ML13186A019

NRR E-mail Capture - Point Beach Nuclear Plant, Unit 2 - Draft Request for Additional Information (Epnb) Regarding Relief Request RR-4L2

ML13186A019
Person / Time
Site:	Point Beach
Issue date:	07/03/2013
From:	Beltz T Plant Licensing Branch III
To:	Millen M Point Beach
References
Download: ML13186A019 (3)

Text

NRR-PMDAPEm Resource From: Beltz, Terry Sent: Wednesday, July 03, 2013 1:15 PM To: Millen, Michael Cc: 'harv.hanneman@nexteraenergy.com'; Clark, Roger; Cumblidge, Stephen; Carlson, Robert

Subject:

Point Beach Nuclear Plant, Unit 2 - Draft Request for Additional Information (EPNB)

Regarding Relief Request RR-4L2 (TAC No. MF1146)

Attachments: Point Beach Nuclear Plant, Unit 2 - Draft Request for Additional Information (EPNB)

Regarding Relief Request RR-4L2 (TAC No. MF1146).docx

Dear Mr. Millen:

By letter to the U.S. Nuclear Regulatory Commission (NRC) dated March 19, 2013 (Agencywide Documents Access and Management System Accession No. ML13079A141), NextEra Energy Point Beach, LLC submitted relief request RR-4L2 covering a steam generator nozzle inner radius examination from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components for Point Beach Nuclear Power Plant, Unit

2. The request applies to the fourth 10-year inservice inspection interval, in which the licensee adopted the 1998 Edition through the 2000 Addenda of ASME Code Section XI as the code of record.

The NRC staff in the Piping & NDE Branch (EPNB) of the Office of Nuclear Reactor Regulatory has identified areas where additional information is needed to complete its review. The draft request for additional information (RAI) is provided as an attachment to this e-mail.

You may accept the draft RAI as a formal Request for Additional Information and provide a response by August 9, 2013. Alternatively, you may request to discuss the contents of this draft RAI with the NRC staff in a conference call, including any change to the proposed response date.

Please let me know if you have any questions or concerns.

Sincerely, TERRY A. BELTZ, SENIOR PROJECT MANAGER U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Mail Stop: O-8D15 1

Hearing Identifier: NRR_PMDA Email Number: 743 Mail Envelope Properties (Terry.Beltz@nrc.gov20130703131400)

Subject:

Point Beach Nuclear Plant, Unit 2 - Draft Request for Additional Information (EPNB) Regarding Relief Request RR-4L2 (TAC No. MF1146)

Sent Date: 7/3/2013 1:14:45 PM Received Date: 7/3/2013 1:14:00 PM From: Beltz, Terry Created By: Terry.Beltz@nrc.gov Recipients:

"'harv.hanneman@nexteraenergy.com'" <harv.hanneman@nexteraenergy.com>

Tracking Status: None "Clark, Roger" <Roger.Clark@nexteraenergy.com>

Tracking Status: None "Cumblidge, Stephen" <Stephen.Cumblidge@nrc.gov>

Tracking Status: None "Carlson, Robert" <Robert.Carlson@nrc.gov>

Tracking Status: None "Millen, Michael" <Michael.Millen@nexteraenergy.com>

Tracking Status: None Post Office:

Files Size Date & Time MESSAGE 1558 7/3/2013 1:14:00 PM Point Beach Nuclear Plant, Unit 2 - Draft Request for Additional Information (EPNB) Regarding Relief Request RR-4L2 (TAC No. MF1146).docx 26870 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST RR-4L2 POINT BEACH NUCLEAR PLANT, UNIT 2 NEXTERA ENERGY POINT BEACH, LLC DOCKET NO. 50-301 (TAC NO. MF1146)

By letter dated March 19, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13079A141), NextEra Energy Point Beach, LLC (the licensee) submitted relief request RR-4L2 covering a steam generator nozzle inner radius examination from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components for Point Beach Nuclear Power Plant, Unit 2. The request for relief applies to the fourth 10-year inservice inspection (ISI) interval, in which the licensee adopted the 1998 Edition through the 2000 Addenda of ASME Code Section XI as the code of record.

In accordance with 10 CFR 50.55a(g)(5)(iii), the licensee has submitted the subject request for relief for limited examination as the geometry of the component is not compatible with the ASME Code figures.

The NRC staff has reviewed and evaluated the information provided by the licensee, and determined that the following information is needed in order to complete its review:

1. The drawing of the flow restrictor provided appears to show that the flow restrictor is constructed of clad ferritic steel, but this is not explicitly stated in the relief request. Please describe the materials of construction for the flow restrictor.