ML031210014

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Transmittal of Annual Progress Report 2002-2003 for University of Missouri-Rolla Reactor Facility
ML031210014
Person / Time
Site: University of Missouri-Rolla
Issue date: 04/25/2003
From: Tokuhiro A
Univ of Missouri
To:
Document Control Desk, Office of Nuclear Reactor Regulation
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MSs University of Missouri-Rolla m~

Nuclear Reactor Facility 70 1870 Miner Circle Rolla, MO 65409-0630 Phone: (573) 341-4236 FAX: (573) 341-4237 April 25, 2003 U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulations Attention: Director Document Control Desk Washington, D.C. 20555

Dear Sir:

Please find enclosed the Annual Progress Report 2002-2003 for the University of Missouri-Rolla Reactor Facility (License R-79, Docket No: 50-123). This report is being filed under the reporting requirements of our Technical Specifications.

Copies of this report are also being sent to our Regional Administrator and Project Manager.

Sincerely, Ir.iraT. Tokuhiro Reactor Director mh Enclosure xc:

Marvin Mendonca, Project Manager (NRC)

Chancellor Gary Thomas (UMR)

Dr. Lee W. Saperstein, Dean, School of Mines & Metallurgy (UMR)

Mr. Ray Bono, Radiation Safety Officer(UMR)

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

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

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

University of Missouri-Columbia Research Reactor (MURR)

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

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

an equal opportunity institution

PROGRESS REPORT 2002-2003 UNIVERSITY OF MISSOURI - ROLLA NUCLEAR REACTOR FACILITY

PROGRESS REPORT 2002-2003 UNIVERSITY OF MISSOURI-ROLLA NUCLEAR REACTOR FACILITY

PROGRESS REPORT FOR THE UNIVERSITY OF MISSOURI-ROLLA NUCLEAR REACTOR FACILITY April 1, 2002 to March 31, 2003

Submitted to The U.S. Nuclear Regulatory Commission and The University of Missouri-Rolla

ii

SUMMARY

During the 2002-2003 reporting period the University of Missouri-Rolla Reactor (UMERR) was in use for 416 hours0.00481 days <br />0.116 hours <br />6.878307e-4 weeks <br />1.58288e-4 months <br />. The major part of this time, about 95% was used for class instruction, research, and training purposes.

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

The reactor facility supported several UMR courses over the year for a total of 2,550 student-hours. About 2,968 visitors visited the reactor during the past year. There were 394 participants, mostly high school students, in the U.S. Department of Energy Reactor Sharing Program.

The reactor produced 12,861.6 kilowatt-hours of thermal energy using approximately 0.66 grams of uranium. A total of 155 samples were neutron irradiated in the reactor with most of them being analyzed in the Reactor Counting Laboratory. An additional 320 samples were exposed to gamma radiation in the reactor without neutron irradiation.

Table of Contents

1.0 INTRODUCTION

.1 1.1 Background Information.....................................

1 1.2 General Facility Status.....................................

2 2.0 REACTOR STAFF AND PERSONNEL...................................

4 2.1 Reactor Staff..................................................................................................4 2.2 Licensed Operators.....................................

4 2.3 Radiation Safety Committee.....................................

5 2.4 Health Physics.....................................

5 3.0 REACTOR OPERATIONS............................................................................................6 4.0 PUBLIC RELATIONS....................................

10 5.0 EDUCTATIONAL UTILIZATION....................................

12 6.0 REACTOR HEALTH PHYSICS ACTIVITIES.....................................

1i5 6.1 Routine Surveys.15 6.2 By-Product Material Release Surveys.15 6.3 Routine Monitoring.15 6.4 Waste Disposal.16 6.5 Instrument Calibrations.16 7.0 PLANS.......

16 7.1 Administrative Changes.16 7.2 Relicensing..................

17 7.3 Strategic Plan

.17 7.4 Instrumentation Upgrade

.17 7.5 Reactor Operating Training

.17

iv Table 3-1.

Table 3-2.

Table 3-3.

Table 3-4.

Table 3-5.

Table 4-1.

Table 5-1.

Table 5-2.

List of Tables Core I01W Technical Data............................................

6 Scrams, Rundowns, And Unplanned Shutdowns.............................................

8 Maintenance.............................................

9 Reactor Utilization...........................................

12 Experimental Facility Use Other Than The Reactor........................................... 12 Public Relations Program...........................................

13 UMR Classes at Reactor Facility 2001-2002 Reporting Period.......................... 15 Reactor Sharing Program...........................................

16 List of Figures Figure 3-1. UMRR Core Configuration.....................................................

7 Appendices A. SOP'S CHANGED DURING THE 2002-2003 REPORTING YEAR 18 B. REVISED SAR PAGES FOR THE 2002-2003 REPORTING YEAR 19

1

1.0 INTRODUCTION

This progress report covers activities at the University of Missouri-Rolla Reactor (UMRR) Facility for the period April 1, 2002 to March 31, 2003 The reactor is operated as a university facility, available to the faculty and students from various departments of the university for their educational and research programs. Several other college and pre-college institutions have made use of the facility during the reporting period.

The facility is also available for the training of reactor personnel from companies with nuclear power plants.

1.1 Background Information The University of Missouri-Rolla Reactor Facility attained initial criticality on December 9th, 1961. The UMRR was the first operating nuclear reactor in the state of Missouri. The reactor design is based on the Bulk Shielding Reactor at Oak Ridge National Laboratory. The reactor is a light water, open pool reactor cooled by natural convective flow. The fuel is MTR plate-type fuel. The initial licensed power was 10 kW. The licensed power was upgraded to 200 kW in 1966. During the summer of 1992, the reactor fuel was converted from high-enriched uranium fuel to low-enriched uranium.

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

Additionally, the facility is equipped with a counting laboratory that has gamma and alpha spectroscopy capabilities. The gamma spectroscopy system includes germanium and sodium-iodide detectors, associated electronics, and state-of-the-art data acquisition and spectrum analysis software. The alpha spectroscopy system consists of a surface barrier detector and data acquisition equipment. The beamport experimental area is equipped with NE-213 and time-of-flight neutron spectroscopy systems.

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

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

We are continuing efforts to upgrade our console using grant awards from DOE combined with money directly from reactor funds. We have received grant funds for Reactor Instrumentation upgrade in Spring 2002 and have received notice of an award for additional grant funds in Spring 2003.

The reactor has funded a graduate student to perform research in support of the relicensing effort. To date research on atmospheric dispersion modeling dose assessments associated with normal operations and accident conditions has been finished. An additional graduate student is now conducting computational analysis of severe accident scenario in support of the SAR.

An independent auditor from the University of Columbia audited the Reactor Facility on December 11, 2002. There were no significant areas of concern. We have entered into an agreement with the University of Missouri-Columbia to audit each other. This has been a very beneficial arrangement for both facilities involved.

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

Physics 4&5, 'Concepts in Physics' Physics 7, 'Environnemental Physics' Chemistry 8, 'Qualitative Analysis Laboratory' Physics 107, 'Modern Physics' Physics 207, 'Modern Physics II' Physics 322, 'Advanced Physics' Chemical Engineering 261, 'Introduction to Environmental Engineering'

3 Chemistry 2, 'General Chemistry Laboratory' Mechanical Engineering 229, 'Energy Conversion' Life Sciences 352, 'Biological Effects of Radiation' Chemistry 251, 'Intermediate Quantitative Analysis' Chemistry 355, 'Instrumental Methods Laboratory' Civil Engineering 310, 'Senior Design Class' Basic Engineering 50, 'Engineering Mechanics - Statics' Engineering Management 386, 'Safety Engineering Management' SOPs have been revised over the past year in order to improve our operations and efficiency. The following is a list of SOPs revised during the reporting period:

SOP 102 SOP 102 SOP 501 SOP 501 SOP 501 SOP 653 SOP 655 SOP 800 SOP 804 SOP 810 SOP 810 Pre-Startup Checklist Procedure (Pages 5,7,8)

Pre-Startup Checklist Procedure (Page 5)

Emergency Procedures For Reactor Building Evacuation (Page 7)

Emergency Procedures For Reactor Building Evacuation (Page 7)

Emergency Procedures For Reactor Building Evacuation (Page 7)

Sealed Source Leak (Page 1)

Radiation Area Monitor (RAM) Calibrations (Page 1,5)

Semi-Annual Checklist (Pages 5,6,7,8,9,& 10)

Safety Amplifier System (Pages 1,2)

Weekly Checklist (Pages 5,10)

Weekly Checklist (Page 5)

The above listed SOP revisions are provided in Appendix A.

