ML19063A994
| ML19063A994 | |
| Person / Time | |
|---|---|
| Site: | 07007003 |
| Issue date: | 08/16/2018 |
| From: | Bailey E Oak Ridge Institute for Science & Education |
| To: | James Smith Division of Decommissioning, Uranium Recovery and Waste Programs |
| Smith J | |
| Shared Package | |
| ML19063A991 | List: |
| References | |
| 18-006, DCN 5326-SR-01-0 | |
| Download: ML19063A994 (64) | |
Text
P.O. Box 117 Oak Ridge, TN 37831
- https://orise.orau.gov August 16, 2018 James Smith, Health Physicist U.S. Nuclear Regulatory Commission Office of Nuclear Material and Safeguards Division of Decommissioning, Uranium Recovery, and Waste Programs Materials Decommissioning Branch TWFN Mail Stop: T-8F5 Rockville, MD 20852
SUBJECT:
DOE CONTRACT NO. DE-SC0014664 INDEPENDENT CONFIRMATORY SURVEY
SUMMARY
AND RESULTS FOR THE AMERICAN CENTRIFUGE LEAD CASCADE FACILITY IN PIKETON, OHIO RFTA NO.18-006; DCN 5326-SR-01-0
Dear Mr. Smith:
The Oak Ridge Institute for Science and Education (ORISE) is pleased to provide the enclosed report, which describes the procedures and results of the independent confirmatory survey that ORISE performed during the period of May 21-25, 2018 at the American Centrifuge Lead Cascade Facility in Piketon, Ohio. NRCs comments on the draft report have been incorporated into this report.
You may contact me at 865.576.6659 or Kaitlin Engel at 865.574.7008 if you have any questions or require additional information.
Sincerely, Erika N. Bailey Survey and Technical Projects Group Manager ORISE KME: lw electronic distribution:
T. Carter, NRC Y. Faraz, NRC M. Learn, NRC S. Roberts, ORISE M. Kunowski, NRC N. Altic, ORISE B. Lin, NRC D. Hagemeyer, ORISE K. Engel, ORISE File/5326
INDEPENDENT CONFIRMATORY SURVEY
SUMMARY
AND RESULTS FOR THE AMERICAN CENTRIFUGE LEAD CASCADE FACILITY IN PIKETON, OHIO K. M. Engel ORISE FINAL REPORT Prepared for the U.S. Nuclear Regulatory Commission AUGUST 2018 Further dissemination authorized to the NRC only; other requests shall be approved by the originating facility or higher NRC programmatic authority.
ORAU provides innovative scientific and technical solutions to advance research and education, protect public health and the environment and strengthen national security. Through specialized teams of experts, unique laboratory capabilities and access to a consortium of more than 100 major Ph.D.-granting institutions, ORAU works with federal, state, local and commercial customers to advance national priorities and serve the public interest. A 501(c) (3) nonprofit corporation and federal contractor, ORAU manages the Oak Ridge Institute for Science and Education (ORISE) for the U.S. Department of Energy (DOE). Learn more about ORAU at www.orau.org.
NOTICES The opinions expressed herein do not necessarily reflect the opinions of the sponsoring institutions of Oak Ridge Associated Universities.
This report was prepared as an account of work sponsored by the United States Government.
Neither the United States Government nor the U.S. Department of Energy, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe on privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, mark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement or recommendation, or favor by the U.S. Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the U.S. Government or any agency thereof.
American Centrifuge Lead Cascade Facility Confirmatory Survey Report 5326-SR-01-0 INDEPENDENT CONFIRMATORY SURVEY
SUMMARY
AND RESULTS FOR THE AMERICAN CENTRIFUGE LEAD CASCADE FACILITY IN PIKETON, OHIO FINAL REPORT Prepared by K. M. Engel ORISE AUGUST 2018 Prepared for the U.S. Nuclear Regulatory Commission This document was prepared for U.S. Nuclear Regulatory Commission by the Oak Ridge Institute for Science and Education (ORISE) through an interagency agreement with the U.S. Department of Energy (DOE) (NRC FIN No. F-1244). ORISE is managed by Oak Ridge Associated Universities under DOE contract number DE-SC0014664.
American Centrifuge Lead Cascade Facility Confirmatory Survey Report i
5326-SR-01-0 CONTENTS FIGURES.......................................................................................................................................................... iii TABLES............................................................................................................................................................. iii ACRONYMS.................................................................................................................................................... iv EXECUTIVE
SUMMARY
.............................................................................................................................. v
- 1. INTRODUCTION....................................................................................................................................... 1
- 2. SITE DESCRIPTION................................................................................................................................. 1
- 3. OBJECTIVE.................................................................................................................................................. 2 3.1 State the Problem.............................................................................................................................. 3 3.2 Identify the Decision........................................................................................................................ 3 3.3 Identify Inputs to the Decision....................................................................................................... 4 3.4 Define the Study Boundaries........................................................................................................... 5 3.5 Develop a Decision Rule.................................................................................................................. 5 3.6 Specify Limits on Decision Errors................................................................................................. 6 3.7 Optimize the Design for Obtaining Data...................................................................................... 6
- 4. APPLICABLE SITE GUIDELINES........................................................................................................ 6
- 5. PROCEDURES............................................................................................................................................ 7 5.1 Survey Unit Selection........................................................................................................................ 7 5.2 Surface Scans...................................................................................................................................... 8 5.3 Number and Location of Confirmatory Direct Measurements................................................. 8
- 6. SAMPLE ANALYSIS AND DATA INTERPRETATION............................................................... 10
- 7. FINDINGS AND RESULTS................................................................................................................... 13 7.1 X-3001 Train 2 and Train 3 North Utility Bays and Drains..................................................... 13 7.2 X-3001 Train 1 and Train 3 Mezzanines..................................................................................... 15 7.3 X-3001 Train 3................................................................................................................................. 17 7.4 X-3001 Train 3 Centrifuge Drains................................................................................................ 18 7.5 X-3001 Train 6................................................................................................................................. 18 7.6 X-7726 CTTF.................................................................................................................................. 19 7.7 X-7726 Second Floor Utility Room............................................................................................. 21 7.8 X-3012 Hot Shop............................................................................................................................ 22 7.9 X-7725 Loading/Storage Area...................................................................................................... 23
- 8.
SUMMARY
.................................................................................................................................................. 24
- 9. REFERENCES........................................................................................................................................... 26
American Centrifuge Lead Cascade Facility Confirmatory Survey Report ii 5326-SR-01-0 APPENDIX A: DATA TABLES AND FIGURES APPENDIX B: SURVEY AND ANALYTICAL PROCEDURES APPENDIX C: MAJOR INSTRUMENTATION
American Centrifuge Lead Cascade Facility Confirmatory Survey Report iii 5326-SR-01-0 FIGURES Figure 2.1. DOE Reservation and Footprint of the Lead Cascade............................................................ 2 Figure 6.1. Box Plot Descriptive Statistics................................................................................................... 11 Figure 6.2. Box Plots for Surface Activity Comparisons........................................................................... 12 Figure 7.1. Q-Q Plot for X-3001 Train 2 North Utility Bay..................................................................... 14 Figure 7.2. Q-Q Plot for X-3001 Train 3 North Utility Bay..................................................................... 14 Figure 7.3. Q-Q Plot for X-3001 Train 1 and Train 3 Mezzanines.......................................................... 16 Figure 7.4. Q-Q Plot for X-3001 Train 3..................................................................................................... 17 Figure 7.5. Q-Q Plot for X-3001 Train 6..................................................................................................... 19 Figure 7.6. Q-Q Plot for X-7726 CTTF....................................................................................................... 20 Figure 7.7. Q-Q Plot for X-7726 Second Floor Utility Room.................................................................. 21 Figure 7.8. Q-Q Plot for X-3012 Hot Shop................................................................................................ 22 Figure 7.9. Q-Q Plot for X-7725 Loading/Storage Area........................................................................... 23 TABLES Table 3.1. Lead Cascade Confirmatory Survey Decision Process.............................................................. 4 Table 4.1. Lead Cascade License Application Contamination Levelsa....................................................... 7 Table 5.1. Survey Units Evaluated................................................................................................................... 9 Table 7.1. Summary Data for X-3001 Train 2 and Train 3 North Utility Bays and Drains................. 15 Table 7.2. Summary Data for X-3001 Train 1 and Train 3 Mezzanine................................................... 16 Table 7.3. Summary Data for X-3001 Train 3............................................................................................. 18 Table 7.4. Summary Data for X-3001 Train 3 Centrifuge Drains............................................................ 18 Table 7.5. Summary Data for X-3001 Train 6............................................................................................. 19 Table 7.6. Summary Data for X-7726 CTTF............................................................................................... 20 Table 7.7. Summary Data for X-7726 Second Floor Utility Room.......................................................... 22 Table 7.8. Summary Data for X-3012 Hot Shop........................................................................................ 23 Table 7.9. Summary Data for X-7725 Loading/Storage Area.................................................................. 24
American Centrifuge Lead Cascade Facility Confirmatory Survey Report iv 5326-SR-01-0 ACRONYMS AA alternative action ACO American Centrifuge Operating, LLC ACP American Centrifuge Plant ALARA as low as reasonably achievable cpm counts per minute CTTF Centrifuge Training and Test Facility DCGL derived concentration guideline levels dpm/100 cm2 disintegration per minute per 100 square centimeters DOE U.S. Department of Energy DQOs data quality objectives DSs decision statements FSS final status survey GCEP Gas Centrifuge Enrichment Plant GM Geiger-Muller Lead Cascade The American Centrifuge Lead Cascade Facility MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual MDC minimum detectable concentration NIST National Institute of Standards and Technology NRC U.S. Nuclear Regulatory Commission ORISE Oak Ridge Institute for Science and Education PSQs principal study questions QQ quantile-quantile ROC radionuclide of concern SU survey unit VSP Visual Sample Plan
American Centrifuge Lead Cascade Facility Confirmatory Survey Report v
5326-SR-01-0 INDEPENDENT CONFIRMATORY SURVEY
SUMMARY
AND RESULTS FOR THE AMERICAN CENTRIFUGE LEAD CASCADE FACILITY IN PIKETON, OHIO EXECUTIVE
SUMMARY
The U.S. Nuclear Regulatory Commission requested that the Oak Ridge Institute for Science and Education (ORISE) perform an independent confirmatory survey at the American Centrifuge Lead Cascade Facility in Piketon, Ohio. In March 2016, American Centrifuge Operating, LLC notified the U.S. Nuclear Regulatory Commission of Centrus Energy Corporations decision to cease operations at the Lead Cascade and to terminate the Lead Cascades Materials license (SNM-7003).
ORISE performed independent assessment activities during the period of May 21-25, 2018.
Confirmatory survey activities included alpha-plus-beta radiation floor scans, beta radiation drain scans, alpha radiation scans and direct measurements, and smear sampling, as applicable, in the X-3001 Train 2 North Utility Bay, X-3001 Train 3 North Utility Bay, X-3001 Trains 2 and 3 North Utility Bay Drains, X-3001 Train 1 Mezzanine, X-3001 Train 3 Mezzanine, X-3001 Train 3, X-3001 Train 3 Centrifuge Drains, X-3001 Train 6, X-7726 Centrifuge Training and Testing Facility, X-7726 Second Floor Utility Room, X-3012 Hot Shop, and X-7725 Loading/Storage Area. ORISEs survey results, combined with laboratory analytical results from the smear samples, did not identify anomalous results or other conditions that preclude the FSS data from demonstrating compliance with the release criteria.
American Centrifuge Lead Cascade Facility Confirmatory Survey Report 1
5326-SR-01-0 INDEPENDENT CONFIRMATORY SURVEY
SUMMARY
AND RESULTS FOR THE AMERICAN CENTRIFUGE LEAD CASCADE FACILITY IN PIKETON, OHIO
- 1. INTRODUCTION The American Centrifuge Lead Cascade Facility (Lead Cascade) was a test loop of the American Centrifuge Plant (ACP) located in Piketon, Ohio. The Lead Cascade demonstrated the effectiveness of the centrifuge design and equipment by processing uranium hexafluoride (UF6) gas in a closed loop. After the demonstration was completed, the facility made a financial decision to cease uranium enrichment operations in February 2016, followed by removal of uranium gas from the centrifuges and process piping, dismantling of process equipment, and other actions needed to ultimately decommission the facility.
In March 2016, American Centrifuge Operating, LLC (ACO) notified the U.S. Nuclear Regulatory Commission (NRC) of Centrus Energy Corporations decision to cease operations at the Lead Cascade and to terminate the Lead Cascades Materials license (SNM-7003). In May 2016, ACO submitted a proposed amendment to the license to downgrade licensed activities at the Lead Cascade to limited operations and to remove the regulatory permission to enrich uranium. NRC issued an approval to the license amendment in December 2016 (NRC 2017).
The NRC requested that the Oak Ridge Institute for Science and Education (ORISE) perform confirmatory surveys in the X-3001 Train 2 North Utility Bay, X-3001 Train 3 North Utility Bay, X-3001 Trains 2 and 3 North Utility Bay Drains, X-3001 Train 1 Mezzanine, X-3001 Train 3 Mezzanine, X-3001 Train 3, X-3001 Train 3 Centrifuge Drains, X-3001 Train 6, X-7726 Centrifuge Training and Testing Facility, X-7726 Second Floor Utility Room, X-3012 Hot Shop, and X-7725 Loading/Storage Area. ORISE performed the confirmatory surveys on May 21-25, 2018.
- 2. SITE DESCRIPTION The footprint of the Lead Cascade is located within the U.S. Department of Energys (DOEs) 1,528-hectare (3,777-acre) federal reservation in a rural area of Pike County, Ohio, approximately 32 kilometers (20 miles) north of Portsmouth, Ohio. Figure 2.1 depicts the portion of the reservation associated with the American Centrifuge Plant. The Lead Cascade facilities were leased from the DOE and are being prepared for return to DOE to meet unrestricted use per lease requirements (ACO 2018a).
American Centrifuge Lead Cascade Facility Confirmatory Survey Report 2
5326-SR-01-0 Figure 2.1. DOE Reservation and Footprint of the Lead Cascade (circled in red)
(ACO 2018a)
- 3. OBJECTIVE The data quality objectives (DQOs) described herein are consistent with the Guidance on Systematic Planning Using the Data Quality Objectives Process (EPA 2006) and provided a formalized method for planning radiation surveys, improving survey efficiency and effectiveness, and ensuring that the type, quality, and quantity of data collected were adequate for the intended decision applications.
The seven steps in the DQO process are as follows:
- 1. State the problem
- 2. Identify the decision/objective
- 3. Identify inputs to the decision/objective
- 4. Define the study boundaries
- 5. Develop a decision rule
American Centrifuge Lead Cascade Facility Confirmatory Survey Report 3
5326-SR-01-0
- 6. Specify limits on decision errors
- 7. Optimize the design for obtaining data 3.1 STATE THE PROBLEM The first step in the DQO process defined the problem that necessitated the study, identified the planning team, and examined the project budget and schedule. The Gas Centrifuge Enrichment Plant (GCEP) lease agreement between DOE and the United States Enrichment Corporation stated in part that prior to returning GCEP Leased Facilities, residual radiological contamination levels shall comply with the NRCs radiological criteria for unrestricted use, as specified in Title 10 of the Code of Federal Regulators 20.1402 (ACO 2018a), which states:
A site will be considered acceptable for unrestricted use if the residual radioactivity that is distinguishable from background radiation results in a total effective dose equivalent to an average member of the critical group that does not exceed 25 mrem per year, including that from groundwater sources of drinking water, and the residual radioactivity has been reduced to levels that are as low as reasonably achievable (ALARA).
NRC requested that ORISE perform confirmatory surveys of the Lead Cascade to provide independent documentation and field reviews and generate independent radiological data to assist the NRC in evaluating the adequacy and accuracy of ACOs final status survey (FSS) results.
Therefore, the problem statement was as follows:
Independent confirmatory surveys are necessary to assist the NRC in their assessment and determination of the adequacy of the FSS design, implementation, and results for demonstrating compliance with the release criteria.
3.2 IDENTIFY THE DECISION The second step in the DQO process identified the principal study questions (PSQs) and alternative actions (AAs); developed decision statements; and organized multiple decisions, as appropriate. This was done by specifying AAs that could result from a yes response to the PSQs and combining the PSQs and AAs into decision statements (DSs). PSQs, AAs, and combined DSs are organized based on the survey unit (SU) type (i.e., the associated FSS methodology) and presented in Table 3.1.
American Centrifuge Lead Cascade Facility Confirmatory Survey Report 4
5326-SR-01-0 Table 3.1. Lead Cascade Confirmatory Survey Decision Process Principal Study Question Alternative Actions PSQ: Do confirmatory survey results agree with the final radiological survey data for the Lead Cascade?
Yes:
Compile confirmatory data and report results to the NRC for their decision making. Provide independent interpretation that confirmatory field surveys did not identify anomalous areas of residual radioactivity, quantitative field and laboratory data satisfied the NRC-approved decommissioning criteria, and/or that statistical sample population examination/assessment conditions were met.
No:
Compile confirmatory data and report results to the NRC for their decision making. Provide independent interpretation of confirmatory survey results identifying any anomalous field or laboratory data and/or when statistical sample population examination/assessment conditions were not satisfied for the NRCs determination of the adequacy of the FSS data.
Decision Statement Confirmatory survey results did/did not identify anomalous results or other conditions that preclude the FSS data from demonstrating compliance with the release criteria.
3.3 IDENTIFY INPUTS TO THE DECISION The third step in the DQO process identified both the information needed and the sources of this information; determined the basis for action levels; and identified sampling and analytical methods to meet data requirements. For this effort, information inputs included the following:
- Applicable instrumentation and survey and sampling procedures, method procedures, and data management procedures (ORAU 2016a)
- The ORAU Environmental Services and Radiation Training Quality Program Manual (ORAU 2016b)
- Applicable laboratory equipment and procedures (ORAU 2017)
- Final status survey report and associated data (ACO 2018a)
- ORISE confirmatory survey results including: surface radiation scans, direct surface activity measurements, and removable gross alpha/beta activity
American Centrifuge Lead Cascade Facility Confirmatory Survey Report 5
5326-SR-01-0 3.4 DEFINE THE STUDY BOUNDARIES The fourth step in the DQO process defined target populations and spatial boundaries; determined the timeframe for collecting data and making decisions; addressed practical constraints; and determined the smallest subpopulations, area, volume, and time for which separate decisions must be made.
Figure 2.1 presents the area of the site associated with the Lead Cascade. The FSS report presented data from five buildings including: X-3001, X-3012, X-7725, X-7726, and X-7727H. At NRCs direction based on the sites prior operations, confirmatory survey activities were performed in buildings X-3001, X-3012, X-7725, and X-7726 during the five days onsite.
3.5 DEVELOP A DECISION RULE The fifth step in the DQO process specified appropriate parameters (e.g., mean, median); confirmed action levels were above detection limits; and developed an ifthendecision rule statement. For this survey effort, the one parameter of interest was the mean uranium surface activity in an individual SU. For assessing the SU means, the project-specific plan included comparing the confirmatory mean surface activity levels for each SU to the mean surface activity reported in the FSS reports, if available, via a two-sample hypothesis test. A preliminary data assessment was performed that consisted of box plots of the SUs. Based on the preliminary assessment and because hypothesis tests of data populations with most results near or below the minimum detectable concentrations (MDCs) can be inconclusive and generally lack sufficient power to detect what would be a small and therefore inconsequential difference, further hypothesis testing was unnecessary. See Section 6 for further details.
Individual sample results were also evaluated against a single pass/fail criterion. The criterion used for individual data points was three times the total surface activity limitspecified in the footnote of Table 4.1, which is 15,000 disintegrations per minute per one hundred square centimeters (dpm/100 cm2) total activity.
American Centrifuge Lead Cascade Facility Confirmatory Survey Report 6
5326-SR-01-0 The modified decision rule was stated as:
If surface activity, averages, maximums, and removable are less than the release limits, then conclude that confirmatory survey data agrees with the FSS data. Otherwise, perform further evaluation(s) and provide technical comments and recommendations to NRC.
3.6 SPECIFY LIMITS ON DECISION ERRORS The sixth step in the DQO process specified the decision makers limits on decision errors, which were then used to establish performance goals for the survey. One order of control was to optimize the confirmatory field measurement detection sensitivities and ensure that laboratory analytical MDCs are sufficient for decision making. The nominal analytical MDCs were less than 10 percent of the contamination limits. Field instrumentation MDCs were optimized by following survey procedures.
3.7 OPTIMIZE THE DESIGN FOR OBTAINING DATA The seventh step in the DQO process was used to review the DQO outputs; develop data collection design alternatives; formulate mathematical expressions for each design; select the sample size to satisfy DQOs; decide on the most resource-effective design of agreed alternatives; and document requisite details. Survey design and laboratory analyses were optimized by implementing the procedures presented in Sections 5 and 6, respectively.
- 4. APPLICABLE SITE GUIDELINES The primary radionuclides of concern (ROCs) are uranium isotopes U-234, U-235, and U-238 from the UF6 feed. In order to demonstrate compliance with the 25 mrem/yr release criterion, a site-specific derived concentration guideline level (DCGLW) was developed and presented in the sites Decommissioning Plan, DP-2605-0001. Using RESRAD-Build, the DCGLW was determined to be 39,200 dpm/100 cm2 total uranium activity. However, ACO noted in their FSS report that the Lead Cascade license application limits are more restrictive and limit total contamination levels for unrestricted release and ALARA purposes. The more restrictive surface contamination limits are presented in the licensees decommissioning plan and are reproduced in Table 4.1 (ACO 2018b).
This lower value will be applied by ACO to demonstrate compliance with NRCs dose criterion and also for ALARA purposes.
American Centrifuge Lead Cascade Facility Confirmatory Survey Report 7
5326-SR-01-0 Additionally, the FSS report noted that the contaminant (uranyl fluoride) sample analysis indicated that other radionuclides would be insignificant as nearly 100 percent of the projected dose is due to the uranium isotopes. Therefore, the final status surveys acceptance was based on the residual alpha activity (although some beta data were collected and presented in the FSS report) (ACO 2018a).
Table 4.1. Lead Cascade License Application Contamination Levelsa Radionuclide Removable (dpm/100 cm2)
Total (dpm/100 cm2)b U-natural, U-235, U-238, and associated decay products.
Transuranics 2 percent by alpha activity, Tc-99 and beta-gamma emitters.
1,000 5,000 a Table source: ACO 2018b b The levels may be averaged over one square meter provided the maximum surface activity in any area of 100 cm2 is less than three times the total value. For the purposes of averaging, any square meter of the surface is considered to be above the total limit if: 1) the average of measurements from a representative number of n sections are above the total limits; or 2) it is determined that the sum of the activity of all isolated spots or particles in any 100 cm2 exceeds three times the total limit.
- 5. PROCEDURES The confirmatory survey activities, conducted during the period of May 21-25, 2018, were in accordance with the project-specific confirmatory survey plan, the ORAU Radiological and Environmental Survey Procedure Manual, and the ORAU Environmental Services and Radiation Training Quality Program Manual (ORISE 2018, ORAU 2016a and 2016b). Appendices B and C provide additional information regarding survey instrumentation and related processes discussed within this section.
5.1 SURVEY UNIT SELECTION ORISE imported ACOs FSS summary data into a spreadsheet and ranked the sites SUs by highest alpha fraction values; the average and maximum alpha value(s) observed for an SU were divided by the total surface activity limit 5,000 dpm/100cm2. The four SUs with the highest alpha fraction, two of which also had the highest beta fractions, were: X-7726 Second Floor Utility Room, X-3001 Train 3-1, X-3001 Train 1 Mezzanine Floor, and X-3001 Train 3 Utility Bay 3 Discretionary. Additional SUs were selected at NRCs discretion based on facility knowledge and the potential for material accumulation, material pathways, and/or other indications of residual contamination. Table 5.1 lists the SUs selected for confirmatory surveys.
American Centrifuge Lead Cascade Facility Confirmatory Survey Report 8
5326-SR-01-0 5.2 SURFACE SCANS SUs that were specifically selected for confirmatory survey based on the sites results received high-density scan coverage (up to 100 percent), while other SUs received low-to medium-density scan coverage (10-50 percent).
ORISE performed alpha-plus-beta radiation scans of the accessible floor space in the confirmatory SUs. Scans were performed using Ludlum Model 43-37 gas-flow proportional floor monitors coupled to Ludlum Model 2221 ratemeter scalers. Ratemeter scalers were coupled to hand-held data loggers for electronically recording the count-rate data.
ORISE performed alpha radiation scans of X-3001 Train 3,X-3001 Train 6, and X-7226 Centrifuge Training and Test Facility (CTTF) Centrifuge Drains that were in use during operations, including the water collection area of each drain. Alpha radiation scans were also performed on the X-7226 CTTF floor mounts and machine stands, X-7725 floor mounts, and X-3001 Trains 2 and 3 North Utility Bay machine mount pads. Scans were performed using Ludlum Model 43-68 gas-flow proportional detectors coupled to Ludlum Model 2221 ratemeter scalers.
ORISE performed beta radiation scans of the accessible portions of the drains in the North Utility Bays using Ludlum Model 44-9 Geiger-Mueller (GM) detectors coupled to Ludlum Model 2221 ratemeter scalers with audible indicators. The use of GM detectors in the North Utility Bay drains was necessary due to the size of the drains. The centrifuge drain piping in Train 3 was too small in diameter to survey the interior surfaces with the GM detector.
All scan surveys were qualitative, and performed to detect elevated direct radiation counts, indicative of residual contamination that would require quantitative investigations using other hand-held instruments. Scan MDCs were not specifically calculated for the GM or floor monitor detectors; see Appendix B for MDC calculations of the hand-held gas proportional detectors.
The scan densities performed within each SU are provided in Table 5.1.
5.3 NUMBER AND LOCATION OF CONFIRMATORY DIRECT MEASUREMENTS The confirmatory measurement locations to determine the average concentration for a SU were randomly selected. The number of measurements was determined using Visual Sample Plan (VSP),
American Centrifuge Lead Cascade Facility Confirmatory Survey Report 9
5326-SR-01-0 version 7.9. The FSS data were used as VSP inputs to generate the confirmatory surface activity measurement sample population sizewith the exception of the CTTF. CTTF FSS data were not readily available; therefore, the parameters required for sample size determination were estimated.
The measurement data were used to independently estimate the mean surface activity for each confirmatory SU and then compare the means with FSS results. The comparisons were performed as an unbiased evaluation to assess whether the confirmatory survey surface activity levels were significantly greater than or less than or equal to the FSS results at the 95% confidence level.
Additional judgmental measurements were collected from locations where surface scans identified elevated direct radiation levels that were potentially in excess of the release limits.
Table 5.1. Survey Units Evaluated Survey Unit Type of Direct Measurements
/ Smears a Number of Random Measurements Number of Judgmental Measurements Scans X-3001 Train 2 North Utility Bay Random/
Judgmental 45 4
High-density scans of floor X-3001 Train 3 North Utility Bay Random/
Judgmental 37 6
High-density scans of floor X-3001 Trains 2 and 3 North Utility Bay Drains Judgmental NA 18 Low-density scan of drains X-3001 Train 1 Mezzanine NA NA NA Medium-density scans of floor X-3001 Train 3 Mezzanine NA NA NA Medium-density scans of floor X-3001 Train 3 Random/
Judgmental 22 2
High-density scans of floor and gamma spec area X-3001 Train 3 Centrifuge Drains Random/
Judgmental 55 8
High-density scans of drains including water collection areas X-3001 Train 6 Judgmental 0
4 Medium-density scans of floor X-7226 CTTF Random/
Judgmental 20 10 High-density scans of floor and centrifuge stand X-7726 2nd Floor Utility Room Judgmental 0
6 High-density scans of floor X-3012 Hot Shop NA NA NA High-density scans of floor; part of floor covered by plastic tarp (not scanned)
American Centrifuge Lead Cascade Facility Confirmatory Survey Report 10 5326-SR-01-0 Table 5.1. Survey Units Evaluated Survey Unit Type of Direct Measurements
/ Smears a Number of Random Measurements Number of Judgmental Measurements Scans X-7725 Loading/Storage Area NA NA NA High-density scans near rollup door, medium-density scans in rest of area a Judgmental direct measurements were performed based on scan results.
NA= Not applicable Direct surface activity measurements were made using Ludlum Model 2221 ratemeter scalers coupled to Ludlum Model 43-68 gas proportional detectors with a 0.8 mg/cm2-thick Mylar window for alpha-only direct measurements. In narrow spaces, beta scans were also conducted using a hand-held Geiger-Mueller (GM) detector with a 1.7 mg/cm2 window. A weighted efficiency was established assuming natural isotopic abundances to quantify total uranium surface activity.
Weighted efficiency determinations were in accordance with NUREG-1507 (NRC 1998), the Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) (NRC 2000), ORAU Survey Protocol C.21 (Scan MDC Determination for Surface Activity) (ORAU 2016a).
Dry smear samples, for determining removable gross alpha/beta activity levels, were collected from each direct measurement location. Smears covered 100 cm2 and were collected post direct measurement.
Material-specific background measurements were collected in building X-3002, within the sites designated non-impacted background area that was, to the extent possible, of similar construction to the target materials. These background measurements were used to correct gross measurement counts for the conversion to surface activity levels in units of dpm/100 cm2.
- 6. SAMPLE ANALYSIS AND DATA INTERPRETATION Samples and data collected on site were returned to the ORISE facility for analysis and interpretation. Sample custody was transferred to the Radiological and Environmental Analytical Laboratory in Oak Ridge, Tennessee. Sample analyses were performed in accordance with the ORAU Radiological and Environmental Analytical Laboratory Procedures Manual (ORAU 2017). Smears were analyzed for removable gross alpha/beta activity using a low-background gas proportional
American Centrifuge Lead Cascade Facility Confirmatory Survey Report 11 5326-SR-01-0 counter. Smear data and direct measurements for surface activity were converted to units of dpm/100 cm2. Additional laboratory instrumentation and processes are provided in Appendices B and C.
FSS data for three of the confirmatory SUs were available for mean uranium surface activity level comparison as follows: 1) X-3001 Train 2 North Utility Bay; 2) X-3001 Train 3 North Utility Bay; and 3) X-3001 Train 3-1. A preliminary data assessment was performed that consisted of box plots of these three SUs. Figure 6.1 shows descriptive statistic information that box plots provide.
Figure 6.1. Box Plot Descriptive Statistics The plots shown in Figure 6.2 illustrate that all of the ORISE population data parameters are less than the FSS data, including the maximum observed values, meaning the FSS data are conservatively biased high. Additionally, the FSS population statistics include a systematic bias as only positive data are reported (i.e., negative results were reported as 0 dpm/100 cm2). A background population would be expected to contain an approximately equal number of positive and negative results with a mean of zero. This bias can be seen in the box plots for the ACO FSS results where all minimum values are zero. Additionally, the random location surface activity levels for these SUs are well below the calculated MDC (see Appendix B for ORISE MDC calculations). Based on this preliminary assessment and because hypothesis tests of data populations with most results near or below the MDCs can be inconclusive and generally lack sufficient power to detect what would be a small and therefore inconsequential difference, further hypothesis testing is unnecessary.
American Centrifuge Lead Cascade Facility Confirmatory Survey Report 12 5326-SR-01-0 Figure 6.2. Box Plots for Surface Activity Comparisons Individual sample results were also evaluated against the contamination levels listed in Table 4.1. As specified in the footnote, the criterion used for individual data points was three times the total surface activity limit, which is 15,000 dpm/100 cm2.
Scan data sets were graphed in a quantile-quantile (Q-Q) plot for assessment. The Q-Q plot is a graphical tool for assessing the distribution of a data set. The Y-axis represents gross alpha-plus-beta surface activity in units of counts per minute (cpm). The X-axis represents the data quantiles about the median value. Values less than the median are represented in the negative quantiles, and the values greater than the median are represented in the positive quantiles. A normal distribution that is not skewed by outliersi.e., a background populationwill appear as a straight line, with the slope of the line subject to the degree of variability among the data population. More than one distribution, such as background plus contamination or other outliers, will appear as a step function.
American Centrifuge Lead Cascade Facility Confirmatory Survey Report 13 5326-SR-01-0
- 7. FINDINGS AND RESULTS The results of the confirmatory survey are discussed in the following subsections. Appendix A provides the tabulated survey data for all SUs investigated.
7.1 X-3001 TRAIN 2 AND TRAIN 3 NORTH UTILITY BAYS AND DRAINS Approximately 100 percent of the accessible floor area was scanned in X-3001 Trains 2 and 3 North Utility Bays. Areas previously remediated by ACO prior to the confirmatory survey were located within both North Utility Bays; these two areas still exhibited elevated radiation levels above background and were therefore selected for judgmental direct measurements. The Q-Q plot shown in Figure 7.1 for X-3001 Train 2 North Utility Bay alpha-plus-beta scan data appears normal with the data indicative of background levels. No direct measurements exceeded the contamination level and all removable activity was less than the MDC of 11 dpm/100 cm2 for alpha and 14 dpm/100 cm2 for beta. Figure 7.2 provides the Q-Q plot for X-3001 Train 3 North Utility Bay data set shows a step function indicating more than one data population due to contamination. No direct measurements exceeded the contamination level and all removable activity was less than the respective MDCs. All removable activity from the drains was less than the respective MDCs. Table 7.1 provides a summary of the survey data for these areas.
American Centrifuge Lead Cascade Facility Confirmatory Survey Report 14 5326-SR-01-0 Figure 7.1. Q-Q Plot for X-3001 Train 2 North Utility Bay Figure 7.2. Q-Q Plot for X-3001 Train 3 North Utility Bay
American Centrifuge Lead Cascade Facility Confirmatory Survey Report 15 5326-SR-01-0 Table 7.1. Summary Data for X-3001 Train 2 and Train 3 North Utility Bays and Drains Survey Unit Alpha-plus-Beta Scan Range (cpm)
ORISE Mean Alpha Activity ACO Mean Alpha Activity ORISE Maximum Total Alpha Activity Maximum Removable Activity Alpha Beta dpm/100 cm2 dpm/100 cm2 X-3001 Train 2 North Utility Bay 740 to 2,072 4.9 26.3 760 4.21 5.20 X-3001 Train 3 North Utility Bay 758 to 2,333 9.9 30.9 2,200 4.21 7.65 X-3001 Trains 2 and 3 North Utility Bay Drains 19 to 38 NA NA NA 1.92 6.42 NA= Not applicable 7.2 X-3001 TRAIN 1 AND TRAIN 3 MEZZANINES Approximately 50 percent of the accessible floor area was scanned in Trains 1 and 3 upper level mezzanines in building X-3001. No areas of elevated radiation levels distinguishable from background were identified; therefore, no direct judgmental measurements or smear samples were collected from these areas. The Q-Q plot for X-3001 Train 1 and 3 Mezzanine data sets appears normal with no outliers. See Figure 7.3. Table 7.2 provides a summary of the survey data for these areas.
American Centrifuge Lead Cascade Facility Confirmatory Survey Report 16 5326-SR-01-0 Figure 7.3. Q-Q Plot for X-3001 Train 1 and Train 3 Mezzanines Table 7.2. Summary Data for X-3001 Train 1 and Train 3 Mezzanine Survey Unit Alpha-plus-Beta Scan Range (cpm)
ORISE Mean Alpha Activity ACO Mean Alpha Activity ORISE Maximum Total Alpha Activity Maximum Removable Activity Alpha Beta dpm/100 cm2 dpm/100 cm2 X-3001 Train 1 Mezzanine 871 to 1,879 NA NA NA NA NA X-3001 Train 3 Mezzanine 859 to 1,861 NA NA NA NA NA NA= Not applicable
American Centrifuge Lead Cascade Facility Confirmatory Survey Report 17 5326-SR-01-0 7.3 X-3001 TRAIN 3 Approximately 100 percent of the floors in all four SUs in this area were scanned, including the wings containing the gamma spectroscopy area. One area in SU1 exhibited elevated alpha-plus-beta radiation levels (approximately 700 cpm) above background and was selected for two judgmental direct measurements and smear sampling. This area was the same area ACO had identified as containing elevated alpha radiation levels (though below the contamination level). The Q-Q plot appears normal for all SUs. See Figure 7.4. No direct measurements exceeded the contamination level and all removable activity levels were less than the respective MDCs. Table 7.3 provides a summary of the survey data for this area.
Figure 7.4. Q-Q Plot for X-3001 Train 3
American Centrifuge Lead Cascade Facility Confirmatory Survey Report 18 5326-SR-01-0 Table 7.3. Summary Data for X-3001 Train 3 Survey Unit Alpha-plus-Beta Scan Range (cpm)
ORISE Mean Alpha Activity ACO Mean Alpha Activity ORISE Maximum Total Alpha Activity Maximum Removable Activity Alpha Beta dpm/100 cm2 dpm/100 cm2 X-3001 Train 3 8 to 2,178 6.0 NA 720 1.92 5.20 NA= Not applicable 7.4 X-3001 TRAIN 3 CENTRIFUGE DRAINS The Centrifuge Drains investigated were from the drains located along the western-most edge of Train 3, where centrifuges were in operation. Approximately 100 percent of the 55 Centrifuge Drains were scanned. During the survey of the randomly selected Centrifuge Drains, elevated radiation levels were noted in the water collection area of the drains. Therefore, all water collection areas of the western-most 180 Centrifuge Drains were scanned. No direct measurements exceeded the Table 4.1 contamination levels and all removable activity was less than the respective MDCs.
Table 7.4 provides a summary of the survey data for these areas.
Table 7.4. Summary Data for X-3001 Train 3 Centrifuge Drains Survey Unit Alpha-plus-Beta Scan Range (cpm)
ORISE Mean Alpha Activity ACO Mean Alpha Activity ORISE Maximum Total Alpha Activity Maximum Removable Activity Alpha Beta dpm/100 cm2 dpm/100 cm2 X-3001 Train 3 Centrifuge Drains 0 to 182
-15.0 NA 2,000 8.79 7.65 NA= Not applicable 7.5 X-3001 TRAIN 6 Approximately 50 percent of the floor area was scanned in Train 6 in building X-3001. Scans were conducted in all four of ACOs SUs for Train 6. One area exhibited elevated radiation levels above background. This area was near and in a water collection area of a Centrifuge Drain; therefore, all water collection areas of the previously in use Centrifuge Drains were scanned. The Q-Q plot for X-3001 Train 6 data set shows a step function indicating more than one data population due to contamination. See Figure 7.5. No direct measurements exceeded the Table 4.1 contamination level,
American Centrifuge Lead Cascade Facility Confirmatory Survey Report 19 5326-SR-01-0 and all removable activity levels were less than the respective MDCs. Table 7.5 provides a summary of the survey data for this area.
Figure 7.5. Q-Q Plot for X-3001 Train 6 Table 7.5. Summary Data for X-3001 Train 6 Survey Unit Alpha-plus-Beta Scan Range (cpm)
ORISE Mean Alpha Activity ACO Mean Alpha Activity ORISE Maximum Total Alpha Activity Maximum Removable Activity Alpha Beta dpm/100 cm2 dpm/100 cm2 X-3001 Train 6 862 to 2,414 NA NA 2,100 1.92 5.20 NA= Not applicable 7.6 X-7726 CTTF Approximately 100 percent of the floor area was scanned in CTTF in building X-7726. Scans were conducted in the Material Storage Area, the Mezzanine, Assembly Stand, the Control Room, and all corridors. Ten areas exhibited elevated radiation levels above background. The Q-Q plot for X-7726 CTTF data set shows a step function indicating more than one data population due to
American Centrifuge Lead Cascade Facility Confirmatory Survey Report 20 5326-SR-01-0 contamination (see Figure 7.6). No direct measurements exceeded the Table 4.1 contamination level and all removable activity was less than the respective MDCs. Table 7.6 provides a summary of the survey data for this area.
Figure 7.6. Q-Q Plot for X-7726 CTTF Table 7.6. Summary Data for X-7726 CTTF Survey Unit Alpha-plus-Beta Scan Range (cpm)
ORISE Mean Alpha Activity ACO Mean Alpha Activity ORISE Maximum Total Alpha Activity Maximum Removable Activity Alpha Beta dpm/100 cm2 dpm/100 cm2 X-7726 CTTF 0 to 3,798 9.1 NA 740 1.92 6.42 NA= Not applicable
American Centrifuge Lead Cascade Facility Confirmatory Survey Report 21 5326-SR-01-0 7.7 X-7726 SECOND FLOOR UTILITY ROOM Approximately 100 percent of the floor area was scanned in the X-7726 Second Floor Utility Room.
Six areas exhibited elevated radiation levels above background. These areas were known to ACO and are believed to be due to operations prior to the Lead Cascade operations. The Q-Q plot for X-7726 Second Floor Utility Room data set shows a step function indicating more than one data population due to contamination (see Figure 7.7). No direct measurement exceeded the contamination level, and all removable activity was less than the respective MDCs. Table 7.7 provides a summary of the survey data for this area.
Figure 7.7. Q-Q Plot for X-7726 Second Floor Utility Room
American Centrifuge Lead Cascade Facility Confirmatory Survey Report 22 5326-SR-01-0 Table 7.7. Summary Data for X-7726 Second Floor Utility Room Survey Unit Alpha-plus-Beta Scan Range (cpm)
ORISE Mean Alpha Activity ACO Mean Alpha Activity ORISE Maximum Total Alpha Activity Maximum Removable Activity Alpha Beta dpm/100 cm2 dpm/100 cm2 X-7726 2nd Floor Utility Room 741 to 3,031 NA NA 3,400
-0.37 3.97 NA= Not applicable 7.8 X-3012 HOT SHOP Approximately 100 percent of the accessible floor area was scanned in the X-3012 Hot Shop; however, a portion of the area was covered with a plastic tarp that was not moved for surveys. No areas of elevated radiation levels above background were identified; therefore, no direct judgmental measurements or smear samples were collected from these areas. The Q-Q plot for X-3012 Hot Shop data set appears normal, with the exception of a possible background distribution outlier. See Figure 7.8. Table 7.8 provides a summary of the survey data for this area.
Figure 7.8. Q-Q Plot for X-3012 Hot Shop
American Centrifuge Lead Cascade Facility Confirmatory Survey Report 23 5326-SR-01-0 Table 7.8. Summary Data for X-3012 Hot Shop Survey Unit Alpha-plus-Beta Scan Range (cpm)
ORISE Mean Alpha Activity ACO Mean Alpha Activity ORISE Maximum Total Alpha Activity Maximum Removable Activity Alpha Beta dpm/100 cm2 dpm/100 cm2 X-3012 Hot Shop 828 to 1,949 NA NA NA NA NA NA= Not applicable 7.9 X-7725 LOADING/STORAGE AREA Approximately 100 percent of the accessible floor area was scanned near the rollup door and static centrifuge stands and approximately 50 percent of the accessible floor space was scanned in the rest of the X-7725 Loading/Storage Area. No elevated radiation levels above background were identified; therefore, no direct judgmental measurements or smear samples were collected from these areas. The Q-Q plot data set for X-7726 Loading/Storage Area appears normal (see Figure 7.9). Table 7.9 provides a summary of the survey data for this area.
Figure 7.9. Q-Q Plot for X-7725 Loading/Storage Area
American Centrifuge Lead Cascade Facility Confirmatory Survey Report 24 5326-SR-01-0 Table 7.9. Summary Data for X-7725 Loading/Storage Area Survey Unit Alpha-plus-Beta Scan Range (cpm)
ORISE Mean Alpha Activity ACO Mean Alpha Activity ORISE Maximum Total Alpha Activity Maximum Removable Activity Alpha Beta dpm/100 cm2 dpm/100 cm2 X-7725 Loading/Storage Area 528 to 1,782 NA NA NA NA NA NA= Not applicable
- 8.
SUMMARY
At the NRCs request, ORISE conducted confirmatory survey activities in the X-3001 Train 2 North Utility Bay, X-3001 Train 3 North Utility Bay, X-3001 Trains 2 and 3 North Utility Bay Drains, X-3001 Train 1 Mezzanine, X-3001 Train 3 Mezzanine, X-3001 Train 3, X-3001 Train 3 Centrifuge Drains, X-3001 Train 6, X-7726 Centrifuge Training and Testing Facility, X-7726 Second Floor Utility Room, X-3012 Hot Shop, and X-7725 Loading/Storage Area at the American Centrifuge Lead Cascade Facility during the period of May 21-25, 2018. The survey activities included alpha-plus-beta radiation floor scans, beta radiation drain scans, alpha radiation scans, alpha direct measurements, and smear sampling, as applicable.
The scans of X-3001 Train 2 North Utility Bay Drains, X-3001 Train 3 North Utility Bay Drains, X-3001 Train 1 Mezzanine, X-3001 Train 3 Mezzanine, X-3012 Hot Shop, and X-7725 Loading/Storage Area were comparable to background. The alpha-plus-beta floor scans identified multiple areas with elevated radiation levels above background in the following areas: X-3001 Train 2 North Utility Bay, X-3001 Train 3 North Utility Bay, X-3001 Train 3, X-3001 Train 3 water collection areas of the Centrifuge Drains, X-3001 Train 6 and in the water collection area of a Centrifuge Drain, X-7726 CTTF, and X-7726 Second Floor Utility Room. Direct measurements and/or smears were judgmentally collected from 58 locations, based on the results of the scanning.
Random direct measurements and smears were collected from a total of 179 locations throughout SUs X-3001 Train 2 North Utility Bay, X-3001 Train 3 North Utility Bay, X-3001 Train 3, X-3001 Train 3 Centrifuge Drains, and X-7726 CTTF. All direct measurements collected were below the Table 4.1 contamination level with a maximum value of 3,400 dpm/100 cm2 and all smears were below the MDC of the analytical equipment, which were 11 and 14 dpm/100 cm2 for alpha and beta removable activity, respectively. The confirmatory survey results did not identify residual
American Centrifuge Lead Cascade Facility Confirmatory Survey Report 25 5326-SR-01-0 contamination that exceeded the Table 4.1 license application contamination limits, and confirmatory survey measurement population statistics were comparable with the reported FSS data for the respective Lead Cascade survey units investigated.
American Centrifuge Lead Cascade Facility Confirmatory Survey Report 26 5326-SR-01-0
- 9. REFERENCES ACO 2018a. Final Status Survey Report for the American Centrifuge Lead Cascade Facility Decommissioning Project in Piketon, Ohio. DP-2605-002. American Centrifuge Operating, LLC. Bethesda, Maryland. April.
ACO 2018b. Decommissioning Plan for the American Centrifuge Lead Cascade Facility, DP-2605-001.
American Centrifuge Operating, LLC. Bethesda, Maryland. January.
EPA 2006. Data Quality Assessment: Statistical Methods for Practitioners. EPA QA/G-9S. U.S.
Environmental Protection Agency. Washington, D.C. February.
NRC 1998. Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions. NUREG-1507. U.S. Nuclear Regulatory Commission.
Washington, D.C. August.
NRC 2000. Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM). NUREG-1575.
Revision 1. U.S. Nuclear Regulatory Commission. Washington, D.C. August.
NRC 2017. U.S. Nuclear Regulatory Commission Website. https://www.nrc.gtove/info-finder/fc/usec-lead-cascade-oh-lc.html. Last Reviewed/Updated, March 7, 2007. Visited May 2018.
ORAU 2014. ORAU Radiation Protection Manual. Oak Ridge Associated Universities. Oak Ridge, Tennessee. October.
ORAU 2016a. ORAU Radiological and Environmental Survey Procedures Manual. Oak Ridge Associated Universities. Oak Ridge, Tennessee. November 10.
ORAU 2016b. ORAU Environmental Services and Radiation Training Quality Program Manual. Oak Ridge Associated Universities. Oak Ridge, Tennessee. November 9.
ORAU 2016c. ORAU Health and Safety Manual. Oak Ridge Associated Universities. Oak Ridge, Tennessee. January.
ORAU 2017. ORAU Radiological and Environmental Analytical Laboratory Procedures Manual. Oak Ridge Associated Universities. Oak Ridge, Tennessee. August 24.
ORISE 2018. Project-Specific Plan for the Confirmatory Survey Activities at the American Centrifuge Lead Cascade Facility, Piketon, Ohio. Oak Ridge Institute for Science and Education. Oak Ridge, Tennessee. May 18.
American Centrifuge Lead Cascade Facility Confirmatory Survey Report 5326-SR-01-0 APPENDIX A: DATA TABLES AND FIGURES
American Centrifuge Lead Cascade Facility Confirmatory Survey Report A-1 5326-SR-01-0 Figure A-1. X-3001 Train 2 North Utility Bay Measurement Locations Table A.1. X-3001, Train 2 North Utility Bay Survey Data Random/
Judgmental Smear ID Coordinates (m)
Surface Material Total Activity Removable Activity X
Y Alpha Alpha Beta cpm dpm/100 cm2 dpm/100 cm2 Random 5326R0068A 2.2 1.5 Floor Concrete 2
-19
-0.37 0.29 Random 5326R0069A 6.5 1.5 Floor Concrete 5
15
-0.37 5.20 Random 5326R0070A 10.8 1.5 Floor Concrete 4
3.4
-0.37
-3.38 Random 5326R0071A 15.1 1.5 Floor Concrete 5
15
-0.37 1.52 Random 5326R0072A 19.4 1.5 Floor Concrete 1
-31
-0.37 2.75 Random 5326R0073A 23.7 1.5 Floor Concrete 0
-42
-0.37 3.97 Random 5326R0074A 28.0 1.5 Floor Concrete 5
15 1.92 0.29 Random 5326R0075A 0.1 5.3 Floor Concrete 4
3.4
-0.37 0.29 Random 5326R0076A 4.4 5.3 Floor Concrete 7
37
-0.37
-3.38 Random 5326R0077A 8.7 5.3 Floor Concrete 4
3.4
-0.37 2.75 Random 5326R0078A 13.0 5.3 Floor Concrete 7
37
-0.37 1.52 Random 5326R0079A 17.3 5.3 Floor Concrete 4
3.4
-0.37
-0.93 Area with elevated radiation levels between two concrete pads.
American Centrifuge Lead Cascade Facility Confirmatory Survey Report A-2 5326-SR-01-0 Table A.1. X-3001, Train 2 North Utility Bay Survey Data Random/
Judgmental Smear ID Coordinates (m)
Surface Material Total Activity Removable Activity X
Y Alpha Alpha Beta cpm dpm/100 cm2 dpm/100 cm2 Random 5326R0080A 21.6 5.3 Floor Concrete 3
-7.9
-0.37
-2.16 Random 5326R0081A 25.9 5.3 Floor Concrete 5
15
-0.37
-0.93 Random 5326R0082A 30.2 5.3 Floor Concrete 4
3.4
-0.37 3.97 Random 5326R0083A 2.2 9.0 Floor Concrete 9
60
-0.37
-0.93 Random 5326R0084A 6.5 9.0 Floor Concrete 8
49
-0.37 1.52 Random 5326R0085A 10.8 9.0 Floor Concrete 6
26 1.92
-0.93 Random 5326R0086A 15.1 9.0 Floor Concrete 1
-31
-0.37 2.75 Random 5326R0087A 19.4 9.0 Floor Concrete 6
26 4.21 5.20 Random 5326R0088A 23.7 9.0 Floor Concrete 4
3.4
-0.37 1.52 Random 5326R0089A 28.0 9.0 Floor Concrete 2
-19 1.92
-0.93 Random 5326R0090A 0.1 12.7 Floor Concrete 9
60
-0.37 1.52 Random 5326R0091A 4.4 12.7 Floor Concrete 7
37
-0.37 2.75 Random 5326R0092A 8.7 12.7 Floor Concrete 3
-7.9
-0.37 3.97 Random 5326R0093A 13.0 12.7 Floor Concrete 3
-7.9
-0.37 0.29 Random 5326R0094A 17.3 12.7 Floor Concrete 5
15
-0.37
-2.16 Random 5326R0095A 21.6 12.7 Floor Concrete 4
3.4 1.92
-2.16 Random 5326R0096A 25.9 12.7 Floor Concrete 3
-7.9
-0.37
-0.93 Random 5326R0097A 30.2 11.8 Floor Concrete 2
-19
-0.37 0.29 Random 5326R0098A 2.2 16.4 Floor Concrete 2
-19
-0.37
-2.16 Random 5326R0099A 6.5 16.4 Floor Concrete 3
-7.9
-0.37
-2.16 Random 5326R0100A 10.8 16.4 Floor Concrete 1
-31
-0.37
-2.16 Random 5326R0001C 15.1 16.4 Floor Concrete 3
-7.9
-0.37 2.75 Random 5326R0002C 19.4 16.4 Floor Concrete 4
3.4
-0.37 2.75 Random 5326R0003C 23.7 16.4 Floor Concrete 3
-7.9
-0.37
-3.38 Random 5326R0004C 28.0 16.4 Floor Concrete 3
-7.9
-0.37 0.29 Random 5326R0005C 0.1 20.1 Floor Concrete 5
15
-0.37
-3.38 Random 5326R0006C 4.4 20.1 Floor Concrete 9
60 1.92 5.20 Random 5326R0007C 8.7 20.1 Floor Concrete 4
3.4 1.92 1.52 Random 5326R0008C 13.0 20.1 Floor Concrete 5
15
-0.37 2.75 Random 5326R0009C 17.3 20.1 Floor Concrete 4
3.4
-0.37 1.52 Random 5326R0010C 21.6 20.1 Floor Concrete 3
-7.9
-0.37 2.75 Random 5326R0011C 25.9 20.1 Floor Concrete 3
-7.9
-0.37
-3.38 Random 5326R0012C 30.2 20.1 Floor Concrete 2
-19
-0.37
-2.16 Mean 4.1 4.9
American Centrifuge Lead Cascade Facility Confirmatory Survey Report A-3 5326-SR-01-0 Table A.1. X-3001, Train 2 North Utility Bay Survey Data Random/
Judgmental Smear ID Coordinates (m)
Surface Material Total Activity Removable Activity X
Y Alpha Alpha Beta cpm dpm/100 cm2 dpm/100 cm2 Judgmental 5326R0013C NA NA Floor Concrete 30 300 4.21 0.29 Judgmental 5326R0014C NA NA Floor Concrete 61 650
-0.37
-0.93 Judgmental 5326R0015C NA NA Floor Concrete 71 760
-0.37 2.75 Judgmental 5326R0016C NA NA Floor Concrete 69 740
-0.37
-0.93 NA= Not applicable
American Centrifuge Lead Cascade Facility Confirmatory Survey Report A-4 5326-SR-01-0 Figure A-2. X-3001 Train 3 North Utility Bay Measurement Locations Area with elevated radiation levels.
American Centrifuge Lead Cascade Facility Confirmatory Survey Report A-5 5326-SR-01-0 Table A.2. X-3001, Train 3 North Utility Bay Survey Data Random/
Judgmental Smear ID Coordinates (m)
Surface Material Total Activity Removable Activity X
Y Alpha Alpha Beta cpm dpm/100 cm2 dpm/100 cm2 Random 5326R0025A 3.2 3.3 Floor Concrete 10 71
-0.37 0.29 Random 5326R0026A 7.5 3.3 Floor Concrete 4
3.4
-0.37
-2.16 Random 5326R0027A 11.8 3.3 Floor Concrete 2
-19
-0.37
-2.16 Random 5326R0028A 16.1 3.3 Floor Concrete 6
26
-0.37
-0.93 Random 5326R0029A 20.4 3.3 Floor Concrete 3
-7.9
-0.37 3.97 Random 5326R0030A 24.7 3.3 Floor Concrete 8
49
-0.37
-0.93 Random 5326R0031A 28.9 3.3 Floor Concrete 0
-42
-0.37
-2.16 Random 5326R0032A 1.1 7.0 Floor Concrete 2
-19
-0.37
-3.38 Random 5326R0033A 5.4 7.0 Floor Concrete 3
-7.9
-0.37 0.29 Random 5326R0034A 9.6 7.0 Floor Concrete 5
15
-0.37 0.29 Random 5326R0035A 13.9 7.0 Floor Concrete 4
3.4
-0.37 1.52 Random 5326R0036A 18.2 7.0 Floor Concrete 6
26
-0.37 0.29 Random 5326R0037A 22.5 7.0 Floor Concrete 6
26
-0.37 1.52 Random 5326R0038A 26.8 7.0 Floor Concrete 8
49
-0.37
-0.93 Random 5326R0039A 31.1 7.0 Floor Concrete 6
26
-0.37 1.52 Random 5326R0040A 3.2 8.6 Floor Concrete 7
37
-0.37
-2.16 Random 5326R0041A 7.5 8.6 Floor Concrete 4
3.4 1.92 3.97 Random 5326R0042A 11.8 10.7 Floor Concrete 3
-7.9
-0.37 1.52 Random 5326R0043A 16.1 10.7 Floor Concrete 4
3.4
-0.37 0.29 Random 5326R0044A 20.4 10.7 Floor Concrete 8
49
-0.37 0.29 Random 5326R0045A 24.7 10.7 Floor Concrete 3
-7.9
-0.37 3.97 Random 5326R0046A 28.9 10.7 Floor Concrete 2
-19 1.92 1.52 Random 5326R0047A 1.1 14.4 Floor Concrete 2
-19
-0.37
-3.38 Random 5326R0048A 5.4 14.4 Floor Concrete 2
-19
-0.37 2.75 Random 5326R0049A 9.6 14.4 Floor Concrete 3
-7.9
-0.37 2.75 Random 5326R0050A 13.9 14.4 Floor Concrete 3
-7.9
-0.37 5.20 Random 5326R0051A 18.2 14.4 Floor Concrete 7
37 4.21
-2.16 Random 5326R0052A 22.5 14.4 Floor Concrete 4
3.4
-0.37 2.75 Random 5326R0053A 26.8 14.4 Floor Concrete 7
37
-0.37
-2.16 Random 5326R0054A 31.1 14.4 Floor Concrete 3
-7.9
-0.37 0.29 Random 5326R0055A 3.2 18.1 Floor Concrete 8
49
-0.37
-0.93 Random 5326R0056A 7.5 18.1 Floor Concrete 6
26
-0.37 3.97 Random 5326R0057A 11.8 18.1 Floor Concrete 5
15 1.92
-3.38 Random 5326R0058A 16.1 18.1 Floor Concrete 3
-7.9
-0.37
-2.16
American Centrifuge Lead Cascade Facility Confirmatory Survey Report A-6 5326-SR-01-0 Table A.2. X-3001, Train 3 North Utility Bay Survey Data Random/
Judgmental Smear ID Coordinates (m)
Surface Material Total Activity Removable Activity X
Y Alpha Alpha Beta cpm dpm/100 cm2 dpm/100 cm2 Random 5326R0059A 20.4 18.1 Floor Concrete 5
15
-0.37 0.29 Random 5326R0060A 24.7 18.1 Floor Concrete 4
3.4
-0.37
-3.38 Random 5326R0061A 28.9 18.1 Floor Concrete 3
-7.9
-0.37
-0.93 Mean 4.6 10 Judgmental 5326R0062A NA NA Floor Concrete 112 1,200
-0.37
-0.93 Judgmental 5326R0063A NA NA Floor Concrete 127 1,400
-0.37
-0.93 Judgmental 5326R0064A NA NA Floor Concrete 104 1,100
-0.37 7.65 Judgmental 5326R0065A NA NA Floor Concrete 137 1,500
-0.37 1.52 Judgmental 5326R0066A NA NA Floor Concrete 130 1,400
-0.37
-2.16 Judgmental 5326R0067A NA NA Floor Concrete 199 2,200
-0.37 2.75 NA= Not applicable
American Centrifuge Lead Cascade Facility Confirmatory Survey Report A-7 5326-SR-01-0 Figure A-3. X-3001 Trains 2 and 3 North Utility Bay Drains Measurement Locations
American Centrifuge Lead Cascade Facility Confirmatory Survey Report A-8 5326-SR-01-0 Table A.3. X-3001, Trains 2 and 3 North Utility Bay Drains Survey Data Random/
Judgmental Smear ID Coordinates (m)
Surface Material Total Activity Removable Activity X
Y Alpha Alpha Beta cpm dpm/100 cm2 dpm/100 cm2 Train 2 Judgmental 5326R0065B NA NA Drain Rusted Metal NA NA 1.92
-2.16 Judgmental 5326R0066B NA NA Drain Rusted Metal NA NA
-0.37 0.29 Judgmental 5326R0067B NA NA Drain Rusted Metal NA NA
-0.37
-0.93 Train 3 Judgmental 5326R0050B NA NA Drain Rusted Metal NA NA
-0.37 3.97 Judgmental 5326R0051B NA NA Drain Rusted Metal NA NA 1.92 6.42 Judgmental 5326R0052B NA NA Drain Rusted Metal NA NA
-0.37 1.52 Judgmental 5326R0053B NA NA Drain Rusted Metal NA NA
-0.37 0.29 Judgmental 5326R0054B NA NA Drain Rusted Metal NA NA 1.92
-0.93 Judgmental 5326R0055B NA NA Drain Rusted Metal NA NA 1.92 2.75 Judgmental 5326R0056B NA NA Drain Rusted Metal NA NA
-0.37
-2.16 Judgmental 5326R0057B NA NA Drain Rusted Metal NA NA
-0.37
-0.93 Judgmental 5326R0058B NA NA Drain Rusted Metal NA NA
-0.37 1.52 Judgmental 5326R0059B NA NA Drain Rusted Metal NA NA
-0.37 1.52 Judgmental 5326R0060B NA NA Drain Rusted Metal NA NA
-0.37 1.52 Judgmental 5326R0061B NA NA Drain Rusted Metal NA NA
-0.37 3.97 Judgmental 5326R0062B NA NA Drain Rusted Metal NA NA
-0.37 0.29 Judgmental 5326R0063B NA NA Drain Rusted Metal NA NA
-0.37
-0.93 Judgmental 5326R0064B NA NA Drain Rusted Metal NA NA
-0.37 2.75 NA= Not applicable
American Centrifuge Lead Cascade Facility Confirmatory Survey Report A-9 5326-SR-01-0 Figure A-4. X-3001 Train 3 Measurement Locations
American Centrifuge Lead Cascade Facility Confirmatory Survey Report A-10 5326-SR-01-0 Table A.4. X-3001, Train 3 Survey Data Random/
Judgmental Smear ID Coordinates (m)
Surface Material Total Activity Removable Activity X
Y Alpha Alpha Beta cpm dpm/100 cm2 dpm/100 cm2 Random 5326R0001A 0.6 3.2 Floor Concrete 4
3.4
-0.37 5.20 Random 5326R0002A 6.5 3.2 Drain Floor Metal 4
3.4
-0.37
-3.38 Random 5326R0003A 12.5 3.2 Floor Concrete 7
37
-0.37 2.75 Random 5326R0004A 18.4 3.2 Drain Floor Metal 3
-7.9
-0.37 2.75 Random 5326R0005A 24.4 3.2 Floor Metal 3
-7.9
-0.37 2.75 Random 5326R0006A 30.3 3.2 Floor Concrete 5
15
-0.37 0.29 Random 5326R0007A 3.6 8.3 Floor Concrete 5
15
-0.37 2.75 Random 5326R0008A 9.5 8.3 Floor Concrete 5
15 1.92
-3.38 Random 5326R0009A 15.5 8.3 Floor Concrete 1
-31
-0.37 0.29 Random 5326R0010A 21.4 8.3 Floor Concrete 7
37
-0.37
-2.16 Random 5326R0011A 27.3 8.3 Floor Concrete 5
15
-0.37
-0.93 Random 5326R0012A 0.6 13.5 Floor Concrete 5
15
-0.37 2.75 Random 5326R0013A 6.5 13.5 Floor Concrete 6
26
-0.37 1.52 Random 5326R0014A 12.5 13.5 Floor Concrete 6
26 1.92 0.29 Random 5326R0015A 18.4 13.5 Floor Concrete 4
3.4
-0.37 1.52 Random 5326R0016A 24.4 13.5 Floor Concrete 4
3.4
-0.37
-2.16 Random 5326R0017A 30.3 13.5 Floor Concrete 2
-19
-0.37
-0.93 Random 5326R0018A 3.6 18.6 Floor Concrete 3
-7.9
-0.37 0.29 Random 5326R0019A 9.5 18.6 Floor Concrete 3
-7.9 1.92 2.75 Random 5326R0020A 15.5 18.6 Floor Concrete 2
-19
-0.37 2.75 Random 5326R0021A 21.4 18.6 Floor Concrete 4
3.4
-0.37
-0.93 Random 5326R0022A 27.3 18.6 Floor Concrete 5
15 1.92 1.52 Mean 4.2 6.0 Judgmental 5326R0023A Near Southwest Corner of Centrifuge Drain 4-12 Floor Concrete 56 590
-0.37
-0.93 Judgmental 5326R0024A Floor Metal/
Concrete 67 720 1.92 3.97 NA= Not applicable
American Centrifuge Lead Cascade Facility Confirmatory Survey Report A-11 5326-SR-01-0 Figure A-5. X-3001 Train 3 Centrifuge Drains Measurement Locations
American Centrifuge Lead Cascade Facility Confirmatory Survey Report A-12 5326-SR-01-0 Table A.5. X-3001, Train 3 Centrifuge Drains Survey Data Random/
Judgmental Smear ID Coordinates (m)
Surface Material Total Activity Removable Activity X
Y Alpha Alpha Beta cpm dpm/100 cm2 dpm/100 cm2 Random 5326R0041C NA NA Over Drain Metal/PVC 0
-42
-0.37
-0.93 Random 5326R0042C NA NA Over Drain Metal/PVC 4
3.4
-0.37
-2.16 Random 5326R0043C NA NA Over Drain Metal/PVC 1
-31
-0.37 1.52 Random 5326R0044C NA NA Over Drain Metal/PVC 1
-31
-0.37
-2.16 Random 5326R0045C NA NA Over Drain Metal/PVC 2
-19
-0.37
-0.93 Random 5326R0046C NA NA Over Drain Metal/PVC 1
-31
-0.37
-2.16 Random 5326R0047C NA NA Over Drain Metal/PVC 3
-7.9
-0.37 0.93 Random 5326R0048C NA NA Over Drain Metal/PVC 3
-7.9
-0.37 6.42 Random 5326R0049C NA NA Over Drain Metal/PVC 0
-42 1.92 1.52 Random 5326R0051C NA NA Over Drain Metal/PVC 1
-31
-0.37 0.29 Random 5326R0052C NA NA Over Drain Metal/PVC 0
-42
-0.37 1.52 Random 5326R0053C NA NA Over Drain Metal/PVC 2
-19 1.92
-0.93 Random 5326R0054C NA NA Over Drain Metal/PVC 1
-31
-0.37 1.52 Random 5326R0055C NA NA Over Drain Metal/PVC 3
-7.9
-0.37 5.20 Random 5326R0056C NA NA Over Drain Metal/PVC 3
-7.9
-0.37
-0.93 Random 5326R0057C NA NA Over Drain Metal/PVC 0
-42 1.92 7.65 Random 5326R0058C NA NA Over Drain Metal/PVC 4
3.4 1.92 0.29 Random 5326R0059C NA NA Over Drain Metal/PVC 1
-31
-0.37 0.29 Random 5326R0061C NA NA Over Drain Metal/PVC 3
-7.9
-0.37 1.52 Random 5326R0062C NA NA Over Drain Metal/PVC 2
-19
-0.37 0.29 Random 5326R0063C NA NA Over Drain Metal/PVC 2
-19
-0.37
-0.93 Random 5326R0064C NA NA Over Drain Metal/PVC 2
-19
-0.37 0.29 Random 5326R0065C NA NA Over Drain Metal/PVC 3
-7.9
-0.37 2.75 Random 5326R0067C NA NA Over Drain Metal/PVC 1
-31
-0.37 2.75
American Centrifuge Lead Cascade Facility Confirmatory Survey Report A-13 5326-SR-01-0 Table A.5. X-3001, Train 3 Centrifuge Drains Survey Data Random/
Judgmental Smear ID Coordinates (m)
Surface Material Total Activity Removable Activity X
Y Alpha Alpha Beta cpm dpm/100 cm2 dpm/100 cm2 Random 5326R0068C NA NA Over Drain Metal/PVC 4
3.4
-0.37
-0.93 Random 5326R0069C NA NA Over Drain Metal/PVC 3
-7.9
-0.37 1.52 Random 5326R0070C NA NA Over Drain Metal/PVC 3
-7.9
-0.37 3.97 Random 5326R0071C NA NA Over Drain Metal/PVC 7
37
-0.37
-3.38 Random 5326R0072C NA NA Over Drain Metal/PVC 2
-19
-0.37
-3.38 Random 5326R0073C NA NA Over Drain Metal/PVC 6
26
-0.37
-2.16 Random 5326R0074C NA NA Over Drain Metal/PVC 2
-19
-0.37 1.52 Random 5326R0076C NA NA Over Drain Metal/PVC 4
3.4
-0.37
-0.93 Random 5326R0077C NA NA Over Drain Metal/PVC 1
-31
-0.37 5.20 Random 5326R0078C NA NA Over Drain Metal/PVC 3
-7.9
-0.37 2.75 Random 5326R0079C NA NA Over Drain Metal/PVC 2
-19
-0.37 3.97 Random 5326R0081C NA NA Over Drain Metal/PVC 1
-31
-0.37 2.75 Random 5326R0082C NA NA Over Drain Metal/PVC 1
-31
-0.37
-0.93 Random 5326R0083C NA NA Over Drain Metal/PVC 2
-19
-0.37 3.97 Random 5326R0084C NA NA Over Drain Metal/PVC 6
26
-0.37
-0.93 Random 5326R0085C NA NA Over Drain Metal/PVC 1
-31
-0.37 2.75 Random 5326R0086C NA NA Over Drain Metal/PVC 1
-31
-0.37 1.52 Random 5326R0087C NA NA Over Drain Metal/PVC 2
-19
-0.37 2.75 Random 5326R0088C NA NA Over Drain Metal/PVC 3
-7.9
-0.37 0.29 Random 5326R0089C NA NA Over Drain Metal/PVC 5
15
-0.37
-0.93 Random 5326R0090C NA NA Over Drain Metal/PVC 5
15
-0.37
-2.16 Random 5326R0091C NA NA Over Drain Metal/PVC 1
-31
-0.37
-3.38 Random 5326R0092C NA NA Over Drain Metal/PVC 1
-31
-0.37
-0.93 Random 5326R0093C NA NA Over Drain Metal/PVC 0
-42
-0.37
-0.93
American Centrifuge Lead Cascade Facility Confirmatory Survey Report A-14 5326-SR-01-0 Table A.5. X-3001, Train 3 Centrifuge Drains Survey Data Random/
Judgmental Smear ID Coordinates (m)
Surface Material Total Activity Removable Activity X
Y Alpha Alpha Beta cpm dpm/100 cm2 dpm/100 cm2 Random 5326R0094C NA NA Over Drain Metal/PVC 1
-31
-0.37
-3.38 Random 5326R0095C NA NA Over Drain Metal/PVC 2
-19
-0.37
-2.16 Random 5326R0096C NA NA Over Drain Metal/PVC 4
3.4
-0.37
-0.93 Random 5326R0097C NA NA Over Drain Metal/PVC 4
3.4 1.92
-3.38 Random 5326R0098C NA NA Over Drain Metal/PVC 3
-7.9
-0.37
-2.16 Random 5326R0099C NA NA Over Drain Metal/PVC 7
37
-0.37 0.93 Random 5326R0100C NA NA Over Drain Metal/PVC 2
-19
-0.37
-3.38 Mean 2.4
-15.0 Judgmental 5326R0019B NA NA Water Collection Area Metal 66 710 1.92 5.20 Judgmental 5326R0018B NA NA Water Collection Area Metal 182 2,000 1.92 7.65 Judgmental 5326R0050C NA NA Water Collection Area Metal 16 140 1.92
-2.16 Judgmental 5326R0060C NA NA Water Collection Area Metal 93 1,000 8.79 0.29 Judgmental 5326R0066C NA NA Water Collection Area Metal 44 460 1.92 1.52 Judgmental 5326R0017B NA NA Water Collection Area Metal 176 2,000 6.50 3.97 Judgmental 5326R0075C NA NA Water Collection Area Metal 37 380
-0.37
-0.93 Judgmental 5326R0080C NA NA Water Collection Area Metal 47 490 4.21 1.52 NA= Not applicable
American Centrifuge Lead Cascade Facility Confirmatory Survey Report A-15 5326-SR-01-0 Figure A-6. X-3001 Train 6 Centrifuge Drain Measurement Locations. 9th Drain from West and 12th Drain from North
American Centrifuge Lead Cascade Facility Confirmatory Survey Report A-16 5326-SR-01-0 Table A.6. X-3001, Train 6 Survey Data Random/
Judgmental Smear ID Coordinates (m)
Surface Material Total Activity Removable Activity X
Y Alpha Alpha Beta cpm dpm/100 cm2 dpm/100 cm2 Judgmental 5326R0017C NA NA Water Collection Area Metal 188 2,100 1.92 2.75 Judgmental 5326R0018C NA NA Floor Concrete 96 1,000
-0.37 2.75 Judgmental 5326R0019C NA NA Drain Ledge Metal 25 240 1.92 5.20 Judgmental 5326R0020C NA NA Drain Floor Metal 1
-31
-0.37
-2.16
American Centrifuge Lead Cascade Facility Confirmatory Survey Report A-17 5326-SR-01-0 Figure A-7. X-7726 CTTF Measurement Locations
American Centrifuge Lead Cascade Facility Confirmatory Survey Report A-18 5326-SR-01-0 Table A.7. X-7726, CTTF Survey Data Random/
Judgmental Smear ID Coordinates (m)
Surface Material Total Activity Removable Activity X
Y Alpha Alpha Beta cpm dpm/100 cm2 dpm/100 cm2 Random 5326R0021C 2.9 2.9 Floor Glazed Concrete 6
26 1.92
-0.93 Random 5326R0022C 11.8 2.9 Floor Glazed Concrete 2
-19
-0.37
-2.16 Random 5326R0023C 20.6 2.9 Floor Glazed Concrete 4
3.4
-0.37 3.97 Random 5326R0024C 29.4 2.9 Floor Glazed Concrete 6
26
-0.37 2.75 Random 5326R0025C 38.3 2.9 Floor Tile 1
-31
-0.37 3.97 Random 5326R0026C 47.1 2.9 Floor Glazed Concrete 8
49 1.92 3.97 Random 5326R0027C 56.0 2.9 Floor Glazed Concrete 3
-7.9
-0.37 2.75 Random 5326R0028C 7.3 10.6 Floor Glazed Concrete 4
3.4
-0.37
-0.93 Random 5326R0029C 16.2 10.6 Floor Glazed Concrete 5
15
-0.37 3.97 Random 5326R0030C 25.0 10.6 Floor Glazed Concrete 3
-7.9
-0.37 2.75 Random 5326R0031C 33.9 10.6 Floor Glazed Concrete 3
-7.9
-0.37
-0.93 Random 5326R0032C 42.7 10.6 Floor Glazed Concrete 4
3.4
-0.37 0.29 Random 5326R0033C 51.5 10.6 Floor Glazed Concrete 12 94
-0.37 5.20 Random 5326R0034C 2.9 18.2 Floor Glazed Concrete 5
15
-0.37 1.52 Random 5326R0035C 11.8 18.2 Floor Glazed Concrete 5
15 1.92 0.29 Random 5326R0036C 20.6 18.2 Plate in Floor Metal 7
37
-0.37 2.75 Random 5326R0037C 29.4 18.2 Floor Glazed Concrete 1
-31
-0.37 0.29 Random 5326R0038C 38.3 18.2 Floor Glazed Concrete 2
-19
-0.37
-0.93 Random 5326R0039C 47.1 18.2 Floor Glazed Concrete 7
37
-0.37 1.52 Random 5326R0040C 56.0 18.2 Floor Glazed Concrete 2
-19
-0.37 1.52 Mean 4.5 9.1 Judgmental 5326R0001B 6.82 45.0 Floor Painted Concrete 1
-31
-0.37
-0.93 Judgmental 5326R0002B 13.0 54.0 Floor Sealed Concrete 5
15
-0.37 2.75
American Centrifuge Lead Cascade Facility Confirmatory Survey Report A-19 5326-SR-01-0 Table A.7. X-7726, CTTF Survey Data Random/
Judgmental Smear ID Coordinates (m)
Surface Material Total Activity Removable Activity X
Y Alpha Alpha Beta cpm dpm/100 cm2 dpm/100 cm2 Judgmental 5326R0003B 53.0 21.0 Floor Sealed Concrete 13 110
-0.37 2.75 Judgmental 5326R0004B 51.0 20.0 Floor Sealed Concrete 2
-19
-0.37 0.29 Judgmental 5326R0005B 48.5 19.5 Floor Sealed Concrete 11 83
-0.37 6.42 Judgmental 5326R0006B 48.3 16.8 Floor Sealed Concrete 9
60 1.92
-0.93 Judgmental 5326R0007B 48.2 16.3 Floor Sealed Concrete 6
26
-0.37
-2.16 Judgmental 5326R0008B 2.6a 11.4a Floor Sealed Concrete 6
26
-0.37 1.52 Judgmental 5326R0015B NAb NAb Equipment Painted Metal 69 740
-0.37 0.29 Judgmental 5326R0016B NAb NAb Equipment Plastic 10 71 1.92 3.97 a Local coordinates referenced to CTTF Material Storage Mezzanine b Smears 15B and 16B are not shown in the figure above.
NA = Not applicable
American Centrifuge Lead Cascade Facility Confirmatory Survey Report A-20 5326-SR-01-0 Figure A-8. X-7726 Second Floor Utility Room Measurement Locations
American Centrifuge Lead Cascade Facility Confirmatory Survey Report A-21 5326-SR-01-0 Table A.8. X-7726, Second Floor Utility Room Survey Data Random/
Judgmental Smear ID Coordinates (m)
Surface Material Total Activity Removable Activity X
Y Alpha Alpha Beta cpm dpm/100 cm2 dpm/100 cm2 Judgmental 5326R0009B 4.7 1.1 Floor Concrete 105 1,100
-0.37
-0.93 Judgmental 5326R0010B 1.4 1.7 Floor Concrete 297 3,300
-0.37
-2.16 Judgmental 5326R0011B 4.0 2.7 Floor Concrete 174 1,900
-0.37 3.97 Judgmental 5326R0012B 3.1 2.5 Floor Concrete 41 420
-0.37 2.75 Judgmental 5326R0013B 2.7 2.6 Floor Concrete 154 1,700
-0.37
-2.16 Judgmental 5326R0014B 1.0 2.9 Floor Concrete 307 3,400
-0.37 3.97 NA= Not applicable
American Centrifuge Lead Cascade Facility Confirmatory Survey Report 5326-SR-01-0 APPENDIX B: SURVEY AND ANALYTICAL PROCEDURES
American Centrifuge Lead Cascade Facility Confirmatory Survey Report B-1 5326-SR-01-0 B.1. PROJECT HEALTH AND SAFETY ORISE performed all survey activities in accordance with the ORAU Radiation Protection Manual, the ORAU Health and Safety Manual, and the ORAU Radiological and Environmental Survey Procedures Manual (ORAU 2014, ORAU 2016c, and ORAU 2016a). Prior to on-site activities, a Work-Specific Hazard Checklist was completed for the project and discussed with field personnel. The planned activities were thoroughly discussed with site personnel prior to implementation to identify hazards present.
Additionally, prior to performing work, a pre-job briefing and walk down of the survey areas were completed with field personnel to identify hazards present and discuss safety concerns. Should ORISE have identified a hazard not covered in the ORAU Radiological and Environmental Survey Procedures Manual (ORAU 2016a) or the projects Work-Specific Hazard Checklist for the planned survey and sampling procedures, work would not have been initiated or continued until the hazard was addressed by an appropriate job hazard analysis and hazard controls.
B.2. CALIBRATION AND QUALITY ASSURANCE Calibration of all field instrumentation was based on standards/sources, traceable to National Institute of Standards and Technology (NIST).
Field survey activities were conducted in accordance with procedures from the following documents:
- ORAU Radiological and Environmental Survey Procedures Manual (ORAU 2016a)
- ORAU Radiological and Environmental Analytical Laboratory Procedures Manual (ORAU 2017)
- ORAU Environmental Services and Radiation Training Quality Program Manual (ORAU 2016b)
The procedures contained in these manuals were developed to meet the requirements of U.S. Department of Energy (DOE) Order 414.1D and the NRC Quality Assurance Manual for the Office of Nuclear Material Safety and Safeguards and contain measures to assess processes during their performance.
American Centrifuge Lead Cascade Facility Confirmatory Survey Report B-2 5326-SR-01-0 Quality control procedures include:
- Daily instrument background and check-source measurements to confirm that equipment operation is within acceptable statistical fluctuations.
- Participation in Mixed-Analyte Performance Evaluation Program and Intercomparison Testing Program laboratory quality assurance programs.
- Training and certification of all individuals performing procedures.
- Periodic internal and external audits.
B.3. SURVEY PROCEDURES B.3.1 SURFACE SCANS Alpha-plus-beta scans were performed using the large-area (floor monitor) gas proportional detector with a 0.8 mg/cm2 window and a physical detector area of 584 cm2. Alpha scans were performed using hand-held gas proportional detectors with a 0.8 mg/cm2 window and a physical detector area of 126 cm2. Beta scans were performed using a hand-held Geiger-Mueller (GM) detector with a 1.7 mg/cm2 window and a physical detector area of 15 cm2. The distance between the detector and surface was maintained at a minimum. Specific scan minimum detectable concentrations (MDCs) were not determined for the large-area gas proportional detector or the GM detector as these instruments were used solely as a qualitative means to identify elevated radiation levels in excess of background. Identifications of elevated radiation levels that could exceed the site criteria were determined based on an increase in the audible signal from the indicating instrument.
Surface alpha scan MDC for the hand-held gas proportional detectors was estimated using the equation below. The scan MDC is a function of many variables, including a two-second observation interval and a probability of detection of 0.9 (90 percent probability of detecting 1 count). The alpha weighted efficiency for the Ludlum 43-68 was 0.07. Instruments were multi-source calibrated and the weighted efficiency was determined based on the relative fractions of U-234, U-235, and U-238 in natural uranium. The scan MDC was calculated using the following equation:
= [ln (1 (1)] x (60
)
x 100 2
American Centrifuge Lead Cascade Facility Confirmatory Survey Report B-3 5326-SR-01-0 Where:
P = probability of detection (unitless) i = observation interval (sec)
= total efficiency = x The most conservative result for the detectors used was a scan MDC of 756 dpm/100 cm2.
B.3.2 SURFACE ACTIVITY MEASUREMENTS Measurements of gross alpha surface activity levels were performed using hand-held gas proportional detectors coupled to portable ratemeter-scalers. Count rates (cpm), which were integrated over one minute with the detector held in a static position, were converted to activity levels (dpm/100 cm2) by dividing the count rate by the total static efficiency (x ) and correcting for the physical area of the detector plus background. The total weighted alpha efficiency for the Ludlum 43-68 was 0.07. Instruments were multi-source calibrated and the weighted efficiency was determined based on the relative fractions of U-234, U-235, and U-238 in natural uranium. The MDC for static surface activity measurements was calculated using the following equation:
= 3 + (4.65)
Where:
B = background in time interval, T (1 min)
T = count time (min) used for field instruments
= total efficiency = x G = geometry correction factor (1.26)
The result for the one detector used for all final quantitative measurements was an alpha static MDC of 105 dpm/100 cm2.
B.4. RADIOLOGICAL ANALYSIS B.4.1 GROSS ALPHA/BETA Smears were counted on a low-background proportional counter for gross alpha and beta activity.
The minimum detectable activity of the procedures is approximately 11 dpm/100 cm2 for alpha and 14 dpm/100 cm2 for beta.
American Centrifuge Lead Cascade Facility Confirmatory Survey Report 5326-SR-01-0 APPENDIX C: MAJOR INSTRUMENTATION
American Centrifuge Lead Cascade Facility Confirmatory Survey Report C-1 5326-SR-01-0 The display of a specific product is not to be construed as an endorsement of the product or its manufacturer by the author or his employer.
C.1. SCANNING AND MEASUREMENT INSTRUMENT/
DETECTOR COMBINATIONS C.1.1 ALPHA-PLUS-BETA Ludlum Gas-flow Proportional Detector Model 43-37, 584 cm2 physical area, 0.8 mg/cm2 Mylar window (Ludlum Measurements, Inc., Sweetwater, Texas) coupled to: Ludlum Ratemeter-scaler Model 2221 (Ludlum Measurements, Inc., Sweetwater, Texas) coupled to: Trimble Geo 7X (Trimble Navigation Limited, Sunnyvale, CA)
C.1.2 ALPHA Ludlum Gas-flow Proportional Detector Model 43-68, 126 cm2 physical area, 0.8 mg/cm2 Mylar window (Ludlum Measurements, Inc., Sweetwater, Texas) coupled to: Ludlum Ratemeter-scaler Model 2221 (Ludlum Measurements, Inc., Sweetwater, Texas)
C.1.3 BETA Ludlum Geiger-Mueller Detector Model 44-9, 15 cm2 physical area, 1.7 mg/cm2 Mylar window (Ludlum Measurements, Inc., Sweetwater, Texas) coupled to: Ludlum Ratemeter-scaler Model 2221 (Ludlum Measurements, Inc., Sweetwater, Texas)
C.2. LABORATORY ANALYTICAL INSTRUMENTATION Low-Background Gas Proportional Counter Series 5 XLB (Canberra, Meriden, CT)
Used in conjunction with:
Eclipse Software Dell Workstation (Canberra, Meriden, CT)