Pacific Northwest Laboratory facilities radionuclide inventory assessment CY 1992-1993

Sula, M.J.; Jette, S.J.

doi:10.2172/10193495

Cited by 6 publications

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“…continuously sampled. Results of the 1992-1993 assessment were documented by Sula and Jette (1994) with updates in 1995, 1999, and 2001. This report documents the most recent m and assessments for 200 2.1…”

Section: Introductionmentioning

confidence: 78%

Assessment of Unabated Facility Emission Potentials for Evaluating Airborne Radionuclide Monitoring Requirements at Pacific Northwest National Laboratory - 2003

Ballinger¹,

Sula²,

Gervais³

et al. 2003

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ph: (865) 576-8401 fax: (865) 576-5728 email: reports@adonis.osti.gov Available to the public from the National Technical Information Service, U.S. Department of Commerce, 5285 Port Royal Rd., Springfield, VA 22161 ph: (800) 553-6847 fax: (703) 605-6900 email: orders@ntis.fedworld.gov online ordering: http://www.ntis.gov/ordering.htm Abstract Assessments were performed to evaluate compliance with the airborne radionuclide emission monitoring requirements in the National Emission Standards for Hazardous Air Pollutants (NESHAP -U.S. Code of Federal Regulations, Title 40, Part 61, Subpart H) and Washington Administrative Code (WAC) 246-247: Radiation Protection -Air Emissions. In these assessments, potential unabated offsite doses were evaluated for emission locations at facilities owned by the U.S. Department of Energy and operated by Pacific Northwest National Laboratory (PNNL) on the Hanford Site. This report describes the inventory-based methods and provides the results for the assessment performed in 2003. vi

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Section: Introductionmentioning

confidence: 78%

Assessment of Unabated Facility Emission Potentials for Evaluating Airborne Radionuclide Monitoring Requirements at Pacific Northwest National Laboratory - 2003

Ballinger¹,

Sula²,

Gervais³

et al. 2003

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“…Thus, the 331 Building main stack is maintained as a major stack and continuously sampled. Results of the 1992-1993 assessment were documented by Sula and Jette (1994), and results of the 1995 assessment were documented in Ballinger, Jette, and Sula (1995). This report documents the most recent methods and assessments for 1999.…”

Section: 1mentioning

confidence: 89%

Assessment of Unabated Facility Emission Potentials for Evaluating Airborne Radionuclide Monitoring Requirements at Pacific Northwest National Laboratory - 1999

Dl¹,

Shields²,

Sula³

et al. 1999

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Portions of this document may be illegible in electronic image products. Images are produced from the best available original document. Summary Assessments were performed to evaluate compliance with the airborne radionuclide emission monitoring requirements in the National Emission Standards for Hazardous Air Pollutants (NESHAP-U.S. Code of Federal Regulations, Title 40 Part 61, Subpart H). In these assessments, potential unabated offsite doses were evaluated for emission locations at facilities owned by the U.S. Department of Energy and operated by Pacific Northwest National Laboratory (pacific Northwest) on the Hanford Site. Two of the facilities evaluated, 325 Building Radiochernical Processing Laboratory, and331 Building Life Sciences Laboratory met state and federal criteria for continuous sampling of airborne radionuclide emissions. One other building, the 3720 Environmental Sciences Laboratory, was recognized as being in transition with the potential for meeting the continuous sampling criteria. The assessments were performed using building radionuclide inventory data obtained in 1999. The list of buildings evaluated is provided in Table S. 1.

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“…Annual release quantities associated with an effective dose equivalent of 0.01 mrem were calculated from dose factors calculated using the EPA compliance code CAP-88 (Sula and Jette 1994). These values are shown in Table 7.2.…”

Section: Stack Radionuclide Sampling System Performancementioning

confidence: 99%

“…(d) Based on submission of silica gel containing 20 mL of water loading, and lab analysis minimum detection level of 1.5 pCi/aliquot for an aliquot size of 5 mL (Le., 300 pCi/L). (e) Based on dose per release factors calculated using CAP-88(Sula and Jette 1994). (f) Dose factor for noncondensible tritium (HT) is about 100 times that for condensible (HTO)tritium.…”

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confidence: 99%

Facility effluent monitoring plan for the 324 Facility

1994

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This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor Battelle Memorial Institute, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for theaccuracy, completeness, orusefulness ofany information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof, or Battelle Memorial Institute. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. PACIFIC NORTHWEST LABORATORY operated by BATTELLE MEMORIAL INSTITUTE for the UNITED STATES DEPARTMENT OF ENERGY under Contract DE-AC06-76RLO I830 @ The contents of this report were printed on recycled paper-DISCLAIMER Portions of this document may be illegible electronic image products. Images are produced from the best available original document. Summary Airborne Effluents Liquid Effluents The 324 Facility in the 300 Area primarily supports the research and development of radioactive and nonradioactive waste vitrification technologies (Le., ceramic melters, in situ vitrification [ISV], Hanford Waste Vitrification Program design support), biological waste remediation technologies, spent nuclear fuel studies, waste mixing and transport studies, and tritium development programs. All of the above-mentioned programs deal with, and have the potential to, release hazardous and/or radioactive material. The potential for discharge would primarily result from 1) conducting research activities using the hazardous materials, 2) storing radionuclides and hazardous chemicals, and 3) waste accumulation and storage. The following summarizes the airborne and liquid effluents, and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterizing effluent streams, monitoring/ sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements.

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Pacific Northwest Laboratory facilities radionuclide inventory assessment CY 1992-1993

Cited by 6 publications

References 0 publications

Assessment of Unabated Facility Emission Potentials for Evaluating Airborne Radionuclide Monitoring Requirements at Pacific Northwest National Laboratory - 2003

Assessment of Unabated Facility Emission Potentials for Evaluating Airborne Radionuclide Monitoring Requirements at Pacific Northwest National Laboratory - 2003

Assessment of Unabated Facility Emission Potentials for Evaluating Airborne Radionuclide Monitoring Requirements at Pacific Northwest National Laboratory - 1999

Facility effluent monitoring plan for the 324 Facility

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