ML052090300

Appendix a Survey Design.

ML052090300
Person / Time
Site:	Saxton File:GPU Nuclear icon.png
Issue date:	07/31/2005
From:	GPU Nuclear
To:	Office of Nuclear Reactor Regulation
References
Download: ML052090300 (65)

Text

Appendix A Survey Design

SNEC CALCULATION COVER SHEET CALCULATION DESCRIPTION Calculation Number Revision Number Effective Date Page Number ESOO-03-030 0 17 of 6 Subject Seal Chambers - Survey Plan Question 1 - Is this calculation defined as 'in QA Scope? Refer to definition 3.5. Yes 1 No El Question 2- Is this calculation defined as a Design Calculation"? Refer to definitions 3.2 and 3.3. Yes 1 No El Question 3 - Does the calculation have the potential to affect an SSC as described in the USAR? Yes El No 3 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/ - 7 l .- Date Technical Reviewer P. Donnachie! K Date /// 3 Additional Review A. Paynterl J s\LJltl I xV Date " 117 /3 Additional Review Date SNEC Management Approval Date

E v SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-030 0 Page 2 of .. /

Subject Seal Chambers - Survey Plan 1.0 PURPOSE 1.1 The purpose of this calculation is to develop survey design for three (3) Seal Chambers.

These areas are Class I survey units located in the Discharge Tunnel. They are shown in Attachment 1-1 through 1-2, and are listed below. Attachment 1-3 shows a general diagram of one of four steel downcomers located in Seal Chamber 3.

Impacted Survey Units Location Material Type Attachment SS8-1 Seal Chamber I - Discharge Tunnel Concrete/Steel 1-1 SS8-2 Seal Chamber 2 - Discharge Tunnel Concrete/Steel 1-1 SS8-3 Seal Chamber 3 - Discharge Tunnel Concrete/Steel 1-2 Part of SS8-3 Seal Chamber 3 - Downcomer Steel 1-3 1.2 The estimated area (in square meters) for these survey units are as shown in the following table. Seal Chamber 3 includes the external surface of the four (4)downcomers.

Seal Chamber I Seal Chamber 2 Seal Chamber 3 73.1 70.9 109.4 2.0

SUMMARY

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

2.1 Step I - GFPC Measurements for Concrete and Clean or Liqhtly Corroded Steel Surfaces 2.1.1 A gas flow proportional counter (GFPC) shall be used in the beta detection mode for this scan survey work (Ludlum 2350-1 with a 43-68B probe).

2.1.2 The minimum required number of static survey points for each Seal Chamber is 8 (see Attachment 1-4 to 1-7 for locations of random start systematic grid survey points). However, because the down comers in Seal Chamber 3 are separate components, an additional 8 points will be established for these four components.

2.1.3 Scanning criteria using the GFPC for these areas and hardware, are identified below:

2.1.3.1 The GFPC detector must be in contact with the surface when scanning except in areas where this is not physically possible.

2.1.3.2 Areas where gouges exceed 2" in depth should not be surveyed using the GFPC (see Section 2.2 for surveys of gouges > 2" in depth).

2.1.3.3 Steel components/hardware that exhibit severely corroded surfaces should not be scanned using the GFPC. See Section 2.2 if this is the case.

2.1.3.4 The GA DCGLw is 6,407 dpm/100 cm2 or 646 cpm above background. This is the static measurement criteria.

2.1.3.5 The action level during first phase scanning is 300 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.

-, .'SNEC CALCULATION SHEET. C  :- -

Calculation Number Revision Number Page Number E900-03-030 l 0 Page 3 of___

Subject Seal Chambers - Survey Plan 2.1.3.6 Areas greater than the DCGLw (646 ncpm) must be identified, bounded and documented to include an area estimate.

2.1.3.7 Other instruments of the type specified in 2.1.1 above may be used, but all instruments must demonstrate an efficiency at or above 25.4% (see Attachment 2-1).

2.1.4 Any location or equipment that cannot be adequately surveyed with the GFPC as described in 2.1.2 above, should be identified for Nal scanning IAW Section 2.2.

NOTE: Scan MDC values for the GFPC instrument are listed in Section 4.15, and have been shown to be adequate for this survey work.

2.2 Step 2 - Na! Scannina of Extremely Corroded Steel or Rough Concrete Surfaces 2.2.1 The purpose of Nal scanning is to locate elevated measurement locations and mark them for sampling. The following criteria apply:

2.2.1.1 Volumetric DCGLw values for concrete is 4.78 PCi/q Cs-137 (administrative limit).

2.2.1.2 The scan speed is set at 5 cm/second when scanning with a 2" by 2" Nal detector while moving side to side in a serpentine pattern over a 12" diameter area, within 2" from the surface. The stand-off distance (2") should be monitored frequently during the scanning process.

2.2.1.3 The action level is 200 gross cpm. The location should be clearly marked for sampling when this level is reached or exceeded. These areas shall be identified, bounded and documented.

2.2.2 The conversion factor for the Nal used in cpm/mR/h, shall not be less than 176,080 cpm/mmRh (see Attachment 3-1 and 3-2) for a typical Nal instrument calibration report).

2.3 Step 3 - Static Measurements Using the Na! Detector 2.3.1 These measurements are to be performed using a fixed geometry of 2" above concrete surfaces at the locations shown on Attachment 1-4 to 1-6. These locations are the same locations developed for GFPC static measurements. Downcomer static measurement locationsshall be omitted.

2.3.2 The detection system shall be a 2" by 2" Nal detector of the type previously used in Section 2.2 above, or may be replaced with a multi-channel analyzer system used IAW Reference 3.1.

2.3.3 The instrument(s) shall be operated in the integral (scalar) mode to allow application of counting statistics to the results.

2.3.3.1 Count times for static Nal measurements shall initially be 5 minutes in duration but may be adjusted IAW the need to attain a desired MDC.

2.3.3.2 If a multi-channel analyzer system is used lAW Reference 3.1, data shall be recorded on copies of Attachment 4-1 (or equivalent).

2.3.5 The decision error rates for Nal static points is assumed the same as those developed for static GFPC measurements i.e., 0.05 for the a value and 0.1 for the j value.

r_ SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-030 0 Page 4 of 69 Subject Seal Chambers - Survey Plan 2.3.6 If remediation is performed as a result of this survey work, this survey design must be revised or re-written entirely.

2.4 Step 4 - Sampling of Concrete and Steel Surfaces 2.4.1 Sample concrete at any location above the action level cited is Section 2.1 (Step 1) or Section 2.2 (Step 2). 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-137 (a 4" diameter area by 1" deep =

-200 cc).

2.4.2 For steel surfaces above the action level for either detection system (200 gross cpm Nal or 300 ncpm GFPC), scrape the surface to collect a sample for gamma scanning by removing as much material as possible in 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).

2.4.3 In general, samples shall be collected at all locations where measurements indicate elevated count rates, or where measurement capability is deemed inadequate due to poor geometry.

2.4.4 One sample of concrete will be collected at the highest measured location in each Seal Chamber as determined by Nal static measurements (Section 2.3).

3.0 REFERENCES

3.1 SNEC procedure E900-OPS-4524.43, "Operation of the Portable Gamma Spectroscopy System".

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

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

3.4 GPU Nuclear, SNEC Facility, SSGS Footprint, Drawing, SNECRM-040, Sheet 1 & 2.

3.5 Plan SNEC Facility License Termination Plan.

3.6 SNEC Calculation No. E900-03-029, Balance of SSGS Footprint 2 - Survey Plan.

3.7 SNEC Calculation No. E900-03-027, Balance of SSGS Footprint - Survey Plan.

3.8 SNEC Calculation No. E900-03-025, SSGS Area Trench & Sump Survey Design.

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

3.10 SNEC Procedure E900-IMP-4500.59, "Final Site Survey Planning and DQA".

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

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

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

Een_ SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-030 0 Page 5 of 6?'

Subject Seal Chambers - Survey Plan 3.14 NUREG-1575, 'Multi-Agency Radiation Survey and Site Investigation Manual", August, 2000.

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

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

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

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

4.0 ASSUMPTIONS AND BASIC DATA 4.1 Remediation History Remediation of the Seal Chambers began with removal of ground water in these semi-isolated structures. Gross decontamination followed to include the removal of contaminated hardware and piping that passed into and through these chambers. One pipe originating in the SNEC Nuclear facility, terminated in Seal Chamber 1. This is thought to be the main source of contamination entering the Discharge Tunnel. Of interest, is the fact that this pipe did not significantly contaminate Seal Chamber 1 which contained the least amount of radiological contamination of the three chambers. Instead, contaminated water and steam from the SSGS Coal Fired Steam plant passing into and through Seal Chamber 3 appears to have had a more significant impact with regard to contaminating the Seal Chamber 3 area. Seal Chamber 2 was also contaminated, but not at the level exhibited by Seal Chamber 3, which required a larger concrete removal effort. Because these chambers are below grade level, surface water in-leakage was a problem and some patching of cracked concrete was necessary to prepare these areas for final status survey work.

Surface cleaning of these areas was performed by removing a thickness of concrete in affected areas. Core bores were taken to determine the depth of the contamination and to estimate remediation effectiveness during and after this process. Remaining piping systems were sampled and gamma scanned to determine the existing concentrations. Obstructions were cut off and concrete surfaces were scraped free of scale when necessary.

Remediation efforts included combinations of the following cleaning techniques:

. scabbling

• grinding and use of an oxy/acetylene torch to remove metal obstructions and pipe

• surface scraping

• water flush 4.2 Cs-137 accounts for the majority of the total activity in the modified sample result (see Attachment 5-1 and 5-2).

• The SNEC modified sample is greater than 96% Cs-137. The next most prevalent radionuclide is Ni-63 (2.6%).

• Cs-137 therefore, 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 3.2). The SNEC facility uses only the lowest reported GFPC efficiency for any of the instruments available for the survey work as input to the

M_ SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-030 0 Page 6 of 6 /

Subject Seal Chambers - Survey Plan survey design process. Attachment 2-1, indicates an instrument efficiency of 0.509. The ISO value of 0.5 is used as the source efficiency. A Ludlum 2350 is used to determine this value (instrument S/N 95352 - probe S/N is 94818).

NOTE Other GFPC instruments may be used during the FSS but they must demonstrate an instrument efficiency at or above 0.509.

4.3 An GFPC detector stand-off distance of 2" is assumed to compensate for rough surfaces in the SSGS area. This factor corrects the overall efficiency by a factor of 0.33 (Reference 3.3), as shown on Attachment 6-1.

4.4 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 6,407 dpm/100 cm2 x (126 cm physical probe area/I 00 cm2) = 8,073 x (0.964 disintegration of Cs-1 37/ disintegration in mix) x s,(0.478) x c, (0.5) x 0.33 (distance factor) which yields -648 net cpm above background (Compass calculates 646 ncpm as the gross beta DCGLw). The 0.08 count per disintegration counting efficiency considers only the Cs-137 contaminant present in the sample material matrix, and is calculated by: E; (0.509) x es (0.5) x 0.964 disintegration of Cs-137/disintegration in mix x 0.33 (efficiency loss factor due to distance from surface) =

0.08 cts/disintegration.

4.5 Surface defects (gouges, cracks, etc.), are present in these survey units, but a portion of the surface area is relatively smooth. Thus the average concentration of the source term will be overestimated by using a distance correction factor of 0.33 for all areas within these survey units (GFPC only).

4.6 Inaccessible areas or corroded steel surfaces, or any area where a 43-68 beta probe can not be used, will be scanned using a 2" x 2" Nal detector. These detectors are set-up and calibrated with a Cs-1 37 window setting typical to that described within Attachment 3-1 and 3-2, with a conversion factor equal to or greater than 176,080 cpm/mRlh.

4.7 MicroShield models of concrete slabs containing Cs-137 were developed for this survey design. Two slab models were used for scanning:

1) a 3" thick slab of concrete 12" in diameter with a density of 2/3 that of concrete to simulate an extremely rough surface (many pits and valleys), and

2) a 1" thick slab of concrete 12" in diameter to simulate a small but relatively smooth surface area.

These models assume that the majority of the activity resides in no more than the first three (3) inches of remaining concrete and that elevated areas are small in diameter. These models are based on remediation information.

