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{{#Wiki_filter:MISSOURIS&TMISSOURI UNIVERSITY OF SCIENCE AND TECINOLOGYFomr, Lnly rs' oU Iissc't-oi' ofMay 26, 2014
==Dear Sir:==
Please find enclosed the Annual Progress Report 2013-2014 for the Missouri Science andTechnology Reactor (License R-79, Docket No: 50-123). This report is being filed underthe reporting requirements of our Technical Specifications. A copy of this report is alsobeing sent to our NRC Project Manager, Mr. Greg Schoenebeck.Sincerely,L4AJ2~A,&n-kWilliam BonzerReactor ManagermhEnclosurecc: Mr. Greg Schoenebeck (NRC)Document Control Desk (NRC)V/'American Nuclear Insurers, c/o LibrarianUniversity of Missouri-Columbia Research Reactor (MURR)Chancellor Cheryl B. Schrader (MST)Michelle Bresnahan, Radiation Safety Officer (MST)Dr Hyoung Lee, Chair of Nuclear Engineering Dept. (MST)Dr. Mark Fitch, Chairman, Radiation Safety Committee (MST)Dr. Samuel Frimpong, Chair Mining and Nuclear Engineering Dept. (MST)Nuclear Reactor Facility o 250 West 13S Street% o Rolla, MO 6(5409-0637Phone: 573-341-4236 o Fax: 573-341-4237 o Email 1Aebonzer@mcst.eduAc)'2"o 0000000000000S00000PROGRESS REPORT2013-2014MISSOURI UNIVERSITY OFSCIENCE AND TECHNOLOGYREACTOR,)J2 000000000000000S0000PROGRESS REPORTFOR THEMISSOURI UNIVERSITY OF SCIENCE AND TECHNOLOGY(FORMALLY THE UNIVERSITY OF MISSOURI-ROLLA)NUCLEAR REACTOR FACILITYApril 1, 2013 to March 31, 2014Submitted toThe United States Nuclear Regulatory CommissionAndMissouri University of Science and Technology
*ii* Table of ContentsSUMMARYS1.0 IN TR O D UCTIO N ............................................................................................................................................... I1.1 BACKGROUND INFORM ATION ............................................................................................................. 1S1.2 G ENERAL FACILITY STATUS ......................................................................................................................... 22.0 REACTO R STA FF AND PER SO NNEL ................................................................................................32.1 R EACTOR STAFF ............................................................................................................................................ 302.2 LICENSED O PERA TORS ................................................................................................................................. 42.3 RADIATION SAFETY C OM M ITTEE ................................................................................................................. 4S2.4 H EALTH PHYSICS ........................................................................................................................................... 5S3.0 R EACTO R O PERA TIO NS ............................................................................................................................... 64.0 ED UC ATIO N A L UTILIZA TIO N .................................................................................................................... 13* 5.0 REACTOR HEALTH PHYSICS ACTIVITIES ........................................................................................ 175.1 ROUTINE SURVEY ......................................................................................................................................... 175.2 BY-PRODUCT M ATERIAL R ELEASE SURVEYS ...................................................................................... 1705.3 ROUTIN E M ONITORING ................................................................................................................................ 175.4 ENVIROM ENTAL M ONITORING ..................................................................................................................... 18S5.5 W ASTE DISPOSAL .................................................... .... ............................................................................... 18S5.6 INSTRUM ENT CALIBRATIONS ....................................................................................................................... 186.0 PLANS .................................................................................................................................................................. 19S6.1 DISTANT EDUCATION .................................................................................................................................... 1906.2 REPLACEMENT OF THE REACTOR BUILDING'S HEATING SYSTEM ......................................................... 196.3 MODELING THE GAMMA SPECTORCOPY OF THE REACTOR CORE ....................................................... 206.4 GLOBAL THREAT REDUCTION INITIATIVE SECURITY ENHNANCEMENT ............................................. 206.5 REACTOR OPERATOR TRAININ G ................................................................................................................... 2000000000 0 APPENDIX A: STANDARD OPERATING PROCEDURES CHANGED DURING THE 2012-2013 REPORTING YEAR00* LIST OF TABLESTABLE 3-1. CORE 120W TECHNICAL DATA .................................................................................................. 60TABLE 3-2. CORE 121W TECHNICAL DATA ............................................................................................................. 100 TABLE 3-3. UNSCHEDULED SHUTDOWNS .................................................................................................. 8TABLE 3-4. MAINTENANCE ........................................................................................................................................ 10STABLE 3-5. EXPERIMENTAL FACILITY USAGE .......................................................................................................... 12TABLE 3-6. REACTOR UTILIZATION .................................................................................................................. 120TABLE 4-1. MISSOURI S&T CLASSES AT REACTOR FACILITY ......................................................................... 140 TABLE 4-2. REACTOR SHARING PROGRAM 2013-2014 (REPORTING PERIOD) ................................................. 1500 LIST OF FIGURES0* FIGURE 3-1. MSTR CORE 120W CONFIGURATION ................................................................................................... 6* FIGURE 3-2. MSTR CORE 121W CONFIGURATION........................................................................... 700000000000000000000
* iv*SUMMARYDuring the 2013-2014 reporting period, the Missouri University of Science andTechnology Reactor (MSTR) was in use for 493.07 hours. The major part of this time, about90%, was used for class instruction, research, and training purposes.The MSTR operated safely and efficiently over the past year. No significant safety-related incidents or personnel exposures occurred.The reactor facility supported several Missouri University of Science and Technology0*(Missouri S&T) courses over the year for 24,768 student-hours. About 2,446 visitors visited the*reactor during the past year. There were 1,660 participants, mostly high school students, in the*U.S. Department of Energy Reactor Sharing Program.0*The reactor produced 35,496.0 kW/hrs kilowatt-hours of thermal energy usingapproximately 1.5 grams of uranium. A total of 351 samples were neutron irradiated in thereactor with the majority being analyzed in the reactor counting laboratory.000000000000000000S9
**
==1.0 INTRODUCTION==
9This progress report covers activities at the Missouri University of Science and Technology* Reactor (MSTR) Facility for the period April 1, 2013 to March 31, 2014.The reactor operates as a University facility. It is available to the faculty and students fromvarious departments of the University for their educational and research programs. Several other college* and pre-college institutions also make use of the facility. The reactor is also available for the training ofpersonnel from commercial concerns with legitimate interest in our facility use.01.1 Background Information*The Missouri University of Science and Technology Reactor (MSTR) (formally University of* Missouri-Rolla Reactor) attained initial criticality on December 9, 1961. The MSTR was the firstoperating nuclear reactor in the State of Missouri. The Bulk Shielding Reactor at Oak Ridge NationalLaboratory is the basis for the reactor's design. The reactor is a light water, open pool reactor cooled by* natural convective flow. The fuel is MTR plate-type fuel. The initial licensed power was 10 kW. The9 licensed power was up-graded to 200 kW in 1966. During the summer of 1992, the reactor fuel wasconverted from highly enriched uranium fuel to low-enriched uranium fuel.0*The facility is equipped with several experimental facilities including a beam port, thermalcolumn, three pneumatic rabbit systems, and several manual sample irradiation containers and systems.The facility also contains a counting laboratory that has both gamma and alpha spectroscopy capabilities.9 The gamma spectroscopy system includes germanium and sodium-iodide detectors, associatedelectronics, state-of-the-art data acquisition, and spectrum analysis software. The alpha spectroscopySsystem consists of a surface barrier detector and data acquisition equipment. Additionally, there is athermo luminance dosimeter reader, digital neutron radiography imager, and x-ray imager for student and* faculty usage.T~The MSTR also uses a biometric device to enhance its traditional security system.000S09 21.2 General Facility StatusThe MSTR operated safely and efficiently over the past year. No significant safety-relatedincidents or personnel exposures occurred.An independent auditor from the University of Columbia audited the reactor facility on December4, 2013. There were no significant areas of concern. There is an agreement between the MSTR and theUniversity of Missouri-Columbia to audit each other. This has been a very beneficial arrangement forboth facilities involved.The reactor staff has continued to review the operation of the reactor facility in an effort toimprove the safety and efficiency of its operation and to provide conditions conducive to its utilization bystudents and faculty. An "outreach" program, implemented over the past few years, has been continued inorder to let both students and faculty in a number of departments across campus know that the reactorcould be used to enhance course work and research. As a result, additional classes have been using thereactor facility to augment their programs, including:1. Chemistry 2, 'General Chemisty Laboratory'2 Civil Engineering 310, 'Senior Design Class'3. Engineering Management 386, 'Safety Engineering Management'4. Mechanical Engineering 229, 'Energy Conversion'5. Life Sciences 352, 'Biological Effects of Radiation'6 Physics 107, 'Modem Physics'7. Physics 207, 'Modem Physics II'8. Physics 322, 'Advanced Physics'9. Materials Science & Engineering 348, 'Energy Materials'10. Materials Science & Engineering 448, 'Advanced Energy Materials'
*39 SOPs were revised, over the past year in order to improve and keep current the operations and* efficiency of the MSTR. The following is a list of SOPs revised during the reporting period:* 1. Index* 2. Index3. SOP 105 Reactor Shutdown & Reactor Securing Procedures4. SOP 309 Response to a Coolant System Leak* 5. SOP 501 Emergency Procedures For Reactor Building Evacuation* 6. SOP 507 Emergency Procedures Administrative Responsibilities* 7. SOP 654 Measurement Of 4aAr Concentration In The Reactor Building Air* 8. SOP 800 Annual Checklist* 9. SOP 813 Rod Drop Time Measurement0* 2.0 REACTOR STAFF AND PERSONNEL* 2.1 Reactor Staff0O Name TitleDr. Arvind Kumarl Reactor Director0* Dr. Hyoung Kohl Lee2  Reactor DirectorMr. William Bonzer Reactor Manager & Senior OperatorMs. Maureen Henry Senior SecretaryMr. Craig Reisner Senior Reactor Operator* Mr. Ray Kendrick Senior Electronics Technic0* 1. Termination Date August 31, 2013* 2. Effective Date September 1, 2013000909 42.2 Licensed Operators1.2.3.4.5.6.7.8.9.10.11.12.13.NameWilliam BonzerCraig ReisnerEthan Barth-TaberNolan Goth'Brandon LahmannMatthew Crinnian.Kathryn KrevDustin Specker'Christopher SwisherlErica Davidson2Cody Stuchal3Ethan Margherio3Jonathan Scott3LicenseSenior OperatorSenior OperatorSenior OperatorSenior OperatorSenior OperatorSenior OperatorSenior OperatorReactor OperatorReactor OperatorReactor OperatorReactor OperatorReactor Operator*Reactor Operator1. Termination Date October 16, 20132. Effective Date December 5, 20133. Effective Date March 21, 20142.3 Radiation Safety CommitteeThe Radiation Safety Committee meets quarterly. The committee met on 6/28/2013, 9/26/2013,12/6/2013 and 2/28/2014 during the reporting period. The committee members are listed below.NameDepartment1. Dr. Mark Fitch2. Mr. Ray BonoCivil EngineeringEnvironmental Health and Safety Services 90SS0009S000SS000S0SSS53. Mr. William Bonzer4. Mr. Randy Stoll5. Dr. Robert Dubois6. Dr. David Wronkiewicz7. Dr. Shoaib Usman8. Dr. Fadha Ahmed9. Dr. Robert Aronstam10. Dr. Amitava Choudhury11. Dr. Carlos Castano12. Mr. Tony HuntNuclear ReactorBusiness ServicesPhysicsGeological Sciences & GeologyMining & Nuclear EngineeringEnvironmental Health and Safety ServicesBiological SciencesChemistryMining & Nuclear EngineeringEnvironmental Health and Safety Services2.4 Health PhysicsThe Environmental Health and Safety (EHS) Department provides the health physics support forthe Missouri S&T Reactor. The EHS Department is organizationally independent of the Reactor Facilityoperations group. Health Physics personnel are listed below.NameTitle1.2.3.4.5.6.7.8.Mr. Ray BonoMr. Brian SmithDr. Fadha AhmedMs. Kelsey FreedlineMs. Amanda BakerMs. Kelsey SalzmanMs. Kathryn KrevMr. Andrew BinghamDirector of Environmental Health and SafetyIndustrial HygienistHealth PhysicistHealth Physics Technician (part time)Health Physics Technician (part time) Left Dec. 2014Health Physics Technician (part time)Health Physics Technician (part time)Health Physics Technician (part time) 9999994S9090900096Table 3-1. Core 120W Technical DataParameter ValueRod 1 3.832% Ak/kRod 2 3.228% Ak/kRod 3 1.778% Ak/kReg Rod 0.293% Ak/kExcess Reactivity 0.652% Ak/kShutdown Margin* 4.354% Ak/k*Assumes Rod I (highest worth rod) and Reg Rod are fully withdrawn.ABCDEFSC-4 F-5 F-I F-17F-4 F-8 F-14 C-I F-10 F-2F-9 C-3 F-12 C-2 F-7 F-3CR F-15 HC F-13 BR F-6Table 3-1. MSTR 120W ConfigurationF- Standard ElementsBR- Bare RabbitCR- Cadmium RabbitKEY TO PREFIXESCR- Cadmium RabbitC- Control ElementsHC- Hot Cell RabbitHF- Half ElementS -Source Holder 99990S990S0S9S0SSS7Table 3-2. Core 121W Technical DataParameter ValueRod 1 3.950% Ak/kRod 2 3.397% Ak/kRod 3 1.975% Ak/kReg Rod 0.270% Ak/kExcess Reactivity 0.219% Ak/kShutdown