Inventory Data Package for the Integrated Disposal ... Library/3rd_Posting/Other...Inventory Data Package for the Integrated Disposal Facility Performance Assessment Author Name:

A-6002-767 (REV 3)

RPP-ENV-58562, Rev. 3

Inventory Data Package for the Integrated Disposal Facility Performance Assessment

Author Name:

K. A. Prindiville

Washington River Protection Solutions, LLC.

Richland, WA 99352 U.S. Department of Energy Contract DE-AC27-08RV14800

EDT/ECN: DRCF UC:

Cost Center: Charge Code:

B&R Code: Total Pages: 118

Key Words: Performance Assessment, Integrated Disposal Facility, IDF, MLLW, LLW, HLW, Hanford Tank Waste

Operations Simulator, HTWOS, Performance Assessment, LAW melter, ILAW glass, Effluent Treatment

Facility, ETF, Secondary Solid Waste, SSW, FFTF

Abstract: This document provides estimates of the waste inventories and associated waste volumes for each of the

waste streams that are planned to be disposed of at the Integrated Disposal Facility (IDF) for purpose of

evaluating the long-term impact on human health and the environment in the 2017 IDF Performance

Assessment (PA).

TRADEMARK DISCLAIMER. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof or its contractors or subcontractors.

Release Approval Date Release Stamp

Approved For Public Release

RPP-ENV-58562 Rev.03 5/9/2016 - 11:21 AM 4 of 118

By Janis D. Aardal at 11:37 am, May 09, 2016

May 09, 2016DATE:

RPP-ENV-58562 Rev.03 9/26/2016 - 12:49 PM 4 of 124

RPP-ENV-58562 Rev.03 5/9/2016 - 11:21 AM 5 of 118RPP-ENV-58562 Rev.03 9/26/2016 - 12:49 PM 5 of 124

Tank Farm Contractor (TFC) RECORD OF REVISION

(1) Document Number: Page ___2

RPP-ENV-58562 Rev. 3

A-6003-835 (REV 5)

Change Control Record (3)

Revision (4) Description of Change – Replace, Add, and Delete Pages Authorized for Release

(5) Author. (print/sign/date) (6) Resp. Mgr. (print/sign/date)

recommendations apply to “as-generated” waste volumes to determine “as-disposed” of waste volumes.

Section 10.0 (now Section 9.0)

• Updated inventory to reflect rerun of HTWOS and addition/distribution of HTWOS “Total Accumulation” inventory to both IDF and non-IDF waste stream mass balance.

• Updated inventory tables to include detailed inventory of WTP SSW streams to include HEPA filters, ion exchange resin, HLW and LAW carbon adsorber beds, HLW silver mordenite absorbent, and other debris.

Added Appendix A-detailed inventory tables for each run case

Added Appendix B- to document calculation checks and numeric table checks


RPP-ENV-58562

Revision 3

Inventory Data Package for the Integrated Disposal Facility Performance Assessment

K. A. Prindiville

Washington River Protection Solutions, LLC

Date Published

May 2016

Prepared for the U.S. Department of Energy

Office of River Protection

Contract No. DE-AC27-08RV14800



This page intentionally left blank.



i

TABLE OF CONTENTS

1.0 INTRODUCTION ........................................................................................................... 1-1

2.0 INTEGRATED DISPOSAL FACILITY WASTE STREAMS SOURCES AND

TERMINOLOGY ............................................................................................................ 2-1

3.0 INTEGRATED DISPOSAL FACILITY WASTE STREAM DESCRIPTIONS ............ 3-1

3.1 WASTE TREATMENT AND IMMOBILIZATION PLANT-

GENERATED WASTE ....................................................................................... 3-1

3.1.1 Immobilized Low-Activity Waste Glass ................................................. 3-1

3.1.2 Low-Activity Waste Melters.................................................................... 3-1

3.1.3 Secondary Solid Waste ............................................................................ 3-2

3.1.4 Effluent Treatment Facility-Generated Secondary Solid Waste .............. 3-2

3.2 NON-WASTE TREATMENT AND IMMOBILIZATION PLANT

GENERATED WASTE ....................................................................................... 3-3

3.2.1 Fast Flux Test Facility Decommissioning Waste .................................... 3-3

3.2.2 Secondary Waste Management Low-Level Waste and Mixed

Low-Level Waste ..................................................................................... 3-4

3.2.3 Onsite Non-CERCLA Non-Tank Low-Level Waste and Mixed

Low-Level Waste ..................................................................................... 3-4

4.0 TANK WASTE INVENTORY ....................................................................................... 4-1

4.1 BEST-BASIS INVENTORY BACKGROUND .................................................. 4-1

4.2 BEST-BASIS INVENTORY UNCERTAINTY ................................................. 4-2

4.2.1 Total Best-Basis Inventory Uncertainty ................................................... 4-2

4.2.2 Tank and Waste Phase Uncertainties ....................................................... 4-2

4.3 BEST-BASIS INVENTORY COMPARISON.................................................... 4-3

4.4 TANK INVENTORY HISTORY OF TECHNETIUM-99 AND

IODINE-129 ...................................................................................................... 4-11

4.4.1 Technetium-99 Tank Waste Inventory History ..................................... 4-11

4.4.2 Iodine-129 Tank Waste Inventory History ............................................ 4-14

5.0 HANFORD TANK WASTE OPERATIONS SIMULATOR ......................................... 5-1

5.1 HANFORD TANK WASTE OPERATIONS SIMULATOR

BACKGROUND ................................................................................................. 5-1


UNCERTAINTY AND LIMITATIONS ............................................................. 5-1


COMPARISON ................................................................................................... 5-4



ii

6.0 WASTE TREATMENT AND IMMOBILIZATION PLANT GENERATED

WASTE INVENTORY ESTIMATES—RESULTS ....................................................... 6-1

6.1 THE ENVIRONMENTAL IMPACT STATEMENT AND HANFORD

TANK WASTE OPERATIONS SIMULATOR CASES INVENTORY

ESTIMATES........................................................................................................ 6-1

6.2 WASTE TREATMENT AND IMMOBILIZATION PLANT

SECONDARY SOLID WASTE STREAM PARTITION FRACTIONS ........... 6-7

7.0 NON-WASTE TREATMENT AND IMMOBILIZATION PLANT-GENERATED

WASTE INVENTORY ESTIMATES ............................................................................ 7-1

7.1 FAST FLUX TEST FACILITY DECOMMISSIONING WASTE

INVENTORY ESTIMATE ................................................................................. 7-1

7.2 SECONDARY WASTE MANAGEMENT LOW-LEVEL WASTE

AND MIXED LOW-LEVEL WASTE INVENTORY ESTIMATE ................... 7-1

7.3 ONSITE NON-CERCLA NON-TANK LOW-LEVEL WASTE AND

MIXED LOW-LEVEL WASTE .......................................................................... 7-3

8.0 INTEGRATED DISPOSAL FACILITY WASTE VOLUME METHODOLOGY ........ 8-1

8.1 IMMOBILIZED LOW-ACTIVITY WASTE GLASS WASTE

VOLUME ESTIMATES ..................................................................................... 8-1

8.2 AS-GENERATED WASTE TREATMENT AND IMMOBILIZATION

PLANT SECONDARY SOLID WASTE VOLUME ESTIMATES................... 8-3

8.3 BACKGROUND-INDUSTRY STANDARDS FOR WASTE

TREATMENT ..................................................................................................... 8-5

8.3.1 Low-Level Waste ..................................................................................... 8-5

8.3.2 Mixed Low-Level Waste ......................................................................... 8-5

8.4 WASTE TREATMENT AND IMMOBILIZATION PLANT

SECONDARY SOLID WASTE TREATMENT AND DISPOSAL

CONSIDERATIONS AND ASSUMPTIONS .................................................... 8-6

8.5 LOW-ACTIVITY WASTE MELTER VOLUME ESTIMATES ....................... 8-8

8.6 EFFLUENT TREATMENT FACILITY-GENERATED SECONDARY

SOLID WASTE ................................................................................................... 8-9

8.7 SECONDARY WASTE MANAGEMENT LOW-LEVEL WASTE

AND MIXED LOW-LEVEL WASTE VOLUME ESTIMATES ..................... 8-11

8.8 FAST FLUX TEST FACILITY DECOMMISSIONING WASTE

DISPOSAL VOLUME ESTIMATE.................................................................. 8-11

8.9 AS-GENERATED ONSITE NON-CERCLA NON-TANK LOW-

LEVEL WASTE AND MIXED LOW-LEVEL WASTE VOLUME

ESTIMATES...................................................................................................... 8-12



iii

9.0 SUMMARY OF RESULTS ............................................................................................ 9-1

9.1 INTEGRATED DISPOSAL FACILITY WASTE FORMS BASED ON

HANFORD TANK WASTE OPERATIONS SIMULATOR RUN

CASES ................................................................................................................. 9-1

9.1.1 Iodine-129 Variations (Figure 9-1 and Figure 9-2) ................................. 9-8

9.1.2 Technetium-99 Variations (Figure 9-3 and Figure 9-4) ........................ 9-11

10.0 DATA QUALITY ASSURANCE FOR THE INTEGRATED DISPOSAL

FACILITY INVENTORY DATA PACKAGE ............................................................. 10-1

11.0 REFERENCES .............................................................................................................. 11-1

LIST OF FIGURES

Figure 2-1. Schematic Showing Generation and Disposal Pathway for Mixed Low-Level

Waste and Low-Level Waste Going to the Integrated Disposal Facility. ................ 2-2

Figure 2-2. Waste Treatment and Immobilization Plant-Generated Waste Streams Going to

Integrated Disposal Facility. .................................................................................... 2-4

Figure 4-1. Published Technetium Inventories in Hanford Tank Waste (Section 4.4.1).......... 4-12

Figure 4-2. Published Iodine-129 Inventories in Hanford Tank Waste (Section 4.4.2). .......... 4-12

Figure 5-1. Hanford Tank Waste Operations Simulator Flow Sheet. ......................................... 5-2

Figure 5-2. Technetium-99 Comparison using Tank Closure and Waste Management

Environmental Impact Statement Partitioning Fractions. ........................................ 5-7

Figure 5-3. Iodine-129 Comparison. ........................................................................................... 5-8

Figure 6-1. Tank Closure Alternative 2B Flowsheet from the Tank Closure and Waste

Management Environmental Impact Statement. ...................................................... 6-2

Figure 6-2. Case 7 – Current Information Case Flowsheet. ....................................................... 6-3

Figure 6-3. Case 8B – Technetium-99 Removal from Low-Activity Waste Vitrification

Off-Gas Condensate Flowsheet. ............................................................................... 6-4

Figure 6-4. Case 9 – Removal of Low-Activity Waste Pretreatment System Flowsheet. .......... 6-5

Figure 6-5. Case 10A and 10B – Low and Medium Efficiency Recycle. .................................. 6-6

Figure 9-1. Iodine-129 Distributions in Integrated Disposal Facility Waste Forms................... 9-9

Figure 9-2. Iodine-129 Inventory in Integrated Disposal Facility Waste Forms. ..................... 9-10

Figure 9-3. Technetium-99 Distributions in Integrated Disposal Facility Waste Forms. ......... 9-12

Figure 9-4. Technetium-99 Inventory in Integrated Disposal Facility Waste Forms. .............. 9-13



iv

LIST OF TABLES

Table 2-1. Integrated Disposal Facility Waste Stream Terminology. ........................................ 2-1

Table 4-1. Best-Basis Inventory Comparison. ............................................................................ 4-5

Table 4-2. Hanford Tank Waste Historical Inventories for Technetium-99 and Iodine-129. .... 4-6

Table 5-1. Comparison of Hanford Tank Waste Operations Simulator Partitioning Fractions

from the Tank Closure and Waste Management Environmental Impact

Statement versus Current Hanford Tank Waste Operations Simulator

Partitioning Fractions. ............................................................................................... 5-5

Table 6-1. 10-010 Partitioning Fractions for Waste Treatment and Immobilization Plant

Secondary Solid Waste Streams. ............................................................................... 6-8

Table 6-2. Hanford Tank Waste Operations Simulator Partitioning Fractions for Waste

Treatment and Immobilization Plant Secondary Solid Waste Streams. .................... 6-8

Table 6-3. Run Case 7 Contaminant Inventory for Waste Treatment and Immobilization

Plant Secondary Solid Waste Streams using 10-010 Partitioning Fractions. .......... 6-10

Table 6-4. Run Case 7 Contaminant Inventory for Waste Treatment and Immobilization

Plant Secondary Solid Waste Streams using Hanford Tank Waste Operations

Simulator Partitioning Fractions. ............................................................................ 6-10

Table 7-1. Fast Flux Test Facility Decommissioning Inventory Estimates for Waste Going

to Integrated Disposal Facility. ................................................................................. 7-1

Table 7-2. Secondary Waste Management Low-Level Waste and Mixed Low-Level Waste

Inventory Estimates for Waste Going to Integrated Disposal Facility. ..................... 7-2

Table 7-3. Onsite Non-CERCLA Non-Tank Low-Level Waste and Mixed Low-Level

Waste Radioactive Constituents of Potential Concern Inventory. ............................ 7-4


Waste Chemical Constituents of Potential Concern Inventory. ................................ 7-5

Table 8-1. Volume Estimates for Immobilized Low-Activity Waste Glass. .............................. 8-2

Table 8-2. Volume Estimates for Waste Treatment and Immobilization Plant Secondary

Solid Waste Streams. ................................................................................................. 8-4

Table 8-3. Volume Estimates for Low-Activity Waste Melters and Residual Glass Volume. .. 8-8

Table 8-4. Effluent Treatment Facility-Generated Secondary Solid Waste Disposal Volume

Estimates. ................................................................................................................ 8-10



v

Table 8-5. As-Generated Secondary Waste Management Waste Volume Estimates. .............. 8-11

Table 8-6. Fast Flux Test Facility Decommissioning Disposal Waste Volume Estimate. ....... 8-11


Waste As-Generated Volume Estimates. ................................................................ 8-12

Table 9-1. Summary of Radionuclide Constituents Inventories and Waste Form

Distributions Resulting from Hanford Tank Waste Operations

Simulator Run Cases (November 2014 Best-Basis Inventory

with radionuclides decayed to January 2008). .......................................................... 9-3

Table 9-2. Summary of Chemical Constituent Inventories and Waste Form Distributions

Resulting from Hanford Tank Waste Operations Simulator Runs. ........................... 9-5

Table 9-3. Tank Closure Alternative 2A Radioactive Constituents of Potential Concern

Balance. ..................................................................................................................... 9-6

Table 9-4. Tank Closure Alternative 2A Chemical Constituents of Potential Concern

Balance. ..................................................................................................................... 9-7

Table 10-1. Source Data Quality Assurance. ............................................................................ 10-1



vi

LIST OF APPENDIX A TABLES

Table A-1. Run Case 7 Radionuclides. ...................................................................................... A-3

Table A-2. Run Case 7 Chemicals. ............................................................................................ A-5

Table A-3. Run Case 8B Radionuclides. ................................................................................... A-7

Table A-4. Run Case 8B Chemicals. ......................................................................................... A-9

Table A-5. Run Case 9 Radionuclides. .................................................................................... A-11

Table A-6. Run Case 9 Chemicals. .......................................................................................... A-13

Table A-7. Run Case 10A Radionuclides. ............................................................................... A-15

Table A-8. Run Case 10A Chemicals. ..................................................................................... A-17

Table A-9. Run Case 10B Radionuclides. ............................................................................... A-19

Table A-10. Run Case 10B Chemicals. ................................................................................... A-21



vii

LIST OF TERMS

BBI Best-Basis Inventory

CERCLA Comprehensive Environmental Response, Compensation, and Liability Act

of 1980

CH Contact Handled

COPC constituent of potential concern

CS Caustic Scrubber

DFLAW Direct Feed Low Activity Waste

DOE U.S. Department of Energy

DKPRO Computer code for radioactive decay (DK) and processing (PRO)

DST double-shell tank

Ecology State of Washington Department of Ecology

EMF Effluent Management Facility

ETF Effluent Treatment Facility

FFTF Fast Flux Test Facility

HDW Hanford Defined Waste (model)

HEPA High-Efficiency Particulate Air (filter)

HLW High-Level Waste

HOG High-Level Waste Off-Gas

HTWOS Hanford Tank Waste Operations Simulator

IDF Integrated Disposal Facility

IHLW Immobilized High-Level Waste

ILAW Immobilized Low-Activity Waste

IX Ion Exchange (resin)

LAWPS Low-Activity Waste Pretreatment System

LAW Low-Activity Waste

LDR Land Disposal Restriction

LERF Liquid Effluent Retention Facility

LLW Low-Level Waste

LOG Low-Activity Waste Off-Gas

MLLW Mixed Low-Level Waste

NEPA National Environmental Policy Act of 1969



viii

ORIGEN2 Oak Ridge Isotope Generation and Depletion Code

ORP DOE Office of River Protection

PA Performance Assessment

PNNL Pacific Northwest National Laboratory

PT Pretreatment

RCB Reactor Containment Building

RCRA Resource Conservation and Recovery Act of 1976

RSD Relative Standard Deviation

RPP River Protection Project

SALDS State-Approved Land Disposal Site

SBS Submerged Bed Scrubber

SLAW Supplemental Low-Activity Waste

SLOG Supplemental Low-Activity Waste Off-Gas

SST single-shell tank

SSW Secondary Solid Waste

TC&WM EIS Tank Closure and Waste Management Environmental Impact Statement

TRAC Track Radioactive Constituents computer code

TRU transuranic

TWINS Tank Waste Information Network System

VSL Vitreous State Laboratory

WESP Wet Electrostatic Precipitator

WRAP Waste Receiving and Processing (facility)

WRPS Washington River Protection Solutions

WTP Waste Treatment and Immobilization Plant



1-1

1.0 INTRODUCTION

This document provides the current estimates of the waste inventories to be disposed in the

Integrated Disposal Facility (IDF) for purposes of evaluating the long-term impact on human

health and the environment in the 2017 IDF Performance Assessment (PA).

Release of contaminants from the waste in a disposal facility into the environment depends on a

number of factors. The most important factors are the inventory of contaminants in a particular

waste form and the waste form release behavior. A PA for a proposed disposal facility evaluates

the breakdown of the waste form, the release of contaminants into the environment, and the

eventual impact of the contaminants, such as groundwater concentrations. The PA provides

information to allow decision makers to define constraints on the disposal facility design,

operation, acceptable waste forms, acceptable waste form inventories, and other criteria to

provide reasonable assurance that the performance objectives of the disposal facility will be met.

This document does not define exactly what the inventory of contaminants will be in each waste

form to be disposed at the IDF. Instead, it proposes a range of inventories that might occur,

realizing that the Waste Treatment and Immobilization Plant (WTP) process flowsheet may

continue to develop over time given ongoing regulatory discussions and technical decisions.

Separate documents will propose a range of waste release behaviors to be evaluated for each

waste form. Evaluating a range of values for each key parameter provides insight into how the

parameters interact. For example, high inventories of key contaminants may be placed into more

robust waste forms. Less robust waste forms may still be allowed, but limits must be determined

for the inventory in these waste forms.

This document has considered inventory ranges for particular waste forms based on operating

scenarios that are not anticipated from the current flowsheets and that may lead to unacceptable

results (i.e., performance objectives may not be met). The purpose in proposing these ranges is

to understand how changes in key parameters affect the outcome over a wide range of values.

This understanding allows for the development of waste acceptance criteria informed by

modeled performance of the disposal facility.

Specifically, five run cases (7, 8B, 9, 10A, and 10B) were developed to explore the range of

inventory in waste streams going to the IDF that result from processing tank waste through the

WTP Facility using different process flowsheet assumptions. In the interest of testing the IDF

system, each case was designed to produce a range of distributions of 99Tc and 129I in glass and

non-glass waste forms. Although Cases 7 and 9 may be more likely representations of the WTP

flowsheet configuration, Cases 10A and 10B are unlikely cases that were developed to test the

limits of 99Tc and 129I loadings in non-glass waste forms against established waste form

performance objectives. For Cases 10A and 10B, process simulators were used to partition

inventory between the different waste forms using contrived process flowsheet configurations to

test the upper limits of what waste form concentrations the IDF could receive and still meet the

performance criteria of the facility. These cases are included to help establish waste acceptance

criteria for specific waste forms.



1-2

Collectively, the five cases serve as a starting point for gaining an understanding of the IDF

disposal system considering all the uncertainties associated with the IDF waste forms. Other run

cases are expected to evolve based on the knowledge gained from these initial run cases and the

maturity of the WTP process flowsheet. The five run cases presented here were repeated with

updated assumptions from the previous version of this document including corrections to the

off-gas reactions and stream splits which have been incorporated into Hanford Tank Waste

Operations Simulator (HTWOS) Version 8.1 (RPP-17152, Rev. 12, “Hanford Tank Waste

Operations Simulator (HTWOS) Version 8.1 Model Design Document”). Notable changes from

the previous version include the splits associated with Hg and 14C in the Low-Activity Waste

(LAW) off-gas system as well as the split associated with 137Cs based on a correction to the

elution factor applied to the cesium ion exchange resin.

This document also recognizes that tank waste compositions are complex and that there are

multiple sources of uncertainty associated with the estimated inventory for each waste stream

modeled. These uncertainties include tank waste composition and inventory uncertainties, WTP

process and operational uncertainties, and model partitioning uncertainties. Evaluating a range

of values helps identify the parameters which have greatest impact on the outcome, and where

improved information (e.g., additional measurements or process definition) may be needed.

The 2017 IDF PA will evaluate a range of contaminant inventories associated with a range of

waste form behaviors. The expected outcome is an understanding of the areas within those

ranges that lead to acceptable outcomes.



2-1

2.0 INTEGRATED DISPOSAL FACILITY WASTE STREAMS SOURCES AND

TERMINOLOGY

The IDF is planning to receive Mixed Low-Level Waste (MLLW) and Low-Level Waste (LLW)

generated by the WTP as a result of the vitrification process. Those waste streams include:

Immobilized Low-Activity Waste (ILAW) glass

Low-Activity Waste (LAW) melters

Secondary solid waste (SSW)

Effluent Treatment Facility (ETF)-generated SSW.

Additional waste streams would be generated that are not a result of the WTP process. These

waste streams would also be disposed of at the IDF and include:

Fast Flux Test Facility (FFTF) decommissioning waste

Secondary waste management LLW and MLLW

Onsite Non-Comprehensive Environmental Response, Compensation, and Liability Act

of 1980 (CERCLA) non-tank LLW and MLLW.

The use of common and consistent terms when referring to these IDF waste streams is a key

consideration for all project efforts associated with the analysis or discussion of waste disposal at

the IDF. Table 2-1 establishes the waste stream names consistently applied in this document.

Additionally, Figures 2-1 and 2-2 provide information related to the generation and disposal

pathways for each of these waste streams.

Table 2-1. Integrated Disposal Facility Waste Stream Terminology.

Waste Stream Names

WTP-Generated Waste Streams Non-WTP-Generated Waste Streams

Immobilized Low-Activity Waste glass Secondary Waste Management LLW and MLLW

Low-Activity Waste melters Fast Flux Test Facility decommissioning waste

Secondary solid waste Onsite Non-CERCLA non-tank LLW and

MLLW Effluent Treatment Facility-generated secondary solid waste

CERCLA = Comprehensive Environmental Response, Compensation, and Liability Act of 1980

LLW = Low-Level Waste

MLLW = Mixed Low-Level Waste

WTP = Waste Treatment and Immobilization Plant



2-2

Figure 2-1. Schematic Showing Generation and Disposal Pathway for Mixed Low-Level

Waste and Low-Level Waste Going to the Integrated Disposal Facility.


ETF = Effluent Treatment Facility LAW = Low-Activity Waste

FFTF = Fast Flux Test Facility LLW = Low-Level Waste

IDF = Integrated Disposal Facility MLLW = Mixed Low-Level Waste

ILAW = Immobilized Low-Activity Waste WTP = Waste Treatment and Immobilization Plant

Prior to disposal, these waste streams would be treated appropriately to meet Land Disposal

Restrictions (LDR)1 and waste acceptance criteria for the IDF. The resulting “as disposed”

1 Congress created the LDR program on November 8, 1984 as part of the Hazardous and Solid Waste Amendments

to the Resource Conservation and Recovery Act of 1976. This law prohibits the land disposal of untreated

hazardous wastes. It required the U.S. Environmental Protection Agency to specify either concentration levels or

methods of treatment for hazardous constituents to either substantially decrease the toxicity of a waste or decrease

the likelihood that contaminants would migrate from a waste and cause contamination of land and groundwater.

The U.S. Environmental Protection Agency responded



2-3

waste forms would be ILAW glass, cementitious (grouted), or compacted waste forms as shown

in Figure 2-1. Alternative treatment methods to grouting may be viable for some secondary

wastes. On a case-by-case basis, modeling assumptions for specific waste streams were

developed from existing practices at the Hanford Site or based on consultation with subject

matter experts.

By establishing the LDR program found in Title 40, Code of Federal Regulations, Part 268, “Land Disposal

Restrictions.” The LDR program identifies treatment standards for hazardous wastes and specifies requirements

that generators, transporters, and owners or operators of treatment, storage, and disposal facilities that manage

restricted wastes destined for land disposal must meet.


RP

P-E

NV

-58562

, Rev

. 3

2-4

Figure 2-2. Waste Treatment and Immobilization Plant-Generated Waste Streams Going to Integrated Disposal Facility.

ETF = Effluent Treatment Facility ILAW = Immobilized Low-Activity Waste LERF = Liquid Effluent Retention Facility

HLW = High-Level Waste LAW = Low-Activity Waste PT = Pretreatment

IDF = Integrated Disposal Facility LAWPS = Low-Activity Waste Pretreatment System WTP = Waste Treatment and Immobilization Plant

Tanks

Off-gas liquids

WTP

Pretreatment

Processes

(Includes WTP

PT and LAWPS) HLW

Vitrification

Process

LAW

Vitrification

Process

LERF/ETF

ETF-Generated Secondary

Solid Waste to the IDF

Secondary Solid Waste to

the IDF

ILAW Glass and LAW

Melters to the IDF

HLW Melters to onsite

storage

HLW Glass to offsite disposal



3-1

3.0 INTEGRATED DISPOSAL FACILITY WASTE STREAM DESCRIPTIONS

3.1 WASTE TREATMENT AND IMMOBILIZATION PLANT-GENERATED

WASTE

To provide an understanding of the relationship between WTP operations and the resulting

WTP-generated waste streams that will be disposed of at the IDF, a simplification of the WTP

process flowsheet is presented in Figure 2-2. Note that the vitrified High-Level Waste (HLW)

glass and HLW melters shown in this figure will not be disposed of at the IDF. Also note that

non-WTP-generated wastes that will be disposed of at the IDF are not shown in Figure 2-2 and

are discussed separately in Section 3.2. A detailed description of the WTP-generated waste

streams including their sources is provided in Sections 3.1.1 through 3.1.4.

Contaminant inventories for the different waste streams produced at the WTP and disposed of at

the IDF over the life of the waste treatment mission were developed from process modeling

using HTWOS. HWTOS was run with different starting conditions and process flow sheet

assumptions to generate a range of inventory values for the different waste streams to support the

2017 IDF PA analysis.

3.1.1 Immobilized Low-Activity Waste Glass

In accordance with 78 FR 75913, “Final Tank Closure and Waste Management Environmental

Impact Statement for the Hanford Site Record of Decision,” the U.S. Department of Energy

(DOE) has implemented Tank Closure Alternative 2B, without supplemental treatment and WTP

without 99Tc removal in the WTP Pretreatment Facility2. The primary waste form for all tank

waste processed at WTP would be an ILAW or Immobilized High-Level Waste (IHLW) glass

waste form. The resulting ILAW glass containers would be disposed of at the IDF while the

IHLW glass canisters would be stored onsite until an offsite geologic repository is identified.

3.1.2 Low-Activity Waste Melters

Spent or failed LAW melters from WTP operations are expected to be MLLW and would also be

disposed of at the IDF. To meet Resource Conservation and Recovery Act of 1976 (RCRA)

LDR requirements, spent or failed LAW melters may be required to be void filled with grout or

macroencapsulated prior to disposal (RPP-RPT-58204, “Spent/Failed Low-Activity Waste

Melter Transport System Evaluation Report”). Additionally, the DOE/EIS-0391, “Final Tank

Closure and Waste Management Environmental Impact Statement for the Hanford Site,

Richland, Washington” (TC&WM EIS) analysis assumed that each LAW melter would be

packaged in an overpack prior to disposal at the IDF.

2 This decision is consistent with 62 FR 8693, “Record of Decision for the Tank Waste Remediation System,

Hanford Site, Richland, WA,” which was not amended in this area as part of the TC&WM EIS Record of

Decision.



3-2

3.1.3 Secondary Solid Waste

SSW is generated as the result of WTP operations. It includes low-level and mixed low-level

radioactive debris and non-debris waste such as melter consumables, failed process components,

analytical laboratory waste, spent resins, spent carbon adsorbent, high-efficiency particulate air

(HEPA) filters, and other process-related waste. Compared to other WTP SSW, the HEPA

filters, spent Ion Exchange (IX) resins, spent carbon adsorber beds, and HLW silver mordenite

absorbent are expected to contain disproportionate amounts of key radionuclides. These MLLW

streams will require different treatment methods (based on contaminant types and levels) to meet

LDR requirements prior to disposal at the IDF. All SSW deemed as LLW would be packaged

and stabilized (grouted) or compacted prior to being disposed of at the IDF.

3.1.4 Effluent Treatment Facility-Generated Secondary Solid Waste

ETF-generated SSW results from treating secondary liquid waste from the 242-A evaporator, the

retrieval of Contact Handled (CH)-transuranic (TRU) tanks, and from WTP operations which

includes low-level and mixed low-level liquid effluent from the melter primary off-gas treatment

system, the LAW vitrification secondary off-gas/vessel vent treatment system, process vessel

washes, floor drains, sumps, and vessel vent header drains. In addition, liquid waste from

Pretreatment Facility sources such as the radioactive liquid disposal vessels and tanks including

process condensates from evaporators, caustic waste from the LAW caustic scrubber, and spent

reagents from the resin addition process would be routed to the Liquid Effluent Retention

Facility (LERF)/ETF for treatment (24590-WTP-RPT-PT-02-005, “Flowsheet Bases,

Assumptions, and Requirements”). For analysis purposes, these liquid waste streams were

assumed to be representative of the ETF-generated SSW received at the IDF3.

The current ETF treatment process is similar to the process that existed when the TC&WM EIS

analysis was performed. Therefore, the differences in the fraction of mobile radionuclides such

as 99Tc and 129I that volatilize and are captured in the liquid off-gas system and ultimately end up

in the ETF-generated SSW is primarily due to changes in the inventory estimate and changes in

the handling of recycle streams at WTP. The earlier HTWOS model that was used in the

TC&WM EIS had a simple recycle scheme for the LAW melter off-gas [Figure D-8 in

RPP-17152, Rev. 1, “Hanford Tank Waste Operations Simulator (HTWOS) Model Design

Description”]. The more recent model (Figure C-15 in RPP-17152, Rev. 12) recycles liquid

effluents to more locations for more effective management of the effluents.

After treatment at the ETF, the liquid portion of the treated waste stream would be disposed of at

the State-Approved Land Disposal Site (SALDS) while the byproduct waste generated from the

ETF solidification process would be packaged and disposed of at the IDF as ETF-generated

SSW. This waste stream originating from the WTP operations is often referred to as WTP

secondary liquid waste.

3 Although leachate from the Mixed Waste Trench and other miscellaneous sources are planned for disposal at the

IDF as part of ETF-generated SSW, the expected radionuclide concentrations and projected waste stream volumes

are assumed insignificant compared to the contributions from WTP operations (RPP-SPEC-43722, “Secondary

Liquid Waste Treatment Plant Project (T3W08) System Specification”). Additionally, IDF leachate contributions

are not included to avoid double counting of inventory in the 2017 IDF PA analysis.



3-3

The high temperatures associated with the LAW vitrification process could cause volatilization

of mobile radionuclides such as 99Tc and 129I that would not be captured in the liquid off-gas

treatment system and would ultimately end up in ETF-generated SSW. Since the fraction of

these constituents ending up in the final waste form is difficult to predict, a wide range of glass

retentions have been proposed to test the limits of 99Tc and 129I loadings in cementitious waste

forms against established waste form performance characteristics.

3.2 NON-WASTE TREATMENT AND IMMOBILIZATION PLANT GENERATED

WASTE

Contaminant inventories associated with the disposal of non-WTP LLW and MLLW (see

Section 7.0) were based on the inventories presented in Appendix D of the TC&WM EIS for

each of these waste streams. Waste sources based on forecasts developed for the TC&WM EIS

have not been updated so that the information included in the TC&WM EIS represents the best

available source for this expected inventory.

3.2.1 Fast Flux Test Facility Decommissioning Waste

In accordance with 78 FR 75913, DOE selected FFTF Alternative 2 Entombment, which would

remove all above-grade structures, including the reactor building. Below-grade structures would

remain in place and be filled with grout to immobilize the remaining radioactive and hazardous

constituents, then covered with a RCRA-compliant barrier.

In accordance with FFTF Alternative 2 Entombment, the remote-handled special components

would be treated at Idaho National Laboratory and returned to the Hanford Site for disposal.

A description of the proposed remote treatment process is included in DOE/EA-01386, “Final

Environmental Assessment for the Remote-handled Waste Disposition Project.”

Bulk sodium inventories would be treated and stored at Hanford for use at the WTP.

Sodium residuals from FFTF components, (e.g., the reactor and miscellaneous traps), would also

be disposed of at the IDF. Table D-80 of the TC&WM EIS reports inventory contributions from

approximately 4,000 gal of sodium residuals.

In addition to sodium residuals, the FFTF secondary waste under the Entombment Alternative

includes:

Demolition waste from the main Reactor Containment Building and Buildings 491E and

491W that cannot be consolidated in below-grade spaces

Radioactive and hazardous materials from other ancillary buildings

The reactor vessel, piping systems, and tanks (drained to the extent practicable of liquid

sodium) that would not fit in below-grade spaces



3-4

Solid waste resulting from waste processing.

3.2.2 Secondary Waste Management Low-Level Waste and Mixed Low-Level Waste

Secondary waste includes workers’ personal protective equipment, tools, and other contaminated

materials from tank farm operations, as well as:

Secondary LLW and MLLW from operation of LLBG 218-W-5, trenches 31 and 34

Secondary LLW and MLLW from operation of the Waste Receiving and Processing

Facility (WRAP)

Secondary LLW and MLLW from operation of the T Plant complex.

3.2.3 Onsite Non-CERCLA Non-Tank Low-Level Waste and Mixed Low-Level Waste

Onsite non-CERCLA non-tank LLW and MLLW includes solid wastes from onsite generators

such as:

Central Waste Complex

Plutonium Finishing Plant

T Plant Complex

Waste Encapsulation and Storage Facility

Waste Receiving and Processing Facility

Groundwater sampling activities

Pacific Northwest National Laboratory (PNNL)

Cold Vacuum Drying Facility

Canister Storage Building

Liquid Waste Processing Facilities (LERF, ETF, SALDS, and Treated Effluent Disposal

Facility).



4-1

4.0 TANK WASTE INVENTORY

For tank waste processed by WTP, the Best-Basis Inventory (BBI) provides the official tank

waste inventory estimates for 177 single-shell tanks (SSTs) and double-shell tanks (DSTs) at the

Hanford Site (RPP-7625, “Guidelines for Updating Best-Basis Inventory”). The BBI is included

in the Tank Waste Information Network System (TWINS) database that stores and provides all

official tank sample/characterization data and other information related to the SSTs and DSTs at

the Hanford Site.

Note that recently completed and planned tank sampling events are reported in RPP-26781,

“Tank Operations Contractor Sampling Projections for FY2016 through FY2020” (which is

updated on an annual basis). The BBI is maintained through quarterly updates which would

include any new tank sample data as applicable in accordance with BBI protocols.

4.1 BEST-BASIS INVENTORY BACKGROUND

BBI estimates are available for each individual waste phase in a tank. These waste phases

include supernate, saltcake solids, saltcake liquid, sludge solids, sludge liquid, and retained gas.

The BBI provides inventory estimates for each standard BBI constituent (25 chemicals and

46 radionuclides) by using:

Sample data

Process knowledge calculations

Waste-type templates based on sample data, and

Hanford Defined Waste (HDW) computer model estimates (RPP-19822, “Hanford

Defined Waste Model – Revision 5.0”).

Sample data are the preferred source of waste concentration information for the BBI. If sample

data are not available, then the “best available” information means process knowledge model

estimates. Process knowledge concentrations are derived from historical tank sample data,

sample data from other tanks, waste transfers, and chemical additions.

Next, waste-type template concentrations are used when other information is not available. Solid

waste-type templates are based on sample data for a particular waste type supplemented with

process knowledge calculations and waste-type concentrations from the HDW model.

Liquid-waste-type templates are based on waste-type concentrations from the HDW model,

adjusted for process knowledge of mercury and other water-insoluble metals.

Lastly, HDW model-based estimates are used if the preceding information is unavailable for all

of the standard radionuclide constituents except for 137mBa, 228Ra, and 90Y which are calculated

from 137Cs, 232Th, and 90Sr, respectively. Model-based values for tank waste radionuclides are

derived from fuel irradiation and plant process records.



4-2

4.2 BEST-BASIS INVENTORY UNCERTAINTY

Uncertainty in the BBI estimates consists of three components; uncertainty in the total inventory

summed over all of the waste tanks, uncertainty in the inventory estimate within each waste tank,

and uncertainty in the inventory estimate within each phase of each waste tank. Uncertainty in

the total inventory summed over all of the waste tanks affects the total inventory that will be

disposed of in separate waste form types at the IDF.

4.2.1 Total Best-Basis Inventory Uncertainty

Uncertainty in the total inventory in all of the waste tanks affects the total inventory that will be

disposed of in separate waste form types at the IDF. Estimating inventories using process

knowledge calculations involves consideration of reactor fuel irradiation and chemical

separations operations, as well as transfer and processing of tank contents. Incomplete

knowledge of the degree of irradiation, process extraction and separations efficiencies, plant

stream flow rates that affect recovery and distribution, and process losses to the environment all

contribute to the uncertainty in developing process knowledge inventory estimates.

Over time, changes in the total BBI inventory have occurred. Generally adjustments have been

made to remove some of the conservative assumptions used in previous estimates to account for

new information, or to align inventory estimates with tank sampling results. For example, some

of the significant uncertainties reported in HNF-3273, “Hanford Defined Waste Model

Limitations and Improvements” were addressed in Revision 5 of the HDW model, which forms

the basis for the 2014 BBI. Because the 2014 BBI represents the most current available

information, it is planned to be used for the 2017 IDF PA analysis.

In order to address global inventory uncertainty, it is recommended that the 2017 IDF PA

analysis perform a sensitivity study using the more conservative inventory estimates from either

the 2002 BBI or the 2014 BBI. The most significant differences between the two BBI estimates

are discussed in Section 4.3. For the sensitivity case, it is recommended that the HTWOS

partitioning fractions from 2017 IDF PA be applied to the 2002 BBI for each waste form that

will be disposed in the IDF. The allocation of inventory between waste forms for each HTWOS

run case is presented in Section 9.0.

4.2.2 Tank and Waste Phase Uncertainties

Uncertainty in the inventory within each waste tank and within each phase of each waste tank is

best characterized as representing the variability in the concentration of the constituents that will

be treated at the WTP. When feed to the WTP is staged in feed staging tanks that are not

completely emptied during a transfer to the WTP, feed blending occurs and the inventory

allocation to different waste tanks captured in the TWINS database becomes less significant to

the variability of the waste forms.

As the waste treatment mission progresses, the remaining feed becomes more blended resulting

in a more averaged feed composition near the end of the mission than may be experienced at the

beginning of the mission. This change in feed composition effectively results in a temporal



4-3

variability that could result in early production feed compositions that are more or less

concentrated than the highly blended product that occurs later in the mission. This variation in

feed composition would result in variability of the concentration of constituents of potential

concern (COPCs) within the waste streams and waste forms destined for disposal at the IDF. For

a disposal facility that is filled by “lifts” stacked one above another, temporal variability would

manifest into spatial variability with early production waste forms being placed in the bottom

“lifts” and later production waste forms placed in the upper “lifts.” If early production waste

forms contain higher inventories of certain COPCs, then the later production waste forms placed

in the “lifts” above them will have lower concentrations of these same COPCs such that temporal

variability in the WTP feed composition would become less significant. Therefore, the average

inventories provided by the HTWOS process flowsheet model represent a reasonable approach

for the 2017 IDF PA analysis.

Allocation of the chemical and radionuclide inventory between different waste phases could also

affect the inventory variability for each waste form. To address this uncertainty, run cases were

developed to explore the effects that these different allocations would have on the different IDF

waste streams. The run cases developed for this purpose are discussed in Section 6.1 of this data

package.

4.3 BEST-BASIS INVENTORY COMPARISON

The BBI tank waste inventory estimates used in the TC&WM EIS were based on published data

from TWINS as of December 1, 2002. All radionuclides were decayed to January 1, 2001. Any

sample data that were released and waste transfers that occurred after December 1, 2002 were

not included (DOE/ORP-2003-02, Environmental Impact Statement for Retrieval, Treatment,

and Disposal of Tank Waste and Closure of Single-Shell Tanks at the Hanford Site, Richland

WA Inventory and Source Term Data Package).

The BBI is maintained through quarterly updates as new information about tank operations and

tank contents are processed. Although newer BBI estimates were available when the TC&WM

EIS modeling was performed, the TC&WM EIS team used the 2002 BBI for tank waste

inventory data based in part on the results of a 2005 review of the 2002 BBI estimates by the

Washington State Department of Ecology (Ecology) and several DOE offices (i.e., Office of

River Protection; Richland Operations Office; Office of Health, Safety, and Security; Office of

Environmental Management; and Office of the General Counsel), and also based in part on the

review of the 8-year span of BBI data and uncertainty (Appendix D, Section D.1.1.5 of the

TC&WM EIS).

The 2017 IDF PA will use the BBI estimate current in November 2014 as a starting point. In

lieu of re-running the HTWOS model to partition the tank inventory into different waste streams,

sensitivity analyses could assume that the starting inventory allocated to each waste stream is

proportional to the increase or decrease in the BBI inventories for each contaminant. For

instance, a sensitivity case using the BBI estimates from the TC&WM EIS could increase the

amount of iodine in each waste form by 39%. This increase would only be applicable to the

waste streams that originated as tank waste. Equitable distributions of the extra inventory may



4-4

not be consistent with the processes that are used to treat the waste, but could give an indication

of the impact of the uncertainty in the BBI total inventory estimate. A separate sensitivity case

could also be performed using the same waste stream partitioning and volume estimates from

Run Case 7 (Section 6.1) with the inventory used in the TC&WM EIS.

The updated tank waste inventory estimates presented in this data package for WTP-generated

waste streams was published from TWINS as of November 2014 (RPP-33715, Rev. 9,

“Double-Shell and Single-Shell Tank Inventory Input to the Hanford Tank Waste Operations

Simulator Model – 2015-2 Update”). All radionuclides were decayed to January 1, 2008.

A comparison of the December 2002 and November 2014 BBI estimates (with radionuclides

decayed to January 1, 2008) is presented in Table 4-1.

A review of the changes in the BBI estimates over a 12-year period between December 2002 and

November 2014 presented in Table 4-2 shows the following:

All of the radionuclide estimates have decreased since the 2002 BBI estimate was

generated except for 241Am, 90Sr, and 233U, 234U, 235U, and 238U which have increased by

8 to 22%. The only long-lived radiological risk driver in this grouping is the uranium

isotope.

Only two chemical estimates, mercury and total uranium, have increased. All the other

chemical constituents have decreased by 1 to 21%.

The largest decrease in the radiological risk drivers was that of 129I, at 39%.

The largest increase in the radiological risk drivers was 233U, 234U, 235U, and 238U at 22%.

The largest increases in chemical hazard drivers were mercury at 9% and total uranium at

8%

99Tc and 129I values in the 2002 BBI are near the higher end of the range of values

reported between December 2002 and November 2014. Therefore, the 2002 BBI

estimate for these radionuclides represents some degree of conservatism.

Total uranium and uranium isotope values in the 2002 BBI are near the lower end of the

range of values reported between December 2002 and November 2014. The range of

values reported is smaller than the uncertainty itself.

Uranium (total) and uranium isotopes (233U, 234U, 235U, and 238U) are more highly retained in soil

and waste forms and less mobile in the environment, so their contribution to the long-term

impacts analysis should be smaller than the contribution from more mobile radionuclides

(i.e., 99Tc and 129I).



4-5

Table 4-1. Best-Basis Inventory Comparison.

Column 1 EIS BBI

(December 2002 BBI

Decay Date:

January 1, 2008)1

Column 2 IDF BBI

(November 2014 BBI

Decay Date:

January 1, 2008)2

Percent Change

[(Column 2-

Column 1)/

Column 1]

Radionuclides Curies Curies Percent

Americium-241 1.45E+05 1.57E+05 +8

Carbon-14 3.12E+03 5.51E+02 -82

Cesium-137 3.90E+07 3.90E+07 0

Hydrogen-3 (tritium) 8.16E+03 2.82E+03 -65

Iodine-1293 4.82E+01 2.94E+01 -39

Neptunium-237 1.41E+02 1.15E+02 -18

Plutonium-239,-240 8.14E+04 6.02E+04 -26

Strontium-90 4.27E+07 4.76E+07 +11

Technetium-994 2.97E+04 2.65E+04 -11

Uranium-233,-234, -235,-238 9.38E+02 1.14E+03 +22

Chemicals Kilograms Kilograms Percent

Acetonitrile Not reported Not reported Not applicable

Benzene Not reported Not reported Not applicable

Butanol (n-butyl alcohol) Not reported Not reported Not applicable

Chromium 5.98E+05 5.91E+05 -1

Lead 8.41E+04 8.20E+04 -2

Mercury 1.83E+03 1.99E+03 +9

Nitrate 7.09E+07 5.60E+07 -21

Uranium (total) 5.97E+05 6.45E+05 +8

Polychlorinated biphenyls Not reported Not reported Not applicable

2,4,6-Trichlorophenol Not reported Not reported Not applicable

1 DOE/EIS-0391, “Final Tank Closure and Waste Management Environmental Impact Statement for the Hanford Site,

Richland, Washington,” Table D-8. 2 RPP-33715, Rev. 9, “Double-Shell and Single-Shell Tank Inventory Input to the Hanford Tank Waste Operations Simulator

Model-2015 – 2 Update.” 3 Inventory analysis presented by Nez Perce tribe at March 2015 scoping meeting concludes tank farm inventory for 129I is

estimated to be 34.1 Ci. Although this estimate is greater than the November 2014 BBI estimate of 29.4 Ci, it is bounded by

the DOE/EIS-0391 inventory of 48.2 Ci. 4 Inventory analysis presented by Nez Perce tribe at March 2015 scoping meeting concludes tank farm inventory for 99Tc is

estimated to be 28,563. Although this estimate is greater than the November 2014 BBI estimate of 26,500 Ci, it is bounded

by the DOE/EIS-0391 inventory of 29,700 Ci.

BBI = Best-Basis Inventory EIS = Environmental Impact Statement IDF = Integrated Disposal Facility


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Table 4-2. Hanford Tank Waste Historical Inventories for Technetium-99 and Iodine-129. (3 sheets)

Radionuclide Tank Inventory

(Ci)a Basis Source

Tc-99 2.72E+04

(3.43E+04)

ORIGEN2b calculation for single pass and N-reactor production (minus K basin fuels

and minus 20% Tc-99 loss from the waste stream that was sent offsite). WHC-SD-WM-RPT-164,

Rev. 0

I-129 6.62E+01 ORIGEN2b calculation for single pass and N-reactor production (minus K basis fuels).

Tc-99 3.26E+04 ORIGEN2b production and DKPRO separations processing no Tc-99 losses during

separations (Hanford Defined Waste [HDW] Model conservative). HNF-SD-WM-TI-740,

Rev. 0 I-129 6.30E+01

ORIGEN2b production and DKPRO separations processing no I-129 losses during

separations (HDW Model conservative).

Tc-99 3.21E+04 TRACc database adjusted to the 1994 Integrated Databased.

DOE/EIS-0189 I-129 3.83E+01 See Volume 2, Appendix A of DOE/EIS-0189.

Tc-99 4.70E+04 Limited double-shell tank analytical results, TRACc database, and HDW Rev. 1e

normalized to HNF-SD-WM-TI-740 (No Tc-99 losses during separations process). HNF-SD-WM-SP-012,

Rev. 0 I-129 N/A No I-129 losses during separations process.

Tc-99 2.83E+04 Best-Basis Inventory (BBI) as of October 1, 1998. HNF-SD-WM-SP-012,

Rev. 1 I-129 9.91E+01 BBI as of October 1, 1998.

Tc-99 2.89E+04 BBI as of October 1998. HNF-4921, Rev. 0

I-129 1.01E+02 BBI as of October 1998.

Tc-99 3.00E+04 BBI as of January 11, 2000. HNF-SD-WM-SP-012,

Rev. 2 I-129 6.29E+01 BBI as of January 11, 2000.

Tc-99 3.10E+04 BBI as of June 2001. HNF-SD-WM-SP-012,

Rev. 3 I-129 6.86E+01 BBI as of June 2001.

Tc-99 2.97E+04 BBI as of December 1, 2002. DOE/ORP-2003-02

I-129 4.82E+01 BBI as of December 1, 2002.


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(Ci)a Basis Source

Tc-99 2.88E+04 BBI as of June 2002. HNF-SD-WM-SP-012,

Rev. 4B I-129 4.88E+01 BBI as of June 2002.

Tc-99 2.91E+04 BBI as of October 2003. HNF-SD-WM-SP-012,

Rev. 5A I-129 4.74E+01 BBI as of October 2003.

Tc-99 2.51E+04

(3.43E+04) ORIGEN2 productionf included process losses of 23% with respect to HDW Rev. 4.

RPP-19822, Rev.0

I-129 3.18E+01

(4.94E+01)

ORIGEN2 productionf included process losses 23% with respect to HDW Rev. 4, and

reduction in fission product yield change of approximately 23%.

Tc-99 2.68E+04 BBI as of September 22, 2004. TWINS (2004)

I-129 4.39E+01 BBI as of September 22, 2004.

Tc-99 2.64E+04 BBI as of October 2010. DOE/EIS 0391

I-129 2.94E+01 BBI as of October 2010.

Tc-99 2.65E+04 BBI as of November 2014. RPP-33715, Rev. 9

I-129 2.94E+01 BBI as of November 2014.

a Numbers in brackets represent total reactor production. b Oak Ridge Isotope Generation and Depletion Code (ORIGEN2) software code used to estimated reactor production of radionuclides (ORNL/TM-7175,

“A User’s Manual for the ORIGEN2 Computer Code”). c Track Radioactive Constituents computer code (TRAC) (SD-WM-TI-057, “Preliminary Estimation of the Waste Inventories in Hanford Tanks Through

1980”). d Integrated Database for Hanford Waste tanks (Letter 9404636B R2, “Request for Office of Waste Management Integrated Data Base High-Level Waste Data

Information Update”). e HDW – Hanford Defined Waste Model Rev. 1 (LA-UR-96-3860, “Hanford Tank Chemical and Radionuclide Inventories: HDW Model Rev. 4”). f Production calculations (RPP-13489, “Activity of Fuel Batches Processed Through Hanford Separations Plants, 1944 Through 1989”).


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(Ci)a Basis Source

References:

DOE/EIS-0189, “Tank Waste Remediation System, Hanford Site, Richland, Washington, Final Environmental Impact Statement.”

DOE/EIS-0391, “Final Tank Closure and Waste Management Environmental Impact Statement for the Hanford Site, Richland, Washington.”

DOE/ORP-2003-02, Environmental Impact Statement for Retrieval, Treatment, and Disposal of Tank Waste and Closure of Single-Shell Tanks at the Hanford

Site, Richland WA Inventory and Source Term Data Package.

HNF-4921, “Immobilized Low-Activity Tank Waste Inventory Data Package.”

HNF-SD-WM-SP-012, Rev. 0, “Tank Waste Remediation System Operation and Utilization Plan.”

HNF-SD-WM-SP-012, Rev. 1, “Tank Waste Remediation System Operation and Utilization Plan.”

HNF-SD-WM-SP-012, Rev. 2, “Tank Farm Contractor Operation and Utilization Plan.”

HNF-SD-WM-SP-012, Rev. 3, “Tank Farm Contractor Operation and Utilization Plan.”

HNF-SD-WM-SP-012, Rev. 4B, “Tank Farm Contractor Operation and Utilization Plan.”

HNF-SD-WM-SP-012, Rev. 5A, “Tank Farm Contractor Operation and Utilization Plan.”

HNF-SD-WM-TI-740, “Standard Inventories of Chemicals and Radionuclides in Hanford Tank Wastes.”

RPP-19822, “Hanford Defined Waste Model – Revision 5.0.”

RPP-33715, “Double-Shell and Single-Shell Tank Inventory Input to the Hanford Tank Waste Operations Simulator Model – 2015-2 Update.”

Tank Waste Information Network System (TWINS), Queried 09/22/2004, [Best Basis Inventory, Best Basis Summary Report],

http://twins.pnl.gov:8001/twins.htm.

WHC-SD-WM-RPT-164, “Inventories for Low-Level Waste Tank Waste.”



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The differences noted in Table 4-2 are primarily due to the BBI Improvement Initiative4, which

was implemented after December 2002, and included the following:

Updated the Oak Ridge Isotope Generation and Depletion Code (ORIGEN2)

(ORNL/TM-7175, “A User’s Manual for the ORIGEN2 Computer Code”) fuel activity

estimates

Updated the HDW model to Revision 5, which accounted for a release of 3H (tritium), 14C, and 129I to the environment and shipment of offsite 99Tc with uranium (RPP-19822)

Updated the BBI templates with new sample data that added a second type of

Reduction-Oxidation (REDOX) Facility waste to the 241-SX Tank Farm, resulting in an

increase in 241-SX Tank Farm inventory

Eliminated non-credible sample detection limit values from inventory estimates

Incorporated new sample data, including 129I analysis of 241-BY Tank Farm salt cake.

4.4 TANK INVENTORY HISTORY OF TECHNETIUM-99 AND IODINE-129

Since mobile radionuclides such as 99Tc and 129I are the two major contaminants of concern

when considering the groundwater impacts related to the disposal of LLW and MLLW at the

IDF, it is important to understand the uncertainties of these estimates.

Figures 4-1 and 4-2 illustrate the trend in the 99Tc and 129I inventories as a function of the year in

which the inventory information was published. Because of the long half-life of 99Tc and 129I,

making decay corrections does not appreciably change the inventory estimates for comparison

purposes. The 2002 BBI estimates used in the TC&WM EIS and the 2014 BBI estimates used in

the 2017 IDF PA analysis are shown in red for comparison purposes.

4.4.1 Technetium-99 Tank Waste Inventory History

The 99Tc present in tank waste was produced as a fission product from uranium that was

irradiated in reactors and processed through separations to extract plutonium at the Hanford Site.

From 1944 to 1989, about 99,000 metric tons of uranium was processed in separations plants

across the Hanford Site (HNF-SD-WM-TI-740, “Standard Inventories of Chemicals and

Radionuclides in Hanford Site Tank Wastes”). As a result, reactor production records show that

approximately 32,600 to 34,000 Ci of 99Tc were produced during this time.

4 During fiscal year 2002, an internal management assessment was conducted to assess compliance with BBI

requirements and prioritize BBI improvements. Assessment results are reported in RPP-10365, “Best-Basis

Inventory Assessment Report.” In October 2001, a value engineering session was conducted to identify BBI

customer needs and prioritize improvements as part of this management assessment. Results of the value

engineering session are discussed in Appendix A of RPP-7625, “Guidelines for Updating Best-Basis Inventory.”



4-12

Figure 4-1. Published Technetium Inventories in Hanford Tank Waste (Section 4.4.1).

Figure 4-2. Published Iodine-129 Inventories in Hanford Tank Waste (Section 4.4.2).

2.97E+042.65E+04

0

5,000

10,000

15,000

20,000

25,000

30,000

35,000

40,000

45,000

50,000

1990 1995 2000 2005 2010 2015

Tc-99 Inventory

Cu

ries

4.82E+01

2.94E+01

0

20

40

60

80

100

120

1990 1995 2000 2005 2010 2015

I-129 Inventory

Cu

rie

s



4-13

Table 4-2 provides historical inventory estimates showing the evolution of the inventory

estimates for 99Tc and 129I (RPP-20692, Rev. 1, “Inventory Data Package for the 2005 Integrated

Disposal Facility Performance Assessment”).

Although a single source of inventory does not exist for the entire operational period,

approximately 1,300 fuel batch records are available that document the amounts and types of

fuel processed, reactor burn-ups, dates irradiated fuel was removed from the reactor, cooling

times before separation, and dates of reprocessing to remove the plutonium. Additionally, waste

discharges to ponds, cribs and trenches were reasonably well documented.

Utilizing these 1,300 fuel batch records, the ORIGEN2 code (ORNL/TM-7175) estimates that

34,000 Ci of 99Tc were produced and that 27,400 Ci of 99Tc remain in Hanford waste tanks. This

early estimate excludes approximately 20% of the 99Tc that was produced in the reactors because

it was shipped offsite with the recovered uranium and was not sent to the Hanford waste tanks

(HNF-SD-WM-TI-740).

Subsequently, the ORIGEN2 code coupled with the decay (DK) and processing (PRO) computer

code (DKPRO), provides an estimate of 32,600 Ci of 99Tc in Hanford waste tanks. The DKPRO

code was developed at Hanford to generate output files listing the curie values for 99Tc and other

key radionuclides associated with each batch of irradiated fuel processed through the various

reprocessing steps assuming no losses during separations; the estimate is therefore considered to

be conservative.

As shown in Table 4-2, the one high estimate of 47,000 Ci was based on limited DST sample

data and early versions of the HDW model (HDW version 1) which did not allow any loss of 99Tc to waste streams not sent to tanks. The remaining estimates fall in the ranges of 26,500 to

34,000 Ci due to the evolution of reactor production calculations used by the ORIGEN2 software

code. Additionally, estimates for process losses have also been incorporated including

approximately 20% of the 99Tc produced in the reactors that was shipped offsite with the

recovered uranium (HNF-SD-WM-TI-740, RPP-19822).

Table 4-2, extracted from RPP-20692, Rev. 0, lists early to present total inventory estimates in

the Hanford waste tanks. Figure 4-1, also extracted from RPP-20692, Rev. 0, shows a slight

reduction in the 99Tc total inventory over time, which is likely due to a combination of the

availability of more sample data and refinements to the HDW model that estimates the fate of 99Tc in the production/reprocessing chemistry.

Efforts to refine the methodology and computer codes for predicting inventories in the waste

tanks at Hanford has continued. By 1999, a suite of computer codes that collectively produced a

BBI estimate for tank waste volumes, tank waste phases (supernate, salt cake, and sludge), and

tank waste tank inventories (curies for radionuclides and kilograms for chemicals) was adopted.

The BBI is the current official estimate of the waste tank inventories (46 radionuclides and

25 chemicals) in the SSTs and DSTs at the Hanford Site (HNF-SD-WM-TI-740).



4-14

4.4.2 Iodine-129 Tank Waste Inventory History

The 129I present in Hanford waste tanks was also formed from the fission of uranium in nuclear

reactors. The estimates for the total 129I produced are based on reactor production calculations

and range between 49.4 and 66 Ci, neglecting any losses from the separations plants. Most of

the difference in these two estimates is based on a recent reduction in the 129I fission product

yield5 by approximately 23% and modeling of process losses (RPP-19822).

The corresponding BBI estimate for 129I based on measurement data has ranged between 29.4

and 101 Ci. The earlier BBI estimates for 129I tend to be higher than the production estimates

and the most current estimates because the earlier BBI was based on older versions of the HDW

model that did not include the most recent estimates of process losses, the elimination of

non-credible sample detection limit values, and the incorporation of new sample data including 129I analysis of 241-BY Tank Farm saltcake. As seen in Figure 4-2, 129I inventory has

demonstrated a high degree of variability over time.

Understanding the uncertainty of the 129I inventory to be disposed of at the IDF is important

because of its potential impact to groundwater. The TC&WM EIS analysis used the

December 2002 BBI estimate for 129I of 48.2 Ci and assumed that 80% goes to off-gas

(WT-ST-042, Rev. 10, “Curie Distribution for Alternatives 1, 2A, 2B, 3A, 3B, 3C, 4, 5, 6A, 6B,

and 6C”) which was disposed of at the IDF as a grouted MLLW.

The current BBI estimate for 129I is 29.4 Ci, which is reasonably consistent with ORIGEN2

production calculations documented in RPP-19822. Revisions to the 129I inventory in the BBI

database based on HDW Rev. 5 changes were not incorporated until October 2005 and have

changed very little since that time.

5 Yield refers to the fraction of a fission product produced per fission. Yield can be broken down by individual

isotope, chemical element spanning several isotopes of different mass number but same atomic number, or nuclei

of a given mass number regardless of atomic number.



5-1


HTWOS is a dynamic event simulation model and is commonly used at the Hanford Site to

estimate inventories in the WTP process flowsheet (RPP-17152, Rev. 12). In this data package,

HTWOS was used for developing inventory estimates for WTP waste streams that are planned to

be disposed of at the IDF such as:

ILAW glass

LAW melters

WTP SSW (debris and non-debris) and,

ETF-generated SSW.

The HTWOS model was used to partition the total inventory into these different waste streams.

Multiple model runs were performed to develop waste stream inventory estimates that account

for uncertainties in the performance of the treatment processes as well as uncertainties in the

WTP treatment process itself.

5.1 HANFORD TANK WASTE OPERATIONS SIMULATOR BACKGROUND

The HTWOS model uses the BBI, the tank farm operations processes that will be used to retrieve

and transfer the waste from the tanks, the WTP processes that will be used to separate the waste

into high-level and low-activity fractions, and the processes that will be used to generate the final

waste form(s).

To date, numerous scenarios for the fate of current tank waste have been produced that model

waste movement from Hanford’s SSTs and DSTs to its final disposition including IHLW glass,

ILAW glass, bulk vitrification, supplemental LAW, contact-handled and remote-handled TRU

waste, tank retrieval losses, tank residuals, and all secondary waste streams. The current process

flow evaluated by HTWOS is illustrated in Figure 5-1.

5.2 HANFORD TANK WASTE OPERATIONS SIMULATOR UNCERTAINTY AND

LIMITATIONS

Although HTWOS provides a “mass balance” of the inventory for each waste stream in the WTP

process flowsheet, these inventory mass balance estimates are highly dependent on projections of

process performance associated with the numerous processes including waste retrieval from

tanks, waste partitioning during pretreatment, and waste form generation. Many of the processes

are still undergoing development and are largely uncertain. These process uncertainties, along

with the uncertainties associated with tank waste compositions (BBI), are important

considerations when evaluating the distribution of contaminants in the IDF waste forms

generated by the HTWOS model.



5-2

Figure 5-1. Hanford Tank Waste Operations Simulator Flow Sheet.

(LAWPS is not shown, however its paths are similar to WTP PT, except there is recycle from off-gas back to tanks).

ETF = Effluent Treatment Facility SALDS = State-Approved Land Disposal Site

HOG = High-Level Waste Off-Gas SLOG = Supplemental Low-Activity Waste Off-Gas

HTWOS = Hanford Tank Waste Operations Simulator STACK = Off-Gas to atmosphere

IDF = Integrated Disposal Facility TRU = transuranic

LAWPS = Low-Activity Waste Pretreatment System WTP = Waste Treatment and Immobilization Plant

LOG = Low-Activity Waste Off-Gas

In order to maintain mass balance at the end of the WTP mission, the HTWOS model tracks and

reports “Total Accumulation,” an inventory term which represents residual inventory left in

various vessels and HTWOS model logic blocks at the end of the model run. For analysis

Underground Tank

TRU Waste

Waste Treatment and Immobilization Plant

Pretreatment (PT)

High-level

Waste (HLW) Low-Activity

Waste (LAW)

Supplemental

Low-Activity

Waste (SLAW)

HLW

Canister

Spent/Failed

HLW Melter

Off-gas (HOG, LOG, SLOG)

LAW

Container

Spent LAW

Melter

Spent SLAW

Melter

Secondary

Solid Waste

(SSW)

STACK

ETF ETF-

Generated

SSW

SALDS

242-A Evaporator



5-3

purposes, the “Total Accumulation” residual inventory was included as part of the 2017 IDF PA

inventory for both IDF and non-IDF waste streams. Excluding the tank farm and TRU residual

inventories, the remaining “Total Accumulation” inventory was manually allocated to ILAW

glass, LAW melters, WTP SSW, ETF generated SSW, and non-IDF waste streams using the

same partition fractions designated by HTWOS for each run case. The resulting adjusted

inventory for each IDF waste stream with radionuclides decayed to January 1, 2008 and

January 1, 2051 is included in Appendix A.

An understanding of the limitations as well as the inventory tracking and reporting features of

HTWOS relative to WTP SSW and ETF-generated SSW inventory projections is important when

evaluating the distribution of contaminants generated by the HTWOS model.

Simulating a series of events and activities the size and complexity of the WTP process requires

the use of numerous modeling simplifications, assumptions, and operating paradigms. Each of

these introduce elements of uncertainty within the overall HTWOS operations. Areas of

uncertainty include waste phase partitioning fractions, distribution of the key radionuclides and

chemicals, operational decisions, and overall flowsheet configuration. These uncertainties, in

conjunction with the tank inventory uncertainties, are important considerations when evaluating

the result and behavior metrics generated by the HTWOS model.

When the HTWOS model was developed, its main purpose was to provide:

DST space projections

Overall mission metrics such as SST retrieval dates and waste immobilization completion

dates to meet certain legal milestones

Projections on the amount of immobilized waste produced at the end of the WTP

mission.

Waste chemistry and unit operations that directly impact these main purposes are modeled with

as much rigor as is practical. Waste chemistry and unit operations that only tangentially impact

these main purposes, such as WTP SSW and ETF-generated SSW compositions needed to

support the 2017 IDF PA, have received significantly less attention.

Although improvements to the HTWOS modeling of SSW has been discussed, such

improvements have not been implemented for the following reasons:

Not enough information exists to develop meaningful assumptions for estimating how

much of the tank waste would be captured in the SSW stream, such as failed equipment

(excluding failed melters) and discarded personnel protective equipment

Inventory expected in the SSW stream was considered to be substantially less than the

tank waste content of other streams sent to the IDF



5-4

The contents of the SSW would likely be drawn from other waste streams disposed in the

IDF and the waste content of these other streams was considered to include or bound the

waste content of the SSW streams.

The projection of ETF-generated SSW inventory was considered to be a sufficient level of detail

for the HTWOS model when the model was developed.

In consideration of these uncertainties and limitations, HTWOS was used for developing the IDF

waste form inventory estimates in the TC&WM EIS analysis and was also used to develop the

2017 IDF PA waste form inventory estimates presented in this data package. Sensitivity cases

are planned to be included as necessary to explore the range uncertainties associated with

HTWOS limitations.

5.3 HANFORD TANK WASTE OPERATIONS SIMULATOR COMPARISON

As previously mentioned, the HTWOS model uses a “mass balance” approach that relies on

waste stream partitioning fractions to model the flows of material through the WTP systems.

The processes and assumptions behind the current HTWOS model (October 2014) are

documented in HTWOS Version 8.1 (RPP-17152, Rev. 12). The processes and assumptions

(and consequently the waste stream partitioning fractions) have changed over time as the details

of the WTP design have evolved. Since the WTP design is not fully complete, there is an

element of uncertainty in the waste stream partitioning fractions and the distribution of key

radionuclides and chemicals among the various waste forms which are sensitive to these

uncertainties.

To qualitatively characterize uncertainty, Table 5-1 has been prepared showing the distribution

of key constituents among the glass and non-glass waste forms. The columns labeled “TC&WM

EIS HTWOS” show the distribution of key constituents and the partitioning fractions from the

TC&WM EIS Tank Closure Alternative 2A. The columns labeled “2017 IDF PA HTWOS”

show the distribution of key constituents and the partitioning fractions from Run Case 7

(Section 6.0) which is most representative of the current WTP process flow sheet as of

October 2014.

The changes in the distribution of 129I between glass and non-glass waste forms are important in

understanding factors that may influence calculated impacts. The current WTP process

flowsheet model retains much more 129I in ILAW glass than the TC&WM EIS, with nearly all

the remainder going to WTP SSW. In the TC&WM EIS case, most of the 129I inventory not

retained in ILAW glass was found in ETF-generated SSW, followed by WTP SSW.

Furthermore, Chapter 7 of the TC&WM EIS showed that the risk budget for 129I at the IDF fence

line was strongly influenced by the distribution of 129I between glass and non-glass waste forms.

In terms of impacts from chemicals, the decrease in the inventory of nitrate for ETF-generated

SSW as shown in Table 5-1 for the “2017 IDF PA HTWOS” will have a similar effect on the

calculated impacts at the IDF fence line.


R

PP

-EN

V-5

8562

, Rev

. 3

5-5

Table 5-1. Comparison of Hanford Tank Waste Operations Simulator Partitioning Fractions from the Tank Closure and

Waste Management Environmental Impact Statement versus Current Hanford Tank Waste Operations Simulator

Partitioning Fractions.

Key

Contaminant

ILAW Glass LAW Melter WTP Secondary Solid

Waste

ETF-Generated

Secondary Solid Waste Total Inventory to IDF

TC&WM

EIS

HTWOS

2017 IDF

PA

HTWOS

TC&WM EIS

HTWOS

2017 IDF

PA

HTWOS

TC&WM

EIS

HTWOS

2017 IDF

PA

HTWOS

TC&WM

EIS

HTWOS

2017 IDF

PA

HTWOS

TC&WM

EIS

HTWOS

2017 IDF

PA

HTWOS

I-129 19.8%

(9.56)

56.2%

(16.5)

Included as part

of ILAW glass

0.08%

(<1)

9.7%

(4.65)

41.2%

(12.1)

69.7%

(33.6)

0.22%

(<1) 47.8 28.6

Tc-99 96.9%

(28,800)

99.6%

(26,400)

Included as part

of ILAW glass

0.14%

(37.5)

1.5%

(431)

0.08%

(20.0)

0.3%

(86.3)

0.0%

(<1) 29,300 26,500

U isotopes 5.8%

(54.7)

1.4%

(15.8)

Included as part

of ILAW glass

0.0%

(<1)

0.4%

(3.64)

0.0%

(<1)

0.0%

(<1)

0.0%

(<1) 58.4 15.8

Cr 76.2%

(456,000)

83%

(490,000)

Included as part

of ILAW glass

0.13%

(744)

0.3%

(1,940)

0.13%

(743)

<1%

(44.3)

<1%

(4.30) 458,000 491,000

Utotal 6.3%

(37,400)

1.3%

(8,100)

Included as part

of ILAW glass

<1%

(11.5)

0.4%

(2,320)

0.0%

(<1)

<1%

(40.0)

<1%

(8.30) 39,800 8,120

NO3 0.0%

(0)

0.0%

(0)

Included as part

of ILAW glass

0.0%

(0)

0.0%

(<1)

0.0%

(0)

12.7%

(9,010,000)

0.29%

164,000 9,010,000 164,000

Note: Radionuclides are reported in (curies) and chemicals reported in (kilograms) and expressed as percentages of the 2002 or 2014 Best-Basis Inventory as applicable. Note

that these IDF inventories include only waste streams that are disposed of at the IDF and therefore do not represent perfect mass balance. Differences can be attributed to

destruction during treatment, stack losses, and disposal offsite at a geologic repository. The TC&WM EIS reports nitrate values calculated as nitrate plus nitrite (oxidized).

EIS = Environmental Impact Statement IDF = Integrated Disposal Facility PA = Performance Assessment

ETF = Effluent Treatment Facility ILAW = Immobilized Low-Activity Waste TC&WM = Tank Closure and Waste Management

HTWOS = Hanford Tank Waste Operations Simulator LAW = Low-Activity Waste WTP = Waste Treatment and Immobilization Plant



5-6

Many of the differences presented in Table 5-1 are due to treatment destruction assumptions

applied to the LAW melter and off-gas systems (i.e., NO3) and the handling of recycle streams

that lead to the use of different split fractions for certain process streams. The earlier HTWOS

model that was used in the TC&WM EIS had a simple recycle scheme for the LAW melter

off-gas (see Figure D-8 in RPP-17152, Rev. 1), whereas the more recent model recycles liquid

effluents to more locations for more effective management of the effluents (see Figure C-15 in

RPP-17152, Rev. 12). Additionally, for the TC&WM EIS analysis, the nitrite inventory in the

tanks was converted on a molecular-weight basis and added to the nitrate inventory and reported

as nitrate.

Table 5-1 shows important differences between the “TC&WM EIS HTWOS” and the “2017 IDF

PA HTWOS” inventory distributions for key mobile radionuclides (99Tc and 129I) in ILAW glass

versus non-glass waste forms (WTP SSW plus ETF-generated SSW). The source of these

differences is largely attributed to changes in the BBI estimates and updates to the HTWOS

partitioning assumptions associated with these constituents.

The 2002 BBI estimate for 99Tc used in the TC&WM EIS was 29,700 Ci, whereas the

November 2014 BBI estimate being used in the 2017 IDF PA is 26,500 Ci, a decrease of

approximately 11% (Table 4-1). The most notable difference between the TC&WM EIS and

2017 PA analysis with respect to 99Tc is the amount that reports to non-glass waste forms (WTP

SSW plus ETF-generated SSW). The TC&WM EIS reports a combined total of 517.3 Ci for

these waste forms, whereas the 2017 IDF PA reports a combined total of only 20 Ci, a significant

decrease of approximately 96%.

A simple comparison can be made by applying the partitioning fractions used in the TC&WM

EIS for Tank Closure Alternative 2A to the 2014 BBI estimates for 99Tc from the 2017 IDF PA

to illustrate how these waste form inventories would look if they were developed using the same

partitioning fractions used in the TC&WM EIS (Figure 5-2).

As shown, the total curies of 99Tc reporting to non-glass waste forms for the 2017 IDF PA

analysis is 478 Ci, which is within 11% of the TC&WM EIS analysis, demonstrating the impact

that relatively small changes in partitioning fractions (< 2%) have on the fate of 99Tc in tank

waste processed at WTP.

Additionally, the 2002 BBI estimate for 129I that was used in the TC&WM EIS was 48.2 Ci

whereas the November 2014 BBI estimate being used in the 2017 IDF PA is 29.4 Ci, a decrease

of approximately 39% (Table 4-2). The ILAW glass partitioning factor for 129I used in the

TC&WM EIS was approximately 20% based on DOE Office of River Protection guidance

(Appendix E of the TC&WM EIS), whereas the 2017 IDF PA used a partitioning factor of 56%

based on refinements to the LAW melter decontamination factors for volatile constituents

(24590-WTP-RPT-PT-02-005, Rev. 7). As a consequence of capturing much less 129I in ILAW

glass, the TC&WM EIS reports a combined total of 38.25 Ci to non-glass waste forms (WTP

SSW plus ETF-generated SSW), whereas the PA reports a combined total of only 12.1 Ci to

non-glass waste forms, a significant decrease of approximately 68%.



5-7

Figure 5-2. Technetium-99 Comparison using Tank Closure and Waste Management

Environmental Impact Statement Partitioning Fractions.

BBI = Best-Basis Inventory ILAW = Immobilized Low-Activity Waste

EIS = Environmental Impact Statement PA = Performance Assessment

ETF = Effluent Treatment Facility TC&WM = Tank Closure and Waste Management

IDF = Integrated Disposal Facility

A simple comparison can be made by applying the partitioning fractions used in the TC&WM

EIS for Tank Closure Alternative 2A to the 2014 BBI estimates for 129I from the 2017 IDF PA to

illustrate how these waste stream inventories would look if they were developed using the same

partitioning fractions used in the TC&WM EIS (Figure 5-3).

Although the partitioning fractions are the same, the inventory of 129I in non-glass waste forms

being analyzed in the 2017 IDF PA is still significantly less (~40%) than what was analyzed in

the TC&WM EIS, demonstrating the influence that changes to the BBI estimates (2002 versus

2014) have relative to analysis of 129I.

28,800

86.3

431

29,317

25,679

79.5

398

26,156

1

10

100

1,000

10,000

100,000

ILAW glass ETF GeneratedSecondary Solid

Waste

Secondary SolidWaste

Total

Tc-99 Inventories Using 2014 BBI and TC&WM EIS Partitioning Factors

EIS

2017 IDF PA



5-8

Figure 5-3. Iodine-129 Comparison.

BBI = Best-Basis Inventory ILAW = Immobilized Low-Activity Waste

EIS = Environmental Impact Statement PA = Performance Assessment

ETF = Effluent Treatment Facility TC&WM = Tank Closure and Waste Management

IDF = Integrated Disposal Facility

9.56

33.6

4.65

47.81

5.82

20.5

2.85

29.16

1

10

100

ILAW glass ETF GeneratedSecondary Solid

Waste

Secondary SolidWaste

Total

I-129 Inventories Using 2014 BBI and TC&WM EIS Partitioning Factors

EIS

2017 IDF PA



6-1

6.0 WASTE TREATMENT AND IMMOBILIZATION PLANT GENERATED WASTE

INVENTORY ESTIMATES—RESULTS

Five HTWOS model run cases (Run Cases 7, 8B, 9, 10A, and 10B)6 were developed to explore

the inventory estimates for waste streams going to the IDF that result from processing tank waste

through the WTP Facility using different process flowsheet assumptions. These assumptions

were developed to evaluate a range of retention efficiencies relative to 99Tc and 129I in ILAW

glass, since the WTP process flowsheet is in flux given ongoing technical decisions and

regulatory discussions. The first three of the five HTWOS model runs that were performed

(Cases 7, 8B, and 9) address operational uncertainties (i.e., technetium removal and WTP

without Low-Activity Waste Pretreatment System (LAWPS). The other two cases evaluate

operational uncertainties regarding process stream recycle efficiencies. The process flowsheet

for the TC&WM EIS Case (Tank Closure Alternative 2B without 99Tc removal) is also included

for comparison purposes; this case is referred to as Case 1.

Summary tables for each HTWOS run case showing the distributions of key radionuclides and

chemicals for each IDF waste stream are provided in Section 9.0. Summary tables for the

TC&WM EIS run case provided for comparison purposes. These summary tables include a

limited number of contaminants and are included for convenience to facilitate comparisons

between the 2017 IDF PA and the results presented in Appendix D of the TC&WM EIS. For the

2017 IDF PA, complete inventory tables including all BBI constituents for the WTP waste

streams are provided in Appendix A of this data package.

A LAWPS facility is included in all process flowsheets with the exception of Case 9. LAWPS,

as analyzed here, allows waste to be treated earlier in time but has no real impact on inventory

since all tank waste inventory will be processed through WTP regardless of the timeframe.

Additionally, the different process flowsheet scenarios presented here demonstrate stream

recycle and glass retention efficiency alternatives that will impact the partitioning of

radionuclides and hazardous chemicals into different secondary waste streams which influence

the contaminant loadings in non-glass waste forms planned for disposal at the IDF.

6.1 THE ENVIRONMENTAL IMPACT STATEMENT AND HANFORD TANK

WASTE OPERATIONS SIMULATOR CASES INVENTORY ESTIMATES

Case 1 – The TC&WM EIS Case

In accordance with 78 FR 75913, DOE has not selected a supplemental treatment technology at

this time, and has implemented Tank Closure Alternative 2B, without supplemental treatment

and WTP without 99Tc removal in the WTP Pretreatment Facility. For the purpose of this data

package, implementation of the Record of Decision is equivalent to the TC&WM EIS

Alternative 2A inventory.

6 Run Cases 2 through 6 were not used for the PA analysis because they were either experimental or because they

were not consistent with 78 FR 75913.



6-2

The process flowsheet for the TC&WM EIS Case is presented in Figure 6-1. The inventory

summary table for the IDF waste streams from the TC&WM EIS Case is presented in

Section 9.0.

Figure 6-1. Tank Closure Alternative 2B Flowsheet from the Tank Closure and Waste

Management Environmental Impact Statement.

Adapted from Figure D-3 (without Tc-99 removal) from Appendix D of DOE/EIS-0391, “Final Tank Closure and Waste

Management Environmental Impact Statement for the Hanford Site, Richland, Washington”

HLW = High-Level Waste ILAW = Immobilized Low-Activity Waste

IDF = Integrated Disposal Facility LAW = Low-Activity Waste

Case 7 – Current Operations Case

The first HTWOS run case was designed to represent the WTP process flowsheet as of

October 2014 using the most current operational assumptions which are in flux, given technical

decisions and regulatory discussions. This case is designated as Case 7, the Current Operations

Case.

The key process flowsheet assumptions for Case 7 include the following:

WTP startup includes 10 years of LAWPS operations to accelerate the pretreatment of

LAW and the use of the LAW melter until the WTP Pretreatment Facility is operational

and the WTP equivalent is operating.

No 99Tc removal in pretreatment (same as TC&WM EIS Alternative 2A).

During the time that LAWPS is operational, the Submerged Bed Scrubber (SBS), Wet

Electrostatic Precipitator (WESP), and Caustic Scrubber (CS) off-gas streams would be

recycled back to tank farms. When WTP becomes operational (10 years later), the SBS

and WESP condensates would be recycled back to the Pretreatment Facility while the CS

waste stream would go to LERF/ETF. This represents the LAW flowsheet as of

October 2014 (ORP-11242, Rev. 7, “River Protection Project System Plan”).



6-3

The primary waste product would be ILAW glass containers (same as TC&WM EIS

Alternative 2A).

During each pass, approximately 32% of the 99Tc is retained in the ILAW glass product.

The remainder goes into the off-gas system (SBS and WESP). The SBS and WESP

condensates are recycled back to the Pretreatment Facility. As a result of this recycle, the 99Tc retention of ILAW glass product is approximately 99% of the total 99Tc inventory,

which is similar to TC&WM EIS Alternative 2A. This case demonstrates the impacts of

a high-efficiency retention of 99Tc in glass due to recycle.

During each pass, approximately 20% of the 129I would be retained in the ILAW glass.

The remainder goes into the off-gas system (SBS and WESP). The SBS and WESP

condensates are recycled back to the Pretreatment Facility. As a result of this recycle, the 129I retention of ILAW glass product is 56%, which is much higher than was analyzed in

TC&WM EIS Alternative 2A (20%). Most of the 129I that is not retained in the glass

after recycle is captured in the carbon absorber media, which is disposed of at the IDF as

WTP SSW.

The process flowsheet for Case 7 is presented in Figure 6-2. The inventory summary table for

the IDF waste streams from Case 7 is presented in Section 9.0. The complete material balance

for Case 7 is included in Excel®7 spreadsheet SVF-4092, “IDF PA Case 7 - Current Information

Case - Mass Balance, MMR-50049.”

Figure 6-2. Case 7 – Current Information Case Flowsheet.

HLW = High-Level Waste LAW = Low-Activity Waste

IDF = Integrated Disposal Facility LAWPS = Low-Activity Waste Pretreatment System

ILAW = Immobilized Low-Activity Waste WTP PT = Waste Treatment and Immobilization Plant Pretreatment

7 Excel® is a registered trademark of Microsoft Corporation in the U.S. and other countries.

7

Tank WTP PT

8 LAW Melters

OffgasCleanup

2 HLW Melters

OffgasCleanup

LAWPS

ILAW glass to IDF

Secondary Waste to IDF



6-4

The other four sensitivity cases (Run Cases 8B, 9, 10A, and 10B) were generated from Case 7

using slightly different process flowsheet assumptions.

Case 8B – Tc-99 Removal from LAW Vitrification Off-Gas Condensate

The key change to the Case 7 process flowsheet assumption for Case 8B includes:

99% removal of 99Tc from the LAW off-gas stream.

Note that the “Accumulator” term presented in this run case is not a WTP unit operation; rather,

it is a way for HTWOS to represent the total inventory being removed to demonstrate the

efficiency of removing 99Tc from SBS-WESP liquid off-gas stream which is in the pertechnetate

form. The disposition of the 99Tc in the “Accumulator” would be IHLW and offsite disposal, not

at the IDF.

The process flowsheet for Case 8B is presented in Figure 6-3. The inventory summary table for

the IDF waste streams from Case 8B is presented in Section 9.0. The complete material balance

for Case 8B is included in Excel® spreadsheet SVF-4094, “IDF PA Case 8B – Tc_Tc-99

Removal from LAW Vitrification Off-Gas Condensate - Mass Balance, MMR-50051.”

Figure 6-3. Case 8B – Technetium-99 Removal from Low-Activity Waste Vitrification

Off-Gas Condensate Flowsheet.

HLW = High-Level Waste LAWPS = Low-Activity Waste Pretreatment System

IDF = Integrated Disposal Facility SBS = Submerged Bed Scrubber

ILAW = Immobilized Low-Activity Waste WESP = Wet Electrostatic Precipitator

LAW = Low-Activity Waste WTP PT = Waste Treatment and Immobilization Plant Pretreatment



6-5

Case 9 – Removal of LAWPS

The key changes to the Case 7 process flowsheet assumption for Case 9 include the following:

LAWPS would not be used. Operations would not start until the WTP Pretreatment and

HLW Facilities are completely ready.

This process flowsheet is somewhat representative of the TC&WM EIS process

flowsheet; however, the TC&WM EIS results are based on a different version of the BBI

(BBI 2002) and different partitioning assumptions for 129I, 99Tc, and other constituents.

The process flowsheet for Case 9 is presented in Figure 6-4. The inventory summary table for

the IDF waste streams from Case 9 is presented in Section 9.0 The complete material balance

for Case 9 is included in Excel® spreadsheet SVF-4095, “IDF PA Case 9 - Removal of LAWPS -

Mass Balance, MMR-50052.”

Figure 6-4. Case 9 – Removal of Low-Activity Waste Pretreatment System Flowsheet.

HLW = High-Level Waste ILAW = Immobilized Low-Activity Waste

IDF = Integrated Disposal Facility LAW = Low-Activity Waste

Case 10A – 32% 99Tc Retention in ILAW Glass

Case 10A represents a contrived scenario that limits the amount of the LAW off-gas stream that

is recycled back into the melters. This unanticipated operating scenario was developed as a

sensitivity case and does not represent a realistic WTP operating condition given the current

configuration of the facilities. This case was contrived to increase the amount of key

contaminants such as 99Tc in non-glass waste forms in order to evaluate its impact on the IDF

system. In the typical operating configuration, the off-gas condensate would be routed to the

ETF for treatment. In order to determine the limitations of the IDF system, the off-gas stream

routed to the ETF in this sensitivity case is done with the realization that it does not meet the



6-6

current ETF waste acceptance criteria. The key change to the Case 7 process flowsheet

assumption for Case 10A includes:

32% of the 99Tc would be retained in the glass product, to investigate the disposal

impacts associated with reduced retention of 99Tc in ILAW glass.

DM-10 testing at Vitreous State Laboratory (VSL) showed that the lowest 99mTc retention in

LAW glass averaged across all LAW feed types tested was 32% (RPP-54130, “Technetium

Retention in WTP LAW Glass with Recycle Flow-Sheet: DM10 Melter Testing,

VSL-12R2640-1, Rev. 0,” Table 5.9). This low retention efficiency represents a sensitivity case

and is not the actual 99Tc ILAW glass retention rate that is expected during WTP operations.

The purpose of this case is to allow the PA team to test the IDF system and explore the impacts

of 99Tc captured in a grouted secondary waste form rather than in a glass waste form.

The process flowsheet for Case 10A is presented in Figure 6-5. The reduced efficiency in the

off-gas recycle was implemented in HTWOS by eliminating the recycle stream from the model.

As a result, the only exit for 99Tc from the process flowsheet was through the off-gas condensate.

The result is that much more material ends up on the media used to treat the off-gas or at the

LERF/ETF. Because this run case was configured to exclude recycle, the glass volume produced

is consistent with a single-pass operation and not a reduced efficiency recycle loop. The

inventory summary table for the IDF waste streams from Case 10A is presented in Section 9.0.

The complete material balance for Case 10A is included in Excel® spreadsheet SVF-4096, “IDF

PA Case 10A - Single Pass Tc_Tc-99 Retention in ILAW Glass of 32% - Mass Balance,

MMR-50053.”

Figure 6-5. Case 10A and 10B – Low and Medium Efficiency Recycle.

HLW = High-Level Waste LAW = Low-Activity Waste

IDF = Integrated Disposal Facility LAWPS = Low-Activity Waste Pretreatment System

ILAW = Immobilized Low-Activity Waste WTP PT = Waste Treatment and Immobilization Plant Pretreatment



6-7

Case 10B –68% 99Tc Retention in ILAW Glass

The key change to the Case 10A process flowsheet assumption for Case 10B includes:

68% of the 99Tc would be retained in the glass product, to investigate the disposal

impacts associated with reduced retention of 99Tc in ILAW glass.

DM-10 testing at VSL demonstrated 99mTc retention in LAW glass averaged across all LAW

feed types tested was 68% with recycle (RPP-54130, Table 5.9). This retention efficiency

represents a contrived sensitivity case and is not the actual 99Tc ILAW glass retention rate

expected during WTP operations. The purpose of this case is to allow the PA team to understand

the IDF system behavior in response to perturbations and explore the impacts of 99Tc captured in

a grouted secondary waste form rather than in a glass waste form. This sensitivity case is done

with the realization that this liquid off-gas waste stream does not meet the current ETF waste

acceptance criteria.

The process flowsheet for Case 10B is presented in Figure 6-5. The inventory summary table for

the IDF waste streams from Case 10B is presented in Section 9.0. The complete material

balance for Case 10B is included in Excel® spreadsheet SVF-4097, “IDF PA Case 10B - Recycle

Pass Tc_Tc-99 Retention in ILAW Glass of 68% - Mass Balance, MMR-50054.”

Note that a subsequent analysis at VSL as presented in report VSL-13R2800-1, “Wet

Electrostatic Precipitator Performance and Technetium-Rhenium Behavior in LAW Recycle

Flow-Sheet” indicates that previously measured technetium concentrations in glass samples are

biased low by approximately 8%. However, the range of 99Tc retention in ILAW glass being

investigated in Run Cases 7 through 9 and in sensitivity cases 10A and 10B is approximately

32% to 99%, which is broad enough to include this new information.

6.2 WASTE TREATMENT AND IMMOBILIZATION PLANT SECONDARY SOLID

WASTE STREAM PARTITION FRACTIONS

HTWOS provides inventories for a limited number of WTP SSW streams. The largest volume

of SSW generated from WTP operations is “other debris” waste which includes pumps, agitators,

melter components, etc. This waste stream is not specifically reported by HTWOS; therefore,

partition fractions were developed using detailed information available in Appendix C of

24590-WTP-RPT-ENS-10-010, “WTP Estimate of Secondary Radioactive Solid Waste

Generation” (10-010) and in Section 3 of 24590-WTP-RPT-ENS-10-009, “Secondary Waste

Estimates for WTP HVAC HEPA Filters” (10-009) to allocate WTP SSW inventory reported by

HTWOS to each of the following waste streams:

HEPA filters

IX resin

LAW and HLW carbon adsorber beds

HLW silver mordenite

Other debris.



6-8

Appendix A of this data package includes a comprehensive table of these inventories as well as

the partitioning fractions used to generate them. The methodology for developing these

partitioning fractions is based on simple ratios. Using 137 Cs from a HEPA filter as an example,

the partitioning fraction was computed as follows:

Partitioning Fraction = Curies of 137Cs on HEPA

Total Curies of 137Cs in WTP SSW

A comparison of the HTWOS partitioning fractions developed from Run Case 7 to the

partitioning fractions developed from the 10-010 and 10-009 documents show very different

distributions of 129I and 99Tc in “like” WTP SSW streams (Table 6-1 and Table 6-2). HTWOS

reports most of the 129I inventory present in WTP SSW to the carbon adsorber beds (98%)

whereas the 10-010 reports only 32% to the carbon adsorber beds and the balance to HLW silver

mordenite absorbent. For 99Tc, HTWOS reports about half of the WTP SSW inventory to HEPA

filters and the other half to IX resins whereas the 10-009 reports almost all of the 99Tc to HEPA

filters (88%) with the remainder going to IX resin.

Table 6-1. 10-010 Partitioning Fractions for Waste Treatment and

Immobilization Plant Secondary Solid Waste Streams.

Waste Stream 29I 137Cs 90Sr 99Tc Cr Hg Pb

High-Efficiency Particulate Air filters 1% 51% 66% 88% 94% 0% 61%

Ion Exchange resin 0% 9% 0% 12% 5% 0% 20%

Low-Activity Waste and High-Level Waste

carbon adsorber beds 36% 0% 0% 0% 0% 100% 0%

High-Level Waste silver mordenite absorbent 62% 0% 0% 0% 0% 0% 0%

Other debris 0% 40% 34% 1% 0% 0% 19%

Table 6-2. Hanford Tank Waste Operations Simulator Partitioning Fractions for

Waste Treatment and Immobilization Plant Secondary Solid Waste Streams.

Waste Stream 29I 137Cs 90Sr 99Tc Cr Hg Pb

High-Efficiency Particulate Air filters 0% 2% 100% 45% 98% 0% 97%

Ion Exchange resin 0% 98% 0% 55% 2% 0% 3%

LAW and HLW carbon adsorber beds 98% 0% 0% 0% 0% 100% 0%

HLW silver mordenite absorbent 2% 0% 0% 0% 0% 0% 0%

Other debris N/A N/A N/A N/A N/A N/A N/A

HLW = High-Level Waste LAW = Low-Activity Waste N/A = not applicable



6-9

The partitioning fractions used in the 10-010 and 10-009 report and by HTWOS are based on the

“Flowsheet Bases, Assumptions, and Requirements” (BARD); however, the 10-010 report

applies cleaning factors to the resulting contaminant inventories retained on all SSW stream

components. As such, the partitioning fractions developed from the 10-010 and 10-009 reports

are based on much lower inventories than those reported by HTWOS, attributing to differences

in the partitioning fractions shown in Tables 6-1 and 6-2. For analysis purposes, the

recommendation for the 2017 IDF PA would be to evaluate a range of distributions of key

contaminants in WTP SSW streams that accommodates for differences in the two partitioning

methodologies.

The partitioning fractions developed from Appendix C of the 10-010 and Section 3 of the 10-009

reports were applied to the WTP SSW inventory reported by HTWOS and a comparison of

several key contaminants for each run case was performed. This comparison shows that Run

Case 7 (presented in Table 6-3) is reasonably bounding and is therefore assumed to be the

representative case for analysis purposes. Inventory distributions based on HTWOS partition

fractions are shown in Table 6-4 for comparison purposes. No comparative inventory from the

TC&WM EIS is provided since the TC&WM EIS did not analyze WTP SSW streams at this

same level of detail. Volume estimates for each of these detailed WTP SSW streams are

presented in Section 8.2.


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Table 6-3. Run Case 7 Contaminant Inventory for Waste Treatment and Immobilization Plant Secondary Solid Waste

Streams using 10-010 Partitioning Fractions.

Waste Stream Debris/Non-Debris 129-I 137-Cs 90-Sr 99-Tc Cr Hg Pb

High-Efficiency Particulate Air Filters Debris 0.13 2,031.17 17.29 17.45 699.62 0.00 7.27

Ion Exchange Resin Non-Debris 0.02 370.76 0.02 2.36 39.77 0.02 2.33

Low-Activity Waste and High-Level Waste Carbon Beds Non-Debris 4.42 0.00 0.00 0.00 0.00 1,001.95 0.00

Other Debris Debris 0.00 1,595.89 8.98 0.11 3.47 0.00 2.31

High-Level Waste Silver Mordenite Absorbent Non-Debris 7.56 0.00 0.00 0.00 0.00 0.01 0.00

Secondary Solid Waste Total 12.12 3,997.82 26.29 19.92 742.86 1,001.98 11.91

Table 6-4. Run Case 7 Contaminant Inventory for Waste Treatment and Immobilization Plant Secondary Solid Waste

Streams using Hanford Tank Waste Operations Simulator Partitioning Fractions.

Waste Stream Debris/Non-

Debris 129-I 137-Cs 90-Sr 99-Tc Cr Hg Pb

High-Efficiency Particulate Air Filters Debris 0.00 71.41 26.29 8.99 731.67 0.00 11.61

Ion Exchange Resin Non-Debris 0.00 3,926.41 0.00 10.93 11.19 0.00 0.30

Low-Activity Waste and High-Level Waste Carbon Beds Non-Debris 11.82 0.00 0.00 0.00 0.00 1,001.98 0.00

Other Debris Debris N/A N/A N/A N/A N/A N/A N/A

High-Level Waste Silver Mordenite Absorbent Non-Debris 0.30 0.00 0.00 0.00 0.00 0.00 0.00

Secondary Solid Waste Total 12.12 3,997.82 26.29 19.92 742.86 1,001.98 11.91

NA = not applicable



7-1

7.0 NON-WASTE TREATMENT AND IMMOBILIZATION PLANT-GENERATED

WASTE INVENTORY ESTIMATES

7.1 FAST FLUX TEST FACILITY DECOMMISSIONING WASTE INVENTORY

ESTIMATE

Table 7-1 includes the inventory estimates for FFTF decommissioning waste which are based on

the TC&WM EIS FFTF Decommissioning Alternative 2 identified in the TC&WM EIS Record

of Decision.

Table 7-1. Fast Flux Test Facility Decommissioning Inventory Estimates for Waste

Going to Integrated Disposal Facility1.

137Cs

Ci

14C

Ci

3H

Ci

99Tc

Ci

Cr

Kg

Pb

Kg

U

Kg

Sodium residuals2 1.43E-03 0.00E+00 2.29E+00 0.00E+00 5.72E-03 4.30E-03 2.86E-02

Secondary waste 1.43E-03 6.33E-04 3.58E-07 1.48E-02 1.79E-03 1.34E-03 4.09E-03

Total3 2.86E-03 6.33E-04 2.29E+00 1.48E-02 7.50E-03 5.64E-03 3.27E-02

Total4 9.61E-04 6.29E-04 1.60E-01 1.48E-02 N/A N/A N/A

1 Table D-80 from Appendix D of DOE/EIS-0391, “Final Tank Closure and Waste Management Environmental Impact

Statement for the Hanford Site, Richland, Washington.” 2 The inventory for approximately 15,142 liters (4,000 gallons) of sodium residuals which includes Fast Flux Test

Facility components (e.g., the reactor and miscellaneous traps). 3 Assumed decay date of September 2003 consistent with Tables D-75 and D-76 of DOE/EIS-0391.

4 Radionuclides decayed to January 1, 2051 (assumed Integrated Disposal Facility closure date).

N/A = not applicable

7.2 SECONDARY WASTE MANAGEMENT LOW-LEVEL WASTE AND MIXED

LOW-LEVEL WASTE INVENTORY ESTIMATE

Table 7-2 includes the inventory estimates for secondary waste based on Waste Management

Alternative 2 reported in the TC&WM EIS. Secondary waste management LLW includes

workers’ personal protective equipment, tools, tank farm activity waste, and other contaminated

waste materials such as secondary LLW and MLLW from operation of:

LLBG 218-W-5, trenches 31 and 34 (TC&WM EIS assumes that LLBG trench 31 and 34

operate through 2050, which is reasonably consistent with the PA assumption that the

IDF operates through 2051)

Waste Receiving and Processing Facility

T Plant complex.


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Table 7-2. Secondary Waste Management Low-Level Waste and Mixed Low-Level Waste Inventory Estimates for

Waste Going to Integrated Disposal Facility1.

129I 137Cs 14C 3H

233U, 234U, 235U, 238U

237Np 239Pu, 240Pu

90Sr 99Tc Cr Hg Pb

Ci Ci Ci Ci Ci Ci Ci Ci Ci Kg Kg Kg

Secondary

Waste2 1.43E-05 1.04E+00 4.04E-05 3.03E+01 1.05E-03 6.17E-06 1.86E+00 6.28E+00 9.95E-02 1.39E+01 2.29E+00 2.32E+02

Secondary

Waste3 1.43E-05 3.28E-01 4.02E-05 1.82E+00 1.05E-03 6.17E-06 1.86 1.88E+00 9.95E-02 N/A N/A N/A

1 Table D-83 from Appendix D of DOE/EIS-0391, “Final Tank Closure and Waste Management Environmental Impact Statement for the Hanford Site, Richland,

Washington.” 2 Radionuclides assumed decayed to January 1, 2001 consistent with decay date for tank waste.


N/A = not applicable



7-3

7.3 ONSITE NON-CERCLA NON-TANK LOW-LEVEL WASTE AND MIXED

LOW-LEVEL WASTE

Table 7-3 and Table 7-4 include inventory estimates for onsite non-CERCLA non-tank LLW and

MLLW as reported in the TC&WM EIS. Onsite non-CERCLA non-tank LLW and MLLW

includes the following onsite generators:



T Plant complex


WRAP


Pacific Northwest National Laboratory (PNNL)


Canister Storage Building, and


Facility).


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Table 7-3. Onsite Non-CERCLA Non-Tank Low-Level Waste and Mixed Low-Level Waste Radioactive Constituents

of Potential Concern Inventory1.

129I 137Cs 14C 3H 233U, 234U, 235U, 238U 237Np 239Pu, 240Pu 90Sr 99Tc

Curies

CH- and RH-LLW 9.98E-05 1.36E+03 8.17E-01 2.68E+03 2.24E-01 4.38E-05 4.22E+00 1.75E+03 7.95E-01

CH- and RH-MLLW 1.22E-03 1.35E+03 6.88E-03 8.28E+02 5.12E-01 7.33E-03 3.81E+00 1.73E+03 4.17E-01

Total2 1.32E-03 2.71E+03 8.24E-01 3.51E+03 7.36E-01 7.37E-03 8.03E+00 3.48E+03 1.21E+00

Total3 1.32E-03 8.56E+02 8.19E-01 2.11E+02 7.36E-01 7.37E-03 8.03E+00 1.04E+03 1.21E+00

1 Table D-84 from Appendix D of DOE/EIS-0391, “Final Tank Closure and Waste Management Environmental Impact Statement for the Hanford Site, Richland,

Washington.” 2 Radionuclides assumed decayed to January 1, 2001 consistent with decay date for tank waste.


CERCLA = Comprehensive Environmental Response, Compensation, and Liability Act of 1980 MLLW = Mixed Low-Level Waste

CH = Contact Handled LLW = Low-Level Waste RH = Remote-Handled



7-5


Waste Chemical Constituents of Potential Concern Inventory1.

Contact Handled- and Remote-Handled-Mixed Low-Level Waste (Kilograms)

Acetonitrile 3.91E+00

Arsenic (As) 6.70E+00

Benzene 1.02 E+00

Boron (B) 3.66 E+00

Butanol (N-butyl Alcohol) 1.39E-03

Cadmium (Cd) 4.95E+01

Chromium (Cr) 1.80E+02

Fluorine (F) 2.74E+02

Lead (Pb) 2.58E+04

Manganese (Mn) 4.76E+01

Mercury (Hg) 8.99E+01

Molybdenum (Mo) 9.39E-05

Nickel (Ni) 1.97 E+00

Nitrate (NO3) 2.97E+03

Polychlorinated Biphenyls 2.50E+01

Silver (Ag) 7.80E+01

Strontium (Sr) 3.13 E+00

Total Uranium (U) 9.48E-01

2,4,6-Trichlorophenol Not reported

Adapted from Table D-85 from Appendix D of DOE/EIS-0391, “Final Tank Closure and Waste Management Environmental

Impact Statement for the Hanford Site, Richland, Washington.”

Note: Inventories predicated on assumption that onsite Non-Comprehensive Environmental Response, Compensation, and

Liability Act of 1980 (CERCLA) non-tank Low-Level Waste and Mixed Low-Level Waste would be generated through 2035

and Integrated Disposal Facility would begin to receive waste in 2009 which is approximately the same operational duration

assumed for the Integrated Disposal Facility Performance Assessment.



7-6




8-1

8.0 INTEGRATED DISPOSAL FACILITY WASTE VOLUME METHODOLOGY

As a result of treating tank waste at WTP, the IDF will receive significant volumes of MLLW

and LLW as follows:

ILAW glass

LAW melters

WTP SSW

ETF-generated SSW.

Additionally, the IDF will receive:

Secondary Waste Management LLW and MLLW

FFTF Decommissioning waste

Onsite non-CERCLA non-tank LLW and MLLW.

Disposal volume estimates for ILAW glass waste were developed using the model results from

HTWOS based on results from Run Case 7 and the sensitivity cases (Run Cases 8B, 9, 10A, and

10B). The data necessary for a mechanistic model of ILAW volumes as a function of feed rates

and glass compositions allow reasonably detailed estimates for ILAW glass volumes.

For other waste streams, a similar level of information is not available; in some cases, the

process engineering is in an early stage of design and review. For these other waste streams,

one approach for estimating waste stream volumes would be to divide the total waste stream

inventory by a waste acceptance criterion or by an assumed waste loading. For the purposes of

analysis, this data package provides reasonable estimates for as-generated waste stream volumes

using the most currently available information from Table B-1 of

24590-WTP-RPT-ENS-10-010.

As-generated volume estimates for secondary waste management LLW and MLLW and onsite

non-CERCLA non-tank LLW and MLLW were based on forecasted estimates from

HNF-EP-0918, Rev. 24, “Solid Waste Integrated Forecast Technical (SWIFT) Report FY2014 -

FY2050, 2014.0.”

8.1 IMMOBILIZED LOW-ACTIVITY WASTE GLASS WASTE VOLUME

ESTIMATES

The ILAW glass packages are stainless steel cylinders that have outside container dimensions of

approximately 2.3 meters in height and 1.22 meters in diameter (7.5 feet in height and 4.0 feet in

diameter). The density of ILAW glass is assumed to be 2.58 metric tons per cubic meter with

each package containing 5.51 metric tons of glass (TC&WM EIS, Appendix E; RPP-17152,

Rev. 9, “Hanford Tank Waste Operations Simulator (HTWOS) Version 7.7 Model Design

Document”).



8-2

Release modeling for ILAW waste forms requires information related to the geometry, number,

and surface area of the waste containers. Table 8-1 includes volume and container estimates for

ILAW glass which are based on HTWOS results for each run case.

Table 8-1. Volume Estimates for Immobilized Low-Activity Waste Glass.

Run Case Number of ILAW Containers ILAW Glass Volumeg (m3)

7 130,584a 278,797

8B 131,610b 280,987

9 127,530c 272,277

10A 108,128d 230,853

10B 107,309e 229,105

TC&WM EIS 92,250f 213,000f

a SVF-4092, “IDF PA Case 7 - Current Information Case - Mass Balance, MMR-50049.”

b SVF-4094, “IDF PA Case 8B - Tc_Tc-99 Removal from LAW Vitrification Off-Gas Condensate - Mass Balance,

MMR-50051.” c SVF-4095, “IDF PA Case 9 - Removal of LAWPS - Mass Balance, MMR-50052.”

d SVF-4096, “IDF PA Case 10A - Single Pass Tc_Tc-99 Retention in ILAW Glass of 32% - Mass Balance, MMR-50053.”

e SVF-4097, “IDF PA Case 10B - Recycle Pass Tc_Tc-99 Retention in ILAW Glass of 68% - Mass Balance, MMR-50054.”

f DOE/EIS-0391, Table 4-85, “Final Tank Closure and Waste Management Environmental Impact Statement for the Hanford

Site, Richland, Washington” (TC&WM EIS). g Estimated based on Immobilized Low-Activity Waste container internal volume of 2.135 m3 per RPP-17152, Rev. 12,

“Hanford Tank Waste Operations Simulator (HTWOS) Version 8.1 Model Design Document.”

ILAW = Immobilized Low-Activity Waste

Overall, the run cases show an increase in the number of ILAW containers of approximately 15

to 30% when compared to the TC&WM EIS Case. These increases are due to changes that

occurred in the HTWOS model assumptions between Revision 3 of ORP-11242 that applies to

TC&WM EIS Case and Revision 7 of ORP-11242 that applies to the 2017 IDF PA run cases.

The revised assumptions for caustic leaching contribute to the increase in the number of ILAW

containers as well as two additional factors which include a revised LAW glass model and a new

liquid/solid equilibrium model. The revised LAW glass model used in HTWOS is similar to the

model used by WTP in their dynamic modeling. Also, some of the wash and leach factors were

replaced with a thermodynamic calculation for selected waste species which more accurately

forecast liquid/solid distribution as waste is mixed, concentrated, and/or treated over the course

of the WTP mission (RPP-17152, Rev. 12).



8-3

8.2 AS-GENERATED WASTE TREATMENT AND IMMOBILIZATION PLANT

SECONDARY SOLID WASTE VOLUME ESTIMATES

The as-generated WTP SSW volume estimates associated with the operation of the WTP facility

are based on waste generation information provided in Table B-1 of

24590-WTP-RPT-ENS-10-010.

From this information, the LLW and MLLW volumes were estimated as the sum of each

individual waste stream volume computed as follows:

V(MLLW, LLW) = Waste Volume (m3) × Mission Duration (years)

Disposal Interval (years)

where the mission duration of WTP operations was assumed to be 28 years (2019 through 2047)

per Revision 6 of ORP-11242.

Table B-1 of 24590-WTP-RPT-ENS-10-010 further classifies WTP SSW as debris or non-debris

waste. Debris waste is expected to be volume-reduced and/or macroencapsulated, whereas

non-debris is expected to be particulate-sized material that would be stabilized into a

cementitious waste form prior to disposal at the IDF. Available treatment and disposal options

are conditional based on the contaminant levels in the original materials. Particulate-sized

material designed to capture mercury and halides pose a treatment and disposal challenge that

must be addressed. The 2017 IDF PA can be used as a tool to evaluate different treatment and

disposal options for these waste streams. Table 8-2 provides the waste type designation of debris

versus non-debris waste along with the as-generated volumes for each WTP SSW stream

identified in Section 6.1.1 which includes:

HEPA filters

IX resin

LAW and HLW carbon adsorber beds

HLW silver mordenite

Other debris.

As discussed in Section 6.1.1, inventory partitioning information from HTWOS and the 10-010

and 10-009 reports suggest that disproportionate amounts of key contaminants report to these

waste streams. Therefore, volume estimates associated with these waste streams over the course

of the WTP mission are needed to determine if concentration levels of these key contaminants

are important to the overall performance of the IDF system.

Waste volumes associated with the operation of LAWPS were considered and compared to those

generated by WTP operating without LAWPS. As a result, SSW volumes from the LAWPS

facility were found to be enveloped by the WTP SSW volumes; therefore, for analysis purposes,

separate volume estimates for LAWPS SSW are not being considered in the 2017 IDF PA.



8-4

Table 8-2. Volume Estimates for Waste Treatment and Immobilization Plant Secondary

Solid Waste Streams.

Waste Treatment and

Immobilization Plant Secondary

Solid Waste Debris Stream1

Number of Containers

Generated Over

Mission Duration Container Type2,3

Total Mission

Volume4,5

(m3)

HEPA filters (1-year) 2,045 Drums 524

HEPA filters (5-year) 5,085 Drums 1,308

Other debris 60,309 Drums/assorted boxes 26,546

Debris total 67,439 N/A 28,378

Waste Treatment and

Immobilization Plant Secondary

Solid Waste Non-Debris Stream

Number of Containers

Generated Over

Mission Duration Container Type2,3

Total Mission

Volume4 (m3)

Ion Exchange resin 112 High Integrity Containers 686

LAW and HLW carbon beds 4,424 Drums 1,137

HLW silver mordenite absorbent 403 Drums 104

Non-Debris total 4,939 N/A 1,927

1 Excludes waste volumes for:

LAW melters and ETF-generated secondary solid waste since those volumes are estimated separately

HLW melters which are assumed to be placed in interim onsite storage until final dispositions decisions are made and

implemented. 2 Drums are 0.257 m3.

3 High Integrity Containers are 6.125 m3 (6 ft × 6 ft × 6 ft).

4 Volumes based on outside container dimension reported in Appendix B of 24590-WTP-RPT-ENS-10-010, “WTP Estimate

of Secondary Radioactive Solid Waste Generation.” 5 Waste Treatment and Immobilization Plant mission duration = 28 years.

ETF = Effluent Treatment Facility HLW = High-Level Waste N/A = not applicable

HEPA = High-Efficiency Particulate Air LAW = Low-Activity Waste

A number of standard pre-approved waste disposal packages are in use at the Hanford Site.

When practical, waste is packaged in these standard pre-approved packages. Some waste

streams (for example, spent melters) present unique circumstances that dictate nonstandard

packaging. The following types of waste packages are expected to be used by the WTP project

for transporting and/or disposing of WTP SSW (24590-WTP-PL-PENG-14-0006, “Secondary

Wastes Compliance Plan”):

Lab packs

16-gallon drums

30-gallon drums

55-gallon drums

85-gallon drums

2 ft × 2 ft × 6 ft Type A box




8-5


8 ft × 8 ft × 20 ft IP1 conex or sea-land type box

LAW locally shielded melter (see Section 9.3)

High Integrity Containers (6 ft × 6 ft × 6 ft)

Other containers.

8.3 BACKGROUND-INDUSTRY STANDARDS FOR WASTE TREATMENT

The current plan for disposing of waste at IDF involves the use of an offsite treatment facility

experienced in treating Hanford waste streams for onsite disposal. Standard practices for treating

waste include stabilization, macroencapsulation as well as some degree of volume reduction via

repackaging and compaction depending on the type and category of waste received. The general

strategy for treating both LLW and MLLW provides a basis for developing WTP SSW treatment

and disposal consideration and assumptions.

8.3.1 Low-Level Waste

Category 1 and Category 3 LLW debris volumes are reduced in order to decrease the volume of

waste shipped for disposal and ensure optimal waste form for disposal. Volume reduction is

accomplished by both thermal (Category 1 LLW) and non-thermal processes (Category 3 LLW).

The thermal process utilizes Bulk Process Units that are large, refractory lined ovens. The Bulk

Process Units operate at 1,800 degrees Fahrenheit. This temperature is sufficient to ignite and

burn all combustible material and results in typical volume reductions of 30:1 to 100:1. This

type of treatment is generally reserved for combustible Category 1 LLW and would not be

performed if residual ash and debris was expected to exceed Category 3 limits.

The non-thermal processes include size reduction, compaction, and decontamination for free

release. The treatment facility uses a super-compactor to compact the waste drums which are

then overpacked into either an overpack drum or box prior to disposal. The typical volume

reductions range from 2:1 to 10:1 depending on debris type. Cylindrical components with metal

frames (e.g., HEPA filters) or thin, hollow shells would tend to be compacted more than

components with less internal void volume.

8.3.2 Mixed Low-Level Waste

Category 1 and Category 3 MLLW are treated via non-thermal processes including

macroencapsulation (debris) and stabilization (non-debris). The facility’s macroencapsulation

process is specifically designed to treat hazardous debris and radioactive lead solids in

compliance with Title 40, Code of Federal Regulations, Part 268.45, “Treatment Standards for

Hazardous Debris” (40 CFR 268.45) and Title 40, Code of Federal Regulations, Part 268.40,

“Applicability of Treatment” (40 CFR 268.40) in preparation for disposal at a mixed waste

Subtitle C landfill.



8-6

The macroencapsulation process involves sorting, segregating, and super-compacting mixed

low-level debris wastes, thus resulting in a volume reduction ratio of approximately 2.5:1. Like

LLW, volume reduction of MLLW debris is dependent on the structure of the debris. The

facility estimates that it can often achieve volume reduction ratios of 2.5:1 by shearing and

repackaging components prior to macroencapsulation. Stabilization is used for mixed low-level

non-debris wastes and is accomplished by introducing reagents into the waste stream producing a

homogeneous, stabilized, final product.

Stabilization has been defined as the Best Demonstrated Available Technology for treating a

wide range of RCRA listed, characteristic waste streams. Analysis of resulting waste forms will

meet the concentration-based (performance) standards or the stabilization treatment technology

requirements to meet RCRA LDR.

8.4 WASTE TREATMENT AND IMMOBILIZATION PLANT SECONDARY SOLID

WASTE TREATMENT AND DISPOSAL CONSIDERATIONS AND

ASSUMPTIONS

The strategy assumed for treating and disposing of secondary waste streams generated from

WTP operations is generally based on industry standards for treating LLW and MLLW (debris

and non-debris) as discussed in Sections 8.3.1 and 8.3.2.

Debris streams will undergo some type of volume reduction via compaction/supercompaction,

sorting, and repackaging at an offsite treatment facility prior to disposal at the IDF. As a result,

these waste streams may become somewhat more concentrated at the time of disposal; however,

the treatment facility will not generate waste streams that exceed the waste acceptance criteria

limits at the IDF (i.e., greater-than-Category 3).

For non-debris waste streams, the disposal volumes will increase slightly based on repackaging

and treatment methods that include the addition of dry materials for stabilization purposes.

Treatment and packaging of all WTP SSW will occur at an offsite commercial vendor facility

and the resulting waste packages will be transported to the IDF for disposal. For analysis

purposes, additional assumptions associated with the treatment, packaging, and disposal volumes

for individual waste streams are described below.

For IX resins, LAW and HLW carbon adsorber beds, and HLW silver mordenite absorbent these

assumptions are:

IX resins would be non-debris MLLW which would be dewatered at WTP before being

transported in High Integrity Containers offsite for treatment. At the treatment facility,

the resin would be repackaged into carbon steel 55-gallon drums with a stabilization

grout for RCRA metals and Category 3 radioactive waste containment using a

Hanford-approved grout formulation meeting regulatory criteria.



8-7

Carbon adsorber beds and HLW silver mordenite absorbent would also be non-debris

MLLW, which from a treatment perspective, contain potentially problematic amounts of

Hg and 129I. The conservative recommendation for disposition of this waste is to dispose

of it at IDF. The beds would be transported to a local offsite treatment facility where

they would be repackaged into carbon steel 55-gallon drums with a stabilization grout for

RCRA metals and Category 3 radioactive waste containment using a Hanford-approved

grout formulation that meets regulatory criteria.

Based on literature reviews and consultation with waste treatment experts, the

stabilization of non-debris waste streams would result in volume increases ranging from

1.5 to 3.0 times the as-generated waste volumes (“Performance Testing of Grout-Based

Waste Forms for the Solidification of Anion Exchange Resins” [ORNL 1990];

WHC-EP-0375, “Engineering Study for the Treatment of Spent Ion Exchange Resin

Resulting from Nuclear Process Applications; PNNL-19681, “Tc-99 Ion Exchange Resin

Testing”). Using a multiplier on the lower end of this range would result in an increased

concentration of contaminants within each disposal package and would be a conservative

estimate of the source term in the 2017 IDF PA. For analysis purposes, a 1.5 multiplier

should be applied to all non-debris waste stream volumes. This assumption is reasonably

consistent with the cementitious waste-to-grout volume ratios discussed in Section 8.4 for

ETF-generated SSW (0.693 L waste/ L grout).

For HEPA filters, these assumptions are:

HEPA filters would be MLLW debris. All HEPA filters will be received at an offsite

treatment facility in carbon steel 55-gallon drums where they will be compacted into

“pucks” at an approximate compaction ratio of 10:1.

Up to 25 pucks could be placed into 4 ft × 4 ft × 6 ft disposal boxes and

macroencapsulated with grout to meet LDR requirements for RCRA constituents8. This

macroencapsulation process would meet Category 3 stabilization requirements, which

exceed Category 1 requirements.

The projected volume of debris waste, excluding HEPA filters, is approximately

28,000 m3. The WTP secondary waste forecast suggests that more than a third of the

debris is compactible debris. Approximately 25% of the projected waste is compactible,

Category 1 LLW that is expected to have a higher compaction ratio than Category 3

MLLW, but also have lower concentrations prior to compaction.

For other debris wastes (excludes HEPA filters), these assumptions are:

Assuming a compaction ratio of 10:1 for the compactible, Category 1 LLW debris and a

compaction ratio of 2.5:1 for all other debris waste, it is recommended that an average

8 The work authorization process implemented at the treatment facility determines the allowable number of pucks

based on waste stream characterization information provided by the waste generator at the time of shipment to the

treatment facility. Disposal box limits (after drums are compacted into pucks at a compaction ratio of

approximately 10:1) are closely managed such that Category 3 limits are not exceeded.



8-8

compaction ratio for the remaining non-HEPA filter debris waste be 5:1

(0.25×10+0.75×2.55).

Note that these reduction factors for debris waste are based on 5 years of actual WRPS SSW

treatment data provided by experts in the waste treatment industry (e-mail from R. Grondin to

R. L. Keller “waste streams slated for offsite” [Grondin, R., 2016-02-18]).

8.5 LOW-ACTIVITY WASTE MELTER VOLUME ESTIMATES

The LAW melters from WTP operations would be disposed of at IDF as MLLW. As such, LAW

melters would require treatment to meet LDR requirements under RCRA.

Up to 18 LAW melters would be required to be void filled with grout, macroencapsulated, or

packaged within in an overpack prior to disposal (RPP-RPT-58204).

According to Tank Closure Alternative 2B from the TC&WM EIS, an estimate of 31 LAW

melters would be disposed of at the IDF. This represents the maximum quantity of LAW melters

that would result from WTP operations and is driven by the expanded ILAW glass operations

and vitrification treatment processes. Additionally, the TC&WM EIS reports 7.620 m3 of

residual glass waste could remain in each melter at the time of disposal. This volume is based on

the glass tank surface dimension of the LAW melter and the maximum glass pool operating

depth (24590-LAW-MOD-LMP-00002, “Data Sheet Low Active Waste Melter 2”).

Two possible disposal volume estimates for LAW melters are presented in Table 8-3 based on

the melter’s physical dimensions and the melter’s overpack dimensions (as assumed in the

TC&WM EIS).

Table 8-3. Volume Estimates for Low-Activity Waste Melters and Residual Glass

Volume.

Waste Type

Number of Melters

Generated over the

WTP Mission

Length

(m)

Width

(m)

Height

(m)

Melter

Volume

(m3)

Mission

Melter

Volume

(m3)

Residual Glass

Waste Volume

over the WTP

Mission (m3)

LAW Melters1 18 6.65 9.32 4.83 299 5,382 137

LAW Melters

Overpack2 31 6.79 9.38 4.86 310 9,610 236

1 RPP-RPT-58204, “Spent/Failed Low-Activity Waste Melter Transport System Evaluation Report,” Table 2-1.

2 DOE/EIS-0391, “Final Tank Closure and Waste Management Environmental Impact Statement for the Hanford Site,

Richland, Washington,” Appendix E.

LAW = Low-Activity Waste WTP = Waste Treatment and Immobilization Plant

Consistent with the TC&WM EIS analysis, HLW melters are assumed to be placed in interim

onsite storage until final dispositions decisions are made and implemented.



8-9

8.6 EFFLUENT TREATMENT FACILITY-GENERATED SECONDARY SOLID

WASTE

Secondary liquid wastes resulting from WTP operations, 242-A evaporator campaigns, and

CH-TRU tank retrievals will be treated at the ETF. Liquid waste received by the ETF is

processed via two treatment trains. The main treatment train is designed to remove radioactive

and hazardous constituents using filtration, ultraviolet oxidation, degasification, reverse osmosis,

and ion-exchange systems. Clean water meeting discharge permit requirements is discharged to

the SALDS location north of 200 West Area. The secondary treatment train processes

wastewater rejected from the main treatment train. The secondary train concentrates the waste to

a brine and then dries the waste using a thin-film drying process. The current plan for the liquid

MLLW resulting from WTP operations, 242-A evaporator, and CH-TRU retrieval is to stabilize

the concentrate (brine) that results from the secondary treatment train at the ETF and send the

resulting cementitious waste form to the IDF for disposal.

Plans for solidifying secondary liquid waste from WTP, condensate from the 242-A evaporator,

and liquid waste resulting from retrieval of CH-TRU tanks at the ETF in preparation for disposal

at the IDF are currently being evaluated. The information needed to estimate this waste volume

based on these plans is still being developed and will not be available until a later time.

Therefore, ETF-generated SSW volumes going to the IDF were based on the liquid volumes

provided by HTWOS (Table 8-4) and the following simplifying assumptions:

The waste form will be a cementitious waste form (i.e., Cast Stone grout) with a monolith

density of 1.8 kg/L and a water-to-dry mix ratio of 0.6 (Tables 2-1 and D-4 of

PNNL-22747/SRNL-STI-2013-00465, “Supplemental Immobilization of Hanford

Low-Activity Waste: Cast Stone Screening Tests”). The water-to-dry mix ratio of 0.6

was selected because of improved flow characteristics and increased waste loading.

The liquid feed streams from WTP will be converted to a brine at ETF prior to being

blended with the dry mix materials. The volume ratios of brine to feed are based on

Table 1 of HNF-58821, “Effluent Treatment Facility Mass Balance Calculation for

DFLAW Mission”). The brine-to-feed volume ratio for the Direct Feed Low Activity

Waste (DFLAW) Effluent Management Facility (EMF)/CS source in Table 1 is

applicable to the WTP and TRU process streams. The brine-to-feed volume ratio for the

242-A evaporator process condensate is reported separately. As shown, the brine-to-feed

volume ratios determined from Table 1 are:

o 242-A process condensate = 0.00232 (gallons brine/gallons feed)

o DFLAW EMF/CS = 0.00926 (gallons brine/gallons feed).

For DFLAW EMF/CS, there are 838 grams of water per liter of waste (page 540 of

HNF-58821).

Using the water-to-dry mix ratio (0.6), the monolith density (1.8 kg/L), the water

concentration from the DFLAW EMF/CS (838 g/L), and the density of the DFLAW

EMF/CS stream (1.2 kg/L), the ratio of waste to grout was approximated as



8-10

0.693 L waste/ L grout. This ratio was then used to estimate the ETF-generated SSW

volume going to the IDF for each HTWOS run case.

Table 8-4 shows the liquid waste volumes generated during the entire WTP mission that will be

sent to LERF and processed at ETF. The resulting estimated solid waste volumes would be

disposed at the IDF. Several HTWOS run cases are provided to illustrate the potential range of

grouted waste volumes to be disposed at the IDF. Although these estimates are based on the

most current information, they will be updated as new information becomes available.

Table 8-4. Effluent Treatment Facility-Generated Secondary Solid Waste Disposal

Volume Estimates.

Run Case

WTP-

TO-

LERF

(gallons)

242-A-TO-LERF

(gallons)

TRU-

PROCESSING-

TO-LERF

(gallons)

Total

Volume

to LERF

(gallons)

Cementitious

Waste Volume

going to the

IDF (m3)*

Case 7: Current

Information Case 3.52E+08 7.07E+07 4.42E+06 4.27E+08 1.89E+04

Case 8B: Tc-99 Removal

from LAW Vitrification

Off-Gas Condensate 3.36E+08 8.00E+07 4.42E+06 4.21E+08 1.82E+04

Case 9: Removal of

LAWPS 3.15E+08 9.23E+07 4.42E+06 4.12E+08 1.73E+04

Case 10A: Single Pass

Tc-99 Retention in ILAW

Glass of 32% 3.36E+08 6.91E+07 4.42E+06 4.09E+08 1.81E+04

Case 10B: Recycle Tc-99

Retention in ILAW Glass

of 68% 3.30E+08 6.15E+07 4.42E+06 3.96E+08 1.77E+04

* Volumes approximated following steps 1-3:

1. Converting each waste stream volume to its associated brine volume (= waste volume × brine-to-feed ratio)

2. Converting brine volume from gallons to liters, then dividing by the approximated waste-to-grout ratio

(0.693 L waste/ L grout)

3. Converting grouted waste volume from liters to m3.

IDF = Integrated Disposal Facility LERF = Liquid Effluent Retention Facility

ILAW = Immobilized Low-Activity Waste TRU = transuranic

LAW = Low-Activity Waste WTP = Waste Treatment and Immobilization Plant

LAWPS = Low-Activity Waste Pretreatment System



8-11

8.7 SECONDARY WASTE MANAGEMENT LOW-LEVEL WASTE AND MIXED

LOW-LEVEL WASTE VOLUME ESTIMATES

Table 8-5 includes volume estimates for secondary waste solids from the operation of the

following facilities:

Tank farms (workers’ personal protective equipment, tools, and other contaminated

materials)

LLBG 218-W-5, trenches 31 and 34

WRAP

T Plant complex.

Table 8-5. As-Generated Secondary Waste Management Waste Volume Estimates.

Waste Type Total Volume (m3) Volume Fraction

Low-Level Waste 1,742 18%

Mixed Low-Level Waste 7,747 82%

Total 9,489 100%

Per HNF-EP-0918, Rev. 24, “Solid Waste Integrated Forecast Technical (SWIFT) Report FY2014 - FY2050,

2014.0.”

Operations activities assumed to be 2019 through 2050, which is the duration for which the Integrated Disposal

Facility is planning to receive waste.

8.8 FAST FLUX TEST FACILITY DECOMMISSIONING WASTE DISPOSAL

VOLUME ESTIMATE

The volume estimate reported in Table 8-6 for FFTF decommissioning waste is based on the

disposal volume used in the TC&WM EIS as reported in release to vadose zone input file for

FFTF Alternative 2.

Table 8-6. Fast Flux Test Facility Decommissioning Disposal Waste Volume Estimate.

Waste Stream Total Disposal Volume (m3)

Fast Flux Test Facility Decommissioning Alternative 2 1,030



8-12

8.9 AS-GENERATED ONSITE NON-CERCLA NON-TANK LOW-LEVEL WASTE

AND MIXED LOW-LEVEL WASTE VOLUME ESTIMATES

Table 8-7 includes volume estimates for solid secondary waste from the following sources:





Pacific Northwest National Laboratory


Canister Storage Building, and


Facility).

Table 8-7. Onsite Non-CERCLA Non-Tank Low-Level Waste and

Mixed Low-Level Waste As-Generated Volume Estimates.

Waste Type Volume (m3)

Low-Level Waste 442

Mixed Low-Level Waste 181

Total 623

Per HNF-EP-0918, Rev. 24, “Solid Waste Integrated Forecast Technical (SWIFT) Report FY2014 - FY2050, 2014.0.”

Operations activities assumed to be 2019 through 2050, which is the duration for which the Integrated Disposal

Facility is planning to receive waste.




9-1

9.0 SUMMARY OF RESULTS

Tables 9-1 and 9-2 provide a summary of the inventory estimates derived from HTWOS. These

summary tables report inventories for a select set of radionuclide and chemical constituents that

includes 129I, 137Cs, 14C, 233U, 234U, 235U, 238U, 237Np, 239Pu, 240Pu, 3H, 90Sr, 99Tc, Cr, Hg, NO3-,

Pb, and U. Comprehensive inventory tables for all BBI constituents with radionuclides decayed

to 2008 and 2051 are included in Appendix A.

Tables 9-3 and 9-4 provide a summary of the inventory estimates from Appendix D of the

TC&WM EIS for Tank Closure Alternative 2A (Alternative 2B with 99Tc removal) to facilitate

comparisons to Tables 9-1 and 9-2. These summary tables report inventories for a select set of

radionuclide and chemical constituents that includes 129I, 137Cs, 14C, 233U, 234U, 235U, 238U, 237Np, 239Pu, 240Pu, 3H, 90Sr, 99Tc, Cr, Hg, NO3

-, Pb, and U.

Since groundwater impacts associated with disposal of MLLW and LLW at the IDF are highly

dependent on the distributions of mobile radionuclides such as 99Tc and 129I present in glass and

grout waste forms, this summary focuses primarily on the inventory and waste form distributions

of these two constituents.

9.1 INTEGRATED DISPOSAL FACILITY WASTE FORMS BASED ON HANFORD

TANK WASTE OPERATIONS SIMULATOR RUN CASES

Five HTWOS model run cases were developed to explore ranges of inventory estimates for

waste streams going to the IDF that result from processing tank waste through the WTP Facility

using different process flowsheet assumptions. Since the capture of 99Tc and 129I in the ILAW

glass is an important consideration when evaluating the performance of the IDF system, each

case was designed to evaluate a range of distributions of these contaminants in glass and grout

waste forms.

Cases 10A and 10B represent sensitivity cases that were contrived to place lower fractions of 99Tc and 129I in ILAW glass, and higher fractions into the LAW liquid off-gas stream which

would be disposed of at the IDF as ETF-generated SSW. As such, the upper limits of loading 99Tc and 129I in a cementitious waste form can be tested against waste form performance

characteristics. Since the inventory allocation is based on a single-pass WTP flowsheet

configuration and the current WTP flowsheet includes recycle, these are unlikely cases from an

operational perspective.

These cases serve as a starting point for gaining an understanding of the IDF disposal system

considering all the uncertainties associated with each IDF waste form. These uncertainties

include tank waste composition and inventory uncertainties, WTP process and operational

uncertainties, and HTWOS model/partitioning uncertainties. Other run cases are expected to

evolve based on the knowledge gained from model runs of these initial cases and maturity of the

WTP process flowsheet. Development of the WTP process flowsheet is in flux pending

technical decisions regulatory discussions.



9-2

The key features of each HTWOS run case are described in the context of the TC&WM EIS

Case (represented by Tank Closure Alternative 2A).

Case 7 – Similar to the TC&WM EIS case except that initially the WTP Pretreatment

Facility recycle configuration is routed from LAW Vitrification back to tank farms, and

the BBI was updated (2014 vs. 2002). A fixed retention of 129I in ILAW glass of 20% is

not included; rather, it is consistent with the TC&WM EIS for the 129I retention factor of

20% for each pass, but exceeds the TC&WM EIS retention factor as a result of recycle.

This case has similar retention of 99Tc in ILAW glass as the TC&WM EIS (~98%). This

run case is the starting point for subsequent HTWOS run cases (Run Cases 8B, 9, 10A,

and 10B).

Case 8B – From an TC&WM EIS perspective, this case is the same as Case 7, except that

a 99Tc removal unit operation has been added after the SBS-WESP process to remove 99Tc at an efficiency of 99% from the LAW liquid off-gas stream prior to being recycled

to backend evaporator in the Pretreatment Facility. This removed 99Tc inventory would

not be disposed of at the IDF and represents the lower range of 99Tc inventory in both

glass and grout waste forms that would be disposed of at the IDF.

Case 9 – Similar to the TC&WM EIS case, the WTP Pretreatment Facility recycle

configuration is routed from LAW Vitrification back to the Pretreatment Facility.

Case 10A – Similar to TC&WM EIS case, 129I retention in ILAW glass is 20%; however,

the recycle efficiency is much lower than the TC&WM EIS such that 32% of 99Tc is

retained in ILAW glass (modeled in HTWOS using a single pass). Case 10A is a

contrived case. Partitioning of the constituents between other phases uses the inherent

split fractions applied in the HTWOS model without consideration of whether the product

stream could be treated using the recommended treatment method or could ultimately be

disposed in the IDF. This case exercises the process modeling tool that is available to

generate an inventory case that could be used to test the limits of the facility to meet

established performance criteria.

Case 10B – Similar to TC&WM EIS case, 129I retention in ILAW glass is 20%; however,

the recycle efficiency is somewhat lower than the TC&WM EIS such that 68% of 99Tc is

retained in ILAW glass (modeled in HTWOS using a single pass). Case 10B is a

contrived case. Partitioning of the constituents between other phases uses the inherent

split fractions applied in the HTWOS model without consideration of whether the product

stream could be treated using the recommended treatment method or could ultimately be

disposed in the IDF. This case exercises the process modeling tool that is available to

generate an inventory case that could be used to test the limits of the facility to meet

established performance criteria.



9-3/9-4

Table 9-1. Summary of Radionuclide Constituents Inventories and Waste Form Distributions Resulting from Hanford Tank Waste Operations Simulator Run Cases (November 2014 Best-Basis Inventory with

radionuclides decayed to January 2008).

1 SVF-4092, “IDF PA Case 7 - Current Information Case - Mass Balance, MMR-50049.”

2 SVF-4094, “IDF PA Case 8B - Tc_Tc-99 Removal from LAW Vitrification Off-Gas Condensate - Mass Balance, MMR-50051.”

3 SVF-4095, “IDF PA Case 9 - Removal of LAWPS - Mass Balance, MMR-50052.”

4 SVF-4096, “IDF PA Case 10A - Single Pass Tc_Tc-99 Retention in ILAW Glass of 32% - Mass Balance, MMR-50053.”

5 SVF-4097, “IDF PA Case 10B - Recycle Pass Tc_Tc-99 Retention in ILAW Glass of 68% - Mass Balance, MMR-50054.”

6 As a result of removing Tc-99 from the LAW off-gas stream, 16,500 Ci of Tc-99 accumulate over the course of the Waste Treatment and Immobilization Plant mission. These Ci would likely be processed in High-Level Waste and would not end up at the IDF.

BBI = Best-Basis Inventory ETF = Effluent Treatment Facility HTWOS = Hanford Tank Waste Operations Simulator IDF = Integrated Disposal Facility ILAW = Immobilized Low-Activity Waste LAW = Low-Activity Waste NA = not applicable

HTWOS Run Case Constituent 129-I 137-Cs 14-C 233-U 234-U 235-U 237-Np 238-U 239-Pu 240-Pu 3-H 90-Sr 99-Tc

HTWOS BBI Inventory 2.94E+01 3.90E+07 5.51E+02 6.82E+02 2.37E+02 9.71E+00 1.15E+02 2.15E+02 4.94E+04 1.08E+04 2.82E+03 4.76E+07 2.65E+04

Units Ci %BBI %IDF Ci %BBI %IDF Ci %BBI %IDF Ci %BBI %IDF Ci %BBI %IDF Ci %BBI %IDF Ci %BBI %IDF Ci %BBI %IDF Ci %BBI %IDF Ci %BBI %IDF Ci %BBI %IDF Ci %BBI %IDF Ci %BBI %IDF

Case 71 ILAW Glass 1.65E+01 56.21% 57.51% 1.05E+04 0.03% 72.41% 0.00E+00 0.00% 0.00% 9.94E+00 1.46% 99.87% 3.01E+00 1.27% 99.76% 1.22E-01 1.25% 99.76% 1.73E+01 15.03% 99.88% 2.70E+00 1.26% 99.76% 4.48E+03 9.06% 99.87% 9.45E+02 8.75% 99.87% 0.00E+00 0.00% 0.00% 2.57E+05 0.54% 99.83% 2.64E+04 99.58% 99.78%

LAW Melters 2.38E-02 0.08% 0.08% 1.36E+01 0.00% 0.09% 0.00E+00 0.00% 0.00% 1.29E-02 0.00% 0.13% 4.25E-03 0.00% 0.14% 1.73E-04 0.00% 0.14% 2.09E-02 0.02% 0.12% 3.85E-03 0.00% 0.14% 5.94E+00 0.01% 0.13% 1.25E+00 0.01% 0.13% 0.00E+00 0.00% 0.00% 3.21E+02 0.00% 0.12% 3.75E+01 0.14% 0.14%

ETF-Generated Secondary Solid Waste 6.42E-02 0.22% 0.22% 6.70E-01 0.00% 0.00% 3.52E+00 0.64% 100.00% 1.78E-05 0.00% 0.00% 2.89E-03 0.00% 0.10% 1.21E-04 0.00% 0.10% 7.08E-05 0.00% 0.00% 2.78E-03 0.00% 0.10% 6.17E-03 0.00% 0.00% 1.28E-03 0.00% 0.00% 2.34E+00 0.08% 100.00% 9.85E+01 0.00% 0.04% 2.29E-01 0.00% 0.00%

Secondary Solid Waste 1.21E+01 41.23% 42.18% 4.00E+03 0.01% 27.49% 0.00E+00 0.00% 0.00% 1.65E-06 0.00% 0.00% 5.16E-07 0.00% 0.00% 2.10E-08 0.00% 0.00% 2.02E-06 0.00% 0.00% 4.65E-07 0.00% 0.00% 2.02E-02 0.00% 0.00% 1.98E-02 0.00% 0.00% 0.00E+00 0.00% 0.00% 2.63E+01 0.00% 0.01% 1.99E+01 0.08% 0.08%

IDF Total 2.87E+01 97.74% 100.00% 1.45E+04 0.04% 100.00% 3.52E+00 0.64% 100.00% 9.95E+00 1.46% 100.00% 3.02E+00 1.27% 100.00% 1.22E-01 1.26% 100.00% 1.73E+01 15.05% 100.00% 2.71E+00 1.26% 100.00% 4.48E+03 9.07% 100.00% 9.46E+02 8.76% 100.00% 2.34E+00 0.08% 100.00% 2.58E+05 0.54% 100.00% 2.64E+04 99.80% 100.00%

Case 8B2 ILAW Glass 1.65E+01 56.25% 57.54% 1.40E+04 0.04% 78.07% 0.00E+00 0.00% 0.00% 1.02E+01 1.50% 99.91% 2.98E+00 1.26% 99.79% 1.21E-01 1.24% 99.79% 1.72E+01 14.95% 99.89% 2.66E+00 1.24% 99.79% 4.51E+03 9.14% 99.88% 9.64E+02 8.92% 99.87% 0.00E+00 0.00% 0.00% 1.83E+05 0.39% 99.85% 9.97E+03 37.62% 99.75%




Accumulator6 NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA 1.65E+04 62.09% NA


Case 93 ILAW Glass 1.65E+01 56.26% 57.54% 9.30E+03 0.02% 75.75% 0.00E+00 0.00% 0.00% 1.17E+01 1.71% 99.87% 2.99E+00 1.26% 99.77% 1.19E-01 1.23% 99.77% 1.72E+01 14.98% 99.86% 2.65E+00 1.23% 99.76% 5.07E+03 10.25% 99.88% 1.06E+03 9.80% 99.88% 0.00E+00 0.00% 0.00% 1.38E+05 0.29% 99.77% 2.64E+04 99.63% 99.83%





Case 10A4 ILAW Glass 5.71E+00 19.43% 19.80% 7.89E+03 0.02% 55.55% 0.00E+00 0.00% 0.00% 9.08E+00 1.33% 98.96% 3.07E+00 1.29% 98.87% 1.25E-01 1.29% 98.87% 1.72E+01 14.91% 98.96% 2.77E+00 1.29% 98.87% 4.37E+03 8.85% 98.96% 9.34E+02 8.65% 98.96% 0.00E+00 0.00% 0.00% 2.15E+05 0.45% 98.95% 8.46E+03 31.91% 31.95%


ETF-Generated Secondary Solid Waste 1.88E+01 63.80% 65.00% 2.53E+03 0.01% 17.81% 2.53E+00 0.46% 100.00% 8.25E-02 0.01% 0.90% 3.08E-02 0.01% 0.99% 1.26E-03 0.01% 0.99% 1.56E-01 0.14% 0.90% 2.79E-02 0.01% 1.00% 3.97E+01 0.08% 0.90% 8.49E+00 0.08% 0.90% 2.76E+00 0.10% 100.00% 2.02E+03 0.00% 0.93% 1.80E+04 67.88% 67.96%



Case 10B5 ILAW Glass 5.72E+00 19.44% 19.80% 7.77E+03 0.02% 55.76% 0.00E+00 0.00% 0.00% 8.35E+00 1.22% 98.94% 2.92E+00 1.23% 98.85% 1.20E-01 1.23% 98.85% 1.70E+01 14.81% 98.98% 2.66E+00 1.24% 98.85% 4.52E+03 9.15% 98.97% 9.62E+02 8.90% 98.97% 0.00E+00 0.00% 0.00% 1.74E+05 0.36% 98.90% 1.80E+04 67.82% 67.89%


ETF-Generated Secondary Solid Waste 1.88E+01 63.83% 64.99% 2.49E+03 0.01% 17.87% 2.40E+00 0.44% 100.00% 7.59E-02 0.01% 0.90% 2.95E-02 0.01% 1.00% 1.21E-03 0.01% 1.00% 1.55E-01 0.13% 0.90% 2.69E-02 0.01% 1.00% 4.11E+01 0.08% 0.90% 8.74E+00 0.08% 0.90% 3.92E+00 0.14% 100.00% 1.68E+03 0.00% 0.96% 8.47E+03 31.94% 31.98%




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Table 9-2. Summary of Chemical Constituent Inventories and Waste Form Distributions Resulting from Hanford Tank

Waste Operations Simulator Runs.

1 SVF-4092, “IDF PA Case 7 - Current Information Case - Mass Balance, MMR-50049.” 2 SVF-4094, “IDF PA Case 8B - Tc_Tc-99 Removal from LAW Vitrification Off-Gas Condensate - Mass Balance, MMR-50051.”

3 SVF-4095, “IDF PA Case 9 - Removal of LAWPS - Mass Balance, MMR-50052.”

4 SVF-4096, “IDF PA Case 10A - Single Pass Tc_Tc-99 Retention in ILAW Glass of 32% - Mass Balance, MMR-50053.”

5 SVF-4097, “IDF PA Case 10B - Recycle Pass Tc_Tc-99 Retention in ILAW Glass of 68% - Mass Balance, MMR-50054.”

BBI = Best-Basis Inventory HTWOS = Hanford Tank Waste Operations Simulator ILAW = Immobilized Low-Activity Waste NA = not applicable

ETF = Effluent Treatment Facility IDF = Integrated Disposal Facility LAW = Low-Activity Waste

HTWOS Run Case Constituent Cr Hg NO3- Pb U

HTWOS BBI Inventory 5.91E+05 1.99E+03 5.60E+07 8.20E+04 6.45E+05

Units Kg %BBI %IDF Kg %BBI %IDF Kg %BBI %IDF Kg %BBI %IDF Kg %BBI %IDF

Case 71 ILAW Glass 4.90E+05 82.94% 99.70% 0.00E+00 0.00% 0.00% 0.00E+00 0.00% 0.00% 7.01E+04 85.44% 88.72% 8.10E+03 1.26% 99.76%

LAW Melters 7.44E+02 0.13% 0.15% 0.00E+00 0.00% 0.00% 0.00E+00 0.00% 0.00% 7.59E+01 0.09% 0.10% 1.15E+01 0.00% 0.14%

ETF-Generated Secondary Solid Waste 4.30E+00 0.00% 0.00% 9.58E+02 48.16% 48.89% 1.64E+05 0.29% 100.00% 8.82E+03 10.76% 11.17% 8.32E+00 0.00% 0.10%

Secondary Solid Waste 7.43E+02 0.13% 0.15% 1.00E+03 50.35% 51.11% 0.00E+00 0.00% 0.00% 1.19E+01 0.01% 0.02% 1.39E-03 0.00% 0.00%

IDF Total 4.92E+05 83.19% 100.00% 1.96E+03 98.51% 100.00% 1.64E+05 0.29% 100.00% 7.90E+04 96.30% 100.00% 8.12E+03 1.26% 100.00%

Case 8B2 ILAW Glass 4.93E+05 83.40% 99.73% 0.00E+00 0.00% 0.00% 0.00E+00 0.00% 0.00% 6.92E+04 84.42% 87.75% 7.99E+03 1.24% 99.79%




Accumulator NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA

IDF Total 4.94E+05 83.62% 100.00% 1.96E+03 98.50% 100.00% 1.64E+05 0.29% 100.00% 7.89E+04 96.20% 100.00% 8.01E+03 1.24% 100.00%

Case 93 ILAW Glass 4.95E+05 83.69% 99.72% 0.00E+00 0.00% 0.00% 0.00E+00 0.00% 0.00% 7.02E+04 85.61% 88.96% 7.94E+03 1.23% 99.76%




IDF Total 4.96E+05 83.93% 100.00% 1.96E+03 98.45% 100.00% 1.64E+05 0.29% 100.00% 7.89E+04 96.24% 100.00% 7.96E+03 1.23% 100.00%

Case 10A4 ILAW Glass 4.60E+05 77.77% 92.77% 0.00E+00 0.00% 0.00% 0.00E+00 0.00% 0.00% 7.08E+04 86.39% 89.77% 8.30E+03 1.29% 98.87%




IDF Total 4.95E+05 83.82% 100.00% 1.96E+03 98.68% 100.00% 2.22E+06 3.97% 100.00% 7.89E+04 96.24% 100.00% 8.39E+03 1.30% 100.00%

Case 10B5 ILAW Glass 4.62E+05 78.10% 92.78% 0.00E+00 0.00% 0.00% 0.00E+00 0.00% 0.00% 7.17E+04 87.43% 90.77% 7.97E+03 1.24% 98.85%




IDF Total 4.98E+05 84.18% 100.00% 1.98E+03 99.37% 100.00% 2.23E+06 3.98% 100.00% 7.90E+04 96.32% 100.00% 8.06E+03 1.25% 100.00%


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Table 9-3. Tank Closure Alternative 2A Radioactive Constituents of Potential Concern Balance.

Table 7-3. Tank Closure Alternative 2A Radioactive Constituents of Potential Concern Balance

Iodine-129 Cesium-137 Carbon-14 Hydrogen-3

(Tritium) Uranium-233,

-234, -235, -238 Neptunium-237 Plutonium -239, -240 Strontium-90 Technetium-99

Best-Basis Inventory

Curies

% of BBI Curies

% of BBI Curies

% of BBI Curies

% of BBI Curies

% of BBI Curies

% of BBI Curies

% of BBI Curies

% of BBI Curies

% of BBI

BBIa 4.82×101

N/A 4.58×107

N/A 3.12×103

N/A 1.21×104

N/A 9.38×102

N/A 1.41×102

N/A 8.14×104

N/A 5.05×107

N/A 2.97×104

N/A

Tank Closure Waste Inventory

Tank residual wasteb 4.82×10-1

1.0 4.58×105

1.0 3.12×101

1.0 1.21×102

1.0 9.38 1.0 1.41 1.0 8.14×102

1.0 5.05×105

1.0 2.97×102

1.0

IHLW glassc 6.99×10-3

0.0 4.49×107

97.9 0 0.0 0 0.0 8.73×102

93.1 1.40×102

99.0 8.06×104

99.0 4.93×107

97.6 2.47×102

0.8

ILAW glass and retired LAW melters

ETF-generated solid

secondary wasted

9.56 19.8 4.45×105

1.0 0 0.0 0 0.0 5.47×101

5.8 8.35×10-3

0.0 1.45 0.0 2.30×103

0.0 2.88×104

96.9

3.36×10

1 69.7 4.59×10

-1 0.0 8.51 0.3 0 0.0 4.03×10

-2 0.0 5.11×10

-20.0 6.90×10

-4 0.0 6.42 0.0 8.63×10

1 0.3

Solid secondary wastee 4.65 9.7 1.95×105

0.4 0 0.0 0 0.0 3.64 0.4 2.83×10-1

0.2 1.98×102

0.2 7.76×105

1.5 4.31×102

1.5

Totalf 4.83×101 100.2 4.60×107 100.2 3.97×101 1.3 1.21×102 1.0 9.41×102 100.3 1.41×102 100.2 8.16×104 100.2 5.06×107 100.1 2.99×104 100.5

O ther Inventory

Solid and liquid secondary

waste from cesium and strontium capsules

Cesium and strontium

capsulesg

Air Emissions

0 N/A 1.99×105

N/A 0 N/A 0 N/A 0 N/A 0 N/A 0 N/A 3.16×105

N/A 0 N/A

0 N/A 4.59×10

7 N/A 0 N/A 0 N/A 0 N/A 0 N/A 0 N/A 1.98×10

7 N/A 0 N/A

Treatment air emissionsh 4.78×101

N/A 4.69×104

N/A 3.10×103

N/A 1.20×104

N/A 4.65×10-1

N/A NR N/A 4.04×101

N/A 3.55×104

N/A 1.47×101

N/A

a Source of BBI data is Inventory and Source Term Data Package, DOE-ORP-2003-02, Rev. 0 (DOE 2003a). b Represents 99.0 percent retrieval. For analysis purposes, waste inventories from tank waste retrieval leaks and ancillary equipment were assumed to be treated in the Waste Treatment Plant. c

To be stored on site until disposition decisions are made and implemented. This inventory would include the retired HLW melters. d Includes secondary liquids that would be sent to the ETF and treated; solids would be disposed of in an Integrated Disposal Facility. Excludes liquid secondary waste from the processing of cesium and

strontium capsules, which would be reported separately. e Includes solid low-level radioactive waste and mixed low-level radioactive waste streams that would be generated by the waste treatment operations. Such waste streams would include debris waste,

melter consumables, failed process components, analytical laboratory waste, spent resins, spent carbon adsorbent, high-efficiency particulate air filters, and other process-related waste. f Totals may exceed 100 percent due to conservative estimates or rounded numbers. BBI percentages were rounded to the nearest tenth. Carbon-14 and hydrogen-3 (tritium) may not total 100 percent; a

portion of each would be released to the offgas streams and stack, and a portion (ETF-generated liquid) would be disposed of in the State-Approved Land Disposal Site. g To be treated in the Waste Treatment Plant, resulting in glass waste, which would be stored on site until disposition decisions are made and implemented. h Includes air emissions from all waste treatment processes, including those from treatment of the cesium and strontium capsules. For analysis purposes, both iodine-129 capture and air emission releases

were assumed. Key: %=percent; BBI=Best-Basis Inventory; ETF=Effluent Treatment Facility; HLW=high-level radioactive waste; IHLW=immobilized high-level radioactive waste; ILAW=immobilized low-activity

waste; LAW=low-activity waste; N/A=not applicable; NR=not reported.

Source: SAIC 2011.


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Table 9-4. Tank Closure Alternative 2A Chemical Constituents of Potential Concern Balance.

Table 7-4. Tank Closure Alternative 2A Chemical Constituents of Potential Concern Balance

Chromium Mercury Nitrate Lead Total Uranium Acetonitrile Benzene Butanol PCBs 2,4,6-TCP

Kg

Best-Basis Inventory

% of

BBI Kg

% of

BBI Kg

% of

BBI Kg

% of

BBI Kg

% of

BBI Kg

% of

BBI Kg

% of

BBI Kg

% of

BBI Kg

% of

BBI Kg

% of

BBI

BBIa 5.98×105

N/A 1.83×103

N/A 7.08×107

N/A 8.41×104

N/A 5.97×105

N/A 2.95×104

N/A 2.40 N/A 3.45×106

N/A 1.68×103

N/A 1.11 N/A

Tank Closure Waste Inventory

Tank residual wasteb

5.98×103 1.0 1.83×101 1.0 7.08×105 1.0 8.41×102 1.0 5.97×103 1.0 2.95×102 1.0 2.40×10-2 1.0 3.45×104 1.0 1.68×101 1.0 1.11×10-2 1.0

IHLW glassc 1.36×105 22.7 0 0.0 0 0.0 7.45×104 88.6 5.52×105 92.5 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0

ILAW glass and retired LAW melters

ETF- generated

solid secondary

wasted

Solid

secondary

wastee

4.56×105

76.2 0 0.0 0 0.0 8.88×103

10.6 3.74×104

6.3 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0

4.43×101 0.0 5.55 0.3 9.01×106 12.7 4.58 0.0 4.00×101 0.0 NR N/A NR N/A NR N/A NR N/A NR N/A

1.94×103 0.3 1.76×103 96.4 0 0.0 2.47×102 0.3 2.32×103 0.4 NR N/A NR N/A NR N/A NR N/A NR N/A

Totalf 6.00×105 100.3 1.78×103 97.7 9.72×106 13.7 8.45×104 100.5 5.98×105 100.2 2.95×102 1.0 2.40×10-2 1.0 3.45×104 1.0 1.68×101 1.0 1.11×10-2 1.0

O ther Inventoryg

T reatment air

emissionsh

NR N/A 1.81×103 N/A NR N/A NR N/A NR N/A NR N/A 7.40×102 N/A NR N/A NR N/A NR N/A

a Source of BBI data is Inventory and Source Term Data Package, DOE-ORP-2003-02, Rev. 0 (DOE 2003a). b Represents 99.0 percent retrieval. For analysis purposes, waste inventories from tank waste retrieval leaks and ancillary equipment were assumed to be treated in the Waste Treatment Plant. c

Includes retired HLW melter inventory. IHLW glass would be stored on site until disposition decisions are made and implemented. d Includes secondary liquids that would be sent to the ETF and treated; solids would be disposed of in an Integrated Disposal Facility. e Includes solid low-level radioactive waste and mixed low-level radioactive waste streams that would be generated by the waste treatment operations. Such waste streams would include deb ris waste,

melter consumables, failed process components, analytical laboratory waste, spent resins, spent carbon adsorbent, high -efficiency particulate air filters, and other process-related waste. Excludes contaminated liquid effluent waste streams that would be treated at the ETF.

f Totals may exceed 100 percent due to conservative estimates or rounded numbers. BBI percentages were rounded to the nearest tenth. The organic chemicals (acetonitrile, benzene, butanol, PCBs,

and 2,4,6-TCP) may not total 100 percent because they would be destroyed during the thermal treatment processes. Nitrate may not total 10 0 percent because it would be volatilized and released through the facility stack.

g No chemical constituents of potential concern have been reported in the cesium and strontium capsule secondary-waste streams. h Includes air emissions from all waste treatment processes, including those from treatment of the cesium and strontium capsules. For analysis purposes, both mercury capture and air emission releases

were assumed. Note: To convert kilograms to pounds, multiply by 2.2046.

Key: %=percent; BBI=Best-Basis Inventory; butanol=n-butyl alcohol; ETF=Effluent Treatment Facility; HLW=high-level radioactive waste; IHLW=immobilized high-level radioactive waste; ILAW=immobilized low-activity waste; Kg=kilograms; LAW=low-activity waste; N/A=not applicable; NR=not reported; PCB=polychlorinated biphenyl; TCP=trichlorophenol.

Source: SAIC 2011.



9-8

This selection of HTWOS run cases was designed to demonstrate the effects that slightly

different process flowsheet assumptions have on the distribution of 99Tc and 129I in the glass

versus non-glass waste forms. Some notable patterns observed include:

99Tc and 129I variations in glass waste form

Recovery of 99Tc from SBS-WESP liquid off-gas stream has significant influence on the

amount going to glass

Effect of single-pass/low and medium efficiency retention

Glass retention

Effect of LAWPS.

Overall this inventory data package maintains mass balance. Note that the inventories shown

address only the portion that is disposed of at the IDF. For each run case, the remainder

(e.g., HLW) will be disposed of offsite at a geologic repository.

9.1.1 Iodine-129 Variations (Figure 9-1 and Figure 9-2)

The HTWOS runs show that depending upon the run case, the 129I content in ILAW glass can

vary significantly from 20% to 56%. The higher retentions shown in Cases 7, 8B, and 9

demonstrate the efficiencies of recycle back to pretreatment versus Cases 10A and 10B which

are modeled in HTWOS using single-pass configuration to achieve 20% retention of 129I

retention in ILAW glass (similar to the TC&WM EIS case).

Comparing Case 7 (WTP with initial recycle from LAW Vitrification back to tank farms) to

Case 9 (WTP with recycle from LAW Vitrification to WTP Pretreatment) shows some very

slight difference, but overall these recycle configurations have no effect on the 129I retention in

ILAW glass.

Cases 10A and 10B show a significant amount of 129I going to ETF-generated SSW (~64%)

demonstrating the effects of HTWOS partitioning using a single-pass configuration versus

recycle (Case 7, 8B, and 9). Although the retention of 129I in ILAW glass was fixed at 20%,

most of the remainder ends up in ETF-generated SSW and about 15% is reported to WTP SSW.

The converse of this is demonstrated for the recycle cases 7, 8B, and 9, where about 56% of the 129I ends up in ILAW glass, and most of the remainder (~41%) ends up in WTP SSW, not

ETF-generated SSW. This is a result of the manner in which HTWOS treats the off-gas waste

streams under recycle conditions. Basically, the inventory that does not end up in the glass

accumulates in the carbon absorber beds and HLW silver mordenite media which is disposed of

as SSW.


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Figure 9-1. Iodine-129 Distributions in Integrated Disposal Facility Waste Forms.

EIS = Environmental Impact Statement IDF = Integrated Disposal Facility SSW = Secondary Solid Waste

ETF = Effluent Treatment Facility ILAW = Immobilized Low-Activity Waste WTP = Waste Treatment and Immobilization Plant

0.00%

10.00%

20.00%

30.00%

40.00%

50.00%

60.00%

70.00%

80.00%

90.00%

100.00%

Case7

Case8B

Case9

Case10A

Case10B

EIS Case7

Case8B

Case9

Case10A

Case10B

EIS Case7

Case8B

Case9

Case10A

Case10B

EIS

ILAW glass ETF Generated Secondary SolidWaste

WTP SSW

I-129 Distributions in IDF Waste Forms


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Figure 9-2. Iodine-129 Inventory in Integrated Disposal Facility Waste Forms.



0.00E+00

5.00E+00

1.00E+01

1.50E+01

2.00E+01

2.50E+01

3.00E+01

3.50E+01

Case7

Case8B

Case9

Case10A

Case10B

EIS Case7

Case8B

Case9

Case10A

Case10B

EIS Case7

Case8B

Case9

Case10A

Case10B

EIS

ILAW Glass ETF Generated Secondary Solid Waste WTP SSW

Cu

rie

s

I-129 Inventory in IDF Waste Forms



9-11

Similar to the ILAW glass results, the ETF-generated SSW and WTP SSW results show that

recycling from LAW Vitrification to tank farms or to WTP Pretreatment has no effect on the

distribution of 129I in glass versus grout and that these distributions are mainly based on the

effects of recycle and glass retention fractions implemented in HTWOS (e.g., 20%, 56% with

recycle).

9.1.2 Technetium-99 Variations (Figure 9-3 and Figure 9-4)

The HTWOS runs show variations in the 99Tc retention in ILAW glass ranging from 32% to

99%.

Case 7 (with LAWPS) and Case 9 (without LAWPS) show negligible differences. Both cases

include recycle; therefore, operation of LAWPS versus WTP Pretreatment has no effect on 99Tc

retention in ILAW glass. Case 8B shows a significant decrease of 99Tc retention in ILAW glass

compared to Case 7 and Case 9 by approximately 61%. Case 8B removes 99% of the 99Tc from

the off-gas liquid recycle stream; therefore, Case 8B (although it includes recycle) is effectively

the same as a single-pass configuration.

Cases 10A and 10B use a single-pass configuration with 99Tc retention in glass fixed at 32% and

68% respectively. Cases 10A and 10B were contrived scenarios developed to test the limits of

non-glass waste form concentrations that IDF could receive and still meet the performance

criteria for the facility. These cases are included to help establish waste acceptance criteria for

specific waste forms. Previous studies at VSL indicate a 32% 99Tc retention in ILAW glass for

single pass and 68% retention with recycle when averaged across all LAW feed types tested.

These HTWOS runs demonstrate a modest range of 99Tc retention in glass, which may not be as

high as what was analyzed in the TC&WM EIS or in previous HTWOS flowsheet runs (>90%).

As shown by the ETF-generated secondary solids and secondary solids results for single pass

(Cases 10A and 10B), most of the 99Tc that does not end up in ILAW glass ends up in

ETF-generated secondary solids with only a small amount (<1%) going to SSW.

Although Case 8B (99% removal of 99Tc from LAW off-gas) effectively represents a single pass,

HTWOS separates and accounts for this 99Tc in the “Accumulator”; therefore, it is not present in

ETF-generated SSW or SSW. The 99Tc inventory in the “Accumulator” at the end of the WTP

mission is 16,500 Ci. For analysis purposes, this inventory will not be disposed of at the IDF

and will likely be disposed of offsite or in IHLW glass.


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Figure 9-3. Technetium-99 Distributions in Integrated Disposal Facility Waste Forms.



0.00%

10.00%

20.00%

30.00%

40.00%

50.00%

60.00%

70.00%

80.00%

90.00%

100.00%

Case 7 Case8B

Case 9 Case10A

Case10B

EIS Case 7 Case8B

Case 9 Case10A

Case10B

EIS Case 7 Case8B

Case 9 Case10A

Case10B

EIS

ILAW glass ETF Generated Secondary Solid Waste WTP SSW

Tc-99 Distributions in IDF Waste Forms


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Figure 9-4. Technetium-99 Inventory in Integrated Disposal Facility Waste Forms.



0.00E+00

5.00E+03

1.00E+04

1.50E+04

2.00E+04

2.50E+04

3.00E+04

Case7

Case8B

Case9

Case10A

Case10B

EIS Case7

Case8B

Case9

Case10A

Case10B

EIS Case7

Case8B

Case9

Case10A

Case10B

EIS

ILAW Glass ETF Generated Secondary Solid Waste WTP SSW

Cu

rie

sTc-99 Inventory in IDF Waste Forms



9-14




10-1

10.0 DATA QUALITY ASSURANCE FOR THE INTEGRATED DISPOSAL FACILITY

INVENTORY DATA PACKAGE

The source data used to develop inventories for the 2017 IDF PA will come directly from

existing sources such as the Best-Basis Inventory (TWINS), HTWOS, and the TC&WM EIS,

and through literature reviews of project-approved technical documents.

No new data will be developed and no calculations will be performed. Each of these sources has

already established compliance with ASME NQA-1-2008, “Quality Assurance Requirements for

Nuclear Facility Applications (QA)” and NQA-1a-2009, “Quality Assurance Requirements for

Nuclear Facility Applications Addenda,” Quality Assurance requirements as presented in

Table 10-1 below.

Table 10-1. Source Data Quality Assurance.

Data Source Required Quality Assurance

Best-Basis Inventory RPP-RPT-58911, Rev. 11, “Tank Waste Information Network System

Quality Assurance Plan.”

Hanford Tank Waste Operations

Simulator

RPP-50816, Rev. 1, “Software Management Plan for Grade D Custom

Developed Hanford Tank Waste Operations Simulator (HTWOS).”

Tank Closure and Waste

Management Environmental Impact

Statement (TC&WM EIS)

A Quality Assurance review by the U.S. Department of Energy (DOE)

was completed in November 2008 to ensure that the TC&WM EIS

Quality Assurance Plan was compliant with:

DOE O 414.C, Quality Assurance

DOE O 451.1B, National Environmental Policy Act Compliance Program

“NEPA Contracting Reform Guidance” (DOE 1996)

DOE P 226.1, Department of Energy Oversight Policy

DOE P 251.1A, Departmental Directives Program Policy

For the IDF PA Inventory Data Package, spreadsheets will be extracted from TWINS and

HTWOS for data presentation purposes. According to TFC-ENG-DESIGN-C-32, “Utility

Calculation Software Management,” spreadsheets exempted from the requirements of this

procedure include:

Spreadsheets that do not perform calculations or do not perform technical data

manipulation

Spreadsheets that are used for administrative type activities (such as table generation)

Spreadsheets that are generated as a result of a query or download from TWINS or other

system registered on the Hanford Information Network System, provided that nothing is

done to modify the data.



10-2

The data quality assurance for all data used as the basis of the inventory estimates in the IDF PA

Inventory Data Package will be consistent with quality assurance requirements presented in

Table 10-1 and with the spreadsheet exemptions included in TFC-ENG-DESIGN-C-32.



11-1

11.0 REFERENCES

40 CFR 268.40, “Applicability of Treatment,” Code of Federal Regulations, as amended.

40 CFR 268.45, “Treatment Standards for Hazardous Debris,” Code of Federal Regulations, as

amended.

62 FR 8693, 1997, “Record of Decision for the Tank Waste Remediation System, Hanford Site,

Richland, WA,” Federal Register, Vol. 62, pp. 8693–8704 (February 26).

78 FR 75913, 2013, “Record of Decision: Final Tank Closure and Waste Management

Environmental Impact Statement for the Hanford Site, Richland, Washington,” Federal

Register, Vol. 78, pp. 75913–75919 (December 13).

24590-LAW-MOD-LMP-00002, “Data Sheet Low Activity Waste Melter 2,” Rev. 1, River

Protection Project Waste Treatment Plant, Richland, Washington.

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NEPA Policy and Assistance, Washington, D.C.



11-2

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11-3

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11-4

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11-5

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11-6

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6C,” Rev. 10, Columbia Energy & Environmental Services, Inc., Richland, Washington.



A-i

HTWOS INVENTORY TABLES



A-ii




A-1

APPENDIX A

HTWOS INVENTORY TABLES

This Appendix includes complete Best-Basis Inventory (BBI) tables for Hanford Tank Waste

Operations Simulator (HTWOS) Run Cases 7, 8B, 9, 10A, and 10B for each Integrated Disposal

Facility (IDF) waste stream (with all radionuclides decayed to 2008 and to 2051, which is the

assumed facility closure date for the IDF). Specifically, these IDF waste streams include:

Immobilized Low-Activity Waste glass

Low-Activity Waste melters

Effluent Treatment Facility -generated secondary solid waste

Secondary solid waste.

Note: HTWOS reports certain radionuclides (i.e., 227Ac, 228Ra, 93mNb) as negative inventory

values, which is due to the fact that HTWOS has four second-order decay chains; parent to

daughter to granddaughter isotope (see Section 2.7.7 in RPP-17152, Rev. 12, “Hanford Tank

Waste Operations Simulator (HTWOS) Version 8.1 Model Design Document”).

During the pretreatment and treatment processing, HTWOS partitions

parent/daughter/granddaughter radionuclides differently because the different isotopes have

different chemical behaviors. This results in a different ratio of parent to daughter to

granddaughter in each process stream than was observed in the original waste stream. When

HTWOS back-decays the radionuclides in each stream to the reference decay date, the different

amounts of parent/daughter/granddaughter isotopes can back-decay to different values (including

negative values) because they are present in different ratios.

None of the radionuclides reporting negative inventories are considered major risk drivers and

therefore will have a negligible impact on the overall performance of the IDF.

This Appendix also includes complete BBI tables for HTWOS Run Cases 7, 8B, 9, 10A, and

10B including more detailed Waste Treatment and Immobilization Plant (WTP) Secondary Solid

waste streams (with all radionuclides decayed to 2008 and to 2051, which is the assumed facility

closure date for the IDF). Each detailed waste stream inventory is reported in curies for

radionuclides and kilograms for chemicals. Specifically, these detailed WTP Secondary Solid

Waste streams include:

High Effluent Particulate Air (HEPA) filters

Ion Exchange resin

Low-Activity Waste and High-Level Waste carbon adsorber beds

High-Level Waste silver mordenite absorbent

Other debris.

The partition fractions used to distribute inventories to these more detailed waste streams were

based on simple ratios computed from information reported in Appendix C of

24590-WTP-RPT-ENS-10-010, “WTP Estimate of Secondary Radioactive Solid Waste



A-2

Generation” and from Tables 3-15 through 3-26 of 24590-WTP-RPT-ENS-10-009, “Secondary

Waste Estimates for WTP HVAC HEPA Filters.” If a BBI constituent was not reported in either

of these source documents, it was listed as NR (not reported) in Section 4 of Tables A-1 through

A-10. Specifically, the list of NR constituents include:

106-Ru 226-Ra 232-Th 243-Cm Cs PO4-3 Y

113m-Cd 227-Ac 232-U 244-Cm Mo SO2

125-Sb 228-Ra 242-Cm 90-Y NO2- SO3

137m-Ba 229-Th 242-Pu 93-Zr NO3- SO4-2

151-Sm 231-Pa 243-Am 93m-Nb OH- TOC

A comparison of this list to the constituents of potential concern analyzed in DOE/EIS-0391,

“Final Tank Closure and Waste Management Environmental Impact Statement for the Hanford

Site, Richland, Washington” shows that nitrate is the only constituent of potential concern that is

NR. All run cases in the 2017 IDF Performance Assessment analysis report zero inventory for

nitrate in WTP Secondary Solid Waste.

REFERENCES

24590-WTP-RPT-ENS-10-009, 2010, “Secondary Waste Estimates for WTP HVAC HEPA

Filters,” Rev. 0, River Protection Project Waste Treatment Plant, Richland, Washington.

24590-WTP-RPT-ENS-10-010, 2010, “WTP Estimate of Secondary Radioactive Solid Waste

Generation,” Rev. 0, River Protection Project Waste Treatment Plant, Richland,

Washington.

DOE/EIS-0391, 2012, “Final Tank Closure and Waste Management Environmental Impact

Statement for the Hanford Site, Richland, Washington,” U.S. Department of Energy,







A-3/A-4

Table A-1. Run Case 7 Radionuclides.

SVF-4092, IDF PA Case 7 - Current Information Case - Mass Balance, MMR-50049.xlsm

WASTE STREAM 106-Ru 113m-Cd 125-Sb 126-Sn 129-I 134-Cs 137-Cs 137m-Ba 14-C 151-Sm 152-Eu 154-Eu 155-Eu 226-Ra 227-Ac 228-Ra 229-Th 231-Pa 232-Th 232-U 233-U 234-U 235-U 236-U 237-Np 238-Pu 238-U 239-Pu 240-Pu 241-Am 241-Pu 242-Cm 242-Pu 243-Am 243-Cm 244-Cm 3-H 59-Ni 60-Co 63-Ni 79-Se 90-Sr 90-Y 93-Zr 93m-Nb 99-Tc

LAW Glass Subtotal (IDF) 1.19E+01 3.30E+03 4.03E+03 3.87E+02 1.62E+01 2.03E-01 1.04E+04 9.86E+03 0.00E+00 2.15E-01 8.50E-05 8.63E-04 1.10E-03 9.21E-03 1.41E+01 2.93E+02 4.13E-08 8.25E-08 9.40E-08 1.42E-01 9.87E+00 2.98E+00 1.21E-01 9.43E-02 1.71E+01 2.28E+02 2.68E+00 4.41E+03 9.29E+02 6.04E+03 7.32E+03 1.21E+02 7.25E-02 3.05E+00 1.33E+01 2.94E+02 0.00E+00 4.94E+01 1.78E-04 4.43E+03 1.40E+02 2.52E+05 2.52E+05 7.76E-04 5.54E-04 2.59E+04

LAW Spent Melter Subtotal (IDF) 1.27E-02 5.19E+00 4.36E+00 4.42E-01 2.33E-02 2.84E-04 1.35E+01 1.27E+01 0.00E+00 2.98E-04 1.18E-07 1.20E-06 1.53E-06 1.13E-05 2.04E-02 4.04E-01 5.75E-11 1.15E-10 1.31E-10 1.82E-04 1.28E-02 4.22E-03 1.71E-04 1.30E-04 2.07E-02 3.40E-01 3.82E-03 5.84E+00 1.23E+00 7.87E+00 9.69E+00 1.34E-01 9.92E-05 4.45E-03 1.57E-02 3.46E-01 0.00E+00 8.89E-02 2.48E-07 7.94E+00 1.79E-01 3.14E+02 3.14E+02 1.08E-06 7.70E-07 3.68E+01

ETF Solid Waste Form to IDF 6.59E-03 1.24E+01 6.87E+01 1.66E+00 6.28E-02 1.17E-05 6.65E-01 6.28E-01 3.52E+00 1.66E-05 4.44E-10 2.06E-07 8.28E-08 1.80E-04 6.32E-02 7.28E+00 3.69E-15 7.47E-11 3.11E-17 2.97E-07 1.76E-05 2.87E-03 1.20E-04 3.35E-05 7.01E-05 3.14E-04 2.75E-03 6.08E-03 1.26E-03 2.05E-02 9.60E-03 4.26E-01 3.36E-04 1.05E-05 4.89E-02 1.08E+00 2.34E+00 1.28E-01 8.56E-05 1.14E+01 2.85E+00 9.64E+01 9.64E+01 2.03E-07 5.65E-03 2.25E-01

Solid Waste Forms from Treatment Processes (IDF) 6.28E-05 7.98E-03 1.30E-02 1.91E-02 1.19E+01 8.26E-02 3.97E+03 3.74E+03 0.00E+00 2.64E-03 6.64E-07 4.04E-05 2.02E-05 3.50E-08 1.58E-06 1.11E-03 1.19E-09 3.97E-09 5.54E-09 2.27E-08 1.64E-06 5.12E-07 2.08E-08 1.56E-08 1.99E-06 1.10E-02 4.61E-07 1.98E-02 1.95E-02 1.04E-02 8.81E-04 3.94E-04 8.70E-09 7.60E-07 6.74E-04 1.10E-03 0.00E+00 4.16E-04 1.68E-05 3.72E-02 5.40E-03 2.57E+01 2.57E+01 2.68E-04 -1.03E-03 1.96E+01

Non-IDF Stream -2.14E-03 5.04E+02 1.51E+00 1.58E-01 5.98E-01 7.11E+02 3.87E+07 3.65E+07 8.24E+02 3.15E+06 7.91E+02 4.82E+04 2.41E+04 1.18E-05 -9.32E+00 -2.89E+02 1.42E+00 4.73E+00 6.61E+00 8.17E+00 6.37E+02 2.14E+02 8.75E+00 6.05E+00 9.02E+01 2.25E+03 1.94E+02 4.30E+04 9.10E+03 1.42E+05 7.15E+04 8.22E-02 6.78E-01 6.38E+01 5.04E-03 1.07E-01 2.81E+03 1.41E+03 3.71E+03 1.26E+05 4.51E-02 4.27E+07 4.27E+07 3.37E+03 2.85E+03 2.14E+01

BBI 1.20E+01 3.89E+03 4.13E+03 3.91E+02 2.94E+01 7.13E+02 3.90E+07 3.68E+07 5.51E+02 3.57E+06 9.07E+02 5.30E+04 2.55E+04 9.95E-03 4.14E+00 6.77E+00 1.48E+00 5.16E+00 6.77E+00 8.87E+00 6.82E+02 2.37E+02 9.71E+00 6.50E+00 1.15E+02 2.63E+03 2.15E+02 4.94E+04 1.08E+04 1.57E+05 8.38E+04 1.22E+02 8.26E-01 7.23E+01 1.35E+01 2.98E+02 2.82E+03 1.62E+03 4.10E+03 1.44E+05 1.44E+02 4.76E+07 4.76E+07 3.73E+03 3.17E+03 2.65E+04

HTWOS Feed 1.20E+01 3.89E+03 4.13E+03 3.91E+02 2.94E+01 7.13E+02 3.90E+07 3.68E+07 8.28E+02 3.57E+06 9.07E+02 5.30E+04 2.55E+04 9.95E-03 4.14E+00 6.77E+00 1.48E+00 5.16E+00 6.77E+00 8.87E+00 6.82E+02 2.37E+02 9.71E+00 6.50E+00 1.15E+02 2.64E+03 2.16E+02 5.14E+04 1.09E+04 1.57E+05 8.39E+04 1.22E+02 8.27E-01 7.23E+01 1.35E+01 2.98E+02 2.82E+03 1.62E+03 4.10E+03 1.44E+05 1.44E+02 4.76E+07 4.76E+07 3.73E+03 3.17E+03 2.65E+04

HTWOS Feed Adjusted Minus TF and TRU Accumulation 1.20E+01 3.83E+03 4.11E+03 3.90E+02 2.94E+01 7.13E+02 3.90E+07 3.68E+07 8.27E+02 3.27E+06 8.25E+02 4.95E+04 2.45E+04 9.43E-03 4.54E+00 9.40E+00 1.43E+00 4.83E+00 6.63E+00 8.39E+00 6.51E+02 2.19E+02 8.95E+00 6.20E+00 1.08E+02 2.51E+03 1.99E+02 4.82E+04 1.02E+04 1.50E+05 7.99E+04 1.21E+02 7.63E-01 6.79E+01 1.34E+01 2.96E+02 2.81E+03 1.48E+03 3.80E+03 1.33E+05 1.44E+02 4.40E+07 4.40E+07 3.49E+03 2.96E+03 2.65E+04

ACCUMULATION STREAM 106-Ru 113m-Cd 125-Sb 126-Sn 129-I 134-Cs 137-Cs 137m-Ba 14-C 151-Sm 152-Eu 154-Eu 155-Eu 226-Ra 227-Ac 228-Ra 229-Th 231-Pa 232-Th 232-U 233-U 234-U 235-U 236-U 237-Np 238-Pu 238-U 239-Pu 240-Pu 241-Am 241-Pu 242-Cm 242-Pu 243-Am 243-Cm 244-Cm 3-H 59-Ni 60-Co 63-Ni 79-Se 90-Sr 90-Y 93-Zr 93m-Nb 99-Tc

PT-Accumulation 1.50E-04 2.35E+00 2.92E-01 3.78E-01 5.46E-02 1.56E+00 3.02E+05 2.85E+05 2.43E-01 1.09E+05 3.10E+01 1.20E+03 3.71E+02 4.22E-06 -3.48E-01 -6.49E+00 1.12E-02 9.46E-02 1.86E-02 6.92E-02 4.31E+00 1.63E+00 6.70E-02 5.05E-02 1.01E+00 2.88E+01 1.47E+00 7.15E+02 1.58E+02 1.84E+03 9.67E+02 8.90E-02 1.08E-02 9.65E-01 2.24E-02 5.00E-01 1.49E+00 2.51E+01 7.89E+01 2.23E+03 6.59E-02 8.98E+05 8.98E+05 1.10E+02 9.77E+01 2.52E+01

TF-Accumulation 7.47E-06 6.61E+01 2.11E+01 1.96E+00 7.59E-02 2.37E-02 1.64E+04 1.54E+04 2.11E-01 3.04E+05 8.20E+01 3.53E+03 1.06E+03 5.20E-04 -3.99E-01 -2.64E+00 4.74E-02 3.26E-01 1.35E-01 4.80E-01 3.08E+01 1.77E+01 7.61E-01 3.01E-01 6.39E+00 1.22E+02 1.71E+01 3.19E+03 6.75E+02 6.67E+03 3.94E+03 8.66E-01 6.42E-02 4.35E+00 1.34E-01 2.43E+00 3.58E+00 1.37E+02 3.03E+02 1.17E+04 4.57E-02 3.63E+06 3.63E+06 2.47E+02 2.13E+02 8.03E+00

