ML17184A004

NRR E-mail Capture - Fort Calhoun - Acceptance Review of Removal of Dry Cask Loading Limits

ML17184A004
Person / Time
Site:	Fort Calhoun
Issue date:	06/30/2017
From:	James Kim Special Projects and Process Branch
To:	Matzke E Omaha Public Power District
References
MF9831
Download: ML17184A004 (3)

Text

NRR-PMDAPEm Resource From: Kim, James Sent: Friday, June 30, 2017 1:15 PM To: MATZKE, ERICK P Cc: BLOME, BRADLEY H

Subject:

Fort Calhoun - Acceptance Review of Removal of Dry Cask Loading Limits (CAC No.

MF9831)

SUBJECT:

FORT CALHOUN STATION, UNIT NO. 1 - ACCEPTANCE OF REQUESTED AMENDMENT RE:

REMOVAL OF DRY CASK LOADING LIMITS (CAC NO. MF9831)

By letter dated June 9, 2017, OPPD submitted a license amendment request for the Fort Calhoun Station (FCS) to request the U.S. Nuclear Regulatory Commission (NRC) approval to delete Technical Specifications (TS} 2.8.3(6), Spent Fuel Cask Loading and associated Figure 2-11, Limiting Burnup Criteria for Acceptable Storage in Spent Fuel Cask; TS 3.2 Table 3-5(24), Spent Fuel Cask Loading; TS 4.3.1.3, Design Features associated with spent fuel casks; and portions of TS 3.2, Table 3-4(5), Footnote (4) on boron concentration associated with cask loading.* The deletion of the TS sections will bring the FCS TS into conformance with 10 CFR 50.68(c) "Criticality accident requirements." The purpose of this letter 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. You will be advised of any further information needed to support the NRC staffs detailed technical review by separate correspondence.

Based on the information provided in your submittal, the NRC staff has estimated that this licensing request will take approximately 160 hours6.667 days <br />0.952 weeks <br />0.219 months <br /> to complete. The NRC staff expects to complete this review in approximately 9 months, which is March 2018. If there are emergent complexities or challenges in our review that would cause changes to the initial forecasted completion date or significant changes in the forecasted hours, the reasons for the changes, along with the new estimates, will be communicated during the routine interactions with the assigned project manager.

These estimates are based on the NRC staffs initial review of the application and they could change, due to several factors including requests for additional information, unanticipated addition of scope to the review, and review by NRC advisory committees or hearing-related activities. Additional delay may occur if the submittal is provided to the NRC in advance or in parallel with industry program initiatives or pilot applications.

If you have any questions, please contact me at (301) 415-4125 or e-mail at James.Kim@nrc.gov 1

James Kim, Project Manager Special Projects and Process Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 2

Hearing Identifier: NRR_PMDA Email Number: 3591 Mail Envelope Properties (James.Kim@nrc.gov20170630131500)

Subject:

Fort Calhoun - Acceptance Review of Removal of Dry Cask Loading Limits (CAC No. MF9831)

Sent Date: 6/30/2017 1:15:13 PM Received Date: 6/30/2017 1:15:00 PM From: Kim, James Created By: James.Kim@nrc.gov Recipients:

"BLOME, BRADLEY H" <bblome@oppd.com>

Tracking Status: None "MATZKE, ERICK P" <ematzke@oppd.com>

Tracking Status: None Post Office:

Files Size Date & Time MESSAGE 3968 6/30/2017 1:15:00 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received: