ML16293A727

NRR E-mail Capture - Verbal Authorization for Joseph M. Farley, Unit 1, October 14, 2016, Relief Request (NL-16-2204)

ML16293A727
Person / Time
Site:	Farley
Issue date:	10/19/2016
From:	Shawn Williams Plant Licensing Branch II
To:	Mcelroy G Southern Nuclear Operating Co
References
Download: ML16293A727 (4)

Text

NRR-PMDAPEm Resource From: Williams, Shawn Sent: Wednesday, October 19, 2016 11:41 AM To: 'gkmcelro@southernco.com' Cc: Coleman, Jamie Marquess; Markley, Michael; Alley, David; Tsao, John; Wheat, Justin Thomas

Subject:

Verbal Authorization for Joseph M. Farley, Unit 1, October 14, 2016, Relief Request (NL-16-2204)

Attachments: Farley, Unit 1, Oct. 14, 2016, RR verbal authorization .docx Mr. McElroy, By teleconference on October 19, 2016, the U.S. Nuclear Regulatory Commission (NRC) provided verbal authorization for the use of Relief Request (FNP-ISI-ALT-21) in application dated October 14, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16288A796). This Alternative will allow Farley Nuclear Plant (FNP), Unit 1, to use a mechanical clamp in accordance with the ASME Code,Section XI, Appendix IX, to temporary repair a leaking weld of the 1-inch drain line upstream of valve Q1G31V017 of the spent fuel pool cooling system and approves a delay the permanent Code repair or replacement of a 1-inch drain line leaking weld until prior to the start of the spring 2018 refueling outage (1 R28).

Attached is the Verbal Authorization provided during the October 19, 2016, conference call. NRC Staff will document a Safety Evaluation within 150 days as related to this Verbal Authorization.

If you have any questions, please contact me at (301) 415-1009.

Shawn Williams, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-348 1

Hearing Identifier: NRR_PMDA Email Number: 3110 Mail Envelope Properties (d563654cb2a848ba923b4199438f44a4)

Subject:

Verbal Authorization for Joseph M. Farley, Unit 1, October 14, 2016, Relief Request (NL-16-2204)

Sent Date: 10/19/2016 11:40:38 AM Received Date: 10/19/2016 11:40:39 AM From: Williams, Shawn Created By: Shawn.Williams@nrc.gov Recipients:

"Coleman, Jamie Marquess" <JAMIEMCO@SOUTHERNCO.COM>

Tracking Status: None "Markley, Michael" <Michael.Markley@nrc.gov>

Tracking Status: None "Alley, David" <David.Alley@nrc.gov>

Tracking Status: None "Tsao, John" <John.Tsao@nrc.gov>

Tracking Status: None "Wheat, Justin Thomas" <JTWHEAT@southernco.com>

Tracking Status: None

"'gkmcelro@southernco.com'" <gkmcelro@southernco.com>

Tracking Status: None Post Office: HQPWMSMRS03.nrc.gov Files Size Date & Time MESSAGE 1218 10/19/2016 11:40:39 AM Farley, Unit 1, Oct. 14, 2016, RR verbal authorization .docx 18931 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

VERBAL AUTHORIZATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION FOR ALTERNATIVE FNP-ISI-ALT-21, VERSION 1.0 ALTERNATE REPAIR OF DRAIN LINE OF SPENT FUEL POOL COOLING PIPING JOSEPH M. FARLEY NUCLEAR PLANT UNIT 1 SOUTHERN NUCLEAR OPERATING COMPANY DOCKET NUMBER 50-348 Technical Evaluation read by David Alley, Chief of the Component Performance, Non-Destructive Examination, and Testing Branch, Office of Nuclear Reactor Regulation By letter dated October 14, 2016, Southern Nuclear Operating Company (the licensee) requested relief from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Appendix IX, IX-1000(a) at Joseph M. Farley Nuclear Plant Unit 1. The licensee submitted for Nuclear Regulatory Commission (NRC) review and approval Alternative FNP-ISI-ALT-21, Version 1.0. This Alternative proposes to use a mechanical clamp in accordance with the ASME Code,Section XI, Appendix IX to temporary repair a leaking weld of the 1-inch drain line upstream of valve Q1G31V017 of the spent fuel pool cooling system. The licensee made this request in accordance with the requirements of 10 CFR 50.55a(z)(2), such that compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.

The NRC staff finds that the licensee will follow the requirements of the ASME Code,Section XI, Appendix IX in the design and installation of a mechanical clamp on the degraded socket weld on the subject drain line except article IX-1000(a). In addition, the licensee will monitor the repair at least once a day. The NRC staff finds that the proposed alternative is acceptable because the design of the proposed mechanical clamp satisfies the ASME Code,Section XI, Appendix IX, except article IX-1000(a).

The NRC staff finds the licensees hardship justification is acceptable because the spent fuel cooling piping is required to be functional during refueling outage and a Code repair during the current 1R27 refueling outage would present hardship and unusual difficulties.

The NRC staff finds that the licensee's proposed alternative provides reasonable assurance of structural integrity and leak tightness for the subject drain line, and that compliance with the ASME Code requirement would result in hardship without a compensating increase in the level of quality and safety.

Authorization read by Michael Markley, Chief of the Plant Licensing Branch II-1, Office of Nuclear Reactor Regulation As Chief of the Plant Licensing Branch II-1, Office of Nuclear Reactor Regulation, I concur with the Component Performance, Non-Destructive Examination, and Testing Branchs determinations.

The NRC staff finds that the proposed alternative provides reasonable assurance of structural integrity and leak tightness of the degraded drain line of the spent fuel cooling system piping. The NRC staff determines that complying with the ASME Code requirement 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, the NRC staff authorizes the use of Alternative FNP-ISI-ALT-21, Version 1.0 at Farley Nuclear Plant Unit 1 until prior to the commencement of the 1R28 refueling outage, currently scheduled in the spring of 2018.

All other requirements of ASME Code,Section XI, for which relief was not specifically requested and authorized by the NRC staff remain applicable, including the third party review by the Authorized Nuclear In-service Inspector.

This verbal authorization does not preclude the NRC staff from asking additional clarification questions regarding Alternative FNP-ISI-ALT-21, Version 1.0, while preparing the subsequent written safety evaluation.