Text

Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule
	ML23193A368
Person / Time
Site:	Robinson
Issue date:	07/12/2023
From:	Basta L; Duke Energy Progress
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
References
	RA-23-0141
	Download: ML23193A368 (1)
	v • d • e

Laura A. Basta H. B. Robinson Steam Electric Plant Unit No. 2 Site Vice President Duke Energy 3581 West Entrance Road Hartsville, SC 29550 843 951 1701 Laura.Basta@duke-energy.com Serial: RA-23-0141 10 CFR 50, Appendix H July 12, 2023 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 / RENEWED LICENSE NO. DPR-23

SUBJECT:

REVISION TO REACTOR VESSEL SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE

REFERENCES:

1. Duke Energy letter, Revision to Reactor Vessel Surveillance Capsule Removal Schedule, dated May 2, 2019 (ADAMS Accession No. ML19122A012)

2. Duke Energy letter, Revised Response to Request for Additional Information (RAI)

Regarding Reactor Pressure Vessel (RPV) Surveillance Capsule Removal, dated December 19, 2019 (ADAMS Accession No. ML19353C963)

3. NRC letter, H. B. Robinson Steam Electric Plant, Unit No. 2 - Request for Revision to Reactor Vessel Material Surveillance Capsule Withdrawal Schedule (EPID L-2019-LLL-0021), dated February 19, 2020 (ADAMS Accession No. ML20021A013)

Ladies and Gentlemen:

Pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Appendix H, "Reactor Vessel Material Surveillance Program Requirements," Paragraph III.B.3, Duke Energy Progress, LLC (Duke Energy) is requesting Nuclear Regulatory Commission (NRC) approval of the enclosed revision to the reactor vessel surveillance capsule withdrawal schedule for H. B.

Robinson Steam Electric Plant, Unit No. 2 (RNP).

By letter dated May 2, 2019 (Reference 1), Duke Energy requested a revision to the reactor vessel material surveillance capsule withdrawal schedule that applies to RNP. The proposed change to the withdrawal schedule for capsule U was necessary to accommodate a migration to 24-month operating cycles and a design change that eliminated part length shield assemblies in the reactor design for the unit. As noted in Duke Energys revised response to a request for additional information (Reference 2), Duke Energy made the following regulatory commitment:

Capsule U will be withdrawn at either 41.3 effective full-power years (EFPY) or during the scheduled refueling outage after the capsule achieves a neutron fluence exposure equal to the peak, projected inside surface fluence for the reactor pressure vessel at 80-years operation.

The NRC approved the revised withdrawal schedule in its safety evaluation (SE) dated February 19, 2020 (Reference 3).

U.S. Nuclear Regulatory Commission RA-23-0141 Page 2 However, a recent fluence analysis in support of the development of a subsequent license renewal application (SLRA) for RNP indicates that capsule U will not achieve a neutron fluence exposure equal to the peak, projected inside surface fluence for the reactor vessel at 80 years of operation if the capsule is withdrawn at 41.3 EFPY. Therefore, Duke Energy requests NRC approval to revise the capsule U withdrawal schedule. An evaluation of this proposed change is provided in Enclosure 1.

The proposed reactor vessel surveillance capsule U withdrawal schedule is described in Westinghouse document CPL-RV000-TM-ME-000001, Revision 1, "H.B. Robinson Unit 2:

Recommended Changes to the Surveillance Capsule Withdrawal Schedule" (provided as ). CPL-RV000-TM-ME-000001, Revision 1 includes an assessment of the impacts of the recent fluence analysis, described in Westinghouse document CPL-REAC-TM-AA-000001, Revision 1, "H. B. Robinson Unit 2 Subsequent License Renewal: Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data" (provided as Attachment 2), on the capsule U withdrawal schedule. Table 4 of CPL-RV000-TM-ME-000001, Revision 1, provides the changes to the surveillance capsule withdrawal schedule needed to satisfy the requirements of American Society for Testing and Materials (ASTM) E 185-82, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels," dated July 1, 1982. of this correspondence contains the following regulatory commitment:

Capsule U will be withdrawn at either 44.4 effective full-power years (EFPY) or during the scheduled refueling outage after the capsule achieves a neutron fluence exposure equal to the peak, projected inside surface fluence for the reactor pressure vessel at 80 years of operation.

The proposed commitment replaces the existing commitment for capsule U to be withdrawn at either 41.3 EFPY or during the scheduled refueling outage after the capsule achieves a neutron fluence exposure equal to the peak, projected inside surface fluence for the reactor pressure vessel at 80-years operation.

Approval of this proposed change is requested by January 31, 2024 to allow scheduling of contract services for the Fall 2024 refueling outage, if necessary.

Should you have any questions concerning this letter, or require additional information, please contact Ryan Treadway, Director - Nuclear Fleet Licensing, at 980-373-5873.

Sincerely, Laura A. Basta Site Vice President : Evaluation of the Proposed Change : Regulatory Commitment 2

U.S. Nuclear Regulatory Commission RA-23-0141 Page 3 3

Westinghouse Report CPL-RV000-TM-ME-000001, Revision 1, H.B. Robinson Unit 2: Recommended Changes to the Surveillance Capsule Withdrawal Schedule : Westinghouse Report CPL-REAC-TM-AA-000001, Revision 1, H. B. Robinson Unit 2 Subsequent License Renewal: Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data cc:

(all with Enclosures/Attachments unless otherwise noted)

L. Dudes, Regional Administrator USNRC Region II J. Zeiler, USNRC Senior Resident Inspector L. Haeg, NRR Project Manager M. Mahoney, NRR Project Manager RA-23-0141 1

ENCLOSURE 1 EVALUATION OF THE PROPOSED CHANGE

Subject:

REVISION TO REACTOR VESSEL SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE

1.0 INTRODUCTION

.............................................................................................................. 2

2.0 BACKGROUND

................................................................................................................ 2 3.0 CURRENT RVSP WITHDRAWAL SCHEDULE FOR RNP.............................................. 4 4.0 PROPOSED RVSP WITHDRAWAL SCHEDULE FOR RNP........................................... 4 5.0 TECHNICAL JUSTIFICATION.......................................................................................... 5 6.0 PRECEDENT.................................................................................................................... 6

7.0 REFERENCES

................................................................................................................. 7 RA-23-0141 2

1.0 INTRODUCTION

This evaluation supports a request from Duke Energy Progress, LLC (Duke Energy) to revise the reactor vessel surveillance program (RVSP) capsule withdrawal schedule for the H. B.

Robinson Steam Electric Plant, Unit No. 2 (RNP).

The proposed revision would align the RNP surveillance capsule U withdrawal schedule with recent projections of neutron fluence for the unit at 80 years of operation while still satisfying the requirements of American Society for Testing and Materials (ASTM) E 185-82, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels (Reference 1). The RNP reactor vessel surveillance capsule withdrawal schedule presently includes removal and subsequent testing of surveillance capsule U at either 41.3 effective full-power years (EFPY) or during the scheduled refueling outage after the capsule achieves a neutron exposure equal to the peak, projected inside surface fluence for the reactor vessel at 80 years of operation. However, a recent fluence analysis in support of the development of a subsequent license renewal application (SLRA) for RNP has indicated that capsule U will not achieve a neutron fluence exposure equal to the peak, projected inside surface fluence for the reactor vessel at 80 years of operation if the capsule is withdrawn at 41.3 EFPY. Although the recent fluence analysis was performed to support the development of a SLRA, as stated in Attachment 2, the methodology used has been generically approved by the NRC for calculating exposures to the reactor vessel beltline and extended beltline and is therefore applicable to the existing licensing basis. RNP is requesting approval to revise the reactor vessel surveillance capsule withdrawal schedule to withdraw capsule U at either 44.4 EFPY or during the scheduled refueling outage after the capsule achieves a neutron fluence exposure equal to the peak, projected inside surface fluence for the reactor vessel at 80 years of operation.

This submittal is made in accordance with the provision of 10 CFR 50, Appendix H, "Reactor Vessel Material Surveillance Program Requirements (Reference 2). Paragraph III.B.3 specifies that a proposed withdrawal schedule must be submitted with a technical justification as specified by 10 CFR 50.4, and that the proposed schedule must be approved prior to implementation.

2.0 BACKGROUND

The NRC has established requirements and criteria in 10 CFR 50.60, Acceptance Criteria for Fracture Prevention Measures for Lightwater Nuclear Power Reactors for Normal Operation (Reference 3), for protecting reactor vessels against fracture. The rule requires the reactor vessel material surveillance program meet the requirements set forth in 10 CFR 50, Appendix H.

10 CFR 50, Appendix H provides the NRC staffs criteria for the design and implementation of the reactor vessel material surveillance programs for operating reactors. The rule, in part, requires reactor vessel surveillance program designs and withdrawal schedules to meet the requirements of ASTM E 185, which is current on the issue date of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code to which the reactor vessel was purchased, although later editions of ASTM E 185 may be used inclusive of the 1982 Edition of ASTM E 185 (ASTM E 185-82). This rule also requires proposed reactor vessel surveillance programs to be submitted to the NRC and approved prior to implementation.

In NRC Administrative Letter (AL) 97-04, "NRC Staff Approval for Changes to 10 CFR Part 50, Appendix H, Reactor Vessel Surveillance Specimen Withdraw Schedules" (Reference 4), the RA-23-0141 3

Commission found that while 10 CFR Part 50, Appendix H, requires prior NRC approval for all withdrawal schedule changes, only certain changes require the NRC staff to review and approve the changes through the NRC's license amendment (10 CFR 50.90) process.

Specifically, only those changes that are not in conformance with the ASTM standard referenced in 10 CFR Part 50, Appendix H (i.e., ASTM E 185), are required to be approved through the license amendment process, whereas changes that are determined to conform to the ASTM standard only require that the NRC staff document its review and verification of such conformance.

The request is also submitted to satisfy RNP renewed operating license condition 3.L "Reactor Vessel Surveillance," which states:

All capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of ASTM E 185-82 to the extent practicable for the configuration of the specimens in the capsule. Any changes to the capsule withdrawal schedule, including spare capsules, must be approved by the NRC prior to implementation. All capsules placed in storage must be maintained for future insertion.

Any changes to storage requirements must be approved by the NRC.

The Electric Power Research Institute (EPRI) developed a Coordinated Reactor Vessel Surveillance Program (CRVSP) for PWRs for the purpose of increasing the population of higher-fluence surveillance data (> 3E+1019 n/cm2, E>1 MeV). The program is documented in EPRI Technical Report, Materials Reliability Program: Coordinated PWR Reactor Vessel Surveillance Program (CRVSP) Guidelines (MRP-326, Revision 1)," dated 2021 (Reference 5).

The general premise of the program is to defer the withdrawal of certain capsules (e.g., those capsules which can provide high-fluence data for specific materials of interest before ~2025) while maintaining compliance with 10 CFR 50, Appendix H and the license renewal guidance provided in NUREG-1801, Revision 2, "Generic Aging Lessons Learned (GALL) Report" (Reference 6). NUREG-1801, Revision 2, is cited because it recommends license renewal capsule testing be performed between one and two times the 60-year peak reactor vessel fluence, as compared to guidance in NUREG-1801, Revision 1, to test the capsule at the 60-year fluence.

By letter dated September 28, 2011 (Reference 7), Duke Energy requested NRC review and approval of a revision to the RNP reactor vessel surveillance capsule withdrawal schedule. The requested change was submitted in accordance with the provision of 10 CFR 50, Appendix H, Paragraph III.B.3, and MRP-326, Revision 0 (Reference 8). The NRC approved the revised reactor vessel surveillance capsule withdrawal schedule in its safety evaluation (SE) dated December 21, 2011 (Reference 9).

By letter dated February 7, 2018 (Reference 10), Duke Energy submitted a license amendment request (LAR) for RNP to revise Technical Specification (TS) 3.4.3, "RCS Pressure and Temperature (P/T) Limits," to reflect that Figures 3.4.3-1 and 3.4.3-2 (P/T limit curves) are applicable up to 46.3 EFPY instead of 50 EFPY with the removal of part length shield assemblies (PLSAs) and migration to 24-month fuel cycles. The NRC approved the revised P/T limit curves in its SE dated August 16, 2018 (Reference 11). The proposed reactor vessel surveillance capsule withdrawal schedule was developed in Attachment 2 of Reference 10 (WCAP-18215, "H.B. Robinson Unit 2 End-of-License Extension Reactor Vessel Integrity Evaluations and Feasibility Study), which includes an evaluation of RNP reactor vessel integrity under the scenario that includes a migration to 24-month fuel cycles and no additional use of PLSAs. Table 7-2 of WCAP-18215 provides the corresponding changes to the surveillance capsule withdrawal schedule required to satisfy the requirements of ASTM E 185-82. In accordance with Paragraph III.B.3 of 10 CFR 50, Appendix H, Duke Energy requested this RA-23-0141 4

change to the capsule withdrawal schedule by letter dated May 2, 2019 (Reference 12) and supplemented by letters dated November 13, 2019 (Reference 13), and December 19, 2019 (Reference 14). The NRC approved the revised withdrawal schedule in its SE dated February 19, 2020 (Reference 15).

3.0 CURRENT RVSP WITHDRAWAL SCHEDULE FOR RNP The currently approved reactor vessel surveillance capsule withdrawal schedule, provided in Section 5.3.1.6 of the RNP Updated Final Safety Analysis Report (UFSAR), is as follows:

The following tabulates the remaining schedule for removal of the Reactor Vessel Materials Surveillance Capsules U, Y, and W:

Capsule Effective Full Power Years U (See Note 1) 41.3 Y (See Note 2)

Reserve W (See Note 2)

Reserve Note 1:

Capsule to location 280° at Cycle 8. Capsule will reach a fluence of approximately 8.09 x 1019 n/cm2 (66 EFPY peak fluence) at approximately 41.3 EFPY. Capsule U will be withdrawn at 41.3 EFPY or during the scheduled refueling outage after the capsule achieves a neutron fluence exposure equal to the peak, projected inside surface fluence for the reactor pressure vessel at 80-years operation.

Note 2:

Capsule Y was relocated to the 290° holder position and Capsule W was relocated to the 270° holder position during RO-27.

4.0 PROPOSED RVSP WITHDRAWAL SCHEDULE FOR RNP With consideration of 60 years of operation (50 EFPY), a total of five capsules must be withdrawn to satisfy ASTM E 185-82 and to meet the guidance in NUREG-1801, Revision 2.

RNP has removed and tested four surveillance capsules. To satisfy the surveillance capsule provisions of ASTM E 185-82, as required by 10 CFR 50, Appendix H, through end-of-license (EOL) (50 EFPY), one additional surveillance capsule must be withdrawn. As indicated in Section 3.0, the current RVSP withdrawal schedule states capsule U will be withdrawn at 41.3 EFPY or during the scheduled refueling outage after the capsule achieves a neutron fluence exposure equal to the peak, projected inside surface fluence for the reactor pressure vessel at 80-years operation. However, a recent fluence analysis (Attachment 2) to support the intent to submit a SLRA (Reference 16) indicates that capsule U will not achieve a neutron fluence exposure equal to the peak, projected inside surface fluence for the reactor pressure vessel at 80 years of operation if the capsule is withdrawn at 41.3 EFPY. To satisfy the 5th capsule requirement and ensure the capsule achieves a neutron fluence consistent with 80 years of operation, RNP proposes to withdraw capsule U at either 44.4 EFPY or during the scheduled refueling outage after the capsule achieves a neutron fluence exposure equal to the peak, projected inside surface fluence for the reactor pressure vessel at 80 years of operation.

The proposed RVSP withdrawal schedule for RNP is consistent with the recommendations of CPL-RV000-TM-ME-000001, Revision 1, H.B. Robinson Unit 2: Recommended Changes to the Surveillance Capsule Withdrawal Schedule, Table 4 (included as Attachment 1 of this letter).

The proposed revised withdrawal schedule is as follows:

RA-23-0141 5

Capsule Effective Full Power Years U (See Note 1) 44.4 Y (See Note 2)

Reserve W (See Note 2)

Reserve Note 1:

Capsule to location 280° at Cycle 8. Capsule will reach a fluence of approximately 8.85 x 1019 n/cm2 (70 EFPY peak fluence) at approximately 44.4 EFPY. Capsule U will be withdrawn at either 44.4 EFPY or during the scheduled refueling outage after the capsule achieves a neutron fluence exposure equal to the peak, projected inside surface fluence for the reactor pressure vessel at 80 years of operation.

Note 2:

Capsule Y was relocated to the 290° holder position and Capsule W was relocated to the 270° holder position during RO-27.

Upon NRC approval, the UFSAR will be updated to reflect this change.

5.0 TECHNICAL JUSTIFICATION Section 7.6 of ASTM E 185-82 provides the requirements for the number of surveillance capsules and withdrawal schedule. The standard requires a sufficient number of surveillance capsules be provided to monitor the effects of neutron irradiation on the reactor vessel throughout its operating lifetime and a withdrawal schedule to meet the monitoring requirements. Table 1 of ASTM E 185-82 requires that the EOL capsule must be withdrawn during a window of time when the capsule fluence is not less than once or greater than twice the peak (EOL) vessel fluence. The proposed revision to the surveillance capsule withdrawal schedule will ensure that capsule U accumulates sufficient fluence to meet the requirements of ASTM E 185-82.

RNP is currently licensed to operate for 60 years. RNP entered the period of extended operation in August of 2010. NUREG-1801, Revision 2, provides guidance related to the reactor vessel surveillance program for first license renewal.Section XI.M31, Program Element 4, states:

"The plant-specific or integrated surveillance program shall have at least one capsule with a projected neutron fluence equal to or exceeding the 60-year peak reactor vessel wall neutron fluence prior to the end of the period of extended operation. The program withdraws one capsule at an outage in which the capsule receives a neutron fluence of between one and two times the peak reactor vessel wall neutron fluence at the end of the period of extended operation and tests the capsule in accordance with the requirements of ASTM E 185-82." and "Plant-specific and fleet operating experience should be considered in determining the withdrawal schedule for all capsules..."

As reported in CPL-RV000-TM-ME-000001, Revision 1 (Attachment 1), the recent fluence projections in support of the development of a SLRA and described in CPL-REAC-TM-AA-000001, Revision 1 (Attachment 2), have changed since the current surveillance capsule withdrawal schedule was developed. Attachments 1 and 2 describe the updated fluence projections and how they were used to develop the projected peak 60-year and 80-year vessel fluences that align with the capsule withdrawal window requirements in ASTM E 185-82 and the guidance provided in NUREG-1801, Revision 2. The projected peak vessel neutron fluence values are as follows:

RA-23-0141 6

For 60 years:

One times the peak vessel wall neutron fluence: 6.19 x 1019 n/cm2

Two times the peak vessel wall neutron fluence: 1.24 x 1020 n/cm2 For 80 years:

One times the peak vessel wall neutron fluence: 8.85 x 1019 n/cm2 Two times the peak vessel wall neutron fluence: 1.77 x 1020 n/cm2 Surveillance capsule U is projected to attain a fluence of 8.85 x 1019 n/cm2 at 44.4 EFPY, which is projected to occur on August 6, 2027. Capsule U will be withdrawn at 44.4 EFPY or during the scheduled refueling outage after the capsule achieves a neutron fluence exposure equal to the peak, projected inside surface fluence for the reactor pressure vessel at 80 years of operation. The next refueling outage after capsule U attains 44.4 EFPY is scheduled for Fall 2028. The proposed withdrawal schedule will ensure capsule U receives a neutron fluence of between one and two times the peak reactor vessel wall neutron fluence at the end of the period of extended operation. Therefore, the proposed withdrawal date for capsule U satisfies ASTM E 185-82 requirements and the NUREG-1801, Revision 2 guidance for license renewal.

As discussed in MRP-326, surveillance data representative of the extended license fluence levels is desirable for both RNP and the PWR fleet because that data can better inform future embrittlement trend curve development. MRP-326 Revision 0 (Reference 8) provided a recommendation that RNP capsule U should be removed during the first scheduled outage that follows estimated capsule exposure to the projected 80-year reactor pressure vessel peak fluence and the capsule should then be tested. MRP-326 Revision 1 (Reference 5) maintained the recommendation from Revision 0 and stated that the prior capsule U withdrawal schedule change (Reference 12) was consistent with the principles behind the recommendation of the CRVSP since RNP capsule U will be withdrawn as soon as an 80-year peak reactor pressure vessel fluence is obtained. Since recent fluence projections described in Attachments 1 and 2 have changed the timing in which capsule U is expected to achieve the 80-year peak reactor vessel fluence, the revised capsule withdrawal schedule to align with this timing is consistent with the recommendations of MRP-326.

NUREG-1801, Revision 2, is cited as it represents the latest guidance provided by the Staff. No request to revise the licensing basis of the RNP renewed operating license is implied by this citation; it is offered only as a reference and objective evidence to support the Technical Justification for the deferral.

6.0 PRECEDENT Similar requests for changes to a site-specific reactor vessel surveillance capsule schedule have been approved by the NRC. Although not an exhaustive industry listing, below are the Safety Evaluations (SE) reviewed as part of preparation of this request. Also included are the associated licensee letters that proposed the reactor vessel surveillance capsule schedule change.

1. Surry Power Station Units 1 and 2 (Dominion Energy):

Submittal dated July 28, 2017 (ADAMS Accession No. ML17213A080)

NRC SE dated December 10, 2018 (ADAMS Accession No. ML18318A062)

2. Watts Bar Nuclear Plant, Unit 2 (Tennessee Valley Authority):

Submittal dated September 5, 2017 (ADAMS Accession No. ML17248A420)

NRC SE dated November 20, 2017 (ADAMS Accession No. ML17312A260)

3. Arkansas Nuclear One, Unit 2 (Entergy):

RA-23-0141 7

Submittal dated September 14, 2017 (ADAMS Accession No. ML17257A121)

NRC SE dated June 27, 2018 (ADAMS Accession No. ML18173A019)

4. Beaver Valley, Unit 1 (FENOC):

Submittal dated October 6, 2017 (ADAMS Accession No. ML17284A195)

NRC SE dated July 2, 2018 (ADAMS Accession No. ML18164A082)

5. H.B. Robinson Steam Electric Plant, Unit 2 (Duke Energy)

Submittal dated May 2, 2019 (ADAMS Accession No. ML19122A012)

NRC SE dated February 19, 2020 (ADAMS Accession No. ML20021A013)

6. Watts Bar Nuclear Plant, Unit 2 (Tennessee Valley Authority):

Submittal dated January 24, 2022 (ADAMS Accession No. ML22024A450)

NRC SE dated November 14, 2022 (ADAMS Accession No. ML22293A408)

7.0 REFERENCES

1. American Society for Testing and Materials (ASTM) E 185-82, Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, dated July 1, 1982

2. 10 CFR 50, Appendix H, Reactor Vessel Material Surveillance Program Requirements

3. 10 CFR 50.60, Acceptance Criteria for Fracture Prevention Measures for Lightwater Nuclear Power Reactors for Normal Operation

4. NRC Administrative Letter 97-04, NRC Staff Approval for Changes to 10 CFR Part 50, Appendix H, Reactor Vessel Surveillance Specimen Withdrawal Schedules, dated September 30, 1997 (ADAMS Accession Number ML031210296)

5. Electric Power Research Institute technical report, Materials Reliability Program:

Coordinated PWR Reactor Vessel Surveillance Program (CRVSP) Guidelines (MRP-326, Revision 1), dated 2021

6. U.S. NRC, Generic Aging Lessons Learned (GALL) Report, NUREG-1801, Revision 2, December 2010 (ADAMS Accession Number ML103490041)

7. Duke Energy letter, Revision to Reactor Vessel Surveillance Capsule Removal Schedule, dated September 28, 2011 (ADAMS Accession No. ML11276A002)

8. Electric Power Research Institute technical report, Materials Reliability Program:

Coordinated PWR Reactor Vessel Surveillance Program (CRVSP) Guidelines (MRP-326),

dated 2011

9. NRC letter, H. B. Robinson Steam Electric Plant, Unit No. 2 - Request for Revision to Reactor Vessel Material Surveillance Capsule Withdrawal Schedule (TAC No. ME7533),

dated December 21, 2011 (ADAMS Accession No. ML11349A026)

10. Duke Energy letter, License Amendment Request Proposing to Revise Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits, dated February 7, 2018 (ADAMS Accession No. ML18038B289)

11. NRC letter, H. B. Robinson Steam Electric Plant, Unit No. 2 - Issuance of Amendment No.

260 Regarding Request to Revise Technical Specification Reactor Coolant System Pressure and Temperature Limits to Reflect 24-Month Fuel Cycles (EPID L-2017-LLA-0033), dated August 16, 2018 (ADAMS Accession No. ML18200A042)

12. Duke Energy letter, Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule, dated May 2, 2019 (ADAMS Accession No. ML19122A012)

13. Duke Energy letter, Response to Request for Additional Information (RAI) Regarding Reactor Pressure Vessel (RPV) Surveillance Capsule Removal (RA-19-0145), dated November 13, 2019 (ADAMS Accession No. ML19317D072)

RA-23-0141 8

14. Duke Energy letter, Revised Response to Request for Additional Information (RAI)

Regarding Reactor Pressure Vessel (RPV) Surveillance Capsule Removal, dated December 19, 2019 (ADAMS Accession No. ML19353C963)

15. NRC letter, H. B. Robinson Steam Electric Plant, Unit No. 2 - Request for Revision to Reactor Vessel Material Surveillance Capsule Withdrawal Schedule (EPID L-2019-LLL-0021), dated February 19, 2020 (ADAMS Accession No. ML20021A013)

16. Duke Energy letter, Notice of Intent to Pursue Subsequent License Renewal for H. B.

Robinson Steam Electric Plant, Unit Number 2, dated March 24, 2023 (ADAMS Accession No. ML23083B312)

RA-23-0141 1

ENCLOSURE 2 REGULATORY COMMITMENT

Subject:

REVISION TO REACTOR VESSEL SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE The action in this document committed to by H. B. Robinson Steam Electric Plant, Unit No. 2 (RNP), is identified in the following table. Statements in this submittal, with the exception of those in the table below, are provided for information purposes and are not considered Regulatory Commitments. Please direct any questions regarding this document or any associated regulatory commitments to Ryan Treadway, Director - Nuclear Fleet Licensing.

