ML110940026

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Submittal of the 2010 Annual Report (Facility License R-83) for Texas Engineering Experiment Station Nuclear Science Center
ML110940026
Person / Time
Site: 05000128
Issue date: 03/31/2011
From: Reece W
Texas A&M Univ
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
2011-0007
Download: ML110940026 (23)
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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 March 31, 2010 2011-0007 U.S. Nuclear Regulatory Commission Attn: Document Control Desk J

Washington, D.C. 20555

Subject:

2010 Annual Report (Facility License R-83)

To Whom It May Concern:

Enclosed please find the 2010 Annual Report for the Texas Engineering Experiment Station Nuclear Science Center, Texas A&M University, College Station, TX 77843.

If you have any questions regarding this, please feel free to call Latha Vasudevan or myself at (979) 845-7551.

Sincerely, W. D. Reece, Director Enclosure LV/jg Xc: 21 1/Central File Annual Report File Dr. Kemble Bennett, Director of TEES, Licensee Dr. Emile Schweikert, RSB Chairman Jim Remlinger, Associate Director Latha Vasudevan NSC RSO RESEARCH AND DEVELOPMENT FOR MANKIND 4mo http://nsctamu.edu

Texas A&M University Nuclear Science Center Annual Report-2010 Nuclear Science Center Texas Engineering Experiment Station Texas A&M University System College Station, Texas 77843-3575

Texas A&M University System Texas Engineering Experiment Station 2010 Annual Report Facility Operating License R-83 Nuclear Science Center 1095 Nuclear Science Road College Station, Texas 77843-3575 Prepared By: Latha Vasudevan, NSC RSO Reviewed By: W. D. Reece, NSC Director March 2011

Texas A&M University System Nuclear Science Center Annual Report 2010 CONTENTS

1. Introduction .......................................................................................................................... 4 1.1 N uclear Science Center Staff .............................................................................. 5
2. Reactor Utilization for 2010 ........................................................................................... 5 2.1 TA MU Academ ic Support Program .................................................................... 7 2.2 D OE University Reactor Sharing Program ......................................................... 7 2.3 Comm ercial Activity 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 ........................................................................... 8 4.1 Scheduled M aintenance ...................................................................................... 8 4.2 Unscheduled Maintenance .................................................................................. 8 4.3 U nscheduled Shutdowns .................................................................................... 9 4.4 Em ergency Plan and Review ............................................................................. 11 4.5 Reactor Safety Board ........................................................................................ 11 4.6 Inspections and A udits ...................................................................................... 11 4.7 N otice of V iolation .......................................................................................... 12
5. Health Physics Surveillance ........................................................................................... 12 5.1 Radioactive Shipm ents ...................................................................................... 12 5.2 Personnel M onitoring ......................................................................................... 12 5.3 Facility M onitoring ........................................................................................... 13 5.4 Particulate Effluent M onitoring ........................................................................ 13 5.5 Gaseous Effluent Monitoring ....... ..................... ............ 14 5.6 Liquid Effluent M onitoring ................................................................................ 15
6. Environm ental M onitoring ............................................................................................. 16 6.1 Environm ental Sam ples ................................................................................... 17 6.2 Site Boundary Dose Rate ................................................................................. 17
7. Radioactive W aste Shipm ents ...................................................................................... 19 Appendix A : N SC Organization Chart ...................................................................................... 20 Appendix B: Reactor Safety Board M embership ..................................................................... 21 2

Texas A&M University System Nuclear Science Center Annual Report 20 10 List of Tables Table 2 Reactor Utilization Summary in 2010 ............................................................... 6 Table 4-2: Unscheduled Maintenance .................................................................................. 8 Table 4-3: Unscheduled Shutdowns .................................................................................... 9 Table 5-3: Total Dose Equivalent (mrem) Recorded on Area Monitors ............................ 13 Table 5-4: Particulate Effluent Releases ............................................................................. 14 Table 5-5: Gaseous Effluent Releases ................................................................................ 15 Table 5-6: Liquid Effluent Releases .................................................................................... 16 Table 6-2: Site Boundary Dose Rates ................................................................................. 18 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 20 10

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. Moreover, 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 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 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 the prototype for distance learning modules. Under the Texas Work Force Commission grants, and American Recovery and Reinvestment Act (ARRA) funds, the NSC is successfully providing the operator training program and four undergraduate students received their reactor operator license from the NRC.

