ML18165A398

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Missouri s & T Reactor - Submittal of Annual Progress Report 2017-2018
ML18165A398
Person / Time
Site: University of Missouri-Rolla
Issue date: 06/12/2018
From: Reisner C
Missouri S & T Reactor
To:
Document Control Desk, Office of Nuclear Reactor Regulation
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Download: ML18165A398 (115)
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An equal opportunity institution MISSOURI .!

S&T I I* r t,

Missouri S & T Reactor 250 West 13 th St, Rolla, MO 65409-0450 (573)341-4236 I reactor@rnst.edu I reactor.rnst.edu

Dear Sir:

Please find enclosed the Annual Progress Report 2017-2018 for the Missouri University of 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 Trailforos.

z:r Sincerely, Interim Reactor Manager Enclosure Cc: Mr. Spyros Trailforos (NRC)

Document Control Desk (NRC)

Dr. Joseph Graham, Reactor Director (S&T)

Dr. Christopher Maples, Interim Chancellor (S&T)

Cuba Plain, Interim Vice Chancellor (S&T)

Ted Ruth, Asst. Vice Chancellor (S&T)

Dr. Richard Wlezein, Vice Provost and Dean (S&T)

Dr. Braden Lusk, Chair of Mining and Nuclear Eng. (S&T)

Dr. Hyoung Lee, Associate Chair of Mining and Nuclear Eng. (S&T)

Dr. Mark Fitch, Chairman, radiation Safety Committee (S&T)

Michelle Bresnahan, radiation Safety Officer (S&T)

Andrew Careaga, Executive Director of Marketing & Communications (S&T)

MSTR PROGRESS REPORT FOR THE MISSOURI UNIVERSITY OF

  • *
  • SCIENCE AND TECHNOLOGY REACTOR
  • *
  • June 12, 2018

PROGRESS REPORT FOR THE MISSOURI UNIVERSITY OF SCIENCE AND TECHNOLOGY NUCLEAR REACTOR FACILITY April 1, 2017 to March 31, 2018 Submitted to The United States Nuclear Regulatory Commission And Missouri University of Science and Technology

I TABLE OF CONTENTS List of Tables ........................................................................................................................................................................ II List of Figures ....................................................................................................................................................................... II Summary..............................................................................................................................................................................III 1.0 Introduction ..................................................................................................................................................................... 1 1.1 Background Information ............................................................................................................................................... 1 1.2 General Facility Status .................................................................................................................................................. 2 2.0 Reactor Staff and Personnel........................................................................................................................................... 4 2.1 Reactor Staff ................................................................................................................................................................. 4 2.2 Licensed Operators ....................................................................................................................................................... 5 2.3 Radiation Safety Committee ......................................................................................................................................... 6 2.4 Health Physics ............................................................................................................................................................... 6 3.0 Reactor Operations ......................................................................................................................................................... 7 4.0 Educational Utilization ................................................................................................................................................. 14 5.0 Reactor Health Physics Activities ................................................................................................................................ 16 5.1 Routine Surveys .......................................................................................................................................................... 16 5.2 By-Product Material Release Surveys ........................................................................................................................ 16 5.3 Routine Monitoring ..................................................................................................................................................... 16 5.4 Waste Disposal ............................................................................................................................................................ 17 5.5 Instrument Calibrations ............................................................................................................................................... 18 6.0 Plans ............................................................................................................................................................................... 19 6.1 Reactor Documentation............................................................................................................................................... 19 6.2 Replacing Control Room Equipment .......................................................................................................................... 19 6.3 Reactor Operator Training .......................................................................................................................................... 20 Appendix: Standard Operating Procedures Changed During the 2017-2018 Reporting Year ........................................... 21

II LIST OF TABLES Table 3-1: Core 122, 124 through 128 Technical Data ...................................................................................................... 7 Table 3-2: Unplanned Shutdowns ..................................................................................................................................... 11 Table 3-3: Maintenance ...................................................................................................................................................... 12 Table 3-4: Reactor Utilization............................................................................................................................................ 13 Table 3-5: Experimental Facility Usage ............................................................................................................................ 13 Table 4-1: Missouri S&T Classes at Reactor Facility ...................................................................................................... 14 Table 4-2: Reactor Sharing Program ................................................................................................................................ 15 LIST OF FIGURES Figure 3-1: MSTR Core 122 Configuration........................................................................................................................ 8 Figure 3-2: MSTR Core 124 Configuration........................................................................................................................ 8 Figure 3-3: MSTR Core 125 Configuration........................................................................................................................ 9 Figure 3-4: MSTR Core 126 Configuration........................................................................................................................ 9 Figure 3-5: MSTR Core 127 Configuration...................................................................................................................... 10 Figure 3-6: MSTR Core 128 Configuration...................................................................................................................... 11

III

SUMMARY

During the 2017-2018 reporting period, the Missouri University of Science and Technology Reactor (MSTR) was in use for 354.37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />. The major part of this time, about 92%, 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 (S&T) courses and operator training over the year for a total of 2,851.7 student-hours. The reactor was visited by 590 visitors during the past year. There were 357 visitors that participated in labs at the reactor.

The reactor produced 16,883.63 kilowatt-hours of thermal energy using approximately 0.739 grams of uranium. A total of 364 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, 2017 to March 31, 2018.

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 MSTR 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 reactors design. The reactor is a light water, open pool reactor cooled by natural convective flow. The initial licensed power was 10 kW. The licensed power was up-graded to 200 kW in 1966. The MSTR fuel is MTR plate-type fuel that was changed from high-enriched uranium to low-enriched uranium fuel during the summer of 1992. The MSTR license was renewed for another 20 years in March of 2009.

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 gamma spectroscopy capabilities. The gamma spectroscopy system includes germanium and sodium-iodide detectors, associated electronics, state-of-the-art data acquisition and spectrum analysis equipment. Additionally, there is a liquid scintillation counter, thermoluminescent dosimeter reader, and x-ray imager for student and faculty to use.

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.

In August, 2017, the Electronics Technician, Anthony Alchin, replaced the Yokogawa temperature and constant air monitor (CAM) digital recorders with chart paper to Yokogawa digital chart recorders. A detailed 50.59 review was submitted to the S&T Radiation Safety Committee for review and there were no concerns or request for changes. The new equipment is performing as expected and saving the reactor money in recorder chart paper.

The S&T Police, campus Environmental Health and Safety department and MSTR staff worked on a new Emergency plan. In August, 2017, the plan was released and training was conducted in January of 2018.

In September of 2017, the restricted area outside the mid-level basement door was completed. The reason for extending the restricted area is to reduce radiation exposure to the public in an unrestricted area.

On October 2-4, 2017, the Nuclear Regulatory Commission (NRC) conduct an inspection at the MSTR.

The inspection covered the following areas: procedures; experiments; health physics; design changes; committees, audits and reviews; and transportation. The MSTR was found to be compliant with current NRC requirements and MSTR Technical Specifications. The inspector complemented the Electronics Technician, Anthony Alchin, on the preparation of the 10 CFR 50.59 review for the digital recorder and suggested posting the radiation surveys for people to see.

An independent auditor from the University of Missouri Research Reactor (MURR) audited the reactor facility on December 6, 2017. The audit cited an improvement in the written entries in to the Control Room Permanent Log Book, posting the current Health Physics surveys, and upgrading the dosimetry for visitors.

There is an agreement between MSTR and MURR to audit each other on an annual basis. This has been a very beneficial arrangement for both facilities involved.

3 In November, 2017, three students took the NRC licensing examination. Two students passed their Reactor Operator Exam.

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. The reactor is used mainly by the Nuclear Engineering Department for classes and research. The Reactor Lab II class reaches out to other departments on campus for collaboration projects. The reactor is working on resurrecting the reactor outreach program that was started in 1990 but has declined over past years.

Much effort has been invested over the past year in revising SOPs for going to an all-digital format. The pre-startup check list, hourly log, secure check list and weekly checklist have all been converted to digital format. All documentation is digitally available to all licensed operators in the control room. The following is a list of SOPs revised during the reporting period:

SOP 102 Pre-Startup Checklist Procedures SOP 105 Reactor Shutdown and Reactor Securing Procedures SOP 106 Restart of Reactor when not It is not Secured SOP 107 Permanent Log, Hourly Log, Operational Data SOP 150 Response to Alarms SOP 151 Response to High Area Radiation Alarm SOP 310 10 CFR 50.59 Changes, Tests, and Experiments SOP 501 Emergency Procedures for Reactor Building Evacuation SOP 502 Emergency Procedure for an Unusual Event SOP 503 Emergency Procedure for Alert SOP 504 Emergency for a Site Area Emergency SOP 505 Enhanced Reactor Security SOP 506 Bomb Threat SOP 507 Emergency Procedures-Administrative Responsibilities SOP 508 Tornado Threat SOP 509 Fire SOP 510 Earthquake SOP 511 Response to Missing Special Nuclear Material SOP 601 Handling of Radioactive Samples SOP 602 Entry Into a High Radiation Area SOP 800 Annual Checklist SOP 810 Weekly Check

4 2.0 REACTOR STAFF AND PERSONNEL 2.1 Reactor Staff Name Title Dr. Hyoung-Koo Lee Reactor Director Dr. Joseph Graham1 Reactor Director Mr. William Bonzer5 Reactor Manager & Senior Reactor Operator Mr. Craig Reisner1 Senior Reactor Operator / Interim Reactor Manager Mr. Anthony Alchin Electronic Technician II & Senior Operator Ms. Maureen Henry4 Officer Support Assistant III Ms. Nhi Ma Reactor Staff (Part-Time)

Ms. Alice Skye2 Reactor Staff (Part-Time)

Ms. Laura Pirrone3 Reactor Operator (Part-Time)

Mr. Keith Kellett3 Reactor Operator (Part-Time)

1. Effective Date: November 2017
2. Effective Date: September 2017
3. Effective Date: February 2017
4. Retirement Date: December 2017
5. Retirement Date: January 2018

5 2.2 Licensed Operators Name License William Bonzer Senior Operator Craig Reisner Senior Operator Anthony Alchin Senior Operator Jonathan Scott1 Reactor Operator Andrew Albert Bingham1 Reactor Operator Steve M. Wagstaff1 Reactor Operator Jacob Stueck2 Reactor Operator Kelly Jacobs2 Reactor Operator Philip Rexing2 Reactor Operator Laura Pirrone Reactor Operator Alexander Watson2 Reactor Operator David Clark2 Reactor Operator Keith Kellett3 Reactor Operator Nicholas Allen3 Reactor Operator

1. Termination Date: December 2016
2. Termination Date: September 2017
3. Effective Date: March 2018

6 2.3 Radiation Safety Committee The Radiation Safety Committee meets quarterly. The committee met on 6/29/2017, 9/15/2017, 12/12/2017 and 3/07/2018 during the reporting period. The committee members are listed below.

Name Department Dr. Mark Fitch Civil Engineering Ms. Michelle Bresnahan Environment Health and Safety Services Dr. David Wronkiewicz Geological Sciences & Geology Dr. Shoaib Usman Mining & Nuclear Engineering Dr. Fadha Al Falahi Environmental Health and Safety Services Dr. Yue-Wern Huang Biological Sciences Dr. Carlos Castano Mining & Nuclear Engineering Dr. Amitava Choudhury Chemistry Mr. Tony Hunt Environmental Health and Safety Services Dr. Muthanna Al-Dahhan Chemical and Biological Engineering Dr. Joseph Graham Mining & Nuclear Engineering Mr. Craig Reisner 1 Nuclear Reactor Mr. William Bonzer4 Nuclear Reactor Mr. Randy Stoll2 Business Services Mr. John Mollenkamp3 Business Services Mr. Anas Massri5 Fiscal Services

1. Joined the committee on November 2017
2. Retired from the committee on May 2017
3. Retired from the committee on August 2017
4. Retired from the committee November 2017
5. Joined the committee on May 2017 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.

Name Title Ms. Michelle Bresnahan Director of Environmental Health and Safety Mr. Tony Hunt Assistant Director of Environmental Health and Safety Dr. Fadha Al Falahi Health Physicist and Laser Safety Officer Mr. Alex Swearingen Health Physics Technician (part-time)

Ms. Jenna Slocum Health Physics Technician (part-time)

Mr. Brandon Ochterbeck Health Physics Technician (part-time)

7 3.0 REACTOR OPERATIONS Core designation 128W is presently in use. The W mode core is completely water reflected and used for normal operations and beam port operations. The T mode (core positioned near graphite thermal column) may be used for various experiments and thermal column experiments.

Table 3-1 presents pertinent core data for the core designations 124 to 128. Figure 3-1 to 3-5 shows the core configuration for each core designation. The excess reactivity, shutdown margin, and rod worths were measured for all core designations during January and February of 2018. The measurements were taken in both T and W mode with reference core conditions.

Tables 3-2 and 3-3 present a listing of unscheduled shutdowns (scrams, rundowns, and unplanned normal shutdowns) along with their causes and corrective actions.

Maintenance activities are listed in Table 3-4. Table 3-5 shows facility use other than the reactor and Table 3-6 shows reactor utilization.

Table 3-1. Core 122, 124 through 128 Technical Data Rod #1 Rod #2 Rod #3 Reg. Rod Shutdown Excess Core Mode

%k/k %k/k %k/k %k/k Marin %k/k Reactivity%k/k W 3.958 3.239 1.778 0.232 4.377 0.640 122 T 4.100 3.160 1.975 0.262 4.116 1.019 W 4.0061 3.2549 1.8959 0.2717 4.795 0.3553 124 T NA NA NA NA NA NA W

125 Not enough reactivity to calculate rod worths or SDM----could not achieve criticality T

W 2.605 2.199 2.09 - 3.121 1.167 126 T NA NA NA NA NA NA W-b 2.378 2.202 2.054 - 3.7774 0.4790 127 W-a1 2.4833 2.2023 2.1115 0.525 3.799 0.7227 W 2.6066 2.2023 2.1376 0.5159 3.7455 0.5944 128 T 2.6416 2.1444 2.1374 0.5630 0.6522 3.6296 1 A power calibration was performed between collecting data for the 127W cores

8 Key to Prefixes for Core Configuration F Full Element C Control Element HF Half Front Element HR Half Rear Element IF Irradiation Fuel Element BRT Bare Rabbit CRT Cadmium Rabbit HC Hot Cell Rabbit S Source A

B S C C4 F5 F11 F17 D F4 F8 F14 C1 F10 F1 E F9 C3 F12 C2 F7 F3 F CRT F15 HC F13 BRT F6 1 2 3 4 5 6 7 8 9 Figure 3-1. MSTR Core 122 Configuration A

B S C C4 F6 F11 F8 D F10 F17 F3 C1 F4 F12 E F9 C3 F12 C2 F7 F3 F CRT F15 HC F13 BRT F6 1 2 3 4 5 6 7 8 9 Figure 3-2. MSTR Core 124 Configuration

9 A S B HR1 HR2 C F4 C4 F17 C1 F5 D F16 F13 F11 F14 F18 E F8 C5 F15 C2 F9 F CRT HF1 HC HF2 BRT 1 2 3 4 5 6 7 8 9 Figure 3-3. MSTR Core 125 Configuration A S B HR1 IF1 HR2 C F4 C4 F17 C1 F5 D F16 F13 F11 F14 F18 E F8 C5 F15 C2 F9 F CRT HF1 HC HF2 BRT 1 2 3 4 5 6 7 8 9 Figure 3-4. MSTR Core 126 Configuration

10 A S B F2 HR2 C F4 C4 F17 C1 F5 D F16 F13 F11 F14 F18 E F8 C5 F15 C2 F9 F CRT HF1 HC HF2 BRT 1 2 3 4 5 6 7 8 9 Figure 3-5. MSTR Core 127 Configuration A S B HR2 F2 C F4 C4 F17 C1 F5 D F16 F13 F11 F14 F18 E F8 C5 F15 C2 F9 F CRT HF1 HC HF2 BRT 1 2 3 4 5 6 7 8 9 Figure 3-6. MSTR Core 128 Configuration

11 Table 3-2: Unplanned Shutdowns Date Type of Rundown, Cause and Corrective Action Taken 10/09/2017 Type: 120% Demand Rundown Cause: Student Operator did not depress range switch enough for it to latch and it popped out Corrective Action Taken: the Student was instructed to firmly depress the range switch 2/05/2018 Type: 120% Demand Rundown Cause: Student failed to Upscale at 60 Linear Channel Corrective Action Taken: Reactor Operator talked to the licensed operator and was told to watch the instrumentation more attentively 2/09/2018 Type: 120% Full Power Rundown Cause: Log and Linear Channel detector read greater than 10% discrepancy with Linear Channel Corrective Action Taken: Detector calibrations were made 2/28/2018 Type: Regulating Rod insert limit on Auto Cause: Linear Recorder was stuck Corrective Action Taken: Maintenance was performed on the Linear Recorder 3/06/2018 Type: 120% Demand Rundown Cause: Student did not depress range switch on Linear Drawer hard enough for it to stay in Corrective Action Taken: The student was instructed to firmly depress the range switch Type of Scram, Cause and Corrective Action Taken There were no Scrams

12 Table 3-3: Maintenance Date Type of Maintenance 4/11/2017 Issue: Start-up channel not operable Corrective Action: Fission chamber was removed from the core and pool and rewired. Fission chamber was inserted into the pool.

4/14/2017 Issue: Regulating Rod was unresponsive. Servo Drive indicated a fault.

Corrective Action: Upon further inspection of the Servo Drive, it was found to be in working condition. However, during some troubleshooting, it was discovered that the Servo Motor was the faulty part. The Servo Motor in the Regulating Rod was replaced with a spare and the Rod was responsive to our actions. Rod heights and speed test were done on the Regulating Rod and was completed satisfactory.

4/21/2017 Issue: CIC and Safety Channel UIC percentages needs to be adjusted.

Corrective Action: Linear CIC adjusted from 20% to 23%, Log n Linear CIC adjusted from 45.8%

to 50.2%, UIC Safety Channel #1 adjusted from 48.5% to 50.1%, and UIC Safety Channel #2 adjusted from 45.0% to 50.6%

6/13/2017 Issue: Beam Port Annunciator activated and the green close light was turned off, beam port unable to be opened.