Item Commitment 1

Capsule U will be withdrawn at either 44.4 effective full-power years (EFPY) or during the scheduled refueling outage after the capsule achieves a neutron fluence exposure equal to the peak, projected inside surface fluence for the reactor pressure vessel at 80 years of operation.

to RA-23-0141 Westinghouse Report CPL-RV000-TM-ME-000001, Revision 1, H.B. Robinson Unit 2:

Recommended Changes to the Surveillance Capsule Withdrawal Schedule

- - This record was final approved on 4/3/2023, 1:16:26 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 Westinghouse Electric Company 302 Building 1332 Beulah Road Pittsburgh, Pennsylvania 15235-5081 USA

Subject:

H.B. Robinson Unit 2: Recommended Changes to the Surveillance Capsule Withdrawal Schedule

Attachment:

A. Recommended H.B. Robinson Unit 2 Surveillance Capsule Withdrawal Schedule This letter transmits the changes recommended to the H.B. Robinson Unit 2 capsule withdrawal schedule.

Attachment A provides technical justification and demonstrates schedule compliance with the applicable version(s) of American Society for Testing and Materials (ASTM) E185. Note that these recommended schedules support the current H.B. Robinson Unit 2 60-year license.

The purpose of Revision 1 of this letter is to reference and provide updates based on the issuance and transmittal to the customer of CPL-REAC-TM-AA-000001, Revision 1, H.B. Robinson Unit 2 Subsequent License Renewal: Reactor Vessel, Vessel Supports, and Bioshield Concrete Exposure Data.

Do not hesitate to contact the undersigned with any questions regarding the contents of this letter.

Electronically Approved*

Author: Derek A. Simpson Reviewed: Donald M. McNutt III License Renewal, Radiation Analysis, & Nuclear Operations Reactor Vessel/Containment Vessel Design & Analysis Electronically Approved*

Approved: Lynn A. Patterson, Manager Reactor Vessel/Containment Vessel Design & Analysis 1Electronically approved records are authenticated in the electronic document management system.

- - This record was final approved on 4/3/2023, 1:16:26 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 CPL-RV000-TM-ME-000001, Rev. 1 Attachment A Page 1 of 13 Attachment A Recommended H.B. Robinson Unit 2 Surveillance Capsule Withdrawal Schedule

- - This record was final approved on 4/3/2023, 1:16:26 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 CPL-RV000-TM-ME-000001, Rev. 1 Attachment A Page 2 of 13 This attachment provides the recommended capsule withdrawal schedule for H.B. Robinson Unit 2 (HBR2). This includes demonstration of the schedules compliance with ASTM E185, as prescribed by 10 CFR 50, Appendix H [Ref. 2] with consideration to NUREG-1801 (GALL) [Ref. 7].

10 CFR 50, Appendix H [Ref. 2] states:

The design of the surveillance program and the withdrawal schedule must meet the requirements of the edition of ASTM E 185 that is current on the issue date of the ASME Code to which the reactor vessel was purchased; for reactor vessels purchased after 1982, the design of the surveillance program and the withdrawal schedule must meet the requirements of ASTM E 185-82.

For reactor vessels purchased in or before 1982, later editions of ASTM E 185 may be used, but including only those editions through 1982. For each capsule withdrawal, the test procedures and reporting requirements must meet the requirements of ASTM E 185 to the extent practicable for the configuration of the specimens in the capsule.

The reactor vessel was designed and constructed to Section III of the 1965 Edition of the ASME Code through the Summer 1965 Addenda. Thus, per 10 CFR 50, Appendix H, the surveillance program withdrawal schedule may meet the requirements of any version of the ASTM E185 standard from the 1966 version (the version which was current on the issue date of the ASME Codes to which the reactor vessel was purchased) through the 1982 version.

Per WCAP-8249 [Ref. 12], the surveillance capsule program was designed to ASTM E185-66 [Ref. 5],

which was the version active at that time the program was developed. Therefore, the requirements of 10 CFR 50, Appendix H were met at the time of the design of the reactor vessel surveillance program.

H.B. Robinson Unit 2 has satisfied the requirements of ASTM E185-82 [Ref. 1] for the first four (4) surveillance capsules, which were pulled to satisfy a 40-year life. A capsule removal schedule was developed in WCAP-18215-NP [Ref. 8] for a 60-year license, which was accepted by the NRC in ML20021A013 [Ref. 13]. This submittal stated that Capsule U would be withdrawn at 41.3 EFPY or during the scheduled refueling outage after the capsule achieves a neutron fluence exposure equal to the peak, projected inside surface fluence for the reactor pressure vessel at 80 years of operation. However, the fluence projections that supported this NRC submittal have changed and, thus, further updates to the capsule withdrawal schedule are necessary in order to ensure that Capsule U meets the requirements for withdrawal at a fluence equivalent to 80 years. It should be noted that the updated fluence analysis in CPL-REAC-TM-AA-000001 [Ref. 17] resulted in no new materials violating the 10 CFR 50, Appendix G

[Ref. 16] or 10 CFR 50.61 [Ref. 15] requirements. In addition, the fluence for the limiting materials associated with the RVI evaluations performed in WCAP-18215-NP [Ref. 8] have decreased and, therefore; the P-T limit curves, upper-shelf energy (USE), and pressurized thermal shock (PTS) conclusions remain valid at 60 years (50 EFPY).

Per WCAP-7373 [Ref. 4], the Robinson Unit 2 reactor contains two types of capsules, referred to as Type I and Type II. Type I capsules contain eight (8) Charpy specimens from each of the three (3) intermediate shell reactor vessel plates. Type II capsules contain eight (8) Charpy specimens from one (1) reactor vessel plate, eight (8) specimens of weld metal, and eight (8) specimens of HAZ metal. Table 1 contains a summary of this capsule information. The Type I capsules that have been withdrawn include capsules S and Z. The Type II capsules that have been withdrawn include capsules V, T, and X. The

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Westinghouse Non-Proprietary Class 3 CPL-RV000-TM-ME-000001, Rev. 1 Attachment A Page 3 of 13 remaining Robinson Unit 2 capsules (U, Y, and W) are all Type I capsules. Capsule Z is omitted from Table 1, as it was inadvertently removed from the reactor vessel per WCAP-15805 [Ref.11]. Correlation monitor and heat-affected zone materials are also omitted from Table 1.

Table 1 H.B. Robinson Unit 2 Surveillance Capsule Contents(a)

Capsule Capsule Type Materials S

I Intermediate Shell Plates W10201-4/5/6 (Heat #s A6604-1, B1256-1, B1250-1)

Correlation Monitor Material V

II Intermediate Shell Plate W10201-5 (Heat # B1256-1)

Weld Metal (Heat # W-5214)

Heat Affected Zone Correlation Monitor Material T

II Intermediate Shell Plate W10201-6 (Heat # B1250-1)

Weld Metal (Heat # W-5214)

Heat Affected Zone Correlation Monitor Material X

II Intermediate Shell Plate W10201-4 (Heat # A6604-1)

Weld Metal (Heat # W-5214)

Heat Affected Zone Correlation Monitor Material U

I Intermediate Shell Plates W10201-4/5/6 (Heat #s A6604-1, B1256-1, B1250-1)

Correlation Monitor Material Y

I Intermediate Shell Plates W10201-4/5/6 (Heat #s A6604-1, B1256-1, B1250-1)

Correlation Monitor Material W

I Intermediate Shell Plates W10201-4/5/6 (Heat #s A6604-1, B1256-1, B1250-1)

Correlation Monitor Material Note for Table 1:

(a) Information taken from WCAP-7373 [Ref. 4] and WCAP-18215-NP [Ref. 8].

ASTM E185-82 Schedule Recommendations The H.B. Robinson Unit 2 Reactor Vessel fluence model which supported the previous schedule change request has been updated. In order to comply with the intent of that schedule, which committed to pull Capsule U at the 80-year peak reactor vessel fluence, a schedule change is required. Table 2 contains the fluence data required to evaluate surveillance capsule withdrawal schedule. Table 4 of this letter contains

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Westinghouse Non-Proprietary Class 3 CPL-RV000-TM-ME-000001, Rev. 1 Attachment A Page 4 of 13 the recommended surveillance capsule withdrawal schedule for updating UFSAR Section 5.3.1.6 [Ref. 3].

The schedule satisfies the regulatory requirements of the Reactor Surveillance Program for 60 years and meets ASTM E185-82 [Ref. 1] as required by 10 CFR 50, Appendix H [Ref. 2].

Per WEC-DUKE-RNP-SLR-22-003 [Ref. 10], 70 EFPY is the applicable term to be used for 80-year reactor vessel integrity calculations. 70 EFPY corresponds to a maximum 80-year fluence of 8.85 x 1019 n/ cm2 and two times the maximum 60-year (50 EFPY) fluence of 1.24 x 1020 n/cm2 (2 x 6.19 x 1019 n/cm2). It should be noted that the maximum fluence projections utilize a 10% positive bias on the relative power of the peripheral and re-entrant corner fuel assemblies. For conservatism, this bias is not applied to the surveillance capsule fluence projections.

As outlined in UFSAR Section 5.3.1.6 and WCAP-18215-NP, H.B. Robinson plans to withdraw Capsule U at approximately 41.3 EFPY or during the scheduled refueling outage after the capsule achieves a neutron fluence exposure equal to the peak, projected inside surface fluence for the reactor pressure vessel at 80 years of operation in order to satisfy NUREG-1801 and ASTM E185-82 requirements for 60 years of operation.

Capsule U is projected to reach the 80-year fluence at 44.4 EFPY and two times the maximum 60-year fluence at 59.1 EFPY. Assuming 28-day outages during each 24-month operating cycle, Capsule U is projected to reach 44.4 EFPY on 8/6/2027 during cycle 36. Capsule U should be exposed (at a minimum) to the peak 80-year fluence, but it should be withdrawn prior to reaching two times the 60-year fluence. By withdrawing Capsule U after 44.4 EFPY but prior to 59.1 EFPY, Capsule U will have a fluence value greater than the peak 80-year fluence and still less than two times the 60-year fluence and, thus; Capsule U will satisfy the withdrawal requirements for the 60-year operating period as well as the 80-year fluence.

Fluence projections out to 100-years are also considered. The projected 100-year (assuming 90 EFPY) peak reactor vessel fluence is 1.16 x 1020 n/cm2. Note that per WEC-DUKE-RNP-SLR-22-003 [Ref. 10], the estimated 100-year term was calculated to be 85.7 EFPY, which is projected to be reached on 7/31/2070 during cycle 57. However, 90 EFPY is assumed as the 100-year term in this letter, as the results are bounding with respect to 85.7 EFPY.

Capsule W is projected to reach the 100-year fluence at 59.7 EFPY, which is projected to be reached on 7/5/2043 during cycle 44. It is recommended that Capsule W be exposed (at a minimum) to the peak 100-year fluence of 1.16 x 1020 n/cm2. By withdrawing Capsule W after 59.7 EFPY, Capsule W will have a fluence value greater than the peak 100-year fluence and, thus; Capsule W will satisfy the withdrawal requirements for the 100-year operating period.

Based on the location of Capsule Y, it is being irradiated at a lead factor of less than 1.0 and currently has a fluence less than the current peak reactor vessel fluence. Therefore, for this capsule to provide meaningful data in the future (i.e., exceed the peak reactor vessel fluence), it is recommended that Capsule Y be relocated to the 0° location (with respect to core cardinal axes) during the outage in which Capsule U is withdrawn, which is recommended to be completed during the first refueling outage after Capsule U reaches 44.4 EFPY (EOC 36, Fall 2028). If relocated during this time, Capsule Y will reach the projected 120-year fluence and will be available for withdrawal after EOC 49 in 2054 (See Table 3). Additional Capsule Y relocation recommendations are also provided in Table 3.

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Westinghouse Non-Proprietary Class 3 CPL-RV000-TM-ME-000001, Rev. 1 Attachment A Page 5 of 13 Evaluation of Compliance with ASTM E185-82 The first step in determining the surveillance capsule withdrawal schedule compliance with ASTM E185-82 is to determine the minimum number of capsules to withdraw and/or test. ASTM E185-82 bases the number of capsules on the maximum RTNDT projected at the vessel surface for all reactor vessel materials. Since the predicted RTNDT shift of the H.B. Robinson Unit 2 RV material exceeds 200°F (see Table 5), a minimum of five (5) surveillance capsules are recommended to be withdrawn per ASTM E185-82. H.B. Robinson Unit 2 has satisfied the ASTM requirements for their first four (4) surveillance capsules, which were pulled to satisfy a 40-year operating life. Because ASTM E185 was written to address a 40-year operating life, appropriate changes discussed in NUREG-1801 (GALL) [Ref. 7] are considered for operation through 60 years. Note that one (1) of the five (5) capsules withdrawn (Capsule Z) was inadvertently removed from the reactor per WCAP-15805 [Ref. 11].

The next step is to demonstrate that the condition of the capsules tested, or scheduled to be tested, meet the requirements of ASTM E185-82. This comparison is performed in Table 6. This table demonstrates that the recommended schedule meets the recommendations of ASTM E185-82 as required by 10 CFR 50, Appendix H and the guidance in the GALL. Note that this table is included for information only, as the surveillance capsule program was designed to ASTM E185-66 [Ref. 5], as discussed in the next section.

Consideration of ASTM E185-66 The reactor vessel was designed and constructed to Section III of the 1965 Edition of the ASME Code through the Summer 1965 Addenda. Per WCAP-8249 [Ref. 12], the surveillance capsule program was designed to ASTM E185-66 [Ref. 5].

10 CFR 50, Appendix H [Ref. 2] requires the design of the surveillance program and the surveillance capsule withdrawal schedule to meet the requirements specified in the edition in the edition of ASTM E185 that is current on the issue date of the ASME Code to which the reactor vessel was purchased. While later editions up to ASTM E185-82 [Ref. 1] are permitted to be used for these objectives, they are not required with respect to the design phase.

Although the surveillance capsule program and surveillance capsule withdrawal schedule were designed to meet the requirements of ASTM E185-66, 10CFR50, Appendix H requires that for each capsule withdrawal, the procedures for performing tests of capsule specimens and for reporting test results must meet the requirements of ASTM E185-82 to the extent practical for the configuration of the specimens in the capsules.

ASTM E185-66 provides the following recommendations for specimen withdrawal:

Specimen Withdrawal - It is recommended that sets of specimens be withdrawn at three or more separate times. One of the data points obtained shall correspond to the neutron exposure of the component near the end of its design life.

H.B. Robinson Unit 2 exceeds the recommended number of withdrawn specimens, and upon implementation of the capsule withdrawal schedule contained herein, there is at least one (1) capsule that will be representative of the fluence at the end-of-life. Therefore, the requirements within ASTM E185-66 are met with consideration to 60 and 80 years of operation.

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Westinghouse Non-Proprietary Class 3 CPL-RV000-TM-ME-000001, Rev. 1 Attachment A Page 6 of 13 While H.B. Robinson Unit 2 is designed to ASTM E185-66, the criteria in ASTM E185-82 are satisfied with respect to the minimum number of surveillance capsules and their withdrawal schedule. As mentioned in the preceding section, the number of capsules required for withdrawal is based on the maximum projected RTNDT shift at the vessel inside surface. Three (3) capsules are recommended to be withdrawn when the predicted transition temperature shift at the vessel inside surface is 100°F, four (4) capsules when the predicted temperature shift is > 100°F and 200°F, and five (5) capsules when the predicted temperature shift is > 200°F. Since the predicted RTNDT shift of the H.B. Robinson Unit 2 RV material exceeds 200°F at 60 years (and will remain so at 80 years), a minimum of five (5) surveillance capsules are recommended to be withdrawn per ASTM E185-82. Per WCAP-7373 [Ref. 4], there were eight (8) capsules originally installed in the reactor vessel. To date, five (5) capsules have been withdrawn and tested, with three (3) capsules remaining for potential testing at higher fluences. Therefore, with the implementation of the recommended schedule, the requirements of ASTM E185-82 are also satisfied.

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Westinghouse Non-Proprietary Class 3 CPL-RV000-TM-ME-000001, Rev. 1 Attachment A Page 7 of 13 References

1. ASTM E185-82, Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, American Society for Testing and Materials, 1982.

2. Code of Federal Regulations 10 CFR 50, Appendix H, Reactor Vessel Material Surveillance Program Requirements, U.S. Nuclear Regulatory Commission, Federal Register, October 2020.

3. H.B. Robinson Unit 2 Updated Final Safety Analysis Report (UFSAR), Revision 30.

4. Westinghouse Report, WCAP-7373, Carolina Power and Light Co. H. B. Robinson Unit No. 2 Reactor Vessel Radiation Surveillance Program, January 1970.

5. ASTM E185-66, Recommended Practice for Surveillance Tests on Structural Materials in Nuclear Reactors, American Society for Testing and Materials, 1966.

6. U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Regulatory Guide 1.99, Revision 2, Radiation Embrittlement of Reactor Vessel Materials, May 1988. [ADAMS Accession Number ML003740284]

7. NUREG-1801, Revision 2, Generic Aging Lessons Learned (GALL) Report, U.S. Nuclear Regulatory Commission, December 2010. [ADAMS Accession Number ML103490041]

8. Westinghouse Report, WCAP-18215-NP, Revision 0, H.B. Robinson Unit 2 End-of-License Extension Reactor Vessel Integrity Evaluations and Feasibility Study, March 2017.

9. Westinghouse Report, WCAP-18215-P, Revision 0, H.B. Robinson Unit 2 End-of-License Extension Reactor Vessel Integrity Evaluations and Feasibility Study, March 2017.

10. WEC-DUKE-RNP-SLR-22-003, Design Input Request (DIR) Reactor Vessel (RV) Integrity (WS02), August 2022.

11. Westinghouse Report, WCAP-15805, Revision 0, Analysis of Capsule X from the Carolina Power &

Light Company H.B. Robinson Unit 2 Reactor Vessel Radiation Surveillance Program, March 2002.

12. Westinghouse Report, WCAP-8249, Analysis of Capsule S from Carolina Power and Light Co. H.B.

Robinson Unit No. 2 Reactor Vessel Radiation Surveillance Program, December 1973.

13. NRC Safety Evaluation, Safety Evaluation by the Office of Nuclear Reactor Regulation Related to Reactor Vessel Surveillance Program Withdrawal Schedule Revision, Duke Energy Progress, LLC, H.B. Robinson Steam Electric Plant, Unit 2, Docket No. 50-261, February 2020. [ADAMS Accession Number ML20021A013]

14. Duke Energy Document, RNP-2077-03-SLR-0510, Revision 0, Projection of Effective Full Power Years (EFPY) for Use in 80-Year Time-Limited Aging Analysis Evaluations for H.B. Robinson Unit 2 Subsequent License Renewal. [Attached in PRIME]

15. Code of Federal Regulations 10 CFR Part 50.61, Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events, U. S. Nuclear Regulatory Commission, Federal Register, November 29, 2019.

16. Code of Federal Regulations 10 CFR 50, Appendix G, Fracture Toughness Requirements, U.S.

Nuclear Regulatory Commission, Federal Register, November 29, 2019.

17. Westinghouse Letter, CPL-REAC-TM-AA-000001, Revision 1, H. B. Robinson Unit 2 Subsequent License Renewal: Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data.

February 2023.

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Westinghouse Non-Proprietary Class 3 CPL-RV000-TM-ME-000001, Rev. 1 Attachment A Page 8 of 13 Table 2 Evaluation of Surveillance Capsule Fluence Projections(a)

EFPY CYCLE(e)

DATE(e)

Capsule Fluence (n/cm2, E > 1.0 MeV)

Peak Vessel Fluence (n/cm2)

Notes U(b)

Y(c)

W(d) 38.07 7.41E+19 4.09E+19 4.34E+19 4.61E+19 EOC 32 (Fall 2020) 42 35 2/12/2025 8.28E+19 4.52E+19 5.64E+19 5.13E+19 44.4 36 8/6/2027 8.85E+19 4.79E+19 6.45E+19 5.45E+19 Cap U hits 80-year fluence (70 EFPY) 47.23 37 7/31/2030 9.19E+19 5.11E+19 6.97E+19 5.78E+19 60-year EOL 48 38 5/8/2031 9.68E+19 5.18E+19 7.64E+19 5.93E+19 50 39 6/4/2033 1.02E+20 5.40E+19 8.31E+19 6.19E+19 EOLE (50 EFPY) 54 41 7/30/2037 1.12E+20 5.84E+19 9.64E+19 6.73E+19 55.6 42 4/3/2039 1.16E+20 6.01E+19 1.02E+20 6.94E+19 Cap U hits 100-yr Fluence (90 EFPY) 59.1 44 12/12/2042 1.24E+20 6.41E+19 1.14E+20 7.41E+19 Cap U hits 2 X 50 EFPY EOLE Fluence 59.7 44 7/5/2043 1.25E+20 6.47E+19 1.16E+20 7.48E+19 Cap W hits 100-year Fluence (90 EFPY) 60 44 10/23/2043 1.26E+20 6.50E+19 1.16E+20 7.52E+19 66 47 1/14/2050 1.40E+20 7.16E+19 1.36E+20 8.32E+19 66.47 47 7/31/2050 1.40E+20 7.22E+19 1.37E+20 8.37E+19 80-year EOL 70 49 3/11/2054 1.49E+20 7.61E+19 1.49E+20 8.85E+19 80-year fluence (70 EFPY) 72 50 4/7/2056 1.54E+20 7.83E+19 1.56E+20 9.12E+19 81.3 55 12/13/2065 1.77E+20 8.85E+19 1.89E+20 1.04E+20 Cap U hits 2 X 80-year fluence (70 EFPY) 85.7 57 7/31/2070 1.88E+20 9.34E+19 2.04E+20 1.10E+20 100-year EOL 90 60 1/13/2075 1.99E+20 9.81E+19 2.19E+20 1.16E+20 100-year fluence (90 EFPY) 104.93 67 7/31/2090 2.36E+20 1.15E+20 2.72E+20 1.36E+20 120-year EOL Notes for Table 2:

(a) Fluence data is taken from CPL-REAC-TM-AA-000001 [Ref. 17].

(b) Capsule U was relocated from 30° to 280° (10° with respect to core cardinal axes) at EOC 8.

(c) Capsule Y was relocated from 150° (30° with respect to core cardinal axes) to 290° (20° with respect to core cardinal axes) at EOC 27.

(d) Capsule W was relocated from 40° to 270° (0° with respect to core cardinal axes) at EOC 27.

(e) Projected based on the data in RNP-2077-03-SLR-0510 [Ref. 14]

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Westinghouse Non-Proprietary Class 3 CPL-RV000-TM-ME-000001, Rev. 1 Attachment A Page 9 of 13 Table 3 Evaluation of Surveillance Capsule Y Relocation(a)

Peak Vessel Fluence(b)

(n/cm2, E > 1.0 MeV)

Relocation Timing Withdrawal Timing Capsule Fluence (n/cm2, E > 1.0 MeV) 1.36E+20 (120-Years, 104.93 EFPY) 45.56 EFPY (EOC 36, 2028) 70.57 EFPY (EOC 49, 2054) 1.40E+20 60.95 EFPY (EOC 44, 2044) 78.26 EFPY (EOC 53, 2062) 1.40E+20 72.49 EFPY (EOC 50, 2056) 89.80 EFPY (EOC 59, 2074) 1.39E+20 Notes for Table 3:

(a) It is assumed that Capsule Y will be moved to the 0° location (with respect to core cardinal axes).

(b) Fluence data taken from Table 2.

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Westinghouse Non-Proprietary Class 3 CPL-RV000-TM-ME-000001, Rev. 1 Attachment A Page 10 of 13 Table 4 H.B. Robinson Unit 2 Surveillance Capsule Withdrawal Schedule Capsule Azimuthal Location Lead Factor(a)

Removal Time (EFPY)

Capsule Fluence (n/cm2, E > 1.0 MeV)

S 280° 1.92 EOC 1 (1.34) 5.26 x 1018 V

290° 0.88 EOC 3 (3.33) 5.59 x 1018 T

270° 2.78 EOC 8 (7.53) 4.18 x 1019 X(e) 270° (50°)

1.54 EOC 20 (20.65) 4.43 x 1019 U(f) 280° (30°)

1.75 44.4(b) 8.85 x 1019(b)

Y(g) 290° (150°)

0.84 Standby (c)

W(h) 270° (40°)

2.50 Standby (c)

Z 230° 0.42 EOC 1 (1.34)

(d)

Notes for Table 4:

(a) Capsules S, V, T, X, and Z lead factors are representative of the entire irradiation period. Capsules U, Y, and W lead factors are the ratio of the fluence of the capsule at its current location to the maximum vessel fluence.

(b) In order to satisfy the 5th capsule requirement for 60-year and 80-year vessel fluence, Capsule U should be withdrawn after 44.4 EFPY, which corresponds to a fluence value of approximately 8.85 x 1019 n/cm2 (projected maximum 80-year vessel fluence value). Capsule U should be withdrawn at EOC 36 (Fall 2028), which is the first refueling outage after 44.4 EFPY is projected to be reached. However, Capsule U must be withdrawn before 59.1 EFPY, which corresponds to a fluence value of approximately 1.24 x 1020 n/cm2 (two times the projected maximum 60-year vessel fluence value).

It is recommended that Capsule U be withdrawn after it reaches the 80-year fluence. To ensure that this fluence is achieved, Capsule U should be withdrawn during the outage following 44.4 EFPY of plant operation (EOC 36, Fall 2028).

(c) Capsules Y and W should remain in the reactor for additional metallurgical data. Capsule W is projected to reach the 100-year (90 EFPY) peak reactor vessel fluence 1.16x 1020 n/cm2 at 59.7 EFPY, which is projected to be reached on 7/5/2043 during cycle 44. Capsule Y should be relocated to the 0° position (with respect to core cardinal axes) at EOC 36 (Fall 2028), which will allow Capsule Y to experience the 120-year fluence (1.36 x 1020 n/cm2) at 76.9 EFPY (projected to be reached on 7/3/2061 during cycle 53).

(d) Capsule Z was inadvertently removed from the reactor vessel per WCAP-15805 [Ref. 11].

(e) Capsule X was relocated from 50° to 270° (0° with respect to core cardinal axes) at EOC 8.

(f) Capsule U was relocated from 30° to 280° (10° with respect to core cardinal axes) at EOC 8.

(g) Capsule Y was relocated from 150° (30° with respect to core cardinal axes) to 290° (20° with respect to core cardinal axes) at EOC 27.

(h) Capsule W was relocated from 40° to 270° (0° with respect to core cardinal axes) at EOC 27.

- - This record was final approved on 4/3/2023, 1:16:26 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 CPL-RV000-TM-ME-000001, Rev. 1 Attachment A Page 11 of 13 Table 5 RTNDT Calculations for the H.B. Robinson Unit 2 Reactor Vessel at 50 EFPY Reactor Vessel Material(a)

RG 1.99(a)

Position Wt. %

Cu(a)

Wt. %

Ni(a)

CF(a)

(°F)

Surface Fluence (x 1019 n/cm2, E > 1.0 MeV)

FF(b)

Predicted RTNDT(c)

(°F)

Reactor Vessel Beltline Materials Upper Shell Plate W10201-1 1.1 0.13 0.11 62.9 2.72 1.27 79.7 Upper Shell Plate W10201-2 1.1 0.15 0.25 84.8 2.72 1.27 107.4 Upper Shell Plate W10201-3 1.1 0.11 0.08 51.8 2.72 1.27 65.6 Intermediate Shell Plate W10201-4 1.1 0.12 0.09 57.1 5.89 1.43 81.8 Using non-credible surveillance data 2.1 67.1 5.89 1.43 96.2 Intermediate Shell Plate W10201-5 1.1 0.10 0.12 51.2 5.89 1.43 73.4 Using credible surveillance data 2.1 38.8 5.89 1.43 55.6 Intermediate Shell Plate W10201-6 1.1 0.09 0.09 44.2 5.89 1.43 63.4 Using non-credible surveillance data 2.1 45.9 5.89 1.43 65.8 Lower Shell Plate W9807-3 1.1 0.12 0.10 58.0 3.33 1.32 76.3 Lower Shell Plate W9807-5 1.1 0.15 0.10 70.5 3.33 1.32 92.7 Lower Shell Plate W9807-9 1.1 0.14 0.15 70.5 3.33 1.32 92.7 Upper Shell Axial Welds 1-273 A, B, & C (Heat #86054B) 1.1 0.22 0.05 100.8 1.98 1.19 119.6 Intermediate Shell Axial Welds 2-273 A, B,

& C (Heat #86054B) 1.1 0.22 0.05 100.8 4.31 1.37 138.3 Lower Shell Axial Welds 3-273 A, B, & C (Heat #86054B) 1.1 0.22 0.05 100.8 3.33 1.32 132.6 Upper Shell to Intermediate Shell Circumferential Weld 10-273 (Heat # W5214) 1.1 0.21 1.01 230.2 2.72 1.27 291.7 Using not fully credible surveillance data 2.1 216.3 2.72 1.27 274.1 Intermediate Shell to Lower Shell Circumferential Weld 11-273 (Heat # 34B009) 1.1 0.19 0.98 217.1 3.33 1.32 285.5 Nozzle Welds 1.1 Note (e)

Note (e) 230.2 0.0157 0.15 34.0 Inlet Nozzle W-10207-1 1.1 0.02 0.90 20.0 0.0132 0.13 2.6 Inlet Nozzle W-10207-2 1.1 0.02 0.90 20.0 0.0132 0.13 2.6 Inlet Nozzle W-10207-3 1.1 0.02 0.90 20.0 0.0132 0.13 2.6 Outlet Nozzle B-3201-1 1.1 Note (d) 0.71 137.9 0.0157 0.15 20.4 Outlet Nozzle B-3201-2 1.1 Note (d) 0.71 137.9 0.0157 0.15 20.4 Outlet Nozzle B-3201-3 1.1 Note (d) 0.71 137.9 0.0157 0.15 20.4 Notes for Table 5:

(a) Values are taken from WCAP-18215-NP [Ref. 8], unless otherwise specified.

(b) FF = fluence factor = f(0.28 - 0.10*log (f)).

(c) RTNDT = CF x FF per RG 1.99 [Ref. 6].

(d) Value contained in WCAP-18215-P [Ref. 9] and is not presented in this Non-Proprietary letter.

(e) Since no chemistry values are available for this material, the chemistry factor for this material is set equal to the highest chemistry factor of the welds contained in the H.B. Robinson Unit 2 vessel. A Cu wt.% value of 0.22 is utilized for the nozzle welds USE.

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Westinghouse Non-Proprietary Class 3 CPL-RV000-TM-ME-000001, Rev. 1 Attachment A Page 12 of 13 Table 6 Comparison of the H.B. Robinson Unit 2 Capsule Withdrawal Schedule with ASTM E185-82, the GALL(a).

Requirement for Capsule Withdrawal Schedule per ASTM E185-82 Table 1(d)

Supplemental Guidance from GALL Comments(b) 1 1.5 EFPY or at the time when the accumulated neutron fluence of the capsule exceeds 5 x 1018 n/cm2, or at the time when the highest predicted RTNDT of all encapsulated materials is approximately 50°F, whichever comes first.

N/A Capsule S was withdrawn at the EOC 1, with an exposure of 1.34 EFPY and a fluence = 5.26 x 1018 n/cm2.

ASTM E185-82 is met because the capsule was withdrawn with a fluence greater than 5 x 1018 n/cm2.

2 3 EFPY or at the time when the accumulated neutron fluence of the capsule corresponds to a value midway between that of the first and third capsules.

N/A Capsule V was withdrawn at the EOC 3, with an exposure of 3.33 EFPY and a fluence = 5.59 x 1018 n/cm2.

ASTM E185-82 is met since the capsule was removed at approximately 3 EFPY.

3 6 EFPY or at the time when the accumulated neutron fluence of the capsule corresponds to the approximate EOL fluence at the reactor vessel 1/4T location, whichever comes first.

N/A Capsule T was withdrawn at the EOC 8, with an exposure of 7.53 EFPY and has a fluence of 4.18 x 1019 n/cm2. The peak 1/4T fluence at EOL (assumed to be 32 EFPY, 3.98 x 1019 n/cm2) is 2.28 x 1019 n/cm2(c).

The intent of ASTM E185-82 is met because the capsule was withdrawn very near 6 EFPY. In addition, at the time of withdrawal of this capsule, the EFPY was likely based on different fluence projections and possibly a different EFPY term.

4 15 EFPY or at the time when the accumulated neutron fluence of the capsule corresponds to the approximate EOL fluence at the reactor vessel inner wall location, whichever comes first.

N/A Capsule X was withdrawn at the EOC 20, with an exposure of 20.65 EFPY and a fluence = 4.43 x 1019 n/cm2. The clad/base metal fluence at EOL (assumed to be 32 EFPY) was approximately 3.98 x 1019 n/cm2.

ASTM E185-82 is met because the capsule fluence was very near the peak fluence of the clad/base metal. The exposures are also well within the 20%

uncertainty required by Regulatory Guide 1.190. In addition, at the time of withdrawal of this capsule, the EFPY was likely based on different fluence projections and possibly a different EFPY term.

- - This record was final approved on 4/3/2023, 1:16:26 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 CPL-RV000-TM-ME-000001, Rev. 1 Attachment A Page 13 of 13 Table 6 Comparison of the H.B. Robinson Unit 2 Capsule Withdrawal Schedule with ASTM E185-82, the GALL(a).

Requirement for Capsule Withdrawal Schedule per ASTM E185-82 Table 1(d)

Supplemental Guidance from GALL Comments(b) 5 Not less than once or greater than twice the peak EOL vessel fluence. This may be modified on the basis of previous tests. This capsule may be held without testing following withdrawal.

Per the GALL, one capsule is withdrawn and tested at a fluence of not less than once or greater than twice the peak 60-year (EOLE) vessel fluence.

For the GALL requirements, Capsule U must be withdrawn between the peak 60-year fluence (50 EFPY, 6.19 x 1019 n/cm2) and two times the peak 60-year fluence (1.24 x 1020 n/cm2).

To meet the requirements of ASTM E185-82 and the GALL, Capsule U is recommended to be withdrawn prior to 59.1 EFPY and a fluence between 6.19 x 1019 n/cm2 (60-year peak fluence) and 1.24 x 1020 n/cm2 (two times the peak 60-year fluence). Note that Capsule U has surpassed the peak 60-year fluence.

ASTM E185-82 and GALL guidance are met because the capsule would be withdrawn with a fluence between the peak 60-year fluence and two times the peak 60-year fluence.

Notes for Table 6:

(a) This comparison table is provided for information only. The H.B. Robinson Unit 2 surveillance program was designed to ASTM E185-66 [Ref. 5].

(b) The capsule fluence values, cycle number and EFPY values are taken from Tables 2 and 4, unless otherwise specified.

(c) The 1/4T fluence value was calculated from the surface fluence, the reactor vessel beltline thickness (9.313 inches), and equation f = fsurf

e-0.24 (x) from RG 1.99, Revision 2, where x = the depth into the vessel wall (inches).

(d) H.B. Robinson Unit 2 meets the requirements of a five (5) capsule withdrawal schedule as described in ASTM E185-82 since the limiting RTNDT is greater than 200°F.

to RA-23-0141 Westinghouse Report CPL-REAC-TM-AA-000001, Revision 1, H. B. Robinson Unit 2 Subsequent License Renewal: Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

- - Electronically approved records are authenticated in the electronic document management system.

FORM NUMBER F-GES-CMPP-PR-DD-000002-1 Rev. 1 Effective Date: 9/29/2021 FORM NUMBER - F-GES-CMPP-PR-DD-000002-1 Rev. 1 DOCUMENT COVER SHEET DOCUMENT NO.

REVISION PAGE 1 of 65 CPL-REAC-TM-AA-000001 1

PE SEAL (If required)

ALTERNATE DOCUMENT NUMBER: N/A TITLE: H. B. Robinson Unit 2 Subsequent License Renewal: Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data ATTACHMENTS:

CPL-REAC-TM-AA-000001_Revision_0 DCRF Rev C 19Jan23.docx

© 2023 WESTINGHOUSE ELECTRIC COMPANY LLC, ALL RIGHTS RESERVED - WESTINGHOUSE PROPRIETARY CLASS 2 Information included in this material is proprietary and confidential and cannot be disclosed or used for any reason beyond the intended purpose without the prior written consent of Westinghouse Electric Company LLC.

NOTE: This selection is only to be used for Westinghouse generated documents.

© 2023 WESTINGHOUSE ELECTRIC COMPANY LLC, ALL RIGHTS RESERVED and/or © 2023 WESTINGHOUSE BUSINESS PARTNER, ALL RIGHTS RESERVED WESTINGHOUSE PROPRIETARY CLASS 2 and/or WESTINGHOUSE BUSINESS PARTNER PROPRIETARY (SEE ATTACHED DOCUMENT)

Information included in this material is proprietary and confidential and cannot be disclosed or used for any reason beyond the intended purpose without the prior written consent of Westinghouse Electric Company LLC.

SUPPLIER OR THIRD PARTY PROVIDED INFORMATION - File And Protect Using Policies For Westinghouse Proprietary Class 2 Information Information included in this material is proprietary and confidential and cannot be disclosed or used for any reason beyond the intended purpose without the prior written consent of the Supplier/Third Party.

Signature Responsibility Name SIGNATURE / DATE(If processing electronic approval select option)

Originator Sylena E. Smith Electronically Approved***

Reviewer Andrew E. Hawk Electronically Approved***

Responsible Manager Jesse J Klingensmith Electronically Approved***

Approval signifies that the document and all required reviews are complete, the appropriate proprietary class has been assigned, electronic file has been provided to PRIME, and the document is released for use.

This document may contain technical data subject to the export control laws of the United States. In the event that this document does contain such information, the Recipients acceptance of this document constitutes agreement that this information in document form (or any other medium), including any attachments and exhibits hereto, shall not be exported, released or disclosed to foreign persons whether in the United States or abroad by recipient except in compliance with all U.S. export control regulations. Recipient shall include this notice with any reproduced or excerpted portion of this document or any document derived from, based on, incorporating, using or relying on the information contained in this document.

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Westinghouse Non-Proprietary Class 3 CPL-REAC-TM-AA-000001, Rev. 1 Page 2 of 65 February 8, 2023

Date Revision Description 0

See PRIME.

Initial issuance.

1 See PRIME.

This revision resolves the comments attached to the PRIME archive and provides neutron exposure data for the embedded anchor bolts of the limiting RPV support structure.

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Westinghouse Non-Proprietary Class 3

© 2023 Westinghouse Electric Company LLC All Rights Reserved To: Si Wu, Nick DeDominicis Date: February 8, 2023 Our ref: CPL-REAC-TM-AA-000001, Rev. 1 From: Radiation Engineering and Analysis Phone: (412)374-4994

Subject:

H. B. Robinson Unit 2 Subsequent License Renewal: Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data Attachment(s): 1. H. B. Robinson Unit 2 Subsequent License Renewal: Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data provides exposure data applicable to the H. B. Robinson Unit 2 reactor pressure vessel (RPV),

RPV support structure and concrete bioshield. These data are intended to be used in downstream evaluations of the RPV integrity, RPV support structure embrittlement, and bioshield concrete degradation. In addition, the information in Attachment 1 needs to be provided to Duke Energy in support of the H. B. Robinson Unit 2 subsequent license renewal (SLR) project.

If you have any questions, feel free to contact me or any of the undersigned.

Sincerely yours, Sylena E. Smith Author:

Sylena E. Smith*

Radiation Engineering and Analysis Reviewer:

Andrew E. Hawk*

Radiation Engineering and Analysis Approver:

Jesse J Klingensmith*

Manager, Radiation Engineering and Analysis : H. B. Robinson Unit 2 Subsequent License Renewal: Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data (62 pages)

Electronically approved records are authenticated in the electronic document management system.

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 1 of 62 February 8, 2023

Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data

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Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 2 of 62 February 8, 2023

© 2023 Westinghouse Electric Company LLC All Rights Reserved Table of Contents 1.0 Introduction............................................................................................................................................. 3 2.0 Analysis Methodology............................................................................................................................ 3 3.0 Discrete Ordinates Model....................................................................................................................... 3 4.0 Dosimetry Comparisons........................................................................................................................ 12 5.0 Exposure Results................................................................................................................................... 12 5.1 Reactor Pressure Vessel........................................................................................................................ 12 5.2 Surveillance Capsules........................................................................................................................... 27 5.3 RPV Support Structure......................................................................................................................... 34 5.4 Bioshield Concrete................................................................................................................................ 53 6.0 References............................................................................................................................................. 62

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Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 3 of 62 February 8, 2023

© 2023 Westinghouse Electric Company LLC All Rights Reserved 1.0 Introduction This attachment describes a discrete ordinates transport analysis performed for H. B. Robinson Unit 2. The results summarized in this attachment are intended to be used in evaluations of the reactor pressure vessel (RPV) integrity, the RPV support structure embrittlement, and the bioshield concrete performed in support of the H. B. Robinson Unit 2 subsequent license renewal (SLR) project.

The neutron transport methodology used to generate the data provided in this attachment followed the guidance of Regulatory Guide 1.190, Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence (Reference 1). The methodology is also consistent with that described in WCAP-18124-NP-A, Fluence Determination with RAPTOR-M3G and FERRET (Reference 2) and WCAP-18124-NP-A Revision 0 Supplement 1-NP-A, Fluence Determination with RAPTOR-M3G and FERRET - Supplement for Extended Beltline Materials (Reference 3). The methodology described in References 2 and 3 has been generically approved for calculating exposures to the RPV beltline as well as the RPV extended beltline materials.

Presently, there are no generically approved methods for calculating exposures of the RPV support structures and bioshield concrete.

2.0 Analysis Methodology Discrete ordinates transport calculations were performed on a fuel-cycle-specific basis to determine the neutron and gamma ray environment within the reactor and bioshield geometry. The specific methods applied were consistent with those described in References 2 and 3.

The transport calculations were carried out using the three-dimensional RAPTOR-M3G discrete ordinates code and the BUGLE-96 cross-section library. The BUGLE-96 library provides a coupled 47-neutron-, 20-gamma-ray-group cross-section data set produced specifically for light water reactor applications. Anisotropic scattering was treated with a P3 Legendre expansion and the angular discretization was modeled with an S16 order of angular quadrature. Energy-and space-dependent core power distributions as well as system operating temperatures were treated on a fuel-cycle-specific basis.

The model geometry used in the transport calculations described herein was based on that described in WCAP-18751-NP, Analysis of Ex-Vessel Neutron Dosimetry from H.B Robinson Unit 2 - Cycle 32 (Reference 4) with expansion of the model geometry to facilitate explicit modeling of the limiting (highest fluence) inlet nozzle and outlet nozzle and the limiting RPV support and surrounding concrete. The enhanced model features 236 radial, 231 azimuthal, and 333 axial intervals.

3.0 Discrete Ordinates Model In developing the analytical models of the reactor geometry shown in Figures 3-1 through 3-5, nominal design dimensions were employed for the various structural components with one exception. For the reactor pressure vessel, the base metal thickness was based on the information in Table 1.1 of NUREG/CR-6453 (Reference 8).

Cycle-dependent water temperatures and, hence, coolant density in the reactor core and downcomer regions of the reactor were taken to be representative of full-power operating conditions. The reactor core was treated as a homogeneous mixture (fuel, cladding, water, and miscellaneous core structures such as fuel assembly grids, See Section A of each topical report to review the NRC staffs Safety Evaluation.

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Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 4 of 62 February 8, 2023

© 2023 Westinghouse Electric Company LLC All Rights Reserved guide tubes, etc.), which was then divided into temperature zones to allow coolant temperatures to be varied through the active fuel height.

Figure 3-1 shows a slice of the model geometry at the 10° azimuth. This view of the geometry features the part-length shield assemblies used in fuel cycles 10 through 31 as well as the outlet nozzle geometry. Figure 3-2 shows a slice of the model geometry at the 80° azimuth. Figure 3-2 shows the core geometry for those cycles that did not feature part-length shield assemblies as well as the inlet nozzle, and the RPV support. Figure 3-3 shows a plan view of the model geometry sliced at the core midplane. Figure 3-3 shows instrument wells in the concrete bioshield as well as the geometric differentiation of the reactor internals, including the core barrel, surveillance capsules and baffle plates. Figure 3-4 shows a plan view of the model geometry sliced near the bottom of the reactor vessel support. Figure 3-5 shows a 3-dimensional view of the concrete bioshield and the pressure vessel support. Figure 3-6 and Figure 3-7 show different views depicting the relative axial positions of the major subcomponents of the RPV support for which exposure values are provided herein.

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Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 5 of 62 February 8, 2023

View of the Model Geometry with Part-Length Shield Assemblies at 10 Degrees

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Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 6 of 62 February 8, 2023

View of the Model Geometry (no Part-Length Shield Assemblies) at 80 Degrees

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Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 7 of 62 February 8, 2023

Plan View of the Model Geometry at the Core Midplane

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Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 8 of 62 February 8, 2023

Plan View of the Model Geometry 190 cm Above the Core Midplane

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Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 9 of 62 February 8, 2023

3-Dimensional View of the Bioshield and Pressure Vessel Support

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Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 10 of 62 February 8, 2023

Relative Axial Positions of the RPV Support Subcomponents - Azimuthal Slice with Nozzle Centimeters Above Core Midplane

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 11 of 62 February 8, 2023

Relative Axial Positions of the RPV Support Subcomponents Dimensional Radial View Centimeters Above Core Midplane

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 12 of 62 February 8, 2023

© 2023 Westinghouse Electric Company LLC All Rights Reserved 4.0 Dosimetry Comparisons The description of the reactor vessel radiation surveillance program for H. B. Robinson Unit 2 is provided in WCAP-7373, Carolina Power and Light Co. H. B. Robinson Unit No. 2 Reactor Vessel Radiation Surveillance Program (Reference 5). The most recent dosimetry analysis for the plant as well as the dosimetry program are discussed in depth in WCAP-18751-NP. The analysis summarized herein used the same methodology, the same geometric model (with a few enhancements as described in Section 2.0) and the same fuel cycle history that was used in the analysis described in WCAP-18751-NP. No new dosimetry data was available from H. B.

Robinson Unit 2. As such, no dosimetry evaluations were performed in the present analysis.

5.0 Exposure Results 5.1 Reactor Pressure Vessel Neutron exposure data at the RPV clad/base metal interface are presented in Tables 5-1 through 5-4. In particular, the fast (E > 1.0 MeV) neutron fluence rates and fluences determined at the RPV clad/base metal interface are provided in Tables 5-1 and 5-2 as a function of irradiation time. Similar data in terms of iron atom displacement rate and iron atom displacements are provided in Tables 5-3 and 5-4. Table 5-2 and Table 5-4 include projections of the neutron fluence and total iron atom displacements, respectively, at the clad/base metal interface with two different projection bases: the first projection being based on the spatial power distribution experienced during Cycle 32 and the second projection being based on the spatial power distribution of Cycle 32 with a 10% positive bias applied to the relative power of the fuel assemblies on the periphery of the core and at the re-entrant corners of the baffle assembly.

Neutron exposure data for various RPV materials are summarized in Tables 5-5 and 5-6. In Table 5-5, the fast neutron fluence at the end of Cycle 32 and as projected for the RPV materials is presented as a function of time with the same two projection bases used for the clad/base metal interface: one based on Cycle 32 and the other based on Cycle 32 with 10% positive bias on the relative power of the peripheral and re-entrant corner fuel assemblies. Similar to the information in Table 5-5, the iron atom displacement at the end of Cycle 32 and as projected for the RPV materials is presented in Table 5-6 as a function of time with the unbiased and biased projection bases.

The limiting inlet nozzle to upper shell weld exposure and the limiting outlet nozzle to upper shell weld exposure presented in Table 5-5 and Table 5-6 represent the most limiting nozzle weld materials in terms of fluence. The fast neutron fluence values for the limiting inlet nozzle weld and the limiting outlet nozzle weld are below the 1.0E+17 n/cm2 threshold beyond which radiation embrittlement would need to be considered.

The fast neutron fluence for the non-limiting inlet nozzle welds and non-limiting outlet nozzle welds are also below the embrittlement threshold; and were not explicitly modeled.

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 13 of 62 February 8, 2023

Fast Neutron Fluence Rate at the RPV Clad / Base Metal Interface Cycle Cycle Length (EFPY)

Total Time (EFPY)

Fluence Rate (n/cm2-s)

Azimuth of Max.

(°)

Axial Location of Max.

(cm) 0° 15° 30° 45° 60° 75° 90° Maximum 1

1.34 1.34 6.49E+10 2.91E+10 1.64E+10 1.07E+10 1.64E+10 2.91E+10 6.49E+10 6.49E+10 0

-54 2

0.85 2.19 6.32E+10 3.01E+10 1.72E+10 1.09E+10 1.71E+10 2.99E+10 6.37E+10 6.38E+10 90 2

3 1.14 3.33 5.31E+10 2.50E+10 1.54E+10 1.02E+10 1.55E+10 2.50E+10 5.40E+10 5.40E+10 90 2

4 0.83 4.16 7.04E+10 3.18E+10 1.71E+10 1.13E+10 1.71E+10 3.17E+10 7.17E+10 7.17E+10 90 50 5

0.85 5.00 6.60E+10 3.02E+10 1.66E+10 1.03E+10 1.65E+10 3.01E+10 6.59E+10 6.60E+10 0

-54 6

0.88 5.88 6.32E+10 2.88E+10 1.61E+10 1.01E+10 1.60E+10 2.86E+10 6.30E+10 6.33E+10 1

-58 7

0.81 6.69 6.43E+10 3.04E+10 1.76E+10 1.08E+10 1.76E+10 3.04E+10 6.42E+10 6.43E+10 0

-58 8

0.84 7.53 6.36E+10 2.95E+10 1.65E+10 1.01E+10 1.64E+10 2.94E+10 6.46E+10 6.46E+10 90 50 9

0.86 8.38 3.44E+10 1.88E+10 1.48E+10 9.50E+09 1.47E+10 1.88E+10 3.47E+10 3.48E+10 90 50 10 0.87 9.26 3.54E+10 2.27E+10 1.71E+10 9.43E+09 1.73E+10 2.26E+10 3.72E+10 3.72E+10 90 50 11 0.92 10.17 3.26E+10 2.28E+10 1.79E+10 8.89E+09 1.78E+10 2.27E+10 3.41E+10 3.42E+10 89 53 12 0.98 11.15 3.06E+10 2.29E+10 1.82E+10 8.71E+09 1.81E+10 2.28E+10 3.21E+10 3.22E+10 89 53 13 0.98 12.14 2.70E+10 2.10E+10 1.77E+10 8.88E+09 1.77E+10 2.09E+10 2.82E+10 2.83E+10 89 53 14 1.00 13.13 2.66E+10 2.20E+10 1.88E+10 9.01E+09 1.88E+10 2.18E+10 2.78E+10 2.80E+10 3

50 15 1.07 14.21 2.53E+10 2.15E+10 1.86E+10 8.71E+09 1.86E+10 2.14E+10 2.64E+10 2.65E+10 3

53 16 1.08 15.28 4.26E+10 2.16E+10 1.14E+10 8.19E+09 1.17E+10 2.15E+10 4.46E+10 4.46E+10 90 50 17 1.18 16.47 3.80E+10 2.02E+10 1.08E+10 7.23E+09 1.09E+10 2.01E+10 3.97E+10 3.98E+10 89 53 18 1.35 17.81 3.39E+10 1.86E+10 1.06E+10 6.68E+09 1.09E+10 1.86E+10 3.55E+10 3.55E+10 89 50 19 1.41 19.23 3.13E+10 1.77E+10 1.08E+10 7.62E+09 1.11E+10 1.76E+10 3.30E+10 3.30E+10 90 50 20 1.42 20.65 2.77E+10 1.63E+10 1.05E+10 7.88E+09 1.09E+10 1.63E+10 2.91E+10 2.91E+10 90 53

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 14 of 62 February 8, 2023

Fast Neutron Fluence Rate at the RPV Clad / Base Metal Interface Cycle Cycle Length (EFPY)

Total Time (EFPY)

Fluence Rate (n/cm2-s)

Azimuth of Max.

(°)

Axial Location of Max.

