ML25282A042
| ML25282A042 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/09/2025 |
| From: | Mack K Point Beach |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| Shared Package | |
| ML25282A060 | List: |
| References | |
| L-2025-162 | |
| Download: ML25282A042 (1) | |
Text
Security Related Information -Withhold from Public Disclosure Under 10 CFR 2.390 NEXTera ENERGYi POINT BEACH U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington DC 20555-0001 RE:
Point Beach Nuclear Plant, Units 1 and 2 Docket Nos. 50-266 and 50-301 Renewed Facility Operating Licenses DPR-24 and PPR-27 Periodic Update of the Updated Final Safety Analysis Report October 9, 2025 L-2025-162 10 CFR 50.59(d)(2) 10 CFR 50.71 (e) 10 CFR 54.37(b)
In accordance with the requirements of 10 CFR 50.71(e), NextEra Energy Point Beach LLC, submits the Updated Final Safety Analysis Report (UFSAR). Some details referenced in the UFSAR are not being released to the public domain (ADAMS) as they have the potential to contain security-related information (10 CFR 2.390). Therefore, non-public and public versions of the UFSAR are enclosed, where the public version shall be released to the public domain (ADAMS).
The summaries of 1 O CFR 50.59 evaluations for engineering changes are attached as Enclosure
- 1. Enclosure 2 is a listing of UFSAR Change Requests (EC/UCRs) incorporated into the UFSAR during the reporting period. Enclosure 3 contains changes incorporated in the Fire Protection Program Design Document (FPPDD). Enclosure 4 contains changes incorporated in the Technical Requirements Manual. Enclosure 5 contains the Technical Specification Bases (TSB) that have been updated during this reporting period. Enclosure 6 contains a report describing how the effects of aging of newly identified structures, systems or components (SSCs) will be managed, as required by 1 O CFR 54.37(b). There have been no Regulatory Commitment changes for this periodic update.
In addition to this submittal letter and the enclosures listed on page 2, the following supporting documents are also being provided as attachments to this letter via the EIE system: UFSAR Rev.
2023 - Nonpublic; UFSAR Rev. 2023 - Public; Technical Requirements Manual Rev. 146; Technical Specifications Bases Rev. 33; Fire Protection Program Design Document Rev. 4; and 10 CFR 54.37(b) Report - 2025 Update.
Nex!Era Energy Point Beach, LLC 6610 Nuclear Road, Two Rivers, WI 54241 Security Related Information -Withhold Under 10 CFR 2.390 Attachment 1 Contained Security Related Information, Upon Separation of Attachment 1 this Letter is Non-Security Related
Security Related Information - Withhold from Public Disclosure Under 10 CFR 2.390 Point Beach Nuclear Plant, Units 1 and 2 Docket Nos. 50-266 and 50-301 L-2025-162 Page 2 This letter contains no new Regulatory Commitments and no changes to existing Regulatory Commitments.
Should you have any questions regarding this submittal, please contact Ms. Maribel Valdez, Fleet Licensing Manager, at 561-904-5164.
