ML20017A115
| ML20017A115 | |
| Person / Time | |
|---|---|
| Issue date: | 01/15/2020 |
| From: | Joseph Donoghue NRC/NRR/DSS |
| To: | Riccardella P Advisory Committee on Reactor Safeguards |
| Wang W | |
| References | |
| Download: ML20017A115 (1) | |
Text
From: Donoghue, Joseph Sent: Wednesday, January 15, 2020 11:51 AM To: Riccardella, Peter <Peter.Riccardella@nrc.gov>
Cc: Nieh, Ho <Ho.Nieh@nrc.gov>; Veil, Andrea <andrea.veil@nrc.gov>; Ross-Lee, MJ
<MaryJane.Ross-Lee@nrc.gov>; Lukes, Robert <Robert.Lukes@nrc.gov>; Burkhart, Larry
<Lawrence.Burkhart@nrc.gov>; Kaizer, Joshua <Joshua.Kaizer@nrc.gov>; Cruz, Holly
<Holly.Cruz@nrc.gov>
Subject:
Response to ACRS letter dated November 26, 2019, regarding NUREG/KM-0013, Credibility Assessment Framework for Critical Boiling Transition Models - A Generic Safety Case to Determine the Credibility of Critical Heat Flux and Critical Power Models"
Dear Chairman Riccardella,
During the 668th meeting of the Advisory Committee on Reactor Safeguards (ACRS), the ACRS reviewed the staffs knowledge management publication, NUREG/KM-0013, Credibility Assessment Framework for Critical Boiling Transition Models - A Generic Safety Case to Determine the Credibility of Critical Heat Flux and Critical Power Models, Draft Report for Comment.
In a letter to Margaret M. Doane dated November 26, 2019, the committee provided its conclusion and recommendation that this framework be extended to other data-driven models. The staff appreciates the committees thorough review and recommendation.
Currently the staff is updating the framework to extend it to data-driven models.
- Regards, Joseph Donoghue Director of Division of Safety Systems Office of Nuclear Reactor Regulation