ML15273A277

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Attachment to A. Mellon, NYSERDA 09-02-2015 Email, Draft Field Sampling and Dose Assessment Plan for the Western New York Nuclear Service Center in Follow-Up to the Aerial Gamma Radiation Survey Conducted in 2014, Prepared for NYSERDA-WVSMP
ML15273A277
Person / Time
Site: West Valley Demonstration Project, P00M-032
Issue date: 08/31/2015
From:
MJW Technical Services
To:
Office of Nuclear Material Safety and Safeguards, State of NY, Energy Research & Development Authority
Amy Snyder
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Download: ML15273A277 (17)
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Table of Contents

1. Background and Introduction .......................................................................................................... 2
2. Project Objectives ............................................................................................................................ 3
3. Relevant Public Exposure Regulations and Standards .................................................................... 3
4. Safety and ALARA Objectives........................................................................................................... 3
5. Quality Assurance Program Plan (QAPP)......................................................................................... 4
6. Participants, Roles, and Responsibilities ......................................................................................... 4
7. Areas Selected for Ground Truth Measurements .......................................................................... 5
8. General Methodologies to be used to Ground Truth Aerial Survey Results.9
9. Potential Obstacles and Contingency Strategy .................................................................. 14
10. Applicable Field Procedures..14
11. Reference Standards and Practices ............................................................................................... 14
12. Data Quality Objectives (DQO) ...................................................................................................... 15
13. Data Validation Strategy ................................................................................................................ 15

DRAFT Field Sampling and Dose Assessment Plan August 31, 2015

1. Background and Introduction The New York State Energy Research and Development Authority (NYSERDA) owns the 3,300-acre Western New York Nuclear Service Center (Center) in the Town of Ashford. Since 1982, NYSERDA and the U.S. Department of Energy (DOE) have been working at the Center to conduct the West Valley Demonstration Project (WVDP), a high-level radioactive waste solidification and cleanup project. In September 2014, DOE and NYSERDA jointly initiated an aerial radiological survey to examine the radiological conditions of the Western New York Nuclear Service Center (Center), adjacent areas, as well as, Cattaraugus Creek from the Center to Lake Erie in Western NY. This survey was conducted by the National Nuclear Security Administrations Remote Sensing Laboratory (RSL). NYSERDA and DOE are presently completing work related to the aerial radiation survey.

The 2014 aerial radiation survey shows five limited areas outside the Center property with radiation levels that are slightly above the background radiation levels seen throughout Western New York (these background levels are caused by naturally occurring radioactive materials like radon, and from certain man-made radioactive materials that are found throughout the environment today). Three of these areas were identified previously during the aerial surveys, and the two other locations were identified during the 2014 Aerial Survey.

Detailed evaluations that were conducted during the Cesium Prong Investigation showed that the levels were low and met all public health and safety standards. Given that radiation decays naturally over time, we would expect to see lower levels today than those seen in earlier surveys. The identification of the two new areas is likely due to either (i) the fact that the areas were not examined during earlier surveys, or ii) improvements in instrument sensitivity since the time of the earlier surveys.

To confirm the results of the new aerial radiation survey and show that the offsite areas continue to meet regulatory requirements for public health and safety, additional information is needed. In order to obtain that information, NYSERDA is initiating a program to conduct radiation surveys of the areas identified, collect and analyze soil samples from certain areas, and to complete a dose assessment for the purpose of confirming that the areas meet the regulatory standards for the protection of public health and safety.

As stated above, the purpose of this project is to collect sufficient data to ground-truth selected areas identified by the 2014 aerial survey, and utilize the data generated to estimate radiation exposures to the public considering current land use for the purpose of framing the aerial survey results within context of applicable regulatory requirements. This work is not being conducted as a MARSSIM-level decommissioning characterization activity. The soil sampling activity will focus on areas with elevated radiation levels as identified through the field surveys, and as such, sampling results will provide a biased and conservative assessment of the radiation doses in the areas of interest.

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DRAFT Field Sampling and Dose Assessment Plan August 31, 2015 It should also be noted that some of the areas identified as having above-background radiation levels in the 2014 aerial radiation survey were sampled and evaluated in detail by NYSERDA in the 1990s. These areas, known collectively as the Cesium Prong, were determined to be in compliance with the regulations for the protection of public health and safety (Dames and Moore, 1995). Because this area was extensively characterized in the 1990s, the current sampling program will not attempt to re-characterize the Cesium Prong. Instead, samples will be collected at several locations within the Cesium Prong to confirm that soil concentrations measured today are consistent with decay-corrected concentrations measured in the 1990s.

In addition, NYSERDA does not intend to prepare a new dose assessment for the Cesium (Cs)

Prong area as part of this current work activity. A copy of the 1995 Western New York Nuclear Service Center Off-Site Radiation Investigation Summary Report is available through NYSERDA.

This project will be conducted by MJW Technical Services, a radiation safety consulting company, under contract to NYSERDA.

2. Project Objectives The objectives of the survey and dose assessment project (the Project) are to:
a. Ground-truth the aerial radiation survey to confirm that areas identified as having above background levels of Cs-137 in the aerial radiation survey (using the RSL criteria described below), also show above background levels of Cs-137 in the soil sample results;
b. Perform radiological surveys of elevated locations identified in the 2014 aerial survey and collect and analyze soil samples from within these areas;
c. Use the radiation survey data and sample analysis results collected through this project to perform radiation dose assessments and determine maximum credible radiation exposures to members of the public using the current land use specific to each area.
3. Relevant Public Exposure Regulations and Standards The radiological surveys results and soil and stream sediment sample data will be compared to the relevant public exposure regulations and standards listed below:
a. 10 CFR 20.1101 - Radiation protection program
b. 10 CFR 20.1301 - Dose limits for individual members of the public
c. 10 CFR 20.1302 - Compliance with dose limits for individual members of the public
d. 40 CFR 190 - Environmental Radiation Protection Standards for Nuclear Power Operations In addition, the soil and sediment concentrations will be compared to the WVDP Phase 1 Decommissioning Plan, Revision 2, Derived Concentration Guidelines (DCGLs) for the current year, which represent radionuclide-specific concentrations that would achieve the regulatory dose standard for release of a licensed property and termination of the license without restrictions (i.e., < 25 mRem/year as per 10CFR 20.1402).
4. Safety and ALARA Objectives All project activities will be conducted in a safe manner, consistent with the ALARA principle of maintaining radiation exposures to a level that is as low as reasonably achievable, and MJW 3

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DRAFT Field Sampling and Dose Assessment Plan August 31, 2015 Technical Services commitment to safety manifested in our corporate and project specific safety plans. MJW Technical Services will conduct the survey and sampling activities under their approved New York State Department of Health Radioactive Materials License and application for reciprocity filed with the U.S. Nuclear Regulatory Commission.

5. Quality Assurance Program Plan (QAPP)

In order to ensure that the surveys and samples are representative, traceable, and reproducible from each boxed area, all activities will be completed per the requirements identified in the QAPP.

6. Participants, Roles, and Responsibilities The project will be performed, by MJW Technical Services, with support by NYSERDA staff. Key positions for executing the project are:

NYSERDA Project Manager The NYSERDA Project Manager will be the primary point of contact and coordination with the MJWTS Project Manager, and ensure that the MJWTS project manager is cognizant of relevant information, issues, objectives, requirements, and potential concerns or deficiencies.

Project Manager The Project Manager (PM) bears overall responsibility for execution of the sampling and exposure assessment activities. The project manager will ensure that the project is executed in a timely manner, in accordance with the project plan and in conformance with all applicable regulatory requirements.

Project Safety Director (PSD)

The Project Safety Director (PSD) will perform hazard and risk assessments as required, develop appropriate safety plans and mitigation methods, and will work with the Project Manager to ensure that the Project Safety Plan is followed and adapted, if required based upon unforeseen field conditions or situations.

Project Certified Health Physicist The Project Certified Health Physicist (PCHP) - will ensure that the collection and analysis of survey data, and the derived dose assessments, are conducted properly and in accordance with appropriate professional and regulatory standards and practices to ensure that results are accurate and defensible.

Project Radiation Safety Officer (RSO)

The Project RSO (PRSO) will ensure that all activities conducted will be in compliance with the MJWTS radioactive materials license, under reciprocity with the requirements of the Nuclear Regulatory Commission. The Project RSO is authorized to halt any action considered to be unacceptable from the standpoint of radiological safety or regulatory compliance.

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DRAFT Field Sampling and Dose Assessment Plan August 31, 2015 Project Health Physicist (HP)

The project HP (PHP) - will be responsible for health physics aspects of the execution of the sampling plan, will ensure that sampling plans are adapted as required to meet project objectives, and will bear primary responsibility for the analysis of survey and laboratory data, and for the performance of the exposure assessments.

Project Quality Assurance and Control Manager The Project Quality Assurance and Control Manager (PQA/QCM) - will be responsible for all aspects of project Quality Assurance and Quality Control actions, and will ensure that appropriate measures are implemented during survey operations, analysis operations, as well as, by the radiochemistry laboratory that is utilized.

Project Data Validation Specialist The Project Data Validation Specialist (PDVS) will be responsible for the validation of data as required by accepted professional practices and standards.

Project Field Supervisor The Project Field Supervisor (PFS) will be responsible for the in-field conduct of survey and sampling operations, and will ensure that applicable safety, compliance, and QA/QC requirements are followed during the execution of field activities. The PFS will supervise the activities of radiological control technicians and any other staff working in the field. The PFS will, in addition, ensure that all field operations are appropriately documented.

Project IT/GIS Specialist The Project IT/GIS Specialist (PITGIS) will be responsible for oversight of data file storage and the processing of acquired data, in particular, GPS-driven radiation survey data.

7. Areas Selected for Ground Truth Measurements Five areas have been selected by NYSERDA, in consultation with RSL, to be examined based upon the results of the aerial survey. The selected areas include location where total anthropogenic exposure and the Cs-137 extracted exposures exceed background levels. Five general areas have been selected (Survey Boxes) and within each Survey Box one or more areas have been selected to be surveyed (Sub Parcels).

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DRAFT Field Sampling and Dose Assessment Plan August 31, 2015 The GPS Coordinates for the approximate centroid of the Survey Boxes are:

Box Area 1 42°2746.97 N 78°4013.53 W Box Area 2 42°2825.66 N 78°4118.84 W Box Area 3 42°2856.20 N 78°4042.19 W Box Area 4 42°3223.84 N 79°0213.07W Box Area 5 42°3112.94 N 78°5825.11 W Figure 1 shows the general location of Survey Boxes 1, 2, and 3 are comparatively close to the WNYNSC site. The Green triangles show the general areas in which survey and sampling will occur.

a. Survey Box 1 includes the off-site portion of the Cesium Prong, which has been extensively characterized in the past. Confirmatory surveys and samples will be collected in this area. The area includes residential properties, with cleared and tree covered areas.
b. Survey Box 2 includes one sampling area that was identified during the Cesium Prong investigation, and three sampling areas identified during the Aerial Radiation Survey of 2014. Confirmatory surveys and samples will be collected in the area previously identified during the Cesium Prong investigation. The other three sampling areas appear to be related to the Cs Prong. These areas are not residential, and have varying terrain and tree cover. These areas were selected for analysis because they had not been observed in the earlier aerial surveys and as such, were not part of the previous Cesium Prong characterization effort.
c. Survey Box 3 includes a survey parcel at the confluence of Buttermilk and Cattaraugus Creeks. Surveys and dose assessment will be conducted to evaluate this active agricultural area.

Figure 2 shows the general location of Survey Boxes 4 and 5, which are located on the Cattaraugus Reservation of the Seneca Nation of Indians.

d. Survey Box 4 includes a wooded area, and the survey and sampling points will span Cattaraugus Creek. The survey parcels are wooded and do not include residences.
e. Survey Box 5 includes two survey parcels that are wooded and in near residential property.

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DRAFT Field Sampling and Dose Assessment Plan August 31, 2015 FIGURE 1 7

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DRAFT Field Sampling and Dose Assessment Plan August 31, 2015 Figure 2 8

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DRAFT Field Sampling and Dose Assessment Plan August 31, 2015

8. General Methodologies to be used to Ground Truth Aerial Survey Results
a. Extent of Survey The extent to which each area is surveyed will initially be determined by considering the size and physical characteristics of the area and the manner in which the area is used (for example open forest vs. agricultural).

Once survey operations commence, the extent of survey will be adapted based upon the initial GPS survey data as described below, as well as, on the ground observation of physical features, such as geological patterns or evidence of possible past stream meandering.

In survey areas that have not been historically evaluated or where the historical data is sparse, survey and sampling actions will be more extensive than in areas that have previously been well characterized. For areas that have been previously characterized, the survey will be used to identify an area where the confirmatory sample or samples will be collected.

b. Survey and sampling strategy The general methodology to conduct the radiological surveys will be as follows:
1. A course grid walkover survey (typically 20 to 30 meter spacing) will be conducted utilizing a 2x2 NaI gamma detector, coupled with a Ludlum Model 2241-2 scaler/ratemeter. The count rate signal from the Ludlum 2241-2 will be transferred to a GPS instrument which will simultaneously log the GPS position and count rate.

The logged data will subsequently be transferred to a computer to be displayed on a map and/or satellite image. Each count rate data point will be assigned to a count rate range. For example; 0-4,000 CPM, 4,001 to 8,000 CPM, 8,001 to 12,000, and greater than 12,000 CPM. These count rate ranges will be color coded (e.g.

green/yellow/orange/red) and displayed as the proper colored dot on the map or satellite image. It is important to note that the count rates in CPM are derived from dynamic (scanning) measurements and not from static counts. While the primary purpose of this data is to, in-part, guide the subjective selection of survey and sampling points, the data can be averaged, and the scanning survey sensitivities determined. Dose calculations, however, will be performed using the static survey measurement s, as subsequently described herein.

For purposes of background evaluation, static count rates and soil samples will be collected in areas in proximity to the survey parcel, but at least 30 meters outside the survey parcel, as determined by the aerial survey.

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DRAFT Field Sampling and Dose Assessment Plan August 31, 2015

2. Subjective observation of the count rate patterns, as displayed in the graphical image, will then be utilized to plan the second phase of survey operations which will include:
a. Tissue equivalent micro R readings at one cm and 100 cm elevation.
b. Static 2x2 NaI detector readings at contact and one meter elevation.
c. Collection of soil and stream sediment samples (zero to 15 cm and 15-30 cm depths) for Boxes 1, 2, 4 and 5.
d. Subsurface soil samples (to 100 cm depth) from Survey Box 3 Area.

The number of static survey and sampling points will be determined by the size of the survey parcel, as well as any patterns that emerge in the GPS/Dynamic count rate graphical patterns. For example, if all count rates are low, a limited number of samples and static survey points will be taken. If elevated areas are discerned, additional points will be taken. It should be noted that the survey areas will be slightly larger than the areas designated based upon the aerial data. In this manner, the color coded GPS count rate data can be used to evaluate if the elevated count rate areas determined by the ground data are smaller or larger, or alternatively shaped than areas derived from the aerial data. At least one sample will be collected in each Sub Zone.

A minimum of 30 background points will be selected for direct measurement and sample collection. This data will be used to determine the background mean over selected areas with similar topography and cover.

c. Sample Analysis Strategy
1. Standard Analysis - All soil and stream sediment samples will be analyzed for gross alpha and beta and gamma spectroscopy.
2. Expanded Analysis - Selected samples will be analyzed more extensively, based upon initial sample results, information gathered in the field, and project Quality Assurance/Quality Control requirements. The expanded analysis will require a 20 day ingrowth period for a precise analysis of some radionuclides, such as Radium-226, and as such will not be included in the dose assessment. If this analysis yields information that would have a significant impact on the dose assessment, the dose assessment will be revised.

Table 2 details the standard and expanded analysis parameters, analytical method, and minimum detectable concentration (MDC), and measurement units.

For informal comparison purposes, a minimum of 3 background samples will be collected from areas not associated with the project. This will include a sample from Hamburg, NY; Eden, NY; and Springville, NY.

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DRAFT Field Sampling and Dose Assessment Plan August 31, 2015 Table 1 - Standard and Expanded Analysis Information Analytical Parameter Method MDC Units Standard Analysis Gross Alpha EPA 900.0 Mod/SW 9310 Mod 4 pCi/g Gross Beta (Nonvolatile Beta) EPA 900.0 Mod/SW 9310 Mod 10 pCi/g Gamma Scan (Cs-137, Ac-227, Co-60, Cd- DOE HASL 300 4.5.2.3/Ga-01-R 0.1 (Cs-137 pCi/g 113m, Eu-154, Pa-231, Ra-226, Ra-228, Sb-125, Sn-126) Only)

Expanded Analysis Am-241,Cm-242,Cm-243/244,Cm- DOE HASL 300 1 pCi/g 245/246 Am-05-RC Mod C-14 EPA EERF C-01 Mod 2 pCi/g I-129 DOE HASL 300 I-01 1 pCi/g Np-237 DOE HASL 300 1 pCi/g Pu-238, 239/240 DOE HASL 300 1 pCi/g Pu-11-RC Mod Pu-241 DOE HASL 300 15 pCi/g Pu-11-RC Mod Sr-90 EPA 905.0 Mod 2 pCi/g Tc-99 DOE HASL 300 5 pCi/g Tc-02-RC Mod U-232 DOE HASL 300 1 pCi/g U-02-RC Mod U-233/234, U-235/236, U-238 DOE HASL 300 1 pCi/g U-02-RC Mod H-3 EPA 906.0 Mod 6 pCi/g Th-229 DOE HASL 300 1 pCi/g Th-01-RC Mod Th-228, Th-230, Th-232 DOE HASL 300 1 pCi/g Th-01-RC Mod Radium 226 (20-day ingrowth) DOEHASL 300 1 pCi/g 4.5.2.3/GA-01-R Radium 228 DOEHASL 300 3 pCi/g 4.5.2.3/GA-01-R 11 MT2015-4008

DRAFT Field Sampling and Dose Assessment Plan August 31, 2015

d. Dose Assessment Strategy Doses will be evaluated using the following strategy:
1. For each area to be sampled within a survey box, the appropriate RESRAD exposure scenario will be identified based on the current land use. Presently, the hiker/recreational receptor and the resident farmer receptor will be the exposure scenarios evaluated as part of ground-truthing the aerial survey results. The dose for these exposure scenarios will be calculated as described below.
2. For areas where external radiation is the primary exposure path (e.g. Hiker/recreational scenario) exposure rates will be derived from 1) the measured isotopic concentrations in the soil samples, 2) the static dose rate measurements, and 3) the aerial survey results.
3. For the resident farmer exposure scenario, the measured isotopic concentrations will be compared to the WVDP surface soil DCGLs represented by the Peak-of-the Mean values in Table 5-11a of the WVDP Decommissioning Plan. However, the DCGLs for Cs-137 and Sr-90 will be reduced by approximately 50% since the Table 5-11a DCGLs were calculated based on releasing the property for unrestricted us in 2041. These DCGLs were calculated to meet the 10 CFR 20.1402 standard for license termination without restrictions.
4. For samples that were analyzed for gamma spectroscopy, gross alpha, and gross beta, where the gross alpha result statistically exceeds background, the activity above background will be attributed to Am-241, the limiting alpha emitting isotope. Where the gross beta result statistically exceeds background, the activity above background will be attributed to Sr-90, the limiting beta emitting isotope.
5. The results from the evaluation described above will be compared to the relevant dose limits in the regulations identified in Table 2.
6. The Cs-137 calculated doses will also be tabulated so they may be easily compared to the Cs-137 doses derived by extraction from the aerial gamma radiation data for the purpose of evaluating the results of the aerial survey.
7. In areas previously characterized (i.e., Cesium Prong) there will be no additional action other than confirmatory soil sampling in several locations to compare decay corrected sampling results from the previous characterization project to levels today.

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DRAFT Field Sampling and Dose Assessment Plan August 31, 2015 Table 2 provides the dose assessment and modeling strategy that will be used to demonstrate compliance with the applicable regulations for all five of the identified areas. In addition, these results will be compared to the DCGLs for unrestricted release detailed in the WVDP Phase 1 Decommissioning Plan.

Table 2 - Dose Assessment and Modeling Strategy Identified Area 10CFR20.1101 10 CFR20.1301 10CFR20.1301 40CFR190 10 No. [<10mR/yr Air (a)(1)** (a)(2)** [<25 mR/yr. CFR20.1402 Path] [<100mR/yr] [<2 mR/hr] Whole Body: Comparison

<75 mR/yr. to WVDP Thyroid: Phase 1 DP

<25 mR/yr.

DCGLs^

Other Organs]

Box 1 - Cesium Completed Completed Completed Completed Completed Prong

  • Box 2 - Cesium No Inhalation Hiker Scenario Calculate Hiker Scenario Comparison Prong Pathway External Dose to WVDP Extension Rate/hr for DCGLs each identified location Box 3 - Field Farm Dust Resident Farmer Calculate Resident Farmer Comparison Buttermilk Inhalation Scenario. WVDP External Dose Scenario. WVDP to WVDP Creek Dose DCGLs will be Rate/hr for DCGLs will be DCGLs Assessment used. each identified used.

location Box 4 - Flood No Inhalation Hiker Scenario Calculate Hiker Scenario Comparison Plain 3 Pathway External Dose to WVDP Rate/hr for DCGLs each identified location Box 5 - Flood No Inhalation Hiker Scenario Calculate Hiker Scenario Comparison Plain 3 Near Pathway External Dose to WVDP Road Rate/hr for DCGLs each identified location

  • Cesium Prong sampling and dose modeling completed in 1995. Confirmatory soil sampling will be conducted.
    • - 10 CFR 1302 - Survey description detailed in Section 7

^ - DCGL will be for current year.

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DRAFT Field Sampling and Dose Assessment Plan August 31, 2015

9. Potential Obstacles and Contingency Strategy One potential obstacle to performing the radiological surveys is inadequate GPS signal (dead zones). This may occur in areas where there is excessive tree cover, or geological feature such as ridges, that may obstruct the GPS Satellite signals.

If this occurs across a very limited section of a Subzone, the survey team will obtain GPS coordinates at the edges of the dead zone and will note them in the survey logs. If low precision or cell tower based location information is available, the grid lines will be mapped and readings will be logged by hand at 20 meter intervals.

If the dead zone is substantial, GPS Survey will be conducted in the areas where it is possible, and grid lines will be established and walked down manually recording the data.

A second potential obstacle will be field conditions encountered that hamper the ability to collect readings in the prescribed geometries. For example, heavy vegetation may hinder the ability to obtain measurement at the prescribed 1 cm and 100 cm elevations. Field personnel will make their best effort to achieve the geometries; however, if this is too time consuming and threatens completion of the work on time, there may be some deviation which will be noted.

10. Applicable Field Procedures MJW Field Procedures applicable to the work will include:
  • Selection and Use of Survey Instruments
  • MJW Field Investigation Procedure
  • GPS Enhanced Overland Gamma Radiation Survey - Including Preparation and Assessment of Radiological and Geographical Data
  • Instrument Operation Procedure - Ludlum 2241-2 Ratemeter/Scaler Coupled with Ludlum 44-9 or Ludlum 44-10 2x2 NaI Detector
  • Instrument Operating Procedure - Bicron MicroRem Meter
  • Project Specific Sample Collection Procedure
  • QAPP
11. Reference Standards and Practices
  • NCRP Report No. 50, Environmental Radiation Measurement, December 1976
  • NUREG 1507,Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions, (December 1997)
  • National Council on Radiation Protection and Measurements Report NCRP No. 129, Recommended Screening Limits for Contaminated Surface Soil and Review of Factors Relevant to Site-Specific Studies, Washington, DC, 1999.
  • NUREG 1506,Measurement Methods for Radiological Surveys in Support of New Decommissioning Criteria
  • NUREG-1576- Multi-Agency Radiological Laboratory Protocols Manual (MARLAP) 14 MT2015-4008

DRAFT Field Sampling and Dose Assessment Plan August 31, 2015

  • WVDP-065, Manual for Radiological Assessment of Environmental Releases at the WVDP. Rev. 3, 8/2000
  • U.S. Nuclear Regulatory Commission, Standards for Protection against Radiation, 10 CFR Part 20, November 16, 2005.
12. Data Quality Objectives (DQO)

The first Data Quality Objective (DQO) relates to the sensitivity and accuracy of the analytical analyses conducted by the selected radiochemistry laboratory. The Minimum Detectable Concentrations for the specified analytes must be sufficient to distinguish activity in excess of background levels. This should be readily achievable.

  • Collect data of sufficient quantity and quality to establish background levels of COCs at or below concentrations identified in the 2014 RSL aerial survey and previous off-site investigations.
  • Collect data of sufficient resolution and quantity to perform dose assessments capable of identifying exposures to the Maximum Exposed Off-Site Individual, using credible survey unit scenarios.

The Second Data Quality Objective relates to the ability to ground-truth the location and elevated Cs-137 zones identified by the Aerial Survey using the 2 x 2 NaI detectors, the Micro Rem meter, and sample analysis. The ability to achieve this objective will, in part, be determined by the instrumentation characteristics, but also by the nature of the terrain, background levels encountered, and potential challenges posed by vegetation and physical obstructions.

13. Data Validation Strategy The project data validation strategy will be to conform to the requirements of MARLAP 2004.
a. Radioanalytical guidance document to be used for validation: Evaluation of Radiochemical Data Usability, April 1997 ES/ER/MS-5.
b. Level 2 Data Reporting - Radiological Analyses (most rigorous).
  • Chain-of-custody (COC) documentation
  • Sample ID and location code
  • Date of collection
  • Date of processing (if applicable)
  • Percent moisture (if applicable)
  • Amount of sample used in analysis
  • Date of analysis
  • Minimum detectable level (for analysis and matrix)
  • Analytical result and uncertainty term in proper units
  • Results for instrument backgrounds, method blanks, standards, matrix spikes, and duplicates analyzed as part of batch QC 15 MT2015-4008

DRAFT Field Sampling and Dose Assessment Plan August 31, 2015

  • Acceptance criteria for batch QC
  • Comments on any peculiarities concerning analysis of a sample
  • Documentation of calibration status of equipment and instruments used in analysis of samples (i.e., efficiencies, quench curves, high voltage determinations - as appropriate to the counting instrumentation)
  • Control chart or other performance verification documentation for daily standard counts and instrument backgrounds
  • Certification for National Institute of Standards and Technology (NIST)-

traceable counting standards and Standard Reference Manual (SRMs),

tracers and/or carriers, if applicable

  • Raw data (instrument print-outs and/or data sheets)
  • Calculations 16 MT2015-4008
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