The NSC is still continuing with the security upgrades and enhancements that were initiated as part of DOE Global Threat Reduction Initiative (GTRI). NSC is continuing to provide technical support for the Y-12 training initiatives.

With the DOE reactor upgrade funding from 2010, the NSC is working on upgrading and replacing the cooling tower and systems as well as trying to purchase 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.

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Texas A&M University System Nuclear Science Center Annual Report 20 10 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, 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 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. The NSC Radiation Safety Office is responsible for the Director of NSC 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 2010 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 $1.75 for nuclear engineering laboratories, staff training, and public tours.

The NSC reactor operated for 1891.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in 2010 with a total integrated power of 78.8 MW-days. There were 430 "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 318.3 MW-days. Table 2 shows the reactor utilization summary in 2010 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 20 10 Table 2: Reactor Utilization Summary in 2010 Days of Reactor Operation 245 Integrated Power (MW-days) 78.8 Number of Hours at Steady-State 1891.2 Number of Pulses 44 Number of Reactor Irradiations (RFS) 430 Beam Port/Thermal Column Experiment Hours 65.63 Hours Irradiation Cell Use 4.47 Number of Visitors 1882 Unscheduled Shutdowns 22 C 2,500 2,413

.P 2,400 a 2,300 2,200 2,1202,1552,143 2,138 2082 2,081 0 2,100 -1,944--I 1,946 1

,9 5 1 1,915 982 n2,000 9241963 1I

- 1,924 2,000 1,891 1,700 .!.

1,600 1,500 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 Year Figure 2. Annual Reactor Utilization in MW-hrs of Operation 6

Texas A&M University System Nuclear Science Center Annual Report 20 10 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 DOE University Reactor Sharing Program The DOE University Reactor Sharing Program that was providing support for those institutions that do not normally have access to a research reactor ended in the year 2007. There was no work done under reactor sharing program in 2010.

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 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 Setup an all-in-one portable gamma detector system for dry cell. A computer, two Keithley picoammeters, and cables installed on a rollaway cart. A visual basic interface routine was also put together that triggers the detector system as well as documents the gamma dose rate and accumulated gamma dose.

Installed a drain to the ventilation system in one of the labs in lower research level to enhance condensation removal from the duct work.

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Texas A&M University System Nuclear Science Center Annual Report 2010 3.2 Experiment Authorization and Modification Authorization There were no new Experiment Authorizations (EA) or Modification Authorizations (MA) covered in 2010.

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 license. Control rod worth and scram time measurements performed in July 2010 gave the following results. The total rod worth was $15.129. The most reactive control rod was Shim Safety #4 with a worth of $ 4.133. The shutdown margin was $ 3.694 and core excess was

$ 5.352. 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 Maintenance Table 4-2 lists the unscheduled maintenance performed in year 2010.

Table 4-2: Unscheduled Maintenance 5/16/2010 Linear Detector - Rebuilt the Compensated Ion Chamber 6/15/2010 IFE -checked the connections to confirm it is functional 7/19/2010 Rod 2 is dropping constantly. Replaced Rod 2 and cleaned both the surface of the rod and the magnet on the drive 8/30/2010 Linear detector is shorted. Created stronger solder joints around the springs 8/31/2010 Rod drawer 1 drops the rod. Solder loose wire in the drawer 9/2/2010 Problems with FAM 2. Replaced the entire cable and the Mylar for the detectors 9/14/10 Rod 3 goes up to about 70%. The rod jammed against part of the 8

Texas A&M University System Nuclear Science Center Annual Report 20 10 source. This was fixed.

9/14/10 Rod 3 gang up circuit does not work. The solder joints on the circuit board were loose. All joints were resoldered and cleaned.

9/22/2010 Radio room box was acting up. The lights were all on and will not turn off. Replaced the transistor and re soldered the broken ground wire.

9/28/2010 Hand and foot monitor was not detecting properly. All mylar had to be replaced and gas flow was adjusted to the correct rate.

11/15/2010 Compensating Voltage showing a short or loose connection.

Pulled the Linear Detector and resolder joints.

11/23/2010 Thermal column alarm would not flash the lights. The gate needed an adjustment to line up the switch.

4.3 Unscheduled Shutdowns There were twenty-two unscheduled reactor shutdowns during 2010. The cause is detailed below in Table 4-3.

Table 4-3: Unscheduled Shutdowns 2/8/2010 Reactor scrammed due to high level alarm on Safety Power Channel #2. The reactor operator increased power from 600kW to 1MW too quickly which caused the alarm.

2/11/2010 Reactor scrammed due to a dropped rod. Magnet current was lost from Shim Safety Control Rod #1 because of indeterminate equipment malfunction.

2/23/2010 Reactor scrammed due to a dropped rod. Magnet current was lost from Shim Safety Control Rod #1 because of equipment malfunction. Control Rod Drive replaced.

4/20/2010 Reactor scrammed due to loss of electricity from offsite.

5/27/2010 Reactor scrammed due to high level alarm on Safety Power Channel #2. The reactor operator increased power from 600kW to 1MW too quickly which caused the alarm.

6/21/2010 Reactor scrammed due to temporary interruption of power to Shim Safety Control Rod #4.

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Texas A&M University System Nuclear Science Center Annual Report 20 10 6/21/2010 Reactor scrammed due to a dropped rod. Magnet current was lost from Shim Safety Control Rod #4 because of equipment malfunction. Control Rod Drive replaced.

7/19/2010 Reactor scrammed due to temporary interruption of power to Shim Safety Control Rod #1 and #2.

8/17/2010 Reactor scrammed due to temporary interruption of power to Shim Safety Control Rod #1 and #2.

8/24/2010 Reactor scrammed due to a dropped rod. Magnet current was lost from Shim Safety Control Rod #2 because of equipment malfunction. Control Rod Drive replaced.

8/24/2010 Reactor scrammed due to a dropped rod. Magnet current was lost from Shim Safety Control Rod #1 and #2 because of indeterminate equipment malfunction.

8/25/2010 Reactor scrammed due to high level alarm on Safety Power Channel # 1. The reactor operator approached 1MW too quickly which caused the alarm.

8/25/2010 Reactor scrammed due to a dropped rod. Mechanical resistance on Shim Safety Control Rod #1 caused it to drop, and vibrations from this drop caused Shim Safety Control Rod

  1. 2 to drop.

8/26/2010 Reactor scrammed due to a dropped rod. Magnet current was lost from Shim Safety Control Rod #1 because of equipment malfunction. Control Rod Drive Module replaced.

8/26/2010 Reactor scrammed due to a dropped rod. Magnet current was lost from Shim Safety Control Rod #2 because of indeterminate equipment malfunction.

8/26/2010 Reactor scrammed due to a dropped rod. Magnet current was lost from Shim Safety Control Rod #2 because of indeterminate equipment malfunction.

8/26/2010 Reactor scrammed due to a dropped rod. Magnet current was lost from Shim Safety Control Rod #2 because of equipment malfunction. The electromagnet was found to be dirty and was cleaned.

9/1/2010 Reactor scrammed due to a dropped rod. Magnet current was lost from Shim Safety Control Rod #1 because of equipment 10

Texas A&M University System Nuclear Science Center Annual Report 20 10 malfunction. A loose wire was repaired in the SSCR#1 Control Rod Drive Module.

9/8/2010 Reactor scrammed due to loss of electricity from offsite.

10/14/2010 Reactor scrammed due to a dropped rod. Magnet current was lost from Shim Safety Control Rod #4 because of indeterminate equipment malfunction.

10/14/2010 Reactor scrammed due to a dropped rod. Magnet current was lost from Shim Safety Control Rod #4 because of equipment malfunction. The electromagnet was found to be dirty and was cleaned.

12/3/2010 Reactor scrammed due to high level alarm on Safety Power Channel # 1. The reactor operator approached 1MW too quickly which caused the alarm.

4.4 Emergency Plan and Review The Nuclear Science Center Management and the members of Reactor Safety Board (RSB) reviewed the NSC Security and Emergency Plans. The Emergency Plan is undergoing a revision to incorporate minor changes in the plan. The update on the Security Plan to include the Compensatory Measures and finger printing requirements were discussed. There has been no mandate to update the security plan by the NRC.

4.5 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 twice in the year 2010. First meeting was in May 2010 as per the Technical Specifications requirement and there were no pending items. The second meeting was conducted to go through a specific experiment safety analysis. Appendix B provides the reactor safety board membership.

4.6 Inspections and Audits The Reactor Safety Board sub- committee 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 2010 for the Health Physics program and no deficiencies were identified.

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Texas A&M University System Nuclear Science Center Annual Report 20 10 4.7 Notice of Violation The NSC received a Non-Cited Violation (Severity Level IV) which "Constitutes a violation of minor significance that is not subject to enforcement action in accordance with Section IV of the Enforcement Policy" in NRC Routine Inspection Report NO. 50-128/2009-201. This violation was the result of deficiencies in the NSC Reactor Operator Requalification Program. The deficiencies were addressed and the facility is in compliance.

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 2010 assured minimal exposure during sample handling, shipment of radioactive material, and normal reactor operation. The radiation exposures were maintained ALARA. During 2010, about 303 radioactive samples were handled of which 288 samples were released to various research facilities including Texas A&M University campus and the rest were retained at the Nuclear Science Center facility. A total of 357 curies were handled in 2010.

5.2 Personnel Monitoring Personnel Monitoring was provided on a monthly basis to approximately 41 personnel. All measured doses to personnel were below the limits set forth in 10 CFR 20. Five individuals received whole body dose greater than 10% of the annual limit in 10 CFR 20. Their deep dose equivalent (DDE) recorded were 503, 546, 593, 521, and 951 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 2010. A total of 5.90 manrem was recorded for the year 2010. When total manrem/curie was determined for 2010, the dose per curie equaled 0.0165 (manrem/Ci).

During 2010, about 1882 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.

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Texas A&M University System Nuclear Science Center Annual Report 20 10 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 350 smear samples were collected and evaluated each month. All accessible areas at the NSC wear surveyed for radiation and contamination levels monthly. Areas where contamination is expected, access/egress controls are in place and are evaluated on shorter intervals. Building monitors and Area monitors were placed at strategic locations in the reactor facility, this provides 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 2010.

Table 5-3: Total Dose Equivalent (mrem) Recorded on Area Monitors Accumulated Dose Monitor ID Location Equivatet Dose Equivalent (mrem)

BLDG MNTR I Upper Research Level 1273 Mezzanine BLDG MNTR 2 Lower Research Level 1955 Mezzanine BLDG MNTR 3 Lower Research Level 603 AREA Control Room 84 AREA Upper Research Level 922 AREA Room next to MHA 3809*

  • Radioactive materials were stored in the temporary locations in MHA.

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 3.71x10- 3 pCi/cc. The total radioactivity released for 2010 was 28.6 pCi. Table 5-4 summarizes monthly particulate effluent releases during 2010. The most common isotopes noted during particulate effluent releases were Sc-46, Sb- 124, and Ir- 192.

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Texas A&M University System Nuclear Science Center Annual Report 20 10 Table 5-4: Particulate Effluent Releases Concentration Dilution Exhaust Additional Actit Quarter Month From FAM Concentration Volume Releases Released Channel 1 (tli/icc) (c L0 Rlae (ttCi/cccc)cc) (1 iCi) (Ci)

January 7.46x10" 3 3.73x10" 5 9.32x10"2 6.95x10-6 February 3.16x10-13 1.58x10-15 9.96x10"2 3.14x10"6 I March 2.66x10"3 1.33x10" 5 9.96z1012 2.65x10"6 Average: 4.42x10"13 2.21x10Is 5 9.74x10"2 4.25x10"6 Total: 2.92x1013 O.OOE+00 1.27x10"5 April 1.90x10" 14 9.49x10-17 9.64x1012 1.83x10-7 May 6.63x10-13 3.31x10" 5 9.96x10"2 6.60x10" 6 II June 1.52x10" 3 7.61x10-16 9.64x1012 1.47x10"6 Average: 2.78x10"13 1.39x10"'s 9.74x1012 2.75x10"6 Total: 2.92x1013 O.OOE+00 8.25X10"6 3

July 6.50x10-1 3.25x10" 5 9.96x1012 6.48x10"6 August <BG <BG 9.96x 1012 <BG HI September <BG <BG 9.64x 1012 <BG 3

Average: 6.50x10"1 3.25x10"'5 9.85x10' 2 6.48x10-6 Total: 2.96x1013 O.OOE+00 6.48x106 3

October 1.13xl0- 5.65xi0"16 9.96x1012 1.13xl0"6 November <BG <BG 9.64x1012 <BG IV December <BG <BG 9.96x1012 <BG Average: 1.13x10-13 5.65x10-16 9.85x1012 1.13x10"6 Total: 2.96x1012 O.OOE+00 1.13x10"6 Annual Average: 3.71x10-13 1.85x10' 5 9.80x1012 3.65x10 6 Summary Total: 1.18x1014 2.86x10 5 notes:

1. Concentration released from stack: Concentration sampled from FAM ( Facility Air Monitor) Channel 1
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 ft3/min)/ (3.53x10"5 cc)
4. Additional Release equal to: (Individual releases calculated from facility air monitoring data)
5. Total Activity Released equal to: (Average release concentration)*(Exhaust Volume)* 106+(Additional Releases)
6. <BG indicates that the monthly count rates were less than the background count rates.

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 2010 was approximately 4.66 Ci with an annual average release concentration of 3.97x10 8 [iCi/cc. Table 5-5 summarizes monthly gaseous effluent (Ar-41) releases during 2010.

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Texas A&M University System Nuclear Science Center Annual Report 20 10 Table 5-5: Gaseous Effluent (Ar-41) Releases Concentration Conetat Dilution Exhaust Additional Total Activity Quarter Month Channel 3 Concentration Volume Releases Released (laCi/cc) 3 (jCi/cc) (cc) (WCi)

(p~i/cc)(Ci)

January 8.80x10"8 4.40x10-'0 9.96x1012 8.77x10l' February 5.15x10"8 2.58x10-' 0 8.99x1012 4.64x10-'

I March 4.21x10"8 2.11 x10-' 0 9.96x1012 4.19x10l' Average: 6.06x10 8 3.03x10-' 0 9.64x1012 5.87x10' Total: 2.89x10 13 O.OOE+00 1.76 April 1.82xl0"8 9.1 1xl0"-1 9.64x1012 1.76x10' May 3.93x10 8 1.97x10l' 9.96x1012 3.91x10"'

II June 5.60 xl0"' 2.80x10' 0 9.64x1012 5.40x10l' Average: 3.79x10-8 1.89x10-" 9.74x1012 3.69x10-1 Total: 2.92x1013 O.OOE+00 1.11 July 1.64x10 8 8.18x10l" 9.96x1012 1.63x10'-

August 3.61x10s 1.80x10l' 9.96x1012 3.17x10-5 3.59x10-'

I September 3.13x10 8 1.56x101' 9.64x1012 3.02x10"'

Average: 2.79x10 4 1.40x10"'0 9.85x10 12 3.17x10 5- 2.75x10'-

Total: 2.96x1013 3.17x10-5 8.24x10-1 October 1.22x10-8 6.09x10-l 9.96x1012 1.21x10' November 1.72x10"9 8.61x10"12 9.64x1012 1.66x10-2 IV December 8.35x10 8 4.17x10' 0 9.96x1012 2.24x101 8.32x10-'

Average: 3.25x10-8 1.62x10"l' 9.85x10 12 2.24x101 3.23x10'-

2.96x1013 2.24x10 1 9.69x10-1 Annual Average: 3.97x10s 1.98x10-10 9.77x1012 1.12x10 1 3.88x10-1 Summary Total: 1.17x10 14 2.24x10' 4.66 notes:

1. Concentration released from the stack equal to: Activity from FAM Channel 3
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)*( 24 hrs/day)*(60 min/hr)*( 7875 ft3 /min)/ (3.53x10-5 cc)
4. Additional Release equal to: (Individual releases calculated from facility air monitoring data)
5. Total Activity Released equal to: (Average Release Concentration)*(Exhaust Volume)* 106+

(Additional Releases) 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 15

Texas A&M University System Nuclear Science Center Annual Report 20 10 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 25 releases in 2010, totaling 3.97x 10 5 gallons including dilution. The total radioactivity released was 4.42 mCi with an annual average concentration of 2.94x10-6 jCi/cc. The annual dose to the public calculated from liquid effluents is about 2.33 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-51, Mn-54, Ir-192, Co-58, Co-60, Zn-65, Sb-122, Sb-124, and Cs-137.

