ML18330A013: Difference between revisions
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ML18330A013 NRO-002 OFFICE DLSE/LB1:PM DLSE /LB1:LA DSRA/SPRA DNRL/LB1:PM NAME GTesfaye MMoore JSchaperow* GTesfaye (signed) | ML18330A013 NRO-002 OFFICE DLSE/LB1:PM DLSE /LB1:LA DSRA/SPRA DNRL/LB1:PM NAME GTesfaye MMoore JSchaperow* GTesfaye (signed) | ||
DATE 11/23/2018 11/26/2018 11/27/2018 11/27/2018 | DATE 11/23/2018 11/26/2018 11/27/2018 11/27/2018 U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS THE NUSCALE POWER, LLC RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION ASSOCIATED WITH THE NUSCALE DESIGN CERTIFICATION APPLICATION MEETING AGENDA October 31, 2018 11:00 - 11:10 AM Introductions and Identification of topics 11:10 - 11:15 AM Discussion of U.S. Nuclear Regulatory Commission Staffs Questions regarding NuScale Power LLCs Response to Request for Additional Information No. 9224, Question 01.05-32 (Open Portion) 11:15 - 11:20 AM Public Comments/Questions 11:20 - 12:30 PM Closed portion Enclosure 1 | ||
U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS THE NUSCALE POWER, LLC RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION ASSOCIATED WITH THE NUSCALE DESIGN CERTIFICATION APPLICATION MEETING AGENDA October 31, 2018 11:00 - 11:10 AM Introductions and Identification of topics 11:10 - 11:15 AM Discussion of U.S. Nuclear Regulatory Commission Staffs Questions regarding NuScale Power LLCs Response to Request for Additional Information No. 9224, Question 01.05-32 (Open Portion) 11:15 - 11:20 AM Public Comments/Questions 11:20 - 12:30 PM Closed portion Enclosure 1 | |||
U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS THE NUSCALE POWER, LLC RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION ASSOCIATED WITH THE NUSCALE DESIGN CERTIFICATION APPLICATION LIST OF ATTENDEES October 31, 2018 Name Organization Getachew Tesfaye U.S. Nuclear Regulatory Commission (NRC) | U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS THE NUSCALE POWER, LLC RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION ASSOCIATED WITH THE NUSCALE DESIGN CERTIFICATION APPLICATION LIST OF ATTENDEES October 31, 2018 Name Organization Getachew Tesfaye U.S. Nuclear Regulatory Commission (NRC) | ||
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U.S. NUCLEAR REGULATORY COMMISSION OVERVIEW OF THE OCTOBER 31, 2018, TELECONFERENCE TO DISCUSS THE NUSCALE POWER, LLC RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION ASSOCIATED WITH THE NUSCALE DESIGN CERTIFICATION APPLICATION The purpose of this teleconference was to discuss the results of the U.S. Nuclear Regulatory Commission (NRC) staffs review of NuScale Power LLCs (NuScale) Response to Request for Additional Information (RAI) No. 9224, Question 01.05-32. This was a follow-up to the October 3, 2018, public meeting where this topic was first discussed (Agencywide Documents Access and Management Systems (ADAMS) Accession No. ML18299A242). | U.S. NUCLEAR REGULATORY COMMISSION OVERVIEW OF THE OCTOBER 31, 2018, TELECONFERENCE TO DISCUSS THE NUSCALE POWER, LLC RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION ASSOCIATED WITH THE NUSCALE DESIGN CERTIFICATION APPLICATION The purpose of this teleconference was to discuss the results of the U.S. Nuclear Regulatory Commission (NRC) staffs review of NuScale Power LLCs (NuScale) Response to Request for Additional Information (RAI) No. 9224, Question 01.05-32. This was a follow-up to the October 3, 2018, public meeting where this topic was first discussed (Agencywide Documents Access and Management Systems (ADAMS) Accession No. ML18299A242). | ||
The following is the summary of the NRC staffs feedback and agreed upon next steps for the resolution of the remaining issues. | The following is the summary of the NRC staffs feedback and agreed upon next steps for the resolution of the remaining issues. | ||
: 1. Response to RAI No. 9224, Question 01.05-32 (ADAMS Accession No. | : 1. Response to RAI No. 9224, Question 01.05-32 (ADAMS Accession No. ML18212A192): | ||
ML18212A192): | |||