Margin* 5.350% Ak/k*Assumes Rod I (highest worth rod) and Reg Rod are fully withdrawn.ABCDEFF- Standard ElemeBR- Bare RabbitCR- Cadmium RatSC-4 F-5 F-1 F-17F-4 F-8 F-14 C-1 F-10 F-11F-9 C-3 F-12 C-2 F-7 F-3CR F-15 HC F-13 BR F-6Figure 3-2. MSTR Core 121W ConfigurationKEY TO PREFIXESnts CR- Cadmium Rabbit 1-FC- Control Elements S -bbit HC- Hot Cell Rabbit-Half ElementSource Holder 8Table 3-2:Unscheduled Shutdowns for 2013-2014Date Type of Rundown/Cause and Corrective Action TakenRUNDOWNS4/8/2013 Action: 120% Demand RundownCause: Operator restarting reactor with a high residual core.Corrective Action Taken: Operator instructed to watch instrumentation.SRO on Duty granted permission to restart reactor.5/2/2013 Action: 120% Demand RundownCause: Student operator downscaled at 60% on Linear Recorder.Corrective Action Taken: SRO instructed student to downscale at 8%, not 60%.SRO on Duty granted permission to restart reactor.5/10/2013 Action: 120% Demand RundownCause: Student downscaled pico-ammeter too soon.Corrective Action Taken: SRO instructed student to follow SOP 104 regardingdownscaling at 8% and upscaling at 60 %SRO on Duty granted permission to restart reactor.6/21/2013 Action: High Area Radiation Rundown 9Cause: A sample returning to the hot cell rabbit system stopped in the glove box near thegamma radiation area monitor instead of passing 'through to the hot cell.Corrective Action Taken: SRO let the sample decay in the glove box and kept personnelout of the room containing the hot cell rabbit system. Sample was removed from glovebox after decaying.SRO on Duty granted permission to restart reactor.12/12/2013 Action: 120% Demand RundownCause: The operator did not push in on range switch far enough for it to stay pressed in.Corrective Action Taken: The operator was reminded to fully press in range switch.SRO on Duty granted permission to restart reactor.2/26/2014 Action: 120% Demand RundownCause: The operator did not fully press in the 20 kW range switch.Corrective Action Taken: No corrective action taken.SRO on Duty granted permission to restart reactor.3/5/2014 Action: 120% Demand RundownCause: The operator did not follow proper startup procedures after the reactor had beenshutdown.Corrective Action Taken: The SRO instructed the operator to follow SOP 106 whenrestarting the reactor.SRO on Duty granted permission to restart reactor.
10UNPLANNED SHUTDOWNSDate Tvne of Unnlanned Shutdown. Cause and Corrective Action TakenUnplanned Shutdowns12/16/20133/6/2014Table 3-3:Action: Rods dropped.Cause: Alternating current power flicker.Corrective Action Taken: None.SRO on Duty granted permission to restart reactor.Action: Control rod #3 dropped.Cause: Undetermined.Corrective Action Taken: None.SRO on Duty granted permission to restart reactor.Maintenance for 2013-2014Date Type of Maintenance8/20/2013 Issue: Rod drive #3 failure.Corrective Action: Removed, repaired reinstalled rod drive #3.9/4/2013 Issue: Magnet #3 failure.
Corrective Action: Removed magnet #3 and replaced with spare magnet.0* 10/1/2013 Issue: Magnet #3 failure.Corrective Action: Removed magnet #3 and replaced with spare magnet.S 1/5/2013 Issue: Magnet #3 failure.0 Corrective Action: Removed magnet #3 and replaced with spare magnet.01/15/2014 Issue: Magnet #3 failure.0 Corrective Action: Removed magnet #3 and replaced with spare magnet.00* 1/27/2014 Issue: Magnet #3 failure.0 Corrective Action: Removed magnet #3 and replaced with spare magnet.02/10/2014 Issue: Magnet #3 failure.0Corrective Action: Removed magnet #3 and replaced with spare magnet.00S 12/20/2014 Issue: Magnet #2 failure.0' Corrective Action: Removed magnet #2 and replaced with spare magnet.000t 12/04 Ise Mge 3fiue0 orcieAto:Rmvdmge # n elcdwt pr ant006 /021 su:Mge 3fiue0'Cretv cin eoe ant# n elcdwt pr ant00102/021 Isu:Mge#2fiue 000040000009S90012Table 3-5. Experimental Facility UsageFacility HoursBare Rabbit Tube 21.38 hrs.Cadmium Rabbit Tube 0.00 hrs.Beam Port 116.531 hrs.Thermal Column 0.0 hrs.Other Core Positions 3.22 hrs.Hot Cell 11.73 hrs.Gamma Exposures 0.0 hrs.Total 152.86 hrs.Table 3-4. Reactor Utilization1. Reactor use 493.07 hrs.2. Time at power 366.52 hrs.3. Energy generated 35,496.0 kW/hrs.4. Total number of samples, neutron irradiated 3515. U-235 Burned 1.553 g6. U-235 Burned and Converted 1.834 g 13* 4.0 EDUCATIONAL UTILIZATION*The reactor facility supported several Missouri S&T courses in the past year for a total of 24,764* student-hours. The number of Missouri S&T students utilizing the facility was 1,404. This usage is adirect result of an aggressive and continuing campus wide "outreach" program. The reactor facility* provided financial support for six students with hourly wages. Additionally, students from severaluniversities, colleges and high schools have used the facility.Table 4-1 lists Missouri S&T classes taught at the facility along with associated reactor usagefor this reporting period.The Reactor Sharing Program, previously funded by the U.S. Department of Energy, wasestablished for colleges, universities, and high schools that do not have a nuclear reactor. This past year,* 1,660 students and instructors from 140 institutions.participated in the program. Table 4-2 lists thoseschools and groups that were involved in this year's Reactor Sharing Program. The majority ofparticipants were high school students. MSTR coordinates with the Missouri S&T Admissions Office toschedule high school students to see other items of interest at Missouri S&T after they have visited the* reactor facility. The students visited the Missouri S&T Chapter of American Nuclear Society, theComputer Integrated Manufacturing Lab, the Foundry, Ceramics Engineering, Mineral Museum,Computer Center, Experimental Mine, Solar Car, Electron Microscope, and Stonehenge. The Reactor* Sharing Program serves as a strong campus-wide recruiting tool by attracting high school students to theuniversity and hopefully sparking some interest in nuclear engineering, science, and technology.The reactor staff continues to educate the public about applications of nuclear science. Over* 2,446 persons visited the facility during this reporting period. Tour groups are typically given a brief9orientation and/or demonstration by a member of the reactor staff.SS 0000000000900009000,900000014Table 4-1 Missouri S&T Classes at Reactor FacilitySemester CLASS NUMBERITITLE # OF TIME AT STUDENTSSTUDENTSREACTOR HOURS2013-2014 Graduate Student's Project 5 234 1170SS2013 NE 206 20 12 240SS2013 NE 308 28 129.5 25904/8/2013 NE 25 Lab 17 1.5 264/22/2013 NE 312 15 2.5 384/24/2013 NE 312 15 2.5 384/25/2014 NE 312 10 2.5 255/14/2014 NE 25 Power Changes 5 1 5FS 2013 NE 206 26 10 2609/4/2013 NE 25 Tour 3 1 39/5/2013 NE 25 Tour 9 1 99/6/2013 NE 25 Tour 9 1 9FS 2013 NE 304 34 36 122412/2/2013 NE 25 Power change 9 2 1812/4/2013 NE 25 Power change 2 2 4SS2014 NE 206 26 84 2184SS2014 NE 308 labs 20 38.5 7702/10/2014 NE 25 Tour 22 1 222/13/2014 NE 25 Tour 10 1 103/17/2014 NE 25 Lab 22 1 223/20/2014 NE 25 Lab 6 1 63/18/2014 NE 312 15 1 153/19/2014 NE 312 26 1 263/20/2014 NE 312 12 1 12_ _TOTAL 366 568 8726 09900S000000000000900000S15Table 4-2 Reactor Sharing Program 2013-2014 (Reporting Period)Date Participants Number Hours4/2013 Visitor's 17 4.54/15-4/18 Chem labs for Spring semester 2013 252 7.54/23/2013 Tour MET class 348/448 10 14/29/2013 Mountain Grove School 5 15/17/2013 Tour for families and students before graduation 21 45/16/13 Army Tour 2 16/2013 Visitor's 7 16/6/2013 Minority Introduction to Engineering 23 16/11/2013 Jackling Introduction to Engineering 18 1.56/13/2013 Jackling Introduction to Engineering 23 1.56/17/2013 Nuclear Engineering Camp (4 groups) 38 26/18/2013 Nuclear Engineering Camp (4 groups) 38 3.56/19/2013 Nuclear Engineering Camp (4 groups) 25 26/20/2013 Minority Introduction to Engineering 23 16/20/2013 Nuclear Engineering Camp (4 groups) 38 26/25/2013 Jackling Camp 18 1.56/27/2013 Jackling Camp 22 3.57/2013 Visitor's 12 2.57/9/2013 Jackling Camp 20 3.57/9/2013 Chemical Engineering Fort Leonard Wood School 23 1.57/11/2013 Jackling Camp 24 3.57/18/2013 Dr. Dewoski Class 6 1 00009000000900009009S000168/2013 Visitor's 6 18/13/2013 Video People 5 1.008/19/2013 Video People 3 .59/2013 Visitor's 7 3.59/10/2013 Tour with Walt Branson 1 .510/2013 Visitor's 13 811/5/2013 IT 1 111/6/2013 Physical Facilities 1 111/7/2013 Seymour and Norwood Schools 23 111/13/2013 Nuclear Regulatory Commission Testing 1 611/13/13 Chem labs 786 1812/3/2013 Offsite Meeting 9 112/3/13 Tour Health Class 5 112/5/2013 Tour Mansfield High School 2 612/5/2013 MURR Inspection 1 1612/9/2013 Training a person on control panel 1 612/10/2013 Computer Tech working in control room 1 81/20/2014 Visitor's 1 .51/13/2014 CDG Group 4 11/15/2014 Climax High School 21 1.51/21/2014 Group meeting on Security 14 62/2014 Visitors 6 22/12/2014 Home School Students 27 12/15/14 Boy Scout Tour 19 12/25/2014 Chemical Engineering Fort Leonard Wood School 19 1.52/26/2014 IT to test equipment 2 12/26/2014 Contractors for Asbestos removal 12 13/2014 Visitor's 4 1.5TOTAL 1660 149 06 17* 5.0 REACTOR HEALTH PHYSICS ACTIVITIES0* The health physics activities at the Missouri S&T Reactor facility consist primarily of radiation0 and contamination surveys, monitoring of personnel exposures, airborne activity, pool water activity, and0 waste disposal. Releases of all by-product material to authorized, licensed recipients are surveyed and0 recorded. In addition, health physics activities include calibrations of portable and stationary radiationdetection instruments, personnel training, special surveys and monitoring of non-routine procedures.005.1. Routine Surveys0Monthly radiation exposure surveys of the facility consist of direct gamma and neutronmeasurements. No unusual exposure rates were identified. Monthly surface contamination surveys* consist of 20 to 40 swipes counted separately for alpha and beta/gamma activity. No significantcontamination outside of contained work areas was found.905.2. By-Product Material Release SurveysThere were no shipments of by-product material released off-campus. There were three by-product releases on campus.0S5.3. Routine Monitoring9Sixty-six reactor facility personnel and students involved with the operations in the reactor* facility are currently assigned Luxel, Optically Stimulated Luminescence (OSL) dosimeters. Three of theReactor Staff have beta, gamma, neutron dosimeters which are read twice monthly. There are four areabeta, gamma, neutron dosimeters and two TLD ring dosimeters, which are also read twice monthly.SThere are also four other beta, gamma, neutron dosimeters used by the health physics personnel and threeSother area beta, gamma, neutron dosimeters that are read monthly. The remaining dosimeters detect betaand gamma radiation only and are read monthly. There are seventeen area dosimeters assigned onSSS
* 180campus for beta and gamma monitoring and one for beta, gamma, and neutron monitoring. In addition,* six digital, direct-reading dosimeters and three chirper dosimeters are used for visitors and high radiationwork. There have been no significant personnel exposures during this reporting period. Visitors are0 monitored with direct reading dosimeters. No visitors received any reportable or significant exposure.0Airborne activity in the reactor bay is monitored by a fixed-filter, particulate continuous air9 monitor (CAM). Low levels of Argon-41 are routinely produced during operations.0*Pool water activity is monitored monthly to ensure that no gross pool contamination or fuelcladding rupture has occurred. Gross counts and spectra of long-lived gamma activity are compared toprevious monthly counts. From April 2013 through March 2014 sample concentrations averaged* 1.71x10i pCi/ml.0*Release of gaseous Ar-41 activity through the building exhausts is determined by relating the0 operating times of the exhaust fans and reactor power during fan operation to previously measured airactivity at maximum reactor power. During this period, an estimated 61,966.39 pCi of Ar-41 was.released into the air.95.4. Waste Disposal0Solid waste, including used water filters, used resins, and contaminated paper/gloves is storedand/or transferred to the campus waste storage area for later shipment to a commercial burial site. Wateris analyzed for radioactive contamination and approval is required before the water is released. During0 this period there were three waste barrels transferred from the reactor facility to the DMSF on campus.905.5. Instrument Calibrations0During this period, portable instruments and area monitors were calibrated annually.S0S0S0S 0*19o0* 6.0 PLANS0The reactor staff will be involved in several major projects during the next reporting period; 1)development of a distant education program, 2) replacement of reactor building's heating system, 3)* modeling the gamma spectroscopy of the reactor core, 4) Global Threat Reduction Initiative securityenhancements, and 5) continuation of the reactor operator training program.S06.1 Distant EducationA distant education system is being developed to conduct laboratory sessions with students of theMissouri S&T Campus and other universities. Due to the size of the Missouri S&T Nuclear Engineeringclasses, the distant education system will allow students to participate in lab sessions as one group in* larger classrooms than what is available in the MSTR building.5 Equipment has been installed to replace the existing rod drive motors and rod height indicators tooutput rod height information over the internet. Additional programing and minor wiring is beingcompleted to output control room instrumentation to be viewed live as the labs are taking place.Audio/video equipment is ready to use for students to watch reactor staff performing the labs, ask0 questions to the staff and obtain data from the control room instrumentation.oS6.2 Replacement of the Reactor Buildinz's Heating SystemS The Missouri S&T campus has been constructing a geo-thermal heating system for many of thecampus buildings. Three geo-thermal power plants will obtain heat from the ground pipe it to other9buildings. The coal power plant providing steam heat to many buildings including the MSTR will be* permanently shut down in the spring of 2014. The MSTR is not one of the buildings that will be heated* with the geo-thermal system. During the summer of 2014 the reactor building will have the steam heaters* replaced with natural gas heaters. Additional maintenance will be performed to replace existing circuitSbreaker panels and ceiling lighting located in the reactor bay while the heating system is changed out.S000oS 206.3 Modeling the Gamma Spectrocopy of the Reactor CoreA dry-well container is being built to hold a sodium iodide detector. This detector will be placenear the reactor core to obtain gamma spectrum readings from individual fuel elements. The gammareadings will be used by the Nuclear Engineering department a private firm to create a computer model ofthe MSTR core. Computer models do exist of the MSTR core, but no gamma spectrum data has beentaken from the fuel and used in previous models.6.4 Global Threat Reduction Initiative Security EnhancementsThe Pacific Northwest National Laboratory (PNNL) will enhance security of the MSTR under theGlobal Threat Reduction Initiative (GTRI) Program.6.5 Reactor Operator TrainingThe MSTR had four students obtain their license of Reactor Operator. The reactor staff is limitingoperator training to only students with a very strong desire to obtain the license and assist reactor staffwith reactor operations. At the end of the reporting period ten students were training for an operator'slicense to take in the fall of 2014 and four for their Senior Reactor Operator upgrade.
