Purpose
1. The staff seeks to understand the applicant’s reasoning for not taking the single failure of an inadvertent actuation block (IAB) valve during several events in the accident analyses (Chapter 6 “Engineered Safety Features” and Chapter 15 “Transient and Accident Analyses”).
2. The staff seeks to understand whether the input motion analysis for the fuel structural analysis provided in Technical Report TR-0816-51127 “NuFuel-HTP2™ Fuel and Control Rod Assembly Designs” (ML 17007A001) covers fuel in a power module located in the Reactor Vessel Flange Tool (RFT).
2. The staff seeks to understand whether the input motion analysis for the fuel structural analysis provided in Technical Report TR-0816-51127 “NuFuel-HTP2™ Fuel and Control Rod Assembly Designs” (ML 17007A001) covers fuel in a power module located in the Reactor Vessel Flange Tool (RFT).
Meeting Feedback
Meeting Dates and Times
04/19/17, 1PM - 3PM EDT
Meeting Location
Teleconference
Contact
Marieliz Vera
(301) 415-5861
Participation Level
Category 1
NRC Participants
Office of New Reactors
External Participants
NuScale Power Inc
Docket Numbers - Facility Names
05200048 - NUSCALE POWER REACTOR