ML20069H427

Thirtieth Annual Progress Rept of Nuclear Science Ctr Tx Engineering Experiment Station Tx A&M Univ Sys College Station,Tx

ML20069H427
Person / Time
Site:	05000128
Issue date:	12/31/1993
From:	Reece W TEXAS A&M UNIV., COLLEGE STATION, TX
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
94-0159, 94-159, NUDOCS 9406130153
Download: ML20069H427 (29)

Text

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TEX A S E N GIN E ElllN G EXPE RIM E NT STATIO N TEXAS A&M UNIVERSITY COU EGE STATION, TEXAS 778G3575

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W A t NUCLEAR SCIENCE CENTER 409 345-7551 06 June 1994 U.S. Nuclear Regulatory Commission 94-0159 ATTN: Document Control Desk Washington, DC 20555

Reference:

Facility Operating License No. R-83, Docket No. 50-128 Technical Specification 6.6.1

'i aave enclosed a copy of our " Thirtieth Annual Progress Report" for your information and review. I am also informing you that the licensee for the NRC license R-83 is now:

Dr. Raymond W Flumerfelt, Deputy Director Texas Engineering Experiment Station Texas A&M University System College Station, Texas 77843 If you have any questions, please let me know.

Sincerely, l

,AN ~ h , n_ I Warren D. Reece, Director Nuclear Science Center  !

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Enclosure <

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RESEARCH AND DEVELOPMENT FOR MANKIND 9406130153 931231 i PDR ADOCK 05000128 ,

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% o THIRTIETH ANNUAL PROGRESS REPORT of the Nuclear Science Center Texas Engineering Experiment Station

,- Texas A&M University System College Station, Texas e

} January 1, 1s53 Through December 31, 1993 1

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s-if . D. Reece, Director i

May 1, 1994 )

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I. Introduction The Nuclear Science Center (NSC) is operated by the Texas Engineering Experiment Station (TEES) as a service to the Texas A&M University System (TAMU) and the State of Texas. The Nuclear Science Center reactor and laboratories are available to students, researchers, faculty and staff from Texas A&M University, other colleges and universities, government agencies, and private industry.

The Nuclear Science Center is comprised of a 1 mega-watt TRIGA reactor operating under license by the U.S. Nuclear Regulatory Commission (NRC); license R-83 currently extends through March, 2003. The nuclear fuel for the reactor is provided by the U.S. Department of Energy (DOE) under contract

1. DE-AC05-76ERO4207 (formerly EY-76-C-05-4207).

II. REACTOR USE The NSC reactor operated for 1944 hours0.0225 days <br />0.54 hours <br />0.00321 weeks <br />7.39692e-4 months <br /> in 1993 for a total integrated power of 81.0 MW-days. During this period, 610 requests for reactor services were fulfilled. These requests are classified as either Academic Use, Internal Research, External Research, or Commercial activities. Academic Use provides services for primary, secondary and higher education programs in the form of educational laboratories or research in pursuit of advance degrees. Internal Research provides services to TAMU .

system basic research. External Research provides access to the reactor facilities by other colleges or universities, government agencies and non profit institutions for basic research.

Commercial work is also performed for private firms in support of research and production.

The Department of Energy provides funding to the NSC under the Reactor Sharing Program to provide no cost or low cost access to researchers and teachers from outside the Texas A&M System.

The state of Texas provides direct funding to provide access to all Texas academic and governmental agencies at reduced costs.

Commercial firms are charged at full recovery rates for research and isotope production in accordance with published service fee schedules.

The reactor was used by students, faculty and staff from 5 departments at Texas A&M University. Access was also provided to the faculty and students from 12 other educational institutions during this year. Escorted tours were provided to 3,310 visitors i

during 1993. A summary listing of the NSC users is provided in j the attached Tables 1-3:

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Nuclear Science Center Table 1 Commercial Account Listing Company / Institution User Name AAE/DCS Traders Mr. Helmut Zimmermann American Biomed Mr. Paul Skidham Arco Exploration & Production Technology Mr. Steven Bergman Cardinal Survey Company Mr. George Newman Columbia Gem House, Inc. Mr. Eric Braunwart Donelick Analytical Mr. Raymond Donelick FRAC-MATE LTD. Mr. Cam Carlson Hughes Aircraft Company Dr. Ron Hart IsoTag Mr. Fred Calaway Isotech Laboratories Mr. Lynn Williams Lockheed Engineering Mr. David Stanley Lousiana State University Dr. Ron Knaus M.D. Anderson, University of Texas Cancer Mr. Tim Ochran j Methodist Hospital Dr. William Cole Poretics Corporation Mr. Greg Stasny

