ML20206L946
| ML20206L946 | |
| Person / Time | |
|---|---|
| Issue date: | 07/31/1986 |
| From: | Forstrom J, Dale Goode NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| References | |
| NUREG-CR-3585, NUREG-CR-3585-V02, NUREG-CR-3585-V2, NUDOCS 8608200415 | |
| Download: ML20206L946 (153) | |
Text
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- s Vol. 2 i
De Minimis Waste Impacts Analysis Methodology IMPACTS - BRC User's Guide and Methodology for Radioactive Wastes Below Regulatory Concern Draft Report for Comment l
Prepared by Jonathan M. Forstom, Daniel J. Goode
( U.S. Nuclear Regulatory Ccmmission t
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- l NOTICE Availability of Reference Materials Cited in NRC Publications
{ Most documents cited in NRC publications will be available from one of the following sources:
- 1. The NRC Public Document Room,1717 H Street, N.W.
Washington, DC 20655
- 2. The Superintendent of Documents, U.S. Goverriment Printing Office, Post Office Box 37082, ,
( Washington, DC 20013 7082 -
i
- 3. The National Technical information Service, Springfield, VA 22161
]
Although the listing that follows represents the majority of documents cited in NRC publications, .
i it is not intended to be exhaustive. i Referenced documents available for inspection and copying for a fee from the NRC Public Docu.
! ment Room include NRC correspondence and internal NRC memoranda: NRC Office of Inspection and Enforcement bulletins, circulars, information notices, inspection and investigation notices; i Licensee Event Reports; vendor reports and correspondence; Commission papers;and applicant and licensee documents and correspondence.
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! Documents available from the National Technical information Service include NUREG series
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i
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{ proceedings are available for purchase from the organization sponsoring the publication cited.
t j Single copies of NRC draf t reports are available free, to the extent of supply, upon written request l
! to the Division of Technical Information and Document Control, U.S. Nuclear Regulatory Com-i mission, Washington, DC 20555. i Copies of industry codes and standards used in a substantive manner in the NRC regulatory process I j are maintained at the NRC Library, 7920 Norfolk Avenue, Bethesda, Maryland, and are available J there for reference use by the public. Codes and standards are usually copyrighted and may be
- purchased from the originating organization or, if they are American National Standards, from the American National Standards institute,1430 Broadway, New York, NY 10018.
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NUREG/CR-3585 Vol. 2 De Minimis Waste Impacts Analysis Methodology IMPACTS - BRC User's Guide and Mr,thodology for Radioactive Wastes Below Regulatory Concern Draft Report for Comment
, Manuscript Completed: July 1986 Data Published: July 1986 Prrpired by Jon than M. Forstom, Daniel J. Goode J
Divisi:n of Waste Management Offics of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555
,p""%
i ei NOTICE f
! Although this report has been authored by
( the NRC staff, NRC has retained the contractor report number of the first report to facilitate categorization and retrieval of this documentation.
I 1
i
ABSTRACT This report describes the methodology and computer program used by NRC to evaluate radiological impacts associated with petitions to have specific slightly contaminated radioactive waste streams designated as "below regulatory concern." These wastes could be treated and disposed of at facilities which are not licensed for low-level radioactive waste management.
The IMPACTS-BRC computer program is implemented on IBM-PC microcomputers using the FORTRAN programming language. Radiological impacts (doses) are estimated for several pathways including direct gamma radiation exposure, worker inhala-I tion and exposure, offsite atmospheric and water releases, and intruder exposures.
Annual impacts are calculated for the maximum individual, critical groups, and general population. The treatment and disposal options include onsite incinera-tion, incineration at municipal and hazardous waste facilities, and disposa! at sanitary landfills and hazardous waste landfills. Modifications to the program (from Volume 1) are primarily for microcomputer compatibility and to provide information needed to evaluate the petitions.
Default environmental and facility parameters are developed representing conservative assumptions about site selection and operational procedures. In particular, the parameters of the groundwater pathway model are modified to represent more conservative assumptions than the original model (Volume 1).
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! i TABLE OF CONTENTS
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ABSTRACT ............................................................. iii 1 INTRODUCTION AND
SUMMARY
........................................ 1 1.1 Purpose .................................................... I
- 1. 2 Scope ...................................................... 1 1.3 Summary .................................................... 1 PART I - IMPACTS-BRC USER'S GUIDE .................................... 3 2 OVERVIEW ........................................................ 3 2.1 Computer Requirements ...................................... 3 2.2 Input ...................................................... 3 2.3 Output ............................. ....................... 3 3 DESCRIPTION OF INPUT DECKS AND MODIFICATION PROCEDURES .......... 5 3.1 TAPES ...................................................... 5 3.2 TAPE 2.DAT .................................................. 6 3.3 TAPE 1.DAT .................................................. 6 4 DESCRIPTION OF OUTPUT DECKS ..................................... 31 4.1 TAPE 6.0VT .................................................. 31 4.2 TAPE 10.0VT ................................................. 31 5 IMPLEMENTATION OF IMPACTS-BRC ................................... 33 5.1 Description of Supplied Computer Disk ...................... 33 5.2 Backup and Working Copies .................................. 33 5.3 Execution of the Example Problems .......................... 34 5.4 Program Verification ....................................... 34 5.5 Flow Chart for Implementation .............................. 34 6 EXAMPLE PROBLEMS ................................................ 37 6.1 Reactor Resins to Hazardous Waste Landfill ................. 37 6.2 Trash and Soil to Municipal Incinerator and Sanitary Landfill ................................................... 39 6.3 Waste Oil to Onsite Incinerator and Sanitary Landfill ...... 42 v
( _ - -_ _ _ _ - - -
TABLE OF CONTENTS (Continued)
Page PART II - MODIFICATIONS TO DE MINIMIS METHODOLOGY FOR BRC . . . . . . . . . . . . 45 7 MODIFICATIONS FOR IBM-PC COMPATIBILITY .......................... 45 7.1 I/O Modifications ......................................... 45 7.2 Compiler Metacommands ...................................... 45 8 CALCU LATIONAL MODIFICATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47 8.1 Deletion of Groundwater Dispersion Calculation ............. 47 8.2 Nuclide-Specific Accounting ................................ 47 8.3 Changes in Facility Types (IQ) ............................. 47 9 MODIFICATIONS TO INPUT DECKS .................................... 49 9.1 Environmental Parameters for Maximum Individual Impacts .... 49 9.2 Groundwater Travel Times ................................... 49
- 9. 3 Retardation Coefficients ................................... 51 9.4 Contact Time Fraction ...................................... 51 9.5 Peclet Numbers ............................................. 53 10 REFERENCES AND BIBLIOGRAPHY ..................................... 55 APPENDICES A. IMPACTS-BRC FORTRAN Source Code Listing B. TAPE 1.DAT - Nuclide-Specific Data C. TAPE 2.DAT - Environmental and Facility Parameters D. Example TAPE 5 - Options and Waste Stream Characteristics E. Example TAPE 6.0UT - Total Waste Stream Doses for all Pathways F. Example TAPE 10 - ICRP Doses by Nuclide G. Installation Procedures vi
TABLE OF CONTENTS (Continued)
LIST OF FIGURES Figure P_ age 1 Structure of TAPE 5 .............................................. 11 2 Structure of TAPE 2.DAT .......................................... 22 3 Structure of TAPE 1.DAT .......................................... 29 LIST OF TABLES Table 1 Data Input Format for Card Type 1, TAPE 5 ........................ 7 2 Data Input Format for Card Type 2, TAPES ........................ 8 3 Data Input Format for Card Type 3, TAPES ........................ 9 4 Data Input Format for Card Type 4, TAPE 5 ........................ 10 5 Data Input Format for Card Type 1, TAPE 2.DAT .................... 12 6 Data Input Format for Card Type 2, TAPE 2.DAT .................... 13 7 Data Input Format for Card Type 3, TAPE 2.DAT .................... 14 8 Data Input Format for Card Type 4, TAPE 2.DAT .................... 15 9 Data Input Format for Card Type 5, TAPE 2.DAT .................... 16 10 Data Input Format for Card Type 6, TAPE 2.DAT .................... 17 11 Data Input Format for Card Type 7, TAPE 2.DAT .................... 18 12 Data Input Format for Card Type 8, TAPE 2. DAT . . . . . . . . . . . . . . . . . . . . 19 13 Data Input Format for Card Type 9, TAPE 2.DAT . . . . . . . . . . . . . . . . . . . . 20 14 Data Input Format for Card Type 10, TAPE 2.DAT ................... 21 15 Radionuclides considered by Impacts-BRC ......................... 23 16 Elemental Solubility Classes Considered by Impacts-BRC .......... 24 17 Data Input Format for Card Type 1, TAPE 1.DAT .................... 26 18 Data Input Format for Card Types 2, 3, 5, TAPE 1.DAT ............. 27 19 Data Input Format for Card Type 4, TAPE 1.DAT .................... 28 20 Definition of TAPE 6.00T Abbreviations . . . . . . . . . . . . . . . . . . . . . . . . . . . 32 21 Summary of Radiological Doses for Reactor Resins to Hazardous Waste Landfill Example .......................................... 38 22 Summary of Radiological Doses for Thrash and Soil to Municipal Incinerator and Sanitary Landfill--Impacts-BRC Example . . . . . . . . . . 40 23 Summary of Radiological Doses for Thrash and Soil to Municipal Incinerator and Open Dump--De Minimis Example ................... 41 24 Summary of ICRP Doses for Waste Oil to Onsite Incinerator and Sanitary Landfill Example ....................................... 43 25 Treatment and Disposal Facility Types ........................... 48 25 Environmental Parameters used for the Maximum Individual ........ 50
- 27 Groundwater Travel Times ........................................ 50 28 Minimum Retardation Coefficients for Selected Elements .......... 52 vii
1 INTRODUCTION AND SUMARY 1.1 Purpose l The purpose of this report is to document the Nuclear Regulatory Commission's technical capability to perform radiological assessments for the evaluation of petitions to have specific radioactive waste streams designated as below regulatory concern (BRC). Section 10 of the Low-Level Radioactive Waste Policy Amendments Act of 1985 mandated the NRC to develop this technical capability.
In compliance with this mandate, a computer program, IMPACTS-BRC, was developed j
from prior NRC technology. This program calculates impacts (radiological doses) resulting from disposal of very low-level waste, using a variety of non-licensed treatment and disposal options.
This report also serves to provide potential petitioners with the means to evaluate their proposed activities by the same methods the NRC will use in considering their petitions. These evaluations are required of petitioners if the NRC is to respond expeditiously to their petitions. Petitioners are also being asked to provide the NRC with the input data needed to properly execute IMPACTS-BRC in order for the NRC to act expeditiously.
- 1. 2 Scope The IMPACTS-BRC methodology is a modification of the technology developed by NRC contractor Dames & Moore, reported by 0.I. Oztunali and G.W. Roles in Volume 1 of NUREG/CR-3585, "De Minimis Waste Impacts Analysis Methodology."
Most of the technical assumptions and calculational methodology have remained the same. The aim of this report (Volume 2) is to describe only the changes
, made to the De Minimis methodology and to provide a user guide for IMPACTS-BRC.
Information regarding the assumptions, techniques, and calculational method-ologies which remain unchanged can be obtained from Volume 1. This report corresponds to Version 1.0 of IMPACTS-BRC.
1.3 Summary This report is divided into two parts. Part I is the user's guide to operation of IMPACTS-BRC, Version 1.0. It provides an overview of the program, defines l input, options, and output, and describes program implementation. It includes example problems to help familiarize the user with the program and to verify proper execution.
The FORTRAN source code and an executable module of IMPACTS-BRC, along with the default BRC input decks and data for the example problems, are supplied on a 5k inch floppy computer diskette. This diskette is available from the National Energy Software Center (NESC), Argonne National Laboratory, 9700 South Cass Ave.,
! Argonne, Illinois 60439. The contents and use of this diskette is also described in Part I.
1 Part II of this report (Volume 2) describes the differences between IMPACTS-BRC and the computer code published in Volume 1. It also describes differences in the procedures and assumptions, including default input data, between the De Minimis methodology (Volume 1) and the BRC methodology.
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The computer program published in Volume 1 was programmed in FORTRAN for a mainframe computer, specifically a VAX 11/780. Several changes in IMPACTS-BRC were required to implement it on an IBM-PC microcomputer. These changes involved input / output procedures and use of certain compiler commands to optimize storage. No attempt was made to optimize overall performance of the program on the IBM-PC, and it is clear that a thorough re programming, with the IBM-PC application in mind, would improve operation.
Several other changes have been made in developing IMPACTS-BRC which were not required for compatibility. Groundwater dispersion has been dropped from the model of groundwater transport because the long-term health impacts are not sensitive to this parameter, and because the computational effort was high for this term. Nuclide-specific accounting has been added in a new output file.
The facility types have been modified to correspond to options likely to be considered under NRC's BRC policy.
The default environmental and facility data have been modified from the example presented in the De Minimis NUREG/CR-3585, Volume 1. The changes are more conservative and result in higher calculated impacts. Most of the data changes have been in parameters of the groundwater pathway. A non-default environmental dataset has been developed for use in estimating maximum individual exposures.
The three regional site environmental datasets are used to estimate critical group and cumulative population impacts.
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PART I - IMPACTS-BRC USER'S GUIDE 2 OVERVIEW IMPACTS-BRC is a computer program which calculates the impacts (radiological doses) from the handling, recycling, incineration, and/or disposal of very low-level radioactive waste at facilities which are not licensed for low-level radioactive waste management. The program includes a number of regional location, disposal facility, and waste treatment options. Pathways for which j the impacts are calculated include transportation, operations, air and water i transport to offsite receptors, and intrusion into disposed waste. These ,
calculated impacts are used to support NRC rulemaking on petitions to designate {
specific waste streams as below regulatory concern which would allow their i treatment and disposal at facilities that are not licensed for low-level radioactive waste management.
IMPACTS-BRC is intended to be a " dynamic" program, in that it can be easily adapted to very specific situations from the generic form in which it is supplied.
Because generic facility, environmental, and radionuclide data are supplied with the program, the user may estimate radiological impacts simply by choosing the desired treatment and disposal options and supplying the characteristics of the waste stream. Or, the user may make the program as situation-specific as desired, simply by changing any or all of the generic data to reflect a specific set of circumstances.
2.1 Computer Requirements IMPACTS-BRC is written in IBM-PC FORTRAN Version 2.00 and runs on 640K IBM-PC and compatible computers. The program has been run under IBM-DOS Version 2.10 and should be fully upward compatible. An 8087 math co processing chip is a useful option, but is not required for program operation. A harddisk system also provides certain operational advantages, but is not required. The program runs in a batch mode using three input data files and generating two output data files. Because portions of the output are printed on 128 character lines, a printer with the capacity to handle lines of this width is also needed.
2.2 Input The first input file, TAPE 1.DAT, contains nuclide specific data for each of 85 radionuclides. Generally, this file will not require user editing, except under the most specific of circumstances. The second input file, TAPE 2.DAT, contains data on the reference environments and facilities used by IMPACTS-BRC.
This file may require user editing for certain situations. The third input file, TAPES, contains data for the waste stream and chosen treatment and disposal options. This file must be edited or created by the user for the specific waste stream (s) and facilities to be considered.
2.3 Output The first output file, TAPE 6.0VT, contains the calculated doses for each pathway for the entire waste stream, indicating the doses from all radionuclides combined.
The second output file, TAPE 10.0VT, contains ICRP doses for most pathways for each individual nuclide in the waste stream, indicating their relative contributions to the total dose.
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l 3 DESCRIPTION OF INPUT DECKS AND MODIFICATION PROCEDURES IMPACTS-BRC uses three input files, described here in the order in which they may require user modification. Data within these files can be changed or added to, or entirely new files created, using a file editing program such as EDLIN, supplied with IBM-DOS. When creating or editing any of these files, it should be noted that data must be right justified within the data fields.
Tables are used to describe the contents of each of the input files, on a card by card basis. In this report, the term " card" refers to a line in the input file, corresponding to a physical computer card. For each card type within a i
file, these tables provide the following:
(1) the input format for the required data, (2) a schematic illustration of the locations for each variable, (3) a list and description of the input variables.
Following the card type tables for each input deck is a figure illustrating the
- sequence of card types within that deck.
3.1 TAPE 5 This input file contains the characteristics of the waste stream and the options under which its impacts are to be calculated. It must be created by the user for the specific waste stream (s) and treatment / disposal options to be considered.
Two variables within TAPE 5 require explanation beyond that contained in the card type tables. On Card Type 1, if the user specifies the data index (IDAT) as 1 or 3, a number of non-default facility parameters must be added to TAPE 2.DAT by the user for the program to operate. The non-default site environment parameters, required when IDAT is specified as 2 or 3, have been provided in TAPE 2.DAT on the supplied diskette. For the BRC methodology, these parameters correspond to a conservative site used to estimate maximum individual exposures.
On Card Type 3, the sorting options for the processing index (IP = 3, 4, or 5) should only be used when the disposal facility is a sanitary landfill (IQ = 2 on Card Type 1). These " sorting options" allow the consideration of three waste treatment processes that might take place at a municipal incinerator:
o Sorting Option 1 - The waste is reduced in size (by such equipment as hammermills), incinerated, and the residue buried at the landfill, o Sorting Option 2 - The waste is reduced in size, separated into combustible and non-combustible fractions, the combustible fraction is incinerated, and the residue and non-combustible fraction are buried at the landfill.
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o Sorting Option 3 - The waste is reduced in size, separated into combustible and non-combustible fractions, and the combustible fraction is incinerated. Recyclable materials (metal and glass) are recovered from the non combustible fraction and recycled. Incinera-tion residue and non recyclable materials are buried at the landfill.
Tables 1 through 4 describe the four card types used in TAPE 5, and Figure 1 depicts the sequential structure of the file. Appendix D contains a hardcopy of the TAPE 5 (EXAMPLES.DAT) that appears on the supplied diskette. This is the data used for the example problems, which are discussed in Section 6.
3.2 TAPE 2.DAT This input file contains data on the reference environments and facilities used by IMPACTS-BRC. It requires editing when the user opts to supply site-specific facility data for use in the impact calculations (IDAT = 1 or 3 in TAPE 5). In this case, the user must insert the site-specific facility data into the file, according to Card Types 8 and 9.
l Portions of the generic BRC data in TAPE 2.DAT are different from that used in the De Minimis methodology. These changes were made to increase the conservatism of IMPACTS-BRC (see Part II). The user is encouraged to alter the generic data supplied in TAPE 2.DAT according to data obtained for the specific situation to be modeled. If such changes are used in the preparation of a petition for BRC rulemaking, they should be documented and justified within the petition.
Tables 5 through 14 describe the ten card types used in TAPE 2.DAT. Figure 2 shows the sequential structure of the file, including where Card Types 8 and 9 would be inserted. Appendix C contains a hardcopy of TAPE 2.DAT as it appears on the supplied diskette.
3.3 TAPE 1.DAT This input file contains nuclide specific data for the 85 radionuclides recognized by IMPACTS-BRC, which are listed in Table 15. This file.does not require any editing. However, the user may elect to change the provided data
! (such as the retardation coefficients) in order to reflect a specific set of circumstances. Inform 1 tion for other nuclides, not currently included, could alternatively be input in this file. These changes should be documented and justified if they are used in the preparation of a petition for BRC rulemaking.
Tables 17 through 19 describe the five card types used within TAPE 1.DAT, and Figure 3 illustrates the sequential structure of the file. A hardcopy of TAPE 1.DAT as it appears on the supplied diskette is contained in Appendix B.
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l TABLE 1 t.
DATA INPUT FORMAT FOR CARD TYPE 1, TAPES Card Type 1 Format (813)
IR IDAT IQ NSTRD IPOP ILFE IINS 10FL 1 3 6 9 12 15 18 21 24 Index Columns Variable Parameter Values Description 1-3 IR Region index 1 Humid, low permeable soil (Northeast) 2 Humid, moderately penneable soil (Southeast) 3 Semi-arid (Southwest) 4-6 IPAT Data index 0 Use default parameters for chosen region 1 Use non-default facility parameters *
? Use non-default environment parameters **
3 Use both I and 2 7-9 10 Disposal facility 1 Onsite incinerator / sanitary landfill index 2 Municipal incinerator / sanitary landfill 3 Onsite incinerator / hazardous waste landfill !!
4 Ha:ardcas waste incinerator / landfill I 5 Hazardous waste incireretor/ landfill II (more conservative) 10 - 12 NSTRO Number of waste Number of waste streams to be modeled streams under the same disposal options (Card Type 1) 13 - 15 IPOP Facility envircnment 1 Rural environment index 2 Urban environment (forpopulationexposurecalculations) 16 - 18 ILFE Dispesal facility Length of time that the disposal facility life is cperational (yrs) 19 - 21 IINS Institutier.al control Length of time between closure of the facility period and loss of active institutional control (yrs) 22 - 24 10FL Overflow index 0 No leachate overflow impacts calculated 1 Impacts of leachate overflow are calculated
- User must provide, see Card Types C and 9 in TAPE 2.DAT.
Provided for the maximum individual site, see Card Type 10 in TAPE 2.DAT.
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i TABLE 2 DATA INPUT FORMAT FOR CARD TYPE 2, TAPE 5 Card Type 2 l Format (A10,3E10.3)
BASN BAS (1,1) BAS (1,2) BAS (1,3) 1 10 20 30 40 Columns Variable Description 1 - 10 BASN Waste stream name (up to 10 characters) 11 - 20 BAS (1,1) Totalmassofthewastestream[metrictons(MT=2.2 tons)]
21 - 30 BAS (1,2) Densityofthewastestream(MT/m3 or g/cm3) 3 31 - 40 BAS (1,3) Volume of the waste stream (m )
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TABLE 3 OATA INPUT FORMAT FOR CARD TYPE 3, TAPES Card Type 3 Format (515,10X,815) 10 IA IKI IK2 IP IX1 IX2 IX3 IX4 ICI IC2 IC3 IC4 1 5 10 15 20 25 35 40 45 50 55 60 65 70 75 Index Columns Variable Parameter Values Description 1-5 10 Dispersability 0 Near zero - waste is solidified in vinyl ester styrene, etc.
index 1 Slight to moderate - waste is solidified in cement 2 Moderate - trash, dewatered resins 3 Severe - dewatered sludge, ash, dirt, powders 6 - 10 IA Accessability 1 Ordinary waste index 2 Activated metals 11 - 15 IKI First packaging 0 Not packaged index 1 Metal contairers 2 Other containers 16 - 20 IK2 Second packaging 0-100 Percent of metal packages recycled - used index when IKI = 1 21 - 25 IP Processing 1 Disposal index 2 Incineration and disposal 3 Sorting option 1 4 Sorting option 2 - Use only if IQ = 2 5 Sorting option 3 26 - 35 blank 36 - 40 !X1 Distribution index 1 Number of shipping vehicles 41 - 45 IX2 Distribution index 2 0-100 Percent of vehicle load which is de minimis waste 46 - 50 IX3 Distribution index 3 Number of processing facilities 51 - 55 IX4 Distribution index 4 Number of disposal facilities s 56 - 60 IC1 Compositien index 1 0-100 Weight percent of combustible component of waste 61 - 65 IC2 Composition index 2 0-100 Weight percent of metal component of waste 66 - 70 IC3 Composition index 3 0-100 Weight percent of glass component of waste 71 - 75 IC4 Cemposition index 4 0-100 Weight percent of other components of weste Note: All of the variables on Card Type 3 are stored in array !$PC(1, .1), J = 1 - 5, 8 - 15.
Composition indices are only used when a sorting option is specified (!P > 2).
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TABLE 4 DATA INPUT FORMAT FOR CARD TYPE 4, TAPE 5 Card Type 4 Format (5(A6.IX,A1,E10.3,2X))
l NUCD S COND Same fer 2rd nuclide Same for 3rd nuclide Same for 4th nuclide Same for 5th nuclide j 1 678 18 20 40 60 80 100 Columns Variable Description i 1-6 NUCD(1) Nuclide name (must be from Table 15) !
7 blank 8 5= SOLD (1) Solubility class *, D. W or Y 9 - 18 COND(1) Nuclidecorcentration(mci /g) 19 - 20 blank 21 - 40 Repeat above for second nuclide: NUCD(2),etc.
41 - 60 for third nuclide 61 - 80 for fourth nuclide 81 -100 for fifth ruclide Note: Card Type 4 is repeated as many times as necessary tn irput all radionuclides present in the waste stream. The last nuclide field read must be blank. If the last radionuclide input is at the end of a fire, a blank line must follow.
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Card ly.P_e 1 Disposal options.
2 -
3 -
4 -
,_ Multiple waste streams (up to NSTRD) to be modeled 2 -
under the same disposal options.
3 -
4 -
1 2
f _ Any number of additional disposal options which may also have multiple waste streams.
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Figure 1. Structure of TAPE 5 11
TABLE 5 DATA INPUT FORMAT FOR CARD TYPE 1, TAPE 2.DAT Card Type 1 Format (10E10.3)
PRC TSC DTTM TTM(1) TTM(2) TTM(3) DTPC TPC(1) TPC(2) TPC(3) 1 10 20 30 40 50 60 70 80 90 100 Columns Variable Description 1 - 10 PRC(IR,!Q) Annual potential infiltration into the disposal cells (m/vr) 11 - 20 TSC(IR,10) Contact time fraction between waste and percolation (dimensionless) 21 - 30 DTTM(IR,10) Incremental groundwater travel time between sectors of the facility (yrs) 31 - 40 TTM(!R,1,IQ) Intruder well TTMf!R,2,!Q) Population well Groundwater travel times from the facility 41 - 50 -
toeachreceptor(yrs) 51 - f0 TTH(IR,3,IQ) Surface water 61 - 70 DTPC(IR,IQ) Incremental Peclet number
- between sectors o# the facility (dimensionless) 71 - 80 TPC(IR,1,IQ) Intruder well 81 - 90 TPC(IR,2,IQ) Population well -
Feelet rurbers* from the facility toeachreceptor(dimensionless) 91 -100 TPC(IR,3.IQ) Surface water Note: IR is the region index, 1 - 3, and !Q is the facility index, 1 - 5.
See Figure 2 for the structure of TAPE 2.DAT.
- Peclet numbers are not used by IPPACTS-BRC, but may be re-activated within the code, i
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-s t TABLE 6 DATA' INPUT FORMAT FOR CARD TYPE 2, TAPE 2.DAT l r Card Type 2 l
Format (10E10.3)
FSC FSA QFC(1) QFC(2) QF5(3) POP q POPE POPW l TPOP TD0Z 1 10 20 30 40 50 60 70 20 90 100 Columns Variable Description 1 - 10 FSC(IP) .' oil-to-air transfe'r factor, intruder construction (dimensionless) 11 - 20 FSA(IR) Soil-to-aw' transfer' factor,intruderagriculture(dimensionless) l 21 - 30 QFC(IR,1) Intruder well
- 31 - 40 QFC(IR,2) Population well - Minimum dilution factors for each receptor (m3 /yr) 41 - 5') QFC(IR,3) Surface water 51 - 60 FOP (IR) Population factor for airborne exposed waste, operations / intrusion (person-yr/m3 )
61 - 70 POPE (IP) .PcFu!ation factor for airborne exposed waste, erosion (person-yr/m3) 71 - 80 POPW(IR) Site selection factor for waterborne exposed waste, erosten/ intrusion (yr/m3 )
81 - 90 TPOP(IR) Population density around transportation route (persons /rai2 )
- 91 -100 TDOZ(IR) l Distarce populationdependent dose factor exposure calculations (mifor tg/ft )ansgortation Note: IR is the region index, 1 - 3. !
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4
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d k
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t TABLE 7 DATA INPUT FORMAT FOR CARD TYPE 3, TAPE 2.DAT l
l I Card Type 3
- Format (10E10.3) 1 WYEL AXOQ EFAC EERO EREC ,
1 10 20 30 40 50 Columns Variable Description 1 - 10 WVEL(IP) Averagewindspeedatthesite(m/sec) 11 - 20 AXCC(!R) Accident atmospheric dispersion factor (yr/m3 ) ,
21 - 30 EFAC(IR) Dust mobil 17ation rate for hazardous waste facility operations (g/m -sec) 31 - 40 EER0(IR) Dust mobilization rate for erosion exposed waste (g/m2 ,3,c) 41 - 50 EREC(IR) Dust mobilization rate for intruder exposed waste (g/m -sec)
Note: IR is the region index, 1 - 3.
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1ABLE 8 DATA INPUT FORMAT FOR Cl$RD TYPE 4 TAPE 2.DAT i
Card Type 4 Fomat (IS)
NRET 1 5 Index 4
Columns Variable Values Description f 1-5 NRET(IR) 1-5 Retardation index for soils in the disposal site vicinity -
values corresponding to 1 and 4 are input from TAPE 1 for each nuclide, values corresponding to 2, 3, and 5 are calculated
. internally from 1 and 4 Note: IR is the region index. 1 - 3.
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TABLE 9 DATA INPUT FORMAT FOR CARD TYPE 5, TAPE 2.DAT I
Card Type 5 j 1
Fomat (10E10.3)
TDIS TVEL VINC X0QI EDFI DEN 1 VANN X0QO EDF0 CEN2 1 10 20 30 40 50 60 70 80 90 100 Columns Variable Description 1 - 10 TDIS(IQ) Transportation distance to the facility (miles) 11 - 20 TVEL(IQ) Transportation velocity to the facility (mi/hr) 21 - 30 VINC(IQ) Annual volume of non-BRC waste incinerated (m3 /yr) 31 - 40 X0QI(IQ) Offsite atmospheric dispersion, elevated release (yr/m3 ) l 41 - 50 ECFI(IO) Exposure duration factor, incineration (dimensionless) 51 - 60 DEN 1(IQ) Average density of waste during shipment and incineration (g/cm3 )
61 - 70 VANN(IQ) Annual volume of non-BRC waste disposed (m /yr).
71 - 80 1000(10) Offsite atmospheric dispersion, ground level release (yr/m3 )
81 - 90 EDF0(IQ) Exposure duration factor, disposal facility crerations (dimensionless) 91 -100 DEN 2(IQ) Average density of waste during disposal (g/cm )
Note: 10 is the facility index, 1 - 5.
16
TABLE 10 DATA INPUT FORMAT FOR CARD TYPE 6, TAPE 2.DAT Card Type 6 Format (10E10.3)
TWI(2) TWI(3) TWO(3) ADAY(1) ADAY(2) ADAY(3) RMIX TWI(1) TWO(1) TWO(2) 1 10 20 30 40 50 60 70 80 90 100 Columns Variable Description 1 - 10 TWI(!Q 1) Low TWI(IQ,2)
Wastetoairtransferfactors(dustloadinglevels) 11 - 20 Medium -
for incinerator operations (dimensionless) 21 - 30 TWI(IQ,3) High 31 - 40 TWO(IQ,1) Lcw TWO(IQ,2)
Waste to air transfer factors (dust loading levels) 41 - 50 Pedium -
for disposal facility operations (dimensionless) 51 - 60 TWO(IQ,3) Hieb 61 - 70 ADAY(!Q,1) *0ffsite release / offsite release" 71 - 80 ADAY(IQ,2)
- Equipment operators / unpackaged waste ** - Daily exposed area from each in )
81 - 90 ADAY(IQ,3) *0ther personrel / packaged waste **
91 -100 RMIX(IC) Covermixingefficiency(dimensionless)
Note: IQ is the facility index, 1 - 5.
- Refers to sanitary landfills.
- Refers to hazardous waste landfills, e
17
TABLE 11 DATA INPUT FORMAT'FOR CARD' TYPE 7, TAPE 2.DAT Card Type 7 l
Ferrat (10E10.3)
EMP EFF SEFF GERO OSWR OSDL 1 10 20 30 40 50 60 Columns Variable Description 1 - 10 EMP(IQ) Waste en lacement efficiency (dimensionless) 11 - 20 EFF(IQ) Volumetric disposal efficiency (m 37 ,2) 21 - 30 SEFF(IO) Surface utilization efficiency (dimensionless) 31 - 40 GER0(!Q) Delay time for erosion (yrs) 41 - 50 OSWR(IQ)* Onsite incirerator weight reduction factor (dimensionless, default = 2.0) 51 - 60 OSDL(IQ)* Onsite operational dust loading (g/m3)
Note: IQ is the facility index, 1 - 5.
- If these two varienies are not user specified, default values are used.
l l
l 18
TABLE 12 DATA INPUT FORMAT FOR CARD TYPE 8, TAPE 2.DAT l
Card Type 8 Format (10E10.3)
DSP PDS WSP STB 1 10 20 30 40 Columns Variable Description 1 - 10 DSP(I) Distance to the center of the population ring (m) 11 - 20 PDS(I) Population within the population ring (persons) 21 - 30 WSP(I) Average wind speed for Stability Class A (m/sec) 31 - 40 STB (I) Fraction of the year that wind is in Stability Class A (dimensionless)
Note: Card Type 8 is repeated 6 tiries (I = 1 - 6) to enter data for.6 population rings and Stability j Classes A - F. This card is used when IDAT = 1 or 3. The supplied TAPE 2.DAT does not contain this card.
19
TABLE 13 DATA INPUT FORMAT FOR CARD TYPE 9, TAPE 2.DAT Card Type 9 Format (10E10.3) l 3
PYT! HYTO DISTI DIST0 EDFID EDF0D 3 1 10 20 30 40 50 60 Columns Variable Description 1 - 10 HYTI Incineration release height (m) 11 - 20 HYTO Disposal operations release height (m) 21 - 30 DIST! Distancetooff-siteindividual,incir.eration(m) f 31 - 40 DIST0 Distance to off-site individual, disposal operations (m)
, 41 - 50 EDFID Exposure duration factor, off-site individual, l
incineration (dimensionless) 51 - 60 EDF0D Exposure duration factor, off-site individual, disposal operations (dimensionless)
Note: This card is used when IDAT = 1 or 3. The supplied TAPE 2.DAT dces not contain this card.
20
_ ._. . - _ . - _. , , , _ , -- . _ . ~ . ,
TABLE 14 DATA INPilT FORMAT FOR CARD TYPE 10, TAPE 2.DAT Card Type 10 Format (10E10.3)
FSC FSA 0FC(l) CFC(2) QFC(3) WVEL AX0Q EFAC 1 10 20 30 40 50 60 70 80 Columns Variable Description 1 - 10 FSC Soil-to-air trecsfer factor, intruder construction (dimensionless) 11 - 20 FSA Soil-to-air transfer factor, intruder aoriculture (dimensionless) 21 - 30 QFC(1) Intruder well 31 - 40 0FC(2) Population well - Minimum dilution factors for each receptor (m3 /yr) 41 - 50 0FC(3) Surface water 51 - 60 WVEL Averece wind speed at the site (m/sec) 61 - 70 AX0Q Accident atmospheric dispersion factor (yr/m3 )
71 - 80 EFAC Dust mobilization rate for hazardous waste facility operations (g/m2-sec)
Note: This card is used when IDAT = 2 or 3. The supplied TAPE 2.DAT contains these data for calculatino irracts to the maximum individual, 21
Card IXP.e 1 - IQ1 1 - IQ2 1 - IQ3 1
2
[ ff --
Northeast site (IR = 1) 3 4
1 - IQ1 !
1 - IQ2 l 1 - IQ3 1 - ff 2
Southeast site (IR = 2) 3 4
1 - IQ1 1 -
IQ2 1 -
IQ3 1
[ --
Southwest site (IR = 3) 2 3
4 5
6 -- IQ1 Onsite incinerator / sanitary landfill 7
5 6 --
IQ2 Municipal incinerator / sanitary landfill 7
5 6 --
IQ3 Onsite incinerator / hazardous waste landfill II 7
5 6 -- IQ4 Hazardous waste incinerator / landfill I 7
5 6 --
IQ5 Hazardous waste incinerator / landfill II 7
<*-- Card Types 8 and 9 must be inserted here if IDAT = 1 or 3.
10 --
Non-default environmental parameters, 4 used when IDAT = 2 or 3.
Figure 2. Structure of TAPE 2.DAT.
22
TABLE 15 RADIONUCLIDES CONSIDERED BY IMPACTS-BRC Default Half-life Default Half-life Default Half-life Isotope Sol. (years) Isotope Sol. (years) Isotope Sol. (years) l t
- H-3 12.3 Tc-99m W 6.91E-4 AC-227 Y 21.6 ,
i C-14 5.730 Ru-103 Y 1.08E-1 Th-228 Y 1.19
! Na-22 D 2.62 Ru-106 Y 1.01 Th-229 Y 7,340 P-32 W 3.91E-2 Ag-108m Y 5 Th-230 Y 8.0E+4 P-33 W 6.68E-2 Ag-110m Y 6.69E-1 Th-232 Y 1.41E+10 S-35 W 2.41E-1 Cd-109 Y 1.24 Pu-231 Y 3.25E+4 Cl-36 W 3.08E+5 Sn-113 W 3.15E-1 U-232 Y 72 Ca-45 W A.52E-1 Sn-126 W 1.0E+5 U-233 Y 1.62E+5 Sc-46 Y 2.30E-1 Sb-124 W 1.65W-1 U-234 Y 2.47E+5 Cr-51 Y 7.62E-2 Sb-125 W 2.71 U-235 Y 7.1E+8 i Mn-54 W 8.30E-1 I-125 D 1.65E-1 U-236 Y 2.39E+7 i Fe-55 Y 2.60 I-129 D 1.17E+7 U-238 Y 4.51E+9 Fe-59 Y 1.25E-1 1-131 D 2.21E-2 Np-237 Y 2.14E+6 '
Co-57 Y 7.40E-1 Cs-134 D 2.046. Pu-236 Y 2.85 Co-58 Y 1.95E-1 Cs-135 D 3.0E+6 Pu-238 Y 86.4 Co-60 Y 5.26 Cs-136 D 3.75E-2 Pu-239 Y 2.44E+4 Ni-59 W 8.0E+4 Cs-137 0 30.0 Pu-240 Y 6,580 Ni-63 W 92 Ba-140 W 3.51E-2 Pu-241 Y 13.2 Zn-65 Y 6.71E-1 La-140 Y 4.59E-3 Pu-242 Y 3.79E+5 Se-75 W 3.30E-1 Ce-141 Y 8.90E-2 Pu-244 Y 7.6E+7 Rb-86 D 5.11E-2 Ce-144 Y 7.78E-1 Am-241 Y 458
- Sr-85 Y 1.75E-1 Eu-152 W 12.7 Am-243 Y 7,950 Sr-89 Y 1.44E-1 Eu-154 W 16 Cm-242 Y 4.45E-1 '
Sr-90 Y 28.1 Yb-169 Y 8.71E-2 Cm-244 Y 17.6
, Zr-95 Y 1.79E-1 Pb-210 W 20.4 Cm-243 Y 32 Nb-94 Y 2.0E+4 Po-210 W 3.79E-1 Cm-248 Y 4.75E+5 Nb-95 Y 9.59E-2 Rn-222
- 1.05E-2 Cf-252 Y 2.646 :
Mo-99 Y 7.61E-3 Ra-228 W 6.7 Tc-99 W ,2.12E+5 Ra-226 W 1,602 f
Sol. = solubility class
= no solubility class D = days W = weeks Y = years
- Element solubility classes are listed in Table 16.
i i
23
{
I TABLE 16 ELEMENTAL SOLUBILITY CLASSES CONSIDERED BY IMPACTS-BRC Solubility Element Class Compounds H
- All compounds C
- All compounds Na D All compounds P W Some phosphates D Most phosphorous compounds S W Elemental sulphur D Information not provided C1 W Information not provided D Information not provided Ca W All compounds Sc Y Information not provided Cr Y 0xides and hydroxides D All other compounds Mn W 0xides, hydroxides, halides and nitrates D All other compounds Fe W 0xides, hydroxides and halides D All other compounds Co Y 0xides, hydroxides, halides and nitrates W All other compounds Ni W 0xides, hydroxides, halides, nitrates, and carbides D All other compounds
. Zn Y 0xides, hydroxides, phosphates and nitrates W Halides and sulphides '
D Sulphates :'
Se W Elemental selenium, oxides, and hydroxides ,
D All other compounds Rb D All compounds Sr Y Strontium titanate W All other compounds Zr Y Zirconium carbide W 0xides, hydroxides, halides and nitrates D All other compounds Nb Y 0xides and hydroxides W All other compounds '
Mo Y Molybdenum, sulphide, oxides and hydroxides D All other compounds Tc W 0xides, hydroxides, halides and nitrates 3 D All other compounds i Ru Y 0xides and hydroxides W Halides D All other compounds Cd Y 0xides and hydroxides )
W Sulphides, halides and nitrates D All other compounds 24
r TABLE 16 (Continued)
ELEMENTAL SOLUBILITY CLASSES CONSIDERED BY IMPACTS-BRC Solubility Element Class Compounds Ag Y 0xides.and hydroxides
! W Nitrates and sulphides i
D -Silver metal and all other compounds Sn W Sulphides, oxides, hydroxides, halides, nitrates and stannic compounds D All other. compounds l Sb W 0xides, hydroxides, sulphides, sulphates, i carbonates, nitrates, and halides l D All other compounds I D All compounds Cs D All compounds Ba D All compounds La Y 0xides, hydroxides and flourides W All other compounds Ce Y 0xides, hydroxides and fluorides W All other compounds
- Eu Y 0xides, hydroxides, carbides and fluorides W All other compounds _ _
Yb Y 0xides, hydroxides, carbides and fluorides W All other compounds Pb D All compounds Po W 0xides, hydroxides and nitrates 4 D All other compounds Rn All compounds Ra W All compounds Ac W All compounds Th Y 0xides and hydroxides 1
W All other compounds Pa W All compounds U D Most hexavalent uranium compounds W Most tetravalent uranium compounds Y UO
- Np W Al$andU0compo$n$s Pu Y Plutonium dioxide W All other compounds Am W All compounds 1 Cm W All compounds Cf Y 0xides and hydroxides l W All other compounds 1
- = no solubility class D = days W = weeks
- Y = years
, 25
- - - _ - - , _ . -. . __ _ - - . _ _ - . . _ . . _ . . ~ . . _ _ - - - .
A TABLE 17 DATA INPUT FORMAT FOR CARD TYPE 1, TAPE 1.DAT Card Type 1 Format (A6,IX,11,A1,10E9.2)
NUC JJ S DCF3 FF(1) FF(2) FF(3) FF(4) FF(5) AL FMF RET (1) RET (4) 1 6789 18 27 36 45 54 63 72 81 90 99 Columns Variable Description 1-6 NUC(N) Nuclide name 7 blank 8 JJ(N) Number of solubility classes for the nuclide 9 5 = SOLB(N) Default solubility class for the nuclide 10 - 18 DCF3(N) Ground contamination fundamental dose conversion factor ferem/yr per pC1/m3 ) ;
19 - 27 FF(N. 1) 28 - 36 FF(N. 2) 37 - 45 FF(N,3) - Fundamental dose conversion factors (various units) 46 - 54 FF(N,4) 55 - 63 FF(N,5) 64 - 72 AL(N) Decay constant (yrs ~)
73 - 81 FMF(N) Waste-to-leachate partition ratio (dimensionless) 82 - 90 RET (N 1)
- Retardationccefficients(dimensionless) 91 - 99 RET (N,4)
Note: P is the nuclide irdex, 1 - 25.
I i
1 26
i TABLE 18 DATA INPUT FORMAT FOR CARD TYPES 2, 3, 5, TAPE 1.DAT Card Types 2, 3, 5 Fonnat (9X,10E9.2) l DCFn(1) DCFn(2) DCFn(3) DCFn(4) DCFn(5) DCFn(6) DCFn(7) DCFn(8) DCFn(9) DCFn(10) 1 0 12 27 26 45 54 63 72 81 90 99 Card Columns M Variable Description 1-9 2,3,5 blank 10 - 99 2 DCF4(N,1-10*) Ground surface contanination fundamental 7 dose conversion factors (mrem /yr per pCi/m )
3 DCF5(N,1-10*) Air imersion fundamental dose conversion factors (mrem /yr per pCi/m3 )
5 DCF2(N,1-10*) Inhalation fundamental dose conversien factor (mrem /pCi)
Note: N is the nuclide ir.dex, 1 - 85.
o These indices refer to the following body crgans:
1 - lung 6 - liver 2 - stomach wall 7 - red marrow 3 - large lower intestine wall 8 - bone surface 4 - total body 9 - thyrnid 5 - kidneys 10 - ICRP total body dose 27
i TABLE 19 DATA INPUT FORMAT FOR CARD TYPE 4, TAPE 1.DAT 1
]
Card Type 4 Format (8X,A1,10E9.2)
S DCF1(1) DCF1(2) DCF1(3) DCF1(4) DCF1(5) DCF1(6) DCF1(7) DCF1(8) DCF1(9) DCF1(10) 1 89 18 27 36 45 54 63 72 81 90 99 Columns Variable Description 1-8 blank 9 5 = SOLT(N, JJ) Solubility class 10 - 99 DCF1(N,JJ,1-10*) Ingestion fundamental dose conversion factors (mrem /pC1)
Note: Card Types 4 and 5 are repeated for each solubility class (JJ times) of the radionuclide.
Card Types 1 - 5 are repeated fer each of the 85 (N = 1 - 85) radionuclides.
- For corresponding body organs, refer to Card Types 2, 3, 5.
28
_- _ . .. -.. . . _ _ - .._. - . - . . . . . . . ~ _ .- . _ , . = - _ _
Card Type Nuclide 1
2 3 H-3 (JJ = 1) 4 5
l 1 l
2 3 C-14 4
5 1
2
- 3 NA-22 i
4 5
4 1
! 2 3
4 P-32 (JJ = 2)
E 4
5 1 -
-l 2 3
4 5 CR-51 (JJ = 3)
! 4 5
1 4 5
i i
Figure 3. Structure of TAPE 1.DAT.
29 4
,- , - , , - -- ,- 1- g-n , g ,m--.e- - ,-.,n-+ .,w---- - ,w-n. - - - - . - , , , . , , - _ - , , , - - - - -
4 DESCRIPTION OF OUTPUT DECKS IMPACTS-BRC generates two output files containing results of the impact calculations. The contents of these files are described in the following sections. Appendices E and F contain examples of the output files, which are the results of the example problems discussed in section 6.
4.1 TAPE 6.0UT This output file receives the calculated doses for each pathway for the entire waste stream, indicating the total impacts. When multiple waste streams are modeled under the same disposal options, the impacts of each are presented, followed by their combined impacts.
For each set of disposal options, the facility chosen and a number of selected parameters are listed first. The following abbreviations are used for the parameters:
LIFE - disposal facility life (ILFE)
REGN regional index (IR)
IPOP - facility environment index (IPOP)
OVFL - overflow index (IOFL)
DATA - disposal / treatment environment index (IDAT)
INST - institutional control period (IINS)
NSTR number of waste streams (NSTRD)
Any non generic parameters used in the modeling are listed next, using the same variable names defined for TAPE 2.DAT. For each waste stream modeled under a set of options, the waste stream name, weight, density, and selected parameters are listed. These parameters are listed under the same variable names defined under TAPE 1.DAT, with the exception of the word " PROCESS", which refers to the waste processing index (IP).
Following this information, the calculated radiological impacts for each of the scenarios (SCN) considered are presented. For recycling and transportation scenarios, only total body doses are calculated. For the remaining scenarios, impacts are calculated for nine body organs and the ICRP total body dose.
Table 20 defines the impact scenarios and units of dose measurement that may appear in TAPE 6.0UT. Appendix E contains the TAPE 6.0VT output for the example problems discussed in section 6.
4.2 TAPE 10.0VT This output file receives ICRP doses for most pathways for each individual nuclide in the waste stream. Its purpose is to break down the total doses presented in TAPE 6.0VT by nuclide, so that important nuclides contributing to total dose can be recognized. For some impact scenarios, doses in TAPE 10.0UT are not normalized by the number of facilities, and therefore do not add up to the total doses presented in TAPE 6.0UT. This is indicated on the output from TAPE 10.0VT. Individual nuclide doses can be normalized for these scenarios by the method described under section 6.3. Appendix F contains the TAPE 10.0VT output for the example problems discussed in section 6.
31
TABLE 20 DEFINITION OF TAPE 6.0VT ABBREVIATIONS Impact Scenario Units
- Definition Metal package recycle:
MAXIND a impacts to maximum individual POPULN c population impacts Metal material recycle: ,
MAXIND a impacts to maximum individual l POPULN c population impacts Glass material recycle:
MAXIND a impacts to maximum individual POPULN c population impacts Transportation:
TR-MAX a impacts to maximum transport worker TR-0CC b total impacts to transport workers TR-POP b impacts to population along transport route Intruder:
INT-C0 a intruder-construction scenario impacts INT-AG a intruder-agriculture scenario impacts Exposed waste:
IN-AIR b intruder-initiated airborne impacts ER-AIR b erosion-initiated airborne impacts IN-WAT a intruder-initiated waterborne impacts i ER-WAT a erosion-initiated waterborne impacts Incineration and operation:
IC-POP b population impacts from incineration IC-IND a off-site individual impacts from incineration IC-WOR b total worker impacts at incinerator IC-MWR a maximum worker impacts at incinerator OP-IND a off-site individual impacts from disposal operations
- OP-WOR b total worker impacts at disposal facility OP-MWR a maximum worker impacts at disposal i facility Leachate accumulation:
LA-OPS a operational leachate discharge impacts to individual LA-PVF a leachate overflow impacts to individual LA-AIR b population airborne impacts due to evaporator operations "a = mrem /yr, b = person-mrem /yr, c = person-mrem /30 yrs.
32
5 IMPLEMENTATION OF IMPACTS-BRC 5.1 Description of Supplied Computer Disk A5 inch floppy computer diskette containing IMPACTS-BRC is available from the National Energy Software Center (NESC), Argonne National Laboratory, 9700 South Cass Ave., Argonne, Illinois 60439. A listing of the directory of this disk should appear as follows:
Volume in drive B has no label Directory of B:
l IMPACTSB FOR 14679 7-15-86 2:42p l IMPCOMM FOR 1067 5-20-86 12:17p READ 1 FOR 3691 5-16-86 3:41p READ 2 FOR 9513 6-09-86 7:18a READS FOR 9267 5-16-86 3:47p UPTAKE FOR 5249 6-09-86 7:19a SPLICE FOR 8857 5-16 3:50p RECYCL FOR 11727 6-09-86 7:19a INCIMP FOR 11973 5-16-86 3:58p INTIMP FOR 6232 7-14-86 11:41a EXPWAS FOR 7134 7-14-86 11:42a OPSIMP FOR 13858 7-14-86 2:55p OVRFLO FOR 6068 7-14-86 11:42a GWATER FOR 9102 7-14-86 11:43a DIVVY FOR 10743 5-19-86 12:31p CHNS FOR 4593 5-19-86 11:45a CALI FOR 2953 5-19-86 11:49a CALE FOR 2707 5-19-86 11:47a UTILS FOR 7463 5-19-86 11:51a IMPACTSB EXE 105912 7-15-86 2:49p TAPE 1 DAT 59350 4-25-86 10:51a TAPE 2 DAT 3475 6-12-86 2:36p EXAMPLES DAT 2759 5-19-86 12:03p 23 File (s) 32768 bytes free 5.2 Backup and Working Copies After verifying the contents of the supplied disk, it is suggested that a backup copy be created in case of subsequent damage to the original. It is also necessary to create a working disk containing the operating system (not supplied), the executable program file IMPACTSB.EXE, and data files TAPE 1.DAT, TAPE 2.DAT, and EXAMPLES.DAT (a working subdirectory containing these four files should be created for harddisk systems). These four files must reside on the same disk (subdirectory) for the program to execute. Omitting the FORTRAN files from the working disk leaves storage space for the generated output files and any additior.il TAPE 5 input files. Instructions for creating the backup and working copies are con'ained in Appendix G.
33
5.3 Execution of the Example Problems IMPACTS-BRC can be executed when the working disk (subdirectory) is in the default drive, by entering the command "IMPACTSB, (name of TAPES)" after the system prompt (do not include the quotation marks). Since the TAPES data for the example problems is contained in file EXAMPLES.DAT on the supplied disk, the command "IMPACTSB, EXAMPLES.DAT" entered at the system prompt will start the sample run.
Run time for the example problems should be about 5 minutes (longer if an 8087 math chip is not installed). If the program runs without error, the message
" NORMAL TERMINATION" is displayed, followed by the system prompt. The program should run properly on the supplied data if the preceeding instructions are followed.
After the program run is completed, output files TAPE 6.0VT and TAPE 10.0VT should be printed. This can be done using the PRINT command (with a harddisk or DOS disk), or by engaging the printer with the Ctrl and PrtSc keys, then using the TYPE command. Since portions of the output are printed on 128 character lines, the printer should be set up to handle lines of this width before printing.
5.4 Program Verification The printed output from execution of the example problems should be compared to the listings in Appendices E and F to verify proper program operation. The outputs should be identical.
5.5 Flow Chart for Implementation STEP 1. Construct TAPE 5 This step is required, unless a run is being repeated with no changes. A new TAPE 5 can be created either by editing the existing file (EXAMPLES.DAT) or by building a new file from scratch. This can be done using a file editing program such as EDLIN, supplied with IBM-DOS. If EXAMPLES.DAT is to be edited, it is advisable to save a copy of the original for use in future program verifications. Because the file to be read as TAPE 5 is designated in the run statement, these files can be given a name that reflects the nature of the data they contain, e.g., EXAMPLE 5.DAT, OIL.DAT, TRASH.DAT.
STEP 2. Edit TAPE 2.DAT This step is usually not required. However, if IDAT is set equal to 1 or 3 in TAPES, Card Types 8 and 9 must be included in TAPE 2.DAT. Optionally (this option is encouraged), the default data supplied in TAPE 2.DAT may also be edited to reflect specific circumstances. If TAPE 2.DAT is edited, it is advisable to retain a copy of the original file.
STEP 3. Edit TAPE 1.DAT This step is optional. The user may elect to edit the default radionuclide data, such as decay rates and retardation coefficients, to reflect specific circumstances or to input data for alternative radionuclides. If TAPE 1.DAT is to be edited, it is advisable to retain a copy of the original file.
34
STEP 4. Run IMPACTS-BRC This step is required. Before running the program, any previous versions of TAPE 6.0VT and TAPE 10.00T which need to be saved should be copied to another disk (or renamed in the subdirectory). Otherwise, they will be overwritten during program execution. It is also necessary to have enough space available on the working disk to store the generated output files.
To run the program, the working disk (subdirectory) containing the executable program file (IMPACTSB.EXE) and the data files (TAPE 1.DAT, TAPE 2.DAT, and TAPE 5) must reside in the default drive. The program is executed by entering the command "IMPACTSB, (name of TAPES)" at the system prompt. Run times for the program vary depending upon the number and size of the waste streams being considered, but typically are on the order of five minutes. If the program l
runs without error, the message " NORMAL TERMINATION" is displayed, followed by L the system prompt.
Error messages will be displayed when the program does not run as expected.
These errors are usually associated with incorrect input in TAPES, or incorrect editing of the other two input tapes. If an errce occurs, return to STEP 1 and use the original input files as templates to help detect input format errors.
STEP 5 can also be performed to help diagnose errors.
STEP 5. Print output and input files This step is required to obtain a hardcopy of the program run results. Since portions of the output are printed on 128 character lines, the printer should be set up to handle lines of this width before printing.
Files can be printed using the PRINT command (with harddisk or DOS disk), or by engaging the printer with the Ctrl and PrtScr keys, then using the TYPE command.
Along with the output files, TAPES and any edited versions of TAPE 1.DAT and TAPE 2.DAT should be printed to verify correct input.
35 i
l l
l 6 EXAMPLE PROBLEMS Three example problems have been included in EXAMPLES.DAT on the supplied diskette. These problems are presented to give the user a feel for actual applications of IMPACTS-BRC. The first two examples use the same TAPES input as the example problems given in Volume 1. The third problem was suggested by an actual petition received by NRC in request for BRC rulemaking.
6.1 Reactor Resins to Hazardous Waste Landfill This example involves the disposal of pressurized water reactor secondary coolant system ion exchange resins at hazardous waste landfills. It is assumed that 80 MT of these reactor resins, having an average density of 1 gm/cm3 , are generated annually. This single waste stream (NSTRD=1) is to be disposed of in the Northeast (IR=1), using default environmental parameters (IDAT=0), at conservative performance hazardous waste landfills II (IQ=5). The disposal facilities are assumed to be located in rural areas (IPOP=1), have 20 year operational lifetimes (ILFE=20), and 30 year institutional control periods (IINS=30). Leachate accumulation impacts are calculated (I0FL=1).
The waste stream itself is moderately dispersible (ID=2), contains no activated metals (IA=1), and is packaged in metal containers (IK=1), 50% of which are recycled (IK2=50). The resins are not incinerated prior to disposal (the disposal only option is chosen, IP=1) therefore there are no processing facil-ities (IX3=0). Ten vehicles (IX1=10) shipping only resins (IX2=100) transport the waste to five disposal facilities (IX4=5). The waste is composed entirely of non-combustible material, and contains no metal or glass (IC's=0, 0, 0,100).
The waste stream contains 32 radionuclides, whose concentrations are given in units of pCi/g.
A summary of the results of this example problem are contained in Table 21.
Inpacts for most of the scenarios considered are fairly low. However, a significant individual dose (when compared to a maximum individual guideline of 1 mrem /yr) appears to be associated with waste transportation. The whole body impact to the maximum exposed transportation worker is calculated to be approximately 5 mrem /yr, due entirely to direct (external) gamma radiation.
4 The results of this problem are the same for both the BRC and De Minimis methodologies for most pathways. Leachate accumulation impacts, however, have increased in the BRC results, due to the more conservative contact times (TSC's) used (see Section 9.4). Groundwater impacts are also higher in the BRC results, due to the shorter groundwater travel times and lower retardation coefficients used (see' Sections 9.2 and 9.3). Both of these pathways still have very low impacts.
Care should be taken in comparing groundwater migration and leachate accumulation impacts, since one or the other would probably occur, but not both. If; for example, a disposal facility is located in a humid area having highly impermeable soils, or is equipped with a functional liner, leachate accumulation impacts may be more likely. On the other hand, if a disposal facility is located in a humid area having moderately permeable soils and is not equipped with a liner,
.l groundwater impacts may be more likely. For this problem, both groundwater impacts and leachate accumulation impacts are quite low.
37
TABLE 21
SUMMARY
OF RADIOLOGICAL DOSES FOR REACTOR RESINS TO HAZARDOUS WASTE LANDFILL EXAMPLE Impact Scenarios Units
- IMPACTS-BRC DE MINIMIS ,
Metal Package Recycle:
Maximum individual a 5.7 E-4 5.7 E-4 Population c 4.8 E+1 4.8 E+1 Transportation:
Maximum worker a 4.7 E+0 4.7 E+0 All workers b 9.4 E+1 9.4 E+1 Population along route b 6.4 E+2 6.4 E+2 Intruder:
Construction scenario a 1.2 E-2 1.2 E-2 Agriculture scenario a 2.4 E-2 2.4 E-2 Exposed Waste:
Intruder water a 7.1 E-7 7.1 E-7 Intruder airborne b 1.6 E-4 1.6 E-4 Erosion water a 3.2 E-5 3.2 E-5 Erosion airborne b 3.3 E-2 3.3 E-2 Disposal Facility Operation:
Off-site individual a 4.5 E-12 4.5 E-12 Off-site population b ** **
Maximum worker a 2.8 E-1 2.8 E-1 All workers b 4.8 E+1 4.8 E+1 Leachate Accumulation:
Leachate treatment a 2.6 E-4 6.2 E-7 Overflow a 1.4 E-4 1.2 E-4 Evaporation b 2.9 E-2 1.8 E-2 Ground Water:
Intruder well a 1.7 E-4 9.0 E-9 Population well a 3.4 E-5 1.3 E-9 Surface water a 6.4 E-7 3.5 E-11
- a = mrem /yr, b = person-mrem /yr, c = person-mrem /30 yrs.
- 0ffsite population exposurer are not calculated for packaged waste disposed at hazardous wasta landfills (see Volume 1, p. 5-30).
All doses are for the total body.
38
IMPACTS-BRC calculated doses are the same or higher than those calculated by i DeMinimis. This is a result of the increased conservatism of the IMPACTS-BRC methodology. These changes are discussed more fully in Part II of this report.
6.2 Trash and Soil to Municipal Incinerator and Sanitary Landfill In this example, two waste streams (NSTRD=2) are considered under the same disposal scenario. The two streams, one combustible trash and the other
" contaminated" soil, are to be disposed of in the Southeast (IR=2), using default environmental parameters (IDAT=0), at sanitary landfills (IQ=2). The disposal facilities are assumed to be located in urban areas (IP0P=2), have 20 year operational lifetimes (ILFE=20), and have negligible institutional j control (IINS=0). Leachate accumulation impacts are calculated (IOFL=1).
l The trash waste stream has an average density of 0.5 g/cm3 , and 100 MT/yr are assumed to be generated. The trash is moderately dispersable (ID=2) ordinary waste (IA=1) that is not packaged (IK1=0, IK2=0). The waste is sorted by Option 3 at the incinerator so that recyclable materials may be recovered (IP=5). Thirty-two vehicles, with 10% of their load being this trash, deliver the waste to four incinerators and the residue to 16 landfills (IX's=32,10, 4, 16). The composition of the trash is 50% combustible, 20% metal, 20% glass, and 10% other materials (IC's=50, 20, 20, 10). This waste stream contains 32 radionuclides.
The " contaminated" soil waste stream has an average density of 1.6 g/cma and is assumed to be generated at a rate of 500 MT/yr. It is highly dispersible (ID=3),
composed entirely of dirt (IA=1, IC's=0, 0, 0, 100), and is not packaged (IK1=0,IK2=0). The soil is not incinerated (IP=1, IX3=0). It is transported by three vehicles (IX1=3) carrying only soil (IX2=100) to a single landfill (IX4=1). This waste stream contains 13 radionuclides which naturally occur in soils, with concentrations that are typically found in natural soils. The purpose of using natural radionuclides and concentrations is to test the conservatism of the program.
A summary of the doses calculated for each of these two waste streams and the total impacts are presented in Table 22. These results differ from those reported for a similar problem using De Minimis (Table 23). The differences are due in part to the more conservative assumptions used in IMPACTS-BRC, which affect leachate and groundwater impacts, but are also due to a change in disposal facility (from open dump to sanitary landfill), as open dump is not a disposal option available in IMPACTS-BRC. Population transportation impacts are affected by an increase in the default transportation distance to the sanitary landfill from 10 miles in De Minimis to 100 miles in IMPACTS-BRC.
Significant impacts (when compared to a maximum individual guideline of 1 mrem /yr) from the trash waste stream appear to be associated with glass material recycle and transportation. Maximum individual exposures for these scenarios are approxirately 3 and 1 mrem /yr, respectively. Other scenarios had fairly low impacts.
There are no significant (1 mrem /yr) individual impacts associated with the
" contaminated" soil waste stream, as would be expected from naturally occurring soil. Impacts from both the trash and soil waste streams are low enough that none of the total individual impacts calculated are greater than 1 mrem /yr.
39
TABLE 22
SUMMARY
OF RADIOLOGICAL DOSES FOR TRASH AND S0IL TO MUNICIPAL INCINERATOR AND SANITARY LANDFILL--IMPACTS-BRC EXAMPLE Waste Stream Impact Scenarios Units
- Trash Cont. Soil Total Recycle:
Metal - max. ind. a 3.2 E-1 Metal population c 2.2 E+4 Glass - max. ind. a 3.3 E+0 Glass population c 9.5 E+3 Transportation:
Maximum worker a 1.2 E+0 7.0 E-2 All workers b 7.3 E+1 4.2 E-1 Population along route b 4.8E+( 2.7 E+0 Intruder:
Construction scenario a 4.6 E-2 1.5 E-2 6.1 E-2 Agriculture scenario a 1.3 E-1 1.6 E-1 3.0 E-1 Exposed Waste:
Intruder water a 1.8 E-6 5.8 E-6 7.6 E-6 Intruder airborne b 2.9 E-3 1.6 E-3 4.5 E-3 Erosion water a 3.5 E-6 6.9 E-4 7.0 E-4 Erosion airborne b 1.1 E-3 3.5 E-3 4.6 E-3 Incinerator Operation:
Off-site individual a 8.7 E-5 --
8.7 E-5 Off-site population b 1.2 E+1 --
1.2 E+1 Maximum worker a 3.9 E-1 --
3.9 E-1 All workers b 5.8 E+1 .- 5.8 E+1 Disposal Facility Operation:
Off-site individual a 3.5 E-5 3.0 E-4 3.4 E-4 Off-site population b 3.2 E-2 1.7 E-2 5.0 E-2 Maximum worker a 9.5 E-2 3.0 E-2 1.3 E-1 All workers b 1.5 E+0 3.0 E-2 1.6 E+0 Leachate Accumulation:
Leachate treatment a 1.4 E-5 5.6 E-3 5.6 E-3 Overflow a 1.4 E-5 5.6 E-3 5.6 E-3 Evaporation b 4.0 E-2 9.9 E-3 5.0 E-2 Ground Water:
Intruder well a 1.2 E-4 1.3 E-2 1.3 E-2 Population well a 5.9 E-6 3.1 E-4 3.1 E-4 Surface water a 4.7 E-8 1.8 E-6 1.8 E-6
- a = mrem /yr, b = person mrem /yr, c = person mrem /30 yrs.
All doses are for the total body.
Cont. = contaminated 40
.. . . .- . -- - . - . . -- .=. -. - - - - . .- .. -
l i
1 TABLE 23
SUMMARY
OF RADIOLOGICAL DOSES FOR TRASH AND SOIL l TO MINICIPAL INCINERATOR AND OPEN DUMP--DE MINIMIS EXAMPLE ,
Waste Stream Impact Scenarios Units
- Trash Cont. Soil . Total
~
Recyc1e:
Metal - max. ind.' a 3.2 E-1 Metal population c 2.2 E+4 Glass - max. ind. a 3.3 E+0 Glass population c 9.5 E+3
- Transportation
2 Maximum worker a 1.2 E+0 7.0 E-2 All workers b 7.3 E+1 4.2 E-1 i Population along route b 4.8 E+1 .2.7 E-1 Intruder:
! Construction scenario a 4.7 E-2 1.5 E-2 6.2 E-2 l Agriculture scenario a 2.0 E-1 1.8 E-1 3.8 E-1
) Exposed Waste:
I Intruder water a 2.7 E-6 8.6 E-6 1.1 E-5
! Intruder airborne b 4.4 E-3 2.4 E-3 6.8 E-3 i Erosion water a 1.2 E-5 6.9 E-4 7.1 E-4 i Erosion airborne b 2.8 E-3 3.5 E-3 6.3 E-3 i
. Incinerator Operation:
, Off-site individual a 8.7 E-5 --
8.7 E Off-site population
~
b 1.2 E+1 --
1.2 E+1
! Maximum worker a 3.9 E-1 - - -
3.9 E-1 All workers b 5.8 E+1 --
5.8 E+1 Disposal Facility Operation:
, Off-site individual a 2.0.E-2 1.3 E-1 1.5 E-1
! Off-site population b 5.1 E+1 2.1 E+1 7.3 E+1 Maximum worker a 1.8 E-1 5.6 E-2. 2.4 E-1 All workers b 2.9 E+0 5.6 E-2 3.0 E+0
]
Leachate Accumulation:
Leachate treatment 3.5 E-7 a 1.5 E-4 1.5 E-4 Overflow a 2.7 E-5 1.1 E-2 1.1 E-2 l Evaporation b 7.8 E-2 2.0 E-2 9.8 E-2
, Ground Water:
! Intruder well a 3.6 E-7 1.6 E-4 1.6 E-4
! Population well a 1.0 E-8 8.0 E-6 8.0 E-6
! Surface water a 5.2 E-10 4.7 E-8 4.7 E-8 "a = mrem /yr, b = person-mrem /yr, c = person-ares /30 yrs.
] All doses are for the total body.
1 i
I 41 i
6.3 Waste Oil to Onsite Incinerator and Sanitary Landfill The following example is derived from a petition submitted to the NRC by the Edison Electric Institute and the Utility Nuclear Waste Management Group (EEI This petition is a request to allow waste oil from nuclear I and UNWMG 1985).
power plants to be treated and disposed of at facilities not licensed for LLW treatment or disposal. The results presented below are not necessarily related to the NRC's official finding on this petition; this problem is presented only to demonstrate the functioning of IMPACTS-BRC.
In this example, waste oil from a power plant is incinerated onsite with nonradiological waste, and the ashes are shipped to a sanitary landfill for disposal (IP=2, IQ=1). The petitioner indicates that the waste oil could also be burned in electric power boilers, which is not considered here. Only one waste stream is considered (NSTR=1) and the non-default site characteristics are used to calculate maximum individual exposures (IDAT=2). The region site specifier (IR=1) indicates that other parameters will be taken from the north-east dataset. The disposal facility is assumed to be located in an urban set-ting (IP0P=2) and leachate accumulation impacts are calculated (IOFL=1) for the disposal scenario. The aisposal facility is assumed to operate for 20 years (ILFE=20) and to have a 5 year institutional control period (IINS=5).
The waste stream consists of oil contaminated during operations at nuclear power plants (EEI and UNWMG 1985). Based on information in the petition, the total volume of waste oil generated annually by all reactors in the U.S. is estimated to be 800 m3 . The density is assumed to be 1 gm/cm3 . The waste stream is slightly dispersable (ID=1), and is composed of combustible material con-taining no activated metals (IA=1) nor any contaminated metal or glass (IC's =
100, 0, 0, 0).
The waste oil is burned at 30 onsite incinerators (IX3=30) and transported to a single sanitary landfill (IX4=1), using 30 vehicles (IX1=30) containing only the ash from the onsitt incinerator (IX2=100). Incineration is assumed to result in a volume reduction factor of 100 (OSWR=100.0). The ash is transported to the sanitary landfill in metal drums (IK1=1), half of which are recycled (IK2=50).
Concentrations for the 20 radionuclides in the waste oil are limit concentra-tions from the petition submitted to NRC (EEI and UNWMG, 1985). The petitioner developed the limit for each radionuclide assuming that it was the only radio-nuclide in the waste stream and that the resultant dose wa: 1 mrem /yr. Thus, the dose from a waste stream containing all 20 radionuclides at their limit concentrations is expected to be higher than 1 mrem /yr.
The results of the IMPACTS-BRC run for this example are summarized in Table 24.
Unlike the two examples above, most of the results presented here are for the weighted whole body dose equivalent (ICRP 1978). The recycle and transporta-tion impacts are for the whole body. The complete results are given in Appendices E and F.
Impacts for several pathways are relatively low. Assuming that 50 percent of the metal drums are recycled, maximum individual impacts from the recycle path-way are estimated t.o be less than 1 mrem /yr. The exposed waste impacts are 42
i s l 3 l l
t TABLE 24
SUMMARY
OF ICRP DOSES FOR WASTE OIL TO ONSITE INCINERATOR AND SANITARY LANDFILL EXAMPLE Impact Scenarios Units
- IMPACTS-BRC Metal Packaee Recycle **:
Maximum individual a 9.6 E-1 l Population c 3.8 E+3 l
Transportation **:
Maximum worker a 1.4 E+3 All workers b 8.3 E+4 Population along route b 2.0 E+6
, Intruder:
Construction scenario a 1.1 E+1 Agriculture scenario a 3.5 E+1 Exposed Waste:
Intruder water a 9.4 E-4 Intruder airborne b 2.1 E-1 Erosion water a 1.2 E-5 Erosion airborne b m3.1 E-3 Incinerator Operation:
Off-site individual a 4.4 E+0 Off-site population b 2.2 E+4 Maximum worker a 6.9 E+2 All workers b 5.7 E+5 Disposal Facility Operation:
Off site individual a 9.6 E-2 Off-site population- b 1.6 E+1 tiaximum worker a 4.3 E+3 All workers b 4.3 E+3 Leachate Accumulation:
Leachate treatment a 2.2 E+1 Overflow a 1.5 E+0 Evaporation b 4.7 E+0 Ground Water:
Intruder well a 9.7 E+0 Population well a 6.6 E-1 Surface water a 2.8 E-2
- a = mrem /yr, b = person-mrem /yr, c = person-mrem /30 yrs.
- These doses are for the total body.
All other doses are ICRP effective whole body doses.
43 ,
also very low. The maximum offsite individual exposure from incineration of the waste oil is estimated to be about 4 mrem /yr. Except for the intruder well, groundwater pathway impacts are very low.
The above impacts are calculated assuming all the radionuclide concentrations in the waste oil are at the limit concentration. Expected concentrations were not used for this problem. Using the ratio method proposed by the petitioner, the sum of the ratios of the radionuclide concentration to the limit concentra-tion for that radionuclide, must be less than 1. To determine if these indi-vidual limit concentrations are appropriate, the output from TAPE 10.00T must be used. TAPE 10.0UT contains the ICRP doses for most pathways by radionuclide.
However, due to the program structure of IMPACTS-BRC, some of these doses are not normalized by the number of treatment or disposal facilities. The pathway headings on TAPE 10.0VT indicate which printed doses are not normalized.
To illustrate how the output is interpreted when the input concentrations are separate limit concentrations, the maximum offsite individual exposures from incineration are investigated. The ICRP dose for the entire waste stream incinerated at 30 facilities is 4.41 mrem /yr. The total non-normalized dose for this pathway on TAPE 10.0VT is 132 mrem /yr, or 4.41 mrem /yr multiplied by 30.
The dose for each nuclide on TAPE 10.0VT should be divided by 30 to represent the dose from that radionuclide, assuming the waste is incinerated at 30 different facilities. For this pathway, it is observed that the doses for all but two radionuclides are less than 30 mrem /yr on TAPE 10.0VT, corresponding to 1 mrem /yr for 30 facilities. The impacts for Ru-103 and Ru-106 are 49 mrem /yr and 37 mrem /yr, respectively, corresponding to maximum individual doses from incineration of waste oil of 1.6 mrem /yr and 1.2 mrem /yr, respectively.
If these limit concentrations were used with the petitioner's proposed ratio method to determine waste oil suitable for incineration, based on a 1 mrem /yr impact, only the limits for Ru-103 and Ru-106 require slight reductions. This conclusion is based, of course, on the validity of all other assumptions.
i i
44
. . o.
l l
l PART II - MODIFICATIONS TO DE MINIMIS METHODOLOGY FOR BRC 7 MODIFICATIONS FOR IBM-PC COMPATIBILITY IMPACTS-BRC is implemented in standard subset FORTRAN-77 using the IBM-PC FORTRAN Compiler Version 2.00. The operating systec is IBM-DOS Version 2.10.
The executable module will utilize the 8087 co processor, if present.
7.1 I/O Modifications
- The De Minimis version of IMPACTS specified the values of the NUC array in the l
main program, through a DATA statement. This array contains the names of the 85 nuclides considered by the model. For the current IBM-PC version of IMPACTS-BRC, these values are read in from TAPE 1.DAT along with other nuclide-specific data.
! Changes are in the main program (IMPACTS), and the subroutine which reads in the l nuclide specific data (READ 1). The changes to READ 1 also affect the structure of the TAPE 1.DAT data file. Subroutine READ 1 was originally a part of Subroutine UPTAKE.
Standard subset FORTRAN-77 and IBM-PC FORTRAN do not allow the values of an array which is contained in COMMON to be specified in a DATA statement. Also, ,
I the BLOCK DATA subprogram is not allowed. A previous IBM-PC version (not the ^
i De Minimis version) had specified the arrays below in a BLOCK DATA subprogram.
- A new subroutine, BLOCKD, has been added to IMPACTS-BRC which specifies the values of the following arrays
1 NXUC(85) - indicates nuclides for which daugnter impacts are
- considered ICH(8,10) - nuclide decay chains
~
, LCH(10) - length of decay chains FK(21) - constant parameters for dose conversion factors FRACT(85,3) - fraction of nuclide released to air from incinerator, values for 85 nuclides at 3 types of incinerators *
\
- 7. 2 Compiler Metacommands j IBM-PC FORTRAN supports several compiler "metacommands" which can be used to optimize program performance. The "$ STORAGE:2" metacommand is utilized in
~
! IMPACTS-BRC. Th'is command was not included in the De Minimis version of tne code. This command causes all integer and logical variables to occupy 2 bytes, instead of the default 4 bytes, significantly reducing the storage requirements for large integer arrays. Several of the subroutines in IMPACTS-BRC would not i compile using the IBM-PC FORTRAN compiler without inclusion of this metacommand.
This problem was detected in the second compile step, FOR2. This metacommand ,
has no effect on program calculations as~1ong as the integer absolute values are less than 32767. This metacommand is not a standard FORTRAN statement and
, may cause an error with other compilers. However, the executable module on
! the supplied disk will run regardless of the compiler brand normally used. ;
I A previous IBM-PC version of IMPACTS-BRC used the "$LARGE" metacommmand to optimize storage space. This metacommand is not available in IBM-PC FORTRAN and has been commented out.
)
i f
45
__~_.-.._ _ ___ ._ . _ _-. , . _ _ _ _ _ __
8 CALCULATIONAL MODIFICATIONS 8.1 Deletion of Groundwater Dispersion Calculation The De Minimis version of IMPACTS included longitudinal dispersion in the groundwater transport calculations. This caused a spreading of radionuclide concentrations at the front and tail end of the release pulse. For the assump-tions in IMPACTS-BRC, the release pulse is a square wave which is advected to the receptor locations. Dispersion is not included and there is no spreading of the front or tail end of the pulse. Several tests were run with and without dispersion and, for the example dispersivity values used in the De Minimis l methodology (5 and 10 cm), the differences in long-term impacts were negligible.
l Dispersion is not included because the calculated doses are insensitive to it, and because the computational effort required is large. The FORTRAN commands, including 2 FUNCTION subprograms, are commented out of the program, although they can easily be re-activated, if desired. Also, the groundwater transport begins at the end of the operational period, not at the end of the institutional control period.
8.2 Nuclide-Specific Accounting Although the ultimate interest in an application of IMPACTS-BRC is the total impact, it is often useful to evaluate the relative contributions of each of the various radionuclides in a given waste stream to the total impacts. Output commands to create a new file, TAPE 10.0VT, have been added to several subroutines in IMPACTS-BRC. This file contains ICRP doses for most of the pathways for each radionuclide included in the waste stream. Operational impacts are not included because the program structure of subroutine OPSIMP is not readily amenable to nuclide specific accounting. These doses are not normalized by the number of facilities, and thus do not necessarily add up to the total dose printed in TAPE 6.0VT. However, the relative contributions of each radionuclide to the total dose are evident from this output. The data from TAPE 10.0VT help deter-mine important radionuclides in the waste stream. These doses can be normalized by dividing by the number of treatment or disposal facilities, as appropriate.
The nuclide specific doses are printed for each individual waste stream; cumulative doses are not printed on TAPE 10.00T. -
Except for changes to Subroutine GWATER, the modifications are simple WRITE statements for the computed impacts. To print the time headings for the groundwater impacts, the array SCN has been added to the call statement in IMPACTSB, the main program, and to the subroutine statement in GWATER. This change also required addition of a dimension statement. In some other sub-routines, temporary arrays have been added to store calculated terms for each radionuclide.
8.3 Changes in Facility Types (IQ)
The De Minimis methodology considered 5 facility types corresponding to values 1-5 of the decision index IQ. The facility types were: onsite generator; municipal incinerator and sanitary landfill; municipal incinerator and open dump; hazardous waste incinerator and landfill; and a second hazardous waste incinerator and landfill. The current IMPACTS-BRC program and input data on TAPE 2.DAT correspond to 5 facility types but do not include onsite disposal or open dump disposal. The treatment and disposal facility types corresponding to 47
IQ=1 and 3 have been changed to onsite incineration and sanitary landfill, and onsite incineration and hazardous waste landfill, respectively. This modifica-tion has resulted in changes to several subroutines including READ 2, INCIMP, and OPSIMP, and to IMPACTS, the main program. For onsite disposal, the TAPE 2.DAT values for IQ=1 or 3 should be edited directly. The default values should be changed to values corresponding to the onsite disposal system.
The current IMPACTS-BRC treatment and disposal facility scenarios are listed in Table 25.
TABLE 25 TREATMENT AND DISPOSAL FACILITY TYPES IQ Treatment facility Disposal facility 1 onsite incinerator sanitary landfill 2 municipal incinerator sanitary landfill 3 onsite incinerator hazardous waste landfill II 4 hazardous waste incinerator hazardous waste landfill I 5 hazardous waste incinerator hazardous waste landfill II The hazardous waste landfill specified by IQ=4 represents average performance and site environmental charactersitics. The landfill specified by IQ=5 represents more conservative assumptions about performance and environmental characteristics.
The De Minimis version of IMPACTS required non-default data to be input when l
the onsite disposal facility was used.(IQ=1). These data were read from the end of TAPE 2.DAT in Subroutine READ 2. These data are not read at the end of TAPE 2.DAT in IMPACTS-BRC; if non-default or site-specific data are to be used, the existing values in TAPE 2.DAT should be directly changed. The values for IQ=1 or 3 should be changed if onsite disposal is simulated.
In the De Minimis version, two parameters were read only if non-default facility-specific data were input for the onsite incinerator. The first is OSWR, the waste weight reduction ratio for onsite incineration. The second is OSDL, the dust loading factor for operational impacts from onsite disposal.
These two parameters have been added to the default dataset and are read for each of the 5 facility types. If these parameters are r.ot included in the !
input file, the default values hardwired in the code are used. Thus, the parameters can be specified for both onsite incineration options (IQ=1 or 3),
as well as for the offsite incineration options, if desired. l l
48
9 MODIFICATIONS TO INPUT DECKS ,
Environmental and facility data for the IMPACTS-BRC code are supplied with the program. These data serve as default parameters for the BRC methodology. These ,
values should be changed if more appropriate or realistic values are available.
The supplied values are very conservative, but may be appropriate when the uncertainty in more realistic values is very high.
9.1 Environmental Parameters for Maximum Individual Impacts The example data presented in the De Minimis NUREG/CR-3585 represent 3 regional sites and 5 facility types. A new set of environmental parameters has been developed for the BRC methodology which represents a very conservative (poor performance) site for waste disposal. This set of parameters is used to compute
! maximum individual impacts and is specified by the input parameter IDAT=2, non-default environmental data, and IR=1. The 3 regional site parameters, which
! have also been modified from the example in the De Minimis methodology, are used j to compute critical group and general population impacts. The values are the i most conservative values from the three sites in the De Minimis methodology.
1 The minimum dilution factor for the intruder well is-based'on minimum require-
! ments for a rural well supplying one person (Solley et al., 1983).
Table 26 indicates the environmental parameters used to calculate maximum individual exposures which are not discussed in following sections.
9.2 Groundwater Travel Times i The supplied groundwater travel times are shorter than the corresponding times !
presented as an example in the De Minimis methodology. This primarily reflects i
l' conservatism. The ranges of groundwater velocities used have been observed in actual field cases at LLW and other waste disposal facilities. Also, the :
groundwater pathway is assumed to occur at the end of the operational period, not after the institutional control period.
The travel time from the disposal unit to the receptor is the summation of the travel times in the unsaturated zone (above the water table) and in the saturated i zone. For the NE and SE sites, the travel time through the unsaturated zone
! is assumed to be 1 year. This value is also used for the maximum individual exposure calculations. The travel time through the unsaturated zone at the SW site is conservatively assumed to be 10 years.
! The groundwater velocities (not discharges) in the saturated zone, and resulting j groundwater travel times are shown in Table 27. The distance between sectors
- is 34 m for the sanitary landfill and 91 m for the hazardous waste' landfill.
The distance to the intruder well, from the closest sector, is half this value.
i For the NE and SE sites, and for maximum individual calculations, the popula-I tion well is 1 km away and the stream is 2 km away. The population _well at the SW site is 3 km from the disposal ~ units. As in the De Minimis methodology, impacts due to water supply from the stream are not considered for the SW site.
i j 49 i
! o 6
TABLE 26 ENVIRONMENTAL PARAMETERS USED FOR THE MAXIMUM INDIVIDUAL Parameter Definition Value PRC Infiltrating percolation 0.18 m/yr FSC Soil-to-air trnsfr fctr (intru-const) 2.64E-10 j FSA Soil-to-air trnsfr fctr (intru-agri) 8.06E-11 QFC(1) Minimum intruder well dilution factor 110
- QFC(2) Minimum population well dilution factor 2.0E+5
. QFC(3) Minimum stream dilution factor 4.5E+6 WVEL Average wind velocity 6.67 m/sec AX0Q Accident X/Q 1.4E-10 yr/m 3 i
EFAC Dust mobilization factor 7.95E-6 TABLE 27 GROUNDWATER TRAVEL TIMES Max individual NE- SE SW Saturated zone velocity (m/yr) 20 1 5 10 j Travel time between sectors (yr) sanitary landfill 1.7 34 6.8 3.4 j hazardous waste landfill 1.7 91 18.2 9.1 Travel time to intruder well (yr) sanitary landfill 1.85 18 4.4 11.7 hazardous waste landfill 1.85 46.5 10.1 14.5 Travel time to population well (yr) !
j sanitary landfill 25 500 100 300 l
{ hazardous waste landfill 25 500 100 300
- Travel time to stream (yr) sanitary landfill 50 1000 200 hazardous waste landfill 50 1000 200 l
e 50
9.3 Retardation Coefficients The supplied retardation coefficients are lower than the example values presented in the De Minimis documentation, reflecting conservatism and poten-tial disposal with mobilizing agents such as organics and other complexants.
