ML11152A048

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Submittal of Annual Progress Report 2010-2011 for the Missouri Science Technology Reactor
ML11152A048
Person / Time
Site: University of Missouri-Rolla
Issue date: 05/26/2011
From: Bonzer W
Missouri Univ of Science & Technology
To:
Office of Nuclear Reactor Regulation
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MISSOURI MISSOURI UNIVERSITY OF SCIENCE AND TECHNOLOGY Formerly University of Missouri-Rolla May 26, 2011

Dear Sir:

Please find enclosed the Annual Progress Report 2010-2011 for the Missouri Science and Technology Reactor (License R-79, Docket No: 50-123). This report is being filed under the reporting requirements of our Technical Specifications. A copy of this report is also being sent to our NRC Project Manager, Ms. Linh N. Tran.

Sincerely, Wilam Bonze William Bonzer Reactor Manager mh Enclosure cc: Linh Tran, Project Manager (NRC)

Document Control Desk (NRC) ,

American Nuclear Insurers, c/o Librarian University of Missouri-Columbia Research Reactor (MURR)

Chancellor John F. Carney III (MST)

Mr. Ray Bono, Radiation Safety Officer (MST)

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

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

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

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I PROGRESS REPORT 2010-2011 I MISSOURI UNIVERSITY OF I SCIENCE AND TECHNOLOGY 41 REACTOR I

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

NUCLEAR REACTOR FACILITY April 1, 2010 to March 31, 2011 Submitted to The United States Nuclear Regulatory Commission And Missouri University of Science and Technology

ii Table of Contents

SUMMARY

1.0 INTR O D UCTIO N ............................................................................................................................................... 1

1.1 BACKGROUND

INFORMATION ....................................................................................................................... 1 G ENERAL FACILITY STATUS ......................................................................................................................... 2 2.0 REACTO R STA FF A N D PER SO N NEL ................................................................................................... 3 2.1 REACTOR STAFF ............................................................................................................................................ 3 2.2 LICENSED O PERA TORS ................................................................................................................................. 3 2.3 RADIATION SAFETY COM M ITrEE ................................................................................................................. 4 2.4 H EALTH PHYSICS ........................................................................................................................................... 4 3.0 R EACTO R O PERATIO N S ................................................................................................................................ 5 4.0 EDU CATIO N A L U TILIZATION .................................................................................................................... 10 5.0 REACTOR HEALTH PHYSICS ACTIVITIES .............................................. 14 5.1 ROUTINE SURVEY ......................................................................................................................................... 14 5.2 BY-PRODUCT MATERIAL R ELEASE SURVEYS ........................................................................................ 14 5.3 R OUTINE M ONITORING ................................................................................................................................ 14 5.4 ENVIROM ENTAL M ONITORING ..................................................................................................................... 15 5.5 W ASTE DISPOSAL ......................................................................................................................................... 15 5.6 INSTRUM ENT CALIBRATIONS ....................................................................................................................... 15 6.0 PLANS ................................................................................................................................................................. 15 6.1 LABORATORY INSTRUM ENTATION UPGRADE ........................................................................................ 16 6.2 REM OTE ANALYSIS OF LABORATORY SAMPLES ...................................................................................... 16 6.3 R EACTOR O PERATOR TRA INING ................................................................................................................. 16 APPENDIX A: STANDARD OPERATING PROCEDURES CHANGED DURING THE 2010-2011 REPORTING YEAR LIST OF TABLES TABLE 3-1. C ORE 120W TECHNICAL DATA ............................................................................................................... 6 TABLE 3-2. UNSCHEDULED SHUTDOW NS FOR 2010-2011 ....................................................................................... 7 TABLE 3-3. MAINTENANCE FOR 2010-2011 .............................................................................................................. 8 TABLE 3-4. REACTOR UTILIZATION ........................................................................................................................... 9 TABLE 3-5. EXPERIM ENTAL FACILITY USAGE ........................................................................................................... 9 TABLE 4-1. M ISSOURI S& T C LASSES AT R EACTOR FACILITY ................................................................................. 11 TABLE 4-2. REACTOR SHARING PROGRAM 2010-2011 (REPORTING PERIOD) .................................................... 12 LIST OF FIGURES FIGURE 3-1. M STR CORE 120W CONFIGURATION ........................................................................................... 6

111

SUMMARY

During the 2010-2011, reporting period the Missouri University of Science and Technology Reactor (MSTR) was in use for 12,831.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 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 University of Science and Technology (Missouri S&T) courses over the year for 12,733.5 student-hours. About 4,479 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 12,915.78 kW/hrs kilowatt-hours of thermal energy using approximately 0.511 grams of uranium. A total of 316 samples were neutron irradiated in the reactor with the majority being analyzed in the Reactor Counting Laboratory.

1

1.0 INTRODUCTION

This progress report covers activities at the Missouri University of Science and Technology Reactor Facility for the period April 1, 2010 to March 31, 2011.

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 Backaround 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 two pneumatic rabbit systems 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 a biometric device 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.

An independent auditor from the University of Columbia audited the reactor facility on December 14, 2010. 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. Chemistry 8, 'Qualitative Analysis Laboratory' 2 Civil Engineering 310, 'Senior Design Class'
3. Engineering Management 386, 'Safety Engineering Management'
4. Mechanical Engineering 229, 'Energy Conversion'
5. Life Sciences 352, 'Biological Effects of Radiation' 6 Physics 107, 'Modern Physics'
7. Physics 207, 'Modern Physics II'
8. 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 102 2 SOP 810
3. SOP Index Note: The above listed SOP revisions are provided in Appendix A

3 2.0 REACTOR S TAFF 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 Mr. Thome Kontos' 2 Senior Electronics Technician Craig Reisner Senior Electronics Technician & Senior Operator

1. Starting date 6/21/2010
2. Termination date 3/23/2011 2.2 Licensed Operators Name License
1. William Bonzer Senior Operator
2. Michelle Bresnahan Senior Operator 2
3. Zack Kulage Senior Operator 2
4. Brian Porter Senior Operator
5. Craig Reisner Senior Operator
6. Andrea Mayor Reactor Operator
7. Jeffery Whited2 Reactor Operator
8. Josh McDowell2 Reactor Operator 3
9. Ethan Barth-Taber Reactor Operator 3
12. Jeff George Reactor Operator 3
13. Luke Echols Senior Operator
1. Termination Date April 2, 2010
2. Termination Date June 10, 2010
3. Effective Date December 3, 2010