4 2.0 REACTOR STAFF AND PERSONNEL 2.1 Reactor Staff Name Dr. Akira Tokuhiro William Bonzer Mendy Kell' Maureen Henry2 James Jackson3 Brian Porter Dan Estel4 Title Director & Senior Operator Reactor Manager & Senior Operator Senior Secretary Senior Secretary Senior Operator & Senior Lab Mechanic Senior Electronics Technician Interim Senior Lab Mechanic

'Departed Reactor 05/10/02 2Hired effective 07/22/02 3Departed Reactor 12/09/02 4Hired effective 12/23/02 2.2 Licensed Operators Name William Bonzer James Jackson Akira Tokuhiro Dan Estel Jeremy Gorelick Craig Heimericks Michelle Minard' Kurt Koch' Hannah YountI License Senior Operator Senior Operator Senior Operator Reactor Operator Reactor Operator Reactor Operator Reactor Operator Reactor Operator Reactor Operator

'Effective in September 16, 2002

5 2.3 Radiation Safety Committee The Radiation Safety Committee meets quarterly. The committee met on 4/17/02, 7/15/02, 11/14/02, and 3/10/03 during the reporting period. The committee members are listed below.

Name Dr. Mark Fitch, (Chairman)

Mr. Ray Bono (Secretary, ex-officio, non-voting)

Mr. William Bonzer Dr. Roger Brown Dr. Robert DuBois Dr. Arvind Kumar until 7/2/02 Dr. Heather Gepford effective 7/2/02 Dr. Ekkehard Sinn Mr. Randy Stoll Dr. Akira Tokuhiro Dr. Nick Tsoulfanidis Department Civil Engineering Environmental Health and Safety Services Nuclear Reactor, Reactor Manager Biological Sciences Physics Nuclear Engineering Nuclear Engineering Chemistry Director, Business Services Director, Nuclear Reactor Nuclear Engineering 2.4 Health Physics Health Physics support is provided through the Environmental Health and Safety Department, which is organizationally independent of the Reactor Facility operations group.

Health Physics personnel are listed below:

Name Mr. Ray Bono Mr. Brian Smith Allison Adams Michelle Minard LeAnn Splitter Julie Tucker Title Health Physicist & Radiation Safety Officer Industrial Hygienist HP Technician HP Technician HP Technician HP Technician

6 3.0 REACTOR OPERATIONS Core designation 101W is presently in use. The "W" mode core is completely water reflected and is used for normal reactor operations. The "T" mode (core positioned near graphite thermal column) may be used for various experiments, including beam port and thermal column experiments.

Table 3-1 presents pertinent core data and Figure 3-1 shows the core configuration of core 10 1W. The excess reactivity, shutdown margin, and rod worths were measured in cold, clean conditions.

Table 3-1. Core 101W Technical Data

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

Figure 3-1. UMRR Core 101W Configuration A

B C

D E

F F-8 F-4 C-4 F-13 C-1 F-3 F-2 F-12 F-15 F-10 C-2 F-1 C-3 F-9 F-14 CR F-5 F-6 F-7 BR 1

2 3

4 5

6 7

8 9

KEY TO PREFIXES F - Standard Elements C - Control Elements BR - Bare Rabbit CR - Cadmium Rabbit S - Source Holder

7 Table 3-2 presents a listing of unscheduled shutdowns (scrams, rundowns, and unplanned normal shutdowns) along with their causes and corrective actions. There were four scrams (unscheduled shutdowns). Each was due to one rod dropping. One was due to the reactor bridge being bumped and the other three were caused by low magnet current settings, in which the electromagnet's magnetic flux did not support the weight of the control rod. None of the four scrams initiated a trip signal due to the nature of the scram.

Five of the 12 rundowns were 120% Full Power rundowns caused by electrical noise spikes to the Log and Linear Channel in which this trip originates. The noise spikes generally were created from the auto controller circuitry. The reactor was at a stable power during each of these trips.

The 120% Demand rundowns occurred due to switching errors and noise spikes originating in the Linear Channel's meter switches. Operators were instructed to properly switch scales to avoid additional switching errors.

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

Table 3-2. Scrams, Rundowns, and Unplanned Shutdowns 05/03/02 120% Full Power Rundown. Cause was a noise spike from auto-controller. No corrective taken. SRO gave permission to restart reactor.

05/16/02 120% Demand Rundown. Cause was operator inattention to Linear Channel.

Corrective action; SRO instructs RO to observe Linear Channel while operating. SRO granted permission to restart the reactor.

05/31/02 120% Full Power Rundown. Noise spike caused rundown. No corrective action taken.

SRO granted permission to restart reactor.

05/31/02 Scram (Unscheduled shutdown). Control rod 3 dropped due to low magnet current.

Corrective action; magnet power supply replacement scheduled. Reactor was not restarted.

06/11/02 120% Full Power Rundown. Caused by noise spike from auto-controller. No corrective action taken. SRO granted permission to restart reactor.

06/11/02 120% Full Power Rundown. Cause was a noise spike from auto-controller. No corrective action taken. SRO granted permission to restart reactor.

07/23/02 Scram (unscheduled shutdown). Caused by jarring of the reactor bridge steps causing one rod to drop. No corrective action taken. SRO granted permission to restart reactor

8 02/01/03 120% Demand Rundown. Caused by trainee downscaling Linear Channel too soon. SRO instructed operator to downscale at 8%. SRO granted permission to restart reactor.

02/06/03 Scram (unscheduled shutdown). Caused by low magnet current to control rod 2.

Corrective action taken was to increase magnet current an additional five milliamps. SRO granted permission to restart reactor.

02/07/03 Scram (unscheduled shutdown). Cause was control rod 2 dropping due to low magnet current. Corrective action taken was magnet current was increased five milliamps. SRO granted permission to restart reactor.

02/08/03 120% Full Power Rundown. Caused by noise spike from auto-controller. Reactor did not exceed 200kW. No corrective action was taken. SRO gave permission to restart reactor.

03/11/03 120% Demand Rundown. Caused by operator downscaling too many scales. Corrective action taken was instructing operator to only down scale one scale at a time. SRO granted permission to restart.

03/11/03 120% Demand Rundown. Caused by operator failing to upscale properly on the Linear Channel. Corrective action taken was to instruct operator to upscale at 60% on Linear Channel. SRO granted permission to restart reactor.

03/18/03 120% Demand Rundown. Caused by operator failing to upscale properly on the Linear Channel. Corrective action taken was SRO instructed operator to upscale at 60% and relieved operator at console. SRO permission granted to restart reactor.

03/18/03 120% Demand Rundown. Caused by operator downscaling improperly on the Linear Channel. Corrective action was the SRO instructed the operator to shut down reactor.

03/19/03 120% Demand Rundown. Caused by operator not downscaling properly on the Linear Channel. Corrective action taken was SRO instructed operator to upscale at 60%. SRO granted permission restart reactor.

Table 3-3. Maintenance for 2002-2003 Date Problem/Event and Action Taken 04/05/02 Problem: Electrical wiring verification.

Corrective Action: Turned off power to allow verification of wiring. Wiring verification completed. Restored power to control room.