4.8 The modeled concentration used was I pCilg 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 pCi/g or 1.6E-06 uCi/cc of Cs-137 for the rough model, and 2.35E-06 uCi/cc for the I" slab model. The calculated MDCscan for these two models is shown in the following table for a typical 2" by 2" Nal detector.

-i ' SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-030 0 Page 7 ofj L Subject Seal Chambers - Survey Plan Matenal/Model Estimated BKGND (ctsimin) MDCscAN (PCisg)

Concrete/1" Slab (2.35 g/cc) 100 Attachment 7-1 to 7-3 = 4.4 Concrete/39 Slab (1.6 fcc 100 Attachment 8-1 to 8-2 = 2.9 4.9 The results of the MicroShield modeling indicate that an exposure rate of approximately 7.888E-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 1.179E-04 mR/h is seen 3 inches from the surface of the thicker 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".

4.10 A third MicroShield model of a surface deposition containing Cs-137 was also developed for this survey design (see Attachment 9-1 to 9-8). For this scenario, the modeled area is assumed to be a 12" diameter disk source with a 1 pCi/cm2 Cs-137 activity evenly dispersed over the surface. The source area is assumed to be a corroded steel plate or a surface 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 1.546E-05. Then the calculated pCi/cm2 MDCscan is 22.5 pCilcm2 (4993 dpm/100 cm2) for a background count rate of 100 cpm. This model is applicable for steel or concrete surface deposits.

4.11 These survey units are below grade and are surrounded by concrete walls and therefore the original GFPC related background values have been adjusted to compensate for shielding effects of these walls. This results in a conservative estimate of background.

4.12 A GFPC variability measurement set was performed in each Seal Chamber (see Attachment 10-1 to 10-3.

4.12.1 Seal Chamber 2 exhibits the largest mean unshielded GFPC value and the largest standard deviation (244 cpm +/- 68.1). Using this value to calculate the MDCscan and static values will produce the most conservative result. The shielded reading for this data yields 140 cpm +/- 21.8, while Seal Chamber 1 exhibits the lowest mean concentration and therefore is the closest to natural background for any of these survey units. Therefore, Seal Chamber 1 data will be used to adjust the Intake Tunnel entrance background data to compensate for the below ground shielding effect. Then:

Mean Intake Tunnel entrance data = 340 cpm +/- 56.8 unshielded, and

= 255 cpm +/- 33.8 shielded Seal Chamber 1 data = 187 cpm +/- 27.7 unshielded, and

= 138 cpm +/- 26.2 shielded Difference in shielded readings = 255 - 138 = 117 cpm Mean IT entrance unshielded data corrected = 340 - 117 cpm = 223 cpm 156.8 The following correction may be used to correct the Williamsburg steel background data:

Mean Williamsburg steel data = 211 cpm +/- 17.7 unshielded, and

= 200 cpm +/- 18.1 shielded Seal Chamber 3 steel data = 158 cpm +/- 10.8 unshielded, and

e- SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-030 0 l Page 8 of 6. /

Subject Seal Chambers - Survey Plan

= 153 cpm +/- 8.6 shielded Difference in shielded readings = 200 - 153 = 47 cpm Mean Williamsburg unshielded data corrected = 211 - 47 cpm = 164 cam +/- 17.7 NOTE The steel data from Seal Chamber 3 are from data points 32 to 39 on Attachment 10-3.

Williamsburg steel data are shown on Attachment 10-4 and Intake Tunnel entrance non-impacted concrete background data is shown on Attachment 10-5.

4.13 The majority of the structural surface area in these chambers is concrete. However, the downcomers in Seal Chamber 3 are steel. If concrete measurements are used to estimate the MDCscan or static values for a steel surface, the result will be an elevated estimate of these values since steel has a lower background. When the data are analyzed using the WRS criteria, the correct background values will be subtracted.

4.14 For static Nal measurements of concrete, background values are determined by taking measurements at an on-site non-impacted structure (see Attachment 11-1). The mean non-impacted area value is similar to the current mean general area values in the Seal Chambers, and thus can be used to estimate static and scan MDC values.

4.15 The GFPC 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), 0.08 counts/disintegration and a 126 cm2 probe area. 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.

Material Value Used (ctsimin) l MDCscAN (dpm/100 cm Steel (Attachment 10-3) 158 Attachment 12-1 = 1,174 Concrete (Attachment 10-2) 244 Attachment 12-2 = 1,459 NOTE: Compass does not use the 126 cnz probe correction factor in the MDCscan equation.

4.16 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 are included (see Attachment 13-1 to 13-6).

4.17 No special area characteristics including any additional residual radioactivity (not previously noted during characterization) have been identified in these survey units.

4.18 Special measurements are included for this survey design. These special measurements are Nal based static measurements that use a Cs-137 window set around the peak energy of 0.622 MeV. The specifications for these measurements are defined in Section 2.3.

4.18.1 The Nal static measurement MDC is based on a background value determined for concrete at an on-site non-impacted concrete structure (see Attachment 11-1). The MicroShield model used assumes a cylindrical source geometry with a diameter of 12" and a depth of 1". The size of the modeled area is comparable to typical elevated areas of concrete found in the SSGS area and surrounding tunnels during previous survey work (see Attachment 9-7 and 9-8).

4.18.2 A background count rate of 100 counts/min (typical) yields a MDCstatic value of 0.713 pCi/g Cs-137. (see Attachment 9-7 and 9-8).

4.19 Compass output is presented in Attachment 14-1 to 14-10.

M_ SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-030 0 Page 9 of 'I Subject Seal Chambers - Survey Plan 4.20 The applicable SNEC site radionuclides and their associated DCGLw values are listed on Exhibit I of this calculation.

4.21 The survey design checklist is listed in Exhibit 2.

4.22 Diagrams shown in this survey design have been developed from Reference 3.4.

4.23 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 3.5. The lower limit area factor for areas less than 1 square meter is 10.1. Area 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 complex calculations are performed internal to applicable computer codes or within an Excel spreadsheet previously identified.

6.0 APPENDICES 6.1 Attachment 1-1 to 1-3, diagrams of Seal Chambers and Downcomers.

6.2 Attachment 1-4 to 1-7, VSP output showing static measurement points.

6.3 Attachment 2-1, is the calibration information for the lowest efficiency GFPC detector.

6.4 Attachment 3-1 to 3-2, are typical calibration sheets for a 2" by 2" Nal detection system.

6.5 Attachment 4-1, is a data collection sheet for a gamma-ray spectrometry system (typical).

6.6 Attachment 5-1 to 5-2, are calculation sheets used to determine the effective volumetric and surface concentration limits (Effective DCGL Calculator).

6.7 Attachment 6-1, is a calculation result for determining efficiency loss for a GFPC detector as a function of distance from a source.

6.8 Attachment 7-1 to 7-3, is calculation sheets to determine the scan MDC for a Nal detection system using a typical background count rate and a 12" diameter 1" thick MicroShield model.

6.9 Attachment 8-1 to 8-2, is calculation sheets to determine the scan MDC for a Nal detection system using a typical background count rate and a 12" diameter 3" thick MicroShield model.

6.10 Attachment 9-1 to 9-8, are calculation sheets used to determine the scan MDC for a Nal detection system using a typical background count rate and surface deposition model from MicroShield.

SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-030 0 Page 10 of 6i Subject Seal Chambers - Survey Plan 6.11 Attachment 10-1 to 10-3, are GFPC variability measurements from the Seal Chamber areas.

6.12 Attachment 10-4 to 10-5, are background measurements using a GFPC instrument in non-impacted areas.

6.13 Attachment 11-1, is Nal background measurements in a non-impacted area.

6.14 Attachment 12-1 to 12-3, are calculation sheets used to determine the scan MDC for a GFPC detection system using a typical background count rate associated with steel and concrete surfaces.

6.15 Attachment 13-1 to 13-6, are sections of survey unit inspection reports for the Seal Chamber areas.

6.16 Attachment 14-1 to 14-10, are Compass output results for the Seal Chambers.

r_- SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-03-030 I 0 Page 11 of 6V Subject Seal Chambers - Survey Plan Exhibit I SNEC Facility DCGL Values (8) 25 mremly Limit 4 mrem/y Goal 25 mremly Limit (All Pathways) (Drinking Water)

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

(dpm/100cm 2 ) (Surface & Subsurface) (Surface & Subsurface)

(pCi! 9) (pCilg)

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-1 37 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.OE+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 mremly regulatory limit will be controlled under this LTP 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).

i _t SNEC CALCULATION SHEET Calculation Number Revision Number Page Number ESOO-03-030 0 Page 12 of 64 Subject Seal Chambers - Survey Plan Exhibit 2 Survey Design Checklist (From Reference 3.5)

Calculation No.{

_____ n o. E900-03-030 SS8-1, SS8-2 & SS8-3 Status Reviewer ITEM REVIEW FOCUS (Circle One) Initials & Date I Has a survey design calculation number been assigned and is a survey design summary G NIA description provided? N/A /,7v3 2 Are drawings/diagrams adequate for the subject area (drawings should have compass Ye ) N/A headings)?

3 Are boundaries properly identified and is the survey area classification clearly indicated? NMA 4 Has the survey area(s) been properly divided into survey units lAW EXHIBIT 10 5 Are physical characteristics of the area/location or system documented? i N/A 6 Is a remediation effectiveness discussion included? e;sN/A Have characterization survey and/or sampling results been converted to units that are N/A comparable to applicable DCGL values? G __

8 Is survey and/or sampling data that was used for determining survey unit variance included? N/A Is a description of the background reference areas (or materials) and their survey and/or oVes 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?/A II Will the condition of the survey area have an impact on the survey design, and has the e NA I 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 Ye N/A design? _

13 Are all necessary supporting calculations and/or site procedures referenced or included? (es N/A 14 Has an effective DCGLw been identified for the survey unit(s)? N/A 15 Was the appropriate DCG LEmCincluded in the survey design calculation? Ye N/A 16 Has the statistical tests that will be used to evaluate the data been identified? d es N/A 17 Has an elevated measurement comparison been performed (Class 1 Area)? rYes>N/A 18 Has the decision error levels been Identified and are the necessary justifications provided? rYe N/A 19 Has scan instrumentation been identified along with the assigned scanning methodology? i j.) N/A 20 Has the scan rate been identified, and is the MDCscan adequate for the survey design? Yes) N/A \

21 Are special measurements e.g., in-situ gamma-ray spectroscopy required under this design, ') N/A and is the survey methodology, and evaluation methods described? -3 22 Is survey instrumentation calibration data included and are detection sensitivities adequate? N/A ->es 23 Have the assigned sample and/or measurement locations been clearly identified on a diagram / N/A or CAD drawing of the survey area(s) along with their coordinates? ________

24 Are investigation levels and administrative limits adequate, and are any associated actions e N/A clearly indicated? N 25 For sample analysis, have the required MDA values been determined.? Yes, N/A 26 Has any special sampling methodology been identified other than provided in Reference 6.3? CYes IA /

/7 (J

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

/S 0c~ 6-~L Seal Chambers 1 & 2 West Inner Wall Ceiling East Inner Wall Floor 102' 1 2 3 4 5 6 7 8 West Wall East Wall j 2 3 4 n p 5 6 7

_ j Window End Wall Sections South Wall Li ____al

¶4VN East Wall North Wall (Mirror Image)

ATTACHMENT -fi----

14 OfY Seal Chamber 3

.. . .. .. . . . ... s . *

,... .. + ,;

a @ @ @ .,+

Ceiling Floor I 241 53. 6 7 East Wall 1 2 3 4 5 6 7 8 9 10 West Wall Window End Wall Sections

. e-I' I;..

South Wall VVN M M M D East Wall North Wall (Mirror Image)

AllACHMENT t - 2

Seal Chamber 3 Downcomers (4 ea) 24" Downcomer Pipe 24" Downcomer Pipe - Exterior View I

I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I II I

I I I I I I I I I I I I II II I

I I

Tr :t --5-,

ATTACHMEt -- =--

f6 4~(0j~

Seal Chamber I West Wall Ceiling a -st -a-l Floor East WallFlo LI L [ L LLn South Wall ry-4.- 125" 352 9

- I I

North Wall 123" Seal Chamber I - Mirror Image ATI A en vi {\

G ,- -t - 4

VI {Cj~(,

Seal Chamber 2 I

Ceiling West Wall r

Floor East Wall D 1 0 I0D LI 0 0

_3 34' 8_

South Wall North Wall Seal Chamber 2 -Mirror Image eA S

4* 4 F6'V Seal Chamber 3 3 4 5 6 695"

- 49 135"

. 63"

_1 1 1 1 1 1 1 1 1 1 7

12

_Z 135" 13 48" g-I ATTACHMEW.J,.- (O -

DOWNCOMERS Seal Chamber 3 Mark a Starting Point on Each Cylinder as (0, 0) c)-I rC m'

(0, 0) A (0, 0) B (0, 0) C (0,) D IN

ORIG'kNAL

.:::::::..-. GFP :Radiationh. M'r ' t stmntCafbrationi rksheet

Performed By: R. J. Reheard Date: I 6124103 Instrument SIN: 95352 l Probe SIN: I 94818 Instrument Vendor Cal. Date: 12/20103 l . C. Due Date: l 12120/03

... .S~re 6t t4 Am-241 (GO 535) S-023 l Cs-137 (GO 536) S.024 i :;:id75o31 Viu 0.25 0.50 i

J l?E ie~r1 ate 418199 12:00 GMT 418199 12:00 GMT l: A~i;" C6%:*1 4.24E-01 3.11E-01

~[ 2 tg Etilo Rj e(e-)(~)

7.43E+03 6.89E+03 El Am-241 C[s-137 Source Radionuclide Decay Date r Cs.137 6124/03 Decay Factor=1 9.075E-01 Elapsed Time (days) l 1538 Activity (pCi)l 2.821 E-01 Source dpm=, 6.262E+05 Source dpm/in Probe Area (cmA2)=* 5.260E+05 2x Emission Rate (sec-1)= 6.253E+03 Probe Area (cmA2) 27c Emission Rate (min.1)=* 3.752E+05 12B : = 27t Emission Rate In Probe Area (min-1)=l 3.151E+05 Record of 1 Minute Source & Background Counting Results 9Check if using ISO 7503-1 Value No. OW Source Gross CPM OW Background CPM OW Source Net CPM RESULTS I 1.61E+05 175 1.608E+05 Counts/Emission (61) 2 1.61 E+05 201 1.604E+05 50.9%

3 1.60E+05 180 1.601E+05 27t EmisslonlDlsintfgratlon (Cs) 4 1.60E+05 161 1.602E+05 50.0%

5 1.61E+05 145 1.607E+05 Counts/Disintigratlon (et) 6 1.60E+05 176 1.603E+05 25.4%

7 1.60E+05 183 1.602E+05 _

a 1.61 E+05 184 1.604E+05 [ I C')

9 1.60E+05 204 1.602E+05 Approved:

10 1.61 E+05 190 1.607E+05 /

Mean=> 179.9 1.604E+05 l Date: @ 2..> 0 1C" l Calibration Calculation Sheet Verification Date=>l December-02 l I B. Brosey/P. Donnachie=l December-02 ATrACHMENT Z - I

6--F iz

00uratek-CALUBRATION CERTIFICATE Duatck kstuumnt Services 628 G dlaha Road Xingstnn. TN 37763 Phone

(865) 376-8337 Fax: (865) 37648331 This Cerilcstce will be nauiinpanied by Calibrutian Chin-t or YmAinirewuoi .-,nt.,ahle

[.'~,0S'CUSTOMXRJNFORMAT1N . '1 .' D 'D.RN R. _1_

Cuslower Neac: Duraek lnrtrumcnt Serviced ManuIacturer Ludlum Addres: 628 Gellaher Rd KIngston, TN 37763 Detector Model: 44-10 Contea Name: Thomas Scott Serial Numnber. 206280 Customer Purchsc Work Order Evaluation buthod:

Order Number. N/A Number. 2tU-01086 Source

-DETECTOREIC1ENCY/RESPONSE/PRECSIONINFORMUSATION

'; t

1) c Nudilde: Co"" Serial Number: 019455 Activity: SuCI nominal Certification Ditc: N/A (Used forPlateau Only)

2) aurscNpclt:Cs1' Scrisl Number 049711 Activity. Variable Ccrtlficution Date: 04d09/03 StierInfqormatIoq n!- ^

• Predislon Tt niRjar (Source #2) 2350-1 #129U0 Count 1 2.00 Due Date 04/30/04 Count 2 2.02 Threshold Ti100 (lUmV) Count 3 2.01 Cable Length sn Average 2.01 N/A NIA Toleruace 110% All counts within *10% oftAvyrage NIA NIA Pus/Fail Pass NIA ,/A r . . f ..- ^.4

• Low Sample Activity (400uR/hr): 111gb Sample Activity (ZmR/br) Dead Time (Dr): Calibration Constant (CC):

Using Source #2 a 68.962 Us Source #2 - 247,213 1.717419E-05 S.738530E+10 i- 1'AS

• .;DETECTOR DATA:, DOSE RATE PROBES 1EirlX t.S Detctur Setup Report YES / NO Devired Elposure Tolerance &10% As Found As Left Barcode Report YES / NO 0.400 0.360-0.440 N/A .401 Voltage Plateau: YES / NO 1 0.90-1.10 N/A .943 High Voltage: 950V 2 1.8-2.2 NIA 2.01

__ ~ ~~~"-i'5,.-e%"*.;:;:. *I..iBMMEN. Pv M9.;e '8E

^Deticton et up with a 2350-1 may be used with any 2350-1 provided that the setup parameters rc scanned into the 2350-1 prior to usc with that specific detector' Calibrated with Sf1 Cable We Cwufy that the ddecioreedu above wa" evvaluatd for propcr opau1Jon pniorto shipmant mad tha1 t met sl .1the Manufsczwm publisbaidopucizz opecIifimalan We tunhucratify that owrCalibratiou Mcsnwameiti~ uartraceabld tothc Nadonal 1n~tunaoftandu" and Todbaotogy. (Wearuc not tciponsiblc for damn..iaocmd daaring abwipmemotsofthw dvct or)

Detector 4I-Cerifid 1: IRevtewcd By:(/%-,~ (>'# & Date: 1 f Certification Date: 1031U03 Certificatiota Due: 10J1J0 ATACMET3 - I

.1 E1 39Vd 2iV31D3lNrld9 ITBEGE9018 WTI EGGZ/01/11

o*2c e LUDLUM MODEL 44-10 HIGH VOLTAGE PLATEAU DATA SHEET Serial Number: 206280

~ '"~*' SORCE (6eod n ?(x 772 8199 773 9919 774 11198 775 12865 776 14141 777 14548 778 14514 779 15155 780 14859 781 14096 782 13438 Detector plateau performed using Cs137 #019456 SuCi nominal value button source Ih for Peakn- -r

t  ;- .

Parameter Se__ing Setting Threshold (10mV1100) 642 612 Window (On) 40 100 High Voltage 7779 CPmR/Hr 101,180 176,080 Background CPM 22 _ 51 CPM~mR/Hrconvorsion performfed using Cs37# 049711 CertifIcation Data: 04109103

.___________________ d m 019455 (Threshold " 642 land indoW A ) 7.

FWHM =665- 615 . 755%

662 x 1OO%

Detector peaked for Cs' 37 using Ludlum peaking procedure and threshold setting of 642 and window setting of 40. As left threshold setting is 612 and window at 100 as requested by John Duskin. 2350-1 #129440 calibration due 04/30/04 used for peaking 44-10 detector.

Performed By: .1 Date: Za 3

Reviewed By: d5 r lvo Date: /i/r /l- d5 ATTACHMNIT 3 -

dV31ondc9 118ESE9PT8 WIT EOOZ/Ol/TT Po 39Vd

c23 EkatEbMzy r,,6..

SNEC FACILITY GAMMA-RAY SPECTROMETRY DATA SHEET SURVEY REQUEST No. DATE  : TIME AREA IDEN77FlCA77O OR DESCRIP77ON:

Photos Taken? Photo ID No. > Time Photos Taken >

DYES[-INO 662 keV ROI 1332 keV ROI Sketch of Measurement Location(s) No. ID/File No.

Net CTS Peak Visible? t CTS Peak Visible?

2 3

4 5

6 7

8 9

10 11 12 13 15 Repeat Count Numbers: Comments:

Measurement Performed By (Print/Sign): Date:

Reviewed By (Print/Sign): Date:

PAGE of ATTACHMENT T-_.l

Effective DCGL Calculator for Cs-137 (dpm/100 cmA2) I- Gross Activity DCGLw 8543 I Gross Activity Administrative Limit ldpml100 cmA2 6407 ldpm/1OO cmA2 25.01mremly TEDE Limit l

I, - Cs.137 Limit . - l CsI 37AdminIstrative Limit SAMPLE NO(s)r IDischarne Tunnel Surface Area I 8233 dpmlO cmA2 6174 dpm/100 CMA2 I ..SNEC AL 1 75%

I I Sample Input Individual Limits Allowed dpml100 Beta dpmIlOO Alpha dpm/lOD Isotope (pCilg, uCI, etc.) % of Total (dpml100 cmA2) cmA2 mremly TEDE cmA2 cmA2 II Am-241 3.10E+00 0.129% 27 11.00 10.19 -NA 11.00 Am-241 2 C-14 0.000% 3,700,000 0.00 0.00 0.00 - WA C-14 3 Co-60 9.54E+00 0.396% 7,100 33.85 0.12 33.85 .. NIA Co-60 4 Cs-1 37 2.32E+03 96.364% 28,000 8232.58 7.35 8232.6 NIA . Cs-1 37 5 Eu-152 0.000% 13,000 0.00 0.00 0.00 NIA . Eu-152 6 H-3 0.000% 120,000,000 0.00 0.00 Not Detectable NIA H-3 7 NI-63 6.34E+01 2.633% 1,800,000 224.98 0.00 Not Detectable NIA Ni-63 8 Pu-238 9.19E-01 0.038%° 30 3.26 2.72 NIA. 3.26 Pu-238 9 Pu-239 1.43E+00 0.059%1 28 5.07 4.53 NIA 5.07 Pu-239 10 PU-241 0.l 000u/ 880 0.00 0.00 Not Detectable I N/A Pu-241 11 Sr-90 9.15E+OO 0.: 380% 8,700 32.47 0.09 32.47 . . NIA Sr-90 I

100.' JUUU10p I I 0043

_Z5.U 8Z99 19 I I I Maximum Permissible

______________________________________________________________ dpml1OO cmA2 I I _____________________________________________________________

IC A1TACHMENT - .- I

SNEC AL 75% Total Activity LimIt DCGLW AdmInIstratIve Limit Effective DCGL Calculator for Cs-137 (in pClig) 1 6.62 IPCii9 1 4.97 JpCiig I I

SAMPLE NUMBER(salJDlscharae Tunnel Volumetric l I CS.137 Umit I Cs- 137 Administrative Llmit 36366.82% 25.0 mremly TEDE LUmit 6.38 pCIg 1 4.78 pC1ig 2844.37% 4.0 mromly Drinking Water (DWI Limit El Check for 25 mrem/y Sample Input 26 mrenWy TEDE 4 mremly DW A Allowed pCI/g for 25 B - Alowed pCIg Value Checked from This Sample Thl Sample Isotope (pCIlg. uCI. etc.)  % of Total Limits (pCltg) Umits (PcII) mremly TEDE for 4 mrmly OW Column A or a mremly TEDE mr*"Vy DW Am-241 3.100 0.129% 9.9 2.3 0.01 0.11 0.01 7.83 5.39 Am-241 2 C-14 0.000% 2.0- 5.4 0.00 0.00 0.00 0.00 0.00 C-14 Co-60 9.540 0.396% 3.5 67.0 0.03 0.34 0.03 68.14 0.57 Co.60 4 Cs-137 2320.00 96.364% 6.6 397 6.38 81.56 6.38 8787.88 23.38 Cs- 137 6 Eu-152 0.000% 10.1 1440 0.00 0.00 0.00 0.00 0.00 Eu-152 6 H-3 0.000% 132 31.1 0.00 0.00 0.00 0.00 0.00 H-3 7 Ni-63 63.40 2.633% 747 19000 0.17 2.23 0.17 2.12 0.01 Ni-63 a Pu-238 0.919 0.038% 1.8 0.41 0.00 0.03 0.00 12.76 8.97 Pu-238 9 Pu-239 1.430 0.059% 1.6 0.37 0.00 0.05 0.00 22.34 15.46 Pu.239 10 Pu-241 0.000% 86 19.8 0.00 0.00 0.00 0.00 0.00 Pu-241 1t Sr-90 9.150 0.380% 1.2 0.61 0.03 0.32 0.03 190.63 60.00 Sr-90 Z.41 L+U~j I 1IUU.UUU7OJ 6.62 84.64 6.62 9091.704 J 113.775 MaxImum Permissible MaxImum pC g PermIssible pCIfg To Use Thb InformatIon, Sample (25mremty) (4 mremly) Inne. llIt Uet-n..- In ntz11n L .I _ _ _ _ _ _ _ _ _ _ _ __ __ __ _ _ _ _ _ _ _ _ ., M , , - m . . . . J. - f I'e

\)

ID ATTACHMENT______P

37

i. Ioss.