4 2.3 Radiation Safety Committee The Radiation Safety Committee meets quarterly. The committee met on 6/16/2010, 9/22/2010, 12/1/2010 and 3/1/2011 during the reporting period. The committee members are as follows:

Name Department

1. Dr. Mark Fitch Civil Engineering
2. Mr. Ray Bono Environmental Health and Safety
3. Mr. William Bonzer Nuclear Reactor
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. Amitava Choudhury Chemistry
11. Dr. Carlos Castano Mining & Nuclear Engineering 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. The health physics personnel are as follows:

Name Title

1. Mr. Ray Bono Director of EHS
2. Mr. Brian Smith Industrial Hygienist
3. Ms. Michelle Bresnahan Assistant Director of EHS and Health Physicist
4. Ms. Thea Tadlock Health Physics Technician (part time)
5. Mr. Philip Mennemeyer Health Physics Technician (part time)
6. Ms. Stacy Nowak Health Physics Technician (part time)

1 5 3.0 REACTOR OPERATIONS Core Confirmation 120W 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 thermal column experiments. Table 3-1 presents pertinent core data and Figure 3-1 shows the core configuration of core 120W. The excess reactivity, shutdown margin, and rod worth's were measured in cold, clean conditions.

6 Table 3-1. Core 120W Technical Data Parameter Value Rod I 3.832%Ak/k Rod 2 3.228 %Ak/k Rod 3 1.778%Ak/k Reg Rod 0.293 %Ak/k Excess Reactivity 0.652 %Ak/k Shutdown Margin* 4.354%Ak/k

  • Assumes Rod 1 (highest worth rod) and Reg Rod are fully withdrawn.

A B S C C-4 F-5 F-i F-17 D F-4 F-8 F-14 C-1 F-10 F-2 E F-9 C-3 F-12 C-2 F-7 F-3 F CR F-15 HC F-13 BR F-6 Figure 3-1. MSTR Core 120W Configuration KEY TO PREFIXES F- Standard Elements CR- Cadmium Rabbit HF- Half Element BR- Bare Rabbit F-Standard Elements C- Control Elements CR-Cadmium Rabbit HC- Hot Cell Rabbit S- Source Holder

7 Table 3-2:Unscheduled Shutdowns for 2010-2011 DateType of Rundown/Cause and Corrective Action Taken RUNDOWNS 4/23/2010 Low CIC Rundown Cause: Trouble shooting intermittent readings on picoammeter caused trip.

Corrective Action Taken: No corrective action taken.

SRO on Duty granted permission to restart reactor.

9/23/2010 120% Rundown Cause: Operator failed toupscale picoammeter.

Corrective Action Taken: SRO on Duty instructed operator to be attentive to console instrumentation.

SRO on Duty granted permission to restart reactor.

10/4/2010 120% Rundown Cause: Student operator failed to upscale picoammeter.

Corrective Action Taken: SRO on Duty instructed student operator to be attentive to console instrumentation.

SRO on Duty granted permission to restart reactor.

1/28/2011 120% Rundown Cause: Student operator failed to upscale picoammeter.

Corrective Action Taken: SRO on Duty instructed student operator to be attentive to console instrumentation.

SRO on Duty granted permission to restart reactor.

2/10/2011 Insert Limit on Auto Rundown Cause: Senior Electronic Technician working on auto-controller caused the reg rod to drive in.

Corrective Action Taken: No corrective action taken.

SRO on Duty granted permission to restart reactor.

8 UNPLANNED SHUTDOWNS Date Type of Unplanned Shutdown, Cause and Corrective Action Taken Unplanned Shutdown 6/09/2010 Action: Rod #3 dropped.

Cause: Undetermined.

Corrective Action Taken: No corrective actions taken.

SRO on Duty granted permission to restart reactor.

6/09/2010 Action: Rod #3 dropped.

Cause: Undetermined.

Corrective Action Taken: No corrective actions taken.

SRO on Duty granted permission to restart reactor.

1/27/2011 Action: Rod #3 dropped.

Cause: Undetermined.

Corrective Action Taken: Magnet current adjusted to a higher value.

SRO on Duty granted permission to restart reactor.

Table 3-3: Maintenance for 2010-2011 Date Type of Maintenance 8/06/2010 Issue: Log & Linear channel would not calibrate to the new core configuration's full power reading by repositioning its CIC detector.

Corrective Action Taken: A full power alignment of the Log & Linear Drawer was completed with its CIC detector positioned as low as it can be placed near the reactor core.

7/01/2010 Issue: Auto-controller will not respond properly.

Corrective Action Taken: Recorded voltages to troubleshoot the auto-controller. Replaced capacitor module and calibrated the auto-controller using a picoamp source to mimic reactor operations.

10/1 3/2010 Issue: Linear channel's CIC power supply is unstable.

Corrective Action Taken: Replaced a high voltage diode.

4/15/2011 Issue: Magnet #3 failed to hold control rod #3.

Corrective Action Taken: Removed magnet #3 and replaced with spare magnet.

Performed rod drop time test.

9 Table 3-4. Reactor Utilization

1. Reactor use 557.72 hrs
2. Time at power 369.08hrs
3. Energy generated 12,915.78 kW/hrs
4. Total number of samples, neutron irradiated 316
5. U-235 Burned 0.511 g
6. U-235 Burned and Converted 0.6029 g Table 3-5. Experimental Facility Usage Facility Hours Bare Rabbit Tube 10.24 hr Cadmium Rabbit Tube 0.08 hr Beam Port 5.87 hr Thermal Column 0.0 hr Other Core Positions 13.82 hr Hot Cell 3.60 hr Gamma Exposures 0.67 hr Total 34.28 hr

10 4.0 EDUCATIONAL UTILIZATION The reactor facility supported several Missouri S&T courses in the past year for a total of 12,733.5 student hours. The number of Missouri S&T students utilizing the facility was 1,370. 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 18 hours 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, 577 students and instructors from 132 institutions participated in the program. Table 4-2 lists those schools and groups that were involved in this year's Reactor Sharing Program. The majority of participants were high school students. MSTR coordinates with the Missouri S&T Admissions Office to schedule high school students to see other items of interest at Missouri S&T after they have visited the reactor facility. The students visited the Missouri S&T Chapter of American Nuclear Society, the Computer Integrated Manufacturing Lab, the Foundry, Ceramics Engineering, Mineral Museum, Computer Center, Experimental Mine, Solar Car, Electron Microscope, and Stonehenge. The Reactor Sharing Program serves as a strong campus-wide recruiting tool by attracting high school students to the university and hopefully sparking some interest in nuclear engineering, science, and technology.

