Text

Independent Survey Results for the Shutdown Reactors at the Vallecitos Nuclear Center, VBWR (License DPR-1, Docket 50-18), EVESR (License DR-10, Docket 50-183); and, Getr (License TR-1, Docket 50-70)
	ML21116A132
Person / Time
Site:	Vallecitos Nuclear Center, Vallecitos
Issue date:	04/23/2021
From:	Bailey E; Oak Ridge Institute for Science & Education
To:	Jack Parrott; Reactor Decommissioning Branch
	Parrott J
Shared Package
ML21110A108	List: ML21110A112; ML21116A132;
References
	DE-SC0014664, RFTA NO.19-003, T-8F5
	Download: ML21116A132 (60)
	v • d • e

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Oak Ridge

TN 37830

orise.orau.gov April 23, 2021 Mr. Jack Parrott, Sr. Project Manager 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 SURVEY

SUMMARY

AND RESULTS FOR THE ESADA VALLECITOS EXPERIMENTAL SUPERHEAT REACTOR BUILDING AND THE VALLECITOS BOILING WATER REACTOR (VBWR) BUILDING AND NRC ANALYTICAL RESULTS FOR THE GE TEST REACTOR AND VBWR AT THE GE HITACHI VALLECITOS NUCLEAR CENTER; SUNOL, CALIFORNIA DOCKET NOS. 05000018, 05000183, AND 05000070; RFTA NO.19-003; DCN 5334-SR-02-0

Dear Mr. Parrott:

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 survey that ORISE performed during the period of February 5-6, 2019 of the two reactor buildings, the ESADA Vallecitos Experimental Superheat Reactor (EVESR) and the Vallecitos Boiling Water Reactor (VBWR), at the GE Hitachi Vallecitos Nuclear Center in Sunol, California. This report also incorporates additional analytical data and information provided by the NRC that was obtained from the GE Test Reactor (GETR) and also from the VBWR. NRCs comments provided for the draft report have been incorporated into this final version.

You may contact me at 865.576.6659 or Tim Vitkus at 865.576.5073 if you have any questions or require additional information.

Sincerely, Erika N. Bailey Survey and Technical Projects Group Manager ORISE KME:TJV:jlc electronic distribution:

K. Conway, NRC T. Vitkus, ORISE A. Huffert, NRC D. Hagemeyer, ORISE File/5334, 5350

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INDEPENDENT SURVEY

SUMMARY

AND RESULTS FOR THE ESADA VALLECITOS EXPERIMENTAL SUPERHEAT REACTOR BUILDING AND THE VALLECITOS BOILING WATER REACTOR (VBWR)

BUILDING AND NRC ANALYTICAL RESULTS FOR THE GE TEST REACTOR AND VBWR AT THE GE HITACHI VALLECITOS NUCLEAR CENTER SUNOL, CALIFORNIA Prepared by:

K. M. Engel and T. J. Vitkus FINAL REPORT Prepared for the:

U.S. Nuclear Regulatory Commission April 2021 Further dissemination authorized to NRC only; other requests shall be approved by the originating facility or higher NRC programmatic authority.

This document was prepared for U.S. Nuclear Regulatory Commission by the Oak Ridge Institute for Science and Education (ORISE) through interagency agreement number 31310018N0014 with the U.S. Department of Energy (DOE). ORISE is managed by Oak Ridge Associated Universities under DOE contract number DE-SC0014664.

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.

VNC EVESR, VBWR, and GETR Buildings Survey Report 5334-SR-02-0 INDEPENDENT SURVEY

SUMMARY

AND RESULTS FOR THE ESADA VALLECITOS EXPERIMENTAL SUPERHEAT REACTOR BUILDING AND THE VALLECITOS BOILING WATER REACTOR (VBWR)

BUILDING AND NRC ANALYTICAL RESULTS FOR THE GE TEST REACTOR AND VBWR AT THE GE HITACHI VALLECITOS NUCLEAR CENTER SUNOL, CALIFORNIA Prepared by:

Date: 4/23/2021 K. M. Engel, Health Physicist, CHP ORISE Prepared by:

Date: 4/23/2021 T. J. Vitkus, Senior Scientist, CHP ORISE Reviewed by:

Date: 4/23/2021 P. H. Benton, Quality Manager ORISE Reviewed by:

Date: 4/23/2021 W. F. Smith, Chemist ORISE Reviewed and approved for release by:

Date: 4/23/2021 E. N. Bailey, Survey and Technical Project Manager ORISE FINAL REPORT APRIL 2021

VNC EVESR, VBWR, and GETR Buildings Survey Report i

5334-SR-02-0 CONTENTS FIGURES........................................................................................................................................................... ii TABLES.............................................................................................................................................................. ii ACRONYMS.................................................................................................................................................... iii EXECUTIVE

SUMMARY

............................................................................................................................. iv

1. INTRODUCTION....................................................................................................................................... 1

2. SITE DESCRIPTION................................................................................................................................. 1

3. RADIONUCLIDES OF CONCERN...................................................................................................... 2

4. PROCEDURES............................................................................................................................................ 3 4.1 Surface Scans...................................................................................................................................... 3 4.2 Direct Measurements and Smear Sampling................................................................................... 3 4.3 Miscellaneous Sampling.................................................................................................................... 4 4.4 NRC Provided Sampling Results.................................................................................................... 5

5. SAMPLE ANALYSIS AND DATA INTERPRETATION................................................................. 5

6. FINDINGS AND RESULTS..................................................................................................................... 6 6.1 Surface Scans...................................................................................................................................... 6 6.2 Total and Removable Surface Activity Levels.............................................................................. 7 6.3 Radionuclide Concentration in Miscellaneous Samples............................................................ 10

7.

SUMMARY

.................................................................................................................................................. 12

8. REFERENCES........................................................................................................................................... 15 APPENDIX A: DATA TABLES APPENDIX B: SURVEY AND ANALYTICAL PROCEDURES APPENDIX C: MAJOR INSTRUMENTATION APPENDIX D: RADIOLOGICAL AND ENVIRONMENTAL SCIENCES LABORATORY CONFIRMATORY MEASUREMENT REPORT

VNC EVESR, VBWR, and GETR Buildings Survey Report ii 5334-SR-02-0 FIGURES Figure 2.1. VNC Site and Reactor Locations................................................................................................. 2 TABLES Table 4.1. Summary of Samples Collected..................................................................................................... 5 Table 6.1. Summary of ORISE Reactor Buildings Survey Results............................................................. 7 Table 6.2. Summary of ORISE and NRC Smear Sample Results.............................................................. 9 Table 6.3. Summary of Water and Filtered Solids Results......................................................................... 10 Table 6.4. Water and Solids Sample Fractional Activity Results............................................................... 11

VNC EVESR, VBWR, and GETR Buildings Survey Report iii 5334-SR-02-0 ACRONYMS cm centimeter cm2 square centimeters cpm counts per minute dpm disintegrations per minute EVESR ESADA Vallecitos Experimental Superheat Reactor GEH GE Hitachi GETR GE Test Reactor GM Geiger-Mueller HTD hard-to-detect m

meter MDC minimum detectable concentration mrem/hr millirem per hour MW megawatt NaI sodium iodide NORM naturally occurring radioactive material NRC U.S. Nuclear Regulatory Commission NTR Nuclear Test Reactor ORAU Oak Ridge Associated Universities ORISE Oak Ridge Institute for Science and Education pCi/g picocuries per gram pCi/L picocuries per liter pCi/sample picocuries per sample RESL Radiological and Environmental Sciences Laboratory ROC radionuclide of concern VBWR Vallecitos Boiling Water Reactor VNC Vallecitos Nuclear Center

VNC EVESR, VBWR, and GETR Buildings Survey Report iv 5334-SR-02-0 INDEPENDENT SURVEY

SUMMARY

AND RESULTS FOR THE ESADA VALLECITOS EXPERIMENTAL SUPERHEAT REACTOR BUILDING AND THE VALLECITOS BOILING WATER REACTOR (VBWR)

BUILDING AND NRC ANALYTICAL RESULTS FOR THE GE TEST REACTOR AND VBWR AT THE GE HITACHI VALLECITOS NUCLEAR CENTER SUNOL, CALIFORNIA EXECUTIVE

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) requested that the Oak Ridge Institute for Science and Education (ORISE) perform an independent survey of the ESADA Vallecitos Experimental Superheat Reactor (EVESR) building and the Vallecitos Boiling Water Reactor (VBWR) building at the GE Hitachi Vallecitos Nuclear Center (VNC) in Sunol, California. Both reactors have not been operational since the 1960s and currently are in a SAFeSTORage condition.

ORISE performed limited scope independent survey activities during the period of February 5-6, 2019. Survey activities included limited gamma scanning; alpha, beta, and gamma direct measurements; smear sampling; and water sampling in the applicable buildings. Objectives of the survey were to collect independent, preliminary radiological data using survey instruments and smear samples to measure radiation levels, identify radionuclides of concern (ROCs), and determine relative fractions between ROCs on selected contaminated surfaces in the buildings. As there has not been a characterization of the ROC makeup at the site, these data provided the initial inputs to the technical basis for developing and evaluating weighted efficiencies for the ORISE and other hand-held detectors used to measure surface activity levels. Soil samples from an exploratory boring near the TR-1 GE Test Reactor (GETR) also were included.

The maximum total surface activity of 1,500 dpm/100 cm2 alpha and 3,400,000 dpm/100 cm2 beta was found in the EVESR. Elevated total activity for alpha and beta also was found within the VBWR, but at levels less than the EVESR. Removable gross beta activity was identified on all smears collected from both the EVESR and VBWR. Gamma measurements at 0.5 meter were used to estimate a dose rate. The maximum dose rate was 1.5 millirem per hour (mrem/hr) above a metal drain on the EVESR 534 foot elevation.

VNC EVESR, VBWR, and GETR Buildings Survey Report v

5334-SR-02-0 All smears were analyzed by gamma spectroscopy. In addition, select smears were analyzed for H-3, C-14, Ni-63, Sr-90, Tc-99, isotopic plutonium, Am-241, and Cm-243/244. Cs-137 was identified on all 10 smears, and the hard-to-detect (HTD) radionuclide, H-3, also was identified on one smear.

The water sample was filtered and the filtered solids and water were analyzed independently via gamma spectroscopy. The water also was analyzed for the beta HTDs H-3, C-14, Ni-63, and Pu-241; Sr-90; and the alpha-emitters isotopic plutonium, Am-241, and Cm-243/244. The solids were analyzed for Sr-90, isotopic plutonium, Am-241, and Cm-243/244. Concentrations of the following radionuclides were above their respective analytical minimum detectable concentrations (MDCs) within the water and/or solid samples:

Beta-gamma and beta emitters: Cs-137, Co-60, and Sr-90,

HTD beta emitters: Ni-63, H-3, and Pu-241,

Alpha emitters: Pu-238, Pu-239/240, Am-241, and Cm-243/244.

Two soil samples from the upper-most and lower-most portions of an exploratory boring near the buildings were analyzed via gamma spectroscopy for gamma emitting ROCs and a portion analyzed for gross alpha and beta activity for indications of elevated concentrations of non-gamma emitting ROCs. No site-related ROCs were identified in the soil samples.

