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{{#Wiki_filter:/RA/}} | {{#Wiki_filter:April 17, 2019 MEMORANDUM TO: Samuel S. Lee, Chief Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors FROM: Marieliz Vera, Project Manager /RA/ | ||
Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors | |||
==SUBJECT:== | |||
==SUMMARY== | |||
OF THE AUGUST 23, 2018, CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC. DESIGN CERTIFICATION APPLICATION SECTION 3.6.3, LEAK-BEFORE-BREAK EVALUATION PROCEDURES, AND SECTION 3.9.4, CONTROL ROD DRIVE SYSTEM The U.S. Nuclear Regulatory Commission (NRC) held a Category 1 public teleconference on August 23, 2018, to discuss Final Safety Analysis Report (FSAR) Tier 2, Chapter 3, Design of Structures, Systems, Components and Equipment, Section 3.6.3, Leak-Before-Break Evaluation Procedures and Section 3.9.4, Control Rod Drive System, of the NuScale Power, LLC (NuScale) Design Certification. | |||
The public meeting notice can be found in the Agencywide Documents Access and Management Systems under Accession No. ML18235A512. This meeting notice was also posted on the NRC public website. | |||
The Meeting Agenda and List of Attendees can be found in Enclosures 1 and 2, respectively. | |||
The Technical Issues discussed are included in Enclosure 3. | |||
Summary: | |||
The purpose of this meeting was to discuss the responses for Request for Additional Information (RAI) 9113, Question 03.06.03-2, Question 03.06.03-9 (ML18204A141), and NuScale Power, LLC. Submittal of Changes to Final Safety Analysis Report Section 3.9.4.4, Control Rod Drive System Operability Assurance Program and Section 1.8, Interfaces with Certified Design. (ML18200A443). | |||
CONTACT: Marieliz Vera, NRO/DLSE/LB1 301-415-5861 | |||
S. Lee For RAI 9113, Question 03.06.03-9, the applicant will provide a supplement to the RAI response reflecting the staffs feedback (Enclosure 3). For Question 03.06.03-2, the two options described on the staffs feedback were discussed and NuScale communicated that it needs to go back and notify the NRC later if it can supplement the response with any of the two options. | |||
For the design change in Section 3.9.4, in the FSAR change letter, the staff noticed that NuScale removed some information from FSAR, Revision 0. The staff discussed that some of that information was necessary and is requested to be re-added. NuScale agreed to add the necessary information and the change will apply to Revision 3 of the FSAR. | |||
Docket No. 52-048 | |||
==Enclosures:== | |||
As stated cc w/encls.: DC NuScale Power, LLC Listserv | |||
ML18348A944 *via email NRC-002 OFFICE NRO/DLSE/LB1: PM NRO/DLSE/LB1: LA NRO/DNRL/LB1: PM NAME MVera CSmith MVera DATE 12/11/2018 01/22/2019 04/17/2019 | |||
U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC. | |||
DESIGN CERTIFICATION APPLICATION SECTION 3.6.3, LEAK-BEFORE-BREAK EVALUATION PROCEDURES, AND SECTION 3.9.4, CONTROL ROD DRIVE SYSTEM Meeting Agenda August 23, 2018 11:00 a.m. - 12:30 p.m. | |||
Public Meeting 11:00 a.m. - 11:05 a.m. Welcome and Introductions 11:05 a.m. - 11:30 a.m. Discussion of the Request for Additional Information 9113 11:30 a.m. 40 a.m. Public - Questions and Comments 11:40 a.m. - 12:20 p.m. Discussion on FSAR change Section 3.9.4 12:20 p.m. - 12:30 p.m. Public - Questions and Comments 12:30 p.m. Adjourn Enclosure 1 | |||
U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC. | |||
DESIGN CERTIFICATION APPLICATION SECTION 3.6.3, LEAK-BEFORE-BREAK EVALUATION PROCEDURES, AND SECTION 3.9.4, CONTROL ROD DRIVE SYSTEM List of Attendees August 23, 2018 NAME AFFILIATION Marieliz Vera U.S. Nuclear regulatory Commission (NRC) | |||
Eric Reichelt NRC Nicholas Hansing NRC Timothy Lupold NRC Prabhat Krishnaswamy NRC contractor Gery Wilkowski NRC contractor Mo Uddin NRC contractor Elizabeth Twombly NRC contractor Marty Bryan NuScale Power, LLC (NuScale) | |||
Wayne Massie NuScale Daniel Diefendorf NuScale Nadja Joergensen NuScale Pei-Yuan Cheng NuScale Greg Myers NuScale Derek Noel NuScale Enclosure 2 | |||
U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC. | |||
DESIGN CERTIFICATION APPLICATION SECTION 3.6.3, LEAK-BEFORE-BREAK EVALUATION PROCEDURES, AND SECTION 3.9.4, CONTROL ROD DRIVE SYSTEM The Staffs Feedback on Request Additional for Information (RAI) 9113 Question 03.06.03-02 NuScale has responded with the maximum strain induced from the cold bending process. | |||
