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TEXAS ENGINEERING EXPERIMENT STATION

TEXAS A&M UNIVERSITY

3575 TAMUCOLLEGE STATION, TEXAS 77843-3575

NUCLEAR SCIENCE CENTER979/845-7551

FAX 979/862-2667

April 27, 2012 2012-0013

U.S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, D.C. 20555

Subject: 2011 Annual Report (Facility License R-83)

To WMhom It May Concern:

Enclosed please find the 2011 Annual Report for the Texas Engineering ExperimentStation Nuclear Science Center, Texas A&M University, College Station, TX 77843.If you bare any questions regarding this, please feel free to call me at (979) 845-7551.

Sincerely,

4eeactor Supervisor

Enclosur-e

Xc: 2.11/Central FileAnnual Report File

AGI9RESEARCH AND DEVELOPMENT FOR MANKIND

http://nsc.tamu.edu

Texas A&M University SystemTexas Engineering Experiment Station

2011 Annual Report

Facility Operating License R-83

Nuclear Science Center1095 Nuclear Science Road

College Station, Texas 77843-3575

April 2012

0

Texas A&M University System Nuclear Science Center Annual Report 2011

* CONTENTS

1. Introduction ......................................................................................................................... 41.1 Nuclear Science Center Staff .................................................................................. 5

2. Reactor Utilization for 2010..................................................................... ......... .52.1 TAM U Academic Support Program .................................................................... 72.2 Commercial Activity and External Research ..................................................... 7

3. Facility and Procedure Changes .................................................................................... 73.1 Facility M odifications ........................................................................................ 73.2 Experiment Authorization and Modification Authorization .............................. 7

4. Reactor M aintenance and Surveillance ........................................................................... 74.1 Scheduled M aintenance ...................................................................................... 74.2 Unscheduled Shutdowns ...................................................................................... 84.3 Emergency Plan and Review ............................................................................. 94.4 Reactor Safety Board ......................................................................................... 94.5 Inspections and Audits ...................................................................................... 10

5. Health Physics Surveillance .......................................... 10* 5.1 Radioactive Shipments ........................................ 10

5.2 Personnel M onitoring ........................................................................................ 105.3 Facility Monitoring ....... ................................... 115.4 Particulate Effluent M onitoring ........................................................................ 115.5 Gaseous Effluent M onitoring ............................................................................ 135.6 Liquid Effluent M onitoring .............................................................................. 14

6. Environm ental M onitoring ............................................................................................ 166.1 Environm ental Samples .................................................................................... 166.2 Site Boundary Dose Rate...................................................................................... 16

7. Radioactive W aste Shipments ...................................... ............................................... 18

Appendix A: NSC Organization Chart ..................................................................................... 19

Appendix B: Reactor Safety Board M embership ...................................................................... 20

2


0List of Tables

Table 2 : Reactor Utilization Summary in 2010 ................................................................. 6Table 4-2: Unscheduled Shutdowns ...................................................................................... 8Table 5-3: Total Dose Equivalent (mrem) Recorded on Area Monitors ............................ 11Table 5-4: Particulate Effluent Releases ............................................................................ 12Table 5-5: Gaseous Effluent Releases ............................................................................... 13Table 5-6: Liquid Effluent Releases ................................................................................... 15Table 6-2: Site Boundary Dose Rates ................................................................................. 17

List of Figures

Figure 2: Annual Reactor Utilization in MW-hrs of Operation ........................................ 6

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1. Introduction

The Texas A&M University (TAMU) Nuclear Science Center (NSC) is a multi-disciplinaryresearch and education center supporting basic and applied research in nuclear related fields ofscience and technology as well as providing educational opportunities for students in these fieldsas a service to the Texas A&M University System and the state of Texas. The NSC also providesservices 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 ofthe NSC reactor pool provides great flexibility in the experiments that may be conducted near thereactor. The NSC reactor facility includes two neutron beam ports, a neutron/gamma irradiationcell, a film neutron radiography system, hot cells with manipulator arms, and other supportingfacilities. Also, NSC has Cs-137 calibrator for use in instrument calibration.

Laboratory facilities include counting laboratories with gas flow proportional detectors and HighPurity Germanium detectors, a two-station pneumatics sample transfer system, a fast neutronirradiation system, a delayed neutron detection system and a prompt gamma neutron activationanalysis system.

The NSC reactor design allows for easy loading/unloading of various types of samples. The NSCroutinely produces a variety of radioisotopes for industry, hospitals, and academic users. TheNSC provides nationally recognized neutron activation analysis (NAA) services to manyresearch and academic institutions in the United States. The Nuclear Engineering Department oncampus is a major user of the NSC reactor. The NSC is also one of the major attractions oncampus. Last year, the NSC hosted approximately 1900 visitors including: elementary, middleschool, high school and college students as well as faculty members, national laboratoryscientists and industrial clients. Through these tours, the NSC taught people with widely varyingbackgrounds about nuclear science.

With strong support from the University, the NSC is continuously increasing the diversity of itsfacilities and services. The NSC is continuing to produce distance learning modules. The NSChas completed the security upgrades and enhancements that were initiated as part of DOE GlobalThreat Reduction Initiative (GTRI). NSC continues to provide technical support for the Y-12training initiatives.

With the DOE reactor upgrade funding from 2010, the NSC is replacing the cooling tower andsystems as well as installing a whole body contamination monitor that will follow nuclearindustry standards.

NSC has submitted the license amendment request as well as the revised Tech Specs, SAR, andother supporting documents for the renewal process with Nuclear Regulatory Commission(NRC). They are under review and are still pending with the NRC.

This annual report has been prepared to satisfy the reporting requirements of TechnicalSpecification 6.6.1 of the facility operating license R-83 and of the Department of Energy

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V University Reactor Fuel Assistance Program subcontract No. C87-101594 (DE-AC07-76ER02426).

1.1 Nuclear Science Center Staff

The staff at the Nuclear Science Center consists of four major groups: Reactor Operations,.Health Physics/Technical Coordination, Reactor Maintenance, and Administrative Services.Personnel directly involved with the operation and maintenance of the reactor are NRC-licensedoperators. The NSC is committed to its educational mission and many members of the staff arepart or full-time students at Texas A&M University. Appendix A shows the Nuclear ScienceCenter Organization Chart.

The Texas Engineering Experiment Station (TEES) of the Texas A&M University Systemoperates the NSC. The Director of the NSC is responsible to the Director of the TEES for theadministration and the proper and safe operation of the facility. The NSC Radiation SafetyOffice is responsible for matters relating to safety and for maintaining a proper radiation safetyprogram. In addition to the internal structure, the Reactor Safety Board (RSB) advises theDeputy Director of the TEES and the Director of the NSC on issues or policy pertaining toreactor safety. The Texas A&M University Environmental Health and Safety Department(EHSD) provide assistance when it is required for emergencies and for special operations asagreed. The Texas A&M University Police Department provides security support on a daily basisand is a key support group in the event of a security incident. The College Station FireDepartment and the College Station Medical Center provides offsite emergency support when itis required as per agreement.

2. Reactor Utilization for 2011

The Nuclear Science Center (NSC) reactor has been in operation since 1961. The reactor is a1 MW MTR-converted TRIGA reactor. Until the refueling in September 2006, the reactor usedhighly enriched uranium fuel (70%), but now uses low enriched uranium fuel (20%). Core IX isthe current core configuration and has been in use since September 2006. The NSC reactor ispulse operational and was pulsed up to $1.71 for nuclear engineering laboratories, staff training,and public tours.

The NSC reactor operated for 2121.4 hours in 2011 with a total integrated power of 86.6 MW-days. There were 535 "Requests for Irradiation" processed at the NSC during the reportingperiod. 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 sinceinitial criticality of the LEU fuel is 404.9 MW-days. Table 2 shows the reactor utilizationsummary in 2011 and Figure 2 shows the annual reactor utilization in MW-hrs of operation.

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Table 2: Reactor Utilization Summary in 2011

Days of Reactor Operation

Integrated Power (MW-days)

243

86.6

Number of Hours at Steady-State 2121.4

Number of Pulses

Number of Reactor Irradiations (RFS)

38

535

1844

18

Number of Visitors

Unscheduled Shutdowns

MW-hours of Operations2200

2100

2000

1900

1800

1700

1600

15002007 2008 2009 2010 2011

Figure 2. Annual Reactor Utilization in MW-hrs of Operation

6


V 2.1 TAMU Academic Support Program

Texas A&M University provides funding for the reactor for such academic activities as nuclearengineering laboratories, neutron activation analysis demonstrations and laboratories, graduatestudent thesis and dissertation research, and undergraduate research projects. The program hasbeen very successful and is crucial for many graduate students who use the NSC reactor forresearch and have not received research grants. The wide range of academic users from theuniversity 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 ofcommercial activities focus on production of radioactive tracers for the Texas petroleum andchemical 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 ofsamples for outside customers. The NSC has many years of experience producing radioisotopesand has developed several customer-specific methods for radioactive sample production and,handling. The production of radioisotopes generally involves handling radioactive material withhigh activities. The NSC staff takes precautions to minimize the exposures during the transfer ofradioactive materials to shipping shields.

3. Facility and Procedure Changes

3.1 Facility Modifications

During 2011, we renovated the Material Handling Area (MHA). The painted floor was strippedand re-sealed. Wooden work benches and storage spaces were replaced with stainless steel. Thegoals of these renovations is to reduce the possibility of fixed contamination and generally toincrease the ease of decontamination. We installed a jib crane on the loading dock to increasesafety while handling heavy shipping containers.

3.2 Experiment Authorization and Modification Authorization

There were no new Experiment Authorizations (EA) or Modification Authorizations (MA)covered in 2011.

4. Reactor Maintenance and Surveillance

4.1 Scheduled Maintenance

NSC personnel performed regular maintenance on the Fuel Element Temperature* Channel, Area Radiation Monitors and the Linear, Log, and Safety Power Channels as required

by the Technical Specifications. They also performed all surveillance required by the reactor

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license. Control rod worth and scram time measurements performed in July 2011 gave thefollowing results. The total rod worth was $14.62. The most reactive control rod was ShimSafety #4 with a worth of $4.028. The shutdown margin was $3.154 and core excess was$5.545. Scram times on all rods were less than 1.2 seconds. In addition, operators performedcalorimetric calibration following each maintenance period, and fuel inspections with noabnormalities noted (as required by the Technical Specification). The cold critical reactivityworth, performed for each reactor experiment, shows that the most reactive fixed experiment isthe Fast Flux Irradiation Device (-$ 1.141).

4.2 Unscheduled Shutdowns

There were eighteen unscheduled reactor shutdowns during 2011. The cause is detailed below inTable 4-2.

Table 4-2: Unscheduled Shutdowns

1/24/2011 Reactor scrammed due to a dropped rod. An operator bumpeda rod drive while placing an experiment and caused the rod todrop.

2/25/2011 Reactor scrammed due to a dropped rod. The transient rod airsupply was mistakenly isolated during maintenance, whichcaused the pressure to drop below an acceptable level.

5/25/2011 Reactor scrammed due to a loss of electricity from offsite.



7/7/2011 Reactor manually scrammed after an unplanned isolation ofcity water due to a water hammer event.

7/12/2011 Reactor scrammed due to a malfunction in Safety AmplifierChannel #2. The malfunction caused the channel to eitherindicate 0% or 150% and was repaired.


8/12/2011 Reactor scrammed due to a malfunction in the magnet of ShimSafety Control Rod #3. The drive was replaced with the sparedrive.

8


8/13/2011

8/18/2011

9/6/2011

9/20/2011

9/26/2011

10/6/2011

10/24/2011

11/15/2011

12/7/2011

Reactor manually scrammed after valves were found to bemispositioned during an ion exchanger regeneration. Reactorpool chemistry was measured and found to be withinspecification.

Reactor scrammed due to a malfunction in the magnet of ShimSafety Control Rod #3. Rod operability checks of the drivecould not reproduce the malfunction.

Reactor scrammed due to a malfunction in the magnet of ShimSafety Control Rod #4. The drive was replaced with the sparedrive.

Reactor scrammed due to the dry cell door interlock. Thereactor bridge was moved away from the dry cell prior tostartup, but the interlock was not reconnected. When the drycell door was opened, the reactor scrammed.