(cm) 0° 15° 30° 45° 60° 75° 90° Maximum 21 1.40 22.05 2.65E+10 1.62E+10 1.08E+10 7.71E+09 1.09E+10 1.61E+10 2.78E+10 2.78E+10 89 50 22 1.44 23.49 3.80E+10 1.83E+10 8.08E+09 5.94E+09 8.17E+09 1.82E+10 4.00E+10 4.00E+10 90 53 23 1.31 24.80 3.34E+10 1.70E+10 8.38E+09 6.45E+09 8.38E+09 1.69E+10 3.51E+10 3.51E+10 90 53 24 1.45 26.24 2.90E+10 1.57E+10 8.49E+09 6.53E+09 8.78E+09 1.56E+10 3.05E+10 3.05E+10 90 93 25 1.37 27.62 2.72E+10 1.52E+10 8.26E+09 6.12E+09 8.27E+09 1.51E+10 2.87E+10 2.87E+10 90 53 26 1.34 28.95 2.00E+10 1.27E+10 8.60E+09 6.57E+09 8.49E+09 1.26E+10 2.10E+10 2.10E+10 90 93 27 1.35 30.31 2.45E+10 1.43E+10 8.22E+09 6.53E+09 8.56E+09 1.43E+10 2.58E+10 2.58E+10 90 93 28 1.46 31.77 3.84E+10 1.91E+10 9.88E+09 6.60E+09 1.00E+10 1.90E+10 4.01E+10 4.02E+10 90 53 29 1.41 33.18 3.09E+10 1.63E+10 9.01E+09 6.62E+09 8.95E+09 1.62E+10 3.25E+10 3.25E+10 90 53 30 1.59 34.78 3.06E+10 1.72E+10 1.07E+10 7.07E+09 1.08E+10 1.74E+10 3.22E+10 3.23E+10 89 50 31 1.43 36.21 2.50E+10 1.60E+10 1.03E+10 6.38E+09 1.03E+10 1.59E+10 2.61E+10 2.62E+10 89 53 32 1.86 38.07 3.80E+10 1.83E+10 1.08E+10 7.82E+09 1.08E+10 1.82E+10 3.85E+10 3.85E+10 90 53 Projections no bias 3.80E+10 1.83E+10 1.08E+10 7.82E+09 1.08E+10 1.82E+10 3.85E+10 3.85E+10 90 53 Projections w/bias 4.15E+10 2.00E+10 1.18E+10 8.55E+09 1.18E+10 1.99E+10 4.21E+10 4.21E+10 90 53

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 15 of 62 February 8, 2023

Fast Neutron Fluence at the RPV Clad / Base Metal Interface Cycle Cycle Length (EFPY)

Total Time (EFPY)

Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

Azimuth of Max.

(°)

Axial Location of Max.

(cm) 0° 15° 30° 45° 60° 75° 90° Maximum 1

1.34 1.34 2.74E+18 1.23E+18 6.92E+17 4.52E+17 6.90E+17 1.23E+18 2.74E+18 2.74E+18 0

-54 2

0.85 2.19 4.44E+18 2.03E+18 1.15E+18 7.45E+17 1.15E+18 2.03E+18 4.44E+18 4.44E+18 0

-54 3

1.14 3.33 6.35E+18 2.92E+18 1.71E+18 1.11E+18 1.70E+18 2.92E+18 6.35E+18 6.35E+18 90

-54 4

0.83 4.16 8.18E+18 3.74E+18 2.15E+18 1.41E+18 2.15E+18 3.73E+18 8.19E+18 8.19E+18 90

-54 5

0.85 5.00 9.95E+18 4.54E+18 2.60E+18 1.68E+18 2.59E+18 4.54E+18 9.95E+18 9.95E+18 0

-54 6

0.88 5.88 1.17E+19 5.34E+18 3.04E+18 1.96E+18 3.03E+18 5.33E+18 1.17E+19 1.17E+19 0

-54 7

0.81 6.69 1.33E+19 6.12E+18 3.49E+18 2.24E+18 3.48E+18 6.11E+18 1.33E+19 1.33E+19 0

-54 8

0.84 7.53 1.50E+19 6.89E+18 3.93E+18 2.50E+18 3.91E+18 6.88E+18 1.50E+19 1.50E+19 0

-54 9

0.86 8.38 1.60E+19 7.39E+18 4.33E+18 2.76E+18 4.31E+18 7.39E+18 1.59E+19 1.60E+19 0

-54 10 0.87 9.26 1.68E+19 8.00E+18 4.80E+18 3.02E+18 4.78E+18 7.96E+18 1.69E+19 1.69E+19 90 2

11 0.92 10.17 1.76E+19 8.65E+18 5.32E+18 3.28E+18 5.30E+18 8.62E+18 1.79E+19 1.79E+19 90 2

12 0.98 11.15 1.85E+19 9.36E+18 5.88E+18 3.55E+18 5.86E+18 9.32E+18 1.89E+19 1.89E+19 90 2

13 0.98 12.14 1.92E+19 1.00E+19 6.43E+18 3.82E+18 6.41E+18 9.97E+18 1.97E+19 1.97E+19 90 2

14 1.00 13.13 2.00E+19 1.07E+19 7.02E+18 4.10E+18 7.00E+18 1.07E+19 2.06E+19 2.06E+19 90 2

15 1.07 14.21 2.08E+19 1.14E+19 7.65E+18 4.40E+18 7.62E+18 1.14E+19 2.15E+19 2.15E+19 90 2

16 1.08 15.28 2.20E+19 1.22E+19 8.04E+18 4.68E+18 8.01E+18 1.21E+19 2.30E+19 2.30E+19 90 2

17 1.18 16.47 2.33E+19 1.29E+19 8.44E+18 4.95E+18 8.42E+18 1.28E+19 2.44E+19 2.44E+19 90 2

18 1.35 17.81 2.47E+19 1.37E+19 8.90E+18 5.23E+18 8.87E+18 1.36E+19 2.59E+19 2.59E+19 90 2

19 1.41 19.23 2.61E+19 1.45E+19 9.38E+18 5.56E+18 9.35E+18 1.44E+19 2.74E+19 2.74E+19 90 2

20 1.42 20.65 2.73E+19 1.52E+19 9.85E+18 5.91E+18 9.82E+18 1.51E+19 2.87E+19 2.87E+19 90 2

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 16 of 62 February 8, 2023

Fast Neutron Fluence at the RPV Clad / Base Metal Interface Cycle Cycle Length (EFPY)

Total Time (EFPY)

Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

Azimuth of Max.

(°)

Axial Location of Max.

(cm) 0° 15° 30° 45° 60° 75° 90° Maximum 21 1.40 22.05 2.85E+19 1.59E+19 1.03E+19 6.25E+18 1.03E+19 1.58E+19 2.99E+19 2.99E+19 90 50 22 1.44 23.49 3.02E+19 1.67E+19 1.07E+19 6.52E+18 1.07E+19 1.67E+19 3.17E+19 3.17E+19 90 50 23 1.31 24.80 3.16E+19 1.74E+19 1.10E+19 6.78E+18 1.10E+19 1.74E+19 3.32E+19 3.32E+19 90 50 24 1.45 26.24 3.29E+19 1.81E+19 1.14E+19 7.07E+18 1.14E+19 1.80E+19 3.45E+19 3.46E+19 90 50 25 1.37 27.62 3.41E+19 1.88E+19 1.18E+19 7.34E+18 1.17E+19 1.87E+19 3.58E+19 3.58E+19 90 50 26 1.34 28.95 3.49E+19 1.93E+19 1.21E+19 7.60E+18 1.21E+19 1.92E+19 3.67E+19 3.67E+19 90 50 27 1.35 30.31 3.59E+19 1.99E+19 1.25E+19 7.87E+18 1.24E+19 1.98E+19 3.78E+19 3.78E+19 90 50 28 1.46 31.77 3.77E+19 2.08E+19 1.29E+19 8.17E+18 1.29E+19 2.07E+19 3.96E+19 3.96E+19 90 50 29 1.41 33.18 3.91E+19 2.15E+19 1.33E+19 8.46E+18 1.33E+19 2.14E+19 4.11E+19 4.11E+19 90 50 30 1.59 34.78 4.06E+19 2.24E+19 1.39E+19 8.82E+18 1.38E+19 2.23E+19 4.27E+19 4.27E+19 90 50 31 1.43 36.21 4.18E+19 2.31E+19 1.43E+19 9.10E+18 1.43E+19 2.30E+19 4.38E+19 4.39E+19 90 50 32 1.86 38.07 4.39E+19 2.42E+19 1.50E+19 9.56E+18 1.49E+19 2.41E+19 4.61E+19 4.61E+19 90 50

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 17 of 62 February 8, 2023

Fast Neutron Fluence at the RPV Clad / Base Metal Interface Cycle Cycle Length (EFPY)

Total Time (EFPY)

Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

Azimuth of Max.

(°)

Axial Location of Max.

(cm) 0° 15° 30° 45° 60° 75° 90° Maximum Projection with no bias on peripheral fuel assemblies 42 4.84E+19 2.64E+19 1.63E+19 1.05E+19 1.63E+19 2.63E+19 5.09E+19 5.09E+19 90 50 48 5.54E+19 2.99E+19 1.84E+19 1.20E+19 1.83E+19 2.98E+19 5.82E+19 5.82E+19 90 50 50 5.77E+19 3.11E+19 1.90E+19 1.25E+19 1.90E+19 3.09E+19 6.06E+19 6.06E+19 90 50 54 6.23E+19 3.34E+19 2.04E+19 1.35E+19 2.03E+19 3.32E+19 6.55E+19 6.55E+19 90 50 60 6.92E+19 3.68E+19 2.24E+19 1.50E+19 2.24E+19 3.66E+19 7.28E+19 7.28E+19 90 53 66 7.61E+19 4.03E+19 2.45E+19 1.65E+19 2.44E+19 4.01E+19 8.01E+19 8.01E+19 90 53 70 8.07E+19 4.26E+19 2.59E+19 1.74E+19 2.58E+19 4.24E+19 8.49E+19 8.49E+19 90 53 72 8.30E+19 4.37E+19 2.65E+19 1.79E+19 2.64E+19 4.35E+19 8.74E+19 8.74E+19 90 53 Projection with 10% positive bias on peripheral fuel assemblies 42 4.89E+19 2.67E+19 1.64E+19 1.06E+19 1.64E+19 2.65E+19 5.13E+19 5.13E+19 90 50 48 5.64E+19 3.04E+19 1.87E+19 1.22E+19 1.86E+19 3.03E+19 5.93E+19 5.93E+19 90 50 50 5.89E+19 3.17E+19 1.94E+19 1.28E+19 1.93E+19 3.15E+19 6.19E+19 6.19E+19 90 50 54 6.40E+19 3.42E+19 2.09E+19 1.39E+19 2.08E+19 3.41E+19 6.73E+19 6.73E+19 90 50 60 7.15E+19 3.80E+19 2.31E+19 1.55E+19 2.31E+19 3.78E+19 7.52E+19 7.52E+19 90 53 66 7.91E+19 4.18E+19 2.54E+19 1.71E+19 2.53E+19 4.16E+19 8.32E+19 8.32E+19 90 53 70 8.41E+19 4.43E+19 2.69E+19 1.82E+19 2.68E+19 4.41E+19 8.85E+19 8.85E+19 90 53 72 8.67E+19 4.56E+19 2.76E+19 1.87E+19 2.75E+19 4.53E+19 9.12E+19 9.12E+19 90 53

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 18 of 62 February 8, 2023

Iron Atom Displacement Rate at the RPV Clad / Base Metal Interface Cycle Cycle Length (EFPY)

Total Time (EFPY)

Iron Atom Displacement Rate (dpa/s)

Azimuth of Max.

(°)

Axial Location of Max.

(cm) 0° 15° 30° 45° 60° 75° 90° Maximum 1

1.34 1.34 1.07E-10 4.85E-11 2.68E-11 1.75E-11 2.67E-11 4.83E-11 1.07E-10 1.07E-10 0

-52 2

0.85 2.19 1.05E-10 5.05E-11 2.81E-11 1.77E-11 2.80E-11 4.98E-11 1.05E-10 1.06E-10 2

2 3

1.14 3.33 8.90E-11 4.20E-11 2.52E-11 1.67E-11 2.52E-11 4.16E-11 8.89E-11 8.96E-11 1

2 4

0.83 4.16 1.19E-10 5.35E-11 2.80E-11 1.83E-11 2.80E-11 5.28E-11 1.18E-10 1.20E-10 2

53 5

0.85 5.00 1.09E-10 5.03E-11 2.71E-11 1.68E-11 2.69E-11 5.01E-11 1.08E-10 1.09E-10 2

-2 6

0.88 5.88 1.04E-10 4.80E-11 2.64E-11 1.64E-11 2.61E-11 4.76E-11 1.04E-10 1.04E-10 0

-54 7

0.81 6.69 1.06E-10 5.06E-11 2.88E-11 1.76E-11 2.86E-11 5.04E-11 1.06E-10 1.06E-10 0

-54 8

0.84 7.53 1.07E-10 4.96E-11 2.69E-11 1.65E-11 2.68E-11 4.89E-11 1.06E-10 1.08E-10 2

53 9

0.86 8.38 5.71E-11 3.12E-11 2.40E-11 1.54E-11 2.38E-11 3.10E-11 5.68E-11 5.74E-11 1

50 10 0.87 9.26 6.15E-11 3.78E-11 2.80E-11 1.54E-11 2.82E-11 3.73E-11 6.12E-11 6.23E-11 1

50 11 0.92 10.17 5.66E-11 3.78E-11 2.92E-11 1.45E-11 2.89E-11 3.73E-11 5.62E-11 5.74E-11 1

53 12 0.98 11.15 5.31E-11 3.79E-11 2.98E-11 1.43E-11 2.95E-11 3.74E-11 5.29E-11 5.39E-11 1

53 13 0.98 12.14 4.67E-11 3.49E-11 2.89E-11 1.45E-11 2.87E-11 3.44E-11 4.65E-11 4.74E-11 1

53 14 1.00 13.13 4.62E-11 3.63E-11 3.06E-11 1.48E-11 3.05E-11 3.59E-11 4.59E-11 4.69E-11 2

53 15 1.07 14.21 4.38E-11 3.55E-11 3.03E-11 1.43E-11 3.01E-11 3.51E-11 4.36E-11 4.45E-11 2

53 16 1.08 15.28 7.39E-11 3.61E-11 1.88E-11 1.34E-11 1.91E-11 3.56E-11 7.33E-11 7.46E-11 1

50 17 1.18 16.47 6.58E-11 3.37E-11 1.77E-11 1.18E-11 1.79E-11 3.33E-11 6.53E-11 6.66E-11 1

53 18 1.35 17.81 5.87E-11 3.11E-11 1.75E-11 1.09E-11 1.78E-11 3.07E-11 5.83E-11 5.95E-11 1

50 19 1.41 19.23 5.42E-11 2.95E-11 1.78E-11 1.24E-11 1.81E-11 2.92E-11 5.41E-11 5.50E-11 1

50 20 1.42 20.65 4.79E-11 2.72E-11 1.74E-11 1.29E-11 1.77E-11 2.68E-11 4.78E-11 4.85E-11 1

53

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 19 of 62 February 8, 2023

Iron Atom Displacement Rate at the RPV Clad / Base Metal Interface Cycle Cycle Length (EFPY)

Total Time (EFPY)

Iron Atom Displacement Rate (dpa/s)

Azimuth of Max.

(°)

Axial Location of Max.

(cm) 0° 15° 30° 45° 60° 75° 90° Maximum 21 1.40 22.05 4.58E-11 2.69E-11 1.77E-11 1.25E-11 1.77E-11 2.66E-11 4.56E-11 4.64E-11 1

50 22 1.44 23.49 6.60E-11 3.07E-11 1.32E-11 9.67E-12 1.34E-11 3.03E-11 6.57E-11 6.68E-11 1

53 23 1.31 24.80 5.78E-11 2.84E-11 1.37E-11 1.04E-11 1.37E-11 2.80E-11 5.76E-11 5.86E-11 1

53 24 1.45 26.24 5.02E-11 2.62E-11 1.41E-11 1.07E-11 1.43E-11 2.58E-11 5.00E-11 5.09E-11 1

93 25 1.37 27.62 4.72E-11 2.54E-11 1.35E-11 9.98E-12 1.35E-11 2.50E-11 4.71E-11 4.78E-11 1

53 26 1.34 28.95 3.46E-11 2.11E-11 1.39E-11 1.06E-11 1.38E-11 2.08E-11 3.45E-11 3.51E-11 1

93 27 1.35 30.31 4.24E-11 2.38E-11 1.38E-11 1.06E-11 1.40E-11 2.35E-11 4.23E-11 4.30E-11 1

93 28 1.46 31.77 6.66E-11 3.20E-11 1.61E-11 1.08E-11 1.63E-11 3.15E-11 6.60E-11 6.74E-11 1

53 29 1.41 33.18 5.36E-11 2.73E-11 1.46E-11 1.07E-11 1.45E-11 2.69E-11 5.34E-11 5.43E-11 1

53 30 1.59 34.78 5.30E-11 2.87E-11 1.74E-11 1.15E-11 1.76E-11 2.87E-11 5.30E-11 5.38E-11 1

50 31 1.43 36.21 4.32E-11 2.66E-11 1.68E-11 1.04E-11 1.68E-11 2.62E-11 4.29E-11 4.38E-11 1

53 32 1.86 38.07 6.36E-11 3.06E-11 1.76E-11 1.27E-11 1.76E-11 3.02E-11 6.34E-11 6.41E-11 2

53 Projections no bias 6.36E-11 3.06E-11 1.76E-11 1.27E-11 1.76E-11 3.02E-11 6.34E-11 6.41E-11 2

53 Projections w/bias 6.95E-11 3.35E-11 1.93E-11 1.39E-11 1.92E-11 3.30E-11 6.92E-11 7.00E-11 2

53

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 20 of 62 February 8, 2023

Total Iron Atom Displacements at the RPV Clad / Base Metal Interface Cycle Cycle Length (EFPY)

Total Time (EFPY)

Iron Atom Displacements (dpa)

Azimuth of Max.

(°)

Axial Location of Max.

(cm) 0° 15° 30° 45° 60° 75° 90° Maximum 1

1.34 1.34 4.53E-03 2.04E-03 1.13E-03 7.36E-04 1.12E-03 2.04E-03 4.50E-03 4.53E-03 0

-52 2

0.85 2.19 7.34E-03 3.38E-03 1.89E-03 1.21E-03 1.87E-03 3.37E-03 7.30E-03 7.34E-03 0

-52 3

1.14 3.33 1.05E-02 4.89E-03 2.79E-03 1.81E-03 2.77E-03 4.85E-03 1.04E-02 1.05E-02 2

-2 4

0.83 4.16 1.35E-02 6.27E-03 3.52E-03 2.29E-03 3.50E-03 6.21E-03 1.35E-02 1.36E-02 2

-2 5

0.85 5.00 1.65E-02 7.62E-03 4.25E-03 2.74E-03 4.22E-03 7.55E-03 1.64E-02 1.65E-02 2

-2 6

0.88 5.88 1.94E-02 8.94E-03 4.98E-03 3.19E-03 4.94E-03 8.87E-03 1.92E-02 1.94E-02 2

-2 7

0.81 6.69 2.21E-02 1.02E-02 5.72E-03 3.64E-03 5.67E-03 1.02E-02 2.19E-02 2.21E-02 2

-2 8

0.84 7.53 2.48E-02 1.15E-02 6.43E-03 4.08E-03 6.38E-03 1.14E-02 2.47E-02 2.50E-02 2

-2 9

0.86 8.38 2.64E-02 1.24E-02 7.08E-03 4.49E-03 7.02E-03 1.23E-02 2.62E-02 2.65E-02 2

-2 10 0.87 9.26 2.80E-02 1.34E-02 7.84E-03 4.91E-03 7.79E-03 1.32E-02 2.78E-02 2.82E-02 2

-2 11 0.92 10.17 2.96E-02 1.45E-02 8.69E-03 5.34E-03 8.62E-03 1.43E-02 2.94E-02 2.98E-02 2

2 12 0.98 11.15 3.12E-02 1.57E-02 9.61E-03 5.78E-03 9.54E-03 1.55E-02 3.11E-02 3.15E-02 2

2 13 0.98 12.14 3.27E-02 1.68E-02 1.05E-02 6.23E-03 1.04E-02 1.65E-02 3.25E-02 3.29E-02 2

2 14 1.00 13.13 3.41E-02 1.79E-02 1.15E-02 6.69E-03 1.14E-02 1.77E-02 3.39E-02 3.44E-02 2

2 15 1.07 14.21 3.55E-02 1.91E-02 1.25E-02 7.17E-03 1.24E-02 1.88E-02 3.54E-02 3.58E-02 2

2 16 1.08 15.28 3.80E-02 2.03E-02 1.31E-02 7.62E-03 1.30E-02 2.00E-02 3.78E-02 3.83E-02 1

2 17 1.18 16.47 4.04E-02 2.16E-02 1.38E-02 8.06E-03 1.37E-02 2.13E-02 4.02E-02 4.08E-02 1

2 18 1.35 17.81 4.29E-02 2.29E-02 1.45E-02 8.52E-03 1.44E-02 2.26E-02 4.27E-02 4.33E-02 1

50 19 1.41 19.23 4.53E-02 2.42E-02 1.53E-02 9.06E-03 1.52E-02 2.39E-02 4.51E-02 4.58E-02 1

50 20 1.42 20.65 4.75E-02 2.54E-02 1.61E-02 9.63E-03 1.60E-02 2.50E-02 4.72E-02 4.79E-02 1

50

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 21 of 62 February 8, 2023

Total Iron Atom Displacements at the RPV Clad / Base Metal Interface Cycle Cycle Length (EFPY)

Total Time (EFPY)

Iron Atom Displacements (dpa)

Azimuth of Max.

(°)

Axial Location of Max.

(cm) 0° 15° 30° 45° 60° 75° 90° Maximum 21 1.40 22.05 4.95E-02 2.66E-02 1.69E-02 1.02E-02 1.68E-02 2.62E-02 4.92E-02 5.00E-02 1

50 22 1.44 23.49 5.25E-02 2.79E-02 1.75E-02 1.06E-02 1.74E-02 2.76E-02 5.22E-02 5.30E-02 1

50 23 1.31 24.80 5.49E-02 2.91E-02 1.80E-02 1.10E-02 1.79E-02 2.87E-02 5.46E-02 5.54E-02 1

50 24 1.45 26.24 5.72E-02 3.03E-02 1.87E-02 1.15E-02 1.86E-02 2.99E-02 5.68E-02 5.77E-02 1

50 25 1.37 27.62 5.92E-02 3.13E-02 1.93E-02 1.19E-02 1.92E-02 3.09E-02 5.89E-02 5.98E-02 1

50 26 1.34 28.95 6.06E-02 3.22E-02 1.98E-02 1.24E-02 1.97E-02 3.18E-02 6.03E-02 6.13E-02 1

50 27 1.35 30.31 6.24E-02 3.32E-02 2.04E-02 1.28E-02 2.03E-02 3.28E-02 6.21E-02 6.31E-02 1

50 28 1.46 31.77 6.55E-02 3.47E-02 2.11E-02 1.33E-02 2.10E-02 3.43E-02 6.52E-02 6.62E-02 1

50 29 1.41 33.18 6.79E-02 3.59E-02 2.18E-02 1.38E-02 2.17E-02 3.54E-02 6.75E-02 6.86E-02 1

50 30 1.59 34.78 7.06E-02 3.74E-02 2.27E-02 1.43E-02 2.26E-02 3.69E-02 7.02E-02 7.13E-02 1

50 31 1.43 36.21 7.25E-02 3.86E-02 2.34E-02 1.48E-02 2.33E-02 3.81E-02 7.21E-02 7.33E-02 1

50 32 1.86 38.07 7.62E-02 4.04E-02 2.45E-02 1.56E-02 2.43E-02 3.98E-02 7.59E-02 7.71E-02 1

50

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 22 of 62 February 8, 2023

Total Iron Atom Displacements at the RPV Clad / Base Metal Interface Cycle Cycle Length (EFPY)

Total Time (EFPY)

Iron Atom Displacements (dpa)

Azimuth of Max.

(°)

Axial Location of Max.

