ML24116A040
| ML24116A040 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/23/2024 |
| From: | Rasmus P Point Beach |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-2024-063 | |
| Download: ML24116A040 (16) | |
Text
April 23, 2024*
CD 2 to this Letter Contains Noi1-Public Information Withhold CD 2 from Public Disclosure in Accordance \vith 10 CFR2.390 United States Nuclear Regulatory Commission Attention: Oocument Control Desk Washington, DC 20555-0001 Point Beach Nuclear Plant, Uhits 1 and 2 Dockets 50-266 and 50--301 Renewed. License Nos. DPR-24 and DPR-27 L-2024-063 10 CFR 50.59(d)(2) 10CFR 50.71(e) 10 CFR 54.37(b)
Periodic Update of the Updated Final Safety Analysis Report In accordance with the requirements of 10 CFR 50.71 (e) and 10 CFR 54.37(b), this letter submits a periodic update since October 4, 2022, bf the Point Beach Nuclear Plant Upd<=1ted Final Safety Analysis Report (UFSAR).
The UFSAR is provided iii its entirety on CD,.ROM ih Portable Document Format (PDF). 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 (1 O CFR 2;390). Therefore, a non--
public arid public version of the UFSAR is.enclosed, Where the* public version shall be released to the public domain (ADAMS).
The summarjei;; of 10 CFR 60.59 evaluations for engineering changes ~re attached a$ Enclosure L Enclosure 2 is a listing of UFSAR Change Requests (EC/UFCRs).incorporated into the UFSAR during the reporting period. Enclosure 3 contains changes incorporated in the Technical Requirements Manual. Enclosure 4 contains the Technical Specification Bases (TSB) that have been updated during (his reporting period. EncJosure 5 contains a report describjng how the
.effeds of aging of newly-identified structures, systems or components (SSCs) will be managed, as required by 10 CFR 54.37(b). There have been no Regulatory Commitment changes for this periodic update.
One copy of the UFSAR revision on CD-ROM is being submitted to the Document Control Desk, Washington; be, along with a copy to the Region Ill Regional Office and a copy to the Resident Inspector at Point Be~u:;h Nuclear Plant.
This letter contains 116 new Regulatory Commitments and no changes to existing Regulatory Commitments.
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U.S. Nuclear Regulatory Cornmis:sion U-2024.:663 I Page 2.* ** *
- Should you hav~ any questions regarding this submission, please contact Mr. Kenneth Mack, Fleet Licensing Manager, at 561.:904"'3635.
- I declare uilder perlalty ofperjurfthat the fdregoirig i~ tn.ie and corre¢t Executed on April 23, 2024;
- Sincerely,.
- P~iul'Rasriius.
General Manager, Regulatory Affairs cc:
NRC R~gio11 tu Aqministrator
- NRC ProjeGt Manager NRC $enior Resident lnsp~ctor
- P$¢W (ie.ss. ebclost:m:~$} * *
. Enclosed Cb.Listing:
CD 1,UFSAR C[) 2, UFSAR Nori:Pul)lic V~rsion (Proprietary).
Pohi.t Beach Nuclea1* Plant 10 CFRS0.59 Report; Point Beach Nuclear Plant Updated Final Safety Analysis Report, Technical Requirements Manual, Technical Specification Bases update, a11d 10 CFR 54.37(b) Aging Management Review Summary Page 1 of 1
Enclostire 1 t9 L-2024-063 Summary Report of Facility Changes, Tests, and Experiments Completed in Accordance with the Requirements ofl 0CFR50.59
Design Change Evaluations Design changes docmi1ented in the followingErtgineering Changes (EC) were instaUed during the period covered by the 10 CFR 50.59 Repoit. A 10 CFR 50.59 evaluation was performed foi' the ECs 1.dentified below. For each of tl1e evaluations performed, there were no activities requiring prior NRC approval identified.