Reactor scrammed due to an electrical surge in the console.Maintenance being performed on the evacuation horn solenoidvalve caused an electrical surge which scrammed the reactor.

Reactor scrammed due to a malfunction in the magnet of ShimSafety Control Rod #4. Rod operability checks of the drivecould not reproduce the malfunction.

Reactor manually scrammed after fuel temperature wasobserved to be lower than expected at 1MW. Subsequenttesting revealed a failure of the Instrumented Fuel Element,which was replaced in service.

Reactor scrammed due to high indicated power on SafetyAmplifier Channel #1 during a planned power transient.Operator error resulted in a larger than planned transient. Nolicense limitations on reactor power or fuel temperature wereexceeded.

Reactor manually scrammed after indication of a malfunctionin the facility air compressor. The faulty part was replaced.

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4.3 Emergency Plan and Review

The Nuclear Science Center Management and the members of Reactor Safety Board (RSB)reviewed the NSC Security and Emergency Plans.

4.4 Reactor Safety Board

The Reactor Safety Board is responsible for providing an independent review and audit of thesafety aspects of the NSC reactor. The Reactor Safety Board met once in 2011. The meeting wason May 26, 2011 as per the Technical Specifications requirement.

4.5 Inspections and Audits

The Reactor Safety Board performed the required audits and inspections as per the TechnicalSpecifications requirement. The results of the audit were shared with the RSB members. Afacility inspection was performed by Nuclear Regulatory Commission in November 2011.

5. Health Physics Surveillance

The purpose of Health Physics surveillance is to ensure safe use of radioactive materials in theNuclear Science Center's research and service activities and to fulfill the regulatory requirementsof U.S. Nuclear Regulatory Commission and State agencies. The NSC maintains a HealthPhysics group as an integral part of the organization. They are responsible for radiological aswell as chemical and physical safety concerns. The radiation safety team at the TAMUEnvironmental Health and Safety Department provides additional support to the NSC HealthPhysics group upon request.

5.1 Radioactive Shipments

The Health Physics monitoring and technical support that was provided in 2011 assured minimalexposure during sample handling, shipment of radioactive material, and normal reactoroperation. The radiation exposures were maintained ALARA. During 2011, about 366radioactive samples were handled and released to various research facilities including TexasA&M University campus. A total of 411 curies were handled in 2011.

5.2 Personnel Monitoring

Personnel Monitoring was provided on a monthly basis to approximately 43 personnel. Allmeasured doses to personnel were below the limits set forth in 10 CFR 20. Nine individualsreceived whole body dose greater than 10% of the annual limit in 10 CFR 20. Their deep doseequivalent (DDE) recorded were .5, .505, .553, .601, .617, .654, .914, 1.092, and 1.454 R for theyear. Airborne monitoring during sample handling continued to show no significant airborne

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W activity, therefore, total effective dose equivalent will equal deep dose equivalent for 2011. Atotal of 8.31 manrem was recorded for the year 2011. When total manrem/curie was determinedfor 2011, the dose per curie equaled 0.0202 (manrem/Ci).

During 2011, about 1844 visitors toured the Nuclear Science Center. Minimal exposures weremeasured with pocket ion chambers worn by these visitors and the pocket ion chamber readingsof their respective tour guides.

NSC employees who were likely to exceed 10% of their total annual dose wore whole bodybadges (Luxel dosimeter) and extremity badges (TLD dosimeters) that were provided byLandauer, a NVLAP accredited supplier. Landauer also provides the reports of the dosesreceived. Employees who potentially handle more radioactive materials on a regular basis wereprovided 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 toNSC workers. Radiation levels and sources of radioactive contamination were routinelymonitored. Approximately 410 smear samples were collected and evaluated each month. Allaccessible areas at the NSC were surveyed for radiation and contamination levels monthly. Areaswhere contamination is expected have access/egress controls in place and are evaluated onshorter intervals. Building monitors and Area monitors are located strategically throughout the

* reactor facility, providing dose equivalent (mrem) on a monthly basis. Table 5-3 summarizes theannual accumulated dose equivalent (mrem) recorded on the area monitors for the year 2011.

Table 5-3: Total Dose Equivalent (mrem) Recorded on Area Monitors

Accumulated DoseMonitor ID Location Equivalen Dose

Equivalent (mrem)

BLDG MNTR 1 Upper Research Level bMezzanine

Lower Research Level aBLDG MNTR 2 Mzaie3184aMezzanine

BLDG MNTR 3 Lower Research Level 2039a

AREA Control Room 112

AREA Upper Research Level 1101

AREA Room next to MHA 4329baRadioactive shipments were stored in the LRL area pending transportbRadioactive materials were stored in the temporary locations in MHA.

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5.4 Particulate Effluent Monitoring

Radioactive particulates were monitored at the base of the central exhaust stack and summarizedon a monthly basis. The annual average release concentration was 3.04x101 2 pCi/cc. The totalradioactivity released for 2011 was 287 LCi. Table 5-4 summarizes monthly particulate effluentreleases during 2011. The most common isotopes noted during particulate effluent releases wereSc-46, Sb-124, and Ir-192.

Table 5-4: Particulate Effluent Releases

Concentration Dilution Additional Total activity releasedfrom channel 1 Concentration Exhaust releases

Quarter Month (RCi/cc) (gCi/cc) Volume (cc) (jICi) (Ci)

January 8.90E-13 4.45E-15 9.96E+12 8.86E-06

February <BG <BG 8.99E+12 <BGMarch 2.76E-12 1.38E-14 9.96E+12 2.75E-05

Average: 1.82E-12 9.12E-15 9.64E+12 1.21E-05Total: 2.89E+13 3.63E-05

April <BG <BG 9.64E+12 <BG

May <BG <BG 9.96E+12 _ _<BG

11 June 7.92E-14 3.96E-16 9.64E+12 7.64E-07


July 1.80E-11 9.01E-14 9.96E+12 1.80E-04

August 2.80E-12 1.40E-14 9.96E+12 2.79E-05

Il September 1.47E-12 7.33E-15 9.64E+12 1.41E-05

Average: 7.43E-12 3.72E-14 9.85E+12 7.38E-05

Total: 2.96E+13 2.22E-04

October 2.81E-12 1.41E-14 9.96E+12 2.80E-05

November <BG <BG 9.64E+12 <BG

IV December <BG <BG 9.96E+12 <BG


Annual Average: 3.04E-12 1.52E-14 9.77E+12 2.87E-05Summary Total: 1.17E+14 2.87E-04

notes:1. Concentration released from the stack: Concentration sampled from Ch 1 multiplied by volume of air going through the

stack

2. Diluted Concentration equal to: Average Release Concentration multiplied by 0.005 (Technical

Specification 3.5.2, dilution value for release concentration at exclusion boundary)

3. Exhaust Volume equal to: ( # days/month)*( 24hrs/dayM*(60min/hr)*( 7875 cfm)/ 3.53E-5cc)

4. Additional Release equal to: (individual releases calculated from facility air monitoring data)5. Total Release equal to: (Average Release Concentration)*(Exhaust Volume)*1 OA-6+(Additional Releases)

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5.5 Gaseous Effluent Monitoring

Argon-41 is the major gaseous effluent produced and released at the Nuclear Science Center.This effluent is monitored at the central exhaust stack. Total Argon-41 released during 2011 wasapproximately 2.82 Ci with an annual average release concentration of 2.79x10 8 ý.Ci/cc. Table5-5 summarizes monthly gaseous effluent (Ar-41) releases during 2011.

Table 5-5: Gaseous Effluent (Ar-41) Releases

Oi

Concentration Dilution Additional Total activityfrom channel 3 Concentration Exhaust Volume releases released

Quarter Month (cc)(40Ci) (lCi) cc (1Ci) (Ci)

January 3.45E-08 1.73E-10 9.96E+12 3.44E-01

February 8.40E-09 4.20E-11 8.99E+12 7.56E-02

I March 6.10E-08 3.05E-10 9.96E+12 6.08E-01

Average: 3.47E-08 1.73E-10 9.64E+12 3.42E-01

Total: 2.89E+13 1.03E+00April 2.97E-08 1.49E-10 9.64E+12 2.86E-01

May 1.60E-08 8.OOE-11 9.96E+12 1.59E-01

June 1.18E-08 5.89E-11 9.64E+12 1.14E-01


July 5.43E-09 2.71E-11 9.96E+12 5.41E-02

August <BG <BG 9.96E+12 1.07E+05 1.07E-01

III September 3.57E-08 1.79E-10 9.64E+12 3.44E-01

Average: 2.06E-08 1.03E-10 9.85E+12 1.07E+05 1.68E-01Total: 2.96E+13 1.07E+05 5.05E-01

October 3.11E-08 1.56E-10 9.96E+12 3.10E-01

November 4.30E-08 2.15E-10 9.64E+12 4.14E-01

IV December <BG <BG 9.96E+12 <BG


Annual Average: 2.79E-08 1.39E-10 9.77E+12 1.07E+05 2.65E-01Summary 1.17E+14 1.07E+05 2.82E+00

notes:1. Concentration released from the stack: Concentration sampled from Ch 3 multiplied by volume of air going

through the stack2. 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)

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5.6 Liquid Effluent Monitoring

Radioactive Liquid effluents are maintained in collection tanks before release from the confinesof the Nuclear Science Center. Sample activity concentrations and isotope identifications weredetermined before each release. The concentration values for each isotope were compared withthe effluent concentrations in water (10 CFR 20) and were determined to be in compliance. InSeptember 2008, a new sewer system was tied into the Texas A&M waste treatment plant forrelease of liquid waste and NSC started releasing liquid waste through the sewer system effectiveSeptember 2008. Sample activity concentrations were then compared with Sewer lineconcentrations (10 CFR 20) and were determined to be in compliance. There were 28 releases in2011, totaling 4.39x 105 gallons including dilution. The total radioactivity released was 7.87 mCiwith an annual average concentration of 3.5 1x10-6 tCi/cc. The annual dose to the publiccalculated from liquid effluents is about 3.35 mrem. Summary of the release data are presentedin the following Table 5-6. Radioactivity concentrations for each isotope found were below theEffluent Concentration limits specified in 10 CFR 20, Appendix B. The radionuclides identifiedin the waste stream were Na-24, Sc-46, Cr-5 1, Mn-54, Ir-192, Co-58, Co-60, Zn-65, Sb-122, Sb-124, and Cs-137.

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0Table 5-6: Liquid Effluent Releases

Quarter

I

Number ofMonth Releases

January 0

VolumeReleased

(cc)

Total AverageRadioactivity Concentration

(Ci) (ACi/cc)

February 1 3.43E+07 3.34E-05 9.74E-07

March 0

Total 1 3.43E+07 3.34E-05 9.74E-07

April

May

June

41

2

2.3 1E+08

2.47E+07

3.75E+07

1.45E-03

1.20E-04

1.69E-04

6.28E-064.86E-064.5 1E-06

I1 Total 7 2.93E+08 1.74E-03 5.21E-06

July 3 2.20E+08 1.21E-03 5.52E-06

August 7 4.39E+08 2.42E-03 5.5 1E-06

September 3 1.90E+08 4.63E-04 2.44E-06

III Total 13 8.49E+08 4.10E-03 4.49E-06

October 3 2.15E+08 7.48E-04 3.49E-06

November 2 1.19E+08 3.81E-04 3.21E-06

December 2 1.52E+08 8.73E-04

IV Total 7 4.85E+08 2.OOE-03 3.35E-06

AnnualSummary Total 28 1.66E+09 7.87E-03 3.51E-06

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S 6. Environmental Monitoring

In conjunction with representatives from the Texas Department of State Health Services(TDSHS) Radiation Control, a quarterly environmental survey is conducted to insure compliancewith federal regulations. This program consists of TLD monitors located at various locations onthe NSC site and two background monitors; one located at 3.84 miles NW of facility and theother 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 exclusionarea boundaries. These measurements are made for periods of approximately 91 days usingTLDs. Monthly measurements of direct gamma exposure rate in pR/h are also made at each ofthe TLD locations. The dosimeters were provided and processed by Texas Department of StateHealth Services, Environmental Monitoring, Division of Regulatory Services, Austin, Texas.

S The total TLD dose is multiplied by the occupancy factor (1/16) to determine the deep dose. Todetermine the dose to the public outside the site area from air effluents, the EPA approved codeCOMPLY was used. The annual dose calculated using COMPLY was 0.1 mrem/yr. This isadded to the deep dose to determine the total dose to the general public and the maximum dosenoted was 1.6 mrem. Table 6-2 summarizes the site boundary dose rates.

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Table 6-2: Site Boundary Dose Rates 2011

Quarterly TLD Deep Internal TotalExposure rates Dose Dose Dose Dose

Site # Location (mrem/91 days) (mrem) (mrem) (mrem) (mrem)2 300ft W of reactor building 6.9 1.9 0.9 7.3 17.0 1.1 0.1 1.23 250ft WSW of reactor building 4.0 0.9 0.0 3.3 8.2 0.5 0.1 0.64 200ftNW of reactor building 8.9 2.8 4.7 7.3 23.7 1.5 0.1 1.65 225ftNE of reactor building 7.9 0.9 0.9 1.6 11.3 0.7 0.1 0.8

10 190ft SEof reactor building 3.0 0.0 0.0 0.0 3.0 0.2 0.1 0.311 300ftNE of reactor building 4.0 0.0 0.0 0.0 4.0 0.3 0.1 0.4

*14 3miNW of facility 0.0 0.0 0.0 0.0 0.0 0.0 0.1 0.118 375ft NE of reactor building 0.0 2.8 2.8 0.8 6.4 0.4 0.1 0.519 320ft NE of reactor building 9.9 0.0 0.0 0.0 9.9 0.6 0.1 0.720 E Wall of accelerator building 4.9 0.0 5.7 12.2 22.8 1.4 0.1 1.521 W Wall of accelerator building 0.0 0.0 3.8 2.4 6.2 0.4 0.1 0.522 S Wall of accelerator building 2.0 0.0 0.0 0.8 2.8 0.2 0.1 0.3*23 0.25mi SE of facility 0.0 0.0 0.0 0.0 0.0 0.0 0.1 0.1

24 N wall of accelerator bldg, NW 1.0 1.9 1.9 4.9 9.7 0.6 0.1 0.725 N wall of accelerator bldg, E 4.9 0 0 4.1 9.0 0.6 0.1 0.7

W Fence of hyperbaric lab, 1 Oft from26 SW comer x x 0 0.8 0.8 0.1 0.1 0.2

E fence of hyperbaric lab, 1 Oft S of27 entrance x x 0 0 0.0 0.0 0.1 0.1

S fence of hyperbaric lab, 1 Oft E of28 personnel gate x x 0 0.8 0.8 0.1 0.1 0.2

325ft SW from reactor building, SW29 comer x x 1.9 2.4 4.3 0.3 0.1 0.4

* 14 and 23 are background TLD's

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7. Radioactive Waste Shipments

In 2011, there was one radioactive waste shipment. Stored material was counted and packagedinto appropriate shipping boxes and remanded into the care of the contracted waste hauler,Bionomics on 11/09/2011. The material was hauled to EnergySolutions (formerly Duratek), andprocessing was completed on 02/09/2012.

There were a total of 1306.8 kg of waste shipped, with a total volume of 14.474 mi3 . The totalactivity of the shipped waste was measured at 8984.36 uCi (332.4MBq).

18


APPENDIX A

<-KK-m

0m ~m,

19


. APPENDIX BReactor Safety Board Membership (2010)

Chairman/Licensee:Dr. Emile Schweikert, ProfessorChemistry Department

Members:Dr. John Ford, Associate ProfessorNuclear Engineering Department'

Dr. Marvin Adams, Associate ProfessorNuclear Engineering Department

Dr. Bill Charlton, Associate ProfessorNuclear Engineering Department

Dr. William Dennis James, Research ChemistChemistry Department

Dr. John Hardy, ProfessorPhysics Department

Dr. Teruki Kamon, Professor* Physics Department

Dr. Sean McDeavitt, Assistant ProfessorNuclear Engineering Department

Dr. Karen Vierow, Associate ProfessorNuclear Engineering Department

Ex-Officio Members:Dr. Warren Reece, DirectorNuclear Science Center

Mr. Jim Remlinger, Associate DirectorNuclear Science Center

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