Sincerely, Director, Licensing and Regulatory Compliance Enclosures (6)
- 1. Summary Report in Accordance with 10 CFR 50.59 and 10 CFR 72.48
- 2. Listing of UFSAR Change Requests (UCRs) Incorporated in Updated Final Safety Analysis Report, Revision 2023
- 3. Listing of UFSAR Change Requests (UFCRs) Incorporated in Fire Protection Safe Shutdown Capability (10 CFR 50, NFPA 805), Revision 2023
- 4. Listing of UFSAR Change Requests (UCRs) Incorporated in Revision 146ofthe Technical Requirements Manual (TRM)
- 5. Listing of Technical Specification Bases (TSB), Revision 33 that have been updated during this reporting period
- 6. 1 O CFR 54.37(b) Aging Management Review Summary Attachments (6):
- 1. UFSAR Rev. 2023 - Nonpublic Version (Proprietary)
- 2. UFSAR Rev. 2023 - Public Version
- 3. Technical Requirements Manual Rev. 146
- 4. Technical Specifications Bases Rev. 33
- 5. Fire Protection Program Design Document Rev. 4
- 6. 10 CFR 54.37(b) Report - 2025 Update cc:
USNRC Regional Administrator, Region Ill USNRC, Project Manager, Point Beach Nuclear Plant USNRC, Senior Resident Inspector, Point Beach Nuclear Plant Public Service Commission of Wisconsin (less enclosures and attachments)
Security Related Information -Withhold Under 10 CFR 2.390 Attachment 1 Contained Security Related Information, Upon Separation of Attachment 1 this Letter is Non-Security Related
Security Related Information - Withhold from Public Disclosure Under 10 CFR 2.390 Point Beach Nuclear Plant, Units 1 and 2 Docket Nos. 50-266 and 50-301 Point Beach Units 1 and 2 to L-2025-162 L-2025-162 Summary Report of Facility Changes, Tests, and Experiments Completed in Accordance with the Requirements of 10 CFR 50.59 and 10 CFR 72.48 for Revision 2023 of the Updated Final Safety Analysis Report 1.0 10 CFR 50.59 Evaluation Summary Report I EVAL 2024-002, Rev. 0 (EC 294920 Unit 1 and EC 294922 Unit 2) 2.0 Executive Summary This 10 CFR 50.59 evaluation assesses the addition of reagent grade glacial acetic acid to the Reactor Coolant System (RCS) zinc injection process at Point Beach Nuclear Plant. The evaluation determines that this activity does not require prior NRC review or license amendment.
3.0 Activity Description The proposed activity involves using reagent grade glacial acetic acid to inject depleted zinc acetate (OZA) solution into the RCS. This modification addresses maintenance of zinc precipitates in solution through controlled pH adjustment, enhanced primary water chemistry control for corrosion mitigation, and alignment with industry best practices for zinc injection systems.
4.0 Key Technical Findings The glacial acetic acid will be added in small amounts not exceeding 0.5 ppm to maintain OZA solution stability. The RCS pH control remains via the existing Boric Acid and Lithium system, with minimal impact from this addition. All RCS materials are constructed of corrosion-resistant materials per Perry's Chemical Engineers' handbook, and the weak concentration of acetic acid with its expected short residence time poses negligible corrosion risks. The activity maintains existing RCS chemistry control parameters and does not affect current plant procedures for the Chemical and Volume Control System.
5.0 1 O CFR 50.59 Screening Results The evaluation addressed all eight screening questions with negative responses, confirming no increase in accident frequency or malfunction likelihood, no increase in radiological consequences, no creation of new accident types or structures, systems, and components Security Related Information -Withhold Under 10 CFR 2.390 Attachment 1 Contained Security Related Information, Upon Separation of Attachment 1 this Letter is Non-Security Related
Security Related Information -Withhold from Public Disclosure Under 10 CFR 2.390 Point Beach Nuclear Plant, Units 1 and 2 Docket Nos. 50-266 and 50-301 Point Beach Units 1 and 2 L-2025-162 malfunctions, no impact on fission product barriers, and no departure from evaluation methodologies described in the Updated Final Safety Analysis Report.
6.0 Regulatory Conclusion Based on comprehensive screening analysis, the proposed activity does not constitute an unreviewed safety question and requires no prior NRC approval. The activity may proceed under existing plant procedures with appropriate chemistry monitoring and control measures in place.
This evaluation demonstrates that the addition of reagent grade glacial acetic acid to the zinc injection system maintains safety margins while enhancing primary chemistry control capabilities.
