ML15070A532

From kanterella
Revision as of 14:24, 31 October 2019 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Resubmission of Tamus/Tees Nuclear Science Center - 2013 Annual Report
ML15070A532
Person / Time
Site: 05000128
Issue date: 03/09/2015
From: Newhouse J
Texas A&M Univ
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
2015-0015
Download: ML15070A532 (20)
v • d • e


Text

JJI TEXAS A&M ENGINEERING EXPERIMENT STATION NUCLEAR SCIENCE CENTER March 9, 2015 2015-0015 Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

TAMUS/TEES Nuclear Science Center, License R-83, 2013 Annual Report Resubmission To Whom It May Concern:

This copy of our 2013 Annual Report was requested in support of our ongoing license renewal.

A previous copy could not be located. If you have any questions, please contact Mr. Jerry Newhouse at 979-845-7551.

Sincerely, Jerry Newhouse Assistant Director Nuclear Science Center Texas A&M Engineering Experiment Station Xc: 2.1 1/Central File TEL. 979.845.7551 1 FAX 979.862.2667 nsc.tamu.edu 1095 Nuclear Science Rd. I 3575 TAMU I College Station, TX 77843-3575

Texas A&M University System Texas Engineering Experiment Station 2013 Annual Report Facility Operating License R-83 Nuclear Science Center 1095 Nuclear Science Road College Station, Texas 77843-3575 Prepared By: Ashley Booth, NSC RSO Reviewed By: R. Skoda, NSC Director April 2014

Texas A&M University System Nuclear Science Center Annual Report 2013 CONTENTS

1. Introduction .......................................................................................................................... 4 1.1 N uclear Science Center Staff ............................................................................. 5
2. Reactor Utilization for 2013 .......................................................................................... 5 2.1 TA M U 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 Maintenance and Surveillance ........................................................................... 8 4.1 Scheduled M aintenance ...................................................................................... 8 4.2 Unscheduled Shutdowns ...................................................................................... 9 4.4 Emergency Plan and Review ............................................................................. 11 4.5 Reactor Safety Board ........................................................................................ 11 4.6 Inspections and A udits ...................................................................................... 11 4.7 N RC Inspection .................................................................................................. 12
5. Health Physics Surveillance ........................................................................................... 12 5.1 Radioactive Shipments ...................................................................................... 12 5.2 Personnel M onitoring ........................................................................................ 12 5.3 Facility Monitoring .......................................................................................... 13 5.4 Particulate Effluent Monitoring ........................................................................ 13 5.5 Gaseous Effluent M onitoring ............................................................................. 14 5.6 Liquid Effluent Monitoring ............................................................................... 15
6. Environm ental M onitoring ............................................................................................. 16 6.1 Environm ental Sam ples ................................................................................... 17 6.2 Site Boundary D ose Rate ................................................................................. 17
7. Radioactive W aste Shipm ents ...................................................................................... 19 Appendix A : N SC Organization Chart ...................................................................................... 20 Appendix B: Reactor Safety Board M em bership ..................................................................... 21 2

Texas A&M University System Nuclear Science Center Annual Report 2013 List of Tables Table 2 : Reactor Utilization Summary in 2013 ................................................................. 6 Table 4-2: 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 2013

1. Introduction The Texas A&M Engineering Experiment Station (TEES) 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 neutron radiography system, a hot cell with manipulator arms, and other supporting facilities. Moreover, NSC has a Cs-137 calibrator for use in instrument calibration.

Laboratory facilities include counting laboratories with gas flow proportional detectors and High Purity Germanium detectors, a pneumatics sample transfer system, a fast neutron irradiation system, and a delayed neutron detection system.

The NSC reactor design allows for easy loading/unloading of various types of samples. The NSC actively produces a variety of radioisotopes for academic and industrial 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 1700 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.

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 Director of the NSC is responsible to the Deputy Director of TEES for the administration and the proper and safe operation of the facility. The NSC Radiation Safety Office is responsible 4

Texas A&M University System Nuclear Science Center Annual Report 2013 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 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 2013 The Nuclear Science Center (NSC) reactor has been in operation since 1961. The reactor is a 1 MW MTR-converted TRIGA reactor. 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 2273.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> in 2013 with a total integrated power of 93.6 MW-days. There were 577 "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 583.5 MW-days. Table 2 shows the reactor utilization summary in 2013 and Figure 2 shows the annual reactor utilization in MW-hrs of operation.

Table 2: Reactor Utilization Summary in 2013 Days of Reactor Operation 229 Integrated Power (MW-days) 93.6 Number of Hours at Steady-State 2273.5 Number of Pulses 70 Number of Reactor Irradiations (RFS) 577 Number of Visitors 1687 Unscheduled Shutdowns 15 5

Texas A&M University System Nuclear Science Center Annual Report 2013 Megawatt Hours of Operation 3000 2500 2413.4 C

2080.8

  • 2000 1951.2 1915.2 1982.4 1891 1778.4 1834.6 1748.84 0

1500 4a-1000 50 500 0

2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 Year Figure 2. Annual Reactor Utilization in MW-hrs of Operation 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 6

Texas A&M University System Nuclear Science Center Annual Report 2013 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 3.1 Facility Air Compressor 3.2 Experiment Authorization and Modification Authorization There were no new Experiment Authorizations (EA) or Modification Authorizations (MA) covered in 2013.
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 June 2013 gave the following results. The total rod worth was $13.39. The most reactive control rod was Shim Safety #4 with a worth of $3.414. The shutdown margin was $3.887 and core excess was

$4.54. Scram times on all rods were less than 1.2 seconds. In addition, operators performed calorimetric calibration following each maintenance period, and fuel inspections with no abnormalities noted (as required by the Technical Specification). The cold critical reactivity worth, performed for each reactor experiment, shows that the most reactive fixed experiment is the Fast Flux Irradiation Device (-$ 1.141).

7

Texas A&M University System Nuclear Science Center Annual Report 2013 4.2 Unscheduled Shutdowns There were fifteen unscheduled reactor shutdowns during 2013. The cause is detailed below in Table 4-3.

Table 4-2: Unscheduled Shutdowns 1/8/2013 Reactor scrammed due to loss of off-site power.

3/25/2013 Reactor scrammed due to high level alarm on Safety Power Channel #2 during power transient while operating against the graphite-filled coupler box.

4/25/2013 Reactor scrammed manually by the control room operator after an object fell into the reactor pool.

5/3/2013 Reactor scrammed manually by the control room operator after two experiments became tangled on each other near the core.

7/3/2013 Reactor scrammed due to loss of power to the operating console.

7/22/2013 Reactor scrammed manually by the control room operator after position indication of the regulating rod was lost.

7/24/2013 Reactor scrammed manually by the control room operator after position indication of the regulating rod was lost.

7/30/2013 Reactor scrammed due to high level alarm on Safety Power Channel #1 during power transient.

7/31/2013 Reactor scrammed manually by the control room operator after observing malfunction of Shim Safety Control Rod #1.

10/30/2013 Reactor scrammed manually by the control room operator after observing malfunction of the FAM system.

11/5/2013 Reactor scrammed due to activation of the BP4 cave interlock.

8

Texas A&M University System Nuclear Science Center Annual Report 2013 11/11/2013 Reactor scrammed due to high level alarm on Safety Power Channel #2 during power transient while operating against the graphite-filled coupler box.

12/16/2013 Reactor scrammed due to rod drop of Shim Safety Control Rods # 1&2 following vibration on the support bridge.

12/19/2013 Reactor scrammed due to rod drop of Shim Safety Control Rod

  1. 4.

12/19/2013 Reactor scrammed manually by operator error.

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.

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 as required in the year 2013.

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 2013 for the Class II research and test reactor safety programs; no deficiencies were identified.

4.7 NRC Inspection Results The NRC conducted an inspection of the NSC in November of 2013. This inspection resulted in zero findings or violations. Additionally, previous findings regarding medical evaluations were placed in a closed status. The full inspection report is available upon request.

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 9

Texas A&M University System Nuclear Science Center Annual Report 2013 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 2013 assured minimal exposure during sample handling, shipment of radioactive material, and normal reactor operation. The radiation exposures were maintained ALARA. During 2013, about 391 radioactive samples were handled and released to various facilities including Texas A&M University campus. A total of 559 curies were handled in 2013.

5.2 Personnel Monitoring Personnel Monitoring was provided on a monthly basis to approximately 66 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 .53, .56, .59, .62, and .65R 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 2013. A total of 9.8 manrem was recorded for the year 2013. When total manrem/curie was determined for 2013, the dose per curie equaled 0.018 (manrem/Ci).

During 2013, about 1687 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 monthly 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. All areas accessible to the general public at the NSC were surveyed for radiation and contamination levels monthly by ion chamber readings and evaluation of smear samples. Areas where contamination is expected are access/egress controlled and are evaluated on shorter intervals as needed. 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 2012.

10

Texas A&M University System Nuclear Science Center Annual Report 2013 Table 5-3: Total Dose Equivalent (mrem) Recorded on Area Monitors Monitor ID Location Accumulated Dose Equivalent (mrem)

BLDG MNTR 1 Upper Research Level 774 Mezzanine BLDG MNTR 2 Lower Research Level 3813a Mezzanine BLDG MNTR 3 Lower Research Level 768a AREA Control Room 47 AREA Upper Research Level 1472 AREA Room next to MHA 441 b aRadioactive shipments were stored in the LRL area pending transport bRadioactive materials were stored in the temporary locations in MHA.

11

Texas A&M University System Nuclear Science Center Annual Report 2013 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 2.98x101 5 [tCi/cc. The total radioactivity released for 2013 was 53.8 p.Ci. Table 5-4 summarizes monthly particulate effluent releases during 2013. The most common isotopes noted during particulate effluent releases were Sc-46, Sb- 124, and Ir- 192.

Table 5-4: Particulate Effluent Releases January <BG <BG 9.96E+12 <BG I

February March 3.40E-13 1.30E-13 1.70E-15 6.51E-16 8.99E+12 9.96E+12

] _3.06E-06 1.30E-06 Average: 2.35E-13 1.18E-15 9.64E+12 1.45E-06 Total: 2.89E+13 4.36E-06 April 4.35E-13 2.18E-15 9.64E+12 4.19E-06 May 1.04E-12 5.22E-15 9.96E+12 1.04E-05 II June 3.39E-13 1.69E-15 9.64E+12 3.27E-06 Average: 6.06E-13 3.03E-15 9.74E+12 5.96E-06 Total: 2.92E+13 1.79E-05 July <BG <BG 9.96E+12 <BG August 7.22E-13 3.61E-15 9.96E+12 7.19E-06 III September <BG <BG 9.64E+12 <BG Average: 7.22E-13 3.61E-15 9.85E+12 7.19E-06 Total: 2.96E+13 7.19E-06 October 5.28E-13 2.64E-15 9.96E+12 5.26E-06 November 2.60E-13 1.30E-15 9.64E+12 2.50E-06 IV December 1.67E-12 8.36E-15 9.96E+12 1.67E-05 Average: 8.20E-13 4.10E-15 9.85E+12 8.14E-06 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/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)* 10A-6+(Additional Releases) 12

Texas A&M University System Nuclear Science Center Annual Report 2013 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 2013 was approximately 0.44 Ci with an annual average release concentration of 8.49x10- 8 ýtCi/cc. Table 5-5 summarizes monthly gaseous effluent (Ar-41) releases during 2013.

Table 5-5: Gaseous Effluent (Ar-41) Releases February <BG <BG 8.99E+12 <BG I March 1.54E-07 7.68E-10 9.96E+12 j 1.53E+00 Average: 9.28E-08 4.64E-10 9.64E+12 I 9.24E-01 Total: 2.89E+13 1.85E+00 April 3.17E-08 1.58E-10 9.64E+12 3.05E-01 May 6.44E-08 3.22E-10 9.96E+12 6.41E-01 11 June 6.45E-08 3.22E-10 9.64E+12 6.22E-01 Average: 5.35E-08 2.68E-10 9.74E+12 5.23E-01 Total: 2.92E+13 1.57E+00 July 3.11E-08 1.55E-10 9.96E+12 3.10E-01 August 2.24E-08 1.12E-10 9.96E+12 1.07E+05 3.30E-01 III September <BG <BG 9.64E+12 <BG Average: 2.68E-08 1.34E-10 9.85E+12 1.07E+05 3.20E-01 Total: 2.96E+13 1.07E+05 6.40E-01 October 7.43E-08 3.72E-10 9.96E+12 1.47E+05 8.87E-01 November <BG <BG 9.64E+12 <BG IV December 2.58E-07 1.29E-09 9.96E+12 6.23E+05 3.20E+00 Average: 1.66E-07 8.32E-10 9.85E+12 3.85E+05 2.04E+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 2013 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 24 releases in 2013, totaling 3.4x10 5 gallons including dilution. The total radioactivity released was 2.76 mCi with an annual average concentration of 2.13x10- 6 .Ci/cc. The annual dose to the public calculated from liquid effluents is about 1.18 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 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 Volume Released Total Average Number of Quarter Month Releases (cc) Radioactivity (Ci) Concentration January 4 2.13E+08 3.84E-04 1.80E-06 February 0 March I 4.96E+07 6.31E-05 1.27E-06 Total 5 2.63E+08 4.47E-04 1.70E-06 April I 6.44E+07 3.8 1E-04 5.92E-06 May 2 9.44E+07 2.12E-04 2.24E-06 June 4 2.14E+08 5.29E-04 2.48E-06 Total 7 3.72E+08 1.12E-03 3.01E-06 July 3 1.52E+08 1.26E-04 5.52E-06 III August 2 9.54E+07 6.83E-05 1.45E-06 September 3 1.74E+08 4.40E-04 2.27E-06 Total 8 4.21E+08 6.34E-04 1.50E-06 October 2 9.78E+07 1.7 IE-04 1.75E-06 November 1 6.87E+07 1.96E-05 2.86E-07 December 1 6.87E+07 3.69E-04 5.37E-06 Total 4 2.35E+08 5.59E-04 2.40E-06 Annual Total 24 1.29E+09 2.76E-03 2.13E-06 Summary 14

Texas A&M University System Nuclear Science Center Annual Report 2013

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 92 days using TLDs. Monthly measurements of direct gamma exposure rate in ptR/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.

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 15

Texas A&M University System Nuclear Science Center Annual Report 2013 Table 6.2: Site Boundary Dose Rates 2013 Internal TLD Deep Dose Total Quarterly Exposure rates Dose Dose=TLD (mrem)_c Dose Site # Location (torero/91 days) (total) dose*(1/16) omply (mrsm) 300 ft. W of reactor building, 2 near fence comer 9 3 10 17 39 2.4375 0.1 2.5375 250 ft W-SW of reactor building, 3 on SW chain fink fence 8 6 8 8 30 1.875 0.1 1.975 200 ft NW ofreactor building, on 4 chain link fence, near butane tank 14 6 13 10 43 2.6875 0.1 2.7875 225 tl NE of reactor building, on 5 fence N of driveway 9 5 6 6 26 1.625 0.1 1.725 190 ft SE ofreactor buildhig, 10 near fence corner 7 5 7 4 23 1.4375 0.1 1.5375 300 ft NE ofreactor building, 11 near fence comer 7 6 4 0 17 1.0625 0.1 1.1625

  • 14 3.84 miles NW of facility 0 0 0 0 0 0 0.1 0.1 18 375 ftNE ofreactor building 8 6 8 6 28 1.75 0.1 1.85 19 320 ftNE of reactor building 3 5 3 4 15 0.9375 0.1 1.0375 20 E Wall ofaccelerator building 3 9 7 3 22 1.375 0.1 1.475 21 W Wall of accelerator building 5 1 5 6 17 1.0625 0.1 1.1625 22 S Wall ofaccelerator building 0 0 5 3 8 0.5 0.1 0.6
  • 23 0.25 miles SE offcility 6 0 5 4 15 0.9375 0.1 1.0375 North Wall of Accelerator 24 Building, First Floor 31 1 13 20 65 4.0625 0.1 4.1625 North Wall ofAccelerator 25 Building, Second Floor 10 0 5 13 28 1.75 0.1 1.85 W Fence of hyberbaric lab, IlOft 26 fromSW corner 9 3 3 5 20 1.25 0.1 1.35 E fence ofhyperbaric lab, lOft S 27 ofertrance 3 3 3 4 13 0.8125 0.1 0.9125 S fence ofhyperbaric lab, lOft E 28 ofpersonnel gate 8 1 5 4 18 1.125 0.1 1.225 325ft SW from reactor building 29 SW corner 6 5 6 7 24 1.5 0.1 1.6
  • Background TLDStation 16

Texas A&M University System Nuclear Science Center Annual Report 2013

7. Radioactive Waste Shipments In 2013, 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 11/13/2013. The material was hauled to EnergySolutions (formerly Duratek), and processing was completed on 02/09/2012.

There were a total of 812.27 kg of waste shipped, with a total volume of 6.9 mi3 . The total activity of the shipped waste was measured at 196.23 uCi (7.2MBq).

17

Texas A&M University System Nuclear Science Center Annual Report 2013 APPENDIX A Nuclear Science Center Organizational Chart Updated (2013) 8 I ii ler ewos Greg Stasnv Aeffles, Booth Joe Snack Deba lrringgltý7,n Drý Hsu Voc;int Mafrager of Operations i AsisatDrco 7R Radiological

'g"al Safety

'ý'J'ci'ýffrc'ý'

Off rcer S,'te", Machine Shop For eman Administrative Coordinator Resfarch Scientist Eng. Resf.,jrch Assc, L

I Scott Mille, James Hickman Varant Shandy Root Mastei instrument Heatlh Physics Machine. Shoin Reactor Super Foreman Maker Supervisor Sr. Reactor Operators Vikicir Vlassov Robert Pack Jim Reynolds Evilly Sutton jared Porter Instium I Technician It Machinist I Office Associaie ent Maker i- Vacant Businp-ss Coordinator

'lesst"Johns I

?ak Kulage t

Estýbarl Butello Anna Buffaloe Mathew Deck Student lech Student Workers Student Worler Russell Mozin&c; PC Apprentice/HP Techs; Wilham Winters Rebecca lone.s Carriencin McDonriel Nicholas Muwcrs Student Techrucians/HP Techsý Kyiorre Riley Hanna Moss Elizabeth Smith Jacob selter 18

Texas A&M University System Nuclear Science Center Annual Report 2013 Appendix B Reactor Safety Board Membership (2013)

Chairman:

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. Radek Skoda, Director Nuclear Science Center Mrs. Ashley Booth, NSC RSO Nuclear Science Center Dr. Yassin Hassan, Professor and Head Nuclear Engineering Department Dr. Latha Vasudevan, RSO Environmental Health and Safety Department 19

Retrieved from "https://kanterella.com/w/index.php?title=ML15070A532&oldid=2036216"