ML20028G077
| ML20028G077 | |
| Person / Time | |
|---|---|
| Site: | U.S. Geological Survey |
| Issue date: | 12/31/1982 |
| From: | INTERIOR, DEPT. OF, GEOLOGICAL SURVEY |
| To: | |
| References | |
| NUDOCS 8302070375 | |
| Download: ML20028G077 (7) | |
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1 U. S. Geological Gurvey TRIGA Reactor ANNUAL REPORT January 1, 1982 - December 31, 1982 NRC License No. R-113 -
Docket No. 50-274 I. Administrative Changes A. Dr. Hugh T. Millard, Jr. replaced Mr . Albert P.
Marranzino as Reactor Administrator.
B. Dr. David McKown replaced Dr. Millard as a member of the Reactor Operation's Committee.
II. Operating Experience The prime function of the Geological Survey TRIGA Reactor -
(GSTR) for the year 1982 continumi to be the provision of neutrons for the various research programs being conducted by the U.S. Geological Survey. Irradiations were also per-formed for other Governmental agencies and educational institutions.
A listing of all irradiations performed during the year 1982 is listed below.
Organization Samples (1982)
Geologic Division (Denver) 18,656 Geologic Division (Reston) 226 Geologic Division (Menlo Park) 52 University of Georgia 49 Oregon State University 28 University of Utah 4 University of British Columbia 2 Colorado School of Mines 1 j 19,018
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The operation of the reactor has been normal. The specific's of operations relating to performance character-istics are: A. Thermal power calibration at 50 KW was performed in January and June, 1982. B. Control rods were calibrated in January. C. Four (4) standard fuel elements were added to the core in January. D. No Class II experiments were approved during 1982. E. During the report period 191 daily ' checklists and 12 monthly checklists were completed in compliance with Technical Specifications requirements for surveillance of the reactor facility. F. Tours of the reactor facilty were provided to 16 groups during the year. The major groups visiting the facility were affiliated with: St. Mary's High School Highland High School . Bennett High School University of Wyoming Rockwell International University of Missouri University of Colorado Geological Survey of Japan During the yea r , 171 visitors were admitted to the reactor facility.
3 III. Tabulation of Energy Generated Mewawatt Time Reactor Number of Month Hours Was Critical Pulses January 1982 68.812 88 hours 20 minutes 0 February 1982 88.655 94 hours 56 minutes O March 1982 86.858 95 hours 34 minutes O April 1982 66.759 72 hours 20 minutes O May 1982 85.516 102 hours 40 minutes 0 June 1982 93.874 127 hours 12 minutes 0 July 1982 112.391 125 hours 33 minutes O August 1982 74.371 87 hours 52 minutes O September 1982 76.441 87 hours 44 minutes 0 October 1982 96.933 105 hours 18 minutes 0 November 1982 85.668 100 hours 38 minutes 'O December 1982 73.189 78 hours 55 minutes 0 1009.467 1167 hours 03 minutes 0 IV . Unscheduled Shutdowns Emergency Shutdowns - number and reason
- 1. Linear power scram - physical Serial 4287 ,
shock to console
- 2. Primary power scram - Serial 4288 power failure
- 3. Percent power scram - physical Serial s289 shock to console Unscheduled Shutdowns
- 1. Manual Scram - Sample failed to Serial #284 leave Reactor signal. Sample was out of reactor. Loss of power to photocell
- 2. Manual Scram - Sample jammed in Serial A285 sample changer block
- 3. Manual Scram - Sample stuck in Serial 5286 transit signal. Sample returned 0.K. Software error
- 4. Manual Scram - Sample stuck in Serial #290 transit signal. Sanple returned 0.K. Bent tube on sample changer.
4 V. Major Maintenance Operations A. Water Systems
- 1. The demineralizer resin was changed once during the year.
- 2. Replu 'ed make-up valve on the secondary water system.
