ML25149A031
| ML25149A031 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 05/01/2025 |
| From: | Bailey E Oak Ridge Institute for Science & Education |
| To: | Amy Snyder Reactor Decommissioning Branch |
| References | |
| DCN: 5365-TR-01-0, 22-004 | |
| Download: ML25149A031 (1) | |
Text
100 ORAU Way
- Oak Ridge
- TN 37830
- orise.orau.gov May 1, 2025 Ms. Amy Snyder Senior Project Manager U.S. Nuclear Regulatory Commission 11545 Rockville Pike Mail Stop A10M Rockville, MD 20852
SUBJECT:
ANALYTICAL DATA
SUMMARY
REPORT FOR SAMPLES COLLECTED FROM THE MULTIPURPOSE HANDLING FACILITY AT THE SAN ONOFRE NUCLEAR GENERATING STATION, SAN CLEMENTE, CALIFORNIA DOCKET NUMBERS 50-361 AND 50-362; RFTA NO.22-004; DCN: 5365-TR-01-0
Dear Ms. Snyder:
The Oak Ridge Institute for Science and Education (ORISE) is pleased to provide the enclosed final report summarizing analytical results for samples collected from the Multipurpose Handling Facility at the San Onofre Nuclear Generating Station in San Clemente, California. Comments on the draft report have been addressed in this final version.
Please feel free to contact me at Erika.Bailey@orau.org if you have any comments or concerns.
Sincerely, Erika N. Bailey Survey Projects Manager ORISE DAK:enb electronic distribution:
N. Fuguet, NRC L. Gersey, NRC G. Chapman, NRC S. Anderson, NRC D. King, ORISE D. Hagemeyer, ORISE File/5365
100 ORAU Way
- Oak Ridge
- TN 37830
- orise.orau.gov ANALYTICAL DATA
SUMMARY
REPORT FOR SAMPLES COLLECTED FROM THE MULTIPURPOSE HANDLING FACILITY AT THE SAN ONOFRE NUCLEAR GENERATING STATION, SAN CLEMENTE, CALIFORNIA D. A. King ORISE FINAL REPORT Prepared for the U.S. Nuclear Regulatory Commission May 2025 DCN 5365-TR-01-0 Further dissemination authorized to NRC only; other requests shall be approved by the originating facility or higher NRC programmatic authority.
100 ORAU Way
- Oak Ridge
- TN 37830
- orise.orau.gov 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.
SONGS MPHF Sample Report 5365-TR-01-0 ANALYTICAL DATA
SUMMARY
REPORT FOR SAMPLES COLLECTED FROM THE MULTIPURPOSE HANDLING FACILITY AT THE SAN ONOFRE NUCLEAR GENERATING STATION, SAN CLEMENTE, CALIFORNIA FINAL REPORT Prepared by D. A. King ORISE May 2025 Prepared for the U.S. Nuclear Regulatory Commission This document was prepared for the U.S. Nuclear Regulatory Commission (NRC) by the Oak Ridge Institute for Science and Education (ORISE) through Interagency Agreement 31310021S0033 between the NRC and the U.S. Department of Energy (DOE). ORISE is managed by Oak Ridge Associated Universities (ORAU) under DOE contract number DE-SC0014664.
SONGS MPHF Sample Report i
5365-TR-01-0 ANALYTICAL DATA
SUMMARY
REPORT FOR SAMPLES COLLECTED FROM THE MULTIPURPOSE HANDLING FACILITY AT THE SAN ONOFRE NUCLEAR GENERATING STATION, SAN CLEMENTE, CALIFORNIA Prepared by:
Date:
5/1/2025 D. A. King, CHP, PMP, Sr. Health Physicist ORISE Reviewed by:
Date:
5/1/2025 E. N. Bailey, Survey Projects Manager ORISE Reviewed by:
Date:
5/1/2025 P. H. Benton, Quality Manager ORISE Reviewed and approved for release by:
Date:
5/1/2025 D. A. Hagemeyer, Sr. Director, IEAV ORISE FINAL REPORT May 2025
SONGS MPHF Sample Report ii 5365-TR-01-0 CONTENTS FIGURES.......................................................................................................................................................... iii TABLES............................................................................................................................................................. iii ACRONYMS & ABBREVIATIONS........................................................................................................... iv
- 1. INTRODUCTION....................................................................................................................................... 1
- 2. SITE DESCRIPTION................................................................................................................................. 1
- 3. METHOD...................................................................................................................................................... 2 3.1 Sampling and Analysis..................................................................................................................... 2 3.2 Radionuclides of Concern and Release Guidelines.................................................................... 3
- 4. RESULTS....................................................................................................................................................... 6
- 5. DISCUSSION................................................................................................................................................ 8
- 6. REFERENCES............................................................................................................................................. 9 APPENDIX A: RESL ANALYTICAL RESULTS APPENDIX B: GEL ANALYTICAL RESULTS
SONGS MPHF Sample Report iii 5365-TR-01-0 FIGURES Figure 2.1. SONGS Site Layout....................................................................................................................... 2 Figure 4.1. Survey Unit C1003-201F1 Concrete Sample Locations........................................................... 6 Figure 4.2. Survey Unit A1003-201F1 Soil Sample Locations.................................................................... 7 TABLES Table 3.1. Applicable Operational DCGLs.................................................................................................... 4 Table 3.2. NUREG-1757, Vol. 2., Rev. 2 Appendix Screening Values..................................................... 4 Table 4.1. Confirmatory Results for Detected ROCs.................................................................................. 8
SONGS MPHF Sample Report iv 5365-TR-01-0 ACRONYMS & ABBREVIATIONS Am-241 americium-241 AMCG average member of the critical group BcDCGL Base Case DCGL C-14 carbon-14 CFR Code of Federal Regulations Cm-243 curium-243 Cm-244 curium-244 Co-60 cobalt-60 cpm counts per minute Cs-134 cesium-134 Cs-137 cesium-137 DCGL derived concentration guideline level EDCGL estimated derived concentration guideline level Eu-152 europium-152 Eu-154 europium-154 Fe-55 iron-55 FSS final status survey H-3 tritium HTD hard-to-detect LTP License Termination Plan MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual MPHF Multipurpose Handling Facility mrem/yr millirem per year Nb-94 niobium-94 Ni-59 nickel-59 Ni-63 nickel-63 Np-237 neptunium-237 NRC U.S. Nuclear Regulatory Commission OpDCGL Operational DCGL OpDCGLwf Operational DCGL for basement/walls floor OpDCGLss Operational DCGL for surface soils ORAU Oak Ridge Associated Universities ORISE Oak Ridge Institute for Science and Education Pu-238 plutonium-238 Pu-239 plutonium-239 Pu-240 plutonium-240 Pu-241 plutonium-241 Pu-242 plutonium-242 RESL Radiological and Environmental Sciences Laboratory ROC radionuclide of concern Sb-125 antimony-125 SCE Southern California Edison SOF sum-of-fractions SONGS San Onofre Nuclear Generating Station Sr-90 strontium-90 Tc-99 technetium-99 TEDE total effective dose equivalent
SONGS MPHF Sample Report 1
5365-TR-01-0 ANALYTICAL DATA
SUMMARY
REPORT FOR SAMPLES COLLECTED FROM THE MULTIPURPOSE HANDLING FACILITY AT THE SAN ONOFRE NUCLEAR GENERATING STATION, SAN CLEMENTE, CALIFORNIA
- 1. INTRODUCTION The San Onofre Nuclear Generating Station (SONGS) consisted of three pressurized water reactors with a total rated capacity of 2,664 net megawatts electrical. The former Multipurpose Handling Facility (MPHF) was an in-process staging area for the accumulation of low-level solid radioactive waste until it was released for shipment. In addition, the MPHF had the capability to contain a maximum of 18,000 gallons of Class III combustible or non-combustible radioactive liquids in leak-tight containers until released for processing or shipment (ENERCON 2014).
In August of 2024, the U.S. Nuclear Regulatory Commission (NRC) requested that the licensee collect replicate samples at four concrete and four surface soil random locations for confirmatory analysis that were planned as part of the final status survey (FSS) process to demonstrate that the residual radioactivity remaining is within the established release criteria. NRC requested that the Oak Ridge Institute for Science and Education (ORISE) compile the associated analytical data in a formal report. This report summarizes sampling and analysis activities, presents the analytical results, and compares those results to the sites derived concentration guideline levels (DCGLs).
- 2. SITE DESCRIPTION SONGS is located in San Clemente, California, in northern San Diego County adjacent to San Onofre State Beach. The site is approximately 102 kilometers (64 miles) south of Los Angeles and 82 kilometers (51 miles) north-northwest of San Diego. The SONGS site lies entirely within the boundaries of the Marine Corps Base Camp Pendleton under a grant of easement between Southern California Edison (SCE) and the United States Government. The site is bounded on the west by the Pacific Ocean, on the east by Interstate Highway 5, and on both the north and south along the coastline by San Onofre State Beach (ENERCON 2014). Figure 2.1 depicts the layout of the SONGS site and the approximate location of the MPHF.
The MPHF consists of an office building and a radiological controlled area that includes a staging building and an equipment pad. The facility is surrounded by a gated chain link fence and is located at the southern edge of the SONGS owner-controlled area (ENERCON 2014, SCE 2022).
SONGS MPHF Sample Report 2
5365-TR-01-0 Figure 2.1. SONGS Site Layout (ENERCON 2014 with approximate MPHF location added)
- 3. METHOD 3.1 SAMPLING AND ANALYSIS The licensee performed FSS activities of the MPHF in August 2024, which included the collection of both concrete cores and surface soil samples (0-6 inches in depth). The FSS design included the collection of 14 random-start, systematic grid concrete sample locations in survey unit C1003-201F1, a remnant of the concrete basement structure. Of these, 25 percent (4) of the 14 locations were also sampled and forwarded to NRCs laboratory for confirmatory analysis. The FSS design also included the collection of 16 random-start, systematic grid surface soil sample locations in survey unit A1003-201F1. Of these, 25 percent (4) of the 16 locations were also sampled and forwarded to NRCs laboratory for confirmatory analysis.
Approximate location of the MPHF
SONGS MPHF Sample Report 3
5365-TR-01-0 NRC utilizes the Radiological and Environmental Sciences Laboratory (RESL) at the Idaho National Laboratory in Idaho Falls, Idaho. The samples were not dried before being sent to RESL. The sample preparation instructions provided with the concrete cores were to cut, crush/homogenize, and analyze only the first 0.5 inch of each concrete core. Each concrete and soil sample was subject to dry gamma spectrometric analysis to identify and quantify fission and activation products, though naturally occurring radionuclides would also be reported. RESL could also subject sample(s) to additional analysisespecially for hard-to-detect radionuclides (HTDs)if, for example, gamma analysis identified significant contamination (Fuguet 2024). RESL performed no additional analyses.
The licensee sent their FSS samples to GEL Laboratories, LLC (GEL). GEL was provided with the same sample preparation instructions for the concrete cores. All the soil samples were presumed to have been processed using the default procedural methods. GEL performed gamma spectrometry on all eight samples, but also performed a full-suite analysis on one concrete sample (e.g., isotopic plutonium and liquid scintillation for select HTD and other beta-emitters).
3.2 RADIONUCLIDES OF CONCERN AND RELEASE GUIDELINES Per the sites proposed license termination plan (LTP) developed specifically for the purpose of this at risk activity, Base Case DCGLs (BcDCGLs) were developed to represent a residual radioactive contamination level, above background, which would result in a total effective dose equivalent (TEDE) of 25 millirem per year (mrem/yr) to an average member of the critical group (AMCG).
Each radionuclide-specific BcDCGL is equivalent to the level of residual radioactivity (above background levels) that could, when considered independently, result in a TEDE of 25 mrem/yr to the AMCG from a given media. To ensure that the summation of dose from each source term, or media, is 25 mrem/year or less after all FSS is completed, the BcDCGLs are further reduced to Operational DCGLs (OpDCGLs). Table 3.1 presents the OpDCGLs for basement walls/floor (OpDCGLwf) and for surface soils (OpDCGLss) for the radionuclides of concern (ROCs) as presented in the LTP (SCE 2024).
SONGS MPHF Sample Report 4
5365-TR-01-0 Table 3.1. Applicable Operational DCGLs a ROC BFM Wall/Floor DCGL (OpDCGLwf) for All Basements Except for Containment (pCi/m2)a Surface Soil (0.15 m)
DCGL (OpDCGLss)
(pCi/g)b Carbon-14 (C-14) 6.743E+05 2.412E+01 Cobalt-60 (Co-60) 2.745E+05 1.907E+00 Cesium-137 (Cs-137) 7.328E+05 7.084E+00 aReproduced from Table 5-7 in SCE 2024 bReproduced from Table 5-9 in SCE 2024 DCGL = derived concentration guideline level ROC = radionuclide of concern BFM = basement fill model pCi/g = picocuries per gram pCi/m2 = picocuries per square meter For completeness, Table 3.2 presents default screening values from NUREG-1757, Vol. 2, Rev. 2 Table H.1 (surfaces) and Table H.2 (soil) (NRC 2022). Default surface screening values units have been converted from dpm/100 cm2 to pCi/m2 to match those in the proposed LTP. A comparison shows that the sites structural surface values are orders of magnitude lower than (i.e., more conservative than) the Table H.1 screening values.
Table 3.2. NUREG-1757, Vol. 2., Rev. 2 Appendix Screening Values ROC Building Surfaces (pCi/m2)a Surface Soil (0.15 m)
(pCi/g)b Carbon-14 (C-14) 1.67E+08 1.2E+01 Cobalt-60 (Co-60) 3.2 E+05 3.8E+00 Cesium-137 (Cs-137) 1.26 E+06 1.1E+01 aFrom Table H.1 in NRC 2022 converted from dpm/100 cm2 to pCi/m2. One dpm is equivalent to 0.0167 Bq; to convert to units of Bq/m2, multiply each value by 1.67. Then multiply by 27.027 to convert to units of pCi/m2 (1Bq =
27.027 pCi).
bFrom Table H.2 in NRC 2022 ROC = radionuclide of concern pCi/g = picocuries per gram pCi/m2 = picocuries per square meter If there are multiple detected site-related ROCs in a sample, the combined dose must be considered.
This is an extremely conservative approach, given DCGLs are typically associated with populations of samples collected across an entire survey unit, but the conservative practice is useful for identifying small areas of elevated activity that may require additional attention. If multiple ROCs are
SONGS MPHF Sample Report 5
5365-TR-01-0 identified in a sample, the sum-of-fractions (SOF) approach would be used to evaluate the total dose from each sample. The SOF calculation is performed as follows:
=
=1 Eq. (3-1)
Where:
Cj is the concentration of ROC j DCGLj is the DCGL for ROC j
SONGS MPHF Sample Report 6
5365-TR-01-0
- 4. RESULTS The four concrete samples from survey unit C1003-201F1 are as follows (note the CV designation for volumetric concrete):
C1003-201F1-CV002-S-NRC - site sample number 02 on Figure 4.1 C1003-201F1-CV003-S-NRC - site sample number 03 on Figure 4.1 C1003-201F1-CV004-S-NRC - site sample number 04 on Figure 4.1 C1003-201F1-CV009-S-NRC - site sample number 09 on Figure 4.1 Figure 4.1. Survey Unit C1003-201F1 Concrete Sample Locations (SDS 2024a)
SONGS MPHF Sample Report 7
5365-TR-01-0 The four soil samples from survey unit A1003-201F1 are as follows (note the SS designation for surface soil):
A1003-201F1-SS005-S-NRC - site sample number 5 on Figure 4.2 A1003-201F1-SS006-S-NRC - site sample number 6 on Figure 4.2 A1003-201F1-SS008-S-NRC - site sample number 8 on Figure 4.2 A1003-201F1-SS015-S-NRC-site sample number 15 on Figure 4.2 Figure 4.2. Survey Unit A1003-201F1 Soil Sample Locations (SDS 2024b)
Appendix A presents RESLs analytical results, and Appendix B presents respective analytical results from GEL. Table 4.1 condenses the RESL results to only the detected ROCs. Appendix A shows that naturally occurring radionuclides, such as Bi-214 and Ac-228, are also detected, though these analytes are expected to be present in concrete and soil, and reported concentrations are unremarkable. Detected Co-60 and Cs-137 values in three concrete samples (CV002, CV003, and CV009) suggest the presence of contamination, though the values are a small fraction of respective DCGLs. As with naturally occurring radionuclides, the detected ROC results are unremarkable. No
SONGS MPHF Sample Report 8
5365-TR-01-0 detections of ROCs were reported for the confirmatory soil samples. Sum-of-fractions calculations were unnecessary.
GEL results presented in Appendix B show that no ROCs were detected in any of the eight samples, including HTDs, plutonium, etc., in concrete sample CV004. GEL provided detection decisions in their report in the form of a U-flagit is standard practice to assign a U-flag when the reported result is less than the method detection limit. RESL did not flag their own data, so all RESL results less than or equal to the reported 2-sigma error were assigned a U-flag (non-detected),
or indistinguishable from instrument background with 95 percent confidence. This approach helps the data assessment process by eliminating inconsequential results from further consideration.
Although the RESL and GEL gamma spectroscopy libraries are different, i.e., different analytes are reported by each laboratory, each lab reported analytical results for each of the ROCs listed in Table 3.1. There is considerable overlap in the analytical results, and the 2-sigma errors are similar, suggesting similar reporting confidence.
Table 4.1. Confirmatory Results for Detected ROCs Sample ID Nuclide Resultsa (pCi/g) 2 Errora Resultsb,c (pCi/m2) 2 Error Flag OpDCGLwf (pCi/m2)
C1003-201F1-CV002-S-NRC Cs-137 0.037 0.008 1,200 250
=
7.328E+05 C1003-201F1-CV003-S-NRC Co-60 0.039 0.022 1,200 700
=
2.745E+05 C1003-201F1-CV003-S-NRC Cs-137 0.122 0.015 3,900 480
=
7.328E+05 C1003-201F1-CV009-S-NRC Co-60 0.017 0.010 540 320
=
2.745E+05 aValues rounded to the nearest thousandth; calculations were performed with full result.
bSignificant figures for the measured or calculated value are reported to the same level of precision as the uncertainty.
cAnalytical results were converted from units of pCi/g to pCi/m2 assuming a concrete density of 2.5 g/cm3 and the sample depth of 1.27 cm (0.5 in).
= represents a detected value (> 2 Error)
- 5. DISCUSSION These results show de minimus ROC concentrations in three of the four concrete samples and no detected ROC concentrations in the four soil samples. Reported concentrations are well below proposed OpDCGLwf values and the default screening values in NUREG-1757, Vol. 2, Rev. 2 (NRC 2022). RESL (NRC) and GEL (licensee) results generally agree given the lack of significant ROC activity and similar 2-sigma reporting errors.
SONGS MPHF Sample Report 9
5365-TR-01-0
- 6. REFERENCES ENERCON 2014. SONGS Units 2 and 3 Environmental Impact Evaluation. Revision 0. Enercon Services, Inc. January 29.
Fuguet 2024.
Subject:
FSS Samples from SONGS SDS Shipment C-24-020. Email from Nathan Fuguet (NRC) to Shane Steidley (RESL). September 17.
NRC 2022. Consolidated Decommissioning Guidance: Characterization, Survey, and Determination of Radiological Criteria. NUREG-1757, Volume 2, Revision 2. U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards. Washington, DC. July.
ORAU 2024. ORAU Environmental Services and Radiation Training Quality Program Manual. Oak Ridge Associated Universities. Oak Ridge, Tennessee. December 11.
SCE 2022. San Onofre Nuclear Generating Station Units 2 & 3 Defueled Safety Analysis Report (DSAR).
Revision 8. Southern California Edison. November.
SCE 2024. San Onofre Nuclear Generating Station License Termination Plan. Revision 0. Southern California Edison. July 24.
SDS 2024a. Radiological Assessments (RA) and Remedial Action Support Surveys (RASS) for Soil for the Multi-Purpose Handling Facility (MPHF) Remnant Concrete Basement Structure, Rev. 3. Survey Area C1003, Survey Unit 201F1. SONGS Decommissioning Solutions. The version provided is not dated.
SDS 2024b. Radiological Assessments (RA) and Remedial Action Support Surveys (RASS) for Soil within the Footprint of the Multi-Purpose Handling Facility (MPHF), Rev. 3. Survey Area A1003, Survey Unit 201F1.
SONGS Decommissioning Solutions. The version provided is not dated.
SONGS MPHF Sample Report 5365-TR-01-0 APPENDIX A: RESL ANALYTICAL RESULTS
SONGS MPHF Sample Report A-1 5365-TR-01-0 SampleID Nuclide Units Results 2 Error Flag A1003-201F1-SS005-S-NRC Zn-65 pCi/g
-0.007 0.010 U
A1003-201F1-SS005-S-NRC Ru-106 pCi/g
-0.03 0.04 U
A1003-201F1-SS005-S-NRC Ba-133 pCi/g
-0.01 0.02 U
A1003-201F1-SS005-S-NRC Ir-192 pCi/g
-0.002 0.005 U
A1003-201F1-SS005-S-NRC Mn-54 pCi/g
-0.001 0.004 U
A1003-201F1-SS005-S-NRC Ag-108m pCi/g
-0.002 0.005 U
A1003-201F1-SS005-S-NRC Cs-134 pCi/g
-0.001 0.009 U
A1003-201F1-SS005-S-NRC Ag-110m pCi/g
-0.002 0.01 U
A1003-201F1-SS005-S-NRC Cs-137 pCi/g 0.001 0.004 U
A1003-201F1-SS005-S-NRC Eu-152 pCi/g 0.002 0.01 U
A1003-201F1-SS005-S-NRC Sb-125 pCi/g 0.01 0.05 U
A1003-201F1-SS005-S-NRC Nb-94 pCi/g 0.00001 0.00005 U
A1003-201F1-SS005-S-NRC Eu-155 pCi/g 0.02 0.06 U
A1003-201F1-SS005-S-NRC Se-75 pCi/g 0.0004 0.001 U
A1003-201F1-SS005-S-NRC Co-57 pCi/g 0.002 0.004 U
A1003-201F1-SS005-S-NRC Co-60 pCi/g 0.003 0.004 U
A1003-201F1-SS005-S-NRC Eu-154 pCi/g 0.016 0.018 U
A1003-201F1-SS005-S-NRC Bi-212 pCi/g 0.44 0.13
=
A1003-201F1-SS005-S-NRC U-238 pCi/g 0.54 0.05
=
A1003-201F1-SS005-S-NRC Ac-228 pCi/g 0.51 0.03
=
A1003-201F1-SS005-S-NRC Bi-214 pCi/g 0.40 0.02
=
A1003-201F1-SS006-S-NRC Eu-152 pCi/g
-0.006 0.008 U
A1003-201F1-SS006-S-NRC Ag-108m pCi/g
-0.004 0.006 U
A1003-201F1-SS006-S-NRC Eu-154 pCi/g
-0.006 0.01 U
A1003-201F1-SS006-S-NRC Nb-94 pCi/g
-0.001 0.003 U
A1003-201F1-SS006-S-NRC Ba-133 pCi/g
-0.004 0.01 U
A1003-201F1-SS006-S-NRC Cs-137 pCi/g
-0.001 0.004 U
A1003-201F1-SS006-S-NRC Ag-110m pCi/g
-0.002 0.01 U
A1003-201F1-SS006-S-NRC Cs-134 pCi/g
-0.002 0.02 U
A1003-201F1-SS006-S-NRC Sb-125 pCi/g 0.001 0.01 U
A1003-201F1-SS006-S-NRC Eu-155 pCi/g 0.002 0.006 U
A1003-201F1-SS006-S-NRC Mn-54 pCi/g 0.002 0.004 U
A1003-201F1-SS006-S-NRC Se-75 pCi/g 0.0002 0.0005 U
A1003-201F1-SS006-S-NRC Co-57 pCi/g 0.0001 0.0002 U
A1003-201F1-SS006-S-NRC Zn-65 pCi/g 0.004 0.006 U
A1003-201F1-SS006-S-NRC Co-60 pCi/g 0.003 0.004 U
A1003-201F1-SS006-S-NRC Ru-106 pCi/g 0.03 0.04 U
A1003-201F1-SS006-S-NRC U-238 pCi/g 0.49 0.11
=
A1003-201F1-SS006-S-NRC Bi-212 pCi/g 0.44 0.06
=
A1003-201F1-SS006-S-NRC Bi-214 pCi/g 0.42 0.03
=
A1003-201F1-SS006-S-NRC Ac-228 pCi/g 0.49 0.03
=
A1003-201F1-SS008-S-NRC Mn-54 pCi/g
-0.004 0.004 U
SONGS MPHF Sample Report A-2 5365-TR-01-0 SampleID Nuclide Units Results 2 Error Flag A1003-201F1-SS008-S-NRC Ag-110m pCi/g
-0.01 0.01 U
A1003-201F1-SS008-S-NRC Se-75 pCi/g
-0.003 0.004 U
A1003-201F1-SS008-S-NRC Eu-154 pCi/g
-0.01 0.01 U
A1003-201F1-SS008-S-NRC Eu-152 pCi/g
-0.01 0.01 U
A1003-201F1-SS008-S-NRC Ba-133 pCi/g
-0.01 0.01 U
A1003-201F1-SS008-S-NRC Nb-94 pCi/g
-0.001 0.003 U
A1003-201F1-SS008-S-NRC Co-57 pCi/g
-0.001 0.004 U
A1003-201F1-SS008-S-NRC Co-60 pCi/g
-0.001 0.003 U
A1003-201F1-SS008-S-NRC Ru-106 pCi/g
-0.03 0.16 U
A1003-201F1-SS008-S-NRC Zn-65 pCi/g
-0.001 0.007 U
A1003-201F1-SS008-S-NRC Cs-137 pCi/g
-0.0005 0.003 U
A1003-201F1-SS008-S-NRC Eu-155 pCi/g 0.001 0.008 U
A1003-201F1-SS008-S-NRC Sb-125 pCi/g 0.002 0.006 U
A1003-201F1-SS008-S-NRC Ag-108m pCi/g 0.003 0.004 U
A1003-201F1-SS008-S-NRC Cs-134 pCi/g 0.0017 0.0020 U
A1003-201F1-SS008-S-NRC U-238 pCi/g 0.47 0.04
=
A1003-201F1-SS008-S-NRC Bi-212 pCi/g 0.45 0.04
=
A1003-201F1-SS008-S-NRC Bi-214 pCi/g 0.34 0.02
=
A1003-201F1-SS008-S-NRC Ac-228 pCi/g 0.44 0.03
=
A1003-201F1-SS015-S-NRC Eu-152 pCi/g
-0.02 0.02 U
A1003-201F1-SS015-S-NRC Cs-134 pCi/g
-0.005 0.006 U
A1003-201F1-SS015-S-NRC Ag-108m pCi/g
-0.004 0.006 U
A1003-201F1-SS015-S-NRC Ru-106 pCi/g
-0.03 0.05 U
A1003-201F1-SS015-S-NRC Sb-125 pCi/g
-0.007 0.01 U
A1003-201F1-SS015-S-NRC Eu-155 pCi/g
-0.007 0.02 U
A1003-201F1-SS015-S-NRC Se-75 pCi/g
-0.002 0.006 U
A1003-201F1-SS015-S-NRC Eu-154 pCi/g
-0.002 0.01 U
A1003-201F1-SS015-S-NRC Nb-94 pCi/g
-0.001 0.005 U
A1003-201F1-SS015-S-NRC Co-57 pCi/g 0.002 0.02 U
A1003-201F1-SS015-S-NRC Ba-133 pCi/g 0.006 0.02 U
A1003-201F1-SS015-S-NRC Co-60 pCi/g 0.001 0.004 U
A1003-201F1-SS015-S-NRC Mn-54 pCi/g 0.001 0.004 U
A1003-201F1-SS015-S-NRC Zn-65 pCi/g 0.003 0.01 U
A1003-201F1-SS015-S-NRC Ag-110m pCi/g 0.01 0.02 U
A1003-201F1-SS015-S-NRC Cs-137 pCi/g 0.004 0.006 U
A1003-201F1-SS015-S-NRC U-238 pCi/g 0.35 0.07
=
A1003-201F1-SS015-S-NRC Bi-212 pCi/g 0.39 0.06
=
A1003-201F1-SS015-S-NRC Bi-214 pCi/g 0.40 0.04
=
A1003-201F1-SS015-S-NRC Ac-228 pCi/g 0.43 0.03
=
C1003-201F1-CV002-S-NRC Eu-155 pCi/g
-0.02 0.03 U
C1003-201F1-CV002-S-NRC Ru-106 pCi/g
-0.11 0.18 U
C1003-201F1-CV002-S-NRC Nb-94 pCi/g
-0.007 0.01 U
SONGS MPHF Sample Report A-3 5365-TR-01-0 SampleID Nuclide Units Results 2 Error Flag C1003-201F1-CV002-S-NRC Ag-108m pCi/g
-0.006 0.01 U
C1003-201F1-CV002-S-NRC Ag-110m pCi/g
-0.02 0.04 U
C1003-201F1-CV002-S-NRC Zn-65 pCi/g
-0.02 0.04 U
C1003-201F1-CV002-S-NRC Se-75 pCi/g
-0.006 0.02 U
C1003-201F1-CV002-S-NRC Co-57 pCi/g
-0.001 0.004 U
C1003-201F1-CV002-S-NRC Cs-134 pCi/g
-0.01 0.02 U
C1003-201F1-CV002-S-NRC Eu-154 pCi/g
-0.01 0.03 U
C1003-201F1-CV002-S-NRC Ba-133 pCi/g
-0.01 0.06 U
C1003-201F1-CV002-S-NRC Eu-152 pCi/g
-0.01 0.08 U
C1003-201F1-CV002-S-NRC Mn-54 pCi/g 0.009 0.02 U
C1003-201F1-CV002-S-NRC Co-60 pCi/g 0.008 0.01 U
C1003-201F1-CV002-S-NRC Sb-125 pCi/g 0.02 0.02 U
C1003-201F1-CV002-S-NRC Cs-137 pCi/g 0.04 0.01
=
C1003-201F1-CV002-S-NRC U-238 pCi/g 0.83 0.14
=
C1003-201F1-CV002-S-NRC Bi-214 pCi/g 0.67 0.09
=
C1003-201F1-CV002-S-NRC Ac-228 pCi/g 0.81 0.07
=
C1003-201F1-CV002-S-NRC Bi-212 pCi/g 0.82 0.06
=
C1003-201F1-CV003-S-NRC Mn-54 pCi/g
-0.02 0.02 U
C1003-201F1-CV003-S-NRC Co-57 pCi/g
-0.01 0.01 U
C1003-201F1-CV003-S-NRC Eu-152 pCi/g
-0.04 0.10 U
C1003-201F1-CV003-S-NRC Zn-65 pCi/g
-0.02 0.06 U
C1003-201F1-CV003-S-NRC Eu-154 pCi/g
-0.03 0.10 U
C1003-201F1-CV003-S-NRC Cs-134 pCi/g
-0.05 0.26 U
C1003-201F1-CV003-S-NRC Se-75 pCi/g 0.003 0.02 U
C1003-201F1-CV003-S-NRC Ba-133 pCi/g 0.02 0.08 U
C1003-201F1-CV003-S-NRC Ag-110m pCi/g 0.03 0.10 U
C1003-201F1-CV003-S-NRC Ru-106 pCi/g 0.05 0.08 U
C1003-201F1-CV003-S-NRC Sb-125 pCi/g 0.05 0.06 U
C1003-201F1-CV003-S-NRC Ag-108m pCi/g 0.02 0.02 U
C1003-201F1-CV003-S-NRC Eu-155 pCi/g 0.04 0.04 U
C1003-201F1-CV003-S-NRC Nb-94 pCi/g 0.02 0.02 U
C1003-201F1-CV003-S-NRC Co-60 pCi/g 0.04 0.02
=
C1003-201F1-CV003-S-NRC U-238 pCi/g 1.1 0.18
=
C1003-201F1-CV003-S-NRC Cs-137 pCi/g 0.12 0.02
=
C1003-201F1-CV003-S-NRC Bi-214 pCi/g 0.80 0.10
=
C1003-201F1-CV003-S-NRC Ac-228 pCi/g 0.87 0.08
=
C1003-201F1-CV003-S-NRC Bi-212 pCi/g 0.86 0.06
=
C1003-201F1-CV004-S-NRC Ru-106 pCi/g
-0.19 0.22 U
C1003-201F1-CV004-S-NRC Mn-54 pCi/g
-0.01 0.02 U
C1003-201F1-CV004-S-NRC Ba-133 pCi/g
-0.17 0.34 U
C1003-201F1-CV004-S-NRC Nb-94 pCi/g
-0.01 0.02 U
C1003-201F1-CV004-S-NRC Zn-65 pCi/g
-0.02 0.06 U
SONGS MPHF Sample Report A-4 5365-TR-01-0 SampleID Nuclide Units Results 2 Error Flag C1003-201F1-CV004-S-NRC Eu-154 pCi/g
-0.01 0.06 U
C1003-201F1-CV004-S-NRC Se-75 pCi/g
-0.01 0.03 U
C1003-201F1-CV004-S-NRC Cs-134 pCi/g
-0.003 0.02 U
C1003-201F1-CV004-S-NRC Sb-125 pCi/g
-0.02 0.16 U
C1003-201F1-CV004-S-NRC Co-57 pCi/g 0.01 0.03 U
C1003-201F1-CV004-S-NRC Eu-152 pCi/g 0.01 0.02 U
C1003-201F1-CV004-S-NRC Co-60 pCi/g 0.01 0.02 U
C1003-201F1-CV004-S-NRC Ag-108m pCi/g 0.009 0.012 U
C1003-201F1-CV004-S-NRC Cs-137 pCi/g 0.013 0.014 U
C1003-201F1-CV004-S-NRC Eu-155 pCi/g 0.03 0.03 U
C1003-201F1-CV004-S-NRC Ag-110m pCi/g 0.06 0.06 U
C1003-201F1-CV004-S-NRC U-238 pCi/g 1.15 0.14
=
C1003-201F1-CV004-S-NRC Ac-228 pCi/g 0.92 0.10
=
C1003-201F1-CV004-S-NRC Bi-214 pCi/g 0.83 0.07
=
C1003-201F1-CV004-S-NRC Bi-212 pCi/g 0.90 0.06
=
C1003-201F1-CV009-S-NRC Eu-152 pCi/g
-0.03 0.04 U
C1003-201F1-CV009-S-NRC Zn-65 pCi/g
-0.03 0.04 U
C1003-201F1-CV009-S-NRC Co-57 pCi/g
-0.015 0.02 U
C1003-201F1-CV009-S-NRC Ru-106 pCi/g
-0.13 0.22 U
C1003-201F1-CV009-S-NRC Se-75 pCi/g
-0.009 0.03 U
C1003-201F1-CV009-S-NRC Nb-94 pCi/g
-0.003 0.02 U
C1003-201F1-CV009-S-NRC Cs-134 pCi/g
-0.005 0.04 U
C1003-201F1-CV009-S-NRC Sb-125 pCi/g 0.006 0.06 U
C1003-201F1-CV009-S-NRC Eu-155 pCi/g 0.01 0.06 U
C1003-201F1-CV009-S-NRC Ag-108m pCi/g 0.07 0.24 U
C1003-201F1-CV009-S-NRC Eu-154 pCi/g 0.04 0.10 U
C1003-201F1-CV009-S-NRC Cs-137 pCi/g 0.007 0.012 U
C1003-201F1-CV009-S-NRC Ba-133 pCi/g 0.008 0.012 U
C1003-201F1-CV009-S-NRC Mn-54 pCi/g 0.002 0.002 U
C1003-201F1-CV009-S-NRC Ag-110m pCi/g 0.05 0.06 U
C1003-201F1-CV009-S-NRC Co-60 pCi/g 0.02 0.01
=
C1003-201F1-CV009-S-NRC U-238 pCi/g 0.64 0.23
=
C1003-201F1-CV009-S-NRC Bi-212 pCi/g 0.79 0.16
=
C1003-201F1-CV009-S-NRC Ac-228 pCi/g 0.80 0.09
=
C1003-201F1-CV009-S-NRC Bi-214 pCi/g 0.76 0.08
=
SONGS MPHF Sample Report 5365-TR-01-0 APPENDIX B: GEL ANALYTICAL RESULTS
SONGS MPHF Sample Report B-1 5365-TR-01-0
SONGS MPHF Sample Report B-2 5365-TR-01-0
SONGS MPHF Sample Report B-3 5365-TR-01-0
SONGS MPHF Sample Report B-4 5365-TR-01-0
SONGS MPHF Sample Report B-5 5365-TR-01-0
SONGS MPHF Sample Report B-6 5365-TR-01-0
SONGS MPHF Sample Report B-7 5365-TR-01-0
SONGS MPHF Sample Report B-8 5365-TR-01-0
SONGS MPHF Sample Report B-9 5365-TR-01-0
SONGS MPHF Sample Report B-10 5365-TR-01-0
SONGS MPHF Sample Report B-11 5365-TR-01-0
SONGS MPHF Sample Report B-12 5365-TR-01-0