1.27 0.92

[5]

Future -- 72.00 1.27 0.92 Note(s):

1. This value is applicable to Capsule 83°.

2. This value is applicable to Capsule 263°

3. This value is applicable to Capsule 97°.

4. Cycle 25 was the current operating cycle at the time this summary report was authored.

5. Values beyond Cycle 25 are based on the average core power distributions and reactor operating conditions of Cycle 24 and are determined both with and without a 1.1 bias on the peripheral and re-entrant corner assembly relative powers.

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 30 of 56 4.3 RPV Support Structure Neutron exposure data for the RPV support structure are provided in Table 4-12 through Table 4-20. In particular:

x Table 4-12 provides the maximum neutron exposures, expressed as fast neutron (E > 1.0 MeV and E > 0.1 MeV) fluences and iron atom displacements (all energies and E > 0.1 MeV), at the RPV support structure. Note that each value reported in Table 4-12 was determined at the RPV support structure inner surface, 0° azimuth, and axial elevation where the maximum exposure of interest occurred.

x Table 4-13 and Table 4-14 provide fast neutron (E > 1.0 MeV) fluence projections at the RPV support structure as a function of height. Note that each fluence value reported in Table 4-13 and Table 4-14 was determined at the RPV support structure inner surface, 0° azimuth, and axial elevation indicated.

x Table 4-15 and Table 4-16 provide fast neutron (E > 0.1 MeV) fluence projections at the RPV support structure as a function of height. Note that each fluence value reported in Table 4-15 and Table 4-16 was determined at the RPV support structure inner surface, 0° azimuth, and axial elevation indicated.

x Table 4-17 and Table 4-18 provide iron atom displacement (all energies) projections at the RPV support structure as a function of height. Note that each displacement value reported in Table 4-17 and Table 4-18 was determined at the RPV support structure inner surface, 0° azimuth, and axial elevation indicated.

x Table 4-19 and Table 4-20 provide iron atom displacement (E > 0.1 MeV) projections at the RPV support structure as a function of height. Note that each displacement value reported in Table 4-19 and Table 4-20 was determined at the RPV support structure inner surface, 0° azimuth, and axial elevation indicated.

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 31 of 56 Table 4-12 Maximum Neutron Exposures at the RPV Support Structure Cycle Cumulative Fast Neutron Fluence Iron Atom Displacements Cycle Length Operating Time (n/cm2) (dpa)

(EFPY) (EFPY) E > 1.0 MeV E > 0.1 MeV All Energies E > 0.1 MeV 1 1.11 1.11 4.86E+16 5.63E+17 1.84E-04 1.69E-04 2 1.12 2.23 9.85E+16 1.17E+18 3.82E-04 3.51E-04 3 1.22 3.45 1.47E+17 1.74E+18 5.69E-04 5.24E-04 4 1.16 4.61 1.81E+17 2.13E+18 6.96E-04 6.41E-04 5 1.30 5.91 2.18E+17 2.56E+18 8.36E-04 7.69E-04 6 1.35 7.26 2.57E+17 3.04E+18 9.92E-04 9.13E-04 7 1.21 8.47 2.94E+17 3.48E+18 1.14E-03 1.05E-03 8 1.38 9.85 3.21E+17 3.82E+18 1.25E-03 1.15E-03 9 1.22 11.07 3.55E+17 4.22E+18 1.38E-03 1.27E-03 10 1.44 12.51 3.97E+17 4.74E+18 1.55E-03 1.42E-03 11 1.32 13.83 4.33E+17 5.17E+18 1.69E-03 1.55E-03 12 1.51 15.34 4.74E+17 5.65E+18 1.84E-03 1.70E-03 13 1.29 16.63 5.12E+17 6.10E+18 1.99E-03 1.83E-03 14 1.43 18.06 5.49E+17 6.54E+18 2.14E-03 1.96E-03 15 1.15 19.21 5.84E+17 6.94E+18 2.27E-03 2.09E-03 16 1.25 20.46 6.22E+17 7.39E+18 2.42E-03 2.22E-03 17 1.25 21.71 6.59E+17 7.82E+18 2.56E-03 2.35E-03 18 1.42 23.13 6.99E+17 8.30E+18 2.71E-03 2.49E-03 19 1.19 24.32 7.41E+17 8.81E+18 2.88E-03 2.65E-03 20 1.23 25.55 7.92E+17 9.40E+18 3.07E-03 2.82E-03 21 1.28 26.83 8.42E+17 9.99E+18 3.27E-03 3.00E-03 22 1.31 28.13 9.02E+17 1.07E+19 3.50E-03 3.22E-03 23 1.40 29.53 9.66E+17 1.15E+19 3.74E-03 3.44E-03 24 1.34 30.88 1.02E+18 1.21E+19 3.96E-03 3.64E-03

[1]

25 1.43 32.30 1.08E+18 1.28E+19 4.18E-03 3.84E-03

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 32 of 56 Table 4-12 Maximum Neutron Exposures at the RPV Support Structure Cycle Cumulative Fast Neutron Fluence Iron Atom Displacements Cycle Length Operating Time (n/cm2) (dpa)

(EFPY) (EFPY) E > 1.0 MeV E > 0.1 MeV All Energies E > 0.1 MeV Projections with no bias on the peripheral and re-entrant corner assembly relative powers

[2]

Future -- 36.00 1.23E+18 1.46E+19 4.77E-03 4.38E-03

[2]

Future -- 42.00 1.48E+18 1.75E+19 5.72E-03 5.27E-03

[2]

Future -- 48.00 1.73E+18 2.04E+19 6.68E-03 6.15E-03 Future[2] -- 54.00 1.98E+18 2.34E+19 7.64E-03 7.03E-03

[2]

Future -- 60.00 2.23E+18 2.63E+19 8.59E-03 7.91E-03

[2]

Future -- 66.00 2.48E+18 2.92E+19 9.55E-03 8.79E-03

[2]

Future -- 72.00 2.73E+18 3.22E+19 1.05E-02 9.67E-03 Projections with a +10% bias on the peripheral and re-entrant corner assembly relative powers

[2]

Future -- 36.00 1.25E+18 1.48E+19 4.82E-03 4.43E-03

[2]

Future -- 42.00 1.52E+18 1.79E+19 5.86E-03 5.39E-03

[2]

Future -- 48.00 1.79E+18 2.11E+19 6.91E-03 6.35E-03

[2]

Future -- 54.00 2.06E+18 2.43E+19 7.95E-03 7.31E-03

[2]

Future -- 60.00 2.33E+18 2.75E+19 8.99E-03 8.27E-03 Future[2] -- 66.00 2.60E+18 3.07E+19 1.00E-02 9.23E-03

[2]

Future -- 72.00 2.87E+18 3.39E+19 1.11E-02 1.02E-02 Note(s):

1. Cycle 25 was the current operating cycle at the time this summary report was authored.

2. Values beyond Cycle 25 are based on the average core power distributions and reactor operating conditions of Cycle 24 and are determined both with and without a 1.1 bias on the peripheral and re-entrant corner assembly relative powers.

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 33 of 56 Table 4-13 Fast Neutron (E > 1.0 MeV) Fluence at the RPV Support Structure -

No Bias on the Peripheral and Re-Entrant Corner Assembly Relative Powers Elevation[1] Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

(cm) 32.30 EFPY[2] 36 EFPY 42 EFPY 48 EFPY 54 EFPY 60 EFPY 66 EFPY 72 EFPY

[3]

231.16 6.31E+16 7.14E+16 8.48E+16 9.83E+16 1.12E+17 1.25E+17 1.39E+17 1.52E+17 228.60 6.98E+16 7.90E+16 9.38E+16 1.09E+17 1.23E+17 1.38E+17 1.53E+17 1.68E+17 213.36 1.26E+17 1.43E+17 1.69E+17 1.96E+17 2.23E+17 2.49E+17 2.76E+17 3.03E+17 198.12 2.05E+17 2.32E+17 2.76E+17 3.20E+17 3.64E+17 4.07E+17 4.51E+17 4.95E+17 182.88 3.25E+17 3.68E+17 4.38E+17 5.08E+17 5.78E+17 6.48E+17 7.18E+17 7.88E+17 167.64 4.77E+17 5.41E+17 6.46E+17 7.50E+17 8.55E+17 9.59E+17 1.06E+18 1.17E+18 152.40 6.37E+17 7.25E+17 8.67E+17 1.01E+18 1.15E+18 1.29E+18 1.43E+18 1.58E+18 137.16 7.82E+17 8.91E+17 1.07E+18 1.24E+18 1.42E+18 1.60E+18 1.77E+18 1.95E+18 121.92 8.96E+17 1.02E+18 1.23E+18 1.43E+18 1.63E+18 1.84E+18 2.04E+18 2.25E+18 106.68 9.80E+17 1.12E+18 1.34E+18 1.57E+18 1.79E+18 2.02E+18 2.24E+18 2.46E+18 91.44 1.06E+18 1.21E+18 1.45E+18 1.70E+18 1.94E+18 2.19E+18 2.43E+18 2.67E+18 76.20 1.05E+18 1.20E+18 1.44E+18 1.68E+18 1.93E+18 2.17E+18 2.41E+18 2.65E+18 60.96 1.06E+18 1.21E+18 1.46E+18 1.70E+18 1.94E+18 2.19E+18 2.43E+18 2.68E+18 45.72 1.07E+18 1.22E+18 1.47E+18 1.72E+18 1.96E+18 2.21E+18 2.46E+18 2.70E+18 30.48 1.07E+18 1.23E+18 1.47E+18 1.72E+18 1.97E+18 2.22E+18 2.46E+18 2.71E+18 15.24 1.07E+18 1.22E+18 1.47E+18 1.72E+18 1.97E+18 2.21E+18 2.46E+18 2.71E+18 0.00 1.07E+18 1.23E+18 1.47E+18 1.72E+18 1.97E+18 2.22E+18 2.47E+18 2.71E+18

-15.24 1.08E+18 1.23E+18 1.48E+18 1.73E+18 1.98E+18 2.23E+18 2.48E+18 2.73E+18

-30.48 1.08E+18 1.23E+18 1.48E+18 1.73E+18 1.98E+18 2.23E+18 2.48E+18 2.73E+18

-45.72 1.07E+18 1.23E+18 1.47E+18 1.72E+18 1.97E+18 2.22E+18 2.47E+18 2.71E+18

-60.96 1.06E+18 1.22E+18 1.46E+18 1.71E+18 1.95E+18 2.20E+18 2.45E+18 2.69E+18

-76.20 1.05E+18 1.20E+18 1.44E+18 1.69E+18 1.93E+18 2.17E+18 2.42E+18 2.66E+18

-91.44 1.02E+18 1.17E+18 1.40E+18 1.64E+18 1.88E+18 2.12E+18 2.35E+18 2.59E+18

-106.68 9.69E+17 1.11E+18 1.33E+18 1.56E+18 1.78E+18 2.01E+18 2.23E+18 2.46E+18

-121.92 8.88E+17 1.01E+18 1.22E+18 1.43E+18 1.63E+18 1.84E+18 2.04E+18 2.25E+18

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 34 of 56 Table 4-13 Fast Neutron (E > 1.0 MeV) Fluence at the RPV Support Structure -

No Bias on the Peripheral and Re-Entrant Corner Assembly Relative Powers Elevation[1] Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

(cm) 32.30 EFPY[2] 36 EFPY 42 EFPY 48 EFPY 54 EFPY 60 EFPY 66 EFPY 72 EFPY

-137.16 7.76E+17 8.86E+17 1.07E+18 1.24E+18 1.42E+18 1.60E+18 1.78E+18 1.96E+18

-152.40 6.36E+17 7.25E+17 8.70E+17 1.02E+18 1.16E+18 1.31E+18 1.45E+18 1.60E+18

-167.64 4.78E+17 5.44E+17 6.51E+17 7.59E+17 8.66E+17 9.74E+17 1.08E+18 1.19E+18

-182.88 3.25E+17 3.69E+17 4.42E+17 5.14E+17 5.86E+17 6.58E+17 7.31E+17 8.03E+17

-198.12 2.02E+17 2.30E+17 2.74E+17 3.19E+17 3.63E+17 4.08E+17 4.52E+17 4.97E+17

-213.36 1.20E+17 1.36E+17 1.62E+17 1.89E+17 2.15E+17 2.41E+17 2.67E+17 2.94E+17

-228.60 7.20E+16 8.17E+16 9.76E+16 1.13E+17 1.29E+17 1.45E+17 1.61E+17 1.77E+17

-243.84 4.58E+16 5.21E+16 6.23E+16 7.24E+16 8.26E+16 9.27E+16 1.03E+17 1.13E+17

-259.08 3.20E+16 3.64E+16 4.36E+16 5.07E+16 5.79E+16 6.50E+16 7.22E+16 7.93E+16

-274.32 2.50E+16 2.84E+16 3.40E+16 3.96E+16 4.52E+16 5.08E+16 5.64E+16 6.20E+16

-289.56 2.04E+16 2.33E+16 2.78E+16 3.24E+16 3.70E+16 4.16E+16 4.61E+16 5.07E+16 Note(s):

1. Elevations are given with respect to the midplane of the active fuel.

2. Value listed is the projected EFPY at the end of Cycle 25.

3. This elevation corresponds to the top of the 6-inch-thick horizontal plate at the top-center of the RPV support structure.

4. Linear interpolation between the EFPY values listed in this table may be performed as necessary.

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 35 of 56 Table 4-14 Fast Neutron (E > 1.0 MeV) Fluence at the RPV Support Structure -

+10% Bias on the Peripheral and Re-Entrant Corner Assembly Relative Powers Elevation[1] Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

(cm) 32.30 EFPY[2] 36 EFPY 42 EFPY 48 EFPY 54 EFPY 60 EFPY 66 EFPY 72 EFPY

[3]

231.16 6.31E+16 7.21E+16 8.67E+16 1.01E+17 1.16E+17 1.30E+17 1.45E+17 1.60E+17 228.60 6.98E+16 7.98E+16 9.59E+16 1.12E+17 1.28E+17 1.44E+17 1.60E+17 1.76E+17 213.36 1.26E+17 1.44E+17 1.73E+17 2.02E+17 2.31E+17 2.60E+17 2.89E+17 3.18E+17 198.12 2.05E+17 2.35E+17 2.82E+17 3.30E+17 3.77E+17 4.25E+17 4.72E+17 5.20E+17 182.88 3.25E+17 3.72E+17 4.48E+17 5.24E+17 6.00E+17 6.77E+17 7.53E+17 8.29E+17 167.64 4.77E+17 5.47E+17 6.60E+17 7.74E+17 8.88E+17 1.00E+18 1.12E+18 1.23E+18 152.40 6.37E+17 7.32E+17 8.87E+17 1.04E+18 1.20E+18 1.35E+18 1.51E+18 1.66E+18 137.16 7.82E+17 9.00E+17 1.09E+18 1.28E+18 1.48E+18 1.67E+18 1.86E+18 2.05E+18 121.92 8.96E+17 1.03E+18 1.26E+18 1.48E+18 1.70E+18 1.92E+18 2.14E+18 2.37E+18 106.68 9.80E+17 1.13E+18 1.37E+18 1.62E+18 1.86E+18 2.11E+18 2.35E+18 2.60E+18 91.44 1.06E+18 1.22E+18 1.49E+18 1.76E+18 2.02E+18 2.29E+18 2.55E+18 2.82E+18 76.20 1.05E+18 1.21E+18 1.48E+18 1.74E+18 2.00E+18 2.27E+18 2.53E+18 2.79E+18 60.96 1.06E+18 1.23E+18 1.49E+18 1.76E+18 2.02E+18 2.29E+18 2.55E+18 2.82E+18 45.72 1.07E+18 1.24E+18 1.51E+18 1.77E+18 2.04E+18 2.31E+18 2.58E+18 2.85E+18 30.48 1.07E+18 1.24E+18 1.51E+18 1.78E+18 2.05E+18 2.32E+18 2.59E+18 2.86E+18 15.24 1.07E+18 1.24E+18 1.51E+18 1.78E+18 2.05E+18 2.32E+18 2.58E+18 2.85E+18 0.00 1.07E+18 1.24E+18 1.51E+18 1.78E+18 2.05E+18 2.32E+18 2.59E+18 2.86E+18

-15.24 1.08E+18 1.24E+18 1.52E+18 1.79E+18 2.06E+18 2.33E+18 2.60E+18 2.87E+18

-30.48 1.08E+18 1.24E+18 1.52E+18 1.79E+18 2.06E+18 2.33E+18 2.60E+18 2.87E+18

-45.72 1.07E+18 1.24E+18 1.51E+18 1.78E+18 2.05E+18 2.32E+18 2.59E+18 2.86E+18

-60.96 1.06E+18 1.23E+18 1.50E+18 1.76E+18 2.03E+18 2.30E+18 2.57E+18 2.84E+18

-76.20 1.05E+18 1.21E+18 1.48E+18 1.74E+18 2.01E+18 2.27E+18 2.54E+18 2.80E+18

-91.44 1.02E+18 1.18E+18 1.44E+18 1.70E+18 1.95E+18 2.21E+18 2.47E+18 2.73E+18

-106.68 9.69E+17 1.12E+18 1.36E+18 1.61E+18 1.85E+18 2.10E+18 2.34E+18 2.58E+18

-121.92 8.88E+17 1.03E+18 1.25E+18 1.47E+18 1.70E+18 1.92E+18 2.14E+18 2.37E+18

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 36 of 56 Table 4-14 Fast Neutron (E > 1.0 MeV) Fluence at the RPV Support Structure -

+10% Bias on the Peripheral and Re-Entrant Corner Assembly Relative Powers Elevation[1] Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

(cm) 32.30 EFPY[2] 36 EFPY 42 EFPY 48 EFPY 54 EFPY 60 EFPY 66 EFPY 72 EFPY

-137.16 7.76E+17 8.96E+17 1.09E+18 1.28E+18 1.48E+18 1.67E+18 1.87E+18 2.06E+18

-152.40 6.36E+17 7.33E+17 8.91E+17 1.05E+18 1.21E+18 1.36E+18 1.52E+18 1.68E+18

-167.64 4.78E+17 5.50E+17 6.66E+17 7.83E+17 9.00E+17 1.02E+18 1.13E+18 1.25E+18

-182.88 3.25E+17 3.73E+17 4.52E+17 5.30E+17 6.09E+17 6.87E+17 7.65E+17 8.44E+17

-198.12 2.02E+17 2.32E+17 2.80E+17 3.29E+17 3.77E+17 4.26E+17 4.74E+17 5.22E+17

-213.36 1.20E+17 1.37E+17 1.66E+17 1.94E+17 2.23E+17 2.52E+17 2.80E+17 3.09E+17

-228.60 7.20E+16 8.26E+16 9.98E+16 1.17E+17 1.34E+17 1.51E+17 1.69E+17 1.86E+17

-243.84 4.58E+16 5.26E+16 6.37E+16 7.47E+16 8.57E+16 9.68E+16 1.08E+17 1.19E+17

-259.08 3.20E+16 3.68E+16 4.46E+16 5.24E+16 6.02E+16 6.79E+16 7.57E+16 8.35E+16

-274.32 2.50E+16 2.87E+16 3.48E+16 4.09E+16 4.70E+16 5.31E+16 5.92E+16 6.53E+16

-289.56 2.04E+16 2.35E+16 2.85E+16 3.35E+16 3.85E+16 4.34E+16 4.84E+16 5.34E+16 Note(s):

1. Elevations are given with respect to the midplane of the active fuel.

2. Value listed is the projected EFPY at the end of Cycle 25.

3. This elevation corresponds to the top of the 6-inch-thick horizontal plate at the top-center of the RPV support structure.

4. Linear interpolation between the EFPY values listed in this table may be performed as necessary.

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 37 of 56 Table 4-15 Fast Neutron (E > 0.1 MeV) Fluence at the RPV Support Structure -

No Bias on the Peripheral and Re-Entrant Corner Assembly Relative Powers Elevation[1] Fast Neutron (E > 0.1 MeV) Fluence (n/cm2)

(cm) 32.30 EFPY[2] 36 EFPY 42 EFPY 48 EFPY 54 EFPY 60 EFPY 66 EFPY 72 EFPY

[3]

231.16 1.77E+18 2.01E+18 2.40E+18 2.79E+18 3.17E+18 3.56E+18 3.95E+18 4.33E+18 228.60 1.90E+18 2.15E+18 2.56E+18 2.98E+18 3.39E+18 3.80E+18 4.22E+18 4.63E+18 213.36 2.70E+18 3.06E+18 3.65E+18 4.24E+18 4.82E+18 5.41E+18 6.00E+18 6.59E+18 198.12 3.54E+18 4.01E+18 4.79E+18 5.56E+18 6.33E+18 7.10E+18 7.88E+18 8.65E+18 182.88 4.73E+18 5.37E+18 6.41E+18 7.45E+18 8.49E+18 9.53E+18 1.06E+19 1.16E+19 167.64 6.19E+18 7.04E+18 8.41E+18 9.78E+18 1.12E+19 1.25E+19 1.39E+19 1.53E+19 152.40 7.74E+18 8.80E+18 1.05E+19 1.23E+19 1.40E+19 1.57E+19 1.75E+19 1.92E+19 137.16 9.17E+18 1.04E+19 1.25E+19 1.46E+19 1.67E+19 1.87E+19 2.08E+19 2.29E+19 121.92 1.04E+19 1.18E+19 1.42E+19 1.65E+19 1.89E+19 2.12E+19 2.36E+19 2.60E+19 106.68 1.14E+19 1.30E+19 1.56E+19 1.82E+19 2.08E+19 2.34E+19 2.60E+19 2.86E+19 91.44 1.26E+19 1.44E+19 1.73E+19 2.01E+19 2.30E+19 2.59E+19 2.88E+19 3.17E+19 76.20 1.24E+19 1.42E+19 1.70E+19 1.98E+19 2.27E+19 2.55E+19 2.84E+19 3.12E+19 60.96 1.23E+19 1.41E+19 1.69E+19 1.97E+19 2.26E+19 2.54E+19 2.82E+19 3.10E+19 45.72 1.23E+19 1.41E+19 1.69E+19 1.98E+19 2.26E+19 2.54E+19 2.83E+19 3.11E+19 30.48 1.23E+19 1.41E+19 1.69E+19 1.97E+19 2.26E+19 2.54E+19 2.82E+19 3.11E+19 15.24 1.23E+19 1.40E+19 1.69E+19 1.97E+19 2.25E+19 2.53E+19 2.82E+19 3.10E+19 0.00 1.23E+19 1.40E+19 1.68E+19 1.96E+19 2.25E+19 2.53E+19 2.81E+19 3.09E+19

-15.24 1.22E+19 1.40E+19 1.68E+19 1.96E+19 2.24E+19 2.53E+19 2.81E+19 3.09E+19

-30.48 1.22E+19 1.39E+19 1.67E+19 1.95E+19 2.23E+19 2.51E+19 2.79E+19 3.07E+19

-45.72 1.21E+19 1.38E+19 1.66E+19 1.93E+19 2.21E+19 2.49E+19 2.77E+19 3.05E+19

-60.96 1.19E+19 1.36E+19 1.63E+19 1.91E+19 2.18E+19 2.46E+19 2.73E+19 3.00E+19

-76.20 1.16E+19 1.33E+19 1.60E+19 1.87E+19 2.13E+19 2.40E+19 2.67E+19 2.94E+19

-91.44 1.12E+19 1.28E+19 1.54E+19 1.80E+19 2.06E+19 2.32E+19 2.58E+19 2.84E+19

-106.68 1.06E+19 1.21E+19 1.46E+19 1.70E+19 1.95E+19 2.19E+19 2.44E+19 2.68E+19

-121.92 9.73E+18 1.11E+19 1.34E+19 1.56E+19 1.78E+19 2.01E+19 2.23E+19 2.46E+19

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 38 of 56 Table 4-15 Fast Neutron (E > 0.1 MeV) Fluence at the RPV Support Structure -

No Bias on the Peripheral and Re-Entrant Corner Assembly Relative Powers Elevation[1] Fast Neutron (E > 0.1 MeV) Fluence (n/cm2)

(cm) 32.30 EFPY[2] 36 EFPY 42 EFPY 48 EFPY 54 EFPY 60 EFPY 66 EFPY 72 EFPY

-137.16 8.59E+18 9.81E+18 1.18E+19 1.38E+19 1.57E+19 1.77E+19 1.97E+19 2.17E+19

-152.40 7.24E+18 8.26E+18 9.91E+18 1.16E+19 1.32E+19 1.49E+19 1.65E+19 1.82E+19

-167.64 5.75E+18 6.55E+18 7.86E+18 9.16E+18 1.05E+19 1.18E+19 1.31E+19 1.44E+19

-182.88 4.32E+18 4.91E+18 5.88E+18 6.85E+18 7.82E+18 8.79E+18 9.76E+18 1.07E+19

-198.12 3.10E+18 3.53E+18 4.22E+18 4.92E+18 5.61E+18 6.30E+18 7.00E+18 7.69E+18

-213.36 2.19E+18 2.49E+18 2.98E+18 3.46E+18 3.95E+18 4.44E+18 4.93E+18 5.42E+18

-228.60 1.56E+18 1.77E+18 2.12E+18 2.47E+18 2.82E+18 3.17E+18 3.51E+18 3.86E+18

-243.84 1.13E+18 1.29E+18 1.54E+18 1.80E+18 2.05E+18 2.30E+18 2.56E+18 2.81E+18

-259.08 8.44E+17 9.61E+17 1.15E+18 1.34E+18 1.53E+18 1.72E+18 1.91E+18 2.10E+18

-274.32 6.64E+17 7.56E+17 9.06E+17 1.06E+18 1.21E+18 1.35E+18 1.50E+18 1.65E+18

-289.56 5.42E+17 6.17E+17 7.39E+17 8.61E+17 9.83E+17 1.11E+18 1.23E+18 1.35E+18 Note(s):

1. Elevations are given with respect to the midplane of the active fuel.

2. Value listed is the projected EFPY at the end of Cycle 25.

3. This elevation corresponds to the top of the 6-inch-thick horizontal plate at the top-center of the RPV support structure.

4. Linear interpolation between the EFPY values listed in this table may be performed as necessary.

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 39 of 56 Table 4-16 Fast Neutron (E > 0.1 MeV) Fluence at the RPV Support Structure -

+10% Bias on the Peripheral and Re-Entrant Corner Assembly Relative Powers Elevation[1] Fast Neutron (E > 0.1 MeV) Fluence (n/cm2)

(cm) 32.30 EFPY[2] 36 EFPY 42 EFPY 48 EFPY 54 EFPY 60 EFPY 66 EFPY 72 EFPY

[3]

231.16 1.77E+18 2.03E+18 2.45E+18 2.88E+18 3.30E+18 3.72E+18 4.14E+18 4.56E+18 228.60 1.90E+18 2.17E+18 2.62E+18 3.07E+18 3.52E+18 3.97E+18 4.42E+18 4.87E+18 213.36 2.70E+18 3.09E+18 3.73E+18 4.37E+18 5.01E+18 5.65E+18 6.29E+18 6.93E+18 198.12 3.54E+18 4.06E+18 4.90E+18 5.74E+18 6.58E+18 7.42E+18 8.26E+18 9.10E+18 182.88 4.73E+18 5.43E+18 6.56E+18 7.69E+18 8.83E+18 9.96E+18 1.11E+19 1.22E+19 167.64 6.19E+18 7.11E+18 8.61E+18 1.01E+19 1.16E+19 1.31E+19 1.46E+19 1.61E+19 152.40 7.74E+18 8.90E+18 1.08E+19 1.27E+19 1.46E+19 1.64E+19 1.83E+19 2.02E+19 137.16 9.17E+18 1.06E+19 1.28E+19 1.51E+19 1.73E+19 1.96E+19 2.18E+19 2.41E+19 121.92 1.04E+19 1.20E+19 1.45E+19 1.71E+19 1.97E+19 2.22E+19 2.48E+19 2.74E+19 106.68 1.14E+19 1.31E+19 1.60E+19 1.88E+19 2.16E+19 2.45E+19 2.73E+19 3.01E+19 91.44 1.26E+19 1.45E+19 1.77E+19 2.08E+19 2.40E+19 2.71E+19 3.03E+19 3.34E+19 76.20 1.24E+19 1.43E+19 1.74E+19 2.05E+19 2.36E+19 2.67E+19 2.98E+19 3.29E+19 60.96 1.23E+19 1.42E+19 1.73E+19 2.04E+19 2.35E+19 2.66E+19 2.96E+19 3.27E+19 45.72 1.23E+19 1.42E+19 1.73E+19 2.04E+19 2.35E+19 2.66E+19 2.97E+19 3.28E+19 30.48 1.23E+19 1.42E+19 1.73E+19 2.04E+19 2.35E+19 2.66E+19 2.97E+19 3.28E+19 15.24 1.23E+19 1.42E+19 1.73E+19 2.04E+19 2.34E+19 2.65E+19 2.96E+19 3.27E+19 0.00 1.23E+19 1.42E+19 1.72E+19 2.03E+19 2.34E+19 2.65E+19 2.95E+19 3.26E+19

-15.24 1.22E+19 1.41E+19 1.72E+19 2.03E+19 2.33E+19 2.64E+19 2.95E+19 3.26E+19

-30.48 1.22E+19 1.41E+19 1.71E+19 2.02E+19 2.32E+19 2.63E+19 2.93E+19 3.24E+19

-45.72 1.21E+19 1.39E+19 1.70E+19 2.00E+19 2.30E+19 2.60E+19 2.91E+19 3.21E+19

-60.96 1.19E+19 1.37E+19 1.67E+19 1.97E+19 2.27E+19 2.57E+19 2.87E+19 3.16E+19

-76.20 1.16E+19 1.34E+19 1.63E+19 1.93E+19 2.22E+19 2.51E+19 2.80E+19 3.10E+19

-91.44 1.12E+19 1.30E+19 1.58E+19 1.86E+19 2.14E+19 2.42E+19 2.71E+19 2.99E+19

-106.68 1.06E+19 1.22E+19 1.49E+19 1.76E+19 2.02E+19 2.29E+19 2.56E+19 2.82E+19

-121.92 9.73E+18 1.12E+19 1.37E+19 1.61E+19 1.86E+19 2.10E+19 2.34E+19 2.59E+19

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 40 of 56 Table 4-16 Fast Neutron (E > 0.1 MeV) Fluence at the RPV Support Structure -

+10% Bias on the Peripheral and Re-Entrant Corner Assembly Relative Powers Elevation[1] Fast Neutron (E > 0.1 MeV) Fluence (n/cm2)

(cm) 32.30 EFPY[2] 36 EFPY 42 EFPY 48 EFPY 54 EFPY 60 EFPY 66 EFPY 72 EFPY

-137.16 8.59E+18 9.92E+18 1.21E+19 1.42E+19 1.64E+19 1.85E+19 2.07E+19 2.28E+19

-152.40 7.24E+18 8.35E+18 1.01E+19 1.19E+19 1.37E+19 1.55E+19 1.73E+19 1.91E+19

-167.64 5.75E+18 6.63E+18 8.04E+18 9.46E+18 1.09E+19 1.23E+19 1.37E+19 1.51E+19

-182.88 4.32E+18 4.97E+18 6.02E+18 7.08E+18 8.13E+18 9.19E+18 1.02E+19 1.13E+19

-198.12 3.10E+18 3.57E+18 4.32E+18 5.08E+18 5.83E+18 6.58E+18 7.34E+18 8.09E+18

-213.36 2.19E+18 2.51E+18 3.05E+18 3.58E+18 4.11E+18 4.64E+18 5.17E+18 5.70E+18

-228.60 1.56E+18 1.79E+18 2.17E+18 2.55E+18 2.93E+18 3.31E+18 3.69E+18 4.07E+18

-243.84 1.13E+18 1.30E+18 1.58E+18 1.86E+18 2.13E+18 2.41E+18 2.69E+18 2.96E+18

-259.08 8.44E+17 9.71E+17 1.18E+18 1.38E+18 1.59E+18 1.80E+18 2.01E+18 2.21E+18

-274.32 6.64E+17 7.65E+17 9.28E+17 1.09E+18 1.25E+18 1.42E+18 1.58E+18 1.74E+18

-289.56 5.42E+17 6.24E+17 7.57E+17 8.90E+17 1.02E+18 1.16E+18 1.29E+18 1.42E+18 Note(s):

1. Elevations are given with respect to the midplane of the active fuel.

2. Value listed is the projected EFPY at the end of Cycle 25.

3. This elevation corresponds to the top of the 6-inch-thick horizontal plate at the top-center of the RPV support structure.

4. Linear interpolation between the EFPY values listed in this table may be performed as necessary.

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 41 of 56 Table 4-17 Iron Atom Displacements (All Neutron Energies) at the RPV Support Structure -

No Bias on the Peripheral and Re-Entrant Corner Assembly Relative Powers Elevation[1] Iron Atom Displacements - All Neutron Energies (dpa)

(cm) 32.30 EFPY [2]

36 EFPY 42 EFPY 48 EFPY 54 EFPY 60 EFPY 66 EFPY 72 EFPY

[3]

231.16 5.25E-04 5.95E-04 7.09E-04 8.23E-04 9.38E-04 1.05E-03 1.17E-03 1.28E-03 228.60 5.62E-04 6.37E-04 7.60E-04 8.82E-04 1.00E-03 1.13E-03 1.25E-03 1.37E-03 213.36 8.17E-04 9.26E-04 1.10E-03 1.28E-03 1.46E-03 1.64E-03 1.81E-03 1.99E-03 198.12 1.10E-03 1.25E-03 1.49E-03 1.72E-03 1.96E-03 2.20E-03 2.44E-03 2.68E-03 182.88 1.50E-03 1.71E-03 2.04E-03 2.37E-03 2.70E-03 3.02E-03 3.35E-03 3.68E-03 167.64 2.00E-03 2.28E-03 2.72E-03 3.16E-03 3.61E-03 4.05E-03 4.49E-03 4.94E-03 152.40 2.53E-03 2.88E-03 3.45E-03 4.02E-03 4.58E-03 5.15E-03 5.71E-03 6.28E-03 137.16 3.02E-03 3.44E-03 4.12E-03 4.81E-03 5.49E-03 6.17E-03 6.85E-03 7.53E-03 121.92 3.43E-03 3.91E-03 4.68E-03 5.46E-03 6.24E-03 7.02E-03 7.80E-03 8.58E-03 106.68 3.76E-03 4.29E-03 5.14E-03 6.00E-03 6.86E-03 7.71E-03 8.57E-03 9.43E-03 91.44 4.14E-03 4.72E-03 5.67E-03 6.62E-03 7.56E-03 8.51E-03 9.46E-03 1.04E-02 76.20 4.08E-03 4.66E-03 5.59E-03 6.53E-03 7.46E-03 8.40E-03 9.34E-03 1.03E-02 60.96 4.07E-03 4.65E-03 5.58E-03 6.51E-03 7.45E-03 8.38E-03 9.32E-03 1.02E-02 45.72 4.08E-03 4.66E-03 5.60E-03 6.53E-03 7.47E-03 8.41E-03 9.35E-03 1.03E-02 30.48 4.08E-03 4.66E-03 5.60E-03 6.53E-03 7.47E-03 8.41E-03 9.35E-03 1.03E-02 15.24 4.07E-03 4.65E-03 5.58E-03 6.52E-03 7.46E-03 8.39E-03 9.33E-03 1.03E-02 0.00 4.06E-03 4.64E-03 5.57E-03 6.51E-03 7.45E-03 8.38E-03 9.32E-03 1.03E-02

-15.24 4.06E-03 4.63E-03 5.57E-03 6.51E-03 7.44E-03 8.38E-03 9.31E-03 1.02E-02

-30.48 4.04E-03 4.62E-03 5.55E-03 6.48E-03 7.41E-03 8.34E-03 9.28E-03 1.02E-02

-45.72 4.01E-03 4.58E-03 5.50E-03 6.43E-03 7.35E-03 8.27E-03 9.20E-03 1.01E-02

-60.96 3.96E-03 4.52E-03 5.43E-03 6.34E-03 7.26E-03 8.17E-03 9.08E-03 1.00E-02

-76.20 3.88E-03 4.43E-03 5.32E-03 6.22E-03 7.11E-03 8.01E-03 8.91E-03 9.80E-03

-91.44 3.75E-03 4.28E-03 5.15E-03 6.01E-03 6.88E-03 7.75E-03 8.61E-03 9.48E-03

-106.68 3.54E-03 4.05E-03 4.87E-03 5.68E-03 6.50E-03 7.32E-03 8.14E-03 8.96E-03

-121.92 3.25E-03 3.71E-03 4.46E-03 5.21E-03 5.96E-03 6.71E-03 7.46E-03 8.21E-03

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 42 of 56 Table 4-17 Iron Atom Displacements (All Neutron Energies) at the RPV Support Structure -

No Bias on the Peripheral and Re-Entrant Corner Assembly Relative Powers Elevation[1] Iron Atom Displacements - All Neutron Energies (dpa)

(cm) 32.30 EFPY [2]

36 EFPY 42 EFPY 48 EFPY 54 EFPY 60 EFPY 66 EFPY 72 EFPY

-137.16 2.87E-03 3.27E-03 3.93E-03 4.59E-03 5.25E-03 5.91E-03 6.57E-03 7.23E-03

-152.40 2.40E-03 2.74E-03 3.29E-03 3.84E-03 4.38E-03 4.93E-03 5.48E-03 6.03E-03

-167.64 1.89E-03 2.15E-03 2.58E-03 3.01E-03 3.43E-03 3.86E-03 4.29E-03 4.72E-03

-182.88 1.39E-03 1.59E-03 1.90E-03 2.21E-03 2.52E-03 2.84E-03 3.15E-03 3.46E-03

-198.12 9.80E-04 1.11E-03 1.33E-03 1.55E-03 1.77E-03 1.99E-03 2.21E-03 2.43E-03

-213.36 6.76E-04 7.69E-04 9.19E-04 1.07E-03 1.22E-03 1.37E-03 1.52E-03 1.67E-03

-228.60 4.73E-04 5.38E-04 6.43E-04 7.49E-04 8.55E-04 9.60E-04 1.07E-03 1.17E-03

-243.84 3.40E-04 3.87E-04 4.63E-04 5.39E-04 6.15E-04 6.91E-04 7.67E-04 8.43E-04

-259.08 2.53E-04 2.87E-04 3.44E-04 4.01E-04 4.58E-04 5.14E-04 5.71E-04 6.28E-04

-274.32 1.99E-04 2.27E-04 2.72E-04 3.17E-04 3.62E-04 4.07E-04 4.51E-04 4.96E-04

-289.56 1.63E-04 1.86E-04 2.23E-04 2.59E-04 2.96E-04 3.33E-04 3.70E-04 4.07E-04 Note(s):

1. Elevations are given with respect to the midplane of the active fuel.

2. Value listed is the projected EFPY at the end of Cycle 25.

3. This elevation corresponds to the top of the 6-inch-thick horizontal plate at the top-center of the RPV support structure.