Corrective Action: Replaced the light on the green close switch as it was blown, but this did not solve the issue. Checking the fuses shown that they were also blown. The fuses were replaced and test on the beam port were done. The lights and annunciator came on as expected and the flashing light to indicate the beam port is open came on. The initial cause is unknown but is believed to be a power surge.

7/13/2017 Issue: CAM was discovered to not read anything except for 30cps. The meter was stuck.

Corrective Action: The G-M detector was inspected and appeared to be in good condition. Put the CAM in a test resulted in the high alarm going off but the meter did not move. The meter was taken off and placed on a current source. The current source was ramped up and the meter suddenly went off scale. Stepping the current down, the meter began to respond as expected with the lowering and rising current. The meter was returned to the CAM. A source was placed near the G-M detector and proper meter response was observed.

2/21/2018 Issue: Fission Chamber was non operable.

Corrective Action: Fission Chamber was removed from the core and pool. It was discovered that a cable was ruined and needed to be fixed. The fission chamber was inserted into the core the next day.

13 Table 3-4. Reactor Utilization

1. Reactor use 354.37 hrs.
2. Time at power 237.07 hrs.
3. Energy generated 16883.63 kWhrs.
4. Total number of samples, neutron irradiated 367
5. U-235 Burned 0.739 g
6. U-235 Burned and Converted 0.872 g Table 3-5. Experimental Facility Usage Facility Hours Bare Rabbit Tube 32.90 hrs.

Cadmium Rabbit Tube 0.0 hrs.

Beam port 4.17 hrs.

Thermal Column 0.0 hrs.

Other Core Positions 12.10 hrs.

Hot Cell 0.0 hrs.

Gamma Exposures 766.4 hrs.

Total 815.57 hrs.

14 4.0 EDUCATIONAL UTILIZATION The reactor facility supported 11 Nuclear Engineering courses in the past year for a total of 300 students and 1920.6 student-hours. The reactor supported 14 graduate students for total of 718.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and Reactor Operator Training for six students for 213 hours0.00247 days <br />0.0592 hours <br />3.521825e-4 weeks <br />8.10465e-5 months <br />. The MSTR was able to provide financial support for two student workers with hourly wages and have two students from the S&T work study program. The reactor supported tours from six teaching institutions, 4 camps and 3 non-Nuclear tours for total of 692 tour-hours.

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

Table 4-1 Missouri S&T Classes at Reactor Facility Time at

  1. of Student Semester Class Number/Title Reactor Students Hours (hrs.)

SP 2017 NE 1105: Nuclear Technology Applications 18 1.75 15.25 SP 2017 NE 2406: Reactor Operations I 20 6.0 100.0 NE 4312: Nuclear Radiation Measurements and SP 2017 44 4.0 81.5 Spectroscopy SP 2017 NE 4438: Reactor Laboratory II 16 75.5 388.75 FS 2017 NE 1105: Nuclear Technology Applications 41 4.9 104.5 FS 2017 NE 2406: Reactor Operations I 20 17.5 312.0 FS 2017 NE 4428: Reactor Laboratory I 34 22.35 284.1 SP 2018 NE 1105: Nuclear Technology Applications 19 3.0 55.0 SP 2018 NE 2406: Reactor Operations I 28 13.25 371.0 NE 4312: Nuclear Radiation Measurements and SP 2018 40 4.0 76.0 Spectroscopy SP 2018 NE 4438: Reactor Laboratory II 20 72.75 132.5 The Reactor Sharing Program was a funded project by the U.S. Department of Energy to establish awareness and share education about the nuclear field beyond the campus. The program was established 1990 and is still in place at the MSTR. This past year, more than 590 students, instructors and public guest visited the

15 MSTR facility for total of 882 hours0.0102 days <br />0.245 hours <br />0.00146 weeks <br />3.35601e-4 months <br />, 357 of them participated in some kind of lab in the reactor bay. New this year, professors from Nuclear Engineering started bring future students to the reactor for departmental tours.

Table 4-2 lists those schools and groups that were involved in this years program that are not part of S&T Nuclear Engineering Department. The majority of participants were high school students. 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.

Table 4-2 Reactor Sharing Program DATE EVENT VISITORS TIME (hrs.)

4/25/2017 Rolla High School 14 0.5 4/27/2017 Mountain Grove HS 7 1.3 5/1/2017 Econ 4540: energy Economics 6 0.5 5/4/2017 East Central college 13 2.5 5/11/2017 MEGSSS 5 1.0 5/18/2017 S&T Student Health 4 0.8 6/13/2017 Jackling Camp 14 1.8 6/15/2017 Jackling Camp 30 1.5 6/19/2017 Nuclear Engineering Camp 22 2.0 6/27/2017 Jackling Camp 18 1.5 6/29/2017 Jackling Camp 26 1.5 7/11/2017 Jackling Camp 24 1.5 7/13/2017 Jackling Camp 28 1.5 7/21/2017 Fort Lenard Wood 29 3.0 9/21/2017 ANS Blue Glow 35 1.5 10/18/2017 RTI Tour 14 1.0 11/4/2017 University of Illinois 9 16 11/16/2017 East Central college 12 1.5 1/3/2018 Missouri State Highway Patrol 4 1.5 2/28/2018 SPS Blue Glow 15 1 3/10/2018 Boy Scouts 21 1.5 3/24/2018 Boy Scouts 15 1.0

16 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 were 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 Thirty-four reactor facility personnel and students involved with the operations in the reactor facility are currently assigned Mirion Technologies, Thermoluminescent dosimeters (TLDs). Three of the Reactor Staff have beta, gamma, neutron dosimeters with three TLD rings and five area dosimeters which are 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,

17 gamma neutron dosimeters that are read monthly. The remaining dosimeters are read monthly. In addition, seven digital, direct-reading dosimeters are used for visitors and high radiation work. There have been no significant personnel 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 2017 through March 2018 sample concentrations averaged 1.3x10-5 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 100,600 µCi of Ar-41 was released into the air.

5.4 Waste Disposal Solid waste, including 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 two containers of waste picked up from the reactor facility. One five gallon bucket of mixed solid waste was picked up from the reactor building on 6/1/2017 and one fifty five gallon barrel of solid waste was picked up on 2/6/2018.

18 5.5 Instrument Calibrations During this period, portable instruments and area monitors were calibrated annually. Thirteen meters were calibrated on 9/18/2017, with the next calibration due in September 2018. Eight meters were calibrated on 3/15/2018, with the next calibration due in March 2019.

19 6.0 PLANS The reactor staff will be involved in four major undertakings during the next reporting period: 1) updating the reactor documentation, specifically the SAR and SOP, 2) replacing control room equipment, 3) expanding research to outside companies and other departments and 4) continuation of the reactor operator training program.

6.1 Reactor Documentation The SAR is in need of updates. In the past 6 years the reactor has undergone several changes that have not been corrected in the SAR. The control room upgrades and chiller upgrades are two of those projects.

The SOP are in the process of being updated with new university name and additional minor changes and corrections. The SOPs that are checklists have been reformatted into fillable PDF files with electronic signatures.

6.2 Replacing Control Room Equipment A process of replacing individual control room instrumentation started in 2017 with the Temperature and CAM recorder. Equipment to be replaced will be selected on a priority basis of what needs replaced and scope of project. Control room equipment replacement will have a thorough analysis of a 10 CFR 50.59 review process. The reactor staff will present the completed 10 CFR 50.59 review to the Radiation Safety Committee as required by MSTR Technical Specifications. The upgrades are for going to paperless recorders.

20 6.3 Reactor Operator Training The MSTR had two students obtain their license of Reactor operator. The reactor staff is limiting operator training to only 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, six students were training for an operators license to take in the fall of 2018.

21 Appendix

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

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Revision: Page 1 of 8 A. PURPOSE:

The purpose of the checklist is to verify that reactor systems are operating correctly prior to reactor start-up.

B. PRECAUTIONS, PREREQUISITES, OR LIMITATIONS:

1. A licensed operator shall be responsible for performing the pre-startup checklist. The operator may assign various steps to be completed by unlicensed personnel; however, the operator is still fully responsible for the proper performance of the checklist and is to directly supervise the unlicensed personnel.
2. The checklist shall be completed prior to the first reactor start-up of the day. The checklist shall be completed prior to a reactor start-up or after a "Secure" checklist has been completed.
3. After each step on the checklist is performed, the operator will record the readings observed, or in cases where no readings are required, will simply check the appropriate blank on the form.
4. Any malfunction or abnormality identified during performance of the checklist shall be immediately reported to the SRO on Duty, and corrected as necessary before completion of the checklist.
5. The following steps will list the Shim/Safety Rods as rods and the Regulating Rod as reg rod.

C. PROCEDURE

Complete the checklist in accordance with the following steps:

1. Date - Record the date by digitally signing with the Date Stamp format or with rubber stamp.
2. Initials - Record the initials of the person performing the checklist.
3. Time - Record the time shown on the console clock.
4. Core Loading - Enter core loading number and mode.
5. Verify that the P.A. system is operable. Turn on the bridge intercom and video monitor.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Revision: Page 2 of 8

6. RAM System Check:
a. Announce, "THE BUILDING ALARM WILL SOUND. THIS IS A TEST. DO NOT EVACUATE THE BUILDING."
b. Check that the setpoints and automatic functions of the RAM systems meet the criteria listed below. For each High Radiation Alarm, verify that both the audible alarm and the visual annunciator are actuated. Reset the RMS II module within ten seconds after trip occurs. Reset the annunciator panel after each High Radiation Alarm check.

CHANNEL SETPOINT AUTOMATIC ACTION

1. Bridge RAM 10 - 18 mR/hr High Radiation Alarm
2. Bridge RAM 15 - 28 mR/hr Building Evacuation Alarm
3. Demin RAM 10 - 18 mR/hr High Radiation Alarm
4. Basement RAM 10 - 18 mR/hr High Radiation Alarm
c. Announce, "TEST COMPLETE, ACKNOWLEDGE ALL FURTHER ALARMS".
7. Verify that all monitors (Bridge, Demin, Basement, and Neutron RAM) read below 2 mrem/hr.
8. CAM: Verify the CAM is operable by observing a normal reading (~50 - 800 cpm) on the CAM recorder.
9. Beam Port Status: Record the status of the beam port ("open" or "shut") as indicated by
1) the "Beam Port or Thermal Column Open" annunciator light and 2) the Beam Port Indication light. Notify the SRO on Duty if beam port is "open".
10. Linear Channel:
a. Depress the zero check button; verify that the digital display reads ".0000".
b. Depress the zero check button again to release the check function.
c. Set the Linear compensating voltage to obtain a Linear reading between 0.02 and 0.05 on the 2 W scale. Following a high power run, the SRO on Duty may adjust the Linear compensating voltage as appropriate.
d. Record the Linear reading. Record the scale.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Revision: Page 3 of 8

11. Linear CIC Voltage: Record the high voltage (HV) and compensating voltage (CV) settings of the Linear power supply. Read the CV setting by depressing the meter range switch and multiplying the meter reading by 0.1. Record to the nearest tenth of a volt.

Values should correspond approximately to the following:

HV ~ 540 VDC CV ~ 2 to 8 VDC

12. a. Observe the Temperature/CAM recorder is operable, the green is illuminated in the top center of the display, and the CF Card is not almost full indicated by a red located after the remaining sample time left at the top of the display.
b. Turn on and date the Startup, Linear, and Log/Period recorders. Reset the annunciator panel.
13. Core Check: Turn the pool lights on.
a. Record water level of pool.
b. Visually verify all fuel elements in the core and fuel storage rack are accounted for.
c. Visually inspect the core, pool floor and walls, beam port, thermal column and bridge for abnormalities and degradation.
d. Check for in-core experiments.
e. Notify the SRO on Duty of abnormalities, degradation or in-core experiments are observed.
f. Insert the source into the core source holder.
14. Start-Up Channel Test: Turn the Log Count Rate selector switch to 102, 103, and 104.

Verify that the meter and recorder follow. Return the selector switch to the "OPERATE" position.

15. Verify Fission Chamber Response: Insert the fission chamber until the green Insert Limit light comes on. Observe the count rate. Raise the fission chamber until the count rate shows a definite decrease. Verify that the 2 cps alarm trips at a count rate greater than or equal to 2 cps. Insert the fission chamber to insert limit. Verify that the count rate is greater than 2 cps. (Following a high power run, the SRO on Duty may position the fission chamber as desired as long as a count rate greater than 2 cps is maintained.)
16. Observe the Log Count Rate H.V. power supply setting is positive 400 VDC. If setting is different then notify the SRO on Duty.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Revision: Page 4 of 8

17. Log and Power Range Test:
a. Depress and hold the 10pA keypad switch on the Log and Linear drawer to obtain a stable digital log power display.
b. Verify receipt of the "Non-Operative" scram and "Low CIC Voltage" rundown audible and visual alarms.
c. Verify that the digital meter and recorder read within the tolerances of the following table. The bargraph should generally follow the digital display and recorder.

Keypad Switch Log Scale (%) Power Range (%)

10 pA 1.0E-52.lE-5 0 - 1%

0.1uA 9.3E-21.9E-1 0 - 1%

1mA 9.l E ll.9E2 90 - 125%

d. Release the switch and reset the annunciator board.
e. Repeat Steps a. through d. for the 0.1 uA and 1 mA switches.
18. Period Response Test:
a. Depress and hold the 3 SEC keypad switch.
b. Verify receipt of the "Non-Operative" scram and "Low CIC Voltage" rundown audible and visual alarms.
c. Verify that the Period bargraph, digital meter, and recorder all read 3.0 seconds.
d. Verify that the 30 second, 15 second, and 5 second period annunciator alarms are actuated.
e. Release the switch. Clear the annunciator panel.

19 Turn on the magnet power using the key switch. Push the Scram Reset button to energize the magnets. Reset the annunciator panel.

20. Record inlet temperature. Notify the SRO on Duty if the inlet temperature is below 60oF.
21. 150% Power Scram Check:
a. Withdraw rods to 3 inches.
b. Depress the test button on Safety Amplifier 1.
c. Verify that a scram occurs before 150%.
d. Verify that the 150% Full Power annunciator light and the audible alarm are activated.
e. Record the trip test reading displayed on Safety Amplifier 1.
f. Depress the reset button on Safety Amplifier 1.
g. Reset the annunciator panel and insert magnets.
h. Repeat steps a - g for Safety Amplifier 2.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Revision: Page 5 of 8

22. Log and Linear Drawer Non-Operative Scram and Rundown Test:
a. Withdraw rods to 3 inches.
b. Depress the NON-OPER keypad switch. Check for the Non-Operate Scram and Low CIC Voltage Rundown visual and audible alarms.
c. Verify that the rods have dropped and rod drives are running down.
d. Try to stop the rundown by turning the control rod lever switch to insert.
e. Stop the rundown with the rundown reset button.
f. Reset the scram, rundown, and annunciator panel.
23. Period Trip Test:
a. Withdraw rods to 3 inches.
b. Depress and hold the PERIOD TEST keypad switch. Verify that the 30 Second Rod Withdrawal Prohibit annunciator is activated with a simulated period greater than or equal to 30 seconds. Acknowledge annunciator panel.
c. Continue depressing the PERIOD TEST keypad switch. Verify that the 15 Second Rundown is activated with a simulated period greater than or equal to 15 seconds.

Acknowledge annunciator panel.

d. Continue depressing the PERIOD TEST keypad switch. Verify that the 5 Second Scram is activated with a simulated period greater than 5 seconds by observing a loss of magnet current and the annunciators.
e. Release the switch.
f. Reset the scram, rundown, and annunciator panel.
24. Manual Scram:
a. Raise rods to 3 inches.
b. Push the manual scram button. Verify that the rods have dropped by visually observing the video display.
c. Push the scram reset button and reset the annunciator panel.
25. Push the annunciator test button and check for burned out bulbs. Replace any burned out bulbs. Reset the annunciator panel.
26. Verify that the magnets are on and that all rods are on insert limit.
27. Prepare hourly checklist and permanent log.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Revision: Page 6 of 8

28. Detector Response Check:
a. Inspect the core. Make certain core cooling is clear and experiments are firmly secured.
b. "Spike" the Log and Linear Channel CIC and the Linear Channel CIC by positioning the neutron source next to the detectors.
c. Insert the source into the holder.
d. Observe the Log/ Period and the Linear recorder traces to verify proper response to the source spike.
e. Observe the Startup Channel recorder to verify that the recorder responded properly with a decreased count rate when the source was moved away from the core.
f. Reset the annunciator panel.
29. Raise the rods to 6 inches. Record the time on both the checklist and in the permanent log.
30. Nitrogen Diffusers Status: Turn on nitrogen diffuser pumps as desired. Record status of pumps as "ON" or "OFF". (Note: At least one pump should be turned on for operations in excess of 20 kW.)
31. Record the intended power level.
32. Announce, "The Reactor Will Be Started and Taken to a Power of _____ Watts".
33. Review the Pre-Startup Checklist. Verify that all of the steps have been completed.

The licensed operator responsible for performing the checklist will initial the checklist thus verifying that it has been properly completed.

