ML111230777

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Email, Draft Request for Additional Information, Relief Requests ISI-3-32 Through ISI-3-34, Alternative to Requirements for Examinations of Welds and Core Support Structure Surfaces, Third 10-Year Inservice Inspection
ML111230777
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 05/03/2011
From: Hall J
Plant Licensing Branch IV
To: Conklin L
Southern California Edison Co
Hall, J R, NRR/DORL/LPL4,301-415-4032
Shared Package
ML111230775 List:
References
TAC ME5329, TAC ME5330
Download: ML111230777 (2)


Text

From: Hall, Randy Sent: Tuesday, May 03, 2011 1:54 PM To: Linda.Conklin@sce.com Cc: Mark.Morgan@sce.com

Subject:

Draft Request for Additional information - Relief Requests ISI-3-32 through ISI-3-34 for San Onofre Nuclear Generating Station (TAC NOS. ME5329 AND ME5330), Units 2 and 3 Attachments: RAI attachment.doc May 3, 2011 Ms. Linda Conklin Manager, Nuclear Licensing San Onofre Nuclear Generating Station Southern California Edison Company Linda:

By letter dated January 21, 2011 (Agencywide Documents Access and Management System Accession No. ML110100732), Southern California Edison Company (SCE, the licensee),

submitted a proposed alternative to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI inservice inspection (ISI) requirements regarding examination of certain reactor pressure vessel welds for the San Onofre Nuclear Generating Station (SONGS), Units 2 and 3. There are 3 separate but related requests for relief in the licensees application; ISI-3-32, ISI-3-33, and ISI-3-34. All three request NRC approval to extend the ISI examination interval from 10 to 20 years for the inspection of specific reactor pressure vessel (RPV) welds, in accordance with the WCAP-16168-NP, Revision 2 report, Risk-Informed Extension of Reactor Vessel In-Service Inspection Interval, October 2007 (ADAMS Accession No. ML072920413). ISI-3-32 and ISI-3-33 address the volumetric examination of certain RPV welds, for Units 2 and 3, respectively. ISI-3-34 addresses the visual examination of certain in-vessel welds for both units.

The NRC staff has reviewed the information provided by SCE and has determined that the additional information requested in the attachment to this e-mail message is needed to complete its review of the relief requests. In order to complete our review of the relief requests in a timely manner, please submit your response to the attached request for additional information (RAI) by June 10, 2011. Please contact me if SCE would like to have a conference call to discuss this request for additional information.

Sincerely, Randy Hall, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation USNRC (301) 415-4032 Randy.Hall@nrc.gov