(cm) 0° 15° 30° 45° 60° 75° 90° Maximum Projection with no bias on peripheral fuel assemblies 42 8.41E-02 4.42E-02 2.67E-02 1.71E-02 2.65E-02 4.36E-02 8.37E-02 8.50E-02 1

50 48 9.62E-02 5.00E-02 3.00E-02 1.95E-02 2.98E-02 4.93E-02 9.57E-02 9.71E-02 1

50 50 1.00E-01 5.19E-02 3.11E-02 2.03E-02 3.09E-02 5.12E-02 9.97E-02 1.01E-01 1

50 54 1.08E-01 5.58E-02 3.33E-02 2.19E-02 3.31E-02 5.50E-02 1.08E-01 1.09E-01 1

50 60 1.20E-01 6.15E-02 3.67E-02 2.43E-02 3.65E-02 6.07E-02 1.20E-01 1.21E-01 1

53 66 1.32E-01 6.73E-02 4.00E-02 2.68E-02 3.98E-02 6.64E-02 1.32E-01 1.33E-01 1

53 70 1.40E-01 7.12E-02 4.22E-02 2.84E-02 4.20E-02 7.02E-02 1.40E-01 1.42E-01 1

53 72 1.44E-01 7.31E-02 4.33E-02 2.92E-02 4.31E-02 7.21E-02 1.44E-01 1.46E-01 1

53 Projection with 10% positive bias on peripheral fuel assemblies 42 8.49E-02 4.45E-02 2.69E-02 1.73E-02 2.67E-02 4.39E-02 8.44E-02 8.57E-02 1

50 48 9.80E-02 5.09E-02 3.05E-02 1.99E-02 3.03E-02 5.02E-02 9.75E-02 9.90E-02 1

50 50 1.02E-01 5.30E-02 3.17E-02 2.08E-02 3.15E-02 5.23E-02 1.02E-01 1.03E-01 1

50 54 1.11E-01 5.72E-02 3.42E-02 2.25E-02 3.40E-02 5.64E-02 1.11E-01 1.12E-01 1

53 60 1.24E-01 6.35E-02 3.78E-02 2.52E-02 3.76E-02 6.27E-02 1.24E-01 1.25E-01 1

53 66 1.37E-01 6.99E-02 4.15E-02 2.78E-02 4.12E-02 6.89E-02 1.37E-01 1.39E-01 1

53 70 1.46E-01 7.41E-02 4.39E-02 2.96E-02 4.37E-02 7.31E-02 1.46E-01 1.48E-01 1

53 72 1.51E-01 7.62E-02 4.51E-02 3.04E-02 4.49E-02 7.52E-02 1.50E-01 1.52E-01 1

53

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 23 of 62 February 8, 2023

Projected Maximum Fast Neutron Fluence at the RPV Welds and Shells Projection with no bias on relative power of peripheral and re-entrant corner fuel assemblies Material Fast Neutron (E > 1.0 MeV) Fluence (n/cm2) 38.07[1]

48 EFPY 50 EFPY 54 EFPY 60 EFPY 66 EFPY 70 EFPY 72 EFPY Limiting Outlet nozzle to upper shell weld (Nozzle at 10°)[2]

2.14E+16 2.79E+16 2.92E+16 3.18E+16 3.58E+16 3.97E+16 4.23E+16 4.36E+16 Limiting Inlet nozzle to upper shell weld (Nozzle at 80°)[2]

3.46E+16 4.50E+16 4.70E+16 5.12E+16 5.75E+16 6.37E+16 6.79E+16 7.00E+16 Upper shell plates 1.65E+19 2.14E+19 2.24E+19 2.43E+19 2.73E+19 3.03E+19 3.22E+19 3.32E+19 Upper shell axial weld 1 (70° (70°)) (Heat #86054B) 6.80E+18 8.51E+18 8.85E+18 9.54E+18 1.06E+19 1.16E+19 1.23E+19 1.26E+19 Upper shell axial weld 2 (190° (80°)) (Heat #86054B) 1.22E+19 1.57E+19 1.63E+19 1.77E+19 1.98E+19 2.18E+19 2.32E+19 2.39E+19 Upper shell axial weld 3 (310° (50°)) (Heat #86054B) 3.64E+18 4.57E+18 4.76E+18 5.14E+18 5.71E+18 6.27E+18 6.65E+18 6.84E+18 Upper shell to intermediate shell circumferential weld (Heat #W5214) 1.88E+19 2.43E+19 2.54E+19 2.77E+19 3.10E+19 3.44E+19 3.66E+19 3.78E+19 Intermediate shell plates 4.61E+19 5.82E+19 6.06E+19 6.55E+19 7.28E+19 8.01E+19 8.49E+19 8.74E+19 Intermediate shell axial weld 1 (10° (80°)) (Heat #86054B) 3.44E+19 4.29E+19 4.46E+19 4.81E+19 5.32E+19 5.84E+19 6.18E+19 6.35E+19 Intermediate shell axial weld 2 (130° (50°)) (Heat #86054B) 1.02E+19 1.28E+19 1.33E+19 1.43E+19 1.58E+19 1.74E+19 1.84E+19 1.89E+19 Intermediate shell axial weld 3 (250° (70°)) (Heat #86054B) 1.96E+19 2.39E+19 2.48E+19 2.66E+19 2.92E+19 3.19E+19 3.36E+19 3.45E+19 Intermediate shell to lower shell circumferential weld (Heat #34B009) 2.14E+19 3.26E+19 3.49E+19 3.94E+19 4.62E+19 5.30E+19 5.75E+19 5.98E+19 Lower shell plates 2.10E+19 3.21E+19 3.43E+19 3.88E+19 4.55E+19 5.22E+19 5.66E+19 5.89E+19 Lower shell axial weld 1 (10° (80°)) (Heat #86054B) 2.10E+19 3.21E+19 3.43E+19 3.88E+19 4.55E+19 5.22E+19 5.66E+19 5.89E+19 Lower shell axial weld 2 (120° (60°)) (Heat #86054B) 1.35E+19 1.66E+19 1.73E+19 1.85E+19 2.04E+19 2.23E+19 2.35E+19 2.41E+19 Lower shell axial weld 3 (240° (60°)) (Heat #86054B) 1.35E+19 1.66E+19 1.73E+19 1.85E+19 2.04E+19 2.23E+19 2.35E+19 2.41E+19 Lower shell to lower vessel head circumferential weld 1.20E+15 1.62E+15 1.71E+15 1.88E+15 2.14E+15 2.39E+15 2.56E+15 2.65E+15 Note: 1. The total EFPY at the end of Cycle 32.

2. The fast neutron fluence for the non-limiting nozzle welds are bounded by the limiting nozzle and are less than 1.0E+17 n/cm2.

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 24 of 62 February 8, 2023

Projected Maximum Fast Neutron Fluence at the RPV Welds and Shells Projection with 10% positive bias on relative power of peripheral and re-entrant corner fuel assemblies Material Fast Neutron (E > 1.0 MeV) Fluence (n/cm2) 38.07[1]

48 EFPY 50 EFPY 54 EFPY 60 EFPY 66 EFPY 70 EFPY 72 EFPY Limiting Outlet nozzle to upper shell weld (Nozzle at 10°)[2]

2.14E+16 2.82E+16 2.96E+16 3.24E+16 3.65E+16 4.06E+16 4.33E+16 4.47E+16 Limiting Inlet nozzle to upper shell weld (Nozzle at 80°)[2]

3.46E+16 4.55E+16 4.77E+16 5.21E+16 5.87E+16 6.52E+16 6.96E+16 7.18E+16 Upper shell plates 1.65E+19 2.18E+19 2.29E+19 2.51E+19 2.83E+19 3.15E+19 3.37E+19 3.48E+19 Upper shell axial weld 1 (70° (70°)) (Heat #86054B) 6.80E+18 8.67E+18 9.04E+18 9.80E+18 1.09E+19 1.21E+19 1.28E+19 1.32E+19 Upper shell axial weld 2 (190° (80°)) (Heat #86054B) 1.22E+19 1.60E+19 1.67E+19 1.82E+19 2.05E+19 2.27E+19 2.42E+19 2.50E+19 Upper shell axial weld 3 (310° (50°)) (Heat #86054B) 3.64E+18 4.66E+18 4.87E+18 5.28E+18 5.90E+18 6.52E+18 6.93E+18 7.14E+18 Upper shell to intermediate shell circumferential weld (Heat #W5214) 1.88E+19 2.48E+19 2.61E+19 2.85E+19 3.22E+19 3.59E+19 3.83E+19 3.95E+19 Intermediate shell plates 4.61E+19 5.93E+19 6.19E+19 6.73E+19 7.52E+19 8.32E+19 8.85E+19 9.12E+19 Intermediate shell axial weld 1 (10° (80°)) (Heat #86054B) 3.44E+19 4.37E+19 4.56E+19 4.94E+19 5.50E+19 6.06E+19 6.44E+19 6.63E+19 Intermediate shell axial weld 2 (130° (50°)) (Heat #86054B) 1.02E+19 1.30E+19 1.36E+19 1.47E+19 1.64E+19 1.81E+19 1.92E+19 1.98E+19 Intermediate shell axial weld 3 (250° (70°)) (Heat #86054B) 1.96E+19 2.43E+19 2.53E+19 2.72E+19 3.01E+19 3.30E+19 3.49E+19 3.59E+19 Intermediate shell to lower shell circumferential weld (Heat #34B009) 2.14E+19 3.36E+19 3.61E+19 4.11E+19 4.85E+19 5.59E+19 6.09E+19 6.33E+19 Lower shell plates 2.10E+19 3.31E+19 3.55E+19 4.04E+19 4.77E+19 5.50E+19 5.99E+19 6.23E+19 Lower shell axial weld 1 (10° (80°)) (Heat #86054B) 2.10E+19 3.31E+19 3.55E+19 4.04E+19 4.77E+19 5.50E+19 5.99E+19 6.23E+19 Lower shell axial weld 2 (120° (60°)) (Heat #86054B) 1.35E+19 1.69E+19 1.76E+19 1.90E+19 2.10E+19 2.31E+19 2.44E+19 2.51E+19 Lower shell axial weld 3 (240° (60°)) (Heat #86054B) 1.35E+19 1.69E+19 1.76E+19 1.90E+19 2.10E+19 2.31E+19 2.44E+19 2.51E+19 Lower shell to lower vessel head circumferential weld 1.20E+15 1.66E+15 1.75E+15 1.94E+15 2.22E+15 2.50E+15 2.68E+15 2.78E+15 Note: 1. The total EFPY at the end of Cycle 32.

2. The fast neutron fluence for the non-limiting nozzle welds are bounded by the limiting nozzle and are less than 1.0E+17 n/cm2.

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 25 of 62 February 8, 2023

Projected Total Iron Atom Displacements for Pressure Vessel Materials Projection with no bias on relative power of peripheral and re-entrant corner fuel assemblies Material Iron Atom Displacements (dpa) 38.07[1]

48 EFPY 50 EFPY 54 EFPY 60 EFPY 66 EFPY 70 EFPY 72 EFPY Outlet nozzle to upper shell weld (Nozzle at 10°)

1.67E-04 2.11E-04 2.20E-04 2.38E-04 2.65E-04 2.93E-04 3.11E-04 3.20E-04 Inlet nozzle to upper shell weld (Nozzle at 80°)

3.12E-04 3.97E-04 4.14E-04 4.47E-04 4.98E-04 5.49E-04 5.83E-04 6.00E-04 Upper shell plates 2.77E-02 3.59E-02 3.76E-02 4.08E-02 4.58E-02 5.07E-02 5.40E-02 5.56E-02 Upper shell axial weld 1 (70° (70°)) (Heat #86054B) 1.13E-02 1.42E-02 1.47E-02 1.59E-02 1.76E-02 1.93E-02 2.05E-02 2.10E-02 Upper shell axial weld 2 (190° (80°)) (Heat #86054B) 2.05E-02 2.62E-02 2.73E-02 2.96E-02 3.31E-02 3.65E-02 3.88E-02 4.00E-02 Upper shell axial weld 3 (310° (50°)) (Heat #86054B) 6.02E-03 7.57E-03 7.88E-03 8.50E-03 9.44E-03 1.04E-02 1.10E-02 1.13E-02 Upper shell to intermediate shell circumferential weld (Heat #W5214) 3.15E-02 4.08E-02 4.27E-02 4.64E-02 5.20E-02 5.76E-02 6.14E-02 6.32E-02 Intermediate shell plates 7.71E-02 9.71E-02 1.01E-01 1.09E-01 1.21E-01 1.33E-01 1.42E-01 1.46E-01 Intermediate shell axial weld 1 (10° (80°)) (Heat #86054B) 5.68E-02 7.09E-02 7.38E-02 7.95E-02 8.80E-02 9.66E-02 1.02E-01 1.05E-01 Intermediate shell axial weld 2 (130° (50°)) (Heat #86054B) 1.66E-02 2.08E-02 2.16E-02 2.33E-02 2.58E-02 2.83E-02 3.00E-02 3.08E-02 Intermediate shell axial weld 3 (250° (70°)) (Heat #86054B) 3.21E-02 3.92E-02 4.07E-02 4.36E-02 4.79E-02 5.23E-02 5.52E-02 5.67E-02 Intermediate shell to lower shell circumferential weld (Heat #34B009) 3.51E-02 5.36E-02 5.73E-02 6.47E-02 7.58E-02 8.69E-02 9.44E-02 9.81E-02 Lower shell plates 3.45E-02 5.27E-02 5.63E-02 6.36E-02 7.46E-02 8.55E-02 9.29E-02 9.65E-02 Lower shell axial weld 1 (10° (80°)) (Heat #86054B) 3.45E-02 5.27E-02 5.63E-02 6.36E-02 7.46E-02 8.55E-02 9.29E-02 9.65E-02 Lower shell axial weld 2 (120° (60°)) (Heat #86054B) 2.19E-02 2.69E-02 2.80E-02 3.00E-02 3.30E-02 3.61E-02 3.81E-02 3.91E-02 Lower shell axial weld 3 (240° (60°)) (Heat #86054B) 2.19E-02 2.69E-02 2.80E-02 3.00E-02 3.30E-02 3.61E-02 3.81E-02 3.91E-02 Lower shell to lower vessel head circumferential weld 1.50E-05 2.03E-05 2.14E-05 2.35E-05 2.67E-05 3.00E-05 3.21E-05 3.32E-05 Note: 1. The total EFPY at the end of Cycle 32.

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 26 of 62 February 8, 2023

Projected Total Iron Atom Displacements for Pressure Vessel Materials Projection with 10% positive bias on relative power of peripheral and re-entrant corner fuel assemblies Material Iron Atom Displacements (dpa) 38.07[1]

48 EFPY 50 EFPY 54 EFPY 60 EFPY 66 EFPY 70 EFPY 72 EFPY Outlet nozzle to upper shell weld (Nozzle at 10°)

1.67E-04 2.16E-04 2.25E-04 2.45E-04 2.75E-04 3.04E-04 3.24E-04 3.34E-04 Inlet nozzle to upper shell weld (Nozzle at 80°)

3.12E-04 4.04E-04 4.23E-04 4.60E-04 5.15E-04 5.71E-04 6.08E-04 6.26E-04 Upper shell plates 2.77E-02 3.67E-02 3.85E-02 4.21E-02 4.75E-02 5.28E-02 5.64E-02 5.82E-02 Upper shell axial weld 1 (70° (70°)) (Heat #86054B) 1.13E-02 1.44E-02 1.50E-02 1.63E-02 1.82E-02 2.01E-02 2.13E-02 2.19E-02 Upper shell axial weld 2 (190° (80°)) (Heat #86054B) 2.05E-02 2.67E-02 2.80E-02 3.05E-02 3.43E-02 3.80E-02 4.05E-02 4.18E-02 Upper shell axial weld 3 (310° (50°)) (Heat #86054B) 6.02E-03 7.71E-03 8.05E-03 8.74E-03 9.76E-03 1.08E-02 1.15E-02 1.18E-02 Upper shell to intermediate shell circumferential weld (Heat #W5214) 3.15E-02 4.17E-02 4.37E-02 4.78E-02 5.39E-02 6.01E-02 6.42E-02 6.62E-02 Intermediate shell plates 7.71E-02 9.90E-02 1.03E-01 1.12E-01 1.25E-01 1.39E-01 1.48E-01 1.52E-01 Intermediate shell axial weld 1 (10° (80°)) (Heat #86054B) 5.68E-02 7.23E-02 7.54E-02 8.16E-02 9.09E-02 1.00E-01 1.07E-01 1.10E-01 Intermediate shell axial weld 2 (130° (50°)) (Heat #86054B) 1.66E-02 2.11E-02 2.21E-02 2.39E-02 2.67E-02 2.94E-02 3.12E-02 3.22E-02 Intermediate shell axial weld 3 (250° (70°)) (Heat #86054B) 3.21E-02 3.99E-02 4.15E-02 4.47E-02 4.94E-02 5.42E-02 5.74E-02 5.89E-02 Intermediate shell to lower shell circumferential weld (Heat #34B009) 3.51E-02 5.53E-02 5.93E-02 6.74E-02 7.96E-02 9.17E-02 9.98E-02 1.04E-01 Lower shell plates 3.45E-02 5.43E-02 5.83E-02 6.63E-02 7.83E-02 9.02E-02 9.82E-02 1.02E-01 Lower shell axial weld 1 (10° (80°)) (Heat #86054B) 3.45E-02 5.43E-02 5.83E-02 6.63E-02 7.83E-02 9.02E-02 9.82E-02 1.02E-01 Lower shell axial weld 2 (120° (60°)) (Heat #86054B) 2.19E-02 2.74E-02 2.85E-02 3.07E-02 3.41E-02 3.74E-02 3.96E-02 4.07E-02 Lower shell axial weld 3 (240° (60°)) (Heat #86054B) 2.19E-02 2.74E-02 2.85E-02 3.07E-02 3.41E-02 3.74E-02 3.96E-02 4.07E-02 Lower shell to lower vessel head circumferential weld 1.50E-05 2.08E-05 2.19E-05 2.43E-05 2.78E-05 3.13E-05 3.37E-05 3.49E-05 Note: 1. The total EFPY at the end of Cycle 32.

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 27 of 62 February 8, 2023

© 2023 Westinghouse Electric Company LLC All Rights Reserved 5.2 Surveillance Capsules Neutron exposure data for the surveillance capsule locations are provided in Tables 5-7 through 5-10. The 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 5-7 and Table 5-8 as a function of irradiation time. Similar data in terms of iron atom displacement rate and iron atom displacements are provided in Tables 5-9 and 5-10. The data in Tables 5-7 through 5-10 are reported in terms of the quadrant equivalent azimuthal angles encompassing the surveillance capsule locations contained in the reactor.

The irradiation history and calculated lead factor for each of the eight in-vessel surveillance capsules is as follows:

Lead Factors for H. B. Robinson Unit 2 Surveillance Capsules Capsule Azimuthal Location Quadrant-Equivalent Location Status Capsule Fast Neutron Fluence (n/cm2)

Lead Factor S

280º 10º Withdrawn EOC 1 5.26E+18 1.92 V

290º 20º Withdrawn EOC 3 5.59E+18 0.88 T

270º 0º Withdrawn EOC 8 4.18E+19 2.78 X(2) 50º, 270º 40º, 0º Withdrawn EOC 20 4.43E+19 1.54 Z(6) 230º 40º Withdrawn EOC 1 1.18E+18 0.43 U(3) 30º, 280º 30º, 10º In Reactor 7.45E+19 1.62 Y(4) 150º, 290° 30º, 20° In Reactor 4.08E+19 0.88 W(5) 40º, 270° 40º, 0° In Reactor 4.37E+19 0.95 Notes:

1. This table was adapted from Table 2-5 of WCAP-18751-NP (Reference 4).

2. Capsule X was relocated from 50° (40° with respect to core cardinal axes) to 270° (0° with respect to core cardinal axes) at EOC 8.

3. Capsule U was relocated from 30° to 280° (10° with respect to core cardinal axes) at EOC 8.

4. Capsule Y was relocated from 150° (30° with respect to core cardinal axes) to 290° (20° with respect to core cardinal axes) at EOC 27.

5. Capsule W was relocated from 40° to 270° (0° with respect to core cardinal axes) at EOC 27.

6. Capsule Z was not analyzed.

The analyzed surveillance capsule dosimetry are described in detail in WCAP-18751-NP (Reference 4).

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 28 of 62 February 8, 2023

Fast Fluence Rate at the Center of the Surveillance Capsules at Core Midplane Cycle Cycle Length (EFPY)

Total Time (EFPY)

Fast (E > 1.0 MeV) Neutron Fluence Rate (n/cm2s) 0° 10° 20° 30° 40° 1

1.34 1.34 1.77E+11 1.25E+11 5.35E+10 4.15E+10 2.79E+10 2

0.85 2.19 1.77E+11 1.30E+11 5.74E+10 4.49E+10 2.92E+10 3

1.14 3.33 1.50E+11 1.06E+11 4.97E+10 4.04E+10 2.74E+10 4

0.83 4.16 1.97E+11 1.40E+11 5.73E+10 4.44E+10 2.98E+10 5

0.85 5.00 1.83E+11 1.32E+11 5.55E+10 4.26E+10 2.77E+10 6

0.88 5.88 1.74E+11 1.25E+11 5.34E+10 4.15E+10 2.69E+10 7

0.81 6.69 1.77E+11 1.29E+11 5.80E+10 4.55E+10 2.89E+10 8

0.84 7.53 1.80E+11 1.30E+11 5.57E+10 4.32E+10 2.75E+10 9

0.86 8.38 9.91E+10 7.30E+10 4.42E+10 3.94E+10 2.60E+10 10 0.87 9.26 1.02E+11 7.84E+10 5.44E+10 4.53E+10 2.55E+10 11 0.92 10.17 9.23E+10 7.50E+10 5.68E+10 4.67E+10 2.43E+10 12 0.98 11.15 8.65E+10 7.20E+10 5.85E+10 4.78E+10 2.42E+10 13 0.98 12.14 7.52E+10 6.41E+10 5.51E+10 4.65E+10 2.44E+10 14 1.00 13.13 7.42E+10 6.52E+10 5.88E+10 4.91E+10 2.49E+10 15 1.07 14.21 7.03E+10 6.26E+10 5.81E+10 4.85E+10 2.41E+10 16 1.08 15.28 1.21E+11 8.81E+10 4.02E+10 2.97E+10 2.13E+10 17 1.18 16.47 1.08E+11 8.05E+10 3.86E+10 2.77E+10 1.87E+10 18 1.35 17.81 9.65E+10 7.19E+10 3.71E+10 2.78E+10 1.77E+10 19 1.41 19.23 8.95E+10 6.73E+10 3.60E+10 2.82E+10 1.99E+10 20 1.42 20.65 7.82E+10 5.96E+10 3.39E+10 2.74E+10 2.03E+10 21 1.40 22.05 7.51E+10 5.80E+10 3.47E+10 2.79E+10 2.00E+10 22 1.44 23.49 1.09E+11 7.76E+10 3.14E+10 2.06E+10 1.51E+10 23 1.31 24.80 9.49E+10 6.88E+10 3.07E+10 2.12E+10 1.62E+10 24 1.45 26.24 8.01E+10 5.93E+10 2.95E+10 2.18E+10 1.64E+10 25 1.37 27.62 7.70E+10 5.80E+10 2.94E+10 2.11E+10 1.57E+10 26 1.34 28.95 5.55E+10 4.44E+10 2.69E+10 2.09E+10 1.59E+10 27 1.35 30.31 6.69E+10 5.10E+10 2.83E+10 2.13E+10 1.64E+10 28 1.46 31.77 1.10E+11 7.84E+10 3.51E+10 2.55E+10 1.73E+10 29 1.41 33.18 8.83E+10 6.53E+10 3.06E+10 2.22E+10 1.62E+10 30 1.59 34.78 8.75E+10 6.54E+10 3.52E+10 2.72E+10 1.86E+10 31 1.43 36.21 7.02E+10 5.60E+10 3.49E+10 2.66E+10 1.69E+10 32 1.86 38.07 1.06E+11 7.41E+10 3.49E+10 2.74E+10 2.02E+10 Projection s no bias 1.06E+11 7.41E+10 3.49E+10 2.74E+10 2.02E+10 Projection s w/bias 1.15E+11 8.11E+10 3.82E+10 3.00E+10 2.21E+10

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 29 of 62 February 8, 2023

Fast Fluence at the Center of the Surveillance Capsules at Core Midplane Cycle Cycle Length (EFPY)

Total Time (EFPY)

Fast (E > 1.0 MeV) Neutron Fluence (n/cm2) 0° 10° 20° 30° 40° 1

1.34 1.34 7.49E+18 5.26E+18 2.26E+18 1.75E+18 1.18E+18 2

0.85 2.19 1.22E+19 8.75E+18 3.80E+18 2.96E+18 1.96E+18 3

1.14 3.33 1.77E+19 1.26E+19 5.59E+18 4.41E+18 2.95E+18 4

0.83 4.16 2.28E+19 1.62E+19 7.08E+18 5.57E+18 3.73E+18 5

0.85 5.00 2.77E+19 1.98E+19 8.57E+18 6.71E+18 4.47E+18 6

0.88 5.88 3.25E+19 2.32E+19 1.00E+19 7.86E+18 5.21E+18 7

0.81 6.69 3.71E+19 2.65E+19 1.15E+19 9.02E+18 5.95E+18 8

0.84 7.53 4.18E+19 2.99E+19 1.30E+19 1.02E+19 6.68E+18 9

0.86 8.38 4.45E+19 3.19E+19 1.42E+19 1.12E+19 7.38E+18 10 0.87 9.26 4.73E+19 3.41E+19 1.57E+19 1.25E+19 8.08E+18 11 0.92 10.17 5.00E+19 3.62E+19 1.73E+19 1.38E+19 8.78E+18 12 0.98 11.15 5.26E+19 3.85E+19 1.91E+19 1.53E+19 9.53E+18 13 0.98 12.14 5.50E+19 4.04E+19 2.09E+19 1.67E+19 1.03E+19 14 1.00 13.13 5.73E+19 4.25E+19 2.27E+19 1.83E+19 1.11E+19 15 1.07 14.21 5.97E+19 4.46E+19 2.47E+19 1.99E+19 1.19E+19 16 1.08 15.28 6.38E+19 4.76E+19 2.60E+19 2.09E+19 1.26E+19 17 1.18 16.47 6.79E+19 5.06E+19 2.75E+19 2.20E+19 1.33E+19 18 1.35 17.81 7.20E+19 5.37E+19 2.91E+19 2.32E+19 1.41E+19 19 1.41 19.23 7.59E+19 5.67E+19 3.07E+19 2.44E+19 1.49E+19 20 1.42 20.65 7.95E+19 5.93E+19 3.22E+19 2.56E+19 1.59E+19 21 1.40 22.05 8.28E+19 6.19E+19 3.37E+19 2.69E+19 1.67E+19 22 1.44 23.49 8.77E+19 6.54E+19 3.51E+19 2.78E+19 1.74E+19 23 1.31 24.80 9.16E+19 6.83E+19 3.64E+19 2.87E+19 1.81E+19 24 1.45 26.24 9.53E+19 7.10E+19 3.78E+19 2.97E+19 1.88E+19 25 1.37 27.62 9.86E+19 7.35E+19 3.90E+19 3.06E+19 1.95E+19 26 1.34 28.95 1.01E+20 7.54E+19 4.02E+19 3.15E+19 2.02E+19 27 1.35 30.31 1.04E+20 7.75E+19 4.14E+19 3.24E+19 2.09E+19 28 1.46 31.77 1.09E+20 8.12E+19 4.30E+19 3.36E+19 2.17E+19 29 1.41 33.18 1.13E+20 8.41E+19 4.44E+19 3.46E+19 2.24E+19 30 1.59 34.78 1.17E+20 8.74E+19 4.61E+19 3.59E+19 2.33E+19 31 1.43 36.21 1.20E+20 8.99E+19 4.77E+19 3.71E+19 2.41E+19 32 1.86 38.07 1.27E+20 9.43E+19 4.98E+19 3.87E+19 2.53E+19