Table 5-6: Liquid Effluent Releases Number Volume Total Average Quarter Month of Released (cc) Radioactivity Concentration Releases (Ci) (ILCi/cc)

January 2 8.86x107 3.10xlO-4 3.50x10-6 February 2 1.15x10 8 3.99x10-4 3.47x10-6 March 0 - - -

Total 2 2.04x10s 7.10x10 4 3.48x10-6 April 2 1.18x10 8 4.08x10-4 3.46x 10-6 May 4 2.39x 108 7.63x 104 3.20x 10-6 June 3 2.25x10 8 6.68x 104 2.97x 10-6 Total 9 5.82x 108 1.84x10-3 3.16x10-6 July 1 5.40x 107 1.33x10-4 2.47x 10-6 August 5 2.65x10 8 4.33x10-4 1.63x 10-6 September 4 1.98x10 8 8.5Ox 10-4 4.29x 10-6 Total 10 5.17x10 8 1.42x10-3 2.74x10-6 October 1 7.82x10 7 2.79x10-4 3.57x10-6 November 1 1.22x 108 1.80x10-4 1.47x 10-6 December 0 - - -

Total 2 2.01x10 8 4.60x10- 4 2.29x10-6 Annual Total 25 1.50x109 4.42x10- 3 Summary 2.94 x10-6

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 16

Texas A&M University System Nuclear Science Center Annual Report 2010 other at 0.25 miles SE of facility. A quarterly sampling and analysis of NSC creek sediment were included in the program. Effective September 2008, NSC no longer discharges liquid waste through the creek but through the municipal sewer system.

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 gR/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.

Additional TLDs were placed on the south side of the facility during the fourth quarter to accommodate a boundary extension. The boundary extension enveloped a small lab building exterior to the existing site boundary.

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 0.2 mrem/yr. This is added to the deep dose to determine the total dose to the general public and the maximum dose noted was 1.5 mrem. Table 6-2 summarizes the site boundary dose rates.

17

Texas A&M University System Nuclear Science Center Annual Report 20 10 Table 6-2: Site Boundary Dose Rates OuInrtdpriv F nngurir TLD Deep Internal Total Site # Location r .. Dose Dose Dose Dose rates (mrem/91 days) (mrem)

(mrem) (mrem) (mrem) 300ft W of 2 2.0 1.9 3.3 3.7 11.0 0.7 0.2 0.9 reactor building 250ft WSW of 3 0.0 0.9 0.0 0.0 1.0 0.1 0.2 0.3 reactor building 200ft NW of 4 3.1 2.8 5.4 8.3 20.0 1.3 0.2 1.5 reactor building 225ft NE of 5 0.0 0.9 4.3 1.8 7.0 0.4 0.2 0.6 reactor building 190ft SE of 10 0.0 0.0 1.1 0.9 2.0 0.1 0.2 0.3 reactor building 300ft NE of 11 0.0 0.0 1.1 0.9 2.0 0.1 0.2 0.3 reactor building

  • 14 3mi NW of 0.0 0.0 0.0 0.0 0.0 0.0 0.2 0.2 facility 375ft NE of 18 2.0 2.8 2.2 3.7 11.0 0.7 0.2 0.9 reactor building 320ft NE of 19 0.0 0.0 0.0 0.0 0.0 0.0 0.2 0.2 reactor building
  • 23 0.25mi SE of 0.0 0.0 0.0 0.0 0.0 0.0 0.2 0.2 facility 300ft SSW of 26 - - 0.9 1.0 0.1 0.2 0.3 reactor building 300ft SSE of 27 - - 0.0 0.0 0.0 0.2 0.2 reactor building 28 300ft S of reactor

- - 0.0 0.0 0.0 0.2 0.2 building 300ft SW of 2.8 29 - - 3.0 0.2 0.2 0.4 reactor building

  • 14 and 23 are background TLD's 18

Texas A&M University System Nuclear Science Center Annual Report 20 10

7. Radioactive Waste Shipments During the year 2010, there were no radioactive waste shipments. Low level radioactive waste is temporarily stored onsite awaiting segregation. The NSC periodically segregates and sorts this waste depending on the level of radioactivity.

19

Texas A&M University System Nuclear Science Center Annual Report 2010 APPENDIX A NuclearScience Center Organizational Chart (updated Atmh 2011) 2 .~, >>' ~Ž $, OWarren R eee Directo

.'S James Remhinger Wqen-Hsing Hsu

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  • NSCNuclear4 * * .'Ra'"dtoa.di'&e kaoEnuineerinL Chris Speaks, ReanrF perzitor' ~Research'

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20

Texas A&M University System Nuclear Science Center Annual Report 20 10 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 Dr. Latha Vasudevan, NSC RSO Nuclear Science Center Mr. Jim Remlinger, Associate Director Nuclear Science Center Dr. Raymond Juzaitis, Professor and Head Nuclear Engineering Department Mr. Daniel Menchaca, RSO Environmental Health and Safety Department 21

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