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| number = ML17251A863 | | number = ML17251A863 | ||
| issue date = 09/08/2017 | | issue date = 09/08/2017 | ||
| title = | | title = SMR DC RAI - Request for Additional Information No. 217, RAI 9088 (14.3.3) | ||
| author name = | | author name = | ||
| author affiliation = NRC | | author affiliation = NRC | ||
| Line 17: | Line 17: | ||
=Text= | =Text= | ||
{{#Wiki_filter:1 NuScaleDCRaisPEm Resource From: Cranston, Gregory Sent: Friday, September 08, 2017 1:59 PM To: RAI@nuscalepower.com Cc: NuScaleDCRaisPEm Resource; Lee, Samuel | {{#Wiki_filter:1 NuScaleDCRaisPEm Resource From: | ||
; Chowdhury, Prosanta; Lupold, Timothy; Hansing, Nicholas; Murray, Demetrius | Cranston, Gregory Sent: | ||
Friday, September 08, 2017 1:59 PM To: | |||
RAI@nuscalepower.com Cc: | |||
NuScaleDCRaisPEm Resource; Lee, Samuel; Chowdhury, Prosanta; Lupold, Timothy; Hansing, Nicholas; Murray, Demetrius | |||
==Subject:== | ==Subject:== | ||
RE: Request for Additional | RE: Request for Additional Information No. 217, RAI 9088 (14.3.3) | ||
Attachments: | Attachments: | ||
Request for Additional | Request for Additional Information No. 217 (eRAI No. 9088).pdf Attached please find NRC staffs request for additional information 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. | ||
Gregory Cranston, Senior Project Manager Licensing Branch 1 (NuScale) | Gregory Cranston, Senior Project Manager Licensing Branch 1 (NuScale) | ||
Division of New Reactor Licensing Office of New Reactors U.S. Nuclear Regulatory Commission 301-415-0546 | Division of New Reactor Licensing Office of New Reactors U.S. Nuclear Regulatory Commission 301-415-0546 | ||
Hearing Identifier: | Hearing Identifier: | ||
NuScale_SMR_DC_RAI_Public Email Number: | |||
240 Mail Envelope Properties (36d5a8dddeb9436eaccbaf433960761d) | |||
==Subject:== | ==Subject:== | ||
RE: Request for Additional Information No. 217, RAI 9088 (14.3.3) | RE: Request for Additional Information No. 217, RAI 9088 (14.3.3) | ||
Tracking Status: None | Sent Date: | ||
Tracking Status: None | 9/8/2017 1:58:34 PM Received Date: | ||
Tracking Status: None | 9/8/2017 1:58:37 PM From: | ||
Cranston, Gregory Created By: | |||
Gregory.Cranston@nrc.gov Recipients: | |||
"NuScaleDCRaisPEm Resource" <NuScaleDCRaisPEm.Resource@nrc.gov> | |||
Tracking Status: None "Lee, Samuel" <Samuel.Lee@nrc.gov> | |||
Tracking Status: None "Chowdhury, Prosanta" <Prosanta.Chowdhury@nrc.gov> | |||
Tracking Status: None "Lupold, Timothy" <Timothy.Lupold@nrc.gov> | |||
Tracking Status: None "Hansing, Nicholas" <Nicholas.Hansing@nrc.gov> | |||
Tracking Status: None "Murray, Demetrius" <Demetrius.Murray@nrc.gov> | |||
Tracking Status: None "RAI@nuscalepower.com" <RAI@nuscalepower.com> | |||
Tracking Status: None Post Office: | |||
HQPWMSMRS07.nrc.gov Files Size Date & Time MESSAGE 556 9/8/2017 1:58:37 PM Request for Additional Information No. 217 (eRAI No. 9088).pdf 88926 Options Priority: | |||
Standard Return Notification: | |||
No Reply Requested: | |||
No Sensitivity: | |||
Normal Expiration Date: | |||
Recipients Received: | |||
Request for Additional Information No. 217 (eRAI No. 9088) | |||
Issue Date: 09/08/2017 Application | |||
==Title:== | |||
NuScale Standard Design Certification 048 Operating Company: NuScale Power, LLC Docket No. 52-048 Review Section: 14.03.03 - Piping Systems and Components - Inspections, Tests, Analyses, and Acceptance Criteria Application Section: 14.3.3 QUESTIONS 14.03.03-2 10 CFR 52.47, Contents of applications; technical information, specifies the level of design information needed to be submitted to support design certification. 10 CFR 52.47(a)(3)(i) requires that the this design information include the principal design criteria for the facility and notes that Appendix A to 10 CFR part 50, general design criteria (GDC), establishes minimum requirements for the principal design criteria for watercooled nuclear power plants. 10 CFR 50, Appendix A, GDC 2 requires SSCs important to safety be designed to withstand appropriate combinations of the effects of normal and accident conditions with the effects of natural phenomena including earthquake. DCD Tier 1, Rev. 0, Table 2.8-2, ITAAC #1 and Table 3.14-2, ITAAC #1 state that the Seismic Category I equipment, including its associated supports and anchorages, withstands design basis seismic loads without loss of its safety-related function(s) during and after an SSE. However, as stated in DCD Tier 1, Sections 2.8.1 and 3.14.1, these ITAAC are specific to mechanical and electrical/I&C equipment such as valves and sensors. These ITAAC do not include other Seismic Category I SSCs such as control rod guide (CRD) tubes and CRD drive shafts. The NRC staff cannot locate a generic ITAAC that cover all Seismic Category I SSCs. Revise an existing ITAAC or add a generic ITAAC that ensures Seismic Category I SSCs including their associated supports and anchorages withstand design basis loads without loss of their function(s) during and after an SSE.}} | |||
