ML113500183
| ML113500183 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 12/13/2011 |
| From: | Hall J Plant Licensing Branch IV |
| To: | Conklin L Southern California Edison Co |
| Hall, J R, NRR/DORL/LPL4, 301-415-4032 | |
| References | |
| TAC ME7542, TAC ME7543 | |
| Download: ML113500183 (2) | |
Text
From:
Hall, Randy Sent:
Tuesday, December 13, 2011 10:28 AM To:
Linda.Conklin@sce.com
Subject:
NRC Acceptance Review for San Onofre Units 2 and 3, Relief Request ISI-3-35 for Snubbers TAC Nos. ME7542 and ME7543 December 13, 2011 Linda Conklin Manager, Nuclear Licensing San Onofre Nuclear Generating Station Southern California Edison
- Linda, By letter dated October 21, 2011, 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-3-35, and this request covers the inservice inspection of all safety-related seismic restraints (snubbers) at SONGS, Units 2 and 3, within the scope described the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM) Edition and Addenda. If granted by NRC, relief request ISI-3-35 would allow the licensee to follow the requirements of the ASME OM Code 2004 Edition, with OMa-2005 and OMb-2006 addenda for the inservice inspection and testing of all safety-related snubbers at SONGS Units 2 and 3, for the duration of the current 3rd ten-year and the entire 4th ten-year inspection intervals.
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.
Consistent with Section 50.55a(g)(4)(iv) of Title 10 of the Code of Federal Regulations (10 CFR), inservice examination of components may meet the requirements in subsequent editions and addenda of the ASME Code as incorporated by reference in 10 CFR 50.55a(b), subject to the limitations and modifications as listed in that section, and subject to Commission approval.
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