ML12151A118

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Missouri University of Science and Technology - Annual Progress Report 2010-2011
ML12151A118
Person / Time
Site: University of Missouri-Rolla
Issue date: 05/23/2012
From: Bonzer W
Missouri Univ of Science & Technology
To:
Document Control Desk, Office of Nuclear Reactor Regulation
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MISSOURI S&T MISSOURI UNIVERSITY OF SCIENCE AND TECHNOLOGY Fcwnerhy Urversiry of Missouli-Ro*ja May 23, 2012

Dear Sir:

Please find enclosed the Annual Progress Report 2010-2011 for the Missouri Science and Technology Reactor (License R-79, Docket No: 50-123). This report is being filed under the reporting requirements of our Technical Specifications. A copy of this report is also being sent to our NRC Project Manager, Ms. Linh N. Tran.

Sincerely, C-'u~ L-<~

William Bonzer Reactor Manager mh Enclosure cc: Linh Tran, Project Manager (NRC)

Document Control Desk (NRC)

American Nuclear Insurers, c/o Librarian University of Missouri-Columbia Research Reactor (MURR)

Chancellor Cheryl B. Schrader (MST)

Mr. Ray Bono, Radiation Safety Officer (MST)

Dr Arvind Kumar, Chair of Nuclear Engineering Dept. (MST)

Dr. Mark Fitch, Chairman, Radiation Safety Committee (MST)

Dr. Samuel Frimpong, Chair Mining and Nuclear Engineering Dept. (MST)

PROGRESS REPORT 2011-2012 MISSOURI UNIVERSITY OF, SCIENCE AND TECHNOLOGY REACTOR

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PROGRESS REPORT FOR THE MISSOURI UNIVERSITY OF SCIENCE AND TECHNOLOGY (FORMALLY THE UNIVERSITY OF MISSOURI-ROLLA)

NUCLEAR REACTOR FACILITY April 1, 2011 to March 31, 2012 Submitted to The United States Nuclear Regulatory Commission And Missouri University of Science and Technology

ii Table of Contents

SUMMARY

1.0 INTR O DU CTIO N ............................................................................................................................................... 1

1.1 BACKGROUND

INFORMATION .............................................................................. 1 1.2 G ENERAL FACILITY STATUS ......................................................................................................................... 2 2.0 R EA CTO R STA FF AND PER SONN EL ..................................................................................................... 3 2.1 R EACTOR STAFF ............................................................................................................................................ 3 2.2 LICENSED O PERATORS ................................................................................................................................. 4 2.3 RADIATION SAFETY C OM MITTEE ................................................................................................................. 5 2.4 H EALTH PHYSICS ........................................................................................................................................... 6 3.0 REACTO R O PERA TIO N S ................................................................................................................................ 6 4.0 EDU CATIO N A L U TILIZATIO N .................................................................................................................... 13 5.0 REACTO R H EA LTH PH Y SICS A CTIV ITIES .......................................................................................... 17 5.1 R OUTINE SURVEY ......................................................................................................................................... 17 5.2 BY-PRODUCT M ATERIAL R ELEASE SURVEYS ............................................................................................. 17 5.3 ROUTINE M ONITORING ................................................................................................................................ 17 5.4 ENVIROM ENTAL M ONITORING ..................................................................................................................... 18 5.5 WASTE DISPOSAL ......................................................................................................................................... 19 5.6 INSTRUM ENT CALIBRA TIONS ....................................................................................................................... 19 6.0 PLAN S ................................................................................................................................................................. 19 6.1 COOLING SYSTEM FOR THE R EACTOR POOL .......................................................................................... 19 6.2 D ISTANT EDUCATION ................................................................................................................................... 19 6.3 REACTOR O PERATOR TRA INING ................................................................................................................. 20 APPENDIX A: STANDARD OPERATING PROCEDURES CHANGED DURING THE 2011-2012 REPORTING YEAR LIST OF TABLES TABLE 3-1. C ORE 120W TECHNICAL DATA ............................................................................................................... 7 TABLE 3-2. UNSCHEDULED SHUTDOW NS FOR 2011-2012 ..................................................................................... 8 TABLE 3-3. MAINTENANCE FOR 2011-2012 ........................................................................................................ 10

111 TABLE 3-4. REACTOR UTILIZATION .......................................................................................................................... 11 TABLE 3-5. EXPERIMENTAL FACILITY USAGE ....................................................................................................... 12 TABLE 4-1. MISSOURI S&T CLASSES AT REACTOR FACILITY ................................................................................. 14 TABLE 4-2. REACTOR SHARING PROGRAM 2011-2012 (REPORTING PERIOD) .................................................... 15 LIST OF FIGURES FIGURE 3-1. MSTR CORE 120W CONFIGURATION ........................................................................................... 7

iv

SUMMARY

During the 2011-2012 reporting period, the Missouri University of Science and Technology Reactor (MSTR) was in use for 489.7 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, about 90%, 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 Technology (Missouri S&T) courses over the year for 2,058 student-hours. About 1,671 visitors visited the reactor during the past year. There were 664 participants, mostly high school students, in the U.S. Department of Energy Reactor Sharing Program.

The reactor produced 26,680 kW/hrs kilowatt-hours of thermal energy using approximately 1.1 grams of uranium. A total of 329 samples were neutron irradiated in the reactor with the majority being analyzed in the Reactor Counting Laboratory.

I

1.0 INTRODUCTION

This progress report covers activities at the Missouri University of Science and Technology Reactor (MSTR) Facility for the period April 1, 2011 to March 31, 2012.

The reactor operates as a University facility. It is available to the faculty and students from various 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 of personnel from commercial concerns with legitimate interest in our facility use.

1.1 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 first operating nuclear reactor in the State of Missouri. The Bulk Shielding Reactor at Oak Ridge National Laboratory 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. The licensed power was up-graded to 200 kW in 1966. During the summer of 1992, the reactor fuel was converted from highly enriched uranium fuel to low-enriched uranium fuel.

The facility is equipped with several experimental facilities including a beam port, thermal column, 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.

The gamma spectroscopy system includes germanium and sodium-iodide detectors, associated electronics, state-of-the-art data acquisition, and spectrum analysis software. The alpha spectroscopy system consists of a surface barrier detector and data acquisition equipment. Additionally, there is a thermo luminance dosimeter reader, digital neutron radiography imager, and x-ray imager for student and faculty usage.

The MSTR also uses a biometric device to enhance its traditional security system.

2 1.2 General Facility Status The MSTR operated safely and efficiently over the past year. No significant safety-related incidents or personnel exposures occurred.

An independent auditor from the University of Columbia audited the reactor facility on December 14, 2011. There were no significant areas of concern. There is an agreement between the MSTR and the University of Missouri-Columbia to audit each other. This has been a very beneficial arrangement for both facilities involved.

The reactor staff has continued to review the operation of the reactor facility in an effort to improve the safety and efficiency of its operation and to provide conditions conducive to its utilization by students and faculty. An "outreach" program, implemented over the past few years, has been continued in order to let both students and faculty in a number of departments across campus know that the reactor could be used to enhance course work and research. As a result, additional classes have been using the reactor 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, 'Modern Physics'
7. Physics 207, 'Modern Physics II'
8. Physics 322, 'Advanced Physics'

3 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. SOP Index
2. SOP 104 Reactor Power Changes and Stable Operations
3. SOP 111 Measurement of Core excess Reactivity and Determination of Shutdown Margin
4. SOP 302 Inspection of Control Rod Note: The above listed SOP revisions are in Appendix A.

2.0 REACTOR STAFF AND PERSONNEL 2.1 Reactor Staff Name Title Dr. Arvind Kumar Reactor Director Mr. William Bonzer Reactor Manager & Senior Operator Ms. Maureen Henry Senior Secretary Mr. Craig Reisner' Senior Reactor Operator 2

Mr. Ray Kendrick Senior Electronics Technician

1. Upgraded from Sr. Lab. Mechanic to Senior Reactor Operator on 3/19/2012
2. Starting date 7/5/2011

4 2.2 Licensed Operators Name License

1. William Bonzer Senior Operator 2
2. Michelle Bresnahan Senior Operator
3. Craig Reisner Senior Operator
4. Ethan Barth-Taber' Senior Operator 4
5. Jeff George Senior Operator
6. Luke Echols Senior Operator 2
7. Spenser Spacek '4 Senior Operator 3
8. Nolan Goth Senior Operator 4
9. Brandon Lahmann Senior Operator 2
10. Thea Tadlock1' Reactor Operator 3
11. Dustin Specker Reactor Operator 4
12. Tyler Knewtson Reactor Operator 3
13. James Hegger Reactor Operator 4
14. Matthew Crinnian Reactor Operator
1. Effective Date April 11, 2011
2. Termination Date September 9, 2011
3. Effective Date November 1, 2011
4. Effective Date November 2, 2011

5 2.3 Radiation Safety Committee The Radiation Safety Committee meets quarterly. The committee met on 6/22/2011, 9/22/2011, 12/2/2011 and 1/19/2012 during the reporting period. The committee members are as follows:

Name Department

1. Dr. Mark Fitch Civil Engineering
2. Mr. Ray Bono Environmental Health and Safety
3. Mr. William Bonzer Nuclear Reactor
4. Mr. Randy Stoll Business Services
5. Ms. Michelle Bresnahan' Environmental Health and Safety
6. Dr. Robert Dubois Physics
7. Dr. David Wronkiewicz Geological Sciences & Engineering
8. Dr. Shoaib Usman Mining & Nuclear Engineering 2
9. Dr. Fadha Ahmed Environmental Health and Safety
10. Dr. Robert Aronstam Biological Sciences 1I. Dr. Amitava Choudhury Chemistry
12. Dr. Carlos Castano Mining & Nuclear Engineering I Michelle Bresnahan left the RSC on June 30, 2011 2 Fadha Ahmed started on January 3, 2012

6 2.4 Health Physics The Environmental Health and Safety (EHS) Department provides the health physics support for the Missouri S&T Reactor. The EHS Department is organizationally independent of the Reactor Facility operations group. The health physics personnel are as follows:

Name Title

1. Ray Bono Director of EHS
2. Fadha Ahmed Health Physicist
4. Michael Hall Health Physics Technician (part time)
5. Kelsey Freedmen Health Physics Technician (part time)
6. Kelsey Salzmann Health Physics Technician (part time)

I. Michelle Breshanhan left of 6/30/2011

2. Thea Tadlock left on6/15/2011
3. Philip Mennemeyer left on 5/15/2011
4. Stacy Nowak left on 5/15/2011
5. Kelsey Salzmann start date 2/14/2011
6. Michael Hall start date 4/5/2011
7. Kelsey Freedmen start date 8/31/2011
8. Fadha Ahmed start date 4/5/2011 3.0 REACTOR OPERATIONS Core Confirmation 120W is presently in use. The "W" mode core is completely water reflected and is used for normal reactor operations. The "T" mode (core positioned near graphite thermal column) may be used for thermal column experiments. Table 3-1 presents pertinent core data and Figure 3-1 shows the core configuration of core 120W. The excess reactivity, shutdown margin, and rod worth's were measured in cold, clean conditions.

7 Table 3-1. Core 120W Technical Data Parameter Value Rod 1 3.832%Ak/k Rod 2 3.228 %Ak/k Rod 3 1.778%Ak/k Reg Rod 0.293 %Ak/k Excess Reactivity 0.652 %Ak/k Shutdown Margin* 4.354%Ak/k

  • Assumes Rod 1 (highest worth rod) and Reg Rod are fully withdrawn.

A B S C C-4 F-5 F-1 F-17 D F-4 F-8 F-14 C-1 F-10 F-2 E F-9 C-3 F-12 C-2 F-7 F-3 F CR F-15 HC F-13 BR F-6 Figure 3-1. MSTR Core 120W Configuration KEY TO PREFIXES F- Standard Eleme nts CR- Cadmium Rabbit HF- Half Element BR- Bare Rabbit C- Control Elements S - Source Holder CR- Cadmium Ralbbit HC- Hot Cell Rabbit

8 Table 3-2:Unscheduled Shutdowns for 2011-2012 DateType of Rundown/Cause and Corrective Action Taken RUNDOWNS 6/8/2011 120% Demand Rundown Cause: Operator failed to upscale picoammeter.

Corrective Action Taken: No corrective action taken.

SRO on Duty granted permission to restart reactor..

11/29/2011 120% Demand Rundown Cause: unknown.

Corrective Action Taken: No corrective action taken.

SRO on Duty granted permission to restart reactor.

2/3/2012 120% Demand Rundown Cause: Operator failed to upscale picoammeter.

Corrective Action Taken: Operator was instructed to watch instrumentation.

SRO on Duty granted permission to restart reactor.

2/3/2012 120% Demand Rundown Cause: Linear recorder spiked due to picoammeter spike.

Corrective Action Taken: none at this time.

SRO on Duty granted permission to restart reactor.

9 UNPLANNED SHUTDOWNS Date Type of Unplanned Shutdown, Cause and Corrective Action Taken Unplanned Shutdowns 9/26/2011 Action: Rod #2 dropped Cause: Undetermined.

Corrective Action Taken: Magnet current adjusted to a higher value.

SRO on Duty granted permission to restart reactor.

10/3/2011 Action: Rods #2 & #3 dropped Cause: Suspected power flicker.

Corrective Action Taken: Magnet current adjusted to a higher value.

SRO on Duty granted permission to restart reactor.

10/3/2011 Action: Rod #3 dropped Cause: Unknown.

Corrective Action Taken: Magnet current adjusted to a higher value.

SRO on Duty granted permission to restart reactor.

10/3/2011 Action: Rods #2 & #3 dropped Cause: Magnet current flickered.

Corrective Action Taken: Replaced magnet #3.

SRO on Duty granted permission to restart reactor.

10 10/11/2011 Action: Scram light flashed.

Cause: Unknown.

Corrective Action Taken: Troubleshot scram circuit.

SRO on Duty granted permission to restart reactor.

10/11/2011 Action: Magnet #3 current went to 0 mA for a moment.

Cause: Magnet failed.

Corrective Action Taken: Replaced magnet #3 and performed rod drop time test.

SRO on Duty granted permission to restart reactor.

Table 3-3: Maintenance for 2011-2012 Date Type of Maintenance 10/17/2011 Issue: Magnet #3 failed.

Corrective action taken: Removed magnet #3 and replaced with spare magnet. Performed rod drop time test for control rod #3.

10/18/2011 Issue: Failure of RAM in lower level basement.

Corrective action taken: Repaired electronic circuit in RAM.

10/20/2011 Issue: Demineralizer RAM and Experiment Room RAM had poor response to the internal source for each RAM.

Corrective action taken: Repositioned internal source closer to gm tube for each RAM.

7/19/2011 Issue: Green lamp not lit on Bridge RAM's remote meter.

Corrective action taken: Replaced lamp.

11 11/3/2011 Issue: Low sensitivity to the check source for each of the RAMs.

Corrective action taken: Adjusted the source closer to GM tube and checked position for each of the RAMs.

12/6/2011 Issue: Noise causing log count rate recorder to change wildly.

Corrective action taken: Replaced an input transistor and resistor in the preamp.

Table 3-4. Reactor Utilization

1. Reactor use 489.7 hrs
2. Time at power 338.8 hrs
3. Energy generated 26,680.4 kW/hrs
4. Total number of samples, neutron irradiated 329
5. U-235 Burned 1.115 g
6. U-235 Burned and Converted 1.317 g

12 Table 3-5. Experimental Facility Usage Facility Hours Bare Rabbit Tube 7.97 hr Cadmium Rabbit Tube 1.63 hr Beam Port 59.47 hr Thermal Column 0.0 hr Other Core Positions 16.50 hr Hot Cell 1.45 hr Gamma Exposures 0.0 hr Total 87.02 hr

13 4.0 EDUCATIONAL UTILIZATION The reactor facility supported several Missouri S&T courses in the past year for a total of 2,058 student-hours, The number of Missouri S&T students utilizing the facility was 356. This usage is'a direct result of an aggressive and continuing campus wide "outreach" program. The reactor facility provided financial support for four students with hourly wages. Additionally, students from several universities, colleges and high schools have used the facility.

Table 4-1 lists Missouri S&T classes taught at the facility along with associated reactor usage for this reporting period.

The University of Missouri-Columbia Nuclear Engineering Department again sent its NE 404 class, "Advanced Reactor Laboratory," to our facility for a total of 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> to participate in a wide variety of reactor-based experiments. The MSTR staff and student-licensed operators conducted the laboratory.

The Reactor Sharing Program, previously funded by the U.S. Department of Energy, was established for colleges, universities, and high schools that do not have a nuclear reactor. This past year, 664 students and instructors from 143 institutions participated in the program. Table 4-2 lists those schools and groups that were involved in this year's Reactor Sharing Program. The majority of participants were high school students. MSTR coordinates with the Missouri S&T Admissions Office to schedule 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, the Computer 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 the university 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 1,671 persons visited the facility during this reporting period. Tour groups are typically given a brief orientation and/or demonstration by a member of the reactor staff.

14 Table 4-1 Missouri S&T Classes at Reactor Facility Semester CLASS NUMBER/TITLE # OF TIME AT STUDENTS STUDENTS REACTOR HOURS 2011-2012 Graduate Student's Project's 5 56 280 SP 2011 NE 206 22 10 220 SP 2011 NE 308 18 3 54 04/04/11 NE 25 31 1 31 04/04/11 NE 404 Columbia Class 10 6 60 04/19/11 NE 312 11 1 11 04/20/11 NE 312 15 2 30 04/21/11 NE 312 14 2 28 04/26/11 NE 25 Power Change 10 2.5 25 04/27/11 NE 25 Power Change 9 2 18 FS 2011 NE 206 17 26 442 FS 2011 NE 304 29 16 464 11/01/11 NE 25 NAA Lab 28 1 28 12/08/11 NE 25 18 3 54 12/09/11 NE 25 10 3 30 01/09/12 NE 25 16 1 16 01/23/12 NE 25 Half-Life 16 1 16 SP 2012 NE 206 38 1 38 SP 2012 NE 308 6 4 24 02/13/12 NE 25 Half-Life 15 1 15 02/14/12 Radio Chemistry Hot Cell Equipment 3 4 12 2011-2012 Trainee Hours 15 50 162 Total 356 1965 2058

15 Table 4-2 Reactor Sharing Program 2011-2012 (Reporting Period)

Date Participants Number Hours 4/2011 Individual tours for April 14 2 04/29/11 Girl Scout Tour 35 2 05/2011 Individual tours for May 22 5 06/2011 Individual tours for June 9 2 06/05/11 Minority Introduction to Engineering 26 1 06/16/11 National Science Foundation Pre-College Tour 5 .5 06/21/11 Jackling Camp 2 groups 43 3 06/23/11 Minority Introduction to Engineering 14 1 06/23/11 Jackling Camp 14 1.5 06/23/11 Jackling Camp 2 groups 45 1.5 06/23/11 Chemical Engineering Fort Leonard Wood School 15 1.5 07/2011 Individual Tours for July 22 3 07/12/11 Jackling Camp 2 groups 35 3 07/13/11 Risk Analysis Group 18 1 07/14/11 Risk Analysis Group 11 1 07/14/11 Jackling Camp 2 groups 26 2 07/18/11 Nuclear Engineering Camp 2 groups 40 2 07/18/11 Nuclear Engineering Camp 4 groups 40 4 07/21/11 Nuclear Engineering Camp 3 groups 40 1.5 07/26/11 Jackling Camp 2 groups 29 3 07/28/11 Jackling Camp 2 groups 20 3.5 08/2011 Individual tours for August 10 3 08/15/11 Nuclear Regulatory Commission Inspection 2 24 09/2011 Individual Tours September 6 2 09/21/11 Radio Techs 2 5 09/22/11 Radio Techs 2 5 09/26/11 Nuclear Career Fair Tour 7 1

16 10/2011 Individual Tours October 18 3.5 10/05/11 Pre-Bidding meeting Cooling System 11 1 10/13/11 Job shadowing Nicholas Temini 1 6 10/17/11 NRC Testing 3 days 2 14 11/2011 Individual Tours November 4 1.5 12/2011 Individual Tours December 5 1 12/14/11 MURR Yearly Audit 2 6 12/21 / 11 Offsite Yearly Meeting 10 1 01/2012 Individual Tours January 3 1.5 02/2012 Individual Tours February 7 2 2/18/12 Boy Scouts 36 2 3/2012 Individual Tours March 13 3 TOTAL 664 127.5

17 5.0. REACTOR HEALTH PHYSICS ACTIVITIES The health physics activities at the Missouri S&T Reactor facility consist primarily of radiation and contamination surveys, monitoring of personnel exposures, airborne activity, pool water activity, and waste disposal. All by-product material released from the reactor facility to authorized recipients is documented and surveyed. In addition, health physics activities include calibrations of portable and stationary radiation detection instruments, personnel training, special surveys, and monitoring of non-routine procedures.

5.1. Routine Surveys Monthly radiation surveys of the facility consist of direct gamma and neutron measurements.

There have been no unexpected exposure rates identified. Monthly surface contamination surveys consist of 20 to 40 swipes counted separately for alpha and beta/gamma activity. There has been no significant contamination outside of contained work areas found.

5.2. By-Product Material Release Surveys There were no shipments of by-product material released off-campus. There was no by-product release on campus.

