ML081300428

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Transmittal of 2007-2008 Annual Progress Report Re Safety Analysis Report for the Missouri University of Science and Technology Reactor
ML081300428
Person / Time
Site: University of Missouri-Rolla
Issue date: 04/28/2008
From: Bonzer W
Missouri Univ of Science & Technology
To:
Office of Nuclear Reactor Regulation
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Download: ML081300428 (49)
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Text

MISSOURI MISSOURI'UNIVERSITY OF SCIENCE AND TECHNOLOGY Formerly University of Missoun-Rolla April 28, 2008

Dear Sir:

Please find enclosed the Annual Progress Report 2007-2008 for the University of Missouri-Rolla Reactor Facility (License R-79, Docket No: 50-123). This report is being filed under the reporting requirements of our Technical Specifications. Copies of this report are also being sent to our Regional Administrator and Project Manager.

Sincerely, William Bonzer Reactor Manager mh Enclosure xc: John Nguyen, Project Manager (NRC)

Document Control Desk (NRC)

U.S. NRC Region III American Nuclear Insurers, c/o Librarian University of Missouri-Columbia Research Reactor (MURR)

Chancellor John F. Carney III (MST)

Mr. Ray Bono, Radiation Safety Officer (MST)

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

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

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

Nuclear Reactor Facility Phone: 573-341-4236

  • 250 West
  • Fax:

1 3 m1 Street 573-341-4237 *

  • Rolla, MO 65409-0630 Email webonzer@mst.edu A~2~

SAFETY ANALYSIS REPORT FOR THE MISSOURI UNIVERSITY OF SCIENCE AND TECHNOLOGY REACTOR

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

NUCLEAR REACTOR FACILITY April 1, 2007 to March 31, 2008 Submitted to The U.S. Nuclear Regulatory Commission And The Missouri Science and Technology University

Table of Contents

SUMMARY

1.0 INTRODUCTION

......................................................................................................... I

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 .................................................................................. 4 2.3 RADIATION SAFETY COMMITTEE ..................................................................... 5 2.4 HEALTH PHYSICS......................................................................................... 6 3.0 REACTOR OPERATIONS.............................................................................................. 7 4.0 EDUCATIONAL UTILIZATION.................................................................................... 14 5.0 REACTOR HEALTH PHYSICS ACTIVITIES ................................................................... 18 5.1 ROUTINE SURVEYS...................................................................................... 18 5.2 BY-PRODUCT MATERIAL RELEASE SURVEYS...................................................... 18 5.3 ROUTINE MONITORING ................................................................................ 18 5.4 WASTE DISPOSAL........................................................................................ 19 5.5 INSTRUMENT CALIBRATIONS ......................................................................... 19 6.0 PLANS .................................................................................................................... 20 6.1 ADMINISTRATIVE CHANGES...............................I............................................ 20 6.2 RELICENSING ............................................................................................ 20 6.3 INSTRUMENTATION UPGRADE ........................................................................ 20 6.4 REACTOR OPERATOR TRAINING ...............................................21 APPENDIX A: SOPS CHANGED DURING THE 2007-2008 REPORTING YEAR ............................ 22 LIST OF TABLES TABLE 3-1. CORE I101W TECHNICAL DATA ...................................................................... 7 TABLE 3-2. UNSCHEDULED SHUTDOWNS FOR 2007-2008 ...................................................... 8 TABLE 3-3. MAINTENANCE FOR 2007-2008................................................................. 11 TABLE 3-4. REACTOR UTILIZATION ........................................................................ 13 TABLE 3-5. EXPERIMENTAL FACILITY USAGE.................................................................. 13 TABLE 4.1. UMR CLASSES AT REACTOR FACILITY ........................................................... 15 TABLE 4.2. REACTOR SHARING PROGRAM...................................................................... 16 LIST OF FIGURES Figure 3-1. UMRR Core 101W Configuration...................................................... 7

iii

SUMMARY

During the 2007-2008, reporting period the Missouri University of Science and Technology Reactor (MSTR) was in use for 861.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br />. The major part of this time, about 95%, 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 MSTR courses over the year for 3,393 student-hours. About 4,875 visitors visited the reactor during the past year. There were 757 participants, mostly high school students, in the U.S. Department of Energy Reactor Sharing Program.

The reactor produced 14,063.29 kilowatt-hours of thermal energy using approximately 0.615 grams of uranium. A total of 397 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 Facility for the period April 1, 2007 to March 31, 2008 The reactor operates as a University facility. It is available to the faculty and students from the 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 BackgZround Information The Missouri University of Science and Technology Reactor (formally University of Missouri-Rolla Reactor) attained initial criticality on December 9, 1961. The MSTR was the first operating nuclear reactor in the State of Missouri. The Bulk Shielding Reactor at Oak Ridge National Laboratory is the basis for the reactor's design. The reactor is a light water, open pool reactor cooled by natural convective flow. The fuel is MTR plate-type fuel. The initial licensed power was 10 kW. The licensed power was up-graded to 200 kW in 1966. During the summer of 1992, the reactor fuel was converted from highly enriched uranium fuel to low-enriched uranium fuel.

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

The facility also contains a counting laboratory that has both gamma and alpha spectroscopy capabilities. The gamma spectroscopy system includes germanium and sodium-iodide detectors, associated electronics, and state-of-the-art data acquisition and spectrum analysis software. The alpha spectroscopy system consists of a surface barrier detector and data acquisition equipment.

Additionally, there is a thermo luminance dosimeter reader and digital radiography imager for student and faculty usage.

The MST Reactor also uses several biometric devices to enhance its traditional security system.

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

The application and supporting documentation to renew the MSTR license was submitted to NRC August 30, 2004 and announced in the Federal Register on November 29, 2004 under title, Notice of License Renewal Application for Facility Operating License, University of Missouri - Rolla (Volume 69, Number 228; Page: 69418-69419). MSTR is operating under an extension of the existing license until the license renewal is completed.

An independent auditor from the University of Columbia audited the Reactor Facility on October 24, 2007. 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. Basic Engineering 50, 'Engineering Mechanics - Statics'
2. Chemistry 2, 'General Chemistry Laboratory'
3. Chemistry 8, 'Qualitative Analysis Laboratory'
4. Chemistry 355, 'Instrumental Methods Laboratory'
5. Civil Engineering 310, 'Senior Design Class'
6. Engineering Management 386, 'Safety Engineering Management'
7. Mechanical Engineering 229, 'Energy Conversion'
8. Life Sciences 352, 'Biological Effects of Radiation'
9. Physics 4 & 5, 'Concepts in Physics'
10. Physics 7, 'Environnemental Physics'
11. Physics 107, 'Modern Physics'
12. Physics 207, 'Modern Physics' II
13. Physics 322, ' Advanced Physics'

3 SOPs were revised, over the past year in order to improve and keep current the operations and efficiency of the MSTR. The.following is a list of SOPs revised during the reporting period:

1. SOP Index Index of SOPs3O3
2. SOP 107 Permanent Log, Hourly Log, and Operational Data
3. SOP 303 Auxiliary Pool Water Cooler System Operations
4. SOP 501 Emergency Procedures for Reactor Building Evacuation
5. SOP 507 Emergency Procedure - Administrative Responsibilities Note: The above listed SOP revisions are provided in Appendix A.

4 2.0 REACTOR STAFF AND PERSONNEL 2.1 Reactor Staff Name Title Dr. Arvind Kumar1 Reactor Director Mr. William Bonzer Reactor Manager & Senior Operator Ms. Maureen Henry Senior Secretary Mr. Brian Porter Senior Electronics Technician & Reactor Operator Mr. Daniel Estel Senior Lab Mechanic & Senior Operator

1. Effective 5/11/2007 2.2 Licensed Operators Name License
1. William Bonzer Senior Operator
2. Daniel Estel Senior Operator
3. Mathew Dennis1 Senior Operator
4. Alfred Schovanez] Senior Operator
5. Michelle Minard Senior Operator
6. Zak Kulage Senior Operator
7. Victor Smith Senior Operator 2
8. Jeffery Joggerst Senior Operator
9. Chad Lisle Reactor Operator
10. Brian Porter Reactor Operator
11. Seth Bradley' Reactor Operator
12. Jason Hall' Reactor Operator
13. Michael Lacey' Reactor Operator
14. Nathan Ayres Reactor Operator
15. Chris Speer Reactor Operator
16. Zach MillerI Reactor Operator

5

17. Beth Faughn' Reactor Operator
18. Krista Kaiser Reactor Operator
19. Andrea Mayor Reactor Operator
1. Termination date 8/28/07
2. Effective date 12/19/07 2.3 Radiation Safety Committee The Radiation Safety Committee meets quarterly. The committee met on 5/9/2007, 8/14/2007, 12/11/2007 and 3/6/2008 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
3. Mr. William Bonzer Nuclear Reactor
4. Mr. Randy Stoll Business Services
5. Dr. Roger Brown1 Biological Sciences
6. Dr. Robert Dubois Physics
7. Dr. Seungjin Kim 3 Mining & Nuclear Engineering
8. Dr. Ekkehard Sinn' Chemistry
9. Dr. David Wronkiewicz Geological Sciences & Geology
10. Dr. Shoaib Usman Mining & Nuclear Engineering
11. Ms. Michelle Bresnahan Environmental Health and Safety Services
12. Dr. Robert Aronstam2 Biological Sciences
13. Dr. Charles Chusuei 2 Chemistry
14. Dr. Jeffrey Kingw 4 Miningw & Nuclear Engineering
  • v I terminated 12/11/2007 2 effective 12/11/2007 3 terminated 5/09/2007 4 effective 5/09/2007

6 2.4 Health Physics Health Physics support is provided through the Environmental Health and Safety Department, which is organizationally independent of the Reactor Facility operations group.

.Health Physics personnel are listed below:

Name Title

1. Mr. Ray Bono Director of Environmental Health and Safety
2. Mr. Brian Smith Industrial Hygienist
3. Ms. Michelle Bresnahan Health Physicist
4. Ms. Krista Kaiser Health Physics Technician (part time)

7 3.0 REACTOR OPERATIONS Core Confirmation 101W is presently in use. The "W" mode core is completely water reflected and is used for normal reactor operations. The "T" mode (core positioned near graphite thermal column) may be used for various experiments, including beam port and thermal column experiments.

Table 3-1 presents pertinent core data and Figure 3-1 shows the core configuration of core 101W. The excess reactivity, shutdown margin, and rod worth's were measured in cold, clean conditions.

Table 3-1. Core 101W Technical Data Parameter Value Rod 1 2.73 %Ak/k Rod 2 2.69 %Ak/k Rod 3 3.22 %Ak/k Reg Rod 0.371%Ak/k Excess Reactivity 0.496 %Ak/k Shutdown Margin* 4.92 %Ak/k

  • Assumes Rod 3 (highest worth rod) and Reg Rod are fully withdrawn.

A B S KEY TO PREFIXES C F-8 F-4 C-4 F - Standard Elements D F-13 C-1 F-3 F-2 F-12 F-15 C - Control Elements E F-10 C-2 F-1 C-3 F-9 F-14 BR - Bare Rabbit CR - Cadmium Rabbit F CR F-5 F-6 F-7 BR S - Source Holder 1 2 3 4 5 6 7 8 9 Figure 3-1. MSTR Core 101W Configuration

8 Table 3-2 lists unscheduled shutdowns during the reporting period. This consisted of twenty rundowns, which the majority were from two sources, electronic noise and students operating the reactor for a nuclear engineering class. Electronic noise periodically activated the 120% Full Power rundown trip. Students learning to operate the reactor at times improperly changed scales on the Linear meter, which activated the 120% Demand Rundown. The unplanned shutdowns, which included a 150% Full Power scram, two non-labeled scrams and one non-labeled rundown were caused by electrical power issues to the reactor building, such as loss of power or a power flicker. Reactor power never increased above 100% full power during any of these shutdowns.