05/20/02 Problem: Electrical upgrade to control room.

Corrective Action: Removed power to the control room. Electrical upgrade completed.

Restored power to control room.

06/04/02 Problem: Replacement of Safety Channel and Magnet Power Supply.

Corrective Action: Installed and tested new Safety Channel and Magnet Power Supply.

06/12/02 Problem: Auto-controller not responding to drifts in reactor power.

Corrective Action: Removed and cleaned all cable pins. Removed and cleaned pins on

9 C17-C20. Tested with source.

06/28/02 Problem: Semi-annual calibration started.

Corrective Action: Completed semi-annual calibration.

07/17/02 Problem: Startup channel would not show more than two counts per second.

Corrective Action: Replaced four transistors and one resistor on the pre-amp.

07/26/02 Problem: Spare Startuap Channel pre-amp not operable.

Corrective Action: Replace four transistors, removed existing pre-amp, replaced with spare, and tested unit.

07/30/02 Problem: Beamport shutter will not close.

Corrective Action: Removed motor and tighten set screw on shaft.

08/09/02 Problem: Control rod visual surveillance.

Corrective Action: Performed annual control rod visual inspection. Performed rod drop time tests 12/23/02 Problem: Semi-annual calibration started.

Corrective Action: Completed semi-annual calibration.

01/10/03 Problem: Rod Drive #1 brake not holding.

Corrective Action: Remove Rod Drive #1 actuator from bridge, replaced solenoid, and brake band. Installed actuator and tested rod height indicator.

01/10/03 Problem: Rod #3 magnet current is fluctuating.

Corrective Action: Removed magnet #3 from the pool. Replaced magnet coil. Installed into pool and performed rod drop time test.

01/15/03 Problem: Rod Drive #3 actuator not holding.

Corrective Action: Removed Rod Drive #3 actuator from bridge, replaced solenoid, and brake band. Installed actuator and tested.

10 Table 3-4. Reactor Utilization

1.

Reactor use 416.0 hrs.

2.

Time at power 148.1 hrs.

3.

Energy generated 12861.6 kW/hrs

4.

Total number of samples Neutron Irradiated 155 Gamma Exposure 320

5.

U-235 Burned 0.6601 g

6.

U-235 Burned and Converted 0.6630 g Table 3-5. Experimental Facility Use Other Than The Reactor Facility Hours Bare Rabbit Tube 4.05 hr.

Cadmium Rabbit Tube 0.02 hr.

Beam Port 1.92 hr.

Other Core Positions 2,048 hr.

Total 2054 hr.

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

Over 2,968 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 lists some of the major occasions or groups and number of visitors for each event.

Table 4-1. Public Relations Program 2002-2003 DATE PARTICIPANTS NUMBER 04/09/02 Omron Transaction Systems, facial identification 2

04/19/02 Tour, Representatives from the Republic of Georgia 8

04/13/02 Spring Open House 63 04/02/02 TJ South 22 04/17/02 UMR Family Tour 8

04/19/02 Pro Day 26 6/9/02-6/14/02 UMR Jackling Session I 44 6/17-6/17/02 UMR Jackling Session II 31 6/23-6/29/02 UMR Jackling Session III 34 6/23-6/25/02 UMR Introduction to Engineering, Admissions 46 7/8-7/12/02 UMR Introduction to Engineering, Admissions 75 07/19/02 UMR Tour for Prospective Students 8

7/21-7/26/02 UMR NE Summer Camp Session I 14 7/21-8/02/02 UMR NE Summer Camp Session II 33 7/21-8/2/02 UMR Jackling II 22 7/28-8/02/02 UMR NE Summer Session II 16 08/01/02 UMR NE Summer Camp half life 16 08/02/02 UMR Tours, 2 groups, half life / blue glow 41 09/29/02 ABET Tour 10 10/12/02 Tour, Mike Evans, President of INPO 2

11/09/02 Open House for UMR 23 12/06/02 International Affairs, group 7

12/06/02 UMR Blue Glow Tours 72 12/07/02 UMR Open House Blue Glow Tours 84 12/18/02 Cub Scouts 12 1/10/03 Highway Patrol 3

02/22/03 Cub Scouts 22 TOTAL FOR 2002-2003T 744 11

12 5.0 EDUCATIONAL UTILIZATION The reactor facility supported several UMR courses in the past year for a total of 3,886 student-hours. The number of UMR students utilizing the facility was 544. This usage is a direct result of an aggressive and continuing campus wide "outreach" program. The reactor facility provided financial support for four students with hourly wages, and one Graduate Research Assistants. Additionally, students from several universities, colleges and high schools have used the facility.

Table 5-1 lists UMR classes taught at the facility along with associated reactor usage for this reporting period.

The University of Missouri-Columbia Nuclear Engineering Department again sent its NE 404 class, "Advanced Reactor Laboratory," to our facility (Spring, 2003) for a total of 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> to participate in a wide variety of reactor experiments that they are unable to perform with their reactor. The laboratory was held from mid-afternoon to the evening (2:00 pm until 9:00 pm) and conducted by the UMR reactor staff.

The Reactor Sharing Program, which is funded by the U.S. Department of Energy, was established for colleges, universities, and high schools which do not have a nuclear reactor. This past year, 408 students and instructors from 29 institutions participated in the program. Table 5-2 lists those schools and groups that were involved in this year's Reactor Sharing Program. The majority of our participants were high school students. We coordinate with the Admissions Office to schedule high school students to see other items of interest at UMR after they have visited our facility, such as the student group 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 getting high school students to the university and hopefully sparking some interest in nuclear engineering, science, and technology.

13 Table 5-1. UMR Classes at Reactor Facility 2002-2003 Reporting Period WS-Winter CLASS NUMBER/TITLE

  1. OF TIME AT STUDENT FS-Fall STUDENTS REACTOR HOURS WS02 NE 25 8

4 32 WS02 NE 306 4

30 120 WS02 NE 308 10 30 300 WS02 NE 300 2

30 60 SS02 NE 490 1

36 36 S02/FSO OURE (Ken Morrison, Will Atkins); Distance 2

45 90 Learning & Remote Monitoring S02/WSO Reactor Operator Trainees 15 24 360 3

S02 OURE (Chris Byrum); Design of a robotic arm 1

7.5 7.5 for control rod inspection S02 NE 304 6

30 180 S02 NE 306 11 30 330 FS02 NE 300 2

30 60 FS02 NE 490 1

45 45 WS03 NE 308 6

30 180 WS03 NE 306 9

30 270 FS02 Chemistry Labs (half-life); Dr. Terry Bone 389 0.5 194.5 4/29/02 Physics 107; Dr. Pringle 24 1

24 S02 NE 400; UMC Students 4

16 64 fs02 NE 25 13 5

65 FS02 NE 105 13 1

13 S03 NE 204 15 1

15 2/03 Research Dr Bertino 1

62 2

12/06/03 Physics 107, Dr. Pringle 17 1

17 TOTALS FOR 2002-2003 554 489 2465

14 Table 5-2. Reactor Sharing Program (2002-2003)

DATE PARTICIPANTS Number 04/02/02 Thomas Jefferson High School 16 04/08/02 Lynn High School 14 04/08/02 World Youth in Science & Engineering 17 04/09/02 South Western Missouri State University 9

04/13/02 Spring Open House 16 04/16/02 Fort Leonard Wood Chemical School Trainees 10 04/17/02 Hazelwood East High School 20 04/17/02 NE 25 7

04/29/02 Physics 6 23 05/16/02 Fort Leonard Wood Tour 14 06/20/02 M.I.T.E. Michelle Schoenborn 41 08/02/02 Central High School 18 09/23/02 Fort Leonard Wood Chemical School Trainees 7

09/30/02 Fort Leonard Wood Chemical School Trainees 11 10/22/02 East Central College 23 10/29/02 Mansfield High School 5

