ML111101067
| ML111101067 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 04/14/2011 |
| From: | Billoch-Colon A Plant Licensing Branch III |
| To: | Hansen J Exelon Generation Co |
| References | |
| TAC ME5836, TAC ME5837, TAC ME5838, TAC ME5839 | |
| Download: ML111101067 (2) | |
Text
From:
Billoch, Araceli Sent:
Thursday, April 14, 2011 3:27 PM To:
'jeff.hansen@exeloncorp.com' Cc:
DiFrancesco, Nicholas; Brown, Eva; Mahoney, Michael; Carlson, Robert
Subject:
Braidwood Station, Units 1 and 2 & Byron Station Units 1 and 2 - Acceptance of Requested Licensing Action Regarding Revision of TS 3.3.1 and TS 3.3.2 to Reflect Installation of Bypass Test Capability (TAC No. ME5836, ME 5837, ME 5838, ME 5839)
Dear Mr. Hansen,
By letter dated March 14, 2011, Exelon Generation Company, LLC, submitted a license amendment for Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2. The proposed amendment would revise certain Required Action Notes in the Braidwood and Byron Technical Specifications (TS) 3.3.1, Reactor Trip System Instrumentation, and TS 3.3.2, Engineered Safety Feature Actuation System Instrumentation. The proposed change will also reflect the standard wording incorporated in NUREG-1431, Revision 3, Standard technical Specifications, Westinghouse Plants, for plants with installed bypass test capability.
The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this amendment 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 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the TS) 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 NRC staff to complete 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. 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. You will be advised of any further information needed to support the NRC staffs detailed technical review by separate correspondence.
If you have any questions, please contact Nicholas DiFrancesco at (301) 415-1115 or me at (301) 415-3302.
Sincerely,
Araceli T. Billoch Colón Project Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Tel. 301-415-3302