ML14154A049

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


Text

MISSOURI S&T MISSOURI UNIVERSITY OF SCIENCE AND TECINOLOGY Fomr, Lnly rs' oU of Iissc't-oi' May 26, 2014

Dear Sir:

Please find enclosed the Annual Progress Report 2013-2014 for the Missouri Science and Technology Reactor (License R-79, Docket No: 50-123). This report is being filed under the reporting requirements of our Technical Specifications. A copy of this report is also being sent to our NRC Project Manager, Mr. Greg Schoenebeck.

Sincerely, L4AJ2~A,

&n-k William Bonzer Reactor Manager mh Enclosure cc: Mr. Greg Schoenebeck (NRC)

Document Control Desk (NRC)V/'

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

Chancellor Cheryl B. Schrader (MST)

Michelle Bresnahan, Radiation Safety Officer (MST)

Dr Hyoung Lee, Chair of Nuclear Engineering Dept. (MST)

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

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

Nuclear Reactor Facility o 250 West 13S Street% o Rolla, MO 6(5409-0637 Phone: 573-341-4236 o Fax: 573-341-4237 o Email 1Aebonzer@mcst.edu Ac)'2"o

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0 0 PROGRESS REPORT 0

0 2013-2014 0

0 MISSOURI UNIVERSITY OF 0

0 SCIENCE AND TECHNOLOGY 0

S REACTOR 0

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PROGRESS REPORT 0

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0 0 MISSOURI UNIVERSITY OF SCIENCE AND TECHNOLOGY 0

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0 NUCLEAR REACTOR FACILITY 0

0 0 April 1, 2013 to March 31, 2014 S Submitted to 0

The United States Nuclear Regulatory Commission 0

And 0 Missouri University of Science and Technology 0

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  • Table of Contents

SUMMARY

S1.0 IN TR O D UCTIO N ............................................................................................................................................... I

1.1 BACKGROUND

INFORM ATION ............................................................................................................. 1 S1.2 G ENERAL FACILITY STATUS ......................................................................................................................... 2 2.0 REACTO R STA FF AND PER SO NNEL ................................................................................................ 3 0 2.1 REACTOR STAFF ............................................................................................................................................ 3 2.2 LICENSED O PERA TORS ................................................................................................................................. 4 2.3 RADIATION SAFETY C OM M ITTEE ................................................................................................................. 4 S2.4 H EALTH PHYSICS ........................................................................................................................................... 5 S3.0 R EACTO R O PERA TIO NS ............................................................................................................................... 6 4.0 ED UC ATIO N A L UTILIZA TIO N .................................................................................................................... 13

  • 5.0 REACTOR HEALTH PHYSICS ACTIVITIES ........................................................................................ 17 5.1 ROUTINE SURVEY ......................................................................................................................................... 17 0 5.2 BY-PRODUCT M ATERIAL R ELEASE SURVEYS ...................................................................................... 17 5.3 ROUTIN E M ONITORING ................................................................................................................................ 17 5.4 ENVIROM ENTAL M ONITORING ..................................................................................................................... 18 S5.5 WASTE DISPOSAL .................................................... .... ............................................................................... 18 S5.6 INSTRUM ENT CALIBRATIONS ....................................................................................................................... 18 6.0 PLANS .................................................................................................................................................................. 19 0 S6.1 DISTANT EDUCATION .................................................................................................................................... 19 6.2 REPLACEMENT OF THE REACTOR BUILDING'S HEATING SYSTEM ......................................................... 19 6.3 MODELING THE GAMMA SPECTORCOPY OF THE REACTOR CORE ....................................................... 20 6.4 GLOBAL THREAT REDUCTION INITIATIVE SECURITY ENHNANCEMENT ............................................. 20 6.5 REACTOR OPERATOR TRAININ G ................................................................................................................... 20 0

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0 APPENDIX A: STANDARD OPERATING PROCEDURES CHANGED DURING THE 2012-2013 REPORTING YEAR 0

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  • LIST OF TABLES 6

0 TABLE 3-1. CORE 120W TECHNICAL DATA ..................................................................................................

TABLE 3-2. CORE 121W TECHNICAL DATA ............................................................................................................. 10 0 TABLE 3-3. UNSCHEDULED SHUTDOWNS .................................................................................................. 8 TABLE 3-4. MAINTENANCE ........................................................................................................................................ 10 STABLE 3-5. EXPERIMENTAL FACILITY USAGE .......................................................................................................... 12 0 TABLE 3-6. REACTOR UTILIZATION .................................................................................................................. 12 TABLE 4-1. MISSOURI S&T CLASSES AT REACTOR FACILITY ......................................................................... 14 0 TABLE 4-2. REACTOR SHARING PROGRAM 2013-2014 (REPORTING PERIOD) ................................................. 15 0

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  • FIGURE 3-1. MSTR CORE 120W CONFIGURATION ................................................................................................... 6
  • FIGURE 3-2. MSTR CORE 121W CONFIGURATION........................................................................... 7 0

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SUMMARY

During the 2013-2014 reporting period, the Missouri University of Science and

    • Technology Reactor (MSTR) was in use for 493.07 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />. The major part of this time, about 90%, was used for class instruction, research, and training purposes.

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

0 The reactor facility supported several Missouri University of Science and Technology

  • (Missouri S&T) courses over the year for 24,768 student-hours. About 2,446 visitors visited the
  • reactor during the past year. There were 1,660 participants, mostly high school students, in the
  • U.S. Department of Energy Reactor Sharing Program.

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  • The reactor produced 35,496.0 kW/hrs kilowatt-hours of thermal energy using approximately 1.5 grams of uranium. A total of 351 samples were neutron irradiated in the reactor with the majority being analyzed in the reactor counting laboratory.

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1.0 INTRODUCTION

9 This progress report covers activities at the Missouri University of Science and Technology

  • Reactor (MSTR) Facility for the period April 1, 2013 to March 31, 2014.

The reactor operates as a University facility. It is available to the faculty and students 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.

0 1.1 Background Information

  • The Missouri University of Science and Technology Reactor (MSTR) (formally University of
  • Missouri-Rolla Reactor) attained initial criticality on December 9, 1961. The MSTR was the first operating nuclear reactor in the State of Missouri. The Bulk Shielding Reactor at Oak Ridge National Laboratory is the basis for the reactor's design. The reactor is a light water, open pool reactor cooled by
  • natural convective flow. The fuel is MTR plate-type fuel. The initial licensed power was 10 kW. The 9 licensed power was up-graded to 200 kW in 1966. During the summer of 1992, the reactor fuel was converted from highly enriched uranium fuel to low-enriched uranium fuel.

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  • The facility is equipped with several experimental facilities including a beam port, thermal column, three pneumatic rabbit systems, and several manual sample irradiation containers and systems.

The facility also contains a counting laboratory that has both gamma and alpha spectroscopy capabilities.

9 The gamma spectroscopy system includes germanium and sodium-iodide detectors, associated electronics, state-of-the-art data acquisition, and spectrum analysis software. The alpha spectroscopy S

system consists of a surface barrier detector and data acquisition equipment. Additionally, there is a thermo luminance dosimeter reader, digital neutron radiography imager, and x-ray imager for student and

  • faculty usage.

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

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

An independent auditor from the University of Columbia audited the reactor facility on December 4, 2013. There were no significant areas of concern. There is an agreement between the MSTR and the University of Missouri-Columbia to audit each other. This has been a very beneficial arrangement for both facilities involved.