Table 3-2: Unscheduled Shutdowns for 2007-2008 SCRAMS Date Type of Shutdown/Cause and Corrective Action Taken 4/2/07 150% Full Power Scram Cause: Electronic noise spike.

Corrective action: None taken. SRO on Duty granted permission to restart the reactor.

RUNDOWNS Date Type of Rundown/Cause and Corrective Action Taken 4/16/07 120% Demand Rundown Cause: Operator did not upscale the Liner Channel as required.

Corrective action: Advised operator to pay attention to the Liner recorder. SRO on Duty granted permission to restart the reactor.

4/23/07 120% Demand Rundown Cause: Operator inattention to the Liner Channel Corrective action: Instructed operator to pay attention to Liner recorder. SRO on Duty granted permission to restart the reactor.

9 5/18/07 High Area Radiation Rundown Cause: Sample from rabbit system, failed to return to glove box. Corrective action: SRO shot more gas through the transfer tube to move the sample to the glove box. SRO on Duty granted permission to restart the reactor.

6/12/07 Regulation Rod Insert Limit on Auto Rundown Cause: Operator inattention when switching into auto-mode.

Corrective action: SRO instructed operator to pay attention to regulating rod height before engaging the auto-controller. SRO on Duty granted permission to restart the reactor.

6/29/07 120% Full Power Rundown.

Cause: Electronic noise spike from auto-controller.

Corrective action: None taken. SRO on Duty granted permission to restart the reactor.

6/29/07 120% Full Power Rundown.

Cause: Electronic noise spike from auto-controller.

Corrective action: None taken. SRO on Duty granted permission to restart the reactor.

6/29/07 120% Full Power Rundown.

Cause: Electronic noise spike from auto-controller.

Corrective action: None taken. SRO on Duty granted permission to restart the reactor.

9/12/07 Regulation Rod Insert Limit on Auto Rundown Cause: Operator inattention when switching into auto-mode.

Corrective action: SRO instructed operator to pay attention to regulating rod height before engaging the auto-controller. SRO on Duty granted permission to restart the reactor.

9/28/07 120% Full Power Rundown.

Cause: Electronic noise spike.

Corrective action: None taken. SRO on Duty granted permission to restart the reactor.

11/14/07 120% Demand Rundown.

Cause: Operator inattention to Liner Channel.

Corrective action: SRO instructed operator to pay closer attention to the Liner Channel. SRO on Duty granted permission to restart the reactor.

12/5/07 120% Demand Rundown.

Cause: Electronic noise when operator switched from auto to manual mode.

Correction action: None taken. SRO on Duty granted permission to restart the reactor. I

10 2/5/08 120% Demand Rundown.

Cause: Operator inattention to Liner Channel.

Corrective action: SRO instructed operator to pay closer attention to the Liner Channel. SRO on Duty granted permission to restart the reactor.

2/6/08 Regulation Rod Insert Limit on Auto Rundown Cause: Operator inattention when switching into auto-mode.

Corrective action: SRO instructed operator to pay attention to regulating rod height before engaging the auto-controller. SRO on Duty granted permission to restart the reactor.

2/22/08 120% Demand Rundown.

Cause: Operator depressed incorrect range scale switch to upscale.

Corrective action: The operator was instructed to use the correct range scale switch. SRO on Duty granted permission to restart the reactor.

2/28/08 120% Demand Rundown.

Cause: Noise spike from auto-controller when switching to manual mode.

Corrective action: None taken. SRO on Duty granted permission to restart the reactor.

3/7/08 120% Full Power Rundown.

Cause: Electronic noise when operator switched from auto to manual mode.

Correction action: None taken. SRO on Duty granted permission to restart the reactor.

3/7/08 120% Full Power Rundown.

Cause: Electronic noise when auto-controller switched from auto to manual mode.

Correction action: None taken. SRO on Duty granted permission to restart the reactor.

3/7/08 12 0% Full Power Rundown.

Cause: Electronic noise when auto-controller switched from auto to manual mode.

Correction action: None taken. SRO on Duty granted permission to restart the reactor.

3/10/08 120% Demand Rundown.

Cause: Operator inattention to Liner Channel.

Corrective action: SRO instructed operator to pay closer attention to the Liner Channel. SRO on Duty granted permission to restart the reactor.

3/28/08 Regulation Rod Insert Limit on Auto Rundown Cause: Operator inattention when switching into auto-mode.

Corrective action: SRO instructed operator to pay attention to regulating rod height before engaging the auto-controller. SRO on Duty granted permission to restart the reactor.

I1I UNPLANNED SHUTDOWNS Date Type of Shutdown/Cause and Corrective Action Taken 4/26/07 Scram.

Cause: Power loss to building.

Corrective action: Restored power to the building. SRO on Duty granted permission to restart the reactor.

6/27/07 Rundown Cause: Momentary power outage.

Corrective action: None taken. SRO on Duty granted permission to restart the reactor.

8/24/07 Scram.

Cause: Electrical power flicker.

Corrective action: Rotated off/on by-pass switch on filtering power supply. SRO on Duty granted permission to restart the reactor.

Table 3-3: Maintenance for 2007-2008 Date Problem/Event and Action Taken 5/2/07 Issue: Control room equipment power outage Action taken: Performed general maintenance and check on control equipment room filtering power supply.

7/5/07 Issue: Auto-controller withdrew and inserted the regulating rod too frequently.

Corrective action: Adjusted the proportional band and reset/repeats on the auto-controller.

9/21/07 Issue: Difficult to test Lower Level RAM's trip point setting, Action taken: Adjusted check source holder on Lower Level RAM.

10/18/07 Issue: Above shim range indicator light would not illuminate.

Action taken: Adjusted control rod #3 shim range indicator micro switch.

10/30/07 -Issue: Pool temperature measurements were unstable.

