ML13290A561
| ML13290A561 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom, Byron, Braidwood, Limerick, Clinton, LaSalle, Crane  |
| Issue date: | 10/09/2013 |
| From: | Joel Wiebe Division of Operating Reactor Licensing |
| To: | Tom Loomis Exelon Corp |
| References | |
| Download: ML13290A561 (2) | |
Text
1 NRR-PMDAPEm Resource From:
Wiebe, Joel Sent:
Wednesday, October 09, 2013 4:28 PM To:
Subject:
Acceptance Review for Request to Use a Provision of a Later Addenda of the ASME Boiler and Pressure Vessel Code,Section XI By letter dated September 25, 2013 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML13270A197), Exelon Generation Company, LLC (Exelon), submitted a request to use a provision of a later Edition and Addenda of the American Society for Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, for Braidwood Station, Units 1 and 2; Byron Station, Units 1 and 2; Clinton Power Station, Unit 1; LaSalle County Station, Units 1 and 2; Limerick Generating Station, Units 1 and 2; Peach Bottom Atomic Power Station, Units 2 and 3; and Three Mile Island Nuclear Station, Unit 1.
Specifically, Exelon proposes to utilize portions of the ASME Section XI, 2007 Edition with the 2008 Addenda in lieu of the current applicable station code editions and addenda. Beginning with the 2007 Edition with the 2008 Addenda, the examination categories for pump casing and valve body welds in both Class 1 and Class 2 components were removed from ASME Section XI. The affected ASME section XI Examination Categories were B-L-1 and B-M-2 for Class 1 components and C-G for Class 2 components. The approval of the 2007 Edition through the 2008 Addenda of the ASME Code for use was announced in the Federal Register on June 21, 2011 (76 FR 36232). The purpose of this e-mail is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this 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 request and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the request in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staffs ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. If additional information is needed, you will be advised by separate correspondence.
If you have any questions, please contact me at (301) 415-6606.
Joel S. Wiebe, Sr. Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Hearing Identifier:
NRR_PMDA Email Number:
870 Mail Envelope Properties (Joel.Wiebe@nrc.gov20131009162800)
Subject:
Acceptance Review for Request to Use a Provision of a Later Addenda of the ASME Boiler and Pressure Vessel Code,Section XI Sent Date:
10/9/2013 4:28:18 PM Received Date:
10/9/2013 4:28:00 PM From:
Wiebe, Joel Created By:
Joel.Wiebe@nrc.gov Recipients:
"Tom Loomis" <thomas.loomis@exeloncorp.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 2793 10/9/2013 4:28:00 PM Options Priority:
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