5.3. Routine Monitorin$!

One hundred and five reactor facility personnel and students involved with the operations in the reactor facility are currently assigned, Thermoluminescent Dosimeters (TLDs). Three of the Reactor Staff have beta, gamma, and fast neutron dosimeters which are read twice monthly. There are also three other beta, gamma dosimeters used by the health physics personnel. There are also four area beta, gamma, and fast neutron dosimeters and two ring dosimeters, which are read twice monthly. There are seven other area beta, gamma, neutron dosimeters that are read monthly. The remaining dosimeters detect beta, gamma, and neutron radiation only and are read monthly. In addition, nine digital, direct-reading dosimeters and three chirper dosimeters are used for visitors and high radiation work. There have been no

18 significant personnel exposures during this reporting period. No visitor that was monitored with direct reading dosimeter received any reportable or significant exposure. There are twenty eight area dosimeters assigned on campus for beta, gamma and neutron monitoring and one for beta, gamma, and fast neutron monitoring.

Airborne activity in the reactor bay is monitored by a fixed filter, particulate continuous air-monitor (CAM). Low levels of Argon-41 are routinely produced during operations. Release of gaseous Ar-41 activity through the building exhausts is determined by relating the operating times of the exhaust fans and reactor power during fan operation to previously measured air activity at maximum reactor power. During the period from April 2011 through March 2012, an estimated 108,517.5 pCi of Ar-41 was released into the air.

Pool water activity is monitored monthly to ensure that no gross pool contamination or fuel cladding rupture has occurred. Gross counts and spectra of long-lived gamma activity are compared to previous monthly counts. During this period, sample concentrations averaged 4.489xl 0- 5 ýtCi/ml.

5.4. Environmental Monitoring There are three environmental dosimeters (TLDs) in place around the reactor building in order to monitor the environment for radiation exposure resulting from activities taking place at the reactor.

These badges are read quarterly. All exposures were within specified limits between April 2011 and March 2012.

5.5. Waste Disposal Solid waste, including used water filters, used resins, and contaminated paper/gloves is stored and/or transferred to the campus waste storage area for later shipment to a commercial burial site. The reactor pool water is analyzed for radioactive contamination and approval is required before the water is released into the sanitary sewer if necessary. During this period there was no waste transferred from the reactor facility to the DMSF on campus.

19 5.6. Instrument Calibrations Calibration of portable instruments and area monitors was completed according to schedule.

6.0 PLANS The reactor staff will be involved in several major projects during the next reporting period; 1) installation of a cooling system for the reactor pool, 2) development of a distant education system, and 3) continuation of the reactor operator training program.

6.1 Cooling System for the Reactor Pool A cooling system for the reactor pool was being installed during the end of the reporting period.

The system is designed to keep the reactor pool temperature constant while the reactor is at full power, 200 kW. The cooling system is a three-phase system with pool water piped to a heat exchanger located in the reactor bay, a second water system taking heat from the heat exchanger to an air-cooled chiller located outside the reactor building. Construction will be complete during the spring of 2012.

6.2 Distant Education A distant education system is being developed to conduct laboratory sessions with students of the Missouri S&T Nuclear Engineering program and students at other universities. Due to the size of the Missouri S&T Nuclear Engineering classes, 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.

Equipment purchases will include motor drives for control rods, data acquisition and video conferencing equipment, web-based multichannel analyzers, and HPGe detectors.

20 6.3 Reactor Operator Trainin2 The Missouri S&T Reactor had three students upgrade their license to Senior Reactor Operator, two students obtain their Senior Reactor Operator license and five students obtain their Reactor Operator license. The reactor staff is limiting operator training to only students with a very strong desire to obtain the license and assist reactor staff with reactor operations. At the end of the reporting period thirteen students were training for an operator's license.

21 APPENDIX A.

STANDARD OPERATING PROCEDURES CHANGED DURING THE 2011-2012 REPORTING YEAR

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***

SOP: INDEX TITLE: INDEX Revised: October 28, 2011 Page 1 of 3 SOP 100-199 Routine Reactor Operation SOP 100 Preamble SOP 101 General Operational Procedures SOP 102 P.re-Startup Checklist Procedures SOP 103 Reactor Startup to Low Power SOP 104 Reactor Power Changes and Stable Operations SOP 105 Reactor Shutdown & Reactor Securing Procedures SOP 106 Restart of Reactor When It Is Not Secured SOP 107 Permanent Log, Hourly Log, and Operational Data SOP 109 Determination of Control Rod Worths by the Rod Drop Method SOP 110 Calibration of Control Rods by Positive Period Method SOP 111 Measurement of Core Excess Reactivity and Determination of Shutdown Margin SOP 112 Fuel Management SOP 150 Response to Alarms SOP 151 Response to a High Area Radiation Alarm SOP 200-299 Facility Operations SOP 200 Bridge Movement Procedure Rev.

