ML061240112

Annual Progress Report 2005-2006 for the University of Missouri-Rolla Reactor Facility

ML061240112
Person / Time
Site:	University of Missouri-Rolla
Issue date:	04/26/2006
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 Rolla, MC 65409-0630 Phone: 573.341.4236 Fax: 573.341.4237 reactor~umr.edu UNIVERSITY (IFMISSOURI-ROLLA April 26, 2006

Dear Sir:

Please find enclosed the Annual Progress Report 2005-2006 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, X,>-,,

William Bonzer Interim Reactor Director mh Enclosure xc: Patrick Isaac, Project Manager (NRC)

Document Control Desk (NRC) ,/

Chancellor John F. Camey 111 (UMR)

Dr. Mariesa L .Crow Dean, School of Mines & Metallurgy (UMR)

Mr. Ray Bono, Radiation Safety Officer(UMR)

American Nuclear Insurers, c/o Librarian ORC)

PROGRESSD REPORT 2005-2006 UNIVERSITY OF MISSOURI-ROLLA NUCLEAR REACTOR FACILITY

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L PROGRESS REPORT ii FOR TIHE UNIVERSITY OF MISSOURI-ROLLA NUCLEAR REACTOR FACILITY April 1, 2005 to March 31, 2006 Submitted to The U.S. Nuclear Regulatory Commission and The University of Missouri-Rolla L

TABLE OF CONTENTS

1.0 INTRODUCTION

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

1.1 BACKGROUND

INFORMATION ................................................................ 1 1.2 GENERAL FACILITY STATUS ................................................................ l 2.0 REACTOR STAFFANDPERSONNEL ................................................................ 3 2.1 REACTOR STAFF ................................................................ 3 2.2 LICENSED OPERATORS ................................................................ 4 2.3 RADIATION SAFETY COMMITTEE ................................................................ 5 2.4 HEALTH PHYSICS ................................................................ 5 3.0 REACTOR OPERATIONS ................................................................ 6 4.0 ED1JCATIONAL 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 .20 6.2 RELICENSING .20 6.3 STRATEGIC PLAN .20 6.4 INSTRUMENTATION UPGRADE .20 6.5 REACTOR OPERATOR TRAINING .21 APPENDIX A: SOPS CHANGED DURING THE 2005-2006 REPORTING YEAR ...................... 22 LISTOF TABLES .............................................................................................

TABLE 3-1. CORE 101W TECHNICAL DATA ................................................................ 6 TABLE 3-2. UNSCHEDULED SHUTDOWNS FOR 2005-2006 ................................................................ 7 TABLE 3-3. MAINTENANCE FOR2005-2006 ..................................... .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 ..................................... 6

iii

SUMMARY

During the 2005-2006 reporting period the University of Missouri-Rolla Reactor (UMRR) was in use for 1630.0 hours0 days <br />0 hours <br />0 weeks <br />0 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 a total of 7,182 student-hours. About 4,900 visitors visited the reactor during the past year. There were 1,106 participants, mostly high school students, in the U.S. Department of Energy Reactor Sharing Program.

The reactor produced 40,797.45 kilowatt-hours of thermal energy using approximately 1.7848 grams of uranium. A total of 302 samples were neutron irradiated in the reactor with most of them being analyzed in the Reactor Counting Laboratory. An additional 325 samples were exposed to gamma radiation in the reactor.

1

1.0 INTRODUCTION

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

Facility ror the period April 1, 2005 to March 31, 2006 The reactor is operated as a university facility, available to the faculty and students from various departments of the University for their educational and research programs. Several oth er college and pre-college institutions also made use of the facility during the reporting period. The facility i, also available for the training-of reactor personnel from commercial concerns with legitimate interest in our facility use.

1.1 1Backg~round Information The University of Missouri-Rolla Reactor Facility attained initial criticality on December 9th, 1961. The UMRR was the first operating nuclear reactor in the State of Missouri. The reactor design is based on the Bulk Shielding Reactor at Oak Ridge National Laboratory. 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.

Additiorally, the facility is equipped with a counting laboratory that has 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.

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.

2 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 title, Nol ice of License Renewal Application for Facility Operating License, University of Missouri--Rolla (Volume 69, Number 228; Page: 69418-69419). UMRR will operate under 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 30, 2005. There were no significant areas of concern. We have entered into an agreeme at with 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 years, has been continued in order to let both students and faculty in a number of departments across campus know how 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 251, 'Intermediate Quantitative Analysis'

5. Chemistry 355, 'Instrumental Methods Laboratory'

6. Chemical Engineering 261, 'Introduction to Environmental Engineering'

7. Civil Engineering 310, 'Senior Design Class'

8. Engineering Management 386, 'Safety Engineering Management'

9. Mechanical Engineering 229, 'Energy Conversion'

10. Life Sciences 352, 'Biological Effects of Radiation'

11. Physics 4 & 5, 'Concepts in Physics'

12. Physics 7, Environnemental Physics

13. Physics 107, 'Modem Physics'

14. Physics 207, 'Modem Physics' II

15. Physics 322, ' Advanced Physics'

3 SOPs have been revised, over the past year in order to improve our operations and efficiency. The following is a list of SOPs revised during the reporting period:

I. SOP 501 Emergency Procedures for Reactor Building Evacuation (Page 7 of 7)

2. SOP 104 Reactor Power Changes and Stable Operations (Page 1 of 4)

3. SOP 107 Permanent Log, Hourly Log and Operational Data (Page 3 of 6)

4. SOP 107 Permanent Log Hourly Log and Operational Data (Page 6 of 6)

5. SOP 501 Emergency Procedures for Reactor Building Evacuation (Page 7 of 7)

6. SOP 102 Pre-Startup Checklist Procedure (Pages 5, 6, 8, & 9 of 9)

7. SOP 501 Emergency Procedures for Reactor Building Evacuation (Page 7 of 7)

8. The above listed SOP revisions are provided in Appendix A.

2.0 REACTOR STAFF AND PERSONNEL 2.1 Reactor Staff Name Title Dr. Akira Tokuhiro I Director & Senior Operator William Bonzer 2 . Interim Director, Reactor Manager & Senior Operator 1 Maureen Henry Senior Secretary Brian Porter Senior Electronics Technician & Reactor Operator Dan Est(l Senior Lab Mechanic & Senior Operator