B. Control Rods
- 1. Replaced seals, "O" rings, and "Down" microswitch and bracket on Transient Rod.
VI. Summary of 10 CFR 50.59 Changes . No changes were made under 10 CFR 50.59. VII. Radioactivity Releases A. Listed below are the total amounts of radioactive gaseous effluents released to the environs beyond the ef fective control of the reactor facility. License (R-113) 10 CFR 20 Argon-41 Allowable Tritium (!YIO) Allo d le Month (curies) (curies) (curies) (curies) January 1992 0.70 5.8 8.6 x 10 5 0.25 February 1982 0.53 5.9 ' 3.9 x 10 5
. 0.25 1%rch 1982 0.54 5.8 11.3 x 10 5 0.25 April 1982 0.58 5.8 7.8 x 10 5 0.25 May 1982 0.91 5.8 7.0 x 10 5 0.25 June 1982 0.% 5.8 7.3 x 10 5 0.25 July 1982 0.70 5.8 9.9 x 10 5 0.25 August 1982 0.47 5.8 10.6 x 10 55 0.25 September 1982 0.54 5.8 17.7 x 10 0.25 October 1982 0.89 5.8 10.3 x 10 5 0.25 tbvember 1982 0.72 5.8 8.0 x 10 3 0.25 December 1982 0.86 5.8 6.9 x 10 5 0.25
'Ibtal 8.40 70.0 1.19 x 10- 3.00 ;
% of allowable 12% 0.04% l (Note al: The argon activities reported are integrated val-ues 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).
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l (Note #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 1982. C. No radio *.ctive waste was shipped offsite during 1982. The total amount of radioactive waste released from the reactor facility during 1982 is estimted .o be approximately 4.0 mci. (Note: The prinicpal radioactive waste generated at the reactor facilty is the demineralizer resin - used - resin with small quantities of rinse water is solid-ified with an oil dry compound prior to release in 55-gallon drums). VIII. Radiation Monitoring A. Our program to monitor and control radiation exposures included the four major elements below during the operating year 1982. ,
- 1. Eighteen area monitors ( 17 g ammas , 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 Mcnitor (CAM) sampling the air in the reactor bay. An equilibrium concentration of 3.0 x 10 8uCi/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, finul sample calculations show less than MPC (10 CFR Part 20, Appendix B, Table II) concentrations for all isotopes in question in the reactor bay.
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- 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 on work table tops and the sample storage caves. Instrument surveys indicate no fixed areas of contamination and radiation leaking at outside wall surfaces and have been less than 0.5 mr/hr at our maximum power level. The maximum count level for a wipe (beta + gamma /100 cm2 ) was 2830 pCi on the floor near the large sample storage cave. ,
- 4. Personnel, X and gamma, beta and neutron film badges are assigned to all permanent occupants of the Nuclear Science Bailding. CaSo4 Dy dosimeters have been used at four outdoor environmental stations.
Reactor facility visitors are issued L-49 self-reading dosimeters. These monitoring results are categorized below: Rem - 1982 Gamma Beta Neutron Reactor Staff Whole Body Highest 0.040 0.000 0.00 Mean 0.015 0.000 0.00 Hands Highest 0.200 0.000 0.00 Mean 0.050 0.000 0.00 Reactor Experimenters Whole Body Highest 0.015 0.000 0.00 Mean 0.009 0.000 0.00 Hands dighest 0.180 0.000 0.00 Mean 0.047 0.000 0.00
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Reactor Visitors All readings were less than 1.0 mrem. Environmental Stations Rom 1982 Exhaust Stack O.0158 West 0.0017 Southwest 0.0003 Southeast 0.0002 Personnel monitoring results cre for the. the fourth quarter of 1981 and the first three quarters of 1992. IX. Environmental Monitoring _ Pursuant to reactor operating procedures, soil and water samples are collected every second year. Samples were collected in 1982. O i I I i t
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