ML041270168

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Annual Progress Report 2003-2004 for the University of Missouri-Rolla Reactor Facility
ML041270168
Person / Time
Site: University of Missouri-Rolla
Issue date: 04/28/2004
From: Tokuhiro A
Univ of Missouri - Rolla
To:
Office of Nuclear Reactor Regulation
References
Download: ML041270168 (42)
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University of Missouri-Rolla to Nuclear Reactor Facility 70 1870 Miner Circle Rolla, MO 65409-0630 Phone: (573) 341-4236 FAX: (573) 341-4237 April 28. 2004

Dear Sir:

Please find enclosed the Annual Progress Report 2003-2004 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,

r. Akira T. Tokuhiro Reactor Director mh Enclosure xc: Patrick Isaac, Project Manager (NRC)

Document Control Desk (NRC)

Chancellor Gary Thomas (UMR)

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

Mr. Ray Bono, Radiation Safety Officer(UMR)

Dr. Robert Mitchell, Dean, School of Engineering (UMR)

Dr. Paula M. Lutz, Dean, College of Arts and Science (UMR)

American Nuclear Insurers, c/o Librarian Dr. Mark Fitch, Chairman, Radiation Safety Committee (UMR)

University of Missouri-Columbia Research Reactor (MURR)

Dr. Arvind Kumar, Chairman of Nuclear Engineering (UMR)

Dr. Arlan R. DeKock, Dean of School of Management & Information Systems

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PROGRESS REPORT 2003-2004 UNIVERSITY OF MISSOURI-ROLLA NUCLEAR REACTOR FACILITY

i PROGRESS REPORT FOR THE UNIVERSITY OF MISSOURI-ROLLA NUCLEAR REACTOR FACILITY April 1, 2003 to March 31, 2004 Submitted to The U.S. Nuclear Regulatory Commission and The University of Missouri-Rolla

ii

SUMMARY

During the 2003-2004 reporting period the University of Missouri-Rolla Reactor (UMRR) was in use for 416 hours0.00481 days <br />0.116 hours <br />6.878307e-4 weeks <br />1.58288e-4 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 4,456 student-hours. About 3,172 visitors visited the reactor during the past year. There were 1,440 participants, mostly high school students, in the U.S. Department of Energy Reactor Sharing Program.

The reactor produced 33661.6 kilowatt-hours of thermal energy using approximately 1.466 grams of uranium. A total of 293 samples were neutron irradiated in the reactor with most of them being analyzed in the Reactor Counting Laboratory. An additional 440 samples were exposed to gamma radiation in the reactor.

iii TABLE OF CONTENTS

1.0 INTRODUCTION

..................................... 1 1.1 Background Information ..................................... 1 1.2 General Facility Status ..................................... 2 2.0 REACTOR STAFF AND PERSONNEL ................................. .. 4 2.1 Reactor Staff ..................................... 4 2.2 Licensed Operators ........................... 4 2.3 Radiation Safety Committee ........................... 4 2.4 Health Physics ......................... 5 3.0 REACTOR OPERATIONS ........................ 6 4.0 EDUCATIONAL UTILIZATION ........................ 10 5.0 REACTOR HEALTH PHYSICS ACTIVITIES ........................ 15 5.1. Routine Surveys .15 5.2. By-Product Material Release Surveys .15 5.3. Routine Monitoring .15 5.4. Waste Disposal .16 5.5. Instrument Calibrations .16 6.0 PLANS ....... 16 6.1. Administrative Changes ................. 16 6.2. Relicensing .17 6.3. Strategic Plan .17 6.4. Instrumentation Upgrade .17 6.5 Reactor Operator Training .17 APPENDIX A. Standard Operating Procedures Changed During The 2003-2004 Reporting Year APPENDIX B. Revised SAR Pages For The 2003-2004 Reporting Year

iv LIST OF TABLES Table 3-1. Core 101W Technical Data ............................................ 6 Table 3-2. Scrams, Rundowns, And Unplanned Shutdowns ............................................ 7 Table 3-3. Maintenance ............................................ 9 Table 3-4. Reactor Utilization ........................................... 10 Table 3-5. Experimental Facility Use Other Than The Reactor ........................................... 10 Table 4-1. UMR Classes at Reactor Facility 2003-2004 Reporting Period .......................... 12 Table 4-2. Reactor Sharing Program ............................................ 13 LIST OF FIGURES Figure 3-1. UMRR Core Configuration ..................................................... 6

I

1.0 INTRODUCTION

This progress report covers activities at the University of Missouri-Rolla Reactor (UMRR) Facility for the period April 1, 2003 to March 31, 2004.

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 other college and pre-college institutions also made use of the facility during the reporting period. The facility is also available for the training of reactor personnel from commercial concerns with legitimate interest in our facility use 1.1 Backaround 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 powver 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.

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. Additionally, 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 beam port experimental area is equipped with NE-213 and time-of-flight neutron spectroscopy systems.

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

2 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 license for UMRR has been extended to January 14, 2005, Amendment No. 16 (August 6, 1999). We have been working on re-licensing during this period and will continue.

We will submit a re-licensing application by December 15, 2004.

We are continuing efforts to upgrade our console using grant awards from DOE combined with money directly from reactor funds. We have received grant funds for Reactor Instrumentation upgrade in Spring 2003 and have received notice of an award for additional grant funds in Spring 2004.

The reactor has supported several graduate students in part or in full, to perform research in support of the relicensing effort. To date research on atmospheric dispersion modeling dose assessments associated with normal operations and accident conditions has been finished. An additional graduate student is now conducting severe accident analysis in support of the SAR.

An independent auditor from the University of Columbia audited the Reactor Facility on December 17, 2003. There were no significant areas of concern. We have entered into an agreement 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. Physics 4&5, 'Concepts in Physics'
2. Physics 7, 'Environnemental Physics'
3. Chemistry 8, 'Qualitative Analysis Laboratory'
4. Physics 107, 'Modern Physics'
5. Physics 207, 'Modern Physics II'
6. Physics 322, 'Advanced Physics'
7. Chemical Engineering 261, 'Introduction to Environmental Engineering'

3

8. Chemistry 2, 'General Chemistry Laboratory'
9. Mechanical Engineering 229, 'Energy Conversion'
10. Life Sciences 352, 'Biological Effects of Radiation'
11. Chemistry 251, 'Intermediate Quantitative Analysis'
12. Chemistry 355, 'Instrumental Methods Laboratory'
13. Civil Engineering 310, 'Senior Design Class'
14. Basic Engineering 50, 'Engineering Mechanics - Statics'
15. Engineering Management 386, 'Safety Engineering Management' 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:
1) SOP 102 Pre-Startup Checklist Procedure (Page 1 of 9)
2) SOP 102 Pre-Startup Checklist Procedure (Page 2 of 9)
3) SOP 102 Pre-Startup Checklist Procedure (Page 3 of 9)
4) SOP 102 Pre-Startup Checklist Procedure (Page 4 of 9)
5) SOP 102 Pre-Startup Checklist Procedure (Page 5 of 9)
6) SOP 102 Pre-Startup Checklist Procedure (Page 6 of 9)
7) SOP 102 Pre-Startup Checklist Procedure (Page 7 of 9)
8) SOP 102 Pre-Startup Checklist Procedure ( Page 8 of 9)
9) SOP 102 Pre-Startup Checklist Procedure (Page 9 of 9)
10) SOP 106 Restart of the Reactor When not secured (Page 1 of 2)
11) SOP 106 Restart of Reactor When not secured (Page 2 of 2)
12) SOP 107 Permanent Log Hourly Log and Operational Data (Page 3 of 6)
13) SOP 107 Permanent Log, Hourly Log and Operational Data (page 6 of 6)
14) SOP 501 Emergency Procedures for Reactor Building Evacuation (Page 7of 7)
15) SOP 501 Emergency Procedures for Reactor Building Evacuation (Page 7of 7)

The above listed SOP revisions are provided in Appendix A.

4 2.0 REACTOR STAFF.AND PERSONNEL 2.1 Reactor Staff Name Title

1) Dr. Akira Tokuhiro Director & Senior Operator
2) William Bonzer Reactor Manager & Senior Operator
3) Maureen Henry Senior Secretary
4) Brian Porter' Senior Electronics Technician & Reactor Operator
5) Dan Estel Senior Lab Mechanic & Senior Operator 2.2 Licensed Operators Name License
1) William Bonzer Senior Operator
2) Akira Tokuhiro Senior Operator
3) Dan Estell Senior Operator
4) Jeremy Gorelick' Senior Operator
5) Craig Heimericks' Senior Operator
6) Michelle Minard Reactor Operator
7) Kurt Koch Reactor Operator
8) Hannah Yount Reactor Operator
9) James Kramer 2 Reactor Operator
10) Christopher Carroll' Reactor Operator
11) Mathew Dennis2 Reactor Operator
12) Zachary Miller Reactor Operator
13) Bren Phillips 2 Senior Operator
14) Brian Porter' Reactor Operator
15) Alfred Schovanez' Reactor Operator
16) Heather Lewis Reactor Operator
17) Michelle Marincel 2 Reactor Operator
18) Seth Bradley2 Reactor Operator I Effective date 4n103 2 Effective date 10/21/03

5 2.3 Radiation Safety Committee The Radiation Safety Committee meets quarterly. The committee met on 6/17/03, 11/25/03, 8/20/03 and 2/6/04 during the reporting period. The committee members are listed below.

Name Department

1) Dr. Mark Fitch, (Chairman) Civil Engineering
2) Mr. Ray Bono (Secretary, ex-officio, non-voting) Environmental Health and Safety Services
3) Mr. William Bonzer Nuclear Reactor, Reactor Manager
4) Dr. Roger Brown Biological Sciences
5) Dr. Robert DuBois Physics
6) Dr. Seungjin Kim Effective 9/9/03 Nuclear Engineering
7) Dr. David Wronkiewicz Effective 9/9/03 Geology/Geophysics
8) Dr. Ekkehard Sinn Chemistry
9) Mr. Randy Stoll Director, Business Services
10) Dr. Akira Tokuhiro Director, Nuclear Reactor
11) Dr. Heather Gepford Until 5/03 Nuclear Engineering 2.4 Health Phvsics 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:

Nam c Title

1) Mr. Ray Bonol Director of Environmental Health and Safety & Radiation Safety Officer
2) Mr. Brian Smith Industrial Hygienist
3) Allison Adams HP Technician
4) Michelle Minard HP Technician 1.Effective as of 1/04

6 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 worths were measured in cold, clean conditions.

