ML20096G188
| ML20096G188 | |
| Person / Time | |
|---|---|
| Site: | U.S. Geological Survey |
| Issue date: | 12/31/1995 |
| From: | Helfer P INTERIOR, DEPT. OF, GEOLOGICAL SURVEY |
| To: | Collins S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| NUDOCS 9601250027 | |
| Download: ML20096G188 (8) | |
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g United States Department of the Interior to
.- GEOLOGIC.\L SI'RVEY
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DENVER FEDER.\L CENTER
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U.S. Nuclear Regulatcry Ccanission January 18, 1996 Division of Radiation Safety and Safeguards ATIN: ' Sanuel J. Collins, Director 611 Ryan Plaza Dr., Suite 400 Arlirgton, TX 76011 i
Dear Mr. Collins:
The attached annual report of the U.S. Geological Survey TRIGA inactor facility is submitted in accordance with license conditions.
The facility docket number is 50-274.
Sincerely, _ .,
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' Paul G. Helfer Acting Reactor Supervisor i
4 sEnclosure copy to:
{nrv - nt Control Desk (2)
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lMr. Blair Nicholas
}611 Ryan Plaza Dr. Suite 400
- . Arlington TX 76011 i
Moch 9601250027 951231 DR ADOCK0500g4 o10
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. U.S. GDOIDGICAL SURVEY TRIGA REACIOR ANNU7.L REEORT JANUARY 1,1995 - DECEMBER 31, 1995 NRC LICENSE NO. R-113 - DOCKET NO. 50-274 r I. Perr.ainel 01ances .
I h e Reactor Health Physicist resigned in May and this' position is being temporarily filled by another staff person. The Reactor Supervisor ~
resigned in September arri this position is being temporarily filled by another staff person. The facility staff consists of 2 Senior Reactor Operators, one also serves as the Acting Reactor Supervisor and one also serves as the Acting Reactor Health Physicist.'
t II. Ooeratirn Experience The Geological Survey TRIGA I'.eactor (GSTR) was in normal
- operation for the year 1995. No major facility changes were made during 3
the year.
t A total of 188 irradiation requests were pr - W during the year, with the average request representing 46 samples and 7.5 full-power hours of reactor operation. A synopsis of irradiations performed during the year is given below, listed by the organization cubmitting *the samples to the reactor staff:
i Oruanization Number of Sanoles i~
i Geologic Division - Geochemistry 6,660 }
Geologic Division - Isotope Geology 977 i' Geologic Division - Cent. Mineral Res. 34 '
Geologic Division - Sedimentary Proc. 30 Non-USGS users 763 .
r Total 8,464 i
A. Thermal power calibrations were performed in February and August, with minor adjustments required.
B. Two new Class I experiment were approved during this period.
Both Class I experiments involved the activation of urine samples, with the intent of determining Th concentrations.
No new Class II experiments were approved durirs the year.
C. During the report period, 156 daily checklists and 12 monthly checklists were completed in compliance with technical specifications requirements for surveillance of the reactor facility. ;
r D. Tours were provided to inlividuals and groups during the year for a total visitor count of approximately)175.
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E. 38 fuel movements were performed during 1995 for the purposes of increasing reactivity and performirg experiments. j
^ III. Tabulation of Eneruv Generated Megawatt Time Reactor Number of Month Hours Was Critical Pulses January 85.065 88 hours0.00102 days <br />0.0244 hours <br />1.455026e-4 weeks <br />3.3484e-5 months <br /> 00 minutes 0 l February 76.362 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> 26 minutes O March 95.988 97 hours0.00112 days <br />0.0269 hours <br />1.603836e-4 weeks <br />3.69085e-5 months <br /> 22 minutes O April 128.901 136 hours0.00157 days <br />0.0378 hours <br />2.248677e-4 weeks <br />5.1748e-5 months <br /> 08 minutes O May 85.433 99 hours0.00115 days <br />0.0275 hours <br />1.636905e-4 weeks <br />3.76695e-5 months <br /> 05 minutes 0 June 63.666 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> 30 minutes 0 July 96.500 97 hours0.00112 days <br />0.0269 hours <br />1.603836e-4 weeks <br />3.69085e-5 months <br /> 48 minutes O August 58.386 61 hours7.060185e-4 days <br />0.0169 hours <br />1.008598e-4 weeks <br />2.32105e-5 months <br /> 10 minutes O September 28.188 29 hours3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br /> 00 minutes 0 October 46.463 47 hours5.439815e-4 days <br />0.0131 hours <br />7.771164e-5 weeks <br />1.78835e-5 months <br /> 42 minutes 0 November 56.317 57 hours6.597222e-4 days <br />0.0158 hours <br />9.424603e-5 weeks <br />2.16885e-5 months <br /> 26 minutes 0 December 56.000 64 hours7.407407e-4 days <br />0.0178 hours <br />1.058201e-4 weeks <br />2.4352e-5 months <br /> 49 minute O i l
Totals 877.269 926 hours0.0107 days <br />0.257 hours <br />0.00153 weeks <br />3.52343e-4 months <br /> 26 minutes 0 l
IV. Unscheduled Shutdowns ;
Serial No. Date Cause j 644 1/10 Manual scram, Rabbit stuck in transfer tube. I 645 1/12 GC watchdog scram due to computer lockup. ;
646 1/18 CSC watchdog scram due to ocanputer lockup. )
647 1/20 CSC watchdog scram due to conputer lockup. i 648 2/1 CSC watchdog scram due to ccanputer lockup.
649 2/13 CSC watchdog scram due to ccanputer lockup 650 2/14 GC watchdog scram due to computer lockup.
651 3/1 CSC watchdog scram due to computer lockup.
652 3/7 GC watchdog scram due to computer lockup.
653 3/7 GC watchdog scram due to ccrputer lockup.
654 3/8 CSC watchdog scram due to computer lockup.
655 3/9 CSC watchdog scram due to computer lockup.
t656 3/10 CSC watchdog scram due to computer lockup.
657 3/16 DAC watchdog scram due to computer lockup.
658 3/22 CSC watchdog scram due to ccxuputer lockup.
659 4/6 GC watchdog scram due to ccxnputer lockup.
660 4/10 CSC watchdog scram due to computer lockup.
661- 4/11 GC watchdog scram due to ccanputer lockup.
662 4/17 CSC watchdog scram due to ccroputer lockup.
663 4/26 GC watchdog scram due to computer lockup.
664 4/26 CSC watchdog scram due to computer lockup.
665 4/27 CSC watchdog scram due to computer lockup.
666 4/27 CSC watchdog scram due to camputer lockup.
667 5/1 CSC watchdog scram due to ccxnputer lockup.
668 5/5 CSC watchdog scram due to ccxtputer lockup.
669 5/18 GC watchdog scram due to conputer lockup.
670 5/24. CSC watchdog sc::am due to ccxnputer lockup.
671 ~5/24 CSC watchdog scram due to ccxtputer lockup.
a 672 6/6 CSC watchdog scram due to camputer lockup.
673 6/7 CSC watchdog scram due to camputer lockup.
674 6/9 CSC watchdog scram due to computer lockup.
675 6/9 GC watchdog scram due to' camputer lockup.
676 6/9 CSC watchdog scram due to camputer lockup.
677 6/14 GC watchdog scram due to computer lockup.
AC Power dip.
678 7/5 679 7/14 CSC watchdog scram due to camputer lockup.
680 7/18 CSC watchdog scram dus. to computer lockup.
681 7/19 CSC watchdog scram due to computer lockup.
682 7/21 CSC watchdog scram due to camputer lockup.
683 7/27 NPP 1000 scram 684 8/7 CSC watchdog scram due to computer lockup.
685 8/9 CSC watchdog scram due to computer lockup.
686 8/16 CSC watchdog scram due to ccmputer lockup.
687 8/29 Auto reboot. l 688 8/29 CSC watchdog scram due to camputer lockup.
689 9/6 CSC watchdog scram due to camputer lockup.
690 9/8 AC Power dip, NH1000 data error scram 691 9/20 NM1000 data error' scram 692 10/13 CSC watchdog scram due to camputer lockup.
693 10/18 CSC watchdog scram due to camputer lockup.
694 11/1 CSC watchdog scram due to camputer, lockup.
695 11/2 CSC watchdog scram due to computer lockup.
696 11/6 CSC watchdog scram due to camputer lockup.
697 11/16 CSC watchdog scram due to camputer lockup.
699 11/29 CSC watchdog scram due to camputer lockup.
700 12/13 CSC watchdog scram due to computer lockup.
701 12/15 CSC watchdog scram due to camputer lockup.
702 12/19 CSC watchdog scram due to computer lockup.
V. Maior Maintenance,0cerations A Fuel Follower control rod (SHIM-2) was replaced with a new rod. The prirary coolant pump was replaced. The secondary cooling tank was cleaned and coated. Other less significant activities included the troubleshoodng and replacement of several items in the digital control system arx1 replacement of the ion exchange resin in January, June and November. !
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VI. Summary of 10 CFR 50.59 changes There was one 50.59 change at the facility during this report period.
It was a change to Section 5.2.4 of the Reactor Operations Manual.
This section was changed from "5.2.4 At least two reactor staff members rust be present at the reactor site whenever the reactor is operating.
The operator at the console shall be an NRC-licensed operator and shall be j inforred of the location of the second permn. The Senior Reactor l Operator-in-Charge of the particular experiment shall be one of the two staff merrbers on site". Changed to "5.2.4 At least t'e reactor staff l members must be on duty whenever the reactor is operating. The operator I at the console shall be an NRC-licensed operator and the second person nust be able to reach the facility within 15 minutes after being contacted j by the console operator. A method of communication nust be available so ,
i that the operator at the console is able to contact the second person within a 5 minute tilae period. The Senior Reactor Operator-in-Charge of the operation must be one of.the two staff members on duty, and must be at the facility during reactor start-up , approach to power, recovery from i unplaned shutdown, recovery from an unse:heduled significant power !
reduction, relocation of any in-core experiment or core component (other l t'un normal control rod movements) with a reactivity worth greater than 1 one dollar, or fuel movement. i The safety committee evaluation of the change made under the provisions of i 10CFR50.59 concluded that the changes to the Reactor Staffing requirements
- l. does not increase the probability of occurrence or the consequences l of an accident or malfunction of equipnent important to safety previously evaluated in the safety analysis report,
- 2. does not create the possibility for an accident or malfunction of a )
different type than any evaluated previously in the safety analysis !
report, and !
