ML18059A709: Difference between revisions
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{{#Wiki_filter:NuScaleDCRaisPEm Resource From: | {{#Wiki_filter:1 NuScaleDCRaisPEm Resource From: | ||
Chowdhury, Prosanta Sent: | |||
Wednesday, February 28, 2018 1:37 PM To: | |||
'RAI@nuscalepower.com' Cc: | |||
Lee, Samuel; Cranston, Gregory; Vera Amadiz, Marieliz; Lupold, Timothy; Hansing, Nicholas; Tabatabai, Omid; NuScaleDCRaisPEm Resource | |||
==Subject:== | ==Subject:== | ||
Request for Additional Information No. 374 RAI No. 9389 (03.09.04) | Request for Additional Information No. 374 RAI No. 9389 (03.09.04) | ||
Attachments: | Attachments: | ||
Request for Additional Information No. 374 (eRAI No. 9389).pdf Attached please find NRC staffs request for additional information (RAI) concerning review of the NuScale Design Certification Application. | |||
Please submit your technically correct and complete response within 60 days of the date of this RAI to the NRC Document Control Desk. | Please submit your technically correct and complete response within 60 days of the date of this RAI to the NRC Document Control Desk. | ||
If you have any questions, please contact me. | If you have any questions, please contact me. | ||
Thank you. | Thank you. | ||
Prosanta Chowdhury, Project Manager Licensing Branch 1 (NuScale) | Prosanta Chowdhury, Project Manager Licensing Branch 1 (NuScale) | ||
Division of New Reactor Licensing Office of New Reactors U.S. Nuclear Regulatory Commission 301-415-1647 | Division of New Reactor Licensing Office of New Reactors U.S. Nuclear Regulatory Commission 301-415-1647 | ||
Hearing Identifier: | Hearing Identifier: | ||
NuScale_SMR_DC_RAI_Public Email Number: | |||
402 Mail Envelope Properties (DM5PR0901MB218294DA0B9BA6051DEDBB079EC70) | |||
==Subject:== | ==Subject:== | ||
Request for Additional Information No. 374 RAI No. 9389 (03.09.04) | Request for Additional Information No. 374 RAI No. 9389 (03.09.04) | ||
Sent Date: | Sent Date: | ||
2/28/2018 1:37:09 PM Received Date: | |||
2/28/2018 1:37:18 PM From: | |||
Chowdhury, Prosanta Created By: | |||
Prosanta.Chowdhury@nrc.gov Recipients: | |||
"Lee, Samuel" <Samuel.Lee@nrc.gov> | "Lee, Samuel" <Samuel.Lee@nrc.gov> | ||
Tracking Status: None "Cranston, Gregory" <Gregory.Cranston@nrc.gov> | Tracking Status: None "Cranston, Gregory" <Gregory.Cranston@nrc.gov> | ||
| Line 40: | Line 51: | ||
Tracking Status: None "Tabatabai, Omid" <Omid.Tabatabai-Yazdi@nrc.gov> | Tracking Status: None "Tabatabai, Omid" <Omid.Tabatabai-Yazdi@nrc.gov> | ||
Tracking Status: None "NuScaleDCRaisPEm Resource" <NuScaleDCRaisPEm.Resource@nrc.gov> | Tracking Status: None "NuScaleDCRaisPEm Resource" <NuScaleDCRaisPEm.Resource@nrc.gov> | ||
Tracking Status: None | Tracking Status: None | ||
"'RAI@nuscalepower.com'" <RAI@nuscalepower.com> | "'RAI@nuscalepower.com'" <RAI@nuscalepower.com> | ||
Tracking Status: None Post Office: | Tracking Status: None Post Office: | ||
Recipients Received: | DM5PR0901MB2182.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 561 2/28/2018 1:37:18 PM Request for Additional Information No. 374 (eRAI No. 9389).pdf 88788 Options Priority: | ||
Standard Return Notification: | |||
No Reply Requested: | |||
No Sensitivity: | |||
Normal Expiration Date: | |||
Recipients Received: | |||
Request for Additional Information No. 374 (eRAI No. 9389) | Request for Additional Information No. 374 (eRAI No. 9389) | ||
| Line 52: | Line 68: | ||
QUESTIONS 03.09.04-12 The NRC regulations in Appendix A, General Design Criteria for Nuclear Power Plants, to 10 CFR Part 50 specify principal design criteria to establish the necessary design, fabrication, construction, testing, and performance requirements for structures, systems, and components (SSCs) important to safety; that is, SSCs that provide reasonable assurance that the facility can be operated without undue risk to the health and safety of the public. The control rod drive shaft is one such SSC. | QUESTIONS 03.09.04-12 The NRC regulations in Appendix A, General Design Criteria for Nuclear Power Plants, to 10 CFR Part 50 specify principal design criteria to establish the necessary design, fabrication, construction, testing, and performance requirements for structures, systems, and components (SSCs) important to safety; that is, SSCs that provide reasonable assurance that the facility can be operated without undue risk to the health and safety of the public. The control rod drive shaft is one such SSC. | ||