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 30 of 62 February 8, 2023

Fast Fluence at the Center of the Surveillance Capsules at Core Midplane Projection with no bias on relative power of peripheral and re-entrant corner fuel assemblies Cycle Cycle Length (EFPY)

Total Time (EFPY)

Fast (E > 1.0 MeV) Neutron Fluence (n/cm2) 0° 10° 20° 30° 40° Projection 42 1.40E+20 1.03E+20 5.41E+19 4.21E+19 2.78E+19 48 1.60E+20 1.17E+20 6.07E+19 4.73E+19 3.16E+19 50 1.66E+20 1.22E+20 6.29E+19 4.91E+19 3.29E+19 54 1.80E+20 1.32E+20 6.73E+19 5.25E+19 3.55E+19 60 2.00E+20 1.46E+20 7.39E+19 5.77E+19 3.93E+19 66 2.20E+20 1.60E+20 8.05E+19 6.29E+19 4.31E+19 70 2.33E+20 1.69E+20 8.50E+19 6.63E+19 4.57E+19 72 2.40E+20 1.74E+20 8.72E+19 6.81E+19 4.69E+19 Projection with 10% positive bias on relative power of peripheral and re-entrant corner fuel assemblies Cycle Cycle Length (EFPY)

Total Time (EFPY)

Fast (E > 1.0 MeV) Neutron Fluence (n/cm2) 0° 10° 20° 30° 40° Projection 42 1.41E+20 1.04E+20 5.45E+19 4.25E+19 2.80E+19 48 1.63E+20 1.20E+20 6.17E+19 4.81E+19 3.22E+19 50 1.70E+20 1.25E+20 6.41E+19 5.00E+19 3.36E+19 54 1.85E+20 1.35E+20 6.89E+19 5.38E+19 3.64E+19 60 2.06E+20 1.50E+20 7.62E+19 5.95E+19 4.06E+19 66 2.28E+20 1.66E+20 8.34E+19 6.52E+19 4.48E+19 70 2.43E+20 1.76E+20 8.82E+19 6.90E+19 4.76E+19 72 2.50E+20 1.81E+20 9.06E+19 7.09E+19 4.90E+19

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 31 of 62 February 8, 2023

Iron Atom Displacement Rate at the Center of the Surveillance Capsules at Core Midplane Cycle Cycle Length (EFPY)

Total Time (EFPY)

Iron Atom Displacement Rate (dpa/s) 0° 10° 20° 30° 40° 1

1.34 1.34 3.00E-10 2.12E-10 8.73E-11 6.80E-11 4.50E-11 2

0.85 2.19 3.00E-10 2.21E-10 9.36E-11 7.34E-11 4.71E-11 3

1.14 3.33 2.54E-10 1.79E-10 8.10E-11 6.61E-11 4.41E-11 4

0.83 4.16 3.34E-10 2.39E-10 9.36E-11 7.26E-11 4.81E-11 5

0.85 5.00 3.09E-10 2.25E-10 9.06E-11 6.97E-11 4.46E-11 6

0.88 5.88 2.95E-10 2.12E-10 8.73E-11 6.79E-11 4.33E-11 7

0.81 6.69 3.00E-10 2.20E-10 9.47E-11 7.44E-11 4.66E-11 8

0.84 7.53 3.05E-10 2.20E-10 9.08E-11 7.06E-11 4.43E-11 9

0.86 8.38 1.66E-10 1.22E-10 7.15E-11 6.41E-11 4.17E-11 10 0.87 9.26 1.71E-10 1.32E-10 8.82E-11 7.40E-11 4.10E-11 11 0.92 10.17 1.55E-10 1.26E-10 9.22E-11 7.64E-11 3.91E-11 12 0.98 11.15 1.45E-10 1.21E-10 9.48E-11 7.82E-11 3.90E-11 13 0.98 12.14 1.26E-10 1.08E-10 8.93E-11 7.61E-11 3.93E-11 14 1.00 13.13 1.24E-10 1.09E-10 9.52E-11 8.04E-11 4.01E-11 15 1.07 14.21 1.18E-10 1.05E-10 9.40E-11 7.93E-11 3.88E-11 16 1.08 15.28 2.04E-10 1.49E-10 6.53E-11 4.85E-11 3.42E-11 17 1.18 16.47 1.82E-10 1.36E-10 6.26E-11 4.52E-11 3.01E-11 18 1.35 17.81 1.62E-10 1.21E-10 6.02E-11 4.52E-11 2.84E-11 19 1.41 19.23 1.50E-10 1.13E-10 5.84E-11 4.59E-11 3.20E-11 20 1.42 20.65 1.31E-10 1.00E-10 5.49E-11 4.46E-11 3.26E-11 21 1.40 22.05 1.26E-10 9.73E-11 5.62E-11 4.54E-11 3.21E-11 22 1.44 23.49 1.83E-10 1.31E-10 5.11E-11 3.36E-11 2.43E-11 23 1.31 24.80 1.59E-10 1.16E-10 4.98E-11 3.45E-11 2.60E-11 24 1.45 26.24 1.34E-10 9.99E-11 4.79E-11 3.56E-11 2.64E-11 25 1.37 27.62 1.29E-10 9.76E-11 4.78E-11 3.43E-11 2.52E-11 26 1.34 28.95 9.28E-11 7.46E-11 4.36E-11 3.40E-11 2.55E-11 27 1.35 30.31 1.12E-10 8.57E-11 4.58E-11 3.47E-11 2.63E-11 28 1.46 31.77 1.84E-10 1.32E-10 5.71E-11 4.16E-11 2.78E-11 29 1.41 33.18 1.48E-10 1.10E-10 4.98E-11 3.62E-11 2.61E-11 30 1.59 34.78 1.47E-10 1.10E-10 5.71E-11 4.43E-11 2.98E-11 31 1.43 36.21 1.18E-10 9.41E-11 5.65E-11 4.33E-11 2.73E-11 32 1.86 38.07 1.78E-10 1.25E-10 5.68E-11 4.47E-11 3.25E-11 Projections no bias 1.78E-10 1.25E-10 5.68E-11 4.47E-11 3.25E-11 Projections w/bias 1.94E-10 1.37E-10 6.21E-11 4.89E-11 3.56E-11

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 32 of 62 February 8, 2023

Total Iron Atom Displacements at the Center of the Surveillance Capsules at Core Midplane Cycle Cycle Length (EFPY)

Total Time (EFPY)

Iron Atom Displacements (dpa) 0° 10° 20° 30° 40° 1

1.34 1.34 1.27E-02 8.94E-03 3.68E-03 2.87E-03 1.90E-03 2

0.85 2.19 2.07E-02 1.49E-02 6.20E-03 4.84E-03 3.16E-03 3

1.14 3.33 2.99E-02 2.13E-02 9.12E-03 7.22E-03 4.75E-03 4

0.83 4.16 3.86E-02 2.76E-02 1.16E-02 9.11E-03 6.00E-03 5

0.85 5.00 4.69E-02 3.36E-02 1.40E-02 1.10E-02 7.20E-03 6

0.88 5.88 5.50E-02 3.95E-02 1.64E-02 1.29E-02 8.40E-03 7

0.81 6.69 6.27E-02 4.51E-02 1.88E-02 1.48E-02 9.59E-03 8

0.84 7.53 7.07E-02 5.09E-02 2.12E-02 1.66E-02 1.08E-02 9

0.86 8.38 7.52E-02 5.42E-02 2.31E-02 1.84E-02 1.19E-02 10 0.87 9.26 7.99E-02 5.78E-02 2.56E-02 2.04E-02 1.30E-02 11 0.92 10.17 8.44E-02 6.15E-02 2.82E-02 2.26E-02 1.41E-02 12 0.98 11.15 8.89E-02 6.52E-02 3.12E-02 2.50E-02 1.53E-02 13 0.98 12.14 9.28E-02 6.85E-02 3.39E-02 2.74E-02 1.66E-02 14 1.00 13.13 9.67E-02 7.20E-02 3.69E-02 2.99E-02 1.78E-02 15 1.07 14.21 1.01E-01 7.55E-02 4.01E-02 3.26E-02 1.91E-02 16 1.08 15.28 1.08E-01 8.06E-02 4.23E-02 3.42E-02 2.03E-02 17 1.18 16.47 1.14E-01 8.57E-02 4.47E-02 3.59E-02 2.14E-02 18 1.35 17.81 1.21E-01 9.08E-02 4.72E-02 3.79E-02 2.26E-02 19 1.41 19.23 1.28E-01 9.58E-02 4.98E-02 3.99E-02 2.41E-02 20 1.42 20.65 1.34E-01 1.00E-01 5.23E-02 4.19E-02 2.55E-02 21 1.40 22.05 1.39E-01 1.05E-01 5.48E-02 4.39E-02 2.69E-02 22 1.44 23.49 1.48E-01 1.11E-01 5.71E-02 4.54E-02 2.81E-02 23 1.31 24.80 1.54E-01 1.15E-01 5.92E-02 4.69E-02 2.91E-02 24 1.45 26.24 1.60E-01 1.20E-01 6.14E-02 4.85E-02 3.03E-02 25 1.37 27.62 1.66E-01 1.24E-01 6.34E-02 5.00E-02 3.14E-02 26 1.34 28.95 1.70E-01 1.27E-01 6.53E-02 5.14E-02 3.25E-02 27 1.35 30.31 1.75E-01 1.31E-01 6.72E-02 5.29E-02 3.36E-02 28 1.46 31.77 1.83E-01 1.37E-01 6.99E-02 5.48E-02 3.49E-02 29 1.41 33.18 1.90E-01 1.42E-01 7.21E-02 5.64E-02 3.61E-02 30 1.59 34.78 1.97E-01 1.48E-01 7.50E-02 5.86E-02 3.76E-02 31 1.43 36.21 2.03E-01 1.52E-01 7.75E-02 6.06E-02 3.88E-02 32 1.86 38.07 2.13E-01 1.59E-01 8.08E-02 6.32E-02 4.07E-02

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 33 of 62 February 8, 2023

Total Iron Atom Displacements at the Center of the Surveillance Capsules at Core Midplane Projection with no bias on relative power of peripheral and re-entrant corner fuel assemblies Cycle Cycle Length (EFPY)

Total Time (EFPY)

Iron Atom Displacements (dpa) 0° 10° 20° 30° 40° Projection 42 2.35E-01 1.75E-01 8.79E-02 6.88E-02 4.47E-02 48 2.69E-01 1.98E-01 9.87E-02 7.72E-02 5.09E-02 50 2.80E-01 2.06E-01 1.02E-01 8.00E-02 5.30E-02 54 3.02E-01 2.22E-01 1.09E-01 8.57E-02 5.71E-02 60 3.36E-01 2.46E-01 1.20E-01 9.41E-02 6.32E-02 66 3.70E-01 2.70E-01 1.31E-01 1.03E-01 6.94E-02 70 3.92E-01 2.86E-01 1.38E-01 1.08E-01 7.35E-02 72 4.03E-01 2.93E-01 1.42E-01 1.11E-01 7.55E-02 Projection with 10% positive bias on relative power of peripheral and re-entrant corner fuel assemblies Cycle Cycle Length (EFPY)

Total Time (EFPY)

Iron Atom Displacements (dpa) 0° 10° 20° 30° 40° Projection 42 2.37E-01 1.76E-01 8.85E-02 6.93E-02 4.51E-02 48 2.74E-01 2.02E-01 1.00E-01 7.86E-02 5.19E-02 50 2.86E-01 2.11E-01 1.04E-01 8.16E-02 5.41E-02 54 3.11E-01 2.28E-01 1.12E-01 8.78E-02 5.86E-02 60 3.47E-01 2.54E-01 1.24E-01 9.71E-02 6.54E-02 66 3.84E-01 2.80E-01 1.36E-01 1.06E-01 7.21E-02 70 4.09E-01 2.97E-01 1.43E-01 1.13E-01 7.66E-02 72 4.21E-01 3.06E-01 1.47E-01 1.16E-01 7.88E-02

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 34 of 62 February 8, 2023

© 2023 Westinghouse Electric Company LLC All Rights Reserved 5.3 RPV Support Structure Maximum projected exposures of the RPV support structures are given in Table 5-11 through Table 5-16. Neutron exposure is given for two energy ranges. Fluence rates and fluence from neutrons with energies greater than 1.0 MeV are provided in Table 5-11 and 5-12, respectively. Fluence rates and fluence from neutrons with energies greater than 0.1 MeV are provided in Table 5-13 through 5-14, respectively. The fluence is reported is the maximum exposure of the major subcomponents of the support structure. The leveling bolts are assumed to be embedded in the upper plate. As such, the exposures for the upper plate were applied to the leveling bolts. Similar data are presented in terms of iron atom displacement rate and iron atom displacements in Tables 5-15 and 5-16.

Maximum exposures of the RPV support structure anchor bolts were analyzed. Two bolt positions, bolts Mark B5 and Mark B6, were selected as limiting bolt locations with respect to neutron exposure. The fast (E > 1.0 MeV) neutron fluence rates and fluences determined at the limiting Mark B5 and Mark B6 RPV support structure anchor bolt locations are provided in Table 5-17 and Table 5-18 as a function of irradiation time. Similarly, the fast (E > 0.1 MeV) neutron fluence rates and fluences determined at the limiting Mark B5 and Mark B6 RPV support structure anchor bolt locations are provided in Table 5-19 and Table 5-20 as a function of irradiation time. Iron atom displacement rates (dpa/s) and iron atom displacements (dpa) determined at the limiting Mark B5 and Mark B6 RPV support structure anchor bolt locations are provided in Table 5-21 and Table 5-22 as a function of irradiation time. These neutron exposures consider the full length of the bolts, including the portions embedded in the concrete bioshield.

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 35 of 62 February 8, 2023

Total Time (EFPY)

Fast Neutron (E > 1.0 MeV) Fluence Rate (n/cm2-s)

Base Plate I-Beams Upper Plate &

Leveling Bolts Support Shoe Shim Plate 1

1.34 1.34 3.19E+08 2.83E+08 9.52E+07 6.86E+07 5.16E+07 2

0.85 2.19 4.23E+08 3.76E+08 1.25E+08 8.94E+07 6.68E+07 3

1.14 3.33 2.94E+08 2.59E+08 8.73E+07 6.32E+07 4.78E+07 4

0.83 4.16 4.60E+08 4.09E+08 1.37E+08 9.77E+07 7.30E+07 5

0.85 5.00 3.99E+08 3.55E+08 1.20E+08 8.59E+07 6.43E+07 6

0.88 5.88 3.96E+08 3.53E+08 1.20E+08 8.58E+07 6.40E+07 7

0.81 6.69 3.78E+08 3.35E+08 1.14E+08 8.20E+07 6.17E+07 8

0.84 7.53 4.00E+08 3.54E+08 1.18E+08 8.50E+07 6.38E+07 9

0.86 8.38 2.41E+08 2.14E+08 7.25E+07 5.22E+07 3.93E+07 10 0.87 9.26 1.91E+08 1.68E+08 5.89E+07 4.37E+07 3.38E+07 11 0.92 10.17 1.94E+08 1.70E+08 5.88E+07 4.37E+07 3.39E+07 12 0.98 11.15 1.87E+08 1.64E+08 5.66E+07 4.21E+07 3.27E+07 13 0.98 12.14 1.74E+08 1.52E+08 5.30E+07 3.93E+07 3.06E+07 14 1.00 13.13 1.77E+08 1.55E+08 5.40E+07 4.01E+07 3.11E+07 15 1.07 14.21 1.74E+08 1.53E+08 5.33E+07 3.95E+07 3.06E+07 16 1.08 15.28 1.83E+08 1.59E+08 5.52E+07 4.14E+07 3.24E+07 17 1.18 16.47 1.86E+08 1.62E+08 5.56E+07 4.13E+07 3.22E+07 18 1.35 17.81 1.75E+08 1.53E+08 5.23E+07 3.88E+07 3.01E+07 19 1.41 19.23 1.74E+08 1.52E+08 5.21E+07 3.84E+07 2.97E+07 20 1.42 20.65 1.64E+08 1.44E+08 4.95E+07 3.65E+07 2.82E+07 21 1.40 22.05 1.58E+08 1.38E+08 4.76E+07 3.51E+07 2.71E+07 22 1.44 23.49 1.98E+08 1.72E+08 5.72E+07 4.20E+07 3.25E+07 23 1.31 24.80 1.87E+08 1.63E+08 5.43E+07 3.98E+07 3.07E+07 24 1.45 26.24 1.76E+08 1.54E+08 5.17E+07 3.78E+07 2.91E+07 25 1.37 27.62 1.66E+08 1.46E+08 4.90E+07 3.58E+07 2.74E+07 26 1.34 28.95 1.36E+08 1.20E+08 4.07E+07 2.98E+07 2.28E+07 27 1.35 30.31 1.61E+08 1.41E+08 4.78E+07 3.49E+07 2.67E+07 28 1.46 31.77 2.04E+08 1.78E+08 5.93E+07 4.36E+07 3.37E+07 29 1.41 33.18 1.78E+08 1.55E+08 5.18E+07 3.80E+07 2.93E+07 30 1.59 34.78 1.73E+08 1.51E+08 5.12E+07 3.77E+07 2.91E+07 31 1.43 36.21 1.65E+08 1.46E+08 5.00E+07 3.66E+07 2.81E+07 32 1.86 38.07 2.29E+08 2.01E+08 6.75E+07 4.91E+07 3.74E+07 Projections no bias 2.29E+08 2.01E+08 6.75E+07 4.91E+07 3.74E+07 Projections w/bias 2.50E+08 2.20E+08 7.36E+07 5.34E+07 4.07E+07

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 36 of 62 February 8, 2023

Total Time (EFPY)

Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

Base Plate I-Beams Upper Plate &

Leveling Bolts Support Shoe Shim Plate 1

1.34 1.34 1.35E+16 1.19E+16 4.02E+15 2.89E+15 2.18E+15 2

0.85 2.19 2.48E+16 2.20E+16 7.38E+15 5.29E+15 3.97E+15 3

1.14 3.33 3.54E+16 3.14E+16 1.05E+16 7.57E+15 5.69E+15 4

0.83 4.16 4.74E+16 4.20E+16 1.41E+16 1.01E+16 7.60E+15 5

0.85 5.00 5.81E+16 5.15E+16 1.73E+16 1.24E+16 9.32E+15 6

0.88 5.88 6.91E+16 6.13E+16 2.06E+16 1.48E+16 1.11E+16 7

0.81 6.69 7.87E+16 6.99E+16 2.35E+16 1.69E+16 1.27E+16 8

0.84 7.53 8.93E+16 7.92E+16 2.67E+16 1.91E+16 1.44E+16 9

0.86 8.38 9.58E+16 8.50E+16 2.86E+16 2.05E+16 1.54E+16 10 0.87 9.26 1.01E+17 8.96E+16 3.02E+16 2.17E+16 1.63E+16 11 0.92 10.17 1.07E+17 9.45E+16 3.19E+16 2.30E+16 1.73E+16 12 0.98 11.15 1.12E+17 9.96E+16 3.37E+16 2.43E+16 1.83E+16 13 0.98 12.14 1.18E+17 1.04E+17 3.53E+16 2.55E+16 1.93E+16 14 1.00 13.13 1.23E+17 1.09E+17 3.70E+16 2.68E+16 2.03E+16 15 1.07 14.21 1.29E+17 1.14E+17 3.88E+16 2.81E+16 2.13E+16 16 1.08 15.28 1.36E+17 1.20E+17 4.07E+16 2.95E+16 2.24E+16 17 1.18 16.47 1.42E+17 1.26E+17 4.28E+16 3.11E+16 2.36E+16 18 1.35 17.81 1.50E+17 1.32E+17 4.50E+16 3.27E+16 2.49E+16 19 1.41 19.23 1.58E+17 1.39E+17 4.73E+16 3.44E+16 2.62E+16 20 1.42 20.65 1.65E+17 1.46E+17 4.96E+16 3.61E+16 2.75E+16 21 1.40 22.05 1.72E+17 1.52E+17 5.17E+16 3.76E+16 2.87E+16 22 1.44 23.49 1.81E+17 1.59E+17 5.43E+16 3.95E+16 3.01E+16 23 1.31 24.80 1.89E+17 1.66E+17 5.65E+16 4.12E+16 3.14E+16 24 1.45 26.24 1.97E+17 1.73E+17 5.89E+16 4.29E+16 3.27E+16 25 1.37 27.62 2.04E+17 1.80E+17 6.10E+16 4.45E+16 3.39E+16 26 1.34 28.95 2.10E+17 1.85E+17 6.27E+16 4.57E+16 3.49E+16 27 1.35 30.31 2.17E+17 1.91E+17 6.47E+16 4.72E+16 3.60E+16 28 1.46 31.77 2.26E+17 1.99E+17 6.75E+16 4.92E+16 3.76E+16 29 1.41 33.18 2.34E+17 2.06E+17 6.98E+16 5.09E+16 3.89E+16 30 1.59 34.78 2.43E+17 2.13E+17 7.24E+16 5.28E+16 4.04E+16 31 1.43 36.21 2.50E+17 2.20E+17 7.46E+16 5.45E+16 4.16E+16 32 1.86 38.07 2.64E+17 2.32E+17 7.86E+16 5.73E+16 4.38E+16

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 37 of 62 February 8, 2023

Maximum Fast Neutron Fluence at the RPV Support Structure Projection with no bias on relative power of peripheral and re-entrant corner fuel assemblies Cycle Cycle Length (EFPY)

Total Time (EFPY)

Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

Base Plate I-Beams Upper Plate &

Leveling Bolts Support Shoe Shim Plate Projection 42 2.92E+17 2.57E+17 8.70E+16 6.34E+16 4.85E+16 48 3.35E+17 2.95E+17 9.97E+16 7.27E+16 5.55E+16 50 3.50E+17 3.08E+17 1.04E+17 7.58E+16 5.79E+16 54 3.79E+17 3.33E+17 1.13E+17 8.20E+16 6.26E+16 60 4.22E+17 3.71E+17 1.25E+17 9.13E+16 6.97E+16 66 4.66E+17 4.09E+17 1.38E+17 1.01E+17 7.68E+16 70 4.95E+17 4.35E+17 1.47E+17 1.07E+17 8.15E+16 72 5.09E+17 4.47E+17 1.51E+17 1.10E+17 8.39E+16 Projection with 10% positive bias on relative power of peripheral and re-entrant corner fuel assemblies Cycle Cycle Length (EFPY)

Total Time (EFPY)

Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

Base Plate I-Beams Upper Plate &

Leveling Bolts Support Shoe Shim Plate Projection 42 2.95E+17 2.59E+17 8.77E+16 6.40E+16 4.89E+16 48 3.42E+17 3.01E+17 1.02E+17 7.41E+16 5.66E+16 50 3.58E+17 3.15E+17 1.06E+17 7.75E+16 5.92E+16 54 3.89E+17 3.42E+17 1.16E+17 8.42E+16 6.43E+16 60 4.37E+17 3.84E+17 1.29E+17 9.43E+16 7.20E+16 66 4.84E+17 4.26E+17 1.43E+17 1.04E+17 7.97E+16 70 5.16E+17 4.53E+17 1.53E+17 1.11E+17 8.49E+16 72 5.32E+17 4.67E+17 1.57E+17 1.15E+17 8.74E+16

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 38 of 62 February 8, 2023

Total Time (EFPY)

Fast Neutron (E > 0.1 MeV) Fluence Rate (n/cm2-s)

Base Plate I-Beams Upper Plate &

Leveling Bolts Support Shoe Shim Plate 1

1.34 1.34 5.56E+09 5.47E+09 2.80E+09 2.25E+09 1.86E+09 2

0.85 2.19 7.27E+09 7.17E+09 3.66E+09 2.93E+09 2.42E+09 3

1.14 3.33 5.12E+09 5.04E+09 2.58E+09 2.07E+09 1.72E+09 4

0.83 4.16 7.92E+09 7.81E+09 4.00E+09 3.20E+09 2.64E+09 5

0.85 5.00 6.89E+09 6.80E+09 3.50E+09 2.80E+09 2.31E+09 6

0.88 5.88 6.79E+09 6.71E+09 3.47E+09 2.78E+09 2.29E+09 7

0.81 6.69 6.55E+09 6.46E+09 3.33E+09 2.67E+09 2.21E+09 8

0.84 7.53 6.86E+09 6.75E+09 3.45E+09 2.77E+09 2.28E+09 9

0.86 8.38 4.03E+09 3.98E+09 2.06E+09 1.65E+09 1.37E+09 10 0.87 9.26 3.36E+09 3.30E+09 1.72E+09 1.39E+09 1.17E+09 11 0.92 10.17 3.41E+09 3.34E+09 1.73E+09 1.40E+09 1.17E+09 12 0.98 11.15 3.29E+09 3.22E+09 1.66E+09 1.35E+09 1.13E+09 13 0.98 12.14 3.05E+09 2.99E+09 1.55E+09 1.26E+09 1.05E+09 14 1.00 13.13 3.10E+09 3.04E+09 1.58E+09 1.28E+09 1.07E+09 15 1.07 14.21 3.04E+09 2.98E+09 1.55E+09 1.26E+09 1.06E+09 16 1.08 15.28 3.27E+09 3.18E+09 1.63E+09 1.33E+09 1.11E+09 17 1.18 16.47 3.27E+09 3.19E+09 1.63E+09 1.32E+09 1.11E+09 18 1.35 17.81 3.06E+09 2.98E+09 1.53E+09 1.24E+09 1.04E+09 19 1.41 19.23 3.01E+09 2.94E+09 1.51E+09 1.23E+09 1.02E+09 20 1.42 20.65 2.84E+09 2.78E+09 1.43E+09 1.16E+09 9.67E+08 21 1.40 22.05 2.72E+09 2.66E+09 1.37E+09 1.11E+09 9.28E+08 22 1.44 23.49 3.44E+09 3.35E+09 1.69E+09 1.36E+09 1.13E+09 23 1.31 24.80 3.22E+09 3.14E+09 1.59E+09 1.28E+09 1.07E+09 24 1.45 26.24 3.02E+09 2.95E+09 1.50E+09 1.21E+09 1.01E+09 25 1.37 27.62 2.84E+09 2.78E+09 1.41E+09 1.14E+09 9.48E+08 26 1.34 28.95 2.32E+09 2.27E+09 1.17E+09 9.43E+08 7.84E+08 27 1.35 30.31 2.73E+09 2.67E+09 1.37E+09 1.10E+09 9.18E+08 28 1.46 31.77 3.56E+09 3.46E+09 1.75E+09 1.41E+09 1.18E+09 29 1.41 33.18 3.07E+09 2.99E+09 1.51E+09 1.22E+09 1.02E+09 30 1.59 34.78 3.00E+09 2.93E+09 1.50E+09 1.21E+09 1.01E+09 31 1.43 36.21 2.83E+09 2.78E+09 1.43E+09 1.16E+09 9.64E+08 32 1.86 38.07 3.95E+09 3.87E+09 1.97E+09 1.59E+09 1.32E+09 Proje ctions no bias 3.95E+09 3.87E+09 1.97E+09 1.59E+09 1.32E+09 Proje ctions w/bias 4.32E+09 4.23E+09 2.15E+09 1.73E+09 1.44E+09

