ML23261A595
| ML23261A595 | |
| Person / Time | |
|---|---|
| Site: | Vallecitos Nuclear Center, Vallecitos File:GEH Hitachi icon.png |
| Issue date: | 03/31/2023 |
| From: | Enercon Services, ReNuke Services Inc |
| To: | Office of Nuclear Material Safety and Safeguards |
| Shared Package | |
| ML23261A591 | List: |
| References | |
| M230128 REN-TR-22-011, Rev 1 | |
| Download: ML23261A595 (1) | |
Text
Enclosure 3 SDR Radiological Characterization Report, TR-22-011 Revision 1
SDR Radiological Characterization Report GE-Hitachi Vallecitos Nuclear Reactors REN-TR-22-011 Revision 1 Prepared for:
(. ) HITACHI Decommissioning Services Prepared by:
~ ~p~~!. tomorrow ReNuke Services, Inc.
704 S. Illinois Avenue, Suite C-20210 Oak Ridge, TN 37830 ENERCON Excellence-Every project Every day.
ENERCON Services, Inc.
500 Townpark Lane Kennesaw, GA 30144 REN-TR-22-011 Revision 1 March 2023
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 Summary of Changes Revisions to the SDR Radiological Characterization Report will be tracked when revisions are issued. Changed sections will be identified by special demarcation in the margin. A summary description of each revision will be noted in the following table.
Revision Number Date Description of Change 0 March 6, 2023 Final
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 TABLE OF CONTENTS
- 1. EXECUTIVE
SUMMARY
................................................................................................ l
- 2. SCOPE AND BACKGROUND ......................................................................................... 3 2.1 SCOPE ....................................................................................................................... 3 2.2 FACILITYBACKGROUND ........................................................................................... 3
- 3.
SUMMARY
OF TECHNICAL APPROACH ................................................................. 8 3 .1 RADIONUCLIDES OF CONCERN .................................................................................. 8 3.2 SCREENING CRITERIA .............................................................................................. 12 3.3 INSTRUMENTATION ................................................................................................. 12 3.4 SURVEYDESIGN .............................. ......... ....... ......... ....... ......... ....... ......... ....... ........ 15 3.5 DUPLICATE SAMPLES .............................................................................................. 15 3.6 PRELIMINARY SURVEY UNITS AND CLASSIFICATIONS ..... .. ...... .. ...... .. ...... .. ...... .. ...... 15
- 4. CURRENT RADIOLOGICAL CONDITIONS ............................................................ 17 4.1 200 AREA CONDITIONS ........................................................................................... 17 4.1.1 Building 200, Control and Office Building ......... .. ...... .. ...... .. ...... .. ...... .. ...... 24 4.1.2 Building 201, GETR Containment Building ............................................... 24 4.1.3 Building 202, Auxiliary Equipment Building ..... .. ...... .. ...... .. ...... .. ...... .. ...... 24 4.1.4 Building 210, Mockup Shop ........................................................................ 25 4.1.5 Building 213, Emergency Equipment Garage ..... .. ...... .. ...... .. ...... .. ...... .. ...... 25 4.1.6 Building 214, Fabrication and Assembly Shop ........................................... 26 4.1.7 Building217, Warehouse ............................................................................ 26 4.1.8 Tank Farm ............................ ......... ....... ......... ....... ......... ....... ......... ....... ........ 26 4.2 300AREACONDITIONS ................... ......... ....... ......... ....... ......... ....... ......... ....... ........ 27 4.2.1 Grounds, 300 Area ....................................................................................... 28 4.2.2 Building 300, Office Building ..................................................................... 33 4.2.3 Building 301, VBWR Reactor Containment ............................................... 33 4.2.4 Building 302, Steam Turbine Building ........................................................ 34 4.2.5 Building 304, Fuel Storage Building ........................................................... 34 4.2.6 Building 348, Stress Corrosion Facility ...................................................... 35 4.2.7 Building 351, EVESRReactor Containment.. ..... .. ...... .. ...... .. ...... .. ...... .. ...... 35 4.2.8 Building 352, EVESR Condenser Building ................................................ 35 4.2.9 Underground Equipment Tunnels Between 351 and 352 .... .. ...... .. ...... .. ...... 36 4.3 DATAGAPS ............................................................................................................. 37
- 5. QUALITY ASSURANCE AND QUALITY CONTROL ............................................. 38 5.1 GENERAL PROVISIONS ..... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... 3 8 11
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 5 .1. 1 Written Procedures ...................................................................................... 38 5.1.2 Instrumentation Selection, Calibration, and Use ........ ......... ....... ......... ........ 38 5.1.3 Chain ofCustody ......................................................................................... 38 5.1.4 Independent Review of Survey Results ....................................................... 39 5.2 TRAINING ........................ .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... 39 5.3 SAMPLE ANALYSIS .................................................................................................. 39
- 6. LIMITATIONS ................................................................................................................ 40 6.1 HIGH BACKGROUND AREAS .... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ..... .40 6.2 INTERNAL ACTIVITY ............................................................................................... .40
- 7. REFERENCES ................................................................................................................. 41 APPENDICES .............................................................................................................................. 43 APPENDIX A ................................................................................ ......... ....... ......... ....... ........ 44 List of Survey Units with MARSSIM Classification ..... ......... ....... ......... ....... ....... .44 APPENDIXB ........................................................................................................................ 49 VNC GEL Analytical Results Database (Microsoft Excel File) ........................... .49 APPENDIX c ........................................................................................................................ 50 VNC Master Survey Results Database (Microsoft Excel file) ............................... 50 APPENDIX D .......................................................................................... ...... .. ...... .. ...... .. ...... 51 Gamma Walkover Survey Results (Microsoft Excel File) ...... ....... ......... ....... ........ 51 APPENDIXE ......................................................................................... ....... ......... ....... ........ 52 VNC Individual Characterization Survey Records ................................................ 52 111
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 List of Tables Table 2.1: List of200 Area (GETR) and 300 Area (VBWR/EVESR) Buildings ............................................ 6 Table 3.1: NUREG Radionuclides of Concern ................................................................................................ 8 Table 3.2: Preliminary Radionuclides of Concern for VNC ........ .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ........ 10 Table 3.3: GEL Requested Isotopic Analysis ................................................................................................. 11 Table 3.4: Detected Radionuclides Comparison .......... .. ...... .. ...................... .. ...... .. ...... .. ...... .. ...... .. ...... .. ........ 11 Table 3.5: NRC Screening Levels for Surface Soil and Building Surfaces ................................................... 12 Table 3.6: Instrumentation .............................................................................................................................. 14 Table 3.7: MARSSIM Class Determination ................................................................................................... 16 Table 4.1: 200 Area Soil Sample Results ...................... ....... ......... ....... ......... ....... ......... ....... ......... ....... .......... 21 Table 4.2: 200 Area Scoping Soil Sample Results ....... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ........ 23 Table 4.3: Building 200 Measurement Results .............................................................................................. 24 Table 4.4: Building 201 Measurement Results ............ .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ........ 24 Table 4.5 Building 202 Measurement Results ................................................................................................ 24 Table 4.6: Building 210 Measurement Results ............. ....... ......... ....... ......... ....... ......... ....... ......... ....... .......... 25 Table 4.7: Building 213 Measurement Results .............................................................................................. 25 Table 4.8: Building 214 Measurement Results ............. ....... ......... ....... ......... ....... ......... ....... ......... ....... .......... 26 Table 4.9: Building 217 Measurement Results .............................................................................................. 26 Table 4.10: 300 Area Soil Sample Results ..................................................................................................... 31 Table 4.11: 300 Area Scoping Soil Sample Results ..... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ........ 32 Table 4.12: Building 300 Impacted Rooms .................................................................................................... 33 Table 4.13: Building 300 Potentially Non-Impacted Rooms ....... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ........ 33 Table 4.14: Building 300 (Impacted rooms) Measurement Results ..... ......... ....... ......... ....... ......... ....... .......... 33 Table 4.15: Building 301 Measurement Results ........... ....... ......... ....... ......... ....... ......... ....... ......... ....... .......... 34 Table 4.16: Building 302 Measurement Results ........... ....... ......... ....... ......... ....... ......... ....... ......... ....... .......... 34 Table 4.17: Building 304 Measurement Results ........... ....... ......... ....... ......... ....... ......... ....... ......... ....... .......... 35 Table 4.18: Building 348 Measurement Results .......... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ........ 35 Table 4.19: Building 351 Measurement Results ............................................................................................ 35 Table 4.20: Building 352 Measurement Results .......... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ........ 36 Table 4.21: Tunnels Measurement Results .................................................................................................... 36 IV
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 LIST OF FIGURES Figure 2-1: Vallecitos Nuclear Center ............................................................................................... 4 Figure 2-3: 300 Area .............. .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. ...... .. .......... 6 Figure 4-1: Current 200 Area ................................................. ......... ....... ......... ....... ......... ....... .......... 18 Figure 4-2: Gamma Walkover Survey Results for 200 Area ........................................................... 19 Figure 4-3: Inside Fence Soil Sample Location ID Map for 200 Area ........... ....... ......... ....... .......... 20 Figure 4-4: Outside Fence Soil Sample Location ID Map for 200 Area .............. .. ...... .. ...... .. ......... 21 Figure 4-5: 200 Area Scoping Gamma Walkovers and Sample Location Map ..... ....... ......... .......... 23 Figure 4-6: Current 300 Area ........................................................................................................... 27 Figure 4-7: Gamma Walkover Survey Results for 300 Area .......... ....... ......... ....... ......... ....... .......... 29 Figure 4-8: Inside Fence Soil Sample Location ID Map for 300 Area .......... .. ...... .. ...... .. ...... .. ........ 29 Figure 4-9: Outside Fence Soil Sample Location ID Map for 300 Area ......................................... 30 Figure 4-10: 300 Area Scoping Gamma Walkovers and Sample Locations Map ............................ 32 v
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 Acronyms and Abbreviations AEC Atomic Energy Commission ACM Asbestos Containing Material ANSI American National Standard Institute CPM Counts per Minute DandD NRC's Decontamination and Decommissioning Software Code D&D Decontamination and Dismantlement DCGL Derived Concentration Guideline Level DP Decommissioning Plan DPC Design Package and Checklist DPM Disintegrations per Minute DQO Data Quality Objectives EPA Environmental Protection Agency EVESR ESADA Vallecitos Experimental Superheat Reactor FSS Final Status Survey GEL GEL Laboratories, LLC GETR General Electric Test Reactor HSF Hillside Storage Facility HSA Historical Site Assessment HUD Housing and Urban Development MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual MDA Minimum Detectable Activity MDC Minimum Detectable Concentration MWt Megawatt Thermal Nai Sodium Iodide NRC Nuclear Regulatory Commission NUREG Nuclear Regulatory Guide PEL Permissible Exposure Level QC Quality Control RSO Radiation Safety Officer Vl
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 SDR Shut Down Reactors SNM Special Nuclear Material SSCs Systems Structures Components TEDE Total Effective Dose Equivalent 11R/hr Microrem Per Hour VBWR Vallecitos Boiling Water Reactor VNC Vallecitos Nuclear Center VSP Visual Sample Plan Vll
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1
- 1. EXECUTIVE
SUMMARY
This report describes the current radiological status of the Vallecitos Nuclear Center (VNC) Shut-Down Reactors (SDR) facilities to support the development of the Vallecitos Boiling Water Reactor I ESADA Vallecitos Experimental Superheat Reactor (VBWR/EVESR) License Termination Plans (LTP) and General Electric Test Reactor (GETR) Decommissioning Plan (DP),
as well as guide future Decontamination and Dismantlement (D&D) planning. The sections that follow describe the conditions, scope, background, and technical approach used during the characterization of the SDR' s and adjacent areas associated with their respective license areas. The sites contain three (3) research reactors initially licensed by the Atomic Energy Commission (AEC) and later the United States Nuclear Regulatory Commission (NRC). All three reactors progressively over the past 60 years have been placed in "SAFSTOR" and contain possession only licenses with the NRC. VBWR Operated from 1957 to 1963 and holds the NRC reactor license numbers DPR-1. EVESR holds the NRC reactor license number DR-I 0 and GETR holds the NRC reactor license TR-1. The Vallecitos Nuclear Center is located on the Vallecitos Nuclear Center Campus in Alameda County, CA. REN-TR-22-010, Vallecitos Nuclear Center Decommissioning Historical Site Assessment (HSA) provides additional operational history on this project.