4. Linear interpolation between the EFPY values listed in this table may be performed as necessary.

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 43 of 56 Table 4-18 Iron Atom Displacements (All Neutron Energies) at the RPV Support Structure -

+10% Bias on the Peripheral and Re-Entrant Corner Assembly Relative Powers Elevation[1] Iron Atom Displacements - All Neutron Energies (dpa)

(cm) 32.30 EFPY [2]

36 EFPY 42 EFPY 48 EFPY 54 EFPY 60 EFPY 66 EFPY 72 EFPY

[3]

231.16 5.25E-04 6.01E-04 7.26E-04 8.50E-04 9.74E-04 1.10E-03 1.22E-03 1.35E-03 228.60 5.62E-04 6.44E-04 7.77E-04 9.10E-04 1.04E-03 1.18E-03 1.31E-03 1.44E-03 213.36 8.17E-04 9.36E-04 1.13E-03 1.32E-03 1.52E-03 1.71E-03 1.90E-03 2.09E-03 198.12 1.10E-03 1.26E-03 1.52E-03 1.78E-03 2.04E-03 2.30E-03 2.56E-03 2.82E-03 182.88 1.50E-03 1.73E-03 2.08E-03 2.44E-03 2.80E-03 3.16E-03 3.52E-03 3.88E-03 167.64 2.00E-03 2.30E-03 2.79E-03 3.27E-03 3.75E-03 4.23E-03 4.72E-03 5.20E-03 152.40 2.53E-03 2.91E-03 3.53E-03 4.15E-03 4.77E-03 5.38E-03 6.00E-03 6.62E-03 137.16 3.02E-03 3.48E-03 4.22E-03 4.97E-03 5.71E-03 6.45E-03 7.20E-03 7.94E-03 121.92 3.43E-03 3.95E-03 4.80E-03 5.65E-03 6.50E-03 7.34E-03 8.19E-03 9.04E-03 106.68 3.76E-03 4.33E-03 5.27E-03 6.20E-03 7.14E-03 8.07E-03 9.01E-03 9.94E-03 91.44 4.14E-03 4.77E-03 5.81E-03 6.84E-03 7.87E-03 8.90E-03 9.94E-03 1.10E-02 76.20 4.08E-03 4.71E-03 5.73E-03 6.75E-03 7.77E-03 8.79E-03 9.81E-03 1.08E-02 60.96 4.07E-03 4.70E-03 5.72E-03 6.73E-03 7.75E-03 8.77E-03 9.79E-03 1.08E-02 45.72 4.08E-03 4.71E-03 5.73E-03 6.75E-03 7.77E-03 8.80E-03 9.82E-03 1.08E-02 30.48 4.08E-03 4.71E-03 5.73E-03 6.75E-03 7.77E-03 8.80E-03 9.82E-03 1.08E-02 15.24 4.07E-03 4.70E-03 5.72E-03 6.74E-03 7.76E-03 8.78E-03 9.80E-03 1.08E-02 0.00 4.06E-03 4.69E-03 5.71E-03 6.73E-03 7.75E-03 8.77E-03 9.78E-03 1.08E-02

-15.24 4.06E-03 4.69E-03 5.70E-03 6.72E-03 7.74E-03 8.76E-03 9.78E-03 1.08E-02

-30.48 4.04E-03 4.67E-03 5.68E-03 6.70E-03 7.71E-03 8.72E-03 9.74E-03 1.08E-02

-45.72 4.01E-03 4.63E-03 5.63E-03 6.64E-03 7.65E-03 8.65E-03 9.66E-03 1.07E-02

-60.96 3.96E-03 4.57E-03 5.56E-03 6.55E-03 7.55E-03 8.54E-03 9.54E-03 1.05E-02

-76.20 3.88E-03 4.48E-03 5.45E-03 6.43E-03 7.40E-03 8.37E-03 9.35E-03 1.03E-02

-91.44 3.75E-03 4.33E-03 5.27E-03 6.21E-03 7.16E-03 8.10E-03 9.04E-03 9.98E-03

-106.68 3.54E-03 4.09E-03 4.98E-03 5.87E-03 6.76E-03 7.65E-03 8.55E-03 9.44E-03

-121.92 3.25E-03 3.75E-03 4.57E-03 5.38E-03 6.20E-03 7.02E-03 7.83E-03 8.65E-03

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 44 of 56 Table 4-18 Iron Atom Displacements (All Neutron Energies) at the RPV Support Structure -

+10% Bias on the Peripheral and Re-Entrant Corner Assembly Relative Powers Elevation[1] Iron Atom Displacements - All Neutron Energies (dpa)

(cm) 32.30 EFPY [2]

36 EFPY 42 EFPY 48 EFPY 54 EFPY 60 EFPY 66 EFPY 72 EFPY

-137.16 2.87E-03 3.31E-03 4.02E-03 4.74E-03 5.46E-03 6.18E-03 6.89E-03 7.61E-03

-152.40 2.40E-03 2.77E-03 3.37E-03 3.96E-03 4.56E-03 5.15E-03 5.75E-03 6.35E-03

-167.64 1.89E-03 2.18E-03 2.64E-03 3.11E-03 3.57E-03 4.04E-03 4.50E-03 4.96E-03

-182.88 1.39E-03 1.60E-03 1.94E-03 2.28E-03 2.62E-03 2.96E-03 3.30E-03 3.64E-03

-198.12 9.80E-04 1.13E-03 1.36E-03 1.60E-03 1.84E-03 2.08E-03 2.32E-03 2.55E-03

-213.36 6.76E-04 7.77E-04 9.41E-04 1.10E-03 1.27E-03 1.43E-03 1.60E-03 1.76E-03

-228.60 4.73E-04 5.44E-04 6.58E-04 7.73E-04 8.88E-04 1.00E-03 1.12E-03 1.23E-03

-243.84 3.40E-04 3.91E-04 4.74E-04 5.57E-04 6.40E-04 7.22E-04 8.05E-04 8.88E-04

-259.08 2.53E-04 2.91E-04 3.52E-04 4.14E-04 4.76E-04 5.38E-04 6.00E-04 6.62E-04

-274.32 1.99E-04 2.29E-04 2.78E-04 3.27E-04 3.76E-04 4.25E-04 4.74E-04 5.23E-04

-289.56 1.63E-04 1.88E-04 2.28E-04 2.68E-04 3.08E-04 3.48E-04 3.88E-04 4.28E-04 Note(s):

1. Elevations are given with respect to the midplane of the active fuel.

2. Value listed is the projected EFPY at the end of Cycle 25.

3. This elevation corresponds to the top of the 6-inch-thick horizontal plate at the top-center of the RPV support structure.

4. Linear interpolation between the EFPY values listed in this table may be performed as necessary.

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 45 of 56 Table 4-19 Iron Atom Displacements (E > 0.1 MeV) at the RPV Support Structure -

No Bias on the Peripheral and Re-Entrant Corner Assembly Relative Powers Elevation[1] Iron Atom Displacements - Neutron Energies > 0.1 MeV (dpa)

(cm) 32.30 EFPY [2]

36 EFPY 42 EFPY 48 EFPY 54 EFPY 60 EFPY 66 EFPY 72 EFPY

[3]

231.16 4.49E-04 5.09E-04 6.06E-04 7.04E-04 8.01E-04 8.99E-04 9.96E-04 1.09E-03 228.60 4.82E-04 5.47E-04 6.52E-04 7.56E-04 8.61E-04 9.66E-04 1.07E-03 1.18E-03 213.36 7.15E-04 8.11E-04 9.66E-04 1.12E-03 1.28E-03 1.43E-03 1.59E-03 1.74E-03 198.12 9.78E-04 1.11E-03 1.32E-03 1.53E-03 1.75E-03 1.96E-03 2.17E-03 2.38E-03 182.88 1.36E-03 1.54E-03 1.84E-03 2.13E-03 2.43E-03 2.73E-03 3.02E-03 3.32E-03 167.64 1.83E-03 2.08E-03 2.48E-03 2.88E-03 3.29E-03 3.69E-03 4.09E-03 4.50E-03 152.40 2.32E-03 2.64E-03 3.16E-03 3.68E-03 4.20E-03 4.72E-03 5.24E-03 5.76E-03 137.16 2.78E-03 3.17E-03 3.79E-03 4.42E-03 5.05E-03 5.67E-03 6.30E-03 6.93E-03 121.92 3.16E-03 3.60E-03 4.31E-03 5.03E-03 5.75E-03 6.46E-03 7.18E-03 7.90E-03 106.68 3.46E-03 3.95E-03 4.74E-03 5.53E-03 6.32E-03 7.11E-03 7.90E-03 8.69E-03 91.44 3.81E-03 4.35E-03 5.22E-03 6.09E-03 6.97E-03 7.84E-03 8.71E-03 9.59E-03 76.20 3.76E-03 4.29E-03 5.15E-03 6.01E-03 6.87E-03 7.74E-03 8.60E-03 9.46E-03 60.96 3.75E-03 4.28E-03 5.14E-03 6.00E-03 6.86E-03 7.72E-03 8.58E-03 9.45E-03 45.72 3.76E-03 4.30E-03 5.16E-03 6.02E-03 6.89E-03 7.75E-03 8.62E-03 9.48E-03 30.48 3.76E-03 4.30E-03 5.16E-03 6.03E-03 6.89E-03 7.76E-03 8.62E-03 9.49E-03 15.24 3.75E-03 4.29E-03 5.15E-03 6.01E-03 6.88E-03 7.74E-03 8.61E-03 9.47E-03 0.00 3.75E-03 4.28E-03 5.14E-03 6.01E-03 6.87E-03 7.73E-03 8.60E-03 9.46E-03

-15.24 3.75E-03 4.28E-03 5.14E-03 6.01E-03 6.87E-03 7.73E-03 8.60E-03 9.46E-03

-30.48 3.73E-03 4.26E-03 5.12E-03 5.98E-03 6.85E-03 7.71E-03 8.57E-03 9.43E-03

-45.72 3.70E-03 4.23E-03 5.08E-03 5.94E-03 6.79E-03 7.65E-03 8.50E-03 9.35E-03

-60.96 3.66E-03 4.18E-03 5.02E-03 5.87E-03 6.71E-03 7.55E-03 8.40E-03 9.24E-03

-76.20 3.58E-03 4.10E-03 4.92E-03 5.75E-03 6.58E-03 7.41E-03 8.24E-03 9.07E-03

-91.44 3.47E-03 3.96E-03 4.76E-03 5.57E-03 6.37E-03 7.17E-03 7.97E-03 8.77E-03

-106.68 3.28E-03 3.74E-03 4.50E-03 5.26E-03 6.02E-03 6.78E-03 7.54E-03 8.29E-03

-121.92 3.01E-03 3.43E-03 4.13E-03 4.82E-03 5.52E-03 6.21E-03 6.90E-03 7.60E-03

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 46 of 56 Table 4-19 Iron Atom Displacements (E > 0.1 MeV) at the RPV Support Structure -

No Bias on the Peripheral and Re-Entrant Corner Assembly Relative Powers Elevation[1] Iron Atom Displacements - Neutron Energies > 0.1 MeV (dpa)

(cm) 32.30 EFPY [2]

36 EFPY 42 EFPY 48 EFPY 54 EFPY 60 EFPY 66 EFPY 72 EFPY

-137.16 2.65E-03 3.02E-03 3.63E-03 4.24E-03 4.85E-03 5.46E-03 6.07E-03 6.68E-03

-152.40 2.21E-03 2.52E-03 3.03E-03 3.53E-03 4.04E-03 4.54E-03 5.05E-03 5.55E-03

-167.64 1.73E-03 1.97E-03 2.36E-03 2.76E-03 3.15E-03 3.54E-03 3.93E-03 4.32E-03

-182.88 1.27E-03 1.44E-03 1.73E-03 2.01E-03 2.29E-03 2.58E-03 2.86E-03 3.15E-03

-198.12 8.80E-04 1.00E-03 1.20E-03 1.39E-03 1.59E-03 1.79E-03 1.98E-03 2.18E-03

-213.36 5.98E-04 6.80E-04 8.13E-04 9.46E-04 1.08E-03 1.21E-03 1.35E-03 1.48E-03

-228.60 4.12E-04 4.69E-04 5.61E-04 6.53E-04 7.44E-04 8.36E-04 9.28E-04 1.02E-03

-243.84 2.93E-04 3.33E-04 3.98E-04 4.64E-04 5.29E-04 5.95E-04 6.60E-04 7.26E-04

-259.08 2.15E-04 2.45E-04 2.94E-04 3.42E-04 3.90E-04 4.39E-04 4.87E-04 5.35E-04

-274.32 1.69E-04 1.92E-04 2.30E-04 2.68E-04 3.06E-04 3.44E-04 3.82E-04 4.20E-04

-289.56 1.38E-04 1.57E-04 1.88E-04 2.19E-04 2.49E-04 2.80E-04 3.11E-04 3.42E-04 Note(s):

1. Elevations are given with respect to the midplane of the active fuel.

2. Value listed is the projected EFPY at the end of Cycle 25.

3. This elevation corresponds to the top of the 6-inch-thick horizontal plate at the top-center of the RPV support structure.

4. Linear interpolation between the EFPY values listed in this table may be performed as necessary.

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 47 of 56 Table 4-20 Iron Atom Displacements (E > 0.1 MeV) at the RPV Support Structure -

+10% Bias on the Peripheral and Re-Entrant Corner Assembly Relative Powers Elevation[1] Iron Atom Displacements - Neutron Energies > 0.1 MeV (dpa)

(cm) 32.30 EFPY [2]

36 EFPY 42 EFPY 48 EFPY 54 EFPY 60 EFPY 66 EFPY 72 EFPY

[3]

231.16 4.49E-04 5.14E-04 6.20E-04 7.26E-04 8.32E-04 9.38E-04 1.04E-03 1.15E-03 228.60 4.82E-04 5.53E-04 6.67E-04 7.81E-04 8.95E-04 1.01E-03 1.12E-03 1.24E-03 213.36 7.15E-04 8.19E-04 9.88E-04 1.16E-03 1.33E-03 1.49E-03 1.66E-03 1.83E-03 198.12 9.78E-04 1.12E-03 1.35E-03 1.58E-03 1.81E-03 2.05E-03 2.28E-03 2.51E-03 182.88 1.36E-03 1.56E-03 1.88E-03 2.20E-03 2.53E-03 2.85E-03 3.17E-03 3.50E-03 167.64 1.83E-03 2.10E-03 2.54E-03 2.98E-03 3.42E-03 3.86E-03 4.30E-03 4.74E-03 152.40 2.32E-03 2.67E-03 3.24E-03 3.80E-03 4.37E-03 4.93E-03 5.50E-03 6.06E-03 137.16 2.78E-03 3.20E-03 3.88E-03 4.57E-03 5.25E-03 5.94E-03 6.62E-03 7.30E-03 121.92 3.16E-03 3.64E-03 4.42E-03 5.20E-03 5.98E-03 6.76E-03 7.55E-03 8.33E-03 106.68 3.46E-03 3.99E-03 4.85E-03 5.71E-03 6.58E-03 7.44E-03 8.30E-03 9.16E-03 91.44 3.81E-03 4.40E-03 5.35E-03 6.30E-03 7.25E-03 8.20E-03 9.15E-03 1.01E-02 76.20 3.76E-03 4.34E-03 5.28E-03 6.22E-03 7.16E-03 8.09E-03 9.03E-03 9.97E-03 60.96 3.75E-03 4.33E-03 5.27E-03 6.20E-03 7.14E-03 8.08E-03 9.02E-03 9.96E-03 45.72 3.76E-03 4.34E-03 5.28E-03 6.23E-03 7.17E-03 8.11E-03 9.05E-03 9.99E-03 30.48 3.76E-03 4.34E-03 5.29E-03 6.23E-03 7.17E-03 8.11E-03 9.06E-03 1.00E-02 15.24 3.75E-03 4.33E-03 5.27E-03 6.22E-03 7.16E-03 8.10E-03 9.04E-03 9.98E-03 0.00 3.75E-03 4.33E-03 5.27E-03 6.21E-03 7.15E-03 8.09E-03 9.03E-03 9.97E-03

-15.24 3.75E-03 4.32E-03 5.27E-03 6.21E-03 7.15E-03 8.09E-03 9.03E-03 9.97E-03

-30.48 3.73E-03 4.31E-03 5.25E-03 6.18E-03 7.12E-03 8.06E-03 8.99E-03 9.93E-03

-45.72 3.70E-03 4.27E-03 5.20E-03 6.13E-03 7.06E-03 7.99E-03 8.92E-03 9.85E-03

-60.96 3.66E-03 4.22E-03 5.14E-03 6.06E-03 6.98E-03 7.90E-03 8.82E-03 9.73E-03

-76.20 3.58E-03 4.14E-03 5.04E-03 5.94E-03 6.84E-03 7.75E-03 8.65E-03 9.55E-03

-91.44 3.47E-03 4.00E-03 4.88E-03 5.75E-03 6.62E-03 7.49E-03 8.37E-03 9.24E-03

-106.68 3.28E-03 3.79E-03 4.61E-03 5.44E-03 6.26E-03 7.08E-03 7.91E-03 8.73E-03

-121.92 3.01E-03 3.47E-03 4.23E-03 4.98E-03 5.74E-03 6.49E-03 7.25E-03 8.00E-03

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 48 of 56 Table 4-20 Iron Atom Displacements (E > 0.1 MeV) at the RPV Support Structure -

+10% Bias on the Peripheral and Re-Entrant Corner Assembly Relative Powers Elevation[1] Iron Atom Displacements - Neutron Energies > 0.1 MeV (dpa)

(cm) 32.30 EFPY [2]

36 EFPY 42 EFPY 48 EFPY 54 EFPY 60 EFPY 66 EFPY 72 EFPY

-137.16 2.65E-03 3.06E-03 3.72E-03 4.38E-03 5.04E-03 5.70E-03 6.37E-03 7.03E-03

-152.40 2.21E-03 2.55E-03 3.10E-03 3.65E-03 4.20E-03 4.75E-03 5.30E-03 5.85E-03

-167.64 1.73E-03 1.99E-03 2.42E-03 2.85E-03 3.27E-03 3.70E-03 4.12E-03 4.55E-03

-182.88 1.27E-03 1.46E-03 1.77E-03 2.08E-03 2.38E-03 2.69E-03 3.00E-03 3.31E-03

-198.12 8.80E-04 1.01E-03 1.23E-03 1.44E-03 1.65E-03 1.87E-03 2.08E-03 2.29E-03

-213.36 5.98E-04 6.87E-04 8.32E-04 9.77E-04 1.12E-03 1.27E-03 1.41E-03 1.56E-03

-228.60 4.12E-04 4.74E-04 5.74E-04 6.74E-04 7.74E-04 8.74E-04 9.74E-04 1.07E-03

-243.84 2.93E-04 3.36E-04 4.08E-04 4.79E-04 5.50E-04 6.22E-04 6.93E-04 7.64E-04

-259.08 2.15E-04 2.48E-04 3.01E-04 3.53E-04 4.06E-04 4.59E-04 5.11E-04 5.64E-04

-274.32 1.69E-04 1.94E-04 2.36E-04 2.77E-04 3.19E-04 3.60E-04 4.01E-04 4.43E-04

-289.56 1.38E-04 1.58E-04 1.92E-04 2.26E-04 2.60E-04 2.93E-04 3.27E-04 3.61E-04 Note(s):

1. Elevations are given with respect to the midplane of the active fuel.

2. Value listed is the projected EFPY at the end of Cycle 25.

3. This elevation corresponds to the top of the 6-inch-thick horizontal plate at the top-center of the RPV support structure.

4. Linear interpolation between the EFPY values listed in this table may be performed as necessary.

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 49 of 56 4.4 Bioshield Concrete Neutron and gamma exposure data for the bioshield concrete are provided in Table 4-21 through Table 4-23.

In particular, fast neutron (E > 1.0 MeV) fluences are provided in Table 4-21 as a function of irradiation time.

Similar data, but for energies greater than 0.1 MeV, are provided in Table 4-22. Calculated gamma doses for the bioshield concrete are provided in Table 4-23. In all cases, the data provided in Table 4-21 through Table 4-23 are the maximum exposures experienced by the bioshield concrete at the azimuthal angles listed relative to the core cardinal axes and at the axial elevation providing the maximum exposure.

Table 4-23 shows that the concrete gamma dose threshold value for consideration of radiation exposure effects, 1x108 Gy (1x1010 rad), is not projected to be exceeded prior to a cumulative operating time of 72 EFPY.

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 50 of 56 Table 4-21 Fast Neutron (E > 1.0 MeV) Fluence at the Bioshield Concrete Cycle Cumulative Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 1 1.11 1.11 5.56E+15 1.90E+16 1.73E+16 1.57E+16 1.73E+16 2.18E+16 2.55E+16 2.55E+16 2 1.12 2.23 1.13E+16 3.84E+16 3.52E+16 3.18E+16 3.50E+16 4.42E+16 5.19E+16 5.19E+16 3 1.22 3.45 1.69E+16 5.71E+16 5.20E+16 4.68E+16 5.18E+16 6.59E+16 7.74E+16 7.74E+16 4 1.16 4.61 2.11E+16 7.26E+16 6.77E+16 6.13E+16 6.74E+16 8.34E+16 9.63E+16 9.63E+16 5 1.30 5.91 2.57E+16 8.99E+16 8.50E+16 7.74E+16 8.48E+16 1.03E+17 1.17E+17 1.17E+17 6 1.35 7.26 3.04E+16 1.06E+17 1.00E+17 9.16E+16 1.00E+17 1.21E+17 1.38E+17 1.38E+17 7 1.21 8.47 3.48E+16 1.21E+17 1.14E+17 1.05E+17 1.14E+17 1.38E+17 1.58E+17 1.58E+17 8 1.38 9.85 3.84E+16 1.34E+17 1.29E+17 1.19E+17 1.29E+17 1.54E+17 1.74E+17 1.74E+17 9 1.22 11.07 4.26E+16 1.50E+17 1.44E+17 1.33E+17 1.44E+17 1.71E+17 1.93E+17 1.93E+17 10 1.44 12.51 4.78E+16 1.69E+17 1.62E+17 1.49E+17 1.62E+17 1.93E+17 2.17E+17 2.17E+17 11 1.32 13.83 5.24E+16 1.85E+17 1.79E+17 1.65E+17 1.79E+17 2.11E+17 2.37E+17 2.37E+17 12 1.51 15.34 5.72E+16 2.02E+17 1.96E+17 1.82E+17 1.96E+17 2.31E+17 2.59E+17 2.59E+17 13 1.29 16.63 6.18E+16 2.18E+17 2.12E+17 1.97E+17 2.11E+17 2.49E+17 2.80E+17 2.80E+17 14 1.43 18.06 6.64E+16 2.34E+17 2.28E+17 2.12E+17 2.27E+17 2.67E+17 3.00E+17 3.00E+17 15 1.15 19.21 7.04E+16 2.48E+17 2.41E+17 2.24E+17 2.40E+17 2.83E+17 3.18E+17 3.18E+17 16 1.25 20.46 7.49E+16 2.63E+17 2.55E+17 2.37E+17 2.55E+17 3.01E+17 3.39E+17 3.39E+17 17 1.25 21.71 7.92E+16 2.78E+17 2.69E+17 2.50E+17 2.69E+17 3.18E+17 3.59E+17 3.59E+17 18 1.42 23.13 8.40E+16 2.95E+17 2.85E+17 2.65E+17 2.85E+17 3.37E+17 3.81E+17 3.81E+17 19 1.19 24.32 8.91E+16 3.13E+17 3.03E+17 2.82E+17 3.02E+17 3.58E+17 4.04E+17 4.04E+17 20 1.23 25.55 9.51E+16 3.34E+17 3.24E+17 3.01E+17 3.23E+17 3.82E+17 4.31E+17 4.31E+17 21 1.28 26.83 1.01E+17 3.55E+17 3.45E+17 3.21E+17 3.44E+17 4.06E+17 4.58E+17 4.58E+17 22 1.31 28.13 1.08E+17 3.80E+17 3.68E+17 3.43E+17 3.67E+17 4.34E+17 4.90E+17 4.90E+17 23 1.40 29.53 1.16E+17 4.06E+17 3.94E+17 3.68E+17 3.93E+17 4.64E+17 5.25E+17 5.25E+17 24 1.34 30.88 1.23E+17 4.29E+17 4.16E+17 3.89E+17 4.15E+17 4.90E+17 5.55E+17 5.55E+17 25[1] 1.43 32.30 1.29E+17 4.52E+17 4.39E+17 4.10E+17 4.38E+17 5.17E+17 5.86E+17 5.86E+17

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 51 of 56 Table 4-21 Fast Neutron (E > 1.0 MeV) Fluence at the Bioshield Concrete Cycle Cumulative Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum Projections with no bias on the peripheral and re-entrant corner assembly relative powers Future[2] -- 36.00 1.47E+17 5.16E+17 5.01E+17 4.68E+17 4.99E+17 5.89E+17 6.68E+17 6.68E+17 Future[2] -- 42.00 1.77E+17 6.18E+17 6.00E+17 5.61E+17 5.98E+17 7.07E+17 8.02E+17 8.02E+17 Future[2] -- 48.00 2.07E+17 7.20E+17 6.99E+17 6.54E+17 6.97E+17 8.24E+17 9.35E+17 9.35E+17 Future[2] -- 54.00 2.36E+17 8.23E+17 7.99E+17 7.47E+17 7.96E+17 9.41E+17 1.07E+18 1.07E+18 Future[2] -- 60.00 2.66E+17 9.25E+17 8.98E+17 8.40E+17 8.96E+17 1.06E+18 1.20E+18 1.20E+18 Future[2] -- 66.00 2.95E+17 1.03E+18 9.98E+17 9.33E+17 9.95E+17 1.18E+18 1.34E+18 1.34E+18 Future[2] -- 72.00 3.25E+17 1.13E+18 1.10E+18 1.03E+18 1.09E+18 1.29E+18 1.47E+18 1.47E+18 Projections with a +10% bias on the peripheral and re-entrant corner assembly relative powers Future[2] -- 36.00 1.49E+17 5.21E+17 5.06E+17 4.73E+17 5.05E+17 5.96E+17 6.75E+17 6.75E+17 Future[2] -- 42.00 1.81E+17 6.33E+17 6.15E+17 5.75E+17 6.13E+17 7.24E+17 8.21E+17 8.21E+17 Future[2] -- 48.00 2.13E+17 7.45E+17 7.24E+17 6.77E+17 7.22E+17 8.52E+17 9.66E+17 9.66E+17 Future[2] -- 54.00 2.46E+17 8.56E+17 8.32E+17 7.79E+17 8.30E+17 9.79E+17 1.11E+18 1.11E+18 Future[2] -- 60.00 2.78E+17 9.68E+17 9.41E+17 8.81E+17 9.38E+17 1.11E+18 1.26E+18 1.26E+18 Future[2] -- 66.00 3.10E+17 1.08E+18 1.05E+18 9.83E+17 1.05E+18 1.23E+18 1.40E+18 1.40E+18 Future[2] -- 72.00 3.42E+17 1.19E+18 1.16E+18 1.08E+18 1.15E+18 1.36E+18 1.55E+18 1.55E+18 Note(s):

1. Cycle 25 was the current operating cycle at the time this summary report was authored.

2. Values beyond Cycle 25 are based on the average core power distributions and reactor operating conditions of Cycle 24 and are determined both with and without a 1.1 bias on the peripheral and re-entrant corner assembly relative powers.

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 52 of 56 Table 4-22 Fast Neutron (E > 0.1 MeV) Fluence at the Bioshield Concrete Cycle Cumulative Fast Neutron (E > 0.1 MeV) Fluence (n/cm2)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 1 1.11 1.11 1.23E+17 2.02E+17 1.80E+17 1.61E+17 1.71E+17 2.06E+17 2.32E+17 2.32E+17 2 1.12 2.23 2.51E+17 4.10E+17 3.66E+17 3.28E+17 3.47E+17 4.17E+17 4.72E+17 4.72E+17 3 1.22 3.45 3.74E+17 6.09E+17 5.41E+17 4.82E+17 5.13E+17 6.20E+17 7.02E+17 7.02E+17 4 1.16 4.61 4.67E+17 7.71E+17 6.97E+17 6.26E+17 6.62E+17 7.83E+17 8.76E+17 8.76E+17 5 1.30 5.91 5.70E+17 9.52E+17 8.71E+17 7.85E+17 8.28E+17 9.65E+17 1.07E+18 1.07E+18 6 1.35 7.26 6.72E+17 1.12E+18 1.03E+18 9.29E+17 9.78E+17 1.14E+18 1.26E+18 1.26E+18 7 1.21 8.47 7.69E+17 1.28E+18 1.17E+18 1.06E+18 1.11E+18 1.30E+18 1.44E+18 1.44E+18 8 1.38 9.85 8.49E+17 1.42E+18 1.32E+18 1.20E+18 1.26E+18 1.44E+18 1.59E+18 1.59E+18 9 1.22 11.07 9.42E+17 1.59E+18 1.47E+18 1.34E+18 1.40E+18 1.61E+18 1.77E+18 1.77E+18 10 1.44 12.51 1.06E+18 1.79E+18 1.66E+18 1.51E+18 1.58E+18 1.81E+18 1.99E+18 1.99E+18 11 1.32 13.83 1.16E+18 1.96E+18 1.82E+18 1.66E+18 1.74E+18 1.99E+18 2.17E+18 2.17E+18 12 1.51 15.34 1.27E+18 2.14E+18 2.00E+18 1.82E+18 1.90E+18 2.17E+18 2.37E+18 2.37E+18 13 1.29 16.63 1.37E+18 2.31E+18 2.16E+18 1.97E+18 2.06E+18 2.34E+18 2.56E+18 2.56E+18 14 1.43 18.06 1.47E+18 2.48E+18 2.32E+18 2.12E+18 2.21E+18 2.51E+18 2.75E+18 2.75E+18 15 1.15 19.21 1.56E+18 2.62E+18 2.45E+18 2.24E+18 2.34E+18 2.66E+18 2.91E+18 2.91E+18 16 1.25 20.46 1.65E+18 2.79E+18 2.60E+18 2.38E+18 2.48E+18 2.82E+18 3.10E+18 3.10E+18 17 1.25 21.71 1.75E+18 2.94E+18 2.74E+18 2.51E+18 2.61E+18 2.99E+18 3.28E+18 3.28E+18 18 1.42 23.13 1.86E+18 3.12E+18 2.91E+18 2.66E+18 2.77E+18 3.17E+18 3.48E+18 3.48E+18 19 1.19 24.32 1.97E+18 3.31E+18 3.09E+18 2.82E+18 2.94E+18 3.36E+18 3.69E+18 3.69E+18 20 1.23 25.55 2.10E+18 3.54E+18 3.30E+18 3.02E+18 3.14E+18 3.59E+18 3.94E+18 3.94E+18 21 1.28 26.83 2.24E+18 3.76E+18 3.51E+18 3.22E+18 3.34E+18 3.81E+18 4.19E+18 4.19E+18 22 1.31 28.13 2.39E+18 4.02E+18 3.75E+18 3.44E+18 3.57E+18 4.08E+18 4.48E+18 4.48E+18 23 1.40 29.53 2.56E+18 4.30E+18 4.02E+18 3.69E+18 3.83E+18 4.37E+18 4.80E+18 4.80E+18 24 1.34 30.88 2.71E+18 4.55E+18 4.25E+18 3.90E+18 4.05E+18 4.61E+18 5.07E+18 5.07E+18 25[1] 1.43 32.30 2.86E+18 4.80E+18 4.48E+18 4.11E+18 4.27E+18 4.87E+18 5.36E+18 5.36E+18

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 53 of 56 Table 4-22 Fast Neutron (E > 0.1 MeV) Fluence at the Bioshield Concrete Cycle Cumulative Fast Neutron (E > 0.1 MeV) Fluence (n/cm2)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum Projections with no bias on the peripheral and re-entrant corner assembly relative powers Future[2] -- 36.00 3.26E+18 5.47E+18 5.11E+18 4.69E+18 4.86E+18 5.55E+18 6.11E+18 6.11E+18 Future[2] -- 42.00 3.91E+18 6.56E+18 6.12E+18 5.62E+18 5.83E+18 6.65E+18 7.33E+18 7.33E+18 Future[2] -- 48.00 4.57E+18 7.65E+18 7.14E+18 6.56E+18 6.80E+18 7.76E+18 8.55E+18 8.55E+18 Future[2] -- 54.00 5.22E+18 8.74E+18 8.15E+18 7.49E+18 7.77E+18 8.86E+18 9.77E+18 9.77E+18 Future[2] -- 60.00 5.88E+18 9.83E+18 9.17E+18 8.42E+18 8.73E+18 9.97E+18 1.10E+19 1.10E+19 Future[2] -- 66.00 6.53E+18 1.09E+19 1.02E+19 9.36E+18 9.70E+18 1.11E+19 1.22E+19 1.22E+19 Future[2] -- 72.00 7.18E+18 1.20E+19 1.12E+19 1.03E+19 1.07E+19 1.22E+19 1.34E+19 1.34E+19 Projections with a +10% bias on the peripheral and re-entrant corner assembly relative powers Future[2] -- 36.00 3.30E+18 5.53E+18 5.16E+18 4.74E+18 4.92E+18 5.61E+18 6.18E+18 6.18E+18 Future[2] -- 42.00 4.01E+18 6.72E+18 6.27E+18 5.76E+18 5.98E+18 6.82E+18 7.51E+18 7.51E+18 Future[2] -- 48.00 4.72E+18 7.91E+18 7.39E+18 6.79E+18 7.03E+18 8.02E+18 8.84E+18 8.84E+18 Future[2] -- 54.00 5.44E+18 9.10E+18 8.50E+18 7.81E+18 8.09E+18 9.23E+18 1.02E+19 1.02E+19 Future[2] -- 60.00 6.15E+18 1.03E+19 9.61E+18 8.83E+18 9.15E+18 1.04E+19 1.15E+19 1.15E+19 Future[2] -- 66.00 6.86E+18 1.15E+19 1.07E+19 9.85E+18 1.02E+19 1.16E+19 1.28E+19 1.28E+19 Future[2] -- 72.00 7.57E+18 1.27E+19 1.18E+19 1.09E+19 1.13E+19 1.28E+19 1.42E+19 1.42E+19 Note(s):

1. Cycle 25 was the current operating cycle at the time this summary report was authored.

2. Values beyond Cycle 25 are based on the average core power distributions and reactor operating conditions of Cycle 24 and are determined both with and without a 1.1 bias on the peripheral and re-entrant corner assembly relative powers.