34. The SRO on Duty will announce The SRO on Duty is ________ and licensed operator in the control room is ________.
35. SRO on Duty name displayed in the control room.
36. The SRO on Duty will initial the checklist verifying that all items have been completed and any problems identified have been satisfactorily resolve.
37. Record the date by digitally signing with the Date Stamp format or with rubber stamp.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Revision: Page 7 of 8 1.Date

2. Initials of the Person Performing Checklist
3. Time (Console Clock)
4. Core Loading
5. P.A., Intercom, Video Monitor On
6. RAM System Check
7. Radiation Level Normal
8. CAM Operable
9. Beam Port Status (OPEN or SHUT)

Zero

10. Linear Channel Meter Reading Scale HV (~540)
11. Linear C.I.C. Voltages CV (~ 2 to 8)
12. Recorders On, Dated, and Green is illuminated on Temperature/CAM Recorder Water Level (inches)
13. Core Check (Lights On) Elements Verified Inspection Source Inserted
14. Start-Up Channel Test (Verify test switch is in the operate position when test is completed.)
15. Verify FC Response, FC Inserted, Count Rate > 2 CPS
16. Log Count Rate HV Power Supply (+400 VDC)
17. Log and Power Range Test
18. Period Response Test
19. Magnet Power On, Scram Reset, Board Reset
20. Inlet Temperature (oF)

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Revision: Page 8 of 8 Safety Amplifier 1

21. 150% Power Trip Test Reading Raise Rods 3 in. Push "Test" Button Scram Test Safety Amplifier 2 Trip Test Reading
22. Log and Linear Drawer Non-Operative Raise Rods 3 in. Press NON-OPER Scram Test switch.
23. Period Trip Test
24. Manual Scram Test Raise Rods 3 in. Push Manual Scram
25. Annunciator Test, All Lights On
26. Magnets On, Rods on Insert Limit
27. Prepare Hourly and Permanent Logs Inspect Core Log Spike
28. Detector Response Check Period Spike Linear Spike Startup Channel Response
29. Raise Rods to 6 in., Record Time in Checklist and permanent log.

No. 1

30. Nitrogen Diffuser Status (ON or OFF)

No. 2

31. Intended Power Level
32. Announce Intention to Start
33. Pre-Startup Check Properly Completed (Licensed Operators Initials)
34. SRO on Duty announcement of licensed operators
35. SRO on Dutys name in Control Room
36. SRO on Dutys Initials
37. Date Revised By: Anthony Alchin Approved By: William Bonzer
      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 105 TITLE: REACTOR SHUTDOWN & REACTOR SECURING PROCEDURES Revised: June 16, 2017 Page 1 of 4 A. PURPOSE To ensure a safe and consistent method to shutdown the Reactor from an operating condition and, when advised by a SRO on Duty, to secure the reactor.

B. PRECAUTIONS, PREREQUISITES, AND LIMITATIONS

1. The SRO on Duty will decide if the Reactor is to be "SHUTDOWN" or "SECURED".
2. A Secure Checklist shall be completed at the end of the work day.
3. Any malfunctions or abnormal conditions noted during or after the Shutdown will be recorded in the Permanent Log and the SRO on Duty shall be notified.
4. An operator assistant shall be present if the Reactor is not in "AUTO" before the shutdown begins to take logs.
5. The RO must be alert to the indication of jamming of control rods during the shutdown process. If this occurs, stop driving in the rods and inform the SRO on Duty.
6. At the end of an operational run, the operator should dispose of trash, coffee cups, soda cans, etc. and leave the Control Room in a clean and orderly appearance.

C. "SHUTDOWN" OF REACTOR

1. Log time, initials, followed by "SHUTDOWN" in the hourly log.
2. Log time and "SHUTDOWN" in the permanent log.
3. Announce over the public address system, "The reactor will be shutdown".
4. Trip "AUTO/MANUAL" switch to "MANUAL" (if in "AUTO").
5. Place the "OPERATE/SHUTDOWN" switch in "SHUTDOWN" position or insert Rev.

safety rods and regulating rod with both control rod lever switches.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 105 TITLE: REACTOR SHUTDOWN & REACTOR SECURING PROCEDURES Revised: June 16, 2017 Page 2 of 4

6. Monitor the decrease in reactor power by changing the Linear Meter Selector Button (1 button to the left) when the Linear Recorder decreases to about 8% of the present scale.

Operation at high power levels will prevent returning to lowest allowed scale (2 watts) and therefore this step is continued only until rods reach their limit.

7. Maintain Log Count Rate Recorder > 20 cps by inserting fission chamber.

Rev.

8. When the rods are fully inserted to their insert limits (green lights):
a. Return "OPERATE/SHUTDOWN" switch to "OPERATE or,
b. Return control rod lever switches to the "NEUTRAL" position.
9. Reactor is now "SHUTDOWN".

D. "SECURE CHECKLIST Refer to form SOP 105.

1. Date by digitally signing with Date Stamp format or with rubber date stamp. Rev.
2. Verify all rod and Reg Rod Insert Limit (Green) Lights on.
3. Turn magnet key 90 degrees CCW and remove from console.
4. Turn off the Log Count Rate, Linear, and Log/Period recorders. Place date at the top of each recorder chart (use date stamp).
5. Push Annunciator "RESET". The "MANUAL SCRAM", "RECORDERS OFF" and "MANUAL OPERATION" Annunciators will remain on.
6. Turn the Reactor Bridge intercom off by pressing the off button. Rev.
7. Return "OPERATE/SHUTDOWN" switch to "OPERATE".
8. Turn TV monitor off.
9. Verify both nitrogen diffusers are off.
10. Verify that all vent fans are off.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 105 TITLE: REACTOR SHUTDOWN & REACTOR SECURING PROCEDURES Revised: June 16, 2017 Page 3 of 4

11. Secure the rabbit system by assuring the controller is turned off. Remove the glove box key. Rev.
12. Verify rabbit system nitrogen gas bottle is shut.
13. Verify core lights are turned off.
14. Hand all keys to the SRO on Duty.
15. Log time using the console clock.
16. Initials of person performing checklist.
17. SRO on Duty shall digitally sign or sign manually verifying completion.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 105 TITLE: REACTOR SHUTDOWN & REACTOR SECURING PROCEDURES Revised: June 16, 2017 Page 4 of 4 SECURE CHECKLIST Rev.

1. Date
2. All Rods on Insert Limit
3. Magnet Power Off
4. Recorders Off and Dated
5. Reset Annunciator
6. Reactor Bridge Intercom Off
7. Shutdown Switch to Operate
8. TV Monitor Off
9. Nitrogen Diffusers Off
10. Vent Fans Off
11. Rabbit System Secured
12. Rabbit Gas Off
13. All Keys to SRO on Duty
14. Core Lights Off
15. Time Completed
16. Performers Initials
17. SRO on Dutys Signature Revised By: Anthony Alchin Approved By: William Bonzer
      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 106 TITLE: RESTART OF REACTOR WHEN IT IS NOT SECURED Revised: Page 1 of 2 A. PURPOSE To be used after the reactor has been shutdown to shut down to zero inches, magnet current turned off, and recorders turned off but not secured. A restart may be initiated without an additional Pre-Startup Checklist being completed.

B. PRECAUTIONS, PREREQUISITES, OR LIMITATIONS

1. This procedure can only be used during the same day of the last completed Pre-Startup Checklist.
2. Verify that the daily Pre-Startup Checklist has been completed.
3. The SRO on Duty shall verify maintenance has not been performed on the control room equipment or the reactor core structure since the reactor has been shutdown to zero inches. If maintenance has been performed, the SRO on Duty shall determine if the reactor is operable by performing a channel test, Pre-Startup Checklist, or independent test to verify the repaired equipment is operable.

C. PROCREDURE Complete the following steps to re-start the reactor.

1. Verify that a secure checklist has not been completed.
2. Record the time and intended power level (2 W - 100 KW) in the permanent logbook.
3. Insert the source and inspect the core.
4. Make certain pico-ammeter is on the 2 watt scale.
5. Adjust the compensating voltage of the linear channel to read between 0.02 and 0.05 on the pico-ammeter.
6. Verify that all rods or at insert limits.
7. Turn recorders on and verify that the Temperature/CAM recorder is on and the green is illuminated.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 106 TITLE: RESTART OF REACTOR WHEN IT IS NOT SECURED Revised: Page 2 of 2

8. Adjust fission chamber to insert limit (this SOP is not intended to be used in a hot restart situation)
9. Spike the Linear and Log/Period CICs. Observe the spikes on the recorders and the proper response by the fission chamber on the Log Count Rate recorder.
10. Turn on magnet current and reset the annunciator and scram. Check magnet currents.
11. Raise control rods to six inches and enter the time into the permanent log book.

The SRO on Duty or his designee shall enter SRO permission granted to restart the reactor into the permanent logbook.

12. Announce intentions to start reactor to desired power. Note: Initial power can not exceed 100 kW.
13. Follow procedures in S.O.P. 103 Reactor Startup to Low Power for raising control rods and observing turn around to attain desired power level not greater than 100 kW.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 107 TITLE: PERMANENT LOG, HOURLY LOG, AND OPERATIONAL DATA Revised: June 16, 2017 Page 1 of 7 A. PURPOSE To provide for records of facility operation and major maintenance. Hourly logs will detail specific instrument readings while the reactor is in operation.

B. PRECAUTIONS, PREREQUISITES, OR LIMITATIONS

1. The licensed Operator on Duty is responsible for the proper completion of all operational logs.
2. Any work affecting the reactor, its operation, and specific use during operation must be clearly and legibly described in the Permanent Log book.
3. The Operator on Duty will report any abnormal conditions entered in the operational logs Rev.

to the SRO on Duty.

4. All log entries are to be made with times recorded from the console clock.
5. All scrams and rundowns shall be documented in the Permanent Log as described in SOP 150, "Response to Alarms".
6. The reactor operator may make entries in the log book when the reactor is leveled at a stable power with the Reg Rod in "Auto". Otherwise, an operator assistant should record log entries (see SOP 102 or 103 for other conditions prior to log entries).
7. Log entries should be printed, rather than in cursive (except for signatures and initials),

and should be in black ink.

C. PROCEDURE

1. Hourly Log Entries
a. The hourly log sheet will be dated.
b. Each Licensed Operator on Duty in the control room and SRO on Duty will place their signatures in appropriate spaces provided at the top of the form/s.
b. A new hourly log will be started at the beginning of each operational day, or when all available columns of both sheets have been filled during the current day of operation, (i.e. a new hourly log sheet is not required for each startup checklist SOP 102).

Revised by: Anthony Alchin Approved By: William Bonzer

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

SOP: 107 TITLE: PERMANENT LOG, HOURLY LOG, AND OPERATIONAL DATA Revised: June 16, 2017 Page 2 of 7

c. The following procedure steps correspond to the numbered steps on the MSTR Hourly Operating Log form.
1. Time from the console clock.
2. Person at the console, initials (student, trainee, or licensed operator).
3. Nominal reactor power level (in watts or kilowatts).
4. Linear recorder reading in percent.
5. Linear Meter Scale.
6. Reg rod in "Auto" and annunciator board reset? Yes or No.
7. Log percent power (digital meter) of the Log and Linear drawer.
8. Check Period Recorder trace for proper indications over the past 10 minutes (approximately) of operation.
9. Log and Linear drawer Power Range reading on digital meter (%).
10. Record the Log Count Rate Recorder reading.
11. Source removed? (Y)es or (N)o Rev.
12. Diffuser pumps on? (Y)es or (N)o. If Y, specify which are on.
13. Exhaust fans on? (Y)es or (N)o. If Y, specify which are on.
14. Record the position of Shim Rod #1 to the nearest tenth of an inch.
15. Record the position of Shim Rod #2 to the nearest tenth of an inch.
16. Record the position of Shim Rod #3 to the nearest tenth of an inch.
17. Record the position of the Regulating Rod to the nearest tenth of an inch.
18. Check Radiation Area Monitors (Reactor Bridge, Demineralizer and Beam Room) to ensure readings are normal i.e. below 2 mrem/hr. Rev.

Revised by: Anthony Alchin Approved By: William Bonzer

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

SOP: 107 TITLE: PERMANENT LOG, HOURLY LOG, AND OPERATIONAL DATA Revised: June 16, 2017 Page 3 of 7

19. Record Reactor Bridge RAM reading in mr/hr.
20. Record the reading on the Safety Channel No. 1.
21. Record the reading on the Safety Channel No. 2.
22. Verify that the time at which a stable power level was obtained is recorded in the Permanent Log as well as other entries to the Permanent Log such as Rev.

samples being irradiated, the person at the console, etc. (See section B of SOP 107).

23. Record the reactor Inlet Temperature (thermocouple 1 or 3) as displayed on the Pool Water Temperature Recorder.
24. Verification that SRO on Duty is aware of his or her status as SRO on Duty.
25. Record initials of SRO on Duty
26. Licensed operator initials or digitally signs.

Rev.

2. Permanent Log Entries
a. All entries in the Permanent Log shall be preceded by the date including when continuing onto a new page. (Use the date stamp) Rev.
b. During completion of the Startup Checklist (SOP 102) use the Check Out stamp and complete values as they become available. See the example below.

0953 Time Check Out Started NE 2406 Purpose 1027 Time Rods at 6 inches 1046 Time Reactor at 0.01 kw Revised by: Anthony Alchin Approved By: William Bonzer

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

SOP: 107 TITLE: PERMANENT LOG, HOURLY LOG, AND OPERATIONAL DATA Revised: June 16, 2017 Page 4 of 7

c. Reactor (Rx) power changes are made in accordance with SOP 103 and entries are Rev.

made prior to the start of a power change and at the new stable power level. The examples below indicate Permanent Log entries for a power change including shutdown of the reactor:

1028 Reactor started to 600W.

1030 Rx at 600W.

1035 Rx shut down.

d. The Sample-Experiment stamp is used to indicate the irradiation of a sample as a Permanent Log entry. This stamp will be used to indicate the production of by-product material. The example below indicates the use of this stamp.

EXPERIMENT 94-17 OPERATOR Bonzer_____

CORE OF FACILITY EXPERIMENTER & START STOP TOTAL POSITION SAMPLE TIME TIME TIME BRT Khouaja 1538 1539 1 min (Foil 1)

e. Changes in the personnel at the console or as SRO on Duty is to be recorded when Rev.

such changes occur. The following examples below shows how this should be done.

1110 SRO Bonzer replaces SRO Reisner as SRO on Duty.

1238 RO Lovecraft replaces SRO Alchin as Licensed Operator in Control Room and at console.

1245 Trainee Romero replaces SRO Lovecraft at console.

1310 Student Russo replaces Trainee Romero at console.

f. Any necessary corrections made in the permanent log book shall be made with a single line through the mistake and initials from the Licensed Operator. Writing over or attempting to change a mistake such as trying to turn a 6 into an 8 is forbidden.
g. Pertinent maintenance recorded in the Permanent Log book should be preceded by a red checkmark in the left-hand margin.

Revised by: Anthony Alchin Approved By: William Bonzer

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

SOP: 107 TITLE: PERMANENT LOG, HOURLY LOG, AND OPERATIONAL DATA Revised: June 16, 2017 Page 5 of 7

3. Operational Data (Recorder Charts)
a. Date all 3 primary recorders in accordance with SOP 102 (startup checklist) and SOP 105 (shutdown checklist).
b. Recorder chart paper is to be replaced as soon as possible after the current roll runs out. If a power change is in progress when the chart runs out, wait until the reactor is leveled out at the desired power prior to replacing the chart. During replacement use the new chart box for the old chart storage. Date both the old chart and all sides of the chart box. Place the chart on storage shelves adjacent to the control room.
c. All chart paper is retained for a period of FIVE YEARS except for the Log/Period Chart which is to be retained for the DURATION of the facility.
4. Ventilation Fan Log Entries
a. After receiving approval from the SRO on Duty to start or stop a building exhaust ventilation fan, complete the requested information on the Fan Operation Log (i.e.

time, fan #, power level, etc.)

b. Fan Operation Logs are retained in the Facility Health Physics files.

Example of Fan Operation Log DATE FAN # TIME TIME PEAK POWER/

ON OFF REMARKS Feb 10, 1996 2 1450 1500 200 KW Revised by: Anthony Alchin Approved By: William Bonzer

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

SOP: 107 TITLE: PERMANENT LOG, HOURLY LOG, AND OPERATIONAL DATA Revised: June 16, 2017 Page 6 of 7 Date __________________ Rev.

HOURLY OPERATING LOG (Page 1 of 2)

Licensed Operators on Duty SROs on Duty Signatures: (1) _______________________ (5) _______________________ (1) _______________________

(2) _______________________ (6) _______________________ (2) _______________________

(3) _______________________ (7) _______________________ (3) _______________________

(4) _______________________ (8) _______________________ (4) _______________________

1. Time at Power
2. Initials - Person at Console
3. Nominal Power (W or kW)
4. Linear Recorder (%)
5. Linear Scale (W or kW)
6. Auto Set/Board Reset ( Y or N)
7. Log Level (%)
8. Period Trace Normal (/)
9. Log and Linear Power Range (%)
10. Log Count Rate Recorder (cps)
11. Source Removed? (Y or N)
12. Diffuser(s) On? (Y or N)
13. Exhaust Fan On? (Y or N)
14. Shim Rod No. 1 (inches)
15. Shim Rod No. 2 (inches)
16. Shim Rod No. 3 (inches)
17. Regulating Rod (inches)
18. Radiation Levels Normal (/)
19. Bridge Monitor (mr/hr)
20. Power Chamber No. 1 (%)
21. Power Chamber No. 2 (%)
22. Permanent Log Entries (/)
23. Core Inlet Water Temp. (oF)
24. SRO on Duty Verification (/)
25. SRO on Duty Initials
26. Licensed Operator Initials Revised by: Anthony Alchin Approved By: William Bonzer
      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 107 TITLE: PERMANENT LOG, HOURLY LOG, AND OPERATIONAL DATA Revised: June 16, 2017 Page 7 of 7 Rev.

Date __________________

HOURLY OPERATING LOG (Page 2 of 2)

1. Time at Power
2. Initials - Person at Console
3. Nominal Power (W or kW)
4. Linear Recorder (%)
5. Linear Scale (W or kW)
6. Auto Set/Board Reset ( Y or N)
7. Log Level (%)
8. Period Trace Normal (/)
9. Log and Linear Power Range (%)
10. Log Count Rate Recorder (cps)
11. Source Removed? (Y or N)
12. Diffuser(s) On? (Y or N)
13. Exhaust Fan On? (Y or N)
14. Shim Rod No. 1 (inches)
15. Shim Rod No. 2 (inches)
16. Shim Rod No. 3 (inches)
17. Regulating Rod (inches)
18. Radiation Levels Normal (/)
19. Bridge Monitor (mr/hr)
20. Power Chamber No. 1 (%)
21. Power Chamber No. 2 (%)
22. Permanent Log Entries (/)
23. Core Inlet Water Temp. (oF)
24. SRO on Duty Verification (/)
25. SRO on Duty Initials
26. Licensed Operator Initials Revised by: Anthony Alchin Approved By: William Bonzer
      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev.

SOP: 150 TITLE: RESPONSE TO ALARMS Revised: July 31, 2017 Page 1 of 4 A. PURPOSE To provide for the proper operator response to alarms while the reactor is operating.

B. PRECAUTIONS, PREREQUISITES, OR LIMITATIONS

1. Refer to SOP 501, "Emergency Procedures - Building Evacuation" for response procedures to a building evacuation alarm.
2. Refer to SOP 151, "Response to a High Area Radiation Alarm" for response procedures to a High Area Radiation Alarm.
3. Authorization to restart the reactor following a scram or rundown can only be made by the SRO on Duty. Rev.

C. SCRAM RESPONSE PROCEDURE

1. Upon receipt of a SCRAM Alarm, the operator will:
a. Acknowledge the alarm.
b. Verify that the shim rods have inserted (audibly, visually, or by observing magnet contact lights and currents).
c. Verify power is decreasing appropriately.
d. Fully insert all rod drives.
e. Notify the SRO on Duty.
f. Record the following information in the permanent logbook:

i) time of scram ii) type of scram (e.g. Bridge Motion, Manual, etc.)

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 150 TITLE: RESPONSE TO ALARMS Revised: July 31, 2017 Page 2 of 4

2. The SRO on Duty will:
a. Determine (to the extent possible) the cause of the scram.
b. Initiate corrective actions as necessary.
c. Record the following information in the permanent logbook:

i) cause of SCRAM ii) corrective action taken iii) SRO "permission granted" to restart Note: In certain instances no corrective action will be necessary, such as a scram due to an AC power flicker. In these cases log the corrective action as "No corrective action necessary".

d. Permission to restart the reactor must be granted by the SRO on Duty prior to reactor restart.

D. RUNDOWN RESPONSE PROCEDURE

1. Upon receipt of a RUNDOWN Alarm signal, the operator will:
a. Acknowledge the alarm
b. Verify that control rods are inserting.
c. Verify that power is decreasing.
d. Notify the SRO on Duty.
e. If the alarm is a "HIGH AREA RADIATION" alarm, refer to SOP 151.
f. A licensed operator may stop the Rundown in the event that the alarm condition has cleared. The Reactor may not be restarted (i.e. rods may not be withdrawn) until items under Step D.2 have been completed.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 150 TITLE: RESPONSE TO ALARMS Revised: July 31, 2017 Page 3 of 4

g. Record the following information in the permanent logbook:

i) time of rundown ii) type of rundown (e.g. Low CIC Voltage, 120% Demand, etc.)

2. The SRO on Duty will:
a. Determine (to the extent possible) the cause of the rundown.
b. Initiate corrective actions as necessary.
c. Record the following information in the permanent logbook:

i) cause of the rundown ii) corrective actions taken iii) SRO "permission granted" to restart Note: In certain instances no corrective action will be necessary, such as a rundown due to an AC power flicker. In these cases log the corrective action as "No corrective action necessary".

d. Permission to restart the reactor must be granted by the SRO on Duty prior to reactor restart.

E. RESPONSE TO A ROD WITHDRAWAL PROHIBIT ALARM Upon receipt of a ROD WITHDRAWAL PROHIBIT Alarm the operator will:

1. Acknowledge the alarm.
2. Notify the SRO on Duty if the alarm is unexplained or unexpected.
3. Identify and correct the cause of the alarm.
4. Reset the annunciator panel after the cause of the alarm has been corrected.
5. The Reactor shall be shutdown if the alarm condition cannot be remedied or if reactor safety is compromised in any way.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 150 TITLE: RESPONSE TO ALARMS Revised: July 31, 2017 Page 4 of 4 F. WHITE LIGHT ANNUNCIATOR ALARM Upon receipt of a white light annunciator alarm the operator will:

1. Acknowledge the alarm.
2. Notify the SRO on Duty if the alarm is unexplained or unexpected.
3. Determine and implement further corrective actions as deemed necessary.
4. In the event of a "Basement Sump Level High" alarm, the operator should have the basement area checked for excessive water in the basement.
5. In the event of a "Pool Demineralizer Effluent Conductivity High" alarm the operator should have the demineralizer conductivity checked and a visual check at the demineralizer return line in the pool for potential leaking resins. If a problem is identified with the Demin system it should be taken off-line and the SRO notified.
6. The reactor shall be shutdown if reactor safety is compromised in any way.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 151 TITLE: RESPONSE TO A HIGH AREA RADIATION ALARM Revised: July 31, 2017 Page 1 of 2 A. PURPOSE To provide for the proper response to a High Area Radiation Alarm.

B. PRECAUTIONS, PREREQUISITES, OR LIMITATIONS

1. Personnel in the affected area should evacuate the area and report to the control room. If the Building Evacuation Alarm is sounded, proceed as directed in SOP 501, "Building Evacuation Procedure".
2. The Building Evacuation Alarm may be actuated at any time it is deemed warranted for the protection of personnel within the facility.

C. PROCEDURE

1. Upon receiving an unanticipated High Area Radiation Alarm:
a. The Reactor Operator will i) announce the location and indicated dose rate of the affected area.

ii) verify that the reactor rundown has occurred and that rods are inserting.

iii) immediately scram the reactor if personnel or reactor safety is in question.

iv) initiate a building evacuation at any time it is deemed warranted.

b. The SRO on Duty will i) report to the control room for a status report.

ii) proceed to the affected area with a survey meter to determine if abnormal radiation levels actually exist.

iii) determine if a building evacuation is necessary.

c. If a Building Evacuation is initiated (either manually or automatically) evacuate the building per SOP 501, "Building Evacuation Procedure".

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 151 TITLE: RESPONSE TO A HIGH AREA RADIATION ALARM Revised: July 31, 2017 Page 2 of 2

2. Prior to restarting the reactor, complete the steps listed in SOP 150, "Alarm Responses" Section D, "Rundown Response Procedure".
3. The key-bypass for the High Radiation Area alarm may be used at the discretion of the SRO on Duty if all of the following criteria are met:
a. The high dose field is anticipated and explained.
b. The high dose field area access is controlled to prevent personnel overexposure.
c. The dose field in the occupied areas of the building are monitored and found to be less than 5 mrem/hr. This dose rate restriction is not intended to apply to facility staff who are cognizant and working in the affected area on a specific task.
d. The dose field outside of the building adjacent to the affected area is surveyed and found to be such that an individual can receive no more than 2 mrem in any one hour period.
e. The key-bypass must be logged into the permanent logbook with the name of the SRO authorizing its use.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 310 TITLE: 10 CFR 50.59 CHANGES, TESTS, AND EXPERIMENTS Complete Revision: July 10, 2017 Page 1 of 10 A. PURPOSE The purpose of this procedure is to provide for the effective review and approval process for changes to the facility as described in the SAR, changes to procedures as described in the SAR, or conduct tests or experiments not described in the SAR, heavily using Regulatory Guide NEI 96-07 as a guideline to ensure regulatory compliance with 10 CFR 50.59, Changes, Tests, and Experiments. In addition, this procedure provides for an effective process to keep documentation up to date with any changes.

B. PRECAUTIONS, PREREQUISITES, AND LIMITATIONS

1. Prior to any 10 CFR 50.59 Screening and Evaluation a detailed written description of the proposed modification shall be prepared that includes all the engineering work involved with the modification.
2. Review and approval requirements for changes that do not require NRC approval are prescribed in 10 CFR 50.59, Changes, Tests, and Experiments. Proposed facility modifications do not require NRC approval if the following conditions are met:
a. the change must not involve a change in Technical Specifications; and
b. the change, test, or experiment does not meet any of the following criteria:
i. results in a more than minimal increase in frequency of an accident, likelihood of a malfunction of a Structure, System, or Component(SSC),

or the consequences (dose) of an accident or a malfunction of an SSC previously evaluated in the SAR.

ii. results in creating a possibility for an accident or a malfunction of an SSC with a different result, than any previously evaluated in the SAR.

iii. results in a departure of a method of evaluation described in the SAR used to establish design bases or safety analyses.

3. 10 CFR 50.59 Screenings and Evaluations shall be prepared by knowledgeable qualified personnel. For purposes of MSTR this means any licensed operators.
4. 10 CFR 50.59 Screenings and Evaluations shall be reviewed and approved by at least one Licensed Staff or Licensed Faculty.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 310 TITLE: 10 CFR 50.59 CHANGES, TESTS, AND EXPERIMENTS Complete Revision: July 10, 2017 Page 2 of 10

5. Digital upgrades for now must always be screened in. NRC considers digital equipment to be susceptible to Common-Cause Failure and therefore Digital upgrades must be evaluated to ensure no possibility of a malfunction of an SSC or an accident not previously evaluated is created.

C. DEFINITIONS/ACRONYMS

1. Change means a modification or addition to, or removal from, the facility or procedures that affects: (1) a design function, (2) method of performing or controlling the function, or (3) an evaluation that demonstrates that intended functions will be accomplished.
2. Described in the SAR encompasses all of the SARs text, tables, diagrams, etc. as well as supplemental information explicitly incorporated by reference.
3. Facility as described in the SAR means the SSCs described in the SAR, the design and performance requirements for such SSCs described in the SAR, an evaluation or method of evaluation included in the SAR for such SSCs which demonstrate such functions will be accomplished.
4. Procedures as described in the SAR means those procedures that contain information described in the SAR sauch as how an SSC is operated or controlled.
5. Tests or Experiments not described in the SAR means any activity where an SSC is utilized or controlled in a manner which is either outside the reference bounds of the bases as described in the SAR or inconsistent with the analyses or descriptions in the SAR.
6. Departure from a Method of Evaluation described in the SAR means (i) changing any of the elements of the method described in the SAR unless the results of the analysis are conservative or essentially the same; or (ii) changing from a method described in the SAR to another method unless that method has been approved by the NRC for the intended application.
7. Design Functions means any SAR described design bases function and other SSC function described in the SAR that support or impact design bases functions. This includes implicit conditions under which intended functions are to be performed. A design function may be performed by safety-related SSCs and non-safety-related SSCs and include functions that if not performed, would initiate an accident the facility is not required to withstand.
8. Method of Evaluation means the calculational framework used for evaluating behavior or response of the facility or an SSC.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 310 TITLE: 10 CFR 50.59 CHANGES, TESTS, AND EXPERIMENTS Complete Revision: July 10, 2017 Page 3 of 10

9. Accident previously evaluated in the SAR means a design basis accident or event described in the SAR such as those analyzed in Chapter 13 of the SAR including transients and events the facility may be required to withstand such as floods, fires, tornadoes, and other external hazards.
10. Malfunction of an SSC important to Safety means the failure of an SSC to perform its intended design basis function(s) as described in the SAR.
11. More than a minimal increase means if an accident or malfunction of an SSC would increase in a discernable, attributable, clear change into a new more substantially frequent class or condition. If a change is neither discernable, clear, nor attributable than the change is considered minimal. While qualitative analysis is acceptable, if quantitative analysis is done the change cannot increase by more than 10%.

D. 10 CFR 50.59 SCREENING The 10 CFR 50.59 Screening should be completed according to the following steps:

1. GENERAL INFO
a. Title - Simple title to identify the activity being performed.
b. Number - The number of the 50.59 Screen. Written in YY-## format.

Example 17-03 is the 3rd 50.59 screening in the year 2017.

c. Prepared By - The name of the licensed operator preparing the Screening.
d. Date - The date the screening was completed.
e. Description of Activity - Detailed description of the activity being screened for 10 CFR 50.59.
2. APPLICABILITY - To determine if 50.59 is even appropriate for the activity planned.
a. If another regulation or a statement in the facility license i.e. Tech Specs covers the activity then a 10 CFR 50.59 is not applicable. NOTE: RTRs have very few applicable Regulations so most changes will not be controlled by another regulation or change process and therefore 10 CFR 50.59 must be used despite not being intended for such applications.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 310 TITLE: 10 CFR 50.59 CHANGES, TESTS, AND EXPERIMENTS Complete Revision: July 10, 2017 Page 4 of 10

3. SCREENING - Determine if an evaluation against the eight criteria of 10 CFR 50.59 (c)(2) is necessary.
a. Does the proposed activity involve a change to an SSC that potentially adversely affects a design function described in the SAR? - If a change made to a SSC whose design function was described in the SAR would make things less conservative or any other way worse than they are currently they should be screened in. Any change to a Design basis Limit for a Fission Product Barrier (DBLFPB) is conservatively considered adverse regardless if its potentially better. This includes changes to input parameters to equations or models used in design bases or safety analyses.
b. Does the proposed activity involve a change to a procedure that potentially adversely affects how an SAR described design function is performed, controlled or tested? - If changes to a procedure have a positive or no effect on how an SSC design function is performed, controlled, or tested should be screened out. Changes that fundamentally alter (replace) the existing means should be conservatively screened in and evaluated.
c. Does the proposed activity involve revising or replacing an SAR described evaluation methodology that is used in establishing the design bases or used in the safety analyses? - If changes are made to a calculation used in evaluating the design bases or safety analyses, then 50.59 evaluation must be completed. This includes using a different model including an updated version of a previously used model. This does not include changing the input parameters of a model or equation.
d. Does the proposed activity involve a test or experiment not described in the SAR, where an SSC is utilized or controlled in a manner that is outside the reference bounds for that SSC or is inconsistent with analyses or descriptions in the SAR? - This involves untried experiments and tests that are significantly different from those previously used or tested in the reactor, as determined by the DNR.
e. Does the proposed activity involve a change to the MSTR Tech Specs? -

A change to the Tech Specs involves a license amendment per 10 CFR 50.90 and must be received before implementation of the proposed activity.

f. If all screening questions are answered NO, provide justification on the following page explaining why each is NO being sure to list any references by section/page to support the argument.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 310 TITLE: 10 CFR 50.59 CHANGES, TESTS, AND EXPERIMENTS Complete Revision: July 10, 2017 Page 5 of 10

g. 50.59 Screening Reviewed and Approved - The screening shall be reviewed and approved with at least two signatures consisting of the following: Licensed Senior Reactor Operator, Radiation Safety Officer, Reactor Manager, and/or Reactor Director.
h. If 50.59 Evaluation is deemed not required, proceed to Section F Document Review and Revision else, continue on to Section E 10 CFR 50.59 Evaluation.

E. 10 CFR 50.59 Evaluation

1. When answering the evaluation questions be as thorough as possible, providing as much detail as achievable between documentation and engineering details of the proposed change and using NEI 96-07 Section 4.3 as a guide.
2. If the proposed change is to a Method of Evaluation used in the SAR to establish design bases or safety analyses, the only relevant criteria is criteria (viii). Criteria (i)-(vii) do not apply and vice versa if not a Method of Evaluation. The irrelevant question(s) must still be answered but may be stated as not relevant due to being or not being a Method of Evaluation.
3. If any question is answered YES, the proposed activity may not be implemented until a License Amendment is obtained through the NRC.
4. 50.59 Evaluation Reviewed and Approved - The screening shall be reviewed and approved with at least two signatures consisting of the following: Licensed Senior Reactor Operator, Radiation Safety Officer, Reactor Manager, and/or Reactor Director.
5. When all paperwork is completed, all paperwork relating to the proposed activity shall be submitted to the Radiation Safety Committee for Review.
6. Proceed to Section F Document Review and Revision.

F. Document Review and Revision

1. The purpose of the Document Review and Revision is to track ensure that all documentation is kept up to date for all changes done to the facility regardless if License Amendment is required to implement.
2. For each question, attach draft copy of each revision that will be needed for the proposed activity and list them in the space provided.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 310 TITLE: 10 CFR 50.59 CHANGES, TESTS, AND EXPERIMENTS Complete Revision: July 10, 2017 Page 6 of 10

3. Document Review and Revision Reviewed and Approved - The screening shall be reviewed and approved with at least two signatures consisting of the following: Licensed Senior Reactor Operator, Radiation Safety Officer, Reactor Manager, and/or Reactor Director.
4. Once complete and License Amendment through the NRC is acquired if necessary, proceed with implementation of proposed activity.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 310 TITLE: 10 CFR 50.59 CHANGES, TESTS, AND EXPERIMENTS Complete Revision: July 10, 2017 Page 7 of 10 10 CFR 50.59 Screening

Title:

Number:

Prepared By: Date:

Description of Activity:

Applicability:

YES NO Is the activity controlled by another Regulation or Change Process that is applicable to RTRs? i.e. 10 CFR 50.54, 10 CFR 50.12, 10 CFR 20, Facility Tech Specs, etc.

If the above question is answered yes, 10 CFR 50.59 is not applicable and the change should be evaluated using the appropriate regulation. NOTE: RTRs have very few applicable Regulations.

Screening:

YES NO 1. Does the proposed activity involve a change to an SSC that potentially adversely affects a design function described in the SAR? NOTE: For digital the answer is always YES. See accompanying procedure for justification.

YES NO 2. Does the proposed activity involve a change to a procedure that potentially adversely affects how an SAR described design function is performed, controlled or tested?

YES NO 3. Does the proposed activity involve revising or replacing an SAR described evaluation methodology that is used in establishing the design bases or used in the safety analyses?

YES NO 4. Does the proposed activity involve a test or experiment not described in the SAR, where an SSC is utilized or controlled in a manner that is outside the reference bounds of the design for that SSC or is inconsistent with analyses or descriptions in the SAR?

YES NO 5. Does the proposed activity involve a change to the MSTR Tech Specs?

If all screening questions are answered NO, then a license amendment or a 50.59 Evaluation is not required.

NOTE: Provide justifications for each NO on next page.

If Screen Question 5 is answered YES, refer to 10 CFR 50.90 for obtaining and receiving a license amendment prior to implementation of activity.

If Screen Question 1, 2, 3, or 4 is answered YES, 50.59 Evaluation is required.

