ML063130314

From kanterella
Jump to navigation Jump to search
Attachment 8, Class 1 Area - Final Status Survey, 09Cx31, Excavated Soil from Screenhouse Area
ML063130314
Person / Time
Site: Big Rock Point  File:Consumers Energy icon.png
Issue date: 10/09/2000
From:
Consumers Energy
To:
NRC/FSME
References
Download: ML063130314 (43)
v • d • e


Text

ATTACHMENT 8 CONSUMERS ENERGY BIG ROCKPOINT DOCKET NUMBERS 50-155 AND 72-043 TRANSMITTAL OF SURVEY PACKAGES IN SUPPORT OF BIG ROCK POINT PHASED LICENSE TERMINATION CLASS I AREA-FINAL STATUS SURVEY, 09CX3 1, EXCAVATED SOIL FROM SCREENHOUSE AREA October 9, 2006 42 Pages

Final Status Survey 09C, 31 Excavated Soil from Screenhouse Area Survey Unit 09 Survey Date: 09-23-2004 SURVEY PACKAGE CLOSURE Final Status Survey Documentation is authorized for closure. All required reviews are completed and data analysis results meets the criteria established for unrestricted release as clean fill available for construction usage.

Signed: ý aa4-ýZ Date: ii-1i-o "

(E isor)

Superv S ign d:G Signed: _ ,_ -- ___.__Date: I2--O9 -oc (tS Superintendent)

Signed: Signed: Date: /)~9~e~~l

/2 091

"(RP & ES Manager)

I

ý f*oý II--,).. .I

... IF I II \V/ Iý I-n)

IN JAN 20 2005 i i ] - i I I i ! _- ,

Final Status Survey Area Requirements Survey 09CX3 1 Excavated Soil from Screenhouse Area Survey Description Final Status Survey 0 9 Cx3 1 encompasses an 825 m 2 area composed of excavated soil originating from tank and piping removal located in Survey Unit 09. Based on Site Characterization (LTP, Appendix 2E) and supporting surveys conducted during the excavation process, the residual radioactivity in soil removed from this area is not expected to exceed fractional concentrations of the DCGL value.

The excavated soil for Final Status Survey (FSS) will be graded to a maximum depth of one (1) meter and surveyed as a Class 1 area in accordance with Special Case Surveys, Procedure RM-76, FinalStatus Survey Design, Section 2.4, and the requirements established in LTP 5.4.2.4 as revised. Sample locations will be established by random start, square grid pattern over the graded area. Each soil sample will be a full core homogenized composite that is representative of total soil thickness. Surface scanning will be conducted over 100% of the survey area.

History The excavated soil for FSS originates from a minor area in Survey Unit 09 that contained subsurface yard piping, storm drain piping, and the liquid radwaste release pipe. This location is a Class 1 area immediately east and south of the Screenhouse.

Current Radiological Status The Historical Site Assessment did not indicate the potential for residual radioactivity in this area. Site characterization analyses and surveys conducted during soil excavation have not identified residual radioactivity above trace concentration levels.

Quality Assurance/Quality Control As a minimum 5% of the sample population of this survey shall be selected for QA/QC verification in accordance with RM-79, FinalStatus Survey Qualtiy Control. Both split samples and sample recounts will take place. In addition, a minimum of 5% of the survey area will receive a verification scan. QNQC soil samples and verification scan locations will be selected using the RAND function in Microsoft 2000 software program.

Additional Sample Analysis Requirements The area of soil excavation intersects the identified waterborne pathway for Tritium migration and shall require Tritium in soil analyses for a minimum of 10% of the sample population.

Tritium soil samples will be sent to an independent laboratory for analysis.

FSS Survey Area Requirements

... . . i.... . ... .. 09q,31

'Pa~e -1f otv-

Post-Construction Expectations Survey 09CX3 1 will be performed in the following activity sequence:

1. Walkdown: Site Characterization personnel will perform a walkdown assessment to insure survey area preparations are complete and confirm that the following post-construction expectations have been satisfied:

a Groundwater and Surface water control is adequate S All construction debris has been removed from the survey area S The current survey area status meets all applicable safety requirements

2. Survey Area Isolation and Control: Control measures will be established to ensure that any potential ongoing decommissioning activities in adjacent locations do not impact the current survey area status. Isolation and control measures include postings, barriers, access points, and the evaluation of ongoing work activities in adjacent areas.
3. Survey Design and Execution: Survey design and execution will follow the Data Quality Objectives for Survey 09Cx31 in accordance with the survey requirements established in RM-76, Final Status Survey Design, RM-77, FinalStatus Survey Implementation, and LTP, Chapter 5. Survey size will be based on the statistical requirements of the Sign Test for Class 1 areas with soil samples collected in random start, systematic data point locations. Surface scanning will be performed with 100% survey area coverage. This survey will be conducted in accordance with approved BRP procedures and follow the guidance of NUREG 1575.
4. Data Quality Assessment: Isolation and control of the survey area will be maintained until the survey Data Quality Assessment demonstrates that the regulatory requirements for unrestricted site release have been satisfied.

FSS Survey Area Requirements

.. Pa& 2of 2

DATA QUALITY OBJECTIVES Survey 09Cx 3 1 Excavated Soil from Screenhouse Area

1. STATE THE PROBLEM The Problem:

To demonstrate that the level of residual radioactivity in the excavated soil area originating from Survey Unit 9 does not exceed the release criteria of 25 mrem/year Total Effective Dose Equivalent (TEDE) as specified in the License Termination Plan (LTP). This soil is to be prepared for Final Status Survey (FSS) by grading out to a depth of one (1) meter or less. The excavated soil is to be designated as a Class I survey area. It must be demonstrated that excavated soils in this survey area satisfy the criteria established for unrestricted release prior disposition as fill material for onsite usage.

Stakeholders:

The primary stakeholders interested in the answer to this problem are Consumers Energy Co., and the general public as represented by the Michigan Department of Environmental Quality (MDEQ), and the US Nuclear Regulatory Commission (USNRC).

The Planning Team:

The planning team consists of members of the BRP Environmental Services Survey Group (ESSG). The primary decision maker will be the Final Status Survey Supervisor.

The Final Status Survey Supervisor will obtain input from the site Construction Group and Scheduling Group for issues relating to schedule and costs.

Schedule:

Approximately five (5) working days are projected to implement the Final Status Survey to collect and analyze field data.

Resources:

- - --- The-primary-res-0-rces neede-d determine the answer to the problem are two (2) technicians to perform fieldwork, one (1) technician to prepare the samples and conduct laboratory analyses, and two (2) site characterization team members to prepare and review the design, generate maps, coordinate field activities and evaluate data.