1. Terminated employment effective August 10, 2005

2. Interim Director effective September 12, 2005

4 2.2 Licensed Operators Name License

1. William Bonzer Senior Operator

2. Akira Tokuhiro 3 Senior Operator

3. Dan Estel Senior Operator

4. Nathan Ayres 2 Reactor Operator 5.. Craig Heimericks Senior Operator

6. Michelle Minard' Senior Operator

7. Kurt Koch 3 Reactor Operator 8 Christopher Carroll 3 Reactor Operator 1o. Mathew Dennis Senior Operator

11. Zachary Miller Reactor Operator

12. Bren Phillips 3 Senior Operator

13. Brian Porter Reactor Operator

14. Alfred Schovanez Senior Operator

15. Michelle Marincel Reactor Operator

1. Seth Bradley Reactor Operator

17. Jason Hall Reactor Operator

1. Ben Swoboda Senior Operator

19. Justin Munson Reactor Operator

20. Michael Lacey Reactor Operator

21. Zak Kulage 2 Reactor Operator

22. Chris Speer 2 Reactor Operator

1. Upgrade date I 1/8/2005

2. Effecfive date I 1182005

3. Ternination date 8/25/05

5 2.3 Radiation Safety Committee The Radiation Safety Committee meets quarterly. The committee met on 6/15/05, 9/16/05, 12/07/05 and 3/1/06 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. Dr. Roger Brown Biological Sciences

5. Dr. Robert DuBois Physics

6. Dr. David Wronkiewicz Geology/Geophysics

7. Dr. Ekkehard Sinn Chemistry

8. Mr. Randy Stoll Administrative Services

9. Dr. Seungjin Kim 2 Mining & Nuclear Engineering

10. Dr. Shoaib Usman Mining & Nuclear Engineering

11. Michelle Minard l Environmental Health and Safety Services

12. I)r. Akira Tokuhiro 3 Nuclear Reactor

1. Effective l/l/2006

2. Effective :/22/05

3. Terminated effective 8/10/05 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.RayBono 1Director of Environmental Health and Safety & Radiation Safety Officer

2. Mr. Brian Smith Industrial Hygienist

3. Michelle Minardl Health Physicist

4. Trevor Knudson 2 Health Physics Technician (part time)

1. Effective cn /l/12006 promoted from Health Physics Technician

2. Effective c-n 4/ 12005

6 3.0 REACTOR OPERATIONS Core Confirmation 101 W 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 worths 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 RegRod 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.

Figure $-1. UMRR Core 101W Configuration A

B SI 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 F-10 C-2 F-1 C-3 F-9 F-14 BR - Bare Rabbit E -

_ CR F-5 F-6 F-7 BR CR - Cadmium Rabbit F -

- S - Source Holder 1 2 3 4 5 6 7 8 9

7 Table 3-2 lists unplanned shutdowns during the reporting period. The reactor had several unscheduled shutdowns consisting of one scram, eighteen rundowns, and fourteen unplanned shutdowns. The majority of these shutdowns were from two sources, students operating the reactor for a nuclear engineering class and a repeated failure of magnet #3. Students learning to operate the reactor at times improperly changed scales on the Linear meter, which activated the 120% Demand Rundown. Magnet #3 failed several times creating ten unplanned shutdowns.

Once the reactor staff successfully sealed the underwater magnet the unplanned shutdown activity diminished.

Table 3-2: Unscheduled Shutdowns for 2005-2006 Date Type of Shutdown/Cause and Corrective Action Taken SCRAMS 11/14/05 Manual Scram.

Cause: Operator unintentionally depressed Manual Scram switch.

Corrective Action: No corrective action taken. SRO on Duty granted permission to restart reactor.

Rundowns 4/06/05 120% Demand Rundown.

Cause: Operator incorrectly upscaled Linear meter while performing power increase.

Corrective Action: SRO instructed operator to upscale correctly. SRO on Duty granted permission to restart reactor.

4/19/05 120% Demand Rundown.

Cause: Operator downscaled Linear meter too soon at 15% instead of 8%.

Corrective Action: SRO instructed student operator to downscale at 8%. SRO on Duty granted permission to restart reactor.

5/02/05 120% Demand Rundown.

Cause: Operator did not upscale Linear meter during power increase.

Corrective Action: SRO instructed operator to upscale at 60%. SRO on Duty granted permission to restart reactor.

8 5//11/05 120% Demand Rundown.

Cause: Operator downscaled Linear meter when should have upscaled.

Corrective Action: SRO instructed operator on proper scaling procedures. SRO on Duty granted permission to restart reactor.

6/29/05 120% Demand Rundown.

Cause: Operator downscaled Linear meter rather than upscaling.

Corrective Action: SRO instructed operator on proper scaling procedures. Reactor was not restarted that day.

7/14/05 120% Demand Rundown.

Cause: Operator used wrong scale on Linear meter when setting compensating voltage.

Corrective Action: SRO corrected the scaling mistake. SRO on Duty granted permission to restart reactor.

7/15/05 120% Demand Rundown.

Cause: Linear record had a paper jam causing recorder pen to remain at 40%. When chart paper was corrected for the paper jam the recorder pen went to 120% of scale.

Corrective Action: SRO instructed operator to pay attention to all instrumentation.

SRO on Duty granted permission to restart reactor.

7/18/05 120% Demand Rundown.

Cause: Operator changed scales incorrectly on Linear meter.

Corrective Action: Operator was instructed to pay better attention to console instrumentation. SRO on Duty granted permission to restart reactor.

