ML101520236

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Annual Report for 2009 - 2010 for Missouri University of Science and Technology Reactor
ML101520236
Person / Time
Site: University of Missouri-Rolla
Issue date: 05/27/2010
From: Bonzer W
Univ of Missouri
To:
Document Control Desk, Office of Nuclear Reactor Regulation
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MISSOURI MISSOURI UNIVERSITY OF SCIENCE AND TECHNOLOGY Formeriy University of fvlssouri.Ro/a/

US Nuclear Regulatory Commission Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 May 27, 2010 NRC:

Enclosed is the annual report for the Missouri University of Science and Technology Reactor Facility, license R-79, docket 50-123.

William Bonzer Reactor Manager Missouri Science and Technology University Nuclear Reactor Facility 250 W 13" St Rolla, Mo 65409-0630 webonzergmst.edu 409C)

PROGRESS REPORT 2009-2010 MISSOURI UNIVERSITY OF SCIENCE AND TECHNOLOGY REACTOR I

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

NUCLEAR REACTOR FACILITY April 1, 2009 to March 31, 2010 Submitted to The United States Nuclear Regulatory Commission And Missouri University of Science and Technology

ii Table of Contents

SUMMARY

1.0 INTRODUCTION

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

1.1 BACKGROUND

INFORM ATION ..............................................................................................................

1.2 GENERAL FACILITY STATUS ..................................................................................................... 2 2.0 REACTOR STAFF AND PERSONNEL ...................................................................................................... 3 2.1 R EA C T O R STA FF ...................................................................................................................................... 3 2.2 LICENSED O PER ATO RS .......................................................................................................................... 4 2.3 RADIATION SAFETY COMMITTEE 4................................

2.4 H EA LTH PH Y SICS ..................................................................................................................................... 5 3.0 REACTOR OPERA TIO NS ................................................................................................................................ 6 4.0 EDUCATIONAL UTILIZATION .................................................................................................................... 10 5.0 REACTOR HEALTH PHYSICS ACTIVITIES .......................................................................................... 14 5.1 ROUTINE SURVEY 5.2 BY-PRODUCT MATERIAL RELEASE SURVEYS 5.3 ROUTINE MONITORING 5.4 ENVIRONMENTAL MONITORING ................................................................................................ 15 5.5 WASTE DISPOSAL 6.0 PL A N S ................................................................................................................................................................. 16 6.1 LABORATORY INSTRUMENTATION UPGRADE 6.2 REMOTE ANALYSIS 6.3 REACTOR OPERATOR TRAINING ................................................................................ 17 APPENDIX A: STANDARD OPERATING PROCEDURES CHANGED DURING THE 2009-2010 R EPO R T IN G Y EA R ............................................................................................................................................ 18 LIST OF TABLES TABLE 3-1. CORE 101W TECHNICAL DATA ................................................................................................. 6 TABLE 3-2. UNSCHEDULED SHUTDOWNS FOR 2009-2010 ........................................................................ 7 TABLE 3-4. REACTOR UTILIZATION ........................................................................................................ 9 TABLE 3-4. REACTOR UTILIZATION ........................................................................................................ 9 TABLE 3-5. EXPERIMENTAL FACILITY USAGE ....................................................................................... 10 TABLE 4.1. MISSOURI S&T CLASSES AT REACTOR FACILITY ............................................................... 11 TABLE 4.2. REACTOR SHARING PROGRAM 2009-2010 (REPORTING PERIOD) ............................... 12 LIST OF FIGURES FIGURE 3-1. MSTR CORE 101W CONFIGURATION .........................................................................................

SUMMARY

During the 2009-2010, reporting period the Missouri University of Science and Technology Reactor (MSTR) was in use for 725.82 hours9.490741e-4 days <br />0.0228 hours <br />1.35582e-4 weeks <br />3.1201e-5 months <br />. The major part of this time, about 95%, was used for class instruction, research, and training purposes.

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

The reactor facility supported several Missouri S&T courses over the year for 8,341 student-hours. About 4,439 visitors visited the reactor during the past year. There were 901 participants, mostly high school students, in the U.S. Department of Energy Reactor Sharing Program.

The reactor produced 19,273.17 kilowatt-hours of thermal energy using approximately 0.7853 grams of uranium. A total of 373 samples were neutron irradiated in the reactor with the majority being analyzed in the Reactor Counting Laboratory.

I

1.0 INTRODUCTION

This progress report covers activities at the Missouri University of Science and Technology Reactor Facility for the period April 1, 2009 to March 31, 2010 The reactor operates as a University facility. It is available to the faculty and students from the various departments of the University for their educational and research programs. Several other college and pre-college institutions also make use of the facility. The reactor is also available for the training of personnel from commercial concerns with legitimate interest in our facility use.

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

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

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

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

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

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

The application and supporting documentation to renew the MSTR license was submitted to NRC August 30, 2004 and announced in the Federal Register on November 29, 2004 under title, Notice of License Renewal Application for Facility Operating License, University of Missouri -

Rolla (Volume 69, Number 228; Page: 69418-69419). March 30, 2009 the NRC issued the renewed Facility Operating License No. R-79 for the MSTR.

An independent auditor from the University of Columbia audited the reactor facility on December 15, 2009. There were no significant areas of concern. There is an agreement between the MSTR and the University of Missouri-Columbia to audit each other. This has been a very beneficial arrangement for both facilities involved.

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

1. Basic Engineering 50, 'Engineering Mechanics - Statics'
2. Chemistry 2, 'General Chemistry Laboratory'
3. Chemistry 8, 'Qualitative Analysis Laboratory'
4. Chemistry 355, 'Instrumental Methods Laboratory'
5. Civil Engineering 310, 'Senior Design Class'
6. Engineering Management 386, 'Safety Engineering Management'
7. Mechanical Engineering 229, 'Energy Conversion'
8. Life Sciences 352, 'Biological Effects of Radiation'
9. Physics 4 & 5, 'Concepts in Physics'
10. Physics 7, 'Environnemental Physics'

3

11. Physics 107, 'Modern Physics'
12. Physics 207, 'Modem Physics II'
13. Physics 322, 'Advanced Physics' SOPs were revised, over the past year in order to improve and keep current the operations and efficiency of the MSTR. The following is a list of SOPs revised during the reporting period:
1. SOP 100 PREAMBLE 2 SOP 101 GENERAL OPERATIONAL PROCEDURES
3. SOP 501 EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION 4 SOP 103 REACTOR STARTUP TO LOW POWER
5. SOP 501 EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Note: The above listed SOP revisions are provided in Appendix A.