2. IDENTIFY THE DECISION Several decisions need to be defined to address the stated problem.

PrincipalStudy Question (1):

Does the mean concentration of residual radioactivity in the survey unit exceed the release criteria stated above?

F.SS Data uatypjectives P9cxge1 Page 1 of 5

Decision (1):

Determine whether the mean concentration of residual radioactivity in the survey exceeds the release criteria stated in the problem.

Actions (1):

Alternative actions include failure of the survey unit, remediation, or no action required.

PrincipalStudy Question (2):

Do any areas of elevated activity in the survey unit exceed the release criteria?

The Decision (2):

Determine if any areas of elevated activity in the survey unit exceed the release criteria.

Actions (2):

Alternative actions include confirmation and investigation, -performing the elevated measurement comparison (EMC), remediation, or no action required.

PrincipalStudy Question (3):

Is the potential dose from residual radioactivity in the survey unit ALARA as stated?

The Decision (3):

Determine if the potential dose from residual radioactivity in the survey unit is ALARA.

ALARA requirements for soil remediation are defined in Chapter 4 of the LTP.

Actions (3):

Alternative actions include remediation or no action required.

3. IDENTIFY INPUTS TO THE DECISION Information Needed:

Characterization measurements are required to define the radionuclides present and determine the extent and variability of residual radioactivity in the survey area for design and implementation of the FSS. Survey area classification, ALARA analysis, potential radionuclides-of-interest--and-site-specific-DGGL-values-are-alt-o requir--d-i-puts to the decision process. The primary information required for evaluation is the analytical results of FSS measurements.

Source of the Information:

The soil sample data to be used for FSS development are the radionuclide-specific measurements of soil samples collected within the affected local coordinate grids during the characterization process. The soil samples obtained are both judgmentally and statistically selected as a result of multiple surveys across the area to be excavated.

The ALARA analysis for potential soil remediation is provided in LTP, Section 4.4. Site-specific DCGL values and BRP radionuclides of interest are defined in LTP Section 5, Table 5-1 and BRP Procedure RM-76, Final Status Survey Design.

The FSS will be conducted in accordance with applicable regulatory guidance as established in LTP Section 5 for Class 1 areas. Soil samples will be utilized for radionuclide-specific measurements in this evaluation.

! '_ .") '_;,!! i ::: "I f! S -;3Data Quality Objectives 09Cx31 Page 2 of 5

4. BOUNDARIES OF THE STUDY Boundariesof the Survey:

The target population for this survey is the total thickness of prepared soil in the survey area of 825 M2 .

Temporal Boundaries:

Scanning and sampling in this survey unit will only be performed during daylight hours under dry weather conditions. Collection of data will take place when surface conditions are most favorable. Surface soils must be free of significant snow cover and standing water prior to surface scanning. Soils must be in a non-frozen state or fragmented for collection to satisfy BRP procedural sampling requirements. The anticipated start date for the survey is 09-23-04.

Constraints:

Cold weather or rainy conditions may effect the operation of electronic equipment.

Adverse weather conditions that include accumulations of rain or snow may limit area access and delay survey efforts.

5. DEVELOP A DECISION RULE The following decision rules have been developed to define a logical process for choosing among alternative actions for the principal study questions associated with this survey area.

Decision Rule (1):

If all reported concentrations for residual radioactivity are less than the site-specific DCGL's and the unity rule has been satisfied for each sample, then the survey unit meets release criteria. No further action is required.

Decision Rule (2):

Ifthe mean value of activity in the survey unit is greater than the DCGL, then the survey unit fails to meet the release criteria.' Remediate, resurvey, and evaluate the results relative tothedecision-rule ---

Decision Rule (3):

Ifthe mean activity in the survey unit is less than the DCGL and any individual sample measurement exceeds this value conduct the Sign Test and the elevated measurement comparison (EMC) per LTP, Chapter 5 and Procedure RM-76, Final Status Survey Design. Ifthe EMC and the Sign Test have been satisfied then the survey unit meets the release criteria and no further action is required. If the EMC or the Sign Test has not been satisfied then remediate the area(s) of elevated activity, resurvey as appropriate, and evaluate the results relative to the decision rule.

1When multiple radionuclides are present the mean activity value is determined as the average of the weighted sum. The DCGL of the weighted sum is 1.

"tI!.I' iI . , '!~:,:::,i" F$SS.Data Quplity Objectives Pae"9C3o Page 3 of 5

Decision Rule (4):

If the potential dose from residual radioactivity in the survey unit is ALARA, then no further action is necessary. If the potential dose from residual radioactivity in the survey unit is not ALARA, then remediate and resurvey.

6. SPECIFY TOLERABLE LIMITS ON DECISION ERRORS The Null Hypothesis:

It is assumed that residual radioactivity in the survey unit exceeds the release criterion.

Type I Error(a):

The a error is the maximum probability of rejecting the null hypotheses when it is true.

Thea error is defined in the LTP at a value of 0.05 (5%) and cannot be changed to a less restrictive value unless prior approval is granted by the USNRC. The a error value of 0.05 will be used for survey planning and data assessment for this survey area.

Type II Error(,8):

The ,8 error is the probability of accepting the null hypothesis when it is false. A value of 0.05 (5%) will be used for survey planning and data assessment for this survey area.

The Lower Bound of the Gray Region (LBGR):

The LBGR is initially set at 0.5 for this survey unit. The LBGR may be adjusted during survey design to achieve an optimum relative shift between 1.0 and 3.0.

Relative Shift (A/c):

The relative shift will be maintained within the range of 1.0 and 3.0 by adjusting the LBGR as appropriate.

7. OPTIMIZE DESIGN FOR OBTAINING DATA Statistical Test Sign Test:

Radionuclides of potential plant origin also present in soil as background activity resulting from fallout constitute only a small fraction of the DCGL. Therefore, the Sign Test will be used where applicable in the FSS evaluation to determine if the survey area meets the requirements for unrestricted release.

Number of Samples Determined:

The number of samples required for this survey will be determined based on the relative shift as defined by the requirements of the Sign Test (LTP, Chapter 5.) and Procedure RM-76, Final Status Survey Design. The LBGR is initially set at 0.5 and may be adjusted as necessary for optimizing the survey design to achieve a relative shift between 1.0 and 3.0. Sample point locations are to be determined using a random start, systematic grid spacing. For sample point locations where access is impractical or unsafe, alternate locations will be randomly selected to achieve the sample size requirement.

- I !'~:1[I I"FSS DFata.Quality Objectives o9Cx 31 Page 4 of 5

Biased Sampling:

Co-60 is the most limiting radionuclide for identification by surface scanning; biased surface and subsurface core samples will be collected in any location that exceeds the scan investigation level.

Scan Coverage:

Scanning for this survey area will provide 100% coverage.

Number of Samples for Quality Control:

A minimum of 5% of the sample population will be collected for quality evaluation.

