ML12111A272
| ML12111A272 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 04/18/2012 |
| From: | Michael Mahoney Plant Licensing Branch III |
| To: | Simpson L Exelon Generation Co |
| Mahoney M | |
| References | |
| TAC ME8296, TAC ME8297, TAC ME8299, TAC ME8298 | |
| Download: ML12111A272 (1) | |
Text
1 Zeleznock, Karen To:
'Lisa.Simpson@exeloncorp.com' Cc:
Zimmerman, Jacob; Mozafari, Brenda; Murphy, Emmett; Anderson, Shaun;
'david.gullott@exeloncorp.com'; 'richard.mcintosh@exeloncorp.com'
Subject:
RE: Acceptance Review Results for Byron and Braidwood License Amendment Request RE:
Changes to Technical Specifications 5.5.9 & 5.6.9-TAC Nos. ME8296-99 Attachments:
image001.gif April 18, 2012 Lisa Simpson Exelon Nuclear Corporate Licensing
Dear Mrs,
Simpson, By letter RS-12-023 dated March 20, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML120830222), Exelon Generation Company, LLC (the licensee) submitted a license amendment request (LAR) for Braidwood Station, Units 1 and 2, and Byron Station, Unit Nos. 1 and 2 (Braidwood and Bryon, respectively). The proposed LAR will revise Braidwood and Byrons Technical Specifications (TSs) 5.5.9 Steam Generator (SG) Program and 5.6.9, Steam Generator Tube Inspection Report. Specifically, the LAR will revise TS 5.5.9 to permanently exclude portions of the SG tube below the top of the SG tubesheet periodic SG tube inspections and plugging or repair for Braidwood, Unit 2 and Byron, Unit 2. In addition, the LAR will revise TS 5.6.9 to remove reference to the previous temporary alternate repair criteria and provide reporting requirements specific to the permanent alternate repair criteria.
The purpose of this e-mail is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this application. 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 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
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 make an independent assessment regarding the acceptability of the proposed amendment 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. A copy of this email will be made publicly available in ADAMS.
Docket Nos. 50-454, 50-455, 50-456, and 50-457 Sincerely, Michael Mahoney Davis-Besse, Perry and FENOC Fleet Project Manager, Licensing Branch III-2 U. S. Nuclear Regulatory Commission
2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Phone: (301)415-3867 Email: Michael.Mahoney@NRC.GOV