10 CFR 50.59 Evaluation 2022"003 Summary Desl!ription and
Purpose:
EC 296438, BEACON" TSM" This activity is to install and configure the BEACON' TSM Core Monitoring System software and hardware at PBNP Units 1 and 2 and to connect the system to the Plant Process Monitoring System (PPCS). this will result fo the ability for PBNP to 11se BEACONTM to calc~llate dynamic uncertainties based on instrume11tation characteristics and time since the last flux map, plus allows the user to perform power distribution survemance while taking fewer flux maps. The system is passive and provides no control or alarm functions atid does 11ot promote any new plant configmation relied upon to remain fonctional d11ring or following a design basis event to ensure any safety related functions. AU physical coliippnent~ and hardware installed or modified by this EC are nu.clear non"safety (NNS).
Evaluation Sunimary:
These changes follow the approval of License Amendment Request (LAR) 295, "BEACON Power Distribution Monitoring System," which detailed changes to Teclmical Specifications (TS) 3.2.4, "Quadrant Power TiltRatio (QPTR)" and TS 3.3.1, Reactor Ptotection System (RPS) Instrumentation, and associated TS Bases.
The proposed activity does not result in a departure from a h1ethod of evaluation described in the UFSAR used in establishing the design bases or in the safety analysis. 111erefore, the proposed activity does notreqµire prior NRC review and approval; Page 1 of 1
Point Beach Nuclear Plant Enclosure 2 to L-2024-063 List of Changes Incorporated in Updated Final Safety Analysis Report
Point Beach Nuclear Plant Enclosure.2 DESCRIPTION OF CHANGES Table of Contents Throughout Editorial Changes: Editorial changes were made to correct grammar, punctuation, spelling, and to ensure consistency between text headings, table titles, figure titles, table of contents, etc. These changes may not be identified by a revision bar; Chapter3 FSAR 3.2-7 through FSA.R 3.2-8 Licensing Basis Change: Added sentence describing BEACON Power Distribution Monitoring System (PDMS). (EC 296438)
FSAR 3.2-10 Licensing Basis Change: Added paragraph describing BEACON Power Distribution Monitoring System (PDMS). (EC 296438)
FSAR 3.2~38 through FSAR 3.2.:39 Editorial Change: Added new Reference No. 56, No. 57 and No. 58. (EC 296438)
Chapter 5 FSAR 5.3-8 Updated Figure to reflect approvJ:d drawing ofrecord.
Chapter 6 FSAR 6.2-1 through FSAR 6,2-2 Licensing Basis Change: Add references to Appendix A,8. (EC 299029)
FSAR 6.2-6 Licensing Basis Change: Add references to Appendix A.8, (EC 299029)
FSAR 6.2-26 through FSAR 6.2-27 Licensing Basis Change:.Add.references to Appendix A.8. (EC 299029)
FSAR 6.4-4 Licensing Basis Chang!: Add Effects of Debris in Response to GL 2004,-02 and references to Appendix A.8. {EC 299029)
FSAR6.4-12 Licensing Ba.sis Change: Add Effects of Debris in Response to GL 2004-02 and references to Appendix A.8. (EC 299029)
FSAR 6.5..:2 through FSAR 6.5-3.
Licensing Basis Change: Changed verbiage to implementthe PASS Elimination. (EC 297321}
FSAR6.5-3 Licensing Basis Change: Provide update to Specify that the respective DAM is poll~d bytheTerminalServer, as reqµiredto reflect changes implemented. (EC 288819)
.FSAl:{6.5-5 Licensing Basis Change: Provide update to spe*cify that the respective DAM.ls polled by the Terminal Server and that High.Activity Alarm lndkations are provided on radiation monitoring system Human Machine Interfaces {HM l's) and Workstations. (EC 288819)
.FSAR 6.5-9 through FSAR 6.5-10 Licensing Basis Change: Added References 8, 9, and 10. (EC 297321}
Page 1 of 3
Point Beach Nuclear Plant Enclosure 2 Chapter 7 FSAR TOC7~iii Editorial Change: Added new Reference Section. {EC 296438)
FSAR 7.6-13 through FSAR 7.6-14 Uc~nsing Basis Change: Added Subsection d. describing BEACON Power Distribution Monitoring System {PDMS). (EC 29643~)
FSAR 7.6-16 Editorial Change: Added new Reference No. 1, l\io. 2 and No. 3. (EC 296438}
Chapters FSAR 8.9-2 Editorial Change: Section 8,9.3 revised to reference a singular fuel oil storage tank. (EC 296648)
Chapter9 FSAR 9$-9 through FSAR9.6-11 Updated Figure to reflect approved drawing of record.
