ML20106F199: Difference between revisions
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==Dear Chairman Sunseri,== | ==Dear Chairman Sunseri,== | ||
In your letter dated March 25, 2020 (ML20085K327), the ACRS reported on the Committees review of the NRC staffs safety evaluation of the NuScale topical report TR-0516-49422, Revision 1, Loss-Of-Coolant Accident Evaluation Model. | In your {{letter dated|date=March 25, 2020|text=letter dated March 25, 2020}} (ML20085K327), the ACRS reported on the Committees review of the NRC staffs safety evaluation of the NuScale topical report TR-0516-49422, Revision 1, Loss-Of-Coolant Accident Evaluation Model. | ||
Your letter contained the following two conclusions and recommendations: | Your letter contained the following two conclusions and recommendations: | ||
: 1. The Loss-Of-Coolant Accident (LOCA) Evaluation Model topical report, with the limitations and conditions imposed by the staff SE report, provides an acceptable methodology to analyze the early stages of LOCAs prior to long-term cooling in the NuScale Power Module (NPM). | : 1. The Loss-Of-Coolant Accident (LOCA) Evaluation Model topical report, with the limitations and conditions imposed by the staff SE report, provides an acceptable methodology to analyze the early stages of LOCAs prior to long-term cooling in the NuScale Power Module (NPM). | ||
Revision as of 17:19, 23 September 2022
| ML20106F199 | |
| Person / Time | |
|---|---|
| Issue date: | 04/14/2020 |
| From: | Renee Taylor Office of Nuclear Reactor Regulation |
| To: | Matthew Sunseri Advisory Committee on Reactor Safeguards |
| Taylor R | |
| References | |
| Download: ML20106F199 (1) | |
Text
From: Taylor, Robert To: Sunseri, Matthew Cc: Moore, Scott; Burkhart, Larry; Snodderly, Michael; Bradford, Anna; Caldwell, Bob; Patton, Rebecca; Donoghue, Joseph; Dudek, Michael; Johnson, Marieliz; Chen, Lin; Betancourt, Luis
Subject:
Response to ACRS"s March 25, 2020 Letter on Topical Report, "Loss-of-Coolant Accident Evaluation Model," TR-0516-49422, Revision 1 Date: Tuesday, April 14, 2020 6:45:39 AM
Dear Chairman Sunseri,
In your letter dated March 25, 2020 (ML20085K327), the ACRS reported on the Committees review of the NRC staffs safety evaluation of the NuScale topical report TR-0516-49422, Revision 1, Loss-Of-Coolant Accident Evaluation Model.
Your letter contained the following two conclusions and recommendations:
- 1. The Loss-Of-Coolant Accident (LOCA) Evaluation Model topical report, with the limitations and conditions imposed by the staff SE report, provides an acceptable methodology to analyze the early stages of LOCAs prior to long-term cooling in the NuScale Power Module (NPM).
- 2. The staffs SE report should be issued.
The NRC staff appreciates the ACRSs review and recommendation and plans to re-issue the approved version of the topical report by June 2020, with the inclusion of any updated design information needed from NuScales recent design change for boron distribution.
The NRC staff also appreciates the time and effort the ACRS has devoted to this important subject, as reflected in meetings held with the ACRS Subcommittee for NuScale on February 19-20, 2020 and the ACRS Full Committee on March 5-6 2020, and looks forward to future interactions with the Committee as part of its NuScale review activities.
Best regards, Rob Robert M. Taylor Deputy Office Director for New Reactors Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission (office) 301-415-1270