ML13149A376

Request for Additional Information Email Regarding Relief Request RBS-ISI-018

ML13149A376
Person / Time
Site:	River Bend
Issue date:	05/29/2013
From:	Wang A Plant Licensing Branch IV
To:	Burmeister B, Clark R Entergy Operations
Wang A
References
RBS-ISI-018, TAC ME9654
Download: ML13149A376 (1)

Text

From: Wang, Alan To: "BURMEISTER, BARRY M"; Joseph Clark (JCLARK@entergy.com)

Cc: Burkhardt, Janet; Lent, Susan

Subject:

River Bend Station, Unit 1, Request for Additional Information Regarding Relief Request RBS-ISI-018 (TAC No.

ME9654)

Date: Wednesday, May 29, 2013 2:21:56 PM Barry and Joey, by letter dated September 25, 2012, Entergy Operations, Inc. (the licensee) submitted Request for Relief RBS-ISI-018 for River Bend Station, Unit 1 (RBS),

pursuant to the provisions of Title 10 of the Code of Federal Regulations (10 CFR) Part 50.55a(g)(5)(iii). The US Nuclear Regulatory Commission (NRC) staff has determined that the following additional information is required to complete its review of the relief request.

This request was discussed with Mr. Barry Burmeister of your staff on May xx, 2013, and it was agreed that a response would be provided within 30 days from the issuance of this email. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1445 or via e-mail at Alan.Wang@nrc.gov.

RBS-ISI-018 states that the reactor vessel support skirt receives a VT-3 visual examination of the entire exterior portion, and as much of the interior portion as can be accessed through the access openings, without removal of the insulation package.

a) What is the estimated VT-3 visual examination coverage percentage for the inside of the RPV support skirt (10%, 20%, etc.)?

b) Please discuss whether any relevant indications (age-related degradation and/or fabrication flaws) have been discovered as a result of the limited-scope examination. If any relevant indications were found please discuss how the indications were dispositioned, in accordance with ASME Code,Section XI requirements.

c) Please discuss the difficulties involved with the removal of the insulation package for performing a full examination of the inside of the reactor vessel support skirt.

Alan Wang Project Manager (River Bend Station)

Nuclear Regulatory Commission Division of Operating Reactor Licensing