The reactor staff continues to educate the public about applications of nuclear science. Over 4,479 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.

11 Table 4-1 Missouri S&T Classes at Reactor Facility Semester CLASS NUMBER/TITLE # OF TIME AT STUDENTS STUDENTS REACTOR HOURS Graduate Student's Project's 6 65.5 390.5 SP2010 NE 308 Reactor Laboratory II 27 2 54 SP2010 NE 312 Gamma Lab & Neutron Lab 25 2.5 62.5 SP2010 NE 25 Nuclear Technology Applications 17 4 68 FS2010 NE 206 18 8 144 FS2010 NE 304 Reactor Laboratory II 21 13.5 283.5 FS2010 NE 25 25 1 25 FS2010 NE 25 20 1 20 FS2010 NE 25 16 1 16 FS 2010 Chemistry Half Life Labs 4 days 729 12 8,748 SP2011 NE 25 Half Life 31 1 31 SP2011 NE 206 Reactor Operations I 18 72 1,296 SP2011 NE 308 Reactor Laboratory II 21 9 189 SP2011 NE 25 Nuclear Tour 31 1 31 SP2011 UMC NE 404 Lab. 10 6 60 SP2011 NE 312 11 1 11 SP2011 NE312 15 1 15 SP2011 NE 312 14 1 14 SP2011 UMC NE 404 Lab. 10 6 60 SP2011 Chem. Labs. 4 day's 266 7 1862 SP2011 UMC NE 404 Labs 9 6 54 SP2011 NE206 18 8 144 2010-2011 Reactor Training 12 151.5 1818 TOTAL 1,370 382 12,733.5

12 Table 4-2 Reactor Sharing Program 2010-2011 (Reporting Period)

Date Participants Number Hours 2010 Individual tours for April 10 2 5/13/10 Chemical Engineering Fort Leonard Wood School 21 1.5 5/2010 Individual tours for May 15 2.0 5/25/2010 Golden Alumni 33 1.0 6/2010 Individual tours of June 4 1.0 6/10/10 Minority Introduction to Engineering 26 2 6/22/10 Jackling Camp 15 1.5 6/24/10 Minority Introduction to Engineering 25 2 6/29/10 Jackling Camp 10 1.5 7/2010 Individual tours for July 14 1.5 7/1/10 Jackling Camp 21 1.5 7/15/10 Jackling Camp 13 1.5 7/12/10 Nuclear Engineering Camp tour 23 5 8/2010 Individual tours for August 32 3.0 8/16/10 Nuclear Regulatory Commission Inspection 2 32 9/2010 Individual Tours September 9 3 9/17/10 Nuclear Engineering 50th Anniversary tours 21 2 9/18/10 Nuclear Engineering 50th Anniversary tours 7 1 9/27/10 Chemical Engineering Fort Leonard Wood School 20 1.5 10/2010 Individual Tours October 2 1.0 10/15/10 Expanding Your Horizons Tour 48 2 11/2010 Individual Tours November 16 2 11/18/2010 East Central College 18 1.5 12/2010 Individual Tours December 18 1.5 12/12/10 MSTR Audit 2 6 12/12/10 Offsite meeting Highway Patrol and Hospital 8 1 1/20/2011 Boy Scouts 10 1 1/27/2011 Heneman Consultants 4 1.5

13 2/2011 Individual tours 6 1.0 2/4/2011 Atlanta University Center for Degree Program 29 1.5 2/8/2011 Chemical Engineering Fort Leonard Wood School 17 1.5 2/10/2010 Chancellor Carney and Dr Kumar Hot Cell demo 2 1 2/11/2011 Meeting x-ray Technician 2 1 2/26/2011 Boy Scout Tour's 39 2 3/2011 Individual Tours 9 1.5 3/15/2011 KY3 Visitors 4 1 3/18/2011 Rolla Daily News Interview 1 1 3/23/2011 Heneman Engineering 3 1 3/29/2011 Chemical Engineering Fort Leonard Wood School 18 1.5 Total 577 98

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. All by-product material released from the reactor facility to authorized recipients is documented and surveyed. 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 surveys of the facility consist of direct gamma and neutron measurements.

There have been no unexpected exposure rates identified. Monthly surface contamination surveys consist of 20 to 40 swipes counted separately for alpha and beta/gamma activity. There has been no significant contamination outside of contained work areas 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 During this period, the Missouri S&T reactor facility changed dosimetry providers. Eighty-one reactor facility personnel and students involved with the operations in the reactor facility are currently assigned, Thermoluminescent Dosimeters (TLDs). Two of the Reactor Staff have beta, gamma, neutron dosimeters which are read twice monthly. There are also four area beta, gamma, neutron dosimeters and two ring dosimeters, which are read twice monthly. There are also five other beta, gamma 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 sixteen area dosimeters assigned on campus for beta and gamma monitoring and one for beta, gamma, and neutron monitoring. In addition, nine digital, direct-reading dosimeters and three chirper dosimeters are used for visitors and high radiation work. There have been no significant personnel exposures during this reporting period. Visitors are monitored with direct reading dosimeters. No visitors received any reportable or significant exposure.

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

15 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 2010 through March 2011 sample concentrations averaged 1.717x105' [Ci/ml.

Release of gaseous Ar-41 activity through the building exhausts is determined by relating the operating times of the exhaust fans and reactor power during fan operation to previously measured air activity at maximum reactor power. During this period, an estimated 26,456.67 ýtCi of Ar-41 was released into the air.

5.4. Environmental Monitoring There are three environmental dosimeters (TLDs) 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 2010 and March 2011.

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. The reactor pool water is analyzed for radioactive contamination and approval is required before the water is released into the sanitary sewer if necessary. During this period there was one waste barrel transferred from the reactor facility to the DMSF on campus.

5.6. Instrument Calibrations Calibration of portable instruments and area monitors was completed according to schedule.

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.

16 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.

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 A second pneumatic transfer system connected to two heavily shielded cells and a glove box has been installed in the reactor core and made operational during this reporting period. The two shielded cells and glove box is located in the beam port room and is referred to as the hot cell system. This year, 2011, the hot cell system will be made available for usage to analyze irradiated samples through a distant location technique. The controlling mechanism for the hot cell system is web based and designed to allow personnel not inside the reactor facility to move an irradiated sample from one shielded cell to another shielded cell containing one or more detectors.