0SSSS0000SSSSSSSSSSSSSSSSSS9S9SSSS0SSS21APPENDIX A.STANDARD OPERATING PROCEDURESCHANGED DURING THE 2013-2014REPORTING YEAR S0SS0000000S000S9000000*** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***SOP: INDEX TITLE: -NýDEXRevised: August 1, 2013SOP 700 -799 ExperimentsPage 3 of3 RevSOP 702SOP 710SOP 711SOP 712Irradiation Request FormsInsertion and Removal of ExperimentsBeam Hole FacilityThermal Column FacilitySOP 800 -899 Reactor InstrumentationSOP 800SOP 801SOP 802SOP 803SOP 804SOP 805SOP 806SOP 810SOP 811SOP 812SOP 813SOP 816SOP 818Annual ChecklistLog N and Linear Drawer CalibrationLinear ChannelLog Count Rate (LCR) ChannelSafety Amplifier SystemAuto Control SystemTemperature ChannelWeekly CheckFire and Smoke Alarm SystemConfinement and Ventilation System CheckRod Drop Time MeasurementMSTR Power CalibrationFunctional Test of Building Security SystemRevRevised By: Maureen HenryApproved By: William Bonzer/ -.I : z/ -,,.. ,., f ..... -AIr xW L ~~K 00000000000S000000*** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***SOP: INDEX TITLE: INDEXRevised: September 9, 2013 Page 3 of 3SOP 700 -799 ExperimentsSOP 702SOP 710SOP 711SOP 712Irradiation Request FormsInsertion and Removal of ExperimentsBeam Hole FacilityThermal Column FacilitySOP 800 -899 Reactor InstrumentationSOP 800SOP 801SOP 802SOP 803SOP 804SOP 806SOP 810SOP 811SOP 812SOP 813SOP 816SOP 818Revised By: MaureenI ,Annual ChecklistLog N and Linear Drawer CalibrationLinear ChannelLog Count Rate (LCR) ChannelSafety Amplifier SystemTemperature ChannelWeekly CheckFire and Smoke Alarm SystemConfinement and Ventilation System CheckRod Drop Time MeasurementMSTR Power CalibrationFunctional Test of Building Security SystemHenry Approved By: William BonzerRevý 4(/~) 32~i~,
S0**MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *ev* SOP: 105 TITLE: REACTOR SHUTDOWN & REACTOR* SECTJRLNG PROCEDURES'* Revised: September 9, 2013 Page 1 of 4* A. PURPOSE*To ensure a safe and consistent method to shutdown the Reactor from an operatingcondition and, when advised, by a SRO on Duty, to secure the reactor. Rev* B. PRECAUTIONS, PREREQUISITES, AND LIMITATIONS* 1. The SRO on Duty will decide if the Reactor is to be "SHUTDOWN" or "SECURED".* 2. A Secure Checklist shall be completed at the end of the work day.0 3. Any malfunctions or abnormal conditions noted during or after the Shutdown will be* recorded in the Permanent Log and the SRO on Duty shall be notified.04. An operator assistant shall be present if the Reactor is not in "AUTO" before theshutdown begins to take logs.* 5. The RO must be alertto the indication ofjamming of control rods during the shutdownprocess. If this occurs, stop driving in the rods and inform the SRO on Duty.6. At the end of an operational run, the operator should dispose of trash, coffee cups, sodacans, etc. and leave the Control Room in a clean and orderly appearance.C. "SHUTDOWN" OF REACTOR* 1. Log time, initials, followed by "SHUTDOWN" in the hourly logo* 2. Log time and "SHUTDOWN" in the permanent log.3. Announce over the public address system, "The reactor will be shutdown".* 4. Trip "AUTO/N'ANUAL" switch to "ILMANUAL" (if in "AUTO").* 5. Place the "OPERATE/SHUTDOWNi" switch in "SHUTDOWN" position or insert* .safety rods and regulating rod with both joysticks.O0* Revised By: William Bonzer, Approved By: William Bon~zer0 , -:'." " '2 ' ..."''0 0S0*** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *Re*SOP: 105 TITLE: REACTOR SHUTDOWN & REACTOR* SECURNG PROCEDURESRevised: September 9, 2013 Page 2 of 46. Monitor the decrease in reactor power by changing the Linear Meter Selector Button (lbutton to the left) when the Linear Recorder decreases to about 8% of the present scale.Operation at high power levels will prevent returning to lowest allowed scale (2 watts)Oand therefore this step is continued only until rods reach their limit.7. Maintain Log Count Rate Recorder > 20 cps by inserting fission chamber.8. Stop rod insertion when reg rod is at 1-2".9. Restart rod insertion. Rev10. When the rods are fully inserted to their insert limits (green lights):a. Return "OPERATE/SHUTDOWN" switch to "OPERATE" or,* b. Return joysticks to the "NEUTRAL" position.S11. Reactor is now "SHUTDOWN".0D. "SECURE CHECKLISTRefer to form SOP 105.1. Use date stamp.2. All rod and Reg Rod Insert Limit (Green) Lights on.3. Turn magnet key 90 degrees CCW and remove from console. Hand key to SRO on* Duty.4. Turn off the Log Count Rate, Linear, and Log/Period recorders. Place date at the topof each recorder chart (use date stamp).S5. Push Annunciator "RESET". The "NLANUAL SCRAi\M", "RECORDERS OFF" and"MANUAL OPERATION" Annunciators will remain on.6. Turn the Reactor Bridge intercom switch to the off position (button up).0S7.. Return "OPERATE/SHUTDOWN" switch to "OPERATE".B*Revised By: William Bonzer Approved By: William Bon~zer/.,' -10.., i 0SS000000000000SS0000*** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***SOP: 105 TITLE: REACTOR SHUTDOWN & REACTORSECURING PROCEDURESRevRevised: September 9, 2013Page 3 of 48. Turn TV monitor off.9. Verify both nitrogen diffusers are off.10. Verify that all vent fans are off.11. Secure the rabbit system by assufing the controller is turned off and the gas bottle isshut. Return the glove box key to the safe.12. Shut off the rabbit system nitrogen gas bottle if the rabbit has been used.13. Turn off the core lights.14. Log time using the console clock.15. Initials of person performing checklist.16. SRO on Duty shall initial.RevRevised By: William BonzerI .' 'jLA ~j ~Approved By: William Bonzer>-U '
00000000000S0000*** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***SOP: 105 TITLE: REACTOR SHUTDOWN & REACTOR SECURING PROCEDURESRevised: September 9,2013 Page 4 of 4SECURE CHECKLIST1. Date2. All Rods on Insert Limit3. Magnet Power Off andKey to SRO4. Recorders Off and Dated5. Reset Annunciator6. Reactor Bridge IntercomOff7. Shutdown Switch toOperate8. TV Monitor Off9. Nitrogen Diffusers Off10. Vent Fans Off11. Rabbit System Secured12. Rabbit Gas Off13. Core Lights Off14. Time Completed15. Operators Initials16. SRO InitialsRevRevised By: William BonzerApproved By: William Bonzer 00MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** RevSOP: 309 TITLE: RESPONSE TO A COOLANT SYSTEM LEAK* Revised: April 8, 2013 Page 1 of 10A. PURPOSETo ensure proper indication and response in the event of a leak in the coolant system.B. PRECAUTIONS, PREREQUISITES, AND LIMITATIONS* 1. Normal pool evaporation is approximately 1/10 inch per day.2. There are "vacuum breaks" in the purification piping to prevent draining the poolbelow approximately 16 ft. above the core. The cooling system will automatically Revshut down if a loss of water pressure occurs or water is detected at a floor watersensor.3. Possible causes are:O a. crack in the pool wall* b. leak in the purification systemc. leak in the seal around the beam port or thermal columnO d. leak through the "forced" cooling pipese. leak in the cooling system Rev4. Report any abnormalities to the SRO on duty.* 5. If a leak is present, shut down the reactor if it is operating.6. Minimize unnecessary exposure to radiation.C. PROCEDURES1. Monitor water level to check the rate the level is decreasing if a leak is suspected.2. Check for leaks at the purification pump, thermal column, beam port, and cooling RevO system.O 3. Check for indications of cracks in the wall (bubbles, dirt, broken cement, etc.* 4. If the leak is due to the purification system, close the pool suction valve (locatednext to the pump) # 19, and stop the purification pump.O 5. If the leak is not due to the purification system, refill the pool as per SOP 301.6. If the leak is due to the purification system or greater than the capacity of thepurification system to refill the pool, the emergency cooling hose will be used tofill as necessary.7. If the leak is due to the cooling system, turn off cooling system if it is operating. Rev* Isolate the leaking area of the cooling system by closing valves before and afterO the leaking area.0O Reviewed By: Craig Reisner Approved By: William Bonzer0 00000000S00SS0SS000S*** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES '*SOP: 501 TITLES: EMERGENCY PROCEDURES FOR REACTORBUILDING EVACUATIONRevised: September 13, 2013Page 7 of 7RevMISSOURI S&T EMERGENCY PHONE LISTReactor Staff CELL HOME WORKWilliam Bonzer, Manager, SRO 578-9463 368-0318 341-4384Craig Reisner, Senior Reactor Operator 573-247-7557 573-729-7277 341-4291Maureen Henry, Sr. Secretary 364-7272 341-6016University Administrative StaffChristine Laughlin, Director Missouri S&T Police 201-1699 816-665-1448 341-4345Dr.Cheryl B. Schrader, Chancellor 201-7392 341-5432 341-4116Walter Branson, VC Chancellor Finance & Adm. 260-402-0317 341-4122James Packard, Director Physical Facilities 578-8167 341-4252Dr. Goodman DO, Director Student Health Services 341-4284Dr. Hyoung Lee,Chair of Nuclear Eng, Reactor Director 573-202-4665 341-4585Dr.Samuel Frimpong, Chair of Mining and Nuclear 426-2338 341-7617Fadha Ahmed, Health Physicist EHS-Missouri S&T 636-223-2054 341-7014LocalMissouri S&T Police 341-4300Rolla City Police 911Rolla Fire Department 911Phelps County Hospital 911Rolla Emergency Management Agency 911RevRevRevState AzenciesMissouri Highway PatrolMissouri State Emergency Mgt. (24 hr.)Missouri Dept. of Natural Resources (24 hr.)(573) 368-2345(573) 751-2748(573) 634-2436Missouri Bureau of Environmental Epidemiology (573) 751-6160 (573) 751-4674 (24hrs)Federal AgenciesNRC, Operations Center (301) 951-0550NRC Duty Officer (24 hr.) (301) 816-5100OtherAmerican Nuclear Insurers (860) 682-1301Radiation Emersencv Assistance Center (865) 576-3131 (865) 576-1005 (24hrs)Revised By: Maureen HenryApproved: William Bonzer 0000S' : *** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ** SOP: 507 TITLE: EMERGENCY PROCEDURES-ADMINISTRATIVE RESPONSIBILITIESRevised: October 22, 2013 Page 2 of 4 Rev* b. communicating with and requesting assistance from the following State andFederal Agencies as required:* Missouri State Highway Patrol: (573) 368-2345* U.S. Nuclear Regulatory Commission, Headquarters* Operation Center 301-951-6550*
* NRC Duty Officer (24 hr.): (301) 816-5100 or* (301) 951-0550.* Missouri State Emergency Management Agency:* (573) 751-2748*
* Missouri Bureau of Environmental Health:* (573) 751-6160 or (573) 751-4674 (24 hrs)*
* Missouri Department of Natural Resources(24-hr. emergency number): (573) 634-2436Radiation Emergency Assistance Center (Oak Ridge, TN):* (865) 576-3131 ; or (865) 481-1000 (24 hours).* .Rolla Emergency Management Agency: (573)364-1213.c. notifying the University of Missouri President and requesting University-Wide assistance, as needed.d. acting as Administrative Spokesman responsible for communications with* the news media and city officials in the absence of both the Vice Chancellor* and the Chair.2. Vice Chancellor -If offsite consequences are expected the Vice Chancellor will be0 responsible for:a. assuming the duties of the Chancellor in his or her absence. Revb. functioning as administrative spokesman responsible for communication tothe Missouri S&T Communications staff for release of news and information* to city officials.* c. assisting in the coordination of Control Group activities in the planning and* preparation phase.* d. notifying American Nuclear Insurers (860) 561-3433 as soon as possible afterdeclaration of an Alert or Site Area Emergency.* e. advising the Chancellor on problems relating to insurance and liability.B0* Reviewed By: William Boazer Approved By: William Bonzer Rev0 I00 OO00* * *
* MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** RevO SOP: 654 TITLE: MEASUREMENT OF 41Ar CONCENTRATIONIN THE REACTOR BUILDING .AIR -* Revision: October 23, 2013 Page 2 of 4O Note: 22Nahas a 1.275 MeV gamma and 41Ar has a 1.294 MeV gamma, so by usinga sodium source for comparison it is easy to determine where the argon peak willoccur.* 5. SamplinoO a. The Reactor building air sample is taken with the air tank positioned on thewest side of the Reactor pool over the fuel storage area. The Reactor building* air sample is taken periodically to detect 4'Ar or any other gaseous activity inO the confinement building air.i. Other samples are taken: on the east side of the Reactor pool near thereactor core, in the corner of the bay near the cage (repeat any of the RevO previous if needed), and on the roof near fan #2 (this one should be* done last)b. Position the air sample tank and collect the sample using an air pump. Allowthe tank to completely fill and note the time and date of the sampling.c. When sampling is complete, turn off the pump and close the tank valves.0 d. Start the stop watch immediately after the sample is taken. Rev* 6. Analysis0a. Immediately transfer, within 10 minutes, the air sampling tank to the NaIdetector in the designated room. Position the tank inside of the lead shield by RevO placing the tank in the lead shield with the hole for the detector on top. ThisO allows the NaI to be placed inside the tank without placing the weight of theO tank on the detector.b. Stop the stop watch once the counting has started. Record this number to Revcalculate decay time.@* Revised By: R@y Bono Approved By: William BonzerO .O 00000C0CS0C0CC0000C000S*** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***SOP: 654 TITLE: MIEASURElivENT OF 41Ar CONCENTRATIONIN THE REACTOR BUILDING AIRRevRevision: October 23, 2013Page 4 of 4d. Determine the concentration of activity of 41Ar taken in the grab sample ofthe Reactor building air as follows:cps 60 s~co-rds 1 Ci 1ef 1 minute 2.22 X 10 dvnz Vo lum e of takA = Concentration of 41Ar activity in sample (ýtCi/ml)eff = Currently determined efficiency of the counting setup (i.e. NaIdetector and volume of marinelli sample container) (cps/(gCi/ml))5. Re-Do Record the following data in the notebook labeled "41Ar in the ReactorBuilding."a. Date of sampleb.C.d.e.f.g.h.i.Time of sampleCount time (t)Net peak count (N)Peak count rate (R)41Ar concentration (A)Reactor power levelBuilding air flow rate (ft3/min or m3/min)Fan number, operating at time sample was taken.Revised By: Ray BonoApproved By: William Bonzer 0000S0000S00000000S*** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***SOP: 800 TITLE: ANNUAL CHECKLISTRevised: August 1, 2013 Page I of 10 Rev.Date CommencedTotal Hours on Hour MeterDate Completed1. Log and Linear Drawer Calibrationa. Log and Linear Log/Period Recorder(1) Cleaned & Lube chassis as needed (v):(2) Speed checked (1" per 5 minutes) (,/):b. LOW CIC Voltage RundownSet Point at A4TP 1: VDC x 200 -VDCVerify Rundown Initiated (/):Verify Alarms Received (V):c. 120% Full Power RundownSet Point: %Verify Rundown Initiated (,/):Verify Alarms Received (/):d. Log and Linear Detector/Cable Resistance Check(Cables should read about 1010 ohms.)(1) Signal Cable Resistance: Meg ohms(2) High Voltage Cable Resistance: Meg ohms(3) Comp. Voltage Cable Resistance: Meg ohmse. Drawer Alignment -Perform the steps listed in the following sections of thedrawer Instruction Manual:Low Voltage Power Supply Check Complete (Sec. 4.3.1):A13TBI-1 to Common reading (+15.00):A13TB1-3 to Common reading (-15.00):High Voltage and Compensating Voltage Check* Low Voltage Set Point at J6: VDC* Low Voltage Set Point at A4TP 1O-A4TP 1: VDC" NON-OPERATE LED on (,/):* Reset High Voltage (J6): VDC" High Voltage (A4TP1O-A4PP1): VDC" NON-OPERATE LED off*(/):" Compensating Voltage at J7: VDCCompensating Voltage at A5TP10-A5TP1: VDCRevised By: William BonzerApproved By: William BonzerI Rev.c ~g2.
