ML22277A438
| ML22277A438 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 08/09/2022 |
| From: | Marlayna Vaaler Doell Reactor Decommissioning Branch |
| To: | Steven Roberts, Van Noordennen G EnergySolutions |
| Doell M, 415-3178 | |
| Shared Package | |
| ML22277A350 | List: |
| References | |
| Download: ML22277A438 (1) | |
Text
From:
Doell, Marlayna To:
Gerard P. Van Noordennen-ext; Sarah Roberts
Subject:
NRC Call on ISOCS Geometry at LACBWR?
Date:
Tuesday, August 9, 2022 4:46:00 PM Hi Gerry and Sarah,
I hope that you are both have a decent week so far! I dont want to ruin it if you are, but I was hoping I could ask you about the potential to have a discussion on the ISOCS geometry used to evaluate the WGTV sump areapreferably THIS Thursday or Friday since both Leah and I are out next week at other sites (sorry!). I have summarized the concern below, but our folks are free Thursday from 11-12 EDT or 1-2 EDT, and pretty much any time on Friday between 10-2 EDT. Let me know if any of those timeslots happen to work, and if not we can look for a time during the week of 8/22 to discuss this and any other questions on the July 7th responses, which I understand will be arriving imminently (in draft form at least!)
To help with the ISOCS discussion, the concern is basically whether setting up the ISOCS instrument with an assumed thickness or depth of contamination to 0.5 inches of contaminated concrete would adequately capture the potential contamination at depth in the WGTV sump, especially given that the continuing characterization concrete core samples (pucks) showed contamination to at least a depth of 1 inch and considering that the judgmental ISOCS shot was 0.9903 SOF. In terms of a teleconference I believe the staff is looking for an additional discussion that either (1) demonstrates why/how the ISOCS setup ensured the residual contamination left in the sump concrete was adequately evaluated and captured as part of the compliance dose calculation, or (2) provides a more detailed dose analysis of the concrete from the sump that would account for the potential additional dose from the elevated area being added to that basement survey unit.
Please let me know if a call in the near term is possible, and if not we will figure out a time as soon as the schedules allow! Thanks as always for the support, give me a shout if you have question or need anything additional, and I will talk to you soon!
Marlayna
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Decommissioning Project Manager U.S. Nuclear Regulatory Commission NMSS/DUWP/RDB
Phone: 301.415.3178 Mobile: 440.668.7399 Home: 605.348.2334 E-mail: marlayna.doell@nrc.gov Office Location: Fulltime Telework from Rapid City, South Dakota!
Mail Stop: T-5A10