ML13018A440

Email Susquehanna Steam Electric Station, Units 1 and 2 - Acceptance of Requested Licensing Action Re_ Low Pressure Safety Limit and Reference Changes (TAC Nos. MF0410 and MF0411)

ML13018A440
Person / Time
Site:	Susquehanna
Issue date:	01/18/2013
From:	Jeffrey Whited Plant Licensing Branch 1
To:	Tripoli J Susquehanna
Whited, Jeffrey
References
TAC MF0410, TAC MF0411
Download: ML13018A440 (2)

Text

From: Whited, Jeffrey To: "Tripoli, John L" Cc: "Jennings, Jason"

Subject:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - ACCEPTANCE OF REQUESTED LICENSING ACTION RE: LOW PRESSURE SAFETY LIMIT AND REFERENCE CHANGES (TAC NOS. MF0410 AND MF0411)

Date: Friday, January 18, 2013 4:48:00 PM

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 -

ACCEPTANCE OF REQUESTED LICENSING ACTION RE: LOW PRESSURE SAFETY LIMIT AND REFERENCE CHANGES (TAC NOS. MF0410 AND MF0411)

Dear Mr. John Tripoli:

By letter dated December 19, 2012, (Agencywide Document Access and Management System Accession No. ML12355A351) PPL Susquehanna, LLC, Inc. submitted a license amendment request for Susquehanna Steam Electric Station, Units 1 and 2 (SSES 1 and 2, respectively). The proposed amendments would modify the SSES Unit 1 and 2 Technical Specifications (TS) Section 2.1.1 to reflect a revised Low Pressure Safety Limit.

The purpose of this e-mail is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this license 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 license amendment request 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 me at 301-415-4090.

Jeffrey Whited Project Manager-Susquehanna Units 1 and 2 Plant Licensing Branch I-2

Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission (301)415-4090