50.59 Screening Reviewed and Approved (two signatures required):

Director _____________________ Date ________ Manager ____________________ Date _______

SRO _____________________ Date ________ SRO ____________________ Date _______

RSO _____________________ Date ________

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 310 TITLE: 10 CFR 50.59 CHANGES, TESTS, AND EXPERIMENTS Complete Revision: July 10, 2017 Page 8 of 10 If a 50.59 Evaluation is not required, provide justification to support this determination (include any applicable references with section/page for support). [Use and attach additional pages as necessary]:

1. Does the proposed activity involve a change to an SSC that adversely affects a design function described in the SAR?
2. Does the proposed activity involve a change to a procedure that adversely affects how an SAR described design function is performed, controlled or tested?
3. Does the proposed activity involve revising or replacing an SAR described evaluation methodology that is used in establishing the design bases or used in the safety analyses?
4. Does the proposed activity involve a test or experiment not described in the SAR, where an SSC is utilized or controlled in a manner that is outside the reference bounds of the design for that SSC or is inconsistent with analyses or descriptions in the SAR?

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 310 TITLE: 10 CFR 50.59 CHANGES, TESTS, AND EXPERIMENTS Complete Revision: July 10, 2017 Page 9 of 10 10 CFR 50.59 Evaluation

Title:

Number:

A separate written response providing the basis for the answer to each of the following questions regardless of answer SHALL be provided on a separate paper accompanying this form. Include references used to perform the Evaluation with Section/Page No.

EFFECT ON ACCIDENTS AND MALFUNCTIONS PREVIOUSLY EVALUATED IN THE SAR YES NO i. Does the proposed activity result in more than a minimal increase in the frequency of occurrence of an accident previously evaluated in the SAR?

YES NO ii. Does the proposed activity result in more than a minimal increase in the likelihood of occurrence of a malfunction of an SSC important to safety previously evaluated in the SAR?

YES NO iii. Does the proposed activity result in more than a minimal increase in the consequences (dose) of an accident previously evaluated in the SAR?

YES NO iv. Does the proposed activity result in more than a minimal increase in the consequences (dose) of a malfunction of an SSC important to safety previously evaluated in the SAR?

POTENTIAL FOR CREATION OF A NEW TYPE OF EVENT NOT PREVIOUSLY EVALUATED IN THE SAR YES NO v. Does the proposed activity create a possibility for an accident of a different type than any previously evaluated in the SAR?

YES NO vi. Does the proposed activity create a possibility for a malfunction of an SSC important to safety with a different result than any previously evaluated in the SAR?

IMPACT ON FISSION PRODUCT BARRIERS AS DESCRIBED IN THE SAR YES NO vii. Does the proposed activity result in a design basis limit for a fission product barrier as described in the SAR as being altered or exceeded?

IMPACT ON EVALUATION METHODOLOGIES DESCRIBED IN THE SAR YES NO viii. Does the proposed activity result in a departure from a method of evaluation used to establish any design basis or any safety analysis described in the SAR?

If the answer to any of the previous questions is YES, then the proposed activity may not be implemented until a License Amendment has been obtained from the NRC.

50.59 Evaluation Reviewed and Approved (two signatures required):

Director _____________________ Date ________ Manager ____________________ Date _______

SRO _____________________ Date ________ SRO ____________________ Date _______

RSO _____________________ Date ________

Date of Review by Radiation Safety Committee:

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 310 TITLE: 10 CFR 50.59 CHANGES, TESTS, AND EXPERIMENTS Complete Revision: July 10, 2017 Page 10 of 10 Document Review and Revision

Title:

Number:

YES NO 1. Do the Technical Specifications address any of the equipment involved in the proposed activity?

If yes, list the Specifications (section number and title):

YES NO 2. Will the proposed activity involve a change in any of the Technical Specifications?

If yes, attach the proposed revision(s) and list the Specifications (section number and title) to be revised:

YES NO 3. Does the SAR address any of the equipment involved with the proposed modification?

If yes, list all applicable SAR Sections (section number and title):

YES NO 4. Will the proposed activity involve a change in any of the SAR?

If yes, attach the proposed revision(s) and list the SAR Sections (section number and title) to be revised:

Attach and list all SOPs that will require revision with this proposed activity:

Attach and list revisions to other MSTR documents that may be required

a. YES NO Emergency Plan?
b. YES NO Physical Security Plan?
c. YES NO Requal Program?
d. YES NO License?
e. YES NO Others?

Document Review and Revision Reviewed and Approved (two signatures required):

Director _____________________ Date ________ Manager ____________________ Date _______

SRO _____________________ Date ________ SRO ____________________ Date _______

RSO _____________________ Date ________

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Revised: August 1, 2017 Page 1 of 7 A. PURPOSE To provide for the safe and orderly evacuation of the Reactor Building.

B. PRECAUTIONS, PREREQUISITES, OR LIMITATIONS

1. This procedure is not intended to be all encompassing. Personnel may deviate from this procedure as needed to maintain safety. Strong reliance is placed upon the good judgement of operating personnel.
2. Any person may manually initiate the evacuation alarm if it is believed conditions merit such action.
3. The Reactor Manager, or a Licensed Operator, may silence the evacuation alarm Rev.

and rescind the evacuation by building announcement if it is determined that the evacuation is unwarranted.

4. Upon sounding of the Building Evacuation Alarm, all personnel except for the RO and the SRO on Duty will proceed directly and calmly to the Physics Building basement area and remain in this area for further instructions.
5. Persons providing escort for visitors are responsible for the safe evacuation of their visitors to the Physics Building basement and for obtaining the Visitor's Logbook from the front office upon exiting the facility. The escort will report the accountability status of the visitors to the SRO on Duty once in the Physics Building basement area.
6. All persons must remain calm and orderly.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Revised: August 1, 2017 Page 2 of 7 C. REACTOR OPERATOR PROCEDURE Rev.

Upon activation of the Evacuation alarm, the Reactor Operator will obtain the "REACTOR OPERATOR EVACUATION CHECKLIST" and follow the steps therein. If the reactor is shut down at the time of alarm, the REACTOR OPERATOR EVACUATION CHECKLIST need not be completed. Proper actions for each step in the checklist are described below:

1. SCRAM REACTOR: The operator will promptly scram the reactor.
2. VERIFY ROD INSERTION: Verify that the shim rods have inserted Rev.

(audibly, or visually, and magnet currents). Verify power is decreasing appropriately.

3. SECURE MAGNET KEY: Remove the key from the console and maintain possession of the key.
4. ANNOUNCE FACILITY STATUS: Announce the status of the facility over the building PA. State the cause of the alarm and areas of the building to avoid as necessary.
5. RECORD TIME: Record the console clock time.
6. WAIT IN CONTROL ROOM FOR SRO: Remain in the control room (or control room area) for the SRO on Duty, if possible. Report facility status to the SRO on Duty upon his arrival. The SRO on Duty may instruct the operator to proceed differently from the items listed in the checklist.
7. OBTAIN PERMANENT LOGBOOK/METERS: Obtain the console permanent logbook. Obtain survey meters and pocket dosimeters, if convenient.
8. VENT FANS OFF: Verify that all three exhaust vent fans are off.
9. OBTAIN EMERGENCY KEYS: Obtain the emergency key box. If the key box is not in its usual location, assume someone else has already obtained it.
10. PROCEED TO PHYSICS BUILDING BASEMENT AREA: Leave the facility and proceed directly to the designated Physics Building basement area.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Revised: August 1, 2017 Page 3 of 7 D. SRO ON DUTY PROCEDURE Rev.

Upon activation of the Evacuation Alarm, the SRO on Duty will obtain the SRO EVACUATION CHECKLIST and follow the steps therein. Proper actions for each step are listed below:

1. PROCEED TO CONTROL ROOM: Proceed directly to the control room for a status report from the Reactor Operator.
2. RECEIVE OPERATOR'S REPORT: Determine the facility status from the Reactor Operator.
3. OBTAIN SURVEY INSTRUMENTS: Obtain survey instruments and dosimeters, if possible.
4. VENT FANS OFF: Verify that all three exhaust vent fans are off.
5. ALL PERSONNEL EVACUATED: Verify that all personnel have left the building.
6. EMERGENCY KEYS OBTAINED: Obtain emergency key box upon exiting the building. If the key box is not in its usual location, assume the key box has already been obtained.
7. PROCEED TO PHYSICS BUILDING BASEMENT AREA: Proceed directly to the Physics Building basement area.

Upon arriving at the Physics Building basement area the SRO on Duty will:

1. Account for all personnel known to have been in the facility. Record the names of each individual evacuated.
2. Receive reports from personnel on the facility status, as necessary.
3. Notify the Reactor Manager, Reactor Director, and Campus Health Physicist as appropriate. Use the Emergency Phone List as needed.
4. If personal contamination is possible, frisk each person evacuated for contamination. Isolate contaminated person(s) in the emergency shower area.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Revised: August 1, 2017 Page 4 of 7

5. Evaluate the situation to determine if the potential for an emergency condition exists per the Reactor Emergency Plan. Implement the following Rev.

procedures as necessary:

  • SOP 502 "Emergency Procedure For An Unusual Event"
  • SOP 503 "Emergency Procedure For An Alert"
  • SOP 504 "Emergency Procedure For A Site Area Emergency"
  • SOP 507 Emergency Procedure - Administrative Responsibilities
  • SOP 620 Handling Injured in Radiation Accidents Rev.
  • SOP 621 "Guidelines For Emergency Exposure"
  • SOP 622 "Handling Injured In Radiation Accidents
6. Take other actions as deemed appropriate.

E. END OF EMERGENCY, REENTRY, AND RECOVERY

1. In the event that an emergency status is declared (i.e. Unusual Event, Alert, or Site Area Emergency), the Emergency Director, Reactor Manager and the Radiation Rev.

Safety Officer shall decide when the emergency no longer exists and an "end of emergency" will be declared.

2. Recovery from emergency conditions will be instituted at the highest organizational level activated during the emergency. Procedures will be written, as needed, to recover from the emergency.
3. Personnel approaching the facility for reentry will report to the Emergency Support Center if radiation levels in excess of 100 mrem/hr are encountered.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Revised: August 1, 2017 Page 5 of 7

-REACTOR OPERATOR-EVACUATION CHECKLIST

1. SCRAM REACTOR _______
2. VERIFY ROD INSERTION _______
3. SECURE MAGNET KEY _______
4. ANNOUNCE FACILITY STATUS _______
5. RECORD TIME _______
6. WAIT IN CONTROL ROOM FOR SRO _______
7. OBTAIN PERMANENT LOGBOOK/METERS _______
8. TURN VENT FANS OFF _______
9. OBTAIN EMERGENCY KEYS _______
10. PROCEED TO PHYSICS BUILDING _______

Rev.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Revised: August 1, 2017 Page 6 of 7

- SRO -

EVACUATION CHECKLIST I. IMMEDIATE ACTIONS

1. PROCEED TO CONTROL ROOM _______
2. RECEIVE OPERATOR'S REPORT _______
3. OBTAIN SURVEY INSTRUMENTS _______
4. VENT FANS OFF _______
5. ALL PERSONNEL EVACUATED _______
6. EMERGENCY KEYS OBTAINED _______
7. PROCEED TO PHYSICS BUILDING _______

II. SUPPLEMENTAL ACTIONS

1. PERSONNEL ACCOUNTABILITY:

A. Have all Personnel Evacuated Building?

_____Yes _____No B. List names of each individual evacuated from building:

2. REFER TO SOP 501 SECTION D. FOR FURTHER INSTRUCTION.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Page Revision: January 8, 2018 Page 7 of 7 MISSOURI S&T EMERGENCY PHONE LIST Reactor Staff CELL HOME WORK Staff On-Call 578-9463 Craig Reisner, Interim Reactor Manager (573) 247-7557 (573) 729-7277 341-4291 Anthony Alchin, Electronics Technician III (816) 274-1771 341-6617 Rev.

University Administrative Staff Michelle Bresnahan, EHS Director, RSO (314) 239-7751 341-4305 Doug Roberts, Director Missouri S&T Police 202-3689 341-4300 Dr. Christopher Maples Interim Chancellor (775) 741-1635 341-7141 341-4114 Cuba Plain, Vice Chancellor, Finance & Operations (573) 268-3208 341-4122 Rev.

Ted Ruth, Asst. Vice Chancellor, Facilities Services (573) 647-6239 341-7619 Dr. Goodman DO, Director Student Health Services 341-4284 Dr. Hyoung Lee, Chair of Nuclear Eng (573) 202-4665 341-4585 Rev.

Dr. Braden Lusk, Chair of Mining and Nuclear (620) 960-1645 341-4174 Dr. Joseph Graham, Reactor Director (719) 244-0042 341-7759 Rev.

Fadha Al Falahi, Health Physicist EHS-MS&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 Missouri 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 (24 hr.) (573) 751-4674 Federal Agencies NRC, Operations Center (301) 951-0550 NRC Duty Officer (24 hr.) (301) 816-5100 Other Radiation Emergency Assistance Center (865) 576-3131 (24 hr.) (865) 576-1005 Revised By: Anthony Alchin Approved By: Craig Reisner

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

SOP: 502 TITLE: EMERGENCY PROCEDURES FOR AN UNUSUAL EVENT Revised: July 31, 2017 Page 1 of 2 A. EMERGENCY ACTION LEVELS In the event that the Emergency Support Center has been activated, the Emergency Director Rev.

shall determine if an Unusual Event condition exists and will respond to the emergency by implementing the appropriate procedures. An Unusual Event condition would exist if one of the conditions listed in the Action Levels in Table I of the Missouri S&T Reactor Emergency Plan exists. (See the attached.) Unusual Events conditions are not expected to warrant emergency notification of offsite organizations.

B. ASSESSMENT ACTIONS Confinement building and site boundary airborne radioactivity levels shall be determined Rev.

from the area radiation monitors and portable monitoring equipment by members of the emergency organization. The Emergency Director shall use this information and Table I to determine that the emergency is appropriately classified.

C. CORRECTIVE ACTIONS The reactor shall be shut down. Physical barriers to contain the radioactivity shall be maintained or implemented where necessary. Installed cleanup systems may be used to reduce the release of radioactive material. Further corrective actions shall be provided as needed for this emergency class.

D. PROTECTIVE ACTIONS The Protective Actions for this emergency classification are based upon a Guide of 1 rem whole body and 5 rem thyroid to members of the general public onsite and MSTR Staff. Rev.

Accountability of personnel following a building evacuation shall be done by the SRO on Duty who will check that the facility is clear of personnel. Further protective actions shall be provided as needed for this emergency class.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 502 TITLE: EMERGENCY PROCEDURES FOR AN UNUSUAL EVENT Revised: July 31, 2017 Page 2 of 2 SOP 502 Table I Emergency Class: Unusual Event Action Levels Purpose

1) Actual or projected radiological a) to assure that the first step in any effluents at the site boundary response later found to be necessary calculated to produce a dose of has been carried out, 15 mrem whole body accumulated in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. b) to bring the operating staff to a state of readiness, and
2) Report or observation of severe natural phenomenon, e.g. tornado, c) to provide for systematic handling of and earthquake. unusual events information and decision making
3) Receipt of bomb threat. Rev.
4) Credible security threat.
5) Fire not extinguished in 15 min.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 503 TITLE: EMERGENCY PROCEDURES FOR AN ALERT Revised: August 1, 2017 Page 1 of 2 A. EMERGENCY ACTION LEVELS In the event that the Emergency Support Center has been activated, the Emergency Director Rev.

shall determine if an Alert condition exists and will respond to the emergency by implementing the appropriate procedures. An Alert condition would exist if one of the conditions listed in the Action Levels in Table I exists. Alert conditions may require providing emergency notification and status information to offsite organizations.

B. ASSESSMENT ACTIONS Confinement building and site boundary airborne radioactivity and radiation levels shall be determined from area radiation monitors and portable monitoring equipment by members of the emergency organization. The Emergency Director shall use this information and Table I to determine that the emergency is appropriately classified.

C. CORRECTIVE ACTIONS The reactor shall be shut down. Physical barriers to contain the radioactive material shall be maintained or implemented where necessary. Installed cleanup systems may be used to reduce the release of radioactive material. Further corrective actions shall be provided as needed for this emergency class.

D. PROTECTIVE ACTIONS The Protective Actions for this emergency classification are based upon a Guide of 1 rem whole body and 5 rem thyroid to members of the general public onsite. Accountability of personnel following a building evacuation shall be done by the SRO on Duty who will check that the facility is clear of personnel. Further protective actions shall be provided as needed for this emergency class.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 503 TITLE: EMERGENCY PROCEDURES FOR AN ALERT Revised: August 1, 2017 Page 2 of 2 SOP 503 Table I Emergency Class: Alert Action Levels Purpose

1) Actual or projected radiological a) to assure that emergency personnel effluents at the site boundary are readily available to respond if calculated to produce a dose of 75 situation becomes more serious or to mrem whole body accumulated in 24 perform confirmatory radiation hours. monitoring if required, and,
2) Actual or projected radiation levels at b) to provide offsite authorities with the site boundary of 20 mrem/hr for 1 current status information.

hour whole body or 100 mrem thyroid dose.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 504 TITLE: EMERGENCY PROCEDURES FOR A SITE AREA EMERGENCY Revised: July, 31, 2017 Page 1 of 2 A. EMERGENCY ACTION LEVELS In the event that the Emergency Support Center has been activated, the Emergency Director Rev.

shall determine if a Site Area Emergency condition exists and will respond to the emergency by implementing the appropriate procedures. A Site Area Emergency would exist if one of the conditions listed in the Action Levels in Table I exists.

Site Area Emergency conditions may require evacuation of non-essential personnel to beyond the site boundary, and require providing emergency notification and status information to offsite organizations and the public.

B. ASSESSMENT ACTIONS Confinement building and site boundary airborne radioactivity and radiation levels shall Rev.

be determined from area radiation monitors and portable monitoring equipment by members of the emergency organization. The Emergency Director shall use this information and Table I to determine that the emergency is appropriately classified. The Campus Health Physicist will determine release and contamination magnitudes and to estimate projected exposures to onsite and offsite population.