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

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

Figure 3-1. UMRR Core 101W Configuration 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-151 C - Control Elements E F-10 C-2 F-1 C-3 F-9 F-14 BR - Bare Rabbit F - CR F-5 F-6 F-7 BR CR - Cadmium Rabbit S - Source Holder 1 2 3 4 5 6 7 8 9

7 Table 3-2 presents a listing of unscheduled shutdowns (scrams, rundowns, and unplanned nonnal shutdowns) along with their causes and corrective actions. One scram occurred due to a building evacuation drill that was conducted during reactor operations. The manual scram of the reactor was enacted as prescribed in the building evacuation standard operating procedure.

Four of the 16 rundowns were 120% Full Power rundowns caused by electrical noise spikes to the Log and Linear Channel in which this trip originates. The noise spikes generally were created from the auto controller circuitry. The reactor was at a stable power during each of these trips. The 120% Demand rundowns occurred due to switching errors and noise spikes originating in the Linear Channel's meter switches. Operators were instructed to properly switch scales to avoid additional switching errors.

Maintenance activities are listed in Table 3-3. Table 3-4 shows reactor utilization and Table 3-5 shows other facility usage.

Table 3-2. Unscheduled Shutdowns for 2003-2004 Date Type of Shutdown/Cause and Corrective Action Taken 04/17/02 120% Demand Rundown.

Cause: Student caused rundown by downscaling the picoamp meter too soon.

Corrective Action: License operator instructed student to downscale at the proper setting. SRO on Du granted permission to restart the reactor.

04/29/0] 120% Demand Rundown.

Cause: While student up scaling to the 2 kW scale, an electrical noise spike occurred.

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

05/14/0 120% Full Power Rundown. While operating at licensed power, an electrical noise spike from auto controller caused rundown.

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

05/28/0] 120% Full Power Rundown.

Cause: While operating the reactor at 90% full power, an electrical noise spike from the auto controller caused the rundown.

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

06/05/0] 15 Second Period Rundown.

Cause: While reloading the core a fuel element was move past the Log & Linear CIC too quickly, causing a rapid period change.

Corrective Action: RO was instructed to move slowly past the Log & Linear CIC with the fuel element SRO on Duty granted permission to restart the reactor.

06/10/0 'Regulating Rod Insert Limit on Auto Rundown.

Cause: While performing a regulating rod calibration by positive period method, the RO applied an improper procedure.

Corrective action: The RO was instructed on proper procedure for conducting the regulating rod

8 calibration. SRO on Duty granted permission to restart the reactor.

08/22/0 120% Demand Rundown.

Cause: Student improperly downscaled Linear picoamp meter during power change.

Corrective action: Instructed student to properly downscale according to SOP. SRO on Duty granted permission to restart the reactor.

09/09/0 120% Demand Rundown.

Cause: SRO was instructing student about reactor operations.

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

09/18/0 120% Full Power Rundown.

Cause: Electrical noise spike in the console instrumentation.

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

09/11/0 120% Demand Rundown.

Cause: Student improperly downscaled too soon.

Corrective Action: Operator instructed student the proper down scaling procedure.

SRO on Duty granted permission to restart the reactor.

09/11/0 120% Full Power Rundown.

Cause: Rundown caused by an electrical noise spike.

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

09/11/0 120% Demand Rundown.

Cause: Student improperly changed scales.

Corrective action: Student instructed to press button in firmly. SRO on Duty granted permission to restart the reactor.

12/15/0 Manual Scram.

Cause: Routine building evacuation drill perform while reactor was operating.

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

12/17/0 120% Demand Rundown.

Cause: Operator did not completely depress picoamp meter switch before releasing.

Corrective action: Operator instructed on procedure for changing scales on the Linear picoamp meter.

SRO on Duty granted permission to restart the reactor.

02/03/0 120% Demand Rundown.

Cause: Operator was not observing the Linear recorder while changing recorder paper.

Corrective action: Operator was instructed to not change recorder paper unless at a stable power in auto-control or having someone help with observation of the control room equipment when in manual and at a stable power. SRO on Duty granted permission to restart the reactor.

02/07/0 120% Demand Rundown.

Cause: Student improperly up-scaled Linear picoamp meter.

Corrective action: SRO instructed student to properly change scales as directed in the SOPs. SRO on Duty granted permission to restart the reactor.

02/10/0 120% Demand Rundown.

Cause: Trainee was not observing Linear recorder.

Corrective action: SRO instructed trainee to watch all the console equipment including the Linear channel recorder. SRO on Duty granted permission to restart the reactor.

02/16/0 120 % Demand Rundown.

Cause: Trainee did not observe increase on Linear channel.

Corrective action: Trainee was instructed to observe this channel. SRO on Duty granted permission to restart the reactor.

03/25/0 120% Demand Rundown.

Cause: Student down-scaled instead of up-scaling during a power increase.

Corrective action: Student instructed on proper scaling procedures. SRO on Duty granted permission t restart the reactor.

9 Table 3-3. Maintenance for 2003-2004 Date Problem/Event and Action Taken 01/07/04 Problem: Therrnocouple #2 mounting screw falls into pool and lands on a fuel element.

Corrective action: Removed screw from top of fuel element with an electro magnet.

01/26/04 Problem: Beam port will not close and beam port motor is blowing fuses.

Corrective action: Beam port motor removed for repair and beam port closed manually.

05/12/03 Problem: Linear channel not responding.

Corrective action: Removed Linear CIC from the core to inspect water proof canister, cables, connectors, and the detector. Resealed canister and reinstalled CIC into the core.

Repeated this process until the CIC was working properly, which took several days. A channel check was performed before taking the reactor to power. Reactor was taken to power and the CIC reposition to read correctly compared to the Log N channel.

06/03/03 Routine annual rod visual inspection: Eight fuel elements and three magnets removed from the core. Rods -were visually inspected abnormalities and a measure of the bow in each rod was recorded. Only one rod was removed from the partially unloaded core at a time. After inspection fuel elements and magnets were reinstalled. Rod drop time tests were performed.

06/16/03 Routine semi-annual calibration started and completed on 7/22/03. Nuclear instrumentation equipment calibrated, including safety channels and thermal power calibration performed. Routine operations were scheduled during the semi-annual calibration.

11/21/03 Problem: Magnet power supply current readings were not stable.

Corrective action: Removed magnet power supply, replaced the magnet current selector switch, and reinstalled unit.

12/31/04 Routine semi-annual calibration started and completed on 2/06/04. Nuclear instrumentation equipment calibrated, including safety channels, rod drop time tests and thermal power calibration performed. Routine operations were scheduled during the semi-annual calibration.

01/09/04 Routine annual radiation monitoring systems calibration performed and completed 01/12/04.

10 Tablc 3-4. Reactor Utilization

1. Reactor use 962.03 hrs.
2. Time at power 397.033.1 hrs.
3. Energy generated 33661.6 kW/hrs
4. Total number of samples Neutron irradiated 293 Gamma Exposure 440
5. U-235 Burned 1.46609 g
6. U-235 Burned and Converted 1.7353 g Table 3-5. Experimental Facility Use Other Than The Reactor Facility Hours Bare Rabbit Tube 82.14 hr.

Cadmium Rabbit Tube 0.00 hr.

Beam Port 3.25 hr.

Other Core Positions 2873 hr.

Total 2054 hr.

4.0 EDUCATIONAL UTILIZATION The reactor facility supported several UMR courses in the past year for a total of 4,456 student-hours. The number of UMR students utilizing the facility was 1,111. This usage is a direct result of an aggressive and continuing campus wide "outreach" program. The reactor facility provided financial support for four students with hourly wages, and part to full support of Graduate Research Assistants. 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, 2004) 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 experiments that they are unable to perform with their reactor. The laboratory was held from late-afternoon to the evening (4:00 pm until 10:30 pm) and

11 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, 1,393 students and instructors from 55 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, 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 3,172 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.

12 Table 4-1. UMR Classes-at Reactor Facility 2003-2004 Reporting Pcriod WS- Winter CLASS NUMBER/TITLE # OF TIME AT STUDENT FS- Fall STUDENTS REACTOR HOURS WS 03 NE 25 8 4 32 VS 03 204 15 1 15 0S03 NE 306 9 30 270 WS03 NE 308 9 30 270 W503 NE 300 5 5 25 FS 03 Reactor Operator Trainees 16 44 704 FS 03 OURE 5 30 150 FS 03 NE 304 16 30 460 FS 03 NE 306 10 30 300 PS 03 Engineering Management Safety Class 20 1 20 FS 03 NE 490 8 30 240 FS 03 Chemistry Labs (half-life); Dr. Terry Bone 626 0.5 313 S 03 Dr Pringle Physics 107 20 1 20 FS 03 NE 25 12 5 60 WS 04 NE 204 10 4 40 WS04 NE 308 26 30 780 WS04. NE 306 8 30 240 WS 04 Dr Thompson UMC 404 14 6.5 91 4/29/03 Physics 20 1 20 WS 04 Chem Labs 212 0.5 106 WS04 NE 204 10 4 40 WS 04 NE 25 28 5 140 PS 03-04 Research Graduate Students 4 30 120 TOTALS FOR 2002-2003 1111 352.5 4456

13 Table 4-2. Reactor Sharing Program (2003-2004) l DATE PARTICIPANTS Number]

4/7/03 Dr Thomas UMC 404 10 4/8/03 St Elizabeth High School Janice Wieberg ,23 4/15/03 Thomas Jefferson High School 22 4/29/03 Potosi High School 40 5/5/03 Fort Leonard Wood Chemical School Trainees 22 6/11/03 Jackling I Session I 34 6/13/03 Jackling I Session I Blue Glow 34 6/16/03 Jackling I Session I Tour 21 6/19/03 Introduction to Engineering Camp 35 6/20/03 Introduction to Engineering Camp 37 6/20/03 Jackling I 37 6/23/03 Jackling I Session Tour 23 6/26/03 MITE Cindy Voght 35 6/27/03 Jackling I Session Blue Glow 24 7/6/03 Introduction to Engineering 44 7/7/03 Visitors from Admission Office 2 7/8/03 Mechanical & Aerospace Engineering 36 7/10/03 Introduction to Engineering Dr. Flori 130 7/11/03 Introduction to Engineering Camp Blue Glow 27 7/13/03 Introduction to Engineering 73 7/21/03 Nuclear Engineering Camp Session I 21 7/23/03 Nuclear Engineering Camp Session 1 24 7/24/03 Nuclear Engineering Night Group 4 7/25/03 Nuclear Engineering Camp Blue Glow 23 7/26/03 Reactor Operators Workshop Camp 7-26-31-04 4 7/28/03 Nuclear Engineering Camp Session II 54 7/30/03 Nuclear Engineering Camp Session II 54 8/2/03 Reactor Operators Workshop Camp 8-2-7-03 4 9/19/03 Freshmen ANS Blue Glow 176 10/21/03 East Central College 13 11/11/03 Newburg High School 28 11/13/03 Parkway West High School 20 11/25/03 Rolla High School 60 2/21/04 Admission Pro Session 25 2/21/04 Boy Scouts 37

