ML071270159

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Annual Progress Report 2006-2007 for the University of Missouri-Rolla Reactor Facility
ML071270159
Person / Time
Site: University of Missouri-Rolla
Issue date: 04/27/2007
From: Bonzer W
Univ of Missouri - Rolla
To:
Document Control Desk, Office of Nuclear Reactor Regulation
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Nuclear Reactor Facility 1870 Miner Circle LE Y Rolla, MO 65409-0630 I aj UNIVERSITY OF MISSOURI-ROLLA Phone: 573.341.4236 Fax: 573.341.4237 reactor@umr.edu U. S. Nuclear Regulatory Commission Document Control Desk Mail Stop 0-3 H8 11555 Rockville Pike Rockville, MD 20852-2738 April 27, 2007

Dear Sir:

Please find enclosed the Annual Progress Report 2006-2007 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, 62_6ý William Bonzer Interim Reactor Director mh Enclosure xc: Marvin Mendonca, Project Manager RC)

Document Control Desk (NRC)

U.S. NRC Region III American Nuclear Insurers, c/o Librarian 4&2o

PROGRESS REPORT 2006-2007 UNIVERSITY OF MISSOURI - ROLLA NUCLEAR REACTOR FACILITY

PROGRESS REPORT FOR THE UNIVERSITY OF MISSOURI-ROLLA NUCLEAR REACTOR FACILITY April 1, 2006 to March 31, 2007 Submitted to The U.S. Nuclear Regulatory Commission And The University of Missouri-Rolla

ii Table of Contents

SUMMARY

1.0 INTRODUCTION

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

1.1 BACKGROUND

INFORMATION .................................................................................................... 1 1.2 G ENERAL FACILITY STATUS .............................................................................................. 1 2.0 REACTOR STAFF AND PERSONNEL ...................................................................................................... 4 2.1 REACTOR STAFF ......................................................................................................................... 4 2.2 LICENSED OPERATORS ............................................................................................................... 4 2.3 RADIATION SAFETY COM M ITTEE ........................................................................................ 5 2.4 H EALTH PHYSICS ....................................................................................................................... 5 3.0 REACTOR OPERATIONS ................................................................................................................................. 7 4.0 EDUCATIONAL UTILIZATION .................................................................................................................... 14 5.0 REACTOR HEALTH PHYSICS ACTIVITIES .......................................... 19 5.1 ROUTINE SURVEYS ................................................................................................................... 19 5.2 BY-PRODUCT M ATERIAL RELEASE SURVEYS ................................................................... 19 5.3 ROUTINE M ONITORING ............................................................................................................ 19 5.44 W ASTE D ISPOSAL ..................................................................................................................... 20 5.5 INSTRUM ENT CALIBRATIONS .............................................................................................. 20 6.0 PLANS ................................................................................................................................................................. 21 6.1 ADM INISTRATIVE CHANGES ................................................................................................ 21 6.2 RELICENSING ............................................................................................................................ 21 6.3 STRATEGIC PLAN ................................................................................................ .......... 21 6.4 INSTRUM ENTATION UPGRADE ............................................................................................ 21 6.5 REACTOR OPERATOR TRAINING ....................................................................................... 22 APPENDIX A: SOPS CHANGED DURING THE 2005-2006 REPORTING YEAR ................................. 23 LIST OF TABLES TABLE 3-1. CORE 101W TECHNICAL DATA ......... o..................................... 7 TABLE 3-2. UNSCHEDULED SHUTDOW NS FOR 2005-2006 .................................................................... 8 TABLE 3-3. M AINTENANCE FO R 2005-2006 .................................................................................. 11 TABLE 3-4. REA CTO R UTILIZATIO N ............................................................................................ 13 TABLE 3-5. EXPERIM ENTAL FACILITY USAGE .................................................................................... 13 TABLE 4.1. UM R CLASSES AT REACTOR FACILITY ........................................................................... 15 TABLE 4.2. REACTOR SHARING PROGRAM .......................................................................................... 16 LIST OF FIGURES FIGURE 3-1. UM RR CORE 101W CONFIGURATION ............................................................................. 7

111

SUMMARY

During the 2006-2007, reporting period the University of Missouri-Rolla Reactor (UMRR) was in use for 3947.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The major part of this time, about 95%, was used for class instruction, research, and training purposes.

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

The reactor facility supported several UMR courses over the year for 3,694.5 Student-hours. About 5,301 visitors visited the reactor during the past year. There were 1,843 partic-ipants, mostly high school students, in the U.S. Department of Energy Reactor Sharing Program.

The reactor produced 18,649.53 kilowatt-hours of thermal energy using approximately 0.8159 grams of uranium. A total of 431 samples were neutron irradiated in the reactor with the majority being analyzed in the Reactor Counting Laboratory. An additional 175 samples received exposure to gamma radiation in the reactor.

I

1.0 INTRODUCTION

This progress report covers activities at the University of Missouri-Rolla Reactor (UMRR)

Facility for the period April 1, 2006 to March 31, 2007 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 UMRR is also available for the training of personnel from commercial concerns with legitimate interest in our facility use.

1.1 Background Information The University of Missouri-Rolla Reactor Facility attained initial criticality on December 9, 1961. The UMRR 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 upgraded 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.

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

1.2 General Facility Status The UMRR 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 UMRR license was submitted, to NRC August 30, 2004 and announced in the Federal Register on November 29, 2004 under

2 title, Notice of License Renewal Application for Facility Operating License, University of Missouri--Rolla (Volume 69, Number 228; Page: 69418-69419). UMRR 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 November 15, 2006. There were no significant areas of concern. There is an agreement between the UMRR 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, 'Modem Physics' II
13. Physics 322, ' Advanced Physics'

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

1. INDEX INDEX (Pages 1, 2, and 3)
2. SOP 101 General Operational Procedures (Pages 1, 2, 3 of 3)
3. SOP 501 Emergency Procedures for Reactor Building Evacuation (Page 7 of 7)

Note: The above listed SOP revisions are provided in Appendix A.

4 2.0 REACTOR STAFF AND PERSONNEL 2.1 Reactor Staff Name Title Mr. William Bonzer Interim Director, 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 2.2 Licensed Operators Name License

1. William Bonzer Senior Operator
2. Daniel Estel Senior Operator
3. Craig Heimericks 3 Senior Operator
4. Mathew Dennis Senior Operator
5. Alfred Schovanez Senior Operator
6. Michelle Minard Senior Operator
7. Ben Swoboda 3 Senior Operator
8. Zak Kulage 1 Senior Operator
9. Victor Smith' Senior Operator
10. Chad Lisle 4 Senior Operator
11. Brian Porter Reactor Operator
12. Seth Bradley Reactor Operator
13. Jason Hall Reactor Operator
14. Justin Munson 3 Reactor Operator
15. Michael Lacey Reactor Operator
16. Nathan Ayres Reactor Operator
17. Chris Speer Reactor Operator
18. Zach Miller Reactor Operator
19. Beth Faughn 2 Reactor Operator
20. Krista Kaiser 2 Reactor Operator

5

21. Andrea Mayor 2 Reactor Operator
1. Upgrade date 01/26/07
2. Effective date 0 1/26/07
3. Termination date 05/15/06
4. Upgrade date 6/27/2006 2.3 Radiation Safety Committee The Radiation Safety Committee meets quarterly. The committee met on 5/11/06, 9/5/06, 11/17/06 and 3/15/07 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 Brown Biological Services
6. Dr. Robert Dubois Physics
7. Dr. Seungjin Kim 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 Minard Environmental Health and Safety Services 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 Minard Health Physicist
4. Mr. Trevor Knudson Health Physics Technician (part time)

6

5. Ms. Krista Kaiser 2 Health Physics Technician (part time) 1.Until 12/31/06
2. Effective on 1/112007

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 F-5 CR - Cadmium Rabbit F F-6 F-7 BR S - Source Holder 1 3 4 5 6 7 8 9 Figure 3-1. UMRR Core 101W Configuration Table 3-2 lists unscheduled shutdowns during the reporting period. This consisted of eighteen rundowns and seven unplanned shutdowns. The majority of rundowns 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, but reactor power

8 never increased above 100% when these trips occurred. Students learning to operate the reactor at times improperly changed scales on the Linear meter, which activated the 120% Demand Rundown. The majority of unplanned shutdowns occurred to repeated failures of the #1 rod drive brake band failing. Failure of the brake band caused the control rod to insert into the core and shutdown the reactor.

Table 3-2: Unscheduled Shutdowns for 2006-2007 Date Type of Shutdown/Cause and Corrective Action Taken SCRAMS No scrams for this reporting period Rundowns 4/04/06 120% Demand Rundown.

Cause: Operator inattention to Liner Channel Corrective Action: Operator instructed to pay closer attention to Liner Channel.

SRO on Duty grants permission to restart reactor.

4/06/06 120% Full Power Rundown.

Cause: Electronic noise spike created when switching auto-controller from auto to manual mode. No power increase occurred during this trip.

Corrective Action: None taken. SRO on Duty grants permission to restart reactor.

8/11/06 120% Full Power Rundown.

Cause: Electronic noise spike created when switching auto-controller from auto to manual mode. No power increase occurred during this trip.

Corrective Action: None taken. SRO on Duty grants permission to restart reactor.

10/04/06 120% Demand Rundown.

Cause: Operator inattention to Liner Channel Corrective Action: Operator instructed to pay closer attention to Liner Channel SRO on Duty grants permission to restart reactor.

10/13/06 120% Full Power Rundown.

Cause: Electronic noise spike created when switching auto-controller from auto to manual mode. No power increase occurred during this trip.

Corrective Action: None taken. SRO on Duty grants permission to restart reactor

9 11/06/06 120% Demand Rundown.

Cause: Operator inattention to Liner Channel Corrective Action: Operator instructed to pay closer attention to Liner Channel.

SRO on Duty grants permission to restart reactor.

11/14/06 120% Demand Rundown.

Cause: Operator did not completely depress the Liner scale button switch on the picoammeter.

Corrective Action: Student was instructed to firmly press Linear scale button switch when up-scaling or down-scaling the picoammeter. SRO on Duty grants permission to restart reactor.

12/14/06 120% Demand Rundown.

Cause: Operator failed to put reactor into auto-control and watch instrumentation.

Corrective Action: Operator instructed to place reactor in auto-control before proceeding with paperwork. SRO on Duty grants permission to restart reactor.

1/05/07 120% Full Power Rundown.

Cause: Electronic noise spike created when opening beam port. No power increase occurred during this trip.

Corrective Action: None taken. SRO on Duty grants permission to restart reactor.

1/05/07 120% Full Power Rundown.

Cause: Electronic noise spike created when opening beam port.

Corrective Action: None taken. SRO on Duty grants permission to restart reactor.

2/09/07 120% Full Power Rundown.

Cause: Electronic noise spike created when switching auto-controller from auto to manual mode. No power increase occurred during this trip.

Corrective Action: None taken. SRO on Duty grants permission to restart reactor.

2/09/07 120% Full Power Rundown.

Cause: Electronic noise spike created when switching auto-controller from auto to manual mode. No power increase occurred during this trip.

Corrective Action: None taken. SRO on Duty grants permission to restart reactor.

2/12/07 120% Demand Rundown.

Cause: Operator did not completely depress the Liner scale button switch on the picoammeter.

Corrective Action: Student was instructed to firmly press Linear scale button switch when up-scaling or down-scaling the picoammeter. SRO on Duty grants permission to restart reactor.

2/23/07 120% Full Power Rundown.

Cause: Electronic noise spike created when switching auto-controller from auto to manual mode. No power increase occurred during this trip.

Corrective Action: None taken. SRO on Duty grants permission to restart reactor.

10 2/26/07 Regulating Rod on Insert Limit Rundown.

Cause: Operator inattention to reg. rod height.

Corrective Action: Operator instructed to pay attention to rod height. SRO on Duty grants permission to restart reactor.

3/02/07 120% Full Power Rundown.

Cause: Electronic noise spike created by auto-controller. No power increase occurred during this trip.

Corrective Action: None taken. SRO on Duty grants permission to restart reactor.

2/26/07 Regulating Rod on Insert Limit Rundown.

Cause: Operator inattention to reg. rod height.

Corrective Action: Operator instructed to pay attention to rod height. SRO on Duty grants permission to restart reactor.

3/14/07 120% Demand Rundown.

Cause: Operator did not completely depress the Liner scale button switch on the picoammeter.

Corrective Action: Student was instructed to firmly press Linear scale button switch when up-scaling or down-scaling the picoammeter. SRO on Duty grants permission to restart reactor.

Unplanned Shutdowns 4/25/06 Unplanned Shutdown.

Cause: Brake band for control rod drive #3 broke.

Corrective Action: Reactor shutdown for brake band repair. SRO on Duty grants permission to restart reactor.

6/22/06 Unplanned Shutdown.

Cause: Power Outage.

Corrective Action: Power restored to reactor building and nuclear instrumentation.

SRO on Duty grants permission to restart reactor.

9/12/06 Unplanned Shutdown.

Cause: Brief electrical brownout situation noticed by fading of overhead lights.

Corrective Action: Pre-startup checklist performed to verify equipment is operational. SRO on Duty grants permission to restart reactor.

9/13/06 Unplanned Shutdown.

Cause: Failure of control rod drive #1 brake solenoid.

Corrective Action: Reactor shutdown for solenoid repair. SRO on Duty grants permission to restart reactor after repair of brake.

11 12/04/06 Unplanned Shutdown.

Cause: Brake band for control rod drive #1 broke.

Corrective Action: brake band replaced. SRO on Duty grants permission to restart reactor after repair of brake.

2/16/07 Unplanned Shutdown.

Cause: Drive cord for period pen on the Log & Liner recorder broke.

Corrective Action: Replaced period pen drive cord. SRO on Duty grants permission to restart reactor.

3/19/07 Unplanned Shutdown.

Cause: Brake band for control rod drive #1 broke.

Corrective Action: Reactor shutdown for brake band repair. SRO on Duty grants permission to restart reactor.

Table 3-3: Maintenance for 2006-2007 Date Problem/Event and Action Taken 04/11/06 Issue: Low voltage trip light activated on Liner Power Supply.

Action taken: Low voltage trip test performed. No corrective action required.

04/14/06 Issue: Shim range switch non-operational on rod drive #2.

Action taken: Replaced shim range switch.

04/21/06 Issue: Incorrect Liner Power Supply low voltage trip.

Action taken: Removed from power supply from console for inspection.

Reinstalled Linear Power Supply and checked voltages and trips.

04/25/06 Issue: Brake band for rod drive #3 failed.

Action taken: Replaced rod drive #3 brake band.

05/08/06 Issue: Unable to reset Liner Power Supply low voltage trip.

Action taken: Cleaned contacts and replaced vacuum tube V9.

07/24/06 Issue: Startup Channel's high voltage power supply replaced.

Action taken: Replaced the fission chamber high voltage power supply Canberra model #3105 with Canberra model #3102.

09/13/06 Issue: Brake band for control rod drive #1 failed.

Action taken: Removed, repaired, and reinstalled brake band spring arm.

10/03/06 Issue: Core light failed to illuminate.

Action taken: Removed core light fixture, cleaned contacts, and replaced bulb.

12 11/24/06 Issue: Lower level basement Radiation Area Monitor (RAM) failure.

Action taken: Removed and replaced lower level RAM ECI module with spare module. Adjusted set trip set points. Calibrated RAM.

12/04/06 Issue: Brake band for control rod drive #1 failed.

Action taken: Replaced brake band.

12/26/06 Issue: Lower level basement Radiation Area Monitor (RAM) failure.

Action taken: Replace EC I module, tested, calibrated, and set trip points.

01/31/07 Issue: Thermocouple #2 readings erratic.

Action taken: Disconnected and reconnected thermocouple #2, which created a stable reading.

02/08/07 Issue: Thermocouple #2 readings erratic.

Action taken: Disconnected and reconnected thermocouple #2, which created a stable reading.

03/15/07 Issue: Log & Liner recorder's period pen not recording on paper.

Action taken: Replaced period pen's drive cable.

03/13/07 Issue: Log & Liner Channel power level reading is lower than other channels.

Action taken: Performed calibration check and repositioned CIC detector.

03/14/07 Issue: Log & Liner Channel power level reading is different than other channels.

Action taken: While reactor was at 100 kW and repositioned Log & Liner CIC to read 50% full power from 58% full power.

03/16/07 Issue: Brake band for control rod drive #1 failure.

Action taken: Replaced brake band.

