ML21312A038

NRR E-mail Capture - ANO-2 RAI Relief Request ANO2-RR-21-002

ML21312A038
Person / Time
Site:	Arkansas Nuclear
Issue date:	11/05/2021
From:	Thomas Wengert NRC/NRR/DORL/LPL4
To:	Keele R Entergy Operations
Wengert T
References
L-2021-LLR-0084
Download: ML21312A038 (4)

Text

From: Wengert, Thomas Sent: Friday, November 5, 2021 9:08 PM To: Keele Jr, Riley D Cc: Clark, Robert; Dixon-Herrity, Jennifer

Subject:

RE: ANO-2 Draft RAI RE: Relief Request ANO2-RR-21-002 (EPD L-2021-LLR-0084)

Attachments: ANO Final RAI Regarding RR ANO2-RR-21-002.pdf On November 5, 2021, the U.S. Nuclear Regulatory Commission (NRC) staff sent Entergy Operations, Inc. the draft Request for Additional Information (RAI) identified below. This RAI relates to the November 5, 2021, relief request concerning the request to allow the conduct of half-nozzle repair of reactor vessel closure head (RVCH) Nozzle #46 at Arkansas Nuclear One, Unit 2).

A conference call was held on November 5, 2021 to clarify this request. A publicly available version of this final RAI (attached with Draft removed) will be placed in the NRCs Agencywide Documents Access and Management System (ADAMS).

From: Wengert, Thomas Sent: Friday, November 05, 2021 6:13 PM To: Keele Jr, Riley D <rkeele@entergy.com>

Cc: Clark, Robert <RCLARK@entergy.com>; Dixon-Herrity, Jennifer <Jennifer.Dixon-Herrity@nrc.gov>;

Mitchell, Matthew <Matthew.Mitchell@nrc.gov>; Collins, Jay <Jay.Collins@nrc.gov>; Min, Seung

<Seung.Min@nrc.gov>

Subject:

ANO-2 Draft RAI RE: Relief Request ANO2-RR-21-002 (EPD L-2021-LLR-0084)

By letter dated November 5, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21309A007), Entergy Operations, Inc. (the licensee) requested approval to allow the conduct of half-nozzle repair of reactor vessel closure head (RVCH)

Nozzle #46 at Arkansas Nuclear One, Unit 2 (ANO-2). The proposed alternative is requested in accordance with Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55(z)(1),

based on the licensees determination that the alternative provides the acceptable level of quality and safety.

The U.S. Nuclear Regulatory Commission (NRC) staff has determined that additional information, as described in the attached request for additional information (RAI), is required for the staff to complete its review of this application. This RAI is identified as draft at this time to confirm your understanding of the information that the NRC staff needs to complete the evaluation.

Please contact me if you would like to set up a conference call with the NRC staff to clarify this request for information.

Tom Wengert Project Manager - Arkansas Nuclear One NRR/DORL/LPL4 (301) 415-4037

Hearing Identifier: NRR_DRMA Email Number: 1415 Mail Envelope Properties (MN2PR09MB544923DF492383676D4927098F8F9)

Subject:

RE: ANO-2 Draft RAI RE: Relief Request ANO2-RR-21-002 (EPD L-2021-LLR-0084)

Sent Date: 11/5/2021 9:07:46 PM Received Date: 11/5/2021 9:07:00 PM From: Wengert, Thomas Created By: Thomas.Wengert@nrc.gov Recipients:

"Clark, Robert" <RCLARK@entergy.com>

Tracking Status: None "Dixon-Herrity, Jennifer" <Jennifer.Dixon-Herrity@nrc.gov>

Tracking Status: None "Keele Jr, Riley D" <rkeele@entergy.com>

Tracking Status: None Post Office: MN2PR09MB5449.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 2196 11/5/2021 9:07:00 PM ANO Final RAI Regarding RR ANO2-RR-21-002.pdf 139315 Options Priority: Normal Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

REQUEST FOR ADDITIONAL INFORMATION PROPOSED ALTERNATIVE TO ASME SECTION XI REQUIREMENTS FOR HALF-NOZZLE REPAIR OF REACTOR VESSEL CLOSURE HEAD PENETRATION NO. 46 ARKANSAS NUCLEAR ONE, UNIT 2 ENTERGY OPERATIONS, INC.

DOCKET NO. 50-368 By letter dated November 5, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21309A007), Entergy Operations, Inc. (the licensee) requested approval to allow the conduct of half-nozzle repair of reactor vessel closure head (RVCH)

Nozzle #46 at Arkansas Nuclear One, Unit 2 (ANO-2). The proposed alternative is requested in accordance with Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55(z)(1) based on the licensees determination that the alternative provides the acceptable level of quality and safety. To complete its review, the U.S. Nuclear Regulatory Commission (NRC or the Commission) staff requests supplemental information as follows.

Regulatory Basis The inservice inspection (ISI) of the American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME) Code,Section XI, Class 1, 2 and 3 components shall be performed in accordance with the requirements of Section XI, Rules for In-service Inspection of Nuclear Power Plant Components, of the ASME Code and applicable editions and addenda as required by 10 CFR 50.55a(g), except where specific written relief has been granted or proposed alternative authorized by the Commission. In order to assess the licensees proposed alternative, the NRC staff requires the following additional information to complete its review.

Request for Additional Information (RAI)

RAI-1

The NRC staff notes that the volumetric inspection area above the weld, for both the Post-Weld UT and Inservice Inspection UT, is not consistent with the area defined by Figure 2 of ASME Code Case N-729-6, Alternative Examination Requirements for PWR [Pressurized Water Reactor] Reactor Vessel Upper Heads with Nozzles Having Pressure-Retaining Partial-Penetration Welds. The dimension a, defining examination above the weld, is based on the incident angle of the weld. The new reactor coolant pressure boundary weld has an incident angle of 0 degrees and therefore, the a dimension should be 1.5-inch.

Provide additional basis for the licensees proposed Post-Weld UT and Inservice Inspection UT areas defined by Figures 3 and 9 to address the deviation from Figure 2 of ASME Code Case N-729-6.

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