Action taken: Increased sampling rate time on Temperature Recorder and tested RWP trip point setting.

12 11/16/07 Issue: Clatter noise when repositioning control rod #3.

Action taken: Replaced wire terminal on brake solenoid control drive #3.

3/11/08 Issue: Auto-controller not withdrawing regulating properly.

Action taken: Replaced two vacuum tubes. Checked for proper regulating rod withdrawal and insertion.

3/12/08 Issue: Auto-controller not withdrawing regulating rod properly.

Action taken: Removed auto-controller for bench testing. Cleaned pins, relays, connections, and approach potentiometer. Installed auto-controller and performed a weekly checklist.

3/25/08 Issue: Auto-controller not withdrawing regulating rod properly.

Action taken: Replaced console auto-manual switch. Cleaned corresponding equipment room relays and wiper blades contacts within the Liner recorder.

Removed the auto-controller for bench testing. Replaced two capacitors, one relay, and cleaned contacts on another relay. Reinstalled the auto-controller and checked for proper set, withdraw, and insertion actions.

2

13 Table 3-4. Reactor Utilization

1. Reactor use 861.75 hrs.
2. Time at power 525.18 hrs.
3. Energy generated 14,063.29 kW/hrs
4. Total number of samples Neutron irradiated 397
5. U-235 Burned 0.615 g
6. U-235 Burned and Converted 0.727 g Table 3-5. Experimental Facility Usage Facility Hours Bare Rabbit Tube 31.8 hr Cadmium Rabbit Tube 0.07 hr Beam Port 10.12 hr Thermal Column 1.08 hr Other Core Positions 0 hr Gamma Exposures 0 hr Total 43.07 hr

14 4.0 EDUCATIONAL UTILIZATION The reactor facility supported several Missouri University of Science and Technology (Missouri S&T) courses in the past year for a total of 3393 student hours. The number of Missouri S&T students utilizing the facility was 1137. This usage is a direct result of an aggressive and continuing campus wide "outreach" program. The reactor facility provided financial support for five students with hourly wages. Additionally, students from several universities, colleges and high schools have used the facility.

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

The University of Missouri-Columbia Nuclear Engineering Department again sent its NE 404 class, "Advanced Reactor Laboratory," to our facility (spring, 2007 and spring of 2008) for a total of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to participate in a wide variety of reactor-based experiments. The MSTR staff and student-licensed operators conducted the laboratory.

The Reactor Sharing Program, which was 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, 757 students and instructors from 122 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 4,875 persons visited the facility during this reporting period. Tour groups are typically given a brief orientation and/or demonstration by a member of the reactor staff.

15 Table 4-1. Missouri S&T Classes at Reactor Facility 2007-2008 Reporting Period Semester CLASS NUMBER/TITLE # OF TIME AT STUDENT STUDENTS REACTOR HOURS WS 07 NE 25 Nuclear Technology Applications 20 10 200 WS 07 NE 206 Reactor Operations I 18 9 162 WS 07 NE 308 Reactor Laboratory II 12 16 192 WS 07 NE 312 Gamma Lab 18 1.5 27 WS 07 NE 312 Neutron Lab 18 1.5 27 WS 07 NE490 Graduate Research 2 35 70 SS 07 NE 206 Reactor Operations I 2 13.5 27 FS 07 NE 206 Reactor Operations I 6 24 144 FS07 NE25 Nuclear Technology Applications 19 2 38 FS07 NE304 Reactor Laboratory I 33 20 660 FS 07 Chemistry Half Life Labs 745 0.5 373 WS 08 NE 206 Reactor Operations I 26 16 416 WS 08 NE 308 Reactor Laboratory II 33 26 858 WS 08 NE 25 Nuclear Technology Applications 25 2 50 WS 08 Chemistry,.Half Life Labs 135 4.0 540 WS 08 UMC NE404 Labs 12 6 72 WS 08 UMC NE404 Labs 12 6 72 WS 08 NE490 Graduate Research 1 65 65 Totals 1137 258 3393

16 Table 4-2 Reactor Sharing Program 2007-2008 (Reporting Period)

Date Participants Number Hours 4/2/07 Bonneville High School 49 2 4/4/07 Bill Bleckman & Fort Leonard Wood Officers 3 1 4/6/07 Open House Spring 8 2 4/20/07 Individual Tours April 6 1 4/23/07 St. Elizabeth High School 11 1.5 4/25/07 FBI Tour 6 1 4/27/07 Lincoln University of Missouri, Jefferson City Tour 9 1 4/30/07 Cabool High School 11 1.5 5/15/07 Canbera Visitors 2 1.5 5/16/07 Andrea Mayor 1 4 5/2007 Individual Tours May 2007 8 1.5 6/6/07 UMR Advancement Department 8 1.5 6/7/07 Minority Introduction to Engineering 11 1 6/12/07 Linn State College 12 8 6/19/07 Jackling Camp Tour 15 1 6/20/07 Jackling Camp Tour 12 2 6/21/07 Jackling Camp Tour 9 1 6/21/07 Minority Introduction to Engineering 15 1 6/26/07 Jackling Camp Tour 21 1.5 6/27/07 Jackling Camp Tour 13 3 6/28/07 Jackling Camp Tour 13 1 7/10/07 Jackling Camp Tour 13 1 7/1/07 . Jackling Camp Tour ..... 21 2 7/12/07 Jackling Camp Tour 12 1.5 7/16/07 Nuclear Engineering Camp Focus Group 10 2 7/17/07 Nuclear Engineering Camp Focus Group 10 2 7/18/07 Nuclear Engineering Camp Focus Group 10 1

