ML14258A020

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NRR E-mail Capture - Request for Additional Information - ANO1-ISI-024 (MF4022)
ML14258A020
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 09/12/2014
From: Andrea George
Plant Licensing Branch IV
To: Clark R
Entergy Nuclear Operations
References
TAC MF4022
Download: ML14258A020 (3)


Text

NRR-PMDAPEm Resource From: George, Andrea Sent: Friday, September 12, 2014 2:46 PM To: CLARK, ROBERT W Cc: Singal, Balwant

Subject:

Request for Additional Information - ANO1-ISI-024 (MF4022)

Attachments: MF4022 formal RAIs.pdf Mr. Clark, By letter dated April 28, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML14118A477), Entergy Nuclear Operations, Inc. (the licensee) requested relief from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, associated with the examination frequency requirements of Code Case N-729-1 at Arkansas Nuclear One (ANO), Unit 1. The licensee proposed an alternative examination requirement for the Reactor Vessel Top Head Penetration Nozzles as documented in Relief Request ANO1-ISI-024.

The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the submittal and requests additional information (RAI) as detailed in the attachment. This email constitutes formal transmittal of the RAIs. Draft RAIs were transmitted on September 3, 2014. The NRC Project Manager was notified that a clarification call is not needed and it was agreed that Entergy will respond to these RAIs within 30 days, which is October 12, 2014.

If circumstances result in the need to revise the agreed-upon response date, please contact me at (301) 415-1081 or via email at andrea.george@nrc.gov.

Thank you, Andrea George Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 301-415-1081 1

Hearing Identifier: NRR_PMDA Email Number: 1568 Mail Envelope Properties (6F9E3C9DCAB9E448AAA49B8772A448C501CDC548FF88)

Subject:

Request for Additional Information - ANO1-ISI-024 (MF4022)

Sent Date: 9/12/2014 2:46:22 PM Received Date: 9/12/2014 2:46:00 PM From: George, Andrea Created By: Andrea.George@nrc.gov Recipients:

"Singal, Balwant" <Balwant.Singal@nrc.gov>

Tracking Status: None "CLARK, ROBERT W" <RCLARK@entergy.com>

Tracking Status: None Post Office: HQCLSTR01.nrc.gov Files Size Date & Time MESSAGE 1409 9/12/2014 2:46:00 PM MF4022 formal RAIs.pdf 38387 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

REQUEST FOR ADDITIONAL INFORMATION REQUEST ANO1-ISI-024 INSPECTION OF REACTOR VESSEL CLOSURE HEAD NOZZLES IN ACCORDANCE WITH ASME CODE CASE N-729-1 AS CONDITIONED BY 10 CFR 50.55a ARKANSAS NUCLEAR ONE, UNIT 1 ENTERGY NUCLEAR OPERATIONS, INC.

DOCKET NUMBER 50-313 By letter dated April 28, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML14118A477), Entergy Nuclear Operations, Inc. (the licensee) requested relief from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, associated with the examination frequency requirements of Code Case N-729-1 at Arkansas Nuclear One (ANO), Unit 1. The licensee proposed an alternative examination requirement for the Reactor Vessel Top Head Penetration Nozzles as documented in Relief Request ANO1-ISI-024. To complete its review, the Nuclear Regulatory Commission staff requests the following additional information.

1) The licensee uses MRP-375, Technical Basis for Reexamination Interval Extension for Alloy 690 PWR Reactor Vessel Top Head Penetration Nozzles, to provide a technical basis for the proposed alternative. In regards to MRP-375, Figures 3-1, 3-3 and 3-5, provide a brief description of the materials tested for each plot that have data points above a hypothetical 7.7 factor of improvement line necessary to support the licensees proposed alternative.
2) Provide any similarities between the items listed in (1) above and the associated nozzles and weld material used in the current reactor pressure vessel upper head at ANO Unit 1.