2.0 REACTOR STAFF AND PERSONNEL 2.1 Reactor Staff Name Title Dr. Arvind Kumar Reactor Director Mr. William Bonzer Reactor Manager & Senior Operator Ms. Maureen Henry Senior Secretary 1

Mr. Brian Porter Senior Electronics Technician & Senior Operator Mr. Craig Reisner Senior Lab Mechanic & Senior Operator

1. Termination Date 3/15, 2010

4 2.2 Licensed Operators Name License

1. William Bonzer Senior Operator
2. Michelle Bresnahan Senior Operator
3. Zak Kulage Senior Operator 4 Victor Smith' Senior Operator 5 Brian Porter Senior Operator
6. Mackenzie Sweeney' Senior Operator
7. Andrea Mayor Reactor Operator
8. Chad Lisle' Reactor Operator 3
9. Craig Reisner Senior Operator 2
10. Jeffery Whited Reactor Operator 2
11. Josh McDowell Reactor Operator
1. Termination date 6/8/2009
2. Effective date 11/24/2009
3. Effective date 3/16/2010 2.3 Radiation Safety Committee The Radiation Safety Committee meets quarterly. The committee met on 6/10/2009, 9/23/2009, 12/9/2009 and 3/17/2010 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
3. Mr. William Bonzer Nuclear Reactor

5

4. Mr. Randy Stoll Business Services
5. Dr. Robert Dubois' Physics
6. Dr. David Wronkiewicz Geological Sciences & Engineering
7. Dr. Shoaib Usman Mining & Nuclear Engineering
8. Ms. Michelle Bresnahan Environmental Health and Safety
9. Dr. Robert Aronstam Biological Sciences
10. Dr. Charles Chusuei Chemistry 2
11. Dr. Allan Pringle Physics 3
12. Dr. Carlos Castano Mining & Nuclear Engineering 4
13. Dr. Jeffrey King Mining & Nuclear Engineering I On sabbatical 9/1/2009 - 9/1/2010 2 Interim for Dr. Robert Dubois 3 New member 7/6/2009 4 Left the University 9/1/2009.

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

Name Title I. Mr. Ray Bono Director of Environmental Health and Safety

2. Mr. Brian Smith Industrial Hygienist
3. Ms. Michelle Bresnahan Health Physicist
4. Ms. Sonya Rhine' Health Physics Technician (part time)
5. Ms. Thea Tadlock Health Physics Technician (part time) 2
6. Ms. Stacy Nowak Health Physics Technician (part time) 1 Left on 9/1/2009 2 Started on 3/1/2010

6 3.0 REACTOR OPERATIONS Core Confirmation 118W 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 118W. The excess reactivity, shutdown margin, and rod worth's were measured in cold, clean conditions.

Table 3-1. Core 118W Technical Data Parameter [ Value Rod 1 2.252 %Ak/k Rod 2 2.173 %Ak/k Rod 3 3.318 %Ak/k Reg Rod 0.371 %Ak/k Excess Reactivity 0.374 %Ak/k Shutdown Margin* 4.051 %Ak/k

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

A KEY TO PREVIXES B S C F-8 F-4 C-4 F-Standard Elements C- Control Elements D F-13 C-1 F-3 F-2 F-12 F-15 HF- Half Element BR- Bare Rabbit E F-10 C-2 F-I C-3 F-9 F-14 HF-1 CR-Cadmium Rabbit S- Source Holder F CR F-5 F-6 F-7 BR

7 Table 3-2:Unscheduled Shutdowns for 2009-2010 DateType of Rundown/Cause and Corrective Action Taken RUNDOWNS Date Type of Rundown/Cause and Corrective Action Taken 4/28/09 120% Demand Rundown Cause: Student operator failed to firmly depress a range button.

Corrective Action: Student operator was instructed to firmly depress range buttons.

SRO on Duty granted permission to restart reactor.

10/2/09 120% Demand Rundown.

Cause: Noise spike from compensated voltage adjustment pot.

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

10/6/09 120% Demand Rundown.

Cause: Noise spike from the Linear Channel's picoampmeter while downscaling meter.

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

10/14/09 120% Demand Rundown.

Cause: Noise spike from the Linear Channel's picoampmeter.

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

2/9/10 Reg. Rod on Insert Limit in Auto-Control.

Cause: Operator had not observed the reg rod inserting to zero inches while in auto-control.

Corrective Action: Operator instructed by SRO on Duty to observe reg rod height and all other equipment. SRO on Duty granted permission to restart reactor.

UNPLANNED SHUTDOWNS Date Type of Unplanned Shutdown, Cause and Corrective Action Taken 6/2/09 Unplanned Shutdown.

Cause: AC power flicker.

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

6/12/09 Unplanned Shutdown.

8 Cause: AC power flicker.

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

7/9/09 Unplanned Shutdown.

Cause: Noise spike in AC power.

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

10/1/09 Unplanned Shutdown.

Cause: AC power flicker.

Corrective Action: None taken. SRO on Duty granted permission to restart 2/4/10 Unplanned Shutdown.

Cause: Rod drive #1 brake band failed Corrective Action: Replaced brake band on rod drive '#1. SRO on Duty granted permission to restart reactor.

2/17/10 Unplanned Shutdown.

Cause: Rod #3 dropped during a power change.

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

2/18/10 Unplanned Shutdown.

Cause: Rod #3 dropped during the pre-startup checklist.

Corrective Action: Magnet #3 removed from the core and replaced with the spare magnet. Rod drop time test completed on rod #3. SRO on Duty granted permission to restart reactor.

Table 3-3: Maintenance for 2009-2010 Date Type of Maintenance 5/12/09 Issue: Rod drive #3 not letting the magnet lower.

Action Taken: Replaced the braking solenoid.

5/29/09 Issue: Auto-controller not staying in auto-control.

Action Taken: Cleaned terminals on auto-controller.

6/1/09 Issue: Acknowledge switch not functioning properly.

Action Taken: Cleaned acknowledge switch.

