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| number = ML19228A250 | | number = ML19228A250 | ||
| issue date = 08/27/2019 | | issue date = 08/27/2019 | ||
| title = Summary of Public Meeting with | | title = Summary of Public Meeting with NuScale to Discuss Structural ITAAC | ||
| author name = Santos C | | author name = Santos C | ||
| author affiliation = NRC/NRO/DLSE/LB1 | | author affiliation = NRC/NRO/DLSE/LB1 | ||
| Line 15: | Line 15: | ||
=Text= | =Text= | ||
{{#Wiki_filter:AUGUST 27, 2019 MEMORANDUM TO: | {{#Wiki_filter:AUGUST 27, 2019 MEMORANDUM TO: | ||
Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors | Samuel S. Lee, Chief Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors FROM: | ||
Cayetano Santos Jr., Project Manager /RA/ | |||
Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors | |||
==SUBJECT:== | ==SUBJECT:== | ||
==SUMMARY== | ==SUMMARY== | ||
OF THE AUGUST 13, 2019, PUBLIC TELECONFERENCE REGARDING THE INSPECTIONS, TESTS, ANALYSES, AND ACCEPTANCE CRITERIA IN NUSCALE POWER, LLCS DESIGN CERTIFICATION APPLICATION On August 13, 2019, a Category 1 public teleconference was held between the U.S. Nuclear Regulatory Commission (NRC) staff and NuScale Power, LLC (NuScale). The purpose of the meeting was to discuss the inspections, tests, analyses, and acceptance criteria (ITAAC) to verify the structural integrity of the reactor building, radioactive waste building, and control building. The meeting notice was posted on the NRC website and is also in the NRCs Agencywide Documents Access and Management System (ADAMS) under Accession Number ML19196A284. The Meeting Summary is provided as Enclosure 1 which captures the summary of topics discussed. The Meeting Agenda and List of Attendees are provided as Enclosures 2 and 3, respectively. | OF THE AUGUST 13, 2019, PUBLIC TELECONFERENCE REGARDING THE INSPECTIONS, TESTS, ANALYSES, AND ACCEPTANCE CRITERIA IN NUSCALE POWER, LLCS DESIGN CERTIFICATION APPLICATION On August 13, 2019, a Category 1 public teleconference was held between the U.S. Nuclear Regulatory Commission (NRC) staff and NuScale Power, LLC (NuScale). The purpose of the meeting was to discuss the inspections, tests, analyses, and acceptance criteria (ITAAC) to verify the structural integrity of the reactor building, radioactive waste building, and control building. The meeting notice was posted on the NRC website and is also in the NRCs Agencywide Documents Access and Management System (ADAMS) under Accession Number ML19196A284. The Meeting Summary is provided as Enclosure 1 which captures the summary of topics discussed. The Meeting Agenda and List of Attendees are provided as Enclosures 2 and 3, respectively. | ||
Docket No. 52-048 | Docket No. 52-048 | ||
==Enclosures:== | ==Enclosures:== | ||
As stated cc w/encl: DC NuScale Power, LLC Listserv CONTACT: Cayetano Santos Jr., NRO/DLSE 301-415-7270 | |||
ML19228A250 | |||
*via email NRO-002 OFFICE DLSE/LB1:PM DLSE/LB1:LA DLSE/LB1:PM NAME CSantos MMoore CSantos (signed) | |||
DATE 08/27/2019 08/27/2019 08/27/2019 | |||
Meeting Summary Public Teleconference Regarding Structural ITAAC August 13, 2019 The discussion was a follow-up of a topic discussed during a public meeting on July 17, 2019 (ADAMS Accession No. ML19212A688). On August 7, 2019, the U.S. Nuclear Regulatory Commission (NRC) staff provided NuScale Power, LLC (NuScale) with proposed revisions to the inspections, tests, analyses, and acceptance criteria (ITAAC) to verify the structural integrity of the reactor building (Enclosure 2). The focus of the meeting was to discuss proposed revisions to this ITAAC. NuScale noted that the existing language for this ITAAC incorporates revisions made in response to Request for Additional Information (RAI) No. 9563 (ADAMS Accession No. ML18302A407) from the NRC staff. Since the proposed revisions shown in eliminate these changes, NuScale asked if incorporating the changes shown in would cause the issues in that RAI to be reopened. The NRC staff confirmed that incorporating the changes shown in Enclosure 2 would not reopen RAI No. 9563. NuScale stated that there were no issues with incorporating the staffs proposed revisions to Tier 2, Section 3.8.4.5.1, Design Summary Report. There was a discussion of the language for the inspections, tests, and analyses (ITA) portion of the ITAAC. At the conclusion of the meeting, the NRC staff agreed to evaluate revised language for the (ITA) to simply state Reconciliation analysis will be performed of the as-built RXB. | |||
