L-2023-073, Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response

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Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response
ML23153A097
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 06/01/2023
From: Strand D
Point Beach
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
L-2023-073
Download: ML23153A097 (1)
v • d • e


Text

NextEra Energy Point Beach, LLC 6610 Nuclear Road, Two Rivers, WI 54241 June 01, 2023 L-2023-073 10 CFR 54.17 U.S. Nuclear Regulatory Commission Attention: Document Control Desk 11545 Rockville Pike One White Flint North Rockville, MD 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 - SECOND ANNUAL UPDATE REQUEST FOR ADDITIONAL INFORMATION (RAI) SET 1 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. NextEra Energy Point Beach, LLC (NEPB) Letter L-2021-224 dated November 30, 2021, Subsequent License Renewal Application - First Annual Update (ADAMS Package Accession No. ML21334A293)
3. NextEra Energy Point Beach, LLC (NEPB) Letter L-2022-177 dated November 28, 2022, Subsequent License Renewal Application - Second Annual Update (ADAMS Package Accession No. ML22332A491
4. NRC Email to R Coffey and attached final request for additional information (RAI) dated May 5, 2023, Point Beach SLRA Second Annual Update - Request for Additional Information Set #1 (ADAMS Accession Nos. ML23136A278 and ML23136A280)

NEPB, 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),

the first annual update (Reference 2), and the second annual update (Reference 3). On May 5, 2023, the NRC issued its Set 1 RAI to NEPB (Reference 4). Attachment 1 to this letter provides the response to this follow-up information request. The information in Attachments 2 and 3 of this letter supersede in its entirety the attachments in Reference 3.

For ease of reference, the index of attached information is provided on page 3 of this letter. Attachment 3 includes associated revisions to the SLRA (Enclosure 3 Attachment 1 of Reference 1) denoted by strikethrough (deletion) and/or bold red underline (insertion) text. Previous SLRA revisions are denoted by bold black text. SLRA table revisions are included as excerpts from each affected table.

Document Control Desk L-2023-073 Page 3

Attachments Index Attachment No.

RAI No.

Subject 1

3.2.2.2.2-1 Application Section 3.2.2.2.2 and 3.2.2.2.4 2

Current Licensing Basis (CLB) Changes Affecting the SLRA 3

Affected SLRA Content Revisions

Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NEPB Response to NRC RAI No. 3.2.2.2.2-1 L-2023-073 Attachment 1 Page 1 of 2

RAI 3.2.2.2.2-1 Application Section 3.2.2.2.2 and 3.2.2.2.4 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 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 making a finding under 10 CFR 54.29(a), the staff requires additional information in regard to the matters described below.

Background

In the Second Annual Update (2022) of the Point Beach Subsequent License Renewal Application (ML22332A491), Change 2 added eight AMR items to SLRA Table 3.2.2-2, Containment Spray - Summary of Aging Management Evaluation. Four of the new items are related to loss of material and four are related to stress corrosion cracking, corresponding to Further Evaluation Sections 3.2.2.2.2 and 3.2.2.2.4, respectively. All of the items are for stainless steel or stainless steel cladding in an environment of Air - indoor uncontrolled (int), all specify the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Aging Management Program (AMP), and all use Note A regarding consistency with NUREG-2191. The two items for the spray additive tank refer to NUREG-2191 Items V.A.EP-81d for loss of material and V.A.EP-103e for cracking. The other six items added to the table refer to NUREG-2191 items V.A.EP-81c (loss of material) or V.A.EP-103d (cracking).