TRU-Accumulation 3.93E-14 5.50E-04 3.41E-06 6.30E-05 6.28E-06 1.86E-09 2.64E+00 2.50E+00 8.33E-04 1.13E+00 3.05E-05 1.77E-02 7.07E-03 7.63E-08 1.47E-06 4.74E-12 2.31E-10 4.67E-06 1.94E-12 6.29E-08 5.45E-09 7.26E-03 2.34E-04 7.01E-05 2.54E-05 2.82E-02 5.37E-03 2.23E+00 2.70E-01 3.27E-01 7.48E-01 5.56E-05 1.33E-05 3.19E-05 5.76E-07 1.22E-05 3.85E-03 1.44E-04 5.41E-04 1.94E-02 3.44E-05 3.34E+01 3.34E+01 1.89E-02 1.73E-02 1.18E-02

LAW Accumulation 2.55E-05 3.33E-01 5.27E-02 6.10E-02 6.17E-03 3.92E-06 1.23E+00 1.16E+00 2.44E-02 5.31E-246 2.12E-249 2.16E-248 2.78E-248 7.55E-07 2.76E-03 7.01E-02 1.02E-252 2.04E-252 2.33E-252 1.01E-05 6.35E-04 2.72E-04 1.11E-05 1.08E-05 5.75E-04 2.54E-02 2.38E-04 6.20E-01 1.37E-01 4.96E-01 8.75E-01 1.42E-02 9.43E-06 3.35E-04 3.69E-03 8.24E-02 4.70E-02 6.09E-03 4.99E-249 5.42E-01 1.18E-02 1.57E+01 1.57E+01 4.85E-254 3.50E-248 5.52E+00

HLW-Accumulation 3.14E-08 6.95E-03 1.65E-04 3.32E-05 1.30E-03 1.62E-02 3.04E+03 2.87E+03 2.77E-05 9.26E+03 2.67E+00 1.03E+02 3.16E+01 9.36E-10 -2.78E-02 -5.72E-01 9.32E-04 7.39E-03 1.55E-03 5.63E-03 3.50E-01 1.26E-01 5.23E-03 3.49E-03 8.25E-02 2.44E+00 1.16E-01 6.11E+01 1.35E+01 1.55E+02 8.16E+01 7.37E-06 9.16E-04 8.14E-02 1.03E-06 2.29E-05 7.87E-01 1.98E+00 6.66E+00 1.76E+02 1.41E-05 7.00E+04 7.00E+04 8.94E+00 7.48E+00 2.22E-04

SLAW-Accumulation 1.40E-04 1.14E+00 1.33E+00 1.00E-01 5.77E-01 8.69E-05 2.11E+01 1.99E+01 3.05E-02 3.08E-20 1.22E-23 1.24E-22 1.58E-22 1.48E-05 9.20E-03 4.48E+00 5.92E-27 1.18E-26 1.35E-26 3.02E-05 1.93E-03 7.24E-04 2.97E-05 2.37E-05 1.42E-03 4.58E-02 6.52E-04 9.63E-01 2.14E-01 1.30E+00 1.39E+00 2.31E-02 1.43E-05 8.63E-04 5.51E-03 1.23E-01 1.66E-01 1.59E-02 2.56E-23 1.39E+00 2.67E-01 6.02E+02 6.02E+02 8.21E-25 4.47E-22 4.43E+02

LAWPS-Accumulation 3.55E-07 4.82E-04 2.67E-04 1.64E-04 9.12E-06 9.33E-05 2.19E+01 2.07E+01 5.35E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.83E-09 7.10E-06 8.15E-05 0.00E+00 0.00E+00 0.00E+00 1.40E-08 9.57E-07 4.93E-07 2.09E-08 9.56E-09 4.42E-06 3.16E-06 4.69E-07 9.03E-05 1.73E-05 7.43E-04 1.01E-04 1.72E-05 1.09E-09 3.76E-07 2.55E-06 5.61E-05 5.11E-04 1.95E-07 0.00E+00 1.76E-05 5.13E-05 8.99E-02 8.99E-02 0.00E+00 0.00E+00 1.05E-02

ETF-Accumulation 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

LERF-Accumulation 2.22E-06 1.76E-01 4.60E-02 1.16E-02 1.41E-04 8.99E-10 1.90E-04 1.79E-04 9.47E-03 1.48E-29 3.93E-34 2.05E-31 8.17E-32 3.99E-07 1.23E-03 1.08E-01 3.09E-39 6.30E-35 2.60E-41 2.06E-09 1.28E-07 4.82E-08 1.99E-09 1.48E-09 4.80E-08 1.70E-06 4.38E-08 4.12E-05 9.08E-06 8.20E-05 5.61E-05 2.66E-03 1.91E-06 5.34E-08 6.19E-04 1.38E-02 2.14E+00 1.67E-03 4.99E-29 1.48E-01 6.47E-03 1.25E+00 1.25E+00 2.21E-31 6.14E-27 4.09E-04

Total Accumulation 3.26E-04 7.01E+01 2.28E+01 2.51E+00 7.15E-01 1.60E+00 3.21E+05 3.03E+05 5.20E-01 4.22E+05 1.16E+02 4.83E+03 1.46E+03 5.41E-04 -7.62E-01 -5.04E+00 5.95E-02 4.28E-01 1.55E-01 5.55E-01 3.55E+01 1.95E+01 8.33E-01 3.55E-01 7.48E+00 1.54E+02 1.87E+01 3.97E+03 8.47E+02 8.67E+03 4.99E+03 9.95E-01 7.59E-02 5.40E+00 1.66E-01 3.15E+00 8.22E+00 1.64E+02 3.89E+02 1.41E+04 3.97E-01 4.60E+06 4.60E+06 3.66E+02 3.18E+02 4.82E+02

Accumulation minus TF and TRU 3.18E-04 4.01E+00 1.72E+00 5.51E-01 6.39E-01 1.58E+00 3.05E+05 2.88E+05 3.08E-01 1.19E+05 3.37E+01 1.30E+03 4.03E+02 2.02E-05 -3.63E-01 -2.40E+00 1.21E-02 1.02E-01 2.02E-02 7.49E-02 4.67E+00 1.75E+00 7.23E-02 5.40E-02 1.09E+00 3.13E+01 1.59E+00 7.78E+02 1.72E+02 1.99E+03 1.05E+03 1.29E-01 1.17E-02 1.05E+00 3.22E-02 7.19E-01 4.63E+00 2.71E+01 8.56E+01 2.40E+03 3.51E-01 9.69E+05 9.69E+05 1.19E+02 1.05E+02 4.74E+02

ADJUSTED INVENTORY TO INCLUDE ACCUMULATION-Radionuclides decayed to 1/1/2008 106-Ru 113m-Cd 125-Sb 126-Sn 129-I 134-Cs 137-Cs 137m-Ba 14-C 151-Sm 152-Eu 154-Eu 155-Eu 226-Ra 227-Ac 228-Ra 229-Th 231-Pa 232-Th 232-U 233-U 234-U 235-U 236-U 237-Np 238-Pu 238-U 239-Pu 240-Pu 241-Am 241-Pu 242-Cm 242-Pu 243-Am 243-Cm 244-Cm 3-H 59-Ni 60-Co 63-Ni 79-Se 90-Sr 90-Y 93-Zr 93m-Nb 99-Tc






TOTAL 1.20E+01 3.83E+03 4.11E+03 3.90E+02 2.93E+01 7.13E+02 3.90E+07 3.68E+07 8.27E+02 3.26E+06 8.23E+02 4.95E+04 2.45E+04 9.43E-03 4.51E+00 8.79E+00 1.43E+00 4.83E+00 6.63E+00 8.39E+00 6.51E+02 2.19E+02 8.95E+00 6.20E+00 1.08E+02 2.51E+03 1.99E+02 4.82E+04 1.02E+04 1.50E+05 7.99E+04 1.21E+02 7.63E-01 6.79E+01 1.34E+01 2.96E+02 2.81E+03 1.48E+03 3.80E+03 1.33E+05 1.44E+02 4.39E+07 4.39E+07 3.48E+03 2.95E+03 2.65E+04

100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 101% 107% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100%

ADJUSTED INVENTORY TO INCLUDE ACCUMULATION-Radionuclides decayed to 1/1/2051 IDF Waste Streams Only 106-Ru 113m-Cd 125-Sb 126-Sn 129-I 134-Cs 137-Cs 137m-Ba 14-C 151-Sm 152-Eu 154-Eu 155-Eu 226-Ra 227-Ac 228-Ra 229-Th 231-Pa 232-Th 232-U 233-U 234-U 235-U 236-U 237-Np 238-Pu 238-U 239-Pu 240-Pu 241-Am 241-Pu 242-Cm 242-Pu 243-Am 243-Cm 244-Cm 3-H 59-Ni 60-Co 63-Ni 79-Se 90-Sr 90-Y 93-Zr 93m-Nb 99-Tc

LAW Glass Subtotal (IDF) 2.44E-12 3.99E+02 8.17E-02 3.87E+02 1.65E+01 1.10E-07 3.91E+03 3.69E+03 0.00E+00 1.60E-01 9.79E-06 2.76E-05 2.11E-06 9.06E-03 3.31E+00 1.23E+00 4.15E-08 8.42E-08 9.43E-08 9.32E-02 9.94E+00 3.01E+00 1.22E-01 9.51E-02 1.73E+01 1.65E+02 2.70E+00 4.47E+03 9.41E+02 5.92E+03 9.36E+02 9.76E+01 7.37E-02 3.08E+00 4.78E+00 5.67E+01 0.00E+00 5.03E+01 6.38E-07 3.35E+03 1.41E+02 9.13E+04 9.13E+04 8.03E-04 7.67E-04 2.64E+04

LAW Spent Melter Subtotal (IDF) 2.60E-15 6.28E-01 8.83E-05 4.42E-01 2.38E-02 1.53E-10 5.05E+00 4.77E+00 0.00E+00 2.22E-04 1.36E-08 3.84E-08 2.94E-09 1.11E-05 4.77E-03 1.70E-03 5.77E-11 1.17E-10 1.31E-10 1.20E-04 1.29E-02 4.25E-03 1.73E-04 1.31E-04 2.09E-02 2.45E-01 3.85E-03 5.93E+00 1.24E+00 7.72E+00 1.24E+00 1.08E-01 1.01E-04 4.50E-03 5.64E-03 6.67E-02 0.00E+00 9.05E-02 8.87E-10 6.02E+00 1.80E-01 1.14E+02 1.14E+02 1.11E-06 1.06E-06 3.74E+01

ETF Solid Waste Form to IDF 1.34E-15 1.50E+00 1.39E-03 1.66E+00 6.42E-02 6.31E-12 2.49E-01 2.35E-01 3.50E+00 1.24E-05 5.11E-11 6.57E-09 1.59E-10 1.77E-04 1.48E-02 3.07E-02 3.71E-15 7.62E-11 3.12E-17 1.95E-07 1.78E-05 2.89E-03 1.21E-04 3.38E-05 7.08E-05 2.27E-04 2.78E-03 6.17E-03 1.27E-03 1.96E-02 1.23E-03 3.45E-01 3.41E-04 1.06E-05 1.76E-02 2.08E-01 2.09E-01 1.30E-01 3.06E-07 8.65E+00 2.86E+00 3.50E+01 3.50E+01 2.10E-07 9.19E-04 2.29E-01

Solid Waste Forms from Treatment Processes (IDF) 1.28E-17 9.64E-04 2.64E-07 1.92E-02 1.21E+01 4.46E-08 1.48E+03 1.40E+03 0.00E+00 1.97E-03 7.65E-08 1.29E-06 3.87E-08 3.44E-08 3.72E-07 4.70E-06 1.19E-09 4.05E-09 5.56E-09 1.50E-08 1.65E-06 5.16E-07 2.10E-08 1.58E-08 2.02E-06 7.95E-03 4.65E-07 2.01E-02 1.97E-02 9.87E-03 1.13E-04 3.19E-04 8.84E-09 7.68E-07 2.43E-04 2.12E-04 0.00E+00 4.23E-04 6.02E-08 2.82E-02 5.41E-03 9.33E+00 9.33E+00 2.77E-04 6.69E-05 1.99E+01

SSW FRACTIONS BASED ON 10-010 and 10-009 106-Ru 113m-Cd 125-Sb 126-Sn 129-I 134-Cs 137-Cs 137m-Ba 14-C 151-Sm 152-Eu 154-Eu 155-Eu 226-Ra 227-Ac 228-Ra 229-Th 231-Pa 232-Th 232-U 233-U 234-U 235-U 236-U 237-Np 238-Pu 238-U 239-Pu 240-Pu 241-Am 241-Pu 242-Cm 242-Pu 243-Am 243-Cm 244-Cm 3-H 59-Ni 60-Co 63-Ni 79-Se 90-Sr 90-Y 93-Zr 93m-Nb 99-Tc

HEPA fraction NR NR NR 51.81% 1.03% 52.45% 50.81% NR 10.40% NR 65.24% 64.99% 65.27% NR NR NR NR NR NR NR 68.98% 68.94% 68.90% 68.85% 54.86% 68.68% 68.39% 68.53% 68.48% 70.74% 68.04% NR NR NR NR NR 0.01% 56.98% 62.75% 57.75% 71.82% 65.75% NR NR NR 87.60%

IX Resin fraction NR NR NR 43.80% 0.14% 8.96% 9.27% NR 1.53% NR 7.64% 7.67% 7.61% NR NR NR NR NR NR NR 0.00% 0.00% 0.00% 0.00% 42.37% 0.00% 0.00% 0.00% 0.00% 3.83% 0.00% NR NR NR NR NR 49.09% 20.28% 19.08% 19.89% 26.01% 0.09% NR NR NR 11.86%

LAW and HLW Carbon Bed fraction NR NR NR 0.00% 36.47% 0.00% 0.00% NR 34.07% NR 0.00% 0.00% 0.00% NR NR NR NR NR NR NR 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR NR NR NR NR 36.25% 0.00% 0.00% 0.00% 0.00% 0.00% NR NR NR 0.00%

Other Debris fraction NR NR NR 4.39% 0.01% 38.59% 39.92% NR 24.63% NR 27.13% 27.34% 27.12% NR NR NR NR NR NR NR 31.02% 31.06% 31.10% 31.15% 2.77% 31.32% 31.61% 31.47% 31.52% 25.43% 31.96% NR NR NR NR NR 14.62% 22.75% 18.17% 22.35% 2.17% 34.16% NR NR NR 0.54%

HLW Silver Mordenite Absorbent fraction NR NR NR 0.00% 62.35% 0.00% 0.00% NR 29.36% NR 0.00% 0.00% 0.00% NR NR NR NR NR NR NR 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR NR NR NR NR 0.03% 0.00% 0.00% 0.00% 0.00% 0.00% NR NR NR 0.00%

WTP SSW INVENTORY-Radionuclides decayed to 1/1/2008 106-Ru 113m-Cd 125-Sb 126-Sn 129-I 134-Cs 137-Cs 137m-Ba 14-C 151-Sm 152-Eu 154-Eu 155-Eu 226-Ra 227-Ac 228-Ra 229-Th 231-Pa 232-Th 232-U 233-U 234-U 235-U 236-U 237-Np 238-Pu 238-U 239-Pu 240-Pu 241-Am 241-Pu 242-Cm 242-Pu 243-Am 243-Cm 244-Cm 3-H 59-Ni 60-Co 63-Ni 79-Se 90-Sr 90-Y 93-Zr 93m-Nb 99-Tc

HEPA Filters Debris NR NR NR 9.93E-03 1.25E-01 4.34E-02 2.03E+03 NR 0.00E+00 NR 4.51E-07 2.70E-05 1.34E-05 NR NR NR NR NR NR NR 1.14E-06 3.56E-07 1.44E-08 1.09E-08 1.11E-06 7.67E-03 3.18E-07 1.38E-02 1.35E-02 7.46E-03 6.07E-04 NR NR NR NR NR 0.00E+00 2.41E-04 1.08E-05 2.19E-02 3.88E-03 1.73E+01 NR NR NR 1.74E+01

IX Resin Non-Debris NR NR NR 8.39E-03 1.66E-02 7.42E-03 3.71E+02 NR 0.00E+00 NR 5.28E-08 3.18E-06 1.56E-06 NR NR NR NR NR NR NR 5.54E-13 1.78E-13 6.14E-15 7.40E-15 8.54E-07 8.08E-08 1.63E-13 1.47E-07 1.45E-07 4.03E-04 6.61E-09 NR NR NR NR NR 0.00E+00 8.59E-05 3.28E-06 7.54E-03 1.41E-03 2.46E-02 NR NR NR 2.36E+00

LAW and HLW Carbon Beds Non-Debris NR NR NR 1.99E-13 4.42E+00 1.54E-11 6.30E-07 NR 0.00E+00 NR 1.43E-18 8.93E-17 4.37E-17 NR NR NR NR NR NR NR 6.18E-19 2.13E-19 8.95E-21 8.39E-21 2.03E-17 4.30E-15 1.95E-19 7.82E-15 7.65E-15 1.40E-14 3.50E-16 NR NR NR NR NR 0.00E+00 1.76E-14 1.11E-16 1.57E-12 3.94E-13 3.05E-09 NR NR NR 2.63E-09

Other Debris Debris NR NR NR 8.41E-04 1.09E-03 3.20E-02 1.60E+03 NR 0.00E+00 NR 1.87E-07 1.13E-05 5.57E-06 NR NR NR NR NR NR NR 5.13E-07 1.60E-07 6.52E-09 4.91E-09 5.58E-08 3.50E-03 1.47E-07 6.34E-03 6.24E-03 2.68E-03 2.85E-04 NR NR NR NR NR 0.00E+00 9.63E-05 3.12E-06 8.48E-03 1.17E-04 8.98E+00 NR NR NR 1.07E-01

HLW Silver Mordenite Absorbent Non-Debris NR NR NR 1.92E-16 7.56E+00 3.07E-11 1.25E-06 NR 0.00E+00 NR 3.59E-19 2.75E-17 1.32E-17 NR NR NR NR NR NR NR 1.24E-18 4.27E-19 1.79E-20 1.68E-20 1.32E-20 8.59E-15 3.90E-19 1.56E-14 1.53E-14 8.27E-15 7.00E-16 NR NR NR NR NR 0.00E+00 2.84E-14 2.38E-17 2.54E-12 4.83E-14 6.10E-09 NR NR NR 2.21E-12

SSW Total NR NR NR 1.92E-02 1.21E+01 8.28E-02 4.00E+03 NR 0.00E+00 NR 6.91E-07 4.15E-05 2.05E-05 NR NR NR NR NR NR NR 1.65E-06 5.16E-07 2.10E-08 1.58E-08 2.02E-06 1.12E-02 4.65E-07 2.02E-02 1.98E-02 1.05E-02 8.93E-04 NR NR NR NR NR 0.00E+00 4.24E-04 1.72E-05 3.79E-02 5.41E-03 2.63E+01 NR NR NR 1.99E+01

BBI 2.94E+01 3.90E+07 4.76E+07 2.65E+04

Check N/A N/A N/A 100% 100% 100% 100% N/A #DIV/0! N/A 100% 100% 100% N/A N/A N/A N/A N/A N/A N/A 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% N/A N/A N/A N/A N/A #DIV/0! 100% 100% 100% 100% 100% N/A N/A N/A 100%

WTP SSW INVENTORY-Radionuclides decayed to 1/1 2051 106-Ru 113m-Cd 125-Sb 126-Sn 129-I 134-Cs 137-Cs 137m-Ba 14-C 151-Sm 152-Eu 154-Eu 155-Eu 226-Ra 227-Ac 228-Ra 229-Th 231-Pa 232-Th 232-U 233-U 234-U 235-U 236-U 237-Np 238-Pu 238-U 239-Pu 240-Pu 241-Am 241-Pu 242-Cm 242-Pu 243-Am 243-Cm 244-Cm 3-H 59-Ni 60-Co 63-Ni 79-Se 90-Sr 90-Y 93-Zr 93m-Nb 99-Tc





HLW Silver Mordenite Absorbent Non-Debris NR NR NR 1.92E-16 7.56E+00 1.65E-17 4.64E-07 NR 0.00E+00 NR 3.97E-20 8.55E-19 2.48E-20 NR NR NR NR NR NR NR 1.24E-18 4.27E-19 1.79E-20 1.68E-20 1.32E-20 6.12E-15 3.90E-19 1.56E-14 1.52E-14 7.74E-15 8.83E-17 NR NR NR NR NR 0.00E+00 2.84E-14 8.32E-20 1.89E-12 4.83E-14 2.16E-09 NR NR NR 2.21E-12SE

CT

ION

5B

SE

CT

ION

1S

EC

TIO

N 2

SE

CT

ION

3A

SE

CT

ION

4S

EC

TIO

N 5

AS

EC

TIO

N 3

B



A-5/A-6

Table A-2. Run Case 7 Chemicals.

SVF-4092, IDF PA Case 7 - Current Information Case - Mass Balance, MMR-50049.xlsm

WASTE STREAM Ag Al As B Ba Be Bi Cd Ce Cl Cr Cs Cu F Fe Hg K La Li Mg Mn Mo Na Nd Ni NO2- NO3- OH- Pb Pd PO4-3 Pr Pu Rb Rh Ru Sb Se Si SO2 SO3 SO4-2 Sr Ta Tc Te Th Ti Tl TOC U V W Y Zn Zr

LAW Glass Subtotal (IDF) 1.11E+03 2.36E+07 4.67E+03 2.23E+07 9.73E+00 4.96E+02 6.46E+04 5.08E+03 5.30E+04 7.35E+05 4.87E+05 5.61E-01 3.56E+02 1.10E+06 2.83E+07 0.00E+00 9.37E+05 6.84E-05 7.75E+06 6.54E+06 6.99E-05 6.49E+03 8.02E+07 3.25E+03 2.25E+03 0.00E+00 0.00E+00 0.00E+00 7.00E+04 2.12E+03 0.00E+00 0.00E+00 7.52E+01 2.74E+02 0.00E+00 3.07E+03 3.48E+03 5.03E+03 1.61E+08 0.00E+00 3.12E+06 0.00E+00 6.05E+01 7.26E-02 1.53E+03 1.40E+03 8.54E-04 8.76E+06 2.34E-04 0.00E+00 8.03E+03 7.61E-01 4.14E+03 8.87E+01 1.73E+07 1.62E+07

LAW Spent Melter Subtotal (IDF) 1.70E+00 2.94E+04 6.22E+00 2.77E+04 1.39E-02 5.91E-01 8.75E+01 7.87E+00 8.77E+01 9.61E+02 7.39E+02 7.13E-04 4.70E-01 1.40E+03 3.52E+04 0.00E+00 1.27E+03 9.51E-08 7.47E+03 8.13E+03 9.72E-08 7.26E+00 1.07E+05 4.59E+00 3.29E+00 0.00E+00 0.00E+00 0.00E+00 7.59E+01 2.23E+00 0.00E+00 0.00E+00 9.96E-02 2.74E-01 0.00E+00 2.69E+00 4.39E+00 6.62E+00 1.97E+05 0.00E+00 3.63E+03 0.00E+00 7.72E-02 1.15E-04 2.17E+00 2.16E+00 1.19E-06 1.09E+04 3.37E-07 1.38E-02 1.14E+01 1.03E-03 2.89E+00 1.30E-01 2.16E+04 2.01E+04

ETF Solid Waste Form to IDF 3.13E+00 1.85E+01 9.61E+01 5.87E+01 7.39E-01 2.03E+00 3.16E+02 4.77E-01 1.14E+03 8.76E+02 4.27E+00 3.56E-05 3.52E+00 4.86E+03 3.13E+02 9.42E+02 6.87E+00 2.73E-03 7.97E+00 1.14E+00 3.38E+01 2.86E+01 3.55E+05 1.14E+01 6.40E+00 4.64E+01 1.64E+05 1.38E+05 8.82E+03 5.98E+00 2.39E+02 0.00E+00 1.88E-04 8.34E-01 0.00E+00 6.44E+00 7.18E+01 1.02E+02 1.88E+03 0.00E+00 0.00E+00 1.77E+03 1.18E+01 6.45E-04 1.33E-02 3.94E+01 2.83E-13 1.07E-05 1.45E-05 8.23E+03 8.25E+00 5.31E-05 2.67E-03 4.10E-03 2.25E+01 1.42E-05

Solid Waste Forms from Treatment Processes (IDF) 1.08E-01 2.17E+01 2.95E-01 2.88E+01 4.05E-02 5.56E-05 2.45E-02 3.29E-01 8.16E-04 8.00E+04 7.39E+02 2.10E-01 3.22E-03 1.04E+05 1.39E-01 9.85E+02 3.11E+02 8.73E-07 1.14E-01 8.70E-03 8.39E-02 1.41E-02 4.66E+03 3.13E-05 6.20E-01 0.00E+00 0.00E+00 0.00E+00 1.19E+01 2.38E-04 4.00E+03 6.70E-07 4.06E-04 1.05E-03 7.79E-07 8.14E-03 1.12E-02 4.95E-01 2.03E-01 5.84E+03 0.00E+00 0.00E+00 3.54E-02 2.19E-07 1.15E+00 2.33E-02 5.04E-05 2.84E-04 1.46E-04 0.00E+00 1.38E-03 2.83E-05 4.64E-04 2.70E-06 1.55E-01 3.23E-02

Non-IDF Stream 2.62E+03 2.52E+06 8.91E+01 1.44E+06 8.48E+03 2.76E+00 4.81E+05 3.58E+03 6.55E+03 4.95E+03 7.12E+04 2.07E+03 2.34E+03 3.29E+04 1.57E+06 1.38E+01 1.60E+04 4.21E+04 7.89E+05 2.24E+04 4.60E+05 2.34E+01 2.18E+06 5.95E+03 1.16E+05 1.69E+07 5.95E+07 2.63E+07 2.65E+03 6.08E-01 5.13E+06 7.99E+02 7.34E+02 9.95E-02 9.29E+02 7.42E-01 1.59E+02 3.39E+01 5.83E+06 -5.84E+03 -3.12E+06 3.78E+06 6.06E+04 2.51E+02 1.26E+00 1.47E+03 6.01E+04 1.38E+03 6.66E+03 8.60E+05 5.83E+05 2.37E+03 1.15E+01 4.75E+02 4.31E+02 4.06E+05

BBI 4.03E+03 8.67E+06 4.88E+03 1.52E+04 9.42E+03 5.02E+02 5.61E+05 8.87E+03 6.96E+03 8.27E+05 5.91E+05 2.09E+03 2.91E+03 1.28E+06 1.27E+06 1.99E+03 9.57E+05 3.20E+04 1.94E+03 2.19E+04 1.64E+05 6.56E+03 4.92E+07 9.70E+03 9.87E+04 1.19E+07 5.60E+07 4.45E+06 8.20E+04 2.14E+03 5.18E+06 8.43E+02 8.45E+02 2.78E+02 9.47E+02 3.09E+03 3.73E+03 5.18E+03 8.41E+05 0.00E+00 0.00E+00 3.82E+06 4.23E+04 2.72E+02 1.56E+03 2.92E+03 6.15E+04 1.51E+03 6.98E+03 8.71E+05 6.45E+05 2.58E+03 4.16E+03 5.81E+02 6.08E+03 4.09E+05

HTWOS Feed 4.03E+03 2.67E+07 4.88E+03 2.37E+07 9.42E+03 5.02E+02 6.02E+05 8.87E+03 6.14E+04 8.28E+05 5.91E+05 2.09E+03 2.91E+03 1.28E+06 3.00E+07 1.99E+03 9.57E+05 4.47E+04 8.54E+06 6.57E+06 4.80E+05 6.56E+03 8.30E+07 9.70E+03 1.25E+05 1.69E+07 5.97E+07 2.65E+07 8.20E+04 2.14E+03 5.20E+06 8.43E+02 8.77E+02 2.78E+02 9.47E+02 3.09E+03 3.73E+03 5.18E+03 1.67E+08 0.00E+00 0.00E+00 3.83E+06 6.38E+04 2.72E+02 1.56E+03 2.92E+03 6.15E+04 8.77E+06 6.98E+03 8.71E+05 6.47E+05 2.58E+03 4.16E+03 5.81E+02 1.74E+07 1.66E+07

HTWOS Feed Adjusted Minus TF and TRU Accumulation 3.82E+03 2.62E+07 4.87E+03 2.37E+07 8.70E+03 5.02E+02 5.47E+05 8.67E+03 6.10E+04 8.28E+05 5.63E+05 2.09E+03 2.73E+03 1.28E+06 2.99E+07 1.97E+03 9.56E+05 4.22E+04 8.54E+06 6.57E+06 4.68E+05 6.55E+03 8.29E+07 9.26E+03 1.20E+05 1.69E+07 5.97E+07 2.64E+07 8.16E+04 2.13E+03 5.14E+06 8.22E+02 8.23E+02 2.75E+02 9.40E+02 3.08E+03 3.72E+03 5.18E+03 1.67E+08 0.00E+00 0.00E+00 3.82E+06 6.09E+04 2.66E+02 1.56E+03 2.91E+03 6.03E+04 8.77E+06 6.79E+03 8.70E+05 5.96E+05 2.40E+03 4.15E+03 5.70E+02 1.74E+07 1.66E+07

ACCUMULATION STREAM Ag Al As B Ba Be Bi Cd Ce Cl Cr Cs Cu F Fe Hg K La Li Mg Mn Mo Na Nd Ni NO2- NO3- OH- Pb Pd PO4-3 Pr Pu Rb Rh Ru Sb Se Si SO2 SO3 SO4-2 Sr Ta Tc Te Th Ti Tl TOC U V W Y Zn Zr

PT-Accumulation 9.18E+01 2.26E+04 2.01E+00 4.22E+00 1.85E+02 1.20E-01 3.07E+02 1.65E+00 1.63E+02 4.88E+02 2.20E+03 1.66E+01 2.50E+01 1.65E+03 1.16E+04 1.72E+00 9.27E+02 1.12E+02 6.63E-01 6.24E+02 7.13E+03 2.58E+00 4.96E+04 3.60E+01 1.13E+03 6.11E+03 5.96E+04 8.54E+03 3.67E+01 2.97E+00 2.61E+03 2.17E+01 1.22E+01 6.58E-03 1.02E+01 2.18E-02 1.70E+00 1.68E+00 9.42E+03 0.00E+00 0.00E+00 2.76E+03 2.24E+02 1.33E+01 1.49E+00 1.43E-01 1.69E+02 1.61E+01 1.27E+02 1.26E+03 4.42E+03 3.47E+01 2.46E-02 5.65E+00 2.87E+00 6.01E+02

TF-Accumulation 2.06E+02 4.65E+05 4.23E+00 2.53E+01 7.22E+02 3.31E-01 5.48E+04 1.98E+02 4.13E+02 5.98E+02 2.76E+04 9.09E-01 1.85E+02 6.23E+03 1.11E+05 1.73E+01 4.55E+02 2.50E+03 2.69E+00 1.68E+03 1.21E+04 3.51E+00 9.17E+04 4.49E+02 5.74E+03 6.43E+03 4.20E+04 6.24E+03 4.18E+02 7.34E+00 6.59E+04 2.08E+01 5.44E+01 3.50E+00 7.44E+00 5.07E+00 2.75E+00 2.71E+00 6.90E+04 0.00E+00 0.00E+00 2.66E+03 2.94E+03 5.93E+00 4.74E-01 3.00E+00 1.23E+03 1.15E+02 1.85E+02 7.70E+02 5.13E+04 1.79E+02 2.71E+00 1.08E+01 1.93E+01 1.80E+03

TRU-Accumulation 1.94E-02 2.91E+02 1.35E-02 2.92E-01 1.55E-01 6.08E-03 3.38E+02 9.73E-02 3.47E+00 1.25E+01 1.62E+01 1.47E-04 9.11E-01 1.57E+02 1.61E+02 2.34E-03 1.66E+00 1.96E-02 7.92E-115 2.52E+00 1.11E+00 3.96E-114 1.31E+03 7.92E-114 2.02E-01 3.37E+02 1.08E+03 1.08E-01 9.32E-01 0.00E+00 1.34E+03 0.00E+00 3.72E-02 0.00E+00 0.00E+00 1.13E-20 7.22E-01 8.75E-03 1.17E+02 0.00E+00 0.00E+00 7.15E+01 1.80E+00 0.00E+00 6.93E-04 0.00E+00 1.77E-08 1.73E-01 8.36E-113 5.54E+00 1.61E+01 2.50E-62 3.60E-299 6.08E-08 2.55E+00 1.21E+00

LAW Accumulation 1.37E-01 1.24E+03 3.51E-01 8.64E+02 5.32E-04 1.89E-02 7.17E+00 2.41E-01 3.43E+00 9.65E+01 9.87E+01 5.80E-05 1.69E-01 3.49E+02 1.10E+03 2.75E-01 1.48E+02 1.67E-249 1.08E-01 2.54E+02 1.71E-249 4.15E-01 8.07E+03 3.82E-01 2.41E-01 6.14E+02 2.67E+03 1.64E+03 3.86E+00 4.91E-01 2.75E+02 0.00E+00 1.06E-02 1.09E-03 0.00E+00 3.59E-03 3.00E-01 2.88E-01 5.84E+03 5.36E-02 8.73E+01 4.24E+02 4.45E-03 8.59E-06 3.26E-01 2.67E-02 2.12E-248 3.40E+02 1.61E-196 1.23E+02 7.14E-01 8.11E-05 4.04E-03 1.19E-02 6.72E+02 6.27E+02

HLW-Accumulation 2.97E+00 1.53E+03 5.69E-04 1.30E+03 1.57E+01 2.74E-05 2.64E+01 6.92E-03 7.31E+00 6.97E-03 8.58E+01 1.67E-01 1.80E+00 9.62E-02 9.95E+02 1.72E-03 1.11E+00 9.65E+00 3.09E+02 5.23E+01 6.12E+02 4.00E-04 1.38E+03 2.06E+00 9.46E+01 3.79E+00 1.24E+02 2.17E+01 9.41E-02 2.32E-04 2.00E-01 1.81E+00 1.04E+00 9.19E-06 8.63E-01 2.20E-05 4.14E-04 4.28E-04 3.63E+03 0.00E+00 3.51E-02 1.06E-01 1.65E+01 1.11E+00 1.31E-05 2.07E-04 1.41E+01 1.27E+00 7.56E+00 1.38E-01 3.48E+02 2.80E+00 2.55E-05 4.51E-01 3.79E-04 5.03E+01

SLAW-Accumulation 7.18E-01 1.51E+03 8.86E+00 8.61E+02 7.32E-03 3.97E-02 2.98E+01 1.12E+00 1.68E+01 5.38E+03 8.42E+02 7.08E-04 5.85E-01 3.17E+04 1.10E+03 3.09E+01 4.34E+02 9.80E-24 2.30E-01 2.53E+02 1.00E-23 1.01E+00 6.06E+04 9.55E-01 7.08E-01 7.71E+02 1.12E+04 3.01E+03 6.13E+00 8.83E-01 1.69E+03 0.00E+00 1.65E-02 8.48E-03 0.00E+00 1.86E-02 6.61E+00 8.08E+00 5.82E+03 2.65E-01 9.20E+01 4.04E+04 9.45E-02 5.42E-05 2.61E+01 1.51E+00 1.22E-22 3.38E+02 8.87E-15 1.52E+02 1.96E+00 4.31E-04 1.58E-02 2.98E-02 6.70E+02 6.25E+02

LAWPS-Accumulation 1.17E-05 3.77E-01 2.37E-03 6.54E-03 4.18E-06 2.39E-04 2.78E-02 4.58E-04 0.00E+00 4.07E-01 1.25E-01 1.21E-03 1.47E-04 6.89E-01 1.18E-02 1.07E-03 2.99E-01 0.00E+00 8.46E-04 0.00E+00 0.00E+00 2.89E-03 2.77E+01 3.60E-04 9.49E-06 8.53E+00 3.00E+01 2.82E+00 3.13E-02 2.13E-04 3.00E+00 0.00E+00 1.53E-06 7.53E-06 0.00E+00 2.69E-04 1.80E-03 2.57E-03 7.03E-02 0.00E+00 0.00E+00 2.41E+00 1.34E-05 3.75E-08 6.22E-04 8.54E-04 0.00E+00 0.00E+00 0.00E+00 3.35E-01 1.41E-03 3.75E-07 1.00E-04 1.05E-05 3.26E-03 0.00E+00

ETF-Accumulation 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

LERF-Accumulation 4.26E-02 6.45E-03 2.04E-01 1.53E-01 3.88E-02 4.97E-03 3.04E+00 3.93E-03 8.55E+00 1.22E+00 4.56E-02 1.04E-08 3.99E-02 3.29E+01 3.12E+00 1.22E+00 2.31E-02 1.78E-28 2.70E-02 3.23E-25 2.73E-24 9.82E-02 1.76E+03 1.27E-01 7.55E-02 2.50E-03 3.49E+02 1.82E+03 2.04E+01 9.20E-02 1.28E-01 0.00E+00 1.18E-06 9.44E-04 0.00E+00 2.46E-03 1.59E-01 1.80E-01 1.27E+01 0.00E+00 0.00E+00 7.78E+00 6.11E-02 1.36E-05 2.41E-05 4.89E-02 2.36E-37 2.51E-30 5.27E-32 8.57E+01 1.31E-04 5.12E-05 2.57E-03 3.94E-03 9.33E-02 1.45E-29

Total Accumulation 3.02E+02 4.92E+05 1.57E+01 3.06E+03 9.23E+02 5.22E-01 5.55E+04 2.01E+02 6.16E+02 6.58E+03 3.09E+04 1.76E+01 2.14E+02 4.01E+04 1.26E+05 5.14E+01 1.97E+03 2.62E+03 3.13E+02 2.87E+03 1.99E+04 7.61E+00 2.14E+05 4.89E+02 6.97E+03 1.43E+04 1.17E+05 2.13E+04 4.86E+02 1.18E+01 7.18E+04 4.44E+01 6.77E+01 3.51E+00 1.85E+01 5.12E+00 1.22E+01 1.30E+01 9.38E+04 3.19E-01 1.79E+02 4.63E+04 3.18E+03 2.03E+01 2.84E+01 4.72E+00 1.41E+03 8.10E+02 3.19E+02 2.39E+03 5.61E+04 2.16E+02 2.75E+00 1.69E+01 1.37E+03 3.70E+03

Accumulation minus TF and TRU 9.57E+01 2.69E+04 1.14E+01 3.03E+03 2.01E+02 1.84E-01 3.73E+02 3.02E+00 1.99E+02 5.97E+03 3.23E+03 1.67E+01 2.76E+01 3.37E+04 1.48E+04 3.41E+01 1.51E+03 1.22E+02 3.10E+02 1.18E+03 7.74E+03 4.10E+00 1.21E+05 3.95E+01 1.23E+03 7.50E+03 7.40E+04 1.50E+04 6.73E+01 4.44E+00 4.58E+03 2.35E+01 1.33E+01 1.71E-02 1.11E+01 4.68E-02 8.77E+00 1.02E+01 2.47E+04 3.19E-01 1.79E+02 4.36E+04 2.41E+02 1.44E+01 2.79E+01 1.73E+00 1.83E+02 6.95E+02 1.34E+02 1.62E+03 4.77E+03 3.75E+01 4.72E-02 6.14E+00 1.35E+03 1.90E+03

ADJUSTED INVENTORY TO INCLUDE ACCUMULATION Ag Al As B Ba Be Bi Cd Ce Cl Cr Cs Cu F Fe Hg K La Li Mg Mn Mo Na Nd Ni NO2- NO3- OH- Pb Pd PO4-3 Pr Pu Rb Rh Ru Sb Se Si SO2 SO3 SO4-2 Sr Ta Tc Te Th Ti Tl TOC U V W Y Zn Zr

LAW Glass Subtotal (IDF) 1.13E+03 2.36E+07 4.68E+03 2.23E+07 9.95E+00 4.96E+02 6.46E+04 5.09E+03 5.32E+04 7.40E+05 4.90E+05 5.65E-01 3.60E+02 1.13E+06 2.83E+07 0.00E+00 9.39E+05 6.86E-05 7.75E+06 6.54E+06 7.10E-05 6.50E+03 8.03E+07 3.27E+03 2.27E+03 0.00E+00 0.00E+00 0.00E+00 7.01E+04 2.12E+03 0.00E+00 0.00E+00 7.64E+01 2.74E+02 0.00E+00 3.07E+03 3.49E+03 5.04E+03 1.61E+08 #DIV/0! #DIV/0! 0.00E+00 6.08E+01 7.66E-02 1.56E+03 1.40E+03 8.57E-04 8.76E+06 2.39E-04 0.00E+00 8.10E+03 7.72E-01 4.14E+03 8.97E+01 1.73E+07 1.62E+07

LAW Spent Melter Subtotal (IDF) 1.74E+00 2.95E+04 6.23E+00 2.77E+04 1.42E-02 5.91E-01 8.76E+01 7.87E+00 8.80E+01 9.68E+02 7.44E+02 7.19E-04 4.75E-01 1.44E+03 3.52E+04 0.00E+00 1.27E+03 9.54E-08 7.47E+03 8.14E+03 9.88E-08 7.27E+00 1.07E+05 4.61E+00 3.32E+00 0.00E+00 0.00E+00 0.00E+00 7.59E+01 2.24E+00 0.00E+00 0.00E+00 1.01E-01 2.74E-01 0.00E+00 2.69E+00 4.40E+00 6.64E+00 1.97E+05 #DIV/0! #DIV/0! 0.00E+00 7.75E-02 1.21E-04 2.21E+00 2.16E+00 1.19E-06 1.09E+04 3.44E-07 1.38E-02 1.15E+01 1.04E-03 2.89E+00 1.31E-01 2.16E+04 2.01E+04

ETF Solid Waste Form to IDF 3.21E+00 1.85E+01 9.63E+01 5.87E+01 7.56E-01 2.03E+00 3.17E+02 4.77E-01 1.14E+03 8.83E+02 4.30E+00 3.59E-05 3.56E+00 4.99E+03 3.13E+02 9.58E+02 6.88E+00 2.74E-03 7.97E+00 1.14E+00 3.44E+01 2.86E+01 3.56E+05 1.15E+01 6.47E+00 4.64E+01 1.64E+05 1.38E+05 8.82E+03 5.99E+00 2.40E+02 0.00E+00 1.91E-04 8.34E-01 0.00E+00 6.44E+00 7.20E+01 1.02E+02 1.88E+03 #DIV/0! #DIV/0! 1.79E+03 1.18E+01 6.80E-04 1.35E-02 3.94E+01 2.84E-13 1.07E-05 1.48E-05 8.24E+03 8.32E+00 5.39E-05 2.67E-03 4.15E-03 2.25E+01 1.42E-05

Solid Waste Forms from Treatment Processes (IDF) 1.10E-01 2.17E+01 2.95E-01 2.88E+01 4.14E-02 5.56E-05 2.45E-02 3.30E-01 8.19E-04 8.06E+04 7.43E+02 2.12E-01 3.26E-03 1.06E+05 1.39E-01 1.00E+03 3.12E+02 8.76E-07 1.14E-01 8.70E-03 8.53E-02 1.41E-02 4.66E+03 3.14E-05 6.27E-01 0.00E+00 0.00E+00 0.00E+00 1.19E+01 2.38E-04 4.00E+03 6.89E-07 4.12E-04 1.05E-03 7.88E-07 8.14E-03 1.13E-02 4.96E-01 2.03E-01 #DIV/0! #DIV/0! 0.00E+00 3.56E-02 2.31E-07 1.17E+00 2.33E-02 5.05E-05 2.84E-04 1.48E-04 0.00E+00 1.39E-03 2.87E-05 4.64E-04 2.73E-06 1.55E-01 3.23E-02

Non-IDF Stream 2.68E+03 2.53E+06 8.93E+01 1.44E+06 8.68E+03 2.76E+00 4.82E+05 3.58E+03 6.57E+03 4.98E+03 7.16E+04 2.09E+03 2.36E+03 3.37E+04 1.57E+06 1.40E+01 1.60E+04 4.22E+04 7.89E+05 2.24E+04 4.67E+05 2.34E+01 2.19E+06 5.97E+03 1.17E+05 1.69E+07 5.95E+07 2.63E+07 2.66E+03 6.09E-01 5.13E+06 8.22E+02 7.46E+02 9.95E-02 9.40E+02 7.42E-01 1.59E+02 3.40E+01 5.84E+06 #DIV/0! #DIV/0! 3.82E+06 6.08E+04 2.65E+02 1.28E+00 1.47E+03 6.03E+04 1.38E+03 6.79E+03 8.62E+05 5.88E+05 2.40E+03 1.15E+01 4.80E+02 4.31E+02 4.06E+05