There were no 10 CFR 72.48 Evaluations identified for 2024 or 2025 Security Related Information -Withhold Under 10 CFR 2.390 Attachment 1 Contained Security Related Information, Upon Separation of Attachment 1 this Letter is Non-Security Related
Security Related Information - Withhold from Public Disclosure Under 10 CFR 2.390 Point Beach Nuclear Plant, Units 1 and 2 Docket Nos. 50-266 and 50-301 Point Beach Units 1 and 2 to L-2025-162 L-2025-162 Listing of UFSAR Change Requests (UCRs) Incorporated in Updated Final Safety Analysis Report, Revision 2023 UCR Number Affected Section Affected Table Affected Figure 288819 11.5; 6.5 296438 3.2; 7.6 296648 8.9.3 297051 Appendix A.3 298817 5.7 299028 Appendix A.3 299029 14.0; 6.2; 6.4 299326 6; 8; 9; 10; 12 299663 7.6; 7.7; 8.3 299664 1.2; 10.1; 2.2; 5.3; 6.5; 8.0; 9.11 ; 9.6 300037 5.2 5.2.1 300215 5.2 300329 3.2; 9.9 Drawings replaced 1
1.2-1 O; 1.2-11 ; 1.2-with "REFER TO 12; 1.2-13; 1.2-14; DRAWING" page 1.2-2; 1.2-3; 1.2-4; 1.2-5; 1.2-6; 1.2-7; 1.2-8; 1.2-9 2
2.2-4 4
4.2-1 sht. 1; 4.2-1 sht. 2; 4.2-1 sht. 3; 4.2-1A sht. 1; 4.2-1A sht. 2; 4.2-1A sht. 3 5
5.2-73-1 ; 5.3-1 sht. 1 and 1.2-4 (Historical);
Security Related Information - Withhold Under 10 CFR 2.390 Attachment 1 Contained Security Related Information, Upon Separation of Attachment 1 this Letter is Non-Security Related
Security Related Information -Withhold from Public Disclosure Under 10 CFR 2.390 Point Beach Nuclear Plant, Units 1 and 2 Docket Nos. 50-266 and 50-301 Point Beach Units 1 and 2 6
7 8
9 10 11 L-2025-162 5.3-1 sht. 2; 5.3-1 sht. 3 6.2-1 sht. 1; 6.2-1 sht. 2; 6.2-1 sht. 3; 6.5-1 7.2-3; 7.3-1; 7.4-1 8-1; 8-2; 8-3 Sh 1; 8-3 Sh 2; 8-3 Sh 3; 8-4; 8-5; 8-6; 8-7; 8-8 9.1-1 ; 9.11-1 ; 9.1-2; 9.2-1 ; 9.3-1; 9.3-2; 9.3-3; 9.3-4; 9.3-5; 9.6-1; 9.6-2; 9.6-3; 9.6-4; 9.6-5; 9.6-6; 9.6-7; 9.9-1 10.1-1 sht. 1; 10.1-1 sht. 2; 10.1-1 sht. 3; 10.1-1Asht.1 ; 10.1-1A sht. 2; 10.1-1A sht. 3; 10.1-2 sht. 1; 10.1-2 sht. 2; 10.1-2 sht. 3; 10.1-2A sht. 1; 10.1-2A sht. 2; 10.1-2A sht. 3; 10.1-3 sht.
1; 10.1-3 sht. 2; 10.1-3A sht. 1 ; 1 0. 1-3A sht. 2; 10.1-4 sht. 1; 10.1-4 sht. 2; 10.1-4 sht. 3; 10.1-4A sht. 1; 10.1 -4A sht. 2; 10.1-4A sht. 3; 10.1-6; 10.1-6A; 10.1 -6B sht.
2; 10.1-7; 10.1 -7A; 10.1-8; 10.1-8A; 10.2-1 sht.1; 10.2-1 sht. 2 11.1-1 sht. 1 ; 11.1-1 sht. 2; 11.1-2; 11.1-3; 11.2-1 sht. 1; 11.2-1 sht. 2; 11.2-2; 11.2-3 sht. 1; 11.2-3 sht. 2; 11.2-4; 11.4-1; 11.4-2; 11.4-3; 11.4-4; 11.4-5; 11.4-6; 11.4-7; 11.4-8 Security Related Information -Withhold Under 10 CFR 2.390 Attachment 1 Contained Security Related Information, Upon Separation of Attachment 1 this Letter is Non-Security Related
Security Related Information -Withhold from Public Disclosure Under 10 CFR 2.390 Point Beach Nuclear Plant, Units 1 and 2 Docket Nos. 50-266 and 50-301 Point Beach Units 1 and 2 to L-2025-162 Listing of UFSAR Change Requests (UCRs) Incorporated in L-2025-162 Fire Protection Safe Shutdown Capability (10 CFR 50, NFPA 805), Revision 2023 Activity is for revision to the PB Fire Protection Program Design Document (FPPDD, Revision 4).