C. CORRECTIVE ACTIONS The reactor shall be shut down. Physical barriers to contain the radioactive material shall be maintained or implemented where necessary. Installed cleanup systems may be used to reduce the release of radioactive material. Further corrective actions shall be provided as needed for this emergency class.

D. PROTECTIVE ACTIONS The Protective Actions for this emergency classification are based upon a Guide of 1 rem whole body and 5 rem thyroid to members of the general public onsite and MSTR staff. Rev.

Accountability of personnel following a building evacuation shall be done by the SRO on Duty who will check that the facility is clear of personnel. Further protective actions shall be provided as needed for this emergency class.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 504 TITLE: EMERGENCY PROCEDURES FOR A SITE AREA EMERGENCY Revised: July, 31, 2017 Page 2 of 2 SOP 504 Table I Emergency Class: Site Area Emergency Action Levels Purpose

1) Actual or projected radiological a) to assure that response centers are effluents at site boundary calculated manned, to produce a dose of 375 mrem whole body accumulated in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. b) to assure that monitoring teams are dispatched,
2) Actual or projected radiation levels at the site boundary of 100 mrem/hr for c) to assure that personnel required for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> whole body or 500 mrem evacuation of onsite areas are at duty thyroid dose. stations, d) to provide consultation with offsite authorities, and e) to provide information for the public through offsite authorities.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 505 TITLE: ENHANCED REACTOR SECURITY Revised: July 31, 2017 Page 1 of 1 A. PURPOSE Rev.

To establish procedures in the event of any disorder on the campus of Missouri S&T such as civil strife or demonstrations which could for any reason have an effect on the security of the Reactor Facility.

B. PROCEDURE

1. The reactor shall be shutdown and the magnet power key secured in its normal storage location.
2. All entrances to the building shall be locked 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day. Only persons who can be identified and have a need to be in the building will be admitted.
3. Access to the main office will be allowed only after visually observing the person to ensure no unauthorized people are present.
4. The SRO on Duty shall lock the Security Door.
5. The SRO on Duty will notify the Missouri S&T Police. Rev.
6. The reactor staff shall not enter into any confrontation with any persons, except to provide for personal safety.
7. A credible security threat effecting the reactor facility exists and an Unusual Event Rev.

is initiated as defined in Table 4.1 of the Reactor Emergency Plan.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 506 TITLE: BOMB THREAT Revised: July 31, 2017 Page 1 of 2 A. PURPOSE To establish procedures for handling of a bomb threat to the reactor building.

B. PROCEDURE

1. Attempt to obtain as much of the information on the attached Campus Bomb Threat Form as possible.
2. If the reactor is in operation at the time of the call, the person receiving the call should inform the SRO on Duty immediately and the Operator shall: Rev.
a. scram the reactor,
b. secure the magnetic power key in its usual storage place, and
c. initiate a building evacuation in accordance with SOP 501.
3. If the reactor is not in operation at the time of the call, the person receiving the call should notify the Reactor Manager (or SRO in his absence). The Reactor Manager Rev.

(or his representative) shall initiate a building evacuation in accordance with SOP 501.

4. The incident shall be reported immediately to the Missouri S&T Police by the person Rev.

who received the call via a telephone in the Physics Building.

5. The Reactor Staff should not attempt to find an alleged bomb. The SRO on Duty Rev.

should be on the lookout for unusual packages as he checks that everyone has evacuated the building.

6. The Missouri S&T Police will assume the responsibility for the emergency from this Rev.

point.

7. The Reactor Director and the Chief of Missouri S&T Police shall decide when the Rev.

emergency no longer exists.

8. The receipt of a bomb threat initiates the Unusual Event emergency class as defined Rev.

in Table 4.1 of the Reactor Emergency Plan.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 506 TITLE: BOMB THREAT Revised: July 31, 2017 Page 2 of 2 BOMB THREAT CHECKLIST Exact time of call ______________________________________________________________

Exact words of caller QUESTIONS TO ASK

1. When is the bomb going to explode? ___________________________________
2. Where is the bomb? ________________________________________________
3. What does it look like? ______________________________________________
4. What kind of bomb is it? ____________________________________________
5. What will cause it to explode? ________________________________________
6. Did you place the bomb? ____________________________________________
7. Why? ___________________________________________________________
8. Where are you calling from? _________________________________________
9. What is your address? ______________________________________________
10. What is your name? ________________________________________________

CALLERS VOICE (circle)

Calm Disguised Nasal Angry Broken Stutter Slow Sincere Lisp Rapid Giggling Deep Crying Squeaky Excited Stressed Accent Loud Slurred Normal If voice is familiar, whom did it sound like? ________________________________________

Were there any background noises? ______________________________________________

Remarks:

Person receiving call: ___________________________________________________________

Telephone number call received at: _______________________________________________

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 507 TITLE: EMERGENCY PROCEDURES - ADMINISTRATIVE RESPONSIBILITIES Revised: August 2, 2017 Page 1 of 5 A. PURPOSE To establish responsibilities for administrative members responsible for coping with a reactor related emergency as set forth in the MSTR Emergency Plan.

B. PRECAUTIONS, PREREQUISITES, LIMITATIONS

1. The duties listed under each official are general in description and are considered fundamental to the protective action to be taken in the event of a reactor-related Rev.

Alert (see SOP 503) or Site Area Emergency (see SOP 504).

2. The specific duties of each office will be directed by the Emergency Support Center (ESC) Director depending upon the nature of the radiological emergency. The ESC Director may delegate any responsibilities to any individual who has sufficient experience and knowledge to handle such responsibilities.
3. The title "Vice Chancellor" used throughout refers to the Vice Chancellor for Rev.

Finance and Operations.

4. The title "Chair" used throughout refers to the Chair of Mining and Nuclear.

C. PROCEDURE

1. Chancellor - If offsite consequences are expected the Chancellor will be responsible for:
a. providing direction and coordination for the Control Group.
b. notifying the University of Missouri President and requesting University- Rev.

Wide assistance, as needed.

c. acting as Administrative Spokesman responsible for communications with the news media and city officials in the absence of both the Vice Chancellor and the Chair.
2. Vice Chancellor - If offsite consequences are expected the Vice Chancellor will be responsible for:
a. assuming the duties of the Chancellor in his or her absence.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 507 TITLE: EMERGENCY PROCEDURES - ADMINISTRATIVE RESPONSIBILITIES Revised: August 2, 2017 Page 2 of 5

b. functioning as administrative spokesman responsible for communication to the Missouri S&T Communications staff for release of news and information to city officials.
c. assisting in the coordination of Control Group activities in the planning and preparation phase.

Rev.

d. advising the Chancellor on problems relating to insurance and liability.
3. Chair of Mining and Nuclear
a. Assumes the duties of administrative spokesman responsible for communication with the news media and city officials in the absence of the Vice Chancellor.
b. Reports changes in federal and state agency policy with the respect to radiological emergency preparedness to the Reactor Director.
4. Radiation Safety Officer (RSO)
a. Implements the action needed to isolate the affected area. Establishes controlled access point and authorizes entry.
b. Analyzes data collection on radiation levels and reports conditions (with recommended actions) to the ESC Director.
c. Provides assessment of the situation at the site of the emergency to the ESC director.
d. Authorizes emergency personnel exposures for volunteers in excess of normal exposure limits.
e. Reports to the ESC Director if an off-campus evacuation is determined to Rev.

be necessary after such an assessment has been made.

f. Establishes written procedures for data collection, (air, water, soil, etc.)

dose rate and contamination levels. These procedures will provide for decontamination and monitoring equipment, their advisability and use.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 507 TITLE: EMERGENCY PROCEDURES - ADMINISTRATIVE RESPONSIBILITIES Revised: August 2, 2017 Page 3 of 5

5. Emergency Support Center Director (i.e. Missouri S&T Police Chief) Rev.
a. Initiates immediate action to isolate the affected area of campus.
b. Requests assistance from the following local emergency support organizations Rev.

via 911 as necessary:

  • Rolla City Police
  • Rolla Fire Department
  • Phelps County Hospital
c. communicating with and requesting assistance from the following State and Federal Agencies as required:

(573) 368-2345

  • U.S. Nuclear Regulatory Commission, Headquarters Operation Center:

(301) 951-6550

  • NRC Duty Officer (24 hr.):

(301) 816-5100 or (301) 951-0550.

  • Missouri State Emergency Management Agency:

(573) 751-2748

  • Missouri Bureau of Environmental Health:

(573) 751-6160 or (573) 751-4674 (24 hrs)

(573) 634-2436

  • Radiation Emergency Assistance Center (Oak Ridge, TN):

(865) 576-3131 or (865) 481-1000 (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />).

  • Rolla Emergency Management Agency:

(573)364-1213

d. Directs all assessment activities.
e. Authorizes voluntary radiation exposures up to 25 rem when immediate action is essential.

Rev.

f. Reports to the Vice Chancellor if an off-campus evacuation is determined to be necessary, and advises him as to further evacuation or possibility of recovery from the emergency.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 507 TITLE: EMERGENCY PROCEDURES - ADMINISTRATIVE RESPONSIBILITIES Revised: August 2, 2017 Page 4 of 5

g. Coordinates all off-campus activities until relieved of this responsibility by supervisors.
h. Reviews and approves proposed changes to the Emergency Plan.
6. Emergency Support Center Manager (i.e. Reactor Manager)

Rev.

a. Evaluates the need for activating the ESC following any radiation emergency.
b. Informs (or delegates to inform) necessary personnel that an emergency exists.
c. Coordinates and supervises the activities of the Emergency Squad in concurrence with ESC director.
d. Supervises efforts to terminate a radiation release.
e. Maintains a log of significant events. Rev.
f. Evaluates campus and facility surveys for protection of personnel.
g. Ensures organization and training of reactor staff for emergency conditions.
h. Reviews the Emergency Plan on an annual basis and makes needed changes.
i. Ensures adequate procedures exist and are reviewed at periodic intervals to cope with emergency conditions.

Rev.

j. Evaluates foreseeable hazards and determines corrective actions.
7. Campus Health Physicist
a. Assumes the duties of the RSO in his absence.
b. Makes all measurements to assess activities in order to establish the extent of the affected area.
c. Supervises and collects data on the radiological emergency.
d. Establishes safety limits and an evacuation zone for emergency workers and the general public.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 507 TITLE: EMERGENCY PROCEDURES - ADMINISTRATIVE RESPONSIBILITIES Revised: August 2, 2017 Page 5 of 5

e. Provides direction in the decontamination of personnel.
f. Reviews changes in Federal and State Agency Policy with respect to radiological emergencies and recommends to the Reactor Manager necessary changes for compliance.
g. Inventories the emergency box on an annual basis and checks all equipment therein for proper operation.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 508 TITLE: TORNADO THREAT Revised: July 31, 2017 Page 1 of 1 A. PURPOSE Rev.

To establish procedures for handling of tornadoes and tornado warnings in vicinity of the reactor building.

B. TORNADO IN IMMEDIATE VICINITY

1. SCRAM reactor.
2. Remove the magnet power key. Rev.
3. Announce over the building PA that all personnel are to immediately proceed to the rear of mid-level basement due to the tornado threat.
4. Go to the rear of the mid-level basement area near the sink for shelter and wait for the tornado to pass.
5. If convenient, shelter may be sought in the subbasement area. Rev.
6. Make certain physical security is re-established as soon as possible after tornado has passed.
7. The report or observation of a severe tornado that directly affects the reactor initiates Rev.

the Unusual Event emergency class as defined in Table 4.1 of the Reactor Emergency Plan.

C. TORNADO WARNING

1. Complete normal reactor shutdown if time permits, otherwise go to Step 1 above.

The reactor is to shutdown when a tornado warning is in effect.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 509 TITLE: FIRE Revised: July 31, 2017 Page 1 of 1 A. PURPOSE Rev.

To establish procedures for the proper handling of a fire in the reactor building.

B. PROCEDURE

1. SCRAM Reactor.

Rev.

2. Remove the magnet power key.
3. Pull fire alarm station located to the left of front office door. (NOTE: There is another fire alarm station on wall to the left of the mid-basement exterior door.)
4. Evacuate building per SOP 501.

Rev.

5. Call 911 for Fire.
6. Make sure physical security is re-established as soon as possible after fire is out.
7. A prolonged fire not extinguished within 15 minutes initiates an Unusual Event Rev.

emergency class as defined in Table 4.1 of the Reactor Emergency Plan.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 510 TITLE: EARTHQUAKE Revised: July 31, 2017 Page 1 of 1 A. PURPOSE Rev.

To establish procedures for handling of an earthquake in the immediate vicinity of the reactor building.

B. PROCEDURE

1. SCRAM the reactor.
2. Remove the magnet power key.
3. If danger is immediate, personnel should seek cover under tables, desks or in strong doorways away from glass, heavy bookcases or shelves.
4. If time permits, personnel should evacuate building to open area east of Reactor Building.
5. Prior to re-entering the building, conduct a radiation exposure rate survey to identify possible abnormal radiation levels.
6. Re-establish physical security as soon as possible.
7. Be prepared for "aftershocks" that may pose additional danger.
8. A severe earthquake felt in the facility initiates the Unusual Event emergency class Rev.

as defined in Table 4.1 of the Reactor Emergency Plan.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 511 TITLE: RESPONSE TO MISSING SPECIAL NUCLEAR MATERIAL Revised: July 31, 2017 Page 1 of 2 A. PURPOSE To establish procedures for the proper initial response to missing special nuclear material (SNM). SNM includes reactor fuel, PuBe sources, and fission chambers.

B. PRECAUTIONS, PREREQUISITES, LIMITATIONS

1. SOP 112, "Fuel Management" establishes provisions for the periodic inventory of all SNM housed at the reactor facility.
2. Any threats, implied or otherwise, concerning the potential theft of SNM must be taken very seriously. Any such threats shall immediately be reported to the Reactor Director.

C. PROCEDURE

1. If any reactor fuel is discovered missing, the following persons/agencies shall be contacted immediately (refer to the emergency call list in SOP 501).
a. Reactor Manager
b. Reactor Director
c. Missouri S&T Police Rev.
d. Vice Provost & Dean, Engineering and Computing
e. Chancellor
f. NRC, Duty Officer (24 hr.) Rev.
g. NRC, Project Manager
h. Campus Health Physicist Note: DOE must be informed in writing as soon as possible and given all pertinent information, i.e. missing fuel serial numbers, total quantity and type of stolen SNM. The fuel custodian should be responsible for this contact.
2. The Reactor Manager and/or staff will immediately try to ascertain the breech of security and cordon off the reactor building of all non-essential persons. Care should be taken not to destroy any physical evidence and latex gloves should be worn by persons in the building.
3. The Missouri S&T Police will direct the investigation and necessary follow up actions Rev.

upon arrival at the facility.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 511 TITLE: RESPONSE TO MISSING SPECIAL NUCLEAR MATERIAL Revised: July 31, 2017 Page 2 of 2

4. The Campus HP should be summoned to check for possible contamination in and outside of building. The HP should verify that the campus area in proximity of the reactor building is free of contamination.
5. If a fission chamber or PuBe source is found missing, the following persons/agencies shall be immediately notified:
a. Reactor Manager
b. Reactor Director
c. Missouri S&T Police Rev
d. Campus Health Physicist 10CFR shall then be consulted to determine the NRC reporting requirements based on the amount and type of material missing.

Revised By: Anthony Alchin Approved By: William Bonzer

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 601 TITLE: HANDLING OF RADIOACTIVE SAMPLES Revision: July 31, 2017 Page 1 of 2 A. PURPOSE To ensure that reactor staff, students, and experimenters handle radioactive materials safely and with proper precautions.

B. PRECAUTIONS, PREREQUISITES, OR LIMITATIONS

1. Wear appropriate protective clothing (e.g. glasses, gloves, etc.) when handling radioactive materials.
2. Use tongs or other handling devices to reduce exposure whenever possible.
3. Have at least one portable radiation survey meter available and operational when working with radioactive samples.
4. If any problems or questions arise, contact a member of the reactor staff of the Health Physicist.

C. PROCEDURE To remove samples from the glove box or reactor pool:

1. Before removing a radioactive sample from the glove box or pool, survey the sample and the sample holding devise to make certain that the dose rate is acceptable.
2. The following dose rate restrictions apply:
a. Samples reading greater than 100 mrem/hr at 1 foot may only be handled with permission from the Health Physicist. In such instances, the Health Physicist (or their designee) shall be present to monitor dose rates.
b. Samples reading 100 mrem/hr or less at 1 foot may be handled by the reactor staff.
c. Samples reading between 5 mrem/hr and 50 mrem/hr at 1 foot may be handled by students or other experimenters under the direct supervision of the reactor staff or health physics staff.
d. Samples reading less than 5 mrem/hr at 1 foot may be handled by students or other experimenters with the permission of the reactor staff.

Revised By: Anthony Alchin Approved By: William Bonzer

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 601 TITLE: HANDLING OF RADIOACTIVE SAMPLES Revision: July 31, 2017 Page 2 of 2
3. After the sample has been removed from the pool or glove box, take it to the radioactive work area for preparation. Keep the sample as far away from your body as possible. Use tongs or tweezers to carry the sample as appropriate. Minimize your exposure time to the extent possible.
4. Remove the sample from the stringer of sample holder and dispose of radioactive wastes in accordance with SOP 600, General Health Physics.
5. After sample counting or when the experiment is completed, place the sample in an envelope or other suitable container labeled with the following:
a. Radioactive Materials tape or label
b. Experimenters name
c. Date
d. Contents (isotope, sample description, etc.)
e. 1 foot radiation level (mrem/hr)
f. IRF number
g. Class number, if applicable Store the sample in the reactor bay safe.
6. Check all areas where radioactive materials have been used with a portable GM detector to ensure that these areas are free of contamination. If contamination is detected, notify the reactor staff. If necessary, the HP will take swipes and count them.
7. Clean up and decontaminate the radioactive work area, if necessary.
8. Check hand, feet, and clothing for contamination with a survey meter and/or at the frisker after handling radioactive samples.
9. Generally clean up the work area and return equipment to its proper location.
10. Make certain that survey meters are turned off.
11. Wash your hands thoroughly after having worked with radioactive material even when gloves are worn.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 602 TITLE: ENTRY INTO A HIGH RADIATION AREA Revision: July 31, 2017 Page 1 of 2 A. PURPOSE To ensure that personnel do not enter into a High Radiation Area by accident or without permission.

