ML23057A017

L1-010-102 B FSS Plan

ML23057A017
Person / Time
Site:	La Crosse  File:Dairyland Power Cooperative icon.png
Issue date:	02/27/2023
From:	Marlayna Vaaler Doell LaCrosseSolutions, Reactor Decommissioning Branch
To:
Doell M
Shared Package
ML23057A009	List: ML23057A010 ML23057A011 ML23057A012 ML23057A013 ML23057A014 ML23057A015 ML23057A016 ML23057A017
References
Download: ML23057A017 (15)

Text

LC-FS-PR-002 Final Status Survey Package Development Revision 3 ATTACHMENT 10 FSS Sample Plan Cover Sheet GENERAL SECTION Survey Area No.: 010 Survey Unit No.: L1-010-102 B Survey Unit Name: Reactor Plant Generator Plant Area (RPGPA)

Survey Unit Type: I/S LSE Open Land Area Subsoil Post Remediation

- Open Land - Structural Interior - Structural Exterior - System Classification: - Class 3 - Class 2 - Class 1 PERPARATION FOR FINAL STATUS SURVEY ACTIVITIES (a checked box signifies an affirmative response)

Reference Grid and/or Reference Coordinates have been established (if appropriate).

A walk-down has been performed of the survey unit and a completed Pre-Turnover Walk-Down form completed in accordance with LC-FS-PR-010, Isolation and Control for Final Status Survey is included with this Sample Plan.

Area Turnover and Control Checklist completed in accordance with LC-FS-PR-010, Isolation and Control for Final Status Survey is included with this Sample Plan and all items and issues that were identified have been resolved.

All preparation activities (clear vegetation, erect scaffolding, etc.) necessary to perform Final Status Surveys have been completed.

Area has been cleared of all non-essential materials and equipment.

Area has been posted and access control measures have been implemented.

ALL ABOVE ACTIONS ARE COMPLETE AND SURVEY UNIT IS PREPARED AND READY FOR FSS ACTIVITIES (signature signifies affirmative response)

FSS Supervisor (Print Name/Signature) Date SURVEY PACKAGE APPROVAL THIS SAMPLE PLAN HAS BEEN COMPLETED, INDEPENDENTLY REVIEWED AND APPROVED FOR IMPLEMENTATION.

Prepared: Date:

(Print Name) (signature)

Approved: Date:

RP FSS Manager (signature)

(Print Name)

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LC-FS-PR-002 Final Status Survey Package Development Revision 3 ATTACHMENT 11 FSS Data Quality Objectives and Survey Design Survey Unit No: L1-010-102 B DATA QUALITY OBJECTIVES 1.0 STATE THE PROBLEM The problem: To demonstrate that the level of residual radioactivity in survey unit L1-010-102 B, designated a Class 1 Final Status Survey (FSS) unit, meets the unrestricted release requirements of 10 CFR 20.1402, Radiological Criteria for Unrestricted Use. The LaCrosse Site Restoration Project (LCSRP) License Termination Plan (LTP) documents the process that will be used to demonstrate that the dose from residual radioactivity, that is distinguishable from background radiation, does not exceed 25 mrem/yr to the Average Member of the Critical Group (AMCG) from all appropriate pathways and to also demonstrate that the residual radioactivity has been reduced to levels that are As Low As Reasonably Achievable (ALARA).

Stakeholders: The primary stakeholders interested in the answer to this problem are Lacrosse Solutions LLC, Dairyland Power Generation LLC, (DPC), the Wisconsin Department of Health Services and the United States Nuclear Regulatory Commission (USNRC).

The Planning Team: The planning team consists of the assigned FSS Supervisor with input from other FSS personnel as well as the Safety Department. The primary decision maker will be the Final Status Survey Supervisor with input from the FSS Manager and the EnergySolutions Director of Radiological Site Closure.

Schedule: A total of EIGHT (8) working days are projected to mobilize and implement the FSS, and to perform a preliminary assessment of the data. One (1) day will be designated to get the survey unit ready for FSS (e.g., marking survey locations). Not included in the schedule is the full data assessment and release record preparation. Weather conditions may temporarily impact the schedule implementation.

Resources: The primary resources needed are the FSS GROUP to prepare the plan and evaluate data, RP/FSS Supervision to monitor and coordinate field activities, a Graphics/GPS Specialist to prepare survey maps, layout diagrams, composite view drawings, and other graphics as necessary to support survey design and reporting, and FSS Technicians to acquire measurements and samples. The LaCrosseSolutions on-site laboratory will analyze all media samples when taken and provide analytical results. A qualified off-site laboratory will be employed to analyze samples for Hard-to-Detect (HTD)

Radionuclides of Concern (ROC). A direct push sampling contractor has also been subcontracted to obtain the samples.

2.0 IDENTIFY THE DECISION Principal Study Question: Are the concentrations of residual radioactivity in the sub-foundation soil (post structure removal), below the Operational Derived Concentration Guideline Levels (Operational DCGLs) that are used to demonstrate compliance with the 25 mrem/yr dose criterion.

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LC-FS-PR-002 Final Status Survey Package Development Revision 3 Alternate Actions: Alternative actions include failure of the survey unit, remediation and resampling the area.

The Decision: If the survey unit fails to demonstrate compliance with the release criteria, then the survey unit is not suitable for unrestricted release. Review and confirm the data using the Data Quality Assessment (DQA) process to identify the appropriate additional action or combination of actions.

3.0 IDENTIFY INPUTS TO THE DECISION Information Needed: The FSS is used to verify that the potential dose from residual radioactivity is below the release criterion for each survey unit. For this Class 1 survey unit, the sampled soil will be scanned with a gamma instrument. Scans will be performed with a NaI detector at a rate of 0.5 m/sec and at a detector height of no greater than 3 from the sampling tube. Media samples will be used to quantify soil activity.

Historical Information: The identified area, L1-010-102 B, is a Class 1 area. The area served as a pass through area for piping and ventilation between the Turbine Building and the other buildings. The radionuclides present in the area will be similar and tied to the reactor operation with variations of contamination levels based on past use of systems and processes. The Reactor Plant Generator Plant Area (RPGPA) Sump Area experienced groundwater intrusion due to rising Mississippi River levels and has caused it to become inaccessible. The deepest part of the RPGPA excavation is at about elevation 618. This elevation would equate to the fourth lowest water record of the Mississippi River at Genoa. Operational surveys and sampling during remediation of the area indicate a relatively uniform exposure rate with Cs-137 concentrations ranging from MDA to 6.38 pCi/g. A Radiological Assessment was performed on the accessible portions of the RPGPA area. Four alarms were noted during the scan survey with an alarm set point of background plus a calculated instrument response of 1,762 cpm (8.5 pCi/g Cs-137). Seven judgmental samples were taken during the RA. The results of the analyses indicate Cs-137 concentrations ranging from MDA to 5.37 pCi/g. The maximum SOF was 0.40, with the overall average SOF of the sample set of 0.10 and a SOF standard deviation of 0.14. The table below presents the results of the RA sampling.

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LC-FS-PR-002 Final Status Survey Package Development Revision 3 Measured Inferred Operational Weight Fraction of Sample ID Location ROC Activity Ratio Activity DCGL OpSOF DCGLOPS (g) (pCi/g) (pCi/g) (pCi/g)

