ML16153A141

Annual Progress Report 2015-2016 for the Missouri Science and Technology Reactor

ML16153A141
Person / Time
Site:	University of Missouri-Rolla
Issue date:	05/26/2016
From:	Bonzer W Missouri Univ of Science & Technology
To:	Office of Nuclear Reactor Regulation
References
Download: ML16153A141 (65)

Text

lVlISSOURI UNIVERSITY OF SCIENCE AND TECHNOLOGY Formeriy University of Missouri-Roi/a May 26, 2016 pear Sir:

Please find enclosed the Annual Progress Report 2015-2016 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, Mr. Spyros Teailforos Sincerely, William Bonzer Reactor Manager mh Enclosure cc: Mr. Spyros Teailforos (NRC) /

Document Control Desk (NRC) V American Nuclear Insurers, c/o Librarian University 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. Ralph Flori Jr, Chair Mining and Nuclear Engineering Dept. (MST)

.I

PROGRESS REPORT 2015-2016 MISSOURI UNIVERSITY OF SCIENCE AND TECHNOLOGY REACTOR

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

NUCLEAR REACTOR FACILITY April 1, 2015 to March 31, 2016 Submitted to The United States Nuclear Regulatory Commission And Missouri University of Science and Technology

11 Table of Contents

1.0 INTRODUCTION

............................................................................................................................................... 1

1.1 BACKGROUND

INFORMATION ....................................................................................................................... 1 1.2 GENERAL FACILITY STATUS ......................................................................................................................... 2 2.0 REACTOR STAFF AND PERSONNEL ...................................*...................................................................... 3 2.1 REACTOR STAFF ............................................................................................................................................. 3 2.2 LICENSED OPERATORS ........................................................................................................................... ;..... 4 2.3

• RADIATION SAFETY COMMITTEE ................................................................................................................. 4 2.4 HEALTH PHYSICS ........................................................................................................................................... 5 3.0 REACTOR OPERATIONS ................................................................................................................................ 6 4.0 EDUCATIONAL UTILIZATION .................................................................................................................... 11 5.0 REACTOR HEALTH PHYSICS ACTIVITIES ........................................................*..................................... 14 5.1 ROUTINE SURVEYS ....................................................................................................................................... 14 5.2 BY-PRODUCT MATERIAL RELEASE SURVEYS ............................................................................................. 14 5.3 ROUTINEMONITORING ................................................................................................................................ 14 5.4 WASTE DISPOSAL .......................................................................................................................................... 15 5.5 INSTRUMENT CALIBRATIONS ....................................................................................................................... 15 6.0 PLANS ....................................................................................................... :...*..................................................... 16 6.1 DISTANT EDUCATION ............................................................... :....................................... ;............................ 16 6.2 REACTOR OPERATOR TRAINING ....................................................... .-........................................................... 16

111 APPENDIX A: STANDARD OPERATING PROCEDURES CHANGED DURING THE 2015-2016 REPORTING YEAR LIST OFT ABLES TABLE 3-1. CORE 122W TECHNICAL DATA .................................................. ;............................................................ 6 TABLE 3-2. UNSCHEDULED SHUTDOWNS .*....*....*............*.*.............*..*..*..*.....*.................*..*..............*.*...*.*................ 7 TABLE3-3. MAINTENANCE *......***..*..........**.*.*..*.....*.*..*.....*...**.*.*..........*..*.*.*...*.*.*.***.*.....*.****..*.....*.*.*.......*.*.*............ 9 TABLE 3-4. EXERIMENTAL FACILITY USAGE ......**.*..*...*.........*.*.*........*.................***..*..*..........*..*..*..................*....... 10 TABLE 3.5 REACTOR UTILIZATION .**......**.*.*.......*..*..*.*.*......*.*......*.*..*..*....*.*...*...*.***.*.*.*.**.*....*.**....*.....*.*.........**..... 10 TABLE 4-1. MISSOURI S&T CLASSES AT REACTOR FACILITY .*....*.**.*..*................*.*.*...*.......*.*..*..*.......*..*.......**..... 12 TABLE 4-2. REACTOR SHARING PROGRAM 2015-2016 (REPORTING PERIOD) *.*.*.....*.*.*..*..........*.........*.*............... 13 r'

LIST OF FIGURES FIGURE 3-1. MSTR CORE 122W CONFIGURATION .*...........*.*...**.*.....**........*.*.*.*.*.*.*.*.*.......***.............*.*......*..*........ 6

lV

SUMMARY

During the 2015-2016 reporting period, the Missouri University of Science and Technology Reactor (MSTR) was in use for 348.78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 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 over 4,180 student-hours. About 3,460 visitors visited the reactor during the past year. There were 820 participants, mostly high school students, in the U.S. Department of Energy Reactor Sharing Program.

The reactor produced 9679.24kW/hrs. kilowatt-hours of thermal energy usmg approximately 0.423 grams of uranium. A total of 136 samples were neutron irradiated in the reactor with the majority being analyzed in the reactor counting laboratory.

1

1.0 INTRODUCTION

This progress report covers activities at the Missouri University of Science and Technology Reactor (MSTR) Facility for the period April 1, 2015 to March 31, 2016.

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 high-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 acqui~ition, and spectrum analysis software. The alpha spectroscopy system consists of a surface barrier detector and data acquisition equipment. Additionally, there is a thermos-luminance dosimeter reader, digital neutron radiography imager, digital x-ray imager, and liquid scintillation counter for student and faculty usage.

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 Missouri - Columbia audited the reactor facility on December 9, 2015. There were no significant areas of concern. There is an agreement between the MSTR and the University of Missouri-Columbia Research Reactor 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, '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'

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 207 FUEL HANDLING

3. SOP 306 ESTIMATION OF ACTIVITY AND REACTIVITY WORTH OF A SAMPLE

4. SOP 308 RESTORATION OF AC POWER FOLLOWING A POWER OUTAGE

5. SOP 312 CRITICAL EXPERMENT PROCEDURES

6. SOP 501 EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION

7. SOP 653 SEALED SOURCE LEAK TEST

8. SOP 702 IRRADIATION REQUEST FORMS

9. SOP 801 LOG AND LINEARDRAWER CALIBRATION

10. SOP 811 FIRE AND SMOKE ALARM SYSTEM

11. SOP 816 MSTR POWER CALIBRATION

12. SOP 818 FUNCTION TEST OF THE BUILDING SECURTIY SYSTEM 2.0 REACTOR STAFF AND PERSONNEL 2.1 Reactor Staff Dr. Hyoung Kohl Lee Reactor Director Mr. William Bonzer Reactor Manager & Senior Operator Ms. Maureen Henry Office Support Assistant III Mr. Craig Reisner Senior Reactor Operator Mr. Anthony Alchin 1 Electronic Technician III & Senior Operator

1. Effective 5-18-2015

4 2.2 Licensed Operators Name License

1. William Bonzer Senior Operator

2. Craig Reisner . Senior Operator

3. Anthony Alchin Senior Operator

4. Erica Davidson 1 Reactor Operator

5. Cody Stuchal Reactor Operator 1

6. Ethan Margherio Reactor Operator

7. Jonathan Scott Reactor Operator

8. Andrew Bingham Reactor Operator

9. Garrett Jones Reactor Operator

10. Steve Wagstaff Reactor Operator

11. Wesley Tucker Reactor Operator

12. Matthew Caddeli2 Reactor Operator 2

13. Jacob Stueck Reactor Operator 2

14. Justen Vinyard Reactor Operator

1. Termination Date August 6, 2015

2. Effective Date October 15, 2015 2.3 Radiation Safety Committee The Radiation Safety Committee meets quarterly. The committee met on 6/26/2015, 9/25/2015, 12/7/2015 and 3/16/2016 during the reporting period. The committee members are listed below.

Department

1. Dr. Mark Fitch Civil Engineering

2. Ms. Michelle Bresnahan Environmental Health and Safety Services

3. Mr. William Bonzer Nuclear Reactor

4. Mr. Randy Stoll Business Services

5. Dr. David Wronkiewicz Geological Sciences & Geology

6. Dr. Shoaib Usman Mining & Nuclear Engineering

5

7. Dr. Fadha Ahmed Environmental Health and Safety Services

8. Dr. Yue-wern Huang 1 Biological Sciences

9. Dr. Amitava Choudhury Chemistry

10. Dr. Carlos Castano Mining & Nuclear Engineering

11. Mr. Tony Hunt Environmental Health and Safety Services

12. Dr. Robert Aronstam2 Biological Science

1. Joined 7-14-2015

. 2. Resigned 7-30-2015 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. Health Physics personnel are listed below:

1. Ms. Michelle Bresnahan Director of Environmental He~lth and Safety

2. Mr. Brian Smith Industrial Hygienist

3. Dr. Fadha Ahmed Health Physicist

4. Mr. Andrew Bingham Health Physics Technician (part time) Left May, 2015

5. Mr. Alex Swearingen Health Physics Technician (part time)

6. Mr. Wesley Tucker Health Physics Technician (part time)

6 3.0 REACTOR OPERATIO NS Core Confirmation 122W 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 122W. The excess reactivity, shutdown margin, and rod worth's were measured in cold, clean conditions.

Table 3-1. Core 122W Technical Data Parameter Value Rod 1 3.958% L1k/k Rod2 3.239% L1k/k Rod3 1.778% L1k/k Reg Rod 0.232% i1k/k Excess Reactivity 0.640% i1k/k Shutdown Margin* 4.3 77% i1k/k

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

A B s c C-4 F-5 F-11 F-17 D F-4 F-8 F-14 C-1 F-10 F-1 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 122W Configuration

7 KEY TO PREFIXES F- Standard Elements CR- Cadmium Rabbit HF- Half Element BR- Bare Rabbit C- Control Elements S - Source Holder CR- Cadmium Rabbit HC- Hot Cell Rabbit Table 3-2: Unscheduled Shutdowns for 2015-2016 Date Type of Rundown/Cause and Corrective Action Taken RUNDOWNS 05/05/2015 Action: 120% demand rundown Cause: Student did not press 200W scale button hard enough.

Corrective Action Taken: Student reminded to firmly press button SRO on Duty granted permission to restart reactor.

10/20/2015 Action: 120% demand rundown Cause: Trainee did not push 200W scale button in firmly.

Corrective Action Taken: Trainee instructed to push buttons in firmly.

SRO on Duty granted permission to restart reactor.

10/26/2015 Action: 120% demand rundown Cause: Student downscaled instead of upscaled.

Corrective Action Taken: Student instructed to pay more attention to which scale they are pushing.

SRO on Duty granted permission to restart reactor.

8 11/02/2015 Action: 120% demand rundown 1

Cause: Student did not fully push in Linear Channel button.

Corrective Act~on Taken: Student told to press buttons more firmly.

SRO on Duty granted permission to restart reactor.

02/03/2015 Action: 120% Full Power Rundown Cause: UIC inserted into core too much during power calibration.

Corrective Action Taken: Instructed to not let go ofUIC.

SRO on Duty granted permission to restart reactor.

02/23/2016 Action: 120% demand rundown Cause: Linear channel scale not pushed in all the way.

Corrective Action Taken: SRO talked to trainee about pushing buttons in firmly.

SRO on Duty granted permission to restart reactor.

UNPLANNED SHUTDOWNS Date Type of Unplanned Shutdown, Cause and Corrective Action Taken Unplanned Shutdowns*

12/10/2015 Action: Power Outage Corrective Action Taken: None. Reactor was secured and operations ended for the day.

9 Table 3-3: Maintenance for 2015-2016 Type of Maintenance 6/23/2015 Issue: Period <30s Trip Activated and unable to be cleared Corrective Action: Relay K2 discovered to be failed replaced with suitable replacement relay. Weekly checklist performed to ensure proper operation of Log & N Drawer.

6/24/2015 Issue: Reg Rod joystick threads holding joystick to console stripped beyone usability.

Corrective Action: Replaced joystick with a 3 position lever switch originally meant for Auto Permit switch. Verified proper operation. Lever Switch as opposed to joystick should have less strain on the threads holding the switch to console. Replaced Main Control Rods Joystick with a Lever Switch for conformity '1!1d to prevent future problems of the same type.

12/03/2016 Issue: Clutch was slipping when rods fully inserted in core. Rod #3 still trying to drive in.

Corrective Action: Limit switch replaced and moved to new higher location. Slip Clutch readjusted to take less pressure to slip on insert.

01/11/2016 Issue: Linear Recorder Output erratic and unstable*.

Corrective Action: Amplifier Module determined cause of issue. Replaced module with one from a spare recorder in the loft. No erratic or unstable output observed after replacement after an hour of continuous running.

10 Table 3-4. Experimental Facility Usage Facilitv Hours Bare Rabbit Tube 8.78 hrs.

Cadmium Rabbit Tube 0.00 hrs.

I Beam Port 0.0 hrs.

Thermal Column 0.0 hrs.

Other Core Positions 3.94 hrs.

Hot Cell 0.0 hrs.

Gamma Exposures 3.2 hrs.

Total 15.92 hrs.

Table 3-5. Reactor Utilization

1. Reactor use 348.78 hrs.

2. Time at power 231.73 hrs.

3. Energy generated 9679.24 kW/hrs.

4. Total number of samples, neutron irradiated 136

5. U-235 Burned 0.423 g

6. U-235 Burned and Converted 0.500 g

11 4.0 EDUCATIONAL UTILIZATION The reactor facility supported several Missouri S&T courses in the past year for a total of over 4,180 student-hours. The number of Missouri S&T students utilizing the facility was 698. 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.

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

The Reactor Sharing Program, previously funded by the U.S. Department of Energy, was established for col~eges, universities, and high schools that do not have a nuclear reactor. This past year, 479 students and instructors from 140 *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 3,460 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.

12 Table 4-1 Missouri S&T Classes at Reactor Facility CLASS #OF TIME AT STUDENTS Semester NUMBER/TITLE STUDENTS RECTOR HOURS 2015- Graduate Students 2016 Project 4* 56.5 226 SS 2015 NE 2406 30 26 780 SS 2015 NE 4438 25 6 150 SS 2015 NE 1105 Tours 17 1 17 SS 2015 NE 1105 Tours 18 1 18 4/8/2015 NE 4312 16 2 32 4/9/2015 NE 4312 16 2 32 4/10/2015 NE 4312 12 2 24 4/14/2015 NE 1105 Lab 17 1 17 4/17/2015 NE 1105 Lab 16 1 16 4/20/2015 Economics Class- 20 1 20 4/21/2015 Chem Lab 1319 60 1 60 4/22/2015 Chem Lab 1319 60 1 60 4/22/2015 NE 4312 20 2 40 4/22/2015 Chem Lab 1319 60 1 60 4/23/2015 NE 4312 16 2 32 4/24/2015 NE 4312 12 2 24 FS 2015 NE2406 17 42 714 9/4/2015 NE 1105 Tour 31 2 62 9/5/2015 NE 1105 Lab 17 1 17 9/6/2015 NE 1105 Lab 19 1 19 FS 2015 NE 4428 35 30 1050 12/2/2015 NE 1105 Power change 30 8 240 SS 2016 NE 2406 31 44 132 2/10/2016 NE 1105 Tour 14 1 14 2/13/2016 NE 1105 Tout 15 1 15 3/23/2014 NE 4312 24 2 48 3/24/2016 NE4312 25 2 50 SS 2016 NE 4438 21 10 210 Total 698 252.5 4,180

13 Table 4-2 Reactor Sharing Program 2015-2016 (Reporting Period)

DATE EVENT VISITORS TIME 4/2015 Visitor's 5 2 4116/2015 Fort Leonard Wood 3 2 5/2015 Visitors 16 3.5 6/2015 Visitors 22 4 6/9/2015 Jacl<ling 22 3.5 6111/2015 Jackling 23 3.5 6/15/2015 Nuclear Engineering Camp 46 6 6/16/2015 Career Opportunity 7 1 6/17/2015 Venturing Crew 11 1 6/22/2015 Jackling 24 3 6/25/2015 Jackling 27 3 7/2015 Visitors 20 14 7/15/2015 Fort Leonard Wood 5 3 7/16/2015 Kanas City Group 3 '

2 8/2015 Visitors 2 1 8/7/2015 Equity, Diversity & Inclusion Group 7 1 8/25/2015 Rep. Jason Chapman 1 1 8/28/2015 Group From Illinois 6 5 9/2015 Visitors 13 4.5 9/18/2015 Col Parker Fema tour 10 1 9/28/2015 NRC Test 1 30 10/20/2016 NRC 1 8 10/21/2016 DNN Radiological Security Partnership 3 3 10/28/2016 USMC 19 2 10/29/2016 Canberra 2 1 11/2015 Visitors 8 2 11119/2015 East Central 21 2 11/20/2015 Central Security 2 3 12/1/2015 Columbia Audit at Reactor 2 8 12/3/2015 Rolla High School 32 2 1112/2016 Fire Department 2 1 1/28/2016 Gasconade County Scholarship 20 1 2/112016 Boy Scouts 28 3 3/23/2016 Stem All Girl groups 3 sets 63 3 TOTAL 479 126.5

14 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. Releases of all by-product material to authorized, licensed recipients are surveyed and recorded. 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 exposure surveys of the facility consist of direct gamma and neutron measurements. 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 significant contamination outside of contained work areas was found.

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

5.3 Routine Monitoring Seventy-five reactor facility personnel and students involved with the operations in the reactor facility are currently assigned Mirian Technologies, Thermo-Luminescent dosimeters (TLDs). Three of the Reactor Staff have beta, gamma, neutron dosimeters which are read twice monthly. There are four area beta, gamma, neutron dosimeters and two TLD ring dosimeter, which are also read twice monthly.

There are three environmental TLDs outside the reactor building which are read quarterly. There are also five other beta, gamma, neutron dosimeters used by the health physics personnel and four other area beta, gamma, neutron dosimeters that are read monthly. The remaining dosimeters detect beta and gamma radiation only and are read monthly. In addition, six digital, direct-reading dosimeters and six cpirper dosimeters are used for visitors and high radiation work. There have been no significant personnel

15 exposures during this reporting period. Visitors are monitored with direct reading dosimeters. No visitors received any reportable or significant exposure.

Airborne activity in the reactor bay is monitored by a fixed filter; particulate continuous air monitors (CAM). Low levels of Argon-41 are routinely produced during operations.

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. From April 2015 through March 2016 sample concentrations averaged 8.44x10-6 µCi/ml.

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 this period, an estimated 36,519.22 µCi of Ar-41 was released into the air.

5.4 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. Water is analyzed for radioactive contamination and approval is required before the water is released. During this period there were no waste disposed from the reactor facility.