13 Table 3-4. Reactor Utilization

1. Reactor use 784.78 hrs.
2. Time at power 425.45 hrs.
3. Energy generated 18,649.53 kW/hrs
4. Total number of samples Neutron irradiated 431 Gamma Exposure 175
5. U-235 Burned 0.8159 g
6. U-235 Burned and Converted 0.9636 g Table 3-5. Experimental Facility Usage Facility Hours Bare Rabbit Tube 12.90 hr Cadmium Rabbit Tube 0.00 hr Beam Port 48.75 hr Other Core Positions 3.70 hr Gamma Exposures 540 hr Total 605.35 hr

14 4.0 EDUCATIONAL UTILIZATION The reactor facility supported several UMR courses in the past year for a total of 3694.5 student hours. The number of UMR students utilizing the facility was 1143. 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 sev-eral universities, colleges and high schools have used the facility.

Table 4-1 lists UMR 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, 2006 and spring of 2007) 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 UMR reactor staff and student-licensed operators conducted the laboratory.

The Reactor Sharing Program, which is 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, 1843 students and instructors from 94 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. UMRR coordinates with the UMR Admissions Office to schedule high school students to see other items of interest at UMR after they have visited the reactor facility. The students visited the UMR-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 5,301 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. UMR Classes at Reactor Facility 2006-2007 Reporting Period WS- Winter CLASS NUMBER/TITLE # OF TIME AT STUDENT FS- Fall STUDENTS REACTOR HOURS WS 06 NE 25 21 10 210 WS 06 NE 206 Reactor Operations I 26 10 260 WS 06 NE 308 Reactor Laboratory 14 18 336 WS 06 NE 490 Graduate Research 1 10 10 WS 06 NE 204 Radiation Laboratory 16 1 16 FS 06 NE 206 11 28 308 FS 06 OURE (Opportunity for Undergraduate Research Expdrience) 1 12 12 FS 06 NE 304 Reactor Laboratory I 29 36 1044 FS 06 Chemistry Labs (Half Life) 675 0.5 337.5 FS 06 NE 25 10 4 40 WS 07 Chemistry Labs (Half Life) 214 .5 107 WS 07 NE 308 24 10 240 WS 07 Dr. Thompson UMC 404 54 6.0 324 WS 07 NE 206 18 20 360 WS 07 NE 25 29 6 174 Totals 1143 172 3778.5

16 Table 4-2. Reactor Sharing Program (2006-2007 Reporting Period)

DATE PARTICIPANTS Number Hours 4/3/06 NE 404 Class Columbia 10 6 4/6/06 St. Elizabeth R- IV High School 14 1.5 4/12/06 Ray Bono with Group from Jefferson City 5 1 4/12/06 Individual tour Alumni's and family 6 1 4/20/06 Parkway West High School 19 1.5 4/22/06 Order of the Golden Shillelagh Tour 16 2 5/2/06 Material Science Class 14 1 5/2006 Individual Tours May 2006 11 4 5/5/06 IT Department Tour 2 1 5/22/06 Admission Department Tour 3 1 6/5/06 Andrea Mayor Training Session 1 4 6/8/06 Minority Introduction to Technical Engineering Program 30 2 6/2006 Individual Tours June 10 5 6/13/06 Jackling Tour 8 1.5 6/14/06 Jackling Tour 12 2 6/14/06 Andrea Mayor 1 4 6/15/06 Andrea Mayor 1 4 6/15/06 Michelle Mayor 1 1.5 6/16/06 University of Arkansas Nuclear Medicine 13 2 6/16/06 REU School of Engineering Tour 14 1 6/22/06 Minority Introduction to Technical Engineering Programs 27 1.5 6/23/06 Andrea Mayor 1 4 6/27/06 Jackling Tour 8 1.5 6/28/06 Missouri Academy Student Research 6 1 6/28/06 Jackling Tour 17 1.5 6/2006 Individual Tours July 5 1 7/11/06 Jackling Tour 16 1.5 7/12/06 Jackling Tour 27 2 7/17/06 Nuclear Engineering Focus Group 6 1 7/18/06 Nuclear Engineering Focus Group 6 4 7/19/06 Nuclear Engineering Focus Group 6 1.5 7/19/06 Nuclear Engineering Camp Focus Group 6 1.5 7/20/06 Nuclear Engineering Camp Focus Group 6 4