17 7/18/07 Nuclear Engineering Camp Tour 33 5 7/23/07 Chemical Engineering Fort Leonard Wood School 17 1.5 7/24/07 Nuclear Engineering Focus Group 10 1.5 7/25/07 Nuclear Engineering Camp Tours 30 3.5 7/26/07 Nuclear Engineering Focus Group 10 2 8/8/07 Individual Tours August 2007 15 2.3 8/9/07 IT Tour 2 .5 8/9/07 Fort Leonard Wood Chemical School 18 1.5 9/2007 Individual tours September 2007 11 3.0 10/2007 Fort Leonard Wood Chemical School 24 1.5 10/1/07 American Nuclear Society Tour 30 1.0 10/2007 Individual Tours October 2007 1 .5 11/8/07 East Central College 15 1.5 11/9/07 Fort Leonard Wood Chemical School 17 1.5 11/14/2007 Mansfield High School 24 1.5 1/29/08 Fort Leonard Wood Chemical School 21 1.5 1/2008 Individual Tours January 2008 10 2 2/2008 Individual Tours February 2008 7 1.5 2/9/08 Atlantic Student Tour 41 2 2/16/08 Boy Scouts 44 2 3/2008 Individual tours 16 4 3/19/08 Fort Leonard Wood Chemical School 12 1.5 3/11/08 Hazelwood High School 30 2 Totals 757 93.3

18 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, pooi water activity, and waste disposal. Releases of all by-product material to authorized, licensed recipients are surveyed and recorded. In addition, health physics activities include calibrations of portable and stationary radiation detection instruments, personnel training, special surveys and monitoring of non-routine procedures.

5.1. Routine Surveys Monthly radiation exposure surveys of the facility consist of direct gamma and neutron measurements. No unusual exposure rates were identified. Monthly surface contamination surveys consist of 20 to 40 swipes counted separately for alpha and beta/gamma activity. No significant contamination outside of contained work areas was found.

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

5.3. Routine Monitoring Seventy-six reactor facility personnel and students involved with the operations in the reactor facility are currently assigned Luxel, Optically Stimulated Luminescence (OSL) dosimeters. Three (Reactor Staff) have beta, gamma, neutron dosimeters which are read twice monthly. There are four area beta, gamma, neutron dosimeters and one TLD ring dosimeter, which are also read bi-monthly.. There are also two 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 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 monitored with direct reading dosimeters. No visitors received any reportable or significant

19 exposure..

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

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 2007 through March 2008 sample concentrations averaged 5.838x 10-6 ýtCi/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 45,342.70 ýtCi of Ar-41 were released into the air.

5.4. Waste Disposal Solid waste, including used water filters, used resins, and contaminated paper/gloves is stored and/or transferred to the campus waste storage area for later shipment to a commercial burial site. Water is analyzed for radioactive contamination and approval is required before the water is released. During this period there were no waste barrels transferred from the reactor facility to the DMSF on campus.

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

20 6.0 PLANS The reactor staff will be heavily involved in several major projects during the next reporting period; 1) license renewal process, 2) revising standard operations procedures, 3) installing new reactor nuclear instrumentation, and 4) continuation of the reactor operator training program.

6.1 Administrative Changes The Reactor Director position has been filled by Dr. Arvind Kumar, Chair of the Missouri S&T Nuclear Engineering department. He has replaced Reactor Manager, Mr. William Bonzer, who was the Interim Reactor Director.

A Technical Specification Amendment was submitted to and approved by the NRC to change the Level One position from the Dean of the School of Mines and Metallurgy to the Chair of the Mining and Nuclear Engineering Department. Dr. Samuel Frimpong is the Chair of the Mining and Nuclear Engineering Department.

6.2. Relicensing License renewal activities will continue during the upcoming reporting period. The present license is valid until NRC completes relicensing. NRC has reviewed materials sent to NRC in August of 2004 and has requested additional information. The response for additional information was sent to NRC in a timely matter.

6.3. Instrumentation Upgrade The reactor instrumentation upgrade is a continual process. A digital radiography imager has been purchased and used at the beam port. Laboratory equipment is being upgraded to enhance the neutron activation analysis labs and research. A broad energy high purity germanium detector with greater efficiency and resolution is intended to be purchased within the next reporting period. The Nuclear Engineering Department intends to create a heavily shielded cell in the reactor facility to work with highly active samples, which may be remotely monitored by students.

21 6.4 Reactor Operator Training One Missouri S&T student obtained a Senior Operator license during this reporting period. 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.

22 APPENDIX A.

STANDARD OPERATING PROCEDURES CHANGED DURING THE 2007-2008 REPORTING YEAR

      • MISSOURI S&T REACTOR STANDARD OPER ATING PROCEDTURES ***.

SOP: INDEX TITLE: INDEX Revised: December 19, 2007 Page 1 of3 SOP 100-199 Routine Reactor Operation SOP 100 Preamble SOP 101 General Operational Procedures SOP 102 Pre-Startup Checklist Procedures SOP 103 Reactor Startup to Low Power SOP 104 Reactor Power Changes and Stable Operations SOP 105 Reactor Shutdown & Reactor Securing Procedures SOP 106 Restart of Reactor When It Is Not Secured SOP 107 Permanent Log, Hourly Log, and Operational Data SOP 109 Determination of Control Rod Worths by the Rod Drop Method SOP 110 Calibration of Control Rods by Positive Period Method SOP 111 Measurement of Core Excess Reactivity and Determination of Shutdown Margin SOP 112 Fuel Management SOP. 150 Response to Alarms SOP 151 Response to a High Area Radiation Alarm SOP 200-299 Facility Operations SOP 200 Bridge Movement Procedure SOP 204 Demineralizer Regeneration SOP 206 Installation and Removal of Experimental Facilities SOP 207 Fuel Handling SOP 208 Reactor Security SOP 209 Securing the Building SOP 210 Occupying Building When Intrusion System Inoperative SOP 300-399 Special Operations SOP 301 Pool Water System.

SOP 302 Inspection of Control Rod SOP 303 Pool Water Cooler System SOP 305 Operation Without Magnet Contract Light Revised By: Maureen Henry Approved By: William Bonzer I to.

    • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES** I Rev SOP: INDEX TITLE: INDEX Revised: December 19, 2007 Page 2 of 3 SOP 306 Estimation of Activity and Reactivity Worth of a Sample SOP 308 Restoration of Power Following a Power Outage SOP 309 Response to a Coolant System Leak SOP 310 Facility Modifications SOP 311 Receipt of Licensed Materials SOP 312 Critical Experiment Procedures SOP 400-499 Reserved for Future Use SOP 500-599 Emergency Procedures SOP 501 Emergency Procedures for Reactor Building Evacuation SOP 502 Emergency Procedures for an Unusual Event SOP 503 Emergency Procedures for an Alert SOP 504 Emergency Procedures for a Site Area Emergency SOP 505 Enhanced Reactor Security SOP 506 Bomb Threat SOP 507 Emergency Procedures - Administrative Responsibilities SOP 508 Tornado Threat SOP 509 Fire SOP 510 Earthquake SOP 511 Response to Missing Special Nuclear Material SOP 600-699 Health Physics Procedures SOP 600 General Health Physics SOP 601 Handling of Radioactive Samples SOP 602 Entry Into A High Radiation Area SOP 603 Release of By - Product Materials On Campus SOP 604 Radioactive Waste Handling Criteria SOP 615 Radiation Work Permit SOP 620 Decontamination Procedures SOP 621 Guidelines for Emergency Exposures SOP 622 Handling Injured in Radiation Accidents SOP 650 Radiation Area Survey Revised By: Maureen Henry Approved By: William Bonzer
      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES **Rev SOP: INDEX TITLE: INDEX Revised: December 19, 2007 Page 3 of 3 SOP 651 Contamination Survey SOP 652 Pool Water Tritium Analysis SOP 653 Sealed Source Leak Test SOP 654 Measurement of 41 A-r Concentration in the Reactor Building Air SOP 655 Radiation Area Monitor (RAM) Calibrations SOP 700 - 799 Experiments SOP 701 Request for Reactor Projects SOP 702 Irradiation Request Forms SOP 703 Reactor Use Forms SOP 710 Insertion and Removal of Experiments SOP 711 Beam Hole Facility SOP 712 Thermal Column Facility SOP 800 - 899 Reactor Instrumentation SOP 800 Semi-Annual Checklist SOP 801 Log N and Linear Drawer Calibration SOP 802 Linear Channel SOP 803 Log Count Rate (LCR) Channel SOP 804 Safety Amplifier System SOP 805 Auto Control System SOP 806' Temperature Channel SOP 809 Relay Test SOP 810 Weekly Check SOP 811 Fire and Smoke Alarm System SOP 812 Confinement and Ventilation System Check SOP 813 Rod Drop Time Measurement SOP 816 MSTR Power Calibration Rev SOP 818 Functional Test of Building Security System Revised By: Maureen Henry Approved By: William Bonzer

MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES Rev SOP: 107 TITLE: PERMANENT LOG, HOURLY LOG AND OPERATIONAL DATA Revised: January 3, 2008 Page 1 of 6 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 to the Senior Operator 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. HourlyLog Entries
a. The hourly log sheet will be dated and each person (student, trainee, etc.) operating the reactor will place their signature in appropriate spaces provided at the top of the form.

Reviewed By: Dan Este! Approved By: William Bonzer

. 7 Vi

I

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

SOP: 107 TITLE: PERMANENT LOG, HOURLY LOG AND OPERATIONAL DATA Revised: January 3, 2008 Page 2 of 6 I b. A new hourly log sheet will be started at the beginning of each operational day, or when all available columns have been filled during the current day of operation, (i.e. a I c.

new hourly log sheet is not required for each startup checklist SOP 102).

The following procedure steps correspond to the numbered steps on the MSTR Hourly Rev I Operating Log form.

1. Time from the console clock.

I 2. Person at the console, initials (student, trainee, or licensed operator).

I 3. Nominal reactor power level (in watts or kilowatts).

4. Linear recorder reading in percent.

U 5. Linear Meter Scale.

6. Reg rod in "Auto" and annunciator board reset? Yes or No.

I 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 I (approximately) of operation.
9. Log and Linear drawer Power Range reading on digital meter (%).

I 10. Record the Log Count Rate Recorder reading.

I 11. Source removed? Yes or No.

12. Diffuser pumps on? Yes or No.

I 13. Exhaust fans on? Yes or No.

I 14. Record the position of Shim Rod #1 to the nearest tenth of an inch.

I 15. Record the position of Shim Rod #2 to the nearest tenth of an inch.

Reviewed By: Dan Estel :Approved By: William Bonzer

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 107 TITLE: PERMANENT LOG, HOURLY LOG AND OPERATIONAL DATA Revised: January 3, 2008 Page 3 of 6
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) for approximately the same values observed during completion of startup checklist (SOP 102).
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. Other entries to the Permanent Log such as samples being irradiated, etc. should also be made at this time. (See section B of SOP 107).

Rev

23. Record the reactor Inlet Temperature (thermocouple 1 or 3) as displayed on the Pool Water Temperature Recorder.
24. Verification 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.
2. Permanent Log Entries
a. All entries in the Permanent. Log shall be preceded by the date (Use the date stamp)

Reviewed By: Dan Estel Approved By: William Bonzer

/- *7'12

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 107 TITLE: PERMANENT LOG, HOURLY LOG AND OPERATIONAL DATA Revised: January 3, 2008 Page 4 of 6
b. During completion of the Startup Checklist (SOP 102) use the Check Out stamp and complete values as they become available. To the right of the purpose the nature of the experiment should also be shown. See the example below.

0953 Time Check Out Started NE 306 Purpose 1027 Time Rods at 6 inches 1046 Time Reactor at 0.0 1 kw

c. Reactor power changes are made in accordance with SOP 103 and entries are made prior to the start of a power change and at the new stable power level. The example below indicates Permanent Log entries for a power change including shutdown of the reactor:

1028 Reactor started to 600W.

1030 Reactor at 600W.

1035 Reactor 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 Rev POSITION SAMPLE TIME TIME TIME BRT Khouaja 1538 1539 1 min (Foil 1)

Note: The number in parentheses ( ) indicates the number of samples.

