ML20141F099
| ML20141F099 | |
| Person / Time | |
|---|---|
| Site: | U.S. Geological Survey |
| Issue date: | 12/31/1996 |
| From: | INTERIOR, DEPT. OF, GEOLOGICAL SURVEY |
| To: | |
| Shared Package | |
| ML20141F044 | List: |
| References | |
| NUDOCS 9705210208 | |
| Download: ML20141F099 (5) | |
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U.S.
GEOLOGICAL SURVEY TRIGA REACTOR AMENDED ANNUAL REPORT JANUARY 1, 1996 - DECEMBER 31, 1996 NRC LICENSE NO. R-113 - DOCKET NO. 50-274 Parsennel Chances A new Reactor Health Physicist was hired in September.
The facility staff continues to be 3 full time employees Creactor operators and health physicist).
The facility is in the process of hiring a full time Reactor Supervisor.
Ccaratina Excerience The Geclogical Survey TRIGA Reactor (GSTR) was in normal cperation for the year 1996.
No major facility changes were made during the year.
A total of 101 irradiation requests were processed dur ng the year.
A synopsis of irradiations performed during the year is 3:ven belew, listed by the organization submitting tne samples to r.he reactor staff:
Cr7anization No. of Samples Geolcgic Division - National Mapping 1279 Geolcgic Division - Mineral Resources 1907 Gecicgic Division - Volcano Hazards 36 Gecicgic Division - Energy Resources 15 Mcn ~JSGS users 706 T:tal 3943 A.
Thermal power calibrations were performed in Feb.
and Aug., with minor adjustments required.
B.
Cne new Class I experiment was approved during the year.
The new experiment involved the activation of evaporated residues of biomass materials.
No new Class II experiments were approved this year.
C.
During the report period, 100 daily checklists and 12 monthly checklists were completed in compliance with technical specifications requirements for surveillance of the reactor facility.
D.
Tours were provided to individuals and groups during the year for a total visitor count of approximately 264.
E.
29 fuel movements were performed during 1996 for i
the purposes of increasing reactivity, performing experiments.
1 9705210208 970514 PDR ADOCK 05000274' R
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III.
Tabulation of Enerav Generated Megawatt TimeReactor Number of Month Hours Was Critical Pulses January 15.000 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> 12 minutes 0
February 43.542 47 hours5.439815e-4 days <br />0.0131 hours <br />7.771164e-5 weeks <br />1.78835e-5 months <br /> 20 minutes 0
March 57.517 61 hours7.060185e-4 days <br />0.0169 hours <br />1.008598e-4 weeks <br />2.32105e-5 months <br /> 09 minutes 0
April 40.239 43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br /> 43 minutes 0
May 34.720 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> 53 minutes 0
June 41.720 44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br /> 14 minutes 0
July 38.025 39 hours4.513889e-4 days <br />0.0108 hours <br />6.448413e-5 weeks <br />1.48395e-5 months <br /> 41 minutes 0
August 50.443 52 hours6.018519e-4 days <br />0.0144 hours <br />8.597884e-5 weeks <br />1.9786e-5 months <br /> 40 minutes 0
September 78.000 79 hours9.143519e-4 days <br />0.0219 hours <br />1.306217e-4 weeks <br />3.00595e-5 months <br /> 01 minute 0
October 32.650 34 hours3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> 09 minutes 0
November 40.433 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> 53 minutes 0
December 39.000 39 hours4.513889e-4 days <br />0.0108 hours <br />6.448413e-5 weeks <br />1.48395e-5 months <br /> 34 minutes 0
Totals 510.639 533 hours0.00617 days <br />0.148 hours <br />8.812831e-4 weeks <br />2.028065e-4 months <br /> 28 minutes 0
IV.
Unscheduled shutdowns Number Date Cause 703 1/3 AC power outage.
704 1/3 AC power outage.
705 1/3 CSC watchdog scram due to computer lockup.
706 2/13 NPP1000 Hi power scram due to noise.
707 2/13 CSC watchdog scram due to computer lockup.
708 3/5 CSC watchdog scram due to computer lockup.
709 3/7 CSC watchdog scram due to computer lockup.
710 3/13 CSC watchdog scram due to computer lockup.
711 3/13 CSC watchdog scram due to computer lockup.
712 3/13 CSC watchdog scram due to computer lockup.
713 4/25 CSC watchdog scram due to computer lockup.
714 4/29 CSC watchdog scram due to computer lockup.
715 5/1 CSC watchdog scram due to computer lockup.
716 6/5 CSC watchdog scram due to computer lockup.
717 8/2 CSC watchdog scram due to computer lockup.
718 8/5 CSC watchdog scram due to computer lockup.
719 8/14 CSC watchdog scram due to computer lockup.
720 8/29 CSC watchdog scram due to computer lockup.
721 8/30 CSC watchdog scram due to computer lockup.
722 9/4 CSC watchdog scram due to computer lockup.
723 9/4 CSC watchdog scram due to computer lockup.
l 724 9/11 CSC watchdog scram due to computer lockup.
