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Safety Evaluation Report Safety Evaluation Report Related to the Renewal of the Operating License for the Research Reactor at the Missouri University of Science and Technology. Docket No. 50-123 March 2009 Safety Evaluation Report Related to the Renewal of Facility License No. R-79 for the Missouri University of Science and Technology Research Reactor, Rolla, Missouri March 2009 Office of Nuclear Reactor Regulation ABSTRACT This safety evaluation report summarizes the findings of a safety review conducted by the staff of the U.S. Nuclear Regulatory Commission (NRC), Office of Nuclear Reactor Regulation. The NRC staff conducted this review in response to a timely application filed by the Board of Curators of the University of Missouri (the licensee) for a 20-year renewal of Facility License No. R-79 to continue to operate the Missouri University of Science and Technology (MST) Research Reactor. In its safety review, the NRC staff considered information submitted by the licensee (including past operating history recorded in the licensee's annual reports to the NRC), inspection reports prepared by NRC personnel, and first-hand observations. On the basis of this review, the NRC staff concludes that MST can continue to operate the facility for the term of the renewed license, in accordance with the renewed facility license, without endangering the health and safety of the public, facility personnel, or the environment. ii CONTENTS Page A b s tra c t ................................................................................................................... i Abbreviations .......................... .. ............................................ vii 1. Intro d u c tio n ........................................................................................................................... 1-1 1 .1 O v e rv ie w ...................................................................................................................... 1-1 1.2 Summary and Conclusions Regarding the Principal Safety Considerations .............. 1-2 1.3 General Description ..................................................................................................... 1-3 1.4 Shared Facilities and Equipm ent ................................................................................. 1-4 1.5 Com parison with Sim ilar Facilities ............................................................................... 1-4 1.6 Sum m ary of Operations ............................................................................................... 1-4 1.7 Com pliance with the Nuclear W aste Policy Act of 1982 ............................................. 1-4 1.8 Major Facility Modifications and History ....................................................................... 1-5 2. Site Characteristics ............................................................................................................... 2-1 2.1 Geography and Dem ography ...................................................................................... 2-1 2.1.1 Geography ................................................................................................................ 2-1 2.1.2 Dem ography ............................................................................................................. 2-1 2.1.3 Conclusions ......................................... 7.................................................................... 2-1 2.2 Nearby Industrial, Transportation, and Military Facilities ............................................. 2-2 2.3 Meteorology .................................................................................................................. 2-2 2.4 Hydrology ..................................................................................................................... 2-3 2.5 Geology, Seism ology, and Geotechnical Engineering ................................................ 2-4 2.6 Conclusions .................................................................................................................. 2-4 3. Design of Structures, System s, and Com ponents ............................................................... 3-1 3.1 Design Criteria ............................................................................................................ 3-1 3.2 Structure Design ............................................................................................................ 3-1 3.3 Meteorological Dam age ............................................................................................... 3-2 3.4 W ater Dam age ............................................................................................................ 3-2 3.5 Seism ic Dam age ........................................................................................................ 3-3 3.6 System s and Com ponents ........................................................................................... 3-3 3.7 Conclusions ............................................................................................................... 3-4 4. Reactor Description ............................................................................................................. 4-1 4.1 Sum m ary Description .................................................................................................. 4-1 4.2 Reactor Core ................................................................................................................ 4-1 4.2.1 Reactor Fuel ............................................................................................................ 4-2 4.2.2 Control Rods ....... ......................................... 4-5 4.2.3 Neutron Moderator and Reflector ........................................................................... 4-7 4.2.4 Neutron Startup Source ........................................................................................... 4-8 4.2.5 Core Support Structure ........................................................................................... 4-8 4.3 Reactor Tank or Pool .................................................................................................. 4-9 4.4 Biological Shield... ............................................ 4-10 4.5 Nuclear Design ........................................................................................................... 4-11 4.5.1 Norm al Operating Characteristics ......................................................................... 4-11 4.5.2 Reactor Core Physics Parameters ................................ 4-12 4.6 Thermal Hydraulic Design .............. *........................................ 4-12 4.7 Conclusions .............................................................................................................. 4-13 5. Reactor Coolant System ...................................................................................................... 5-1 iii 5.1 Summary Description ....................................................................... 5-I 5.2 Primary Coolant System..................................................................... 5-1 5.3 Secondary Coolant System................................................................. 5-3 5.4 Primary Coolant Cleanup System.......................................................... 5-3 5.5 Pool Water Makeup System................................................................ 5-4 5.6 Nitrogen-16 Control System ................................................................ 5-4 5.7 Conclusions .................................................................................. 5-4 6. Engineered Safety Features...................................................................... 6-1 6.1 Introduction................................................................................... 6-1 6.2 Engineered Safety Features................................................................ 6-1 6.2.1 Confinement and Ventilation Systems ................................................. 6-1 6.2.2 Containment .............................................................................. 6-1 6.2.3 Emergency Core Cooling System ...................................................... 6-2 6.3 Conclusions.................................................................................. 6-2 7. Instrumentation and Control Systems ........................................................... 7-1 7.1 Summary Description ....................................................................... 7-1 7.2 Design of Instrumentation and Control Systems ......................................... 7-1 7.2.1 Design Criteria ............................................................................ 7-1 7.2.2 Design-Basis Requirements............................................................. 7-2 7.2.3 System Description....................................................................... 7-2 7.3 Reactor Control System..................................................................... 7-6 7.4 Reactor Protection System ................................................................. 7-7 7.5 Control Console and Display Instruments................................................. 7-8 7.6 Radiation Monitoring Systems.............................................................. 7-8 7.7 Conclusions.................................................................................. 7-9 8. Electric Power...................................................................................... 8-1 8.1 Normal Electrical Power System..........................................................
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