11/06/02 Parkway West High School 16 11/12/02 Fairview K-8 50 Rolla High School 25 12/03/02 Marshfield High School 5

12/18/02 Boy Scouts 12 02/07/03 Rolla Middle School Job Shadowing 3

02/10/03 Waynesville High School 14 03/17/03 Fort Leonard Wood Chemical School Trainees 14 03/24/03' Charles Beasley 1

03/28/03 Charles Beasley 1

03/31/03 NE 404 10 High School Students 2002-2003 Alfred Schovanez (Washington, MO) Neutron Exposure to Zener. diodes 1

2002-2003 Justin Munson (Warsaw, MO) Neutron Exposure to Diodes 1

2002 Kevin Johnson, (West Plains, KS) Neutron Exposure to TTL & CMOS 1

2002 Keong Kam (Overland Park, KS) Gamma Exposure to Zener Diodes 1

2003 Matt Krantz (Loudon, TN) Gamma exposure to TTL Logic chips 1

2003 Matt McCreary (Arnold, MO) Gamma exposure to TTL & Logic chips 1

TOTAL FOR 2002-2003 408

15 6.0 REACTOR HEALTH PHYSICS ACTIVITIES The health physics activities at the UMR Reactor Facility consist primarily of radiation and contamination surveys, monitoring of personnel exposures, airborne activity, pool water activity and waste disposal. Releases of all by-product material to authorized, licensed recipients are surveyed and recorded. In addition, health physics activities include calibrations of portable and stationary radiation detection instruments, personnel training, special surveys and monitoring of non-routine procedures.

6.1.

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.

6.2.

By-Product Material Release Surveys There were no shipments of by-product material released off-campus from the reactor facility. There were no shipments released on-campus.

6.3.

Routine Monitoring Fifty-two reactor facility personnel and students involved with the operations in the reactor facility are currently assigned Luxel, optically stimulated luminescence (OSL) dosimeters.

Four (Reactor Staff) have beta, gamma, neutron dosimeters which are read twice a month. There are four area beta, gamma, neutron dosimeters and one TLD ring dosimeter, which are read monthly. The remaining dosimeters detect beta and gamma radiation only and are read monthly.

There are 23 area dosimeters assigned on campus for beta and gamma monitoring and one for beta, gamma, and neutron monitoring. In addition, 5 digital, direct-reading dosimeters, 5 chirpers and 2 pocket ion chamber dosimeters are used for visitors and high radiation work. There have been no significant personnel exposures during this reporting period. Visitors are monitored with direct reading dosimeters. No visitors received any reportable nor significant exposure.

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

16 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 2002 through March 2003 sample concentrations averaged 2.02xlZ IOLCi/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 3.83 millicuries of Ar-41 were released into the air.

6.4.

Waste Disposal Solid waste, including used water filters, used resins and contaminated paper is stored and/or transferred to the campus waste storage area for later shipment to a commercial burial site.

Water is analyzed for radioactive contamination and approval is required before the water is released. During this period no waste was transferred from the Reactor Facility.

6.5.

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

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

7.1 Administrative Changes UJMRR is presently fully staffed. Mrs. Maureen Henry has filled the vacant Senior Secretary position as of July 22, 2002. Mr. Dan Estel, who served as Interim Senior Laboratory Mechanic from December 9 h, 2002 has recently been appointed permanently as Senior Laboratory Mechanic.

17 7.2.

Relicensing Relicensing activities will continue during the upcoming reporting period. Our present license has been extended and is valid until January, 2005. Emphasis will be directed toward the SAR accident scenarios and Emergency Plan.

7.3.

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

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

7.4.

Instrumentation Upgrade The reactor console upgrade is well underway. Several pieces of new equipment have been installed under the provisions of 10 CFR Part 50.59. New Safety Channels and a magnet power supply were installed in Spring of 2002. The Linear drawer maybe replaced during the upcoming reporting period. Most of the changes will be made under the provisions of 50.59; however, some changes may require NRC approval.

7.5 Reactor Operator Training The second annual group of reactor operator trainees took the NRC examination during the week of March 10, 2003. Twelve applicants tested for reactor operator licenses, with an additional three UMRR operators performing the SRO upgrade exams. Test results from NRC are expected during the month of April 2003. Six student ROs remain active at the reactor.

18 APPENDIX A.

STANDARD OPERATING PROCEDURES CHANGED DURING THE 2002-2003 REPORTING YEAR

CbNhiu, LiI C0PY

  • $* UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Page Revision: June 7, 2002 Pages of 8

21. 150% Power Scram Check:
a. Withdraw the 'oto3 inches.
b. Depress the scram test button on the Safety Amplifier
c. Verify that a scram occurs before 150%.
d. Verify that the 150% annunciator light and the audible alarm is activated.
e. Depress the reset button on the Safety Amplifier 1
f.

Reset the annunciator panel and insert magnets

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

Record results RevA a Rev

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

Withdraw the shim rods to 3 inches.

b.

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

c.

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

d.

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

e.

Stop the rundown with the rundown reset button.

f.

Reset the scram, rundown, and annunciator panel.

23. Period Trip Test:
a.

Withdraw the shim rods to 3 inches.

b.

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

c.

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

d.

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

e.

Release the switch.

f.

Reset the scram, rundown, and annunciator panel.

24. Manual Scram:
a.

Raise shim rods to 3 inches.

b.

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

c.

Push the scram reset button and reset the annunciator panel.

Revised By: William Bonzer

'NV1 "I'II Approved By: Akira Tokuhiro g

l-) _

co 0iia CuPY aUMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Revision:

June 7 2002 Page 7 of 8

1. Date
2. Initials of the Person Performing Checklist l
3. Time (Console Clock)
4. Core Loading
5. P.A., Intercom, Video Monitor On
6. RAM System Check
7. Radiation Level Normal
8. Beam Port and Thermal Column Status (OPEN or SHUT) l
9. Linear Channel Zero Meter Reading l

Scale

=

_=__

10. Linear C.I.C. Voltages HV (-540) l CV (-2 to 8)

=

=_ _

I11. Recorders On, Dated, "RCD" Light On Temp. & CAM Recorders

12. Core Check (Lights On)

Level Check l

In~~spect Core==

Source Inserted

13. Start-Up Channel Test Am p
14. Verify FC Response, FC Inserted, Count Rate > 2 CPS

=

15. Log Count Rate HV Power Supply (+400 VDC) l
16. Log and Power Range Test

=

=

_=

17. Period Response Test 11
18. Magnet Power On, Scram Reset, Board Reset

=

=

F

19. Inlet Temperature (OF)___

IRe

~av.

Revised By: William Bonzer 6L~wv-Approved By: Akira Tokuhiro

    • UMR REACTOR STANDARD Cap SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Revision: June 7.

2002 Page8 of 8

20. Magnet Currents (milliamps)

No. 1

-=

=

=

[

No. 2 l

No.3 3

21. 150% Power Safety Amplifier I Raise Rods 3 in. Push Scram Test "Test" Button Safety Amplifier 2
22. Log and Linear Drawer Non-Operative Raise Rods 3 in. Press Scram Test NON-OPER switch.

l

23. Period Trip Test

=

=

=

24. Manual Scram Test Raise Rods 3 in. Push ll Manual Scraml
25. Annunciator Test, All Lights On
26. Magnets On, Rods on Insert Limit
27. Prepare Hourly and Permanent Logs

=

_=___

28. Detector Response Check Inspect Core Log Spike

=

Period Spike Linear Spike Startup Channel

Response

29. Raise Rods to 6 in., Record Time in Both Logs
30. Nitrogen Diffuser Status No. Ill (ON or OFF)No2_

No..,

31. Intended Power Level
32. Announce Intention to Start
33. Pre-Startup Check Properly Completed (Lic. Op. Initials) l
34. Senior Operator's Initials
35. Date Rev.

Rev.

