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Enclosure 1: DP-2605-0002, Revision 0, Final Status Survey Report for the American Centrifuge Lead Cascade Facility Decommissioning Project
	ML18145A131
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Site:	07007003
Issue date:	04/30/2018
From:	; American Centrifuge Operating, Centrus Energy Corp
To:	; Office of Nuclear Material Safety and Safeguards
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References
	ACO 18-0015 DP-2605-0002, Rev 0
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Enclosure 1 of ACO 18-0015 DP-2605-0002, Final Status Survey Report/or the American Centrifuge Lead Cascade Facility Decommissioning Project Revision 0 Information Contained Within Does Not Contain Export Controlled Information Reviewing Official:

ECI Reviewer# 152 Date:

04/ 19/2018

DP-2605-0002 inal tatus urvey epor for the American Centrifuge Lead Cascade Facility Decommissioning Project Revision 0 in Piketon, Ohio The American Centrifuge' American Centrifuge Operating, LLC License Number SNM-7003 Docket Number 70-7003 IO CFR Part 1045 review completed by DC #4 798 on 04/19/2018 Information Contained Within Does Not Contain Export Controlled Information Reviewing Official:

ECI Reviewer # 152 Date:

04/ 19/18 April 2018

DP-2605-0002, Final Status Survey Report for the American Centrifuge Lead Cascade Facility Decommissioning Proj ect Revision O April 2018 ALARA ASG bkg BSA CFR cm2 cpm CTTF DCGL DOE dpm FSSR GCEP GCPM HP LBGR ACRONYMS as low as reasonably achievable Auxiliary Standby Generator

Background

Buffer Storage Area Code of Federal Regulations square centimeters Counts Per Minute Centrifuge Training and Test Facility Derived Concentration Guideline Level U.S. Department of Energy disintegrations per minute Final Status Survey Report Gas Centrifuge Enrichment Plant Gross Counts Per Minute Health Physics Lower Band of the Gray Region Lead Cascade American Centrifuge Lead Cascade Facility LEC Liquid Effluent Collection MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual MDA minimum detectable activity MDCR minimum detectable count rate m2 square meters rnrem millirem

DP-2605-0002, Final Status Survey Report for the American Centrifuge lead Cascade Facility Decommissioning Project Revision O April 2018 NNSS Nevada National Security Site NRC U.S. Nuclear Regulatory Commission pCi/m2 picocurie per square meters RPSD Reference Point Standard Deviation TLD Thermoluminescence Dosimeter u

uranium U02F2 uranyl fluoride WRS Wilcoxon Rank Sum 2

DP-2605-0002, Final Status Survey Report for the American Centrifuge Lead Cascade Facility Decommissioning Proj ect Revision O April 2018 TABLE OF CONTENTS I.

EXECUTIVE

SUMMARY

.............................................................................................. 5 II.

REPORT BACKGROUND............................................................................................. 7 Ill.

OVERVIEW OF RE SUL TS.......................................................................................... 13 IV. CHANGES IN FINAL STATUS SURVEY.................................................................. 18 V.

METHODS USED......................................................................................................... 18 VI.

SUMMARY

OF VALUES............................................................................................ 19 VII. SURVEY RESULTS..................................................................................................... 28 VIII. DESCRIPTION OF CHANGES.................................................................................... 45 IX. AS LOW AS REASONABLY ACHIEVABLE PRACTICES..................................... 45 X.

SURVEY UNIT FAILURES......................................................................................... 45 XI.

RESRAD-BUILD EVALUATION............................................................................... 46 XII. REMOVABLE CONTAMINATION EXCEEDANCES.............................................. 46 Appendix A - Withheld Information.................................................................................... A-1 Appendix B - Final Status Surveys [Redacted].................................................................... B-1 Appendix C - RESRAD-BUILD Evaluations...................................................................... C-1 3

DP-2605-0002, Final Status Survey Report for the American Centrifuge Lead Cascade Facility Decommissioning Project Revision O April 2018 TABLES Table II.b-1 Ludlum 2224 Detection Limits.............................................................................. 8 Table II.c-1 Summary Statistics for Alpha........................................................................ 11 Table II.c-2 Summary Statistics for Beta........................................................................... 11 Table III-I Distribution of Alpha Measurements.............................................................. 14 Table III-2 Distribution of Beta Measurements................................................................ 16 Table VI-1 Sample Size Determination............................................................................. 19 Table VI-2 Statistical Evaluation of Systematic Survey Units.......................................... 21 Table VI-3 Follow-up Surveys.......................................................................................... 26 Table VII-I Summary of the Lead Cascade Final Status Survey Results........................... 30 Table XI-1 Summary ofRESRAD-BUILD Evaluations...................................................46 FigureI-1 Figure II-1 Figure II-2 Figure III-I Figure III-2 Figure III-3 FIGURES DOE Reservation.......................................................................................... 5 American Centrifuge Lead Cascade Facility Footprint............................. A-2 Lead Cascade Building X-3001 Layout..................................................... A-3 Alpha Results from the Final Status Survey................................................ 14 Retrospective Power Curve......................................................................... 15 Beta Results from the Final Status Survey................................................... 16 4

DP-2605-0002, Final Status Survey Report for the American Centrifuge lead Cascade Facility Decommissioning Project Revision O April 2018 I.

Executive Summary The footprint of the American Centrifuge Lead Cascade Facility (Lead Cascade) is located within a highly developed industrial U.S. Department of Energy (DOE) reservation which has been subject to extensive environmental characterizations. Figure I-1 below depicts the portion of the reservation associated with the American Centrifuge Program that is roughly enclosed by the below red circle.

Figure 1-1 DOE Reservation The Gas Centrifuge Enrichment Plant (GCEP) Lease between the DOE and the United States Enrichment Corporation for the GCEP Appendix 1, Section 4.3, Return ofGCEP Leased Premises, GCEP Leased Facilities, and GCEP Leased Personalty, Section (c) states in part, "Prior to returning the GCEP Leased Facilities, the Corporation will comply with the following criteria: 1)

For radiological contamination, the GCEP Leased Facilities shall be returned in a condition that meets U.S. Nuclear Regulatory Commission's (NRC) radiological criteria for unrestricted use in 10 Code of Federal Regulations (CFR) 20.1402, as amended." The facilities covered by this Decommissioning Plan fall within the GCEP Leased Facilities as defined in the GCEP Lease.

Therefore, based upon this lease condition, at the completion of decontamination and decommissioning of the Lead Cascade, the facilities will be prepared for return to the DOE for unrestricted use per lease requirements.

5

DP-2605-0002, Final Status Survey Report for the American Centrifuge l ead Cascade Facility Decommissioning Proj ect Revision O April 2018 The Lead Cascade decommissioning efforts began in the first quarter of 2017. Packaging and shipping activities associated with the classified and/or contaminated waste were completed over a ten-month period which began in March 2017. The final shipment to the Nevada National Security Site (NNSS) was completed in December 2017.

Contaminated equipment and piping installed in the Lead Cascade was removed, containerized, and shipped to NNSS. After contaminated items were removed, the areas were cleaned and the survey plan commenced. The survey plan goal was to ensure residual contamination levels were less than 10 CFR Part 20 free release criteria and the Lead Cascade License Application limits.

The base assumptions when developing the Final Status Survey were:

1. The buildings/facilities would continue to be utilized as industrial facilities following decommissioning and therefore the dose model would be for that of full-time workers in an industrial setting.

2. The greatest exposure potential would be from a building occupancy scenario.

3. The occupancy time was based on an 8-hour work day, 5 days per week, and 50 weeks per year

4. The contaminant was uranyl fluoride (U02F2) at assays between 0.3 and 5 percent 235U.

Health Physic sample analysis indicated other radionuclides were not an issue.

5. The Licensee's analysis indicated that nearly 100 percent of the projected dose is due to the uranium isotopes and the highest dose occurs in the first year. Therefore, the Final Status Survey's acceptance was based on residual alpha activity.

Since all Lead Cascade equipment has been removed the floor spaces where Lead Cascade equipment operated or dismantled; the X-3001 Process Building, Train 3 and the North Utility Bay, and the X-7726 Centrifuge Training and Test Facility (CTTF) had the highest potential for residual contamination. The primary focus of the Final Status Survey was the floor surface.

However, multiple measurements were taken on walls and vertical supports in these areas.

For Class I survey units, a 100 percent scan of the surface was performed with a floor monitor.

Additional surveys were performed at locations when the count rate exceeded 1,500 Counts Per Minute (cpm); the location was quantified using the Ludlum 2224.

Depending on probability of contamination, Class II Surveys Units were a 50 percent scan using the floor monitor, or a systematic grid using the Ludlum 2224. Large areas with the highest potential for contamination were divided into equal size areas such that the Survey Unit did not exceed 1,000 square meters (m2). The typical size of a Survey Unit was 676 ni. In small areas (less than 200 m2) and Class III areas survey locations were selected by the Health Physics (HP)

Technicians; maintaining a triangular grid when possible.

6

DP-2605-0002, Final Status Survey Report f or the American Centrifuge l ead Cascade Facility Decommissioning Project Revision O April 2018 As committed within DP-2605-0001, Decommissioning Plan for the American Centrifuge Lead Cascade Facility in Piketon, Ohio, submitted to the NRC on January 5, 2018, American Centrifuge Operating, LLC, the Licensee, has prepared this Final Status Survey Report (FSSR) which presents the results of the final status radiological surveys for the Lead Cascade Decommissioning Project in Piketon, Ohio.

II.

Report Background Based on RESRAD-BUILD (discussed in Section V.b of the Decommissioning Plan - DP-2605-0001), a revised DCGLw of39,200 disintegrations per minute (dpm)/100 square centimeters (cm2) meets the 25 millirem (mrem) criteria (rounded) [as revised during the Request for Additional Information phase of the review process]. The Lead Cascade License Application limits are more restrictive and limit total contamination levels for unrestricted release to 5,000 dpm/100 cm2. This is consistent with the Lead Cascade License Application limits; therefore, a contamination level for the Final Status Survey will be 5,000 dpm/100 cm2 alpha was selected to be consistent with Lead Cascade License Application limits and as low as reasonably achievable (ALARA) guidelines.

II.a Survey Units Discussion The areas impacted by Lead Cascade operations are shown in Figure 11-1 (see Appendix A of this report). Due to the size of the areas, multiple survey units were selected based on the potential for residual contamination being present.

Except for the X-3002 Process Building areas, each of the impacted areas were on the Licensee's Routine Survey program and a review of the data at the time of cessation of Lead Cascade operations indicated removable contamination levels were less than 200 dpm/100 cm2 alpha and less than 700 dpm/100 cm2 beta. As shown in Figure II-2 (see Appendix A of this report), there were two small areas with elevated levels of contamination within the X-3001 building due to Lead Cascade Operations. Within these two areas, discrete locations exceeded total contamination levels of 5,000 dpm/100 cm2* After remediation, all levels were less than the Lead Cascade License Application Table 4.6-1 levels.

II.b Survey Instrumentation Ludlum 2224 The primary instrument personnel used during the Final Status Survey was the Ludlum Model 2224-1 Alpha-beta Scaler Ratemeter equipped with a 100 cm2 Ludlum 43-89 dual phosphor alpha/beta scintillation probe. The average detection limit (Lo) is the true net signal level that may be expected (a priori) to lead to detection. Calculated as follows:

LD = 2.71+4.650-8 7

DP-2605-0002, Final Status Survey Report for the American Centrifuge Lead Cascade Facility Decommissioning Project Revision O April 20 I 8 Table II.b-1 below shows data from a recent Reference Point Background study performed with a Ludlum 2224 in the X-3002 building and depicts the expected Lo in both cpm and dpm.