Meeting Summary Public Teleconference Regarding Structural ITAAC August 13, 2019 The discussion was a follow-up of a topic discussed during a public meeting on July 17, 2019 (ADAMS Accession No. ML19212A688). On August 7, 2019, the U.S. Nuclear Regulatory Commission (NRC) staff provided NuScale Power, LLC (NuScale) with proposed revisions to the inspections, tests, analyses, and acceptance criteria (ITAAC) to verify the structural integrity of the reactor building (Enclosure 2). The focus of the meeting was to discuss proposed revisions to this ITAAC. NuScale noted that the existing language for this ITAAC incorporates revisions made in response to Request for Additional Information (RAI) No. 9563 (ADAMS Accession No. ML18302A407) from the NRC staff. Since the proposed revisions shown in | |||
There was an opportunity for members of the public to provide comments and ask questions. | There was an opportunity for members of the public to provide comments and ask questions. | ||
No comments or questions were received. | No comments or questions were received. | ||
NRC Markup of NuScales Proposed Structural ITAAC and Section 3.8.4.5.1 | NRC Markup of NuScales Proposed Structural ITAAC and Section 3.8.4.5.1 3.8.4.5.1 Design Summary Report A design summary report is prepared for Seismic Category I structures documenting that the structures meet the acceptance criteria specified in Section 3.7 and Section 3.8. | ||
3.8.4.5.1 Design Summary Report A design summary report is prepared for Seismic Category I structures documenting that the structures meet the acceptance criteria specified in Section 3.7 and Section 3.8. | |||
Deviations from the design due to as-procured or as-built conditions are acceptable based on an evaluation consistent with the methods and procedures of Section 3.7 and Section 3.8 provided the following acceptance criteria are met: | Deviations from the design due to as-procured or as-built conditions are acceptable based on an evaluation consistent with the methods and procedures of Section 3.7 and Section 3.8 provided the following acceptance criteria are met: | ||
the structural design meets the acceptance criteria specified in Section 3.8, and the in-structure seismic response spectra meet the acceptance criteria specified in Section 3.7. | |||
the seismic demand meet the acceptance criteria in Section 3.7. | |||
Deviations from the design are tracked as required by 10 CFR Part 50, Appendix B, Criterion III, Design Control. | Deviations from the design are tracked as required by 10 CFR Part 50, Appendix B, Criterion III, Design Control. | ||
Depending on the extent of the deviations, the evaluation may range from documentation of an engineering judgment to performance of a revised analysis and design. The results of the evaluation will be documented in an as-built summary report. | Depending on the extent of the deviations, the evaluation may range from documentation of an engineering judgment to performance of a revised analysis and design. The results of the evaluation will be documented in an as-built summary report. | ||
Post construction, a Design Summary Report is prepared that documents the results of a reconciliation analysis of the cumulative effect of changes between the approved design and the actual design basis loads and as-built structural components to demonstrate that (1) the computed demand continues to be within the capacity of the structural component and (2) the | Post construction, a Design Summary Report is prepared that documents the results of a reconciliation analysis of the cumulative effect of changes between the approved design and the actual design basis loads and as-built structural components to demonstrate that (1) the computed demand continues to be within the capacity of the structural component and (2) the Design Commitment Inspection, Tests, Analyses Acceptance Criteria The RXB is Seismic Category I and maintains its structural integrity under the design basis loads. | ||
Reconciliation analysis will be performed of the as-built RXB under the actual design basis loads for the as-built RXB. | |||
: i. An inspection and analysis will be performed of the as-built RXB. | |||
ii. An inspection will be performed of the as-built RXB. | |||
: i. A design summary report exists and concludes that (1) the as-built RXB maintains its structural integrity in accordance with the approved design under the actual design basis loads for the as-built RXB, and (2) the in-structure responses for the as-built RXB are enveloped by those in the approved design. the deviations between the drawings used for construction and the as-built RXB have been reconciled, and the RXB maintains its structural integrity under the design basis loads and that all demand to capacity ratios are less than 1.0 (i.e. D/C < 1.0). | |||