8/12/05 120% Demand Rundown.

Cause: Electrical noise spike occurred while operator was upscaling Linear meter.

Corrective Action: No corrective action taken. SRO on Duty granted permission to restart reactor.

9/08/05 120% Demand Rundown.

Cause: Operator incorrectly scaled Linear meter.

Corrective Action: Operator was instructed to correctly scale Linear meter during power changes. SRO on Duty granted permission to restart reactor.

9/11/05 120% Full Power Rundown.

Cause: Electronic noise induced when depressing a console switch. Reactor power was stable at 100% full power during this trip.

Corrective Action: No corrective action taken. SRO on Duty granted permission to restart reactor.

9 10/31/05 120% Demand Rundown.

Cause: Student operator down scaled Linear meter too soon.

Corrective Action: SRO instructed operator to down scale at 8%. SRO on Duty granted permission to restart reactor.

I 1/07/05 120% Demand Rundown.

Cause: Operator did not upscale Linear meter.

Corrective Action: Operator instructed to upscale Linear meter during power changes.

SRO on Duty granted permission to restart reactor.

11/29/05 120% Demand Rundown.

Cause: Student operator down scaled Linear meter too soon.

Corrective Action: SRO instructed operator to down scale at 8% rather than at 140/%.

SRO on Duty granted permission to restart reactor.

12/29/05 120% Demand Rundown.

Cause: Operator did not upscale Linear meter during power increase.

Corrective Action: Operator was instructed to upscale at 60% and to pay attention to all instrumentation. SRO on Duty granted permission to restart reactor.

01/12/06 120% Full Power Rundown.

Cause: Electronic noise spike induced when auto-controller switched out of auto control and into manual control. No power increase occurred during this trip.

Corrective Action: No corrective action taken. SRO on Duty granted permission to restart reactor.

03/08/06 15 Second Period Rundown.

Cause: Operator performing reactor power doubling time calculations for research lab project.

Corrective Action: No corrective action taken. SRO on Duty granted permission to restart reactor.

03/20/06 120% Demand Rundown Cause: While operator changed scales on Linear meter a scaling switch button did not stay depressed and popped out.

Corrective Action: SRO instructed operator to apply more pressure to the scaling switch button when changing scales. SRO on Duty granted permission to restart reactor.

Unplanned Shutdowns 4/11/05 Unplanned Rundown Shutdown.

Cause: Intermittent relay connection.

Corrective Action: No corrective action necessary. SRO on Duty granted permission to restart reactor.

10 4/13/05 Unplanned Rundown Shutdown.

Cause: Electrical noise spike. No trips violated.

Corrective Action: Electronic Technician informed.

SRO on Duty grants permission to restart reactor.

9/11/05 Unplanned Shutdown.

Cause: Control rod # 3 dropped.

Corrective Action: No corrective action taken. Reactor was not restarted that day.

9/15/05 Unplanned Shutdown.

Cause: Control rod # 3 dropped.

Corrective Action: No corrective action taken. Reactor was not restarted that day.

10/12/05 Unplanned Shutdown.

Cause: Control rod #3 dropped.

Corrective Action: No corrective action taken. SRO on Duty granted permission to restart reactor.

10/12/05 Unplanned Shutdown.

Cause: Control rod #3 dropped.

Corrective Action: No corrective action taken. SRO on Duty granted permission to restart reactor.

11/04/05 Unplanned Shutdown.

Cause: Control rod #3 dropped, operator observed temporary loss of magnet curren.

Corrective Action: No corrective action taken. SRO on Duty granted permission to restart reactor.

11/04/05 Unplanned Shutdown.

Cause: Control rod #3 dropped, operator observed temporary loss of magnet current.

Corrective Action: Operator checked rod drop current, then reset current level to 1:

ma. above rod drop current. SRO on Duty granted permission to restart reactor.

11/07/05 Unplanned Shutdown.

Cause: Control rod #3 dropped, but unsure of reason.

Corrective Action: Operator increased magnet current from 63 to 68 ma. SRO on Duty granted permission to restart reactor.

11/07/05 Unplanned Shutdown.

Cause: Control rod #3 dropped, but unsure of reason.

Corrective Action: Operator increased magnet current from 68 to 75 ma. SRO on Duty granted permission to restart reactor.

11/07/05 Unplanned Shutdown.

Cause: Control rod #3 dropped, but unsure of reason.

Corrective Action: No corrective action taken. SRO on Duty granted permission to restart reactor.

I1 11/29/05 Unplanned Shutdown.

Cause: Brake band for control rod drive #3 broke, allowing the rod to fully insert.

Corrective Action: Replaced brake band for control rod #3 drive and tested the brake for proper operation.

01/30/06 Unplanned Shutdown.

Cause: Brake band for control rod drive #3 broke, allowing the rod to fully insert.

Corrective Action: Replaced brake band for control rod drive #3 and tested the brake for proper operation.

02/07/06 Unplanned Shutdown.

Cause: Control rod #3 dropped due to magnet current fluctuation.

Corrective Action: No corrective action taken. SRO on Duty granted permission to restart reactor.

Table 3**3: Maintenance for 2005-2006 Date Problem/Event and Action Taken 04/13/0'; Issue: Liner channel recorder's limit switch was causing intermittent rundowns.

Action taken: Cleaning and adjustment of the limit switch's circuit contacts was performed.

05/04/05 Issue: Magnet power supply selector switch was loose.

Action taken: Tighten magnet current selector switch.

06/15/0' Issue: Liner channel recorder showing incorrect values.

Action taken: Tighten the recorder pen's cable to match Linear meter..

06/16/05 Issue: Liner channel recorder showing incorrect values.

Action taken: Adjusted and tighten recorder pen cable to match Linear meter.

06/20/05 Issue: A reactor core light was not illuminating.

Action taken: Replaced the reactor core light bulb.

