DOE 2000. - Waste Isolation Pilot Plant - U.S. Department of Energy

WIPP RH PSAR DOE/WIPP-03-3174 CHAPTER 5
Onsite receptors are assumed to be located 328 ft (100 m) from the release point. The site boundary P/Q
values are based on the distance from the release point to the WIPP Site boundary (see Figure 5.2.1), and
exclusive use P/Q values are based on the distance from the release point to the Exclusive Use Area
boundary (see Figure 5.2.2). For assessing the consequences of postulated accidental releases from the
Underground exhaust or the WHB, the following conditions are assumed:
1. NRG 1.145 15 , Releases through Vents or Other Building Penetrations release model, regulatory
position 1.3.1
2. Atmospheric Conditions
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WIPP Site three-year averaged meteorological data
A-F stability
3. Dimensions (smallest cross section) of the Filter Building and the WHB:
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Filter Building - 23 ft (7 m high), 88.6 ft (27 m) wide
WHB - 63 ft (19.2 m) high, 157 ft (47.8 m) wide
The GXQ program produced the following atmospheric dispersion coefficients (P/Q) (s/m 3 ); 17
Consequence Methodology
Distance Underground Exhaust WHB Exhaust
328 ft (100 m) 4.50E-03 5.07E-03
Exclusive Use 4.21E-04 4.00E-04
Site Boundary 2.91E-05 2.98E-05
Consequence assessment calculations are determined for the: (1) MEI located at the Exclusive Use Area
boundary and (2) the non-involved worker (328 ft [100 m]) for releases from the WHB vent and the
exhaust shaft vent. Atmospheric transport is the only significant release and exposure pathway during
normal operations and accident conditions during the disposal phase. Based on the site characteristics
information in Chapter 2, surface water and groundwater transport from normal or accidental releases of
radioactive material is not considered likely. Human exposure pathways from the airborne radioactive
material include inhalation, air immersion, ingestion, and ground-shine. Radiological dose consequences
are calculated assuming the inhalation pathway in Committed Effective Dose Equivalent (CEDE) and are
calculated using Equation 5-5.
External (ground-shine and air immersion) and ingestion dose calculations are not performed due to their
minimal contribution to the Total Effective Dose Equivalent (TEDE). Section A.3 in Appendix A of
DOE-STD-3009-94 1 states that the airborne pathway is of primary interest in the non-reactor nuclear
facilities, therefore CEDE will be reported as the dose consequences for each accident evaluated. The
calculated dose in CEDE is then compared to the non-involved worker and MEI radiological risk
evaluation guidelines discussed in Section 5.2.2 (Tables 5.2-4a).
5.2-12 January 22, 2003