ML22319A155
| ML22319A155 | |
| Person / Time | |
|---|---|
| Site: | 99902078 |
| Issue date: | 11/15/2022 |
| From: | NRC |
| To: | NRC/NRR/DNRL/NRLB |
| References | |
| Download: ML22319A155 (2) | |
Text
From:
Bruce Bavol Sent:
Tuesday, November 15, 2022 12:39 PM To:
NuScale-SDA-720DocsPEm Resource Cc:
Bruce Bavol
Subject:
(Clarification Question) NuScale TR-0716-50350, Revision 2, Rod Ejection Accident Methodology (Clarification Question) NuScale TR-0716-50350, Revision 2, Rod Ejection Accident Methodology On Wednesday, November 2, 2022, staff provided the following question to NuScale regarding TR-0716-50350, Revision 2: Table 2-2: Core Flow as a Function of Power contains different low/high flowrates between the core design basemodel (EC-100204-0) and the S3K scoping evaluation (EE-101801-A). It is not clear if this difference is associated with how uncertainties and margin are applied to the flowrates. Specifically, the flowrates in S3K scoping evaluation do not appear to include any margin or uncertainty. Please provide the basis for not including uncertainty or margin consistently between the core design basemodel and the S3K scoping evaluation.
On Wednesday, November 9, 2022, a clarification call was held with NuScale to discuss the above question. NuScale clarified that the S3K scoping evaluation document (EE-101801-A) was performed for a preliminary NuScale design and was not indented to be used or relied on for final design decisions or calculations. Based on the discussion the staff considers this issue resolved.
Bruce M. Bavol Project Manager Office of Nuclear Reactor Regulation DNRL/NRLB Work Phone: (301) 415-6715 Email: Bruce.Bavol@nrc.gov
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(Clarification Question) NuScale TR-0716-50350, Revision 2, Rod Ejection Accident Methodology Sent Date:
11/15/2022 12:38:42 PM Received Date:
11/15/2022 12:38:45 PM From:
Bruce Bavol Created By:
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"Bruce Bavol" <Bruce.Bavol@nrc.gov>
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