United States Nuclear Regulatory Commission - Protecting People and the Environment

Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities – 2006: Thirty-Ninth Annual Report (NUREG-0713, Volume 28)

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Publication Information

Manuscript Completed: August 2007
Date Published: December 2007

Prepared by
E.D. Dickson
D.E. Lewis
D.A. Hagemeyer*

Division of Fuel, Engineering and Radiological Research
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

*Oak Ridge Associated Universities
210 Badger Road
Oak Ridge, TN 37830

Office of Nuclear Regulatory Research

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Abstract

This report summarizes the occupational exposure data that are maintained in the U.S. Nuclear Regulatory Commission's (NRC's) Radiation Exposure Information and Reporting System (REIRS). The bulk of the information contained in the report was compiled from the 2006 annual reports submitted by five of the seven categories1 of NRC licensees subject to the reporting requirements of 10 CFR 20.2206. The annual reports submitted by these licensees consist of radiation exposure records for each monitored individual. These records are analyzed for trends and presented in this report in terms of collective dose and the distribution of dose among the monitored individuals. Because there are no geologic repositories for high-level waste currently licensed, and no low-level waste disposal facilities in operation, only five categories will be considered in this report.

Annual reports for 2006 were received from a total of 199 NRC licensees, of which 104 were commercial operators of nuclear power reactors. Compilations of the reports submitted by the 199 licensees indicated that 127,074 individuals were monitored, 64,743 of whom received a measurable dose (Table 3.1). The collective dose incurred by these individuals was 12,846 person-rem, which represents a 7% decrease from the 2005 value. The number of workers receiving a measurable dose also decreased, resulting in an average measurable dose of 0.20 rem for 2006. The average measurable dose is defined as the total effective dose equivalent (TEDE) divided by the number of workers receiving a measurable dose.2 The figures for commercial reactors have been adjusted to account for transient reactor workers.

In calendar year 2006, the annual collective dose per reactor for light water reactor (LWR) licensees was 106 person-rem. This represents a 4% decrease from the value reported for 2005 (110). The annual collective dose per reactor for boiling water reactors (BWRs) was 143 person-rem, and, for pressurized water reactors (PWRs), it was 87 person-rem.

Analyses of transient worker data indicate that 27,799 individuals completed work assignments at two or more licensees during the monitoring year. The dose distributions are adjusted each year to account for the duplicate reporting of transient workers by multiple licensees. In 2006, the average measurable dose per worker for all licensees calculated from reported data was 0.15 rem. The corrected dose distribution resulted in an average measurable dose per worker for all licensees of 0.20 rem.

1 Commercial nuclear power reactors; industrial radiographers; fuel processors (including uranium enrichment), fabricators, and reprocessors; manufacturers and distributors of by-product material; independent spent fuel storage installations; facilities for land disposal of low-level waste; and geologic repositories for high-level waste. There are currently no NRC licensees inVolumeved in low-level waste disposal or geologic repositories for high-level waste.

2 The number of workers with measurable dose includes any individual with a dose greater than zero rem and does not include doses reported as "not detectable."

Page Last Reviewed/Updated Tuesday, October 22, 2013