E. w F jWWW1J I Cs-I 37 Efficiency Loss with Distance From Source 1.0 _

(I) Data: Datal -Loss (1) - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Model: ExpD ecayl 0

-j ChiA2 = 0.00018 0.8 _ ._ yO 0.03536 +/-0.02118 C-) x0 0 +/-O EC) C m a) --------------- ------------------- Al 1.00693 +/-0.01 809 tI 1.61706 +/-0.07558

-13.

0.6 -t Ij 0 Fit = yO+A1 eA(_(xxO)it1 )

C 0.4 L.

U-

- -- - -- - -- -- - -- - -- -- - -- - - - - - ---- 7 t - --- - -

0.2

• 1*

I I l l a 1 I

0.0 0.5 1.0 1.5 2.0 2.5 3.0 Inches from 150 cm 2Source

,;? 7 6-Nal Scan MDC Calculation - Concrete.mcd Nal Scan MDC Calculation - 1" Thick Slab b := ~100~

.~~ . - ..

p := 0.5

. ,-- f-MS

.. t t

-%outu to .s-77.888:10,.d afl.J

.- is8 KS1-.

. -s 1,-4

-'(I 9 rifsRj o i = 6.096 ObservationInterval (seconds)

(b-O i) 60 MDCR i = (d-ji). 60 oi MD -RI43.4 -"- 't-IMDCR --:~43.294 3, net counts per minute i:.:.:::1,:.,,. ... - .: .

I--

MDCR i w MDCR surveyor : r z M.

4;P

<-r., 61-r28 MDCR R r618 net counts per minute

-. -^_-. - -_ . Y _ ...I _ j MDCR surveyor MDERC Conv MDER . - 038 ~ jiR/h MDC scan MDER scnMs output'I 10 3

,d pCi/g 11/12/2003

Nal Scan MDC Calculation - Concrete.mcd where:

b = backgroundin counts per minute bi= backgroundcounts in observation interval Conv = Na! manufacturers reportedresponse to energy of contaminant(cpmfuRfh) d = index of sensitivity (Table 6.5 MARSSIM), 1.38 = 95% of correctdetection's, 60%false positives HSd = hot spot diameter (in centimeters)

MDCCa,, = Minimum Detectable Concentrationforscanning (pCi/g)

MDCR, = Minimum Detectable Count Rate (ncpm)

MDCR,,eor =MDCRi correctedby humanperformancefactor(ncpm)

MDER = Minimum Detectable Exposure Rate (uR/h)

MS,,,, = MicroShield output exposure ratefor I pCilg of contaminant (mRmh) 0i = obervationInterval (seconds) p = humanperformancefactor SR = scan rate in centimeterspersecond z

11/12/2003

1r1i

- '- , -, '1 "

l.. Al -,

I .  :

• MicroShield v5.05 (5.05-00121)

GPU Nuclear Page :1 File Ref:

DOS File  : SLAB3.MS5 Date:

Run Date  : November 12 2003 By.

Run Time  : 1:43:03 PM Checked:

Duration  : 00.00:01 Case

Title:

12 Cylinder

Description:

Cs-1 37 @ 1 pCilg in 1* Thick Slab Geometry: 8 - Cylinder Volume - End Shields Source Dimensions lHeight 254 cm 1.0 inI lRadius 15.24 cm 6.0inl Y Dose Points A I X V Y I Z

1. 1 Ocm 10.16cm OcmI 0.0 in 4.0 in 0.0 inl C) Shields Shield Name I Dimension I Material l Density Source 113.097 ir3 Concrete 235 Air Gap Air 0.00122 Source Input

\'3- Grouping Method : Actual Photon Energies Nuclide I curies l becquerels uGi/corr I Bq/crr?

Ba-1 37m 4.1201e-009 1.5245e+002 2.2231e-006 8.2255e-002 Cs-1 37 4.3553e-009 1.6115e+002 2.3500e-006 8.6950e-002 Buildup The material reference is : Source Integration Parameters Radial 40 Circumferential 40 Y Direction (axial] 40 Results 0 Energy Activit Fluence Rate Fluence Rate Exposure Rate Exposure Rate ner MeV/cnrr/sec MeV/cOrr/sec mR/hr mR/hr Me photons/sec No Buildup With Buildup No Buildup With Buildup 0.0318 3.156e+00 6.355e 06 7.682e-06 5.293e-08 6.399e 08 0.0322 5.823e+00 1.222e-05 1.486e-05 9.832e*08 1.1 96e-07 0.0364 2.119e+00 6.726e-06 8.749e-06 3.821 e-08 4.971 e-08 0.6616 1.372e+02 3.202e-02 4.057e-02 6.207e-05 7.865e*05 TOTALS: 1.483e+02 3.204e-02 4.060e-02 6.226e-05 7.888e-05

Nal Scan MDC Calculation - Concrete in Nal Scan MDC Calculation - 3" Thick Slab, Partial Densitv b :=100

. .. I. - ,

p:-O0.5

~ -4. HS, ddS;75--

-= 30.48~

, SR :, 5 d.:--138 I; -2_ i rv._S Conv :- 176.080 MS-7'940

~.... ~s-

.ouLJuL.tS.

1-- -'- -R-o i = 6.096 ObservationInterval (seconds)

(b O;)

60 IDCR i = (d- b) 60 MDCR - 43.294

, , : , I _- . - . .....

net counts ver minute 0

MDCRMDCR MDRsurveyor := r IM3CR..srvey I.--.. - :.r.,.!.,. 61.228 ,.,,,.I i- net counts per minute

, e .... .. . .

MDCR surveyor MDERC Conv jiR/h MDC sMDER MS output' f 10 MdDC ,.-. -'12949 :: pCfig U -.\....w;^.M~scan.-

v._z. _:SCA I'A;^..-;

11/12/2003

...*.* . .  : ', J ~'-

' ' ' : --I I1 '

2T1p.j MicroShield v5.05 (5.05-00121)

GPU Nuclear Page :1 File Rel:

DOS File  : SLAB4.MS5 Date:

Run Date  : November 12.2003 By.

Run Time  : 1:51:28 PM Checked-- -- --

Duration  : 00:00:01 Case

Title:

12 Cylinder

Description:

Cs-1 37 @ 1 pCilg in 3' Thick Slab - Partial Density Geometry: 0 - Cylinder Volume - End Shields Source Dimensions Height 7.62 cm 3.0 in!

lRadius 15.24cm 6.0inl Dose Points A X Y z

1. 1 0cm 15.24cm Ocm O0.Oin 6.0in O.Oir Shields A Shield Name Dimension Material Density Source 339.292 ir? Concrete 1.6 Air Gap Air 0.00122 19 Source Input Grouping Method : Actual Photon Energies im Nucrde curies becquerels l uCi/crri? Bao/crr?

Ba-1 37m 8.4156e-009 3.1138e+002 1.5136e-006 5.6003e-002 Cs-1 37 8.8960e-009 3.291 5e+002 1.6000e-006 5.9200e-002 Buildup The material reference is : Source Integration Parameters Radial 40 Circumferential 40 0 Y Direction (axial) 40 Results Actit Fluence Rate Fluence Rate Exposure Rate Exposure Rate MnerVy Activity MeV/crr?/sec MeV/crr?/sec mR/hr mR/hr MeV photons/sec No Buildup With Buildup No Buildup With Buildup 0.0318 6.446e+00 6.306e-06 7.619e-06 5.253e-08 6.346e-08 0.0322 1.189e+01 1.212e-05 1.473e-05 9.756e-08 1.1 86e-07 0.0364 4.328e+00 6.676e-06 a687e-06 3.793e-08 4.936e-08 0.6616 2.802e+02 4.228e-02 6.072e-02 8.1 97e-05 1.1 77e-04

Nat 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 informationlassumptions 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 0.05 meters/second 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 6.1 seconds.

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 g/cc) with a nominal thickness of 2 mm.

2) The areal hot spot size is assumed to be -0.073 M2 .

3) The modeling diameter is 0.3048 meters (12" 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.

1of 5 1111212003 11/12/2003 ATTACHMENT 9 - I 1of 5

33 o7 6_f 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 (d7 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 Postive and False Postive Proportions l 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 11/12/2003 ATTACHMENT q 2- 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 (4c)

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 Bq/kg.

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 Currie (Currie 1968, NRC 1984) and Altshuler and Pastemack (Altshuler and Pasternak 1963) provide details of the derivations involved.

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

Lc - 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 4C; 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.

11/12/2003 A TACHME 9E -. 3 3 of 5

Nal Scan MOC Calculation - Surface -

Nal Scan MDC Calculation - Surface Deposition

- - '- .'e-,, .- - .

• S 4 b :- 100 p =0.5^

HS.--

f*i i ;7 -

30.48 SR-,=5 d: .38 Conv := 176.080 .. ;I-

~

MS6it- i_~ 1~..54.1

£1iA eSRJ 0 = 6.096 ObservationInterval (seconds)

(b-O i) 60 NMDCR~ := dr MDCRi - 43.294 net counts per minute MDCR; surveyor = r MDCRsurv -_612228 net counts per minute o.-. I . ......... ..

MDCR surveyor.

MDER=

Conv 0.34_ -87 MDER~=0348' '-s~`

_ 4.. 4t _ _

jiR/h MSscan MDER sa-Ms output'1 10 3 MDC:-22.492:

.s.can. ! ... pCi/cm' VmDC ~ 23 dpVm/00 cm-11/12/2003 ATTACHMENT O/- 4 of 5

Nal Scan MDC Calculation - Surface 36 4&-~6 5 where:

b = background in counts perminute b= background counts in observation interval Conv = Nal manufacturers or calibrationinformation reportedresponse to energy of contaminant (cpmfuRlh) d = index ofsensitivity (Table 6.5 MARSSIM), 1. 38 = 95% of correct detection's, 60°/6false positives HSd = hot spot diameter (in centimeters)

MDCC,ca = Minimum Detectable Concentrationforscanning(pCi/cm 2)

MDCR, = Minimum Detectable Count Rate (ncpm)

MDCRjwy,ver = MDCR, correctedby human performancefactor(ncpm)

MDER = Minimum Detectable Exposure Rate (uR/h)

MSO,,, = MicroShieldoutput exposure ratefor I pCi/cm2 of contaminant(mR/h)

Oj = obervationInterval (seconds) p = human performancefactor SR = scan rate in centimeters per second 11/12/2003 A17ACHME - ' 5 of 5

kIi ' , ' ~d ~

MicroShield v5.05 (5.05-00121)

GPU Nuclear Page :1 File Ref:

DOS File  : DISKMS5 Date:

Run Date  : November 12. 2003 ByC Run Time  : 229:58 PM Checked:

Duration  : 00:00:00 Case

Title:

Disk

Description:

Cs-137 Surface Source with Fe2O3 @ 0.2 cm Geometry: 3 - Disk Source Dimensions lRadius 15.24 cm 6.0 inl Dose Points A X Y0n Z

1. 1 7.82 cm 0 cm 0 cm 3.1 in 0.0 in 0.0;i tz Shields

-I Shield Name Dimension Material Densitv Shield 1 .2cm Iron Oxide 5.1 Air Gap Ai 0.00122 rni Source Input Grouping Method: Actual Photon Energies Nucfide curies becquerels uCicrril Bq/crr?

Ba-1 37m 6.9026e-01 0 25540e+001 9.4600e-007 3.5002e-002 Cs-1 37 7.2966e-010 26997e+001 1.0000e-006 3.7000e-002 Buildup The material reference is : Shield 1 Integration Parameters 1W Radial 401 lCircumferential 40 Results Energy Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate Eer MeV AhllYIY photons/sec MeV/cri?/sec No Buildup MeV/crr?/sec With Buildup NomR/hr Buildup WithmR/hr-Buildup 0.0318 5.287e-01 1.526e-08 1.733e-08 1.271 e-1 0 1.443e-10 0.0322 9.755e-01 3.442e-08 3.921 e-08 2.770e-1 0 3.1 55e-1 0 0.0364 3.550e-01 7.533e-08 8.847e-08 4.280e-1 0 5.026e-1 0 0.6616 2.298e.01 7.279e-03 7.973e-03 1.411e-05 1.546e-05 TOTALS: 2.484e+01 7.279e-03 7.973e-03 1.411 e-05 1.546e 05

3k 0-~-L Nal Static Measurement MDC Calculation Use when Backeround Count Time # Sample Count Time B:=100 TSB-=5 TB. -1 CF:= 1708

__ ^ . SB '7.. - MSO -7. 8 8 8 :lJ0~r.'

MSO

,W .r_

3 II;,_. - -.-.~- i, -

91 b

Mas ...: .3

,,,Ci 2 . 2 2 I K- 1.437-.10.

. . .. .. 4z :-Is RBB RB:= B Backgroundcounting rate TB L c:= 2.33- Calculationof criticallevel (page 6-34 ofMARSSIM)

L C = 23.3 Criticallevel Any count above this value shouldbe regardedat being greaterthan background L c+B = 123.3 (page 6-37 ofMARSSIM).

L D := 3 + 4.65 *4 LD =49-5 Detection limit

[3 MDC:= -

K-TSB MDC',-'-""

-= '3.06'10-* Results in pCi {DC\

_._w17 . - t.!, ';

2.22 ... .. :,*Sov, Pci StMass'.-...  ;: g I

ATTACI-MET-_- --

-- - 3 5 O - ze-tv- -

where:

B = background count in time TB (counts)

CF = conversion factor for instrument calibration (cpm/mR/h)

Ci = number of curies in MicroShield model K = instrument efficiency and other correction factors used to convert to appropriate units LC = critical level (in counts)

LD = detection limit (in counts)

Mass = mass of model in grams MDC = Minimum Detectable Concentration (pCig)

MSO = MicroShield output in mR/h RB = background count rate (cpm)

TSB = sample count time (in minutes)

TB = background count time (in minutes) 2 ATiACLWME? - -0

LI/o 0-SEAL CHAMBER No. 1 JG1135 Instrument 126218 95080 SS8-1 FSS-407 BHB No. Location Date Time Detector Counts Count Time (sec) Mode Designator Shielded Unshielded 2 SS8-1 FP1S 11/32003 9:57 1 1.49E+02 60 SCL Shielded 1.49E+02 3 SS8-1 FPIU 11/3/2003 9:58 1 1.76E+02 60 SCL Unshielded _ . 1.76E+02 4 SS8-1 FP2S 1131/2003 10:00 1 1.87E+02 60 SCL Shielded 1.87E+02 5 SS8-1 FP2U 11/3/2003 10:01 1 1.84E+02 60 SCL Unshielded _ 1.84E+02 6 SS8-1 FP3S 11/32003 10:02 1 1.63E+02 60 SCL Shielded 1.63E+02 7 SS8-1 FP3U 11/3/2003 10:04 1 1.77E+02 60 SCL Unshielded _ 1.77E+02 8 SS8-1 FP4S 11/3/2003 10:05 1 1.05E+02 60 SCL Shielded 1.05E+021 9 SS8-1 FP4U 11/3/2003 10:06 1 1.66E+02 60 SCL Unshielded _ 1.66E+02 10 SS8-1 FP5S 11/3/2003 10:07 1 1.18E+02 60 SCL Shielded 1.18E+02 11 SS8-1 FP5U 11/32003 10:08 1 1.86E+02 60 SCL Unshielded _ 1.86E+02 12 SS8-1 FP6S 11/32003 10:10 1 1.21E+02 60 SCL Shielded 1.21E+02 13 SS8-1 FP6U 11/3/2003 10:11 1 2.59E+02 60 SCL Unshielded _ 2.59E+02 14 SS8-1 FP7S 11/3/2003 10:12 1 1.08E+02 60 SCL Shielded 1.08E+021 15 SS8-1 FP7U 11/32003 10:13 1 1.89E+02 60 SCL Unshielded _ 1.89E+02 16 SS8-1 FP8S 11/32003 10:14 1 1.35E+02 60 SCL Shielded 1.35E+02 17 SS8-1 FP8U 11/3/2003 10:15 1 1.90E+02 60 SCL Unshielded 1.90E+02 18 SS8-1 FP9S 11/3/2003 10:23 1 1.38E+02 60 SCL Shielded 1.38E+02 19 SS8-1 FP9U 11/32003 10:24 1 1.55E+02 60 SCL Unshielded Di 1.55E+02 20 SS8-1FP10S 11/3/2003 10:25 1 1.03E+02 60 SCL Shielded 1.03E+02 21 SS8-lFP10U 11/3/2003 10:26 1 2.05E+02 60 SCL Unshielded _ 2.05E+02 22 SS8-1FP11S 11/32003 10:28 1 1.20E+02 60 SCL Shielded 1.20E+02 23 SS8-lFP11U 11/3/2003 10:29 1 1.67E+02 60 SCL Unshielded 1.67E+02 24 SS8-1FP12S 11/3/2003 10:30 1 1.23E+02 60 SCL Shielded 1.23E+02 25 SS8-1FP12U 11/32003 10:31 1 1.91E+02 60 SCL Unshielded _ 1.91E+02 26 SS8-1FP13S 11/3/2003 10:33 1 1.49E+02 60 SCL Shielded 1.49E+02 27 SS8-lFP13U 11/3/2003 10:34 1 1.77E+02 60 SCL Unshielded _ 1.77E+02 28 SS8-1FP14S 11/32003 10:35 1 1.22E+02 60 SCL Shielded 1.22E+021 29 SS8-1FP14U 11/32003 10:36 1 1.54E+02 60 SCL Unshielded _ 1.54E+02 30 SS8-1FP15S 11/3/2003 10:38 1 1.34E+02 60 SCL Shielded 1.34E+02 31 SS8-IFP15U 1113/2003 10:39 1 1.65E+02 60 SCL Unshielded _ 1.65E+02 32 SS8-1FP16S 11/3/2003 10:40 1 1.53E+02 60 SCL Shielded 1.53E+02 33 SS8-IFP16U 11/3/2003 10:41 1 2.37E+02 60 SCL Unshielded _ 2.37E+02 34 SS8-1FP17S 11/3/2003 10:43 1 1.78E+02 60 SCL Shielded 1.78E+02 35 SS8-1FP17U 11/3/2003 10:44 1 1.74E+02 60 SCL Unshielded _ 1.74E+02 36 SS8-1FP18S 11/32003 10:46 1 1.81E+02 60 SCL Shielded 1.81E+02 37 SS8-1FP18U 11/3/2003 10:47 1 2.19E+02 60 SCL Unshielded _ 2.19E+02 Minimum 1.03E+02 1.54E+02 Maxlmum 1.87E+02 2.59E+02 Mean 1.38E+02 1.87E+02 Sigma - 2.62E+01 2.77E+01 ATTAGHMENT/L- 1

1/1/ L011*iL SEAL CHAMBER No. 2 BN8487 Instrument 126179 94819 SS8-2 FSS-409 BHB No. Location Date Time Detector Counts Count Time (sec) Mode Designator Shielded Unshielded 4 SS8-2FP2S 1113/2003 10:02 1 1.38E+02 60 SCL Shielded 1.38E+02 5 SS8-2FP2U 11/3/2003 10:03 1 2.09E+02 60 SCL Unshielded ] 2.09E+02 6 SS8-2FP3S 1113/2D03 10:06 1 1.18E+02 60 SCL Shielded 1.18E+02 7 SS8-2FP3U 11/3/2003 10:07 1 2.27E+02 60 SCL Unshielded ] 2.27E+02 8 SS8-2FP4S 11/3/2003 10:09 1 1.15E+02 60 SCL Shielded 1.15E+02 9 SS8-2FP4U 11/3/2003 10:10 1 3.06E+02 60 SCL Unshielded 3 _ 3.06E+02 10 SS8-2FP5S 1113/2003 10:11 1 1.18E+02 60 SCL Shielded 1.18E+02 11 SS8-2FP5U 11/3/003 10:13 1 2.53E+02 60 SCL Unshielded 1 2.53E+02 12 SS8-2FP6S 11/3/2003 10:15 1 1.19E+02 60 SCL Shielded 1.19E+02 _ __

13 SS8-2FP6U 11/3/2003 10:16 1 2.24E+02 60 SCL Unshielded ] 2.24E+02 14 SS8-2FP7S 11/3/2003 10:18 1 1.30E+02 60 SCL Shielded 1.30E+02 15 SS8-2FP7U 11/3/2003 10:19 1 3.97E+02 60 SCL Unshielded ] 3.97E+02 16 SS8-2FP8S 1113/2003 10:22 1 1.48E+02 60 SCL Shielded 1.48E+02 _

17 SS8-2FP8U 11/3/2003 10:23 1 3.12E+02 60 SCL Unshielded ] 3.12E+02 18 SS8-2FP9S 11/3/2003 1025 1 1A2E+02 60 SCL Shielded 1.42E+02 _

19 SS8-2FP9U 11/3/2003 10:26 1 2.70E+02 60 SCL Unshielded 3 2.70E+02 20 SS8-2FP10S 11/3/2003 10:28 1 1.04E+02 60 SCL Shielded 1.04E+02 _

21 SS8-2FP1OU 11/3/003 10:29 1 1.32E+02 60 SCL Unshielded 13 1.32E+02 22 SS8-2FP11S 11/3/2003 10:31 1 1.32E+02 60 SCL Shielded 1.32E+02 23 SS8-2FP11U 113/N2003 10:33 1 2.91E+02 60 SCL Unshielded 2.91E+02 24 SS8-2FP12S 11/3/003 10:34 1 1.63E+02 60 SCL Shielded 1.63E+02 25 SS8-2FP12U 11/3/003 10:36 1 1.90E+02 60 SCL Unshielded _ 1.90E+02 26 SS8-2FP13S 11/3/2003 10:38 1 1.61E+02 60 SCL Shielded 1.61E+02 27 SS8-2FP13U 11/3/2003 10:39 1 1.98E+02 60 SCL Unshielded _ 1.98E+02 28 SS8-2FP14S 11/3/2003 10:42 1 1.64E+02 60 SCL Shielded 1.64E+02 29 SS8-2FP14U 11/3/003 10:43 1 1.87E+02 60 SCL Unshielded _ 1.87E+02 30 SS8-2FP15S 11/3/2003 10:48 1 1.74E+02 -- 60-- SCL- Shielded - 1.74E+02 31 SS8-2FP15U 11/3/O03 10:50 1 3.20E+02 60 SCL Unshielded _ 3.20E+02 32 SS8-2FP16S 11/3/2003 10:52 1 1A1E+02 60 SCL Shielded _ 1.41E+02 33 SS8-2FP16U 11/3/O03 10:53 1 1.71E+02 60 SCL Unshielded _ 1.71E+02 34 SS8-2FP17S 11/3/2003 10:55 1 1.69E+02 60 SCL Shielded 1.69E+02 35 SS8-2FP17U 11/3/2003 10:56 1 2.16E+02 60 SCL Unshielded _ 2.16E+02 Minim um = 1.04E+02 1.32E+02 Maximumrn 1.74E+02 3.97E+02 Mean 1.40E+02 2.44E+02 Slgma 2.18E+01 6.81E+01

-ATTACHMENT /0 2-

?.

9/' of- 6 0 _ .0 SEAL CHAMBER No. 3 BB7173 Instrument126188 SS8-3 SS8-3 FSS-395 BHB No Location Date Time Detector Counts Count Time (sec) Mode L)estanator Shielded Unshielded SS8-3 FP1S 10/29/2003 8:38 1 1.53E+02 60 SCL Shielded 1 .53E+02 2 SCL Unshielded -

3 SS8-3 FPIS 10/29/2003 8:40 1 2.47E+02 60 2.47E+02 8:42 1 1.67E+02 60 SCL Shielded 0 1.67E+02 4 SS8-3 FP2S 10129/2003 1012912003 8:43 1 2.43E+02 60 SCL Unshielded _

5 SS8-3 FP2S _2.43E+02 1012912003 8:46 1 1.98E+02 60 SCIL Shielded 1.98E+02 6 SS8-3 FP3S 10129/2003 8:47 1 2.36E+02 60 SCL Unshielded 0 2.36E+02 7 SS8-3 FP3S SCL Shielded 8 SS8-3 FP4S 1012912003 8:49 1 1.73E+02 60 1.73E+02 1012912003 8:50 1 2.28E+02 60 SCL Unshielded - X __ 2.28E+02 9 SS8-3 FP4S 0 10129/2003 8:51 1 1.96E+02 60 SCL Shielded 1.96E+02 10 SS8-3 FP5S 1012912003 8:52 1 2.53E+02 60 SCL Unshielded _ _2.53E+02 11 SS8-3 FP5S 1012912003 8:55 1 2.15Ei-02 60 SCL Shielded 2.1 5E+02 12 SS8-3 FP6S 2.95E+02 60 SCL Unshielded 13 SS8-3 FP6S 1012912003 8:56 1 _2.95E+02 1012912003 8:58 1 1.87E+02 60 SCL Shielded 1.87E+02 14 SS8-3 FP7S 1012912003 8:59 1 2.20E+02 60 SCL Unshielded 0 _2.20E+02 15 SS8-3 FP7S 10129/2003 9:01 1 1.71 E+02 60 SCL Shielded

_ 1.71 E+02_

16 SS8-3 FP8S 1012912003 9:02 1 2.41 E+02 60 SCL Unshielded E+02 17 SS8-3 FP8S _2.41 1012912003 9:04 1 1.82E+02 60 SCL Shielded 1.82E+02 18 SSB-3 F89F 10129/2003 9:05 1 2.55E+02 60 SCL Unshielded 2.55E+02 19 SS 8-3 FF9P 20 SS8-3 FP9OS 10129/2003 9:48 1 1.71 E+02 60 SCL Shielded 1.71 E+02 10/2912003 9:49 1 2.23E+02 60 SCL Unshielded ._ 2.23E+02 21 SS8-3 FPFOS 10/2912003 9:51 1 2.04E+02 60 SCL Shielded 2.04E+02_

22 S S8-3 FP11S 10/2912003 9:52 1 2.65E+02 60 SCL Unshielded D 2.65E+02 23 SS8-3 FF11S 10129/2003 9:53 1 1.84E+02 60 SCL Shielded 1.84E+02 24 S S8-3 FP12S 1012912003 9:55 1 2.13E+02 60 SCL Unshielded X+2.1 3E+02 25 SS8-3 FP12S 0 10/29/2003 9:56 1 2.07E+02 60 SCL Shielded 2.07E+02 -_-

26 SS8-3 FP13S 1012912003 9:58 1 2.56E+02 60 SCL Unshielded 0 2.56E+02 27 SS8-3 FP13S SS8-3 FP145 10129/2003 9:59 1 2.1 1E+02 60 SCL Shielded 2.1 1E+02_

28 60 SCL Unshielded 2.56E+02 29 SS8-3 FP145 1012912003 10:00 1 2.56E+02 _

10129/2003 10:02 1 2.24E+02 60 SCL Shielded 2.24E+021 30 SS8-3 FP15S 1012912003 10:03 1 2.78E+02 60 SCL Unshielded 0 I 2.78E+02 31 SS8-3 FP15S SS8-3 FP165 1012912003 10:04 1 1.58E+02 60 SCL Shielded 1.58E+021 32 SCL Unshielded 33 SS8-3 FP16S 1012912003 10:06 1 1.64E+02 60 I 1.64E+02 1012912003 10:08 1 1.7E+O2 60 SCL Shielded 1.47E+021 34 SS8-3 FP17S 1012912003 10:10 1 1.53E+02 60 SCL Unshielded 1.53E+02 35 SS8-3 FP17S 10129/2003 10:13 1 1.61E+02 60 SCL Shielded 1.61E+02 36 SS8-3 FP18S 1012912003 10:14 1 1.70E+02 60 SCL Unshielded 0 I 1.70E+02 37 S8-3 FP18 10/29/2003 10:16 1 1.44E+02 60 SCL Shielded 1.44E+021 38 SS8-3 FP19S 39 SS8-3 FP19S 10/2912003 10:17 1 1.46E+02 60 SCL Unshielded

_ 1 1A6E+02 10:21 1 2.30E+02 60 SCL Shielded 0 2.30E+021 40 SS3 FP20S 1012912003 10/29/2003 10:22 1 2.68E.02 60 SCL Unshielded I 2.68E+02 41 SSB-3 FP20S 1012912003 10:25 1 2.14E_02 60 SCL Shielded 2.14E+021 42 SS8-3 FP21S 1012912003 10:27 1 2.95E+02 60 SCL Unshielded I 2.95E+02 43 SS8-3 FP21S 1012912003 10:30. 1 2.35E+02 60 SCL Shielded 2.35E+021 44 SS8-3 FP22S 1012912003 10:31 1 2.87E+02 60 SCL Unshielded_ 2.87E+02 45 SS8-3 FP22S 10/29/2003 10:34 1 1.92E+02 60 SCL Shielded 1.92E+02 46 SS8-3 FP23S 10/29/2003 10:35 1 2.20E+02 60 SCL Unshielded 2.20E+02 47 SS8-3 FP23S 10129/2003 10:37 1 2.24E+02 60 SCL Shielded 2.24E+02 48 SS8-3 FP24S 10129/2003 10:39 1 3.04E+02 60 SCL Unshielded p 3.04E+02 49 SS8-3 FP24S Minimum = 1.44E+02 1.46E+02 Maximum=;> 2.35E+02 3.04E+02 Mean - 1.90E+02 2.38E+02 Slgma=> 2.72E+01 4A3E+O1 ATTACHMENT /e9

0 HL

- Williamsburg Steel Background Measurements SR-48 37122N21 Instrument95348 RJR9291 Time Detector Counts CountTime(sec) Mode Designator FSS.004 BHB 0 BKGNO 11114/2002 6:47 1 6.54E+03 1800 SCL Indal Background p3 Stee CF(cpm)= I 1 Source Check 1111412002 9:54 1 .70E+0S 60 SCL Source a Shielded Unshielded 2 STEELAtS 1111412002 10:32 t 2.13E+02 60 SCL Shielde 2.13E.02 :_______

3 STEELA1U 11142002 10:33 1 2.04E+02 60 SCL Unshielded _ -_.  : 2.04E+02 4 STEELA2S 11114no2 10:37 1 2.03E+02 60 SCL Shielded 2.03E+02 -_-:*__-

5 STEELA2U 11)1412002 10:38 1 2.25E+02 60 SCL Unshielded 2.25E+02 6 STEELA3S 1111412002 10:39 1 1.85E+02 60 SCL Shblded 1.85E+02 ._._--_-:

7 STEELA3U 11)14)2002 10:40 1 2.09E+02 60 SCL Unshielded ...---

• 2.09E+02 8 STEELA4S 11/14/2002 10:42 1 2.03E+02 60 SCL Shielded 2.03E+02 ._.:_--

9 STEELA4U 11/14J2002 10:43 1 1.67E+02 60 SCL Unshielded . .-

. .. 1.67E+02 10 STEELA5S 11/1412002 10:44 1 1.55E+02 60 SCL Shieded 1.55E+02 -_.-_:-

11 STEELASU 11)1412002 10:45 1 226E+02 60 SCL Unshielded ._._.-_._-: 2.26E+02 12 STEELA6S 1111412002 10:46 1 1.92E+02 60 SCL Shielded 1.92E+02 _...._..

13 STEELA6U 11)1412002 10:47 1 1.95E+02 60 SCL Unshielded _ . -.... ::: 1.95E+02 14 STEELA7S 111142002 10:48 1 1.96E+02 60 SCL Shielded 1.96E+02 15 STEELA7U 11/14002 10:50 1 2.01E+02 60 SCL Unshielded B .___..._ .:_. 2.01E+02 16 STEELABS 11/14/2002 10:51 1 2.15E+02 60 SCL Shelded 2.15E+02  ::._.-_:

17 STEELA8U 1141202 10:52 1 2.38E.02 60 SCL Unshielded _ 2.38E+02 18 STEELA9S 11114/2002 10:53 1 2.00E+02 60 SCL Shielded 2_OOE+02 -_.-_._.

19 STEELA9U 11114/2002 10:54 1 1.92E+02 60 SCL Unshielded _ 1.92E+02 20 STEELA10S 1111412002 10:56 1 1.83E+02 60 SCL Shielded 1.83E+02 21 STEELA1OU 11/1412002 10:57 1 2.25E+02 60 SCL Unshielded _ 2.25E402 22 STEELA11S 1111412002 10:58 1 1.95E+02 60 SCL Shieled 1.95E02 :____:.-.

23 STEELA11U 11/1412002 10:59 1 2.15E+02 60 SCL Unshielded B ..:-:... .... 2.15E402 24 STEELA12S 11114/2002 11:00 1 1.77E+02 60 SCL Shielded 1.77E+02 _  :-_.. _:_

25 STEELA12U 11/14/2002 11.01 1 2.34E+02 60 SCL Unshieded 0 2 34E+02 26 STEELA13S 11114/2002 11:03 1 2.02E+02 60 SCL Shelded 2.02E+02 -:-_.:.:

27 STEELA13U 1111412002 1105 1 2.18E+02 60 SCL Unshielded .: -. ....--.

_ 2.18E+02 28 STEELA14S 11/1412002 11.06 1 1.89E+02 60 SCL Shielded 1.89E+02 ... _A__.

29 STEELA14U 1111412002 11:07 1 1.99E+02 60 SCL Unshielded _ 1.99E+02 30 STEELA15S 11114102 11:08 1 2.16E+02 60 SCL Shielded 2.16E+02 -_:__-:__

31 STEELA15U 11412002 11:09 1 2.15E+02 60 SCL Unrshelded B .____.__:_.- 2.15E+02 32 STEELA16S 1111412002 11:10 1 1.88E+02 60 SCL Shielded _ 1.88E+02 .::.--.: ..

33 STEELA16U 1111412002 11:11 1 2.05E+02 60 SCL Unshielded B 2.05Ee02 34 STEELA17S 1111412002 11:13 1 2.12E+02 60 SCL Shielded 2.12E+02 ._-__: :__

35 STEELA17U 11/1412002 11:14 1 2.11E+02 60 SCL Unshielded _ 2.1 1E+02 36 STEELA18S 11/1412002 11:15 1 2.00E+02 60 SCL Shielded 0 2.00 E+02 :---.._.__

37 STEELA1BU 1111412002 11:16 1 1.93E+02 60 SCL Unshielded A 1.93E+02 38 STEELA19S 11/1412002 11:17 1 1.84E+02 60 SCL Shielded 1.84E+02 .:_:_:-.:

39 STEELA19U 11)1412002 11:18 1 2.09E+02 60 SCL Unshielded A 2.09E+02 40 STEELA20S 11)1412002 11:19 1 1.94E+02 60 SCL Shielded 1.94E+02 -. :.:..._

41 STEELA20U 11/1412002 11:20 1 2.30E+02 60 SCL Unshielded A 2.30E+02 42 STEELA21S 1111412002 1122 1 2.10E+02 60 SCL Shielded 2.1 OE+02 ..... ___:

43 STEELA21U 1)1412002 11:23 1 4 M .I QU 60 gn SCL UnhieldedB 1.93E+02 I *.J - CtUK en

gy vvO~-~

Intake Tunnel Concrete Backaround 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+021 3 INTAK E IU 1012/2003 13:05 1 3.37E+02 60 SCL Unshielded i - - 3.37E+02 4 INTAK N 1P 10/212003 13:06 1 2.35E+02 60 SCL Shielded 2.35E+02 5 INTAK NU 10212003 13:07 1 2.77E+02 60 SCL Unshielded i 2.77E+02 6 INTAKXN IP 10/2/2003 13:09 1 2.85E+02 60 SCL Shielded 2.85E+02 7 INTAK XN IU 101212003 13:10 1 4.30E+02 60 SCL Unshielded 4.30E+02 8 INTAKT 1P 10/212003 13:12 1 2.49E+02 60 SCL Shielded 2.49E+02 9 INTAKT1U 10/2/2003 13:13 1 3.86E+02 60 SCL Unshielded _ 3.86E+02 10 INTAK S 1P 10/2/2003 13:15 1 2.73E+02 60 SCL Shielded 2.73E+02 11 INTAKS IU 10/2/2003 13:16 1 2.95E+02 60 SCL Unshielded 2.95E+02 12 INTAKW1P 101/22003 13:17 1 1.98E+02 60 SCL Shielded 1.98E+02 13 INTAKW1U 101212003 13:18 1 2.90E+02 60 SCL Unshielded ___ 2.90E+02 14 INTAKXS 1P 10/2/2003 13:20 1 2.98E+02 60 SCL Shielded 2.98E+02 15 INTAKXS 1U 1012/2003 13:21 1 3.65E+02 60 SCL Unshielded Pi 3.65E+02 Shielded Unshielded Minimum = 1.98E+02 2.77E+02.

Maximumi 2.98E+02 4.30E+02 Mean > 2.55E+02 3.40E+02 Slqma 3.38E+0 1 5.68E+01 ATTACH-MENT / o *. .

ysii 0- kLv Intake Tunnel Concrete Background Measurements - Nal Instrument 126188 RR9291 Time Detector Counts Count Time (sec) Mode Designator FSS-337 1 INTAKT 1 10/2/2003 13:23 4 5.70E+01 60 SCL @4"' - 5.70E+01 2 INTAK E 1 10/2/2003 13:24 4 1.70E+02 60 SCL @4"' y 1.70E+02 3 INTAK N 1 1012/2003 13:26 4 8.60E+01 60 SCL @4"' -y 8.60E+01 4 INTAKXN 1 10/212003 13:27 4 6.30E+01 60 SCL @4'" y 6.30E+01 5 INTAK S 1 1012/2003 13:29 4 1.04E+02 60 SCL @ 4"' y 1.04E+02 6 INTAK W 1 10/212003 13:30 4 1.08E+02 60 SCL @ 4"' _ 1.08E+02 7 INTAK XS 1 10/2/2003 13:31 4 8.40E+01 60 SCL @ 4'" Y 8.40E+01 Minimum 5.70E+01 Maximum 41.70E+02 Mean, 9.60E+01 Siqmaz 4 3.77E+01 ATTACHMENT IL - /

L11 0f-Beta Scan Measurement MDC Calculation Steel in Seal Chamber 3 Ei:=-.509%33.96364 E5:=.5 b :=158 pO:=0.5 W d:=8.8 d :=1.38 A :=100

-=4 ObservationInterval (seconds) o Sr Si. ObservationInterval (seconds) s (b o6)

• 60 b 1 = 10.5 Counts in observationInterval C:= I (Ei.ES lo@)4 C=17.474 ADCR i := (db 4) ° VM- .. net counts per minute MDCR i +b =225.182 gross counts per minute AfDCR i

- = 16.8 net counts per minute in observation interval

°i MDCscan :=C.MDCR i AfDCscan = 1.174-*10 dpm per 100 cm2 MARSSIM. Pages 6-38 to 6-43 3 ATTACHMENT / wL-. l I 21111003

I/7 0- 0-Beta Scan Measurement MDC Calculation Concrete in Seal Chambers

--:=.509-.33%96364 b :=244 P:= 0 .S 8.

Wd:=& Sr :=2.2 d := 1.38 es =5 ad A :=100 d=4 Observation Interval (seconds) Og -

Observation Interval (seconds)

Sr r

(b o ;)

60

= 081 b i = 16.3 Counts in observationInterval C:= I (fir-s 100)  ;;

C=17.474 AfDCRi (dig) 60 MMR =3.5 1 net counts per minute MDCR i+ b =327.487 gross counts per minute MD CYi

__ _= 20.9 net counts per minute in observation interval Gi M1DCscan:=C.MDCRj MDCscan = 1.459.)O, dpm per 100 cm MARSSIK Pages 6-38 to 643 3 ATTACHMENI__ 11/12/2003

vk 4;Ji where:

b = backgroundcountsper minute bi= backgroundcounts in observation interval p = human performancefactor Wd = detector width in centimeters S. = scan rate in centimetersper second d = index ofsensitivity (Table 6.5 MARSSIM), 1.38 = 95% ofcorrect detection's, 60%falsepositives MDCSCaJ = Minimum Detectable Concentrationfor scanning (dpm/1100 square centimeters)

C = constant used to convert MDCR to MDC e, -instrument efficiency (counts/emission) a5=source efficiency (emissions/disintegration)

A = instrumentphysical probe area (in square centimeters)

MARS! SIM. Pages 6-38 to 6-43 4 ATTACHMENT /ZI v 11/12/2003

L11.1 77 0--_6y_

Nurnber Saxton Nuclear Experimental Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual I E900O-IMP-4-520.fl6 Tilte Revision No.

Survey Unit Inspection in Support of FSS Design 0 EXHIBIT 3 Surface Measurement Test Area (SMTA) Data Sheet ORIGINAL

, T-V SECTION t'-DESCRIPTiON-,:, .

SMTA Number SMTA - S R .. Survey Unit Number 3 SMTA Location SECL cUbei vWeA41lI Survey Unit Inspector r& Date Jo Il l Time j1-q2_

"  :  ; SECTION 2-CALIPER INFORMATION & PERSONNEL INVCOLVED ., -,. . .'-

I Caliper Manufacturer /l i4tA OYl Caliper Model Number C Caliper Serial Number l 7 &_ &-7. Calibration Due Date (as applicable) j ,.

Rad Con Technician l ,4I Date lIA- Time l M-Survey Unit Inspector Approval i n.'1z-' ' Date it k Jo /

, SECTION 3 - MEASUREMENT RESULTS SMTA Grid Map & Measurement Results in Units of mm Comments (Insert Results in White Blocks Below) Comments

. "7 " , '49 25 31 § o j.J jr-LS50 4 T

~. O* 11

• oqt 2o 1.0 bt 'st5PCLrcf

.;<t p9. -. 4;lu

- ' ... '..... . . .. . . ,. , . Vk

't-2 94

-O o 3 o, aI1" o 1

, iA i, oj 7.3 q.6 g C0' 036 \-o.3 ct d.io i

~~~~<6'~ ~3___29__________ 1

_ ~ t - -

Average Measurement I.~ mm Additional Measurements Required S'SSg -(II 33.7 3 I - -L- 3 A.TTACMN /

55 V-1<g53.0 S I I "." )

S2s-7-oM 1 (5-VL Xs" ATTACHIMENT_ /3 -

9 ZG 39Vd 8331Nnd9 1t8ESE9018 6Z:91 E00Z/90/1T

30 d 6/

Number Saxton Nuclear ExperiJGQelXAL SAXTON NUCLEAR I Facility Policy and Procedure Manual E900-lMP-4520.06 TrUe Revisin No.

Survey Unit Inspection in Support of FSS Design O0 EXHIBIT 3 Surface Measurement Test Area (SMTA) Data Sheet

',.~-. .:SECTIONI - DESCRIPTION - . o SMTA Number SMTA- 55I?-2-J l Survey Unit Number :55 -

SMTA Location SECA Lcvie 46 7,z

• SV Survey Unit Inspector l 5J L- Date l /( l Time l /Vo SECTION 2 - CALIPER INFORMATION & PERSONNEL INVOLVED Caliper Manufacturer IWA-C.- l Caliper Model Number Cs) -G C5 Caliper Serial Number 7G3 S 3 Calibration Due Date (as applicable) v k Rad Con Technician I ,1- Date Time l4 Survey Unit Inspector Approval l ttSIL Date 8 II

'0

. SECTION S - WASUREMENT RESULTS SMTA Grid Map & Measurement Results in Units of mm  ;

(Insert Results in White Blocks Below) Comments

-. 1 . @ `7 . 13 19 25 31

- 7~ ~ in*~ ~5 'Th,'ic~Lz&'& ~3VL5 4.-4'

< f ~g ,- .fr 5. e c-q vlzv¢tt vr, i sUeT

-  % f2 - - -2

,;'>.~~: ,-.21 27 .

¢9..:;.S'.; 33,i

-C Y11- Z.g

.P-b-i .10- ~ 1  ; 22 . 28 ' 34' i~ .1 '\Z9 I* i M 1 Z.7 6 . 17. 23 29 35 ^

9-- *1J~

7. . .7. ls 3.e- 7 1 . ._3, Average Measurement _ IL mmI

&%W1 Additional Measurements Required 5Sr-- - o- 11 C 2) 1 j vS5 Y -2.OIL.J _72 ( ^ 4-)l)f 55 g, L-Ac13 / Li T MCE 7 1- y5.,ATTACHMENT.. 3 9

I £1/ 0 Number 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 3 C;I UAL Surface Measurement Test Area (SMTA) Data Sheet V l

. .'.SECTION 1-DESCRIPTION - - -'

SMTA Number SMTA- -3 Survey Unit Number 5S s -3 SMTA Location Sf L C4gb-_ ' 3 Survey Unit Inspector Q5\ Sko J Date to

( 063 Time l 160 t;;7;97 " -. SECTION 2 - CALIPER INFORMATION & PERSONNEL INVOLVED Caliper Manufacturer A , vC) Caliper Model Number l C 4 C Caliper Serial Number l -7 G3 5 9j3 Calibration Due Date (as applicable) ,v h-Rad Con Technician I v4- Date lv 4- Time l Survey Unit Inspector Approval l. msfsk,. . Date I\ 10 O)

- SECTION 3 - mdaSUREMENT RESULTS SMTA Grid Map & Measurement Results in Units of mm C (Insert Results in White Blocks Below) Comments 2j9y '* l :3j 1 49 25* ' 31 1 V T uA T

,Y-- 8.14 20 26 32.

31- 7' i 2-3r 30zi .

1O8 46 22 28 34 32i z /' 2?7} Z7Gc

'Z el 1 flF -3C.c Z5,2- 9J It 25 U)3¢ 176- i.23 2r 3 2.. 76a 754 0 3 Average Measurement 7lI mm Additional Measurements Required 55S- 3 -cc; > I Z& e6w d SS$IV -01 > f 7 Wg, s tt1-1 t'Y2'/

II / '.3-ATACHMENT 9

.. w Number Saxton Nuclear Experimerntal Corporation SAXTON NUCLEAR Facility Policy and Procedure Manual E900-IMP-4520.06 Tie Revision No.

Survey Unit Inspection in Support of FSS Design 0 EXHIBIT 1 ORIGINAL Survey Unit Inspection Check Sheet

,. .. _SECTION 1- SURVEY UNIT INSPECTION DESCRIPTION Survey Unit # B y_ Survey Unit Location l Sclb- C Date I 1,103 i Time j1j Inspection Team Members i

• - - SECTION 2 - SURVEY UNIT INSPECTION SCOPE Inspection Requirements (Check the appropriate Yes/No answer.) l Yes j N IA

1. Have sufficient surveys (i.e.. post remediation. charactenzation. etc.) been obtained for the survey unit? JV 'Jl

2. Do the surveys (from Question 1) demonstrate that the survey unit will most likely pass the FSS? ,/ I l

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

4. Have all tools. non-permanent equipment. and material not needed to perform the FSS been removed? I 1

5. Are the survey surfaces relatively free of loose debris (i.e.. din, concrete dust, metal filings. etc.)? j 1/ _

6. Are the survey surfaces relatively free of liquids (i.e.. water, moisture. oil. etc.)? 94- rag Ad V.IP o2.tL ,tL l

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.) [\ I

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

10. Are the survey surfaces easily accessible? (No scaffolding, high reach, etc. is needed to perform the FSS) = j.

11. Is lighting adequate to perform the FSS? 1/

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

13. Have photographs been taken showing the overall condition of the area? V

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 andlor justifications in the 'Comments section below. Attach additional sheets as necessary.

Comments: CD Sv£v('Tuw t$

Survey Unit Inspector (print/sign) l s3 % t Il A Date l h 6/0-3 Survey Designer (print/sign) (5i)> o- c ,h4 . l Date l a aU V 4 "r- ae 11101 6

8 , 0 ~,'X L<ai! P _513 Numbe 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 a EXHIBIT I Survey Unit Inspection Check Sheet

.-SECTION 1 - SURVEY UNIT INSPECTION DESCRIPTION Survey Unit # l S - Survey Unit Location i CLMA-V #

Date l11 ) ITime I/ Inspection Team Members l ,

- SECTION 2 - SURVEY UNIT INSPECTION SCOPE Inspection Requirements (Check the appropriate Yes/No answer.) I Yes No NIA

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

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

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

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

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

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

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.)

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

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

11. Is lighting adequate to perform the FSS? l Iv/

12. Is the area industrially safe to perform the FSS? (Evaluate potential fadl & trip hazards, confined spaces. etc.) j /

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 andor justifications in the Comments section below. Attach additional sheets as necessary.

Comments: t -t- S4 SW- 'a'me VK/ 4-~

Survey Unit Inspector (print/sign) Date l I l, Survey Designer (print/sign) f-J@ JDate 17 o.3B0e W

/ 6 .

6

5$3' C.)

ORIGINAL Saxton Nuclear Exp.erimental Corporation Number SAXTON NUCLEAR Facility Policy and Procedure Manual E900-IMP-4520.06 Tritle ReiinNo.

Survey Unit Inspection in Support of FSS Design o EXHIBIT I Survey Unit Inspection Check Sheet

'  ; .-.:.;,-SECTION I - SURVEY UNIT INSPECTION DESCRIPTION.

Survey Unit # 5; S 5 Survey Unit Location l S E A L C A- b - 3 Date \\\l3o- Time l Inspection Team Members

' .SECTION 2 - SURVEY UNIT INSPECTION SCOPE Inspection Requirements (Check the appropriate Yes/No answer.) FYes No N/A

1. Have sufficient surveys (i.e.. post remediation. charactenzation. etc.) been obtained for the survey unit? JVI"l

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

3. Is the physical work (i.e.. remediation & housekeeping) in or around the survey unit complete? 1l/'

4. Have all tools. non-permanent equipment. and material not needed to perform the FSS been removed? l f 7 -

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

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

7. Are the survey surfaces free of all paint. which has the potential to shield radiation? l /

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

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

10. Are the survey surfaces easily accessible? (No scaffolding, high reach, etc. is needed to perform the FSS) _ 4

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.) ) V

13. Have photographs been taken showing the overall condition of the area? H

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: ().S J¢.N'C(' U Ltj 5 COplPI rt j C I 6l X4 j

/9Nvctett /3-;

Survey Unit Inspector (print/sign) l j /Z, e l Date \ 13/-

Survey Designer (print/sign) Il4 v -4Date l///;

ILIJ 6

s~o-a Site Report Site Summary Site Name: Seal Chambers 1, 2 and 3 Planner(s): BHB Contaminant Summary NOTE: Surface soil DCGLw units are pCig.

Building surface DCGLw units are dprnm100 cm2.

Screening Contaminant Type DCGLw Value Used? Area (m') Area Factor Gross Activity Building Surface 6,407 No 36 1 25 1.2 16 1.5 9 2 4 3.4 1 10.1 COMPASS vl.0.0 1111012003 Page 1 ATTACHMENT 17- t

Building Surface Survey Plan Survey Plan Summary Site: Seal Chambers 1, 2 and 3 Planner(s): BHB Survey Unit Name: Seal Chamber 1 Comments:

Area (m2 ): 73 Classification: I Selected Test: WRS Estimated Sigma (cpm): 68.1 DCGL (cpm): 646 Sample Size (N/2): 8 LBGR (cpm): 450 Estimated Conc. (cpm): 21 Alpha: 0.050 Estimated Power 1.00 Beta: 0.100 EMC Sample Size (N): 8 Prospective Power Curve

_ 1 I -x I I 0.9 . I P.. .- t = I

_ 0.8

- 0.7 1~ _ _ _ _ __ =-

1-=1 iv

_ 0.6

r-0.4 I - I-I =_- __

- =

' 0.3

• i

- = _ - _ __ - _ _=

L 0.1 I-___g _=_

O.

I- _ __ = =_ __

0 100 200 300 400 SOO 600 700 800 Net Beta (cpm)

- PLBwer - DCGL - Estimated Power

- LB( IR

• l-beta COMPASS v1.0.0 A ACE11+/-1ZT2003 Page 1 ATTACHMENi-T L't- .

BS 7c a Building Surface Survey Plan Contaminant Summary DCGLw Contaminant (dpm/100 cm')

Gross Activity 6,407 Beta Instrumentation Summary 2

Gross Beta DCGLw (dpm/100 cm ): 6,407 Total Efficiency: 0.08 Gross Beta DCGLw (cpm): 646 ID Type Mode Area (cm')

11 GFPC Beta 126 Contaminant Energy' Fraction' Inst. Eff. Surf. Eff. Total Eff.

Gross Activity 187.87 1.0000 0.16 0.50 0.0810

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

2Activity fraction Gross Survey Unit Mean (cpm): 244

• 68 (1-sigma)

Count Time (min): 1 Number of Average Standard MDC Material BKG Counts (cpm) Deviation (cpm) (dpm/100 cm')

Concrete 7 223 56.8 719 COMPASS v1.0.0 11)1212003 Page 2 ATTACHMENT 1 - 3

II * .i * ~P i a £ S . __ _ I _rl.._ __ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

A, a

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

1)Enter Scanning Instrument Efficienciei 2)Enter Scan MDC Parameters I 3) View EMC Results

.1' Scan MDC Required per Contaminant Contaminant DCGLwb I Area Factor Scan MDC Required l

. Gross Activity 6,407 1.99 12.750 C) iii I I Statistical Design Hot Spot Design 1

1

.M N/2: I 8 Actual Scan MDCO I 1.411 BoundedArea(ml: [ 9.1 Area Factor I N/A K), AreaFactor. 1.99 Bounded Area (m1): I N/A 1, ji,¶ DCGLw- l 6,407 Post-EMC N12: I a Scan MDCRequired*: l 12.750 1[011111IM Mx

Is dpm/1 00 cm a'V'4 IJ

• No additional samples are requred because the actual

• A.4 II .. . . . . . .

scan MDC isless than the DCGLw for each contaminant.

P Enable Trainini -E.[1_ i]1 vl.0.0

s i d6-r-Building Surface Survey Plan Survey Plan Summary Site: Seal Chambers 1, 2 and 3 Planner(s): BHB Survey Unit Name: Seal Chamber 2 Comments:

Area (m2 ): 71 Classification: 1 Selected Test: WRS Estimated Sigma (cpm): 68.1 DCGL (cpm): 646 Sample Size (N/2): 8 LBGR (cpm): 450 Estimated Conc. (cpm): 21 Alpha: 0.050 Estimated Power: 1.00 Beta: 0.100 EMC Sample Size (N): 8 Prospective Power Curve V -I I rn 09 I I 0.8c1 0.8 ____ ______

4. p- __ __- __

C

'0.6 --

Z0.6

'.05 I0- _ ___ __

- 04 0 - _ =__

c . -

s0. - _ __

01 E> . = =_ = =_

0 100 200 300 400 500 600 700 800 Net Beta (cpm)

- Power -DCGL - '- Estirnated Power

- LBGR

• 1-beta COMPASS v1.0.0 11/1212003 Page 1 A1TACHME E / l- .

6 0 otoA Building Surface Survey Plan Contaminant Summary DCGLw Contaminant (dpmJ100 cm 2)

Gross Activity 6,407 Beta Instrumentation Summary Gross Beta DCGLw (dpm/100 cm): 6,407 Total Efficiency: 0.08 Gross Beta DCGLw (cpm): 646 2

ID Type Mode Area (cm )

11 GFPC Beta 126 Contaminant Energy' Fraction 2 Inst Eff. Surf. Eff. Total Eff.

Gross Activity 187.87 1.0000 0.16 0.50 0.0810

'Average beta energy (keV) [NiA Indicates alpha emission]

2 Acivity fraction Gross Survey Unit Mean (cpm): 244* 68 (1-sigma)

Count Time (min): 1 Number of Average Standard MDC Material BKG Counts (cpm) Deviation (cpm) (dpm/100 cm2)

Concrete 7 223 56.8 719 COMPASS v1.0.0 1111212003 Page 2 A7IACHMEtN7 I L( -

L9E3 Elevated Measurement Comparison (EMC) for Beta j*i Followthe order of each tab below to perform the EMC.

1I Enter Scanning Instrument Efficiencie] 2I Enter Scen MDC Parameters 1 s3View EMC Resultt Ee Scan MDC Required per Contaminant Contaminant I DCGLWA I Area Factor I Scan MDC Required* l Gross Activity 6,407 2.03 13,006

-I 9r.

paLl.

iii

-1 Statistical Design Hot Spot Design N/2: [I Actual Scan MDC: r 1,411 Bounded Area (m): 8 8.9 Area Factor l N/A AreaFactor 2.03 Bounded Area (ml: N/A 49 I H DCGLW-. l 6,407 Post-EMCNJ2: l T ScanMDCRequiredc r 13.006 M

• dpm/1 00 - m2 No addtional samples are required because the actual LI scan MDC isless than the DCGLw for each It I ji . contaminant.

P Enable Trainin OK l

• I) It i v1.0.0

6- 6L Ud Building Surface Survey Plan Survey Plan Summary Site: Seal Chambers 1, 2 and 3 Planner(s): BHB Survey Unit Name: Seal Chamber 3 Comments:

Area (m2): 109 Classification: 1 Selected Test: WRS Estimated Sigma (cpm): 68.1 DCGL (cpm): 646 Sample Size (N/2): 8 LBGR (cpm): 450 Estimated Conc. (cpm): 91.5 Alpha: 0.050 Estimated Power 1.00 Beta: 0.100 EMC Sample Size (N): 8 Prospective Power Curve

_ 1 Y 09 'I I I tA+H 1 t 0.8 Qi 0.7 'I I l \Il t 0.6

• ' 0.5

_ 0.4 el TI Tv l e:. 0.3 6~02 5 0.1 1 I T I T_ k l l O.

0 100 200 300 400 500 600 700 800 NetBeta (cpm)

- Power - DCGL - - Estimated Power

- LBGR

• 1-beta COMPASS v1.0.0 COMPSS v.0.01111212003 Page 1 A7FAcHimEvL;i-...-&-

0 IL Building Surface Survey Plan Contaminant Summary DCGLw Contaminant (dpmlO00 cm2)

Gross Activity 6,407 Beta Instrumentation Summary Gross Beta DCGLw (dpml1 00 cm): 6,407 Total Efficiency: 0.08 Gross Beta DCGLw (cpm): 646 ID Type Mode Area (cm2) 11 GFPC Beta 126 Contaminant Energy 1 Fraction2 Inst Eff. Surf. Eff. Total Eff.

Gross Activity 187.87 1.0000 0.16 0.50 0.0810 Average beta energy (keV) [N/A indicates alpha emission]

'Activity fraction Gross Survey Unit Mean (cpm): 244i 68 (1-sigma)

Count Time (min): I Number of Average Standard MDC Material BKG Counts (cpm) Deviation (cpm) (dpml100 cm')

Steel 4 152.5 8.3 599 COMPASS v1.0.0 1111212003 Page 2 A1TAG~MEN ~ -

- ,*, I.

MWIM11HII&L II , II I P I I 'I I - I

=-

-7 E Elevated Measurement Comparison (EMC) for Beta Follow the order of each tab below to perform the EMC.

11 Enter Scanning Instrument Efficiencie4 21 Enter Scan MDC Parameters 3)View EMC Results I Scan MDC Required per Contaminant Contaminant DCGLw l Area Factor I Scan MDC Required I Gross Activity 6,407 1.66 10,636 I,'

Statistical Design Hot Spot Design 1.

4..- N/2: l 3 Actual Scan MDC?: l 1,167 Bounded Area(m5: l 13.7 Area Factor I N/A F AreaFactor l 1.66 Bounded Area(ml:: l N/A DCGLw- 1 6,407 Post-EMC N/2: I 8 I. 4%.

Scan MDC Required' l 10.636 M_

w 1 XI AX *dpm/l 00 cm' No additional samples are required because the actual scan MDC isless than the DCGLw for each M~) .contarminant 11%

P Enable Traininc I t II , 'il.0.0 0 1-1