B. PRECAUTIONS, PREREQUISITES, OR LIMITATIONS A High Radiation Area could exist in the lower level of the Reactor Building when the beam port or thermal column is open during reactor operation or when an exposed source produces a radiation level at which an individual might receive a deep-dose equivalent of 100 mrem in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at a distance of 1 foot from the radiation source or from any surface that the radiation penetrates.

C. PROCEDURE The SRO on Duty or Health Physicist shall be responsible for determining when a High Rev.

Radiation Area exists and will follow the following procedures:

1. Before the status of an area is changed to a High Radiation Area, the SRO on Duty, the Health Physicist, or their designee shall, by personal survey, ensure that no one is present in the area to become a High Radiation Area. An announcement to that effect will be made over the building public address system.
2. The doors leading to the High Radiation Area shall be locked and access will be controlled by the SRO on Duty or Health Physicist.
3. The SRO on Duty or Health Physicist shall assure the proper "High Radiation sign is on the doors.
4. The SRO on Duty or Health Physicist shall give permission for anyone to enter the High Radiation Area and shall be responsible for ensuring that each person is properly equipped with personnel monitoring devices.
5. Persons entering a High Radiation Area established by opening the beamport or thermal column shall wear neutron and gamma sensitive dosimeters. The SRO on Duty will be responsible for entering the persons name and time in and out of the area into the permanent log book.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 602 TITLE: ENTRY INTO A HIGH RADIATION AREA Revision: July 31, 2017 Page 2 of 2

6. When a door leading to a High Radiation Area is unlocked, the SRO on Duty or Health Physicist shall designate a member of the reactor staff to guard the door to assure that no one enters the area without proper warning or protection.
7. After the High Radiation Area designation is rescinded, the SRO on Duty or Health Physicist or his designee shall ensure, by personally monitoring the area, that the radiation levels are less than 100 mrem/hour. Then an announcement that the High Radiation Area has been rescinded will be made over the building public address system.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 800 TITLE: ANNUAL CHECKLIST Complete Revision: August 2, 2017 Page 1 of 10 Date Commenced: Date Completed:

Total Hours on Hour Meter:

1. Log and Linear Drawer Calibration a) Log and Linear Log/Period Recorder (1) Clean & Lube chassis as needed (): _____

(2) Speed checked (1 per 5 minutes) (): _____

b) LOW CIC Voltage Rundown (1) Set Point at A4TP1: VDC x 200 = VDC (2) Verify Rundown Initiated (): _____

(3) Verify Alarms Received (): _____

c) 120% Full Power Rundown (1) Set Point:  %

(2) Verify Rundown Initiated (): _____

(3) Verify Alarms Received (): _____

d) Log and Linear Detector/Cable Resistance Check (Cables should read about 1010 .)

(1) Signal Cable Resistance: M (2) High Voltage Cable Resistance: M (3) Comp. Voltage Cable Resistance: M e) Drawer Alignment - Perform the steps listed in the following sections of the drawer Instruction Manual:

(1) Low Voltage Power Supply Check Complete (Sec. 4.3.1):

i. A13TB1-1 to Common reading (+15.00):

ii. A13TB1-3 to Common reading (-15.00):

(2) High Voltage and Compensating Voltage Check

i. Low Voltage Set Point at J6: VDC ii. Low Voltage Set Point at A4TP10-A4TP1: VDC iii. NON-OPERATE LED on (): _____

iv. Reset High Voltage (J6): VDC

v. High Voltage (A4TP10-A4PP1): VDC vi. NON-OPERATE LED off (): _____

vii. Compensating Voltage at J7: VDC viii. Compensating Voltage at A5TP10-A5TP1: VDC Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 800 TITLE: ANNUAL CHECKLIST Complete Revision: August 2, 2017 Page 2 of 10 (3) Log Displays Pico-amp Expected Tolerance for Initial Date Log Bargraph Log Digital Log Recorder Current Readings Reading 8 pA 1.0E-5% 4.0 E-6%-2.5 E-5%

86 pA 1.0E-4% 4.0 E-5%-2.5 E-4%

820 pA 1.0E-3% 7.0E-4%--1.4E-3%

10 nA 1.0E-2% 7.0E-3%--1.4E-2%

80 nA 1.0E-1% 7.0E-2%--1.4E-0%

800 nA 1.0E -0% 7.0E-1%--1.4E-0%

8 A 1.0E+1% 7.0E-0%--1.4E+1%

80 A 1.0E+2% 7.0E+1%--1.4E+2%

(4) Period Alignment & displays (section 4.3.4)

i. 4.3.4.1- Slope/voltage/sec: ________

ii. 4.3.4.2- Voltage reading, with stable source, at A1TP2 & A1TP10 (0.909+/-0.02): ________

iii. 4.3.4.3- Voltage at A1TP2 & A1TP10 with 3 sec period: ________

Settings Period Bargraph Period Digital Period Recorder Initial Date Infinity ()

3 Sec (5) Linear Displays Tolerance for Linear Pico-amp True Expected Linear Digital Voltage True Expected Bargraph Initial Date Current Readings Display Tolerances Readings Display 8 A 8%-12% 10% 0.7V-0.9V 16 A 18%-22% 20% 1.5V-1.7V 24 A 28%-32% 30% 2.3V-2.5V 32 A 38%-42% 40% 3.1V-3.3V 40 A 48%-52% 50% 3.9V-4.1V 48 A 58%-62% 60% 4.7V-4.9V 56 A 68%-72% 70% 5.5V-5.7V 64 A 78%-82% 80% 6.3V-6.5V 72 A 88%-92% 90% 7.1V-7.3V 80 A 98%-102% 100% 7.9V-8.1V 88 A 108%-112% 110% 8.7V-8.9V 96 A 118%-122% 120% 9.3V-9.7V 100 A 123%-127% 125% 9.9V-10.1V Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 800 TITLE: ANNUAL CHECKLIST Complete Revision: August 2, 2017 Page 3 of 10 f) Isolated Outputs check (4.3.9) (): _____

g) Keypad switch test Test Switch Indication Initial Date Log:  %

1 mA Lin:  %

Log:  %

0.1 uA Per: -100, +100 sec (): _____

Lin: 0+/- 1% (): _____

10 pA Log:  %

3 SEC Per: 3.0 +/- 0.1 sec (): _____

NON-OPER LED On (): _____

Rising Linear Level (): _____

LINEAR TEST Trip #4:  %

Rising Period Level (): _____

Trip #1: sec PERIOD TEST Trip #2: sec Trip #3: sec LOG TEST Rising Log Level (): _____

h) Cables Reconnected (): _____

Independent Verification of Cable Connections (): _____ Initial:

i) Log and Linear Channel Calibration Complete: Initial: _____ Date:

2. Linear Power Channel a) Linear Power Supply Clean chassis as needed (): _____

b) Linear Power Supply Voltage Display Meter Display Output Voltage Initial Date HIGH VOLTAGE COMPENSATING VOLTAGE Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 800 TITLE: ANNUAL CHECKLIST Complete Revision: August 2, 2017 Page 4 of 10 c) Linear Recorder (1) Lube & Clean Chassis as needed (): _____

(2) Speed check (1 / 2 minutes) (): _____

d) Linear Calibration Note: From 10-5 to 10-8, the overall accuracy should be better than 2% of full scale. From 10-9 to 10-10 the overall accuracy should be better than 4% of full scale. Any instrument found to be out of calibration should be realigned in accordance with procedures.

Pico-amp Meter Recorder Initial Date Current Acceptable Reading Actual Reading Acceptable Reading Actual Reading 60 A 58 A - 62 A 58% - 62%

6 A 5.8 A - 6.2 A 58% - 62%

600 nA 580 nA - 620 nA 58% - 62%

60 nA 58 nA - 62 nA 58% - 62%

6 nA 5.6 nA - 6.4 nA 56% - 64%

600 pA 560 pA - 640 pA 56% - 64%

200 pA 160 pA - 240 pA 16% - 24%

e) Linear CIC Detector/Cable Resistance Check (Cables should read about 1010 .)

(1) Signal Cable Resistance: M (2) High Voltage Cable Resistance: M (3) Comp. Voltage Cable Resistance: M f) Cables Reconnected (): _____

Independent Verification of Cable Connections (): _____ Initial:

g) Linear Channel Calibration Complete: Initial: _____ Date:

3. Log Count Rate Channel a) Log Count Rate Recorder (1) Lube & Clean Chassis as needed (): _____

(2) Speed check (1 / 2 minutes) (): _____

b) Fission Chamber Pre-amp (1) Clean Chassis as needed (): _____

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 800 TITLE: ANNUAL CHECKLIST Complete Revision: August 2, 2017 Page 5 of 10 c) Log Count Rate Channel Calibration Note: All readings should give 0.7 to 1.4 ratio of true-to-observed readings.

Pulse Generator Meter Recorder Initial Date 10 100 1,000 10,000 d) High Voltage (350 VDC to 450 VDC) VDC h) Linear CIC Detector/Cable Resistance Check (Cables should read about 1010 .)

(1) Signal Cable Resistance: M (2) High Voltage Cable Resistance: M (3) Fission Chamber Cable Resistance: M i) Cables Reconnected (): _____

Independent Verification of Cable Connections (): _____ Initial:

j) Log Count Rate Channel Calibration Complete: Initial: _____ Date:

4. Safety Amplifier System a) Safety Channel System Cable Resistance Check (Cables should read about 1010 .)

(1) UIC 1 Signal Cable Resistance: M (2) UIC 1 High Voltage Cable Resistance: M (3) UIC 2 Signal Cable Resistance: M (4) UIC 2 High Voltage Cable Resistance: M b) Safety Amplifier HV Tests

i. H.V. 1 Output Voltage VDC ii. Monitor H.V. 1/100 VDC iii. H.V. 2 Output Voltage VDC iv. Monitor H.V. 2/100 VDC Revised By: Anthony Alchin Approved By: William Bonzer
      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 800 TITLE: ANNUAL CHECKLIST Complete Revision: August 2, 2017 Page 6 of 10 c) H.V. 1 Failure Test

i. Trip Point Setting VDC ii. SCRAM occurred (Y/N) _____

iii. Magnet Power Supply SCRAM Light Illuminated (Y/N) _____

iv. Reset H.V. to 300 VDC (Y/N) _____

d) H.V. 2 Failure Test

i. Trip Point Setting VDC ii. SCRAM occurred (Y/N) _____

iii. Magnet Power Supply SCRAM Light Illuminated (Y/N) _____

iv. Reset H.V. to 300 VDC (Y/N) _____

e) NIM Bin Power Supply

i. Output Voltage Readings
i. + 24 VDC VDC ii. 24 VDC VDC iii. + 12 VDC VDC iv. 12 VDC VDC
v. + 6 VDC VDC vi. 6 VDC VDC ii. Output Voltage Readings
i. 150% Full Power Annunciator (Y/N) _____

ii. Audible Alarm (Y/N) _____

iii. SCRAM Occurred (Y/N) _____

iv. Power Restored (Y/N) _____

f) Safety Amplifier Current Tests

i. Safety Amplifier #1 Applied Current Accepted Digital Digital Display Accepted Bargraph Bargraph Display Initial Date Digital Display Reading Display Reading 6.7 nA 9% - 11% 7% - 13%

13.2 nA 19% - 21% 17% - 23%

19.8 nA 29% - 31% 27% - 33%

26.4 nA 39% - 41% 37% - 43%

33.0 nA 49% - 51% 47% - 53%

39.6 nA 59% - 61% 57% - 63%

46.2 nA 69% - 71% 67% - 73%

52.8 nA 79% - 81% 77% - 83%

59.4 nA 89% - 91% 87% - 93%

66.0 nA 99% - 101% 97% - 103%

72.6 nA 109% - 111% 107% - 113%

79.2 nA 119% - 121% 117% - 123%

85.8 nA 129% - 131% 127%- 133%

92.4 nA 139% - 141% 137% - 143%

99.0 nA 149% - 152% 147% - 153%

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 800 TITLE: ANNUAL CHECKLIST Complete Revision: August 2, 2017 Page 7 of 10 ii. Safety Amplifier #1 Applied Current Accepted Digital Digital Display Accepted Bargraph Bargraph Display Initial Date Digital Display Reading Display Reading 6.7 nA 9% - 11% 7% - 13%

13.2 nA 19% - 21% 17% - 23%

19.8 nA 29% - 31% 27% - 33%

26.4 nA 39% - 41% 37% - 43%

33.0 nA 49% - 51% 47% - 53%

39.6 nA 59% - 61% 57% - 63%

46.2 nA 69% - 71% 67% - 73%

52.8 nA 79% - 81% 77% - 83%

59.4 nA 89% - 91% 87% - 93%

66.0 nA 99% - 101% 97% - 103%

72.6 nA 109% - 111% 107% - 113%

79.2 nA 119% - 121% 117% - 123%

85.8 nA 129% - 131% 127%- 133%

92.4 nA 139% - 141% 137% - 143%

99.0 nA 149% - 152% 147% - 153%

g) Cables Reconnected (): _____

Independent Verification of Cable Connections (): _____ Initial:

h) Safety Amplifier System Calibration Complete: Initial: _____ Date:

5. Temperature Channel Note: All readings should be +/- 2 °F.

a) Verification of Temperature Readings Date:

Thermocouple Thermocouple Thermocouple Thermometer Thermometer Thermometer Temperature Range (take one reading from Initials Initials Initials

  1. 1 #2 #3 each temperature range) 60 F - 70 F 70 F - 80 F 80 F - 90 F 90 F - 125 F 125 F - 135 F 135 F - 145 F Revised By: Anthony Alchin Approved By: William Bonzer
      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 800 TITLE: ANNUAL CHECKLIST Complete Revision: August 2, 2017 Page 8 of 10 i) Temperature > 135 °F RWP Test Thermocouple #1 Thermocouple #2

> 135 °F Trip Temperature

> 135 °F Annunciator ()

Audible Alarm ()

RWP at Trip ()

Initial: _____ Date:

j) Low Temperature Alarm Temperature Thermocouple #1 Thermocouple #2 Thermocouple #3 Initial Date

< 60 °F Rec Alarm ()

k) Cables Reconnected (): _____

Independent Verification of Cable Connections (): _____ Initial:

l) Safety Amplifier System Calibration Complete: Initial: _____ Date:

6. Regulated Power Supply a) Clean chassis as needed (): _____

b) Mode set for Line Conditioner (): _____

Additional comments:

Complete: Initial: _____ Date:

7. Conductivity Bridge a) Check and clean chassis as needed (): _____

Additional comments:

Complete: Initial: _____ Date:

8. Rod Indicator Calibration Indicator Rod 1 Rod 2 Rod 3 Reg Rod 1

6 12 18 24 Rod Speeds (in/min)

Complete: Initial: _____ Date:

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 800 TITLE: ANNUAL CHECKLIST Complete Revision: August 2, 2017 Page 9 of 10

9. Fire Alarm Check a) Cleaned system containers as needed (): _____

b) Checked batteries (): _____

c) Checked pull stations (): _____

d) Checked smoke detectors (): _____

e) Check beam smoke detector (): _____

f) Audibles & Visuals (): _____

g) Monitoring Station (): _____

Additional comments:

Complete: Initial: _____ Date:

10. Security System Check a) Door Sensors (): _____

b) Motion Detectors () _____

c) Tamper & 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> circuits() _____

d) Duress Alarm () _____

e) Battery () _____

f) High Radiation () _____

g) Low Pool Water () _____

Additional Comments:

Complete: Initial: _____ Date:

11. Public Address System a) Clean chassis as needed (): _____

Additional comments:

Complete: Initial: _____ Date:

12. Hand and Foot Monitor a) Clean chassis as needed (): _____

b) Perform Source Check with (): _____

Additional comments:

Complete: Initial: _____ Date:

13. Portal Detector a) Clean chassis as needed (): _____

b) Perform Source Check with (): _____

Additional comments:

Complete: Initial: _____ Date:

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 800 TITLE: ANNUAL CHECKLIST Complete Revision: August 2, 2017 Page 10 of 10

14. Constant Air Monitor a) Clean chassis as needed (): _____

b) Perform Source Check with (): _____

Additional comments:

Complete: Initial: _____ Date:

15. Power Calibration (SOP 816)

Complete: Initial: _____ Date:

16. RAM Calibration (SOP 655)

Complete: Initial: _____ Date:

Annual Calibration Comments:

I have reviewed the results of this Annual Check on this dae and discussed any problems and/or errors with the operating staff.

Comments:

Reactor Manager Date Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 810 TITLE: WEEKLY CHECK Revised: August 9, 2017 Page 1 of 11 A. PURPOSE To ensure the proper operation of the control and safety-related instruments of the reactor and to functionally test the Physical Security Alarm System.

B. PRECAUTIONS, PREREQUISITES, OR LIMITATIONS

1. The Weekly Check should be completed on the first working day of each week the reactor is to be operated.
2. The security system, pool conductivity, and Low Pool Water scram shall be checked weekly but under no circumstance shall the surveillance interval exceed 14 days. The remaining portion of the checklist may be omitted if the reactor will not be operated that week.
3. The weekly check should be performed by a licensed operator, or a student/trainee under the direct supervision of a licensed operator.
4. Complete the Weekly Surveillance Checklist form and forward it to the Reactor Manager for review and signature. Any abnormalities, problems, or out of service equipment should be brought to the attention of the Reactor Manager.
5. The following steps will list the Shim/Safety Rods as rods and the Regulating Rod as reg rod.