Co-60 8.60E-02 3.83E+00 0.02245 Sr-90 0.502 7.78E-02 1.97E+03 0.00004 L1-SUB-TDS-AJGS-B01-SS 0 854 Cs-137 1.55E-01 1.74E+01 0.00891 0.04250 Eu-152 5.14E-02 8.51E+00 0.00604 Eu-154 3.99E-02 7.89E+00 0.00506 Co-60 1.03E-01 3.83E+00 0.02689 Sr-90 0.502 6.53E-01 1.97E+03 0.00033 L1-SUB-TDS-AJGS-B02-SS 0 799 Cs-137 1.30E+00 1.74E+01 0.07476 0.11393 Eu-152 5.85E-03 8.51E+00 0.00069 Eu-154 8.89E-02 7.89E+00 0.01127 Co-60 2.98E-02 3.83E+00 0.00778 Sr-90 0.502 2.11E-02 1.97E+03 0.00001 L1-SUB-TDS-AJGS-B03-SS 0 1063 Cs-137 4.21E-02 1.74E+01 0.00242 0.02507 Eu-152 1.00E-01 8.51E+00 0.01175 Eu-154 2.45E-02 7.89E+00 0.00311 Co-60 0.00E+00 3.83E+00 0.00000 Sr-90 0.502 4.75E-02 1.97E+03 0.00002 L1-SUB-TDS-AJGS-B04-SS 0 806 Cs-137 9.47E-02 1.74E+01 0.00545 0.06435 Eu-152 1.46E-02 8.51E+00 0.00172 Eu-154 4.51E-01 7.89E+00 0.05716 Co-60 2.42E-01 3.83E+00 0.06319 Sr-90 0.502 2.70E+00 1.97E+03 0.00137 L1-SUB-TDS-AJGS-B05-SS 0 845 Cs-137 5.37E+00 1.74E+01 0.30880 0.40179 Eu-152 2.42E-01 8.51E+00 0.02844 Eu-154 0.00E+00 7.89E+00 0.00000 Co-60 2.80E-02 3.83E+00 0.00731 Sr-90 0.502 4.04E-02 1.97E+03 0.00002 L1-SUB-TDS-AJGS-B06-SS 0 988 Cs-137 8.04E-02 1.74E+01 0.00462 0.01753 Eu-152 4.21E-02 8.51E+00 0.00495 Eu-154 4.99E-03 7.89E+00 0.00063 Co-60 9.52E-02 3.83E+00 0.02486 Sr-90 0.502 9.24E-02 1.97E+03 0.00005 L1-SUB-TDS-AJGS-B07-SS 0 822 Cs-137 1.84E-01 1.74E+01 0.01058 0.04385 Eu-152 1.10E-02 8.51E+00 0.00129 Eu-154 5.58E-02 7.89E+00 0.00707 Radionuclides of Concern: The radiological characterization of the LaCrosse Nuclear Power Station (LNPS) for radionuclides of concern is based on concrete core samples obtained at biased locations with elevated contact dose rates and/or evidence of leaks/spills.

LaCrosseSolutions Technical Support Document RS-TD-313196-001, Radionuclides of Concern During LACBWR Decommissioning evaluates the results of the concrete core analysis data from the Reactor Containment, Waste Treatment Building, Waste Gas Tank Vault and the Off-Gas Pipe Tunnel. Insignificant dose contributors were determined consistent with the guidance of NUREG-1757, Volume 2, Revision 1, Consolidated Decommissioning Guidance - Characterization, Survey, and Determination of Radiological Criteria, Final Report. Based upon the analysis, it was determined that Co-60, Sr-90, Cs-137, Eu-152, Eu-154 accounted for nearly 100% of all dose in the contaminated concrete and soil as discussed in Section 5.1 of Chapter 5 of the LTP and is fully accounted-for with the adjustment made to the DCGLs for the contribution of IC radionuclides.

Release Criteria: The table below presents the final Base Case DCGLs for the decommissioning of LCSRP. Residual radionuclide concentrations are required to be less than the LACBWR Base Case DCGLs. Each radionuclide-specific DCGL is equivalent to the level of residual activity (above background levels) that could, when considered independently, result in a TEDE of 25mRem/year to the AMCG. To ensure that the Page 3 of 6

LC-FS-PR-002 Final Status Survey Package Development Revision 3 summation of dose from each source term is 25mRem/year or less after all FSS is completed, Adjusted Base Case DCGLs are reduced based on an expected, or a priori, fraction of the 25mRem/year dose limit from each source term. The reduced DCGL is termed the Operational DCGL.