* ** MISSOURI S&T REACTOR STANDARDSOP: 800 TITLE:Revised: March 12, 2014OPERATING PROCEDURES * * *ANNUAL CHECKLISTPage 2 of 10Rev.99909S99S000000S0SS000SLog DisplaysPicoamp Expected Tolerance for Log Log Log Initial DateCurrent Readings Reading Bargraph Digital Recorder.8 pA 1.OE-5% 4.0 E-6%-2.5 E-5%86 pA 1.OE-4% 4.0 E-5%-2.5 E-4%820 pA 1.0E-3% 7.0E-4%--1.4E-3%10 nA 1.OE-2% 7.0E-3%--1.4E-2%80 nA I.OE-I% 7.0E-2%--1.4E-0%800 nA tOE -0% 7.OE-1%-1.4E-0%8 gLA .0E+I% 7.OE-0%-1.4E+1%80 EpA 1.OE+2% 7.OE+I%-l.4E+2%Period Alignment & displays (section 4.3.4)4.3.4.1- Slope/voltage/sec:4.3.4.2- Voltage reading, with stable source, at AITP2 & A1TP10 (0.909+/-0.02)4.3.4.3- Voltage at A1TP2 & A1TP10 with 3 sec period:Settings Period Bargraph Period Digital Period Recorder DateInfinity (cc)3 SecLiner DisplaysFPocep-amp Tolerance for True True Expected Linear Bargraph Linear Digital VoltageCurrent Expected Readings Readings Display Display Tolerances Initial Date8 iLA 8%-12% 10% 0.7V-0.9V16 pA 18%-22% 20% 1.SV-1.7V24 pA 28%-32% 30% 2.3V-2.5V32 pA 38%-42% 40% 3. IV-3.3V40 pA 48%-52% 50% 3.9V-4.IV48 ,A 58%-62% 60% 4.7V-4.9V56 pA 68%-72% 70% 5.5V-5.7V64 pA 78%-82% 80% 6.3 V-6.5V72 .uA 88%-92% 90% 7. IV-7.3V80 pLA 98%-102% 100% 7.9V-8.1V88 uA 108%-112% 110% 8.7V-8.9V96 MA 118%-122% 120% 9.3V-9.7V100 .uA 123%-127% 125% 9.9V-I0.IVRevRevev.Revised By: William BonzerApproved By: William Bonzer R.,./ .--....................... .... , ..--R2ev.
00009990090S.00009*
* MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES * *SOP: 800 TITLE: ANNUAL CHECKLIST.Revised: January 29, 2014 -. Page 3 of 10 Rev.f. Isolated Outputs check (4.3:9)(,") -&#xf7;.g. Keypad switch testTest Switch Indication.1mA Log: _%_ _Lin: %0.1 uA Log: %'_'_ "Per: -0I D4O-100 sec (V)___"Lin: 0=- 1% (/).10 pA Log: < %3 SEC Per: 3.0 +/- 0.1 sec (V)_.NON-OPER L'ED On ()__LINEAR TEST- Rising Linear Lev.el (/)Trio #4: ..'%PERIOD TEST Rising Period Level (). "__Sr. ,.:_ Tri1p L: ". secTrip #2: " secTrin 43: secLOG TEST Rising .og Level (./).RevRe-vh. Cables Reconnected (,/):;..Independent Verification of Cable Cnnection, , .Initials:i. Log and Linear Drawer Calibration Complete: .iii~a. DateLinear Power Channela. Linear Power Supply(D) Clearned chassis as needed ._..b. i.er Power Supply voltageNLY7 veter diply ___utV Imliais DtR'evis.ed 'y:Wiliami Bonzer ..icpro-ed Bv: WilliaM Bonz.&#xfd; f SSSS0SSSSSSSS00S0S" * * * .MISSOURI S&T REACTOR STA.NDAR-D OPERATI[:tJ PROCEDURES ***SOP: 800. TITLE: AN U-Ai, CHECKLISTRevised: January 29,:-2O0.4 Page,4 oflO Rev,............................................................5"7,; . Linear Recorder N-..(1) Lube & Cl.,eand Chassis as needed (/"): U=(2) Speed check (1"/ 2 minutes) (V,:d. Linear Calibration (Note: From 10-5 to 10-8, the overall accuracy should be better*-than 2% of full scale. From. 9 to 10-10 the overall accuracy should be.better than 4,%. Any instrument found to be out of calibration should berealigned in accordance with procedures.):--------- METER ---- RECORDER ------PicoAmrrp Acceptable Actual Acceptable ActualGenerator Reading Reading Reading Reading6.Ox I0-A (57.A -63 jA) (57%-63%')6.0x !06A (5.7,uA-6;3gA) (57%-63%)6.0xl0 A (5%nA-630n.A) (57% .',.1.O0 0UA (57nA-63nA) (57%-63%)* ___6.0- 10-A (5_3,",-6.6nA- (53%-66%0_)6..Ox tU,"A. A530pA-66OpA) .(.3 %-66%)ik (I30pA-260pA) (13%-26%)Se. inezr I.T Detector/Cable Resistance Check (near/about I101 ohbms..)(1) Signal Cable Resistance: _ _Meg oh-ms(2) High Voltage Cable Resistance: Meg ohmsk-. Comp. Voltage Cable Resistance _ _Meg ohms(4) Reco nnect al cables( /) ._._ ..f. Lin~er Channel completed:. T.* intials Da! aR coniiecticn of cables ver ed. trtta _ Date3 Log Couant Rate Channel "a.. t Rate Recorder(1) Luce &. Cleaned chassis as needed (./':( ,2.Rozer speed (1 "/2 minruteu )/: .b Fissi.on Chanmber Preamip(U) (l.e.,eeL i chassis 'ms nee ded' .Revised B '"z. .. ,,,....... *.A -ed BV: V.1iIBarn 1,zer e 9099999909099900000009-**
* MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES * **SOP: 800 TITLE: ANNUAL CHECKLISTRevised: August 1, 2013 Page 5 of 10 Rev.c. Log Count Rate Channel Calibration(Note: All readings should give 0.7 to 1.4 ratio of true-to-observed readings.)Pulse Generator101001 00010 000MeterRecorderd. High Voltage (350 VDC to 450 VDC)e. Log Count Rate Cable CheckHigh voltage cableSignal cableFission chamber cablemeg ohmsmeg ohmsmeg ohmsf. Log Count Rate Channel completedReconnect all cablesg. Reconnection of cables verified4. Safety Amplifier Systema. Cable chec9UIC I Signal MegOhmseUIC I H.V. _MegOhmseUIC 2 Signal MegOhmseUIC 2 H.V. _MegOhmsinitialsDateinitials DateSafety Amplifier Current Tests (Safety Amplifier #1)Applied Accepted Digital Display Accepted BargraphCurrent Digital Reading Bargraph DisplayDigital Display Display6.7nA 9-11% 7-13%13.2nA 19-21% 17-23%19.8nA 29-31% 27-33%26.4nA 39-41% 37-43%33.OnA 49-51% 47-53%39.6nA 59-61% 57-63%46.2nA 69-71% 67-73%52.8nA 79-81% 77-83%59.4nA 89-91% 87-93%66.0nA 99-101% 97-103%72.6nA 109-111% 107-113%79.2nA 119-121% 117-123%85.8nA 129-131% 127-133%92.4nA 139-141% 137-143%99.OnA 149-152% 147-153%Revised By: William BonzerApproved By: William Bonzer I Rev.
00000.00000000009000000*** MISSOURI S&T REACTOR STANDARDSOP: 800 TITLE:Revised: August 1, 2013OPERATING PROCEDURES ***ANNUAL CHECKLISTPage 6 of 10I Rev.Safety Amplifier #2Applied Accepted Digital Accepted BargraphCurrent Digital Display Bargraph DisplayDigital Display Reading Display6.7nA 9-11% 7-13%13.2nA 19-21% 17-23%19.8nA 29-31%- 27-33%26.4nA 39-41% 37-43%33.0nA 49-51% 47-53%39.6nA 59-61% 57-63% _ __46.2nA 69-71% 67-73%52.8nA 79-81% 77-83%59.4nA 89-91% 87-93%66.OnA 99-101% 97-103%72.6nA 109-111% 107-113%79.2nA 119-121% 117-123%85.8nA 129-131% 127-133%92.4nA 139-141% 137-143%99.0nA 149-152% 147-153%C .*H.V. 1 Output VoltageeMonitor H.V. 1/100eH.V. 2 Output VoltageeMonitor H.V. 2/100voltsvolts-voltsvoltsd. H.V. 1 Failure Test9 Trip Point Setting(volts)" Scram Occurred (y/n)" Magnet Power Supply SCRAM Light'Illuminated (y/n)o Reset H.V. to 300VDC (y/n)e. H.V. 2 Failure Teste Trip Point Setting(volts)* Scram Occurred (y/n)" Magnet Power Supply SCRAM Light Illuminated (y/n)* Reset H.V. to 300VDC (y/n)f. NIM Bin Power SupplyOutput Voltages Readingse +24 VDC* -24 VDC9 +12 VDC* -12 VDCe +6VDCRevised By: William BonzerApproved By: William Bonzer Rev.LA) L&J.'V V f~
*** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***SOP: 800 TITLE: ANNUAL CHECKLISTRevised: August 1, 2013.-6VDCPage 7 of 10Rev.g. AC Power Off Scram Teste 150% Full Power Annunciator (y/n)*Audible Alarm (y/n)" SCRAM Occurred (y/n)" Power Restored (y/n)h. Safety Amplifier System Test CompletedInitialsDatei. Reconnection of cables verifiedInitialsDate_Rev.5. Temperature Channel(Note: All readings should be + 2&deg;F.)a. Verification of Temperature ReadingsDate00 ::~:0000000000Temperature C1 MRange(take on reading ,"from each Etemperature range) E a ,F- &c 060&deg;F-70&deg;F70&deg;F-80&deg;F80&deg;F-90&deg;F90&deg;F-125&deg;F1250F-135&deg;F1350F-145&deg;FRevised By: William Bonzer&{YU~~~YYI 5c2Approved By: William BonzerRev.
90009090SS0009000000.SSSSSS*** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***SOP: 800 TITLE: ANNUAL CHECKLISTRevised: August 1, 2013 Page 8 of 10 Rev.b. Temperature > 135 Rod withdraw prohibit test Initials __ DateThermocouple #1 Thermocouple #3> 135&deg;F Trip Temperature @> 135&deg;F Annunciator ('i)Audible Alarm (xI)RWP @ Trip ('1)Initials Datec. Low Temperature AlarmTemperature Thermocouple #1 Thermocouple #2 Thermocouple #3< 60'F Rec Alarm (d)d. Thermocouples reinstalled, cabling reconnected. Initials Date6. Regulated Power Supplya. Cleaned chassis as needed (/):b. Mode set for Line Conditioner (V)7. Conductivity Bridgea. Check & Cleaned chassis as neededb. Additional Comments8. Rod Indicator CalibrationInitials DateIndicator Rod 11 ,6"12"18"24"Rod Speeds(in/min)Rod 2Rod 3Reg. RodInitial DateRevised By: William BonzerApproved By: William Bonzer Rev.
0909000000090090000909099SS*** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ** *SOP: 800 TITLE: ANNUAL CHECKLISTRevised: August 1, 2013 Page 9 of 10 Rev.9. Fire Alarm Checka. Cleaned system containers as needed (V) __b. Checked batteries (-/)c. Checked pull stations (V)e. Checked smoke detectors (/)f. Check beam smoke detector (V/)g. Audibles & Visuals (V)h. Monitoring Station (V)i. Additional commentsCompleted Initial Date10. Security System Checka. Door Sensors (,/)b. Motion Detectors (V)c. Tamper & 24 hours circuits(,'d. Duress Alarm (/)e. Battery (V)f. High Radiation ($)g. Low Pool Water (V)h. Additional Comments:Completed11. Public Address Systema. Cleaned chassis as neededb. Additional Comments:Initial DateInitial Date12. Hand and Foot Monitora. Cleaned chassis as neededb. Perform Source Check with;_c. Additional Comments:13. Portal Detectora. Cleaned chassis as neededb. Perform Source Check with:c. Additional Comments:14. Constant Air Monitora. Cleaned chassis and recorder as neededb. Perform Source Check with:c. Additional Comments:Revised By: William BonzerApproved By: William BonzerRev.LI) ~Q&1A1~
*** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***SOP: 800 TITLE: ANNUAL CHECKLISTRevised: March 12, 2014 Page 10 of 10Rev.I Rev15. Power Calibration (SOP 816)16. RAM Calibration -RAM Calibration shall be performedannually. Record the latest date the RAM calibration was performed.Annual Calibration Comments:I have reviewed the results of this Annual Check on this date and discussed any problemsand/or errors with the operating staff.Comments:Reactor ManagerDateRevised By: William BonzerW2Q SLa"Approved By: William BonzerRev.610LLtia--
0*** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***SOP: 813 TITLE: ROD DROP TIME MEASUREMENTComplete Revision: September 5, 2013 Page 1 of 30 A. PURPOSE0 To provide instructions for determining accurate and consistent control rod drop times.B. PRECAUTIONS, PREREQUISITES, OR LIMITATIONS01. Complete a Pre-Startup Checklist prior to withdrawing rods unless core loading isbelow 50% critical mass.2. Rods shall only be withdrawn one at a time for the purpose of these tests.3. The rod drop time for each rod must be less than 1 second. If the rod drop time exceeds0 1 second the rod shall be visually inspected for pitting and cracking.4. Rod drop times must be measured a) semiannually, b) when a control assembly ismoved to a new core position, c) when a magnet assembly has been removed, and d)after rod visual inspections. (Tech. Spec. 4.2.1.)* C. PROCEDURE*' EQUIPMENT NEEDED:*1. Tenma model 72-8385 (or equivalent) oscilloscope*) 2. MicrophoneS"3. BNC cable*4. Duct tape00* STEPS:01 1. Tape microphone onto one of the rod shrouds.0 2. Connect microphone to channel I input jack of the scope.* 3. Connect BNC cable from channel 2 input of the scope to the rod drop BNC*located behind the startup channel.* 4. Perform reactor Pre-Startup Checklist as required.*5. Raise each rod 3 inches.* 6. Determine the drop current for each rod by slowly reducing magnet current untilrod drops. Record the drop currents on the rod drop measurement form.0 7. Insert all rods to 0.0 inchesi 8. Set magnet current for each magnet about 20 mAmps above drop current.00 Written By: Ray Kendrick Approved By: William Bonzer0
*** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***SOP: 813 TITLE: ROD DROP TIME MEASUREMENT* Complete Revision: September 5, 2013 Page 2 of)310 9. Recommended scope control settings are as follows:a. Trigger mode* i. Type: edgeii. Source: ch2*O iii. Slope: rise* iv. Mode: single* v. Coupling :DC mode* "b. Run/stop button: press until greenc. Input controls (chl)i. Coupling: AC* ii. BW limit: close*0 iii. Volts/div: coarseiv. Probe:xlv. Invert: closevi. Volts/division, bottom Of scope: 2mV* d. Input controls (ch2)* i. Coupling: DC.iii. BWlimit: closeiii. Probe: xliv. Invert: close0 v. Volts /division, bottom of scope :5v* e. Time/div: 100 msec.* 10. Measure the rod drop times as follows:a. Fully withdraw (24 inches) one rod. Verify the Run/Stop button is green.* b. Press the SCRAM button. (Sweep should start and the sound of rod hittingbottom should be heard.)* c. Adjust the left cursor to the ch2 rise and the right cursor to the chl burst*O beginning.d. Record the AT on the rod drops form.11. Repeat step 10 for other rods as necessary.12. Shut down or secure the reactor and remove all the rod drop equipment.9 13. Complete a reactor secured checklist, if appropriate, list all data on the rod drop time* measurement form and forward to the reactor manager for review.9000Written By: Ray Kendrick Approved By: William Bonzer0 2Y 000"90000900000000S09SS .SSS*** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***SOP: 813 TITLE: ROD DROP TIME MEASUREMENTComplete Revision: September 5, 2013Page 3 of 3ROD DROP TIME MEASUREMENT FORM[DESCRIPTION ROD [ ROD 2 ROD 31. Drop Current2. Current Used for DropTime Measurement3. Rod Drop TimePerformed By: Date:Comments:Reactor Manager Review:Written By: Ray KendrickApproved By: William BonzerW~ 3lLA-}}