These samples may include sample splits, sample recounts, or 3 rd party sample analysis. Quality analyses will be conducted as defined in LTP, Chapter 5 and Procedure RM-79, FinalStatus Survey Quality Control.

Additional Sample Analysis Requirements:

An additional quantity of soil shall be collected for Tritium analysis in the same locations as samples selected for QA/QC. A minimum of 10% of the sample population will be sampled. Tritium analyses will be performed by an independent laboratory. Data results will be provided in the FSS package.

Investigation Levels:

Investigation levels are defined in LTP, Chapter 5 and BRP Procedure RM-76, Final Status Survey Design, by individual survey area classification; however, prior to regulatory approval of the LTP a more conservative approach for investigation will be established for this survey as shown below:

Investigation Levels for Survey 09C131 Classification Scan Measurement Soil Sample Analysis Class 1 > DCGL > DCGLw The investigation levels for soil sample measurements are meant to include any individual radionuclide result greater than the site-specific DCGL or where the combined radionuclide values exceed the unity rule. Co-60 is the most limiting radionuclide for identification by surface scanning; further investigation will be initiated at any location that exceeds the Co-60 Scan DCGL of 1818 CPM above background as detailed in the survey design.

SI I I . - FSS-Pata Quality Objectives 09Cý31 Page 5 of 5

SURVEY DESIGN Survey 09Cx 3 1 Final Status Survey Design Excavated Soil from Screenhouse Area Survey Unit Description Final Status Survey 09C13 1 is composed of excavated soil from the area west and south of the Screenhouse, originating in Survey Unit 09, Grids 139, 158, 177, and 178. It must be demonstrated that the soil in this prepared survey area meets the criterion established for unrestricted release prior to on site disposition as clean fill material.

The soil has been graded out to a maximum thickness of one (1) meter. Soil sample locations will be determined using a random start square grid pattern over the graded area. Each soil sample will be a homogenized composite representative of the total thickness of soil. Surface scanning will be conducted over 100% of the graded area.

Soil Sample Design Scopincq Data Sample measurements obtained to determine suitability for transport and FSS of the soil excavated identified only background or MDA levels of residual radioactivity. As a conservative measure, input values for survey design were estimated based on surveys conducted for characterization of this survey area (LTP Appendix 2-E).

Table 1 Input Data for Survey Design (pCi/g)

Radionuclides Cs-1 37 Co-60 a 0.43 0.43 DCGL 11.93 3.21 Sample Requirements The number of sample data points for this survey is based on the requirements of the Sign Test.

The Unity Rule is used for the presence of multiple radionuclides. The Standard Deviation of the weighted sum is described by the following:

(1DCGLcsl37) 2 Gcoo

+ + DCGLcoso) 2 FSS Design o09C43 1

-Oage: Iof 7

= 1.) t3.21)

G"=0.14 Relative Shift The DCGL for the weighted sum is 1.0. The relative shift is determined using an LBGR value set at 72% of the DCGLw.

Relative Shift = DCGL-LBGR Relative Shift = 1-0.72 0.14 Relative Shift = 2.0 With a and 3 error levels set at 0.05 and the relative shift of 2.0, the Sign Test requires 15 sample data points (Table 5.5 NUREG 1575). As a conservative measure 18 samples will be collected in this survey unit.

Sample Locations Sample locations are selected in a random-start systematic pattern with the southwest corner of the survey unit as origin (X=0, Y=0). Two random numbers between 0 and I are generated using the RAND function within Microsoft 2000 Excel software program (Table 2). The numbers are applied to the survey unit maximum X and Y dimensions to determine the random start location.

Table 2 Random Numbers Random #, X Axis Random #, Y Axis 0.796703 0.253317 Survey Unit 09CX31 Dimensions: X (EMW) = 55.0 meters Y (N/S) = 15.0 meters Random Start Location: X = (0.796703)(55) = 43.8 meters With SW Corner Origin Y = (0.253317)(15) = 3.8 meters FSS Design

, 09Co31

Sample Spacing Samples are located in a square grid pattern with sample spacing determined by the following:

L - where A= area of survey unit and n = number of samples.

L= 825 = 6.8 meters Sample point locations are identified in Attachment 1.

QNQC Sampling A minimum of 5% of the sample population and 5% of the scan survey area are required to be selected for QAIQC verification in accordance with BRP Procedure RM-79, Final Status Survey Quality Control. As a conservative measure, three (3) soil samples and 10% of the scan survey area will be selected for QA/QC evaluation. Data point locations will be selected using the RAND function in the Microsoft 2000 Excel software program:

RANDo*(b-a)+a where a = 1 and b = total number of soil samples to be collected.

Verification scan start point and track direction is determined using the above function. The first sample location selected will determine the start point of the verification scan, and the second sample location will determine the direction in which the scan will track. QA/QC location results are listed in Table 3:

Table 3 Random Numbers Generated for QA/QC

-Rido--m-- Random 0Samle Sample Verification Scan Sample Samples Number Number Split Sample: 14 Start Point: 12 Sample Recount: 4 Scan Towards: 2 Sample Recount: 3 Minimum Scan Area Requirement: 82.5 m 2 Surface Scanning The coverage requirement for surface scanning in this Class 1 area is 100%. The Scan MDC has been established at fractional values of the DCGLw for typical background activity levels at Big Rock Point. Scan MDC values for varying backgrounds are provided in Attachment 2. The investigation level for identification of potential areas of elevated activity in this survey area will be the Scan DCGL as defined by the following:

FSS Design

! -I I I - * -! . :;-!: * *pa*09C3o1

Scan DCGL = Detector Rating CPM

  • Exposure Model uR/hr
  • DCGLw uR/hr pCi/g Scan DCGL for Co-60 = 1818 cpm Scan DCGL for Cs-1 37 = 3518 cpm Where:1 Detector Rating = 1200 CPM Cs -137 and 565 CPM Co -60 uR/hr uR/hr Exposure Model - 1.229 uR/hr Cs- 1 3 7 and 5.029 uR/hr Co-60 5pCi/g 5 pCi/g DCGLW = 11.93 pCi/g Cs-137 and 3.21 pCi/g Co-60 The DCGLw for Co-60 is the most limiting value for scanning measurements performed to identify areas of potentially elevated activity. Scanning conducted for this Final Status Survey will assume all residual radioactivity to originate from Co-60 and the instrument response at the Co-60 DCGLw (1818 cpm) will be used as the scanning investigation level for Survey 09Cx3 1.

These values established in EA-BRP-SC-0201, Nal Scanning Sensitivity for Open Land Survey.

FSS Design Iiii* li! ,'!

  • ! *.'* *:, !i  :* l' i=09cx 3I e*,of7

Attachment I Soil Sample Locations N Final Status Survey 09Cxsl Excavated Soil from Screenhouse Area 09-23-2004 Y. 55Omewws 0 5 10 20 1 1Meters Lmc Excavinted Sol 0 Soil SairCfe Locations Note; Coordinate location relative to SVV Corner of survey uni where X0 m. and Y,0 m.

Random Stafl Locelhonw X- 43.8 mefers, Y- 3.8 molars. Sample spacing is 6.8 metlrs.

FSS Design 09CX31 Page 5 of 7

Attachment 2 Scan MDC In Varying Backgrounds CPA MD.' M.ER-,W -

Background d' Is MD C R,, Cs-137 Co-60 Cs-1 37 Co-60 2000 2.48 4 28.64 607.47 0.51 1.08 2.06 1.07

  • .ý::.'.5006 *'*:-, ! 2.48,' '" *3 :0 : "47:""*;

3000 2.48 4 35.07 744.00 0.62 1.32 2.52 1.31 3500 2.48 4 37.88 803.61 0.67 1.42 2.72 1.41 4000 2.48 4 40.50 859.10 0.72 1.52 2.91 1.51 4500 2.48 4 42.95 911.21 0.76 1.61 3.09 1.60 5500 2.48 4 47.49 1,007.38 0.84 1.78 3.42 1.77 6000 2.48 4 49.60 1,052.17 0.88 1.86 3.57 1.85 6500 2.48 4 51.63 1,095.14 0.91 1.94 3.71 1.93 7000 2.48 4 53.57 1,136.48 0.95 2.01 3.85 2.00 8000 2.48 4 57.27 1,214.95 1.01 2.15 4.12 2.14 8500 2.48 4 59.04 1,252.34 1.04 2.22 4.25 2.20 9000 2.48 4 60.75 1,288.65 1.07 2.28 4.37 2.27 9500 2.48 4 62.41 1,323.96 1.10 2.34 4.49 2.33 10500 2.48 4 65.61 1,391.90 1.16 2.46 4.72 2.45 11000 2.48 4 67.16 1,424.65 1.19 2.52 4.83 2.51 11500 2.48 4 68.67 1,456.67 1.21 2.58 4.94 2.56 12000 2.48 4 70.14 1,488.00 1.24 2.63 5.04 2.62

~1200 2.4.8 ~ 4ý ýY75 'i586 ~.17'>7~ V55 5____

13000 2.48 4 73.01 1,548.76 1.29 2.74 5.25 2.73 13500 2.48 4 74.40 1,578.26 1.32 2.79 5.35 2.78 14000 2.48 4 75.77 1,607.22 1.34 2.84 5.45 2.83 14500 2.48 4 77.11 1,635.67 1.36 2.89 5.55 2.88

~~160001 2.48 ~ 7 42. 4,6:3r 19 24 -564 223

-4 ~ I i~J. ~ 71.......74 "b~b&Is  !(iR/hr)',' ri Cld'a

'xosre

___________& 6 +66-0 _---_ I.3 _ _ _ _ _ __ _ _ _ _ _ _ _ _ _

FSS Design 09Cal Page 6 of 7

Attachment 3 Area Factors for Open Land Survey Evaluation Cotaine Calculated Area Factors at Time of Peak Dose Area (Mt) H-3 Mn-54 Fe-55 Co-60 Sr-90 Cs-1 37 Eu-152 Eu- Eu-1 55 154 8094 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 4047 1.00 1.01 1.00 1.01 1.00 1.02 1.02 1.01 1.02 2024 1.00 1.03 1.00 1.03 1.00 1.03 1.03 1.03 1.03 1012 1.35 1.04 1.00 1.04 1.00 1.04 1.05 1.04 1.04 506 2.91 1.09 1.98 1.08 1.98 1.13 1.07 1.07 1.06 253 6.05 1.14 3.95 1.13 3.94 1.20 1.11 1.11 1.09 126 12.4 1.20 7.93 1.20 7.87 1.29 1.17 1.16 1.14 63 24.9 1.30 15.8 1.30 15.6 1.41 1.27 1.26 1.23 32 49.2 1.49 31.2 1.49 30.5 1.62 1.44 1.45 1.39 16 98.9 1.78 62.0 1.78 59.9 1.93 1.72 1.73 1.63 8 198 2.38 123 2.38 117 2.58 2.30 2.31 2.14 4 397 3.61 243 3.62 230 3.91 3.49 3.52 3.19 2 794 5.68 473 5.75 452 6.14 5.48 5.55 4.90 1 1590 9.57 905 9.73 887 10.3 9.24 9.39 7.88 FSS Design 09clal Page 7 of 7

A RM-76 Revision 1 FINAL STATUS SURVEY DESIGN Page 19 of 19 RM-76-5 FINAL STATUS SURVEY APPROVAL AND AUTHORIZATION FOR IMPLEMENTATION Survey Code FSS 09Cx31_

Survey Area

Description:

Approximately 825 m 2 of excavated soil has been prepared for Special Case Final Status Survey in the Soil Verification Area and graded to a depth of one (1) meter. This soil originated from the excavation immediately west and south of the Screenhouse to remove miscellaneous piping components.

The survey area is authorized for FinalStatusSurveyImplementation.

0D-23-oat Designed by Date Technical Review by Date RM-?'6.doae c t'-i1i t:'-:,i

It RM-77 Revision 1 FINAL STATUS SURVEY IMPLEMENTATION Page 9 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 1 of 3 Step Initial Date (1) 1.0 PREPARATION FOR SURVEY Or.,g/

Survey #

1.1 Survey Area Status:

__ a. Final Status Survey Design has been approved for implementation (see RM-76-5, Final Status Survey Approval and Authorization for Supplementation).

1. Survey area walkdown complete
2. Survey area determined ready for FSS
3. Decommissioning activities that may impact the environmental status of the survey area have been completed.
4. Survey area environment is controlled by barriers and postings or other approved method to restrict ESSG access.

- b. Survey area has been turned over to the Environmental ServicesSur.veyGroup-(ESSG)_in-acceptable-condition- --

for FSS. Na,-ý4 1.2 Field Preparation:

a. Survey unit boundaries delineated (Step 6.1.1)
b. Statistical soil samples predetermined in the survey design are located and marked within the survey unit.

(Step 6.1.2) 7 c. Soil sample locations verified (Step 6.1.2.c)

d. Instruments and equipment have been collected and calibrated for data measurement and collection (Step 6.1.3)

/ e. Field documentation is prepared (Step 6.1.4) EoQr3--t r! iF RM-77.doc

RM-77 Revision 1 FINAL STATUS SURVEY IMPLEMENTATION Page 10 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 2 of 3 Initial Date 2.0 DATA COLLECTION 2.1 Soil Survey:

-' All soil samples collected and controlled (Step 6.2.1).

