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At least 289 records · Page 16
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DOE OSTI2018

Marine Sciences Laboratory Radionuclide Air Emissions Report for Calendar Year 2017

The U.S. Department of Energy Office of Science (DOE-SC) Pacific Northwest Site Office has oversight and stewardship duties associated with the Pacific Northwest National Laboratory Marine Sciences Laboratory (MSL), located on Battelle Land-Sequim. The facility has two buildings with the potential to emit low levels of radioactive materials. This report is prepared to document compliance with the Code of Federal Regulation, Title 40, Protection of the Environment, Part 61, National Emission Standards for Hazardous Air Pollutants, Subpart H, “National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities” and Washington Administrative Code Chapter 246-247, Radiation Protection–Air Emissions. Compliance is indicated by comparing the estimated effective dose equivalent (EDE) to the maximally exposed individual (MEI) with the 10 millirem per year (mrem/yr) U.S. Environmental Protection Agency (EPA) standard. The MSL has only fugitive emissions sources. Despite the fact that the regulations are intended for application to point source emissions, fugitive emissions are included with regard to complying with the EPA standard. The EDE to the MSL MEI due to routine operations in 2017 was 1.6E-04 mrem (1.6E-06 mSv). No non-routine emissions occurred in 2017. The MSL is in compliance with the federal and state 10 mrem/yr standard.

40 CFR 61 Subpart H↗
DOE OSTI2018

PNNL Richland Campus Radionuclide Air Emissions Report for Calendar Year 2017

This report documents radionuclide air emissions that result in the 2017 highest effective dose equivalent (EDE) to an offsite member of the public, referred to as the maximally exposed individual (MEI). The report has been prepared in compliance with the Code of Federal Regulations, Title 40, Protection of the Environment, Part 61, National Emission Standards for Hazardous Air Pollutants, Subpart H, “National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities” and Washington Administrative Code Chapter 246-247, “Radiation Protection–Air Emissions.” The dose to the PNNL Richland Campus MEI from routine major and minor point source emissions in 2017 from PNNL Richland Campus sources is 2.1E-5 mrem (2.1E-7 mSv) EDE. The dose from all fugitive sources is 2.1E-6 mrem (2.1E-8 mSv) EDE. The dose from radon emissions is 3.9E-10 mrem (3.9E-12 mSv) EDE. No nonroutine emissions occurred in 2017. The total radiological dose to the MEI from all PNNL Richland Campus radionuclide emissions, including fugitive emissions and radon, is 2.3E-5 mrem (2.3E-7 mSv) EDE, or more than 10,000 times less than the federal and state standard of 10 mrem/yr, with which the PNNL Richland Campus is in compliance.

40 CFR 61 Subpart H↗
DOE OSTI2018

Pacific Northwest National Laboratory Annual Site Environmental Report for Calendar Year 2017

This report provides a synopsis of ongoing environmental management performance and compliance activities conducted during 2017, to meet the requirements of DOE Order 231.1B, Environmental, Safety and Health Reporting, and DOE Order 458.1, Radiation Protection of the Public and the Environment. The report addresses the operations that occur on the PNNL Richland Campus in Richland, Washington, and at the PNNL Marine Sciences Laboratory (MSL) near Sequim, Washington. It describes the location of and background for each facility; addresses compliance with all applicable DOE, federal, state, and local regulations and site-specific permits; documents environmental monitoring efforts and their status; presents potential radiation doses to staff and the public in the surrounding areas; and describes DOE-required data quality assurance methods used for data verification.

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2017

Chemical Waste Landfill Annual Post-Closure Care Report Calendar Year 2016

The purpose of this CWL Annual Post-Closure Care Report is to document monitoring, inspection, maintenance, and repair activities conducted during CY 2016 in accordance with PCCP Attachment 1. This annual report documents post-closure care activities conducted from January through December 2016 and fulfills the PCCP requirement for annual reporting to the NMED. The PCCP requires monitoring, inspection, and maintenance/repair activities that must be documented and reported for each CY. Monitoring activities include semi-annual groundwater monitoring for specific volatile organic compounds (VOCs) and metals, and annual vadose zone soil-gas monitoring for specific VOCs. Inspection, maintenance, and repair activities are required for the following components: final cover (vegetation and surface); storm-water diversion structures; monitoring networks and sampling equipment (groundwater and soil-gas); and security fence, locks, gates, signage, and survey monuments. The CWL final cover is a vegetative at-grade soil cover, or ET Cover.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2018

Chemical Waste Landfill Annual Post-Closure Report Calendar Year 2017

The Chemical Waste Landfill (CWL) at SNL/New Mexico (SNL/NM) is a remediated hazardous waste landfill that underwent closure. The CWL Post-Closure Care Permit (PCCP), which became effective June 2, 2011 and as modified, defines all post-closure requirements. This sixth CWL Annual Post-Closure Care Report documents all activities and results as required by the PCCP Attachment 1, Section 1.12.

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DOE OSTI2016

RCRA Permit for a Hazardous Waste Management Facility Permit Number NEV HW0101, Annual Summary/Waste Minimization Report, Calendar Year 2015, Nevada National Security Site, Nevada

This report summarizes the EPA identification number of each generator from which the Permittee received a waste stream, a description and quantity of each waste stream in tons and cubic feet received at the facility, the method of treatment, storage, and/or disposal for each waste stream, a description of the waste minimization efforts undertaken, a description of the changes in volume and toxicity of waste actually received, any unusual occurrences, and the results of tank integrity assessments. This Annual Summary/Waste Minimization Report is prepared in accordance with Section 2.13.5 of Permit Number NEV HW0101.

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DOE OSTI2019

National Emission Standards for Hazardous Air Pollutants - Radionuclide Emissions (Calendar Year 2018)

The U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) operates the Nevada National Security Site (NNSS) and the North Las Vegas Facility (NLVF). From 1951 through 1992, the NNSS was the continental testing location for U.S. nuclear weapons.The release of radionuclides from NNSS activities has been monitored since the initiation of atmospheric testing. After 1962, testing was limited to underground detonations, which greatly reduced radiation exposure to the public. Since the end of nuclear testing in 1992, radiation monitoring has focused on detecting airborne radionuclides from historically contaminated soils. These radionuclides are derived from re-suspension of soil (primarily by wind) and emission of tritium-contaminated soil moisture through evapotranspiration. Low amounts of legacy-related tritium are also emitted to air at the NLVF, an NNSS support complex in North Las Vegas. To protect the public from harmful levels of man-made radiation, the Clean Air Act, National Emission Standards for Hazardous Air Pollutants (NESHAP) (Title 40 Code of Federal Regulations [CFR] Part 61Subpart H) limits the release of radioactivity from a U.S. Department of Energy (DOE) facility to that which would cause 10 millirem per year (mrem/y) effective dose equivalent to any member of the public. This limit does not include radiation unrelated to NNSS activities. Unrelated doses could come from naturally occurring radioactive elements, from sources such as medically or commercially used radionuclides, or from sources outside of the United States, such as Japan’s Fukushima nuclear power plant, which was damaged in 2011. NNSA/NFO demonstrates compliance with the NESHAP limit by reporting environmental measurements of radionuclide air concentrations at critical receptor locations on the NNSS (U.S. Environmental Protection Agency [EPA] and DOE 1995). This method was approved by the EPA in 2001 and has been the method used to demonstrate compliance with the 40 CFR 61.92 dose standard since 2005. Six locations on the NNSS have been established to act as critical receptor locations to demonstrate compliance with the NESHAP limit. These locations are actually pseudo-critical receptor stations because no member of the public resides at these onsite locations. Compliance is demonstrated if the measured annual average concentration is less than the NESHAP Concentration Level (CL) for Environmental Compliance listed in 40 CFR 61, Appendix E, Table 2. For multiple radionuclides, compliance is demonstrated when the sum of the fractions (determined by dividing each radionuclide’s concentration by its CL and then adding the fractions together) is less than 1.0. In 2018, the potential dose from radiological emissions to air from both current and past NNSS activities was well below the 10 mrem/y dose limit. This is demonstrated by air sampling data collected at the critical receptor air monitoring stations which had average concentrations of radioactivity that were a fraction of the CL values. Concentrations ranged from 0.1% to a maximum of 5.2% of the allowed NESHAP limit. Clean Air Package 1988 (CAP88-PC) was used to model dose to the offsite public from all 2018 NNSS radionuclide emissions. The model showed the maximally exposed individual to be on the northern end of Amargosa Valley; this individual received a potential dose of 0.07 mrem/y. The potential dose to the public from NLVF emissions was also very low at 0.000008 mrem/y, over six orders of magnitude lower than the 10 mrem/y limit.

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2016

Corrective Action Management Unit Report of Post-Closure Care Activities (Calendar Year 2015)

The Corrective Action Management Unit (CAMU) at Sandia National Laboratories, New Mexico (SNL/NM) consisted of a containment cell, two treatment systems, and four associated waste staging and storage areas, and support areas; all were used for management of remediation wastes between 1997 and 2003. The U.S. Department of Energy and Sandia Corporation (Sandia) operated the CAMU in accordance with the requirements of: (1) The Class III Permit Modification Request for the CAMU (SNL/NM September 1997, as amended); and (2) Module IV of Permit NM5890110518, “Special Conditions Pursuant to the 1984 Hazardous and Solid Waste Amendments (HSWA) to Resource Conservation and Recovery Act (RCRA) for Sandia National Laboratory, U.S. Environmental Protection Agency (EPA) Identification Number NM5890110518,” August 1993, (EPA 1993, as amended) and subsequently administered by the New Mexico Environment Department (NMED). The CAMU underwent closure in 2003 in accordance with the Closure Plan in Appendix D of the Class III Permit Modification (SNL/NM September 1997). The containment cell was closed with wastes in place. Hazardous wastes were removed from all other CAMU systems and areas, and they underwent clean closure. The NMED approved completion of closure in May 2004 (Kieling May 2004). From May 2004 until February 2015, the containment cell underwent post-closure care (i.e., monitoring, inspections, maintenance, and repairs) in accordance with the Closure Plan. On December 19, 2014, NMED renewed the Hazardous Waste Facility Operating Permit (Permit) for Sandia National Laboratories. The renewed Permit was issued January 26, 2015 (NMED January 2015) with an effective date of February 26, 2015. The CAMU is undergoing post-closure care in accordance with the Permit.

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DOE OSTI2016

Solid Waste Management Units and Areas of Concern Annual Long-Term Monitoring and Maintenance Report for Calendar Year 2015, March 2016

Long-term controls were maintained at 21 Solid Waste Management Units (SWMUs) and Areas of Concern (AOCs) in accordance with the requirements of the Long-Term Monitoring and Maintenance Plan for SWMUs and AOCs Granted Corrective Action Complete with Controls in Attachment M of the Resource Conservation and Recovery Act Facility Operating Permit which took effect February 26, 2015. Maintenance and controls at these SWMUs and AOCs are described and documented in this report. The need for maintenance or repair activities were not identified at any of the inspected SWMUs or AOCs. Four repairs identified in 2014 were completed in 2015. Based upon the inspections performed and site conditions observed, the administrative and physical institutional controls in place at the SWMUs and AOCs are effectively providing continued protection of human health and the environment.

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

Chemical Waste Landfill Annual Post-Closure Care Report, Calendar Year 2019

The Chemical Waste Landfill (CWL) at Sandia National Laboratories/New Mexico (SNL/NM) is a remediated hazardous waste landfill that underwent closure in accordance with Title 20, Chapter 4, Part 1 of the New Mexico Administrative Code (20.4.1.600 NMAC), incorporating Title 40, Code of Federal Regulations (CFR), Part 265, (40 CFR § 265) Subpart G, and the CWL Final Closure Plan (SNL/NM December 1992 and subsequent revisions). The CWL Post- Closure Care Permit (PCCP) (NMED October 2009), which became effective June 2, 2011 (Kieling June 2011) and as modified, defines all post-closure requirements. This ninth CWL Annual Post-Closure Care Report documents all activities and results as required by the PCCP Attachment 1, Section 1.12.

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DOE OSTI2020

Nevada National Security Site E-Tunnel Wastewater Disposal System Quarterly Monitoring Report, Water Pollution Control Permit NEV 96021 (First Quarter Calendar Year 2020)

This report includes the results of monthly inspections and monitoring for January, February, and March 2020. Monthly inspections and monitoring were conducted on January 15, February 12, and March 17, 2020. Inspections include a visual assessment of the berms, ponding, water levels relative to the overflow pipes, tunneling or burrowing into the berms, soil conditions on and around the berms, erosion or sloughing of the slopes of the berms, seeps at the toe of the berms, deep-rooting botanicals on the berms, and fencing. Monthly monitoring includes measurements of the instantaneous flow rate, hydrogen ion activity (pH), and specific conductance of the E-Tunnel Wastewater Disposal System discharge.

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DOE OSTI2021

Chemical Waste Landfill Annual Post-Closure Report. Calendar Year 2020

The purpose of this CWL Annual Post-Closure Care Report is to document monitoring, inspection, maintenance, and repair activities conducted during CY 2020 as required by PCCP Attachment 1, Section 1.12 (NMED October 2009 and subsequent revisions). This annual report documents post-closure care activities conducted from January through December 2020 and fulfills the PCCP requirement for annual reporting to the NMED.

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DOE OSTI2021

Results for the First Quarter Calendar Year 2021 Tank 50 Salt Solution Sample

Tank 50 aqueous waste is analyzed on a quarterly basis and the results are compared to the Waste Acceptance Criteria (WAC) of the Z-Area Saltstone Production Facility (SPF). The information from this characterization will be used by Savannah River Remediation (SRR) for the transfer of aqueous waste from Tank 50 to SPF, where the waste will be treated and disposed in the Saltstone Disposal Facility. This Technical Report compares results, where applicable, to SPF WAC Limits and Targets. A memorandum reporting the average Cs-137 value and comparison to WAC Limits has been previously issued.

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DOE OSTI2022

Results for the September Bimonthly Calendar Year 2021 Tank 50 Salt Solution Sample

In this Technical Report, the chemical and radionuclide contaminant results from the 2021 September bimonthly sample of Tank 50 salt solution are presented in tabulated form. The information from this characterization will be used by Savannah River Remediation (SRR) for the transfer of aqueous waste from Tank 50 to the Saltstone Production Facility (SPF), where the waste will be treated and disposed in the Saltstone Disposal Facility. This Technical Report compares results, where applicable, to SPF Waste Acceptance Criteria (WAC) Limits and Targets that were established at the time the Tank 50 sample was obtained. The chemical and radionuclide contaminant results from the characterization of the 2021 September bimonthly sampling of Tank 50 were requested by SRR personnel via a Task Technical Request (TTR) and details of the testing are presented in the Savannah River National Laboratory (SRNL) Task Technical and Quality Assurance Plan (TTQAP). This Technical Report is the TTR deliverable relating Salt Solution Analysis from the SRR request.

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DOE OSTI2020

Environmental Monitoring Report, Calendar year 2020. Knolls Laboratory and Kesselring Site

The results of the effluent and environmental monitoring programs at the Knolls Laboratory and Kesselring Site are summarized and assessed in this report. Tables 1 - 4 summarize the major elements of the environmental monitoring programs at each site. Information regarding the U.S. Department of Energy – Office of Environmental Management (DOE-EM) Separations Process Research Unit (SPRU) Disposition Project (SPRU DP), is also included in this report; however, the project was completed in 2020 and will no longer be reported in subsequent reports. DOE-EM will be continuing to perform other Decontamination & Decommissioning (D&D) work at Knolls Laboratory and Kesselring Site, which may require environmental monitoring, and will be included in this report, as warranted. Operations at the Knolls Laboratory, which includes SPRU and other DOE-EM activities, and the Kesselring Site continue to have no adverse effect on human health and the quality of the environment.

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2022

Results for the March Bimonthly Calendar Year 2022 Tank 50 Salt Solution Sample

In this Technical Report, the chemical and radionuclide contaminant results from the 2022 March bimonthly sample of Tank 50 salt solution are presented in tabulated form. The information from this characterization will be used by Savannah River Mission Completion (SRMC) for the transfer of aqueous waste from Tank 50 to the Saltstone Production Facility (SPF), where the waste will be treated and disposed in the Saltstone Disposal Facility. This Technical Report compares results, where applicable, to SPF Waste Acceptance Criteria (WAC) LIMITS and TARGETS that were established at the time the Tank 50 sample was obtained. The chemical and radionuclide contaminant results from the characterization of the 2022 March bimonthly sampling of Tank 50 were requested by SRMC personnel via a Task Technical Request (TTR) and details of the testing are presented in the Savannah River National Laboratory (SRNL) Task Technical and Quality Assurance Plan (TTQAP). This Technical Report is the TTR deliverable relating Salt Solution Analysis from the SRMC request.

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