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 39 of 62 February 8, 2023

Total Time (EFPY)

Fast Neutron (E > 0.1 MeV) Fluence (n/cm2)

Base Plate I-Beams Upper Plate &

Leveling Bolts Support Shoe Shim Plate 1

1.34 1.34 2.34E+17 2.31E+17 1.18E+17 9.48E+16 7.83E+16 2

0.85 2.19 4.30E+17 4.23E+17 2.17E+17 1.74E+17 1.43E+17 3

1.14 3.33 6.14E+17 6.05E+17 3.09E+17 2.48E+17 2.05E+17 4

0.83 4.16 8.21E+17 8.08E+17 4.14E+17 3.32E+17 2.74E+17 5

0.85 5.00 1.01E+18 9.90E+17 5.07E+17 4.07E+17 3.36E+17 6

0.88 5.88 1.19E+18 1.18E+18 6.03E+17 4.84E+17 3.99E+17 7

0.81 6.69 1.36E+18 1.34E+18 6.89E+17 5.52E+17 4.56E+17 8

0.84 7.53 1.54E+18 1.52E+18 7.80E+17 6.25E+17 5.16E+17 9

0.86 8.38 1.65E+18 1.63E+18 8.35E+17 6.70E+17 5.53E+17 10 0.87 9.26 1.74E+18 1.72E+18 8.82E+17 7.08E+17 5.85E+17 11 0.92 10.17 1.84E+18 1.81E+18 9.32E+17 7.48E+17 6.19E+17 12 0.98 11.15 1.94E+18 1.91E+18 9.84E+17 7.90E+17 6.54E+17 13 0.98 12.14 2.04E+18 2.01E+18 1.03E+18 8.29E+17 6.86E+17 14 1.00 13.13 2.14E+18 2.10E+18 1.08E+18 8.70E+17 7.20E+17 15 1.07 14.21 2.24E+18 2.20E+18 1.13E+18 9.13E+17 7.56E+17 16 1.08 15.28 2.35E+18 2.31E+18 1.19E+18 9.58E+17 7.94E+17 17 1.18 16.47 2.47E+18 2.43E+18 1.25E+18 1.01E+18 8.35E+17 18 1.35 17.81 2.60E+18 2.56E+18 1.32E+18 1.06E+18 8.79E+17 19 1.41 19.23 2.74E+18 2.69E+18 1.38E+18 1.11E+18 9.25E+17 20 1.42 20.65 2.86E+18 2.81E+18 1.45E+18 1.17E+18 9.68E+17 21 1.40 22.05 2.98E+18 2.93E+18 1.51E+18 1.22E+18 1.01E+18 22 1.44 23.49 3.14E+18 3.08E+18 1.58E+18 1.28E+18 1.06E+18 23 1.31 24.80 3.27E+18 3.21E+18 1.65E+18 1.33E+18 1.10E+18 24 1.45 26.24 3.41E+18 3.35E+18 1.72E+18 1.39E+18 1.15E+18 25 1.37 27.62 3.53E+18 3.47E+18 1.78E+18 1.43E+18 1.19E+18 26 1.34 28.95 3.63E+18 3.56E+18 1.83E+18 1.47E+18 1.22E+18 27 1.35 30.31 3.75E+18 3.68E+18 1.89E+18 1.52E+18 1.26E+18 28 1.46 31.77 3.91E+18 3.84E+18 1.97E+18 1.59E+18 1.32E+18 29 1.41 33.18 4.05E+18 3.97E+18 2.04E+18 1.64E+18 1.36E+18 30 1.59 34.78 4.20E+18 4.12E+18 2.11E+18 1.70E+18 1.41E+18 31 1.43 36.21 4.33E+18 4.24E+18 2.18E+18 1.75E+18 1.46E+18 32 1.86 38.07 4.56E+18 4.47E+18 2.29E+18 1.85E+18 1.54E+18

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 40 of 62 February 8, 2023

Maximum Fluence for E > 0.1 MeV Neutrons at the RPV Support Structure Projection with no bias on relative power of peripheral and re-entrant corner fuel assemblies Cycle Cycle Length (EFPY)

Total Time (EFPY)

Fast Neutron (E > 0.1 MeV) Fluence (n/cm2)

Base Plate I-Beams Upper Plate &

Leveling Bolts Support Shoe Shim Plate Projection 42 5.05E+18 4.95E+18 2.54E+18 2.04E+18 1.70E+18 48 5.80E+18 5.68E+18 2.91E+18 2.35E+18 1.95E+18 50 6.05E+18 5.93E+18 3.03E+18 2.45E+18 2.03E+18 54 6.55E+18 6.42E+18 3.28E+18 2.65E+18 2.20E+18 60 7.29E+18 7.15E+18 3.66E+18 2.95E+18 2.45E+18 66 8.04E+18 7.88E+18 4.03E+18 3.25E+18 2.70E+18 70 8.54E+18 8.37E+18 4.28E+18 3.45E+18 2.86E+18 72 8.79E+18 8.62E+18 4.40E+18 3.55E+18 2.95E+18 Projection with 10% positive bias on relative power of peripheral and re-entrant corner fuel assemblies Cycle Cycle Length (EFPY)

Total Time (EFPY)

Fast Neutron (E > 0.1 MeV) Fluence (n/cm2)

Base Plate I-Beams Upper Plate &

Leveling Bolts Support Shoe Shim Plate Projection 42 5.10E+18 5.00E+18 2.56E+18 2.06E+18 1.71E+18 48 5.91E+18 5.80E+18 2.97E+18 2.39E+18 1.99E+18 50 6.19E+18 6.06E+18 3.10E+18 2.50E+18 2.08E+18 54 6.73E+18 6.60E+18 3.37E+18 2.72E+18 2.26E+18 60 7.55E+18 7.40E+18 3.78E+18 3.05E+18 2.53E+18 66 8.37E+18 8.20E+18 4.19E+18 3.38E+18 2.80E+18 70 8.91E+18 8.73E+18 4.46E+18 3.59E+18 2.98E+18 72 9.18E+18 9.00E+18 4.60E+18 3.70E+18 3.08E+18

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 41 of 62 February 8, 2023

Total Time (EFPY)

Iron Atom Displacement Rate (dpa/s)

Base Plate I-Beams Upper Plate &

Leveling Bolts Support Shoe Shim Plate 1

1.34 1.34 1.77E-12 1.70E-12 8.34E-13 6.65E-13 5.47E-13 2

0.85 2.19 2.32E-12 2.23E-12 1.09E-12 8.67E-13 7.12E-13 3

1.14 3.33 1.63E-12 1.57E-12 7.68E-13 6.13E-13 5.06E-13 4

0.83 4.16 2.52E-12 2.43E-12 1.19E-12 9.46E-13 7.76E-13 5

0.85 5.00 2.20E-12 2.12E-12 1.04E-12 8.29E-13 6.81E-13 6

0.88 5.88 2.17E-12 2.09E-12 1.03E-12 8.22E-13 6.74E-13 7

0.81 6.69 2.09E-12 2.01E-12 9.92E-13 7.91E-13 6.51E-13 8

0.84 7.53 2.19E-12 2.10E-12 1.03E-12 8.19E-13 6.73E-13 9

0.86 8.38 1.29E-12 1.24E-12 6.15E-13 4.91E-13 4.04E-13 10 0.87 9.26 1.07E-12 1.03E-12 5.13E-13 4.15E-13 3.45E-13 11 0.92 10.17 1.09E-12 1.04E-12 5.16E-13 4.17E-13 3.48E-13 12 0.98 11.15 1.05E-12 1.00E-12 4.97E-13 4.02E-13 3.35E-13 13 0.98 12.14 9.75E-13 9.32E-13 4.64E-13 3.75E-13 3.13E-13 14 1.00 13.13 9.91E-13 9.48E-13 4.72E-13 3.82E-13 3.18E-13 15 1.07 14.21 9.72E-13 9.31E-13 4.64E-13 3.75E-13 3.13E-13 16 1.08 15.28 1.04E-12 9.91E-13 4.88E-13 3.95E-13 3.30E-13 17 1.18 16.47 1.05E-12 9.94E-13 4.87E-13 3.94E-13 3.28E-13 18 1.35 17.81 9.77E-13 9.30E-13 4.57E-13 3.68E-13 3.07E-13 19 1.41 19.23 9.62E-13 9.18E-13 4.52E-13 3.64E-13 3.03E-13 20 1.42 20.65 9.07E-13 8.66E-13 4.28E-13 3.44E-13 2.86E-13 21 1.40 22.05 8.70E-13 8.31E-13 4.11E-13 3.31E-13 2.75E-13 22 1.44 23.49 1.10E-12 1.04E-12 5.03E-13 4.04E-13 3.35E-13 23 1.31 24.80 1.03E-12 9.79E-13 4.74E-13 3.80E-13 3.15E-13 24 1.45 26.24 9.66E-13 9.21E-13 4.48E-13 3.59E-13 2.98E-13 25 1.37 27.62 9.09E-13 8.67E-13 4.22E-13 3.39E-13 2.80E-13 26 1.34 28.95 7.42E-13 7.10E-13 3.49E-13 2.80E-13 2.32E-13 27 1.35 30.31 8.73E-13 8.35E-13 4.09E-13 3.28E-13 2.72E-13 28 1.46 31.77 1.14E-12 1.08E-12 5.22E-13 4.19E-13 3.48E-13 29 1.41 33.18 9.79E-13 9.32E-13 4.52E-13 3.63E-13 3.01E-13 30 1.59 34.78 9.60E-13 9.14E-13 4.47E-13 3.59E-13 2.99E-13 31 1.43 36.21 9.05E-13 8.67E-13 4.28E-13 3.44E-13 2.85E-13 32 1.86 38.07 1.26E-12 1.21E-12 5.88E-13 4.70E-13 3.89E-13 Proje ctions no bias 1.26E-12 1.21E-12 5.88E-13 4.70E-13 3.89E-13 Proje ctions w/bias 1.38E-12 1.32E-12 6.42E-13 5.14E-13 4.25E-13

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 42 of 62 February 8, 2023

Total Time (EFPY)

Iron Atom Displacements (dpa)

Base Plate I-Beams Upper Plate &

Leveling Bolts Support Shoe Shim Plate 1

1.34 1.34 7.47E-05 7.18E-05 3.52E-05 2.81E-05 2.31E-05 2

0.85 2.19 1.37E-04 1.32E-04 6.45E-05 5.13E-05 4.22E-05 3

1.14 3.33 1.96E-04 1.88E-04 9.21E-05 7.34E-05 6.04E-05 4

0.83 4.16 2.61E-04 2.51E-04 1.23E-04 9.81E-05 8.07E-05 5

0.85 5.00 3.20E-04 3.08E-04 1.51E-04 1.20E-04 9.89E-05 6

0.88 5.88 3.80E-04 3.66E-04 1.80E-04 1.43E-04 1.18E-04 7

0.81 6.69 4.34E-04 4.17E-04 2.05E-04 1.63E-04 1.34E-04 8

0.84 7.53 4.91E-04 4.73E-04 2.32E-04 1.85E-04 1.52E-04 9

0.86 8.38 5.26E-04 5.06E-04 2.49E-04 1.98E-04 1.63E-04 10 0.87 9.26 5.56E-04 5.35E-04 2.63E-04 2.10E-04 1.72E-04 11 0.92 10.17 5.87E-04 5.65E-04 2.78E-04 2.22E-04 1.82E-04 12 0.98 11.15 6.20E-04 5.96E-04 2.93E-04 2.34E-04 1.93E-04 13 0.98 12.14 6.50E-04 6.25E-04 3.08E-04 2.46E-04 2.03E-04 14 1.00 13.13 6.81E-04 6.55E-04 3.22E-04 2.58E-04 2.13E-04 15 1.07 14.21 7.14E-04 6.86E-04 3.38E-04 2.70E-04 2.23E-04 16 1.08 15.28 7.50E-04 7.20E-04 3.55E-04 2.84E-04 2.34E-04 17 1.18 16.47 7.89E-04 7.57E-04 3.73E-04 2.99E-04 2.47E-04 18 1.35 17.81 8.30E-04 7.96E-04 3.92E-04 3.14E-04 2.60E-04 19 1.41 19.23 8.73E-04 8.37E-04 4.13E-04 3.30E-04 2.73E-04 20 1.42 20.65 9.14E-04 8.76E-04 4.32E-04 3.46E-04 2.86E-04 21 1.40 22.05 9.52E-04 9.13E-04 4.50E-04 3.61E-04 2.98E-04 22 1.44 23.49 1.00E-03 9.60E-04 4.73E-04 3.79E-04 3.13E-04 23 1.31 24.80 1.04E-03 1.00E-03 4.92E-04 3.95E-04 3.26E-04 24 1.45 26.24 1.09E-03 1.04E-03 5.13E-04 4.11E-04 3.40E-04 25 1.37 27.62 1.13E-03 1.08E-03 5.31E-04 4.26E-04 3.52E-04 26 1.34 28.95 1.16E-03 1.11E-03 5.46E-04 4.37E-04 3.62E-04 27 1.35 30.31 1.20E-03 1.15E-03 5.63E-04 4.51E-04 3.74E-04 28 1.46 31.77 1.25E-03 1.20E-03 5.87E-04 4.71E-04 3.90E-04 29 1.41 33.18 1.29E-03 1.24E-03 6.07E-04 4.87E-04 4.03E-04 30 1.59 34.78 1.34E-03 1.28E-03 6.30E-04 5.05E-04 4.18E-04 31 1.43 36.21 1.38E-03 1.32E-03 6.49E-04 5.21E-04 4.31E-04 32 1.86 38.07 1.46E-03 1.39E-03 6.84E-04 5.48E-04 4.54E-04

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 43 of 62 February 8, 2023

Total Iron Atom Displacements at the RPV Support Structure Projection with no bias on relative power of peripheral and re-entrant corner fuel assemblies Cycle Cycle Length (EFPY)

Total Time (EFPY)

Iron Atom Displacements (dpa)

Base Plate I-Beams Upper Plate &

Leveling Bolts Support Shoe Shim Plate Projection 42 1.61E-03 1.54E-03 7.57E-04 6.07E-04 5.02E-04 48 1.85E-03 1.77E-03 8.68E-04 6.96E-04 5.76E-04 50 1.93E-03 1.85E-03 9.05E-04 7.25E-04 6.00E-04 54 2.09E-03 2.00E-03 9.79E-04 7.85E-04 6.49E-04 60 2.33E-03 2.23E-03 1.09E-03 8.74E-04 7.23E-04 66 2.57E-03 2.46E-03 1.20E-03 9.63E-04 7.97E-04 70 2.73E-03 2.61E-03 1.28E-03 1.02E-03 8.46E-04 72 2.81E-03 2.68E-03 1.31E-03 1.05E-03 8.70E-04 Projection with 10% positive bias on relative power of peripheral and re-entrant corner fuel assemblies Cycle Cycle Length (EFPY)

Total Time (EFPY)

Iron Atom Displacements (dpa)

Base Plate I-Beams Upper Plate &

Leveling Bolts Support Shoe Shim Plate Projection 42 1.63E-03 1.56E-03 7.63E-04 6.12E-04 5.06E-04 48 1.89E-03 1.81E-03 8.85E-04 7.09E-04 5.87E-04 50 1.97E-03 1.89E-03 9.25E-04 7.42E-04 6.14E-04 54 2.15E-03 2.06E-03 1.01E-03 8.06E-04 6.67E-04 60 2.41E-03 2.31E-03 1.13E-03 9.04E-04 7.48E-04 66 2.67E-03 2.55E-03 1.25E-03 1.00E-03 8.28E-04 70 2.84E-03 2.72E-03 1.33E-03 1.07E-03 8.82E-04 72 2.93E-03 2.80E-03 1.37E-03 1.10E-03 9.08E-04

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 44 of 62 February 8, 2023

Cumulative Operating Time (EFPY)

Fast Neutron (E > 1.0 MeV) Fluence Rate (n/cm2-s)

Mark B5 Mark B6 1

1.34 1.34 8.20E+07 4.30E+08 2

0.85 2.19 8.42E+07 4.45E+08 3

1.14 3.33 7.00E+07 3.70E+08 4

0.83 4.16 9.24E+07 4.80E+08 5

0.85 5.00 8.61E+07 4.50E+08 6

0.88 5.88 8.17E+07 4.28E+08 7

0.81 6.69 8.43E+07 4.46E+08 8

0.84 7.53 8.44E+07 4.43E+08 9

0.86 8.38 4.86E+07 2.66E+08 10 0.87 9.26 5.16E+07 3.00E+08 11 0.92 10.17 4.92E+07 2.93E+08 12 0.98 11.15 4.75E+07 2.87E+08 13 0.98 12.14 4.25E+07 2.60E+08 14 1.00 13.13 4.28E+07 2.67E+08 15 1.07 14.21 4.12E+07 2.58E+08 16 1.08 15.28 5.80E+07 3.14E+08 17 1.18 16.47 5.31E+07 2.88E+08 18 1.35 17.81 4.80E+07 2.63E+08 19 1.41 19.23 4.51E+07 2.48E+08 20 1.42 20.65 4.04E+07 2.25E+08 21 1.40 22.05 3.91E+07 2.20E+08 22 1.44 23.49 5.15E+07 2.72E+08 23 1.31 24.80 4.62E+07 2.47E+08 24 1.45 26.24 4.06E+07 2.22E+08 25 1.37 27.62 3.91E+07 2.13E+08 26 1.34 28.95 2.98E+07 1.70E+08 27 1.35 30.31 3.53E+07 1.96E+08 28 1.46 31.77 5.23E+07 2.80E+08 29 1.41 33.18 4.35E+07 2.35E+08 30 1.59 34.78 4.41E+07 2.41E+08 31 1.43 36.21 3.73E+07 2.13E+08 32 1.86 38.07 5.08E+07 2.68E+08 Projections no bias 5.08E+07 2.68E+08 Projections with bias 5.55E+07 2.93E+08

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 45 of 62 February 8, 2023

Cumulative Operating Time (EFPY)

Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

Mark B5 Mark B6 1

1.34 1.34 3.46E+15 1.81E+16 2

0.85 2.19 5.72E+15 3.01E+16 3

1.14 3.33 8.24E+15 4.34E+16 4

0.83 4.16 1.06E+16 5.59E+16 5

0.85 5.00 1.30E+16 6.79E+16 6

0.88 5.88 1.52E+16 7.98E+16 7

0.81 6.69 1.74E+16 9.12E+16 8

0.84 7.53 1.96E+16 1.03E+17 9

0.86 8.38 2.09E+16 1.10E+17 10 0.87 9.26 2.23E+16 1.18E+17 11 0.92 10.17 2.37E+16 1.26E+17 12 0.98 11.15 2.51E+16 1.35E+17 13 0.98 12.14 2.64E+16 1.43E+17 14 1.00 13.13 2.78E+16 1.52E+17 15 1.07 14.21 2.91E+16 1.60E+17 16 1.08 15.28 3.11E+16 1.71E+17 17 1.18 16.47 3.31E+16 1.82E+17 18 1.35 17.81 3.51E+16 1.93E+17 19 1.41 19.23 3.71E+16 2.04E+17 20 1.42 20.65 3.89E+16 2.14E+17 21 1.40 22.05 4.06E+16 2.23E+17 22 1.44 23.49 4.30E+16 2.36E+17 23 1.31 24.80 4.49E+16 2.46E+17 24 1.45 26.24 4.67E+16 2.56E+17 25 1.37 27.62 4.84E+16 2.65E+17 26 1.34 28.95 4.96E+16 2.72E+17 27 1.35 30.31 5.11E+16 2.80E+17 28 1.46 31.77 5.35E+16 2.93E+17 29 1.41 33.18 5.55E+16 3.04E+17 30 1.59 34.78 5.77E+16 3.16E+17 31 1.43 36.21 5.94E+16 3.25E+17 32 1.86 38.07 6.23E+16 3.41E+17

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 46 of 62 February 8, 2023

Maximum Fast Neutron Fluence for the Embedded RPV Support Structure Anchor Bolts Cycle Cycle Length (EFPY)

Cumulative Operating Time (EFPY)

Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

Mark B5 Mark B6 Projection with no bias on relative power of peripheral and re-entrant corner fuel assemblies Projection 42 6.86E+16 3.74E+17 48 7.83E+16 4.25E+17 50 8.15E+16 4.42E+17 54 8.79E+16 4.76E+17 60 9.75E+16 5.27E+17 66 1.07E+17 5.77E+17 70 1.14E+17 6.11E+17 72 1.17E+17 6.28E+17 Projection with 10% positive bias on relative power of peripheral and re-entrant corner fuel assemblies Cycle Cycle Length (EFPY)

Cumulative Operating Time (EFPY)

Fast Neutron (E > 1.0 MeV) Fluence (n/cm2)

Mark B5 Mark B6 Projection 42 6.92E+16 3.77E+17 48 7.97E+16 4.33E+17 50 8.32E+16 4.51E+17 54 9.02E+16 4.88E+17 60 1.01E+17 5.44E+17 66 1.11E+17 5.99E+17 70 1.18E+17 6.36E+17 72 1.22E+17 6.55E+17

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 47 of 62 February 8, 2023

Cumulative Operating Time (EFPY)

Fast Neutron (E > 0.1 MeV) Fluence Rate (n/cm2-s)

Mark B5 Mark B6 1

1.34 1.34 1.25E+09 5.03E+09 2

0.85 2.19 1.65E+09 5.23E+09 3

1.14 3.33 1.14E+09 4.33E+09 4

0.83 4.16 1.81E+09 5.67E+09 5

0.85 5.00 1.56E+09 5.29E+09 6

0.88 5.88 1.55E+09 5.03E+09 7

0.81 6.69 1.47E+09 5.23E+09 8

0.84 7.53 1.55E+09 5.19E+09 9

0.86 8.38 9.03E+08 3.00E+09 10 0.87 9.26 7.04E+08 3.42E+09 11 0.92 10.17 7.12E+08 3.32E+09 12 0.98 11.15 6.82E+08 3.24E+09 13 0.98 12.14 6.33E+08 2.94E+09 14 1.00 13.13 6.43E+08 3.00E+09 15 1.07 14.21 6.30E+08 2.91E+09 16 1.08 15.28 6.77E+08 3.59E+09 17 1.18 16.47 6.87E+08 3.29E+09 18 1.35 17.81 6.46E+08 2.98E+09 19 1.41 19.23 6.41E+08 2.80E+09 20 1.42 20.65 6.05E+08 2.53E+09 21 1.40 22.05 5.79E+08 2.47E+09 22 1.44 23.49 7.39E+08 3.13E+09 23 1.31 24.80 6.94E+08 2.82E+09 24 1.45 26.24 6.54E+08 2.51E+09 25 1.37 27.62 6.16E+08 2.41E+09 26 1.34 28.95 5.01E+08 1.91E+09 27 1.35 30.31 5.94E+08 2.21E+09 28 1.46 31.77 7.61E+08 3.21E+09 29 1.41 33.18 6.59E+08 2.68E+09 30 1.59 34.78 6.40E+08 2.73E+09 31 1.43 36.21 6.11E+08 2.40E+09 32 1.86 38.07 8.74E+08 3.10E+09 Projections no bias 8.74E+08 3.10E+09 Projections with bias 9.54E+08 3.39E+09

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 48 of 62 February 8, 2023

Cumulative Operating Time (EFPY)

Fast Neutron (E > 0.1 MeV) Fluence (n/cm2)

Mark B5 Mark B6 1

1.34 1.34 5.25E+16 2.12E+17 2

0.85 2.19 9.68E+16 3.52E+17 3

1.14 3.33 1.38E+17 5.08E+17 4

0.83 4.16 1.85E+17 6.55E+17 5

0.85 5.00 2.27E+17 7.97E+17 6

0.88 5.88 2.70E+17 9.36E+17 7

0.81 6.69 3.07E+17 1.07E+18 8

0.84 7.53 3.48E+17 1.21E+18 9

0.86 8.38 3.73E+17 1.29E+18 10 0.87 9.26 3.92E+17 1.38E+18 11 0.92 10.17 4.12E+17 1.47E+18 12 0.98 11.15 4.34E+17 1.57E+18 13 0.98 12.14 4.53E+17 1.67E+18 14 1.00 13.13 4.73E+17 1.76E+18 15 1.07 14.21 4.95E+17 1.86E+18 16 1.08 15.28 5.18E+17 1.98E+18 17 1.18 16.47 5.43E+17 2.10E+18 18 1.35 17.81 5.71E+17 2.23E+18 19 1.41 19.23 5.99E+17 2.35E+18 20 1.42 20.65 6.27E+17 2.47E+18 21 1.40 22.05 6.52E+17 2.57E+18 22 1.44 23.49 6.86E+17 2.72E+18 23 1.31 24.80 7.15E+17 2.83E+18 24 1.45 26.24 7.44E+17 2.95E+18 25 1.37 27.62 7.71E+17 3.05E+18 26 1.34 28.95 7.92E+17 3.13E+18 27 1.35 30.31 8.18E+17 3.22E+18 28 1.46 31.77 8.53E+17 3.37E+18 29 1.41 33.18 8.82E+17 3.49E+18 30 1.59 34.78 9.14E+17 3.63E+18 31 1.43 36.21 9.42E+17 3.74E+18 32 1.86 38.07 9.93E+17 3.92E+18