6.3 Reactor Operator Training The Missouri S&T Reactor had one student obtain their Senior Operator's license and two students obtain their Operator's license. Staff member Craig Reisner was made the training coordinator.

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 the reporting period twelve students were training for an operator's license.

17 APPENDIX A.

STANDARD OPERATING PROCEDURES CHANGED DURING THE 2010-2011 REPORTING YEAR

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

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Revision: January 21, 2011 Page 1 of 8 A. PURPOSE:

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

B. PRECAUTIONS, PREREQUISITES, 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 and is to directly supervise the unlicensed personnel.
2. The checklist shall be completed prior to the first reactor start-up of the day. The checklist shall be completed prior to a reactor start-up or after a "Secure" checklist has been completed.
3. After each step on the checklist is performed, the operator will record the readings observed, 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 SRO on Duty, and corrected as necessary before completion of Rev.

the checklist.

5. The following steps will list the Shim/Safety Rods as rods and the Regulating Rod as reg rod.

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.

Reviewed: Craig Reisner Approved By: William Bonzer

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MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES **

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Revision: January 21, 2011 Page 2 of 8

6. RAM System Check:
a. Announce, "THE BUILDING ALARM WILL SOUND. THIS IS A TEST. DO NOT EVACUATE THE BUILDING."
b. Check that the setpoints and automatic functions of the RAM systems meet the criteria listed below. For each High Radiation Alarm, verify that both the audible alarm and the visual annunciator are actuated. Reset the RMIS II module within ten seconds after trip occurs. Reset the annunciator panel after each High Radiation Alarm check.

CHANNEL SETPOINT I AUTOMATIC ACTION

1. Bridge RAM 10 - 18 mR/hr High Radiation Alarm
2. Bridge RAM 15 - 28 mR/hr Building Evacuation Alarm
3. Demin RAM 10 - 18 mR/hr High Radiation Alarm
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 tore!lhr.

Rev.

8. CAM: Verify the CAM is operable by observing a normal reading ( 800 cpm) on the CAM recorder.
9. Beam Port Status: Record the status of the beam port ("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 SRO on Duty if beam port is "open".
10. Linear Channel:
a. Depress the zero check button; verify that the digital display reads '.0000".
b. Depress the zero check button again to release the check function.
c. Set the Linear compensating voltage to obtain a Linear reading between 0.02 and 0.05 on the 2 W scale. Following a high power run, the SRO on Duty may adjust the Linear compensating voltage as appropriate.
d. Record the Linear reading. Record the scale.

Reviewed: Craig Reisner Approved By: William Bonzer

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MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES

  • SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Revision: January 21, 2011 Page 3 of 8
11. 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 by 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

12. a. Observe the Temperature and CAM recorders are operable, the "RCD" is illuminated in the upper left hand corner of the display, and recorders are not out of paper.
b. Turn on and date the Startup, Linear, and Log/Period recorders. Reset the annunciator panel.
13. 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.
c. Visually inspect the core, pool floor and walls, beam port, thermal column and bridge for abnormalities and degradation.
d. Check for in-core experiments.R
e. Notify the SRO on Duty of abnormalities, degradation or in-core experiments are Rev observed.
f. Insert the source into the core source holder.
14. 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.

15. 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.)
16. Observe the Log Count Rate H.V. power supply setting is positive 400 VDC. If setting is different then notify the SRO on Duty.
17. Log and Power Range Test:
a. Depress and hold the 1OpA keypad switch on the Log and Linear drawer to obtain a stable digital log power display.
b. Verify receipt of the "Non-Operative" scram and "Low CIC Voltage" rundown Reviewed: Craig Reisner Approved By: William Bonzer
  • /"*"~~~~~~

.*. .*/,.. .... j ** -*>. .

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES
  • SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Revision: January 21, 2011 Page 4 of 8 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 (%) [Power Range (%)

Re V.

10 pA L.OE-5---2.1E-5 0 - 1%

0.luA 9.3.E-2.---1.9E-1 0 - 1%

1mA 9.1 E 1---1.9E2 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.
18. 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 3.0 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.

19 Turn on the magnet power using the key switch. Push the Scram Reset button to energize the magnets. Reset the annunciator panel.

20. Record inlet temperature. Notify the SRO on Duty if the inlet temperature is below 60'F. R[ev
21. 150% Power Scram Check:
a. Withdraw rods to 3 inches.
b. Depress the test button on Safety Amplifier 1.
c. Verify that a scram occurs before 150%.
d. Verify that the 150% Full Power annunciator light and the audible alarm are activated.
e. Record the trip test reading displayed. on Safety Amplifier 1.
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.

Reviewed: Craig Reisner Approved By: William Bonzer 2... . '... . ,.-."*'"-3.

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES
  • SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Revision: January 21, 2011 Page 5 of 8
22. Log and Linear Drawer Non-Operative Scram and Rundown Test:
a. Withdraw 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 rods to 3 inches.
b. Depress and hold the PERIOD TEST keypad switch. Verify that the 30 Second Rod Withdrawal Prohibit annunciator is activated with a simulated period greater than or equal to 30 seconds. Acknowledge annunciator panel.
c. Continue depressing the PERIOD TEST keypad switch. Verify that the 15 Second Rundown is activated with a simulated period greater than or equal to 15 seconds.

Acknowledge annunciator panel.

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.
24. Manual Scram:
a. Raise rods to 3 inches.
b. Push the manual scram button. Verify that the rods have dropped by visually observing the video display.
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 out bulbs. Reset the annunciator panel.
26. Verify that the magnets are on and that all rods are on insert limit.
27. Prepare hourly checklist and permanent log.
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 Reviewed: Craig Reisner Approved By: William Bonzer

/ .. .:.

-.. . . '.'..V".,, . ... *,i . ,, : *.*

ISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES

  • M*

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Revision: January 21, 2011 Page 6 of 8 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 rods to 6 inches. Record the time onboth 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 performing the checklist will initial the checklist thus verifying that it has been properly completed.

34. The SRO on Duty will announce "The SRO on Duty is and .Rev licensed operator in the control room is "

Rev

35. SRO on Duty name displayed in the control room.
36. The SRO on Duty will initial the checklist verifying that all items have been completed Rev and any problems identified have been satisfactorily resolve.
37. Record the date using the rubber date stamp.