Base Case DCGL for Soil Operational DCGL for Soil Radionuclide (pCi/g) (pCi/g)

Co-60 1.06E+01 3.83E+00 Sr-90 5.47E+03 1.97E+03 Cs-137 4.83E+01 1.739E+01 Eu-152 2.36E+01 8.51E+00 Eu-154 2.19E+01 7.89E+00 Ten percent of all continuing characterization samples taken will be sent off-site for the full suite of HTD analyses. In addition, a minimum of one sample beyond the 10% minimum will be selected at random, also for HTD analysis. Additionally, if levels of residual radioactivity in an individual sample exceed a SOF of 0.1, then the sample(s) will be analyzed for HTD radionuclides. All samples will be analyzed for tritium.

All FSS samples will be analyzed onsite via gamma spectroscopy and all FSS samples will be sent to the offsite laboratory for H-3 analyses. Three (3) soil samples collected at systematic and/or biased locations during the FSS of the survey area will be analyzed offsite for Sr-90.

Additionally, if a sample exceeds 0.10 of the sum of fractions (SOF) for the operational DCGL with the gamma spec on site analysis then that soil sample will be sent offsite to be analyzed for Sr-90 analysis.

Radiological Survey Data: Analytical data obtained from the analysis of subsurface direct push samples. The action level is the Operational DCGL.

Basis for the Action Level: The action level provides the criterion used during the decision process for choosing among alternative actions (e.g., whether to take action or not to take action or whether to choose one action versus another). The action levels associated with the evaluation of FSS data are specified in the LTP and LaCrosseSolutions procedure LC-FS-PR-008, Final Status Survey Data Assessment.

Basis for Scan Measurements: Scan surveys for this survey unit area of interest will not be performed since the subsurface environment is not accessible for scanning. However, scan surveys of the extracted sampling tubes will be performed with a Ludlum Model 2350-1 Data Logger in combination with Model 44-10 sodium iodide detector. Alarm set points for the scanning for the sampling tubes will not be set. The scanning is a qualitative measurement only.

Basis for Quality Control (QC) Measurements: In compliance with QAPP LC-QA-PN-001 section 4.0, Quality Control (QC) samples are performed primarily as verification that the original characterization and FSS results are valid. Five percent (5%) of all soil samples collected in a survey area, with a minimum of one sample collected, will be the QC requirement. A minimum of two QC samples will be collected.

Investigation Levels: Investigation levels are concentrations of radioactivity that: 1) are Page 4 of 6

LC-FS-PR-002 Final Status Survey Package Development Revision 3 based on the release criteria, and 2) triggers a response, such as further investigation to bound or remediation if exceeded. Exceeding an investigation level will require additional actions in accordance with LaCrosseSolutions procedure LC-FS-PR-008, Final Status Survey Data Assessment. For this Class 1 survey unit, if the Operational DCGL is exceeded, then bound the areal extent and depth of elevated activity and notify the FSS Supervisor. If the Base Case DCGL is exceeded, then the area(s) must be remediated. If the Operational DCGL is exceeded, an evaluation will be made as to the area of the exceedance and its impact on the ultimate release (e.g., the ability to pass the Sign Test).

Sampling and Analysis Methods to Meet the Data Requirements: Systematic soil sample locations have been selected using the VSP software. Sample locations may be moved if there is a physical impedance or safety hazard in the location. The location will be moved to the nearest location without an impedance or hazard with subsequent GPS coordinates obtained. Soils will be sampled to a depth of one meter from the backfill and sand interface (i.e., the elevation of the original excavation).

4.0 DEFINE THE BOUNDARIES OF THE SURVEY Boundaries of the Survey: This survey examines subsurface soil of the identified Class 1 Survey Unit L1-010-102 B.

Temporal boundaries: Inclement weather is always a possibility. Temperature extremes and precipitation could make performing the survey more difficult.