TOTAL 3.82E+03 2.62E+07 4.87E+03 2.37E+07 8.69E+03 5.02E+02 5.47E+05 8.67E+03 6.10E+04 8.28E+05 5.63E+05 2.09E+03 2.73E+03 1.28E+06 2.99E+07 1.97E+03 9.56E+05 4.22E+04 8.54E+06 6.57E+06 4.68E+05 6.55E+03 8.29E+07 9.25E+03 1.20E+05 1.69E+07 5.97E+07 2.64E+07 8.16E+04 2.13E+03 5.14E+06 8.22E+02 8.23E+02 2.75E+02 9.40E+02 3.08E+03 3.72E+03 5.18E+03 1.67E+08 #DIV/0! #DIV/0! 3.82E+06 6.09E+04 2.65E+02 1.56E+03 2.91E+03 6.03E+04 8.77E+06 6.79E+03 8.70E+05 5.96E+05 2.40E+03 4.15E+03 5.70E+02 1.74E+07 1.66E+07

100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% #DIV/0! #DIV/0! 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100%

SSW FRACTIONS BASED ON 10-010 and 10-009 Ag Al As B Ba Be Bi Cd Ce Cl Cr Cs Cu F Fe Hg K La Li Mg Mn Mo Na Nd Ni NO2- NO3- OH- Pb Pd PO4-3 Pr Pu Rb Rh Ru Sb Se Si SO2 SO3 SO4-2 Sr Ta Tc Te Th Ti Tl TOC U V W Y Zn Zr

HEPA fraction 4.53% 17.39% 17.89% 62.10% 6.43% 0.15% 5.17% 50.79% 0.21% 0.00% 94.18% NR 0.00% 0.00% 44.22% 0.00% 56.46% 7.86% 91.84% 69.10% 12.79% NR 40.68% 4.20% 13.13% NR NR NR 61.05% 1.03% NR #DIV/0! 8.09% 5.61% 5.04% 78.35% 5.42% 31.35% 41.49% NR NR NR 15.98% 0.00% 63.36% 20.43% 7.69% 71.77% 23.04% NR 8.06% 41.24% 0.23% NR 87.47% 60.66%

IX Resin fraction 43.06% 62.12% 53.58% 0.54% 22.10% 93.91% 29.47% 23.43% 90.28% 95.63% 5.35% NR 0.00% 0.08% 0.00% 0.00% 42.37% 5.18% 0.04% 0.12% 0.00% NR 55.24% 45.56% 38.04% NR NR NR 19.53% 83.67% NR #DIV/0! 0.00% 61.81% 76.38% 0.00% 72.52% 63.57% 0.12% NR NR NR 0.23% 0.00% 34.99% 4.19% 25.51% 0.00% 38.40% NR 0.00% 16.62% 93.95% NR 0.01% 0.38%

LAW and HLW Carbon Bed fraction 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR 0.00% 98.32% 0.00% 100.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR 0.00% 0.00% 0.00% NR NR NR 0.00% 0.00% NR #DIV/0! 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR NR NR 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR 0.00% 0.00% 0.00% NR 0.00% 0.00%

Other Debris fraction 52.41% 20.48% 28.53% 37.37% 71.47% 5.95% 65.36% 25.78% 9.52% 4.37% 0.47% NR 100.00% 0.01% 55.78% 0.00% 1.17% 86.96% 8.12% 30.78% 87.21% NR 4.08% 50.24% 48.83% NR NR NR 19.42% 15.31% NR #DIV/0! 91.91% 32.59% 18.58% 21.65% 22.06% 5.08% 58.40% NR NR NR 83.79% 100.00% 1.65% 75.39% 66.80% 28.23% 38.56% NR 91.94% 42.15% 5.83% NR 12.52% 38.96%

HLW Silver Mordenite Absorbent fraction 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR 0.00% 1.59% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR 0.00% 0.00% 0.00% NR NR NR 0.00% 0.00% NR #DIV/0! 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR NR NR 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR 0.00% 0.00% 0.00% NR 0.00% 0.00%

WTP SSW INVENTORY Ag Al As B Ba Be Bi Cd Ce Cl Cr Cs Cu F Fe Hg K La Li Mg Mn Mo Na Nd Ni NO2- NO3- OH- Pb Pd PO4-3 Pr Pu Rb Rh Ru Sb Se Si SO2 SO3 SO4-2 Sr Ta Tc Te Th Ti Tl TOC U V W Y Zn Zr

HEPA Filters Debris 5.00E-03 3.78E+00 5.28E-02 1.79E+01 2.66E-03 8.13E-08 1.27E-03 1.67E-01 1.70E-06 0.00E+00 7.00E+02 NR 0.00E+00 1.69E-01 6.13E-02 0.00E+00 1.76E+02 6.88E-08 1.05E-01 6.02E-03 1.09E-02 NR 1.90E+03 1.32E-06 8.23E-02 NR NR NR 7.27E+00 2.45E-06 NR #DIV/0! 3.33E-05 5.91E-05 3.97E-08 6.38E-03 6.11E-04 1.56E-01 8.41E-02 NR NR NR 5.68E-03 0.00E+00 7.44E-01 4.77E-03 3.89E-06 2.04E-04 3.42E-05 NR 1.12E-04 1.19E-05 1.05E-06 NR 1.36E-01 1.96E-02

IX Resin Non-Debris 4.75E-02 1.35E+01 1.58E-01 1.54E-01 9.15E-03 5.22E-05 7.22E-03 7.72E-02 7.39E-04 7.71E+04 3.98E+01 NR 0.00E+00 8.99E+01 5.52E-07 2.24E-02 1.32E+02 4.54E-08 4.16E-05 1.01E-05 1.88E-08 NR 2.58E+03 1.43E-05 2.38E-01 NR NR NR 2.33E+00 1.99E-04 NR #DIV/0! 8.60E-09 6.52E-04 6.02E-07 1.20E-08 8.17E-03 3.15E-01 2.41E-04 NR NR NR 8.16E-05 0.00E+00 4.11E-01 9.77E-04 1.29E-05 4.94E-12 5.70E-05 NR 1.39E-09 4.78E-06 4.36E-04 NR 1.21E-05 1.23E-04

LAW and HLW Carbon Beds Non-Debris 1.27E-12 2.54E-09 7.44E-11 1.33E-08 3.60E-13 1.24E-15 1.99E-13 2.50E-10 1.70E-14 4.23E-02 7.26E-10 NR 0.00E+00 1.05E+05 3.65E-11 1.00E+03 1.07E-07 1.52E-18 6.31E-11 3.61E-12 1.09E-11 NR 1.20E-06 3.39E-16 7.37E-11 NR NR NR 5.40E-09 4.76E-15 NR #DIV/0! 4.61E-16 3.36E-14 3.16E-17 1.82E-11 7.37E-13 1.64E-10 5.05E-11 NR NR NR 1.01E-11 0.00E+00 4.59E-10 7.81E-12 1.06E-15 1.23E-13 1.59E-14 NR 1.58E-15 7.05E-15 1.03E-14 NR 8.11E-11 1.18E-11

Other Debris Debris 5.78E-02 4.45E+00 8.43E-02 1.08E+01 2.96E-02 3.31E-06 1.60E-02 8.50E-02 7.79E-05 3.52E+03 3.47E+00 NR 3.26E-03 5.58E+00 7.74E-02 2.01E-03 3.65E+00 7.62E-07 9.28E-03 2.68E-03 7.44E-02 NR 1.90E+02 1.58E-05 3.06E-01 NR NR NR 2.31E+00 3.64E-05 NR #DIV/0! 3.79E-04 3.44E-04 1.46E-07 1.76E-03 2.49E-03 2.52E-02 1.18E-01 NR NR NR 2.98E-02 2.31E-07 1.94E-02 1.76E-02 3.38E-05 8.03E-05 5.73E-05 NR 1.28E-03 1.21E-05 2.70E-05 NR 1.94E-02 1.26E-02

HLW Silver Mordenite Absorbent Non-Debris 1.02E-13 8.36E-11 1.09E-10 1.53E-10 1.45E-13 1.66E-19 2.83E-14 3.82E-10 5.54E-17 2.18E-07 6.10E-10 NR 0.00E+00 1.69E+03 2.71E-13 7.92E-03 1.56E-09 9.51E-19 1.31E-13 2.34E-14 1.88E-11 NR 2.06E-09 1.88E-17 8.00E-11 NR NR NR 2.76E-09 6.27E-17 NR #DIV/0! 9.22E-16 1.42E-15 3.64E-19 3.64E-11 7.29E-13 1.62E-10 2.08E-13 NR NR NR 2.02E-11 0.00E+00 3.87E-13 1.54E-11 7.50E-17 8.71E-16 1.85E-15 NR 3.15E-15 5.30E-17 3.11E-19 NR 1.44E-15 4.28E-14

SSW Total 1.10E-01 2.17E+01 2.95E-01 2.88E+01 4.14E-02 5.56E-05 2.45E-02 3.30E-01 8.19E-04 8.06E+04 7.43E+02 NR 3.26E-03 1.06E+05 1.39E-01 1.00E+03 3.12E+02 8.76E-07 1.14E-01 8.70E-03 8.53E-02 NR 4.66E+03 3.14E-05 6.27E-01 NR NR NR 1.19E+01 2.38E-04 NR #DIV/0! 4.12E-04 1.05E-03 7.88E-07 8.14E-03 1.13E-02 4.96E-01 2.03E-01 NR NR NR 3.56E-02 2.31E-07 1.17E+00 2.33E-02 5.05E-05 2.84E-04 1.48E-04 NR 1.39E-03 2.87E-05 4.64E-04 NR 1.55E-01 3.23E-02

BBI 5.91E+05 1.99E+03 8.20E+04

Check 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% N/A 100% 100% 100% 100% 100% 100% 100% 100% 100% N/A 100% 100% 100% N/A N/A N/A 100% 100% N/A #DIV/0! 100% 100% 100% 100% 100% 100% 100% N/A N/A N/A 100% 100% 100% 100% 100% 100% 100% N/A 100% 100% 100% N/A 100% 100%

SE

CT

ION

1S

EC

TIO

N 2

SE

CT

ION

3A

SE

CT

ION

4S

EC

TIO

N 5

A



A-7/A-8

Table A-3. Run Case 8B Radionuclides.

SVF-4094, IDF PA Case 8B - Tc_Tc-99 Removal from LAW Vitrification Off-Gas Condensate - Mass Balance, MMR-50051











PT-Accumulation 1.78E-04 1.85E+00 2.85E-01 1.18E-01 5.80E-02 2.90E+00 2.84E+05 2.68E+05 3.34E-01 4.61E+04 1.13E+01 4.13E+02 1.71E+02 3.91E-06 -1.69E-01 -3.03E+00 9.84E-03 5.01E-02 1.26E-02 2.38E-02 1.31E+00 1.30E+00 5.51E-02 2.92E-02 5.98E-01 9.52E+00 1.25E+00 2.36E+02 5.07E+01 6.65E+02 3.24E+02 1.92E-02 3.57E-03 3.00E-01 9.04E-04 1.99E-02 2.16E+00 1.42E+01 3.57E+01 1.27E+03 6.65E-02 2.56E+05 2.56E+05 7.90E+01 7.36E+01 8.35E+00



LAW Accumulation 3.60E-05 3.76E-01 6.21E-02 1.93E-02 5.19E-03 3.57E-06 6.65E-01 6.27E-01 3.49E-02 5.41E-247 2.17E-250 2.23E-249 2.90E-249 7.71E-07 1.18E-03 9.09E-02 1.04E-253 2.08E-253 2.37E-253 2.88E-06 1.70E-04 2.29E-04 9.74E-06 4.93E-06 9.55E-04 2.42E-02 2.18E-04 6.50E-01 1.36E-01 8.15E-02 9.16E-01 3.15E-03 9.63E-06 5.58E-05 1.50E-04 3.31E-03 1.09E-01 1.96E-02 5.06E-250 1.77E+00 1.26E-02 1.49E+01 1.49E+01 3.12E-255 3.59E-249 2.08E+00

HLW-Accumulation 3.99E-08 2.18E-03 2.16E-04 2.85E-05 8.76E-04 5.66E-02 6.47E+03 6.11E+03 1.59E-05 3.37E+03 8.30E-01 3.02E+01 1.25E+01 1.82E-09 -1.27E-02 -2.61E-01 7.10E-04 3.64E-03 8.67E-04 1.69E-03 9.23E-02 8.80E-02 3.73E-03 2.00E-03 4.22E-02 6.40E-01 8.45E-02 1.58E+01 3.40E+00 4.79E+01 2.16E+01 3.24E-06 2.39E-04 2.15E-02 1.90E-07 4.17E-06 7.58E-01 9.94E-01 2.58E+00 8.85E+01 1.93E-05 1.80E+04 1.80E+04 5.82E+00 4.81E+00 3.03E-04

SLAW-Accumulation 1.85E-04 8.45E-01 1.63E+00 3.44E-02 4.70E-01 1.15E-04 1.33E+01 1.26E+01 3.63E-02 3.64E-22 1.44E-25 1.47E-24 1.88E-24 1.95E-05 2.80E-03 1.54E+00 7.01E-29 1.40E-28 1.59E-28 8.11E-06 4.59E-04 4.54E-04 1.93E-05 1.03E-05 1.64E-03 4.32E-02 4.35E-04 1.11E+00 2.37E-01 2.51E-01 1.54E+00 4.77E-03 1.59E-05 1.38E-04 2.50E-04 5.49E-03 3.13E-01 2.95E-02 3.03E-25 2.64E+00 2.66E-01 3.95E+01 3.95E+01 8.21E-27 5.03E-24 2.60E+00


ETF-Accumulation 5.39E-05 4.40E-03 2.07E-01 3.34E-04 5.14E-03 8.02E-06 2.70E-01 2.55E-01 0.00E+00 8.63E-07 3.42E-10 3.47E-09 4.44E-09 4.76E-07 9.67E-06 1.61E-04 1.66E-13 3.32E-13 3.78E-13 1.10E-07 5.83E-06 1.24E-06 4.79E-08 6.60E-08 1.64E-05 2.26E-05 9.86E-07 3.39E-04 8.27E-05 3.66E-04 7.59E-04 8.49E-05 7.58E-08 5.55E-08 9.49E-06 2.10E-04 2.09E-01 3.95E-05 8.20E-10 3.35E-03 7.93E-03 1.01E-01 1.01E-01 6.77E-11 5.52E-09 2.66E-02

LERF-Accumulation 2.44E-06 1.05E-01 5.66E-02 3.16E-03 1.38E-04 6.98E-10 1.35E-04 1.27E-04 5.79E-03 4.96E-28 1.31E-32 6.85E-30 2.73E-30 5.57E-07 3.21E-04 4.99E-02 1.03E-37 2.10E-33 8.66E-40 4.44E-10 2.38E-08 2.17E-08 9.22E-10 4.97E-10 3.77E-08 8.99E-07 2.09E-08 2.22E-05 4.79E-06 1.42E-05 3.03E-05 3.79E-04 1.02E-06 6.71E-09 2.18E-05 4.79E-04 3.25E+00 1.47E-03 1.67E-27 1.31E-01 7.19E-03 4.93E-01 4.93E-01 7.39E-30 2.06E-25 2.22E-05


Accumulation minus TF and TRU 4.56E-04 3.18E+00 2.25E+00 1.75E-01 5.40E-01 2.95E+00 2.91E+05 2.75E+05 4.12E-01 4.94E+04 1.21E+01 4.43E+02 1.84E+02 2.52E-05 -1.78E-01 -1.61E+00 1.05E-02 5.38E-02 1.35E-02 2.55E-02 1.40E+00 1.39E+00 5.89E-02 3.13E-02 6.43E-01 1.02E+01 1.33E+00 2.54E+02 5.45E+01 7.13E+02 3.48E+02 2.76E-02 3.84E-03 3.21E-01 1.34E-03 2.95E-02 6.80E+00 1.53E+01 3.83E+01 1.36E+03 3.60E-01 2.74E+05 2.74E+05 8.49E+01 7.85E+01 1.31E+01








100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 104% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100%


LAW Glass Subtotal (IDF) 2.44E-12 4.01E+02 8.17E-02 3.87E+02 1.65E+01 1.66E-07 5.19E+03 4.90E+03 0.00E+00 1.53E-01 9.31E-06 2.65E-05 2.04E-06 9.06E-03 3.25E+00 8.52E-01 4.04E-08 8.13E-08 9.19E-08 9.56E-02 1.02E+01 2.98E+00 1.21E-01 9.64E-02 1.72E+01 1.69E+02 2.66E+00 4.51E+03 9.59E+02 5.87E+03 9.62E+02 9.76E+01 7.54E-02 3.05E+00 4.78E+00 5.67E+01 0.00E+00 5.02E+01 6.14E-07 3.35E+03 1.41E+02 6.51E+04 6.51E+04 7.76E-04 7.41E-04 9.97E+03





HEPA fraction NR NR NR 52% 1.03% 52.45% 50.81% NR 10.40% NR 65.24% 64.99% 65.27% NR NR NR NR NR NR NR 68.98% 68.94% 68.90% 68.85% 54.86% 68.68% 68.39% 68.53% 68.48% 70.74% 68.04% NR NR NR NR NR 0.01% 56.98% 62.75% 57.75% 71.82% 65.75% NR NR NR 87.60%

IX Resin fraction NR NR NR 44% 0.14% 8.96% 9.27% NR 1.53% NR 7.64% 7.67% 7.61% NR NR NR NR NR NR NR 0.00% 0.00% 0.00% 0.00% 42.37% 0.00% 0.00% 0.00% 0.00% 3.83% 0.00% NR NR NR NR NR 49.09% 20.28% 19.08% 19.89% 26.01% 0.09% NR NR NR 11.86%

LAW and HLW Carbon Bed fraction NR NR NR 0% 36.47% 0.00% 0.00% NR 34.07% NR 0.00% 0.00% 0.00% NR NR NR NR NR NR NR 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR NR NR NR NR 36.25% 0.00% 0.00% 0.00% 0.00% 0.00% NR NR NR 0.00%

Other Debris fraction NR NR NR 4% 0.01% 38.59% 39.92% NR 24.63% NR 27.13% 27.34% 27.12% NR NR NR NR NR NR NR 31.02% 31.06% 31.10% 31.15% 2.77% 31.32% 31.61% 31.47% 31.52% 25.43% 31.96% NR NR NR NR NR 14.62% 22.75% 18.17% 22.35% 2.17% 34.16% NR NR NR 0.54%

HLW Silver Mordenite Absorbent fraction NR NR NR 0% 62.35% 0.00% 0.00% NR 29.36% NR 0.00% 0.00% 0.00% NR NR NR NR NR NR NR 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR NR NR NR NR 0.03% 0.00% 0.00% 0.00% 0.00% 0.00% NR NR NR 0.00%








BBI 2.94E+01 3.90E+07 4.76E+07 2.65E+04



HEPA Filters Debris NR NR NR 9.35E-03 1.25E-01 2.32E-08 7.39E+02 NR 0.00E+00 0.00E+00 5.00E-08 8.41E-07 2.52E-08 NR NR NR NR NR NR NR 1.16E-06 3.53E-07 1.43E-08 1.09E-08 1.10E-06 5.06E-03 3.15E-07 1.29E-02 1.26E-02 6.57E-03 7.86E-05 NR NR NR NR NR 0.00E+00 2.41E-04 3.78E-08 1.63E-02 3.88E-03 6.15E+00 NR NR NR 1.18E+01

IX Resin Non-Debris NR NR NR 7.90E-03 1.66E-02 3.97E-09 1.35E+02 NR 0.00E+00 0.00E+00 5.85E-09 9.92E-08 2.94E-09 NR NR NR NR NR NR NR 5.64E-13 1.77E-13 6.10E-15 7.46E-15 8.49E-07 5.33E-08 1.61E-13 1.37E-07 1.34E-07 3.54E-04 8.55E-10 NR NR NR NR NR 0.00E+00 8.58E-05 1.15E-08 5.61E-03 1.41E-03 8.77E-03 NR NR NR 1.60E+00

LAW and HLW Carbon Beds Non-Debris NR NR NR 1.87E-13 4.42E+00 8.26E-18 2.29E-07 NR 0.00E+00 0.00E+00 1.58E-19 2.78E-18 8.23E-20 NR NR NR NR NR NR NR 6.29E-19 2.12E-19 8.89E-21 8.47E-21 2.02E-17 2.84E-15 1.93E-19 7.29E-15 7.09E-15 1.23E-14 4.53E-17 NR NR NR NR NR 0.00E+00 1.76E-14 3.90E-19 1.17E-12 3.93E-13 1.08E-09 NR NR NR 1.78E-09

Other Debris Debris NR NR NR 7.91E-04 1.09E-03 1.71E-08 5.81E+02 NR 0.00E+00 0.00E+00 2.08E-08 3.54E-07 1.05E-08 NR NR NR NR NR NR NR 5.22E-07 1.59E-07 6.47E-09 4.95E-09 5.55E-08 2.31E-03 1.46E-07 5.91E-03 5.78E-03 2.36E-03 3.69E-05 NR NR NR NR NR 0.00E+00 9.63E-05 1.09E-08 6.31E-03 1.17E-04 3.20E+00 NR NR NR 7.27E-02

HLW Silver Mordenite Absorbent Non-Debris NR NR NR 1.81E-16 7.56E+00 1.64E-17 4.55E-07 NR 0.00E+00 0.00E+00 3.98E-20 8.56E-19 2.48E-20 NR NR NR NR NR NR NR 1.26E-18 4.24E-19 1.78E-20 1.69E-20 1.31E-20 5.67E-15 3.87E-19 1.46E-14 1.42E-14 7.29E-15 9.06E-17 NR NR NR NR NR 0.00E+00 2.83E-14 8.33E-20 1.89E-12 4.83E-14 2.17E-09 NR NR NR 1.50E-12SE

CT

ION

5B

SE

CT

ION

1S

EC

TIO

N 2

SE

CT

ION

3A

SE

CT

ION

4S

EC

TIO

N 5

AS

EC

TIO

N 3

B



A-9/A-10

Table A-4. Run Case 8B Chemicals.

SVF-4094, IDF PA Case 8B - Tc_Tc-99 Removal from LAW Vitrification Off-Gas Condensate - Mass Balance, MMR-50051



LAW Spent Melter Subtotal (IDF) 1.36E+00 2.77E+04 5.11E+00 2.61E+04 1.46E-02 5.57E-01 7.73E+01 6.15E+00 5.93E+01 7.74E+02 5.71E+02 6.43E-04 4.17E-01 1.27E+03 3.31E+04 0.00E+00 1.25E+03 8.05E-08 8.47E+03 7.65E+03 8.23E-08 7.08E+00 9.58E+04 3.90E+00 2.66E+00 0.00E+00 0.00E+00 0.00E+00 7.01E+01 1.66E+00 0.00E+00 0.00E+00 9.48E-02 2.69E-01 0.00E+00 2.37E+00 3.77E+00 5.50E+00 1.87E+05 0.00E+00 3.58E+03 0.00E+00 4.50E-02 9.26E-05 6.57E-01 2.12E+00 1.01E-06 1.03E+04 2.55E-07 1.38E-02 8.75E+00 9.14E-04 2.56E+00 1.13E-01 2.03E+04 1.89E+04

ETF Solid Waste Form to IDF 2.98E+00 1.84E+01 9.76E+01 6.53E+01 6.73E-01 2.38E+00 3.20E+02 5.46E-01 1.11E+03 8.80E+02 4.32E+00 3.24E-05 3.47E+00 4.80E+03 2.96E+02 9.37E+02 6.84E+00 2.73E-03 8.60E+00 1.14E+00 3.38E+01 3.01E+01 3.50E+05 1.10E+01 6.05E+00 4.64E+01 1.64E+05 1.30E+05 9.57E+03 5.72E+00 2.39E+02 0.00E+00 1.95E-04 8.89E-01 0.00E+00 7.19E+00 7.19E+01 1.02E+02 2.16E+03 0.00E+00 0.00E+00 1.77E+03 1.09E+01 6.06E-04 1.71E-03 4.46E+01 2.83E-13 1.07E-05 1.45E-05 8.23E+03 8.26E+00 3.00E-05 4.62E-03 2.43E-03 2.69E+01 1.42E-05

Solid Waste Forms from Treatment Processes (IDF) 1.01E-01 2.19E+01 2.82E-01 2.88E+01 3.71E-02 5.56E-05 2.41E-02 3.37E-01 7.73E-04 8.00E+04 7.43E+02 2.06E-01 3.24E-03 1.05E+05 1.31E-01 9.97E+02 3.11E+02 8.77E-07 1.14E-01 8.90E-03 8.43E-02 1.41E-02 4.65E+03 3.06E-05 5.86E-01 0.00E+00 0.00E+00 0.00E+00 1.17E+01 2.38E-04 4.00E+03 6.67E-07 3.83E-04 1.05E-03 7.77E-07 8.14E-03 1.13E-02 4.78E-01 2.04E-01 5.90E+03 0.00E+00 0.00E+00 3.62E-02 2.19E-07 7.97E-01 2.71E-02 5.05E-05 2.85E-04 1.46E-04 0.00E+00 1.37E-03 2.84E-05 4.64E-04 2.67E-06 1.55E-01 3.23E-02

Non-IDF Stream 2.70E+03 2.47E+06 8.96E+01 1.54E+06 8.64E+03 2.84E+00 4.81E+05 3.43E+03 6.57E+03 4.96E+03 6.90E+04 2.07E+03 2.35E+03 3.28E+04 1.45E+06 1.43E+01 1.56E+04 4.21E+04 7.39E+05 2.29E+04 4.62E+05 2.42E+01 1.87E+06 6.02E+03 1.17E+05 1.69E+07 5.95E+07 2.63E+07 2.74E+03 9.28E-01 5.13E+06 7.95E+02 7.42E+02 1.54E-01 9.27E+02 9.62E-01 1.59E+02 3.44E+01 5.37E+06 -5.90E+03 -3.14E+06 3.80E+06 6.19E+04 2.51E+02 9.72E+02 1.22E+03 6.02E+04 1.38E+03 6.66E+03 8.61E+05 5.84E+05 2.38E+03 1.27E+01 4.76E+02 4.32E+02 4.06E+05





PT-Accumulation 3.09E+01 2.45E+04 3.35E+00 4.19E+00 4.87E+01 1.69E-01 1.60E+03 1.48E+00 4.12E+02 4.86E+02 1.75E+03 1.53E+01 1.28E+01 2.14E+03 5.37E+03 1.06E+00 3.37E+02 4.20E+01 5.42E-01 1.85E+02 4.61E+03 2.10E+00 4.22E+04 3.78E+01 4.47E+02 5.62E+03 5.02E+04 8.77E+03 4.67E+01 3.91E-02 3.03E+03 2.59E+01 4.04E+00 1.67E-02 1.20E+01 4.95E-02 1.54E+00 2.76E+00 4.37E+03 0.00E+00 0.00E+00 3.64E+03 1.52E+02 1.38E+01 4.92E-01 6.36E-01 1.15E+02 1.38E+01 1.35E+02 4.31E+02 3.73E+03 2.19E+01 5.83E-02 5.32E+00 1.93E+00 5.58E+02



LAW Accumulation 4.21E-01 1.43E+03 6.50E-01 9.40E+02 1.80E-03 2.81E-02 8.29E+00 2.96E-01 1.31E+00 1.04E+02 7.06E+01 3.16E-05 8.41E-03 4.63E+02 1.20E+03 1.85E-01 4.36E+01 1.71E-250 9.64E-02 2.76E+02 1.75E-250 3.67E-01 9.04E+03 5.64E-01 6.94E-01 5.80E+02 2.98E+03 2.05E+03 6.03E+00 7.56E-03 3.59E+02 0.00E+00 1.11E-02 3.28E-03 0.00E+00 8.73E-03 2.74E-01 4.91E-01 6.35E+03 8.94E-02 1.02E+02 5.45E+02 9.58E-03 1.38E-05 1.23E-01 1.33E-01 2.15E-249 3.69E+02 1.09E-198 4.48E+01 6.54E-01 9.62E-05 1.16E-02 1.76E-02 7.31E+02 6.83E+02

HLW-Accumulation 1.56E+00 1.33E+03 1.34E-03 8.38E+02 3.53E+00 2.85E-05 8.86E+01 1.51E-03 5.75E+00 1.03E-02 5.35E+01 3.51E-01 8.69E-01 5.44E-02 3.75E+02 6.56E-04 2.01E+00 3.03E+00 3.76E+02 1.32E+01 3.44E+02 6.52E-04 4.37E+02 2.08E+00 3.10E+01 1.73E+00 1.36E+02 8.99E+00 8.53E-02 2.82E-05 9.12E-02 1.90E+00 2.70E-01 1.16E-05 8.90E-01 1.58E-05 2.30E-04 3.03E-04 2.37E+03 6.51E-05 3.88E-02 5.68E-02 9.73E+00 1.01E+00 1.79E-05 3.58E-04 7.88E+00 1.01E+00 6.03E+00 4.33E-02 2.53E+02 1.51E+00 4.44E-05 3.91E-01 2.61E-04 4.10E+01

SLAW-Accumulation 7.79E-01 1.59E+03 1.13E+01 9.10E+02 4.14E-03 4.26E-02 2.34E+01 7.64E-01 5.77E+00 4.84E+03 5.37E+02 4.38E-04 7.43E-02 2.19E+04 1.16E+03 2.45E+01 2.89E+02 1.16E-25 2.13E-01 2.67E+02 1.18E-25 1.00E+00 4.76E+04 9.75E-01 9.91E-01 7.30E+02 1.59E+04 2.94E+03 7.33E+00 2.53E-02 1.48E+03 0.00E+00 1.90E-02 1.46E-02 0.00E+00 1.79E-02 2.66E+00 5.10E+00 6.15E+03 1.05E-01 9.63E+01 1.39E+04 1.87E-02 3.15E-05 1.54E-01 3.02E+00 1.45E-24 3.58E+02 8.69E-16 4.65E+01 1.30E+00 2.96E-04 3.48E-02 3.05E-02 7.09E+02 6.61E+02

LAWPS-Accumulation 6.49E-06 2.77E-01 2.07E-03 9.07E-03 8.74E-06 1.14E-03 2.92E-02 3.03E-04 0.00E+00 3.20E-01 1.24E-01 1.02E-03 1.94E-04 1.15E+00 1.01E-02 1.78E-03 5.00E-01 0.00E+00 1.51E-03 0.00E+00 0.00E+00 2.95E-03 2.85E+01 2.69E-04 6.19E-06 8.77E+00 3.29E+01 2.04E+00 8.46E-02 4.32E-04 2.56E+00 0.00E+00 9.45E-07 1.11E-05 0.00E+00 4.62E-04 2.05E-03 3.62E-03 1.42E-01 0.00E+00 0.00E+00 4.74E+00 1.40E-05 3.49E-08 4.93E-04 2.64E-03 0.00E+00 0.00E+00 0.00E+00 4.35E-01 1.59E-03 3.75E-07 1.81E-04 8.37E-06 6.60E-03 0.00E+00

ETF-Accumulation 3.53E-04 2.88E-01 1.70E-01 8.24E-03 6.64E-07 3.18E-04 3.05E-02 8.73E-04 3.03E-10 7.09E+01 1.12E+00 9.67E-06 4.51E-03 2.27E+01 2.21E-03 9.58E-02 2.26E+01 2.70E-10 1.13E-03 9.02E-12 2.76E-10 1.35E-02 1.87E+02 7.18E-04 1.17E-03 5.17E+00 1.97E+02 1.74E+00 5.71E-02 3.77E-03 1.62E+00 0.00E+00 5.85E-06 1.35E-03 0.00E+00 8.68E-03 1.35E-01 2.61E-01 6.03E-03 0.00E+00 0.00E+00 6.37E+01 1.99E-05 2.45E-09 1.57E-03 5.28E-03 3.43E-09 1.57E-11 3.08E-08 0.00E+00 2.96E-03 8.28E-07 6.46E-03 3.08E-05 7.59E-04 2.59E-11

LERF-Accumulation 2.67E-02 3.68E-03 3.41E-01 8.58E-02 2.59E-04 3.22E-03 1.84E+00 2.16E-03 4.10E+00 1.31E+00 2.84E-02 7.34E-09 2.95E-03 2.29E+01 1.56E+00 7.10E-01 9.74E-03 2.41E-27 2.24E-02 8.21E-24 3.25E-23 7.53E-02 1.62E+03 7.81E-02 4.61E-02 1.72E-03 3.42E+02 1.31E+03 1.33E+01 3.00E-03 8.62E-02 0.00E+00 6.37E-07 1.32E-03 0.00E+00 1.99E-03 6.85E-02 1.23E-01 3.75E+00 0.00E+00 0.00E+00 3.45E+00 4.97E-02 6.88E-06 1.31E-06 1.05E-01 7.87E-36 6.88E-29 2.41E-31 1.85E+01 6.27E-05 3.00E-05 4.62E-03 2.43E-03 2.81E-02 4.88E-28


Accumulation minus TF and TRU 3.37E+01 2.89E+04 1.58E+01 2.69E+03 5.22E+01 2.44E-01 1.72E+03 2.54E+00 4.29E+02 5.50E+03 2.42E+03 1.57E+01 1.38E+01 2.46E+04 8.11E+03 2.66E+01 6.95E+02 4.50E+01 3.77E+02 7.41E+02 4.95E+03 3.56E+00 1.01E+05 4.15E+01 4.80E+02 6.94E+03 6.98E+04 1.51E+04 7.35E+01 7.92E-02 4.87E+03 2.78E+01 4.33E+00 3.73E-02 1.29E+01 8.73E-02 4.68E+00 8.74E+00 1.92E+04 1.94E-01 1.98E+02 1.81E+04 1.62E+02 1.48E+01 7.71E-01 3.91E+00 1.23E+02 7.42E+02 1.41E+02 5.41E+02 3.99E+03 2.34E+01 1.16E-01 5.76E+00 1.44E+03 1.94E+03



LAW Spent Melter Subtotal (IDF) 1.38E+00 2.77E+04 5.12E+00 2.61E+04 1.47E-02 5.58E-01 7.76E+01 6.16E+00 5.97E+01 7.79E+02 5.73E+02 6.48E-04 4.19E-01 1.29E+03 3.31E+04 0.00E+00 1.25E+03 8.06E-08 8.47E+03 7.65E+03 8.32E-08 7.09E+00 9.59E+04 3.92E+00 2.67E+00 0.00E+00 0.00E+00 0.00E+00 7.02E+01 1.66E+00 0.00E+00 0.00E+00 9.53E-02 2.69E-01 0.00E+00 2.37E+00 3.77E+00 5.51E+00 1.87E+05 #DIV/0! #DIV/0! 0.00E+00 4.51E-02 9.78E-05 6.57E-01 2.12E+00 1.01E-06 1.03E+04 2.61E-07 1.38E-02 8.81E+00 9.22E-04 2.56E+00 1.14E-01 2.03E+04 1.89E+04

ETF Solid Waste Form to IDF 3.00E+00 1.85E+01 9.79E+01 6.53E+01 6.77E-01 2.38E+00 3.21E+02 5.46E-01 1.12E+03 8.86E+02 4.34E+00 3.26E-05 3.49E+00 4.89E+03 2.96E+02 9.50E+02 6.85E+00 2.74E-03 8.60E+00 1.14E+00 3.42E+01 3.01E+01 3.51E+05 1.11E+01 6.07E+00 4.64E+01 1.64E+05 1.31E+05 9.58E+03 5.72E+00 2.39E+02 0.00E+00 1.96E-04 8.89E-01 0.00E+00 7.19E+00 7.20E+01 1.02E+02 2.16E+03 #DIV/0! #DIV/0! 1.78E+03 1.09E+01 6.40E-04 1.71E-03 4.46E+01 2.84E-13 1.07E-05 1.48E-05 8.23E+03 8.31E+00 3.03E-05 4.62E-03 2.45E-03 2.69E+01 1.42E-05

Solid Waste Forms from Treatment Processes (IDF) 1.02E-01 2.20E+01 2.83E-01 2.88E+01 3.73E-02 5.56E-05 2.42E-02 3.37E-01 7.79E-04 8.06E+04 7.46E+02 2.08E-01 3.26E-03 1.07E+05 1.31E-01 1.01E+03 3.12E+02 8.78E-07 1.14E-01 8.90E-03 8.52E-02 1.41E-02 4.66E+03 3.08E-05 5.88E-01 0.00E+00 0.00E+00 0.00E+00 1.18E+01 2.38E-04 4.00E+03 6.90E-07 3.85E-04 1.05E-03 7.88E-07 8.14E-03 1.13E-02 4.78E-01 2.04E-01 #DIV/0! #DIV/0! 0.00E+00 3.63E-02 2.31E-07 7.97E-01 2.71E-02 5.06E-05 2.85E-04 1.49E-04 0.00E+00 1.38E-03 2.87E-05 4.64E-04 2.69E-06 1.55E-01 3.23E-02

Non-IDF Stream 2.72E+03 2.47E+06 8.99E+01 1.54E+06 8.69E+03 2.84E+00 4.82E+05 3.43E+03 6.62E+03 5.00E+03 6.93E+04 2.09E+03 2.36E+03 3.35E+04 1.46E+06 1.45E+01 1.56E+04 4.22E+04 7.39E+05 2.29E+04 4.67E+05 2.43E+01 1.88E+06 6.05E+03 1.17E+05 1.69E+07 5.96E+07 2.63E+07 2.74E+03 9.28E-01 5.13E+06 8.22E+02 7.46E+02 1.54E-01 9.39E+02 9.62E-01 1.59E+02 3.45E+01 5.37E+06 #DIV/0! #DIV/0! 3.82E+06 6.21E+04 2.65E+02 9.72E+02 1.23E+03 6.03E+04 1.38E+03 6.79E+03 8.62E+05 5.88E+05 2.40E+03 1.27E+01 4.81E+02 4.32E+02 4.06E+05


100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% #DIV/0! #DIV/0! 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100%


HEPA fraction 4.53% 17.39% 17.89% 62.10% 6.43% 0.15% 5.17% 50.79% 0.21% 0.00% 94.18% NR 0.00% 0.00% 44.22% 0.00% 56.46% 7.86% 91.84% 69.10% 12.79% NR 40.68% 4.20% 13.13% NR NR NR 61.05% 1.03% NR #DIV/0! 8.09% 5.61% 5.04% 78.35% 5.42% 31.35% 41.49% NR NR NR 15.98% 0.00% 63.36% 20.43% 7.69% 71.77% 23.04% NR 8.06% 41% 0% NR 87% 61%

IX Resin fraction 43.06% 62.12% 53.58% 0.54% 22.10% 93.91% 29.47% 23.43% 90.28% 95.63% 5.35% NR 0.00% 0.08% 0.00% 0.00% 42.37% 5.18% 0.04% 0.12% 0.00% NR 55.24% 45.56% 38.04% NR NR NR 19.53% 83.67% NR #DIV/0! 0.00% 61.81% 76.38% 0.00% 72.52% 63.57% 0.12% NR NR NR 0.23% 0.00% 34.99% 4.19% 25.51% 0.00% 38.40% NR 0.00% 17% 94% NR 0% 0%

LAW and HLW Carbon Bed fraction 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR 0.00% 98.32% 0.00% 100.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR 0.00% 0.00% 0.00% NR NR NR 0.00% 0.00% NR #DIV/0! 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR NR NR 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR 0.00% 0% 0% NR 0% 0%

Other Debris fraction 52.41% 20.48% 28.53% 37.37% 71.47% 5.95% 65.36% 25.78% 9.52% 4.37% 0.47% NR 100.00% 0.01% 55.78% 0.00% 1.17% 86.96% 8.12% 30.78% 87.21% NR 4.08% 50.24% 48.83% NR NR NR 19.42% 15.31% NR #DIV/0! 91.91% 32.59% 18.58% 21.65% 22.06% 5.08% 58.40% NR NR NR 83.79% 100.00% 1.65% 75.39% 66.80% 28.23% 38.56% NR 91.94% 42% 6% NR 13% 39%

HLW Silver Mordenite Absorbent fraction 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR 0.00% 1.59% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR 0.00% 0.00% 0.00% NR NR NR 0.00% 0.00% NR #DIV/0! 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR NR NR 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR 0.00% 0% 0% NR 0% 0%







SSW Total 1.02E-01 2.20E+01 2.83E-01 2.88E+01 3.73E-02 5.56E-05 2.42E-02 3.37E-01 7.79E-04 8.06E+04 7.46E+02 NR 3.26E-03 1.07E+05 1.31E-01 1.01E+03 3.12E+02 8.78E-07 1.14E-01 8.90E-03 8.52E-02 NR 4.66E+03 3.08E-05 5.88E-01 NR NR NR 1.18E+01 2.38E-04 NR #DIV/0! 3.85E-04 1.05E-03 7.88E-07 8.14E-03 1.13E-02 4.78E-01 2.04E-01 NR NR NR 3.63E-02 2.31E-07 7.97E-01 2.71E-02 5.06E-05 2.85E-04 1.49E-04 NR 1.38E-03 2.87E-05 4.64E-04 NR 1.55E-01 3.23E-02

BBI 5.91E+05 1.99E+03 8.20E+04


SE

CT

ION

1S

EC

TIO

N 2

SE

CT

ION

3A

SE

CT

ION

4S

EC

TIO

N 5

A



A-11/A-12

Table A-5. Run Case 9 Radionuclides.