Table 11.b-l Ludlum 2224 Detection Limits Lo dpm/100cm 2

cpm Alpha Beta Alpha Beta Wall 10.3 65.2 125 285 Floor 11.6 77.5 141 !

339 Column 9.5 51.1 116 223 Using the above data, for scanning items and areas the calculated minimum detectable count rate (MDCR) is approximately 16 cpm alpha and 137 cpm beta (MDCR based on Multi-Agency Radiation Survey and Site Investigation Manual [MARSSIM] Chapter 6 calculation accounting for surveyor efficiency). This calculation assumed a 4 second pause time over area with elevated count rate. Testing at the Lead Cascade indicates that an area with 100 cpm (alpha plus beta) above background is easily distinguishable.

100 cpm above background would indicate the possibility of greater than 1,000 dpm of natural uranium. Therefore, when 100 cpm above background is observed a static survey of the location is recorded.

When recording contamination levels, surface or source efficiency (es) is set to 0.25 for alpha and 0.5 for beta and applied to the final results. The formula for reporting results is:

dpm

=

100 cm 2 GCPM - BKG E.ff

e, Background (BKG) is defined as the daily average count rate of the Reference Point. This daily background was used for direct alpha and beta measurements.

Since uranium is an alpha emitter and uranium nuclides result in the most dose in the first year, the primary focus of the surveys was on alpha results. However, both alpha and beta results were recorded and evaluated.

Floor Monitor A Ludlum 239-1 Floor Monitor was used to scan a survey units floor area to determine areas of elevated radioactivity. The instrument is equipped with a Ludlum 2224 scaler/ratemeter connected to a 430 cm2 (effective area) gas proportional detector utilizing P-10 counting gas. The detector height was set to 0.5-inch (1.27 cm). A 0.5-inch detector height was selected to minimize risk of detector damage, while providing reasonable assurance of detecting contamination at or below the Lead Cascade License Application Table 4.6-1 limits. Typical background levels were between 900 and 1,100 cpm (alpha plus beta).

8

DP-2605-0002, Final Status Survey Report for the American Centrifuge Lead Cascade Facility Decommissioning Project Revision O April 2018 An action level ( or MDCRAL) was established where follow-up surveys would be required to ensure the DCGLw ( or basis level) was not exceeded with 95 percent confidence. MDCRAL assuming natural uranium (alpha plus beta) with a 0.5-inch detector height is determined as follows:

dpm MDCRAL(cpm) = 5,000 100 cm2 x 0.043 x 0.25 x 4.3 = 229 cpm (alpha)

The MCDRAL for uranium beta is 1,591 cpm. Therefore, assuming 5,000 dpm/100 cm2 of natural uranium alpha contamination with uranium daughters (beta emitters) in equilibrium the expected MDCRAL (alpha plus beta) will be 1,820 cpm above background or roughly 3,000 gross cpm.

Since there are fewer beta emissions expected for higher uranium assay; when using the Floor Monitor during the Lead Cascade Final Status Survey, if the observed gross count rate (alpha plus beta) was greater than or equal to 1,500 cpm, the area was marked. At this location, a survey is performed with the Ludlum 2224 to quantify contamination levels.

Ludlum 12 Meters Other items and equipment that remain after decommissioning (walls, uprights, Centrifuge Machine mounts, installed equipment, etc.) and items slated for free release were surveyed using a Ludlum 12 meter equipped with a Model 43-5 Alpha Scintillation Probe for alpha contamination monitoring or a Model 44-9 GM Pancake Probe for beta-gamma contamination monitoring. This combination exhibits normal alpha background between 5 to 25 cpm, and normal beta-gamma background between 30 and 100 cpm.

A count rate of 100 cpm is easily observed in the field, and at the Lead Cascade, the minimum detectable count rate (MDCR) is defined to be 100 cpm.

Since, 100 cpm meets or exceeds the Lead Cascade free release criteria for surveys, the minimum documented results using the Ludlum 12 are:

200 dpm/100 cm2 alpha and 700 dpm/100 cm2 beta for removable (or wipe) samples, and 400 dpm/100 cm2 alpha and 5,000 dpm/100 cm2 beta for direct measurements.

The limits for surveys performed using the Ludlum 12 are the values listed in Lead Cascade License Application Table 4.6-1 or 1,000 dpm/100 cm2 removable or 5,000 dpm/100 cm2 total.

Tennelec LB5100 A removable contamination sample was collected at each direct survey point.

Removable contamination samples were counted with the Tennelec LB5100. The Tennelec LB5100 has a typical detection limit (MDA) of less than 10 dpm for both alpha and beta.

9

DP-2605-0002, Final Status Survey Report for the American Centrifuge Lead Cascade Facility Decommissioning Project Revision O April 2018 11.c Survey Techniques During equipment removal and packaging, HP personnel performed job coverage surveys using the Ludlum 12 meters to identify areas that may require decontamination/remediation. None were identified; therefore, except for the known areas (Class I survey units, etc.) the alpha residual contamination was expected to be less than 400 dpm/100 en/.

The Final Status Survey was designed following the guidance in MARSSIM. Areas identified as impacted have been segregated into Class I, Class II, and Class III areas. Each area was further divided into survey units not to exceed 1,000 m2. For Class II survey unit areas exceeding 200 m2, survey points were selected based on a triangular grid pattern. For Class III survey units the survey points were selected by the technician performing the survey.

For surveys exceeding 9 m2, a minimum of 15 data points was collected. The HP technicians were allowed collect additional reading based on their knowledge of the area.

When using the Ludlum 2224, at each survey location, a 1 m2 area was scanned and a static 1-minute survey was performed at the spot with the highest count rate observed during the scan. A removable contamination sample was collected at each direct survey point.

For surveys using the Floor Monitor, scans were made and locations exceeding a count rate of 1,500 cpm identified, and the location was later scanned with a Ludlum 2224.

For surveys performed using Ludlum 12s, the area/item was scanned, if the observed count was less than 100 cpm above background; either less than 400 dpm/100 cm2 alpha or less than 5,000 dpm/100 cm2 beta was documented. If and area/item indicated greater than 100 cpm above background (alpha or beta), a follow-up survey with the Ludlum 2224 was performed.

Because uranium may exist in trace quantities of structural materials (primarily concrete),

background reference data were collected for Final Status Surveys. A location in the X-3002 building not impacted by Lead Cascade or prior DOE operations was selected. Background readings of the Reference Point were collected over a 17-day period prior to start of the surveys.

Tables II.c-1 and II.c-2 below show a summary of Reference Point data.

10

DP-2605-0002, Final Status Survey Report for the American Centrifuge lead Cascade Facility Decommissioning Project Revision O April 2018 Table 11.c-1 Summary Statistics Table 11.c-2 Summary Statistics Fo~ Alpha For Beta a cpm for a 1 min. count

~ cpm for a 1 min. count Mean 3.147368 Mean 239.1053 Standard Error 0.183269 Standard Error 1.795632 Median 3

Median 240 Mode 3

Mode 234 Standard Deviation 1.786286 Standard Deviation 17.50166 Sample Variance 3.190817 Sample Variance 306.308 Kurtosis 2.888277 Kurtosis

-0.26046 Skewness 1.008768 Skewness

-0.0717 Range 11 Range 84 Minimum 0

Minimum 195 Maximum 11 Maximum 279 Sum 299 Sum 22715 Count 95 Count 95 A minimum of five readings of the reference point was collected daily. In addition to the daily background, additional data points from the Reference Point background study were used as appropriate (if daily background standard deviation appeared disproportionate) when performing the Wilcoxin Rank Sum (WRS) tests. A minimum of five backgrounds were used to evaluate each survey unit. However, normally 15 background readings were used when performing the WRS evaluation for a Survey Unit.

A WRS statistical tests described in MARS SIM Section 5.5.2.2 was used to evaluate survey results collected with the Ludlum 2224. The WRS test compares alpha measurements from the reference area and survey unit. Criteria evaluated during the WRS test include:

1. Sample average is less than 5,000 dpm/100 cm2;

2. Sample standard deviation is less than 3 times the Reference Point(s) standard deviation;

3. Difference of the sample mean and sample median are less than 1;

4. Sample survey points are less than two times the Lo; and

5. Sample standard deviation is less than 1.645 times the reference point standard deviation.

If the survey unit fails these criterion, additional surveys would be collected to ensure the survey unit is acceptable.

The Class I Survey Units are areas that had or have known contamination levels exceeding Table 4.6-1 of the License Application levels (cited in Section V.b of this Decommissioning Plan) and areas that required decontamination because of Lead Cascade activities. These areas had a 100 percent survey performed using a floor monitor. In addition, contamination levels were quantified using the Ludlum 2224. The two small areas located in the X-3001 building North Utility Bay were classified as Class I Survey Units.

11

DP-2605-0002, Final Status Survey Report for the American Centrifuge Lead Cascade Facility Decommissioning Project Revision O April 2018 Depending on probability of contamination, Class II Surveys Units were either a 50 percent scan using the floor monitor, or a systematic grid using the Ludlum 2224. Large areas, such as Train 3 of the X-3001 building, were divided into equal size areas such that the Survey Unit did not exceed 1,000 m2. The typical size ofa Survey Unit is 676 m2.

Each systematic survey unit with an area greater than 200 m2 was gridded and 15 randomly generated survey locations selected based on a triangular grid. For areas less than 200 m2, a triangular grid area was selected. At each survey location, a 1 m2 area was scanned and a static survey performed at the location of the highest observed scanning count rate.

For systematic surveys using a Ludlum 2224, 15 data points were preselected using a triangular grid. Additional locations were selected based on inspection of the area (i.e., discolored areas, cracks, etc.).

For determining sample locations Lis calculated:

L=

Area 0.866

n Next Row = 0.866

L Systematic Floor Survey Units in for areas greater than 200 m2:

1. Area was gridded.

2. The random start locations (X and Y) between 1 and 5 were determined.

3. Distance from Random Start L calculated.

4. Next Row was calculated.

Using the Excel spreadsheet function (RAND BETWEEN), a random start location was determined within in a 5-meter square area in the Northwest corner of each survey unit. Additional readings may be taken at the HP Technicians or managements discretion.

As part of the decommissioning Lead Cascade process, equipment, components, and piping were removed and containerized for shipment. Job coverage surveys were performed as an ongoing piece of the ALARA process. A considerable amount of housekeeping cleaning efforts was made after completion of equipment removal. Prior to performance of a survey HP personnel inspected the area for debris or items that might damage survey equipment and cleanliness that might impact survey equipment performance.

12

DP-2605-0002, Final Status Survey Report for the American Centrifuge l ead Cascade Facility Decommissioning Project Revision O April 2018 III.

Overview of Results During the Final Status Survey, 1,576 direct measurements were collected using the Ludlum 2224.

97.8 percent of the alpha results and 95.2 percent of the beta results were less than the instruments LD. Several areas were scanned using a Floor Monitor; in these areas random direct measurements were also collected and included in the totals. There was no alpha (or beta) results exceeding 5,000 dpm/1 00 cm2.

Except as noted below, all survey locations were less than 1,000 dpm/100 cm2 alpha and beta and removable samples collected were all less than 20 dpm/100 cm2 (alpha and beta). The results of the direct survey location were binned to show distribution of Ludlum 2224 results. Binning of the data based was based on the following binning criteria:

1. Reference Point Standard Deviation (RPSD) - 22 dpm/100 cm2 alpha and 76 dpm/100 cm2 beta.

2. Curries* Critical Level Le defined as 2.33 times the RPSD - 52 dpm/100 cm2 alpha and 176 dpm/100 cm2 beta.

3. Curries Detection Limit, MDA or LD defined as 2.71 + 4.65 times the RPSD - 137 dpm/100 cm2 alpha and 364 dpm/100 cm2 beta.

4. Curries Determination Limit, LQ defined 14.1 times the RPSD - 315 dpm/100 cm2 alpha and 1,067 dpm/100 cm2 beta.

5. 10 percent of the Lead Cascade License Application limits - 500 dpm/100 cm2 alpha.

6. Lower Band of Gray Region (LBGR) - 2,500 dpm/100 cm2 alpha.

7. The Lead Cascade License Application limits - 5,000 dpm/100 cm2 alpha or beta.

Limits for Qualitative Detection and Quantitative Determination, Lloyd A. Currie 13

DP-2605-0002, Final Status Survey Report for the American Centrifuge lead Cascade Facility Decommissioning Project Revision O April 2018 Table III-I below shows the distribution of alpha measurements from the Final Status Survey:

Table 111-1 Distribution of Alpha Measurements a dpm/100 cm2 Frequency a dpm/100 cm2 22 1,020 52 307 Mean 27.34397 137 215 Standard Error 1.729556 315 21 Median 6.956522 500 9

Mode 0

2500 4

Standard Deviation 68.66141 5000 0

Sample Variance 4,714.389 More 0

Kurtosis 185.5194 1,576 Skewness 11.21100 Range 1398 Minimum 0

Maximum 1398 Sum 43,094.09 Count 1,576 Figure III-I below depicts the Alpha results from the Final Status Survey:

Alpha results 100%

90%

80%

70%

60%

50%

40%

30%

20%

10%

°"

22 52 137 314 500 2500 5000 M0<e Figure 111-1 Alpha Results from the Final Status Survey 14

DP-2605-0002, Final Status Survey Report for the American Centrifuge l ead Cascade Facility Decommissioning Project Revision O April 2018 Figure 111-2 below provides the Retrospective Power Curve which was developed using the data above:

V, QJ V,

V, ro c... -~

C 1.2 1

J 0.8 QJ

]

0.6 ro

-5 0.4

> -~

-f;l 0.2

.0 0....

c...

0 0

Power Curve {retrospective)

DCGL set at 5,000 dpm/100 cm m = 5 n = 15 Overall Std Dev= 68.689 500 1000 1500 2000 2500 3000 3500 4000 4500 5000 5500 dpm/100 cm 2 Figure 111-2 Retrospective Power Curve The curve above shows that a Survey Unit with less than 2,500 dpm/100 cm2 would almost always pass the criteria established and the data quality objectives of the Final Status Survey were easily achieved.

The maximum result was 1,398 dprn/100 cm2 alpha, and no survey points exceeded the LBGR; indicating a probability of passing of 99.97 percent for all measurements. Therefore, no further clean up or remediation of Lead Cascade spaces were indicated and the data indicates the Lead Cascade impacted areas meet the 10 CFR 20.1402 performance criteria of 25 mrem and the Lead Cascade License Application limits.

15

DP-2605-0002, Final Status Survey Report for the American Centrifuge Lead Cascade Facility Decommissioning Proj ect Revision O April 2018 Table III-2 below shows the distribution of beta measurements from the Final Status Survey:

Table 111-2 Distribution of Beta Measurements

~ dpm/100 cm2 Frequency

~ dpm/100 cm2 76 1,009 176 300 Mean 86.08230 364 192 Standard Error 3.472277 1,067 75 Median 14.52991 5,000 0

Mode 0

More 0

Standard Deviation 137.845 1,576 Sample Variance 19,001.37 Kurtosis 7.764477 Skewness 2.512507 Range 898.2906 Minimum 0

Maximum 898.2906 Sum 135,665.7 Count 1,576 Figure III-3 below depicts the Beta results from the Final Status Survey:

Beta Results 100%

90%

80%

7°"

60%

5°"

4°"

3°"

2°"

1°"

°"

76 176 364 1067 5000 More Figure 111-3 Beta Results from the Final Status Survey 16

DP-2605-0002, Final Status Survey Report for the American Centrifuge lead Cascade Facility Decommissioning Project Revision O April 2018 The beta results included 27 measurements taken on ceramic tiles in restrooms and change rooms in Class III areas. These were identified during the original baseline survey performed in 2004.

Average beta results for the ceramic tiles survey locations were 577 dpm/100 cm2* Therefore, while beta results were collected and evaluated. Only when the survey points alpha results were also elevated was any significance placed on the observed beta results.

20 ventilation system surveys were performed in the X-3001 building and the ventilation units supplying air to the X-7726 facility were surveyed. These surveys did not reveal elevated alpha or beta readings and removable contamination samples were all less than 20 dpm.

The eight floor drains to the "oily water" Liquid Effluent Collection (LEC) tanks in X-3001 building Utility Bay were surveyed. These surveys did not reveal elevated alpha or beta readings and removable contamination samples were all less than 20 dpm.

72 machine mounts in Trains 3 and 4 and 30 of the X-3001 building machine mounts in Train 6 of the X-3001 building were surveyed. These surveys included removable contamination sample of the drain and drain headers to the LEC tanks. These surveys did not reveal elevated alpha or beta readings and removable contamination samples were all less than 20 dpm.

In the Decommissioning Plan (DP-2605-0001), the Licensee committed to investigating survey locations exceeding 1,000 dpm/100 cm2 alpha-anomalous data. After reviewing the survey data, the Licensee performed additional measurements if a sample location indicated greater than two times the alpha Lo. These anomalous areas were:

X-3001 building, Train 3 one survey location indicated 332 dpm/100 cm2 alpha and 156 dpm/100 cm2 beta. This area was the location of a Test unit evaluating gas flows. The follow-up survey indicated roughly a 1 m2 area with (rounded) average alpha levels of 180 dpm/100 cm2 alpha and 85 dpm/100 cm2 beta. Removable contamination samples were less than 10 dpm. Since levels were significantly less than the Lead Cascade License Application limits, no further actions were taken.

X-7726 facility 2nd Floor Utility Room - one survey location that indicated 466 dpm/100 cm2 alpha and 742 dpm/100 cm2 beta. Inspection of the area revealed a discoloration on the cement floor due to an apparent oil spill. After cleaning the area, a follow-up survey of a 1 m2 area surrounding the elevated survey point indicated the (rounded) average levels were 104 dpm/100 cm2 alpha and 450 dpm/100 cm2 beta. Removable contamination samples were less than 10 dpm. It should be noted this area was not used during Lead Cascade operations and considered DOE legacy contamination. This was noted to be present after DOE equipment removal was performed in 2008. Residual contamination levels in the 2008 survey indicated levels were positive but less than the Posting levels stated in the Lead Cascade License Application.

During a scanning survey using the Floor Monitor, a peak count rate of 1,500 cpm was used as an action level. 1,500 cpm above background indicated the probability of exceeding 1,000 dpm/100 cm2 alpha or beta. When 1,500 cpm was observed, direct measurements were collected to quantify contamination levels.

17

DP-2605-0002, Final Status Survey Report for the American Centrifuge Lead Cascade Facility Decommissioning Project Revision O April 2018 There were six instances, within Class I areas, where the peak count action level was observed during a scan using the Floor Monitor. As shown in Table VI-3 of this report, the maximum levels recorded in the follow-up surveys were 1,398 dpm/100 cm2 alpha and 761 dpm/100 cm2 beta.

Average (rounded) contamination levels in these Class I areas were:

X-3001 building, Train 2 N Utility Bay Concrete Floor "Hot Spot"- 105 dpm/100 cm2 alpha and 119 dpm/100 cm2 beta.

X-3001 building, Train 3 N Utility Bay Concrete Floor "Hot Spot" - 360 dpm/100 cm2 alpha and 332 dpm/100 cm2 beta.

Data collected with the Floor Monitor indicated count rates were significantly less than the required scan MDC to reliably detect DCGLEMC levels of uranium alpha. As discussed within the Decommissioning Plan (DP-2605-0001), the DCGLEMC (assuming 5,000 dpm/100 cm2 rather than the revised DCGLw of 39,200 dpm/100 cm2) was estimated to be 24,963 dpm/100 cm2, which corresponds to an alpha scanning count rate of approximately 9,000 cpm with the Floor Monitor.

Since there was no evidence of exceeding 5,000 dpm/100 cm2, DCGLEMC evaluations were not performed.

IV. Changes in Final Status Survey Lower action levels or review levels were selected based on a review of incoming survey data. In addition, direct readings, as shown in Table VI-3, were taken in several areas (i.e., floor surfaces in the X-3001 building, Trains 1, 2, 5, 7, and 8; transfer corridors; and the X-3002 building) where the floor monitor was used.

V. Methods Used Review of the Licensee's survey data and data from the scoping surveys suggest that contamination at the Lead Cascade is localized and not "normally" distributed and contamination levels are expected to be significantly less than the revised DCGLw (or 39,200 dpm/100 cm2).

Therefore, 5,000 dpm/100 cm2 alpha was used as the basis for the Final Status Survey. This aligns with commitments made within Chapter 4.0 of the Lead Cascade License Application.

Using MARSSIM criteria (formula 5-1) the minimum number of sample locations to ensure that any elevated areas of contamination would be identified and sufficient data was obtained for statistical analysis in the Survey Unit are shown in the following Table V-1. This table was developed using the X-3001 building Utility Bay Scoping Survey data performed in 2015.

As discussed within Section XIV.a of the Decommissioning Plan, adjusting the LBGR to roughly 85 percent of the survey basis (5,000 dpm/100 cm2 versus the revised DCGLw of 39,200 dpm/100 cm2) would indicate 12 to 15 sample locations would be required. Based upon this information, the Radiation Protection Manager selected 15 samples locations, which is in line with the statistical approach used during the 2004 baseline survey to estimate the average contamination levels in the GCEP facilities. Therefore, the minimum number of sample locations was set to 15.

18

DP-2605-0002, Final Status Survey Report for the American Centrifuge l ead Cascade Facility Decommissioning Project Revision O April 2018 VI. Summary of Values A scoping survey performed shortly after the Lead Cascade was shut down in 2015 served as the basis to design the Final Status Survey. The Scoping Survey evaluated areas at the Lead Cascade most likely to contain residual contamination. Data from the X-3001 Utility Bay showed the highest standard deviation (28.67) and was used to determine the minimum number of data points for a WRS test.

Setting the LBGR to 50 percent of the alpha count rate expected for 5,000 dpm/100 cm2 yielded a value of nine sample locations refer to Table VI-1 below. The sample size calculation for N includes a 20 percent factor for overall uncertainty. Based on the Radiation Protection Manager's judgment, 15 data points was selected as the minimum number of data points for a Survey Unit.

For a large area such as Train 3 of the X-3001 building in which four Survey Units were performed, 59 samples would provide with 95 percent confidence that at least 95 percent of the population lies at or below the maximum value.

Table VI-1 Sample Size Determination DCGLw 410 cpm for 5,000 dpm a LBGR 205 Set to 50 percent of DCGLw

13.

205 X-3001 Utility Bay StdDev 28.67 Scoping Survey Data Ncr 7.1 5 Relative Shift Pr 1.000000 Probability Table 5.1 - Utility Bay Z1-a 1.645 a and B = 0.05 Table 5.2 Z1-B 1.645 a and B = 0.05 Table 5.2 Z 1-a 1.96 a and B = 0.025 Table 5.2 Z1-B 1.96 a and B = 0.025 Table 5.2 N(o.o5) 17 Scoping Survey Data N<0.025,0.05) 21 Scoping Survey Data nco 05) 9 Scoping Survey Data nco 025,0 05) 10 Scoping Survey Data 19

DP-2605-0002, Final Status Survey Report f or the American Centrifuge l ead Cascade Facility Decommissioning Proj ect Revision O April 2018 To determine if enough survey points were collected, each survey with data collected with the Ludlum 2224 was evaluated using MARSSIM criteria (formula 5-1). Table VI-2 below provides a summary of the survey unit evaluation which includes the WRS evaluation.

Each WRS evaluation is provided with the Final Status Surveys contained within Appendix B of this report.

Class I survey units which passed the criteria of the 100 percent scan and additional data points collected when an individual reading exceeded two times the Lo are not included in Table VI-2.

This data is discussed within Section IV.a of this report.

Table VI-3 below provides a summary of the follow-up surveys completed for the Class I survey units as well as the areas noted within Table VI-2 which exceeded two times the Lo.

20

DP-2605-0002, Final Status Survey Report for the American Centrifuge lead Cascade Facility Decommissioning Project Revision 0 Table VI-2 Statistical Evaluation of Systematic Survey Units Ave Max Max Location Pts SD a Ave p p

Ala P,

N(o.os)

N (o.025,o.o5J (l

(l X-3001 Train 1 Auxiliary Standby Generator (ASG) 1/2 15 21.9 24.6 80.2 28.3 218.8 8.3 1.000000 17.3 20.8 X-3001 Train 1 Utility Bay 1st Floor Area 15 18.7 22.1 67.2 37.2 154.3 9.3 1.000000 17.3 20.8 X-300 I N Utility Bay, West Stairwell 25 37.3 31.9 102.2 0.1 1.7 6.4 1.000000 17.3 20.8 X-300 I Train I Mezzanine Floor 20 85.8 46.5 180.9 65.3 168.9 4.4 1.000000 17.3 20.8 X-3001 Train l Cascade Floor 15 44.7 32.6 95.1 37.4 128.2 6.3 1.000000 17.3 20.8 X-3001 Train 2 N Utility Bay-1 18 26.1 23.0 77.8 31.6 154.0 8.9 1.000000 17.3 20.8 X-3001 Train 2 N Utility Bay-2 15 26.8 23.2 66.5 13.4 101.7 8.8 1.000000 17.3 20.8 X-3001 Train 2 N Utility Bay I st Floor Walls 19 23.0 30.4 97.1 99.7 507.7 6.7 1.000000 17.3 20.8 X-3001 Train 2 N Utility Bay Equipment Pads 15 49.4 40.9 140.6 1.1 14.5 5.0 1.000000 17.3 20.8 X-3001 Train 2 Cascade 15 84.3 41.7 146.1 102.8 197.3 4.9 1.000000 17.3 20.8 X-3001 Train 2 Mezzanine Walls 15 24.3 16.7 55.7 88.3 140.5 12.2 1.000000 17.3 20.8 X-3001 Train 2 Mezzanine Floor 15 33.5 32.8 95.1 17.9 111.3 6.2 1.000000 17.3 20.8 X-300 l Train 3-1

15 23.9 85.4 332.3 23.8 156.4 2.4 0.944167 21.9 26.3 X-3001 Train 3-2 15 26.6 22.1 69.0 57.5 299.1 9.3 1.000000 17.3 20.8 X-300 I Train 3-3 15 24.7 23.7 71.6 58.6 138.5 8.7 1.000000 17.3 20.8 X-3001 Train 3-4 15 10.4 15.9 56.2 53.6 348.7 12.9 1.000000 17.3 20.8 21 April 2018 Survey n(0.05) n(0.025,0.05)

Points Acceptable 9

10 Yes 9

10 Yes 11 13 Yes 9

10 Yes 9

10 Yes

DP-2605-0002, Final Status Survey Report for the American Centrifuge lead Cascade Facility Decommissioning Project Revision 0 Table VI-2 Statistical Evaluation of Systematic Survey Units Ave Max Max Location Pts SD a Ave P p

Al<J P,

N(o.osJ N (o.02s,o.osJ (l

(l X-3001 Train 3 Utility Bay-I 15 27.8 24.3 86.9 8.8 53.8 8.4 1.000000 17.3 20.8 X-3001 Train 3 Utility Bay-2 15 34.0 31.9 109.4 13.4 99.8 6.4 1.000000 17.3 20.8 X-3001 Train 3 Utility Bay-3 Discretionary 15 59.8 47.6 163.6 402.5 898.3 4.3 1.000000 17.3 20.8 X-3001 Train 3 Utility Bay 1st Floor Walls 25 36.1 36.7 150.8 178.3 641.0 5.6 1.000000 17.3 20.8 X-3001 Train 3 Utility Bay Equipment Pads 16 44.3 34.1 115.0 2.9 43.6 6.0 1.000000 17.3 20.8 X-300 I Train 3 Mezzanine Walls 15 39.4 26.0 90.0 67.2 229.3 7.9 1.000000 17.3 20.8 X-3001 Train 3 Mezzanine Floor 15 46.7 20.1 88.1 35.9 125.1 10.2 1.000000 17.3 20.8 X-3001 Train 4-1 16 33.7 31.5 81.8 43.6 159.8 6.5 1.000000 17.3 20.8 X-300 I Train 4-2 16 12.3 24.1 81.8 7.4 61.5 8.5 1.000000 17.3 20.8 X-3001 Train 4-3 16 9.1 16.9 48.6 21.6 141.8 12.1 1.000000 17.3 20.8 X-3001 Train 4-4 16 1.5 4.2 12.2 37.3 146.2 49.4 1.000000 17.3 20.8 X-3001 Train 4 Utility Bay Equipment Pad 15 17.2 16.6 46.2 0.0 0.0 12.3 1.000000 17.3 20.8 X-3001 Train 4 Diesel Generator Room 3/4 15 29.2 31.4 72.9 114.7 231.9 6.5 1.000000 17.3 20.8 X-3001 East Stairwel l 25 8.5 11.5 41.7 0.7 12.3 17.9 1.000000 17.3 20.8 X-3001 Train 4 N Utility Bay Floor Area 18 56.7 22.5 109.0 130.1 284.0 9.1 1.000000 17.3 20.8 X-3001 Train 4 N Utility Bay-2 15 38.5 32.0 107.3 45.6 115.4 6.4 1.000000 17.3 20.8 22 April 2018 Survey n(0.05) n(0.025,0.05)

Points Acceptable 9

10 Yes 9

10 Yes

DP-2605-0002, Final Status Survey Report for the American Centrifuge l ead Cascade Facility Decommissioning Project Revision 0 Table VI-2 Statistical Evaluation of Systematic Survey Units Ave Max Max Location Pts SD a Ave p p

Ala Pr Nco.os)

N co.02s,o.os) a a

X-3001 Train 4 Mezzanine Floor 15 36.3 24.7 88.1 63.7 158.2 8.3 1.000000 17.3 20.8 X-3001 Train 5 Floor 15 9.4 16.4 51.1 33.3 140.9 12.5 1.000000 17.3 20.8 X-3001 Train 6-1 15 66.5 39.9 126.4 23.0 95.4 5.1 1.000000 17.3 20.8 X-3001 Train 6-2 18 35.6 37.5 153.0 32.1 167.4 5.5 1.000000 17.3 20.8 X-3001 Train 6-3 16 2.7 7.5 21.9 41.3 308.1 27.4 1.000000 17.3 20.8 X-3001 Train 6-4 18 24.3 24.2 85.8 5.3 38.4 8.5 1.000000 17.3 20.8 X-3001 Train 7 Cascade Floor Directs 15 34.4 25.6 80.2 6.3 60.4 8.0 1.000000 17.3 20.8 X-3001 Train 8 Floor 15 16.2 20.9 60.8 22.8 142.7 9.8 1.000000 17.3 20.8 X-3001 Transfer Corridor 25 45.7 22.2 102.1 75.6 296.7 9.2 1.000000 17.3 20.8 X-3012 Transfer Corridor-I 15 42.1 27.8 90.0 102.4 222.3 7.4 1.000000 17.3 20.8 X-3012 Maintenance Shop-I 17 7.8 13.4 39.4 0.7 11.5 15.2 1.000000 17.3 20.8 X-3012 Maintenance Shop-2 17 1.9 6.8 27.8 2.6 26.1 30.3 1.000000 17.3 20.8 X-3012 Maintenance Shop-3 17 4.0 10.5 37.1 16.4 162.0 19.5 1.000000 17.3 20.8 X-3012 Maintenance Shop-4 15 4.3 10.6 39.4 14.3 72.2 19.3 1.000000 17.3 20.8 X-3012 Maintenance Shop Walls 25 3.3 14.8 74.2 89.5 480.6 13.8 1.000000 17.3 20.8 X-3002 Transfer Corridor 25 13.4 18.4 62.6 5.2 65.3 11.2 1.000000 17.3 20.8 X-3002 Train 4-1 15 3.6 7.0 25.5 25.0 117.5 29.3 1.000000 17.3 20.8 23 April 2018 Survey n(0.05) n(0.025,0.05)

Points Acceptable 9

10 Yes 9

10 Yes

DP-2605-0002, Final Status Survey Report for the American Centrifuge lead Cascade Facility Decommissioning Project Revision 0 Table VI-2 Statistical Evaluation of Systematic Survey Units Ave Max Max Location Pts SD a Ave p p

A/CJ P,

N(o.osJ N co.025,o.o5J (l

(l X-3002 Train 4-2 15 6.5 12.9 37.1 30.4 148.2 15.9 1.000000 17.3 20.8 X-7727H Transfer Corridor 25 48.5 28.5 109.0 61.9 236.5 7.2 1.000000 17.3 20.8 X-7725 Rm 161 15 2.9 10.5 40.9 18.8 88.9 19.5 1.000000 17.3 20.8 X-7725 Rm 162 16 18.7 31.8 92.0 0.0 0.0 6.4 1.000000 17.3 20.8 X-7725 Rm 161 Walls 18 5.3 11.2 32.5 35.7 208.1 18.3 1.000000 17.3 20.8 X-7725 BSA-1 15 10.7 18.7 67.2 0.6 9.2 10.9 1.000000 17.3 20.8 X-7725 BSA-2 15 0.0 0.0 0.0 6.5 97.5 205.0 1.000000 17.3 20.8 X-7725 BSA-3 15 1.2 3.3 9.3 9.9 109.0 62.8 1.000000 17.3 20.8 X-7725 BSA-4 19 0.0 0.0 0.0 0.6 12.3 205.0 1.000000 17.3 20.8 X-7725 Rm 373 27 11.9 9.8 41.7 337.2 522.8 18.2 1.000000 17.3 20.8 X-7725 1st Off, Break,

& Locker Rooms 25 9.2 14.2 55.7 293.3 826.9 14.4 1.000000 17.3 20.8 X-7725 2nd Floor Offices 25 21.2 24.4 100.0 317.5 551.2 8.4 1.000000 17.3 20.8 X-7725 3rd Floor Offices 25 3.4 7.5 22.0 203.1 347.3 27.4 1.000000 17.3 20.8 X-3012 North Offices/ Area Control Room 25 19.9 24.7 104.3 18.7 467.6 8.3 1.000000 17.3 20.8 X-3012 1st Floor Offices/Break Rm/Locker 25 10.9 18.1 58.5 204.3 607.8 11.3 1.000000 17.3 20.8 X-3012 2 11d Floor Mezzanine Offices 15 6.2 11.3 32.5 6.3 94.4 18.1 1.000000 17.3 20.8 X-7726 2nd Floor Offices-Security 15 33.2 42.2 143.9 250.4 498.5 4.9 1.000000 17.3 20.8 24 April 20/8 Survey nco.05) ll(0.025,0.05)

Points Acceptable 9

10 Yes 9

10 Yes

DP-2605-0002, Final Status Survey Report for the American Centrifuge lead Cascade Facility Decommissioning Project Revision 0 Table VI-2 Statistical Evaluation of Systematic Survey Units Ave Max Max Location Pts SD a Ave 13 13 Ma Pr N(o.os)

N(o.02s,o.os)

(l (l

X-7726 3rd Floor Offices-Engineering 17 5.6 9.7 34.1 207.7 377.6 21.2 1.000000 17.3 20.8 X-7726 Oil Drain Area 15 5.3 15.7 58.4 38.8 223.2 13.0 1.000000 17.3 20.8 X-7726 Level I Cage 9

5.7 17.1 51.2 84.6 294.6 12.0 1.000000 17.3 20.8 X-7726 Level I (I & 2) 50 0.5 2.3 I 1.6 48.3 321.7 89.3 1.000000 17.3 20.8 X-7726 Level 2 18 5.7 11.1 39.4 52.2 122.8 18.4 1.000000 17.3 20.8 X-7726 Level 2 Mezzanine 19 4.9 9.2 30.1 177.2 294.8 22.2 1.000000 17.3 20.8 X-7726 Level 2 Build Stand Walls 15 18.9 22.6 76.5 103.9 386.9 9.1 1.000000 17.3 20.8 X-7726 Level 3 15 5.7 10.6 29.3 1.2 18.5 19.4 1.000000 17.3 20.8 X-7726 Level 4 15 14.7 19.8 58.0 106.7 259.5 10.3 1.000000 17.3 20.8 X-7726 Level 5 15 24.0 17.2 46.4 125.1 209.6 11.9 1.000000 17.3 20.8 X-7726 Level 6 / 6.5 15 13.1 20.0 58.0 125.4 195.8 10.2 1.000000 17.3 20.8 X-7726 Level 7 16 0.6 I. I 2.4 187.5 396.5 188.5 1.000000 17.3 20.8 X-7726 Level 7 Build Stand Walls 15 0.0 0.0 0.0 87.8 222.6 205.0 1.000000 17.3 20.8 X-7726 Level 7 Catwalk 15 15.5 16.8 58.0 143.3 238.0 12.2 1.000000 17.3 20.8 X-7726 Stairwell 25 6.7 14.4 51.2 115.6 293.7 14.2 1.000000 17.3 20.8 X-7726 DOE Room Floor 20 9.3 22.1 87.8 127.7 372.7 9.3 1.000000 17.3 20.8 X-7726 DOE Room Walls 10 2.0 4.6 14.6 144.4 315.1 44.9 1.000000 17.3 20.8 X-7726 Personal Spaces 25 27.5 33.2 100.0 205.5 728.8 6.2 1.000000 17.3 20.8 X-7726 2nd Floor Utility Rm*

25 32.1 96.5 466.1 126.6 742.4 2.1 0.921319 24.4 29.3 25 April 2018 Survey n(0.05) n(0.025,0.05)

Points Acceptable 9

10 Yes 9

IO Yes 9

10 Yes 9

10 Yes 12 15 Yes

DP-2605-0002, Final Status Survey Report for the American Centrifuge lead Cascade Facility Decommissioning Project Revision 0 April 2018 Table VI-2 Statistical Evaluation of Systematic Survey Units Ave Max Max Survey Location Pts SD a Ave p p

Ma Pr N(o.os>

N(o.02s,o.os>

nco.OS) n(0.025,0.05)

Points (l

(l Acceptable

Follow-up surveys required for I m2 area at the data point exceeding two times Lo. See Table Vl-3 for those results.

Table VI-3 Follow-up Surveys Location Pts Ave a SD a Max a Ave I}

Max I}

Discussion X-3001, Train 2 N Utility Bay Concrete Floor "Hot Spot" - Class I Directs**

17 I 05.1 118.9 488.0 119.2 269.0 Survey taken after I 00% scan of area.

X-3001, Train 3 N Utility Bay Concrete Floor "Hot Spot" - Class I Directs *

15 359.7 454.1 1,398.0 332.1 761.0 Survey taken after 100% scan of area.

X-3001, Post Decon Train 3-1 follow-up (1 Survey of a 1 m2 area when exceeding two m2) of Survey Point 14 18 179.7 141.0 421.7 86.5 347.0 times Lo.

X-7726 Post Decon 2nd Floor Utility Room Survey of a 1 m2 area when exceeding two follow-up ( 1 m2) 9 103.5 109.5 361.0 449.8 744.4 times Lo.

- Combines all direct readings from survey data 26

DP-2605-0002, Final Status Survey Report f or the American Centrifi1ge l ead Cascade Facility Decommissioning Project Revision O April 2018 VI.a Elevated Results Discussion When a direct measurement indicated greater than two times the Lo (or MDA) or if greater than a count rate of 1,500 cpm was observed when using the Floor Monitor, an additional survey was performed with the Ludlum 2224 to quantify levels in the area. During the course of the Final Status Survey, there were six occurrences that were greater than 1,500 cpm and two areas greater than two times the Lo. Final follow-up surveys were performed to confirm residual contamination in these areas were less than the Lead Cascade License Application limits. These findings are discussed below.

The X-3001 building, Train 2 N Utility Bay Concrete Floor "Hot Spot" - Class I survey unit:

Prior to remediation, the average levels were 102 dpm/100 cm2 alpha and 210 dpm/100 cm2 beta; maximum 345 dpm/100 cm2 alpha and 1,044 dpm/100 cm2 beta.

After remediation, one indication of greater than 1,500 cpm was observed when scanning with the Floor Monitor. Survey of this location indicated 488 dpm/100 cm2 alpha and 71 dpm/100 cm2 beta.

The area was placed on Quarterly Routine Survey frequency, systematic survey of entire 9 m2 area on February 22, 2018 indicated average levels were 81 dpm/100 cm2 alpha and 122 dpm/100 cm2 beta; maximum levels were 285 dpm/100 cm2 alpha and 269 dpm/100 en/ beta.

Combining the two follow-up surveys indicates the Train 2 N Utility Bay Concrete Floor "Hot Spot" - Class I area average levels were l 05 dpm/100 cm2 alpha and 119 dpm/100 cm2 beta; maximum levels (rounded) were 488 dpm/100 cm2 alpha and 269 dpm/100 cm2 beta.

The X-3001 building, Train 3 N Utility Bay Concrete Floor "Hot Spot" - Class I survey unit:

Prior to remediation, an equipment pad indicated greater than 5,000 dpm/100 cm2, which was removed and appropriately disposed.

After remediation, a survey performed prior to 100 percent scan indicated average levels were 415 dpm/100 cm2 alpha and 303 dpm/100 cm2 beta; maximum levels were 1,022 dpm/100 cm2 alpha and 604 dpm/100 cm2 beta.

100 percent scan with the Floor Monitor indicated five locations greater than 1,500 cpm.

Average results for these five locations were 791 dpm/100 cm2 alpha and 530 dpm/100 cm2 beta; maximum results were 1,398 dpm/100 cm2 alpha and 666 dpm/100 cm2 beta.

This area was place on Quarterly Routine Survey frequency, systematic survey of 10 ft2 area on February 22, 2018 indicated average levels were 144 dpm/100 cm2 alpha and 233 dpm/100 cm2 beta; maximum levels were 587 dpm/100 cm2 alpha and 761 dpm/100 cm2 beta.

Combining the two follow-up surveys indicates the Train 3 N Utility Bay Concrete Floor "Hot Spot" - Class I area average levels (rounded) were 360 dpm/100 cm2 alpha and 322 dpm/100 cm2 beta; maximum levels were 1,398 dpm/100 cm2 alpha and 761 dpm/100 cm2 beta.

27

DP-2605-0002, Final Status Survey Report for the American Centrifuge l ead Cascade Facility Decommissioning Project Revision O April 2018 Follow-up surveys of the X-3001 building, Train 3-1 area which indicated greater than two times the Lo:

18 readings were taken in a 1 m2 area surrounding the elevated reading. Average results (rounded) were 180 dprn/100 cm2 alpha and 86 dpm/100 cm2 beta.

Since this area was the location of a special testing unit, a scan of the X-3001 building, Train 3, Cascade 2 was performed using the floor monitor with no indication greater than 1,500 cpm. This scan also included a 100 percent scan at the location of the Feed Cart.

A scan of the floor spaces of Cascade 1 (the location of 240 machine Demonstration Cascade) was also made. Results of this scan were less than 100 cprn.

Follow-up surveys of the X-7726 facility 2nct Floor Utility Room area which indicated greater than two times the Lo:

Inspection of the area indicated discoloration of the concrete. The area was cleaned with a solution of vinegar and baking soda. Initial alpha count rate immediately after cleaning were less than 20 cpm, however elevated beta still existed. There was no documentation of this survey as the area was still moist. The Licensee's experience with this cleaning indicated a three-day wait was appropriate.

Three days later, 9 additional readings were collected in a 1 m2 area at the location of the highest reading. Average results (rounded) were 104 dpm/100 cm2 alpha and 450 dprn/100 cm2 beta.

VII. Survey Results Each of the Final Status Surveys performed (See Appendix B within this report) depict:

The number of samples taken for the survey unit.

A description of the survey unit, including a map or drawing of the survey unit showing the reference system and random start systematic sample locations for Class II survey units for areas greater than 200 m2.

Class I survey uni ts were 100 percent scanned and direct measurement collected when observed count rate exceeded 1,500 cpm. Class III survey locations were selected based on HP Technicians knowledge of the areas.

The measured sample concentrations in units dprn/100 cm2*

Table VI-2 of this report provides a summary of the survey unit evaluation which requires the WRS evaluation. A WRS statistical evaluation of the measured concentrations 1s provided with the Final Status Surveys contained within Appendix B of this report.

Additionally, each survey provides:

28

DP-2605-0002, Final Status Survey Report for the American Centrifuge Lead Cascade Facility Decommissioning Project Revision O April 2018 The WRS evaluation sheets indicating that a given survey unit satisfied the DCGLw. Since no measurements exceeded 5,000 dpm/100 cm2, an elevated measurement comparison was not deemed necessary.

A discussion of anomalous data is provided within Section III of this report. These included a discussion of results of any areas of elevated direct radiation detected during scanning which exceeded the investigation level. There were no measurement locations in excess of the DCGLw.

Table VII-1 below provides a summary of the results obtained during the Final Status Survey effort.

29

DP-2605-0002, Final Status Survey Report for the American Centrifuge Lead Cascade Facility Decommissioning Project Revision 0 Table VII-1 Summary of the Lead Cascade Final Status Survey Results Bldg Area Sub Area ID Survey Survey Notes Survey Location Class Date Pts.

X-3001 Train 1 N Utility ASG 112 Class III 1211312017 Included interior walls; 15 Bay smears < 1 0 dpm X-3001 Train I N Utility 1st Floor Area Class II 12/1512017 Concrete floor; smears <

15 Bay 10 dpm X-3001 Train 1 N Utility Columns Class II 12/1412017 Metal 9

Bay N Utility Removable X-3001 Train 1 Floor Drains Class II 1211412017 contamination; samples <

2 Bay 10 dpm X-3001 Train I N Utility West Stairwell Class II 12/1912017 Included wall data points; 25 Bay smears < IO dpm X-3001 Train I Train Train 1 Class II 11412018 15 random data readings; 15 Cascade smears < 10 dpm X-3001 Train 1 Train Train 1-1 Class II 11412018 50% Scan; < 1,500 cpm NIA X-3001 Train 1 Train Train 1-2 Class II 11412018 50% Scan; < 1,500 cpm NIA X-3001 Train 1 Train Train 1-3 Class II 11412018 50% Scan; < 1,500 cpm NIA X-3001 Train I Train Train 1-4 Class II 1/412018 50% Scan; < 1,500 cpm NIA X-3001 Train 1 Train Columns Class II 1/412018 Metal 15 N Utility Mezzanine Concrete floor, includes 5 X-3001 Train I Floor and Class III 11212018 columns; smears < 10 20 Bay Columns dpm N Utility Heating &

Units 3001-1242A & L-X-3001 Train 1 Venti lation Class III 11312018 NIA Bay Units 11448; smears< 10 dpm 30 April 2018 Ave a Ave p Max a Maxp 22 28 80 219 19 37 67 154

<200

<700

<400

<5,000 NIA NIA

<400

<5,000 37 0

102 2

45 37 95 128 NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA

<200

<700

<400

<5,000 86 65 181 169 NIA NIA

<400

<5,000

DP-2605-0002, Final Status Survey Report for the American Centrifuge Lead Cascade Facility Decommissioning Project Revision 0 Table VII-1 Summary of the Lead Cascade Final Status Survey Results Bldg Area Sub Area ID Survey Survey Notes Survey Location Class Date Pts.

Concrete 100% scan 1 location >

X-3001 Train 2 N Utility Floor "Hot Class I 1/912018 1,500 cpm; results <

I Bay Spot" 5,000 dpml l 00 cm2; smears < IO dpm Concrete Systematic survey of X-3001 Train 2 N Utility Floor "Hot Class I 212212018 Class I area (3001 -Q-16 Bay Spot" follow-UB2HS) (9 m2 area) up N Utility I st Floor Mixed media (concrete, X-3001 Train 2 Bay Walls Class II 1113012017 metal, and drywall);

19 smears < 1 0 dpm N Utility All removable X-3001 Train 2 Floor Drains Class II 1211312017 contamination; smears <

2 Bay 10 dpm X-3001 Train 2 N Utility Mezzanine Class II 1212012017 Concrete Floor; smears <

15 Bay Floor 10 dpm X-3001 Train 2 N Utility Mezzanine Class II 1212012017 Metal walls; smears < I 0 15 Bay Walls dpm X-3001 Train 2 N Utility Train 2 Utility Class II 11/1712017 Concrete Floor; smears <

18 Bay Bay-I 10 dpm X-3001 Train 2 N Utility Train 2 Utility Class II 11/1712017 Concrete Floor; smears <

15 Bay Bay-2 10 dpm X-3001 Train 2 N Utility Equipment Class II 12/1312017 Concrete; smears < 10 15 Bay Pads dpm X-3001 Train 2 N Utility Floor Cracks Class II 1112712017 Spot check of cracks in 22 Bay floor 31 April 2018 Ave a Avep Max a Maxp NIA NIA 486 71 81 122 285 269 23 100 97 508 NIA NIA

<400

<5,000 34 18 95 111 24 88 56 140 26 32 78 154 27 13 66 102 49 I

141 15 NIA NIA

<400

<5,000

DP-2605-0002, Final Status Survey Report for the American Centrifuge l ead Cascade Facility Decommissioning Proj ect Revision 0 Table VII-1 Summary of the Lead Cascade Final Status Survey Results Bldg Area Sub Area ID Survey Survey Notes Survey Location Class Date Pts.

N tility Heating &

Surveys of Units X-3001-X-3001 Train 2 Ventilation Class II 1/812018 L-1144G & X-3001 -L-2 Bay Units 1242-B; smears < 10 dpm X-3001 Train 2 Train Train 2 Class II 11312018 15 random data readings 15 Cascade in Train 2 X-3001 Train 2 Train Train 2-1 Class II 11312018 50% Scan; < 1,500 cpm NIA X-3001 Train 2 Train Train 2-2 Class II 11312018 50% Scan; < 1,500 cpm NIA X-3001 Train 2 Train Train 2-3 Class II 11312018 50% Scan; < 1,500 cpm NIA X-3001 Train 2 Train Train 2-4 Class II 11312018 50% Scan; < 1,500 cpm NIA X-3001 Train 2 Train Columns Class II 12/1212017 Metal 17 Concrete 1 00% scan 5 locations >

X-3001 Train 3 N Utility Floor "Hot Class I 119120 I 8 1,500 cpm; all results <

5 Bay 5,000 dpm/100 cm2; Spot" smears < 10 dpm Concrete Systematic survey of X-3001 Train 3 N Utility Floor "Hot Class I 212212018 Class 1 area(3001 -Q-10 Bay Spot" follow-UB3HS) (10 ft2 area) up N Utility 1st Floor Mixed media (concrete, X-3001 Train 3 Bay Walls Class II 12/1 I 12017 metal, and drywall);

25 smears < 10 dpm N Utility Removable X-3001 Train 3 Floor Drains Class II 12/1312017 contamination; samples <

2 Bay 10 dpm X-3001 Train 3 N Utility Mezzanine Class II 1212112017 Concrete Floor; smears <

15 Bay Floor 10 dpm X-3001 Train 3 N Utility Mezzanine Class II 1212012017 Metal walls; smears < 10 15 Bay Walls dpm.

32 April 2018 Ave a Ave p Max a Maxp NIA NIA

<400

<5,000 84 103 146 197 NIA IA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA

<400

<5,000 791 530 1,138 666 144 587 233 761 36 178 151 641 NIA IA

<400

<5,000 47 36 88 125 39 67 90 229

DP-2605-0002, Final Status Survey Report for the American Centrifuge Lead Cascade Facility Decommissioning Project Revision 0 Table VII-1 Summary of the Lead Cascade Final Status Survey Results Bldg Area Sub Area ID Survey Survey Notes Survey Location Class Date Pts.

X-3001 Train 3 N

ti lity Overhead Class II 12/12120 17 29 locations; smears < 10 29 Bay dpm X-3001 Train 3 Utility Equipment Class II 1113012017 Concrete; smears < I 0 16 Bay Pads dpm X-3001 Train 3 N Utility Uti lity Bay-I Class II 121512017 Concrete Floor; smears <

15 Bay 10 dpm X-3001 Train 3 N Utility Uti lity Bay-2 Class II 121512017 Concrete floor; smears <

15 Bay 10 dpm Restrooms, closets, etc.

X-3001 Train 3 N Utility Utility Bay-3 Class II 121612017 Mixed media (concrete, 15 Bay Discretionary metal, and drywall);

smears < IO dpm X-3001 Train 3 N Utility Columns Class II 12/1812017 Metal; smears < 10 dpm 9

Bay X-300 I Train 3 N Utility Floor Cracks Class II 121612017 Spot check of cracks in 29 Bay floor; smears < IO dpm Survey Complete; Units X-300 l-L-1 I 44M, X-3001 -L-l 144N, X-3001 -

Utility Heating &

L-11440, X-3001 -L-X-3001 Train 3 Ventilation Class II 1111/2018 1144P, X-3001-L-l 144R, 8

Bay Units X-300 I-L-I I 44Q, X-3001-1242C, & X-3001-214 1 C; Alpha Smears <

10 dpm 33 April 2018 Ave a Ave p Max a Maxp NIA NIA

<400

<5,000 44 115 44

.)

28 9

87 54 34 13 109 100 60 402 164 898 NIA NIA

<400

<5,000

<200

<700

<400

<5,000 IA NIA

<400

<5,000

DP-2605-0002, Final Status Survey Report for the American Centrifuge Lead Cascade Facility Decommissioning Project Revision 0 Table VII-1 Summary of the Lead Cascade Final Status Survey Results Bldg Area Sub Area ID Survey Survey Notes Survey Location Class Date Pts.

4-foot section remains X-3001 Roof IA Roof Vent Class II 10/1612017 in place; Internal 2

Area removable alpha levels 64 dpml lOO cm2 Consisted of 5 separate Machine surveys; 60 Machine X-3001 Train 3 Train Mount Wells Class II 11 121/2017 mounts and 12 drain 72 and Drains headers; smears < 10 dpm alpha Concrete floor. One X-3001 Train 3 Train Train 3-1 Class II 11 121 12017 reading > 2* LD; smears <

15 10 dpm Post Decon Additional measurements X-3001 Train 3 Train Train 3-1 Class II 11 12212017 of 1 m2 area with elevated 18 follow-up reading X-3001 Train 3 Train Train 3-2 Class II 121412017 Concrete floor; smears<

15 10 dpm X-3001 Train 3 Train Train 3-3 Class II 11 12812017 Concrete floor; smears <

15 10 dpm X-3001 Train 3 Train Train 3-4 Class II 1112912017 Concrete floor; smears <

15 10 dpm X-3001 Train 3 Train Columns Class II 12/1212017 Metal 17 N Utility Diesel Included wall locations; X-3001 Train 4 Generator Class Ill 121812017 15 Bay Room 314 smears < IO dpm Included walls of X-3001 Train 4 N Utility East Stairwell Class Ill 12/1912017 stairwel l 25 random 25 Bay locations; smears < 1 0 dpm 34 April 2018 Ave a Ave p Max a Maxp

<200

<700

<400

<5,000 NIA NIA

<400

<5,000 24 24 332 156 253 180 327 422 27 58 69 299 24 59 72 138 10 54 56 349

<200

<700

<400

<5,000 29 115 73 232 9

1 42 12

DP-2605-0002, Final Status Survey Report for the American Centrifuge Lead Cascade Facility Decommissioning Project Revision 0 Table VII-1 Summary of the Lead Cascade Final Status Survey Results Bldg Area Sub Area ID Survey Survey Notes Survey Location Class Date Pts.

X-3001 Train 4 N Utility Floor Area Class II 121812017 Surveys complete; smears 18 Bay-I

< 10 dpm X-3001 Train 4 N Utility Floor Area Class II 121812017 Surveys complete; smears 15 Bay-2

< 10 dpm X-3001 Train 4 N Utility Columns Class II 12/1812017 Metal; smears < 10 dpm 9

Bay X-3001 Train 4 N Utility Floor Drains Class II 12/1312017 Smears < IO dpm 2

Bay X-3001 Train 4 N Utility Mezzanine Class II 1212212017 Concrete plus columns; 15 Bay Floor smears< 10 dpm X-3001 Train 4 N Utility Equipment Class II 1211812017 Concrete; smears < 1 0 15 Bay Pads dpm Consisted of 5 separate Machine surveys; 60 Machine X-3001 Train 4 Train Mount Wells Class II 12/1212017 mounts and 12 drain 72 headers; smears < 10 dpm alpha Survey Complete. Units X-3001-L-l 144S, X-3001 -L-l 144T, X-3001-North Heating &

L-1144U, X-3001 -L-X-3001 Train 4 Uti lity Ventilation Class II 1/11/2018 1144V, X-3001 -L-8 Bay Units 1 144 W, X-3001 -L-I 144X, X-3001-1242D, and X-3001-2141D; smears < IO dpm X-3001 Train 4 Train Train 4-1 Class II 12/712017 Concrete floor; smears <

16 10 dpm 35 April 2018 Ave a Ave p Max a Maxp 57 130 109 284 39 46 107 115 NIA NIA

<400

<5,000 NIA NIA

<400

<5,000 36 64 88 158 17 0

46 0

NIA NIA

<400

<5,000 NIA IA

<400

<5,000 34 44 82 160

DP-2605-0002, Final Status Survey Report for the American Centrifuge lead Cascade Facility Decommissioning Project Revision 0 Table VII-1 Summary of the Lead Cascade Final Status Survey Results Bldg Area ub Area ID Survey Survey Notes Survey Location Class Date Pts.

X-3001 Train 4 Train Train 4-2 Class II 12/712017 Concrete floor; smears <

16 10 dpm X-3001 Train 4 Train Train 4-3 Class II 12/712017 Concrete floor; smears <

16 10 dpm X-3001 Train 4 Train Train 4-4 Class II 12/712017 Concrete floor; smears <

16 10 dpm X-3001 Train 4 Train Columns Class II 12/1312017 Metal 16 Cascade Floor Concrete 15 random X-3001 Train 5 Train Directs Class II 1/1712018 readings; smears < 10 15 dpm alpha X-3001 Train 5 Train Train 5-1 Class II 1/1712018 50% Scan; < 1,500 cpm NIA X-3001 Train 5 Train Train 5-2 Class II 1/1712018 50% Scan; < 1,500 cpm NIA X-3001 Train 5 Train Train 5-3 Class II 1/1712018 50% Scan; < 1,500 cpm NIA X-3001 Train 5 Train Train 5-4 Class II 111712018 50% Scan; < 1,500 cpm NIA X-3001 Train 5 Train Columns Class II 111712018 Metal 15 X-3001 Train 6 Train Machine Class II 12/1912017 Surveyed 30 Machine 30 Mounts Mounts; smears < IO dpm X-3001 Train 6 Train Train 6-1 Class II 1211412017 Concrete floor; smears <

15 10 dpm X-3001 Train 6 Train Train 6-2 Class II 1211412017 Concrete floor; smears <

18 10 dpm X-3001 Train 6 Train Train 6-3 Class II 11812018 Concrete floor; smears <

16 10 dpm X-3001 Train 6 Train Train 6-4 Class II 1/812018 Concrete floor; smears <

18 10 dpm X-3001 Train 6 Train Columns Class II 12/1912017 Metal 30 36 April 2018 Ave a Ave p Max a Maxp 12 7

82 62 9

22 49 142 2

37 12 146

<200

<700

<400

<5,000 9

33 51 141 NIA NIA NIA NIA NIA NIA IA IA NIA NIA NIA NIA NIA NIA NIA NIA

<200

<700

<400

<5,000 NIA NIA

<400

<5,000 66 23 126 95 36 32 153 167 3

41 22 308 24 5

86 38

<200

<700

<400

<5,000

DP-2605-0002, Final Status Survey Report for the American Centrifuge l ead Cascade Facility Decommissioning Proj ect Revision 0 Table VII-1 Summary of the Lead Cascade Final Status Survey Results Bldg Area Sub Area ID Survey Survey Notes Survey Location Class Date Pts.

Cascade Floor Concrete 15 random X-3001 Train 7 Train Directs Class II 111612018 readings; smears < 10 15 dpm alpha X-3001 Train 7 Train Train 7-1 Class II 111612018 50% Scan; < 1,500 cpm NIA X-3001 Train 7 Train Train 7-2 Class II 1/1612018 50% Scan; < 1,500 cpm NIA X-3001 Train 7 Train Train 7-3 Class II 1/1612018 50% Scan; < 1,500 cpm NIA X-3001 Train 7 Train Train 7-4 Class II 111612018 50% Scan; < 1,500 cpm NIA X-3001 Train 7 Train Columns Class II 1/1812018 Metal 15 Cascade Floor Concrete 15 random X-3001 Train 8 Train Directs Class II 1/1812018 readings; smears < 10 15 dpm alpha X-3001 Train 8 Train Train 8-1 Class II 1/1812018 50% Scan; < 1,500 cpm NIA X-3001 Train 8 Train Train 8-2 Class II 1/1812018 50% Scan;< 1,500 cpm NIA X-3001 Train 8 Train Train 8-3 Class II 111812018 50% Scan; < 1,500 cpm NIA X-3001 Train 8 Train Train 8-4 Class II 111812018 50% Scan; < 1,500 cpm NIA X-3001 Train 8 Train Columns Class II 111812018 Metal 15 Transfer Transfer X-3001 Corridor NIA Corridor-I and Class II 1/1912018 50% Scan; < 1,500 cpm NIA 2

X-3001 Transfer IA Transfer Class II 1/1912018 Concrete; 25 random 25 Corridor Corridor directs; smears < 10 dpm X-7727H Transfer NIA Transfer Class III 112312018 Concrete; 25 random 25 Corridor Corridor directs; smears < IO dpm X-7727H NIA NIA 7727H-1 Class III 112312018 50% Scan; < 1,500 cpm NIA X-7727H NIA NIA 7727H-2 Class II I 112312018 50% Scan; < 1,500 cpm NIA X-7727H NIA NIA 7727H-3 Class Ill 1/2312018 50% Scan; < 1,500 cpm NIA X-7727H NIA IA 7727H-4 Class III 112312018 50% Scan; < 1,500 cpm NIA 37 April 2018 Ave a Ave p Max a Maxp 34 6

80 60 NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA

<200

<700

<400

<5,000 16 23 61 143 NIA IA IA NIA NIA IA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA

<400

<5,000 NIA NIA NIA NIA 46 76 102 297 49 62 109 236 NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA

DP-2605-0002, Final Status Survey Report for the American Centrifuge Lead Cascade Facility Decommissioning Proj ect Revision 0 Table VTI-1 Summary of the Lead Cascade Final Status Survey Results Bldg Area Sub Area ID Survey Survey Notes Survey Location Class Date Pts.

X-3012 Transfer IA Transfer Class II 1/1912018 50% Scan; < 1,500 cpm IA Corridor Corridor X-3012 Transfer NIA Transfer Class II 1119120 18 15 directs; smears < 10 15 Corridor Corridor-I dpm Transfer Transfer X-3002 Corridor NIA Corridor-I Class III 50% Scan; < 1,500 cpm NIA West Floor 211312018 Transfer Transfer X-3002 Corridor IA Corridor-2 Class III 50% Scan;< 1,500 cpm NIA East Floor 211412018 X-3002 Transfer IA Transfer Class Ill 211512018 Concrete; 25 random 25 Corridor Corridor directs; smears < 10 dpm X-3002 Train 4 Train Train 4-1 Class Ill 212112018 Concrete; I 5 random 15 directs; smears < IO dpm X-3002 Train 4 Train Train 4-2 Class Ill 212112018 Concrete; I 5 random 15 directs; smears < IO dpm Buffer X-7725 Storage NIA Room 161 Class II 12/112017 Concrete; 15 random 15 Area directs; smears < IO dpm (BSA)

X-7725 BSA NIA Room 162 Class II 12/112017 Concrete; 15 random 16 directs; smears< IO dpm X-7725 BSA NIA Room 1611162 Class II 12/15120 17 Mixed media; smears <

18 Walls 10 dpm BSA X-7725 IA Columns Class II 1113012017 Metal 34 38 April 2018 Ave a Ave p Max a Maxp NIA IA IA NIA 42 102 90 222 NIA NIA NIA NIA NIA NIA NIA NIA 13 5

63 65 4

25 26 117 6

30 37 148 3

19 41 89 19 0

92 0

5 36 32 208

<200

<700

<400

<5,000

DP-2605-0002, Final Status Survey Report for the American Centrifuge l ead Cascade Facility Decommissioning Project Revision 0 Table VII-1 Summary of the Lead Cascade Final Status Survey Results Bldg Area Sub Area ID Survey Survey Notes Survey Location Class Date Pts.

BSA North-BSA X-7725 IA Static Stands Class II 111812017 Metal; smears < 10 dpm 22 BSA Concrete; 15 random X-7725 IA BSA-I Class II 112212018 directs; smears< 10 dpm 15 BSA Concrete; 15 random X-7725 IA BSA-2 Class II 112212018 directs; smears< 10 dpm 15 BSA Concrete; I 5 random X-7725 NIA BSA-3 Class II 112212018 directs; smears< IO dpm 15 BSA Concrete; 1 5 random X-7725 IA BSA-4 Class II 112212018 directs; smears < 10 dpm 19 X-7725 C &Cl IA C&CI Non-513012017*

Concrete floor; smears <

28 aisleway Impacted 10 dpm Concrete floor, walls, and X-7725 3rd Floor IA Room 373 Class II 21212018 Radioactive Material 27 Area; smears < 10 dpm HP Judgmental survey; 1st Off, Break, included desks, 25% scan X-7725 Northwest NIA

& Locker Class 111 21512018 of aisles, direct readings, 25 Rooms and smears; smears < 1 0 dpm HP Judgmental survey; 2nd Floor included desks, 25% scan X-7725 Northwest IA Offices Class III 113112018 of aisles, direct readings, 25 and smears; smears < 10 dpm 39 April 2018 Ave a Ave p Max a Maxp NIA IA

<400

<5,000 11 I

67 9

0 7

0 98 I

10 9

109 0

1 0

12 NIA IA

<400

<5,000 12 337 42 523 9

293 56 827 21 317 100 551

DP-2605-0002, Final Status Survey Report for the American Centrifuge Lead Cascade Facility Decommissioning Project Revision 0 Table VTI-1 Summary of the Lead Cascade Final Status Survey Results Bldg Area Sub Area ID Survey Survey Notes Survey Location Class Date Pts.

HP Judgmental survey; 3rd Floor included desks, 25% scan X-7725 Northwest NIA Offices Class Ill 113012018 of aisles, direct readings, 25 and smears; smears < 10 dpm HP Judgmental survey; 2nd Floor included desks, 25% scan X-7726 Northwest NIA Offices -

Class Ill 112912018 of aisles, direct readings, 15 Security and smears; smears < I 0 dpm HP Judgmental survey; 3rd Floor included desks, 25% scan X-7726 Northwest NIA Offices -

Class III 112912018 of aisles, direct readings, 17 Engineering and smears; smears < I 0 dpm North Offices HP Judgmental survey; X-3012 North NIA I Area Control Class III 21612018 included desks, direct 25 Room readings, and smears; smears < IO dpm 2nd Floor HP Judgmental survey; X-3012 South NIA Mezzanine Class III 2/712018 included desks, direct 15 Offices readings, and smears; smears < IO dpm I 51 Floor HP Judgmental survey; X-3012 South NIA Offices I Class Ill 21812018 included desks, direct 25 Break Rm I readings, and smears; Locker Rm smears < 1 0 dpm X-7726 I st Floor NIA Oil Drain Class II 1211812017 Concrete; 15 directs; 15 Area smears < IO dpm 40 April 2018 Ave a Ave p Max a Maxp 3

203 22 347 33 250 144 499 6

208 34 378 20 19 104 468 6

6 32 94 11 204 59 608 5

39 58 223

DP-2605-0002, Final Status Survey Report for the American Centrifuge Lead Cascade Facility Decommissioning Project Revision 0 Table VII-1 Summary of the Lead Cascade Final Status Survey Results Bldg Area Sub Area ID Survey Survey Notes Survey Location Class Date Pts.

Assembly Metal floor; 15 directs; X-7726 Stand NIA Leve12 Class II 1211812017 smears < 1 0 dpm 18 Area Assembly Metal floor; 15 directs; X-7726 Stand NIA Level 7 Class II 12119120 I 7 smears < IO dpm 16 Area X-7726 CTTF NIA Level 1 (I, 2, Class II 112412018 50% Floor scan; < 1,500 NIA and 3) cpm X-7726 CTTF NIA Level 1 Walls Class II 112412018 Random directs on walls; 50 (I and 2) smears < 10 dpm X-7726 CTTF NA Level I Class II I 125120 I 8 Metal up to 8-foot JO Columns Assembly Level 2 Build Drywall, concrete block, X-7726 Stand NIA Stand Walls Class II 112512018 and metal, direct reading; 15 Area smears < IO dpm Assembly Level 7 Build Drywall, concrete block, X-7726 Stand NIA Stand Walls Class II 112512018 and metal, direct reading; 15 Area smears < 10 dpm Assembly Metal Floor; 15 random X-7726 Stand NIA Level 3 Class II 1125120 I 8 directs; smears< 10 dpm 15 Area Assembly Metal Floor and walls; X-7726 Stand NIA Level4 Class II 1126120 I 8 smears < 1 0 dpm I 5 Area Assembly Metal Floor and walls; X-7726 Stand NIA Level 5 Class II 112612018 smears < 10 dpm 15 Area 41 April 2018 Ave a Ave p Max a Max p 6

52 39 123 1

188 2

396 NIA NIA NIA NIA 0

48 12 322

<200

<700

<400

<5,000 0

88 0

223 19 104 77 387 6

I 29 19 15 107 58 260 24 125 46 210

DP-2605-0002, Final Status Survey Report/or the American Centrifuge Lead Cascade Facility Decommissioning Project Revision 0 Table VII-1 Summary of the Lead Cascade Final Status Survey Results Bldg Area Sub Area ID Survey Survey Notes Survey Location Class Date Pts.

Assembly Levels 6 and Metal flooring and walls; X-7726 Stand NIA Class II 112612018 15 Area 6.5 smears < 10 dpm Assembly Level 7 Metal Floor; smears < I 0 X-7726 Stand NIA Catwalk Class II 112612018 dpm 15 Area X-7726 CTTF NIA Leve12 Class Il 1/2512018 Concrete floor, smears <

19 Mezzanine 10 dpm Concrete floors and X-7726 CTTF NIA Personal Class II 112612018 walls, includes readings 25 Spaces of ceramic tiles; smears <

10 dpm X-7726 CTTF IA DOE Room Class II 112612018 Concrete floors and 20 Floor walls; smears < IO dpm X-7726 CTTF NIA DOE Room Class II 2/1 12018 Cinder block walls; 10 Walls smears < 1 0 dpm X-7726 CTTF NIA Levell Cage Class II 112612018 Concrete floor; smears <

9 10 dpm Level I 24 Machine mounts; X-7726 CTTF NIA Machine Class Il I 12612018 20 Mounts smears < 10 dpm X-7726 CTTF NIA Stairwell Class II 112512018 Concrete; random directs; 25 smears < IO dpm X-7726 CTTF NIA Floor Pits I Class II 112612018 2 floor pits; smears < I 0 2

Grates dpm X-7726 CTTF NIA 2nd floor Class II 2/1 12018 Area contains electrical 25 Utility Room utilities for the X-7726 42 April 2018 Ave a Ave f}

Max a Max (}

13 125 58 196 15 143 58 238 5

177 30 295 28 206 100 729 9

128 88 373 2

144 15 315 6

85 51 295 NIA NIA

<400

<5,000 7

116 51 294 NIA NIA

<400

<5,000 32 127 466 742

DP-2605-0002, Final Status Survey Report for the American Centrifuge Lead Cascade Facility Decommissioning Project Revision 0 Table VII-1 Summary of the Lead Cascade Final Status Survey Results Bldg Area Sub Area ID Survey Survey Notes Survey Location Class Date Pts.

facility. Not used during Lead Cascade operations.

Originally contained training cascade process piping and equipment.

Small area with residual contamination from DOE operations identified in 2008 < 5,000 dpml l 00 cm2; smears < 10 dpm Post Decon Survey after cleaning, X-7726 CTTF NIA 2nd Floor Class II 211212018 roughly I m2 area with 9

Uti lity Room residual contamination; follow-up smears < 1 0 dpm Heating &

Survey Complete; Unit J-X-7726 4th Floor NIA Ventilation Class II 212612018 2006 & J-2008; Smears <

2 Units 10 dpm X-3012 South NIA Maintenance Class II 211512018 Concrete floor; 15 17 Shop-I directs; smears< IO dpm X-3012 South NIA Maintenance Class II 211412018 Concrete floor; 15 17 Shop-2 directs; smears < 10 dpm X-3012 South NIA Maintenance Class II 2/1312018 Concrete floor; 15 17 Shop-3 directs; smears < 10 dpm X-3012 South NIA Maintenance Class II 2/1412018 Concrete floor; 15 15 Shop-4 directs; smears< IO dpm X-3012 South NIA Maintenance Class II 212312018 Metal, Drywall, and 25 Shop Walls Concrete block; random 43 April 2018 Ave a Av p Max a Maxp 104 450 361 744 NIA NIA

<400

<5,000 8

I 39 12 2

3 28 26 4

16 37 162 4

14 39 72 3

89 74 481

DP-2605-0002, Final Status Survey Report for the American Centrifuge l ead Cascade Facility Decommissioning Project Revision 0 Table VII-I Summary of the Lead Cascade Final Status Survey Results Bldg Area Sub Area ID Survey Survey Notes Survey Location Class Date Pts.

locations; smears < I 0 dpm Ave a Ave fl

No additional activities occurred within this area following the survey completed in the second quarter of 2017; therefore, survey was not repeated.

44 April 2018 Max a Max fl

DP-2605-0002, Final Status Survey Report for the American Centrifuge Lead Cascade Facility Decommissioning Project Revision O April 2018 VIII. Description of Changes Additional Final Status Surveys were performed to quantify levels when a direct measurement exceeded two times Lo or a Floor Monitor scan indicated greater than 1,500 cpm. These follow-up surveys revealed no instances of exceeding the established limit of 5,000 dpm/100 cm2; therefore, no changes to the Survey Plan were warranted.

Additional direct measurements were taken in an effort to support the return of the facilities at the time of final DOE lease termination.

IX. As Low As Reasonably Achievable Practices The Final Status Surveys were performed using approved Radiation Protection procedures. During remediation of the two Class I areas, work was performed under continuous HP coverage, and mini-gulper and vacuum cleaners were used to collect debris and minimize intake of radioactive material. Appropriate personal protective equipment was worn during remediation activities and during the performance of the Final Status Surveys. All debris and equipment was collected and appropriately disposed.

Personnel performing these activities were monitored for external as well as internal doses. Except for completion of the Final Status Survey, 99 percent of work with radioactive material was completed in December 2017. Review of Thermoluminescence Dosimeters (TLD) and bioassay data did not reveal evidence of abnormal exposure--four personnel had a positive TLD reading, while bioassay data indicated that all personnel were less than the minimum recording level. The 2017 REIRS data shows a Total Collective Total Effective Dose Equivalent was 0.049 rem.

X. Survey Unit Failures In addition to meeting the 10 CFR 20.1402 criteria of25 mrem, the goal of the Final Status Survey was to provide evidence that residual contamination levels would be less than Table 4.6-1 of the Lead Cascade License Application limits of 5,000 dpm/100 cm2 total and 1,000 dpm/100 cm2 removable. The Final Status Survey data showed:

1. There were no areas required to remain controlled for radioactivity as outlined in Chapter 4.0 of the Lead Cascade License Application.

2. There were no data points that exceeded 5,000 dpm/100 cm2*

3. Removable contamination levels were less than 10 dpm/100 cm2.

4. Average contamination levels for each survey unit were significantly less than the basis level of 5,000 dpm/100 cm2.

5. All sample locations were less than the LBGR.

6. Difference between the largest survey unit measurement and smallest reference area measurement was significantly Jess than the DCGLw.

45

DP-2605-0002, Final Status Survey Report for the American Centrifuge Lead Cascade Facility Decommissioning Project Revision O April 2018 Therefore, there were no survey units that failed.

XI. RESRAD-BUILD Evaluation A RESRAD-BUILD evaluation was performed for the areas listed in Table XI-1 below. The actual evaluations are provided within Appendix C of this report, while Table XI-1 provides a summary of the findings. The Licensee used the average residual contamination of the area plus the 1.96 standard deviations for the basis of the total residual contamination.

Table XI-1 Summary of RESRAD-BUILD Evaluations 234U nsu nsu Area Receptor Dose/Yr (mrem/yr)

Location dom oCi/m2 pCi/m2 pCi/m2 m2 0

J X-3001 201.2 4,500.1 203.9 4,357.9 28,209 l.28E-I I.30E-4 X-3012 Maintenance 43.3 969.0 43.9 938.4 2,761 2.76E-2 3.29E-5 X-7725 - Class II Areas 32.3 722.6 32.7 699.7 6,523

2. 14E-2 2.49E-5 X-7726 CTTF 78.0 1,744. 1 79.0 1,688.9 2,073 4.96E-2 5.84E-5 X-3001 Train 3 N Utility Bay Concrete Floor "Hot Spot" - Class I Area 1,127.1 25,213.6 1,142.4 24,4 16.5 9

7.18E-I 8.llE-4 X-3001Train 2 N Utility Bay Concrete Floor "Hot Spot" - Class I Area 306.0 6,844.8 310.1 6,628.4 9

l.95 E-I 2.20E-4 Overall 143.2 3,203 145 3,102 48,590 9.13E-2 7.68E-5 dpm - average plus 1.96 standard deviations of survey points taken in given location Area is approximate size of area used for RES RAD evaluations JO JOO I.30E-4 1.3 1 E-4 3.29E-5 3.29E-5 2.49E-5 2.50E-5 5.84E-5 5.85E-5 8.11 E-4 8.12E-4 2.20E-4 2.21 E-4 7.68E-5 7.70E-5 J,000 I.45E-4 3.64E-5 2.77E-5 6.48E-5 9.03E-4 2.45E-4 8.66E-5 These evaluations show the calculated dose for an industrial worker working in the area for a year (i.e., 2,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />); confirming that the Licensee meets the 25 mrem criteria as required by 10 CFR 20.1402.

XII. Removable Contamination Exceedances Removable contamination samples were counted with the Tennelec LB5100. Typical detection limit (MDA) is less than 10 dpm for both alpha and beta. All removable contamination samples were less than 20 dpm and over 99 percent of the samples were less than 10 dpm. Note: all smears recorded in units dprn/100 cm2. Therefore, no adjustment to the DCGLw was required.

46

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