Table 28 indicates De Minimis methodology values, values calculated from draft EPA BRC rulemaking documents, and the values supplied in TAPE 2.DAT.
9.4 Contact Time Fraction
! The source term for groundwater contamination problems is not currently well understood. The concentration of radionuclides in leachate passing through the disposal unit varies widely in actual field situations. This variaticn is due, in part, to site-specific geochemical and moisture conditions, variation in waste packaging and processing prior to disposal, and different radionuclide inventories. In draft EPA technical reports to support standards for LLW management, the performance assessment model used includes five different methods for estimating the source term.
In the De Minimis methodology, source term concentrations were estimated using a ratio method based on actual data from the Maxey Flats and West Valley LLW sites. For a given radionuclide, the leachate concentration in a trench sump was divided by the average concentration of that radionuclide in the waste. An average ratio for each radionuclide was calculated from the ratios for several trenches. Because the trenches at Maxey Flats and West Valley were saturated with water, and the disposal units at a sanitary or hazardous waste lanofill are not expected to be saturated, a correction factor was introduced to reduce the leachate concentration. This correction factor assumed that the transfer of radionuclide from the waste to the leachate was controlled by the extent of water saturation and the amount of time the percolating water was in contact with the waste. The resulting Contact Time Fractions reduced concentrations for the groundwater and leachate treatment pathways by a factor ranging from 3.6E-5 to 1.3E-2.
The Contact Time Fractions in the supplied TAPE 2.DAT are all equal to unity.
Thus, the average ratios determined from the sites are used to calculate leachate concentrations based solely on the average radionuclide concentrations in the waste. Data from some leaching experiments and field measurements indicate that leachate concentrations may not be directly affected by the contact time of the waste and water, or by the extent of water saturation (e.g.
Siskind et al. 1986; Arora and Dayal 1983; Essington et al. 1986). Even with this assumption, the mass of a radionuclide leaving the disposal unit will be reduced at lower saturation because the volume of water percolating through the unit is lower. This conservative assumption, that the leachate concentration ratios are the same as Maxey Flats and West Valley data, is required because of the uncertainty in estimating the source term without knowledge of the site-specific leaching and waste composition. ,
i The release fraction for C-14 used in the De Minimis methodology was determined I in a manner different from that used for most of the other radionuclides, including H-3 and Co-60. The fraction for C-14 was determined using the leachate concentrations from the West Valley trench sumps and the trench inventories from .
the Maxey Flats site. The resulting ratio for C-14 was 5.76E-3, while the l ratios for H-3, Co-60, and Am-241, using both concentrations and inventu-ies '
51
, . ,e -
G-
. ~ - .
l
-i TABLE 28 i MINIMUM RETARDATION COEFFICIENTS FOR SELECTED ELEMENTS Element BRC De Minimis EPA R*
H 1 1 1.05 C 1 10 1.05 P 1 43 -
S 1 9 Mn 10 43 766 Fe 1 630 7651 Ni 1 420 766 Co 1 420 205 Zn 1 9 Sr 1 9 103 Tc 1 2 1.17 Cd 1 .9 -
I 1 2 1.05 Cs 1 85 1276 Ce 100 840 5611 Th 100 840 -
Pu 10 840 9181 Am 100 300 23971
" EPA R = 1.0 + 5.1 * (EPA's Kd) 52
from Maxey Flats, were 1.15, 1.48E-2, and 4.11E-3, respectively. Given the typical geochemical behavior of C-14 relative to other radionuclides, it is unreasonable to assume that the C-14 release ratio is lower than the ratio for Co-60. Furthermore, it was assumed for the De Minimis methodology, and the BRC methodology, that the I-129 and Tc-99 ratios were one order of magnitude lower than the ratio for H-3. For consistency, the C-14 ratio for the BRC methodology l
is also assumed to be one order of magnitude lower than the H-3 value, or 0.115.
' This is a more conservative assumption and is geochemically more consistent with the other ratios used.
9.5 Peclet Numbers Peclet numbers are not needed because they only affect the groundwater dispersion calculations, which have been dropped from IMPACTS-BRC. However, for consistency and ease of modification, IMPACTS-BRC still reads the Peclet number values from TAPE 2.
4 9
1 4
53
- - - --- --- + rr rr---
10 REFERENCES AND BIBLIOGRAPHf
(
Aikens, A.E. , Jr. , R.E. Berlin, J. Clancy, and 0. I. Oztunali, Generic Methodology for Assessment of Radiation Doses from Groundwater Migration of Radionuclides in LWR Wastes in Shallow Land Burial Trenches, Atomic Industrial Forum, Inc., AIF/NESP-013, January 1979. -Available from Atomic Industrial Forum, Inc., 7101 Wisconsin Ave., Washington DC-20014. <
< Arora H., and R. Dayal, Properties of Radioactive Wastes and Waste Containers, Quarterly Progress Report October-December 1982, BNL-NUREG-32498, submitted to USNRC, 1983.
Bland, J.S. , J. A. Lieberman, H.W. Morton, and W. A. Rodger, Development of
! Recommended Regulatory Cutoff Levels for Low-Level Radioactively Con- -
taminated Oils from Nuclear Power Plants, Otha, Inc. report prepared for i Utility Nuclear Waste Management Group, submitted to USNRC, October 1983.
! Chan, D.W. , J.P. Davis, R. Danna, J. A. Palmer, J.V. Palmer, B.R. Parrish, and M. Donovan, Evaluation of the Potential for De-regulated Disposal of Very 4 Low Level Wastes from Nuclear Power Plants, NESP of AIF by General Physics L
] Corp., GP-R-211006, January 1986a. Available from Atomic Industrial Forum, Inc., 7101 Wisconsin Ave., Washington DC 20014.
Chan, D.W. , J.P. Davis, and B.R. Wofford, A Guide for Obtaining Regulatory Approval to Dispose of Very Low-Level Wastes from Nuclear Power Facilities by Alternative Means, NESP of AIF by General Physics Corp., GP-R-211013, j Draft, January 1986b. Available from Atomic Industrial Forum, Inc.,
l 7101 Wisconsin Ave., Washington DC 20014. L j Codell, R.B., Simplified Analysis for Liquid Pathway Studies, USNRC Report j NUREG-1054, August 1984.
! EEI and UNWMG, Petition for Rulemaking Regarding the Disposal of Radioactively i Contaminated Waste Oil from Nuclear Power Plants Which is Below Regulatory j Concern, submitted to USNRC, July 1984, with revisions and response to comments submitted to USNRC, July 1985.
EPA, PRESTO-EPA: A Low-Level Radioactive Waste Environmental Transport and Risk Assessment Code--Methodology and User's Manual, EPA 520/5-83-004, undated.
4 Essington, E.H., W.L. Polzer, E.A. Lopez, and E.A. Stallings, Leaching of i Solutes from Ion-Exchange Resins Buried in Bandelier Tuff, Draft report j LA-UR-86-1051, submitted to USNRC, April 1986. T l International Commission on Radiological Protection (ICRP), Limits for Intakes
- of Radionuclides by Workers, Part 1, ICRP Publication 30, July 1978.
l
- Lachajczyk, T. , et al. , Radiation Exposures and Health Risks Resulting from Less Restrictive Disposal Alternatives for Very Low-Level Radioactive Wastes, Envirodyne Engineers Inc. final report submitted to EPA Office of Radiation Program, undated. Available from U.S. EPA Office of Radiation Programs, Washington DC 20460.
l Lin, M., and 0.R. MacKenzie, Tests of Absorbents and Solidification Techniques i for Oil Wastes, USNRC Report NUREG/CR-2977, November 1983.
} 55 L
i
McKenzie, D.H. , et al. , Relevance of Biotic Pathways to the Long-Term Regulation of Nuclear Waste Disposal, USNRC Report NUREG/CR-2675, several volumes, ,
1982-1985. l Merrell, G.B., V.C. Rogers, K.K. Nielson, and M.W. Grant, The PATHRAE Performance Assessment Code for the Land Disposal of Radioactive Wastes, DRAFT report submitted to EPA by Rogers and Assoc. Engineering Corp. ,
j RAE-8469/3, January 1985. Available from U.S. EPA Office of Radiation Programs, Washington DC 20460.
Napier, B. A. , et al. , Intruder Dose Pathway Analysis for the Onsite Disposal of Radioactive Wastes: The 0NSITE/MAXII Computer Program, USNRC Report NUREG/CR-3620, October 1984.
Neuder, S.M., Onsite Disposal of Radioactive Waste, Vol. 1, Guidance for Disposal by Subsurface Burial, USNRC Report NUREG-1101, March 1986.
U.S. Nuclear Regulatory Commission, Final Environmental Statement on the Transportation of Radioactive Material by Air and Other Modes, USNRC Report NUREG-0170, Vol. 1, December 1977.
U.S. Nuclear Regulatory Commission, Draft Environmental Impact Statement on 10 CFR Part 61 " Licensing Requirements for Land Disposal of Radioactive Waste," USNRC Report NUREG-0782, September 1981.
i U.S. Nuclear Regulatory Commission, Final Environmental Impact Statement on 10 CFR Part 61 " Licensing Requirements for Land Disposal of Radioactive Waste," USNRC Report NUREG-0945, November 1982.
Oztunali, 0.I., and G.W. Roles, De Minimis Waste Impacts Analysis Methodology, USNRC Report NUREG/CR-3585, Vol.1, February 1984.
Oztunali, 0.I., and G.W. Roles, Update of Part 61 Impacts Analysis Methodology, USNRC Report NUREG/CR-4370, January 1986.
Rogers, V.C., R.D. Baird, and M.W. Grant, PREST 0-BRC: User's Guide and Documentation for Below Regulatory Concern Modifications to the PREST 0 Code, RAE Draft report RAE-51-1 submitted to EPA Office of Radiation Programs, October 1984. Available from U.S. EPA Office of Radiation Programs, Washington DC 20460.
Siskind, B. , B.S. Bowerman, C.R. Kempf, and D.R. MacKenzie, An Evaluation of i Used Oil Contaminated with Radionuclides, Draft BNL technical report A-3173 submitted to USNRC, April 1986.
Solley, W.B., E.B. Chase, and W.B. Mann, IV, Estimated Use of Water in the United States in 1980, U.S. Geological Survey Circular 1001, 1983.
Widmayer, D.A., User's Guide for 10 CFR 61 Impact Analysis Codes, USNRC Report NUREG-0959, January 1983.
56
)
l APPENDICES A. IMPACTS-BRC FORTRAN SOURCE CODE LISTING B. TAPE 1.DAT - NUCLIDE-SPECIFIC DATA C. TAPE 2.DAT - ENVIRONMENTAL AND FACILITY PARAMETERS D. EXAMPLE TAPES - OPTIONS AND WASTE STREAM CHARACTERISTICS E. EXAMPLE TAPE 6.0VT - TOTAL WASTE STREAM DOSES FOR Al.L PATHWAYS F. EXAMPLE TAPE 10.0VT - ICRP DOSES BY NUCLIDE G. INSTALLATION PROCEDURES I
l l
l 57 .
i t
APPENDIX A IMPACTS-BRC FORTRAN SOURCE CODE LISTING
CBRC IMPB 10
- $ STORAGE:2 IMPB 20 PROGRAM IMPACTSB IMPB 30 C IMPB 40 C********************************************************************* IMPB 50 C IMPB 60 C PROGRAM TITLE: IMPACTS-BRC VERSION 1.0 IMPB 70 C IMPB 80 C DEVELOPED FOR: U.S. NUCLEAR REGULATORY COMMISSION IMPB 90 C 0FFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS IMPB 100 C DIVISION OF WASTE MANAGEMENT IMPB 110 C IMPB 120 l C DATE: MAY 1986 IMPR 130 C IMPB 140 C NRC CONTACT: CHIEF, GE0 TECHNICAL BRANCH PHONE: (301) 492-7000 IMPB 150 C DIVISION OF WASTE MANAGEMENT IMPB 160 C IMPB 170 C CODE DEVELOPER: DR. 0.I. OZTUNALI, EBASCO SERVICES INC. IMPB 180 C WITH MODIFICATIONS BY DANIEL J. GOODE, NRC IMPB 190 C IMPB 200 C TITLES OF ASSOCIATED DOCUMENTATION AND NUREG NUMBERS: IMPB 210 C IMPB 220
- C OZTUNALI, 0.I., AND G.W. ROLES, DE MINIMIS WASTE IMPACTS ANALYSIS IMPB 230 C METHODOLOGY, VOL 1, NUREG/CR-3585, 1984. IMPB 240 C IMPB 250 C FORSTROM, J.M., AND D.J. GOODE, DE MINIMIS WASTE IMPACTS ANALYSIS IMPB 260 C METHODOLOGY, VOL 2 IMPACTS-BRC USER'S GUIDE ~AND METHODOLOGY FOR IMPB 270 C RADIOACTIVE WASTE BELOW REGULATORY CONCERN, NUREG/CR-3585, 1986. IMPB 280
, C IMPB 290 l C THIS PROGRAM WAS PREPARED FOR AN AGENCY OF THE UNITED STATES IMPB 300 C GOVERNMENT. NEITHER THE UNITED STATES GOVERNMENT NOR ANY AGENCY IMPB 310 C THEREOF, NOR ANY OF THEIR EMPLOYEES, MAKES ANY WARRANTY, EXPRESSED IMPB 320 C OR IMPLIED, OR ASSUMES ANY LEGAL LIABILITY OR RESPONSIBILITY FOR IMPB 330 C ANY THIRD PARTY'S USE, OR THE RESULTS OF SUCH USE, 0F ANY PORTION IMPB 340 C OF THIS PROGRAM OR REPRESENTS THAT ITS USE BY SUCH THIRD PARTY IMPB 350 C WOULD NOT INFRINGE PRIVATELY OWNED RIGHTS. IMPB 360 C IMPB 370 C***********************************************************************IMPB 380 C IMPB 390 C THIS CODE REPRESENTS AN ANALYSIS METHODOLOGY FOR DETERMINING THE IMPB 400 C RADIOLOGICAL IMPACTS ASSOCIATED WITH THE DISPOSAL OF DE MINIMIS IMPB 410 C WASTE. IT CALCULATES THE IMPACTS UNDER A NUMBER OF SCENARIOS, IMPB 420 C INCLUDING THOSE INVOLVED WITH: TRANSPORTATION OF THE WASTE; IMPB 430 C SORTING / INCINERATION / RECYCLE OF THE WASTE; AND FINAL TREATMENT / IMPB 440 C DISPOSAL CONSIDERATIONS. IMPB 450 C IMPB 460 C THE INPUT /0UTPUT FILES ARE IDENTIFIED AS FOLLOWS: IMPB 470 C IMPB 480 C TAPE 1= INPUT FILE CONTAINING THE BASIC DOSE CONVERSION FACTORS, IMPB 490 C NUCLIDE NAMES, GROUNDWATER RETARDATION COEFFICIENTS, ETC. IMPB 500 C IMPB 510 C TAPE 2= INPUT FILE CONTAINING THE DEFAULT ENVIRONMENTAL, IMPB 520 C TREATMENT, AND DISPOSAL PARAMETERS USED IN THIS ANALYSIS. IMPB 530 C ALSO CONTAINS NON-DEFAULT FACILITY AND ENVIRONMENT DATA. IMPd 540 i
C IMPB 550 C TAPE 5= INPUT FILE CONTAINING THE WASTE STREAM CHARACTERISTICS IMPB 560 1
C PERTAINING TO A SPECIFIC APPLICATION. THIS FILE WILL IMPB 570 4
C MOST LIKELY CHANGE WITH EACH CASE UNDER CONSIDERATION. IMPB 580 A-1
,3 . ., + - - - - . , - - p _. p.-. , _ , - - - - - .
C IMPB 590 C TAPE 6= OUTPUT FILE CONTAINING THE MAIN RESULTS OF THE ANALYSIS IMPB 600 C .
IMPB 610 C TAPE 10= OUTPUT FILE CONTAINING ICRP DOSES FOR EACH NUCLIDE IMPB 620 C (MOST PATHWAYS) IMPB 630 C IMPB 640 C MODIFICATIONS TO THE ORIGINAL IBM-PC VERSION ARE NOTED BY "CBRC" IMPB 650 C IMPB 660 C********************************************************************* IMPB 670 C IMPB 680 )
CBRC $LARGE IMPB 690 CHARACTERORG(10)*9,SCN(36)*6,FAS(5)*20,NUCT*6,SOLT*1 IMPB 700
$ INCLUDE:'IMPCOMM.FOR' IMPB 710 COMMON /CHYN/NXUC(85),ICH(8,10),LCH(10),ACT(8),8CT(8,2)/UPTK/FK(21)IMPB 720 COMMON /DC FS/ FF( 85 , 5 ) , DC F1( 159,10 ) ,0C F2( 159 ,10 ) ,0C F3 ( 85 ) , IMPB 730
+ DC F4 ( 85,10 ) , DC F 5 ( 85,10 ) , NUCT( 159 ) ,50 LT( 159 ) IMPB 740 DIMENSION TYMD(16),BIMPT(10,65) IMPB 750 DATA ORG/' LUNGS ' ' S. WALL ,' ' LLI WALL',' T. BODY ',
, IMPB 760
. ' KIDNEYS ',' LIVER ' ' ,RED MAR ',' BONE * , IMPB 770
' THYROID ',' ICRP '/ IMPB 780
. DATA SCN/' INT-CO',' INT-AG','IN-AIR','ER-AIR','IN-WAT','ER-WAT', IMPB 790
'IC-POP','IC-IND','IC-WOR','IC-MWR','OP-POP','0P-IND', IMPB 800
. 'OP-WOR','OP-MWR',' 20YR',' 40YR',' 60YR',' 80YR', IMPB 810
. ' 100YR',' 120YR',' 160YR',' 200YR',' 400YR',' 600YR', IMPB 820
. ' 800YR' ,' IK YR' ,' 2K YR' ,' SK YR' ,'10K YR' ,'20K YR' , IMPB 830
. 'TR-MAX','TR-0CC','TR-POP','LA-OPS','LA-0VF','LA-AIR'/ IMPB 840 CBRC CHANGES TO FACILITY NAMES IMPB 850 DATA FAS/'ONSITE INC, S. LANDF',' SANITARY LANDFILL ' IMPB 860
'ONSITE INC, H. LANDF',' HAZARDOUS WASTE I ' IMPB 870
. ' HAZARDOUS WASTE II '/ IMPB 880 DATA TYMD/20.,40.,60.,80.,100.,120.,160.,200.,400.,600., IMPB 890
. 800.,1000.,2000.,5000.,10000.,20000./ IMPB 900 DATA NTYM/16/ IMPB 910 101 FORMAT (813) IMPB 920 CBRC 102 FORMAT (1H1/2X,A20//2X' LIFE ='13,2X'0 VFL ='I3,2X'NS1R='13/ IMPB 930 CBRC MODIFY FIRST LINE BECAUSE HEADER ADDED BELOW IMPB 940 102 FORMAT (//2X,A20//2X' LIFE ='I3,2X'0 VFL ='I3,2X'NSTR='I3/ IMPB 950
- 2X'REGN='I3,2X' DATA ='I3/2X'IPOP='I3,2X' INST ='I3) IMPB 960 103 FORMAT (1H1) IMPB 970 104 FORMAT (/2X' TRANSPORTATION IMPACTS'10X,A6' ='1PE9.2' MREM /YR' IMPB 980
- /34X, A6 =' E9.2' PERSON-MREM /YR'/34X, A6' =' E9.2' PERSON-MREM /YR') IMPB 990 CBRC */34X,A6' ='E9.2' MREM / YEAR'/34X,A6' ='E9.2' PERSON-MREM /YR') IMPB1000 106 FORMAT (1H1/2X' CUMULATIVE IMPACTS'/) IMPB1010 00 10 I=1,3 IMPB1020 10 FRACT(7,1)=FRACT(29,1) IMPB1030 CBRC THIS REPLACES BLOCK DATA SUBPROGRAM IMPB1040 CALL BLOCKD IMPB1050 CALL READ 1 '
IMPB1060 i C IMPB1070 1 C START OF A GIVEN CASE - ONE FACILITY AND ANY NUMBER OF IMPB1080 )
C WASTE STREAMS WITH GIVEN CHARACTERISTICS IMPB1090 C IMPB1100 CBRC CHANGES TO OPEN STATEMENTS FOR NAMING TAPE 5 AND CREATING TAPE 6 IMPB1110 OPEN(5, FILE =' ') IMPB1120 l OPEN(6, FILE =' TAPE 6.00T', STATUS ='NEW') IMPB1130 CBRC TAPE 10 IS USED FOR NUCLIDE SPECIFIC OUTPUT AND DEBUGGING IMPB1140 OPEN(10, FILE =' TAPE 10.0VT', STATUS ='NEW') IMPB1150 CBRC WRITE HEADER ON TAPES 6 AND 10 IMPB1160 WRITE (6,1000) IMPB1170 WRITE (10,1000) IMPB1180 1000 FORMAT (1H1/' IMPACTS-BRC',10X,' VERSION 1.0') IMPB1190 CBRC END IMPB1200 A-2
20 READ (5,101.END=50) IR,IDAT,IQ,NSTRD,IPOP,ILFE,IINS,10FL IMPB1210 WRITE (6,102) FAS(IQ),ILFE,IOFL,NSTRD,IR,IDAT,IPOP,IINS IMPB1220 CBRC WRITE SCENARIO HEADER ON TAPE 10.0UT IMPB1230
- WRITE (10,1002) FAS(IQ) IMPB1240 l 1002 FORMAT (//2X,A20) IMPB1250 CBRC END IMPB1260 CALL READ 2 IMPB1270 CALL ZER0(BIMPT,650) IMPB1280 00 40 ISTRD=1,NSTRD IMPB1290 i CALL ZER0(BIMP,650) IMPB1300 l
IF(ISTRD.NE.1) WRITE (6,103) IMPB1310 C .IMPB1320 C CALCULATE IMPACTS IMPB1330 C IMPB1340 CALL READS IMPB1350 CBRC SAVE DISPOSAL / INCINERATION / SORTING OPTION IMPB1360 INCIN=ISPC(1,5) IMPB1370 CALL SPLICE IMPB1380 CALL INTIMP IMPB1390 CALL EXPWAS IMPB1400 CALL OPSIMP IMPB1410 IF(10FL.NE.0) CALL OVRFLO IMPB1420 l CBRC ADD SCN TO GWATER CALL TO PRINT TIMES ON TAPE 10 IMPB1430
- CALL GWATER(NTYM,TYMD,SCN) IMPB1440 CBRC IMPB1450 C IMPB1460 C NORMALIZE INDIVIDUAL IMPACTS WITH NUMBER OF FACILITIES IMPB1470 C IMPB1480 CALL DIVVY (1,1,2) IMPB1490.
CALL DIVVY (1,5,6) IMPB1500 CBRC CALL DIVVY (2,8,8) IMPB1510
- CBRC CALL DIVVY (2,10,10) IMPB1520 I
CBRC NORMALIZE INCINERATOR IMPACTS ONLY IF INCINERATION OCCURS IMPB1530
- IF(INCIN.NE.1) CALL DIVVY (2,8,8) IMPB1540
- IF(INCIN.NE.1) CALL DIVVY (2,10,10) IMPB1550 CBRC END IMPB1560 CALL DIVVY (1,12,12) IMPB1570 CALL DIVVY (1,14,14) IMPB1580
! CALL DIVVY (1,15,64) IMPB1590 1
C IMPB1600 WRITE (6,104) (SCN(I+26), BAS (1,1),I=5,7) IMPB1610 CALL PRNTE(ORG,SCN,BIMP) IMPB1620 00 30 I=1,10 IMPB1630 DO 30 J=1,65 IMPB1640 30 BIMPT(I,J)=BIMPT(I,J)+BIMP(I,J) IMPB1650 40 CONTINUE IMPB1660 IF(NSTRD.EQ.1)GO TO 20 IMPB1670 WRITE (6,106) IMPB1680 CALLPRNTE(ORG,5CN,BIMPT) .
IMPB1690 GO TO 20 IMPB1700 C IMPB1710 C END OF A GIVEN CASE, GO TO 20 FOR NEW CASE IMPB1720 C IMPB1730 50 CLOSE (5) IMPB1740 CLOSE (6) IMPB1750 CBRC CLOSE TAPE 10 IMPB1760 CLOSE(10) IMPB1770 STOP ' NORMAL TERMINATION' IMPB1780 END IMPB1790 A-3
CHARACTER BASN*10,NUC*6,50L*1,SOLB*1 ICOM 10 COMMON / BAST / BAS ( 2 ,92 ) , B IMP ( 10,65 ) , I S PC( 2 ,15 ) , PDC F( 85 ,10 ,7 ) ICOM 20
+ /CH RC/BASN( 2 ) , NUC(85) , SO L( 85 ) , SO LB( 85 ) ICOM 30
+ /DTNX/IR,IDAT,IQ,IPOP,ILFE,IINS,IOFL,NSTR ICOM 40-
+ /NUCS/AL( 85 ) , FMF( 85) , RET ( 85,5) , FRACT( 85,3 ) , NUX(85 ) ICOM 50
+ /D R P 1/ FS C ( 3 ) , FSA( 3 ) , P RC( 3,5 ) , TS C ( 3,5 ) , Q FC( 3,3 ) , ICOM 60
+ DTTM( 3 ,5 ) , TTM( 3,3,5 ) , DT PC( 3,5 ) , T PC( 3,3,5 ) , N RET ( 3 ) ICOM 70
+ /DRP2/TPOP( 3 ) ,TD0Z( 3 ) ,WVEL( 3 ) , E FAC( 3 ) , POP ( 3 ) , ICOM 80
+ POPE (3),POPW(3),AX0Q(3),EER0(5),EREC(5) ICOM 90
+ / FAC P/TDI S( 5) ,TV E L( 5 ) ,VINC( 5 ) , X0QI( 5) , ED FI( 5 ) , ICOM 100
+ DEN 1( 5) ,VANN( 5 ) , X000( 5) , EDF0( 5 ) , DEN 2( 5 ) , ICOM 110
+ TWI(5,3),TWO(5,3),ADAY(5,3),RMIX(5), ICOM 120
+ EMP( 5 ) , E FF( 5 ) , S EFF( 5 ) ,GER0( 5 ) ,0 SWR ICOM 130 CBRC RED 1 10
$ STORAGE:2 REDI 20 SUBROUTINE READ 1 REDI 30 C RED 1 40 C********************************************************************* RED 1 50 C THIS SUBROUTINE READS IN THE FUNDAMENTAL DCF FROM TAPE 1.
REDI 60 C UPTAKE USES THESE TO COMPUTE THE PDCFS AS NEEDED.
REDI 70 C********************************************************************* REDI 80 C REDI 90 CBRC $LARGE REDI 100 CHARACTER BASN*10,NUC*6,NUCT*6,50L*1,50LB*1,SOLT*1 REDI 110 COMMON /CH RC/ BAS N( 2 ) , NUC( 85 ) ,50 L( 85) , SO LB( 85 ) REDI 120
+ /NUCS/AL( 85) , FMF( 85 ) , RET ( 85,5) , FRACT( 85,3 ) , NUX( 85 ) REDI 130 COMMON /DC FS/ FF( 85,5 ) ,0C F 1( 159,10 ) ,0C F2 ( 159 ,10 ) , DC F3( 85 ) , REDI 140
+ DC F4 ( 85 ,10 ) ,0C F5 ( 85 ,10 ) , NUCT( 159 ) , SO LT( 159 ) RED 1 150 CBRC 101 FORMAT (A6,1X,II,A1,12E9.2) RED 1 160 CBRC NEW FORMAT TO DROP Al AND A2 WHICH ARE NOT USED RED 1 170 101 FORMAT (A6,1X,II,A1,10E9.2) REDI 180 102 FORMAT (9X,10E9.2) REDI 190 103 FORMAT (8X,A1,10E9.2/9X,10E9.2) REDI 200 OPEN(1, FILE =' TAPE 1.DAT' ) RED 1 210 INCT=0 REDI 220 00 30 INUC=1,85 REDI 230 READ (1,101) NUC(INUC),JJ,SOLB(INUC),DCF3(INUC),(FF(INUC,I),I=1,5),RE01240
CBRC
- AL( I NUC ) , FMF( INUC ) , RET ( I NUC ,1 ) , R ET( INUC ,4 ) , A1, A2 REDI 260 A2= RET (INUC,4) RED 1 270 Al=(A2/ RET (INUC,1))**0.334 RED 1 280 RET (INUC,5)=A2*Al RED 1 290 RET (INUC,3)=A2/A1 REDI 300 RET (INUC,2)= RET (INUC,1)*Al. RED 1 310 READ (1,102) (DCF4(INUC,1),I=1,10),(DCF5(INUC,I),I=1,10) REDI 320 INCT=INCT+1 RE01 330 REDI 340 l NUCT(INCT)=NUC(INUC)
READ (1,103) SOLT(INCT),(DCF1(INCT,I),I=1,10),(DCF2(INCT,I),I=1,10) RED 1 350 ,
IF(JJ.EQ.1)GO TO 30 REDI 360 ;
DO 20 IJ=2,JJ RE01 370 ;
INCT=INCT+1 RED 1 380 NUCT(INCT)=NUC(INUC) RE01 390 f READ (1,103) SOLT(INCT),(DCF1(INCT,I),!=1,10),(DCF2(INCT,I),I=1,10)REDI 400 l 20 CONTINUE RED 1 410 '
30 CONTINUE REDI 420 )
CLOSE (1) RE01 430 l RETURN REDI 440 )
END REDI 450 >
~
A-4
CBRC RED 2 10
$ STORAGE:2 RED 2 20 SUBROUTINE READ 2 RED 2 30 C RED 2 40 Ca**************************************************"************"** RED 2 50 C THIS SUBROUTINE READS IN THE TREATMENT / DISPOSAL SITE
- RED 2 60 C ENVIRONMENTAL CHARACTERISTICS AND TREATMENT / DISPOSAL RED 2 70 C TECHNOLOGY CHARACTERISTICS FROM TAPE 2. RED 2 80 C******************"************************************************* RED 2 90 C RED 2 100 CBRC $LARGE RED 2 110
, $ INCLUDE:'IMPCOMM.FOR' RED 2 120
! DIMENSION PDS(6),WSP(6), STB (6),DSP(6) RED 2 130 102 FORMAT (10E10.3) RED 2 140 104 FORMAT (ISIS) RE02 150 202 FORMAT (/2X'0PTIONAL X0Q PARAMS'/(2X,1P,4E10.3)) RED 2 160 203 FORMAT (2X,1P,6E10.3) RED 2 170 204 FORMAT (/2X'0PTIONAL ENVIRONMENTAL PARAMETERS'/2X'PRC ='1PE9.2, RED 2 180
. 2X ' TXC = ' E9.2,2X ' QFC = ' 3E9. 2/2X ' FSC = ' E9.2,2X ' DTTM= ' E9. 2, RED 2 190
. 2X'TTM ='3E9.2/2X'FSA ='E9.2,2X'DTPC='E9.2,2X'TPC ='3E9.2/ RED 2 200
. . 2X'WVEL='E9.2,2X'AW00='E9.2,2X'EFAC='E9.2) RED 2 210 1 CBRC 205 FORMAT (/2X'0PTIONAL FACILITY PARAMETERS'/2X'VINC='1PE9.2, RED 2 220 CBRC .2X'VANN='E9.2,2X'ADAYS='3E9.2/2X'EMP ='E9.2,2X'EFF ='E9.2, RED 2 230 CBRC .2X'SEFF='E9.2,2X' DEN 1='E9.2,2X' DEN 2='E9.2/ RED 2 240 CBRC .2X'RMIX='E9.2,2X'GER0='E9.2,2X'0 SWR ='E9.2,2X'0SDL='E9.2) RE02 250 CBRC .2X'RMIX='E9.2,2X'0 SWR ='E9.2,2X'0SDL='E9.2) RED 2 260
, C RED 2 270
- C READ DEFAULT SITE ENVIRONMENTAL PARAMETER VALUES RED 2 280 l C RED 2 290 l OPEN(2, FILE =' TAPE 2.DAT') RED 2 300
- D0 10 I=1,3 RE02 310 i READ (2,102) (PRC(I,J),TSC(I,J),DTTM(I,J),(TTM(I,K,J),K=1,3), RED 2 320 D I PC( I ,J ) , ( I PC( 1, K ,J ) , K= 1,3 ) ,J= 1,5 ) RED 2 330 READ (2,102) FSC(I),FSA(I),(QFC(I,J),J=1,3), POP (I), POPE (I), RED 2 340 POPW( I ) , TPOP( I ) , TD0Z( I ) ,WVEL( I ) , AX00( I ) , EFAC( I ) , RED 2 350 EER0(I),EREC(I) RED 2 360 i READ (2,104) NRET(I) RED 2 370 10 CONTINUE RED 2 380 C RED 2 390 C READ DEFAULT FACILITY PARAMETER VALUES RED 2 400 C RED 2 410 00 12 I=1,5 RED 2 420 READ (2,102) TDIS(I),TVEL(I),VINC(I),X0QI(I),EDFI(I), DEN 1(I), RED 2 430 VANN ( I ) , X000( I ) , ED F0( I ) , D EN2( I ) , ( TWI( I ,J ) ,J= 1,3 ) , RED 2 440 4 (TWO(I,J),J=1,3),(ADAY(I,J),J=1,3),RMIX(I), RED 2 450 EMP( I ) , E F F( I ) , S E FF( I ) ,GER0( I ) ,0 SWR ,0SD L RED 2 460 CBRC
- EMP(I),EFF(I),SEFF(I),GER0(I) RED 2 470
', CBRC COMPUTE SPECIAL DUST LOADING IF OSDL INPUT (ORIGINALLY IQ=1) RE02 480 IF(OSDL.GT.0.) TWO(I,3)=0SDL*1.E-6/ DEN 2(I) RED 2 490 12 CONTINUE RED 2 500 C RED 2 510 C START READING OPTIONAL PARAMETER VALUES RED 2 520 C RED 2 530 CBRC 10=1 DOES NOT REQUIRE NON-DEFAULT INPUT RED 2 540 CBRC IF(IQ.EQ.1. AND. IDAT.EQ.0)IDAT=2 RED 2 550 CBRC I F(IQ.EQ.1. AND. IDAT.EQ.1)IDAT=3 RED 2 560 IF(IDAT.EQ.0)GO TO 22 RED 2 570 IF(IDAT.EQ.2)GO TO 20 RED 2 580 C RE02 590 a, ,
. A-5
- ~ -
~a ., , , -- ,
3 i
C SITE-SPECIFIC POP AND X0Q OPTION RED 2 600 C RED 2 610 00 14 I=1,6 RED 2 620 14 READ (2,102) DSP(I),PDS(I),WSP(I), STB (I) '
RED 2 630 WRITE (6,202)(DSP(I),PDS(I),WSP(I), STB (I),I=1,6) RED 2 640 READ (2,102) HYTI,HYTO,DISTI, DISTO,EDFID,EDF00 RED 2 650
! WRITE (6,203) HYTI,HYTO,DISTI, DISTO,EDFID,EDF00 RED 2 660
- Al=0. RED 2 670 A2=0. RED 2 680 l D0 16 I1=1,6 RED 2 690 Al=A1+ STB (II)*X0QFC(HYTI,DISTI,WSP(II),II) RED 2 700 A2=A2+ ST B( I I )
- X00 FC ( HY TO , D I ST0,WS P( I I ) , I I ) RED 2 710 16 CONTINUE RED 2 720 X001(IQ)=Al RED 2 730 X000(IQ)=A2 RED 2 740 EDFI(IQ)=EDFID RED 2 750 EDF0(IQ)=EDF00 RED 2 760
, Al=0. RED 2 770 D0 18 11=1,6 RED 2 780 DO 18 12=1,6 RED 2 790 Al=A1+PDS(II)* STB (I2)*X0QFC(HYTI,DSP(II),WSP(12),12) RED 2 800 18 CONTINUE RED 2 810 POP (IR)=Al RE02 820 i POPE (IR)=3.*Al RED 2 830 20 IF(IDAT.EQ.1)G0 TO 22 RED 2 840 C RED 2 850 C SITE-SPECIFIC ENVIRONMENTAL PARAMETERS RED 2 860 C RED 2 870
] READ (2,102) PRC(IR,1Q),TSC(IR,1Q),DTTM(IR,IQ), RED 2 880
! + (TTM(IR,J,IQ),J=1,3),DTPC(IR,IQ),(TPC(IR,J,IQ),J=1,3), RED 2 890
+ FSC(IR),FSA(IR),(QFC(IR,J),J=1,3),WVEL(IR),AX0Q(IR),EFAC(IR) RED 2 900
] READ (2,104) NRET(IR) RED 2 910 WRITE (6,204) PRC(IR,IQ),TSC(IR IQ),(QFC(IR.J),J=1,3), RED 2 920 4
- FSr( I R ) , DTTM( I R , IQ) ,( TTM( I R ,J , IQ) ,J=1,3 ) , FSA( I R) , DTPC( I R , IQ) , RED 2 930
- ( T PC( I R ,J , IQ) ,J=1,3 ) ,WVEL( I R) , AX0Q( IR) , EFAC( I R) RED 2 940 l CBRC 22 IF(IQ.NE.1)G0 TO 24 RED 2 950 4 22 CONTINUE RED 2 960 j C RED 2 970 i C SITE-SPECIFIC TREATMENT / DISPOSAL PARAMETERS RED 2 980 4
C RED 2 990 CBRC NOT USED IN IMPACTS-BRC RED 21000 i CBRC' READ (2,102) VINC(1),VANN(1),(ADAY(1,J),J=1,G),EMP(1),EFF(1), RED 21010 l CBRC + S E F F( 1 ) , D EN 1( 1 ) , D EN2 ( 1 ) , RM I X ( 1 ) , GER0( 1 ) ,0 SWR ,0SDL RED 21020
- CBRC TWO(1,3)=0SDL*1.E-6/ DEN 2(1) RED 21030 l CBRC WRITE (6,205)VINC(1),VANN(1),( ADAY(1,J) J=1,3),EMP(1) EFF(1), RED 21040 CBRC + S E FF( 1 ) , DEN 1( 1 ) ,0 EN2( 1 ) , RM I X ( 1 ) , GE R0( 1 ) ,0 SWR ,0SD L RED 21050
!. CBRC RED 21060
' 24 IF(IPOP.EQ.1.0R.IDAT.EQ.1.0R.IDAT.EQ.3)GO TO 28 RED 21070 C RED 21080 C MODIFY POP FOR URBAN ENVIRONMENT 4 RED 21090 C RED 21100 I i DO 26 I=1,3 RED 21110 l i
POPE (I)= POPE (I)*10. RED 21120 26 POP (I)= POP (I)*10. RED 21130 28 CLOSE (2) RED 21140 RETURN RED 21150 END RED 21160 3
A-6 v
CBRC REDS 10
$ STORAGE:2 RED 5 20 SUBROUTINE READS REDS 30 1
C REDS 40 C********************************************************************** REDS 50 C THIS SUBROUTINE READS IN THE WASTE STREAM CHARACTERISTICS REDS 60 C FROM TAPES. IT ALSO CALLS SUBROUTINE " UPTAKE" TO COMPUTE RED 5 70 C THE PATHWAY DOSE CONVERSION FACTORS AND THEN CALCULATES THE
- REDS 80 C TRANSPORTATION EXPOSURES. REDS 90 C********************************************************************* REDS 100 C RED 5 110 CBRC $LARGE REDS 120 j
CHARACTER NUCD*6, SOLD *1, BLANK *6 REDS 130
$ INCLUDE:'IMPCOMM.FOR' RED 5 140 DIMENSION NUCD(5), SOLO (5),COND(5) REDS 150 DATA BLANK /' '/ REDS 160 101 FORMAT (A10,3E10.3) REDS 170 j 102 FORMAT (ISIS) REDS 180 i 103 FORMAT (5(A6,1X,A1,E10.3,2X)) RED 5 190 104 FORMAT (/2X' WASTE: 'A10,2X' WEIGHT:'1PE9.2' MT DENSITY:' RED 5 200
- E9.2' MT/M3'//2X'ID='I2,2X'IA='I2,2X'IK1='I2,2X RED 5 210
- 'IK2='I3,2X' PROCESS ='I2/2X'IXS='4I4/2X'ICS='414) RED 5 220 j NSTR=1 RED 5 230 CALL ZER0(BAS,184) REDS 240 D0 10 I=1,85 REDS 250 SOL (I)=SOLB(I) REDS 260 10 NUX(I)=0 REDS 270 C REDS 280 C START READING WASTE STREAM CHARACTERISTICS REDS 290 C RED 5 300 READ (5,101) BASN(1), BAS (1,1),CAS(1,2), BAS (1,3) RED 5 310 READ (5,102) (ISPC(1,J),J=1,15) REDS 320 WRITE (6,104) BASN(1), BAS (1,1), BAS (1,2),(ISPC(1,J),J=1,5), REDS 330 (ISPC(1,J),J=8,15) REDS 340 CBRC WRITE WASTE STREAM HEADER ON TAPE 10 REDS 350 WRITE (10,1004) BASN(1) RED 5 360 1004 FORMAT (//2X,A10) RED 5 370 i CBRC END RED 5 380 12 READ (5,103,END=20) (NUCD(I),50LD(I),COND(I),1=1,5) RED 5 390
' IF(NUCD(1).EQ. BLANK)GO TO 20 REDS 400 DO 18 J=1,5 RED 5 410 D0 14 I=1,85 RED 5 420 IF(NUCD(J).EQ.NUC(I))GO TO 16 RED 5 430 i 14 CONTINUE REDS 440 IF(NUCD(J).EQ. BLANK)GO TO 20 REDS 450 STOP ' CANT FIND NUCLIDE NAME READ 5' REDS 460 16 NUX(I)=1 REDS 470 SOL (I)= SOLD (J) RED 5 480
- BAS (1,I+7)=COND(J) REDS 490 18 CONTINUE REDS 500 GO TO 12 REDS 510 C RED 5 520 20 CALL UPTAKE REDS 530 CBRC IQ=1 NO LONGER REFERS TO ONSITE DISPOSAL REDS 540 CBRC IF(IQ.EQ.1) RETURN RED 5 550 C RED 5 560 A-7 0
.l I
']
l 1
)
TRANSPORTATION SECTION REDS 5/0 C
C RED 5 580 l
C BAS (5) - MAXIMUM DRIVER IMPACTS ~ REDS 590 l
)
C BAS (6) - TOTAL DRIVERS IMPACTS REDS 600 C BAS (7) - POPULATION IMPACTS REDS 610 C REDS 620 Al=ISPC(1,9)/100. REDS 630 DGA=0. REDS 640 DO 22 I=1,85 REDS 650 I F( NUX( I ) . EQ .1 ) DGA= DGA+ PDC F( I ,4,5 )
- BAS ( 1, I +7 ) REDS 660 22 CONTINUE RED 5 670 DGA= DGA* BAS ( 1,2 )/( Al
- BAS ( 1,2 ) + DEN 1( IQ ) * ( 1. -A1 )) RED 5 680 CBRC ADD FACTORS FOR NUCLIDE SPECIFIC ACCOUNTING REDS 690 FAC= BAS ( 1,2 )/( Al
- BAS ( 1,2) + DEN 1( IQ) *( 1. -A1) ) REDS 700 FAC3=Al REDS 710 CBRC END REDS 720 A3= BAS (1,1)/4.534 RED 5 730 IF(ISPC(1,3).NE.0)A3=A3/0.75 RED 5 740 A4=A3/(ISPC(1,8)*A1) RED 5 750 IF(IQ.GT.3)G0 TO 24 REDS 760 A2=( C0FF( 1. ,2. ) *2. +C0FF( 1. ,4. ) *0. 5)/8760. REDS 770 I F( A4. GT . 750. ) BAS ( 1,5 )=DGA* Al
- A2
- 1. 6* 750. RED 5 780 I F( A4. LE . 750. ) BAS ( 1,5 )=DGA* Al
- A2
- 1. 6 *A4 RED 5 790 CBRC SAVE FACTOR FOR NUCLIDE-SPECIFIC CALCULATIONS REDS 800 FAC2=750. REDS 810 IF(A4.LE.750) FAC2=A4 REDS 820 CBRC END REDS 830 GO TO 26 RED 5 840 24 A2=(C0FF(1. ,2. )*5.+C0FF(1. ,4.)*0.5)/8760. REDS 850 I F( A4. GT . 250. ) EAS( 1,5 )= DGA* Al
- A2* 1. 6*250. RED 5 860 I F( A4. LE . 250. ) BAS ( 1,5)=DGA*Al
- A2* 1. 6
- A4 REDS 870 CBRC SAVE FACTOR FOR NUCLIDE-SPECIFIC CALCULATIONS REDS 880 FAC2=250. RED 5 890 IF(A4.LE.250.) FAC2=A4 RED 5 900 CBRC END REDS 910 26 BAS (1,6)=2.*DGA*A2*1.6*A3 REDS 920 Al=T POP ( I R)
- T DI S( IQ)
- T D0Z( I R )/T VE L( IQ) REDS 930 BAS ( 1,7 )=Al
- 100.
- DGA* A3
- 1. 6* C0FF( 1. ,4. )/8760. REDS 940 CBRC COMPUTE AND PRINT TRANSPORTATION IMPACTS BY NUCLIDE REDS 950
- WRITE (10,7010) REDS 960 7010 FORMAT (//2X,' TRANSPORTATION ICRP IMPACTS BY NUCLIDE (MREM /YR)'// RED 5 970
- 2X,'NUC RED 5 980 MAX INDIVIDUAL'/)
FAC4= FAC* FAC2* FAC3*A2 *1.6 RED 5 990 TRNT0T=0.0 RED 51003 DO 30 I=1,85 RED 51010 IF(NUX(I).NE.1) GOTO 30 RE051020 D0ST= FAC4
- PDC F( I ,4 ,5 )
- BAS ( 1, I + 7 )
RE051030 WRITE (10,7020) NUC(I),DOST RED 51040 7020 FORMAT (2X,A6,4X,1PE12.3) RED 51050 TRNTOT=TRNT0T+DOST RE051060 30 CONTINUE RE051070 WRITE (10,7030) TRNTOT RED 51080 7030 FORMAT (/2X,' TOTAL TRANSPORTATION IMPACTS =', RED 51090
- RED 51100 IPE12.3)
CBRC END RED 51110 RETURN RED 51120 END RED 51130 A-8
CBRC UPTK 10
$ STORAGE:2 UPTK 20 SUBROUTINE UPTAKE UPTK 30 C UPTK 40 C*********************************************************************
- UPTK 50 C THIS SUBROUTINE READS IN (TAPE 1) THE FUNDAMENTAL DOSE UPTK 60 C CONVERSION FACTORS AND RELATED NUCLIDE-SPECIFIC PARAMETERS UPTK 70 C AND UPTAKE FACTORS, AND CALCULATES THE PATHWAY DOSE CONVERSION
- UPTK 80 C FACTORS USED IN DETERMINING THE IMPACTS IN THE REMAINDER OF UPTK 90 C THIS CODE. INCORPORATED ARE 85 RADIONUCLIDES,10 BODY ORGANS
- UPTK 100 C AND 7 MAJOR EXPOSURE PATHWAYS. SEE APPENDIX D OF VOLUME 1. UPTK 110 C********************************************************************* UPTK 120 C UPTK 130 CBRC $LARGE UPTK 140 CHARACTER BASN*10,NUC*6,50L*1,50LB*1,IFA9*6,IPAl*6,IPAS*6, UPTK 150
- NUCT*6,SOLT*1 UPTK 160 COMMON /8 AST/ BAS COM( 834 ) , I S PC( 2 ,15 ) , PDC F( 85 ,10,7 ) UPTK 170
+ /CH RC/BASN( 2 ) , NUC( 85) ,50 L( 85 ) ,50 LB( 85 ) UPTK 180
+ /NUCS/AL( 85 ) , FMF( 85 ) , RET ( 85,5) , FRACT( 85,3) , NUX( 85) UPTK 190 COMMON /DC FS/ FF( 85,5 ) ,0C F1 ( 159,10 ) , DC F2 ( 159,10 ) ,0C F3 ( 85 ) , UPTK 100
+ DC F4 ( 85,10 ) ,0C F5 ( 85,10 ) , NUCT( 159 ) ,50 LT( 159 ) UPTK 210 COMMON /UPTK/V 1, V2, S 1, S2, Z , R I , R , CY , D , F2, F3, F5, F7, UPTK 220
+ F8, F8P, F11, F13, F13P, F14, F15, F18 UPTK 230 DATA IPA 9, IPA 1,IPAS/'I-129 ','I-131 ','I-125 '/ UPTK 240 00 80 INUC=1,85 UPTK 250 00 10 IJ=1,159 UPTK 260 INCT=IJ UPTK 270 IF(NUCl(INCT).EQ.NUC(INUC))GO TO 20 UPTK 280 10 CONTINUE UPTK 290 STOP ' CANT FIND NUCLIDE NAME IN NUCT' UPTK 300 20 IF(50LT(INCT).EQ.50L(INUC)) GO TO 50 UPTK 310 INCT=INCT+1 UPTK 320
- IF(NUCT(INCT).NE.NUC(INUC))GO TO 40 UPTK 330 GO TO 20 UPTK 340 40 WRITE (6,101) NUC(INUC),50L(INUC),NUCT(INCT),50LT(INCT) ~
UPTK 350 101 FORMAT (//2X,2(A6,2X,A1,2X)) UPTK 360 STOP ' CANT FIN 3 SOLUBILITIES FOR NUCT' UPTK 370 50 PTP=F2+F3*(FF(INUC,2)*F5+FF(INUC,3)*F7*365.) UPTK 380 PT=PTP* FF( INUC ,1) UPTK 390 FT= F8* FF( I NUC ,2 )
- F5+ F8P
- FF( I NUC ,3 )
- F7
- 365. + F11 UPTK 400 F12N=FF(INUC,4)*F13+FF(INUC,5)*F13P UPTK 410 V=V1 UPTK 420 IF(NUC(INUC) .EQ. IPA 9)V=V2 UPTK 430 IF(NUC(INUC).EQ. IPA 1)V=V2 UPTK 440 IF(NUC(INUC).EQ. IPA 5)V=V2 UPTK 450 D1=86400.*V/(S2*Z) UPTK 460 D2=86400.*R*V/S1 UPTK 470 W1=RI/(S2*Z) UPTK 480 W2=R*RI/S1 UPTK 490 DO 70 10=1,10 UPTK 500 Al= F18* ( F14 *( F15
- DC F2( I NCT , IO) +DC F5( I NUC , IO) +Al *01 UPTK 520 PDCF(INUC,IO,2)=F15*DCF2(INCT IO)+DCF5(INUC,IO)+0.242*Al*D1 UPTK 530 PDCF(INUC,10,3)=PDCF(INUC,10,1)+(01*PT+(02/CY)*PTP)*DCF1(INCT,10) UPTK 540 PDC F( I NU C , I O ,4 ) =( PT/D )
- PT+( W2/CY )
- P TP+ FT/1000. ) *DC F1( I NCT , IO) +W1 *Al UPTK 570 PDC F( INUC ,10,7 )= PDC F( I NUC , IO ,6) +( F12N/1000. ) *DC F1( INCT ,10) UPTK 580 DO 60 J=1,7 UPTK 590 60 PDCF(INUC,IO,J)=PDCF(INUC,IO,J)*1.E+12 UPTK 600 70 CONTINUE UPTK 610 80 CONTINUE UPTK 620 RETURN UPTK 630 END UPTK 640
,g
4 CBRC SPLC 10
$ STORAGE:2 SPLC 20 SUBROUTINE SPLICE SPLC 30 C SPLC 40 C*********************************************************************
- SPLC 50 C THIS SUBROUTINE ACCOUNTS FOR THE POSSIBLE DIVISION OF A WASTE SPLC 60 C STREAM INTO SUB-STREAMS (MAXIMUM 0F 3) BASED ON SELECTED WASTE
- SPLC 70 C SORTING OPTIONS AT A MUNICIPAL WASTE INCINERATOR. IT ALSO SPLC 80 C CALLS SUBROUTINES TO CALCULATE INCINERATION AND SORTING / SPLC 90 C RECOVERY IMPACTS, AND ANY IMPACTS ASSOCIATED WITH RECYCLED
- SPLC 100 C********************************************************************* SPLC 110 C SPLC 120 CBRC SLARGE SPLC 130
$ INCLUDE:'IMPCOMM.FOR' SPLC 140 ISTR=1 SPLC 150 )
C SPLC 160 ,
C DO METAL PACKAGE RECYCLING SPLC 170 C SPLC 180 IF(ISPC(ISTR,3).NE.1.0R.ISPC(ISTR,4).EQ.0)GO TO 20 SPLC 190 CALL RECYCL(ISTR,0.,0.,0 ,1) SPLC 200 20 11=IQ SPLC 210 12=ISPC(ISTR,5) SPLC 220 IF(12.EQ.1) RETURN SPLC 230 16=ISPC(ISTR,12) SPLC 240 17=ISPC(ISTR,13) SPLC 250 18=ISPC(ISTR,14) SPLC 260
, 19=ISPC(ISTR,15) SPLC 270 IF(12.GT.3)G0 TO 30 SPLC 280
! C SPLC 290 C SECTION BELOW FOR INCINERATE / DISPOSE AND SORTING OPTION 1 SPLC 300 C SPLC 310 CALL INCIMP(11,I2,ISTR) SPLC 320 WRF=2.0 SPLC 330
- CBRC IF(IQ.EQ.1) WRF=0 SWR SPLC 340 CBRC USE OSWR FOR VOLUME REDUCTION IF INPUT (ORIGINALLY IQ=1) SPLC 350 IF(OSWR.GT.O.) WRF=0 SWR SPLC 360 BAS (ISTR,1)= BAS (ISTR,1)/WRF SPLC 370 BAS (ISTR,2)=0.89 SPLC 380 BAS (ISTR,3)= BAS (ISTR,1)/ BAS (ISTR,2) SPLC 390
- DO 24 J=8,92 .SPLC 400 l 24 BAS (ISTR,J)= BAS (ISTR,J)*WRF SPLC 410 ISPC(ISTR,1)=3 SPLC 420 ISPC(ISTR,2)=1 SPLC 430 ISPC(ISTR,3)=0 SPLC 440 ISPC(ISTR,5)=1 SPLC 450 RETURN SPLC 460 ;
C SPLC 470 '
C SECTION BELOW FOR SORTING OPTION 2 SPLC 480 C SPLC 490 30Al=(0.95"I6+0.05*I7+0.05*I8+0.10*I9)/100. SPLC 500 l A2=(0.05*I6+0.05*I7+0.10*I8+0.90*I9)/100. SPLC 510 '
A3= BAS (ISTR,1) SPLC 520 ,
NSTR=NSTR+1 SPLC 530 1 DO 32 J=1,92 SPLC 540 l 32 BAS (NSTR,J)= BAS (ISTR,J) SPLC 550 DO 34 J=1,15 SPLC 560 34 ISPC(NSTR,J)=ISPC(ISTR,J) SPLC 570 BASN(NSTR)=BASN(ISTR) SPLC 580 C SPLC 590 A-10
i C RESIDUE SECTION SPLC 600
'C SPLC 610 BAS (ISTR,1)= BAS (ISTR,1)/9.40 SPLC 620 BAS (ISTR,2)=.89 SPLC 630 BAS (ISTR,3)= BAS (ISTR,1)/ BAS (ISTR,2) SPLC 640 DO 36 J=8,92 SPLC 650 36 BAS (ISTR,J)= BAS (ISTR,J)*Al*9.40 SPLC 660 CALL INCIMP(II,12,ISTR) SPLC 670 ISPC(ISTR,1)=3 SPLC 680 ISPC(ISTR,2)=1 SPLC 690 ISPC(ISTR,3)=0 SPLC 700 ISPC(ISTR,5)=1 SPLC 710 IF(12.EQ.5) GO TO 40 SPLC 720 C SPLC 730 C OISCARD MATERIAL SECTION SPLC 740 C SPLC 750 BAS (NSTR,1)= BAS (NSTR,1)*(1. -A1) SPLC 760 BAS (NSTR,2)=0.62 SPLC 770 BAS (NSTR,3)= BAS (NSTR,1)/ BAS (NSTR,2) SPLC 780 BAS (NSTR,6)=0. SPLC 790 BAS (NSTR,7)=0. SPLC 800 ISPC(NSTR,1)=1 SPLC 810 ISPC(NSTR,2)=2 SPLC 820 ISPC(NSTR,3)=0 SPLC 830 ISPC(NSTR,5)=1 SPLC 840 RETURN SPLC 850 C SPLC 860 C SECTION BELOW FOR SORTING OPTION 3 SPLC 870 C
SPLC 880 40 BAS (NSTR,1)= BAS (NSTR,1)*A2 SPLC 890 BAS (NSTR,2)=0.84 SPLC 900 BAS (NSTR,3)= BAS (NSTR,1)/ BAS (NSTR,2) SPLC 910 BAS (NSTR,6)=0. SPLC 920 BAS (NSTR,7)=0. SPLC 930 ISPC(NSTR,1)=1 SPLC 940 ISPC(NSTR,2)=2 SPLC 950 ISPC(NSTR,3)=0 SPLC 960 ISPC(NSTR,5)=1 SPLC 970 C .
SPLC 980 C RECYCLE OF SCRAP METAL AND GLASS SPLC 990 C >
SPLC1000 I F(17.EQ.0. AND.18. EQ. 0) RETURN 5PLC1010 A4=A3*(1.-Al-A2) SPLC1020 A5=.9*I7+.85*I8 SPLC1030 WT1=.9'A4*I7/A5 SPLC1040 WT2=A4-WT1 SPLC1050 CALL RECYCL(ISTR,WT1,WT2,A3,2) SPLC1060 RETURN SPLC1070 END SPLC1080 A-11
.CBRC RECY 10
$ STORAGE:2 RECY 20 SUBROUTINE RECYCL(ISTR,WT1,WT2,WTOT,NX) RECY 30 C RECY 40 C********************************************************************** RECY 50 C THIS SUBROUTINE CALCULATES IMPACTS RESULTING FROM RECYCLE RECY 60 C 0F CONTAMINATED MATERIALS. THERE ARE AT PRESENT 3 RECYCLE RECY 70 C SCENARIOS CONSIDERED: RECYCLE OF METAL CONTAINERS; RECYCLE RECY 80 C 0F THE METAL FRACTION OF THE WASTE STREAM COMPOSITION; ANO RECY 90 C RECYCLE OF THE GLASS FRACTION. RECY 100 C********************************************************************* RECY 110 C RECY 120 CBRC $LARGE RECY 130 i $ INCLUDE:'IMPCOMM.FOR' RECY 140 DIMENSION RI(85),RP(85) RECY 150 l
! CBRC ARRAY TO SAVE METAL RECYCLE IMPACTS RECY 160 DIMENSION BRC3(83) RECY 170 DATA RI/2.13E-05,. 41E-07,7.15E-02,1.96E-03,2.85E-04,1.92E-04, RECY 180
+ 8.17E-04,2.25E-04,6.57E-02,1.07E-01,2.20E-02,7.30E-01, RECY 190
+ 2. 60 E-02 ,3. 9 s E-03,1. 80 E-02 ,8. 20 E-02,1. 53 E-06 ,3. 80 E-06, RECY 200
+ 1.40E-02,1.22E-02,2.03E-03,1.71E-02,1,15E-04,6.25E-04, RECY 210
+ 5.60E-02,5.10E-02,1.83E-04,1.26E-03,4.63E-07,4.08E-03, RECY 220
+ 8. 50E- 03 ,6 .10 E-03 ,4 . 80 E-02 ,8 . 89 E-02 ,8 . 98E-04 ,8. 36 E-03 , RECY 230
+ 6.50E-02,5.91E-02,3.51E-04,1.40E-03,9.80E-05,6.56E-04, RECY 240
+ 4.60E-02,2.40E-04,7.02E-02,1.90E-02,8.81E-04,7.38E-02, RECY 250
+ 5.47E-04,1.54E-03,1.91E-03,3.72E-02,1.01E-02,8.24E-03, RECY 260
+ 1.13E-01,6.56E+00,2.59E-02,2.99E+00,1.34E+00,5.89E+00, RECY 270
+ 8.92E-01,9.97E-02,8.54E-02,1.57E-01,1,13E-01,1,03E-01, RECY 280
+ 8.80E-04,2.71E-03,9.57E-02,1.62E-03,9.17E-01,1.23E-01, RECY 290
+ 1.17 E-01,1.10 E-01,1,10 E-01,1,19 E-06 ,1, 04 E-01,1. 09 E+ 00 , RECY 300
+ 9.00E-02,9.21E-01.1.30E-01,4.92E-01,1.24E-01,1.08E-01, RECY 310
+ 4.58E-03/ RECY 320 DATA RP/2.95E+00,7.80E-01.1.23E403,1.83E+01,2.66E+00,1.89E+00, RECY 330
. 2.26E+02,3.52E+00,2.77E+02,4.27E+00,1.31E+02,5.69E-01, RECY 340
. 6.93E+00,2.61E+01,1,00E+01,2.61E+03,4.66E+00,1.04E-01, RECY 350
. 6.52E+01,5.59E+01,1.89E+01,6.98E+01,6.39E-02,1.25E+02, RECY 360
. 2.48E+01,6.13E+03,1.71E+00,1,18E+01,1.87E+00,1.64E+01, RECY 370
. 2.22E+00,4.38E+01,1.46E+03,5.67E+02,8.42E+00,3.77E+01, RECY 380
. 7.81E+03,2.41E+02,1.45E+01,5.71E+00,1.18E+01,6.11E+00, RECY 390 6.01E+02,6.50E+01,2.82E+02,2.10E+03,8.21E+00,2.96E+02, RECY 400
. 5.08E+00,1.11E+01,2.70E+02,2.57E+03,4.05E+01,8.15E+00, RECY 410
. 4.21E-01,3.38E+02,3.97E+01,1.50E+03,1.35E+03,9.96E+02, RECY 420
. 1.38E+03,9.35E+00,8.00E+00,2.42E+02,9.25E+00,9.59E+00, RECY 430
. 6.24E+00,9.44E+02,8.95E+00,2.32E+02,1.54E+03,1.77E+00, RECY 440
. 9.81E+00,1.03E+01,1.03E+01,9.51E-04,9.68E+00,1.68E+03, RECY 450 ,
- 1. 36 E+02,1. 42 E+03,3. 67 E-01,5. 65 E+02,6. 94 E+00,9. 96 E+ 00, dECY 460 l
. 1.02E+00/ RECY 470 DATA PAKF, FIND,FPOP,DISF/1.E-3,0.33,0.46,0.9738/, RECY 480
- WMET,WGLS/857.,90./ RECY 490 RECY 500 101 FORMAT (/2X' METAL PACKAGE RECYCLE IMPACTS'3X'MAXIND r'
- 1PE9.2' MREM /YR'/34X'P3PULN ='E9.2' PERSON-MREM /30 YRS') RECY 510 RECY 520 102 FORMAT (/2X' METAL MATERIAL RECYCLE IMPACTS'2X'MAXIND ='
- 1PE9.2' MREM /YR'/34X'POPULN ='E9.2' PERSON-MREM /30 YRS') RECY 530 RECY 540 103 FORMAT (/2X' GLASS MATERIAL RECYCLE IMPACTS'2X'MAXIND ='
- 1PE9.2' MREM /YR'/34X'POPULN ='E9.2' PERSON-MREM /30 YRS') RECY 550 RECY 560 IF(NX.NE.1)GO TO 20 C
RECY 570 A-12
C METAL PACKAGE RECYCLE RECY 580 C RECY 590 IP=ISPC(ISTR,5) RECY 600 I F( I P . NE .1 ) FCORR= 1. / I SPC( I ST R ,10 ) RECY 610 I F( I P . EQ .1 ) FCORR= 1. / I S PC ( I STR ,11 ) RECY 620 Al=0. RECY 630 A2=0. RECY 640 CBRC PRINT HEADER FOR TAPE 10 OUTPUT RECY 650 WRITE (10,7030) RECY 660 7000 FORMAT (//2X,' METAL PACKAGE RECYCLE ICRP IMPACTS BY ', RECY 670 l
t
'NUCLIDE (MREM /YR)'// RECY 680
- 2X,'NUC DOSIND'/) RECY 690 BRC1=0.01*ISPC(ISTR,4)*PAKF* BAS (ISTR,1)/0.0009*flND*FCORR RECY 700 BRCTOT=0.0 RECY 710 CBRC END RECY 720 00 10 I=1,85 RECY 730 IF(NUX(I).EQ.0)GO TO 10 RECY 740 Al=A1+ BAS (ISTR,I+7)*RI(I) RECY 750 A2=A2+ BAS (ISTR,I+7)*RP(I) RECY 760 CBRC PRINT IMPACT FOR EACH NUCLIDE RECY 770 BRC2=BRCl* BAS (ISTR,I+7)*RI(I) RECY 780 WRITE (10.7010) NUC(I),BRC2 RECY 790 7010 FO*" . ...A6,3X,1PE12.3) RECY 800 BRC10T=BRCTOT+BRC2 RECY 810 CBRC END RECY 820 10 CONTINUE RECY 830 CBRC PRINT TOTAL IMPACT RECY 840 WRITE (10,7015) BRCTOT RECY 850 7015 FORMAT (/2X,' TOTAL RECYCLE IMPACT =',1PE12.3) RECY 860 CBRC END RECY 870 A3=0.01*ISPC(ISTR,4)*PAKF* BAS (ISTR,1)/0.0009 RECY 880 Al= FIND *FCORR*A3*Al RECY 890 A2=FP0P*A3*A2 RECY 900 WRITE (6,101) A1, A2 RECY 910 RETURN RECY 920 C RECY 930 C METAL FRACTION RECYCLE RECY 940 C RECY 950 20 Al=C. RECY 960 A2=0. RECY 970 CBRC PRINT HEADER FOR TAPE 10 OUTPUT RECY 980 WRITE (10,7020) RECY 990 7020 FORMAT (//2X,' METAL AND GLASS RECYCLE ICRP IMPACTS BY NUCLIDE'// RECY1000 2X,'**** IMPACTS ARE NOT NORMALIZED BY NUMBER OF ', RECY1010
' FACILITIES ****'// RECY1020 2X,' NUC METAL IND GLASS IND'/) RECY1030 BRC1= FIND *WT1/(0.0009aISPC(1,10)) RECY1040 CBRC END RECY1050 DO 30 I=1,85 RECY1060 IF(NUX(I).EQ.0)GO TO 30 RECY1070 Al=A1+ BAS (NSTR,1+7)*RI(I) RECY1080 A2=A2+ BAS (NSTR,1+7)*RP(I) RECY1990 CBRC SAVE METAL RECYCLE IMPACT FOR THIS NUCLIDE RECY1100 BRC3(I)=BRCl* BAS (NSTR,1+7)*RI(I) RECY1110 73 CONTINUE RECY1120 A l = FI N0
- WT 1 *A1/( 0. 0009
- I S PC ( 1,10 ) ) RECY1130 A2=FPOP*WT1*A2/0.0009 RECY1140 WRITE (6,102) A1 A2 RECY1150 C RECY1160 A-13
C GLASS FRACTION RECYCLE RECY1170 C RECY1180 FCORR=WT2/(ISPC(1,10)*WGLS) RECY1190 Al=0. RECY1200 A3=0. RECY1210 CBRC FACTOR FOR GLASS IMPACTS RECY1220 BRC1=FCORR*0.3*0lSF*1.6*0.6936*0.0228 RECY1230 00 40 I=1,85 RECY1240 IF(NUX(I).EQ.0)GO TO 40 RECY1250 Al=A1+ BAS ( NSTR ,1+7)*PDCF(I ,4,5) RECY1260 Y=EXM( AL(I)) RECY1270 X=EXM(AL(I)*30.) RECY1280 Z=1.0 RECY1290 IF(Y.NE.1. ) Z=(1..-X)/(30.*(1.-Y)) RECY1300 A3=A3 + Z
- BAS ( N ST R , I + 7 )
- BAS ( N ST R ,1 +7 )
- PDC F( I ,4 ,5 ) RECY1330 WRITE (10,7030) NUC(I),BRC3(I),BRC2 RECY1340 7030 FORMAT (2X,A6,3X,1P2E12.3) RECY1350 CBRC END RECY1360 40 CONTINUE RECY1370 A2=0.3*DISF*1.6*.6936 RECY1380 Al=FCORR*A2*Al*.0228 RECY1390 A3=FCORR*A2*A3*ISPC(1,10)*52. RECY1400 WRITE (6,103) A1,A3 RECY1410 RETUR!1 REC 11420 END RECY1430 i
o A-14
l -
1 CBRC INCI 10
$5TORAGE:2 INCI 20 SUBROUTINEINCIMP(II,I2,ISTR) INCI 30 C INCI 40 C********************************************************************=* INCI 50 C THIS SUBROUTINE CALCULATES THE IMPACTS ASSOCIATED WITH THE INCI 60 C INCINERATION OF WASTE STREAMS. IMPACTS ARE CALCULATED FOR INCI 70 C BOTH FACILITY WORKERS AND MEMBERS OF THE SURROUNDING INCI 80 C POPULATION.
INCI 90 C********************************************************************* INCI 100 C INCI 110 CBRC $LARGE INCI 120
$ INCLUDE:'IMPCOMM.FOR' INCI 130 DIMENSION QT1(10),QT3(10),QT5(10) INCI 140 CBRC ADD DOSNUC ARRAY FOR NUCLIDE CALCULATIONS INCI 150 DIMENSION DOSNUC(3,85) INCI 160 C INCI 170 C BIMP(7) - 0FFSITE POPULATION - INCINERATION IMPACTS INCI 180 C BIMP(8) - MAXIMUM INDIVIDUAL - INCINERATION IMPACTS INCI 190 C BIMP(9) - ALL WORKERS - INCINERATION IMPACTS INCI 200 C BIMP(10) - MAXIMUM WORKER - INCINERATION IMPACTS INCI 210 C INCI 220 IF(12.EQ.1) RETURN INCI 230 I4=ISPC(ISTR,1) INCI 240 FDS=1.0 INCI 250 I F(I4. LT.3)FDS=10.* *(I4-3) INCI 260 I4=ISPC(ISTR,2) INCI 270 FAC=1.0 INCI 280 IF(14.GT.1)FAC=10.**(1-14) INCI 290 C INCI 300 C SUM THE GENERIC IMPACT CONSTANTS INCI 310 C INCI 320 CALL ZER0(QT1,10) INCI 330 CALLZER0(QT3,10) INCI 340 CALL ZER0(QT5,10) INCI 350 CBRC CLEAR ARRAY OF NUCLIDE-SPECIFIC DOSES INCI 360 CALL ZER0(DOSNUC 255) INCI 370 DO 14 J=1,85 INCI 380 IF(NUX(J).EQ.0)GO TO 14 INCI 390 Al=FRACT(J,2) INCI 400 CBRC I F( I I . EQ .1. 0R . I I . GT . 3 ) Al= F RACT(J ,1 ) INCI 410 IF(II.EQ.1.0R.II.EQ 3) Al=FRACT(J,1) INCI 420 IF(II.GT.3) Al=FRACT(J,3) INCI 430 CBRC END INCI 440 10 D0 12 I=1,10 INCI 450 QT 1( I )=QT 1( I ) + BAS ( I ST R ,J +7 )
- PDC F(J , I ,3 )
- Al INCI 470 12 QTS (I)=QT5(I)+ BAS (ISTR,J+7)*PDCF(J,I,5) INCI 480 CBRC RETAIN ICRP IMPACT FOR EACH NUCLIDE INCI 490 BASNUC= BAS (ISTR J+7) INCI 500 DOSNUC(1,J)=BASNUC*PDCF(J,10,1) INCI 510 DOSNUC( 2,J )= BASNUC* PDC F(J ,10,3 ) *Al INCI 520 DOSNUC(3,J)=BASNUC*PDCF(J ,10,5) INCI 530 CBRC END INCI 540 C INCI 550 A-15
C SUBSTRACT AIRBORNE RELEASE FRACTION INCL 560 C INCI 570 BAS ( I ST R , J + 7 ) = BAS ( I ST R ,J +7 ) * ( 1. -A1 ) INCI 580 14 CONTINUE INCI 590 CBRC WRITE HEADER ON TAPE 10 INCI 600 WRITE (10,7000) INCI 610
- 7000 FORMAT (//2X,' INCINERATION ICRP IMPACTS BY NUCLIDE (MREM /YR)'// INCI 620 1
- 2X,'**** IMPACTS NOT NORMALIZED BY NUMBER OF ', INCI 630 4
' PROCESSING FACILITIES ****'//2X, INCI 640
- 'NUC MAXIMUM OFF-SITE INDIVIDUAL '/) INCI 650 CBRC END INCI 660
' INCI 670 C
C START OFF-SITE IMPACT CALCULATIONS INCI 680 C INCI 690 DO 20 I=1,10 INCI 700 Al=QT3(I)* BAS (ISTR,1) INCI 710 BIMP(1,7)=BIMP(I,7)+Al* POP (IR) INCI 720 20 BIMP(I,8)=BIMP(I,8)+Al*XDQI(II)*EDFI(II) INCI 730 CBRC COM!UTE AND PRINT ICRP IMPACTS BY NUCLIDE INCI 740 FAC MAS = BAS ( I STR ,1 )
- X0Q I ( I I )
- ED FI ( I I ) INCI 750 00ST=0.0 INCI 760 D0 21 J=1,85 INCI 770 IF(NUX(J).EQ.0) GOTO 21 INCI 780 D058=DOSNUC(2,J)*FACMAS INCI 790 WRITE (10,7010) NUC(J), DOS 8 INCI 800 7010 FORMAT (2X,A6,4X,1PE10.3) INCI 810 DOST=DOST+ DOS 8 INCI 820 21 CONTINUE INCI 830 WRITE (10,7015) DOST INCI 840
! 7015 FORMAT (/2X,' TOTAL NON-NORMALIZED INCINERATOR IMPACT =',1 PIE 12.3) INCI 850 CBRC END INCI 860 CBRC WORKER IMPACTS ARE COMPUTED FOR ONSITE INCINERATION INCI 870 CBRC IF(II .EQ.1) RETURN INCI 880 C INCI 890 C START WORKER IMPACT CALCULATIONS INCI 900-C INCI 910 Al=0.237* BAS (ISTR,1)/VINC(II) INCI 920 ADS L=Al*TWI(II ,1)* FDS INCI 930 i
ADSM=Al*TWI(II,2)*FDS INCI 940 ADSHRH=Al*TWI(II,3) INCI 950 ADS HM L=Al
- TWI ( I I ,3 )
- 0. 5 * ( 1. + FDS ) INCI 960 Al=Al*FAC*1.6/ DEN 1(II) INCI 970 ADGL=Al*D0FF(30. ) INCI 980 ADGM=Al* D0FF(10. ) INCI 990 ADGH=Al* DOFF (1.) INCIl000 DO 30 I=1,10 INCIl010 Al=QT1(I)*ADSL+QT5(I)*ADGL INCIl020 A2=QT1(I)*ADSL+QT5(I)*ADGM INCIl030 A3=QTI(I)*ADSM+ QTS (I)*ADGM INCIl040 A4=QTI(I)*ADSM+ QTS (I)*ADGH INCIl050 AS=QTI(I)*ADSHRH+ QTS (I)*ADGH INCIl060 A6=QT1(I)*ADSHML+QT5(I)*ADGH INCIl070 C INCIl080 A-16
C SELECT THE MAXIMUN WORKER INCIl090 C INCI1100 l A7=AMAXI(A1,A2,A3,A4,AS,A6) INCI1110 I F( A7. GT . B IMP ( I ,10) ) B IMP ( I ,10 ) =A7 INCI1120 l CBRC GO TO (30,22,22,24,24),11 INCI1130 GO T0 (22,22,24,24,24),11 INCI1140 22 DUM=2.*A1+2.*A2+8.*A3+6.*A4+4.*A5+8.*A6 INCI1150 IF(12.EQ.3)DUM=DUM+2.*A3+A4 INCI1160 IF(12.EQ.4)DUM=DUM+3.*A3+A4+A6 INCI1170 IF(I2.EQ.5)DUM=DUM+2.*A2+4.*A3+2.*A4+2.*A6 INCI1180 GO TO 26 INCI1190 24 DUM=6.*A1+2.*A2+4 *A3+2.*A4+2.*A5+2.*A6 INCI1200 26 BIMP(I,9)=BIMP(I,9)+DUM INCI1210 30 CONTINUE INCI1220 CBRC ICRP IMPACTS BY NUCLIDE FOR WORKERS INCI1230 WRITE (10,7020) INCI1240 7020 FORMAT (//2X,' WORKER INCINERATION ICRP IMPACTS BY NUCLIDE ', INCI1250
- '(MREM /YR)'//2X,'**** IMPACTS ARE NOT NORMALIZED BY ', INCI1260
' NUMBER OF PROCESSING FACILITIES ****'// INCI1270
- 2X,'NUC RESIDUE HANDLERS MAINTENANCE'/) INCI1280 AST=0.0 INCI1290
,, A6T=0.0 INCI1300 DO 40 J=1,85 INCI1310 IF(NUX(J).EQ.0) GOTO 40 INCI1320 D1=DOSNUC(1,J) INCI1330 D3=DOSNUC(3,J) INCI1340 A5=D1*ADSHRH+D3*ADGH INCI1350 A6=D1*ADSHML+D3*ADGH INC11360 WRITE (10,7030) NUC(J),AS,A6 INCI1370 7030 FORMAT (2X A6,3X,1P2E12.3) INCI1380 AST=AST+A5 INCI1390 A6T=A6T+A6 INCI1400 40 CONTINUE INCI1410 WRITE (10,7035) AST,A6T INCI1420 7035 FORMAT (/2X,' TOTAL NON-NORMALIZED WORKER IMPACTS'/11X,1P2E12.3) INCI1430 CBRC END INCI1440 RETURN INCI1450 END INCI1460 A-17
. - _ _ . - =-
l CBRC INTI 10
$ STORAGE:2 INTI 20 SUBROUTINE INTIMP INTI 30 C INTI 40 C********************************************************************* INTI 50 C THIS SUBROUTINE CALCULATES THE INADVERlANT INTRUDER IMPACTS
- INTI 60 C FOR THE CONSTRUCTION AND AGRICULTURE SCENARIOS.
- INTI 70 C********************************************************************* INTI 80 C INTI 90 CBRC $LARGE INTI 100
$1NCLUDE:'IMPCOMM.FOR' INTI 110 DATA CONST/2.51E-5/ INTI 120 C INTI 130 C BIMP(1) - INTRUDER-CONSTRUCTION IMPACTS INTI 140 C BIMP(2) - INTRUDER-AGRICULTURE IMPACTS INTI 150 i
C INTI 160 <
CBRC EACH STREAM HANDLED SEPARATELY INTI 170 CBRC DO 60 ISTR=1,NSTR INTI 180 ISTR=1 INTI 190 FD S= EMP( IQ)
- BAS ( I ST R ,1)/ VANN( IQ) INTI 200 C8RC IF(IQ.EQ.1)FDS=FDS*SEFF(IQ) INTI 210 A9=1.0 INTI 220 IF(ISPC(ISTR,2).GT.1) A9=0.1 INTI 230 GDEL=IINS INTI 240 CBRC PRINT HEADER FOR TAPE 10 FOR NUCLIDE IMPACT OUTPUT INTI 250 WRITE (10,7000) INTI 260 7000 FORMAT (//2X,' INTRUDER ICRP IMPACTS BY NUCLIDE (MREM /YR)'// INTI 270
- 2X,'**** IMPACTS ARE NOT NORMALIZED BY NUMBER ', INTI 280
'0F DISPOSAL FACILITIES ****'// INTI 290 2X,'NUC CONSTRUCTION AGRICULTURE'/) INTI 300 CONT 0T=0.0 INTI 310 AGRTOT=0.0 INTI 320 3
CBRC END INTI 330 l DO 50 INUC=1,85 INTI 340 IF(NUX(INUC).EQ.0)GO TO 50 INTI 350 Al=FDS*A9" BAS (ISTR,INUC+7) INTI 360 CALL CHNS(INUC,GDEL,IEN,IBG,NCH) INTI 370 DO 40 I=1,10 INTI 380 CALL CALI(INUC,I,C1,C2,C3,C4,IEN,IBG,NCH) INTI 390 A2=C1 INTI 400 B5=RMII(IQ)*Al*A2*0.27 INTI 410 B2=Al*A2*0.057 INTI 420 Bl=Al*FSC(IR)*C2 INTI 430 B3=RMIX(IQ)*Al*FSA(IR)*C3 INTI 440 B4=RMIX(IQ)*0.5*Al*C4 INTI 450 BIMP(I,1)=BIMP(I,1)+Bl+B2 INTI 460 40 BIMP(I,2)=BIMP(I,2)+B3+B4+B5 INTI 470 CBRC PRINT ICRP (I=10) IMPACT FOR EACH NUCLIDE INTI 480 CONINT=Bl+B2 INTI 490 AGRINT=B3+B4+B5 INTI 500 WRITE (10,7010) NUC(INUC),CONINT,AGRINT INTI 510 7010 F10RMAT(2X,A6,3X,1P2E12.3) INTI 520 CONT 0T= CONT 0T+CONINT INTI 530 AGRTOT=AGRTOT+AGRINT INTI 540 CBRC END INTI 550 A-18
50 CONTINUE INTI 560 A1 AL(57)*IINS INTI 570 A2=AL(62)*IINS INTI 580 l RAD = BAS (ISTR,64)*EXM(A1) INTI 590 l I F( A1.NE. A2) RAD = RAD + BAS (ISTR,69)*Al*( EXM( A1)-EXM( A2))/( A2-A1) INTI 600 RAD = RAD *FDS*CONST INTI 610 00 55 I=1,10 INTI 620 55 BIMP(I 2)=BIMP(I,2)+ RAD *PDCF(56,I,2) INTI 630 CBRC PRINT ICRP (I=10) IMPACT FOR RADON INTI 640
, AGRINT= RAD *PDCF(56,10,2) INTI 650
- WRITE (10,7020) AGRINT INTI 660 3
7020 FORMAT (2X,' RAD 0N',16X,1PE12.3) INTI 670
.AGRTOT=AGRTOT+AGRINT INTI 680 WRITE (10,7025) CONT 0T,AGRTOT INTI 690 7025 FORMAT (/2X,' TOTAL NON-NORMALIZED INTRUDER IMPACTS'/ INTI 700 ,
11X,1P2E12.3) INTI 710 t CBRC END INTI 720 60 CONTINUE INTI 730 C INTI 740 RETURN INTI 750
- END INTI 760 4
1 l
l l
1 J
A-19
CBRC EXPW 10
$ STORAGE:2 EXPW 20 SUBROUTINE EXPWAS EXPW 30 i C EXPW 40 l C*********************************************************************
- EXPW 50 C THIS SUBROUTINE CALCULATES THE IMPACTS FROM THE INTRUDER- EXPW 60 C INITIATED AND EROSION INITIATED EXPOSED WASTE SCENARIOS. EXPW 70 C********************************************************************* EXPW 80 C EXPW 90 CBRC $LARGE EXPW 100
$ INCLUDE:'IMPCOMM.FOR' EXPW 110 COMMON /CHYN/NXUC(85),ICH(8,10),LCH(10),ACT(8),BCT(8,2) EXPW 120 C EXPW 130 C BIMP(3) - INTRUDER-AIR IMPACTS EXPW 140 C BIMP(4) - EROSION-AIR IMPACTS EXPW 150 C BIMP(5) - INTRUDER-WATER IMPACTS EXPW 160 C BIMP(6) - EROSION-WATER IMPACTS EXPW 170 C EXPW 180 GREC=IINS EXPW 190 GEROD=GER0(IQ) EXPW 200 AREC=1.8E+3*RMIX(IQ)*EMP(IQ) EXPW 210 CBRC IF(IQ.EQ.1)AREC=AREC*SEFF(IQ) EXDW 220 AERD=I LFE* VANN( IQ)/( EMP( IQ)
- E FF( IQ) ) EXPW 210 FRA=19.75*EREC(IR)* POP (IR)*AREC EXPW 240 FEA=19.75*EER0(IR)* POPE (IR)*AERO EXPW 250 FRW=1.15E-4*POPW(IR)*AREC EXPW 260 FEW=1.15E-4*POPW(IR)*AER0 EXPW 270 CBRC EACH STREAM HANDLED SEPARATELY EXPW 280 CBRC 10 00 40 ISTR=1,NSTR EXPW 290 10 ISTR=1 EXPW 300 19=ISPC(ISTR,2) EXPW 310 A9=1.0 EXPW 320 IF(19.GT.1) A9=10.**(1-19) EXPW 330 A2= BAS (ISTR,1)/VANN(IQ) EXPW 340 CBRC PRINT HEADER FOR TAPE 10 OUTPUT EXPW 350 WRITE (10,7000) EXPW 360 7000 FORMAT (//2X,' EXPOSED WASTE ICRP IMPACTS BY NUCLIDE (MREM /YR)'// EXPW 370
- IMPACTS ARE NOT NORMALIZED BY NUMBER ',
1 2X,'**** EXPW 380
'0F DISPOSAL FACILITIES ****'// EXPW 390
- 2X,'NUC INTRUDER-AIR EROSION-AIR INTRUDER-WATER', EXPW 400
- EXPW 410
' EROSION-WATER'/)
ARITOT=0.0 EXPW 420 ARETOT=0.0 EXPW 430 WTITOT=0.0 EXPW 440 WTETOT=0.0 EXPW 450 CBRC END EXPW 460 A-20
l l
DO 30 INUC=1,85 EXPW 470
- IF(NUX(INUC).EQ.0)GO TO 30 EXPW 480 CALL CHNS(INUC,GREC,IEN,IBG,NCH) EXPW 490 i
l D0 12 I=1,8 EXPW 500 12 BCT(1,1)=ACT(I) EXPW 510 CALLCHNS(INUC,GER00,IEN,IBG,NCH) EXPW 520 D0 14 I=1,8 EXPW 530 14 BCT(I,2)=ACT(I) EXPW 540 A8= BAS (ISTR.INUC+7) EXPW 550 Bl=FRA*A2*AB*A9 EXPW 560 B2=FEA*A2*A8 EXPW 570 B3=FRW*A2*AS*A9 EXPW 580 B4=FEW*A2*A8 EXPW 590 D0 25 10RG=1,10 EXPW 600 CALL CALE(INUC,IORG,C1,C2,C3,C4,IEN,IEG,NCH) EXPW 610 BIMP(IORG,3)=BIMP(IORG,3)+Bl*C1 EXPW 620 BIMP(10RG,4)=BIMP(IORG,4)+B2*C2 EXPW 630 BIMP(IORG,5)=BIMP(IORG,5)+B3*C3 EXPW 640 BIMP(IORG,6)=BIMP(IORG,6)+34*C4 EXPW 650 I
25 CONTINUE .
EXPW 660 CBRC PRINT ICRP (IORG=10) IMPACTS FOR EACH NUCLIDE EXPW 670 AIRINT=Bl*C1 EXPW 680 AIRER 0=B2*C2 -EXPW 690 WATINT=B3*C3 EXPW 700 WATER 0=B4*C4 EXPW 710 WRITE (10,7010) NUC(INUC),AIRINT,AIRERO,WATINT, WATER 0 EXPW 720
. 7010 FORMAT (2X,A6,3X,1P4E12.3) EXPW 730
! ARIT0T=ARITOT+AIRINT EXPW 740 ARETOT=ARETOT+AIRERO EXPW 750 WTITOT=WTITOT+WATINT '
EXPW 760 WTETOT=WTETOT+WATERO EXPW 770 CBRC END EXPW 780 30 CONTINUE EXPW 790 CBRC PRINT TOTAL IMPACT EXPW 800' WRITE (10,7015) ARITOT,ARETOT,WTITOT,WTETOT EXPW 810 7015 FORMAT (/2X,' TOTAL NON-NORMALIZED EXPOSED WASTE IMPACTS'/ EXPW 820
- 11X,1P4E12.3) EXPW 830 CBRC END EXPW 840 j 40 CONTINUE EXPW 850 i
RETURN EXPW 860 END EXPW 870 l
i 1
A-21
CBRC .
