ML23060A236
ML23060A236 | |
Person / Time | |
---|---|
Site: | National Bureau of Standards Reactor |
Issue date: | 03/01/2023 |
From: | Holly Cruz NRC/NRR/DANU/UNPL |
To: | |
References | |
Download: ML23060A236 (20) | |
Text
NIST Test Reactor Restart Review NRC Public Meeting March 2, 2023
Agenda
- Welcome and Introductions
- NIST Introductory Remarks
- Discussion of NRC Review
- Opportunity for Members of the Public to Ask the NRC Staff Questions
- Closing Remarks
- Adjourn
NRC Opening Remarks Rob Taylor Deputy Director for New Reactors Office of Nuclear Reactor Regulation
NIST Opening Remarks NRC Review of NIST Restart Request Jeremy Bowen Deputy Director Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation
NRC Preparing to Authorize Restart of the NIST Test Reactor
- Safety systems and components were unaffected and will perform as intended
- Corrective actions and enhancements will preclude recurrence of a similar event
- Additional planned actions provide further enhancements to safety
- Increased NRC oversight of the facility will continue
Restart Decision
- The NRC staff is finalizing a formal memorandum to NIST describing the NRC's decision on restart
- The basis for the staffs decision will be detailed in a technical evaluation report attached to the memo
- An inspection report will be issued in parallel, documenting NRC review of corrective actions and ongoing oversight
- Pending receipt of the restart authorization, NIST must still finish loading fuel in the core and begin controlled power ascension and operation under increased NRC oversight
Josh Borromeo NPUF Licensing Branch Chief Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation
NIST Test Reactor Background
- Normally Operated 24/7
- Refueling ~50 days
- Plate-type fuel with 34 plates per element and up to 30 elements in the core
- Non-pressurized heavy water primary cooling system with helium cover gas
Event Overview
- Immediately after beginning the power ascension, there was increasing radioactivity at the building exhaust stack monitor which automatically shutdown the reactor
- All safety systems functioned properly and there were no significant radiological consequences for NIST workers, the public, or the environment
- The direct cause of the event is attributed to a fuel element that was not properly latched in place which resulted in the element being displaced and overheating
No Offsite Consequences
- Fuel temperature safety limit (450°C) was exceeded based on observations of small amount once molten fuel material present on the lower grid plate
- Radiation doses onsite were a small fraction of the regulatory limits for members of the public, with even lower doses beyond NIST property
- Less than a fraction of a millirem measured at site boundary and confirmed by the staff
- standard chest x-ray is about 10 mrem
- regulatory limit is 100 mrem/year
Causes of the Event Understood
- NIST submitted a request to restart the facility which included root causes and corrective actions
- 7 root causes and 23 corrective actions were identified
- The NRC special inspection team (SIT) evaluated the root causes and corrective actions and identified necessary improvements
- Following the SIT, the NRC staff and NIST agreed to a series of additional corrective actions to enhance safety, which were memorialized in a confirmatory order on August 1, 2022
NRCs Review of Restart Request
- The NRC staffs review of the event and the licensees subsequent corrective actions are documented in a technical evaluation report
- The NRC staff ensured there was no functional damage, which included:
- the effectiveness of NISTs clean-up activities in removing sufficient debris from the reactor vessel and reactor vessel internals to confirm structures, systems, and components can perform their functions,
- the primary coolant system will perform its intended design function with the potential remaining debris; and
- NIST will not reuse any fuel that was in the core at the time of the event
- The NRC also reviewed the limiting safety system settings and maximum hypothetical accident and confirmed both continue to meet regulatory requirements and are adequate
License Amendments to Support Restart Decision
- An amendment to revise the fuel element latch verifications in technical specifications to address a root cause of the event
- An amendment to modify Safety Analysis Report to address potential debris remaining in the primary coolant system
- An amendment on core load methodology authorizing the method used for the use of additional fresh fuel elements
Travis Tate NPUF Oversight Branch Chief Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation
NRC Oversight of NIST
- NIST has been under enhanced NRC oversight since the February 3, 2021, event
- A special inspection was performed following the event to understand the direct and contributing causes
- Apparent violations of NRC regulatory requirements were included in the associated inspection report and informed NISTs corrective actions
- The NRC staff conducted inspections to assess the effectiveness of completed corrective actions and support NISTs ability to safely restart
- A confirmatory order was issued on August 1, 2022, outlining additional actions required to be completed by NIST
NRC Inspection Areas
- Emergency response (equipment, procedures)
- Fueling, defueling, latching procedures
- Primary system clean-up and restart core
- Start-up and abnormal conditions procedures
- Operator and supervisor training
- Safety Culture
Future NRC Inspection and Oversight
- A supplemental inspection plan was issued on August 1, 2022, outlining NRC enhanced oversight activities
- The NRC staff will continue to assess NISTs implementation of corrective actions, confirm completion of all confirmatory order actions, and document the results in inspection reports
- Increased oversight of the NIST reactor will continue until routine inspections are appropriate
Question and Answer Session List of Acronyms ADR-alternative dispute resolution CO-confirmatory order HEPA-high efficiency particulate air mrem-millirem MW-megawatt NIST-National Institute of Standards and Technology NRC-U.S. Nuclear Regulatory Commission NPUF-non-power production and utilization facilities SIT-special inspection team TER-technical evaluation report TS-technical specifications