: a. NRC Feedback: The staff requested clarifications on the applicants responses to RAI 9224 (ADAMS Accession No. ML18212A192) and RAI 9534 (ADAMS Accession No. ML18275A426) related to the NuScale Accident Source Term Topical Report and its implementation in the Final Safety Analysis Report. The staff sought clarifications in areas where novel approaches or assumptions were being used as well as unique features of the NuScale design (e.g., evacuated containment) that might affect the approaches and assumptions taken in the accident source term methodology. The main purpose was to obtain clarifications on two issues related to these RAI responses: the basis for the containment leak rate and the approach for selecting thermal hydraulic conditions for estimating fission product aerosol deposition in the containment. | : a. NRC Feedback: The staff requested clarifications on the applicants responses to RAI 9224 (ADAMS Accession No. ML18212A192) and RAI 9534 (ADAMS Accession No. ML18275A426) related to the NuScale Accident Source Term Topical Report and its implementation in the Final Safety Analysis Report. The staff sought clarifications in areas where novel approaches or assumptions were being used as well as unique features of the NuScale design (e.g., evacuated containment) that might affect the approaches and assumptions taken in the accident source term methodology. The main purpose was to obtain clarifications on two issues related to these RAI responses: the basis for the containment leak rate and the approach for selecting thermal hydraulic conditions for estimating fission product aerosol deposition in the containment. | ||
: b. Next Step: During the meeting, the NuScale provided the clarifications requested by the NRC staff. The NRC staff concluded the meeting by stating that it plans to formally request (through the RAI process) additional information on the basis for the containment leak rate. For the thermal hydraulic conditions being used to estimate fission product aerosol deposition in the containment, the applicant stated it would provide a report for audit that provides technical justification for the applicants approach for selecting thermal hydraulic conditions. | : b. Next Step: During the meeting, the NuScale provided the clarifications requested by the NRC staff. The NRC staff concluded the meeting by stating that it plans to formally request (through the RAI process) additional information on the basis for the containment leak rate. For the thermal hydraulic conditions being used to estimate fission product aerosol deposition in the containment, the applicant stated it would provide a report for audit that provides technical justification for the applicants approach for selecting thermal hydraulic conditions. | ||
: 2. The proprietary information discussion topics for the closed portion of the meeting, prepared by the NRC staff, can be found in ADAMS (Accession No. ML18327A133). | : 2. The proprietary information discussion topics for the closed portion of the meeting, prepared by the NRC staff, can be found in ADAMS (Accession No. ML18327A133). | ||
1 Enclosure 3}} | 1 Enclosure 3}} | ||
Revision as of 15:13, 2 February 2020
| ML18330A013 | |
| Person / Time | |
|---|---|
| Site: | NuScale |
| Issue date: | 11/27/2018 |
| From: | Getachew Tesfaye NRC/NRO/DLSE/LB1 |
| To: | Samson Lee NRC/NRO/DLSE/LB1 |
| Tesfaye G/NRO/8013 | |
| References | |
| Download: ML18330A013 (5) | |
Text
November 27, 2018 MEMORANDUM TO: Samuel S. Lee, Chief Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors FROM: Getachew Tesfaye, Senior Project Manager /RA/
Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors
SUBJECT:
SUMMARY
OF THE OCTOBER 31, 2018, CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS THE NUSCALE POWER, LLC RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION ASSOCIATED WITH THE NUSCALE DESIGN CERTIFICATION APPLICATION The U.S. Nuclear Regulatory Commission (NRC) held a Category 1 public teleconference on October 31, 2018, to discuss responses to the NRC staffs requests for additional information associated with the NuScale Power, LLC (NuScale) design certification application. Participants included personnel from NuScale. Members of the general public did not participate in this teleconference.
The public meeting notice dated October 1, 2018, can be found in the NRCs Agencywide Documents Access and Management Systems under Accession No. ML18303A263. This meeting notice was also posted on the NRC public website.