SOP 206 Installation and Removal of Experimental Facilities SOP 207 Fuel Handling SOP 208 Reactor Security SOP 209 Securing the Building SOP 210 Occupying Building When Intrusion System Inoperative SOP 300-399 Special Operations SOP 301 Pool Water System SOP 302 Inspection of Control Rod SOP 303 Pool Water Cooler System SOP 306 Estimation of Activity and Reactivity Worth of a Sample SOP 308 Restoration of Power Following a Power Outage SOP 309 Response to a Coolant System.Leak SOP 3 10 Facility Modifications SOP 311 Receipt of Licensed Materials SOP 312 Critical Experiment Procedures Revised By: Maureen Henry Approved By: William Bonzer

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***

SOP: INDEX TITLE: INDEX Revised: October 28, 2011 Page 2 of 3 SOP 400-499 Reserved for Future Use SOP 500-599 Emergency Procedures SOP 501 Emergency Procedures for Reactor Building Evacuation SOP 502 Emergency Procedures for an Unusual Event SOP 503 Emergency Procedures for an Alert SOP 504 Emergency Procedures for a Site Area Emergency SOP 505 Enhanced Reactor Security SOP 506 Bomb Threat SOP 507 Emergency Procedures - Administrative Responsibilities SOP 508 Tornado Threat SOP 509 Fire SOP 510 Earthquake SOP 511 Response to Missing Special Nuclear Material SOP 600-699 Health Physics Procedures SOP 600 General Health Physics SOP 601 Handling of Radioactive Samples SOP 602 Entry Into A High Radiation Area SOP 603 Release of By - Product Materials On Campus SOP 604 Radioactive Waste Handling Criteria SOP 615 Radiation Work Permit SOP 620 Decontamination Procedures SOP 621 Guidelines for Emergency Exposures SOP 622 Handling Injured in Radiation Accidents SOP 650 Radiation Area Survey SOP 651 Contamination Survey SOP 652 Pool Water Tritium Analysis SOP 653 Sealed Source Leak Test SOP 654 Measurement of 41Ar Concentration in the Reactor Building Air SOP 655 Radiation Area Monitor (RAlVl) Calibrations Revised By: Maureen Henry Approved By: William Bonzer 2

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      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***

SOP: INDEX TITLE: INDEX Revised: October 28, 2011 Page 3 of 3 SOP 700 - 799 Experiments Rev SOP 702 Irradiation Request Forms Rev SOP 710 Insertion and Removal of Experiments SOP 711 Beam Hole Facility SOP 712 Thermal Column Facility SOP 800 - 899 Reactor Instrumentation SOP 800 Semi-Annual Checklist SOP 801 Log N and Linear Drawer Calibration SOP 802 Linear Channel SOP 803 Log Count Rate (LCR) Channel SOP 804 Safety Amplifier System SOP 805 Auto Control System SOP 806 Temperature Channel SOP 810 Weekly Check SOP 811 Fire and Smoke Alarm System SOP 812 Confinement and Ventilation System Check SOP 813 Rod Drop Time Measurement SOP 816 MSTR Power Calibration SOP 818 Functional Test of Building Security System Revised By: Maureen Henry Approved By: William Bonzer

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    • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 104 TITLE: REACTOR POWER CHANGES AND STABLE OPERATIONS Revised: February 9, 2012 Page 1 of 4 A. PURPOSE To provide for a safe and consistent method to 1) change power after the reactor has been leveled at low power and 2) operate the reactor at steady-state power.

B. PRECAUTIONS, PREREQUISITES. OR LIMITATIONS

1. This procedure is applicable after SOP 103, "Reactor Startup to Low Power" has been completed.
2. Both Safety Channels and the Power Range of the Log and Linear drawer should begin to show turnaround at about 500 W. If turnaround has not been observed by a power of 1 Rev kW, the reactor will be shut down and the SRO on Duty notified.
3. At least one nitrogen diffuser should be turned on for operations greater than 20 kw.

This requirement may be waived by the SRO on Duty for special tests. Reactor bridge radiation levels shall not be allowed to equal or exceed 50 mr/hr.

4. Prior to taking the reactor to a power level in excess of 100 kW, the reactor must first be leveled at a power between 10 kW and 100 kW and hourly logs taken to verify the proper operation of the reactor instrumentation. This requirement is only applicable to the first power increase above 100 kW for a particular operational run.
5. At least one building exhaust fan shall be turned on for reactor operations at 200 kW.
6. At least one building exhaust fan should be turned on when the constant air monitor reaches a value of about 1500 cpm.
7. The licensed operator shall control all reactivity changes to the reactor by direct manipulation or by directing the manipulation of the controls and experiments being conducted at the facility.
8. The operator must be alert and attentive at all times during reactor operations. All nuclear instruments (Startup, Linear, Period, Log, Safety No. 1, Safety No. 2, and the Power Range of the Log and Linear drawer) must be closely monitored for proper response. If at any time an improper response is suspected, the SRO on Duty shall be notified and a reactor shutdown initiated as deemed necessary by the Reactor Operator.

Revised By: William Bonzer Approved By: William Bonzer

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    • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES Rev SOP: 104 TITLE: REACTOR POWER CHANGES AND STABLE OPERATIONS Revised: February 9, 2012 Page 2 of 4
9. The console operator should scram or shut down the reactor without hesitation if any doubt exists about reactor safety.
10. If a scram or rundown occurs, permission to restart the reactor can only be authorized by the SRO on Duty.
11. The following steps will list the Shim/Safety Rods as rods and the Regulating Rod as reg Rev rod.

C. POWER INCREASE PROCEDURE

1. Record the intent to increase power with the time in the permanent logbook.

Example: 1028 Reactor started to 20 kW.

2. Announce the intention to increase power over the PA system.

Example: "Reactor power will be increased from 20 W to 20 kW."