07/27/05 Issue: Startup channel recorder was responding slower than usual.

Action taken: Checked connections, cleaned tube bases and lubricated pulleys.

10/11/05 Issue: Control rod drive #1 had a broken brake band.

Action taken: Replaced brake band.

10/12/05- Issue: Control rod magnet #3 failed.

10/17/05 Action taken: Removed magnet from core and repaired, reinstalled in core, and performed rod drop time tests.

12 111/04/0'- Issue: Control rod magnet #3 failed.

11/07/05 Action taken: Removed magnet from core and repaired, reinstalled in core, and performed rod drop time tests.

11/08/05;- Issue: Control rod magnet #3 failed.

11/14/05 Action taken: Removed magnet from core and repaired, reinstalled in core, and performed rod drop time tests.

11/16/05- Issue: Control rod magnet #3 failed.

11/22/0' Action taken: Removed magnet from core and repaired, reinstalled in core, and performed rod drop time tests.

11/29/0' Issue: Control rod drive #3 had broken brake band.

Action taken: Replaced brake band.

12/16/05 Issue: Control rod magnet #3 failed.

Action taken: Removed magnet from core and repaired, reinstalled in core, and performed rod drop time tests.

02/08/06- Issue: Control rod magnet #3 failed.

02/09/06 Action taken: Removed magnet from core and repaired, reinstalled in core, and performed rod drop time tests.

03/27/06- Issue: Log & Liner channel showing lower values than the Liner channel.

03/28/06 Action taken: Verified recorder response with Log & Liner test switches, performed Log & Linear drawer calibration, and adjusted Linear CIC detector from 100% to 96%.

13 Table 3-4. Reactor Utilization I Reactor use 1630.0 hrs.

2. Time at power 858.7 hrs.

3. Energy generated 40,797.45 kW/hrs

4. Total number of samples Neutron irradiated 302 Gamma Exposure 325

5. U-235 Burned 1.7848 g

6. U-235 Burned and Converted 2.1078 g Table 3-5. Experimental Facility Usage Facilit Hours Bare Rabbit Tube 12.78 hr Cadmium Rabbit Tube 0.00 hr Beam Port 2.41 hr Other Core Positions 2.49 hr Gamma Exposures 632.37 hr Total 650.05 hr

14 4.0 EDUCATIONAL UTILIZATION The reactor facility supported several UMR courses in the past year for a total of 2906 student-hours. The number of UMR students utilizing the facility was 1039. This usage is a direct result of an aggressive and continuing campus wide "outreach" program. The reactor facility provided financial support for seven students with hourly wages, and partial support of a Graduate Research Assistant. Additionally, students from several 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, 2005) for a total of 6.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> to participate in a wide variety of reactor-based experiments. The laboratory was conducted by the UMR reactor staff and student licensed operators.

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, 1106 students and instructors from 72, 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 our participants were high school students. We coordinate with the UMR Admissions Office to schedule high school students to see other items of interest at UMR after they have visited our facility, such as the UMR-Chapter of American Nuclear Society, the Computer Integrated Manufacturing Lab, the Foundry, Ceramics Engineering, Mineral Museum, Compuler 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 4,839 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 2005-2006 Reporting Period VS- Winter CLASS NUMBER/TITLE # OF TIME AT STUDENT]

IS- Fall STUDENTS REACTOR HOURS WS 05 NE 25 Nuclear Technology Applications 26 2 52 WS 05 NE 206 Reactor Operations I 18 9 162 WS 05 NE 308 Reactor Laboratory II 14 24 336 SS 05 _ NE 300 Special Topics 3 24 72 WS 05 NE 490 Graduate Research 1 26 26 WS 05 _ NE 204 Radiation Laboratory 16 2 32 SS 05 _ NE 206 1 24 72 FS 05 NE 206 18 23 414 FS 05 OURE (Opportunity for Undergraduate Research Experience) 8 20 160 FS 05 NE 304 Reactor Laboratory I 15 30 450 FS 05 Chemistry Labs (Half Life) 638 _0.5 3_19.0 FS 05 Dr Pringle PhysicslO7 21 1 21 FS 05 NE 25 22 4 88 WS 06 Chemistry Labs (Half-life) Dr Long 188 0.5 132 WS 06 NE 308 15 8 120 WS 06 Dr. Thompson UMC 404 9 6.0 54.0 WS 06 NE 206 26 18 468

_ TOTAL 1039 282 2906

16 Table 4-2. Reactor Sharing Program (2005-2006)

DATE PARTICIPANTS Number Hours 4/3/05 Tour with Charles Beasley and family 3 1 4/7/05 Innovation Nuclear Infraction and Education 30 2 4/10/05 Publication Tour 2 1 4/15/05 ANS Preview Tour 36 3 4/19/05 Ash Grove High School 12 2 4/20/05 Alumni Visit 2 .5 4/20.'05 MEER 11 Global Research Class 2 .5 4/2005 Individual Tours April of 2005 1 .5 4/27/05 Lutheran High School 34 3 4/27./05 Power change NE 25 8 1.5 4/28/05 Power changes NE 25 18 1.5 4/28/05 Lebanon High School 33 3 5/2/05 Scavenger Hunt 8 1 5/2005 Individual Tours May of 2005 10 3.5 5/4105 Reactor Robotic Show and Tell 40 3 5/4/05 Tom Shipley with UMR News 2 1 5/4/1)5 Staff Excellence Award 3 1 5/11,'05 Alfred Schovanez Tour with Home School students 2 1 6/3/)5 University of Arkansas Medical School 9 1.5 6/9/05 Minority Introduction to Technical Engineering Programs 36 2 6/16/'05 Minority Introduction to Technical Engineering Programs 30 3 6/17/05 Robotics camp at UMRR 38 6 6/23/05 Jackling/Introduction to Engineering Camp 37 2 6/23/05 Financial Aid office Tour 3 1 6/30105 INIE Tour 5 1 6/30/05 Jackling/Introduction to Engineering Camp 28 2 7/20D5 Individual Tours month of July 7 4.5 7/6 to 7/9/05 Reactor Operators Workshop 4 28.5 7/11/05 Nuclear Engineering Camp 7 4.5 7/13/05 Nuclear Engineering Blue Glow and control room 38 3 7/14/05 Jackling/Engineering Camp 31 2 7/14/05 Nuclear Engineering Camp Focus Group 7 4.5 7/18/05 Nuclear Engineering Camp Focus Group 7 4.5 7/20/05 Nuclear Engineering Camp Tour Half Life 15 1.5 7/20/25 Nuclear Engineering Camp Tour Half Life 15 1.5 7/22 to 7/26/05 Reactor Operator Workshop 4 28.5