OPSI 10
$ STORAGE:2 OPSI 20 SUBROUTINE OPSIMP '
OPSI 30 C OPSI 40 C********************************************************************* OPSI 50 .
C THIS SUBROUTINE CALCULATES THE ON-SITE AND OFF-SITE IMPACTS
- OPSI 60 C ASSOCIATED WITH DISPOSAL OPERATIONS.
- OPSI 70 C********************************************************************* OPSI 80 C OPSI 90 CBRC $LARGE OPSI 100 SINCLUDE:'IMPCOMM.FOR' OPSI 110 C OPSI 120 C BIMP(11) - 0FFSITE POPULATION - OPERATIONAL IMPACTS OPSI 130 C BIMP(12) - MAXIMUM OFFSITE INDIVIDUAL - OPERATIONAL IMPACTS OPSI 140 C BIMP(13) - ALL WORKERS - OPERATIONAL IMPACTS OPSI 150 C BIMP(14) - MAXIMUM WORKER - OPERATIONAL IMPACTS OPSI 160 C OPSI 170 GO T0 (20,20,30,30,30),10 OPSI 180 CBRC GO T0 (10,20,20,30,30),IQ OPSI 190 C - OPSI 200 C START CALCULATION OF 0FF-SITE RELEASES FROM ON-SITE FACILITY OPSI 210 CBRC THIS SECTION NOT USED IN IMPACTS-BRC OPSI 220 C OPSI 230 CBRC 10 DIAM =SQRT( ADAY(IQ,1)/3.1415927) OPSI 240 CBRC D0 16 ISTR=1,NSTR OPSI 250 CBRC 15=ISPC(ISTR,1) OPSI 260 CBRC FDS=1. OPSI 270 CBRC I F( 15. LT. 3)FDS=10. * *( IS-3) OPSI 280 CBRC I F( IQ. EQ. 3)FDS=(1.+ FDS)/2. OPSI 290 CBRC Al= FDS
- EMP( 1 )
- 0. 237
- TWO( 1,3 ) *WVEL( I R)
- 2.
- DI AM* 3. OPSI 300 CBRC A2=Al* BAS (ISTR,1)*3.15E+7/VANN(1) OPSI 310 CBRC DO 14 I=1,10 OPSI 320 C5RC A3=0. OPSI 330 CBRC D0 12 J=1,85 OPSI 340 CBRC I F( NUX(J ) . EQ .1 ) A3=A3+ BAS ( I STR ,J +7 )
- PDC F(J , I ,3) OPSI 350 CBRC 12 CONTINUE OPSI 3C0 CBRC BIMP(I,11)=BIMP(I,11)+A2*A3* POP (IR) OPSI 370 CBRC 14 BIMP(I,12)=BIMP(I,12)+A2*A3*X0Q0(IQ)*EDF0(IQ) OPSI 380 CBRC 16 CONTINUE OPSI 390 CBRC RETURN OPSI 400 CBRC END OPSI 410 C OPSI 420 C START MUNICIPAL WASTE FACILITY IMPACTS OPSI 430 C OPSI 440 20 DP0P=SQRT(ADAY(IQ,1)/3.1415927) OPSI 450 DEQP=SQRT(ADAY(IQ,2)/3.1415927) OPSI 460 DOTH=SQRT(ADAY(IQ,3)/3.1415927) OPSI 470 CBRC EACH STREAM HANDLED SEPARATELY OPSI 480 CBRC 00 26 ISTR=1,NSTR OPSI 490 ISTR=1 OPSI 500 15=ISPC(ISTR,1) OPSI 510 FDS=1. OPSI 520 IF(IS. LT.3)FDS=10. * *(15-3) OPSI 530 19=ISPC(ISTR,2) OPSI 540 FAC=1. OPSI 550 I F(19.GT.1) FAC=10. * *(1-19) OPSI 560 ASl=FDS* emf (IQ)*0.237* BAS (ISTR,1)/VANN(IQ) OPSI 570 AS2=AS 1
- TWO( I Q ,3 ) *WV E L( I R )
- 2 .
- DPOP
- 9. 45 E+7 OPSI 580 AG1=AS1*(FAC/FDS)*1.6/ DEN 2(IQ) OPSI 590 A-22
l D0 24 I=1,10 OPSI BOO Al=0. OPSI 610 A2=0. OPSI 620 A3=0. OPSI 630 AS=0. OPSI 640 DO 22 J=1,85 OPSI 650 IF(NUX(J).EQ.0)GO TO 22 OPSI 660 Al=A1+ BAS (ISTR,J+7)*PDCF(J ,1,1) OPSI 670 A2=A2+ BAS ( I ST R , J +7 )
- PDC F(J , I ,3 )
- FRACT(J ,3 ) OPSI 680 A3=A3+ BAS (ISTR,J+7)*PDCF(J ,I ,3) OPSI 690 A5=A5+ BAS (ISTR,J+7)*PDCF(J ,I ,5) OPSI 700 22 CONTINUE OPSI 710 C OPSI 720 C 0FF-SITE RELEASES OPSI 730 C OPSI 740 BIMP(I,11)=BIMP(I,11)+AS2*A3* POP (IR) OPSI 750 CBRC I F( I Q . EQ . 3 ) B I MP ( I ,11 )=BIMP ( I ,11 ) + BAS ( I ST R ,1 )
- A2
- A3
- X 0Q0( I Q )
- ED F0( I Q ) 0 PSI 770 CBRC I F( IQ . EQ . 3 ) B I MP ( I ,12 ) = B IMP ( I ,12 ) + BAS ( I ST R ,1 ) *A2
- X0Q0( I Q ) * .119 OPSI 780 C OPSI 790 C WORKER EXPOSURES OPSI 800 C OPSI 810 ADSL=AS1*TWO(IQ,1) OPSI 820 ADSM=AS1*TWO(IQ,2) OPSI 830 ADSH=AS1*TWO(IQ,3) OPSI 840 ADGL=AGl* DOFF ( 50. )*C0FF( 50. , DOTH) OPSI 850 ADGM=AGl* D0FF( 30. )* C0FF( 30. , DOTH) 0 PSI 860 ADGH=AGl*D0FF( 1.)*C0FF( 1. ,DEQP) OPSI 870 AC0V=6.26E-2*AG1 OPSI 880 CBRC I F( I Q . EQ . 3 ) ACOV= 0. 25 *AGl
- D EN2( I Q) /D EN2( 2 ) OPSI 890 B2=Al*ADSL+A5*(ADGM+AC0V) OPSI 900 B4=Al*ADSM+A5*(ADGM+ACOV) -OPSI 910 B6=Al*ADSH+AS*(ADGH+AC0V) OPSI 920 B7=2.*B2+4.*B4+2.*B6 OPSI 930 CBRC IF(IQ.EQ.2)B7=2.*B2+5.*B4+3.*B6 OPSI 940 CSRC DISPOSAL WORKERS FOR SANITARY LANDFILL (IQ=1 OR 2) .0 PSI 950 IF(IQ.EQ.1.0R.IQ.EQ.2) B7=2.*B2+5.*B4+3.*B6 OPSI 960 BIMP(I,13)=BIMP(I,13)+B7/10. OPSI 970 BIMP(I,14)=BIMP(I,14)+B7/10. OPSI 980 24 CONTINUE OPSI 990 26 CONTINUE OPSIl000 RETURN OPSIl010-C OPSIl020 C START HAZARDOUS WASTE FACILITY IMPACTS OPSIl030 C OPSIl040 30 DPOP=SQRT(ADAY(IQ,1)/3.1415927) OPSIl050 i
DEQP=SQRT(ADAY(IQ,2)/3.1415927) OPSIl060 D0TH=SQRT(ADAY(IQ,3)/3.1415927) OPSIl070 t
I A-23
i I
l CBRC EACH STREAM HANDLED SEPARATELY 095I1080 CBRC DO 38 ISTR=1,NSTR OPSIl090 ISTR=1 OPSI1100 l 15=ISPC(ISTR,1) OPSI1110 j FDS=1. OPSI1120 IF(IS. LT.3)FDS=10. * *(I5-3) OPSI1130 19=ISPC(ISTR,2) OPSI1140 FAC=1. OPSI1150 I F(19.GT.1) FAC=10. * *(1-19) OPSI1160 ASl=FDS*EMP(IQ)*0.237* BAS (ISTR,1)/VANN(IQ) OPSI1170 AS2=AS 1
- E FAC( I R )
- ADAY( IQ ,2 )
- 3 .15 E+ 1 OPSI1180 AS3=AS1
- E FAC( I R )
- ADAY( IQ ,2 )/( 2. *DP0P *3. E+ 6* WVEL( I R)
- DEN 2( IQ) ) OPSI1190 AG1=AS1*( FAC/FDS)*1.6/ DEN 2(IQ) OPSI1200 AX1= BAS (ISTR,2)*2.6E-11*FDS*ISPC(ISTR,11) OPSI1210 AX2=AX1*1.248*AX0Q(IR) OPSI1220 DO 36 I=1,10 OPS 11230 Al=0. OPSI1240 A2=0. OPSI1250 A3=0. OPSI1260 A5=0. OPSI1270 DO 32 J=1,85 OPSI1280 ;
IF(NUX(J).EQ.0)G0 TO 32 OPS 11290 Al=A1+ BAS (ISTR,J+7)*PDCF(J,I,1) OPSI1300 A2=A2+ BAS (ISTR ,J+7)* PDC F(J ,I ,2) OPSI1310 A3=A3+ BAS (ISTR ,J+7)* PDC F(J ,I ,3) OPSI1320 A5=A5+ BAS (ISTR,J+7)* PDCF(J ,I ,5) OPSI1330 32 CONTINUE OPSI1340 DIAM =DEQP OPSI1350 IF(ISPC(ISTR,3) .NE.0)DI AM=DOTH OPSI1360 ADGL=AGl*D0FF( 50. ) *C0FF( 50. ,DI AM) OPSI1370 ADGM=AGl*D0FF( 30. ) *C0FF( 30. ,DI AM) OPSI1380 ADGH=AGl*D0FF( 1.)*C0FF( 1. , DIAM) OPSI1390 AC0V=2.49E-2*AG1 OPSI1400 IF(ISPC(ISTR,3).NE.0)G0 TO 34 OPSI1410 C OPSI1420 C SECTION BELOW FOR UNPACKAGED WASTE OPSI1430 C OPSI1440 BIMP(I,11)=BIMP(I,11)+AS2*A3* POP (IR) OPSI1450 BIMP(I,12)=BIMP(I,12)+AS2*A3*X0Q0(IQ)*EDF0(IQ) OPSI1460 ADSL=AS3 OPSI1470 Bl=Al*ADSL+A5*( ADGL+AC0V) OPSI1480 82=Al*ADSL+A5*(ADGM+AC0V) OPSI1490 B3=Al*ADSL+A5*(ADGH+AC0V) OPSI1500 B4=AV.AXI(B1,82,83) OPSI1510 BIMP(I,13)=BIMP(I,13)+14.*Bl+15.*B2+29.*B3 OPSI1520 BIMP(I ,14)=BIMP(I,14)+B4 OPSI1530 G0 (0 36 OPSI1540 C OPSI1550 C SECTION BELOW FCR PACKAGED WASTE OPSI1560 C OPSI1570 34 EIMP(I,12)=BIMP(I,12)+AX2*A2 OPSI1580 ADSL=AX1 OPSI1590' Bl=A2*ADSL+A5*( ADGL+ACOV) OPSI1600 B2=A2*ADSL+A5*(ADGM+ACOV) OPSI1610 B3=A2* ADS L+A5*( ADGH+AC0V) OPSI1620 B4=AMAX1(B1,B2,83) OPSI1630 B IMP ( I ,13 )=BIMP( I ,13 ) + 14.
- B l + 15.
- B2+29.
- B3 OPSI1640 BIMP(I,14)=BIMP(I,14)+B4 OPSI1650 36 CONTINUE OPSI1660 38 CONTINUE OPSI1670 RETURN- OPSI1680 END OPSI1690 A-24
CBRC OVRF 10
$ STORAGE:2 OVRF 20 SUBROUTINE OVRFLO OVRF 30 C OVRF 40 C******************************************************************** OVRF 50 C THIS ROUTINE CALCULATES AND PRINTS RADIOLOGICAL IMPACTS OVRF 60 l C FOR THREE SCENARIOS WHICH MAY RESULT FROM LEACHATE ACCUMU- OVRF 70 C LATION AT A DISPOSAL FACILITY: OVRF 80 C 1) DURING OPERATION OF THE FACILITY, ACCUMULATING LEACHATE OVRF 90
, C IS REMOVED, TREATED, AND RELEASED TO A NEARBY STREAM. OVRF 100 C 2) AFTER CLOSURE, ACCUMULATING LEACHATE IS ALLOWED TO FILL OVRF 110 C UP THE DISPOSAL CELLS, OVERFLOW, AND REACH A NEARBY STREAM
- OVRF 120 C 3) AFTER CLOSURE, ACCUMULATING LEACHATE IS REMOVED AND OVRF 130 C PROCESSED THROUGH AN EVAPORATOR, THUS IMPACTING THE LOCAL
- OVRF 140 C POPULATION. OVRF 150 C******************************************************************* DVRF 160 C OVRF 170 CBRC $LARGE OVRF 180
$ INCLUDE:'IMPCOMM.FOR' OVRF 190 DIMENSION FIN (85),F2N(85) OVRF 200 DATA FIN /85*1./,F2N/85*1./ OVRF 210 GDEL=IINS OVRF 220 VTOT=ILFE*VANN(IQ) OVRF 230 VL=PRC(IR,IQ)*VTOT/(EMP(IQ)*EFF(IQ)) OVRF 240 A8=ISPC(1,11)*4.5E6 OVRF 250 CBRC EACH STREAM HANDLED SEPARATELY OVRF 260 CBRC DO 30 ISTR=1,NSTR OVRF 270 ISTR=1 OVRF 280 19=ISPC(ISTR,2) OVRF 290 A9=1.0 OVRF 300 IF(19.GT.1) A9=0.1 OVRF 310 A4=A9* BAS (ISTR,1)*VL/VANN(IQ) OVRF 320 CBRC PRINT HEADER FOR TAPE 10 FOR NUCLIDE IMPACT OUTPUT OVRF 330 WRITE (10,7000) OVRF 340 7000 FORMAT (//2X,'0VERFLOW ICRP IMPACTS BY NUCLIDE (MREM /YR)'// OVRF 350
- 2X,'**** IMPACTS ARE NOT NORMALIZED BY NUMBER OF ', OVRF 360
' DISPOSAL FACILITIES ****'// OVRF 370 2X,'NUC TREATMENT OVERFLOW EVAPORATOR'/) OVRF 380 TRTOT=0.0 OVRF 390 OVRTOT=0.0 OVRF 400 EVPTOT=0.0 OVRF 410 CBRC END OVRF 420 DO 20 INUC=1,85 OVRF 430 IF(NUX(INUC).EQ.0)G0 TO 20 OVRF 440 A7=1. OVRF 450 Al=ILFE*(1.-EXM(AL(INUC))) OVRF 460 I F( A1. GT . 0. ) A7=( 1. -EXM( AL( I NUC )
- I LFE) )/A1 OVRF 470 A5=A4 *A7
- BAS ( I ST R , I NUC+7 )
- FM F( I NUC ) OVRF 480 A6=AS*EXM(AL(INUC)*GDEL) OVRF 490 Al=A5* FIN (INUC)*TSC(IR,IQ)/A8 OVRF 500 A2=A6*F2N(INUC)/A8 OVRF 510 A3=A6*FRACT(INUC,2)* POP (IR) OVRF 520 D0 10 I=1,10 OVRF 530 BIMP( I ,63 )=BIMP( I ,63 ) +Al* PDC F( INUC , I ,7 ) OVRF 540 B I MP( I ,64 )= BI MP ( I ,64 ) +A2
- PDC F( I NUC , I ,7 ) OVRF 550 10 BIMP(I,65)=BIMP(I,65)+A3*PDCF(INUC,I,3) OVRF 560 A-25
CBRC PRINT ICRP (I=10) IMPACTS FOR EACH NUCLIDE OVRF 570 TREAT =Al*PDCF(INUC,10,7) OVRF 580 OVERF=A2*PDCF(INUC,10,7) OVRF 590 EVAPO=A3*PDCF(INUC,10,3) OVRF 600 WRITE (10,7010) NUC(INUC), TREAT,0VERF,EVAPO OVRF 610 7010 FORMAT (2X,A6,3X,1P3E12.3) OVRF 620 l TRTOT=TRTOT+ TREAT OVRF 630 OVRTOT=0VRTOT+0VERF OVRF 640 EVPTOT=EVPTOT+EVAPO OVRF 650 1 CBRC END OVRF 660 20 CONTINUE OVRF 670 CBRC PRINT TOTAL IMPACTS OVRF 680 WRITE (10,7015) TRTOT,0VRTOT,EVPTOT OVRF 690 7015 FORMAT (/2X,' TOTAL NON-NORMALIZED OVERFLOW IMPACTS'/11X,1P3E12.3) OVRF 700 CBRC END OVRF 710 30 CONTINUE OVRF 720 RETURN OVRF 730 i END OVRF 740 I
h 4
i l
l i
i A-26
CBRC ADD SCN TO CALL GWTR 10
$ STORAGE:2 GWTR 20 SUBROUTINE GWATER(NTYM,TYMD,5CN) GWTR 30 C GWTR 40 C*********************************************************************
- GWTR 50 C THIS SUBROUTINE CALCULATES THE IMPACTS RESULTING FROM GWTR 60 C GROUNDWATER MIGRATION OF RADI0 ACTIVITY TO THREE BIOTA ACCESS
- GWTR 70
! C LOCATIONS (INTRUDER-WELL, POPULATION-WELL AND SURFACE WATER).
- GWTR 80 l C********************************************************************* GWTR 90 l C GWTR 100 CBRC $LARGE GWTR 110 SINCLUDE:'IMPCOMM.FOR' GWTR 120 DIMENSION TYMD(16),RES(16,3) GWTR 130 CBRC DIMENSION ARRAYS FOR TIMES AND NUCLIDE-SPECIFIC DOSES GWTR 140 CHARACTER SCN(36)*6 GWTR 150 DIMENSION DOSNUC(16),DOSSUM(16,3) GWTR 160 CBRC END GWTR 170 CBRC GDEL=IINS GWTR 180 CBRC BEGIN GW TRANSPORT AT END OF FACILITY LIFE GWTR 190 GDEL=0.0 GWTR 200 NSEC=10 GWTR 210 PERC=PRC(IR,10)*TSC(IR,IQ) GWTR 220 TVOL=ILFE"VANN(IQ)*PRC(IR,IQ)/(EMP(IQ)*EFF(IQ)) GWTR 230 CBRC IF( TVOL. LT.7700. )TVOL=7700. GWTR 240 CBRC USE LOWER MINIMUM INDIVIDUAL WATER PUMPAGE GWTR 250 IF(TVOL.LT.110.) TV0L=110. GWTR 260 NPTH=3 GWTR 270 IF(IR.EQ.3)NPTH=2 GWTR 280 CBRC PRINT HEADER FOR GWATER OUTPUT ON TAPE 10 GWTR 290 WRITE (10,7000) (SCN(IT),IT=15,30) GWTR 300 7000 FORMAT (//2X,' GROUNDWATER ICRP IMPACTS BY NUCLIDE (MREM /YR) AT ', GWTR 310
- 'EACH TIME'/2X,'**** IMPACTS.ARE NOT NORMALIZED BY NUMBER OF ', GWTR 320
' DISPOSAL FACILITIES ****'// GWTR 330
- 2X,'FIRST R0W IS INTRUDER WELL'/ GWTR 340 2X,'SECOND R0W IS POPULATION WELL'/ GWTR 350
- 2X,' THIRD R0W IS SURFACE WATER'// GWTR 360 16(2X,A6)/) GWTR 370 CBRC END GWTR 380 CBRC EACH STREAM HANDLED SEPARATELY GWTR 390 CBRC D0 90 ISTR=1,NSTR GWTR 400 ISTR=1 GWTR 410 A9=1.0 GWTR 420 IF(ISPC(ISTR,2) .GT.1) A9=0.1 GWTR 430 11=NRET(IR)-1 GWTR 440 TDUM= EMP ( IQ )
- E FF( I Q)
- S E F F( I Q )/( P ERC
- A9 ) GWTR 450 I F(II . LE.0)I1=1 GWTR 460 CBRC ZERO SUMS GWTR 470 CALL ZER0(DOSSUM,48) GWTR 480 DO 80 INUC=1,85 GWTR 490 IF(NUX(INUC).EQ.0)GO TO 80 GWTR 500
- IF(BAS (ISTR,INUC+7).LT.1.E-14)G0 TO 80 GWTR 510 TDUR=TDUM/FMF(INUC) GWTR 520 CBRC PRINT NUCLIDE NAME GWTR 530 WRITE (10,7010) NUC(INUC) GWTR 540 7010 FORMAT (2X,A6) GWTR 550 CBRC END GWTR 560-C GWTR 570 A-27
CALL ZER0(RES,3*16) GWTR 580 I DO 30 IPTH =1,3 GWTR 590 l Al= RET (INUC,II)*TTM(IR, IPTH,1Q)+GDEL _GWTR 600 D0 20 ITYM=1,NTYM GWTR 610 TYM=TYMD(ITYM) GWTR 620 A2=TYMD(ITYM)-TDUR GWTR 630 00 10 ISEC=1,10 GWTR 640-B3=1.0/(A1+ RET (INUC,II)*(ISEC-1)*DTTM(IR,IQ)) GWTR 650 CBRC IF(TYM*1.1*B3.LT.I.0) GO TO 20 GWTR 660 CBRC REPLACE DISPERSION CALCULATION WITH SQUARE WAVE GWTR 670 IF(TYM*B3.LT.1.0) GOTO 20 GWTR 680 BRKTHU=1.0/B3 GWTR 690 IF(TYM.GT.TDUR+BRKTHU) GOTO 20 GWTR 700 A3=1.0 GWTR 710 CBRC B4=TPC(IR, IPTH,IQ)+(ISEC-1)*DTPC(IR,1Q) GWTR 720 CBRC A3=0.5*ERFS(B3*TYM,B4) GWTR 730 CBRC I F( A2.GT . 0. 0) A3=A3-0. 5* ER FS ( B3 *A2,84 ) GWTR 740 CBRC I F( A3.LT.0.0) A3=0.0 GWTR 750 CBRC END GWTR 760 10 RES(ITYM, IPTH)=RES(ITYM, IPTH)+A3 GWTR 770 20 CONTINUE GWTR 780 30 CONTINUE GWTR 790 C GWTR 800 Bl= BAS (ISTR,1)* BAS (ISTR,INUC+7)/TDUR GWTR 810 00 70 IPTH =1,NPTH GWTR 820 K=14+(IPTH-1)*16 GWTR 830 B2=B1/(QFC(IR, IPTH)*NSEC) GWTR 840 I F( TVO L . GT . Q FC ( I R , I P TH ) ) B 2= B2
- Q FC ( I R , I PTH ) / TVO L GWTR 850 12=6 GWTR 860 IF(IPTH.EQ.3)I2=7 GWTR 870 00 60 ITYM=1,NTYM GWTR 880 A3=EXM(AL(INUC)*TYMD(ITYM)) GWTR 890 00 50 I=1,10 GWTR 900 A4=A3
- R ES ( ITYM , I P TH )
- B2
- PDC F( I NUC ,1, I 2 ) GWTR 910 50 BIMP(I,K+ITYM)T81MP(I,K+ITYM)+A4 GWTR 920 CBRC SAVE ONLY ICRP DOSE, I=10 GWTR 930 DOSNUC(ITYM)=A4 GWTR 940 DOSSUM(ITYM, IPTH)=DOSSUM(ITYM, IPTH)+A4 GWTR 950 CBRC END GWTR 960 60 CONTINUE GWTR 970 CBRC PRINT ICRP DOSE FOR THIS NUCLIDE AT EACH TIME GWTR 980 WRITE (10,7020) (DOSNUC(IT),IT=1,16) GWTR 990 7020 FORMAT (IP16E8.1) GWTR1000 CBRC END GWTR1010 70 CGhTINUE GWTR1020 80 CONTINUE GWTR1030 CBRC PRINT TOTAL IMPACTS GWTR1040 WRITE (10,7025) ((DOSSUM(IDS,JDS), IDS =1,16),JDS=1,3) GWTR1050 7025 FORMAT (/2X,' TOTAL NON-NORMALIZED GROUNDWATER IMPACTS' GWTR1060
- GWTR1070 3(/IP16E8.1))
CBRC END GWTR1080 90 CONTINUE GWTR1090 RETURN GWTR1100 END GWTR1110 A-28 i
CBRC DIVY 10
$5 TOP. AGE:2 . DIVY 20 Ca****************************************************************** DIVY 30 C DIVY 40 SUBROUTINE DIVVY (MODE,N1,N2) DIVY 50 C DIVY' 60 C********************************************************************** DIVY 70 C THIS ROUTINE DIVIDES SELECTED IMPACTS BY EITHER THE NUMBER DIVY E0 C 0F DISPOSAL FACILITIES OR BY THE NUMBER OF PROCESSING DIVY 90 C FACILITIES (DEPENDING ON THE VALUE OF MODE). DIVY 100
, C********************************************************************* DIVY 110 l C DIVY 120 COMMON / BAST / BAS ( 2,92 ) , B I MP( 10,65 ) , I S PC( 2 ,15 ) , PDC F( 85,10,7 ) DIVY 130 l IF(MODE.EQ.2)GO TO 20 DIVY 140 IF(ISPC(1,11).EQ.0) WRITE (6,100) DIVY 150 ADIV=ISPC(1,11) DIVY 160 IF(ADIV.EQ.0.) ADIV=1. DIVY 170 D0 10 I=1,10 DIVY 180 i D0 10 J=N1,N2 DIVY 190 10 BIMP(I,J)=BIMP(I,J)/ADIV DIVY 200
- RETURN DIVY 210 20 ' I F( I SPC( 1,10) . EQ . 0)WRI TE( 6,101) DIVY 220 ADIV=ISPC(1,10) DIVY 230 IF(ADIV.EQ.0.) ADIV=1. DIVY 240 DO 30 I=1,10 DIVY 250
< DO 30 J=N1,N2 DIVY 260 30 BIMP(I,J)=BIMP(I,J)/ADIV DIVY 270 4 100 FORMAT (//2X'**** NUMBER OF DISPOSAL FACILITIES = 1 ****'//) DIVY 280 101 FORMAT (//2X'**** NUMBER OF PROCESSING FACILITIES = 1 ****'//) DIVY 290 RETURN DIVY 300 END DIVY 310 e
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A-29
l l
CBRC BLOCK DATA DIVY 320 CBRC CHANGE BLCCK DATA SUBPROGRAM TO SUBROUTINE BLOCKD DIVY 330 CBRC*************************************************************** DIVY 340 CBRC DIVY 350 SUBROUTINE BLOCKD DIVY 360 CBRC DIVY 370 CBRC**************************************************************** DIVY 380 CBRC DIVY 390 COMMON /CHYN/NXUC(85),ICH(8,10),LCH(10),ACT(8),BCT(8,2) DIVY 400
+ /NUCS/ALFR(595),FRACT(85,3),NUX(85)/UPTK/FK(21) DIVY 410 DIMENSION NXUC2(85),ICH2(8,10),LCH2(10),FK2(21),FRACT2(85,3) DIVY 420 CBRC DIVY 430 DATA NXUC2/27*0,1,0,1,16*0,1,6*0,1,0,3*1,3*0,24*1/ DIVY 440 DATA ICH2/85,84,78,75,69,63,58,60,83,75,69,63,58,60, 0, 0, DIVY 450
+ 82,74,68,64,59, 0, 0, 0,81,73,67,62,57,56,54,55, DIVY 460
+ 80,74,68,64,59, 0, 0, 0,76,79,71,66,61, 0, 0, 0, DIVY 470
+ 77,70,67,62,57,56,54,55,72,65,60, 0, 0, 0, 0, 0, DIVY 480
+ 28,30,29, 0, 0, 0, 0, 0,47,48, 0, 0, 0, 0, 0, 0/ DIVY 490 DATA LCH2/8,6,5,8,5,5,8,3,3,2/ DIVY 500 DATA FK2/8.E-4,.01,.0483,7.65E-4,240. 0037,.25,1.,1600., DIVY 510
+ 190.,50.,95.,.3,50.,60.,370.,6.9,1.,8.5E-9,8000.,16./ DIVY 520 DATA FRACT2/.9,.75,26*2.5E-3,4*.01,7*2.5E-3,3*.01,43*2.5E-3, DIVY 530
+ .9,.75,26*5.0E-3,4*.01,7*5.0E-3,3*.01,43*5.0E-3, DIVY 540
+ .9,.75,26*2.5E-3,4*.01,7*2.5E-3,3*.01,43*2.5E-3/ DIVY 550 CBRC + .9,.75,26*.019,4*.038,7*.019,3*.038,43*.019/ DIVY 560 D0 10 I=1,85 DIVY 570 NXUC(I)=NXUC2(I) DIVY 580 D0 10 J=1,3 DIVY 590 FRACT(I,J)=FRACT2(I,J) DIVY 600 10 CONTINUE DIVY 610 CBRC DIVY 620 00 20 I=1,10 DIVY 630 LCH(I)=LCH2(I) DIVY 640 D0 20 J=1,8 DIVY 650 ICH(J,I)=ICH2(J,I) DIVY 660 20 CONTINUE DIVY 670 CBRC DIVY 680 DO 30 I=1,21 DIVY 690 FK(I)=FK2(I) DIVY 700 30 CONTINUE DIVY 710 CBRC DIVY 720 RETURN DIVY 730 END DIVY 740 C DIVY 750 A-30
l l l' l
l' C********************************************************************* DIVY 760 C DIVY 770 SUBROUTINE PRNTE(ORG,SCN,BI) DIVY 780 -
C DIVY 790 C********************************************************************* DIVY 800 C THIS ROUTINE PRINTS OUT MOST OF THE FINAL IMPACT RESULTS DIVY 810 C TO TAPE 6. DIVY 820 C********************************************************************* DIVY 830 C DIVY 840 CBRC $LARGE DIVY 850 CHARACTER ORG(10)*9,5CN(36)*6 DIVY 860 DIMENSION BI(10,65) DIVY 870 WRITE (6,107) DIVY 880 WRITE (6,105) ORG DIVY 890 WRITE (6,103) (SCN(J),(BI(I,J),I=1,10),J=1,2) DIVY 900 WRITE (6,108) DIVY 910 WRITE (6,105) ORG DIVY 920 WRITE (6,103) (SCN(J),(BI(I,J),I=1,10),J=3,6) DIVY 930 WRITE (6,109) DIVY 940 WRITE (6,105) ORG DIVY 950 WRITE (6,103) (SCN(J),(BI(I,J),I=1,10),J=7,14) DIVY 960 WRITE (6,114) DIVY 970 WRITE (6,105) ORG DIVY 980 WRITE (6,103) (SCN(J-29),(BI(I,J),I=1,10),J=63,65) DIVY 990 WRITE (6,110) DIVY1000 WRITE (6,111) DIVY1010 WRITE (6,104) ORG DIVY1020 WRITE (6,103) (SCN(J),(BI(I,J),I=1,10),J=15,30) DIVY1030 WRITE (6,112) DIVY1040 WRITE (6,104) ORG DIVY1050 WRITE (6,103) (SCN(J-16),(BI(I,J),I=1,10),J=31,46) DIVY1060 WRITE (6,113) DIVY1070 WRITE (6,104) ORG DIVY1080 WRITE (6,103) (SCN(J-32),(BI(I,J),I=1,10),J=47,62) DIVY1090 C
DIVY1100 103 FORMAT (2X,A6,1P,10E9.2) DIVY1110
.104 FORMAT (4X,' TIME',10A9) DIVY1120 105 FORMAT (4X,'SCN ',10A9) DIVY1130 CBRC 107 FORMAT (/2X' INTRUDER IMPACTS:'/) DIVY1140 CBRC 108 FORMAT (/2X' EXPOSED WASTE IMPACTS:'/) DIVY1150 CBRC 109 FORMAT (/2X' INCINERATION AND GPERATIONAL IMPACTS:'/) DIVY1160 CBRC 110 FORMAT (IH1/2X' GROUND WATER IMPACTS:') DIVY1170 107 FORMAT (/2X' INTRUDER IMPACTS (MREM /YR):'/) DIVY1180 108 FORMAT (/2X' EXPOSED WASTE IMPACTS (MREM /YR):'/) DIVY1190 109 FORMAT (/2X' INCINERATION AND OPERATIONAL IMPACTS:', DIVY1200 UNITS: IC-IND,IC-MWR,0P-IND,0P-MWR - (MREM /YR)'/ DIVY1210
- 49X,'IC-POP,IC-WOR,0P-POP,0P-WOR - (PERSON-MREM /YR)'/) DIVY1220 110 FORMAT (1H1/2X' GROUND WATER IMPACTS (MREM /YR):') DIVY1230 111 FORMAT (/2X' INTRUDER-WELL') DIVY1240 112 FORMAT (/2X' POPULATION-WELL') DIVY1250 113 FORMAT (/2X' POPULATION-SURFACE WATER') DIVY1260 CBRC 114 FORMAT (/2X'LEACHATE ACCUMULATION IMPACTS:'/) DIVY1270 114 FORMAT (/2X'LEACHATE ACCUMULATION IMPACTS (MREM /YR):'/) DIVY1280 RETURN DIVY1290 END DIVY1300 C
DIVY1310 A-31
CBRC CHNS 10
$ STORAGE:2 CHNS 20 SUBROUTINE CHNS(INUC,GDEL,IEN,IBG,NCH) CHNS 30 C CHNS 40 l C********************************************************************** CHNS 50 (
C THIS ROUTINE IS IDENTICAL IN LOGIC WITH THE ACTDR SUBROUTINE CHNS 60 C 0F THE MILDOS CODE. FIRST, THE CHAIN MEMBERS ARE DETERMINED, CHNS 70 C THEN THE ACTDR CALCULATIONS ARE APPLIED. HOWEVER, HERE, DUE CHNS 80 C TO SUBSTRACTIONS BETWEEN A LARGE AND A SMALL NUMBER, DOUBLE CHNS 90 C PRECISION IS USED TO INCREASE THE ACCURACY OF THE RESULTS. CHNS 100 C********************************************************************* CHNS 110 C CHNS 120 CBRC $LARGE CHNS 130 COMMON /CHYN/NXUC(85),1CH(8,10),LCH(10),ACT(8),BCT(8,2) CHNS 140
+ /NUCS/AL( 85) , FM F( 85 ) , RET ( 85,5 ) , F RACT( 85,3) , NUX( 85 ) CHNS 150 REAL*8 Y , Z , DACT( 8) , H LM( 8 ) , EH LM(8) CHNS 160 CALL ZER0(ACT,8) CHNS 170 IF(NXUC(INUC).NE.0)G0 TO 12 CHNS 180 10 ACT(1)=EXM(AL INUC)*GDEL) CHNS 190 RETURN CHNS 200 12 DO 16 NCH=1,10 CHNS 210 IEN=LCH(NCH) CHNS 220 D0 14 IBG=1,IEN CHNS 230 IF(INUC.EQ.ICH(IBG,NCH))GO TO 18 CHNS 240 14 CONTINUE CHNS 250 16 CONTINUE CHNS 260 STOP ' CANT FIND NUCLIDE IN CHAINS' CHNS 270 18 IF(IBG.EQ.IEN)GO TO 10 CHNS 280 IEND=IEN-IBG+1 CHNS 290 DO 20 I=1,IEND CHNS 300
' CHNS 310 J=ICH(IBG+I-1,NCH)
HLM(I)=AL(J) CHNS 320 Y=HLM(I)*GDEL CHNS 330 Z=0. CHNS 340 I F(Y. LT.85. )Z=DEXP(-Y) CHNS 350 20 EHLM(I)=Z CHNS 360 DACT(1)=EHLM(1) CHNS 370 DO 60 I=2,IEND CHNS 380 Y=1.0 CHNS 390 DO 30 J=2,I CHNS 400 30 Y=Y*HLM(J) CHNS 410 DACT(I)=0. CHNS 420 DO 50 K=1,I CHNS 430 1 Z=EHLM(K) CHNS 440 1
DO 40 J=1,1 CHNS 450 IF(K.NE.J)Z=Z/(HLM(J)-HLM(K)) CHNS 460 40 CONTINUE CHNS 470 .i CHNS 480 1 DACT(I)=DACT(I)+Z 50 CONTINUE CHNS 490 i DACT(I)=DACT(I)*Y CHNS 500 l I F(DACT(I) . LT.0. )DACT(I)=0. CHNS 510 60 CONTINUE CHNS 520 00 70 I=1,IEND CHNS 530 70 ACT(I)=DACT(I) CHNS 540 RETURN CHNS 550 END CHNS 560 A-32
CBRC CALI 10
$ STORAGE:2 CALI 20 SUBROUTINE CALI(INUC,IP,C1,C2,C3,C4,IEN,IBG,NCH) CALI 30 C CALI 40 C********************************************************************* CALI 50 C THIS ROUTINE OBTAINS THE C1,C2,C3,C4 COEFFICIENTS USED IN
- CALI 60 C THE INTRUDER IMPACT CALCULATIONS. IF INUC IS NOT A MEMBER CALI 70 C 0F A CHAIN, THEN THE SECTION BEFORE STATEMENT 15 IS USED.
- CALI 80 C 0THERWISE THE SECTION AFTER STATEMENT 15 IS USED.