Revised By: William Bonzer Approe y: Alira Tokulhiro

SOP: 501

      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

TITLE:

EMERGENCYPROCEDURES FOR REACTOR BUILDING EVACUATION Revised: July 29, 2002 Pge707 UMR REACTOR EMERGENCY PHONE LIST Reactor Staff Cell -

Pager HOME WORK Brian Porter, Sr. Electronics Tech.

368-3090 3414291 Jim Jackson, Sr. Lab Mechanic,SRO (573)699-4897 3414291 Rev.

William Bonzer, Manager, SRO 465-5544 368-3727 341-4384 Akira TokuhiroDirectorSRO 578-0542 428-6420 368-7121 341-4746 Ray Bono, Health PhysicistlRadiation Safety Officer 428-6469 364-5728 341-4240, 4305, 4403 Maureen Henry, Sr. Secretary 364-7272 341-4236 Rev.

University Administrative Staff

1. Director, UMR Police, William Bleckman 364-1294 341-4345
2. Chancellor, Gary Thomas 368-3552 341-4114
3. Vice Chancellor for Admin.Services, Steve Malott 364-7927 3414122
4. Director, Physical Plant, Marvin Patton 364-6278 3414252
5. Director, Health Service - Infirmary, Dwight

Deardeuff,

MD 364-0809 341-4284

6. Dean, School of Mines and Metallurgy, Lee W. Saperstein578-0602 368-3782 341-4153
7. Radiation Safety Officer, Ray Bono 428-6469 364-5728 341-4240 4305,4403 Local UMR University Police Rolla City Police.

Rolla Fire Department Phelps County Hospital Rolla Emeriencv Management Agency 341-4300 341-4111 9-911 9-911 9-911 9-911 State Agencies Missouri Highway Patrol Missouri State Emergency Mgt. Agency (24 hr.)

Missouri Dept. of Natural Resources (24 hr.)

Missouri Bureau of Environmental Health (573) 751-6160 368-2345 (573) 751-2748 (573) 634-2436 (573) 751-4674 (after hrs)

Federal Agencies NRC, Lisle, IL, Region m NRC Duty Officer (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) (call first) (301) 816-5100 1-800-522-3025 (301) 951-0550 (301) 415-0550 (back up #)

Other American Nuclear Insurers Radiation Emergency Assistance Center Revised: July 29,2002 (860) 561-3433 (865) 576-3131 (865) 576-1005 (24hrs)

.LQQ)La" D

William Bonzer pproved By: Akira Tokuhiro Revised By:

SOP: 501

      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

TITLE:

EMERGENCY PROCEDURES FOR REACTOR

-BUILDING EVACUATION Revised: September26,2002 Page 7 of 7 UMR REACTOR EMERGENCY PHONE LIST Reactor Staff Brian Porter, Sr. Electronics Tech.

Jim Jackson, Sr. Lab Mechanic, RO William Bonzer, Manager, SRO Akira Tokuhiro,Director Ray Bono, Health Physicist Maureen Henry, Sr. Sec.

Cell 465-5544 578-0542 Pagrer HOME 368-3090 (573) 699-4897 368-3727 364-1961 428-6469 364-5728 364-7272 WORK 341-4291 341-4291 Rev.

341-4384 341-4746 341-4240 4305 4403 341-4236 University Administrative Staff

1. Director, UMR Police, William Bleckman 364-1294 341-4345
2. Chancellor, Gary Thomas 308-8240 368-3552 341-4116
3. Vice Chancellor for Admin.Services, Steve Malott 364-7927 341-4122
4. Director, Physical Plant, Marvin Patton 364-6278 341-4252
5. Director, Health Service:- Infirmary, Dwight

Deardeuff,

MD 364-0809 341-4284

6. Dean, School of Mines and Metallurgy, Lee W. Saperstein578-0602 368-3782 341-4153
7. Radiation Safety Officer, Nick Tsoulfanidis 341-3595 341-4745 Local UMR University Police 341-4300 341-4111 Rolla City Police 9-911 Rolla Fire Department 9-911 Phelps County Hospital 9-911 Rolla Emergency Management Agency 9-911 Rev.

State Agencies Missouri Highway Patrol Missouri State Emergency Mgt. Agency (24 hr.)

Missouri Dept. of Natural Resources (24 hr.)

Missouri Bureau of Enviromental Epidemiologv 368-2345 (573) 751-2748 Rev.

(573) 634-2436 (573) 751-4674 (24hrs)

(573) 751-6160 Federal Agencies NRC, Lisle, IL, Region III NRC Duty Officer (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) 1-800-522-3025 (301) 415-0550 (301) 816-5100 (301) 951-0550 Other American Nuclear Insurers Radiation Emergency Assistance Center Revised 07/26/02 (860) 561-3433 (423) 576-3131 (865) 576-1005 (24hrs)

Rev William Bonzer

':5- z' "

Revised By:

Approved By: Akira Tokuhiro

      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 501 TITLE: EMERGENCY PROCEDURES FOR REACTOR BUILDING EVACUATION Revised: January 6, 2003 Page 7 of 7 UMR REACTOR EMERGENCY PHONE LIST Reactor Staff Brian Porter, Sr. Electronics Tech.

William Bonzer, Manager, SRO Akira Tokuhiro, Director, SRO Daniel Estel, RO Ray Bono, Radiation Safety Officer Jim Jackson, SRO Maureen Henry, Sr. Sec.

Cell 578-9463 578-0542 Pager HOME WORK 368-3090 341-4291 368-3727 341-4384 364-1961 341-4746 (573) 435-6820 341-4291 428-6469 364-5728 341-4240,4305,4403 (573) 699-4897 341-4258 364-7272 341-4236 Rev.

University Administrative Staff

1. Director, UMR Police, William Bleckman
2. Chancellor, Gary Thomas 308-8240
3. Vice Chancellor for Admin.Services, Steve Malott
4. Director, Physical Plant, Marvin Patton
5. Director, Health Service - Infirmary, Dwight

Deardeuff,

MD

6. Dean, School of Mines and Metallurgy, Lee W. Saperstein 578-0602
7. Radiation Safety Officer. Rav Bono 428-6469 364-1294 368-3552 364-7927 364-6278 364-0809 341-4345 341-4116 341-4122 341-4252 341-4284 368-3782 341-4153 364-5728 341-4240,4305,4403

.ev.

Local UMR University Police Rolla City Police Rolla Fire Department Phelps County Hospital RollaR meraenev Management Agencv 341-4300_ Rev.

9-911 9-911 9-911 9-911 State Agencies Missouri Highway Patrol Missouri State Emergency Mgt. Agency (24 hr.)

Missouri Dept. of Natural Resources (24 hr.)

(573) 368-2345 (573) 751-2748 (573) 634-2436 Missouri Bureau of Environmental Epidemiology (573)751-6160 (573) 751-4674 (24hrs)

Federal Agencies NRC, Operations Center (301) 816-5100 Rev.

NRC Duty Officer (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)

(301) 816-5100 l

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

W il 1ia onen William Bonzer I

I q /

Approved By:

To ro Revised By:

GOO YIO i

UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 653 TITLE: SEALED SOURCE LEAK TEST Complete Revision:

March 20, 1995 Page 1 of 2 A.

PURPOSE To ensure the integrity and encapsulation of sealed sources and to guard against contamination of personnel.

B.

PRECAUTIONS. PREREQUISITES. OR LIMITATIONS 1.

This procedure is to be performed by Health Physics staff personnel.

2.

The following sources located at the reactor facility are to be leak tested semi-annually: PuBe S/N M-1092 (Reactor Startup Source), PuBe SIN M-169 (RAM e

Calibration Source), Cs-137 S/N-549RAM Calibration Source). Th v

)s 3 7

3.

Leak test requirements are listed in item 14 (A through F) of NRC Materials License A7 number 24-00513-40.

lo/if{ x C.

PROCEDURE

1.

