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DOE OSTI2018

Xyce Parallel Electronic Simulator Reference Guide Version 6.10

This document is a reference guide to the Xyce Parallel Electronic Simulator, and is a companion document to the Xyce Users' Guid [1] . The focus of this document is (to the extent possible) exhaustively list device parameters, solver options, parser options, and other usage details of Xyce . This document is not intended to be a tutorial. Users who are new to circuit simulation are better served by the Xyce Users' Guide.

97 MATHEMATICS AND COMPUTING↗
DOE OSTI2018

SIERRA Multimechanics Module: Aria Thermal Theory Manual - Version 4.50.

This document describes the theoretical foundation of thermal analysis in Sierra Mechanics. The SIERRA Multimechanics Module: Aria, henceforth referred to as Aria for brevity, was developed at Sandia National Laboratories under the ASC program, and approximates linear and nonlinear continuum models of heat transfer. Aria uses the SIERRA Framework, which provides data management services commonly required by computational mechanics software, and facilitates the development of coupled, multi-mechanics applications for massively parallel computers. The mathematical models in Aria are based heavily on those of COYOTE, a well-established thermal analysis program that was also developed at Sandia and its ASC code predecessor, Calore. Aria, Calore and COYOTE share a significant body of numerical methods, which are described in detail by Reddy and Gartling. Throughout this document, the terms software and implementation are synonymous with the Aria thermal-fluid analysis computer program. Whether one uses Aria to perform heat transfer analysis, or in developing a new capability for the Aria application, this document provides the information needed understand the existing numerical algorithm implementations. Justification for the fundamental assumptions of heat transfer, nor derivation of the energy conservation equations are included in this document. For a more thorough theoretical background, one is referred to one of the many available textbooks, e.g. Another reference, which is freely available in downloadable electronic form, is Lienhard and Lienhard.

97 MATHEMATICS AND COMPUTING↗
DOE OSTI2018

SIERRA Multimechanics Module: Aria Thermal Theory Manual - Version 4.48

This document describes the theoretical foundation of thermal analysis in Sierra Mechanics. The SIERRA Multimechanics Module: Aria, henceforth referred to as Aria for brevity, was developed at Sandia National Laboratories under the ASC program, and approximates linear and nonlinear continuum models of heat transfer. Aria uses the SIERRA Framework, which provides data management services commonly required by computational mechanics software, and facilitates the development of coupled, multi-mechanics applications for massively parallel computers. The mathematical models in Aria are based heavily on those of COYOTE, a well-established thermal analysis program that was also developed at Sandia and its ASC code predecessor, Calore. Aria, Calore and COYOTE share a significant body of numerical methods, which are described in detail by Reddy and Gartling. Throughout this document, the terms software and implementation are syn onymous with the Aria thermal-fluid analysis computer program. Whether one uses Aria to perform heat transfer analysis, or in developing a new capability for the Aria application, this document provides the information needed understand the existing numerical algorithm implementations. Justification for the fundamental assumptions of heat transfer, nor derivation of the energy conservation equations are included in this document. For a more thorough theoretical background, one is referred to one of the many available textbooks, e.g. Another reference, which is freely available in downloadable electronic form, is Lienhard and Lienhard.

71 CLASSICAL AND QUANTUM MECHANICS, GENERAL PHYSIC↗
DOE OSTI2019

Underground Test Area Activity Preemptive Review Guidance Nevada National Security Site, Nevada

This report is a revision to the preemptive review (PER) guidance originally released as U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) document DOE/NV--1552 in 2016 (NNSA/NFO, 2016). PER committees review various products, including data, documents, software/codes, analyses, and models. PER committees provide technical recommendations to support regulatory decisions that are the responsibility of the DOE Environmental Management (EM) Nevada Program and NDEP. PERs are designed to be adaptable to the varying requirements of individual CAU studies. Their goals include the following: Maintaining high technical standards; ensuring work is technically adequate, competently performed, and documented consistent with other programmatic documents; and verifying that established quality requirements are satisfied. Helping focus CAU studies on UGTA Activity objectives identified in the FFACO by implementing Section 3 of Appendix VI, which includes the UGTA Strategy Flowchart (Figure 3-2) and Process Flow Diagram Dictionary for the UGTA CAUs (Table 3-1). Providing a mechanism for early identification of technical and/or strategy issues that could affect successfully implementing the UGTA strategy. Providing assurance to NDEP that work in progress and final reports are technically sound. Providing independent reviews that allow for a better understanding of the technical work, and result in products that are transparent and sufficient to allow the DOE EM Nevada Program to meet regulatory objectives.

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2019

Fiscal Year 2018 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada National Security Site, Nye County, Nevada

The U.S. Department of Energy Standard Disposal Authorization Statement and Tank Closure Documentation (DOE-STD-5002-2017) requires preparation of an Annual Summary Report comparing low-level radioactive waste disposal facilities operations with the Disposal Authorization Statement (DAS) and its supporting technical documents including the performance assessment (PA) and the composite analysis (CA). The fiscal year (FY) 2018 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) was prepared by reviewing planned and discovered changes, waste receipts, monitoring results, research and development (R&D) results, and the status of DAS conditions and issues to assess the validity of the DASs, PAs, and CAs. The Area 3 RWMS was placed in stand-by in 2006 and remained inactive in FY 2018. Resumption of waste disposal operations is planned for FY 2019. No proposed actions, new information, or discoveries affecting the Area 3 RWMS were identified in FY 2018. No significant changes have occurred since preparation of the most recent special analysis, which indicates a continuing reasonable expectation of meeting the PA performance objectives and measures, and the CA dose constraint in DOE O 435.1, “Radioactive Waste Management.” No changes were made to documents supporting the Radioactive Waste Management Basis (RWMB) including the PA, CA, DAS, waste acceptance criteria (WAC), closure plan, monitoring plan, or maintenance plan. Monitoring results for the most recent year with available data, calendar year (CY) 2017, indicate no changes to long-term trends and no results inconsistent with expected performance. R&D results for the Area 3 RWMS Drainage Lysimeter Facility continue to be consistent with the conceptual site model (CSM). All Area 3 RWMS DAS conditions and secondary issues were closed in 2002. The Area 5 RWMS continued disposal operations within the Northern Expansion Area in FY 2018. Eighty-six changes involving proposed actions, new information, or discoveries affecting the Area 5 RWMS PA and CA were screened during FY 2018 in the Unreviewed disposal question (UDQ) process. Twenty-two changes required UDQ evaluations and two changes resulted in unreviewed composite analysis question evaluations. None of the proposed actions, new information, or discoveries had significant impacts on the PAs or CAs. All of the planned changes were implemented. No special analyses were performed, and no changes were made to documents supporting the RWMB including the PA, CA, DAS, WAC, closure plan, monitoring plan, or maintenance plan. Planning continued and construction commenced on development of the Western Expansion Area within the Radioactive Waste Management Complex. All Area 5 RWMS DAS conditions and secondary issues were closed in 2002. The cumulative effects of changes occurring since preparation of the Area 5 RWMS PA and CA were assessed with the current baseline PA/CA model. Model results indicate that there is a reasonable expectation that the PA performance objectives and measures, and the CA dose constraint in DOE O 435.1, “Radioactive Waste Management,” can be met. No PA or CA mean result exceeds 50% of its performance objective. Monitoring results and R&D results continue to be consistent with the CSM. Monitoring results for CY 2017 indicate no changes to long-term trends and no results inconsistent with expected performance. R&D results for the Area 5 RWMS Weighing Lysimeter Facility continue to be consistent with the CSM. The FY 2018 review of Area 3 RWMS and Area 5 RWMS disposal operations supports the following conclusions: The Area 3 and Area 5 RWMS PA and associated CA assumptions and conclusions remain valid based on consideration of all changes identified or planned; The reasonable expectation that the Area 3 and Area 5 RWMSs will meet the performance objectives identified in DOE O 435.1, “Radioactive Waste Management”, remains valid; and The DAS, based on interpretation of the data collected, monitoring results, and other information, continues to be adequate.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2017

Scaled Wind Farm Technology (SWiFT) Facility (Safety Assessment, Rev. 0)

This Safety Assessment (SA) documents the hazard analysis conducted for the Scaled Wind Farm Technology (SWiFT) Facility. The Sandia National Laboratories (SNL) Authorization Basis process requires Safety Assessment documents for all moderate-hazard industrial facilities. Together with the Primary Hazard Screening (PHS) Document [SNL11A00204), the SA documents the SWiFT safety basis, which is defined as the safety analysis and hazard controls that provide reasonable assurance that a DOE facility can be operated in a manner that adequately protects the workers, collocated/onsite workers, the public, and the environment. The SA specifically addresses the potential impact of hazards on the worker, collocated worker, and public.