5.5 Instrument Calibrations During this period, portable instruments and area monitors were calibrated annually.

16 6.0 PLANS The reactor staff will be two major projects during the next reporting period distant education program and continuation of the reactor operator training program.

6.1 Distant Education A distant education system has been developed to conduct laboratory sessions with students of the Missouri S&T Campus and other universities. Due to the size of the Missouri S&T Nuclear Engineering classes, the distant education system allows students to participate in lab sessions as one group in larger a classroom than what is available for room in the MSTR building.

Equipment has been installed to replace the existing rod drive motors and rod height indicators to output rod height information over the internet. Audio/video equipment is used for students to watch reactor staff performing the labs, to ask questions to the staff and obtain data from the control room instrumentation.

The reactor staff has conducted distant education with the Missouri S&T Nuclear Engineering Department, Missouri S&T Chemistry Department and University of Illinois Nuclear Engineering students at Urbana, Illinois. These departments are providing feedback from students participating in the labs to improve our presentation techniques and provide suggestions regarding audio/video equipment improvements.

6.2 Reactor Operator Training The MSTR had three students obtain their Reactor Operatot lienses. The reactor staff is limiting operator training to around ten students with a very strong desire to obtain the license and assist reactor staff with reactor operations. The new training program has proven to be effective in keeping the students that want the license and work with reactor staff. At the end of the reporting period eight students were training for an operator's license to take in the fall of2016 and three for the spring of2017.

17 APPENDIX A.

STANDARD OPERATING PROCEDURES CHANGED DURING THE 2015-2016 REPORTING YEAR

. ***MISSOURI S&T REACTOR STANDARD OPERATING PROC:EDURES ***

SOP: INDEX TITLE: INDEX Revised: September 14, 2015 Page 1 of 3 SOP 100-1.99 Routine Reactor Operation SOP 100 Preamble SOP 101 General Operational. Procedures SOP 102 Pre-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 Exc.ess 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 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 Auxiliary Pool Water Cooler System Operations I Rev SOP 306 Estimation of Activity and Reactivity Worth of a Sample SOP 308 Restoration of AC Power Following a Power Outage Response to a Coolant System Leak I Rev SOP 309 SOP 3f0 Facility Modifications SOP 311 Receipt of Licensed Materials SOP 312 Critical Experiment Procedures SOP 400-499 Reserved for Future Use Revised By: Maureen Henry Approved By: William Bonzer w~~

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

SOP: INDEX TITLE: INDEX Revised: September 14, 2015 Page 2 of3 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 Spedal 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 J Rev 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 41 Ar Concentration in the Reactor Building Air SOP 655 Radiation Area Monitor (RAM) Calibrations Revised By: Maureen Henry. Approved By: William Bonzer (A)~~

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

SOP: INDEX TITLE: INDEX Revised: September 14, 2015 Page 3of3 SOP 700 - 799 Experiments SOP 702 Irradiation Request Forms SOP 710 Insertion and Removal of Experiments SOP 711 Beam Hole Facility .

SOP 712 Thermal Column Facility SOP 800 - 899 Reactor Instrumentation SOP 800 Annual Checklist SOP 801 Log and Linear Drawer Calibration SOP 802 Linear Channel SOP 803 Log Count Rate (LCR) Channel SOP 804 Safety Amplifier 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 UMR Power Calibration SOP 818 Function Test of Building Security System I Rev Revised By: Maureen Henry Approved By: William Bonzer

• • • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES*** Rev SOP: 207 TITLE: FUEL HANDLING Revised: August 7, 2015 Page 1 of 7 A. PURPOSE To provide for the safe and efficient movement of fuel elements and control rod fuel elements to and from the core and the Fuel Storage Rack.

B. PRECAUTIONS, PREREQUISITES, AND LIMITATIONS

1. All rearrangements of the core, fuel movement, and associated Health Physics monitoring, or other actions involving fuel shall be under the direct supervision of a Senior Reactor Operator.

2. All fuel movements shall be logged in the permanent log book.

3. Prior to any fuel movement, a completed Transfer Order Form must be filled out and approved by either the Reactor Manager or Reactor Director.

4. When moving fuel elements, the fuel handling tool must be kept in a vertical attitude.

5. A licensed operator shall visually confirm that there are no unoccupied internal lattice positions in the core before a new core is taken critical.

6. When loading to a new core configuration, measure the core excess reactivity, shutdown margin, and rod worths prior to exceeding a power of 1 kW. Log this information on a Core and Rack Storage Form ..

7. When loading to a new core configuration that involves a reactivity change greater than 0.2% delta-k/k or changes in control rod locations, excess reactivity and shutdown margin :rn,ust be determined for both the "W" and "T" modes.

Revised By: William Bonzer Approved By: William Bonzer

• • • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES*** Rev SOP: 207 TITLE: FUEL HANDLING Revised: August 7, 2015 Page 2 of7 C. PROCEDURE I. Unloading <!f Fuel Elements (unrodded) from the Core to the Fuel Storage Rack.

1. Complete a Start-Up Checklist (SOP 102).

2. Withdraw shim/safety Rods 1, 2 and 3 to shim range.

3. Unlock the fuel handling tools.

4. In accordance with the Transfer Order Form, the person with the fuel handling tool will request permission to move the fuel element. Example:

"Request permission to move fuel element Fl from grid position D7 to rack storage RlO".

• . 5. With the Control Room Operator's approval, latch the fuel element with the handling tool. Announce, "Tool latched".

6. The Control Room Operator will then grant permission to remove the fuel element from the core .

._ /

7. Withdraw the assembly from the core. When the fuel handling tool and attached element have cleared the core grid plate, announce, "Element clear".

8. Move the element to the fuel storage end of the pool.

9. Rotate the fuel element 180° so that the bow of the fuel element remains toward the center of the pool.

10. Insert the fuel element into the designated location and check to ensure that it is properly seated in the fuel rack. Announce "Element seated".

11. Unlatch the fuel handling tool.

Revised By: William Bonzer Approved By: William Bonzer

• • • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 207 TITLE: FUEL HANDLING Revised: August 7, 2015 Page 3 of7

12. The Control Room Operator shall log the fuel movement in the permanent log book.

13. Transfer the element identification tag from the core status board to the fuel storage status board.

14. Repeat Steps 4 through 13 to remove additional elements from the core.

15. Lock the fuel handling tool in its holder and return the key to the safe.

16. Complete the necessary information on the Transfer Order form.

17. Perform a Reactor Secured Checklist (SOP 105) as appropriate.

II. Unloading of Control Rod Fuel Elements from the Core to the Fuel Storage Rack.

1. Unload fuel elements from the core (per Section I of this procedure) such that the core loading is below one-half of a critical mass. A single control rod fuel assembly may be removed from the core with this loading.

2. Unload all of the fuel elements from the core if two or more control rod fuel elements are to be removed.

3. Disconnect and uncouple the control rod drive, shroud and magnet extension.

4. Remove the shroud and magnet extension from the control rod element.

5. Remove the control rod from the element, if desired.

6. To unload, complete Steps 3 through 17 of Section I of this procedure.

Note: The control rod fuel element may be transferred to an appropriate "basket to facilitate easy movement within the pool.

Revised By: William Bonzer Approved By: William Bonzer WJJ~~

• • • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES*** Rev SOP: 207 TITLE: FUEL HANDLING Revised: August 7, 2015

• Page 4of7 III. Loading of Fuel Elements from the Fuel Storage Rack to the Core

1. The Control Room Operator must comply with SOP 312 (Approach to Criti~al) during the loading of the core. The Control Room Operator will be responsible for collecting the necessary data, constructing the 1/M plot and instructing fuel handlers as to assemblies that may be loaded.

2. All control rod fuel elements and control rods must be installed in the core per Section IV prior to the loading of any fuel element

3. Control rod drop times must be completed per SOP 813 on all rods of control assemblies that have been moved or that have had their magnet assemblies removed and reinstalled prior to the loading of any fuel element.

4. Complete Steps 1, 2, and 3 from Section I of this procedure.

5. In accordance with the Transfer Order Form, the person with the fuel handling tool will request permission to move the fuel element. (Example "Request permission to move fuel element Fl from storage rack RIO to grid position D7. ")

6. With Control Room Operator approval, latch and remove the fuel element from the storage rack, transport the demerit to the edge of the core grid plate and announce, "Approaching core". *

7. Wait for the Control Room Operator's approval prior to movement into the core area. Following the Control Room Operator's approval, place the fuel element in the core. The fuel element must be rotated 180° so that the bow of fuel points to center of pool.

8. When the element is seated, announce, "Element seated". Do not unlatch the fuel. Be prepared to immediately remove the fuel element from the core if instructed by the Control Room Operator.

Revised By: William Bonzer Approved By: William Bonzer

• • • MISSOURI S&TREACTOR STANDARD OPERATING PROCEDURES*** Rev SOP: 207 TITLE: FUEL HANDLING Revised: August 7, 2015 Page 5 of7

9. With Control Room Operator approval, unlatch the element and move the tool clear of the core area. Announce, "Tool clear".

10. The Control Room Operator shall log the fuel movement in the permanent log.

11. Transfer the identification tag for the element from the fuel storage status board to the core status board.

12. To load additional fuel elements, repeat Steps 5 through 12 as instructed by the Control Room Operator.

13. When loading is complete, complete Steps 15, 16, and 17 of Section I of this procedure.

IV. Loading Control Rod Fuel Elements from the Fuel Storage Rack to the Core.

1. Complete a Pre-Startup Checklist to the extent possible. The 2 cps interlock may need to be bypassed by an SRO and other steps such as dropping rods may be omitted when no control rods are loaded in the core.

2. Load all of the control rod fuel elements in accordance with Steps 5 through 12 in Section III.

3. Insert control rods and reassemble the drive mechanisms.

4. Check the withdraw and insert control, observe the rod position indication, and ensure proper operation of the control rod drive system.

5. Perform Rod Drop Times (SOP 813) on all rod assemblies that have been moved or whose magnet assemblies have been removed and reinstalled.

6. If fuel loading is to continue go to section III of this procedure, otherwise complete Steps 15, 16, and 17 of Section I of this procedure.

Revised By: William Bonzer Approved By: William Bonzer w:JL;~n ~

• • • MISSOURI S&TREACTOR STANDARD OPERATING PROCEDURES*** Rev SOP: 207 TITLE: FUEL HANDLING Revised: August 7, 2015 Page 6 of7 TRANSFER ORDER FORM Description of Fuel Movement Lo ading Number ---------------

I ELEMENT ID I FROlVI 1

• TO I COMMENTS I Authorized by_______ Accomplished by 1 _ _ _ __

(Reactor Manager or Director) 2 _ _ _ __

Date - - - - - - - Date completed Revised By: William Bonzer Approved By: William Bonzer

• • • MISSOURI S&TREACTOR STANDARD OPERATING PROCEDURES*** I Rev SOP: 207 TITLE: FUEL HANDLING Revised: August 7, 2015 Page 7 of7 MSTR CORE AND RACK STORAGE FORM I Rev DATE ------ LOADING NUMBER - - -

Rl R2 R3 R4 R5 R6 R7 R8 R9 RIO Rl 1 R12 R13 R14 R15 I*

RACK STORAGE FACILITY R16 R17 R18 R19 R20 R21 I R22 I R23 I R24 I R25 R26 R27 R28 R29 R30 A

Core Excess Reactivity _ _ _ _ _ __

R Shut-Down Margin _ _ _ _ _ _ __

Rod Worths Rod 1: - - - - Rod 3: -~---

Rod 2: Reg Rod: _ __

n F.

F 2 3 4 56 7 -8 9 Rev MSTR CORE STATUS Elem. U-235 Mass Elem. U-235 Mass Elem. U-235 Mass Total U-235 Mass (Grams) _ _ _ __

Review and Approval:

(Reactor Director or Manager)

Revised By: William Bonzer Approved By: William Bonzer n

• • • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** j Re:v SOP: 306 TITLE: ESTIMATION OF ACTIVITY AND REACTIVITY WORTH OF A SAMPLE Revised: May 21, 2015 Page 1 of3 A. PURPOSE The purpose of this procedure is to provide guidance for calculating the radioactivity and reactivity.

B. PRECAUTIONS, PREREQUISITES, OR LIMITATIONS

1. SOP 702, "Request for Irradiation" specifies when this procedure is to be used.

2. Values obtained using these procedure are to be considered approximate.

C. PROCEDURE

1. Calculation of Activity (eq. 1) where m = Mass of the element to be irradiated (grams) a = Isotopic abundance of the element .

NA =Avogadro's Number (6.02xl023 atoms/mole)

AW = Isotopic weight (grams/mole) cra = Isotopic activation cross-section (cm2) .

<D =Neutron flux (n/cm2 -sec)

T 112 =Half life of the produced radioisotope (min) t = Irradiation time (min)

Sample Calculation:

A 0.0985 gm sample of A1 27 is to be irradiated in a flux of 5x10 10 n/cm2-sec.

What is the activity after 5 min. of irradiation? (cra = 0.241b = 0.241x10-24 cm2, T112 = 2.24 min, 3.7x10 7 dis/sec= 1 mCi)

Revised by: William Bonzer Approved By: William Bonzer

• • • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES*** Rev SOP: 306 TITLE: ESTIMATION OF ACTIVITY AND REACTIVITY WORTH OF A SAMPLE Revised: May 21, 2015 Page _2 of 3 23 Act= 1xo.09ssx6.02x10 (0. 214 x 10 _24)(S x 10 10) 27

-(0.693)(5) 1- e 2.24 = 2.08 x 10 7 dis/sec= 0.56 mCi

2. Calculation of Reactivity Worth of a Sample The reactivity worth of a sample Ps when placed in the neutron flux <l>s can be calculated by comparing it to the reactivity worth Pa of a known absorber placed in the neutron flux a using the following formula (eq.2) where a = Microscopic absorption cross-section (barns) m =Mass (grams)

AW = Isotopic weight (grams/mole)

=Neutron thermal flux (n/cm2 -sec)

Subscripts "s" and "a" refer to the s.ample and known absorber respectively.

Using data from a reactivity experiment with a piece of indium absorber placed in the various positions of the row D at the reactor power of 20W the eq. (2) can be simplified to Ps = 1.4 x 10- 21 x crsms x Q)~ x abundance of Isotope (eq. 3)

AW5 (Note: The value of the neutron flux <l>s must correspond to the reactor power of 20W.)

Sample Calculation:

A 2.0 gm sample of Al-27 (as = 0.241 barns) is to be irradiated in a flux of 2.6xl0 10 n/cm2 sec. at 2 kW. What is the expected reactivity worth?

Revised by: William Bonzer Approved By: William Bonzer

• • • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES*** Rey SOP: 306 TITLE: ESTIMATION OF ACTIVITY AND REACTIVITY WORTH OF A SAMPLE Revised: May 21, 2015 Page 3 of3 2

21 0.241 x 2.0 ( 10 20 )

p = 1.4 x 10- x 27 x 2.6 x 10 x 2000

= 1.7 x 10-6 ~k/k

3. Calculation of Reactivity Worth of a Void When a void is placed in or near the reactor core a change in reactivity can be expected. This is due to the void coefficient of reactivity. A void itself will add negative reactivity to the reactor, but the greatest concern is the removal or collapse of a void which will add positive reactivity.

The void coefficient measured at the core periphery is -1 o-6 ~k/k/cm3 .

Sample Calculation:

A sample will be placed next to the core in an empty 250 ml bottle. What is change in reactivity due to the void?

p = 250 cm3 (1 o-6 ~k/k/cm3 ) = 2.5 x 104 ~k/k.

Revised by: William Bonzer Approved By: William Bonzer

• • • MISSOURI S&TREACTOR STANDARD OPERATING PROCEDURES*** Rev SOP: 308 . TITLE: RESTORATION OF AC POWER FOLLOWING A POWER OUTAGE Revised: May 28, 2015 Page 1 of2 A. PURPOSE The purpose of this SOP is to ensure that power is restored to equipment in a safe and efficient manner following a trip of umegulated and/or regulated power and to prevent damage to the equipment.

B. PRECAUTIONS, PREREQIDSITES, OR LIMITATIONS

1. Personnel restoring unregulated and/or regulated power should be familiar with* the operation of the equipment affected.

2. A weekly check should be performed before operating the reactor at a power higherthan 20 kW following a loss and restoration of power.

3. Any malfunctions or abnormality of equipment should be immediately reported to the SRO Rev on Duty.

C. PROCEDURE

S

1. Reset the unregulated and regulated power supplies, which are located in the equipment room behind the console panel.

2. All annunciator lights and buzzer may be on. I Rev

3. Push the am1unciator acknowledge button to silence the buzzer.

4.* Reset the Linear power supply located in the control room. (Note: The power supply must Rev warm up for several minutes before it will reset.

5. Press the annunciator panel reset button. The annunciator should now indicate a normal Rev situation. (Note: A normal situation is indicated by all lights being extinguished, except Manual Scram, Recorder Off and Manual Operation.)

Written By: William Bonzer Approved By: William Bonzer w JL:,,.. G1r>v;,;

• • • MISSOURl S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 308 TITLE: RESTORATION OF AC POWER FOLLOWING A POWER OUTAGE Revised: May 28, 2015 Page 2 of2

6. Notify the SRO on Duty of the power outage or tag the console to assure a weekly check is completed prior to reactor runs exceeding 20 kW. 1

7. Start the demineralizer pump by pushing its "Start" button. (Note: The start button is Rev located on the intermediate level, on the wall behind the pump.

Written By: William Bonzer Approved By: William Bonzer

~

-;1fJ I,,_.uI '-Li*L-Cl'"i I/ D~ {. .

• • • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 312 TITLE: CRITICAL EXPERILVIENT PROCEDURES Revised: August 7, 2015 Page 1 of 5 A. REACTIVITY REQUIREMENTS Any individual experiment involving a worth of more than 0.4% reactivity will be installed in the partially unloaded core and the reactor brought to power by a critical experiment. No single independent experiment worth more than 0.7% will be installed in the reactor.

B. PROCEDURE

\Vhen a new configuration of fuel elements for a new core position is to be used in.the reactor, source multiplication in the core will be measured after each element is added.

The data obt~ned will be plotted (as it is obtained) to allow prediction of the point at which the reactor will go critical. In the case where a large sample or experiment is to be positioned in or near the core, the reactor will be unloaded, the sample or experiment positioned, and the same procedure used to approach criticality. The steps in the procedure are as follows:

1. A calculation of the critical mass of the projected loading will be made.

2. The control rod fuel elements and rod drives will be installed in the desired positions.

3. The reactor checkout procedure will be carried out, as for a reactor start-up. Note that during the initial stages of the experiment, it will be necessary to bypass the 2 cps interlock. This will be under direct superv~sion of the SRO in charge of the critical experiment.

4. The rods and reg rod will be raised to the Shim Range.

5. A neutron source will be installed and approximately 50% of the critical mass calculated in step (1) will be loaded, with constant surveillance of the count rate.

Whenever fuel elements are loaded or unloaded, fuel element numbers and positions will be carefully recorded both in the log book and on the loading chart.

At this point, the count rate in the fission chamber channel will be determined using the scaler, to give a measure of the source multiplication.

Revised By: ""William Bonzer Approved By: William Bonzer

• • • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES*** Rev SOP: 312 TITLE: CRITICAL EXPERilYIENT PROCEDURES Revised: August 7, 2015 Page 2 of 5..

6. The rods then will be fully withdrawn and another count made. Then the rods

• will be dri:r~n back to Shim Range.

7. One additional fuel element will be loaded, and the measurements of steps (5) and (6) repeated. This data *will be plotted to give the "Subcritical Multiplication Curve" as soon as it is obtained, before any further loading is done. The curve obtained from plotting the data taken with the rods fully withdrawn gives an indication of when it will be possible to make the reactor critical by withdrawing rods. The data taken with the rods at Shim Range gives a curve which indicates the possibility of going critical during the actual loading operation.

8. Step (7) will be repeated until the reactor goes critical at which point rod positi_ons will be recorded. If the reactor goes critical without sufficient excess reactivity for operational use, the loading will be continued in half-element increments using the Shim Range Subcritical Multiplication Curve to ensure the criticality is not reached during loading of an element. This completes the critical experiment and at this point, a new core configuration will be designated. At the completion of the experiment, fuel handling tools will be locked and the plots of the data obtained and the loading chart will be attached to a page in the log book of core loadings. The person loading fuel will maintain a position which will allow instant reversal of motion of the fuel element if the operator at the console orders it. The loader will maintain positive control. over the fuel element until the operator specifically gives permission to release it."

C. PLOTTINGDATA

• I. Select loading chart as illustrated in Figure 1 and record data on loading chart and in log book as critical experiment progresses.

2. Prepare graph as illustrated in Figure 2.

3. In step B-5 of this procedure, the initial 50% loading and rod position count will be at the base count rate C0

• Revised By: William Bonzer Approved By: *wmiam Bonzer w~~ iJ.JA:~-1 ~Y>

• • • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** ReY SOP: 312 TITLE: CRITICAL EXPERJMENT PROCEDURES Revised: August 7, 2015 Page 3of5 ..

4. Beyond this point the various counts at Shim *Range and fully withdrawn rod positions when loading elements will be designated as Ct.

5. At each element addition (when Shim Range and fully withdrawn count is made) the subcritical multiplication M will be:

where C0 remains constant and Ct will vary for each counting condition.

6. The value of l/M shall then be plotted on the curve vs. the nun1ber of elements added for Shim Range (6) and fully withdrawn rod positioned (0).

r.

D. LOADING NUIVIBERING SYSTEM The system for designating a loading will be as follows:

1. Each new core configuration will be designated by a number which will be the successive number following the last loading.

2. A loading diagram will be made out and stapled in the log book of core loadings for each loading.

Revised By: William Bonzer Approved By: William Bonzer vu* k;/\ ~1--'1

• • • IvIISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 312 TITLE: CRITICAL EXPERI1\1ENT PROCEDURES Revised: August 7, 2015 Page 4 of 5 ..

Transfer Order Form Sheet - - - - of - - - - No. - - - - - -

Loading No. - - - - - -

Move Elem. No. From To Remarks r

Authorized by _ _ _ _ _ _ _ _ _ __ Accomplished by 1 _ _ _ _ __

Date 2 ------

Date, time completed _ _ _ _ __

Figure 1 Revised By: William Bonzer Approved By: William Bonzer uJ~ ~~Vl vuJlv~rr G-r~?

• • • MISSOURJ S&T REACTOR STANDARD OPERATING PROCEDURES*** Rev SOP: 312 TITLE: CRITICAL EXPERJMENT PROCEDURES Revised: August 7, 2015 Page 5 of 5.

1 0.9 0.8 0.7 1 0.6 M

0.5 0.4 0.3 0.2 0.1 0

1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 Number of Elements Figure 2 Revised By: .William Bonzer Approved By: William Bonzer w~~ wJt;~~~

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

SOP: 501 TITLES: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Revised: May 21, 2015 Page 7 of7 I Rev MISSOURI S&T EMERGENCY PHONE LIST Reactor Staff CELL HOME WORK William Benzer, Manager, SRO 578-9463 368-0318 341-4384 Craig Reisner, Senior Reactor Operator 573-247-7557 573-729-7277 341-4291 Anthony Alchin, Electronics Technician III 816-274-1771 341-6617 Rev Maureen Henry, Office Support Ast. III 201-7275 341-6016 University Administrative Staff Michelle Bresnahan, EHS Director, Radiation Safety Officer 314-239-7751 341-4305 Raymon Bogart Interim,Director Missouri S&T Police 201-58&5 426-5 815 341-4300 Dr.Cheryl B. Schrader, Chancellor 201-7392 341-7141 341-4116 Walter Branson, VC Chancellor Finance & Adm. 260-402-0317 341-4122 James Packard, Director Physical Facilities 578-8167 341-4252 Dr. Goodman DO, Director Student Health Services 341-4284 Dr.Hyoung Lee,Chair of Nuclear Eng, Reactor Director 573-202-4665 341-4585 Dr.Ralph Flori Jr, Interim Chair of Mining and Nuclear 578 -3130 341-7583 Rev Fadha Ahmed, Health Physicist EHS-Missouri S&T 314-960-9211 636-223-2054 341-7014 Local Missouri S&T Police 341-4300 Rolla City Police 911 Rolla Fire Department 911 Phelps County Hospital 911 Rolla Emergency Management Agency 911 State Agencies Missouri Highway Patrol (573) 368-2345 Mis.souri State Emergency Mgt. (24 hr.) (573) 751-2748 Missouri Dept. of Natural Resources (24 hr.) (573) 634-2436 Missouri Bureau of Environmental Epidemiology (573) 751-6160 (573) 751-4674 (24hrs)

Federal Agencies

• NRC, Operations Center (301) 951-0550 NRC Duty Officer (24 hr.) (301) 816-5100 American Nuclear Insurers (860) 682-1301 Radiation Emergency Assistance Center (865) 576-3131 (865) 576-1005 (24hrs)

Revised By: Maureen Henry Approved: William Bonzer

~

r , i '{)/) " (? *'

...... v ~l;:v*VI"> 1 ..J.-v:~-2f"?

~ '(-L-Lul,"'\._

\(' fl.

• • • MISSOURI S&TREACTOR STANDARD OPERATING PROCEDURES*** I Rev .

SOP: 653 TITLE: SEALED SOURCE LEAK TEST Revised: March 31, 2016 Page 1 of 2 A. PURPOSE To ensure the integrity and encapsulation of sealed sources and to guard against contamination of personnel.

B. PRECAUTIONS, PREREQUISITES, OR LIMITATIONS

1. This procedure is to be performed by Health Physics staff personnel.

2. The following sources located at the reactor facility are to be leak tested semi-annually: PuBe SIN M-1092 (Reactor Startup Source), PuBe SIN M-169 (RAM Calibration Source), Cs-137 SIN 74-156 (RAM Calibration Source). The Cs 137 1* Rev source is located in the JL Shepherd Shield SN5409 .

• 3. Leak test requirements are listed in item 14 (A through F) ofNRC Materials License number 24-00513-40.

C. PROCEDURE

1. The leak test should be performed with filter-paper discs or with cotton-tipped applicators depending upon the source activity, configuration, and containment.

2. The source, source holder, and immediately surrounding area should be rubbed.firmly with the swipes held with tongs or forceps or with cotton-tipped applicators in.order to remove any surface contamination that may be present. If access to the sealed source is prevented by the construction of the device, the swipes should be taken as near the source as possible:

3. Each swipe or applicator should be placed in a separate envelope appropriately labeled for identification.

4. Frisk the swipes with an open window G-M probe. If any detectable activity is observed above background, contact the Reactor Health Physicist for appropriate approvals before removing the swipe from the facility. If no detectable activity is identified, the swipes may be removed from the facility for counting at the Health Physics office.

Revised By: William Bonzer Approved By: William Bonzer i

.~,.1l-J*

\

i_./V~"".

!; , u ...,...-v1 r ,'.? **

'1.::i.,(J;V \ !!--)

d V"

J' ~

/v , J'. U11

11 '

-~~-

1t_.-,i.-'l

)

n

..J u

?

cf'/

ld., .,-,.y:-.., .lJ

• • • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES*** Rev SOP: 653 . TITLE: SEALED SOURCE LEAK TEST

. Revised: March 31, 2016 Page 2 of2

5. Evaluation 9f swipes taken from sealed sources containing a beta-gamma emitter should be made with shielded, end-window, Geiger-Mueller counter or equivalent.

Evaluation of swipes taken from sealed sources containing an alpha emitter should be made with a gas-flow proportional counter or equivalent.

6. If the results of the test indicate a removable contamination in excess of 0.005 microcuries, the following steps shall be taken:

a. The source is to b.e taken from service immediately and held* in secured storage until it can be decontaminated.

b. Notify the Reactor Manager.

c. File a report with the NRC that contains the information required by section 14.E of the Materials License.

Revised By: William Bonzer Approved By: William Bonzer

. I * .1 :J '

(/v J'.,.~La,-.-'Y">

i/

fl ::S...c***v<. *i.-J 3'

vv'~Ql'-tr-~ f2~x>*~'

• • MISSOURI S&TREACTOR STANDARD OPERATING PROCEDURES*** Rev SOP: 702 TITLE: IRRADIATION REQUEST FORMS Revised: March 31, 2016 Page 1 of 8 A. PURPOSE To provide for the thorough Reactor Staff review of all experiments to be irradiated by neutrons from the JYISTR. The review evaluates potential 1) reactivity effects, 2) dose I Rev hazards to the experimenter, and 3) hazards to the reactor.

B. PRECAUTIONS, PREREQUISITES OR LIMITATIONS

1. All sample irradiations must be performed under an approved Irradiation Request Form (IRF) with two approval signatures.

2. All materials to be irradiated are to either be corrosion resistant or encapsulated in corrosion resistant containers.

3. Approved IRFs remain valid for future irradiations.

4. IRFs will be numbered sequentially following the last two digits of the current year (e.g. 95-1, 95-2, etc.).

5. Radiation Safety Committee approval is required for

a. experiments worth more than 0.4% 6.k/k,

b. explosive materials,

c. fueled experiments, or

d. untried experiments.

6. The total reactivity worth of all experiments is limited to 1.2% 6.k/k.

7. Experiments having moving parts shall not have an insertion rate greater than 0.05%

6.k/k per second.

8. Cooling is to be provided as needed to prevent the surface temperature of an experiment being irradiated from exceeding the boiling point of the pool.

Revised By: William Bonzer Approved By: William Bonzer

/d *:_,Qe<-~*)*V'

.. i] f,} .. 1")

l**v ...d<-~*i-vi ~::J.._.~......,v\ i

_i RtJ-,-v)<Q) ,:r7

- 0

• • MISSOURI S&TREACTOR STANDARD OPERATING PROCEDURES*** Re.v SOP: 702 TITLE: IRRADIATION REQUEST FORMS Revised: March 31, 2016 Page 2 of 8 C. PROCEDURE - IRRADIATION REQUEST FORM The IRF should be completed according to the following steps:

1. IRRADIATION REQUEST - This section of the IRF should be completed by the experimenter.

a. Sample Description - Describe the sample material to be irradiated (e.g.

dried tobacco leaves, powdered milk, gold foil, etc.)

b. Physical Form - Specify the physical form of the sample material (e.g, powder, ash, liquid, etc).

c. Encapsulation - Check the box marked "Poly-vial" or check "other" and describe.

d. Irradiation Location - Specify the irradiation facility to be used. More than one facility may be authorized on a single IRF. If "Other" is specified, describe the irradiation location (for example: "wire stringer in Grid Position C-3").

e. Irradiation Limits - Specify the irradfatiQn limits as follows:

1) Power - Specify the maximum reactor power for irradiation.

Samples may NOT be irradiated at powers higher than specified.

2) Time - Specify the irradiation time for the sample( s) at the maximum power. Samples may be irradiated at lower powers for times longer than the specified irradiation time as long as the total fluence (i.e.

kW-hrs) does not exceed the product of the specified maximum power and irradiation time.

3) Mass - Specify the maximum sample mass (grams) to be irradiated in any single irradiation.

Handwritten revisions to the limits are allowed based on the measure dose rate from the initial irradiation(s).

Revised By: William Bonzer

' 'j.1

• ~/*

,.  !)

A.'

i f t /J

(.tl) ,_x:.-~GL/'YY°l 1[-...L.-* \}'"";:,*v :z. .L *;

0

• • MISSOURI S&TREACTOR STANDARD OPERATING PROCEDURES*** Rev SOP: 702 TITLE: IRRADIATION REQUEST FORMS Revised: March 31, 2016 Page 3 of 8 Assume dose rate is a linear function of power, irradiation time, and sample mass. Revised irradiation limits require the review and approval of either the SRO on Duty, Reactor Manager, or Reactor Director as signified by their initials with dates.

f. Expected Dose Rate - Specify the expected 1 foot dose rate when the sample comes out of the reactor based on one of the categories below:

Experience - The expected dose rate may be based on measurements made during previous similar irradiations. In such instances, record the IRF number of the previous similar irradiation.

Calculations - The expected dose rate may be calculated using the DR=6CE rule (or other appropriate method) where DR is the 1 foot dose rate in mrem/hr, C is the expected activity in mCi, and Eis the gamma energy in Me V. The expected activity can be calculated using A= N <J¢(1- e -J.i;,,) where N is the number of target atoms, cr is the cross section, <p is the neutron flux, A. is the decay constant and tirr is the irradiation time.

Completely Unknown -A trial irradiation is required ifthe expected dose rate is completely unknown. The irradiation limits for a trial irradiation are normally reactor power:::; 2 kW, irradiation time:::; 1 minute, and sample mass :::; . 1 gram. The reviewers may approve different trial irradiation limits at their discretion. Dose rates for higher powers, masses and times* can then be linearly extrapolated based on the measured dose rate resulting from the trial irradiation.

g. Reactivity Worth - Estimate the reactivity worth of the sample based on one of the categories below:

Default-A default reactivity worth of <0.05% .6..k/k may be used for the rabbit facilities if the sample mass is less than 7 grams. A default reactivity worth for core periphery stringers of <0.1 % .6..k/k may be used for holders with a volume of 3 5 cm3 or less and a sample mass of 7 grams or less. (Note: The default mass and location values are based on a report by Wagner, 1992.) Beamport and thermal column irradiations have a default reactivity of 0.0%.

Approved By: William Bonzer i,,.,-li.* ......(::...~c....e,:..,...~**-:

// . ~ '"'-* ~ .

.~ . . '"' .. v~y~t

• • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES*** Re.v SOP: 702 TITLE: IRRADIATION REQUEST FORMS Revised: March 31, 2016 Page 4of8 Experience - The estimated reactivity worth based on previous "experience" may be specified along with the applicable IRF number.

If no previous experience exists, estimate the reactivity worth using I Rev SOP 306.

Completely Unknown - If reactivity worth is completely unknown and not easily calculated, it must be experimentally determined.

h. Comments - Provide additional comments, if any.

i. Request Completed By - The person completing items a through h ab_ove should sign their name in the blank provided.

2. REVIEW AND APPROVAL-This portion of the IRF is to be completed by one of the reviewers and approved by both of the reviewers.

a. Analysis of Potential Hazards - Reviewers shall analyze potential hazards associated with the experiment with regard to following:

1. Reactivity - Review the expected reactivity worth information.

Assure that the Technical Specification Section 3 .7 requirements are met. Check the box marked "None" or "Other" as appropriate. If "Other" is specified, explain.

2. Dose Rate - Review the expected dose rate information and assess potential dose rate hazards. Check the box marked "None" or "Other" as appropriate. If "Other" is specified, explain.

3. Reactor Equipment - Verify that no corrosion problems exist.

Verify that no explosive materials or fueled experiments are to be irradiated without Radiation Safety Committee approval. Verify that proper provisions for cooling have been made. Evaluate the experiment with respect to potential hazards to the reactor or reactor operations (for example, detector "shadowing"). Check the box marked "None" or "Other" as appropriate. If "Other" is specified, explain.

Revised By: William Bonzer Approved By: William Bonzer

. * ~ ,') *1 ~

/jJ 0:'.-~kt.rn

• • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rey SOP: 702 TITLE: IRRADIATION REQUEST FORMS Revised: March 31, 2016 Page 5 of 8

4. Other - Evaluate the experiment for any other types of conceivable hazards to personnel or equipment.

b.

c.

Additional Restrictions/Requirements - The reviewers are to specify any additional restrictions or requirements deemed appropriate.

Approvals - Reviewers shall signify approval of the experiment by signing and dating in the appropriate blank. Two signatures are required from either the Director, Manager, SROs, or the Health Physicist.

D. PROCEDURE - SAMPLE IRRADIATION LOG A Sample Irradiation Log will accompany each IRF to document sample irradiation information. An entry shall be made on the Sample Irradiation Log for each sample irradiated.

1.

• Date - Specify the date of the sample irradiation.

2. Sample ID - Specify the sample identification number or name.

3. Experimenter's Name - Provide the name of the experimenter responsible for the sample. *

4. Location - Specify the irradiation location.

5. Power - Specify the power level at which the irradiation is performed.

6. Time In - Specify the console time at which the irradiation began.

7. Time Out - Specify the console time at which the irradiation ended.

8. Total Time - Specify the total time of the irradiation.

Revised By: William Bonzer Approved By: William Bonzer i/V

.\[,ii)/

vt.£14.;-v">

-'")

~<::;;_A-:rv~) I .~**/);j t.,.. ...-~.....

LJL..li~~-Cl/::.--1,....,,

/2 ri

• tJ *~e:""'.---/'**)_.~:l..,..,)

• • MISSOURI S&TREACTOR STANDARD OPERATING PROCEDURES*** Re.v SOP: 702 TITLE: IRRADIATION REQUEST FORMS Revised: March 31, 2016 Page 6 of 8

9. Dose Rate @ 1 foot - Record the 1 foot dose rate from the sample at the time of initial sample handling.

10. Decay Time- Specify the approximate decay time between the end of the irradiation and the time of the dose rate measurement.

11.

• Initials - Either the console operator (licensed operator, student, or trainee) or. the experimenter will provide their initials signifying that sample irradiation iruormation is complete.

Revised By: William Bonzer Approved By: William Bonzer L,,U "'J)li,,;.,,y,

• • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES*** Rev SOP: 702 TITLE: IRRADIATION REQUEST FORMS Revised: March 31, 2016 Page 7 of 8 IRRADIATION REQUEST FORM IRF :# *_ _

1. IRRADIATION REQUEST

a. Sample D e s c r i p t i o n : - - - - - - - - - - - - - - - - - - - - - - - - - - - -

b. Physical Form: _ _ _ _ __ c. Encapsulation ()Poly-Vial ()Other _ _ _ _ _ _ _ __

d. Irradiation Location: () Bare Rabbit () Cad Rabbit ()Beam Port ()Thermal Column

()Other _ _ _ _ _ _ _ _ _ __

e. Irradiation Limits: 1) Power: _ _ _ __ 2) Time: _ _ _ __ 3) Mass: ---~-gm

f. Expected 1 Foot Dose Rate: _ _ _ _mrem/hr Based on: () experience (IRF# _*--~

() calculations (attached)

() completely unknown

g. Expected Reactivity Worth: _ _ _ _ % k/k Based on: ()default

( ) experience (IRF#_ _ __.

()SOP 306 calculations (attached)

() completely unknown

h. Comments: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

i. Request Completed By:--------------~-

2. REVIEW AND APPROVAL

a. Analysis of Potential Hazards:

1. Reactivity ()None ()Other _ _ _ _ _ _ _ _ __

2. Dose Rate ()None ()Other _ _ _ _ _ _ _ _ __

3. Reactor Equipment ()None ()Other _ _ _ _ _ _ _ _ __

4. Other ()None ()Other----------

b. Additional Restrictions/Requirements_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

c. Irradiation Request Reviewed and Approved (two signatures required):

Director _ _ _ _ _ _ _ _ _ Date _ _ _, Manager _ _ _ _ _ _ _ _ _ Date _ __

SRO Date , SRO Date _ __

Health Physicist _ _ _ _ _ _ _ _ _ Date _ _ __

Revised By: William Bonzer /"""",

Approved By: William Bonzer I I /)

t:) ,:S__ ~I -.t\_, .* 3. ).: :J '.',. '. . . . ,*_.(i~I.

~ .._ ~.*;,'--. ,:_ .*~.: . -; .,. ~- -~ )

.-,*,* _ *-,.--..*

• _.. ~;---..:-*0 1 .*

~,

SAMPLE IRRADIATION LOG

=< Page#_ __ ~ (/)

1-1 (I) 0 (I)

<! '"O l"--l*

(/)

Irradiation Information l:::l (I) --..l to Dose Rate p.. 0

.. N

'-< Sample Experimenter's Time Time Total @1 ft Decay Time ~ ~

~

~

f---<

0 (f.J C' ' ,__ Date ID Name Location Power In Out Time (mR/hR) (Approx.) Initials µ (f.J

<"'":. ~ l>-) 0

. -, Pl ,_. . c:::

~-~- sto

('<----

\~ *--~ 0 ~ >--1 ~

,_.... f---< (/.J 1,'* -. l:::l

~', N 0\ >--1 f<l:>

) (I) [-i >--1 1-1

..trJ [g (0J >-=! ;J>

} \

~~

t1 0 y-- """" (f.J

?:!

• ~*' >

~ >--1 s~

Z.o

~ ;J>

'°doES tEJ ""O (f.J trJ

~~

0 >--1

~

>rj 1-1

~~""O Gf'J.

0

~

(I) p_,. '"O to  :~

I (I)

CJ trJ

'-< 0 00

,. 0 c:::

,~.

\

=<

>--+-,

~

...... 00 (f.J

\.:-...,

\------

r~:-..~

8 **

-)(-

to

( __ }

0 i=l 3 N (I) 1-1

(~\)

'~i ~

':g

/\.j

• • • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 801 TITLE: LOG AND LINEAR DRAWER CALIBRATION Revised: March 3 1, 2016 Page 1of4 A. PURPOSE To provide a consistent method for checking the calibration of the Log and Linear drawer which includes Log N, Period, and Power Range.

B. PRECAUTIONS, PREREQUISITES AND LIMITATIONS

1. This procedure is to be performed annually. Rev

2. A second knowledgeable person shall check all cable connections that have been broken and reconnected.

3. Refer to Section 1, "Log and Linear Drawer Calibration" of the Annual Checklist (SOP I Rev 800) for forms to document this procedure.

C. PROCEDURES

a. Open the housings of both the Log and Linear drawer and the Log/Period recorders and clean as necessary. Pay particular-attention to assure air vents are cle(;ll'.

b. 80% High Voltage Rundown

~' 1. Obtain the magnet key from the SRO on duty and have a Licensed Operator raise shim rods 3 inches.

2. Adjust A4R4, on the high voltage card A4, t9 the lower voltage that will cause the Low CIC Voltage Rundown trip to occur.

'i 3. Record the voltage at A4TP1 where the trip had occurred. (200 times the voltage at A4TP1 equals the desired HV)

4. Verify receipt of the visual and audible alarms for Low CIC Voltage. Verify that a rod rundoWn is initiated.

5. Adjust A4R4 to 540V. (200 times the voltage at A4TPT equals the desired HV)

6. Reset the annunciator panel.

7. Remove the magnet key from the console and return it to the SRO on Duty.

Revised By: William Bonzer

. J 4

{J . 0 l/\j ftL-~vYI ~6~.Y 'I

• • • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 801 TITLE: LOGANDLINEARDRAWERCALIBRATION Revised: March 31, 2016 Page 2of4

c. 120% Full Power Rundown

1. Disconnect the 3 detector cables (signal, HV, and CV) at the drawer.

2. Connect- the Keithley 263 pico-amp source to 15 of the Log and* Linear J Rev drawer. Adjust current to 100% full power.

3. Reset annunciator panel.

4. Obtain the magnet key from the SRO on Duty and have a Licensed Operator raise shim rods 3 inches.

5. Slowly increase current to obtain a reading of 120%.

6. Observe from the Linear Power Range digital display when the 120% J Rev rundown occurs.

7. Observe the 120% Full Power rundown and annunciator. Record values.

8. Reset the annunciator panel.

9. Remove the magnet key from the console and return it to the SRO on Duty.

d. Log and Linear Detector/Cable Check - Discharge each cable through a multimeter by connecting the meter probes to the outer shield and center conductor. Use the highest voltage scale and observe the voltage decline to 0 volts. Measure the resistance of the detector cable with an electrometer at 1000 VDC. Record the results. The cables should read about 10 10 ohms. Again discharge the cables with the multimeter.

e. Drawer Alignment - Perform the steps in Section 4.3.1, "Low Voltage Power Supplies" from the Log and Linear drawer equipment manual.

High Voltage/Compensating Voltage Check

1. Measure HV at 16.

2. Adjust A4R4 as needed to measure 540 VDC.

3. Adjust A4R4 to a lower voltage until the non-operate LED turns on and the Low CIC Annunciator panel alarms.

4. Record the HV at 16 that the trip occurred at. .

5. Record the voltage measured from A4TP10-A4TP1.

6. Verify that the keypad non-operate switch LED illuminates. Record. the results.

7. Adjust A4R4 to measure 540 VDC at 16.

8. Reset annunciator panel.

9. Verify and record the non-operate keypad switch LED goes off.

10. Record the HV at 16. The high voltage at 16 should be 540 VDC +/- 1 V.

Revised By: William Bonzer uJ :.,UL.a,l\~/j

• • • 'MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES*** Rev SOP: 801 TITLE: LOG AND LINEAR DRAWER CALIBRATION Revised: March 31, 2016 Page 3 of 4

11. Record the voltage measured from A4TP10-A4TP1.

12. If the Low CIC Voltage trip point needs to be adjusted follow the Log and Linear equipment manual steps 4.3 .2.1 and 4.3 .2.2.

13. Me~sure compensating voltage at J7. Adjust A5R4 to 5.8 Vas needed.

14.

• Record compensating voltage level at J7. The compensating voltage should be 5.8 VDC +/- 1 V.

15. Record voltage at A5TP10-A5TP1.

Log Amplifier Alignment L Connect the Keithley 263 pico-amp source to JS of the Long and Linear Rev drawer. Use the readings from the Keithley 263 pico-amp source for the current settings.

2. Complete in the Log Displays Table of SOP 800 for the listed current levels.

3. If alignment is necessary follow steps 4.3 .3 .1-9 of the Log and Linear equipment manual. Repeat Step 3 following any adjustment in alignment.

Period Alignment

1. Perform Section 4.3 .4, "Period Amplifier" in the Log and Linear drawer equipment manual. These adjustments determine the accuracy of the period. When performing these steps, the following guidance should be used.

a. Set the oscilloscope to read 50 mV/cm (DC mode) and 0.2 sec/cm.

b. Use the single sweep display mode with internal triggering. .

c. Save the ramp using the "save mode". After the ramp has been saved, use the cursor feature to automatically read the voltage change for a time span of about 1 second. (Note: The cursor feature* provides a more accurate measurement than manually reading the scope.) *

2. Complete the Period Displays Table on the Annual Checklist.

• • • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES*** Rev SOP: 801 TITLE: LOGANDLINEARDRAWERCALIBRATION Revised: March 31, 2016 Page 4 of 4 Linear Amplifier Alignment Rev

1. Use the Keithley 263 pico-amp source connected to the Log and Linear drawer atJ5. *

2. Connect the voltage meter to ATPlO-ATPl.

3. Apply the currents listed in the Linear Displays Table of SOP 800 and record the displayed readings. .

4. If the Linear Amplifier circuit needs aligned, follow steps 4.3 .5 .1-3 of the Log and Linear equipment manual.

f. Isolated Outputs - Adjust the zero and span on each isolator, as necessary, for equal inputs and outputs.

g. Keypad Switches - Fill out the Keypad Switch Table by depressing the indicated switch and recording the associated readings.

h. Discharge the detector cables at the connectors and the corresponding jacks at the drawer. Reconnect the detector HV, CV, and signal cables. Have an independent knowledgeable person verify cables are properly connected.

i. The person that performed this calibration procedure shall initial and date that the calibration has been properly completed..

Revised By: William Bonzer Approved By: William Bonzer

• • • MISSOURI S&T REACTOR STA1'IDARD OPERi\TlliG PROCEDURES *** Re SOP: 811 TITLE: FIRE AND SMOKE ALAR.Lvi SYSTEi'Vf Re-vised: August 18, 2015 Page 1 of.1 A PURPOSE To ensure that the fire and smoke alarm system is operable during annual calibrations. Re B. PROCEDURE

1. Inform Nlissouri S&T Police of fire alarm system test.

2. Test emergency power by turning circuit breaker No. 32 in the power panel off.

3. If alarm sounds, replace power supply batteries in the battery box and repeat test

4. Check at least one (1) sensor, such as pull station in front office, to insure the system will operate.

5. Tum circuit breaker No. 32 on.

6. Using a heat and smoke source, check each smoke detector by placing the source Re close to each detector. Acknowledge alarm condition at master station for all detectors.

7. Remove cover of each pull station by turning the .top screw and pull the inside lever of each of the two (2) pull stations. AcknovV:ledge alarm condition at master station.

8. Use Test Filter 6424 Projected Beam Detector sheet iii front of the Beam Detector.

Acknowledge alarm condition at master station.

9. Ensure all alarm conditions are cleared.

Note: Acknowledgment of alarm will consist. of verification of audible and visual alarms aJ;J.d resetting by pressing Signal Silence and Reset/Lamp Test buttons at master station. .

Revised By: Anth~ony Alchin "---/ Approved By: William Bonzer

,f . I'/""

/r...---

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

SOP: 816 MSTRPOWERCALIBRATION Revised: March 31, 2016 Page 1of4 A. PURPOSE To ensure that the power indicated on the linear and log channels is the power generated in the reactor.

B. PRECAUTIONS, PREREQUISITES, OR LIMITATIONS

1. In accordance with Technical Specification 4.2.2(3) all console instruments and I Rev safety system shall be calibrated once each ye~r, not to exceed 15 months.

2. The power generation in the Missouri S&T Reactor is limited by Technical I Rev Specifications to 200 kW. It is, therefore, important that the reactor power is less or, in an ideal case, equal to the power indicated in the reactor control room. The calibration of the power instrnments is performed by the calibration procedure described below. (For more details see the report MSTR/85-i.) Stable Rev atmospheric conditions are helpful for a successful calibration.

C. PROCEDURE

1. Tum on both nitrogen diffusers and the pool lights.

2. Set up pool level measuring equipment. It is recommended that two gauges be used in order to have redundant measurements. (Minimum recommended scale division is 0.001 inches.)

3. After the diffusers have been on for at least 3 0 minutes start to take level readings every 15 minutes. Continue for at least one hour prior to the reactor startup to determine the average pool level drop. Be sure to note accurately the time of each reading., Record also the temperature of the pool water inlet thermocoup l es. I Rev

4. Take the reactor to some intermediate power level, e.g." 20, 30, or 40 kW. Note the time the reactor reaches that power level. After rnnning the reactor at this power for a time tp such that the reactor thermal output is between 30 and 50 kW hr. shut down the reactor and note the shutdown time. For example, it is recommended that the reactor power be chosen 40 kW and the operational time tp 1 hr.

Approved By: William Bonzer

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

SOP: 816 lVISTR POWER CALIBRATION I Rev Revised: March 31, 2016 Page 2of4

5. Once all control rods and magnets are fully inserted, note time and pool level every 15 mi.nutes until level decreases equal the rate of decrease before the power run. During this time also continue to take temperature readings using all reactor thermocouples.

6. Plot the data measured with both relative height gauges such as to construct the time-dependent plot of h, i.e. the relative change in height of the pool water surface before, during, and after the power run. (Use units of cm for the plot ofh.)

7. Determine 6 has shown in the sketch below h (cm)

t. h

-Time .... Time t(cm) at at Power Shutdown r-- tp

-1

8. Calculate the average pool water temperature Tw using the data taken immediately before the beginning-of the power run and after the reactor shutdown. (Use only the inlet temperature readings.)

9. Using Figure 1 and data determined in step 7 and 8 determine the amount of heat Q generated in the reactor during the calibration run. (The fact that the coefficient Revised By: William Bonzer_,-, Approved By: William Bonzer

~-.1

(~~s>v'Z<5.L.:*;

./. -

~...).,,._:-;\..-'~./)

v .

~ ./

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

SOP: 816 MSTR POWER CALIBRATION I Rev Revised: March 31, 2016 Page 3 of 4 of the thermal volumetric expansion is to be taken at the temperature which is 1 K higher than the average pool temperature has already been tciken into account while constr.ucting the plot in Figure 1.)

10. Calculate the reactor power using the relationship p [kW]= Q [kW hr}

tp[hr]

11. It the power indicated on the linear and/or Log N recorder is equal to or greater than the calculated power P by not more than 5% no further action is needed. In any other case the position of the pertinent neutron detector needs to be adjusted so as to satisfy the above condition.

12. After both power channels (linear and log) have been properly adjusted take the I Rev reactor to 200 kW and adjust, if necessary, both safety channels so as to indicate the reactor power of 200 kW.

Revised By: William Bonzer Approved By: William Bonzer

' .u1'.Ji L . L-t......r ;""}'"'1 ~

.\) ..) "" i~

1.::;t~./"?JI,},,.'

• • • MISSOURl S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 816 MSTR POWER CALIBRATION Revised: March 31, 2016 Page 4of4

. --;-*-:*-~:7*:*

.-::~*--~~:::*.:::.;.

Fig)JrG 2. UMRR The.rrnal Output vs. Change in Pool Water Height Revised By: William Bonzer Approved By: William Bonzer

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

SOP: 818 TITLE: FUNCTION TEST OF THE BUILDING SECURITY SYSTElVI Complete Revision: May 27, 2015 Page 1 of2

• A. PURPOSE In accordance with Technical Specification 4.2.2, all console instruments and safety systems will be calibrated once each year not to exceed 15 months.

B. PRECAUTIONS, PREREQUISITES, OR LilVllTATIONS After each item is completed, a second knowledgeable person will check connections (where connections have been broken and reconnected), to ensure that the equipment is corniected and on line. This step is very important because failure to reconnect ~ome of the equipment can cause violations of Technical Specifications if the reactor is operated.

C. PROCEDURE A list of equipment in the form of a checklist on SOP 800 will be used to record the date that each system was checked or calibrated. Procedures listed in the Technical manuals have been reprinted in the form of SOP's. As each piece of equipment is checked or calibrated, it shall be checked off on the checklist to ensure that the list has been completed and to serve as a record of the date when the item was completed.

1. Contact Central Dispatch Inc. at 364-6686 and the Missouri S&T Police at extension 4300 to make them aware of the security testing taking place and for verification of each alarm. Also verify each alarm with the Reactor Managers email and cell phone.

2. Arm the alarm system. After the set delay time is up, release the switch for the security door (dead bolt switch). *

3. After the alarm has been verified, continue to check all non-24 hour alarms.

4. Clear the .alarms and verify that all were received.

5. Do not arm the *security system. Check the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> alarms and no alarms should sound.

6. After the alarm has been verified clear the security system.

Revised By: Craig Reisner Approved By: William Bonzer

~)~ "'

ij"-") i.X-Z.L-CI:_

.() /.) * ..'WI 1-')

.,._,..-[

.I--) -~n *> *

?Y>

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

SOP: 818 TITLE: FUNCTION TEST OF THE BUILDING SECURITY SYSTEM Complete Revision: May 27, 2015 Page 2of2

7. Do not arm the security system. Check the Duress Alarm.

8. After the alarm has been verified clear the security system.

9. Arm the security system. Remove the AC power cord from the building AC power plug-in. This steps checks the back-up battery and no alarms should sound.

10. Plug the AC cord back into the wall receptacle and unarm the security system.

11. Open the doors on the security system panels. After alarm has been verified, close and lock doors, and reset the alarm syste.m.

12. Remove the front cover from the motion detector located at the entrance to the secure area.

13. After alarm has been verified, replace cover, and reset the alarm.

14. Repeat steps 12 and 13 on the remaining motion detectors.

15. After the alarm has been verified clear the security system.

16. Using either the intermediate or be9Ili room RAM modules, cause a High Radiation alarm to sound.

17. After alarm has been verified, reset the annunciator panel.

18. Using the battery test switch, test the unit battery.

19. Check all the door tampers by removing covers or cover plates on doors.

20. Complete checklist in SOP 800, step 10.

Revised By: Craig Reisner Approved By: William Bonzer epr~ ...-/1;.

~ j &'

w 1 '

.JLJLi,~.....,,. j :51vJ4J

lVlISSOURI UNIVERSITY OF SCIENCE AND TECHNOLOGY Formeriy University of Missouri-Roi/a May 26, 2016 pear Sir:

Please find enclosed the Annual Progress Report 2015-2016 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, Mr. Spyros Teailforos Sincerely, William Bonzer Reactor Manager mh Enclosure cc: Mr. Spyros Teailforos (NRC) /

Document Control Desk (NRC) V American Nuclear Insurers, c/o Librarian University 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. Ralph Flori Jr, Chair Mining and Nuclear Engineering Dept. (MST)

.I

PROGRESS REPORT 2015-2016 MISSOURI UNIVERSITY OF SCIENCE AND TECHNOLOGY REACTOR

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

NUCLEAR REACTOR FACILITY April 1, 2015 to March 31, 2016 Submitted to The United States Nuclear Regulatory Commission And Missouri University of Science and Technology

11 Table of Contents

SUMMARY

1.0 INTRODUCTION

............................................................................................................................................... 1

1.1 BACKGROUND

INFORMATION ....................................................................................................................... 1 1.2 GENERAL FACILITY STATUS ......................................................................................................................... 2 2.0 REACTOR STAFF AND PERSONNEL ...................................*...................................................................... 3 2.1 REACTOR STAFF ............................................................................................................................................. 3 2.2 LICENSED OPERATORS ........................................................................................................................... ;..... 4 2.3

• RADIATION SAFETY COMMITTEE ................................................................................................................. 4 2.4 HEALTH PHYSICS ........................................................................................................................................... 5 3.0 REACTOR OPERATIONS ................................................................................................................................ 6 4.0 EDUCATIONAL UTILIZATION .................................................................................................................... 11 5.0 REACTOR HEALTH PHYSICS ACTIVITIES ........................................................*..................................... 14 5.1 ROUTINE SURVEYS ....................................................................................................................................... 14 5.2 BY-PRODUCT MATERIAL RELEASE SURVEYS ............................................................................................. 14 5.3 ROUTINEMONITORING ................................................................................................................................ 14 5.4 WASTE DISPOSAL .......................................................................................................................................... 15 5.5 INSTRUMENT CALIBRATIONS ....................................................................................................................... 15 6.0 PLANS ....................................................................................................... :...*..................................................... 16 6.1 DISTANT EDUCATION ............................................................... :....................................... ;............................ 16 6.2 REACTOR OPERATOR TRAINING ....................................................... .-........................................................... 16

111 APPENDIX A: STANDARD OPERATING PROCEDURES CHANGED DURING THE 2015-2016 REPORTING YEAR LIST OFT ABLES TABLE 3-1. CORE 122W TECHNICAL DATA .................................................. ;............................................................ 6 TABLE 3-2. UNSCHEDULED SHUTDOWNS .*....*....*............*.*.............*..*..*..*.....*.................*..*..............*.*...*.*................ 7 TABLE3-3. MAINTENANCE *......***..*..........**.*.*..*.....*.*..*.....*...**.*.*..........*..*.*.*...*.*.*.***.*.....*.****..*.....*.*.*.......*.*.*............ 9 TABLE 3-4. EXERIMENTAL FACILITY USAGE ......**.*..*...*.........*.*.*........*.................***..*..*..........*..*..*..................*....... 10 TABLE 3.5 REACTOR UTILIZATION .**......**.*.*.......*..*..*.*.*......*.*......*.*..*..*....*.*...*...*.***.*.*.*.**.*....*.**....*.....*.*.........**..... 10 TABLE 4-1. MISSOURI S&T CLASSES AT REACTOR FACILITY .*....*.**.*..*................*.*.*...*.......*.*..*..*.......*..*.......**..... 12 TABLE 4-2. REACTOR SHARING PROGRAM 2015-2016 (REPORTING PERIOD) *.*.*.....*.*.*..*..........*.........*.*............... 13 r'

LIST OF FIGURES FIGURE 3-1. MSTR CORE 122W CONFIGURATION .*...........*.*...**.*.....**........*.*.*.*.*.*.*.*.*.......***.............*.*......*..*........ 6

lV

SUMMARY

During the 2015-2016 reporting period, the Missouri University of Science and Technology Reactor (MSTR) was in use for 348.78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 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 over 4,180 student-hours. About 3,460 visitors visited the reactor during the past year. There were 820 participants, mostly high school students, in the U.S. Department of Energy Reactor Sharing Program.

The reactor produced 9679.24kW/hrs. kilowatt-hours of thermal energy usmg approximately 0.423 grams of uranium. A total of 136 samples were neutron irradiated in the reactor with the majority being analyzed in the reactor counting laboratory.

1

1.0 INTRODUCTION

This progress report covers activities at the Missouri University of Science and Technology Reactor (MSTR) Facility for the period April 1, 2015 to March 31, 2016.

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 high-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 acqui~ition, and spectrum analysis software. The alpha spectroscopy system consists of a surface barrier detector and data acquisition equipment. Additionally, there is a thermos-luminance dosimeter reader, digital neutron radiography imager, digital x-ray imager, and liquid scintillation counter for student and faculty usage.

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 Missouri - Columbia audited the reactor facility on December 9, 2015. There were no significant areas of concern. There is an agreement between the MSTR and the University of Missouri-Columbia Research Reactor 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, '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'

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 207 FUEL HANDLING

3. SOP 306 ESTIMATION OF ACTIVITY AND REACTIVITY WORTH OF A SAMPLE

4. SOP 308 RESTORATION OF AC POWER FOLLOWING A POWER OUTAGE

5. SOP 312 CRITICAL EXPERMENT PROCEDURES

6. SOP 501 EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION

7. SOP 653 SEALED SOURCE LEAK TEST

8. SOP 702 IRRADIATION REQUEST FORMS

9. SOP 801 LOG AND LINEARDRAWER CALIBRATION

10. SOP 811 FIRE AND SMOKE ALARM SYSTEM

11. SOP 816 MSTR POWER CALIBRATION

12. SOP 818 FUNCTION TEST OF THE BUILDING SECURTIY SYSTEM 2.0 REACTOR STAFF AND PERSONNEL 2.1 Reactor Staff Dr. Hyoung Kohl Lee Reactor Director Mr. William Bonzer Reactor Manager & Senior Operator Ms. Maureen Henry Office Support Assistant III Mr. Craig Reisner Senior Reactor Operator Mr. Anthony Alchin 1 Electronic Technician III & Senior Operator

1. Effective 5-18-2015

4 2.2 Licensed Operators Name License

1. William Bonzer Senior Operator

2. Craig Reisner . Senior Operator

3. Anthony Alchin Senior Operator

4. Erica Davidson 1 Reactor Operator

5. Cody Stuchal Reactor Operator 1

6. Ethan Margherio Reactor Operator

7. Jonathan Scott Reactor Operator

8. Andrew Bingham Reactor Operator

9. Garrett Jones Reactor Operator

10. Steve Wagstaff Reactor Operator

11. Wesley Tucker Reactor Operator

12. Matthew Caddeli2 Reactor Operator 2

13. Jacob Stueck Reactor Operator 2

14. Justen Vinyard Reactor Operator

1. Termination Date August 6, 2015

2. Effective Date October 15, 2015 2.3 Radiation Safety Committee The Radiation Safety Committee meets quarterly. The committee met on 6/26/2015, 9/25/2015, 12/7/2015 and 3/16/2016 during the reporting period. The committee members are listed below.

Department

1. Dr. Mark Fitch Civil Engineering

2. Ms. Michelle Bresnahan Environmental Health and Safety Services

3. Mr. William Bonzer Nuclear Reactor

4. Mr. Randy Stoll Business Services

5. Dr. David Wronkiewicz Geological Sciences & Geology

6. Dr. Shoaib Usman Mining & Nuclear Engineering

5

7. Dr. Fadha Ahmed Environmental Health and Safety Services

8. Dr. Yue-wern Huang 1 Biological Sciences

9. Dr. Amitava Choudhury Chemistry

10. Dr. Carlos Castano Mining & Nuclear Engineering

11. Mr. Tony Hunt Environmental Health and Safety Services

12. Dr. Robert Aronstam2 Biological Science

1. Joined 7-14-2015

. 2. Resigned 7-30-2015 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. Health Physics personnel are listed below:

1. Ms. Michelle Bresnahan Director of Environmental He~lth and Safety

2. Mr. Brian Smith Industrial Hygienist

3. Dr. Fadha Ahmed Health Physicist

4. Mr. Andrew Bingham Health Physics Technician (part time) Left May, 2015

5. Mr. Alex Swearingen Health Physics Technician (part time)

6. Mr. Wesley Tucker Health Physics Technician (part time)

6 3.0 REACTOR OPERATIO NS Core Confirmation 122W 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 122W. The excess reactivity, shutdown margin, and rod worth's were measured in cold, clean conditions.

Table 3-1. Core 122W Technical Data Parameter Value Rod 1 3.958% L1k/k Rod2 3.239% L1k/k Rod3 1.778% L1k/k Reg Rod 0.232% i1k/k Excess Reactivity 0.640% i1k/k Shutdown Margin* 4.3 77% i1k/k

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

A B s c C-4 F-5 F-11 F-17 D F-4 F-8 F-14 C-1 F-10 F-1 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 122W Configuration

7 KEY TO PREFIXES F- Standard Elements CR- Cadmium Rabbit HF- Half Element BR- Bare Rabbit C- Control Elements S - Source Holder CR- Cadmium Rabbit HC- Hot Cell Rabbit Table 3-2: Unscheduled Shutdowns for 2015-2016 Date Type of Rundown/Cause and Corrective Action Taken RUNDOWNS 05/05/2015 Action: 120% demand rundown Cause: Student did not press 200W scale button hard enough.

Corrective Action Taken: Student reminded to firmly press button SRO on Duty granted permission to restart reactor.

10/20/2015 Action: 120% demand rundown Cause: Trainee did not push 200W scale button in firmly.

Corrective Action Taken: Trainee instructed to push buttons in firmly.

SRO on Duty granted permission to restart reactor.

10/26/2015 Action: 120% demand rundown Cause: Student downscaled instead of upscaled.

Corrective Action Taken: Student instructed to pay more attention to which scale they are pushing.

SRO on Duty granted permission to restart reactor.

8 11/02/2015 Action: 120% demand rundown 1

Cause: Student did not fully push in Linear Channel button.

Corrective Act~on Taken: Student told to press buttons more firmly.

SRO on Duty granted permission to restart reactor.

02/03/2015 Action: 120% Full Power Rundown Cause: UIC inserted into core too much during power calibration.

Corrective Action Taken: Instructed to not let go ofUIC.

SRO on Duty granted permission to restart reactor.

02/23/2016 Action: 120% demand rundown Cause: Linear channel scale not pushed in all the way.

Corrective Action Taken: SRO talked to trainee about pushing buttons in firmly.

SRO on Duty granted permission to restart reactor.

UNPLANNED SHUTDOWNS Date Type of Unplanned Shutdown, Cause and Corrective Action Taken Unplanned Shutdowns*

12/10/2015 Action: Power Outage Corrective Action Taken: None. Reactor was secured and operations ended for the day.

9 Table 3-3: Maintenance for 2015-2016 Type of Maintenance 6/23/2015 Issue: Period <30s Trip Activated and unable to be cleared Corrective Action: Relay K2 discovered to be failed replaced with suitable replacement relay. Weekly checklist performed to ensure proper operation of Log & N Drawer.

6/24/2015 Issue: Reg Rod joystick threads holding joystick to console stripped beyone usability.

Corrective Action: Replaced joystick with a 3 position lever switch originally meant for Auto Permit switch. Verified proper operation. Lever Switch as opposed to joystick should have less strain on the threads holding the switch to console. Replaced Main Control Rods Joystick with a Lever Switch for conformity '1!1d to prevent future problems of the same type.

12/03/2016 Issue: Clutch was slipping when rods fully inserted in core. Rod #3 still trying to drive in.

Corrective Action: Limit switch replaced and moved to new higher location. Slip Clutch readjusted to take less pressure to slip on insert.

01/11/2016 Issue: Linear Recorder Output erratic and unstable*.

Corrective Action: Amplifier Module determined cause of issue. Replaced module with one from a spare recorder in the loft. No erratic or unstable output observed after replacement after an hour of continuous running.

10 Table 3-4. Experimental Facility Usage Facilitv Hours Bare Rabbit Tube 8.78 hrs.

Cadmium Rabbit Tube 0.00 hrs.

I Beam Port 0.0 hrs.

Thermal Column 0.0 hrs.

Other Core Positions 3.94 hrs.

Hot Cell 0.0 hrs.

Gamma Exposures 3.2 hrs.

Total 15.92 hrs.

Table 3-5. Reactor Utilization

1. Reactor use 348.78 hrs.

2. Time at power 231.73 hrs.

3. Energy generated 9679.24 kW/hrs.

4. Total number of samples, neutron irradiated 136

5. U-235 Burned 0.423 g

6. U-235 Burned and Converted 0.500 g

11 4.0 EDUCATIONAL UTILIZATION The reactor facility supported several Missouri S&T courses in the past year for a total of over 4,180 student-hours. The number of Missouri S&T students utilizing the facility was 698. 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.

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

The Reactor Sharing Program, previously funded by the U.S. Department of Energy, was established for col~eges, universities, and high schools that do not have a nuclear reactor. This past year, 479 students and instructors from 140 *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 3,460 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.

12 Table 4-1 Missouri S&T Classes at Reactor Facility CLASS #OF TIME AT STUDENTS Semester NUMBER/TITLE STUDENTS RECTOR HOURS 2015- Graduate Students 2016 Project 4* 56.5 226 SS 2015 NE 2406 30 26 780 SS 2015 NE 4438 25 6 150 SS 2015 NE 1105 Tours 17 1 17 SS 2015 NE 1105 Tours 18 1 18 4/8/2015 NE 4312 16 2 32 4/9/2015 NE 4312 16 2 32 4/10/2015 NE 4312 12 2 24 4/14/2015 NE 1105 Lab 17 1 17 4/17/2015 NE 1105 Lab 16 1 16 4/20/2015 Economics Class- 20 1 20 4/21/2015 Chem Lab 1319 60 1 60 4/22/2015 Chem Lab 1319 60 1 60 4/22/2015 NE 4312 20 2 40 4/22/2015 Chem Lab 1319 60 1 60 4/23/2015 NE 4312 16 2 32 4/24/2015 NE 4312 12 2 24 FS 2015 NE2406 17 42 714 9/4/2015 NE 1105 Tour 31 2 62 9/5/2015 NE 1105 Lab 17 1 17 9/6/2015 NE 1105 Lab 19 1 19 FS 2015 NE 4428 35 30 1050 12/2/2015 NE 1105 Power change 30 8 240 SS 2016 NE 2406 31 44 132 2/10/2016 NE 1105 Tour 14 1 14 2/13/2016 NE 1105 Tout 15 1 15 3/23/2014 NE 4312 24 2 48 3/24/2016 NE4312 25 2 50 SS 2016 NE 4438 21 10 210 Total 698 252.5 4,180

13 Table 4-2 Reactor Sharing Program 2015-2016 (Reporting Period)

DATE EVENT VISITORS TIME 4/2015 Visitor's 5 2 4116/2015 Fort Leonard Wood 3 2 5/2015 Visitors 16 3.5 6/2015 Visitors 22 4 6/9/2015 Jacl<ling 22 3.5 6111/2015 Jackling 23 3.5 6/15/2015 Nuclear Engineering Camp 46 6 6/16/2015 Career Opportunity 7 1 6/17/2015 Venturing Crew 11 1 6/22/2015 Jackling 24 3 6/25/2015 Jackling 27 3 7/2015 Visitors 20 14 7/15/2015 Fort Leonard Wood 5 3 7/16/2015 Kanas City Group 3 '

2 8/2015 Visitors 2 1 8/7/2015 Equity, Diversity & Inclusion Group 7 1 8/25/2015 Rep. Jason Chapman 1 1 8/28/2015 Group From Illinois 6 5 9/2015 Visitors 13 4.5 9/18/2015 Col Parker Fema tour 10 1 9/28/2015 NRC Test 1 30 10/20/2016 NRC 1 8 10/21/2016 DNN Radiological Security Partnership 3 3 10/28/2016 USMC 19 2 10/29/2016 Canberra 2 1 11/2015 Visitors 8 2 11119/2015 East Central 21 2 11/20/2015 Central Security 2 3 12/1/2015 Columbia Audit at Reactor 2 8 12/3/2015 Rolla High School 32 2 1112/2016 Fire Department 2 1 1/28/2016 Gasconade County Scholarship 20 1 2/112016 Boy Scouts 28 3 3/23/2016 Stem All Girl groups 3 sets 63 3 TOTAL 479 126.5

14 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. Releases of all by-product material to authorized, licensed recipients are surveyed and recorded. 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 exposure surveys of the facility consist of direct gamma and neutron measurements. 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 significant contamination outside of contained work areas was found.

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

5.3 Routine Monitoring Seventy-five reactor facility personnel and students involved with the operations in the reactor facility are currently assigned Mirian Technologies, Thermo-Luminescent dosimeters (TLDs). Three of the Reactor Staff have beta, gamma, neutron dosimeters which are read twice monthly. There are four area beta, gamma, neutron dosimeters and two TLD ring dosimeter, which are also read twice monthly.

There are three environmental TLDs outside the reactor building which are read quarterly. There are also five other beta, gamma, neutron dosimeters used by the health physics personnel and four other area beta, gamma, neutron dosimeters that are read monthly. The remaining dosimeters detect beta and gamma radiation only and are read monthly. In addition, six digital, direct-reading dosimeters and six cpirper dosimeters are used for visitors and high radiation work. There have been no significant personnel

15 exposures during this reporting period. Visitors are monitored with direct reading dosimeters. No visitors received any reportable or significant exposure.

Airborne activity in the reactor bay is monitored by a fixed filter; particulate continuous air monitors (CAM). Low levels of Argon-41 are routinely produced during operations.

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. From April 2015 through March 2016 sample concentrations averaged 8.44x10-6 µCi/ml.

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 this period, an estimated 36,519.22 µCi of Ar-41 was released into the air.

5.4 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. Water is analyzed for radioactive contamination and approval is required before the water is released. During this period there were no waste disposed from the reactor facility.

5.5 Instrument Calibrations During this period, portable instruments and area monitors were calibrated annually.

16 6.0 PLANS The reactor staff will be two major projects during the next reporting period distant education program and continuation of the reactor operator training program.

6.1 Distant Education A distant education system has been developed to conduct laboratory sessions with students of the Missouri S&T Campus and other universities. Due to the size of the Missouri S&T Nuclear Engineering classes, the distant education system allows students to participate in lab sessions as one group in larger a classroom than what is available for room in the MSTR building.

Equipment has been installed to replace the existing rod drive motors and rod height indicators to output rod height information over the internet. Audio/video equipment is used for students to watch reactor staff performing the labs, to ask questions to the staff and obtain data from the control room instrumentation.

The reactor staff has conducted distant education with the Missouri S&T Nuclear Engineering Department, Missouri S&T Chemistry Department and University of Illinois Nuclear Engineering students at Urbana, Illinois. These departments are providing feedback from students participating in the labs to improve our presentation techniques and provide suggestions regarding audio/video equipment improvements.

6.2 Reactor Operator Training The MSTR had three students obtain their Reactor Operatot lienses. The reactor staff is limiting operator training to around ten students with a very strong desire to obtain the license and assist reactor staff with reactor operations. The new training program has proven to be effective in keeping the students that want the license and work with reactor staff. At the end of the reporting period eight students were training for an operator's license to take in the fall of2016 and three for the spring of2017.

17 APPENDIX A.

STANDARD OPERATING PROCEDURES CHANGED DURING THE 2015-2016 REPORTING YEAR

. ***MISSOURI S&T REACTOR STANDARD OPERATING PROC:EDURES ***

SOP: INDEX TITLE: INDEX Revised: September 14, 2015 Page 1 of 3 SOP 100-1.99 Routine Reactor Operation SOP 100 Preamble SOP 101 General Operational. Procedures SOP 102 Pre-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 Exc.ess 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 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 Auxiliary Pool Water Cooler System Operations I Rev SOP 306 Estimation of Activity and Reactivity Worth of a Sample SOP 308 Restoration of AC Power Following a Power Outage Response to a Coolant System Leak I Rev SOP 309 SOP 3f0 Facility Modifications SOP 311 Receipt of Licensed Materials SOP 312 Critical Experiment Procedures SOP 400-499 Reserved for Future Use Revised By: Maureen Henry Approved By: William Bonzer w~~

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

SOP: INDEX TITLE: INDEX Revised: September 14, 2015 Page 2 of3 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 Spedal 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 J Rev 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 41 Ar Concentration in the Reactor Building Air SOP 655 Radiation Area Monitor (RAM) Calibrations Revised By: Maureen Henry. Approved By: William Bonzer (A)~~

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

SOP: INDEX TITLE: INDEX Revised: September 14, 2015 Page 3of3 SOP 700 - 799 Experiments SOP 702 Irradiation Request Forms SOP 710 Insertion and Removal of Experiments SOP 711 Beam Hole Facility .

SOP 712 Thermal Column Facility SOP 800 - 899 Reactor Instrumentation SOP 800 Annual Checklist SOP 801 Log and Linear Drawer Calibration SOP 802 Linear Channel SOP 803 Log Count Rate (LCR) Channel SOP 804 Safety Amplifier 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 UMR Power Calibration SOP 818 Function Test of Building Security System I Rev Revised By: Maureen Henry Approved By: William Bonzer

• • • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES*** Rev SOP: 207 TITLE: FUEL HANDLING Revised: August 7, 2015 Page 1 of 7 A. PURPOSE To provide for the safe and efficient movement of fuel elements and control rod fuel elements to and from the core and the Fuel Storage Rack.

B. PRECAUTIONS, PREREQUISITES, AND LIMITATIONS

1. All rearrangements of the core, fuel movement, and associated Health Physics monitoring, or other actions involving fuel shall be under the direct supervision of a Senior Reactor Operator.

2. All fuel movements shall be logged in the permanent log book.

3. Prior to any fuel movement, a completed Transfer Order Form must be filled out and approved by either the Reactor Manager or Reactor Director.

4. When moving fuel elements, the fuel handling tool must be kept in a vertical attitude.

5. A licensed operator shall visually confirm that there are no unoccupied internal lattice positions in the core before a new core is taken critical.

6. When loading to a new core configuration, measure the core excess reactivity, shutdown margin, and rod worths prior to exceeding a power of 1 kW. Log this information on a Core and Rack Storage Form ..

7. When loading to a new core configuration that involves a reactivity change greater than 0.2% delta-k/k or changes in control rod locations, excess reactivity and shutdown margin :rn,ust be determined for both the "W" and "T" modes.

Revised By: William Bonzer Approved By: William Bonzer

• • • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES*** Rev SOP: 207 TITLE: FUEL HANDLING Revised: August 7, 2015 Page 2 of7 C. PROCEDURE I. Unloading <!f Fuel Elements (unrodded) from the Core to the Fuel Storage Rack.

1. Complete a Start-Up Checklist (SOP 102).

2. Withdraw shim/safety Rods 1, 2 and 3 to shim range.

3. Unlock the fuel handling tools.

4. In accordance with the Transfer Order Form, the person with the fuel handling tool will request permission to move the fuel element. Example:

"Request permission to move fuel element Fl from grid position D7 to rack storage RlO".

• . 5. With the Control Room Operator's approval, latch the fuel element with the handling tool. Announce, "Tool latched".

6. The Control Room Operator will then grant permission to remove the fuel element from the core .

._ /

7. Withdraw the assembly from the core. When the fuel handling tool and attached element have cleared the core grid plate, announce, "Element clear".

8. Move the element to the fuel storage end of the pool.

9. Rotate the fuel element 180° so that the bow of the fuel element remains toward the center of the pool.

10. Insert the fuel element into the designated location and check to ensure that it is properly seated in the fuel rack. Announce "Element seated".

11. Unlatch the fuel handling tool.

Revised By: William Bonzer Approved By: William Bonzer

• • • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 207 TITLE: FUEL HANDLING Revised: August 7, 2015 Page 3 of7

12. The Control Room Operator shall log the fuel movement in the permanent log book.

13. Transfer the element identification tag from the core status board to the fuel storage status board.

14. Repeat Steps 4 through 13 to remove additional elements from the core.

15. Lock the fuel handling tool in its holder and return the key to the safe.

16. Complete the necessary information on the Transfer Order form.

17. Perform a Reactor Secured Checklist (SOP 105) as appropriate.

II. Unloading of Control Rod Fuel Elements from the Core to the Fuel Storage Rack.

1. Unload fuel elements from the core (per Section I of this procedure) such that the core loading is below one-half of a critical mass. A single control rod fuel assembly may be removed from the core with this loading.

2. Unload all of the fuel elements from the core if two or more control rod fuel elements are to be removed.

3. Disconnect and uncouple the control rod drive, shroud and magnet extension.

4. Remove the shroud and magnet extension from the control rod element.

5. Remove the control rod from the element, if desired.

6. To unload, complete Steps 3 through 17 of Section I of this procedure.

Note: The control rod fuel element may be transferred to an appropriate "basket to facilitate easy movement within the pool.

Revised By: William Bonzer Approved By: William Bonzer WJJ~~

• • • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES*** Rev SOP: 207 TITLE: FUEL HANDLING Revised: August 7, 2015

• Page 4of7 III. Loading of Fuel Elements from the Fuel Storage Rack to the Core

1. The Control Room Operator must comply with SOP 312 (Approach to Criti~al) during the loading of the core. The Control Room Operator will be responsible for collecting the necessary data, constructing the 1/M plot and instructing fuel handlers as to assemblies that may be loaded.

2. All control rod fuel elements and control rods must be installed in the core per Section IV prior to the loading of any fuel element

3. Control rod drop times must be completed per SOP 813 on all rods of control assemblies that have been moved or that have had their magnet assemblies removed and reinstalled prior to the loading of any fuel element.

4. Complete Steps 1, 2, and 3 from Section I of this procedure.

5. In accordance with the Transfer Order Form, the person with the fuel handling tool will request permission to move the fuel element. (Example "Request permission to move fuel element Fl from storage rack RIO to grid position D7. ")

6. With Control Room Operator approval, latch and remove the fuel element from the storage rack, transport the demerit to the edge of the core grid plate and announce, "Approaching core". *

7. Wait for the Control Room Operator's approval prior to movement into the core area. Following the Control Room Operator's approval, place the fuel element in the core. The fuel element must be rotated 180° so that the bow of fuel points to center of pool.

8. When the element is seated, announce, "Element seated". Do not unlatch the fuel. Be prepared to immediately remove the fuel element from the core if instructed by the Control Room Operator.

Revised By: William Bonzer Approved By: William Bonzer

• • • MISSOURI S&TREACTOR STANDARD OPERATING PROCEDURES*** Rev SOP: 207 TITLE: FUEL HANDLING Revised: August 7, 2015 Page 5 of7

9. With Control Room Operator approval, unlatch the element and move the tool clear of the core area. Announce, "Tool clear".

10. The Control Room Operator shall log the fuel movement in the permanent log.

11. Transfer the identification tag for the element from the fuel storage status board to the core status board.

12. To load additional fuel elements, repeat Steps 5 through 12 as instructed by the Control Room Operator.

13. When loading is complete, complete Steps 15, 16, and 17 of Section I of this procedure.

IV. Loading Control Rod Fuel Elements from the Fuel Storage Rack to the Core.

1. Complete a Pre-Startup Checklist to the extent possible. The 2 cps interlock may need to be bypassed by an SRO and other steps such as dropping rods may be omitted when no control rods are loaded in the core.

2. Load all of the control rod fuel elements in accordance with Steps 5 through 12 in Section III.

3. Insert control rods and reassemble the drive mechanisms.

4. Check the withdraw and insert control, observe the rod position indication, and ensure proper operation of the control rod drive system.

5. Perform Rod Drop Times (SOP 813) on all rod assemblies that have been moved or whose magnet assemblies have been removed and reinstalled.

6. If fuel loading is to continue go to section III of this procedure, otherwise complete Steps 15, 16, and 17 of Section I of this procedure.

Revised By: William Bonzer Approved By: William Bonzer w:JL;~n ~

• • • MISSOURI S&TREACTOR STANDARD OPERATING PROCEDURES*** Rev SOP: 207 TITLE: FUEL HANDLING Revised: August 7, 2015 Page 6 of7 TRANSFER ORDER FORM Description of Fuel Movement Lo ading Number ---------------

I ELEMENT ID I FROlVI 1

• TO I COMMENTS I Authorized by_______ Accomplished by 1 _ _ _ __

(Reactor Manager or Director) 2 _ _ _ __

Date - - - - - - - Date completed Revised By: William Bonzer Approved By: William Bonzer

• • • MISSOURI S&TREACTOR STANDARD OPERATING PROCEDURES*** I Rev SOP: 207 TITLE: FUEL HANDLING Revised: August 7, 2015 Page 7 of7 MSTR CORE AND RACK STORAGE FORM I Rev DATE ------ LOADING NUMBER - - -

Rl R2 R3 R4 R5 R6 R7 R8 R9 RIO Rl 1 R12 R13 R14 R15 I*

RACK STORAGE FACILITY R16 R17 R18 R19 R20 R21 I R22 I R23 I R24 I R25 R26 R27 R28 R29 R30 A

Core Excess Reactivity _ _ _ _ _ __

R Shut-Down Margin _ _ _ _ _ _ __

Rod Worths Rod 1: - - - - Rod 3: -~---

Rod 2: Reg Rod: _ __

n F.

F 2 3 4 56 7 -8 9 Rev MSTR CORE STATUS Elem. U-235 Mass Elem. U-235 Mass Elem. U-235 Mass Total U-235 Mass (Grams) _ _ _ __

Review and Approval:

(Reactor Director or Manager)

Revised By: William Bonzer Approved By: William Bonzer n

• • • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** j Re:v SOP: 306 TITLE: ESTIMATION OF ACTIVITY AND REACTIVITY WORTH OF A SAMPLE Revised: May 21, 2015 Page 1 of3 A. PURPOSE The purpose of this procedure is to provide guidance for calculating the radioactivity and reactivity.

B. PRECAUTIONS, PREREQUISITES, OR LIMITATIONS

1. SOP 702, "Request for Irradiation" specifies when this procedure is to be used.

2. Values obtained using these procedure are to be considered approximate.

C. PROCEDURE

1. Calculation of Activity (eq. 1) where m = Mass of the element to be irradiated (grams) a = Isotopic abundance of the element .

NA =Avogadro's Number (6.02xl023 atoms/mole)

AW = Isotopic weight (grams/mole) cra = Isotopic activation cross-section (cm2) .

<D =Neutron flux (n/cm2 -sec)

T 112 =Half life of the produced radioisotope (min) t = Irradiation time (min)

Sample Calculation:

A 0.0985 gm sample of A1 27 is to be irradiated in a flux of 5x10 10 n/cm2-sec.

What is the activity after 5 min. of irradiation? (cra = 0.241b = 0.241x10-24 cm2, T112 = 2.24 min, 3.7x10 7 dis/sec= 1 mCi)

Revised by: William Bonzer Approved By: William Bonzer

• • • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES*** Rev SOP: 306 TITLE: ESTIMATION OF ACTIVITY AND REACTIVITY WORTH OF A SAMPLE Revised: May 21, 2015 Page _2 of 3 23 Act= 1xo.09ssx6.02x10 (0. 214 x 10 _24)(S x 10 10) 27

-(0.693)(5) 1- e 2.24 = 2.08 x 10 7 dis/sec= 0.56 mCi

2. Calculation of Reactivity Worth of a Sample The reactivity worth of a sample Ps when placed in the neutron flux <l>s can be calculated by comparing it to the reactivity worth Pa of a known absorber placed in the neutron flux a using the following formula (eq.2) where a = Microscopic absorption cross-section (barns) m =Mass (grams)

AW = Isotopic weight (grams/mole)

=Neutron thermal flux (n/cm2 -sec)

Subscripts "s" and "a" refer to the s.ample and known absorber respectively.

Using data from a reactivity experiment with a piece of indium absorber placed in the various positions of the row D at the reactor power of 20W the eq. (2) can be simplified to Ps = 1.4 x 10- 21 x crsms x Q)~ x abundance of Isotope (eq. 3)

AW5 (Note: The value of the neutron flux <l>s must correspond to the reactor power of 20W.)

Sample Calculation:

A 2.0 gm sample of Al-27 (as = 0.241 barns) is to be irradiated in a flux of 2.6xl0 10 n/cm2 sec. at 2 kW. What is the expected reactivity worth?

Revised by: William Bonzer Approved By: William Bonzer

• • • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES*** Rey SOP: 306 TITLE: ESTIMATION OF ACTIVITY AND REACTIVITY WORTH OF A SAMPLE Revised: May 21, 2015 Page 3 of3 2

21 0.241 x 2.0 ( 10 20 )

p = 1.4 x 10- x 27 x 2.6 x 10 x 2000

= 1.7 x 10-6 ~k/k

3. Calculation of Reactivity Worth of a Void When a void is placed in or near the reactor core a change in reactivity can be expected. This is due to the void coefficient of reactivity. A void itself will add negative reactivity to the reactor, but the greatest concern is the removal or collapse of a void which will add positive reactivity.

The void coefficient measured at the core periphery is -1 o-6 ~k/k/cm3 .

Sample Calculation:

A sample will be placed next to the core in an empty 250 ml bottle. What is change in reactivity due to the void?

p = 250 cm3 (1 o-6 ~k/k/cm3 ) = 2.5 x 104 ~k/k.

Revised by: William Bonzer Approved By: William Bonzer

• • • MISSOURI S&TREACTOR STANDARD OPERATING PROCEDURES*** Rev SOP: 308 . TITLE: RESTORATION OF AC POWER FOLLOWING A POWER OUTAGE Revised: May 28, 2015 Page 1 of2 A. PURPOSE The purpose of this SOP is to ensure that power is restored to equipment in a safe and efficient manner following a trip of umegulated and/or regulated power and to prevent damage to the equipment.

B. PRECAUTIONS, PREREQIDSITES, OR LIMITATIONS

1. Personnel restoring unregulated and/or regulated power should be familiar with* the operation of the equipment affected.

2. A weekly check should be performed before operating the reactor at a power higherthan 20 kW following a loss and restoration of power.

3. Any malfunctions or abnormality of equipment should be immediately reported to the SRO Rev on Duty.

C. PROCEDURE

S

1. Reset the unregulated and regulated power supplies, which are located in the equipment room behind the console panel.

2. All annunciator lights and buzzer may be on. I Rev

3. Push the am1unciator acknowledge button to silence the buzzer.

4.* Reset the Linear power supply located in the control room. (Note: The power supply must Rev warm up for several minutes before it will reset.

5. Press the annunciator panel reset button. The annunciator should now indicate a normal Rev situation. (Note: A normal situation is indicated by all lights being extinguished, except Manual Scram, Recorder Off and Manual Operation.)

Written By: William Bonzer Approved By: William Bonzer w JL:,,.. G1r>v;,;

• • • MISSOURl S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 308 TITLE: RESTORATION OF AC POWER FOLLOWING A POWER OUTAGE Revised: May 28, 2015 Page 2 of2

6. Notify the SRO on Duty of the power outage or tag the console to assure a weekly check is completed prior to reactor runs exceeding 20 kW. 1

7. Start the demineralizer pump by pushing its "Start" button. (Note: The start button is Rev located on the intermediate level, on the wall behind the pump.

Written By: William Bonzer Approved By: William Bonzer

~

-;1fJ I,,_.uI '-Li*L-Cl'"i I/ D~ {. .

• • • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 312 TITLE: CRITICAL EXPERILVIENT PROCEDURES Revised: August 7, 2015 Page 1 of 5 A. REACTIVITY REQUIREMENTS Any individual experiment involving a worth of more than 0.4% reactivity will be installed in the partially unloaded core and the reactor brought to power by a critical experiment. No single independent experiment worth more than 0.7% will be installed in the reactor.

B. PROCEDURE

\Vhen a new configuration of fuel elements for a new core position is to be used in.the reactor, source multiplication in the core will be measured after each element is added.

The data obt~ned will be plotted (as it is obtained) to allow prediction of the point at which the reactor will go critical. In the case where a large sample or experiment is to be positioned in or near the core, the reactor will be unloaded, the sample or experiment positioned, and the same procedure used to approach criticality. The steps in the procedure are as follows:

1. A calculation of the critical mass of the projected loading will be made.

2. The control rod fuel elements and rod drives will be installed in the desired positions.

3. The reactor checkout procedure will be carried out, as for a reactor start-up. Note that during the initial stages of the experiment, it will be necessary to bypass the 2 cps interlock. This will be under direct superv~sion of the SRO in charge of the critical experiment.

