ML12122A032
ML12122A032 | |
Person / Time | |
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Site: | 05000128 |
Issue date: | 04/27/2012 |
From: | Newhouse J Texas A&M Univ |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
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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 April 27, 2012 2012-0013 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
Subject:
2011 Annual Report (Facility License R-83)
To WMhom It May Concern:
Enclosed please find the 2011 Annual Report for the Texas Engineering Experiment Station Nuclear Science Center, Texas A&M University, College Station, TX 77843.
If you bare any questions regarding this, please feel free to call me at (979) 845-7551.
Sincerely, 4eeactor Supervisor Enclosur-e Xc: 2.11/Central File Annual Report File AGI9 RESEARCH AND DEVELOPMENT FOR MANKIND http://nsc.tamu.edu
Texas A&M University System Texas Engineering Experiment Station 2011 Annual Report Facility Operating License R-83 Nuclear Science Center 1095 Nuclear Science Road College Station, Texas 77843-3575 April 2012 0
Texas A&M University System Nuclear Science Center Annual Report 2011
- CONTENTS
- 1. Introduction ......................................................................................................................... 4 1.1 Nuclear Science Center Staff .................................................................................. 5
- 2. Reactor Utilization for 2010..................................................................... ......... .5 2.1 TAM U Academic Support Program .................................................................... 7 2.2 Commercial Activity and External Research ..................................................... 7
- 3. Facility and Procedure Changes .................................................................................... 7 3.1 Facility M odifications ........................................................................................ 7 3.2 Experiment Authorization and Modification Authorization .............................. 7
- 4. Reactor M aintenance and Surveillance ........................................................................... 7 4.1 Scheduled M aintenance ...................................................................................... 7 4.2 Unscheduled Shutdowns ...................................................................................... 8 4.3 Emergency Plan and Review ............................................................................. 9 4.4 Reactor Safety Board ......................................................................................... 9 4.5 Inspections and Audits ...................................................................................... 10
- 5. Health Physics Surveillance .......................................... 10
- 5.1 Radioactive Shipments ........................................ 10 5.2 Personnel M onitoring ........................................................................................ 10 5.3 Facility Monitoring ....... ................................... 11 5.4 Particulate Effluent M onitoring ........................................................................ 11 5.5 Gaseous Effluent M onitoring ............................................................................ 13 5.6 Liquid Effluent M onitoring .............................................................................. 14
- 6. Environm ental Monitoring ............................................................................................ 16 6.1 Environm ental Samples .................................................................................... 16 6.2 Site Boundary Dose Rate...................................................................................... 16
- 7. Radioactive W aste Shipments ...................................... ............................................... 18 Appendix A: NSC Organization Chart ..................................................................................... 19 Appendix B: Reactor Safety Board Membership ...................................................................... 20 2
Texas A&M University System Nuclear Science Center Annual Report 2011 0List of Tables Table 2 : Reactor Utilization Summary in 2010 ................................................................. 6 Table 4-2: Unscheduled Shutdowns ...................................................................................... 8 Table 5-3: Total Dose Equivalent (mrem) Recorded on Area Monitors ............................ 11 Table 5-4: Particulate Effluent Releases ............................................................................ 12 Table 5-5: Gaseous Effluent Releases ............................................................................... 13 Table 5-6: Liquid Effluent Releases ................................................................................... 15 Table 6-2: Site Boundary Dose Rates ................................................................................. 17 List of Figures Figure 2: Annual Reactor Utilization in MW-hrs of Operation ........................................ 6 3
Texas A&M University System Nuclear Science Center Annual Report 2011
- 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 experiments that may be conducted near the reactor. The NSC reactor facility includes two neutron beam ports, a neutron/gamma irradiation cell, a film neutron radiography system, hot cells with manipulator arms, and other supporting facilities. Also, NSC has Cs-137 calibrator for use in instrument calibration.
Laboratory facilities include counting laboratories with gas flow proportional detectors and High Purity Germanium detectors, a two-station pneumatics sample transfer system, a fast neutron irradiation system, a delayed neutron detection system and a prompt gamma neutron activation analysis system.
The NSC reactor design allows for easy loading/unloading of various types of samples. The NSC routinely 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 approximately 1900 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 is continuing to produce distance learning modules. The NSC has completed the security upgrades and enhancements that were initiated as part of DOE Global Threat Reduction Initiative (GTRI). NSC continues to provide technical support for the Y-12 training initiatives.
With the DOE reactor upgrade funding from 2010, the NSC is replacing the cooling tower and systems as well as installing a whole body contamination monitor that will follow nuclear industry standards.
NSC has submitted the license amendment request as well as the revised Tech Specs, SAR, and other supporting documents for the renewal process with Nuclear Regulatory Commission (NRC). They are under review and are still pending with the NRC.
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 4
Texas A&M University System Nuclear Science Center Annual Report 2011 V 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,.
Health Physics/Technical Coordination, Reactor Maintenance, and Administrative Services.
Personnel directly involved with the operation and maintenance of the reactor are NRC-licensed operators. The NSC is committed to its educational mission 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 Director of the TEES for the administration and the proper and safe operation of the facility. The NSC Radiation Safety Office is responsible for matters relating to safety and for maintaining a proper radiation safety program. 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. The College Station Fire Department and the College Station Medical Center provides offsite emergency support when it is required as per agreement.
- 2. Reactor Utilization for 2011 The Nuclear Science Center (NSC) reactor has been in operation since 1961. The reactor is a 1 MW MTR-converted TRIGA reactor. Until the refueling in September 2006, the reactor used highly enriched uranium fuel (70%), but now uses low enriched uranium fuel (20%). Core IX is the current core configuration and has been in use since September 2006. The NSC reactor is pulse operational and was pulsed up to $1.71 for nuclear engineering laboratories, staff training, and public tours.
The NSC reactor operated for 2121.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> in 2011 with a total integrated power of 86.6 MW-days. There were 535 "Requests 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. The cumulative total energy output since initial criticality of the LEU fuel is 404.9 MW-days. Table 2 shows the reactor utilization summary in 2011 and Figure 2 shows the annual reactor utilization in MW-hrs of operation.
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Texas A&M University System Nuclear Science Center Annual Report 2011 Table 2: Reactor Utilization Summary in 2011 Days of Reactor Operation 243 Integrated Power (MW-days) 86.6 Number of Hours at Steady-State 2121.4 Number of Pulses 38 Number of Reactor Irradiations (RFS) 535 Number of Visitors 1844 Unscheduled Shutdowns 18 MW-hours of Operations 2200 2100 2000 1900 1800 1700 1600 1500 2007 2008 2009 2010 2011 Figure 2. Annual Reactor Utilization in MW-hrs of Operation 6
Texas A&M University System Nuclear Science Center Annual Report 2011 V 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 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 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. Outside research grants fund a significant amount of the NSC's research.
The NSC is 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 During 2011, we renovated the Material Handling Area (MHA). The painted floor was stripped and re-sealed. Wooden work benches and storage spaces were replaced with stainless steel. The goals of these renovations is to reduce the possibility of fixed contamination and generally to increase the ease of decontamination. We installed a jib crane on the loading dock to increase safety while handling heavy shipping containers.
3.2 Experiment Authorization and Modification Authorization There were no new Experiment Authorizations (EA) or Modification Authorizations (MA) covered in 2011.
- 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 surveillance required by the reactor 7
Texas A&M University System Nuclear Science Center Annual Report 2011 license. Control rod worth and scram time measurements performed in July 2011 gave the following results. The total rod worth was $14.62. The most reactive control rod was Shim Safety #4 with a worth of $4.028. The shutdown margin was $3.154 and core excess was
$5.545. Scram times on all rods were less than 1.2 seconds. In addition, operators performed calorimetric calibration following each maintenance period, and fuel inspections with no abnormalities noted (as required by the Technical Specification). The cold critical reactivity worth, performed for each reactor experiment, shows that the most reactive fixed experiment is the Fast Flux Irradiation Device (-$ 1.141).
4.2 Unscheduled Shutdowns There were eighteen unscheduled reactor shutdowns during 2011. The cause is detailed below in Table 4-2.
Table 4-2: Unscheduled Shutdowns 1/24/2011 Reactor scrammed due to a dropped rod. An operator bumped a rod drive while placing an experiment and caused the rod to drop.
2/25/2011 Reactor scrammed due to a dropped rod. The transient rod air supply was mistakenly isolated during maintenance, which caused the pressure to drop below an acceptable level.
5/25/2011 Reactor scrammed due to a loss of electricity from offsite.
5/27/2011 Reactor scrammed due to a loss of electricity from offsite.
6/6/2011 Reactor scrammed due to a loss of electricity from offsite.
7/7/2011 Reactor manually scrammed after an unplanned isolation of city water due to a water hammer event.
7/12/2011 Reactor scrammed due to a malfunction in Safety Amplifier Channel #2. The malfunction caused the channel to either indicate 0% or 150% and was repaired.
8/9/2011 Reactor scrammed due to a loss of electricity from offsite.
8/12/2011 Reactor scrammed due to a malfunction in the magnet of Shim Safety Control Rod #3. The drive was replaced with the spare drive.
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Texas A&M University System Nuclear Science Center Annual Report 2011 8/13/2011 Reactor manually scrammed after valves were found to be mispositioned during an ion exchanger regeneration. Reactor pool chemistry was measured and found to be within specification.
8/18/2011 Reactor scrammed due to a malfunction in the magnet of Shim Safety Control Rod #3. Rod operability checks of the drive could not reproduce the malfunction.
9/6/2011 Reactor scrammed due to a malfunction in the magnet of Shim Safety Control Rod #4. The drive was replaced with the spare drive.
9/20/2011 Reactor scrammed due to the dry cell door interlock. The reactor bridge was moved away from the dry cell prior to startup, but the interlock was not reconnected. When the dry cell door was opened, the reactor scrammed.
9/26/2011 Reactor scrammed due to an electrical surge in the console.
Maintenance being performed on the evacuation horn solenoid valve caused an electrical surge which scrammed the reactor.
10/6/2011 Reactor scrammed due to a malfunction in the magnet of Shim Safety Control Rod #4. Rod operability checks of the drive could not reproduce the malfunction.
10/24/2011 Reactor manually scrammed after fuel temperature was observed to be lower than expected at 1MW. Subsequent testing revealed a failure of the Instrumented Fuel Element, which was replaced in service.
11/15/2011 Reactor scrammed due to high indicated power on Safety Amplifier Channel #1 during a planned power transient.
Operator error resulted in a larger than planned transient. No license limitations on reactor power or fuel temperature were exceeded.
12/7/2011 Reactor manually scrammed after indication of a malfunction in the facility air compressor. The faulty part was replaced.
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Texas A&M University System Nuclear Science Center Annual Report 2011 4.3 Emergency Plan and Review The Nuclear Science Center Management and the members of Reactor Safety Board (RSB) reviewed the NSC Security and Emergency Plans.
4.4 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 Reactor Safety Board met once in 2011. The meeting was on May 26, 2011 as per the Technical Specifications requirement.
4.5 Inspections and Audits The Reactor Safety Board performed the required audits and inspections as per the Technical Specifications requirement. The results of the audit were shared with the RSB members. A facility inspection was performed by Nuclear Regulatory Commission in November 2011.
- 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 2011 assured minimal exposure during sample handling, shipment of radioactive material, and normal reactor operation. The radiation exposures were maintained ALARA. During 2011, about 366 radioactive samples were handled and released to various research facilities including Texas A&M University campus. A total of 411 curies were handled in 2011.
5.2 Personnel Monitoring Personnel Monitoring was provided on a monthly basis to approximately 43 personnel. All measured doses to personnel were below the limits set forth in 10 CFR 20. Nine individuals received whole body dose greater than 10% of the annual limit in 10 CFR 20. Their deep dose equivalent (DDE) recorded were .5, .505, .553, .601, .617, .654, .914, 1.092, and 1.454 R for the year. Airborne monitoring during sample handling continued to show no significant airborne 10
Texas A&M University System Nuclear Science Center Annual Report 2011 W activity, therefore, total effective dose equivalent will equal deep dose equivalent for 2011. A total of 8.31 manrem was recorded for the year 2011. When total manrem/curie was determined for 2011, the dose per curie equaled 0.0202 (manrem/Ci).
During 2011, about 1844 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.
NSC employees who were likely to exceed 10% of their total annual dose wore whole body badges (Luxel dosimeter) and extremity badges (TLD dosimeters) that were provided by Landauer, a NVLAP accredited supplier. Landauer also provides the reports of the doses received. Employees who potentially handle more radioactive materials on a regular basis were provided two extremity badges and were changed out on a bimonthly basis.
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 410 smear samples were collected and evaluated each month. All accessible areas at the NSC were surveyed for radiation and contamination levels monthly. Areas where contamination is expected have access/egress controls in place and are evaluated on shorter intervals. Building monitors and Area monitors are located strategically throughout the
- reactor facility, providing dose equivalent (mrem) on a monthly basis. Table 5-3 summarizes the annual accumulated dose equivalent (mrem) recorded on the area monitors for the year 2011.
Table 5-3: Total Dose Equivalent (mrem) Recorded on Area Monitors Accumulated Dose Monitor ID Location Equivalen Dose Equivalent (mrem)
BLDG MNTR 1 Upper Research Level b Mezzanine BLDG MNTR 2 LowerMzaie3184a Research Level a Mezzanine BLDG MNTR 3 Lower Research Level 2039a AREA Control Room 112 AREA Upper Research Level 1101 AREA Room next to MHA 4329b aRadioactive shipments were stored in the LRL area pending transport bRadioactive materials were stored in the temporary locations in MHA.
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Texas A&M University System Nuclear Science Center Annual Report 2011 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 3.04x101 2 pCi/cc. The total radioactivity released for 2011 was 287 LCi. Table 5-4 summarizes monthly particulate effluent releases during 2011. The most common isotopes noted during particulate effluent releases were Sc-46, Sb-124, and Ir-192.
Table 5-4: Particulate Effluent Releases Concentration Dilution Additional Total activity released from channel 1 Concentration Exhaust releases Quarter Month (RCi/cc) (gCi/cc) Volume (cc) (jICi) (Ci)
January 8.90E-13 4.45E-15 9.96E+12 8.86E-06 February <BG <BG 8.99E+12 <BG March 2.76E-12 1.38E-14 9.96E+12 2.75E-05 Average: 1.82E-12 9.12E-15 9.64E+12 1.21E-05 Total: 2.89E+13 3.63E-05 April <BG <BG 9.64E+12 <BG May <BG <BG 9.96E+12 _ _<BG 11 June 7.92E-14 3.96E-16 9.64E+12 7.64E-07 Average: 7.92E-14 3.96E-16 9.74E+12 7.64E-07 Total: 2.92E+13 7.64E-07 July 1.80E-11 9.01E-14 9.96E+12 1.80E-04 August 2.80E-12 1.40E-14 9.96E+12 2.79E-05 Il September 1.47E-12 7.33E-15 9.64E+12 1.41E-05 Average: 7.43E-12 3.72E-14 9.85E+12 7.38E-05 Total: 2.96E+13 2.22E-04 October 2.81E-12 1.41E-14 9.96E+12 2.80E-05 November <BG <BG 9.64E+12 <BG IV December <BG <BG 9.96E+12 <BG Average: 2.81E-12 1.41E-14 9.85E+12 2.80E-05 Total: 2.96E+13 2.80E-05 Annual Average: 3.04E-12 1.52E-14 9.77E+12 2.87E-05 Summary Total: 1.17E+14 2.87E-04 notes:
- 1. Concentration released from the stack: Concentration sampled from Ch 1 multiplied by volume of air going through the stack
- 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)*( 24hrs/dayM*(60min/hr)*( 7875 cfm)/ 3.53E-5cc)
- 4. Additional Release equal to: (individual releases calculated from facility air monitoring data)
- 5. Total Release equal to: (Average Release Concentration)*(Exhaust Volume)*1 OA-6+(Additional Releases) 12
Texas A&M University System Nuclear Science Center Annual Report 2011 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 2011 was approximately 2.82 Ci with an annual average release concentration of 2.79x10 8 ý.Ci/cc. Table 5-5 summarizes monthly gaseous effluent (Ar-41) releases during 2011.
Table 5-5: Gaseous Effluent (Ar-41) Releases Concentration Dilution Additional Total activity from channel 3 Concentration Exhaust Volume releases released Quarter Month (cc)
(40Ci) (lCi) cc (1Ci) (Ci)
January 3.45E-08 1.73E-10 9.96E+12 3.44E-01 February 8.40E-09 4.20E-11 8.99E+12 7.56E-02 I March 6.10E-08 3.05E-10 9.96E+12 6.08E-01 Average: 3.47E-08 1.73E-10 9.64E+12 3.42E-01 Total: 2.89E+13 1.03E+00 April 2.97E-08 1.49E-10 9.64E+12 2.86E-01 Oi May June 1.60E-08 1.18E-08 8.OOE-11 5.89E-11 9.96E+12 9.64E+12 1.59E-01 1.14E-01 Average: 1.92E-08 9.58E-11 9.74E+12 1.86E-01 Total: 2.92E+13 5.59E-01 July 5.43E-09 2.71E-11 9.96E+12 5.41E-02 August <BG <BG 9.96E+12 1.07E+05 1.07E-01 III September 3.57E-08 1.79E-10 9.64E+12 3.44E-01 Average: 2.06E-08 1.03E-10 9.85E+12 1.07E+05 1.68E-01 Total: 2.96E+13 1.07E+05 5.05E-01 October 3.11E-08 1.56E-10 9.96E+12 3.10E-01 November 4.30E-08 2.15E-10 9.64E+12 4.14E-01 IV December <BG <BG 9.96E+12 <BG Average: 3.71E-08 1.85E-10 9.85E+12 3.62E-01 Total: 2.96E+13 7.24E-01 Annual Average: 2.79E-08 1.39E-10 9.77E+12 1.07E+05 2.65E-01 Summary 1.17E+14 1.07E+05 2.82E+00 notes:
- 1. Concentration released from the stack: Concentration sampled from Ch 3 multiplied by volume of air going through the stack
- 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)*( 24hrs/day)*(60min/hr)*( 7875 cfm)/ 3.53E-5cc)
- 4. Additional Release equal to: (Individual releases calculated from facility air monitoring data)
- 5. Total Release equal to: (Average Release Concentration)*(Exhaust Volume)*1OA-6+(Additional Releases) 13
Texas A&M University System Nuclear Science Center Annual Report 2011 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. The concentration values for each isotope were compared with the effluent concentrations in water (10 CFR 20) and were determined to be in compliance. In September 2008, a new sewer system was tied into the Texas A&M waste treatment plant for release of liquid waste and NSC started releasing liquid waste through the sewer system effective September 2008. Sample activity concentrations were then compared with Sewer line concentrations (10 CFR 20) and were determined to be in compliance. There were 28 releases in 2011, totaling 4.39x 105 gallons including dilution. The total radioactivity released was 7.87 mCi with an annual average concentration of 3.5 1x10-6 tCi/cc. The annual dose to the public calculated from liquid effluents is about 3.35 mrem. Summary of the release data are presented in the following Table 5-6. Radioactivity concentrations for each isotope found were below the Effluent Concentration limits specified in 10 CFR 20, Appendix B. The radionuclides identified in the waste stream were Na-24, Sc-46, Cr-5 1, Mn-54, Ir-192, Co-58, Co-60, Zn-65, Sb-122, Sb-124, and Cs-137.
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Texas A&M University System Nuclear Science Center Annual Report 2011 0 Table 5-6: Liquid Effluent Releases Volume Total Average Number of Released Radioactivity Concentration Quarter Month Releases (cc) (Ci) (ACi/cc)
January 0 February 1 3.43E+07 3.34E-05 9.74E-07 March 0 I Total 1 3.43E+07 3.34E-05 9.74E-07 April 4 2.3 1E+08 1.45E-03 6.28E-06 May 1 2.47E+07 1.20E-04 4.86E-06 June 2 3.75E+07 1.69E-04 4.5 1E-06 I1 Total 7 2.93E+08 1.74E-03 5.21E-06 July 3 2.20E+08 1.21E-03 5.52E-06 August 7 4.39E+08 2.42E-03 5.5 1E-06 September 3 1.90E+08 4.63E-04 2.44E-06 III Total 13 8.49E+08 4.10E-03 4.49E-06 October 3 2.15E+08 7.48E-04 3.49E-06 November 2 1.19E+08 3.81E-04 3.21E-06 December 2 1.52E+08 8.73E-04 IV Total 7 4.85E+08 2.OOE-03 3.35E-06 Annual Summary Total 28 1.66E+09 7.87E-03 3.51E-06 15
Texas A&M University System Nuclear Science Center Annual Report 2011 S 6. Environmental Monitoring In conjunction with representatives from the Texas Department of State Health Services (TDSHS) 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.
6.1 Environmental Samples Since the implementation of discharging liquid waste to the sewer, TDSHS no longer requires the collection of a quarterly sediment sample. A letter from TDSHS to this effect is on file.
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 pR/h are also made at each of the TLD locations. The dosimeters were provided and processed by Texas Department of State Health Services, Environmental Monitoring, Division of Regulatory Services, Austin, Texas.
S The total TLD dose is multiplied by the occupancy factor (1/16) to determine the deep dose. To determine the dose to the public outside the site area from air effluents, the EPA approved code COMPLY was used. The annual dose calculated using COMPLY was 0.1 mrem/yr. This is added to the deep dose to determine the total dose to the general public and the maximum dose noted was 1.6 mrem. Table 6-2 summarizes the site boundary dose rates.
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Texas A&M University System Nuclear Science Center Annual Report 2011 Table 6-2: Site Boundary Dose Rates 2011 Quarterly TLD Deep Internal Total Exposure rates Dose Dose Dose Dose Site # Location (mrem/91 days) (mrem) (mrem) (mrem) (mrem) 2 300ft W of reactor building 6.9 1.9 0.9 7.3 17.0 1.1 0.1 1.2 3 250ft WSW of reactor building 4.0 0.9 0.0 3.3 8.2 0.5 0.1 0.6 4 200ftNW of reactor building 8.9 2.8 4.7 7.3 23.7 1.5 0.1 1.6 5 225ftNE of reactor building 7.9 0.9 0.9 1.6 11.3 0.7 0.1 0.8 10 190ft SEof reactor building 3.0 0.0 0.0 0.0 3.0 0.2 0.1 0.3 11 300ftNE of reactor building 4.0 0.0 0.0 0.0 4.0 0.3 0.1 0.4
- 14 3miNW of facility 0.0 0.0 0.0 0.0 0.0 0.0 0.1 0.1 18 375ft NE of reactor building 0.0 2.8 2.8 0.8 6.4 0.4 0.1 0.5 19 320ft NE of reactor building 9.9 0.0 0.0 0.0 9.9 0.6 0.1 0.7 20 E Wall of accelerator building 4.9 0.0 5.7 12.2 22.8 1.4 0.1 1.5 21 W Wall of accelerator building 0.0 0.0 3.8 2.4 6.2 0.4 0.1 0.5 22 S Wall of accelerator building 2.0 0.0 0.0 0.8 2.8 0.2 0.1 0.3
- 23 0.25mi SE of facility 0.0 0.0 0.0 0.0 0.0 0.0 0.1 0.1 24 N wall of accelerator bldg, NW 1.0 1.9 1.9 4.9 9.7 0.6 0.1 0.7 25 N wall of accelerator bldg, E 4.9 0 0 4.1 9.0 0.6 0.1 0.7 W Fence of hyperbaric lab, 1Oft from 26 SW comer x x 0 0.8 0.8 0.1 0.1 0.2 E fence of hyperbaric lab, 1Oft S of 27 entrance x x 0 0 0.0 0.0 0.1 0.1 S fence of hyperbaric lab, 1Oft E of 28 personnel gate x x 0 0.8 0.8 0.1 0.1 0.2 325ft SW from reactor building, SW 29 comer x x 1.9 2.4 4.3 0.3 0.1 0.4
- 14 and 23 are background TLD's 17
Texas A&M University System Nuclear Science Center Annual Report 2011
- 7. Radioactive Waste Shipments In 2011, there was one radioactive waste shipment. Stored material was counted and packaged into appropriate shipping boxes and remanded into the care of the contracted waste hauler, Bionomics on 11/09/2011. The material was hauled to EnergySolutions (formerly Duratek), and processing was completed on 02/09/2012.
There were a total of 1306.8 kg of waste shipped, with a total volume of 14.474 mi3 . The total activity of the shipped waste was measured at 8984.36 uCi (332.4MBq).
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Texas A&M University System Nuclear Science Center Annual Report 2011 APPENDIX A
<-K K-m 0m ~m, 19
Texas A&M University System Nuclear Science Center Annual Report 2011
. APPENDIX B Reactor Safety Board Membership (2010)
Chairman/Licensee:
Dr. Emile Schweikert, Professor Chemistry Department Members:
Dr. John Ford, Associate 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 Dr. Sean McDeavitt, Assistant Professor Nuclear Engineering Department Dr. Karen Vierow, Associate Professor Nuclear Engineering Department Ex-Officio Members:
Dr. Warren Reece, Director Nuclear Science Center Mr. Jim Remlinger, Associate Director Nuclear Science Center 20