Reviewed By: Dan Estel Approved By: William Bonzer

..)&~

      • MISSOURI S&T REACTOR S'1'AN=J OFETA-IITN=*-rKEIRUES *** Rev SOP: 107 TITLE: PERMANENT LOG, HOURLY LOG AND OPERATIONAL DATA Revised: January 3, 2008 Page 5 of 6
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 Rev 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.

Exam)le of Fan Operation Log DATE FAN # TIME TIME PEAK POWER/

ON OFF REMARKS Feb 10, 1996 2 1450 1500 200 KW Rev Reviewed By: Dan Estel Approved By: William Bonzer

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ** I Rev SOP: 107 TITLE: PERMANENT LOG, HOURLY LOG AND OPERATIONAL DATA Revised: January 3, 2008 Page 6 of 6
  • Date (Start a new form each day) HOURLY OPERATING LOG Signatures: (1) (5) (9)

(Including Licensed (2) (6) (10) Rev Operator on Duty) (3) (7) (11)

(4) (8) (12)

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 (I)
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. I (%)
21. Power Chamber No. 2 (%)
22. Permanent Log Entries (/)
23. Core Inlet Water Temp. ('F) Rev
24. SRO on Duty Verification (/)
25. SRO on Duty Initials
26. Licensed Operator Initials Reviewed By: Dan Estel Approved By: William

-. 1',;

Bonzer C-* .**',*'**'A_4-**"*.

-YV Ctý

      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 303

Title:

Auxiliary Pool Water Cooler System Operations Issued: May 8, 2007 Page 1 of 2 A. Purpose To provide for a safe and consistent method to 1) turn on the cooling system, 2) turn off the cooling system, and 3) restart the cooling system after a power failure.

B. Precautions, Prerequisites, or Limitations

1. Personnel involved with the cooling system should be familiar with the operation of the equipment involved.
2. The Reactor Manager will give permission to operate the cooling system.
3. Authorization to operate the cooling system following a power outage should only
  • bemade by the Reactor Manager.

C. Procedure to start chiller

1. Open valves #58 (water in) and #59 (water out).
2. Close valve #60 (heat exchanger bypass). Coolant flow is now through the cooling system.
3. Verify that the cooling system's control box has power. A red light will be illuminated on the front of the temperature control module. Power comes from sub panel C (next to left side of the yellow flammable storage locker), circuit breaker # 2.
4. The low-pressure-freeze stat, located on the left side of the cooling system's control box, should have the cut in set at approximately 50 psig and the differential set at approximately 10 psig. If setting is not correct, contact the Reactor Manager for further instruction, and do not continue the start procedure.
5. Adjust set point on the Temperature control (TC), located on top of cooling system's control box, to 657F.
6. Adjust set point on the freeze stat (FZ), located on top of the cooling system's control box, to 407F.

Written by: Daniel N. Estel Approved by: William Bonzer q

  • --*.,,,.. , )(,.-,

IQ-'- [*,

      • UMIR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 303

Title:

Auxiliary Pool Water Cooler System Operations Issued: May 8, 2007 Page 2 of 2

7. Pull and hold the momentary-on toggle switch located on the bottom of the cooling system's control box, then cycle the OFF-ON switch, located on the right side of the cooling system's control box, to ON. Continue to hold the toggle switch until the pressure gauge located on the chiller assembly reads at least 50 psig.
8. Release the toggle switch.
9. The chiller is now on.

D. Procedure to turn the chiller OFF.

1. Switch the OFF-ON switch to OFF.
2. Within approximately one minute, the pressure gauge will reduce to approximately 5 psig and stabilized. Open valve labeled #60 (heat exchanger bypass).
3. Close valves labeled #58 (water in) and #59 (water out).
4. The cooling system is now off and isolated from the normal flow of the pool water.

E. Procedure to restart the chiller after a power outage.

1. After restarting the pool water pump, verify that the cooling system's control box has power. Power is located in sub panel C, circuit breaker # 2.
2. Pull and hold the momentary-on toggle switch located on the bottom of the cooling system's control box, then cycle the OFF-ON switch, located on the right side of the cooling system's control box, from ON to OFF and then back ON.

Continue holding the toggle switch until the pressure gauge located on the cooling system assembly reads at least 50 psig. Release the toggle switch.

3. The cooling system is now on.

Written by: Daniel N. Estel Approved by: William Bornzer

_~~2J Y_ . ,-.. / i*,

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Revised: December 19, 2007 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, Reactor Director, or a Licensed Operator, may silence the evacuation alarm 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 Reactor Operator and the Senior Operator 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.

C. EVACUATION PROCEDURE Upon sounding of the Evacuation Alarm:

Revised By: Maureen Henry Approved By: William Bonzer

,/VVuk.

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Revised: December 19, 2007 Page 2 of 7
1. REACTOR OPERATOR 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 (audibly, visually, or by observing the magnet contact lights 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 Rit.

Revised By: Maureen Henry Approved By: William Bonzer

,/,I) - , ' Y"-'

MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Revised: December 19, 2007 Page 3 of 7

10. PROCEED TO PHYSICS BUILDING BASEMENT AREA: Leave the facility and proceed directly to the designated Physics Building basement area.

II. SENIOR OPERATOR ON DUTY The Senior Operator 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.

III. 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.

Revised By: Maureen Henry Approved By: William Bonzer

    • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES **Rev SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDIN4G EVACUATION Revised: December 19, 2007 Page 4of 7
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) 'inthe emergency shower area.
5. Evaluate the situation to determine if the potential for an emergency condition exists. Implement the following 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 "Adminlistrative Responsibilities"
  • SOP 620 "Decontamination Procedure"
  • SOP 622 "Handling Injured In Radiation Accidents"
6. Take other actions as deemed appropriate.

D. 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 Reactor Director or the Reactor Manager and the Radiation 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 mren/liir are encountered.