The data collected during this characterization, as well as that previously collected for site radiological scoping and the HSA supports the development of a L TPs and DP in accordance with the following NRC regulatory guidance documents:
- 1) Regulatory Guide 1.179, Standard Format and Content of License Termination Plans for Nuclear Power Reactors;
- 2) NUREG-1537, Part 1, Chapter 17, Guidelines for Preparing and Reviewing Applications for Licensing of Non-Power Reactors;
- 3) NUREG-1757, Consolidated NMSS Decommissioning Guidance;
- 4) NUREG-1575, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM).
The data will specifically assist in the development of radiation safety protocols and project dose estimates; estimation of expected radiological waste volumes; methodologies for removal and packaging of radiological waste; and disposal options for radioactively impacted materials generated during decommissioning activities. This data will also be incorporated into the decision-making process for the development of Final Status Survey (FSS) Data Quality Objectives (DQO) described in MARSSIM.
For the characterization effort, ReNuke and ENERCON developed a Characterization Plan [1] to establish the measurement and sampling technical approach along with the project quality assurance requirements. Radiological work permits were developed and were approved by the VNC Radiation Safety Officer (RSO) for all survey areas, as necessary. The SDR's Structures Systems and Components (SSC's) and affected areas were separated into survey units with survey 1
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 instructions and corresponding plans developed for each unit, forming Survey Packages. The survey instructions/plans were implemented by qualified Health Physics technician(s) (HP's) and the data was documented on a radiological survey(s). This report contains summary of the survey results. All completed survey packages have been turned over to GEH for retention.
2
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1
- 2. SCOPE AND BACKGROUND 2.1 Scope The GEH SDR characterization scope was to determine the nature and extent of residual radioactive materials and was accomplished through the following methods:
Radiation and Contamination sampling and surveys on building surfaces and structures Exterior gamma walkovers and soil sampling and analysis The activation analysis of reactor components and pool liner was not performed as part of this characterization report. These will be done as part of removal planning, waste packaging and transport/disposal manifesting. The Component Activation Analysis for VBWR Reactor Pressure Vessel was contracted by GEH to David James Associates. Although some removable contamination data may be included in this report for the VBWR vessel, the internals of the three SDR's and associated component activation analyses are not the focus of this report. The three SDR pressure vessels will each be addressed separately from this report.
2.2 Facility Background GEH VNC is licensed by NRC to possess radioactive materials within the VNC Campus, located in Sunol, California. Various activities/projects have been started and stopped at the VNC over its long history, including Hot Cell work and continued Fuel Testing at the NTR. Pertaining specifically to the three (3) SDRs in scope, the site is broken into three (3) general areas; the 100, 200 and 300 areas, as shown in Figure 2-1 of this section. GETR is located in the 200 area as shown in Figure 2-2, while both VBWR and EVESR are located in the 300 area as shown in Figure 2-3. More detailed information including license history and dates of operation of the operating history of GETR, VBWR, and EVESR are available in the HSA.
3
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every projeCI. Everyday REN-TR-22-011 Revision 1 Figure 2-1: Vallecitos Nuclear Center 0 0 0 0 I'
0
~
M w
.,.w 0
0
.,.w 0
~
0 0
~
w N3 500 ~----------~----------~--------~
'~-
0 0 4(
0 0 C) If')'
(") In w 'l w N 3 000 I ~-- I ........ >.J~~n* j<'
-~-
0 0
0 0
g
_/ ~
~ 0
...... (\J w w DRAl N"'uE DITCH-II 1J EATHE11 STATION 4
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 Figure 2-2: 200 Area I
ft ~Ct I
I
//
'/
I I 202 213 BLDG 200 GETR SIT DRAINAGE DITCH /
The 200 area was constructed and centered around the GETR Reactor, also known as building 201.
The 200 area consists of seven (7) significant remaining structures today, (200, 201, 202, 210, 213, 214, 217) but included numerous buildings that have been completely removed or that have concrete pad or foundation remnants. Building 204 shown in Figure 2-2 is not present.
5
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 Figure 2-3: 300 Area
~
~ L . ______
HILLSIDE" STDR FACI1JTY
- 1 0 LAKE LEE 61 BLDG 300 AREA VB.t , EV SR lf The 300 area was constructed and centered around the VBWR Reactor, also known as building 301. Following shutdown ofthe VBWR, the focus of the 300-area shifted to the operation ofthe EVESR Reactor, also known as building 351. The 300 area consists of seven (7) significant remaining structures today, (300, 301, 302, 304, 348, 351, 352) but included numerous buildings that have been completely removed or have concrete pad or foundation remnants. Building 349 is the Waste Evaporator Plant and is not included in this report as it is not attached to the SDR Licenses and is still operational to support overall site operations under separate USNRC license SNM-960.
Though not all 200 and 300 area buildings fall within the scope of this characterization effort, a comprehensive list of the 200 area (GETR) and 300 area (VBWR/EVESR) buildings, with historical use, is shown in Table 2.1. Buildings no longer present or that are not within the scope of this characterization are shown with parenthesis around the building number.
Table 2.1: List of200 Area (GETR) and 300 Area (VBWR/EVESR) Buildings Building ID Historical Use 200 VBWR RX Control & Office Building 201 Reactor Containment Building 202 Auxiliary Equipment Bldg.
(204) Electrical and Instrument Shops (removed) 206 Stack Gas Monitor Shack 210 Mockup and Maintenance Shop, New Fuel Storage Vault 213 Emergency Equipment Building (originally), currently Storage 214 Fabrication & Assembly Shop (215) Gas Supply & Air Compressor Shop 6
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 BUl*td*mg ID H.IS t onca. I Use 217 Spare Parts Storage Building (247) Hillside Radioactive Materials Storage (247A) Bunker Storage Building (249) Hillside Storage 300 VBWR/EVESR Control Building 301 VBWR Containment Building (304) VBWR Fuel Pool - currently used for VNC operations RAM storage (308) Water Softener Area (removed)
(309) GTD (removed)
(310) Nucleopore Facility (removed)
(311) Electric Shop (removed)
(313) Liquid Waste Area (removed) 348 Stress Corrosion and Test Facility (349) Waste Evaporator Plant- in use supporting VNC operations 351 EVESR Reactor Containment Building 352 Condenser Building EVESR (with access to underground tunnels) 352 EVESR Misc. Equipment Building (353) EVESR Cooling Tower (removed)
(354) EVESR Dump Condenser (removed)
(355) Boiler Facility (removed)
(355) EVESR Boiler (removed) 356 Stack Gas Monitoring (358) Test Space (removed)
(361) Vacant Building 7
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1
- 3.
SUMMARY
OF TECHNICAL APPROACH Radiological characterization surveys were performed to establish the current radiological status of the 200 and 300 areas as they exist today. The site characterization survey included radiological surface measurements on building surfaces and equipment in addition to volumetric measurements on surrounding soils and materials as needed. The characterization surveys were designed, performed, evaluated, and documented in accordance with the following sections. Due to time constraints associated with producing the USNRC requested Limited Post-Shutdown Decommissioning Activity Report (LPSDAR), the normal MARSSIM guidance order-sequence of first completing the HSA, then Scoping surveys followed by characterization was altered with Scoping Surveys and HSA development done in parallel. Planning for characterization commenced during the scoping process and before the HSA had been finalized.
3.1 Radionuclides of Concern Based upon facility operating history and historical radiological analyses, both alpha and beta/gamma emitting radionuclides could be present in the 200 and 300 areas. Evaluation of radionuclides of concern identified in NUREG/CR-3474, NUREG/CR-4289, yields a substantial of list of radionuclides. This list can be found in Table 3.1, with corresponding VNC detected radionuclides also identified.
Table 3.1: NUREG Radionuclides of Concern Detected During 2022 Half Life Characterization Nuclide (yr) Citation Source {above Critical Level)
Ag-108m 4.18E+02 NUREG/CR-3474 No Ag-110m 6.84E-01 NUREG/CR-3474 No Am-241 4.32E+02 NUREG/CR-4289 Yes Ar-39 2.69E+02 NUREG/CR-3474 No Ba-133 1.05E+01 NUREG/CR-3474 No C-14 5.73E+03 NUREG/CR-3474 Yes Ca-41 1.03E+05 NUREG/CR-3474 No Ce-141 8.90E-02 NUREG/CR-3474 Yes Cl-36 3.01E+05 NUREG/CR-3474 No Cm-243,244 1.81E+01 NUREG/CR-4289 Yes Co-58 1.94E-01 NUREG/CR-3474 No NUREG/CR-34 74 NUREG/CR-4289 Co-60 5.27E+OO Yes NUREG-1757 Cr-51 7.58E-02 NUREG/CR-3474 No Cs-134 2.06E+OO NUREG/CR-3474 NUREG-1757 No NUREG/CR-34 74 NUREG/CR-4289 Cs-137 3.02E+01 Yes NUREG-1757 NUREG/CR-34 74 NUREG/CR-4289 Eu-152 1.36E+01 Yes NUREG-1757 8
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 Detected During 2022 HalfLife (yr) Characterization (above Critical Nuclide Citation Source Level)
NUREG/CR-34 74 NUREG/CR-4289 Eu-154 8.59E+OO No NUREG-1757 Eu-155 4.96E+OO NUREG/CR-34 74 NUREG-1757 No Fe-55 2.70E+OO NUREG/CR-3474 No Fe-59 1.22E-01 NUREG/CR-3474 No NUREG/CR-34 74 NUREG/CR-4289 H-3 1.23E+01 Yes NUREG-1757 Hf-178m 3.00E+01 NUREG/CR-3474 No Ho-166m 1.20E+03 NUREG/CR-3474 No 1-129 1.57E+07 NUREG/CR-34 74 NUREG/CR-4289 No Kr-81 2.10E+05 NUREG/CR-3474 No Kr-85 1.07E+01 NUREG/CR-3474 No Mn-53 3.70E+06 NUREG/CR-3474 No Mn-54 8.56E-01 NUREG/CR-34 74 NUREG-1757 No Mo-93 3.50E+OO NUREG/CR-3474 No Nb-92m 2.78E-02 NUREG/CR-3474 No NUREG/CR-34 74 NUREG/CR-4289 Nb-94 2.03E+04 Yes NUREG-1757 Ni-59 7.50E+04 NUREG/CR-34 74 NUREG/CR-4289 No NUREG/CR-34 74 NUREG/CR-4289 Ni-63 1.00E+02 Yes NUREG-1757 Np-237 2.14E+06 NUREG/CR-4289 No Pb-205 1.51E+07 NUREG/CR-3474 No Pm-145 1.77E+01 NUREG/CR-3474 No Pu-238 8.78E+01 NUREG/CR-4289 NUREG-1757 Yes NUREG/CR-34 74 NUREG/CR-4289 Pu-239 2.41E+04 Yes NUREG-1757 Pu-240 6.60E+03 NUREG/CR-4289 NUREG-1757 Yes Pu-241 14.4 NUREG-1757 YES Sb-124 1.65E-01 NUREG/CR-3474 No Sc-46 2.29E-01 NUREG/CR-3474 No Se-79 6.50E+04 NUREG/CR-3474 No Sm-146 1.00E+08 NUREG/CR-3474 No Sm-151 9.30E+01 NUREG/CR-3474 No Sn-121m 5.00E+OO NUREG/CR-3474 No Sr-90 2.88E+01 NUREG/CR-34 74 NUREG/CR-4289 Yes Tc-99 2.13E+05 NUREG/CR-34 74 NUREG/CR-4289 No U-233 1.59E+05 NUREG/CR-3474 No Zn-65 6.69E-01 NUREG/CR-3474 No Zr-93 1.53E+06 NUREG/CR-3474 No
- Pu-241 were detected on the smear from inside the VBWR vessel. Even though that smear is not considered part of this characterization effort, the results have been included in the survey records.
9
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 This list of radionuclides was narrowed down considering half-life and radioactive decay and consideration of the 2019 source term report [Ref 9]. A preliminary list of ROCs is shown in Table 3.2.
Table 3.2: Preliminary Radionuclides of Concern for VNC Half-life ROCs Detected during Radionuclide (years) Characterizations H-3 12.3 b C-14 5.72E+03 a, b Co-60 5.27 a, b Ni-59 1.01E+05 Ni-63 100.1 a, b Sr-90 28.8 a, b Nb-94 2.03E+04 b Tc-99 2.11E+05 a, b Cs-137 30.2 a, b Eu-152 13.5 b Eu-154 8.59 Pu-238 87.7 a, b Pu-239/240 6564 a, b Pu-241 14.35 a, b Am-241 432.2 a, b Cm-243/244 18.1 a, b a 2019 Report [9]
b Detected > critical level in characterization sample analysis.
Characterization included isotopic analysis of composited wipe samples from VBWR and composited wipe samples from EVESR that demonstrated detectable gross alpha/beta activity. In all, seven (7) composite samples were sent to GEL Laboratories, LLC (GEL) for analysis.
Volumetric samples were collected at various GETR and VBWR/EVESR locations and analyzed by gamma spectroscopy in the Vallecitos on-site laboratory while samples were also sent to GEL for off-site analysis. The on-site lab only performed gamma spec analysis whereas GEL performed additional methods including chemical separations. The analyses requested from GEL are shown in Table 3.3. GEL analytical results are included in Appendix B.
10
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 Table 3.3: GEL Requested Isotopic Analysis Analytical Process Requested Analyte Gamma Spectroscopy Report all detects Am-241 Cm-243/244 Np-237 Alpha Spectroscopy Pu-238 Pu-239/240 Pu-242 H-3 C-14 Sr-90 (Y-90)
Liquid Scintillation Ni-63 Tc-99 Pu-241 The reported radionuclides are shown in Table 3.4. One goal of both on-site and off-site analysis was to confirm or amend the list ofradionuclides identified in a 2019 characterization effort [Ref 9]. Table 3.4 lists radionuclides identified in 2019 and 2022. In 2022, GEL reported analytical results as positive at a 99% confidence level, minimizing false positives to 1%. For this evaluation, a measured value exceeding the Critical Level was used as an indication of a positive measurement.
Table 3.4: Detected Radionuclides Comparison 2022 Characterization Radionuclide 2019 -2020 Characterization {above Critical Level)
Am-241 Yes Yes C-14 Yes Yes Cs-137 Yes Yes Co-60 Yes Yes Cm-243/244 Yes Yes Eu-152 No Yes H-3 Yes No Ni-63 Yes Yes Pu-238 Yes Yes Nb-94 No Yes Pu-239/240 Yes Yes Pu-241 No No*
Pu-242 No No*
Sr-90 Yes Yes
- Th1s radwnuchde was detected m the Part 61 analys1s for VBWR vessel charactenzatwn.
This list does not supersede the 2019 source term results but provides confirmations of radionuclides previously identified as ROCs.
11
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 3.2 Screening Criteria The VNC characterization effort included evaluation of SSCs and, to some extent, of surface soils surrounding the facility. Establishing screening criteria is critical for selecting field instrumentation and determining action levels. Two sets of screening criteria were considered: one set for surface soils and one for building surfaces. Screening criteria are not stipulated in any of the license documents. Development of the VBWR/EVESR LTP and GETR DP will require determination of appropriate criteria for radioactivity on building and structural surfaces and in soil. Title 10 Code of Federal Regulations Part 20 (10CFR20) specifies radiological criteria for unrestricted use as 25 millirem TEDE.
NRC License Termination Screening Levels contained in Appendix H ofNUREG-1757 Volume 2 for surface soils and building surfaces, reproduced in Table 3.5 below, were considered during the characterization process at VNC. If a radionuclide was not listed in NUREG-1757, NUREG/CR-5512, Volume 3, was cited for use as it is the source document for NUREG-1757, Vol. 2. These screening criteria provide a point of comparison for analytical results of samples collected around the VNC.
Table 3.5: NRC Screening Levels for Surface Soil and Building Surfaces NUREG-1157, Table B.2 NUREG-1157, Table B.1 or Radionuclide or NUREG/CR-5512 Vol NUREG/CR-5512 Vol3.
- 3. Table 6.91 (pCi/g) Table 5.19 (dpm/100cm 2)
H-3 110 1.2E+08 C-14 12 3.7E+06 Ni-59 5.5E+03 4.26E+06 Co-60 3.8 7.1E+03 Ni-63 2.1E+03 1.8E+06 Sr-90 1.7 8.7E+03 Tc-99 19 1.3E+06 Cs-137 11 2.8E+04 Eu-152 8.7 1.27E+04 Eu-154 8.0 1.15E+04 Pu-238 8.17 3.06E+01 Pu-239/240* 2.28 2.79E+01 Pu-241 71.6 1.42E+03 Am-241 2.08 2.70E+01 Cm-243/244* 3.2 3.94E+01
- Total concentrahon of the pmred rad10nuchdes 3.3 Instrumentation Radiation detection instruments were selected considering the preliminary list of ROCs, decay emissions (i.e., alpha, beta, gamma). Table 3.7 provides a list of instrumentation (or equivalent) 12
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 used for the characterization surveys along with typical detection abilities. MARSSIM recommends that the minimum detectable concentration (MDC) for static measurements of surface activity be no greater than 50 percent of the SCREENING CRITERIA The survey methods used for characterization did not necessarily meet this criterion for all surveys, due to both ambient and material backgrounds. This fact did not affect the effectiveness of this effort, as the purpose was to perform a preliminary characterization to assist in decommissioning planning and not final status surveys.
All instrumentation used during characterization surveys were calibrated at least annually, or when repairs necessitate calibration. All instruments were calibrated using sources traceable to the National Institute of Standards and Technology. At a minimum, instruments were functionally checked at the beginning and end of each day of use to ensure proper operation in accordance with manufacturers guidance directs the technicians to investigate potential indications of radiological activity presence. Daily checks included background measurements and source response checks and were performed in a non-impacted area using appropriate check sources. These measurements were recorded to document that the instruments were operating properly.
13
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every projeCI. Everyday REN-TR-22-011 Revision 1 Table 3.6: Instrumentation Nominal Scan Typical4n Nominal Direct Measurement MDC (2 Instrument I Detection Nominal Detection Probe Measurement MDC (1 sec observation, Detector Model Capability Background Efficiency Area minute count) surveyor efficiency 0.5)
Ludlum 2360/43-93 Alpha Alpha: 3 CPM Alpha: 20% 100 cm 2 Alpha: 100 dpm/l00cm 2 Alpha: 300 (field survey, Beta-gamma Beta-gamma: 300 Beta-gamma: Beta-gamma: 590 Beta-gamma: 1900 surface efficiency = cpm 20% dpm/l00cm 2 dpm/l00cm 2 0.25 alpha; =0 .5 beta/gamma)
Ludlum 19 Gamma 17 5 cpm per !J.Rihr N/A N/A N/A N/A Ludlum 3030E/43- Removable Alpha: 1 CPM Alpha: 32% 100 cm 2 Alpha: 20 dpm/l00cm 2 N/A 10-1 (lab analysis, Alpha, Beta- Beta-gamma: 80 Beta-gamma: w1pe area Beta-gamma: 100 N/A surface efficiency = gamma cpm 27% dpm/l00cm 2 1) 137 Ludlum 2221/44-10 Gamma 9750 cpm Cs 900 6.4 pCi/g cpm/j..LR/hr 3.4 pCi/g 6 N/A N/A
°Co 430 cpm/j..LR/hr Note: Values adapted from NUREG-1575, Rev. 1 [5] and MARSSlN and NUREGH-1507, Rev. 1 [13].
14
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 3.4 Survey Design The packages generated for each survey unit are called Design Package and Checklists (DPC).
DPC's were created utilizing Visual Sample Plan (VSP) Software, which generates sample locations when building specs are inputted. Based on the HSA and scoping surveys, the Rad Engineer prescribed the requirements of the surveying and sampling. DPC' s were generated for each survey unit in accordance with MARSSIM guidelines and included prescribed sample locations (Room Dimensions/ill's) and surface survey requirements (Scans/Totals/Screening Criteria). Qualified field technicians utilized these pre-generated survey unit designs to measure out sample locations and direct survey and sampling requirements. The characterization survey is a living process, as the technician encounters contamination or radioactive materials/containers, this will drive additional investigations. The field technicians document the extent and results of all surveys performed on an official radiological survey report for final review by the Rad Engineer, to ensure it satisfied all requirements of the DPC. Originally, surface screening surveys were limited to building surfaces only. GEH requested investigations into key systems and components (known as the "hotlist"). Hotlist item surveys were limited to the exteriors of items/objects/equipment, do to RWP Limitations. Exterior soil surfaces were managed with the same DPC process but utilized different sampling and survey techniques as discussed in the Characterization Plan.
Survey unit assessments were conducted for each survey unit using the Data Quality Assessment process described in Chapter 8 ofMARSSIM. In these assessments, data for each survey unit was evaluated to determine if the survey unit meets or exceeds applicable screening criteria.
3.5 Duplicate Samples Duplicate samples/measurements were collected at a minimum of 10 percent of total samples per survey unit. Duplicate sample results may be compared to each other to assure agreement, if necessary. Duplicate sample comparison will be performed if characterization data is used as FSS.
3.6 Preliminary Survey Units and Classifications The 200 and 300 areas were segmented into logical areas of similar history and/or construction as survey units. Utilizing guidance available in the MARSSIM, an initial classification of either impacted or non-impacted was assigned to each survey unit. Non-impacted areas are areas where historical information and/or process knowledge does not indicate the existence of residual radioactive material and does not indicate any reason to suspect the presence of residual radioactive materials. Impacted areas are areas where historical information and/or process knowledge indicates a potential presence of residual radioactive materials. Survey unit classifications were defined based on available data from the HSA and scoping surveys as Class 1, Class 2 or Class 3 designations. Class 1 areas have the greatest potential for residual activity while Class 3 areas have the least potential for impacted areas. Refer to Table 3.5, below.
15
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 Buildings/areas within controlled area boundaries of Area 200 and Area 300 are a minimum of MARSSIM Class 3. A list of survey units with an initial MARSSIM classification is included in Appendix A Updates to the preliminary classifications as defined in the HSA have been made.
However, following a more detailed evaluation of the characterization data, including the applicable ROCs and instrument and material backgrounds, updates to area classifications will be included in the applicable license termination plan for EVESR and the decommissioning plan for
- GETR, Table 3.7: MARSSIM Class Determination MARSSIM Class Applied Criteria Class 1 Detectable results >Screening Criteria Class 2 Detectable results 10% to 100% of Screening Criteria Class 3 Detectable results <10% Screening Criteria Non-Impacted No detectable results above background 16
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1
- 4. CURRENT RADIOLOGICAL CONDITIONS The following sections summarize the results of the radiological characterization effort. Per MARSSIM guidance all measurement results, whether positive, negative, or less than MDA, were included in the calculations of the mean, maximum, and standard deviation. The results are summarized by building. The completed survey design packages have been retained for future reference, but not included in this report.
A table is provided in Appendix A presenting each Survey Unit and their associated classification.
If any additional data is needed in reference to room dimensions, activity or findings, reference the Master Survey Database and/or the individual survey records.
Available laboratory analytical data has been compiled into a Microsoft Excel database and attached as Appendix B . Radiological characterization of building surfaces included collection of approximately 2,400 individual sample locations comprised ofthe protocols described in Section 3.0, in addition to scoping survey data, routine annual survey data, and miscellaneous other survey data were collected and analyzed in support of the overall project. NOTE - total alpha surface activity calculations included use of a surface correction factor of0.25 times instrument efficiency, regardless of the type of surface being surveyed. This survey data has been compiled into a Microsoft Excel database and is attached as Appendix C.
Radiological scoping and characterization of the open land in and around VBWR/EVESR and GETR included approximately 146,000 data points collected during gamma walkover surveys plus over eighty (80) surface soil samples collected. Soil sample data tables and location maps are shown later in this section. The gamma walkover data has been compiled into a Microsoft Excel database and is attached as Appendix D.
Individual Survey records for the characterization are included in Appendix E. Photographs associated with the project can be found in some of these records.
Results of the radiological characterization were used to update the preliminary MARSSIM classifications from scoping/HSA. Preliminary Screening results are presented below. Site Specific DCGL Screening is being developed as a separate scope and will be applied for updating the initial classifications as presented herein.
4.1 200 Area Conditions A summary of the data collected as part of this characterization effort reported the below figures.
Removable Alpha Results >Screening Criteria Four (4) locations in GETR exceeded 20 dpm/100cm 2 removable alpha. Survey unit 200-104 had a preliminary MARSSIM Class 2 designation and has been reclassified as MARSSIM Class 1.
Removable Beta Results >Screening Criteria 17
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 Seventy (70) locations in GETR exceed 1,000 dpm/100cm 2 removable beta-gamma.
All were in survey units with a preliminary Class 1 designation.
Static Total Alpha Results >Screening Criteria Thirty-five (35) locations in GETR exceed 500 dpm/100cm 2 total alpha. Survey units 200-102, 200-112, 200-HALLS, and 200-KIT had a preliminary MARSSIM Class 2 designation and have been reclassified as MARSSIM Class 1.
Static Total Beta Results >Screening Criteria There are 202locations in GETR that exceed 5,000 dpm/100cm 2 . Survey unit 210-2xx had a preliminary MARSSIM Class 2 designation and has been reclassified as MARSSIM Class 1.
Figure 4-1: Current 200 Area Blue ID's Y001 to X009 designate concrete pads with historical structures that could not be identified.
Grounds, 200 Area Figure 4-2 shows gamma walkover survey results for the GETR area, also known as the 200 area.
Gamma walkover survey results north of the containment building (201) and in the vicinity of the 18
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 GETR tank farm clearly show elevated gamma count rates as the red area in the top-center of the figure. According to the survey team, the elevated readings in red near the GETR containment personnel hatch (adjacent to the south side of GETR containment building) are due to poly tank located there. The other elevated areas located at distances south and east of the GETR containment, will need revisited in the future. The survey team indicated there were radioactive waste containers stored in these locations at the time the surveys were performed. These waste containers have been moved to the Hillside Storage Facility.
Figure 4-3 and Figure 4-4 provide an overlay map of where soil samples were taken and correlates to their specific ID number for reference in Table 4.1, "200 Area Soil Sample Results". Onsite Gamma Spectroscopy Analyses were performed with a "Gamma Vision" in accordance with site procedure NSP 12080. The reported results are qualitative in nature.
Note: Some locations landed on concrete or asphalt leading the field technicians to provide a smear sample, rather than a volumetric soil sample.
Figure 4-2: Gamma Walkover Survey Results for 200 Area Legend GammaCPM
- 1,080- 10,000
- 10.001 - 20,000 20,001 - 30,000 Subject Property : GETR Source: ESRI WOrld Imaqery Basemap Vallecitos Nuclear Center Sunol 1 California 1: 1,500 19
- ENERCON Nuke people bwld1ng a tomorrow Excellence-Every proJect Everyday.
SDR Radiological Characterization Report REN-TR-22-011 Revision 1 Figure 4-3: Inside Fence Soil Sample Location ID Map for 200 Area 20
- ENERCON Nuke people bwld1ng a tomorrow Excellence-Every proJect Everyday.
SDR Radiological Characterization Report REN-TR-22-011 Revision 1 Figure 4-4: Outside Fence Soil Sample Location ID Map for 200 Area T able 41 200 Area s01*t samp.e I ResuIts Sample Activity 2Sigma MDC Mass Activity MDC Type Sample ID Description Nuclide (uCi/ml) (%) (uCi/ml) (g) (pCi/g) (pCi/g)
Soil 22PI359-1 200-YARD.2-1 Cs-137 7.66E-08 58.0% 5.64E-08 618.7 6.19E-02 4.56E-02 Soil 22PI359-2 200-YARD.2-2 Cs-137 7.06E-08 42.2% 3.77E-08 587.2 6.01E-02 3.21E-02 Soil 22PI359-3 200-YARD.2-3 None .............. .............. .............. 543.0 .............. ..............
Soil 22PI359-4 200-YARD.2-4 Cs-137 2.26E-07 18.7% 4.20E-08 598.1 1.89E-01 3.51E-02 Soil 22PI359-5 200-YARD.2-5 Cs-137 2.01E-07 26.2% 5.93E-08 618.5 1.62E-01 4.79E-02 Soil 22PI359-6 200-YARD.2-6 Cs-137 8.54E-08 37.8% 3.92E-08 537.1 7.95E-02 3.65E-02 Soil 22PI359-7 200-YARD.2-7 Cs-137 7.94E-08 46.9% 4.87E-08 645.9 6.15E-02 3.77E-02 Soil 22PI359-8 200-YARD.2-8 Cs-137 1.36E-07 27.5% 3.93E-08 566.2 1.20E-01 3.47E-02 Soil 22PI359-9 200-YARD.2-9 Cs-137 2.74E-07 20.4% 5.75E-08 694.0 1.97E-01 4.14E-02 Soil 22PI359-10 200-YARD.2-10 Cs-137 5.59E-08 56.9% 4.07E-08 607.1 4.60E-02 3.35E-02 Soil 22PI359-11 200-YARD.2-11 Cs-137 8.26E-08 50.2% 5.19E-08 437.8 9.43E-02 5.93E-02 Soil 22PI359-12 200-YARD.2-12 Cs-137 3.51E-07 14.8% 4.65E-08 762.4 2.30E-01 3.05E-02 21
- ENERCON Nuke people bwld1ng a tomorrow Excellence-Every proJect Everyday.
SDR Radiological Characterization Report REN-TR-22-011 Revision 1 Sample Activity 2Sigma MDC Mass Activity MDC lype ~ample ILJ uescnpt1on Nucnae (ULifml) ('Yo) (ULifml) (g) (PLifg) (PLifg)
Soil 22PI362-1 VNC-214-SWSP-001 Cs-137 7.12E-06 4.2% 7.57E-08 391.2 9.10E+00 9.68E-02 (beneath steel plate) Co-60 1.61E-07 23.9% 4.76E-08 2.06E-01 6.08E-02 Soil 22PP362-3 VNC-200-SS-507 Cs-137 9.80E-07 8.9% 6.44E-08 313.6 1.56E+00 1.03E-01 (North Fenceline) Co-60 5.50E-08 41.4% 3.56E-08 8.77E-02 5.68E-02 Smear 22SM360-1 200-Yard.2-13 None Smear 22SM360-2 200-Yard.2-130 None Smear 22SM360-3 200-Yard.2-14 None Smear 22SM360-4 200-Yard.2-140 None Smear 22SM359-1 200-Yard.1-1 None Smear 22SM359-2 200-Yard.1-2 None Smear 22SM359-3 200-Yard.1-3 None Smear 22SM359-4 200-Yard.1-4 None Smear 22SM359-5 200-Yard.1-5 None Smear 22SM359-6 200-Yard.1-6 None Smear 22SM359-7 200-Yard.1-7 None Smear 22SM359-8 200-Yard.1-8 None Smear 22SM359-9 200-Yard.1-9 None Smear 22SM359-10 200-Yard.1-10 None Smear 22SM359-11 200-Yard.1-11 None Smear 22SM359-12 200-Yard.1-12 None Smear 22SM359-13 200-Yard.1-13 None Smear 22SM359-14 200-Yard.1-14 None Smear 22SM359-15 200-Yard.1-15 None Smear 22SM359-16 200-Yard.1-16 None Smear 22SM359-17 200-Yard.1-17 None Smear 22SM359-18 200-Yard.1-18 None Smear 22SM359-19 200-Yard.1-19 None Smear 22SM359-20 200-Yard.1-20 None Smear 22SM359-21 200-Yard.1-200 None Smear 22SM359-22 200-Yard.1-21 None Smear 22SM359-23 200-Yard.1-210 None 22
- ENERCON Nuke people bwld1ng a tomorrow Excellence-Every proJect Everyday.
SDR Radiological Characterization Report REN-TR-22-011 Revision 1 Figure 4-5: 200 Area Scoping Gamma Walkovers and Sample Location Map Legend Ganliml CFI'M 1,rM - 10,coo HI.I) 'J 1 - 2!1,00[)
2!1.001 - n,OOD Subject Property<
'*'M ""1 ih:;+c I'. !. I:!.,.Hr f.-wu t .. r GE7ie "S.afY.ll, ::;:~ F r.:rn ~
Table 4.2: 200 Area Scoping Soil Sample Results Sample Activity 2Sigma MDC Type Sample ID Description Nuclide (uCi/ml) (%) (uCi/ml)
Soil 22PI220-18 VNC-2022-GETR-S0-001 Cs-137 9.42E-07 8.4% 5.00E-08 Soil 22PI220-19 VNC-2022-GETR-S0-002 Cs-137 2.55E-07 25.0% 6.51E-08 Soil 22PI220-20 VNC-2022-GETR-S0-003 Cs-137 2.45E-07 21.2% 5.09E-08 Soil 22PI220-21 VNC-2022-GETR-S0-004 Cs-137 1.40E-06 6.7% 4.38E-08 Soil 22PI220-22 VNC-2022-GETR-S0-005 Cs-137 7.43E-06 4.2% 7.21E-08 Co-60 1.79E-07 24.1% 6.06E-08 Soil 22PI220-23 VNC-2022-GETR-S0-006 Cs-137 2.60E-07 24.1% 6.77E-08 Soil 22PI220-24 VNC-2022-GETR-S0-007 Cs-137 2.36E-07 20.5% 4.70E-08 Soil 22PI220-25 VNC-2022-GETR-S0-008 Cs-137 1.03E-07 41.1% 5.16E-08 Soil 22PI220-26 VNC-2022-GETR-S0-009 Cs-137 1.53E-07 26.6% 4.43E-08 Soil 22PI220-27 VNC-2022-GETR-S0-015 Cs-137 2.06E-07 25.6% 5.86E-08 Soil 22PI220-28 VNC-2022-GETR-S0-017 Cs-137 2.71E-07 16.4% 4.02E-08 Soil 22PI220-29 VNC-2022-GETR-S0-018 Cs-137 6.90E-07 10.8% 6.15E-08 Soil 22PI220-30 VNC-2022-GETR-S0-020 Cs-137 1.34E-07 30.8% 4.47E-08 Soil 22PI220-31 VNC-2022-GETR-S0-023 None Detected N/A N/A N/A 23
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 4.1.1 Building 200, Control and Office Building Building 200 consists of the GETR Control Room, a change room, decon room, restrooms, a small Lab, Special Nuclear Material (SNM) vault, offices and a kitchen. Remediation of wall contamination, drainage lines and overhead ductwork is required in this space. For specific locations of elevated activity, survey records can be found in appendix E. Building 200 is impacted and requires remediation.
Table 4.3: Building 200 Measurement Results Measurement Average (net) Maximum (net)
Removable Alpha 1 dpm/100cm 2 43 dpm/100cm 2 Removable Beta 41 dpm/100cm 2 687 dpm/100cm 2 Total (static) Alpha 86 dpm/100cm 2 1,262 dpm/100cm 2 Total (static) Beta 843 dpm/100cm 2 210,443 dpm/100cm 2 Gamma Dose 7 !J.Rihr 1,990 !J.Rihr 4.1.2 Building 201, GETR Containment Building Building 201, i.e., GETR reactor containment, has four levels (552-ft, 567-ft, 589-ft, 611-ft) and was previously known to be contaminated. Surveys in 201 resulted in overall average and maximum results presented in Table 4.4. Contamination is present throughout the building on each level with the highest levels generally located on the 589- and 611-foot levels. Building 201 is impacted and requires remediation.
Table 4.4: Building 201 Measurement Results Measurement Average (net) Maximum (net)
Removable Alpha 1 dpm/100cm 2 20 dpm/100cm 2 2
Removable Beta 11,435 dpm/100cm 1,022,759 dpm/100cm 2 Total (static) Alpha 176 dpm/100cm 2 3,634 dpm/100cm 2 Total (static) Beta 1,515,438 dpm/100cm 2 15,806,359 dpm/100cm 2 Gamma Dose 482 !J.Rihr 1,700 !J.Rihr 4.1.3 Building 202, Auxiliary Equipment Building The building contained miscellaneous support equipment including instrument air dryer, receiver, and two diesel generators. Currently, Building 202 is considered impacted. Survey results in the building are affected by Tank Farm dose rates. Further investigation is required following mitigation of dose rates from the Tank Farm to confirm whether the building is impacted and class.
Table 4.5 Building 202 Measurement Results Measurement Average (net) Maximum (net) 2 Removable Alpha 1 dpm/100cm 8 dpm/100cm 2 Removable Beta 17 dpm/100cm 2 118 dpm/100cm 2 Total (static) Alpha 24 dpm/100cm 2 135 dpm/100cm 2 2
Total (static) Beta 5,374 dpm/100cm 132,535 dpm/100cm 2 24
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 I GammaDose 114 !J.Rihr 200 !J.Rihr 4.1.4 Building 210, Mockup Shop Building 210 is a two-story concrete structure approximately 47 feet long and 24 feet wide located southeast of the GETR containment. The north end of the building served as the mock-up shop.
The building also contained engineering offices. A fuel storage vault was in the southwest comer of the building. All alpha survey results were less than screening criteria. A maximum total beta activity reading of24,617 dpm/100cm2 was found in one of nine sample locations during a scoping survey performed on June 7, 2022. At that time, a maximum gamma dose rate 115 11R/hr net was also found at the same survey location, in a room on the first floor of the building. During later characterization surveys performed on June 28, 2022 and July 11, 2022, involving over 60 survey locations, a maximum total beta activity 17,776 dpm/100 cm2 was found. Gamma dose rate at this and two nearby survey locations were 50 11R/hr net during these surveys.
Figure 4-2 shows two distinct gamma "hotpots" located adjacent to the south side of the building.
The survey team and VNC Operations Management state that radioactive waste containers had been stored at those locations and have since been moved to the Hillside Storage Facility (HSF).
It is recommended that Building 210 be resurveyed to re-assess conditions. Building 210 is considered Class 3.
Table 4.6: Building 210 Measurement Results Measurement Average (net) Maximum (net)
Removable Alpha 1 dpm/100cm 2 8 dpm/100cm 2 Removable Beta 8 dpm/100cm 2 109 dpm/100cm 2 Total (static) Alpha 12 dpm/100cm 2 137 dpm/100cm 2 Total (static) Beta 1,996 dpm/100cm 2 17,766 dpm/100cm 2 Gamma Dose 6 !J.Rihr 50 !J.Rihr 4.1.5 Building 213, Emergency Equipment Garage Building 213 is located at the southeast comer of the 200 area and is currently used as a garage.
Characterization surveys showed gamma dose rates near background and contamination surveys on the floor, walls and ceiling indicate the structure may be non-impacted.
Table 4.7: Building 213 Measurement Results Measurement Average (net) Maximum (net)
Removable Alpha 1 dpm/100cm 2 8 dpm/100cm 2 Removable Beta 4 dpm/100cm 2 45 dpm/100cm 2 Total (static) Alpha 11 dpm/100cm 2 118 dpm/100cm 2 Total (static) Beta 194 dpm/100cm 2 951 dpm/100cm 2 Gamma Dose 0 !J.Rihr 0 !J.Rihr 25
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 4.1.6 Building 214, Fabrication and Assembly Shop Building 214 is listed on different drawings as either a fabrication and assembly shop or the East Mock-up Shop. Characterization surveys showed gamma dose rates at background and contamination surveys on the floor, walls and ceiling indicate the structure is Class 3.
Table 4.8: Building 214 Measurement Results Measurement Average (net) Maximum (net)
Removable Alpha 1 dpm/100cm 2 3 dpm/100cm 2 Removable Beta 170 dpm/100cm 2 329 dpm/100cm 2 Total (static) Alpha 16 dpm/100cm 2 125 dpm/100cm 2 Total (static) Beta 363 dpm/100cm 2 1,927 dpm/100cm 2 Gamma Dose 0 !J.Rihr 0 !J.Rihr 4.1.7 Building 217, Warehouse Building 217 is a two-story steel beam and steel sided structure used as a warehouse. The north end of the building is referred to as the Patio Storage Area. The building is not shown on a 1965 drawing but is depicted on a 1978 drawing. Alpha survey results were below screening criteria.
Figure 4-2 shows elevated gamma readings emanating from the Tank Farm on the west side of the building with some areas on the east side of the building below background levels for the 200 Area. Building 217 is currently considered Class 3 but will be reevaluated in the future and may be found to be non-impacted.
Table 4.9: Building 217 Measurement Results Measurement Average (net) Maximum (net)
Removable Alpha 1 dpm/100cm 2 10 dpm/100cm 2 Removable Beta 16 dpm/100cm 2 84 dpm/100cm 2 Total (static) Alpha 22 dpm/100cm 2 200 dpm/100cm 2 Total (static) Beta 229 dpm/100cm 2 1,282 dpm/100cm 2 Gamma Dose 26 !J.Rihr 50 !J.Rihr 4.1.8 Tank Farm The tank farm is largely intact from GETR operational days. The red area on Figure 4-2 clearly shows elevate gamma readings emanating from the tank farm affecting the northwest portion of the 200 area. Historical records indicate that in addition to much of the equipment, piping and tanks remaining in place, leaks and spills are known to have occurred over the years of operations. Some historical small scale near surface soil cleanup did occur after known leaks or spills, but contamination may be encountered below grade. During future tank farm remediation, it is recognized that in addition to equipment removal, soil remediation and extensive sampling at depth, around and beneath equipment will be performed to assess the extent of 26
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 contamination spread and ensure it is remediated to prescribed levels. The tank farm area is impacted and requires remediation.
4.2 300 Area Conditions A summary of the data collected as part of this characterization effort reported the below figures .
Removable Alpha Results >Screening Criteria Six (6) locations in VBWR/EVESR exceed 20 dpm/100cm 2 removable alpha. Survey units 300-115, and 300-209C had a preliminary Class 2 designation and have been reclassified as Class 1.
Removable Beta Results >Screening Criteria Eighty-five (85) locations in VBWR/EVESR exceed the 1,000 dpm/100cm 2 removable beta-gamma activity. All were in survey units with a preliminary Class 1 designation.
Static Total Alpha Results >Screening Criteria Seventy-nine (79) locations in VBWR/EVESR exceed 500 dpm/100cm 2 total alpha.
All were in survey units with a preliminary Class 1 designation.
Static Total Beta Results >Screening Criteria There are 347 locations in VBWR/EVESR that exceed 5,000 dpm/100cm 2 total beta-gamma activity. Survey units 300-113, 300-209B, and 352-352A had a preliminary Class 2 designation and have been reclassified as Class 1.
Figure 4-6: Current 300 Area Green ID's X001 to X006 designate concrete pads with historical structures that could not be identified. Surveys of these pads were completed as part of the overall 300 area grounds survey.
27
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 4.2.1 Grounds, 300 Area Gamma walkover surveys ofland areas in and around GETR and VBWR/EVESR were performed using a Ludlum Model 2221 with 44-10 detector attached to a data logging GPS system. The GPS unit logged both the GPS coordinates and gamma ratemeter providing results that could be exported to a comma separated variable file for evaluation and mapping of the area(s). The result is color-coded maps depicting the gross gamma ratemeter, i.e., counts per minute (CPM), results.
These maps are useful to visualize trends in gross gamma count rate. They should not be used to determine compliance with screening criteria but are useful in locating potential areas of elevated count rates that affect other areas. Color coding on the maps is shown in increments of 10,000.
The gross gamma background rate can be greatly affected by localized conditions but is typically about 10,000 CPM. Normal variability resulting in doubling of the gross gamma results is common. Background gross gamma results can be greatly affected by parameters such as local radiological conditions, geology, and topographical geometry to the detector.
Figure 4-7 shows gamma walkover survey results for the VBWR/EVESR area. Gamma walkover surveys in the vicinity ofBuilding 304 and western portion of the fenced 300 area were impacted by the higher-level radioactive material stored in Building 304 and were not completed. Impact of Building 304 is clearly seen via the red area in the center of the figure. Some areas are overgrown with vegetation and were not accessible to the survey team. Although some areas are not depicted in red, the elevated gamma readings indicated in red extend to beyond 100 feet from building 304 in all directions, unless there was/is an obstruction such as a building present between the radioactive materials in Building 304 and the detector. All areas in line of sight of Building 304 to at least 100 feet radius have elevated gamma readings greater than 30,000 CPM.
An investigation into a septic tank associated with building 300 and outside of the 300 fence line was performed to assess potential contamination spread. The septic tank was opened, and a sample was obtained and analyzed on the VNC gamma spectroscopy system. Due to poor geometry and the limited amount of material obtained, the sample is considered as qualitative only. A (VNC)
Counting Lab Analysis Report dated 03/28/2022 reported Cs-13 7 present in the septic tank sample at 3.22E-04 uCi/sample with an MDC of2.37E-05 uCi .
Figures 4-8 and 4-9 provide an overlay map of where soil samples were taken and correlate to their specific ID number for reference in Table 4.10 "300 Area Soil Sample Results". Onsite Gamma Spectroscopy Analyses were performed with a "Gamma Vision" in accordance with site procedure NSP 12080. The reported results are considered qualitative in nature at this time due to differing analysis sequences and protocols used.
Note: Some locations fell on concrete or asphalt leading the field technicians to provide a smear sample, rather than a soil sample at those locations.
28
- ENERCON Nuke people bwld1ng a tomorrow Excellence-Every proJect Everyday.
SDR Radiological Characterization Report REN-TR-22-011 Revision 1 Figure 4-7: Gamma Walkover Survey Results for 300 Area Legend Gamma CPM
- 1,080 - 10,000 10,001 - 20 ,000 20 ,001 - 30 ,000 S ubject Prope rt y '
Vt~lled t os N u cl e~r Ce,te*
S.Jnol, Calitorn a 1 :3 ,000 Figure 4-8: Inside Fence Soil Sample Location ID Map for 300 Area
- ENERCON Nuke people bwld1ng a tomorrow Excellence-Every proJect Everyday.
SDR Radiological Characterization Report REN-TR-22-011 Revision 1 Figure 4-9: Outside Fence Soil Sample Location ID Map for 300 Area 30
- ENERCON Nuke people bwld1ng a tomorrow Excellence-Every proJect Everyday.
SDR Radiological Characterization Report REN-TR-22-011 Revision 1 Table 4.10: 300 Area Soil Sample Results sample ~-~ lVI 25"1gma MDC Act"lVI"ty MDC Type Sample ID Description Nuclide (uCi/ml) (%) (uCi/ml) Mass (g) (pCi/g) (pCi/g)
Smear 22SM283-1 300-Yard.1-1 None .............. .............. .............. .............. .............. ..............
Smear 22SM283-2 300-Yard.1-2 None .............. .............. ************** .............. .............. ..............
Smear 22SM283-3 300-Yard.1-3 None .............. .............. .............. .............. .............. ..............
Soil 22PI282-1 300-Yard.1-4 Cs-137 1.05E-06 8.8% 6.65E-08 954.9 5.50E-01 3.48E-02 Soil 22PI282-2 300-Yard.1-5 Cs-137 2.84E-06 5.5% 7.36E-08 897.7 1.58E+00 4.10E-02 Soil 22PI282-3 300-Yard.1-6 Cs-137 4.63E-07 12.6% 5.28E-08 926.3 2.50E-01 2.85E-02 Soil 22PI282-4 300-Yard.1-7 Cs-137 4.07E-06 4.8% 6.95E-08 868.9 2.34E+00 4.00E-02 Soil 22PI282-5 300-Yard.1-8 Cs-137 4.05E-07 13.5% 4.78E-08 881.8 2.30E-01 2.71E-02 Soil 22PI282-6 300-Yard.1-9 Cs-137 1.20E-07 32.4% 4.53E-08 765 7.84E-02 2.96E-02 Smear 22SM283-4 300-Yard.1-10 None .............. .............. .............. .............. .............. ..............
Soil 22PI282-7 300-Yard.1-11 Cs-137 2.58E-07 21.1% 5.89E-08 1006.4 1.28E-01 2.93E-02 Soil 22PI282-8 300-Yard.1-11D Cs-137 2.46E-07 21.9% 5.44E-08 979.3 1.26E-01 2.78E-02 Soil 22PI282-9 300-Yard.1-12 Cs-137 5.72E-07 12.6% 6.34E-08 955.1 2.99E-01 3.32E-02 Soil 22PI282-10 300-Yard.1-12D Cs-137 4.25E-07 13.0% 4.92E-08 885.1 2.40E-01 2.78E-02 Smear 22SM283-5 300-Yard.1-13 None .............. .............. .............. .............. .............. ..............
Smear 22SM283-6 300-Yard.1-14 None .............. .............. .............. .............. .............. ..............
Smear 22SM283-7 300-Yard.1-15 None .............. .............. .............. .............. .............. ..............
Soil 22PI282-11 300-Yard.1-16 Cs-137 3.29E-07 17.8% 6.00E-08 906 1.82E-01 3.31E-02 Soil 22PI282-12 300-Yard.1-17 Cs-137 9.45E-08 47.9% 5.39E-08 1065.8 4.43E-02 2.53E-02 Soil 22PI282-13 300-Yard.1-18 Cs-137 2.97E-07 19.2% 5.95E-08 962 1.54E-01 3.09E-02 Smear 22SM283-8 300-Yard.1-19 None .............. .............. .............. .............. .............. ..............
Smear 22SM283-9 300-Yard.1-19D None .............. .............. .............. .............. .............. ..............
Smear 22SM283-10 300-Yard.1-20 None .............. .............. .............. .............. .............. ..............
Soil 22PI282-14 300-Yard.1-21 Cs-137 3.76E-07 20.2% 7.57E-08 966.3 1.95E-01 3.92E-02 Soil 22PI282-15 300-Yard.1-22 Cs-137 4.00E-07 13.3% 4.75E-08 715.4 2.80E-01 3.32E-02 Soil 22PI282-16 300-Yard.1-23 None ----------- ----------- ----------- 889.2 ----------- -----------
Soil 22PI282-17 300-Yard.1-24 Cs-137 1.02E-06 7.9% 5.02E-08 887.9 5.74E-01 2.83E-02 Soil 22PI282-18 300-Yard.1-25 Cs-137 2.29E-07 23.2% 5.96E-08 871.7 1.31E-01 3.42E-02 Soil 22PI282-19 300-Yard.1-26 Cs-137 6.73E-08 57.9% 4.85E-08 815.8 4.12E-02 2.97E-02 Smear 22SM283-11 300-Yard.1-27 None .............. .............. .............. .............. .............. ..............
Soil 22PI282-20 300-Yard.1-28 Cs-137 4.26E-07 14.5% 5.94E-08 879.5 2.42E-01 3.38E-02 Soil 22PI282-21 300-Yard.1-29 Cs-137 4.90E-08 67.7% 4.49E-08 891.3 2.75E-02 2.52E-02 Soil 22PI282-22 300-Yard.1-30 Cs-137 4.43E-07 14.0% 5.96E-08 1003.5 2.21E-01 2.97E-02 Soil 22PI282-23 300-Yard.1-31 Cs-137 2.91E-07 19.7% 5.62E-08 961.2 1.51E-01 2.92E-02 Soil 22PI282-24 300-Yard.1-32 Cs-137 2.53E-07 22.5% 6.20E-08 854 1.48E-01 3.63E-02 Soil 22PI282-25 300-Yard.1-33 Cs-137 4.40E-07 12.6% 4.95E-08 945.7 2.33E-01 2.62E-02 Cs-137 3.18E-07 21.2% 6.91E-08 945.2 1.68E-01 3.66E-02 Soil 22PI282-26 300-Yard.1-34 U-235 2.76E-08 41.8% Unk 1.46E-02 Unk Soil 22PI282-27 300-Yard.1-35 Cs-137 4.28E-07 13.5% 5.28E-08 989.6 2.16E-01 2.67E-02 Soil 22PI299-1 300-YARD.2-1 Cs-137 7.30E-07 10.5% 6.21E-08 746.5 4.89E-01 4.16E-02 Soil 22PI299-2 300-YARD.2-2 Cs-137 2.13E-06 6.0% 6.14E-08 494.0 2.16E+00 6.21E-02 Soil 22PI299-3 300-YARD.2-2D Cs-137 1.99E-06 5.8% 4.93E-08 517.8 1.92E+00 4.76E-02 Soil 22PI299-4 300-YARD.2-3 Cs-137 1.11E-07 43.4% 5.26E-08 719.4 7.71E-02 3.66E-02 Soil 22PI299-5 300-YARD.2-4 Cs-137 6.65E-08 66.5% 5.61E-08 843.9 3.94E-02 3.32E-02 Soil 22PI299-6 300-YARD.2-8 Cs-137 6.61E-07 11.0% 5.95E-08 829.4 3.98E-01 3.59E-02 Soil 22PI299-7 300-YARD.2-9 Cs-137 9.65E-08 45.7% 5.59E-08 872.8 5.53E-02 3.20E-02 Soil 22PI299-8 300-YARD.2-10 Cs-137 1.03E-07 33.2% 4.12E-08 688.8 7.48E-02 2.99E-02 Soil 22PI299-9 300-YARD.2-11 Cs-137 6.59E-07 11.1% 6.05E-08 854.3 3.86E-01 3.54E-02 Soil 22PI299-10 300-YARD.2-12 Cs-137 8.19E-08 51.1% 4.84E-08 774.1 5.29E-02 3.13E-02 Soil 22PI299-11 300-YARD.2-13 Cs-137 2.87E-07 21.3% 6.18E-08 666.2 2.15E-01 4.64E-02 Soil 22PI299-12 300-YARD.2-13D Cs-137 2.18E-07 18.4% 3.98E-08 633.1 1.72E-01 3.14E-02 Soil 22PI299-13 300-YARD.2-14 Cs-137 3.26E-07 16.9% 5.73E-08 775.0 2.10E-01 3.70E-02 Soil 22PI299-14 300-YARD.2-15 None .............. .............. .............. 898.9 .............. ..............
Soil 22PI362-2 By Tunnel Drain Cs-137 2.75E-07 18.1% 4.89E-08 1039.1 1.32E-01 2.35E-02 31
- ENERCON Nuke people bwld1ng a tomorrow Excellence-Every proJect Everyday.
SDR Radiological Characterization Report REN-TR-22-011 Revision 1 Figure 4-10: 300 Area Scoping Gamma Walkovers and Sample Locations Map Legend Gamma CP!Iil
, .raa - 1a.co:1 SUbjG.ct P r*op <~rty:*
'.'l!Uedb:-5: tt x ~~ r C'enter "olf.I \"~ F\* t'l't.~=!
- un:.t.. ::ill'-;,nlo:.
Table 4.11: 300 Area Scoping Soil Sample Results Sample Activity 2Sigma MDC Sample ID Description Nuclide Type (uCi/ml) (%) (uCi/ml)
Soil 22PI220-1 VNC-2022-SITE-S0-002 Cs-137 6.12E-08 59.3% 4.97E-08 Soil 22PI220-2 VNC-2022-SITE-S0-003 Cs-137 8.10E-08 53.4% 5.51E-08 Soil 22PI220-3 VNC-2022-VBWR-S0-004 None Detected N/A N/A N/A Soil 22PI220-4 VNC-2022-VBWR-S0-005 Cs-137 1.90E-07 26.2% 5.39E-08 Soil 22PI220-5 VNC-2022-VBWR-S0-006 None Detected N/A N/A N/A Soil 22PI220-6 VNC-2022-VBWR-S0-007 Cs-137 1.35E-07 36.1% 5.81E-08 Soil 22PI220-7 VNC-2022-VBWR-S0-008 Cs-137 5.83E-08 46.6% 3.42E-08 Soil 22PI220-8 VNC-2022-VBWR-S0-009 Cs-137 1.93E-07 26.1% 5.67E-08 Soil 22PI220-9 VNC-2022-VBWR-S0-010 Cs-137 4.20E-07 12.2% 3.97E-08 Soil 22PI220-10 VNC-2022-VBWR-S0-011 Cs-137 1.11E-07 36.4% 5.06E-08 Soil 22PI220-11 VNC-2022-VBWR-S0-012 Cs-137 1.01E-07 36.4% 4.11E-08 Soil 22PI220-12 VNC-2022-VBWR-S0-013 Cs-137 9.42E-08 52.7% 6.11E-08 Soil 22PI220-13 VNC-2022-VBWR-S0-014 Cs-137 1.69E-07 24.0% 4.00E-08 Soil 22PI220-14 VNC-2022-VBWR-S0-015 Cs-137 8.46E-08 48.0% 5.05E-08 Soil 22PI220-15 VNC-2022-VBWR-S0-016 Cs-137 8.88E-08 41.6% 3.98E-08 Soil 22PI220-16 VNC-2022-VBWR-S0-017 Cs-137 1.43E-07 30.5% 4.92E-08 32
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 22PI220-17 VNC-2022-VBWR-50-023 Cs-137 Co-60 4.2.2 Building 300, Office Building The 300 building is an office building that contains a wide assortment of workspaces, offices, laboratories, operating station, a hot cell, control rooms, office storage, RAM Storage and restrooms.
The following rooms in building 300 were identified as impacted with varying MARSSIM classifications:
Table 4.12: Building 300 Impacted Rooms 103 105 113 115 118 119 121 122 201 203 216 108A 108B 108C 120C 209A 209B 209C Hall/West Entry Hot Cell Hot Cell Airlock Main Hall1 Main Hall3 Mechanical access Staircase 2-1 Annex Rooms currently considered Class 3 but that area potentially non-impacted include:
Table 4.13: Building 300 Potentially Non-Impacted Rooms 114 116 117 207 208 211 212 213 217 218 219 208A 208B Main Hall2 Mechanical access Staircase 1-1 Staircase 1-2 Staircase 2-2 A summary of the measurement results for the impacted rooms in building 300 are in Table 4.14.
Table 4.14: Building 300 {Impacted rooms) Measurement Results Measurement Average (net) Maximum (net) 2 Removable Alpha 1 dpm/100cm 44 dpm/100cm 2 Removable Beta 26 dpm/100cm 2 3,483 dpm/100cm 2 Total (static) Alpha 39 dpm/100cm 2 3,271 dpm/100cm 2 2
Total (static) Beta 11,148 dpm/100cm 4.43E+06 dpm/100cm 2 Gamma Dose 3 !J.Rihr 112 !J.Rihr 4.2.3 Building 301, VBWR Reactor Containment Building 301, i.e., reactor enclosure VBWR, has two levels (Basement, Level 1) and was previously known to be contaminated. A limited effort was put into surveying this building as remediation for lead and asbestos was pending. The VBWR has containment piping systems and equipment have been removed during earlier remedial action and is in a semi-gutted mode.
33
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 Building 304 also affected the background levels in 301. Surveys in 301 resulted in overall average and maximum results presented in Table 4.15. Contamination is generally spread throughout each level with the highest levels located on the basement level. Building 301 is impacted and requires remediation.
Table 4.15: Building 301 Measurement Results Measurement Average (net) Maximum (net)
Removable Alpha 2 dpm/100cm 2 24 dpm/100cm 2 Removable Beta 1,972 dpm/100cm 2 59,704 dpm/100cm 2 Total (static) Alpha 12,195 dpm/100cm 2 1,080 dpm/100cm 2 Total (static) Beta 9.36E+05 dpm/100cm 2 4.87E+07 dpm/100cm 2 Gamma Dose 523 !J.Rihr 7,000 !J.Rihr 4.2.4 Building 302, Steam Turbine Building Building 302 is a 2-story warehouse/electrical building that formerly was used as the steam turbine building. Upon scoping, contamination was encountered in multiple locations on the first floor.
There were multiple Radioactive Material Drums being stored in the building as well as an access port to a large highly contaminated trench. The Characterization crew were unable to survey the interior ceiling and various other areas due to limited accessibility. Table 4.16 presents the summary of average and maximum values from the scoping surveys. Building 302 requires removal of radioactive waste prior to performing additional surveys to determine the radiological status. Given the buildings historical use, and findings during scoping, it was surveyed as Class 1 and is considered impacted.
Table 4.16: Building 302 Measurement Results Measurement Average (net) Maximum (net)
Removable Alpha 0 dpm/100cm 2 0 dpm/100cm 2 Removable Beta 39 dpm/100cm 2 236 dpm/100cm 2 Total (static) Alpha N/A dpm/100cm 2 157* dpm/100cm 2 Total (static) Beta N/A dpm/100cm 2 6,946* dpm/100cm 2 Gamma Dose N/A !J.Rihr 992* !J.Rihr
- One measurement result 4.2.5 Building 304, Fuel Storage Building Building 304, fuel storage building, is currently housing/storing multiple containers with elevated radiation levels. This building is impacting a large footprint of the 300 area as gamma radiation from materials stored within can be detected approximately 100 yards away on the south fence line. A limited removable activity survey was performed in this building to provide information of potential radiological conditions once the containers are removed. Table 4.17provides the removable activity results summary. Additional data collection is required to determine future actions once the materials have been removed. Given the buildings historical use, it is considered impacted.
34
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 Table 4.17: Building 304 Measurement Results Measurement Average (net) Maximum (net)
Removable Alpha 0 dpm/100cm 2 0 dpm/100cm 2 Removable Beta 77 dpm/100cm 2 418 dpm/100cm 2 Total (static) Alpha N/A dpm/100cm 2 N/A dpm/100cm 2 Total (static) Beta N/A dpm/100cm 2 N/A dpm/100cm 2 Gamma Dose N/A !J.Rihr N/A !J.Rihr 4.2.6 Building 348, Stress Corrosion Facility Given the age of the site and the limited information found relating to site incidents, 348 was surveyed as part of scoping with no elevated contamination encountered. However, Building 304 contributes significantly to gamma background levels in building 348 as noted in the footnote beneath Table 4.18, which provides a summary of survey results.
Table 4.18: Building 348 Measurement Results Measurement Average (net) Maximum (net)
Removable Alpha 0 dpm/100cm 2 4 dpm/100cm 2 Removable Beta 40 dpm/100cm 2 428 dpm/100cm 2 Total (static) Alpha 36 dpm/100cm 2 149 dpm/100cm 2 Total (static) Beta 0* dpm/100cm 2 0* dpm/100cm 2 Gamma Dose N/A !J.Rihr N/A !J.Rihr
- H1gh beta/gma background from Bmldmg 304 resulted mall net measurements :SO dpm/1 00cm2 4.2.7 Building 351, EVESR Reactor Containment Building 351, i.e., EVESR containment building, has six levels (487-ft, 500-ft, 503-ft, 519-ft, 534-ft) and was previously known to be contaminated. Surveys in 351 resulted in overall average and maximum results presented in Table 4. Contamination is present throughout the building on each level with the highest levels located on the 534-foot level. Building 351 is impacted and requires remediation. Removal of interferences, i.e., piping, equipment, waste, et al, is required throughout the building prior to performing a comprehensive radiological survey for remedial planning.
Table 4.19: Building 351 Measurement Results Measurement Average (net) Maximum (net)
Removable Alpha 2 dpm/100cm 2 19 dpm/100cm 2 Removable Beta 1,091 dpm/100cm 2 38,034 dpm/100cm 2 Total (static) Alpha 466 dpm/100cm 2 1,878 dpm/100cm 2 Total (static) Beta 2.15E+06 dpm/100cm 2 2.14E+07 dpm/100cm 2 Gamma Dose 200 !J.Rihr 1,600 !J.Rihr 4.2.8 Building 352, EVESR Condenser Building Building 352, the EVESR condenser building and identified on historical drawings as "Dump Condenser and Miscellaneous Equipment Building". Resin processing was performed in portions 35
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 of Building 352. Access is gained to underground tunnels that connect Building 352 to Building 351 (EVESR Containment). These tunnels are discussed separately below. Surveys in 352 resulted in average and maximum results presented in Table 4.20. Building 352 is impacted and requires remediation.
Table 4.20: Building 352 Measurement Results Measurement Average (net) Maximum (net)
Removable Alpha 2 dpm/100cm 2 18 dpm/100cm 2 Removable Beta 120 dpm/100cm 2 5585 dpm/100cm 2 Total (static) Alpha 19 dpm/100cm 2 125 dpm/100cm 2 Total (static) Beta 2.06E+04 dpm/100cm 2 1.64E+06 dpm/100cm 2 Gamma Dose 6 !J.Rihr 37 !J.Rihr 4.2.9 Underground Equipment Tunnels Between 351 and 352 The underground equipment tunnels between Building 351 and Building 352 allow for process piping, equipment, and penetration access. The tunnels are known to be contaminated. Floor drains present in the tunnels exhibit elevated dose rates indicating contaminated piping beneath the floor.
The underground tunnels between 3 51 and 3 52 are impacted and require remediation.
Table 4.21: Tunnels Measurement Results Measurement Average (net) Maximum (net)
Removable Alpha 1 dpm/100cm 2 6 dpm/100cm 2 Removable Beta 907 dpm/100cm 2 4,455 dpm/100cm 2 Total (static) Alpha 188 dpm/100cm 2 682 dpm/100cm 2 Total (static) Beta 5.76E+05 dpm/100cm 2 5.02E+06 dpm/100cm 2 Gamma Dose 137 !J.Rihr 2,185 !J.Rihr 4.3 Data Gaps Radionuclide and curie content of the reactors, associated systems, components, and tanks, and other items destined for disposal as radioactive waste will be required prior to preparing them for shipment and disposal.
Determination of activation products and depth profiles in materials surrounding the reactors will be required to determine radionuclide content.
High activity radioactive material from VNC operations is stored in Building 304 which is not part of the current characterization scope, presenting a challenge to performing characterization over a large portion of the 300 Area (VBWR/EVESR).
Elevated gamma background levels are seen in all directions from Building 304, west of the 300 area past the Hillside Storage Area, north past the 300 area fence line and adjacent roadway, east toward the 300 area fence line and south toward Lake Lee.
Similarly, drums stored in Building 302 hampered characterization efforts in that vicinity.
36
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 Areas of the site and property not within the scope of this radiological characterization effort including Building 304 high activity material, miscellaneous stored radioactive materials and tanks, the Building 349 Waste Evaporator Plant and the Hillside Storage Area all contribute to elevated gamma background levels in some areas and can affect survey results including beta readings. Due to elevated gamma readings, it was not practical to perform gamma scan surveys for drainage systems, ditches, and swales on the south portion of the 300 area to Lake Lee.
Surface soil samples were obtained at mostly random locations due to the inability to identify elevated areas of soil activity in both the 200 and 300 areas due to elevated gamma readings Due to these elevated readings it is not practical to perform soil walkover scanning to identify elevated areas for sampling including sampling at depth.
It was determined that it would be most cost efficient to re-address soils in the future, after background gamma levels have been reduced by moving high activity radioactive material containers or shipping those identified as waste to an appropriate disposal site.
Currently, there is little information about sub-surface radioactivity and no effort was made as part of this characterization effort to characterize soils beneath buildings. Little investigation was performed outside of the 300 area fences, other than the septic tank that was discovered late in the characterization effort.
Further investigation into the impact the site has had on ditches, swales, drains heading toward Lake Lee or other areas may need to be performed in the future after gamma background levels have been reduced. The same may need to be performed in the 200 area around the Tank Farm. These areas can be more easily and economically addressed after elevated gamma readings from the above-mentioned areas have been reduced and during and after GETR Tank farm remediation work.
37
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1
- 5. QUALITY ASSURANCE AND QUALITY CONTROL ReNuke and ENERCON ensured that quality and regulatory requirements were satisfied during the characterization effort. Activities were controlled by procedures and the Site Characterization Plan. These documents included the following Quality Control (QC) measures as an integral part of the survey process.
5.1 General Provisions 5.1.1 Written Procedures Survey tasks were controlled by characterization survey instructions contained in each survey package, ReNuke procedures, and the VNC Characterization Plan. The following procedures were used and referenced in the characterization survey instruction during the characterization project:
RENUKE-RP-1 00 Radiation Protection Plan RENUKE-RP-1 05 Instrumentation and Measurements RENUKE-RP-105.100 Instrumentation Calibration RENUKE-RP-105.200 Instrumentation Setup and Performance Checks RENUKE-RP-105.300 Instrumentation Selection and Use RENUKE-RP-105.400 Calculation Detection Sensitivity RENUKE-RP-105.500 Radiological Survey Activities RENUKE-RP-114 Training and Qualifications ofRP Personnel RENUKE-RP-115 Training in Radiation Protection RENUKE-RP-132 Radioactive Source Control RENUKE-RP-501 Radiation protection Instrumentation VNC-HASP-300 Characterization Health and Safety Plan 5.1.2 Instrumentation Selection, Calibration, and Use ReNuke selected instruments that are proven to reliably detect the radionuclides present at VNC.
Instruments were calibrated by qualified vendors under approved procedures using calibration sources traceable to the National Institute of Standards and Technology. All detectors were subject to daily response checks when in use per guidance established in American National Standard Institute (ANSI) standard ANSI N323-1997.
5.1.3 Chain of Custody The Chain of Custody procedure located in RENUKE-RP-105 .500 established responsibility for the custody of samples from the time of collection until results were obtained. All samples shipped off site for analysis were accompanied by a chain-of-custody record to track each sample.
38
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 5.1.4 Independent Review of Survey Results The survey package and survey data from each area received an independent review to verify all documentation is complete and accurate.
5.2 Training All project personnel received site specific training to identify the specific hazards present in the survey areas in addition to the characterization process. The training included a briefing and review of the VNC Characterization Plan, ReNuke procedures, and the Site Health and Safety Plan.
Personnel were also required to read each document. Copies of all training records were maintained on site through the duration of the onsite activities.
5.3 Sample Analysis ReNuke and ENERCON utilized both the onsite laboratory and a third-party vendor, GEL Laboratories (GEL) in Charleston, SC, for all radioanalytical services during the characterization project. All samples sent to GEL were accompanied by a Chain of Custody with their receipt acknowledgement via email. GEL is used extensively in the nuclear industry for environmental, bioassay, and waste characterization analyses. GEL provides QC with all laboratory reports including blanks, spikes, and duplicates.
39
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1
- 6. LIMITATIONS 6.1 High Background Areas As noted throughout this report, there were several areas where the background radiation was elevated due to the presence of stored radioactive materials (304 building, 200 tank farm, 200 area). The status of these areas at the time of the survey is documented in the photographs in Appendix A In these areas, surveys may not be complete, but will be verified following the pre-decommissioning cleanout of legacy materials and stored radioactive materials. Due to the time constraint put on this project, characterization was required to continue with the Building 304 gamma radiation impacting much of the 300 area. Similarly, the 200 area Tank Farm elevates gamma exposure rates in the north portion of the 200 area. There is limited accessibility to soil in this area and the Tank Farm is known to need remediated. Evaluating the best approach for these effected areas, it was decided to take physical samples as directed in the DPCs, but to hold off on gamma walkovers, searching for hotspots, as this can most effectively be done at a later date.
Systematic samples but not judgmental or biased samples were taken in such areas due to the elevated gamma readings. Future remediation and D&D activities will allow for performance of additional characterization surveys and sampling in the 200 and 300 areas. During and following future remedial activities (disposal campaign(s)/D&D), additional radiological surveys and sampling will be performed. Results will be analyzed to ensure the information submitted in the DP remains valid. A revised DP will be submitted to the NRC if a revision is required.
6.2 Internal Activity The internal surfaces of various components potentially containing radioactive materials were not surveyed at this time. This includes primary coolant piping and tanks, heat exchangers, water sampling systems, building ventilation, the primary coolant pumps, GETR and EVESR reactor vessels and other system piping, ducts and tanks. For the most part, these SSCs will be removed and disposed of as radioactive waste during decommissioning. Follow-up sutveys will be performed as needed to support final status.
40
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1
- 7. REFERENCES
- 1. CP-VNC-RADChar-00007, Vallecitos Nuclear Center Decommissioning Characterization Plan, 2022.
- 2. VNC-HASP-300, Vallecitos Nuclear Center Characterization Site Health and Safety Plan, 2022
- 3. NUREG-153 7, Part 1, Chapter 17, Guidelines for Preparing and Reviewing Applications for Licensing ofNon-Power Reactors
- 4. NUREG-1757, Consolidated Decommissioning Guidance
- 5. NUREG-1575, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM).
- 6. 10 CFR 20, Standards for the Protection Against Radiation
- 7. REN-TR-003, Vallecitos Nuclear Center Decommissioning Industrial Hygiene Scoping Report, 2022.
- 8. ENERCON I ReNuke, Vallecitos Nuclear Center Decommissoning Environmental Scoping Report, 2022.
- 9. Chesapeake Nuclear Services, Inc., Radiological Characterization and Source Term for the Shutdown Reactors at Vallecitos Nuclear Center, 2019.
- 10. REN-TR-22-010, Vallecitos Nuclear Center Decommisisoning Historical Site Assessment, 2022.
- 11. United States Nuclear Regulatory Commission, Decontamination and Decommissioning (DandD) Software Package.
- 12. Argonne National Laboratory, RESRAD Family of Codes.
- 13. United States Federal Government, NUREG-1507 Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions, 1997.
- 14. ANSI N323-1997, Radiation Protection Instrumentation Test and Calibration, Portable Survey Instruments, American National Standard Institute (ANSI) Standard
- 15. NUREG/CR-3474, Long-Lived Activation Products in Reactor Materials.
- 16. NUREG/CR-4289, Residual Radionuclide Contamination Within and Around Commercial Nuclear Power Plants.
41
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1
- 17. REN-TR-22-007, Vallecitos Nuclear Center Decommissioning Scoping Plan for Environmental Compliance
- 18. REN-TR-22-005, Vallecitos Nuclear Center Decommissioning Biological Hazards Observation Report
- 19. Regulatory Guide 1.179, StandardFormatandContentofLicense Termination Plans for Nuclear Power Reactors
- 20. Chesapeake Nuclear Services, Radiological Radiological Assessment of Outside Contaminated Areas at the Vallecitos Nuclear Center, 2020.
42
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 APPENDICES 43
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 Appendix A List of Survey Units with MARSSIM Classification
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 MARSSIM Building Room Class COMMENTS 200 102 1 Office 200 103 2 Office 200 104 1 Office 200 106 2 Office 200 108 1 Office 200 110 2 Office 200 111 2 Office 200 112 1 Office 200 113 2 Office 200 114 2 Office 200 115 2 Office 200 116 1 Office 200 117 2 Office 200 118 2 Office 200 125 1 Office 200 CR 1 Control room 200 CRE 1 Office/Entry combined as 1 unit 200 CRO 1 Office/Entry combined as 1 unit 200 Exteriors 3 200 HALL. I 1 Halls combined as 1 unit 200 HALL.2 1 Halls combined as 1 unit 200 HALL.3 1 Halls combined as 1 unit 200 HALL.4 1 Halls combined as 1 unit 200 JANITOR 1 Janitor/Storage rooms combined as 1 unit 200 KITCHEN 1 Kitchen 200 MEN 1 Men's changing room 200 SNM 1 Special nuclear material storage 200 STORAGE 1 Janitor/Storage rooms combined as 1 unit 200 WOMEN 1 Women's changing room 200 YARD. I 2 Open land inside 200 area fence 200 YARD.2 3 Open land outside 200 area fence 200 YARD. I 1 200 inside fence hotlist items 1st floor, equipment hatch, and personal hatch 201 EQUIP 1 combined as 1 survey unit for characterization 201 L552 1 GETR 552' level 1st fl, equipment hatch, and personal hatch 201 L567 1 combined as 1 survey unit for characterization 201 L589 1 GETR 589' level 201 L611 1 GETR 611' level
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 MARSSIM Building Room Class COMMENTS 1st fl, equipment hatch, and personal hatch 201 PERS 1 combined as 1 survey unit for characterization 202 101 1 Workshop/garage 202 102 1 Workshop/garage 202 BERM 1 CA & BERM Combined to 1 survey unit 202 CA 1 CA & BERM Combined to 1 survey unit Concrete building divided into 4 interior rooms. The 210 101 1 north-western most room is Room 101.
Concrete building divided into 4 interior rooms. The 210 102 1 north-eastern most room is Room 102.
Concrete building divided into 4 interior rooms. The 210 103 1 middle room on the east side is Room 103.
Concrete building divided into 4 interior rooms. The 210 104 1 large room on the south side is Room 104.
210 201 1 210 2nd floor all rooms combined as 1 survey unit 210 202 1 210 2nd floor all rooms combined as 1 survey unit 210 203 1 210 2nd floor all rooms combined as 1 survey unit 210 204 1 210 2nd floor all rooms combined as 1 survey unit 210 205 1 210 2nd floor all rooms combined as 1 survey unit 213 GARAGE 2 214 214 3 217 BLDG 2 217 101 2 217 102 2 217 103 2 217 104 2 217 201 2 217 202 2 217 203 2 217 204 2 217 217B 2 217 OFF 2 300 103 1 300 105 2 300 113 1 300 114 3 Potentially non-impacted 300 115 1 300 116 3 Potentially non-impacted 300 117 3 Potentially non-impacted 300 118 3
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 300 119 2
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 MARSSIM Building Room Class COMMENTS 300 121 2 300 122 3 300 201 2 300 203 2 300 207 3 Potentially non-impacted 300 208 3 Potentially non-impacted 300 211 3 Potentially non-impacted 300 212 3 Potentially non-impacted 300 213 3 Potentially non-impacted 300 216 2 300 217 3 Potentially non-impacted 300 218 3 Potentially non-impacted 300 219 3 Potentially non-impacted 300 108A 1 300 108B 2 300 108C 3 300 120C 1 300 208A 3 Potentially non-impacted 300 208B 3 Potentially non-impacted 300 209A 2 300 209B 1 300 209C 1 300 Exterior Platform 3 Potentially non-impacted 300 Exteriors 3 300 Hall/West Entry 2 300 Hot Cell 1 300 Hot Cell Airlock 1 300 MainHalll 3 300 MainHall2 3 Potentially non-impacted 300 MainHall3 3 300 Mechanical access 2 Inaccessible 300 Mechanical access 3 Potentially non-impacted 300 Staircase 1-1 3 Potentially non-impacted 300 Staircase 1-2 3 Potentially non-impacted 300 Staircase 2-1 3 300 Staircase 2-2 3 Potentially non-impacted 300 YARD.l 2 Gamma walkover scans I Soil samples 300 YARD.2 3 Gamma walkover scans I Soil samples
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 300 WATERCOLL 1
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 MARSSIM Building Room Class COMMENTS 301 PORT.l 1 301 PORT.2 1 302 101 1 302 102 1 302 103 1 302 104 1 302 105 1 302 BLDG 1 304 WHO 1 304 WH.l 1 348 101 3 Potentially non-impacted 348 102 3 Potentially non-impacted 348 103 3 Potentially non-impacted 348 104 3 Potentially non-impacted 348 105 3 Potentially non-impacted 348 Hall 3 Potentially non-impacted 352 1 1 352 2 1 352 3 1 352 4 1 352 5 1 352 6 1 352 7 1 352 8 1 352 352A 1 352 MAIN 1 300 Annex Annex 1 301 VBWR Basement 1 301 VBWR Equipment Portal 1 301 VBWR Levell 1 301 VBWR Personnel Portal 1 351 EVESR 487level 1 351 EVESR 500 level 1 351 EVESR 503 level 1 351 EVESR 519level 1 351 EVESR 534level 1 351 EVESR 549level 1 213 213 1
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 202 202 1
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 Appendix B VNC GEL Analytical Results Database {Microsoft Excel File)
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 Appendix C VNC Master Survey Results Database {Microsoft Excel file)
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 AppendixD Gamma Walkover Survey Results {Microsoft Excel File)
- ENERCON Nuke SDR Radiological Characterization Report
~ people bwld1ng a tomorrow Excellence-Every proJect Everyday.
REN-TR-22-011 Revision 1 Appendix E VNC Individual Characterization Survey Records
- ENERCON Nuke people bwld1ng a tomorrow Excellence-Every proJect Everyday.
SDR Radiological Characterization Report REN-TR-22-011 Revision 1