4. The rods and reg rod will be raised to the Shim Range.

5. A neutron source will be installed and approximately 50% of the critical mass calculated in step (1) will be loaded, with constant surveillance of the count rate.

Whenever fuel elements are loaded or unloaded, fuel element numbers and positions will be carefully recorded both in the log book and on the loading chart.

At this point, the count rate in the fission chamber channel will be determined using the scaler, to give a measure of the source multiplication.

Revised By: ""William Bonzer Approved By: William Bonzer

• • • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES*** Rev SOP: 312 TITLE: CRITICAL EXPERilYIENT PROCEDURES Revised: August 7, 2015 Page 2 of 5..

6. The rods then will be fully withdrawn and another count made. Then the rods

• will be dri:r~n back to Shim Range.

7. One additional fuel element will be loaded, and the measurements of steps (5) and (6) repeated. This data *will be plotted to give the "Subcritical Multiplication Curve" as soon as it is obtained, before any further loading is done. The curve obtained from plotting the data taken with the rods fully withdrawn gives an indication of when it will be possible to make the reactor critical by withdrawing rods. The data taken with the rods at Shim Range gives a curve which indicates the possibility of going critical during the actual loading operation.

8. Step (7) will be repeated until the reactor goes critical at which point rod positi_ons will be recorded. If the reactor goes critical without sufficient excess reactivity for operational use, the loading will be continued in half-element increments using the Shim Range Subcritical Multiplication Curve to ensure the criticality is not reached during loading of an element. This completes the critical experiment and at this point, a new core configuration will be designated. At the completion of the experiment, fuel handling tools will be locked and the plots of the data obtained and the loading chart will be attached to a page in the log book of core loadings. The person loading fuel will maintain a position which will allow instant reversal of motion of the fuel element if the operator at the console orders it. The loader will maintain positive control. over the fuel element until the operator specifically gives permission to release it."

C. PLOTTINGDATA

• I. Select loading chart as illustrated in Figure 1 and record data on loading chart and in log book as critical experiment progresses.

2. Prepare graph as illustrated in Figure 2.

3. In step B-5 of this procedure, the initial 50% loading and rod position count will be at the base count rate C0

• Revised By: William Bonzer Approved By: *wmiam Bonzer w~~ iJ.JA:~-1 ~Y>

• • • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** ReY SOP: 312 TITLE: CRITICAL EXPERJMENT PROCEDURES Revised: August 7, 2015 Page 3of5 ..

4. Beyond this point the various counts at Shim *Range and fully withdrawn rod positions when loading elements will be designated as Ct.

5. At each element addition (when Shim Range and fully withdrawn count is made) the subcritical multiplication M will be:

where C0 remains constant and Ct will vary for each counting condition.

6. The value of l/M shall then be plotted on the curve vs. the nun1ber of elements added for Shim Range (6) and fully withdrawn rod positioned (0).

r.

D. LOADING NUIVIBERING SYSTEM The system for designating a loading will be as follows:

1. Each new core configuration will be designated by a number which will be the successive number following the last loading.

2. A loading diagram will be made out and stapled in the log book of core loadings for each loading.

Revised By: William Bonzer Approved By: William Bonzer vu* k;/\ ~1--'1

• • • IvIISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 312 TITLE: CRITICAL EXPERI1\1ENT PROCEDURES Revised: August 7, 2015 Page 4 of 5 ..

Transfer Order Form Sheet - - - - of - - - - No. - - - - - -

Loading No. - - - - - -

Move Elem. No. From To Remarks r

Authorized by _ _ _ _ _ _ _ _ _ __ Accomplished by 1 _ _ _ _ __

Date 2 ------

Date, time completed _ _ _ _ __

Figure 1 Revised By: William Bonzer Approved By: William Bonzer uJ~ ~~Vl vuJlv~rr G-r~?

• • • MISSOURJ S&T REACTOR STANDARD OPERATING PROCEDURES*** Rev SOP: 312 TITLE: CRITICAL EXPERJMENT PROCEDURES Revised: August 7, 2015 Page 5 of 5.

1 0.9 0.8 0.7 1 0.6 M

0.5 0.4 0.3 0.2 0.1 0

1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 Number of Elements Figure 2 Revised By: .William Bonzer Approved By: William Bonzer w~~ wJt;~~~

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

SOP: 501 TITLES: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Revised: May 21, 2015 Page 7 of7 I Rev MISSOURI S&T EMERGENCY PHONE LIST Reactor Staff CELL HOME WORK William Benzer, Manager, SRO 578-9463 368-0318 341-4384 Craig Reisner, Senior Reactor Operator 573-247-7557 573-729-7277 341-4291 Anthony Alchin, Electronics Technician III 816-274-1771 341-6617 Rev Maureen Henry, Office Support Ast. III 201-7275 341-6016 University Administrative Staff Michelle Bresnahan, EHS Director, Radiation Safety Officer 314-239-7751 341-4305 Raymon Bogart Interim,Director Missouri S&T Police 201-58&5 426-5 815 341-4300 Dr.Cheryl B. Schrader, Chancellor 201-7392 341-7141 341-4116 Walter Branson, VC Chancellor Finance & Adm. 260-402-0317 341-4122 James Packard, Director Physical Facilities 578-8167 341-4252 Dr. Goodman DO, Director Student Health Services 341-4284 Dr.Hyoung Lee,Chair of Nuclear Eng, Reactor Director 573-202-4665 341-4585 Dr.Ralph Flori Jr, Interim Chair of Mining and Nuclear 578 -3130 341-7583 Rev Fadha Ahmed, Health Physicist EHS-Missouri S&T 314-960-9211 636-223-2054 341-7014 Local Missouri S&T Police 341-4300 Rolla City Police 911 Rolla Fire Department 911 Phelps County Hospital 911 Rolla Emergency Management Agency 911 State Agencies Missouri Highway Patrol (573) 368-2345 Mis.souri State Emergency Mgt. (24 hr.) (573) 751-2748 Missouri Dept. of Natural Resources (24 hr.) (573) 634-2436 Missouri Bureau of Environmental Epidemiology (573) 751-6160 (573) 751-4674 (24hrs)

Federal Agencies

• NRC, Operations Center (301) 951-0550 NRC Duty Officer (24 hr.) (301) 816-5100 American Nuclear Insurers (860) 682-1301 Radiation Emergency Assistance Center (865) 576-3131 (865) 576-1005 (24hrs)

Revised By: Maureen Henry Approved: William Bonzer

~

r , i '{)/) " (? *'

...... v ~l;:v*VI"> 1 ..J.-v:~-2f"?

~ '(-L-Lul,"'\._

\(' fl.

• • • MISSOURI S&TREACTOR STANDARD OPERATING PROCEDURES*** I Rev .

SOP: 653 TITLE: SEALED SOURCE LEAK TEST Revised: March 31, 2016 Page 1 of 2 A. PURPOSE To ensure the integrity and encapsulation of sealed sources and to guard against contamination of personnel.

B. PRECAUTIONS, PREREQUISITES, OR LIMITATIONS

1. This procedure is to be performed by Health Physics staff personnel.

2. The following sources located at the reactor facility are to be leak tested semi-annually: PuBe SIN M-1092 (Reactor Startup Source), PuBe SIN M-169 (RAM Calibration Source), Cs-137 SIN 74-156 (RAM Calibration Source). The Cs 137 1* Rev source is located in the JL Shepherd Shield SN5409 .

• 3. Leak test requirements are listed in item 14 (A through F) ofNRC Materials License number 24-00513-40.

C. PROCEDURE

1. The leak test should be performed with filter-paper discs or with cotton-tipped applicators depending upon the source activity, configuration, and containment.

2. The source, source holder, and immediately surrounding area should be rubbed.firmly with the swipes held with tongs or forceps or with cotton-tipped applicators in.order to remove any surface contamination that may be present. If access to the sealed source is prevented by the construction of the device, the swipes should be taken as near the source as possible:

3. Each swipe or applicator should be placed in a separate envelope appropriately labeled for identification.

4. Frisk the swipes with an open window G-M probe. If any detectable activity is observed above background, contact the Reactor Health Physicist for appropriate approvals before removing the swipe from the facility. If no detectable activity is identified, the swipes may be removed from the facility for counting at the Health Physics office.

Revised By: William Bonzer Approved By: William Bonzer i

.~,.1l-J*

\

i_./V~"".

!; , u ...,...-v1 r ,'.? **

'1.::i.,(J;V \ !!--)

d V"

J' ~

/v , J'. U11

11 '

-~~-

1t_.-,i.-'l

)

n

..J u

?

cf'/

ld., .,-,.y:-.., .lJ

• • • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES*** Rev SOP: 653 . TITLE: SEALED SOURCE LEAK TEST

. Revised: March 31, 2016 Page 2 of2

5. Evaluation 9f swipes taken from sealed sources containing a beta-gamma emitter should be made with shielded, end-window, Geiger-Mueller counter or equivalent.

Evaluation of swipes taken from sealed sources containing an alpha emitter should be made with a gas-flow proportional counter or equivalent.

6. If the results of the test indicate a removable contamination in excess of 0.005 microcuries, the following steps shall be taken:

a. The source is to b.e taken from service immediately and held* in secured storage until it can be decontaminated.

b. Notify the Reactor Manager.

c. File a report with the NRC that contains the information required by section 14.E of the Materials License.

Revised By: William Bonzer Approved By: William Bonzer

. I * .1 :J '

(/v J'.,.~La,-.-'Y">

i/

fl ::S...c***v<. *i.-J 3'

vv'~Ql'-tr-~ f2~x>*~'

• • MISSOURI S&TREACTOR STANDARD OPERATING PROCEDURES*** Rev SOP: 702 TITLE: IRRADIATION REQUEST FORMS Revised: March 31, 2016 Page 1 of 8 A. PURPOSE To provide for the thorough Reactor Staff review of all experiments to be irradiated by neutrons from the JYISTR. The review evaluates potential 1) reactivity effects, 2) dose I Rev hazards to the experimenter, and 3) hazards to the reactor.

B. PRECAUTIONS, PREREQUISITES OR LIMITATIONS

1. All sample irradiations must be performed under an approved Irradiation Request Form (IRF) with two approval signatures.

2. All materials to be irradiated are to either be corrosion resistant or encapsulated in corrosion resistant containers.

3. Approved IRFs remain valid for future irradiations.

4. IRFs will be numbered sequentially following the last two digits of the current year (e.g. 95-1, 95-2, etc.).

5. Radiation Safety Committee approval is required for

a. experiments worth more than 0.4% 6.k/k,

b. explosive materials,

c. fueled experiments, or

d. untried experiments.

6. The total reactivity worth of all experiments is limited to 1.2% 6.k/k.

7. Experiments having moving parts shall not have an insertion rate greater than 0.05%

6.k/k per second.

8. Cooling is to be provided as needed to prevent the surface temperature of an experiment being irradiated from exceeding the boiling point of the pool.

Revised By: William Bonzer Approved By: William Bonzer

/d *:_,Qe<-~*)*V'

.. i] f,} .. 1")

l**v ...d<-~*i-vi ~::J.._.~......,v\ i

_i RtJ-,-v)<Q) ,:r7

- 0

• • MISSOURI S&TREACTOR STANDARD OPERATING PROCEDURES*** Re.v SOP: 702 TITLE: IRRADIATION REQUEST FORMS Revised: March 31, 2016 Page 2 of 8 C. PROCEDURE - IRRADIATION REQUEST FORM The IRF should be completed according to the following steps:

1. IRRADIATION REQUEST - This section of the IRF should be completed by the experimenter.

a. Sample Description - Describe the sample material to be irradiated (e.g.

dried tobacco leaves, powdered milk, gold foil, etc.)

b. Physical Form - Specify the physical form of the sample material (e.g, powder, ash, liquid, etc).

c. Encapsulation - Check the box marked "Poly-vial" or check "other" and describe.

d. Irradiation Location - Specify the irradiation facility to be used. More than one facility may be authorized on a single IRF. If "Other" is specified, describe the irradiation location (for example: "wire stringer in Grid Position C-3").

e. Irradiation Limits - Specify the irradfatiQn limits as follows:

1) Power - Specify the maximum reactor power for irradiation.

Samples may NOT be irradiated at powers higher than specified.

2) Time - Specify the irradiation time for the sample( s) at the maximum power. Samples may be irradiated at lower powers for times longer than the specified irradiation time as long as the total fluence (i.e.

kW-hrs) does not exceed the product of the specified maximum power and irradiation time.

3) Mass - Specify the maximum sample mass (grams) to be irradiated in any single irradiation.

Handwritten revisions to the limits are allowed based on the measure dose rate from the initial irradiation(s).

Revised By: William Bonzer

' 'j.1

• ~/*

,.  !)

A.'

i f t /J

(.tl) ,_x:.-~GL/'YY°l 1[-...L.-* \}'"";:,*v :z. .L *;

0

• • MISSOURI S&TREACTOR STANDARD OPERATING PROCEDURES*** Rev SOP: 702 TITLE: IRRADIATION REQUEST FORMS Revised: March 31, 2016 Page 3 of 8 Assume dose rate is a linear function of power, irradiation time, and sample mass. Revised irradiation limits require the review and approval of either the SRO on Duty, Reactor Manager, or Reactor Director as signified by their initials with dates.

f. Expected Dose Rate - Specify the expected 1 foot dose rate when the sample comes out of the reactor based on one of the categories below:

Experience - The expected dose rate may be based on measurements made during previous similar irradiations. In such instances, record the IRF number of the previous similar irradiation.

Calculations - The expected dose rate may be calculated using the DR=6CE rule (or other appropriate method) where DR is the 1 foot dose rate in mrem/hr, C is the expected activity in mCi, and Eis the gamma energy in Me V. The expected activity can be calculated using A= N <J¢(1- e -J.i;,,) where N is the number of target atoms, cr is the cross section, <p is the neutron flux, A. is the decay constant and tirr is the irradiation time.

Completely Unknown -A trial irradiation is required ifthe expected dose rate is completely unknown. The irradiation limits for a trial irradiation are normally reactor power:::; 2 kW, irradiation time:::; 1 minute, and sample mass :::; . 1 gram. The reviewers may approve different trial irradiation limits at their discretion. Dose rates for higher powers, masses and times* can then be linearly extrapolated based on the measured dose rate resulting from the trial irradiation.

g. Reactivity Worth - Estimate the reactivity worth of the sample based on one of the categories below:

Default-A default reactivity worth of <0.05% .6..k/k may be used for the rabbit facilities if the sample mass is less than 7 grams. A default reactivity worth for core periphery stringers of <0.1 % .6..k/k may be used for holders with a volume of 3 5 cm3 or less and a sample mass of 7 grams or less. (Note: The default mass and location values are based on a report by Wagner, 1992.) Beamport and thermal column irradiations have a default reactivity of 0.0%.

Approved By: William Bonzer i,,.,-li.* ......(::...~c....e,:..,...~**-:

// . ~ '"'-* ~ .

.~ . . '"' .. v~y~t

• • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES*** Re.v SOP: 702 TITLE: IRRADIATION REQUEST FORMS Revised: March 31, 2016 Page 4of8 Experience - The estimated reactivity worth based on previous "experience" may be specified along with the applicable IRF number.

If no previous experience exists, estimate the reactivity worth using I Rev SOP 306.

Completely Unknown - If reactivity worth is completely unknown and not easily calculated, it must be experimentally determined.

h. Comments - Provide additional comments, if any.

i. Request Completed By - The person completing items a through h ab_ove should sign their name in the blank provided.

2. REVIEW AND APPROVAL-This portion of the IRF is to be completed by one of the reviewers and approved by both of the reviewers.

a. Analysis of Potential Hazards - Reviewers shall analyze potential hazards associated with the experiment with regard to following:

1. Reactivity - Review the expected reactivity worth information.

Assure that the Technical Specification Section 3 .7 requirements are met. Check the box marked "None" or "Other" as appropriate. If "Other" is specified, explain.

2. Dose Rate - Review the expected dose rate information and assess potential dose rate hazards. Check the box marked "None" or "Other" as appropriate. If "Other" is specified, explain.

3. Reactor Equipment - Verify that no corrosion problems exist.

Verify that no explosive materials or fueled experiments are to be irradiated without Radiation Safety Committee approval. Verify that proper provisions for cooling have been made. Evaluate the experiment with respect to potential hazards to the reactor or reactor operations (for example, detector "shadowing"). Check the box marked "None" or "Other" as appropriate. If "Other" is specified, explain.

Revised By: William Bonzer Approved By: William Bonzer

. * ~ ,') *1 ~

/jJ 0:'.-~kt.rn

• • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rey SOP: 702 TITLE: IRRADIATION REQUEST FORMS Revised: March 31, 2016 Page 5 of 8

4. Other - Evaluate the experiment for any other types of conceivable hazards to personnel or equipment.

b.

c.

Additional Restrictions/Requirements - The reviewers are to specify any additional restrictions or requirements deemed appropriate.

Approvals - Reviewers shall signify approval of the experiment by signing and dating in the appropriate blank. Two signatures are required from either the Director, Manager, SROs, or the Health Physicist.

D. PROCEDURE - SAMPLE IRRADIATION LOG A Sample Irradiation Log will accompany each IRF to document sample irradiation information. An entry shall be made on the Sample Irradiation Log for each sample irradiated.

1.

• Date - Specify the date of the sample irradiation.

2. Sample ID - Specify the sample identification number or name.

3. Experimenter's Name - Provide the name of the experimenter responsible for the sample. *

4. Location - Specify the irradiation location.

5. Power - Specify the power level at which the irradiation is performed.

6. Time In - Specify the console time at which the irradiation began.

7. Time Out - Specify the console time at which the irradiation ended.

8. Total Time - Specify the total time of the irradiation.

Revised By: William Bonzer Approved By: William Bonzer i/V

.\[,ii)/

vt.£14.;-v">

-'")

~<::;;_A-:rv~) I .~**/);j t.,.. ...-~.....

LJL..li~~-Cl/::.--1,....,,

/2 ri

• tJ *~e:""'.---/'**)_.~:l..,..,)

• • MISSOURI S&TREACTOR STANDARD OPERATING PROCEDURES*** Re.v SOP: 702 TITLE: IRRADIATION REQUEST FORMS Revised: March 31, 2016 Page 6 of 8

9. Dose Rate @ 1 foot - Record the 1 foot dose rate from the sample at the time of initial sample handling.

10. Decay Time- Specify the approximate decay time between the end of the irradiation and the time of the dose rate measurement.

11.

• Initials - Either the console operator (licensed operator, student, or trainee) or. the experimenter will provide their initials signifying that sample irradiation iruormation is complete.