Constraints: The area presents a safety hazard due to being located below the grade level.

Access has been established for safely entering the excavation. Daily inspections are required of the excavation by a competent person.

5.0 DEVELOP A DECISION RULE Decision Rule: If any measurement data results exceed the release criteria, then use the DQA process to evaluate the alternative action or combination of actions.

6.0 SPECIFY TOLERABLE LIMITS ON DECISION ERRORS The Null Hypothesis: Residual radioactivity in the survey unit exceeds the release criterion.

Type I Error: This is also known as the error. This is the error associated with incorrectly concluding the null hypothesis has been rejected. In accordance with LTP section 5.6.2.6, the error was set at 0.05 (5%).

Type II Error: This is also known as the error. This is the error associated with incorrectly concluding the null hypothesis has been accepted. In accordance with LTP section 5.6.2.6, the error was set at 0.05 (5%).

Lower Bound of the Grey Region: Seven soil samples were analyzed and gamma walkovers were performed of the accessible soils during the RA of L1-010-102 B. The average SOF of the sample set was 0.10, with a standard deviation of 0.14. The LBGR is set at 0.10 Sigma: Seven soil samples were analyzed and gamma walkovers were performed of the accessible soils during the RA of L1-010-102 B. The average SOF of the sample set was 0.10, Page 5 of 6

LC-FS-PR-002 Final Status Survey Package Development Revision 3 with a standard deviation of 0.14. Sigma is set at 0.14.

7.0 OPTIMIZE DESIGN Type of statistical test:

Sign Test FSS Data Quality Objectives and Survey Design Number of Systematic samples: The number of systematic survey locations required for sampling of the soil, had the excavation still been open and the soil accessible, is 14. For conservatism, this number was increased to obtain twenty-eight (28) samples via geo-probe at systematic locations and to the depths of the original excavation. Twenty-eight (28) locations for soil samples will be generated using a triangular pattern with a random start point. Sampling will be performed at the locations designated on the CAD drawing survey map. Sample locations may be moved if there is a physical impedance or safety hazard in the location. The location will be moved to the nearest location without an impedance or hazard.

Number of Biased samples and locations: Biased samples can be performed with input from the FSS supervisor. A minimum of three (3) biased samples will be obtained from the unit. One of the three samples will be in the southwest corner of the trench box area (black outlined area on the sample map), which had the highest readings and focus during the remediation of the sump area.

Number of Continuing Characterization samples and locations: As part of this FSS, continuing characterization samples will be obtained. Continuing characterization samples will focus on the RPGPA sump area, areas where drains and suspected broken lines were present in the Turbine Building, as well as the drainage pathway from the southeast of the Reactor Building (tritium contamination). A total of seven (7) continuing characterization samples will be taken.

Number of samples for Quality Control: Two (2) random generated soil samples will be collected. Using a random number generator, the QC location was determined to be at locations B13 and B21.

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LC-FS-PR-002 Final Status Survey Package Development Revision 3 ATTACHMENT 12 FSS Survey Instructions I/S LSE Open Land Area Subsurface Survey Area No.: 010

Description:

Post Remediation Reactor Plant Generator Plant Area Survey Unit No.: L1-010-102 B

Description:

(RPGPA)

Survey Unit Type:

- Open Land - Structure Interior - Structure Exterior - System Survey Unit Classification:

Classification: - Class 3 - Class 2 - Class 1 General Instructions:

1. Personnel will follow all relevant safety directives and procedures while performing this work.

2. Survey and sampling will be performed by qualified technicians under the direction of FSS Supervision.

3. Instrumentation used in the field will be used in accordance with applicable procedures.

4. Portable radiological instrumentation and/or detectors will remain in the custody of the assigned technician, and positive control will be maintained until collected data has been downloaded and instrument has been returned to inventory.