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

1. Chemistry 2, 'General Chemisty Laboratory' 2 Civil Engineering 310, 'Senior Design Class'
3. Engineering Management 386, 'Safety Engineering Management'
4. Mechanical Engineering 229, 'Energy Conversion'
5. Life Sciences 352, 'Biological Effects of Radiation' 6 Physics 107, 'Modem Physics'
7. Physics 207, 'Modem Physics II'
8. Physics 322, 'Advanced Physics'
9. Materials Science & Engineering 348, 'Energy Materials'
10. Materials Science & Engineering 448, 'Advanced Energy Materials'
  • 3 9 SOPs were revised, over the past year in order to improve and keep current the operations and
  • efficiency of the MSTR. The following is a list of SOPs revised during the reporting period:
  • 1. Index
  • 2. Index
3. SOP 105 Reactor Shutdown & Reactor Securing Procedures
4. SOP 309 Response to a Coolant System Leak
  • 5. SOP 501 Emergency Procedures For Reactor Building Evacuation
  • 6. SOP 507 Emergency Procedures Administrative Responsibilities
  • 7. SOP 654 Measurement Of 4aAr Concentration In The Reactor Building Air
  • 8. SOP 800 Annual Checklist
  • 9. SOP 813 Rod Drop Time Measurement 0
  • 2.0 REACTOR STAFF AND PERSONNEL
  • 2.1 Reactor Staff 0

O Name Title 0 Dr. Arvind Kumarl Reactor Director

  • Dr. Hyoung Kohl Lee 2 Reactor Director Mr. William Bonzer Reactor Manager & Senior Operator Ms. Maureen Henry Senior Secretary Mr. Craig Reisner Senior Reactor Operator
  • Mr. Ray Kendrick Senior Electronics Technic 0
  • 1. Termination Date August 31, 2013
  • 2. Effective Date September 1, 2013 0

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4 2.2 Licensed Operators Name License

1. William Bonzer Senior Operator
2. Craig Reisner Senior Operator
3. Ethan Barth-Taber Senior Operator
4. Nolan Goth' Senior Operator
5. Brandon Lahmann Senior Operator
6. Matthew Crinnian. Senior Operator
7. Kathryn Krev Senior Operator
8. Dustin Specker' Reactor Operator
9. Christopher Swisherl Reactor Operator 2
10. Erica Davidson Reactor Operator 3
11. Cody Stuchal Reactor Operator 3
12. Ethan Margherio Reactor Operator 3
13. Jonathan Scott *ReactorOperator
1. Termination Date October 16, 2013
2. Effective Date December 5, 2013
3. Effective Date March 21, 2014 2.3 Radiation Safety Committee The Radiation Safety Committee meets quarterly. The committee met on 6/28/2013, 9/26/2013, 12/6/2013 and 2/28/2014 during the reporting period. The committee members are listed below.

Name Department

1. Dr. Mark Fitch Civil Engineering
2. Mr. Ray Bono Environmental Health and Safety Services

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3. Mr. William Bonzer Nuclear Reactor
4. Mr. Randy Stoll Business Services
5. Dr. Robert Dubois Physics 0 6. Dr. David Wronkiewicz Geological Sciences & Geology S 7. Dr. Shoaib Usman Mining & Nuclear Engineering S 8. Dr. Fadha Ahmed Environmental Health and Safety Services 0
9. Dr. Robert Aronstam Biological Sciences 0
10. Dr. Amitava Choudhury Chemistry
11. Dr. Carlos Castano Mining & Nuclear Engineering 0
12. Mr. Tony Hunt Environmental Health and Safety Services 9

S 0 2.4 Health Physics 0

The Environmental Health and Safety (EHS) Department provides the health physics support for 0 the Missouri S&T Reactor. The EHS Department is organizationally independent of the Reactor Facility operations group. Health Physics personnel are listed below.

S S Name Title 0

0 1. Mr. Ray Bono Director of Environmental Health and Safety 0 2. Mr. Brian Smith Industrial Hygienist S 3. Dr. Fadha Ahmed Health Physicist 0 4. Ms. Kelsey Freedline Health Physics Technician (part time)

S 5. Ms. Amanda Baker Health Physics Technician (part time) Left Dec. 2014 S 6. Ms. Kelsey Salzman Health Physics Technician (part time)

7. Ms. Kathryn Krev Health Physics Technician (part time)

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8. Mr. Andrew Bingham Health Physics Technician (part time)

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Table 3-1. Core 120W Technical Data 9

Parameter Value 9 Rod 1 3.832% Ak/k 9

Rod 2 3.228% Ak/k 9 Rod 3 1.778% Ak/k Reg Rod 0.293% Ak/k 9 Excess Reactivity 0.652% Ak/k Shutdown Margin* 4.354% Ak/k 4 *Assumes Rod I (highest worth rod) and Reg Rod are fully withdrawn.

S 9 A 0 B S 9 C C-4 F-5 F-I F-17 0 D F-4 F-8 F-14 C-I F-10 F-2 9 E F-9 C-3 F-12 C-2 F-7 F-3 0

F CR F-15 HC F-13 BR F-6 0

0 Table 3-1. MSTR 120W Configuration 9

KEY TO PREFIXES F- Standard Elements CR- Cadmium Rabbit HF- Half Element BR- Bare Rabbit C- Control Elements S - Source Holder CR- Cadmium Rabbit HC- Hot Cell Rabbit

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Table 3-2. Core 121W Technical Data 9

Parameter Value 0 Rod 1 3.950% Ak/k S Rod 2 3.397% Ak/k Rod 3 1.975% Ak/k 9 Reg Rod 0.270% Ak/k 9 Excess Reactivity 0.219% Ak/k 0 Shutdown Margin* 5.350% Ak/k S

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

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B S S

C C-4 F-5 F-1 F-17 9 D F-4 F-8 F-14 C-1 F-10 F-11 S E F-9 C-3 F-12 C-2 F-7 F-3 0 F CR F-15 HC F-13 BR F-6 S

S S Figure 3-2. MSTR Core 121W Configuration KEY TO PREFIXES F- Standard Eleme nts CR- Cadmium Rabbit 1-F- Half Element BR- Bare Rabbit C- Control Elements S - Source Holder CR- Cadmium Ratbbit HC- Hot Cell Rabbit

8 Table 3-2:Unscheduled Shutdowns for 2013-2014 Date Type of Rundown/Cause and Corrective Action Taken RUNDOWNS 4/8/2013 Action: 120% Demand Rundown Cause: Operator restarting reactor with a high residual core.

Corrective Action Taken: Operator instructed to watch instrumentation.

SRO on Duty granted permission to restart reactor.

5/2/2013 Action: 120% Demand Rundown Cause: Student operator downscaled at 60% on Linear Recorder.

Corrective Action Taken: SRO instructed student to downscale at 8%, not 60%.

SRO on Duty granted permission to restart reactor.

5/10/2013 Action: 120% Demand Rundown Cause: Student downscaled pico-ammeter too soon.

Corrective Action Taken: SRO instructed student to follow SOP 104 regarding downscaling at 8% and upscaling at 60 %

SRO on Duty granted permission to restart reactor.

6/21/2013 Action: High Area Radiation Rundown

9 Cause: A sample returning to the hot cell rabbit system stopped in the glove box near the gamma radiation area monitor instead of passing 'through to the hot cell.

Corrective Action Taken: SRO let the sample decay in the glove box and kept personnel out of the room containing the hot cell rabbit system. Sample was removed from glove box after decaying.

SRO on Duty granted permission to restart reactor.

12/12/2013 Action: 120% Demand Rundown Cause: The operator did not push in on range switch far enough for it to stay pressed in.

Corrective Action Taken: The operator was reminded to fully press in range switch.

SRO on Duty granted permission to restart reactor.

2/26/2014 Action: 120% Demand Rundown Cause: The operator did not fully press in the 20 kW range switch.

Corrective Action Taken: No corrective action taken.

SRO on Duty granted permission to restart reactor.

3/5/2014 Action: 120% Demand Rundown Cause: The operator did not follow proper startup procedures after the reactor had been shutdown.

Corrective Action Taken: The SRO instructed the operator to follow SOP 106 when restarting the reactor.

SRO on Duty granted permission to restart reactor.

10 UNPLANNED SHUTDOWNS Date Tvne of Unnlanned Shutdown. Cause and Corrective Action Taken Unplanned Shutdowns 12/16/2013 Action: Rods dropped.

Cause: Alternating current power flicker.

Corrective Action Taken: None.

