Text

Rev. 0 to Calculation E900-04-007, Discharge Tunnel Survey Design for Class 1 Areas, Appendix a to Final Status Survey Report for Saxton Nuclear Experimental Corp Saxton Steam Generating Station Structural Surfaces -Discharge Tunnel SSI, SS
	ML052140065
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Site:	Saxton File:GPU Nuclear icon.png
Issue date:	05/13/2004
From:	Brosey B; FirstEnergy Corp
To:	; Office of Nuclear Reactor Regulation
References
	E900-04-007, Rev 0
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Appendix A Class 1 Areas Survey Design

SNEC CALCULATION COVER SHEET CALCULATION DESCRIPTION Calculation Number Revision Number Effectivepate Page Number E900-04-007 0 1 of 1/

Subject Discharge Tunnel Survey Design for Class 1 Areas Question I - Is this calculation defined as 'In QA Scope*? Refer to definition 3.5. Yes 0 No ]

Question 2- Is this calculation defined as a 'Design Calculation'? Refer to definitions 3.2 and 3.3. Yes 0 No ED Question 3 - Does the calculation have the potential to affect an SSC as described in the USAR? Yes El No 0 NOTES: If a 'Yes' answer Isobtained 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 Originator's 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 SSCs may be implemented by the TR.

DESCRIPTION OF REVISION - S ORIGINAL

_ :--::.-;- APPROVALSIGNATURES __:°____

Calculation Originator B. BroseyI Date IC io i1 Technical Reviewer P. DonnachielW) Date 5 o/

Additional Review A. Paynterl o k Date Additional Review Date SNEC Management Approval Date

SNEC CALCULATION SHEET -

Calculation Number Revision Number Page Number E900-04-007 0 Page 2 ofj/1 Subject Discharge Tunnel Survey Design for Class I Areas 1.0 PURPOSE 1.1 The purpose of this calculation is to develop a survey design for Class I surfaces within the Discharge Tunnel. This is a partial survey that addresses areas bypassed by Shonka Research Associates (SRA) (Reference 3.1) during their scan survey of this structure. The entire Class 1 survey areas of the Discharge Tunnel are listed below.

Survey Units Location Material Type Classification Area (mA2)

SS1 Floor of DT to 150 f Concrete 1 109.5 SS4 Ceiling of Discharge Tunnel to 150 ft Concrete 1 107.7 SS6-1 South Wall of DT to 150 f Concrete 1 118 SS6-2 North Wall of DT to 150 It Concrete - 127.5 SS6-2 East Wall (included with the North Wall) Concrete I 7.4 NOTE 1: There is very little exposed steel inthese survey units (-< 1%of the total area).

NOTE 2: This is the total surface for the Class I areas Inthe Discharge Tunnel. It does not include the transition area between the Discharge Tunnel, the Spray Pump Pit, Seal Chambers or the access area into the Discharge Tunnel.

2.0

SUMMARY

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

General survey instructions:

Scan the areas listed on Attachment 1-1 using a GFPC detector.

Scan the same areas using a 2' by 2" Nal detector.

Scan any additional locations within the Class I areas as directed by SNEC site management or as deemed appropriate when bounding an area.

Locate the randomly placed static measurement points for these survey units and make a 1 minute static measurement at each location using a GFPC detector.

Mark any location for potential sampling determined to be above the action level defined for a Nal detector LAW Section 2.2.

2.1 Step 1 - GFPC Scanninq and Static Measurements 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 Scanning parameters are as shown in the following Table.

Scan Coverage % Scan Speed (cmlsecT Detector Geonetry I 100% of marked areasl 2.2 Contact

'Marked surfaces are identified In Class I areas only.

Areas bypassed by SRA are shown on Attachment 2-1 through 2-5. Each of these areas have been identified by reviewing the draft SRA survey report for the Discharge Tunnel and then documenting all bypassed areas. In addition, SRA and SNEC personnel have performed walk-downs of the Discharge Tunnel and determined additional locations requiring follow-up survey work. Each of these areas were then assigned a specific label derived from the survey unit where they reside.

The total surface area of these bypassed areas is -112 square meters.

SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-04-007 0 Page 3ofJ.L Subject Discharge Tunnel Survey Design for Class I Areas NOTE Steel components/hardware that exhibit severely corroded surfaces (scaled or bubbled surfaces) should be scanned using a Nal detector. See Section 2.2 for instructions on scanning these components or structures.

2.1.3 Additional surface areas may be scanned lAW site management direction or to more completely bound an elevated area (using Nal or GFPC). If additional areas are scanned:

locate the area on a diagram and determine the approximate dimensions.

. Ensure the area has been inspected lAW Reference 3.2 and meets the requirements and general criteria of this survey design. Contact the cognizant GRCS with any questions regarding these criteria.

Document the addition of this area in the survey results.

2.1.4 The following Table shows the applicable Discharge Tunnel DCGLw values.

Surface GA DCGLw (dpm/100 cm 2) Volumetric DCGLw (pCig-Cs-137) 8968 (A.L= 6726) 6.52 (AL.= 4.89)

NOTE: A.L is the site Administrative Umit (75% of effective DCGLw) 2.1.5 The following is the calculated GFPC detection efficiency for this survey design.

GFPC Detection Efficiency Data El es %Cs-137 Efficiency Loss Factor l countsldisintegration l 0.478 0.5 0.982 0.23 0.054 2.1.6 GFPC detectors exhibiting an instrument efficiency (ei) less than 0.478 should not be used for this survey work.

2.1.7 The following is the Compass output values for this survey design.

MDCsta~tic MDCscan

-(pm/10cm 2) m C Action Level Assigned During Phase I Scanning (ncpm) 1,251 2,466 300

'As calculated by the Compass computer program assuming a background value of 266 cpm (corrected Williamsburg data).

2.1.8 The number of necessary static measurement points (see Attachment 3-1 through 3-4), was determined using the Compass computer program (Reference 3.3).

Compass output is presented in Attachment 4-1 through 4-13. The number of static measurement points per survey unit was determined to be ten (10). VSP (Reference 3.4), is then used to plot these points on area diagrams. Five (5) additional points are added so that the total number of points per survey unit for this design is fifteen (15).

2.1.9 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 112 minute duration to identify the actual count rate from the elevated location.

SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-04-007 0 Page 4 of 11 Subject Discharge Tunnel Survey Design for Class I Areas 2.1.10 Areas greater than the calculated DCGLw (424 ncpm) must be identified, documented, marked, and bounded to include an area estimate.

NOTE lf remediation actions are taken as a result of this survey, this survey design must be revised or re-written entirely. Review results thoroughlybefore taking this action.

2.1.11 Any location or hardware that cannot be adequately surveyed with the GFPC as described in the note below Section 2.1.2, should be identified for Nal scanning lAW Section 2.2.

2.2 Nal Scanning and Sampling 2.2.1 The purpose of Nal scanning is to identify elevated measurement locations in difficult to reach areas or on highly corroded steel surfaces and mark them for potential sampling. The following criteria apply:

2.2.1.1 A minimum of 100% scan coverage of the SRA bypassed areas is required.

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 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 300 cross cpm. When an area is thought to be at this level during phase one scanning, the detector should be held stationary for at least 15 seconds to record the actual count rate. If the area is confirmed to be above the action level, the location should be marked for potential sampling.

These areas shall be bounded and documented.

2.2.2 The conversion factor for the Nal used in cpm/mRlh, shall not be less than 208.000 cpmlmR/h (see Attachment 5-1 to 5-3 for a typical Nal instrument calibration report).

2.2.3 IAW site management instruction, sample concrete at any location above the action level cited is Section 2.2.1.3. 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).

2.2.4 For steel surfaces above the action level, 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).

Core bore radionuclide concentrations will be averaged and an assessment will be made as to average depth of the contaminant. MicroShield will be used to determine annual dose per radionuclide. LTP Chapter 6, Equation 6-1 will then be used to determine the unity fraction for the surface and volume contaminant fractions.

SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-04-007 0 Page 5 ofJ¢ Subject Discharge Tunnel Survey Design for Class I Areas

3.0 REFERENCES

3.1 Shonka Research Associates, Inc., 'Final Report for SCM Survey of Saxton Nuclear Experimental Corporation", Revision 0, October 17, 2003.

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

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

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

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

3.7 SNEC Calculation No. E900-03-016, "Shonka Discharge Tunnel and Intake Tunnels FSS Survey Design", 7-28-03.

3.8 Plan SNEC Facility License Termination Plan.

3.9 GPU Nuclear, SNEC Facility, SSGS Footprint, Drawing, SNECRM-039, 040 & 041.

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".

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

3.15 NUREG-1575, "Multi-Agency Radiation Survey and Site Investigation Manual", August, 2000.

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

4.0 ASSUMPTIONS AND BASIC DATA 4.1 Remediation History Remediation of the Discharge Tunnel began with removal of ground water in this semi-isolated below grade structure. Gross decontamination followed to include the removal of contaminated hardware and piping that passed into and through the Seal 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 Discharge Tunnel. Because the Discharge Tunnel is below grade level, surface water in-leakage is a problem and some patching of cracked concrete was necessary to prepare this area for final status survey work.

7 SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-04-007 0 Page 6 ofJL1 Subject Discharge Tunnel Survey Design for Class I Areas Surface cleaning of the Discharge Tunnel was performed by removing a thickness of concrete in affected areas. Core bores were then taken to determine the depth of the contamination and to estimate remediation effectiveness. Remaining piping systems were sampled and gamma scanned to determine the existing concentrations. 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 flushing

pumping

hand removal of solids and sediment 4.2 Cs-137's detection efficiency has been checked by SNEC personnel using ISO standard 7503-1 methodology (Reference 3.5). The SNEC facility uses only the lowest reported GFPC efficiency for any of the instruments available for the survey work as input to the survey design process. Attachment 6-1, is an example of an instrument efficiency check sheet showing an instrument efficiency of 0.509. Detectors with values less then 0.478 for the instrument efficiency should not be used for this work. An ISO standard value of 0.5 is used as the source efficiency.

4.3 A GFPC detector stand-off distance of 2.7" is assumed for all areas to compensate for rough surfaces in each survey unit. This factor corrects the overall efficiency by a factor of 0.23 (Reference 3.6), as shown on Attachment 7-1. 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 a residual source term will be overestimated.

4.4 The overall counting efficiency for this survey design assumes a mix ratio as developed in Attachment 8-1 through 8-6.

4.5 The instrument and source efficiency is assumed to be as shown in Section 2.1.5. The detection efficiency is based on the instruments response to Cs-137. All other nuclides except Ni-63 are less than 1% of the total mix lAW Attachment 8. Ni-63 provides no additional counting efficiency. A rough surface efficiency correction factor is also employed to ensure a representative efficiency is used for weathered, broken or remediated concrete surface. From Attachment 1-1 a worst case surface gouge depth is listed as 2.7 inches.

From Reference 3.6 and Attachment 7-1 this gap would reduce the overall efficiency by a factor of -0.23. The resulting efficiency is then 0.054 cts/dis.

4.6 The detectors physical probe area is 126 cm2, and the instrument is calibrated to the same source area for Cs-1 37. The gross activity DCGLw is taken to be 6,726 dpm/100 cm2 x (126 cm2 physical probe area/100 cm2) = 8,475 x (0.982 disintegration of Cs-137/ disintegration in mix) x sj (0.478) x vs (0.5) x 0.23 (distance factor) which yields -457 net cpm above background (Compass calculates 424 ncpm as the gross beta DCGLw). The 0.054 count per disintegration counting efficiency considers only the Cs-137 contaminant present in the sample material matrix, and is calculated by: Ej (0.478) x ce(0.5) x 0.982 disintegration of Cs-137/disintegration in mix x 0.23 (efficiency loss factor due to distance from surface) =

0.054 ctsfdisintegration.

_ SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-04-007 0 Page 7 of IC Subject Discharge Tunnel Survey Design for Class I Areas 4.7 Badly corroded steel surfaces will be scanned using a 2" x 2" Nal detector. These detectors are set-up and calibrated with a Cs-137 window setting typical to that described in Attachment 5-1 to 5-3.

4.8 MicroShield models containing Cs-137 were developed for this survey design when scanning with a Nal detector (Attachment 9-5 to 9-7). One slab model was developed for scanning concrete surfaces, and one disk source for surface deposition.

1) Model 1 - a 1 thick slab of concrete 12" in diameter, and

2) Model 2-a surface deposit (12" diameter), on a corroded surface 4.9 The modeled concentration used was 1 pCi/g Cs-137, and the density of concrete is assumed to be 2.35 glcc. Then the concentration of Cs-137 in the first model is 2.35g/cc x 1 pCi/g or 2.35E-06 uCi/cc of Cs-137 for the concrete model, and 1.OE-06 uCi/cm 2 for the surface model. The calculated MDCscan for these two models is shown in the following table for a typical windowed 2" by 2" Nal detector.

MatedialModel BKGND (cts/min) MDCscAN (pCUg) or dpm/100 cm' Concrete Slab 2.35 cc 100 Attachment 9-1 =3.74 Cii' Surface (0.125' Fe Coating) 100 Attachment 9-3 =4354 NOTE: Background is assumed to range from about 100 to 200 cpm Inthe Discharge Tunnel.

4.10 The results of the MicroShield modeling indicate that an exposure rate of approximately 7.865E-05 mR/h is obtained at a distance of 3" from the surface of the slab model, (2" inches from the face of the detector). 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".

4.11 The second MicroShield model of a surface deposition incorporates a Cs-137 concentration of 1 pCi/cm 2 (see Attachment 9-7). For this scenario, the modeled area is assumed to be a 12" diameter disk source. The activity is uniformly dispersed over the surface. The source is assumed to be a corroded steel plate. This model incorporates a 0.125" thickness of iron oxide (Fe2O3) to simulate a corroded steel surface. The resulting mR/h value was 1.501E-

05. Then the calculated pCi/cm 2 MDCscan is 19.6 pCi/cm2 (4354 dpm/100 cm2 ) for a background count rate of 100 cpm (see Attachment 9-1 to 9-4).

4.12 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.

4.13 The Discharge Tunnel variability results and the Williamsburg background measurements are used to estimate the actual background for a similar below grade concrete surface. The following correction was used to correct the Williamsburg concrete background data:

Mean Williamsburg concrete data = 211 cpm +/- 26.9 shielded, and

= 306 cpm +/- 34.5 unshielded Discharge Tunnel concrete data = 171 cpm +/- 19.3 shielded, and

= 297 cpm +/- 61.1 unshielded Difference in shielded readings = 211 - 171 = 40 cpm Mean Williamsburg unshielded data corrected = 306 - 40 cpm = 266 cpm +/- 34.5 cpm. The background data may be see on Attachment 10-1. The Discharge Tunnel variability measurements are shown on Attachment 11-1.

SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-04-007 0 Page 8 of LL Subject Discharge Tunnel Survey Design for Class I Areas 4.14 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), 0.054 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.

4.15 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 12-1 to 12-9).

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

4.17 No special measurements are included for this survey design.

4.18 The applicable SNEC site individual radionuclides and their associated DCGLw values are listed on Exhibit I of this calculation.