CALI 90
\
C********************************************************************* CALI 100 i C CALI 110 CBRC $LARGE CALI 120 l COMMON / BAST /BASCOM( 834 ) , I S PC ( 2,15 ) , PDC F( 85 ,10,7 ) CALI 130
+ /CHYN/NXUC(85),ICH(8,10),LCH(10),ACT(8),8CT(8,2) CALI 140
+ /NUCS/AL( 85 ) , FMF( 85 ) , R ET( 85,5 ) , F RACT( 85,3 ) , NUX( 85 ) CALI 150 IF(NXUC(INUC).NE.0)G0 TO 15 CALI 160 a
10 Al=ACT(1) CALI 170 C1=Al*PDCF(INUC,IP,5) .
CALI 180 C2=Al*PDCF(INUC,IP,2) CALI 190 i
C3=Al*PDCF(INUC,IP,3) CALI 200 C4=Al*PDCF(INUC,IP,4)*FMF(INUC) CALI 210 RETURN CALI 220 15 IEND=IEN-IBG+1 CALI 230 C1=0. CALI 240 C2=0. CALI 250 C3=0. CALI 260 C4=0. CALI 270 D0 20 I=1,IEND CALI 280 NN=ICH(IBG+I-1,NCH) CALI 290 C1=C1+ACT(I)*PDCF(NN,IP,5) CALI 300 C2=C2+ACT(I)*PDCF(NN,IP,2) CALI 310 C3=C3+ACT(I)*PDCF(NN,IP,3) CALI 320 C4=C4+ACT( I )
- PDC F( NN , I P ,4 )
- FMF( NN ) CALI 330 20 CONTINUE CALI 340 RETURN CALI 350 END CALI 360 s
.t A-33
CBRC CALE 10
$ STORAGE:2 CALE 20 SUBROUTINECALE(INUC,IP,C1,C2,C3,C4,IEN,IBG,NCH) CALE 30 C CALE 40 C*************************"******************************************* CALE 50 C THIS ROUTINE PERFORMS THE SAME FUNCTION AS SUBROUTINE "CALI",
- CALE 60 C ONLY NOW FOR SUBROUTINE "EXPWAS" RATHER THAN "INTIMP". CHAIN
- CALE 70 C EFFECTS FOR INTRUDER- AND EROSION-INITIATED EXPOSED WASTE CALE 80 C SCENARIOS ARE CALCULATED IN THIS ROUTINE. CALE 90 C****************"**************************************************** CALE 100 C CALE 110 CBRC $LARGE CALE 120 COMMON / BAST /BASCOM( 834 ) , I S PC( 2 ,15 ) , P DC F( 85 ,10 ,7 ) CALE 130
/CHYN/NXUC(85),ICH(8,10),LCH(10),ACT(8),BCT(8,2) CALE 140 '
IF(NXUC(INUC).NE.0)G0 TO 15 CALE 150 C1=BCT( 1,1)* PDCF(INUC ,IP ,3) CALE 160 C2=BCT(1,2)*PDCF(INUC,IP,3) CALE 170 C3=BCT(1,1)*PDCF(INUC,IP,7) CALE 180 C4=BCT(1,2)*PDCF(INUC,IP,7) CALE 190 RETURN CALE 200 15 IEND=IEN-IBG+1 CALE 210-C1=0. CALE 220 C2=0. CALE 230 C3=0. CALE 240 C4=0. CALE 250 D0 20 I=1,IEND CALE 260 NN=ICH(IBG+I-1,NCH) CALE 270 C1=C1+BCT(I,1)'PDCF(NN,IP,3) CALE 280 C2=C2+BCT(I,2)*PDCF(NN,IP,3) CALE 290 C3=C3+BCT( I,1)* PDCF(NN ,IP ,7) CALE 300 20 C4=C4+BCT(I,2)*PDCF(NN,IP,7) CALE 310 RETURN CALE 320 END CALE 330 l
l l
A-34
CBRC UTIL 10
$ STORAGE:2 UTIL 20 SUBROUTINEZER0(A,N) UTIL 30
- DIMENSION A(N) UTIL 40 l
D0 10 I=1,N UTIL 50 10 A(I)=0. UTIL 60 RETURN UTIL 70 END UTIL 80 C UTIL 90 CBRC SUBPROGRAMS FOR GROUNDWATER DISPERSION CALCULATIONS NOT USED UTIL 100 CBRC FUNCTION ERFS(A1,A2) UTIL 110 i
CBRC A3=0.5*SQRT(A2/A1) UTIL 120
- CBRC A4=A3*(1.-A1) UTIL 130 CBRC A5=A3*(1.+A1) UTIL 140
!- UTIL 150 CBRC IF(A4.GT.0)G0 TO 10 CBRC ERFS=2.+EXM(A4*A4)*(POLY (A5)-POLY (-A4)) UTIL 160 CBRC RETURN UTIL 170 CBRC 10 ERFS=EXM(A4*A4)*(POLY (A4)+ POLY (AS)) UTIL 180 CBRC RETURN UTIL 190 CBRC END UTIL 200 C UTIL 210 CBRC FUNCTION POLY (X1) UTIL 220 CBRC DATA A1,A2,A3,A4,AS,P/.254829592, .284496736,1.421413741, UTIL 230 CBRC * -1.453152027,1.061405429,.3275911/' UTIL 240 CBRC T1=1./(1.+P*X1) UTIL 250 CBRC POLY =T1*( A1+T1*( A2+T1*( A3+T1*( A4+T1*AS)))) UTIL 260 CBRC RETURN UTIL 270 CBRC END UTIL 280 4
C UTIL 290 FUNCTION EXM(A1) UTIL 300 A2=0.0 UTIL 310 IF( A1. LT.85. ) A2=EXP(-A1) .UTIL 320 EXM=A2 UTIL 330 RETURN UTIL 340 END UTIL 350 C UTIL 360 FUNCTION C0FF(X,R) UTIL 370 DATA U/.0097/ UTIL 380 Al=El(U*X) UTIL 390 R1=SQRT(R*R+X*X) UTIL 400 C0FF=( Al-El(U*R1))/A1 UTIL 410 RETURN UTIL 420 END UTIL 430 C UTIL 440 FUNCTION D0FF(X) UTIL 450 DATA U/.0097/ UTIL 460 Al=1.+.95*U+.35*U*U UTIL 470 A2=EXM(U)*(1.-U*EXP(U)*El(U)) - UTIL 480 Y=U*X UTIL 490 D0 FF=( 1. + . 95
- Y+ . 35
- Y" Y)
- EXM( Y) * ( 1. -Y
- EX P ( Y )
- El( Y ) )/( Al *A2 ) UTIL 500 RETURN UTIL 510
. END UTIL 520 C UTIL 530
- A-35
FUNCTION X0QFC(H,R,V,IS) UTIL 540 -
DIMENSION A(6),B(6),C(6) UTIL 550 1 DATA A/.2,.12,.08,.06,.03,.016/,B/2*0.. 0002,.0015,2*.0003/, UTIL 560
- C/2*0.,2*.5,2*1./ UTIL 570 SIGZ=A(IS)*R/((1.+D(IS)*R)**C(IS)) UTIL 580 X0Q FC=2. 032
- EX P(-0. 5* ( H/S IGZ ) * ( H/S I GZ ) ) /( V
- R* S I GZ ) UTIL 590 RETURN UTIL 600 END UTIL 610 l C UTIL 620 FUNCTION El(X) UTIL 630 DIMENSION A(5),AT(4),BT(4) UTIL 640 DATA A0,A/ .57721566,.99999193, .24991055,.05519968, UTIL 650
+ .00976004,.00107857/ UTIL 660 DATA AT/3.5733287401,18.0590169730,8.6347608925,0.2677737343/ UTTL 07u DATA BT/9.5733223454,25.6329561486,21.0996530827,3.9584969228/ UTIL 680 IF(X.GT.0..ANO.X.LE.1.) GO TO 10 UTIL 690 IF(X.GT.I.) GO TO 30 UTIL 700 STOP 'El ARGUMENT NEGATIVE' UTIL 710 10 E=0. - UTIL 720 XP=1. UTIL 730 DO 20 I=1,5 UTIL 740 XP=XP*X UTIL 750 20 E=E+A(I)*XP UTIL 760 E1=(E+A0)-ALOG(X) UTIL 770 RETURN UTIL 780 30 ET=0. . UTIL 790 EB=0. UTIL 800 XP=1. UTIL 810 DO 40 I=1,4 UTIL 820 XP=XP*1 UTIL 830 IF(I.EQ.4) 60 TO 50 UTIL 840 J=4-I UTIL 850 ET=ET+AT(J)*XP UTIL 860 40 EB=EB+BT(J)*XP UTIL 870
- 50 E=(XP+ET+AT(4))/(XP+EB+BT(4)) UTIL 880
- E1=E/(X*EXP(X)) UTIL 890 I RETURN UTIL 900 END - UTIL 910 l
A-36 .
"9 w m w w 4 h"* Y
l APPENDIX B TAPE 1.DAT - NUCLIDE SPECIFIC DATA i
l
[
H-3 1* .00E000 4.80E+00 1.20E-02 1.40E-02 9.00E-01 9.00E-01 5.64E-02 1.15E+00 1.0bE+00 1.00E+00
.00E000 .00EOOO .00E000 .00E+00 .00E000 .00E+00 .00E000 .00E+00 .00EOOO .00E000
.00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00
- 8.36E-08 1.08E-07 1.43E-07 8.30E-08 8.56E-08 8.28E-08 8.26E-08 6.56E-08 8.28E-08 8.98E-08 1.25E-07 1.25E-07 1.33E-07 1.2SE-07 1.29E-07 1.24E-07 1.24E-07 9.85E-08 1.24E-07 1.26E-07 C-14 1* .00E+00 5.50E+00 3.10E-02 1.50E-02 4.60E+03 9.10E+03 1.21E-04 0.103 1.0 1.00E+01
.00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .0CE+00 .00E+00 .00E+00 .00E+00
.00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00
- 8.49E-07 1.21E-06 1.46E-06 1.92E-06 1.06E-06 1.23E-06 3.38E-06 7.05E-06 8.89E-07 1.54E-06 6.18E-09 7.35E-09 7.22E-09 1.41E-08 7.92E-09 8.88E-09 2.42E-08 5.08E-08 6.48E-09 1.09E-08 NA-22 1D 1.34E-05 4.60E-03 8.30E-02 3.50E-02 1.00E+02 2.00E+02 2.65E-01 1.62E-04 1.0 7.20E+02 1.85E-04 1.70E-04 1.68E-04 1.97E-04 1.82E-04 1.73E-04 1.88E-04 2.06E-04 2.30E-04 1.90E-04 9.84E-03 9.10E-03 8.99E-03 1.05E-02 9.73E-03 9.25E-03 9.99E-03 1.10E-02 1.23E-02 1.01E-02 D 2.57E-05 1.04E-05 1.35E-05 1.36E-05 1.49E-05 1.40E-05 1.95E-05 2.50E-05 1.21E-05 1.86E-05 9.43E-06 6.22E-06 7.53E-06 9.16E-06 9.91E-06 9.45E-06 1.30E-05 1.67E-05 8.14E-06 1.14E-05 P-32 2W .00E+00 1.10E+00 5.70E-02 1.60E-02 1.00E+05 2.00E+04 1.77E+01 1.26E-03 1.0 3.60E+02 .00E+00 .00E+00
.00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00
.00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 D 4.06E-06 3.00E-06 2.45E-05 4.70E-06 4.01E-06 4.02E-06 1.48E-05 2.70E-05 4.02E-06 7.51E-06 7.53E-06 5.01E-07 3.91E-06 3.56E-06 3.00E-06 3.01E-06 1.11E-05 2.02E-05 3.01E-06 5.21E-06 W 4.06E-06 3.00E-06 2.45C-05 4.70E-06 4.01E-06 4.02E-06 1.48E-05 2.70E-05 4.02E-06 7.51E-06 9.87E-05 1.28E-06 1.04E-05 3.87E-06 2.11E-06 2.11E-06 7.76E-06 1.42E-05 2.11E-06 1.56E-05 P-33 2W .00E+00 1.10E+00 5.70E-02 1.60E-02 1.00E+05 2.00E+04 1.04E+01 1.26E-03 1.0 3.60E+02 .00E+00 .00E+00
.00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00
.00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 D 3.47E-07 6.73E-07 3.13E-06 1.11E-06 3.47E-07 3.47E-07 1.85E-06 4.88E-06 3.47E-07 9.18E-07 1.10E-06 3.08E-07 6.85E-07 7.95E-07 2.58E-07 2.58E-07 1.37E-06 3.64E-06 2.58E-07 6.33E-07 W 3.47E-07 6.73E-07 3.13E-06 1.11E-06 3.47E-07 3.47E-07 1.85E-06 4.88E-06 3.47E-07 9.18E-07 1.56E-05 3.29E-07 1.39E-06 3.27E-06 1.87E-07 1.87E-07 9.95E-07 2.65E-06 1.87E-07 2.32E-06 S-35 2W .00E+00 5.90E-01 1.00E-01 1.60E-02 7.50E+02 1.00E+02 2.88E+00 1.20E-02 1.0 4.20E+01 .00E+00 .00E+00
.00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00
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asu ^
9 4
0 2 0 0
+ -
E E 0 2 0 7 1
0 3 0 0 _
+ - _
E E _
0 9 _
0 0 1
38731303874142 00000000000000 _
+- - - - ++- - - - - - _
EEEEEEEEEEEEEE 07108070976864 53877705846368 25288812536168 28742422875453 00000000000000
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EEEEEEEEEEEEEE 70708061110302 65382801899692 41184814116168 69831311984242 00000000000000 EEEEEEEEEEEEEE 77307062110000 .
42419136145557 13362672456167 39820203983231 00000000000000
+ - - + ++- - - - -
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+- - - - +-
EEEEEEEEEEEEEE 06001060600000 57710185472221 21484892265156 58731315874242 00000000000000 EEEEEEEEEEEEEE 07100020970000 03806080843139 25242442532222 49833334984444 00000000000000 EEEEEEEEEEEEEE 00700000680000 03018120547470 25511132675354 39853533985454 00000000000000 EEEEEEEEEEEEEE 090O0000110000 5 1 0.S.4 8 0 5 4 4 1. 2. 1 6 24573752572322 09840418875151 00000000000000 _
+- - +- - -
EEEEEEEEEEEEEE 64102026908180 00882833012723 9752521113831 _
Y YW Y W Y _
2 2 $
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l APPENDIX C TAPE 2.DAT - ENVIRONMENTAL AND FACILITY PARAMETERS w
f e
S
000005 01 0 00000.05 00000.05 91 01 11 1 0 50 00 0. 0 00 00 0 00000- 00000- 00000- - - - 1 - + - + - 0 E E E 0E EE E EE EE 0 0 0 0 00 0 00 00 0 6 6 2 0 00 0 00 00 0 0 9 9 99 1 01 01 7 7 3 5 55 4 14 14 3 000002 10 12 12 0 00000.0 00000+ 00000+
0 00000.0 00000+
1 0 .
- 5 11
- +
11 00 00 00 00 0
+ - + - +
E E E E1 EE EE EE EE 0 0 0 0 0 00 00 00 00 8 0 0 3 30 31 31 31 2 1 0 3 35 37 37 37 2 6. 6 3 31 31 31 31 000007 000007 10 00000.00 12 12 12 06 11 0 0 1 10 10 10 10 0 00000- 00000- 00000+ - 1 - + + - + - + 0-E E E E7 EE EE EE EE E 0 0 0 0 00 00 00 00 5 1 1 0 0 00 04 04 04 9 1
1 0 1 11 18 18 1
.8 7 1 1 0 9 97 93 93 93 00000.0 9 00000.10 00000.1 1 40 0
41 00 00 00 00 42 42 42 0.10 00000-E 00000-E 00000- +6 ++ ++ ++ ++ 0-E E8 EE EE EE EE E 0 0 0 0 00 50 50 50 4 1 5 9 6 60 34 34 34 5 2 9 9 96 18 18 18 1 1 5 3 2 28 93 93 93 0 00510 0500 00 7 0.1001 1
000.03 0.10 000+0-000.02 0.1 000.02 0.1 01001 01 0. 6 000+0- 000+0- + - - - - 1 - - + - + - 0 .
000E0E 000E0E E E EEEEE EEEE EE 56 000000 222020 0 0 00 00 00 111015 0 5 0 3 0 8 0.0 8 0 0.0 0 0
0 0 0 7 8 3 07.577
- 0. 6 . .
0500 00 00 5 5 8 1 8 1 1 26 4 14 14 66 2066 55 000.030.00 000+0+-
000.0 000+0+ -
00 00020.00 000+0+ -
0 100.01 01
- 0-10 10010 01
- 0-01 10 01 06 5+
0 000E0EE 000E0EE 000E0EE EE0EE EE0EE EE 2E 5550500 1110100 '3330300 09100 00100 00 0 0 03 0 00 0 04 33 39 30 30 30 5 5 50 0 55 8 58 33 30 30 30
- 3. 3 . . 4 2 42 4 42 5 46 3 33 32 32 32 2557 4411158 005.0 886+6+ -
00 440+0+-
0 00 775.025.00 56 10330310330330355 11011011011011080 114E4EE 1E1EE 114+4+ - - + - + - +- - + - + .+
5 00 111E1EE EEEEEEEEEEEEEEE1E 0 00 0 00 7 03 4 04 0 05 007.00000000000000000000000000 00 3
0, 5 6 05 8 09 110670100600600 . ...
- 2. 25
. . . . . . . 2 4 21 2 27 9 1111911111111 0002037 8821238 0000036 40059040940140i70 0 00 0 00 0000000 01000001 01001O .
441 +1 +- 668+8+ - ++++++ - + ++ ++ 0+- - + - - 10 339E9EE 1E1EE EEEEEEE EEEEEEEE EEEEEE 1 0 00 0 00 0000000 40000000 000000 1 5 03 8 04 0000005 0088040 400400 5 75 2 75 4411179 5.0024050 2 . . . . ...
500500 4 75 7 71 3399977 4141124 249249 00000.1 11 1 00000.11 10 00000.11 013.+10013010010 11 10110010710010001 0 .1 11111 - - 11111 - - 11111 - - + - ++ - .+ - + + - +1 -
EE EE EE EE7EEEEE4EEEEEE E 00 00 00 00 00000 000000 6 68 80 61 00 01100 007007 0 96 14 01 00 04300 503503 29 31 8
84 22 27722 324324 2242220 1 182110 3333300 0070010 0010010 0000010
- - - + - - . - - + - - - - - + 2080.10017010010810120520120100 01 EE 0.EEEE + 00- +- .+ - - + - EE0EEEE EEEEEEE fE 0EEEE0EEEEEE .E 0000000 00 0081100 00 0000 0000000 00 10000 00000004 44 001110000047100 0000 000000 61 6416 88 0806 0000066 00 7000 005005 77 3794 3123 2
11 1111126 11 3811 117117 y
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1 APPENDIX D l EXAMPLE TAPES - OPTIONS AND WASTE STREAM CHARACTERISTICS 4
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1 0 5 1 1 20 30 1
- SEC-RESINS 80.00 1.0 80.00 2 1 1 50 1 -1 -1 to 100 0 5 0 0 0 100
' H-3
- 1.15E-04 C-14
- 4.25E-06 CR-51 Y 1.33E-03 MN-54 W 2.36E-05 FE-55 Y 2.08E-05 FE-59 Y 6.62E-05 CO-58 Y 3.92E-05 CO-60 Y 4.03E-05 ZN-65 Y 9.12E-06 NI-59 W 2.49E-08 NI-63 W 7.66E-06 SR-90 Y 8.42E-06 NB-94 Y 7.86E-10 ZR-95 Y 2.69E-05 TC-99 W 3.58E-08 RU-103 Y 9.37E-05 AG-110 Y 5.88E-05 l-129 D 1.06E-07 CS-134 D 3.19E-04 CS-135 D 3.58E-08
. CS-137 D 9.54E-04 CE-141 Y 1.33E-04 CE-144 Y 1.47E-04 PU-238 Y 7.29E-06 PU-239 Y 3.69E-06 PU-241 Y 1.61E-04 PU ?42 Y 8.08E-09 AM-241 Y 8.54E-06 AM-243 Y 5.76E-07 CM-242 Y 1.61E-05 CM-243 Y 3.94E-09 CM-244 Y 4.42E-06 $
, 2 0 2 2 2 20 0 1 TRASH 100, 0.5 200.
I 2 1 0 0 5 -1 -1 32 10 4 16 50 20 20 10 H-3
- 1.15E-04 C-14
- 4.25E-06 CR-51 Y 1.33E-03 MN-54 W 2.36E-05 FE-55 Y 2.08E-05 FE-59 Y 6.62E-05 Co-58 Y 3.92E-05 CO-60 Y 4.03E-05 ZN-65 Y 9.12E-06 NI-59 W 2.49E-08 Ni-63 W 7.66E-06 SR-90 Y 8.42E-06 NB-94 Y 7.86E-10 ZR-95 Y 2.69E-05 TC-99 W 3.58E-08 RU-103 Y 9.37E-05 AC-110 Y 5.88E-05 1-129 D 1.06E-07 CS-134 D 3.19E-04 CS-135 D 3.58E-08
- CS-137 D 9.54E-04 CE-141-Y 1.33E-04 CE-144'Y 1.47E-04 PU-238 Y 7.29E-06 PU-239 Y 3.69E-06 PU-241 Y 1.61E-04 PU-242 Y 8.08E-09 AM-241 Y 8.54E-06 AM-243 Y 5.76E-07 CM-242 Y 1.61E-05 o, CM-243 Y 3.94E-09 CM-244 Y 4.42E-06 $
8 CON-DIRT 500. 1.6 312.5 i H 3 1 0 0 -1 -1 -1 3 100 0 1 0 0 0 100 U-238 Y 5.95E-07 U-234 Y 5.95E-07 TH-230 Y 5.95E-07 RA-226 W 5.95E-07 RN-222
i 1 2 1 1 2 20 5 1 1.0 -800.0
~
WASTE OIL 800.0 1 1 1 50 2 -1 -1 30 100. 30 1 100 0 0 0 AC-110 Y 2.4E-03 CE-141 Y 1.9E-01 CE-144 Y 6.5E-03 CO-58 Y 2.2E-02 Co-60 Y 3.9E-04 CR-51 Y' -1.8E+00 CS-134 D 1.2E-03 CS-137 D 8.1E-04 FE-55 Y 2.6E-01 FE-59 Y 3.OE-02
' MN-54 W 6.2E-03 NB-95 Y 6.1E-02 N1-63 W 2.1E-01 RB-86 D 8.8E-02 RU-103 Y 7.6E-02 RU-106 Y 5.9E-03 SR-89 Y 3.1E-02 SR-90 Y 7.1E-04 ZN-65 Y 1.0E-02 ZR-95 Y 3.4E-02 s
i t
S S
4 4
2
- i
APPENDIX E EXAMPLE TAPE 6.0VT - TOTAL WASTE STREAM DOSES FOR ALL PATINAYS D
IMPACTS-BRC VERSION 1.0 H *ARDOUS WASTE 11 LIFE = 20 OVFL= 1 NSTR= 1 REGN- 1 DATA = 0 IPOP= 1 INST = 30 WASTE: SEC-RESINS WEIGHT: 8.00E+01 MT DENSITY: 1.00E+00 MT/M3 1D= 2 lA= 1 IK1= 1 IK2= 50 PROCESS = 1 IXS= 10 100 0 5 ICS= 0 0 0 100 METAL PACKAGE RECYCLE IMPACTS MAXIND = 5.71E-04 MREM /YR t POPULN = 4.81E+01 PERSON-MREM /30 YRS TRANSPORTATION IMPACTS TR-MAX = 4.68E+00 MREM /YR TR-0CC = 9.36E+01 PERSON-MREM /YR
, TR-POP = 6.b1E+02 PERSON-MREM /VR INTRUDER IMPACTS (MREM /YR):
SCN LUNGS S. WALL LLI WALL T. BODY KlDNEYS LIVER RED MAR BONE THYROID ICRP INT-C0 1.23E-02 1.22E-02 1.22E-02 1.22E-02 1.22E-02 1.24E-02 1.23E-02 1.31E-02 1.22E-02 1.23E-02 INT-AG 2.40E-02 2.38E-02 2.38E-02 2.38E-02 2.38E-02 2.41E-02 2.39E-02 2.52E-02 2.38E-02 2.39E-02 q
EXPOSED WASTE IMPACTS (MREM /YR):
>" SCN LUNGS S. WALL LLI WALL T. BODY KlDNEYS LIVER RED MAR BONE THYROID ICRP IN-AIR 1.16E-03 1.30E-05 1.93E-05 1.57E-04 2.48E-04 1.64E-03 6.44E-04 7.70E-03 5.89E-05 7.03E-04 ER-AIR 2.72E-01 6.18E-05 9.53E-04 3.33E-02 5.25E-02 4.07E-01 1.54E-01 2.03E+00 1.13E-02 1.69E-01 IN-WAT 1.21E-06 2.69E-07 3.55E-07 7.09E-07 1.18E-06 2.90E-06 1.62E-06 1.01E-05 8.30E-07 1.51E-06 ER-WAT 4.33E-06 7.90E-07 1.11E-05 3.23E-05 6.96E-05 5.34E-04 2.03E-04 2.54E-03 1.03E-05 1.46E-04 INCINERATION AND OPERATIONAL IMPACTS: UNITS: IC-IND,1C-MWR,0P-lND,0P-MWR - (MREM /YR)
IC-POP,1C-WOR,0P-POP,0P-WOR - ( PERSON-MREM /YR)
SCN LUNGS S. WALL LLI WALL T. BODY KlDNEYS LIVER RED MAR BONE THYROID ICRP IC-POP .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 IC-IND .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 BC-WOR .00E+00 .00E+00 00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 IC-MWR .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 OP-POP .00E+00 .00E+00 00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 OP-lND 4.64E-11 1.43E-13 2.29E-13 4.50E-12 6.80E-12 5.09E-11 1.94E-11 2.42E-10 6.28E-13 2.27E-11 OP-WOR 1.48E+02 3.74E+01 3.76E+01 4.79E+01 5.34E+01 1.59E+02 8.36E+01 6.18E+02 3.86E+01 9.15E+01 OP-MWR 6.23E-01 2.40E-01 2.40E-01 2.76E-01 2.95E-01 6.60E-01 3.99E-01 2.24E+00 2.44E-01 4.26E-01 LEACHATE ACCUMULATION IMPACTS (MREM /YR):
k SCN LUNGS S. WALL LLI WALL T. BODY KIDNEYS LIVER RED MAR BONE THYROID ICRP LA-OPS 2.18E-04 1.65E-04 4.30E-04 2.57E-04 3.76E-04 1.65E-03 7.66E-04 7.18E-03 3.60E-04 6.28E-04 LA-OVF 7.77E-05 4.58E-05 8.07E-05 1.43E-04 2.41E-04 1.45E-03 6.15E-04 6.70E-03 2.46E-04 4.53E-04 LA-AIR 3.80E-02 2.63E-02 3.40E-02 2.85E-02 2.51E-02 5.01E-02 4.57E-02 1.88E-01 4.19E-02 3.71E-02 G
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4 SANITARY LANDFILL LIFE = 20 OVFL= 1 NSTR= 2 RECN= 2 DATA = 0 BPOP= 2 INST = 0 I
WASTE: TRASH WEICHT: 1.00E+02 MT DENSITY: 5.00E-01 MT/M3 ID= 2 IA= 1 IK1= 0 IK2= 0 PROCESS = 5 IXS= 32 10 4 16 ICS= 50 20 20 10
' METAL MATERIAL RECYCLE IMPACTS MAXIND = 3.21E-01 MREM /YR
' POPULN = 2.16E+04 PERSON-MREM /30 YRS' CLASS MATERIAL RECYCLE IMPACTS MAXIND = 3.32E+00 MREM /YR i
POPULN = 9.51E+03 PERSON-MREM /30 YRS i TRANSPORTATION IMPACTS TR-MAX = 1.15E+00 MREM /YR TR-0CC = 7.33E+01 PERSON-MREM /YR TR-POP = 4.80E+02 PERSON-MREM /YR INTRUDER IMPACTS (MREM /YR):
i SCN LUNCS S. WALL LLI WALL T. BODY KIDNEYS LIVER RED MAR BONE THYROID ICRP
- AT-C0 4.63E-02 4.60E-02 4.60E-02 4.61E-02 4.61E-02 4.63E-02 4.61E-02 4.73E-02 4.60E-02 4.62E-02 INT-AC 1.29E-01 1.29E-01 1.29E-01 1.29E-01 1.29E-01 1.29E-01 1.29E-01 1.30E-01 1.29E-01 1.29E-01 90 EXPOSED WASTE IMPACTS (MREM /YR)
, as SCN LUNGS S. WALL LLI WALL T. BODY KIDNEYS LIVER RED MAR BONE TH(ROID ICRP IN-AIR 2.05E-02 6.48E-04 1.24E-03 2.92E-03 4.45E-03 2.37E-02 9.84E-03 1.06E-01 1.68E-03 1.12E-02 ER-AIR 9.29E-03 1.15E-06 3.13E-05 1.13E-03 1.79E-03 1.39E-02 5.26E-03 6.91E-02 3.84E-04 5.77E-03
, IN-WAT 3.48E-06 9.22E-07 1.38E-06 1.76E-06 2.72E-06 4.16E-06 2.98E-06 9.88E-06 2.15E-06 3.18E-06 4 ER-WAT 4.45E-07 4.21E-08 1.17E-06 3.49E-06 7.61E-06 5.87E-05 2.22E-05 2.80E-04 1.10E-06 1.60E-05 INCINERATION AND OPERATIONAL IMPACTS: UNITS: IC-IND,1C-MWR,OP-IND,0P-MWR - (MREM /YR)
IC-POP, I C-WOR,0P-POP,0P-WOR - (PERSON-MREM /YR)
SCN LUNCS S. WALL LLI WALL T. BODY KIDNEYS LIVER RED MAR BONE THYROID ICRP IC-POP 7.34E+01 3.39E+00 6.50E+00 1.15E+01 1.67E+01 8.48E+01 3.64E+01 3.79E+02 7.23E+00 4.09E+01 BC-IND 5.59E-04 2.58E-05 4.95E-05 8.74E-05 1.27E-04 6.46E-04 2.77E-04 2.89E-03 5.50E-05 3.11E-04 IC-WOR 5.78E+01 5.7/E+01 5.17E+01 5.77E+01 5.77E+01 5.78E+01 5.77E+01 5.80E+01 5.77E+01 5.77E+01 IC-MWR 3.96E-01 3.94E-01 3.94E-01 3.94E-01 3.94E-01 3.96E-01 3.95E-01 4.02E-01 3.94E-01 3.95E-01 OP-POP 2.24E-01 7.09E-03 1.36E-02 3.20E-02 4.86E-02 2.59E-01 1.08E-01 1.16E+00 1.84E-02 1.23E-01 OP-IND 2.42E-04 7.67E-06 1.47E-05 3.46E-05 5.26E-05 2.80E-04 1.16E-04 1.26E-03 1.99E-05 1.33E-04
,OP-WOR 1.49E+00 1.47E+00 1.47E+00 1.48E+00 1.48E+00 1.49E+00 1.48E+00 1.57E+00 1.47E+00 1.48E+00 OP-MWR 9. 33E-02 9.21 E-02 9.21 E-02 9.22E-02 9.23 E-02 9. 34E-02 9.26E-02 9.84E-02 9.21 E-02 9.27E-02 LEACHATE ACCUMULATION IMPACTS (MREM /YR):
, SCN LUNCS S. WALL LLI WALL T. BODY . KIDNEYS LIVER RED MAR BONE THYROID ICRP LA-OPS 1.13E-05 4.70E-06 2.39E-05 1. 36E-05 2.41 E-05 1.31 E-04 5.50E-05 5.90E-04 .2.31 E-05 4.45E-05 LA-0VF 1.13E-05 4.70E-06 2.39E-05 1.36E-05 2.41E-05 1.31E-04 5.50E-05 5.90E-04 2.31E-05 4.45E-05 j LA-AIR 8.83E-02 3.67E-02 5.34E-02 4.02E-02 4.15E-02 1.20E-01 7.36E-02 4.79E-01 9.30E-02 7.22E-02
GROUND WATER IMPACTS (MREM /YR):
INTRUDER-WELL TIME LUNGS S. WALL LLI WALL T. BODY KIONEYS LIVER RED MAR DONE THYROID ICRP 20YR 1.36E-04 6.97E-05 1.34E-04 9.88E-05 1.16E-04 1.18E-04 1.42E-04 1.87E-04 9.79E-04 1.59E-04 40YR 1.42E-04 5.45E-05 1.12E-04 1.04E-04 1.18E-04 1.23E-04 1.68E-04 2.56E-04 1.85E-03 1.91E-04 60YR 1.43E-04 6.39E-05 1.21E-04 1.19E-04 1.23E-04 1.33E-04 1.96E-04 3.35E-04 2.73E-03 2.27E-04 80YR 1.10E-04 5.91E-05 1.03E-04 1.06E-04 9.90E-05 1.09E-04 1.77E-04 3.22E-04 3.00E-03 2.10E-04 100YR 7.95E-05 5.17E-05 8.35E-05 9.03E-05 7.52E-05 8.41E-05 1.52E-04 2.91E-04 2.98E-03 1.83E-04 120YR 6.03E-05 4.69E-05 7.24E-05 8.02E-05 6.05E-05 7.17E-05 1.37E-04 2.86E-04 2.97E -03 1.67E-04 160YR 4.05E-05 4.19E-05 5.93E-05 6.94E-05 4.49E-05 5.52E-05 1.20E-04 2.63E-04 2.96E-03 1.50E-04 200YR 3.25E-05 3.98E-05 5.47E-05 6.51E-05 3.89E-05 5.07E-05 1.14E-04 2.65E-04 2.95E-03 1.43E-04 400YR 2.58E-07 1.76E-07 5.31E-06 8.64E-07 1.60E-06 1.17E-05 4.61E-06 6.16E-05 1.69E-07 3.88E-06 600YR 5.03E-06 3.66E-07 1.50E-05 3.95E-05 8.67E-05 6.69E-04 2.52E-04 3.19E-03 4.82E-06 1.82E-04
- 800YR 3.97E-06 3.27E-07 1.37E-05 3.09E-05 6.76E-05 5.23E-04 1.97E-04 2.50E-03 3.77E-06 1.43E-04 1K YR 3.17E-06 2.91E-07 1.22E-05 2.44E-05 5.34E-05 4.12E-04 1.55E-04 1.98E-03 2.99E-06 1.13E-04 2K YR 3.60E-06 3.14E-07 1.27E-05 2.71E-05 5.94E-05 4.59E-04 1.73E-04 2.24E-03 3.42E-06 1.27E-04 5K YR 3.62E-06 3.11E-07 1.20E-05 2.64E-05 5.79E-05 4.47E-04 1.68E-04 2.24E-03 3.46E-06 1.25E-04 10K YR 1.91E-07 1.24E-07 5.59E-06 8.86E-07 1.79E-06 1.38E-05 5.36E-06 7.33E-05 1.04E-07 4.44E-06 20K YR 1.45E-07 9.31E-08 4.21E-06 6.68E-07 1. 35E-06 1.04E-05 4.04E-06 5.52E-05 7.92E-08 3. 35E-06 POPULATION-WELL TIME LUNGS S. WALL LLI WALL T. BODY KIDNEYS LIVER RED NAR BONE THYROID ICRP 20YR .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 40YR .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 60YR .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 80YR .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 100YR 7.31E-07 4.80E-07 7.60E-07 8.28E-07 6.88E-07 7.44E-07 1.38E-06 2.50E-06 2.72E-05 1.67E-06 n, 120YR 1.65E-06 1.29E-06 1.92E-06 2.19E-06 1.64E-06 1.80E-06 3.68E-06 6.98E-06 8.12E-05 4.52E-06 e 160YR 3.31E-05 3.43E-06 4.67E-06 5.66E-06 3.62E-06 4.08E-06 9.66E-06 1.93E-05 2.42E-04 1.21E-05 45 200YR 2.95E-06 3.62E-06 4.70E-06 5.88E-06 3.45E-06 3.95E-06 1.01E-05 2.07E-05 2.69E-04 1.28E-05 400YR 2.38E-06 3.38E-06 4.13E-06 5.37E-06 2.97E-06 3.44E-06 9.45E-06 1.97E-05 2.49F-06 4.31E-06 600YR 1.44E-09 1.69E-09 1.57E-08 2.92E-09 1.67E-09 1.47E-09 1.70E-09 1.76E-09 1.46E-09 3.01E-09 800YR 7.44E-10 8.77E-10 8.72E-09 1.71E-09 9.84E-10 7.84E-10 1.01E-09 1.07E-09 7.82E-10 1.79E-09 IK YR 2.82E-09 2.15E-09 7.29E-08 1.18E-08 2.18E-08 1.63E-07 6.38E-08 8.63E-07 1.84E-09 5.37E-08 2K YR 2.22E-08 1.47E-08 6.45E-07 1.02E-07 2.05E-07 1.58E-06 6.13E-07 8.37E-06 1.23E-08 5.09E-07 5K YR 2.01E-08 1.30E-08 5.86E-07 9.30E-08 1.87E-07 1.45E-06 5.62E-07 7.69E-06 1.09E-08 4.66E-07 10K YR 4.58E-08 1.27E-08 5.56E-07 2.92E-07 6.27E-07 4.84E-06 1.84E-06 2.46E-05 3.74E-08 1.40E-06 20K YR 1.32E-08 8.48E-09 3.83E-07 6.08E-08 1.23E-07 9.48E-07 3.68E-07 5.03E-06 7.22E-09 3.05E-07 POPULATION-SURFACE WATER
. TIME LUNGS S. WALL LLI WALL T. BODY KIDNEYS LIVER RED MAR BONE THYRolD ICPP 20YR .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 40YR .00E+00 .00E+00 00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 60YR .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 80VR .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 100YR .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 120YR .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 00E+00 .00E+00 160YR .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 200YR 2.57E-08 2.85E-08 3.62E-08 4.65E-08 2.89E-08 3.27E-08 8.01E-08 1.62E-07 1.23E-06 7.60E-08 400YR 1.86E-07 2.63E-07 3.23E-07 4.21E-07 2.32E-07 2.68E-07 7.33E-07 1.53E-06 1.22E-05 6.96E-07 600YR 1.19E-10 1.94E-10 2.54E-09 4.28E-10 2.02E-10 1.35E-10 2.09E-10 2.19E-10 1.12E-10 4.42E-10 800YR 7.88E-11 1.50E-10 2.16E-09 3.61E-10 1.62E-10 9.58E-11 1.70E-10 1.79E-10 7.39E-11 3.73E-10 1K YR 7.10E-11 1.40E-10 2.06E-09 3.45E-10 1.54E-10 8.79E-11 1.61E-10 1.71E-10 6.61E-11 3.57E-10
. 2K YR 1.67E-1C 1.99E-10 5.00E-09 8.09E-10 1.11E-09 7.57E-09 3.06E-09 3.99E-08 1.18E-10 2.75E-09 SK YR 9.42E-10 6.15E-10 2.78E-08 4.42E-09 8.91E-09 6.87E-08 2.67E-08 3.65E-07 5.37E-10 2.21E-08 10K YR 8.22E-10 5.34E-10 2.41E-08 3.84E-09 7.73E-09 5.97E-08 2.32E-08 3.17E-07 4.70E-13 1.92E-08 20K YR 1.47E-09 4.42E-10 1.96E-08 9.24E-09 1.98E-08 1.53E-07 5.80E-08 7.77E-07 1.19E-09 4.45E-08
WASTE: CON-DIRT ID= 3 IA= 1 WEICHY: 5.00E+02 MT DENSITY: 1.60E+00 MT/M3 IXS=
IK1= 0 IK2= 0 PROCESS = 1 3 100 0 1 ICS= 0 0 0 100 TRANSPORTATION IMPACTS TR-MAX = 6.95E-02 MREM /YR TR-0CC = 4.17E-01 PERSON-HREM/YR TR-POP = 2. 73E+00 PERSON-MREM /YR INeHuuER MPACTS (MREM /YR):
SCN LUNGS S. WALL LLI WALL T. BODY KIDNEYS LIVER REO MAR I N T-CO 1.90E-02 1.42E-02 1.42E-02 1. 45 E-02 BONE THYROID ICRP INT-AG 1.64E-01 1.47E-01 1.46E-01 1.64E-01 1.43E-02 1.44E-02 1.53E-02 3.08E-02 1.42E-02 1.58E-02 EXPOSED WASTE IMPACTS (MREM /YR): 1.56E-01 1.50E-01 1.59E-01 1.86E-01 1.84E-01 1.66E-01 SCN LUNGS S. WALL LLI WALL T. BODY KlDNEYS LIVER RED MAR BONE THYRotD IN-AIR 2.19E-02 ER-AIR 9.85E-063.46E-04 4.82E-02 2.17E-05 1.5 7E-04 1.60E-03 3.51E-03 9.21E-04 2.03E-03 2.80E-03
. 1.27E-03 1 57.65E-03 22E-02
-02 1.71E-04 55EICRP 103 8 26E IN-WAT .82E-01 3.76E-04 1.69E-02 T 2.2.49E-06 8.30E-08 1.64E-06 6.94E-045.82E-06 3.56E-03 2.99E-05 8.92E-06 7 73E 06 6 82E ER-WA 97E-04 9.88E-06 1.95E-04 . .
-05 2.49E-06 1.01E-05 INCINERATION AND OPERATIONAL IMPACTS: 1.06E-03 9.21E-04 8.13E-03 2.97E-04 1.20E-03 w UNITS:
IC-I ND,1C-MWR,0P-IND,0P-MWR - (MREM /YR )
IC-POP,1C-WOR, OP-POP,0P-WOR -
SCN LUNCS S. WALL (PERSON-MREM /YR)
IC-POP .00E+00 .00E+00 LLI WALL T. BODY KIDNEYS
.00E+00 .00E+00 LIVER RED MAR BONE THT.060 IC-IND .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 ICRP
.00E+00 .00E+00 IC-WOR .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00
.00E+00 BC-MWR .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 OP-POP 2. 39E-01 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00
.00E+00 .00E+00 .00E+00 .00E+00 OP-IND 4.14E-03 1.87E-06 2.98E-05 3.02E-04 1. 74E-04 2.41E-04 1 05E-03 11.08E-0 i
1.87E-03 8.37E-02 OP-WOR5.13E-02 OP-MWR 5.13E-022.85E-02 2.85E-02 2.85E-02 2.85E-02 2.97E-02 2.97E-02 2.87E-02 2.87E-02 2.93E-02
. 2.93E-02
-01 2.85E-02 3 36L 02 1 08E.56E-02 3.23E-05 1.
3 36E3.60E-02 02 1.08E-01 2.85E-02 3.60E-02 LEACHATE ACCUMULATION IMPACTS (MREM /YR):
SCN LUNGS S. WALL LLI WALL T. BODY KIONEYS LIVER RED MAR BONE THYROID LA-OPS 1.36E-03 2.74E-04 1.09E-03 5.62E-03 4.60E-03 5.89E-03 . . 7 89E-03 ICRP 8 78E LA-AIR 8.67E-02 2.03E-04 7.23E-04 9.91E-03 2.56E-03 9.37E-03 4 52E-0 e .
- 2 1.41E-03
-1 5.58E-03 1.10E-03 4.53E-02
=
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CUMULATIVE IMPACTS INTRUDER IMPACTS (MREM /YR):
SCN LUNGS S. WALL LLI WALL T. BODY KlDNEYS LIVER RED MAR BONE THYROID ICRP INT-C0 6.53E-02 6.03E-02 6.03E-02 6.05E-02 6.04E-02 6.07E-02 6.14E-02 7.82E-02 6.03E-02 6.20E-02 INT-AC 2.93E-01 2.76E-01 2.75E-01 2.93E-01 2.84E-01 2.79E-01 2.88E-01 3.16E-01 3.12E-01 2.94E-01 EXPOSED WASTE IMPACTS (MREM /YR):
SCN LUNGS S. WALL LLI WALL T. BODY KIDNEYS LIVER RED MAR BONE THYROID ICRP IN-AIR 4.23E-02 6.58E-04 1.40E-03 4.52E-03 5.37E-03 2.49E-02 1.54E-02 1.89E-01 1.85E-03 1.89E-02 ER-AIR 5.74E-02 2.28E-05 3.77E-04 4.64E-03 3.82E-03 1.67E-02 1.75E-02 2.51E-01 7.59E-04 2.26E-02 IN-WAT 5.97E-06 1.00E-06 3.02E-06 7.58E-06 3.26E-05 1.31E-05 1.07E-05 7.81E-05 4.64E-06 1.32E-05 ER-WAT 2.98E-04 9.93E-06 1.97E-04 6.97E-04 3.57E-03 1.12E-03 9.43E-04 6.41E-03 2.98E-04 1.22E-03 INCINERATION AND OPEhATIONAL IMPACTS: UNITS: IC-IND,1C-MWR,0P-IND,OP-MWR - (MREM /YR)
IC-POP, lC-WOR,0P-POP,0P-WOR - ( PERSON-MREM /YR) rn SCN LUNGS S. WALL LLI WALL T. BODY KIDNEYS LlVER RED MAR BONE THYRolD ICRP e
'd IC-POP 7.34E*01 3.39E+00 6.50E+00 1.15E+01 1.67E+01 8.48E+01 3.64E+01 3.79E+02 7.23E+00 4.09E+01 IC-lND 5.59E-04 2.58E-05 4.95E-05 8.74E-05 1.27E-04 6.46E-04 2.77E-04 2.89E-03 5.50E-05 3.11E-04 IC-WOR 5.78E+01 5.77E+01 5.77E+01 5.77E+01 5.77E+01 5.78E+01 5.77E+01 5.80E+01 5.77E+01 5.77E+01 IC-MWR 3.96E-01 3.94E-01 3.94E-01 3.94E-01 3.94E-01 3.96E-01 3.95E-01 4.02E-01 3.94E-01 3.95E-01 OP-POP 4.63E-01 7.20E-03 1.53E-02 4.94E-02 5.87E-02 2.73E-01 1.68E-01 2.07E+00 2.02E-02 2.06E-01 OP-IND 4.39E-03 9.54E-06 4.44E-05 3.37E-04 2.27E-04 5.21E-04 1.17E-03 1.69E-02 5.22E-05 1.58E-03 OP-WOR 1.54E+00 1.50E+00 1.50E+00 1.50E+00 1.50E+00 1.52E+00 1.52
~
OP-MWR 1.45E-01 1.21E-01 1.21E-01 1.22E-01 1.21E-01 1.23E-01 1.26[+00 E-01 1.68E+00 1.50E+001.29E-01 2.06E-01 1.21E-01 1.52E+00 LEACHATE ACCUMULATION IMPACTS (MREM /YR): .