Revised By: Maureen Henry Approved By: William Bonzer ILI

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** I Rev SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Revised: December 19, 2007 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 LOGBOOKIMETERS
8. TURN VENT FANS OFF
9. OBTAIN EMERGENCY KEYS
10. PROCEED TO PHYSICS BUILDING BASEMENT AREA Revised By: Maureen Henry Approved By: William Bonzer 7/

/ .1

'~~MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES **Rev SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDIN~G EVACUATION Revised: December 19, 2007 Page 6 of 7

-SRO -

EVACUATION CHECKLIST

1. 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 ___
1. 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 C.111 FOR FURTHER INSTRUCTION.

Revised By: Maureen Henry Approved By: William Bonzer

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES
  • Rev SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Revised: December 19, 2007 Page 7 of 7 MISSOURI S&T EMERGENCY PHONE LIST Reactor Staff CELL HOMEE WORK Brian Porter, Sr. Electronics Tech., RO 341-6617 William Bonzer, Manager, SRO 341-4384 Daniel Estel, Sr.-Lab Mechanic, SRO 341-4291 Ray Bono, EHS Director, Radiation Safety Officer ~~ - 341-4240, 4305 Maureen Henrv, Sr. Secretarv xný 341-4236 University Administrative Staff William Bleckman, Director Missouri S&T Police 341-4345 John F. Carney H1I, Chancellor aw 341-4116 Steve Malott, Vice Chancellor Admin. Services 341-4122 Marvin Patton, Director Physical Facilities 341-4252 Rev Jerry Thomas DO, Director Health Services - Infirmary 341-4284 Arvind Kumar, Chair of Nuclear Engineering, Reactor Director 341-4747 Samuel Frimpong, Chair of Mining and Nuclear ' 341-7617 Michelle Bresnahan_ Health Phvsicist FH-S-Missouri S&T 341-7014 Michelle Bresnahan Health Phv.-icist EHS-Missouri S&T Local Missouri S&T Police 341-4300 Rev Rolla City Police 3-911 Rolla Fire Department 3-911 Phelps County Hospital 3-911 Rcnln lier~eiicv Manaementr A rencv 3-911 Rnll:i'PTni-raf-.ilr.viVn-n.qcrpme Agency 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 Eoidemiology (573) 751-6160 (573) 751-4674 (24hrs)

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

Revised By: Maureen Henry Approved: William Bonzer

. /' -

.1

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 507 TITLE: EMERGENCY PROCEDURES-ADMINISTRATIVE RESPONSIBILITIES Revised: January 3, 2008 Page 1 of 4 Rev A. PURPOSE To establish responsibilities for administrative members responsible for coping with a reactor related emergency as set forth in the MSTR Emergency Plan. Rev B. PRECAUTIONS, PREREQUISITES. LIMITATIONS
1. The duties listed under each official are general in description and areconsidered fundamental to the protective action to be taken in the event of a reactor-related Alert (see Missouri S&T Reactor SOP 503) or Site Area Emergency (see Missouri S&T Rev Reactor 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 of Administrative Services.
4. The title "Chair" used throughout refers to the Chair of Nuclear and Mining. Rev C. PROCEDURE
1. Chancellor - If offsite consequences are expected the Chancellor will be responsible Rev for:
a. providing direction and coordination for the Control Group.

Reviewed By: Daniel Estel Approved By: William Bonzer

/ 1-) C*

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** f Rev SOP: 507 TITLE: EMERGENCY PROCEDURES-ADMINISTRATIVE RESPONSIBILITIES Revised: January 3, 2008 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, Region III:

1-800-522-3025

  • NRC Duty Officer (24 hr.): (301) 816-5100, (301) 951-0550, or (301) 415-0550
  • Missouri State Emergency Management Agency:

(573) 751-2748

  • Missouri Bureau of Environmental Health:

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

  • 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
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 Rev 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 absence.
b. functioning as administrative spokesman responsible for communication with the news media and 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.

Reviewed By: Daniel Estel Approved By: William Bonzer

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 507 TITLE: EMERGENCY PROCEDURES-ADMINISTRATIVE RESPONSIBILITIES Revised: January 3, 2008 Page'3of4 Rev
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 Vice Chancellor if an off-campus evacuation is determined to 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 deconta-mination and monitoring equipment, their advisability and use.
5. Emergency Support Center Director (i.e. Reactor Director)
a. Initiates immediate action to isolate the affected area of campus.
b. Requests assistance from the following local emergency support organizations as necessary:
  • Rolla City Police, 3-911
  • Rolla Fire Department, 3-911
  • Phelps County Hospital, 3-911 Rev
c. Directs all assessment activities.
d. Authorizes voluntary radiation exposures up to 25 rem when immediate actioin is essential.

Reviewed By: Daniel Estel Approved By: William Bonzer 1y ~ L,

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 507 TITLE: EMERGENCY PROCEDURES-ADMINISTRATIVE RESPONSIBILITIES Revised: January 3, 2008 Page 4 of 4 Rev
e. 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.
f. Evaluates foreseeable hazards and determines corrective actions.
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)
a. Assumes the duties of the ESC Director in his absence.
b. Evaluates the need for activating the ESC following any radiation emergency.
c. Informs (or delegates to inform) necessary personnel that an emergency exists.
d. Coordinates and supervises the activities of the Emergency Squad in concurrence with ESC director.
e. Supervises efforts to terminate a radiation release.
f. Promptly informs the Missouri S&T Campus Police to "rope off' or physically control a 100 m circle and post with radiation signs as necessary.

g Maintains a log of significant events. Rev

h. Evaluates campus and facility surveys for protection of personnel.
i. Ensures organization and training of reactor staff for emergency conditions.
j. Reviews the Emergency Plan on an annual basis and makes needed changes.
k. Ensures adequate procedures exist and are reviewed at periodic intervals to cope with emergency conditions.
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.
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.

Reviewed By: Daniel Estel Approved By: William Bonzer

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