SRO on Duty granted permission to restart reactor.

3/6/2014 Action: Control rod #3 dropped.

Cause: Undetermined.

Corrective Action Taken: None.

SRO on Duty granted permission to restart reactor.

Table 3-3: Maintenance for 2013-2014 Date Type of Maintenance 8/20/2013 Issue: Rod drive #3 failure.

Corrective Action: Removed, repaired reinstalled rod drive #3.

9/4/2013 Issue: Magnet #3 failure.

0 Corrective Action: Removed magnet #3 and replaced with spare magnet.

  • 10/1/2013 Issue: Magnet #3 failure.

0 Corrective Action: Removed magnet #3 and replaced with spare magnet.

0S 1/5/2013 Issue: Magnet #3 failure.

0 0 Corrective Action: Removed magnet #3 and replaced with spare magnet.

0 1/15/2014 Issue: Magnet #3 failure.

0 Corrective Action: Removed magnet #3 and replaced with spare magnet.

0* 1/27/2014 Issue: Magnet #3 failure.

0 0 Corrective Action: Removed magnet #3 and replaced with spare magnet.

0 2/10/2014 Issue: Magnet #3 failure.

0 0Corrective Action: Removed magnet #3 and replaced with spare magnet.

0t 12/04 Ise Mge 3fiue 0 orcieAto:Rmvdmge # n elcdwt pr ant Issue: Magnet #2 failure.

0S 12/20/2014 0'

0 Corrective Action: Removed magnet #2 and replaced with spare magnet.

6 /021 su:Mge 3fiue 0'Cretv cin eoe ant# n elcdwt pr ant 0

0 102/021 Isu:Mge#2fiue

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Table 3-5. Experimental Facility Usage 0

Facility Hours 4 Bare Rabbit Tube 21.38 hrs.

Cadmium Rabbit Tube 0.00 hrs.

Beam Port 116.531 hrs.

Thermal Column 0.0 hrs.

Other Core Positions 3.22 hrs.

0 0 Hot Cell 11.73 hrs.

Gamma Exposures 0.0 hrs.

Total 152.86 hrs.

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1. Reactor use 493.07 hrs.
2. Time at power 366.52 hrs.

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3. Energy generated 35,496.0 kW/hrs.
4. Total number of samples, neutron irradiated 351
5. U-235 Burned 1.553 g
6. U-235 Burned and Converted 1.834 g 0

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  • 4.0 EDUCATIONAL UTILIZATION
  • The reactor facility supported several Missouri S&T courses in the past year for a total of 24,764
  • student-hours. The number of Missouri S&T students utilizing the facility was 1,404. This usage is a direct result of an aggressive and continuing campus wide "outreach" program. The reactor facility
  • provided financial support for six students with hourly wages. Additionally, students from several universities, colleges and high schools have used the facility.

Table 4-1 lists Missouri S&T classes taught at the facility along with associated reactor usage

    • for this reporting period.
    • The Reactor Sharing Program, previously funded by the U.S. Department of Energy, was established for colleges, universities, and high schools that do not have a nuclear reactor. This past year,
  • 1,660 students and instructors from 140 institutions.participated in the program. Table 4-2 lists those schools and groups that were involved in this year's Reactor Sharing Program. The majority of
    • participants were high school students. MSTR coordinates with the Missouri S&T Admissions Office to schedule high school students to see other items of interest at Missouri S&T after they have visited the
  • reactor facility. The students visited the Missouri S&T Chapter of American Nuclear Society, the Computer Integrated Manufacturing Lab, the Foundry, Ceramics Engineering, Mineral Museum, Computer Center, Experimental Mine, Solar Car, Electron Microscope, and Stonehenge. The Reactor
  • Sharing Program serves as a strong campus-wide recruiting tool by attracting high school students to the university and hopefully sparking some interest in nuclear engineering, science, and technology.

The reactor staff continues to educate the public about applications of nuclear science. Over

  • 2,446 persons visited the facility during this reporting period. Tour groups are typically given a brief 9orientation and/or demonstration by a member of the reactor staff.

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0 Table 4-1 Missouri S&T Classes at Reactor Facility 0

0 Semester CLASS NUMBERITITLE # OF TIME AT STUDENTS 0 STUDENTS REACTOR HOURS 0

0 2013-2014 Graduate Student's Project 5 234 1170 0

SS2013 NE 206 20 12 240 9

SS2013 NE 308 28 129.5 2590 4/8/2013 NE 25 Lab 17 1.5 26 0

4/22/2013 NE 312 15 2.5 38 0

4/24/2013 NE 312 15 2.5 38 0 4/25/2014 NE 312 10 2.5 25 0 5/14/2014 NE 25 Power Changes 5 1 5 9 FS 2013 NE 206 26 10 260 0 9/4/2013 NE 25 Tour 3 1 3 9/5/2013 NE 25 Tour 9 1 9 0 9/6/2013 NE 25 Tour 9 1 9 0, FS 2013 NE 304 34 36 1224 12/2/2013 NE 25 Power change 9 2 18 9 12/4/2013 NE 25 Power change 2 2 4 0 SS2014 NE 206 26 84 2184 0 SS2014 NE 308 labs 20 38.5 770 0 2/10/2014 NE 25 Tour 22 1 22 0 2/13/2014 NE 25 Tour 10 1 10 3/17/2014 NE 25 Lab 22 1 22 0 3/20/2014 NE 25 Lab 6 1 6 0 3/18/2014 NE 312 15 1 15 3/19/2014 NE 312 26 1 26 3/20/2014 NE 312 12 1 12

_ _TOTAL 366 568 8726

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0 0 Table 4-2 Reactor Sharing Program 2013-2014 (Reporting Period) 0 0 Date Participants Number Hours 4/2013 Visitor's 17 4.5 0

4/15-4/18 Chem labs for Spring semester 2013 252 7.5 0 4/23/2013 Tour MET class 348/448 10 1 0 4/29/2013 Mountain Grove School 5 1 0 5/17/2013 Tour for families and students before graduation 21 4 5/16/13 Army Tour 2 1 0

6/2013 Visitor's 7 1 0

0 6/6/2013 Minority Introduction to Engineering 23 1 6/11/2013 Jackling Introduction to Engineering 18 1.5 0

9 6/13/2013 Jackling Introduction to Engineering 23 1.5 6/17/2013 Nuclear Engineering Camp (4 groups) 38 2 0 6/18/2013 Nuclear Engineering Camp (4 groups) 38 3.5 0

6/19/2013 Nuclear Engineering Camp (4 groups) 25 2 0

0 6/20/2013 Minority Introduction to Engineering 23 1 6/20/2013 Nuclear Engineering Camp (4 groups) 38 2 0 6/25/2013 Jackling Camp 18 1.5 6/27/2013 Jackling Camp 22 3.5 S 7/2013 Visitor's 12 2.5 7/9/2013 Jackling Camp 20 3.5 7/9/2013 Chemical Engineering Fort Leonard Wood School 23 1.5 7/11/2013 Jackling Camp 24 3.5 7/18/2013 Dr. Dewoski Class 6 1

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8/2013 Visitor's 6 1 0 8/13/2013 Video People 5 1.00 9 8/19/2013 Video People 3 .5 0 9/2013 Visitor's 7 3.5 0 9/10/2013 Tour with Walt Branson 1 .5 10/2013 Visitor's 13 8 0 11/5/2013 IT 1 1 0 11/6/2013 Physical Facilities 1 1 0 11/7/2013 Seymour and Norwood Schools 23 1 0 11/13/2013 Nuclear Regulatory Commission Testing 1 6 9 11/13/13 Chem labs 786 18 0 12/3/2013 Offsite Meeting 9 1 12/3/13 Tour Health Class 5 1 0 12/5/2013 Tour Mansfield High School 2 6 0 12/5/2013 MURR Inspection 1 16 0 12/9/2013 Training a person on control panel 1 6 12/10/2013 Computer Tech working in control room 1 8 9

1/20/2014 Visitor's 1 .5 0 1/13/2014 CDG Group 4 1 0 1/15/2014 Climax High School 21 1.5 1/21/2014 Group meeting on Security 14 6 9 2/2014 Visitors 6 2 S

2/12/2014 Home School Students 27 0 1 0 2/15/14 Boy Scout Tour 19 1 0 2/25/2014 Chemical Engineering Fort Leonard Wood School 19 1.5 2/26/2014 IT to test equipment 2 1 2/26/2014 Contractors for Asbestos removal 12 1 3/2014 Visitor's 4 1.5 TOTAL 1660 149

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0* 5.0 REACTOR HEALTH PHYSICS ACTIVITIES

  • The health physics activities at the Missouri S&T Reactor facility consist primarily of radiation 0 and contamination surveys, monitoring of personnel exposures, airborne activity, pool water activity, and 0 waste disposal. Releases of all by-product material to authorized, licensed recipients are surveyed and 0 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.