SCN LUNCS S. WALL LLI WALL T. BODY KIDNEYS LIVER RED MAR BONE THYRO 10 ICRP LA-OPS 1.37E-03 2.78E-04 1.11E-03 5.64E-03 4.63E-03 6.02E-03 7.94E-03 8.84E-02 1.43E-03 5.62E-03
+
LA-OVF 1.37E-03 2.78E-04 1.11E-03 5.64E-03 4.63E-03 6.02E-03 7.94E-03 8.84E-02 1.43E-03 5.62E-03 LA-AIR 1.75E-01 3.69E-02 5.41E-02 5.01E-02 4.40E-02 1.29E-01 1.19E-01 1.17E+00 9.41E-02 1.17E-01 i
e e
o GROUND WATER IMPACTS (MREM /YR):
- INTRUDER-WELL TIME LUNGS S. WALL LLI WALL T. BODY KIDNEYS LIVER RLD MAR BONE THYROID ICRP 20YR 1.36E-04 6.97E-05 1.34E-04 9.88E-05 1.16E-04 1.18E-04 1.42E-04 1.87E-04 9.79E-04 1.59E-04 40YR 1.42E-04 5.45E-05 1.12E-04 1. 04 E-04 1.18 E-04 1.23E-04 1.68E-04 2.56E-04 1.85E-03 1.91E-04 60YR 1.43E-04 6.39E-05 1.21E-04 1.19E-04 1.23E-04 1.33E-04 1.96E-04 3.35E-04 2.73E-03 2.27E-04
- 80YR 1.10E-04 5.91E-05 1.03E-04 1.06E-04 9.90E-05 1.09E-04 1.77E-04 3.22E-04 3.00E-03 2.10E-04 100YR 7.95E-05 5.17E-05 8.35E-05 9.03E-05 7.52E-05 8.41E-05 1.52E-04 2.91E-04 2.98E-03 1.83E-04
' 120YR 6.03E-05 4.69E-05 7.24E-05 8.02E-05 6.05E-05 7.17E-05 1.37E-04 2.86E-04 2.97E-03 1.67E-04 e
160YR 5.39E-04 6.81E-05 3.47E-04 2.83E-03 5.43E-04 5.53E-04 1.92E-03 1.64E-02 3.46E-03 1.29E-03 200YR 5.23E-04 6.56E-05 3.37E-04 2.78E-03 5.29E-04 5.40E-04 1.88E-03 1.61E-02 3.45E-03 1.26E-03 400YR 9.00E-04 4.74E-05 5.23E-04 4.98E-03 9.00E-04 9.08E-04 3.24E-03 2.91E-02 9.09E-04 2.05E-03
'600YR 1.26E-03 7.35E-05 1.08E-03 7.10E-03 1.33E-03 1.95E-03 7.05E-03 8.13E-02 1.26E-03 4.48E-03 800YR 1.53E-03 8. 79E-05 1.24E-03 8.62E-03 1.59E-03 2.07E-03 7.99E-03 8.95E-02 1.54E-03 5.07E-03
- 1K YR 1.75E-03 9.95E-05 1.37E-03 9.84E-03 1.79E-03 2.18E-03 8.74E-03 9.61E-02 1.77E-03 5.54E-03
. , 2K YR 2.30E-03 1.43E-04 2.37E-03 1.31E-02 2.33E-03 2.83E-03 1.53E-02 1.89E-01 2.3?E-03 9.67E-03
- SK YR 7.44E-04 8.96E-05 2.85E-03 5.09E-03 1.10E-03 4.17E-03 2.01E-02 3.03E-01 7.10E-04 1.27E-02 10K YR 4.12E-05 2.04E-06 5.88E-05 3.83E-04 6.59E-04 5.07E-03 2.71E-03 3.22E-02 4.08E-05 1.73E-03 20K YR 1.72E-06 1.67E-06 3.23E-05 5.28E-06 1.21E-05 1.15E-05 6.40E-06 7.57E-05 1.51E-06 8.23E-06 POPULATION-WELL TIME LUNGS S. WALL LLI WALL T. BODY KIDNEYS LIVER RED MAR BONE THYROID ICRP 20YR .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00
- 40YR .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 00E+00
= 60YR .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00
- 80YR .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00L+00 .00E+00 '
n, a
. 100YR 7.31E-07 4.80E-07 7.60E-07 8.28E-07 6.88E-07 7.44E-07 1.38E-06 2.50E-06 2.72E-05 1.67E-06 e
120YR 1.65E-06 1.29E-06 1.92E-06 2.19E-06 1.64E-06 1.80E-06 3.68E-06 6.98E-06 8.12E-05 4.52E-06 CD - 160YR 3.31E-06 3.43E-06 4.67E-06 5.66E-06 3.62E-06 4.08E-06 9.66E-06 1.93E-05 2.42E-04 1.21E-05 200YR 2.95E-06 3.62E-06 4.70E-06 5.88E-06 3.45E-06 3.95E-06 1.01E-05 2.07E-05 2.69E-04 1.28E-05 400YR 2.38E-06 3.38E-06 4.13E-06 5.37E-06 2.97E-06 3.44E-06 9.45E-06 1.97E-05 2.49E-06 4.31E-06 600YR 1.44E-09 1.69E-09 1.57E-08 2.92E-09 1.67E-09 1.47E-09 1.70E-09 1.76E-09 1.46E-09 3.01E-09 800YR 7.44E-10 8.77E-10 8.72E-09 1.71E-09 9.84E-10 7.84E-10 1.01E-09 1.07E-09 7.82E-13 1.79E-09 3 .
4 1K YR 2.82E-09 2.15E-09 7.29E-08 1.18E-08 2.18E-08 1.63E-07 6.38E-08 8.63E-07 1.84E-09 5.37E-08 2K YR 2.22E-08 1.47E-08 6.45E-07 1.02E-07 2.05E-07 1.58E-06 6.13 E-07 8. 37E-06 1.23 E-08 5.09E-07
. # 5K YR 5.59E-05 2.95E-06 3.28E-05 3.10E-04 5.61 E-05 5.72E-05 2.02E-04 1.82E-03 5.65E-05 1.28E-04 10K YR 7. 79E-06 1.07E-06 3.56E-05 5.44E-05 7.81E-06 1.51 E-05 2. 33E-04 3.61 E-03 7. 34E-06 1.47E-04 20K YR 1.32E-08 8.48E-09 3.83E-07 6.08E-08 1.23E-07 9.48E-07 3.68E-07 5.03E-06 7.22E-09 3.05E-07 POPULATION-SURFACE WATER TIME LUNGS S. WALL LLI WALL T. BODY KIDNEYS LIVER RED MAR BONE THYROID ICRP
. 20YR .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00
.00E+00 .00E+00
, . 40YR .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 00E+00 .00E+00 60YR .000+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 80YR .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 100YR .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 120YR .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00
, 160YR .00E+00 .00E+00 .00E+00 00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00
.' 200YR 2.57E-08 2.65E-08 3.62E-08 4.65E-08 2.89E-08 3.27E-08 8.01E-08 1.62E-07 1.23E-06 7.60E-08 400YR 1.86E-07 2.63E-07 3.23E-07 4.21E-07'2.32E-07 2.68E-07 7.33E-07 1.53E-06 1.22E-05 6.96E-07 600YR 1.19E-10 1.94E-10 2.54E-09 4.28E-10 2.02E-10 1.35E-10 2.09E-10 2.i9E-10 1.12E-10 4.42E-10 800YR 7.88E-11 1.50E-10 2.16E-09 3.61E-10 1.62E-10 9.58E-11 1.70E-10 1.79E-10 7.39E-11 3.73E-10 1K YR 7.10E-11 1.40E-10 2.06E-09 3.45E-10 1.54E-10 8.79E-11 1.61E-10 1.71E-10 6.61E-11 3.57E-10 2K YR 1.67E-10 1.99E-10 5.00E-09 8.09E-10 1.11E-09 7.57E-09 3.06E-09 3.99E-08 1.18E-10 2.75E-09 SK YR 9.42E-10 6.15E-10 2.78E-08 4.42E-09 8.91E-09 6.87E-08 2.67E-08 3.65E-07 5.37E-10 2.21E-08 10K YR 3.25E-07 1.59E-08 2.10E-07 1.81 E-06 3.31 E-07 3.83 E-07 1.19E-06 1.08E-05 3.27E-07 7.59E-07 20K YR 6.46E-08 3.67E-08 1.60E-06 9.51E-07 5.88E-08 3.49E-07 1.06E-05 1.72E-04 4.23E-08 6.69E-06
e 00 SITE INC, S. LAM 9F LIFE = 20 OVFL= 1 NSTR= 1 REGN= 1 DATA = 2 I PO P= 2 INST = 5 OPTIONAL ENVIRONMENTAL PARAMETERS PRC = 1.80E-01 TXC = 1.00E+00 QFC = 1.10E+02 2.00E+05 4.50E+06 FSC = 2.64E-10 DTTM= 1.70E+00 TT*1 = 1.85E+00 2.50E+01 5.00E+01
. FSA = 8.06E-11 DTPC= .00E+00 TPC = .00E+00 .00E+00 .00E+00 WVEL= 6.67E+00 AWOQ= 1.40E-10 EFAC= 7.95E-06 WASTE: WASTE OIL WElGHT: 8.00E+02 MT DENSITY: 1.00E+00 MT/M3 ID= 1 IA= 1 IK1= 1 lK2= 50 PROCESS = 2 IXS= 30 100 30 1 ICS= 100 0 0 0 METAL PACKAGE RECYCLE IMPACTS MAXIND = 9.64E-01 MREM /YR POPULN = 3.83E+03 PERSON-MREM /30 YRS
'7 RANS PORT AT 10N ' I M PACT S TR-MAX = 1.39E+03 MREM /YR TR-0CC = 8.33E+04 PERSON-MREM /YR TR-POP = 2.04E+06 PERSON-MREM /YR INTRUDER IMPACTS (MREM /YR):
SCN LUNGS S. WALL LLI WALL T. B00Y KIDNEYS LIVER RED MAR BONE THYROID ICRP rn INT-CO 1.14E+01 1.09E+01 1.09E+01 1.09E+01 1.09E+01 1.09E+01 1.09E+01 1.09E+01 1.09E+01 1.10E+01
- INT-AG 3.06E+01 3.05E+01 3.08E+01 3.05E+01 3.05E+01 3.05E+01 3.0$E+01 3.05E+01 3.05E+Cl 3.05E+01 EXPOSED WASTE IK* ACTS (MREM /YR):
SCN LUNGS S. WALL LLI WALL T. BODY KIDNEYS LIVER RED MAR BONE THYROID ICRP s IN-AIR 5.03E-01 5.97E-02 5.22E-01 1.11E-01 1.03E-01 1.24E-01 1.08E-01 1.24E-01 9.61E-02 2.05E-01
. ER-AIR 5.82E-03 1.87E-03 1.39E-02 3.13E-03 1.57E-03 1.57E-03 1.57E-03 1.57E-03 1.57E-03 3.13E-03 IN-WAT 9.29E-04 3.21E-04 2.13E-03 5.88E-04 7.29E-04 8.54E-04 7.25E-04 8.28E-04 6.50E-04 9.41E-04 ER-WAT 6.42E-06 7.93E-06 6.93E-05 1.18E-05 6.42E-06 6.42E-06 6.42E-06 6.42E-06 6.42E-06 1.18E-05 INCINERATION AND OPERATIONAL IMPACTS: UNITS: I C- I ND,1 C-MWR, O P- I ND, O P-MWR - (MREM /YR)
IC-POP,1C-WOR,OP-POP,OP-WOR - ( PERSON-MREM /YR)
SCN LUNCS S. WALL LLI WALL T. BODY K l DN EYS LIVER RED MAR BONE THYROID ICRP IC-POP 2.36E+04 7.27E+03 1.23E+05 7.43E+03 8.22E+03 8.34E+03 8.71E+03 1.30E+04 7.69E+03 2.21E+04 IC-!ND 4.71E+00 1.45E+00 2.46E+01 1.49E+00 1.64E+00 1.67E+00 1.74E+00 2.61E+00 1.52E+00 4.41E+00 IC-WOR 5.'71E+05 5.71E+05 5.71E+05 5.71E+05 5.71E+05 5.71E+05 5.71E+05 5.71E+05 5.71E+05 5.71E+05 IC-MW3 6.89E+02 6.89E+02 6.89E+02 6.89E+02 6.89E+02 6.89E+02 6.89E+02 6.89E+02 6.89E+02 6.89E+02 O P-POP 2.01 E+01 5.78E+00 6.49E+01 7.03E+00 7.93F+00 8.26E+00 8.26E+00 1.47E+01 7.52E+00 1.60E+01 OP-4ND ll21E-01 3.47E-02 3.89E-01 4.22E-02 4.76E-02 4.95E-02 4.96E-02 8.83E-02 4.51E-02 9.61E-02 OP-WOR 4.25E+03 4.25E+03 4.25E+03 4.25E+03 4.25E+03 4.25E+03 4.25E+03 4.25E+03 4.25E+03 4.25E+03
. OP-MWR 4.25E+03 4.25E+03 4.25E+03 4.25E+03 4.25E+03 4.25E+03 4.25E+03 4.25E+03 4.25E+03 4.25E+03 LEACHATL ACCUMULATION IMPACTS (MREM /YR):
SCN LUNCS S. WALL LLI WALL T. BODY KlDNEYS LIVER RED MAR BONE THYROID ICRP LA-OPS 8.44E+00 7.29E+00 1.55E+02 6.57E+00 7.27E+00 7.49E+00 7.82E+00 1.48E+01 6.14E+00 2.19E+01 LA-OVF 7.96E-01 7.08E-01 8.5GE+00 1.09E+00 7.67E-01 9.00E-01 8.21E-01 8.88E-01 7.57E-01 1.46E+00 LA-AIR 1.11E+01 1.61E+00 2.14E+01 2.66E+00 1.65E+00 1.83E+00 1.81E+00 2.00E+00 1.64E+00 4.68E+00 .
9 e
. _ - _ _ _ - _ _ - _ _ - _ - _ - - _ _ _ _ _ _ - - _ _ ____ __,__- _-_____ __-_ - __-___ - - - - _ _ - - - - - - _ - _ - _ _ _ _ _ _ - - = - - _
GROUND WATER IMPACTS (MREM /YR):
INTRUDER-WELL TIME LUNGS S. WALL LLI WALL T. B00Y K10NEYS LIVER RED MAR BONE THYROID ICHP 20YR 5.24E+00 6.26E+00 5.67E+01 9.42E+00 5.20E+00 5.29E+00 5.75E+00 6.28E+00 5.19E+00 9.69E+00 40YR 4.35E+00 5.33E+00 4.79E+01 7.97E+00 4.34E+00 4.34E+00 4.67E+00 5.02E+00 4.33E+00 0.09E+00 60YR 3.73E+00 4.58E+00 4.08E+01 6.83E+00 3.72E+00 3.72E+00 3.92E+00 4.13E+00 3.72E+00 6.90E+00 80YR 3.20E+00 3.93E+00 3.49E+01 5.86E+00 3.19E+00 3.19E+00 3.32E+00 3.45E+00 3.19E+00 5.90E+00 100YR 2.75E+00 3.38E+00 2.99E+01 5.03E+00 2.74E+00 2.74E+00 2.82E+00 2.90E+00 2.74E+00 5.06E+00 120YR 2.36E+00 2.91E+00 2.56E401 4.32E+00 2.36E+00 2.36E+00 2.40E+00 2.45E+00 2.36E+00 4.34E+00 160YR 1.74E+00 2.15E+00 1.89E+01 3.19E+00 1.74E+00 1.74E+00 1.76E+00 1.78E+00 1.74E+00 3.20E+00 200YR 1.29E+00 1.59E+00 1.39E+01 2.36E+00 1.29E+00 1.29E+00 1.29E+00 1.30E+00 1.29E+00 2.36E+00 400YR 2.86E-01 3.53E-01 3.08E+00 5.23E-01 2.86E-01 2.86E-01 2.86E-01 2.86E-01 2.86E-01 5.23E-01 600YR 6.33E-02 7.82E-02 6.84E-01 1.16E-01 6.33E-02 6.33E-02 6.33E-02 6.33E-02 6.33E-02 1.16E-01
- 800YR 1.40E-02 1.73E-02 1.52E-01 2.57E-02 1.40E-02 1.40E-02 1.40E-02 1.40E-02 1.40E-02 2.57E-02 IK YR 3.1 E-03 3.85E-03 3.36E-02 5.71E-03 3.12E-03 3.12E-03 3.12E-03 3.12E-03 3.12E-03 5.71E-03 2K YR 1 E-06 2.07E-06 1.80E-05 3.06E-06 1.67E-06 1.67E-06 1.67E-06 1.67E-06 1.67E-06 3.06E-06 SK YR . DE+00 .00E+00 .00E+00 .00E+00 .00E+00 00E+00 .00E+00 .00E+00 00E+00 .00E+00 10K YR 00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 20K YR .00E+Go .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 >
POPULATION-WELL
- TIME LUNGS S. WALL LLI WALL T. BODY KIDNEYS LIVER RED MAR BONE THYROID ICRP 20YR .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00- .00E+00 .00E+00 .00E+00 40YR 3.57E-01 4.37E-01 3.93 E+00 6.54E-01 3.56E-01 3.56E-01 3.83E-01 4.11' 01 3.55E-01 6.63E-01 60YR 3.40E-01 4.17E-01 3.72E+00 6.?2E-01 3.39E-01 3.39E-01 3.58E-01 3.776 31 3.39E-01 6.29E-01 80YR 2.91E-01 3.58E-01 3.18E+00 5.34E-01 2.91E-01 2.91E-01 3.02E-01 3.14E-01 2.91E-01 5.38E-01 100YR.2.50E-01.3.06E-01 2.72E+0C 4.58E-01 2.50E-01 2.50E-01 2.57E-01 2.64E-01 2.50E-01 4.61E-01 rf 120YR 2.15E-01 2.65E-01 2.33E+00 3.94E-01 2.15E-01 2.15E-01 2.19E-01 2.23E-01 2.15E-01 3.95E-01 r pa 160YR 1.59E-01 1.96E-01 1.72E+00 2.91E-01 1.59E-01 1.59E-01 1.60E-01 1.62E-01 1.59E-01 2.91E-01 CD 200YR 1.17E-01 1.45E-01 1.27E+00 2.15E-01 1.17E-01 1.17E-01 1.18E-01 1.19E-01 1.17E-01 2.15E-01 400YR 2.60E-02 3.21E-02 2.81E-01 4.77E-02 2.60E-02 2.60E-02 2.60E-02 2.60E-02 2.60E-02 4.77E-02 600YR 5.77E-03 7.13E-03 6.23E-02 1.06E-02 5.77E-03 5.77E-03 5.77E-03 5.77E-03 5.77E-03 1.06E-02
. 800YR 1.28E-03 1.5et-03 1.38E-02 2.34E-03 1.28E-03 1.23C-03 1.28E-03 1.28E-C1 1.28E-03 2.34E-03
. 1K YR 2.84E-04 3.51E-04 3.06E-03 5.20E-04 2.84E-04 2.84E-04 2.84E-04 2.84E-04 2.84E-04 5.20E-04
. . 2K YR 1.52E-07 1.88E-07 1.64E-06 2.79E-07 1.52E-07 1.52E-07 1.52E-07 1.52E-07 1.52E-07 2.79E-07 SK YR .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 e 10K YR . .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 00E+00 .00E+00 .00E+00 .00E+00 .00E+00
, .- 20K YR .00E+00 .00E+00 .00E+00 .00F+0G .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 POPULATION-SURFACE WATER TIME LUNGS S. WALL LLI WALL T. BODY KIDNEYS L6VER RED MAR BONE THYROID ICRP 20YR .00E+00 .00E+00 .00E+00 .OOE+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00
~
'40YR .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 3 60YR 1.08E-02 1.31E-02 1.17E-01 1.96E-02 1.08E-02 1.08E-02 1.13E-02 1.18E-02 1.07E-02 1.99E-02 80YR 1.54E-02 1.88E-02 1.66E-01 2.80E-02 1.54E-02 1.54E-02 1.59E-02 1.65E-02.1.53E-02 2.83E-02 100YR 1.32E-02 1.62E-02 1.42E-01 2.41E-02 1,32E-02 1.32E-02 1.35E-02 1.38E-02 1.32E-02 2.42E-02 120YR 1.13E-02 1.39E-02 1.22E-01 2.07E-02 1.13E-02 1.13E-02 1.15E-02 1.17E-02 1.13E-02 2.08E-02
- 160)R 8.35E-03 1.03E-02 9.01E-02 1.53E-02 8.34E-03 8.34E-03 8.41E-03 8.49E-03 8.34E-03 1.53E-02 200YR 6.16E-03 7.60E-03 6.65E-02 1.13E-02 6.16E-03 6.16E-03 6.19E-03 6.22E-93 6.15E-03 1.13E-02
. 400YR 1.36E-03 1.68E-03 1.47E-02 2.50E-03 1.36E-03 1.36E-03 1.36E-03 1.36F-03 1.J6E-03 2.50E-03
. 600YR 3.03E-04 3.74E-04 3.27E-03 5.$4E-04 3.03E-04 3.03E-04 3.03E-04 3.03E-04 3.03E-04 5.54E-04 i 800YR 6.71E-05 8.29E-05 7.24E-04 1.23E-04 6.71E-05 6.71E-05 6.71E-05 6.71E-05 6.71E-05 1.23E-04
. 1K YR 1.49E-05 1.84E-05 1.61E-04 2.73E-05 1.49E-05 1.49E-05 1.49E-05 1.49E-05 1.49E-05 2.73E-05 2K YR 7.99E-09 9.86E-09 8.62E-08 1.46E-08 7.99E-09 7.99E-09 7.99E-09 7.99E-09 7.99E-09 1.46E-08
+ SK YR .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 10K YR .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00
. 20K YR .00E+00 .00E+00 .00E+00 .00E+GO .00E+00 .00E+00 .00E+00 .00E+00 .00E+00 .00E+00
_ ___ __ _____ ___ ,-- ,~- _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _
S APPENDIX F EXAMPLE TAPE 10.0VT - ICRP DOSES BY NUCLIDE e
4 4
9 e e
O
. . _ , . _ . . ._ _ _ _ __ _ _ _ , . _ .__..__..______m..
__.__m__.____.___._ _ . _ _ _ _ _ _ . , . _ _ . _ _ ,- - . ~ . . . . . - .. _ - - - ~ ~ . , - - - - - -_
4 1
IMPACTS-P8ic VERSION 1.0 HAZARDOUS WASTE II 2
SEC-RES!NS 1
4 TRANSP0dTATION ICRP IMPACTS BY NUCLIDE (MREM /YR)
NUC MAX INDIVIDUAL j -
H-3 .000E+00 C-14 .000E+00 CR-51 1.210E-01 5.921E-02 MM-54
. CO-58 9.662E-02
-CO-60 3.073E-01 NI-59 . 00s .E+00
' N1-63 000E+00
. ZN-65 1 ',76E-02 i SR-90 7.953E-10 f .
ZR-95 1.221E-01 NS-94 3.673E-06 4
m TC-99 2.4 eE-13 s RU-103 1.277E-01
. H AG-110 4.802E-01 l I-129 8.396E-07 4
CS-134 1.477E+00
, CS-135 000E+0U ,
CS-137 1.591E+00
, CE-141 2.421E-02
- E CE-144 1.953E-02 PU-238 3.909E-07
< , PU-239 .000E+00 PU-241 1.085E-07
- PU-242 5.128E-10 AM-241 3.214E-04 AM-243 2.666E-04 CM-242 3.810E-06 CM-243 1.076E-06
- CM-244 1.292E-07 i TOTAL TRANSPORTATION IMPACTS = '4.681E+00 e
. V e
. METAL PACKAGE RECYCLE ICRP IMPACTS BY NUCLIDE (MREM /YK)
NUC DOSIND H-3 7.185E-09 C-14 4.251E-12 CR-51 4.174E-04 MN-54 1.523E-06 FE-55 4.454E-11
, FE-59 5.049E-06 Co-58 2.070r-06 CO-60 9.693E-06
.- ZR-95 4.419E-06 NB-94 1.176E-10 TC-99 4.052E-14 RU-103 2.336L-06 AC-110 1.533E-05 l *29 3.047E-11 CS-134 4.304E-05 CS'135 2.520E-11 CSti37 5.317E-05 CE-141 2.134E-07 CE-144 6.640E-07
,, PU-238 2.502E-06 e PU-239 1.191E-06 b3 PU-241 5.620E-10 PU-242 2.465E-09 AM-241 2.255E-06 AM-243 1.556E-06 CM-242 6.139E-06 CM-243 5.686E-09 CM-244 1.608E-06 TOTAL RECYCLE IMPACT = 5.706E-04 4
0 A. . _ _ _ _ _ _
_ _ _ . . . . _ - . _ . . _ _ _ _ . . _ . _ . _ . . . _ . . . _ _ . . _ _ . . _ . . _ _ _ _ _ . . _ _ . . _ . _ . _ _ _ _ ._______m. ._ _. . m . _ . . -_ - -.- - - s-- -.
f l
l INTRUDER ICRP IMPACTS BY NUCLIDE IMr;EM/YR)
! **** IMPACTS ARE NOT NORMALIZED BY NUMBER OF DISPOSAL FACILITIES ****
NUC CONSTRUCTION ACRICULTURE H-3 1.287E-10 2.859E-04 C-14 '2.226E-12 1.304E-04 CR-51 .000E+00 .000E+00 '
MN-54 5.953E-14 1.156E-13 FE-55 1.321E-62 6.868E-12 :
t FE-59 .000E+00 .000E+00 CO-58 .000E+00 .000E+00 CO-60 4.458E-04 8.659E-04 NI-59 1.110E-12 3.264E-11 +
Ml-63 6.780E-10 2.191E-08 .!
ZN-65 4.547E-17 8.906E-17 !
' .SR-90 2.807E-07 9.649E-07 ZR-95 .000E+00 .000E+00 NS-94 2.793E-07 5.425E-07 TC-99 1.254E-11 1.111E-07 RU-103 .000E+00 .360E+00 s AG-110 4.347E-15 8.443E-15
. 1-129 6.468E-C8 6.714E-07
- i. CS-134 4.436E-06 8.616E-06 ,
CS-135 1. I'* E-11 3.660E-10 1 i CS-137 6. 0', ~ :-02 1.176E-01 !
i ,, CE-141 .000E*00 .000E+00 e CE-144 3.665E-15 7.119E-15 ba 70-238 8.490E-05 1.127E-04 PU-239 6.171E-05 8.191E-05 PU-241 7.880E-05 1.270E-04 PU-242 1.310E-07 1.739E-07
, AM-241 1.604E-04 2.641E-04 AM-243 3.003E-05 5.497E-05 . t CM-242 9.689E-07 1. 286 E.-06 .
. CM-243 6.712E-08 1.186E-07 CM-244 1.354E-05 1.968E-05
.000E+00 RADON l'l TOTAL NON-NORMALIZED INTRUDER IMPACTS 6.143E-02 1.196E-01 i
i i c l
4 3
4 T
1 m
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S E
I T
I R
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. . P E N R 43 63 61111 82 79154 2217311211. :. M 7 D T .I l Y N
_ L B C
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95000000990408800407200522422774 T1 U
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- - ++++++- + + - ++ +- ++- - - - - - - - -
S0 A-Y ZI A- EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE 75000000510506400103900785266169 WE 2 B L N 95000000240802200001200145558427 D9 A O 87000000600509100506700606773513 E6 S M I S
T R S 14 42 1 48 2 36 682141712 O1 C O O P A N R X .
P E .
E M T 88082008290701109790507444745685 4 I
O N R 00011000102001101001001000000000 I
- - + - ++ - - - - +- +- - - - +- - - - - - - - - -
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_ P A EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE ZE R E - 980800065764015059668O8787064395 9 C RA R E210680098901013034401O5803409871 ll2 350340016639029040644.O.6302157534 A0 I
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M E S U 16 27 35324 69 23144 1111221142 R7 T T R O S C T N A A N -
W PM I N
D O
I N
E 30 45714891213234 S 145980935054901933344334444444 L O
- 4555556566999911211111222222222 A P
- C 31 - - - - - - - - - - - - - - 1 - - - - - - - - - - - - - - T X
- U - RNEEOo1iNRRBCUC SSSEEUUUUMMMMM O E
- N HCCMFFCCNNZSZNTRA1CCCCCPPPPAACCC T n *
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OVERFLOW ICRP IMPACTS BY NUCLIDE (MREM /YR)
-FE-59 8.468E-06 .000E+00 .000E+00 CO-58 2.288E-06 .000E+00 .000E+00 Co-60 4.820E-05 9.189E-07 1.651E-06 NI-59 6.517E-10 6.516E-10 7.837E-10 NI-63 5.078E-07 4.051E-07 4.739E-07 ZN-65 1.401E-05 5.330E-19 2.467E-19 SR-90 5.817E-06 2.773E-06 3.597E-05 ZR-95 1.031E-06 .000E+00 .000E+00 NB-94 2.443E-08 2.441E-08 6.407E-09 TC-99 8.326E-08 8.325E-08 2.118E-07 RU-103 1.282E-04 .000E+00 .000E+00 AG-110 2.051E-07 2.440E-20 2.914E-20 1-129 2.710E-05 2.710E-05 6.517E-04 CS-134 3.317E-05 1.309E-09 4.316E-10 CS-135 2.059E-09 2.059E-09 6.468E-10 CS-137 3.341E-04 1.671E-04 5.388E-05 CE-141 8.660E-08 .000E+00 .000E+00
.n CE-144 1.020E-06 2.511E-18 6.101E-18 Ln PU-238 3.036E-06 2.386E-06 5.584E-04 PU-239 1.899E-06 1.898E-06 4.380E-04 PU-241 9.338E-07 1.933E-07 .3.901E-05 PU-242 h.011E-09 4.010E-09 9.198E-07 AM-241 1.819E-03 1.738E-03 9.437E-03 o AM-243 1.281E-04 1.278E-04 6.841E-04 CM-242 4. 704 E-07 2.226E-27 3.979E-26 i CM-243 3.690E-08 1.924E-08 1.556E-07 l CM-244 2.817E-05 8.638E-06 7.327E-05 l
l TOTAL NON-NORMALIZED OVERFLOW IMPACTS '
3.139E-03 2.263E-03 3.709E-02 a
E C00 000 000 000 000 000 000 000 000 000 000
> OOO COO COO 000 000 000 000 000 000 000 000
+++ +++ +++ +++ +++ +++ +++ +++ + ++ +++ +++
M WWW WWW WWW WWW WWW WWW WWW WWW WWW WWW WWW O 000 000 000 000 000 000 000 N C. O O. C. O O. C. O. O. C. O. O.
E C00 000 000 000 000 000 000 000 000 000 000
> OOO COO C00 000 000 000 000 000 000 000 000
+++ +++ +++ +++ +++ +++ +++ +++ + ++ +++ WWW +++
M WWW WWW WWW WWW WWW WWW WWW WWW WWW WWW O
e C. 0 0 000 000 000 000 000 000 000 000 000 000 M 000 000 000 000 000 000 000 000 000 000 000
> OOO 000 000 000 000 000 000 000 000 000 000
+++ +++ +++ +++ +++ +++ +++ +++ ++ + +++ +++
M WWW WWW WWW WWW WWW WWW WWW WWW WWW WWW WWW D 000 000 000 000 000 000 000 000 000 000 000 C 000 000 000 000 000 000 OOC 000 mmo Nm3 000
> OOO C00 000 000 000 000 000 000 00- 000
+++ +++ +++ +++ +++ +++ +++ +++ eee ee ee "e +++
M WWW WWW WWW WWW WWW WWW WWW WWW WWW WWW WWW N 000 000 000 000 000 000 000 000
@. c. m. O. m. 2 000 eme JCM
& 000 004 000 000 000 000 000 000 Ome MON 000
> OOM 000 000 000 000 000 000 000 Cow Oew OOO
++ e ++ e +++ +++ +++ +++ +++ +++ eae e es +++
M WWW WWW WWW WWW WWW WWW WWW WWW WWW WWW WWW e C00 000 000 000 000 000 O. C. A. 0 0. @. N. ". o. e. m. .e C. O O.
@ N eNe NmW
% COO C3C 000 000 000 000 000 000 mmo Omo COO
> C00 000 000 000 000 000 000 000 000 000 000 O +++ + e+ +++ +++ +++ +++ +++ +++ 8 e+ t e+ +++
O WWW WWW WWW WWW WWW WWW WWW WWW WWW WWW WWW C C00 000 000 000 000 000 O C. O. O. O C. A. J. C. O. C. O. C. O. O.
e en mN E COO 000 000 000 000 000 000 Nmc COO Nmo COO
> OOO COO COO COO 000 000 000 mmo Oro COO C00 O +++ + e+ +++ +++ +++ +++ +++ e s+ e a+ e e+ +++
0 WWW WWW WWW WWW WWW WWW WWW WWW WWW WWW WWW
@ 000 000 000 000 000 000 000 O. . O. N. m. c. e. m. o. C. O O
@ e@ w@ ec
- C 000 300 000 000 000 000 000 @OO MOO NOC C00
- > 000 000 000 000 000 000 000 NOC 000 000 000
- O +++
WWW WWW e++ +++ +++ +++ +++ +++
WWW WWW WWW WWW WWW e++ e++ e++ +++
O WWW WWW WWW WWW 4 000 000 000 000 000 000 000 000 000 M N O. C. N. O. C.
W @ e @ N
& & 000 200 000 000 *m OOO COO DOO @OO NOO OOO
> C00 000 000 000 CO C00 eOO COO COO 000 J O +++ e++ +++ +++ a+ +++ +++ s++ e++ e++ +++
- O WWW WWW WWW WWW WWW WWW WWW WWW WWW WWW WWW WO N 000 000 E4 A. O. C 000 000 000 000 000 n. O. O. M O. O
. N. O. C.
-6 m C N m @
J & 000 200 000 000 300 000 000 MOO SCO NOO 000 I4 > COO COO C00 000 NOO COO C eOO COO C00 000 OM O +++ e++ +++ +++ e++ +++ ++0 0, e++ e++ e++ +++
40 4 WWW WWW WWW WWW WWW WWW WWW WWW WWW WWW WWW WA e M C O. O. A. O. C 000 000 000 000 000 000 M. O. O.
300 000 w- m m c m n 40 M 000 200 000 000 000 000 aCO eOO moo 500 000 a6 > OCO COO 000 000 NOO 000 000 eOO COO COO 000 EO O +++ e++ +++ +++ e++ +++ +++ t ++ e++ e++ +++
> N WWW WWW WWW WWW WWW WWW WWW WWW WWW WWW WWW NE e 000 000 ZW C O. O C O O. C O. O. C. O. O. M. O. O. @. Q. O. N. O. C. N. O. C. C. O. O.
WD e D 2 e b XZ E3 E C00 300 000 000 NGO COO COO COO SCO NOC 000 wZ > OOO COO COO COO -00 000 000 woo OOO COO C00 O +++ 3 + + +++ +++ e++ +++ +++ e++ 3 ++ e++ +++
W> O WWW WWW WWW WWW WWW WWW WWW WWW WWW WWW WWW Om e COO COO JC e C C. O. C. O. O. N. C. O 000 000 @. O O. N. O. O. @. O. O C. 0 0 e @ e @
OW DN M DOO 200 000 000 DOO OOO COO @OO MOO NOO OOO Z- J > OOO COO C00 000 -00 000 000 000 000 000 300 J J O e++ e++ +++ +++ e++ +++ +++ e++ e++ e++ e++
>< W O WWW WWW WWW WWW WWW WWW WWW WWW WWW WWW WWW CZ J3% 300 000 000 000 000 000 000 000 x J W . C. O. O. N. O. C. N. O. C.
MO WZW N e m m e N #
WZ 30<
O -3 % AOC 300 000 000 MOO C00 000 NOC @OO NOC eOO 4H MH > OOO 000 000 000 e00 000 000 000 000 000 MOO AO W4U O e++ a++ +++ +++ e++ +++ +++ a++ e++ e++ e++
ZZ OJO @ WWW WWW WWW WWW WWW WWW WWW WWW WWW WWW WWW 334 000 000 000 000 400 000 000 000 W gA6 M. O. O. N. Q. Q. A. C. O.
AC -OZ N e N e e e m E4 ZA3 O - M C C00 000 000 000 000 000 000 000 000 000 000
-M M > COO 000 000 000 000 000 000 000 000 000 000 H
EO -
M-M O 3
+++
WWW +++ +++ +++ +++ +++ +++ +++ +++ +++ +++WWW WWW WWW WWW WWW WWW WWW WWW WWW WWW W4 HA 303 3- 000 000 000 000 000 000 000 000 000 000 000
<E Oxo 3- C E O O E C00 000 000 000 000 000 000 000 000 000 000 Z HZO > OOO OOOeOOO40COAOOOmOCOCOOOOOOOOOOOMC000000 34 MOE O +++#+++a+++A+++n+++c+++c+++4+++a+++c+++c+++
O* EO- N MWWWeWWWeWWWeWWWsWWW eWWWeWWWsWWWeWWW eWWWeWWW
%* -WI Z000 O* 6Mr =I C. O. O. Oe O OO O.Z O O.O. 2. Z O.O.O.W 6 O.