SVF-4095, IDF PA Case 9 - Removal of LAWPS - Mass Balance, MMR-50052


LAW Glass Subtotal (IDF) 1.19E+01 3.35E+03 4.01E+03 3.87E+02 1.62E+01 1.69E-01 9.20E+03 8.69E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9.21E-03 1.40E+01 2.01E+02 0.00E+00 0.00E+00 0.00E+00 1.42E-01 1.16E+01 2.97E+00 1.18E-01 9.30E-02 1.71E+01 2.35E+02 2.63E+00 5.01E+03 1.05E+03 6.03E+03 7.98E+03 1.20E+02 7.47E-02 3.05E+00 1.33E+01 2.94E+02 0.00E+00 4.47E+01 0.00E+00 4.03E+03 1.40E+02 1.35E+05 1.35E+05 0.00E+00 0.00E+00 2.60E+04

LAW Spent Melter Subtotal (IDF) 1.64E-02 4.65E+00 5.51E+00 4.62E-01 1.73E-02 2.16E-04 1.10E+01 1.04E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.10E-05 1.92E-02 2.33E-01 0.00E+00 0.00E+00 0.00E+00 1.83E-04 1.48E-02 3.92E-03 1.57E-04 1.27E-04 2.31E-02 2.79E-01 3.48E-03 6.18E+00 1.29E+00 8.11E+00 9.42E+00 1.69E-01 9.09E-05 3.93E-03 1.90E-02 4.20E-01 0.00E+00 5.90E-02 0.00E+00 5.29E+00 1.69E-01 1.68E+02 1.68E+02 0.00E+00 0.00E+00 2.78E+01











LAW Accumulation 2.47E-04 7.93E-01 1.36E-01 1.86E-02 5.63E-03 7.87E-06 7.63E-01 7.21E-01 1.52E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.65E-07 3.51E-03 4.85E-02 0.00E+00 0.00E+00 0.00E+00 9.26E-06 5.63E-04 2.86E-04 1.17E-05 1.17E-05 5.53E-04 3.44E-02 2.52E-04 4.51E-01 1.04E-01 1.48E-01 7.98E-01 4.06E-03 7.72E-06 9.63E-05 7.46E-04 1.64E-02 7.40E-02 7.18E-03 0.00E+00 5.52E-01 9.17E-03 1.38E+01 1.38E+01 0.00E+00 0.00E+00 4.82E+00

HLW-Accumulation 2.17E-07 3.43E-01 4.12E-04 4.60E-05 9.76E-04 2.77E-02 2.96E+03 2.80E+03 2.52E-05 5.61E+03 1.66E+00 1.03E+02 3.31E+01 1.56E-09 -2.76E-02 -1.81E-01 1.74E-04 7.38E-03 5.17E-04 3.16E-03 1.96E-01 8.57E-02 3.52E-03 3.16E-03 3.89E-02 2.19E+00 7.67E-02 3.16E+01 7.28E+00 9.55E+01 5.29E+01 9.92E-06 5.32E-04 5.34E-02 1.78E-06 3.90E-05 1.84E+00 2.14E+00 6.23E+00 1.67E+02 2.25E-05 5.53E+04 5.53E+04 5.09E+00 4.45E+00 6.36E-04

SLAW-Accumulation 6.22E-04 1.41E+00 2.05E+00 3.56E-02 4.68E-01 1.19E-04 1.35E+01 1.28E+01 1.86E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.16E-05 7.00E-03 1.30E+00 0.00E+00 0.00E+00 0.00E+00 1.85E-05 1.13E-03 5.69E-04 2.34E-05 2.19E-05 1.13E-03 6.24E-02 5.08E-04 8.25E-01 1.90E-01 4.13E-01 1.44E+00 7.65E-03 1.37E-05 2.55E-04 1.38E-03 3.03E-02 5.86E-01 1.41E-02 0.00E+00 1.10E+00 1.88E-01 4.11E+01 4.11E+01 0.00E+00 0.00E+00 3.54E+02

LAWPS-Accumulation 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00


LERF-Accumulation 7.44E-06 1.51E-01 7.00E-02 3.37E-03 1.20E-04 1.70E-09 1.90E-04 1.80E-04 3.93E-03 4.55E-31 1.21E-35 6.63E-33 2.65E-33 3.05E-07 7.47E-04 3.18E-02 9.38E-41 1.91E-36 7.89E-43 9.74E-10 5.99E-08 2.78E-08 1.14E-09 1.02E-09 2.86E-08 2.20E-06 2.49E-08 2.94E-05 6.76E-06 2.35E-05 5.10E-05 7.15E-04 1.54E-06 1.41E-08 1.29E-04 2.83E-03 3.81E+00 1.03E-03 1.62E-30 8.06E-02 4.85E-03 1.56E+00 1.56E+00 7.12E-33 1.98E-28 3.65E-04




LAW Glass Subtotal (IDF) 1.19E+01 3.37E+03 4.02E+03 3.87E+02 1.65E+01 1.70E-01 9.30E+03 8.78E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9.22E-03 1.25E+01 1.62E+02 0.00E+00 0.00E+00 0.00E+00 1.43E-01 1.17E+01 2.99E+00 1.19E-01 9.39E-02 1.72E+01 2.39E+02 2.65E+00 5.07E+03 1.06E+03 6.10E+03 8.08E+03 1.20E+02 7.57E-02 3.09E+00 1.33E+01 2.94E+02 0.00E+00 4.59E+01 0.00E+00 4.13E+03 1.41E+02 1.38E+05 1.38E+05 0.00E+00 0.00E+00 2.64E+04

LAW Spent Melter Subtotal (IDF) 1.64E-02 4.67E+00 5.51E+00 4.63E-01 1.76E-02 2.17E-04 1.11E+01 1.05E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.11E-05 1.70E-02 1.88E-01 0.00E+00 0.00E+00 0.00E+00 1.85E-04 1.48E-02 3.95E-03 1.58E-04 1.29E-04 2.33E-02 2.83E-01 3.50E-03 6.25E+00 1.31E+00 8.20E+00 9.54E+00 1.69E-01 9.21E-05 3.98E-03 1.90E-02 4.20E-01 0.00E+00 6.06E-02 0.00E+00 5.42E+00 1.70E-01 1.72E+02 1.72E+02 0.00E+00 0.00E+00 2.82E+01




1.20E+01 3.83E+03 4.11E+03 3.90E+02 2.94E+01 7.13E+02 3.90E+07 3.68E+07 5.91E+02 3.27E+06 8.24E+02 4.94E+04 2.45E+04 9.43E-03 4.49E+00 9.02E+00 1.43E+00 4.83E+00 6.63E+00 8.39E+00 6.51E+02 2.19E+02 8.95E+00 6.20E+00 1.08E+02 2.52E+03 1.99E+02 4.82E+04 1.02E+04 1.50E+05 7.99E+04 1.21E+02 7.63E-01 6.80E+01 1.34E+01 2.96E+02 2.81E+03 1.48E+03 3.80E+03 1.33E+05 1.44E+02 4.40E+07 4.40E+07 3.49E+03 2.96E+03 2.65E+04

100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 101% 104% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100%

INVENTORY TO INCLUDE ACCUMULATION-Radionuclides decayed to 1/1/2051 IDF Waste Streams Only 106-Ru 113m-Cd 125-Sb 126-Sn 129-I 134-Cs 137-Cs 137m-Ba 14-C 151-Sm 152-Eu 154-Eu 155-Eu 226-Ra 227-Ac 228-Ra 229-Th 231-Pa 232-Th 232-U 233-U 234-U 235-U 236-U 237-Np 238-Pu 238-U 239-Pu 240-Pu 241-Am 241-Pu 242-Cm 242-Pu 243-Am 243-Cm 244-Cm 3-H 59-Ni 60-Co 63-Ni 79-Se 90-Sr 90-Y 93-Zr 93m-Nb 99-Tc

LAW Glass Subtotal (IDF) 2.43E-12 4.07E+02 8.13E-02 3.87E+02 1.65E+01 9.14E-08 3.45E+03 3.26E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9.05E-03 3.17E+00 9.18E-01 0.00E+00 0.00E+00 0.00E+00 9.36E-02 1.17E+01 2.99E+00 1.19E-01 9.39E-02 1.72E+01 1.70E+02 2.65E+00 5.06E+03 1.05E+03 5.92E+03 1.02E+03 9.75E+01 7.57E-02 3.08E+00 4.78E+00 5.66E+01 0.00E+00 4.59E+01 0.00E+00 3.07E+03 1.41E+02 4.90E+04 4.90E+04 0.00E+00 0.00E+00 2.64E+04

LAW Spent Melter Subtotal (IDF) 3.35E-15 5.64E-01 1.12E-04 4.63E-01 1.76E-02 1.17E-10 4.14E+00 3.90E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.09E-05 4.33E-03 1.07E-03 0.00E+00 0.00E+00 0.00E+00 1.20E-04 1.48E-02 3.95E-03 1.58E-04 1.29E-04 2.33E-02 2.02E-01 3.50E-03 6.25E+00 1.30E+00 7.92E+00 1.20E+00 1.37E-01 9.21E-05 3.97E-03 6.82E-03 8.10E-02 0.00E+00 6.06E-02 0.00E+00 4.04E+00 1.70E-01 6.11E+01 6.11E+01 0.00E+00 0.00E+00 2.82E+01
















BBI 2.94E+01 3.90E+07 4.76E+07 2.65E+04








CT

ION

5B

SE

CT

ION

1S

EC

TIO

N 2

SE

CT

ION

3A

SE

CT

ION

4S

EC

TIO

N 5

AS

EC

TIO

N 3

B



A-13/A-14

Table A-6. Run Case 9 Chemicals.

SVF-4095, IDF PA Case 9 - Removal of LAWPS - Mass Balance, MMR-50052


LAW Glass Subtotal (IDF) 9.77E+02 2.30E+07 4.68E+03 2.17E+07 6.78E+00 4.96E+02 6.60E+04 5.65E+03 5.40E+04 7.35E+05 4.92E+05 4.93E-01 3.57E+02 1.11E+06 2.76E+07 0.00E+00 9.37E+05 0.00E+00 7.44E+06 6.38E+06 0.00E+00 6.49E+03 7.87E+07 3.08E+03 1.96E+03 0.00E+00 0.00E+00 0.00E+00 7.02E+04 2.12E+03 0.00E+00 0.00E+00 8.53E+01 2.73E+02 0.00E+00 3.06E+03 3.49E+03 5.03E+03 1.57E+08 0.00E+00 3.14E+06 0.00E+00 4.65E+01 5.94E-02 1.54E+03 1.84E+03 0.00E+00 8.55E+06 0.00E+00 0.00E+00 7.88E+03 6.67E-01 4.13E+03 8.09E+01 1.69E+07 1.58E+07

LAW Spent Melter Subtotal (IDF) 1.39E+00 2.77E+04 5.58E+00 2.61E+04 1.51E-02 6.33E-01 8.70E+01 7.22E+00 7.52E+01 8.23E+02 6.58E+02 6.00E-04 4.49E-01 1.27E+03 3.31E+04 0.00E+00 1.08E+03 0.00E+00 5.81E+03 7.65E+03 0.00E+00 7.76E+00 1.05E+05 4.20E+00 2.58E+00 0.00E+00 0.00E+00 0.00E+00 8.32E+01 3.33E+00 0.00E+00 0.00E+00 1.05E-01 3.34E-01 0.00E+00 5.42E+00 4.20E+00 6.13E+00 1.84E+05 0.00E+00 3.64E+03 0.00E+00 5.63E-02 9.92E-05 1.64E+00 2.07E+00 0.00E+00 1.02E+04 0.00E+00 0.00E+00 1.04E+01 9.41E-04 7.07E+00 1.07E-01 2.03E+04 1.89E+04

ETF Solid Waste Form to IDF 2.61E+00 1.84E+01 9.08E+01 5.95E+01 9.99E-01 2.14E+00 2.97E+02 4.83E-01 1.05E+03 8.67E+02 3.89E+00 3.21E-05 3.37E+00 4.76E+03 2.85E+02 8.98E+02 7.05E+00 2.73E-03 7.95E+00 1.14E+00 3.38E+01 2.98E+01 3.48E+05 1.01E+01 5.57E+00 4.64E+01 1.64E+05 1.23E+05 8.62E+03 7.96E+00 2.38E+02 0.00E+00 1.72E-04 1.19E+00 0.00E+00 1.17E+01 6.84E+01 9.85E+01 1.84E+03 0.00E+00 0.00E+00 1.78E+03 1.22E+01 6.32E-04 1.26E-02 5.67E+01 2.83E-13 1.07E-05 1.45E-05 7.83E+03 8.25E+00 2.47E-05 4.58E-03 2.29E-03 2.29E+01 1.42E-05


Non-IDF Stream 2.74E+03 2.51E+06 9.04E+01 1.52E+06 8.48E+03 2.84E+00 4.80E+05 2.98E+03 6.54E+03 4.97E+03 6.71E+04 2.06E+03 2.34E+03 3.54E+04 1.62E+06 1.35E+01 1.73E+04 4.20E+04 7.81E+05 2.25E+04 4.59E+05 2.49E+01 2.28E+06 5.98E+03 1.16E+05 1.67E+07 5.99E+07 2.54E+07 2.71E+03 1.22E+00 5.13E+06 8.12E+02 7.28E+02 1.70E-01 8.92E+02 1.41E+00 1.60E+02 3.47E+01 5.92E+06 -6.04E+03 -3.14E+06 3.81E+06 6.07E+04 2.32E+02 1.32E+00 1.01E+03 6.02E+04 1.38E+03 6.67E+03 8.62E+05 5.84E+05 2.37E+03 2.01E+01 4.63E+02 4.32E+02 4.01E+05





PT-Accumulation 9.76E+01 2.74E+04 1.68E+00 5.19E+00 2.00E+02 2.14E-01 2.36E+01 3.10E+01 2.27E+02 4.69E+02 1.74E+03 2.20E+01 2.40E+01 1.21E+03 1.47E+04 3.15E+00 3.06E+02 1.68E+02 4.08E-01 6.07E+02 6.13E+03 1.52E+00 3.59E+04 1.66E+02 1.71E+03 4.10E+03 4.10E+04 7.43E+03 1.84E+01 3.98E-01 1.36E+03 1.03E+01 9.32E+00 3.76E-02 4.53E+01 2.00E-01 1.10E+00 1.89E+00 8.31E+03 0.00E+00 0.00E+00 1.07E+03 2.97E+02 3.21E+01 1.18E+00 2.52E-01 8.69E+01 1.36E+01 1.19E+02 3.86E+02 4.10E+03 2.66E+01 1.16E-01 2.47E+01 9.65E-01 6.01E+03

TF-Accumulation 2.06E+02 4.62E+05 4.23E+00 2.53E+01 7.21E+02 3.32E-01 5.49E+04 1.99E+02 4.13E+02 6.64E+02 2.75E+04 1.04E+00 1.86E+02 6.18E+03 1.11E+05 1.88E+01 4.68E+02 2.50E+03 2.69E+00 1.68E+03 1.22E+04 3.50E+00 9.35E+04 4.52E+02 5.74E+03 7.10E+03 4.55E+04 6.24E+03 4.19E+02 7.34E+00 6.55E+04 2.02E+01 5.39E+01 3.49E+00 8.08E+00 5.07E+00 2.75E+00 2.71E+00 6.91E+04 0.00E+00 0.00E+00 2.68E+03 2.95E+03 6.09E+00 5.28E-01 2.99E+00 1.21E+03 1.15E+02 1.84E+02 7.76E+02 5.13E+04 1.78E+02 2.71E+00 1.11E+01 1.93E+01 1.92E+03


LAW Accumulation 1.75E-01 1.24E+03 3.41E-01 8.41E+02 3.69E-04 4.68E-02 4.82E+00 1.30E+00 1.70E+01 9.85E+01 9.66E+01 3.52E-05 4.12E-02 2.67E+02 1.07E+03 4.40E-01 4.32E+01 0.00E+00 8.58E-02 2.47E+02 0.00E+00 3.24E-01 7.60E+03 3.90E-01 2.99E-01 5.08E+02 2.06E+03 1.89E+03 2.08E+00 8.86E-02 1.79E+02 0.00E+00 7.73E-03 8.34E-03 0.00E+00 4.42E-02 2.27E-01 3.88E-01 5.68E+03 3.50E-04 5.93E+01 1.36E+02 4.27E-03 1.54E-05 2.84E-01 5.23E-02 0.00E+00 3.31E+02 0.00E+00 4.99E+01 7.57E-01 9.02E-05 2.56E-02 1.21E-02 6.55E+02 6.11E+02

HLW-Accumulation 5.37E+00 1.30E+03 1.02E-03 1.08E+03 1.19E+01 1.12E-04 7.01E-02 5.74E-01 6.17E+00 2.16E-02 4.19E+01 1.62E-01 1.35E+00 7.02E-02 8.49E+02 3.42E-03 8.42E-01 9.52E+00 3.26E+02 3.59E+01 3.54E+02 8.08E-04 1.05E+03 8.73E+00 9.71E+01 2.41E+00 8.70E+01 1.78E+01 1.04E-01 2.29E-04 9.35E-02 5.61E-01 5.41E-01 2.16E-05 2.39E+00 9.39E-05 7.02E-04 9.26E-04 2.96E+03 0.00E+00 2.94E-02 7.79E-02 1.73E+01 1.69E+00 3.75E-05 1.59E-04 4.70E+00 7.40E-01 5.34E+00 1.63E-01 2.30E+02 1.52E+00 6.44E-05 1.31E+00 5.10E-04 3.04E+02

SLAW-Accumulation 4.56E-01 1.53E+03 5.75E+00 9.23E+02 1.20E-03 8.68E-02 1.46E+01 2.30E+00 2.37E+01 4.55E+03 5.69E+02 4.50E-04 2.79E-01 1.80E+04 1.18E+03 2.93E+01 2.11E+02 0.00E+00 1.63E-01 2.71E+02 0.00E+00 8.14E-01 3.91E+04 7.48E-01 5.98E-01 7.22E+02 1.12E+04 2.96E+03 3.71E+00 1.70E-01 6.27E+02 0.00E+00 1.41E-02 2.09E-02 0.00E+00 8.13E-02 3.74E+00 6.47E+00 6.23E+03 6.09E-03 6.54E+01 1.03E+04 1.30E-02 3.25E-05 2.09E+01 1.07E+00 0.00E+00 3.62E+02 0.00E+00 6.11E+01 1.52E+00 2.53E-04 4.80E-02 2.33E-02 7.18E+02 6.70E+02

LAWPS-Accumulation 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00


LERF-Accumulation 2.46E-02 3.58E-03 1.73E-01 1.91E-01 9.57E-03 7.99E-03 1.14E+00 6.83E-03 7.08E+00 1.61E+00 2.50E-02 1.04E-08 1.28E-02 1.62E+01 1.79E+00 1.65E+00 7.87E-03 1.37E-30 1.53E-02 7.85E-27 2.02E-26 6.28E-02 1.21E+03 7.35E-02 4.61E-02 1.48E-03 3.96E+02 9.65E+02 1.05E+01 1.63E-02 2.96E-02 0.00E+00 8.91E-07 1.67E-03 0.00E+00 7.76E-03 1.18E-01 1.92E-01 4.42E+00 0.00E+00 0.00E+00 1.09E+00 1.10E-01 6.44E-06 2.15E-05 3.19E-02 7.17E-39 6.62E-32 1.04E-34 3.06E+01 7.48E-05 2.47E-05 4.58E-03 2.29E-03 3.44E-02 4.63E-31


Accumulation minus TF and TRU 1.04E+02 3.14E+04 7.95E+00 2.85E+03 2.12E+02 3.56E-01 4.42E+01 3.52E+01 2.81E+02 5.12E+03 2.45E+03 2.22E+01 2.57E+01 1.95E+04 1.78E+04 3.45E+01 5.61E+02 1.78E+02 3.27E+02 1.16E+03 6.49E+03 2.72E+00 8.48E+04 1.76E+02 1.81E+03 5.33E+03 5.48E+04 1.33E+04 3.47E+01 6.74E-01 2.17E+03 1.09E+01 9.88E+00 6.85E-02 4.77E+01 3.33E-01 5.19E+00 8.94E+00 2.32E+04 6.44E-03 1.25E+02 1.15E+04 3.15E+02 3.38E+01 2.23E+01 1.40E+00 9.16E+01 7.07E+02 1.24E+02 5.28E+02 4.34E+03 2.82E+01 1.94E-01 2.60E+01 1.37E+03 7.59E+03


LAW Glass Subtotal (IDF) 1.00E+03 2.31E+07 4.69E+03 2.17E+07 6.95E+00 4.96E+02 6.61E+04 5.67E+03 5.43E+04 7.39E+05 4.95E+05 4.98E-01 3.61E+02 1.13E+06 2.76E+07 0.00E+00 9.38E+05 0.00E+00 7.44E+06 6.38E+06 0.00E+00 6.49E+03 7.88E+07 3.14E+03 1.99E+03 0.00E+00 0.00E+00 0.00E+00 7.02E+04 2.12E+03 0.00E+00 0.00E+00 8.64E+01 2.73E+02 0.00E+00 3.06E+03 3.49E+03 5.04E+03 1.57E+08 #DIV/0! #DIV/0! 0.00E+00 4.68E+01 6.69E-02 1.56E+03 1.85E+03 0.00E+00 8.55E+06 0.00E+00 0.00E+00 7.94E+03 6.75E-01 4.13E+03 8.46E+01 1.69E+07 1.58E+07

LAW Spent Melter Subtotal (IDF) 1.43E+00 2.77E+04 5.59E+00 2.61E+04 1.55E-02 6.33E-01 8.71E+01 7.25E+00 7.55E+01 8.28E+02 6.61E+02 6.07E-04 4.53E-01 1.29E+03 3.31E+04 0.00E+00 1.08E+03 0.00E+00 5.81E+03 7.65E+03 0.00E+00 7.77E+00 1.05E+05 4.28E+00 2.62E+00 0.00E+00 0.00E+00 0.00E+00 8.32E+01 3.33E+00 0.00E+00 0.00E+00 1.07E-01 3.34E-01 0.00E+00 5.42E+00 4.20E+00 6.14E+00 1.84E+05 #DIV/0! #DIV/0! 0.00E+00 5.65E-02 1.12E-04 1.66E+00 2.07E+00 0.00E+00 1.02E+04 0.00E+00 0.00E+00 1.05E+01 9.52E-04 7.07E+00 1.12E-01 2.03E+04 1.89E+04

ETF Solid Waste Form to IDF 2.68E+00 1.84E+01 9.10E+01 5.95E+01 1.02E+00 2.14E+00 2.97E+02 4.85E-01 1.06E+03 8.73E+02 3.90E+00 3.24E-05 3.41E+00 4.83E+03 2.85E+02 9.14E+02 7.05E+00 2.75E-03 7.95E+00 1.14E+00 3.43E+01 2.98E+01 3.48E+05 1.03E+01 5.66E+00 4.64E+01 1.64E+05 1.23E+05 8.62E+03 7.96E+00 2.38E+02 0.00E+00 1.74E-04 1.19E+00 0.00E+00 1.17E+01 6.85E+01 9.87E+01 1.84E+03 #DIV/0! #DIV/0! 1.78E+03 1.23E+01 7.12E-04 1.27E-02 5.67E+01 2.83E-13 1.07E-05 1.47E-05 7.84E+03 8.31E+00 2.50E-05 4.58E-03 2.39E-03 2.30E+01 1.42E-05


Non-IDF Stream 2.81E+03 2.52E+06 9.06E+01 1.52E+06 8.68E+03 2.84E+00 4.80E+05 2.99E+03 6.56E+03 5.00E+03 6.74E+04 2.09E+03 2.36E+03 3.60E+04 1.62E+06 1.37E+01 1.73E+04 4.22E+04 7.81E+05 2.25E+04 4.65E+05 2.49E+01 2.29E+06 6.10E+03 1.18E+05 1.67E+07 6.00E+07 2.54E+07 2.71E+03 1.22E+00 5.13E+06 8.23E+02 7.37E+02 1.70E-01 9.37E+02 1.41E+00 1.60E+02 3.48E+01 5.92E+06 #DIV/0! #DIV/0! 3.82E+06 6.10E+04 2.61E+02 1.34E+00 1.01E+03 6.03E+04 1.38E+03 6.79E+03 8.62E+05 5.88E+05 2.40E+03 2.01E+01 4.84E+02 4.32E+02 4.01E+05

3.82E+03 2.56E+07 4.87E+03 2.33E+07 8.69E+03 5.02E+02 5.46E+05 8.67E+03 6.20E+04 8.27E+05 5.63E+05 2.09E+03 2.73E+03 1.28E+06 2.93E+07 1.97E+03 9.56E+05 4.22E+04 8.23E+06 6.41E+06 4.65E+05 6.55E+03 8.16E+07 9.25E+03 1.20E+05 1.67E+07 6.01E+07 2.55E+07 8.16E+04 2.13E+03 5.14E+06 8.23E+02 8.23E+02 2.75E+02 9.37E+02 3.08E+03 3.72E+03 5.18E+03 1.63E+08 #DIV/0! #DIV/0! 3.82E+06 6.11E+04 2.61E+02 1.56E+03 2.91E+03 6.03E+04 8.56E+06 6.79E+03 8.70E+05 5.96E+05 2.40E+03 4.15E+03 5.68E+02 1.69E+07 1.62E+07

100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% #DIV/0! #DIV/0! 100% 100% 102% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100%


HEPA fraction 4.53% 17.39% 17.89% 62.10% 6.43% 0.15% 5.17% 50.79% 0.21% 0.00% 94.18% NR 0.00% 0.00% 44.22% 0.00% 56.46% 7.86% 91.84% 69.10% 12.79% NR 40.68% 4.20% 13.13% NR NR NR 61.05% 1.03% 0.00% #DIV/0! 8.09% 5.61% 5.04% 78.35% 5.42% 31.35% 41.49% NR NR NR 15.98% 0.00% 63.36% 20.43% 7.69% 71.77% 23.04% NR 8.06% 41.24% 0.23% NR 87.47% 60.66%

IX Resin fraction 43.06% 62.12% 53.58% 0.54% 22.10% 93.91% 29.47% 23.43% 90.28% 95.63% 5.35% NR 0.00% 0.08% 0.00% 0.00% 42.37% 5.18% 0.04% 0.12% 0.00% NR 55.24% 45.56% 38.04% NR NR NR 19.53% 83.67% 0.00% #DIV/0! 0.00% 61.81% 76.38% 0.00% 72.52% 63.57% 0.12% NR NR NR 0.23% 0.00% 34.99% 4.19% 25.51% 0.00% 38.40% NR 0.00% 16.62% 93.95% NR 0.01% 0.38%

LAW and HLW Carbon Bed fraction 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR 0.00% 98.32% 0.00% 100.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR 0.00% 0.00% 0.00% NR NR NR 0.00% 0.00% 0.00% #DIV/0! 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR NR NR 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR 0.00% 0.00% 0.00% NR 0.00% 0.00%

Other Debris fraction 52.41% 20.48% 28.53% 37.37% 71.47% 5.95% 65.36% 25.78% 9.52% 4.37% 0.47% NR 100.00% 0.01% 55.78% 0.00% 1.17% 86.96% 8.12% 30.78% 87.21% NR 4.08% 50.24% 48.83% NR NR NR 19.42% 15.31% 0.00% #DIV/0! 91.91% 32.59% 18.58% 21.65% 22.06% 5.08% 58.40% NR NR NR 83.79% 100.00% 1.65% 75.39% 66.80% 28.23% 38.56% NR 91.94% 42.15% 5.83% NR 12.52% 38.96%

HLW Silver Mordenite Absorbent fraction 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR 0.00% 1.59% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR 0.00% 0.00% 0.00% NR NR NR 0.00% 0.00% 0.00% #DIV/0! 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR NR NR 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR 0.00% 0.00% 0.00% NR 0.00% 0.00%


HEPA Filters Debris 3.43E-03 3.79E+00 4.04E-02 1.79E+01 1.86E-03 8.13E-08 1.29E-03 1.82E-01 1.73E-06 0.00E+00 7.02E+02 NR 0.00E+00 1.68E-01 5.76E-02 0.00E+00 1.76E+02 6.87E-08 1.05E-01 6.02E-03 1.09E-02 NR 1.86E+03 1.27E-06 5.77E-02 NR NR NR 7.23E+00 2.45E-06 0.00E+00 #DIV/0! 2.30E-05 5.91E-05 3.96E-08 6.38E-03 6.12E-04 1.26E-01 8.33E-02 NR NR NR 5.70E-03 0.00E+00 6.14E-01 6.18E-03 3.89E-06 2.05E-04 3.42E-05 NR 1.11E-04 1.17E-05 1.05E-06 NR 1.36E-01 1.93E-02

IX Resin Non-Debris 3.26E-02 1.35E+01 1.21E-01 1.54E-01 6.39E-03 5.22E-05 7.38E-03 8.39E-02 7.54E-04 7.70E+04 3.99E+01 NR 0.00E+00 8.98E+01 5.19E-07 2.34E-02 1.32E+02 4.53E-08 4.16E-05 1.01E-05 1.87E-08 NR 2.53E+03 1.38E-05 1.67E-01 NR NR NR 2.31E+00 1.99E-04 0.00E+00 #DIV/0! 5.94E-09 6.51E-04 6.00E-07 1.20E-08 8.18E-03 2.55E-01 2.39E-04 NR NR NR 8.18E-05 0.00E+00 3.39E-01 1.27E-03 1.29E-05 4.95E-12 5.70E-05 NR 1.37E-09 4.72E-06 4.35E-04 NR 1.21E-05 1.21E-04

LAW and HLW Carbon Beds Non-Debris 8.72E-13 2.55E-09 5.69E-11 1.33E-08 2.51E-13 1.24E-15 2.04E-13 2.72E-10 1.74E-14 4.22E-02 7.29E-10 NR 0.00E+00 1.05E+05 3.43E-11 1.05E+03 1.07E-07 1.52E-18 6.31E-11 3.62E-12 1.08E-11 NR 1.18E-06 3.26E-16 5.17E-11 NR NR NR 5.37E-09 4.75E-15 0.00E+00 #DIV/0! 3.19E-16 3.36E-14 3.16E-17 1.82E-11 7.37E-13 1.32E-10 4.99E-11 NR NR NR 1.01E-11 0.00E+00 3.79E-10 1.01E-11 1.06E-15 1.23E-13 1.59E-14 NR 1.56E-15 6.97E-15 1.03E-14 NR 8.11E-11 1.16E-11

Other Debris Debris 3.97E-02 4.46E+00 6.45E-02 1.08E+01 2.07E-02 3.31E-06 1.64E-02 9.23E-02 7.95E-05 3.51E+03 3.49E+00 NR 3.26E-03 5.57E+00 7.26E-02 2.10E-03 3.65E+00 7.61E-07 9.28E-03 2.68E-03 7.40E-02 NR 1.87E+02 1.52E-05 2.15E-01 NR NR NR 2.30E+00 3.64E-05 0.00E+00 #DIV/0! 2.62E-04 3.43E-04 1.46E-07 1.76E-03 2.49E-03 2.04E-02 1.17E-01 NR NR NR 2.99E-02 2.27E-07 1.60E-02 2.28E-02 3.38E-05 8.05E-05 5.73E-05 NR 1.27E-03 1.20E-05 2.70E-05 NR 1.94E-02 1.24E-02

HLW Silver Mordenite Absorbent Non-Debris 7.01E-14 8.38E-11 8.35E-11 1.53E-10 1.01E-13 1.66E-19 2.89E-14 4.15E-10 5.65E-17 2.18E-07 6.13E-10 NR 0.00E+00 1.69E+03 2.54E-13 8.26E-03 1.55E-09 9.49E-19 1.31E-13 2.34E-14 1.87E-11 NR 2.02E-09 1.81E-17 5.61E-11 NR NR NR 2.74E-09 6.26E-17 0.00E+00 #DIV/0! 6.38E-16 1.42E-15 3.63E-19 3.64E-11 7.29E-13 1.31E-10 2.06E-13 NR NR NR 2.02E-11 0.00E+00 3.19E-13 1.99E-11 7.50E-17 8.73E-16 1.86E-15 NR 3.11E-15 5.24E-17 3.11E-19 NR 1.44E-15 4.23E-14

SSW Total 7.57E-02 2.18E+01 2.26E-01 2.88E+01 2.89E-02 5.56E-05 2.50E-02 3.58E-01 8.35E-04 8.05E+04 7.46E+02 NR 3.26E-03 1.06E+05 1.30E-01 1.05E+03 3.11E+02 8.75E-07 1.14E-01 8.72E-03 8.48E-02 NR 4.58E+03 3.02E-05 4.40E-01 NR NR NR 1.18E+01 2.38E-04 0.00E+00 #DIV/0! 2.85E-04 1.05E-03 7.86E-07 8.14E-03 1.13E-02 4.01E-01 2.01E-01 NR NR NR 3.57E-02 2.27E-07 9.70E-01 3.03E-02 5.06E-05 2.85E-04 1.49E-04 NR 1.38E-03 2.84E-05 4.63E-04 NR 1.55E-01 3.19E-02

BBI 5.91E+05 1.99E+03 8.20E+04

Check 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% N/A 100% 100% 100% 100% 100% 100% 100% 100% 100% N/A 100% 100% 100% N/A N/A N/A 100% 100% 0% #DIV/0! 100% 100% 100% 100% 100% 100% 100% N/A N/A N/A 100% 100% 100% 100% 100% 100% 100% N/A 100% 100% 100% N/A 100% 100%

SE

CT

ION

1S

EC

TIO

N 2

SE

CT

ION

3A

SE

CT

ION

4S

EC

TIO

N 5

A



A-15/A-16

Table A-7. Run Case 10A Radionuclides.

SVF-4096, IDF PA Case 10A - Single Pass Tc_Tc-99 Retention in ILAW Glass of 32% - Mass Balance, MMR-50053




ETF Solid Waste Form to IDF 2.31E-01 3.86E+01 1.01E+03 4.35E+00 1.87E+01 4.82E-02 2.51E+03 2.37E+03 2.53E+00 1.33E-03 5.19E-07 5.47E-06 6.81E-06 2.31E-03 1.56E-01 6.10E+01 2.52E-10 5.77E-10 5.73E-10 1.22E-03 8.20E-02 3.04E-02 1.24E-03 8.87E-04 1.54E-01 2.10E+00 2.76E-02 3.89E+01 8.32E+00 1.17E+02 6.55E+01 1.32E+00 8.35E-04 5.79E-02 1.45E-01 3.21E+00 2.75E+00 5.00E-01 8.67E-05 4.47E+01 3.53E+01 2.01E+03 2.01E+03 3.11E-07 5.66E-03 1.80E+04


Non-IDF Stream 2.65E-03 1.92E+02 4.92E-01 1.31E-01 5.02E-01 7.12E+02 3.87E+07 3.65E+07 8.25E+02 3.20E+06 8.10E+02 4.88E+04 2.42E+04 8.21E-06 -8.62E+00 -2.33E+02 1.42E+00 4.74E+00 6.61E+00 8.19E+00 6.37E+02 2.13E+02 8.71E+00 6.03E+00 8.99E+01 2.24E+03 1.93E+02 4.29E+04 9.07E+03 1.42E+05 7.13E+04 7.13E-02 6.75E-01 6.39E+01 4.86E-03 1.06E-01 2.80E+03 1.39E+03 3.72E+03 1.25E+05 -3.15E-03 4.35E+07 4.35E+07 3.34E+03 2.83E+03 5.47E+00





PT-Accumulation 1.89E-04 2.25E+00 1.15E-01 5.62E-02 3.46E-02 1.27E+00 2.79E+05 2.64E+05 1.47E-01 6.56E+04 1.45E+01 7.07E+02 2.88E+02 1.19E-06 -2.99E-01 -6.06E+00 9.63E-03 9.08E-02 2.61E-02 6.32E-02 4.38E+00 2.47E+00 1.03E-01 6.42E-02 1.19E+00 3.82E+01 2.31E+00 9.12E+02 1.92E+02 1.70E+03 1.23E+03 1.13E-02 1.34E-02 8.83E-01 1.07E-03 2.35E-02 1.98E+00 3.55E+01 7.75E+01 3.08E+03 2.26E-02 3.32E+05 3.32E+05 1.30E+02 1.13E+02 3.64E+00



LAW Accumulation 5.49E-05 3.78E-01 3.57E-02 1.39E-02 1.38E-03 2.11E-06 3.85E-01 3.64E-01 2.24E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.30E-07 2.57E-03 1.23E-01 0.00E+00 0.00E+00 0.00E+00 7.24E-06 5.04E-04 2.77E-04 1.16E-05 7.37E-06 5.50E-04 1.06E-02 2.59E-04 2.54E-01 5.35E-02 1.91E-01 3.41E-01 3.06E-03 3.72E-06 1.27E-04 2.95E-04 6.52E-03 4.54E-02 1.15E-02 0.00E+00 9.98E-01 6.51E-03 1.12E+02 1.12E+02 0.00E+00 0.00E+00 1.47E+00

HLW-Accumulation 2.86E-08 2.45E-03 5.74E-05 2.70E-05 9.60E-04 4.69E-02 1.19E+04 1.12E+04 1.58E-05 3.40E+03 7.53E-01 3.72E+01 1.52E+01 4.95E-10 -1.58E-02 -3.85E-01 5.43E-04 4.73E-03 1.56E-03 3.37E-03 2.38E-01 1.28E-01 5.34E-03 3.40E-03 5.88E-02 1.97E+00 1.19E-01 4.65E+01 9.82E+00 8.74E+01 6.28E+01 5.87E-06 6.86E-04 4.50E-02 5.63E-07 1.24E-05 5.14E+00 1.74E+00 4.02E+00 1.50E+02 8.62E-06 1.71E+04 1.71E+04 6.76E+00 5.50E+00 2.63E-04

SLAW-Accumulation 6.52E-05 6.36E-01 3.83E-02 1.72E-02 1.54E-03 2.28E-06 4.20E-01 3.97E-01 3.60E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.66E-07 3.11E-03 1.15E-01 0.00E+00 0.00E+00 0.00E+00 1.09E-05 7.43E-04 4.39E-04 1.84E-05 1.12E-05 6.87E-04 1.68E-02 4.12E-04 4.06E-01 8.57E-02 2.26E-01 5.44E-01 3.85E-03 5.96E-06 1.53E-04 3.48E-04 7.68E-03 4.24E-02 2.11E-02 0.00E+00 1.84E+00 7.25E-03 2.30E+02 2.30E+02 0.00E+00 0.00E+00 1.47E+00



LERF-Accumulation 2.22E-05 1.62E-01 1.71E-01 4.43E-03 1.82E-02 8.82E-06 1.86E+00 1.76E+00 3.29E-03 4.08E-18 1.62E-21 1.64E-20 2.10E-20 1.74E-06 7.31E-04 5.18E-01 7.85E-25 1.57E-24 1.79E-24 2.03E-06 1.42E-04 7.82E-05 3.27E-06 2.05E-06 1.24E-04 3.95E-03 7.31E-05 8.53E-02 1.81E-02 9.07E-02 1.19E-01 9.62E-04 2.08E-06 5.96E-05 9.05E-05 2.00E-03 2.75E+00 4.81E-03 3.38E-21 4.17E-01 3.37E-02 1.96E+01 1.96E+01 3.35E-22 6.39E-20 1.54E+01


Accumulation minus TF and TRU 3.32E-04 3.43E+00 3.61E-01 9.26E-02 5.67E-02 1.31E+00 2.91E+05 2.75E+05 2.09E-01 6.90E+04 1.52E+01 7.44E+02 3.03E+02 3.64E-06 -3.08E-01 -5.69E+00 1.02E-02 9.55E-02 2.77E-02 6.66E-02 4.62E+00 2.59E+00 1.09E-01 6.76E-02 1.25E+00 4.02E+01 2.43E+00 9.59E+02 2.02E+02 1.79E+03 1.29E+03 1.92E-02 1.41E-02 9.28E-01 1.80E-03 3.98E-02 9.97E+00 3.73E+01 8.16E+01 3.23E+03 7.02E-02 3.50E+05 3.50E+05 1.37E+02 1.18E+02 2.20E+01








100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 161% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100%




ETF Solid Waste Form to IDF 4.70E-14 4.67E+00 2.04E-02 4.35E+00 1.88E+01 2.60E-08 9.39E+02 8.87E+02 2.51E+00 9.72E-04 5.85E-08 1.73E-07 1.30E-08 2.27E-03 3.71E-02 1.33E-01 2.53E-10 5.88E-10 5.75E-10 8.03E-04 8.25E-02 3.08E-02 1.26E-03 8.97E-04 1.56E-01 1.52E+00 2.79E-02 3.97E+01 8.45E+00 1.12E+02 8.41E+00 1.07E+00 8.51E-04 5.85E-02 5.21E-02 6.18E-01 2.46E-01 5.12E-01 3.10E-07 3.41E+01 3.53E+01 7.18E+02 7.18E+02 3.23E-07 9.24E-04 1.80E+04















BBI 2.94E+01 3.90E+07 4.76E+07 2.65E+04



HEPA Filters Debris NR NR NR 9.29E-03 4.52E-02 2.13E-08 7.12E+02 6.72E+02 0.00E+00 0.00E+00 4.99E-08 8.40E-07 2.52E-08 NR NR NR NR NR NR NR 1.04E-06 3.49E-07 1.42E-08 1.05E-08 1.05E-06 5.08E-03 3.13E-07 1.30E-02 1.27E-02 6.59E-03 7.26E-05 NR NR NR NR NR 0.00E+00 2.39E-04 3.77E-08 1.61E-02 2.99E-03 6.15E+00 NR NR NR 1.20E+01

IX Resin Non-Debris NR NR NR 7.85E-03 5.99E-03 3.63E-09 1.30E+02 1.23E+02 0.00E+00 0.00E+00 5.85E-09 9.92E-08 2.94E-09 NR NR NR NR NR NR NR 5.06E-13 1.75E-13 6.05E-15 7.16E-15 8.10E-07 5.36E-08 1.60E-13 1.38E-07 1.35E-07 3.56E-04 7.89E-10 NR NR NR NR NR 0.00E+00 8.50E-05 1.15E-08 5.56E-03 1.08E-03 8.77E-03 NR NR NR 1.63E+00

LAW and HLW Carbon Beds Non-Debris NR NR NR 1.86E-13 1.60E+00 7.55E-18 2.21E-07 2.09E-07 0.00E+00 0.00E+00 1.58E-19 2.78E-18 8.23E-20 NR NR NR NR NR NR NR 5.65E-19 2.10E-19 8.82E-21 8.12E-21 1.92E-17 2.85E-15 1.92E-19 7.34E-15 7.15E-15 1.24E-14 4.18E-17 NR NR NR NR NR 0.00E+00 1.75E-14 3.89E-19 1.16E-12 3.03E-13 1.09E-09 NR NR NR 1.81E-09

Other Debris Debris NR NR NR 7.87E-04 3.95E-04 1.56E-08 5.59E+02 5.28E+02 0.00E+00 0.00E+00 2.08E-08 3.54E-07 1.05E-08 NR NR NR NR NR NR NR 4.68E-07 1.57E-07 6.42E-09 4.75E-09 5.29E-08 2.32E-03 1.45E-07 5.95E-03 5.83E-03 2.37E-03 3.41E-05 NR NR NR NR NR 0.00E+00 9.53E-05 1.09E-08 6.24E-03 9.04E-05 3.20E+00 NR NR NR 7.39E-02

HLW Silver Mordenite Absorbent Non-Debris NR NR NR 1.80E-16 2.73E+00 1.50E-17 4.38E-07 4.14E-07 0.00E+00 0.00E+00 3.98E-20 8.56E-19 2.48E-20 NR NR NR NR NR NR NR 1.13E-18 4.19E-19 1.76E-20 1.62E-20 1.25E-20 5.70E-15 3.84E-19 1.47E-14 1.43E-14 7.31E-15 8.36E-17 NR NR NR NR NR 0.00E+00 2.81E-14 8.32E-20 1.87E-12 3.72E-14 2.17E-09 NR NR NR 1.53E-12SE

CT

ION

5B

SE

CT

ION

1S

EC

TIO

N 2

SE

CT

ION

3A

SE

CT

ION

4S

EC

TIO

N 5

AS

EC

TIO

N 3

B



A-17/A-18

Table A-8. Run Case 10A Chemicals.