5. Detailed field notes and observations will be documented during survey and sampling.

6. Photographs should be taken as necessary to clarify survey and sampling activities or survey constraints.

7. Samples will be controlled under Chain-of-Custody in accordance with procedure LC-FS-PR-012, Chain-Of-Custody.

8. Documents generated during the performance of survey and sampling will be complete and legible. Corrections will be made using a single lineout followed by an initial and date.

9. Sample & measurement locations will be identified using coordinates consistent with the established reference coordinate system. Sample and measurement locations will be identified by marks or flags prior to and during survey implementation.

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LC-FS-PR-002 Final Status Survey Package Development Revision 3 ATTACHMENT 12 FSS Survey Instructions I/S LSE Open Land Area Survey Area No.: 010

Description:

Subsurface Post Remediation Reactor Plant Generator Plant Area Survey Unit No.: L1-010-102 B

Description:

(RPGPA)

Specific Instructions:

1. Review current and/or previous radiological survey results and/or drawings for the areas within the scope of this survey package (e.g., LACBWR Radiological Characterization Survey Report for October and November 2014 Field Work).

2. Initialize and maintain an Attachment 13, FSS FIELD LOG from the survey package. All FSS Technicians and the FSS Supervisor shall ensure sufficient detail is included in the Field Log such as: date, time, and location where each measurement or soil sample is attained, any anomalies (impediments to sample, etc.), and personnel present in the survey unit during the survey (non-FSS personnel). Proceed to the survey unit area and perform a walk-down and visually inspect the land areas within the survey unit.

Systematic survey points will be developed for soil surveys using the VSP program and the QC locations will be a randomly selected. GPS will be used to identify the systematic locations. All samples will be analyzed onsite by gamma spectroscopy after drying.

3. Scan surveys for this survey unit area of interest will not be performed. Scan surveys of the extracted sampling tubes will be performed.

4. Alarm set points for the scanning for the sampling tubes will not be set. The scanning is a qualitative measurement only.

5. Scan sampling tubes using a Model 2350-1 data logger in Latching Mode paired with a Model 44-10 detector. Perform gamma scans by scanning at a scan speed of 0.5 meters per second while maintaining the detector end-cap less than three inches from the tube surface.

A. In preparation for using the Model 2350-1 data logger in Latching Mode, ensure that the meters response time is set to a fixed response using command (G2) and that the fixed response time constant is set to 1 second using command (SXG1).

B. Display the Latching Mode screen using command (SVD7).

C. Monitor the audible and visual output of the survey meter.

D. Log the maximum rate meter reading electronically using command (Q0).

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LC-FS-PR-002 Final Status Survey Package Development Revision 3 E. Upon completion of the survey, the Model 2350-1 response time should be reset to fast response (variable) using command (G1) and the parameter saved. Turn off the Latching Mode by entering command (SVM0).

6. For direct measurements and sample analyses, MDCs less than 10% of the Operational Derived Concentration Guideline Level (DCGL) are preferable while MDCs up to 50%

of the Operational DCGL are acceptable.

7. A total of 28 systematic samples will be taken within the survey unit. An additional 7 continuing characterization samples and a minimum of 3 judgmental samples will also be obtained. Systematic sampling will be performed at the locations designated on the CAD drawing survey map. Sample locations may be moved if there is a physical impedance or safety hazard in the location. The location will be moved to the nearest location without an impedance or hazard. Sampling will be performed utilizing direct push methods or augering. Soils will be sampled from the interface of backfill and sand (original depth of excavation prior to backfill) to a depth of one meter. Multiple sample pushes are anticipated to be performed at each location to achieve sufficient sample volumes.