Enclosed is the meeting agenda (Enclosure 1), list of participants (Enclosure 2), and overview (Enclosure 3).
Docket No.52-048
Enclosures:
- 1. Meeting Agenda
- 2. List of Attendees
- 3. Meeting Overview cc w/encl.: DC NuScale Power, LLC Listserv CONTACT: Getachew Tesfaye NRO/DLSE 301-415-8013
ML18330A013 NRO-002 OFFICE DLSE/LB1:PM DLSE /LB1:LA DSRA/SPRA DNRL/LB1:PM NAME GTesfaye MMoore JSchaperow* GTesfaye (signed)
DATE 11/23/2018 11/26/2018 11/27/2018 11/27/2018 U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS THE NUSCALE POWER, LLC RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION ASSOCIATED WITH THE NUSCALE DESIGN CERTIFICATION APPLICATION MEETING AGENDA October 31, 2018 11:00 - 11:10 AM Introductions and Identification of topics 11:10 - 11:15 AM Discussion of U.S. Nuclear Regulatory Commission Staffs Questions regarding NuScale Power LLCs Response to Request for Additional Information No. 9224, Question 01.05-32 (Open Portion) 11:15 - 11:20 AM Public Comments/Questions 11:20 - 12:30 PM Closed portion Enclosure 1
U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS THE NUSCALE POWER, LLC RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION ASSOCIATED WITH THE NUSCALE DESIGN CERTIFICATION APPLICATION LIST OF ATTENDEES October 31, 2018 Name Organization Getachew Tesfaye U.S. Nuclear Regulatory Commission (NRC)
Michael Dudek NRC Hossein Esmaili NRC Shawn Campbell NRC Jason Schaperow NRC Sheila Ray NRC Paul Infanger NuScale Power, LLC (NuScale)
Etienne Mullin NuScale Scott Weber NuScale Dan Lassiter NuScale Mark Shaver NuScale Paul Guinn NuScale John Hosmer NuScale Enclosure 2
U.S. NUCLEAR REGULATORY COMMISSION OVERVIEW OF THE OCTOBER 31, 2018, TELECONFERENCE TO DISCUSS THE NUSCALE POWER, LLC RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION ASSOCIATED WITH THE NUSCALE DESIGN CERTIFICATION APPLICATION The purpose of this teleconference was to discuss the results of the U.S. Nuclear Regulatory Commission (NRC) staffs review of NuScale Power LLCs (NuScale) Response to Request for Additional Information (RAI) No. 9224, Question 01.05-32. This was a follow-up to the October 3, 2018, public meeting where this topic was first discussed (Agencywide Documents Access and Management Systems (ADAMS) Accession No. ML18299A242).
The following is the summary of the NRC staffs feedback and agreed upon next steps for the resolution of the remaining issues.
- 1. Response to RAI No. 9224, Question 01.05-32 (ADAMS Accession No. ML18212A192):
- a. NRC Feedback: The staff requested clarifications on the applicants responses to RAI 9224 (ADAMS Accession No. ML18212A192) and RAI 9534 (ADAMS Accession No. ML18275A426) related to the NuScale Accident Source Term Topical Report and its implementation in the Final Safety Analysis Report. The staff sought clarifications in areas where novel approaches or assumptions were being used as well as unique features of the NuScale design (e.g., evacuated containment) that might affect the approaches and assumptions taken in the accident source term methodology. The main purpose was to obtain clarifications on two issues related to these RAI responses: the basis for the containment leak rate and the approach for selecting thermal hydraulic conditions for estimating fission product aerosol deposition in the containment.
- b. Next Step: During the meeting, the NuScale provided the clarifications requested by the NRC staff. The NRC staff concluded the meeting by stating that it plans to formally request (through the RAI process) additional information on the basis for the containment leak rate. For the thermal hydraulic conditions being used to estimate fission product aerosol deposition in the containment, the applicant stated it would provide a report for audit that provides technical justification for the applicants approach for selecting thermal hydraulic conditions.
- 2. The proprietary information discussion topics for the closed portion of the meeting, prepared by the NRC staff, can be found in ADAMS (Accession No. ML18327A133).
1 Enclosure 3