17 WIND ENERGY↗
DOE OSTI2018

Xyce TM Parallel Electronic Simulator Reference Guide, Version 6.9

This document is a reference guide to the Xyce Parallel Electronic Simulator, and is a companion document to the Xyce Users' Guide. The focus of this document is (to the extent possible) exhaustively list device parameters, solver options, parser options, and other usage details of Xyce . This document is not intended to be a tutorial. Users who are new to circuit simulation are better served by the Xyce Users' Guide.

42 ENGINEERING↗
DOE OSTI2019

The Historic Water, Sewer, and Steam/HTHW Systems in Mercury, Area 23, Nevada National Security Site, Nye County, Nevada (Appendix B - Resource Forms)

This report provides documentation intended to satisfy the mitigation requirements for a substantial portion of the above- and belowground utilities in Mercury on the Nevada National Security Site (NNSS) outlined in the associated Memorandum of Agreement (MOA). The U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) manages the property and anticipates conducting activities in the future that will affect these resources. These structures are entirely within the Mercury Historic District, which is eligible to the National Register of Historic Places. The district is considered eligible under Criteria A and C for the theme of nuclear testing, with a period of significance from 1951 through 1992. The utilities addressed here include the systems related to potable water and steam/high temperature hot water distribution, as well as the sewage system. More specifically, this documentation covers these underground utilities that were installed in Mercury from 1951 through 1977 and above-ground components installed from 1951 through 1992. Introduction The information in this report is intended to meet the requirements of the Memorandum of Agreement between the National Nuclear Security Administration Nevada Field Office (NNSA/NFO) and the Nevada State Historic Preservation Officer Regarding Water and Sewer Upgrades at Mercury in Nye County, Nevada (MOA) signed on January 30, 2018. The purpose of the MOA is to mitigate the adverse effects of proposed activities on utilities in the Mercury Historic District. The MOA covers the potable water, sewage, and steam/high temperature hot water (HTHW) systems in Mercury. A historic context related to the district as a whole is documented in Reno et al. The State Historic Preservation Officer (SHPO) has concurred with NNSA/NFO’s determination that the district is eligible for listing in the National Register of Historic Places (NRHP) under Criteria A and C at the national level, with a period of significance of 1951 to 1992, which encompasses the period of nuclear testing at the Nevada National Security Site. The utility systems are not considered individually eligible for the National Register, but are contributing components to the eligibility of the district. This report combines information from an unpublished preliminary historic context on the underground utilities written prior to the initiation of recording activities and included as an attachment to the MOA and new data acquired during the course of meeting the MOA requirements. In addition to documenting the underground utility components exposed during excavation of discovery holes to verify pipe locations, Desert Research Institute (DRI) also recorded numerous above-ground elements and equipment in accessible vaults to develop a more complete representation of the historic utilities in Mercury. The information below is organized in the order it is discussed in the MOA.

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2019

Xyce Parallel Electronic Simulator Reference Guide (V.6.12)

This document is a reference guide to the Xyce Parallel Electronic Simulator, and is a companion document to the Xyce Users' Guide [1]. The focus of this document is (to the extent possible) exhaustively list device parameters, solver options, parser options, and other usage details of Xyce. This document is not intended to be a tutorial. Users who are new to circuit simulation are better served by the Xyce Users' Guide.

47 OTHER INSTRUMENTATION↗
DOE OSTI2019

MELCOR Code Change History: Revision 11932 to 14959 Patch Release Addendum

This document summarily provides brief descriptions of the MELCOR code enhancement made between code revision number 11932 and 14959. Revision 11932 represents the last official code release; therefore, the modeling features described within this document are provided to assist users that update to the newest official MELCOR code release, 14959. Along with the newly updated MELCOR Users' Guide and Reference Manual, users will be aware and able to assess the new capabilities for their modeling and analysis applications. Following the official release an addendum section has been added to this report detailing modifications made to the official release which support the accompanying patch release. The addendums address user reported issues and previously known issues within the official code release which extends the original Quick look document to also support the patch release. Furthermore, the addendums section documents the recent changes to input records in the Users' Guide applicable to the patch release and corrects a few issues in the revision 14959 release as well.