6 O.O.WO O.O O.OOO. O O.O Z O. O.O. Z -0 0 0. - 0 0 0. N F-6
I SR-90
.0E+00 .0E+00 4.7E-06 2.9E-06 1.7E-06 1.1E-06 7.9E-07 3.0E-07 4.2E-09 5.3E-11 4.9E-13 3.9E-15 7.3E-26 .0E+00 .0E+00 .0E+00
.OE+00 0E+00 .0E+00 0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 3.1E-12 4.5E-14 4.8E-16 1.5E-26 .0E+00 .0E+00 .0E+00
.0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 3.8E-18 7.1E-28 .0E+00 .0E+00 .0E+00 ZR-95
.OE+00 0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00
.0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00
.0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 NB-94
.0E+00 .0E+00 1.1E-08 1.1E-08 1.1E-08 1.1E-08 2.2E-08 2.2E-08 4.5E-08 7.7E-08 9.9E-08 1.1E-07 1.1E-07 .0E+00 .0E+00 .0E+00
.OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 4.6E-09 9.1E-09 1.3E-08 2.2E-08 .0E+00 .0E+00 .0E+00
.0E+00 0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 6.6E-10 6.3E-09 .0E+00 .0E+00 .0E+00 TC-99 l
.0E+00 .0E+00 2.5E-07 2.5E-07 2.5E-07 2.5E-07 5.0E-07 5.0E-07 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00
.0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 1.0E-07 2.1E-07 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00
.OE+00 0E+00 .OE+00 .0E+00 .0E+0a .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 2.3E-09 .0E+00 .0E+00 .0E+00 .0E+00 RU-103
.0E+00 .OE+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .OE+00
.0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00
.OE+00 0E+00 .0E+00 .OE+00 .0E+0( .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 AG-110
.0E+00 0E+00 1.1E-31 2.5E-40 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00
.0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00
.0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 1-129
.0E+00 0E+00 8.1E-05 8.1E-05 8.1E-05 8.1E-05 1.6E-04 1.6E-04 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00
.0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 3.3E-05 6.7E-05 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00
.0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 7.5E-07 .0E+00 .0E+00 .0E+00 .0E+00 CS-134
.0E+00 .0E+00 2.9E-13 3.4E-16 3.9E-19 4.5E-22 1.2E-27 1.6E-33 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 n .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 e .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00
%J .0E+00 0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 CS-135
.0E+00 .0E+00 2.0E-09 2.0E-09 2.0E-09 2.0E-09 3.9E-09 3.9E-09 7.9E-09 1.4E-08 1.8E-08 2.0E-08 2.0E-08 2.0E-08 2.0E-08 2.0E-08
.0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 8.1E-10 1.6E-09 2.4E-09 4.1E-09 4.1E-09 4.0E-09 4.0E-09
.0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 5.9E-11 5.9E-10 5.9E-10 5.9E-10 5.8E-10 CS-137
.0E+00 .0E+00 9.8E-05 6.2E-05 3.9E-05 2.5E-05 2.0E-05 7.8E-06 1.5E-07 2.6E-09 3.3E-11 3.7E-13 3.4E-23 .0E+00 .0E+00 .0E+00
.0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 1.6E-10 3.1E-12 4.5E-14 7.0E-24 .0E+00 .0E+00 .0E+00
.0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 1.1E-15 9.9E-25 .0E+00 .0E+00 .0E+00 CE-141
.0E+00 0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00
.0E+00 .0E+00 .OE+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00
.0E+00 0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 CE-144
.0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00
.0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .OE+00
.0E+00 0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 PU-238
.OE+00 .0E+00 .0E+00 .0E+00 .OE+00 .OE+00 .0E+00 .0E+00 .0E+00 7.6E-08 1.5E-08 3.1E-09 2.0E-12 1.8E-22 1.4E-39 .0E+00
.OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 7.4E-24 1.7E-40 .OE+00 0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 1.3E-42 .0E+00
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INCINERATION ICRP IMPACTS BY NUCLIDE (MREM /YR)
IMPACTS NOT NORMALIZED BY NUMBER OF PROCESSING FACILITIES ****
NUC MAXIMUM OFF-SITE INDIVIDUAL H-3 1.780E-05 C-14 1.345E-05 CR-51 5.833E-07 MN-54 2.457E-07 FE-55 3.087E-08 FE-59 1.353E-06 CO-58 4.913E-07 CO-60 2.298E-06 NI-59 7.796E-12 NI-63 6.353E-09 ZN-65 8.308E-07 SR-90 1.413E-06 ZR-95 3.706E-07 NB-94 8.522E-11 TC-99 2.724E-10 RU-103 6.777E-06 AG-110 2.806E-06 1-129 8.359E-07 CS-134 5.717E-05 CS-135 6.039E-10 CS-137 1.211E-04 "E CE-141 5.799E-07 ha CE-144 9.231E-06 c) PU-238 2.418E-04 PU-239 1.383E-04 PU-241 9.364E-05 PU-242 2.933E-01 AM-241 3.594E-04 AM-243 2.464E-05 CM-242 4.195E-05 CM-243 1.149E-07 CM-244 1.069E-04 TOTAL NON-NORMALIZED INCINERATOR IMPACT = 1.245E-03
I WORKER INCINERATION ICRP IMPACTS BY NUCLIDE (MREM /YR)
- IMPACTS ARE NOT NORMALIZED BY NUMBER OF PROCESSING FACILITIES NUC RESIDUE HANDLERS MAINTENANCE P-3 4.798E-09 2.639E-09 l C-14 1.534E-11 8.436E-12 CR-51 4.077E-02 4.077E-02 Mh-54 1.995E-02 1.995E-02 ,
FE-55 2.736E-08 1.505E-08 l FE-57 8.052E-02 8.052E-02 1 CO-53 3.255E-02 3.254E-02 i CO-63 1.035E-01 1.035E-01 !
l NI-59 7.763E-12' 4.270E-12 NI-63 5.833E-09 3.208E-09 ZN-65 5.290E-03 5.290E-03 SR-93 4.043E-06 2.224E-06 ZR-95 4.114E-02 4.114E-02 N8-94 1.238E-06 1.237E-06 TC-99 8.602E-11 4.735E-11 RU-103 4.301E-02 4.301E-02 AG-110 1.618E-01 1.618E-01 1-129 2.887E-07 2.861E-07 CS-134 4.974E-01 4.974E-01 CS-135 7.930E-11 4.362E-11 CS-137 5.359E-01 5.359E-01 lp CE-141 8.155E-03 8.155E-03 pa CE-144 6.597E-03 6.588E-03 Fd PU-238 7.412E-04 4.077E-04 PU-239 4.240E-04 2.332E-04 PU-241 2.868E-04 1.578E-04 PU-242 8.991E-07 -4.946E-07 AM-241 1.092E-03 6.495E-04 AM-243 1.571E-04 1.268E-04 CM-242 1.250E-04 6.931E-05 CM-243 6.833E-07 5.389E-07 CM-244 3.001E-04 1.651E-04 TOTAL NON-NORMALIZED WORKER IMPACTS 1.580E+00 1.578E+00 6
METAL AND CLASS RECYCLE ICRP IMPACTS BY NUCLIDE
- IMPACTS ARE NOT NORMALIZED BY NUMBER Of FACILITIES ****
NUC METAL IND CLASS IND H-3 4.042E-06 .000E+00 C-14 2.391E-09 .000E+00 CR-51 2.348E-01 8.589E-02 MN-54 8.567E-04 4.201E-02 FE-55 2.505E-08 .000E+00 FE-59 2.840E-03 1.696E-01 Co-58 1.164E-03 6.855E-02 Co-60 5.453E-03 2.180E-01 NI-59 6.286E-11 .000E+00 NI-63 4.803E-08 .000E+00 ZN-65 2.107E-04 1.114E-02 SR-90 8.683E-06 5.643E-10 ZR-95 2.486E-03 8.667E-02 NB-94 6.614E-08 2.606E-06 TC-99 2.735E-11 1.737E-13 RU-103 1.314E-03 9.060E-02 AC-110 8.625E-03 3.407E-01 1-129 1.714E-08 5.957E-07 CS-134 2.421E-02 1.048E+00 CS-135 1.418E-08 .000E+00 i CS-137 2.991E-02 1.129E+00 J
'fwa CE-141 CE-144 1.200E-04 3.735E-04 1.718E-02 1.385E-02 i
PG PU-238 1.407E-03 2.774E-07 PU-239 6.697E-04 .000E+00 PU-241 3.161E-07 7.699E-08 PU-242 1.387E-06 3.638E-10 AM-241 1.268E-03 2.280E-04 AM-243 8.753E-04 1.892E-04 CM-242 3.453E-03 2.703E-06 CM-243 3.198E-06 7.633E-07 CM-244 9.043E-04 9.165E-08 s
INTRUDER ICRP IMPACTS BY NUCLIDE (MREM /YR)
IMPACTS ARE NOT NORMALIZED BY NUMBER OF OlSPOSAL FACILITIES NUC CONSTRUCTION ACRICULTURE H-3 3.180E-10 4.643E-04 C-14 2.542E-12 9.787E-05 CR-51 1.905E-02 5.323E-02 - !
MM-54 9.317E-03 2.604E-02 FE-55 1.800E-08 6.558E-08 FE-59 3.761E-02 1.051E-01 CO-58 1.520E-02 4.249E-02 CO-60 4.836E-02 1.351E-01 NI-59 5.027E-12 9.818E-11 NI-63 3.847E-09 8.253E-08 ZN-65 2.471E-03 6.965E-03 SR-90 2.666E-06 6.208E-06 ZR-95 1.922E-02 5.371E-02 NB-94 5.781E-07 1.616E-06 TC-99 5.643E-11 3.288E-07 RU-103 1.999E-02 5.590E-02 AG-110 7.556E-02 2.112E-01 1-129 1.350E-07 2.042E-06 CS-134- 2.324E-01 6.495E-01 CS-!35 5.230E-11 1.168E-09 CS-137 2.504E-01 6.999E-01 "E CE-141 3.810E-03 1.065E-02 bd CE-144 3.085E-03 8.604E-03 68 PU-238 4.888E-04 4.581E-04 PU-239 2.796E-04 2.620E-04 PU-241 1.892E-04 1.774E-04 PU-242 5.929E-07 5.558E-07 AM-241 6.996E-04 8.692E-04 AM-243 8.636E-05 1.672E-04 CM-242 8.217E-05 8.124E-05 CM-243 3.809E-07 6.914E-07 CM-244 1.979E-04 2.032E-04 RADON- .000E+00 TOTAL NON-NORMALIZED INTRUDER IMPACTS 7.384E-01 2.061E+00
EXPOSED WASTE ICRP IMPACTS BY NUCLIDE (MREM /YR)
- IMPACTS ARE NOT NORMALIZED BY NUMBER OF DISPOSAL FACILITIES ****
NUC INTRUDER-AIR EROSION-AIR INTRUDER-WATER EROSION-WATER H-3 9.207E-08 6.497E-32 7.267E-10 2.775E-32 C-14 2.087E-07 4.072E-07 2.906E-09 3.067E-01 CP-51 5.403E-06 .000E+00 5.206E-08 .000E+00 MN-54 2.276E-06 .000E+00 1.384E-07 .000E+00 FE-55 2.860E-07 .000E+00 2.910E-09 .000E+00 FE-59 1.253E-05 .000E+00 1.307E-07 .000E+00 CO-SP 4.551E-06 .000E+00 3.443E-08 .000E+00 CO-60 2.129E-05 .000E+00 9.947E-08 .000E+00 NI-55 7.222E-11 1.576E-10 5.039E-13 5.952E-11 NI-63 5.885E-08 6.955E-11 4.222E-10 2.700E-11 ZN-65 7.696E-06 .000E+00 1.396E-07 .000E+00 SR-9C 1.309E-05 5.403E-16 8.467E-09 1.891E-17 ZR-95 3.433E-06 .000E+00 2.348E-08 .000E+00 NB-94 7.894E-10 1.679E-09 2.524E-11 2.90SE-09 TC-99 1.255E-09 2.755E-09 8.283E-12 9.837E-10 RU-1E3 3.123E-05 .000E+00 2.540E-07 .000E+00 AC-110 2.600E-05 .000E+00 1.827E-07 .000E+00 1-129 3.852E-06 8.481E-06 2.689E-09 3.204E-07 CS-134 5.295F-04 .000E+00 1.348E-05 .000E+00 CS-135 5.594E-09 1.232E-08 1.495E-10 1.781E-08 CS-137 1.122E-03 2.293E-13 2.919E-05 3.230E-13
]'
pa CE-141 CE-144 5.371E-06 8.551E-05
.000E+00
.000E+00 4.251E-08 2.954E-07
.000E+00
.000E+00 Sb PU-238 2.240E-03 2.255E-06 8.035E-08 4.337E-09 PU-239 1.282E-03 2.743E-03 4.660E-08 5.397E-06 j PU-241 8.674E-04 9.049E-04 3.608E-08 7.568E-05 '
PU-242 2.717E-06 5.972E-06 9.944E-11 1.183E-08 AM-241 3.330E-03 1.621E-03 5.147E-06 1.356L-04 -
AM-243 2.282E-04 4.723E-04 3.578E-07 3.910E-05 l
CF-242 3.886E-04 2.570E-08 1.825E-07 4.941E-11 l CM-243 1.065E-06 3.838E-09 1.105E-09 7.552E-12 l CM-244 9.906E-04 8.108E-06 9.801E-07 1.600E-08 I 1
TOTAL NON-NORMALIZED EXPOSED WASTE IMPACTS 1.120E-02 5.766E-03 5.092E-05 2.564E-04
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2R-95 7.8E-38 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00
.OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00
.0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 NB-94 5.9E-08 1.2E-07 1.8E-07 2.0E-07 2.0E-07 2.OE-07 2.0E-07 2.OE-07 1.9E-07 1.9E-07 1.9E-07 1.9E-07 1.8E-07 .0E+00 .0E+00 .OE+00
.0E+00 .OE+00 .0E+00 .0E+00 1.8E-09 5.4E-09 1.6E-08 1.8E-08 1.80-08 1.8E-08 1.7E-08 1.7E-08 1.7E-08 .0E+00 .OE+00 0E+00
.OE+00 .0E+00 .0E+00 .OE+00 .OE+00 .0E+00 .0E+00 5.2E-10 5.2E-09 5.1E-09 5.1E-09 5.1E-09 4.9E-09 .0E+00 .0E+00 .0E+00 TC-99 1.3E-06 2.6E-06 3.9E-06 4.4E-06 4.4E-06 4.4E-06 4.4E-06 4.4E-06 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 0E+00 .0E+00 .OE+00 .0E+00 4.0E-08 1.2E-07 3.6E-07 4.0E-07 .0E+00 .OE+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 ,
.0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 1.8E-09 1.8E-08 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 I RU-103
.OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 0E+00 .0E+00 .0E+00 .0E+00 .0Ef 00 .0E+00 .0E+00 .0E+00 .0E+00
.0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 . OWOO .0E+00 .0E+00 .0E+00 .0E+00
.OE+00 .0E+00 .0E+00 .OE+00 .0E+00 0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 AG-110 9.4E-14 4.5E-22 1.7E-30 4.4E-39 .0E+00 0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00
.0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0EeOO .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00
.0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+90 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 1-129 4.2E-04 8.4E-04 1.3E-03 1.4E-03 1.4E-03 1.4E-03 1.4E- ?3 1.4E-03 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00
.0E+00 .0E+00 .0E+00 .0E+00 1.3E-05 3.8E-05 1.1E-04 1.3E-04 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00
.0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 5.8E-07 5.8E-06 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 CS-134 1.1E-06 2.6E-09 4.5E-12 5.9E-15 6.8E-18 7.9E-21 1.1E-26 1.4E-32 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00
.0E+00 .0E+00 .0E+00 .0E+00 6.2E-20 2.1E-22 8.7E-28 1.3E-33 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00
.0E+00 .OE+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 1.8E-35 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 CS-135 1 OE-08 2.1E-08 3.1E-08 3.4E-08 3.4E-08 3.4E-08 3.4E-08 3.4E-08 3.4E-08 3.4E-08 3.4E-08 3.4E-08 3.4E-08 3.4E-08 3.4E-08 3.4E-08 "f .0E+00 .0E+00 .0E+00 .0E+00 3.1E-10 9.4E-10 2.8E-09 3.1E-09 3.1E-09 3.1E-09 3.1E-09 3.1E-09 3.1E-09 3.1E-09 3.1E-09 3.1E-09
>a .0E+00 0E+00 .0E+00 .0E+00 .0E+00 .0E+00 0E+00 4.5E-11 4.5E-10 4.5E-10 4.5E-10 4.5E-10 4.5E-10 4.5E-10 4.5E-10 4.5E-1Q
'J CS-137 1.3E-03 1.6E-03 1.5E-03 1.1E-03 6.8E-04 4.3E-04 1.7E-04 6.8E-05 6.7E-07 6.6E-09 6.5E-11 6.4E-13 5.9E-23 .0E+00 .0E+00 .0E+00
.0E+00 .OE+00 .0E+00 .0E+00 6.2E-06 1.2E-05 1.4E-05 6.2E-06 6.1E-08 6.0E-10 5.9E-12 5.8E-14 5.4E-24 .0E+00 .OE+00 .0E+00
.OE+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 8.7E-08 8.6E-09 8.4E-11 8.3E-13 8.2E-15 7.6E-25 .0E+00 .OE+00 .0E+00 CE-141
.OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00
.0E+00 .0E+00 0E+00 .0E+00 0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00
.0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 CE-144
.0E+00 .0E+00 3.1E-28 5.7E-36 .0E+00 .0E+00 .0E+00 .0E+00 .0F+00 .0E+00 .0E+00 0E+00 .0E+00 .0E+00 .0E+00 .0E+00
.0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00
.OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 PU-238
.0E+00 .0E+00 1.0E-05 8.5E-06 7.3E-06 1.2E-05 9.0E-06 9.8E-06 3.9E-06 1.2E-06 2.7E-07 5.3E-08 1.8E-11 6.2E-22 2.4E-39 .0E+00
.0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 4.9E-10 1.6E-12 5.7E-23 2.2E-40 .0E+00
.OE+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 7.6E-15 2.7E-24 1.0E-41 .0E+00 PU-239
.0E+00 .OE+00 9.4E-06 9.4E-06 9.4E-06 1.9E-05 1.9E-05 2.8E-05 5.6E-05 8.3E-05 9.2E-05 9.1E-05 8.9E-05 8.2E-05 7.1E-05 5.3E-05
.0E+00 .0E+00 .0E+00 0E+00 .OE+00 .0E+00 .0E+00 0E+00 .0E+00 .OE+00 .0E+00 8.3E-07 8.1E-06 7.4E-06 6.5E-06 4.9E-06
.0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 3.8E-08 3.5E-07 3.1E-07 2.3E-07 PU-241
.0E+a0 .0F+00 3.1E-07 1.1E-07 3.8E-08 2.7E-08 3.3E-09 6.0E-10 3.3E-14 1.4E-18 4.2E-23 1.2E-27 .0E+00 .OE+00 .0E+00 .0E+00
.0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+40 .0E+00 .0E+00 .0E+00 1.1E-29 .0E+00 .0E+00 .0E+00 .0E+00
.0E+00 .OE+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 PU-242
.0E+00 .0E+00 2.0E-08 2.0E-08 2.0E-08 4.0E-08 4.0E-08 6.0E-08 1.2E-07 1.8E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 2.0E-07 1.9E-07
.OE+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 1.8E-09 1.8E-08 1.8E-08 1.8E-08 1.8E-08
.0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 8.6E-11 8.6E-10 8.5E-10 8.4E-10
AM-241 *
.0E+00 .OE+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 2.4E-03 1.8E-03 1.3E-03 8.8E-04 2.2E-05 .0E+00 .0E+00 0E+00 .0E+00 .0E+00 .0E+00 .00+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 1.5E-10 .0E+00
.0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 3.OE-18 AM-243
.0E+00 .0E+00 .OE+00 .0E+00 .OE+00 .0E+00 .0E+00 .CE+00 .0E+00 4.0E-04 3.9E-04 3.8E-04 1.1E-03 1.9E-03 .0E+00 .0E+00
.OE+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .qE+00 1.6E-05 .0E+00
.0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .OE+00 .OE+00 .0E+00 .0E+00 4.8E-07 I l
CM-242 '
.0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00
.0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00
.0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 CM-243
.0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 2.SE-26 .OE+00 .0E+00 .0E+00
.OE+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+oo .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00
.OE+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 0E+00 .0E+00 .0E+00 .OE+00 .0E+0C CM-244
.0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 0E+00 .0E+00 9.8E-39 .0E+00 .OE+00 .0E+00
.0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .OE+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00
.0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .OE+00 TOTAL NON-NORMALIZED CROUNDWATER IMPACTS
'E 2.5E-03 3.1E-03 3.6E-03 3.4E-03 2.9E-03 2.7E-03 2.4E-03 2. 3E-03 6.2E-05 2.9E-03 2.3 E-03 1.8E-03 2.0E-03 2.0E-03 7.1 E-05 5.4E-05
>4 .0E+00 .0E+00 .0E+00 .OE+00 2.7E-05 7.2E-05 1.9E-04 2.1E-04 6.9E-05 4.8E-08 2.9E-08 S.6E-07 8.1E-06 7.5E-06 2.2E-05 4.9E-06 c3 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 1.2E-06 1.1E-05 7.1E-09 6.OE-09 5.7E-09 4.4E-08 3.5E-07 3.1E-07 7.1E-07
CON-DIRT TRANSPORTATION IChP IMPACTS BY NUCLIDE (MREN/YR)
NUC MAX INDIVIDUAL PB-210 2.305E-05 PO-210 2.439E-07 RN-222 2.128E-02 RA-226 7.072E-05 RA-228 1.590E-02 AC-227 1,841E-04 TH-228 3.181E-02 TH-230 2.395E-06 TH-232 .OOOE+00 PA-231 2.120E-05 U-234 ~ 094E-06 U-235 7.716E-05 U-238 1.466E-04 TOTAL TRANSPORTATION IMPACTS = 6.952E-02 INTRUDER ICRP IMPACTS BY NUCLIDE (MREM /YR)
, **** IMPACTS ARE NOT NORMALIZED BY NUMBER OF DISPOSAL FACILITIES ****
[a NUC CONSTRUCTION ACRICULTURE u)
PB-210 8.082E-06 2.818E-05 PO-210 1.138E-05 3. 462 E- 05 RM-222 4.359E-03 1.218E-02 RA-226 2.558E-05 8.894E-05 RA-228 3.261E-03 9.141E-03 AC-227 6.878E-05 1.428E-04 TH-228 6.799E-03 1.848E-02 TH-230 3.354E-04 3.235E-04 TH-232 5.670E-04 5.467E-04 PA-231 4.372E-05 6.634E-05 U-234 1.437E-04 1.349E-04 U-235 2.176E-05 4.974E-05 U-238 1.575E-04 2.033E-04 RADON 1.242E-01 TOTAL NON-NORMAllZED INTRUDER IMPACTS 1.580E-02 1.656E-01
EXPOSED WASTE ICOP IMPACTS BY CUCLIDE (MREM /YR)
- IMPACTS ARE NOT NORMALIZED CY CUMBE;t OF DISPOSAL FACILITIES ***5 NUC INTRUDER-AIR ERO$l0N-AIR INTRUDER-WATER EROSION-WATER PB-210 5.531E-05 8.443E-19 4.146E-07 1.375E-18 PO-210 1.653E-04 .000E+00 6.200E-06 .000E+00 RN-222 1.818E-06 4.352E-22 1.423E-08 7.085E-22 RA-226 1.244E-04 4.994E-04 7.323E-07 5.755E-04 RA-228 8.632E-05 .000E+00 6.818E-07 .000E+00 AC-227 1.740E-04 4.389E-18 3.047E-07 4.160E-19 TH-228 1.324E-03 .000E+00 1.983E-07 .000E+00 TH-230 1.561E-03 3.670E-03 3.264E-07 3.387E-04 TH-232 2.647E-03 8.933E-03 5.920E-07 1.754E-04 PA-231 2.464E-04 9.063E-04 5.717E-07 1.022E-04 U-234 6.565E-04 1. 4 72 E-03 1.174E-08 3.085E-06 U-235 2.726E-05 7.929E-05 5.540E-10 2.243E-06 U-238 5.840E-04 1.290E-03 1.698E-08 2.028E-06 TOTAL NON-NORMALIZED EXPOSED WASTE IMPACTS 7.653E-03 1.685E-02 1.006E-05 1.199E-03 DVERFLOW ICRP IMPACTS BY NUCLIDE (MREM /YR)
IMPACTS ARE NOT NORMALIZED BY NUMBER OF DISPOSAL FACILITIES NUC TREATMENT OVERFLOW EVAPORATOR PS-210 4.696E-04 4.696E-04 3.644E-04 PO-210 5.666E-04 5.666E-04 8.787E-05 17 RN-222 2.657E-04 2.457E-04 1.975E-04 os RA-226 C3 1.119E-03 1.119E-03 1.106E-03 RA-228 4.664E-04 4.664E-04 3.435E-04 AC-227 3.506E-04 3.506E-04 1.164E-03 TH-228 4.994E-05 4.994E-05 1.940E-03 TH-230 5.019E-04 5.019E-04 1.396E-02 TH-232 9.084E-04 9.084E-04 2.362E-02 PA-231 8.781E-04 8.781E-04 2.201E-03 U-234 5.496E-07 5.496E-07 1.788E-04 u-235 2.586E-08 2.586E-08 7.401E-06 U-238 7.922E-07 7.922E-07 1.586E-04 TOTAL NON-NORMALIZED OVERFLOW IMPACTS 5.578E-03 5.578E-03 4.533E-02 GROUNDWATER
- ICRP IMPACTS BY NUCLIDE (MREM /YR) AT EACH TIME IMPACTS ARE NOT NORMAllZED BY NUMBER OF DISPOSAL FACILITIES ****
FIRST ROW IS INTRUDER WELL SECOND ROW IS POPULATION WELL THIRD ROW IS SURFACE WATER 20YR 40YR 60YR 80YR 100YR 120YR 160YR 200YR 400YR 600YR 800YR 1 K YR 2K YR SK YR 10K YR 20K YR PB-210
.OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00
.0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00
.OE+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00
.OE+00 .OE+00 .0E+00 .OE+00 .0E+00 .OE+00
.0Et00 .OE+00
.0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .OE+00 .OE+00
O O COO COO 000 000 000 00@ 00@ 000 WOO COO @c @Ce o
+Qv +++ +++ +++ +++ +++ ++ e ++ e +++
C00 000 Coo ooo Coo ooO ooo ooo ooo ooO OO WWW WWW WWW WWW WWW WWW WWW WWW WWW WWW WWW WWW e++ e++ e+
00o e+e WWW C. 0 0 000 000 000 000 000 QQw . . . o. o. e. C. 0 e0 000 400 000 m. o. c.
N # m N 4 @
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C0 000 000 000 000 000 000 000 OOC 000 000 000 000
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wh 3 Q w w @ w wwh 000 000 m3C COC 000 000 MOO MOO 200 WOO @OO NOC NdC ooO . coo coo 000 000 000 000 000 000 000 000 000 000
+++ +++ ee+ +++ +++ +++ e++ e++ e++ e++ e+4 e++ s e+
WWW WWW WWW WWW WWW WWW WWW WWW W6W WWW WWW WWW WWW l 000 WQQ 500 r C. O. O. 4. M. O. o. c. o. C. o. o. Q. Q. o. c. o. Q. N. o. o. @. C. C. . . . e. c. o. M. M. o.
l ee M @ m @ M m em COO C00 mco coo NOO C00 MOO MOO C00 000 000 000 MOO p+++o o +++ 000 Ooo coo moo coo coo ooo Oc0 ooo oco coo e++ +++ e++ +++ e++ 6++ +++ +++ +++ +++
coo e++
WWW WWW WWW WWW WWW WWW WWW WWW 6WW WWW WWW WWW WWW QQW 000 200 000 000 000 000 600
. . . C. 0 0 w o. o. o.00 m. o. c. c. o. o.
COO COO mCo COO COO C00 400 40e coo 000 000 000 MOO h
WWW WWW WWW WWW WWW hk hk hhk WWWh WmW kh WWW hkWWW hkh hkh hhh kkh WWW WWW WWW WWW k
C. 0 0 000 m o. o. c. o. o. C. 0 0 000 N C. O. W o.o. c. o. o. c. o. o. c. o. o. c. o. o. a c. o.
000 000 moC 200 000 000 300 300 000 000 000 000 MOO OgQ C00 000 MOO C00 000 000 000 cop 000 opo COO 000 bwb bbb bb bbb bbb bbb bw bb bbW bbb bWb bbb bbb 999 999 ". M
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- 99 999 999 ".99 e
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WWW WWW WmW e +
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$88++ +++ 888 888 e++ $ sk+8 888 +++ 888 +++ 888+++ 888 +++8E++k +8+k 8 888 888
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WWW WWW WWW WWw WWW WWW WmW wWW WWW mmW WWW WWW www
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000 goo 000 ggo000 eCO COO C00 000 000 000 000 000 000 000 Waa WWa CCC ata000 att aaa 000ata 000 ata000 000 Waa att aaa 000 awwogggCO pCO ggy C00 000 000 000 000 e 000 000e C00 000 e000 Wat mmw 000 e e e e o. o. o. CeOe O. e e e e e m
C00 000 000 Cop 000 00g 000 000 000 000 000 000 000 000 000 0000 aaa aaw aamCop aaWgCO WaoCOO att000ata000aaa aamcogaWo ogo bow Cog aaw Cog taWw(Opp "99 9 9 999 999 o99 999 999 999 o99 999 9 9 999 -o99 =
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mmWe8.8. mm. e88. Wmm mmm 8.99Wmm ff8. mWW 8.88.mWm 999 ~fel mmW U. W. O. C. 0 0 000 000 000, 000 000 000 000 000 000 000 000 997 999 fil 797 999 mm.
.W mmm mmW mmm mmm 999 Wmm 798mm.999mmm 988 mmW 999 Wmm fffmWW VffmmWe Offf W u.u. C. 0 0 000 000
. 000 000 000 000 000 O. W. O. C. 0 0 000 N o. C. o.
?ff 999 WmW WWW
- m. ff8 mm. fff Wmm 999 mmm 899 mmW 999 mmWV89 mWe WWm ???mWm 999mW fff 897 mmm fff M
. . . C. 0 0 Q00 000 000 000 000 000 000 000 000 000 Z
0000 gM Ef.ffEfffE9ffEfffEfffEfffEfffEfff5fffafffsiff=899 emmmeWmWemmmemmWeW WemmmeWeme.mWNmWmNWWmNmWm -mm vfff 000.z000.s000.n000 000.Z000.2000.Z000.4000.6C.o.o.Ql C. 0. C. Qe O. 0 0 -00 .0 0 F-21
a CMSITE INC, S. LANDF WASTE OIL TRANSPORTATION ICRP IMPACTS BV NUCLIDE (MREM /YR)
MUC MAX 1MD4VIDUAL CR-51 2.672E+02 MM-54 2.537E+01 FE-55 .000E+00 FE-59 1.767E+02 CO-58 8.844E+01 Co-60 4.851E+00 Ni-63 .OOCE+00 ZN-65 2.808E+01 RB-86 4.124E+01 SR-89 1.323E-03 SR-90 1.094E-07 ZR-95 2.518E+02 l MB-95 2.300E+02 RU-103 1.689E+02 Ru-106 5.255E+00 AG-110 3.197E+01 CS-134 9.061E+OO CS-137 2.203E+00 CE-141 5.641E+01 CE-144 1.408E+00 7
m TOTAL TRANSPORTATION IMPACTS = 1.389E+03 N
METAL PACKAGE RECYCLE ICRP IMPACTS BY NUCLIDE (MREM /YR)
MUC DOSIND CR-51 9.416E-01 MM-54 6.668E-04 FE-55 9.279E-07 FE-59 3.813E-03 CO-58 1.936E-03 CO-60 1.563E-04 NI-63 3.901E-06 ZM-65 6.844E-04 RB-86 8.734E-04 SR-89 1.743E-05 SR-90 2.169E-06 ZR-95 9.308E-03 NB-95 5.457E-05 RU-103 3.158E-03 RU-106 1.760E-04 AG-110 1.043E-03 CS-134 2.699E-04 CS-137 7.524E-05 CE-141 5.081E-04 CE-144 4.894E-05 TOTAL RECYCLE IMPACT = 9.644E-01
I INCINERATION ICOP IZPACTS BY NUCLIDE (MREM /Y3)
- IMPACTS NOT NORMAllZED BY NUMBER OF PROCESSING FACILITIES NUC MAXIMUM OFF-SITE INDIVIDUAL CR-51 3.556E+00 MN-54 2.90SE-01
'E-55 1.739E+00 EE-59 2.763E+00 CO-58 1.242E+00 CO-60 1.OO2E-01 MI-63 7.846E-On ZN-65 4.104E+00 RB-86 1.215E+01 SR-89 1.980E+00 dR-90 5.368E-01 ZR-95 2.110E+00 NS-95 6.943E+00 RU-103 4.953E+01 Ru-106 3.699E+01 AC-110 5.160E-01 CS-134 9.688E-01 CS-137 4.632E-01 CE-141 3.732E+00 CE-144 1.839E+00 TOTAL NON-NORMALIZED INCINERATOR IMPACT = 1.323E+02 l' WORKER INCINERATION ICRP !MPACTS BY NUCLIDE (MREM /YR) m ****
Ld IMPACTS ARE NOT NORMALIZED BY NUMBER OF PROCESSING FACILITIES NUC RESIDUE HANDLERS MAINTENANCE CR-51 3.977E+03 3.977E+03 MN-54 3.777E+02 3.777E+02 FE-55 2.467E-02 1.246E-02 FE-59 2.630E+03 2.630E+03 CO-58 1.316E+03 1.316E+03 CO-60 7.220E+01 7.220E+01 Ni-63 1.154E-02 5.827E-03 ZN-65 4.180E+02 4.180E+02 RS-86 6.138E+02 6.138E+02 SR-89 5.155E-02 3.578E-02 SR-90 2.459E-02 1.242E-U2 ZR-95 3.748E+03 3.748E+03 N8-95 3.424E+03 3.424E+03 RU-103 2.514E+03 2.514E+03 RU-106 7.829E+01 7.825E+01 AC-110 4.758E+02 4.758E+02 CS-134 1.349E+02 1.349E+02 CS-137 3.280E+01 3.280E+01 CE-141 8.397E+02 8.396E+02 CE-144 2.102E+01 2.099E+01 TOTAL NCM-NORMALIZED WORKER IMPACTS 2.067E+04 2.067E+04
ICTCUCER ICOP IMPACTS BY NUCLIDE (MREM /Y2)
IMPACTS ARE NOT NORMALIZED BY NUMBER OF DISPOSAL FACILITIES "*
NUC CONSTRUCTION AGRICULTURE CR-51 7.109E-18 1.986E-17 MM-54 5.978E-01 1.670E+00 FE-55 1.235E-02 8.113E-03 FE-59 2.404E-10 6.717E-10 .
CO-58 2.650 E-06 7.406E-06 Co-60 3.844E+00 1.074E+01 NI-63 2.119E-02 4.235E-02 ZN-65 2.496E-01 7.037E-01 RB-86 1.857E-28 5.194E-28 SR-89 2.253E-12 7.424E-12 SR-90 4.145E-02 1.221E-02 ZR-95 1.523E-06 4.257E-06 M8-95 7.038E-14 1.967E-13 i RU-103 2.944E-12 8.232E-12
[ RU-106 2.633E-01 7.356E-01 AC-110 3.436E-01 9.600E-01 CS-134 2.562E+00 7.162E+00 CS-137 3.009E+00 8.412E+00 CE-141 1.050E-15 2.933E-15 CE-144 2.644E-02 7.043E-02 RADON .000E+00 TOTAL N04-pe0RMALIZED INTRUDER IMPACTS 1.097E+01 3.051E+01 7
$ EXPOSED WASTE ICRP IMPACTS BY NUCLIDE (MREM /YR) l IMPACTS ARE NOT NORMALIZED SY NUMBER OF DISPOSAL FACILITIES ****
1 NUC INTRUDER-AIR EROSION-AIR INTRUDER-WATER EROS!OII-WATER CR-51 4.724E-21 .000E+00 1.943E-23 .000E+00 Mel-54 3.421E-04 .000E+00 8.876E-06 .000E+00 FE-55 3.501E-02 .000E+00 1.520E-04 .000E+00 FE-59 1. 877E-1L3 .000E+00 8.351E-16 .000E+00 CO-58 1.859E-09 .000E+00 6.001E-12 .000E+00 -
Co-60 3.963E-03 .000E+00 7.901E-06 .000E+00 NI-63 5.782E-C2 3.128E-03 1.770E-04 1.176E-05 ZN-65 1.821E-03 .000E+00 ,1.410E-05 .000E+00 -
RS-86 2.732E-30 .OSOE+00 2.864E-32 .000E+00 SR-89 5.440E-12 .C00E+00 1.442E-14 .000E+00 SR-90 3.630E-02 7.473 E-11 1.002E-05 2.533E-14 ZR-95 6.376E-10 000E+00 1.861E-12 .000E+00 se8-95 1.061E-16 .000E+00 2.266E-18 .000E+00 RU-103 1.078E-14 .000E+00 3.739E-17 .000E+00 RU-106 2.275E-02 .000E+00 6.858E-05 .000E+00 AG-110 2.769E-04 000E+00 8.303E-07 000E+00 CS-134 1.368E-02 .000E+00 1.486E-04 .000E+00 CS-137 3.158E-02 3.194E-10 3.507E-04 4.355E-12 CE-141 3.467E-18 000E+00 1.171E-20 .000E+00 CE-144 1.635E-03 .000E+00 2.411E-06 .000E+00 TOTAL Isost-IIONNALIZED EXPOSED WASTE.lMPACTS 2.052E-01 3.128E-03 9.411E-04 1.176E-05 utx- _2 sax
DVECFLOW IC2P IMPACTS BY NUC:.lDE (MREM /Y;I) '
- IMPACTS ARE NOT NORMALIZED BY NUMBER OF DISPOSAL FACILITIES ****
MUC TREATMENT OVERFLOW EVAPORATOR CR-51 2.632E-02 4.571E-22 7.%2E-22 MM-54 2.399E-02 3.68SE-04 1.018E-04 FE-55 6.780E-01 1.784E-01 2.943E-01 FE-59 2.609E-01 2.316E-13 3.729 t.-13 CO-58 3.729E-02 1.707E-09 3.788E-09 CD-60 3.172E-02 1.639E-02 5.890E-02 NI-63 9.465E-01 9.115E-01 2.133E+00 ZM-65 1.044E+00 6.057E-03 5.606E-03 RB-86 2.949E-02 8.661E-32 6.067E-32 SR-89 7.453E-02 2.676E-12 7.232E-12 SR-90 3.335E-02 2.948E-02 7.649E-01 2R-95 8.860E-02 3.498E-10 8.586E-10 M8-95 2.354E+00 4.699E-16 1.576E-16 PU-103 7.017E+00 8.041E-14 3.320E-13 Ru-106 9.158E+00 2.966E-01 1.409E+00 AG-110 5.691E-04 3.991E-06 9.535E-06 CS-134 8.483E-03 1.565E-03 1.032E-03 CS-137 1.929E-02 1.719E-02 1.108E-02 CE-141 8.411E-03 1.021E-19 2.166E-19 CE-144 3.067E-03 3.564E-05 1.731E-04 TOTAL NON-NORMALIZED OVERFLOW IMPACTS 2.189E+01 1.458E+00 4.678E+00 7
ha CROUM0 WATER ICRP IMPACTS SY MUCLIDE (MREM /YR) AT EACH TIME W **** IMPACTS ARE le0T NORMALIZED BY NUMBER OF OISPOSAL FACILITIES ****
FIRST ROW IS INTRUOER WELL SEcomo POW IS POPULATION WELL THIRD ROW IS SURFACE WATER 20YR 40YR 60YR 80YR 100YR 120YR 160YR 200YR 400YR 600YR 800YR 1K YR 2K YR SK YR 10K YR 20K YR CR-51
.0E+00 .0E+00 .0E+00 .0E+00 0E+00 .bE+00 .0E+00 0E+00 .0E+00 .0E+00 0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00
.0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00
.0E+00 .0E+00 .0E+00 .CE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 MM-54 2.3E-09 2.6E-16 2.2E-23 1.6E-30 1.1E-37 .0E+00 .0E+00 .0E+00 .0E+00 0E+00 0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00
.0E+00 .0E+00 .0E+00 .0E+00 0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00
.0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 FE-55 1.1E-01 5.5E-04 2.6E-06 1.3E-08 6.0E-11 2.9E-13 6.6E-18 1.5E-22 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00
.OE+00 4.5E-05 2.4E-07 1.1E-09 5.5E-12 2.6E-14 6.0E-19 1.4E-23 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00
.0E+00 .0E+00 1.1E-08 8.4E-11 4.1E-13 1.9E-15 4.5E-20 1.0E-24 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .OE+00 FE-59
.0E+00 .OE+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00
.0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00
.0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .0E+00 CO-58 3.0E-30 .0E+00 .0E+00 .OE+00 .0E+00 .0E+00 .0E+00 .OE+00 .OE+00 0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00 .0E+00
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APPENDIX G INSTALLATION PROCEDURES
Backup Copy It is advisable to duplicate the supplied diskette and to keep the orginal as a backup copy. This can be accomplished on a dual drive personal computer (PC) by using the following procedure:
- 1. Start the PC with the DOS diskette in drive A.
- 2. Insert a blank diskette that will become the duplicate diskette into drive B.
- 3. At the A> prompt type:
FORMAT B: ,
This will format the duplicate diskette.
When the diskette in drive B is formatted, a message will appear on the screen saying FORMAT COMPLETE, and # bytes (on diskette and available).
- 4. Remove the DOS diskette from drive A and insert the original diskette, with write protect tab in place, into drive A.
- 5. Leave the newly formatted diskette in drive B.
- 6. At the A> prompt type:
COPY *.* B:
This will copy all the files from the original diskette to the duplicate diskette. The names of the files will appear on the screen as each file is copied. When the A> prompt appears on the screen, the copying is complete.
- 7. Be sure the red light is out on both drives, then remove the original diskette from drive A and put it away for safe keeping.
G-1
Working Diskette To execute IMPACTS-BRC, it is necessary to create a bootable working diskette containing DOS, the executable program file, and the input data files. The FORTRAN files are omitted from the working diskette to leave storage space for the generated output files. The working disk is created by continuing from step 7:
- 8. Remove the new duplicate diskette from drive B. '
- 9. Insert the DOS diskette into drive A.
- 10. Insert a blank diskette that will become the working disk into drive B.
- 11. At the A> prompt type:
FORMAT B:/S This will format the working diskette and install DOS so that the disk will be bootable.
- 12. Remove the 005 diskette from drive A and insert the duplicate diskette. Leave the newly formatted working diskette in drive B.
- 13. At the A> prompt type:
COPY IMPACTSB.EXE B:
This will copy the executable program file to the working diskette.
When the A> prompt appears on the screen again, type:
COPY *.DAT B:
This will copy the 3 data files TAPE 1.DAT, TAPE 2.DAT, and -
EXAMPLES.DAT, to the working diskette. The names of each file will appear on the screen as it is copied. When the A> prcmpt reappears on the screen, copying is complete.
By removing the duplicato disk from drive A and moving the working disk from drive B to A, the example probelems for IMPACTS-BRC can now be executed according to the directions given in section 5.3.
L G-2
1 LtPORf NUMSE A idssefamF er ff0C. 88W F8' **. tari IIRC pores 335 U S. NUCLt.R REGULt TORY COthAsiSS808e (2 Set
%*,",'s,'- B18UOGRAPHIC DATA SHEET NUREG/CR-3585,Vol. 2
$EE INSTRUCTIONS ON TME REVtR$$
, ,1a .No su.v.ru ,/
DE MINIMIS WASTE IMPACTS ANALYSIS METHODOLOGY VOLUME 2 /
IMPACTS-h . of R.,0,,, CO ,ur o r
WASTES BE(c USER'S GUIDE AND METHODOLOGY FOR
.ON, ...R W REGULATORY CONCERN g
- J y 1986
. ,.U1,.OR ,,,
Jona an M. Forstrom and Daniel J. Goode f 4 o...R.,OR,,,,u.O Nr ...R j
/ July 1986 E .ND W.tLING . DOR t 55 f rac8em /q Ceep 8 PROpT/T.$K,VWORK WNsf NUMOER 7 PL*F ORMING ORG.Ni2.f ION N Division of Waste i nagement f Office of Nuclear F erial Safety and Safeguards . Oa cR .~rNu sea U.S. Nuclear Regulato Commission Washington, DC 20555 J
.t(,NG . R g SS ifar8wW lg Coef 11e TYPE OF REPORT 10 $PONSOR NG ORG.sgel.f gON N.W4 .NQ Same as above. User's Guide as PER,00 COv tRED flarferse.9 *pfge) 13 SUPPLtWENT.flV NOTES This is an NRC staff report published a Volume 2 a contractor report.
,2 w.1R.cirm-.,,
, This report describes the mh do gy and computer program used by NRC to evaluate radiological impacts associated wit itions to have specific slightly contaminated radioactive waste streams designa as "below regulatory concern." These wastes could be treated and disposed of at fa ies which are not licensed for low-level radioactive waste management. >
' -PC microcomputers using the FORTRAN The IMPACTS-BRC computer program is impleme ed on progranning language, Radiological impact ' (doses) a estimated for several pathways including direct gamma radiation exposure worker inha tion and exposure, offsite atmospheric and water releases, and intr r exposures. nnual impacts are calculated for the maximum individual, critical groups, nd general pop tion. The treatment and disposal options include onsite incinergion, incineration. t municipal and hazardous waste facilities, and disposal at sanitary landfills and ha rdous waste landfills.
Modifications to the program (from Vo1@e 1) are primarily microcomputer compatibility and to provide information needed to aluate the petitions.
Default environmental and facility pafameters are developed re esenting conservative assumptions about site selection and pperational procedures. Invarticular, the parameter ;
of the groundwater pathway model arejmodified to represent more dLnservative assumptions thantheoriginalmodel(Volume 1),g r,
- i. ooco..N r .N.t .. . . . . ..ORoi oiicR 10R. ....,.
} _
BelowRegulatoryConcern(BRC) t Unlimited i)e Minimis Waste .
s Low-level Radioactive Waste ,,,,C,,,,,,,,,,,,,,,,,,
Impact Analysis Code '
UncTa,ssifted
. ,oi N,,, . R.,0, N .No. o e R..
(f As, reportJ Unclassified
,,hv.. RO,,.o..
16 9 Rett
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.f UNITED STATES P-'
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