9 7/23/09 Issue: Gamma RAM calibration.

Action Taken: Completed annual gamma RAM calibration.

8/3/09 Issue: Annual control rod visuals Action Taken: Unloaded more than 50% critical mass of the core. Removed, inspected and reinstalled rods #1, #2, and #3 one at a time. Reloaded core and performed rod drop time tests.

8/13/09 Issue: Neutron RAM calibration.

Action Taken: Completed annual neutron RAM calibration.

9/4/09 Issue: Sump pump in lower level basement not working.

Action Taken: Repaired basement sump pump.

12/17/09 Issue: Annual calibration on control room equipment started.

Action Taken: Started routine calibration on control room equipment.

12/17/09 Issue: Rod drive #3 stop turning to withdraw or insert magnet.

Action Taken: Remove rod drive from the bridge, replaced one gear and several bearings. Reinstalled rod drive and conducted rod drop time test for #3 control rod.

Table 3-4. Reactor Utilization

1. Reactor use 725.82 hrs
2. Time at power 363.92hrs
3. Energy generated 19,273.17 kW/hrs
4. Total number of samples, neutron irradiated 373
5. U-235 Burned 0.7853 g
6. U-235 Burned and Converted 0.9274 g

10 Table 3-5. Experimental Facility Usage Facility Hours Bare Rabbit Tube 13.13 hr Cadmium Rabbit Tube 0.24 hr Beam Port 26.72 hr Thermal Column 0.0 hr Other Core Positions 4.63 hr Gamma Exposures 977.19 hr Total 1021.91 hr 4.0 EDUCATIONAL UTILIZATION The reactor facility supported several Missouri University of Science and Technology (Missouri S&T) courses in the past year for a total of 8,341.5 student hours. The number of Missouri S&T students utilizing the facility was 1,298 This usage is a direct result of an aggressive and continuing campus wide "outreach" program. The reactor facility provided financial support for three students with hourly wages. Additionally, students from several universities, colleges and high schools have used the facility.

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

The University of Missouri-Columbia Nuclear Engineering Department again sent its NE 404 class, "Advanced Reactor Laboratory," to our facility for a total of 5.5 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 MSTR staff and student-licensed operators conducted the laboratory.

The Reactor Sharing Program, previously funded by the U.S. Department of Energy, was established for colleges, universities, and high schools that do not have a nuclear reactor. This past year, 600 students and instructors from 96 institutions participated in the program. Table 4-2 lists

11 those schools and groups that were involved in this year's Reactor Sharing Program. The majority of participants were high school students. MSTR coordinates with the Missouri S&T Admissions Office to schedule high school students to see other items of interest at Missouri S&T after they have visited the reactor facility. The students visited the Missouri S&T Chapter of American Nuclear Society, the Computer Integrated Manufacturing Lab, the Foundry, Ceramics Engineering, Mineral Museum, Computer Center, Experimental Mine, Solar Car, Electron Microscope, and Stonehenge. The Reactor Sharing Program serves as a strong campus-wide recruiting tool by attracting high school students to the university and hopefully sparking some interest in nuclear engineering, science, and technology.

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

Over 4,439 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.

Table 4-1. Missouri S&T Classes at Reactor Facility 2009-2010 Reporting Period Semester CLASS NUMBER/TITLE # OF TIME AT STUDENT STUDENTS REACTOR HOURS WS 09 NE 25 Nuclear Technology Applications 26 8.0 208 WS 09 ,NE 206 Reactor Operations I 27 1.5 364 WS 09 NE 308 Reactor Laboratory II 27 6 486 WS 09 NE 312 Gamma Lab & Neutron Lab 27 4 180 FS 09 NE 25 Nuclear Technology Applications 28 8 224 FS 09 NE 206 Reactor Operations I 8 24 192 FS 09 NE 105 28 2 30 FS 09 NE 304 Reactor Laboratory I 27 6 2880 FS 09 Chemistry Half Life Labs 768 0.5 384 WS 10 NE 312 Gamma Lab & Neutron Lab 30 4 121 WS 10 Chemistry Half Life Labs 207 0.5 104 WS 10 NE 206 Reactor Operations I 25 1.5 450 WS 10 NE 308 Reactor Laboratory II 27 1.5 1080 WS 10 NE 25 Nuclear Technology Applications 20 4 80 WS 10 UMC NE 404 Lab. 9 5.5 49.5 2009-2010 Reactor Training 8 175 1400

12 2009-2010 David Gallego - Graduate Project 1 30 30 2009-2010 Zach Kullage - Graduate Project 1 16 16 2009-2010 Amol Patil - Graduate Project 1 25 25 2009-2010 Warren Vaz - Graduate Project 1 8 8 2009-2010 Hiral Patel - Graduate Project 1 10 10 2009-2010 Edwin Grant - Graduate Project 1 20 20 Total 1298 361 8,341.5 Table 4-2 Reactor Sharing Program 2009-2010 (Reporting Period)

Date Participants Number Hours 4/2009 Individual tours for April 26 5 4/3/09 Fly In Tour 23 1 4/9/09 Mansfield High School 41 2 5/2009 Individual tours for May 5 4 5/21/09 Chemical Engineering Fort Leonard Wood School 23 1.5 5/26/09 2 nd Aero Space Manufacturing Conference 96 3.5 6/2009 Individual tours of June 12 4 6/2/09 Golden Alumni 22 .5 6/4/09 Minority Introduction to Engineering 14 1.5 6/4/09 Minority Introduction to Engineering 15 1.5 6/11/09 NE Department visitors 7 .5 6/12/09 NE Department visitors 4 .5 6/19/09 Vienna High School 17 1.5 7/7/09 Jackling Camp 10 1.5 7/9/09 Jackling Camp 9 1.5 7/2009 Individual Tours of July 9 2.0 7/13/09 Nuclear Engineering Camp tour 14 1 7/13/09 Nuclear Engineering Camp Tour 11 1 7/30/09 Chemical Engineering Fort Leonard Wood School 21 1.5