Reviewed: Craig Reisner Approved By: William Bonzer

  • * .i "j
      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES
  • SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Revision: January 21, 2011 Page 7 of 8 l.Date
2. Initials of the Person Performing Checklist
3. Time (Console Clock)
4. Core Loading
5. P.A., Intercom, Video Monitor On
6. RAM System Check
7. Radiation Level Normal
8. CAM Operable
9. Beam Port Status (OPEN or SHUT) Rev Zero
10. Linear Channel Meter Reading Scale HV (-540)

Voltages

11. Linear C.I.C.

CV (- 2 to 8)

12. Recorders On, Dated, "RCD" Light On Temp. & CAM Recorders Water Level (inches)
13. Core Check (Lights On) Elements Verified Inspection Source Inserted
14. Start-Up Channel Test (Verify test switch is in the operate oosition when test is completed.)
15. Verify FC Response, FC Inserted, Count Rate > 2 CPS
16. Log Count Rate HV Power Supply (+400 VDC)
17. Log and Power Range Test
18. Period Response Test
19. Magnet Power On, Scram Reset; Board Reset
20. Inlet Temperature ('F)

Reviewed: Craig Reisner Approved By: William Bonzer

,.' ;Jg , -/ .

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

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Revision: January 21, 2011 Page 8 of 8 Safety Amplifier 1

21. 150% Power Trip Test Reading Raise Rods 3 in. Push Scram Test Safety Amplifier 2 "Test" Button Trip Test Reading
22. Log and Linear Drawer Non-Operative Raise Rods 3 in. Press Scram Test NON-OPER switch.
23. Period Trip Test
24. Manual Scram Test Raise Rods 3 in. Push Manual Scram
25. Annunciator Test, All Lights On
26. Magnets On, Rods on Insert Limit
27. Prepare Hourly and Permanent Logs Inspect Core Log Spike
28. Detector Response Check Period Spike Linear Spike Startup Channel

Response

29. Raise Rods to 6 in., Record Time in Checklist and permanent log.
30. Nitrogen Diffuser Status No. 1 (ON or OFF) No. 2 3 1. Intended Power Level
32. Announce Intention to Start
33. Pre-Startup Check Properly Completed (Licensed Operator's Initials)
34. SRO on Duty announcement's of licensd operators Rev
35. SRO on Duty's name in Control Room
36. SRO on Duty's Initials
37. Date Reviewed: Craig Reisner Approved By: William Bonzer
      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK Revised: February 21, 2011 Page 1 of 11 A. PURPOSE To ensure the proper operation of the control and safety-related instruments of the reactor and to functionally test the Physical Security Alarm System.

B. PRECAUTIONS, PREREQUISITES, OR LIMITATIONS

1. The Weekly Check should be completed on the first working day of each week the reactor is to be operated.
2. The security system, pool conductivity, and Low Pool Water scram shall be checked Rev.

weekly but under no circumstance shall the surveillance interval exceed 14 days. The remaining portion of the checklist may be omitted if the reactor will not be operated that week.

3. The weekly check should be performed by a licensed operator, or a student/trainee under the direct supervision of a licensed operator.
4. Complete the Weekly Surveillance Checklist form and forward it to the Reactor Manager for review and signature. Any abnormalities, problems, or out of service equipment should be brought to the attention of the Reactor Manager.
5. The following steps will list the Shim/Safety Rods as rods and the Regulating Rod as reg rod.

C. PROCEDURE Select the Reactor Bridge Station on the Building Intercom, check the PA system, perform a core check, install the neutron source, turn on and date the Source Range, Linear, and Log/Period recorders. Turn on the core camera and select core on the monitor selector. Obtain Magnet Power Key and turn on magnet power. Reset the Scram and console resets.

1. Rod Prohibits 1.1. Recorders Off - Verify that the rods will not withdraw if any one of 4 primary recorders is turned off. Repeat the following steps for the 1) Source Range recorder,
2) Linear recorder, 3) Log/Period recorder, and 4) Temperature recorder.
a. Turn off the recorder.

Reviewed By: Craig Reisner Approved By: William Bonzer

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

SOP: 810 TITLE: WEEKLY CHECK Revised: February 21, 2011 Page 3 of 11

b. Announce "The Building Alarm will sound. This is a test do not evacuate the building." on the Building PA System.
c. Have a second person check that the audible and visual alarms are functional on the remote meters located near the detectors. Using the Bridge RAM check source switch (NORMAL green light), record the value at which the High Area Radiation rundown and Building Evacuation Alarm occur. Check the automatic reset of the RAM, reset the Building Alarm (Scram Reset Button), acknowledge the annunciator, depress Rundown Reset and Annunciator Reset. Record the value of alarms.
d. Repeat step c for the Demin RAM and Experiment Room RAM except for the Rev.

Building Evacuation Alarm.

e. Verify that the Evacuation Alarm actuated between 20 mrem/hr and 28 mrem/hr.
f. Verify that the High Area Radiation alarms actuated between 10 mrern/hr and 15 mremihr.
g. Upon completion of testing announce "Test Complete. Acknowledge all further alarms," on the building PA system.

2.2. 120% Demand

a. Withdraw rods to 3 inches.
b. Turn off the Linear recorder
c. Remove Linear recorder potentiometer cover and manually rotate potentiometer arm, note recorder reading when trip point is reached.
d. When inward motion of rods is verified, lower recorder below reset point, reset rundown and all alarms, turn recorder on and replace cover, and compare actual and specified trip points.
e. Record the trip point value and that the audible/visual alarms are functional.

2.3. 120% Full Power

a. Withdraw rods to 3 inches.
b. Depress "LINEAR TEST" switch.
c. Observe the Linear digital display and record the value at which the 120% full power trip occurs.
d. Release the "LINEAR TEST" switch.
e. Observe the "120% Full Power" annunciator and audible alarm.
f. Reset the annunciator and rundown.

2.4. Low CIC Voltage Linear Power Supply

a. Withdraw rods to 3 inches.
b. Push and hold alarm test button on Linear CIC Power Supply. Observe High Reviewed By: Craig Reisner Approved By: William Bonzer
      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK Revised: February 21, 2011 Page 2 of 11

b. Attempt to withdraw rods. Verify rods cannot be withdrawn.
c. Verify that the Recorder Off annunciator illuminates and that the console audible alarm is actuated.
d. Turn the recorder on, reset the annunciator.
e. Verify the rods can be withdrawn. Rev.