The leak test should be performed with filter-paper discs or with cotton-tipped applicators depending upon the source activity, configuration, and containment.

2.

The source, source holder, and immediately surrounding area should be rubbed firmly with the swipes held with tongs or forceps or with cotton-tipped applicators in order to remove any surface contamination that may be present. If access to the sealed source is prevented by the construction of the device, the swipes should be taken as near the source as possible.

3.

Each swipe or applicator should be placed in a separate envelope appropriately labeled for identification.

4.

Frisk the swipes with an open window G-M probe. If any detectable activity is observed above background, contact the Reactor Health Physicist for appropriate approvals before removing the swipe from the facility. If no detectable activity is identified, the swipes may be removed from the facility for counting at the Health Ph ics office.

Revised By:

ono Approved By: Albert Bolon

      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 655 TITLE: RADIATION AREA MONITOR (RAM) CALIBRATIONS Revised:

February 17, 1997 Page 1 of 6 A.

PURPOSE To provide for the efficient calibration of the fixed Radiation Area Monitors and to minimize personnel exposure during the calibration.

B.

PRECAUTIONS. PREREQUISITES. OR LIMITATIONS LU6

1. The RAMs are to be calibrated annually.

1 A

aX

2.

The Cs-137 source shall be kept inside the shield. Only the plug will be removed from Rev.

the shield when the detector is to be exposed to the Cs-137 source.

3.

The person-who handles the Cs-137 source must wear a minimum of a pocket dosimeter and a film badge.

4.

The person who handles the neutron source shall wear a neutron dosimeter. Ring badges are optional but advisable.

5.

The person who handles the source should minimize their exposure time in close proximity to the source.

6.

The reactor must be shutdown and only authorized personnel allowed in the calibration area during the calibration to prevent accidental exposure while the sources are being handled. If a whole body dose > 100 mrem could be received, high radiation area Rev.

control is required.

7.

Notify the Reactor Manager prior to performing this procedure.

C.

PROCEDURE - GAMMA RAM CALIBRATION

1. Calculate Source to Detector Distances: Calculate source to detector distances to provide target dose rates of 2 mrem/br, 20 mrem/hr, and 200 mrem/hr. Use the inverse Rev.

square law (DR,/DR2 = d22/dj2) and the exponential decay law (DR, = DRae-).

SJA 294 The Cs-137 source (SNAG49-) was certified to read 114.4 mrem/hr at a distance of 1.64

!L/'Ki ft (19.68 inches) on July 23, 1979. The haiflife of Cs-137 is 30.17 years.

AT Revised By: William Bonzer Approved By: DaOYjreeman

t f:;L -

11 P1 I r L

~

CONT fl

_0i-SOP: 655 Revised:

      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

TITLE: RADIATION AREA MONITOR (RAM) CALIBRATIONS February 17, 1997 Page5 of6 Gamma RAM Calibration Form SV 7Y Source (SN-5I49-) Decay Time (since July, 1979):

(years)

L1,4 3 Calculated Source Target Dose Measured Dose Rates to Detector Distance Rate l

(inches)

(mrem/hr)

Reactor Bridge Demin Level Beam Room I

(mrem/hr)

(mrem/hr)

(mrem/hr) 2+0.4 20+4 200+ 40 l

l l

Rev.

Alarm setpoints reset verified All readings are within +/-20% of Target Dose Rates.

(Initials)

(Initials)

Calibration Performed By:

Date

/

/

Approved By:

Date

/_/

Reactor Manager Approved By:

Date _

/__

Health Physicist Revised By: William Bonzer tLe 2cZt w

Appro avid Freeman PpvOFV

      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 800

Title:

SEMI-ANNUAL CHECKLIST Date Revised: June 7, 2002,r l

5 11 KUL

~5 of 10

b.

Fission Chamber Preamp Initial Date (1) Cleaned chassis as needed (2) Additional Comments

c.

Log Count Rate Channel Calibration (Note:

All readings should give 0.7 to 1.4 ratio of true-to-observed readings.)

Pulse Generator 10 100 1,000

_ 10,000 Meter RecorderInitial Date

d.

High Voltage (350 VDC to 450 VDC)

5.

Reconnect all cables Reconnection of cables verified

4.

Safety Amplifier System

a.
  • UIC 1 Signal
  • UIC 1 H.V.
  • UIC 2 Signal
  • UIC 2 H.V.

MegOhms MegOhms

_MegOhms MegOhms Rev

b.

Safety Amplifier 1 Current Tests Applied Accepted Digital Accepted Bar Current Digital Display Bar Graph Graph Digital Display Reading Display Display 6.7nA 9-11%

7-13%

13.2nA 19-21%

17-23%

19.8nA 29-31%

27-33%

26.4nA 39-41% l 37-43%

33.OnA 49-51%

47-53%

39.6nA 59-61%

57-63%

46.2nA 69-71%

67-73%

52.8nA 79-81%

77-83%

59.4nA 89-91%

87-93%

66.OnA 99-101%

97-103%

72.6nA 109-111%

107-113%

79.2nA 119-121%

117-123%

85.8nA 129-131%

127-133%

92.4nA 139-141%

- 133-143%

99.OnA 149-152%

147-153%

Revised By: William Bonzer Approved By: Akira Tohuhiro,

      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

Title:

SEMI-ANNUAL CHECKLIST SOP: 800 Date Revised: June 7, 2002 C""ON TROLLED COPY 6 of 10 Safety Amplifier 1 Current Tests Applied Accepted Digital Accepted Bar Current Digital Display Bar Graph Graph Digital Display Reading Display Display 6.7nA 9-11%

7-13%

13.2nA 19-21%

17-23%I 19.8nA 29-31%

27-33%

26.4nA 39-41%

37-43%

33.0nA 49-51%

47-53%

39.6nA 59-61%

57-63%

46.2nA 69-71%

67-73%1 52.8nA 79-81%

77-83%1 59.4nA 89-91%

87-93%

66.OnA 99-101%

97-103%

72.6nA 109-111%

107-113%

79.2nA 119-121%

117-123%

85.8nA 129-131%

127-133%

92.4nA 139-141%

133-143%

99.OnAll 149-152%

147-153%

Rev

c.
  • H.V. 1 Output Voltage
  • MonitorH.V. 1/100
  • H.V. 2 Output Voltage
  • Monitor H.V. 2/100
d.

H.V. 1 Failure Test

__VDC

__VDC

__VDC VDC

  • Trip Point Setting
  • Audible Alarm (y/n)
  • Scram Occurred (y/n)
  • Magnet Power Supply SCRAM Light Illuminated (y/n)
  • Reset H.V; to 300VDC (y/n)

__VDC Revised By: William Bonzer t5u 1,~Lv.Zw5YA Approved By: Akira Tokuhiro,

~,LG

M**

R REACTOR STANDARD OPERATING PROCEDURES ***

Title:

SEMI-ANNUAL CHECKLIST SOP: 800 Date Revised: June 7, 2002 2r

^RtA g

H.V. 2 Failure Test 7 of 10 e.

  • Trip Point Setting
  • Audible Alarm (y/n)
  • Magnet Power Supply SCRAM Light Illuminated (y/n)
  • Reset H.V. to 300VDC (y/n)
f.

NIM Bin Power Supply Output Voltages

  • +24VDC tev

-24VDC

  • +12VDC
  • -12VDC
  • +6VDC
  • -6VDC
g.

AC Power Off (y/n)

  • Audible Alarm (y/n)

Safety Amplifier System Tests Completed

5.

PAT 60 Controller

a.

PAT 60 (1) Cleaned chassis as needed

b.

Check dial settings and record the following (1) Approach (2) Proportional Bank (3) Rate Time (4) Reset (5) Gain (if applicable)

__VDC VDC

__VDC VDC

__VDC

__VDC (Initials)

.(date)

Initial Date Setting Initial Date Revised By: William Bonzer Approvi

      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

Title:

SEMI-ANNUAL CHECKLIST SOP: 800 Date Revised: Juiie 7, 2002

'OgI r uLW 8 of 10 I - - I

v

-I

o.