However, NuScale has not indicated whether they have data to confirm that a cold working strain can increase the susceptibility of the material to systems, and components (SCC) - which was part of the RAI. NuScale has indicated that only if the fracture toughness reduction affects the applicability of the limit load analysis methodology used for leak-before-break (LBB), the cold-worked pipes will be solution annealed. | |||
If NuScale intends to solution anneal all cold worked austenitic piping, the issue of SCC susceptibility would be resolved, and RAI 9113, Question 03.06.03-02 may be closed. | |||
Question 03.06.03-09 This RAI is directly related to the request for additional data from NuScale for Emc2 to conduct independent confirmatory analysis of its LBB procedure and results. In its response, NuScale provided axial forces and resultant moments at various weld locations (total of 36) for Main Steam (MS) Line 1 and 2, and Feed Water Line 1 and 2. The results also include axial forces and resultant moments for various loading conditions such as deadweight (DW), thermal (TH), | |||
pressure (PR), safe shutdown earthquake (SSE), and seismic anchor motion (SAM) at each location. | |||
Emc2 has reviewed the data carefully to determine if they are sufficient to proceed with the confirmatory analyses, using one preliminary example case. The staff attempted to duplicate the normal and maximum stresses at one weld location in the MS Line 1 - which corresponds to one specific point in the smooth bounding analysis curve (SBAC) curve in Figure 3.6-24 using equations (3.6-6 to 3.6-8) provided in Section 3.6.3.3.2 of the FSAR. In doing so, Emc2 found that the data provided by NuScale are not completely adequate and additional data, i.e. all three component values (Mx, My and Mz) of resultant moment for each loading conditions (i.e. DW, TH, PR, SSE and SAM) at 36 weld locations are required - as the resultant moment alone was not sufficient. | |||
NuScale is requested to provide this additional data so the confirmatory analyses can move forward as planned. | |||
Enclosure 3}} | |||
Revision as of 09:23, 20 October 2019
| ML18348A944 | |
| Person / Time | |
|---|---|
| Site: | NuScale |
| Issue date: | 04/17/2019 |
| From: | Amadiz Marieliz Vera NRC/NRO/DLSE/LB1 |
| To: | Samson Lee NRC/NRO/DLSE/LB1 |
| Vera A M/NRO/5861 | |
| References | |
| Download: ML18348A944 (6) | |
Text
April 17, 2019 MEMORANDUM TO: Samuel S. Lee, Chief Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors FROM: Marieliz Vera, Project Manager /RA/
Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors
SUBJECT:
SUMMARY
OF THE AUGUST 23, 2018, CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC. DESIGN CERTIFICATION APPLICATION SECTION 3.6.3, LEAK-BEFORE-BREAK EVALUATION PROCEDURES, AND SECTION 3.9.4, CONTROL ROD DRIVE SYSTEM The U.S. Nuclear Regulatory Commission (NRC) held a Category 1 public teleconference on August 23, 2018, to discuss Final Safety Analysis Report (FSAR) Tier 2, Chapter 3, Design of Structures, Systems, Components and Equipment, Section 3.6.3, Leak-Before-Break Evaluation Procedures and Section 3.9.4, Control Rod Drive System, of the NuScale Power, LLC (NuScale) Design Certification.
The public meeting notice can be found in the Agencywide Documents Access and Management Systems under Accession No. ML18235A512. This meeting notice was also posted on the NRC public website.
The Meeting Agenda and List of Attendees can be found in Enclosures 1 and 2, respectively.
The Technical Issues discussed are included in Enclosure 3.
Summary:
The purpose of this meeting was to discuss the responses for Request for Additional Information (RAI) 9113, Question 03.06.03-2, Question 03.06.03-9 (ML18204A141), and NuScale Power, LLC. Submittal of Changes to Final Safety Analysis Report Section 3.9.4.4, Control Rod Drive System Operability Assurance Program and Section 1.8, Interfaces with Certified Design. (ML18200A443).
CONTACT: Marieliz Vera, NRO/DLSE/LB1 301-415-5861
S. Lee For RAI 9113, Question 03.06.03-9, the applicant will provide a supplement to the RAI response reflecting the staffs feedback (Enclosure 3). For Question 03.06.03-2, the two options described on the staffs feedback were discussed and NuScale communicated that it needs to go back and notify the NRC later if it can supplement the response with any of the two options.