4.19 The survey design checklist is listed in Exhibit 2.

4.20 Diagrams shown in this survey design have been developed from Reference 3.9.

4.21 The decision error for this survey design is 0.05 for the a value and 0.1 for the J value.

4.22 The GFPC data will be evaluated IAW the WRS statistical testing criteria.

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 3.1. 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 (m=) AREA FACTOR 1 10.1 4 3.4 9 2 16 1.5 25 1.2 36 1

SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-04-007 0 Page 9ofJ11 Subject Discharge Tunnel Survey Design for Class I Areas 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, Areas in the Discharge Tunnel bypassed by SRA, 'Difficult to Survey Surface Areas".

6.2 Attachment 2-1 to 2-5, Diagrams of the Discharge Tunnel showing the areas requiring scanning.

6.3 Attachment 3-1 to 3-4, Diagrams of the Discharge Tunnel showing static measurement locations.

6.4 Attachment 4-1 to 4-13, are Compass output results for the Discharge Tunnel.

6.5 Attachment 5-1 to 5-3, is typical calibration information for a 2" by 2" Nal detector with a Cs-1 37 window setting.

6.6 Attachment 6-1, is typical calibration information for a GFPC detector.

6.7 Attachment 7-1, is a calculation result for used to determine efficiency loss for a GFPC detector as a function of distance from a source.

6.8 Attachment 8-1 to 8-6, are DCGL Calculation Logic sheets for the Discharge Tunnel area.

6.9 Attachment 9-1 to 9-4, are the calculation sheets for MDCscan values for a concrete slab and a surface deposit.

6.9.1 Attachment 9-5 to 9-7, are calculation sheets from MicroShield for both the slab and surface models used for determining the MDCscan values for a Nal detection system.

6.10 Attachment 10-1, is background measurements using a GFPC instrument in non-impacted at the old Williamsburg coal fired steam plant site.

6.11 Attachment 11-1, is site GFPC variability measurements from the Discharge Tunnel area.

6.12 Attachment 12-1 to 12-9, are sections of survey unit inspection reports for the Discharge Tunnel.

1" MSNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-04-007 I 0 Page 10 of I l Subject Discharge Tunnel Survey Design for Class 1 Areas Exhibit I SNEC Facility Individual Radionuclide DCGL Values (8) 25 mremly Limit 4 mremly Goal 25 mremly Limit (All Pathways) (Drinking Water)

Radionuclide Surface Area Open Land Areas Open Land Areas )

(dpm/100cm2 ) (Surface & Subsurface) (Surface & Subsurface)

(pClUg) (pClg)

Am-241 2.7E+01 9.9 2.3 C-14 3.7E+06 2 5.4 Co-60 7.1 E+03 3.5 67 Cs-137 2.8E+04 6.6 397 Eu-152 1.3E+04 10.1 1440 H-3 1.2E+08 132 31.1 Ni-63 1.8E+06 747 1.9E+04 Pu-238 3.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 mremly goal, only the DCGL values that constitute the 25 mremny regulatory limit will be controlled under this LTP and the NRC's approving license amendment.

(b) Listed values are from the subsurface model. These values are the most conservative values between the two models (i.e.,

surface &subsurface).

.. : SNEC CALCULATION SHEET Calculation Number Revision Number Page Number E900-0407 0 Page 11 of jL Subject Discharge Tunnel Survey Design for Class I Areas Exhibit 2 Survey Design Checklist (From Reference 3.5)

Calculation No. E900-04-007 lSS, SS4, SS6-1, and SS6-2 Status Reviewer ITEM REVIEW FOCUS (Circle One) initis & Date I Has a survey design calculation number been assigned and is a survey design summary 5)N/A /0 2 Are drawings/diagrams adequate for the subject area (drawings should have compass (?'esN/AI 2reA dr awi gsldi gr ams adequ te~ headings)? _ _ _ _ _

3 Are boundaries properly identified and is the survey area classification clearly indicated? (ei) NWA 4 Has the survey area(s) been properly divided into survey units lAW EXHIBIT 10YeW NIA 5 Are physical characteristics of the area/location or system documented? (i N/A 6 Is a remediation effectiveness discussion included? Ye N/A 7 Have characterization survey and/or sampling results been converted to units that are Ye iA comparable to applicable DCGL values?

8 Is survey and/or sampling data that was used for determining survey unit variance included?7 Ye)A 9 Is a description of the background reference areas (or materials) and their survey andlor (Iej WA 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? (g) N/A 11 WWill the condition of the survey area have an Impact on the survey design, and has the WA 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 NIA design?

13 Are all necessary supporting calculations and/or site procedures referenced or included? i jj _j 14 Has an effective DCGLw been identified for the survey unit(s)? Cei) N/A 15 Was the appropriate DCGLEMC included In the survey design calculation?

16 Has the statistical tests that will be used to evaluate the data been identified? NIA 17 Has an elevated measurement comparison been performed (Class I Area)? (es) WA 18 Has the decision error levels been identified and are the necessary justifications provided? {%ei N/A 19 Has scan instrumentation been identified along with the assigned scanning methodology? _i ___sNA 20 Has the scan rate been identified, and is the MDCscan adequate for the survey design?

21 Are special measurements e.g., in-situ gamma-ray spectroscopy required under this design, S and is the survey methodology, and evaluation methods described? -gg 22 Is survey instrumentation calibration data included and are detection sensitivities adequate? ( Y-s )N(A 23 Have the assigned sample and/or measurement locations been clearly identified on a diagram FeT) 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 so N/A clearly indicated?

25 For sample analysis, have the required MDA values been determined.?

26 Has any special sampling methodology been identified other than provided in Reference 6.3? 1 / ,p.

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

Discharge Tunnel Class I Areas Not Surveyed by SRA ROUGH OR DlfFICULT TO SURVEY SURFACE AREAS Weighted Depth Location Code Area (InchesA2) (Meters £2) Average Depth (mm) Inches Area Fraction Correction SS6-2-001A 234 0.1510 10.2 0.40 0.13% 0.001 SS6-2-002A 361 0.2329 14.2 0.56 0.21% 0.001 SS6-2-003A 52 0.0336 12.1 0.48 0.03% 0.000 SS6-2-004A 105 0.0677 13.3 0.52 0.06% 0.000 SS6-2-005A 280 0.1807 10.7 0.42 0.16% 0.001 SS6-24006A 56 0.0361 11.2 0.44 0.03% 0.000 SS6-2-007A 308 0.1987 11.3 0.44 0.18% 0.001 SS6-2-008A 66 0.0426 16.6 0.65 0.04% 0.000 SS6-2-009A 66 0.0426 14.9 0.59 0.04% 0.000 SS6-2-01OA 13923 8.9831 8.8 0.35 8.02% 0.028 SS6-2-011A 16 0.0103 12.6 0.50 0.01% 0.000 SS6-2-012A 33 0.0213 15.7 0.62 0.02% 0.000 SS6-2-013A 2130 1.3743 9.5 0.37 1.23% 0.005 SS6-2-014A 25 0.0161 7.2 0.28 0.01% 0.000 SS6-2-015A 216 0.1394 15.7 0.62 0.12% 0.001 SS6-2-016A 120 0.0774 10.1 0.40 0.07% 0.000 SS6-2-017A 33865 21.8497 31.75 1.25 19.51% 0.244 SS6-2-018A 11286 7.2817 6.35 0.25 6.50% 0.016 SS6-2-019A 3841 2.4782 6.35 0.25 2.21% 0.006 SS6-1-001A 432 0.2787 16.7 0.66 0.25% 0.002 SS6-1-002A 28 0.0181 11.2 0.44 0.02% 0.000 SS6-1-003A 381 0.2458 21.1 0.83 0.22% 0.002 SS6-1-004A 323 0.2084 7.9 0.31 0.19% 0.001 SS6-1-005A 81 0.0523 10.5 OA1 0.05% 0.000 SS6-1-006A 52 0.0336 30.1 1.19 0.03% 0.000 SS6-1-007A 20 0.0129 13.3 0.52 0.01% 0.000 SS6-1-008A 6 0.0039 18.8 0.74 0.00% 0.000 SS6-1-009A 63 0.0406 13 0.51 0.04% 0.000 SS6-1-010A 238 0.1536 14.6 0.57 0.14% 0.001 SS6-1-011A 162 0.1045 6.3 0.25 0.09% 0.000 SS6-1-012A 7339 4.7351 35.5 1.40 4.23% 0.059 SS6-1-013A 11686 7.5398 9.3 0.37 6.73% 0.025 SS6-1-014A 192 0.1239 10.8 0.43 0.11% 0.000 SS6-1-01SA 500 0.3226 9.6 0.38 0.29% 0.001 SS6-1-016A 624 0.4026 12.3 0.48 0.36% 0.002 SS6-1-017A 52 0.0336 8.5 0.33 0.03% 0.000 SS6-1 018A 20 0.0129 15.2 0.60 0.01% 0.000 SS6-1-019A 2133 1.3762 19.1 0.75 1.23% 0.009 SS6-1-020A 1791 1.1556 18.7 0.74 1.03% 0.008 SS6-1-021A 3955 2.5518 22.5 0.89 2.28% 0.020 SS6-1-022A 1751 1.1297 8.7 0.34 1.01% 0.003 SS6-1-023A 1498 0.9665 19.05 0.75 0.86% 0.006 SS6-1-024A 1175 0.7581 6.35 0.25 0.68% 0.002 SS6-1-025A 4775 3.0808 6.35 0.25 2.75% 0.007 SS1-001A 341 0.2200 8.8 0.35 0.20% 0.001 SS1-002A 3916 2.5266 22.4 0.88 2.26% 0.020 SS1-003A 2457 1.5853 68.3 2.69 1A2% 0.038 SS1-004A 350 0.2258 23.4 0.92 0.20% 0.002 SS1-005A 1304 . 0.8413 27.6 1.09 0.75% 0.008 SS1-006A 14914 9.6225 6.35 0.25 8.59% 0.021 SS4-001A 6203 4.0022 18.5 0.73 3.57% 0.026 SS4-002A 1938 1.2504 11.1 0.44 1.12% 0.005 SS4-003A 252 0.1626 4.3 0.17 0.15% 0.000 SS4-004A 3744 2.4156 18.5 0.73 2.16% 0.016 SS4-005A 1168 0.7536 13.2 0.52 0.67% 0.003 SS4-006A 664 0.4284 0.4 0.02 0.38% 0.000 SS4-007A 840 0.5420 4 0.16 0.48% 0.001 SS4-008A 1393 0.8988 2.3 0.09 0.80% 0.001 SS4-009A 325 0.2097 8.7 0.34 0.19% 0.001 SS4-010A 105 0.0677 2.1 0.08 0.06% 0.000 SS4-011A 6825 4.4035 44.45 1.75 3.93% 0.069 SS4-012A 1495 0.9646 25.4 1.00 0.86% 0.009 SS4-013A 19074 12.3065 6.35 0.25 10.99% 0.027 TotalArea=>1 173568 112.0 : 100.00% 0.700 Mean Depth> 14.6 0.58 Max-> 2.69 Mln=> 0.02 Sigma-> 0.42 2 Sigma + Mean=> 1A2.

&-TRAGHMENT +/--

5 --

DT Floor - SS1 r -- ,'55.403A S8&Z2-018A .s

r. -. . - ..O ! _

JSS14-04 SS14i02A

-;. SSIA East Wall ATTACHMENT Z I

DT Ceiling - SS4 SS4-001A 4,..' ..;

rI.-~-

L~

SS4-002.A

SS4-ZA SS-01 I SS4-003A ATTACHFAWT._I 2

DT South Wall - SS6-1 OA IS&OA sss-101 ATTACHMENT z 3

DT North Wall - SS6-2 ATrACHMENT L....--.-t

Corner of DT I\ ~~SS4-013A *,

144" SS4-008A Transition Area to SPP Floor - SS1 Ceiling - SS4 SS6-1-024A SS6-1-012A

-I w.- Z-

1.

-- I sr

-i

} 144' SW Wall - SS6-1 ATTACWMEg 1 NE Wall - SS6-2

ss1 North FLOOR OF DISCHARGE TUNNEL TO 150'

7126"

, 8 9 10 11

- 63" -J I 2 3 4 5 6 x/

+ -

Entrance Transition Area to SPP 120' Mark ATTACHMENT 3P - /

SS4 North CEILING OF DISCHARGE TUNNEL TO 150' 120' Mark 150' Mark ATTACHMENT -

in

\\ A-,.

L O-E,)

0) 12 e

6!

0q C

U) 0 I-

-J LU z

z L.;

to C .--

CM, MO 0 CO) e~n

_) _

N)

CO I-C-,

0 C,)

L..

'U CD

SS6-2 NORTH WALL OF DISCHARGE TUNNEL TO 150' (Facing North)

Entrance Area 150'Mark 120'Mark Facing East Wall A1TACHMENT . 3 .

Site Report Site Summary Site Name: Discharge Tunnel Class I Areas Planner(s): BHB Contaminant Summary NOTE: Surface soil DCGLw units are pCVg.

Building surface DCGLw units are dpn)100 cm2.

Screening Contaminant Type DCGLw Value Used? Area (m') Area Factor Gross Activity Building Surface 6,726 No 0.z5, 10.1 1 10.1 4 3.4 9 2 16 1.5 25 1.2 36 1 5$; 0 5/812004 Page 1 COMPASS vl.0.O COMPASS v1.0.0 5/82004 Page I ATTAC;HMENT - -I-

' Building Surface Survey Plan Survey Plan Summary Site: Discharge Tunnel Class I Areas Planner(s): BHB Survey Unit Name: Discharge Tunnel SSI Comments: Floor of DT Area (M2 ): 110 Classification: 1 Selected Test: WRS Estimated Sigma (cpm): 62.1 DCGL (cpm): 424 Sample Size (Nt2): 10 LBGR (cpm): 300 Estimated Conc. (cpm): 31 Alpha: 0.050 Estimated Power. 1.00 Beta: 0.100 EMC Sample Size (N): 10 Prospective Power Curve Z os - I - - I - =

re 0.8 - - - - - -i C0.8 ;

.0.5 . I-

_0.4 - T -

1i

-503

.~0.2 60O2 - _---

0. -

o~~o 0--

I- __ _

0 50 100 150 200 250 300 350 400 450 500 Net Beta (cpm)

- Power - DCGL - - Estimated Power

- LBGR a 1-beta COMPASS v1.0.0 62004 Page 1 A1TACHMENT U 2

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

Gross Activity 6,726 Beta Instrumentation Summary Gross Beta DCGLw (dpm/100 cm2): 6,726 Total Efficiency: 0.05 Gross Beta DCGLw (cpm): 424 ID Type Mode Area (cm2 )

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

Gross Actrvity 187.87 1.0000 0.48 0.11 0.0540 Average beta energy (keV) [N/A indicates alpha emission]

'Activity fraction Gross Survey Unit Mean (cpm): 297 *62 (1-sigma)

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

Concrete 31 266 34.5 1,251 COMPASS v1.0.0 518/2004 Page 2 ATTACHMENT I4 .3

W O C.I j I.1-i -I I 7-1x Elevated Measurement Comparison (EMC) for Beta j . Followthe order of each tab belowto perfor the EMC.

i 1)Enter Scarrig Instrumient Ef" 21EnterScanMDCParameters - 3JVie" EMC Results - -

Scan MDC Required per Contamina nt

.i Contaminant DCGLwA Area Factor Scan MDC Required*

Gross Activity 6.726 1.68 12.510 Statistical Design Holt Spot Design N/2: l _10 Actual Scan MDC-. l 2.466 BoundedAream(m2 : l 11.0 Area Factor l N/A AreaFactor. I 1.86 Bounded ArEea(rn2): l N/A' DCGLw": 6.728 Post-ENIICN/2: I 10 j ScanMDCRequired: l 12.510 .iI

_dpm/1 00 cm2';- No addtionS s wnples are reqLured because the actual

'jJ scan MDDC is k-ts than the DCGLw fwoeach contarrfiant r EnableTrainint II -""OK I vN.W.O AT ACHMENT ' -

'_/ Building Surface Survey Plan Survey Plan Summary Site: Discharge Tunnel Class I Areas Planner(s): BHB Survey Unit Name: Discharge Tunnel SS4 Comments: Ceiling of DT Area (M2 ): 108 Classification: I Selected Test: WRS Estimated Sigma (cpm): 62.1 DCGL (cpm): 424 Sample Size (N/2): 10 LBGR (cpm): 300 Estimated Conc. (cpm): 31 Alpha: 0.050 Estimated Power: 1.00 Beta: 0.100 EMC Sample Size (N): 10 Prospective Power Curve

, 0.83 0.7~ I

_ Os. - _ _ - _

0.6 0.4*-L -- b-ta 4 0.13-0 SS10 l0 20 S 0 i ~.-- -ow - - -C6 - -

~-0 .zrz 0 s0 100 150 200 250 300 350 400 450 500 Net Beta (CPni)

- Power - DCGL - - Estimated Power

- L8GR U I-beta COMPASS v1.0.0 5/8/2004 Page 1 AiTACHMENT SC . r

Building Surface Survey Plan Contaminant Summary DCGLw 2

Contaminant (dpmI/100 cm )

Gross Activity 6,726 Beta Instrumentation Summary Gross Beta DCGLw (dpm/1 00 cm2): 6,726 Total Efficiency: 0.05 Gross Beta DCGLw (cpm): 424 ID Type Mode Area (cm')

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

Gross Activity 187.87 1.0000 0.48 0.11 0.0540

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

2Activity fraction Gross Survey Unit Mean (cpm): 297

62 (1-sigma)

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

Concrete 31 266 34.5 1,251 COMPASS v1.0.0 518/2004 Page 2 ATTACHMENT 69.

PRIM Iii IN ~=0 I XII Elevated Measurement Comparison (EMC) for Beta

Ft / Followthe order of each tab belowto perform the EMC.

1 '1

.J -

1)Enter Scyng Instrunent Effvciende 2)Enter Scan MDC Paraneters I - -3)View EMC Results -- -

Scan MDC Required per Contaminant Contaminant DCGLw Area Factor Scan MDC Required' Gross Activity 6.726 1.87 12.578 I

7-r

I Statistical Design Hot Spot Design f-I'.-

N12: l 10 Actual Scan MDC-. l 2.466 Bounded Area (m2): l 10.8 Area Factor F N/A KU Area Factor l 1.87 BoundedArea(m ): 2 I N/A DCGL-W. l 6.726 Post-EMCN/2: F 10 Scan MDC Required' l 12.578

dpm/1 00 cm2 No addtinal sanvies afe reqnued because the actual (9 scan MDC isless than the DCGLw for each contaffinant.

j jj P Enable Trainin vl.O.O ATTACHMEW. L/

%'J, Building Surface Survey Plan Survey Plan Summary Site: Discharge Tunnel Class 1 Areas Planner(s): BHB Survey Unit Name: Discharge Tunnel SS6-1 Comments: South Wall of DT Area (m2 ): 118 Classification: 1 Selected Test: WRS Estimated Sigma (cpm): 62.1 DCGL (cpm): 424 Sample Size (Nt2): 10 LBGR (cpm): 300 Estimated Conc. (cpm): 31 Alpha: 0.050 Estimated Power 1.00 Beta: 0.100 EMC Sample Size (N): 10 Prospective Power Curve w- I l l 1--

"09 !

0.8 i----- - -

0.7-I - - --

0.6 -

,0.4 _ -

. 0.33 - - -

S .l _- - _

0.1 - - -

0 0 S0 100 lS0 200 2S0 '300 350 400 450 500 Net Beta (cpm)

- Power - DCGL. - - Estimated Power

- LBGR

1-beta COMPASS v1.0.0 5/8/2004 Page I ATTACHMENT J. 8

Building Surface-Survey-Plan --

Contaminant Summary DCGLw Contaminant (dpm/100 cm')

Gross Activity 6,726 Beta Instrumentation Summary Gross Beta DCGLw (dpm/100 cm2): 6,726 Total Efficiency 0.05 Gross Beta DCGLw (cpm): 424 ID Type Mode Area (cm')

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

Gross Activity 187.87 1.0000 0.48 0.11 0.0540

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

2Activity fraction Gross Survey Unit Mean (cpm): 297t 62 (1-sigma)

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

Concrete 31 266 34.5 1,251 51812004 Page 2 vl.0.0 COMPASS v1.0.0 A C/i004 Page 2 ATrACHMENT i' -_ 9

RION11977WHIS IM - 101 x Elevated Measurement Comparison (EMC) for Beta Followthe order of each tab belowto performthe EMC.

.1 d - 1)Enter Scarring Instrument Effcienciel 2)Enter Scan MDC Parameters 31 View EMC Results

. I I

Scan MDC Required per Contaminant

.1 -' Contaminant I DCGLw I Area Factor I Scan MDC Required* I

-4 Gross Activity 6.726 1.80 12.107 (I__ I Statistical Design Hot Spot Design N12: I 10 Actual S;can MDC'. l 2.466 Bounded Area (rnr): I 11.8 AreaFactor l N/A Area Factor I 1.80 BoundecdArea(rm2): l fN/A DCGLw'. r 6.726 Pos t-EMC N12: l 10 Scan MDC RequiredK 12.107 I-E I dpmII 00 cm' fh, No adcitional samples are reqiued becaume the actual

.l. I scan MDC i less than the DCGLw for each contamrtant R Enable Trainin v1.0.0 A -TiACKME NTTZ- ,O

'Iz' Building Surface-Survey Plan--- --

Survey Plan Summary Site: Discharge Tunnel Class I Areas Planner(s): BHB Survey Unit Name: Discharge Tunnel SS6-2 Comments: North Wall of DT Area (m2 ): 135 Classification: I Selected Test: WRS Estimated Sigma (cpm): 62.1 DCGL (cpm): 424 Sample Size (N12): 10 LBGR (cpm): 300 Estimated Conc. (cpm): 31 Alpha: 0.050 Estimated Power 1.00 Beta: 0.100 EMC Sample Size (N): 10 Prospective Power Curve

_ 1

- - I-- 1I - I a os

. I- - - - I 1 I

_ 0.8

'- 0.7 I- - -I - -- -

U 0.6 I A. 05

-I--4 - --

_ 0.4 I I

- 0.3 C0.2 . l _4 _

E . l __ __ _ _

1 0.1 0~~~ I I vX0XX=

I II=

0 50 100 150 200 250 300 350 400 450 500 Net Beta (cpm)

- Power - DCGL I-- Estimated Power

- LBGR a 1-beta COMPASS v1.0.0 5/8I2004 Page 1 ATTACHMENT - //

Building SurfaceaSurvey Plan Contaminant Summary DCGLw Contaminant (dpm/l00 cm')

Gross Activity 6,726 Beta Instrumentation Summary 2

Gross Beta DCGLw (dpm/100 cm : 6,726 Total Efficiency: 0.05 Gross Beta DCGLw (cpm): 424 ID Type Mode Area (cm')

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

Gross Activity 187.87 1.0000 0.48 0.11 0.0540

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

2Activity fraction Gross Survey Unit Mean (cpm): 297+/-t 62 (1-sigma)

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

Concrete 31 266 34.5 1,251 COMPASS v1.0.0 518/2004 Page 2 ATTACHMIENT, Y - ia.