Revision as of 08:24, 28 June 2018

Missouri Science and Technology Reactor Annual Process Report for 2013-2014, April 1, 2013 to March 31, 2014
ML14154A049
Person / Time
Site: University of Missouri-Rolla
Issue date: 05/26/2014
From: Bonzer W
Missouri Univ of Science & Technology
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML14154A049 (51)


Text

MISSOURIS&TMISSOURI UNIVERSITY OF SCIENCE AND TECINOLOGYFomr, Lnly rs' oU Iissc't-oi' ofMay 26, 2014

Dear Sir:

Please find enclosed the Annual Progress Report 2013-2014 for the Missouri Science andTechnology Reactor (License R-79, Docket No: 50-123). This report is being filed underthe reporting requirements of our Technical Specifications. A copy of this report is alsobeing sent to our NRC Project Manager, Mr. Greg Schoenebeck.Sincerely,L4AJ2~A,&n-kWilliam BonzerReactor ManagermhEnclosurecc: Mr. Greg Schoenebeck (NRC)Document Control Desk (NRC)V/'American Nuclear Insurers, c/o LibrarianUniversity of Missouri-Columbia Research Reactor (MURR)Chancellor Cheryl B. Schrader (MST)Michelle Bresnahan, Radiation Safety Officer (MST)Dr Hyoung Lee, Chair of Nuclear Engineering Dept. (MST)Dr. Mark Fitch, Chairman, Radiation Safety Committee (MST)Dr. Samuel Frimpong, Chair Mining and Nuclear Engineering Dept. (MST)Nuclear Reactor Facility o 250 West 13S Street% o Rolla, MO 6(5409-0637Phone: 573-341-4236 o Fax: 573-341-4237 o Email 1Aebonzer@mcst.eduAc)'2"o 0000000000000S00000PROGRESS REPORT2013-2014MISSOURI UNIVERSITY OFSCIENCE AND TECHNOLOGYREACTOR,)J2 000000000000000S0000PROGRESS REPORTFOR THEMISSOURI UNIVERSITY OF SCIENCE AND TECHNOLOGY(FORMALLY THE UNIVERSITY OF MISSOURI-ROLLA)NUCLEAR REACTOR FACILITYApril 1, 2013 to March 31, 2014Submitted toThe United States Nuclear Regulatory CommissionAndMissouri University of Science and Technology

  • ii* Table of ContentsSUMMARYS1.0 IN TR O D UCTIO N ............................................................................................................................................... I1.1 BACKGROUND INFORM ATION ............................................................................................................. 1S1.2 G ENERAL FACILITY STATUS ......................................................................................................................... 22.0 REACTO R STA FF AND PER SO NNEL ................................................................................................32.1 R EACTOR STAFF ............................................................................................................................................ 302.2 LICENSED O PERA TORS ................................................................................................................................. 42.3 RADIATION SAFETY C OM M ITTEE ................................................................................................................. 4S2.4 H EALTH PHYSICS ........................................................................................................................................... 5S3.0 R EACTO R O PERA TIO NS ............................................................................................................................... 64.0 ED UC ATIO N A L UTILIZA TIO N .................................................................................................................... 13* 5.0 REACTOR HEALTH PHYSICS ACTIVITIES ........................................................................................ 175.1 ROUTINE SURVEY ......................................................................................................................................... 175.2 BY-PRODUCT M ATERIAL R ELEASE SURVEYS ...................................................................................... 1705.3 ROUTIN E M ONITORING ................................................................................................................................ 175.4 ENVIROM ENTAL M ONITORING ..................................................................................................................... 18S5.5 W ASTE DISPOSAL .................................................... .... ............................................................................... 18S5.6 INSTRUM ENT CALIBRATIONS ....................................................................................................................... 186.0 PLANS .................................................................................................................................................................. 19S6.1 DISTANT EDUCATION .................................................................................................................................... 1906.2 REPLACEMENT OF THE REACTOR BUILDING'S HEATING SYSTEM ......................................................... 196.3 MODELING THE GAMMA SPECTORCOPY OF THE REACTOR CORE ....................................................... 206.4 GLOBAL THREAT REDUCTION INITIATIVE SECURITY ENHNANCEMENT ............................................. 206.5 REACTOR OPERATOR TRAININ G ................................................................................................................... 2000000000 0 APPENDIX A: STANDARD OPERATING PROCEDURES CHANGED DURING THE 2012-2013 REPORTING YEAR00* LIST OF TABLESTABLE 3-1. CORE 120W TECHNICAL DATA .................................................................................................. 60TABLE 3-2. CORE 121W TECHNICAL DATA ............................................................................................................. 100 TABLE 3-3. UNSCHEDULED SHUTDOWNS .................................................................................................. 8TABLE 3-4. MAINTENANCE ........................................................................................................................................ 10STABLE 3-5. EXPERIMENTAL FACILITY USAGE .......................................................................................................... 12TABLE 3-6. REACTOR UTILIZATION .................................................................................................................. 120TABLE 4-1. MISSOURI S&T CLASSES AT REACTOR FACILITY ......................................................................... 140 TABLE 4-2. REACTOR SHARING PROGRAM 2013-2014 (REPORTING PERIOD) ................................................. 1500 LIST OF FIGURES0* FIGURE 3-1. MSTR CORE 120W CONFIGURATION ................................................................................................... 6* FIGURE 3-2. MSTR CORE 121W CONFIGURATION........................................................................... 700000000000000000000
  • iv*SUMMARYDuring the 2013-2014 reporting period, the Missouri University of Science andTechnology Reactor (MSTR) was in use for 493.07 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />. The major part of this time, about90%, was used for class instruction, research, and training purposes.The MSTR operated safely and efficiently over the past year. No significant safety-related incidents or personnel exposures occurred.The reactor facility supported several Missouri University of Science and Technology0*(Missouri S&T) courses over the year for 24,768 student-hours. About 2,446 visitors visited the*reactor during the past year. There were 1,660 participants, mostly high school students, in the*U.S. Department of Energy Reactor Sharing Program.0*The reactor produced 35,496.0 kW/hrs kilowatt-hours of thermal energy usingapproximately 1.5 grams of uranium. A total of 351 samples were neutron irradiated in thereactor with the majority being analyzed in the reactor counting laboratory.000000000000000000S9

1.0 INTRODUCTION

9This progress report covers activities at the Missouri University of Science and Technology* Reactor (MSTR) Facility for the period April 1, 2013 to March 31, 2014.The reactor operates as a University facility. It is available to the faculty and students fromvarious departments of the University for their educational and research programs. Several other college* and pre-college institutions also make use of the facility. The reactor is also available for the training ofpersonnel from commercial concerns with legitimate interest in our facility use.01.1 Background Information*The Missouri University of Science and Technology Reactor (MSTR) (formally University of* Missouri-Rolla Reactor) attained initial criticality on December 9, 1961. The MSTR was the firstoperating nuclear reactor in the State of Missouri. The Bulk Shielding Reactor at Oak Ridge NationalLaboratory is the basis for the reactor's design. The reactor is a light water, open pool reactor cooled by* natural convective flow. The fuel is MTR plate-type fuel. The initial licensed power was 10 kW. The9 licensed power was up-graded to 200 kW in 1966. During the summer of 1992, the reactor fuel wasconverted from highly enriched uranium fuel to low-enriched uranium fuel.0*The facility is equipped with several experimental facilities including a beam port, thermalcolumn, three pneumatic rabbit systems, and several manual sample irradiation containers and systems.The facility also contains a counting laboratory that has both gamma and alpha spectroscopy capabilities.9 The gamma spectroscopy system includes germanium and sodium-iodide detectors, associatedelectronics, state-of-the-art data acquisition, and spectrum analysis software. The alpha spectroscopySsystem consists of a surface barrier detector and data acquisition equipment. Additionally, there is athermo luminance dosimeter reader, digital neutron radiography imager, and x-ray imager for student and* faculty usage.T~The MSTR also uses a biometric device to enhance its traditional security system.000S09 21.2 General Facility StatusThe MSTR operated safely and efficiently over the past year. No significant safety-relatedincidents or personnel exposures occurred.An independent auditor from the University of Columbia audited the reactor facility on December4, 2013. There were no significant areas of concern. There is an agreement between the MSTR and theUniversity of Missouri-Columbia to audit each other. This has been a very beneficial arrangement forboth facilities involved.The reactor staff has continued to review the operation of the reactor facility in an effort toimprove the safety and efficiency of its operation and to provide conditions conducive to its utilization bystudents and faculty. An "outreach" program, implemented over the past few years, has been continued inorder to let both students and faculty in a number of departments across campus know that the reactorcould be used to enhance course work and research. As a result, additional classes have been using thereactor facility to augment their programs, including:1. Chemistry 2, 'General Chemisty Laboratory'2 Civil Engineering 310, 'Senior Design Class'3. Engineering Management 386, 'Safety Engineering Management'4. Mechanical Engineering 229, 'Energy Conversion'5. Life Sciences 352, 'Biological Effects of Radiation'6 Physics 107, 'Modem Physics'7. Physics 207, 'Modem Physics II'8. Physics 322, 'Advanced Physics'9. Materials Science & Engineering 348, 'Energy Materials'10. Materials Science & Engineering 448, 'Advanced Energy Materials'

  • 39 SOPs were revised, over the past year in order to improve and keep current the operations and* efficiency of the MSTR. The following is a list of SOPs revised during the reporting period:* 1. Index* 2. Index3. SOP 105 Reactor Shutdown & Reactor Securing Procedures4. SOP 309 Response to a Coolant System Leak* 5. SOP 501 Emergency Procedures For Reactor Building Evacuation* 6. SOP 507 Emergency Procedures Administrative Responsibilities* 7. SOP 654 Measurement Of 4aAr Concentration In The Reactor Building Air* 8. SOP 800 Annual Checklist* 9. SOP 813 Rod Drop Time Measurement0* 2.0 REACTOR STAFF AND PERSONNEL* 2.1 Reactor Staff0O Name TitleDr. Arvind Kumarl Reactor Director0* Dr. Hyoung Kohl Lee2 Reactor DirectorMr. William Bonzer Reactor Manager & Senior OperatorMs. Maureen Henry Senior SecretaryMr. Craig Reisner Senior Reactor Operator* Mr. Ray Kendrick Senior Electronics Technic0* 1. Termination Date August 31, 2013* 2. Effective Date September 1, 2013000909 42.2 Licensed Operators1.2.3.4.5.6.7.8.9.10.11.12.13.NameWilliam BonzerCraig ReisnerEthan Barth-TaberNolan Goth'Brandon LahmannMatthew Crinnian.Kathryn KrevDustin Specker'Christopher SwisherlErica Davidson2Cody Stuchal3Ethan Margherio3Jonathan Scott3LicenseSenior OperatorSenior OperatorSenior OperatorSenior OperatorSenior OperatorSenior OperatorSenior OperatorReactor OperatorReactor OperatorReactor OperatorReactor OperatorReactor Operator*Reactor Operator1. Termination Date October 16, 20132. Effective Date December 5, 20133. Effective Date March 21, 20142.3 Radiation Safety CommitteeThe Radiation Safety Committee meets quarterly. The committee met on 6/28/2013, 9/26/2013,12/6/2013 and 2/28/2014 during the reporting period. The committee members are listed below.NameDepartment1. Dr. Mark Fitch2. Mr. Ray BonoCivil EngineeringEnvironmental Health and Safety Services 90SS0009S000SS000S0SSS53. Mr. William Bonzer4. Mr. Randy Stoll5. Dr. Robert Dubois6. Dr. David Wronkiewicz7. Dr. Shoaib Usman8. Dr. Fadha Ahmed9. Dr. Robert Aronstam10. Dr. Amitava Choudhury11. Dr. Carlos Castano12. Mr. Tony HuntNuclear ReactorBusiness ServicesPhysicsGeological Sciences & GeologyMining & Nuclear EngineeringEnvironmental Health and Safety ServicesBiological SciencesChemistryMining & Nuclear EngineeringEnvironmental Health and Safety Services2.4 Health PhysicsThe Environmental Health and Safety (EHS) Department provides the health physics support forthe Missouri S&T Reactor. The EHS Department is organizationally independent of the Reactor Facilityoperations group. Health Physics personnel are listed below.NameTitle1.2.3.4.5.6.7.8.Mr. Ray BonoMr. Brian SmithDr. Fadha AhmedMs. Kelsey FreedlineMs. Amanda BakerMs. Kelsey SalzmanMs. Kathryn KrevMr. Andrew BinghamDirector of Environmental Health and SafetyIndustrial HygienistHealth PhysicistHealth Physics Technician (part time)Health Physics Technician (part time) Left Dec. 2014Health Physics Technician (part time)Health Physics Technician (part time)Health Physics Technician (part time) 9999994S9090900096Table 3-1. Core 120W Technical DataParameter ValueRod 1 3.832% Ak/kRod 2 3.228% Ak/kRod 3 1.778% Ak/kReg Rod 0.293% Ak/kExcess Reactivity 0.652% Ak/kShutdown Margin* 4.354% Ak/k*Assumes Rod I (highest worth rod) and Reg Rod are fully withdrawn.ABCDEFSC-4 F-5 F-I F-17F-4 F-8 F-14 C-I F-10 F-2F-9 C-3 F-12 C-2 F-7 F-3CR F-15 HC F-13 BR F-6Table 3-1. MSTR 120W ConfigurationF- Standard ElementsBR- Bare RabbitCR- Cadmium RabbitKEY TO PREFIXESCR- Cadmium RabbitC- Control ElementsHC- Hot Cell RabbitHF- Half ElementS -Source Holder 99990S990S0S9S0SSS7Table 3-2. Core 121W Technical DataParameter ValueRod 1 3.950% Ak/kRod 2 3.397% Ak/kRod 3 1.975% Ak/kReg Rod 0.270% Ak/kExcess Reactivity 0.219% Ak/kShutdown Margin* 5.350% Ak/k*Assumes Rod I (highest worth rod) and Reg Rod are fully withdrawn.ABCDEFF- Standard ElemeBR- Bare RabbitCR- Cadmium RatSC-4 F-5 F-1 F-17F-4 F-8 F-14 C-1 F-10 F-11F-9 C-3 F-12 C-2 F-7 F-3CR F-15 HC F-13 BR F-6Figure 3-2. MSTR Core 121W ConfigurationKEY TO PREFIXESnts CR- Cadmium Rabbit 1-FC- Control Elements S -bbit HC- Hot Cell Rabbit-Half ElementSource Holder 8Table 3-2:Unscheduled Shutdowns for 2013-2014Date Type of Rundown/Cause and Corrective Action TakenRUNDOWNS4/8/2013 Action: 120% Demand RundownCause: Operator restarting reactor with a high residual core.Corrective Action Taken: Operator instructed to watch instrumentation.SRO on Duty granted permission to restart reactor.5/2/2013 Action: 120% Demand RundownCause: Student operator downscaled at 60% on Linear Recorder.Corrective Action Taken: SRO instructed student to downscale at 8%, not 60%.SRO on Duty granted permission to restart reactor.5/10/2013 Action: 120% Demand RundownCause: Student downscaled pico-ammeter too soon.Corrective Action Taken: SRO instructed student to follow SOP 104 regardingdownscaling at 8% and upscaling at 60 %SRO on Duty granted permission to restart reactor.6/21/2013 Action: High Area Radiation Rundown 9Cause: A sample returning to the hot cell rabbit system stopped in the glove box near thegamma radiation area monitor instead of passing 'through to the hot cell.Corrective Action Taken: SRO let the sample decay in the glove box and kept personnelout of the room containing the hot cell rabbit system. Sample was removed from glovebox after decaying.SRO on Duty granted permission to restart reactor.12/12/2013 Action: 120% Demand RundownCause: The operator did not push in on range switch far enough for it to stay pressed in.Corrective Action Taken: The operator was reminded to fully press in range switch.SRO on Duty granted permission to restart reactor.2/26/2014 Action: 120% Demand RundownCause: The operator did not fully press in the 20 kW range switch.Corrective Action Taken: No corrective action taken.SRO on Duty granted permission to restart reactor.3/5/2014 Action: 120% Demand RundownCause: The operator did not follow proper startup procedures after the reactor had beenshutdown.Corrective Action Taken: The SRO instructed the operator to follow SOP 106 whenrestarting the reactor.SRO on Duty granted permission to restart reactor.