ESSG 2.2 Surface Scan:

__ Surface Scan complete. Action response requirements have been conducted on any identified areas exceeding the investigation level (Step 6.3).

ESSG 2.3 Judgmental Soil Samples:

a. Judgmental soil samples have been collected and controlled (Step 6.2.3).
b. Deep core profiles performed in areas identified to contain elevated residual activity (Step 6.2.3).

ESSG 370--- SAM P LE PRE PARATION-AN D-B-O-RATORYANALYS]-S 3.1 Sample Preparation (Step 6.4.1):

V a. Soil samples are homogenous V b. Soil samples are visibly dry prior to packing C. Non-soil materials have been removed from sample

-LI d. Soil samples have been transferred to one-liter Marinelli containers and are labeled and sealed. 9.'-

Z6 -

ESSG I.-'

RM-77.doc

RM-77 Revision 1 FINAL STATUS SURVEY IMPLEMENTATION Page 11 of 12 RM-77-1 SURVEY IMPLEMENTATION CHECKLIST Page 3 of 3 Initial Date 3.2 Laboratory Analysis:

7 Isotopic analyses are complete. The spectroscopy report requires a signature of completion by the laboratory analyst and a signature of evaluation documenting that a second level review has been performed (Step 6.4.2). ESSG 3.3 Sample Control and Documentation:

Chain of custody documentation exhibits control of soil samples (Step 6.4.3). L2K qi36 ESSG i ato4 Reviewed by Date RM-77.doc

RM-59 Revision 7 SAMPLING AND ANALYSIS OF OPEN LAND Page 7 of 9 AREAS FOR SITE CHARACTERIZATION SURVEYS ATTACHMENT RM-59-1 SAMPLING AND ANALYSIS REPORT Date: 09-23-2004 Time: 14:24 Location:Powerline/SVA Tech: mjk/jlr SURVEY IDENTIFICATION I DESCRIPTION Survey 09C. 31, Final Status Survey of excavated soil originating west and south of the Screenhouse.

SURVEY TYPE Survey Type: Characterization 'x Scan (Motive)

_,___*_ Remediation, X- Final Scan (Static)

SURVEY DESIGN Sample Collection: Judqmental Random x Systematic Scan Coverage: 100  %

ANALYSI Inst./Seriai No. Detector 6 " DAILY CHECK: -x SAT ____UNSAT INIT" Scan 186201/JB365 Investiqation of Unidentified"Peaks:

.. __" N/A x SAT __ UNSAT INIT:_

Minimum Detectable Activity (Section 5.3.3) x SAT UNSAT INIT:

.. OMMENTS Sample Design: Random start with a square grid systematic pattern. Eighteen soil samples were collected all of which showed concentrations of radioactivity at a fraction of the DCGLw.

100% mobile scan did not identify areas of activity above background.

Technician Second LevelSicReview-nature:

  • F*,*' Date: /0- 1? - oq Signature: Date: 11-o1-oLI RM-59A661 ý' C

Activity Summary Final Status Survey 09C131 Excavated Soil from Screenhouse Area 09-23-2004

,Sample01 X. I No.. - 1oora. ,  %,oora.- ?IUVIjy PULVuIty, M

20 9838nd 0.061 rd 3' ~' 16.6 38, 06,n 4! 24 8 J' 0 09 __ nd

,.' 5, 30.2,'ý 38 ý003* _ _ . n

.. I Iý . ýi R ,LV*

~,.

'17A'74n

)W-¸ * *,* . . I. z 4 4 II- - I-

    • ~i~

'7 ,43.8 '.[ _______38~

4 ' 50:6 38

____ 50.6 ~ rd n~1

'.'10,  :,!-: ' 43.8.: .'. 1;>

0.6- *-- ri"'*

d !.:-.:

I 1 ' 370 J 0;- rid-,

S . 234 .106 0:03

.14 16.6 06 rid 16 3.,0: 10.6 nd 17V' ' 22.,0 12.8 ri.d:

ý'1!:Oi J'34.9 .5. rid

  • Coordinate location relative to SW Comer of survey unit where X=O m. and Y=O m.

Not. nd indicates activity not detected above MDA values.

Soil Sample Locations N 4

Final Status Survey 09Cx 31 Excavated Soil from Screenhouse Area 09-23-2004 Y= 15 meters 17 0

16 Is 14 13 12 11i 10 18 0 Is 1 12 13 14 56 7 Is X=55.0 meter F(ThQ-yQ 0 5 10 20 1 I I , I = I I I Meters Legend Excavated Soil S Soil Sample Locations Note: Coordinate location relative to SW Corner of survey unit where X=O m. and Y=O m.

Random Start Location: X= 43.8 meters, Y= 3.8 meters. Sample spacing is 6.8 meters.

Mobile Scan Survey Final Status Survey 09Cx31 N

Excavated Soil from Screenhouse Area 09-24-2004 6000 Y= 15 meters 4500 4500 4500 4500 4500 .17 4500 4600 4500 4700 4500 40 110 4600 16 15 14 13 4500 12 11 9 4000 4600 4200 0 5000 W"

4500 4700 4500 4500 4500 4300 4500 4800 S500 4500 4700 4600 4300 4400 30 47,0 4500 4600 400 4700 *0 5000 4500 45 304700400 0 3 4800 4704 5 460 6 7 8 4600 4300 4200 4500 4500 5000 4500 5000 4700 5000 4800 4300 4500 X=55.0 meters 5000 0 5 10 20 I i I I 1 I Ih atorn Legend Excavated Soil 0 Soil Sample Locations Primary Scan : /o,  %

Technician Signature: Date: _-_--_

Time: //.'-?o QC Verification Scan: 1O~t  % (~CIAqM Technician Signature: (*a- Z 1--_a Date: q- 01Y L-/

71- Time: /,, -

Numbers in Red indicate Average General Area Activity (cpm)

Identified During Mobile Scan Numbers in Blue indicate Average General Area Activity (cpm)

Identified During QC Verification Scan

RM-72 F " , .- Revision 0 SAMPLE CHAIN-OF-CUSTODY Page 4 of 5 RM-72-1 CHAIN-OF-CUSTODY RECORD Sample Number Sampling Location Date Time Final Disposition of Sample

____ ___ )i 3.%) _i_____________'

  • 3j'*"'*' (A\.,N.Q)(.s.3,) 123/0 143$ 93_V

-v (* -"C)t-3-) C *,, __ _ ___ ___,__ ___

(-7

____.3_-(-3 _

____q ) iAoL li',_fo2-99tAA jS __ __.0 __ __ __ _ vo(23o

  • ,(3 A *.* CI.*Z:3 /P4, 1q'35 (Szýt,- I qq.P LL.CC3')CK LYI)231o 1 521 C(01_______

1Z __ _ __ _ __ _ Z1z3l 1,52$ _ _ _ _ _

Q.L LCR3XzŽo c.Zp6'4Z- ~ t Nz~')8., (413lo 11001 9CtoC

(

Pq q)(h 3) (2 012L64__I____.;______

ILQ W\-\l q~4~z\

is__ _______ ___9 H I- UI- I (Samples may be analyzed and stored, shipped for offsite evaluation or analyzed and disposed of.)

