ML022960447

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Texas a & M University Research Reactor Annual Report
ML022960447
Person / Time
Site: 05000128
Issue date: 10/03/2002
From: Spellman M
Texas A&M Univ
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML022960447 (20)


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 October 3, 2002 2002-0059 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Z) '5r C/'-/ /-"/C, ý--' V -

To Whom This May Concern:

Enclosed is a copy of the TAMU Nuclear Science Center 2001 Annual Report. Please feel free to call me if you have any questions at 979-845-7551.

Sincerely, Michael Spellman AssiFtant Director Enclosure MS/jig xc: 2.1 1/Central File RESEARCH AND DEVELOPMENT FOR MANKIND http:l/nsc tamu edu

Texas A&M University Nuclear Science Center 2001 Annual Report "I

Nuclear Science Center Texas Engineering Experiment Station Engineering Program Texas A&M University System College Station, Texas

Texas A&M University System Texas Engineering Experiment Station Nuclear Science Center 2001 Annual Report Facility Operating License R-83 1095 Nuclear Science Road College Station, Texas 77843-3575 April 2002

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

1. Introduction ......................................................................................................................... 3 1.1 Nuclear Science Center Staff .............................................................................. 3
2. Reactor Utilization for 2000 ............................................................................................ 5 2.1 Research Enhancement Program (REP) .............................................................. 5 2.2 TAM U Academic Support Program ................................................................... 6 2.3 DOE University Reactor Sharing Program ......................................................... 6 2.4 Commercial Activity and External Research ..................................................... 6
3. Facility and Procedure Changes ..................................................................................... 7 3.1 Facility M odifications ......................................................................................... 7 3.2 Experiment Authorizations and M odifications ................................................... 7 4.1 Scheduled M aintenance ........................................................................................ 8 4.2 Unscheduled M aintenance .................................................................................. 8 4.3 Emergency Planning and Review ........................................................................ 9 4.4 Unscheduled Shutdowns ..................................................................................... 9 5.0 Health Physics Surveillance ......................................................................................... 10 5.1 Radioactive Shipments ..................................................................................... 10 5.2 Personnel M onitoring ....................................................................................... 10 5.3 Facility M onitoring ............................................................................................ 10 5.4 Particulate Effluent M onitoring ....................................................................... 11 5.2 Gaseous Effluents M onitoring ......................................................................... 12 5.6 Liquid Effluents M onitoring .............................................................................. 13 6.0 Environmental M onitoring ............................................................................................ 14 6.1 Environmental Survey Samples ....................................................................... 14 6.2 Site Boundary Dose Rate .................................................................................. 15 7.0 Radioactive W aste Shipments ....................................................................................... 17 8.0 Reactor Safety Board ..................................................................................................... 17 2

Texas A&M University System Nuclear Science Center Annual Report

1. Introduction The Texas A&M University 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, a 1-MW, pool-type TRIGA reactor, is at the heart of the NSC facilities which includes: a 2-MW micro-beam accelerator, a 60Co gamma calibration range, a real-time neutron radiography facility, a large-object irradiation cell, hot cells and manipulators, radiation measurement laboratories, radiochemical laboratories, five HPGe gamma spectroscopy systems, and a variety of instruments for radiation detection and measurement.

The NSC reactor design allows for easy load/unload of various types of samples. The NSC actively produces various kinds of radioisotopes for industry, hospitals, and academic users. The NSC provides nationally recognized neutron actii'ittion analysis (NAA) services to many research and academic institutions in the United States. The NSC reactor also actively supports the Nuclear Engineering Department on campus, one of the largest nuclear engineering programs in the United States. The NSC is one of the major attractions on campus. Last year alone, the NSC hosted 2,910 visitors including: elementary, middle, high school, and college students, faculty members, clients, and national laboratory and industrial scientists and engineers. Through these tours, the NSC teaches people with widely varying backgrounds what nuclear power is, and what radiation is and a little about nuclear science.

With the strong support from the University, the NSC is continuously increasing the diversity of its facilities and services. Currently, the NSC is developing a new Fast Flux Irradiation Device (FFID), which will have a cooling system to remove the heat generated in the device, a new topaz irradiation device for quality irradiation of gemstones, an 1251 recovery system and long-wire irradiation device. The NSC recently has completed development of the second generation Xe 124 irradiation system for 1251 production.