10UNPLANNED SHUTDOWNSDate Tvne of Unnlanned Shutdown. Cause and Corrective Action TakenUnplanned Shutdowns12/16/20133/6/2014Table 3-3:Action: Rods dropped.Cause: Alternating current power flicker.Corrective Action Taken: None.SRO on Duty granted permission to restart reactor.Action: Control rod #3 dropped.Cause: Undetermined.Corrective Action Taken: None.SRO on Duty granted permission to restart reactor.Maintenance for 2013-2014Date Type of Maintenance8/20/2013 Issue: Rod drive #3 failure.Corrective Action: Removed, repaired reinstalled rod drive #3.9/4/2013 Issue: Magnet #3 failure.

Corrective Action: Removed magnet #3 and replaced with spare magnet.0* 10/1/2013 Issue: Magnet #3 failure.Corrective Action: Removed magnet #3 and replaced with spare magnet.S 1/5/2013 Issue: Magnet #3 failure.0 Corrective Action: Removed magnet #3 and replaced with spare magnet.01/15/2014 Issue: Magnet #3 failure.0 Corrective Action: Removed magnet #3 and replaced with spare magnet.00* 1/27/2014 Issue: Magnet #3 failure.0 Corrective Action: Removed magnet #3 and replaced with spare magnet.02/10/2014 Issue: Magnet #3 failure.0Corrective Action: Removed magnet #3 and replaced with spare magnet.00S 12/20/2014 Issue: Magnet #2 failure.0' Corrective Action: Removed magnet #2 and replaced with spare magnet.000t 12/04 Ise Mge 3fiue0 orcieAto:Rmvdmge # n elcdwt pr ant006 /021 su:Mge 3fiue0'Cretv cin eoe ant# n elcdwt pr ant00102/021 Isu:Mge#2fiue 000040000009S90012Table 3-5. Experimental Facility UsageFacility HoursBare Rabbit Tube 21.38 hrs.Cadmium Rabbit Tube 0.00 hrs.Beam Port 116.531 hrs.Thermal Column 0.0 hrs.Other Core Positions 3.22 hrs.Hot Cell 11.73 hrs.Gamma Exposures 0.0 hrs.Total 152.86 hrs.Table 3-4. Reactor Utilization1. Reactor use 493.07 hrs.2. Time at power 366.52 hrs.3. Energy generated 35,496.0 kW/hrs.4. Total number of samples, neutron irradiated 3515. U-235 Burned 1.553 g6. U-235 Burned and Converted 1.834 g 13* 4.0 EDUCATIONAL UTILIZATION*The reactor facility supported several Missouri S&T courses in the past year for a total of 24,764* student-hours. The number of Missouri S&T students utilizing the facility was 1,404. This usage is adirect result of an aggressive and continuing campus wide "outreach" program. The reactor facility* provided financial support for six students with hourly wages. Additionally, students from severaluniversities, colleges and high schools have used the facility.Table 4-1 lists Missouri S&T classes taught at the facility along with associated reactor usagefor this reporting period.The Reactor Sharing Program, previously funded by the U.S. Department of Energy, wasestablished for colleges, universities, and high schools that do not have a nuclear reactor. This past year,* 1,660 students and instructors from 140 institutions.participated in the program. Table 4-2 lists thoseschools and groups that were involved in this year's Reactor Sharing Program. The majority ofparticipants were high school students. MSTR coordinates with the Missouri S&T Admissions Office toschedule high school students to see other items of interest at Missouri S&T after they have visited the* reactor facility. The students visited the Missouri S&T Chapter of American Nuclear Society, theComputer Integrated Manufacturing Lab, the Foundry, Ceramics Engineering, Mineral Museum,Computer Center, Experimental Mine, Solar Car, Electron Microscope, and Stonehenge. The Reactor* Sharing Program serves as a strong campus-wide recruiting tool by attracting high school students to theuniversity and hopefully sparking some interest in nuclear engineering, science, and technology.The reactor staff continues to educate the public about applications of nuclear science. Over* 2,446 persons visited the facility during this reporting period. Tour groups are typically given a brief9orientation and/or demonstration by a member of the reactor staff.SS 0000000000900009000,900000014Table 4-1 Missouri S&T Classes at Reactor FacilitySemester CLASS NUMBERITITLE # OF TIME AT STUDENTSSTUDENTSREACTOR HOURS2013-2014 Graduate Student's Project 5 234 1170SS2013 NE 206 20 12 240SS2013 NE 308 28 129.5 25904/8/2013 NE 25 Lab 17 1.5 264/22/2013 NE 312 15 2.5 384/24/2013 NE 312 15 2.5 384/25/2014 NE 312 10 2.5 255/14/2014 NE 25 Power Changes 5 1 5FS 2013 NE 206 26 10 2609/4/2013 NE 25 Tour 3 1 39/5/2013 NE 25 Tour 9 1 99/6/2013 NE 25 Tour 9 1 9FS 2013 NE 304 34 36 122412/2/2013 NE 25 Power change 9 2 1812/4/2013 NE 25 Power change 2 2 4SS2014 NE 206 26 84 2184SS2014 NE 308 labs 20 38.5 7702/10/2014 NE 25 Tour 22 1 222/13/2014 NE 25 Tour 10 1 103/17/2014 NE 25 Lab 22 1 223/20/2014 NE 25 Lab 6 1 63/18/2014 NE 312 15 1 153/19/2014 NE 312 26 1 263/20/2014 NE 312 12 1 12_ _TOTAL 366 568 8726 09900S000000000000900000S15Table 4-2 Reactor Sharing Program 2013-2014 (Reporting Period)Date Participants Number Hours4/2013 Visitor's 17 4.54/15-4/18 Chem labs for Spring semester 2013 252 7.54/23/2013 Tour MET class 348/448 10 14/29/2013 Mountain Grove School 5 15/17/2013 Tour for families and students before graduation 21 45/16/13 Army Tour 2 16/2013 Visitor's 7 16/6/2013 Minority Introduction to Engineering 23 16/11/2013 Jackling Introduction to Engineering 18 1.56/13/2013 Jackling Introduction to Engineering 23 1.56/17/2013 Nuclear Engineering Camp (4 groups) 38 26/18/2013 Nuclear Engineering Camp (4 groups) 38 3.56/19/2013 Nuclear Engineering Camp (4 groups) 25 26/20/2013 Minority Introduction to Engineering 23 16/20/2013 Nuclear Engineering Camp (4 groups) 38 26/25/2013 Jackling Camp 18 1.56/27/2013 Jackling Camp 22 3.57/2013 Visitor's 12 2.57/9/2013 Jackling Camp 20 3.57/9/2013 Chemical Engineering Fort Leonard Wood School 23 1.57/11/2013 Jackling Camp 24 3.57/18/2013 Dr. Dewoski Class 6 1 00009000000900009009S000168/2013 Visitor's 6 18/13/2013 Video People 5 1.008/19/2013 Video People 3 .59/2013 Visitor's 7 3.59/10/2013 Tour with Walt Branson 1 .510/2013 Visitor's 13 811/5/2013 IT 1 111/6/2013 Physical Facilities 1 111/7/2013 Seymour and Norwood Schools 23 111/13/2013 Nuclear Regulatory Commission Testing 1 611/13/13 Chem labs 786 1812/3/2013 Offsite Meeting 9 112/3/13 Tour Health Class 5 112/5/2013 Tour Mansfield High School 2 612/5/2013 MURR Inspection 1 1612/9/2013 Training a person on control panel 1 612/10/2013 Computer Tech working in control room 1 81/20/2014 Visitor's 1 .51/13/2014 CDG Group 4 11/15/2014 Climax High School 21 1.51/21/2014 Group meeting on Security 14 62/2014 Visitors 6 22/12/2014 Home School Students 27 12/15/14 Boy Scout Tour 19 12/25/2014 Chemical Engineering Fort Leonard Wood School 19 1.52/26/2014 IT to test equipment 2 12/26/2014 Contractors for Asbestos removal 12 13/2014 Visitor's 4 1.5TOTAL 1660 149 06 17* 5.0 REACTOR HEALTH PHYSICS ACTIVITIES0* The health physics activities at the Missouri S&T Reactor facility consist primarily of radiation0 and contamination surveys, monitoring of personnel exposures, airborne activity, pool water activity, and0 waste disposal. Releases of all by-product material to authorized, licensed recipients are surveyed and0 recorded. In addition, health physics activities include calibrations of portable and stationary radiationdetection instruments, personnel training, special surveys and monitoring of non-routine procedures.005.1. Routine Surveys0Monthly radiation exposure surveys of the facility consist of direct gamma and neutronmeasurements. No unusual exposure rates were identified. Monthly surface contamination surveys* consist of 20 to 40 swipes counted separately for alpha and beta/gamma activity. No significantcontamination outside of contained work areas was found.905.2. By-Product Material Release SurveysThere were no shipments of by-product material released off-campus. There were three by-product releases on campus.0S5.3. Routine Monitoring9Sixty-six reactor facility personnel and students involved with the operations in the reactor* facility are currently assigned Luxel, Optically Stimulated Luminescence (OSL) dosimeters. Three of theReactor Staff have beta, gamma, neutron dosimeters which are read twice monthly. There are four areabeta, gamma, neutron dosimeters and two TLD ring dosimeters, which are also read twice monthly.SThere are also four other beta, gamma, neutron dosimeters used by the health physics personnel and threeSother area beta, gamma, neutron dosimeters that are read monthly. The remaining dosimeters detect betaand gamma radiation only and are read monthly. There are seventeen area dosimeters assigned onSSS

  • 180campus for beta and gamma monitoring and one for beta, gamma, and neutron monitoring. In addition,* six digital, direct-reading dosimeters and three chirper dosimeters are used for visitors and high radiationwork. There have been no significant personnel exposures during this reporting period. Visitors are0 monitored with direct reading dosimeters. No visitors received any reportable or significant exposure.0Airborne activity in the reactor bay is monitored by a fixed-filter, particulate continuous air9 monitor (CAM). Low levels of Argon-41 are routinely produced during operations.0*Pool water activity is monitored monthly to ensure that no gross pool contamination or fuelcladding rupture has occurred. Gross counts and spectra of long-lived gamma activity are compared toprevious monthly counts. From April 2013 through March 2014 sample concentrations averaged* 1.71x10i pCi/ml.0*Release of gaseous Ar-41 activity through the building exhausts is determined by relating the0 operating times of the exhaust fans and reactor power during fan operation to previously measured airactivity at maximum reactor power. During this period, an estimated 61,966.39 pCi of Ar-41 was.released into the air.95.4. Waste Disposal0Solid waste, including used water filters, used resins, and contaminated paper/gloves is storedand/or transferred to the campus waste storage area for later shipment to a commercial burial site. Wateris analyzed for radioactive contamination and approval is required before the water is released. During0 this period there were three waste barrels transferred from the reactor facility to the DMSF on campus.905.5. Instrument Calibrations0During this period, portable instruments and area monitors were calibrated annually.S0S0S0S 0*19o0* 6.0 PLANS0The reactor staff will be involved in several major projects during the next reporting period; 1)development of a distant education program, 2) replacement of reactor building's heating system, 3)* modeling the gamma spectroscopy of the reactor core, 4) Global Threat Reduction Initiative securityenhancements, and 5) continuation of the reactor operator training program.S06.1 Distant EducationA distant education system is being developed to conduct laboratory sessions with students of theMissouri S&T Campus and other universities. Due to the size of the Missouri S&T Nuclear Engineeringclasses, the distant education system will allow students to participate in lab sessions as one group in* larger classrooms than what is available in the MSTR building.5 Equipment has been installed to replace the existing rod drive motors and rod height indicators tooutput rod height information over the internet. Additional programing and minor wiring is beingcompleted to output control room instrumentation to be viewed live as the labs are taking place.Audio/video equipment is ready to use for students to watch reactor staff performing the labs, ask0 questions to the staff and obtain data from the control room instrumentation.oS6.2 Replacement of the Reactor Buildinz's Heating SystemS The Missouri S&T campus has been constructing a geo-thermal heating system for many of thecampus buildings. Three geo-thermal power plants will obtain heat from the ground pipe it to other9buildings. The coal power plant providing steam heat to many buildings including the MSTR will be* permanently shut down in the spring of 2014. The MSTR is not one of the buildings that will be heated* with the geo-thermal system. During the summer of 2014 the reactor building will have the steam heaters* replaced with natural gas heaters. Additional maintenance will be performed to replace existing circuitSbreaker panels and ceiling lighting located in the reactor bay while the heating system is changed out.S000oS 206.3 Modeling the Gamma Spectrocopy of the Reactor CoreA dry-well container is being built to hold a sodium iodide detector. This detector will be placenear the reactor core to obtain gamma spectrum readings from individual fuel elements. The gammareadings will be used by the Nuclear Engineering department a private firm to create a computer model ofthe MSTR core. Computer models do exist of the MSTR core, but no gamma spectrum data has beentaken from the fuel and used in previous models.6.4 Global Threat Reduction Initiative Security EnhancementsThe Pacific Northwest National Laboratory (PNNL) will enhance security of the MSTR under theGlobal Threat Reduction Initiative (GTRI) Program.6.5 Reactor Operator TrainingThe MSTR had four students obtain their license of Reactor Operator. The reactor staff is limitingoperator training to only students with a very strong desire to obtain the license and assist reactor staffwith reactor operations. At the end of the reporting period ten students were training for an operator'slicense to take in the fall of 2014 and four for their Senior Reactor Operator upgrade.

