ML19296B352

Annual Operating Rept 1979

ML19296B352
Person / Time
Site:	U.S. Geological Survey
Issue date:	12/31/1979
From:	INTERIOR, DEPT. OF, GEOLOGICAL SURVEY
To:
References
NUDOCS 8002200442
Download: ML19296B352 (8)

Text

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U;. S. Geological Survey TRIGA Peactor ANNUAL REPORT January 1, 1979 - December 31, 1979 I. Administrative Changes John Morgan replaced Leland Thatcher on the Reactor Operations Committee.

II. Operating Experience The prime function of the Geological Survey TRIGA Reactor (GSTR) for the year 1979 has been to provide neutrons for the various research programs being conducted by the Geologic Division and the Water Resources Division of the U.S. Geological Survay. As time was available, irradiations were also performed for other Governmental agencies and education institutes.

A l'ating of all irradiations perfonned during the year 1979 is tabulated below:

Organization Samples (1979)

Geologic Division (Denver) 27,332 Water Resources Division 24 Georgia Institute of Technology 22 Colorado State University 14 California Institute of Technology 3 Geologic Division (Menlo Park) 2 University of Minnesota 1 University of Colorado 1 27,175 The operation of the reactor has been normal. The specifics of operating relating to perfonnance characteristics, changes in the facility design or operating procedures are:

A. Thermal power calibration at 50 KW was performed in January and June 1979.

B. Control rods were calibrated and inspected in January 1979.

L. Two (2) fuel elements were added to the core from storage in January 1979.

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D. One Class 11 experiment was approved. Experiment P-12 was approved August 28, 1979 by the Reacto.- Operations Committee. It covers the expansion of P-ll, the delayed neutron systen, to four (4) termini and four (4) counters operating simultaneously or singly.

E. During the report period 214 daily checklists and 12 monthly checklists were completed in compliance with Technical Specification requirements for surveillance o+ the reactor facility.

F. Tours of the reactor facility were provided to 20 groups during the year. The major groups visiting the facility were affiliated with:

Colorado Geological Survey

. Colorado State Science Fair University of Wyoming U.S. Navy Colorado State University Colorado School of Mines American Nuclear Society Bureau of Mines Bennett High School University of Denver During the year, 336 visitors were admitted to the reactor facility.

III. Tabulation of Energy Generated Megawatt Time Reactor Pulsing Month Hours Was Critical Number - K/B January 1979 67.381 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> 01 minutes 0 February 1979 92.478 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> 46 minutes 0 March 1979 89.380 106 hours0.00123 days <br />0.0294 hours <br />1.752645e-4 weeks <br />4.0333e-5 months <br /> 42 minutes 0 April 1979 100.118 107 hours0.00124 days <br />0.0297 hours <br />1.76918e-4 weeks <br />4.07135e-5 months <br /> 19 minutes 0 May 1979 65.114 71 hours8.217593e-4 days <br />0.0197 hours <br />1.173942e-4 weeks <br />2.70155e-5 months <br /> 31 minutes 0 June 1979 46.857 55 hours6.365741e-4 days <br />0.0153 hours <br />9.093915e-5 weeks <br />2.09275e-5 months <br /> 11 minutes 0 July 1979 68.256 77 hours8.912037e-4 days <br />0.0214 hours <br />1.273148e-4 weeks <br />2.92985e-5 months <br /> 43 minutes 0 August 1979 62.787 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 46 minutes 0 September 197f 48.869 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> 38 minutes 0 October 1979 73.388 85 hours9.837963e-4 days <br />0.0236 hours <br />1.405423e-4 weeks <br />3.23425e-5 months <br /> 03 minutes 0 November 1979 73.092 77 hours8.912037e-4 days <br />0.0214 hours <br />1.273148e-4 weeks <br />2.92985e-5 months <br /> 35 minutes 0 Decenber 1979 68.794 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> 15 minutes 0 Total 856.514 987 hours0.0114 days <br />0.274 hours <br />0.00163 weeks <br />3.755535e-4 months <br /> 30 minutes 0

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IV. Unscheduled Shutdowns Emergency Shutdowns - number and reason

1. Manual Scram - Sample failed to return signal. Spring broken on blower direction solenoid. (Serial #209)

2. - Dip in electrical power. (Serial #218)

3. Manual Scram - Sample failed to leave reactor signal.

Sample slow returning. (Serial #219) 4 Manual Scram - Sample failed to leave reactor signal.

Sample slow returning. (Serial #220)

5. Manual Scram - Sample failed to leave reactor signal.

Sample slow returning. (Serial #221)

6. Manual Scram - Sample failed to leave reactor signal .

Sample returned OK. (Serial #225)

7. Manual Scram - Sample failed to leave reactor signal.

Sample returned OK. (Serial #226)

8. Manual Scram - Sample failed to leave reactor signal.

Sample returned OK. (Serial #229)

9. Manual Scram - Loss of percent power signal. Wet cable connector. (Serial #231)

10. Manual Scram - Sample failed to leave reactor signal.

Sample returned OK. (Serial #232)

11. - Shim rod ON light burned out. (Serial #233).

12. Manual Scram - Sample failed to leave redctor signal.

Sanole returned OK. (Serial #234)

13. - Loss of power. (Serial #235)

Unscheduled Shutdowns - number and reason

1. Manual Scram - Sample stuck in transit in signal. (Serial #207)

2. Manual Scram - Sample to eject. (Serial #208)

3. Manual Scram - Sample late in returning. Jammed changer, (Serial #210)

4. Manual Scram - Sample late returning. (Serial #211)

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5. Manual Scram - Trouble with sample changer. (Serial #212)

6. Manual Scram - Computer problem. (Serial #213)

7. Manual Scram - Trouble with sample changer. (Serial #214)

8. Manual Scram - Sample changer jammed. (Serial #215)

9. Manual Scram - Sample changer jammed. (Serial #216)

10. Manual Scram - Sample changer jammed. (Serial #217)

11. Manual Scram - Sample slow in returning. (Serial #222)

12. Manual Scram - Sample stuck in transit IN signal. (Serial #223)

13. Manual Scram - Sample stuck in transit IN signal. (Serial #224)

14. Manual Scram - Sample stuck in transit IN signal. (Serial #227)

15. Manual Scram - Improper sequence. (Serial #228)

16. Manual Scram - Sample stuck in transit IN signal. (Serial # 230)

17. Manual Scram - Sample stuck in transit OUT signal. (Serial # 236)

V. Major Maintenance Operations A. Water Systans

1. The demineralizer resin was changed twice during the year.

B. Control Rods

1. A visual inspection was made of the control rods and each one was calibrated.

2. A new Reg. rod drive motor and gear box was installed and checked out.

3. Reworked the transient rod drive mechanism. Replaced the bottom "0" ring seal on the shaft and installed new piston seal and split ring.

VI. Summary of 10 CFR 50.50 Chances No changes were made under 10 CFR 50.59.

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VII. Radioactivity Releases A. Listed below are the total amounts of radioactive gaseous effluents released to the environs beyond the effective control of the reactor facility.

License (R-ll3) 10 CFR 20 Argon-41 Allowable Tritium (HTO) Allowable Month (curies) (curies) (curies) (curies)

January 1979 0.49 5.8 13.8 x 10',,

0.25 February 1979 0.55 5.8 14.8 x 10_s 0.25 March 1979 0.60 5.8 24.4 x 10 s 0.25 April 1979 0.68 5.8 8.2x10[s 0.25 May 1979 0.36 5.8 18.1 x 10_ s 0.25 June 1979 0.31 5.8 10.1 x 10 s 0.25 July 1979 0.30 5.8 12.9 x 10[s 0.25 August 1979 0.56 5.8 10.7 x 10_s 0.25 September 1979 0.38 5.8 7.1 x 10 s 0.25 October 1979 0.69 5.8 7.2 x 10 s

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0.25 flovember 1979 0.43 5.8 9.9 x 10 s 0.25 December 1979 0.60 5.8 16.6 x 10- 0.25 Total 5.95 70.0 1.53 x 10 3.00

% of allowable 8.5% 0.05%

(flote #1- The argon activities reported are integrated values obtained from the facility's gaseous stack monitor. Calculated values have been substituted for measured values in the few instances when the monitoring system was down for maintenance or repair).