13 8/09 Individual Tours August 13 6 9/09 Individual Tours September 9 4 9/17/09 Leadership in Missouri Tour 36 1.5 10/7/09 Department of Energy 4 .5 10/8/09 Visitors 5 1.0 10/23/09 Alumni Visitors 13 1.0 11/10/09 East Central College 17 1.5 11/16/09 St Elizabeth High School 18 1.5 12/10/09 Ash Grove High School 19 1.5 1/25/10 Visitors January 4 1.0 2/3/10 Prospective student tour 1 .5 2/12/10 Atlanta University Center for Degree Program 40 1.0 2/15/10 American Nuclear Society Visitors 8 .5 3/11/10 Chemical Engineering Fort Leonard Wood School 22 1.5 3/12/10 Transfer Student Tour 12 .5 Total 600 59

14 5.0. REACTOR HEALTH PHYSICS ACTIVITIES The health physics activities at the Missouri S&T Reactor facility consist primarily of radiation and contamination surveys, monitoring of personnel exposures, airborne activity, pool water activity, and waste disposal. Releases of all by-product material to authorized, licensed recipients are surveyed and recorded. In addition, health physics activities include calibrations of portable and stationary radiation detection instruments, personnel training, special surveys and monitoring of non-routine procedures.

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

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

5.3. Routine Monitoring Eighty reactor facility personnel and students involved with the operations in the reactor facility are currently assigned Luxel, Optically Stimulated Luminescence (OSL) dosimeters. Two of the Reactor Staff have beta, gamma, neutron dosimeters which are read twice monthly. There are four area beta, gamma, neutron dosimeters and one TLD ring dosimeter, which are also read twice monthly. There are also four other beta, gamma, neutron dosimeters used by the health physics personnel and three other area beta, gamma, neutron dosimeters that are read monthly.

The remaining dosimeters detect beta and gamma radiation only and are read monthly. There are fourteen area dosimeters assigned on campus for beta and gamma monitoring and one for beta, gamma, and neutron monitoring. In addition, six digital, direct-reading dosimeters and three chirper dosimeters are used for visitors and high radiation work. There have been no significant

15 personnel exposures during this reporting period. Visitors are monitored with direct reading dosimeters. No visitors received any reportable or significant exposure.

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

Pool water activity is monitored monthly to ensure that no. gross pool contamination or fuel cladding rupture has occurred. Gross counts and spectra of long-lived gamma activity are com-pared to previous monthly counts. From April 2009 through March 2010 sample concentrations averaged 1.774x10- 4 ýtCi/ml. The increase in pool water activity can be attributed to the increase in reactor operations combined with use of a more efficient High Purity Germanium Detector (HPGe) system for counting.

Release of gaseous Ar-41 activity through the building exhausts is determined by relating the operating times of the exhaust fans and reactor power during fan operation to previously measured air activity at maximum reactor power. During this period, an estimated 59,189.97 VCi of Ar-41 was released into the air.

5.4. Environmental Monitoring There are three environmental dosimeters (InLight EX9 dosimeters supplied by Landauer INC.) in place around the reactor building in order to monitor the environment for radiation exposure resulting from activities taking place at the reactor. These badges are read quarterly. All exposures were within specified limits between April 2009 and March 2010.

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

16 5.6. Instrument Calibrations During this period, portable instruments and area monitors were calibrated annually.

6.0 PLANS The reactor staff will be involved in several major projects during the next reporting period; 1) modifying the beam port room laboratory equipment, 2) conducting remote analysis of neutron irradiated samples, and 3) continuation of the reactor operator training program.

6.1 Laboratory Instrumentation Upgrade The beam port room will be modified during this reporting period.

A vibration free table has been installed to support sample imaging with digital radiography equipment. A larger imager and a higher quality camera will be purchased to improve the radiography images. Another robotic device will be installed to enhance positioning of samples while in the beam of neutrons. A core reconfiguration may be conducted this summer to increase the neutron flux at the beam port for the radiography equipment and other research projects. i Two heavily shielded cells and glove box have been installed in the beam port room to hold neutron irradiated samples that require additional shielding. A pneumatic transfer system (rabbit system) has been installed near the reactor core to transfer samples to the cells. The rabbit system and cells will be made an operable system this summer.

6.2 Remote analysis of laboratory samples The two heavily shielded cells located in the beam port room will be used to analyze samples. One of the cells holds eleven samples and is capable of transferring any one of the samples to the other cell for detector analysis. A variety of detectors will be available for the type of analysis desired. A web-based system will be used for researchers to move samples from one

17 cell to the other and conduct detector analysis of the sample. The researchers will use the web to perform the analysis of the irradiated samples that are located in the two cells. This will provide remote access to the cells.

6.3 Reactor Operator Training One Missouri S&T Reactor staff member obtained a Senior Operator's license and two student trainees obtained an Operator's license during this reporting period. The reactor staff is limiting operator training to only students with a very strong desire to obtain the license and assist reactor staff with reactor operations. At the end of this reporting period six students were training for an operator's license.

18 APPENDIX A.

STANDARD OPERATING PROCEDURES CHANGED DURING THE 2009-2010 REPORTING YEAR

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

SOP: 100 TITLE: PREAMBLE Revised: September 10, 2009 Page I of 2 A. PURPOSE The purpose of this document is to set forth the procedures for routine and emergency operations of the Missouri University of Science and Technology Reactor (MSTR). The goal of these procedures is to assure that the MSTR will be operated safely; presenting no Rev.

hazard to the public or to the operating staff, and secondprily, that reactor equipment will be safeguarded. It is mandatory that all personnel involved with reactor operations be completely familiar with these procedures and that these procedures be followed.

B. PRECAUTIONS, PREREQUISITES, OR LIMITATIONS

1. These procedures are intended to reflect and implement Facility License Number R-79, as amended, and Title 10 of the Code of Federal Regulations.
2. Only two copies of the SOPs are to be considered controlled copies. The controlled copies shall contain all of the approved procedures and will incorporate new or revised procedures as they are approved. The controlled copies should be retained in the office reception area (Reactor Manager's Copy) and in the Control Room (Control Room Copy). All other copies of SOPs are to be considered complimentary only and shall not be used for facility evolutions.
3. The SOPs shall be reviewed annually by either the Reactor Manager, Reactor Director, or a licensed operator. Identified weaknesses, inadequacies, or recommendations for improvements should be discussed with the Reactor Manager to determine if revision to the SOPs is required.