1. Relinquished bb Date Time Received in good condition by:

3__J L- 'A)O

2. 01inished y)y: Date Time Received in good condition by:

_____i_______y 9Date Tme Re d g

3. Relinquished by: Date Time Received in good condition by:
4. Relinquished by: Date Time Received in good condition by:

RM-72.doc

RM-78 Revision 1 FINAL STATUS SURVEY ASSESSMENT RM-78-3 DATA ASSESSMENT REPORT Page 1 of 8 FINAL STATUS SURVEY: 09CQ3 1 1.0 DATA VERIFICATION 1.1 Data Acceptance x Review the Implementation Checklist (RM-77-1) to verify that survey isolation and control measures were executed prior to FSS and are being maintained.

x Review RM-77, Final Status Survey Implementation, to verify that methods, techniques, and survey activities required for FSS have been applied in accordance with the appropriate procedures.

1.2 Field QC Records:

n/a Review all assessments, Condition Reports and audits to ensure that identified issues have been resolved.

Comments:

x Verify scan instrumentation was in calibration and the QC source checks were performed prior to and after surveys.

x -Vetify-daily-QCsource ch-ecks-f6)-Cb- r-&b-ea?*amma spectroscopy detector properly logged prior to soil sample analysis.

1.3 Review Verification:

x Verify that the Data Quality Objectives are complete.

x Verify that the survey design has been technically reviewed.

RMV-7'8.doc II

RM-78 Revision 1 FINAL STATUS SURVEY ASSESSMENT RM-78-3 DATA ASSESSMENT REPORT Page 2 of 8 x Verify that gamma spectroscopy results have received a technical review.

x Verify the Sample and Analysis Report (RM-59-1) is completed and reviewed.

Data Verification Completed: No Comments Assesesor Date RM -78.doc1'.-j () 1-1 !'-! ',' ':':.::: "I

RM-78 Revision 1 FINAL STATUS SURVEY ASSESSMENT RM-78-3 DATA ASSESSMENT REPORT Page 3 of 8 2.0 DATA VALIDATION 2.1 Documentation Review:

Perform documentation review for quality control purposes and validate the data collected is complete and appropriate for use as defined by the survey design. Documentation includes:

x Field measurement records x Chain-of-custody x Quality Control (QC) measurement records x Current qualification of survey personnel n/a Corrective Action Reports x Data inputs (laboratory spectroscopy) x Sample preparation techniques 2.2 Detection Limit Review:

x Scan MDCs are below established site DCGLs.

x Forced-count values are assigned as necessary when activity is not detected in a sample.

x Minimum Detectable Concentration (MDC) values of gamma spectroscopy are below established DCGLs.

2.3 Quality Control (QC) Data Review:

x Quality Control (QC) data results have received required reviews and are complete and consistent.

x Results of judgmental samples have been reviewed and evaluated.

x Review to ensure that the analytical results of judgmental samples do not impact the evaluation for unrestricted release of the survey area.

RI\/-78,doc '1lj I

RM-78 Revision 1 FINAL STATUS SURVEY ASSESSMENT RM-78-3 DATA ASSESSMENT REPORT Page 4 of 8 2.4 Qualification of Data:

Statistical radionuclide-specific measurements for completeness. Evaluate the survey for determination of data usability and confirm that sufficient qualified data are present for the decision process.

a. Total number of statistical samples planned for the survey: 18
b. Total number of statistical samples determined as valid: 18 b x120
c. Calculate % Completeness: 120%

a x Qualified data are >100% completeness and are sufficient to support the Sign Test requirement for determination of unrestricted release.

Data Validation Completed: Yes No Comments: Refer to RM-78-3 Attachment 1 for verification of analysis results. 2.4.a. 2.4.b.

and 2.4.c.

Refer to the Additional Sampling Requirements section for Tritium in Soil data results.

/1-o- Oq Assessor Date RIMf-7'8.doig' F!

RM-78 Revision 1 FINAL STATUS SURVEY ASSESSMENT RM-78-3 DATA ASSESSMENT REPORT Page 5 of 8 3.0 DATA QUALITY ASSESSMENT 3.1 Review the DQOs and Survey Design:

x Confirm that all inputs to the decision have been reviewed and are complete.

x Verify that boundaries or constraints identified in the survey area have not affected the quality of the data.

x Review the Statement of Hypothesis and confirm that it remains relevant.

x Confirm that Type I and Type II error limits are consistent with DQOs.

x Confirm that the survey design is consistent with DQOs and that the appropriate number of data points were obtained.

3.2 Preliminary Review:

3.2.1 Preliminary Evaluation:

x Quality Assessment (QA) reports consistent with procedure RM-79, Final Status Survey Quality Control.

x Survey is of sufficient intensity to satisfy classification requirement.

x Potential trends of radioactivity levels in the survey area do not impact a decision for unrestricted release.

Comments:

RM-78.doc r .

RM-78 Revision 1 FINAL STATUS SURVEY ASSESSMENT RM-78-3 DATA ASSESSMENT REPORT Page 6 of 8 3.2.2 Calculate Basic Statistical Quantities:*

a. Number of qualified data points 18
b. Calculation of the Mean 0.003 (SOR)

C. Calculation of the Median 0.003 (SOR)

d. Calculation Standard Deviation 0.006 (SOR)
  • Note:Statistical Quantities are calculatedon RM-78-3, Attachment 1.

n/a Attach graphic representation of the data if any radionuclide-specific measurements exceed 50% of the DCGL.

x Sample QAIQC measurements consistent with FSS data.

3.3 Statistical Evaluation:

NOTE: If all measurement data are less than the DCGLw, statistical testing in not required and the survey unit meets the regulatory requirement for unrestricted release.

x All survey measurements are below the DCGLw.

3.3.1 Verify Assumptions of the Statistical Test n/a Review the posting plot to verify that the if data exhibits spatial independence. Spatial trends must be investigated and resolved prior to further assessment.

n/a Review to verify dispersion symmetry. The appearance of skewed data must be investigated for cause and documented prior to further assessment.

RM-7'8.doctiii "

RM-78 Revision 1 FINAL STATUS SURVEY ASSESSMENT RM-78-3 DATA ASSESSMENT REPORT Page 7 of 8 n/a Review the dataset standard deviation and range for data variance.