1.2. Source Range < 2 CPS

a. Remove source from holder and/or withdraw fission chamber until Source Range CR <2 alarm is received. Record value at which the alarm occurs from recorder.
b. Attempt to withdraw rods. Verify rods cannot be withdrawn.
c. Verify that the CR <2 cps annunciator illuminates and that the console audible alarm is actuated.
d. Insert source and/or insert the fission chamber to the insert limit. Reset annunciator.

1.3. Inlet Temperature Above 135 Degrees

a. Plug the thermocouple simulator into the test input jack for one of the inlet thermocouples (thermocouple #1 or #3). (Randomly alternate which inlet thermocouple is checked from week to week.) Record the thermocouple tested.
b. Slowly adjust the simulator to a higher setting, until the "Inlet Temperature Above 135°F" annunciator and audible alarm are energized.
c. Attempt to withdraw rods. Verify rods do not withdraw.
d. Record the temperature displayed on the recorder when the "Inlet Temperature Above 135'F" trip occurs.
e. Disconnect the thermocouple simulator from the thermocouple test input jack.
f. Reset annunciator.
g. Verify rods can be withdrawn. Rev.

1.4. Shim Rods Below Shim Range Withdraw rods between 1/2 inch and 3 inches and attempt to withdraw the reg rod.

Note that the reg rod will withdraw just far enough to clear the insert limit light.

Attempt to withdraw the rods. Note that further withdrawal cannot be made. Insert all rods to the insert limit and record these results. Verify the rods can be withdrawn. Rev.

2. Rundowns 2.1. Radiation Area Monitoring (RAM) System
a. Withdraw rods to 3 inches.

Reviewed By: Craig Reisner Approved By: William Bonzer

,/7

MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK Revised: February 21, 2011 Page 4 of 11 Voltage meter and record the value when the under voltage alarm light comes on.

Release the test button. The under voltage alarm light shall actuate at a voltage equal or above 440VDC.

c. Acknowledge the annunciator alarm and observe Low CIC voltage annunciator light. Check for insertion of control rods (rundown in progress).
d. When the High Voltage on the Linear CIC Power Supply has increased to approximately 500 volts push alarm reset. The under voltage alarm light will go off allowing the operator to reset the rundown (push rundown reset) and the annunciator.
e. Record value of the trip point.

2.5. Regulating Rod on Insert Limit on Auto

a. Withdraw the rods to 3 inches and reg rod to 0.5 inches (use the shim range bypass).
b. Adjust Linear recorder setpoint so that "auto permit" comes on.
c. With reg rod at approximately 0.5 inches withdrawn, switch the reg rod control to "Auto" and reset the annunciator.
d. Adjust the red pointer (auto setpoint) to be slightly below black pointer (Linear signal) so that an insert on the reg rod will result.
e. When the reg rod reaches insert limit observe rods inserting, Manual Operation and "Reg Rod insert limit on Auto" annunciators.
f. Acknowledge and reset rundown and annunciators.
g. Record results.
3. Scrams 3.1. Bridge Motion Scram
a. Withdraw rods to 3 inches.
b. Release bridge lock and move the bridge a small distance.
c. Observe a Bridge Motion and Manual Scram annunciators illuminate and that the rods scram. Acknowledge the annunciator alarm.
d. Return bridge to original position and reset all annunciators. Re-insert the magnets.
e. Record results.

Reviewed By: Craig Reisner Approved By: William Bonzer

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

SOP: 810 TITLE: WEEKLY CHECK Revised: February 21, 2011 Page 5 of 11 3.2. Low Pool Water Scram

a. Withdraw rods to 3 inches.
b. Lower pool float to lowest position attainable or until scram occurs.
c. Observe. a Low Pool Water and annunciator illuminate and that the rods scram.

Acknowledge the annunciator alarm.

d. Re-insert the magnets.
e. Record results.

3.3. Non-Operative Scram and Rundown Test

a. Withdraw rods to 3 inches.
b. Depress the "NON-OPERATE" switch.
c. Verify rods have dropped and rod drives are inserting.
d. Release the "NON-OPERATE" switch.
e. Verify the "Log N Non-operate" and "Low CIC High Voltage" annunciators and audible alarms are activated.
f. Reset the Scram, Rundown, and Annunciator panel.
g. Depress and release the test switches listed below. For each verify a scram has Rev.

occurred and the "Log N Non-operate" and "Low CIC High Voltage" annunciators and audible alarms are activated. Reset the scram and annunciator panel after each switch is checked. The following switches are to be checked: Rev.

0 1 mA switch,

  • 0.1 gA switch,
  • 10 pA switch, and
3. SEC switch.

3.4. 150% Full Power Scram

a. Withdraw the rods to 3 inches.
b. Depress the scram test button on Safety Amplifier # 1 and hold. Observe that the Rev.

scram occurs prior to 150%.

c. Push reset on the Safety Amplifier # 1, acknowledge the annunciator and observe the 150% Full Power Scram annunciator. Rev.
d. Reset annunciator and insert the magnets.
e. Performs steps a-d for Safety Amplifier #2.
f. Record results.

3.5. Manual Scram

a. Withdraw rods to 3 inches.

Reviewed By: Craig Reisner Approved By: William Bonzer

  • . ) 7.
      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES **

SOP: 810 TITLE: WEEKLY CHECK Revised: February 21, 2011 Page 6 of 11

b. Push Manual Scram button and observe the control rods dropping.
c. Acknowledge the annunciator and Manual Scram light. Push Scram Reset, Annunciator Reset and insert the magnets.
d. Record results.
4. Period Trips
a. Withdraw rods to 3 inches.
b. Depress the "PERIOD TEST" switch to inject a ramp signal and observe the period digital display. Continue holding the switch down throughout the following steps.

4.1. 30 Second Trip - Verify that the <30 second audible and visual alarms are received at an indicated period of 30 seconds or more. Attempt to withdraw rods. Verify that rods cannot be withdrawn. Record the value (digital meter) at which the <30 second trip was received. Acknowledge the alarm.

4.2. 15 Second Trip - Continue depressing the "PERIOD TEST" button until the <15 second rundown occurs. Verify that the audible and visual alarms are received and that the rods begin to rundown. Acknowledge the alarm and .record the actual trip point (digital meter).

4.3. 5 Second Trip - Continue depressing the "PERIOD TEST" button until the <5 second scram occurs. Verify that the audible alarm is received and that the <5 second and 150% full power annunciators are activated. Record the value (digital meter) at which the <5 second alarm occurs.