3. Switch the reactor to "Manual" control.
4. Carefully monitor all nuclear instruments (Startup, Linear, Period, Log, Safety No. 1, Safety No. 2, and the Power Range of the Log and Linear drawer) for proper response during the power transient.
5. Withdraw rods in small increments while carefully monitoring the "prompt jump" on the Period Channel. The prompt jumps should normally not be allowed to reach a 30 second period.
6. Limit the rate of power increase to an approximate 50 second persistent period as indicated by the Period Channel. The SRO on Duty may authorize shorter periods. Rev
7. Upscale the Linear Channel as necessary when it reaches approximately 60% of scale. Rev If the Linear Channel is reading 60% or greater prior to initiating the power increase, it may be upscaled before beginning the power increase.
8. Level the reactor at the desired power.
9. Place the reactor in autocontrol.

Revised By: William Bonzer Approved By: William Bonzer

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    • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 104 TITLE: REACTOR POWER CHANGES AND STABLE OPERATIONS Revised: February 9, 2012 Page 3 of 4
10. RAFT (Reset, Announce, Fission Chamber, Time):
a. Reset the annunciator panel. Verify that the "Manual" light is off when in autocontrol.
b. Announce the reactor power over the building PA.
c. Position Fission Chamber to read midscale.
d. Record Time at power in the permanent log.

Example: 1032 Reactor at 20 kW.

11. Complete the Hourly Log Sheet.

D. POWER DECREASE PROCEDURE

1. Record the intent to change power in the permanent logbook.

Example: 1401 Reactor power decreased to 60 kW.

2. Announce the intention to change power over the PA system.

Example: "Reactor power will be decreased from 200 kW to 60 kW."

3. Switch the reactor to "Manual" control.
4. Carefully monitor all nuclear instruments (Start-up, Linear, Period, Log, Safety No. 1, Safety No. 2, and the Power Range of the Log and Linear drawer) for proper response during the power transient.
5. Insert rods to achieve the desired rate of power decrease.
6. Reposition the Fission Chamber as necessary to keep the reading on the upper half of the scale.
7. Downscale the Linear Channel as necessary when the reading reaches about 8%.
8. Level reactor power at the desired power level.
9. Place the reactor in autocontrol.

Revised By: William Bonzer Approved By: William Bonzer

    • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 104 TITLE: REACTOR POWER CHANGES AND STABLE OPERATIONS Revised: February 9, 2012 Page 4 of 4
10. RAFT (Reset, Announce, Fission Chamber, Time):
a. Reset the annunciator panel. Verify that the "Manual" light is off when in autocontrol.
b. Announce the reactor power over the building PA.
c. Position Fission Chamber to read midscale.
d. Record Time at power in the permanent log.

Example: 1406 Reactor at 60 kW.

11. Complete the Hourly Log Sheet.

E. STEADY STATE POWER OPERATIONS

1. Constant Power - Automatic Control
a. In the event an abnormality is detected in the automatic control system, the reactor shall be switched to manual control and the SRO on Duty notified.
b. The position of the reg rod should be monitored to assure that it does not reach the Rev insert or withdrawal limit while in auto control. In the event the reg rod reaches approximately the 6 inch or 18 inch position, switch to manual and reposition rods while maintaining the constant power level. If the rods approach the withdrawal Rev limit or lower limit of shim range, the SRO on Duty should be notified.
c. Complete the hourly operating log at hourly intervals.
2. Constant Power - Manual Control
a. The power level should be maintained constant by manually adjusting rods. The Operator will continuously monitor the instrumentation. All entries in permanent log or the hourly log should be recorded by an assistant. Rev
b. At hourly intervals, an assistant should be summoned to record the appropriate information in the hourly operation log.

Revised By: William Bonzer Approved By: William Bonzer

      • MISSOURI S&T STANDARD OPERATING PROCEDURES ***

SOP: 111 TITLE: MEASUREMENT OF CORE EXCESS REACTIVITY Rev ANND DETERMINATION OF SHUTDOWN MARGIN Revised: February 9, 2012 Page 1 of 3 A. PURPOSE:

To provide for the consistent and safe method of measuring core excess reactivity and for determining shutdown margin.

B. PRECAUTIONS, PREREQUISITES, OR LIMITATIONS:

1. The reactor should be "clean" when performing this procedure. The reactor will be considered clean if operations within the previous 52 hours6.018519e-4 days <br />0.0144 hours <br />8.597884e-5 weeks <br />1.9786e-5 months <br /> have been limited to 20 kilowatt-hours.
2. Refer to SOP 109 and SOP 110 for rod calibration procedures.
3. Following any change in core configuration, the excess reactivity of the core shall be determined for both the W and T modes.
4. The shutdown margin shall be determined after the excess reactivity of the core and the total worth of each control rod have been experimentally determined for a new core conflguration.
5. Excess reactivity and shutdown margin requirements are as follows:
a. Students and trainees may operate the reactor under the direct supervision of a licensed RO provided the excess reactivity is less than 0.7% delta k/k.

Rev

b. Trainees may operate the reactor under the direct supervision of a SRO when the excess reactivity is equalto or greater than 0.7% delta k/k and less than 1.5% delta k/k.
c. The minimum shutdown margin under any condition of operation with the Rev highest worth control rod and any non-scrammable control rod fully withdrawn shall be no less than 1.0% delta k/k.

C. EXCESS REACTIVITY MEASUREMENT PROCEDURE:

Excess reactivity may be measured by either the Positive Period Method or the Static Method. Both methods are described below.

