ML070330212

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Submittal of Correction Page for the 2006 Annual Report of the U.S. Geological Survey Triga non-power Reactor Facility
ML070330212
Person / Time
Site: U.S. Geological Survey
Issue date: 01/26/2007
From: Timothy Debey
US Dept of Interior, Geological Survey (USGS)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML070330212 (2)


Text

U USGS science for a changingworld Department of the Interior US Geological Survey Box 25046 MS-974 Denver CO, 80225 So-944-January 26, 2007 U.S. Nuclear Regulatory Commission Document Control Desk Washington DC 20555

Dear NRC staff:

Enclosed is a correction page for the 2006 annual report of the U.S. Geological Survey TRIGA non-power reactor facility that was submitted one week ago. Please replace the original page 4 with the enclosed page 4. Corrections were made in the Personnel Monitoring Results table.

Sincerely, Timothy M. DeBey Reactor Supervisor Enclosure Copy to:

Al Adams, ,MS 12 G-13-,,-

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2. One Continuous Air Monitor (CAM) samples the air in the reactor bay. An equilibrium concentration of about 1 x 1e gCi/ml present for two minutes will result in an increase of 400 cpm above background. There are two alarm setpoints. A low-level alarm is set at 3000 cpm and the high level alarm is 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. Three areas were identified greater than 30 pCi/1 00 cm 2 beta contamination. One 71.3 pCi/1 00 cm2 was near the large cave in the reactor bay, 55.2 pCi/1 00 cm 2 was near the walk thru on the east side of the reactor console, and 45.9 pCi/1 00 cm 2 was near the middle of building 10. One area that was identified greater then 15 pCi/1 00 cm 2 alpha was near the walk thru on the east side of the reactor console. All other areas were less than 30 pCi/1 00 cm2 beta and 15 pCi/1 00 cm 2 alpha.

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 (1211(05 - 11130106)

Deep Dose Shallow Dose Equivalent Equivalent Name Whole Body (Rem) Whole Body (Rem) Extremity (Rem)

DeBey, T 0.237 0.261 0.430 Lightner,G 0.117 0.202 0.236 Liles, D 0.122 0.134 0.295 Lietz, P 10.073 0.074 0.231 Perryman, R 10.053 0.143 0.204 Note: December's personnel dosimetry results are not available at this time.

Reactor visitors and occasional experimenters wore pocket dosimeters that resulted in no individual reading that was greater than one (1) mrem.

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