The purpose of the revision is to incorporate previously evaluated and installed modifications.
1.Updated App. C Section 3.3.5.3 NFPA 805 Ch 3 cable construction compliance to incorporate; EC 297870 (FPEE 2023-001) and, EC 298631 (FPEE 2023-002). These ECs/FPEEs accounted for cabling material and testing differences used in those modifications that still meet PB FP Program (FPTE-011) requirements.
2.Section 8.5 was updated to incorporate AR 02474775 to remove reference to AOP-40G.
PCR 02407989 cancelled AOP-40G and associated BG AOP-40G based on EC 292094.
Security Related Information - Withhold Under 10 CFR 2.390 Attachment 1 Contained Security Related Information, Upon Separation of Attachment 1 this Letter is Non-Security Related
Security Related Information -Withhold from Public Disclosure Under 10 CFR 2.390 Point Beach Nuclear Plant, Units 1 and 2 Docket Nos. 50-266 and 50-301 L-2025-162 Point Beach Units 1 and 2 to L-2025-162 Listing of UFSAR Change Requests (UCRs) Incorporated in Revision 146ofthe Technical Requirements Manual (TRM)
Affected Date of Affected Summary Section Chanae Paae(s)
TRM 2.1 Unit 1 03/28/2025 TOC 1, Updates for CORE OPERATING LIMITS 1.0-2, 1, REPORT (COLR) UNIT 1 CYCLE 43 12-17, 20 TRM 3.2.2 03/24/2025 TOC 1, 1 Added note to Power Distribution Monitoring System (PDMS)
TRM 2.1 Unit 2 02/17/2025 1, 4, 12-Updates for CORE OPERATING LIMITS 17,20 REPORT (COLR) UNIT 2 CYCLE 40 TRM 3.3.1, TRM 02/17/2025 TOC 1, 2, "Post Accident" changed to "Contingency",
4.3 1.0-2, 1, removed section 4.3 "Post Accident Sampling 3.3.1-6 System TRM 2.1 Unit 2 02/17/2025 TOC 1, Updates for CORE OPERATING LIMITS 16-26, REPORT (COLR) UNIT 2 CYCLE 41 29-30 TRM 3.3.1 02/17/2025 TOC 1, 1, Change for ODCM 5
TRM TOC 02/17/2025 TOC 1 Page correction TRM 4.12 02/17/2025
- TOC2, Changes to diesel fuel oil requirements 2, 3, 4, 6-9 TRM 3.7.6 02/17/2025 2, 3, 7, 8 Editorial TRM 3.5.1 02/17/2025 4
Editorial TRM 2.2 08/01/2024 TOC 1, 9, Revised Reactor Vessel Materials Surveillance 10 Capsule Schedules ML24087A033 Security Related Information -Withhold Under 10 CFR 2.390 Attachment 1 Contained Security Related Information, Upon Separation of Attachment 1 this Letter is Non-Security Related
Security Related Information - Withhold from Public Disclosure Under 10 CFR 2.390 Point Beach Nuclear Plant, Units 1 and 2 Docket Nos. 50-266 and 50-301 L-2025-162 Point Beach Units 1 and 2 to L-2025-162 Listing of Technical Specification Bases (TSB) that have been updated during this reporting period Affected Date of Affected Summary Section Change Page(s)
TS B 3.9.2 06/09/2025 3.9.2-1 The Technical Specification Task Force reviewed and approved TSTF-555-T, "Clarify the Nuclear Instrumentation Bases Regarding the Detection of an Improperly Loaded Fuel Assembly."