14 Table 4-2. Reactor Sharing Program (2003-2004) (continued)

DATE PARTICIPANTS Number 3/1/04 Dr. Thompson UMC 404 14 3/3/04 Kabool High School 11 3/5/04 Hazelwood High School 50 3/6/04 PRO Session 27 3/22/04 Fort Leonward Wood Chemical School Trainees 16 3/25/04 St. Elizebeth High School 19 2003 Keong Kam, Overland Park KS, Gamma Exposure to Zenner diodes. High 1 2003 Matt Krantz, Loudon Tn. Gamma exposeure to TTL Logic chips 1 2003 Matt McCreary, Arnold Mo. Gamma exposeure to TTL Logic 1 4/18/03 Spring Open House 18 9/23/03 SOMM Open House 26 Total 2003-2004 1440

15 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 Survevs 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 Survevs There was one shipment of by-product material released off-campus from the reactor facility on 2/20/04 consisting of 30 Microcuries of Co-60. There were no by product material shipments released on-campus.

5.3. Routine Monitorini Sixty-one reactor facility personnel and students involved with the operations in the reactor facility are currently assigned Luxel, optically stimulated luminescence (OSL) dosimeters.

Four (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 read monthly. The remaining dosimeters detect beta and gamma' radiation only and are read monthly.

There are 23 area dosimeters assigned on campus for beta and gamma monitoring and one for beta, gamma, and neutron monitoring. In addition, 5 digital, direct-reading dosimeters, 5 chirpers and 2 pocket ion chamber 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 nor significant exposure.

Airborne activity in the reactor bay is monitored by a fixed-filter, particulate continuous

16 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 2003 through March 2004 sample concentrations averaged 1.866x10-5 ptCi/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 81,270.38 Microucuries of Ar-41 were released into the air.

5.4. Waste 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 were two waste barrels transferred from the Reactor Facility to the Dangerous Materials Storage Facility (DMSF) on campus. The first barrel contained 13 pounds of pool filters and was moved from the reactor to the DMSF on 8/7//2003. The barrel had activity of 0.112 Microcuries. The second barrel consisted of 70 pounds of solid (i.e. gloves, paper towels, and plastic bags). This barrel was moved from the reactor to the DMSF on 7/22/2003. The barrel had no detectable activity.

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

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

6.1 Administrative Changes

17 UMRR is presently fully staffed. No changes in personnel occurred during this reporting period.

6.2. Relicensing Relicensing activities will continue during the upcoming reporting period. Our present license is valid until January, 2005. The required materials including SAR, technical specifications, emergency plan, operator requalification plan, and environmental report will be submitted to NRC this year, 2004, to initiate the process of renewing the UMRR license.

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 console upgrade is continuing. Several pieces of new equipment have been installed under the provisions of 10 CFR Part 50.59. New Safety Channels and a magnet power supply were installed in Spring of 2002. The Linear drawer may be replaced during the upcoming reporting period. UMRR is taking an aggressive role in partnering with security companies to test security equipment within our facility. We have successfully tested and acquired a facial recognition system that allows only authorized personnel into the reactor bay. Another company is testing several biometric access devices that will be installed this year, 2004. These devices will require fingerprints-and PIN cards to access our vital areas. Most of the changes will be made under the provisions of 50.59; however, some changes may require NRC approval.

6.5 Reactor Operator Training The results of the second annual group of reactor operator trainees, which took the NRC examination during the week of March 10, 2003, were release to UMRR in April 2003. Six

18 trainees were licensed as reactor operators (ROs) with an additional three ROs upgraded to senior reactor operators (SROs). Five trainees did not pass the NRC operators examination March, 2003 and successfully retook the exam September, 2003 with an additional RO upgrading to an SRO.

The training program is progressing well with a third group of trainees schedule for the operator's examination May, 2004.

An 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 would be attending UMR and intending to 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 included UMRR's Technical Specifications, Safety Analysis Report, Emergency Plan, Standard Operating Procedures, and the 10CFR20. Students were received lectures regarding reactor theory and operated the reactor to demonstrate basic principles of the reactor theory. Presently of the eight students receiving this introductory training three are scheduled to take the NRC operators exam in May of 2004. Two Reactor Operation Workshops will be offered this summer to selected UMR Nuclear Engineering Camp attendees.

APPENDIX A.

STANDARD OPERATING PROCEDURES CHANGED DURING THE 2002-2003 REPORTING YEAR

  • UIRV* REACTOR STANDARD -OPERATING PROCEDURES ***

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Revised: September 30, 2003 Page 1 of 9 IRev A. PURPOSE:

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

B. PRECAUTIONS. PREREOUISITES. OR LIMITATIONS:

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

C. PROCEDURE Complete the checklist in accordance with the following steps:

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

Revised By: William Bonzer Approved By: Akira Tokuhiro

&Ui2K-& v l/

      • UMRREACTORSTANDARD 'OPERATINGPROCEDURES ***

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Revised: September 30, 2003 Page 2 of 9 JRev

6. RAM System Check:
a. Announce, "THE BUILDING ALARM WVILL SOUND. THIS IS A TEST.

DO NOT EVACUATE THE BUILDING."

b. Check that the setpoints and automatic functions of the RAIVI sy'stems meet the criteria listed below. For each High Radiation Alarm, verify that both the audible alarm and the visual annunciator are actuated. Reset the RMS II module within Rev.

ten seconds after trip occurs. Reset the annunciator panel after each High Radiation Alarm check.