17 DATE PARTICIPANTS Number Hours 7/2/2005 St Louis Jr. Science Academy 14 1 8/11/()5 Individual Tour's 8/2005 9 4 9/12/05 Individual Tour's 9/2005 3 .5 10/13/05 East Central College 10 2 10/17/05 Fall Open House 30 2 10/17/05 Individual Tour's 10/2005 10 2 10/22/05 Girl Scouts Tour 160 3 10/24-26/05 Paul Doyle NRC testing 1 30 10/28/05 Chancellor Carney tour with Dr Kumar 2 1 11/1/2005 Expanding Your Horizons training 3 1 11/2/2005 Expanding Your Horizons training 3 1 11/14/2005 Expanding Your Horizons 63 6 11/19/05 New Reactor Trainees 6 1.5 11/10/05 Jefferson High School 12 2 11/10/05 Andrea Mayor training with Dan Estel 1 4 11/12/05 Open House Campus Wide 8 1 11/30/05 Offsite meeting Fire, Ray Bono, Police, and Hospital 8 1 11/2005 Individual Tours 8 2.5 12/7/05 Individual Tours 4 1.5 12/7/05 Mansfield High School 22 1.5 12/8/05 East Central College 12 1.5 12/14/05 Highway Patrol Tour 2 1.5 12/13/05 Andrea Mayor Trianing 1 4.5 1/3/05 Individual Tour's 7 3.5 1/5/05 UMR Police Tour 3 1 1/26/05 NRC visit Pat Izac, Young, Deem 3 8 2/8/05 Individual Tours 2/2006 5 1.0 2/17/06 Lynn State College 12 7 2/18/06 Boy Scouts Tour 42 2 2/20/06 Campus wide Open House President Day 5 3 2/22/06 Andrea Mayor Training 1 4 3/3/05v Fairgrove High School 20 1 3/3/06 Pro Session students tour 2 .5 3/2006 Individual Tours 15 2.5 3/20/2006 NE 404 From Columbia' 8 6 3/23/2C006 Hazelwood West High Tour 22 1.5 Totals 1106 247.5

18 5.0 REACTOR HEALTH PHYSICS ACTIVITIES The health physics activities at the UMR Reactor facility consists 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. Ily-Product Material Release Surveys There were no shipments of by-product material released off-campus. There was one by-product release on campus. On 5/3/2005, there was a release of 70 pounds of cold waste picked up from the nuclear reactor facility and taken to UMR's Dangerous Materials Storage Facility.

5.3. Routine Monitoring Sixty three 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 twice 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 20 area dosimeters assigned on campus for beta and gamnna monitoring and one for beta, gamma, and neutron monitoring. In addition, 9 digital, direct-reading dosimeters and 5 chirpers dosimeters are used for visitors and high radiation werk.

There have been no significant personnel exposures during this reporting period. Visitors are

19 monitor d 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 2005 through March 2006 sample concentrations averaged 5.642x10-6 ~iCi/ml.

Release of gaseous Ar-4 1 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 101,742.35 microucuries of Ar-41 were released into the air.

5.4. WVaste Disposal solid waste, including used water filters, used resins, and contaminated paper 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 was one waste barrel transferred from the Reactor facility to the Dangerous Materials Storage Facility (DMSF) on campus. This 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 5/3/2005, the barrel had no detectable activity.

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 four major projects during the next reporti ig period; I) license renewal process 2) implementation and revision of the new activities plan, 3) installing new reactor nuclear instrumentation, and 4) continuation of the reactor operator training program.

6.1 Administrative Changes UMRR is presently staffed with Reactor Manager, Mr. William Bonzer also acting as Interim 'Reactor Director. Dr. Akira Tokuhiro was Reactor Director and has obtained a position at another university. The Reactor Director position will be filled, as in the past, with a Nuclear Engineering Faculty member once the faculty member position is filled.

6.2. Reficensing License renewal activities will continue during the upcoming reporting period. Our present license is valid until relicensing is completed by NRC. NRC has started reviewing the required materials including SAR, technical specifications, emergency plan, operator requalification plan, and environmental report 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 teachi:ng.

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 continuing. A thermal luminance detector (TLD) reader has been purchased and is used for labs involving gamma exposure. Under provisions Df

21 10CFR50.59 the installation of a pool water cooling system will be completed during the upcoming reporting period. Laboratory equipment is being upgraded to enhance the neutron activation analysis types of labs and research. A high purity germanium detector with greater efficiency, rabbit system and glove box is intended to be purchased during this reporting period.

This eqt ipment will allow additional samples be irradiated and processed through our gamma spectroscopy systems.

6.5 Reactor Operator Traininig The results of the forth annual group of reactor operator trainees, which initially took the NRC examination during the week of October 24, 2005, were release to UMRR in December 2005. Three trainees were licensed as reactor operators (ROs) with an additional RO upgraded to senior reactor operators (SRO). One trainee did not pass the NRC operators examination October. 2005 and will retake the exam Spring, 2005. The training program has undergone successful revisions in response to input from the NRC.