0SSSS0000SSSSSSSSSSSSSSSSSS9S9SSSS0SSS21APPENDIX A.STANDARD OPERATING PROCEDURESCHANGED DURING THE 2013-2014REPORTING YEAR S0SS0000000S000S9000000*** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***SOP: INDEX TITLE: -NýDEXRevised: August 1, 2013SOP 700 -799 ExperimentsPage 3 of3 RevSOP 702SOP 710SOP 711SOP 712Irradiation Request FormsInsertion and Removal of ExperimentsBeam Hole FacilityThermal Column FacilitySOP 800 -899 Reactor InstrumentationSOP 800SOP 801SOP 802SOP 803SOP 804SOP 805SOP 806SOP 810SOP 811SOP 812SOP 813SOP 816SOP 818Annual ChecklistLog N and Linear Drawer CalibrationLinear ChannelLog Count Rate (LCR) ChannelSafety Amplifier SystemAuto Control SystemTemperature ChannelWeekly CheckFire and Smoke Alarm SystemConfinement and Ventilation System CheckRod Drop Time MeasurementMSTR Power CalibrationFunctional Test of Building Security SystemRevRevised By: Maureen HenryApproved By: William Bonzer/ -.I : z/ -,,.. ,., f ..... -AIr xW L ~~K 00000000000S000000*** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***SOP: INDEX TITLE: INDEXRevised: September 9, 2013 Page 3 of 3SOP 700 -799 ExperimentsSOP 702SOP 710SOP 711SOP 712Irradiation Request FormsInsertion and Removal of ExperimentsBeam Hole FacilityThermal Column FacilitySOP 800 -899 Reactor InstrumentationSOP 800SOP 801SOP 802SOP 803SOP 804SOP 806SOP 810SOP 811SOP 812SOP 813SOP 816SOP 818Revised By: MaureenI ,Annual ChecklistLog N and Linear Drawer CalibrationLinear ChannelLog Count Rate (LCR) ChannelSafety Amplifier SystemTemperature ChannelWeekly CheckFire and Smoke Alarm SystemConfinement and Ventilation System CheckRod Drop Time MeasurementMSTR Power CalibrationFunctional Test of Building Security SystemHenry Approved By: William BonzerRevý 4(/~) 32~i~,

S0**MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *ev* SOP: 105 TITLE: REACTOR SHUTDOWN & REACTOR* SECTJRLNG PROCEDURES'* Revised: September 9, 2013 Page 1 of 4* A. PURPOSE*To ensure a safe and consistent method to shutdown the Reactor from an operatingcondition and, when advised, by a SRO on Duty, to secure the reactor. Rev* B. PRECAUTIONS, PREREQUISITES, AND LIMITATIONS* 1. The SRO on Duty will decide if the Reactor is to be "SHUTDOWN" or "SECURED".* 2. A Secure Checklist shall be completed at the end of the work day.0 3. Any malfunctions or abnormal conditions noted during or after the Shutdown will be* recorded in the Permanent Log and the SRO on Duty shall be notified.04. An operator assistant shall be present if the Reactor is not in "AUTO" before theshutdown begins to take logs.* 5. The RO must be alertto the indication ofjamming of control rods during the shutdownprocess. If this occurs, stop driving in the rods and inform the SRO on Duty.6. At the end of an operational run, the operator should dispose of trash, coffee cups, sodacans, etc. and leave the Control Room in a clean and orderly appearance.C. "SHUTDOWN" OF REACTOR* 1. Log time, initials, followed by "SHUTDOWN" in the hourly logo* 2. Log time and "SHUTDOWN" in the permanent log.3. Announce over the public address system, "The reactor will be shutdown".* 4. Trip "AUTO/N'ANUAL" switch to "ILMANUAL" (if in "AUTO").* 5. Place the "OPERATE/SHUTDOWNi" switch in "SHUTDOWN" position or insert* .safety rods and regulating rod with both joysticks.O0* Revised By: William Bonzer, Approved By: William Bon~zer0 , -:'." " '2 ' ..."0 0S0*** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *Re*SOP: 105 TITLE: REACTOR SHUTDOWN & REACTOR* SECURNG PROCEDURESRevised: September 9, 2013 Page 2 of 46. Monitor the decrease in reactor power by changing the Linear Meter Selector Button (lbutton to the left) when the Linear Recorder decreases to about 8% of the present scale.Operation at high power levels will prevent returning to lowest allowed scale (2 watts)Oand therefore this step is continued only until rods reach their limit.7. Maintain Log Count Rate Recorder > 20 cps by inserting fission chamber.8. Stop rod insertion when reg rod is at 1-2".9. Restart rod insertion. Rev10. When the rods are fully inserted to their insert limits (green lights):a. Return "OPERATE/SHUTDOWN" switch to "OPERATE" or,* b. Return joysticks to the "NEUTRAL" position.S11. Reactor is now "SHUTDOWN".0D. "SECURE CHECKLISTRefer to form SOP 105.1. Use date stamp.2. All rod and Reg Rod Insert Limit (Green) Lights on.3. Turn magnet key 90 degrees CCW and remove from console. Hand key to SRO on* Duty.4. Turn off the Log Count Rate, Linear, and Log/Period recorders. Place date at the topof each recorder chart (use date stamp).S5. Push Annunciator "RESET". The "NLANUAL SCRAi\M", "RECORDERS OFF" and"MANUAL OPERATION" Annunciators will remain on.6. Turn the Reactor Bridge intercom switch to the off position (button up).0S7.. Return "OPERATE/SHUTDOWN" switch to "OPERATE".B*Revised By: William Bonzer Approved By: William Bon~zer/.,' -10.., i 0SS000000000000SS0000*** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***SOP: 105 TITLE: REACTOR SHUTDOWN & REACTORSECURING PROCEDURESRevRevised: September 9, 2013Page 3 of 48. Turn TV monitor off.9. Verify both nitrogen diffusers are off.10. Verify that all vent fans are off.11. Secure the rabbit system by assufing the controller is turned off and the gas bottle isshut. Return the glove box key to the safe.12. Shut off the rabbit system nitrogen gas bottle if the rabbit has been used.13. Turn off the core lights.14. Log time using the console clock.15. Initials of person performing checklist.16. SRO on Duty shall initial.RevRevised By: William BonzerI .' 'jLA ~j ~Approved By: William Bonzer>-U '

00000000000S0000*** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***SOP: 105 TITLE: REACTOR SHUTDOWN & REACTOR SECURING PROCEDURESRevised: September 9,2013 Page 4 of 4SECURE CHECKLIST1. Date2. All Rods on Insert Limit3. Magnet Power Off andKey to SRO4. Recorders Off and Dated5. Reset Annunciator6. Reactor Bridge IntercomOff7. Shutdown Switch toOperate8. TV Monitor Off9. Nitrogen Diffusers Off10. Vent Fans Off11. Rabbit System Secured12. Rabbit Gas Off13. Core Lights Off14. Time Completed15. Operators Initials16. SRO InitialsRevRevised By: William BonzerApproved By: William Bonzer 00MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** RevSOP: 309 TITLE: RESPONSE TO A COOLANT SYSTEM LEAK* Revised: April 8, 2013 Page 1 of 10A. PURPOSETo ensure proper indication and response in the event of a leak in the coolant system.B. PRECAUTIONS, PREREQUISITES, AND LIMITATIONS* 1. Normal pool evaporation is approximately 1/10 inch per day.2. There are "vacuum breaks" in the purification piping to prevent draining the poolbelow approximately 16 ft. above the core. The cooling system will automatically Revshut down if a loss of water pressure occurs or water is detected at a floor watersensor.3. Possible causes are:O a. crack in the pool wall* b. leak in the purification systemc. leak in the seal around the beam port or thermal columnO d. leak through the "forced" cooling pipese. leak in the cooling system Rev4. Report any abnormalities to the SRO on duty.* 5. If a leak is present, shut down the reactor if it is operating.6. Minimize unnecessary exposure to radiation.C. PROCEDURES1. Monitor water level to check the rate the level is decreasing if a leak is suspected.2. Check for leaks at the purification pump, thermal column, beam port, and cooling RevO system.O 3. Check for indications of cracks in the wall (bubbles, dirt, broken cement, etc.* 4. If the leak is due to the purification system, close the pool suction valve (locatednext to the pump) # 19, and stop the purification pump.O 5. If the leak is not due to the purification system, refill the pool as per SOP 301.6. If the leak is due to the purification system or greater than the capacity of thepurification system to refill the pool, the emergency cooling hose will be used tofill as necessary.7. If the leak is due to the cooling system, turn off cooling system if it is operating. Rev* Isolate the leaking area of the cooling system by closing valves before and afterO the leaking area.0O Reviewed By: Craig Reisner Approved By: William Bonzer0 00000000S00SS0SS000S*** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES '*SOP: 501 TITLES: EMERGENCY PROCEDURES FOR REACTORBUILDING EVACUATIONRevised: September 13, 2013Page 7 of 7RevMISSOURI S&T EMERGENCY PHONE LISTReactor Staff CELL HOME WORKWilliam Bonzer, Manager, SRO 578-9463 368-0318 341-4384Craig Reisner, Senior Reactor Operator 573-247-7557 573-729-7277 341-4291Maureen Henry, Sr. Secretary 364-7272 341-6016University Administrative StaffChristine Laughlin, Director Missouri S&T Police 201-1699 816-665-1448 341-4345Dr.Cheryl B. Schrader, Chancellor 201-7392 341-5432 341-4116Walter Branson, VC Chancellor Finance & Adm. 260-402-0317 341-4122James Packard, Director Physical Facilities 578-8167 341-4252Dr. Goodman DO, Director Student Health Services 341-4284Dr. Hyoung Lee,Chair of Nuclear Eng, Reactor Director 573-202-4665 341-4585Dr.Samuel Frimpong, Chair of Mining and Nuclear 426-2338 341-7617Fadha Ahmed, Health Physicist EHS-Missouri S&T 636-223-2054 341-7014LocalMissouri S&T Police 341-4300Rolla City Police 911Rolla Fire Department 911Phelps County Hospital 911Rolla Emergency Management Agency 911RevRevRevState AzenciesMissouri Highway PatrolMissouri State Emergency Mgt. (24 hr.)Missouri Dept. of Natural Resources (24 hr.)(573) 368-2345(573) 751-2748(573) 634-2436Missouri Bureau of Environmental Epidemiology (573) 751-6160 (573) 751-4674 (24hrs)Federal AgenciesNRC, Operations Center (301) 951-0550NRC Duty Officer (24 hr.) (301) 816-5100OtherAmerican Nuclear Insurers (860) 682-1301Radiation Emersencv Assistance Center (865) 576-3131 (865) 576-1005 (24hrs)Revised By: Maureen HenryApproved: William Bonzer 0000S' : *** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ** SOP: 507 TITLE: EMERGENCY PROCEDURES-ADMINISTRATIVE RESPONSIBILITIESRevised: October 22, 2013 Page 2 of 4 Rev* b. communicating with and requesting assistance from the following State andFederal Agencies as required:* Missouri State Highway Patrol: (573) 368-2345* U.S. Nuclear Regulatory Commission, Headquarters* Operation Center 301-951-6550*

  • NRC Duty Officer (24 hr.): (301) 816-5100 or* (301) 951-0550.* Missouri State Emergency Management Agency:* (573) 751-2748*
  • Missouri Bureau of Environmental Health:* (573) 751-6160 or (573) 751-4674 (24 hrs)*
  • Missouri Department of Natural Resources(24-hr. emergency number): (573) 634-2436Radiation Emergency Assistance Center (Oak Ridge, TN):* (865) 576-3131 ; or (865) 481-1000 (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />).* .Rolla Emergency Management Agency: (573)364-1213.c. notifying the University of Missouri President and requesting University-Wide assistance, as needed.d. acting as Administrative Spokesman responsible for communications with* the news media and city officials in the absence of both the Vice Chancellor* and the Chair.2. Vice Chancellor -If offsite consequences are expected the Vice Chancellor will be0 responsible for:a. assuming the duties of the Chancellor in his or her absence. Revb. functioning as administrative spokesman responsible for communication tothe Missouri S&T Communications staff for release of news and information* to city officials.* c. assisting in the coordination of Control Group activities in the planning and* preparation phase.* d. notifying American Nuclear Insurers (860) 561-3433 as soon as possible afterdeclaration of an Alert or Site Area Emergency.* e. advising the Chancellor on problems relating to insurance and liability.B0* Reviewed By: William Boazer Approved By: William Bonzer Rev0 I00 OO00* * *
  • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** RevO SOP: 654 TITLE: MEASUREMENT OF 41Ar CONCENTRATIONIN THE REACTOR BUILDING .AIR -* Revision: October 23, 2013 Page 2 of 4O Note: 22Nahas a 1.275 MeV gamma and 41Ar has a 1.294 MeV gamma, so by usinga sodium source for comparison it is easy to determine where the argon peak willoccur.* 5. SamplinoO a. The Reactor building air sample is taken with the air tank positioned on thewest side of the Reactor pool over the fuel storage area. The Reactor building* air sample is taken periodically to detect 4'Ar or any other gaseous activity inO the confinement building air.i. Other samples are taken: on the east side of the Reactor pool near thereactor core, in the corner of the bay near the cage (repeat any of the RevO previous if needed), and on the roof near fan #2 (this one should be* done last)b. Position the air sample tank and collect the sample using an air pump. Allowthe tank to completely fill and note the time and date of the sampling.c. When sampling is complete, turn off the pump and close the tank valves.0 d. Start the stop watch immediately after the sample is taken. Rev* 6. Analysis0a. Immediately transfer, within 10 minutes, the air sampling tank to the NaIdetector in the designated room. Position the tank inside of the lead shield by RevO placing the tank in the lead shield with the hole for the detector on top. ThisO allows the NaI to be placed inside the tank without placing the weight of theO tank on the detector.b. Stop the stop watch once the counting has started. Record this number to Revcalculate decay time.@* Revised By: R@y Bono Approved By: William BonzerO .O 00000C0CS0C0CC0000C000S*** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***SOP: 654 TITLE: MIEASURElivENT OF 41Ar CONCENTRATIONIN THE REACTOR BUILDING AIRRevRevision: October 23, 2013Page 4 of 4d. Determine the concentration of activity of 41Ar taken in the grab sample ofthe Reactor building air as follows:cps 60 s~co-rds 1 Ci 1ef 1 minute 2.22 X 10 dvnz Vo lum e of takA = Concentration of 41Ar activity in sample (ýtCi/ml)eff = Currently determined efficiency of the counting setup (i.e. NaIdetector and volume of marinelli sample container) (cps/(gCi/ml))5. Re-Do Record the following data in the notebook labeled "41Ar in the ReactorBuilding."a. Date of sampleb.C.d.e.f.g.h.i.Time of sampleCount time (t)Net peak count (N)Peak count rate (R)41Ar concentration (A)Reactor power levelBuilding air flow rate (ft3/min or m3/min)Fan number, operating at time sample was taken.Revised By: Ray BonoApproved By: William Bonzer 0000S0000S00000000S*** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***SOP: 800 TITLE: ANNUAL CHECKLISTRevised: August 1, 2013 Page I of 10 Rev.Date CommencedTotal Hours on Hour MeterDate Completed1. Log and Linear Drawer Calibrationa. Log and Linear Log/Period Recorder(1) Cleaned & Lube chassis as needed (v):(2) Speed checked (1" per 5 minutes) (,/):b. LOW CIC Voltage RundownSet Point at A4TP 1: VDC x 200 -VDCVerify Rundown Initiated (/):Verify Alarms Received (V):c. 120% Full Power RundownSet Point: %Verify Rundown Initiated (,/):Verify Alarms Received (/):d. Log and Linear Detector/Cable Resistance Check(Cables should read about 1010 ohms.)(1) Signal Cable Resistance: Meg ohms(2) High Voltage Cable Resistance: Meg ohms(3) Comp. Voltage Cable Resistance: Meg ohmse. Drawer Alignment -Perform the steps listed in the following sections of thedrawer Instruction Manual:Low Voltage Power Supply Check Complete (Sec. 4.3.1):A13TBI-1 to Common reading (+15.00):A13TB1-3 to Common reading (-15.00):High Voltage and Compensating Voltage Check* Low Voltage Set Point at J6: VDC* Low Voltage Set Point at A4TP 1O-A4TP 1: VDC" NON-OPERATE LED on (,/):* Reset High Voltage (J6): VDC" High Voltage (A4TP1O-A4PP1): VDC" NON-OPERATE LED off*(/):" Compensating Voltage at J7: VDCCompensating Voltage at A5TP10-A5TP1: VDCRevised By: William BonzerApproved By: William BonzerI Rev.c ~g2.
  • ** MISSOURI S&T REACTOR STANDARDSOP: 800 TITLE:Revised: March 12, 2014OPERATING PROCEDURES * * *ANNUAL CHECKLISTPage 2 of 10Rev.99909S99S000000S0SS000SLog DisplaysPicoamp Expected Tolerance for Log Log Log Initial DateCurrent Readings Reading Bargraph Digital Recorder.8 pA 1.OE-5% 4.0 E-6%-2.5 E-5%86 pA 1.OE-4% 4.0 E-5%-2.5 E-4%820 pA 1.0E-3% 7.0E-4%--1.4E-3%10 nA 1.OE-2% 7.0E-3%--1.4E-2%80 nA I.OE-I% 7.0E-2%--1.4E-0%800 nA tOE -0% 7.OE-1%-1.4E-0%8 gLA .0E+I% 7.OE-0%-1.4E+1%80 EpA 1.OE+2% 7.OE+I%-l.4E+2%Period Alignment & displays (section 4.3.4)4.3.4.1- Slope/voltage/sec:4.3.4.2- Voltage reading, with stable source, at AITP2 & A1TP10 (0.909+/-0.02)4.3.4.3- Voltage at A1TP2 & A1TP10 with 3 sec period:Settings Period Bargraph Period Digital Period Recorder DateInfinity (cc)3 SecLiner DisplaysFPocep-amp Tolerance for True True Expected Linear Bargraph Linear Digital VoltageCurrent Expected Readings Readings Display Display Tolerances Initial Date8 iLA 8%-12% 10% 0.7V-0.9V16 pA 18%-22% 20% 1.SV-1.7V24 pA 28%-32% 30% 2.3V-2.5V32 pA 38%-42% 40% 3. IV-3.3V40 pA 48%-52% 50% 3.9V-4.IV48 ,A 58%-62% 60% 4.7V-4.9V56 pA 68%-72% 70% 5.5V-5.7V64 pA 78%-82% 80% 6.3 V-6.5V72 .uA 88%-92% 90% 7. IV-7.3V80 pLA 98%-102% 100% 7.9V-8.1V88 uA 108%-112% 110% 8.7V-8.9V96 MA 118%-122% 120% 9.3V-9.7V100 .uA 123%-127% 125% 9.9V-I0.IVRevRevev.Revised By: William BonzerApproved By: William Bonzer R.,./ .--....................... .... , ..--R2ev.

