ML070880933
| ML070880933 | |
| Person / Time | |
|---|---|
| Site: | 05000128 |
| Issue date: | 03/23/2007 |
| From: | Reece W Texas A&M Univ |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2007-0026 | |
| Download: ML070880933 (22) | |
Text
TEXAS ENGINEERING EXPERIMENT STATION TEXAS A&M UNIVERSITY 3575 TAMU COLLEGE STATION, TEXAS 77843-3575 NUCLEAR SCIENCE CENTER 979/845-7551 FAX 979/862-2667 March 23, 2007 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 2007-0026
Subject:
2006 Annual Report (Facility License R-83)
To Whom It May Concern:
Enclosed please find the 2006 Annual Report for the Texas A&M University Nuclear Science Center. If you have any questions regarding this, please feel free to call Latha Vasudevan, Jim Remlinger or myself at (979) 845-7551.
Sincerely, Dr. W. D. Reece, Director Enclosure LV/jg Xc:
21 1/Central File Annual Report File Jim Remlinger, Associate Director Latha Vasudevan, Radiological Safety Officer Aoob RESEARCH AND DEVELOPMENT FOR MANKIND http://nsc.tamu.edu
Texas A&M University Nuclear Science Center 2006 Annual Report Nuclear Science Center Texas Engineering Experiment Station Texas A&M University System College Station, Texas.
Texas A&M University System Texas Engineering Experiment Station Nuclear Science Center 2006 Annual Report Facility Operating License R-83 1095 Nuclear Science Road College Station, Texas 77843-3575 March 2007
Texas A&M University System Nuclear Science Center Annual Report 2006 CONTENTS
- 1.
Introduction..........................................................................................................................
4 1.1 N uclear Science Center Staff.............................................................................
5
- 2.
Reactor U tilization for 2006...........................................................................................
5 2.1 TAM U A cadem ic Support Program...................................................................
6 2.2 D OE U niversity Reactor Sharing Program.........................................................
7 2.3 Com m ercial A ctivity and External Research......................................................
7
- 3.
Facility and Procedure Changes....................................................................................
7 3.1 Facility M odifications.........................................................................................
7 3.2 Experiment Authorization and Modification Authorization...............................
8
- 4.
Reactor M aintenance and Surveillance..........................................................................
9 4.1 Scheduled M aintenance....................................................................................
9 4.2 Unscheduled M aintenance..................................................................................
9 4.3 Em ergency Planning and Review.....................................................................
10 4.4 Unscheduled Shutdowns..................................................................................
10 4.5 N otice of Violation...............................................................................................
11
- 5.
H ealth Physics Surveillance.........................................................................................
11 5.1 Radioactive Shipm ents...................................................................................
11 5.2 Personnel M onitoring......................................................................................
11 5.3 Facility M onitoring...........................................................................................
12 5.4 Particulate Effluent M onitoring.......................................................................
12 5.5 Gaseous Effluent M onitoring..........................................................................
13 5.6 Liquid Effluent M onitoring..............................................................................
15
- 6.
Environm ental M onitoring..........................................................................................
16 6.1 Environm ental Sam ples....................................................................................
16 6.2 Site Boundary D ose Rate.................................................................................
16
- 7.
Radioactive W aste Shipm ents......................................................................................
18
- 8.
Reactor Safety Board..................................................................................................
18 Appendix A: NSC Organization Chart....................................
19 Appendix B: Reactor Safety Board M embership....................................................................
20 2
Texas A&M University System Nuclear Science Center Annual Report 2006 List of Tables Table 2-1:
Reactor Utilization Summary in 2006................................................................
6 Table 3-1:
M odification Authorizations...............................................................................
8 Table 4-1:
Unscheduled M aintenance..................................................................................
9 Table 4-2:
Unscheduled Shutdowns..................................................................................
10 Table 5-1:
Total Dose Equivalent (mrem) Recorded on Area M onitors............................
12 Table 5-2:
Particulate Effluent Releases............................................................................
13 Table 5-3:
Gaseous Effluent (Ar-41) Releases...................................................................
14 Table 5-4:
Liquid Effluent Releases..................................................................................
15 Table 6-1:
Environmental Sample Analysis.....................................................................
16 Table 6-2:
Site Boundary Dose Rates..............................................................................
17 List of Figures
.Figure 2-1:
Annual Reactor Utilization.................................................................................
6 3
Texas A&M University System Nuclear Science Center Annual Report 2006
- 1.
Introduction The Texas A&M University (TAMU) Nuclear Science Center (NSC) is a multi-disciplinary research and education center supporting basic and applied research in nuclear related fields of science and technology as well as providing educational opportunities for students in these fields as a service to the Texas A&M University System and the state of Texas. The NSC also provides services to commercial ventures requiring radiation or isotope production services.
The NSC reactor is a 1 MW TRIGA research reactor in a large (108,000-gal.) pool. The size of the NSC reactor pool provides great flexibility in the types and sizes of experiments that may be placed near the reactor. The Science Center has a calibration facility using a Cs-137 calibrator, a neutron radiography facility, a large-object irradiation cell, hot cells and manipulators, and other supporting facilities.
Laboratory facilities include three counting laboratories with three High Purity Germanium detectors, a three-station pneumatics sample transfer system, a fast neutron irradiation system, a delayed neutron detection system, a film neutron radiography system, a large neutron/gamma irradiation cell, and two neutron beam ports.
The NSC reactor design allows for easy load/unload of various types of samples. The NSC actively produces a variety of radioisotopes for industry, hospitals, and academic users. The NSC provides nationally recognized neutron activation analysis (NAA) services to many research and academic institutions in the United States. The Nuclear Engineering Department on campus is a major user of the NSC reactor. The NSC is also one of the major attractions on campus. Last year, the NSC hosted 2151 visitors including: elementary, middle school, high school and college students as well as faculty members, national laboratory scientists and industrial clients. Through these tours, the NSC taught people with widely varying backgrounds about nuclear science.
With strong support from the University, the NSC is continuously increasing the diversity of its facilities and services. The NSC continues to perform research on developing a technique for the production of 1-125. The NSC and the Nuclear Engineering Department are part of the Innovations in Nuclear Infrastructure and Education Grant. As part of this, the NSC is building a robust neutron detection system and is producing the prototype for distance learning modules.
The NSC also refurbished the delayed neutron counting system and the neutron radiography system. The NSC is pursuing to set up a prompt gamma neutron activation analysis system.
At the end of December 2005, a Safety Accident and Analysis Report for the conversion of our current fuel to TRIGA 30-20 fuel was submitted to the NRC. In the second half of 2006, the NSC, with the assistance of General Atomics, Idaho National Labs and the Department of Energy, undertook the major projects of shipping spent LEU fuel, receiving new LEU 30/20 fuel and converting the core from TRIGA HEU to TRIGA LEU 30/20 fuel. The first step in this evolution was to ship spent LEU fuel to INL. In July of 2006, the NSC completed the packaging and shipment of 82 spent fuel elements to INL with no incidents.
4
Texas A&M University System Nuclear Science Center Annual Report 2006 Prior to receiving new fuel, the NSC received an amendment (# 16) to the R-83 license from the Nuclear Regulatory Commission (NRC) allowing possession ofU-235 to prepare for the conversion of HEU to LEU. In August of 2006, the NSC received and inspected 93 new TRIGA LEU 30/20 fuel elements. The inspection results were satisfactory for all 93 elements.
In September 2006, NSC received another amendment (# 17) to the R-83 license from NRC that authorized the conversion of HEU to LEU. Shortly after, NSC disassembled the TRIGA HEU core and converted the core using the newly received TRIGA LEU fuel in September 2006. A start-up testing program consistent with NRC requirements was performed in late September and early October. The reactor attained initial criticality on September 28, 2006. Startup testing was completed and the reactor was declared steady-state operational in October. After further testing, the core was declared pulse-operational in November of 2006.
This annual report has been prepared to satisfy the reporting requirements of Technical Specification 6.6.1 of the facility operating license R-83 and of the Department of Energy University Reactor Fuel Assistance Program subcontract No C87-101594 (DE-AC07-76ER02426).
1.1 Nuclear Science Center Staff The staff at the Nuclear Science Center consists of four major groups: Reactor Operations, Reactor Maintenance, Health Physics/Technical Coordination, and Administrative Services Appendix A provides the NSC organization chart. Personnel directly involved with the operation and maintenance of the reactor are NRC-licensed operators. The NSC is committed to its educational responsibilities and many members of the staff are part or full-time students at Texas A&M University. Appendix A shows the Nuclear Science Center Organization Chart.
