ML18004A530
| ML18004A530 | |
| Person / Time | |
|---|---|
| Site: | NuScale |
| Issue date: | 01/04/2018 |
| From: | NRC |
| To: | NRC/NRO/DNRL/LB1 |
| References | |
| Download: ML18004A530 (3) | |
Text
1 NuScaleDCRaisPEm Resource From:
Cranston, Gregory Sent:
Thursday, January 04, 2018 12:57 PM To:
RAI@nuscalepower.com Cc:
NuScaleDCRaisPEm Resource; Lee, Samuel; Chowdhury, Prosanta; Karas, Rebecca; Burja, Alexandra; Franovich, Rani; Schmidt, Jeffrey
Subject:
Request for Additional Information No. 321 RAI No. 9092 (15.4.1)
Attachments:
Request for Additional Information No. 321 (eRAI No. 9092).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:
348 Mail Envelope Properties (CY4PR09MB128721E1CF4D74F1FA39A202901F0)
Subject:
Request for Additional Information No. 321 RAI No. 9092 (15.4.1)
Sent Date:
1/4/2018 12:56:46 PM Received Date:
1/4/2018 12:56:51 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 "Karas, Rebecca" <Rebecca.Karas@nrc.gov>
Tracking Status: None "Burja, Alexandra" <Alexandra.Burja@nrc.gov>
Tracking Status: None "Franovich, Rani" <Rani.Franovich@nrc.gov>
Tracking Status: None "Schmidt, Jeffrey" <Jeffrey.Schmidt2@nrc.gov>
Tracking Status: None "RAI@nuscalepower.com" <RAI@nuscalepower.com>
Tracking Status: None Post Office:
CY4PR09MB1287.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 556 1/4/2018 12:56:51 PM Request for Additional Information No. 321 (eRAI No. 9092).pdf 55613 Options Priority:
Standard Return Notification:
No Reply Requested:
No Sensitivity:
Normal Expiration Date:
Recipients Received:
Request for Additional Information No. 321 (eRAI No. 9092)
Issue Date: 01/04/2018 Application
Title:
NuScale Standard Design Certification 048 Operating Company: NuScale Power, LLC Docket No.52-048 Review Section: 15.04.01 - Uncontrolled Control Rod Assembly Withdrawal from a Subcritical or Low Power Startup Condition Application Section: 15.4.1 QUESTIONS 15.04.01-3 Standard Review Plan (SRP) Section 15.4.1, Uncontrolled Control Rod Assembly Withdrawal from a Subcritical or Low Power Startup Position; SRP Section 15.4.2, Uncontrolled Control Rod Assembly Withdrawal at Power; and SRP Section 15.4.3, Control Rod Misoperation (System Malfunction or Operator Error), provide guidance for complying with Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix A, General Design Criteria [(GDC)]
for Nuclear Power Plants, 10, Reactor design; 13, Instrumentation and control; 17, Electric power systems; 20, Protection system functions;; and 25, Protection system requirements for reactivity control malfunctions. Per the above SRP sections, the reviewer is to evaluate whether the initial conditions and parameter values selected for each analysis are justified. In addition, the reviewer is to evaluate the sequence of events to ensure it is justified based upon expected values of relevant monitored parameters and instrument indications.
Reactor coolant system (RCS) pressure is one acceptance criterion for anticipated operational occurrences. The staff notes that Final Safety Analysis Report (FSAR) Tier 2, Sections 15.4.1 through 15.4.3, evaluate limiting RCS pressure scenarios but do not provide the key inputs or the sequence of events for these scenarios. To enable the staff to evaluate whether the initial conditions/parameter values and sequence of events for the limiting RCS pressure scenarios are justified, please provide the following: