ML052090273

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Final Status Survey Report for Saxton Nuclear Experimental Corporation Saxton Steam Generating Station Structural Surfaces - Basement SS14, SS15, SS16, SS17, Appendix a, E900-03-027 Calculation Sheet
ML052090273
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 10/23/2003
From: Brosey B, Donnachie P, Paynter A
GPU Nuclear Corp
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
E910-05-037 E900-03-027, Rev 0
Download: ML052090273 (61)


Text

Appendix A SSGS Footprint Survey Design

ORIGINAL BEVY SNEC CALCULATION COVER SHEET CALCULATION DESCRIPTION Calculation Number Revision Number Effective Dyte Page Number E900-03-027 0

3 I

of A2 Subject Balance of SSGS Footprint - Survey Plan Question I - Is this calculation defined as 'in QA Scope'? Refer to definition 3.5. Yes 0 No ID Question 2-Is this calculation defined as a 'Design Calculationr? Refer to definitions 3.2 and 3.3.

Yes 0 No 0 Question 3 - Does the calculation have the potential to affect an SSC as described in the USAR?

Yes E No 0 NOTES: If a 'Yes' answer is obtained for Question 1, the calculation must meet the requirements of the SNEC Facility Decommissioning Quality Assurance Plan. If a 'Yes' answer is obtained for Question 2, the Calculation Originators Immediate supervisor should not review the calculation as the Technical Reviewer. If a 'YES' answer Is obtained for Question 3, SNEC Management approval is required to implement the calculation. Calculations that do not have the potential to affect SSC's may be Implemented by the TR.

DESCRIPTION OF REVISION APPROVAL SIGNATURES Calculation Originator B. Brosey/

?

Date 10 I5' 103 Technical Reviewer P. Donnachie Date 1

Additional Review A. Paynter/

Date 1

3 Additional Review Date SNEC Management Approval Date

F ig SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-027 0

Page 2 of Lv Subject Balance of SSGS Footprint - Survey Plan 1.0 PURPOSE 1.1 The purpose of this calculation is to develop a survey design for the remaining sections of the SSGS 790' El floor that were not scanned by SRA, and to locate static measurement points over the entire 790' El floor area. This area is a Class 1 survey area. All of these survey units are shown on Attachment 1-1 to 1-5 (1-2 & 1-3 depict the missed areas and 14 & 1-5 are a listing of these areas).

1.2 The total area for these survey units is -320 square meters. The exact amount of area represented by these missed locations is not estimated. The Trench and Sump areas are subtracted from the total area. There are five (5) survey units:

1.2.1 Section 1 -Attachment 2-1 (SS14-1) - 65 m2 1.2.2 Section 2 -Attachment 2-2 (SS14-2) - 58.2 m2 1.2.3 Section 3 - Attachment 2-3 (SS14-3) - 83.1 m2 1.2.4 Section 4 - Attachment 24 (SS14-4) - 61 m2 1.2.5 Section 5 - Attachment 2-5 (SS14-5) - 52.7 m2 2.0

SUMMARY

OF RESULTS The following information should be used to develop a survey request for this survey design:

2.1 Phase 1 - GFPC Measurements for Concrete and Clean Steel Surfaces 2.1.1 For this design, the minimum number of static survey points (GFPC) for each survey unit is 8 (see Attachment 3-1 through 3-15). Additional points have been added to provide coverage over the entire survey unit. 1 minute shielded and unshielded count times area required for all static measurements.

2.1.2 The starting point (0, 0) for physically locating each static survey point is shown on the attachments (see Attachment 4-1 to 4-5). Contact the cognizant SR coordinator if there are any questions regarding these starting locations.

2.1.3 The scan speed is set at 2.2 cm/sec. Scan coverage is set at 100% for all Class 1 concrete and clean steel surfaces that were not previously scanned by SRA.

2.1.4 This survey design requires the detector be in contact with the surface during all measurement phases except in areas where this is not physically possible (gouges, cavities, etc.). Any areas that cannot be surveyed lAW this instruction shall be listed for further evaluation.

2.1.5 All surfaces have been evaluated with respect to the average depth of gouges in these areas. Areas where gouges exceed 2 1/2" in depth should not be surveyed using the GFPC. These areas should have been identified lAW Reference 3.1 prior to starting this survey work. Additional locations (discovered during survey work),

that cannot be adequately surveyed (for any reason) should be listed and marked for further evaluation. Whenever possible, these areas should be scanned using a Nal detector lAW Section 2.2 of this calculation.

2.1.6 The DCGLw is 13.000 dpm1100 cm2 or 983 cym above background for a static measurement (from Compass output).

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SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-027 0

Page 3 of /a2 Subject Balance of SSGS Footprint - Survey Plan 2.1.7 The action level during first phase scanning is 500 cpm above background. If this level is reached, the surveyor should stop and perform a count of at least 1/2 minute duration to identify the actual count rate from the elevated location.

NOTE: Static and Scan MDC values are listed in the tables in Section 4.21 and 4.22.

2.1.8 Areas greater than the DCGLw (983 ncPm) must be identified, documented, marked, and bounded to include an area estimate.

2.1.9 If remediation actions are taken as a result of this survey, this survey design must be revised or re-written entirely.

2.1.10 When an obstruction is encountered during the static measurement phase that will not allow placement of a static survey point, contact the cognizant SR coordinator for permission to delete the survey point. Document the reason for the deletion.

2.1.11 A smear survey shall be performed at static measurement point locations. These smears shall be obtained after static measurements are acquired. Smears shall be assayed for beta/gamma and alpha contamination. Report results in net counts per minute. A composite gamma scan shall also be performed and reported.

2.1.12 A gas flow proportional counter (GFPC) shall be used in the beta detection mode for phase 1 survey work (Ludlum 2350-1 with a 43-68B probe).

2.1.13 Other instruments of the type specified in 2.1.12 above may be used durin, the FSS but they must demonstrate an efficiency at or above the value listed in -1 (23.9%).

2.2 Phase 2 - Nal Scanning for Corroded Steel and Extremely Rough Concrete Surfaces 2.2.1 These locations have been previously marked for scanning using a 2" by 2" Nal detector or have been identified during phase I survey work. All of these areas shall be clearly identified, bounded and documented.

2.2.2 For open areas, the scan speed is set at 10 cm/second when scanning with a 2" by 2" Na! detector, and moving side to side in a serpentine pattern within a distance of 2" from the survey area. The stand-off distance (2") should be monitored frequently during the scanning process. When a suspect area is identifed, a stationary count over the area should be performed to determine the actual count rate (typically 10 to 15 seconds for second stage scanning).

2.2.3 For areas where Nal scanning (described in Section 2.2.2) is not appropriate, hold the detector stationary near the center of the suspect region, within 2" from the surface and determine the count rate. If the area is larger than 12 in, take several measurements in/over the area. Record the approximate dimensions of the area and the position of the detector with respect to where the measurement(s) were taken.

2.2.4 When access to an area does not allow the detector to be within 2" from the surface, perform a measurement at the closest location. Record the result, the actual distance from the face of the detector and the estimated size of the area.

2.2.5 If a count rate of 300 gross cpm is identified, the location should be clearly marked for sampling.

-< hi SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-027 0

Page 4 of 1.

Subject Balance of SSGS Footprint - Survey Plan 2.2.6 The conversion factor for Nal results in cpm/mR/h shall not be less than 180,000 cpm/mR/h (see Attachment 6-1 for a typical instrument calibration report).

2.3 Phase 3 - Sampling of Concrete and Steel Surfaces 2.3.1 Sample concrete at any location above the action level cited is Section 2.1 (phase 1) or Section 2.2 (phase 2) previously discussed. The action level for Phase 1 is 500 (GFPC) ncpm and the action level for phase 2 is 300 cross c m (Na!). A 4" long core bore sample is preferred so that the depth of penetration can be identified.

However, when a core bore cannot be taken because of the quality of the concrete, or because of limited access in an area, sampling should remove the first 1" of concrete and yield a volume of at least 200 cc to ensure an adequate counting MDA for Cs-1 37 (a 4 diameter area by I" deep = -200 cc).

2.3.2 For steel surfaces above the action level for either detection system (300 gross cpm Nal or 500 ncpm GFPC), scrane the surface to collect a sample for a gamma scanning by removing as much material as possible over the suspect area.

Document the approximate size of the area where the materials were removed.

Whenever possible, obtain a volume of no less then 25 cc's (200 cc's is preferred).

3.0 REFERENCES

3.1 SNEC procedure E900-IMP-4520.06, "Survey Unit Inspection in Support of FSS Design".

3.2 Compass Computer Program, Version 1.0.0, Oak Ridge Institute for Science and Education.

3.3 Visual Sample Plan, Version 2.0 (or greater), Copyright 2002, Battelle Memorial Institute.

3.4 SNEC Procedure E900-IMP-4500.59, uFinal Site Survey Planning and DQA".

3.5 GPU Nuclear, SNEC Facility, SSGS Footprint, Drawing, SNECRM-041_SIRO.

3.6 SNEC Calculation No. E900-03-019, Shonka SSGS Footprint & CV Steam Pipe Tunnel (SSGS Side) FSS Survey Design.

3.7 SNEC Calculation No: E900-03-025, SSGS Area Trench & Sump survey Design.

3.8 Plan SNEC Facility License Termination Plan.

3.9 SNEC Calculation No. E900-03-012, Effective DCGL Worksheet Verification.

3.10 ISO 7503-1, Evaluation of Surface Contamination, Part 1: Beta-emitters (maximum beta energy greater than 0.15 MeV) and alpha-emitters, 1988.

3.11 SNEC Calculation No. 6900-02-028, GFPC Instrument Efficiency Loss Study.

3.12 MicroShield, Computer Radiation Shielding Code, Version 5.05-00121, Grove Engineering.

3.13 NUREG-1507, "Minimum Detectable Concentrations With Typical Radiation Survey Instruments for Various Contaminants and Field Conditions," June 1998.

3.14 SNEC procedure E900-IMP-4520.04, "Survey Methodology to Support SNEC License Termination".

3.15 SNEC Calculation No. E900-03-020, CV Interior FSS Survey Design.

r<

SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-027 0

Page 5 of /*2 Subject Balance of SSGS Footprint - Survey Plan 3.16 NUREG-1575, "Multi-Agency Radiation Survey and Site Investigation Manual", August, 2000.

3.17 Microsoft Excel 97, Microsoft Corporation Inc., SR-2,1985-1997.

4.0 ASSUMPTIONS AND BASIC DATA 4.1 A gas flow proportional counter (GFPC) will be used in the beta detection mode as the phase 1 survey instrument (a Ludlum 2350-1 with a 43-68B probe).

4.2 The Compass computer program is used to develop the number of fixed point measurement locations that are to be taken within this Class 1 survey unit (Reference 3.2) 4.3 The WRS statistical testing criteria will be applicable for this survey design (beta measurements only).

4.4 The number of static measurement points chosen by Compass are located on diagrams by the Visual Sample Plan (VSP) computer code (Reference 3.3). These survey units contain rough areas missed during the SRA survey work.

4.5 VSP is used to plot random start systematically spaced fixed point survey locations. The coordinates of the survey points are provided on each diagram. Because of edge effects and a desire to error on the conservative side, additional measurement points have been forced either by increasing the MARSSIM overage above the required 20%, or by extending the systematically spaced static points over the entire length of individual survey units.

4.6 Reference 3.4 was used as guidance during the survey design development phase.

4.7 The drawing used to determine the physical extent of these areas is listed as Reference 3.5.

4.8 Remediation History Remediation of the SSGS Footprint began with gross decontamination of the sump areas and removal of contaminated hardware and piping systems. Surface cleaning was performed by removing a thickness of the concrete surface in affected areas. Core bores were then taken to determine the depth of the contamination and to estimate remediation effectiveness. Remaining piping systems were sampled and gamma scanned to determine the existing concentrations. Many obstructions were cut off and concrete surfaces were scraped free of paint and scale. Remediation efforts included combinations of the following cleaning techniques:

  • Scabbling and power chisel
  • grinding and use of an oxy/acetylene torch to remove metal obstructions
  • surface scraping
  • water flush 4.9 This survey design uses an effective gross activity DCGLw value developed for and reported in Reference 3-6 & 3.7.

Five (5) radionuclides were not considered since there was no significant values in any sample result for these nuclides (Pu-241, C-14, Ni-63, H-3 and Eu-152). All samples were decayed to 7/15/03 before they were combined as a single representative concentration (see Reference 3-6 & 3.7).

M_

SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-027 0

Page 6 of /2 Subject Balance of SSGS Footprint - Survey Plan The SNEC License Termination Plan (LTP) (Reference 3.8) allows the use of a 2 sigma plus the mean treatment when combining multiple sample results to form an effective concentration mix. This approach was used to determine the effective DCGLw values for the SSGS Footprint.

The decayed "2 sigma plus the mean" sample result were used as input to the spreadsheet titled "Effective DCGL Calculator for Cs-137" (Reference 3-9), to determine the effective DCGL value for the SSGS Footprint. This spreadsheet calculates a gross activity DCGLw value of -17,498 dpm/100 cm2 (see Reference 3-6 & 3-7). A further correction to the gross activity DCGLw is necessary to address de-listed radionuclides and an administrative limit set by the SNEC facility. The SNEC facility has instituted an administrative limit of 75% of the allowable dose for the area. The de-listed radionuclide dose is accounted for within the 75% administrative limit. The 75% administrative limit is applied as follows: 0.75 x 17,461 dpm/100 cm2 = 13,124 dpm/100 cm2. This value is rounded to 13.000 dpm/100 cm2.

4.10 Cs-1 37 accounts for the majority of the total activity in the modified sample result.

  • The SNEC modified sample is greater than 99% Cs-137.

Cs-137 provides the only reasonably detectable radionuclide in this mix. Cs-137's detection efficiency has been checked by SNEC personnel using ISO standard 7503-1 methodology (Reference 3.10). The SNEC facility uses only the lowest reported GFPC efficiency for any of the instruments available for the survey work as input to the survey design process. -1 indicates an instrument efficiency of 0.478. The ISO value of 0.5 is used as the source efficiency. The instrument S/N used to determine this value is 126218 and the probe S/N is 95080.

Other GFPC instruments may be used during the FSS but theV must demonstrate an efficiency at or above 0.478 for the instrument efficienci.

4.11 The current version of Compass (version 1.0) does not perform correctly when using the gross activity option for multiple radionuclides. Therefore, an alternative will be implemented for this survey design. The alternative approach involves several small changes that will not negatively impact the survey design process. These changes are:

4.11.1 For this survey design, the effective efficiency will be calculated using the following:

Ej = 0.478 x [any surface condition correction factor that impacts efficiency e.g.,

the impact from an increase in the average distance between the detector and source caused by a rough surface (uneven source area)].

Es = [0.5 (ISO for Cs-137 energy betas)] x [the fraction of Cs-137 in the source area, which would be 1 for the Cs-1 37 calibration source or 0.996 for Cs-137 in the SSGS footprint]

4.11.2 A radionuclide will be created in the library of Compass called 'Gross Activity". This radionuclide will have the same nuclear parameters as Cs-137 (half-life, decay time, etc.). The effect will be (when called up) that "Gross Activity" will replace Cs-137 on the print-out from the Compass program (administrative impact only).

4.11.3 Only "Gross Activity" will be used in the Compass program for this survey design.

However, the Area Factors (AF) input to Compass will be for Co-60, which is the more conservative of all SNEC AF values for radionuclides present in the mix. Note

as_

SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-027 0

Page 7 of JP Subject Balance of SSGS Footprint - Survey Plan that Co-60 AF values are very close to Cs-137 AF values so there is little additional impact from using a Co-60 area factor.

4.11.4 A detector stand-off distance of 2 tA" is used to compensate for rough surfaces in the SSGS area. This factor corrects the overall efficiency by a factor of 0.25 (see Reference 3.7 & 3.11) 4.12 The detectors physical probe area is 126 cm2, and the instrument is calibrated to the same source area for Cs-137. The gross activity DCGLw is taken to be 13,000 dpm/100 cm2 x (126 cm2 physical probe area/100 cm2) = 16,380 x (0.996 disintegration of Cs-137/

disintegration in mix) x cj (0.478) x es (0.5) x 0.25 (distance factor) which yields -975 net cpm above background (Compass calculates 983 ncpm as the gross beta DCGLw). The 0.06 count per disintegration counting efficiency considers only the Cs-137 contaminant present in the sample material matrix, and is calculated by: ei (0.478) x cE (0.5) x 0.996 disintegration of Cs-137/disintegration in mix x 0.25 (efficiency loss factor due to distance from surface) = 0.06 cts/disintegration.

4.13 Surface defects (gouges, cracks, etc.), are present in this survey unit, but a portion of the surface area in this survey unit is relatively smooth. Thus the average concentration of the source term will be overestimated by using a distance correction factor of 0.25 for all areas within these survey units.

4.14 Inaccessible areas or corroded steel surfaces, or any area where a 43-68 beta probe can not be used, will be gamma scanned using a 2" x 2" Nal detector. The detector will be set-up and calibrated with a Cs-137 window setting typical to that described in Attachment 6-1 (with a minimum conversion value of 180,000 cpm/mRlh).

4.15 MicroShield models of concrete slabs containing Cs-137 were developed for this survey design (see Reference 3.7 & 3.12). Two models were used:

1) a 3" thick slab of concrete 18" long by 12", wide with a density of 2/3 that of concrete to simulate an extremely rough surface (many pits and valleys), and
2) a 1V thick slab of concrete 18" long and 6" wide to simulate a narrow but relatively smooth surface such as the bottom of the Trench channel. The concentration used was 1 pCi/g Cs-137 and the full density of concrete is assumed to be 2.35 g/cc. Then the concentration of Cs-137 in the first model is 2.35g/cc x 2/3 x 1 pCilg or 1.567E-06 uCicc of Cs-1 37 for the rough model, and 2.35E-06 uCi/cc for the smaller slab model. A 1" thickness was modeled for the smaller slab since volumetric contamination in concrete in the SSGS Footprint area has not been seen much below 1" in concrete core bore samples taken from this structure. From Reference 3.7, the calculated MDCscan for these two models is 2 and 4.8 pCi/g Cs-1 37 respectively.

4.16 The results of the MicroShield modeling indicate that an exposure rate of approximately 6.611E-05 mR/h is obtained at a distance of 3" (2" inches from the face of the detector),

from the surface of the smaller slab model, and 1.601E-04 mR/h is seen 3 inches from the surface of the larger or rough surface model. Exposure rate is measured to the center of the detector and therefore the air gap between the surface of both models is taken to be 2".

4.17 A third MicroShield model of a surface deposition containing Cs-137 was also developed for this survey design (see Attachment 7-1 to 7-7). For this scenario, the modeled area is assumed to be an 18" diameter disk source with a 1 pCVcm 2 activity evenly dispersed over the surface. The source area is assumed to be a corroded steel plate or a surface

MI SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-027 l0 Page 8of /

Subject Balance of SSGS Footprint - Survey Plan deposited concrete source. This model incorporates a 2 mm thickness of iron oxide (Fe2O3) to simulate a corroded steel surface or a near surface deposit in concrete. The resulting mR/h value was 2.212E-05. Then the calculated pCi/cm2 MDCscan is 14.5 pCVcm 2 (3200 dpm/100 cm2) for a background count rate of 100 cpm. For an area where background is 300 cpm the MDCscan would be 25 pCi/cm2 (5600 dpm/100 cm2). For a steel or concrete surface deposit this would be well under the surface DCGLw. For the case where penetration into concrete is suspected, a gross count rate of 300 cpm will be used to indicate an area where sampling of the surface or volume materials should be performed.

4.18 The volumetric DCGLw for concrete is assumed the same as soil for the site and from Reference 3.6 & 3.7 the Cs-137 volumetric DCGLw is calculated to be 4.93 pCi/g. This is the administrative limit for the SSGS area. The volumetric limit can be compared directly to the Nal scanning results. Scanning using the prescribe criteria will detect values at or above the DCGLw of 4.93 pCi/g Cs-137. When an elevated scan result is observed while scanning with the Nal, a sample will be taken. The sample will be a grab sample or a core bore sample. The sample should be collected to a minimum depth of 1" for a grab sample or 4" for a core bore sample. Core bore samples are preferred whenever possible.

4.19 This survey unit is below grade and is surrounded by concrete walls. Since below grade ambient background radiation levels (shielded measurements) are typically lower than grade level ambient background levels, an adjustment to GFPC background values is made. Additionally (see Reference 3.12), steel background values are lower than concrete background values for both GFPC and Nal measurements. Therefore, corrected steel background values will be used as input to the Compass program since these values will be conservative when subtracted from gross concrete GFPC measurement values and will be valid for steel surface measurements as well. See additional discussion on background below.

4.19.1 The shielded steel measurement data from the SNEC CV -790' El data (Reference 3.15), has been subtracted from the Williamsburg shielded steel value to yield a mean net difference of 35 cpm (see Attachment 8-1). This value was then subtracted from the Williamsburg unshielded GFPC data to develop a conservative value representing background for both steel and concrete in the SSGS Footprint.

This method produces Static and Scan MDC values that are reported by Compass to be lower than previously calculated in Reference 3.7. The values from Reference 3.7 are shown in the tables in Section 4.23 and 4.24. All of these values meet survey design constraints.

4.19.2 For Nal measurements, background values were determined by taking measurements at an on-site non-impacted structure (see Attachment 9-1). These values are then used to conservatively estimate the MDCscan values for concrete and steel surfaces. Nal scanning is only used to determine sampling locations. No adjustment of Nal background values are made. Concrete background values are used to determine MDCscan values (see Attachment 9-1 for background Nal values).

4.19.3 Area variability measurements are taken in the SSGS Footprint using the GFPC.

These measurements provide the highest estimate of area variability between background and the survey unit measurements, and are used to determine the number of required static points for these survey units (see Attachment 10-1).

SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-027 0

Page 9of 12 Subject Balance of SSGS Footprint - Survey Plan 4.20 There are two types of structural materials found in these five survey units (concrete and steel). The majority of steel surfaces are severely corroded making them unfit for survey work using a GFPC instrument. These surfaces will be scanned with a Nal detector to determine sampling points:

4.21 The static beta-gamma MDC calculation results for these survey units are shown in -1 to 3-15, and are based on steel background data. The results summarized below are from Reference 3.7, and are based on corrected concrete background values.

Non-impacted concrete background material results are shown on Attachment 11-1. These values were used in Reference 3.7, and are valid for this survey design as well.

Material Valid for Survey Units Corrected BKGND (ctslmin)

MDCsTATc (dpm/lOO cm Concrete (Reference 3.7)

SS14-6 & SS14-1 to SS14-5 298 (corrected bkgnd data)

Compass = 1,101 Steel (Attachment 3-2 SS14-1 to SS14-5 176 (corrected bk nd data)

Compass = 855 4.22 The scan MDC calculation is determined based on a 2.2 cm/sec scan rate, a 1.38 index of sensitivity (95%

correct detection probability and 60%

false positive),

0.06 counts/disintegration and a 126 cm2 probe area. Compass calculates a value of 1,671 dpm/100 cm2 using the corrected steel background materials. The value calculated for corrected concrete materials from Reference 3.7 is reported in the following table.

In all cases, the scan MDC is less than the gross activity DCGLw for these survey units.

Therefore, there is no need to add additional survey points to this survey design for purposes of meeting hot spot design criteria (see Attachment 3-1 to 3-15).

Material Valid for Survey Units Corrected BKGND (cts/min)

MDCscAN (dp m1 00 cm")

Concrete (Reference 3.7)

SS14-6 & SS14-1 to SS14-5 298 (corrected bkgnd data) l Compass = 2,175 Steel (Attachment 3-3)

SS14-1 to SS14-5 176 (corrected bkgnd data) _ Compass = 1,671 NOTE: Compass does not use the 126 cm2 probe correction factor in the MDCscan equation.

4.23 The survey units described in this survey design were inspected after remediation efforts were completed. A copy of portions of the SNEC facility post-remediation inspection report (Reference 3.1), is included as Attachment 12-1 to 12-_..

4.24 No special area characteristics including any additional residual radioactivity (not previously noted during characterization) have been identified in this survey unit.

4.25 The decision error for this survey design is 0.05 for the a value and 0.1 for the p value.

4.26 Special measurements including gamma-ray spectroscopy are not included in this survey design. Gross gamma scans are conducted along with gross beta scans.

4.27 Sampling of concrete material will be performed lAW this survey design if elevated areas are located during the scanning process (see Section 2.3).

4.28 The applicable SNEC site radionuclides and their associated DCGLw values are listed on Exhibit 1 of this calculation.

4.29 The survey design checklist is listed in Exhibit 2.

4.30 The Area Factors for this survey unit is shown below (Co-60). These values (as applicable),

were input to the Compass computer program and are the same as those reported in Reference 3.7. The lower limit area factor for areas less than 1 square meter is 10.1. Area

SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-027 0

Page 10 of )*

Subject Balance of SSGS Footprint - Survey Plan factors for values between the values listed in the following table, are interpolated from the data by Compass.

AREA (mi)

AREA FACTOR 1

10.1 4

3.4 9

2 16 1.5 25 1.2 36 1

5.0 CALCULATIONS 5.1 All major calculations are performed intemal to applicable computer codes or within an Excel spreadsheet.

6.0 APPENDICES 6.1 -1 to 1-5, includes a diagram of the SSGS Footprint that contain these survey units, depicts the missed SRA survey areas, and contains a list of these areas.

6.2 -1 to 2-5, are base diagrams of each survey unit.

6.3 -1 to 3-15, is Compass output as a result of each survey design input parameter for these survey units.

6.4 -1 and 4-5, is the VSP plotted static measurement locations for each section of this survey unit. Some dimensions are included.

6.5 -1, is the SNEC site calibration sheet for the GFPC radiation measurement instrument with the lowest Cs-1 37 detection efficiency to be used on this survey work.

6.6 -1, is a typical Nal detector calibration sheet for a Cs-137 windowed instrument.

6.7 -1, is the MicroShield output for a disk source of Cs-1 37.

6.8 -2 to 7-7, are Nal scan criteria and calculated MDCscan results for selected background values.

6.9 -1, is background values for the GFPC detection system taken at the Williamsburg Coal Fired Steam plant.

6.10 Attachment 9-1, is concrete background measurements for a Nal instrument taken at the mouth of the Intake Tunnel.

6.11 0-1, is measurements taken in the SSGS Footprint as a measurement variability assessment.

6.12 Attachment 11-1, is a series of concrete GFPC measurements taken at the mouth of the Intake Tunnel.

6.13 Attachment 12-1 to 12-

, is the survey units inspection report.

C-<

SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-027 0

l Page 11 of Subject Balance of SSGS Footprint - Survey Plan Exhibit I SNEC Facility DCGL Values (a) 25 mrem/y Limit 4 mremly Goal 25 mremly Limit (All Pathways)

(Drinking Water)

Radionuclide Surface Area Open Land Areas Open Land Areas (b)

(dpm/100cm2)

(Surface & Subsurface)

(Surface & Subsurface)

(pCi/g)

(pc019)

Am-241 2.7E+01 9.9 2.3 C-14 3.7E+06 2

5.4 Co-60 7.1 E+03 3.5 67 Cs-137 2.8E+04 6.6 397 Eu-152 1.3E+04 10.1 1440 H-3 1.2E+08 132 31.1 Ni-63 1.8E+06 747 1.9E+04 Pu-238 3.0E+01 1.8 0.41 Pu-239 2.8E+01 1.6 0.37 Pu-241 8.8E+02 86 19.8 Sr-90 8.7E+03 1.2 0.61 NOTES:

(a) While drinking water DCGLs will be used by SNEC to meet the drinking water 4 mrem/y goal, only the DCGL values that constitute the 25 mrem/y regulatory limit will be controlled under this LUP and the NRC's approving license amendment (b) Usted values are from the subsurface model. These values are the most conservative values between the two models (i.e.,

surface & subsurface).

SNEC CALCULATION SHEET i.

Calculation Number Revision Number Page Number E900-03-027 0

Page 12 of___

Subject Balance of SSGS Footprint - Survey Plan Exhibit 2 Survev Design Checklist Calculation No.l E900-03-027 l SS14.1, SS14-2, SS14-3, SS14-4 & SS14-5 Status Reviewer rTEM REVIEW FOCUS (Circle One) lnItWs & pate 1

Has a survey design calculation number been assigned and is a survey design summary Ses) N/A 10 1.

/a;

______description provided?

2 Are drawings/diagrams adequate for the subject area (drawings should have compass (Yes

~headings)?

3 Are boundaries properly identified and Is the survey area classification clearly indicated?

YesA 4

Has the survey area(s) been properly divided into survey units lAW EXHIBIT 10 Ye N/A 5

Are physical characteristics of the area/location or system documented?

es N/A 6

Is a remediation effectiveness discussion Included?

7 Have characterization survey and/or sampling results been converted to units that are comparable to applicable DCGL values?

Is survey and/or sampling data that was used for determining survey unit variance included?

Yes N/A 9

Is a description of the background reference areas (or materials) and their survey and/or N/A sampling results included along with a Justification for their selection?

10 Are applicable survey and/or sampling data that was used to determine variability Included?

j N/Aj 1 1 Will the condition of the survey area have an impact on the survey design, and has the

)IA probable Impact been considered in the design?

Has any special area characteristic including any additional residual radioactivity (not 12 previously noted during characterization) been Identified along with Its impact on survey Yes

/A design ?

13 Are all necessary supporting calculations and/or site procedures referenced or Included?

/

(A 14 Has an effective DCGLw been Identified for the survey unit(s)?

(;

)N/A 15 Was the appropriate DCGLEM Included In the survey design calculation?

N/A 16 Has the statistical tests that will be used to evaluate the data been Identified?

Cfefi) N/A 17 Has an elevated measurement comparison been performed (Class I Area)?

es N/A 18 Has the decision error levels been Identified and are the necessary justifications provided?

6 i)UA 19 Has scan instrumentation been Identified along with the assigned scanning methodology?

CYs) N/A

=

20 Has the scan rate been identified, and Is the MDCscan adequate for the survey design?

LsN/A 21 Are special measurements e.g., In-situ gamma-ray spectroscopy required under this design,

< A) and Is the survey methodology, and evaluation methods described?

i 22 Is survey Instrumentation calibration data Included and are detection sensitivities adequate?

(7 N/A 23 Have the assigned sample and/or measurement locations been clearly identified on a diagram WNA or CAD drawing of the survey area(s) along with their coordinates?

Y eS 24 Are Investigation levels and administrative limits adequate, and are any associated actions clearly indicated? 7IlA 25 For sample analysis, have the required MDA values been determined.?

Yes N/A 26 Has any special sampling methodology been idenUfied other than provided In Reference 6.3?

Yes N/A 1

NOTE: a copy of this completed form or equivalent, shall be Included within the survey design calculation.

15 (East Wall)

SS14-1 (floor)

(75.2 m2 Total. 65 m-2 2No Trc)

(i Z]

SS16 Walls up to 2 meters SS17 Walls > 2 meters -

SS14-3 0

X

V4 LLJ Mi U

SSGS FOOTPRINT PLAN EL. 790'-0"

c SC., ILI,

__z ------

S Si !r-ooJ Ss 1I!O

____Sv 7,

14 t

SETIN Li -

I

£St~I~'~-'

e, e,0 co SIhII 5-51.W1 2-c I

~

F SEC TIO N 9 31-SECTION 4 SE NEN I;--,I Li

$.J T-1-3 5s;

¶ 7 T

ho 7 U S

i PLAN EL. 790' A FACHME NT A-C

55 IM-3-ouk.

5s IL4 -

cc~

S Lfw-j.dlo; S -M i]3 -

it 5s w-o-cal

  • S 1 -qX _e ~S-5S114-4-%

S Sl-

-40 I

11

%L -~-ioo

<':i 11-1

-5,.0 C.

,floppy

/

U~DDM~)4 10ftM"I 5ilu s¢

'1-PLAN EL. 790' ATTACHMENT

SSGS Floor Class-i Areas Missed by Shonka Survey Unit-Location Approximate area (in)

Depth (mm)

Materials Evaluation area SS14-1-001 Trough North 3345 3.4 Concrete SS14-1-002 Large Pad, NE 2932 8.4 Concrete SS14-1-003 Sm Pad N.E.

768 5.2 Concrete SS14-1-004 Sm Gouge N.E.

88 17.4 Concrete SS14-1-005 Bolt Heads 60 12.8 Concrete, Steel SS 14-1-006 Areas Under Stairs 8923 2.1 Concrete SS 14-1-007 Rough Areas Adjacent to Sec 852 10.2 Concrete I Trench SS14-1-008 Deep Gouge East of Trench 180 81.7 Concrete,

  • SS 14-1-009 Trough Areas, South 8001 15.4 Concrete SS14-1-010 Octagonal Pad 3580 0.4 Concrete SS14-1-011 Pipe Imprint 727 42.2 Concrete SS14-1-012 Rough Areas South of Trench 1644 24.4 Concrete SS14-1-013 Pedastal, rough areas north of 11385 32.4 Concrete, Steel Section 2 of trough, around down comer SS14-1-014 Area around Downcomer 3967.5 0.4 Concrete, Steel SS14-1-015 Temp storage location of 352.5 6.1 Concrete Down comer Cover SS14-1-016 Downcomer Covers and 9035

>120 Steel

  • flanges SS14-2-001 Concrete adjacent to Down 1152 17.4 Concrete
  • comer Cover SS14-2-002 Concrete adjacent to Down 1152 17.4 Concrete
  • comer Cover SS14-2-003 1/2 of Down Cover storage 705 6.1 Concrete location SS14-2-004 2 pipes to intake Tunnel 4476 14.2 Steel
  • SS14-2-005 Gouge 81 15.6 Concrete SS14-2-006 Rough Areas South of Trench 316 9.4 Concrete SS14-2-007 Trough adjacent to Wall 523 0.2 Concrete SS14-2-008 Pump Pedestals 24,965 22.1 Concrete SS14-2-009 North sump edge 680 32 Concrete, Steel SS14-2-010 South sump edge 1782 30.6 Concrete SS14-2-011 Downcomer Covers and 5669

>120 Steel

  • flanges SS14-3-001 Pad 7310 23.4 Concrete SS14-3-002 Pad 7310 24.6 Concrete SS14-3-003 Pipes 1413 49.6 Concrete, Steel
  • SS14-3-004 Pad 4800 36 Concrete SS14-3-005 Pad 480 36 Concrete SS14-3-006 Rough Area 3690 38.2 Concrete, Steel SS14-3-007 Rough Area 4160 63 Concrete
  • SS14-3-008 Pipes/Drains 4700

>126 Concrete, Steel

  • SS14-3-009 Cutout Pipe trenches 1227 87 Concrete
  • SS14-3-010 Rough Patches North or 714 24 Concrete Trench SS14-3-011 Trough 9216 15 Concrete A1TACHMENEN T

4

SSI4-4-OOl Trough 6736 32.8 Concrete SSI4-4-002 Rough Area East of sump 2793 14.8 Concrete SS14-4-003 Rough SE of Sump 3440 20.5 Concrete SS14-4-004 Foundation 3960 42 Concrete SSI4-4-005 Foundation 8190 52.3 Concrete

  • SS14-4-006 Pipe opening 10214 10.4 Concrete, Steel
  • SS14-4-007 Rough Areas North and South 1030 17.5 Concrete of Trench SS14-5-001 Trough 7348 30.5 Concrete
  • SS14-5-002 Rough Areas West Trench 1980 61.8 Concrete
  • SS14-5-003 Pedestal, Gouge 1977 43.2 Concrete, Steel SS14-5-004 Floor Adjacent to Valve 7285 34.5 Concrete
  • SS14-5-005 Valve, Pipe 4229 50.5 Steel
  • SS15-001 Recesses in East Wall 2748 5.5 Concrete SS15-002 Steel trim on Recesses in East 936 0.4 Steel Wall
  • Area that may require evaluation via gamma analysis, due to inaccessible surfaces.

A1TTACHME Nrr

/ i

SS14-1 (floor) 65 mA2 - No Trench SS1 5 (East Wall)

LZI I

m ATTA(rt4AFNT____.__

SS14-2 (floor) 58.2 mA2 - No Trench


001 a

Al~rr C wwR A 2

SS14-3 (floor) 83.1 No Trench SS16 Walls up to 2 meters SS17 Walls > 2 meters Iz ad,

SS14-4 (floor) 61 mA2 - No Trench I'I 7

e IA------

ATTACHMENTS

SS14-5 (floor) 52.7 mA2 - No Trench EL ATrACHMENT

'vW Building Surface Survey Plan Survey Plan Summary Site:

Planner(s):

Survey Unit Name:

Comments:

Area (m2):

Selected Test:

DCGL (cpm):

LBGR (cpm):

Alpha:

Beta:

SSGS Trench Area BHB SS14-1 Remaining Surfaces - 790' El SSGS Footprint 65 Classification:

WRS Estimated Sigma (cpm):

983 Sample Size (N/2):

800 Estimated Conc. (cpm):

0.050 Estimated Power.

0.100 EMC Sample Size (N):

1 65.2 8

163 1.00 8

Prospective Power Curve

_ 0.8 0.7 W 0.6 I 05 A0.

_ 0.4 c

-' 0.7

.0.

t 0.6

=04 03 I

I I

.I

.I I

=

-I.-

=I

=

I:

r

-I 100 200 300 400 500 600 700 Net Beta (cpm)

DCGL I

I beta 800 900 1000 1100 Estimated Power Power LBGR COMPASS v1.0.0 1011412003 ATAr.HMEN 3

I Page 1

Building Surface Survey Plan Contaminant Summary DCGLw Contaminant (dpm/100 cm')

Gross Activity 13,000 Beta Instrumentation Summary Gross Beta DCGLw (dpm/100 cmz):

Total Efficiency:

Gross Beta DCGLw (cpm):

13,000 0.06 983 ID Type Mode Area (cm2) 7 GFPC Beta 126 Contaminant Energy' Fraction 2 Inst. Eff.

Surf. Eff.

Total Eff.

Gross Activity 187.87 1.0000 0.12 0.50 0.0595

' Average beta energy (keV) [N/A indicates alpha emission]

2Activity fraction Gross Survey Unit Mean (cpm): 339 +/- 65 (1-sigma)

Count Time (min): I Number of Average Standard MDC Material BKG Counts (cpm)

Deviation (cpm)

(dpm/100 cm')

Steel 37 175.9 17.7 855 COMPASS vl.0.0 10/1412003 Page 2 COMPASS v1.0.0 10/14/2003 Page 2 AM CH ME

Crio Elevated Measurement Comp arison (EMC) for Beta Follow the order of each tab below to perform the EMC.

.d

-i Hi fiI

,;-4

.i-,

)1)

Enter Scanning Instrument Efficiencie{

2) Enter Scan MDC Parameters T
3) View EMC Results Scan MDC Required per Contaminant Contaminant I

DCGLw*

Area Factor Scan MDC Required*

Gross Activity 13,000 2.25 29,250 Statistical Design N/2: l 8

I Bounded Area (m): l 8.1 i

Area Factor: 1 2.25 l

DCGLw*: l 13.000 Scan MDC Required*: l 29.250 Hot Spot Design Actual Scan MDC: 1 1,671 Area Factor: I N/A Bounded Area (m2): I N/A Post-EMC N/2: I 8

IsE_

  • dpmr/1 00 cm2 Q11

.I f

MIJ k; No additional samples are required because the actual scan MDC is less than the DCGLw for each contaminant.

Cr l P Enable Traininc v.1O!2, ATTACHMENT-13

3

WIe Building Surface Survey Plan Survey Plan Summary Site:

Planner(s):

Survey Unit Name:

Comments:

Area (m2):

Selected Test:

DCGL (cpm):

LBGR (cpm):

Alpha:

Beta:

SSGS Trench Area BHB SS14-2 Remaining Surfaces - 790' El SSGS Footprint 58 Classification:

WRS Estimated Sigma (cpm):

983 Sample Size (N/2):

800 Estimated Conc. (cpm):

0.050 Estimated Power:

0.100 EMC Sample Size (N):

I 65.2 8

163 1.00 8

Prospective Power Curve

_1 0.

t o

_ 0.8 I-0.7 GDI t 0.6

r. 0 S 0-s

= 0.4

.- 0.3 E. 0.2

.0.

5 0.1 O~

W

-I--

_I _

II

-I-

,~~~

I

_~

~

I___

100 200 300 400 500 600 700 Net Beta (cpm)

Power DCGI.

I LBGR a

I-beta 800 900 1000 1100 Estimated Power COMPASS vl.0.0 1011412003 Page 1 COMPASS v1.0.0 101103Pg

Building Surface Survey Plan Contaminant Summary DCGLw Contaminant (dpm/100 cm')

Gross Activity 13,000 Beta Instrumentation Summary Gross Beta DCGLw (dpm/100 cm'):

Total Efficiency:

Gross Beta DCGLw (cpm):

13,000 0.06 983 ID Type Mode Area (cm')

7 GFPC Beta 126 Contaminant Energy' Fraction' Inst. Eff.

Surf. Eff.

Total Eff.

Gross Activity 187.87 1.0000 0.12 0.50 0.0595 1Average beta energy (keV) [NMA indicates alpha emission]

' Activity fraction Gross Survey Unit Mean (cpm): 339 +/- 65 (1-sigma)

Count Time (min): 1 Number of Average Standard MDC Material BKG Counts (cpm)

Deviation (cpm)

(dpm/100 cm')

Steel 37 175.9 17.7 855 COMPASS u1.0.0 1011412003 A-ACHMUf 3

Page 2

Elevated Measurement Comparison (EMC) for Beta Follow the order of each tab belowto perform the EMC.

j nstrument f nter can arameers 3J View EMC Results I

d

.. 

-

I 1

I Scan MDC Required per Contaminant Contaminant I

DCGLW" I

Area Factor I

Scan MDC Required*

l Gross Activity 1 3.000 2.48 32.240 Statistical Design N/2: I 8

Bounded Area (mi: 1 7.3 Area Factor l 2.48 DCGLw` 1 13,000 Scan MDC Required*: I 32.240 Hot Spot Design Actual Scan MDC) l 1.671 Area Factor: I N/A BoundedArea(m): I N/A Post-EMC N/2: I 8

=_11.1W-i

  • dpm/100 cm2 No additional samples are required because the actual scan MDC is less than the DCGLw for each contaminant.

lP Enable Traininc

'.:1. s ri IOKfl t.-rACHMENIA-

-. G

'6?/ Building Surface Survey Plan Survey Plan Summary Site:

Planner(s):

Survey Unit Name:

Comments:

Area (m2):

Selected Test:

DCGL (cpm):

LBGR (cpm):

Alpha:

Beta:

Prospective Po%

SSGS Trench Area BHB ss14-3 Remaining Surfaces - 790' El SSGS Footprint 83 Classification:

WRS Estimated Sigma (cpm):

983 Sample Size (N12):

800 Estimated Conc. (cpm):

0.050 Estimated Power:

0.100 EMC Sample Size (N):

I 65.2 8

163 1.00 8

wer Curve

- o1 0.9

_ 0.8 0.7 41 c.i

= 0.6

  • 0.5 t 0.6 4.0.

= 0.1 O

I T, II

_ H

-r

-I-

-I I

-I-

.I I

=L 4-100 200 300 400 500 600 700 NetBeta (cpm)

DCGL a

l-beta 800 900 1000 1100 Power LBGR Estimated Power COMPASS vI.0.0 1 0/1412003

^ rTACHME-Page 1

Building Surface Survey Plan Contaminant Summary DCGLw Contaminant (dpml100 cm2)

Gross Activity 13.000 Beta Instrumentation Summary Gross Beta DCGLw (dpml100 cm2):

Total Efficiency:

Gross Beta DCGLw (cpm):

13.000 0.06 983 ID Type Mode Area (cm')

7 GFPC Beta 126 Contaminant Energy' Fraction' Inst. Eff.

Surf. Eff.

Total Eff.

Gross Activity 187.87 1.0000 0.12 0.50 0.0595

'Average beta energy (keV) [N/A indicates alpha emission]

' Activity fraction Gross Survey Unit Mean (cpm): 339* 65 (1-sigma)

Count lime (min): 1 Number of Average Standard MDC Material BKG Counts (cpm)

Deviation (cpm)

(dpml100 cm')

Steel 37 175.9 17.7 855 COMPASS vl.0.0 I Oil 412003 Page 2 COMPASS vi.0.0 1011412003 Page 2

-I I:

II I.

rI.

..iJ Elevated Measurement Comparison (EMC) for Beta Follow the order of each tab below to perform the EMC.

1) Enter Scanning Instrument Efficiencie4I 2J Enter Scan MDC Parameters T 31 View EMC Results

.1

'I I

I'

-

I.

'-

3 1 11*

Scan MDC Required per Contaminant Contaminant l

DCGLw*

I Area Factor I

Scan MDC Required*

I GrossActivity 13.000 1.90 24,700 Statistical Design N/2: I 8

Bounded Area (m): 1 10.4 Area Factor: I 1.90 DCGLw": j 13,000 Scan MDC Required*: l 24,700 Hot Spot Design Actual Scan MDC: l 1,671 Area Factor: I N/A Bounded Area (m5: I N/A Post-EMC N/2:

8 I

  • dpmr/100 cm2 No additional samples are required because the actual scan MDC is less than the DCGLw for each contaminant.

Wo Enable Traininc

1 IC IE= i*71 D 43 1

A c"MFiNt; ------

'4?/ Building Surface Survey Plan Survey Plan Summary Site:

Planner(s):

Survey Unit Name:

Comments:

Area (m2):

Selected Test:

DCGL (cpm):

LBGR (cpm):

Alpha:

Beta:

SSGS Trench Area BHB SS14-4a Remaining Surfaces - 790' El SSGS Footprint 61 Classification:

WRS Estimated Sigma (cpm):

983 Sample Size (N/2):

800 Estimated Conc. (cpm):

0.050 Estimated Power 0.100 EMC Sample Size (N):

1 65.2 8

163 1.00 8

Prospective Power Curve

,1 V..

_ 0.8 0.7 t 0.6 0.5

_ 0.4

= 03 6 0.2 E 0.1 O-i--

I I

I I--l A I 1

i

!I I

1 T 1 I

I

.~

~ ~

I

_I

-I4---------

-It-l

=

2

.~

I I

100 200 300 400 500 600 700 NetBeta(cpm)

Power DCGL I

LBGR I-beta 800 900 1000 1100 Estimated Power COMPASS v1.0.0 1011412003 Page 1 ATTACHMEINc._S----

l-o-

Building Surface Survey Plan Contaminant Summary DCGLw Contaminant (dpml100 cm2)

Gross Activity 13,000 Beta Instrumentation Summary Gross Beta DCGLw (dpml100 cm2):

Total Efficiency:

Gross Beta DCGLw (cpm):

13,000 0.06 983 ID Type Mode Area (cm')

7 GFPC Beta 126 Contaminant Energy' Fraction" Inst. Eff.

Surf. Eff.

Total Eff.

Gross Activity 187.87 1.0000 0.12 0.50 0.0595

' Average beta energy (keV) [N/A indicates alpha emission]

2 Activity fraction Gross Survey Unit Mean (cpm): 339

  • 65 (1-sigma)

Count Time (min): I Number of Average Standard MDC Material BKG Counts (cpm)

Deviation (cpm)

(dpm/100 cm')

Steel 37 175.9 17.7 855 COMPASS v1.0.0 1011412003 Page 2

-r

, 1,,. "

_

. --,.- -.1

2i;A Elevated Measurement Comparison (EMC) for Beta I

Followthe order of each tab belowto perform the EMC.

it

1) Enter Scannina Instrument Efficienciel 21 Enter Scan MDC Parameters

.l IJ I

3) View EMC Results J

I Scan MDC Required per Contaminant Contaminant l

DCGLW" I

Area Factor I

Scan MDC Required*

I GrossActivity 13,000 2.39 31.070 l

Statistical Design N/2: [

8 Bounded Area (m): 1 7.6 Area Factor: 1 2.39 DCGLw": l 13,000 Scan MDC Required*: 1 31,070 Hot Spot Design Actual Scan MD? :j 1,671 Area Factor.

N/A BoundedArea(m2): I N/A Post-EMC N/2: [

8 FIJI I

I dpm/1 00 cm2 Q

i No additional samples are required because the actual scan MDC is less than the DCGLw for each contaminant I

i '

W Enable Trainin

'a1.ii.,

lmi]

  • A~rli i

3 1

VJ Building Surface Survey Plan Survey Plan Summary Site:

SSGS Trench Area Planner(s):

BHB Survey Unit Name:

SS14-5 Comments:

Remaining Surfaces - 790' El SSGS Footprint Area (M2):

53 Classification:

Selected Test:

WRS Estimated Sigma (cpm):

DCGL (cpm):

983 Sample Size (N/2):

LBGR (cpm):

800 Estimated Conc. (cpm):

Alpha:

0.050 Estimated Power Beta:

0.100 EMC Sample Size (N):

Prospective Power Curve I

65.2 8

163 1.00 8

_1 0.

_ 0.8 0.7 t 0.6

  • 0.5

_ 0.4 c 03

. 02 Z 0.1 E

! I I-I H

i-I I

v ____

_I-I -I--

II 100 200 300 4100 500 600 700 NetBeta (cpm)

DCGL w

I-beta 800 900 1000 1100 Power LBGR Estimated Power COMPASS v1.0.0 1011412003 Page 1

'TACHMEM 3

- /3

Building Surface Survey Plan Contaminant Summary DCGLw Contaminant (dpml100 cm2)

Gross Activity 13,000 Beta Instrumentation Summary Gross Beta DCGLw (dpmnl00 cm):

Total Efficiency:

Gross Beta DCGLw (cpm):

13,000 0.06 983 ID Type Mode Area (cm 2) 7 GFPC Beta 126 Contaminant Energy' Fraction2 Inst. Eff.

Surf. Eff.

Total Eff.

Gross Activity 187.87 1.0000 0.12 0.50 0.0595

' Average beta energy (keV) [NIA indicates alpha emission]

' Activity fraction Gross Survey Unit Mean (cpm): 339

  • 65 (1-sigma)

Count Time (min): 1 Number of Average Standard MDC Material BKG Counts (cpm)

Deviation (cpm)

(dpml100 cm')

Steel 37 175.9 17.7 855 COMPASS v1.0.0 10/1412003 ATACHMAE-Page 2

F3-,TV7.

'Ij -I I U,

--.-.F R- --

--. .

i :,.

f

.,. I

., " --X '. gain'..,

UT I

Elevated Measurement Comparison (EMC) for Beta II Follow the order of each tab belowto perform the EMC.

) Enter Scanning Instrument Efficiencie{

2) Enter Scan MDC Parameters I
3) View EMC Results

.1 I

-j I,

.,.-. '-.4

J Scan MDC Required per Contaminant Contaminant I

DCGL*

I Area Factor I

Scan MDC Required*

I Gross Activity 13,000 2.67 34,710 i

I II I

ii i

II i

I1.

Statistical Design N/2: l 8

BoundedArea(m): ;

6.6 Area Factor l 2.67 DCGGLW":

13,000 Scan MDC Required*: l 34.710 Hot Spot Design I

Actual Scan MDC't l 1,671 Area Factor I N/A I

BoundedArea(m):

I N/A Post-EMCN/2: I 8

I

  • dpm/100 cm2 No additional samples are required because the actual scan MDC is less than the DCGLw for each contaminant l/ Enable Trainin
  • 1 O.

Ii I

,-3

.- J-C-

SS14-1 107" "qqN I

+6

+9 - 1

51 "ff

"-w SS14-2 1

-~~

102"I 1

2 m

7 0 - 2

SS14-3

/ 1-A 6 =0

+10 lill" 4-WE 1 a

8 14

©

  • 2 11/D~

.-- - 3

SS14-4 95 "f

>-N D

312" 0

+11 13 14 - 4

SS14-5 2

305"

"'N

-t-89" 7

8 5

6 LIII 9

\\1 10 1112 - 5 13 14

ORIGINAL C

R?;,s; A 4Liki'

Ghi Rt l

fIn i

ne1BtCallbv tlrn Wog-ksheet.. :

Petio d By-,

R J. Reheard Date_

6 l24103 Insinalm tTWI 126218 Probe SIN 95080 Infsrumeri Vendor Cat Dai s-1WtO3 Cal. Due Date l1V20103 Am-241 (GO 535) S4023 0.25 4/U49 12:00 GMT 4.2AE-01 7.43E4'03 jJOAn,241 Cs.137 (GO 536) S.024 0.50 41tf09 12:00 G4T J IE-01

.S9E+03 l

137 Source Radtonucide Decay DOti Cs137 124103 11 Dcay Factoe 9.5E1 Ep4 rime (days)=

1538 Actjvnty (,aCt 2.821E-41 Source dpm=*

6.261E40S Source dpeMn Probe Area (ernm2)=

5.260E+05 2fl Emission Rafa (secl)=:>

6253E+O3 Probe Arta (cm^2) 2x Emission Rat* (min.t 3.752E+05, 12t 27EssiknRateinPtobeAseJa(mm.tin 3.151 E+4 5 Record otl MinuteSource&Back qroundountlncResults C1 bec t 1rnsISO 7so3-Vate No.

OW Source Gross CPM OW Backgrund CPM oW Sowze Ndl CPht RESULTS I

1.48E4-OS 181 1A93E415 CountslEmrisslon (E) 2 1.49Et05 203 1.490E+05 47.3%

3 1.50E+0S 186 1.499E405 211 EmisslonD~slrinlgratlon (Cs) 4 I.SOE+05 193 1.502E+05 SO____

5 1.51E405 182 1.507EtO5 CounmtlDisntilration (El) 1 515E405 164 1.508E+05 23.9%

7 1.52E+05,

170 1.515E405 r I 1.51E405 3 177 1.513EO_5 1.5ZE#05 161 1.520E405 Approved:

V-tkuJ/ '5r 10 1.52E405 162 1.515EV05 U

Mean=

177.9 1.505E40S Date:

0

/7L-o0 I

Calibration Calculation Sheet Verification Dalel December-02 I

B. Brosey/P. Donnachiezfl December-02 I

I ATTACHMEN1 6-

Uu To HI 10:41 FAX 8653768331 DURATEK INS SERVICES LUDLUM MODEL 44-10 HIGH VOLTAGE PLATEAU DATA SHEET (Detector peaked uslng Cs137 #019454 5uCi button)

Serial Number:

196021 700

.37,380 701 39,576 702 40,089 703 41,493 704 42,322-705 42,859 706 42,756 707 41,336 708 40.700 709 NIA 710 N/A 711 WA Parameter Setting Comments Threshold (1OmV1100) 612 Peaked for CS137 at Window (On) 100 662keV High Voltage l

705 CPMlmR 221,028

,,','a;b.D H~~ues,

'f*

'i61od-~,~

Z4'.l id-dWffo '.-.0'

.W-FWHM= 685 - 605 12.1%

662 xl100° 12O1%

Detector peaked for Cs'37 using Ludlum peaking procedure and threshold setting of 612 and window setting of 100 as requested by John Duskin. 2350-1 #117566 calibration due 01/22104 used for peaking 44-f1i'detector.

4, Performed By:

Reviewed i~

yf2 e

Date:

3 Date:

L____

ATTACHMENT G I

MicroShield v5.05 (5.05-00121)

GPU Nuclear Page

1 DOS Fie
OISKMSS RuDate : October13.22003 Run Time : :2214 PM DWation
o1YaMO Fie Ref Date:

By:

Checked Case

Title:

Disk

==

Description:==

Cs-137 Surface Source with Fe2O3 @ 0.2 cm Geometry: 3-Disk x

Source Dimensions IR, 2286cm 90nl Dose Points Ai X

l Y

Z lt1 7.82 cm 0cm 0 cm 11 in O n QO in Shields Sh'eld jN&e Dimensi Mderial I

Density Shield 1

.2 cm Iron Oodde 5.1 AirGao Ak Q100122 Source Input Grouping Method: Actual Photon Energies WrNaIde I

cuies becucetels u twcrrH 6/cnr Ba-137m 1.5531eO09 57464e+W1 9.468e-007 3.5032e4-Cs-137 1.6417e-009

&0744e+001 1.0000e-0J06 a700~e4)2 Buildup The material reference is : Shield 1 Integration Parameters lR -

S401 GtrurienfentenS 401 Results Eteg Ac" Fklence Rate Fluence Rate Exposue Rate Empmse Rate Me

/oo I MeWc-0/sec MeV/c?/sec mR/ht mRYhu phtos e No Buik Wth B6>

No Buid 8

ithulu 0.031B 1.190Oe" 1.52Be-08 1.735e-08 1.273e-10 1.446e-1O Q0Q322 a195e+00 a448e-08 3L928e-08 2.775e-10 161e-lO 0.0364 7.987e-1 7.604e-08 8.933e-08 4.320e-10 5.075e-10 Q6616 5.1T7e+O1 1.022e-02 1.14te-02 1.980e-05 2212e-0 TOTALS:

5.589e+01 1.022e-02 1.141e-02 1.981e-O5 212e-i ATTACHMENTL7L*

I

Nal Scan MDC Calculation - Surface Sodium Iodide Scan MDC Over a Plane Source A scan MDC for a Nal detector is subject to the following input data:

1) The rate of movement of the detector over the surface
2) The height of the detector over the surface
3) The size of the Nal detector being used
4) The density of any surface contaminant that covers the source term
5) The radionuclide being measured
6) The background level in the area including that from the type of materials being surveyed
7) The surveyors efficiency (usually taken to be 50%)
8) The discriminator level setting of the count rate instrument
9) The plausible radionuclide mix for the area and its detectable gamma emission rate per unit area representing a valid surface model.

Since it is necessary to know these parameters before calculating the MDC scan, the following information/assumptions will be used to identify initial MDC scan results for a 2" by 2" Nal detector under select site conditions.

Basic Instrument Assumptions

1) Scanning is performed using a 2" by 2" Nal detector operated with in a window set around the Cs-1 37 peak area

(-100 keV width).

2) The background count rate is primarily due to naturally occurring radionuclides found in site structural materials plus ambient cosmic interactions.
3) Scanning speed is initially assumed to be 0.1 meterstsecond at a distance of 2" above the surface from the face of the detector. For a 2" by 2" Nal detector this is the same as being 3" from the center of the detector volume.
4) The initial observation interval is 4.6 second.
5) Level of performance for first stage scanning is 95% for the true positive rate, and 60% for the false positive rate which yields a d' value of 1.38. Second stage scanning is reviewed on page 2 of this Attachment.

Basic Modeling Assumptions

1) Corrosion materials on steel surfaces have a density the same as iron oxide (5.1 glcc) with a nominal thickness of 2 mm.
2) The areal hot spot size is assumed to be -0.16 M2.
3) The modeling diameter is 0.457 meters (18" diameter circle).
4) The distance of the detector above the surface is assumed to be 5 centimeters.
5) A surface is uniformly contaminated within the modeled area.

4 nl14 A P A1TACHMEN I

uof A

I, I,

-tlduvuo

. vim i

Nal Scan MDC Calculation - Surface Scan Rate Determination Signal Detection Theory. Personnel conducting radiological surveys for residual contamination must interpret the audible output of a portable survey instrument to determine when the signal (or "clicks") exceed the background level by a margin sufficient to conclude that contamination is present. It is difficult to detect low levels of contamination because both the signal and the background vary widely. Signal detection theory provides a framework for the task of deciding whether the audible output of the survey meter during scanning is due to background or signal plus background levels. An index of sensitivity (d) that represents the distance between the means of the background and background plus signal in units of their common standard deviation, can be calculated for various decision errors (correct detection and false positive rate).

As an example, for a correct detection rate of 95% (complement of a false negative rate of 5%) and a false positive rate of 5%, d' is 3.29 (similar to the static MDC for the same decision error rates). The index of sensitivity is independent of human factors, and therefore, the ability of an ideal observer (theoretical construct), may be used to determine the minimum d' that can be achieved for particular decision errors. The ideal observer makes optimal use of the available information to maximize the percent correct responses, providing an effective upper bound against which to compare actual surveyors. Table 6.5 lists selected values of d'.

Two Stages of Scanning. The framework for determining the scan MDC is based on the premise that there are two stages of scanning. That is, surveyors do not make decisions on the basis of a single indication, rather, upon noting an increased number of counts, they pause briefly and then decide whether to move on or take further measurements. Thus, scanning consists of two components: continuous monitoring and stationary sampling. In the first component, characterized by continuous movement of the probe, the surveyor has only a brief look at potential sources, determined by the scan speed. The surveyors willingness to decide that a signal is present at this stage is likely to be liberal, in that the surveyor should respond positively on scant evidence, since the only cost of a false positive is a little time. The second component occurs only after a positive response was made at the first stage. This response is marked by the surveyor interrupting his scanning and holding the probe stationary for a period of time, while comparing the instrument output signal during that time to the background counting rate. Owing to the longer observation interval, sensitivity is relatively high. For this decision, the criterion should be more strict, since the cost of a yes decision is to spend considerably more time taking a static measurement.

Table 6.5 Values of d' for Selected True Positive and False Positive Proportions 1

False Positive True Positive Proportion Proportion 0.60 0.65 0.70 0.75 0.80 0.85 0.90 0.95 0.05 1.90 2.02 2.16 2.32 2.48 2.68 2.92 3.28 0.10 1.54 1.66 1.80 1.96 2.12 2.32 2.56 2.92 0.15 1.30 1.42 1.56 1.72 1.88 2.08 2.32 2.68 0.20 1.10 1.22 1.36 1.52 1.68 1.88 2.12 2.48 0.25 0.93 1.06 1.20 1.35 1.52 1.72 1.96 2.32 0.30 0.78 0.91 1.05 1.20 1.36 1.56 1.80 2.16 0.35 0.64 0.77 0.91 1.06 1.22 1.42 1.66 2.02 0.40 0.51 0.64 0.78 0.93 1.10 1.30 1.54 1.90 0.45 0.38 0.52 0.66 0.80 0.97 1.17 1.41 1.77 0.50 0.26 0.38 0.52 0.68 0.84 1.04 1.28 1.64 0.55 0.12 0.26 0.40 0.54 0.71 0.91 1.15 1.51 0.60 0.00 0.13 0.27 0.42 0.58 0.82 1.02 1.38 10/1412003 2 of 5 ATTACHMEFrN____7C__

  • a 1 0/1412003 2 of 5

Nal Scan MDC Calculation -Surface Since scanning can be divided into two stages, it is necessary to consider the survey's scan sensitivity for each of these stages. Typically, the minimum detectable count rate (MDCR) associated with the first scanning stage will be greater due to the brief observation intervals of continuous monitoring-provided that the length of the pause during the second stage is significantly longer. Typically, observation intervals during the first stage are on the order of 1 or 2 seconds, while the second stage pause may be several seconds long. The greater value of MDCR from each of the scan stages is used to determine the scan sensitivity for the surveyor.

Determination of MDCR and Use of Surveyor Efficiency. The minimum detectable number of net source counts in the interval is given by s. Therefore, for an ideal observer, the number of i source counts required for a specified level of performance can be arrived at by multiplying the square root of the number of background counts by the detectability value associated with the desired performance (as reflected in d') as shown in Equation 6-8 (MARSSIM):

Prior to performing field measurements, an investigator must evaluate the detection sensitivity of the equipment proposed for use to ensure that levels below the DCGL can be detected (see Section 4.3).

After a direct measurement has been made, it is then necessary to determine whether or not the result can be distinguished from the instrument background response of the measurement system. The terms that are used in this manual to define detection sensitivity for fixed point counts and sample analyses are:

Critical level (Lc)

Detection limit (LD)

Minimum detectable concentration (MDC)

The critical level (Lc) is the level, in counts, at which there is a statistical probability (with a C predetermined level of confidence) of incorrectly identifying a measurement system background value as being greater than background. Any response above this level is considered to be greater than background.

The detection limit (LD) is an a priori estimate of the detection capability of a D measurement system, and is also reported in units of counts. The minimum detectable concentration (MDC) is the detection limit (counts) multiplied by an appropriate conversion factor to give units consistent with a site guideline, such as Bqlkg.

The following discussion provides an overview of the derivation contained in the well known publication by Currie (Currie 1968) followed by a description of how the resulting formulae should be used. Publications by Cunrie (Currie 1968, NRC 1984) and Altshuler and Pastemack (Altshuler and Pastemak 1963) provide details of the derivations involved.

The two parameters of interest for a detector system with a background response greater than zero are:

L4 - the net response level, in counts, at which the detector output can be considered "above background" LD - the net response level, in counts, that can be expected to be seen with a detector with a fixed level of certainty Assuming that a system has a background response and that random uncertainties and systematic uncertainties are accounted for separately, these parameters can be calculated using Poisson statistics. For these calculations, two types of decision errors should be considered. A Type I error (or "false positive") occurs when a detector response is considered to be above background when, in fact, only background radiation is present. A Type II error (or "false negative") occurs when a detector response is considered to be background when in fact radiation is present at levels above background. The probability of a Type I error is referred to as a (alpha) and is associated with Lc; the probability of a Type II error is referred to as B (beta) and is associated LD. Figure 6.2 (MARSSIM) graphically illustrates the relationship of these terms with respect to each other and to a normal background distribution.

I 011412003 A1TACHMENT 7 

3 of 5 1 0/14/2003 AllTACHMENT_7-3 of 5

Nal Scan MDC Calculation - Surface Nal Scan MDC Calculation b := 100 p := 0.5 HS d=45.72

~~~-i--,-;*;*

SR :d ii d8=

t Conv := 221

...g

"-?;.r -- -!

-:7

-5 MSoutnut : r 1 -

..f.s_...,

... o4.-As Is HS

.3

'SR --'

0 i = 4.572 Observation Interval (seconds)

(b-O i) 1*

60 MDCR; = (d-j)-i60 1

MDCR i = 49.992 MDCR surveyor:

net counts per minute MDCR i MDCR surveyor = 70.7 MDCR surveyor.

Conv C

scan MS 3

net counts per minute MDER =-03

-...s j

jiR/h MDC s7q::- T-14 46-1 pCi/cm2 7.......-..I MDC C 222 - 3211.1 d7m/OOcm2 sDc anpm1

  • C0:2

,.~

S 7

i-A0/AC14/2T003 of 10/14/2003 4 of 5

Nal Scan MDC Calculation - Surface Nal Scan MDC Calculation

. 1

-p 0.5 HS d :5.72 b := 300 p :.='0.5 HS d :- ~-45.72

,-.-5,.1 SR d

1.38 a

Cy 21 Conv := 221 sO a-,

1 r.-

MS o ut:= 2.212-10 5>

tp 7

T.t.....

~HI 0 i = 4.572 Observation Interval (seconds)

(b-o O) bi:=

C i60 MDCR i:

-bi)6 i

MDCR i = 86.589 net counts per minute MDCRi MDCR surveyor r

Al; MDCR

= 122.455 A YO

..... 1.

MDCR surveyor.

MDERC Cony net counts per minute MDER '-0.554 1 fLR/h MDC scan :=

MDER M3 MS output 1 1 0

=25 pCi/cm2 sfa:. _,..._.,.

1 MDC

-222-'5561

i. dpm/00 cm2 scan 1-1, g...4 1 0/-41 2 0 07 4 of 5

-ATTACH MENTL_-_J-R-10/1412003 4 of 5

Nal Scan MDC Calculation - Surface where:

b = background in counts per minute b= background counts in observation interval Corn = Nal manufacturers or calibration information reported response to energy of contaminant (cpm/uR/h) d = index of sensitivity (Table 6.5 MARSSIM), 1.38 = 95% of correct detections, 60%false positives HSd = hot spot diameter (in centimeters)

MDCSC~ = Minimum Detectable Concentrationfor scanning (pCi/cm2)

MDCRj = Minimum Detectable Count Rate (ncpm)

MDCRsytr,, = MDCR, corrected by human performancefactor (ncpm)

MDER = Minimum Detectable Exposure Rate (uR/h)

MSO.,F, = MicroShield output exposure rate for I pCi/cm2 of contaminant (mMA)

O0 = obervation Interval (seconds) p = human performance factor SR = scan rate in centimeters per second 10/13/2003 ATTACHMENT 7

  • 5 of 5

Williamsbura Steel Backaround Measurements SR-48

{1nzl~~

~

r;Inwo same ueo ou omlaes MoOe WlQMtOf

--- I 0

bKUNU 11714/2002 641 1

6.548*03 I

Souce Check 111142002 954 S

1.70E.05 1la0 SCL inlla BacgrOuna 13 S~CFJ/P.)-

I 35 s0 SCL Source a

Shielded Unshield~d NFT enm 2

STEELAIS 11/14QO02 10:32 1

213E802 60 SCL Shielded 3

STEELA1U 111442002 10:33 1

2.04E.02 60 SCL Unshielded 1

4 STEELA2S 11/14420 10:37 1

203E802 60 SCL Shielded 5

STEELA2U 111442002 10:38 1

2.25E*02 60 SCL Unshielded 13 8

STEELA3S 11114402 10:39 1

1.85E.02 60 SCL Shielded 7

STEELA3U 1111442002 10:40 1

209E.02 60 SCL Unshielded tt 8

STEELA4S 11114422 10:42 1

2.03E-02 60 SCL Shielded 9

STEELA4U 11114422 10:43 1

1.67E.02 60 SCL Unshieldedt 10 STEELASS 111442002 10:44 1

1.55E-02 60 SCL Shielded 11 STEELA5U 11114=002 1045 1

226E-02 60 SCL Unshe 1p 12 STEELA6S 111442002 1046 1

1.92E-02 60 SCL Shielded 13 STEELABU 11114i2002 1047 1

1.95E-02 60 SCL Unshielded PI 14 STEELA7S 1111442002 1048 1

198E-02 60 SCL Shielded 15 STEELA7U 11/1442002 10:50 1

2.01E+02 60 SCL Unshielded C

16 STEELA8S 111142002 10:51 1

215E-02 60 SCL Shielded 17 STEELA8U 1t/1412002 10:52 1

2.38E.02 60 SCL Unshielded 13 18 STEELA9S 11114200 10:53 1

2.OOE+02 60 SCL Shielded 19 STEELA9U 11114/2002 10.54 1

1.92E.02 60 SCL Unshielded PI 20 STEELA10S 11114420 10.58 1

1.83E 02 60 SCL Shielded 21 STEELA1OU 11n4o2002 10:57 1

2.25E+02 6o SCL Unshielded 22 STEELA11S 1111442002 10:58 1.95E-02 60SC.

hile 23 STEELAIIU 1111420 10:59 1

2.15E+02 60 SCL Unshielded 1

24 STEELA12S 111144202 11:00 1

1.77E+02 60 SCL Shielded 25 STEELA12U 1111442 11:01 1

2.34E+02 60 SCL Unshielded e

1 26 STEELA13S 11114120 11:03 1

2z02E002 60 SCL.

Shielded 27 STEELA13U 11114420 11:05 1

2.18E+02 60 SCL Unshielded 1

28 STEELA14S 111144202 11:06 1

189E+02 60 SCL Shielded 29 STEELA14U 111142002 11:07 1

1.99sE02 60 SCL Unshielded 1C 30 STEELA1SS 111442002 11:08 1

216E802 60 SCL Shielded 31 STEELA15U 1111442002 11:09 1

2.15E+02 60 SCL Unshielded PI 32 STEELA16S 1111442oo2 11:10 1

1.88E+02 60 SCL Shielded 33 STEELA1EU 11442002 11:11 1

2050E02 60 SCL Unishielded PI 34 STEELA17S 111142002 11:13 1

212E802 60 SCL Shielded 35 STEELA17U 111142002 11:14 1

211tE002 60 SCL Unshielded P

36 STEELAIBS 11114420 11:15 1

2.OOE-02 60 SCL Shielded 37 STEELA1SU 11I4N402 11:16 1

1.93E-02 60 SCL Unshielded A

38 STEELA19S 11442002 11:17 1

1.84E-02 60 SCL Shielded 39 STEELA19U 11114420 11:18 1

2.090.02 60 SCL Unshielded 1

40 STEELA20S 111t4200 11:19 1

1.94E802 60 SCL Shielded 41 STEELA20U 11114420 11:20 1

2.30E-02 6o SCL Unshielded 42 STEELA21S 11/14420 11:22 1

2.10E 02 60 SCL Shielded 43 STEELA21U 11114/200 1123 1

1.93E.02 60 SCL Unshielded 44 STEELA22S 11/1442002 1124 1

2.05E-02 60 SCL Shielded 45 STEELA22U 11144202 1125 1

1t91E+02 60 SCL Unshielded PI 46 STEELA23S 1111442002 112e 1

1.77E+02 60 SCL Shielded 47 STEELA23U 11114420 11327 1

1250E+02 60 SCL Unmshielded p 46 STEELA24S 11/14420 11428 1

2.38E+02 60 SCL Shielded 49 STEELA24U 11114422 13:30 1

2.44E+02 60 SCL Unshielded 1

so STEELQ tS 11/142002 11733 1

213E-02 60 SCL Shielded 51 STEELQCttU 11/1442002 13:34 1

710E+02 60 SCL Unshielded PI 52 STEELBC19S 11/1442oo2 1t3:

1 1.32E-02 60 SCL Shielded 53 STEELBC19U 11/14420 13:37 1

12.0E802 60 SCL Unshielded PI 68t STEEL8tS 11/1442OO2 13:09 1

2.22E-02 60 SCL Shielded 59 STEELBtU 11142002 13:10 1

1.94E-02 60 SCL Unshielded 60 STEELB2S 11/1442002 13:12 1

1.18E-02 60 SCL Shielded 71 STEEL82U 11114/2oo2 13:13 1

2.10E-02 60 SCL Unshielded 72 STEELB83S 11/14,2002 13:14 1

2103E02 60 SCL Shielded 73 STEEL83U 11114r22 13:15 1

215E*02 60 SCL Unshieled 74 STEEL8t4S 11/14/2002 13:27 1

2.03E802 60 SCL Shielded 75 STEELB4U 111144202 13:18 1

1.7.E-02 60 SCL Unshielded 76 STEELIS 11/14r42002 1319 1

2.32E-02 60 SCL Shielded 77 STEELB1OU 11/142002 1320 1

2.03E+02 60 SCL Unshielded 68 STEELB5S r1114o2=

13:22 1

2.22E+02 eo SCL Shieklded 69 STEEL96U III 1r4foo=

13:23 1

2.22E-02 eo SCL Unseled P

70 STEELE17S 11114/2002 13:24 1

2.21 E-02 60 SCL Shieldett 7 1 STEELB7U 11114nw 13:25 1

2.1 E+02 eo SCL Unshiettded 72 STEELOBSS 11/144002 13-26 1

181E802 60 SCL Shielded 73 STEELB1su 1111142002 13:24 1

213E+02 6o SCL Unshielded 1

74 STEEL9Ss 11/112w2 13:29 1

1jDOE-2 eo SCL Shielsed 75 STEELB9U 11/11V2w2 13:30 1

2.17E+02 so SCL Unshielded 78 STEELB105 l1111C202 1341 1

Z.4$E-02 eo SCL Shietlxed T7 STEELB10U 11114n202 13 42 1

2.32E+02 eo SCL Unthbieded 78 STEELQCBSS 11114n2002 13:44

.1 1.B1E-M2 60 SCL Shielded 0

79 STEELOC85U I1t4no2=

13:45 1

Z.13E-02 eo SCL Unshbieded p

72.~13E.0:

2.03E802 1.30E-01 I.lOE+01 7.10E+01 2 03E-02 I

1.32E.02 1 96E-02

? I 300E.01 1.57E-02 1

4 30E801 1 80E.02 I

1 50E-01 1 89E.02 2 I 2.50E-01 1.70E802 I

1.80E+01 I

1.58E+02 I

4.20E+01 I

1.OOE+06 2.10E802 2

l 5.20E01 l

l 1.63E802 I

1.40E-01 I

1.75E+02 I

3.800E01 -

1.59E+02 I

6.60E01 1.76E+02 I

2.70E801 1.73E+02 I

5.90E*01-1.83E802 I

3.80E801 2.18E802 1.97E802 I

4.80E801 Minimumt 1.55 042 1.325402

.3.70E001 Maxmum.m 2450+02 21 5002 7.1OE+01 Mean l

2O00E02 1.76E+02 2.39E+01

Sloma, 1.81E+01 I

.77E+01 i

2.65E01 ATTACHMENT L.-I

Intake Tunnel Concrete Background Measurements - Nal Instrument 126188 RR9291 Time Detector Counts Count Time (sec) Mode Designator FSS-337 1

INTAK T 1 1012/2003 13:23 4

5.70E+01 60 SCL

@ 4'"

_ _ 5.70E+01 2

INTAK E 1 101212003 13:24 4

1.70E+02 60 SCL

@ 4"'

1.70E+02 3

INTAK N 1 10/2/2003 13:26 4

8.60E+01 60 SCL

@ 4"'

8.60E+01 4

INTAKXN 1 101212003 13:27 4

6.30E+01 60 SCL

@4"'

y 6.30E+01 5

INTAK S 1 10/2/2003 13:29 4

1.04E+02 60 SCL

@ 4"'

y 1.04E+02 6

INTAK W 1 101212003 13:30 4

1.08E+02 60 SCL

@4"'

1.08E+02 7

INTAK XS 1 101212003 13:31 4

8.40E+01 60 SCL

@ 4" 1 8.40E+01 Minimum 5.70E+01 Maximum 1.70E+O2 Mean 9.60E+01 Siqma > 3.77E+01 ATTACHMENT 4

I

SSGS Footprint Concrete Variability Measurements Instrument 126179 KL3171 Time Detector Counts CountTime (sec) Mode Designator FSS-338 BHB 2

3 SSGS 1S 10/2/2003 14:18 SSGS1U 1012/2003 14:19 1

1 1.94E+02 3.09E+02 60 60 SCL SCL Shi Unsl ielded hielded ff 4

SSGS2S 10122003 14:21 1

2.29+02 60 SCL Shielded 5

SSGS2U 1012/2003 14:22 1

5.23E+02 60 SCL Unshielded p 6

SSGS 3S 10/212003 14:23 1

2.13E+02 60 SCL Shielded 7

SSGS 3U 10/2/2003 14:25 1

3.34E+02 60 SCL Unshielded p 8

SSGS 4S 1012/2003 14:26 1

2.37E+02 60 SCL Shielded 9

SSGS4U 10/2/2003 14:28 1

4.64E+02 60 SCL Unshielded _

10 SSGS 58 10122003 14:30 1

1.81 E+02 60 SCL Shielded 11 SSGS 5U 10/2/2003 14:31 1

3.13E+02 60 SCL Unshielded p 12 SSGS6S 10/2/2003 14:33 1

1.87E+02 60 SCL Shielded 13 SSGS6U 10/212003 14:34 1

4.06E+02 60 SCL Unshielded 14 SSGSC7S 102003 14:36 1

2.44E+02 60 SOL Shielded 15 SSGS 7U 101212003 14:37 1

3.68E+02 60 SCL Unshielded 16 SSGS 8S 10/2/2003 14:39 1

1.71 E+02 60 SCL Shielded 17 SSGS8U 101212003 14:40 1

3.22E+02 60 SCL Unshielded 18 SSGS 9S 1012/2003 14:42 1

2.26E+02 60 SCL Shielded 19 SSGS 9U 1012/2003 14:43 1

3.124+02 60 SCL Unshielded 20 SSGS 10S 101212003 14:44 1

2.16E+02 60 SCL Shielded 21 SSGS IOU 10/2/2003 14:46 1

3.21E+02 60 SCL Unshielded 22 SSGS 11S 10/212003 14:48 1

1.28E+02 60 SCL Shielded 23 SSGS IIU 101212003 14:50 1

1.99E+02 60 SCL Unshielded 24 SSGS 12S 10/212003 14:52 1

1.99E+02 60 SCL Shielded 25 SSGS 12U 101212003 14:54 1

3.26E+02 60 SCL Unshielded 26 SSGS 13S 101212003 14:55 1

2.53E+02 60 SCL Shielded 27 SSGS 13U 10/2/2003 14:56 1

3.67E+02 60 SCL Unshielded 28 SSGS 14S 10/212003 14:58 1

2.36E+02 60 SCL Shielded 29 SSGS 14U 1012003 14:59 1

3.862+02 60 SCL Unshielded 30 SSGS 15S 10/2003 15:01 1

2.21E+02 60 SCL Shielded 31 SSGS 15U 101212003 15:02 1

3.55E+02 60 SCL Unshielded 32 SSGS 16S 10/212003 15:04 1

1.89E+02 60 SCL Shielded 33 SSGS 16U 101212003 15:05 1

2.48E+02 60 SCL Unshielded 34 SSGS 17S 10/212003 15:07 1

2.38E+02 60 SCL Shielded 35 SSGS 17U 10/2/2003 15:08 1

3.69E+02 60 SCL Unshielded 36 SSGS 18S 10/212003 15:10 1

1.93E+02 60 SCL Shielded 37 SSGS 18U 101212003 15:11 1

3.52E+02 60 SCL Unshielded 38 SSGS 19S 10/2/2003 15:12 1

2.37E+02 60 SCL Shielded 39 SSGS 19U 101212003 15:14 1

3.13E+02 60 SCL Unshielded 40 SSGS 20S 10/212003 15:16 1

2.49E+02 60 SCL Shielded 41 SSGS 20U 10/212003 15:17 1

3.40E+02 60 SCL Unshielded 42 SSGS 21S 10/212003 15:19 1

2.17E+02 60 SCL Shielded 43 SSGS21U 1012/2003 15:20 1

3.26E+02 60 SCL Unshielded 44 SSGS22S 10/212003 15:21 1

2.21 E+02 60 SCL Shielded 45 SSGS 22U 1012/2003 15:23 1

2.75E+02 60 SCL Unshielded 46 SSGS 23S 10/212003 15:24 1

2.07E+02 60 SCL Shielded 47 SSGS 23U 101212003 15:26 1

2.93E+02 60 SCL Unshielded 48 SSGS 24S 10/212003 15:27 1

2.16E+02 60 SCL Shielded 49 SSGS24U 1012/2003 15:29 1

3.12E+02 60 SCL Unshielded I Minimun Maximun Mear Siqmc 1.94E+02 l 3

E 3.09E+02 3 2.292+02 5.23E+02 2.13E+02ff I 3.34E+02 2.37E+021 I 4.64E+02 1.81 E+021 3 3.13E+02 1.87E+021 4.06E+02 2.44E+02 3.68E+02 1.71 E+02 3.22E+02 2.26E+02 3.12E+02 2.16E+02 3.21 E+02 1.28E+02 1.99E+02 1.99E+02 3.26E+02 2.53E+02 3.67E+02 2.36E+02 3.86E+02 2.21 E+021 3.55E+02 1.89E+02 2.48E+02 2.38E+02 3.69E+02 1.93E+021 3.52E+02 2.37E+02 3.13E+02 2.49E+02 3.40E+02 2.17E+02 I 3.26E+02 2.21 E+02 2.75E+02 2.07E+02 2.93E+02 2.16E+02 3.12E+02 Shielded Unshielded m

1.28E+021 1.99E+02 m 2.53E+02 5.23E+02 n

2.13E+02 3.39E+02 ra 2.87E+01 6.52E+01 ATTACHMEN17__LO -

I -

Intake Tunnel Concrete Background Measurements - GFPC Instrument 126188 RR9291 Time Detector Counts Count Time (sec) Mode Designator FSS-337 BHB 2

INTAKE 1P 10/2/2003 13:04 1

2.46E+02 60 SCL Shielded 2.46E+02l 3

INTAK E 1U 10P/2003 13:05 1

3.37E+02 60 SCL Unshielded p 3.37E+02 4

INTAK N 1P 1012/2003 13:06 1

2.35E+02 60 SCL Shielded 2.35E+02 5

INTAK N IU 1012/2003 13:07 1

2.77E+02 60 SCL Unshielded 2.77E+02 6

INTAKXN 1P 10/2/2003 13:09 1

2.85E+02 60 SCL Shielded 2.85E+02 7

INTAK XN 1U 10/2/2003 13:10 1

4.30E+02 60 SCL Unshielded 4.30E+02 8

INTAK T IP 10/212003 13:12 1

2.49E+02 60 SCL Shielded 2.49E+02 9

INTAKT IU 10/2/2003 13:13 1

3.86E+02 60 SCL Unshielded 3.86E+02 10 INTAK S 1P 1012t2003 13:15 1

2.73E+02 60 SCL Shielded 2.73E+02 11 INTAK S 1U 10/2/2003 13:16 1

2.95E+02 60 SCL Unshielded _

2.95E+02 12 INTAK W IP 10/2/2003 13:17 1

1.98E+02 60 SCL Shielded 1.98E+02 13 INTAKW 1U 10/2/2003 13:18 1

2.90E+02 60 SCL Unshielded 2.90E+02 14 INTAKXS IP 10/2/2003 13:20 1

2.98E+02 60 SCL Shielded 2.98E+02 15 INTAKXS IU 10/2/2003 13:21 1

3.65E+02 60 SCL Unshielded B _

3.65E+02 Shielded Unshielded Minimum [ 1.98E+02 2.77E+02 Maximum >

2.98E+02 4.30E+02 Mean 2.S5E+02 3.40E+02 Slqma 3.38E+01 5.68E+01 ATTACHMENT-- I

-(-

NumberO RIG INAL Saxton Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual E900-IMP-4520.06 Title Revision No.

Survey Unit Inspection in Support of FSS Design 0

EXHIBIT I Survey Unit Inspection Check Sheet SECTION 1 - SURVEY UNIT INSPECTION DESCRIPTION Survey Unit# l 5S i4l Survey Unit Location l sP Date !'AI/o3 lTime tooo l Inspection Team Members SECTION 2 - SURVEY UNIT INSPECTION SCOPE Inspection Requirements (Check the appropriate Yes/No answer)

Yes No 7 N;A

1.

Have sufficient surveys {i.e. pcst remediation. characterization. etc ! been obtained fcr the survey unit!

2.

Do the surveys (from Question 1) demonstrate that the survey unit wilt most likelv ass the FSS;

3.

Is the physical work (i.e.. remediation & housekeeping) in or around the survey Unin complete-

4.

Have all tools non-permanent equipment. and material not needed to perform the FSS been removed?

V/

I

5.

Are the survey surfaces relatively tree of loose debris ti e. dirt. concrete dust. metal filings. etc ~

5 Are the survey surfaces relatively free of liquids ( e. water. moisture. 9it. etc i-

7.

Are Ine survey surfaces free of all paint, which has the potential to shield rac!alicng'

8.

Have the Surface Measurement Test Areas (SMTA) been established-lReter Et E-h:t 2 !or :nstructions

9.

Have the Surface Measurement Test Areas ISMTA) data been collected0 -Refer to Exribit 2 cir instructions I 1/

10. Are the survey surfaces easily accessible? (No scaffolding, high reach. etc.s needJed zo perfcrm the FSS)
11. Is lighting adequate to perform the FSSP
12. Is the area industrially safe to perform the FSS? (Evaluate potential fall S trip !azards. confined spaces. etc.)
13. Have photographs been taken showing the overall condition of the area' P"
14. Have all unsatisfactory conditions been resolved7 NOTE: If a No' answer is obtained above. the inspector should immediately c-rrec: the proDlem or initiate corrective actions through the responsible site department, as applicable. Document actions taken and/or justifications in the 'Comments section below. Attach additional sheets as necessary.

Comments.

gSrC VA ct5 C.d4 m oay 1o9 l°t-'CT.

Survey Unit Inspector (prinlsign) l f5I/ \\ t Date 1

Survey Designer (printlsign) lLO

a.

g L

Date lL' 9 6

WT4i 6-h

'2-\\

SAXTON NUCLEAR NumberORIGINAL E900-IMP-4520.06 Saxton Nuclear Experimental Corporation Facility Policy and Procedure Manual Tetle Revision No.

_Survey Unit Inspection in Support of FSS Design O

EXHIBIT I Survey Unit Inspection Check Sheet SECTION 1 - SURVEY UNIT INSPECTION DESCRIPTION Survey Unit # SK1, I SurvevUnit Lccation g

. c)ZGS Date jh'gk

§ Time.

13v Inspect:cn Team M0embers SECTION 2 - SURVEY UNIT INSPECTION SCOPE inspecticn Requirements cChieck the acprccriate Yes;Nc answer; i

Have suffic:ent surveys Ji e pCSt reme1iation ;?racen:3nc.- e' een cc:airec !cr !he sur~ev vt'

2.

Do :he itrveys ifrom Cuesticn 11 I cemcnsirtle Inai *-

e ru t,.

-CsE:

"ev e:ass the FS3-Vz C

NJ. A

.1.-i 3

Is.he.mn's;ci1 wcrk :i e reiieafaticn & rouse e-cfrn: n :r arrur.v he sur.e vidt nc'CieeP '

4, Have V lcoas non-permanent eutmCr ien! ar:-

.; 'ci nee'e o h:oFe3crr C

ceen !e'e':

5 Are !l.e suriev surfaces relative!v !ee ir 'ooe recr s 'e e

it. :crcrete.us!

ne!al filings e!Cc Are *.-e -

ies reiaevve'e free :f ru:cs : e.vaer mncis: re. C., a!-

7 Are *.-e sur.ey surfaces free cf atil caint. whnich ras :,ne cotentva: to sn:eed rac:az:cn'

9.

Have he Surface Measurement -.es: Are3s.SMTTAi ceen estacits.!eo",Peie, on E nic:t 'or.5strLctcf(S¶

9.

Have !he Surface Measurement Test Areas S?,MTA) JatL teen ::le-ea e

  • Per lo E.xracit 2 for nS:r-uc n.cn1
10. Are 'he survey surfaces easily accessite ' i No scaff cicin. hrgn ge3cn.. etc *s.eetee to perfcrm the FSS-
11. Is ligntrg acecuate to perform the FSST
12. Is the area industrially safe to perfcrrn the FSS, oEvaiuate :ctenriai 'ail a roo nazarcs. -:cnfinea scaces. etc..
13. Have photcgrachs been taken snowing the overall cnrcition of the are37
14. Have ail unsatisfactory conditions been rescivea 7 NOTE: If a 'No' answer is obtained above. 'he inscector should immediateiy crrrec: the proolem or initiate correc::ve achons thrcugn the responsible site department, as apolicaole. Document act:cns tahen andtor justifications in the 'Ccmments sec icr. ceiow Attach aoditicnat sheets as necessary.

Comments:

11-0641 40 l

f

,!S9 Survey Unit Inspector (printtsicn)

-z L'-"_

Date IO L7tZ o3 Survey Designer (print/sign)

T4 l Date I (02Z/9 k.10f

 -T-W 12 - -

6

.NuOR~IGINAkL Saxton Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual E900-IMP-4520.06 Title Revision No.

Survey Unit Inspection in Support of FSS Design O

EXHIBIT 1 Survey Unit Inspection Check Sheet r

SECTION 1

- SURVEY UNIT INSPECTION DESCRIPTION Survev Unit l S5 IkA 5

! SurveyUnitLccation.

rLM'os s'

5 Date Time Inspection Team M'vlembers SECTION 2 - SURVEY UNIT INSPECTION SCOPE Inspecticn Requirements (Check t;he apprccprate Yes;Nc ans-wer

'y as NC IA, I

Have sutfic:ent surveys ;i e. Ccst rerreliation :rarac en!za3cn e!S ceen *c an r 'te surveyv J.t.I

2.

Do :he surveys (from Cuesnicn iI aeInmonstrate *nat tIe suirrev unit wijl ncs. lke v n.ass 'te -SS 2

Is hte :tvsical work.1 e rerneciatcrn.1 nous p

Cer

ir.:r arcur-. nle s;:t.e',
nit ^-nioie!p
4.

Have all :cols non-oermanenh ecuicrne't -ir.:

. 1ct r'eedea oc ce'crm he rSS ceen -e!rc'e.

/

5 Are tne survev surfaces relativeiv 'ree af ecrrs i e unt. c.:rncrete eus: nep!ai tilrgs -'!c Are :t.e suriey surfaces relarively free ft iouics i e.vrmer mcisture cii e

~.---.-

Are tr e sur.ey surfaces free of ail aint. wnich naS 'he octenltai to srue!C rac*-:rr

3.

Have the Surface Measurement 7est Areas.SsITA) been estaclist.ec -Refe! *o E.nicit: or :nsur,,c:;cns

9.

Have the Surface Measurement Test Areas tS.',ITAi cala -een c-llec:ed7 Peie-to E.xricit for ns:ruc::cns

10. Are the survey surfaces easily accessible' iNo scarfoloing. hign re3cn. ec *s e.eeed to :erfcrm !he -SS; V

.1. Is lignting acequate to perform the FSS^

12. Is the area industrially safe to perfcrmr the FSS' 'Evaluate pctential fail & trio nazarcs. :nlfinea soaces. ecc.:
13. Have photcgraohs been taken snowing the overall condition of the area 7
14. Have all unsatisfactory conditions ceen resclveo-NOTE: If a No answer is obtained above. 'he *nscec:cr shculd immediately correc: the prcolem or initiate corrective actlons thrcugh the responsible site department, as applicable. Document acticns taken and/or justifications in the Oomments secticn below Attach additional sheets as necessary.

Comments:

Q, Survey Unit Inspector (print/sign) l

\\4-N Date Ito12.-1 Survey Designer(print/sign) l ro" o

ti4 l Date Ito0/?-?

L -)

oil GWIM-OR}

Number Saxton Nuclear Experimental Corporation A qiON NUCLEAR Facility Policy and Procedure Manual E900-IMP-4520.06 e>,...

Revision No.

Su Fe Unit Inspection in Support of FSS Design 0

EXHIBIT I Survey Unit Inspection Check Sheet

.;.... SECTION 1 - SURVEY UNIT INSPECTION DESCRIPTION.

'Survey Unit#

i Survey Unit Location IsLs A

Date.

' Jl§ l Time 151 Inspection Team Members SECTION 2 - SURVEY UNIT INSPECTION SCOPE.

Inspection Requirements (Check the appropriate Yes/No answer.)

Yes No N/A

1.

Have sufficient surveys (i.e.. post remediation, characterization. etc.) been obtained for the survey unit?

2.

Do the surveys (from Question 1) demonstrate that the survey unit will most likely pass the FSS?

7

=

=

3.

Is the physical work (i.e.. remediation & housekeeping) in or around the survey unit complete?

4.

Have all tools, non-permanent equipment, and material not needed to perform the FSS been removed?

I/

5. Are the survey surfaces relatively free of loose debris (i.e., dirt, concrete dust. metal filings. etc.)?
6.

Are the survey surfaces relatively free of liquids (i.e.. water, moisture, oil, etc.)?

V

7.

Are the survey surfaces free of all paint, which has the potential to shield radiation?

S.

Have the Surface Measurement Test Areas (SMTA) been established? (Refer to Exhibit 2 for instructions.)

v

9.

Have the Surface Measurement Test Areas (SMTA) data been collected? (Refer to Exhibit 2 for instructions.)

10. Are the survey surfaces easily accessible? (No scaffolding, high reach. etc. is needed to perform the FSS)
11. Is lighting adequate to perform the FSS?
12. Is the area industrially safe to perform the FSS? (Evaluate potential fall & trip hazards. confined spaces. etc.)
13. Have photographs been taken showing the overall condition of the area?
14. Have all unsatisfactory conditions been resolved?

NOTE: If a No answer is obtained above. the inspector should immediately correct the problem or initiate corrective actions through the responsible site department, as applicable. Document actions taken and/or justifications in the Comments section below. Attach additional sheets as necessary.

Comments:

Survey Unitnspector (prinsign) l Date lo ln Survey Designer (print/sign) I --B.

/

h Date l 01/z/)

6 12 -'-

L 7 NUCLR Saxton Nuclear Exper Or N NUCLEAR Facility Policy and F 7Z; !

& id 416 Number E900-IMP-4520.06 rimental Corporation Procedure Manual I

,....N~

I.

'T Revision No.

lSurveyUnit Inspection in Support of FSS Design 0

EXHIBIT I Survey Unit Inspection Check Sheet t Survey Unit#

5Y 5 L4l Survey Unit Location i J

FLwawL o 2-,ss Cc5

.Date

/Zi l Time lb ISl Inspection Team Members l

'0'

/

1H.lNSPECIf 99M IYA!i NO 44 

j I,

Inspection Requirements (Check the appropriate Yes/No answer.)

Yes No N/A

1.

Have sufficient surveys (i.e., post remediation, characterization, etc.) been obtained for the survey unit?

2.

Do the surveys (from Question 1) demonstrate that the survey unit will most likely pass the FSS?

3.

Is the physical work (I.e., remediation & housekeeping) in or around the survey unit complete?

4.

Have all tools, non-permanent equipment, and material not needed to perform the FSS been removed?

i/

5.

Are the survey surfaces relatively.free of loose debris (i.e., dirt, concrete dust, metal filings, etc.)?

7

6.

Are the survey surfaces relatively free of liquids (i.e.. water, moisture, oil, etc.)?

V/

7.

Are the survey surfaces free of all paint, which has the potential to shield radiation?

8.

Have the Surface Measurement Test Areas (SMTA) been established? (Refer to Exhibit 2 for Instructions.)

V/

9.

Have the Surface Measurement Test Areas (SMTA) data been collected? (Refer to Exhibit 2 for instructions.)

v

'10. -Are the survey surfaces easily accessible? (No scaffolding, high reach, etc. Is needed to perform the FSS)

II. Is lighting adequate to perform the FSS?

1i2. Is the area industrially safe to perform the FSS? (Evaluate potential fall & trip hazards, confined spaces, etc.)

V

13. Have photographs been taken showing the overall condition of the area?
14. Have all unsatisfactory conditions been resolved?

NOTE: If a 'No answer is obtained above, the inspector should Immediately correct the problem or Initiate corrective actions through the responsible site department, as applicable. Document actions taken and/or justifications In the Comments section below. Attach additIonal sheets as necessary.

Comments:

Survey Unit Inspector (print/sign) l Z

Date 1/2/3 Survey Designer(print/sign) I 3.A 3

?65 1

te IDl21 I 3 P T -T'j-C, i'l (" -T7 1 Z - S-6