, Protechnics/Spectratek Mr. Mike Brewer 1 j Schlumberger Well Services Mr. J.F. Poupeau

.I j Scientech, Inc. Mr. Veryl'Frahm i

Scimed Life Systems, Inc. Mr. Albert Your i,

Shell Development Company Mr. Jay Postlewaite Southwest Texas State University Mr. Dwight Sitta l i

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Nuclear Science Center -

Table 1 Commercial Account Listing Company / Institution User Name Stanford University, Dept of Geology Mr. Trevor A. Dumitru TAMU, Research Foundation, Chemistry Dr. Kenny Kennicutt Texas Instuments Corporation Ms. Cheryl Blackburn TPL, INC. Mr. Timothy C. Tierma Tracer Services Ltd. Mr. Norman Seely Tracerco Mr. Dave Bucior Tru-Tec Division Mr. Chuch Winfield TruTag Systems Mr. Wade Hutchinson U.S. Dept. of Interior, Geological Survey Mr. Roy Knight University of California, LANL Mr. Archie velarde

Western Atlas, Inc. Mr. Billie Dean Rose Woodson-Tenent Labs, Inc. Mr. Edward McCarthy ,

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Texas Academic Accounts Company / Institution User Name Department of Anthropology Dr. Harry J. Shafer N.E./405/REECE Dr. W. D. Reece N.E./606/REECE Dr. W. D. Reece N.E./691/ PARISH Dr. Parish TAMU, College of Geo Sciences, Oceanography Dept Dr. Paul Boothe TAMU, College of Sci, Dept of Animal Science Dr. Ellis TAMUS, College of Eng, Dept of Nuclear Engineering Dr. W. D. Reece TAMUS, College of Science, Dept of Chemistry Dr. Marvin Rowe TAMUS, College of Eng, Dept of Nuclear Engineering Dr. John Poston TAMUS, College of Eng, Dept of Nuclear Engineering Dr. Ted Parish TAMUS, College of Eng, Dept of Nuclear Engineering Dr. Yassin Hassan TAMUS, College of Eng, Dept of Nuclear Engineering Dr. Wesley Bolch ~

Department of Anthropology (Archeology) Dr. David L. Carlson Department of Geology & Geophycies Dr. Thomas T. Tieh '

Horticultural Sciences Department Dr. Edward L. McWilliams Ocean Drilling Program (Coll of Geosciences) Dr. James F. Allen Soil & Crop Sciences / Dept. Of Agriculture Dr. Richard H. Loeppe TAMU, College of A&LS, Dept of Animal Science Dr. William Ellis TAMU, College of Geo Sciences, Dept of Geology Dr. John Spang TAMU, College of Geo Sciences, Dept of Physics Dr. Eugene Barasch i

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I" Nuclear Science Center Table 2 Texas Academic Accounts P.

[ Company / Institution User Name TAMU, College of Sci, CCCA Dr. Dennis James TAMU, College of Sci, Dept of Chemistry Dr. O. M. Bockris TAMU, College of Sci, Dept of Physics Dr. Eugene Barasch TAMU, College of Vet Med, Dept of Physio & Pharm Dr. Sheri Keele TAMUS, College of Eng, Dept of Nuclear Engineering Dr. Dan Reece

TAMUS, College of Eng, Dept of Nuclear Engineering Dr. John Wagner TAMUS, College of Eng, Dept of Nuclear Engineering Dr. Ted Parish I

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Nuclear Science Center Table 3 External Academic and Research Accounts Company / Institution User Name Lousiana State University Dr. Ron Knaus McLennan Community College Mr. Don Tatum Miami University Dr. Kevin Crowley New Mexico Technical College Dr. Phillip Kyle Reactor Tours-DOE Funded various Sam Houston State University Dr. Bill Covington Southern Methodist University Dr. Shari Kelley Stanford Univ., Dept of Geology, Research Dr. Trevor Dumitru Texas State Technical College Ms. Georgia Martini 4 U.S. Dept of Agriculture Dr. Al Hollister

'! Univ of Houston, Inst For Beam Particle Dynamics Dr. In-Gann Chen .

Univ of Texas At Austin, Dept of Geological Scie Dr. Mark Cloos Univ Of Texas At El Paso Dr. Elizabeth Anthony University of Houston Dr. Liu I

University of Southwest Lousiana

] Dr. John Meriwether

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III. FACILITY AND PROCEDURE CHANGES In accordance with the requirements of 10CFR50.59, changes to the facility and procedures were reviewed and documented.

During 1993 no changes were performed that required additional safety analysis or changes to the Technical Specifications. . The 6

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following changes were implemented as not representing an unreviewed safety question, and not increasing the probability of an accident previously analyzed in the Safety Analysis Report.

A. Facility Modification Date WR # Facility Modification 01/93 93-003 Fuel Vault Ventilation 01/93 93-166 Secondary Treatment System Fill Valve Control 04/93 93-029 Upgraded Area Radiation Monitors 11/93 93-030 New Linear Flux Monitor Drawer 11/93 93-127 Upgrade Materials Handling Area B. Procedure Chances No procedures contained in the SAR were changed.

IV. FACILITY MAINTENANCE All required maintenance as set forth in the Technical l Specifications was performed annually, semi-annually, or weekly i

! as required. Pre-startup checklists are performed daily prior to reactor operation to assure reactor facility readiness.

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5 V. TECHNICAL SPECIFICATION SURVEILLANCE '

l The Technical Specification requirements for maintenance and surveillance were completed for all required channels as follows:

A. Calibrations Fuel Element Temperature Measuring Channel Linear Power Channel l l

Log Power Channel '

High Power (Safety) Channels

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Area Radiation Monitoring Channels )

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B. Compliance Testina i

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Control rod worth, and time measurements were performed in l January, 1993. Total rod worth was measured at $6.39; providing i

2 a shutdown margin of $3.30. The rod scram time is within the +

) Technical Specification limit of 1.2 seconds. The maximum I

allowable pulse reactivity insertion is $2.09 for Core VIII-A as 1

determined by a pulse test program. An administrative limit of  !

$1.90 is imposed for pulse operations.

l The power level (linear) channel was calibrated by the  ;

calorimetric method on 01/08/93. The pulse measuring channel was j calibrated on 01/29/93. Pulse operation parameters are verified l

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t semi-annually by pulsing the reactor for comparison of pulse energy and fuel temperature to previous pulse operation values.

Nineteen fuel elements were inspected in January 1993. In addition, all control rods and fueled followers were visually inspected. All elements satisfied the inspection criteria.

The reactivity worth for each experiment was measured or estimated before initially performing an experiment. The most reactive ($0.98) fixed experiment are the East Face Stone Irradiator Boxes.

C. Readiness Review and Emeroency Plannino A review of the NSC security plan and emergency plan was conducted by the NSC staff on 03/16/93. The annual facility evacuation drill and staff emergency response was conducted on 09/23/93. A review of the NSC ALARA program was conducted by the Office of Radiological Safety on 06/20/93.

L VI. REACTOR OPERATIONS 1

lt A. Availability The NSC reactor operates 3 days a week from 0800 to 1700 and 2 days a week from 0800 to 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />. Performance statistics N

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for calendar year 1993 are as follows:

Number of Days Reactor Operated - 238 )

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Reactor Operation (MW-Days) - 81.0 )

Number of Hours at Steady State - 1971 J

Average Number of Operating Hours Per Week - 37.9 Total Number of Pulses - 38 l

L Number of Irradiations - 610 i <

I Beam Port Experiment-Hours - 32.7

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. Irradiation Cell Experiment-Hours - 0 l Number of Visitors - 3310 t

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B. Unscheduled Outages A total of 8 unscheduled shutdowns occurred during 1993.

The unscheduled shutdowns were caused by the following: 1 Loss of Facility Electrical Power -

5 occurrences Operator Error -

3 occurrences C. Reportable Occurrences There were no reportable occurrences.

bg VII. ADMINISTRATION The reporting structure and reactor organizational I

requirements are contained in the Technical Specifications. The complete Nuclear Science Center organization is identified in chart format on Figure 1.

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Nuc. ear Science Cen er -

Texas Engineering Experirnent Station Dan Reece Director 845-5007 t' Bruce

3. Carlisle Assistan t Director 845-5998 o

w h) Bill Larry Anthony Asher KrisonIls Joy Res ti vo R1bordo Man ager Coordin ator M an age r Factit ty Operations M an ager Hecith Physics Support Fact!!!y Services Support Services Anthony Berncdette Tc h si n Armont Potsy Boca Astor Harris Suzy David Th o m ca Te d B racte e n Hectne Fisher J oh nson Shane Donald Bob B rig h twe!! Lipscom b Yvo n n e Goulden M i tchet t Paul Ray-Gidden Michell Horn Pcte Ray mon d '

M odglin Kevin Pecrcy Sean Joe O'Kel I y Sn oc t Ken n y Roody F re d Sanchez e

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c VIII. HEALTH PHYSICS SURVEILLANCE A dedicated Health Physics group is maintained at the NSC reactor facility as an integral part of the line organization.

Additional support is provided on request by the TAMU Madiological Safety Office.

l A. Irradiation Support l l

Health Physics monitoring and technical support provided l

both quality assurance and hazards reduction during the i I

processing of over 665 irradiation requests and shipping 356 shipments of radioactive material. Of these, 93 shipments were sent to other locations on the Texas A&M campus.

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B. Personnel Monitorinc

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1 Personnel Monitoring was provided to 49 NSC employees and 58 experimental personnel using the facilities. All of the

radiation exposures'to personnel were below the limits set forth l l

in 10CFR20.101. Only two personnel recieved annual maximum l exposure over 10% of the federal limits: 610 and 550 mrem. A total of 4.99 man-rem was recorded for 1993.

During 1993, 3,310 persons visited the Nuclear Science l l

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Center. No detectable exposures were measured with film badges.

Dosimetry results were provided by an NVLAP accredited supplier, Landauer.

t C. Facility Monitorina F

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[ Surveys of the Nuclear Science Center facilities are performed to assess radiological hazards to NSC workers.

f Radiation levels and sources of radioactive contamination are l frequently monitored. Approximately 350 smear samples were 1

l collected and evaluated each month. Radioactive effluent a

j releases were monitored for isotopic content and activity; there

were 26 planned releases of radioactive liquid effluents totalling 6.70 x 105 liters.

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. I D. Particulate Effluent Monitorina Radioactive particulates are monitored at the base of the central exhaust stack and are summarized on a monthly basis. The

annual average release rate was 1.3135 x 10-" pCi/cc. Total activity of paticulate release for 1993 was 1.34 x 10-' Ci. a

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.The following table summarizes annual particulate effluent releases during 1993.

I RADIOACTIVE PARTICULATE EFFLUENT RELEASES Average Diluted Exhaust Total Release conc.*1 Conc *2 Volume *3 Release *4 M Month (uci/cc) (uci/cc) (cc) (Ci) 1 January 1.60E-11 7.9800E-14 1. 0117 E+ 13 1.614604E 4 February 3.37E-12 1.6850E-14 9.1377E+12 3.079405E-5 March <bkgd <bkgd 1.0117E+13 <bkgd Average: 9.665E-12 4.8325E 14 9.7904E+12 9.612805E-5 Total 2.9371E+13 1.922604E-4 II April (bkgd (bkgd 9.7904E+12 <bkgd May 1,48E-11 7.410E 14 1. 0117 E + 13 1.499304E-4

, June 1.41E-11 7.068E-14 9.7904E+12 1.384004E 4 i

j Average 1.448E-11 7.239E-14 9.8992E+12 1.441604E-4 5 Total 2.9697E+13 2.883304E 4 9

1 III July 5.15E 12 2.575E 14 1. 0117 E + 13 5.210105E 5 August 2.65E-11 1.325E-13 1. 0117 E + 13 2.680904E-4 September <bkgd <bkgd 9.7904E+12 <bkgd Average 1.055E-11 5.275E-14 1.0008E+13 1.067304kE-4 g

Total 3.0024E+13 3.201904E-4 I

[ IV Oc t.ober 4.80E 11 2.400E-13 1. 0117 E+ 13 4.856004E-4 15 i

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November 2.40E-13 1.200E-15 9.7904E+12 2.349706E-6 December 5.30E-12 2.650E 14 1.0117E+13 5.361905E-5 Averages 1. 7 8 4 7E -11 8.923E-14 1.0008E+13 1.805204E-4 Total 3.0024E+13 5.415704E-4 ANNUAL

SUMMARY

Averages 1.3135e-11 6.5675e-14 9.9263E+12 1.318874E-4 Total: 1.1912E+14 1.342353E-3 Notes (1) Average Release Concentration data from Form 805, Channel 1

" Activity Released" (2) Diluted Concentration equal to Average Release Concentration multiplied by 0.005(Technical Specification 3.5.2, dilution value for release concentration at exclusion boundary)

(3) Exhaust Volume equal to:(# days / month)*(24 hrs / day)*(60 min /hr)*

(8000cfm)/(3.53E-Scfm/cc) ,

(4) Total Release equal to: (Average Release Concentration) i

• (Exhaust volume)/(IE6uCi/Ci) 2 l Total Central Exhaust Air Volume: 1.19 x 10' cc 1 j Central Exhaust Annual Average Release Rate: 1. 31 x 10-12 pCi/cc. l l

Total Central Exhaust Annual Release: 1. 3 4 x 10-' C1. I 16 l

E. 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 release during 1993 was 17.84 Ci with an annual release rate of 1.611 x 10-' pCi/cc (no dilution factors applied). Release rates are also determined using the dilution factors for the release rate at the exclusion area boundary. The total amount released is determined from the undiluted release rate. These data are summarized below:

RADIOACTIVE GASEOUS EFFLUENT RELEASES t

Average Diluted Exhaust Total Release Conc.(1) Conc.(2) Volume (3) Release (4)

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I January 1.39E-07 7.00E-10 1.0117E+13 1.4062 February <bkgd <bkgd 9.1377E+12 <bkgd March 1.52E-07 7.60E-10 1.0117E+13 1.5418 Average: 1.457E-07 7.285E-10 9.7904E+12 1.4740 Total: 2.9371E+13 2.9480 II April 2.33E-07 1.17E-9 9.7904E+12 2.2841 May 1.83E-07 9.20E-10 1.0117E+13 1.8514

-f f June 4.95E-07 2.48E-9 9.7904E+12 4.8462 Average: 3.038E-07 1.519e-9 9.8992E+12 2.9939 Total: 2.9697E+13 8.9817 III July 2.03E-07 1.02E-09 1.01167E+13 2.0537 17 i

, , August 3.33E-07 1.67E-09 1.01167E+13 3.3689 September 1.84E-08 9.00E-11 9.79037E+12 0.1801 Average: 1.848E-07 9.24E-10 1.00080E+13 1.8676 Total: 3.00238E+13 5.6027 IV October 2.33E-08 1.2E-10 1.01167E+13 0.2357 November 3.04E-10 1.52E-12 9.79037E+12 0.0030 December 6.80E-09 3.0E-11 1.01167E+13 0.0688 Average: 1.0135E-08 5.0673E-11 1.00080E+13 0.1025 Total: 3.00238E+13 0.3075 ANNUAL

SUMMARY

Average: 1.6110E-07 8.0550E-10 9.92635E+12 1.6095 Total: 1.1912E+14 17.840 Notes: (1) Average Release Concentration data from Form 805, Channel 3 " Activity Released" (2) Diluted Concentration equal to Average Release Concentration multiplied by 0.005 (Technical

Specification 3.5.2, dilution value for release i

i concentration at exclusion boundary)

(3) Exhaust volume is equal to:

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(# days / month)*(24 hrs / day)*(60 min /hr)*(8000cfm)/

(3.53E-Scfm/cc)

(4) Total Release equal to: (Average Release Concentration)

• (Exhaust Volume)/(lE6uCi/Ci)

.i I Total Air Volume: 1.19 x 10" cc I

1 Central Exhaust Average Release Rate: 1.61 x 10 4 pCi/cc Total Ar-41 Activity Released: 17.84 Ci

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• F. Licuid Effluents Monitoring Radioactive Liquid effluents are collected in liquid holdup waste tanks prior to release from the confines of the Nuclear Science Center. Sample activity concentrations and isotope identification was determined prior to each release. There were 26 releases in 1993, totalling 6.70 x 105 liters, excluding dilutents from the Nuclear Science Center. The total radioactivity released for 1993 was 3.69 x 10 Ci with an average concentration of 5.89 x 10 pCi/cc. Summaries of the radioisotopic data are presented below. Radioactivity concentrations for each isotope were below the limits specified in 10CFR20, Appendix B Table II, Column 2.

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RADIOACTIVE LIQUID EFFLUENT RELEASES Total of Monthly Isotopic Release Activity (C1) ,

Month Reloanon Na-24 Sc 46 Cr-51 Mn 54 co 57 l January 1 5.11E-5 8.7 8E- 5 j February 2 4.58E-6 5.23E-6 March 1 5.39E-5 1.632-4 l l

April 2 1. 97 E - 5 6.81E-5 I

~May 2 2.52E-5 2.268 4 1.11E-4 l-L June 1 3.55E-5 4.48E-5 July 2 1.22E-5 1.47E-5 )

August 5 6.85E-5 2.88E-4 1.93E-4

September 2 2.3BE 1.35E-4

1. October 3 1.45E-7 3.59E 5 1. 38E 4 l

November 2 6.50E 6 2.78E-6 J Decembot 3 3.8BE-5 3. 57 E 4 1.7 0E- 4 ,

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Totals: 26 1.45E-7 3.76E-4 8.71E-4 1.13E-3 2.78E-6 Monthly Iostopic Release Activity (Ci)

Honth co-58 Co-60 Zn -65 Sb-124 Ir-192 January 9.9E-6 3.50E-5 8. 2 8E- 6 4.09E-5 1.77E-4 February 1.14E-6 1.05E-6 March 2.47E-5 9.96E-6 9.60E-6 April 7.66E-6 1.46E-5 1.28E-4 May 1.65E-5 2.19E-5 8.13E-6 7.74E-5 June 4.02E-6 8.22E-6 9.62E-5 July 1.73E-6 4.16E-6 2.78E-6 5.87E-5 August 2.48E-5 5.05E-5 8.60E-6 1.10E-4 September 1.48E-5 3.90E-5 6.43E-6 2.65E-5 Ocober 1.57E-5 3.90E-5 1.29E-5 8.33E-6 4.12E-5 November 5.29E-7 1.60E-5 December 1.90E-5 4.95E-5 2.00E-5 7.95E-7 3.95E-5 Totals: 1.39E-4 2.64E-4 7.71E-5 5.00E-5 7.81E-4 Month Average Released fec) Activity (Ci) Conc.

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January 2.48E+7 4.10E-4 1.65E-5 February 3.26E+7 1.20E-5 3.68E-7 March 5.22E+7 2.61E-4 5.00E-6

, April 3.73E+7 2.38E-4 6.38E-6 May 5.19E+7 4.86E-4 9.37E-6 June 5.00E+7 1.89E-4 3.77E-6 j July 3.68E+7 9.43E-5 2.56E-6 .

August 1.48E+8 7.43E-4 5.02E-6 September 3.73E+7 2.46E-4 6.58E-6 October 7.11E+7 2.91E-4 4.10E-6 November 6.26E+7 2.58E-5 4.12E-7 ,

December 6.58E+7 6.95E-4 1.06E-5

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. . Armuel Totalst 6.70Eo8 3.96E-3 ArmuG1 Avg 5.89E-6 The annual summary for liquid waste effluent is as follows:

Total Liquid Volume: 6.70 x 10' liters (1.77 x 10' gallons)

Average Release Rate: 5.89 x 10 pCi/cc Total Activi' v: 3. 6 9 x 10 Ci IX. ENVIRONMENTAL MONITORING l

In conjunction with representatives of the State of Texas Department of Health, a quarterly environmental survey program was implemented. This program consists of TLD monitors located .

q around the NSC site and the collection, analysis, and evaluation of soil, water, vegetation and milk samples.

A. Environmental Survey Samoles Il The environmental survey samples were collected in accordance fi with the schedules of the cooperative surveillance program 4 between the Texas State Department of Health and the Texas A&M University. These samples were analyzed using an intrinsic f germanium detection system for isotopic identification. Data e

from these samples reflect the continued use of retention 9

facilities and sample analysis for laboratory effluents prior to a 21 L

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f Summaries of the environmental survey program for 1993 are presented in the four tables below for isotopic activity as reported to the NSC or as determined by the NSC when data from the state was unavailable.