SVF-4096, IDF PA Case 10A - Single Pass Tc_Tc-99 Retention in ILAW Glass of 32% - Mass Balance, MMR-50053



LAW Spent Melter Subtotal (IDF) 1.57E+00 2.66E+04 4.09E+00 2.50E+04 1.54E-02 5.93E-01 8.74E+01 7.42E+00 6.97E+01 5.64E+02 6.50E+02 6.16E-04 5.29E-01 8.46E+02 3.18E+04 0.00E+00 1.06E+03 4.30E-08 2.53E+03 7.34E+03 4.40E-08 8.30E+00 1.10E+05 4.58E+00 3.17E+00 0.00E+00 0.00E+00 0.00E+00 9.95E+01 1.47E+00 0.00E+00 0.00E+00 1.02E-01 2.36E-01 0.00E+00 2.53E+00 3.35E+00 4.39E+00 1.72E+05 0.00E+00 3.21E+03 0.00E+00 5.62E-01 1.16E-04 6.66E-01 1.78E+00 5.38E-07 9.83E+03 1.22E-07 2.44E-02 1.14E+01 1.11E-03 2.15E+00 1.22E-01 1.95E+04 1.82E+04

ETF Solid Waste Form to IDF 2.31E+01 1.14E+04 1.17E+03 1.60E+02 7.62E-01 5.81E+00 1.34E+03 6.52E+01 1.23E+03 3.68E+05 3.43E+04 9.02E-02 3.36E+01 6.05E+05 3.26E+02 1.64E+03 4.67E+04 2.73E-03 2.34E+01 1.14E+00 3.38E+01 1.37E+02 1.76E+06 3.39E+01 2.29E+01 2.82E+04 2.22E+06 8.88E+04 7.96E+03 2.15E+01 5.50E+04 0.00E+00 6.65E-01 5.58E+00 0.00E+00 3.12E+01 8.75E+02 1.26E+03 1.49E+03 0.00E+00 0.00E+00 9.32E+05 1.08E+01 1.04E-03 1.06E+03 5.45E+02 5.20E-06 1.08E-05 5.66E-05 5.19E+03 8.27E+01 8.63E-05 3.04E-03 5.71E-03 3.14E+01 1.42E-05


Non-IDF Stream 2.62E+03 2.46E+06 8.75E+01 1.53E+06 8.62E+03 2.81E+00 4.83E+05 1.40E+03 6.55E+03 4.99E+03 6.68E+04 2.07E+03 2.35E+03 3.31E+04 1.39E+06 9.80E+00 1.60E+04 4.20E+04 7.28E+05 2.29E+04 4.58E+05 2.34E+01 1.94E+06 5.93E+03 1.16E+05 1.68E+07 5.74E+07 2.55E+07 2.70E+03 4.50E-01 5.07E+06 7.99E+02 7.32E+02 8.71E-02 9.20E+02 5.46E-01 1.58E+02 3.33E+01 5.42E+06 -3.81E+03 -2.38E+06 2.89E+06 6.23E+04 2.42E+02 3.22E-01 7.10E+02 6.00E+04 1.38E+03 6.63E+03 8.64E+05 5.80E+05 2.37E+03 4.37E+01 4.72E+02 4.31E+02 4.05E+05





PT-Accumulation 3.66E+01 3.47E+04 7.55E-01 1.97E+00 6.26E+01 5.52E-02 9.20E+02 2.48E+00 1.66E+02 1.05E+02 2.83E+03 1.54E+01 1.49E+01 9.94E+02 8.50E+03 3.33E-01 1.49E+02 1.44E+02 3.30E-01 2.09E+02 8.90E+03 8.26E-01 3.17E+04 5.71E+01 1.01E+03 2.96E+03 5.36E+04 5.18E+03 1.78E+01 5.61E-01 4.22E+03 2.09E+01 1.56E+01 7.57E-03 1.84E+01 6.23E-02 4.59E-01 7.55E-01 8.82E+03 0.00E+00 0.00E+00 9.77E+02 2.45E+02 2.09E+01 2.14E-01 3.56E-01 2.37E+02 1.30E+01 1.57E+02 3.07E+02 6.92E+03 2.67E+01 3.77E-02 8.95E+00 1.21E+00 2.21E+03

TF-Accumulation 2.05E+02 4.69E+05 4.23E+00 2.53E+01 7.17E+02 3.31E-01 5.49E+04 1.98E+02 4.15E+02 6.65E+02 2.82E+04 1.04E+00 1.85E+02 6.22E+03 1.11E+05 1.88E+01 4.70E+02 2.50E+03 2.69E+00 1.67E+03 1.22E+04 3.51E+00 9.30E+04 4.52E+02 5.74E+03 7.11E+03 4.55E+04 6.25E+03 4.19E+02 7.34E+00 6.54E+04 2.21E+01 5.53E+01 3.49E+00 7.92E+00 5.07E+00 2.76E+00 2.71E+00 6.94E+04 0.00E+00 0.00E+00 2.69E+03 2.93E+03 7.36E+00 5.30E-01 3.00E+00 1.21E+03 1.15E+02 1.88E+02 7.78E+02 5.16E+04 1.79E+02 2.71E+00 1.11E+01 1.93E+01 1.85E+03


LAW Accumulation 2.67E-01 1.49E+03 2.43E-01 9.06E+02 1.51E-02 1.53E-02 8.63E+00 3.65E-01 3.04E+00 3.62E+01 4.74E+01 2.00E-05 1.31E-02 3.75E+02 1.16E+03 1.10E-01 2.34E+01 0.00E+00 9.16E-02 2.66E+02 0.00E+00 2.29E-01 9.09E+03 4.48E-01 3.29E-01 4.35E+02 1.70E+03 2.26E+03 2.03E+00 1.57E-01 7.45E+02 0.00E+00 4.33E-03 2.12E-03 0.00E+00 1.70E-02 1.46E-01 2.46E-01 6.13E+03 3.54E-06 5.93E+01 1.33E+02 8.17E-02 5.89E-05 8.68E-02 9.88E-02 0.00E+00 3.56E+02 0.00E+00 5.08E+01 7.76E-01 1.69E-04 9.85E-03 1.39E-02 7.06E+02 6.58E+02

HLW-Accumulation 1.02E+00 1.53E+03 4.05E-04 1.02E+03 3.44E+00 3.09E-05 4.47E+01 3.04E-03 5.08E+00 8.17E-03 6.92E+01 6.55E-01 8.11E-01 7.15E-02 4.58E+02 3.86E-04 2.62E+00 7.56E+00 4.60E+02 1.12E+01 4.57E+02 4.47E-04 6.10E+02 2.36E+00 5.27E+01 1.81E+00 1.96E+02 5.27E+00 1.17E-01 2.88E-04 9.78E-02 1.06E+00 7.93E-01 3.57E-06 1.04E+00 2.91E-05 2.49E-04 3.29E-04 2.85E+03 3.86E-06 2.36E-02 3.76E-02 1.31E+01 1.07E+00 1.55E-05 1.73E-04 1.42E+01 7.19E-01 6.56E+00 7.50E-02 3.58E+02 1.40E+00 1.90E-05 4.68E-01 6.66E-04 1.30E+02

SLAW-Accumulation 3.66E-01 2.05E+03 2.61E-01 8.13E+02 1.74E-02 1.73E-02 1.28E+01 5.53E-01 8.32E+00 3.72E+01 1.58E+02 2.25E-05 1.44E-02 3.92E+02 1.05E+03 9.51E-02 2.77E+01 0.00E+00 1.05E-01 2.39E+02 0.00E+00 2.56E-01 1.41E+04 7.28E-01 5.56E-01 7.01E+02 2.79E+03 4.78E+03 2.56E+00 1.88E-01 1.28E+03 0.00E+00 6.93E-03 2.61E-03 0.00E+00 2.11E-02 1.52E-01 2.69E-01 5.51E+03 1.60E-05 3.51E+01 2.15E+02 1.54E-01 7.19E-05 8.64E-02 1.49E-01 0.00E+00 3.20E+02 0.00E+00 8.04E+01 1.23E+00 2.25E-04 1.31E-02 2.26E-02 6.33E+02 5.91E+02

LAWPS-Accumulation 6.61E-04 2.79E+00 6.69E-03 1.33E-02 3.95E-07 3.27E-04 8.51E-03 6.06E-04 0.00E+00 1.20E+00 7.40E-02 2.16E-03 5.36E-04 3.53E-01 2.91E-02 4.53E-04 1.87E+00 0.00E+00 1.51E-03 0.00E+00 0.00E+00 1.17E-02 4.83E+01 2.90E-03 1.36E-03 1.59E+01 2.86E+01 1.56E+01 1.79E-02 3.20E-05 6.68E-01 0.00E+00 2.28E-05 4.12E-06 0.00E+00 2.68E-05 4.22E-03 6.65E-03 4.54E-02 0.00E+00 0.00E+00 6.91E-01 2.18E-05 1.33E-08 1.99E-03 2.88E-05 0.00E+00 0.00E+00 0.00E+00 4.12E-01 6.47E-03 3.75E-07 7.95E-05 3.73E-06 4.77E-03 0.00E+00


LERF-Accumulation 1.33E-01 6.50E+01 1.29E+00 1.66E-01 1.69E-03 4.76E-03 5.66E+00 1.14E-01 6.54E+00 3.08E+02 1.62E+02 6.89E-05 2.77E-02 2.86E+03 1.93E+00 1.49E+00 2.61E+01 1.30E-21 3.06E-02 4.73E-23 1.34E-21 1.24E-01 5.42E+03 1.83E-01 1.37E-01 2.01E+01 2.59E+03 1.07E+03 8.08E+00 4.94E-02 2.99E+02 0.00E+00 1.46E-03 9.76E-04 0.00E+00 5.05E-03 7.53E-01 1.29E+00 4.78E+00 0.00E+00 0.00E+00 6.50E+01 4.89E-02 1.29E-05 9.10E-01 5.74E-01 1.62E-20 8.05E-23 1.31E-19 1.79E+01 2.19E-01 8.63E-05 3.04E-03 5.70E-03 5.21E-02 1.28E-22





LAW Spent Melter Subtotal (IDF) 1.59E+00 2.66E+04 4.09E+00 2.50E+04 1.55E-02 5.93E-01 8.75E+01 7.42E+00 6.99E+01 5.64E+02 6.54E+02 6.21E-04 5.32E-01 8.49E+02 3.18E+04 0.00E+00 1.06E+03 4.32E-08 2.53E+03 7.34E+03 4.49E-08 8.30E+00 1.10E+05 4.61E+00 3.20E+00 0.00E+00 0.00E+00 0.00E+00 9.95E+01 1.47E+00 0.00E+00 0.00E+00 1.04E-01 2.36E-01 0.00E+00 2.54E+00 3.35E+00 4.40E+00 1.72E+05 #DIV/0! #DIV/0! 0.00E+00 5.64E-01 1.26E-04 6.66E-01 1.78E+00 5.40E-07 9.83E+03 1.25E-07 2.44E-02 1.15E+01 1.12E-03 2.15E+00 1.24E-01 1.95E+04 1.82E+04

ETF Solid Waste Form to IDF 2.33E+01 1.14E+04 1.17E+03 1.60E+02 7.68E-01 5.82E+00 1.34E+03 6.52E+01 1.24E+03 3.69E+05 3.45E+04 9.09E-02 3.38E+01 6.07E+05 3.26E+02 1.64E+03 4.67E+04 2.74E-03 2.34E+01 1.14E+00 3.45E+01 1.37E+02 1.76E+06 3.41E+01 2.31E+01 2.82E+04 2.22E+06 8.89E+04 7.97E+03 2.15E+01 5.50E+04 0.00E+00 6.78E-01 5.58E+00 0.00E+00 3.12E+01 8.76E+02 1.26E+03 1.49E+03 #DIV/0! #DIV/0! 9.32E+05 1.09E+01 1.13E-03 1.06E+03 5.46E+02 5.23E-06 1.08E-05 5.79E-05 5.19E+03 8.37E+01 8.73E-05 3.04E-03 5.80E-03 3.14E+01 1.42E-05


Non-IDF Stream 2.64E+03 2.46E+06 8.76E+01 1.53E+06 8.69E+03 2.81E+00 4.84E+05 1.40E+03 6.57E+03 5.00E+03 6.72E+04 2.09E+03 2.36E+03 3.32E+04 1.39E+06 9.81E+00 1.60E+04 4.22E+04 7.28E+05 2.29E+04 4.67E+05 2.34E+01 1.94E+06 5.96E+03 1.17E+05 1.68E+07 5.75E+07 2.55E+07 2.71E+03 4.50E-01 5.08E+06 8.21E+02 7.46E+02 8.71E-02 9.39E+02 5.46E-01 1.58E+02 3.33E+01 5.42E+06 #DIV/0! #DIV/0! 2.89E+06 6.25E+04 2.62E+02 3.23E-01 7.11E+02 6.03E+04 1.38E+03 6.79E+03 8.65E+05 5.87E+05 2.40E+03 4.37E+01 4.79E+02 4.31E+02 4.05E+05


100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% #DIV/0! #DIV/0! 100% 100% 101% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100%


HEPA fraction 4.53% 17.39% 17.89% 62.10% 6.43% 0.15% 5.17% 50.79% 0.21% 0.00% 94.18% NR 0.00% 0.00% 44.22% 0.00% 56.46% 7.86% 91.84% 69.10% 12.79% NR 40.68% 4.20% 13.13% NR NR NR 61.05% 1.03% 0.00% #DIV/0! 8.09% 5.61% 5.04% 78.35% 5.42% 31.35% 41.49% NR NR NR 15.98% 0.00% 63.36% 20.43% 7.69% 71.77% 23.04% NR 8.06% 41.24% 0.23% NR 87.47% 60.66%

IX Resin fraction 43.06% 62.12% 53.58% 0.54% 22.10% 93.91% 29.47% 23.43% 90.28% 95.63% 5.35% NR 0.00% 0.08% 0.00% 0.00% 42.37% 5.18% 0.04% 0.12% 0.00% NR 55.24% 45.56% 38.04% NR NR NR 19.53% 83.67% 0.00% #DIV/0! 0.00% 61.81% 76.38% 0.00% 72.52% 63.57% 0.12% NR NR NR 0.23% 0.00% 34.99% 4.19% 25.51% 0.00% 38.40% NR 0.00% 16.62% 93.95% NR 0.01% 0.38%

LAW and HLW Carbon Bed fraction 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR 0.00% 98.32% 0.00% 100.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR 0.00% 0.00% 0.00% NR NR NR 0.00% 0.00% 0.00% #DIV/0! 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR NR NR 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR 0.00% 0.00% 0.00% NR 0.00% 0.00%

Other Debris fraction 52.41% 20.48% 28.53% 37.37% 71.47% 5.95% 65.36% 25.78% 9.52% 4.37% 0.47% NR 100.00% 0.01% 55.78% 0.00% 1.17% 86.96% 8.12% 30.78% 87.21% NR 4.08% 50.24% 48.83% NR NR NR 19.42% 15.31% 0.00% #DIV/0! 91.91% 32.59% 18.58% 21.65% 22.06% 5.08% 58.40% NR NR NR 83.79% 100.00% 1.65% 75.39% 66.80% 28.23% 38.56% NR 91.94% 42.15% 5.83% NR 12.52% 38.96%

HLW Silver Mordenite Absorbent fraction 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR 0.00% 1.59% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR 0.00% 0.00% 0.00% NR NR NR 0.00% 0.00% 0.00% #DIV/0! 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR NR NR 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR 0.00% 0.00% 0.00% NR 0.00% 0.00%


HEPA Filters Debris 4.62E-03 3.97E+00 4.72E-02 1.84E+01 2.34E-03 7.70E-08 1.24E-03 2.43E-01 1.54E-06 0.00E+00 6.52E+02 NR 0.00E+00 8.69E-02 6.64E-02 0.00E+00 1.67E+02 6.88E-08 1.09E-01 6.14E-03 1.09E-02 NR 1.86E+03 1.25E-06 7.72E-02 NR NR NR 7.53E+00 2.32E-06 0.00E+00 #DIV/0! 3.13E-05 5.97E-05 3.97E-08 6.04E-03 4.71E-04 1.35E-01 7.21E-02 NR NR NR 5.85E-03 0.00E+00 5.13E-01 5.54E-03 3.89E-06 2.05E-04 3.42E-05 NR 1.11E-04 1.18E-05 9.97E-07 NR 1.42E-01 1.95E-02

IX Resin Non-Debris 4.39E-02 1.42E+01 1.41E-01 1.59E-01 8.03E-03 4.95E-05 7.04E-03 1.12E-01 6.70E-04 4.26E+04 3.70E+01 NR 0.00E+00 4.63E+01 5.98E-07 7.19E-03 1.25E+02 4.54E-08 4.33E-05 1.03E-05 1.88E-08 NR 2.53E+03 1.36E-05 2.24E-01 NR NR NR 2.41E+00 1.89E-04 0.00E+00 #DIV/0! 8.08E-09 6.58E-04 6.01E-07 1.14E-08 6.30E-03 2.75E-01 2.07E-04 NR NR NR 8.39E-05 0.00E+00 2.84E-01 1.13E-03 1.29E-05 4.95E-12 5.70E-05 NR 1.37E-09 4.77E-06 4.12E-04 NR 1.27E-05 1.22E-04

LAW and HLW Carbon Beds Non-Debris 1.17E-12 2.66E-09 6.65E-11 1.37E-08 3.16E-13 1.17E-15 1.94E-13 3.63E-10 1.55E-14 2.33E-02 6.76E-10 NR 0.00E+00 5.39E+04 3.95E-11 3.22E+02 1.02E-07 1.52E-18 6.58E-11 3.69E-12 1.09E-11 NR 1.18E-06 3.22E-16 6.91E-11 NR NR NR 5.59E-09 4.51E-15 0.00E+00 #DIV/0! 4.34E-16 3.39E-14 3.16E-17 1.72E-11 5.68E-13 1.43E-10 4.33E-11 NR NR NR 1.04E-11 0.00E+00 3.17E-10 9.07E-12 1.06E-15 1.23E-13 1.59E-14 NR 1.55E-15 7.04E-15 9.77E-15 NR 8.49E-11 1.17E-11

Other Debris Debris 5.34E-02 4.67E+00 7.53E-02 1.11E+01 2.60E-02 3.13E-06 1.56E-02 1.23E-01 7.07E-05 1.94E+03 3.23E+00 NR 3.24E-03 2.87E+00 8.37E-02 6.45E-04 3.47E+00 7.61E-07 9.68E-03 2.74E-03 7.43E-02 NR 1.87E+02 1.50E-05 2.87E-01 NR NR NR 2.40E+00 3.45E-05 0.00E+00 #DIV/0! 3.56E-04 3.47E-04 1.46E-07 1.67E-03 1.92E-03 2.19E-02 1.02E-01 NR NR NR 3.06E-02 2.28E-07 1.34E-02 2.04E-02 3.38E-05 8.05E-05 5.72E-05 NR 1.26E-03 1.21E-05 2.56E-05 NR 2.04E-02 1.25E-02

HLW Silver Mordenite Absorbent Non-Debris 9.43E-14 8.77E-11 9.75E-11 1.58E-10 1.27E-13 1.57E-19 2.76E-14 5.55E-10 5.02E-17 1.21E-07 5.69E-10 NR 0.00E+00 8.72E+02 2.93E-13 2.54E-03 1.48E-09 9.50E-19 1.36E-13 2.39E-14 1.88E-11 NR 2.02E-09 1.79E-17 7.50E-11 NR NR NR 2.86E-09 5.94E-17 0.00E+00 #DIV/0! 8.67E-16 1.43E-15 3.64E-19 3.44E-11 5.62E-13 1.41E-10 1.78E-13 NR NR NR 2.08E-11 0.00E+00 2.67E-13 1.79E-11 7.50E-17 8.73E-16 1.85E-15 NR 3.11E-15 5.29E-17 2.95E-19 NR 1.51E-15 4.27E-14

SSW Total 1.02E-01 2.28E+01 2.64E-01 2.97E+01 3.63E-02 5.27E-05 2.39E-02 4.78E-01 7.43E-04 4.45E+04 6.92E+02 NR 3.24E-03 5.48E+04 1.50E-01 3.22E+02 2.96E+02 8.75E-07 1.19E-01 8.89E-03 8.52E-02 NR 4.57E+03 2.99E-05 5.88E-01 NR NR NR 1.23E+01 2.25E-04 0.00E+00 #DIV/0! 3.87E-04 1.06E-03 7.87E-07 7.70E-03 8.69E-03 4.32E-01 1.74E-01 NR NR NR 3.66E-02 2.28E-07 8.10E-01 2.71E-02 5.06E-05 2.85E-04 1.48E-04 NR 1.37E-03 2.87E-05 4.39E-04 NR 1.63E-01 3.22E-02

BBI 5.91E+05 1.99E+03 8.20E+04

Check 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% N/A 100% 100% 100% 100% 100% 100% 100% 100% 100% N/A 100% 100% 100% N/A N/A N/A 100% 100% 0% #DIV/0! 100% 100% 100% 100% 100% 100% 100% N/A N/A N/A 100% 100% 100% 100% 100% 100% 100% N/A 100% 100% 100% N/A 100% 100%

SE

CT

IO

N 1

SE

CT

IO

N 2

SE

CT

IO

N 3

AS

EC

TIO

N 4

SE

CT

IO

N 5

A



A-19/A-20

Table A-9. Run Case 10B Radionuclides.

SVF-4097, IDF PA Case 10B - Recycle Pass Tc_Tc-99 Retention in ILAW Glass of 68% - Mass Balance, MMR-50054














LAW Accumulation 1.51E-04 3.73E-01 6.10E-02 9.54E-03 1.02E-03 2.61E-06 2.03E-01 1.91E-01 1.94E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.48E-07 3.41E-03 1.50E-01 0.00E+00 0.00E+00 0.00E+00 6.97E-06 4.65E-04 3.40E-04 1.46E-05 7.97E-06 3.74E-04 1.02E-02 3.24E-04 2.81E-01 5.58E-02 5.19E-02 3.95E-01 1.36E-03 3.68E-06 2.39E-05 1.64E-04 3.60E-03 6.06E-02 6.03E-03 0.00E+00 5.49E-01 4.61E-03 3.56E+00 3.56E+00 0.00E+00 0.00E+00 7.40E-01

HLW-Accumulation 6.73E-08 2.11E-03 1.04E-04 2.19E-05 4.52E-04 1.38E-02 1.90E+03 1.79E+03 2.29E-05 2.46E+03 8.15E-01 2.57E+01 7.42E+00 6.25E-10 -7.99E-03 -3.34E-01 3.17E-04 2.38E-03 1.25E-03 2.91E-03 1.87E-01 1.23E-01 5.22E-03 2.68E-03 2.13E-02 6.32E-01 1.17E-01 1.82E+01 3.71E+00 3.56E+01 2.17E+01 5.96E-06 2.38E-04 1.83E-02 4.32E-07 9.44E-06 1.52E+00 6.85E-01 1.76E+00 6.18E+01 7.26E-06 1.07E+04 1.07E+04 1.84E+00 1.63E+00 2.66E-04

SLAW-Accumulation 1.49E-04 3.29E-01 6.38E-02 9.61E-03 1.17E-03 3.07E-06 2.60E-01 2.45E-01 1.93E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.72E-07 3.17E-03 1.50E-01 0.00E+00 0.00E+00 0.00E+00 5.53E-06 3.67E-04 2.67E-04 1.14E-05 6.17E-06 4.09E-04 8.91E-03 2.55E-04 2.48E-01 4.92E-02 6.34E-02 3.39E-01 1.51E-03 3.22E-06 2.81E-05 1.68E-04 3.68E-03 7.55E-02 5.53E-03 0.00E+00 5.04E-01 5.31E-03 9.09E+00 9.09E+00 0.00E+00 0.00E+00 1.00E+00



LERF-Accumulation 1.20E-04 2.67E-01 6.89E-01 7.69E-03 3.50E-02 3.05E-05 3.30E+00 3.12E+00 7.34E-03 4.20E-18 1.66E-21 1.69E-20 2.16E-20 4.60E-06 1.55E-03 1.37E+00 8.09E-25 1.62E-24 1.84E-24 3.52E-06 2.24E-04 1.29E-04 5.47E-06 2.88E-06 3.25E-04 4.23E-03 1.23E-04 1.09E-01 2.26E-02 1.41E-01 1.39E-01 1.99E-03 2.42E-06 6.54E-05 1.52E-04 3.32E-03 3.91E+00 2.56E-03 3.49E-21 2.29E-01 6.13E-02 1.50E+01 1.50E+01 3.45E-22 6.58E-20 1.45E+01









1.20E+01 3.83E+03 4.11E+03 3.90E+02 2.94E+01 7.13E+02 3.90E+07 3.68E+07 8.27E+02 3.27E+06 8.25E+02 4.95E+04 2.45E+04 9.43E-03 4.53E+00 7.74E+00 1.43E+00 4.84E+00 6.63E+00 8.39E+00 6.51E+02 2.19E+02 8.94E+00 6.20E+00 1.08E+02 2.52E+03 1.99E+02 4.83E+04 1.02E+04 1.50E+05 8.00E+04 1.21E+02 7.64E-01 6.80E+01 1.34E+01 2.96E+02 2.81E+03 1.48E+03 3.80E+03 1.33E+05 1.44E+02 4.40E+07 4.40E+07 3.49E+03 2.96E+03 2.65E+04

100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 120% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100%




ETF Solid Waste Form to IDF 4.70E-14 4.62E+00 2.04E-02 4.34E+00 1.88E+01 2.60E-08 9.25E+02 8.73E+02 2.39E+00 7.84E-04 4.74E-08 1.41E-07 1.05E-08 2.27E-03 3.75E-02 2.20E-01 2.04E-10 4.87E-10 4.67E-10 7.71E-04 7.59E-02 2.95E-02 1.21E-03 8.61E-04 1.55E-01 1.57E+00 2.69E-02 4.10E+01 8.70E+00 1.11E+02 8.62E+00 1.05E+00 8.67E-04 5.80E-02 5.14E-02 6.09E-01 3.49E-01 4.84E-01 3.05E-07 3.22E+01 3.53E+01 5.97E+02 5.97E+02 2.93E-07 8.97E-04 8.46E+03















BBI 2.94E+01 3.90E+07 4.76E+07 2.65E+04








CT

ION

5B

SE

CT

ION

1S

EC

TIO

N 2

SE

CT

ION

3A

SE

CT

ION

4S

EC

TIO

N 5

AS

EC

TIO

N 3

B



A-21/A-22

Table A-10. Run Case 10B Chemicals.

SVF-4097, IDF PA Case 10B - Recycle Pass Tc_Tc-99 Retention in ILAW Glass of 68% - Mass Balance, MMR-50054



LAW Spent Melter Subtotal (IDF) 1.67E+00 2.65E+04 4.26E+00 2.50E+04 1.95E-02 6.45E-01 8.69E+01 1.02E+01 7.60E+01 5.20E+02 6.39E+02 5.84E-04 3.64E-01 7.64E+02 3.18E+04 0.00E+00 1.06E+03 4.65E-08 4.14E+03 7.35E+03 4.75E-08 8.49E+00 1.05E+05 4.48E+00 3.03E+00 0.00E+00 0.00E+00 0.00E+00 9.55E+01 1.58E+00 0.00E+00 0.00E+00 1.04E-01 2.35E-01 0.00E+00 2.72E+00 3.34E+00 4.36E+00 1.75E+05 0.00E+00 3.29E+03 0.00E+00 5.17E-02 1.14E-04 1.32E+00 2.13E+00 5.81E-07 9.84E+03 1.32E-07 2.44E-02 1.19E+01 1.06E-03 2.22E+00 1.25E-01 1.95E+04 1.82E+04

ETF Solid Waste Form to IDF 2.46E+01 1.14E+04 1.17E+03 1.62E+02 7.87E-01 5.64E+00 1.35E+03 6.33E+01 1.32E+03 3.69E+05 3.45E+04 8.90E-02 3.37E+01 6.06E+05 3.22E+02 1.64E+03 4.66E+04 2.73E-03 2.41E+01 1.14E+00 3.38E+01 1.38E+02 1.76E+06 3.42E+01 2.36E+01 2.17E+04 2.23E+06 8.73E+04 7.17E+03 2.18E+01 5.50E+04 0.00E+00 6.97E-01 5.58E+00 0.00E+00 3.09E+01 8.75E+02 1.26E+03 1.41E+03 0.00E+00 0.00E+00 9.26E+05 1.14E+01 1.02E-03 4.99E+02 5.15E+02 4.22E-06 1.08E-05 4.87E-05 5.16E+03 7.98E+01 1.45E-04 2.09E-02 7.96E-03 3.17E+01 1.42E-05


Non-IDF Stream 2.50E+03 2.47E+06 8.52E+01 1.49E+06 8.56E+03 2.71E+00 4.77E+05 1.61E+03 6.61E+03 4.50E+03 6.56E+04 2.07E+03 2.33E+03 3.02E+04 1.53E+06 -2.70E+00 1.64E+04 4.21E+04 7.51E+05 2.28E+04 4.63E+05 2.24E+01 2.04E+06 5.87E+03 1.16E+05 1.68E+07 5.75E+07 2.53E+07 2.64E+03 5.16E-01 5.07E+06 8.18E+02 7.41E+02 8.53E-02 9.37E+02 5.12E-01 1.55E+02 3.08E+01 5.57E+06 -3.79E+03 -2.39E+06 2.88E+06 5.97E+04 2.62E+02 3.72E-01 8.35E+02 6.01E+04 1.38E+03 6.55E+03 8.65E+05 5.81E+05 2.38E+03 4.40E+01 4.78E+02 4.31E+02 4.04E+05





PT-Accumulation 7.35E+01 2.63E+04 9.47E-01 5.67E+00 1.23E+02 2.29E-01 5.35E+03 1.98E+00 3.69E+02 9.60E+01 1.48E+03 1.16E+01 3.30E+01 5.28E+02 1.25E+04 1.29E+00 1.63E+02 9.43E+01 4.58E-01 3.34E+02 3.69E+03 1.50E+00 3.09E+04 7.43E+01 1.02E+03 3.04E+03 4.02E+04 9.54E+03 5.87E+01 4.51E-02 2.41E+03 3.89E+00 5.06E+00 1.32E-02 2.52E+00 2.80E-01 1.52E+00 1.25E+00 7.27E+03 0.00E+00 0.00E+00 1.12E+03 7.48E+02 3.34E+00 1.56E-01 5.64E-01 2.03E+02 1.28E+01 2.32E+02 1.14E+02 6.53E+03 2.18E+01 6.20E-02 1.43E+00 1.94E+00 3.04E+03



LAW Accumulation 3.24E-01 1.54E+03 2.65E-01 9.84E+02 2.29E-03 5.78E-02 7.90E+00 5.06E-01 1.60E+00 2.88E+01 8.72E+01 1.06E-05 4.61E-03 1.69E+02 1.25E+03 3.61E-01 2.41E+01 0.00E+00 1.17E-01 2.89E+02 0.00E+00 3.94E-01 8.59E+03 4.96E-01 3.82E-01 4.20E+02 1.82E+03 2.27E+03 5.65E+00 1.11E-02 3.78E+02 0.00E+00 4.78E-03 3.17E-03 0.00E+00 6.81E-02 4.16E-01 3.45E-01 6.65E+03 5.72E-03 8.26E+01 1.98E+02 1.12E-02 2.04E-05 4.37E-02 1.60E-01 0.00E+00 3.87E+02 0.00E+00 1.47E+01 9.71E-01 1.10E-04 1.54E-02 1.55E-02 7.66E+02 7.14E+02

HLW-Accumulation 8.86E-01 1.26E+03 5.62E-04 9.46E+02 7.92E+00 2.09E-04 3.29E+02 2.32E-03 1.84E+00 1.10E-02 3.25E+01 1.04E-01 2.16E+00 6.61E-02 7.61E+02 1.92E-03 5.88E-01 5.92E+00 3.44E+02 2.10E+01 2.41E+02 2.04E-03 6.20E+02 3.08E+00 4.98E+01 1.26E+00 4.67E+01 1.08E+01 3.96E-01 4.45E-05 1.36E-01 2.62E-01 3.09E-01 6.50E-06 1.67E-01 1.41E-04 4.39E-04 4.73E-04 2.47E+03 2.73E-05 7.36E-02 1.44E-01 2.90E+01 2.25E-01 1.57E-05 6.47E-04 1.14E+01 7.38E-01 1.11E+01 5.27E-02 3.52E+02 1.14E+00 6.12E-05 3.92E-02 2.85E-03 1.33E+02

SLAW-Accumulation 3.27E-01 1.33E+03 2.99E-01 8.85E+02 3.24E-03 6.39E-02 7.31E+00 4.61E-01 4.54E-01 3.48E+01 2.33E+01 1.28E-05 4.92E-03 2.20E+02 1.13E+03 4.27E-01 2.29E+01 0.00E+00 2.13E-01 2.60E+02 0.00E+00 4.79E-01 7.59E+03 4.44E-01 3.58E-01 4.26E+02 1.74E+03 1.84E+03 5.64E+00 1.16E-02 4.09E+02 0.00E+00 4.22E-03 3.18E-03 0.00E+00 6.99E-02 4.17E-01 3.95E-01 5.98E+03 1.29E-01 8.73E+01 3.45E+02 2.11E-02 1.99E-05 5.90E-02 1.92E-01 0.00E+00 3.48E+02 0.00E+00 1.52E+01 7.63E-01 1.04E-04 1.67E-02 1.38E-02 6.89E+02 6.43E+02

LAWPS-Accumulation 3.23E-04 1.84E+00 7.60E-03 1.49E-02 7.94E-07 3.53E-04 1.89E-02 4.57E-03 0.00E+00 1.04E+00 2.14E-01 2.37E-03 3.01E-04 1.19E-01 1.70E-02 5.11E-04 1.40E+00 0.00E+00 4.80E-03 0.00E+00 0.00E+00 8.01E-03 4.82E+01 1.92E-03 9.84E-04 1.59E+01 5.06E+01 1.05E+01 3.13E-02 1.82E-03 1.86E+00 0.00E+00 7.08E-05 1.14E-04 0.00E+00 2.23E-03 5.43E-03 6.92E-03 5.41E-02 0.00E+00 0.00E+00 1.24E+00 2.08E-05 3.70E-09 1.75E-03 3.72E-04 0.00E+00 0.00E+00 0.00E+00 5.97E-01 3.92E-03 3.75E-07 5.39E-03 5.87E-05 3.50E-03 0.00E+00


LERF-Accumulation 2.49E-01 8.44E+01 3.42E+00 1.03E+00 1.91E-03 5.80E-02 1.01E+01 2.59E-01 2.16E+01 7.98E+02 2.38E+02 1.21E-04 3.65E-02 5.35E+03 2.88E+00 1.41E+01 7.46E+01 1.34E-21 1.51E-01 1.76E-22 1.54E-21 1.00E+00 1.01E+04 2.55E-01 1.78E-01 1.71E+00 5.43E+03 1.35E+03 4.96E+01 2.20E-02 5.96E+02 0.00E+00 1.86E-03 4.29E-03 0.00E+00 4.67E-02 2.99E+00 3.66E+00 1.42E+01 0.00E+00 0.00E+00 1.14E+04 1.37E-01 1.81E-05 8.56E-01 4.88E+00 1.67E-20 8.29E-23 1.35E-19 1.91E+01 3.69E-01 1.45E-04 2.09E-02 7.96E-03 4.05E-01 1.32E-22





LAW Spent Melter Subtotal (IDF) 1.71E+00 2.66E+04 4.27E+00 2.50E+04 1.97E-02 6.45E-01 8.78E+01 1.02E+01 7.65E+01 5.21E+02 6.41E+02 5.87E-04 3.69E-01 7.68E+02 3.18E+04 0.00E+00 1.06E+03 4.66E-08 4.14E+03 7.35E+03 4.79E-08 8.50E+00 1.05E+05 4.52E+00 3.06E+00 0.00E+00 0.00E+00 0.00E+00 9.57E+01 1.58E+00 0.00E+00 0.00E+00 1.05E-01 2.35E-01 0.00E+00 2.72E+00 3.34E+00 4.36E+00 1.75E+05 #DIV/0! #DIV/0! 0.00E+00 5.24E-02 1.16E-04 1.32E+00 2.14E+00 5.83E-07 9.84E+03 1.37E-07 2.44E-02 1.20E+01 1.07E-03 2.22E+00 1.25E-01 1.95E+04 1.82E+04

ETF Solid Waste Form to IDF 2.51E+01 1.14E+04 1.18E+03 1.62E+02 7.99E-01 5.65E+00 1.36E+03 6.33E+01 1.33E+03 3.69E+05 3.46E+04 8.95E-02 3.41E+01 6.09E+05 3.22E+02 1.65E+03 4.67E+04 2.74E-03 2.41E+01 1.14E+00 3.41E+01 1.38E+02 1.76E+06 3.45E+01 2.38E+01 2.17E+04 2.23E+06 8.73E+04 7.18E+03 2.18E+01 5.50E+04 0.00E+00 7.01E-01 5.58E+00 0.00E+00 3.09E+01 8.77E+02 1.26E+03 1.41E+03 #DIV/0! #DIV/0! 9.29E+05 1.15E+01 1.04E-03 4.99E+02 5.16E+02 4.24E-06 1.08E-05 5.04E-05 5.16E+03 8.07E+01 1.46E-04 2.09E-02 7.98E-03 3.17E+01 1.42E-05


Non-IDF Stream 2.55E+03 2.48E+06 8.53E+01 1.50E+06 8.69E+03 2.71E+00 4.82E+05 1.61E+03 6.65E+03 4.51E+03 6.58E+04 2.09E+03 2.36E+03 3.03E+04 1.54E+06 -2.72E+00 1.64E+04 4.22E+04 7.51E+05 2.28E+04 4.67E+05 2.25E+01 2.04E+06 5.92E+03 1.17E+05 1.68E+07 5.76E+07 2.53E+07 2.65E+03 5.16E-01 5.08E+06 8.23E+02 7.45E+02 8.53E-02 9.40E+02 5.12E-01 1.56E+02 3.09E+01 5.57E+06 #DIV/0! #DIV/0! 2.89E+06 6.05E+04 2.65E+02 3.72E-01 8.36E+02 6.03E+04 1.38E+03 6.78E+03 8.65E+05 5.88E+05 2.40E+03 4.40E+01 4.79E+02 4.31E+02 4.04E+05

3.82E+03 2.20E+07 4.87E+03 1.99E+07 8.70E+03 5.02E+02 5.46E+05 8.67E+03 5.96E+04 8.28E+05 5.63E+05 2.09E+03 2.72E+03 1.28E+06 2.49E+07 1.97E+03 9.56E+05 4.22E+04 3.67E+06 5.42E+06 4.67E+05 6.55E+03 8.12E+07 9.25E+03 1.20E+05 1.68E+07 5.98E+07 2.54E+07 8.16E+04 2.13E+03 5.14E+06 8.23E+02 8.23E+02 2.75E+02 9.40E+02 3.08E+03 3.72E+03 5.18E+03 1.34E+08 #DIV/0! #DIV/0! 3.82E+06 6.06E+04 2.65E+02 1.56E+03 2.91E+03 6.03E+04 7.22E+06 6.78E+03 8.70E+05 5.96E+05 2.40E+03 4.15E+03 5.70E+02 1.43E+07 1.38E+07

100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% #DIV/0! #DIV/0! 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100% 100%


HEPA fraction 4.53% 17.39% 17.89% 62.10% 6.43% 0.15% 5.17% 50.79% 0.21% 0.00% 94.18% NR 0.00% 0.00% 44.22% 0.00% 56.46% 7.86% 91.84% 69.10% 12.79% NR 40.68% 4.20% 13.13% NR NR NR 61.05% 1.03% NR #DIV/0! 8.09% 5.61% 5.04% 78.35% 5.42% 31.35% 41.49% NR NR NR 15.98% 0.00% 63.36% 20.43% 7.69% 71.77% 23.04% NR 8.06% 41.24% 0.23% NR 87.47% 60.66%

IX Resin fraction 43.06% 62.12% 53.58% 0.54% 22.10% 93.91% 29.47% 23.43% 90.28% 95.63% 5.35% NR 0.00% 0.08% 0.00% 0.00% 42.37% 5.18% 0.04% 0.12% 0.00% NR 55.24% 45.56% 38.04% NR NR NR 19.53% 83.67% NR #DIV/0! 0.00% 61.81% 76.38% 0.00% 72.52% 63.57% 0.12% NR NR NR 0.23% 0.00% 34.99% 4.19% 25.51% 0.00% 38.40% NR 0.00% 16.62% 93.95% NR 0.01% 0.38%

LAW and HLW Carbon Bed fraction 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR 0.00% 98.32% 0.00% 100.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR 0.00% 0.00% 0.00% NR NR NR 0.00% 0.00% NR #DIV/0! 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR NR NR 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR 0.00% 0.00% 0.00% NR 0.00% 0.00%

Other Debris fraction 52.41% 20.48% 28.53% 37.37% 71.47% 5.95% 65.36% 25.78% 9.52% 4.37% 0.47% NR 100.00% 0.01% 55.78% 0.00% 1.17% 86.96% 8.12% 30.78% 87.21% NR 4.08% 50.24% 48.83% NR NR NR 19.42% 15.31% NR #DIV/0! 91.91% 32.59% 18.58% 21.65% 22.06% 5.08% 58.40% NR NR NR 83.79% 100.00% 1.65% 75.39% 66.80% 28.23% 38.56% NR 91.94% 42.15% 5.83% NR 12.52% 38.96%

HLW Silver Mordenite Absorbent fraction 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR 0.00% 1.59% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR 0.00% 0.00% 0.00% NR NR NR 0.00% 0.00% NR #DIV/0! 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR NR NR 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% NR 0.00% 0.00% 0.00% NR 0.00% 0.00%







SSW Total 9.67E-02 2.28E+01 2.51E-01 2.97E+01 3.55E-02 5.27E-05 2.45E-02 4.63E-01 7.56E-04 4.45E+04 6.94E+02 NR 3.23E-03 5.50E+04 1.48E-01 3.24E+02 2.96E+02 8.76E-07 1.19E-01 8.84E-03 8.53E-02 NR 4.55E+03 3.02E-05 5.54E-01 NR NR NR 1.25E+01 2.25E-04 NR #DIV/0! 3.60E-04 1.06E-03 7.88E-07 7.70E-03 8.69E-03 4.15E-01 1.68E-01 NR NR NR 3.54E-02 2.30E-07 6.60E-01 2.56E-02 5.06E-05 2.85E-04 1.48E-04 NR 1.34E-03 2.87E-05 4.39E-04 NR 1.63E-01 3.21E-02

BBI 5.91E+05 1.99E+03 8.20E+04


SE

CT

ION

1S

EC

TIO

N 2

SE

CT

ION

3A

SE

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4S

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N 5

A



B-i

ENGINEERING CALCULATION DOCUMENTATION



B-ii




B-1

APPENDIX B

ENGINEERING CALCULATION DOCUMENTATION








Page 1 of 3 A-6003-508 (REV 4)

INFORMATION CLEARANCE REVIEW AND RELEASE APPROVAL

Part I: Background Information

Title: Information Category:

Abstract Journal Article Summary

Internet Visual Aid Software

Publish to OSTI? Yes No Full Paper Report Other

Trademark/Copyright “Right to Use” Information or Permission Documentation

Yes NA

Document Number: Date:

Author:

Part II: External/Public Presentation Information Conference Name:

Sponsoring Organization(s):

Date of Conference: Conference Location:

Will Material be Handed Out? Yes No Will Information be Published? Yes No (If Yes, attach copy of Conference format instructions/guidance.)

Part III: WRPS Document Originator Checklist

Description Yes N/A Print/Sign/Date

Information Product meets requirements in TFC-BSM-AD-C-01?

Document Release Criteria in TFC-ENG-DESIGN-C-25 completed? (Attach checklist)

If product contains pictures, safety review completed?

Part IV: WRPS Internal Review

Function Organization Date Print Name/Signature/Date

Subject Matter Expert

Responsible Manager

Other:

Part V: IRM Clearance Services Review

Description Yes No Print Name/Signature

Document Contains Classified Information? If Answer is “Yes,” ADC Approval Required

Print Name/Signature/Date

Document Contains Information Restricted by DOE Operational Security Guidelines?

Reviewer Signature:

Print Name/Signature/Date

Document is Subject to Release Restrictions? Document contains:

If the answer is “Yes,” please mark category at right and describe limitation or responsible organization below:

Applied Technology Protected CRADA

Personal/Private Export Controlled

Proprietary Procurement – Sensitive

Patentable Info. OUO

Predecisional Info. UCNI

Restricted by Operational Security Guidelines

Other (Specify)

Additional Comments from Information Clearance Specialist Review?

Information Clearance Specialist Approval

Print Name/Signature/Date When IRM Clearance Review is Complete – Return to WRPS Originator for Final Signature Routing (Part VI)

Inventory Data Summary for the Integrated Disposal Facility Performance Assessment

RPP-ENV-58562 Revision 3 May 2016

Lee, Kearn (Pat)

Not Applicable

Not Applicable

Not Applicable Not Applicable

✔

Lee, Kearn (Pat)

WRPS

WRPS

Lee, Kearn (Pat)

Rutland, Paul L

✔ ✔

✔

✔

✔

✔

✔

Lee, Kearn (Pat)

IDMS Data File att.IDMS Data File att.

09/23/201608/31/2016

x

x

x

x

IDMS Data File att.IDMS Data File att.

By Lana Perry at 7:40 am, Sep 26, 2016

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Page 2 of 3 A-6003-508 (REV 4)

INFORMATION CLEARANCE REVIEW AND RELEASE APPROVAL

Part VI: Final Review and Approvals

Description Approved for Release

Print Name/Signature Yes N/A

WRPS External Affairs

WRPS Office of Chief Counsel

DOE – ORP Public Affairs/Communications

Other:

Other:

Comments Required for WRPS-Indicate Purpose of Document:

Information Release Station

Was/Is Information Product Approved for Release? Yes No

If Yes, what is the Level of Releaser? Public/Unrestricted Other (Specify)

Date Information Product Stamped/Marked for Release:

Was/Is Information Product Transferred to OSTI? Yes No

Forward Copies of Completed Form to WRPS Originator

Holloway, Jerry NRoden, Mari L

Marshall, Richard

Pyles, Gary L

✔

The report is a data package that supplies input values to be used in the 2017 Integrated Disposal Facility Performance Assessment. The Washington Department of Ecology is a stakeholder in the development of the work product and ORP has requested that the data packages be shared with Ecology.

x

xxxORP

IDMS Data File att.IDMS Data File att.IDMS Data File att.IDMS Data File att.


Approved for Public Release; Further Dissemination Unlimited

X

X

09/26/2016

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- <workflow name="(LRP)Normal - RPP-ENV-58562 R3_Inv Data Sum IDF PA"id="210153479">

- <task name="Clearance Process" id="0" date-initiated="20160831T0945"performer="Lana R Perry" performer-id="86772" username="h0028549"><comments>Due Wednesday 09-07-2016 COB Please approve Inventory

Data Summary for the Integrated Disposal Facility Performance Assessment, submitted by Kearn (Pat) Lee for public release. Thank you, Lana Perry Information Clearance</comments>

</task><task name="Add XML" id="1" date-done="20160831T0945" /><task name="Manager Approval" id="41" date-due="20160905T0945" date-

done="20160831T1012" performer="Paul L Rutland" performer-id="140633218"username="h4494439" disposition="Approve" authentication="true" />

<task name="Document Reviewer3" id="52" date-due="20160905T1012" date-done="20160901T1107" performer="Gary L Pyles" performer-id="147601648"username="h6400308" disposition="Public Release" authentication="true" />

<task name="Document Reviewer2" id="53" date-due="20160905T1012" date-done="20160907T1655" performer="Mari L Roden" performer-id="179713158"username="h0048955" disposition="Public Release" authentication="true" />

<task name="Document Reviewer1" id="54" date-due="20160905T1012" date-done="20160912T1321" performer="Jerry N Holloway" performer-id="140435533" username="h0087835" disposition="Public Release"authentication="true" />

<task name="Doc Owner Clearance Review" id="13" date-due="20160913T1321"date-done="20160921T0616" performer="Kearn P Lee" performer-id="148796764" username="h8500694" disposition="Send On"authentication="true" />

<task name="Milestone 1" id="24" date-done="20160921T0616" />- <task name="ORP Document Reviewer1" id="57" date-due="20160923T0616"

date-done="20160922T1528" performer="Richard A Marshall" performer-id="203862915" username="h4535783" disposition="Public Release"authentication="true"><reviewer performer="Gary L Pyles" performer-id="147601648"

username="h6400308" /></task>

- <task name="Doc Owner Reviews ORP Comments" id="61" date-due="20160923T1528" date-done="20160922T1533" performer="Kearn P Lee"performer-id="148796764" username="h8500694" disposition="Send On"authentication="true"><comments>There were no comments provided and no additional red-line

strike out files in the attachments.</comments></task><task name="Milestone 2" id="62" date-done="20160922T1534" /><task name="Verify Doc Consistency" id="4" date-due="20160923T1533" date-

done="20160926T0731" performer="Lana R Perry" performer-id="86772"username="h0028549" disposition="Cleared" authentication="true" />

</workflow>

Page 3 of 3

9/26/2016

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RPP-ENV-58562Revision 3

Copy No.

Inventory Data Summary for the Integrated Disposal Facility Performance Assessment

Prepared for the U.S. Department of EnergyAssistant Secretary for Environmental Management

Contractor for the U.S. Department of EnergyOffice of River Protection under Contract DE-AC27-08RV14800

P.O. Box 850 Richland, Washington 99352


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Copy No.

Inventory Data Summary for the Integrated DisposalFacility Performance Assessment

K. A. PrindivilleWashington River Protection Solutions

Date PublishedMay 2016

To be Presented atNot Applicable

Not ApplicableNot Applicable

Not Applicable

Published inNot Applicable

Prepared for the U.S. Department of EnergyAssistant Secretary for Environmental Management

Contractor for the U.S. Department of EnergyOffice of River Protection under Contract DE-AC27-08RV14800

P.O. Box 850 Richland, Washington 99352

Copyright License By acceptance of this article, the publisher and/or recipient acknowledges the U.S. Government's right to retain a non exclusive, royalty-free licensein an to any copyright covering this paper.

Release Approval Date



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LEGAL DISCLAIMERThis report was prepared as an account of work sponsored by an agency ofthe United States Government. Neither the United States Government norany agency thereof, nor any of their employees, makes any warranty,express or implied, or assumes any legal liability or responsibility for theaccuracy, completeness, or any third party's use or the results of such useof any information, apparatus, product, or process disclosed, or representsthat its use would not infringe privately owned rights. Reference herein toany specific commercial product, process, or service by trade name,trademark, manufacturer, or otherwise, does not necessarily constitute orimply its endorsement, recommendation, or favoring by the United StatesGovernment or any agency thereof or its contractors or subcontractors. Theviews and opinions of authors expressed herein do not necessarily state orreflect those of the United States Government or any agency thereof.

This report has been reproduced from the best available copy.

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