Revised By: William Bonzer Approved By: William Bonzer L,,U "'J)li,,;.,,y,

• • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES*** Rev SOP: 702 TITLE: IRRADIATION REQUEST FORMS Revised: March 31, 2016 Page 7 of 8 IRRADIATION REQUEST FORM IRF :# *_ _

1. IRRADIATION REQUEST

a. Sample D e s c r i p t i o n : - - - - - - - - - - - - - - - - - - - - - - - - - - - -

b. Physical Form: _ _ _ _ __ c. Encapsulation ()Poly-Vial ()Other _ _ _ _ _ _ _ __

d. Irradiation Location: () Bare Rabbit () Cad Rabbit ()Beam Port ()Thermal Column

()Other _ _ _ _ _ _ _ _ _ __

e. Irradiation Limits: 1) Power: _ _ _ __ 2) Time: _ _ _ __ 3) Mass: ---~-gm

f. Expected 1 Foot Dose Rate: _ _ _ _mrem/hr Based on: () experience (IRF# _*--~

() calculations (attached)

() completely unknown

g. Expected Reactivity Worth: _ _ _ _ % k/k Based on: ()default

( ) experience (IRF#_ _ __.

()SOP 306 calculations (attached)

() completely unknown

h. Comments: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

i. Request Completed By:--------------~-

2. REVIEW AND APPROVAL

a. Analysis of Potential Hazards:

1. Reactivity ()None ()Other _ _ _ _ _ _ _ _ __

2. Dose Rate ()None ()Other _ _ _ _ _ _ _ _ __

3. Reactor Equipment ()None ()Other _ _ _ _ _ _ _ _ __

4. Other ()None ()Other----------

b. Additional Restrictions/Requirements_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

c. Irradiation Request Reviewed and Approved (two signatures required):

Director _ _ _ _ _ _ _ _ _ Date _ _ _, Manager _ _ _ _ _ _ _ _ _ Date _ __

SRO Date , SRO Date _ __

Health Physicist _ _ _ _ _ _ _ _ _ Date _ _ __

Revised By: William Bonzer /"""",

Approved By: William Bonzer I I /)

t:) ,:S__ ~I -.t\_, .* 3. ).: :J '.',. '. . . . ,*_.(i~I.

~ .._ ~.*;,'--. ,:_ .*~.: . -; .,. ~- -~ )

.-,*,* _ *-,.--..*

• _.. ~;---..:-*0 1 .*

~,

SAMPLE IRRADIATION LOG

=< Page#_ __ ~ (/)

1-1 (I) 0 (I)

<! '"O l"--l*

(/)

Irradiation Information l:::l (I) --..l to Dose Rate p.. 0

.. N

'-< Sample Experimenter's Time Time Total @1 ft Decay Time ~ ~

~

~

f---<

0 (f.J C' ' ,__ Date ID Name Location Power In Out Time (mR/hR) (Approx.) Initials µ (f.J

<"'":. ~ l>-) 0

. -, Pl ,_. . c:::

~-~- sto

('<----

\~ *--~ 0 ~ >--1 ~

,_.... f---< (/.J 1,'* -. l:::l

~', N 0\ >--1 f<l:>

) (I) [-i >--1 1-1

..trJ [g (0J >-=! ;J>

} \

~~

t1 0 y-- """" (f.J

?:!

• ~*' >

~ >--1 s~

Z.o

~ ;J>

'°doES tEJ ""O (f.J trJ

~~

0 >--1

~

>rj 1-1

~~""O Gf'J.

0

~

(I) p_,. '"O to  :~

I (I)

CJ trJ

'-< 0 00

,. 0 c:::

,~.

\

=<

>--+-,

~

...... 00 (f.J

\.:-...,

\------

r~:-..~

8 **

-)(-

to

( __ }

0 i=l 3 N (I) 1-1

(~\)

'~i ~

':g

/\.j

• • • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 801 TITLE: LOG AND LINEAR DRAWER CALIBRATION Revised: March 3 1, 2016 Page 1of4 A. PURPOSE To provide a consistent method for checking the calibration of the Log and Linear drawer which includes Log N, Period, and Power Range.

B. PRECAUTIONS, PREREQUISITES AND LIMITATIONS

1. This procedure is to be performed annually. Rev

2. A second knowledgeable person shall check all cable connections that have been broken and reconnected.

3. Refer to Section 1, "Log and Linear Drawer Calibration" of the Annual Checklist (SOP I Rev 800) for forms to document this procedure.

C. PROCEDURES

a. Open the housings of both the Log and Linear drawer and the Log/Period recorders and clean as necessary. Pay particular-attention to assure air vents are cle(;ll'.

b. 80% High Voltage Rundown

~' 1. Obtain the magnet key from the SRO on duty and have a Licensed Operator raise shim rods 3 inches.

2. Adjust A4R4, on the high voltage card A4, t9 the lower voltage that will cause the Low CIC Voltage Rundown trip to occur.

'i 3. Record the voltage at A4TP1 where the trip had occurred. (200 times the voltage at A4TP1 equals the desired HV)

4. Verify receipt of the visual and audible alarms for Low CIC Voltage. Verify that a rod rundoWn is initiated.

5. Adjust A4R4 to 540V. (200 times the voltage at A4TPT equals the desired HV)

6. Reset the annunciator panel.

7. Remove the magnet key from the console and return it to the SRO on Duty.

Revised By: William Bonzer

. J 4

{J . 0 l/\j ftL-~vYI ~6~.Y 'I

• • • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 801 TITLE: LOGANDLINEARDRAWERCALIBRATION Revised: March 31, 2016 Page 2of4

c. 120% Full Power Rundown

1. Disconnect the 3 detector cables (signal, HV, and CV) at the drawer.

2. Connect- the Keithley 263 pico-amp source to 15 of the Log and* Linear J Rev drawer. Adjust current to 100% full power.

3. Reset annunciator panel.

4. Obtain the magnet key from the SRO on Duty and have a Licensed Operator raise shim rods 3 inches.

5. Slowly increase current to obtain a reading of 120%.

6. Observe from the Linear Power Range digital display when the 120% J Rev rundown occurs.

7. Observe the 120% Full Power rundown and annunciator. Record values.

8. Reset the annunciator panel.

9. Remove the magnet key from the console and return it to the SRO on Duty.

d. Log and Linear Detector/Cable Check - Discharge each cable through a multimeter by connecting the meter probes to the outer shield and center conductor. Use the highest voltage scale and observe the voltage decline to 0 volts. Measure the resistance of the detector cable with an electrometer at 1000 VDC. Record the results. The cables should read about 10 10 ohms. Again discharge the cables with the multimeter.

e. Drawer Alignment - Perform the steps in Section 4.3.1, "Low Voltage Power Supplies" from the Log and Linear drawer equipment manual.

High Voltage/Compensating Voltage Check

1. Measure HV at 16.

2. Adjust A4R4 as needed to measure 540 VDC.

3. Adjust A4R4 to a lower voltage until the non-operate LED turns on and the Low CIC Annunciator panel alarms.

4. Record the HV at 16 that the trip occurred at. .

5. Record the voltage measured from A4TP10-A4TP1.

6. Verify that the keypad non-operate switch LED illuminates. Record. the results.

7. Adjust A4R4 to measure 540 VDC at 16.

8. Reset annunciator panel.

9. Verify and record the non-operate keypad switch LED goes off.

10. Record the HV at 16. The high voltage at 16 should be 540 VDC +/- 1 V.

Revised By: William Bonzer uJ :.,UL.a,l\~/j

• • • 'MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES*** Rev SOP: 801 TITLE: LOG AND LINEAR DRAWER CALIBRATION Revised: March 31, 2016 Page 3 of 4

11. Record the voltage measured from A4TP10-A4TP1.

12. If the Low CIC Voltage trip point needs to be adjusted follow the Log and Linear equipment manual steps 4.3 .2.1 and 4.3 .2.2.

13. Me~sure compensating voltage at J7. Adjust A5R4 to 5.8 Vas needed.

14.

• Record compensating voltage level at J7. The compensating voltage should be 5.8 VDC +/- 1 V.

15. Record voltage at A5TP10-A5TP1.

Log Amplifier Alignment L Connect the Keithley 263 pico-amp source to JS of the Long and Linear Rev drawer. Use the readings from the Keithley 263 pico-amp source for the current settings.

2. Complete in the Log Displays Table of SOP 800 for the listed current levels.

3. If alignment is necessary follow steps 4.3 .3 .1-9 of the Log and Linear equipment manual. Repeat Step 3 following any adjustment in alignment.

Period Alignment

1. Perform Section 4.3 .4, "Period Amplifier" in the Log and Linear drawer equipment manual. These adjustments determine the accuracy of the period. When performing these steps, the following guidance should be used.

a. Set the oscilloscope to read 50 mV/cm (DC mode) and 0.2 sec/cm.

b. Use the single sweep display mode with internal triggering. .

c. Save the ramp using the "save mode". After the ramp has been saved, use the cursor feature to automatically read the voltage change for a time span of about 1 second. (Note: The cursor feature* provides a more accurate measurement than manually reading the scope.) *

2. Complete the Period Displays Table on the Annual Checklist.

• • • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES*** Rev SOP: 801 TITLE: LOGANDLINEARDRAWERCALIBRATION Revised: March 31, 2016 Page 4 of 4 Linear Amplifier Alignment Rev

1. Use the Keithley 263 pico-amp source connected to the Log and Linear drawer atJ5. *

2. Connect the voltage meter to ATPlO-ATPl.

3. Apply the currents listed in the Linear Displays Table of SOP 800 and record the displayed readings. .

4. If the Linear Amplifier circuit needs aligned, follow steps 4.3 .5 .1-3 of the Log and Linear equipment manual.

f. Isolated Outputs - Adjust the zero and span on each isolator, as necessary, for equal inputs and outputs.

g. Keypad Switches - Fill out the Keypad Switch Table by depressing the indicated switch and recording the associated readings.

h. Discharge the detector cables at the connectors and the corresponding jacks at the drawer. Reconnect the detector HV, CV, and signal cables. Have an independent knowledgeable person verify cables are properly connected.

i. The person that performed this calibration procedure shall initial and date that the calibration has been properly completed..

Revised By: William Bonzer Approved By: William Bonzer

• • • MISSOURI S&T REACTOR STA1'IDARD OPERi\TlliG PROCEDURES *** Re SOP: 811 TITLE: FIRE AND SMOKE ALAR.Lvi SYSTEi'Vf Re-vised: August 18, 2015 Page 1 of.1 A PURPOSE To ensure that the fire and smoke alarm system is operable during annual calibrations. Re B. PROCEDURE

1. Inform Nlissouri S&T Police of fire alarm system test.

2. Test emergency power by turning circuit breaker No. 32 in the power panel off.

3. If alarm sounds, replace power supply batteries in the battery box and repeat test

4. Check at least one (1) sensor, such as pull station in front office, to insure the system will operate.

5. Tum circuit breaker No. 32 on.

6. Using a heat and smoke source, check each smoke detector by placing the source Re close to each detector. Acknowledge alarm condition at master station for all detectors.

7. Remove cover of each pull station by turning the .top screw and pull the inside lever of each of the two (2) pull stations. AcknovV:ledge alarm condition at master station.

8. Use Test Filter 6424 Projected Beam Detector sheet iii front of the Beam Detector.

Acknowledge alarm condition at master station.

9. Ensure all alarm conditions are cleared.

Note: Acknowledgment of alarm will consist. of verification of audible and visual alarms aJ;J.d resetting by pressing Signal Silence and Reset/Lamp Test buttons at master station. .

Revised By: Anth~ony Alchin "---/ Approved By: William Bonzer

,f . I'/""

/r...---

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

SOP: 816 MSTRPOWERCALIBRATION Revised: March 31, 2016 Page 1of4 A. PURPOSE To ensure that the power indicated on the linear and log channels is the power generated in the reactor.

B. PRECAUTIONS, PREREQUISITES, OR LIMITATIONS

1. In accordance with Technical Specification 4.2.2(3) all console instruments and I Rev safety system shall be calibrated once each ye~r, not to exceed 15 months.

2. The power generation in the Missouri S&T Reactor is limited by Technical I Rev Specifications to 200 kW. It is, therefore, important that the reactor power is less or, in an ideal case, equal to the power indicated in the reactor control room. The calibration of the power instrnments is performed by the calibration procedure described below. (For more details see the report MSTR/85-i.) Stable Rev atmospheric conditions are helpful for a successful calibration.

C. PROCEDURE

1. Tum on both nitrogen diffusers and the pool lights.

2. Set up pool level measuring equipment. It is recommended that two gauges be used in order to have redundant measurements. (Minimum recommended scale division is 0.001 inches.)

3. After the diffusers have been on for at least 3 0 minutes start to take level readings every 15 minutes. Continue for at least one hour prior to the reactor startup to determine the average pool level drop. Be sure to note accurately the time of each reading., Record also the temperature of the pool water inlet thermocoup l es. I Rev

4. Take the reactor to some intermediate power level, e.g." 20, 30, or 40 kW. Note the time the reactor reaches that power level. After rnnning the reactor at this power for a time tp such that the reactor thermal output is between 30 and 50 kW hr. shut down the reactor and note the shutdown time. For example, it is recommended that the reactor power be chosen 40 kW and the operational time tp 1 hr.

Approved By: William Bonzer

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

SOP: 816 lVISTR POWER CALIBRATION I Rev Revised: March 31, 2016 Page 2of4

5. Once all control rods and magnets are fully inserted, note time and pool level every 15 mi.nutes until level decreases equal the rate of decrease before the power run. During this time also continue to take temperature readings using all reactor thermocouples.

6. Plot the data measured with both relative height gauges such as to construct the time-dependent plot of h, i.e. the relative change in height of the pool water surface before, during, and after the power run. (Use units of cm for the plot ofh.)

7. Determine 6 has shown in the sketch below h (cm)

t. h

-Time .... Time t(cm) at at Power Shutdown r-- tp

-1

8. Calculate the average pool water temperature Tw using the data taken immediately before the beginning-of the power run and after the reactor shutdown. (Use only the inlet temperature readings.)

9. Using Figure 1 and data determined in step 7 and 8 determine the amount of heat Q generated in the reactor during the calibration run. (The fact that the coefficient Revised By: William Bonzer_,-, Approved By: William Bonzer

~-.1

(~~s>v'Z<5.L.:*;

./. -

~...).,,._:-;\..-'~./)

v .

~ ./

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

SOP: 816 MSTR POWER CALIBRATION I Rev Revised: March 31, 2016 Page 3 of 4 of the thermal volumetric expansion is to be taken at the temperature which is 1 K higher than the average pool temperature has already been tciken into account while constr.ucting the plot in Figure 1.)

10. Calculate the reactor power using the relationship p [kW]= Q [kW hr}

tp[hr]

11. It the power indicated on the linear and/or Log N recorder is equal to or greater than the calculated power P by not more than 5% no further action is needed. In any other case the position of the pertinent neutron detector needs to be adjusted so as to satisfy the above condition.

12. After both power channels (linear and log) have been properly adjusted take the I Rev reactor to 200 kW and adjust, if necessary, both safety channels so as to indicate the reactor power of 200 kW.

Revised By: William Bonzer Approved By: William Bonzer

' .u1'.Ji L . L-t......r ;""}'"'1 ~

.\) ..) "" i~

1.::;t~./"?JI,},,.'

• • • MISSOURl S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 816 MSTR POWER CALIBRATION Revised: March 31, 2016 Page 4of4

. --;-*-:*-~:7*:*

.-::~*--~~:::*.:::.;.

Fig)JrG 2. UMRR The.rrnal Output vs. Change in Pool Water Height Revised By: William Bonzer Approved By: William Bonzer

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

SOP: 818 TITLE: FUNCTION TEST OF THE BUILDING SECURITY SYSTElVI Complete Revision: May 27, 2015 Page 1 of2

• A. PURPOSE In accordance with Technical Specification 4.2.2, all console instruments and safety systems will be calibrated once each year not to exceed 15 months.

B. PRECAUTIONS, PREREQUISITES, OR LilVllTATIONS After each item is completed, a second knowledgeable person will check connections (where connections have been broken and reconnected), to ensure that the equipment is corniected and on line. This step is very important because failure to reconnect ~ome of the equipment can cause violations of Technical Specifications if the reactor is operated.

C. PROCEDURE A list of equipment in the form of a checklist on SOP 800 will be used to record the date that each system was checked or calibrated. Procedures listed in the Technical manuals have been reprinted in the form of SOP's. As each piece of equipment is checked or calibrated, it shall be checked off on the checklist to ensure that the list has been completed and to serve as a record of the date when the item was completed.

1. Contact Central Dispatch Inc. at 364-6686 and the Missouri S&T Police at extension 4300 to make them aware of the security testing taking place and for verification of each alarm. Also verify each alarm with the Reactor Managers email and cell phone.

2. Arm the alarm system. After the set delay time is up, release the switch for the security door (dead bolt switch). *

3. After the alarm has been verified, continue to check all non-24 hour alarms.

4. Clear the .alarms and verify that all were received.

5. Do not arm the *security system. Check the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> alarms and no alarms should sound.

6. After the alarm has been verified clear the security system.

Revised By: Craig Reisner Approved By: William Bonzer

~)~ "'

ij"-") i.X-Z.L-CI:_

.() /.) * ..'WI 1-')

.,._,..-[

.I--) -~n *> *

?Y>

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

SOP: 818 TITLE: FUNCTION TEST OF THE BUILDING SECURITY SYSTEM Complete Revision: May 27, 2015 Page 2of2

7. Do not arm the security system. Check the Duress Alarm.

8. After the alarm has been verified clear the security system.

9. Arm the security system. Remove the AC power cord from the building AC power plug-in. This steps checks the back-up battery and no alarms should sound.

10. Plug the AC cord back into the wall receptacle and unarm the security system.

11. Open the doors on the security system panels. After alarm has been verified, close and lock doors, and reset the alarm syste.m.

12. Remove the front cover from the motion detector located at the entrance to the secure area.

13. After alarm has been verified, replace cover, and reset the alarm.

14. Repeat steps 12 and 13 on the remaining motion detectors.

15. After the alarm has been verified clear the security system.

16. Using either the intermediate or be9Ili room RAM modules, cause a High Radiation alarm to sound.

17. After alarm has been verified, reset the annunciator panel.

18. Using the battery test switch, test the unit battery.

19. Check all the door tampers by removing covers or cover plates on doors.

20. Complete checklist in SOP 800, step 10.

Revised By: Craig Reisner Approved By: William Bonzer epr~ ...-/1;.

~ j &'

w 1 '

.JLJLi,~.....,,. j :51vJ4J