FSAR9.lh1 Licensing Bc1sis Change: Changed verbiage to implementthe PASS Elimination. (EC 297321)
FSAR 9.11-3 Licensing Basis Change: Changed verbiage to implementthe PASS Elimination. (EC 297321)
FSAR 9.11,-6 Chapter 10 FSAR 10.1,-22 Updated Figure to reflect approved drawing of record.
FSAR 10.1-25 Updated Figure to refleclapproved drawing of rec::ord.
Chapter 11 FSAR 11.5-3 through FSAR.11.5-5 Licensing Basis Change: Provide updates to clarify new system function. {EC.288,81Q)
FSAR 11.5-22 Editorial Change: Corrected a minor typographical error,.. DAM 03-03{04~03)versus DAIVI 03-03(03-04). (EC 298690)
FSAR 11.5-27 Licensing Basi.s Change: Add 155 Witness\ 'CR Workstation 1', 'CR Workstation 2, and TSC Workstation to Functional Block Dlagn:.1m, (EC'288819)
Chapter 14 F5AR 14.0-1 Licensing Basis Change: Add references to GL 2004~02 and Appendix A.8. (EC 299029)
Page 2 of 3
Point Beach Noclear PJant Enclosure 2 Appendix A FSAR TOC-A-ji Licensing Basis Change: Add FSAR Appendix A.8 Resolution of NRC ~eneric Letter 2004-
- 02. {EC 299029)
FSARA.3-11 Editorial Change: FSAR Appendix A.3 Reference change from Engineering chahge EC 29637 4 to reference Erigineering Evaluation 2020-0020. (EC 299028)
FSAR A.8~1 through FSAR A.8-10 Licensing Basis Change: Add FSAR Appendix A.8 Resolution of NRCGeneric Letter 2004-
- 02. (EC 299029)
Page 3.of 3
Point Beach Nuclear Plant, Enclosi.Jl'e 3 Enclosul'e 3 to L-2024-063 Table of changes for the Technical Requirements Manual.
Point Beach Nucleal' Plant, Enclosure 3 Affec_ted
- Date of Affected Section Change Page(s)
Summary TRM 4.17 February 2024 1, 2 Implemented Amendments 27 4/276 for Pre-Stressed Concrete Containment Tendon Surveillance Proaram TRM 3.2.1 October 2023 2
The changes incorporated the Use of BEACON as approved by the NRG via Amendments 272/274 TRM-3.2:.2 October 2023 All Pages New TRM created for the Power Distribution Monitoring System - to align with the Use of BEACON as approved by the NRG via Amendments 272/27 4 TRM 2.1 October 2023 1, 4, 12, The changes included updates forthe Unit 1 Unit 1 13_, 14, Cycle 42 core Operating Limits Report 15,16, 17, 20 TRM 4.20 September AU Pages New TRM for the Risk Informed Completion Time 2023 Program that was implemented per Amendments 271/273 TRM 2.1 March 2023 1, 4, 12, The changes included updates for the Unit 2 Uliit2 13, 14, 15, Cycle 40 Core Operating Limits Report 16, 17,20 TRM 3.3.1 February 2023 Page 6 Removed reference to "Post Accident" and replaced with "contingency" to align with Elilnination of Req1.1irements for Post Accident Samolino Svstems - Amendments 270/272 TRM4.3 February 20:23 All Pages Canceled this TRM to align with Elimination of Requirement for Post Accident Sampling Systems
- Amendment 270/272 TRM 3.7.6 October 2022 Pages 3, Extended the Turbine Valve Testing Frequency 7,8 from 9 to 18 months per EC 2977911 Page 1 of 1
Point Beach Nuclear Plant Enclosure 4 to L-2024-063 Table of changes for Technical Specification Bases
Point Beach Nuclear Plant Enclosure 4 Affected Date of Affected Section Chanae Paae(s)
Summarv TS B 3.1.4 Implemented Amendments 272/274 Regarding Revision to Use BEACON Power Distribution Monitoring System TS B 3.2.1 Implemented Amendments 272/27 4 Regarding Revision to Use BEACON Power Distribution Monitoring System TS B 3.2.2 Implemented Amendments 272/27 4 Regarding Revision to Use BEACON Power Distribution Monitorina System TS B 3.2.3 Implemented Amendments 272/274 Regarding Revision to Use BEACON Power Distribution Monitoring System TS B 3.2.4 Implemented Amendments 272/27 4 Regarding Revision to Use BEACON Power Distribution Monitorina Svstem TS B 3.3.1 Implemented Amendments 272/274 Regarding Revision to Use BEACON Power Distribution Monitoring System TS B 3.3.1 Implemented Amendments 271/273 for Risk-Informed Extended Completion Times-RITSTF Initiative 4b (RICT)
