ML12152A074

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Acceptance Review Email Relief Request ISI-3-36, Reactor Coolant Pressure Boundary Testing, Third 10-Year Inservice Inspection Interval
ML12152A074
Person / Time
Site: San Onofre  
Issue date: 05/31/2012
From: Hall J
Plant Licensing Branch IV
To: Conklin L
Southern California Edison Co
Hall J
References
TAC ME8486, TAC ME8487
Download: ML12152A074 (2)


Text

From:

Hall, Randy To:

Linda.Conklin@sce.com Cc:

Lent, Susan; Burkhardt, Janet

Subject:

NRC Acceptance Review for San Onofre Units 2 and 3, Relief Request ISI-3-36, Pressure Testing Boundary TAC Nos. ME8486 and ME8487 Date:

Thursday, May 31, 2012 8:57:22 AM May 31, 2012

Linda Conklin Manager, Nuclear Licensing San Onofre Nuclear Generating Station Southern California Edison

Linda,

By letter dated April 17, 2012, Southern California Edison (the licensee) submitted a request for relief from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI for the San Onofre Nuclear Generating Station (SONGS), Units 2 and 3. In its letter, the licensee designated this relief request as ISI-3-36, and this request covers alternatives to testing the reactor coolant pressure boundary (RCPB) at SONGS, Units 2 and 3, for the 3rd ten-year inservice inspection interval.

If authorized by NRC, relief request ISI-3-36 would allow the licensee to perform an alternative to the full system leakage test for all vent, drain and branch lines of 1-inch nominal pipe size or smaller connected to the reactor coolant pressure boundary, as well as four 2-inch drain lines from the cold leg to the reactor coolant drain tank. Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(a)(3)(ii), allows the NRC to authorize alternatives when compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.

The purpose of this e-mail is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this relief request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.

The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and to make an independent assessment regarding the acceptability of the proposed relief request in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence.

If you have any questions, please contact me at (301) 415-4032.

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