ML18088A018: Difference between revisions

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Request for Additional Information No. 402 (eRAI No. 9449)
Request for Additional Information No. 402 (eRAI No. 9449)
Issue Date: 03/29/2018 Application Title: NuScale Standard Design Certification 048 Operating Company: NuScale Power, LLC Docket No. 52-048 Review Section: 04.03 - Nuclear Design Application Section:
Issue Date: 03/29/2018 Application
 
==Title:==
NuScale Standard Design Certification 048 Operating Company: NuScale Power, LLC Docket No. 52-048 Review Section: 04.03 - Nuclear Design Application Section:
QUESTIONS 04.03-2 GDC 10, Reactor design, requires that the reactor core and associated coolant, control, and protection systems be designed with appropriate margin to assure that specified acceptable design limits (SAFDLs) are not exceeded during any condition of normal operation, including the effects of anticipate operational occurrences. GDC 25, Protection system requirements for reactivity control malfunctions, requires that the protection system be designed to assure that SAFDLs are not exceeded for any single malfunction of the reactivity control systems. FSAR, Tier 2, Section 4.3.1 states that the control system withdrawal rate is designed to assure that SAFDLs are not exceeded for accidental withdrawal of control rods; FSAR, Tier 2, Section 15.4.1.2 states that the transient analyses assume a maximum allowed control rod assembly (CRA) withdrawal rate of 15 in/min; and FSAR Tier 2, Table 14.2-80 states that Test #80 will verify that the rod insertion and withdrawal speeds are within design limits. NRC staff did not identify design information regarding a specific limit on the withdrawal speed. NRC staff needs to establish a finding that the transient and accident analyses are performed using suitably conservative values for CRA withdrawal rate. Accordingly, NRC staff requests that the applicant update FSAR, Tier 2, Section 4.3 to specify a design limit on CRA withdrawal rate.}}
QUESTIONS 04.03-2 GDC 10, Reactor design, requires that the reactor core and associated coolant, control, and protection systems be designed with appropriate margin to assure that specified acceptable design limits (SAFDLs) are not exceeded during any condition of normal operation, including the effects of anticipate operational occurrences. GDC 25, Protection system requirements for reactivity control malfunctions, requires that the protection system be designed to assure that SAFDLs are not exceeded for any single malfunction of the reactivity control systems. FSAR, Tier 2, Section 4.3.1 states that the control system withdrawal rate is designed to assure that SAFDLs are not exceeded for accidental withdrawal of control rods; FSAR, Tier 2, Section 15.4.1.2 states that the transient analyses assume a maximum allowed control rod assembly (CRA) withdrawal rate of 15 in/min; and FSAR Tier 2, Table 14.2-80 states that Test #80 will verify that the rod insertion and withdrawal speeds are within design limits. NRC staff did not identify design information regarding a specific limit on the withdrawal speed. NRC staff needs to establish a finding that the transient and accident analyses are performed using suitably conservative values for CRA withdrawal rate. Accordingly, NRC staff requests that the applicant update FSAR, Tier 2, Section 4.3 to specify a design limit on CRA withdrawal rate.}}

Revision as of 18:02, 30 November 2019

2018/03/29 Nuscale SMR DC RAI - Request for Additional Information No. 402 Erai No. 9449 (04.03)
ML18088A018
Person / Time
Site: NuScale
Issue date: 03/29/2018
From:
NRC
To:
NRC/NRO/DNRL/LB1
References
Download: ML18088A018 (3)


Text

NuScaleDCRaisPEm Resource From: Chowdhury, Prosanta Sent: Thursday, March 29, 2018 8:45 AM To: Request for Additional Information Cc: Lee, Samuel; Cranston, Gregory; Bavol, Bruce; Karas, Rebecca; Drzewiecki, Timothy; NuScaleDCRaisPEm Resource

Subject:

Request for Additional Information No. 402 eRAI No. 9449 (04.03)

Attachments: Request for Additional Information No. 402 (eRAI No. 9449).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 1

Hearing Identifier: NuScale_SMR_DC_RAI_Public Email Number: 433 Mail Envelope Properties (BN7PR09MB2609409FE51BF8D1EF287E099EA20)

Subject:

Request for Additional Information No. 402 eRAI No. 9449 (04.03)

Sent Date: 3/29/2018 8:44:41 AM Received Date: 3/29/2018 8:44:46 AM 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 "Bavol, Bruce" <Bruce.Bavol@nrc.gov>

Tracking Status: None "Karas, Rebecca" <Rebecca.Karas@nrc.gov>

Tracking Status: None "Drzewiecki, Timothy" <Timothy.Drzewiecki@nrc.gov>

Tracking Status: None "NuScaleDCRaisPEm Resource" <NuScaleDCRaisPEm.Resource@nrc.gov>

Tracking Status: None "Request for Additional Information" <RAI@nuscalepower.com>

Tracking Status: None Post Office: BN7PR09MB2609.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 551 3/29/2018 8:44:46 AM Request for Additional Information No. 402 (eRAI No. 9449).pdf 11747 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

Request for Additional Information No. 402 (eRAI No. 9449)

Issue Date: 03/29/2018 Application

Title:

NuScale Standard Design Certification 048 Operating Company: NuScale Power, LLC Docket No.52-048 Review Section: 04.03 - Nuclear Design Application Section:

QUESTIONS 04.03-2 GDC 10, Reactor design, requires that the reactor core and associated coolant, control, and protection systems be designed with appropriate margin to assure that specified acceptable design limits (SAFDLs) are not exceeded during any condition of normal operation, including the effects of anticipate operational occurrences. GDC 25, Protection system requirements for reactivity control malfunctions, requires that the protection system be designed to assure that SAFDLs are not exceeded for any single malfunction of the reactivity control systems. FSAR, Tier 2, Section 4.3.1 states that the control system withdrawal rate is designed to assure that SAFDLs are not exceeded for accidental withdrawal of control rods; FSAR, Tier 2, Section 15.4.1.2 states that the transient analyses assume a maximum allowed control rod assembly (CRA) withdrawal rate of 15 in/min; and FSAR Tier 2, Table 14.2-80 states that Test #80 will verify that the rod insertion and withdrawal speeds are within design limits. NRC staff did not identify design information regarding a specific limit on the withdrawal speed. NRC staff needs to establish a finding that the transient and accident analyses are performed using suitably conservative values for CRA withdrawal rate. Accordingly, NRC staff requests that the applicant update FSAR, Tier 2, Section 4.3 to specify a design limit on CRA withdrawal rate.