ML12261A299

R. E. Gina Nuclear Power Plant - Acceptance Review for Relief Request RR-09

ML12261A299
Person / Time
Site:	Ginna
Issue date:	09/17/2012
From:	Thadani M Plant Licensing Branch 1
To:	Harding T Rochester Gas & Electric Corp
Thadani M
References
TAC ME9519
Download: ML12261A299 (2)

Text

From: Thadani, Mohan To: Harding Jr, Thomas Cc: Jackson, Jarred A; Mahoney, Michael; Tsao, John

Subject:

Acceptance Review for Relief Request RR-09 (TAC NO. ME9519)

Date: Monday, September 17, 2012 9:54:00 AM Mr. Harding:

The NRC staff has reviewed the subject relief request for acceptance for a detailed technical review. The NRC staff concludes that the relief request is acceptable for detailed review. Our acceptance review is documented below.

Thanks.

Mohan Mr. Joseph E. Pacher Vice President R.E. Ginna Nuclear Power Plant R.E. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, NY 14519

SUBJECT:

R.E. GINNA NUCLEAR POWER PLANT - ACCEPTANCE REVIEW FOR RELIEF REQUEST RR-09 (TAC NO. ME9519)

Dear Mr. Pacher:

By letter dated September 6, 2012,(ADAMS Accession No. ML12254A378), Ginna Nuclear Power Plant, LLC (the licensee) requested the U.S. Nuclear Regulatory Commission (NRC) staff for relief from the requirements to perform code repair (Relief Request ISI-09) during the 2012 scheduled refueling outage.

The proposed relief request R-09 seeks relief from the requirements to perform code repair during the 2012 scheduled refueling outage . The Relief request is submitted instead, to support planned repair during the 2014 refueling outage.

The purpose of this letter is to provide the results of the NRC staff=s acceptance review of this relief 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 technical specifications) 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 staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed relief 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.

Mohan C Thadani Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation (301) 415-1476 Mohan.Thadani@nrc.gov