ML16152A133

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Acceptance of Requested Licensing Action License Amendment Request to Change Technical Specification Section 6.0, Administrative Controls, for Permanently Defueled Condition
ML16152A133
Person / Time
Site: Oyster Creek
Issue date: 06/24/2016
From: John Lamb
Plant Licensing Branch IV
To: Bryan Hanson
Exelon Generation Co, Exelon Nuclear
Lamb J, DORL/LPLIV-2, 415-3100
References
CAC MF8005
Download: ML16152A133 (3)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 24, 2016 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Generation Company, LLC Oyster Creek Nuclear Generating Station 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

OYSTER CREEK NUCLEAR GENERATING STATION-ACCEPTANCE OF REQUESTED LICENSING ACTION RE: LICENSE AMENDMENT REQUEST TO CHANGE TECHNICAL SPECIFICATION SECTION 6.0, "ADMINISTRATIVE CONTROLS," FOR PERMANENTLY DEFUELED CONDITION (CAC NO. MF8005)

Dear Mr. Hanson:

By letter dated May 17, 2016 (Agencywide Documents Access and Management System Accession No. ML16138A129), Exelon Generation Company, LLC requested an amendment to the technical specifications (TSs), of Renewed Facility Operating License No. DPR-16, for Oyster Creek Nuclear Generating Station (OCNGS). The proposed amendment would revise OCNGS TS Section 6.0, Administrative Controls," for permanently defueled condition.

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 TSs) 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. Hanson If you have any questions, please contact me at (301) 415-3100 or via e-mail at John.Lamb@nrc.gov.

nG.Lamb.S!7~

nt Licensing IV-2 and Decommissioning ransition Branch ivision of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-219 cc: Distribution via Listserv

ML16152A133 OFFICE NRR/DORL/LPL4-2/PM NRR/DORL/LPL4-2/LA NRR/DORL/LPL4-2/BC(A) NRR/DORL/LPL4-2/PM NAME Jlamb PBlechman SAnderson Jlamb DATE 6/22/2016 6/01/2016 6/24/2016 6/24/2016