ML23122A034

NRR E-mail Capture - Beaver Valley - Request for Additional Information Regarding Unit 1 - 180 Day Steam Generator Tube Inspection Report

ML23122A034
Person / Time
Site:	Beaver Valley
Issue date:	05/02/2023
From:	Sujata Goetz NRC/NRR/DORL/LPL1
To:	Lashley P Energy Harbor Nuclear Corp
References
Download: ML23122A034 (5)

Text

From: Sujata Goetz Sent: Tuesday, May 2, 2023 8:30 AM To: Lashley, Phil H Cc: Beck, Andrew

Subject:

Beaver Valley - Request for Additional Information Regarding Unit 1 - 180 Day Steam Generator Tube Inspection Report Attachments: RAI attachment.docx

Dear Mr. Lashley,

By letter dated March 27, 2023 (ML23087A063), Energy Harbor Nuclear Corp. submitted information summarizing the results of the Fall 2022 steam generator (SG) inspections performed at Beaver Valley Power Station, Unit 1. The inspections were performed during refueling outage 28 (1R28). Technical Specification (TS) Section 5.6.6.1 requires that a report be submitted within 180 days after the initial entry into hot shutdown (MODE 4) following completion of an inspection of the SGs performed in accordance with TS Section 5.5.5.1, which requires that a SG Program be established and implemented to ensure SG tube integrity is maintained.

The Nuclear Regulatory Commission staff has reviewed your submittal and has determined that additional information, as stated in the attachment to this email, is needed to complete its review.

The staff requests that you provide a response to this RAI by June 17, 2023. If you have any questions, please let me know.

Sincerely,

Sujata Goetz Project Manager, Calvert Cliffs

Nuclear Regulatory Commission 11555 Rockville Pike Office of the Nuclear Reactor Regulation NRC/NRR/DORL/LPL1 Office O8F2 Mailroom O8-B1A Rockville, MD 20852-2738 Washington, DC 20555-0001

(o) 301.415.8004 (f) 301.415.3313

Hearing Identifier: NRR_DRMA Email Number: 2066

Mail Envelope Properties (MN2PR09MB5467AA04464AB27ECD35AC24806F9)

Subject:

Beaver Valley - Request for Additional Information Regarding Unit 1 - 180 Day Steam Generator Tube Inspection Report Sent Date: 5/2/2023 8:29:35 AM Received Date: 5/2/2023 8:29:00 AM From: Sujata Goetz

Created By: Sujata.Goetz@nrc.gov

Recipients:

"Beck, Andrew" <abeck@energyharbor.com>

Tracking Status: None "Lashley, Phil H" <phlashley@energyharbor.com>

Tracking Status: None

Post Office: MN2PR09MB5467.namprd09.prod.outlook.com

Files Size Date & Time MESSAGE 1272 5/2/2023 8:29:00 AM RAI attachment.docx 26230 image003.png 455

Options Priority: Normal Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

BEAVER VALLEY POWER STATION, UNIT 1

REQUEST FOR ADDITIONAL INFORMATION

FALL 2022 STEAM GENERATOR TUBE INSPECTION REPORT

DOCKET NO. 50-334

By letter dated March 27, 2023 (ML23087A063), Energy Harbor Nuclear Corp. submitted information summarizing the results of the Fall 2022 steam generator (SG) inspections performed at Beaver Valley Power Station, Unit 1. The inspections were performed during refueling outage 28 (1R28). Technical Specification (TS) Section 5.6.6.1 requires that a report be submitted within 180 days after the initial entry into hot shutdown (MODE 4) following completion of an inspection of the SGs performed in accordance with TS Section 5.5.5.1, which requires that a SG Program be established and implemented to ensure SG tube integrity is maintained.

To complete its review of the inspection, the U.S. Nuclear Regulatory Commission (NRC) staff requests the following additional information:

1. The report section describing channel head bowl visual inspections states that during the 1R24 visual channel head inspection, an anomaly was observed on the divider plate to channel head weld in the hot leg of SG A. In addition, the report states the anomaly was re-inspected during 1R28 and that there was no change in the anomaly from 1R21 to 1R28.

The report also states that an evaluation of the anomaly was previously performed and concluded that it is an artifact of manufacturing, not representative of a crack-like condition created by the operating environment or a fabrication flaw. The NRC staff review of the 1R21 and 1R24 steam generator tube inspection reports did not find mention of an anomaly in the visual inspection results discussion.

a. Provide greater detail about the anomaly appearance and the evaluation that concluded that it is an artifact of manufacturing rather than a crack-like condition.

b. Clarify if this anomaly was visually observed during the 1R21 channel head bowl visual inspections. If it was not, please explain the apparent typographical error in the statement that there was no change from 1R21 to 1R28.

ENCLOSURE