4.4. Release the "PERIOD TEST" switch, reset the scram, rundown, and annunciator panel.

5. Rod Drop Currents
a. Withdraw rods to 3 inches.
b. Using a screwdriver slowly reduce magnet current using current adjustment # 1, Rev.

visually observe rod #1 drop. Record this drop current value.

c. Repeat Steps a and b for Rods #2 and #3.
d. Insert all rod drives to insert limit.
e. Set all magnet currents to "normal" (i.e. Drop Current plus 15 ma).
6. Test of Annunciators 6.1. Interlock Bypass Reviewed By: Craig Reisner Approved By: William Bonzer

, .3," II

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

SOP: 810 TITLE: WEEKLY CHECK Revised: February 21, 2011 Page 7. of 11 Bypass each interlock one at a time to ensure that each individual bypass operates the annunciator and the bypass lights are functional.

6.2. Servo Limits

a. Note linear level recorder reading.
b. Change the automatic set point for auto permit by adjusting the star wheel.

Remove Linear recorder potentiometer cover and manually rotate potentiometer Rev.

arm. Note linear level at which the auto permit light comes on (<+2%). Continue to lower and note reading until the auto permit light goes off (>-2%).

c. Record results.

6.3. Pool Demineralizer Effluent Conductivity High Rev.

a. Record pool and demin effluent readings.
b. Check the alarm setpoint by pressing the ALARM 1/ALARM 2 Key and observing "alarm 1 set" setpoint is 0.500 M£2 - cm.
c. Increase the alarm I setpoint to a number higher than the conductivity cell reading and press the enter key. Observe the "ALARM" indicator flashing on the display. Observe that the console annunciator and audible alarm are activated.
d. Reset the "alarm 1 setpoint" to 0.500 Mf2 - cm.
7. "REACTOR ON" Lights With magnet key inserted and all scrams reset check the "reactor on" lights (1) above console (2) at reactor entrance and (3) basement level.
8. Building Evacuation Alarm
1. Announce over the PA, "The Building Alarm will sound. This is a test. Do not evacuate the building."
2. Push the Building Evacuation Alarm and note the audible alarm.
3. Reset Building Evacuation Alarm by pushing Scram Reset
4. Announce over building PA "Test complete. Acknowledge all further alarms."
9. Nitrogen Diffusers
1. With the bridge intercom station selected, start diffuser #1. The green operation light should illuminate. Note the sound level of the pump and no unusual noise.
2. Shutdown the #1 pump and repeat step 1 for the #2 nitrogen diffuser.
3. Record results.

Reviewed By: Craig Reisner Approved By: William Bonzer

MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK Revised: February 21, 2011 Page 8 of 11

10. Beam Port Warning Lights
1. Announce over the building PA. "Attention personnel, stand clear of the Beam Port".
2. Open the Beam Port by holding the Beam Port control switch in the open position Rev.

until the "Red" (open) light comes on.

3. Acknowledge the annunciator alarm and verify that the Basement Level Warning Light (Flashing Red) activates.
4. Close the Beam Port by holding the Beam Port Switch until the Green (closed) light comes on. Reset the annunciator and observe that the light goes out.
5. Announce over the Building PA "Beam Port secured".
11. Constant Air Monitor (CAM)
1. Remove the CAM filter and place in an envelope labeled with the date and time the filter was used. Rev.
2. Install new filter on CAM.
3. Place envelope on a gamma spectroscopy system and count for one hour.
4. Create a gamma spectroscopy report of the spectrum.
5. Observe report for abnormally high peaks.
6. Save report as a computer file. Rev.
12. Secure Check - Complete a Secure Checklist (SOP 105) to ensure that all console equipment is secured.
13. Security System Check- Inform the Missouri S&T Police (4300) that the security system Rev.

will be checked and verify the appropriate alarms are received by them.

13.1. Security Door

a. Hold in or close dead bolt on the security door.
b. Reset the alarm system.
c. Open dead bolt switch by releasing or opening dead bolt and ensure alarm occurs in Missouri S&T Police dispatch station. Rev.

13.2. Ultrasonics

a. Hold or close dead bolt on security door. Reset alarm system.
b. While holding the dead bolt switch, move around or have someone walk towz one of the UT's. A different ultrasonic detector should be tested each week.

Reviewed By: Craig Reisner Approved By: William Bonzer t,,,,* *)

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

SOP: 810 TITLE: WEEKLY CHECK Revised: February 21, 2011 Page 9 of 11

c. Allow the ultrasonic to reset by moving clear of the detector or stand still.

13.3. Duress

a. Momentarily depress the alarm button.

13.4. Doors

a. While holding the dead bolt switch closed, reset the alarm.
b. Open one of the exterior doors equipped with an intrusion alarm. A different door should be tested each week.
c. Repeat steps a and b for one of the interior doors equipped with an intrusion alarm. A different door should be tested each week.
d. When all intrusion channels have been tested, verify Missouri S&T Police have IRev.

received alarms. This completes the security check.

e. When all channels of the security system have been functionally tested and operate properly, initial the weekly checklist.
14. Checklist Completed By - The person who performed the checklist should sign and date in the blanks provided. If a nonlicensed operator performed the checklist, the licensed operator who supervised the checklist shall also sign and date the form.
15. Reviewed and Approved - The Reactor Manager shall review and approve the checklist.

Review and approval of the Weekly Checklist may be delegated to a Senior Reactor Operator in the event that the Reactor Manager is unavailable for the review.

Reviewed By: Craig Reisner Approved By: William Bonzer

MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES

  • SOP: 810 TITLE: WEEKLY CHECK Revised: February 21, 2011 Page 10 of 11 WEEKLY SURVEILLANCE CHECKLIST Date Performed
1. Rod Prohibits 1.1. Recorder Off Alarms (V") Prohibit (/)
  • Source Range recorder
  • Linear recorder
  • Log/Period recorder
  • Temperature recorder Set Point Alarms (,/) Prohibit (V')

1.2. Source Range <2 cps cps 1.3. Inlet Temperature >135°F OF Thermocouple tested 1.4. Shim Rods below shim range N/A N/A

2. Rundowns 2.1. RAM Syste Rundown Bldg. Alarm Remote and Station Set Point Set Point Alarms (V) Local Alarm (V,)

Bridge mrem/hr mrem/hr Demin mrem/hr N/A Basement mrem/hr N/A Rundown Set Point Alarms (-/)

2.2. 120% Demand rundown 2.3. 120% Full Power Rundown 2.4. Low CIC Linear P.S. VDC

