Air sampling in the workplace. Final report

Abstract

Atlanta,3490 PiedmontGA 30305Road' NE-Suite 1410 MASTER DISTRIBUTION OF THIS DOCUMENT 18 UNLIMITE.I_ Use of N UREG-1400 by Licensees This report, NUREG-1400, was written to provide technical information to licensees using Regulatory Guide 8.25, Revision 1, 'Air Sampling in the Workplace." The report was reviewed by the U.S. Nuclear Regulatory Commission (NRC) staff for its technical content. NUREG-1400 is not and should not be used as a regulatory compliance document, because it neither establishes regulatory positions nor defines what is acceptable to the NRC. For the case in which a licensee has made a commitment to conduct air sampling in accordance with the recommendations in Regulatory Guide 8.25, NUREG-1400 should not be used in compliance reviews to determine whether the recommendations have been followed. Instead, NUREG-1400 is a technical resource for the licensee to use to obtain technical information when information is wanted. Regulatory Guide 8.25 specifically states that the guide does not apply to activities conducted under 10 CFR Part 50 at reactor facilities, however, NUREG-1400 provides examples of reactor facilities to demonstrate all types of air sampling programs.

Assessing the need for a routine monitoring program in three Nuclear Medicine centers in Chile

“…where A j is the average annual activity of the radionuclide j handled by a worker; e(g) j is the dose coefficient for inhalation of 5 μm aerosols of radionuclide j by a worker (Sv Bq −1 ); f f s is a safety factor as the physical form of the radionuclide manipulated based on its physical and chemical properties; the value used was 0.01, which is reported for nonvolatile powder and liquid material (Hickey et al, 1993); f hs is a handling safety weighing factor based on experience from operations and the presentation of radionuclide j; f ps is a protection safety weighing factor, based on permanent use of protection instruments in the workplace (i.e. gloves, fume hood) and 0.001 is a conversion factor from Sv to mSv.…”

Technical Basis Document for Internal Dosimetry at Sandia National Laboratories Revision 2.

“…(The basis for this value is that experience has shown that worker intakes are unlikely to exceed one-millionth of the material being handled or processed, as discussed in NUREG-1400)." (Hickey 1993) This statement of the NRC is equivalent to saying that air sampling should be considered when workers may have unlikely intakes in any year that exceed 1% of an ALI or 10% of the NRC monitoring reference level of 0.1 ALI. The NRC unlikely intake fraction of 1x10 -6 for loose radioactive material is used to calculate a derived activity level (DAL) for the loose activity that could be processed in any one work day without likely exceeding the DOE monitoring reference level of 40 S-DACh or intake of 0.02 S-ALI for any control year of practice, i.e., 2% of the S-ALI.…”

Corrective Action Decision Document for Corrective Action Unit 168: Area 25 and 26 Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada, Rev. No.: 2 with Errata Sheet

“…• The total activity per railroad car was conservatively calculated as the highest surface contamination value multiplied by the surface area of the railroad car; potential intakes from this total activity per railroad car are determined based on the guidance provided in NUREG-1400, Air Sampling in the Workplace (Hickey et al, 1993). …”