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5.1. Routine Surveys 0

Monthly radiation exposure surveys of the facility consist of direct gamma and neutron measurements. No unusual exposure rates were identified. Monthly surface contamination surveys

  • consist of 20 to 40 swipes counted separately for alpha and beta/gamma activity. No significant contamination outside of contained work areas was found.

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

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5.3. Routine Monitoring 9

Sixty-six reactor facility personnel and students involved with the operations in the reactor

  • facility are currently assigned Luxel, Optically Stimulated Luminescence (OSL) dosimeters. Three of the Reactor Staff have beta, gamma, neutron dosimeters which are read twice monthly. There are four area beta, gamma, neutron dosimeters and two TLD ring dosimeters, which are also read twice monthly.

SThere S are also four other beta, gamma, neutron dosimeters used by the health physics personnel and three other area beta, gamma, neutron dosimeters that are read monthly. The remaining dosimeters detect beta and gamma radiation only and are read monthly. There are seventeen area dosimeters assigned on S

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campus for beta and gamma monitoring and one for beta, gamma, and neutron monitoring. In addition,

  • six digital, direct-reading dosimeters and three chirper dosimeters are used for visitors and high radiation work. There have been no significant personnel exposures during this reporting period. Visitors are 0 monitored with direct reading dosimeters. No visitors received any reportable or significant exposure.

0 Airborne activity in the reactor bay is monitored by a fixed-filter, particulate continuous air 9 monitor (CAM). Low levels of Argon-41 are routinely produced during operations.

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  • 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 2013 through March 2014 sample concentrations averaged 0* 1.71x10ipCi/ml.
  • Release of gaseous Ar-41 activity through the building exhausts is determined by relating the 0 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 61,966.39 pCi of Ar-41 was

. released into the air.

9 5.4. Waste Disposal 0

Solid waste, including used water filters, used resins, and contaminated paper/gloves is stored and/or transferred to the campus waste storage area for later shipment to a commercial burial site. Water is analyzed for radioactive contamination and approval is required before the water is released. During 0 this period there were three waste barrels transferred from the reactor facility to the DMSF on campus.

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5.5. Instrument Calibrations 0During this period, portable instruments and area monitors were calibrated annually.

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  • 6.0 PLANS 0

The reactor staff will be involved in several major projects during the next reporting period; 1) development of a distant education program, 2) replacement of reactor building's heating system, 3)

  • modeling the gamma spectroscopy of the reactor core, 4) Global Threat Reduction Initiative security enhancements, and 5) continuation of the reactor operator training program.

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6.1 Distant Education A distant education system is being developed to conduct laboratory sessions with students of the 5* Missouri S&T Campus and other universities. Due to the size of the Missouri S&T Nuclear Engineering classes, the distant education system will allow students to participate in lab sessions as one group in

  • larger classrooms than what is available in the MSTR building.

5 Equipment has been installed to replace the existing rod drive motors and rod height indicators to output rod height information over the internet. Additional programing and minor wiring is being completed to output control room instrumentation to be viewed live as the labs are taking place.

Audio/video equipment is ready to use for students to watch reactor staff performing the labs, ask 0 questions to the staff and obtain data from the control room instrumentation.

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6.2 Replacement of the Reactor Buildinz's Heating System S The Missouri S&T campus has been constructing a geo-thermal heating system for many of the 9 campus buildings. Three geo-thermal power plants will obtain heat from the ground pipe it to other buildings. The coal power plant providing steam heat to many buildings including the MSTR will be

  • permanently shut down in the spring of 2014. The MSTR is not one of the buildings that will be heated
  • with the geo-thermal system. During the summer of 2014 the reactor building will have the steam heaters
  • replaced with natural gas heaters. Additional maintenance will be performed to replace existing circuit Sbreaker panels and ceiling lighting located in the reactor bay while the heating system is changed out.

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20 6.3 Modeling the Gamma Spectrocopy of the Reactor Core A dry-well container is being built to hold a sodium iodide detector. This detector will be place near the reactor core to obtain gamma spectrum readings from individual fuel elements. The gamma readings will be used by the Nuclear Engineering department a private firm to create a computer model of the MSTR core. Computer models do exist of the MSTR core, but no gamma spectrum data has been taken from the fuel and used in previous models.

6.4 Global Threat Reduction Initiative Security Enhancements The Pacific Northwest National Laboratory (PNNL) will enhance security of the MSTR under the Global Threat Reduction Initiative (GTRI) Program.

6.5 Reactor Operator Training The MSTR had four students obtain their license of Reactor Operator. The reactor staff is limiting operator training to only students with a very strong desire to obtain the license and assist reactor staff with reactor operations. At the end of the reporting period ten students were training for an operator's license to take in the fall of 2014 and four for their Senior Reactor Operator upgrade.

0 S

S 21 S

S 0

0 0

APPENDIX A.

0 S

S STANDARD OPERATING PROCEDURES S

S CHANGED DURING THE 2013-2014 S

S REPORTING YEAR S

S S

S S

S S

S S

S S

S 9

S 9

S S

S S

0 S

S S

S 0

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

S SOP: INDEX TITLE: -NýDEX S Revised: August 1, 2013 Page 3 of3 Rev 0

SOP 700 - 799 Experiments 0

0 SOP 702 Irradiation Request Forms SOP 710 Insertion and Removal of Experiments 0 SOP 711 Beam Hole Facility 0 SOP 712 Thermal Column Facility 0 SOP 800 - 899 Reactor Instrumentation SOP 800 Annual Checklist Rev 0 SOP 801 Log N and Linear Drawer Calibration S SOP SOP 802 803 Linear Channel Log Count Rate (LCR) Channel 0 SOP 804 Safety Amplifier System 0 SOP 805 Auto Control System SOP 806 Temperature Channel 0 SOP 810 Weekly Check S SOP 811 Fire and Smoke Alarm System SOP 812 Confinement and Ventilation System Check SOP 813 Rod Drop Time Measurement 9 SOP 816 MSTR Power Calibration SOP 818 Functional Test of Building Security System 0

0 0

0 0

0 Revised By: Maureen Henry Approved By: William Bonzer

/ -.I :p*z/ -

I ,,..,., f A ..... -

~ r xW L~

K

0 0

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

SOP: INDEX TITLE: INDEX Revised: September 9, 2013 Page 3 of 3 0

SOP 700 - 799 Experiments 0

0 SOP 702 Irradiation Request Forms SOP 710 Insertion and Removal of Experiments 0 SOP 711 Beam Hole Facility 0 SOP 712 Thermal Column Facility 0 SOP 800 - 899 Reactor Instrumentation 0 SOP 800 Annual Checklist SOP 801 Log N and Linear Drawer Calibration SOP 802 Linear Channel 0 SOP 803 Log Count Rate (LCR) Channel SOP 804 Safety Amplifier System 0 Rev SOP 806 Temperature Channel S SOP 810 Weekly Check SOP 811 Fire and Smoke Alarm System 0 SOP 812 Confinement and Ventilation System Check SOP 813 Rod Drop Time Measurement 0 SOP 816 MSTR Power Calibration SOP 818 Functional Test of Building Security System 0

0 0

0 Revised By: Maureen Henry Approved By: William Bonzer

(/~) 32~i~,

I ,

ý4

S 0

    • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *ev
  • SOP: 105 TITLE: REACTOR SHUTDOWN & REACTOR
  • SECTJRLNG PROCEDURES'
  • Revised: September 9, 2013 Page 1 of 4
  • A. PURPOSE*

To ensure a safe and consistent method to shutdown the Reactor from an operating condition and, when advised,by a SRO on Duty, to secure the reactor. Rev

  • B. PRECAUTIONS, PREREQUISITES, AND LIMITATIONS
  • 1. The SRO on Duty will decide if the Reactor is to be "SHUTDOWN" or "SECURED".
  • 2. A Secure Checklist shall be completed at the end of the work day.

0 3. Any malfunctions or abnormal conditions noted during or after the Shutdown will be recorded in the Permanent Log and the SRO on Duty shall be notified.

0*

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 alertto the indication ofjamming 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 logo
  • 2. Log time and "SHUTDOWN" in the permanent log.
3. Announce over the public address system, "The reactor will be shutdown".
  • 4. Trip "AUTO/N'ANUAL" switch to "ILMANUAL" (if in "AUTO").
  • 5. Place the "OPERATE/SHUTDOWNi" switch in "SHUTDOWN" position or insert
  • . safety rods and regulating rod with both joysticks.

O 0

  • Revised By: William Bonzer, Approved By: William Bon~zer 0 * , -:'." " '2 . ' .. "'

'0

0 S

0

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *Re
  • SOP: 105 TITLE: REACTOR SHUTDOWN & REACTOR
  • SECURNG PROCEDURES Revised: September 9, 2013 Page 2 of 4
6. Monitor the decrease in reactor power by changing the Linear Meter Selector Button (l 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)

Oand therefore this step is continued only until rods reach their limit.

7. Maintain Log Count Rate Recorder > 20 cps by inserting fission chamber.
8. Stop rod insertion when reg rod is at 1-2".
9. Restart rod insertion. Rev
10. When the rods are fully inserted to their insert limits (green lights):
a. Return "OPERATE/SHUTDOWN" switch to "OPERATE" or,
  • b. Return joysticks to the "NEUTRAL" position.

0 S11. Reactor is now "SHUTDOWN".

D. "SECURE CHECKLIST Refer to form SOP 105.

1. Use date stamp.
2. All rod and Reg Rod Insert Limit (Green) Lights on.
3. Turn magnet key 90 degrees CCW and remove from console. Hand key to SRO on
  • Duty.
4. Turn off the Log Count Rate, Linear, and Log/Period recorders. Place date at the top of each recorder chart (use date stamp).

S

5. Push Annunciator "RESET". The "NLANUAL SCRAi\M", "RECORDERS OFF" and "MANUAL OPERATION" Annunciators will remain on.
6. Turn the Reactor Bridge intercom switch to the off position (button up).

0 S7.. Return "OPERATE/SHUTDOWN" switch to "OPERATE".

  • Revised B

By: William Bonzer Approved By: William Bon~zer 0.., 1 /.,' -

i

0 S

S

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev 0 SOP: 105 TITLE: REACTOR SHUTDOWN & REACTOR 0 SECURING PROCEDURES Revised: September 9, 2013 Page 3 of 4 0

0 8. Turn TV monitor off.

0 0 9. Verify both nitrogen diffusers are off.

0

10. Verify that all vent fans are off.

0 11. Secure the rabbit system by assufing the controller is turned off and the gas bottle is shut. Return the glove box key to the safe.

0 12. Shut off the rabbit system nitrogen gas bottle if the rabbit has been used.

0 13. Turn off the core lights.

0 14. Log time using the console clock.

0 15. Initials of person performing checklist.

S

16. SRO on Duty shall initial.

S Rev 0

0 0

0 Revised By: William Bonzer Approved By: William Bonzer I

>-U*ig*. '

LAj ~

.' 'j

~

0 0

0

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev 0 SOP: 105 TITLE: REACTOR SHUTDOWN & REACTOR SECURING PROCEDURES Revised: September 9,2013 Page 4 of 4 SECURE CHECKLIST 0

0 0

0 0 1. Date

2. All Rods on Insert Limit 0

0 3. Magnet Power Off and Key to SRO

4. Recorders Off and Dated
5. Reset Annunciator S
6. Reactor Bridge Intercom 0 Off 0 7. Shutdown Switch to Operate 0 8. TV Monitor Off
9. Nitrogen Diffusers Off 0 10. Vent Fans Off
11. Rabbit System Secured
12. Rabbit Gas Off
13. Core Lights Off
14. Time Completed
15. Operators Initials
16. SRO Initials Revised By: William Bonzer Approved By: William Bonzer

0 0

MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 309 TITLE: RESPONSE TO A COOLANT SYSTEM LEAK

  • Revised: April 8, 2013 Page 1 of 1 0

A. PURPOSE To ensure proper indication and response in the event of a leak in the coolant system.

B. PRECAUTIONS, PREREQUISITES, AND LIMITATIONS

  • 1. Normal pool evaporation is approximately 1/10 inch per day.
2. There are "vacuum breaks" in the purification piping to prevent draining the pool below approximately 16 ft. above the core. The cooling system will automatically Rev shut down if a loss of water pressure occurs or water is detected at a floor water sensor.
3. Possible causes are:

O a. crack in the pool wall

  • b. leak in the purification system
c. leak in the seal around the beam port or thermal column O d. leak through the "forced" cooling pipes
e. leak in the cooling system Rev
4. Report any abnormalities to the SRO on duty.
  • 5. If a leak is present, shut down the reactor if it is operating.
6. Minimize unnecessary exposure to radiation.

C. PROCEDURES

1. Monitor water level to check the rate the level is decreasing if a leak is suspected.
2. Check for leaks at the purification pump, thermal column, beam port, and cooling Rev O system.

O 3. Check for indications of cracks in the wall (bubbles, dirt, broken cement, etc.

  • 4. If the leak is due to the purification system, close the pool suction valve (located next to the pump) # 19, and stop the purification pump.

O

5. If the leak is not due to the purification system, refill the pool as per SOP 301.
6. If the leak is due to the purification system or greater than the capacity of the purification system to refill the pool, the emergency cooling hose will be used to fill as necessary.
7. If the leak is due to the cooling system, turn off cooling system if it is operating. Rev
  • Isolate the leaking area of the cooling system by closing valves before and after O the leaking area.

0 O Reviewed By: Craig Reisner Approved By: William Bonzer 0

0 0

0 0

0 *** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES '*

SOP: 501 TITLES: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Revised: September 13, 2013 Page 7 of 7 Rev 0

0 MISSOURI S&T EMERGENCY PHONE LIST 0

S Reactor Staff CELL HOME WORK William Bonzer, Manager, SRO 578-9463 368-0318 341-4384 0 Craig Reisner, Senior Reactor Operator 573-247-7557 573-729-7277 341-4291 Rev Maureen Henry, Sr. Secretary 364-7272 341-6016 0

S University Administrative Staff Christine Laughlin, Director Missouri S&T Police 201-1699 816-665-1448 341-4345 S Dr.Cheryl B. Schrader, Chancellor 201-7392 341-5432 341-4116 341-4122 Rev Walter Branson, VC Chancellor Finance & Adm. 260-402-0317 James Packard, Director Physical Facilities 578-8167 341-4252 Dr. Goodman DO, Director Student Health Services 341-4284 Rev Dr. Hyoung Lee,Chair of Nuclear Eng, Reactor Director 573-202-4665 341-4585 Dr.Samuel Frimpong, Chair of Mining and Nuclear 426-2338 341-7617 0 Fadha Ahmed, Health Physicist EHS-Missouri S&T 636-223-2054 341-7014 S