TS B 3.3.2 Implemented Amendments 271/273 for Risk-Informed Extended Completion Times - RITSTF Initiative 4b (RICT)
TS B 3.4.11 Implemented Amendments 271/273 for Risk-Informed Extended Completion Times - RITSTF Initiative 4b (RICT)
TS B 3.5.2 Implemented Amendments 271/273 for Risk -
Informed Extended Completion Times - RITSTF Initiative 4b (RICT)
TS B 3.6.2 Implemented Amendments 271/273 for Risk'"
Informed Extended Completion Times - RITSTF Initiative 4b (RICT)
TS B 3.6.3 Implemented Amendments 271/273 for Risk -
Informed E)(tended Completion Times - RITSTF Initiative 4b (RICT)
TS B 3.7.2 Implemented Amendments 271/273 for Risk-Informed Extended Completion Times - RITSTF Initiative 4b (RICT)
TS B 3.7.4 Implemented Amendments 271/273for Risk-Informed Extended Completion Times-RITSTF Initiative 4b (RICT)
TS B 3.7.5 Implemented Amendments 271/273 for Risk-Informed Extended Completion Times - RITSTF Initiative 4b (RICT)
TS B 3.7,7 Implemented Amendments 271/273 for Risk-Informed Extended Completion Times - RITSTF Initiative 4b (RICT)
Page 1 of2
Point Beach Nuclear Plant Enclosme 4 TS B 3.7.8 Implemented Amendments 271/273 for Risk-Informed Extended Completion times - RITSTF Initiative 4b (RICT)
TS B 3.8.1 Implemented Amenclments 271/273for Risk-Informed Extended Completion Times - RITSTF Initiative 4b (RICT)
TS B 3.8.4 Implemented Amendments 271/273 for Risk-Informed Extended Completion Times-RITSTF Initiative 4b (RICT)
TS B ~.5.3 February Pages 1, Changes used TSTF-575-T to update TS B for 2024 2,3 ECCS - Shutdown to delete any discus~ions regarding a loss of coolant accident or other design basis accidents and revise the statement in the Applicable Safety Analysis Section to state that an ECCS train satisfies Criterion 4 of NRC Policy Statement, not Criterion 3 TS B 3.6.1 Implemented Amendments 274/276 for Pre-Stressed Concrete Containment Tend oh Surveillance ProQram Page 2 of 2
Point Beach Nuclear Plant Enclosure 5 to L-2024-063
Aging Management Review Smnmmy
Point Beach Nuclear Plant Enclosure 5 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 10 CFR 54.37(b) Report - 2024 FSAR Update 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 September 1, 2022 (the latest date of last year's report) and March 1, 2024. This review is performed in accordance with Fleet procedure EN-M-106-1001.
Regulatory Requirements and Guidance 10 CFR 54.37(b)
After the renewed license is issued, the FSAR update required by 10 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 Newly Identified Systems, Structures, and Components (SSCs)
The intent of 10 CFR 54.37(b) is to capture those SSCs that, ifthey 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 1 O 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.
- The sscs* would have been in the scope of license renewal ba$ed.on the CLB change if 10 CFR 54.4(a) were applied to the sscs.
(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 10 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 1 O 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 NRG staff.may also discover newly identified SSCs, One way.to identify these SSCs is through the LR-ISG process.
Newly identified SSC In 2024, 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 (September 1, 2022). This review did not identify any additional components that would be considered "newly ide1itified" and subject to 10CFR54.37(b) reporting requirements.
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