97 MATHEMATICS AND COMPUTING↗
DOE OSTI2019

SNL CSP Library Archive Project (FY19 Report)

Sandia National Laboratories (SNL) National Solar Thermal Test Facility (NSTTF) and Tech Library have been collaborating over the course of the FY19 period to establish and maintain the first and only digital collection in the world of Concentrating Solar Power (CSP) related historical documents, dating back to the CSP program inception here at Sandia in the 1970's thru to the present. The unclassified, unrestricted (UUR) collection, comprised of internally generated Sandia documents as well as a significant number of external reports will be searchable via both the Sandia website and OSTI, DOE's document repository. DOE is currently championing efforts to get the collection launched, where international partners, which include Australia and Germany, plan to forward related documents to be included in the CSP archive. Advancing this transformative project will make the CSP collection accessible to the Sandia and global communities.

14 SOLAR ENERGY↗
DOE OSTI2020

MCNP6 Source Primer: Release 1.0

This document contains examples of MCNP general source usage to support the MCNP6 User’s Manual. The examples range from basic to advanced sources with different applications. There are also examples of how MCNP can fail and warnings for the users to look for at the output to ensure proper results are being created. The overall aim of this document is to provide solid examples of how to define sources with MCNP as well as how to verify the sources are setup properly. The reasoning for needing such complex sources is not discussed in the present work. Also, this document is not meant to be exhaustive of every MCNP source option and combinations of source options possible. However, it is intended to frequently update this document with new source examples provided by users. Please feel free to contact the MCNP6 development team to learn about how to submit a new or updated source example. Please include “General Sources Primer” in the subject line to route the request to the appropriate developers.

97 MATHEMATICS AND COMPUTING↗
DOE OSTI2020

Scan of an Unpublished Report: "Fission Product Behavior During Severe LWR Accidents: Recommendations for the MELCOR Code System"

This document provides a scanned version of a 1987 SAND report that was never formally published. However, this report was referenced within the MELCOR Reference Manual and, therefore, provides historical information and technical basis for the MELCOR code. This document is being made available to permit users of the MELCOR code access to the information. The title page has been edited to prevent any confusion with regards to the possible documentation identifiers, such as the SAND report number or the intended date of publication. Beyond these modifications, a cover, distribution, and back cover are prepended and appended to the document to conform to modern SAND report style guidelines. The first four chapters of this report were updated and released under the title "Fission Product Behavior During Severe LWR Accidents: Recommendations for the MELCOR Code System. Volume I" and were made available by the U.S. NRC through the Adams database under accession number ML19227A327. No prior release of the remaining content of this report has occurred.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2020

Verification and Validation of the PLTEMP/ANL Code for Thermal-Hydraulic Analysis of Experimental and Test Reactors

The document compiles in a single volume the verification and validation works done for the PLTEMP/ANL code during the years of its development and improvement. The verification of sixteen capabilities of the PLTEMP/ANL Version 4.3 code that were identified by research reactor analysts as frequently used in their thermal-hydraulic analysis are described and documented. Each chapter of the document deals with the verification or validation of a specific model. The model verification is usually done by comparing the code with hand calculation, Microsoft spreadsheet calculation, or Mathematica calculation. The model validation is done by comparing the code with experimental data or a widely tested code like the RELAP5 code. In addition, some PLTEMP/ANL verification works that are available in the open literature are simply referenced and not included in the document. PLTEMP/ANL has been used in conversion safety analysis reports of several US and foreign research reactors that have been licensed and converted. A list of such reactors is given.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗
DOE OSTI2020

