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Site Management Guide (Blue Book)

The U.S. Department of Energy (Department) Office of Legacy Management (LM), established in 2003, manages the Department’s postclosure responsibilities and ensures the future protection of human health and the environment. During World War II and the Cold War, the Federal government developed and operated a vast network of industrial facilities for the research, production, and testing of nuclear weapons, as well as other scientific and engineering research. These processes left a legacy of radioactive and chemical waste, environmental contamination, and hazardous facilities and materials at well over 100 sites. Since 1989, the Department has taken an aggressive accelerated cleanup approach to reduce risks and cut costs. At most Departmental sites undergoing cleanup, some residual hazards will remain at the time cleanup is completed due to financial and technical impracticality. However, the Department still has an obligation to protect human health and the environment after cleanup is completed. LM fulfills DOE’s postclosure obligation by providing long-term management of postcleanup sites which do not have continuing missions. LM is also responsible for sites under the Formerly Utilized Sites Remedial Action Program (FUSRAP). Currently, the U.S. Army Corps of Engineers (USACE) is responsible for site surveys and remediation at FUSRAP sites. Once remediation is completed, LM becomes responsible for long-term management. LM also has responsibility for uranium processing sites addressed by Title II of the Uranium Mill Tailings Radiation Control Act (UMTRCA). UMTRCA Title II sites are sites that were commercially owned and are regulated under a U.S. Nuclear Regulatory Commission (NRC) license. For license termination, the owner must conduct an NRC-approved cleanup of any on-site radioactive waste remaining from former uranium ore-processing operations. The site owner must also provide full funding for inspections and, if necessary, ongoing maintenance. Once site cleanup is complete, LM accepts title to these sites on behalf of the United States and assumes long-term management.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Integrating repositories with fuel cycles: The airport authority model

The organization of the fuel cycle is a legacy of World War II and the cold war. Fuel cycle facilities were developed and deployed without consideration of the waste management implications. This led to the fuel cycle model of a geological repository site with a single owner, a single function (disposal), and no other facilities on site. Recent studies indicate large economic, safety, repository performance, nonproliferation, and institutional incentives to collocate and integrate all back-end facilities. Site functions could include geological disposal of spent nuclear fuel (SNF) with the option for future retrievability, disposal of other wastes, reprocessing with fuel fabrication, radioisotope production, other facilities that generate significant radioactive wastes, SNF inspection (navy and commercial), and related services such as SNF safeguards equipment testing and training. This implies a site with multiple facilities with different owners sharing some facilities and using common facilities - the repository and SNF receiving. This requires a different repository site institutional structure. We propose development of repository site authorities modeled after airport authorities. Airport authorities manage airports with government-owned runways, collocated or shared public and private airline terminals, commercial and federal military facilities, aircraft maintenance bases, and related operations - all enabled and benefiting the high-value runway asset and access to it via taxi ways. With a repository site authority the high value asset is the repository. The SNF and HLW receiving and storage facilities (equivalent to the airport terminal) serve the repository, any future reprocessing plants, and others with needs for access to SNF and other wastes. Non-public special-built roadways and on-site rail lines (equivalent to taxi ways) connect facilities. Airport authorities are typically chartered by state governments and managed by commissions with members appointed by the state governor, county governments, and city governments. This structure (1) enables state and local governments to work together to maximize job and tax benefits to local communities and the state, (2) provides a mechanism to address local concerns such as airport noise, and (3) creates an institutional structure with large incentives to maximize the value of the common asset, the runway. A repository site authority would have a similar structure and be the local interface to any national waste management authority. (authors)

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Ten Years of Legacy Management: U.S. DOE Office of Legacy Management Accomplishments - 13246

The U.S. Department of Energy (DOE) established the Office of Legacy Management (LM) to provide a long-term, sustainable solution to environmental impacts that remain from nuclear weapons production during World War II and the Cold War. The production activities created adverse environmental conditions at over 100 sites. When LM was established on December 15, 2003, it became responsible for 33 sites where active environmental remediation was complete. Currently, LM is responsible for long-term surveillance and maintenance of environmental remedies, promotion of beneficial reuse of land and buildings, and management of records and information at 89 sites in 29 states and Puerto Rico. LM is also responsible for meeting contractual obligations associated with former contractor workers' pensions and post-retirement benefits. Effectively addressing this environmental and human legacy will continue to require a focused and well-managed effort. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

The Walls Come Tumbling Down: Decontamination and Demolition of 29 Manhattan Project and Cold War-Era Buildings and Structures at Los Alamos National Laboratory-12301

When the nation's top scientists and military leaders converged on Los Alamos, New Mexico in the 1943, to work on the Manhattan Project, the facilities they used to conduct their top-secret work were quickly constructed and located in the middle of what eventually became the Los Alamos town site. After one of these early facilities caught on fire, it seemed wise to build labs and production facilities farther away from the homes of the town's residents. They chose to build facilities on what was then known as Delta Prime (DP) Mesa and called it Technical Area 21, or TA-21. With wartime urgency, a number of buildings were built at TA-21, some in as little as a few months. Before long, DP Mesa was populated with several nondescript metal and cinder-block buildings, including what became, immediately following the war, the world's first plutonium production facility. TA-21 also housed labs that used hazardous chemicals and analyzed americium, tritium and plutonium. TA-21 was a bustling center of research and production for the next several decades. Additional buildings were built there in the 1960's, but by the 1990's many of them had reached the end of their service lives. Labs and offices were moved to newer, more modern buildings. When Los Alamos National Laboratory received $212 million in funding from the American Recovery and Reinvestment Act in July 2009 for environmental cleanup projects, about $73 million of the funds were earmarked to decontaminate and demolish 21 of the old buildings at TA-21. Although some D and D of TA-21 buildings was performed in the 1990's, many of the facilities at DP Site remained relatively untouched for nearly three decades following their final operational use. In 2006, there were over three dozen buildings or structures on the mesa to be removed so that soil cleanup could be completed (and the land made available for transfer and reuse). The total footprint of buildings across the mesa was approximately 18,580 m{sup 2} (200,000 ft{sup 2}). The initially approved baseline for the ARRA D and D Project was to remove 22 buildings and structures that included approximately 14,680 m{sup 2} (158,000 ft{sup 2}) of footprint. By employing efficiencies during subcontracting, demolition, and waste segregation, the savings allowed an additional 1,580 m{sup 2} (17,000 ft{sup 2}) of footprint to be removed using ARRA funds. Additionally, the lessons learned from this experience were used to apply NNSA funding to the removal of six additional non-contaminated buildings and structures. In the end, 29 buildings and structures, including stacks, cooling towers and tanks, were removed from the mesa. The entire DP East area was cleared of buildings and sub-grade structures and the soils cleaned to residential standards. The total footprint reduction at TA-21 as a result of this effort was in excess of 17,650 m{sup 2} (190,000 ft{sup 2}). The use of a Laboratory self-performance team to start demolition of non-contaminated structures resulted in steady work performance early in the project while subcontracts were being put in place to perform more complicated abatement and contaminated demolition activities. Most importantly, there were no serious worker injuries and the minor injuries recorded were those common to construction type activities. Extensive monitoring along the site boundary demonstrated that no hazardous chemicals or radioactive contamination were released and radiological dose to the public was negligible. The ARRA demolition activities were completed six months in advance of the deadline for employing ARRA funds. Additionally, over 17,585 m{sup 3} (23,000 yds{sup 3}) of building demolition debris was safely removed from DP Mesa. All of the major buildings have been removed, unencumbered access to the SWMUs that are required to be cleaned up by the Consent Order with the state of New Mexico, has been achieved, and a significant portion of the mesa has been prepared to support a process that will eventually transfer this land from federal government control for further use. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Evaluation of the Effects of Microbes on Autunite Dissolution and the Spectral Induced Polarization Response in Hanford Vadose Zone Sediment - 18440

As a result of the U.S. nuclear weapons program during the second World War and throughout the Cold War, there now exists a significant amount of uranium contamination at the U.S. Department of Energy Hanford site located in Washington State. Much of this contamination is in the form of mobile uranyl carbonates species within the vadose zone, which at Hanford varies up to 100 m thick in the Central Plateau. In-situ immobilization of mobile uranium via injections of a soluble sodium tripolyphosphate amendment may prove effective in the formation of low-solubility uranyl phosphate solid phases, autunite. However, the injected polyphosphate undergoes hydrolysis in aqueous solutions to form orthophosphate, which serves as a readily available nutrient for the various microorganisms in the sediment. Sediment-filled column experiments conducted under saturated oxygen restricted conditions using a geophysical technique known as spectral induced polarization (SIP) have shown the impact of microbes on the dissolution of synthetic autunite. Two sets of experiments were conducted using test columns. Each experiment had a pair of columns inoculated with microbes (with a glucose solution acting as a nutrient source) which were monitored using SIP in conjunction with regular sampling of pore-water. Columns were built with two silver/silver chloride (Ag/AgCl) coiled current electrodes at either end and four Ag potential electrodes along the side, which allowed the measurement of three distinct points along the length of the column. SIP measures phase which is the time delay between an injected current and measured voltage, in this case measured in radians. Three sampling ports were added to correspond with the geophysical measurements. Pore-water samples taken over the course of the experiment were analyzed for dissolved elements including uranium, iron, phosphorous, calcium, and magnesium. SIP results were plotted over time in order to determine correlations between changes in electrical phase and changes in pore-water chemistry. It was determined that changes in the phase and bulk resistivity detected with SIP corresponded to changes in the pore-water chemistry due to the growth of microbes. The first experiment ran for five months and had measurements done once a week, the second only ran one month but had measurements taken five times a week in order to understand initial changes in column chemistry in greater detail. SIP may be an effective way to remotely track changes indicative of bacterial activities on the surrounding environment. This method has the potential for field application at a larger scale for the purpose of tracking microbe growth in response to tripolyphosphate amendment. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Uranium Partitioning upon Ammonia Gas Treatment on Phyllosilicate Minerals

In the past, > 200,000 kg of U was released to the Hanford Site vadose zone from disposal and leakage of waste byproducts from plutonium production during World War II and the Cold War (Zachara et al., 2007). U is highly mobile due to the presence of carbonates and oxidizing conditions, with K{sub d} of 0.1 - 8 mL/g at the site (Zachara et al., 2007; Szecsody et al., 2013; Serne et al., 2008). NH{sub 3} (gas) injection is being investigated as a remediation technique as it is an in situ method that will not introduce additional liquid that could drive contaminants deeper into vadose zone towards groundwater. Objectives: To understand the impact of alkaline injection on geochemical processes in the Hanford Site vadose zone, including: 1)Long-term fate of uranium (U); 2)Dissolution and re-precipitation of secondary minerals. Apparent K{sub d}'s increase significantly with NH{sub 3} gas treatment, especially for six-month aging. - K{sub d} decreases after aeration, primarily due to U desorption at lower pH. U removal is still significantly greater than natural conditions (K{sub d} < 8 vs. > 100 mL/g). - Three-day aeration has higher loading than six-month after ammonia gas treatment and aeration. However, significantly greater desorption of U occurs with aeration in the six-month aged sample potentially due to transformation into different, more soluble solid phases with longer term aging. - U removal is primarily due to (1) co-precipitation of U with secondary minerals and (2) adsorption to minerals' surface, although further research is required to identify dominant mechanisms. Future experiments will focus on garnering a better understanding of the solid phase U speciation. Solids will be characterized using SEM-EDS, EMPA, XPS, XAFS, and TEM to better understand the effects of basic treatments on initial minerals and formation of secondary precipitates.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Iodine Speciation Across the Length of the Hanford 200-UP-1 Operable Unit Radioiodine Plume and Biogeochemical Drivers of Speciation - 17270

In 1943, construction began on the first of nine nuclear reactors at the Hanford Site to produce plutonium for the development of atomic weapons for the Manhattan Project during World War II and throughout the Cold War. Over a production period lasting from 1944 to 1987, approximately 110,000 tons of nuclear fuel was processed. During the production period, billions of gallons of liquid nuclear waste and millions of tons of solid waste were produced. Approximately 4.7 Ci of radioiodine (I-129) was discharged to liquid disposal sites, during disposition of the waste. Following percolation of the liquid waste through the vadose zone, three large I-129 groundwater plumes have formed beneath Central Plateau Facilities including both 200 East and 200 West Areas. Analysis of I-129 plumes in the 200-ZP-1 Operable Unit (OU) (200 West Area) showed iodine speciation that was dominated by iodate even though iodide was thought to be dominant species in waste. Experimental results demonstrated that iodate interacts with calcite via a co-precipitation and/or adsorption mechanism. From sorption experiments performed on Hanford sediments, iodate interacted more strongly than iodide during adsorption experiments. These results would indicate that iodate migration would be retarded compared to iodide, but results from groundwater samples obtained from eight wells in the 200 ZP-1 OU did not support this hypothesis. Due to different chemical processes used during plutonium processing, iodine species in other plumes such as in the 200-UP-1 OU (200 West Area) may be different. In addition, species distribution may change longitudinally between the source area and the distal end of the plume. Groundwater samples will be taken at a location near the source, in the middle of the plume and at the distal end of the plume. These samples will be analyzed for iodine speciation using ion chromatography coupled to an inductively coupled plasma mass spectrometer. Results from the different samples will be compared to give an initial determination of species distribution at different locations along the plume. Data generated from these samples can then be used to inform the conceptual model that is being developed for iodine as part of an evaluation of remediation options for the 200-UP-1 OU. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Nuclear Weapons and the Atmospheric Test Era

The era of atmospheric testing defies a simple description. Beginning with the goal of proving fission, the United States’ test program grew in complexity as scientists explored thermonuclear reactions, met the military demand for a variety of weapons for an increasing number of delivery platforms, and reacted to the ever-growing public fear of fallout. And, of course, political considerations were always present, first in the prosecution of World War II and later in the Cold War. To understand the atmospheric test program, then, is to understand how science, politics, and the public shaped our society in ways that are still difficult to fully understand.

45 MILITARY TECHNOLOGY, WEAPONRY, AND NATIONAL DEF↗

Integrity Monitoring, Prediction and Assessment, Corrosion Control, and Repair of the Hanford Storage Tanks – 25213

The Hanford Nuclear Reservation site contains approximately 211 million liters of radioactive and chemically hazardous waste arising from nuclear weapons production, beginning with World War II, and continuing through the Cold War [1]. The waste is stored in 177 carbon-steel underground storage tanks, of which 149 are single-shell tanks (SSTs) and the remaining are double-shell tanks (DSTs). The mission of an ongoing River Protection Project is to retrieve the waste from the underground storage tanks and then treat and immobilize (i.e., vitrify) it for disposal. Waste from the older SSTs is being progressively retrieved into the newer DSTs for storage pending treatment, immobilization, and disposal. Figure 1 depicts a typical DST design [2]. The tank is approximately 23 m in diameter and 9 m high and has a domed structure and has a capacity of 4000 m3. The tank wall and floor vary in thickness between approximately 10 mm and 25 mm depending on location. The thicker wall sections are near the curved transition between the tank wall and the floor, while the thinner sections are located near the top of the tank wall. The tank floor thickness varies from 25 mm at the tank center to 10 mm near the tank wall. The tanks were constructed of either ASTM A516 Grade 65 or ASTM A537 Class 1 carbon steel and were post-weld heat treated to reduce the risk of SCC.

Shukla, Pavan K. [Savannah River National Laborato↗

Feasibility Study for Cathodic Protection of Waste Tanks at Hanford

The Hanford Nuclear Reservation site contains approximately 211 million liters of radioactive and chemically hazardous waste arising from nuclear weapons production, beginning with World War II, and continuing through the Cold War. The waste is stored in 177 carbon-steel underground storage tanks, of which 149 are single-shell tanks (SSTs) and the remaining are double-shell tanks (DSTs). The mission of an ongoing River Protection Project is to retrieve the waste from the underground storage tanks and then treat and immobilize (i.e., vitrify) it for disposal. Waste from the older SSTs is being progressively retrieved into the newer DSTs for storage pending treatment, immobilization, and disposal. Waste chemistry controls are in place to mitigate general corrosion, pitting corrosion, and stress corrosion cracking (SCC) and minimize corrosion risks to the carbon steel tank liners of DST at the Hanford Site. The chemistry control program focuses on preserving liner integrity while balancing the need for caustic/nitrite additions that have large downstream impacts on vitrification. Some of the DSTs store salt cake or sludge waste layers contain out-of-specification interstitial liquids that contact the primary tank bottom or sidewall. Remediation of such layers through chemical additions is not practical. At the present time, the most significant leak integrity concern at Hanford is for corrosion of the tank bottoms of DSTs where the solids layer is out of specification because of hydroxide ion depletion and consequently, pH values that are less than 12. Cathodic protection (CP) has been proposed as a possible way to protect the liners of such tanks against corrosion. The objective of this project was to investigate the feasibility of applying CP to Hanford DSTs to mitigate internal corrosion of the carbon steel tank primary liners. The scope of the project included (1) a literature review on the application of CP to storage tank systems, in general, and to waste tanks at the Savannah River Site (SRS) and Hanford, (2) a review of the finite element analysis (FEA) model recently developed to evaluate potentials for a DST, and (3) the development of a boundary element analysis (BEA) model for CP for a DST. Tank AN-107, one of the Hanford DSTs, was selected for this work because (1) the bottommost waste layer in the tank is out-of-specification, and (2) electrochemical and resistivity data, based on recent waste sampling and testing, are available for this tank. The overarching conclusion of this study is that, based on the available information, it is feasible to apply CP to mitigate internal corrosion of the primary liners of the Hanford DSTs. However, significant additional information and work are required before a CP system can be designed. Recommendations for next steps in the design of the CP system will be presented.

WIERSMA, BRUCE↗

Progress Update: Reactor Disassembly Grouting

Grouting the P&R reactors in order to remove these basins as an environmental threat. This will end the Cold War legacy and end the environmental footprint.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

The Architecture of Mercury - Nevada's Atomic Boom Town: An Architectural Survey of Mercury, Area 23, Nevada National Security Site, Nye County, Nevada (Rev. 1)

The U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) plans to modernize the Mercury town site at the Nevada National Security Site in Nye County, Nevada, to meet current and future National Weapons Science, Global and Homeland Security Programs, and Environmental Management mission requirements. These plans include anticipated demolitions, consolidations, and rebuilding at Mercury to be an undertaking subject to review under Title 54 U.S.C. § 306108, commonly known as Section 106 of the National Historic Preservation Act, Title 54 U.S.C. §300101, et seq., and its implementing regulations, 36 C.F.R. Part 800. Prior to the present survey, Mercury had not yet been systematically recorded, and therefore an area of approximately 364 hectares (900 acres) was surveyed for architectural resources by the Desert Research Institute. This effort resulted in the identification, recording, and evaluation of the Mercury Historic District (SHPO Resource No. D230), including the identification of its contributing components. This district is recommended eligible to the National Register of Historic Places under Criteria A and C. It is unevaluated under Criteria B and D at this time. The Mercury Historic District contains 154 individual landscapes, buildings, and structures. Of these resources, all except one are recommended as contributing elements of the historic district during its period of significance corresponding to nuclear testing from 1951 through 1992. During most of the Cold War, the land now called the Nevada National Security Site was named the Nevada Test Site.

54 ENVIRONMENTAL SCIENCES↗

The Architecture of Area 12 Camp - Nevada's Atomic Ghost Town. An Architectural Survey of Area 12 Camp, Nevada National Security Site, Nye County, Nevada

The U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) plans to demolish 10 buildings and one structure in Area 12 Camp at the Nevada National Security Site (NNSS) in Nye County, Nevada, to meet current and future National Weapons Science, Global and Homeland Security Program, and Environmental Management mission requirements and to reduce dangers to site workers from some of these resources. These demolitions constitute an undertaking subject to review under Title 54 U.S.C. § 306108, commonly known as Section 106 of the National Historic Preservation Act, Title 54 U.S.C. § 300101, et seq., and its implementing regulations, 36 C.F.R. Part 800. These resources were recorded and evaluated as individually ineligible for the National Register of Historic Places (National Register or NRHP) by Menocal and Shaw (2019). Upon review by the Nevada State Historic Preservation Office (SHPO) and internal review by Desert Research Institute (DRI) and NNSA/NFO staff, it was determined that these resources needed to be rerecorded and evaluated in relation to what appeared to be a National Register-eligible Historic District made up of the entirety of Area 12 Camp. Based on preliminary information, it appeared that all 11 resources would likely be contributing elements of that historic district. With that assumption in mind, recording of the entire proposed Area 12 Camp Historic District was done for three purposes. First, it would result in a definitive significance evaluation of the 11 resources in question. Second, recording of the entire camp would be offered as an appropriate mitigation measure for the demolition of these resources. Third, it would present an essential background for future management of resources within the district boundaries. Prior to the present survey, Area 12 Camp had not yet been systematically recorded; therefore, DRI surveyed an area of approximately 229 acres for architectural resources. This effort resulted in the identification, recording, and evaluation of the Area 12 Camp Historic District (SHPO Resource No. D372), including the identification of its contributing components. This district is recommended eligible for the National Register of Historic Places under Criteria A and C. It is unevaluated under Criteria B and D. The Area 12 Historic District contains 71 Principal Resources, which include landscapes, buildings, and structures. Of these resources, 69 (including 10 of the 11 resources to be removed) are recommended as contributing elements of the historic district during its period of significance corresponding to nuclear testing from 1960 through 1992. During most of the Cold War, the government reservation now called the NNSS was named the Nevada Test Site (NTS).

54 ENVIRONMENTAL SCIENCES↗

Evaluation of Fire Station 23-425, Mercury, Area 23, Nevada National Security Site, Nye County, Nevada

The U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) plans to modernize the Mercury town site at the Nevada National Security Site (NNSS) in Nye County, Nevada, to meet current and future National Weapons Science, Global and Homeland Security Programs, and Environmental Management mission requirements. These plans—including anticipated demolitions, consolidations, and rebuilding at Mercury—are considered an undertaking subject to review under Title 54 U.S.C. § 306108, commonly known as Section 106 of the National Historic Preservation Act, Title 54 U.S.C. § 300101, et seq., and its implementing regulations, 36 C.F.R. Part 800. Desert Research Institute (DRI) completed an architectural survey of Mercury. This effort resulted in the identification, recordation, and evaluation of the Mercury Historic District, including the identification of its contributing components. This district was recommended eligible for listing to the National Register of Historic Places (NRHP or National Register) under Criteria A and C but was unevaluated under Criteria B and D at that time. The Mercury Historic District contains 153 individual landscapes, buildings, and structures. Of these resources, all except one are recommended as contributing elements of the historic district during its period of significance corresponding to nuclear testing from 1951 through 1992. During most of the Cold War, the land now called the NNSS was named the Nevada Test Site (NTS). This report concerns the proposed demolition of the 1966 Fire Station 23-425 in Mercury as a phase of the larger modernization program mentioned above. Further evaluation of this property indicates that it does not meet any of the Secretary of the Interior’s Significance Criteria for eligibility for the NRHP at either the national or local levels. However, it does remain an important contributing element of Mercury Historic District. This is part of a series of reports.

54 ENVIRONMENTAL SCIENCES↗

Evaluation of 1950s-Era Architectural Resources in Blocks 10, 11, and 17, Mercury, Area 23, Nevada National Security Site, Nye County, Nevada

The U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) plans to modernize the Mercury town site at the Nevada National Security Site (NNSS) in Nye County, Nevada, to meet current and future National Weapons Science, Global and Homeland Security Programs, and Environmental Management mission requirements. These plans, including anticipated demolitions, consolidations, and rebuilding at Mercury, are considered an undertaking subject to review under Title 54 U.S.C. § 306108, commonly known as Section 106 of the National Historic Preservation Act, Title 54 U.S.C. § 300101, et seq., and its implementing regulations, 36 C.F.R. Part 800. The Desert Research Institute (DRI) completed an architectural survey of Mercury. This effort resulted in the identification, recording, and evaluation of the Mercury Historic District (Nevada State Historic Preservation Office [SHPO] Resource No. D230), including the identification of its contributing components (Reno et al. 2018). This district was recommended eligible to the National Register of Historic Places (NRHP or National Register) under Criteria A and C but was unevaluated under Criteria B and D at that time. The Mercury Historic District contains 154 individual landscapes, buildings, and structures. Of these resources, DRI recommends all except one as contributing elements of the historic district during its period of significance corresponding to nuclear testing from 1951 through 1992. During most of the Cold War, the land now called the NNSS was formerly the Nevada Test Site (NTS). This report is concerned with evaluating resources dating to the 1950s in Blocks 10, 11, and 17 in Mercury prior to the proposed demolition of 22 resources in Blocks 10 and 11 as a phase of the larger modernization program mentioned above. Although the Mercury Historic District as a whole is eligible to the National Register, further evaluation of these properties as detailed in this report indicates that none are individually eligible under any of the Secretary of Interior’s Significance Criteria, either at the national or local level. This is one report in the report series "Evaluation, Finding of Effect, and Mitigation Documentation for 1950s-Era Architectural Resources, Mercury, Area 23, Nevada National Security Site, Nye County, Nevada".

54 ENVIRONMENTAL SCIENCES↗

A Section 110 Evaluation of the Project 57 Rad-Safe Area Personnel Decontamination Building, Nye County, Nevada

Project 57 was an open-air, plutonium-dispersal safety test conducted by the United States in 1957 on a portion of the Nevada Test and Training Range (NTTR) (formerly the Las Vegas Bombing and Gunnery Range). The Project 57 test area, once known as Area 13, was a block of land abutting the northeastern boundary of the Nevada Test Site (NTS). The NTS was renamed the Nevada National Security Site (NNSS) in 2010. In keeping with the historical Cold War period designation, NTS will be used when discussing historic period events, while NNSS will be applied for contemporary activities. During Project 57, the high explosives of a nuclear weapon were triggered asymmetrically to simulate an accidental detonation. The test was conducted to study the extent of plutonium contamination from a nonnuclear yield accident, as well as assess the biological and environmental hazards such an event could create. Following the conclusion of the experiment, the contaminated area surrounding the ground zero (GZ) was fenced off and some of the contaminated equipment was buried in place. The Project 57 Rad-Safe area was abandoned. In 1981, the U.S. Department of Energy (DOE) decontaminated and decommissioned the Project 57 site. This Section 110 documentation was prompted by recognition that more than five decades have passed since the abandonment of the Project 57 Rad-Safe area, particularly the personnel decontamination building, which leaves the temporary structure vulnerable to natural forces of weathering and decay. However, these temporary facilities remain partially standing, allowing for a condition assessment and recommendations regarding the Rad-Safe area’s historical significance. The National Nuclear Security Administration, Nevada Field Office (NNSA/NFO) determined there was no area of potential effect (APE) (direct, indirect, or visual) because there is no planned undertaking and the Project 57 Rad-Safe area will continue to remain unused. Instead, a 4.5-acre study area was established to facilitate recording the Project 57 personnel decontamination building and the remaining accessory resources. The study area is bounded on the east by Valley Road and it extends to the east far enough to encompass the former Project 57 Rad-Safe area (Figure A-2). The Section 110 study area is located in the northwest quarter of Section 35, Township 07S Range 54E Mount Diablo Base and Meridian. It is on the 1962 Groom Mine SW USGS 7.5-minute series topographic quadrangle. Desert Research Institute (DRI) surveyed the Section 110 study area, resulting in the recording and evaluation of the Project 57 Rad-Safe area personnel decontamination building and four accessory resources (AR-1 through AR-4). Copies of the building form and report are on file at DRI and with the NNSA/NFO in Las Vegas, Nevada.

54 ENVIRONMENTAL SCIENCES↗

Technetium Incorporation in Glass for the Hanford Tank Waste Treatment and Immobilization Plant

A priority of the United States Department of Energy (U.S. DOE) is to dispose of nuclear wastes accumulated in 177 underground tanks at the Hanford Nuclear Reservation in eastern Washington State. These nuclear wastes date from the Manhattan Project of World War II and from plutonium production during the Cold War. The DOE plans to separate high-level radioactive wastes from low activity wastes and to treat each of the waste streams by vitrification (immobilization of the nuclides in glass) for disposal. The immobilized low-activity waste will be disposed of here at Hanford and the immobilized high-level waste at the national geologic repository. Included in the inventory of highly radioactive wastes is large volumes of 99Tc (~9 × 10E2 TBq or ~2.5 × 104 Ci or ~1500 kg). A problem facing safe disposal of Tc-bearing wastes is the processing of waste feed into in a chemically durable waste form. Technetium incorporates poorly into silicate glass in traditional glass melting. It readily evaporates during melting of glass feeds and out of the molten glass, leading to a spectrum of high-to-low retention (ca. 20 to 80%) in the cooled glass product. DOE-ORP currently has a program at Pacific Northwest National Laboratory (PNNL), in the Department of Materials Science and Engineering at Rutgers University and in the School of Mechanical and Materials Engineering at Washington State University that seeks to understand aspects of Tc retention by means of studying Tc partitioning, molten salt formation, volatilization pathways, and cold cap chemistry. Another problem involves the stability of Tc in glass in both the national geologic repository and on-site disposal after it has been immobilized. The major environmental concern with 99Tc is its high mobility in addition to a long half-life (2.1×105 yrs). The pertechnetate ion (TcO4-) is highly soluble in water and does not adsorb well onto the surface of minerals and so migrates nearly at the same velocity as groundwater. Long-term corrosion of glass waste forms is an area of current interest to the DOE, but attention to the release of Tc from glass has been little explored. It is expected that the release of Tc from glass should be highly dependent on the local glass structure as well as the chemistry of the surrounding environment, including groundwater pH. Though the speciation of Tc in glass has been previously studied, and the Tc species present in waste glass have been previously reported, environmental Tc release mechanisms are poorly understood. The recent advances in Tc chemistry that have given rise to an understanding of incorporation in the glass giving rise to significantly higher single-pass retention during vitrification are presented. Additionally, possible changes to the baseline flowsheet that allow for relatively minor volumes of Tc reporting to secondary waste treatment will be discussed.

Kruger, Albert A.↗