RBG-47854, Supplement to Request for Alternative in Accordance with 10 CFR 50.55a (z)(1) Proposed Alternative to 10 CFR 50.55a Examination Requirements for Reactor Pressure Vessel Weld Inspections (RR-RBS-ISI-015)

Supplement to Request for Alternative in Accordance with 10 CFR 50.55a (z)(1) Proposed Alternative to 10 CFR 50.55a Examination Requirements for Reactor Pressure Vessel Weld Inspections (RR-RBS-ISI-015)

ML18106A068
Person / Time
Site:	River Bend
Issue date:	04/12/2018
From:	Schenk T Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RBG-47854, RR-RBS-ISI-015
Download: ML18106A068 (2)

Text

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Entergy Operations, Inc.

River Bend Station 5485 U.S. Highway 61N SI. Francisville, LA 70775 Tel 225-38 1-4 177 Timothy Schenk Regu latory Assurance Manager River Bend Station RBG-47854 April 12, 2018 Attn: Document Control Desk U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738

SUBJECT:

Supplement to Request for Alternative in Accordance with 10 CFR 50.55a (z)(1)

Proposed Alternative to 10 CFR 50.55a Examination Requirements for Reactor Pressure Vessel Weld Inspections (RR- RBS-ISI-015)

River Bend Station , Unit 1 Docket No. 50-458 License No. NPF-47

Dear Sir or Madam :

In accordance with 10 CFR 50.55a, "Codes and Standards," paragraph (z)(1), Entergy previously requested NRC approval of the proposed alternative to American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Sub Article IWB-2500 to allow reduced requirements for nozzle-to-vessel weld and inner radius examinations for River Bend Station (RBS).

Entergy originally submitted this request by RBS letter RBG-47825, dated February 13, 2018

[ADAMS Accession Number ML18045A028].

It has recently been determined that the title of the letter contained a typographical error and the Attachment 1 to the letter is missing a reference to ASME Code Case N-648-1 , Alternative Requirements for Inner Radius Examination of Class 1 Reactor Vessel Nozzles. This supplement is to clarify the following.

• The correct code referenced in the title is 10 CFR 50.55a (z)(1)

• Entergy has adopted ASME Code Case N-648-1 , Alternative Requirements for Inner Radius Examination of Class 1 Reactor Vessel Nozzles, with the provisions stipulated in Regulatory Guide 1.147, in the RBS Forth Interval lSI Program Plan . Entergy may therefore perform examinations on inner radius sections with either the VT -1 or the volumetric examination method.

The supplemental information provided does not change the scope of the original submittal.

Entergy requests approval of this request by November 30, 2018, in order to support refueling outage twenty (RF-20) scheduled for January 2019.

RBG-47854 Page 2 of 2 There are no regulatory commitments contained in this submittal. If you require additional information , please contact Mr. Tim Schenk at (225) -381 -4177 or tschenk@entergy.com.

TAS/alc cc : U. S. Nuclear Regulatory Commission Attn : Lisa Regner 11555 Rockville Pike Rockville , MD 20852 U.S. Nuclear Regulatory Commission Region IV 1600 East Lamar Blvd.

Arlington , TX 76011 -4511 NRC Resident Inspector PO Box 1050 St. Francisville, LA 70775 Central Records Clerk Public Utility Commission of Texas 1701 N. Congress Ave.

Austin , TX 78711 -3326 Department of Environmental Quality Office of Environmental Compliance Radiological Emergency Planning and Response Section Ji Young Wiley P.O. Box 4312 Baton Rouge , LA 70821 -4312 RBF1-18-0080 LAR-2018-02