00009990090S.00009*

  • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES * *SOP: 800 TITLE: ANNUAL CHECKLIST.Revised: January 29, 2014 -. Page 3 of 10 Rev.f. Isolated Outputs check (4.3:9)(,") -÷.g. Keypad switch testTest Switch Indication.1mA Log: _%_ _Lin: %0.1 uA Log: %'_'_ "Per: -0I D4O-100 sec (V)___"Lin: 0=- 1% (/).10 pA Log: < %3 SEC Per: 3.0 +/- 0.1 sec (V)_.NON-OPER L'ED On ()__LINEAR TEST- Rising Linear Lev.el (/)Trio #4: ..'%PERIOD TEST Rising Period Level (). "__Sr. ,.:_ Tri1p L: ". secTrip #2: " secTrin 43: secLOG TEST Rising .og Level (./).RevRe-vh. Cables Reconnected (,/):;..Independent Verification of Cable Cnnection, , .Initials:i. Log and Linear Drawer Calibration Complete: .iii~a. DateLinear Power Channela. Linear Power Supply(D) Clearned chassis as needed ._..b. i.er Power Supply voltageNLY7 veter diply ___utV Imliais DtR'evis.ed 'y:Wiliami Bonzer ..icpro-ed Bv: WilliaM Bonz.ý f SSSS0SSSSSSSS00S0S" * * * .MISSOURI S&T REACTOR STA.NDAR-D OPERATI[:tJ PROCEDURES ***SOP: 800. TITLE: AN U-Ai, CHECKLISTRevised: January 29,:-2O0.4 Page,4 oflO Rev,............................................................5"7,; . Linear Recorder N-..(1) Lube & Cl.,eand Chassis as needed (/"): U=(2) Speed check (1"/ 2 minutes) (V,:d. Linear Calibration (Note: From 10-5 to 10-8, the overall accuracy should be better*-than 2% of full scale. From. 9 to 10-10 the overall accuracy should be.better than 4,%. Any instrument found to be out of calibration should berealigned in accordance with procedures.):--------- METER ---- RECORDER ------PicoAmrrp Acceptable Actual Acceptable ActualGenerator Reading Reading Reading Reading6.Ox I0-A (57.A -63 jA) (57%-63%')6.0x !06A (5.7,uA-6;3gA) (57%-63%)6.0xl0 A (5%nA-630n.A) (57% .',.1.O0 0UA (57nA-63nA) (57%-63%)* ___6.0- 10-A (5_3,",-6.6nA- (53%-66%0_)6..Ox tU,"A. A530pA-66OpA) .(.3 %-66%)ik (I30pA-260pA) (13%-26%)Se. inezr I.T Detector/Cable Resistance Check (near/about I101 ohbms..)(1) Signal Cable Resistance: _ _Meg oh-ms(2) High Voltage Cable Resistance: Meg ohmsk-. Comp. Voltage Cable Resistance _ _Meg ohms(4) Reco nnect al cables( /) ._._ ..f. Lin~er Channel completed:. T.* intials Da! aR coniiecticn of cables ver ed. trtta _ Date3 Log Couant Rate Channel "a.. t Rate Recorder(1) Luce &. Cleaned chassis as needed (./':( ,2.Rozer speed (1 "/2 minruteu )/: .b Fissi.on Chanmber Preamip(U) (l.e.,eeL i chassis 'ms nee ded' .Revised B '"z. .. ,,,....... *.A -ed BV: V.1iIBarn 1,zer e 9099999909099900000009-**
  • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES * **SOP: 800 TITLE: ANNUAL CHECKLISTRevised: August 1, 2013 Page 5 of 10 Rev.c. Log Count Rate Channel Calibration(Note: All readings should give 0.7 to 1.4 ratio of true-to-observed readings.)Pulse Generator101001 00010 000MeterRecorderd. High Voltage (350 VDC to 450 VDC)e. Log Count Rate Cable CheckHigh voltage cableSignal cableFission chamber cablemeg ohmsmeg ohmsmeg ohmsf. Log Count Rate Channel completedReconnect all cablesg. Reconnection of cables verified4. Safety Amplifier Systema. Cable chec9UIC I Signal MegOhmseUIC I H.V. _MegOhmseUIC 2 Signal MegOhmseUIC 2 H.V. _MegOhmsinitialsDateinitials DateSafety Amplifier Current Tests (Safety Amplifier #1)Applied Accepted Digital Display Accepted BargraphCurrent Digital Reading Bargraph DisplayDigital Display Display6.7nA 9-11% 7-13%13.2nA 19-21% 17-23%19.8nA 29-31% 27-33%26.4nA 39-41% 37-43%33.OnA 49-51% 47-53%39.6nA 59-61% 57-63%46.2nA 69-71% 67-73%52.8nA 79-81% 77-83%59.4nA 89-91% 87-93%66.0nA 99-101% 97-103%72.6nA 109-111% 107-113%79.2nA 119-121% 117-123%85.8nA 129-131% 127-133%92.4nA 139-141% 137-143%99.OnA 149-152% 147-153%Revised By: William BonzerApproved By: William Bonzer I Rev.

00000.00000000009000000*** MISSOURI S&T REACTOR STANDARDSOP: 800 TITLE:Revised: August 1, 2013OPERATING PROCEDURES ***ANNUAL CHECKLISTPage 6 of 10I Rev.Safety Amplifier #2Applied Accepted Digital Accepted BargraphCurrent Digital Display Bargraph DisplayDigital Display Reading Display6.7nA 9-11% 7-13%13.2nA 19-21% 17-23%19.8nA 29-31%- 27-33%26.4nA 39-41% 37-43%33.0nA 49-51% 47-53%39.6nA 59-61% 57-63% _ __46.2nA 69-71% 67-73%52.8nA 79-81% 77-83%59.4nA 89-91% 87-93%66.OnA 99-101% 97-103%72.6nA 109-111% 107-113%79.2nA 119-121% 117-123%85.8nA 129-131% 127-133%92.4nA 139-141% 137-143%99.0nA 149-152% 147-153%C .*H.V. 1 Output VoltageeMonitor H.V. 1/100eH.V. 2 Output VoltageeMonitor H.V. 2/100voltsvolts-voltsvoltsd. H.V. 1 Failure Test9 Trip Point Setting(volts)" Scram Occurred (y/n)" Magnet Power Supply SCRAM Light'Illuminated (y/n)o Reset H.V. to 300VDC (y/n)e. H.V. 2 Failure Teste Trip Point Setting(volts)* Scram Occurred (y/n)" Magnet Power Supply SCRAM Light Illuminated (y/n)* Reset H.V. to 300VDC (y/n)f. NIM Bin Power SupplyOutput Voltages Readingse +24 VDC* -24 VDC9 +12 VDC* -12 VDCe +6VDCRevised By: William BonzerApproved By: William Bonzer Rev.LA) L&J.'V V f~

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***SOP: 800 TITLE: ANNUAL CHECKLISTRevised: August 1, 2013.-6VDCPage 7 of 10Rev.g. AC Power Off Scram Teste 150% Full Power Annunciator (y/n)*Audible Alarm (y/n)" SCRAM Occurred (y/n)" Power Restored (y/n)h. Safety Amplifier System Test CompletedInitialsDatei. Reconnection of cables verifiedInitialsDate_Rev.5. Temperature Channel(Note: All readings should be + 2°F.)a. Verification of Temperature ReadingsDate00 ::~:0000000000Temperature C1 MRange(take on reading ,"from each Etemperature range) E a ,F- &c 060°F-70°F70°F-80°F80°F-90°F90°F-125°F1250F-135°F1350F-145°FRevised By: William Bonzer&{YU~~~YYI 5c2Approved By: William BonzerRev.

90009090SS0009000000.SSSSSS*** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***SOP: 800 TITLE: ANNUAL CHECKLISTRevised: August 1, 2013 Page 8 of 10 Rev.b. Temperature > 135 Rod withdraw prohibit test Initials __ DateThermocouple #1 Thermocouple #3> 135°F Trip Temperature @> 135°F Annunciator ('i)Audible Alarm (xI)RWP @ Trip ('1)Initials Datec. Low Temperature AlarmTemperature Thermocouple #1 Thermocouple #2 Thermocouple #3< 60'F Rec Alarm (d)d. Thermocouples reinstalled, cabling reconnected. Initials Date6. Regulated Power Supplya. Cleaned chassis as needed (/):b. Mode set for Line Conditioner (V)7. Conductivity Bridgea. Check & Cleaned chassis as neededb. Additional Comments8. Rod Indicator CalibrationInitials DateIndicator Rod 11 ,6"12"18"24"Rod Speeds(in/min)Rod 2Rod 3Reg. RodInitial DateRevised By: William BonzerApproved By: William Bonzer Rev.

0909000000090090000909099SS*** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ** *SOP: 800 TITLE: ANNUAL CHECKLISTRevised: August 1, 2013 Page 9 of 10 Rev.9. Fire Alarm Checka. Cleaned system containers as needed (V) __b. Checked batteries (-/)c. Checked pull stations (V)e. Checked smoke detectors (/)f. Check beam smoke detector (V/)g. Audibles & Visuals (V)h. Monitoring Station (V)i. Additional commentsCompleted Initial Date10. Security System Checka. Door Sensors (,/)b. Motion Detectors (V)c. Tamper & 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> circuits(,'d. Duress Alarm (/)e. Battery (V)f. High Radiation ($)g. Low Pool Water (V)h. Additional Comments:Completed11. Public Address Systema. Cleaned chassis as neededb. Additional Comments:Initial DateInitial Date12. Hand and Foot Monitora. Cleaned chassis as neededb. Perform Source Check with;_c. Additional Comments:13. Portal Detectora. Cleaned chassis as neededb. Perform Source Check with:c. Additional Comments:14. Constant Air Monitora. Cleaned chassis and recorder as neededb. Perform Source Check with:c. Additional Comments:Revised By: William BonzerApproved By: William BonzerRev.LI) ~Q&1A1~

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***SOP: 800 TITLE: ANNUAL CHECKLISTRevised: March 12, 2014 Page 10 of 10Rev.I Rev15. Power Calibration (SOP 816)16. RAM Calibration -RAM Calibration shall be performedannually. Record the latest date the RAM calibration was performed.Annual Calibration Comments:I have reviewed the results of this Annual Check on this date and discussed any problemsand/or errors with the operating staff.Comments:Reactor ManagerDateRevised By: William BonzerW2Q SLa"Approved By: William BonzerRev.610LLtia--

0*** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***SOP: 813 TITLE: ROD DROP TIME MEASUREMENTComplete Revision: September 5, 2013 Page 1 of 30 A. PURPOSE0 To provide instructions for determining accurate and consistent control rod drop times.B. PRECAUTIONS, PREREQUISITES, OR LIMITATIONS01. Complete a Pre-Startup Checklist prior to withdrawing rods unless core loading isbelow 50% critical mass.2. Rods shall only be withdrawn one at a time for the purpose of these tests.3. The rod drop time for each rod must be less than 1 second. If the rod drop time exceeds0 1 second the rod shall be visually inspected for pitting and cracking.4. Rod drop times must be measured a) semiannually, b) when a control assembly ismoved to a new core position, c) when a magnet assembly has been removed, and d)after rod visual inspections. (Tech. Spec. 4.2.1.)* C. PROCEDURE*' EQUIPMENT NEEDED:*1. Tenma model 72-8385 (or equivalent) oscilloscope*) 2. MicrophoneS"3. BNC cable*4. Duct tape00* STEPS:01 1. Tape microphone onto one of the rod shrouds.0 2. Connect microphone to channel I input jack of the scope.* 3. Connect BNC cable from channel 2 input of the scope to the rod drop BNC*located behind the startup channel.* 4. Perform reactor Pre-Startup Checklist as required.*5. Raise each rod 3 inches.* 6. Determine the drop current for each rod by slowly reducing magnet current untilrod drops. Record the drop currents on the rod drop measurement form.0 7. Insert all rods to 0.0 inchesi 8. Set magnet current for each magnet about 20 mAmps above drop current.00 Written By: Ray Kendrick Approved By: William Bonzer0

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***SOP: 813 TITLE: ROD DROP TIME MEASUREMENT* Complete Revision: September 5, 2013 Page 2 of)310 9. Recommended scope control settings are as follows:a. Trigger mode* i. Type: edgeii. Source: ch2*O iii. Slope: rise* iv. Mode: single* v. Coupling :DC mode* "b. Run/stop button: press until greenc. Input controls (chl)i. Coupling: AC* ii. BW limit: close*0 iii. Volts/div: coarseiv. Probe:xlv. Invert: closevi. Volts/division, bottom Of scope: 2mV* d. Input controls (ch2)* i. Coupling: DC.iii. BWlimit: closeiii. Probe: xliv. Invert: close0 v. Volts /division, bottom of scope :5v* e. Time/div: 100 msec.* 10. Measure the rod drop times as follows:a. Fully withdraw (24 inches) one rod. Verify the Run/Stop button is green.* b. Press the SCRAM button. (Sweep should start and the sound of rod hittingbottom should be heard.)* c. Adjust the left cursor to the ch2 rise and the right cursor to the chl burst*O beginning.d. Record the AT on the rod drops form.11. Repeat step 10 for other rods as necessary.12. Shut down or secure the reactor and remove all the rod drop equipment.9 13. Complete a reactor secured checklist, if appropriate, list all data on the rod drop time* measurement form and forward to the reactor manager for review.9000Written By: Ray Kendrick Approved By: William Bonzer0 2Y 000"90000900000000S09SS .SSS*** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***SOP: 813 TITLE: ROD DROP TIME MEASUREMENTComplete Revision: September 5, 2013Page 3 of 3ROD DROP TIME MEASUREMENT FORM[DESCRIPTION ROD [ ROD 2 ROD 31. Drop Current2. Current Used for DropTime Measurement3. Rod Drop TimePerformed By: Date:Comments:Reactor Manager Review:Written By: Ray KendrickApproved By: William BonzerW~ 3lLA-