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 54 of 56 Table 4-23 Gamma Dose at the Bioshield Concrete Cycle Cumulative Gamma Dose (Gy)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 1 1.11 1.11 3.68E+05 9.74E+05 8.88E+05 8.31E+05 8.92E+05 1.01E+06 1.11E+06 1.11E+06 2 1.12 2.23 7.50E+05 1.96E+06 1.79E+06 1.68E+06 1.80E+06 2.05E+06 2.25E+06 2.25E+06 3 1.22 3.45 1.11E+06 2.91E+06 2.64E+06 2.45E+06 2.65E+06 3.03E+06 3.34E+06 3.35E+06 4 1.16 4.61 1.40E+06 3.70E+06 3.43E+06 3.19E+06 3.44E+06 3.85E+06 4.15E+06 4.16E+06 5 1.30 5.91 1.72E+06 4.57E+06 4.30E+06 4.00E+06 4.32E+06 4.76E+06 5.04E+06 5.05E+06 6 1.35 7.26 2.03E+06 5.37E+06 5.07E+06 4.73E+06 5.09E+06 5.59E+06 5.94E+06 5.95E+06 7 1.21 8.47 2.31E+06 6.12E+06 5.77E+06 5.39E+06 5.79E+06 6.37E+06 6.78E+06 6.80E+06 8 1.38 9.85 2.57E+06 6.80E+06 6.50E+06 6.11E+06 6.53E+06 7.07E+06 7.46E+06 7.48E+06 9 1.22 11.07 2.85E+06 7.58E+06 7.25E+06 6.80E+06 7.29E+06 7.88E+06 8.28E+06 8.30E+06 10 1.44 12.51 3.21E+06 8.53E+06 8.17E+06 7.66E+06 8.21E+06 8.87E+06 9.29E+06 9.32E+06 11 1.32 13.83 3.52E+06 9.35E+06 9.01E+06 8.47E+06 9.05E+06 9.72E+06 1.02E+07 1.02E+07 12 1.51 15.34 3.84E+06 1.02E+07 9.84E+06 9.30E+06 9.89E+06 1.06E+07 1.11E+07 1.11E+07 13 1.29 16.63 4.15E+06 1.10E+07 1.06E+07 1.01E+07 1.07E+07 1.14E+07 1.19E+07 1.20E+07 14 1.43 18.06 4.45E+06 1.18E+07 1.14E+07 1.08E+07 1.15E+07 1.22E+07 1.28E+07 1.28E+07 15 1.15 19.21 4.71E+06 1.24E+07 1.21E+07 1.14E+07 1.21E+07 1.29E+07 1.36E+07 1.36E+07 16 1.25 20.46 5.01E+06 1.32E+07 1.28E+07 1.21E+07 1.28E+07 1.37E+07 1.44E+07 1.45E+07 17 1.25 21.71 5.29E+06 1.39E+07 1.35E+07 1.28E+07 1.35E+07 1.45E+07 1.53E+07 1.53E+07 18 1.42 23.13 5.61E+06 1.48E+07 1.43E+07 1.35E+07 1.43E+07 1.54E+07 1.62E+07 1.62E+07 19 1.19 24.32 5.96E+06 1.57E+07 1.51E+07 1.44E+07 1.52E+07 1.63E+07 1.72E+07 1.72E+07 20 1.23 25.55 6.36E+06 1.67E+07 1.62E+07 1.54E+07 1.62E+07 1.74E+07 1.83E+07 1.84E+07 21 1.28 26.83 6.77E+06 1.78E+07 1.72E+07 1.64E+07 1.73E+07 1.85E+07 1.95E+07 1.95E+07 22 1.31 28.13 7.24E+06 1.90E+07 1.84E+07 1.76E+07 1.85E+07 1.98E+07 2.09E+07 2.09E+07 23 1.40 29.53 7.75E+06 2.04E+07 1.97E+07 1.89E+07 1.98E+07 2.12E+07 2.23E+07 2.24E+07 24 1.34 30.88 8.20E+06 2.15E+07 2.08E+07 1.99E+07 2.09E+07 2.24E+07 2.36E+07 2.37E+07 25[1] 1.43 32.30 8.64E+06 2.27E+07 2.20E+07 2.10E+07 2.21E+07 2.36E+07 2.49E+07 2.50E+07

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 55 of 56 Table 4-23 Gamma Dose at the Bioshield Concrete Cycle Cumulative Gamma Dose (Gy)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum Projections with no bias on the peripheral and re-entrant corner assembly relative powers Future[2] -- 36.00 9.86E+06 2.58E+07 2.50E+07 2.40E+07 2.51E+07 2.69E+07 2.84E+07 2.85E+07 Future[2] -- 42.00 1.18E+07 3.10E+07 3.00E+07 2.88E+07 3.01E+07 3.22E+07 3.41E+07 3.42E+07 Future[2] -- 48.00 1.38E+07 3.61E+07 3.50E+07 3.35E+07 3.51E+07 3.76E+07 3.98E+07 3.99E+07 Future[2] -- 54.00 1.58E+07 4.12E+07 3.99E+07 3.83E+07 4.01E+07 4.29E+07 4.55E+07 4.56E+07 Future[2] -- 60.00 1.77E+07 4.63E+07 4.49E+07 4.31E+07 4.51E+07 4.82E+07 5.12E+07 5.13E+07 Future[2] -- 66.00 1.97E+07 5.14E+07 4.99E+07 4.79E+07 5.00E+07 5.36E+07 5.69E+07 5.70E+07 Future[2] -- 72.00 2.17E+07 5.66E+07 5.48E+07 5.27E+07 5.50E+07 5.89E+07 6.25E+07 6.27E+07 Projections with a +10% bias on the peripheral and re-entrant corner assembly relative powers Future[2] -- 36.00 9.97E+06 2.61E+07 2.53E+07 2.43E+07 2.54E+07 2.72E+07 2.88E+07 2.88E+07 Future[2] -- 42.00 1.21E+07 3.17E+07 3.08E+07 2.95E+07 3.09E+07 3.30E+07 3.50E+07 3.51E+07 Future[2] -- 48.00 1.43E+07 3.73E+07 3.62E+07 3.47E+07 3.63E+07 3.89E+07 4.12E+07 4.13E+07 Future[2] -- 54.00 1.64E+07 4.29E+07 4.16E+07 4.00E+07 4.18E+07 4.47E+07 4.74E+07 4.75E+07 Future[2] -- 60.00 1.86E+07 4.85E+07 4.71E+07 4.52E+07 4.73E+07 5.05E+07 5.36E+07 5.38E+07 Future[2] -- 66.00 2.07E+07 5.41E+07 5.25E+07 5.05E+07 5.27E+07 5.63E+07 5.98E+07 6.00E+07 Future[2] -- 72.00 2.29E+07 5.97E+07 5.79E+07 5.57E+07 5.82E+07 6.22E+07 6.60E+07 6.62E+07 Note(s):

1. Cycle 25 was the current operating cycle at the time this summary report was authored.

2. Values beyond Cycle 25 are based on the average core power distributions and reactor operating conditions of Cycle 24 and are determined both with and without a 1.1 bias on the peripheral and re-entrant corner assembly relative powers.

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 of LTR-REA-21-2-NP, Revision 1 June 7, 2021 Page 56 of 56 References

1. USNRC Regulatory Guide 1.190, Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence, Office of Nuclear Regulatory Research, March 2001.

2. Westinghouse Report WCAP-18124-NP-A, Revision 0, Fluence Determination with RAPTOR-M3G and FERRET, July 2018.

3. Westinghouse InfoGram IG-13-2, Fluence Attenuation Profile in Reactor Pressure Vessel Shell and Inlet/Outlet Nozzle Regions, July 2013.

- - This record was final approved on 6/8/2021 11:36:44 AM. (This statement was added by the PRIME system upon its validation)

St. Lucie Nuclear Plant Units 1 and 2 Dockets 50-335 and 50-389 L-2021-192 Enclosure 4 Enclosure 4 Non-proprietary Reference Documents and Redacted Versions of Proprietary Reference Documents (Public Version)

Attachment 3 Westinghouse Report LTR-SDA-21-021-NP, Revision 2, St. Lucie Units 1&2 Subsequent License Renewal:

Reactor Pressure Vessel Supports Assessment, September 15, 2021 (27 Total Pages, including cover sheets)

St. Lucie Nuclear Plant Units 1 and 2 Dockets 50-335 and 50-389 L-2021-192 Enclosure 4 Enclosure 4 Non-proprietary Reference Documents and Redacted Versions of Proprietary Reference Documents (Public Version)

Attachment 4 Westinghouse Report WCAP-18609-NP, Revision 2, St. Lucie Units 1 & 2 Subsequent License Renewal:

Time-Limited Aging Analyses on Reactor Vessel Integrity, July 16, 2021 (141 Total Pages, including cover sheets)

Westinghouse Non-Proprietary Class 3 2-6 2.4 ST. LUCIE UNIT 1 NEUTRON FLUENCE DATA TABLES AND FIGURES Table 2.4-1 St. Lucie Unit 1 Fast Neutron Fluence Rate (E > 1.0 MeV) at the RPV Clad/Base Metal Interface Cycle Cumulative Fast Neutron (E > 1.0 MeV) Fluence Rate (n/cm2-s)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 1 1.05 1.05 2.48E+10 1.51E+10 1.46E+10 1.08E+10 1.47E+10 1.48E+10 2.48E+10 2.48E+10 2 0.74 1.79 2.48E+10 1.51E+10 1.46E+10 1.08E+10 1.47E+10 1.48E+10 2.48E+10 2.48E+10 3 0.69 2.48 2.48E+10 1.51E+10 1.46E+10 1.08E+10 1.47E+10 1.48E+10 2.48E+10 2.48E+10 4 1.22 3.70 2.48E+10 1.51E+10 1.46E+10 1.08E+10 1.47E+10 1.48E+10 2.48E+10 2.48E+10 5 1.12 4.82 2.54E+10 1.32E+10 1.11E+10 7.89E+09 1.12E+10 1.29E+10 2.55E+10 2.55E+10 6 1.36 6.18 3.58E+10 2.04E+10 1.70E+10 1.25E+10 1.72E+10 1.98E+10 3.58E+10 3.58E+10 7 1.05 7.22 3.58E+10 2.04E+10 1.70E+10 1.25E+10 1.72E+10 1.98E+10 3.58E+10 3.58E+10 8 1.18 8.41 3.58E+10 2.04E+10 1.70E+10 1.25E+10 1.72E+10 1.98E+10 3.58E+10 3.58E+10 9 1.29 9.70 3.58E+10 2.04E+10 1.70E+10 1.25E+10 1.72E+10 1.98E+10 3.58E+10 3.58E+10 10 1.31 11.01 1.89E+10 1.48E+10 1.72E+10 1.32E+10 1.73E+10 1.44E+10 1.89E+10 1.89E+10 11 1.21 12.22 1.60E+10 1.29E+10 1.83E+10 1.36E+10 1.83E+10 1.26E+10 1.60E+10 1.89E+10 12 1.27 13.48 1.99E+10 1.51E+10 2.01E+10 1.43E+10 2.04E+10 1.49E+10 2.00E+10 2.10E+10 13 1.14 14.62 1.69E+10 1.31E+10 1.73E+10 1.33E+10 1.75E+10 1.29E+10 1.69E+10 1.81E+10 14 1.18 15.80 1.85E+10 1.44E+10 1.73E+10 1.35E+10 1.74E+10 1.41E+10 1.85E+10 1.85E+10 15 1.62 17.42 2.26E+10 1.51E+10 1.26E+10 1.01E+10 1.25E+10 1.46E+10 2.27E+10 2.27E+10 16 1.44 18.86 2.27E+10 1.49E+10 1.47E+10 1.28E+10 1.47E+10 1.45E+10 2.27E+10 2.27E+10 17 1.39 20.26 1.88E+10 1.33E+10 1.22E+10 1.13E+10 1.22E+10 1.29E+10 1.88E+10 1.88E+10 18 1.40 21.66 2.11E+10 1.34E+10 1.28E+10 1.09E+10 1.29E+10 1.30E+10 2.11E+10 2.11E+10 19 1.42 23.08 2.00E+10 1.33E+10 1.25E+10 1.12E+10 1.26E+10 1.29E+10 1.99E+10 2.00E+10 20 1.27 24.35 2.16E+10 1.46E+10 1.23E+10 1.11E+10 1.23E+10 1.41E+10 2.13E+10 2.16E+10 21 1.38 25.73 2.18E+10 1.43E+10 1.13E+10 1.02E+10 1.14E+10 1.37E+10 2.16E+10 2.18E+10 22 1.35 27.08 2.40E+10 1.53E+10 1.14E+10 1.03E+10 1.15E+10 1.47E+10 2.39E+10 2.40E+10 23 1.31 28.39 2.38E+10 1.56E+10 1.31E+10 1.15E+10 1.32E+10 1.51E+10 2.37E+10 2.38E+10 24 1.29 29.67 2.81E+10 1.72E+10 1.57E+10 1.39E+10 1.60E+10 1.66E+10 2.81E+10 2.81E+10 WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 2-7 Table 2.4-1 St. Lucie Unit 1 Fast Neutron Fluence Rate (E > 1.0 MeV) at the RPV Clad/Base Metal Interface (Continued)

Cycle Cumulative Fast Neutron (E > 1.0 MeV) Fluence Rate (n/cm2-s)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 25 1.33 31.00 3.16E+10 1.96E+10 1.58E+10 1.36E+10 1.59E+10 1.91E+10 3.18E+10 3.18E+10 26 1.33 32.33 3.13E+10 1.94E+10 1.68E+10 1.47E+10 1.69E+10 1.88E+10 3.13E+10 3.13E+10 27 1.30 33.64 2.96E+10 1.73E+10 1.29E+10 1.05E+10 1.32E+10 1.68E+10 2.97E+10 2.97E+10 28 1.30 34.94 2.59E+10 1.64E+10 1.42E+10 1.27E+10 1.41E+10 1.59E+10 2.59E+10 2.59E+10 29 1.37 36.31 2.89E+10 1.72E+10 1.34E+10 1.19E+10 1.35E+10 1.66E+10 2.90E+10 2.90E+10 30(a) 1.35 37.66 2.83E+10 1.71E+10 1.41E+10 1.27E+10 1.43E+10 1.66E+10 2.83E+10 2.83E+10 Notes:

(a) Cycle 30 was the current operating cycle at the time the exposures reported in this table were determined. Values listed are based on the projected EFPY for this cycle.

WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 2-8 Table 2.4-2 St. Lucie Unit 1 Fast Neutron Fluence (E > 1.0 MeV) at the RPV Clad/Base Metal Interface Cycle Cumulative Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 1 1.05 1.05 8.23E+17 5.01E+17 4.83E+17 3.57E+17 4.87E+17 4.92E+17 8.24E+17 8.24E+17 2 0.74 1.79 1.40E+18 8.53E+17 8.21E+17 6.07E+17 8.29E+17 8.36E+17 1.40E+18 1.40E+18 3 0.69 2.48 1.94E+18 1.18E+18 1.14E+18 8.42E+17 1.15E+18 1.16E+18 1.94E+18 1.94E+18 4 1.22 3.70 2.90E+18 1.77E+18 1.70E+18 1.26E+18 1.72E+18 1.73E+18 2.90E+18 2.90E+18 5 1.12 4.82 3.77E+18 2.22E+18 2.08E+18 1.53E+18 2.10E+18 2.18E+18 3.78E+18 3.78E+18 6 1.36 6.18 5.29E+18 3.08E+18 2.80E+18 2.06E+18 2.83E+18 3.01E+18 5.29E+18 5.29E+18 7 1.05 7.22 6.46E+18 3.75E+18 3.36E+18 2.47E+18 3.39E+18 3.66E+18 6.46E+18 6.46E+18 8 1.18 8.41 7.78E+18 4.50E+18 3.98E+18 2.93E+18 4.02E+18 4.39E+18 7.78E+18 7.78E+18 9 1.29 9.70 9.23E+18 5.32E+18 4.67E+18 3.44E+18 4.72E+18 5.19E+18 9.24E+18 9.24E+18 10 1.31 11.01 1.00E+19 5.93E+18 5.38E+18 3.98E+18 5.43E+18 5.78E+18 1.00E+19 1.00E+19 11 1.21 12.22 1.06E+19 6.42E+18 6.08E+18 4.50E+18 6.13E+18 6.26E+18 1.06E+19 1.06E+19 12 1.27 13.48 1.14E+19 7.01E+18 6.86E+18 5.06E+18 6.93E+18 6.84E+18 1.14E+19 1.14E+19 13 1.14 14.62 1.20E+19 7.49E+18 7.49E+18 5.54E+18 7.56E+18 7.31E+18 1.20E+19 1.20E+19 14 1.18 15.80 1.27E+19 8.02E+18 8.13E+18 6.04E+18 8.20E+18 7.83E+18 1.27E+19 1.27E+19 15 1.62 17.42 1.38E+19 8.80E+18 8.77E+18 6.56E+18 8.84E+18 8.58E+18 1.39E+19 1.39E+19 16 1.44 18.86 1.49E+19 9.47E+18 9.44E+18 7.14E+18 9.51E+18 9.24E+18 1.49E+19 1.49E+19 17 1.39 20.26 1.57E+19 1.01E+19 9.97E+18 7.64E+18 1.01E+19 9.81E+18 1.57E+19 1.57E+19 18 1.40 21.66 1.66E+19 1.07E+19 1.05E+19 8.12E+18 1.06E+19 1.04E+19 1.66E+19 1.66E+19 19 1.42 23.08 1.75E+19 1.12E+19 1.11E+19 8.62E+18 1.12E+19 1.10E+19 1.75E+19 1.75E+19 20 1.27 24.35 1.84E+19 1.18E+19 1.16E+19 9.06E+18 1.17E+19 1.15E+19 1.84E+19 1.84E+19 21 1.38 25.73 1.93E+19 1.25E+19 1.21E+19 9.51E+18 1.22E+19 1.21E+19 1.93E+19 1.93E+19 22 1.35 27.08 2.04E+19 1.31E+19 1.26E+19 9.95E+18 1.27E+19 1.27E+19 2.04E+19 2.04E+19 23 1.31 28.39 2.13E+19 1.37E+19 1.31E+19 1.04E+19 1.32E+19 1.34E+19 2.13E+19 2.13E+19 24 1.29 29.67 2.25E+19 1.44E+19 1.38E+19 1.10E+19 1.39E+19 1.40E+19 2.25E+19 2.25E+19 25 1.33 31.00 2.38E+19 1.53E+19 1.44E+19 1.16E+19 1.45E+19 1.48E+19 2.38E+19 2.38E+19 26 1.33 32.33 2.51E+19 1.61E+19 1.51E+19 1.22E+19 1.52E+19 1.56E+19 2.51E+19 2.51E+19 WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 2-9 Table 2.4-2 St. Lucie Unit 1 Fast Neutron Fluence (E > 1.0 MeV) at the RPV Clad/Base Metal Interface (Continued)

Cycle Cumulative Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 27 1.30 33.64 2.63E+19 1.68E+19 1.57E+19 1.26E+19 1.58E+19 1.63E+19 2.63E+19 2.63E+19 28 1.30 34.94 2.74E+19 1.75E+19 1.62E+19 1.31E+19 1.64E+19 1.70E+19 2.74E+19 2.74E+19 29 1.37 36.31 2.87E+19 1.82E+19 1.68E+19 1.36E+19 1.69E+19 1.77E+19 2.87E+19 2.87E+19 (a) 30 1.35 37.66 2.99E+19 1.89E+19 1.74E+19 1.42E+19 1.75E+19 1.84E+19 2.99E+19 2.99E+19 Projections with no bias on the peripheral and re-entrant corner assembly relative powers Future(b) -- 42.00 3.38E+19 2.13E+19 1.93E+19 1.58E+19 1.94E+19 2.07E+19 3.38E+19 3.38E+19 (b)

Future -- 48.00 3.93E+19 2.45E+19 2.18E+19 1.81E+19 2.20E+19 2.38E+19 3.93E+19 3.93E+19 (b)\

Future -- 54.00 4.48E+19 2.78E+19 2.44E+19 2.03E+19 2.45E+19 2.69E+19 4.48E+19 4.48E+19 (b)

Future -- 60.00 5.03E+19 3.10E+19 2.69E+19 2.25E+19 2.71E+19 3.01E+19 5.03E+19 5.03E+19 (b)

Future -- 66.00 5.58E+19 3.43E+19 2.94E+19 2.48E+19 2.96E+19 3.32E+19 5.58E+19 5.58E+19 (b)

Future -- 72.00 6.12E+19 3.75E+19 3.20E+19 2.70E+19 3.22E+19 3.64E+19 6.12E+19 6.12E+19 Projections with a +10% bias on the peripheral and re-entrant corner assembly relative powers (b)

Future -- 42.00 3.41E+19 2.15E+19 1.94E+19 1.60E+19 1.96E+19 2.09E+19 3.41E+19 3.41E+19 (b)

Future -- 48.00 4.01E+19 2.50E+19 2.22E+19 1.84E+19 2.23E+19 2.43E+19 4.01E+19 4.01E+19 (b)

Future -- 54.00 4.60E+19 2.85E+19 2.50E+19 2.08E+19 2.51E+19 2.76E+19 4.60E+19 4.60E+19 Future(b) -- 60.00 5.19E+19 3.20E+19 2.77E+19 2.33E+19 2.79E+19 3.10E+19 5.19E+19 5.19E+19 (b)

Future -- 66.00 5.78E+19 3.55E+19 3.05E+19 2.57E+19 3.07E+19 3.44E+19 5.79E+19 5.79E+19 (b)

Future -- 72.00 6.38E+19 3.91E+19 3.33E+19 2.82E+19 3.34E+19 3.78E+19 6.38E+19 6.38E+19 Notes:

(a) Cycle 30 was the current operating cycle at the time the exposures reported in this table were determined. Values listed are based on the projected EFPY for this cycle.

(b) Values beyond Cycle 30 are based on the average core power distributions and reactor operating conditions of Cycle 29 and are determined both with and without a 1.1 bias on the peripheral and re-entrant corner assembly relative powers.

WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 2-10 Table 2.4-3 St. Lucie Unit 1 Iron Atom Displacement Rate at the RPV Clad/Base Metal Interface Cycle Cumulative Iron Atom Displacement Rate (dpa/s)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 1 1.05 1.05 3.93E-11 2.41E-11 2.30E-11 1.71E-11 2.32E-11 2.39E-11 3.92E-11 3.93E-11 2 0.74 1.79 3.93E-11 2.41E-11 2.30E-11 1.71E-11 2.32E-11 2.39E-11 3.92E-11 3.93E-11 3 0.69 2.48 3.93E-11 2.41E-11 2.30E-11 1.71E-11 2.32E-11 2.39E-11 3.92E-11 3.93E-11 4 1.22 3.70 3.93E-11 2.41E-11 2.30E-11 1.71E-11 2.32E-11 2.39E-11 3.92E-11 3.93E-11 5 1.12 4.82 4.02E-11 2.11E-11 1.75E-11 1.25E-11 1.77E-11 2.09E-11 4.01E-11 4.02E-11 6 1.36 6.18 5.46E-11 3.14E-11 2.60E-11 1.94E-11 2.63E-11 3.06E-11 5.45E-11 5.46E-11 7 1.05 7.22 5.46E-11 3.14E-11 2.60E-11 1.94E-11 2.63E-11 3.06E-11 5.45E-11 5.46E-11 8 1.18 8.41 5.46E-11 3.14E-11 2.60E-11 1.94E-11 2.63E-11 3.06E-11 5.45E-11 5.46E-11 9 1.29 9.70 5.46E-11 3.14E-11 2.60E-11 1.94E-11 2.63E-11 3.06E-11 5.45E-11 5.46E-11 10 1.31 11.01 2.89E-11 2.28E-11 2.63E-11 2.03E-11 2.64E-11 2.22E-11 2.88E-11 2.89E-11 11 1.21 12.22 2.45E-11 1.99E-11 2.79E-11 2.09E-11 2.80E-11 1.96E-11 2.44E-11 2.89E-11 12 1.27 13.48 3.04E-11 2.33E-11 3.07E-11 2.21E-11 3.10E-11 2.30E-11 3.04E-11 3.21E-11 13 1.14 14.62 2.58E-11 2.03E-11 2.65E-11 2.04E-11 2.67E-11 2.00E-11 2.58E-11 2.76E-11 14 1.18 15.80 2.83E-11 2.22E-11 2.64E-11 2.08E-11 2.66E-11 2.19E-11 2.83E-11 2.83E-11 15 1.62 17.42 3.47E-11 2.33E-11 1.93E-11 1.56E-11 1.91E-11 2.26E-11 3.46E-11 3.47E-11 16 1.44 18.86 3.47E-11 2.30E-11 2.24E-11 1.97E-11 2.26E-11 2.24E-11 3.46E-11 3.47E-11 17 1.39 20.26 2.88E-11 2.04E-11 1.86E-11 1.74E-11 1.87E-11 1.99E-11 2.87E-11 2.88E-11 18 1.40 21.66 3.22E-11 2.07E-11 1.96E-11 1.68E-11 1.97E-11 2.01E-11 3.22E-11 3.22E-11 19 1.42 23.08 3.06E-11 2.06E-11 1.91E-11 1.72E-11 1.94E-11 2.00E-11 3.04E-11 3.06E-11 20 1.27 24.35 3.30E-11 2.25E-11 1.89E-11 1.71E-11 1.88E-11 2.17E-11 3.25E-11 3.30E-11 21 1.38 25.73 3.33E-11 2.19E-11 1.74E-11 1.57E-11 1.75E-11 2.13E-11 3.29E-11 3.33E-11 22 1.35 27.08 3.67E-11 2.35E-11 1.75E-11 1.59E-11 1.76E-11 2.28E-11 3.65E-11 3.67E-11 23 1.31 28.39 3.64E-11 2.40E-11 2.01E-11 1.77E-11 2.03E-11 2.33E-11 3.62E-11 3.64E-11 24 1.29 29.67 4.30E-11 2.64E-11 2.40E-11 2.14E-11 2.45E-11 2.58E-11 4.28E-11 4.30E-11 25 1.33 31.00 4.84E-11 3.02E-11 2.42E-11 2.09E-11 2.43E-11 2.95E-11 4.84E-11 4.84E-11 26 1.33 32.33 4.78E-11 2.98E-11 2.57E-11 2.27E-11 2.59E-11 2.90E-11 4.77E-11 4.78E-11 WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 2-11 Table 2.4-3 St. Lucie Unit 1 Iron Atom Displacement Rate at the RPV Clad/Base Metal Interface (Continued)

Cycle Cumulative Iron Atom Displacement Rate (dpa/s)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 27 1.30 33.64 4.52E-11 2.66E-11 1.98E-11 1.62E-11 2.02E-11 2.60E-11 4.52E-11 4.52E-11 28 1.30 34.94 3.97E-11 2.53E-11 2.18E-11 1.95E-11 2.16E-11 2.46E-11 3.96E-11 3.97E-11 29 1.37 36.31 4.42E-11 2.64E-11 2.06E-11 1.83E-11 2.07E-11 2.57E-11 4.41E-11 4.42E-11 (a) 30 1.35 37.66 4.32E-11 2.63E-11 2.16E-11 1.96E-11 2.19E-11 2.57E-11 4.31E-11 4.32E-11 Note:

(a) Cycle 30 was the current operating cycle at the time the exposures reported in this table were determined. Values listed are based on the projected EFPY for this cycle.

WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 2-12 Table 2.4-4 St. Lucie Unit 1 Iron Atom Displacements at the RPV Clad/Base Metal Interface Cycle Cumulative Iron Atom Displacements (dpa)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 1 1.05 1.05 1.30E-03 7.99E-04 7.63E-04 5.66E-04 7.69E-04 7.93E-04 1.30E-03 1.30E-03 2 0.74 1.79 2.21E-03 1.36E-03 1.30E-03 9.63E-04 1.31E-03 1.35E-03 2.21E-03 2.21E-03 3 0.69 2.48 3.07E-03 1.88E-03 1.80E-03 1.34E-03 1.81E-03 1.87E-03 3.06E-03 3.07E-03 4 1.22 3.70 4.59E-03 2.81E-03 2.68E-03 1.99E-03 2.71E-03 2.79E-03 4.58E-03 4.59E-03 5 1.12 4.82 5.98E-03 3.54E-03 3.29E-03 2.43E-03 3.32E-03 3.51E-03 5.97E-03 5.98E-03 6 1.36 6.18 8.29E-03 4.87E-03 4.39E-03 3.24E-03 4.43E-03 4.81E-03 8.27E-03 8.29E-03 7 1.05 7.22 1.01E-02 5.90E-03 5.24E-03 3.88E-03 5.29E-03 5.81E-03 1.00E-02 1.01E-02 8 1.18 8.41 1.21E-02 7.06E-03 6.20E-03 4.59E-03 6.26E-03 6.94E-03 1.21E-02 1.21E-02 9 1.29 9.70 1.43E-02 8.32E-03 7.25E-03 5.37E-03 7.32E-03 8.18E-03 1.43E-02 1.43E-02 10 1.31 11.01 1.55E-02 9.26E-03 8.34E-03 6.21E-03 8.41E-03 9.09E-03 1.54E-02 1.55E-02 11 1.21 12.22 1.64E-02 1.00E-02 9.40E-03 7.01E-03 9.48E-03 9.84E-03 1.64E-02 1.64E-02 12 1.27 13.48 1.76E-02 1.09E-02 1.06E-02 7.87E-03 1.07E-02 1.07E-02 1.76E-02 1.76E-02 13 1.14 14.62 1.85E-02 1.17E-02 1.16E-02 8.61E-03 1.17E-02 1.15E-02 1.85E-02 1.85E-02 14 1.18 15.80 1.96E-02 1.25E-02 1.25E-02 9.38E-03 1.26E-02 1.23E-02 1.95E-02 1.96E-02 15 1.62 17.42 2.14E-02 1.37E-02 1.35E-02 1.02E-02 1.36E-02 1.34E-02 2.13E-02 2.14E-02 16 1.44 18.86 2.29E-02 1.47E-02 1.45E-02 1.11E-02 1.46E-02 1.45E-02 2.29E-02 2.29E-02 17 1.39 20.26 2.42E-02 1.56E-02 1.54E-02 1.18E-02 1.55E-02 1.53E-02 2.41E-02 2.42E-02 18 1.40 21.66 2.56E-02 1.65E-02 1.62E-02 1.26E-02 1.63E-02 1.62E-02 2.56E-02 2.56E-02 19 1.42 23.08 2.70E-02 1.75E-02 1.71E-02 1.34E-02 1.72E-02 1.71E-02 2.69E-02 2.70E-02 20 1.27 24.35 2.83E-02 1.84E-02 1.78E-02 1.40E-02 1.80E-02 1.80E-02 2.82E-02 2.83E-02 21 1.38 25.73 2.98E-02 1.93E-02 1.86E-02 1.47E-02 1.87E-02 1.89E-02 2.97E-02 2.98E-02 22 1.35 27.08 3.13E-02 2.03E-02 1.93E-02 1.54E-02 1.95E-02 1.99E-02 3.12E-02 3.13E-02 23 1.31 28.39 3.28E-02 2.13E-02 2.02E-02 1.61E-02 2.03E-02 2.08E-02 3.27E-02 3.28E-02 24 1.29 29.67 3.46E-02 2.24E-02 2.11E-02 1.70E-02 2.13E-02 2.19E-02 3.45E-02 3.46E-02 25 1.33 31.00 3.66E-02 2.37E-02 2.22E-02 1.79E-02 2.23E-02 2.31E-02 3.65E-02 3.66E-02 26 1.33 32.33 3.86E-02 2.49E-02 2.32E-02 1.88E-02 2.34E-02 2.43E-02 3.85E-02 3.86E-02 WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 2-13 Table 2.4-4 St. Lucie Unit 1 Iron Atom Displacements at the RPV Clad/Base Metal Interface (Continued)

Cycle Cumulative Iron Atom Displacements (dpa)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 27 1.30 33.64 4.05E-02 2.60E-02 2.41E-02 1.95E-02 2.42E-02 2.54E-02 4.03E-02 4.05E-02 28 1.30 34.94 4.21E-02 2.70E-02 2.49E-02 2.03E-02 2.51E-02 2.64E-02 4.20E-02 4.21E-02 29 1.37 36.31 4.40E-02 2.82E-02 2.58E-02 2.11E-02 2.60E-02 2.75E-02 4.39E-02 4.40E-02 (a) 30 1.35 37.66 4.59E-02 2.93E-02 2.68E-02 2.19E-02 2.70E-02 2.86E-02 4.57E-02 4.59E-02 Projections with no bias on the peripheral and re-entrant corner assembly relative powers Future(b) -- 42.00 5.19E-02 3.29E-02 2.96E-02 2.44E-02 2.98E-02 3.21E-02 5.18E-02 5.19E-02 (b)

Future -- 48.00 6.03E-02 3.79E-02 3.35E-02 2.79E-02 3.37E-02 3.70E-02 6.01E-02 6.03E-02 (b)

Future -- 54.00 6.87E-02 4.29E-02 3.74E-02 3.14E-02 3.76E-02 4.19E-02 6.85E-02 6.87E-02 (b)

Future -- 60.00 7.71E-02 4.79E-02 4.13E-02 3.48E-02 4.15E-02 4.67E-02 7.68E-02 7.71E-02 (b)

Future -- 66.00 8.54E-02 5.30E-02 4.52E-02 3.83E-02 4.55E-02 5.16E-02 8.52E-02 8.54E-02 (b)

Future -- 72.00 9.38E-02 5.80E-02 4.91E-02 4.17E-02 4.94E-02 5.64E-02 9.35E-02 9.38E-02 Projections with a +10% bias on the peripheral and re-entrant corner assembly relative powers (b)

Future -- 42.00 5.24E-02 3.32E-02 2.98E-02 2.47E-02 3.00E-02 3.24E-02 5.23E-02 5.24E-02 (b)

Future -- 48.00 6.15E-02 3.86E-02 3.41E-02 2.84E-02 3.43E-02 3.77E-02 6.13E-02 6.15E-02 (b)

Future -- 54.00 7.05E-02 4.40E-02 3.83E-02 3.22E-02 3.85E-02 4.29E-02 7.03E-02 7.05E-02 Future(b) -- 60.00 7.96E-02 4.95E-02 4.26E-02 3.60E-02 4.28E-02 4.82E-02 7.93E-02 7.96E-02 Future(b) -- 66.00 8.86E-02 5.49E-02 4.68E-02 3.97E-02 4.71E-02 5.34E-02 8.84E-02 8.86E-02 (b)

Future -- 72.00 9.77E-02 6.03E-02 5.11E-02 4.35E-02 5.13E-02 5.87E-02 9.74E-02 9.77E-02 Notes:

(a) Cycle 30 was the current operating cycle at the time the exposures reported in this table were determined. Values listed are based on the projected EFPY for this cycle.

(b) Values beyond Cycle 30 are based on the average core power distributions and reactor operating conditions of Cycle 29 and are determined both with and without a 1.1 bias on the peripheral and re-entrant corner assembly relative powers.

WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 2-32 2.5 ST. LUCIE UNIT 2 NEUTRON FLUENCE DATA TABLES AND FIGURES Table 2.5-1 St. Lucie Unit 2 Fast Neutron (E > 1.0 MeV) Fluence Rate at the RPV Clad/Base Metal Interface Cycle Cumulative Fluence Rate (n/cm2-s)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 1 1.11 1.11 3.19E+10 2.03E+10 1.71E+10 1.26E+10 1.71E+10 1.97E+10 3.19E+10 3.19E+10 2 1.12 2.23 3.36E+10 1.98E+10 1.71E+10 1.28E+10 1.71E+10 1.93E+10 3.37E+10 3.37E+10 3 1.22 3.45 3.01E+10 1.80E+10 1.47E+10 1.07E+10 1.47E+10 1.75E+10 3.02E+10 3.02E+10 4 1.16 4.61 2.05E+10 1.61E+10 1.56E+10 1.18E+10 1.56E+10 1.58E+10 2.05E+10 2.05E+10 5 1.30 5.91 1.99E+10 1.61E+10 1.55E+10 1.13E+10 1.55E+10 1.57E+10 1.99E+10 2.00E+10 6 1.35 7.26 2.14E+10 1.37E+10 1.22E+10 9.79E+09 1.22E+10 1.34E+10 2.14E+10 2.14E+10 7 1.21 8.47 2.31E+10 1.44E+10 1.21E+10 1.02E+10 1.21E+10 1.40E+10 2.32E+10 2.32E+10 8 1.38 9.85 1.40E+10 1.10E+10 1.30E+10 1.01E+10 1.30E+10 1.08E+10 1.41E+10 1.41E+10 9 1.22 11.07 1.92E+10 1.58E+10 1.39E+10 1.00E+10 1.39E+10 1.55E+10 1.92E+10 1.98E+10 10 1.44 12.51 2.05E+10 1.59E+10 1.37E+10 1.06E+10 1.37E+10 1.55E+10 2.05E+10 2.09E+10 11 1.32 13.83 1.92E+10 1.42E+10 1.43E+10 1.16E+10 1.43E+10 1.39E+10 1.92E+10 1.92E+10 12 1.51 15.34 1.94E+10 1.25E+10 1.23E+10 1.07E+10 1.23E+10 1.22E+10 1.94E+10 1.94E+10 13 1.29 16.63 2.14E+10 1.41E+10 1.30E+10 1.14E+10 1.30E+10 1.38E+10 2.14E+10 2.14E+10 14 1.43 18.06 1.87E+10 1.27E+10 1.23E+10 1.06E+10 1.23E+10 1.24E+10 1.87E+10 1.87E+10 15 1.15 19.21 2.18E+10 1.41E+10 1.20E+10 9.78E+09 1.20E+10 1.37E+10 2.19E+10 2.19E+10 16 1.25 20.46 2.22E+10 1.46E+10 1.23E+10 9.93E+09 1.23E+10 1.42E+10 2.22E+10 2.22E+10 17 1.25 21.71 2.08E+10 1.40E+10 1.18E+10 9.70E+09 1.18E+10 1.38E+10 2.16E+10 2.16E+10 18 1.42 23.13 2.00E+10 1.42E+10 1.21E+10 1.00E+10 1.19E+10 1.39E+10 2.01E+10 2.02E+10 19 1.19 24.32 2.54E+10 1.75E+10 1.65E+10 1.29E+10 1.65E+10 1.68E+10 2.52E+10 2.54E+10 20 1.23 25.55 2.99E+10 1.95E+10 1.86E+10 1.54E+10 1.86E+10 1.90E+10 2.99E+10 2.99E+10 21 1.28 26.83 2.85E+10 1.89E+10 1.84E+10 1.50E+10 1.83E+10 1.84E+10 2.85E+10 2.85E+10 22 1.31 28.13 3.30E+10 2.13E+10 1.92E+10 1.68E+10 1.92E+10 2.07E+10 3.31E+10 3.31E+10 23 1.40 29.53 3.30E+10 2.14E+10 2.12E+10 1.70E+10 2.12E+10 2.09E+10 3.30E+10 3.30E+10 24 1.34 30.88 3.01E+10 1.95E+10 1.84E+10 1.46E+10 1.84E+10 1.90E+10 3.02E+10 3.02E+10 25(a) 1.43 32.30 2.88E+10 1.87E+10 1.79E+10 1.38E+10 1.80E+10 1.85E+10 2.92E+10 2.92E+10 Note:

(a) Cycle 25 was the current operating cycle at the time the exposures reported in this table were determined. Values listed are based on the projected EFPY for this cycle.

WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 2-33 Table 2.5-2 St. Lucie Unit 2 Fast Neutron (E > 1.0 MeV) Fluence at the RPV Clad/Base Metal Interface Cycle Cumulative Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 1 1.11 1.11 1.12E+18 7.10E+17 5.99E+17 4.41E+17 5.99E+17 6.91E+17 1.12E+18 1.12E+18 2 1.12 2.23 2.30E+18 1.41E+18 1.20E+18 8.92E+17 1.20E+18 1.37E+18 2.30E+18 2.30E+18 3 1.22 3.45 3.46E+18 2.10E+18 1.77E+18 1.30E+18 1.77E+18 2.04E+18 3.46E+18 3.46E+18 4 1.16 4.61 4.20E+18 2.68E+18 2.33E+18 1.73E+18 2.33E+18 2.61E+18 4.20E+18 4.20E+18 5 1.30 5.91 5.00E+18 3.33E+18 2.96E+18 2.19E+18 2.96E+18 3.25E+18 5.00E+18 5.00E+18 6 1.35 7.26 5.90E+18 3.90E+18 3.47E+18 2.60E+18 3.47E+18 3.81E+18 5.91E+18 5.91E+18 7 1.21 8.47 6.78E+18 4.45E+18 3.93E+18 2.99E+18 3.93E+18 4.34E+18 6.79E+18 6.79E+18 8 1.38 9.85 7.37E+18 4.92E+18 4.48E+18 3.42E+18 4.48E+18 4.80E+18 7.38E+18 7.38E+18 9 1.22 11.07 8.11E+18 5.53E+18 5.02E+18 3.80E+18 5.02E+18 5.40E+18 8.13E+18 8.13E+18 10 1.44 12.51 9.05E+18 6.25E+18 5.64E+18 4.29E+18 5.64E+18 6.10E+18 9.06E+18 9.06E+18 11 1.32 13.83 9.84E+18 6.83E+18 6.23E+18 4.76E+18 6.23E+18 6.67E+18 9.85E+18 9.85E+18 12 1.51 15.34 1.08E+19 7.43E+18 6.81E+18 5.27E+18 6.81E+18 7.25E+18 1.08E+19 1.08E+19 13 1.29 16.63 1.16E+19 8.00E+18 7.34E+18 5.73E+18 7.34E+18 7.81E+18 1.16E+19 1.16E+19 14 1.43 18.06 1.25E+19 8.57E+18 7.89E+18 6.21E+18 7.89E+18 8.36E+18 1.25E+19 1.25E+19 15 1.15 19.21 1.32E+19 9.08E+18 8.33E+18 6.56E+18 8.32E+18 8.86E+18 1.33E+19 1.33E+19 16 1.25 20.46 1.41E+19 9.65E+18 8.81E+18 6.95E+18 8.81E+18 9.41E+18 1.41E+19 1.41E+19 17 1.25 21.71 1.49E+19 1.02E+19 9.27E+18 7.33E+18 9.27E+18 9.96E+18 1.50E+19 1.50E+19 18 1.42 23.13 1.58E+19 1.08E+19 9.81E+18 7.78E+18 9.80E+18 1.06E+19 1.59E+19 1.59E+19 19 1.19 24.32 1.68E+19 1.15E+19 1.04E+19 8.26E+18 1.04E+19 1.12E+19 1.68E+19 1.68E+19 20 1.23 25.55 1.79E+19 1.22E+19 1.12E+19 8.86E+18 1.11E+19 1.19E+19 1.80E+19 1.80E+19 21 1.28 26.83 1.91E+19 1.30E+19 1.19E+19 9.46E+18 1.19E+19 1.27E+19 1.91E+19 1.91E+19 22 1.31 28.13 2.04E+19 1.39E+19 1.27E+19 1.02E+19 1.27E+19 1.35E+19 2.05E+19 2.05E+19 23 1.40 29.53 2.19E+19 1.48E+19 1.36E+19 1.09E+19 1.36E+19 1.45E+19 2.19E+19 2.19E+19 24 1.34 30.88 2.32E+19 1.57E+19 1.44E+19 1.15E+19 1.44E+19 1.53E+19 2.32E+19 2.32E+19 25(a) 1.43 32.30 2.45E+19 1.65E+19 1.52E+19 1.21E+19 1.52E+19 1.61E+19 2.45E+19 2.45E+19 WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 2-34 Table 2.5-2 St. Lucie Unit 2 Fast Neutron (E > 1.0 MeV) Fluence at the RPV Clad/Base Metal Interface (Continued)

Projections with no bias on the peripheral and re-entrant corner assembly relative powers (b)

Future -- 36.00 2.80E+19 1.88E+19 1.74E+19 1.38E+19 1.73E+19 1.83E+19 2.81E+19 2.81E+19 Future(b) -- 42.00 3.37E+19 2.25E+19 2.08E+19 1.66E+19 2.08E+19 2.19E+19 3.38E+19 3.38E+19 Future(b) -- 48.00 3.94E+19 2.62E+19 2.43E+19 1.94E+19 2.43E+19 2.55E+19 3.95E+19 3.95E+19 Future(b) -- 54.00 4.51E+19 2.99E+19 2.78E+19 2.21E+19 2.78E+19 2.91E+19 4.52E+19 4.52E+19 Future(b) -- 60.00 5.08E+19 3.36E+19 3.13E+19 2.49E+19 3.12E+19 3.27E+19 5.09E+19 5.09E+19 Future(b) -- 66.00 5.65E+19 3.73E+19 3.48E+19 2.76E+19 3.47E+19 3.63E+19 5.66E+19 5.66E+19 Future(b) -- 72.00 6.22E+19 4.10E+19 3.82E+19 3.04E+19 3.82E+19 3.99E+19 6.23E+19 6.23E+19 Projections with a +10% bias on the peripheral and re-entrant corner assembly relative powers Future(b) -- 36.00 2.83E+19 1.90E+19 1.76E+19 1.40E+19 1.75E+19 1.85E+19 2.84E+19 2.84E+19 Future(b) -- 42.00 3.45E+19 2.30E+19 2.14E+19 1.70E+19 2.13E+19 2.24E+19 3.46E+19 3.46E+19 Future(b) -- 48.00 4.07E+19 2.70E+19 2.52E+19 2.01E+19 2.51E+19 2.64E+19 4.08E+19 4.08E+19 Future(b) -- 54.00 4.69E+19 3.11E+19 2.90E+19 2.31E+19 2.90E+19 3.03E+19 4.70E+19 4.70E+19 Future(b) -- 60.00 5.31E+19 3.51E+19 3.28E+19 2.61E+19 3.28E+19 3.42E+19 5.32E+19 5.32E+19 Future(b) -- 66.00 5.93E+19 3.91E+19 3.66E+19 2.91E+19 3.66E+19 3.81E+19 5.94E+19 5.94E+19 Future(b) -- 72.00 6.55E+19 4.31E+19 4.04E+19 3.22E+19 4.04E+19 4.21E+19 6.56E+19 6.56E+19 Notes:

(a) Cycle 25 was the current operating cycle at the time the exposures reported in this table were determined. Values listed are based on the projected EFPY for this cycle.

(b) Values beyond Cycle 25 are based on the average core power distributions and reactor operating conditions of Cycle 24 and are determined both with and without a 1.1 bias on the peripheral and re-entrant corner assembly relative powers.

WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 2-35 Table 2.5-3 St. Lucie Unit 2 Calculated Maximum Iron Atom Displacement Rate at the RPV Clad/Base Metal Interface Cycle Cumulative Iron Atom Displacement Rate (dpa/s)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 1 1.11 1.11 4.86E-11 3.11E-11 2.61E-11 1.94E-11 2.61E-11 3.04E-11 4.86E-11 4.86E-11 2 1.12 2.23 5.13E-11 3.04E-11 2.61E-11 1.97E-11 2.61E-11 2.98E-11 5.12E-11 5.13E-11 3 1.22 3.45 4.59E-11 2.76E-11 2.25E-11 1.65E-11 2.25E-11 2.71E-11 4.58E-11 4.59E-11 4 1.16 4.61 3.13E-11 2.47E-11 2.38E-11 1.81E-11 2.38E-11 2.43E-11 3.13E-11 3.14E-11 5 1.30 5.91 3.05E-11 2.47E-11 2.37E-11 1.75E-11 2.37E-11 2.43E-11 3.04E-11 3.06E-11 6 1.35 7.26 3.27E-11 2.11E-11 1.86E-11 1.51E-11 1.86E-11 2.07E-11 3.26E-11 3.27E-11 7 1.21 8.47 3.53E-11 2.21E-11 1.86E-11 1.57E-11 1.86E-11 2.17E-11 3.53E-11 3.53E-11 8 1.38 9.85 2.15E-11 1.69E-11 1.99E-11 1.56E-11 1.99E-11 1.66E-11 2.14E-11 2.15E-11 9 1.22 11.07 2.94E-11 2.43E-11 2.12E-11 1.54E-11 2.12E-11 2.38E-11 2.93E-11 3.02E-11 10 1.44 12.51 3.14E-11 2.44E-11 2.09E-11 1.63E-11 2.09E-11 2.39E-11 3.13E-11 3.19E-11 11 1.32 13.83 2.94E-11 2.19E-11 2.18E-11 1.78E-11 2.18E-11 2.15E-11 2.93E-11 2.94E-11 12 1.51 15.34 2.97E-11 1.93E-11 1.89E-11 1.65E-11 1.89E-11 1.89E-11 2.96E-11 2.97E-11 13 1.29 16.63 3.27E-11 2.17E-11 2.00E-11 1.75E-11 2.00E-11 2.13E-11 3.26E-11 3.27E-11 14 1.43 18.06 2.86E-11 1.95E-11 1.88E-11 1.63E-11 1.88E-11 1.91E-11 2.85E-11 2.86E-11 15 1.15 19.21 3.34E-11 2.17E-11 1.84E-11 1.51E-11 1.84E-11 2.12E-11 3.33E-11 3.34E-11 16 1.25 20.46 3.40E-11 2.25E-11 1.88E-11 1.53E-11 1.88E-11 2.20E-11 3.39E-11 3.40E-11 17 1.25 21.71 3.19E-11 2.15E-11 1.81E-11 1.49E-11 1.81E-11 2.14E-11 3.29E-11 3.29E-11 18 1.42 23.13 3.06E-11 2.17E-11 1.85E-11 1.55E-11 1.83E-11 2.15E-11 3.08E-11 3.09E-11 19 1.19 24.32 3.89E-11 2.69E-11 2.52E-11 1.98E-11 2.52E-11 2.60E-11 3.84E-11 3.89E-11 20 1.23 25.55 4.57E-11 3.00E-11 2.84E-11 2.36E-11 2.84E-11 2.93E-11 4.56E-11 4.57E-11 21 1.28 26.83 4.36E-11 2.91E-11 2.81E-11 2.31E-11 2.79E-11 2.84E-11 4.35E-11 4.36E-11 22 1.31 28.13 5.05E-11 3.28E-11 2.93E-11 2.58E-11 2.93E-11 3.20E-11 5.04E-11 5.05E-11 23 1.40 29.53 5.04E-11 3.29E-11 3.23E-11 2.61E-11 3.23E-11 3.22E-11 5.03E-11 5.04E-11 24 1.34 30.88 4.60E-11 3.00E-11 2.81E-11 2.24E-11 2.80E-11 2.94E-11 4.60E-11 4.60E-11 25(a) 1.43 32.30 4.41E-11 2.87E-11 2.74E-11 2.12E-11 2.74E-11 2.86E-11 4.44E-11 4.44E-11 Note:

(a) Cycle 25 was the current operating cycle at the time the exposures reported in this table were determined. Values listed are based on the projected EFPY for this cycle.

WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 2-36 Table 2.5-4 St. Lucie Unit 2 Iron Atom Displacements at the RPV Clad/Base Metal Interface Cycle Cumulative Iron Atom Displacements (dpa)

Cycle Length Operating Time (EFPY) (EFPY) 0° 15° 30° 45° 60° 75° 90° Maximum 1 1.11 1.11 1.70E-03 1.09E-03 9.14E-04 6.79E-04 9.14E-04 1.07E-03 1.70E-03 1.70E-03 2 1.12 2.23 3.51E-03 2.16E-03 1.83E-03 1.37E-03 1.83E-03 2.11E-03 3.50E-03 3.51E-03 3 1.22 3.45 5.28E-03 3.22E-03 2.70E-03 2.01E-03 2.70E-03 3.15E-03 5.27E-03 5.28E-03 4 1.16 4.61 6.40E-03 4.11E-03 3.56E-03 2.66E-03 3.55E-03 4.03E-03 6.39E-03 6.40E-03 5 1.30 5.91 7.63E-03 5.11E-03 4.52E-03 3.37E-03 4.52E-03 5.02E-03 7.62E-03 7.63E-03 6 1.35 7.26 9.01E-03 6.00E-03 5.30E-03 4.00E-03 5.29E-03 5.88E-03 8.99E-03 9.01E-03 7 1.21 8.47 1.04E-02 6.84E-03 6.00E-03 4.60E-03 6.00E-03 6.71E-03 1.03E-02 1.04E-02 8 1.38 9.85 1.13E-02 7.56E-03 6.84E-03 5.26E-03 6.84E-03 7.41E-03 1.12E-02 1.13E-02 9 1.22 11.07 1.24E-02 8.49E-03 7.66E-03 5.86E-03 7.66E-03 8.33E-03 1.24E-02 1.24E-02 10 1.44 12.51 1.38E-02 9.60E-03 8.61E-03 6.60E-03 8.61E-03 9.42E-03 1.38E-02 1.38E-02 11 1.32 13.83 1.50E-02 1.05E-02 9.52E-03 7.33E-03 9.51E-03 1.03E-02 1.50E-02 1.50E-02 12 1.51 15.34 1.64E-02 1.14E-02 1.04E-02 8.12E-03 1.04E-02 1.12E-02 1.64E-02 1.64E-02 13 1.29 16.63 1.78E-02 1.23E-02 1.12E-02 8.83E-03 1.12E-02 1.21E-02 1.77E-02 1.78E-02 14 1.43 18.06 1.91E-02 1.32E-02 1.21E-02 9.56E-03 1.21E-02 1.29E-02 1.90E-02 1.91E-02 15 1.15 19.21 2.03E-02 1.40E-02 1.27E-02 1.01E-02 1.27E-02 1.37E-02 2.02E-02 2.03E-02 16 1.25 20.46 2.16E-02 1.48E-02 1.35E-02 1.07E-02 1.35E-02 1.45E-02 2.15E-02 2.16E-02 17 1.25 21.71 2.28E-02 1.57E-02 1.42E-02 1.13E-02 1.42E-02 1.54E-02 2.28E-02 2.28E-02 18 1.42 23.13 2.42E-02 1.66E-02 1.50E-02 1.20E-02 1.50E-02 1.63E-02 2.42E-02 2.42E-02 19 1.19 24.32 2.57E-02 1.77E-02 1.59E-02 1.27E-02 1.59E-02 1.73E-02 2.56E-02 2.57E-02 20 1.23 25.55 2.74E-02 1.88E-02 1.70E-02 1.36E-02 1.70E-02 1.85E-02 2.74E-02 2.74E-02 21 1.28 26.83 2.92E-02 2.00E-02 1.82E-02 1.46E-02 1.82E-02 1.96E-02 2.92E-02 2.92E-02 22 1.31 28.13 3.13E-02 2.13E-02 1.94E-02 1.56E-02 1.94E-02 2.09E-02 3.12E-02 3.13E-02 23 1.40 29.53 3.35E-02 2.28E-02 2.08E-02 1.68E-02 2.08E-02 2.23E-02 3.34E-02 3.35E-02 24 1.34 30.88 3.54E-02 2.41E-02 2.20E-02 1.77E-02 2.20E-02 2.36E-02 3.54E-02 3.54E-02 25(a) 1.43 32.30 3.74E-02 2.54E-02 2.32E-02 1.87E-02 2.32E-02 2.49E-02 3.74E-02 3.74E-02 WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 2-37 Table 2.5-4 St. Lucie Unit 2 Iron Atom Displacements at the RPV Clad/Base Metal Interface (Continued)

Projections with no bias on the peripheral and re-entrant corner assembly relative powers (b)

Future -- 36.00 4.28E-02 2.89E-02 2.65E-02 2.13E-02 2.65E-02 2.83E-02 4.28E-02 4.28E-02 Future(b) -- 42.00 5.15E-02 3.45E-02 3.18E-02 2.55E-02 3.18E-02 3.39E-02 5.15E-02 5.15E-02 Future(b) -- 48.00 6.02E-02 4.02E-02 3.71E-02 2.98E-02 3.71E-02 3.94E-02 6.02E-02 6.02E-02 Future(b) -- 54.00 6.89E-02 4.59E-02 4.25E-02 3.40E-02 4.24E-02 4.50E-02 6.89E-02 6.89E-02 Future(b) -- 60.00 7.76E-02 5.16E-02 4.78E-02 3.83E-02 4.77E-02 5.06E-02 7.76E-02 7.76E-02 Future(b) -- 66.00 8.63E-02 5.73E-02 5.31E-02 4.25E-02 5.30E-02 5.61E-02 8.63E-02 8.63E-02 Future(b) -- 72.00 9.51E-02 6.29E-02 5.84E-02 4.68E-02 5.83E-02 6.17E-02 9.50E-02 9.51E-02 Projections with a +10% bias on the peripheral and re-entrant corner assembly relative powers Future(b) -- 36.00 4.32E-02 2.92E-02 2.68E-02 2.16E-02 2.68E-02 2.86E-02 4.32E-02 4.32E-02 Future(b) -- 42.00 5.27E-02 3.54E-02 3.26E-02 2.62E-02 3.26E-02 3.47E-02 5.27E-02 5.27E-02 Future(b) -- 48.00 6.22E-02 4.15E-02 3.85E-02 3.09E-02 3.84E-02 4.07E-02 6.21E-02 6.22E-02 Future(b) -- 54.00 7.17E-02 4.77E-02 4.43E-02 3.55E-02 4.42E-02 4.68E-02 7.16E-02 7.17E-02 Future(b) -- 60.00 8.11E-02 5.39E-02 5.01E-02 4.02E-02 5.00E-02 5.29E-02 8.11E-02 8.11E-02 Future(b) -- 66.00 9.06E-02 6.01E-02 5.59E-02 4.48E-02 5.58E-02 5.89E-02 9.05E-02 9.06E-02 Future(b) -- 72.00 1.00E-01 6.63E-02 6.17E-02 4.95E-02 6.16E-02 6.50E-02 1.00E-01 1.00E-01 Notes:

(a) Cycle 25 was the current operating cycle at the time the exposures reported in this table were determined. Values listed are based on the projected EFPY for this cycle.

(b) Values beyond Cycle 25 are based on the average core power distributions and reactor operating conditions of Cycle 24 and are determined both with and without a 1.1 bias on the peripheral and re-entrant corner assembly relative powers.

WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 6-2 Table 6-1 RTPTS Calculations for St. Lucie Unit 1 Reactor Vessel Beltline Materials at 72 EFPY Fluence(b) Predicted (a) RTNDT(U)(d) U (e) M RTPTS Material CF (x 1019 n/cm2, FF(c) RTNDT (°F)

E > 1.0 MeV) (°F) (°F) (°F) (°F)

(°F)

Beltline Intermediate Shell Plate C-7-1 74.60 6.38 1.447 0 108.0 0 17.0 34.0 142.0 Intermediate Shell Plate C-7-2 74.60 6.38 1.447 -10 108.0 0 17.0 34.0 132.0 Intermediate Shell Plate C-7-3 73.80 6.38 1.447 10 106.8 0 17.0 34.0 150.8 Lower Shell Plate C-8-1 107.80 6.35 1.447 20 155.9 0 17.0 34.0 209.9 with credible surveillance data(f) 81.84 6.35 1.447 20 118.4 0 8.5 17.0 155.4 Lower Shell Plate C-8-2 108.35 6.35 1.447 20 156.7 0 17.0 34.0 210.7 with credible surveillance data(f) 82.67 6.35 1.447 20 119.6 0 8.5 17.0 156.6 Lower Shell Plate C-8-3 82.60 6.35 1.447 0 119.5 0 17.0 34.0 153.5 with credible surveillance data(f) 62.83 6.35 1.447 0 90.9 0 8.5 17.0 107.9 Intermediate to Lower Shell Girth Weld Seam 9-203 124.25 6.32 1.446 -60 179.6 0 28.0 56.0 175.6 (Heat # 90136) with credible surveillance data(f) 85.79 6.32 1.446 -60 124.0 0 14.0 28.0 92.0 Intermediate Shell Axial Weld Seams 2-203 A, B, & C 90.65 3.91 1.351 -56 122.5 17 28.0 65.5 132.0 (Heat #s 34B009 / A-8746)

Lower Shell Axial Weld Seams 3-203 A, B, & C 188.80 3.88 1.350 -60 254.8 0 28.0 56.0 250.8 (Heat # 305424) with non-credible Beaver Valley Unit 1 176.28 3.88 1.350 -60 237.9 0 28.0 56.0 233.9 surveillance data(f)

Extended Beltline Upper Shell Plate C-6-1 113.10 0.301 0.671 33 75.9 0 17.0 34.0 142.9 Upper Shell Plate C-6-2 113.10 0.301 0.671 15 75.9 0 17.0 34.0 124.9 Upper Shell Plate C-6-3 113.10 0.301 0.671 15 75.9 0 17.0 34.0 124.9 Upper to Intermediate Shell Girth Weld 172.22 0.377 0.730 -56 125.8 17 28.0 65.5 135.3 Seam 8-203 (Heat # 21935)

Upper Shell Axial Seams 1-203 A, B, and C 208.62 0.377 0.730 -50 152.3 0 28.0 56.0 158.3 (Heat #s 21935 / 12008)

Notes contained on the following page.

WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 6-3 Notes:

(a) Chemistry factors (CFs) are taken from Table 5-4.

(b) The 72 EFPY maximum fluence values for the reactor vessel materials were taken from Table 2.4-5. Only those projected fluence values with a 1.1 bias on the peripheral and re-entrant corner assembly relative powers are considered.

(c) FF = fluence factor = f(0.28 - 0.10

log (f)).

(d) RTNDT(U) values taken from Table 3-1.

(e) Per 10 CFR 50.61WKHEDVHPHWDO = 17°F when surveillance data is non-FUHGLEOHRUQRWXVHGWRGHWHUPLQHWKH&)DQGWKHEDVHPHWDO = 8.5°F when credible surveillance data is used to determine the CF. Also, per 10 CFR 50.61WKHZHOGPHWDO = 28°F when surveillance data are non-credible or not used to determine the CF, and the weld PHWDO = 14°F when credible surveillance data are used to determine the CF. +RZHYHU need not exceed 0.5

57NDT.

(f) The credibility evaluation for the St. Lucie Unit 1 surveillance data in Appendix B determined that the St. Lucie Unit 1 surveillance data for the Lower Shell Plate C-8-2 and Heat # 90136 materials are deemed credible. Therefore, the Position 2.1 CF can be used with a reduced margin term in lieu of the Position 1.1 CF. The Beaver Valley Unit 1 Heat # 305424 surveillance weld was determined to be non-credible in WCAP-18102-NP [Ref. 28].

WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 6-4 Table 6-2 RTPTS Calculations for St. Lucie Unit 2 Reactor Vessel Beltline Materials at 72 EFPY Fluence(b) Predicted (a) RTNDT(U)(d) U (e) M RTPTS Material CF (x 1019 n/cm2, FF (c)

RTNDT (°F)

E > 1.0 MeV) (°F) (°F) (°F) (°F)

(°F)

Beltline Intermediate Shell Plate M-605-1 74.15 6.56 1.452 30 107.7 0 17.0 34.0 171.7 with credible surveillance data(f) 102.12 6.56 1.452 30 148.3 0 8.5 17.0 195.3 Intermediate Shell Plate M-605-2 91.50 6.56 1.452 10 132.9 0 17.0 34.0 176.9 Intermediate Shell Plate M-605-3 74.15 6.56 1.452 0 107.7 0 17.0 34.0 141.7 with credible surveillance data(f) 102.12 6.56 1.452 0 148.3 0 8.5 17.0 165.3 Lower Shell Plate M-4116-1 37.00 6.53 1.451 20 53.7 0 17.0 34.0 107.7 Lower Shell Plate M-4116-2 44.00 6.53 1.451 20 63.9 0 17.0 34.0 117.9 Lower Shell Plate M-4116-3 44.00 6.53 1.451 20 63.9 0 17.0 34.0 117.9 Intermediate to Lower Shell Girth Weld Seam 101-171 40.05 6.52 1.451 -50 58.1 0 28.0 56.0 64.1 (Heat #s 83637 / 3P7317)

Intermediate Shell Axial Weld Seams 101-124A, B, & C 36.35 4.31 1.372 -56 49.9 17 24.9 60.4 54.2 (Heat # 83642)

Intermediate Shell Axial Weld Seam 101-124C Repair 34.05 4.31 1.372 -50 46.7 0 23.4 46.7 43.4 (Heat # 83637) with credible surveillance data(f) 23.55 4.31 1.372 -50 32.3 0 14.0 28.0 10.3 Lower Shell Axial Welds Seams 101-142A, B, & C 34.05 4.29 1.371 -50 46.7 0 23.3 46.7 43.4 (Heat # 83637) with credible surveillance data(f) 23.55 4.29 1.371 -50 32.3 0 14.0 28.0 10.3 WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 6-5 Table 6-2 RTPTS Calculations for St. Lucie Unit 2 Reactor Vessel Beltline Materials at 72 EFPY (Continued)

Fluence(b) Predicted (a) RTNDT(U)(d) U (e) M RTPTS Material CF (x 1019 n/cm2, FF(c) RTNDT (°F)

E > 1.0 MeV) (°F) (°F) (°F) (°F)

(°F)

Extended Beltline Upper Shell Plate M-604-1 118.00 0.152 0.506 50 59.7 0 17.0 34.0 143.7 Upper Shell Plate M-604-2 118.25 0.152 0.506 50 59.8 0 17.0 34.0 143.8 Upper Shell Plate M-604-3 116.60 0.152 0.506 10 59.0 0 17.0 34.0 103.0 Upper to Intermediate Shell Girth Weld Seam 106-121 34.05 0.175 0.538 -50 18.3 0 9.2 18.3 -13.4 (Heat # 83637) with credible surveillance data(f) 23.55 0.175 0.538 -50 12.7 0 6.3 12.7 -24.7 Upper Shell Axial Weld Seams 101-122A & C 74.13 0.175 0.538 -40 39.9 0 19.9 39.9 39.8 (Heat # 5P5622)

Upper Shell Axial Weld Seams 101-122A & C 96.64 0.175 0.538 -50 52.0 0 26.0 52.0 54.0 (Heat # 2P5755)

Upper Shell Axial Weld Seam 101-122B 74.13 0.175 0.538 -40 39.9 0 19.9 39.9 39.8 (Heat # 5P5622)

Hot Leg Nozzle A 89.92 0.0103 0.112 -30 10.1 0 5.0 10.1 -9.9 M-4103-2 Hot Leg Nozzle B 90.36 0.0103 0.112 -20 10.1 0 5.1 10.1 0.2 M-4103-1 Hot Leg Nozzle to Shell Weld 63.70 0.0103 0.112 -60 7.1 0 3.6 7.1 -45.7 Seam 105-121A (Heat # 4P6519)

Hot Leg Nozzle to Shell Weld 68.00 0.0103 0.112 -60 7.6 0 3.8 7.6 -44.8 Seam 105-121B (Various SMAWs)

Notes contained on the following page.

WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 6-6 Notes:

(a) Chemistry factors (CFs) are taken from Table 5-5.

(b) The 72 EFPY maximum fluence values for the reactor vessel materials were taken from Table 2.5-5. Only those projected fluence values with a 1.1 bias on the peripheral and re-entrant corner assembly relative powers are considered.

(c) FF = fluence factor = f(0.28 - 0.10

log (f)).

(d) RTNDT(U) values taken from Table 3-2.

(e) Per 10 CFR 50.61WKHEDVHPHWDO = 17°F when surveillance data is non-FUHGLEOHRUQRWXVHGWRGHWHUPLQHWKH&)DQGWKHEDVHPHWDO = 8.5°F when credible surveillance data is used to determine the CF. Also, per 10 CFR 50.61WKHZHOGPHWDO = 28°F when surveillance data are non-credible or not used to determine the CF, and the weld PHWDO = 14°F when credible surveillance data are used to determine the CF. +RZHYHU QHHGQRWH[FHHG 57NDT.

(f) The credibility evaluation for the St. Lucie Unit 2 surveillance data in Appendix B determined that the St. Lucie Unit 2 surveillance data for the Intermediate Shell Plate M-605-1 and Heat # 83637 are deemed credible.

WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 7-1 7 UPPER-SHELF ENERGY The decrease in Charpy upper-shelf energy (USE) is associated with the determination of acceptable RPV toughness during the license renewal period when the vessel is exposed to additional irradiation.

The requirements on USE are included in 10 CFR 50, Appendix G [Ref. 8]. 10 CFR 50, Appendix G requires utilities to submit an analysis at least three years prior to the time that the USE of any RPV material is predicted to drop below 50 ft-lb, as measured by Charpy V-notch specimen testing.

There are two methods that can be used to predict the decrease in USE with irradiation, depending on the availability of credible surveillance capsule data as defined in RG 1.99, Revision 2 [Ref. 4]. For vessel beltline materials that are not in the surveillance program or have non-credible data, the Charpy USE (Position 1.2) is assumed to decrease as a function of fluence and copper content, as indicated in RG 1.99, Revision 2.

When two or more credible surveillance sets become available from the reactor, they may be used to determine the Charpy USE of the surveillance material. The surveillance data are then used in conjunction with the Regulatory Guide to predict the change in USE (Position 2.2) of the RPV material due to irradiation. Per RG 1.99, Revision 2, when credible data exist, the Position 2.2 projected USE value should be used in preference to the Position 1.2 projected USE value.

The 72 EFPY Position 1.2 USE values of the vessel materials can be predicted using the corresponding 1/4T fluence projections, the copper content of the materials, and Figure 2 in RG 1.99, Revision 2 (see Figures 7-1 and 7-2 of this report). Only those projected fluence values with a 1.1 bias on the peripheral and re-entrant corner assembly relative powers are considered.

The predicted Position 2.2 USE values are determined for the reactor vessel materials that are contained in the surveillance program by using the reduced plant surveillance data along with the corresponding 1/4T fluence projection. The surveillance data from Tables 4-1 and 4-2 was plotted in RG 1.99, Revision 2, Figure 2 (see Figures 7-1 and 7-2 of this report). This data was fitted by drawing a line parallel to the existing lines as the upper bound of all the surveillance data. These reduced lines were used instead of the existing lines to determine the Position 2.2 USE values. Note, Position 2.2 USE projections are performed only for those St. Lucie Units 1 and 2 vessel base metal materials from which the surveillance materials were extracted and weld metal materials with the same heat and flux type as the surveillance weld.

The projected USE values were calculated to determine if the St. Lucie Units 1 and 2 beltline and extended beltline materials remain above the 50 ft-lb criterion at 72 EFPY (SLR). These calculations are summarized in Tables 7-1 and 7-2.

WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 7-2 USE Conclusion As shown in Tables 7-1 and 7-2, all of the St. Lucie Units 1 and 2 reactor vessel beltline materials are projected to remain above the USE screening criterion of 50 ft-lb (per 10 CFR 50, Appendix G) at 72 EFPY (SLR). The limiting projected USE value at SLR for St. Lucie Unit 1 is Intermediate Shell Plate C-7-3 with a projected USE of 54.8 ft-lb. The limiting projected USE value at SLR for St. Lucie Unit 2 is Lower Shell Plate M-4116-1 with a projected USE of 66.4 ft-lb.

WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 7-3 Table 7-1 Predicted USE Values for the St. Lucie Unit 1 Beltline and Extended Beltline Materials at SLR (72 EFPY) 1/4T Unirradiated Projected USE Projected Weight % Fluence(b)

Material USE(a) Decrease(c) USE Cu(a) (x 1019 n/cm2, (ft-lb) (%) (ft-lb)

E > 1.0 MeV)

Beltline Materials Position 1.2 Results Intermediate Shell Plate C-7-1 0.11 3.80 81.9 28 59.0 Intermediate Shell Plate C-7-2 0.11 3.80 81.9 28 59.0 Intermediate Shell Plate C-7-3 0.11 3.80 76.05 28 54.8 Lower Shell Plate C-8-1 0.15 3.78 81.9 33 54.9 Lower Shell Plate C-8-2 0.15 3.78 103 33 69.0 Lower Shell Plate C-8-3 0.12 3.78 88.4 29 62.8 Intermediate to Lower Shell Girth Weld Seam 9-203 0.27 3.77 144 52 69.1 (Heat # 90136)

Intermediate Shell Axial Weld Seams 2-203 A, B, & C 0.19 2.33 102.3 41 60.4 (Heat #s 34B009 / A-8746)

Lower Shell Axial Weld Seams 3-203 A, B, & C 0.27 2.31 112 49 57.1 (Heat # 305424)

Extended Beltline Materials Position 1.2 Results Upper Shell Plate C-6-1 0.16 0.179 68 17 56.4 Upper Shell Plate C-6-2 0.16 0.179 80 17 66.4 Upper Shell Plate C-6-3 0.16 0.179 84 17 69.7 Upper to Intermediate Shell Girth Weld Seam 8-203 0.183 0.225 109 24 82.8 (Heat # 21935)

Upper Shell Axial Seams 1-203 A, B, and C 0.213 0.225 118 26 87.3 (Heat #s 21935 / 12008)

Beltline Materials Position 2.2 Results Lower Shell Plate C-8-2 0.15 3.78 103 39 62.8 Intermediate to Lower Shell Girth Weld Seam 9-203 0.27 3.77 144 49 73.4 (Heat # 90136)

Notes:

(a) Copper weight percent values and unirradiated USE values were taken from Table 3-1.

(b) Values taken from Table 8-3. Only those projected fluence values with a 1.1 bias on the peripheral and re-entrant corner assembly relative powers are considered.

(c) Position 1.2 percentage USE decrease values were calculated by plotting the 1/4T fluence values on RG 1.99, Figure 2 and using the material-specific Cu wt. % values. Position 2.2 percentage USE decrease values were determined by drawing an upper-bound line parallel to the existing RG 1.99, Figure 2 lines through the applicable surveillance data points. These results should be used in preference to the existing graph lines for determining the decrease in USE, because the surveillance data is credible. The St. Lucie Unit 1 surveillance data use for the RG 1.99, Position 2.2 projection can be found in Table 4-1.

WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 7-4 Table 7-2 Predicted USE Values for the St. Lucie Unit 2 Beltline and Extended Beltline Materials at 72 EFPY 1/4T Unirradiated Projected USE Projected Weight % Fluence(b)

Material USE(a) Decrease(c) USE Cu(a) 19 (x 10 n/cm , 2 (ft-lb) (%) (ft-lb)

E > 1.0 MeV)

Beltline Materials Position 1.2 Results Intermediate Shell Plate M-605-1 0.11 3.91 105 29 74.6 Intermediate Shell Plate M-605-2 0.13 3.91 113 31 78.0 Intermediate Shell Plate M-605-3 0.11 3.91 113 29 80.2 Lower Shell Plate M-4116-1 0.06 3.89 91 27 66.4 Lower Shell Plate M-4116-2 0.07 3.89 105 27 76.7 Lower Shell Plate M-4116-3 0.07 3.89 100 27 73.0 Intermediate to Lower Shell Girth Weld Seam 101-171 0.07 3.89 96 30 67.2 (Heat #s 83637 / 3P7317)

Intermediate Shell Axial Weld Seams 101-124A, B, & C 0.05 2.57 116 24 88.2 (Heat # 83642)

Intermediate Shell Axial Weld Seam 101-124C Repair 0.05 2.57 136 24 103.4 (Heat # 83637)

Lower Shell Axial Welds Seams 101-142A, B, & C 0.05 2.56 136 24 103.4 (Heat # 83637)

Extended Beltline Materials Position 1.2 Results Upper Shell Plate M-604-1 0.16 0.0906 90 15 76.5 Upper Shell Plate M-604-2 0.16 0.0906 82 15 69.7 Upper Shell Plate M-604-3 0.16 0.0906 106 15 90.1 Upper to Intermediate Shell Girth Weld Seam 106-121 0.05 0.104 136 12 119.7 (Heat # 83637)

Upper Shell Axial Weld Seams 101-122A & C 0.153 0.104 102 18 83.6 (Heat # 5P5622)

Upper Shell Axial Weld Seams 101-122A & C 0.21 0.104 109 22 85.0 (Heat # 2P5755)

Upper Shell Axial Weld Seam 101-122B 0.153 0.104 102 18 83.6 (Heat # 5P5622)

Hot Leg Nozzle A 0.127 0.0103(d) 107 9 97.4 M-4103-2 Hot Leg Nozzle B 0.127 0.0103(d) 111 9 101.0 M-4103-1 Hot Leg Nozzle to Shell Weld Seam 105-121A 0.131 0.0103(d) 107 11 95.2 (Heat # 4P6519)

Hot Leg Nozzle to Shell Weld Seam 105-121B 0.05 0.0103(d) 128 8 117.8 (Various SMAWs)

Beltline Materials Position 2.2 Results Intermediate Shell Plate M-605-1 0.11 3.91 105 32 71.4 Notes contained on the following page.

WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 7-5 Notes:

(a) Copper (Cu) weight percent values and unirradiated USE values were taken from Table 3-2. If the base metal or weld Cu weight percentages are below the minimum value presented in Figure 2 of RG 1.99, Revision 2 [Ref. 4] (0.1 for base metal and 0.05 for welds), then the Cu weight percentages were conservatively rounded up to the minimum value for projected USE decrease determination.

(b) Values taken from Table 8-4. Fluence values above 1017 n/cm2 (E > 1.0 MeV) but below 2 x 1017 n/cm2 (E > 1.0 MeV) were rounded to 2 x 1017 n/cm2 (E > 1.0 MeV) when determining the % decrease because 2 x 1017 n/cm2 is the lowest fluence displayed in Figure 2 of RG 1.99. Only those projected fluence values with a 1.1 bias on the peripheral and re-entrant corner assembly relative powers are considered.

(c) Position 1.2 percentage USE decrease values were calculated by plotting the 1/4T fluence values on RG 1.99, Figure 2 and using the material-specific Cu wt. % values. The percent-loss lines were extended into the low fluence area of RG 1.99, Figure 2, i.e., below 1018 n/cm2, in order to determine the USE percent decrease, as needed. Position 2.2 percentage USE decrease values were determined by drawing an upper-bound line parallel to the existing RG 1.99, Figure 2 lines through the applicable surveillance data points. These results should be used in preference to the existing graph lines for determining the decrease in USE, because the surveillance data is credible. The St. Lucie Unit 2 surveillance data used for the RG 1.99, Position 2.2 projection can be found in Table 4-2.

(d) Values are the maximum fluence values instead of the 1/4T fluence values.

WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 7-6 100.0

% Copper Base Metal Weld 0.35 0.30 0.30 0.25 Limiting Plate Percent USE Decrease: 24% from 0.25 0.20 Transverse Specimens in Capsule 97° Limiting Ht. # 90136 Percent USE Decrease: 31%

0.20 0.15 from Capsule 97° 0.15 0.10 0.10 0.05 Upper Limit Percentage Drop in USE 10.0 Intermediate Shell Plate 1/4T Fluence = 3.80 x 1019 n/cm2 Upper Shell Welds and 1/4T Fluence = 2.25 x 1018 n/cm2 Lower Shell Plate and 1/4T Fluence = 3.78 x 1019 n/cm2 Upper Shell Plates and 1/4T Fluence = 1.79 x 1018 n/cm2 Intermediate to Lower Girth Weld 1/4T Fluence = 3.77 x 1019 n/cm2 Lower Shell Axial Welds 1/4T Fluence = 2.31 x 1019 n/cm2 Measured Plate Data for Lower Shell C-8-2 and Intermediate Shell Axial Welds 1/4T Fluence = 2.33 x 1019 n/cm2 Measured Weld Data for Heat # 90136 1.0 1.00E+17 1.00E+18 1.00E+19 1.00E+20 Neutron Fluence, n/cm2 (E > 1 MeV)

Figure 7-1 Regulatory Guide 1.99, Revision 2, St. Lucie Unit 1 Predicted Decrease in USE at 72 EFPY as a Function of Copper and Fluence WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 7-7 100.0

% Copper Base Metal Weld 0.35 0.30 0.30 0.25 0.25 0.20 0.20 0.15 0.15 0.10 0.10 0.05 Upper Limit Percentage Drop in USE Limiting Surv. Plate Percent USE Decrease:

23% from Transverse Specimens from Capsule 263° 10.0 Hot Leg Nozzle to Upper Shell Welds Maximum Fluence = 1.03 x 1017 n/cm2 Intermediate Shell Plate 1/4T Fluence = 3.91 x 1019 n/cm2 Upper Shell Welds and 1/4T Fluence = 1.04 x 1018 n/cm2 Lower Shell Plate and and Intermediate to Lower Girth Weld Upper Shell Plates 1/4T Fluence = 3.89 x 1019 n/cm2 1/4T Fluence = 9.06 x 1017 n/cm2 Measured Plate Data for Intermediate Shell Plate M-605-1 Intermediate Shell Axial Welds Measured Weld Data for Heat # 83637 1/4T Fluence = 2.57 x 1019 n/cm2 and Lower Shell Axial Welds 1/4T Fluence = 2.56 x 1019 n/cm2 1.0 1.00E+17 1.00E+18 1.00E+19 1.00E+20 Neutron Fluence, n/cm2 (E > 1 MeV)

Figure 7-2 Regulatory Guide 1.99, Revision 2, St. Lucie Unit 2 Predicted Decrease in USE at 72 EFPY as a Function of Copper and Fluence WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 8-7 Table 8-5 Calculation of the St. Lucie Unit 1 ART Values at the 1/4T Location for the Reactor Vessel Beltline and Extended Beltline Materials at EOLE (54 EFPY) 1/4T R.G. 1.99, Predicted Fluence(b) 1/4T RTNDT(U)(c) I (d) M ART Material Rev. 2 CF(a) RTNDT (x 1019 n/cm2, FF(b) (°F) (°F) (°F) (°F) (°F)

Position (°F)

E > 1.0 MeV)

Beltline Intermediate Shell Plate C-7-1 1.1 74.60 2.74 1.269 0 94.7 0 17.0 34.0 128.7 Intermediate Shell Plate C-7-2 1.1 74.60 2.74 1.269 -10 94.7 0 17.0 34.0 118.7 Intermediate Shell Plate C-7-3 1.1 73.80 2.74 1.269 10 93.7 0 17.0 34.0 137.7 Lower Shell Plate C-8-1 1.1 107.80 2.73 1.268 20 136.7 0 17.0 34.0 190.7 with credible surveillance data(e) 2.1 81.84 2.73 1.268 20 103.8 0 8.5 17.0 140.8 Lower Shell Plate C-8-2 1.1 108.35 2.73 1.268 20 137.4 0 17.0 34.0 191.4 with credible surveillance data(e) 2.1 82.67 2.73 1.268 20 104.8 0 8.5 17.0 141.8 Lower Shell Plate C-8-3 1.1 82.60 2.73 1.268 0 104.7 0 17.0 34.0 138.7 with credible surveillance data(e) 2.1 62.83 2.73 1.268 0 79.7 0 8.5 17.0 96.7 Intermediate to Lower Shell Girth Weld Seam 9-203 1.1 124.25 2.72 1.267 -60 157.4 0 28.0 56.0 153.4 (Heat # 90136) with credible surveillance data(e) 2.1 85.79 2.72 1.267 -60 108.7 0 14.0 28.0 76.7 Intermediate Shell Axial Weld Seams 2-203 A, B, & C 1.1 90.65 1.70 1.146 -56 103.9 17 28.0 65.5 113.4 (Heat #s 34B009 / A-8746)

Lower Shell Axial Weld Seams 3-203 A, B, & C 1.1 188.80 1.69 1.144 -60 216.0 0 28.0 56.0 212.0 (Heat # 305424) with non-credible Beaver Valley 2.1 176.28 1.69 1.144 -60 201.7 0 28.0 56.0 197.7 Unit 1 surveillance data(e)

WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 8-8 Table 8-5 Calculation of the St. Lucie Unit 1 ART Values at the 1/4T Location for the Reactor Vessel Beltline and Extended Beltline Materials at EOLE (54 EFPY) (Continued) 1/4T R.G. 1.99, Predicted Fluence(b) 1/4T RTNDT(U)(c) I (d) M ART Material Rev. 2 CF(a) 19 2 (b) RTNDT (x 10 n/cm , FF (°F) (°F) (°F) (°F) (°F)

Position (°F)

E > 1.0 MeV)

Extended Beltline Upper Shell Plate C-6-1 1.1 113.10 0.129 0.470 33 53.2 0 17.0 34.0 120.2 Upper Shell Plate C-6-2 1.1 113.10 0.129 0.470 15 53.2 0 17.0 34.0 102.2 Upper Shell Plate C-6-3 1.1 113.10 0.129 0.470 15 53.2 0 17.0 34.0 102.2 Upper to Intermediate Shell Girth Weld Seam 8-203 1.1 172.22 0.162 0.520 -56 89.6 17 28.0 65.5 99.1 (Heat # 21935)

Upper Shell Axial Seams 1-203 A, B, and C 1.1 208.62 0.162 0.520 -50 108.6 0 28.0 56.0 114.6 (Heat #s 21935 / 12008)

Notes:

(a) Chemistry factors are taken from Table 5-4.

(b) Fluence and fluence factors taken from Table 8-1.

(c) RTNDT(U) values taken from Table 3-1.

(d) Per the guidance of RG 1.99, Revision 2 [Ref. 4]WKHEDVHPHWDO = 17°F for Position 1.1 and Position 2.1 with non-FUHGLEOHVXUYHLOODQFHGDWDDQGWKHEDVHPHWDO = 8.5°F for Position 2.1 with credible surveillance data. Also, per RG 5HYLVLRQWKHZHOGPHWDO = 28°F for Position 1.1 and Position 2.1 with non-FUHGLEOHVXUYHLOODQFHGDWDDQGWKHZHOGPHWDO = 14°F for Position 2.1 with credible surveillance data. +RZHYHU need not exFHHG 57NDT for either base metals or welds, with or without surveillance data.

(e) The credibility evaluation for the St. Lucie Unit 1 surveillance data in Appendix B determined that the St. Lucie Unit 1 surveillance data for the Lower Shell Plate C-8-2 and Heat # 90136 materials are deemed credible. Therefore, the Position 2.1 CF can be used with a reduced margin term in lieu of the Position 1.1 CF. The Beaver Valley Unit 1 Heat # 305424 surveillance weld was determined to be non-credible in WCAP-18102-NP [Ref. 28].

WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 8-9 Table 8-6 Calculation of the St. Lucie Unit 1 ART Values at the 3/4T Location for the Reactor Vessel Beltline and Extended Beltline Materials at EOLE (54 EFPY) 3/4T R.G. 1.99, Predicted Fluence(b) 3/4T RTNDT(U)(c) I (d) M ART Material Rev. 2 CF(a) RTNDT (x 1019 n/cm2, FF(b) (°F) (°F) (°F) (°F) (°F)

Position (°F)

E > 1.0 MeV)

Beltline Intermediate Shell Plate C-7-1 1.1 74.60 0.974 0.993 0 74.0 0 17.0 34.0 108.0 Intermediate Shell Plate C-7-2 1.1 74.60 0.974 0.993 -10 74.0 0 17.0 34.0 98.0 Intermediate Shell Plate C-7-3 1.1 73.80 0.974 0.993 10 73.3 0 17.0 34.0 117.3 Lower Shell Plate C-8-1 1.1 107.80 0.970 0.991 20 106.9 0 17.0 34.0 160.9 with credible surveillance data(e) 2.1 81.84 0.970 0.991 20 81.1 0 8.5 17.0 118.1 Lower Shell Plate C-8-2 1.1 108.35 0.970 0.991 20 107.4 0 17.0 34.0 161.4 with credible surveillance data(e) 2.1 82.67 0.970 0.991 20 82.0 0 8.5 17.0 119.0 Lower Shell Plate C-8-3 1.1 82.60 0.970 0.991 0 81.9 0 17.0 34.0 115.9 with credible surveillance data(e) 2.1 62.83 0.970 0.991 0 62.3 0 8.5 17.0 79.3 Intermediate to Lower Shell Girth Weld Seam 9-203 1.1 124.25 0.965 0.990 -60 123.0 0 28.0 56.0 119.0 (Heat # 90136) with credible surveillance data(e) 2.1 85.79 0.965 0.990 -60 84.9 0 14.0 28.0 52.9 Intermediate Shell Axial Weld Seams 2-203 A, B, & C 1.1 90.65 0.603 0.859 -56 77.8 17 28.0 65.5 87.3 (Heat #s 34B009 / A-8746)

Lower Shell Axial Weld Seams 3-203 A, B, & C 1.1 188.80 0.599 0.857 -60 161.7 0 28.0 56.0 157.7 (Heat # 305424) with non-credible Beaver Valley 2.1 176.28 0.599 0.857 -60 151.0 0 28.0 56.0 147.0 Unit 1 surveillance data(e)

WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 8-10 Table 8-6 Calculation of the St. Lucie Unit 1 ART Values at the 3/4T Location for the Reactor Vessel Beltline and Extended Beltline Materials at EOLE (54 EFPY) (Continued) 3/4T R.G. 1.99, Predicted Fluence(b) 3/4T RTNDT(U)(c) I (d) M ART Material Rev. 2 CF(a) 19 2 (b) RTNDT (x 10 n/cm , FF (°F) (°F) (°F) (°F) (°F)

Position (°F)

E > 1.0 MeV)

Extended Beltline Upper Shell Plate C-6-1 1.1 113.10 0.0459 0.280 33 31.6 0 15.8 31.6 96.2 Upper Shell Plate C-6-2 1.1 113.10 0.0459 0.280 15 31.6 0 15.8 31.6 78.2 Upper Shell Plate C-6-3 1.1 113.10 0.0459 0.280 15 31.6 0 15.8 31.6 78.2 Upper to Intermediate Shell Girth Weld Seam 8-203 1.1 172.22 0.0576 0.316 -56 54.4 17 27.2 64.1 62.5 (Heat # 21935)

Upper Shell Axial Seams 1-203 A, B, and C 1.1 208.62 0.0576 0.316 -50 65.9 0 28.0 56.0 71.9 (Heat #s 21935 / 12008)

Notes:

(a) Chemistry factors are taken from Table 5-4.

(b) Fluence and fluence factors taken from Table 8-1.

(c) RTNDT(U) values taken from Table 3-1.

(d) Per the guidance of RG 1.99, Revision 2 [Ref. 4]WKHEDVHPHWDO = 17°F for Position 1.1 and Position 2.1 with non-FUHGLEOHVXUYHLOODQFHGDWDDQGWKHEDVHPHWDO = 8.5°F for Position 2.1 with credible surveillance data. Also, per RG 5HYLVLRQWKHZHOGPHWDO = 28°F for Position 1.1 and Position 2.1 with non-crediblHVXUYHLOODQFHGDWDDQGWKHZHOGPHWDO = 14°F for Position 2.1 with credible surveillance data. +RZHYHU QHHGQRWH[FHHG 57NDT for either base metals or welds, with or without surveillance data.

(e) The credibility evaluation for the St. Lucie Unit 1 surveillance data in Appendix B determined that the St. Lucie Unit 1 surveillance data for the Lower Shell Plate C-8-2 and Heat # 90136 materials are deemed credible. Therefore, the Position 2.1 CF can be used with a reduced margin term in lieu of the Position 1.1 CF. The Beaver Valley Unit 1 Heat # 305424 surveillance weld was determined to be non-credible in WCAP-18102-NP [Ref. 28].

WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 8-11 Table 8-7 Calculation of the St. Lucie Unit 2 ART Values at the 1/4T Location for the Reactor Vessel Beltline and Extended Beltline Materials at EOLE (55 EFPY) 1/4T R.G. 1.99, Predicted Fluence(b) 1/4T RTNDT(U)(c) I (d) M ART Material Rev. 2 CF(a) RTNDT (x 1019 n/cm2, FF(b) (°F) (°F) (°F) (°F) (°F)

Position (°F)

E > 1.0 MeV)

Beltline Intermediate Shell Plate M-605-1 1.1 74.15 2.86 1.279 30 94.9 0 17.0 34.0 158.9 with credible surveillance data(e) 2.1 102.12 2.86 1.279 30 130.6 0 8.5 17.0 177.6 Intermediate Shell Plate M-605-2 1.1 91.50 2.86 1.279 10 117.1 0 17.0 34.0 161.1 Intermediate Shell Plate M-605-3 1.1 74.15 2.86 1.279 0 94.9 0 17.0 34.0 128.9 with credible surveillance data(e) 2.1 102.12 2.86 1.279 0 130.6 0 8.5 17.0 147.6 Lower Shell Plate M-4116-1 1.1 37.00 2.85 1.278 20 47.3 0 17.0 34.0 101.3 Lower Shell Plate M-4116-2 1.1 44.00 2.85 1.278 20 56.2 0 17.0 34.0 110.2 Lower Shell Plate M-4116-3 1.1 44.00 2.85 1.278 20 56.2 0 17.0 34.0 110.2 Intermediate to Lower Shell Girth Weld Seam 101-171 1.1 40.05 2.84 1.278 -50 51.2 0 25.6 51.2 52.4 (Heat #s 83637 / 3P7317)

Intermediate Shell Axial Weld Seams 101-124A, B, & C 1.1 36.35 1.90 1.175 -56 42.7 17 21.4 54.6 41.3 (Heat # 83642)

Intermediate Shell Axial Weld Seam 101-124C Repair 1.1 34.05 1.90 1.175 -50 40.0 0 20.0 40.0 30.0 (Heat # 83637) with credible surveillance data(e) 2.1 23.55 1.90 1.175 -50 27.7 0 13.8 27.7 5.3 Lower Shell Axial Welds Seams 101-142A, B, & C 1.1 34.05 1.88 1.173 -50 40.0 0 20.0 39.9 29.9 (Heat # 83637) with credible surveillance data(e) 2.1 23.55 1.88 1.173 -50 27.6 0 13.8 27.6 5.3 WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 8-12 Table 8-7 Calculation of the St. Lucie Unit 2 ART Values at the 1/4T Location for the Reactor Vessel Beltline and Extended Beltline Materials at EOLE (55 EFPY) (Continued) 1/4T R.G. 1.99, Predicted Fluence(b) 1/4T RTNDT(U)(c) I (d) M ART Material Rev. 2 CF(a) RTNDT (x 1019 n/cm2, FF(b) (°F) (°F) (°F) (°F) (°F)

Position (°F)

E > 1.0 MeV)

Extended Beltline Upper Shell Plate M-604-1 1.1 118.00 0.0679 0.344 50 40.6 0 17.0 34.0 124.6 Upper Shell Plate M-604-2 1.1 118.25 0.0679 0.344 50 40.7 0 17.0 34.0 124.7 Upper Shell Plate M-604-3 1.1 116.60 0.0679 0.344 10 40.1 0 17.0 34.0 84.1 Upper to Intermediate Shell Girth Weld Seam 106-121 1.1 34.05 0.0793 0.372 -50 12.7 0 6.3 12.7 -24.7 (Heat # 83637) with credible surveillance data(e) 2.1 23.55 0.0793 0.372 -50 8.8 0 4.4 8.8 -32.5 Upper Shell Axial Weld Seams 101-122A & C 1.1 74.13 0.0793 0.372 -40 27.6 0 13.8 27.6 15.2 (Heat # 5P5622)

Upper Shell Axial Weld Seams 101-122A & C 1.1 96.64 0.0793 0.372 -50 36.0 0 18.0 36.0 21.9 (Heat # 2P5755)

Upper Shell Axial Weld Seam 101-122B 1.1 74.13 0.0793 0.372 -40 27.6 0 13.8 27.6 15.2 (Heat # 5P5622)

Notes:

(a) Chemistry factors are taken from Table 5-5.

(b) Fluence and fluence factors taken from Table 8-2.

(c) RTNDT(U) values taken from Table 3-2.

(d) Per the guidance of RG 1.99, Revision 2 [Ref. 4]WKHEDVHPHWDO = 17°F for Position 1.1 and Position 2.1 with non-FUHGLEOHVXUYHLOODQFHGDWDDQGWKHEDVHPHWDO = 8.5°F for Position 2.1 with credible surveillance data. Also, per RG 5HYLVLRQWKHZHOGPHWDO = 28°F for Position 1.1 and Position 2.1 with non-FUHGLEOHVXUYHLOODQFHGDWDDQGWKHZHOGPHWDO = 14°F for Position 2.1 with credible surveillance data. +RZHYHU QHHGQRWH[FHHG 57NDT for either base metals or welds, with or without surveillance data.

(e) The credibility evaluation for the St. Lucie Unit 2 surveillance data in Appendix B determined that the St. Lucie Unit 2 surveillance data for the Intermediate Shell Plate M-605-1 and Heat

83637 are deemed credible.

WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 8-13 Table 8-8 Calculation of the St. Lucie Unit 2 ART Values at the 3/4T Location for the Reactor Vessel Beltline and Extended Beltline Materials at EOLE (55 EFPY) 3/4T R.G. 1.99, Predicted (a) Fluence(b) 3/4T RTNDT(U)(c) I (d) M ART Material Rev. 2 CF RTNDT (x 1019 n/cm2, FF(b) (°F) (°F) (°F) (°F) (°F)

Position (°F)

E > 1.0 MeV)

Beltline Intermediate Shell Plate M-605-1 1.1 74.15 1.02 1.005 30 74.5 0 17.0 34.0 138.5 with credible surveillance data(e) 2.1 102.12 1.02 1.005 30 102.6 0 8.5 17.0 149.6 Intermediate Shell Plate M-605-2 1.1 91.50 1.02 1.005 10 91.9 0 17.0 34.0 135.9 Intermediate Shell Plate M-605-3 1.1 74.15 1.02 1.005 0 74.5 0 17.0 34.0 108.5 with credible surveillance data(e) 2.1 102.12 1.02 1.005 0 102.6 0 8.5 17.0 119.6 Lower Shell Plate M-4116-1 1.1 37.00 1.01 1.003 20 37.1 0 17.0 34.0 91.1 Lower Shell Plate M-4116-2 1.1 44.00 1.01 1.003 20 44.1 0 17.0 34.0 98.1 Lower Shell Plate M-4116-3 1.1 44.00 1.01 1.003 20 44.1 0 17.0 34.0 98.1 Intermediate to Lower Shell Girth Weld Seam 101-171 1.1 40.05 1.01 1.003 -50 40.2 0 20.1 40.2 30.3 (Heat #s 83637 / 3P7317)

Intermediate Shell Axial Weld Seams 101-124A, B, & C 1.1 36.35 0.673 0.889 -56 32.3 17 16.2 46.9 23.2 (Heat # 83642)

Intermediate Shell Axial Weld Seam 101-124C Repair 1.1 34.05 0.673 0.889 -50 30.3 0 15.1 30.3 10.5 (Heat # 83637) with credible surveillance data(e) 2.1 23.55 0.673 0.889 -50 20.9 0 10.5 20.9 -8.1 Lower Shell Axial Welds Seams 101-142A, B, & C 1.1 34.05 0.669 0.887 -50 30.2 0 15.1 30.2 10.4 (Heat # 83637) with credible surveillance data(e) 2.1 23.55 0.669 0.887 -50 20.9 0 10.4 20.9 -8.2 WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 8-14 Table 8-8 Calculation of the St. Lucie Unit 2 ART Values at the 3/4T Location for the Reactor Vessel Beltline and Extended Beltline Materials at EOLE (55 EFPY) (Continued) 3/4T R.G. 1.99, Predicted Fluence(b) 3/4T RTNDT(U)(c) I (d) M ART Material Rev. 2 CF(a) 19 2 (b) RTNDT (x 10 n/cm , FF (°F) (°F) (°F) (°F) (°F)

Position (°F)

E > 1.0 MeV)

Extended Beltline Upper Shell Plate M-604-1 1.1 118.00 0.0241 0.193 50 22.8 0 11.4 22.8 95.5 Upper Shell Plate M-604-2 1.1 118.25 0.0241 0.193 50 22.8 0 11.4 22.8 95.6 Upper Shell Plate M-604-3 1.1 116.60 0.0241 0.193 10 22.5 0 11.3 22.5 55.0 Upper to Intermediate Shell Girth Weld Seam 106-121 1.1 34.05 0.0282 0.212 -50 7.2 0 3.6 7.2 -35.6 (Heat # 83637) with credible surveillance data(e) 2.1 23.55 0.0282 0.212 -50 5.0 0 2.5 5.0 -40.0 Upper Shell Axial Weld Seams 101-122A & C 1.1 74.13 0.0282 0.212 -40 15.7 0 7.8 15.7 -8.6 (Heat # 5P5622)

Upper Shell Axial Weld Seams 101-122A & C 1.1 96.64 0.0282 0.212 -50 20.4 0 10.2 20.4 -9.1 (Heat # 2P5755)

Upper Shell Axial Weld Seam 101-122B 1.1 74.13 0.0282 0.212 -40 15.7 0 7.8 15.7 -8.6 (Heat # 5P5622)

Notes:

(a) Chemistry factors are taken from Table 5-5.

(b) Fluence and fluence factors taken from Table 8-2.

(c) RTNDT(U) values taken from Table 3-2.

(d) Per the guidance of RG 1.99, Revision 2 [Ref. 4]WKHEDVHPHWDO = 17°F for Position 1.1 and Position 2.1 with non-FUHGLEOHVXUYHLOODQFHGDWDDQGWKHEDVHPHWDO = 8.5°F for Position 2.1 with credible surveillance data. Also, per RG 1.99, Revision WKHZHOGPHWDO = 28°F for Position 1.1 and Position 2.1 with non-FUHGLEOHVXUYHLOODQFHGDWDDQGWKHZHOGPHWDO = 14°F for Position 2.1 with credible surveillance data. +RZHYHU QHHGQRWH[FHHG 57NDT for either base metals or welds, with or without surveillance data.

(e) The credibility evaluation for the St. Lucie Unit 2 surveillance data in Appendix B determined that the St. Lucie Unit 2 surveillance data for the Intermediate Shell Plate M-605-1 and Heat

83637 are deemed credible.

WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 8-15 Table 8-9 Calculation of the St. Lucie Unit 1 ART Values at the 1/4T Location for the Reactor Vessel Beltline and Extended Beltline Materials at SLR (72 EFPY) 1/4T R.G. 1.99, Predicted (a) Fluence(b) 1/4T RTNDT(U)(c) I (d) M ART Material Rev. 2 CF RTNDT (x 1019 n/cm2, FF(b) (°F) (°F) (°F) (°F) (°F)

Position (°F)

E > 1.0 MeV)

Beltline Intermediate Shell Plate C-7-1 1.1 74.60 3.80 1.345 0 100.3 0 17.0 34.0 134.3 Intermediate Shell Plate C-7-2 1.1 74.60 3.80 1.345 -10 100.3 0 17.0 34.0 124.3 Intermediate Shell Plate C-7-3 1.1 73.80 3.80 1.345 10 99.3 0 17.0 34.0 143.3 Lower Shell Plate C-8-1 1.1 107.80 3.78 1.344 20 144.9 0 17.0 34.0 198.9 with credible surveillance data(e) 2.1 81.84 3.78 1.344 20 110.0 0 8.5 17.0 147.0 Lower Shell Plate C-8-2 1.1 108.35 3.78 1.344 20 145.6 0 17.0 34.0 199.6 with credible surveillance data(e) 2.1 82.67 3.78 1.344 20 111.1 0 8.5 17.0 148.1 Lower Shell Plate C-8-3 1.1 82.60 3.78 1.344 0 111.0 0 17.0 34.0 145.0 with credible surveillance data(e) 2.1 62.83 3.78 1.344 0 84.5 0 8.5 17.0 101.5 Intermediate to Lower Shell Girth Weld Seam 9-203 1.1 124.25 3.77 1.343 -60 166.9 0 28.0 56.0 162.9 (Heat # 90136) with credible surveillance data(e) 2.1 85.79 3.77 1.343 -60 115.2 0 14.0 28.0 83.2 Intermediate Shell Axial Weld Seams 2-203 A, B, & C 1.1 90.65 2.33 1.229 -56 111.4 17 28.0 65.5 120.9 (Heat #s 34B009 / A-8746)

Lower Shell Axial Weld Seams 3-203 A, B, & C 1.1 188.80 2.31 1.227 -60 231.6 0 28.0 56.0 227.6 (Heat # 305424) with non-credible Beaver Valley 2.1 176.28 2.31 1.227 -60 216.2 0 28.0 56.0 212.2 Unit 1 surveillance data(e)

WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 8-16 Table 8-9 Calculation of the St. Lucie Unit 1 ART Values at the 1/4T Location for the Reactor Vessel Beltline and Extended Beltline Materials at SLR (72 EFPY) (Continued) 1/4T R.G. 1.99, Predicted Fluence(b) 1/4T RTNDT(U)(c) I (d) M ART Material Rev. 2 CF(a) 19 2 (b) RTNDT (x 10 n/cm , FF (°F) (°F) (°F) (°F) (°F)

Position (°F)

E > 1.0 MeV)

Extended Beltline Upper Shell Plate C-6-1 1.1 113.10 0.179 0.544 33 61.5 0 17.0 34.0 128.5 Upper Shell Plate C-6-2 1.1 113.10 0.179 0.544 15 61.5 0 17.0 34.0 110.5 Upper Shell Plate C-6-3 1.1 113.10 0.179 0.544 15 61.5 0 17.0 34.0 110.5 Upper to Intermediate Shell Girth Weld Seam 8-203 1.1 172.22 0.225 0.598 -56 102.9 17 28.0 65.5 112.4 (Heat # 21935)

Upper Shell Axial Seams 1-203 A, B, and C 1.1 208.62 0.225 0.598 -50 124.7 0 28.0 56.0 130.7 (Heat #s 21935 / 12008)

Notes:

(a) Chemistry factors are taken from Table 5-4.

(b) Fluence and fluence factors taken from Table 8-3.

(c) RTNDT(U) values taken from Table 3-1.

(d) Per the guidance of RG 1.99, Revision 2 [Ref. 4]WKHEDVHPHWDO = 17°F for Position 1.1 and Position 2.1 with non-FUHGLEOHVXUYHLOODQFHGDWDDQGWKHEDVHPHWDO = 8.5°F for Position 2.1 with credible surveillance data. Also, per RG 5HYLVLRQWKHZHOGPHWDO = 28°F for Position 1.1 and Position 2.1 with non-FUHGLEOHVXUYHLOODQFHGDWDDQGWKHZHOGPHWDO = 14°F for Position 2.1 with credible surveillance data. +RZHYHU QHHGQRWH[FHHG 57NDT for either base metals or welds, with or without surveillance data.

(e) The credibility evaluation for the St. Lucie Unit 1 surveillance data in Appendix B determined that the St. Lucie Unit 1 surveillance data for the Lower Shell Plate C-8-2 and Heat # 90136 materials are deemed credible. Therefore, the Position 2.1 CF can be used with a reduced margin term in lieu of the Position 1.1 CF. The Beaver Valley Unit 1 Heat # 305424 surveillance weld was determined to be non-credible in WCAP-18102-NP [Ref. 28].

WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 8-17 Table 8-10 Calculation of the St. Lucie Unit 1 ART Values at the 3/4T Location for the Reactor Vessel Beltline and Extended Beltline Materials at SLR (72 EFPY) 3/4T R.G. 1.99, Predicted (a) Fluence(b) 3/4T RTNDT(U)(c) I (d) M ART Material Rev. 2 CF RTNDT (x 1019 n/cm2, FF(b) (°F) (°F) (°F) (°F) (°F)

Position (°F)

E > 1.0 MeV)

Beltline Intermediate Shell Plate C-7-1 1.1 74.60 1.35 1.084 0 80.8 0 17.0 34.0 114.8 Intermediate Shell Plate C-7-2 1.1 74.60 1.35 1.084 -10 80.8 0 17.0 34.0 104.8 Intermediate Shell Plate C-7-3 1.1 73.80 1.35 1.084 10 80.0 0 17.0 34.0 124.0 Lower Shell Plate C-8-1 1.1 107.80 1.34 1.082 20 116.7 0 17.0 34.0 170.7 with credible surveillance data(e) 2.1 81.84 1.34 1.082 20 88.6 0 8.5 17.0 125.6 Lower Shell Plate C-8-2 1.1 108.35 1.34 1.082 20 117.3 0 17.0 34.0 171.3 with credible surveillance data(e) 2.1 82.67 1.34 1.082 20 89.5 0 8.5 17.0 126.5 Lower Shell Plate C-8-3 1.1 82.60 1.34 1.082 0 89.4 0 17 34.0 123.4 with credible surveillance data(e) 2.1 62.83 1.34 1.082 0 68.0 0 8.5 17.0 85.0 Intermediate to Lower Shell Girth Weld Seam 9-203 1.1 124.25 1.34 1.081 -60 134.3 0 28.0 56.0 130.3 (Heat # 90136) with credible surveillance data(e) 2.1 85.79 1.34 1.081 -60 92.7 0 14.0 28.0 60.7 Intermediate Shell Axial Weld Seams 2-203 A, B, & C 1.1 90.65 0.828 0.947 -56 85.8 17 28.0 65.5 95.4 (Heat #s 34B009 / A-8746)

Lower Shell Axial Weld Seams 3-203 A, B, & C 1.1 188.80 0.821 0.945 -60 178.4 0 28.0 56.0 174.4 (Heat # 305424) with non-credible Beaver Valley 2.1 176.28 0.821 0.945 -60 166.6 0 28.0 56.0 162.6 Unit 1 surveillance data(e)

WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 8-18 Table 8-10 Calculation of the St. Lucie Unit 1 ART Values at the 3/4T Location for the Reactor Vessel Beltline and Extended Beltline Materials at SLR (72 EFPY) (Continued) 3/4T R.G. 1.99, Predicted Fluence(b) 3/4T RTNDT(U)(c) I (d) M ART Material Rev. 2 CF(a) RTNDT (x 1019 n/cm2, FF(b) (°F) (°F) (°F) (°F) (°F)

Position (°F)

E > 1.0 MeV)

Extended Beltline Upper Shell Plate C-6-1 1.1 113.10 0.0637 0.333 33 37.6 0 17.0 34.0 104.6 Upper Shell Plate C-6-2 1.1 113.10 0.0637 0.333 15 37.6 0 17.0 34.0 86.6 Upper Shell Plate C-6-3 1.1 113.10 0.0637 0.333 15 37.6 0 17.0 34.0 86.6 Upper to Intermediate Shell Girth Weld Seam 8-203 1.1 172.22 0.0798 0.373 -56 64.3 17 28.0 65.5 73.8 (Heat # 21935)

Upper Shell Axial Seams 1-203 A, B, and C 1.1 208.62 0.0798 0.373 -50 77.9 0 28.0 56.0 83.9 (Heat #s 21935 / 12008)

Notes:

(a) Chemistry factors are taken from Table 5-4.

(b) Fluence and fluence factors taken from Table 8-3.

(c) RTNDT(U) values taken from Table 3-1.

(d) Per the guidance of RG 1.99, Revision 2 [Ref. 4]WKHEDVHPHWDO = 17°F for Position 1.1 and Position 2.1 with non-FUHGLEOHVXUYHLOODQFHGDWDDQGWKHEDVHPHWDO = 8.5°F for Position 2.1 with credible surveillance data. Also, per RG 5HYLVLRQWKHZHOGPHWDO = 28°F for Position 1.1 and Position 2.1 with non-FUHGLEOHVXUYHLOODQFHGDWDDQGWKHZHOGPHWDO = 14°F for Position 2.1 with credible surveillance data. +RZHYHU QHHGQRWH[FHHG 57NDT for either base metals or welds, with or without surveillance data.

(e) The credibility evaluation for the St. Lucie Unit 1 surveillance data in Appendix B determined that the St. Lucie Unit 1 surveillance data for the Lower Shell Plate C-8-2 and Heat # 90136 materials are deemed credible. Therefore, the Position 2.1 CF can be used with a reduced margin term in lieu of the Position 1.1 CF. The Beaver Valley Unit 1 Heat # 305424 surveillance weld was determined to be non-credible in WCAP-18102-NP [Ref. 28].

WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 8-19 Table 8-11 Calculation of the St. Lucie Unit 2 ART Values at the 1/4T Location for the Reactor Vessel Beltline and Extended Beltline Materials at SLR (72 EFPY) 1/4T R.G. 1.99, Predicted Fluence(b) 1/4T RTNDT(U)(c) I (d) M ART Material Rev. 2 CF(a) RTNDT (x 1019 n/cm2, FF(b) (°F) (°F) (°F) (°F) (°F)

Position (°F)

E > 1.0 MeV)

Beltline Intermediate Shell Plate M-605-1 1.1 74.15 3.91 1.351 30 100.2 0 17.0 34.0 164.2 with credible surveillance data(e) 2.1 102.12 3.91 1.351 30 138.0 0 8.5 17.0 185.0 Intermediate Shell Plate M-605-2 1.1 91.50 3.91 1.351 10 123.6 0 17.0 34.0 167.6 Intermediate Shell Plate M-605-3 1.1 74.15 3.91 1.351 0 100.2 0 17.0 34.0 134.2 with credible surveillance data(e) 2.1 102.12 3.91 1.351 0 138.0 0 8.5 17.0 155.0 Lower Shell Plate M-4116-1 1.1 37.00 3.89 1.350 20 50.0 0 17.0 34.0 104.0 Lower Shell Plate M-4116-2 1.1 44.00 3.89 1.350 20 59.4 0 17.0 34.0 113.4 Lower Shell Plate M-4116-3 1.1 44.00 3.89 1.350 20 59.4 0 17.0 34.0 113.4 Intermediate to Lower Shell Girth Weld Seam 101-171 1.1 40.05 3.89 1.350 -50 54.1 0 27.0 54.1 58.1 (Heat #s 83637 / 3P7317)

Intermediate Shell Axial Weld Seams 101-124A, B, & C 1.1 36.35 2.57 1.253 -56 45.5 17 22.8 56.8 46.4 (Heat # 83642)

Intermediate Shell Axial Weld Seam 101-124C Repair 1.1 34.05 2.57 1.253 -50 42.7 0 21.3 42.7 35.3 (Heat # 83637) with credible surveillance data(e) 2.1 23.55 2.57 1.253 -50 29.5 0 14.0 28.0 7.5 Lower Shell Axial Welds Seams 101-142A, B, & C 1.1 34.05 2.56 1.252 -50 42.6 0 21.3 42.6 35.2 (Heat # 83637) with credible surveillance data(e) 2.1 23.55 2.56 1.252 -50 29.5 0 14.0 28.0 7.5 WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 8-20 Table 8-11 Calculation of the St. Lucie Unit 2 ART Values at the 1/4T Location for the Reactor Vessel Beltline and Extended Beltline Materials at SLR (72 EFPY) (Continued) 1/4T R.G. 1.99, Predicted Fluence(b) 1/4T RTNDT(U)(c) I (d) M ART Material Rev. 2 CF(a) RTNDT (x 1019 n/cm2, FF(b) (°F) (°F) (°F) (°F) (°F)

Position (°F)

E > 1.0 MeV)

Extended Beltline Upper Shell Plate M-604-1 1.1 118.00 0.0906 0.397 50 46.9 0 17.0 34.0 130.9 Upper Shell Plate M-604-2 1.1 118.25 0.0906 0.397 50 47.0 0 17.0 34.0 131.0 Upper Shell Plate M-604-3 1.1 116.60 0.0906 0.397 10 46.3 0 17.0 34.0 90.3 Upper to Intermediate Shell Girth Weld Seam 106-121 1.1 34.05 0.104 0.425 -50 14.5 0 7.2 14.5 -21.0 (Heat # 83637) with credible surveillance data(e) 2.1 23.55 0.104 0.425 -50 10.0 0 5.0 10.0 -30.0 Upper Shell Axial Weld Seams 101-122A & C 1.1 74.13 0.104 0.425 -40 31.5 0 15.8 31.5 23.1 (Heat # 5P5622)

Upper Shell Axial Weld Seams 101-122A & C 1.1 96.64 0.104 0.425 -50 41.1 0 20.6 41.1 32.2 (Heat # 2P5755)

Upper Shell Axial Weld Seam 101-122B 1.1 74.13 0.104 0.425 -40 31.5 0 15.8 31.5 23.1 (Heat # 5P5622)

Notes:

(a) Chemistry factors are taken from Table 5-5.

(b) Fluence and fluence factors taken from Table 8-4.

(c) RTNDT(U) values taken from Table 3-2.

(d) Per the guidance of RG 1.99, Revision 2 [Ref. 4]WKHEDVHPHWDO = 17°F for Position 1.1 and Position 2.1 with non-FUHGLEOHVXUYHLOODQFHGDWDDQGWKHEDVHPHWDO = 8.5°F for Position 2.1 with credible surveillance data. Also, per RG 5HYLVLRQWKHZHOGPHWDO = 28°F for Position 1.1 and Position 2.1 with non-FUHGLEOHVXUYHLOODQFHGDWDDQGWKHZHOGPHWDO = 14°F for Position 2.1 with credible surveillance data. +RZHYHU QHHGQRWH[FHHG 57NDT for either base metals or welds, with or without surveillance data.

(e) The credibility evaluation for the St. Lucie Unit 2 surveillance data in Appendix B determined that the St. Lucie Unit 2 surveillance data for the Intermediate Shell Plate M-605-1 and Heat

83637 are deemed credible.

WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 8-21 Table 8-12 Calculation of the St. Lucie Unit 2 ART Values at the 3/4T Location for the Reactor Vessel Beltline and Extended Beltline Materials at SLR (72 EFPY) 3/4T R.G. 1.99, Predicted (a) Fluence(b) 3/4T RTNDT(U)(c) I (d) M ART Material Rev. 2 CF RTNDT (x 1019 n/cm2, FF(b) (°F) (°F) (°F) (°F) (°F)

Position (°F)

E > 1.0 MeV)

Beltline Intermediate Shell Plate M-605-1 1.1 74.15 1.39 1.091 30 80.9 0 17.0 34.0 144.9 with credible surveillance data(e) 2.1 102.12 1.39 1.091 30 111.4 0 8.5 17.0 158.4 Intermediate Shell Plate M-605-2 1.1 91.50 1.39 1.091 10 99.8 0 17.0 34.0 143.8 Intermediate Shell Plate M-605-3 1.1 74.15 1.39 1.091 0 80.9 0 17.0 34.0 114.9 with credible surveillance data(e) 2.1 102.12 1.39 1.091 0 111.4 0 8.5 17.0 128.4 Lower Shell Plate M-4116-1 1.1 37.00 1.38 1.090 20 40.3 0 17.0 34.0 94.3 Lower Shell Plate M-4116-2 1.1 44.00 1.38 1.090 20 48.0 0 17.0 34.0 102.0 Lower Shell Plate M-4116-3 1.1 44.00 1.38 1.090 20 48.0 0 17.0 34.0 102.0 Intermediate to Lower Shell Girth Weld Seam 101-171 1.1 40.05 1.38 1.090 -50 43.6 0 21.8 43.6 37.3 (Heat #s 83637 / 3P7317)

Intermediate Shell Axial Weld Seams 101-124A, B, & C 1.1 36.35 0.913 0.974 -56 35.4 17 17.7 49.1 28.5 (Heat # 83642)

Intermediate Shell Axial Weld Seam 101-124C Repair 1.1 34.05 0.913 0.974 -50 33.2 0 16.6 33.2 16.4 (Heat # 83637) with credible surveillance data(e) 2.1 23.55 0.913 0.974 -50 22.9 0 11.5 22.9 -4.1 Lower Shell Axial Welds Seams 101-142A, B, & C 1.1 34.05 0.908 0.973 -50 33.1 0 16.6 33.1 16.3 (Heat # 83637) with credible surveillance data(e) 2.1 23.55 0.908 0.973 -50 22.9 0 11.5 22.9 -4.2 WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 8-22 Table 8-12 Calculation of the St. Lucie Unit 2 ART Values at the 3/4T Location for the Reactor Vessel Beltline and Extended Beltline Materials at SLR (72 EFPY) (Continued) 3/4T R.G. 1.99, Predicted Fluence(b) 3/4T RTNDT(U)(c) I (d) M ART Material Rev. 2 CF(a) 19 2 (b) RTNDT (x 10 n/cm , FF (°F) (°F) (°F) (°F) (°F)

Position (°F)

E > 1.0 MeV)

Extended Beltline Upper Shell Plate M-604-1 1.1 118.00 0.0322 0.229 50 27.0 0 13.5 27.0 104.0 Upper Shell Plate M-604-2 1.1 118.25 0.0322 0.229 50 27.1 0 13.5 27.1 104.1 Upper Shell Plate M-604-3 1.1 116.60 0.0322 0.229 10 26.7 0 13.3 26.7 63.3 Upper to Intermediate Shell Girth Weld Seam 106-121 1.1 34.05 0.0371 0.248 -50 8.4 0 4.2 8.4 -33.1 (Heat # 83637) with credible surveillance data(e) 2.1 23.55 0.0371 0.248 -50 5.8 0 2.9 5.8 -38.3 Upper Shell Axial Weld Seams 101-122A & C 1.1 74.13 0.0371 0.248 -40 18.4 0 9.2 18.4 -3.2 (Heat # 5P5622)

Upper Shell Axial Weld Seams 101-122A & C 1.1 96.64 0.0371 0.248 -50 24.0 0 12.0 24.0 -2.1 (Heat # 2P5755)

Upper Shell Axial Weld Seam 101-122B 1.1 74.13 0.0371 0.248 -40 18.4 0 9.2 18.4 -3.2 (Heat # 5P5622)

Notes:

(a) Chemistry factors are taken from Table 5-5.

(b) Fluence and fluence factors taken from Table 8-4.

(c) RTNDT(U) values taken from Table 3-2.

(d) Per the guidance of RG 1.99, Revision 2 [Ref. 4]WKHEDVHPHWDO = 17°F for Position 1.1 and Position 2.1 with non-FUHGLEOHVXUYHLOODQFHGDWDDQGWKHEDVHPHWDO = 8.5°F for Position 2.1 with credible surveillance data. Also, per RG 5HYLVLRQWKHZHOGPHWDO = 28°F for Position 1.1 and Position 2.1 with non-credible VXUYHLOODQFHGDWDDQGWKHZHOGPHWDO = 14°F for Position 2.1 with credible surveillance data. +RZHYHU QHHGQRWH[FHHG 57NDT for either base metals or welds, with or without surveillance data.

(e) The credibility evaluation for the St. Lucie Unit 2 surveillance data in Appendix B determined that the St. Lucie Unit 2 surveillance data for the Intermediate Shell Plate M-605-1 and Heat

83637 are deemed credible.

WCAP-18609-NP July 2021 Revision 2

- - This record was final approved on 7/16/2021 9:37:38 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 8-23 Table 8-13 Calculation of the St. Lucie Unit 2 ART Values For the Hot Leg Nozzle Materials at SLR (72 EFPY)

Maximum R.G. 1.99, Predicted Fluence(b) RTNDT(U)(c) I (d) M ART Material Rev. 2 CF(a) FF(b) RTNDT (x 1019 n/cm2, (°F) (°F) (°F) (°F) (°F)

Position (°F)

E > 1.0 MeV)

Hot Leg Nozzle A 1.1 89.92 0.0103 0.112 -30 10.1 0 5.0 10.1 -9.9 M-4103-2 Hot Leg Nozzle B 1.1 90.36 0.0103 0.112 -20 10.1 0 5.1 10.1 0.2 M-4103-1 Hot Leg Nozzle to Shell Weld Seam 105-121A 1.1 63.70 0.0103 0.112 -60 7.1 0 3.6 7.1 -45.7 (Heat # 4P6519)

Hot Leg Nozzle to Shell Weld Seam 105-121B 1.1 68.00 0.0103 0.112 -60 7.6 0 3.8 7.6 -44.8 (Various SMAWs)

Notes:

(a) Chemistry factors are taken from Table 5-5.

(b) Fluence and fluence factors taken from Table 8-4.

(c) RTNDT(U) values taken from Table 3-2.

(d) Per the guidance of Regulatory Guide 1.99, Revision 2 [Ref. 4]WKHEDVHPHWDO = 17°F for Position 1.1 and Position 2.1 with non-FUHGLEOHVXUYHLOODQFHGDWDDQGWKHEDVHPHWDO = 8.5°F for Position 2.1 with credible surveillance data. Also, per ReguODWRU\*XLGH5HYLVLRQWKHZHOGPHWDO = 28°F for Position 1.1 and Position 2.1 with non-credible surveillance data, and WKHZHOGPHWDO = 14°F for Position 2.1 with credible surveillance data. +RZHYHU QHHGQRWH[FHHG 57NDT for either base metals or welds, with or without surveillance data.

WCAP-18609-NP July 2021 Revision 2

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St. Lucie Nuclear Plant Units 1 and 2 Dockets 50-335 and 50-389 L-2021-192 Enclosure 4 Enclosure 4 Non-proprietary Reference Documents and Redacted Versions of Proprietary Reference Documents (Public Version)

Attachment 5 Westinghouse Report LTR-SDA-II-20-32-NP, Revision 3, St. Lucie Units 1 & 2 Subsequent License Renewal: 80-Year Projected Transient Cycles, July 15, 2021 (14 Total Pages, including cover sheets)

St. Lucie Nuclear Plant Units 1 and 2 Dockets 50-335 and 50-389 L-2021-192 Enclosure 4 Enclosure 4 Non-proprietary Reference Documents and Redacted Versions of Proprietary Reference Documents (Public Version)

Attachment 6 Westinghouse Report LTR-SDA-II-20-31-NP, Rev. 3, St. Lucie Units 1 & 2 Subsequent License Renewal:

Primary Equipment and Piping Environmentally Assisted Fatigue Evaluations, September 14, 2021 (24 Total Pages, including cover sheets)

Westinghouse Non-Proprietary Class 3 LTR-SDA-II-20-31-NP, Rev.

6HSWHPEHU 14, 2021 Foreword:

This document contains Westinghouse Electric Company LLC and Flowserve Corporation proprietary information and data. The proprietary information has been identified in brackets with coding (w) for Westinghouse and (fs) for Flowserve. In addition, coding (a,c,e) associated with the brackets sets forth the basis on which information is considered proprietary. These code letters are listed with their meanings in BMS-LGL-84, and are defined as follows:

a. The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where the prevention of its use by any competitors without license from Westinghouse and Flowserve constitutes a competitive economic advantage over other companies.

c. The information, if used by a competitor, would reduce the competitors expenditure of resources or improve the competitors advantage in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product.

e. The information reveals aspects of past, present, or future development plans and programs of potential commercial value to Westinghouse and Flowserve.

The proprietary information and data contained within the brackets of this document were obtained at considerable Westinghouse and Flowserve expense and its release could seriously affect competitive positions. This information is to be withheld from public disclosure in accordance with the Rules of Practice 10 CFR 2.390 and the information presented herein is to be safeguarded in accordance with 10 CFR 2.390.

Withholding of this information does not affect the public interest.

This information has been provided for your internal use only and should not be released to persons or organizations outside the Directorate of Regulation and the ACRS (Advisory Committee on Reactor Safeguards) without the express written approval of Westinghouse and Flowserve. Should it become necessary to release this information to such persons as part of the review procedure, please contact Westinghouse and Flowserve, which will make the necessary arrangements required to protect proprietary interests.

The proprietary information in brackets has been deleted in this non-proprietary version. The deleted information is provided in the proprietary version of this report (LTR-SDA-II-20-31-P).

2

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Westinghouse Non-Proprietary Class 3 LTR-SDA-II-20-31-NP, Rev.

6HSWHPEHU14, 2021 1.0 Introduction and Summary of Results The St. Lucie Unit 1 and Unit 2 Subsequent License Renewal (SLR) program is intended to extend the operation license of these plants from 60 years to 80 years. Nuclear Regulatory Commission (NRC) guidance on the content of SLR applications is provided in NUREG-2191 [2.1] and NUREG-2192 [2.2].

Specifically, Section 4.3 of NUREG-2192 [2.2] provides the following guidance related to addressing the effects of a reactor water environment:

Applicants should include Cumulative Usage Factor including Reactor Water Environmental Effects (CUFen) calculations for the limiting component locations exposed to the reactor water environment.

This sample set includes the locations identified in NUREG/CR-6260 [2.3] and additional plant-specific component locations in the reactor coolant pressure boundary if they may be more limiting than those considered in NUREG/CR-6260. Plant-specific justification can be provided to demonstrate that calculations for the NUREG/CR-6260 locations do not need to be included. Environmental effects on fatigue for these critical components may be evaluated using the guidance in RG 1.207, Revision 1

[2.4]; NUREG/CR-6909, Revision 0 [2.5] (with average temperature used consistent with the clarification that was added to NUREG/CR-6909, Revision 1 [2.6]); or other subsequent NRC-endorsed alternatives.

To address the concern that there may be additional component locations more limiting than those considered in NUREG/CR-6260 [2.3], Westinghouse performed an environmentally assisted fatigue (EAF) screening evaluation in CN-SDA-II-20-022 [3] for the Safety Class 1 reactor coolant pressure boundary components in major equipment and piping that meet the six criteria for time-limited aging analyses (TLAAs) in 10 CFR 54.3(a), including the locations listed in NUREG/CR-6260 [2.3]. The goal of the EAF screening evaluation was to eliminate locations for which environmental conditions are not a concern and provide a list of sentinel locations, which supplement those identified in NUREG/CR-6260 [2.3], to be addressed through separate aging management plans, such as EAF evaluations or inspections supported by fracture evaluations. This letter report summarizes the results of EAF evaluations performed for the following sentinel locations identified in CN-SDA-II-20-022 [3]. The remaining sentinel locations from CN-SDA-II-20-022 [3] are being evaluated by other vendors.

x Units 1 & 2 Reactor Vessel (RV) Outlet Nozzle x Units 1 & 2 RV Inlet Nozzle x Units 1 & 2 RV Wall Transition x Unit 2 Control Element Drive Mechanism (CEDM) Upper Housing Tube x Unit 2 CEDM Upper Housing Lower End Fitting x Unit 2 CEDM Motor Housing Lower End Fitting x Units 1 & 2 Reactor Coolant Pump (RCP) Cover x Units 1 & 2 Reactor Coolant Loop (RCL) Suction Leg RCP Suction Nozzle x Units 1 & 2 RCL Cold Leg RCP Discharge Nozzle x Units 1 & 2 RCL Cold Leg Resistance Temperature Detector (RTD) Nozzle 3

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6HSWHPEHU 14, 2021 x Units 1 and 2 RCL Cold Leg Spray Nozzle (Leading Carbon Steel (CS)/Low Alloy Steel (LAS) and Stainless Steel (SS) Locations) x Unit 1 4 x 4 x 4 Main Spray/Auxiliary Spray Line Tee x Unit 2 4 x 4 x 4 Main Spray Line Tee x Unit 2 Pressurizer (PZR) Relief Valve Piping 4 x 4 x 4 Tee x Units 1 & 2 RCL Letdown and Suction Leg Drain Nozzle (Leading CS/LAS and SS Locations) x Unit 1 RCL Hot Leg Drain Nozzle (Leading SS Location) x Unit 1 Loop 1B1 Charging Line Socket Weld at Elbow x Unit 2 Loop 2A2 Charging Line Socket Welded Coupling x Units 1 & 2 Cold Leg Safety Injection Nozzle (Leading CS/LAS and SS Locations) x Unit 1 Loop 1B1 Safety Injection Line V3237 Valve Transition Weld x Unit 1 Loop 1B1 Safety Injection Line 12 x 1 Branch x Unit 2 Loop 2A1 Safety Injection Line V3227 Valve Transition Weld x Unit 2 Loop 2A1 Safety Injection Line 12 x 12 x 6 Tee x Unit 1 Shutdown Cooling Line 12 x 2 Branch x Unit 1 Shutdown Cooling Line 10 x 1 Branch 4

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Westinghouse Non-Proprietary Class 3 LTR-SDA-II-20-31-NP, Rev.

6HSWHPEHU 14, 2021 2.0 Environmentally Assisted Fatigue Evaluation Methodology In general, the EAF evaluations of the sentinel locations presented in this report can be categorized into the following groups:

1. Simplified EAF Evaluations

2. Comparative EAF Evaluations

3. Detailed EAF Evaluations Each of these EAF evaluation groups are described in Sections 2.1 to 2.3. The general method to calculate the Fen factors is described in Sections 2.4 to 2.7. The transient cycles considered in the EAF evaluations are described in Section 2.8.

2.1 Simplified EAF Evaluations (Group 1)

The simplified EAF evaluations utilize the fatigue results from the existing analysis of record (AOR) along with the guidelines in RG 1.207 [2.4] and the Fen equations in NUREG/CR-6909 [2.6] to calculate a CUFen less than 1.0. The process to perform this evaluation is summarized as follows:

1. A detailed review of the fatigue AOR is performed to determine the controlling regions based on stress results and materials of construction.

2. The design fatigue curves in Section A.2.1 of NUREG/CR-6909 [2.6] are applied to the fatigue results from the AOR to derive a cumulative usage factor (CUF).

3. The Fen equations in Section A.2 of NUREG/CR-6909 [2.6] are applied to the fatigue results from Step 2 to derive a CUFen.

The goal of the simplified EAF evaluations is to calculate a CUFen below 1.0 through typical linear elastic fatigue analysis techniques. Conservatisms in the stress and fatigue analyses in the AORs may be identified and removed in the CUF calculations. Conservatism reduction methods may include the use of 80-year projected cycles or reduced stress magnitudes based on actual transient severities.

The CUFen is initially calculated by applying conservative constant Fen values to the CUF or partial fatigue usage factors of individual fatigue pairs. For any component locations that cannot accept this conservative method (i.e., CUFen > 1.0), strain rate dependent Fen values may be calculated for significant fatigue pairs using the modified rate approach described in Section 4.4 of NUREG/CR-6909 [2.6].

2.2 Comparative EAF Evaluations (Group 2)

The comparative EAF evaluations compare sentinel locations across transient sections to demonstrate that a sentinel location is less limiting than a location from NUREG/CR-6260 [2.3] or another location for which a more detailed EAF evaluation will be performed. This comparison incorporates critical analysis items such as controlling thermal transient severity, transient occurrences, stress algorithms, and analysis methods used to evaluate components of interest.

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Westinghouse Non-Proprietary Class 3 LTR-SDA-II-20-31-NP, Rev.

6HSWHPEHU 14, 2021 2.3 Detailed EAF Evaluations (Group 3)

The general process to perform the detailed EAF evaluations is similar to the simplified EAF evaluations in described in Section 2.1 except that a detailed finite element model based on plant-specific geometry is utilized to support the evaluation. A finite element analysis is performed to generate transient stress time histories that will be used to determine the stress peaks and valleys for the fatigue evaluation, as well as the corresponding strain rates and temperature information needed for the Fen calculations. The stress peaks and valleys and applicable Fen factors will be used to determine the CUFen for the limiting locations.

2.4 Fen Equations The materials for the sentinel locations in the EAF evaluations include carbon steel (CS), low alloy steel (LAS), stainless steel (SS), and Ni-Cr-Fe alloy (NiA). The Fen for each of these materials was calculated using the equations in Section A.2 of NUREG/CR-6909 [2.6], which are presented in Equation 2-1 to Equation 2-3.

CS and LAS:

Fen = exp(0.003 - 0.031 *) S* T* O* 2-1 Where:

S* = 2.0 + 98 S 6ZW

S* = 3.47 6!ZW

6 6XOIXU&RQWHQW ZW

T* = 0.395 T < 150°C (302°F)

T* = (T - 75)/190 & ) 7& )

T = Service Temperature (°C) for calculation of T*

O* = 1.49 DO < 0.04 ppm O* = ln(DO/0.009) SSP'2SSP O* = 4.02 DO > 0.5 ppm DO = Dissolved Oxygen Content (ppm)

= 0 !V

= ln( 2.2) V V

= ln(0.00042.2) V

6WUDLQ5DWH V 6

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Westinghouse Non-Proprietary Class 3 LTR-SDA-II-20-31-NP, Rev.

6HSWHPEHU 14, 2021 Wrought and Cast Austenitic SS:

Fen = exp(- T*

O*) 2-2 Where:

T* = 0 T < 100°C (212°F)

T* = (T - 100)/250 100°C ) 7& )

T = Service Temperature (°C)

= 0 !V

= ln( 7.0) V V

= ln(0.00047.0) V

6WUDLQ5DWH V All wrought and cast SSs and heat treatments and SS weld metals:

O* = 0.29 DO < 0.1 ppm Sensitized high-carbon wrought and cast SSs:

O* = 0.29 '2SSP All wrought SSs except sensitized high-carbon SSs:

O* = 0.14 '2SSP DO = Dissolved Oxygen Content (ppm)

NiA (except Inconel 718):

Fen = exp(- T*

O*) 2-3 Where:

T* = 0 T < 50°C (122°F)

T* = (T - 50)/275 & ) 7& )

T = Service Temperature (°C)

= 0 !V

= ln( 5.0) V V

= ln(0.00045.0) V

6WUDLQ5DWH V O* = 0.06 1:&%:5ZDWHU LH'2SSP PWR or HWC BWR water (i.e., DO < 0.1 O* = 0.14 ppm)

DO = Dissolved Oxygen Content (ppm) 7

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Westinghouse Non-Proprietary Class 3 LTR-SDA-II-20-31-NP, Rev.

6HSWHPEHU 14, 2021 2.5 Maximum Fen Values

[

] w-a,c,e

[

] w-a,c,e 8

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Westinghouse Non-Proprietary Class 3 LTR-SDA-II-20-31-NP, Rev.

6HSWHPEHU 14, 2021 2.6 Dissolved Oxygen Content Per PSLWEC-21-0009 [4], the RCS DO content is controlled using 0-COP-05.04 [5]. When the RCS temperature is above 250°F, the DO content in the RCS is maintained below 5 ppb (0.005 ppm) in Modes 1 and 2 and 10 ppb (0.01 ppm) in Modes 3 and 4 as discussed in 0-COP-05.04 [5] and supported by data from 2010 to 2020 (contained in the U1 RCS DO 10 years.xlsx and U2 RCS DO 10 years.xlsx spreadsheets attached to PSLWEC-21-0009 [4]). When the RCS temperature is below 250°F, the DO content may exceed 10 ppb (0.01 ppm). Therefore, the following assumptions regarding the DO content are made in the EAF screening evaluation:

x When the RCS temperature is greater than 250°F, a constant DO content of 0.01 ppm is assumed.

x When the RCS temperature is less than or equal to 250°F, the DO content that maximizes the Fen is assumed.

2.7 Maximum Temperature for Fen Equations Per Section A.2 of NUREG/CR-6909 [2.6], a maximum temperature limit of 325°C (617°F) is specified for the Fen equations as a reasonable bound to cover most anticipated light water reactor operating conditions when considering the use of average temperature. In cases where transient temperatures exceed 325°C (617°F), the guidelines in NUREG/CR-6909 [2.6] state that the analyst shall document the exceedance and justify its use in the Fen equations. The EAF evaluations assumed that [

] w-a,c,e 2.8 Transients The design transients and cycles in the AORs were originally based on a 40-year operating period. However, the transient cycles analyzed herein must be applicable for an 80-year period of operation to support the St.

Lucie Units 1 & 2 SLR program. 80-year transient cycle projections were developed in [6] for the transients included in the current St. Lucie Fatigue Monitoring Program as well as additional transients that were identified as fatigue-sensitive for the SLR TLAA evaluations. For transients where 80-year cycle projections were developed in [6], the design transients from the AORs remain bounding for an 80-year period of operation.

The design transient cycles from the AORs were initially considered in the EAF evaluations. However, the transient cycles considered in the EAF evaluations were reduced from those considered in the AOR for some locations to obtain a CUFen less than 1.0. To inform potential changes to plant documents, Table 2-1 lists the minimum number of cycles analyzed for any transients where cycles were reduced in the EAF evaluations. Note that the reduced cycles in Table 2-1 bound the 80-year projected cycles developed in [6].

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Westinghouse Non-Proprietary Class 3 LTR-SDA-II-20-31-NP, Rev.

6HSWHPEHU 14, 2021 Table 2-1: Summary of Cycle Reductions for EAF Evaluations 80-Year Projected Minimum Reduced Margin (3)

Transient Cycles (1) Cycles (2)

Unit 1 Unit 2 Unit 1 Unit 2 Unit 1 Unit 2 Reactor Trip 106 72 142 95

Plant Heatup 143 124 193 245

Plant Cooldown 141 123 192 245

Primary Leak Test 2 5 5 150

Plant Loading 1290 1284 6500 6000

Plant Unloading 1290 1284 6500 6000

Purification and 3504 1700 8000 7000

Boric Acid Dilution Notes:

(1) The 80-year projected cycles are provided in Section 2.0 of [6].

(2) The minimum reduced cycles reflect the minimum number of cycles analyzed for any transients where cycles were reduced from the design cycles to obtain a CUFen less than 1.0.

(3) The margin was calculated as follows:

Reduced Cycles Projected Cycles Margin =

Reduced Cycles 3.0 Environmentally Assisted Fatigue Evaluation Results The results of the EAF evaluations are presented in Table 3-1 and Table 3-2 for each of the sentinel equipment and piping locations listed in Section 1.0. These tables include the original AOR CUF, the reduced CUF for SLR, the Fen and CUFen, and a summary of the conservatisms removed from the AOR.

The EAF evaluations were performed using the guidelines in [2.4] and the Fen equations in [2.6]. The transient cycles considered in the EAF evaluations are bounding for an 80-year period of operation. The CUFen for each location is less than the ASME Code limit of 1.0 and is therefore acceptable.

As described in Section 2.8, the transient cycles considered in the EAF evaluations were reduced from those considered in the AOR for some locations to obtain a CUFen less than 1.0. Changes to plant documents (such as cycle counting procedures, FSAR, etc.) may be required to address the reduced transient cycles considered in these EAF evaluations to support the SLR program.

The CUFen values for some locations in Table 3-1 and Table 3-2 are close to the ASME Code limit of 1.0.

However, the CUFen calculations included sufficient conservatism in both the analyzed transient cycles and Fen values. As shown in Table 2-1WKHDQDO\]HGWUDQVLHQWF\FOHVLQFOXGHDPDUJLQRIDWOHDVWDERYHWKH

80-year projected cycles. In addition, the Fen values were calculated based on enveloping temperature, strain rate, dissolved oxygen content, and sulfur content values.

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6HSWHPEHU 14, 2021 Table 3-1: Summary of EAF Results for Equipment Sentinel Locations CUF EAF Line / Component / Material SLR CUF Conservatism Reduction Fen (2) CUFen Evaluation Reference System Location Category AOR (1) SLR Summary Group No conservatism reduction was required.

The LAS ASME design fatigue curve considered in the AOR is more Outlet Nozzles LAS [ ]w-a,c,e [ ]w-a,c,e [ ]w-a,c,e 0.494 [ ]w-a,c,e [7] conservative than the fatigue curve in Section A.2.1 of [2.6]. The design cycles from the AOR were considered for all transients.

No conservatism reduction was required.

The LAS ASME design fatigue curve considered in the AOR is more RV Inlet Nozzles LAS [ ]w-a,c,e [ ]w-a,c,e [ ]w-a,c,e 0.311 [ ]w-a,c,e [7] conservative than the fatigue curve in (Unit 1)

Section A.2.1 of [2.6]. The design cycles from the AOR were considered for all transients.

No conservatism reduction was required.

The LAS ASME design fatigue curve considered in the AOR is more Vessel Wall LAS [ ]w-a,c,e [ ]w-a,c,e [ ]w-a,c,e 0.036 [ ]w-a,c,e [7] conservative than the fatigue curve in Transition (3)

Section A.2.1 of [2.6]. The design cycles from the AOR were considered for all transients.

The LAS design fatigue curve in Section A.2.1 of [2.6] was applied. The cycles were reduced for the following transients:

x Heatup: reduced from 500 cycles to Outlet Nozzles LAS [ ]w-a,c,e [ ]w-a,c,e [ ]w-a,c,e 0.916 [ ]w-a,c,e [7] 400 cycles x Cooldown: reduced from 500 cycles RV to 400 cycles (Unit 2)

The design cycles from the AOR were considered for all other transients.

The LAS design fatigue curve in Section A.2.1 of [2.6] was applied. The design Inlet Nozzles LAS [ ]w-a,c,e [ ]w-a,c,e [ ]w-a,c,e 0.621 [ ]w-a,c,e [7]

cycles from the AOR were considered for all transients.

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Westinghouse Non-Proprietary Class 3 LTR-SDA-II-20-31-NP, Rev.

6HSWHPEHU 14, 2021 CUF EAF Line / Component / Material SLR CUF Conservatism Reduction Fen (2) CUFen Evaluation Reference System Location Category AOR (1) SLR Summary Group No conservatism reduction was required.

The LAS ASME design fatigue curve considered in the AOR is more Vessel Wall LAS [ ]w-a,c,e [ ]w-a,c,e [ ]w-a,c,e 0.025 [ ]w-a,c,e [7] conservative than the fatigue curve in Transition (3)

Section A.2.1 of [2.6]. The design cycles from the AOR were considered for all transients.

The SS design fatigue curve in Section A.2.1 of [2.6] was applied. Temperature dependent Fen values were calculated for significant fatigue pairs. Refinements Upper were made regarding the interaction of Housing - stress cycles between different transients Tube and SS [ ]w-a,c,e [ ]w-a,c,e [ ]w-a,c,e 0.991 [ ]w-a,c,e [8] when forming fatigue pairs. The cycles Lower End were reduced for the following Fitting transients:

x Reactor Trip: reduced from 480 to 95 cycles The design cycles from the AOR were CEDM considered for all other transients.

(Unit 2) The Ni-Cr-Fe alloy (NiA) design fatigue curve in Section A.2.1 of [2.6] was applied. Temperature dependent Fen values were calculated for significant fatigue pairs. Refinements were made Motor regarding the interaction of stress cycles Housing -

NiA [ ]w-a,c,e [ ]w-a,c,e [ ]w-a,c,e 0.997 [ ]w-a,c,e [8] between different transients when Lower End forming fatigue pairs. The cycles were Fitting reduced for the following transients:

x Plant Unloading: reduced from 15000 to 13400 cycles The design cycles from the AOR were considered for all other transients.

The SS design fatigue curve in Section RCP Pump Cover SS [ ]fs-a,c,e [ ]w-a,c,e [ ]w-a,c,e 0.991 [ ]w-a,c,e [8]

A.2.1 of [2.6] was applied. Temperature 12

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Westinghouse Non-Proprietary Class 3 LTR-SDA-II-20-31-NP, Rev.

6HSWHPEHU 14, 2021 CUF EAF Line / Component / Material SLR CUF Conservatism Reduction Fen (2) CUFen Evaluation Reference System Location Category AOR (1) SLR Summary Group (Units 1 & dependent Fen values were calculated for

2) significant fatigue pairs. The cycles were reduced for the following transients:

x Heatup and Cooldown: reduced from 500 to 245 cycles The design cycles from the AOR were considered for all other transients.

Notes:

(1) The AOR CUFs are listed in Section 2.0 of [3].

(2) This Fen value represents a weighted average value, defined as the CUFen divided by the SLR CUF. The actual Fen values may vary between individual fatigue pairs.

(3) CUFen values for both the RV lower shell-to-bottom head transition and the upper shell transition were calculated. The reported value reflects the higher value for the upper shell transition.

Table 3-2: Summary of EAF Results for Piping Sentinel Locations CUF EAF Line / Component / Material SLR CUF Conservatism Reduction Fen (2) CUFen Evaluation Reference System Location Category AOR (1)

SLR Summary Group The SS design fatigue curve in Section Suction Leg -

w-a,c,e w-a,c,e w-a,c,e w-a,c,e A.2.1 of [2.6] was applied. The design RCP Suction SS [ ] [ ] [ ] 0.730 [ ] [8]

cycles from the AOR were considered for Nozzle all transients.

Cold Leg - The SS design fatigue curve in Section RCP A.2.1 of [2.6] was applied. The design RCL SS [ ]w-a,c,e ]w-a,c,e [ ]w-a,c,e 0.090 [ ]w-a,c,e [8]

Discharge cycles from the AOR were considered for (Units 1 &

Nozzle all transients.

2)

The NiA design fatigue curve in Section A.2.1 of [2.6] was applied. Strain rate Cold Leg - dependent Fen values were calculated for NiA [ ]w-a,c,e [ ]w-a,c,e [ ]w-a,c,e 0.498 [ ]w-a,c,e [8]

RTD Nozzle significant fatigue pairs. The design cycles from the AOR were considered for all transients.

Spray and Cold Leg The SS design fatigue curve in Section SS [ ]w-a,c,e [ ]w-a,c,e [ ]w-a,c,e 0.512 [ ]w-a,c,e [8]

Aux. Spray Spray Nozzle A.2.1 of [2.6] was applied. Refinements 13

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6HSWHPEHU 14, 2021 CUF EAF Line / Component / Material SLR CUF Conservatism Reduction Fen (2) CUFen Evaluation Reference System Location Category AOR (1) SLR Summary Group (Unit 1) (Leading SS were made regarding the interaction of Location) stress cycles between different transients when forming fatigue pairs. The design cycles from the AOR were considered for all transients.

The CS design fatigue curve in Section Cold Leg A.2.1 of [2.6] was applied. Refinements Spray Nozzle were made regarding the interaction of (Leading CS/LAS [ ]w-a,c,e [ ]w-a,c,e [ ]w-a,c,e 0.157 [ ]w-a,c,e [8] stress cycles between different transients CS/LAS when forming fatigue pairs. The design Location) cycles from the AOR were considered for all transients.

A comparative evaluation was performed 4 x 4 x 4 to demonstrate that the Unit 1 PZR spray Main nozzle (leading SS location) is more SS [ ]w-a,c,e --- --- --- [ ]w-a,c,e [8]

Spray/Auxiliar limiting with respect to EAF than the Unit y Spray Tee 1 4 x 4 x 4 main spray/auxiliary spray tee.

The SS design fatigue curve in Section A.2.1 of [2.6] was applied. Refinements Cold Leg were made regarding the interaction of Spray Nozzle SS [ ]w-a,c,e [ ]w-a,c,e [ ]w-a,c,e 0.512 [ ]w-a,c,e [8] stress cycles between different transients (Leading SS when forming fatigue pairs. The design Location) cycles from the AOR were considered for all transients.

Spray and The CS design fatigue curve in Section Aux. Spray Cold Leg A.2.1 of [2.6] was applied. Refinements (Unit 2) Spray Nozzle were made regarding the interaction of (Leading CS [ ]w-a,c,e [ ]w-a,c,e [ ]w-a,c,e 0.157 [ ]w-a,c,e [8] stress cycles between different transients CS/LAS when forming fatigue pairs. The design Location) cycles from the AOR were considered for all transients.