(flote #2: The tritium concentrations are estimates based on the amount of water lost by evaporation from the reactor times the concentration of tritium as HTO).

B. There were no radioactive liquid effluents released from the reactor facility during the year 1979.

C. Solid radioactive material released as radioactive wastes has been shipped via Garrett Truck Lines to Richland, Washington. fline 55. gallon drums were received by ?!uclear Engineering. All shipments were in compliance with Title 49 CFR Parts 170-189.

The total amount of radioactive waste released from the reactor facility during 1979 is estimated to be approximately 15.0 mci.

(flote: The principal radioactive waste generated at the reactor facility is the demineralizer resin - used resin with small quantities of rinse water is solidified with an oil dry compound prior to release in 55-gallon drums).

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VIII. Radiation Monitoring A. Our program to monitor and control radiation exposures included the four major elements below during the operating year 1979.

1. Eighteen area monitors (17 gammas, 1 neutron) located throughout the Nuclear Science Building. To provide a background signal, a small check source is attached to the scintillation detector. High alarm set points range from 2 mr/hr to 50 mr/hr. High level alarms have been infrequent and are documented in appropriate Log Books.

2. One Continuous Air Monitor (CAM) sampling the air in the reactor bay. An equilibrium concentration of 3 x 10 pCi/cc present for two minutes will result in an increase of 900 cpm above background. There are two alarm set points. A low-level alarm is set at 3,000 cpm, and the high-level alarm is set at 10,000 cpm.

Reactor bay air is sampled during all reactor operations. The fixed particulate air filter is changed and counted daily on a Beckman Low Beta II counting system. The charcoal filter, fitted behind the air filter, is changed and counted weekly. In all instances, final sample calculations show less than MPC (10 CFR Part 20, Appendix B, Table II) concentrations for all isotopes in question in the reactor bay.

3. Contamination wipe surveys and radiation surveys with portable survey instruments are performed at least once each month. All portable instruments are calibrated with a certified 3-curie Cs-137 source and wipes are counted on a Beckman Low Beta II counting system.

Wipe surveys have shown the reactor area remains free of tactile contamination except for intermittent low level activity to approximately 240 pCi beta and gamma per 100 cm2 on work table tops and the sample storage caves. Instrument surveys indicate no fixed areas of contamin-ation and radiation leaking at outside wall surfaces and have been less than 0.5 mr/hr at our maximum power level .

4. Personnel, X and gamna, beta and neutron film badges are assigned to all permanent occupants of the Nuclear Science Building. CaSO4:Dy dosimeters have been used at four outdoor environmental stations.

Reactor facility visitors are issued L-49 self-reading dosimeters.

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These monitoring results are categorized below:

Rem - 1979 Reactor Staff Gamma Beta Neutron Whole Body Highest 0.040 0.000 0.00 Mean 0.025 0.000 0.00 Hands Highest 0.300 0.000 0.00 Mean 0.050 0.000 0.00 Reactor Experimenters Whole Body Highest 0.030 0.000 0.00 Mean 0.006 0.000 0.00 Hands Highest 0.260 0.000 0.00 Mean 0.071 0.000 0.00 Reactor Visitors

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All readings were less than 1.0 mrem.

Environmental Stations Rem 1979 Exhaust Stack 0.0564 West 0.0005 Southwest 0.0000 Southeast 0.0000 Personnel monitoring results are for the fourth quarter of 1978 and the first three quarters of 1979.

Environmental monitoring is for an ll-month period.

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IX. Environmental Monitoring Pursuant to reactor operating procedures, soil and water samples are collected every second year. Samples were not collected in 1979 but will be collected in 1980.

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