ML120110025

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Acceptance Review Email, Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirements Related to Diesel Generator Test Loads, Voltage, and Frequency
ML120110025
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 01/11/2012
From: Hall J
Plant Licensing Branch IV
To: Hooper D
Wolf Creek
Hall, J R, NRR/DORL/LPL4, 301-415-4032
References
TAC ME7674
Download: ML120110025 (2)


Text

From:

Hall, Randy Sent:

Wednesday, January 11, 2012 8:08 AM To:

Hooper Diane M Cc:

Wideman Steve G; Burkhardt, Janet; Lent, Susan

Subject:

Acceptance of License Amendment Request for Wolf Creek Re: Revision to Technical Specification (TS) 3.8.1, "AC Sources - Operating" - TAC ME7674 January 11, 2012 Diane M. Hooper Licensing Supervisor Wolf Creek Generating Station Wolf Creek Nuclear Operating Corporation

Dear Diane,

By letter dated November 30, 2011 (Letter No. WO 11-0086), Wolf Creek Nuclear Operating Corporation (WCNOC) submitted a license amendment request for Wolf Creek Generating Station (WCGS). The proposed changes will revise Technical Specification (TS) 3.8.1. "AC Sources - Operating," to correct nonconservative values for the load testing of the diesel generators (DGs) at WCGS. Specifically, the following Surveillance Requirements (SRs) related to DG test loads, voltage and frequency will be revised; SR 3.8.1.2, SR 3.8.1.3, SR 3.8.1.7, SR 3.8.1.10, SR 3.8.1.11, SR 3.8.1.12, SR 3.8.1.14, SR 3.8.1.15, SR 3.8.1.19, and SR 3.8.1.20.

The purpose of this e-mail is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs 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 staff to proceed with 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. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence.

Sincerely, Randy Hall, Senior Project Manager Plant Licensing Branch IV

Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation USNRC (301) 415-4032 Randy.Hall@nrc.gov