17 7/24/06 Nuclear Engineering Focus Group II 7 1.5 7/25/06 Nuclear Engineering Focus Group II 7 4 7/26/06 Nuclear Engineering Camp Focus Group II 7 1.5 7/26/06 Nuclear Engineering Camp Tour Half Life 29 3 7/26/06 Nuclear Engineering Camp Focus Group II 7 1 7/27/06 Nuclear Engineering Camp Focus Group II 7 4 7/31/06 Andrea Mayor Training 1 4 8/3/06 Fort Leonard Wood School 18 2 8/2006 Individual Tours August 2006 4 1 8/7/06 Andrea Mayor Training 1 5 8/11/06 Andrea Mayor Training 1 4 8/21/06 Andrea Mayor Training 1 4 9/1/06 Andrea Mayor Training 1 4 9/6/06 Computer IT Center 1 .5 9/26/06 Andrea Mayor Training 1 4 9/27/06 Fort Leonard Wood School 18 2 9/30/06 Open House 7 2 10/6/06 Engineering Management Tour 11 1.5 10/6/06 Memmorville College 11 0.8 10/2006 Individual Tours 10 2.5 10/9/06 Andrea Mayor Training 1 4 10/14/06 Girl Scout Groups Bridging the Gap 54 3 10/16/06 Chem. Labs FS 2006 80 2 10/17/06 Chem. Labs FS 2006 229 6 10/18/06 Chem. Labs FS 2006 130 4 10/19/06 Chem. Labs FS 2006 236 6 10/25/06 Andrea Mayor 1 4 10/27/06 NE Department 3 8 11/1/06 Liberty High School 19 .5 11/1/06 Andrea Mayor 1 4 11/2/06 Mansfield High School 26 2 11/3/06 Expanding Your Horizons Tour 54 5 11/8/06 Andrea Mayor Training 1 4 11/9/06 Thomas Jefferson High School 18 1.5 11/11/06 Open House 21 2

18 11/15/06 Andrea Mayor Training 1 4 11/16/16 East Central College 11 1.5 11/20/06 Andrea Mayor 1 4 12/4/06 Andrea Mayor 1 4 12/7/06 Offsite Safety Meeting 6 1 12/11/06 Andrea Mayor Training 1 4 12/14/06 St Louis Community College 30 1 1/26/07 Fort Leonard Wood School 32 3 2/5/07 NE 404 Bobby Thompson Group 11 6 2/9/07 NE 105 Student 1 1 2/12/07 NE 404 Bobby Thompson Group From Columbia 11 6 2/17/07 Boy Scouts 46 3 2/24/07 Atlantic Group 29 2 2/26/07 Professor Lou Dodds 1 .5 2/26/07 NE 404 Bobby Thompson 11 6 3/2/07 Tour from Columbia meeting with Bill Bonzer 11 .5 3/5/07 Hazelwood High School 22 1 3/5/07 Hazelwood High School 22 1 3/5/07 NE 404 Bobby Thompson 11 6 3/9/07 Professor Hagihat 1 .5 3/9/07 Prospective Student Tour 1 .5 3/12/07 St Charles College 15 1.3 3/14/07 Ash Grove High School 23 1 3/19/07 Chem Labs WS 2007 67 2 3/20/07 Chem Labs WS 2007 41 1 3/21/07 Chem Labs WS 2007 62 2 3/22/07 Chem Labs WS 2007 36 1 3/30/07 Fort Leonard Wood School 22 1.5 Total 1955 247.6

19 5.0 REACTOR HEALTH PHYSICS ACTIVITIES The health physics activities at the UMR Reactor facility consist primarily of radiation and contamination surveys, monitoring of personnel exposures, airborne activity, pool water activity, and waste disposal. Releases of all by-product material to authorized, licensed recipients are surveyed and recorded. In addition, health physics activities include calibrations of portable and stationary radiation detection instruments, personnel training, special surveys and monitoring of non-routine procedures.

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

5.2. By-Product Material Release Surveys There were no shipments of by-product material released off-campus. There were two by-product releases on campus. On 8/16/2006, there was a transfer of 70 pounds of cold waste (no activity) picked up from the nuclear reactor facility and taken to UMR's Dangerous Materials Storage Facility (DMSF). On 8/16/2006, there was a transfer of 80 pounds of waste water filters picked up from the nuclear reactor facility and taken to UMR's DMSF. The water filters contained 7.76x10.4 [Ci of Co-60.

