L-2023-073, Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response
| ML23153A097 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| 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) | |
Text
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.
NextEra Energy Point Beach, LLC
6610 Nuclear Road, Two Rivers, WI 54241
Document Control Desk L-2023-073 Page 3
Attachments Index Attachment RAI No. Subject No.
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 th e 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 e xtended 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 comple te its review and enable making a finding under 10 CFR 54.29(a), the staff requires additional in formation in regard to the matters described below.
Background
In the Second Annual Update (2022) of the Point Beach Subsequen t License Renewal Application (ML22332A491), Change 2 added eight AMR items to SL RA Table 3.2.2-2, Containment Spray - Summary of Aging Management Evaluation. F our of the new items are related to loss of material and four are related to stress corr osion cracking, corresponding to Further Evaluation Sections 3.2.2.2.2 and 3.2.2.2.4, respective ly. 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 consiste ncy 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 Material Environment Aging Effect Re-Aging Management NUREG-2191 Table Notes Function quiring Manage-Program Item 1 ment Item Piping Pressure Stainless Air - indoor un-Cracking Inspection of Internal V.A.EP-103d 3.2-1, A boundary steel controlled (int) Surfaces in Miscellane- 007 ous Piping and Ducting Components (B.2.3.25)
Piping Pressure Stainless Air - indoor un-Loss of material Inspection of Internal V.A.EP-81c 3.2-1, A boundary steel controlled (int) Surfaces in Miscellane- 048 ous Piping and Ducting Components (B.2.3.25)
Tank (spray addi-Pressure Carbon steel Air - indoor un-Cracking Inspection of Internal V.A.EP-103e 3.2-1, A tive) boundary with stainless controlled (int) Surfaces in Miscellane- 007 steel cladding ous Piping and Ducting Components (B.2.3.25)
Tank (spray addi-Pressure Carbon steel Air - indoor un-Loss of material Inspection of Internal V.A.EP-81d 3.2-1, A tive) boundary with stainless controlled (int) Surfaces in Miscellane- 048 steel cladding ous Piping and Ducting Components (B.2.3.25)
Valve body Pressure CASS Air - indoor un-Cracking Inspection of Internal V.A.EP-103d 3.2-1, A boundary controlled (int) Surfaces in Miscellane- 007 ous Piping and Ducting Components (B.2.3.25)
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 Material Environment Aging Effect Re-Aging Management NUREG-2191 Table Notes Function quiring Manage-Program Item 1 ment Item Valve body Pressure CASS Air - indoor un-Loss of material Inspection of Internal V.A.EP-81c 3.2-1, A boundary controlled (int) Surfaces in Miscellane- 048 ous Piping and Ducting Components (B.2.3.25)
Valve body Pressure Stainless Air - indoor un-Cracking Inspection of Internal V.A.EP-103d 3.2-1, A boundary steel controlled (int) Surfaces in Miscellane- 007 ous Piping and Ducting Components (B.2.3.25)
Valve body Pressure Stainless Air - indoor un-Loss of material Inspection of Internal V.A.EP-81c 3.2-1, A boundary steel controlled (int) Surfaces in Miscellane- 048 ous Piping and Ducting Components (B.2.3.25)
Issue The two items added to SLRA Table 3.2.2-2 for the spray additiv e 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-Sc ope 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 an d is therefore not consistent with the AMP used in the referenced NUREG-2191 items. As a resu lt, the Note A indicating consistency with NUREG-2191 is incorrect.
NRC Request Please clarify the aging management program for the loss of mat erial and cracking entries added to SLRA Table 3.2.2-2 for the spray additive tank exposed to in door 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 Int ernal Surfaces in Miscellaneous Piping and Ducting Components (B.2.3.25). Table 3.2.2-2 incorr ectly referred to NUREG 2191 Items V.A.EP-81d and V.A.EP-103e for carbon steel tanks with st ainless steel cladding exposed to air - indoor uncontrolled (int). The correct NUREG-2191 Item s are V.A.EP-81c (loss of material) and V.A.EP-103d (cracking), respectively.
Accordingly, Table 3.2.2-2 is r evised 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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