S Local Missouri S&T Police 341-4300 Rolla City Police 911 Rolla Fire Department 911 0 Phelps County Hospital Rolla Emergency Management Agency 911 911 0 State Azencies Missouri Highway Patrol (573) 368-2345 0 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 (573) 751-4674 (24hrs)

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

Revised By: Maureen Henry Approved: William Bonzer

0 0

0 0

S' : *** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *

  • SOP: 507 TITLE: EMERGENCY PROCEDURES-ADMINISTRATIVE RESPONSIBILITIES Revised: October 22, 2013 Page 2 of 4 Rev
  • b. communicating with and requesting assistance from the following State and Federal Agencies as required:
  • Missouri State Highway Patrol: (573) 368-2345
  • U.S. Nuclear Regulatory Commission, Headquarters
  • Operation Center 301-951-6550
  • NRC Duty Officer (24 hr.): (301) 816-5100 or
  • (301) 951-0550.
  • Missouri State Emergency Management Agency:
  • (573) 751-2748
  • Missouri Bureau of Environmental Health:
  • (573) 751-6160 or (573) 751-4674 (24 hrs)
  • (865) 576-3131 ; or (865) 481-1000 (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />).
  • . Rolla Emergency Management Agency: (573)364-1213

. c. notifying the University of Missouri President and requesting University-Wide assistance, as needed.

d. acting as Administrative Spokesman responsible for communications with
  • the news media and city officials in the absence of both the Vice Chancellor
  • and the Chair.
2. Vice Chancellor - If offsite consequences are expected the Vice Chancellor will be 0 responsible for:
a. assuming the duties of the Chancellor in his or her absence. Rev
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.
  • d. notifying American Nuclear Insurers (860) 561-3433 as soon as possible after declaration of an Alert or Site Area Emergency.
  • e. advising the Chancellor on problems relating to insurance and liability.

B 0

  • Reviewed By: William Boazer Approved By: William Bonzer Rev 0 I 0

0

O O

0 0

  • *** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev O SOP: 654 TITLE: MEASUREMENT OF 41Ar CONCENTRATION IN THE REACTOR BUILDING .AIR -
  • Revision: October 23, 2013 Page 2 of 4 O Note: 22Nahas a 1.275 MeV gamma and 41Ar has a 1.294 MeV gamma, so by using a sodium source for comparison it is easy to determine where the argon peak will occur.

o* 5. Samplin O a. The Reactor building air sample is taken with the air tank positioned on the west side of the Reactor pool over the fuel storage area. The Reactor building

  • air sample is taken periodically to detect 4'Ar or any other gaseous activity in O the confinement building air.
i. Other samples are taken: on the east side of the Reactor pool near the reactor core, in the corner of the bay near the cage (repeat any of the Rev O previous if needed), and on the roof near fan #2 (this one should be
  • done last)
b. Position the air sample tank and collect the sample using an air pump. Allow the tank to completely fill and note the time and date of the sampling.
c. When sampling is complete, turn off the pump and close the tank valves.

0 d. Start the stop watch immediately after the sample is taken. Rev 0* 6. Analysis

a. Immediately transfer, within 10 minutes, the air sampling tank to the NaI detector in the designated room. Position the tank inside of the lead shield by Rev O placing the tank in the lead shield with the hole for the detector on top. This O allows the NaI to be placed inside the tank without placing the weight of the O tank on the detector.
b. Stop the stop watch once the counting has started. Record this number to Rev time.

calculate decay

  • Revised By: R@y Bono Approved By: William Bonzer O .

O

0 0

0 0 *** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 654 TITLE: MIEASURElivENT OF 4 1Ar CONCENTRATION 0 IN THE REACTOR BUILDING AIR Revision: October 23, 2013 Page 4 of 4 C

0 C

S d. Determine the concentration of activity of 4 1Ar taken in the grab sample of 0 the Reactor building air as follows:

C cps 60 s~co-rds 1 Ci 1 ef 1 minute 2.22 X 10 dvnz Vo lum e of tak 0 A = Concentration of 41Ar activity in sample (ýtCi/ml) eff = Currently determined efficiency of the counting setup (i.e. NaI C detector and volume of marinelli sample container) (cps/(gCi/ml))

C 5. Re-Do Record the following data in the notebook labeled "41Ar in the Reactor 0 Building."

0 a. Date of sample 0 b. Time of sample C. Count time (t)

d. Net peak count (N) 0 e. Peak 41Ar count rate (R) concentration (A)

C f.

g. Reactor power level 0 h. Building air flow rate (ft3/min or m3 /min)
i. Fan number, operating at time sample was taken.

0 0

S Revised By: Ray Bono Approved By: William Bonzer

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

0 SOP: 800 TITLE: ANNUAL CHECKLIST Revised: August 1, 2013 Page I of 10 Rev.

0 Date Commenced Date Completed Total Hours on Hour Meter 0 1. Log and Linear Drawer Calibration S a. Log and Linear Log/Period Recorder (1) Cleaned & Lube chassis as needed (v):

0 (2) Speed checked (1" per 5 minutes) (,/):

b. LOW CIC Voltage Rundown Set Point at A4TP 1: VDC x 200 - VDC Verify Rundown Initiated (/):

0 Verify Alarms Received (V):

0 0 c. 120% Full Power Rundown Set Point:  %

S Verify Rundown Initiated (,/):

Verify Alarms Received (/):

d. Log and Linear Detector/Cable Resistance Check 0 (Cables should read about 1010 ohms.)

(1) Signal Cable Resistance: Meg ohms 0 (2) High Voltage Cable Resistance: Meg ohms 0 (3) Comp. Voltage Cable Resistance: Meg ohms 0 e. Drawer Alignment - Perform the steps listed in the following sections of the drawer Instruction Manual:

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

A13TBI-1 to Common reading (+15.00):

0 A13TB1-3 to Common reading (-15.00):

0 High Voltage and Compensating Voltage Check 0

  • Low Voltage Set Point at J6: VDC S
  • Low Voltage Set Point at A4TP 1O-A4TP 1: VDC

" NON-OPERATE LED on (,/):

  • Reset High Voltage (J6): VDC

" High Voltage (A4TP1O-A4PP1): VDC

" NON-OPERATE LED off(/):

" Compensating Voltage at J7: VDC Compensating Voltage at A5TP10-A5TP1: VDC Revised By: William Bonzer Approved By: William Bonzer I Rev.

c ~g2.

  • ** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES * *
  • SOP: 800 TITLE: ANNUAL CHECKLIST Revised: March 12, 2014 Page 2 of 10 Rev.

Log Displays Picoamp Expected Tolerance for Log Log Log Initial Date 9 Current Readings Reading Bargraph Digital Recorder.

9 8 pA 1.OE-5% 4.0 E-6%-2.5 E-5%

9 86 pA 1.OE-4% 4.0 E-5%-2.5 E-4% Rev 820 pA 1.0E-3% 7.0E-4%--1.4E-3%

0 10 nA 1.OE-2% 7.0E-3%--1.4E-2%

9 80 nA I.OE-I% 7.0E-2%--1.4E-0%

S 800 nA tOE -0% 7.OE-1%-1.4E-0%

8 gLA .0E+I% 7.OE-0%-1.4E+1%

9 80 EpA 1.OE+2% 7.OE+I%-l.4E+2%

9 Period Alignment & displays (section 4.3.4)

S 4.3.4.1- Slope/voltage/sec:

0 4.3.4.2- Voltage reading, with stable source, at AITP2 & A1TP10 (0.909+/-0.02) 4.3.4.3- Voltage at A1TP2 & A1TP10 with 3 sec period:

0 Settings Period Bargraph Period Digital Period Recorder Date 0

0 Infinity (cc) 0 3 Sec Liner Displays 0 FPocep-amp Tolerance for True True Expected Linear Bargraph Linear Digital Voltage Current Expected Readings Readings Display Display Tolerances Initial Date S

0 8 iLA 8%-12% 10% 0.7V-0.9V 16 pA 18%-22% 20% 1.SV-1.7V S 24 pA 28%-32% 30% 2.3V-2.5V S 32 pA 38%-42% 40% 3. IV-3.3V Rev 0 40 pA 48%-52% 50% 3.9V-4.IV 0 48 ,A 58%-62% 60% 4.7V-4.9V 0 56 pA 68%-72% 70% 5.5V-5.7V 64 pA 78%-82% 80% 6.3 V-6.5V S 72 .uA 88%-92% 90% 7. IV-7.3V 80 pLA 98%-102% 100% 7.9V-8.1V 88 uA 108%-112% 110% 8.7V-8.9V 96 MA 118%-122% 120% 9.3V-9.7V 100 .uA 123%-127% 125% 9.9V-I0.IV Revised By: William Bonzer Approved By: William Bonzer Rev.