TS B 3.8.1 02/17/2025 3.8.1-2 Typographical Error Correction on Page B 3.8.1-2 TS B 3.6.5 02/17/2025 3.6.5-2, 3, 4 Implement Amendments 275, 277 for Units 1 and 2, respectively TS B 3.8.1 02/17/2025 3.8.1-3, 4 Updated for NFPA 805 TS B 3.5.3 02/17/2025 3.5.3-1, 2, 3 Revised to adopt TSTF-575-T.
TS B 3.4.7 02/17/2025 3.4.7-3 Revision to RCS Loops - Mode 5, Loops Filled Security Related Information - Withhold Under 10 CFR 2.390 Attachment 1 Contained Security Related Information, Upon Separation of Attachment 1 this Letter is Non-Security Related
Security Related Information -Withhold from Public Disclosure Under 10 CFR 2.390 Point Beach Nuclear Plant, Units 1 and 2 Docket Nos. 50-266 and 50-301 Point Beach Units 1 and 2 to L-2025-162 10 CFR 54.37(b)
Aging Management Review Summary NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 10 CFR 54.37(b) Report - 2025 FSAR Update L-2025-162 REPORT CONSISTENT WITH 10 CFR 54.37(b) ON HOW EFFECTS OF AGING OF NEWLY IDENTIFIED STRUCTURES, SYSTEMS, OR COMPONENTS ARE MANAGED This report addresses the requirements of 10 CFR 54.37(b) for the period between March 1, 2024 (the latest date of last year's report) and September 1, 2025. This review is performed in accordance with Fleet procedure EN-AA-106-1001.
Regulatory Requirements and Guidance 10 CFR 54.37(b)
After the renewed license is issued, the FSAR update required by 1 O CFR 50.71 (e) must include any systems, structures, and components newly identified that would have been subject to an aging management review or evaluation of time-limited aging analysis in accordance with §54.21.
This FSAR update must describe how the effects of aging will be managed such that the intended function(s) in §54.4(b) will be effectively maintained during the period of extended operation.
RIS 2007-16, Revision 1 (ML100250279)
Newly Identified Systems, Structures, and Components (SSCs)
The intent of 1 O CFR 54.37(b) is to capture those SSCs that, if they had been identified at the time of the license renewal application, would have been subject to an aging management review or evaluation of TLAAs. In the context of 10 CFR 54.37(b), newly identified SSCs that should be included in the next FSAR update required by 10 CFR 50.71(e) are those SSCs that meet one of the two following conditions:
(1) There is a change to the current licensing basis (CLB) that meets the following criteria:
- The change impacts SSCs that were not in scope for license renewal when the NRG approved the license renewal application.
Security Related Information -Withhold Under 10 CFR 2.390 Attachment 1 Contained Security Related Information, Upon Separation of Attachment 1 this Letter is Non-Security Related
Security Related Information - Withhold from Public Disclosure Under 10 CFR 2.390 Point Beach Nuclear Plant, Units 1 and 2 Docket Nos. 50-266 and 50-301 Point Beach Units 1 and 2
- The SSCs would have been in the scope of license renewal based on the CLB change if 10 CFR 54.4(a) were applied to the SSCs.
L-2025-162 (2) SSCs were installed in the plant at the time of the license renewal review that, in accordance with the CLB at the time, should have been included in the scope of license renewal per 1 O CFR 54.4(a) but were not identified as in scope until after issuance of the renewed license.
SSCs that are plant additions or modifications installed after the renewed license is issued are not subject to the provisions of 10 CFR 54.37(b).
Identification of SSCs under 10 CFR 54.37(b) The language of 10 CFR 54.37(b) does not limit how or who finds newly identified SSCs. A licensee may identify SSCs that should be within the scope of its license renewal program at any time. The NRC staff may also discover newly identified SSCs. One way to identify these SSCs is through the LR-ISG process.
Using the guidance of RIS 2007-16, Rev. 1, PBNP staff reviewed changes to the plant that had taken place since the last 54.37(b) review of the Current License Basis. This review did not identify any additional components that would be considered "newly Identified" and subject to 10 CFR 54.37(b) reporting requirements.
Security Related Information - Withhold Under 10 CFR 2.390 Attachment 1 Contained Security Related Information, Upon Separation of Attachment 1 this Letter is Non-Security Related