4 x 4 x 4 A comparative evaluation was performed Main SS [ ]w-a,c,e --- --- --- [ ]w-a,c,e [8] to demonstrate that the Unit 2 4 x 2 Spray Tee auxiliary spray reducer is more limiting 14

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Westinghouse Non-Proprietary Class 3 LTR-SDA-II-20-31-NP, Rev.

6HSWHPEHU 14, 2021 CUF EAF Line / Component / Material SLR CUF Conservatism Reduction Fen (2) CUFen Evaluation Reference System Location Category AOR (1) SLR Summary Group with respect to EAF than the Unit 2 4 x 4 x 4 main spray tee.

A comparative evaluation was performed PZR Relief to demonstrate that the Unit 2 4 x 4 x 4 Valve 4 x 4 x 4 SS 0.053 --- --- --- [ ]w-a,c,e [8] main spray tee is more limiting with Piping Tee respect to EAF than the Unit 2 4 x 4 x (Unit 2) 4 PZR relief valve piping tee.

The CS design fatigue curve in Section A.2.1 of [2.6] was applied. Strain rate dependent Fen values were calculated for Suction Leg significant fatigue pairs. Emergency and Drain Nozzle faulted condition transients were excluded (Leading CS [ ]w-a,c,e [ ]w-a,c,e [ ]w-a,c,e 0.170 [ ]w-a,c,e [8] from the fatigue evaluation. Refinements CS/LAS were made regarding the interaction of Location) stress cycles between different transients when forming fatigue pairs. The design cycles from the AOR were considered for all transients.

The SS design fatigue curve in Section Letdown A.2.1 of [2.6] was applied. Temperature and and strain rate dependent Fen values were Suction calculated for significant fatigue pairs.

Leg Drain Emergency and faulted condition (Unit 1) transients were excluded from the fatigue evaluation. Refinements were made Suction Leg regarding the interaction of stress cycles Drain Nozzle between different transients when forming SS [ ]w-a,c,e [ ]w-a,c,e [ ]w-a,c,e 0.902 [ ]w-a,c,e [8]

(Leading SS fatigue pairs. The cycles were reduced for Location) the following transients:

x Heatup: reduced from 500 to 130 cycles x Cooldown: reduced from 500 to 130 cycles x Reactor Trip: reduced from 400 to 95 cycles 15

- - This record was final approved on 9/15/2021 7:17:29 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 LTR-SDA-II-20-31-NP, Rev.

6HSWHPEHU 14, 2021 CUF EAF Line / Component / Material SLR CUF Conservatism Reduction Fen (2) CUFen Evaluation Reference System Location Category AOR (1) SLR Summary Group x Leak Test: reduced from 200 to 5 cycles Since the safe end was replaced in May 2010 per ISI-PSL-1-2010 [11], this location would only experience a portion of the cycles that occur for an 80-year plant life. To inform potential changes to plant documents with cycle limits based on an 80-year plant life, an equivalent number of 80-year cycles were calculated as follows by adding the cycles from the 2009 cycle counting report [13]:

x Heatup: 193 cycles x Cooldown: 192 cycles x Reactor Trip: 142 cycles x Leak Test: 5 cycles The design cycles from the AOR were considered for all other transients.

The CS design fatigue curve in Section A.2.1 of [2.6] was applied. Strain rate dependent Fen values were calculated for Suction Leg significant fatigue pairs. Emergency and Drain Nozzle faulted condition transients were excluded (Leading CS [ ]w-a,c,e [ ]w-a,c,e [ ]w-a,c,e 0.180 [ ]w-a,c,e [8] from the fatigue evaluation. Refinements Letdown CS/LAS were made regarding the interaction of and Location) stress cycles between different transients Suction when forming fatigue pairs. The design Leg Drain cycles from the AOR were considered for (Unit 2) all transients.

The SS design fatigue curve in Section Suction Leg A.2.1 of [2.6] was applied. Temperature Drain Nozzle and strain rate dependent Fen values were SS [ ]w-a,c,e [ ]w-a,c,e [ ]w-a,c,e 0.909 [ ]w-a,c,e [8]

(Leading SS calculated for significant fatigue pairs.

Location) Emergency and faulted condition transients were excluded from the fatigue 16

- - This record was final approved on 9/15/2021 7:17:29 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 LTR-SDA-II-20-31-NP, Rev.

6HSWHPEHU 14, 2021 CUF EAF Line / Component / Material SLR CUF Conservatism Reduction Fen (2) CUFen Evaluation Reference System Location Category AOR (1) SLR Summary Group evaluation. Refinements were made regarding the interaction of stress cycles between different transients when forming fatigue pairs. The cycles were reduced for the following transients:

x Heatup: reduced from 500 to 375 cycles x Cooldown: reduced from 500 to 375 cycles x Leak Test: reduced from 200 to 150 cycles The design cycles from the AOR were considered for all other transients.

The SS design fatigue curve in Section Hot Leg Drain A.2.1 of [2.6] was applied. Temperature Hot Leg Nozzle dependent Fen values were calculated for Drain SS [ ]w-a,c,e [ ]w-a,c,e [ ]w-a,c,e 0.976 [ ]w-a,c,e [8]

(Leading SS significant fatigue pairs. The design cycles (Unit 1)

Location) from the AOR were considered for all transients.

A finite element analysis was performed to refine the derived transient stresses and the corresponding CUF value. The SS design fatigue curve in Section A.2.1 of

[2.6] was applied. Temperature dependent Fen values were calculated for significant fatigue pairs. The cycles were reduced for Socket Weld at the following transients:

Charging Elbow (Loop SS [ ]w-a,c,e [ ]w-a,c,e [ ]w-a,c,e 0.941 [ ]w-a,c,e [9]

(Unit 1) x Plant Loading: reduced from 15000 to 1B1) 6500 cycles x Plant Unloading: reduced from 15000 to 6500 cycles x Purification and Boric Acid Dilution:

reduced from 9000 to 8000 cycles The cycles for the Loss of Letdown transient were increased from 50 to 500 17

- - This record was final approved on 9/15/2021 7:17:29 AM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 LTR-SDA-II-20-31-NP, Rev.

6HSWHPEHU 14, 2021 CUF EAF Line / Component / Material SLR CUF Conservatism Reduction Fen (2) CUFen Evaluation Reference System Location Category AOR (1) SLR Summary Group cycles based on the 80-year transient cycle projections performed in CN-SDA-II 026 [6] and the design cycle fatigue reconciliation performed in CN-SDA 20 [15]. The design cycles from the AOR were considered for all other transients.

A finite element analysis was performed to refine the derived transient stresses and the corresponding CUF value. The SS design fatigue curve in Section A.2.1 of

[2.6] was applied. Temperature dependent Fen values were calculated for significant fatigue pairs. The cycles were reduced for the following transients:

x Plant Loading: reduced from 15000 to 6000 cycles Socket Welded Charging x Plant Unloading: reduced from 15000 Coupling SS [ ]w-a,c,e [ ]w-a,c,e [ ]w-a,c,e 0.975 [ ]w-a,c,e [9]

(Unit 2) to 6000 cycles (Loop 2A2) x Purification and Boric Acid Dilution:

reduced from 24000 to 7000 cycles The cycles for the Loss of Letdown transient were increased from 50 to 500 cycles based on the 80-year transient cycle projections performed in CN-SDA-II 026 [6] and the design cycle fatigue reconciliation performed in CN-SDA 20 [15]. The design cycles from the AOR were considered for all other transients.

Cold Leg Safety The LAS design fatigue curve in Section Safety Injection A.2.1 of [2.6] was applied. The design Injection Nozzle LAS [ ]w-a,c,e [ ]w-a,c,e [ ]w-a,c,e 0.653 [ ]w-a,c,e [7]

cycles from the AOR were considered for (Unit 1) (Leading all transients.

CS/LAS Location) 18

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Westinghouse Non-Proprietary Class 3 LTR-SDA-II-20-31-NP, Rev.

6HSWHPEHU 14, 2021 CUF EAF Line / Component / Material SLR CUF Conservatism Reduction Fen (2) CUFen Evaluation Reference System Location Category AOR (1) SLR Summary Group Cold Leg Safety The SS design fatigue curve in Section Injection A.2.1 of [2.6] was applied. The design SS [ ]w-a,c,e [ ]w-a,c,e [ ]w-a,c,e 0.243 [ ]w-a,c,e [7]

Nozzle cycles from the AOR were considered for (Leading SS all transients.

Location)

The SS design fatigue curve in Section V3237 Valve A.2.1 of [2.6] was applied. Temperature Transition dependent Fen values were calculated for SS 0.0622 [ ]w-a,c,e [ ]w-a,c,e 0.939 [ ]w-a,c,e [8]

Weld (Loop significant fatigue pairs. The design cycles 1B1) from the AOR were considered for all transients.

The SS design fatigue curve in Section A.2.1 of [2.6] was applied. Temperature dependent Fen values were calculated for 12 x 1 significant fatigue pairs. The cycles were Branch (Loop SS 0.0702 [ ]w-a,c,e [ ]w-a,c,e 0.953 [ ]w-a,c,e [8] reduced for the following transients:

1B1) x Cooldown: reduced from 500 to 450 cycles The design cycles from the AOR were considered for all other transients.

Cold Leg Safety The LAS design fatigue curve in Section Injection w-a,c,e w-a,c,e w-a,c,e w-a,c,e A.2.1 of [2.6] was applied. The design Nozzle LAS [ ] [ ] [ ] 0.872 [ ] [7]

cycles from the AOR were considered for (Leading all transients.

Safety CS/LAS Injection Location) (3)

(Unit 2) Cold Leg Safety The SS design fatigue curve in Section Injection w-a,c,e w-a,c,e w-a,c,e w-a,c,e A.2.1 of [2.6] was applied. The design SS [ ] [ ] [ ] 0.743 [ ] [7]

Nozzle cycles from the AOR were considered for (Leading SS all transients.

Location) (3) 19

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Westinghouse Non-Proprietary Class 3 LTR-SDA-II-20-31-NP, Rev.

6HSWHPEHU 14, 2021 CUF EAF Line / Component / Material SLR CUF Conservatism Reduction Fen (2) CUFen Evaluation Reference System Location Category AOR (1) SLR Summary Group A comparative evaluation was performed V3227 Valve to demonstrate that the Unit 2 12 x 12 x Transition SS 0.526 --- --- --- [ ]w-a,c,e [14] 6 tee is more limiting with respect to Weld (Loop EAF than the Unit 2 V3227 valve 2A1) transition weld.

A finite element analysis was performed to refine the derived transient stresses and the corresponding CUF value. The SS design fatigue curve in Section A.2.1 of

[2.6] was applied. Temperature dependent Fen values were calculated for significant 12 x 12 x 6 fatigue pairs. The cycles were reduced for Tee (Loop SS 0.526 [ ]w-a,c,e [ ]w-a,c,e 0.877 [ ]w-a,c,e [10]

the following transients:

2A1) x Heatup: reduced from 500 to 400 cycles x Cooldown: reduced from 500 to 400 cycles The design cycles from the AOR were considered for all other transients.

The SS design fatigue curve in Section 12 x 2 A.2.1 of [2.6] was applied. The design SS 0.0086 [ ]w-a,c,e [ ]w-a,c,e 0.384 [ ]w-a,c,e [8]

Branch cycles from the AOR were considered for Shutdown all transients.

Cooling The SS design fatigue curve in Section (Unit 1) 10 x 1 A.2.1 of [2.6] was applied. The design SS 0.0100 [ ]w-a,c,e [ ]w-a,c,e 0.384 [ ]w-a,c,e [8]

Branch cycles from the AOR were considered for all transients.

Notes:

(1) The AOR CUFs are listed in Section 2.0 of [3].

(2) This Fen value represents a weighted average value, defined as the CUFen divided by the SLR CUF. The actual Fen values may vary between individual fatigue pairs.

(3) CUFen values for configurations with and without thermal sleeves were calculated for the Unit 2 cold leg safety injection nozzles. The reported value reflects the higher value for the configuration without a thermal sleeve.

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Westinghouse Non-Proprietary Class 3 LTR-SDA-II-20-31-NP, Rev.

6HSWHPEHU 14, 2021 4.0 References

1. Westinghouse Letter, LTR-AMER-MKG-20-1686, Revision 6, Westinghouse Final Revised Offer for Subsequent License Renewal for St. Lucie Units 1 & 2.

2. NRC Documents:

2.1. NRC Document, NUREG-2191, Volumes 1 and 2, Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR) Report, July 2017 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML17187A031 and ML17187A204).

2.2. NRC Document, NUREG-2192, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants, July 2017 (ADAMS Accession No. ML17188A158).

2.3. NRC Document, NUREG/CR-6260, Application of NUREG/CR-5999 Interim Fatigue Curves to Selected Nuclear Power Plant Components, February 1995.

2.4. NRC Regulatory Guide, 1.207, Revision 1, Guidelines for Evaluating the Effects of Light-Water Reactor Water Environments in Fatigue Analyses of Metal Components, (ADAMS Accession No. ML16315A130).

2.5. NRC Document, NUREG/CR-6909, Revision 0, Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials, (ADAMS Accession No. ML070660620).

2.6. NRC Document, NUREG/CR-6909, Revision 1, Effect of LWR Water Environments on the Fatigue Life of Reactor Materials, (ADAMS Accession No. ML16319A004).

3. Westinghouse Calculation Note, CN-SDA-II-20-022, Revision 1, St. Lucie Units 1 & 2 Subsequent License Renewal: Primary Equipment and Piping Environmentally Assisted Fatigue Screening Evaluation.

4. Florida Power & Light Design Input Transmittal, PSLWEC-21-0059, Rev. 0, Design Input Transmittal for WS04 Environmentally Assisted Fatigue (EAF) to Support the St. Lucie Unit 1 and Unit 2 Subsequent License Renewal, June 4, 2021.

5. Florida Power & Light Procedure, 0-COP-05.04, Revision 119, Chemistry Department Surveillances and Parameters, August 12, 2020. (electronically attached to [4])

6. Westinghouse Calculation Note, CN-SDA-II-20-026, Revision 2, St. Lucie Unit 1 and Unit 2 80-Year Transient Cycle Projections.

7. Westinghouse Calculation Note, CN-SDA-II-20-023, Revision 0, St. Lucie Units 1 & 2 Subsequent License Renewal: Environmentally Assisted Fatigue Analysis of Reactor Vessel and Safety Injection Nozzles.

8. Westinghouse Calculation Note, CN-SDA-II-21-010, Revision 0, St. Lucie Units 1 & 2 Subsequent License Renewal: Primary Equipment and Piping Environmentally Assisted Fatigue Evaluation.

9. Westinghouse Calculation Note, CN-SDA-II-21-007, Revision 0, St. Lucie Units 1 & 2 Subsequent License Renewal: Environmentally Assisted Fatigue Evaluation for the Units 1 & 2 Charging Line Socket Weld Limiting Location.

21

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Westinghouse Non-Proprietary Class 3 LTR-SDA-II-20-31-NP, Rev.

6HSWHPEHU 14, 2021

10. Westinghouse Calculation Note, CN-SDA-II-21-009, Revision 0, St. Lucie Units 1 & 2 Subsequent License Renewal: Unit 2 Loop 2A1 Safety Injection Line 12 x 12 x 6 Tee Environmentally Assisted Fatigue Evaluation.

11. ISI-PSL-1-2010, OAR-1 Owners Activity Report for St. Lucie Nuclear Power Plant Unit 1 Refueling Outage SL-1-23, dated August 26, 2010 (ADAMS Accession No. ML102520487).

12. FPL Letter, PSLWEC-21-0014, Revision 0, Design Input Transmittal for WS08 80-Year Cycle Projections to Support the St. Lucie Unit 1 and Unit 2 Subsequent License Renewal, February 11, 2021.

13. St. Lucie Plant Procedure, 0010134, Revision 24, Component Cycles and Transients, with 2009 Appendix B, Annual Report of Cumulative Component Cycles and Transients, February 1, 2010 (electronically attached to [12] as 2009 report.pdf).

14. Westinghouse Calculation Note, CN-SDA-II-21-008, Revision 0, St. Lucie Unit 2 Subsequent License Renewal - Safety Injection Line Transients and ANSYS-WESTEMS Interface File Development.

15. Westinghouse Calculation Note, CN-SDA-21-20, Revision 0, St. Lucie Units 1 & 2 Subsequent License Renewal: Loss of Letdown Design Cycle Fatigue Reconciliation.

22

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LTR-SDA-II-20-31-NP Revision 3 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 Matthews Eric J Sep-14-2021 20:07:39 Verifier Approval Oakman Jamie L Sep-14-2021 20:15:33 Manager Approval Klimek John Sep-15-2021 07:17:29 Files approved on Sep-15-2021

- - This record was final approved on 9/15/2021 7:17:29 AM. (This statement was added by the PRIME system upon its validation)

St. Lucie Nuclear Plant Units 1 and 2 Dockets 50-335 and 50-389 L-2021-192 Enclosure 4 Enclosure 4 Non-proprietary Reference Documents and Redacted Versions of Proprietary Reference Documents (Public Version)

Attachment 7 BWXT Report MSLEF-SR-01-NP, Revision 0, St.

Lucie Unit 1 Replacement Steam Generator Environmentally Assisted Fatigue Report (Non-Proprietary), July 16, 2021 (21 Total Pages, including cover sheets)

St. Lucie Nuclear Plant Units 1 and 2 Dockets 50-335 and 50-389 L-2021-192 Enclosure 4 Enclosure 4 Non-proprietary Reference Documents and Redacted Versions of Proprietary Reference Documents (Public Version)

Attachment 8 Framatome Document No. 86-9329647-000, St. Lucie SLR CUFen Evaluations Summary - Non Proprietary, July 15, 2021 (21 Total Pages, including cover sheets)

St. Lucie Nuclear Plant Units 1 and 2 Dockets 50-335 and 50-389 L-2021-192 Enclosure 4 Enclosure 4 Non-proprietary Reference Documents and Redacted Versions of Proprietary Reference Documents (Public Version)

Attachment 9 Structural Integrity Report No. 2001262.403, Revision 0, Summary of Fatigue Usage for Charging Nozzle at St. Lucie, Units 1 and 2 for Subsequent License Renewal, June 25, 2021 (8 Total Pages, including cover sheets)

St. Lucie Nuclear Plant Units 1 and 2 Dockets 50-335 and 50-389 L-2021-192 Enclosure 4 Enclosure 4 Non-proprietary Reference Documents and Redacted Versions of Proprietary Reference Documents (Public Version)

Attachment 10 Westinghouse Report WCAP-18617-NP, Revision 1, St. Lucie Units 1 & 2 Subsequent License Renewal:

Technical Justification for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis, June 3, 2021 (69 Total Pages, including cover sheets)

St. Lucie Nuclear Plant Units 1 and 2 Dockets 50-335 and 50-389 L-2021-192 Enclosure 4 Enclosure 4 Non-proprietary Reference Documents and Redacted Versions of Proprietary Reference Documents (Public Version)

Attachment 11 Westinghouse Report LTR-SDA-20-097-NP, Revision 3, St. Lucie Units 1 & 2 Subsequent License Renewal: Alloy 600 Half Nozzle Repair Flaw Evaluation, September 15, 2021 (23 Total Pages, including cover sheets)

Westinghouse Non-Proprietary Class 3 Forward This document contains Westinghouse Electric Company LLC proprietary information and data which has been identified by brackets. Coding (a,c,e) associated with the brackets sets forth information which is considered proprietary.

The proprietary information and data contained within the brackets in this report were obtained at considerable Westinghouse expense and its release could seriously affect our competitive position.

This information is to be withheld from public disclosure in accordance with the Rules of Practice 10 CFR 2.390 and the information presented herein is safeguarded in accordance with 10 CFR 2.390. Withholding of this information does not adversely affect the public interest.

This information has been provided for your internal use only and should not be released to persons or organizations outside the Directorate of Regulation and the Advisory Committee on Reactor Safeguards (ACRS) without the express written approval of Westinghouse Electric Company LLC.

Should it become necessary to release this information to such persons as part of the review procedure, please contact Westinghouse Electric Company LLC, which will make the necessary arrangements required to protect the Companys proprietary interests.

Several locations in this topical report contain proprietary information. Proprietary information is identified and bracketed. For each of the bracketed locations, the reason for the proprietary classification is provided, using a standardized system. The proprietary brackets are labeled with three (3) different letters, a, c, and e which stand for:

a. The information reveals the distinguishing aspects of a process or component, structure, tool, method, etc. The prevention of its use by Westinghouses competitors, without license from Westinghouse, gives Westinghouse a competitive economic advantage.

c. The information, if used by a competitor, would reduce the competitors expenditure of resources or improve the competitors advantage in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product.

e. The information reveals aspects of past, present, or future Westinghouse- or customer-funded development plans and programs of potential commercial value to Westinghouse.

LTR-SDA-20-097-NP Rev. Page 2 of 21

- - This record was final approved on 9/15/2021 2:59:31 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 1.0 Introduction Small diameter Alloy 600 nozzles, such as pressurizer and Reactor Coolant System hot-leg instrumentation nozzles in Combustion Engineering (CE) designed pressurized water reactors (PWR) have developed leaks or partial through-wall cracks as a result of primary water stress corrosion cracking (PWSCC). The residual stresses imposed by the partial-penetration J welds between the nozzles and the low alloy or carbon steel pressure boundary components are the driving force for crack initiation and propagation.

St. Lucie Units 1 and 2 have experienced instances of Alloy 600 instrument nozzle leakage over the design life of the plants. Therefore, repair has been done to the alloy 600 small bore nozzles for both St. Lucie Units 1 and 2 by relocating the partial penetration attachment weld from the interior surface of the pipe or pressurizer to the outside surface of the pipe or pressurizer. Preventative repairs were also preformed to prevent the leakage. Table 1 of L-2018-027 [1] and L-2014-252 [2] summarize the alloy 600 small bore nozzle repairs for St.

Lucie Unit 1 and Unit 2, respectively. These tables are reproduced in Tables 1-1 and 1-2. Note that there are two methods of repair:

1) Half Nozzle Repair shown as Design A and Design B in Figure 1-1; In the half nozzle repair technique, the Alloy 600 nozzle is cut outboard of the partial-penetration weld and replaced with a short Alloy 690 nozzle section that is welded to the outside surface of the pressure boundary component. This repair leaves a short section of the original nozzle attached to the inside surface with the J weld.

2) Sleeve Repair shown as Design C and Design D in Figure 1-1; In the sleeve repair technique, the entire Alloy 600 nozzle is removed by machining and the bore diameter is slightly enlarged. An alloy 690 nozzle is inserted into the bore and rolled into place. A sleeve is placed between the Alloy 690 nozzle and the bore. The end of the sleeve at the interior surface of the piping or the pressurizer is either roll expanded or welded to the interior surface of the piping or pressurizer.

Alloy 600 small bore nozzle repairs were evaluated based on fracture mechanics analysis justifying the acceptability of indications in the J weld based on a conservative postulated flaw size and flaw growth considering the applicable design cycles. The evaluation was performed based on the fracture mechanics analysis provided in Combustion Engineering Owners Group (CEOG) Topical Report CE NPSD-1198-P [3] and WCAP-15973 [4 and 5].

Reports [3] and [4 and 5] provides a bounding flaw evaluation that covers all small diameter Alloy 600/690 nozzle repairs in accordance with ASME Section XI requirements. The flaw growth analysis included in the report assumes the total number of design cycles, consistent with the St. Lucie Units 1 and 2 Updated Final Safety Analysis Reports (UFSAR). The analyses associated with the flaw growth analysis of the Unit 1 and Unit 2 Alloy 600 instrument nozzle repairs was evaluated for St. Lucie Units 1 and 2 first license renewal application (see Subsection 4.6.4 of [6]) and determined to remain valid for the period of extended operation (i.e., 60 years design life), in accordance with 10 CFR 54.21(c)(1)(i).

LTR-SDA-20-097-NP Rev. Page 3 of 21

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Westinghouse Non-Proprietary Class 3 The purpose of this letter is to reassess the Alloy 600 half nozzle repairs for the St. Lucie Units 1 and 2 subsequent license renewal (SRL) including the following topics, in accordance with the request in USNRC Safety Evaluation Report (SER) related to St. Lucie Units 1 and 2 first license renewal [7]:

1. Calculate the maximum bore diameter at the end of 80 years operation considering the carbon and low-alloy steel borated water corrosion to demonstrate that the limiting allowable bore diameters are not exceeded.

2. Reconcile that the fatigue crack growth and flaw stability evaluation in WCAP-15973 [4 and 5] remain valid for the 80 years operation of St. Lucie Units 1 and 2 plants to demonstrate that the ASME code acceptance criteria for crack growth and crack stability are met for the rest of the plant life including the extended operation.

3. Provide acceptable bases and arguments for concluding that unacceptable growth of the existing flaw by stress corrosion into the vessels or piping is improbable.

Note that Alloy 600 weld pad is used at the outer wall in some repairs for St. Lucie Unit 2 as noted in Table 1-2. These Alloy 600 weld pads at the outer wall are managed by the Alloy 600 inspection program [8] and is thus outside of the evaluation scope of this calculation note.

Revision 1 of this letter incorporates the editorial comments from the customer.

Revision 2 of this letter corrects the ADAMS Access number for reference [5]. For clarity, a separate reference [5.a] is added for the US NRC Safety Evaluation Report with its own ADAMS Access number.

The purpose of Revision 3 of this letter is to remove the export control statement, which does not apply to non-proprietary documents. The changes are marked using a change bar at the left side of the page.

Figure 1-1 Nozzle Repair Designs LTR-SDA-20-097-NP Rev. 3 Page 4 of 21

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Westinghouse Non-Proprietary Class 3 Table 1-1 St. Lucie Unit 1 Replacement history Alloy 600 Small Bore Nozzles on Hot Leg Piping Tag ID Hot Leg Replacement Replacement Method Reason for A or B Date (Figure 1-1 Design A) Replacement PDT-1121D B 2001 1/2 Nozzle Repair Leakage TE-1112HA A 2005 1/2 Nozzle Repair Preventative TE-1112HB A 2005 1/2 Nozzle Repair Preventative TE-1112HC A 2005 1/2 Nozzle Repair Preventative TE-1112HD A 2005 1/2 Nozzle Repair Preventative TE-1111X A 2005 1/2 Nozzle Repair Preventative TE-1122HA B 2005 1/2 Nozzle Repair Preventative TE-1122HB B 2005 1/2 Nozzle Repair Preventative TE-1122HC B 2005 1/2 Nozzle Repair Preventative TE-1122HD B 2005 1/2 Nozzle Repair Preventative TE-1121X B 2005 1/2 Nozzle Repair Preventative PDT-1111A A 2005 1/2 Nozzle Repair Preventative PDT-1111B A 2005 1/2 Nozzle Repair Preventative PDT-1111C A 2005 1/2 Nozzle Repair Preventative PDT-1111D A 2005 1/2 Nozzle Repair Preventative PDT-1121A B 2005 1/2 Nozzle Repair Preventative PDT-1121B B 2005 1/2 Nozzle Repair Preventative PDT-1121C B 2005 1/2 Nozzle Repair Preventative RC-143 A 2005 1/2 Nozzle Repair Preventative LTR-SDA-20-097-NP Rev. Page 5 of 21

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Westinghouse Non-Proprietary Class 3 Table 1-2 St. Lucie Unit 2 Replacement history Alloy 600 Small Bore Nozzles on Hot Leg Piping Repair Repair Method Reason for Location Tag ID Date (Figure 1-1 Design) Repair PZR Stm Space A 1994 1/2 Nozzle Repair(1) (B) Linear Indications Upper Head PZR Stm Space B 1994 1/2 Nozzle Repair(1) (B) Linear Indications Upper Head PZR Stm Space Leakage /

C 1994 1/2 Nozzle Repair(1) (B)

Upper Head Linear Indications PZR Stm Space D 1994 1/2 Nozzle Repair(1) (B) Preventative Upper Head PZR Wtr Space RC-105 1995(2) Sleeve Repair(1) (C) Preventative Lower Head PZR Wtr Space Sleeve Repair(1) (C)

RC-130 1995 Preventative Lower Head PZR Wtr Space Sleeve Repair(1) (C)

TE-1101 1995 Preventative Side Shell RCS Hot Leg Sleeve Repair(1)(3) (C)

TE-1112HA 1989 Preventative RTD Nozzle RCS Hot Leg Sleeve Repair(1)(3) (C)

TE-1111X 1989 Preventative RTD Nozzle RCS Hot Leg Sleeve Repair(1)(3) (C)

TE-1122HC 1989 Preventative RTD Nozzle RCS Hot Leg Sleeve Repair(1)(3) (C)

TE-1122HD 1989 Preventative RTD Nozzle RCS Hot Leg Sleeve Repair(1)(3) (C)

TE-1121X 1989 Preventative RTD Nozzle RCS Hot Leg TE-1112HB 2003 1/2 Nozzle Repair (A) Preventative RTD Nozzle RCS Hot Leg TE-1112HC 2003 1/2 Nozzle Repair (A) Preventative RTD Nozzle RCS Hot Leg TE-1112HD 2003 1/2 Nozzle Repair (A) Preventative RTD Nozzle RCS Hot Leg TE-1122HA 2003 1/2 Nozzle Repair (A) Preventative RTD Nozzle RCS Hot Leg TE-1122HB 2003 1/2 Nozzle Repair (A) Preventative RTD Nozzle LTR-SDA-20-097-NP Rev. Page 6 of 21

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Westinghouse Non-Proprietary Class 3 Table 1-2 St. Lucie Unit 2 Replacement history Alloy 600 Small Bore Nozzles on Hot Leg Piping -

Continued Repair Repair Method Reason for Location Tag ID Date (Figure 1-1 Design) Repair RCS Hot Leg PDT-1121B 1995 Sleeve Repair (D) Leakage Flow Nozzle RCS Hot Leg PDT-1111A 1995 Sleeve Repair (D) Preventative Flow Nozzle RCS Hot Leg PDT-1111B 1995 Sleeve Repair (D) Preventative Flow Nozzle RCS Hot Leg PDT-1111C 1995 Sleeve Repair (D) Preventative Flow Nozzle RCS Hot Leg PDT-1111D 1995 Sleeve Repair (D) Preventative Flow Nozzle RCS Hot Leg PDT-1121A 1995 Sleeve Repair (D) Preventative Flow Nozzle RCS Hot Leg PDT-1121C 1995 Sleeve Repair (D) Preventative Flow Nozzle RCS Hot Leg PDT-1121D 1995 Sleeve Repair (D) Preventative Flow Nozzle RCS Hot Leg Sample Line 1995 Sleeve Repair (D) Preventative Flow Nozzle (1)

PZR Heater 1/2 Nozzle Repair 30 2011 Preventative Sleeves (B)

Notes:

1. Nozzle welded to a nickel alloy weld pad.

2. Per [8], this location was repaired again in 2018 with a similar design. The only difference is that the nickel alloy weld pad was changed from Alloy 600 equivalent to Alloy 690 equivalent weld metal.

3. Alloy 600 weld pad was used at the outer wall. Per [8], any Alloy 600 material at the outer wall of the repair is managed by the Alloy 600 inspection program, and is beyond the scope of the evaluation in this calculation note.

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Westinghouse Non-Proprietary Class 3 2.0 Method Discussion WCAP-15973 [4 and 5] evaluated the half-nozzle repair for the Alloy 600 nozzles of all the CE designed PWRs from a corrosion, fatigue crack growth and stress corrosion assessment perspective. It was concluded that corrosion of carbon and low alloy steels would be within Code limits and it would be acceptable to leave a flaw in place in small diameter Alloy 600 nozzles and partial penetration for the 40-year plant design life. This calculation note reconciles the evaluation in WCAP-15973 [4 and 5] for the 80-year plant operation of St. Lucie Units 1 and 2 considering the actual plant operation and plant specific geometries. The reconciliation in Section 5.0 shows that the conclusions in WCAP-15973 [4 and 5] remain valid for the period of extended operation.

3.0 Discussion of Significant Assumptions

1. The corrosion rate calculated in Section 2.3 of WCAP-15973-P [4] was based on [

]a,c,e The plant specific corrosion rates based on the generation data review were calculated to be 1.20 mpy [1] and 1.34 mpy [2] for Unit 1 and Unit 2, respectively. Therefore, the corrosion rate of [ ]a,c,e bounds the corrosion rate based on St. Lucie Unit 1 and Unit 2 power generation data. It is assumed that the corrosion rate of [ ]a,c,e remains bounding for the rest of the 80 year operation.

2. In order to use the stress corrosion assessment in WCAP-15973 [4 and 5], NRC requires that the plants demonstrate that the contaminant concentrations in the reactor coolant have been typically maintained at levels below 10 ppb for dissolved oxygen, 150 ppb for halide ions and 150 ppb for sulfate ions. Per reference [1] and [2], plant chemistry reviews show that for both St. Lucie Unit 1 and Unit 2, typical contaminant concentrations for dissolved oxygen, halide ions and sulfate ions are maintained at less than 5 ppb, far below the NRC requirement. It is assumed that the contaminant concentrations is maintained below the NRC requirement for the 80 year operation.

The assumptions above will be examined every ten years when the plant submits the plants request relief from Code requirements for existing and future half nozzle repair technique that leaves the cracks in place which is in conflict with ASME Code Section XI requirements. The most recent relief requests [1 and 2] were submitted and approved in 2018 for St. Lucie Unit 1 and 2014 for St. Lucie Unit 2.

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Westinghouse Non-Proprietary Class 3 4.0 Acceptance Criteria Acceptance criteria for crack growth and stability are based on ASME Code 2007 Edition with 2008 Addenda,Section XI, IWB-3600 [9] and the acceptance criteria specified in RG 1.161 for the Elastic-Plastic Fracture Mechanics (EFPM) evaluation.

For the corrosion evaluation, ASME Code requirements for the maximum allowable hole size cannot be exceeded considering the corrosion that may occur in the crevice region of the replaced nozzles. The allowable diameter of a corroded hole is calculated based on the allowable shear stress of the weld in accordance with paragraph NB-3227.2(a) and the reinforcement requirement in NB-3332.2 of ASME Code 1989 Edition,Section III [10]. The maximum allowable corroded hole diameter for small Alloy 600 partial penetration welded nozzles is calculated in A-CEOG-9449-1242 Rev. 00 [11].

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Westinghouse Non-Proprietary Class 3 5.0 Carbon and Low-Alloy Steel Borated Water Corrosion Evaluations As shown in Figure 1-1, four designs (Design A, B, C, and D) were used for half nozzle repair in St. Lucie Unit 1 and 2 plants. The corrosion evaluation for Design A/B and Design C/D are discussed separately as below.

Design A/B Corrosion Evaluation For Designs A and B, a small gap remains between the remnant of the original alloy 600 component and the new alloy 690 component. As a result, primary coolant (borated water) will fill the crevice between the nozzle or heater sleeve and the pipe or the pressurizer wall. Since a crevice exists, the low alloy and carbon steels are exposed to borated water and corrosion could occur.

The corrosion rate evaluation was performed in Section 2.3 of WCAP-15973-P [4] considering all the CE designed PWR plants. [

]a,c,e Reference [1]

reviewed St. Lucie Unit 1 generation data from 4/15/2001 (oldest half nozzle repair for Unit 1) to 12/31/2017. Reference [2] reviewed St. Lucie Unit 2 generation data from 1/1/1995 to 2/28/2014; note that the oldest half nozzle repair with Design A/B occurred in 1994. The plant specific corrosion rates based on the generation data review were calculated to be 1.20 mpy [1]

and 1.34 mpy [2] for Unit 1 and Unit 2, respectively. The corrosion rate of [ ]a,c,e calculated in Section 2.3 of [4] bounds the corrosion rate calculated for St. Lucie Unit 1 and Unit 2, [

]a,c,e a,c,e The corrosion rate of [ ] from [4] is thus conservatively used herein to calculate the amount of general corrosion based thinning for the vessels or piping over the life of the plant considering 80 years of operation. Note that with the approval of subsequent license renewal application, the plant licenses for St. Lucie Unit 1 and Unit 2 will be extended to 2056 and 2063, respectively.

Table 5-1 calculates the maximum repair bore diameter at the end of 80 years operation for all the design A/B half-nozzle repairs and compares the results to the corresponding limiting allowable diameter. It shows that repair bore diameter at the end of 80 years operation is below the limiting allowable diameter for all the design A/B half-nozzle repairs. Therefore, these repairs have acceptable wall thickness until the end of 80 years operation.

