ML24116A201

Nrctva ISFSI CBS (RFI)

ML24116A201
Person / Time
Site:	Browns Ferry, Sequoyah, Watts Bar
Issue date:	04/17/2024
From:	Neal D Division of Reactor Safety II
To:	Cupp B Tennessee Valley Authority
References
Download: ML24116A201 (1)

Text

From: Darrell Neal To: Cupp, Brian D Cc: Binoy Desai; Paula Cooper

Subject:

NRC ISFSI Inspection (Bowns Ferry, Watts Bar, and Sequoyah)

Date: Wednesday, April 17, 2024 12:14:00 PM

Good afternoon Brian,

My name is Darrell Neal, and I am an NRC Region II ISFSI POC for the final disposition of the Holtec CBS issue that we have been following for the past year.

As was discussed during the March 6th NRC public meeting on the CBS subject, the NRC has determined that we will be pursuing inspection and disposition of potential SL IV non-cited violations for each user of CBS-type casks. If applicable to your sites this issue will be assessed and cited against the general/specific licensee use of CBS-type casks who may not have performed an adequate 72.48 evaluation of the CBS design change and/or failed to request that the CoC holder (Holtec) obtain license amendment pursuant to 10 CFR 72.244 prior to implementing the CBS design change.

To inspect and disposition this issue we will be opening a remote inspection under IP 60855 to review the applicable documentation and determine if Bowns Ferry, Watts Bar, and Sequoyahs ISFSI loading activities apply to this potential NCV. To complete this inspection, we request the following documents from each site:

1. The specific model(s) and quantity of CBS-type casks that have been loaded at your site and the dates they were loaded.

Note: The CBS design change applies to the following Holtec HI-STORM 100 and HI-STORM FW cask designs (MPC 68M-CBS, MPC 32M-CBS, MPC 89-CBS)

2. All 72.48 screenings/evaluations performed by your site associated with the CBS design change.

3. Documentation of any/all CAP entries associated with the CBS design change.

It is our goal to complete and document this inspection activity as part of the 2024 2nd quarter integrated inspection report. A date and time for an exit meeting will be established following our review. We respectfully request that these documents be provided to us by 5/17/2024. If you are unable to accommodate our request by this date, please notify us promptly.

We understand that this request is abnormal and outside of our regularly scheduled inspection process for NRC oversight of ISFSI operations, and that this type of request may be a bit of a surprise to your organization. We greatly appreciate your cooperation in this matter. If you have any questions or concerns, please contact both myself and Paula Cooper; or Binoy Desai, our Region II Branch Chief responsible for ISFSI oversight.

Thanks,

Darrell Neal Engineering Branch 3 Division of Reactor Safety U.S. NRC - Region II

( 404-997-4639

• darrell.neal@nrc.gov