ML110400023

U. S. Geological Survey Triga Non-Power Reactor Annual Report - January 1, 2010 - December 31, 2010

ML110400023
Person / Time
Site:	U.S. Geological Survey
Issue date:	01/31/2011
From:	Timothy Debey US Dept of Interior, Geological Survey (USGS)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML110400023 (6)

Text

5 USGS science for a changing world Department of the Interior US Geological Survey Box 25046 MS-974 Denver CO, 80225 January 31, 2011 U.S. Nuclear Regulatory Commission Document Control Desk Washington DC 20555

Dear NRC staff,

The 2010 annual report is herein submitted for the U.S. Geological Survey TRIGA non-power reactor facility.

This report is generated in compliance with our license conditions.

The facility docket number is 50-274.Sincerely, Timothy M. DeBey Reactor Supervisor Enclosure Copy to: Linh Tran, MS OWFN 12H15 1L U.S. GEOLOGICAL SURVEY TRIGA REACTOR ANNUAL REPORT JANUARY 1, 2010 -DECEMBER 31, 2010 NRC LICENSE NO. R-113 -DOCKET NO. 50-274 I. Personnel Changes: Benjamin Boyle (student employee) left the facility in August 2010.Karl Frank (student employee) left the facility in November 2010.II. Operating Experience The Geological Survey TRIGA Reactor (GSTR) was in normal operation for the year 2010. No major facility changes were made during the year.A synopsis of irradiations performed during the year is given below, listed by the organization submitting the samples to the reactor staff: Or-ganization Geologic Discipline

-INAA Geologic Discipline

-Geochronology Non-USGS Total Number of Samples 668 1107 2563 4338 A. Thermal power calibrations were performed in January and July, with minor adjustments made to the instrumentation.

B. During the report period, 192 daily checklists and 12 monthly checklists were completed in compliance with technical specifications requirements for surveillance of the reactor facility.C. Tours were provided to individuals and groups during the year for a total visitor count of approximately 500.I Ill. Tabulation of Energy Generated MWH operated Jan Feb Mar Apr May June July Aug Sept Oct Nov Dec Totals 37.726 78.497 153.283 20.850 56.799 41.984 40.129 101.683 19.416 50.192 70.278 41.774 712.610 Critical hours 44h 41m 81h 25m 156h 55m 23h 4m 59h 27m 44h 17m 43h 8m 103h 47m 23h 29m 56h 18m 81h 8m 46h 55m 764h 34m Pulses 0 0 0 2 0 0 0 0 0 0 4 0 6 IV. Unscheduled Shutdowns Number Date 1066 1067 1068 1069 1070 1071 1072 1073 1074 1075 01/07/10 02/11/10 02/23/10 02/23/10 05/13/10 06/30/10 07/09/10 07/13/10 09/07/10 09/21/10 Cause NET Fault DAC DIS064 timeout NP1000 hi power NP1000 hi power DAC DIS064 timeout NPP1 000 hi power due to incorrect power demand NPP1000 hi power due to sample lowering NPP1000 hi power DAC DIS064 timeout NPP1000 hi power V. Significant Maintenance Operations 01/10 Replaced Mylar window and upgraded computer software on the G5000 swipe counter detector 02/10 Replaced pressure gauge in the primary cooling system 02/10 Replaced Mylar window and cleaned G5000 counting system 04/10 Replaced resin in demineralizer tank 04/10 Installed bulk water high temperature test circuit.06/10 Replaced DIS064 board in CSC & DAC 07/10 Replaced test signal potentiometer R196 on NPP1000 instrument 09/10 Replaced CRT displays on control console with LCD displays 10/10 Replaced 2 O-ring seals on transient rod 11/10 Replaced bottom O-ring on transient rod drive 2 VI. Summary of 10 CFR 50.59 changes There were two 50.59 changes that were evaluated, approved, and implemented in CY 2010. One was to add a test circuit for testing the pool water temperature alarm.The change involved hard-wiring a test circuit to the existing water temperature monitoring circuitry.

The second 50.59 change involved an upgrade to the console.Currently one LCD flat-panel monitor has replaced one old CRT monitor; a second LCD flat-panel monitor in combination with a DELL computer was added to replace/emulate the old Tektronics monitor. Further upgrades will be performed during CY2011.VII. Radioactivity Releases A. Listed below are the total amounts of radioactive gaseous effluent released to the environment beyond the effective control of the reactor facility.Table 1. Gaseous Effluents Released to the Environment Month Argon-41 R-113 License Tritium (HTO IOCFR20 Allowable (mCi)

• Allowable (Ci) (Ci) (mCi)January 0.335 5.833 0.12 124 February 0.282 5.833 0.00 124 March 1.230 5.833 0.11 124 April 0.001 5.833 0.00 124 May 0.044 5.833 0.12 124 June 0.155 5.833 0.00 124 July 0.320 5.833 0.11 124 August 0.843 5.833 0.00 124 September 0.142 5.833 0.14 124 October 0.282 5.833 0.00 124 November 0.794 5.833 0.08 124 December 0.477 5.833 0.10 124 Total 4.905 70.00 0.76 1488% of Allowable 7.0% -------------------

0.051%* Note: 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 were performed by Test America Laboratories.

B. A solid low-level waste shipment of 7.5 cu.ft., part of which was reactor generated, was shipped this calendar year.VIII. Radiation Monitorina 3

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 very infrequent and due to sample movements.

2. One Continuous Air Monitor (CAM) samples the air in the reactor bay. An equilibrium concentration of about 1 x 108 ýtCi/ml present for two minutes will result in an increase of about 400 cpm above background.

The alarm setpoints are a low-level alarm set at 3000 cpm and the high level alarm set at 10000 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 concentration values in 10 CFR Part 20, Appendix B, Table 2 for all particulate radioisotopes produced 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-1 37 source traceable to NBS, and wipes are counted on a Gamma Products G5000 low level counting system. The highest removable contamination found was equal to 523 pCi/1 00 cm beta, on top of the north lead storage cave. This area was successfully decontaminated below MDA.The next highest removable contamination found was equal to 176.5 pCi/100 cm 2 beta, on top of the north lead storage cave as well. No areas were greater than 17.2 pCi/1 00 cm 2 alpha 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. LiF TLD dosimeters were used at four outdoor environmental stations.

Reactor facility visitors are issued self-reading dosimeters.

Reactor staff personnel are issued beta, gamma, albedo neutron badges.Table 2. Personnel Monitoring Results (1211109 -11130110)Employee code Whole Body (Rem) Whole Body (Rem) Extremity (Rem)Deep Dose Equiv. Shallow Dose Equiv.E0888 0.072 0.073 0.293 E0607 0.105 0.089 0.431 E0707 0.091 0.091 0.240 E0908 0.028 0.028 0.143 E0509 0.000 0.00 0.041 E0610 0.012 0.012 0.000 E1109 0.000 0.000 0.041 4 Reactor visitors and occasional experimenters wore pocket in no individual's reading that was greater than 1.6 mrem.dosimeters that resulted Table 3. Environmental Dose Results Location Dose Dose Dose Dose Total Jan-Mar Apr-June July-Sept.

Oct.- Dec.(RAD) (RAD) (RAD) (PAD) RAD Exhaust 0.050 0.020 0.027 0.038 0.135 Stack Cooling 0.009 0.000 0.005 0.006 0.011 Tower Fence West Vehicle 0.020 0.012 0.015 0.022 0.069 Gate West Room 0.023 0.013 0.041 0.066 0.143 151 Gate Southwest 0.004 0.003 0.000 0.006 0.013 Light Pole Control 0.039 0.038 0.048 0.050 0.175 (background)

Southeast 0.002 0.000 0.000 0.002 0.004 Light Pole Note: Above totals have the background subtracted (see control).

Environmental TLDs were supplied and analyzed by Global Dosimetry Solutions.

X. Environmental Monitorina 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.

Environmental soil and water samples were taken and analyzed.

No elevated readings or reactor-produced isotopes were identified (fallout Cs-1 37 was identified).

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