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Westinghouse Non-Proprietary Class 3 Table 5-1 Summary of Limiting Allowable Diameter Calculations for Half-Nozzle Repair - Design A and B St. Lucie Unit 1 Corrosion Evaluation for 80 Years Operation Repair Bore Repair Limiting Earliest Nozzle Repair Diameter Diameter at Method Allowable Nozzle Location(1) Repair Bore Diameter Corrosion Loss the end of 80 (Figure 1-1 Diameter Year(1) (inch)(2) (inch)(3) years operation Design)(1) (inch)(5)

(inch)(4)

Hot Leg Piping A 2001 1.063 [ ]a,c,e [ ]a,c,e 1.27 St. Lucie Unit 2 Corrosion Evaluation for 80 Years Operation Repair Bore Repair Limiting Earliest Nozzle Repair Diameter Diameter at Method Allowable Nozzle Location(6) Repair Bore Diameter Corrosion Loss the end of 80 (Figure 1-1 Diameter Year(6) (inch)(7) (inch)(8) years operation Design)(6) (inch)(5)

(inch)(4)

PZR Stm Space Upper Head B 1994 1.325 [ ]a,c,e [ ]a,c,e 2.26 RCS Hot Leg RTD Nozzle A 2003 1.063 [ ]a,c,e [ ]a,c,e 1.27 Pressurizer Heater Sleeve B 2011 1.693 [ ]a,c,e [ ]a,c,e 2.26 Notes:

1. Information from Table 1-1.

2. See St. Lucie Unit 1 relief request [1].

3. [

]a,c,e

4. Repair bore diameter at the end of 80 years operation is equal to the sum of nozzle repair bore diameter and diameter corrosion loss.

5. Limiting Allowable diameter is from Table 2 of A-CEOG-9449-1242 [11].

6. Information from Table 1-2.

7. See St. Lucie Unit 2 relief request [2].

8. [

]a,c,e LTR-SDA-20-097-NP Rev. Page 11 of 21

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Westinghouse Non-Proprietary Class 3 Design C/D Corrosion Evaluation For Designs C and D, the end of the Alloy 690 sleeve at the interior surface of the piping or the pressurizer is either roll expanded or welded to the interior surface of the piping or pressurizer to eliminate corrosion of the carbon steel by stopping the replenishment of borated solution in contact with the carbon steel. As discussed in Section 2.5 of WCAP-15973 [4], since the borated solution confined in the tight crevice between the sleeve and the interior surface of the piping or pressurizer cannot be replenished, the crevice region will fill with corrosion products when corrosion occurs. The presence of corrosion products in the crevice will prevent access of the corrodent (borated water) to the carbon and low alloy steel, reducing the corrosion rate.

Further corrosion will result in the crevice corrosion products becoming denser and less permeable to the primary coolant. Eventually, the corrosion process will stifle because the steel will become isolated from the coolant. The lifetime maximum diametrical loss for the tight crevice like sleeve repair in Design C/D is conservatively assessed as [ ]a,c,e in Section 2.5 of WCAP-15973 [4].

Table 5-2 calculates the maximum repair bore diameter at the end of 80 years operation for all the design C/D half-nozzle repairs and compares the results to the corresponding limiting allowable diameter. It shows that repair bore diameter at the end of 80 years operation is below the limiting allowable diameter for all the design C/D half-nozzle repairs. Note that Design C/D repairs were only performed in St. Lucie Unit 2 plant. Therefore, these repairs have acceptable wall thickness until the end of 80 years operation.

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Westinghouse Non-Proprietary Class 3 Table 5-2 Summary of Limiting Allowable Diameter Calculations for Half-Nozzle Repair - Design C and D St. Lucie Unit 2 Corrosion Evaluation for 80 Years Operation Repair Bore Repair Limiting Earliest Nozzle Repair Diameter Diameter at Method Allowable Nozzle Location(1) Repair Bore Diameter Corrosion Loss the end of 80 (Figure 1-1 Diameter Date(1) (inch)(2) (inch) years operation Design)(1) (inch)(4)

(inch)(3)

PZR Wtr Space Lower Head C 1995 1.5 [ ]a,c,e [ ]a,c,e 2.26 PZR Wtr Space Side Shell C 1995 1.325 [ ]a,c,e [ ]a,c,e 1.62 RCS Hot Leg RTD Nozzle C 1989 1.129 [ ]a,c,e [ ]a,c,e 1.27 RCS Hot Leg Flow Nozzle D 1995 1.178 [ ]a,c,e [ ]a,c,e 1.27 Notes:

1. Information from Table 1-2.

2. See St. Lucie Unit 2 relief request [2].

3. Repair bore diameter at the end of 80 years operation is equal to the sum of nozzle repair bore diameter and diameter corrosion loss.

4. Limiting Allowable diameter is from Table 2 of A-CEOG-9449-1242 [11].

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Westinghouse Non-Proprietary Class 3 6.0 Carbon and Low Alloy Steel Fatigue Crack Growth and Flaw Stability Fatigue crack growth evaluation for half nozzle repair was performed to bound all the CE PWRs in WCAP-15973 [4 and 5]. Calculations were performed assuming that a crack had propagated through the nozzle and associated weld metal and had reached the interface with the carbon or low alloy steel. The postulated flaws were subjected to anticipated (Level A/B) transients for the plant evaluation period to determine the final flaw size using the guidance outlined in ASME Code Section XI, Appendix A. The final flaw size was then used in subsequent flaw stability calculations. WCAP-15973 [4 and 5] provided the results of fatigue crack growth evaluations and crack stability analyses for pressurizer heater sleeves and instrument nozzles and hot leg pipe nozzles, including the effects of the support skirt and pressurizer in-surges. The details of the calculation are in CN-CI-02-71 [12]. The results indicate that the ASME code acceptance criteria for crack growth and crack stability are met.

In addition, a plant specific fatigue crack growth and flaw stability evaluation for postulated flaws at small-bore locations in the pressurizer and Hot Leg Piping for St. Lucie Units 1 & 2 was performed in CN-CI-02-69, Rev. 0 [13] using the same methods as CN-CI-02-71 [12] to support a 60 year fatigue life. The results in CN-CI-02-69, Rev. 0 [13] also demonstrate that the ASME code acceptance criteria for crack growth and crack stability are met.

The NRC SE to WCAP-15973-P-A [5, 5.a] states that Licensees seeking to reference this topical report for future licensing applications need to demonstrate the following:

1. The geometry of the leaking penetration is bounded by the corresponding penetration reported in calculation report CN-CI-02-71, Revision 01.

2. The plant-specific pressure and temperature profiles in the pressurizer water space for the limiting curves (cooldown curves) do not exceed the analyzed profile shown in Figure 6-2 of Calculation Report CN-CI-02-71, Revision 01.

3. The plant-specific Charpy upper-shelf energy (USE) data shows a USE value of at least 70 ft-lb to bound the USE value used in the analysis. If the plant-specific Charpy USE data does not exist and the licensee plans to use Charpy USE data from other plants pressurizers and hot leg piping, then justification (e.g., based on statistical or lower bound analysis) has to be provided.

4. If the licensee plans on using this alternative beyond the 40 years and through the license renewal period, the thermal fatigue crack growth analysis shall be re-evaluated to include the extended period, as applicable, and submitted as a time limited aging analysis in their license renewal application as required by 10 CFR 54.21(c)(1).

Note that CN-CI-02-71, Revision 01 was later revised to Revision 02, but only editorial changes were made in Revision 02 (see Reference [12]). No technical change was made to CN-CI-02-71, Revision 01.

The four NRC requests are addressed correspondingly in the following paragraphs:

1. The fatigue crack growth and flaw stability analyses specific for St. Lucie plants geometry were performed in CN-CI-02-69, Rev. 0 [13], which was submitted to NRC as part of the St. Lucie License Renewal activity. An extended license was approved for St. Lucie Unit 1 and Unit 2. The calculation and results in CN-CI-02-69, Rev. 0 [13] are equivalent to that LTR-SDA-20-097-NP Rev. Page 14 of 21

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Westinghouse Non-Proprietary Class 3 shown in CN-CI-02-71, Rev. 1. It is recognized that the calculations of CN-CI-02-69, Rev.

0 [13] did not address the pressurizer heater sleeves since the half nozzle repair of the small diameter nozzle at the heater sleeve location at St. Lucie Unit 2 occurred about 9 years after the study in CN-CI-02-69, Rev. 0 [13]. However, the geometry of the St. Lucie Unit 2 pressurizer heater sleeves with half nozzle repair was reviewed and determined to be equivalent to that shown in CN-CI-02-71, Rev. 1. Therefore, the half nozzle repairs for St.

Lucie plants as listed in Table 1-1 and Table 1-2 are addressed by the analyses in CN-CI-02-71 [12] and CN-CI-02-69 [13].

2. As discussed in [1], since Figure 6-2 of [12] applies to the pressurizer and the hot leg piping does not see the transients experienced by the pressurizer, the evaluation of the pressurizer limiting curves is considered not applicable to the hot leg nozzles per [1]. All the half nozzle repair locations for St. Lucie Unit 1 are on the hot leg piping. Therefore, this request does not apply to St. Lucie Unit 1.

The pressurizer cooldown transient used in CN-CI-02-71 Rev. 1 and Rev. 2 [12] as shown in Figure 6-2 of [12] has [

]a,c,e Per [2], cooldown of the pressurizer water space for St. Lucie Unit 2 is administratively controlled by a plant procedure to a maximum rate of 75oF per hour for normal operation, which is within the rates shown in Figure 6-2 of CN-CI-02-71 [12].

3. Charpy USE value of 70 ft-lb was used in Section 6.3.3.2 of CN-CI-02-71 [12] to support an elastic-plastic fracture mechanics (EPFM) analysis of the pressurizer lower shell and lower head. The analysis was not performed on the pressurizer upper head and the hot leg piping because the pressurizer upper head and hot leg piping are not affected by the large in-surge transient or thermal stress that occurs at the pressurizer lower head and lower shell.

All the half nozzle repair locations for St. Lucie Unit 1 are on the hot leg piping. Therefore, the evaluation of the plant-specific Charpy USE data is only applicable to pressurizer lower shell and lower head of St. Lucie Unit 2 plant. As discussed in [2], Charpy USE data for the pressurizer was not required when the pressurizer was built and thus was not determined.

However, the Charpy impact data for the two lower shell plates, the upper head, and the bottom head of the pressurizer was reviewed in [2] along with the Charpy impact data and USE for six plates in the reactor vessel (RV) shell. The pressurizer lower shell plates, upper head and bottom head are made to the same alloy specification, SA-533 Grade B Class 1, as the six RV plates. The four pressurizer items and the six RV items have similar chemistry and received similar heat treatment. Therefore, it can be reasonably expected that the USE data for the pressurizer material should be comparable to that of the RV plates [2]. The review of the Charpy impact data for the pressurizer items along with the Charpy impact data and USE for the RV items in [2] demonstrated that the St. Lucie Unit 2 pressurizer lower shell and lower head is expected to exhibit USE well in excess of 70 ft-lb and is bounded by the analysis in CN-CI-01-71 [12].

4. The fatigue crack growth and flaw stability analyses in CN-CI-02-71 [12] were performed using design cycles that were specified in the plant design process. These design cycles were intended to be conservative and bounding for all foreseeable plant operational conditions. Experience has shown that actual plant operation is often very conservatively LTR-SDA-20-097-NP Rev. Page 15 of 21

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Westinghouse Non-Proprietary Class 3 represented by these design cycles. The use of actual operating history data allows the quantification of these conservatisms. [

]a,c,e Therefore, the design cycles used in CN-CI-02-71 [12] are bounding for the period of extended 80 years operation.

It is noted that the analyses in CN-CI-02-71 [12] were based on the 1992 Edition of ASME Code,Section XI [15] while the Section XI Code year for St. Lucie Unit 1 and Unit 2 is currently 2007 Edition with 2008 Addenda [9]. The comparison of 1992 Edition and 2007 Edition with 2008 Addenda ASME Code,Section XI is performed herein regarding the fatigue crack growth and flaw stability analyses in CN-CI-02-71 [12]. It shows that the flaw characterization in IWA-3300, guidance outlined in Appendix A for the fatigue crack growth analysis, and the flaw stability acceptance criteria in IWB-3610 are the same in the two versions of ASME Code Section XI. It is noted that in ASME Code Section XI, 2007 Edition with 2008 Addenda, it is added in IWA-3300 that combination of multiple planar flaws is not required for fatigue or stress corrosion cracking analysis. This does not affect the analyses in CN-CI-02-71

[12], which didnt need to address the combination of multiple planar flaws.

Based on the evaluation above, the conclusion from the fatigue crack growth and flaw stability analyses in WCAP-15973 [4 and 5] and CN-CI-02-71 [12] remains valid for the 80 years of operation. The ASME code acceptance criteria for crack growth and crack stability are met for the rest of the plant life including the extended operation.

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Westinghouse Non-Proprietary Class 3 7.0 Carbon and Low Alloy Steel Stress Corrosion Cracking Assessment Section 3.6 of WCAP-15973 [4 and 5] evaluated the possibility that a crack that had propagated through an Alloy 600 nozzle and weld metal would continue to propagate by a stress corrosion mechanism through the carbon or low alloy steel component. Stress corrosion cracking (SCC) is dependent on the simultaneous presence of three elements: an aggressive environment, a susceptible material condition, and a stress (applied plus residual) in excess of some threshold value. If any element is missing, SCC will not occur. WCAP-15973 [4 and 5] concluded that the environmental conditions expected in PWRs indicate that SCC initiation and propagation in the carbon or low alloy steels component base metals as a result of cracked Alloy 600 nozzles left in place during nozzle repair is not a concern. In addition, the tests conducted indicated that there was no SCC growths of existing defects even at high stress intensity factor levels for low potential (PWR) conditions. WCAP-15973 [4 and 5] also reviewed the field experience and concluded that PWR field experience is consistent with laboratory observations and confirms that SCC of carbon and low alloy steel components as a result of nozzle repairs is not likely for CE plants.

The NRC SE to WCAP-15973-P-A [5, 5.a] states that Licensees seeking to implement half-nozzle replacements may use the stress corrosion assessment in WCAP-15973 [4 and 5] as the bases for concluding that existing flaws in the weld metal will not grow by stress corrosion if the following conditions are met:

1. Conduct appropriate plant chemistry reviews and demonstrate that a sufficient level of hydrogen overpressure has been implemented for the RCS and that the contaminant concentrations in the reactor coolant have been typically maintained at levels below 10 ppb for dissolved oxygen, 150 ppb for halide ions and 150 ppb for sulfate ions.

2. During the outage in which the half-nozzle repairs are scheduled to be implemented, licensees adopting the stress corrosion crack growth arguments will need to review their plant specific RCS coolant chemistry histories over the last two operating cycles for their plants and confirm that these conditions have been met over the last two operating cycles.

Per reference [1] and [2], plant chemistry reviews show that for both St. Lucie Unit 1 and Unit 2, typical contaminant concentrations for dissolved oxygen, halide ions and sulfate ions are maintained at less than 5 ppb.

Therefore, the conclusion in WCAP-15973 [4 and 5] remains valid for 80 years of operation and the existing flaws in the weld metal will not grow by stress corrosion.

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Westinghouse Non-Proprietary Class 3 8.0 Summary and Conclusion The Alloy 600 half nozzle repairs for the St. Lucie Units 1 and 2 are reassessed for the subsequent license renewal (SRL). The results for the evaluation of corrosion, fatigue crack growth and flaw stability, and corrosion stress cracking are summarized below:

1. For Design A/B of half nozzle repair in Figure 1-1, the corrosion rate of [ ]a,c,e from WCAP-15973 [4 and 5] is determined to bound the corrosion rate of 1.20 mpy [1]

for St. Lucie Unit 1 and 1.34 mpy [2] for St. Lucie Unit 2 based on the plant power generation data. Table 5-1 summarizes the amount of general corrosion based thinning at the half nozzle repair locations over the life of the plant considering 80 years of operation, which is calculated by conservatively using the [ ]a,c,e corrosion rate from WCAP-15973 [4 and 5]. The results in Table 5-1 show that the repair bore diameter at the end of 80 years operation is below the limiting allowable diameter for all the design A/B half-nozzle repairs. Therefore, these repairs have acceptable wall thickness until the end of 80 years operation.

2. For Design C/D of half nozzle repair in Figure 1-1, since the borated solution confined in the tight crevice between the sleeve and the interior surface of the piping or pressurizer cannot be replenished, the crevice region will fill with corrosion products when corrosion occurs. The presence of corrosion products in the crevice will prevent access of the corrodent (borated water) to the carbon and low alloy steel, reducing the corrosion rate.

Further corrosion will result in the crevice corrosion products becoming denser and less permeable to the primary coolant. Eventually, the corrosion process will stifle because the steel will become isolated from the coolant. The lifetime maximum diametrical loss for the tight crevice like sleeve repair in Design C/D is conservatively assessed as [

]a,c,e in Section 2.5 of WCAP-15973 [4]. Table 5-2 shows that the maximum repair bore diameter at the end of 80 years operation is below the limiting allowable diameter for all the design C/D half-nozzle repairs. Therefore, these repairs are also acceptable for 80 years of operation regarding the corrosion evaluation.

3. Section 6 reconciled the fatigue crack growth and flaw stability evaluation in WCAP-15973 [4 and 5] for the extended 80 years operation of St. Lucie Unit 1 and Unit 2 plants.

The design cycles used in the fatigue crack growth analysis in [4 and 5] are conservative and bound the projected transient cycles for 80 years of operation. The geometry of half-nozzle repair locations in St. Lucie Unit 1 and Unit 2 is bounded by what analyzed in CN-CI-02-71 [12]. The plant-specific pressurizer cooldown curves are also bounded by the profile analyzed in CN-CI-02-71 [12]. The review of the Charpy impact data for the plant specific pressurizer items along with the Charpy impact data and upper shelf energy (USE) for the RV items in [2] demonstrated that the St. Lucie Unit 2 pressurizer lower shell and lower head is expected to exhibit USE well in excess of 70 ft-lb and is bounded by the analysis in CN-CI-01-71 [12]; the pressurizer lower head and lower shell flaw stability evaluation based on elastic-plastic fracture mechanics (EPFM) analysis in CN-CI-01-71

[12] thus can be used to demonstrate the acceptability of the half nozzle repairs performed at St. Lucie 2 pressurizer locations. Therefore, the conclusion from the fatigue crack growth and flaw stability analyses in WCAP-15973 [4 and 5] and CN-CI-02-71 [12]

remains valid for the 80 years of operation. The ASME code acceptance criteria for crack LTR-SDA-20-097-NP Rev. Page 18 of 21

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Westinghouse Non-Proprietary Class 3 growth and crack stability are met for the rest of the plant life including the extended operation.

4. As discussed in WCAP-15973 [4 and 5], cracks that may be present in Alloy 600 remnants left in place following a half-nozzle repair or cracks that may initiate after completion of the repair will not propagate by stress corrosion cracking (SCC) through the carbon or low alloy steel components. Per [1] and [2], plant chemistry reviews show that for both St.

Lucie Unit 1 and Unit 2, typical contaminant concentrations for dissolved oxygen, halide ions and sulfate ions are maintained at less than 5 ppb. The very low primary side oxygen levels that result in corrosion potentials is well below the critical cracking potentials for the carbon or low alloy steel materials.

Therefore, the alloy 600 half nozzle repairs in the St. Lucie Unit 1 and Unit 2 plants are evaluated to be acceptable regarding corrosion, fatigue crack growth and flaw stability, and stress corrosion cracking for 80 years of operation. The conditions for using the topical report, WCAP-15973 [5], listed in the NRC SER [5.a] Sections 3.1, 3.2 and 3.3 are satisfied. Note that the evaluation herein also confirms that the conclusions in the responses to NRC request for additional information (RAI) 4.6.4-1 and 4.6.4-2 for the original St. Lucie Units 1 and 2 license renewal application in ML022890457 [16] remain valid for 80 years of operation.

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Westinghouse Non-Proprietary Class 3 9.0 References

1. FPL Letter, L-2018-027, St. Lucie Unit 1 Docket No. 50-335 Inservice Inspection Plan, Fifth Ten-Year Interval Unit 1 Relief Request No. 5, Revision 0, February 8, 2018. (ADAMS Access Number ML18039A437)

2. FPL Letter, L-2014-252, St. Lucie Unit 2 Docket No. 50-389 In-Service Inspection Plan, Fourth Ten-Year Interval Unit 2 Relief Request 2, August 1, 2014. (ADAMS Access Number ML14224A010)

3. CE Owners Group Topical Report, CE NPSD-1198-P, Rev. 00, Low-Alloy Steel Component Corrosion Analysis Supporting Small-Diameter Alloy 600/690 Nozzle Repair/Replacement Programs CEOG, February 8, 2001.

4. Westinghouse Report, WCAP-15973-P, Rev. 1, Low-Alloy Steel Component Corrosion Analysis Supporting Small-Diameter Alloy 600/690 Nozzle Repair/Replacement Programs, May 2004.

5. Westinghouse Report, WCAP-15973-P-A, Rev. 0 (NRC approved version of WCAP-15973-P, Revision 1 with SER and resolved questions), Low-Alloy Steel Component Corrosion Analysis Supporting Small-Diameter Alloy 600/690 Nozzle Repair/Replacement Programs, February 2005. (ADAMS Access Number ML050700431)

a. USNRC SER, Final Safety Evaluation for Topical Report WCAP-15973-P, Revision 01, Low-Alloy Steel Component Corrosion Analysis Supporting Small-Diameter Alloy 600/690 Nozzle Repair/Replacement Program (TAC No. MB6805), January 12, 2005. (ADAMS Access Number ML050180528)

6. License Renewal Application, St. Lucie Units 1 and 2, November 30, 2011 (Renewed License Issued 10/02/2003). https://www.nrc.gov/reactors/operating/licensing/renewal/applications/st-lucie.html

7. NUREG-1779, Safety Evaluation Report Related to the License Renewal of St Lucie Nuclear Plant, Units 1 and 2, September 2003. (ADAMS Accession Number ML032940205).

8. FPL Letter, PSLWEC-21-0005, Revision 0, Design Input Transmittal for WS09a Alloy 600 Locations to Support the St. Lucie Unit 1 and Unit 2 Subsequent License Renewal, February 4, 2021.

9. ASME Boiler and Pressure Vessel Code, 2007 Edition with 2008 Addenda,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components.

10. ASME Boiler and Pressure Vessel Code, 1989 Edition,Section III, Rules for Construction of Nuclear Facility Components.

11. CE Design Analysis, A-CEOG-9449-1242 Rev. 00, Evaluation of the Corrosion Allowance for Reinforcement and Effective Weld to Support Small Ally 600 Nozzle Repairs, June 13, 2000.

12. Westinghouse Calculation Note, CN-CI-02-71, Rev. 2, Summary of Fatigue Crack Growth Evaluation Associated with Small Diameter Nozzles in CEOG Plants, December 9, 2005.

13. Westinghouse Calculation Note, CN-CI-02-69, Rev. 0, Evaluation of Fatigue Crack Growth Associated with Small Diameter Nozzles for St. Lucie 1 & 2, October 9, 2002 (Attached to FPL Letter L2002-222, Adams Accession # ML023380149).

14. Westinghouse Calculation Note, CN-SDA-II-20-026, Rev. 0, St. Lucie Unit 1 and Unit 2 80-Year Transient Cycle Projections, February 25, 2021.

15. ASME Boiler and Pressure Vessel Code, 1992 Edition,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components.

LTR-SDA-20-097-NP Rev. Page 20 of 21

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Westinghouse Non-Proprietary Class 3

16. FPL Letter, L-2002-165, Response to NRC Request for Additional Information for Review of the St. Lucie Units1 and 2 License Renewal Application, October 10, 2002 (Adams Accession

ML022890450).

LTR-SDA-20-097-NP Rev. Page 21 of 21

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LTR-SDA-20-097-NP Revision 3 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 Song Xiaolan Sep-14-2021 13:55:25 Verifier Approval White Jay D Sep-14-2021 17:34:57 Manager Approval Rigby Stephen Sep-15-2021 14:59:31 Files approved on Sep-15-2021

- - This record was final approved on 9/15/2021 2:59:31 PM. (This statement was added by the PRIME system upon its validation)

St. Lucie Nuclear Plant Units 1 and 2 Dockets 50-335 and 50-389 L-2021-192 Enclosure 4 Enclosure 4 Non-proprietary Reference Documents and Redacted Versions of Proprietary Reference Documents (Public Version)

Attachment 12 Westinghouse Report LTR-SDA-20-104-NP, Rev. 3, St. Lucie Units 1&2 Subsequent License Renewal:

Evaluation of Time-Limited Aging Analysis of the Reactor Vessel Internals, September 14, 2021 (11 Total Pages, including cover sheets)

Westinghouse Non-Proprietary Class 3 LTR-SDA-20-104-NP, Rev. 3 September 14, 2021 Foreword:

This document contains Westinghouse Electric Company LLC proprietary information and data which has been identified in brackets. Coding (a,b,c,e) associated with the brackets sets forth the basis on which information is considered proprietary. These code letters are listed with their meanings in BMS-LGL-84, and are defined as follows:

a. The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where the prevention of its use by any of Westinghouses competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.

b. The information consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which secures a competitive economic advantage, e.g., by optimization or improved marketability.

c. The information, if used by a competitor, would reduce the competitors expenditure of resources or improve the competitors advantage in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product.

e. The information reveals aspects of past, present, or future Westinghouse or customer funded development plans and programs of potential commercial value to Westinghouse.

The proprietary information and data contained within the brackets of this document were obtained at considerable Westinghouse expense and its release could seriously affect our competitive position. This information is to be withheld from public disclosure in accordance with the Rules of Practice 10 CFR 2.390 and the information presented herein is to be safeguarded in accordance with 10 CFR 2.390. Withholding of this information does not affect the public interest.

This information has been provided for your internal use only and should not be released to persons or organizations outside the Directorate of Regulation and the ACRS (Advisory Committee on Reactor Safeguards) without the express written approval of Westinghouse Electric Company LLC. Should it become necessary to release this information to such persons as part of the review procedure, please contact Westinghouse Electric Company LLC, which will make the necessary arrangements required to protect the Companys proprietary interests.

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Westinghouse Non-Proprietary Class 3 LTR-SDA-20-104-NP, Rev. 3 September 14, 2021 1.0 Introduction and Summary of Results The critical plug locations are determined from the previous two calculations that evaluated the required preload of the U1 CSB repair plugs, [1] and [2]. The 3 plugs with the smallest previously calculated margins are the critical CSB repair plug locations. The calculation results encompass the evaluation of all plugs.

In accordance with the original evaluation of CSB repair plug flange deflection measurements documented in [9], actual CSB repair plug flange deflection measurement tool readings must be greater than or equal to the minimum required values. The minimum required deflection value is described in the detailed evaluation method in Section 2.1 and calculated in Section 2.2. Satisfaction of this criterion demonstrates that the plugs have sufficient preload to perform their intended function over the operating life of the plant.

Actual CSB repair plug flange deflection measurement tool readings exceed the minimum required values in all cases. Therefore, the acceptance criterion outlined in the calculation note is met, and the CSB repair plugs will perform their intended function for the remainder of the plant service life considering SLR. This calculation addressed the time-limited aging analysis (TLAA) performed for license extension in [1] and shows that the TLAA is acceptable with Extended Power Uprate (EPU) for 72 effective full power years (EFPY). The CSB repair plug results are provided in Table 1-1. The minimum margin is [ ] b,c,e for plug ID 17-5 based on the measurement tool readings from EOC 6. For comparison, the minimum margin was [ ]b,c,e at Plug ID 14-2 calculated for 54 EFPY in [2]. The minor difference of [ ]b,c,e is reasonable since the relaxation factor as a function of fluence decreases exponentially, so the added fluence due to SLR has a minor effect on the relaxation of the plugs.

Additionally, the fatigue analysis of the Unit 1 damaged core support barrel, along with other fatigue analyses performed for the EPU on reactor vessel internals (RVI) components for both units (Unit 1 and Unit 2) are addressed to encompass all time-limited aging analysis (TLAA) on the RVI. The number of occurrences for the design transients remain conservatively applicable for SLR as confirmed by the 80-year cycle projections performed in [6]. The fatigue analyses evaluations are discussed in Sections 2.3 and 2.4 of this letter. The EPU thermal and hydraulic loads on the RVI are applicable to SLR per Item 2 in the Attachment to the design input transmittal [7]. Therefore, the fatigue analysis results in the analyses of record remain applicable to SLR.

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Westinghouse Non-Proprietary Class 3 LTR-SDA-20-104-NP, Rev. 3 September 14, 2021 Table 1-1: Summary of Calculation Results for Selected Plugs Required Minimum Req. Plug Minimum Plug-Plug-Flange Overall Overall Flange Flange Deflection Fluence at Plug at Deflection Margin at Margin at Margin Plug ID Deflection Actual 72 EFPY Measurement Tool EOL at 54 EOL at 72 Difference for EOC 6 Measurement at Reading for EOC 6 EFPY EFPY to EOL EOC 6 to EOL 6 - 12 [ ]b,c,e [ ]b,c,e [ ]b,c,e [ ]b,c,e [ ]b,c,e [ ]b,c,e [ ]b,c,e 17 - 5 [ ]b,c,e [ ]b,c,e [ ]b,c,e [ ]b,c,e [ ]b,c,e [ ]b,c,e [ ]b,c,e 14 - 2 [ ]b,c,e [ ]b,c,e [ ]b,c,e [ ]b,c,e [ ]b,c,e [ ]b,c,e [ ]b,c,e 4

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Westinghouse Non-Proprietary Class 3 LTR-SDA-20-104-NP, Rev. 3 September 14, 2021 2.0 Evaluation Methodology and Analyses 2.1 Evaluation Method

[

]a,c,e In summary, the method of evaluation consists of calculating the plug preloads, then necessary adjustment factors are calculated and applied. Additionally, tool readings are calculated and compared to the minimum deflection measurement tool readings. The evaluation is limited to critical plug locations. This methodology is consistent with first license renewal (as clarified in RAI 4.6.3-2 of [10]) and considers iron atom displacements for a 10% bias on the peripheral and re-entrant corner assembly relative powers, as well as a 10% increase to account for fluence uncertainty at 72 EFPY.

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Westinghouse Non-Proprietary Class 3 LTR-SDA-20-104-NP, Rev. 3 September 14, 2021 2.2 Unit 1 CSB Plug Calculations Calculation of Plug Preloads Required to Resist Hydraulic Drag Forces

[ ]a,c,e Calculation of Irradiation-Induced Relaxation Factors Fluence at Plug ID 6-12: Fluence6L mean DPAEFPY72_6_12 DPAEOC6_6_12 1

Fluence at Plug ID 17-5: Fluence6L mean DPAEFPY72_17_5 DPAEOC6_17_5 2

Fluence at Plug ID 14-2: Fluence6L mean DPAEFPY72_14_2 DPAEOC6_14_2 3

Relaxation Factor in Plug Flange from EOC 6 Through EOL

[

]a,c,e Calculation of Required Plug Flange Deflection

[

]a,c,e Where tempi is the CSB repair plug flange deflection loss due to thermal cycling, per [4].

Calculation of Required Minimum Plug Flange Deflection Measurement Tool Reading

[

]a,b,c,e 6

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Westinghouse Non-Proprietary Class 3 LTR-SDA-20-104-NP, Rev. 3 September 14, 2021 2.3 Evaluation of Unit 1 RVI Fatigue Analyses The Unit 1 RVI fatigue analyses are performed for the EPU in calculation note CN-RIDA-09-9, [3]. The EPU thermal and hydraulic loads are applicable to SLR per Item 2 in the Attachment to the design input transmittal [7]. The number of design transient event occurrences projected for SLR in [6] is bounded by the number of design transient event occurrences used in the fatigue analysis of [3]. Since the inputs to the fatigue analysis performed for EPU are not affected by SLR, the Unit 1 RVI fatigue analyses performed for the EPU in calculation note CN-RIDA-09-9, [3], remain applicable. This evaluation meets the fatigue criteria specified in the May 1972 draft of Section III, Subsection NG of the ASME Boiler and Pressure Vessel Code to address RAI 4.6.3-1 of [10].

2.4 Evaluation of Unit 2 RVI Fatigue Analyses The Unit 2 RVI fatigue analyses are performed for the EPU in calculation note CN-RIDA-14-114, [8]. The EPU thermal and hydraulic loads are applicable to SLR per Item 2 in the Attachment to the design input transmittal [7]. The number of design transient event occurrences projected for SLR in [6] is bounded by the number of design transient event occurrences used in the fatigue analysis of [8]. Since the inputs to the fatigue analysis performed for EPU are not affected by SLR, the Unit 2 RVI fatigue analyses performed for the EPU in calculation note CN-RIDA-14-114, [8], remain applicable. This evaluation meets the fatigue criteria specified in the May 1971 Edition with Addenda through Winter 1973 of Section III, Subsection NG of the ASME Boiler and Pressure Vessel Code.

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Westinghouse Non-Proprietary Class 3 LTR-SDA-20-104-NP, Rev. 3 September 14, 2021 3.0 Comparison of Actual Plug Flange Deflection Versus Minimum Required Results The minimum margin [ ]b,c,e at Plug ID 17-5. For comparison, the minimum margin was [

b,c,e

] at Plug ID 14-2 calculated for 54 EFPY in [2]. The minor difference of [ ]b,c,e is reasonable since the relaxation factor as a function of fluence decreases exponentially, so the added fluence due to SLR has a minor effect on the relaxation of the plugs.

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Westinghouse Non-Proprietary Class 3 LTR-SDA-20-104-NP, Rev. 3 September 14, 2021 4.0 References

1. Westinghouse Calculation Note, F-ME-C-000019, Rev. 00, Evaluation of CSB Repair Plug Preloads for RSG and License Renewal, September 20, 2001.

2. Westinghouse Calculation Note, CN-RIDA-09-4, Rev. 0, St. Lucie Unit 1 EPU Evaluation of CSB Repair Plug Preload, March 31, 2009.

3. Westinghouse Calculation Note, CN-RIDA-09-9, Rev. 1, St. Lucie Unit 1 EPU Reactor Vessel Internals Stress Analysis, August 30, 2013, as modified by:

(a) Assessment Record, CN-RIDA-09-9-R1-ASMT-1.

4. Combustion Engineering Calculation, 19367-640-60, Rev. 01, Calculation of Minimum Allowable Plug Flange Deflections, September 10, 1985.

5. Combustion Engineering Document, 19367-MD-GI-01, Rev. 05, Guidelines for Post Installation Inspection of Core Support Barrel Plugs and Patches, October 23, 1985.

6. Westinghouse Calculation Note, CN-SDA-II-20-026, Rev. 1, St. Lucie Unit 1 and Unit 2 80-Year Transient Cycle Projections, June 4, 2021.

7. Florida Power & Light Company Letter, PSLWEC-21-0013, Rev. 0, Design Input Transmittal for WS07a Other TLAAs to Support the St. Lucie Unit 1 and Unit 2 Subsequent License Renewal, February 24, 2021.

8. Westinghouse Calculation Note, CN-RIDA-14-114, Rev. 1, Design Reconciliation of St. Lucie Unit 2 Reactor Vessel Internals under Normal Operating plus Upset Conditions with AREVA Fuel, March 19, 2015.

9. Combustion Engineering Report, CEN-324 (F), Engineering Overview Report of St. Lucie Unit One Post Cycle Six Inspection, May 12, 1986.

10. Florida Power & Light Company Letter, L-2002-165, St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Response to NRC Request for Additional Information for Review of the St. Lucie Units 1 and 2 License Renewal Application, October 10, 2002. (ADAMS Accession Number ML022890450).

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LTR-SDA-20-104-NP Revision 3 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 DiFiore Michael A Sep-14-2021 14:19:26 Verifier Approval Delport Gerrie W Sep-14-2021 14:58:44 Manager Approval Rigby Stephen Sep-14-2021 15:28:51 Files approved on Sep-14-2021

- - This record was final approved on 9/14/2021 3:28:51 PM. (This statement was added by the PRIME system upon its validation)

St. Lucie Nuclear Plant Units 1 and 2 Dockets 50-335 and 50-389 L-2021-192 Enclosure 4 Enclosure 4 Non-proprietary Reference Documents and Redacted Versions of Proprietary Reference Documents (Public Version)

Attachment 13 Westinghouse Report LTR-SDA-20-099-NP, Revision 2, St. Lucie Units 1&2 Subsequent License Renewal:

Task 9E RCP Casing Code Case N-481 Evaluation, September 14, 2021 (21 Total Pages, including cover sheets)

St. Lucie Nuclear Plant Units 1 and 2 Dockets 50-335 and 50-389 L-2021-192 Enclosure 4 Enclosure 4 Non-proprietary Reference Documents and Redacted Versions of Proprietary Reference Documents (Public Version)

Attachment 14 Structural Integrity Report No. 2001262.402, Revision 1, Flaw Tolerance Evaluation of St. Lucie Units 1 and 2 CASS Components for SLR, July 15, 2021 (32 Total Pages, including cover sheets)

St. Lucie Nuclear Plant Units 1 and 2 Dockets 50-335 and 50-389 L-2021-192 Enclosure 4 Enclosure 4 Non-proprietary Reference Documents and Redacted Versions of Proprietary Reference Documents (Public Version)

Attachment 15 Framatome Document No. 86-9329648-000, St. Lucie SLR Crack Growth Analysis Summary - Non Proprietary, July 2, 2021 (19 Total Pages, including cover sheets)

St. Lucie Nuclear Plant Units 1 and 2 Dockets 50-335 and 50-389 L-2021-192 Enclosure 4 Enclosure 4 Non-proprietary Reference Documents and Redacted Versions of Proprietary Reference Documents (Public Version)

Attachment 16 Structural Integrity Report No. 2001262.401, Revision 1, Flaw Tolerance Evaluation of St. Lucie, Units 1 and 2 Surge Line Using ASME Code,Section XI, Appendix L for Subsequent License Renewal, July 15, 2021 (9 Total Pages, including cover sheets)

L-2021-192, Westinghouse, Report LTR-REA-21-1-NP, Revision 1, St. Lucie Units 1 & 2 Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 2021

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