ML16260A017

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Acceptance of Requested Licensing Action Revision of Technical Specifications Section 5.5.6 for Extension of Type a and Type C Leak Rate Test Frequencies Amendment
ML16260A017
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 09/21/2016
From: Render D
Plant Licensing Branch 1
To: Brian Sullivan
Entergy Nuclear Operations
Render D, NRR/DORL/LPLI-1, 415-3629
References
CAC MF8305
Download: ML16260A017 (3)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 21, 2016 Mr. Brian Sullivan Site Vice President Entergy Nuclear Operations, Inc.

James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093

SUBJECT:

JAMES A. FITZPATRICK NUCLEAR POWER PLANT-ACCEPTANCE OF REQUESTED LICENSING ACTION RE: REVISION OF TECHNICAL SPECIFICATIONS SECTION 5.5.6 FOR EXTENSION OF TYPE A AND TYPE C LEAK RATE TEST FREQUENCIES AMENDMENT (CAC NO. MF8305)

Dear Mr. Sullivan:

By application dated August 29, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16242A332), Entergy Nuclear Operations, Inc. submitted a license amendment for James A. FitzPatrick Nuclear Power Plant. The proposed amendment request would revise Technical Specification 5.5.6 Primary Containment Leak Rate Testing Program. These revisions would extend the Type A Primary Containment Integrated Leak Rate Test interval to 15 years and extend the Type C Local Leak Rate Test testing interval up to 75 months. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this 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 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 NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment 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 staff's 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 staff's detailed technical review by separate correspondence.

B. Sullivan If you have any questions, please contact me at (301) 415-3629.

Diane Render, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-333 cc: Distribution via Listserv

ML16260A017 concurrence via email*

OFFICE DORL/LPLl-1 /PM DORL/LPLl-1/LA DORL/LPLl-1 /BC DORL/LPLl-1 /PM NAME DRender KGolstein* TTate DRender DATE 09/15/2016 09/19/16 09/19/2016 09/21/2016