Vegetation Samples 1993 Quarter Sample Location Concentration (pCi/ml) 1st TAMU dairy < MDA 2nd TAMU dairy < MDA 4

3rd TAMU dairy < MDA

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1993 Quarter Sample Location Concentration (pCi/ml) f 1st Brazos River < MDA ist NSC Creek < MDA 2nd Brazos River < MDA 0

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3rd Brazos River < MDA 3rd NSC Creek < MDA l 4th Brazos River Not Analyzed ,

4th NSC Creek < MDA Milk Samples 1992 Quarter Sample Location Concentration (pCi/ml) ist TAMU Dairy < MDA ,

2nd TAMU Dairy < MDA 3rd TAMU Dairy Not Analyzed 4th TAMU Dairy < MDA i

l Soil Samples  ;

1992 Quarter Sample Location Concentration (pC1/ml)

$' Ist NSC Soil 1.35 x 10'5 (II-192) 2nd NSC Soil 9.83 x 10 (Pb-212' ,

Pb-214) 3rd NSC Soil < MDA ,

4th NSC Soil 1.79 x 10~ (Co - 6'O ,

2n-65, II-192)

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= - - B. 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 90 days, using TLDs. The dosimeters are provided and processed by Texas Department of Health, Bureau of Radiation Control, Division of Environmental Programs. The state background monitor (survey point 14A) is located at a point 5.25 miles west-southwest of the facility and generally at right angles to the prevailing southeasterly winds.

Site # Location Ortly Annual Exposure Rate Exposure (mR/91 day) 1993 (mR) 2 300 ft. W of reactor 17.7 48.6 j building, near fence corner

$ 3 250 ft W-SW of reactor 106.8 671.0

! building, on SW chain link I

j fence 4 200 ft NW of reactor 26.1 71.6

building, on chain link 3

j_ fence, near butane tank.

I 5 225 ft NE of reactor 10.8 28.8 building, on fence N of driveway 6 300 ft N-NE reactor 31.9 131.5 building, near fence corner 24

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10 190 ft SE of reactor 5.0 16.0 building, near fence corner 11 300 ft NE of reactor 1.6 2.1 building, near fence corner 12 375 f t NE of reactor 15.5 63.8 building, near waste storage shed 13 320 ft NE of reactor 13.2 45.4 building, near waste storage shed 14A 5.25 miles W-SW of reactor 0.0 0.0 ,

building, at FM 60 bridge over Brazos River The highest exposure point was determined to be at site #3 (671.0 mR/yr) which is on the WSW corner of the reactor building.

This radioactive material storage location was moved in December

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of 1993. The boundary readings for 1994 should be considerably less. The closest off-site point of extended occupancy is located just beyond the site boundary fence directly behind the site #10 monitoring location; those occupants continue to receive l

only background exposure.  !

I Site #6 (131.5 mR/yr) located NNE of the Reactor Building is the second highest location. This dose may be attributed to  :

j normal operation of the facility calibration range. Current l '

f plans are to restrict access to this area of the site boundary in 1994. This will prevent public access and allow the dosimeter to be relocated further from the calibration range.

l i

l 25 j

I f

I'

h t r- .

• ' *

• X. RADIOACTIVE WASTE l

Ir

. A. Solid Waste W

f t

During the 1993 year, there was no solid waste released from the NSC for disposal offsite.

XI. Reactor Safety Board '

I r A. Membershio 1

]

Chairman:

Feenan Jennings, Director, University Research L>

Services i

!1 Members: .

1:

Dr. Ted Parish, Professor, Nuclear Engineering ti h Department 4

I Dr. Robert Kenefick, Professor, Physics Department I

l

) Dr. Roger Koppa, Associate Professor, Industrial Engineering Department

. l Dr. Earl Morris, Professor, Veterinary Medicine-Large Animal Clinic I

26 d _ _

v -.

{

• * *

• Dr. Emile Schweikert, Professor, Chemistry Department 1 . l

't

! Ex-Officio Members:

Dr. Warren Reece, Director, Nuclear Science Center e, ,

i

}

l Ms. Martha Brown, Assistant Director, Nuclear ,

1 ,

g Science Center i '

d 1

Mr. Bruce Carlisle, Assistant Director, Nuclear 3 Science Center t i

~

l Dr. Milton McLain, Director, Radiological Safety i

i j office i

il ,

1 L

Dr. John Poston, Professor and Head, Nuclear e

i Engineering Department

}.

1 i

? ,

y TEES:

y Dr. Kenneth Hall, Deputy Director ,

Dr. Kenneth Peddicord, Director 1

~.

27 '

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