ML13249A318

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Acceptance Review Email, License Amendment Request to Revise Updated Safety Analysis Report for Westinghouse Plant-Specific Leak-Before-Break Analysis
ML13249A318
Person / Time
Site: Fort Calhoun 
Issue date: 09/06/2013
From: Lynnea Wilkins
Plant Licensing Branch IV
To: Hansher B
Omaha Public Power District
Wilkins L
References
TAC MF2559
Download: ML13249A318 (1)


Text

1 Burkhardt, Janet From:

Wilkins, Lynnea Sent:

Friday, September 06, 2013 1:45 PM To:

HANSHER, BILL R (bhansher@oppd.com)

Cc:

EDWARDS, MICHAEL L (medwards@oppd.com); Burkhardt, Janet; Sebrosky, Joseph

Subject:

Acceptance of Fort Calhoun LAR Re: Plant Specific Leak Before Break Analysis (MF2559)

Bill, By letter dated August 5, 2013 (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML13220A072), Omaha Public Power District (the licensee) submitted for Nuclear Regulatory Commission (NRC) review and approval a license amendment request at Fort Calhoun Station. The license amendment request is related to the leak-before-break (LBB) application for the reactor coolant system piping. To satisfy one of the commitments as part of its license renewal application, the licensee submitted a plant-specific LBB analysis before the period of extended operation, which begins at midnight, August 9, 2013.

The purpose of this message is to provide the results of the NRC staffs acceptance review of this 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 staffs ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence.

If you have any questions, please contact me at (301) 415-1377 or Joe Sebrosky at (301) 415-1132.

Lynnea Wilkins, Project Manager Fort Calhoun Station, Unit 1 Cooper Nuclear Station Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation US Nuclear Regulatory Commission Phone: 301-415-1377