General Design Criterion (GDC) 1, Quality standards and records, in 10 CFR Part 50, Appendix A, (as further specified in 10 CFR 50.55a), requires that this SSC be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed In previous RAIs 8835, Question 03.09.04-8 and 9181, Question 03.09.04-10, the applicant has established that the control rod drive shaft will be considered an ASME BPV Code, Subsection NG internal structure. As internal structures have no requirement beyond the Certificate Holder certifying that the internal structure shall not adversely affect the integrity of the core support structure, unless specifically stipulated, the applicant specified the following: | General Design Criterion (GDC) 1, Quality standards and records, in 10 CFR Part 50, Appendix A, (as further specified in 10 CFR 50.55a), requires that this SSC be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed In previous RAIs 8835, Question 03.09.04-8 and 9181, Question 03.09.04-10, the applicant has established that the control rod drive shaft will be considered an ASME BPV Code, Subsection NG internal structure. As internal structures have no requirement beyond the Certificate Holder certifying that the internal structure shall not adversely affect the integrity of the core support structure, unless specifically stipulated, the applicant specified the following: | ||
x | x CRD shaft scram loads and control rod drive shaft deflection limits will be established by testing. | ||
CRD shaft scram and SEE loads are added to FSAR Table 3.9-6 for Service Level A and D loading combinations for control rod drive shafts. | CRD shaft scram and SEE loads are added to FSAR Table 3.9-6 for Service Level A and D loading combinations for control rod drive shafts. | ||
x | x The control rod drive shafts are evaluated against the limits of NG-3222.1 and NG-3222.2 for normal operating (Service Level A) conditions. Service Level A loads for the control rod drive shafts are the deadweight of the control rod assembly and scram loading. | ||
x | x The control rod drive shafts are evaluated against 110% of the limits of NG-3222.1 and NG-3222.2 for Service Level D loads. Consideration of cyclic loading is not required. | ||
x | x Martensitic stainless steel materials used in the control rod drive shafts shall be Cv tested in accordance with NG-2331. | ||
The above information should be incorporated into the DCD, as well as a pointer provided to the additional requirements for control rod drive system materials located in Section 4.5.1 of the DCD. This information supports GDC 1 as mentioned above Also, in the response to 03.09.04-8, BPCV should be BPVC, and in the response to 03.09.04-10, SEE should be SSE in the first bullet point. | The above information should be incorporated into the DCD, as well as a pointer provided to the additional requirements for control rod drive system materials located in Section 4.5.1 of the DCD. This information supports GDC 1 as mentioned above Also, in the response to 03.09.04-8, BPCV should be BPVC, and in the response to 03.09.04-10, SEE should be SSE in the first bullet point. | ||
Finally, in the response to 03.09.04-10, the addition to FSAR Table 3.9-6 (SCRAM) requires a corresponding addition to FSAR Table 3.9-2, as the term SCRAM is currently undefined.}} | Finally, in the response to 03.09.04-10, the addition to FSAR Table 3.9-6 (SCRAM) requires a corresponding addition to FSAR Table 3.9-2, as the term SCRAM is currently undefined.}} | ||
Latest revision as of 07:44, 6 January 2025
| ML18059A709 | |
| Person / Time | |
|---|---|
| Site: | NuScale |
| Issue date: | 02/28/2018 |
| From: | NRC |
| To: | NRC/NRO/DNRL/LB1 |
| References | |
| Download: ML18059A709 (3) | |
Text
1 NuScaleDCRaisPEm Resource From:
Chowdhury, Prosanta Sent:
Wednesday, February 28, 2018 1:37 PM To:
'RAI@nuscalepower.com' Cc:
Lee, Samuel; Cranston, Gregory; Vera Amadiz, Marieliz; Lupold, Timothy; Hansing, Nicholas; Tabatabai, Omid; NuScaleDCRaisPEm Resource
Subject:
Request for Additional Information No. 374 RAI No. 9389 (03.09.04)
Attachments:
Request for Additional Information No. 374 (eRAI No. 9389).pdf Attached please find NRC staffs request for additional information (RAI) concerning review of the NuScale Design Certification Application.
Please submit your technically correct and complete response within 60 days of the date of this RAI to the NRC Document Control Desk.
If you have any questions, please contact me.
Thank you.
Prosanta Chowdhury, Project Manager Licensing Branch 1 (NuScale)
Division of New Reactor Licensing Office of New Reactors U.S. Nuclear Regulatory Commission 301-415-1647
Hearing Identifier:
NuScale_SMR_DC_RAI_Public Email Number:
402 Mail Envelope Properties (DM5PR0901MB218294DA0B9BA6051DEDBB079EC70)
Subject:
Request for Additional Information No. 374 RAI No. 9389 (03.09.04)
Sent Date:
2/28/2018 1:37:09 PM Received Date:
2/28/2018 1:37:18 PM From:
Chowdhury, Prosanta Created By:
Prosanta.Chowdhury@nrc.gov Recipients:
"Lee, Samuel" <Samuel.Lee@nrc.gov>
Tracking Status: None "Cranston, Gregory" <Gregory.Cranston@nrc.gov>
Tracking Status: None "Vera Amadiz, Marieliz" <Marieliz.VeraAmadiz@nrc.gov>
Tracking Status: None "Lupold, Timothy" <Timothy.Lupold@nrc.gov>
Tracking Status: None "Hansing, Nicholas" <Nicholas.Hansing@nrc.gov>
Tracking Status: None "Tabatabai, Omid" <Omid.Tabatabai-Yazdi@nrc.gov>
Tracking Status: None "NuScaleDCRaisPEm Resource" <NuScaleDCRaisPEm.Resource@nrc.gov>
Tracking Status: None
"'RAI@nuscalepower.com'" <RAI@nuscalepower.com>
Tracking Status: None Post Office:
DM5PR0901MB2182.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 561 2/28/2018 1:37:18 PM Request for Additional Information No. 374 (eRAI No. 9389).pdf 88788 Options Priority:
Standard Return Notification:
No Reply Requested:
No Sensitivity:
Normal Expiration Date:
Recipients Received:
Request for Additional Information No. 374 (eRAI No. 9389)
Issue Date: 02/28/2018 Application
Title:
NuScale Standard Design Certification 048 Operating Company: NuScale Power, LLC Docket No.52-048 Review Section: 03.09.04 - Control Rod Drive Systems Application Section:
QUESTIONS 03.09.04-12 The NRC regulations in Appendix A, General Design Criteria for Nuclear Power Plants, to 10 CFR Part 50 specify principal design criteria to establish the necessary design, fabrication, construction, testing, and performance requirements for structures, systems, and components (SSCs) important to safety; that is, SSCs that provide reasonable assurance that the facility can be operated without undue risk to the health and safety of the public. The control rod drive shaft is one such SSC.
General Design Criterion (GDC) 1, Quality standards and records, in 10 CFR Part 50, Appendix A, (as further specified in 10 CFR 50.55a), requires that this SSC be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed In previous RAIs 8835, Question 03.09.04-8 and 9181, Question 03.09.04-10, the applicant has established that the control rod drive shaft will be considered an ASME BPV Code, Subsection NG internal structure. As internal structures have no requirement beyond the Certificate Holder certifying that the internal structure shall not adversely affect the integrity of the core support structure, unless specifically stipulated, the applicant specified the following:
x CRD shaft scram loads and control rod drive shaft deflection limits will be established by testing.
CRD shaft scram and SEE loads are added to FSAR Table 3.9-6 for Service Level A and D loading combinations for control rod drive shafts.
x The control rod drive shafts are evaluated against the limits of NG-3222.1 and NG-3222.2 for normal operating (Service Level A) conditions. Service Level A loads for the control rod drive shafts are the deadweight of the control rod assembly and scram loading.
x The control rod drive shafts are evaluated against 110% of the limits of NG-3222.1 and NG-3222.2 for Service Level D loads. Consideration of cyclic loading is not required.
x Martensitic stainless steel materials used in the control rod drive shafts shall be Cv tested in accordance with NG-2331.
The above information should be incorporated into the DCD, as well as a pointer provided to the additional requirements for control rod drive system materials located in Section 4.5.1 of the DCD. This information supports GDC 1 as mentioned above Also, in the response to 03.09.04-8, BPCV should be BPVC, and in the response to 03.09.04-10, SEE should be SSE in the first bullet point.
Finally, in the response to 03.09.04-10, the addition to FSAR Table 3.9-6 (SCRAM) requires a corresponding addition to FSAR Table 3.9-2, as the term SCRAM is currently undefined.