ML25017A375
| ML25017A375 | |
| Person / Time | |
|---|---|
| Site: | North Carolina State University |
| Issue date: | 01/17/2025 |
| From: | Paulette Torres NRC/NRR/DANU |
| To: | Hawari A North Carolina State University |
| References | |
| L-2020-NFR-0007 | |
| Download: ML25017A375 (6) | |
Text
From:
Paulette Torres Sent:
Friday, January 17, 2025 3:05 PM To:
ayman.hawari@ncsu.edu Cc:
Colby Fleming; Austin Wells; Duane Hardesty (He/Him/His); Holly Cruz (She/Her/Hers)
Subject:
North Carolina State University LRA-REQUEST FOR ADDITIONAL INFORMATION (EPID L-2020-NFR-0007)
Attachments:
RAI-10462-R1-FINAL.docx Dr. Ayman I. Hawari, Director Nuclear Reactor Program Department of Nuclear Engineering North Carolina State University Campus Box 7909 2500 Stinson Drive Raleigh, NC 27695-7909 Dr. Hawari, The U.S. Nuclear Regulatory Commission (NRC) staff is continuing its review of the North Carolina State University (NCSU) PULSTAR Nuclear Research Reactor license renewal application (LRA) letter, dated February 24, 2017 (Agencywide Documents Access and Management System Accession No. ML17088A819). Included with the NCSU LRA was the Safety Analysis Report (ML17201Q129 - redacted version). In reference to the Pool Inlet Break and Pool Outlet Break Loss-of-Coolant Accident scenarios performed by NCSU for their PULSTAR reactor safety analysis that drain the reactor pool and result in air cooling of the fuel (NCSU letter dated February 2, 2022 (ML22033A245) and supplemented in letter dated June 7, 2022 (ML22159A237), the NRC staff has identified the items in the enclosure, which need additional information.
The NRC staff held a phone call with Colby Fleming and Austin Wells on December 17, 2024, discussing the draft RAIs. The final RAIs are enclosed. We request that you provide responses within 30 days from the date of this email.
If you have any questions, please contact me at (301) 415-5656, or by email at Paulette.Torres@nrc.gov.
Respectfully, Paulette A. Torres Non-Power Production and Utilization Facility Licensing (UNPL)
Division of Advanced Reactors and Non-Power Production and Utilization Facilities (DANU)
Office of Nuclear Reactor Regulation (NRR)
(301) 415-5656 paulette.torres@nrc.gov Docket No. 50-297 License No. R-120 EPID: L-2020-NFR-0007 cc: GovDelivery Subscribers
Hearing Identifier:
NRR_DRMA Email Number:
2702 Mail Envelope Properties (SA0PR09MB70361A7AF713EE9810C946D9FE1B2)
Subject:
North Carolina State University LRA-REQUEST FOR ADDITIONAL INFORMATION (EPID L-2020-NFR-0007)
Sent Date:
1/17/2025 3:05:10 PM Received Date:
1/17/2025 3:05:00 PM From:
Paulette Torres Created By:
Paulette.Torres@nrc.gov Recipients:
"Colby Fleming" <ncsorrel@ncsu.edu>
Tracking Status: None "Austin Wells" <ajwells2@ncsu.edu>
Tracking Status: None "Duane Hardesty (He/Him/His)" <Duane.Hardesty@nrc.gov>
Tracking Status: None "Holly Cruz (She/Her/Hers)" <Holly.Cruz@nrc.gov>
Tracking Status: None "ayman.hawari@ncsu.edu" <ayman.hawari@ncsu.edu>
Tracking Status: None Post Office:
SA0PR09MB7036.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 1925 1/17/2025 3:05:00 PM RAI-10462-R1-FINAL.docx 26063 Options Priority:
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1 REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION 297-NC STATE LICENSE RENEWAL AND POWER UPRATE NORTH CAROLINA STATE UNIVERSITY AT RALEIGH NORTH CAROLINA STATE UNIVERSITY, UNIT 1 DOCKET NO. 05000297 ISSUE DATE: 01/17/2025
=
Background===
The U.S. Nuclear Regulatory Commission (NRC) staff is continuing its review of the North Carolina State University (NCSU) PULSTAR Nuclear Research Reactor license renewal application (LRA) letter, dated February 24, 2017 (Agencywide Documents Access and Management System Accession No. ML17088A819). Included with the NCSU LRA was the Safety Analysis Report (ML17201Q129 - redacted version). In reference to the Pool Inlet Break and Pool Outlet Break Loss-of-Coolant Accident scenarios performed by NCSU for their PULSTAR reactor safety analysis that drain the reactor pool and result in air cooling of the fuel (NCSU letter dated February 2, 2022 (ML22033A245) and supplemented in letter dated June 7, 2022 (ML22159A237), the NRC staff requires the following additional information to continue its review of the LRA. We request that you provide responses within 30 days from the date of this letter.
These requests for additional information have been developed based on the following requirements and guidance applicable to the NCSU LRA:
Title 10 of the Code of Federal Regulations (10 CFR).
Part 20, Standards for Protection against Radiation, of 10 CFR require that radiation doses to workers and members of the public be limited. To support meeting the public dose limits, 10 CFR Part 20, also limits the release of radioactive materials from the licensed facility to the environment (e.g., 10 CFR Part 20, Appendix B, Table 3).
Section 50.9, Completeness and accuracy of information, of 10 CFR require that information provided to the Commission by a licensee shall be complete and accurate in all material respects.
NUREG-1537 Part 1, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors, Format and Content, issued February 1996 (ADAMS Accession No. ML042430055).
NUREG-1537 Part 2, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors, Standard Review Plan and Acceptance Criteria, issued February 1996 (ADAMS Accession No. ML042430048).
Question 1 Degradation of the NCSU PULSTAR reactor, the reactor coolant systems, and associated components is a function of time, pressure, temperature, and stress. The NCSU PULSTAR operates at atmospheric pressure (SAR 4.3) and nominal pool temperature of 70 °F-105°F (SAR Table 4-9) and therefore these factors in a reactor environment are not significant. However, the reactor and its systems have been in service for approximately 60 years and the NRC staff need reasonable assurance of its continued operability and reliability, e.g., that the chances of a pipe
2 failure and material degradation are highly unlikely, to allow the NRC staff to make a determination that these components and materials are not highly susceptible to failure over time.
- Provide a detailed description of the NCSU PULSTAR reactor coolant system to include information such as:
- a. Joint designs and related specifications.
- b. Pipe diameter and wall thickness (nominal and any measurements since installation, if performed).
- c. All welding information such as material classification, material type and weld inspection records from original construction.
- d. All piping, fittings, and valves primary material specifications and material type.
- e. Design and any related specifications for all piping supports.
- Provide diagrams/drawings that shows all locations where the piping system penetrates the NCSU PULSTAR reactor pool and any other structures (such as walls and piping supports).
- Provide any history of deviation from the specified NCSU PULSTAR reactor pool water chemistry limits and operating temperature and the corrective action taken.
Question 2 Although a Certified Material Test Report (CMTR) is not required for a Non-Power Production and Utilization Facility (NPUF), provide an equivalent written report or an equivalent quality assurance (QA) documentation that contains data and information that attests to the actual physical and chemical properties of the primary coolant system piping, fittings, and weld materials.
Question 3 Describe in detail any degradation of piping materials that is known or suspected to have occurred in the NCSU PULSTAR reactor. Discuss any other recurrence of this type of material degradation at other research and test reactors, if known, and how they apply to the NCSU PULSTAR reactor.
Question 4 The NCSU PULSTAR reactor primary coolant system is comprised of the reactor pool and liner, the 16 N delay tanks, the primary pump, the heat exchanger, a purification loop and associated piping (SAR 5.2). The primary coolant loop is modeled with primary components including the 16 N decay tank, coolant pump, heat exchanger and pipes connecting the components (SAR 4.6.2.1). Provide the frequency of the primary coolant loop utilization during reactor operation.
Specify in your response the frequency when the primary coolant loop line has operated with:
- a. No water flow (not in use).
- b. Low water flow.
- c. Stagnant water flow.
3 Question 5 A "code of construction," also commonly referred to as a "building code," is a set of regulations established by local or state governments that define minimum standards for the design and construction of buildings, aiming to protect public health and safety by ensuring structures meet requirements for structural integrity, fire safety, plumbing, electrical systems, and accessibility features. Provide the "code of construction/building code(s)" used for the NCSU PULSTAR reactor pool and the primary coolant loop if different from the references given in SAR 3.1.3 and SAR 3.1.5.
OFFICE NRR/DANU/UNPL/PM NRR/DANU/UNPL/BC NAME PTorres HCruz DATE 01/16/2025 01/15/2025