2ev. R

... .... .,./

0 *

  • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES **

0 SOP: 800 TITLE: ANNUAL CHECKLIST.

0 Revised: January 29, 2014 -. Page 3 of 10 Rev.

0 f. Isolated Outputs check (4.3:9)(,") - ÷.

9 g. Keypad switch test 9

Test Switch Indication 9

.1mA Log: _%_ _

Lin:  %

0 0.1 uA Log:  %'_'_ "

0 Per: -0ID4O-100 sec (V)___"

Lin: 0=- 1% (/).

9 10 pA Log: <  %

3 SEC Per: 3.0 +/- 0.1 sec (V)_.

NON-OPER L'ED On ()__

LINEAR TEST- Rising Linear Lev.el (/) Rev 0 Trio #4: . . '%

PERIOD TEST Rising Period Level (). "__

Sr. ,.:_L:". Tri1p sec S. Trip #2: " sec 0 Trin 43: sec Re-v LOG TEST Rising .og Level (./).

h. Cables Reconnected (,/):;..

0 Independent Verification of Cable Cnnection, , . Initials:

0 i. Log and Linear Drawer Calibration Complete: .iii~a. Date 0 Linear Power Channel

a. Linear Power Supply 9 (D) Clearned chassis as needed . _..
b. i.er Power Supply voltage NLY7 veter diply ___utV Imliais Dt R'evis.ed Bonzer

'y:Wiliami . .icpro-ed Bv: WilliaM Bonz.ý f

S S " * * * .MISSOURI S&T REACTOR STA.NDAR-D OPERATI[:tJ PROCEDURES ***

S SOP: 800. TITLE: AN U-Ai, CHECKLIST Revised: January 29,:-2O0.4 Page,4 oflO Rev 5"7,;

-9

-. Linear Recorder N-..

(1) Lube & Cl.,eand Chassis as needed (/"): U=

S (2) Speed check (1"/ 2 minutes) (V,:

0

d. Linear Calibration (Note: From 10-5 to 10-8, the S *-than 2% of full scale. From.

overall accuracy should be better 9 to 10-10 the overall accuracy should be.

S better than 4,%. Any instrument found to be out of calibration should be realigned in accordance with procedures.):


METER ---- RECORDER ------

PicoAmrrp Acceptable Actual Acceptable Actual S Generator 6.Ox I0-A Reading (57.A -63 jA)

Reading Reading (57%-63%')

Reading S 6.0x !06A (5.7,uA-6;3gA) (57%-63%)

6.0xl0 A (5%nA-630n.A) (57% .',.

1.O0 0UA (57nA-63nA) (57%-63%)* ___

6.0- 10-A (5_3,",-6.6nA- (53%-66%0_)

6..Ox tU,"A. A530pA-66OpA) . (.3 %-66%)

2,0.,,* ik (I30pA-260pA) (13%-26%)

Se. inezr I.T Detector/Cable Resistance Check (near/about I101 ohbms..)

S (1) Signal Cable Resistance: _ _Meg oh-ms (2) High Voltage Cable Resistance: Meg ohms k-. Comp. Voltage Cable Resistance _ _Meg ohms (4) Reco nnect al cables( /) ._._ ..

S

f. Lin~er Channel completed:. T.*intials Da!a R coniiecticnof cables ver ed. trtta _ Date S

S 0

3 Log Couant Rate Channel "

a.. t Rate Recorder (1) Luce &. Cleaned chassis as needed (./':

(,2.Rozer speed (1 "/2 minruteu )/: .

0 b Fissi.on Chanmber Preamip (U) (l.e.,eeLi chassis 'ms nee ded' .

S 0 Revised B '"z. *.A.. ,,,.......

- ed BV: V.1iIBarn 1,zer e S

9 0 **

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

9 SOP: 800 TITLE: ANNUAL CHECKLIST 9 Revised: August 1, 2013 Page 5 of 10 Rev.

c. Log Count Rate Channel Calibration 9 (Note: All readings should give 0.7 to 1.4 ratio of true-to-observed readings.)

9 Pulse Generator Meter Recorder 10 100 9 1 000 9 10 000

d. High Voltage (350 VDC to 450 VDC) 0
e. Log Count Rate Cable Check High voltage cable meg ohms 9 Signal cable Fission chamber cable meg ohms meg ohms 0

9 f. Log Count Rate Channel completed initials Date 9 Reconnect all cables 9 g. Reconnection of cables verified initials Date 0 4. Safety Amplifier System 0

a. Cable chec 9UIC I Signal MegOhms 0 eUIC I H.V. _MegOhms eUIC 2 Signal MegOhms 0 eUIC 2 H.V. _MegOhms 0 Safety Amplifier Current Tests (Safety Amplifier #1)

Applied Accepted Digital Display Accepted Bargraph Current Digital Reading Bargraph Display 0 Digital Display Display 6.7nA 9-11% 7-13%

0 13.2nA 19.8nA 19-21%

29-31%

17-23%

27-33%

26.4nA 39-41% 37-43%

9- 33.OnA 49-51% 47-53%

39.6nA 59-61% 57-63%

46.2nA 69-71% 67-73%

52.8nA 79-81% 77-83%

59.4nA 89-91% 87-93%

66.0nA 99-101% 97-103%

72.6nA 109-111% 107-113%

79.2nA 119-121% 117-123%

85.8nA 129-131% 127-133%

92.4nA 139-141% 137-143%

99.OnA 149-152% 147-153%

Revised By: William Bonzer Approved By: William Bonzer I Rev.

0 0

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

0 SOP: 800 TITLE: ANNUAL CHECKLIST Revised: August 1, 2013 Page 6 of 10 I Rev.

0 Safety Amplifier #2

0. Applied Accepted Digital Accepted Bargraph Current Digital Display Bargraph Display 0 Digital Display Reading Display 0 6.7nA 9-11% 7-13%

0 13.2nA 19.8nA 19-21%

29-31%-

17-23%

27-33%

0 26.4nA 39-41% 37-43%

33.0nA 49-51% 47-53%

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

0 46.2nA 69-71% 67-73%

52.8nA 79-81% 77-83%

59.4nA 89-91% 87-93%

66.OnA 99-101% 97-103%

0 72.6nA 109-111% 107-113%

79.2nA 119-121% 117-123%

0 85.8nA 129-131% 127-133%

92.4nA 139-141% 137-143%

99.0nA 149-152% 147-153%

0 C. *H.V. 1 Output Voltage volts 0 eMonitor H.V. 1/100 volts 0 eH.V. 2 Output Voltage -volts eMonitor H.V. 2/100 volts 9 d. H.V. 1 Failure Test 0 9 Trip Point Setting (volts)

" Scram Occurred (y/n) 0 " Magnet Power Supply SCRAM Light'Illuminated (y/n) o Reset H.V. to 300VDC (y/n) 0

e. H.V. 2 Failure Test 0

e Trip Point Setting (volts) 0

" Magnet Power Supply SCRAM Light Illuminated (y/n) 0

  • Reset H.V. to 300VDC (y/n)
f. NIM Bin Power Supply Output Voltages Readings e +24 VDC
  • -24 VDC 9 +12 VDC
  • -12 VDC e +6VDC Revised By: William Bonzer Approved By: William Bonzer Rev.

