ML103490497

Acceptance Review for License Application NL-10-2104 H* Temporary Alternate Repair Criteria

ML103490497
Person / Time
Site:	Vogtle
Issue date:	12/14/2010
From:	Patrick Boyle Plant Licensing Branch II
To:	Ajluni M Southern Nuclear Operating Co
Boyle, Patrick, NRR/DORL/LPL2-1/415-3936
References
NL-10-2104 H, TAC ME5067, TAC ME5068
Download: ML103490497 (1)

Text

From: Boyle, Patrick Sent: Tuesday, December 14, 2010 3:11 PM To: Ajluni, Mark J.

Cc: Martin, Robert; Taylor, Robert; Hess, Thomas A.; Lingam, Siva

Subject:

Acceptance review for license application NL-10-2104 H* Temporary Alternate Repair Criteria By letter dated November 23, 2010 (ML103300241), Southern Nuclear Operating Company (SNC) submitted a request for an amendment to Facility Operating License Nos. NPF-68 and NPF-81 for Vogtle Electric Generating Plant (VEGP), Units 1 and 2, respectively. Specifically the amendment proposed to revise VEGP Technical Specification (TS) 5.5.9, "Steam Generator (SG) Program," to exclude portions of the tube below the top of the steam generator tube sheet from periodic steam generator tube inspections for Unit 1 during Refueling Outage 16 and the subsequent operating cycle and for Unit 2 during Refueling Outage 15 and the subsequent operating cycle. In addition, the amendment proposed to revise Technical Specification (TS) 5.6.10, "Steam Generator Tube Inspection Report" to remove reference to previous interim alternate repair criteria and provide reporting requirements specific to the temporary alternate repair criteria. The amendment was submitted pursuant to Title 10 of the Code of Federal Regulations Part 50.90.

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 the scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the request 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 proposed action 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 compare 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 the 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.

Patrick G. Boyle Project Manager NRR-DORL Plant Licensing Branch II-1 Office: O-8D09 Phone: 301-415-3936 Docket Nos.: 50-321, 50-366 TAC: ME5067, ME5068