ML21102A342

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Submittal of Periodic Update of the Final Safety Analysis Report
ML21102A342
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 04/02/2021
From: Strope M
Point Beach
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML21102A337 List:
References
NRC-2021-0009
Download: ML21102A342 (6)
v • d • e


Text

Security Related Information - Withhold from Public Disclosure Under 10 CFR 2.390 POINT BEACH April 2, 2021 NRG 2021-0009 10 CFR 50.71(e) 10 CFR 54.37(b)

U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 Periodic Update of the 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 of the Point Beach Nuclear Plant Final Safety Analysis Report (FSAR). to this letter includes 1 CD-ROM containing the non-public version of the Point Beach FSAR, including the description of changes. The FSAR is being submitted in its entirety, constituting a total replacement copy. Enclosure 1 contains security related infoITT1ation as defined by 10 CFR 2.390( d) and should be withheld from public disclosure. The enclosure reflects changes since the last periodic update of October 18, 2019. to this letter includes 1 CD-ROM containing the public version of the Point Beach FSAR. to this letter includes a report describing how the effects of aging of newly-identified structures, systems or components (SSCs) will be managed, as required by 10 CFR 54.37(b).

This letter contains no new Regulatory Commitments and no revisions to existing Regulatory Commitments.

Security Related lnfonnatlon -Withhold Under 10 CFR 2.390.

Enclosure 1 Contains Security Related Information, Upon Separation of Enclosure 1 this letter is Non-Security Related.

NextEra Energy Pomt Beach, LLC 6610 Nuclear Road, Two Rivers, WI 54241

Security Related Information - Withhold from Public Disclosure Under 10 CFR 2.390 Document Control Desk Page 2 I declare under penalty of perjury that this submittal accurately presents changes made since the previous submittal that reflect information and analyses submitted to the NRG or prepared pursuant to NRG requirements, and changes made under the provisions of 10 CFR 50.59.

Executed on April 2, 2021.

Sincerely, NextEra Energy Point Beach, LLC

~

Michael Strope Site Vice President Enclosures (3) cc: Administrator, Region 111, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW (less enclosures)

Security Related lnfonnatlon - Withhold Under 10 CFR 2.390.

Enclosure 1 Contains Security Related lnfonnation, Upon Separation of Enclosure 1 this letter is Non-Security Related.

Security Related lnfonnation - Withhold from Public Disclosure Under 10 CFR 2.390 ENCLOSURE 1 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 2020 UPDATE OF THE FINAL SAFETY ANALYSIS REPORT NOT FOR PUBLIC DISCLOSURE Security Related lnfonnatlon - Withhold Under 10 CFR 2.390.

Enclosure 1 Contains Security Related Information, Upon Separation of Enclosure 1 this letter Is Non-Securtty Related.

ENCLOSURE 2 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 2020 UPDATE OF THE FINAL SAFETY ANALYSIS REPORT REDACTED - PUBLIC VERSION

ENCLOSURE 3 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 REPORT CONSISTENT WITH 10 CFR 54.37(b)

ON HOW EFFECTS OF AGING OF NEWLY-IDENTIFIED STRUCTURES, SYSTEMS, OR COMPONENTS ARE MANAGED This update follows the guidance_ regarding the app~opriate level of detail for reports under 10 CFR 54.37(b) that is presented in Frequently Asked Questions (FAQs) About License Renewal-Inspection Procedure (IP) 71003, "Post-Approval Stte Inspection for License Renewal." This report provides summa~ information as required by 10 CFR 54.37(b) for the period between September 13, 2019 through March 1, 2021.

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 effecuvely 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, if they had been identified at the time of the license renewal application, wouJd 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:

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(1) There is a change to the current licensing basis (GLB) that meets the following criteria:

The change impacts SSGs that were not in scope for license renewal when the NRG approved the license renewal application.

The SSGs would have been in the scope of license renewal based on the GLB change if 10 GFR 54.4(a) were applied to the SSGs.

(2) SSGs were installed in the plant at the time of the license renewal review that, in accordance with the GLB at the time, should have been included in the scope of license renewal per 10 GFR 54.4(a) but were not identified as in scope until after issuance of the renewed license.

SSGs that are plant additions or modifications installed after the renewed license is issued are not subject to the provisions'of 10 GFR 54.37(b).

Identification of SSGs under 10 GFR 54.37(b)

The language of 10 GFR 54.37(b) does not limit how or who finds newly identified SSGs. A licensee may identify SSGs that should be within the scope of its license renewal program at any time. The NRG staff may also discover newly identified SSGs. One way to identify these SSGs is through the LR-ISG process.

Newly Identified SSC In 2021, 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 Licensing Basis (September 2019). This review did not identify any additional components that that would be considered 0

"newly identified and subject to 10 CFR 54.37(b) reporting requirements.

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