LA) L&J.'V V f~

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

SOP: 800 TITLE: ANNUAL CHECKLIST Revised: August 1, 2013 Page 7 of 10 Rev.

. -6VDC

g. AC Power Off Scram Test e 150% Full Power Annunciator (y/n)
  • Audible Alarm (y/n)

" SCRAM Occurred (y/n)

" Power Restored (y/n)

h. Safety Amplifier System Test Completed Initials Date
i. Reconnection of cables verified Initials Date_

Rev.

5. Temperature Channel (Note: All readings should be + 2°F.)
a. Verification of Temperature Readings Date Temperature C1 M 0 Range (take on reading,"

from each E 0 ::~: temperature range) E a 0

F- &c 0

0 60°F-70°F 0 70°F-80°F 0 80°F-90°F 90°F-125°F 0 125 0 F-135°F 135 0 F-145°F 0

0 0

0 0

Revised By: William Bonzer Approved By: William Bonzer Rev.

&{YU~~~YYI 5c2

9 0 *** MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***

0 SOP: 800 TITLE: ANNUAL CHECKLIST Revised: August 1, 2013 Page 8 of 10 Rev.

0 9

b. Temperature > 135 Rod withdraw prohibit test Initials __ Date 0 Thermocouple #1 Thermocouple #3 9 > 135°F Trip Temperature @

> 135°F Annunciator ('i) 0 Audible Alarm (xI)

S RWP @ Trip ('1)

S 0

0 Initials Date 0

9 c. Low Temperature Alarm 0 Temperature Thermocouple #1 Thermocouple #2 Thermocouple #3 0 < 60'F Rec Alarm (d) 0 d. Thermocouples reinstalled, cabling reconnected. Initials Date 0

6. Regulated Power Supply Initials Date 0 a. Cleaned chassis as needed (/):

0 b. Mode set for Line Conditioner (V)

. 7. Conductivity Bridge

a. Check & Cleaned chassis as needed S b. Additional Comments S 8. Rod Indicator Calibration S

S Indicator Rod 1 Rod 2 Rod 3 Reg. Rod 1 ,

S 6" 12" 18" 24" S Rod Speeds (in/min)

Initial Date Revised By: William Bonzer Approved By: William Bonzer Rev.

0 9

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES **
  • 0 SOP: 800 TITLE: ANNUAL CHECKLIST Revised: August 1, 2013 Page 9 of 10 Rev.

9 0 9. Fire Alarm Check 0 a. Cleaned system containers as needed (V) __

b. Checked batteries (-/)

0 c. Checked pull stations (V) 0 e. Checked smoke detectors (/)

f. Check beam smoke detector (V/)

0 g. Audibles & Visuals (V)

h. Monitoring Station (V) 0 i. Additional comments 0 Completed Initial Date
10. Security System Check 9 a. Door Sensors (,/)

0 b. Motion Detectors (V)

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

0 e. Battery (V) 9 f. High Radiation ($)

0 g. Low Pool Water (V)

h. Additional Comments:

Completed Initial Date 0 Initial Date 0 11. Public Address System

a. Cleaned chassis as needed
b. Additional Comments:

0 12. Hand and Foot Monitor 9 a. Cleaned chassis as needed 0 b. Perform Source Check with;_

c. Additional Comments:

9 0 13. Portal Detector

a. Cleaned chassis as needed 9 b. Perform Source Check with:

9 c. Additional Comments:

S 14. Constant Air Monitor

a. Cleaned chassis and recorder as needed S b. Perform Source Check with:
c. Additional Comments:

Revised By: William Bonzer Approved By: William Bonzer Rev.

LI) ~Q& 1A1 ~

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

SOP: 800 TITLE: ANNUAL CHECKLIST Revised: March 12, 2014 Page 10 of 10 Rev.

I Rev

15. Power Calibration (SOP 816)
16. RAM Calibration - RAM Calibration shall be performed annually. Record the latest date the RAM calibration was performed.

Annual Calibration Comments:

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

Comments:

Reactor Manager Date Revised By: William Bonzer Approved By: William Bonzer Rev.

W2Q SLa" 610LLtia--

0

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

SOP: 813 TITLE: ROD DROP TIME MEASUREMENT Complete Revision: September 5, 2013 Page 1 of 3 0 A. PURPOSE 0 To provide instructions for determining accurate and consistent control rod drop times.

B. PRECAUTIONS, PREREQUISITES, OR LIMITATIONS

01. Complete a Pre-Startup Checklist prior to withdrawing rods unless core loading is below 50% critical mass.
2. Rods shall only be withdrawn one at a time for the purpose of these tests.
3. The rod drop time for each rod must be less than 1 second. If the rod drop time exceeds 0 1 second the rod shall be visually inspected for pitting and cracking.
4. Rod drop times must be measured a) semiannually, b) when a control assembly is moved to a new core position, c) when a magnet assembly has been removed, and d) after rod visual inspections. (Tech. Spec. 4.2.1.)

C. PROCEDURE

  • ' EQUIPMENT NEEDED:
  • 1. Tenma model 72-8385 (or equivalent) oscilloscope
  • ) 2. Microphone S"3. BNC cable
  • 4. Duct tape 0

0

  • STEPS:

01 1. Tape microphone onto one of the rod shrouds.

0 2. Connect microphone to channel I input jack of the scope.

  • 3. Connect BNC cable from channel 2 input of the scope to the rod drop BNC
  • located behind the startup channel.
  • 4. Perform reactor Pre-Startup Checklist as required.
  • 5. Raise each rod 3 inches.
  • 6. Determine the drop current for each rod by slowly reducing magnet current until rod drops. Record the drop currents on the rod drop measurement form.

0 7. Insert all rods to 0.0 inches i 8. Set magnet current for each magnet about 20 mAmps above drop current.

0 0 Written By: Ray Kendrick Approved By: William Bonzer 0

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

SOP: 813 TITLE: ROD DROP TIME MEASUREMENT

  • Complete Revision: September 5, 2013 Page 2 of)3 10 9. Recommended scope control settings are as follows:
a. Trigger mode
  • i. Type: edge ii. Source: ch2
  • O iii. Slope: rise
  • iv. Mode: single
  • "b. Run/stop button: press until green
c. Input controls (chl)
i. Coupling: AC
  • ii. BW limit: close
  • 0 iii. Volts/div: coarse iv. Probe:xl
v. Invert: close vi. Volts/division, bottom Of scope: 2mV
  • d. Input controls (ch2)
  • i. Coupling: DC

. iii. BWlimit: close iii. Probe: xl iv. Invert: close 0 v. Volts /division, bottom of scope :5v

  • e. Time/div: 100 msec.
  • 10. Measure the rod drop times as follows:
a. Fully withdraw (24 inches) one rod. Verify the Run/Stop button is green.
  • b. Press the SCRAM button. (Sweep should start and the sound of rod hitting
    • bottom should be heard.)
  • c. Adjust the left cursor to the ch2 rise and the right cursor to the chl burst
  • O beginning.
d. Record the AT on the rod drops form.
11. Repeat step 10 for other rods as necessary.
12. Shut down or secure the reactor and remove all the rod drop equipment.

9 13. Complete a reactor secured checklist, if appropriate, list all data on the rod drop time

  • measurement form and forward to the reactor manager for review.

9 0

0 0

Written By: Ray Kendrick Approved By: William Bonzer 0 2Y

0

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

0 SOP: 813 TITLE: ROD DROP TIME MEASUREMENT Complete Revision: September 5, 2013 Page 3 of 3 0"

9 0

0 ROD DROP TIME MEASUREMENT FORM 0

0 [DESCRIPTION ROD [ ROD 2 ROD 3 9 1. Drop Current 0 2. Current Used for Drop 0 Time Measurement 0 3. Rod Drop Time 0

Performed By: Date:

0 0 Comments:

0 0

S 0 Reactor Manager Review:

9 S

S .

S S

S Written By: Ray Kendrick Approved By: William Bonzer W~ 3lLA-