Vadose Zone Model for B-3A/B Pond for Composite Analysis

The objectives of the vadose modeling for the updated Hanford Site composite analysis (CA) are to simulate the flow and transport of water and radionuclide releases from the surface to the water table and to provide radionuclide transfer rates for the plateau to river (P2R) model, version 8.3 (CP-57037, Model Package Report: Plateau to River Groundwater Model, Version 8.3). Water additions include natural recharge and water discharged to the ground as a result of industrial processes associated with Hanford Site operations. Contaminant sources include radionuclides in water discharged to the ground during operations and radionuclides disposed “dry” in solid waste burial grounds or other means. The following 16 radionuclides were selected for this modeling effort; carbon-14 (C-14), chlorine-36 (Cl-36), tritium (H-3), iodine-129 (I-129), neptunium-237 (Np-237), rhenium-187 (Re-187), strontium-90 (Sr-90), technetium-99 (Tc-99), uranium-232 (U-232), uranium-233 (U-233), uranium-234 (U-234), uranium-235 (U-235), uranium-236 (U-236), uranium-238 (U-238), radium-226 (Ra-226), and thorium-230 (Th-230). The simulation time starts in 1943 and ends at 12070, which is 10,000 years after assumed Hanford Site closure in 2070. The parallel version of the Subsurface Transport Over Multiple Phases (STOMP) simulator officially named the exascale Subsurface Transport Over Multiple Phases (eSTOMP), is used to simulate flow and transport for the vadose models. The documentation for the STOMP code is comprehensive. The theoretical and numerical approaches applied in the STOMP code are documented in a published theory guide (PNNL-12030, STOMP Subsurface Transport Over Multiple Phases Version 2.0 Theory Guide). The code has undergone a rigorous verification procedure against analytical solutions, laboratory-scale experiments, and field-scale demonstrations. The application guide (PNNL-11216, STOMP Subsurface Transport Over Multiple Phases Application Guide) provides instructive examples in the application of the code to classical groundwater problems. The user’s guide (PNNL-15782, STOMP: Subsurface Transport Over Multiple Phases Version 4.0: User’s Guide) describes the general use, input file formatting, compilation, and execution of the code. The primary output of the vadose zone modeling is radionuclide transfer rates to the groundwater for input into the P2R model. The rates will be summed over the 100 by 100 m P2R grid cells that fall within the vadose zone model source domain. The Hanford Site Central Plateau was subdivided into 26 individual vadose zone models, with 13 in the 200 East Area and 13 in the 200 West Area. Waste sites that have a completed performance assessment (PA) or past-leak analysis were not included as sources of radionuclides. Instead the vadose zone to groundwater transfer rates of the Environmental Restoration Disposal Facility, Integrated Disposal Facility, US Ecology, and Waste Management Area C (WMA C) PAs and the past-leak analysis for WMA C were used as direct input to the P2R model. Each of the vadose zone models is documented in separate environmental calculation files (ECFs). This ECF describes the B-3A/B Ponds model. The scope of this ECF is to document the development and results of the B-3 A/B Ponds vadose zone model. CP-63515, Model Package Report: Central Plateau Vadose Zone Models, describes the approach, assumptions, process of determining the number of models required and domain of each model, input data, and processing common to all the models.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2019

Review of Amendment Delivery and Distribution Methods, and Relevance to Potential In Situ Source Area Treatment at the Hanford Site

The U.S. Department of Energy’s Hanford Site in southeastern Washington State is a complex of multiple facilities where historical release events in the Central Plateau area have resulted in subsurface contamination of the vadose zone, a perched-water zone, and underlying aquifer. Although some contaminants have already migrated through the vadose zone into the groundwater, contaminants remaining in the unsaturated zone are a potential long-term risk as a source for further groundwater contamination. Moreover, a perched-water zone located in the 200-DV-1 Operable Unit at Hanford creates further remediation difficulties. Remediation options are limited for contaminants located in the vadose and perched-water zones within the Central Plateau due to considerable depth, co-located contaminants, and complexities associated with physical and biogeochemical heterogeneities. Existing comprehensive reviews discuss potential remedial technologies relevant to Hanford Site conditions (e.g., deep vadose zone and perched water) and provide treatment technology recommendations. Many of the recommended in situ remediation technologies rely on introduction of amendments into the subsurface to achieve remedial goals. However, there are currently few review or guidance documents that provide a comprehensive look at mechanisms and considerations related to amendment delivery and distribution. This document summarizes amendment types, delivery techniques, subsurface access methods, and the applicability of delivery methods and amendments for specific subsurface target zones, including in the context of Hanford Central Plateau applications. Guidance on the appropriateness of a remedial technology for a specific site and contaminant is not included within this document. Rather, this document is intended to be used when considering remediation technologies and the associated amendments. An overview of amendment types (i.e., liquid, gas, and solids) and access/distribution methods used in subsurface remediation is provided, along with discussion of the maturity level (low, medium, or high), advantages, and limitations that relate to the potential effectiveness of each approach in the context of site-specific factors (subsurface geology, geochemistry, contaminant properties, etc.). There are many Hanford Site-specific factors that influence the suitability and appropriateness of amendment delivery strategies. Excluding amendment delivery approaches that are unsuitable for the Hanford context, each approach was assessed for applicability to the following target zones: unsaturated high permeability, unsaturated low permeability, perched water, saturated high permeability, and saturated low permeability zones. This compilation and discussion related to amendment delivery mechanisms provides a useful resource for evaluating remedial alternatives for source area contamination in the Hanford Central Plateau.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2020