_.__- __. If I-P W 4. I r4 -1 5 Elevated Measurement Comparison (EMC) for Beta Followthe order of each tab belowto perform the EMC.

1I Enter Scanning Instrument Efficiencief 23Enter Scan MDC Paraneters 3) View EMC ResultIs

.J Scan MDC Required per Contaminant -

Contaminant l DCGLwa l e Factor I Scan MDC Required*

- Gross Activity 6.726 1.68 11.300 rI Statistical Design Bounded Area N12:

(m2 :

1 l

10 13.5

-Hot Spot Design Actual Scan MDC 1.

Area Factor I

I 2.466 N/A Area Factor l 1.68 Bounded Area (rn): l N/A DCGLw'-. 6.726 Post-EMCNW2: 10 Scan MDCRequired*. l11.300 I.. x

' dpmtl 00 cm' Q No adhtional safwfs ae requied because the actA scan MDC isles than he DCGLw for each contafnakt P Enable Traininc vl.0.0

!77f,C;i il,EN7 L/ . / --?

Duratek fy pI ca 1 ORIGINAL CALIBRATION CERTIFICATE Duratek Instrunent Services 628 Gallaher Road Kingston, TN 37763 Phone: (865) 376-8337 Fax: (865) 376-8331 This Certificate vill be accompanied by Calibmtion Charts or Readings where applicable CUSTOMER INFORMATION DETECTORINFORMATION Customer Name: Duratek Instrument Services Manufacturer. Ludlum Address: 628 Gallaher Rd Kingston, TN 37763 Detector Model: 44-10 Contact Name: Thomas Scott Serial Number 196022 Customer Purchase Work Order Evaluation Method:

Order Number. N/A Number. 2004-01500 Source

--':'-DETECTOR EFFCIENCYIRESPONSE/PRECISION INFORMATION I) Source Nuclide: Cs Serial Number: 019454 Activity: 5ACi Certification Date: NIA (Used forPlateau Only)

2) Source Nuclide: Cs"37 Serial Number: 049711 Activity: Variable Certification Date: 04109/03

' ' Scaler Information Precision Test mR/Hr (Source #2) 2350-1 #126172 Count 1 2.04 Due Date 4/0612005 Count 2 2.04 Threshold T=100 (lOmV) - Count3 - 2.02 Cable Length Sft. Average 2.03 N/A NIA Tolerance 410% All counts within 4110% of Average N/A N/A Pass/Fail Pass N/A NIA Low Sample Activity (40WuRlhr): High Sample Activity (2mRlhr) Dead Time (Dl): Calibration Constant (CC:

Using Source #2 = 73.971 Usin Source #2 =258,839 1.739467E.05 6.214138E+10

' ^'ATrACDIIENTS ' DETECTOR DATA: DOSE RATE PROBES 'i llr)

Detector Setup Report YES / NO Desired Exposure Toleranced410% As Found As Left Barcode Report YES / NO 0.400 0.360-0.440 0.403 0.403 Voltage Plateau: YES / NO 1 0.90-1.10 0.956 0.956 High Voltage: 1000V 2 1.8-2.2 2.04 2.04

.- e. - ' . . . - COMMENTS

- Detectors set up with a 2350-1 may be used with any 2350-1 provided that the setup parameters are scanned into the 2350-1 prior to use with that specific detector**

Calibrated with 5f1. Cable STATEMENTOFCERTIFICAMON '.

We Certify that the ddector listed above was evaluated forproper operation priorto shipment and that it mdt all he Manufacturers published operating specifications. We fuither certifiy that our Calibration Measurernents are traceable to the National Institute of Standards and Tedcnology. (We are not responsible for da gaze inacrred durin shipment or use ofthis ddeclorl Detector _---

Certfied Bt : NA ;ld *r I Reviewed By: r O-;~ .. Date:

Certification Date: 0416/04 1Certification Due: 0416105 A1TACHMENT- L- 1

d Duratek- ORIGINAL CALIBRATION I ypi cat CERTIFICATE Duratek Instrument Services 628 Gallaher Road Kingston, TN 37763 Phone: (865) 376-8337 Fax: (865) 376-8331 Thiq Ce tiificaite will be neonmnanied bv Calibrntinn Charts nr Rendinpq where arnlicable

.. ,; CUSTOMER INFORMATION. ISTR NTO ON'.

Customer Name: Duratek Inc. - Instrument Services Fadlity Manufacturer. Ludlum Address: 628 Gallaher Road, Kingston, TN 37763 Model: 2350-1 Serial Number. 126172 Contact Name: Thomas Scott Probe: N/A Serial Number. N/A Customer Purchase Work Order Calibration Method:

OrderNumber. N/A Number. 2004-01500 Electronic and Source

-. .' .I'NSTRUMNT CALIBRATION INFORMATION -... ..

Calibration Standard Instrument Response Instrument Range Value Comments (CP)C Before After Calibrated in accordance with M) Calibration Calibration IN-WI-239 Rev 0 400K 400,000 403,896 403,896 Pulser: 101500 Cal Due: 09118/04 40K 40,000 40,025 40,025 D-814: 2525 Cal Due: 10/22/04 4K 4,000 4,002 4,002 Psychron: 7480 Cal Due: 02/10/05 400 400 401 401 EPPROM Version: 37122N21 RV Cal Values . . Desired HV. ;As Found *. As Left

. (M2350 HV Entry) *.(Voltmeter) (VDC)

O DCj_ (VDC) 600 600 605 605 Temp: 22.8°C 1,200 1,200 1,203 1,203 Pressure: 745 mmlig 1,800 1,800 1,798 1,798 Humidity: 31%

Parameter . r:'A Tolerance (-10%.!) - .; Found AsLeft Threshold T= 100 10 * (9 to 11) mVDC 10.2 10.2 Geotropism: SAT ACKlScroll: SAT Threshold T = 500 50 4 (45 to 55) mVDC 48.6 48.6 BAT>4.5: SAT Volume: SAT Threshold T =1000 100:1 (90 to 110) mVDC 98 98 Count: SAT Audio Divide: SAT Window Width W = 100 10 1(9 to 11) mVDC 9.3 9.3 Alarms: SAT Lamp:SAT Display-to-mV ratio: 100 to 10 mV Overload Test: SAT We Certify that the instrument listed above was calibrated and inspected priorto shipment and that it met all the Manufacturers published operating specifications.

We fiurther certify that our Calibration Measurements are traceable to the National Institute of Standards and Technology. (We are no responsible for damage incurred during shipment or use ofthis instrument).