- 4. Each SOP revision shall be listed on the revision form located in front of the Reactor Manager's Controlled Copy of the SOPs. Each licensed operator shall acknowledge-the revision by initialing the revision form prior to conducting reactor operations. Approval authority for revisions shall meet the following Rev.

requirements:

a. Changes that do not change the original intent of the procedures may be made with the approval of the Facility Director or designated alternate. Rev.
b. Substantive changes to the approved procedures shall be made only with the additional approval of the Radiation Safety Committee.

Revised By: William Bonzer Approved By: William Bonzer .-

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4V

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

SOP: 100 TITLE: PREAMBLE Reviseed: September 10, 2009 Page 2 of 2 D. Handwritten revisions to the Controlled SOPs may be made provided the following conditions are satisfied:

a) Handwritten revisions are clearly legible and neatly made in red ink in both Control SOPs.

b) Handwritten revisions are reviewed and approved by both a SRO and the Rev.

Reactor Director or designated alternate. Review and approval shall be documented by initialing and dating the revision.

c) Handwritten revisions should be listed on the revision form located in the front of the Reactor Manager's controlled copy of SOPs in red ink.

In the absence of the Reactor Director, the Reactor Manager may review and temporarily approve handwritten revisions provided the Reactor Director or designated alternate reviews the revision as soon as practical upon his return. Rev.

Revised By: William Bonzer Approved By: William Bonzer i.. 7 6':;" / - K

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

SOP: 101 TITLE: GENERAL OPERATIONAL PROCEDURES Revised: November 19, 2009 Page I of 3 A. PURPOSE:

To provide written general operational procedures for routine operations.

B. PROCEDURE

1. Reactor operations must at all times meet the requirements of the Facility License R-79, Technical Specifications, and security in accordance with the provisions of 10 CFR 73.67(f).
2. At least two persons, as per Technical Specification 6.1.3 "Staffing", shall be Rev.

present in the Reactor Building when the reactor is operating.

3. a) A licensed operator who is responsible for reactor operation shall be present in the control room at all times when the reactor is operating.

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

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

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

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

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

Revised By: William Bonzer Approved By: William Bonzer

I

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

SOP: 101 TITLE: GENERAL OPERATIONAL PROCEDURES Revised: November 19, 2009 Page 2 of 3

6. All reactor operational personnel are responsible for entering in the appropriate log book any work on or around the reactor or reactor components important enough to justify a record for future reference.
7. All personnel are responsible for notifying the SRO on Duty of any work beingi Rev.

done that could either directly or indirectly affect reactor operations.

8. Log books will be kept in the permanent log book cabinet, except the one Rev.

currently in use, which may be kept on the console. If the books are removed from the control room, permission must be granted by the Reactor Manager. Any books removed shall be returned as soon as possible.

9. Only the SRO on Duty may key bypass control channel automatic functions. The Rev use of any interlock bypass key requires a permanent log entry for insertion and removal. This log entry shall include date and time. This requirement does not apply when the reactor is shut down (e.g. performance of the Weekly Checklist procedure).
10. Any abnormal behavior or abnormal change in core reactivity associated with reactor startup or operation should be reported to the SRO on Duty immediately if Rev there is any doubt about reactor safety, the reactor shall be immediately shut down by the Operator-on-Duty. The cause should then be determined and corrective action taken.
11. The Standard Operating Procedure (SOPs) should be followed to the extent practicable, especially whenever the Pre-Startup Checklist is being completed, when the reactor is being started, or when the reactor power is being changed.
12. The SRO on Duty has the authority to instruct the reactor operator to disregard'lRev certain SOPs provided that no safety requirements are violated. (For example, SOP 305 does. not have to be performed every pre-startup checklist.)
13. All surveillance time intervals referred to in the SOPs are as defined in Section 1 of the Technical Specifications.

Revised By: William Bonzer Approved By: William Bonzer 4101

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

SOP: 101 TITLE: GENERAL OPERATIONAL PROCEDURES Revised: November 19, 2009 Page 3 of 3

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

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

SOP 655, "Radiation Area Monitor (RAM) Calibrations" SOP 800, "Semi-Annual Checklist" SOP 801, "Log N and Linear Drawer Calibration" SOP 802, "Linear Channel" Rev SOP 803, "Log Count Rate (LCR) Channel" SOP 804, "Safety Amplifier System" SOP 805, "Auto Control System" I Rev SOP 806, "Temperature Channel" SOP 809, "Relay Test" SOP 811, "Fire and Smoke Alarm System" SOP 813, "Rod Drop Time Measurement" SOP 818, "Functional Test of Building Security System"

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

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

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

SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Revised: December 10, 2009 Page 1 of 7 A. PURPOSE To provide for the safe and orderly evacuation of the Reactor Building.

B. PRECAUTIONS, PREREQUISITES, OR LIMITATIONS

1. This procedure is not intended to be all encompassing. Personnel may deviate from this procedure as needed to maintain safety. Strong reliance is placed upon the good judgement of operating personnel.
2. Any person may manually initiate the evacuation alarm if it is believed conditions merit such action.
3. The Reactor Manager, Reactor Director, or a Licensed Operator, may silence the evacuation alarm and rescind the evacuation by building announcement if it is determined that the evacuation is unwarranted.
4. Upon sounding of the Building Evacuation Alarm, all personnel except for the RO and the SRO on Duty will proceed directly and calmly to the Physics Building Rev basement area and remain in this area for further instructions.
5. Persons providing escort for visitors are responsible for the safe evacuation of their visitors to the Physics Building basement and for obtaining the Visitor's Logbook from the firont office upon exiting the facility. The escort will report the accountability status of the visitors to the SRO on Duty once in the Physics Building basement area.
6. All persons must remain calm and orderly.