Questionable data must be investigated for cause and documented prior to further assessment.

n/a Compare the prospective power curve with the retrospective power curve. Verify that the data exhibits adequate power and confirm that the sample size is sufficient to satisfy the DQOs.

3.4 Draw Conclusions from the Data:

3.4.1 Investigation Levels and Response Actions x Determine if data results have exceeded any investigation level.

Document findings.

3.4.2 Evaluation for Unrestricted Release Select applicable conclusion:

x Survey area acceptance criteria met and survey area satisfies the requirements for unrestricted release:

x All concentrations are less than the DCGLw. The Null Hypothesis is rejected.

n/a The mean concentration of the survey area is below the DCGLw but individual measurements in the survey unit exceed the DCGLw. The Sign Test and EMC evaluation are successful and the Null Hypothesis is rejected.

-"I::'

RM-78.do'dj U f.!; .!

RM-78 Revision 1 FINAL STATUS SURVEY ASSESSMENT RM-78-3 DATA ASSESSMENT REPORT Page 8 of 8 n/a Survey area acceptance criteria not met and survey area fails to satisfy the requirements for unrestricted release:

n/a The mean concentration in the survey area exceeds the DCGLw. and the null hypothesis is confirmed.

n/a The mean concentration of the survey area is below the DCGLw but individual measurements in the Unit exceed the DCGLw..

The Sign Test and EMC evaluation are unsuccessful and the null hypothesis is confirmed.

Data Quality Assessment Completed: Y No Comments As'sessor Date Reviews:

Date Technical eview Date ES Superintendent Date RFP&ES Manager RM-78.06)

RM 78-3, Attachment 1:

Analysis of Data Results Final Status Survey 09C131 Excavated Soil from Screenhouse Area 09-23-2004 Sample Cs-137 Co-60 Weighted *Weighted Sum Number (pCilg) (pCllg) Sum <DCGLw? DCGL-W. Sum Sign 1 0.0219 0.0061 0.004 yes 0.996 +1 2 0.0252 0.0054 0.004 yes 0.996 +1 3 0.0525 -0.0011 0.004 yes 0.996 +1 4 0.0870 0.0500 0.023 yes 0.977 +1 5 0.0271 -0.0089 -0.001 yes 0.999 +1 6 0.0266 -0.0003 0.002 yes 0.998 +1 7 0.0332 0.0082 0.005 yes 0.995 +1 8 0.0562 -0.0060 0.003 yes 0.997 +1 9 -0.0004 -0.0103 -0.003 yes 0.997 +1 10 0.0173 0.0158 0.006 yes 0.994 +1 11 0.0229 -0.0221 -0.005 yes 0.995 +1 12 0.0168 0.0154 0.006 yes 0.994 +1 13 0.0285 -0.0045 0.001 yes 0.999 +1 14 0.0125 -0.0106 -0.002 yes 0.998 +1 15 0.0257 -0.0004 0.002 yes 0.998 +1 16 -0.0086 -0.0100 -0.004 yes 0.996 +1 17 0.0050 -0.0085 -0.002 yes 0.998 +1 18 0.0521 0.0065 0.006 yes 0.994 +1 St. Deviation (SOR): 0.006 Mean (SOR): 0.003 Median (SOR): 0.003 Number of Positive Differences (S+): n/a Critical Value, k, Table 1.3 of Marssim: n/a S+ >thank?: n/a Survey Unit Pass or Fail: *Pass Note: Forced-Countvalues are used for samples with activity levels below the MDA.

  • If all measurement data are less than the DCGL w, then the Sign Test is not required.

9 ,,

RM-79 Revision 1 FINAL STATUS SURVEY QUALITY CONTROL Page 13 of 13 RM-79-1 FSS QUALITY CONTROL EVALUATION RESULTS FSS Package # 09C, 31 QC Package # 09C*n1 QC Measurement Type Acceptance Criteria Reference Met*?

x 1. Replicate Scan 2 No Step 5.1.3

2. Sample Recounts Step 5.1.4.1 x a. In-house (Q / No
b. Third party Yes / No
3. Split Samples Step 5.1.4.2 x c. In-house CýZ/No
d. Third party Yes / No
  • NOTE: If Acceptance Criteria is not met, completion of Attachment RM-79-2, FSS Quality Control Investigation Results, is required.

Comments:

1. Replicate Verification Scan Information is documented in the Implementation Section of this report, FSS Mobile Scan Map.

2a. In-House Sample Recount Worksheet is attached.

3c. Split Sample Verification Worksheet is attached.

Reviews:

rva'I6atpr Date ate I-Technical Review Date RM-79.docrI t- r *1 i; {" i

QA Verification Split Sample Analysis Table I Date: 912312004 QA: 09C, 3 1 Excavated Soil From Screenhouse Area Type: Split Sample Lab: In House A* B C D E F G BRP - Results in Result BRPI BRP BRP Acceptance Split Split Results Comparison Agreement Sample Radionuclide Belt Results  % Error RP Ratio Results Ratio are (pCilg) (Sigma) (Table 1) Below MDA (pCVg) F/A Compare MDA G with D) 14 Co-60 0.0603 n/a n/a n/a 0.0642 1.06 YES 14 Cs-137 0.0516 n/a n/a n/a < 0.0657 1.27 YES

_ _ _ __ _ _ 4- _ _ __ _ _ _ _ _ __I Resolution C AJDA

< Indicates results less than the MDA.

QA Verification Sample Recount Analysis Table 1 Date: 9/23/2004 QA: FSS 09C13 1 Excavated Soil From Screenhouse A Type: Sample Recount Lab: In- House A B C D E F G BRP BRP' BRP Acceptance Recount Comparison Results in Result I BPRecountAgemn Sample Radionuclide Results  % Error sResults ReuRatio RatioRe Below (pCi/gI) (Sigma) Resolution (Table 1) Result (pC/g) FIA Compare MDA I ( Below MDA G with D) 3 Co-60 0.0689 n/a n/a n/a 0.0666 0.97 YES 3 Cs-137 0.0525 38.17 2.62 n/a 0.0718 1.37 YES 4 Co-60 < 0.0789 n/a n/a n/a _ 0.0706 0.91 YES 4 Cs-137 0.0870 16.44 6.08 0.5-2.0 < 0.0671 0.77 YES t

Resolution Ct = A)s ( B 10 0) 1

< Indicates results less than the MDA.

Tritium in Soil Analysis of Data Results Final Status Survey 09Cx31 Screenhouse Excavation Area 09-23-2004 Sample Tritium in Soil Number (pCilg) 3 0.00 4 0.00 14 0.00 Mean: 0.00 Median: 0.00 St. Dev: 0.00 Note: DCGL for Tritium is 327 pCi/g.

Sample data results are a fraction of the DCGL.