Instrument 7

Calibrated By: NILQ §P-Ž 1^L Reviewed By: ( ,-,-'t) ( rj. Date:

Calibration Date: 04/06104 l CalibrationDue: 04/06105 A1TACHMENTI .A -

-- -Y?1,C;,- I ORIGINAL LUDLUM MODEL 44-10 HIGH VOLTAGE PLATEAU DATA SHEET Serial Number: 196022 HIGH VOLTAGE SOURCE (10 second count) 705 17,537 706 21,507 707 24,743 708 25,998 709 27,826 710 (SET) 28,245 711 28,040 712 26,415 713 25,339 714 22,792 Detector plateau performed using Cs137 #019454 5uCi nominal value button source Detector Parameters for Peaking Parameter Setting Setting Threshold (10mV/100) 642 612 Window (On) 40 100 High Voltage 710 710 CPM/mRIHr 122,572 208,705 Background CPM 27 63 CPMImRlHr conversion performed using Cs137 #049711 Certification Date: 04109/03 FWHM values performed with Cs1 37 #019454 (Threshold = 642 and Window = 40)

FWHM = 679-596 11.5%

662 xl100%

Detector peaked for Cs137 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 #126172 calibration due 04/06/05 used for peaking 44-10 detector.

Performed By: "VQl C,--11-P Date: 4 I, IO4-I Reviewed By: _( Date: e- e - C ATTACHMEN __ 5 - 3

01119P) C? 19~- ORIGtNiAL

' ;GPCRadiai ' e' u;' e 1 m C lib -ti' h orkshee f Performed By: R. Reheard Date: [ 6124103 Instrument SIN: 95352 l Probe StN:l 94818 Instrument Vendor Cal. Date: 12120J03 j . C?1. Due Date: 12120/03

.uil i:i3! j- !;; i : e .)(3 j Am-241 (GO 535) S-023 0.25 4/8199 12:00 GMT 4.24E-01 7.43E+03 Am-241 Cs-137 (GO 536) S-024 0.50 418199 12:00 GMT _ 3.11E-01 6.89E+03 Cs-137 Source Radionuclide Decay Date Cs.137 6/24103 Decay Factor=* 9.075E-01 jJ Elapsed Time (days)= 1538 Activity (pC[)= 2.821 E-01 Source dpm: 6.262E+05 Source dpm/in Probe Area (cmA2)* 5.260E+05 27n Emission Rate (sec 1p) 6.253E+03 Probe Area (cmA2) 27r Emission Rate (min-1)=5 3.752E+05 I 126 27r Emission Rate in Probe Area (min.1)=* 3.1 51 E+05 Record of 1 Minute Source & Backqround Counting Results 0 Checkifusing1Io7503-1 Value No. OW Source Gross CPM OW Background CPM OW Source Net CPM RESULTS / I1:

I 1.61E+05 175 1.608E+05 Counts/Emission (el) ptl 2 1.61E+05 201 1.604E+05 50.9%

3 1.60E+05 180 1.601E+05 27c Emlssion/Dlsintlgratlon (Es) 4 1.60E+05 161 1.602E+05 50.0%

5 1.61 E+05 145 1.607E+05 CountslDlsInUgratlon (Et) 6 1.60E+05 176 .1.603E+05 25.4%

7 1.60E+05 183 1.602E+05 8 1.61E+05 184 1.604E+05 l\

9 10 1.60E+05 1.61 E+05 Mean=

204 190 179.9 1.602E+05 1.607E+05 1.604E+05

_ Approved:

Date: (2 s

9

'4'

/ou5 -

r 1 I Calibration Calculation Sheet Verification Date=l December-02 l B. Brosey/P. Donnachie=>. December-02 I ATTACHMEN 4 *L/

ll -

w X Cs-1 37 Efficiency Loss with Distan ce From Source 10 _ , .

Data: Data1Loss Model: EpODecayI

- -- - -- - -- - - -- - - -- - - - Chi'2= 0.0001 8 0 08 Yo 0 03536 +/-0.02118 W xD 0 t0 Al 1 00593 0.01 609 I- - - - -- - - -

_- - - - -- -- --- -- -- ti 1.T1706 :0.07558 06 -S.

0)

Et _1 Fit= yO4A1 eA(_(xxO)lt1)

LI 04

--- --- --- --- --- --- t-;-- - -----

02 4 I

. I 0.0 0.5. 1.0 1.5 2.0 2.5 3.0 Inches from 150 cm2 Source ATTACHMENT _ - I

DCGL Calculation Logic-Discharge Tunnel I. Survey Unit: SNEC Discharge Tunnel I.

Description:

The purpose of this calculation is to determine a representative isotopic mix for the Discharge Tunnel from available sample analyses. The effective surface area and volumetric DCGLWs are then determined from the mean percent of applicable samples.

Ill. Data Selection Logic Tables: The radionuclide selection logic and subsequent DCGL calculations are provided in seven (7) tables. These tables were developed using Microsoft Excel spreadsheet software. Table explanation is as follows.

Table 1: Data Listing - This table, which has been extracted from a larger database, provides a list of the most representative Discharge Tunnel sample analyses. These results are from scoping, characterization, and pre/post remediation surveys. The samples consist of various sediments, scrapings and concrete cores that were taken in support of the aforementioned surveys. As applicable, a sample number, sample location/description, radionuclide concentration, analysis date are provided for each sample. Positive nuclide concentrations are noted with yellow/shaded background fields while MDAs are noted in the gray shaded fields.

Table 2: Decayed Listing - This table provides the best overall representation of data selected and decayed from Table 1. In Table 1 half-life values (days) are listed above each respective nuclide column. Samples are decayed to the date noted above Table I (e.g. January 15, 2004). Positive results are denoted in a yellow background field while

MDAvalues are in a gray background.

Table 3: Decayed Listing of Positive Nuclides & MDAs Removed- This table provides the

'decayed values of positive nuclides selected in Table 2-In addition MDA values have___ ___

been removed from this table.

Table 4: Mean Percent of Total for Positive Nuclides - This table provides the calculation methodology for determining the relative fractions of the total activity contributed by each radionuclide. From this information the mean, sigma, and mean % of total are calculated.

The mean % of total values is used to calculate the surface gross activity DCGLW per MARSSIM equation 4-4. See Table 6. Note that the Co-60 mean percents were averaged using only samples I & 2. In addition, the mean percents calculated from sample 2 for Am-241, Pu-238, Pu-239 and Ni-63 were not averaged throughout the spreadsheet since there was only one sample where these respective nuclides were positive. This results in higher "mean percent of total' values in the mix, which are conservative.

Table 5: Ratio to Cs-1 37 for Positive Nuclides -This table provides the calculation methodology for determining the surrogate ratio to Cs-137 for each radionuclide. From this information the mean, sigma, and mean % of total are calculated. The mean % of total values is used to calculate the volumetric DCGLW per MARSSIM equation 1-14. See Table 7. Note that the Co-60 ratios were averaged using only samples I & 2. In addition, the ratios calculated from sample 2 for Am-241, Pu-238, Pu-239 and Ni-63 were not averaged throughout the spreadsheet since there was only one sample where these respective nuclides were positive. This results in higher "mean percent of total' values in the mix, which are conservative.

Note: From Tables 4 and 5 only the "mean % of total" values are used as Input to the "Effective DCGL Calculation Spreadsheet" as illustrated in Tables 6 and 7.

ATTACHMENT ,

Table 6: Effective DCGL Calculator for Cs-I 37 (dpm/1 00 cmA2) - This table provides the surface gross activity DCGLW calculation results from data inputted from Table 4.

Table 7: Effective DCGL Calculator for Cs-I 37 (in pCVg) - This table provides the surrogate volumetric modified Cs-137 DCGLW calculation results from data inputted from Table 5.

IV. Summary - Since the Discharge Tunnel is a concrete structure the release limit is primarily based on the surface area DCGLW,. However, a small portion of the Discharge Tunnel ceiling Class I area has volumetric contamination. Using the above data selection logic tables the calculated gross activity DCGLW for surface area is 8,968 dpmII00 cm2 . The Cs-137 volumetric DCGLW is 6.52 pCi/g. These values would be reduced by 25% as part of SNEC's requirement to apply an administrative limit as required by the License Termination Plan (LTP).