ii. The dimensions of the RXB critical sections conform to the approved design. | |||
as-built in-structure seismic response is enveloped by the in-structure seismic response in the approved design. | as-built in-structure seismic response is enveloped by the in-structure seismic response in the approved design. | ||
The design summary report documents that the Seismic Category I structures meet acceptance criteria specified in Section 3.7 and Section 3.8 of the UFSAR. | The design summary report documents that the Seismic Category I structures meet acceptance criteria specified in Section 3.7 and Section 3.8 of the UFSAR. | ||
Deviations from the design are tracked as required by 10 CFR Part 50, Appendix B, and are evaluated consistent with the methods and procedures of Section 3.7 and Section 3.8. Deviations include changes outside applicable tolerances in load, dimension, and configuration between the approved design and as-built structure. Depending on the extent of the deviation, the evaluation may range from documentation of the basis of an engineering judgment to inclusion of the change in the performance of a revised analysis. The results of these evaluations will be documented in the Design Summary Report. | Deviations from the design are tracked as required by 10 CFR Part 50, Appendix B, and are evaluated consistent with the methods and procedures of Section 3.7 and Section 3.8. Deviations include changes outside applicable tolerances in load, dimension, and configuration between the approved design and as-built structure. Depending on the extent of the deviation, the evaluation may range from documentation of the basis of an engineering judgment to inclusion of the change in the performance of a revised analysis. The results of these evaluations will be documented in the Design Summary Report. | ||
Meeting Agenda August 13, 2019 12:00 p.m. - 1:00 p.m. | Meeting Agenda August 13, 2019 12:00 p.m. - 1:00 p.m. | ||
The purpose of this teleconference was for the U.S. Nuclear Regulatory Commission (NRC) staff to discuss structural ITAAC. | The purpose of this teleconference was for the U.S. Nuclear Regulatory Commission (NRC) staff to discuss structural ITAAC. | ||
Time | Time Topic Speaker 12:00 p.m. - 12:05 p.m. | ||
===Introductions=== | |||
All 12:05 p.m. - 12:45 p.m. | |||
Discussion of Structural ITAAC NRC/NuScale 12:45 p.m. - 1:00 p.m. | |||
Public Comments Public 1:00 p.m. | |||
Adjourn All | |||
LIST OF ATTENDEES August 13, 2019 12:00 p.m. - 1:00 p.m. | LIST OF ATTENDEES August 13, 2019 12:00 p.m. - 1:00 p.m. | ||
Name | Name Organization Cayetano Santos U.S. Nuclear Regulatory Commission (NRC) | ||
Bhagwat Jain | Bhagwat Jain NRC Bob Caldwell NRC Nadja Joergensen NuScale Power, LLC (NuScale) | ||
Chris Maxwell | Chris Maxwell NuScale Edan Engstrom NuScale Marty Bryan NuScale Evren Ulku NuScale Spain Abney NuScale}} | ||
Latest revision as of 15:01, 4 January 2025
| ML19228A250 | |
| Person / Time | |
|---|---|
| Site: | NuScale |
| Issue date: | 08/27/2019 |
| From: | Cayetano Santos NRC/NRO/DLSE/LB1 |
| To: | Samson Lee NRC/NRO/DLSE/LB1 |
| Santos C 415-7270 | |
| References | |
| Download: ML19228A250 (7) | |
Text
AUGUST 27, 2019 MEMORANDUM TO:
Samuel S. Lee, Chief Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors FROM:
Cayetano Santos Jr., Project Manager /RA/
Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors
SUBJECT:
SUMMARY
OF THE AUGUST 13, 2019, PUBLIC TELECONFERENCE REGARDING THE INSPECTIONS, TESTS, ANALYSES, AND ACCEPTANCE CRITERIA IN NUSCALE POWER, LLCS DESIGN CERTIFICATION APPLICATION On August 13, 2019, a Category 1 public teleconference was held between the U.S. Nuclear Regulatory Commission (NRC) staff and NuScale Power, LLC (NuScale). The purpose of the meeting was to discuss the inspections, tests, analyses, and acceptance criteria (ITAAC) to verify the structural integrity of the reactor building, radioactive waste building, and control building. The meeting notice was posted on the NRC website and is also in the NRCs Agencywide Documents Access and Management System (ADAMS) under Accession Number ML19196A284. The Meeting Summary is provided as Enclosure 1 which captures the summary of topics discussed. The Meeting Agenda and List of Attendees are provided as Enclosures 2 and 3, respectively.