I emperature Channel (Note: All readings should be + 20F.)

a.

Verification of Temperature Readings Date Rev

b.

Temperature > 1350 Rod Withdrawal Prohibit Test ll Thermocouple #1 I Thermocouple #3 1

>135OF Trip Temperature I

>135 0F Annunciator Audible Alarm Rod Prohibit Withdrawal Initials

7. Regulated Power Supply
a.

Cleaned chassis as needed

b.

Additional comments

8. Conductivity Bridge
a.

Cleaned chassis as needed

b.

Additional comments Initial Date Revised By: William Bonzer wA lav.W Approved B: Akira Tokubiro An/{

SOP: 800 Date Revised: Jur

      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

Title:

SEMI-ANNUAL CHECKLIST ie 7, 2002

9.

Rod Indicator Calibration Actual Height Rod 1, R

I--u..IiELL COP Y 9 of 10 Initial Date

.od 2 Rod 3 Reg. Rod 1"

6" 12" 18" 24"

10. Fire Alarm Check
a.

Cleaned system containers as needed

b.

Checked batteries

c.

Checked pull stations

d.

Checked heat detectors

e.

Checked smoke detectors f All indicator lamps operate Initial Date Rev

11. Security System Check
a.

Door Sensors

b.

Motion Detectors

c.

Tamper Switch

d.

Duress Alarm

e.

Battery

f.

High Radiation

g.

Low Pool Water

h.

Additional Comments:

Initial Date

12. Public Address System
a.

Cleaned chassis as needed

b.

Additional Comments

13. Hand and Foot Monitor
a.

Cleaned chassis as needed

b.

Perform Source Check

1. Additional Comments
14. Portal Detector
a.

Cleaned chassis as needed

b.

Perform Source Check

c.

Additional Comments Revised By: William Bonzer UUn.

,a,

Approved By: Akira Tokuhiro I

A1

1M REACTOR STANDARD OPERATING PROCEDURES SOP: 800

Title:

SEMI-ANNUAL CHECKLIST Date Revised: June 7,2002 1 0 of 10 Ue~itLLEO G~Ur

15. Constant Air Monitor
a.

Cleaned chassis and recorder as needed

b.

Perform Source Check

c.

Additional Comments

16. Rod Drop Test (SOP 813)
17. Power Calibration (SOP 816)
18. Thermal Column Open Alarms - Verify that the control room audio and visual alarms, and the basement red flashing light comes on when the thermal column is opened by about 1 inch.

Verify that the alarms clear when the thermal column door is closed.

19. RAM Calibration - RAM Calibration shall be performed annually. Record the latest date the RAM calibration was performed.

I have reviewed the results of this Semi-Annual Check on this date and discussed any problems and/or errors with the operating staff.

Rev Director (Date) or Reactor Manager (Date)

Revised By: William Bonzer tlt-QI Q '

Approved By: Akira Tokuhiro

      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 804 TITLE: Safety Amplifier System Complete Revision:

June 7,2002 Page 1 of 2 A.

PURPOSE To ensure that the safety amplifier system is operational.

B.

PRECAUTIONS, PREREQUISITES AND LIMITATIONS 1

In accordance with Technical Specification 4.2.2 all console instruments and safety system shall be calibrated twice each year, not to exceed 7-1/2 months.

2 After each item is completed, a second knowledgeable person will check connections (where connections have been broken and reconnected) to ensure that the equipment is connected and on line.

3 A licensed operator must be in the control room when using the magnet key.

4 Record values on semi-annual checklist SOP 800.

C.

PROCEDURE 1

Disconnect the H.V. and signal cables from Safety Amplifiers 1 and 2.

2 Measure and record the cable resistance of each cable.

3 Discharge each cable with a DMM before reconnecting to the safety amplifiers.

4 Connect the pico-amp source to Safety Amplifier 1 signal input and apply currents as listed in the semi-annual checklist. Record the Rev readings for the digital display and bar graph. If current readings do not meet listed tolerances adjust the safety amplifier as described per the technical manual. Repeat current tests until no further adjustments are necessary.

5 Perform step 4 for Safety Amplifier 2.

6 Record the H.V. 1 output voltage and voltage read at MONITOR H.V.

1/100 and COM.

7 Record the H.V. 2 output voltage and voltage read at MONITOR H.V.

2/100 and COM.

8 Raise control rods to three inches. Lower H.V. 1 to the trip set point to activate the H.V. 1 FAILURE light.

9 Record the High Voltage output at which the trip occurs.

Revised by William Bonze Approved by: Akira Tokuhiro LSO,,&LV \\LUvb.A

    • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 804 TITLE: Safety Amplifier System Complete Revision:

June 7, 2002 al,1JIJLD jI Page 2of 2 10 Verify and record that the 150% Full Power annunciator light is illuminated and the audible alarm is sounding.

11 Verify and record that the H.V. IFailure light is illuminated.

12 Verify and record that a scram has occurred.

13 Verify and record that the Magnet Power Supply SCRAM light is illuminated.

14 Reset HIV to 300 Volts.

15 Insert magnets.

16 Repeat steps 8 and 15 for H.V. 2.

17 Record each of the NIM Bin power supply voltages.

18 Raise the rods to three inches and turn off AC power to the Safety Amplifier's NIM Bin power supply.

19 Verify and record the 150% Full Power annunciator light is illuminated and that the audible alarm is sounding.

20 Verify and record that a scram has occurred.

21 Turn on AC power to the Safety Amplifier's NIM Bin.

22 Reset Safety Amplifiers 1 and 2.

23 Reconnect UIC cables to Safety Amplifiers.

Revised by William Bonzer p

b T

Approvedt by: Akira Tokuhiro e......

      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 810 TITLE: WEEKLY CHECK Revised: June 7, 2002 3

F R

L z,.MF Page 5 of II 3.2.A.

Non-Operative Scram and Rundown Test

a.

Withdraw rods to 3 inches.

b.

Depress the "NON-OPERATE" switch.

c.

Verify rods have dropped and control 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 that 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:

1 mA switch, 0.lI.A switch, 10 pA switch, and 3 SEC switch.

3.3. 150% Full Power Scram ao

a.

Withdraw the rods to 3 inches.

b.

Depress the scram test button on Safety Amplifier

c.

Verify that a scram occurred before 150%.

d.

Verify that the 150% annunciator light and audible alarm is activated.

e.

Depress the reset button on Safety Amplifier 1 f

Reset the annunciator panel and insert magnets

g.

Repeat steps a - f for Safety Amplifier 2.

h.

Record results Rev/

yz/4)

A-T Rev 3.4. Manual Scram

a.

Withdraw rods to 3 inches.

b.

Push. Manual Scram button.

c.

Acknowledge the annunciator, observe Manual Scram light and all magnet contact lights are off. Push Scram Reset, Annunciator Reset and insert the magnets.

d.

Record results.

Revised By: William Bonzer If A-N5R~s9 Approved By: Akira Tokuhiro

,,7

SOP: 810 Revised. June 7.

    • UMR REACTOR STANDARD OPERATING-PROCEDURES ***

T=E: WEFKLY CHECK 2002.

Page 10 of II a Io N~

Date Performed

1.

Rod Prohibits 1.1. Recorder Off Source Range recorder Linear recorder Log/Period recorder Temperature recorder Alarms (/)

Prohilbit W)

Set Point

___ cps Alarms (/)

Prohibit (./)

1.2. Source Range <2 cps 1.3. InletTemperature>1350F

_F 1.4. Shim Rods below shim range N/A N/A

2.