Vadose Zone Model for SALDS for Composite Analysis

The objectives of the vadose modeling for the updated Hanford Site composite analysis (CA) are to simulate the flow and transport of water and radionuclide releases from the surface to the water table and to provide radionuclide transfer rates for the plateau to river (P2R) model, version 8.3 (CP-57037, Model Package Report: Plateau to River Groundwater Model, Version 8.3). Water additions include natural recharge and water discharged to the ground as a result of industrial processes associated with Hanford Site operations. Contaminant sources include radionuclides in water discharged to the ground during operations and radionuclides disposed “dry” in solid waste burial grounds or other means. The following 16 radionuclides were selected for this modeling effort: carbon-14 (C-14), chlorine-36 (Cl-36), tritium (H-3), iodine-129 (I-129), neptunium-237 (Np-237), rhenium-187 (Re-187), strontium-90 (Sr-90), technetium-99 (Tc-99), uranium-232 (U-232), uranium-233 (U-233), uranium-234 (U-234), uranium-235 (U-235), uranium-236 (U-236), uranium-238 (U-238), radium-226 (Ra-226), and thorium-230 (Th-230). The simulation time starts in 1943 and ends at 12070, which is 10,000 years after assumed Hanford Site closure in 2070. The parallel version of the Subsurface Transport Over Multiple Phases (STOMP1) simulator, officially named the exascale Subsurface Transport Over Multiple Phases (eSTOMP) is used to simulate flow and transport for the vadose models. The documentation for the STOMP code is comprehensive. The theoretical and numerical approaches applied in the STOMP code are documented in a published theory guide (PNNL-12030, STOMP Subsurface Transport Over Multiple Phases Version 2.0 Theory Guide). The code has undergone a rigorous verification procedure against analytical solutions, laboratory-scale experiments, and field-scale demonstrations. The application guide (PNNL-11216, STOMP Subsurface Transport Over Multiple Phases Application Guide) provides instructive examples in the application of the code to classical groundwater problems. The user’s guide (PNNL-15782, STOMP: Subsurface Transport Over Multiple Phases Version 4.0: User’s Guide) describes the general use, input file formatting, compilation, and execution of the code. The primary output of the vadose zone modeling is radionuclide transfer rates to the groundwater for input into the P2R model. The rates will be summed over the 100 by 100 m P2R grid cells that fall within the vadose zone model source domain. The Hanford Site Central Plateau was subdivided into 26 individual vadose zone models, with 13 in the 200 East Area and 13 in the 200 West Area. Waste sites that have a completed performance assessment (PA) or past-leak analysis were not included as sources of radionuclides. Instead the vadose zone to groundwater transfer rates of the Environmental Restoration Disposal Facility, Integrated Disposal Facility, US Ecology, and Waste Management Area C (WMA C) PAs and the past-leak analysis for WMA C were used as direct input to the P2R model. Each of the vadose zone models is documented in separate environmental calculation files (ECFs). This ECF describes the State-Approved Land Disposal Site (SALDS) model. The scope of this ECF is to document the development and results of the SALDS vadose zone model. CP-63515, Model Package Report: Central Plateau Vadose Zone Models, describes the approach, assumptions, process of determining the number of models required and domain of each model, input data, and processing common to all the models.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2020

Data call questions related to potential NEPA/Data gaps

Based on review of the related NEPA documents, and consideration of the potential gaps in NEPA coverage, a number of questions have been generated. These questions are generally higher level (less detailed) questions that should help to establish the applicability of analyses in existing NEPA documents and the ability of these documents to provide NEPA coverage for the Proposed Action. These questions do not request detailed information about SRS facilities/activities and the Proposed Action like typically would be requested when performing impacts analyses for an EIS. We do not believe detail information is needed; if it is needed, it may be an indication that an SA is not the appropriate level of NEPA documentation for the Proposed Action.

54 ENVIRONMENTAL SCIENCES↗