C. EVACUATION PROCEDURE Upon sounding of the Evacuation Alarm:

Revised By: William Bonzer Approved By: William Bonzer

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

SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDING'EVACUATION Revised: December 10, 2009 Page 2 of 7

1. REACTOR OPERATOR The Reactor Operator will obtain the "REACTOR OPERATOR EVACUATION CHECKLIST" and follow the steps therein. If the reactor is shut down at the time of alarm, the REACTOR OPERATOR EVACUATION CHECKLIST need not be completed. Proper actions for each step in the checklist are described below:
1. SCRAM REACTOR: The operator will promptly scram the reactor.
2. VERIFY ROD INSERTION: Verify that the shim rods have inserted (audibly, visually, or by observing the magnet contact lights and magnet currents). Verify power is decreasing appropriately.
3. SECURE MAGNET KEY: Remove the key from the console and maintain possession of the key.
4. ANNOUNCE FACILITY STATUS: Announce the status of the facility over the building PA. State the cause of the alarm and areas of the building to avoid as necessary.
5. RECORD TIME: Record the console clock time.
6. WAIT IN CONTROL ROOM FOR SRO: Remain in the control room (or control room area) for the SRO on Duty, if possible. Report facility status to the SRO on Duty upon his arrival. The SRO on Duty may instruct the operator to proceed differently from the items listed in the checklist.
7. OBTAIN PERMVIANENT LOGBOOK/METERS: Obtain the console permanent logbook. Obtain survey meters and pocket dosimeters, if convenient.
8. VENT FANS OFF: Verify that all three exhaust vent fans are off.
9. OBTAIN EMERGENCY KEYS: Obtain the emergency key box. If the key box is not in its usual location, assume someone else has already obtained it.

Revised By: William Bonzer Approved By: William Bonzer A ,.'* . " - * . - '-

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

SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Revised: December 10, 2009 Page 3 of 7

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

II. SRO ON DUTY Rev The SRO on Duty will obtain the SRO EVACUATION CHECKLIST and follow the steps therein. Proper actions for each step are listed below:

1. PROCEED TO CONTROL ROOM: Proceed directly to the control room for a status report from the Reactor Operator.
2. RECEIVE OPERATOR'S REPORT: Determine the facility status from the Reactor Operator.
3. OBTAIN SURVEY INSTRUMENTS: Obtain survey instruments and dosimeters, if possible.
4. VENT FANS OFF: Verify that all three exhaust vent fans are off.
5. ALL PERSONNEL EVACUATED: Verify that all personnel have left the building.
6. EMERGENCY KEYS OBTAINED: Obtain emergency key box upon exiting the building. If the key box is not in its usual location, assume the key box has already been obtained.
7. PROCEED TO PHYSICS BUILDING BASEMENT AREA: Proceed directly to the Physics Building basement area.

III. Upon arriving at the Physics Building basement area the SRO on Duty will:

1. Account for all personnel known to have been in the facility. Record the names of each individual evacuated.
2. Receive reports from personnel on the facility status, as necessary.

Revised By: William Bonzer .- "n, Approved By: William Bonzer '-I

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MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES **

SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Revised: December 10, 2009 Page 4 of 7

3. Notify the Reactor Manager, Reactor Director, and Campus Health Physicist as appropriate. Use the Emergency Phone List as needed.
4. If personal contamination is possible, frisk each person evacuated for contamination. Isolate contaminated person(s) in the emergency shower area.
5. Evaluate the situation to determine if the potential for an emergency condition exists. Implement the following procedures as necessary:
  • SOP 502 "Emergency Procedure For An Unusual Event" SOP 503 "Emergency Procedure For An Alert" SOP 504 "Emergency Procedure For A Site Area Emergency" SOP 507 "Emergency Procedure - Administrative Responsibilities" Rev

- SOP 621 "Guidelines For Emergency Exposure"

- SOP 622 "Handling Injured In Radiation Accidents"

6. Take other actions as deemed appropriate.

D. END OF EMERGENCY, REENTRY, AND RECOVERY In the event that an emergency status is declared (i.e. Unusual Event, Alert, or Site -Area Emergency), the Reactor Director or the Reactor Manager and the Radiation Safety. Officer shall decide when the emergency no longer exists and an "end of emergency" will be declared.

2. Recovery from emergency conditions will be instituted at the highest organizational level activated during the emergency. Procedures will be written, as needed, to recover from the emergency.
3. Personnel approaching the facility for reentry will report to the Emergency Support Center if radiation levels in excess of 100 mrem/hr are encountered.

Revised By: William Bonzer Approved By: William Bonzer

  • .- 7,-

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

SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Revised: December 10, 2009 Page 5 of 7

- REACTOR OPERATOR -

EVACUATION CHECKLIST

1. SCRAM REACTOR
2. VERIFY ROD INSERTION
3. SECURE MAGNET KEY
4. ANNOUNCE FACILITY STATUS
5. RECORD TIME
6. WAIT IN CONTROL ROOM FOR SRO
7. OBTAIN PERMANENT LOGBOOKIMETERS
8. TURN VENT FANS OFF
9. OBTAIN EMERGENCY KEYS
10. PROCEED TO PHYSICS BUILDING BASEMENT AREA Revised By: William Bonzer Approved By: William Bonzer
' / . .' , * , .2 . .

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      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES
  • SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Revised: December 10, 2009 Page 6 of 7

-SRO -

EVACUATION CHECKLIST

1. IMMEDIATE ACTIONS
1. PROCEED TO CONTROL ROOM
2. RECEIVE OPERATOR'S REPORT
3. OBTAIN SURVEY INSTRUMENTS
4. VENT FANS OFF
5. ALL PERSONNEL EVACUATED
6. EMERGENCY KEYS OBTAINED
7. PROCEED TO PHYSICS BUILDING II. SUPPLEMENTAL ACTIONS
1. PERSONNEL ACCOUNTABILITY:

A. Have all Personnel Evacuated Building?

Yes No B. List names of each individual evacuated from building:

2. REFER TO SOP 501 SECTION C.111 FOR FURTHER INSTRUCTION.

Revised By: William Bonzer Approved By: William Bonzer

  • MISSOURIS&T REACTOR STANDARD OPERATING PROCEDURES
  • SOP: 501 TITLE EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Revised: December 10, 2009 Page 7 of 7 MISSOURI S&T EMERGENCY PHONE LIST Reactor Staff CELL HOME WORK Brian Porter, Sr. Electronics Tech., RO 368-3090 341-6617 William Bonzer, Manager, SRO 578-9463 368-3727 341-4384 Craig Reisner, Senior Lab Mechanic 573-729-7277 341-4291 Maureen Henry, Sr. Secretary 364-7272 341-4236 Rev University Administrative Staff Rev Director Missouri S&T Police 341-4345 John F. Carney III, Chancellor 647-9040 1-7141 341-4116 Rev Steve Mallot Vice Chancellor Admin. Services 364-7927 341-4122 Director Physical Facilities 341-4252 Jerry Thomas DO, Director Health Services - Infirmary 364-6845 341-4284 Arvind Kumar, Chair of Nuclear Engineering, Reactor Director 364-2143 341-4747 Samuel Frimpong, Chair of Mining and Nuclear 426-2338 341-7617 Michelle Bresnahan. Health Phvsicist EHS-Missouri S&T 314-239-7751 341-7014 Local Missouri S&T Police 341-4300 Rolla City Police 3-911 Rolla Fire Department 3-911 Phelps County Hospital 3-911 Rolla Emeraencv Manaaement Acencv 3-911 State Agencies Missouri Highway Patrol (573) 368-2345 Missouri State Emergency Mgt. (24 hr.) (573) 751-2748 Missouri Dept. of Natural Resources (24 hr.) (573) 634-2436 Missouri Bureau of Environmental Epidemioloc, (573) 751-6160 (573) 751-4674 (24hrs)

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

Revised By: William Bonzer Approved: William Bonzer

I

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 103 TITLE: REACTOR STARTUP TO LOW POWER Revised: December 30, 2009 Page 1 of 6 A. PURPOSE To provide a safe and consistent method for performing a reactor startup to a low power level.

B. PRECAUTIONS, PREREOUISITES, LIMITATIONS

1. Licensed operators shall have reviewed and signed for all SOP revisions prior to Rev operating the reactor.
2. The Pre-Startup Checklist shall be completed and approved by the SRO on Duty prior to commencing reactor startup.
3. The reactor will be considered "clean" if power levels within the past 52 hours6.018519e-4 days <br />0.0144 hours <br />8.597884e-5 weeks <br />1.9786e-5 months <br /> have not exceeded 20 kW-hr.
4. The reactor will be considered "hot" following a shutdown while the neutron population is still decreasing as determined by the Startup Channel count rate.
5. The reactor will be considered "high residual" when it is neither "clean" nor "hot" as defined above.
6. The licensed operator shall control all reactivity changes to the reactor by direct manipulation or by directing the manipulation of the controls and experiments being conducted at the facility.
7. The operator must be alert and attentive at all times during reactor operations. All nuclear instruments (Startup, Linear, Log, Period, Safety No. 1, Safety No. 2 and the 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 SRO on Duty shall be Rev notified and a reactor shutdown initiated as deemed necessary by the Reactor Operator.
8. The console operator should scram or shut down the reactor without hesitation if any doubt exists about reactor safety.
9. If a scram or rundown occurs permission to restart the reactor can only be authorized by the SRO on Duty. Rev Revised By: William Bonzer Approved By: William Bonzer

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  • i l
      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 103 TITLE: REACTOR STARTUP TO LOW POWER Revised: December 30, 2009 Page 2 of 6
10. The following steps will list the Shim/Safety Rods as rods and the Regulating Rod as Rev reg rod.

C. STARTUP TO LOW POWER PROCEDURE FOR A CLEAN CORE

1. Initial Reactor Status - The Pre-Startup Checklist shall be completed and approved.

The rods should be at 6 inches and the neutron source inserted into the core. Rev

2. Withdraw Rods To Shim Range:
a. Withdraw rods to a position between 12.5 and 13.0 inches. Verify that the yellow Shim Range indicator lights are illuminated.
b. Withdraw the reg rod to 15.0 inches.

Rev

c. MILESTONE - VERIFY DOUBLING: Verify that the Startup Channel count rate has approximately doubled; showing a clear increase in response to the rod withdraws. If a clear increase is not observed, the startup shall be halted and the SRO on Duty notified.
3. Withdraw Rods To 18 Inches: Rev
a. During this maneuver, limit the rate of power increase by pausing approximately 5 seconds between each rod pull. If necessary, pause longer between each pull to limit the slope on the Startup Channel recorder to 45 degrees. (This corresponds to an approximate 84 second period.)
b. Withdraw rods in one inch (or less) increments, pausing between each pull as specified above.
c. Verify that the Startup Channel responds properly to each rod pull.
d. Continue until the rods are at 18.0 inches. Rev
4. Withdraw Rods To Instrument Turnaround:
a. During this maneuver, limit the rate of power increase by pausing approximately 5 seconds between each rod pull. If necessary, pause longer between each pull to limit the slope on the Startup Channel recorder to 45 degrees. (This corresponds to Revised By: William Bonzer Approved By: William Bonzer

(/L ,7.'k A-. 1 A>

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES Rev SOP: 103 TITLE: REACTOR STARTUP.TO LOW POWER Revised: December 30, 2009 Page 3 of 6 an approximate 84 second period.)
b. Withdraw the rods in 0.25 inch (or less) increments, pausing between each pull as Rev specified above.
c. Verify that the Startup Channel responds properly to each rod pull.
d. Closely observe the Linear, Log, and Period indicators for "turnaround" (i.e. rising neutron signal indication).
e. MILESTONE - IDENTIFY "TURNAROUND": Linear, Log, and Period "turnaround" must be identified before the Startup Channel signal reaches full scale. If the Startup Channel nears the top of its scale and proper turnaround is not observed, then the power shall be leveled in the operating range of the Startup Channel and the SRO on Duty notified.
f. After positive "turnaround" is noted on each the Linear, Log, and Period indicators, the fission chamber may be withdrawn to a convenient height (normally the fission chamber should be adjusted to read approximately 100 count per second).
g. The Startup Channel signal should not be allowed to increase off scale.
5. Continue Power Increase and Level At Low Power:
a. After instrument "turnaround" has been confirmed, limit the rate of power increase to an aipproximate 50 second period as indicated by the Period indicators. The SRO Rev on Duty may authorize shorter periods.
b. Upscale the Linear Channel as necessary when it reaches approximately 60% of the selected scale. Rev
c. The neutron source should be withdrawn from the core when the Linear channel is on the 20 Watt scale.
d. Level reactor power between 2 and 20 Watts.
e. Place the reactor in autocontrol as desired.
f. RAFT (Reset, Announce, Fission Chamber, Time):

Revised By: William Bonzer Approved By: William Bonzer

.i).

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES
  • Rev SOP: 103 TITLE: REACTOR STARTUP TO LOW POWER Revised: December 30, 2009 Page 4 of 6 i) Reset the annunciator panel. Verify that the "Manual" light is off when in auto control.

ii) Announce the reactor power over the building PA.

ii) Position Fission Chamber to read midscale.

iv) Record Time at power in the permanent logbook.

g. Complete the Hourly Log sheet.
6. Refer to the appropriate SOP for further operations.

D. REACTOR RE-START WITH A HOT CORE (DECREASING SOURCE RANGE COUNT RATE FOLLOWING A SHUTDOWN)

1. Position the fission chamber low enough such that the count rate will not go below 2 cps during the startup. At the same time, try to position the detector high enough to have as much range for increasing count rates as possible.
2. Adjust the Linear compensating voltage until the signal follows the actual power decay or until the lower limit of sensitivity is reached. Make sure the Linear signal is positive.
3. Record thý intention to restart the reactor and the intended power level in the permanent logbook.
4. If the reactor is being restarted following an automatic scram or rundown or following an unanticipated shutdown, permission to restart must be granted by the SRO on Duty.
5. Withdraw Rods to Shim Range
a. Withdraw the rods to a position between 12.5 and 13.0 inches. Verify that the Re*V yellow Shim Range indicator lights are illuminate.
b. Withdraw the reg rod to 15.0 inches.

Rev

c. Readjust the fission chamber position and Linear Compensating Voltage as Revised By: William Bonzer Approved By: William Bonzer

/(- J

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES *** Rev SOP: 103 TITLE: REACTOR STARTUP TO LOW POWER Revised: December 30, 2009 Page 5 of 6 needed. Doubling in count rate need not (and most likely will not) be observed at this point.
6. Withdraw Rods To 18 Inches: Rev
a. During this maneuver, limit the rate of power increase by pausing approximately 5 seconds between each rod pull. If necessary, pause longer between each pull to limit the slope on the Startup Channel recorder to 45 degrees. (This corresponds to an approximate 84 second period.)
b. Withdraw rods in one inch (or less) increments, pausing between each pull as Rev specified above.
c. Verify that the Startup Channel responds properly to each rod pull. The rate of decrease in the count rate should slow and may turnaround and begin to rise depending on the power history.
d. Continue until the rods are at 18.0 inches. Rev
7. Withdraw Rods To Instrument Turnaround:
a. During this maneuver, limit the rate of power increase by pausing approximately 5 seconds between each rod pull. If necessary, pause longer between each pull to limit the slope on the Startup Channel recorder to 45 degrees. (This corresponds to an approximate 84 second period.)
b. Withdraw rods in 0.25 inch (or less) increments, pausing between each pull as Rev specified above.
c. Verify that the Startup Channel responds properly to each rod pull. The rate of decrease in the count rate should slow and eventually turnaround and begin to rise.
d. Closely observe the Linear, Log, and Period indicators for "turnaround" (which means a positive signal response).
e. MILESTONE - IDENTIFY "TURNAROUND": Linear, Log, and Period "turnaround" must be identified before the Startup Channel signal reaches full scale and prior to obtaining shim rod positions less than one inch below the critical rod heights before shutdown. If these conditions are not met, notify the SRO on Duty and insert rods to shim range and reposition the Revised By: William Bonzer Approved By: William Bonzer

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      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES Rev 3 SOP: 103 TITLE: REACTOR STARTUP TO LOW POWER Revised: December 30, 2009 Page 6 of 6 fission chamber and readjust the Linear compensating voltage as necessary.

Repeat Steps D.5 through D.7 as necessary to satisfy this requirement.

f. After positive "turnaround" is noted on each the Linear, Log, and Period indicators, the fission chamber may be withdrawn to a convenient height (normally the fission chamber should be adjusted to read approximately 100 count per
  • second).
0. The Startup Channel signal should not be allowed to increase off scale.

1 8.Continue Power Increase and Level At Low Power:

  • a. Complete this step as specified for a clean core.

I 9. Refer to the appropriate SOP for further operations.

E. STARTUP TO LOW POWER PROCEDURE FOR A HIGH RESIDUAL CORE

1. Perform the startup steps as prescribed for a clean core except:
  • a. pause slightly longer between rod withdrawals, 3 b. the Linear compensating voltage may be readjusted with shim rods at 6 inches, as necessary. Immediately following a high power run it may not be possible to adjust the compensating voltage as low as 0.05. In such instances, adjust the Rev 3 compensating voltage to obtain the lowest stable positive signal. The SRO on Duty is to be notified in such instances.
c. be prepared for the reactor to behave differently than usual, and
d. be prepared for the critical rod heights to be different than for a cold, clean core.

U I

I Revised By: William Bonzer Approved By: William Bonzer U, 2..!

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

SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Revised: March 12, 2010 Page 7 of 7 MISSOURI S&T EMERGENCY PHONE LIST Reactor Staff CELL HOME WORK William Bonzer, Manager, SRO 578-9463 368-3727 341-4384 1Rev Craig Reisner, Senior Lab Mechanic 573-729-7277 341-4291 Maureen Henry, Sr. Secretary 364-7272 341-4236 University Administrative Staff Director Missouri S&T Police 341-4345 John F. Carney III, Chancellor 647-9040 341-7141 341-4116 Steve Malott, Vice Chancellor Admin. Services 364-7927 341-4122 Director Physical Facilities 341-4252 Jerry Thomas DO, Director Health Services - Infirmary 364-6845 341-4284 Arvind Kumar, Chair of Nuclear Engineering, Reactor Director 364-2143 341-4747 Samuel Frimpong, Chair of Mining and Nuclear 426-2338 341-7617 Michelle Bresnahan, Health Physicist EHS-Missouri S&T 314-239-7751 341-7014 Local Missouri S&T Police 341-4300 Rolla City Police 3-911 Rolla Fire Department 3-911 Phelps County Hospital 3-911 Rolla Emergency Management Agency 3-911 State Agencies Missouri Highway Patrol (573). 368-2345 Missouri State Emergency Mgt. (24 hr.) (573) 751-2748 Missouri Dept. of Natural Resources (24 hr.) (573) 634-2436 Missouri Bureau of Environmental Epidemiology (573) 751-6160 (573) 751-4674 (24hrs)

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

Revised By: William Bonzer Approved: William, Bonzer:,,-ý

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