(!440VDC) 2.5. Regulating Rod on Insert Limit on Auto N/A

3. Scrams Alarms (V) Scram (

3.1. Bridge Motion Scram 3.2. Low Pool Water Scram 3.3. Log and Linear Non-Op. Scram Rev.

  • Non-operate switch (raise rods 3")

I mA switch

0. 1 gA switch
  • 10 pA switch
  • 3 sec switch 3.4. 150% Full Power Scram Safety Amplifier I Safety Amplifier 2 3.5. Manual Scram Reviewed By: Craig Reisner Approved By: William Bonzer
      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK Revised: February 21, 2011 Page 11 of 11 Date

4. Period Trips Set Point Alarms (,') Trip Operational (V) 4.1. 30 Sec RWP 4.2. 15 Sec Rundown Rev.

4.3. 5 Sec Scram

5. Rod Drop Currents Drop Current 5.1. Rod#l mA Rev.

5.2. Rod #2 mA 5.3. Rod #3 mA

6. Test of Annunciators 6.1. Interlock Bypass Alarms (,') Operational (V)
  • 30 second period Rev,
  • Radiation area high
  • <2 CPS 6.2. Servo Limits: Lin. Rec. Reading  % Permit on at  % Permit off at %

6.3. Pool/Demineralizer Resistivity Pool Demin Local Alarm (-V) Annunciator (,)

M92-cm Mn2-cm

7. "Reactor on" Lights Operational (/)

7.1. Main Entrance 7.2. Control Room 7.3. Beam Room

8. Buildinz Evacuation Alarm Operational (V):
9. Nitrogen Diffusers Pump Operational (V) Indicator Light On (v')
  1. 1
  1. 2
10. Beam Port Warning Light: Annunciator (1) Flashing Light (,/)
11. Constant Air Monitor Completed (-/):
12. Secure Check List: Completed (/l):
13. Security System Check: Completed (-/):
14. Checklist Completed By: Date
15. Reviewed and Approved:

Manager Reviewed By: Craig Reisner Approved By: William Bonzer

      • MISSOURI S&T REACTOR STANDARD OPERATING PROCEDURES
  • SOP: INDEX TITLE INDEX Revised: February 21, 2011 Page 1 of 3 SOP 100-199 Routine Reactor Operation SOP 100 Preamble SOP 101 General Operational Procedures SOP 102 Pre-Startup Checldist Procedures SOP 103 Reactor Startup to Low Power SOP 104 Reactor Power Changes and Stable Operations SOP 105 Reactor Shutdown & Reactor Securing Procedures SOP 106 Restart of Reactor When It Is Not Secured SOP 107 Permanent Log, Hourly Log, and Operational Data SOP 109 Determination of Control Rod Worths by the Rod Drop Method SOP 110 Calibration of Control Rods by Positive Period Method SOP 111 Measurement of Core Excess Reactivity and Determination of Shutdown Margin SOP 112 Fuel Management SOP 150 Response to Alarms SOP 151 Response to a High Area Radiation Alarm SOP 200-299 Facility Operations SOP 200 Bridge Movement Procedure SOP 204 Demineralizer Regeneration SOP 206 Installation and Removal of Experimental Facilities SOP 207 Fuel Handling SOP 208 Reactor Security SOP 209 Securing the Building SOP 210 Occupying Building When Intrusion System Inoperative SOP 300-399 Special Operations SOP 301 Pool Water System SOP 302 Inspection of Control Rod SOP 303 Pool Water Cooler System Rev.

SOP 306 Estimation of Activity and Reactivity Worth of a Sample SOP 308 Restoration of Power Following a Power Outage SOP 309 Response to a Coolant System Leak SOP 310 Facility Modifications SOP 311 Receipt of Licensed Materials SOP 312 Critical Experiment Procedures Revised By: Maureen Henry Approved By: William Bonzer N1l

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

SOP: INDEX TITLE INDEX Revised- February 21, 2011 Page 2 of 3 SOP 400-499 Reserved for Future Use SOP 500-599 Emergency Procedures SOP 501 Emergency Procedures for Reactor Building Evacuation SOP 502 Emergency Procedures for an Unusual Event SOP 503. Emergency Procedures for an Alert SOP 504 Emergency Procedures for a Site Area Emergency SOP 505 Enhanced Reactor Security SOP 506 Bomb Threat SOP 507 Emergency Procedures - Administrative Responsibilities SOP 508 Tornado Threat SOP 509 Fire SOP 510 Earthquake SOP 511 Response to Missing Special Nuclear Material SOP 600-699 Health Physics Procedures SOP 600 General Health Physics SOP 601 Handling of Radioactive Samples SOP 602 Entry Into A High Radiation Area SOP 603 Release of By - Product Materials On Campus SOP 604 Radioactive Waste Handling Criteria SOP 615 Radiation Work Permit SOP 620 Decontamination Procedures SOP 621 Guidelines for Emergency Exposures SOP 622 Handling Injured in Radiation Accidents SOP 650 Radiation Area Survey SOP 651 Contamination Survey SOP 652 Pool Water Tritium Analysis SOP 653 Sealed Source Leak Test SOP 654 Measurement of 44 1Ar Concentration in the Reactor Building -Air SOP 655 Radiation Area Monitor (RANI) Calibrations SOP 700 - 799 Experiments SOP 701 Request for Reactor Projects SOP 702 Irradiation Request Forms SOP 703 Reactor Use Forms Revised By: Maureen Henry Approved By: William Bonzer

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

SOP: INDEX TITLE INDEX Revised: February 21, 2011 Page 3 of 3 SOP 701 Request for Reactor Projects SOP 702 Irradiation Request Forms SOP 703 Reactor Use Forms SOP 710 Insertion and Removal of Experiments SOP 711 Beam Hole Facility SOP 712 Thermal Column Facility SOP 800 - 899 Reactor Instrumentation SOP 800 Semi-Annual Checklist SOP 801 Log N and Linear Drawer Calibration SOP 802 Linear Channel SOP 803 Log Count Rate (LCR) Channel SOP 804 Safety Amplifier System SOP 805 Auto Control System SOP 806 Temperature Channel Rev.

SOP 810 Weekly Check SOP 811 Fire and Smoke Alarm System SOP 812 Confinement and Ventilation System Check SOP 813 Rod Drop Time Measurement SOP 816 MSTR Power Calibration SOP 818 Functional Test of Building Security System Revised By: Maureen Henry Approved By: William Bonzer LC 4/

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