ML110880040

Email Acceptance Review for License Application NL-11-0280 Steam Generator Water Level Hi-Hi Setpoint Change

ML110880040
Person / Time
Site:	Vogtle
Issue date:	03/28/2011
From:	Patrick Boyle Plant Licensing Branch II
To:	Ajluni M, Stringfellow N Southern Nuclear Operating Co
References
TAC ME5778, TAC ME5779
Download: ML110880040 (1)

Text

From: Boyle, Patrick Sent: Monday, March 28, 2011 2:32 PM To: Ajluni, Mark J.; Stringfellow, N. Jack Cc: Midlik, David W.; Hill, Lesa P.; Martin, Robert; Lingam, Siva; Boyle, Patrick

Subject:

Acceptance review for license application NL-11-0280 Steam Generator water level Hi-Hi Setpoint change Mr. Ajluni:

By letter dated March 3, 2011 (ML110660458), 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) 3.3.1, "Reactor Trip System Instrumentation," and TS 3.3.2 Engineered Safety Feature Actuation System Instrumentation, to correct a non-conservative TS requirement by revising the Nominal Trip Setpoint and Allowable Value specified in Table 3.3.2-1 for Function 5c, Steam Generator Water Level High-High. 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.: 50-424, 50-425 TAC: ME5778, ME5779