ML12297A397

Request for Additional Information Email, Relief Request ISI-3-36, Reactor Coolant Pressure Boundary Testing, Third 10-Year Inservice Inspection Interval

ML12297A397
Person / Time
Site:	San Onofre
Issue date:	10/23/2012
From:	Brian Benney Plant Licensing Branch IV
To:	Conklin L Southern California Edison Co
Benney B
References
TAC ME8486, TAC ME8487
Download: ML12297A397 (1)

Text

From: Benney, Brian To: Benney, Brian; Linda.Conklin@sce.com Cc: Burkhardt, Janet; Chen, Qiao-Lynn

Subject:

ME8486-87 RAIs Date: Tuesday, October 23, 2012 2:25:09 PM

Dear Ms. Conklin:

By letter dated April 17, 2012 (Agencywide Documents Access and Management System (ADAMS) accession number ML12109A079), Southern California Edison (the licensee) requested relief from certain American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI requirements.

The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided by the licensee and determined that the additional information identified in the attachment is needed in order for the NRC staff to complete its review. The staff is requesting a written response to the RAls no later than November 15, 2012.

Please contact me if you would like to have a clarifying conference call.

Thank you, Brian Benney REQUEST FOR ADDITIONAL INFORMATION REQUEST FOR RELIEF ISI-3-36 LEAKAGE TEST SOUTHERN CALIFORNIA EDISON SAN ONOFRE NUCLEAR GENERATING STATION, UNITS 2 AND 3 DOCKET NUMBER: 50-361, 50-362 By letter dated April 17, 2012 (Agencywide Documents Access and Management System (ADAMS) accession number ML12109A079), Southern California Edison (the licensee) requested relief from certain American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI requirements. To complete its review, the Nuclear Regulatory Commission staff requests for the following additional information.

1. In section 4 of the request you state that, meeting those requirements involves considerable time to establish and return from the required temporary configuration resulting in both risk of delaying normal plant startup following a refueling outage and an increase in personnel radiation exposure and safety concern. Please detail the safety concern caused by erecting scaffolding and changing valve positions to conduct the pressure test as required by table IWB-2500-1.