CHANNEL l SETFOINT l AUTOMATIC ACTION

1. Bridge RAIM 10 - 18 mR/hr High Radiation Alarm
2. Bridge RAM 15 - 28 mRlhr Building Evacuation Alarm
3. Demin RAM 10--l8mR/hr HighRadiationAlarm
4. Basement RAM 10 - 18 mR/hr High Radiation Alarm
c. Announce, "TEST COMPLETE, ACKNOWLEDGE ALL FURTHER ALARMS".
7. Verify that all monitors (Bridge, Demin, Basement, and Neutron RAM) read below 2 Rev mrem/hr.
8. Beamport and Thermal Column Status: Record the status of the beamport and thermal .column ("open" or "shut") as indicated by 1) the "Beam Port or Thermal Column Open" annunciator light and 2) the Beam Port Indication light. Notify the Senior Operator on Duty if either facility is "open".
9. Linear Channel:
a. Depress the zero check button; verify that the digital display reads "0.000". Rev
b. Depress the zero check button again to release the check function. Set the Linear compensating voltage to obtain a Linear reading between 0.02 and 0.05 on the 2 Vv scale. Following a high power run, the SRO on Duty may adjust the Linear compensating voltage as appropriate.
c. Record the Linear reading. Record the scale.

Revised By: William Bonzer Approved By: Akira Tokuhiro LA- n r 7,

      • UMR REACTOR STANDARD'OPERATING PROCEDURES ***

SOP: 102 TITLE: PRE-STARTUIP CHECKIST PROCEDURE Revised: September 30, 2003 Page 3 of 9 IRev

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

Values should correspond approximately to the following:

HV -540 VDC CV - 2 to 8 VDC

11. a. Observe the temperature and CAM recorder "RCD" is illuminated in the upper left hand corner of the display.
b. Turn on and date the Startup, Linear, and Log/Period recorders. Reset the annunciator panel.
12. Core Check: Turn the pool lights on.
a. Record water level of pool.
b. Visually verify all fuel elements in the core and fuel storage rack are accounted for. Rev.
c. Visually inspect the core and pool for abnormalities. Check in-core experiments.
d. Insert the source into the core source holder.
13. Start-Up Channel Test: Turn the Log Count Rate selector switch to 102, 103, and 104.

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

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

Revised By: William Bonzer Approved By: Akira Tokuhiro 6u~b Sai, X7

UMR REACTOR STANDARD:OPERATING PROCEDURES ***

SOP: 102 TITLE: PRE-STARTUP CHIECKLIST PROCEDURE Revised: September 30, 2003 Page 4 of 9 IRev

16. Log and Power Range Test:
a. Depress and hold the 1OpA keypad switch on the Log and Linear drawer to obtain Rev.

a stable digital log power display.

b. Verify receipt of the "Non-Operative" scram and "Low CIC Voltage" rundown audible and visual alarms.
c. Verify that the digital meter and recorder read within the tolerances of the following table. The bargraph should generally follow the digital display and recorder.

Keypad Switch [ Log Scale (%) PowerRange (%) I 10pA 4.0 E 2.5 E -5 0-1%

0.luA 8.4 E 1.2 E -1 0-1%

lmA8AE 1 - 1.2E2 90 - 100%

d. Release the switch and reset the annunciator board.
e. Repeat Steps a. through d. for the 0.1 uA and 1 mA switches.
17. Period Response Test:
a. Depress and hold the 3 SEC keypad switch.
b. Verify receipt of the "Non-Operative" scram and "Low CIC Voltage" rundown audible and visual alarms.
c. Verify that the Period bargraph, digital meter, and recorder all read about 3 seconds.
d. Verify that the 30 second, 15 second, and 5 second period annunciator alarms are actuated.
e. Release the switch. Clear the annunciator panel.
18. Turn on the magnet power using the key switch. Push the Scram Reset button to energize the magnets. Reset the annunciator panel.
19. Record inlet temperature. Notify the SRO on Duty if the inlet temperature is below 600 F.
20. Record the magnet currents. (Typical readings should be between 25 and 85 mamp.)

Revised By: William Bonzer Approved By: Akira Tokuhiro DVcWrv; p.m~. G 2 /

U*IR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 102 TITLE: PRE-STARTUPCHIJECKLIST PROCEDURE Revised: September 30, 2003 Page 5 of 9 Rev

21. 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. Rev.
e. Record the trip test reading displayed on Safety-Amplifier 1.
f. Depress the reset button on Safety Amplifier 1.
g. Reset the annunciator panel and insert magnets.
h. Repeat steps a - g for Safety Amplifier 2.
22. 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.

23. 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.
c. Continue depressing the PERIOD TEST keypad switch. Verify that the 15 Second Rundown is activated with a simulated period greater than or equal to 15 seconds.
d. Continue depressing the PERIOD TEST keypad switch. Verify that the-5 Second Scram is activated with a simulated period greater than 5 seconds by observing a loss of magnet current and the annunciators.
e. Release the switch.
f. Reset the scram, rundown, and annunciator panel.