GENERAL ENGINEERING LABORATORIES, LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com 10 CFR Part 50/61 Certificate of Analysis GEL Sample ID: 123759002 Client: Big Rock Nuclear Facility Client Sample ID: #3 FSS 09CX31 Collect Date: September 23, 2004 Matrix: Soil Receive Date: October 18, 2004 Amount of Sample Received: Report Date: November 01, 2004 Aliquot Run Date Activity.2 Uncertainty MDA I RL Units Analyte Qualifier H-3 10/27104 - 1. 16E+0 I 2.24E+02 3.92E+02 5.00E+02 pCi/L U Moisture 10/29/04 4.01E+00 percent Note(s):1. Calculated MDAs are a-posteriori values.

2. Activity concentration net +1-2 sigma overall on reference date.
3. Results are statistically positive at the 99.9% confidence level (activity is greater than three times the uncertanity)

U Indicates the target analyte was analyzed for but not detected above the detection limit.

Page 3 of 14 1.-I

GENERAL ENGINEERING LABORATORIES, LLC 4 .

2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.corn 10 CFR Part 50/61 Certificate of Analysis GEL Sample ID: 123759003 Client: Big Rock Nuclear Facility' Client Sample ID: #4 FSS 09CX31 Collect Date: September 23, 2004 Matrix: Soil Receive Date: October 18, 2004 Amount of Sample Received: Report Date: November 01, 2004 Activity 2 Uncertainty MDA RL Units Analyte Alfquot Run Date Qualifier H-3 10/27/04 6.92E÷0l 2.21E+02 3.81E+02 5.00E+02 pCilL U Moisture 10/29/04 4.5 2E+00 percent Note(s):1. Calculated MDAs are a-posteriori values.

2. Activity concentration net +/- 2 sigma overall on reference date.
3. Results are statistically positive at the 99.9% confidence level (activity is greater than three times the uncertanity)

U Indicates the target analyte was analyzed for but not detected above the detection limit.

Page 4 of [4 4!

GENERAL ENGINEERING LABORATORIES, LLC C. ',

. 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com 10 CFR Part 50/61 Certificate of Analysis (GELSample ID: 123759009 Client: Big Rock Nuclear Facility Client Sample ID: #14 FSS 09CX31 Collect Date: September 23, 2004 Matrix: Soil Receive Date: October 18, 2004 Amount of Sample Received: Report Date: November 01, 2004 Analyte Aliquot Run Date Activity 2 Uncertainty MDA I RL Units Qualifier H-3 10/27/04 5.70E+01I 2.17E+02 3.75E+02 5.00E+02 pCiIL U

Moisture 10/29/04 3.84E+00 percent Note(s):1. Calculated MDAs are a-posteriori values.

2. Activity concentration net +/- 2 sigma overall on reference date.
3. Results are statistically positive at the 99.9% confidence level (activity is greater than three times the uncertanity)

U Indicates the target analyte was analyzed for but not detected above the detection limit.

Page 10 of 14

T375116A Filename: H3VAC.WAT TRITIUM WATER/SOIL Sample ID Sample Dup Run Date File type

  • Excel Using the Vacuum Distillation Rig 1200725333 123759001 10/27/2004 9:34 a Version #: 13 1200725334 123759001 10/27/2004 10:05 Batch : 375116 1200725335 10/27/2004 10:37 Analyst: JLB1 Prccedure Code: LSC-VH3S Date: 10/22/2004 Parmname: Tritium BKG Count time: 30 min Batcl Counted on : LSCBLUE Sample Count Raw Net Sample Counting Bkg Time Sample ID Volume Position# Time CPM CPM Efficiency CPM Counted Ip mL min 123759001 10.0000 10-2 30 28.47 21.30 26.75 7.17 10/27/2004 2:39 M cMi13 3 1123759002 10.0000 10-3 30 7.10 -0.07 27.20 7.17 10/27/2004 3:11
  1. if o091tl1 123759003 10.0000 10-4 30 7.60 0.43 28.01 7.17 10/27/2004 3:43 123759004 10.0000 10-5 30 14.20 7.03 28.29 7.17 10/27/2004 4:15 123759005 10,0000 10-6 30 14.77 7.60 24.53 7.17 10/27/2004 4:47 123759006 10.0000 10-7 30 10.77 3.60 30.06 7.17 10/27/2004 5:18 123759007 10.0000 10-8 30 13.70 6.53 27.91 7.17 10/27/2004 5:50 123759008 10.0000 10-9 30 27.50 20.33 29.35 7.17 10/27/2004 6:22
  1. 1&4 At,,123759009 10.0000 .10-10 30 7.53 0.36 28.45 7.17 10/27/2004 6:54 123759010 10.0000 10-11i 30 7.93 0.76 26.55 7.17 10/27/2004 7:26 123759011 10.0000 10-12 30 25.33 18.16 23.13 7.17 10/27/2004 7:58 123759012 10.0000 53-1 30 25.30 18.13 21.91 7.17 10/27/2004 8:30 1200725332 10.0000 53-2 30 7.33 0.16 29.01 7.17 10/27/2004 9:02 1200725333 10.0000 53-3 30 31.23 24.06 27.54 7.17 10/27/2004 9:34 1200725334 10.0000 53-4 30 109.50 102.33 22.66 7.17 10/27/2004 10:05

.1200725335 10.0000 53-5 30 43.40 36.23 23.00 7.17 10/27/2004 10:37 Page 1

T375116A Sample Typ D Standard ID NC NC units Recovery/RPD DUP 9%

MS 0134-H 1.17 pCi/G 105%

LCS 0134-H -7.98 pCi/G 89%

-kr - Tritium Tritium Tritium MDA Error SkIW MDA RESULT ERROR Met? Met?

lc:) pCi/G pCi/G pCi/G 0.0292 0.26 0.0263 Yes Yes

  • 3 ocir-y--. 0.0199 0.00 0.0113 Yes Yes Lf C) 31 0.0188 1 0.00 0.0109 Yes. Yes 0.0229 0.07 0.0160 Yes Yes 0.0255 0.08 0.0180 Yes Yes 0.0269 0.04 0.0172 Yes Yes 0.0230 0.06 0.0159 Yes Yes 0.0222 0.19 0.0198 Yes Yes N'l k .0.0138 0.00 0.0080 Yes Yes 0.0195 0.01 0.0115 Yes Yes 0.0323 0.25 0.0279 Yes Yes 0.0319 0.24 0.0274 Yes Yes 0.3678 0.02 0.2116 Yes Yes 0.0283 0.29 0.0265 Yes Yes 0.0344 1.49 0.0562 Yes Yes 0.4639 7.10 0.4984 Yes Yes Page 2
Retrieved from "https://kanterella.com/w/index.php?title=ML063130314&oldid=2581484"