ML17031A003

2017/01/30 NRR E-mail Capture - Verbal Authorization for Seabrook Relief Request RA-17-001

ML17031A003
Person / Time
Site:	Seabrook
Issue date:	01/30/2017
From:	Justin Poole Plant Licensing Branch 1
To:	Browne K J Nextera Energy
References
Download: ML17031A003 (4)

Text

1NRR-PMDAPEm ResourceFrom:Poole, JustinSent:Monday, January 30, 2017 4:25 PMTo:Browne, Kenneth

Subject:

Verbal Authorization for Seabrook Relief Request RA-17-001Attachments:Seabrook verbal authorization 1-30-2017.docxMr. Browne, In accordance with NRR Office Instruction LIC-102, "Relief Request Reviews," the NRR staff has provided verbal authorization for Seabrook Station, Unit 1 relief request RA-17-001 as described in your letter to the NRC dated January 27, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17028A010).

The script read this afternoon that provides verbal authorization is attached. The NRC staff intends to follow-up this verbal authorization with a written safety evaluation within approximately 150 days.

Please let me know if you have any questions. A copy of this email and attached verbal authorization will become publicly available in ADAMS.

Justin C. Poole Project Manager NRR/DORL/LPL I U.S. Nuclear Regulatory Commission (301)415-2048 Hearing Identifier: NRR_PMDA Email Number: 3301 Mail Envelope Properties (Justin.Poole@nrc.gov20170130162400)

Subject:

Verbal Authorization for Seabrook Relief Request RA-17-001 Sent Date: 1/30/2017 4:24:44 PM Received Date: 1/30/2017 4:24:00 PM From: Poole, Justin Created By: Justin.Poole@nrc.gov Recipients: "Browne, Kenneth" <Kenneth.J.Browne@nexteraenergy.com>

Tracking Status: None Post Office: Files Size Date & Time MESSAGE 808 1/30/2017 4:24:00 PM Seabrook verbal authorization 1-30-2017.docx 22150 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received:

1 VERBAL AUTHORIZATION BY THE OFFICE NUCLEAR REGULATION FOR RELIEF REQUEST RA-17-001 TEMPORARY REPAIR OF SERVICE WATER PIPING SEABROOK STATION UNIT 1 NEXTERA ENERGY SEABROOK LLC DOCKET NO. 50-443 JANUARY 30, 2017 Technical Evaluation read by David Alley, Chief of the Component Performance, Non-Destructive Examination, and Testing Branch, NRR By letter dated January 27, 2017, NextEra Energy Seabrook LLC (the licensee) requested relief from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, IWA-4412, at Seabrook Station Unit 1. Pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(2), the licensee submitted Relief Request RA-17-001 for a temporary repair of leaking service water piping on the basis that complying with the specified ASME Code requirement to repair the degraded piping would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.

The affected piping is on the discharge side of the 'A' train service water system piping. The through wall flaw is located at weld FW1818-F0602, which connects a 24-inch elbow to straight pipe downstream of check valve 1-SW-V-53. The licensee proposed to install a 6-inch encapsulation which consists of a weldolet, weld neck flange and blind flange, on the leaking flaw which was caused by seawater corrosion. The licensee demonstrated the structural integrity of the subject pipe in accordance with ASME Code Case N-513-3 "Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping,Section XI, Division 1." The licensee also demonstrated that considering the flaw growth rate, the 6-inch encapsulation will maintain the structural integrity of the pipe up to the end of the next refueling outage (OR18) in Spring 2017. In addition, the licensee will perform daily walkdowns and ultrasonic inspections of the affected area at a frequency of no more than 30 days. As a defense-in-depth measure, the licensee stated that the relief request would expire if the ongoing ultrasonic testing identify that the flaw progresses outside the encapsulated area to the point that the ASME Code minimum thickness of 0.105 inch is challenged. The NRC staff finds that the licensee has provided adequate hardship justification. The NRC staff finds that the proposed encapsulation has sufficient margin with respect to the predicted growth of the flaw at the end of next refueling outage in Spring 2017 and is designed to support all the loadings of the pipe. Therefore, the NRC finds that Relief Request RA-17-001 will provide reasonable assurance that the structural integrity of the subject service water piping and its intended safety function will be maintained up to the end of the next refueling outage (OR18) in Spring 2017.

Authorization read by Rick Ennis, Acting Chief of the Plant Licensing Branch I, NRR As Acting Chief of the Plant Licensing Branch I, Office of Nuclear Reactor Regulation, I agree with the conclusions of the Component Performance, Non-Destructive Examination, and Testing Branch.

2 The NRC staff concludes that the proposed alternative provides reasonable assurance of structural integrity of the subject service water piping. The NRC staff finds that complying with IWA-4412 of the ASME Code,Section XI, would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(2). Therefore, as of January 30, 2017, the NRC authorizes the use of Relief Request RA-17-001 at Seabrook Station Unit 1 until the end of the next refueling outage (OR18) in Spring 2017, or until the flaw progresses outside the encapsulated area such that the pipe wall thickness is below 0.105 inch, whichever occurs first. All other requirements in ASME Code,Section XI, for which relief was not specifically requested and approved in this relief request remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.

This verbal authorization does not preclude the NRC staff from asking additional clarification questions regarding the Relief Request while preparing subsequent written safety evaluation.