- 3. does not reduce the margin of safety as defined in the basis for any j technical specification. i l
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1 VII. . RadioactivLty Releases 1
A. Listed below are the total amounts of radioactive gasecus effluents released to the environs beyord the effective control of the reactor facility. .
License (R-113) 10 CFR 20 Argon-41 Allowable , Tritium (HIO) Allowable Month (Curies) (curies) ,
(mcuries) (mCuries)
January 0.450 5.8 . 0.221 250 February 0.510 5.8 0.114 250 March 0.410 5.8 0.295 250 April 0,590 5.8 0.114 250 May 0.290 5.8 O.239 250 June 0.160 5.8 0.076 250 July 1.060 5.8 ;- 0.032 250 August 0.200 5.8
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0.760 250 l September 1.030 5.8 -
. 0.131 250 October 0.160 5.8 ( 0.125 250 November 0.190 5.8 -
0.091 250 Wmhor L19_0, 5.8 0.127 250 Total 5.240 70.0 2.325 3000
% of allowable limits: 7.49% .078%
Note: 'Ihe tritium concentrations are estimates based on the amount of water lost by evaporation from the reactor multiplied by the concentration of tritium as HIO. Tritium sample analyses are being performed by Colorado State University and Barringer labs (December) .
t B. No low level solid waste or solidi'fied resin was shipped for burial in Washington state during the year.:
Note: The principal radioactive waste generated at the reactor facility is the demineralizer resin - used resin with strall quantities of rinse water was de-watered by evaporation and placed in in 55-gallon drums.
VIII. Radiation Monitorira _ _ _ _ _
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 from 2 mR/hr to 50 mR/hr. High level alarms are infrequent and due to sample novemerfs. .
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- 2. One Continuous Air Monitor (CAM) sampling tge air in the reactor bay. An equilibrium concentration of about 1 x 10- uCi/ml present for two minutes will result in an increase of 520 cpm above b ekground. 'Ihere are two alarm setpoints. A low-level alarm is set at 3000 cpu and the high level alarm is set at 10000 cpm. 1 Reactor bay air is sampled during all reactor operations. 'Ihe fixed l particulate air filter is changed each week and counted on a HPGe multichannel analyzer counting system. 'Ihe charcoal filter, fitted behind the air filter, is also changed and counted weekly. In all instances, final sample calculations showed less than 10 CFR Part 20 Appendix B l 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 a month. All portable instruments are calibrated with a 3-Curie (initial activity) Cs-137 source traceable to NBS and wipes are counted on a Garna Products G4020 low level
_ counting system.
Fourteen contaminated areas were noted durig routine wipe surveys.
Beta activities ranging from 30 to 790 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 1.5 mR/hr) during 1 NW operations.
4.-Personnel, X and gamma, beta and neutron film badges are assigned to all permanent emmnts of the Nuclear Science Building. Li-7 TID-dosimeters have been used at six outdoor envircsT=ute stations. Reactor facility visitors are issued self-reading dosimeters. Reactor staff personnel are issued albacio neutron badges.
Personnel monitoring resulte are categorized below:
Deep Dose Shallow Dose Equivalent Equivalent Whole Body Whole Body Extremity Reactor Staff Helfer P. 80 80 140 Perryman R. 30 90 130 DeBey T.** 80 80 140_ j ramel S.** 20 20 120 !
Dose is in millirem and includes information from dosimetry reports for period 12-01-94 to 11-30-95. Report for Dec., 1995 has not been received 00 DeBey nonitoring period 12-01-94 to 09-15-95 00 Lassel monitoring period 12-01-94 to 05-23-95 Reactor Visitors and Occasional Experinenters No individual reading was greater than 1 mrem.
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Enviiumerital Stations - TLD Monitorirn Results location . E6D Exhaust Stack, -
0.1542
.m West Gate (Rm'149) 0.0514 Ioadirg Dock Gate (Rm 151) 0.0992 Fence (by Coo).ing Tower) 0.0372 Southwest Light Pole 0.0136 Southeast Light Pole 0.0100
- Control (background)- .
0.1732 e
Note: Above totals have the background subtracted (see control).
IX. Envilumh(wl Monitorira PursuanttodSTRg.vcidures,onandoff-sitesoilandwatersamplesare collected and analyzed on'a biennial basis. Envirumadal soil and water sanples were hollected in 1994.
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l There have been no uncontrolled radioactivity. releases. from the reactor to the present date. 'Ihus, the data on file fram past years to the present are considered to be background information.
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