The Texas Engineering Experiment Station (TEES) of the Texas A&M University System operates the NSC. The Director of the NSC is responsible to the Deputy Director of the TEES for the administration and the proper and safe operation of the facility. In addition to the internal structure, the Reactor Safety Board (RSB) advises the Deputy Director of the TEES and the Director of the NSC on issues or policy pertaining to reactor safety. The Texas A&M University Environmental Health and Safety Department (EHSD) provide assistance when it is required for emergencies and for special operations as agreed. The Texas A&M University Police Department provides security support on a daily basis and is a key support group in the event of a security incident.
- 2.
Reactor Utilization for 2006 The Nuclear Science Center (NSC) reactor has been in operation since 1962. The reactor is a 1-MW, MTR-converted TRIGA reactor. Until the refueling in September, the reactor used highly enriched uranium fuel (70%), but now uses low enriched uranium fuel (20%). Core VIII-A is the current core configuration and has been in use since March 1986. The NSC reactor is pulse 5
Texas A&M University System Nuclear Science Center Annual Report 2006 operational and is pulsed up to powers of approximately 1,100 MW for nuclear engineering laboratories, staff training, and public tours.
The NSC reactor operated for 2457.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> in 2006 with a total integrated power of 100.6MW-days. There were 602 "Request for irradiation" processed at the NSC during the reporting period. The NSC provided services to TAMU departments, other universities, research centers, and secondary schools in and outside the state of Texas. Many departments at TAMU and other universities used the reactor regularly in the past year. The NSC reactor had about 97%
availability in 2006. The cumulative total energy output since initial criticality of the FLIP fuel is 3466.25 MW days, and the cumulative total energy output since initial criticality of the LEU fuel is 16.16 MW days.
Table 2-1: Reactor Utilization Summary in 2006 Days of Reactor Operation 297 Integrated Power (MW-days) 100.6 Number of Hours at Steady-State 2457.3 Number of Pulses 26 Number of Reactor Irradiations (RFS) 602 Beam Port/Thermal Column Experiment Hours 903.4 Hours Irradiation Cell Use 100.8 Number of Visitors 2151 Unscheduled Shutdowns 1
2,500-2,413 2,300.-
4 2,2,120 2,155 2,143 2 138 2,02,1008 2,100 1,963 1,946 1,951 1,91 t,,1,944 1,924 o w,9 15 1,900-1,700 1,.500 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 Year Figure 2-1. Annual Reactor Utilization 2.1 TAMU Academic Support Program Texas A&M University provides funding for the reactor for such academic activities as nuclear engineering laboratories, neutron activation analysis demonstrations and laboratories, graduate student thesis and dissertation research, and undergraduate research projects. The program has 6
Texas A&M University System Nuclear Science Center Annual Report 2006 been very successful and is crucial for many graduate students who use the NSC reactor for research and have not received research grants. The wide range of academic users from the university reflects in the NSC's reputation as a multi-disciplinary institution.
2.2 DOE University Reactor Sharing Program The DOE University Reactor Sharing Program provides funds for reactor experimentation to those institutions that do not normally have access to a research reactor. The NSC has participated in the program since 1980. During the 2005-2006 contract year, nine research institutions utilized the NSC with the support of the Reactor Sharing Program. Additionally, the funding provided reactor tours and "hands on" projects to many secondary schools. The research projects supported by the program include items such as dating geological material and producing high-current superconducting magnets. The funding gave several small colleges and universities the opportunity to use the NSC facilities for teaching courses in nuclear processes, specifically neutron activation analysis and gamma spectroscopy. The Reactor Sharing Program supported the use of the Fast Flux Irradiation Device for multiple users at New Mexico Institute of Mining and Technology and the University of Nevada at Las Vegas. This device has near optimum neutron fluxes for 39Arl/Ar dating.
2.3 Commercial Activity and External Research The NSC provides services to a variety of users that provide their own funding. The majority of commercial activities focus on production of radioactive tracers for the Texas petroleum and chemical industries. Another commercial activity uses the converted Thermal Column area to produce micropore filters used in ultra-pure water systems in the semiconductor industry.
Outside research grants fund a significant amount of the NSC's research. The NSC is currently involved with neutron. activation analysis and radioassays for a wide variety of samples for outside customers. The NSC has many years of experience producing radioisotopes and has developed several customer-specific methods for radioactive sample production and handling.
The production of radioisotopes generally involves handling radioactive material with high activities. The NSC staff takes precautions to minimize the exposures during the transfer of radioactive materials to shipping shields.
- 3.
Facility and Procedure Changes 3.1 Facility Modifications A new motorized gate was installed at the entrance to the facility. It has a variable speed control to reduce jerking, and hopefully increase dependability. It also has an emergency edge sensor for safety.
7
Texas A&M University System Nuclear Science Center Annual Report 2006 New card reader access panels were installed to outside doors, gates, and controlled access points throughout the facility. All the outside conduit and wiring were done. In addition, a new intercom and remote control for the reception room and control room were installed.
A new computer and monitor were installed in the Reception Room. It is connected to the card reader computer which in turn displays the personnel entry into and out of the facility automatically as their card is swiped.
Two other computer monitors were installed in the Reception Room to replace the analog meters for the Area Radiation Monitors and Facility Air Monitors with digital and graphic displays.
A new computer controlled heating and air conditioning unit has been installed, replacing the original pneumatic controlled system.
New switch panels were installed in the Control Room improving access and appearance.
3.2 Experiment Authorization and Modification Authorization There were no new Experiment Authorizations covered in 2006, but there were four Modification Authorizations (MA#56 through MA#59) that got initiated. The following Table 3-1 outlines the individual MA's and their current status.
Table 3-1: Modification Authorizations MA#
Title Description Status 56 Uninterruptible Power Installation of Uninterruptible power Approved Supply supplies routing a vast majority of console electronics to mitigate the numerous electrical surges and equipment damage.
57 Un-irradiated Fuel Installation of an un-irradiated Fuel Approved storage Racks storage rack to store the new LEU fuel prior to the conversion.
58 Facility Air Monitoring Replacement of all Lin/Log meters In progress Channels-Upgrade and the analog ratemeters and the and to be installation of computer monitor for approved readout.
59 Area Radiation Replacement of all analog meters In progress Monitors-Upgrade and the installation of computer and to be monitor for readout.
approved 8
Texas A&M University System Nuclear Science Center Annual Report 2006
- 4.
Reactor Maintenance and Surveillance 4.1 Scheduled Maintenance NSC personnel performed regular maintenance on the Fuel Element Temperature Channel, Area Radiation Monitors and the Linear, Log, and Safety Power Channels as required by the Technical Specifications. They also performed all surveillances required by the reactor license. Control rod worth and scram time measurements performed in December 2006 gave the following results. The total rod worth is $17.016. The most reactive control rod is Shim Safety
- 4 with a worth of $4.609. The shutdown margin was $4.175 and core excess was $621.1.
Scram times on all rods were less than 1.2 seconds. In addition, operators performed calorimetric calibration following each maintenance period, and fuel inspections with no abnormalities noted (as required by the Technical Specification). The cold critical reactivity worth, performed for each reactor experiment, shows the most reactive fixed experiment is the Fast Flux Irradiation Device (-$1.24) with leveling high boron loading the negative worth.
4.2 Unscheduled Maintenance Table 4-1: Unscheduled Maintenance 01-27-06 The south core light was replaced.
A shorted "open" switch for the front gate was replaced 02-06-06 allowing the gate to stay closed.
02-03-06 The rod down switch and wiring to the engaged switch was replaced on Rod Drive 4 restoring proper indications.
03-23-06 Replaced power supply on one of the security cameras, removing floating lines from the image.
03-14-06 Intermittent connections to the Transient Rod encoder were replaced restoring position indications.
04-04-06 The supports for the cooling tower were re-secured and the splash panels were reinstalled.
04-12-06 The magnet on Rod Drive I was replaced.
06-02-06 Four solid state relays and a bad connection were repaired, restoring alarm indicating lights for the FAM system.
9
Texas A&M University System Nuclear Science Center Annual Report 2006 06-20-06 The connection for the bridge interlock scram circuit was repaired.
08-31-06 The conduit for the limit switches on the irradiation cell door was repaired.
10-05-06 The power cable and plug were replaced on the FAM pump motors.
10-06-06 The crane control was disassembled and cleaned after being dropped in the pool.
11-10-06 A shorted connection in the Reg. Rod drawer was repaired.
11-14-06 The make up valve for the cooling tower was replaced.
11-17-06 The magnets were replaced on Rod Drive 3 & 4.
12-06-06 The alert relay in Lab. 3 ARM was replaced after it failed to alarm.
12-08-06 A reactor core light was replaced.
4.3 Emergency Planning and Review The Nuclear Science Center staff and the RSB reviewed the NSC Security and Emergency Plans.
A successful facility wide emergency drill involving the offsite response teams such as fire department, ambulance and college station medical center was conducted on December 19, 2006.
Completion of all security related compensatory measures were implemented within the deadlines prescribed in the Confirmatory Action Letter issued by the NRC.
4.4 Unscheduled Shutdowns There was one unscheduled reactor shutdown during 2006. The cause is detailed below in Table 4-2.
Table 4-2: Unscheduled Shutdowns 6/07/2006 Reactor scrammed due to inadvertent disconnection of leads from experiment scram signal to the safety channels during maintenance.
10
Texas A&M University System Nuclear Science Center Annual Report 2006 4.5 Notice of Violation In May 2006, Nuclear Science Center received a Severity Level IV violation due to a potential over exposure event happened on March 2006. Nuclear Regulatory Commission (NRC) conducted a special investigation in March 2006 following the notification of event. A detailed response to the "Notice of Violation" was filed with the NRC including the corrective actions that were implemented following the incident. All applicable features of the radiation safety program were adequately implemented.
- 5.
Health Physics Surveillance The purpose of Health Physics surveillance is to ensure safe use of radioactive materials in the Nuclear Science Center's research and service activities and to fulfill the regulatory requirements of U.S. Nuclear Regulatory Commission and State agencies. The NSC maintains a Health Physics group as an integral part of the organization. They are responsible for radiological as well as chemical, and physical safety concerns. The radiation safety team at the TAMU Environmental Health and Safety Department provides additional support to the NSC Health Physics group upon request.
5.1 Radioactive Shipments The Health Physics monitoring and technical support that was provided in 2006 assured minimal exposure during sample handling, shipment of radioactive material, and normal reactor operation. The radiation exposures were maintained ALARA. During 2006, about 415 radioactive samples were handled of which 394 samples were sent to various research facilities including Texas A&M University campus and the rest were retained at the Nuclear Science Center facility. A total of 372 curies were handled in 2006.
5.2 Personnel Monitoring Personnel Monitoring was provided to approximately 42 personnel. All measured doses to personnel were below the limits set forth in 10 CFR 20. Two individuals received whole body dose greater than 10% of the annual limit inl0 CFR 20. The doses recorded were 899 and 733 mrem deep dose equivalent for the year. Airborne monitoring during sample handling continued to show no significant airborne activity. Therefore, total effective dose equivalent will equal deep dose equivalent for 2006. A total of 6.564 manrem was recorded for the year 2006. When total manrem/curie was determined for 2006, the dose per curie equaled 0.0176 (manrem/Ci).
During 2006, about 2151 visitors toured the Nuclear Science Center. Minimal exposures were measured with pocket ion chambers worn by these visitors and the pocket ion chamber readings of their respective tour guides.
11
Texas A&M University System Nuclear Science Center Annual Report 2006 NSC employees who were likely to exceed 10% of their total annual dose wore TLDs/film badges and extremity dosimeters that were provided by Landauer, a NVLAP accredited supplier.
Landauer also provided the analysis reports of the doses received.
5.3 Facility Monitoring Surveys of the Nuclear Science Center facilities were performed to assess radiological hazards to NSC workers. Radiation levels and sources of radioactive contamination were routinely monitored. Approximately 350 smear samples were collected and evaluated each month. All accessible areas at the NSC are surveyed for radiation and contamination levels monthly. Areas where contamination is expected, access/egress controls are in place and are evaluated on shorter intervals. Area monitors were placed at strategic locations in the reactor facility, this provides dose equivalent (mrem) on a monthly basis. Table 5-1 summarizes the annual accumulated dose equivalent (mrem) recorded on the area monitors for 2006.
Table 5-1: Total Dose Equivalent (mrem) Recorded on Area Monitors Accumulated Dose Monitor ID Location Equivalen Dose Equivalent (mrem)
BLDG MNTR 1 Upper Research Level 1271 Mezzanine BLDG MNTR 2 Lower Research Level 622 Mezzanine BLDG MNTR 3 Lower Research Level 30 AREA Control Room 1096 AREA Upper Research Level 756 AREA Room next to MHA 1014 5.4 Particulate Effluent Monitoring Radioactive particulates were monitored at the base of the central exhaust stack and summarized on a monthly basis. The annual average release concentration was 1.69 E-1 1 giCi/cc and the diluted concentration was 8.46E-14 ptCi/cc. The total radioactivity activity released for 2006 was 1.27E-03 Ci. Table 5-2 summarizes monthly particulate effluent releases during 2006. The isotopes noted during effluent releases were Sc-46 and Sb-124.
12
Texas A&M University System Nuclear Science Center Table 5-2: Particulate Effluent Releases Annual Report 2006 total:
1.82E+13 6.53E-06 Z./dt-U4 April 2.43E-11 1.22E-13 6.12E+12 O.OOE+00 1.49E-04 May 1.38E-1 1 6.92E-1 4 6.32E+12 0.OOE+00 8.76E-05 11 June
<MDA
<MDA 6.12E+12 O.OOE+00
<MDA Average:
1.27E-11 6.37E-14 6.19E+12 O.OOE+00 7.88E-05 total:
1.86E+13 O.OOE+00 2.37E-04 July 7.86E-12 3.93E-14 6.32E+12 O.OOE+00 4.97E-05 August 3.49E-1I 1.74E-13 6.32E+12 O.OOE+00 2.21E-04 III September 3.18E-11 1.59E-13 6.12E+12 O.OOE+00 1.95E-04 Average:
2.49E-11 1.24E-13 6.25E+12 O.OOE+00 1.55E-04 total:
1.89E+13 O.OOE+00 4.65E-04 October 2.50E-12 1.25E-14 6.32E+1 2 O.OOE+00 1.58E-05 November 5.26E-12 2.63E-14 6.32E+12 0.OOE+00 3.32E-05 IV December 4.02E-1 1 2.01 E-1 3 6.12E+12 0.00E+00 2.46E-04 Average:
1.60E-11I 8.00E-14 6.25E+12 0.00E+00 9.84E-05 total:
.8E1 o.ooE+oo 2.95E-04 notes:
- 1. Average Release Concentration equal to: Concentration released from Channel 1, NSC Form 805
- 2. Diluted Concentration equal to Average Release Concentration multiplied by 0.005 (Technical Specification 3.5.2, dilution value for release concentration at exclusion boundary)
- 3. Exhaust Volume equal to: (# dayslmonth)*( 24hrs/day)*( 60min/hr)*( 5000cfmy 3.53E-5cfm/cc)
- 4. Additional Release equal to: (Individual releases calculated from facility air monitoring data)
- 5. Total Release equal to: (Average Release Concentration)*( Exhaust volume) (1CV 1E6 pCi)+(Additional Release)
MDA is based on the conversion factor for the Channel 1 (Stack particulate detector):
9.62E-14 ItCi/ce (January-October) and 1.03E-13 liCi/ce (November-December).
5.5 Gaseous Effluent Monitoring Argon-41 is the major gaseous effluent produced and released at the Nuclear Science Center.
This effluent is monitored at the central exhaust stack. Total Argon-41 released during 2006 was 8.54 Ci with an annual average release concentration of 1.08E-07 itCi/cc and with a diluted 13
Texas A&M University System Nuclear Science Center Annual Report 2006 concentration of 5.38E-10 gCi/cc. Table 5-3 summarizes monthly gaseous effluent (Ar-41) releases during 2006.
Table 5-3: Gaseous Effluent (Ar-41) Releases JFebruary I7.81 E-08 3.90E-1 0 5.71 E+1 2 0.00E+00 4.46E-01 I
March 1.16E-07 5.78E-10 6.32E+12 O.OOE+00 7.32E-01 Average:
1.08E-07 5.40E-10 6.12E+12 9.80E-02 7.65E-01 total:
1.82E+13 9.80E-02 2.29E+00 April 6.24E-08 3.12E-10 6.12E+12 0.OOE+00 3.82E-01 May 5.80E-08 2.90E-10 6.32E+12 O.OOE+00 3.67E-01 II June 7.13E-08 3.57E-10 6.12E+12 1.90E-01 6.27E-01 Average:
6.39E-08 3.19E-10 6.19E+12 6.33E-02 4.58E-01 total:
1.86E+13 2.53E-01 1.37E+00 July 2.79E-07 1.39E-09 6.32E+12 0.OOE+00 1.76E+00 August 1.94E-07 9.68E-1 0 6.32E+1 2 O.OOE+00 1.22E+00 III September 1.09E-07 5.46E-10 6.12E+12 0.OOE+00 6.69E-01 verage:
1.94E-07 9.69E-10 6.25E+12 O.OOE+00 1.22E+00 total:
1.88E+13 0.OOE+00 3.66E+00 October 8.915E-08 4.46E-1 0 6.32E+1 2 0.00E+00 5.64E-01 IV November 3.78E-08 1.89E-10 6.12E+12 O.OOE+00 2.31E-01 December 6.69E-08 3.35E-10 6.32E+12 O.OOE+00 4.23E-01 Average:
6.46E-08 3.23E-10 6.32E+12 0.OOE+00 4.06E-01 notes:
- 1. Average Release Concentration equal to: Concentration released from Channel 3, NSC Form 805
- 2. Diluted Concentration equal to: Average Release Concentration multiplied by 0.005 (Technical Specification 3.5.2, dilution value for release concentration at exclusion boundary)
- 3. Exhaust Volume equal to: (# days/month)*( 24hrslday)*( 60min/hr)*( 5000cfm) 3.53E-5cfmlcc)
- 4. Additional Release equal to: (Individual releases calculated from facility air monitoring data)
- 5. Total Release equal to: (Average Release Concentration)*( Exhaust volume)* (1 CV I E6 pCi)+(Additional Release)
MDA is based on the conversion factor for the Channel 3 (Stack gas detector):
2.3 1E-09 ltCi/cc (January-June) and 3.07E-09 [tCi/cc (July-December).
14
Texas A&M University System Nuclear Science Center Annual Report 2006 5.6 Liquid Effluent Monitoring Radioactive Liquid effluents are maintained in collection tanks before release from the confines of the Nuclear Science Center. Sample activity concentrations and isotope identifications were determined before each release. There were 20 releases in 2006, totaling 6.75E+05 gallons including dilution. The total radioactivity released was 1.98E-03 Ci with an annual average concentration of 7.8E-07 gCi/cc. The annual dose to the public calculated from liquid effluents is 6.7 mrem. Summaries of the release data are presented in the Table 5-4. Radioactivity concentrations for each isotope found were below the Effluent Concentration limits specified in 10 CFR 20, Appendix B. Some of the major radionuclides identified in the waste stream are Sc46, Mn54, Co 8, Co60, Zn65, Sb124 and J131.
Table 5-4: Liquid Effluent Releases Volume Total Average Number of Released Radioactivity Concentration Quarter Month Releases (cc)
(Ci)
(ttCi/cc)
I January 2
1.71E+08 2.96E-04 1.74E-06 February 2
1.47E+08 3.65E-04 2.49E-06 March Quarter Total:
4 3.17E+08 6.61E-04 II April 3
4.13E+08 4.88E-04 1.18E-06 May June 1
1.26E+08 5.14E-05 4.08E-07 Quarter Total:
4 5.39E+08 5.39E-04 III July 4
7.63E+08 2.94E-04 3.30E-06 August September 5
6.68E+08 2.94E-04 2.31E-06 Quarter Total:
9 1.43E+09 5.89E-04 IV October November 3
2.69E+08 1.96E-04 7.28E-07 December Quarter Total:
3 2.69E+08 1.96E-04 Annual Total:
20 2.56E+09 1.98E-03 7.8E-07 Summary I
I I
I I
- No releases 15
Texas A&M University System Nuclear Science Center Annual Report 2006
- 6.
Environmental Monitoring In conjunction with representatives from the Texas Department of Health, Bureau of Radiation Control, a quarterly environmental survey is conducted to insure compliance with federal regulations. This program consists of TLD monitors located at various locations on the NSC site and two background monitors one located at 3.84 miles NW of facility and the other at 0.25 miles SE of facility. The collection, analysis, and evaluation of NSC creek sediment are also included in the program.
6.1 Environmental Samples The environmental samples were collected in accordance with the schedules of the cooperative surveillance program between the Texas Department of Health and the Texas A&M University.
NSC creek sediment samples were analyzed using an intrinsic germanium detection system for isotopic identification at the NSC. A second set of sediment samples were analyzed by the Texas Department of Health for comparison. The concentrations of environmental samples determined for each quarter are listed below in Table 6-1. The most common isotopes were Mn-54, Co-58, Co-60, Fe-59, Zn-65, Pb-214, etc. The concentrations were less than 1E-6 [tCi/g.
Table 6-1: Environmental Sample Analysis Quarter Sediment
[.Ci/g 1st NSC creek
<lE-06 2nd NSC creek
<lE-06 3rd NSC creek
<5E-07 4th NSC creek
<lE-06 6.2 Site Boundary Dose Rate The environmental survey program measures the integrated radiation exposures at the exclusion area boundaries. These measurements are made for periods of approximately 91 days using TLDs. Monthly measurements of direct gamma exposure rate in ptrem/h are also made at each of the TLD locations. The dosimeters are provided and processed by Department of State Health Services, Environmental Monitoring, Division of Regulatory Services, Austin, Texas.
Total TLD dose is multiplied by the occupancy factor (1/16) to determine total deep dose to the general public. To determine internal exposure to individuals outside the site area the EPA's 16
Texas A&M University System Nuclear Science Center Annual Report 2006 approved code, COMPLY was used. The exposure calculated via COMPLY was 0.1 mrem/yr.
This exposure is added to the calculated total deep dose. This total is the dose received by the general public. Table 6-2 summarizes the site boundary dose rates.
Table 6-2: Site Boundary Dose Rates Internal Total Quarterly Exposure rates TLD Deep Dose Dose Site #
Location (mreni91 days)
Dose Dose (mrem)
(mrem) 300 ft. W of reactor building, near 2
fence comer 2.9 2.1 3.3 3.1 11.4 0.71 0.1 0.81 250 fl W-SW of reactor building, on SW chain link 3
fence 0
0 1.1 0
1.1 0.068 0.1 0.168 200 ft NW of reactor building, on chain link fence, near 4
butane tank 4.8 3.1 4.4 3.9 16.2 1.01 0.1 1.11 225 ft NE of reactor building, on fence N of 5
driveway 0
0 1.1 0
1.1 0.068 0.1 0.168 190 ft SE of reactor building, near 10 fence comer 0
0 1.1 0
1.1 0.068 0.1 0.168 300 ft NE of reactor building, near 11 fence comer 0
0 0
0 0
0 0.1 0.1 375 ft NE of 18 reactor building 1
0 1
0 2
0.125 0.1 0.225 17
Texas A&M University System Nuclear Science Center Annual Report 2006 320 ft NE of 19 reactor building 0
0 0
0 0
0 0.1 0.1 3 miles NW of 14 facility 0
0 0
0 0
0 0.1 0.1 0.25 miles SE 23 of facility 0
0 0
0 0
0 0.1 0.1
- 7.
Radioactive Waste Shipments During the year 2006, there was no solid waste released from the NSC for disposal offsite.
However, dry solid wastes with short half-lives (<300 d) were properly stored for decay, which will eventually be segregated, sorted and disposed as non-radioactive waste.
- 8.
Reactor Safety Board The Reactor Safety Board is responsible for providing an independent review and audit of the safety aspects of the NSC reactor. The RSB meets at least once a year to review audit reports, security and emergency plans, new experiments and modifications to the facility. Appendix B provides the reactor safety board membership.
18
Texas A&M University System Nuclear Science Center Annual Report 2006 APPENDIX A NSC ORGANIZATION CHART-2006 19
Texas A&M University System Nuclear Science Center Annual Report 2006 APPENDIX B Reactor Safety Board Membership (2006)
Chairman/Licensee:
Dr. Theresa Maldonado, Deputy Director Texas Engineering Experiment Station Members:
Dr. John Ford, Assistant Professor Nuclear Engineering Department Dr. Marvin Adams, Associate Professor Nuclear Engineering Department Dr. Bill Charlton, Associate Professor Nuclear Engineering Department Dr. William Dennis James, Research Chemist Chemistry Department Dr. John Hardy, Professor Physics Department Dr. Teruki Kamon, Professor Physics Department Ex-Officio Members:
Dr. Warren Reece, Director Nuclear Science Center Dr. Latha Vasudevan, NSC RSO Nuclear Science Center Dr. William Burchill, Professor and Head Nuclear Engineering Department Mr. John Salsman, Director Environmental Health and Safety Department Mr. Daniel Menchaca, RSO Environmental Health and Safety Department Mr. Jim Remlinger, Associate Director Nuclear Science Center 20