A discussion on the methodology for calculating radiological and toxicological consequences for the spent nuclear fuel project at the Hanford Site

Abstract

This report contains technical information used to determine accident consequences for the Spent Nuclear Fuel Project safety documents. It does not determine accident consequences or describe specific accident scenarios, but instead provides generic information used to calculate radiological consequences and toxicological exposures for postulated accident releases. TRADEMARK DISCLAIMER ECN 647503 Revision 2 shows jointpequency tables and wind roses for the IO0 and 200 Areas of the Hanford Site using the average of nine years of data (1983 to 1991)). Revision includes the overall site 95% values for air transport factors. Distances have been revised in each direction to follow the methodgiven in NRCRegulatory Guide 1.145. HNF-SD-SNF-TI-059 REV 2 A DISCUSSION ON THE METHODOLOGY FOR CALCULATING RADIOLOGICAL AND TOXICOLOGICAL CONSEQUENCES FOR THE SPENT NUCLEAR FUEL PROJECT AT THE HANFORD SITE HNF-SD-SNF-TI-059Revision 2Paul D. RittmannMay 1999 TI-059.R2 I-INF-SD-SNF-TI-059 REV 2This page intentionally left blank. 11May 1999 HNF-SD-SNF-TI-059 REV 2 CONTENTS ... 111May 1999 HNF-SD-SNF-TI-059 REV 2 CONTENTS (Continued) HNF-SD-SNF-TI-059 REV 2 LIST OF TABLES HNF-SD-SNF-TI-059 REV 2 A DISCUSSION ON THE METHODOLOGY FOR CALCULATING RADIOLOGICAL AND TOXICOLOGICAL CONSEQUENCES FOR THE SPENT NUCLEAR FUEL PROJECT AT THE HANFORD SITEby Paul D. Rittmann, PhD CHP PURPOSEThis report contains technical support information used to determine accident consequences for the Spent Nuclear Fuel (SNF) Project safety documents. It does not determine accident consequences or describe specific accident scenarios, but instead provides generic information used to calculate radiological doses and air concentrations of toxic chemicals for postulated accident releases from SNF facilities.Both radionuclides and toxic chemicals may be released into the air through postulated accidents and then travel downwind to other onsite workers and offsite to members of the public. Section 2.0 provides the methodology for modeling the air transport of airborne materials. It contains air transport factors that were generated for the locations of the SNF Project facilities in the 200 East Area and in the 100 K Area. Guidance is provided on the appropriate selection and use of these air transport factors for calculating accident consequences.Specific modeling assumptions and methods for radiological emissions are presented in Section 3.0. This section lists radionuclide inventories for high-burnup Mark IV fuel. This inventory is developed into a unit dose for calculating accident consequences (i.e., dose equivalent) from radionuclides released into the air. Calculated radiological doses are evaluated by comparison with guidance from U.S. Department of Energy, Richland Operations Office (DOE-RL). Postulated accidents that lead to doses exceeding the guidelines require mitigation.The method for calculating air concentrations of toxic chemicals is presented in Section 4.0. This section lists chemical inventories for high-burnup Mark IV fuel and a dis...

105-K Basin material design basis feed description for spent nuclear fuel project facilities. Volume 2: Sludge

“…The methodology for evaluating the radiological and toxicological consequences associated with the SNF safety/regulatory assessment design basis feed material is documented in Rittman (1998). Rittman (1998) used the radioisotopic inventories listed in and calculated unit dose factors for the isotopes, based on the isotope activity per gram of uranium and the isotope committed effective-dose equivalent. The unit dose factor indicates the dose to the receptor who inhales one gram of the exposed fuel.…”

Evaluation of KE Basin Sludge Radioisotopics and Volumes in Support of the Sludge Water System Safety Analysis

“…The inhalation dose factors listed in Table 3-28 are from Federal Guidance Report Number 11 (Eckerman, Wolbarst, and Richardson1988). These are the same values used in HNF-SD-SNF-TI-059 Revision 2 (Rittmann 1999) for the Spent Nuclear Fuel Project safety basis documents.…”