Revised By: William Bonzer Approved By: William Bonzer

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      • MISSOURI S&T STANDARD OPERATING PROCEDURES ***

SOP: 111 TITLE: MEASUREMENT OF CORE EXCESS REACTIVITY Rev AND DETERMINATION OF SHUTDOWN MARGIN Revised: February 9, 2012 Page 2 of 3 1 Positive Period Method

a. Take the reactor critical at a low power (e.g. 20 watts).
b. Verify that the neutron source is removed from the source tube.
c. Log the critical rod positions.
d. Use the positive period method described in SOP 110 to measure the reactivity worth of each rod tip. The rod tip is that portion of the rod between the critical rod position and the fully withdrawn position. For example, if the critical rod height of a rod was 21.0 inches, the rod tip would be the portion of the rod between 21.0 inches and fully withdrawn (24.0 inches).
e. The excess reactivity is the sum of the reactivity worths of all four rod tips.
2. Static Method
a. Obtain Critical Rod Heights. Obtain critical rod heights for the reactor at a low power of 20 watts with the neutron source removed.
b. Determine Critical Rod Worths. Use the rod worth curves to determine the reactivity worth of each rod at its respective critical rod height.
c. Sum Critical Rod Worths. Sum the critical rod worths found above for 4

all four rods, 'i PCritical'

d. Sum of the Total Rod Worths. Sum the total reactivity worths for each 4

rod when fully withdrawn (use the rod worth curves), Z t PTotaJ."

e. Compute Excess Reactivity. Calculate the core excess reactivity PExCess by subtracting the sum critical rod worth's from the sum of the total rod worth's as follows:

4 PExcess Tota -. PCritical i=2. A=Wi Revised By: William Bonzer Approved By: William Boazer

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  • '*MISSOURI S&T STANDARD OPERATING PROCEDURES ***

SOP: 111 TITLE: MEASUREMENT OF CORE EXCESS REACTIVITY Rev AND DETERMINATION OF SHUTDOWN MARGIN Revised: February 9, 2012 Page 3 of 3 D. SHUTDOWN MARGIN DETERMINATION PROCEDURE:

1. Determine the Total Rod Worths. Sum the total reactivity worths for each rod when fully withdrawn for all four rods (use the rod worth curves).
2. Determine the Excess Reactivity. Determine the excess reactivity by one of the methods described in Section C above.
3. Determine the Total High Rod Worth. Using the rod worth curves, determine the total worth of the highest worth rod when fully withdrawn, PHgh Rod
4. Determine the Total Reg Rod Worth. Using the rod worthRe,curves, Rod determine the total worth of the regulating rod when fully withdrawn, PRod
5. Calculate the Shutdown Margin. Calculate the shutdown margin by subtracting the excess reactivity, the total high rod worth, and the total regulating rod worth from the sum of the total rod worths as shown below:

4 High Rod Reg Rod SDM = P,'ta - PExcess - PTotal - PTotal Revised By: William Bonzer Approved By: William Bonzer i 1.

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES
  • Rev SOP: 302 TITLE: INSPECTION OF CONTROL RODS Revised: December 13, 2011 Page 1 of 2 A. REACTIVITY REQUIREMENTS Before a control rod can be removed from the core, all fuel elements necessary to ensure the loading is below 50% of the critical mass when all rods are removed, shall be removed from the core.

B. PERSONNEL REOUIREMENTS For this procedure there must be a Senior Operator and one assistant with some fuel Rev handling experience in the bay area. A Reactor Operator will be in the control room. A Health Physicist or their delegate shall monitor radiation levels.

C. MATERIAL REQUIREMENTS Rod removal jumper cable with auxiliary magnet and rod removal safety basket. I Rev.

D. PROCEDURE

1. Person in charge will contact the Reactor Manager to obtain permission to start Rev this procedure.
2. The startup check out will be completed, and the rods withdrawn to shim range. Rev
3. Fuel transfer forms (SOP 207) will be filled out and checked for accuracy. Rev
4. Fuel will be transferred one element at a time as directed by person in charge, until all required elements have been removed in accordance with SOP 207. If the fuel has been previously unloaded (eg. the day before) it is not necessary to repeat the startup check out procedure; however, it would be proper to have the recorders on.
5. The rods will be fully inserted into the core and magnet power de-energized. Rev
6. The scram magnet extension and control rod drive shroud will be removed and Rev suspended from bridge.

Revised By: William Bonzer Approved By: William Bonzer

I

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 302 TITLE: INSPECTION OF CONTROL RODS Revised: December 13, 2011 Page 2 of 2
7. Connect the auxiliary magnet to the 12VDC power supply.

Rev

8. Place the rod removal safety basket as close tothe rod to be removed as possible.
9. The auxiliary magnet will manually be placed on the rod to be removed and magnet power energized.
10. The Senior Operator will carefully supervise the withdrawal of the rod and placement of it in the safety basket.
11. De-energize magnet power and disconnect the auxiliary magnet. Carefully raise the basket containing the rod
12. The Health Physicist shall monitor radiation levels of the rod as it comes out of the pool, is behind the shielding, and as it is placed into the pool.
13. When the rod is out of the pool, place the rod behind as much shielding as necessary, and inspect for pitting and cracking. Record general comments and any particular information for each rod.
14. Log results of inspection into the permanent logbook.
15. Using basket, lower rod into the pool, and position near control rod elements.

Position magnet over the rod, energize magnet power and withdraw the rod from the basket. Place rod into control rod element and de-energize magnet power.

Rod shall be positioned with front half of rod facing center of pool. Front half is identified with black marking on top of control rod.

16. Repeat steps 8 through 15 for the other two rods.
17. Reinstall magnet extensions and rod drive shrouds.
18. Perform Rod Drop Time Measurement per SOP 813.
19. Reload core per SOP 207.

Revised By: William Bonzer Approved By: William Bonzer

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