Docket No.52-048
Enclosures:
As stated cc w/encl: DC NuScale Power, LLC Listserv CONTACT: Cayetano Santos Jr., NRO/DLSE 301-415-7270
- via email NRO-002 OFFICE DLSE/LB1:PM DLSE/LB1:LA DLSE/LB1:PM NAME CSantos MMoore CSantos (signed)
DATE 08/27/2019 08/27/2019 08/27/2019
Meeting Summary Public Teleconference Regarding Structural ITAAC August 13, 2019 The discussion was a follow-up of a topic discussed during a public meeting on July 17, 2019 (ADAMS Accession No. ML19212A688). On August 7, 2019, the U.S. Nuclear Regulatory Commission (NRC) staff provided NuScale Power, LLC (NuScale) with proposed revisions to the inspections, tests, analyses, and acceptance criteria (ITAAC) to verify the structural integrity of the reactor building (Enclosure 2). The focus of the meeting was to discuss proposed revisions to this ITAAC. NuScale noted that the existing language for this ITAAC incorporates revisions made in response to Request for Additional Information (RAI) No. 9563 (ADAMS Accession No. ML18302A407) from the NRC staff. Since the proposed revisions shown in eliminate these changes, NuScale asked if incorporating the changes shown in would cause the issues in that RAI to be reopened. The NRC staff confirmed that incorporating the changes shown in Enclosure 2 would not reopen RAI No. 9563. NuScale stated that there were no issues with incorporating the staffs proposed revisions to Tier 2, Section 3.8.4.5.1, Design Summary Report. There was a discussion of the language for the inspections, tests, and analyses (ITA) portion of the ITAAC. At the conclusion of the meeting, the NRC staff agreed to evaluate revised language for the (ITA) to simply state Reconciliation analysis will be performed of the as-built RXB.
There was an opportunity for members of the public to provide comments and ask questions.
No comments or questions were received.
NRC Markup of NuScales Proposed Structural ITAAC and Section 3.8.4.5.1 3.8.4.5.1 Design Summary Report A design summary report is prepared for Seismic Category I structures documenting that the structures meet the acceptance criteria specified in Section 3.7 and Section 3.8.
Deviations from the design due to as-procured or as-built conditions are acceptable based on an evaluation consistent with the methods and procedures of Section 3.7 and Section 3.8 provided the following acceptance criteria are met:
the structural design meets the acceptance criteria specified in Section 3.8, and the in-structure seismic response spectra meet the acceptance criteria specified in Section 3.7.
the seismic demand meet the acceptance criteria in Section 3.7.
Deviations from the design are tracked as required by 10 CFR Part 50, Appendix B, Criterion III, Design Control.
Depending on the extent of the deviations, the evaluation may range from documentation of an engineering judgment to performance of a revised analysis and design. The results of the evaluation will be documented in an as-built summary report.
Post construction, a Design Summary Report is prepared that documents the results of a reconciliation analysis of the cumulative effect of changes between the approved design and the actual design basis loads and as-built structural components to demonstrate that (1) the computed demand continues to be within the capacity of the structural component and (2) the Design Commitment Inspection, Tests, Analyses Acceptance Criteria The RXB is Seismic Category I and maintains its structural integrity under the design basis loads.
Reconciliation analysis will be performed of the as-built RXB under the actual design basis loads for the as-built RXB.
- i. An inspection and analysis will be performed of the as-built RXB.
ii. An inspection will be performed of the as-built RXB.
- i. A design summary report exists and concludes that (1) the as-built RXB maintains its structural integrity in accordance with the approved design under the actual design basis loads for the as-built RXB, and (2) the in-structure responses for the as-built RXB are enveloped by those in the approved design. the deviations between the drawings used for construction and the as-built RXB have been reconciled, and the RXB maintains its structural integrity under the design basis loads and that all demand to capacity ratios are less than 1.0 (i.e. D/C < 1.0).
ii. The dimensions of the RXB critical sections conform to the approved design.
as-built in-structure seismic response is enveloped by the in-structure seismic response in the approved design.
The design summary report documents that the Seismic Category I structures meet acceptance criteria specified in Section 3.7 and Section 3.8 of the UFSAR.
Deviations from the design are tracked as required by 10 CFR Part 50, Appendix B, and are evaluated consistent with the methods and procedures of Section 3.7 and Section 3.8. Deviations include changes outside applicable tolerances in load, dimension, and configuration between the approved design and as-built structure. Depending on the extent of the deviation, the evaluation may range from documentation of the basis of an engineering judgment to inclusion of the change in the performance of a revised analysis. The results of these evaluations will be documented in the Design Summary Report.
Meeting Agenda August 13, 2019 12:00 p.m. - 1:00 p.m.
The purpose of this teleconference was for the U.S. Nuclear Regulatory Commission (NRC) staff to discuss structural ITAAC.
Time Topic Speaker 12:00 p.m. - 12:05 p.m.
Introductions
All 12:05 p.m. - 12:45 p.m.
Discussion of Structural ITAAC NRC/NuScale 12:45 p.m. - 1:00 p.m.
Public Comments Public 1:00 p.m.
Adjourn All
LIST OF ATTENDEES August 13, 2019 12:00 p.m. - 1:00 p.m.
Name Organization Cayetano Santos U.S. Nuclear Regulatory Commission (NRC)
Bhagwat Jain NRC Bob Caldwell NRC Nadja Joergensen NuScale Power, LLC (NuScale)
Chris Maxwell NuScale Edan Engstrom NuScale Marty Bryan NuScale Evren Ulku NuScale Spain Abney NuScale