8. Scan each sample tube taken at each location. Measure a one meter length from the interface of the backfill and sand downward in elevation (sample zone) and mark the sampling tube(s). The one meter sample zone from the interface of the backfill and sand may span two sampling tubes. Account for the volume in the first sampling tube when measuring the second sample tube. Cut the sampling tube at each mark. Multiple sample pushes may be required to obtain sufficient volume. The first direct push will be performed with a dual tube. This method collects all materials to a desired depth by using multiple tubes. Additional samples may be obtained from each location with the use of a MC-5 sample head. This method collects only the four foot section from a starting elevation (obtained from the dual tube). Collect and homogenize the sample zone from each sample tube. Archive any other portions of the sample tubes. The volume above and/or sample below the one meter sample zone will be analyzed if the original sample exceeds 0.10 of the sum of fractions (SOF). Split soil samples will be collected at all soil sample locations. The split will be maintained onsite in the event that regulators request the sample media.

9. Continuing Characterization samples will focus on the RPGPA sump area, areas where drains were present in the Turbine Building, as well as the drainage pathway from the southeast of the Reactor Building (tritium contamination). A total of seven (7) continuing characterization samples will be taken. NOTE: Continuing characterization samples have a C designator in the sample identification rather than an F designator.

This is utilized to distinguish between continuing characterization and judgmental samples. Additionally, a minimum of three (3) biased samples will be taken within the unit. One of the three samples will be in the southwest corner of the trench box area (black outlined area on the sample map), which had the highest readings and focus during the remediation of the sump area.

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LC-FS-PR-002 Final Status Survey Package Development Revision 3

10. Ten percent of all continuing characterization samples taken will be sent off-site for the full suite of HTD analyses. In addition, a minimum of one sample beyond the 10%

minimum will be selected at random, also for HTD analysis. Additionally, if levels of residual radioactivity in an individual sample exceed a SOF of 0.1, then the sample(s) will be analyzed for HTD radionuclides. All samples will be analyzed for tritium.

11. All FSS samples will be analyzed onsite via gamma spectroscopy and all FSS samples will be sent to the offsite laboratory for H-3 analyses. Three (3) soil samples collected at systematic and/or biased locations during the FSS of the survey area will be analyzed offsite for Sr-90. Additionally, if a sample exceeds 0.10 of the sum of fractions (SOF) for the operational DCGL with the gamma spec on site analysis then that soil sample will be sent offsite to be analyzed for Sr-90.

12. Five percent (5%) of all soil samples collected in a survey area, with a minimum of one sample collected, will be the QC requirement. Using a random number generator, the QC locations were identified as locations B13 and B21.

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LC-FS-PR-002 Final Status Survey Package Development Revision 3 ATTACHMENT 7 Sample & Measurement Unique Identification Designation (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) (12) (13) (14) (15) (16) (17)

L 1 0 1 0 1 0 2 F/C S/J/Q G S B 0 1 S B Classification & Survey Area Survey Unit Number & Survey and Surface Type Sample or Measurement No. Media Type Sequence Indicator Measurement Type 1st digit indicates type of Survey Area 6th ,7th and 8th digits indicate The 9th digit indicate The 11th digit indicates The 13th digit indicates the The 16th and 17th L = Open Land Area Survey Unit Number the type of survey. the type of surface alphabetical sequence. 14th and digits indicate the B = Structural Survey Area (from Tables 6-1 and 6-2) A = Assessment where the 15th digits indicate the numerical type of media that S = System B = Background measurement was measurement number, was sampled.

S = Scoping taken. sequentially 01 through 99 SS = Surface Soil 2nd digit indicates Classification C = Characterization F = Floor Sequence A-J allows the survey SB = Subsurface 1 = Class 1 R = Remedial Action W = Wall Soil 2 = Class 2 unit to be divided into 10 smaller F = FSS C = Ceiling survey units SM = Sediment 3 = Class 3 I = Investigation S = System WT = Water 4 = Non-impacted V = Verification R = Roof LQ = Other liquids 5 = Unassigned Q = QA/QC P = Paved Road besides water 3rd, 4th and 5th digits indicates Survey Area Number The 10th digit G = Ground OL = Oil (The Survey Area Number, Survey Unit Number and indicates the type of L = Water CV = Volumetric classification are taken from the updated master copy of measurement. The 12th digit indicates Concrete Survey Units for Structures that are maintained by the AV = Volumetric B = Background the material FSS Supervisor) Asphalt S = Systematic composition of the surface where the MT = Metal J = Biased PT = Paint I = Investigation measurement was taken. SW = Smear Sample V = Verification BD = Beta Direct Q = QA/QC C = Concrete AD = Alpha Direct M = Metal GM = Gamma W = Wood measurement B = Cinder Block BS = Beta Scan K = Brick GS = Gamma Scan A = Asphalt JS = Juncture Scan S = Soil JD = Juncture T = Tar Direct L = Liquid PS = Penetration O = Other (describe) Scan PD = Penetration Direct Page 1 of 1

LC-FS-PR-002 Final Status Survey Package Development Revision 3 ATTACHMENT 14 FSS Samples/Measurement Identification & Coordinates I/S LSE Open Land Area Survey Area No.: 010

Description:

Subsurface Post Remediation Reactor Plant Generator Plant Area Survey Unit No.: L1-010-102 B

Description:

(RPGPA)

No. Type Media Sample/Measurement ID Number Northing Easting 1 S SB L1-010-102-FSGS-B01-SB 2 S SB L1-010-102-FSGS-B02-SB 3 S SB L1-010-102-FSGS-B03-SB 4 S SB L1-010-102-FSGS-B04-SB 5 S SB L1-010-102-FSGS-B05-SB 6 S SB L1-010-102-FSGS-B06-SB 7 S SB L1-010-102-FSGS-B07-SB 8 S SB L1-010-102-FSGS-B08-SB 9 S SB L1-010-102-FSGS-B09-SB 10 S SB L1-010-102-FSGS-B10-SB 11 S SB L1-010-102-FSGS-B11-SB 12 S SB L1-010-102-FSGS-B12-SB 13 S SB L1-010-102-FSGS-B13-SB 14 S SB L1-010-102-FSGS-B14-SB 15 S SB L1-010-102-FSGS-B15-SB 16 S SB L1-010-102-FSGS-B16-SB 17 S SB L1-010-102-FSGS-B17-SB See Map 18 S SB L1-010-102-FSGS-B18-SB 19 S SB L1-010-102-FSGS-B19-SB 20 S SB L1-010-102-FSGS-B20-SB 21 S SB L1-010-102-FSGS-B21-SB 22 S SB L1-010-102-FSGS-B22-SB 23 S SB L1-010-102-FSGS-B23-SB 24 S SB L1-010-102-FSGS-B24-SB 25 S SB L1-010-102-FSGS-B25-SB 26 S SB L1-010-102-FSGS-B26-SB 27 S SB L1-010-102-FSGS-B27-SB 28 S SB L1-010-102-FSGS-B28-SB 27 C SB L1-010-102-CJGS-B01-SB 28 C SB L1-010-102-CJGS-B02-SB 29 C SB L1-010-102-CJGS-B03-SB 30 C SB L1-010-102-CJGS-B04-SB 31 C SB L1-010-102-CJGS-B05-SB 32 C SB L1-010-102-CJGS-B06-SB

LC-FS-PR-002 Final Status Survey Package Development Revision 3 33 C SB L1-010-102-CJGS-B07-SB 34 J SB L1-010-102-FJGS-B29-SB 35 J SB L1-010-102-FJGS-B30-SB 36 J SB L1-010-102-FJGS-B31-SB 37 Q SB L1-010-102-FQGS-B13-SB 38 Q SB L1-010-102-FQGS-B21-SB Type: B = Background, R = Random, S = Systematic, J = Biased, I = Investigation, V = Verification, Q = QA/QC Media: SS = Surface Soil, SB = Subsurface Soil, SM = Sediment, WT = Water, CV = Volumetric Concrete, AV = Volumetric Asphalt, MT =

Metal, PT = Paint, SW = Smear, TB = Direct Beta-gamma Measurement, TA = Direct Alpha Measurement, GM = Static Gamma Measurement