ML110060551

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Acceptance of Braidwood and Byron LAR SG Tarc (TACs ME5198 - ME5201)
ML110060551
Person / Time
Site: Byron, Braidwood  Constellation icon.png
Issue date: 01/06/2011
From: Nicholas Difrancesco
Plant Licensing Branch III
To: Schofield L
Exelon Corp
DiFrancesco N, NRR/DORL/LPL3-2, 415-1115
References
TAC ME5198, TAC ME5199, TAC ME5200, TAC ME5201
Download: ML110060551 (2)


Text

From: DiFrancesco, Nicholas Sent: Thursday, January 06, 2011 10:37 AM To: Lisa.Schofield@exeloncorp.com Cc: jeff.hansen@exeloncorp.com; Lingam, Siva; Boyle, Patrick; Wohl, Marilyn

Subject:

Acceptance of Braidwood & Byron LAR Re: SG TARC (TACs ME5198 - ME5201)

Lisa, By letter dated December 14, 2010, Exelon Generation Company, LLC, submitted license amendment request (LAR) for Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2 (ADAMS Accession No. ML103510352). The LAR proposes to revise the Braidwood and Byron Technical Specifications (TS) 5.5.9, "Steam Generator (SG) Program," to exclude portions of the tube below the top of the steam generator tubesheet from periodic steam generator tube inspections and plugging or repair for Braidwood Unit 2 during Refueling Outage 15 and the subsequent operating cycle and for Byron Unit 2 during Refueling Outage 16 and the subsequent operating cycle. In addition, this LAR proposes to revise TS 5.6.9, "Steam Generator (SG) Tube Inspection Report," to remove reference to previous interim alternate repair criteria and provide reporting requirements specific to the temporary alternate criteria.

The purpose of this message is to provide the results of the Nuclear Regulatory Commission (NRC) staff's acceptance review of this LAR. 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 was also intended to identify whether the applications have 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 must fully describe the changes requested and follow, 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 has concluded that it provides technical information in sufficient detail to enable the NRC staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendments in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the NRC staff to complete its technical review, you will be advised by separate correspondence.

If you have any questions, please contact me at (301) 415-1115.

Sincerely, Nicholas DiFrancesco Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation