ML13022A090

2013/01/18 NRR E-mail Capture - Point Beach Nuclear Plant, Unit 1 - Draft Request for Additional Information for Relief Request 1-RR-4 (TAC No. M9905)

ML13022A090
Person / Time
Site:	Point Beach
Issue date:	01/18/2013
From:	Beltz T A Plant Licensing Branch III
To:	Millen M Point Beach
References
TAC ME9905
Download: ML13022A090 (3)

Text

1NRR-PMDAPEm ResourceFrom:Beltz, TerrySent:Friday, January 18, 2013 10:02 AMTo:Michael.Millen@nexteraenergy.comCc:'Hanneman, Harv'; Carlson, Robert; Lupold, Timothy; Cumblidge, StephenSubject:Point Beach Nuclear Plant, Unit 1 - Draft Request for Additional Information for Relief Request 1-RR-4 (TAC No. M9905)Attachments:Point Beach Relief Request 1-RR-4 - Request for Additional Information (TAC No. ME9905).docx Dear Mr. Millen:

By letter dated November 9, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12318A125), as supplemented by letter dated December 14, 2012 (ADAMS Accession No. ML12349A364), NextEra Energy Point Beach, LLC (the licensee) submitted a relief request (1-RR-4) for use of the alternate root mean square error criteria for sizing flaws that is greater than the requirements of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Case N-695, "Qualification Requirements for Dissimilar Metal Piping Welds," at the Point Beach Nuclear Plant, Unit 1. The U.S. Nuclear Regulatory Commission staff in the Piping & NDE Branch of the Office of Nuclear Reactor Regulation has identified that additional information is needed to complete its review. The draft request for additional information (RAI) is attached.

You may accept this as a formal request for additional information and respond to the question by February 15, 2013. Alternatively, you may request to discuss the content of this 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 Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation (301) 415-3049 Terry.Beltz@nrc.gov Hearing Identifier: NRR_PMDA Email Number: 587 Mail Envelope Properties (7E9EA9BB82325E46B07B0F04F99B40D87C56034518)

Subject:

Point Beach Nuclear Plant, Unit 1 - Draft Request for Additional Information for Relief Request 1-RR-4 (TAC No. M9905) Sent Date: 1/18/2013 10:01:58 AM Received Date: 1/18/2013 10:01:00 AM From: Beltz, Terry Created By: Terry.Beltz@nrc.gov Recipients: "'Hanneman, Harv'" <Harv.Hanneman@nexteraenergy.com> Tracking Status: None "Carlson, Robert" <Robert.Carlson@nrc.gov> Tracking Status: None "Lupold, Timothy" <Timothy.Lupold@nrc.gov>

Tracking Status: None "Cumblidge, Stephen" <Stephen.Cumblidge@nrc.gov> Tracking Status: None "Michael.Millen@nexteraenergy.com" <Michael.Millen@nexteraenergy.com> Tracking Status: None Post Office: HQCLSTR01.nrc.gov Files Size Date & Time MESSAGE 1477 1/18/2013 10:01:00 AM Point Beach Relief Request 1-RR-4 - Request for Additional Information (TAC No. ME9905).docx 23149 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received:

REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST 1-RR-4 POINT BEACH NUCLEAR PLANT, UNIT 1 NEXTERA ENERGY POINT BEACH, LLC DOCKET NUMBER 50-266 (TAC NO. ME9905) By letter dated November 9, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12318A125), as supplemented by letter dated December 14, 2012 (ADAMS Accession No. ML12349A364), NextEra Energy Point Beach, LLC (the licensee) submitted Relief Request (RR) 1-RR-4 requesting the use of alternate root mean square (RMS) error criteria for sizing flaws that is greater than the requirements of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) Case N-695, "Qualification Requirements for Dissimilar Metal Piping Welds," at the Point Beach Nuclear Plant Unit 1. 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 of the relief request. 1. While the inspection procedure is described as having a depth-sizing RMS Error of 0.212 inches, no information is stated about the detection and length sizing capabilities of the inspection procedure. Has the inspection procedure passed the Appendix VIII detection and length sizing requirements of ASME Code Case N-695?