5.3. Routine Monitoring Seventy eight 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 a month. There are four area beta, gamma, neutron dosimeters and one TLD ring dosimeter, which are also read bi-monthly. There are two other beta, gamma, neutron dosimeters used by the health physics personnel 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

20 beta and gamma monitoring and one for beta, gamma, and neutron monitoring. In addition, six digital, direct-reading dosimeters and four 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 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 2006 through March 2007 sample concentrations averaged 8.197x 106 PCi/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 113,980.34 pCi 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 two waste barrels transferred from the reactor facility to the DMSF on campus. One barrel consisted of 70 pounds of solid waste (i.e. gloves, paper towels, and plastic bags). This barrel was moved from the reactor to the DMSF on 8/16/2006, and had no detectable activity. The second barrel consisted of 80 pounds of waste water filters. This barrel was moved from the reactor to the DMSF on 8/16/2006, and had an activity of 7.76x10 4 [tCi of Co-60.

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

21 6.0 PLANS The reactor staff will be heavily involved in four major projects during the next reporting period; 1) administrative changes, 2) license renewal process 3) implementation and revision of the new activities plan, 4) installing new reactor nuclear instrumentation, and 5) continuation of the reactor operator training program.

6.1 Administrative Changes The Reactor Manager, Mr. William Bonzer, is also acting as Interim Reactor Director.

The Reactor Director position should be filled during the next reporting period.

6.2. Relicensing License renewal activities will continue during the upcoming reporting period. The present license is valid until NRC completes relicensing. NRC has started reviewing the required materials including SAR, technical specifications, emergency plan, operator requalification plan, and environmental reporting during this reporting period. The renewal process is expected to involve NRC approving or requiring additional information regarding the materials received from UMRR.

6.3. Strategic Plan A strategic plan has been developed to help the facility achieve its vision "to become nationally recognized as the leading educational and training university reactor in the country and to become recognized as an active 200 kW facility in terms of research". The strategic plan identifies strategic goals and action items to enhance research, educational outreach and teaching.

The action items will be initiated over the coming year and will guide the facility towards its vision.

6.4. Instrumentation Upgrade The reactor instrumentation upgrade is a continual process. A digital radiography imager has been purchased to use with the beam port. Under provisions of 10CFR50.59 the installation of a pool water cooling system has been completed during this reporting period. Laboratory equipment is being upgraded to enhance the neutron activation analysis labs and research. A high

22 purity germanium detector with greater efficiency, rabbit system and glove box are intended to be purchased within the next reporting period. This equipment will allow additional samples to be irradiated and processed through our gamma spectroscopy systems.

6.5 Reactor Operator Training The results of the fifth annual group of reactor operator trainees, which initially took the NRC examination during the week of January 8, 2007, were release to UMRR in February 2007.

Three trainees were licensed as reactor operators (ROs) with an additional two ROs being upgraded to senior reactor operators (SRO). One trainee did not pass the NRC operators examination and may retake the examination during the summer of 2007. 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.

23 APPENDIX A.

STANDARD OPERATING PROCEDURES CHANGED DURING THE 2006-2007 REPORTING YEAR

  • ** UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: INDEX

Title:

INDEX Revised: January 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 11.1 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 IRev.

SOP 305 Operation Without Magnet Contact Light Revised By: Maureen Henry Approved By: William Bonzer

  • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: INDEX

Title:

INDEX Revised: January 11, 2007 Page 2 of3 SOP 306 Estimation of Activity and Reactivity Worth of a Sample SOP 308 Restoration of Power Following a Power Outage IRev.

SOP 309 Response to a Coolant System Leak SOP 310 Facility Modifications Rev SOP 311 Receipt of Licensed Materials SOP 312 Critical Experiment Procedures SOP 401-499 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 Rev 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

      • UMR RE.ACTOR STANDARD OPERATING PROCEDURES ***

SOP: INDEX

Title:

INDEX Revised: January 11, 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 Ar 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 I Rev.

SOP 703 Reactor Use Form 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 Rev.

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 Rev.

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 UMRR Power Calibration SOP 818 Functional Test of Building Security System Revised By: Maureen Henry Approved By: William Bonzer

,- .. '. I 4m_ý_

UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 101 TITLE: GENERAL OPERATIONAL PROCEDURES Revised: January 23, 2007 Page I of 3 A. PURPOSE:

To provide written general operational procedures for routine operations.

B. PROCEDURE

1. Reactor operations must at all times meet the requirements of the Facility License R-79, Technical Specifications, and security in accordance with the provisions of Rev.