Revised By: William Bonzeur Approved By: Akira Tokuhiro

      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 102 TITLE: PRE-STARTUIPCHECKLIST PROCEDURE Revised: September 3 0, 2003 Page 6 of 9 l Rev

24. 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.
25. Push the annunciator test button and check for burned out bulbs. Replace any burned Rev.

out bulbs. Reset the annunciator panel.

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

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

Revised By: William Bonzer Approved By: Akira Tokuhiro

UMR REACTOR STANDARD'OPERATING PROCEDURES

  • SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Revised: September 30, 2003 Page 7 of 9 jRev
34. The Senior Operator on Duty will announce "The SRO on Duty is and the licensed operator in the control room is ".

Rev.

35. SRO on Duty's picture displayed in the control room.
36. The Senior Operator on Duty will initial the checklist verifying that all items have been completed and any problems identified have been satisfactorily resolved.
37. Record the date using the rubber date stamp.

Revised By: William Bonzer -Approved By: Akira Tokuhiro Is. Ail., - M) * /' fo- ,#

    • TJRREACTOR STANDARD OPERATLNG PROCEDURES **

SOP: 102 TITE: PRE-STARTUP CEECKLIST PROCEDURE Revised: September'30, 2003 Page 8 of 9 IRev

1. Date
2. Initials of the Person Perfmmng Checklist .
3. Time (Console Clock)
4. Core Loading .
5. PA., Intercom. Video Monitor On _ --
6. RAMvl System Check ._.
7. Radiation Level Normal __=_
8. Beam Port and Thenial Column Status (OPEN or SHUT) = =
9. Linear Channel Zero ._. __:__

Meter Reading . _.

Scale

10. Linear CI.C. Voltages HV (-540)

._ CV (- 2 to 8)

11. Recorders On, Dated. "RCD' Light On Temp. & CAM Recorders _ .
12. Core Check (Lights On) Water Level (inches) . ____

Elements Verified Inspect Core Source Inserted l

13. Start-Up Channel Test
14. Verify FC Response, FC Inserted. Count Rate > 2 CPS .
15. Log CountRate IV Power Supply (+400 VDC)
16. Log and Power Range Test M
17. Period Response Test
18. Mamet Power On. Scram Reset, Board Reset _
19. Inlet Temerature ('Z 1 - I_

Revised By: William Bonzer,, Approved By; Akia Tokuhiro b v ^ r?

- f*? J

      • TIVIR REACTOR STANDARD OPERATING PROCEDURES ***
  • SOP: 102 - TrILE: PRE-STARTUP CHECKLIST PROCEDURE Revised. September 30, 2003 . Page 9 of 9 1Rev
20. Magnet Cutrents (milliamps) No. 1 (A) l l No.2 (B) T =

Re' No. 3 (C) .

SafetyAmplifler 1 Trip Test Reading Raise Rds 3 in. Push Scram Test Safety Amplifei 2 'Test" Button Trip TestReading

22. Log and Linear Drawver Non-Operative Raise Rods 3 in. Press Scram Test NON-OPER switch. _
23. Period Tnip Test . . .  : l ___
24. Manual Scram Test TRai se

[Manual Rods 3 in. Push Scram

25. Annunciator Test, All Lights On
26. Magnets On, Rods onInsertLimit . _
27. Prepare Hourly and Permanent Logs
28. Detector Response Check _ _Core __ect Period Spike _

Linear Spike _

Startup Channel Response _

29. Raise Rods to 6 in., Record Tine in Both Logs _
30. Nitrogen Diffuser Status No. I (ON or OFF) No. 2
31. Intended Power Level
32. Announce Intention to Start
33. Pre-Startup Check Properly Completed (Licensed Operator's Initials) l
34. Senior Operator on Duty announcemnent's oflicensed operators
35. Senior Operator on Duty's Picture in Control Room . ._____
36. Senior Operator onDutv's Initials ;___-I I Re 37.Date Revised By: Wiliam BonzerA Akmroved By:AiaTkhr
  • .0 , t~1") v / / ,X
      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 106 TITLE: Restart Of Reactor When It Is Not Secured Revised: September 30, 2003 Page 1 of 2 A. Purpose To be used when the reactor is shutdown to zero inches, magnet current turned off, and recorders turned off but not secured. A restart may be initiated without an additional Pre-Startup Checklist being completed.

B. Precautions. Prerequisites. Limitations This procedure can only be used during the same day of the last completed Pre-Startup Checklist.

Verify that the daily Pre-Startup Checklist has been completed.

The SRO on Duty shall verify maintenance has not been performed on the control room equipment or the reactor core structure since the reactor has been shutdown to zero inches. If maintenance has been performed, the SRO on Duty shall determine if the reactor is operable by performing a channel test, Pre-Startup Checklist, or independent test to verify the repaired equipment is operable.

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

1) Verify that a secure checklist has not been completed.
2) Record the time and intended power level ( 2 W - 100 KW) in the permanent logbook.
3) Insert the source and inspect the core.
4) Make certain picoammeter is on the 2 watt scale.
5) Adjust the compensating voltage of the linear channel to read between 0.02 and 0.05 on the picoammeter.
6) Verify that all rods or at insert limits.
7) Turn recorders on and verify that RCD: is illuminated on the temperature and constant air monitor recorders and that both systems are on.