Yin additional reactor operator training program was initiated August, 2003 for high school students attending a week of UMR Nuclear Engineering Camp. This program is titled as the Reactor Operations Workshop and design specifically for students who plan to attend UMR and become licensed operators at UMRR. Four students from each of the two nuclear engineering camps were selected to complete a four-day training course that provided a thorough introduction to the UMRR licensed documentation, which include the facility's Technical Specifications, Safety Analysis Report, Emergency Plan, Standard Operating Procedures, and the I OCFR20.

Students received lectures regarding reactor theory and operated the reactor to reinforce basic principles of the reactor theory. Two students participating in this program are UMRR licensed operator.; and a third student is an active trainee schedule to test for the RO examination during this reporting period.

Two Reactor Operation Workshop sessions were offered in summer 2005 to select UMR Nuclear Engineering Camp attendees. The Reactor Operations Workshop will again be offered for the fourth year this summer of 2006.

22 APPENDIX A.

STANDARD OPERATING PROCEDURES CHANGED DURING THE 2005-2006 REPORTING YEAR

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

- SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Revised September 9, 2005 Page 7 of 7 UMR REACTOR EMERGENCY PHONE LIST Reactor Staff Cell HOME WORK Brian Forter, Sr. Electronics Tech. RO 368-3090 341-4291 William Bonzer, Interim DirectorManager, SRO 578-9463 368-3727 341-4384 REV Daniel Estel, SRO,Senior Lab Mechanic (573) 435-6328 3414291 l Ray Bono, Radiation Safety Officer 428-6469 364-5728 341-4240,4305.4403 Maureen Henrv. Sr. Sec. 364-7272 341-4236 Univer-4tv Administrative Staff

1. Dire-tor, UMR Police, William Bleckman 364-1294 341-4345

2. Chancellor, John F. Carney III 647-9040 341-7141 3414116 } REV

3. Vice Chancellor for Admin.Services, Steve Malott 364-7927 3414122

4. Director, Physical Plant, Marvin Patton 364-6278 3414252

5. Director, Health Service - Infirmary, Jerry Thomas DO 364-6845 3414284

6. Dean, SoMEER- Mariesa L. Crow 341-5158 3414153

7. Radiation Safetv Officer. Rav Bono 428-6469 364-5728 341-4240,4305,4403 Local UMR University Police 341-4300 Rolla City Police 9-911 Rolla Fi-e Department 9-911 Phelps County Hospital 9-911 Rolla Er aereencv Manacnement Aaencv 9-911 State Agencies Missouri Highway Patrol (573) 368-2345 Missouri State Emergency Mgt. Agency (24 hr.) (573) 751-2748 Missouri Dept. of Natural Resources (24 hr.) (573) 634-2436 Missouri Bureau of Environmental Epidemiology (573)751-6160 (573) 751-4674 (24hrs)

Federal Asencies NRC, Operations Center (301) 816-5100 NRC Duty Officer (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) (301) 816-5100 Other Americaii Nuclear Insurers (860) 561-3433 Radiation Emergency Assistance Center (423) 576-3131 (865) 576-1005 (24hrs)

RevisedBy: Maureen Henry Approved By: William Bonzer WUASH I\

/ /

- UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 104 TITLE: REACTOR POWER CHANGES AND STABLE OPERATIONS Revised: February 28. 1996 Page 1 of 4 A. ELLRPOSE To provide for a safe and consistent method to 1) change power after the reactor has been leveled at low power and 2) operate the reactor at steady-state power.

B. PRECAUTIONS. PREREQUISITES, OR LIMITATIONS

1. This procedure is applicable after SOP 103, "Reactor Startup to Low Power" has been completed.

2. Both Safety Channels and the Power Range of the Log and Linear drawer should begin IRev.

to show turnaround at about 5 kW. If turnaround has not been observed by a power of 10 kW, the reactor will be shut down and the SRO on Duty notified.

3. At least one nitrogen diffuser should be turned on for operations greater than 20 kilowatts. This requirement may be waived by the SRO on Duty for special tests.

Reactor bridge radiation levels shall not be allowed to equal or exceed 30 mr/hr.

4. Prior to taking the reactor to a power level in excess of 100 kW, the reactor must first be leveled at a power between 10 kW and 100 kW and hourly logs taken to verify the proper operation of the reactor instrumentation. This requirement is only applicable to the first power increase above 100 kW for a particular operational run.

5. At least one building exhaust fan shall be turned on for reactor operations at 200 k0.

6. At least one building exhaust fan should be turned on when the constant air monitor reaches a value of about 6G9Ocpm. ,i' c

7. The licensed operator shall control all reactivity changes to the reactor by direct C/a /O.

manipulation or by directing the manipulation of the controls and experiments being conducted at the facility.

8. The operator must be alert and attentive at all times during reactor operations. All nuclear instruments (Startup, Linear, Period, Log, Safety No. 1, Safety No. 2, and the l Rev.

Power Range of the Log and Linear drawer) must be closely monitored for proper response. If at any time an improper response is suspected, the Senior Operator on Duty shall be notified and a reactor shutdown initiated as deemed necessary by the Reactor Operator.

Revised By: William Bonzer Approved By: Albert Bolon

I

' UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 107 TITLE: PERMANENT LOG, HOURLY LOG AND OPERATIONAL DATA Revised: September 30, 2003 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.

, = value,~Fed (and d - vS r cceded)

turrents t for e-appx t

21. Record the reading on the Safety Channel No. 1.

22. Record the reading on the Safety Channel No. 2.

23. 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). l Rev.

24. Record the reactor Inlet Temperature (thermocouple 1 or 3) as displayed cn the Pool Water Temperature Recorder.

25. Verification SRO on Duty is aware of his or her status as SRO on Duty.

Re-,

26. Record initials if SRO on duty -

27. Licensed operator initials.

2. Permanent Log Entries

a. All entries in the Permanent Log shall be preceded by the date (Use the date stamp).