Latest revision as of 11:40, 8 January 2025
| ML17251A863 | |
| Person / Time | |
|---|---|
| Site: | NuScale |
| Issue date: | 09/08/2017 |
| From: | NRC |
| To: | NRC/NRO/DNRL/LB1 |
| References | |
| Download: ML17251A863 (3) | |
Text
1 NuScaleDCRaisPEm Resource From:
Cranston, Gregory Sent:
Friday, September 08, 2017 1:59 PM To:
RAI@nuscalepower.com Cc:
NuScaleDCRaisPEm Resource; Lee, Samuel; Chowdhury, Prosanta; Lupold, Timothy; Hansing, Nicholas; Murray, Demetrius
Subject:
RE: Request for Additional Information No. 217, RAI 9088 (14.3.3)
Attachments:
Request for Additional Information No. 217 (eRAI No. 9088).pdf Attached please find NRC staffs request for additional information 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.
Gregory Cranston, Senior Project Manager Licensing Branch 1 (NuScale)
Division of New Reactor Licensing Office of New Reactors U.S. Nuclear Regulatory Commission 301-415-0546
Hearing Identifier:
NuScale_SMR_DC_RAI_Public Email Number:
240 Mail Envelope Properties (36d5a8dddeb9436eaccbaf433960761d)
Subject:
RE: Request for Additional Information No. 217, RAI 9088 (14.3.3)
Sent Date:
9/8/2017 1:58:34 PM Received Date:
9/8/2017 1:58:37 PM From:
Cranston, Gregory Created By:
Gregory.Cranston@nrc.gov Recipients:
"NuScaleDCRaisPEm Resource" <NuScaleDCRaisPEm.Resource@nrc.gov>
Tracking Status: None "Lee, Samuel" <Samuel.Lee@nrc.gov>
Tracking Status: None "Chowdhury, Prosanta" <Prosanta.Chowdhury@nrc.gov>
Tracking Status: None "Lupold, Timothy" <Timothy.Lupold@nrc.gov>
Tracking Status: None "Hansing, Nicholas" <Nicholas.Hansing@nrc.gov>
Tracking Status: None "Murray, Demetrius" <Demetrius.Murray@nrc.gov>
Tracking Status: None "RAI@nuscalepower.com" <RAI@nuscalepower.com>
Tracking Status: None Post Office:
HQPWMSMRS07.nrc.gov Files Size Date & Time MESSAGE 556 9/8/2017 1:58:37 PM Request for Additional Information No. 217 (eRAI No. 9088).pdf 88926 Options Priority:
Standard Return Notification:
No Reply Requested:
No Sensitivity:
Normal Expiration Date:
Recipients Received:
Request for Additional Information No. 217 (eRAI No. 9088)
Issue Date: 09/08/2017 Application
Title:
NuScale Standard Design Certification 048 Operating Company: NuScale Power, LLC Docket No.52-048 Review Section: 14.03.03 - Piping Systems and Components - Inspections, Tests, Analyses, and Acceptance Criteria Application Section: 14.3.3 QUESTIONS 14.03.03-2 10 CFR 52.47, Contents of applications; technical information, specifies the level of design information needed to be submitted to support design certification. 10 CFR 52.47(a)(3)(i) requires that the this design information include the principal design criteria for the facility and notes that Appendix A to 10 CFR part 50, general design criteria (GDC), establishes minimum requirements for the principal design criteria for watercooled nuclear power plants. 10 CFR 50, Appendix A, GDC 2 requires SSCs important to safety be designed to withstand appropriate combinations of the effects of normal and accident conditions with the effects of natural phenomena including earthquake. DCD Tier 1, Rev. 0, Table 2.8-2, ITAAC #1 and Table 3.14-2, ITAAC #1 state that the Seismic Category I equipment, including its associated supports and anchorages, withstands design basis seismic loads without loss of its safety-related function(s) during and after an SSE. However, as stated in DCD Tier 1, Sections 2.8.1 and 3.14.1, these ITAAC are specific to mechanical and electrical/I&C equipment such as valves and sensors. These ITAAC do not include other Seismic Category I SSCs such as control rod guide (CRD) tubes and CRD drive shafts. The NRC staff cannot locate a generic ITAAC that cover all Seismic Category I SSCs. Revise an existing ITAAC or add a generic ITAAC that ensures Seismic Category I SSCs including their associated supports and anchorages withstand design basis loads without loss of their function(s) during and after an SSE.