NEVADA NATIONAL SECURITY SITE, WASTE DISPOSAL OPERATIONS - DISPOSAL VOLUME REPORT FY 2021 - QUARTER TWO
FY21 Second Quarter Volume Report
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FY21 Second Quarter Volume Report
This chapter, together with Appendix H, provides the necessary CWTS inventory limits and trigger values for every parent radionuclide not screened out in Sections 2.3.6, 2.3.7, and 2.3.8. Also provided are details associated with how generic and special waste forms are handled on a DU-specific basis, and a discussion of the conversion of preliminary inventory limits (via transport runs summarized in Chapter 5) into final inventory limits for use in the CWTS limits system. Using the final inventory limits, a projected 2065 CWTS inventory is generated for use in the PA closure analysis outlined in Chapter 9.
The Technical Optimization Model (TOM) is used by Savannah River Mission Completion (SRMC) to carry out facility-wide material balance and validate chemistrydependent processes for the purpose of their System Plan.The TOM simulates material movement and chemical reactions at the Tank Farm (TF), Salt Waste Processing Facility (SWPF) and Defense Waste Processing Facility (DWPF).
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Chapter 12 includes references for the entire report.
This appendix to Chapter 5, Section 5.1 provides supplemental concentration profiles for radionuclide species in STs and ETs that contribute to at least 0.1% of the sum-of-fractions. All concentrations are reported as pCi L -1 per Ci parent buried. The following nomenclature is used for all radionuclides in all DUs: an uppercase letter suffix indicates a SWF (e.g., I-129G, C-14N, H-3F, etc.), while the absence of an uppercase letter denotes a generic waste form (e.g., I-129, C-14, H-3, etc.).
This chapter summarizes activities performed to ensure the quality of the information throughout the PA.
Supplemental transport model results for the LAWV from Chapter 5, Section 5.2.2 are provided in Section E.1.1 to compare concentrations at the 100-meter POA for the nominal PA case, best estimate case, and various sensitivity cases (Figure E-1 through Figure E-12). Second, Figure E-13 through Figure E-30 in Section E.1.2 display concentrations at the 100-meter POA for decay-chain daughter and parent radionuclides. Third, Figure E-31 through Figure E-34 in Section E.1.3 show maximum concentration contours for I-129. Only contour plots for I-129 from the remaining sensitivity runs are shown because I-129 is identified as the only radionuclide that impacts disposal limits for the LAWV. All concentration units, whether noted or not in the y-axis labels, are pCi L-1 per Ci parent buried.
Table A-1, Table A-2, and Table A-3, respectively, list SAs, UDQEs, and other analyses and assessments prepared in support of the ELLWF since the previous ELLWF PA was issued in early 2008.
This appendix contains information and key data in support of Chapter 3 and Chapter 8. The following topics are addressed: PIF aquifer cutouts for ELLWF aquifer flow and transport analyses. Limits aquifer cutouts for ELLWF aquifer flow and transport analyses.
This chapter provides a description of the methods used for the sensitivity and uncertainty quantification analyses and identifies the parameters and assumptions found to be most important in the determination of compliance with PA performance objectives, development of WAC, establishment of individual DU inventory limits, and other regulatory decisions.
The work documented within this PA is the result of years of multidisciplinary research and modeling activities accomplished through the efforts of the individuals named in this section. Individuals who directly helped prepare this report are listed in Section 11.1; those who significantly contributed to the work described herein are acknowledged in Section 11.2.
This chapter summarizes safety functions and features, events, and processes; conceptual models which apply to all DUs; property data packages; and modeling tools developed and implemented in this PA to analyze ELLWF performance. Conceptual models of GW flow and transport in the VZ, which are specific to type of DU, are presented in Chapter 4.
This appendix contains supporting information and key data used during the IHI analysis, including the following: • A list of parent radionuclides requiring IHI inventory limits (Section G.1) • Tables of IHI acute and chronic dose factors, inventory limits, and concentration limits for all DUs (Section G.2) • IHI acute and chronic dose history time profiles for all DUs (Section G.3)
For the GW and air pathways described in Sections 3.5, 3.6, and 3.7, POs are evaluated for MOPs based on a 100-meter POA for all DUs. In this chapter, POs are assessed for the IHI who may physically disrupt the facility at some time after the end of IC and when the POA is at the DUs (Aleman et al., 2021).
This chapter summarizes the results of PA compliance against all relevant PA POs and measures. The final inventory limits presented in Chapters 7 and 8, as well as the methodology employed, provide assurance that POs will be met throughout the compliance periods. Deterministic and stochastic closure analyses also demonstrate a minimal likelihood of exceeding POs. Potential peaks post compliance are also addressed where future work is proposed to improve the understanding in actual uncertainties.
In accordance with DOE M 435.1-1 requirements and as implemented by DOE/RL-2000-29, the U.S. Department of Energy (DOE), Richland Operations Office has prepared this annual summary for fiscal year (FY) 2023 for maintenance of the Hanford Site Composite Analysis reported in DOE/RL-2019-52 (hereinafter referred to as the updated Hanford Site Composite Analysis). This is the first annual summary report to transition from maintenance of the initial Hanford Site Composite Analysis reported in PNNL-11800 and PNNL-11800, Addendum 1 to maintenance of the updated Hanford Site Composite Analysis following DOE approval of that update.