Revised By: William Bonzer Approved By: Akira Tokuhiro IJLs 5 A

i*UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 107 TITLE: PERMANENT LOG, HOURLY LOG AND OPERATIONAL DATA Revised: September30, 2003 -;age 6 of 6 Date _ , S , . i (Start a new form each day) HOURLY OPERATING LOG Signatures: (1) (4) (7) . Re (Including Licensed (2) ' (5) (8)

Operator on Duty) (3) (6) (9)

(InMl (lo eve)

1. Time at Power

2. hitials - 'Person at Console

3. Nominal Power (Wor kW)

4. Linear Recorder (%)

5. Linear Scale (W or kW)

6. Auto Set/Board Reset (Y orN)

7. Log Level (%)-

8. Period Trace Normal(I')

9. Log and Linear Power Range (%)

Log Count Rate Recorder (cps) o10.

11. Source Removed? (Y or N)

12. Diffuser(3) On? (Y or N)

13. Exhaust I an On? (Y or N)

14. Shim Rod No. 1 (inches)

15. Shim Roc' No. 2 (inches)

16. Shim Roc. No. 3 (inches)

17. Regulating Rod (inches)

18. Radiation Levels Normal (1r)

19. Bridge Monitor (mr/hr) yzi.

1/iN,

-I-

,-Is

_-'2 , fagnet -im ntusiNo d(9)i

21. Power Chamber No. 1 (%)

22. Power Chumber No. 2 (%)

23. Permanen: Log Entries (X) 0

24. Core Inlet Water Temp. ( F) j

25. SRO on Duty Verification (4')

26. SRO on Duty Initials-

27. Licensed Operator Initials [ i - l il i z=

.7 I

pproved By: Akira Tokuhiro Revised By: William Bonzer

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: C01 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Revised January 11, 2006 Page 7 of 7 UMR REACTOR EMERGENCY PHONE LIST Reactor Staff Cell HOME WORK Brian Porter, Sr. Electronics Tech. RO 368-3090 341-4291 William Bonzer, Interim Director,Manager, SRO 578-9463 368-3727 341-4384 Daniel Estel, SRO,Senior Lab Mechanic (573) 435-6328 341-4291 Ray Bono, Radiation Safety Officer 428-6469 364-5728 341-4240,4305,4403 Maureen Henrv. Sr. Sec. 364-7272 341-4236 University Administrative Staff

1. Director, UMR Police, William Bleckman 364-1294 341-4345

2. Chan-ellor, John F. Carney III 647-9040 341-7141 341-4116

3. Vice Chancellor for Admin.Services, Steve Malott 364-7927 . 341-4122

4. Director, Physical Plant, Marvin Patton 364-6278 341-4252

5. Director, Health Service - Infirmary, Jerry Thomas DO 364-6845 341-4284

6. Dean, SoMEER- Mariesa L. Crow 341-5158 341-4153

7. Radiation Safety-Officer. Ray-Bono 428-6469 364-5728 341-4240,4305,4403 Local UMR University Police 341-4300 Rolla City Police 9-911 Rolla Fire Department 9-911 Phelps County Hospital 9-911 Rolla E rergency Management Agencv 9-911 State Agencies Missouri Highway Patrol (573) 368-2345 Missouri State Emergency Mgt. Agency (24 hr.) (573) 751-2748 Missouri Dept. of Natural Resources (24 hr.) (573) 634-2436 Missouri Bureau of Environmental Epidemioloev (573)751-6160 (573) 751-4674 (24hrs)

Federal Agencies NRC, Operations Center (301) 816-5100 NRC Duty Officer (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) (301) 816-5100 Other American Nuclear Insurers (860) 682-1301 JREV.

Radiation Emergency Assistance Center (423) 576-3131 (865) 576-1005 (24hrs)

Revised .By: Maureen Henry Approved By: William Bonzer AlZ6" 3p

~V%/xccuW &Iyb1a'

UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: [02 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Revised: March 3, 2006 Page 5 of 9

20. 150% Power Scram Check:

a. Withdraw the control rods to 3 inches.

b. Depress the test button on Safety Amplifier 1.

c. Verify that a scram occurs before 150%.

d. Verify that the 150% Full Power annunciator light and the audible alarm are activated.

e. Record the trip test reading displayed on Safety Amplifier 1. Rev

f. Depress the reset button on Safety Amplifier 1.

g. Reset the annunciator panel and insert magnets.

h. Repeat steps a - f for Safety Amplifier 2.

21. Log and Linear Drawer Non-Operative Scram and Rundown Test:

a. Withdraw shim rods to 3 inches.

b. Depress the NON-OPER keypad switch. Check for the Non-Operate Scram and Low CIC Voltage Rundown visual and audible alarms.

c. Verify that the rods have dropped and rod drives are running down.

d. Try to stop the rundown by lifting the shim joy stick.

e. Stop the rundown with the rundown reset button.

f. Reset the scram, rundown, and annunciator panel.

22. Period Trip Test:

a. Withdraw shim rods to 3 inches.

b. Depress and hold the PERIOD TEST keypad switch. Verify that the 30 Second Rod Withdrawal Prohibit annunciator is activated with a simulated period greater than or equal to 30 seconds. Acknowledge annunicator panel.

c. Continue depressing the PERIOD TEST keypad switch. Verify that the 15 Second Rundown is activated with a simulated period greater than or equal to 1S seconds. Acknowledge annunciator panel.

d. Continue depressing the PERIOD TEST keypad switch. Verify that the 5 Seccnd Scram is activated with a simulated period greater than 5 seconds by observing a loss of magnet current and the annunciators.

e. Release the switch.

f. Reset the scram, rundown, and annunciator panel.

Revised By: William Bonzer Approved By: William Bonzer LAJ j)i _

• • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Revised: March 3, 2006 Page 6 of 9

23. Manual Scram:

a. Raise shim rods to 3 inches.

b. Push the manual scram button. Verify that the rods have dropped by visually observing the video display and noting that the blue magnet contact lights are off.

c. Push the scram reset button and reset the annunciator panel.

