ML110250291
| ML110250291 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 01/25/2011 |
| 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 ME5329, TAC ME5330 | |
| Download: ML110250291 (2) | |
Text
From:
Hall, Randy Sent:
Tuesday, January 25, 2011 11:27 AM To:
Linda.Conklin@sce.com
Subject:
NRC Acceptance Review for San Onofre Units 2 and 3, Relief Requests ISI 32, ISI-3-33, and ISI-3-34 (TAC Nos. ME5329 and ME5330)
January 25, 2011 Linda Conklin Manager, Nuclear Licensing San Onofre Nuclear Generating Station Southern California Edison
- Linda, By letter dated January 7, 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 (ADAMS Accession Number ML110100732). In its letter, submitting Relief Requests ISI-3-32 through ISI-3-34, the licensee requested approval of alternatives to the inservice inspection (ISI) requirements in the ASME Code,Section XI, for volumetric examination of certain reactor vessel pressure retaining welds, and for visual examinations of accessible interior attachment welds and core support structure surfaces. Specifically, the licensee requested approval to extend the examination intervals for the subject components from 10 to 20 years, on a one-time basis, effectively deferring the inspections from the third 10-year ISI interval until the fourth 10-year ISI interval for each unit.
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 of Title 10 of the Code of Federal Regulations (10 CFR), an alternative to the requirements of that section or portion thereof may be used when authorized by the NRC. The applicant shall demonstrate that: 1) the proposed alternatives would provide an acceptable level of quality and safety, or 2) compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
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