L-2024-026, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules

Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules

ML24058A115
Person / Time
Site:	Saint Lucie
Issue date:	02/27/2024
From:	Catron S Florida Power & Light Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
L-2024-026
Download: ML24058A115 (1)

Text

February 27, 2024 L-2024-026 10 CFR 54.17 10 CFR 50 Appendix H

U.S. Nuclear Regulatory Commission Attn: Document Control Desk 11545 Rockville Pike One White Flint North Rockville, MD 20852-2746

St. Lucie Nuclear Plant Unit 1 Docket 50-335 Renewed Facility Operating License DPR-67

REVISED REACTOR VESSEL MATERIALS SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULES, ST. LUCIE UNIT 1

References:

1. FPL Letter L-2021-192 dated October 12, 2021 - Subsequent License Renewal Application -

Revision 1 (ADAMS Accession No. ML21285A107)

2. FPL Letter L-2022-043 dated April 7, 2022 - Subse quent License Renewal Application Revision 1 -

Supplement 1 (ADAMS Accession No. ML22097A202)

3. FPL Letter L-2022-044 dated April 13, 2022 - Subseq uent License Renewal Application Revision 1 -

Supplement 2 (ADAMS Accession No. ML22103A014)

4. FPL Letter L-2022-071 dated May 19, 2022 - Subseque nt License Renewal Application Revision 1 -

Supplement 3 (ADAMS Accession No. ML22139A083)

5. NRC Safety Evaluation Related to the SLRA of St. Lucie Plant, Units 1 and 2 dated July 21,2023 (ADAMS Accession No. ML23200A146)

Florida Power & Light Company (FPL), owner and licensee for St. Lucie Nuclear Plant (PSL) Units 1 and 2, has submitted a revised and supplemented subsequent license renewal application (SLRA) for the Facility Operating Licenses for PSL Units 1 and 2 (References 1 - 4). Based on the NRCs review of the SLRA, the NRC issued its Safety Evaluation for the SLRA (Reference 5).

The primary reason for this request is to revise the surveillance capsule withdrawal schedule in the Current License Basis (CLB) for the St. Lucie Unit 1 to that reviewed and found acceptable to the NRC, as documented in Reference 5. In reaching this conclusion of acceptability, the NRC found that FPL provided an acceptable demonstration, in accordance with 10 CFR 52.21(c)(1)(iii), that the effects of aging due to neutron fluence on the intended functions of the Reactor Pressure Vessel (RPV) beltline and extended beltline materials would be adequately managed through the neutron fluence monitoring Aging Management Program (AMP) and the reactor vessel material surveillance AMP for the subsequent period of extended operation. The NRC also concluded that the proposed changes to UFSAR Table 5.4-3 contained an adequate summary description of the Neutron Fluence Projections Time Limited Aging Analysis (TLAA) evaluation for the subsequent period of extended operation as required by 10 CFR 54.21(d).

Florida Power & Light Company

15430 Endeavor Drive, Jupiter, FL 33478 St. Lucie Nuclear Plant Unit 1 Docket 50-335 L-2024-026 l Page 2 of 3

There have been no changes since issuance of Reference 5 that would impact the analysis and conclusion that the NRC performed.

The proposed changes are provided in Table 5.4-3 in Appendix A1 of the SLRA. Attached is a copy of the relevant page that illustrates the change that the NRC found acceptable in Reference 5. Upon approval, the UFSAR will be updated to reflect the proposed change in accordance with 10 CFR 50.71(e).

Should you have any questions regarding this submittal, please contact Kenneth Mack at (561) 304-6206 or Kenneth.Mack2@fpl.com.

Sincerely, Sincerely,

Steve Catron Steve Catron Licensing and Regulatory Compliance Director - Nuclear Fleet Licensing and Regulatory Compliance Director - Nuclear Fleet Florida Power & Light Company

Cc: Regional Administrator, USNRC, Region II Senior Resident Inspector, USNRC, St. Lucie Plant Chief, USNRC, Division of New and Renewed Licenses Senior Project Manager, USNRC, Division of New and Renewed Licenses Chief, Bureau of Radiation Control, Florida Department of Health St. Lucie Nuclear Plant Unit 1 Docket 50-335 L-2024-026 l Page 3 of 3