Rundowns

2. 1. RAM Systc Station Bridge Demin Basement Rundown Set Point mrem/hr

__mre/hr

_mremAbr Bldg. Alarm Set Point mrem/hr NIA N/A Alarms fiV)

Remote and Local Alarm (4 Rundown Set Point Alarms (/)

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

(z440VDC) 2.5. Regulating Rod on Insert Limit on Auto VDC N/A

3.

Scrams 3.1. Bridge Motion Scram 3.2. Log and Linear Non-Op. Scram Non-operate switch (raise rods 3")

1mA switch 0.1 AA switch 10 pA swich 3 sec switch 3.3. 150% Full Power Scram Safety Amplifier I Safety Amplifier 2 3.4. Manual Scram Alarms (/)

Scramn i/)

IRev.

Revised By: William Bonzer roved By: Akira Tokuhiro

aOP1 U*

UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 102 TITLE: PRE-STARTUP CHECKLIST PROCEDURE Page Revision: June 7, 2002 Page 5of 8

21. 150% Power Scram Check.

C. c',

I

a. Withdraw the ods to 3 inches.
b. Depress the scram test button on the Safety Amplifier
c. Verify that a scram occurs before 150%.
d. Verify that the 150% annunciator light and the audible alarm is activated.

RI

e. Depress the reset button on the Safety Amplifier 1
f. Reset the annunciator panel and insert magnets
g. Repeat steps a - f for Safety Amplifier 2.
h.

Record results t'i

-Af-.A-(

(b-t

-i (4/c z

'eV

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

Withdraw the shim rods to 3 inches.

b.

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

c.

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

d.

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

e.

Stop the rundown with the rundown reset button.

f.

Reset the scram, rundown, and annunciator panel.

23. Period Trip Test:
a.

Withdraw the shim rods to 3 inches.

b.

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

c.

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

d.

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

e.

Release the switch.

f.

Reset the scram, rundown, and annunciator panel.

24. Manual Scram:
a.

Raise shim rods to 3 inches.

b.

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

c.

Push the scram reset button and reset the annunciator panel.

Revised By: William Bonzer

'I~w

-t7W Approved By: Akira Tokubiro

)S a

t"

COIPTFRLLEi COPY

      • UMR REACTOR STANDARD OPERATING PROCEDURES ***

TITLE: PRE-STARTUP CHECKLIST PROCEDURE 2002 Page 7 of 8 SOP: 102 Revision: "June 7. LwL

1. Date
2. Initials of the Person Performing Checklist l

ll

3. Time (Console Clock)
4. Core Loading
5. P.A., Intercom, Video Monitor On

==

=

=

l

6. RAM System Check
7. Radiation Level Normal
8. Beam Port and Thermal Column Status (OPEN or SHUT)
9. Linear Channel Zero l

Meter Reading

==_=__

Scale

10. Linear C.I.C. Voltages HV (-540) l CV (- 2 to 8)

I11. Recorders On, Dated, "RCD" Light On Temp. & CAM Recorders

12. Core Check (Lights On)

Level Check

-Inspect Core Source Inserted

_=_=_

13. Start-Up Channel Test
14. Verify FC Response, FC Inserted, Count Rate > 2 CPS
15. Log Count Rate HV Power Supply (+400 VDC)
16. Log and Power Range Test
17. Period Response Test
18. Magnet Power On, Scram Reset, Board Reset I
19. Inlet Temperature (OF)

Rev.

Pev.

LJIL

(

I A Revised By: William Bonzer Approved By: Akira Tokuhiro

19 APPENDIX B.REVISED SAR CHANGED DURING THE 2002-2003 REPORTING YEAR

3-38 3.5.6 Safety Channels E

N!

'A V -

11 I

. I.-i g.*.'



PI -.

O r - -

'W

.1-4 it.f.;.

is

-I Two redundant safety channels are a part of the reactor protection system. They provide the mechanism for scramming the reactor when power exceeds 150% of licensed full power. Each safety channel consists of an uncompensated ion chamber and a sensing circuit within the safety amplifier. A current to operate the magnets, which hold the shim/safety rods, is supplied from the magnet power supply A sensing circuit in each safety amplifier is capable of actuating a shut off of magnet current An indicator lamp located on the front of each safety amplifier becomes energized if reactor power should reach a predetermined limit. The safety amplifier scram circuit activates a shutting off of magnet current. An additional safety amplifier relay activates the 150% full power annunciator light and audible alarm. Magnet current will remain shut off until reactor power is below the predetermined set point and the safety amplifier reset switch is depressed.

The safety amplifier scram circuit will activate shut off of magnet current. The safety amplifier scram circuit consists of relay connections providing a current from the negative to positive input of the magnet power supply scram input. If a relay is actuated the magnet current will shut off. The safety amplifier scram circuit consist of relays from two safety amplifiers, two high voltage power supplies, a five second period trip, and the scram logic series containing bridge motion Log and Linear non-operative and manual scram circuitry described in section 3.5.8. In this way, the reactor will be scrammed not only if-the power level increases beyond a predetermined limit, but also if the reactor power level is increasing too rapidly. A test switch is mounted on the front of each safety amplifier to provide testing of the scram circuitry. The scram circuits are of a fail-safe design.

Rev

-;1 Safety amplifiers are contained in separate NIMs (Nuclear Insrumentation Module). High voltage power supplies for the ion.chambers are contained in a single NUV In the case offailure of either high voltage power supply, the scram circuit is actuated. Adi indicator light will illuminate on the high voltage NLM upon Rev failure of the high voltage power supply. The magnet power supply is contained inl a NIM. A SCRAM indicator lamp will illuminate on the magnet power supply when the safety channel scram circuit is initiated. The four NhIfs are located in a NIM Bin power supply, which provides power to each NIM.

3.5.7 Alarms, Prohibits, Rundowns, and Scrams There are a number of built-in engineered protective action levels derived-from the UMRR iumentaton. According to the degree of their severity, some of them require only the

3-43 and 3-44 be scrammed are summarized in Table IX.

g 3

A I 3.5.8 Scram Logic.

LLLi-z lp The scram logic circuitry for the 5 second period scram and the 150% full power scrams contained in the power safety amplifier are discussed in Section 3;5.6. In this section the logic and operation of the circuit processing bridge motion, Linear non-operative, Log and Linear non-operative, and manual scram signals will be described.

The scram circuit for the bridge motion, Linear non-operative, Log and Linear Son-operative and manual scrams consists of a set of open-on-failure relay contacts wired in series with a scram relay. Therefore, any of these scram signals or component failure will result in de-energizing the scram relay. This in turn opens the regulated power circuitry to the magnet current relay, thereby jRev cutting the current in the safety magnets and subsequently releasing the shim/safety rods. The scram relay can only be reset after the condition causing a scram has been removed and the reset relay energized by manually pushing the reset button.

The bridge motion scram is controlled by a micro-switch on the reactor bridge. As long as this switch is closed, a relay in the circuit is energized. A slight change in the position of the bridge, approximately 0.25 cm (0.1 in), will open the contact, de-energizing the motion relay which opens its contacts in the scram circuit.

As discussed in Sections 3.5.2 and 3.5.3, the status of the Linear drawer and the Log and Linear drawer are monitored by a Non-Operative circuits. If the +/- 15 VDC power supplies, CIC HV power supplies, or certain test switches are activated, the Non-Operative circuits de-energize a relay which breaks the scram circuit by de-energizing the scram relay thus causing a reactor scram.

Additionally, the Non-Operative relays also initiate a reactor rundown.

When the manual scram button is pressed two contacts are mechanically opened: one of them causes the scram relay to de-energize and another one interrupts regulated power to the magnet power supply. Hence, the ac power circuit to the magnet power amplifier is opened in two different and independent ways.

In addition, the scram circuit also contains contacts of the relay which monitors the unregulated ac power. In the case when electrical power is lost the scram circuit opens and initiates a reactor scram.

P4EW SAFETY CEIANNL 3YSYME343DEL-DOC May 31. 2002

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