For the design change in Section 3.9.4, in the FSAR change letter, the staff noticed that NuScale removed some information from FSAR, Revision 0. The staff discussed that some of that information was necessary and is requested to be re-added. NuScale agreed to add the necessary information and the change will apply to Revision 3 of the FSAR.
Docket No.52-048
Enclosures:
As stated cc w/encls.: DC NuScale Power, LLC Listserv
ML18348A944 *via email NRC-002 OFFICE NRO/DLSE/LB1: PM NRO/DLSE/LB1: LA NRO/DNRL/LB1: PM NAME MVera CSmith MVera DATE 12/11/2018 01/22/2019 04/17/2019
U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC.
DESIGN CERTIFICATION APPLICATION SECTION 3.6.3, LEAK-BEFORE-BREAK EVALUATION PROCEDURES, AND SECTION 3.9.4, CONTROL ROD DRIVE SYSTEM Meeting Agenda August 23, 2018 11:00 a.m. - 12:30 p.m.
Public Meeting 11:00 a.m. - 11:05 a.m. Welcome and Introductions 11:05 a.m. - 11:30 a.m. Discussion of the Request for Additional Information 9113 11:30 a.m. 40 a.m. Public - Questions and Comments 11:40 a.m. - 12:20 p.m. Discussion on FSAR change Section 3.9.4 12:20 p.m. - 12:30 p.m. Public - Questions and Comments 12:30 p.m. Adjourn Enclosure 1
U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC.
DESIGN CERTIFICATION APPLICATION SECTION 3.6.3, LEAK-BEFORE-BREAK EVALUATION PROCEDURES, AND SECTION 3.9.4, CONTROL ROD DRIVE SYSTEM List of Attendees August 23, 2018 NAME AFFILIATION Marieliz Vera U.S. Nuclear regulatory Commission (NRC)
Eric Reichelt NRC Nicholas Hansing NRC Timothy Lupold NRC Prabhat Krishnaswamy NRC contractor Gery Wilkowski NRC contractor Mo Uddin NRC contractor Elizabeth Twombly NRC contractor Marty Bryan NuScale Power, LLC (NuScale)
Wayne Massie NuScale Daniel Diefendorf NuScale Nadja Joergensen NuScale Pei-Yuan Cheng NuScale Greg Myers NuScale Derek Noel NuScale Enclosure 2
U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC.
DESIGN CERTIFICATION APPLICATION SECTION 3.6.3, LEAK-BEFORE-BREAK EVALUATION PROCEDURES, AND SECTION 3.9.4, CONTROL ROD DRIVE SYSTEM The Staffs Feedback on Request Additional for Information (RAI) 9113 Question 03.06.03-02 NuScale has responded with the maximum strain induced from the cold bending process.
However, NuScale has not indicated whether they have data to confirm that a cold working strain can increase the susceptibility of the material to systems, and components (SCC) - which was part of the RAI. NuScale has indicated that only if the fracture toughness reduction affects the applicability of the limit load analysis methodology used for leak-before-break (LBB), the cold-worked pipes will be solution annealed.
If NuScale intends to solution anneal all cold worked austenitic piping, the issue of SCC susceptibility would be resolved, and RAI 9113, Question 03.06.03-02 may be closed.
Question 03.06.03-09 This RAI is directly related to the request for additional data from NuScale for Emc2 to conduct independent confirmatory analysis of its LBB procedure and results. In its response, NuScale provided axial forces and resultant moments at various weld locations (total of 36) for Main Steam (MS) Line 1 and 2, and Feed Water Line 1 and 2. The results also include axial forces and resultant moments for various loading conditions such as deadweight (DW), thermal (TH),
pressure (PR), safe shutdown earthquake (SSE), and seismic anchor motion (SAM) at each location.
Emc2 has reviewed the data carefully to determine if they are sufficient to proceed with the confirmatory analyses, using one preliminary example case. The staff attempted to duplicate the normal and maximum stresses at one weld location in the MS Line 1 - which corresponds to one specific point in the smooth bounding analysis curve (SBAC) curve in Figure 3.6-24 using equations (3.6-6 to 3.6-8) provided in Section 3.6.3.3.2 of the FSAR. In doing so, Emc2 found that the data provided by NuScale are not completely adequate and additional data, i.e. all three component values (Mx, My and Mz) of resultant moment for each loading conditions (i.e. DW, TH, PR, SSE and SAM) at 36 weld locations are required - as the resultant moment alone was not sufficient.
NuScale is requested to provide this additional data so the confirmatory analyses can move forward as planned.
Enclosure 3