ML15112A126
| ML15112A126 | |
| Person / Time | |
|---|---|
| Site: | MIT Nuclear Research Reactor |
| Issue date: | 05/27/2015 |
| From: | Alexander Adams Research and Test Reactors Branch B |
| To: | Newton T Massachusetts Institute of Technology (MIT) |
| Sebrosky J, NRR/JLD, 415-1132 | |
| References | |
| Download: ML15112A126 (6) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 27, 2015 Dr. Thomas H. Newton, Jr.
Director of Reactor Operations Massachusetts Institute of Technology MITNRL-NW 12 138 Albany Street Cambridge, MA 02139
SUBJECT:
MASSACHUSETTS INSTITUTE OF TECHNOLOGY - PLAN FOR AUDIT RELATED TO APPLICABILITY OF FUKUSHIMA LESSONS LEARNED TO RESEARCH AND TEST REACTORS
Dear Dr. Newton:
The purpose of this letter is to provide you the details of an audit that the U.S. Nuclear Regulatory Commission (NRC) is conducting of your facility to support its evaluation of applicability of Fukushima lessons learned to research and test reactors. The NRC staff's preliminary assessment for your facility, as well as other research and test reactors, is discussed in a paper dated March 2, 2015, "Draft White Paper Applicability of Fukushima Lessons Learned to Facilities other than Operating Power Reactors." The draft white paper can be found in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML15042A367.
As discussed in the draft white paper, the NRC staff recognizes that the Massachusetts Institute of Technology (MIT) research reactor is a tank type reactor. Because of its low power, natural convection flow of reactor coolant is sufficient to remove decay heat from the reactor and prevent bulk boiling, even in the event of a loss of all electrical power and active decay heat removal systems. Therefore, there is not a near-term need to replenish the water around the reactor fuel lost by evaporation. However, the staff is reviewing the MIT reactor's ability to address scenarios where extreme external events could possibly result in loss of coolant inventory that could cause inadequate decay heat removal and fuel damage.
The enclosure to this document provides the detail of the NRC staff's plan to audit your facility.
At this time the NRC staff does not envision the need to visit your facility, but may request documents from you to support the audit. The NRC staff plans to document the result of its audit in an audit report and subsequent staff assessment.
T. Newton Should you have any questions concerning this audit, please contact Mr. Patrick Boyle at (301) 415-3936 or by electronic mail at Patrick.Boyle@nrc.gov.
Sincerely,
~~at?~
Alexander Adams, Jr., cV Research and Test Reactors Licensing Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No.: 50-020 License No.: R-37
Enclosure:
Audit Plan for Massachusetts Institute of Technology Research Reactor Associated with Evaluation of Applicability of Fukushima Lessons Learned cc: See next page
T. Newton MASSACHUSETTS INSTITUTE OF TECHNOLOGY Docket No.50-020 cc:
City Manager City Hall Cambridge, MA 02139 Department of Environmental Protection One Winter Street Boston, MA 02108 Mr. Robert Gallagher, Acting Director Radiation Control Program Department of Public Health Schrafft Center, Suite 1M2A 529 Main Street Charlestown, MA 02129 Nuclear Preparedness Manager Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611
Audit Plan for Massachusetts Institute of Technology Research Reactor Associated with Evaluation of Applicability of Fukushima Lessons Learned BACKGROUND AND AUDIT BASIS This audit plan was developed in accordance with U.S. Nuclear Regulatory Commission (NRC)
Office of Nuclear Reactor Regulation (NRR) Office Instruction LIC-111, "Regulatory Audits" (ADAMS Accession No. ML082900195) to support the NRC staff's assessment of applicability of Fukushima lessons learned to the 6 Megawatt thermal (MW 1) Massachusetts Institute of Technology research reactor (MITR)
The staff identified the need for additional information for three high-power research and test reactors (RTRs) (including the MITR) in a preliminary assessment dated March 2, 2015, "Draft White Paper Applicability of Fukushima Lessons Learned to Facilities other than Operating Power Reactors." The draft white paper can be found in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML15042A367. In accordance with LIC-111, one of the reasons for performing an audit is to, "establish an understanding of potential concerns to inform future regulatory actions or decisions, such as generic communications."
As discussed in the draft white paper, for the three reactors (including the MITR), NRC staff will perform additional assessments regarding the reactors' capabilities to prevent or mitigate loss of coolant accidents (LOCAs) as a result of beyond-design-basis natural phenomena (e.g., seismic events). For these RTRs, the early loss of reactor coolant can result in failure of the fuel cladding and subsequent radiological release unless reactor coolant makeup can be provided from installed facility equipment or from portable external sources.
The MITR is a tank type reactor. Because of its low power, natural convection flow of reactor coolant is sufficient to remove decay heat from this reactor and prevent bulk boiling, even in the event of a loss of all electrical power and active decay heat removal systems. Therefore, there is no near-term need to replenish the water around the reactor fuel lost by evaporation.
However, if the initiating external event also causes (or occurs concurrently with) the failure of the core tank, then the resulting loss of coolant inventory could result in inadequate decay heat removal and fuel damage.
AUDIT SCOPE The audit scope for the MITR is to collect additional information regarding the seismic capabilities of the reactor to assess the level of margin inherent in the design to withstand a beyond design basis earthquake and to preclude a seismically-induced LOCA from a beyond-design-basis earthquake. The staff will also collect additional information regarding the capabilities of this reactor to prevent or mitigate LOCAs as a result of other beyond-design-basis natural phenomena (e.g., tornado born missiles).
Enclosure
NRC AUDIT TEAM Title Team Member Team Lead John Adams Japan Lessons-Learned Division (JLD) Project Joe Sebrosky Manager Seismic Technical Support Yong Li Structural Technical Suooort Amitava Ghosh JLD Mitigating Strategies Technical Support On Yee (as required)
RTR Technical Support Michael Balazik RTR Project Manager Patrick Bovie LOGISTICS For the IVllTR, the staff believes that a desk audit of calculations, licensing material regarding the design of the reactor, and drawings will be able to address the staff information needs.
DELIVERABLES An audit report or summary will be issued by December 31, 2015, to document the results of the audit. The staff intends to use the audit report to support a safety assessment for the three RTRs by first quarter calendar year 2016.
INFORMATION NEEDS Seismic Review For MITR:, the RTR staff will work with the licensee to obtain applicable licensee seismic calculations. Once the NRR RTR staff obtains these calculations they will be provided to the NRR seismic and structural reviewer. Once the review of these calculations is completed, these calculations will be either destroyed or returned to the licensee. Additional information needs maybe identified based on the review of these calculations.
Structural Review The NRR RTR staff will obtain the necessary drawings and information to allow the NRR structural staff and JLD mitigating strategies staff to determine if other natural hazards (e.g.,
tornado born missile) have the capability to cause a LOCA and if so the staff will assess the mitigation capabilities that the MITR might be able to employ.
References MITR Sa1'ety Analysis Report
T. Newton Should you have any questions concerning this audit, please contact Mr. Patrick Boyle at (301) 415*-3936 or by electronic mail at Patrick.Boyle@nrc.gov.
Sincerely, IRA/
Alexander Adams, Jr., Chief Research and Test Reactors Licensing Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No.: 50-020 License No.: R-37
Enclosure:
Audit Plan for Massachusetts Institute of Technology Research Reactor Associatied with Evaluation of Applicability of Fukushima Lessons Learned cc: See next page DISTRIBUTION:
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