ML19015A274

SMR DC RAI - Request for Additional Information No. 486 Erai No. 9296 (12.3)

ML19015A274
Person / Time
Site:	NuScale
Issue date:	01/15/2019
From:	NRC
To:	NRC/NRO/DLSE/LB1
References
Download: ML19015A274 (4)

Text

NuScaleDCRaisPEm Resource From: Cranston, Gregory Sent: Tuesday, January 15, 2019 12:16 PM To: NuScaleDCRaisPEm Resource Cc: Chowdhury, Prosanta; Tesfaye, Getachew

Subject:

Request for Additional Information No. 486 eRAI No. 9296 (12.3)

Attachments: Request for Additional Information No. 486 (eRAI No.9296).pdf From: Cranston, Gregory Sent: Friday, June 01, 2018 3:10 PM To: Request for Additional Information <RAI@nuscalepower.com>

Cc: Lee, Samuel <Samuel.Lee@nrc.gov>; Dudek, Michael <Michael.Dudek@nrc.gov>; Chowdhury, Prosanta

<Prosanta.Chowdhury@nrc.gov>; Lavera, Ronald <Ronald.LaVera@nrc.gov>; Tesfaye, Getachew

<Getachew.Tesfaye@nrc.gov>

Subject:

Request for Additional Information No. 486 eRAI No. 9296 (12.3)

Attached please find NRC staffs request for additional information (RAI) concerning review of the NuScale Design Certification Application. Password will be sent separately. A redacted (public) version of this RAI was issued today.

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.

1

Hearing Identifier: NuScale_SMR_DC_RAI_Public Email Number: 559 Mail Envelope Properties (BYAPR09MB3605EEC748CEFD386FFBF88490810)

Subject:

Request for Additional Information No. 486 eRAI No. 9296 (12.3)

Sent Date: 1/15/2019 12:16:12 PM Received Date: 1/15/2019 12:16:15 PM From: Cranston, Gregory Created By: Gregory.Cranston@nrc.gov Recipients:

"Chowdhury, Prosanta" <Prosanta.Chowdhury@nrc.gov>

Tracking Status: None "Tesfaye, Getachew" <Getachew.Tesfaye@nrc.gov>

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

Tracking Status: None Post Office: BYAPR09MB3605.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 885 1/15/2019 12:16:15 PM Request for Additional Information No. 486 (eRAI No.9296).pdf 59141 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

Request for Additional Information No. 486 (eRAI No.9296)

Issue Date: 06/01/2018 Application

Title:

NuScale Standard Design Certification 048 Operating Company: NuScale Power, LLC Docket No.52-048 Review Section: 12.03-12.04 - Radiation Protection Design Features Application Section: 12.3, 12.2 QUESTIONS 12.03-60 Regulatory Basis 10 CFR 52.47(a)(5) requires applicants to identify the kinds and quantities of radioactive materials expected to be produced in the operation and the means for controlling and limiting radiation exposures within the limits of 10 CFR Part 20.

Appendix A to Part 50General Design Criteria for Nuclear Power Plants, Criterion 61"Fuel storage and handling and radioactivity control," requires systems which may contain radioactivity to be designed with suitable shielding for radiation protection and with appropriate containment, confinement, and filtering systems.

10 CFR 20.1101(b) states that "the licensee shall use, to the extent practical, procedures and engineering controls based upon sound radiation protection principles to achieve occupational doses and doses to members of the public that are as low as is reasonably achievable (ALARA)." 10 CFR 20.1003 states that ALARA "means making every reasonable effort to maintain exposures to radiation as far below the dose limits in this part as is practical consistent with the purpose for which the licensed activity is undertaken, taking into account the state of technology, the economics of improvements in relation to state of technology, the economics of improvements in relation to benefits to the public health and safety, and other societal and socioeconomic considerations, and in relation to utilization of nuclear energy and licensed materials in the public interest."

NuScale DSRS Section 12.3, "Radiation Protection Design Features," states in the specific acceptance criteria that areas inside the plant structures should be subdivided into radiation zones, with maximum design dose rate zones and the criteria used in selecting maximum dose rates identified.

Background

NuScale DCD Tier 2, Revision 0 Figure 12.3-1g, " Reactor Building Radiation Zone Map - 100' Elevation,"

shows that the area above the reactor pool area (Room 010-022 per DCD Figure 1.2-216," Reactor Building 100'-0" Elevation"), as a Radiation Zone II. DCD Tier 2 Revision 0 Table 12.3-1,"Normal Operation Radiation Zone Designations," shows that areas designated as radiation zone II have dose rates 0.25 mrem/hr and 2.5 mrem/hr.

DCD Tier 2, Revision 0 Table 12.2-10, "Reactor Pool Cooling, Spent Fuel Pool Cooling, Pool Cleanup and Pool Surge Control System Component Source Terms - Radionuclide Content," provides the radionuclides concentration in the reactor pool water. Independent calculations of the dose rate from the ultimate heat sink pool water using the radionuclide concentrations listed in Table 12.2-10 column "Reactor Pool Water (Ci/gram)," performed by the staff resulted in radiation zone designations higher than the radiation zone assigned to room 010-022 in DCD Figure 12.3-1 by the applicant.

Key Issue: The staff needs to understand the methods, models and assumptions used by the applicant to calculate the radiation zones depicted in DCD Chapter 12.3.

Question To facilitate staff understanding of the application information in support of its reasonable assurance review regarding the assignment of radiation zones, the staff requests that the applicant:

1. Explain/justify the methods, models, and assumptions used to determine the aforementioned radiation zoning assignment.

2. As appropriate, identify other areas of the Reactor Building where the previous methods, models and assumptions, have been applied

3. As necessary, revise and update Section 12.3 of the NuScale DCD to accurately reflect plant radiation zones, OR Provide the specific alternative approaches used and the associated justification.