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). The facility license currently extends to March 2003.

1.1 Nuclear Science Center Staff The staff at the Nuclear Science Center consists of into five groups including: Reactor Operations, Reactor Maintenance, Health Physics, Technical Coordination, and Administrative Service (see Figure 1). 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.

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Texas A&M University System Nuclear Science Center Annual Report Nuclear Science Center January 2002 Dan Reece Director Senor Reactor Operator Mike Spetman Assistant Director Senior Reactor Operator -

,BI1 Asher Tom Fisher Vasudevan Jm iLatha Remlinger Joy Rbardo Manager Supervisor Radiologicat Safety Officer Technical Coordinator Manager Reactor Operations Reactor Maintenance Health Physics Senior Reactor Operator Administrative Services Senior Reactor Operator . I Business Admer R acatoJoe Reactor Su Snookt JoeSnok VACANT VCAN Vacant Si Young Jang Yvonne Mitchell Foreman Scentic Instrument Maker Supervisor Graduate Student Accounting Assistant ItI Senior Reactor Operator Mechanical Shop Senor Reactor Operator Health Phtysics t peston Pratt Preto Pratt I Elz Gozae Senior Reactor Operator Troy Bohnert Technician I Tim Hinkle SudenttTech OMatenal I Bob Pack Control DirnitryJittchenkcyv Graduate Student i EkaGnae Senior Secretary

[ Mechanical Maintenance S Brad Orth Dirsen Dunlap Rob Buchheit Sung Woo Lee SnoRecoOprtr Student Tech Technician IGraduate I IHP 1 1Student SB ~1Vacant HP Technician It Wen-Sing Hsu Graduate Student Sento TectI S Tec SdStudent TechI Figure 1-1. NSC Organization Chart The Texas Engineering Experiment Station (TEES) of the Texas A&M University System operates the Nuclear Science Center (NSC). The Director of the Nuclear Science Center (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) provides assistance when it is required for emergencies and for special operations as agreed.

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Texas A&M University System Nuclear Science Center Annual Report

2. Reactor Utilization for 2000 The Nuclear Science Center (NSC) reactor has been in operation since 1962. The reactor is a 1 MW, MTR-converted TRIGA reactor. The reactor uses highly enriched uranium fuel (70%), but will use a 20% enriched fuel core when DOE funds become available. Core VIII-A is the current core configuration and has been in use since March 1986. The NSC reactor is pulse 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 1935.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in 2001 with a total integrated power of 81.1MW "days. There were 624 irradiations and services performed at the NSC during the reporting period. The NSC provided services to TAMUS 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 90% of availability in 2000.

Table 2-1. Reactor Utilization Summary in 2001 Days of Reactor Operation 233 Integrated Power (MW-days) 81.1 Number of Hours at Steady-State 1935.1 Number of Pulses 65 Number of Reactor Irradiations (RFS) 625 Beam Port/Thermal Column Experiment Hours 968 Hours Irradiation Cell Use 587 Number of Visitors 1919 Unscheduled Shutdowns 4

. 2,300 2,209 S2,200 2.120 2.155 2,1432,082

~2,100 O 2,000 1,944 1,924 1,963 1,945 0~~ 192 2,00 S1,900 1,700 1,600 1,500 1993 1994 1995 1996 1997 1998 1999 2000 2001 Year Figure 2-1. Annual Reactor Utilization 2.1 Research Enhancement Program (REP)

The 7 0 th Texas Legislature established the Research Enhancement Program (REP) in 1987 to "encourage and provide for research conducted by faculty members." The REP replaced the 5

Texas A&M University System Nuclear Science Center Annual Report former "Organized Research" program. The TAMU Office of the Vice President for Research administers the REP funds and generally allocates these funds to the NSC early in the fiscal year.

TAMUS faculty members who desire to use the irradiation services at the NSC reactor must apply at the NSC to receive local funding for each individual project. This proposal method is flexible and does not hinder a project's start-up time.

2.2 TAMU Academic Support Program Texas A&M University (TAMU) 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.

2.3 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 Nuclear Science Center (NSC) has participated in the program since 1980. During the 2000-2001-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 super conducting 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 39Ar/4°Ar dating.

2.4 Commercial Activity and External Research The NSC provides services to a variety of users who provide their own funding. The majority of commercial activities relate producing 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 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 their exposures during the transfer of radioactive materials to shipping shields.

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Texas A&M University System Nuclear Science Center Annual Report

3. Facility and Procedure Changes 3.1 Facility Modifications The following are facility modifications and maintenance items authorized and implemented in accordance with 10 CFR 50.59. NSC staff meeting minutes or RSB meeting minutes document the approval for these items as appropriate.

Safety Channel and Scram CircuitReplacement. (Alay 24,2001)

NSC staff built and installed a new safety power-measuring channel. The new instrument is functionally identical to the old instrument. The new drawer's test device is adjustable whereas the previous design was not. Individual continuous-monitoring magnet-power current meters replaced the selector switch with one meter. A NIM module houses and powers the new system.

The NSC staff and the Reactor Safety Board reviewed the new design through modification authorization (MA) #54.

Modification of Overlap CircuitFor Wide-Range Monitor NSC Electronics staff replaced two resistors in the wide range monitor (Log Drawer). These resistors control the overlap between the pulse counting and current measuring circuits.

Subsequent testing verified the improvement. The NSC staff reviewed the replacement and calculated the replacement would not affect any function of the safety system.

3.2 Experiment Authorizations and Modifications Second Revision to Experiment Authorization to Produce 1-25 (June1, 2001)

The latest change is for the modified xenon irradiation device- the modified device positions the target xenon gas in a higher flex for improved 1-125 yield. The new device also provides improved indications. Functionally, the device is unchanged. The Reactor Safety Board and the NSC staff reviewed the modifications per 10CFR50.59.

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Texas A&M University System Nuclear Science Center Annual Report

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 September 2001 gave the following results.

The total rod worth is $16.35. The most reactive control rod is Shim Safety #4 with a worth of

$4.32. The shutdown margin was $4.87 and core excess was $5.23. 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 Pneumatic Receiver

(-$1.35) with leveling high boron loading the negative worth.

4.2 Unscheduled Maintenance 01-04-01 Replaced diodes in the thermal column Continuous Air Monitor. This fault caused failure during regular maintenance 03-19-01 Replaced overhead crane controller.

04-30-01 Repaired and tested Rod-drive 'C' Engaged switch. Fault presented indication from resetting.

06-12-01 Replaced secondary pump adjustment bolts. Fault caused excessive seal leakage.

07-09-01 Replaced and repaired Irradiation Cell duct work.

07-25-01 Replaced overhead crane controllers. Operators dropped and broke the controller.

07-26-01 Replaced relays and other components on the Irradiation Cell man-lift.

07-31-02 Replaced, aligned and tested Transient Rod "Rod Down" switch. Failure prevented indication from returning to zero on insertion.

10-16-01 Replaced "Rod Down" switch on and made repair to control rod drive mechanism '3'. Rod Down indication failed.

09-24-01 Cleaned and inspected solenoid valve that silences the Evacuation Horn from The Reception Room. Silence function failed during regular maintenance.

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Texas A&M University System Nuclear Science Center Annual Report 11-06-01 Replaced all cables for the Facility Air Monitor equipment.

4.3 Emergency Planning and Review The NSC staff and Reactor Safety Board reviewed the NSC Security Plan on May 3, 2001 and December 6, 2001 respectively, Reactor Safety Board members completed all required external audits for the Emergency and Security plans during the reporting period.

4.4 Unscheduled Shutdowns There were 12 unscheduled reactor shutdowns occurred during 2000. Four shutdowns resulted from a loss of facility electrical power. The remaining causes are detailed below:

1-19-01 The Reactor Operator trainee repositioned the Safety-Power monitor test switch to the test position.

1-29-01 When approaching 1MW with the reactor positioned against the thermal couple 4-9-01 device, Safety Power Monitor #2 sees a high flux. The circuit over-responds 10-4-01 during a transient. The over-response sometimes causes high-power scrams 10-9-01 below 1MW. This happened five times.

10-9-01 6-11-01 Safety-Power monitor channel I caused a scram with the reactor at 1MW, steady state. NSC staff realigned the drawer.

11-13-01 Reactor scrammed when operators opened the Irradiation Cell door with the cell door scram interlock activated. The reactor was operating in the stall.

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Texas A&M University System Nuclear Science Center Annual Report 5.0 Health Physics Surveillance The purpose of Health Physics surveillance is to ensure safe use of radioactive materials in Nuclear Science Center's (NSC) 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 chemical and physical safety concerns as well as radiological. 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 2001 assured minimal exposure during sample handling, shipment of radioactive material, and normal reactor operation. The radiation exposures were maintained ALARA. During 2001, about 401 radioactive samples were handled of which 366 were sent to various research facilities including Texas A&M University campus and the rest retained at the Nuclear Science Center facility. A total of 279 curies were handled in 2001.

5.2 Personnel Monitoring Personnel Monitoring was provided to approximately 55 personnel. All measured doses to personnel were below the limits set forth in 10 CFR 20. One individual received whole body dose greater than 10% of the annual limit inl0 CFR 20. The dose recorded was 690-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 2001. A total of 3.83 manrem was recorded for all of 2001. When total manrem/curie was determined for 2001, the dose per curie equaled 0.0137.

During 2001, 1919 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 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 10

Texas A&M University System Nuclear Science Center Annual Report shorter intervals. Area monitors were placed at strategic locations in the reactor facility, this provides dose equivalent (mrem) on a monthly basis. The following table summarizes the annual accumulated dose equivalent (mrem) recorded on the area monitors for 2001.

Table 1. Total Dose Equivalent (mrem) Recorded on Area Monitors Monitor ID Location Accumulated Dose Equivalent (mrem)

BLDG MNTR I Upper Research Level 780 Mezzanine BLDG MNTR 2 Lower Research Level 180 Mezzanine BLDG MNTR 3 Lower Research Level 150 AREA Control Room 90 AREA Upper Research Level 620 AREA Hand and Foot Monitor 1110 Room 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 1.19E-1 I jCifcc. Total activity released for 2001 was 7.23E-04 Ci. The following table summarizes monthly particulate effluent releases during 2001.

Table 2. Monthly Particulate Effluent Releases Average Diluted Exhaust Total Release Conc. Concentration Volume Release Quarter Month (pCi/cc) ("Ci/cc) (cc) (Ci)

I January 1.93E- 11 9.65E-14 6.32E+12 1.22 E-04 February 1.53E-1 1 7.63E-14 5.71E+12 8.72E-05 March <MDA <MDA 6.32E+12 <MDA Average: 1.73E-11 8.64E-14 6.12E+12 1.05E-04 TOTAL 1.82E+13 2.09E-04 1I April 1.15 E-12 5.74E-15 6.12E+12 7.02E-06 May I <MDA I <MDA 6.32E+12 <MDA 11

Texas A&M University System Nuclear Science Center Annual Report June 1.51E- I1 7.53 E14 6.12E+12 9.21E-05 Average: 8.113-12 4.0513-14 6.19E+12 4.96E-05 TOTAL 1.86E+13 9.92E-05 III July 1.87E-1I 9.37E-14 6.32 E+12 1.19E-04 August 7.55E-12 3.78E-14 6.32 E+12 4.78E-05 September 7.86E-12 3.93E-14 6.12 E+12 4.81E-05 Average: 1.14E-11 5.69E-14 6.25 E+12 7.15E-05 TOTAL 1.88 E+13 2.14E-04 IV October 2.31E-12 1.16E-14 6.32 E+I2 1.46E-05 November 2.71E-11 1.35E-13 6.12E+12 1.66E-04 December 3.21E-12 1.60E-14 6.321E+12 2.03E-05 Average: 1.09E- 11 5.44E-14 6.25E+12 6.69E-05 I Total: 1.88E+13 2.01E-04 Annual Average: 1.79E-11 8.94E-14 6.20E+12 7.31E-05 Summary I Total: 7.43E+13 .7.23E-04 0 Minimum Detectable Activity (MDA) 4.5 E-14 pCi/cc 5.2 Gaseous Effluents 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 2001 was 5.203 Ci with an annual average release concentration of 6.96 E-8 PCi/cc and with a diluted concentration of 3.48 E-10 pCi/cc.

The following table summarizes monthly gaseous effluent releases during 2001.

Table 3. Monthly Gaseous Effluent Releases Average Diluted Exhaust Total Release Conc. Concentration Volume Release Quarter Month ("Ci/cc) (pCi/cc) (cc) (Ci)

January 6.74E-08 3.37E-10 6.32E1+12 4.26E-01 February 5.89E-08 2.95E-10 5.71E+12 3.36E-01 March 9.33E-08 4.67E-10 6.32E+12 5.90E-01 Average: 7.32E-08 3.66E-10 6.12E+12 4.51E-01 1.82E+13 1.35E+00 in April 1.62E-08 8.10E-1 1 6.12E+1 2 9.91E-02 12

Texas A&M University System Nuclear Science Center Annual Report May 8.62E-08 4.31E-10 6.32E+12 5.45E-01 June 1.16E-07 5.80E-10 6.12E+12 7.09E-01 Average: 7.28E-08 3.64E-10 6.19E+12 4.51E-01 1.86E+13 1.35E+00 III July 3.73E-09 1.86E-1 1 6.32E+12 2.35E-02 August 1.01E-07 5.05E-10 6.32E+12 6.38E-01 September 5.78E-08 2.89E-10 6.12E+12 3.53E-01 Average: 5.42E-08 2.71E-10 6.25E+12 3.39E-01 1.88E+13 1.O1E+00 IV October 5.34E-08 2.67E-10 6.32E+12 3.37E-01 November 1.56E-08 7.79E-11 6.12E+12 9.53E-02 December 1.66E-07 8.29E-10 6.32E+12 1.04E+00 Average: 7.82E-08 3.91E-10 6.32E+12 4.94E-01 1.88E+13 1.48E+00 Annual Average: 6.96E-08 3.48E-10 6.22E+12 4.34E-01 Summary_ 1_7.43E+13 5.20E+00

  • Minimum Detectable Activity (MDA) 6.2 E-10 pCi/cc 5.6 Liquid Effluents 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 21 releases in 2001, totaling 9.35E+5 gallons including dilution. The total radioactivity released was 7.16E-04 Ci with an annual average concentration of 2.02E-07 piCi/cc.

Summaries of the release data are presented in the table below. 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 Na4, Sc 46, Sb2 and Coe.

Fable 4. Monthly Liquid Effluent Releases

= I Total Average Number of Volume Radioactivity Concentration Quarter Month Releases Released (cc) (Ci) (PtCi/cc)

I January 1 2.17E+08 1.78 E-05 8.19E-08 February 3 6.79 E+08 4.36 E-05 6.42 E-08 March 1 1.12 E+08 7.01 E-05 6.27 E-07 Quarter Total: 5 1.01 E+09 1.31 E-04

+ t I II April 1 8.66 E+07 4.41 E-06 5.09 E-08 13

Texas A&M University System Nuclear Science Center Annual Report May 2 2.77 E--08 1.23 E-04 4.44 E-07 June 2 2.79 E+08 1.01 E-05 3.60 E-08 Quarter Total: 5 6.43 E+08 1.37 E-04 II July 1 2.65 E+08 9.78 E-06 3.70 E-08 August 1 1.08 E+08 5.31 E-06 4.91 E-08 September 3 6.43 E+08 1.26 E-04 1.97 E-07 Quarter Total: 5 1.02 E+09 1.41 E-04 IV October 3 5.11 E+08 1.34 E-04 2.61 E-07 November * * *

  • December 3 3.61 E+08 1.72 E-04 4.77 E-07 Quarter Total: 5 8.71 E+08 3.06 E-04 Annual Total: 21 3.54 E+09 7.16 E-04 2.02 E-07 Summary_
  • No releases 6.0 Environmental Monitoring In conjunction with representatives from the Texas Department of Health, Bureau of Radiation Control, a quarterly environmental survey program 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, and milk samples from the dairy downwind of the facility are also included in the program.