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 49 of 62 February 8, 2023

Maximum Fluence for E > 0.1 MeV Neutrons at the Embedded RPV Support Structure Anchor Bolts Cycle Cycle Length (EFPY)

Cumulative Operating Time (EFPY)

Fast Neutron (E > 0.1 MeV) Fluence (n/cm2)

Mark B5 Mark B6 Projection with no bias on relative power of peripheral and re-entrant corner fuel assemblies Projection 42 1.10E+18 4.30E+18 48 1.27E+18 4.89E+18 50 1.32E+18 5.08E+18 54 1.43E+18 5.47E+18 60 1.60E+18 6.06E+18 66 1.76E+18 6.65E+18 70 1.87E+18 7.04E+18 72 1.93E+18 7.23E+18 Projection with 10% positive bias on relative power of peripheral and re-entrant corner fuel assemblies Cycle Cycle Length (EFPY)

Cumulative Operating Time (EFPY)

Fast Neutron (E > 0.1 MeV) Fluence (n/cm2)

Mark B5 Mark B6 Projection 42 1.11E+18 4.34E+18 48 1.29E+18 4.98E+18 50 1.35E+18 5.19E+18 54 1.47E+18 5.62E+18 60 1.65E+18 6.26E+18 66 1.83E+18 6.90E+18 70 1.95E+18 7.33E+18 72 2.01E+18 7.54E+18

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 50 of 62 February 8, 2023

Cumulative Operating Time (EFPY)

Iron Atom Displacement Rate (dpa/s)

Mark B5 Mark B6 1

1.34 1.34 3.93E-13 2.00E-12 2

0.85 2.19 4.71E-13 2.08E-12 3

1.14 3.33 3.36E-13 1.72E-12 4

0.83 4.16 5.16E-13 2.25E-12 5

0.85 5.00 4.48E-13 2.10E-12 6

0.88 5.88 4.44E-13 2.00E-12 7

0.81 6.69 4.21E-13 2.08E-12 8

0.84 7.53 4.43E-13 2.06E-12 9

0.86 8.38 2.59E-13 1.20E-12 10 0.87 9.26 2.37E-13 1.36E-12 11 0.92 10.17 2.26E-13 1.33E-12 12 0.98 11.15 2.17E-13 1.30E-12 13 0.98 12.14 1.94E-13 1.18E-12 14 1.00 13.13 1.96E-13 1.20E-12 15 1.07 14.21 1.88E-13 1.16E-12 16 1.08 15.28 2.67E-13 1.43E-12 17 1.18 16.47 2.44E-13 1.31E-12 18 1.35 17.81 2.19E-13 1.19E-12 19 1.41 19.23 2.05E-13 1.12E-12 20 1.42 20.65 1.84E-13 1.01E-12 21 1.40 22.05 1.77E-13 9.87E-13 22 1.44 23.49 2.38E-13 1.24E-12 23 1.31 24.80 2.12E-13 1.12E-12 24 1.45 26.24 1.88E-13 1.00E-12 25 1.37 27.62 1.78E-13 9.63E-13 26 1.34 28.95 1.44E-13 7.62E-13 27 1.35 30.31 1.70E-13 8.81E-13 28 1.46 31.77 2.42E-13 1.28E-12 29 1.41 33.18 2.00E-13 1.07E-12 30 1.59 34.78 2.01E-13 1.09E-12 31 1.43 36.21 1.75E-13 9.57E-13 32 1.86 38.07 2.50E-13 1.23E-12 Projections no bias 2.50E-13 1.23E-12 Projections with bias 2.74E-13 1.35E-12

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 51 of 62 February 8, 2023

Cumulative Operating Time (EFPY)

Iron Atom Displacements (dpa)

Mark B5 Mark B6 1

1.34 1.34 1.66E-05 8.42E-05 2

0.85 2.19 2.77E-05 1.40E-04 3

1.14 3.33 3.96E-05 2.02E-04 4

0.83 4.16 5.29E-05 2.60E-04 5

0.85 5.00 6.49E-05 3.16E-04 6

0.88 5.88 7.72E-05 3.72E-04 7

0.81 6.69 8.80E-05 4.25E-04 8

0.84 7.53 9.97E-05 4.79E-04 9

0.86 8.38 1.07E-04 5.11E-04 10 0.87 9.26 1.12E-04 5.48E-04 11 0.92 10.17 1.18E-04 5.86E-04 12 0.98 11.15 1.24E-04 6.26E-04 13 0.98 12.14 1.30E-04 6.62E-04 14 1.00 13.13 1.36E-04 7.00E-04 15 1.07 14.21 1.42E-04 7.39E-04 16 1.08 15.28 1.48E-04 7.88E-04 17 1.18 16.47 1.56E-04 8.36E-04 18 1.35 17.81 1.65E-04 8.87E-04 19 1.41 19.23 1.75E-04 9.36E-04 20 1.42 20.65 1.83E-04 9.81E-04 21 1.40 22.05 1.91E-04 1.03E-03 22 1.44 23.49 2.01E-04 1.08E-03 23 1.31 24.80 2.10E-04 1.13E-03 24 1.45 26.24 2.18E-04 1.17E-03 25 1.37 27.62 2.26E-04 1.21E-03 26 1.34 28.95 2.32E-04 1.25E-03 27 1.35 30.31 2.39E-04 1.28E-03 28 1.46 31.77 2.50E-04 1.34E-03 29 1.41 33.18 2.59E-04 1.39E-03 30 1.59 34.78 2.69E-04 1.44E-03 31 1.43 36.21 2.76E-04 1.49E-03 32 1.86 38.07 2.91E-04 1.56E-03

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 52 of 62 February 8, 2023

Iron Atom Displacements at the Embedded RPV Support Structure Anchor Bolts Cycle Cycle Length (EFPY)

Cumulative Operating Time (EFPY)

Displacements (dpa)

Mark B5 Mark B6 Projection with no bias on relative power of peripheral and re-entrant corner fuel assemblies Projection 42 3.20E-04 1.71E-03 48 3.66E-04 1.95E-03 50 3.81E-04 2.02E-03 54 4.12E-04 2.18E-03 60 4.58E-04 2.41E-03 66 5.06E-04 2.65E-03 70 5.37E-04 2.80E-03 72 5.53E-04 2.88E-03 Projection with 10% positive bias on relative power of peripheral and re-entrant corner fuel assemblies Cycle Cycle Length (EFPY)

Cumulative Operating Time (EFPY)

Displacements (dpa)

Mark B5 Mark B6 Projection 42 3.23E-04 1.73E-03 48 3.73E-04 1.98E-03 50 3.90E-04 2.07E-03 54 4.23E-04 2.24E-03 60 4.74E-04 2.49E-03 66 5.26E-04 2.75E-03 70 5.60E-04 2.92E-03 72 5.78E-04 3.00E-03

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 53 of 62 February 8, 2023

© 2023 Westinghouse Electric Company LLC All Rights Reserved 5.4 Bioshield Concrete Neutron and gamma ray exposures of the bioshield concrete are presented in Tables 5-23 through 5-25. Table 5-23 presents the fluence due to neutrons with energies greater than 1.0 MeV at various azimuths of the bioshield concrete. Similarly, Table 5-24 presents the fluence due to neutrons with energies greater than 0.1 MeV. As observed in Table 5-24, the majority of the concrete bioshield is anticipated to exceed the neutron fluence limit of 1x1019 n/cm2 cited in subsection 3.5.2.2.2.6 of NUREG-2192, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants (Reference 6), beyond which concrete material properties might begin to degrade.

Table 5-25 presents the gamma dose to the bioshield concrete at various azimuths in terms of gray. As evident from the data in Table 5-25, the gamma dose to the plant bioshield is projected to exceed the dose threshold for consideration of photon radiation exposure effects to the concrete (1x108 Gy (1x1010 rad)), with the exceedance beginning at approximately 67 EFPY.

Several informative figures were produced to show the extent to which the bioshield concrete meets or exceeds the threshold neutron fluence value in NUREG-2192. The concrete bioshield neutron exposure for neutrons with E >

0.1 MeV is shown in the figures consistent with the energy cutoff specified in NUREG-2192. Presented in Figure 5-1 is a three-dimensional view of the bioshield concrete fast (E > 0.1 MeV) neutron fluence binned by order of magnitude. Figure 5-2 shows a 2-dimensional slice of the Figure 1 data at 9 cm above the core midplane (the location of maximum fluence). At 70 EFPY, the volume of concrete with fast (E > 0.1 MeV) neutron fluence of 1x1019 neutrons/cm2 or higher was 347,000 cm3 for the quadrant.

Figures 5-3 and 5-4 show data similar to that in Figures 5-1 and 5-2 with 10% positive bias applied to the peripheral and re-entrant fuel assembly relative powers. The fluence is also binned by order of magnitude in these figures. The location of maximum fluence occurred at 34 cm above the core midplane. With 10% positive bias applied to the peripheral and re-entrant fuel assembly relative powers, the volume of concrete with fast (E > 0.1 MeV) neutron fluence of 1x1019 neutrons/cm2 or higher was 377,000 cm3 for the quadrant.

Considering the analytical uncertainty in the calculated fluence at the surface of the bioshield wall as discussed in LTR-REA-21-81-NP, Recommended Responses to United States Nuclear Regulatory Commission (USNRC)

Requests for Additional Information (RAIs) 3.5.2.2.2.6-1 and 3.5.2.2.2.7-1 Related to the Point Beach Subsequent License Renewal Application (SLRA) (Reference 7), the volume of concrete that experiences fast (E > 0.1 MeV) neutron fluence of 1x1019 neutrons/cm2 or higher at 70 EFPY could be as much as 547,000 cm3, or 2.2 m3 for the whole plant. Figure 5-5 shows 2-dimentional slices of the bioshield at key azimuths with fluence binned by order of magnitude and shows the depth to which the concrete above the NUREG-2192 threshold extends to be approximately 10 cm at its deepest point.

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 54 of 62 February 8, 2023

Projected Fast Neutron Fluence at the Concrete Bioshield Projection with no bias on relative power of peripheral and re-entrant corner fuel assemblies Position Fast (E > 1.0 MeV) Neutron Fluence (n/cm2) 38.07[1]

48 EFPY 50 EFPY 54 EFPY 60 EFPY 66 EFPY 70 EFPY 72 EFPY Maximum[2] 1.23E+18 1.54E+18 1.60E+18 1.73E+18 1.92E+18 2.11E+18 2.23E+18 2.30E+18 0° 1.18E+18 1.48E+18 1.55E+18 1.67E+18 1.85E+18 2.04E+18 2.16E+18 2.22E+18 15° 8.56E+17 1.06E+18 1.11E+18 1.19E+18 1.31E+18 1.44E+18 1.52E+18 1.57E+18 30° 5.09E+17 6.26E+17 6.50E+17 6.97E+17 7.68E+17 8.39E+17 8.86E+17 9.10E+17 45° 3.40E+17 4.24E+17 4.41E+17 4.74E+17 5.25E+17 5.76E+17 6.10E+17 6.26E+17 50° 3.81E+17 4.74E+17 4.93E+17 5.30E+17 5.87E+17 6.43E+17 6.80E+17 6.99E+17 60° 5.21E+17 6.41E+17 6.66E+17 7.14E+17 7.87E+17 8.60E+17 9.09E+17 9.33E+17 65° 6.08E+17 7.47E+17 7.75E+17 8.32E+17 9.16E+17 1.00E+18 1.06E+18 1.09E+18 70° 7.16E+17 8.83E+17 9.17E+17 9.84E+17 1.09E+18 1.19E+18 1.25E+18 1.29E+18 80° 1.09E+18 1.36E+18 1.41E+18 1.52E+18 1.69E+18 1.85E+18 1.96E+18 2.02E+18 85° 1.23E+18 1.54E+18 1.60E+18 1.73E+18 1.92E+18 2.11E+18 2.23E+18 2.30E+18 90° 1.20E+18 1.51E+18 1.57E+18 1.70E+18 1.89E+18 2.07E+18 2.20E+18 2.26E+18 Projection with 10% positive bias on relative power of peripheral and re-entrant corner fuel assemblies Position Fast (E > 1.0 MeV) Neutron Fluence (n/cm2) 38.07[1]

48 EFPY 50 EFPY 54 EFPY 60 EFPY 66 EFPY 70 EFPY 72 EFPY Maximum[2] 1.23E+18 1.57E+18 1.64E+18 1.78E+18 1.98E+18 2.19E+18 2.33E+18 2.40E+18 0° 1.18E+18 1.51E+18 1.58E+18 1.71E+18 1.92E+18 2.12E+18 2.25E+18 2.32E+18 15° 8.56E+17 1.08E+18 1.13E+18 1.22E+18 1.36E+18 1.49E+18 1.59E+18 1.63E+18 30° 5.09E+17 6.37E+17 6.63E+17 7.15E+17 7.92E+17 8.70E+17 9.22E+17 9.47E+17 45° 3.40E+17 4.31E+17 4.50E+17 4.87E+17 5.42E+17 5.98E+17 6.35E+17 6.53E+17 50° 3.81E+17 4.83E+17 5.03E+17 5.44E+17 6.06E+17 6.67E+17 7.08E+17 7.29E+17 60° 5.21E+17 6.53E+17 6.79E+17 7.32E+17 8.12E+17 8.92E+17 9.45E+17 9.71E+17 65° 6.08E+17 7.60E+17 7.91E+17 8.53E+17 9.45E+17 1.04E+18 1.10E+18 1.13E+18 70° 7.16E+17 8.99E+17 9.36E+17 1.01E+18 1.12E+18 1.23E+18 1.30E+18 1.34E+18 80° 1.09E+18 1.38E+18 1.44E+18 1.56E+18 1.74E+18 1.92E+18 2.04E+18 2.10E+18 85° 1.23E+18 1.57E+18 1.64E+18 1.78E+18 1.98E+18 2.19E+18 2.33E+18 2.40E+18 90° 1.20E+18 1.54E+18 1.61E+18 1.74E+18 1.95E+18 2.15E+18 2.29E+18 2.36E+18 Note: 1. The total EFPY at the end of Cycle 32.

2. The maximum exposure occurred at 85°.

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 55 of 62 February 8, 2023

Projected Fast Fluence for Energies Greater Than 0.1 MeV Neutrons at the Concrete Bioshield Projection with no bias on relative power of peripheral and re-entrant corner fuel assemblies Position Fast (E > 0.1 MeV) Neutron Fluence (n/cm2) 38.07[1]

48 EFPY 50 EFPY 54 EFPY 60 EFPY 66 EFPY 70 EFPY 72 EFPY Maximum[2] 1.85E+19 2.32E+19 2.42E+19 2.61E+19 2.90E+19 3.18E+19 3.37E+19 3.47E+19 0° 1.64E+19 2.06E+19 2.15E+19 2.32E+19 2.58E+19 2.83E+19 3.00E+19 3.09E+19 15° 1.39E+19 1.73E+19 1.80E+19 1.93E+19 2.14E+19 2.35E+19 2.48E+19 2.55E+19 30° 8.09E+18 9.97E+18 1.04E+19 1.11E+19 1.23E+19 1.34E+19 1.42E+19 1.45E+19 45° 4.89E+18 6.09E+18 6.33E+18 6.82E+18 7.54E+18 8.26E+18 8.75E+18 8.99E+18 50° 5.74E+18 7.14E+18 7.42E+18 7.98E+18 8.82E+18 9.67E+18 1.02E+19 1.05E+19 60° 7.87E+18 9.71E+18 1.01E+19 1.08E+19 1.19E+19 1.31E+19 1.38E+19 1.42E+19 65° 9.25E+18 1.14E+19 1.19E+19 1.27E+19 1.40E+19 1.53E+19 1.62E+19 1.67E+19 70° 1.10E+19 1.36E+19 1.42E+19 1.52E+19 1.68E+19 1.84E+19 1.95E+19 2.00E+19 80° 1.61E+19 2.01E+19 2.09E+19 2.26E+19 2.50E+19 2.75E+19 2.91E+19 2.99E+19 85° 1.75E+19 2.20E+19 2.29E+19 2.47E+19 2.74E+19 3.01E+19 3.19E+19 3.28E+19 90° 1.57E+19 1.98E+19 2.06E+19 2.23E+19 2.47E+19 2.72E+19 2.88E+19 2.96E+19 Projection with 10% positive bias on relative power of peripheral and re-entrant corner fuel assemblies Position Fast (E > 0.1 MeV) Neutron Fluence (n/cm2) 38.07[1]

48 EFPY 50 EFPY 54 EFPY 60 EFPY 66 EFPY 70 EFPY 72 EFPY Maximum[2] 1.85E+19 2.37E+19 2.47E+19 2.68E+19 3.00E+19 3.31E+19 3.52E+19 3.62E+19 0° 1.64E+19 2.10E+19 2.20E+19 2.38E+19 2.66E+19 2.94E+19 3.13E+19 3.23E+19 15° 1.39E+19 1.76E+19 1.84E+19 1.99E+19 2.21E+19 2.44E+19 2.59E+19 2.66E+19 30° 8.09E+18 1.02E+19 1.06E+19 1.14E+19 1.26E+19 1.39E+19 1.47E+19 1.51E+19 45° 4.89E+18 6.21E+18 6.47E+18 7.00E+18 7.79E+18 8.58E+18 9.11E+18 9.37E+18 50° 5.74E+18 7.27E+18 7.58E+18 8.19E+18 9.12E+18 1.00E+19 1.07E+19 1.10E+19 60° 7.87E+18 9.89E+18 1.03E+19 1.11E+19 1.23E+19 1.35E+19 1.44E+19 1.48E+19 65° 9.25E+18 1.16E+19 1.21E+19 1.31E+19 1.45E+19 1.59E+19 1.69E+19 1.73E+19 70° 1.10E+19 1.39E+19 1.45E+19 1.56E+19 1.74E+19 1.91E+19 2.02E+19 2.08E+19 80° 1.61E+19 2.05E+19 2.14E+19 2.32E+19 2.59E+19 2.85E+19 3.03E+19 3.12E+19 85° 1.75E+19 2.24E+19 2.34E+19 2.53E+19 2.83E+19 3.13E+19 3.32E+19 3.42E+19 90° 1.57E+19 2.02E+19 2.11E+19 2.29E+19 2.56E+19 2.83E+19 3.01E+19 3.09E+19 Note: 1. The total EFPY at the end of Cycle 32.

2. The maximum exposure occurred at 6°.

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 56 of 62 February 8, 2023

Projected Photon Exposures at the Concrete Bioshield Projection with no bias on relative power of peripheral and re-entrant corner fuel assemblies Position Gamma Ray Dose (Gy) 38.07[1]

48 EFPY 50 EFPY 54 EFPY 60 EFPY 66 EFPY 70 EFPY 72 EFPY Maximum[2]

5.45E+07 6.87E+07 7.16E+07 7.74E+07 8.60E+07 9.46E+07 1.00E+08 1.03E+08 0° 5.21E+07 6.59E+07 6.87E+07 7.42E+07 8.25E+07 9.08E+07 9.63E+07 9.91E+07 15° 4.59E+07 5.74E+07 5.97E+07 6.43E+07 7.12E+07 7.81E+07 8.27E+07 8.50E+07 30° 3.13E+07 3.89E+07 4.04E+07 4.34E+07 4.80E+07 5.25E+07 5.55E+07 5.71E+07 45° 2.26E+07 2.82E+07 2.93E+07 3.16E+07 3.50E+07 3.83E+07 4.06E+07 4.17E+07 50° 2.43E+07 3.02E+07 3.14E+07 3.38E+07 3.74E+07 4.10E+07 4.34E+07 4.46E+07 60° 3.06E+07 3.80E+07 3.95E+07 4.24E+07 4.69E+07 5.13E+07 5.43E+07 5.58E+07 65° 3.48E+07 4.32E+07 4.49E+07 4.83E+07 5.34E+07 5.84E+07 6.18E+07 6.35E+07 70° 3.95E+07 4.92E+07 5.11E+07 5.50E+07 6.08E+07 6.66E+07 7.05E+07 7.25E+07 80° 4.88E+07 6.13E+07 6.38E+07 6.88E+07 7.63E+07 8.38E+07 8.88E+07 9.13E+07 85° 5.05E+07 6.36E+07 6.62E+07 7.15E+07 7.94E+07 8.74E+07 9.26E+07 9.53E+07 90° 5.04E+07 6.37E+07 6.64E+07 7.17E+07 7.97E+07 8.78E+07 9.31E+07 9.58E+07 Projection with 10% positive bias on relative power of peripheral and re-entrant corner fuel assemblies Position Gamma Ray Dose (Gy) 38.07[1]

48 EFPY 50 EFPY 54 EFPY 60 EFPY 66 EFPY 70 EFPY 72 EFPY Maximum[2]

5.45E+07 7.01E+07 7.32E+07 7.95E+07 8.89E+07 9.84E+07 1.05E+08 1.08E+08 0° 5.21E+07 6.72E+07 7.02E+07 7.63E+07 8.54E+07 9.44E+07 1.01E+08 1.04E+08 15° 4.59E+07 5.84E+07 6.10E+07 6.60E+07 7.36E+07 8.11E+07 8.62E+07 8.87E+07 30° 3.13E+07 3.96E+07 4.12E+07 4.46E+07 4.95E+07 5.45E+07 5.78E+07 5.95E+07 45° 2.26E+07 2.87E+07 3.00E+07 3.24E+07 3.61E+07 3.98E+07 4.23E+07 4.35E+07 50° 2.43E+07 3.08E+07 3.21E+07 3.47E+07 3.86E+07 4.26E+07 4.52E+07 4.65E+07 60° 3.06E+07 3.87E+07 4.03E+07 4.35E+07 4.84E+07 5.33E+07 5.65E+07 5.81E+07 65° 3.48E+07 4.40E+07 4.58E+07 4.95E+07 5.51E+07 6.06E+07 6.43E+07 6.62E+07 70° 3.95E+07 5.01E+07 5.22E+07 5.64E+07 6.28E+07 6.92E+07 7.35E+07 7.56E+07 80° 4.88E+07 6.24E+07 6.52E+07 7.06E+07 7.88E+07 8.70E+07 9.25E+07 9.52E+07 85° 5.05E+07 6.48E+07 6.77E+07 7.35E+07 8.22E+07 9.08E+07 9.66E+07 9.95E+07 90° 5.04E+07 6.49E+07 6.79E+07 7.37E+07 8.25E+07 9.13E+07 9.71E+07 1.00E+08 Note: 1. The total EFPY at the end of Cycle 32.

2. The maximum exposure occurred at 4°.

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 57 of 62 February 8, 2023

3-Dimensional View of Fast (E > 0.1 MeV) Neutron Fluence (n/cm2) to the Bioshield Concrete at 70 EFPY (No bias applied to peripheral or re-entrant corner relative powers)

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 58 of 62 February 8, 2023

2-Dimensional Slice of Fast (E > 0.1 MeV) Neutron Fluence (n/cm2) to the Bioshield Concrete Clipped 9 cm Above the Core Midplane at 70 EFPY (No bias applied to peripheral or re-entrant corner relative powers)

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 59 of 62 February 8, 2023

3-Dimensional View of Fast (E > 0.1 MeV) Neutron Fluence (n/cm2) to the Bioshield Concrete at 70 EFPY (10% positive bias applied to peripheral and re-entrant corner relative powers)

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 60 of 62 February 8, 2023

2-Dimensional Slice of Fast (E > 0.1 MeV) Neutron Fluence (n/cm2) to the Bioshield Concrete at 34 cm Above the Core Midplane at 70 EFPY (10% positive bias applied to peripheral or re-entrant corner relative powers)

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 61 of 62 February 8, 2023

2-Dimensional Slice of Fast (E > 0.1 MeV) Neutron Fluence (n/cm2) to the Bioshield Concrete for Representative Azimuthal Positions at 70 EFPY (10% positive bias applied to peripheral and re-entrant corner relative powers) 85° (Max. >1E19) 80° (CL of RPV Support) 50° (Instrument well edge) 52° (Min. >1E19)

- - This record was final approved on 2/10/2023, 2:06:12 PM. (This statement was added by the PRIME system upon its validation)

Westinghouse Non-Proprietary Class 3 to CPL-REAC-TM-AA-000001, Rev. 1 Attachment Page 62 of 62 February 8, 2023

1. United States Nuclear Regulatory Commission, Regulatory Guide 1.190, Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence, March 2001.

2. Westinghouse Report WCAP-18124-NP-A, Rev. 0, Fluence Determination with RAPTOR-M3G and FERRET," July 2018. (Report Accession No. 18204A010, Verification Letter Accession No. ML18220A854)

3. Westinghouse Report WCAP-18124-NP-A, Rev. 0 Supplement 1-NP-A, Rev.0, Fluence Determination with RAPTOR-M3G and FERRET - Supplement for Extended Beltline Materials, May 2022. (Report Accession No. ML22153A139, Verification Letter Accession No. ML22200A029)

4. Westinghouse Report WCAP-18751-NP, Rev. 0, Analysis of Ex-Vessel Neutron Dosimetry from H.B Robinson Unit 2 - Cycle 32, March 2022.

5. Westinghouse Report WCAP-7373, Rev. 0, Carolina Power and Light Co. H. B. Robinson Unit No. 2 Reactor Vessel Radiation Surveillance Program, January 1970.

6. United States Nuclear Regulatory Commission Document NUREG-2192, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants, July 2017.

7. Westinghouse Letter LTR-REA-21-81-NP, Rev. 0, Recommended Responses to United States Nuclear Regulatory Commission (USNRC) Requests for Additional Information (RAIs) 3.5.2.2.2.6-1 and 3.5.2.2.2.7-1 Related to the Point Beach Subsequent License Renewal Application (SLRA), July 2021.

8. United States Nuclear Regulatory Commission Document NUREG/CR-6453, H.B. Robinson 2 Pressure Vessel Benchmark, October 1997.

v t e Letter Sequence Request
EPID:L-2023-LLL-0013, 0 to Updated Final Safety Analysis Report (Open)
Initiation Request, Request Acceptance Administration Questions Answers Results Approval... Other: ML24009A271, RA-23-0055, Notice of Intent to Pursue Subsequent License Renewal for H. B. Robinson Steam Electric Plant, Unit Number 2
MONTHYEAR2023-07-12 [Table View]

RA-23-0141, Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule

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RA-23-0141, Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule

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