L-2021-155, Subsequent License Renewal Application on Aging Management - Request for Additional Information (Rai), Set 4 Response

Subsequent License Renewal Application on Aging Management - Request for Additional Information (Rai), Set 4 Response

ML21242A230
Person / Time
Site:	Point Beach
Issue date:	08/30/2021
From:	Maher W Point Beach
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2021-155
Download: ML21242A230 (5)

Text

NEXTera ENERGY S POINT BEACH August 30, 2021 L-2021-155 10 CFR 54.17 U.S. Nuclear Regulato1y Commission Attention: Document Control Desk 11545 Rockville Pike One \"X/hite Flint North Rockville, lVID 20852-2746 Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 SUBSEQUENT LICENSE RENEWAL APPLICATION -AGING MANAGEMENT REQUEST FOR ADDITIONAL INFORMATION (RAI) SET 4 RESPONSE

References:

1. NextEra Energy Point Beach, LLC (NEPB) Letter NRC 2020-0032 dated November 16, 2020, Application for Subsequent Renewed Facility Operating Licenses (ADAMS Package Accession No. ML20329A292)

2. U.S. Nuclear Regulatory Commission (NRC) Letter dated January 15, 2021, Point Beach Nuclear Plant, Units 1 and 2 - Determination of Acceptability and Sufficiency for Docketing, Proposed Review Schedule, and Notice of Opportunity to Request a Hearing Regarding the NextEra Energy Point Beach, LLC Application for Subsequent License Renewal (EPID No. L-2020-SLR-0002)

(ADAlVIS Accession No. ML21006A417)

3. NRC Letter dated January 15, 2021, Point Beach Nuclear Plant, Units 1 and 2 -Aging Management Audit Plan Regarding the Subsequent License Renewal Application Review (ADAMS Accession No. ML21007A260)

4. US Nuclear Regulatory Commission Meeting with NextEra Energy Concerning the Point Beach Subsequent License Renewal Application Review - June 3, 2021 Public Meeting (ADAlVIS Accession No. ML21148A116)

5. NRC Email and Attachment dated August 4, 2021, Point Beach SLRA RAI Set 4 Final (ADAlVIS Accession Nos. ML21238A232, ML21238A233)

N EPB, owner and licensee for Point Beach Nuclear Plant (PBN) Units 1 and 2, has submitted a subsequent license renewal application (SLRA) for the Facility Operating Licenses for PBN Units 1 and 2 (Reference 1).

On Janua1y 15, 2021, the NRC determined that NEPB's SLRA was acceptable and sufficient for docketing (Reference 2), and on January 15, 2021 issued the regulatory audit plan for the aging management portion of the SLRA review (Reference 3). Based on the information exchanged and discussions held during the public meeting held on June 3, 2021(Reference4), the NRC issued its Set 4 RAI to NEPB (Reference 5). The attachment to this letter provides the response to this information request.

For ease of reference, the index of attached information is provided on page 3 of this letter. The attachment includes associated revisions to the SLRA (Enclosure 3 Attachment l of Reference 1) denoted by NextEra Energy Point Beach, LLC 6610 Nuclear Road, Two Rivers, WI 54241

Document Control Desk L-2021-155 Page 2 strikethrough (deletion) and/or bold red underline (insertion) text. Previous SL.RA revisions are denoted by bold black text. SL.RA table revisions are included as excerpts from each affected table.

Should you have any questions regarding this submittal, please contact me at (561) 304-6256 or William.Maher@fpl.com.

I declare under penalty of perjury that the foregoing is uue and correct.

Executed on the 30 1h day of August 2021.

Sincerely, William D. Maher Licensing Director - Nuclear Licensing Projects Cc: Administrator, Region III, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC Public Service Commission Wisconsin

Document Control Desk L-2021 -155 Page 3 Attachment Index A ttachment RAINo. Subj ect No.

1 3.3.2.2.8-1 Aging Management Evaluation I tem Number 3.3-1, 233

Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NEPB Response to NRC RAI No. 3.3.2.2.8-1 L-2021-155 Attachment 1 Page 1of2

1. SLRA Section 3.3.2.2.8, "Cracking Due to Stress Corrosion Cracking in Aluminum Alloys" RAI 3.3.2.2.8-1 Regulatory Basis:

10 CFR 54.21 (a)(3) requires an applicant to demonstrate that the effects of aging for structures and components will be adequately managed so that the intended function(s) will be maintained consistent with the current licensing basis for the period of extended operation. One of the findings that the NRC staff must make to issue a renewed license (10 CFR 54.29(a)) is that actions have been identified and have been or will be taken with respect to managing the effects of aging during the period of extended operation on the functionality of structures and components that have been identified to require review under 10 CFR 54.21, such that there is reasonable assurance that the activities authorized by the renewed license will continue to be conducted in accordance with the current licensing basis. In order to complete its review and enable it to make a finding under 10 CFR 54.29(a), the staff requires additional information in regard to the matters described below.

Background:

During the review of SLRA Table 3.3-1, "Summary of Aging Management Evaluations for the Auxiliary Systems," the staff determined that Table 3.3-1 omits Item Number 3.3-1, 233 for cracking due to stress corrosion cracking for insulated aluminum piping, piping components, and tanks in air or condensation. Item Number 3.3-1, 233 requires further evaluation according to SLR-SRP Section 3.3.2 .2.8.

Issue:

Because Item Number 3.3-1, 233 was omitted from Table 3.3-1, the SLRA does not include a discussion of aging management for this item.

Request:

Please provide the SLRA Table 3.3-1 entry and disposition for Item Number 3.3-1, 233.

NEPB Response:

SLRA Table 3.3-1 has been revised to include entry and disposition of Item Number 3.3-1, 233.

References:

None.

Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NEPB Response to NRC RAI No. 3.3.2.2.8-1 L-2021-155 Attachment 1 Page 2 of 2 Associated SLRA Revisions:

SLRA Table 3.3-1 (page 3.3-74) is revised as follows:

Table 3.3-1: Summary of Aging Management Evaluations for the Auxiliary Systems Item Component Aging Effect/Mechanism Aging Management Further Evaluation Discussion Number Program Recommended (AMP)/TLAA 3.3-11 233 Insulated aluminum Cracking due to SCC AMP XI.M29 1 Yes {SRP-SLR Not aQQlicable.

QiQing 1 QiQing "Outdoor and Section 3.3.2.2.8} There are no insulated comQonents 1tanks Large AtmosQheric aluminum QiQing 1 exQosed to air1 Metallic Storage QiQing comQonents 1or condensation Tanks 1" AMP tanks exQosed to air1 Xl.M32 1 "One-Time condensation in the lnsQection 1" AMP Auxilia!Y Sllstems.

XI.M36 1 "External Surfaces Monitoring of Mechanical ComQonentsi" or AMP XI.M42 1 "Internal Coatings/Linings for ln-ScoQe PiQing 1PiQing ComQonents, Heat Exchangers 1and Tanks" Associated

Enclosures:

None.