Since the completion of the ORISE survey and issuance of a preliminary draft report, the NRC provided smear sampling data from 29 smears collected during a follow-up site inspection that NRC performed for the GETR and VBWR buildings. These smears were analyzed by the Radiological and Environmental Sciences Laboratory (RESL). RESL identified the following radionuclides on these smear samples: Cs-137, Co-60, Ni-63, Sr-90, Tc-99, U-234, U-238, Am-241, Pu-238, Pu-239, and Am-241/Pu-238. The analytical data from the combined smear sample populations (both ORISE-and NRC-collected) together with the water and solids results were assessed to evaluate the radionuclide mixtures and to estimate various activity ratios relative to the predominant radionuclide identified in samples, Cs-137. The fractional activity levels of the radionuclide mixture in the water and solids samples provided the basis for calculating the nominal weighted efficiencies for ORISE scintillation detectors, and were used to convert independent survey alpha and beta direct measurements on building surfaces to units of surface activity. These total weighted efficiencies were 0.25 for beta and 0.11 for alpha. Additionally, because of the variability in fractional activity, ORISE

VNC EVESR, VBWR, and GETR Buildings Survey Report vi 5334-SR-02-0 calculated a range of weighted efficiencies that were based on the assumed ROC fractions for a Geiger-Mueller (GM) beta-gamma detectorthe type of detector the site uses in order to bound the range of estimated gross surface activity levels. These total weighted beta efficiencies ranged from 0.12 to 0.19.

The data provided in this report represent an initial independent evaluation of the radionuclide makeup at the GE Vallecitos reactor facilities and only provides a preliminary assessment of the radionuclide mixtures, essentially representing the removable fraction of the radionuclides present on building surfaces. Volumetric sampling of representative building area surface populations would be necessary to fully assess and establish the ROC inventory, the relationships between ROCs, and the variability of the inventory makeup across the site.

VNC EVESR, VBWR, and GETR Buildings Survey Report 1

5334-SR-02-0 INDEPENDENT SURVEY

SUMMARY

AND RESULTS FOR THE ESADA VALLECITOS EXPERIMENTAL SUPERHEAT REACTOR BUILDING AND THE VALLECITOS BOILING WATER REACTOR (VBWR)

BUILDING AND NRC ANALYTICAL RESULTS FOR THE GE TEST REACTOR AND VBWR AT THE GE HITACHI VALLECITOS NUCLEAR CENTER SUNOL, CALIFORNIA

1. INTRODUCTION The GE Hitachi (GEH) Vallecitos Nuclear Center (VNC) in Sunol, California, has been engaged in research, development, testing, and post-irradiation examination of reactor fuel since the 1950s (NRC 1999). GEH is the holder of four Nuclear Regulatory Commission (NRC) licensed reactors, although most of the reactor-related activities have ceased. The R-33 Nuclear Test Reactor (NTR) remains operational while the Vallecitos Boiling Water Reactor (VBWR) (shutdown in 1963), TR-1 GE Test Reactor (GETR) (shutdown in 1977), and ESADA Vallecitos Experimental Superheat Reactor (EVESR) (shutdown in 1967) are in a SAFeSTORage condition (NRC 2015).

The NRC requested that the Oak Ridge Institute for Science and Education (ORISE) perform independent survey activities within the EVESR and VBWR reactor buildings. Objectives of the limited scope survey were to collect radiological data using survey instruments and smear samples to independently measure radiation levels and acquire preliminary data for the NRCs use in the evaluation of the sites assumed radionuclides of concern (ROCs) and the relative fractions between ROCs that are present on contaminated surfaces in the buildings. The ROC and relative fraction data would provide the technical basis for developing and evaluating weighted radiation detector efficiencies for hand-held detectors used to measure surface activity levels at the VNC. ORISE performed these surveys on February 5-6, 2019. ORISE did not conduct any independent investigations within the GETR at the time due to safety concerns associated with accessing the reactor level. However, the NRC was able to perform limited surveys and sampling within the GETR and also obtained additional samples from the VBWR during a subsequent follow-up site visit. NRC provided the resulting sample analytical data for inclusion in this report.

2. SITE DESCRIPTION The VNC is located at 6705 Vallecitos Road, Sunol, California. The site is approximately 56 kilometers (35 miles) east-southeast of San Francisco, California, in the Pleasanton quadrangle of Alameda County. The site is situated in a primarily agricultural setting with a small residential

VNC EVESR, VBWR, and GETR Buildings Survey Report 2

5334-SR-02-0 population existing west of the site. The nearest sizable town is Pleasanton, California, located 6.4 kilometers (4.0 miles) north-northwest of the site.

The EVESR was a 17-megawatt (MW) thermal experimental research reactor initially licensed in 1963 and shut down in 1967. The VBWR was a 50-MW thermal experimental research reactor initially licensed in 1957 and shutdown in 1963. For both reactors, all fuel and special nuclear material have been removed and shipped offsite. Much of the equipment used to operate the reactors (e.g., instrumentation, piping, pumps, valves) has been removed as well (NRC 2015). Both reactor locations are shown on Figure 2.1.

Figure 2.1. VNC Site and Reactor Locations

3. RADIONUCLIDES OF CONCERN The exact ROCs at the EVESR, VBWR, and GETR are unknown. The site assumes that most ROCs remaining to be beta-gamma emittersfission and activation productsresulting from reactor operations and for Cs-137 to be the predominant ROC. Uranium and transuranics from fuel experiments are a possibility; however, full characterization data of the buildings were not available during the ORISE independent survey or the NRCs follow-up site visit.

VNC EVESR, VBWR, and GETR Buildings Survey Report 3

5334-SR-02-0

4. PROCEDURES The procedures described in Sections 4.1 through Section 4.3 are specific to the ORISE survey activities for the EVESR and VWBR that were conducted during the period of February 5-6, 2019.

These activities were in accordance with the Oak Ridge Associated Universities (ORAU) Radiological and Environmental Survey Procedure Manual and the ORAU Environmental Services and Radiation Training Quality Program Manual (ORAU 2016a, currently 2019). Appendices B and C provide additional information regarding survey instrumentation and related processes discussed within this section.

4.1 SURFACE SCANS Limited gamma scans were performed with Ludlum Model 44-10 5-centimeter (cm) by 5-cm (2-inch x 2-in) sodium iodide (NaI) scintillation detectors coupled to Ludlum Model 2221 ratemeter-scalers with audible indicators. Scans were performed to determine the overall levels of gamma radiation in select areas within each of the two buildings surveyed.

4.2 DIRECT MEASUREMENTS AND SMEAR SAMPLING In total, 10 locations were selected for direct measurements and smear sampling within the two reactor buildings: eight locations within the EVESR and two locations within the VBWR. Three locations on the main floor of the EVESR were judgmentally selected based on elevated direct radiation levels observed while gamma scanning. All other locations within the EVESR and VBWR were determined by the NRC/site staff, with one location selected from each building elevation.

Direct surface activity measurements for alpha and beta radiation were made using Ludlum Model 2221 ratemeter-scalers coupled to Ludlum Model 43-92 zinc sulfide alpha detectors and Ludlum Model 44-142 plastic scintillator beta detectors. Direct surface activity measurements for gamma radiation were made using the same ratemeter-scaler and NaI scintillation detector combination described for the gamma surface scans s. NaI direct measurements were collected both on contact and at 0.5 meters (m) from the surface to estimate dose rates. Alpha and beta direct measurements were made on contact with building surfaces.

Dry smear samples, for determining removable gross alpha and beta activity levels, were collected from each direct measurement location. Smears covered 100 cm2 and were collected post-direct measurement, except for smear 5334R0004, which was collected prior to direct measurements.

VNC EVESR, VBWR, and GETR Buildings Survey Report 4

5334-SR-02-0 Ultimately, as detailed in Section 5, smears were assessed for additional radiological parameters, beyond just the removable gross alpha and beta activity. Additional smear analytes included H-3, C-14, or other hard-to-detect (HTD) radionuclides. The ORISE procedure when smear sampling for removable H-3 and C-14 activity specifies that smears be pre-moistened with deionized water or scintillation cocktailin order to improve collection efficiencyprior to sampling. Each smear is placed into a vial containing the wetting agent and then sealed. However, information as to the potential source term upon which to base radionuclide-specific sampling methods and the analyses was not available prior to the investigation and these specific requirements could not be accommodated prior to or during the site visit.

4.3 MISCELLANEOUS SAMPLING A water sample was collected from the VBWR basement level where water up to 7 cm deep covered 75 percent of the floor. The water sample was formed from aliquots collected from various locations throughout the basement to fill the sample container.

The site had collected samples from an exploratory boring near the TR-1 GETR building, and the two soil samples collected from the upper-most and lower-most sections of the boring were provided to ORISE for laboratory analysis per NRCs request.

Table 4.1 provides a summary of the independent survey samples collected from the EVESR and VBWR buildings or were otherwise obtained while on site.

VNC EVESR, VBWR, and GETR Buildings Survey Report 5

5334-SR-02-0 Table 4.1. Summary of Samples Collected Reactor Building Sample ID Sample Type Location/Description Level Surface EVESR 5334R0001 Smear Near Fuel Pool by Cart Main Concrete Floor 5334R0002 Smear Near Stairs in Track Main Concrete/Metal Floor 5334R0003 Smear Adjacent to Entry Main Concrete Floor 5334R0004 Smear Site Location Main Concrete Floor 5334R0005 Smear Site Location 534' Elev.

Concrete Floor 5334R0006 Smear Site Location 519' Elev.

Concrete Floor 5334R0007 Smear Site Location 503' Elev.

Concrete Floor 5334R0008 Smear Site Location 483' Elev.

Concrete Floor VBWR 5334R0009 Smear Site Location Main Concrete Floor 5334R0010 Smear Off Catwalk Reactor Lead Brick Floor 5334W0001 Water Various Locations Throughout Basement Level Reactor NA 5334W0002 Solids Solids Separated from Water Sample W0001 Reactor NA Other 5334S0017 Soil Upper Most Portion of Boring 9EB NA NA 5334S0018 Soil Lower Most Portion of Boring 9EB NA NA NA = Not Applicable 4.4 NRC PROVIDED SAMPLING RESULTS The NRC collected 15 smear samples and took custody of 14 others from the licensee. The 29 total locations from throughout the VBWR and GETR were sampled during a March 2019 NRC site inspection. Sixteen samples were collected in the basement and first floor of the VBWR and 13 samples were collected from the GETR basement, first floor, and top floor. The U.S.

Department of Energy Idaho Operations Offices Radiological and Environmental Sciences Laboratory (RESL) analyzed these smears on NRCs behalf and NRC provided the results to ORISE for inclusion in this report.

5. SAMPLE ANALYSIS AND DATA INTERPRETATION The independent survey samples and data collected on-site by ORISE staff were returned to the ORISE facility for analysis and interpretation. Sample custody was transferred to the ORISE 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 (currently ORAU 2020). Table A-1 provides a summary table of the sample

VNC EVESR, VBWR, and GETR Buildings Survey Report 6

5334-SR-02-0 matrices, the sample building location, the specific analyses performed as described below, and whether the analyte concentration was above the minimum detectable concentration (MDC) for each sample.

Smears were analyzed for removable gross alpha and beta activity using a low-background gas proportional counter. Smear data and direct measurements for surface activity were converted to units of disintegrations per minute per 100 square centimeters (dpm/100 cm2).

All smears were also analyzed by gamma spectroscopy for radionuclide identification. The removable activity, total activity, and gamma spectroscopy results were used to select specific smears for analyses of the HTDs H-3, C-14, Ni-63, and Pu-241; and/or Sr-90; Tc-99; isotopic plutonium; Am-241; and Cm-243/244. Results are reported in units of picocuries per sample (pCi/sample).

The water sample was filtered, and the water and solids were analyzed independently via gamma spectroscopy followed by selective analysis for H-3, C-14, Ni-63, Sr-90, Tc-99, isotopic plutonium, Am-241, and Cm,-243/244. The water sample was acidified and allowed to equilibrate before analyzing for Ni-63, Sr-90, Tc-99, and alpha emitters. Results are reported in units of picocuries per liter (pCi/L) for the water and pCi/sample for the solids.

Soil samples were crushed, homogenized, and analyzed by gamma spectrometry for gamma-emitting fission and activation products and for gross alpha and beta concentrations using a low-background proportional counter. Analytical results are reported in units of picocuries per gram (pCi/g).

6. FINDINGS AND RESULTS The results of the survey are discussed in the following subsections. Appendix A provides the survey data for the two buildings investigated. Appendices B and C provide additional details regarding field and laboratory instrumentation as well as additional information on calibration, quality assurance, survey and analytical procedures, and detection sensitivities.

6.1 SURFACE SCANS The gamma radiation levels correlating to select measurement and smear sampling locations ranged from 47,000 counts per minute (cpm) to 200,000 cpm in the EVESR basement, with higher levels over the floor sump. On the VBWR main floor, gamma radiation levels ranged from 20,000 cpm to

VNC EVESR, VBWR, and GETR Buildings Survey Report 7

5334-SR-02-0 700,000 cpm. In the VBWR basement, gamma radiation levels ranged from 400,000 cpm to over 1,000,000 cpm, with higher levels over drain holes in the floor.

6.2 TOTAL AND REMOVABLE SURFACE ACTIVITY LEVELS Table 6.1 provides summarized ranges of the gamma radiation levels and total and removable alpha and beta surface activity levels for the EVESR and VBWR direct measurement and smear sampling locations. Table A.2 provides the results for each location.

Table 6.1. Summary of ORISE Reactor Buildings Survey Results Building Ranges Gamma Total Activity (dpm/100 cm2)

Removable Activity (dpm/100 cm2)

Contact (cpm)

At 0.5 m (cpm)

At 0.5 m (mR/hr)a Alpha Beta Alpha Beta EVESR Minimum 24,000 24,000 0.0b 45 9,800 0

19 Maximum 3,700,000 1,300,000 1.5 1,500 3,400,000 7

1,900 VBWR Minimum 48,000 56,000 0.1 0

11 Maximum 300,000 320,000 0.4 45 29,000 0

19 a () x 1

(//). Weighted sensitivity is an ORISE determined value.

b.

For total activity, all locations were above the static beta MDC and all but two locations were above the static alpha MDC. Nine out of the 10 smears collected showed removable beta activity above the analytical MDC; however, the gross alpha activity on all 10 smears were below the analytical MDC.

Appendix B provides surface activity measurement and analytical MDCs.

Radionuclide-specific analytical results for the smears identified a maximum of 890 pCi/sample Cs-137, 4.5 pCi/sample H-3, and 0.016 pCi/sample Pu-239/240. Results for Co-60, C-14, Ni-63, Sr-90, Tc-99, Pu-238, Pu-241, Am-241, and Cm-243/244 were below their respective MDCs.

Tables A.3 through A.5 in Appendix A provide the full results.

Table A.6 provides the sample analysis summary matrix for the NRC samples. Sample results that were greater than two times the analytical one standard deviation uncertainty were indicated as detectable. The maximum activity results for these smear samples were as follows: 16,190 pCi for Cs-137, 76 pCi for Co-60, 11.6 pCi for Ni-63, 129 pCi for Sr-90, 3.1 pCi for Tc-99, 0.029 pCi for U-234, 0.023 pCi for U-238, 3.0 pCi for Am-241, 0.40 pCi for Pu-238, 1.10 pCi for Pu-239, and 0.31 pCi for Am-241/Pu-238. All analytical results for each sample are provided in Appendix D.

VNC EVESR, VBWR, and GETR Buildings Survey Report 8

5334-SR-02-0 Table A.7 provides the combined analytical data from both the ORISE and NRC smears samples and the ORISE water and solid samples. Additionally, the table provides the ratios of the predominant radionuclide identified in samples, Cs-137, to total sample activity. Table 6.2 provides a summary of the results and the calculated Cs-137 to total activity ratios based on the mean and median activities for VBWR smears, GETR smears, and EVESR smears.

The radionuclide activities and the Cs-137 to total activity ratios for individual samples (including the ORISE water/solids samples for completeness) can be found in Table A.7. The individual ratios ranged from 0.24 to 1.00, indicative of wide variability in the concentration of the other ROCs relative to Cs-137. The range of Cs-137 to total activity ratios as it pertains to survey instrument detector efficiency, is discussed further in Section 7 of the report.

VNC EVESR, VBWR, and GETR Buildings Survey Report 9

5334-SR-02-0 Table 6.2. Summary of ORISE and NRC Smear Sample Results a, b Cs-137 Co-60 Ni-63 Sr-90 Tc-99 U-234 U-238 Am-241 Pu-238 Pu-239 Am-241/

Pu-238 C-14 H-3 Total Sample Activity Cs-137:

TA Mean-All Smear Samples 1,201 10 6.4 40 2.3 0.020 6.8 2.1 0.31 0.33 0.16 4.5 1,274 0.942 StdDev-All Smear Samples 2,746 12 1.9 24 0.67 0.0081 6.14 0.52 0.073 0.20 0.071 Median-All Smear Samples 179 1.5 6.4 11 2.6 0.018 0.018 2.1 0.31 0.11 0.093 4.5 207 0.863 Minimum-All Smear Samples 7.3 1.0 1.1 4.2 1.2 0.010 0.010 1.3 0.23 0.016 0.016 Maximum-All Smear Samples 16,200 75.8 11.6 129 3.1 0.029 31 3.0 0.40 1.1 0.31 4.5 Mean-VBWR Smear Samples 1,627 17 11.6 46 0.019 0.015 2.1 0.31 0.39 0.23 1,705 0.954 StdDev-VBWR Smear Samples 3,890 18 35 0.0074 0.0047 0.77 0.11 0.29 0.10 Median-VBWR Smear Samples 174 7.4 11.6 8.1 0.018 0.015 2.1 0.31 0.13 0.30 204 0.852 Minimum-VBWR Smear Samples 7.3 1.10 4.2 0.016 0.013 1.26 0.23 0.031 0.093 Maximum-VBWR Smear Samples 16,200 76 11.6 129 0.023 0.016 3.0 0.40 1.10 0.31 Mean-GETR Smear Samples 1,252 1.23 1.13 13.6 2.3 0.020 0.017 0.050 1,271 0.986 StdDev-GETR Smear Samples 1,173 0.75 0.31 1.1 0.011 0.009 0.024 Median-GETR Smear Samples 1,270 1.30 1.13 13.6 2.6 0.021 0.017 0.050 1,289 0.985 Minimum-GETR Smear Samples 8.4 1.0 1.1 1.2 0.010 0.010 0.016 Maximum-GETR Smear Samles 3,700 2

1 13.6 3.1 0.029 0.023 0.084 Mean-EVESR Smear Samples 157 27 0.016 4.5 189 0.832 StdDev-EVESR Smear Samples 302 13 Median-EVESR Smear Samples 45 27 0.016 4.5 77 0.585 Minimum-EVESR Smear Samples 8.1 23.4 Maximum-EVESR Smear Samples 890 31 0.016 4.5 a Only sample data greater than MDC or the result was greater than two times the measurement 1 standard deviation uncertainty were used b Smear results are in units of pCi/sample.

VNC EVESR, VBWR, and GETR Buildings Survey Report 10 5334-SR-02-0 6.3 RADIONUCLIDE CONCENTRATION IN MISCELLANEOUS SAMPLES Table 6.3 provides a summary of the water and filtered solids samples. All data are provided in Tables A.8 through A.11 in Appendix A. Analytical data from the water and solids samples were used to determine the fractional activities presented in Table 6.4.

Table 6.3. Summary of Water and Filtered Solids Results Radionuclide 5334W0001 (water)

(pCi/L) 5334W0002 (solids filtered from W0001) (pCi/sample)

Gross Alpha 11a (19)

NA Gross Beta 44,000 NA Cs-137 65,000 25,000 Co-60 11.4 130 H-3 2,500 NA C-14 3a (53)

NA Ni-63 520 NA Sr-90 1,000 1,200 Tc-99 33a (42)

NA Pu-238 0.51 2.10 Pu-239/240 2.22 6.40 Pu-241 0a (44) 26.9 Am-241 4.63 19.3 Cm-243/244 0.000a (0.069) 0.106 a Reported concentration less than the listed parenthetical MDC NA = not analyzed

VNC EVESR, VBWR, and GETR Buildings Survey Report 11 5334-SR-02-0 Table 6.4. Water and Solids Sample Fractional Activity Results Water Cs-137 Co-60 H-3 Sr-90 Tc-99 C-14 Ni-63 Pu-241 Pu-238 Pu-239/240 Am-241 Cm-243/244 Activity (pCi/L) 6.5E+04 1.1E+01 2.5E+03 1.0E+03 3.3E+01 3.0E+00 5.2E+02 0.0E+00 5.1E-01 2.2E+00 4.6E+00 0.0E+00 Total Activity Fractions 9.4E-01 1.7E-04 3.6E-02 1.5E-02 4.8E-04 0.0E+00 7.5E-03 0.0E+00 7.4E-06 3.2E-05 6.8E-05 0.0E+00 Beta Fractions 9.4E-01 1.7E-04 3.6E-02 1.5E-02 4.8E-04 0.0E+00 7.5E-03 0.0E+00 NA NA NA NA Alpha Fractions NA NA NA NA NA NA NA NA 6.9E-02 3.0E-01 6.3E-01 0.0E+00 Solids Cs-137 Co-60 H-3 Sr-90 Tc-99 C-14 Ni-63 Pu-241 Pu-238 Pu-239/240 Am-241 Cm-243/244 Activity (pCi/sample) 2.6E+04 1.3E+02

--a 1.2E+03 2.7E+01 2.1E+00 6.4E+00 1.9E+01 1.1E-01 Total Activity Fractions 9.50E-01 4.81E-03 4.30E-02 1.0E-03 7.8E-05 2.4E-04 7.2E-04 4.0E-06 Beta Fractions 9.5E-01 4.8E-03 4.3E-02 0.0E+00 NA NA NA NA Alpha Fractions NA NA NA NA NA NA NA NA 7.5E-02 2.3E-01 6.9E-01 3.8E-03 NA = Not analyzed

VNC EVESR, VBWR, and GETR Buildings Survey Report 12 5334-SR-02-0 The Table 6.4 fractional activity levels from the water sample results were used to calculate nominal detector weighted efficiencies for the Ludlum Model 44-142 beta and Ludlum Model 43-92 alpha scintillation detectors that ORISE used during the survey. The total weighted efficiencies were 0.25 for beta and 0.11 for alpha. See Appendix B for weighted efficiency calculations. All total activities provided in Table 6.1 and Appendix A were calculated using these weighted efficiencies.

Additionally, for comparative purposes, ORISE calculated weighted beta efficiencies for a typical Ludlum model 44-9 Geiger-Mueller (GM) detector, similar to what the site uses for routine monitoring. These other efficiencies were based on the ROC fractions for individual water sample results and the results from both the ORISE and NRC smears. The resulting GM detector efficiency range of 0.12 to 0.19 represents how detection efficiency varies across the site, dependent upon the actual ROCs present in the inventorymost notably affected (lowered) when HTDs are present and the relative ROC fractions for a specific area or building. In those cases where there is uncertainty in the site inventory and hence uncertainty in the range of detector efficiencies, a common conservative approach is to use a default weighted efficiency on the lower end of the observed range. Such an approach might be considered until such a time that a more thorough inventory characterization study is performed. Based on these conditions, GM efficiencies of approximately 0.10 may better represent contamination levels, account for additional uncertainty in HTD contributions, and minimize the potential for underestimating surface activity.

The two soil samples had gross alpha and beta results above the MDCs, with maximum values at 6.4 pCi/g and 11.9 pCi/g, respectively, and are typical of background activity because of naturally occurring radioactive material (NORM) in soils. Gamma spectroscopy did not identify any radionuclides, other than NORM, in the soil samples.

7.

SUMMARY

At the NRCs request, ORISE conducted survey activities of two of the shutdown reactor buildings, EVESR and VBWR, at the GEH VNC in Sunol, California, during the period of February 5-6, 2019. The survey activities were of limited scope and included gamma scanning; alpha, beta, and gamma direct measurements; smear sampling; and water sampling in the two buildings.

Objectives of the survey were to independently collect radiological data using survey instruments and smear samples to measure radiation levels followed by sample analyses to identify the ROCs

VNC EVESR, VBWR, and GETR Buildings Survey Report 13 5334-SR-02-0 present and their relative fractions. These data were required for the NRCs use in the assessment and confirmation of the sites assumptions regarding overall ROC inventory in each building, including the presence of HTDs, and the impact of the ROC inventory on the detector efficiencies.

The survey results provided the inputs required to preliminarily estimate the hand-held detector weighted efficiencies that were used in the calculation of residual radiological surface activity levels present on building surfaces. Other confirmatory activities included the analysis of two soil samples from an exploratory boring near the TR-1 GETR building. Only naturally occurring radionuclides consistent with background concentrations were identified in the soil samples.

The maximum total activity and removable surface activity was found in the EVESR. Maximum total surface activity levels were 1,500 dpm/100 cm2 alpha and 3,400,000 dpm/100 cm2 beta. For the removable activity assessment, gross beta activity was identified above the MDC on all smears; however, all alpha activity was below the analytical MDC. The maximum removable gross beta activity was 1,900 dpm/100 cm2. Elevated total alpha and beta surface activity also was identified within the VBWR, but at levels less than the EVESR. Gamma measurements at 0.5 m were used to estimate a dose rate. The maximum dose rate was 1.5 millirem per hour (mrem/hr) at 0.5 m in the EVESR on the 534-foot elevation above a metal drain.

Cs-137 was identified as the predominant ROC on each of the 10 smears collected, with results ranging from 7.3 to 890 pCi/sample. H-3 activity of 4.5 pCi/sample was identified on one smear, 0.016 pCi/sample of Pu-239/240 was identified on a separate smear, and U-238 was identified on two other smears with activities of 31 and 23.4 pCi/sample. All remaining analytes were less than the MDC.

The laboratory analyses of the water sample and the solids identified Cs-137, Co-60, Sr-90, Ni-63, H-3, Pu-241, Pu-238, Pu-239/240, Pu-241, Am-241, and Cm-243/244 above their respective MDCs.

The maximum results were 65,000 pCi/L Cs-137, 130 pCi/sample Co-60, 2,500 pCi/L H-3, 520 pCi/L Ni-63, 1,200 pCi/sample Sr-90, 2.10 pCi/sample Pu-238, 6.40 pCi/sample Pu-239/240, 26.9 pCi/sample Pu-241, 19.3 pCi/sample Am-241, and 0.106 pCi/sample Cm-243/244. The fractional activities from these samples provided the inputs for calculating the ORISE alpha and beta detector total weighted efficiencies that were used to convert cpm to surface activity.

VNC EVESR, VBWR, and GETR Buildings Survey Report 14 5334-SR-02-0 Cs-137 was also the predominant ROC for the NRC smears collected from the GETR and VBWR buildings with a maximum activity of 16,190 pCi. The maximum activity for the other identified ROCs were 76 pCi Co-60, 11.6 pCi Ni-63, 129 pCi Sr-90, 3.1 pCi Tc-99, 0.029 pCi U-234, 0.023 pCi U-238, 3.0 pCi Am-241, 0.40 pCi Pu-238, 1.10 pCi Pu-239, and 0.31 pCi Am-241/Pu-238.

The ORISE and NRC sample analytical data were consolidated, and the Cs-137 to total activity ratio was calculated for each smear sample. The ratios ranged from 0.242 to 1.00 indicating a wide variability in removable ROC activities throughout the three buildings. These variable ratios also result in a range of potential weighted efficiencies that are dependent on ROC makeup. Therefore, various individual ORISE and NRC smear data activity ratios representing variable fractions were used to calculate a corresponding weighted efficiency range for a typical GM detector used at the site for routine surveys. The weighted efficiencies ranged from 0.12 to 0.19, primarily dependent upon the fraction of HTD ROCs present in the sample.

The results provided in this report represent an initial independent evaluation of the radionuclide makeup at the GE Vallecitos reactor facilities. The sample population from which these data and assessments were generated were limited, and require several qualifications regarding the collection, analysis, and representativeness of the smear samples. The smears were collected as dry smears using moderate pressure. The removal efficiency of surface activity is highly variable in itself. The comparison of the total to removable activity levels in Table A.2 shows that only a very small fraction0.003 to 0.417%of the activity at a given location was removable. Furthermore, the removal efficiencies for the individual ROCs are likely to vary based on physio-chemical binding to matrix. Also, because sampling was via dry rather than wet smears, the collection efficiency for the HTDs H-3 and C-14 was not optimal. As such, it must be emphasized that the prior note regarding low removal efficiencies applies to only the ORISE H-3/C-14 removable activity data.

As demonstrated by the analytical data, ROC total activity composition and levels in each building are highly variable. The ratios developed using only smear data provide a preliminary assessment with large uncertainties in the radionuclide mixtures and the variability in the ratios between the EVESR, VBWR, and GETR buildings. Until such time that the site conducts a comprehensive volumetric ROC inventory characterization, a preliminary weighted efficiency that accounts for HTD ROCs of approximately 0.10 would provide a conservative and potentially more representative estimate of surface activity levels should higher than anticipated levels of HTDs be present.

VNC EVESR, VBWR, and GETR Buildings Survey Report 15 5334-SR-02-0

8. REFERENCES NRC 1999. NRC To Meet With Public in California to Discuss GE Vallecitos Nuclear Center. Notice to Public. U.S. Nuclear Regulatory Commission. Arlington, Texas. October.

NRC 2015. GEH Vallecitos Center (VNC) Request for DR-10 and TR-1 License Continuation. U.S.

Nuclear Regulatory Commission. Washington, D.C. December.

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 Health and Safety Manual. Oak Ridge Associated Universities. Oak Ridge, Tennessee. January.

ORAU 2019. ORAU Environmental Services and Radiation Training Quality Program Manual. Oak Ridge Associated Universities. Oak Ridge, Tennessee. April 30.

ORAU 2020. ORAU Radiological and Environmental Analytical Laboratory Procedures Manual. Oak Ridge Associated Universities. Oak Ridge, Tennessee. June 30.

VNC EVESR, VBWR, and GETR Buildings Survey Report 5334-SR-02-0 APPENDIX A:

DATA TABLES

VNC EVESR, VBWR, and GETR Buildings Survey Report A-1 5334-SR-02-0 Table A.1. Requested ORISE Sample Analyses Sample ID Matrix Bldg.

Analytes Requested Gamma Spec Gross Alpha Gross Beta H-3 C-14 Ni-63 Sr-90 Tc-99 Iso-Pu (Pu-238, and -239/240)

Am-241 and Cm-243/244 Pu238 Pu239/240 Pu241 Am241 Cm243/244 5334W0001 Water VBWR U

U U

5334W0002 Solids VBWR x

5334R0009 Smear VBWR U

U U

5334R0010 Smear VBWR U

U U

5334R0001 Smear EVSER U

U 5334R0002 Smear EVSER U

U U

5334R0003 Smear EVSER U

U U

U 5334R0004 Smear EVSER U

U U

5334R0005 Smear EVSER U

U U

5334R0006 Smear EVSER U

U 5334R0007 Smear EVSER U

U 5334R0008 Smear EVSER U

U U

= Analysis performed and result greater than MDC.

U = Analysis performed and result less than MDC.

-- = Analysis not requested.

VNC EVESR, VBWR, and GETR Buildings Survey Report A-2 5334-SR-02-0 Table A.2. Total and Removable Activity Reactor Building Smear ID Location Description Level Surface Gamma Total Activity (dpm/100 cm2)

Removable (dpm/100 cm2)

Contact (cpm)

@0.5m (cpm)

@0.5m (mrem/hr)a Alpha Beta Alpha Beta EVESR 5334R0001 Near Fuel Pool by cart Main Concrete Floor 490,000 270 750,000 7

25 5334R0002 Near Stairs in Track Main Concrete/Metal Floor 320,000 100 99,000 2

19 5334R0003 Adjacent to Entry Main Concrete Floor 510,000 1,500 2,800,000 4

1,200 5334R0004 Site Location Main Metal Floor 24,000 27,000 0.0 150 9,800 0

21 5334R0005 Site Location 534' Elev.

Concrete Floor 820,000 930,000 1.1 730 3,400,000 2

1,900 Site Location 534' Elev.

Metal Drain/Floor 3,700,000 1,300,000 1.5 5334R0006 Site Location 519' Elev.

Concrete Floor 34,000 30,000 0.0 45 50,000 4

75 5334R0007 Site Location 503' Elev.

Concrete Floor 29,000 24,000 0.0 280 36,000 2

150 5334R0008 Site Location 483 Elev.

Concrete Floor 59,000 67,000 0.1 210 46,000 0

110 VBWR 5334R0009 Site Location Main Concrete Floor 48,000 56,000 0.1 45 29,000 0

19 5334R0010 Off Catwalk Reactor Lead Brick Floor 300,000 320,000 0.4 0

11 a () x 1

(//). Weighted sensitivity was an ORISE determined value.

-- = Not analyzed and/or calculated.

Bold Font = Results greater than MDC.

VNC EVESR, VBWR, and GETR Buildings Survey Report A-3 5334-SR-02-0 Table A.3. Smear Sample Results for Cs-137, Co-60, H-3, and C-14 Reactor Building Smear ID Cs-137 (pCi/sample)

Co-60 (pCi/sample)

H-3 (pCi/sample)

C-14 (pCi/sample)

Conc.

TPU a MDC Conc.

TPU MDC Conc.

TPU MDC EVESR 5334R0001 8.1

+/-

1.7 2.9

-1.3

+/-

2.2 4.1 4.5

+/-

1.2 1.7 0.59

+/-

0.69 1.16 5334R0002 9.9

+/-

2.4 5.0

-1.0

+/-

2.1 3.9 0.18

+/-

0.99 1.71 0.34

+/-

0.68 1.16 5334R0003 195

+/-

14 3

0.6

+/-

2.1 4.4

+/-

5334R0004 11.1

+/-

2.0 3.7 2.1

+/-

2.3 5.0 0.5

+/-

1.0 1.7 0.05

+/-

0.67 1.16 5334R0005 890

+/-

71 4

-0.5

+/-

2.2 4.1

-0.39

+/-

0.96 1.71 0.46

+/-

0.69 1.16 5334R0006 38.7

+/-

3.6 2.8

-0.9

+/-

2.1 4.2

+/-

5334R0007 50.9

+/-

4.7 2.7 0.7

+/-

2.1 4.2

+/-

5334R0008 55.2

+/-

4.8 3.7 0.0

+/-

2.4 4.9 0.29

+/-

0.99 1.71 0.03

+/-

0.67 1.16 VBWR 5334R0009 7.3

+/-

1.6 2.8

-0.6

+/-

1.9 3.7 0.36

+/-

0.99 1.71 0.91

+/-

0.70 1.16 5334R0010 7.8

+/-

1.5 2.6

-1.2

+/-

1.1 3.8

+/-

a Uncertainties are based on total propagated uncertainties (TPU) at the 95% confidence level.

-- = Not analyzed and/or calculated.

Bold Font = Results greater than MDC MDC = minimum detectable concentration.

VNC EVESR, VBWR, and GETR Buildings Survey Report A-4 5334-SR-02-0 Table A.4. Smear Sample Results for Ni-63, Sr-90, Tc-99, and Pu-241 Reactor Building Smear ID Ni-63 (pCi/sample)

Sr-90 (pCi/sample)

Tc-99 (pCi/sample)

Pu-241 (pCi/sample)

Conc.

TPU a MDC Conc.

TPU MDC Conc.

TPU MDC EVESR 5334R0001

+/-

5334R0002

+/-

5334R0003

+/-

-0.10

+/-

0.38 0.72

+/-

-2.5

+/-

3.7 6.7 5334R0004

+/-

5334R0005

+/-

5334R0006 1.34

+/-

0.87 1.43

+/-

5334R0007

+/-

-0.59

+/-

0.92 1.69

+/-

5334R0008

+/-

VBWR 5334R0009

+/-

5334R0010 0.41

+/-

0.84 1.43

+/-

a Uncertainties are based on total propagated uncertainties (TPU) at the 95% confidence level.

MDC = minimum detectable concentrations.

-- = Not analyzed and/or calculated.

VNC EVESR, VBWR, and GETR Buildings Survey Report A-5 5334-SR-02-0 Table A.5. Smear Sample Results for Pu-238, Pu-239/240, Am-241, and Cm-243/244 Reactor Building Smear ID Pu-238 (pCi/sample)

Pu-239/240 (pCi/sample)

Am-241 (pCi/sample)

Cm-243/244 (pCi/sample)

Conc.

TPU a MDC Conc.

TPU MDC Conc.

TPU MDC EVESR 5334R0001

+/-

5334R0002

+/-

5334R0003 0.0000

+/-

0.0078 0.0119 0.016

+/-

0.016 0.012 0.008

+/-

0.011 0.012 0.0041

+/-

0.0080 0.0122 5334R0004

+/-

5334R0005

+/-

5334R0006

+/-

5334R0007

+/-

5334R0008

+/-

VBWR 5334R0009

+/-

5334R0010

+/-

a Uncertainties are based on total propagated uncertainties (TPU) at the 95% confidence level.

MDC = minimum detectable concentrations.

Bold Font = Results greater than MDC.

-- = Not analyzed and/or calculated.

VNC EVESR, VBWR, and GETR Buildings Survey Report A-6 5334-SR-02-0 Table A.6. NRC Sample Matrix Sample ID Building Gamma Spec Fe-55 Ni-63 Sr-90 Tc-99 Pu-241 Pu-238,

-239/240 Am-241, Cm-243/244 040219-NRC-2 VBWR a

U b

-- c 040219-NRC-3 VBWR U

U U

U 040219-NRC-4 VBWR 040219-NRC-5 VBWR U

040219-NRC-6 VBWR U

040219-NRC-8 VBWR U

040219-NRC-9 VBWR 040219-NRC-10 GETR U

U U

040219-NRC-11 GETR U

U U

040219-NRC-12 GETR U

U U

040219-NRC-13 GETR U

040219-NRC-14 GETR U

040219-NRC-15 GETR U

U U

040219-NRC-16 GETR U

U U

U 040219-NRC-17 GETR U

U U

040219-NRC-B VBWR U

U 040219-NRC-C VBWR U

040219-NRC-D VBWR U

040219-NRC-K VBWR U

040219-NRC-L VBWR 040219-NRC-M VBWR 040219-NRC-N VBWR U

040219-NRC-O VBWR U

U 040219-NRC-P VBWR 040219-GETR-A GETR U

U 040219-GETR-B GETR 040219-GETR-C GETR U

040219-GETR-D GETR U

U U

040219-Inside-Step-Off-Pad GETR U

a Analysis performed and result greater than 2 standard deviations.

b Analysis performed and result less than 2 standard deviations.

c Data not provided.

VNC EVESR, VBWR, and GETR Buildings Survey Report A-7 5334-SR-02-0 Table A.7. ORISE and NRC Sample Results and Activity Ratios a Sample ID Matrix Building Cs-137 Co-60 Ni-63 Sr-90 Tc-99 U-234 U-238 Am-241 Pu-238 Pu-239 Am-241/

Pu-238 C-14 H-3 Total Sample Activity Cs-137:

TA NRC Samples 040219-NRC-2 Smear VBWR 119 119 1.000 040219-NRC-3 Smear VBWR 113 113 1.000 040219-NRC-4 Smear VBWR 160 4.2 164 0.974 040219-NRC-5 Smear VBWR 380 0.018 0.13 0.30 380 0.999 040219-NRC-6 Smear VBWR 242 0.016 0.013 0.098 0.31 242 0.998 040219-NRC-8 Smear VBWR 3,700 8.5 0.023 0.016 3.0 0.40 1.10 3,713 0.996 040219-NRC-9 Smear VBWR 16,200 76 129 16,405 0.988 040219-NRC-10 Smear GETR 2,510 0.027 0.015 2,510 1.000 040219-NRC-11 Smear GETR 1,290 13.6 1,304 0.990 040219-NRC-12 Smear GETR 1,900 3.1 1,903 0.998 040219-NRC-13 Smear GETR 2,640 1.4 0.029 0.023 0.084 2,642 0.999 040219-NRC-14 Smear GETR 1,270 1.0 0.015 0.010 0.016 1,271 0.999 040219-NRC-15 Smear GETR 980 1.3 2.6 984 0.996 040219-NRC-16 Smear GETR 8.4 1.2 10 0.875 040219-NRC-17 Smear GETR 10.9 2.0 0.010 0.019 13 0.843 040219-NRC-B Smear VBWR 27 27 1.000 040219-NRC-C Smear VBWR 45 45 1.000 040219-NRC-D Smear VBWR 179 0.031 0.093 179.1 0.999 040219-NRC-K Smear VBWR 380 1.10 381.1 0.997 040219-NRC-L Smear VBWR 2,490 11.5 79.8 2,581 0.965 040219-NRC-M Smear VBWR 157 8.1 165 0.951 040219-NRC-N Smear VBWR 168 11.6 180 0.935 040219-NRC-O Smear VBWR 4,700 6.2 1.26 0.23 0.60 4,708 0.998 040219-NRC-P Smear VBWR 215 1.5 8.1 225 0.957 040219-GETR-A Smear GETR 13.9 13.9 1.000

VNC EVESR, VBWR, and GETR Buildings Survey Report A-8 5334-SR-02-0 Table A.7. ORISE and NRC Sample Results and Activity Ratios a Sample ID Matrix Building Cs-137 Co-60 Ni-63 Sr-90 Tc-99 U-234 U-238 Am-241 Pu-238 Pu-239 Am-241/

Pu-238 C-14 H-3 Total Sample Activity Cs-137:

TA 040219-GETR-B Smear GETR 640 1.2 641 0.998 040219-GETR-C Smear GETR 1,300 1,300 1.000 040219-GETR-D Smear GETR 3,700 3,700 1.000 040219-Inside-Step-Off-Pad Smear GETR 17.2 1.1 18.3 0.938 ORISE Samples 5334W0001 Water VBWR 65,000 11.4 520 1,000 4.63 0.51 2.22 2,500 69,039 0.942 5334W0002 Solids from W0001 VBWR 25,000 130 1,200 19.3 2.1 6.4 26,358 0.948 5334R0001 Smear EVESR 8.1 4.5 12.6 0.643 5334R0002 Smear EVESR 9.9 31 40.9 0.242 5334R0003 Smear EVESR 195 0.016 195.0 1.000 5334R0004 Smear EVESR 11.1 11.1 1.000 5334R0005 Smear EVESR 890 890.0 1.000 5334R0006 Smear EVESR 38.7 38.7 1.000 5334R0007 Smear EVESR 50.9 23.4 74.3 0.685 5334R0008 Smear EVESR 55.2 55.2 1.000 5334R0009 Smear VBWR 7.3 7.3 1.000 5334R0010 Smear VBWR 7.8 7.8 1.000 a Units are pCi for NRC samples, pCi/L for water sample, pCi/g for soil samples, and pCi/sample for smear and solids samples.

-- = Analysis was not performed or that the reported analytical concentrations were less than 2 standard deviations for NRC samples or less than MDC for ORISE samples and the respective ROCs were not included in the Total Sample Activity summation.

VNC EVESR, VBWR, and GETR Buildings Survey Report A-9 5334-SR-02-0 Table A.8. Water, Solids, and Soil Sample Results for Gross Alpha and Beta Reactor Building Sample ID Description Alpha Beta Conc. a TPU b MDC Conc.

TPU MDC VBWR 5334W0001 Water 11

+/-

23 19 44,000

+/-

4,900 14 5334W0002 Solids

+/-

Other 5334S0017 Soil 5.7

+/-

2.9 3.9 11.9

+/-

2.8 3.3 5334S0018 Soil 6.4

+/-

3.0 3.9 10.3

+/-

2.6 3.3 a 5334W0001 units are pCi/L. 5334W0002 units are pCi/sample. 5334S0017 and 5334S0018 units are pCi/g.

b Uncertainties are based on total propagated uncertainties (TPU) at the 95% confidence level.

MDC = minimum detectable concentrations.

-- = Not analyzed and/or calculated.

Bold font = Results greater than MDC.

Table A.9. Water, Solids, and Soil Sample Results for Cs-137, Co-60, H-3, and C-14 Reactor Building Sample ID Description Cs-137 Co-60 H-3 C-14 Conc. a TPU b MDC Conc.

TPU MDC Conc.

TPU MDC VBWR 5334W0001 Water 65,000

+/-

4,800 33 c 11.4

+/-

2.5 4.5 2,500

+/-

300 240 3

+/-

31 53 5334W0002 Solids 25,000

+/-

2,200 27 c 130

+/-

11 8

+/-

Other 5334S0017 Soil 0.009

+/-

0.012 0.034

-0.002

+/-

0.020 0.038

+/-

5334S0018 Soil

-0.001

+/-

0.037 0.078 0.028

+/-

0.040 0.095

+/-

a 5334W0001 units are pCi/L. 5334W0002 units are pCi/sample. 5334S0017 and 5334S0018 units are pCi/g.

b Uncertainties are based on total propagated uncertainties (TPU) at the 95% confidence level.

c Due to the elevated activity levels of Cs-137 for Samples 5334W0001 and 5334W0002, the reported MDC values were not rounded in order to accurately reflect the instrument MDC.

Bold Font = Results greater than MDC are bolded.

-- = Not analyzed and/or calculated.

MDC = minimum detectable concentrations.

VNC EVESR, VBWR, and GETR Buildings Survey Report A-10 5334-SR-02-0 Table A.10. Water, Solids, and Soil Sample Results for Ni-63, Sr-90, Tc-99, and Pu-241 Reactor Building Sample ID Description Ni-63 Sr-90 Tc-99 Pu-241 Conc. a TPU b MDC Conc.

TPU MDC Conc.

TPU MDC VBWR 5334W0001 Water 520

+/-

40 36 1,000

+/-

43 8

33

+/-

26 42 0

+/-

25 44 5334W0002 Solids

+/-

1,200

+/-

32 1

+/-

26.9

+/-

6.1 7.1 Other 5334S0017 Soil

+/-

5334S0018 Soil

+/-

a 5334W0001 units are pCi/L. 5334W0002 units are pCi/sample. 5334S0017 and 5334S0018 units are pCi/g.

b Uncertainties are based on total propagated uncertainties (TPU) at the 95% confidence level.

MDC = minimum detectable concentrations.

Bold Font = Results greater than MDC are bolded.

-- = Not analyzed and/or calculated.

Table A.11. Water, Solids, and Soil Sample Results for Pu-238, Pu-239/240, Am-241, Cm-243/244 Reactor Building Sample ID Description Pu-238 Pu-239/240 Am-241 Cm-243/244 Conc. a TPU b MDC Conc.

TPU MDC Conc.

TPU MDC VBWR 5334W0001 Water 0.51

+/-

0.25 0.31 2.22

+/-

0.53 0.31 4.63

+/-

0.76 0.07 0.000

+/-

0.045 0.069 5334W0002 Solids 2.10

+/-

0.28 0.01 6.40

+/-

0.73 0.01 19.3

+/-

1.8 0.0 0.106

+/-

0.041 0.012 Other 5334S0017 Soil

+/-

-0.014

+/-

0.021 0.054

+/-

5334S0018 Soil

+/-

-0.062

+/-

0.037 0.085

+/-

a 5334W0001 units are pCi/L. 5334W0002 units are pCi/sample. 5334S0017 and 5334S0018 units are pCi/g.

b Uncertainties are based on total propagated uncertainties (TPU) at the 95% confidence level.

MDC = minimum detectable concentrations.

Bold Font = Results greater than MDC are bolded.

-- = Not analyzed and/or calculated.

VNC EVESR, VBWR, and GETR Buildings Survey Report 5334-SR-02-0 APPENDIX B:

SURVEY AND ANALYTICAL PROCEDURES

VNC EVESR, VBWR, and GETR Buildings Survey Report B-1 5334-SR-02-0 B.1. PROJECT HEALTH AND SAFETY ORISE performed all survey activities in accordance with the Oak Ridge Associated Universities (ORAU) Radiation Protection Manual, the ORAU Health and Safety Manual, and the ORAU Radiological and Environmental Survey Procedures Manual (ORAU 2014, ORAU 2016b, 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.

Field survey activities were conducted in accordance with procedures from the following documents:

ORAU Radiological and Environmental Survey Procedures Manual (ORAU 2016)

ORAU Radiological and Environmental Analytical Laboratory Procedures Manual (ORAU 2020)

ORAU Environmental Services and Radiation Training Quality Program Manual (ORAU 2019)

The procedures contained in these manuals were developed to meet the requirements of U.S. Department of Energy (DOE) Order 414.1D and the U.S. Nuclear Regulatory Commission (NRC) Quality Assurance Manual for the Office of Nuclear Material Safety and Safeguards and contain measures to assess processes during their performance.

VNC EVESR, VBWR, and GETR Buildings Survey Report B-2 5334-SR-02-0 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 Scans for elevated gamma radiation were performed by passing the detector slowly over the surface.

The distance between the detector and surface was maintained at a minimum. Specific scan minimum detectable concentrations (MDCs) for the sodium iodide (NaI) scintillation detectors scintillation detectors were not determined, as the instruments were used solely as a qualitative means to identify elevated gamma 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.

B.3.2 SURFACE ACTIVITY MEASUREMENTS Measurements of gross alphas and beta surface activity levels were performed using hand-held detectors coupled to portable ratemeter-scalers. Counts (cpm), which were integrated over 1-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. Using the analytical data obtained from the water sample, a weighted alpha and beta efficiency was determined. See Table B.1 for weighted efficiencies.

VNC EVESR, VBWR, and GETR Buildings Survey Report B-3 5334-SR-02-0 Table B.1. Weighted Efficiencies Nuclide Half-Life (yrs)

Total Intensity Mean E (keV)

Max. E (keV)

Relative Fraction i

s t

Beta Emitters Cs-137 3.01E+01 1.00 187 549 0.941 0.52 0.50 0.24 Co-60 5.27E+00 1.00 96 318 0.00 0.43 0.25 0.00 H-3 1.23E+01 1.00 6

19 0.036 0.00 0.25 0.00 Sr-90 2.88E+01 1.00 196 546 0.01 0.52 0.50 0.00 Tc-99 2.11E+05 1.00 85 294 0.00 0.42 0.25 0.00 C-14 5.70E+03 1.00 50 156 0.00 0.27 0.25 0.00 Ni-63 1.01E+02 1.00 17 67 0.01 0.00 0.25 0.00 Pu-241 1.43E+01 1.00 7

21 0.00 0.00 0.25 0.00 Total Weighted Beta Efficiency for Ludlum Model 44-142: 0.25 Alpha Emitters Pu-238 8.77E+01 1.00 5,486 NA 0.07 0.45 0.25 0.01 Pu-239 2.41E+04 1.00 5,139 NA 0.30 0.47 0.25 0.04 Am-241 4.33E+02 1.00 5,487 NA 0.63 0.45 0.25 0.07 Cm-243 2.89E+01 1.00 5,816 NA 0.00 0.47 0.25 0.00 Total Weighted Alpha Efficiency for Ludlum Model 43-92: 0.11 NA = Not Applicable 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 (instrument efficiency x source efficiency)

G = geometry correction factor (1.0)

The result for the detectors used for all measurements was an alpha static MDC of 84 dpm/100 cm2 (using a background of 2 cpm) and a beta static MDC of 560 dpm/100 cm2 (using a background of 850 cpm).

VNC EVESR, VBWR, and GETR Buildings Survey Report B-4 5334-SR-02-0 B.3.3 WATER SAMPLING A water sample (approximately 1 liter) was collected by ORISE personnel using a clean pipette to transfer water into a new sample container. The container was then labeled and security sealed in accordance with ORISE procedures. ORISE shipped the sample under chain-of-custody to the ORISE laboratory for analysis.

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 13 dpm/100 cm2 for beta.

B.4.2 GAMMA SPECTROSCOPY The smear and soil Samples were analyzed as received. Net material weights were determined, and the samples counted using intrinsic, high purity, germanium detectors coupled to a pulse height analyzer system. Background and Compton stripping, peak search, peak identification, and concentration calculations were performed using computer capabilities inherent in the analyzer system. All total absorption peaks (TAPs) associated with the ROCs were reviewed for consistency of activity. Spectra also were reviewed for other identifiable TAPs. Sample specific gamma spectroscopy MDCs vary across the energy calibration range in accordance to efficiencies, sample quantities, geometries, isotope abundances, Compton background, and count times. Approximate MDCs for example isotopes for samples with a quantity of 1 sample (smears and filters), 1 liter (waters) and grams (soils) are presented in table B.4.2. Count times for smears and waters are typically 1000 minutes, soil samples range from 1 to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> depending on quantity available.

Table B.2. MDCs and Total Absorption Peak Radionuclide TAP (keV)a MDC (pCi/sample)

MDC (pCi/L)

MDC (pCi/g)

Am-241 59.54 4.8 17 0.28 Cs-137 661.66 4.5 9.6 0.32 Eu-152 344.28 11.7 20 0.64 Co-60 1332.49 4.4 5.4 0.25 a kilo electron volt

VNC EVESR, VBWR, and GETR Buildings Survey Report B-5 5334-SR-02-0 B.4.3 ALPHA SPECTROSCOPY Samples were dissolved by a combination of potassium hydrogen fluoride and pyrosulfate fusions.

The fusion cakes were dissolved, and all alpha emitters were co-precipitated on barium sulfate. The barium sulfate was re-dissolved and the contaminants of concern were separated from the other actinides by extraction chromatography utilizing Eichrom Technologies resins, co-precipitated with cerium fluoride, and analyzed using passivated implanted planar silicon detectors, alpha spectrometers, and multichannel analyzers. The alpha spectroscopy detector system calculated an MDC for each individual isotope per sample based on the detector background, counting efficiency, chemical yield, and sample quantity. The typical MDC for samples with a quantity of 1 (total or grams) is approximately 0.01 pCi/sample or pCi/g. Water MDCs vary directly with the quantity analyzed, with a 100 mL sample giving an approximate MDC of 0.15 pCi/L.

B.4.4 PU-241 ANALYSIS Solid, unfiltered aqueous and filtered samples were processed, and all plutonium isotopes were separated from the other actinides using the alpha spectroscopy procedure, AP11. The Pu isotopes were coprecipitated on cerium fluoride and counted with an alpha spectrometry system for chemical yield determination. The sample was then placed in a scintillation cocktail and counted using a liquid scintillation analyzer. The typical MDC for a sample quantity of 0.5 total (smear) is approximately 7 pCi/total. A 100 mL water sample will give an approximate MDC of 36 pCi/L.

B.4.5 SR-90 ANALYSIS Sr-90 concentrations were quantified by total sample dissolution followed by radiochemical separation and counted on a low background proportional counter. Samples were homogenized and dissolved by a combination of potassium hydrogen fluoride and pyrosulfate fusions. The fusion cakes were dissolved and strontium was co-precipitated on lead sulfate. The strontium was separated from residual calcium and lead by precipitating strontium sulfate from Ethylenediaminetetraacetic Acid (EDTA) at a pH of 4.0. Strontium was separated from barium by complexing the strontium in Diethylenetriaminepentaacetic Acid (DTPA) while precipitating barium as barium chromate. The strontium was ultimately converted to strontium carbonate and counted on a low-background gas proportional counter. The typical MDC for a 60-minute count time using this procedure is 0.4 pCi/g for a 1 gram solid sample, 0.7 pCi/sample for a sample quantity of 0.5 total, and 6.6 pCi/L for a 50 mL water sample.

VNC EVESR, VBWR, and GETR Buildings Survey Report B-6 5334-SR-02-0 B.4.6 H-3 AND C-14 ANALYSIS H-3 and C-14 analysis for the smear samples was performed using a material oxidizer and counted by liquid scintillation. The material oxidizer combusts samples in a stream of oxygen gas and passes the products, including H-3 as water vapor and C-14 as carbon dioxide, through a series of catalysts.

The H-3 and C-14 are then captured in succession by trapping scintillation cocktails specific to water and carbon dioxide. The typical MDC for a 60-minute count time using this procedure is approximately 1.0 to 2.5 pCi/g for both isotopes, with a sample quantity of 1 sample (smears).

H-3 analysis in the water sample was determined by distillation using an Allihn condenser. An aliquot of the distillates was added to a scintillation cocktail, and the samples were counted using a liquid scintillation analyzer. A 10 mL water distillation aliquot generates an MDC of approximately 250 pCi/L for a 60 minute count.

C-14 analysis in the water sample was determined by treating the sulfuric acid and potassium permanganate. The sample was heated to release carbon as carbon dioxide, and water vapor was removed by a coil condenser. The carbon dioxide was purged through the system with an inert gas and bubbled through a trapping scintillation cocktail specific to carbon dioxide. A batch yield was used to determine the chemical yield. The C-14 was counted on a liquid scintillation analyzer. The typical MDC is approximately 45 pCi/g for a 25 mL water sample using a 60 minute count.

B.4.7 NI-63 ANALYSIS Ni-63 in environmental samples was precipitated as a nickel/dimethylglyoxime precipitate on an extraction chromatographic resin. Iron was removed from soil, solids, and smear samples prior to the nickel separation using anion exchange chromatography. Samples that contain sufficient amounts of radioactive cobalt were processed through an anion exchange column prior to passing the samples through the Ni resin. Other potential interfering elements were removed from the Ni column with a buffered ammonium citrate solution. Nickel was eluted off the column with dilute nitric acid. The Ni-63 activity was determined via liquid scintillation counting. The typical MDC is approximately 30 pCi/L for a 50 mL water sample using a 60-minute count and 1.5 pCi/sample for a sample quantity of 1 total (smears.)

VNC EVESR, VBWR, and GETR Buildings Survey Report B-7 5334-SR-02-0 B.4.8 TC-99 ANALYSIS Solid samples were leached with dilute nitric acid. The leachates were passed through an extraction chromatographic column containing a resin, which is highly specific for technetium in the pertechnatate form. The technetium was absorbed onto the extraction resin. The resin was added to a scintillation vial containing an appropriate cocktail and counted using a liquid scintillation analyzer.

Water samples were treated as leachates and carried through the same procedure. All interfering beta emitting radionuclides were effectively removed (including C-14, P-32, S-35, Sr-90, Y-90, and Th-234) using a resin under the conditions in this procedure. Tritium may follow technetium because of the absorption of some tritium-labeled compounds by the resin. Possible tritium interferences were eliminated by setting the technetium counting window above the maximum energy for tritium beta particles. The typical MDC is approximately 35 pCi/L for a 50 mL water sample using a 60-minute count and 1.7 pCi/sample for a sample quantity of 1 total (smears.)

B.4.9 DETECTION LIMITS Detection limits, referred to as MDCs, were based on a 95% confidence level. Because of variations in background levels, measurement efficiencies, and contributions from other radionuclides in samples, the detection limits differ from sample to sample and instrument to instrument.

VNC EVESR, VBWR, and GETR Buildings Survey Report 5334-SR-02-0 APPENDIX C:

MAJOR INSTRUMENTATION

VNC EVESR, VBWR, and GETR Buildings Survey Report C-1 5334-SR-02-0 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 GAMMA Ludlum NaI Scintillation Detector Model 44-10, Crystal: 5.1 cm x 5.1 cm (Ludlum Measurements, Inc., Sweetwater, Texas) coupled to: Ludlum Ratemeter-scaler Model 2221 (Ludlum Measurements, Inc., Sweetwater, Texas)

C.1.2 ALPHA Ludlum ZnS(Ag) Scintillation Detector Model 43-92, 100 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 Plastic Scintillation Detector Model 44-142, 100 cm2 physical area, 1.2 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, Connecticut)

Used in conjunction with:

Eclipse Software Dell Workstation (Canberra, Meriden, Connecticut)

High-Purity, Extended Range Intrinsic Detector CANBERRA/Tennelec Model No: ERVDS30-25195 Canberra Lynx Multichannel Analyzer Canberra Gamma-Apex Software (Canberra, Meriden, Connecticut)

Used in conjunction with:

Lead Shield Model G-11 (Nuclear Lead, Oak Ridge, Tennessee) and

VNC EVESR, VBWR, and GETR Buildings Survey Report C-2 5334-SR-02-0 Dell Workstation (Canberra, Meriden, Connecticut)

High-Purity, Intrinsic Detector EG&G ORTEC Model No. GMX-45200-5 Canberra Lynx Multichannel Analyzer Canberra Gamma-Apex Software (Canberra, Meriden, Connecticut)

Used in conjunction with:

Lead Shield Model G-11 (Nuclear Lead, Oak Ridge, Tennessee) and Dell Workstation (Canberra, Meriden, Connecticut)

High-Purity, Intrinsic Detector EG&G ORTEC Model No. GMX-30P4 Canberra Lynx Multichannel Analyzer Canberra Gamma-Apex Software (Canberra, Meriden, Connecticut)

Used in conjunction with:

Lead Shield Model G-11 (Nuclear Lead, Oak Ridge, Tennessee) and Dell Workstation (Canberra, Meriden, Connecticut)

High-Purity, Intrinsic Detector EG&G ORTEC Model No. CDG-SV-76/GEM-MX5970-S Canberra Lynx Multichannel Analyzer Canberra Gamma-Apex Software (Canberra, Meriden, Connecticut)

Used in conjunction with:

Lead Shield Model G-11 (Nuclear Lead, Oak Ridge, Tennessee) and Dell Workstation (Canberra, Meriden, Connecticut)

CANBERRA (Mirion Technologies)

Alpha AnalystTM Integrated Alpha Spectrometer System with A450-18AM Alpha Passivated Implanted Planar Silicon detectors CANBERRA Apex-Alpha software v.1.4.0.71 Used in conjunction with:

Dell Workstation Liquid Scintillation Counter Perkin Elmer Tricarb 5110TR (Perkin Elmer, Waltham, Massachusetts)

VNC EVESR, VBWR, and GETR Buildings Survey Report 5334-SR-02-0 APPENDIX D:

RADIOLOGICAL AND ENVIRONMENTAL SCIENCES LABORATORY CONFIRMATORY MEASUREMENT REPORT

U. S. DEPARTMENT OF ENERGY - IDAHO OPERATIONS OFFICE RADIOLOGICAL AND ENVIRONMENTAL SCIENCES LABORATORY

1RUWK%RXOHYDUG06,GDKR)DOOV,'

Page 1 of 1 CONFIRMATORY MEASUREMENT REPORT FOR U.S. NUCLEAR REGULATORY COMMISSION 11545 Rockville Pike, MS T-5 A10 Rockville, Maryland 20852 This report is authorized by the RESL Senior Technical Manager for Chemistry (STM-C). Information regarding the technical aspects of this report may be obtained from Mr. David S. Sill, STM-C at: sillds@id.doe.gov or 208-526-8031.

Approved By:

David S. Sill, STM-C DOE-ID, RESL This report shall not be reproduced, except in full, unless written permission has been obtained from RESL. This report may contain information that is CONFIDENTIAL and subject to legal privileges. If you are not the intended recipient, do not read, use, disseminate, distribute or copy this report. If you have received this report in error, please notify the sender immediately and delete this report.

The results listed in this report are only applicable to the aliquot(s) taken from the sample(s) as received.

The sample information is logged into the sample analysis database as received; RESL is not responsible for the validity of the data provided by the customer.

The sample(s) are analyzed in the same condition as received. RESL assumes no responsibility for the sampling, handling, preservation, or transportation of samples provided for analyses.

All analytical radiochemistry was performed at RESL facilities by qualified personnel using current validated technical procedures that are directly applicable to the specific analyses.

Any additions to, deviations, or exclusions from the procedure or process are noted as such in the report.

Radiological & Environmental Sciences Laboratory VNC EVESR, VBWR, and GETR Buildings Survey Report D-1 5334-SR-02-0

Sample ID: 040219-GETR-A Matrix: Smear Site Name: GETR

Contact:

Stephanie Anderson Nuclide Results Co-60 2 +/- 3 E-1 pCi Cs-137 1.39 +/- 0.11 E1 pCi Fe-55 2 +/- 47 E-2 pCi Ni-63

-2 +/- 4 E-1 pCi Sample ID: 040219-GETR-B Matrix: Smear Site Name: GETR

Contact:

Stephanie Anderson Nuclide Results Co-60 8 +/- 4 E-1 pCi Cs-137 6.4 +/- 0.4 E2 pCi Tc-99 1.2 +/- 0.3 E0 pCi Sample ID: 040219-GETR-C Matrix: Smear Site Name: GETR

Contact:

Stephanie Anderson Nuclide Results Co-60 1.1 +/- 0.7 E0 pCi Cs-137 1.30 +/- 0.08 E3 pCi Sr-90 1 +/- 3 E-1 pCi Sample ID: 040219-GETR-D Matrix: Smear Site Name: GETR

Contact:

Stephanie Anderson Nuclide Results Am-241/Pu-238

-1.8 +/- 1.8 E-3 pCi Cm-244

-1.8 +/- 1.8 E-3 pCi Samples Approved by: _______________________________________________________________

ACTIVITIES ARE AS OF:

UNCERTAINTIES ARE ONE SIGMA 05/06/2019 Department of Energy Radiological & Environmental Sciences Laboratory NUCLEAR REGULATORY COMMISSION Page 1 of 10 Date: 5/8/2019 VNC EVESR, VBWR, and GETR Buildings Survey Report D-2 5334-SR-02-0

Sample ID: 040219-GETR-D Co-60 2.6 +/- 1.3 E0 pCi Cs-137 3.7 +/- 0.3 E3 pCi Pu-239

-1.7 +/- 1.7 E-3 pCi U-234 3 +/- 2 E-3 pCi U-238 1.5 +/- 1.5 E-3 pCi Sample ID: 040219-Inside-Step-Off-Pad Matrix: Smear Site Name: GETR

Contact:

Stephanie Anderson Nuclide Results Co-60 5 +/- 3 E-1 pCi Cs-137 1.72 +/- 0.18 E1 pCi Fe-55 4 +/- 47 E-2 pCi Ni-63 1.1 +/- 0.4 E0 pCi Sample ID: 040219-NRC-10 Matrix: Smear Site Name: GETR

Contact:

Stephanie Anderson Nuclide Results Am-241/Pu-238 3 +/- 2 E-3 pCi Co-60 7 +/- 4 E-1 pCi Cs-137 2.51 +/- 0.15 E3 pCi Pu-239 1.6 +/- 1.2 E-3 pCi U-234 2.7 +/- 0.8 E-2 pCi U-238 1.5 +/- 0.6 E-2 pCi Sample ID: 040219-NRC-11 Matrix: Smear Site Name: GETR

Contact:

Stephanie Anderson Nuclide Results Co-60 5 +/- 3 E-1 pCi Samples Approved by: _______________________________________________________________

ACTIVITIES ARE AS OF:

UNCERTAINTIES ARE ONE SIGMA 05/06/2019 Department of Energy Radiological & Environmental Sciences Laboratory NUCLEAR REGULATORY COMMISSION Page 2 of 10 Date: 5/8/2019 VNC EVESR, VBWR, and GETR Buildings Survey Report D-3 5334-SR-02-0

Sample ID: 040219-NRC-11 Cs-137 1.29 +/- 0.08 E3 pCi Fe-55 8 +/- 9 E-1 pCi Sr-90 1.36 +/- 0.05 E1 pCi Tc-99 3 +/- 4 E-1 pCi Sample ID: 040219-NRC-12 Matrix: Smear Site Name: GETR

Contact:

Stephanie Anderson Nuclide Results Co-60 1.5 +/- 1.0 E0 pCi Cs-137 1.90 +/- 0.19 E3 pCi Fe-55

-1 +/- 9 E-1 pCi Sr-90

-2 +/- 3 E-1 pCi Tc-99 3.1 +/- 0.4 E0 pCi Sample ID: 040219-NRC-13 Matrix: Smear Site Name: GETR

Contact:

Stephanie Anderson Nuclide Results Am-241/Pu-238 8.4 +/- 1.4 E-2 pCi Co-60 1.4 +/- 0.4 E0 pCi Cs-137 2.64 +/- 0.16 E3 pCi Pu-239 8 +/- 5 E-3 pCi U-234 2.9 +/- 0.8 E-2 pCi U-238 2.3 +/- 0.7 E-2 pCi Samples Approved by: _______________________________________________________________

ACTIVITIES ARE AS OF:

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Sample ID: 040219-NRC-14 Matrix: Smear Site Name: GETR

Contact:

Stephanie Anderson Nuclide Results Am-241/Pu-238 1.6 +/- 0.5 E-2 pCi Cm-244 1.8 +/- 1.8 E-3 pCi Co-60 10 +/- 4 E-1 pCi Cs-137 1.27 +/- 0.08 E3 pCi Pu-239 3 +/- 2 E-3 pCi U-234 1.5 +/- 0.5 E-2 pCi U-238 1.0 +/- 0.4 E-2 pCi Sample ID: 040219-NRC-15 Matrix: Smear Site Name: GETR

Contact:

Stephanie Anderson Nuclide Results Co-60 1.3 +/- 0.4 E0 pCi Cs-137 9.8 +/- 0.6 E2 pCi Fe-55 1 +/- 9 E-1 pCi Sr-90 6 +/- 3 E-1 pCi Tc-99 2.6 +/- 0.4 E0 pCi Sample ID: 040219-NRC-16 Matrix: Smear Site Name: GETR

Contact:

Stephanie Anderson Nuclide Results Co-60 1.2 +/- 0.4 E0 pCi Cs-137 8.4 +/- 0.9 E0 pCi Fe-55 2 +/- 9 E-1 pCi Sr-90

-2 +/- 3 E-1 pCi Samples Approved by: _______________________________________________________________

ACTIVITIES ARE AS OF:

UNCERTAINTIES ARE ONE SIGMA 05/06/2019 Department of Energy Radiological & Environmental Sciences Laboratory NUCLEAR REGULATORY COMMISSION Page 4 of 10 Date: 5/8/2019 VNC EVESR, VBWR, and GETR Buildings Survey Report D-5 5334-SR-02-0

Sample ID: 040219-NRC-16 Tc-99

-3 +/- 3 E-1 pCi Sample ID: 040219-NRC-17 Matrix: Smear Site Name: GETR

Contact:

Stephanie Anderson Nuclide Results Am-241/Pu-238 1.8 +/- 1.8 E-3 pCi Cm-244

-1.8 +/- 0.9 E-3 pCi Co-60 2.0 +/- 0.6 E0 pCi Cs-137 1.09 +/- 0.16 E1 pCi Pu-239

-1.7 +/- 0.9 E-3 pCi U-234 1.0 +/- 0.4 E-2 pCi U-238 1.9 +/- 0.5 E-2 pCi Sample ID: 040219-NRC-2 Matrix: Smear Site Name: VBWR

Contact:

Stephanie Anderson Nuclide Results Co-60 3 +/- 3 E-1 pCi Cs-137 1.19 +/- 0.08 E2 pCi Tc-99 1 +/- 3 E-1 pCi Sample ID: 040219-NRC-3 Matrix: Smear Site Name: VBWR

Contact:

Stephanie Anderson Nuclide Results Co-60 2 +/- 2 E-1 pCi Samples Approved by: _______________________________________________________________

ACTIVITIES ARE AS OF:

UNCERTAINTIES ARE ONE SIGMA 05/06/2019 Department of Energy Radiological & Environmental Sciences Laboratory NUCLEAR REGULATORY COMMISSION Page 5 of 10 Date: 5/8/2019 VNC EVESR, VBWR, and GETR Buildings Survey Report D-6 5334-SR-02-0

Sample ID: 040219-NRC-3 Cs-137 1.13 +/- 0.07 E2 pCi Fe-55 2 +/- 9 E-1 pCi Sr-90 4 +/- 4 E-1 pCi Tc-99 4 +/- 5 E-1 pCi Sample ID: 040219-NRC-4 Matrix: Smear Site Name: VBWR

Contact:

Stephanie Anderson Nuclide Results Co-60 3 +/- 2 E-1 pCi Cs-137 1.60 +/- 0.11 E2 pCi Sr-90 4.2 +/- 0.4 E0 pCi Sample ID: 040219-NRC-5 Matrix: Smear Site Name: VBWR

Contact:

Stephanie Anderson Nuclide Results Am-241/Pu-238 3.0 +/- 0.3 E-1 pCi Co-60 7 +/- 12 E-1 pCi Cs-137 3.8 +/- 0.3 E2 pCi Pu-239 1.3 +/- 0.2 E-1 pCi U-234 1.8 +/- 0.6 E-2 pCi U-238 8 +/- 5 E-3 pCi Sample ID: 040219-NRC-6 Matrix: Smear Site Name: VBWR

Contact:

Stephanie Anderson Nuclide Results Am-241/Pu-238 3.1 +/- 0.3 E-1 pCi Co-60 8 +/- 9 E-1 pCi Samples Approved by: _______________________________________________________________

ACTIVITIES ARE AS OF:

UNCERTAINTIES ARE ONE SIGMA 05/06/2019 Department of Energy Radiological & Environmental Sciences Laboratory NUCLEAR REGULATORY COMMISSION Page 6 of 10 Date: 5/8/2019 VNC EVESR, VBWR, and GETR Buildings Survey Report D-7 5334-SR-02-0

Sample ID: 040219-NRC-6 Cs-137 2.42 +/- 0.16 E2 pCi Pu-239 9.8 +/- 1.5 E-2 pCi U-234 1.6 +/- 0.6 E-2 pCi U-238 1.3 +/- 0.5 E-2 pCi Sample ID: 040219-NRC-8 Matrix: Smear Site Name: VBWR

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Stephanie Anderson Nuclide Results Am-241 3.0 +/- 0.3 E0 pCi Co-60 8.5 +/- 1.2 E0 pCi Cs-137 3.7 +/- 0.2 E3 pCi Pu-238 4.0 +/- 0.8 E-1 pCi Pu-239 1.10 +/- 0.17 E0 pCi Pu-241 3.1 +/- 1.8 E0 pCi U-234 2.3 +/- 0.7 E-2 pCi U-238 1.6 +/- 0.6 E-2 pCi Wt% Pu-239 8.8 +/- 1.4 E1 Wt% U-235 8.6 +/- 0.4 E-1 Sample ID: 040219-NRC-9 Matrix: Smear Site Name: VBWR

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Stephanie Anderson Nuclide Results Co-60 7.6 +/- 0.6 E1 pCi Cs-137 1.62 +/- 0.10 E4 pCi Sr-90 1.29 +/- 0.02 E2 pCi Samples Approved by: _______________________________________________________________

ACTIVITIES ARE AS OF:

UNCERTAINTIES ARE ONE SIGMA 05/06/2019 Department of Energy Radiological & Environmental Sciences Laboratory NUCLEAR REGULATORY COMMISSION Page 7 of 10 Date: 5/8/2019 VNC EVESR, VBWR, and GETR Buildings Survey Report D-8 5334-SR-02-0

Sample ID: 040219-NRC-B Matrix: Smear Site Name: VBWR

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Stephanie Anderson Nuclide Results Co-60

-6 +/- 8 E-1 pCi Cs-137 2.7 +/- 0.3 E1 pCi Fe-55 1 +/- 5 E-1 pCi Ni-63 7 +/- 4 E-1 pCi Sample ID: 040219-NRC-C Matrix: Smear Site Name: VBWR

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Stephanie Anderson Nuclide Results Co-60 3 +/- 2 E-1 pCi Cs-137 4.5 +/- 0.4 E1 pCi Tc-99 4 +/- 3 E-1 pCi Sample ID: 040219-NRC-D Matrix: Smear Site Name: VBWR

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Stephanie Anderson Nuclide Results Am-241/Pu-238 9.3 +/- 1.3 E-2 pCi Cm-244

-1.8 +/- 0.9 E-3 pCi Co-60 6 +/- 7 E-1 pCi Cs-137 1.79 +/- 0.13 E2 pCi Pu-239 3.1 +/- 0.7 E-2 pCi U-234 4 +/- 3 E-3 pCi U-238

-1.5 +/- 0.7 E-3 pCi Samples Approved by: _______________________________________________________________

ACTIVITIES ARE AS OF:

UNCERTAINTIES ARE ONE SIGMA 05/06/2019 Department of Energy Radiological & Environmental Sciences Laboratory NUCLEAR REGULATORY COMMISSION Page 8 of 10 Date: 5/8/2019 VNC EVESR, VBWR, and GETR Buildings Survey Report D-9 5334-SR-02-0

Sample ID: 040219-NRC-K Matrix: Smear Site Name: VBWR

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Stephanie Anderson Nuclide Results Co-60 1.10 +/- 0.19 E0 pCi Cs-137 3.8 +/- 0.2 E2 pCi Tc-99 4 +/- 3 E-1 pCi Sample ID: 040219-NRC-L Matrix: Smear Site Name: VBWR

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Stephanie Anderson Nuclide Results Co-60 1.15 +/- 0.08 E1 pCi Cs-137 2.49 +/- 0.15 E3 pCi Sr-90 7.98 +/- 0.16 E1 pCi Sample ID: 040219-NRC-M Matrix: Smear Site Name: VBWR

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Stephanie Anderson Nuclide Results Co-60 4 +/- 4 E-1 pCi Cs-137 1.57 +/- 0.10 E2 pCi Sr-90 8.1 +/- 0.4 E0 pCi Sample ID: 040219-NRC-N Matrix: Smear Site Name: VBWR

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Stephanie Anderson Nuclide Results Co-60 1.2 +/- 0.6 E0 pCi Cs-137 1.68 +/- 0.14 E2 pCi Fe-55 2 +/- 5 E-1 pCi Samples Approved by: _______________________________________________________________

ACTIVITIES ARE AS OF:

UNCERTAINTIES ARE ONE SIGMA 05/06/2019 Department of Energy Radiological & Environmental Sciences Laboratory NUCLEAR REGULATORY COMMISSION Page 9 of 10 Date: 5/8/2019 VNC EVESR, VBWR, and GETR Buildings Survey Report D-10 5334-SR-02-0

Sample ID: 040219-NRC-N Ni-63 1.16 +/- 0.10 E1 pCi Sample ID: 040219-NRC-O Matrix: Smear Site Name: VBWR

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Stephanie Anderson Nuclide Results Am-241 1.26 +/- 0.13 E0 pCi Cm-244 1.8 +/- 1.8 E-3 pCi Co-60 6.2 +/- 0.6 E0 pCi Cs-137 4.7 +/- 0.3 E3 pCi Pu-238 2.3 +/- 0.2 E-1 pCi Pu-239 6.0 +/- 0.6 E-1 pCi Pu-241 2.5 +/- 1.7 E0 pCi U-234 6 +/- 3 E-3 pCi U-238 4 +/- 3 E-3 pCi Wt% Pu-239 8.8 +/- 1.2 E1 Wt% U-235 1.07 +/- 0.05 E0 Sample ID: 040219-NRC-P Matrix: Smear Site Name: VBWR

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Stephanie Anderson Nuclide Results Co-60 1.5 +/- 0.2 E0 pCi Cs-137 2.15 +/- 0.13 E2 pCi Sr-90 8.1 +/- 0.4 E0 pCi Samples Approved by: _______________________________________________________________

ACTIVITIES ARE AS OF:

UNCERTAINTIES ARE ONE SIGMA 05/06/2019 Department of Energy Radiological & Environmental Sciences Laboratory NUCLEAR REGULATORY COMMISSION Page 10 of 10 Date: 5/8/2019 VNC EVESR, VBWR, and GETR Buildings Survey Report D-11 5334-SR-02-0

ML21116A132

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