Revised by: William Bonzer A Approved By-. Aldra Tokuhiro I'd *fI Ag t.Y v

  • $** UMR REACTOR STANDARD1:OPERATING PROCEDURES ***

SOP: 106 TITLE: Restart Of Reactor When It Is Not Secured Revised: September 30, 2003 - Page 2 of 2

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

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

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

Revised By: William Bonzer Approved By: Akira Tokuhiro bii'-41t A.. , 4 y

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.
20. Check Magnet- Currents for approximately the same values observed (and recorded) during the startup checklist (SOP 102).
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 on the Pool Water Temperature Recorder.
25. Verification SRO on Duty is aware of his or her status as SRO on Duty. Rev
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 1Z-1-i-fi? 11G

      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 107 TITLE: PERIANENT LOG, HOURLY LOG AND OPERATIONAL DATA Revised: September 30,2003 Page 6 of 6 Date -_._-_.

(Start a new form each day) HOURLY OPERATING LOG Signatures: (1) (4) l Re (Including Licensed (2) (5) ()

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

(10)_ _ (1)_ (12)

\. _, .

1. Time at Power
2. Initials - Person at Console _ j
3. Nominal Power (W or kW) I .
4. Linear Recorder (%) _
5. Linear Scale (W or kW) _
6. Auto Set/Board Reset ( Y or N) . -
7. Log Level (%) {I.
8. Period Trace Normal (0)
9. Log and Linear Power Range (%)
10. Log Count Rate Recorder (cps) .i
11. Source Removed? (YorN)
12. Diffuser(s) On? (Y or N)
13. ExhaustFan On? (YorN)
14. Shim RodNo. 1 (inches)
15. Shim Rod No.2 (inches)
16. Shim Rod No.3 (inches)
17. Regulating Rod (inches)
18. Radiation Levels Normal(f)
19. Bridge Monitor (mr/hr)
20. Magnet Currents Normal({) __l_
21. Power Chamber No. 1(%)
22. Power Chamber No. 2 (%) _
23. Permanent Log Entries (1)
24. Core Inlet Water Temp. (OF) I . I 1 111
25. SRO onDuty Verification (1F) I I I . I Il
26. SRO onDuty Initials I I I I
27. Licensed Operator Initials
  • l Revised By: William Bonzer lir Tokhi0 ovedBy:
      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Revised: November 21, 2003 Page 7 of 7 UMR REACTOR EMERGENCY PHONE LIST Reactor Staff Cell Pager HOME WORK Brian Porter, Sr. Electronics Tech. RO 368-3090 341-4291 William Bonzer, Manager, SRO 578-9463 368-3727 341-4384 Akira Tokuhiro, Director, SRO 578-0542 368-7121 341-4746 Daniel Estel, SRO (573) 435-6328 341-4291 Ray Bono, Radiation Safety Officer 428-6469 364-5728 341-4240.43015.4403 Maireein -Ttenrv- Sr. Sec. 364-7272 341-4236 Universitv Administrative Staff

1. Director, UMR Police, William Bleckman 364-1294 341-4345
2. Chancellor, Gary Thomas 308-8240 368-3552 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, Dwight

Deardeuff,

MD 364-0809 3414284

6. Interim Dean, School of Mines and Metallurgy, I Rev.

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 Emergencv 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 Enidemioloav (573)751-6160 (573) 751-4674 (24firs)

Federal Agencies NRC, Operations Center (301) 816-5100 NRC Dutv 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) 561-3433 Radiation Emergencv Assistance Center (423) 576-3131 (865) 576-1005 (24hrs)

Revised By: William Bonzer Approved By: Akira Tokuhiro

      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Revised: May 13, 2003 Page 7 of 7 UMR REACTOR EMERGENCY PHONE LIST Reactor Staff Cell Pazer HOME WORK Brian Porter, Sr.;Electronics Tech. 368-3090 341-4291 William Bonzer, Manager, SRO 578-9463 368-3727 341-4384 Akira Tokuhiro, Director, SRO 578-0542 368-7121 341-4746 Daniel Estel, RO (573) 435-6328 341-4291 Ray Bono, Radiation Safety Officer 428-6469 364-5728 341-4240,T305.4403 Jim Jackson, SRO (573) 699-4897 341-4258 Rev.

Maureen Henrv. Sr. Sec. 364-7272 341-4236 Universitv Administrative Staff

1. Director, UMR Police, William Bleckman 364-1294 341-4345
2. Chancellor, Gary Thomas 308-8240 368-3552 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, Dwight

Deardeuff,

MD 364-0809 341-4284 I

6. Dean, School of Mines and Metallurgy, i

Lee W. Saperstein 578-0602 368-3782 341-4153

7. RadintinnqafetvOfflcer Rav Bonn 42R-6469 364-572R 341-424043054403 1;}'.

Local UMR University Police 341-4300 l Rev.

Rolla City Police 9-911 Rolla Fire Department 9-911 Phelps County Hospital 9-911 Rolla Pmereencv 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 V11 M~cniriRlr JlaUUll DUIzLaU n-fil USL

-vinn--fl

..... II-d- tL ni~mn1o

.l... U-

%SI Y

{IC7RINIM1

.J/J

_K1J KA

.P*U I

{ARM7%\;7A1-jK7j 1-'JI IJX

.S UI

(')Al,-

Ut 1 1b Federal A2encies NRC, Operations Center (301) 816-5100 Rev.

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 l Other American Nuclear Insurers (860) 561-3433 Radiation Emergencv Assistance Center (423) 576-3131 (865) 576-1005 (24hrs)

Revised By: William Bonzer Approved By: Akira Tokuhiro

APPENDIX B.

REVISED SAR CHANGED DURING THE 2002-2003 REPORTING YEAR

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