725 9/24 CSC watchdog scram due to computer lockup.
726 9/25 CSC watchdog scram due to computer lockup.
727 9/30 CSC watchdog scram due to computer lockup.
728 10/9 CSC watchdog scram due to computer lockup.
]
729 10/11 CSC watchdog scram due to computer lockup.
i 730 10/16 CSC watchdog scram due to computer lockup.
731 10/25 CSC watchdog scram due to computer lockup.
732 11/8 CSC watchdog scram due to computer lockup.
733 11/25 CSC watchdog scram due to computer lockup.
734 12/18 CSC watchdog scram due to computer lockup.
735 12/24 CSC watchdog scram due to computer lockup.
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v.
Maior Maintenance operations There were no major maintenance items this year.
VI.
Summary of 10 CFR 50.59 chances There were no 50.59 changes at the facility during this report period.
V:!.
Radioactivity Releases A.
Listed below are the total amounts of radioactive gaseous effluents released to the environment beyond the effective control of the reactor facility.
License (R-113) 10 CFR 20 Argon-41 Allowable Tritium (HTO)
Allowable M;n:h
.( Ci ).
(Ci)
(mci)
(mci)
January 0.045 5.8 0.142 124 February 0.041 5.8 0.153 124 March 0.110 5.8 0.250 124 April 0.006 5.8 0.063 124 vy 0.008 5.8 0.038 124 a
June 0.016 5.8 0.057 124 July 0.013 5.8 0.149 124 August 0.177 5.8 0.071 124 Septemcer 0.426 5.8 0.071 124 Octccer 0.219 5.8 0.227 124 Ncvemcer 0.212 5.8 0.108 124 Decemcer 0 ?OA 5.8 0.125 124
)
Tctals 1.479 70.0 1.454 1468
% of alicwable 2.11%
0.098%
Ncte:
The tritium concentrations are estimates based on the amount of water lost by evaporation from the reactor multiplied by the concentration of tritium as HTO.
Tritium sample analyses are being performed by Barringer Labs.
B.
No lcw level solid waste was shipped for burial in Washington during the year.
Note:
The principal radioactive waste generated at the reactor facility is the demineralizer resin.
Used resin with small quantities of rinse water was de-watered by evaporation and placed in 55-gallon drums.
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6 VIII.
Radiation Monitorino A. Our program to monitor and control radiation exposures included the four major elements below during the operating year.
1.
Fifteen gamma-sensitive area monitors are located throughout the Nuclear Science Building.
A remote readout panel is located in the reactor health physics office.
High alarm set points range frcr 2 mR/hr to 50 mR/hr.
High level alarms are very infrequent and due to sample movements.
- 2. One Continuous Air Monitor (CAM) sampling the air ig the reactor bay.
An equilibrium concentration of about 1 x 10-uCi/ml present for two minutes will result in an increase of 400 ccr above background.
There are two alarm setpoints.
A low-level alarr
~
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 each week and counted on a HPGE gamma spectrometer counting system.
The charcoal filter, fitted behind the air filter, is also changed and counted weekly.
In all instances, sample data were less than airborne effluent concentration values (10 CFR Part 20, Appendix B, Table 2) for all particulate' radioisotopes produce by the reactor.
- 3. Contamination wipe surveys and radiation surveys with portable survey instruments are performed at least once a month.
All portable instruments are calibrated with a 3-Curie (initial activity) Cs-137 source traceable to NBS and wipes are counted en a Gamma Products G4020 low level counting system.
Sixcontaminatedareaswerenotedduringrouginewipesurveys.
Beta activities ranging from 30 to 148 pCi/100 cm were noted.
Soap and water were used to remove this contamination.
The roof area over the reactor tank is roped off and posted as a radiation area (averaging 2.5 mR/hr) during 1 MW operations.
4.
Personnel, X and gamma, beta and neutron dosimeters are assigned to all permanent occupants of the Nuclear Science Building.
LiF TLD dosimeters are used at four outdoor environmenta.
stations.
Reactor facility visitors are issued self-reading dosimeters.
Reactor staff are issued albedo neutron badges.
Deep Dose Shallow Dose Equivalent Equivalent Name Whole Body Whole Body Extremitv Helfer P.
0.000 0.000 0.020 Perryman R.
0.000 0.000 0.060 Liles D.
0.000 0.000 0.030
- Liles monitoring period 9/18/96 to 12/31/96.
All doses in Rem.
Reactor Visitors and Occasional Experimenters No individual reading was greater than 2 mrem.
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Environmental Stations Bam Exhaust Stack 0.0686 Cooling tower fence 0.0308 west vehicle gate 0.0341 west Room 151 gate 0.0474 Southwest 0.0198 Southeast 0.0046
-Control (background) 0.1235 Note: Above totals have the background subtracted (see control).
3 IX.
Environmental Monitorinc There have been no uncontrolled radioactivity releases from the reactor to the present date.
Thus, the data on file from past years to the present are considered to be background information.
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