C. PROCEDURE

Select the Reactor Bridge Station on the Building Intercom, check the PA system, perform a core check, install the neutron source, turn on and date the Source Range, Linear, and Log/Period recorders. Turn on the core camera and select core on the monitor selector. Obtain Magnet Power Key and turn on magnet power. Reset the Scram and console resets.

1. Rod Prohibits 1.1. Recorders Off - Verify that the rods will not withdraw if any one of 4 primary recorders is turned off. Rev.

Repeat the following steps for the 1) Source Range recorder, 2) Linear recorder, and

3) Log/Period recorder.
a. Turn off the recorder.
b. Attempt to withdraw rods. Verify rods cannot be withdrawn.
c. Verify that the Recorder Off annunciator illuminates and that the console audible alarm is actuated.
d. Turn the recorder on, reset the annunciator.
e. Verify the rods can be withdrawn.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 810 TITLE: WEEKLY CHECK Revised: August 9, 2017 Page 2 of 11 Use the following steps for the Temperature/CAM Recorder:

Rev.

a. Press Memory Stop and select Mem+Math.
b. Attempt to withdraw rods. Verify rods cannot be withdrawn.
c. Verify that the Recorder Off annunciator illuminates and that the console audible alarm is actuated.
d. Press Memory Start, reset the annunciator.
e. Verify the rods can be withdrawn.
f. Turn off the recorder.
g. Attempt to withdraw rods. Verify rods cannot be withdrawn.
h. Verify that the Recorder Off annunciator illuminates and that the console audible alarm is actuated.
i. Turn recorder on and verify recording, reset the annunciator.
j. Verify the rods can be withdrawn.

1.2. Source Range < 2 CPS

a. Remove source from holder and/or withdraw fission chamber until Source Range CR <2 alarm is received. Record value at which the alarm occurs from recorder.
b. Attempt to withdraw rods. Verify rods cannot be withdrawn.
c. Verify that the CR <2 cps annunciator illuminates and that the console audible alarm is actuated.
d. Insert source and/or insert the fission chamber to the insert limit. Reset annunciator.

1.3. Inlet Temperature Above 135 Degrees

a. Plug the thermocouple simulator into the test input jack for one of the inlet thermocouples (thermocouple #1 or #3). (Randomly alternate which inlet thermocouple is checked from week to week.) Record the thermocouple tested.
b. Slowly adjust the simulator to a higher setting, until the "Inlet Temperature Above 135°F" annunciator and audible alarm are energized.
c. Attempt to withdraw rods. Verify rods do not withdraw.
d. Record the temperature displayed on the recorder when the "Inlet Temperature Above 135°F" trip occurs.
e. Disconnect the thermocouple simulator from the thermocouple test input jack.
f. Reset annunciator.
g. Verify rods can be withdrawn.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 810 TITLE: WEEKLY CHECK Revised: August 9, 2017 Page 3 of 11 1.4. Shim Rods Below Shim Range Withdraw rods between 1/2 inch and 3 inches and attempt to withdraw the reg rod.

Note that the reg rod will withdraw just far enough to clear the insert limit light.

Attempt to withdraw the rods. Note that further withdrawal cannot be made. Insert all rods to the insert limit and record these results. Verify the rods can be withdrawn.

2. Rundowns 2.1. Radiation Area Monitoring (RAM) System
a. Withdraw rods to 3 inches.
b. Announce "The Building Alarm will sound. This is a test do not evacuate the building." on the Building PA System.
c. Have a second person check that the audible and visual alarms are functional on the remote meters located near the detectors. Using the Bridge RAM check source switch (NORMAL green light), record the value at which the High Area Radiation rundown and Building Evacuation Alarm occur. Check the automatic reset of the RAM, reset the Building Alarm (Scram Reset Button), acknowledge the annunciator, depress Rundown Reset and Annunciator Reset. Record the value of alarms.
d. Repeat step c for the Demin RAM and Experiment Room RAM except for the Building Evacuation Alarm.
e. Verify that the Evacuation Alarm actuated between 20 mrem/hr and 28 mrem/hr.
f. Verify that the High Area Radiation alarms actuated between 10 mrem/hr and 15 mrem/hr.
g. Upon completion of testing announce "Test Complete. Acknowledge all further alarms," on the building PA system.

2.2. 120% Demand

a. Withdraw rods to 3 inches.
b. Turn off the Linear recorder
c. Remove Linear recorder potentiometer cover and manually rotate potentiometer arm, note recorder reading when trip point is reached.
d. When inward motion of rods is verified, lower recorder below reset point, reset rundown and all alarms, turn recorder on and replace cover, and compare actual and specified trip points.
e. Record the trip point value and that the audible/visual alarms are functional.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 810 TITLE: WEEKLY CHECK Revised: August 9, 2017 Page 4 of 11 2.3. 120% Full Power

a. Withdraw rods to 3 inches.
b. Depress "LINEAR TEST" switch.
c. Observe the Linear digital display and record the value at which the 120% full power trip occurs.
d. Release the "LINEAR TEST" switch.
e. Observe the "120% Full Power" annunciator and audible alarm.
f. Reset the annunciator and rundown.

2.4. Low CIC Voltage Linear Power Supply

a. Withdraw rods to 3 inches.
b. Push and hold alarm test button on Linear CIC Power Supply. Observe High Voltage meter and record the value when the under voltage alarm light comes on. Release the test button. The under voltage alarm light shall actuate at a voltage equal or above 440VDC.
c. Acknowledge the annunciator alarm and observe Low CIC voltage annunciator light. Check for insertion of control rods (rundown in progress).
d. When the High Voltage on the Linear CIC Power Supply has increased to approximately 500 volts push alarm reset. The under voltage alarm light will go off allowing the operator to reset the rundown (push rundown reset) and the annunciator.
e. Record value of the trip point.

2.5. Regulating Rod on Insert Limit on Auto

a. Withdraw the rods to 3 inches and reg rod to 0.5 inches (use the shim range bypass).
b. Adjust Linear recorder setpoint so that "auto permit" comes on.
c. With reg rod at approximately 0.5 inches withdrawn, switch the reg rod control to "Auto" and reset the annunciator.
d. Adjust the red pointer (auto setpoint) to be slightly below black pointer (Linear signal) so that an insert on the reg rod will result.
e. When the reg rod reaches insert limit observe rods inserting, Manual Operation and "Reg Rod insert limit on Auto" annunciators.
f. Acknowledge and reset rundown and annunciators.
g. Record results.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 810 TITLE: WEEKLY CHECK Revised: August 9, 2017 Page 5 of 11

3. Scrams 3.1. Bridge Motion Scram
a. Withdraw rods to 3 inches.
b. Release bridge lock and move the bridge a small distance.
c. Observe a Bridge Motion and Manual Scram annunciators illuminate and that the rods scram. Acknowledge the annunciator alarm.
d. Return bridge to original position and reset all annunciators. Re-insert the magnets.
e. Record results.

3.2. Low Pool Water Scram

a. Withdraw rods to 3 inches.
b. Lower pool float to lowest position attainable or until scram occurs.
c. Observe a Low Pool Water and annunciator illuminate and that the rods scram.

Acknowledge the annunciator alarm.

d. Re-insert the magnets.
e. Record results.

3.3. Non-Operative Scram and Rundown Test

a. Withdraw rods to 3 inches.
b. Depress the "NON-OPERATE" switch.
c. Verify rods have dropped and rod drives are inserting.
d. Release the "NON-OPERATE" switch.
e. Verify the "Log N Non-operate" and "Low CIC High Voltage" annunciators and audible alarms are activated.
f. Reset the Scram, Rundown, and Annunciator panel.
g. Depress and release the test switches listed below. For each verify a scram has occurred and the "Log N Non-operate" and "Low CIC High Voltage" annunciators and audible alarms are activated. Reset the scram and annunciator panel after each switch is checked. The following switches are to be checked:
  • 1 mA switch,
  • 0.1A switch,
  • 10 pA switch, and
  • 3 SEC switch.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 810 TITLE: WEEKLY CHECK Revised: August 9, 2017 Page 6 of 11 3.4. 150% Full Power Scram

a. Withdraw the rods to 3 inches.
b. Depress the scram test button on Safety Amplifier #1 and hold. Observe that the scram occurs prior to 150%.
c. Push reset on the Safety Amplifier #1, acknowledge the annunciator and observe the 150% Full Power Scram annunciator.
d. Reset annunciator and insert the magnets.
e. Performs steps a-d for Safety Amplifier #2.
f. Record results.

3.5. Manual Scram

a. Withdraw rods to 3 inches.
b. Push Manual Scram button and observe the control rods dropping.
c. Acknowledge the annunciator and Manual Scram light. Push Scram Reset, Annunciator Reset and insert the magnets.
d. Record results.
4. Period Trips
a. Withdraw rods to 3 inches.
b. Depress the "PERIOD TEST" switch to inject a ramp signal and observe the period digital display. Continue holding the switch down throughout the following steps.
c. 30 Second Trip - Verify that the <30 second audible and visual alarms are received at an indicated period of 30 seconds or more. Attempt to withdraw rods. Verify that rods cannot be withdrawn. Record the value (digital meter) at which the <30 second trip was received. Acknowledge the alarm.
d. 15 Second Trip - Continue depressing the "PERIOD TEST" button until the

<15 second rundown occurs. Verify that the audible and visual alarms are received and that the rods begin to rundown. Acknowledge the alarm and record the actual trip point (digital meter).

e. 5 Second Trip - Continue depressing the "PERIOD TEST" button until the <5 second scram occurs. Verify that the audible alarm is received and that the <5 second and 150% full power annunciators are activated. Record the value (digital meter) at which the <5 second alarm occurs.
f. Release the "PERIOD TEST" switch, reset the scram, rundown, and annunciator panel.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 810 TITLE: WEEKLY CHECK Revised: August 9, 2017 Page 7 of 11

5. Rod Drop Currents
a. Withdraw rods to 3 inches.
b. Using a screwdriver slowly reduce magnet current using current adjustment #1, visually observe rod #1 drop. Record this drop current value.
c. Repeat Steps a and b for Rods #2 and #3.
d. Insert all rod drives to insert limit. .
e. Set all magnet currents to "normal" (i.e. Drop Current plus 15 ma).
6. Test of Annunciators 1.1. Interlock Bypass Bypass each interlock one at a time to ensure that each individual bypass operates the annunciator and the bypass lights are functional.

1.2. Servo Limits

a. Note linear level recorder reading.
b. Change the automatic set point for auto permit by adjusting the star wheel.

Remove Linear recorder potentiometer cover and manually rotate potentiometer arm. Note linear level at which the auto permit light comes on

(<+2%). Continue to lower and note reading until the auto permit light goes off

(>-2%).

c. Record results.

6.3. Pool Demineralizer Effluent Conductivity High

a. Record pool and demin effluent readings.
b. Check the alarm setpoint by pressing the ALARM 1/ALARM 2 Key and observing alarm 1 set setpoint is 0.500 M - cm.
c. Increase the alarm 1 setpoint to a number higher than the conductivity cell reading and press the enter key. Observe the ALARM indicator flashing on the display. Observe that the console annunciator and audible alarm are activated.
d. Reset the alarm 1 setpoint to 0.500 M - cm.
7. "REACTOR ON" Lights With magnet key inserted and all scrams reset check the "reactor on" lights (1) above console (2) at reactor entrance and (3) basement level.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 810 TITLE: WEEKLY CHECK Revised: August 9, 2017 Page 8 of 11

8. Building Evacuation Alarm
1. Announce over the PA, "The Building Alarm will sound. This is a test. Do not evacuate the building."
2. Push the Building Evacuation Alarm and note the audible alarm.
3. Reset Building Evacuation Alarm by pushing Scram Reset.
4. Announce over building PA "Test complete. Acknowledge all further alarms."
9. Nitrogen Diffusers
1. With the bridge intercom station selected, start diffuser #1. The green operation light should illuminate. Note the sound level of the pump and no unusual noise.
2. Shutdown the #1 pump and repeat step 1 for the #2 nitrogen diffuser.
3. Record results.
10. Beam Port Warning Lights
1. Announce over the building PA. "Attention personnel, stand clear of the Beam Port".
2. Open the Beam Port by holding the Beam Port control switch in the open position until the "Red" (open) light comes on.
3. Acknowledge the annunciator alarm and verify that the Basement Level Warning Light (Flashing Red) activates.
4. Close the Beam Port by holding the Beam Port Switch until the Green (closed) light comes on. Reset the annunciator and observe that the light goes out.
5. Announce over the Building PA "Beam Port secured".
11. Constant Air Monitor (CAM)
1. Remove the CAM filter and place in an envelope labeled with the date and time the filter was used.
2. Install new filter on CAM.
3. Place envelope on a gamma spectroscopy system and count for one hour.
4. Create a gamma spectroscopy report of the spectrum.
5. Observe report for abnormally high peaks.
6. Save report as a computer file.
12. Secure Check - Complete a Secure Checklist (SOP 105) to ensure that all console equipment is secured.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 810 TITLE: WEEKLY CHECK Revised: August 9, 2017 Page 9 of 11

13. Security System Check - Inform the Missouri S&T Police (4300) that the security system will be checked and verify the appropriate alarms are received by them.

13.1. Security Door

a. Hold in or close dead bolt on the security door.
b. Reset the alarm system.
c. Open dead bolt switch by releasing or opening dead bolt and ensure alarm occurs in Missouri S&T Police dispatch station.

13.2. Ultrasonics

a. Hold or close dead bolt on security door. Reset alarm system.
b. While holding the dead bolt switch, move around or have someone walk toward one of the UT's. A different ultrasonic detector should be tested each week.
c. Allow the ultrasonic to reset by moving clear of the detector or stand still.

13.3. Duress

a. Momentarily depress the alarm button.

13.4. Doors

a. While holding the dead bolt switch closed, reset the alarm.
b. Open one of the exterior doors equipped with an intrusion alarm. A different door should be tested each week.
c. Repeat steps a and b for one of the interior doors equipped with an intrusion alarm. A different door should be tested each week.
d. When all intrusion channels have been tested, verify Missouri S&T Police have received alarms. This completes the security check.
e. When all channels of the security system have been functionally tested and operate properly, initial the weekly checklist.
14. Checklist Completed By - The person who performed the checklist should sign and date in the blanks provided. If a non-licensed operator performed the checklist, the licensed operator who supervised the checklist shall also sign and date the form.
15. Reviewed and Approved - The Reactor Manager shall review and approve the checklist.

Review and approval of the Weekly Checklist may be delegated to a Senior Reactor Operator in the event that the Reactor Manager is unavailable for the review.

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 810 TITLE: WEEKLY CHECK Revised: August 9, 2017 Page 10 of 11 WEEKLY SURVEILLANCE CHECKLIST Date Performed ______________________

1. Rod Prohibits 1.1. Recorder Off Alarms () Prohibit ()
  • Source Range recorder _________ __________
  • Linear recorder _________ __________
  • Log/Period recorder _________ __________
  • Temperature recorder _________ __________

Set Point Alarms () Prohibit ()

1.2. Source Range <2 cps _________cps_________ __________

1.3. Inlet Temperature >135oF __________oF _________ __________

Thermocouple tested __________

1.4. Shim Rods below shim range N/A N/A __________

2. Rundowns 2.1. RAM System Rundown Bldg. Alarm Remote and Station Set Point Set Point Alarms () Local Alarm ()

Bridge ________mrem/hr ________mrem/hr _________ _____________

Demin ________mrem/hr N/A _________ _____________

Basement ________mrem/hr N/A _________ _____________

Rundown Set Point Alarms ()

2.2. 120% Demand rundown ______________% _________

2.3. 120% Full Power Rundown ______________% _________

2.4. Low CIC Linear P.S. ___________VDC _________

(440VDC) 2.5. Regulating Rod on Insert Limit on Auto N/A _________

3. Scrams Alarms () Scram ()

3.1. Bridge Motion Scram _________ _________

3.2. Low Pool Water Scram _________ _________

3.3. Log and Linear Non-Op. Scram

  • Non-operate switch (raise rods 3") _________ _________
  • 1 mA switch _________ _________
  • 0.1 A switch _________ _________
  • 10 pA switch _________ _________
  • 3 sec switch _________ _________

3.4. 150% Full Power Scram Safety Amplifier 1 _________ _________

Safety Amplifier 2 _________ _________

3.5. Manual Scram _________ _________

Date ____________________________

Revised By: Anthony Alchin Approved By: William Bonzer

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

SOP: 810 TITLE: WEEKLY CHECK Revised: August 9, 2017 Page 11 of 11

4. Period Trips Set Point Alarms () Trip Operational ()

4.1. 30 Sec RWP _______ _________ ________________

4.2. 15 Sec Rundown _______ _________ ________________

4.3. 5 Sec Scram _______ _________ ________________

5. Rod Drop Currents Drop Current 5.1. Rod #1 ________mA 5.2. Rod #2 ________mA 5.3. Rod #3 ________mA
6. Test of Annunciators 6.1. Interlock Bypass Alarms () Operational ()
  • Shim range _________ _____________
  • 30 second period _________ _____________
  • Radiation area high _________ _____________
  • <2 CPS _________ _____________

6.2. Servo Limits: Lin. Rec. Reading ________% Permit on at _______% Permit off at _______%

6.3. Pool/Demineralizer Resistivity Pool Demin Local Alarm () Annunciator ()

_____ M-cm _______M-cm _____________ ______________

7. "Reactor on" Lights Operational ()

7.1. Main Entrance _____________

7.2. Control Room _____________

7.3. Beam Room _____________

8. Building Evacuation Alarm Operational (): __________________
9. Nitrogen Diffusers Pump Operational () Indicator Light On ()
  1. 1 __________________ __________________
  1. 2 __________________ __________________
10. Beam Port Warning Light: Annunciator () ______________ Flashing Light () _____________
11. Constant Air Monitor Completed (): _______________
12. Secure Check List: Completed (): _______________
13. Security System Check: Completed (): _______________
14. Checklist Completed By: ___________________________________ Date_____________
15. Reviewed and Approved: ________________________________________

Manager Revised By: Anthony Alchin Approved By: William Bonzer

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