ML13330B639

Verbal Authorization of Relief Request 13R-13 for Reactor Vessel Closure Head Penetration Nozzle Repair Inservice Inspection Program - Third 10-Year Interval

ML13330B639
Person / Time
Site:	Harris
Issue date:	11/27/2013
From:	Andrew Hon Plant Licensing Branch II
To:	Jessie Quichocho Plant Licensing Branch II
Hon A
References
TAC MF3104
Download: ML13330B639 (3)

Text

November 27, 2013 MEMORANDUM TO: Jessie F. Quichocho, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Andrew Hon, Project Manager /RA/

Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

SUBJECT:

SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 - VERBAL AUTHORIZATION OF RELIEF REQUEST I3R-13 FOR REACTOR VESSEL CLOSURE HEAD PENETRATION NOZZLE REPAIR INSERVICE INSPECTION PROGRAM - THIRD 10-YEAR INTERVAL (TAC NO. MF3104)

By letter dated November 22, 2013 (Agencywide Documents Access and Management System Accession No. ML13329A354) as supplemented by letter dated November 25, 2013 (Accession Nos. ML13330A749 and ML13330A996), Duke Energy Progress, Inc. (the licensee) submitted Relief Request I3R-13, Reactor Vessel Closure Head Nozzle Repair Inservice Inspection Program - Third 10-year Interval for Shearon Harris Nuclear Power Plant, Unit 1. Pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a, the licensee requested the U.S. Nuclear Regulatory Commission (NRC) approval of an alternative for the repair examination requirements of the American Society of Mechanical Engineers (ASME) Code associated with a reactor vessel closure head nozzle penetration.

The licensee proposed to use the alternatives in ASME Code,Section XI, Code Case N-638-1, and Code Case N-729-1 to complete the repair procedures and nondestructive evaluation examinations.

The NRC staff reviewed the licensees submittal and determined that the proposed alternative will provide an acceptable level of quality and safety. During a conference call with the licensee on November 26, 2013, the NRC staff granted a verbal authorization on the use of Relief Request I3R-13 in accordance with 10 CFR 50.55a(a)(3)(i). The script for the verbal authorization is enclosed.

NRC

Participants:

Licensee

Participants:

J. Quichocho T. Lupold E. Kapopoulos S. Cahill J. Tsao S. Vitto K. Riley J. Terrell P. Lessard J. Dion F. Dean S. Volk A. Hon J. Caves Docket No. 50-400

Enclosure:

Verbal Authorization Script

ML13330B639 OFFICE LPL2-2/PM LPL2-2/LA LPL2-2/BC LPL2-2/PM NAME AHon BClayton JQuichocho AHon DATE 11/26/13 11/26/13 11/27/13 11/27/13

VERBAL AUTHORIZATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION FOR RELIEF REQUEST I3R-13 ALTERNATE REPAIR OF REACTOR VESSEL CLOSURE HEAD PENETRATION NOZZLE NUMBER 37 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 Docket No. 50-400 The following script was read by Timothy Lupold, Chief of the Component Performance, Non Destructive Examination, and Testing Branch on November 26, 2013, to the staff of Duke Energy Progress, Inc., coordinated by Andrew Hon from the U.S. Nuclear Regulatory Commission By letter to the U.S. Nuclear Regulatory Commission (NRC) dated November 22, 2013, as supplemented by letter dated November 25, 2013, Duke Energy Progress, Inc. (the licensee) submitted Relief Request I3R-13 for the repair of the degraded reactor vessel closure head penetration nozzle No. 37 for the Shearon Harris Nuclear Power Plant, Unit 1 (Harris). In RR I3R-13, the licensee proposed to use the inside diameter temper bead welding method to repair the degraded nozzle No. 37 utilizing American Society of Mechanical Engineers (ASME) Code Cases N-638-1 and N-729-1 in lieu of the requirements of ASME, Sections III and XI, and the original Construction Code.

On the basis of information submitted, the NRC staff has determined that the proposed repair will restore the pressure boundary and provide reasonable assurance that the structural integrity of the repaired reactor vessel closure head penetration nozzle No. 37 will be maintained for a period of time that exceeds the inspection interval mandated by ASME Code Case N-729-1 with conditions set forth in Section 50.55a(g)(6)(ii)(D) of the Code of Federal Regulations (10 CFR).

The NRC staff finds that the proposed alternative provides an acceptable 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(a)(3)(i).

The following script was by Jessie F. Quichocho, Chief of the Plant Licensing Branch II-2, during the same conference call with Duke Energy Progress, Inc.

As Chief of the Plant Licensing Branch II-2, Office of Nuclear Reactor Regulation, I concur with the Component Performance, Non-Destructive Examination, and Testing Branchs conclusions.

Effective November 26, 2013, the NRC staff authorizes the proposed alternative at Harris for the reactor vessel head penetration repair described in Relief Request I3R-13 for the third 10-year Inservice inspection interval that will end on May 1, 2017, for Shearon Harris Nuclear Power Plant Unit 1. The NRC staff also authorizes the inspection provision of Relief Request I3R-13 in accordance with the requirements of ASME Code Case N-729-1 with conditions set forth in 10 CFR 50.55a(g)(6)(ii)(D).

All other requirements of ASME Code,Section XI, and 10 CFR 50.55a(g)(6)(ii)(D) 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 RR I3R-13 while preparing the subsequent written safety evaluation. The NRC staffs goal is to issue the written safety evaluation within 150 days in accordance with the Office of Nuclear Reactor Regulation standards.

Enclosure