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I DEc 12 -ENGINEERING DATA TRANSMITTAL 35%\hbc\ . a \ 2. To: (Receiving Organization) Risk Methodology and P D & ' i h 12-6-59 Signature of EDT Date Originator BD-7400-172-2 (04/94) GEF097 BD- 7400-172-1 (02/89) ..

Prepared for the U.S. Department of Energy Assistant Secretary for Environmental Management Under DOE idaho Operations Office Contract DE-AC07-761D01570 a. Westinghouse Hanford Co. b. Westinghouse Savannah River Co. DISCLAIMER Portions of this document may be illegible in electronic image products. Images are produced from the best available original document.

CENTRAL FILES ( 2 ) t c r \ % OSTI (2)A RELEASE STAMPA-6400-073 (08/94) WEF124

Several user-oriented programs for the Hewlett-Packard HP-41CV are explained. (This hand-held programmable calculator has alphanumeric display prompting that facilitates data input and continuous memory and simplifies field use.) The first program builds, stores, alters, and ages a list of radionuclides. This program only handles single-and double-decay chains. The second program performs convenient conversions for the six nuclides of concern in plutonium handling. The conversions are between mass, activity, and weight percents of the isotopes. The source can be aged and/or neutron generation rates can be computed. The third program is a timekeeping program that improves the process of manually estimating and tracking personnel exposure during high dose rate tasks by replacing the pencil, paper, and stopwatch method. This program requires a time module. The remaining four programs deal with computations of time-integrated air concentrations at various distances from an airborne release. Building wake effects, source depletion by ground deposition, and sector averaging can all be included in the final printout of the "X/Q-Hanford" and "X/Q-Pasquill" programs. The shorter versions of the^e, "H/Q" and "P/Q," coinpute centerline or sector-averaged values and include a subroutine to facilitate dose estimation by entering dose factors and quantities released. The horizontal and vertical dispersion,parameters in the Pasquill-Gifford programs were modeled with simple, two-parameter functions that agreed very well with the usual textbook graphs.

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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...

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