24. Push the annunciator test button and check for burned out bulbs. Replace any burned out bulbs. Reset the annunciator panel.

25. Verify that the magnets are on and that all rods are on insert limit.

26. Prepare hourly checklist and permanent log. Rev

27. Detector Response Check:

a. Inspect the core. Make certain core cooling is clear and experiments are firmly secured.

b. "Spike" the Log and Linear Channel CIC and the Linear Channel CIC by positioning the neutron source next to the detectors.

c. Insert the source into the holder.

d. Observe the Log/ Period and the Linear recorder traces to verify proper response to the source spike.

e. Observe the Startup Channel recorder to verify that the recorder responded properly with a decreased count rate when the source was moved away from the core.

f. Reset the annunciator panel.

28. Raise the shim rods to 6 inches. Record the time on both the checklist and in the permanent log.

29. Nitrogen Diffusers Status: Turn on nitrogen diffuser pumps as desired. Record status of pumps as "ON" or "OFF". (Note: At least one pump should be turned on for operations in excess of 20 kW.)

30. Record the intended power level.

31. Announce, "The Reactor Will Be Started and Taken to a Power of Watts'.

Revised By: William Bonzer Approved By: William Bonzer

.\J1 &tlke 1 2 -

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Revised: March 3, 2006 Page 8 of 9 I.Date

2. Initials of the Person Performing Checklist l

3. Tin:.e (Console Clock)'

4. Core Loading

5. P.A., Intercom, Video Monitor On .

6. RAM System Check

7. Radiation Level Normal

8. Beam Port and Thermal Column Status (OPEN or SHUT)

9. Linear Channel Zero Meter Reading Scale l

10. Linoar C.I.C. Voltages HV (-540) = = = =

l__ . CV (- 2 to 8)

11. Recorders On, Dated, "RCD" Light On Temp & CAM Recorders

12. Core Check (Lights On) Water Level (inches) . . -

Elements Verified . . -

Inspection . . -

Source Inserted

13. Start-Up Channel Test . _

14. Verify FC Response, FC Inserted, Count Rate > 2 CPS _

15. Log Count Rate HV Power Supply (+400 VDC) _

16. Log and Power Range Test _

17. Period Response Test 18.M net Power On, Scram Reset, Board Reset .

19. Inlel Temperature CF)__

Revised By: William Bonzer Approved By: William Bonzer

• ,,IA Lat R

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE

• Revised: March 3, 2006 Page 9 of 9

20. 150% Power Safety Amplifier 1 Scram Test Trip Test Reading Raise Rods 3 in. Push Safety Amplifier 2 "Test" Button Trip Test Reading l

21. Log and Linear Drawer Non-Operative Raise Rods 3 in. Press Sc-am Test NON-OPER switch. l .

22. Period Trip Test . .

23. Manual Scram Test l Raise Rods 3 in. Push Manual Scram

24. Annunciator Test, All Lights On = == =

25. Ma gnets On,,_.

Rods on Insert Limit _ _ -

26. Prepare Hourly and Permanent Logs . -

27. Detector Response Check Inspect Core . -

Log Spike . -

Period Spike Linear Spike =_ _ _ Rev Startup Channel

Response

28. Raise Rods to 6 in., Record Time in Checklist and permanent log.

29. Nitrogen Diffuser Status No. I (ON or OFF)

No. 2 _ _

30. Intended Power Level

31. Announce Intention to Start

32. Pre- Startup Check Properly Completed (Licensed Operator's Initials)

33. Senior Operator on Duty announcement's of licensed operators

34. Senior Operator on Duty's Picture in Control Room

35. Sen:or Operator on Duty's Initials

36. Dato=

- 1 Revised By: William Bonzer A Ap-proved By: William Boraxr L-tJyt,,t art~l .. 1&_n_ 2 A

• ** UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Revised March 6, 2006 Page 7 of 7 UMR REACTOR EMERGENCY PHONE LIST Reactor Staff Cell HOME WORK Brian Porter, Sr. Electronics Tech. RO 368-3090 341-4291 William Bonzer, Interim Director, Manager, SRO 578-9463 368-3727 341-4384 Daniel Estel, ,Senior Lab Mechanic,SRO (573) 435-6328 341-4291 Ray Bono, Director, Radiation Safety Officer 428-6469 364-5728 341-4240,4305,4403 Maureen Henry. Sr. Sec. 364-7272 341-4236 University Administrative Staff

1. Director, UMR Police, William Bleckman 364-1294 341-4345

2. Chancellor, John F. Carney III 647-9040 341-7141 341-4116

3. Vice Chancellor for Admin.Services, Steve Malott 364-7927 341-4122

4. Director, Physical Plant, Marvin Patton 364-6278 341-4252

5. Director, Health Service - Infirmary, Jerry Thomas DO 364-6845 341-4284

6. Dean, SoMEER- Mariesa L. Crow 341-5158 341-4153

7. Health Physicist, Michelle Minard 426-2401 341-7014 REV.

Local UMR University Police 341-4300 Rolla City Police 9-911 Rolla Fire Department 9-911 Phelps County Hospital 9-911 Rolla E iergency Management Agency 9-911 State Aginces Missouri Highway Patrol (573) 368-2345 Missouri State Emergency Mgt. Agency (24 hr.) (573) 751-2748 Missouri Dept. of Natural Resources (24 hr.) (573) 634-2436 Missouri Bureau of Environmental Epidemiologzy (573)751-6160 (573) 751-4674 (24hrs)

Federal Agencies NRC, Operations Center (301) 816-5100 NRC Duty Officer (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) (301) 816-5100 Other American Nuclear Insurers (860) 682-1301 Radiatio1 Emergencv Assistance Center (423) 576-3131 (865) 576-1005 (24hrA)

Revised By: Maureen Henry Approved By: William Bonzer