10 CFR 73.67(f).

2. At least two persons, one of whom is a Senior Operator, shall be present in the Reactor Building when the reactor is operating.
3. a) A licensed operator who is responsible for reactor operation shall be present in the control room at all times when the reactor is operating.

b) Students and trainees may operate the reactor controls subject to the following conditions. In such cases the licensed operator maintains complete and total responsibility for all aspects of reactor operations.

i) Students and trainees may operate the reactor controls under the direct supervision of a licensed-operator provided the excess reactivity is less than 0.7% delta k/k.

ii) Trainees may operate the reactor controls under the direct supervision of a Senior Reactor Operator when the excess reactivity is greater than 0.7% delta k/k and less than 1.5% delta k/k.

4. The reactor will be operated with the minimum amount of excess reactivity necessary to fulfill operational requirements as determined by the Reactor Director.
5. To reduce radiological activity within the demineralizer tank, turn off the reactor pool's water pump after a high power run is performed, which has continuously operated for a 50 kW-hour or more. The pump should be turned off within a few minutes after the reactor has shutdown and the magnet console key is turned off. Rev.

Activate and silence the Pool Demineralizer Effluent Conductivity High annunciator. Record in the permanent log book, "Water pump turned off after high power run". Turn on the water pump and reset the annunciator the next working day or if the reactor will be operated later in the day.

Revised By: William Bonzer Approved By: William Bonzer K?-/ , 2 -.

UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 101 TITLE: GENERAL OPERATIONAL PROCEDURES Revised: January 23, 2007 Page 2 of 3

6. All reactor operational personnel are responsible for entering in the appropriate log book any work on or around the reactor or reactor components important enough to justify a record for future reference.
7. All personnel are responsible for notifying the Senior Operator on Duty of any work being done that could either directly or indirectly affect reactor operations.
8. Log books will be kept in the permanent log book safe, except the one currently in use, which may be kept on the console. If the books are removed from the control room, permission must be granted by the Reactor Manager. Any books removed shall be returned as soon as possible.
9. Only the Senior Operator on Duty may key bypass control channel automatic functions. The use of any interlock bypass key requires a permanent log entry for Rev.

insertion and removal. This log entry shall include date and time. This requirement does not apply when the reactor is shut down (e.g. performance of the Weekly Checklist procedure).

0. Any abnormal behavior or abnormal change in core reactivity associated with reactor startup or operation should be reported to the Senior Operator on Duty immediately. If there is any doubt about reactor safety, the reactor shall be immediately shut down by the Operator-on-Duty. The cause should then be determined and corrective action taken.
11. The Standard Operating Procedure (SOPs) should be followed to the extent practicable, especially whenever the Pre-Startup Checklist is being completed, when the reactor is being started, or when the reactor power is being changed.
12. The Senior Operator on Duty has the authority to instruct the reactor operator to disregard certain SOPs provided that no safety requirements are violated. (For example, SOP 305 does not have to be performed every pre-startup checklist.)
13. All surveillance time intervals referred to in the SOPs are as defined in Section 1 of the Technical Specifications.

Revised By: William Bonzer -* Approved By: William Bonzer

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  • ** UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 101 TITLE: GENERAL OPERATIONAL PROCEDURES Revised: January 2 )3,2007 Page 3 of 3

14. The following procedures are to be performed by the Reactor Senior Electronics Technician or other qualified individual as determined by the Reactor Manager.

A licensed operator will participate when reactor operation is involved (e.g. Rod DropTime Measurements).

SOP 655, "Radiation Area Monitor (RAM) Calibrations" SOP 800, "Semi-Annual Checklist" SOP 801, "Log and Linear Drawer Calibration" SOP 802, "Linear Channel" SOP 803, "Log Count Rate (LCR) Channel" SOP 804, "Safety Amplifier System" SOP 805, "Auto Control System" Rev.

SOP 806, "Temperature Channel" SOP 807, "Neutron RAM System" SOP 809, "Relay Test" SOP 811, "Fire and Smoke Alarm System" SOP 813, "Rod Drop Time Measurement" SOP 818, "Functional Test of Building Security System"

15. Only person(s) specifically approved by the Reactor Manager shall perform the following procedure:

SOP 204, "Demineralizer Regeneration" Revised By: William Bonzer Approved By: William Bonzer

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