6.1 Environmental Survey 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 and milk samples from the dairy were analyzed using an intrinsic germanium detection system for isotopic identification at the NSC. A second set of sediment and milk samples were analyzed by the Texas Department of Health for comparison.

The concentrations of environmental samples determined for each quarter are listed below.

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Texas A&M University System Nuclear Science Center Annual Report Table 5. Environmental Sample Analysis MILK 2001 Quarter Sample Location Concentration (tCi/mL)

TDH Ist TAMU Dairy < 3.9 E-09 2 nd TAMU Dairy < 4.1 E-09 3 rd TAMU Dairy < 4.6 E-09 4 th TAMU Dairy < 3.1 E-09 SEDIMENT (g.tCi/g)-NSC

]st NSC creek 9.0 E-06 2 NSC creek 1.4 E-05 3 rd NSC creek 1.1 E-06 4th NSC creek 7.2 E-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 Prem/h are also made at each of the TLD locations. The dosimeters are provided and processed by Texas Department of Health (TDH), Bureau of Radiation Control, Division of Environmental Programs 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 approved code COMPLY was used. The exposure calculated via COMPLY was 0.093 mrem/yr. This exposure is added to the calculated total deep dose. This total is the dose received by the general public.

I Table 6. Site Boundary Dose Rates I 15

Texas A&M University System Nuclear Science Center Annual Report Site Location Quarterly Exposure Rate TLD Deep Internal Total Dose

  1. Dose Dose Dose (mrem)

(nreml9l days) (mrem) (mrem) 2 300 ft. W of 5.2 4.6 4.2 3.8 17.8 1.11 0.093 1.203 reactor building, near fence comer 3 250 ft W-SW 3.1 2.8 2.1 1.9 9.9 0.618 0.093 0.711 of reactor building, on SW chain link fence 4 200 ft NW of 9.3 8.4 6.3 7.6 31.6 1.975 0.093 2.068 reactor building, on chain link fence, near butane tank.

5 225 ft NE of 3.1 2.8 2.1 1.9 9.9 0.618 0.093 0.711 reactor building, on fence N of driveway 10 19Oft SE of 5.2 2.8 2.1 1.9 12 0.75 0.093 0.843 reactor building, near fence comer 11 300 ft NE of 2.1 0.9 1.0 1.9 5.9 0.368 0.093 0.461 reactor building, near fence comer 18 375 ft NE of 6.2 4.6 1 4.2 3.8 18.8 1.175 0.093 1.268 reactor building 16

Texas A&M University System Nuclear Science Center Annual Report 19 320 ft NE of 4.1 3.7 2.1 2.8 12.7 0.793 0.093 0.886 reactor building 14 3.84 miles 0.0 1.9 0.0 1.0 1.9 0.118 0.093 0.211 NW of facility I 23 0.25 miles 0.0 0.0 0.0 0.0 0.0 0.0 0.093 0.093 SE of facility 7.0 Radioactive Waste Shipments During the year 2001 there was no solid waste released from the NSC for disposal offsite.

8.0 Reactor Safety Board The Reactor Safety Board is responsible for providing an independent review and audit of the safety aspects of the NSCR. The RSB meets at least once a year to review audit reports, security and emergency plans, new experiments and modifications to the facility.

Membership (2001)

ChairmanfLicensee:

Dr. Glen Williams/Dr. B. Don Russell Texas Engineering Experiment Station Members:

Dr. Marvin Adams, Associate Professor Nuclear Engineering Department Dr. William Dennis James, Research Chemist Chemistry Department Dr. Robert Kenefick, Professor Physics Department Dr. Earl Morris, Professor Veterinary Medicine-Large Animal Medicine 17

Texas A&M University System Nuclear Science Center Annual Report Ex-Officio Members:

Dr. Warren Reece, Director Nuclear Science Center Latha Vasudevan, Ph. D, Radiological Safety Officer Nuclear Science Center Mr. John Salsman, Assistant Director, Radiological Safety Environmental Health and Safety Department Dr. Alan Waltar, Professor and Head Nuclear Engineering Department Mr. Robert Berry, Reactor Supervisor AGN201, Nuclear Engineering Department 18