Table 3.2.2-2: Containment Spray - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Re-quiring Manage-ment Aging Management Program NUREG-2191 Item Table 1

Item Notes Piping Pressure boundary Stainless steel Air - indoor un-controlled (int)

Cracking Inspection of Internal Surfaces in Miscellane-ous Piping and Ducting Components (B.2.3.25)

V.A.EP-103d 3.2-1, 007 A

Piping Pressure boundary Stainless steel Air - indoor un-controlled (int)

Loss of material Inspection of Internal Surfaces in Miscellane-ous Piping and Ducting Components (B.2.3.25)

V.A.EP-81c 3.2-1, 048 A

Tank (spray addi-tive)

Pressure boundary Carbon steel with stainless steel cladding Air - indoor un-controlled (int)

Cracking Inspection of Internal Surfaces in Miscellane-ous Piping and Ducting Components (B.2.3.25)

V.A.EP-103e 3.2-1, 007 A

Tank (spray addi-tive)

Pressure boundary Carbon steel with stainless steel cladding Air - indoor un-controlled (int)

Loss of material Inspection of Internal Surfaces in Miscellane-ous Piping and Ducting Components (B.2.3.25)

V.A.EP-81d 3.2-1, 048 A

Valve body Pressure boundary CASS Air - indoor un-controlled (int)

Cracking Inspection of Internal Surfaces in Miscellane-ous Piping and Ducting Components (B.2.3.25)

V.A.EP-103d 3.2-1, 007 A

Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NEPB Response to NRC RAI No. 3.2.2.2.2-1 L-2023-073 Attachment 1 Page 2 of 2

Table 3.2.2-2: Containment Spray - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Re-quiring Manage-ment Aging Management Program NUREG-2191 Item Table 1

Item Notes Valve body Pressure boundary CASS Air - indoor un-controlled (int)

Loss of material Inspection of Internal Surfaces in Miscellane-ous Piping and Ducting Components (B.2.3.25)

V.A.EP-81c 3.2-1, 048 A

Valve body Pressure boundary Stainless steel Air - indoor un-controlled (int)

Cracking Inspection of Internal Surfaces in Miscellane-ous Piping and Ducting Components (B.2.3.25)

V.A.EP-103d 3.2-1, 007 A

Valve body Pressure boundary Stainless steel Air - indoor un-controlled (int)

Loss of material Inspection of Internal Surfaces in Miscellane-ous Piping and Ducting Components (B.2.3.25)

V.A.EP-81c 3.2-1, 048 A

Issue The two items added to SLRA Table 3.2.2-2 for the spray additive tank refer to NUREG-2191 Items V.A.EP-81d and V.A.EP-103e. In NUREG-2191, the corresponding AMP for V.A.EP-81d and V.A.EP-103e is XI.M42, Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks. SLRA Table 3.2.2-2 lists the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components for these items and is therefore not consistent with the AMP used in the referenced NUREG-2191 items. As a result, the Note A indicating consistency with NUREG-2191 is incorrect.

NRC Request Please clarify the aging management program for the loss of material and cracking entries added to SLRA Table 3.2.2-2 for the spray additive tank exposed to indoor uncontrolled air and describe how the table will be revised to accurately reflect consistency with NUREG-2191.

NEPB Response:

The aging management program for the loss of material and cracking entries added to SLRA Table 3.2.2-2 for the spray additive tank is Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B.2.3.25). Table 3.2.2-2 incorrectly referred to NUREG 2191 Items V.A.EP-81d and V.A.EP-103e for carbon steel tanks with stainless steel cladding exposed to air - indoor uncontrolled (int). The correct NUREG-2191 Items are V.A.EP-81c (loss of material) and V.A.EP-103d (cracking), respectively.

Accordingly, Table 3.2.2-2 is revised to correct the NUREG-2191 Items for the spray additive tank exposed to indoor uncontrolled air.

Attachments 2 and 3 of this letter supersede Attachments 1 and 2 of L-2022-177 [Ref. 1], in their entirety.

References:

1. NextEra Energy Point Beach, LLC (NEPB) Letter L-2022-177 dated November 28, 2022, Subsequent License Renewal Application - Second Annual Update (ADAMS Package Accession No. ML22332A491

Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 CLB Changes Affecting the SLRA L-2023-073 Attachment 2 Page 1 of 1



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