2 ATTACHMENT_- 8

[ TARI F i natl i iDatLinn (itnil De1y 0te0 TtJ2 T1 2 TV12 T1'2 Tt 12 T1/2 11J2 T1.2 T112 T12 T V2 Januars t; 2004 b6.

SlItC Sanmpl no0 3h195D930531 SNxCS091CO3U SXOSDOOZ64h SXSSDS9267 Location/Oesciption Dischour0 Discharoe SSG S unne v'1ull

~unnnnI Foon Svraco 6 Da- L meSCeni.

UnuneS Setimnnl SSG0 carge Tunnel/'r Seunnt 4 IC a

-E7C SSGSDischargeTunnelF",r Seodknet O!C I

100 It 8

III ,

0o4 30 0.3 0.16 120 4800 iia T1 2.3 2

6 0.2 1

0.04 16 I

0.04 I

60 6 55 19674 Eu152I 20 I

Analysis DOte July 29 1999:

e. SSGSDischru'ge 'nelSP-1. Cebn . Sect . Sice 1 7

S Mav 6 2003 C:5 vliplsn c Luu I 194:

11 7.02 1

0-06 May 22 2001 I TAMI C 'J - M.-.-A I 1.44.. i.rql.l I I E SmleoLocutionil~escription .3 6=~ I Sr-90O Co-SO CS-137 1Am-241 Pu-238 PU.

II SX1SSD990CS ConnrI.t nII I Iuy4,67E-01 1.OO8E sO2 lOS9E-O1l3 85E-02 4 05E-02 I I I I I 1999 1 121 5X15500053 I DmicthaneTunnelO SnuraL neScraonirr I 7 79..l4i 1 7 i0flcn0ft I I 9= O4 I A 22S~nl I F 16r..A I I XAV.ff I 7)ZAX.fl I A PAl.d1 I A ruir ,flOI ; ¶11-.fl I I S6F;:

.O I ~July29 ii 1000q I

.-.- I t -7Ct I I ilS6E-01 145Ee00 I--

I. --- I I I I I I I Noevmber 22 19991 t-SIC I I I 174E-01I 219E+00 I I I I I I I

-505 I 1 I 9.27E-02 II 182E+00 I III I I I IS6I1SXCC.A2M I SS DisccargeTunnelSP-S.Ceftlr Sect 1 Siot 1 SsC I 722E-01 I 257E-02 I 2-20-02 I 2r57E-01lI 1;81E-02 I 2.59E-02 I 17 SXCI;2525 I $S$ Dischargeunnel2, Cencrete Y41Ccn-SOS56Ounld,mg Strucnnre I1.93E+,00 II361E-02 I OE-02I 2+65En01 I 5-0 e -5 D1 I v 22 2001 I Mlen#- 1,57E.01 I1 22E.00 I 1 77E+-00 4 52E+02 18 35E-01I Sigme. 30 401 2 919 5224 1363 0 1 997 _

Ia/u Orl7otai 3,14% 0 24% 0,35% 90 40% 0 17% _ %J KEY IYellov- Shaded Background

PosItive Result I lGray Shaded Background - CJDA 3

cOt

TABLE 3 - Decayed Listing of Positive Nuclides & MDAs Removed (pCI/g)

I SNEC Sample No Location'Descriptlon Co-60 Cs-137 Am-241 Pu-238 Pu-239 Ni-63 Total (pCilg)

SX1S0D990031 Discharge Tunnel Wall Scraping 4.67E-01 1.08E'02 108.77 2 SX105D990033 Discharge Tunnel 6 Drain Line Scraping 1 66E+01 4.33E+03 5 36E+00 1 54E+00 2.50E+00 5 33E+01 4409 52 3 SXSSD99264 SSGS Discharge Tunnel Floor Sediment -670G 1 45E+00 1.45 4 SXSSD992i6 SSGS Discharge Tunnel Floor Sediment -610 2.09E-+"00 2 09 5 SXSSDO92E7 SSGS Discharge Tunnel Floor Sediment -550C 1.82E+00 1 82 6 SXCC42!e SSGS Discharge Tunnel SP-3. Ceiling. Sect 1 Slice 1 2+57E+01 _ 25 65 7 SXCw3S38 SSGS Discharge Tunnel # 2. Concrete Core - SR-SE. Building Structure 0all 2.65E+01 26.47 8 SXCf3539 SSGS Discharge. Tunnel # 3. Concrete WvallCore - SR-5E. Building Structure 1 40E+00 1.40 9 SXCw735 SSGS Tunnel, North /fall-S-8 From Floor 2 12E+01 21.16 10 SXSD923 SSGS Tunnel. Rubble l 700'. SR-OCO£ 1 41E-011 0 14 I.lean~* 8 55E+00 4 52E+02 5 36E+00 1 54E+00 2 50E+00 5 33E+01 523 14 Sigma- 11.433 1363 086 _ _I Ilean % cfTotai 1.63% 86.38% 1 02% 0 30% 0.48% 10.19% 100.00%

TABLE 4 - Mean Percent of Total for Positive Nucildes ISNEC Sample No Locatlon;Description Co-80 Cs-137 Am-241 Pu-238 Pu-239 NI-63 Total I sX10SD990031 Discharge Tunnel Wall Scraping 0.43% 99 .57% 100.00%

2 SX105D990033 Discharge Tunnel 6' Drain Line Scraping 0Q38% 98.20% 0.12% 0.04% 0.06% 121% 100.00%

3 SX5SD99264 SSGS Discharge Tunnel Floor Sediment -670C 100.00%/_ 100 00%

4 SXSSD9926E SSGS Discharge Tunnel Floor Sediment -610 100.00% 1000%

5 SXSSD99267 SSGS Discharge Tunnel Floor Sediment -550 100.00% 100.00%

6 SXCC423- SSGS Discharge Tunnel SP-3. Ceiling. Sect 1.Slice 1 100.00% 100 00%

7 SXCW353B SSGS Discharge Tunnel # 2. Concrete Wall Core - SR-5E. Building Structure 100.00% 100 00%

_8 SXCw3539 SSGS Discharge. Tunnel # 3. Concrete Wall Core - SR-5E. Building Structure 100.00% 1000%

9 SXCw73s SSGS Tunnel. North Wall 6 From Floor 100.00% 100.00%

10 SXSD923 SSGS Tunnel, Rubble C 700. SR-000E 100.00% 100.00%

tleanw 4 03E-03 9 98E-01 1 22E-03 3 50E-04 5 67E-04 1 21E-02 1.02 Sigmas 0 0004 0 006 I lean '% ofTotaw 0 40% 98.20% 0 12% 0.03% 0 06% 1 19% 100 00 TABLE 6 - Ratio to Cs-137 for Positive Nuclides SITEC Sample Ito LocationlDescription Co-60 Cs-137 Am-241 Pu-238 Pu-239 Ni.63 Total 1 SX10DD990031 Discharge Tunnel Wall Scraping 4 31E-03 1.OOE+00 l _ __ ______ 1 00 2 SX10SD990033 Discharge Tunnel E Drain Line Scraping 3.84E-03 11.OOE+00 I 24E-03 3.57E-04 5 77E-04 1123E-02 102 1l 3 SXSSD99264 SSGS Discharge Tunnel Floor Sediment -670l 1 .0E+00 _ _ _ l 1.00 4 Sx5SD99266 SSGS Discharge Tunnel Floor Sediment -610 1 OOE+00 1 00 I______

5 SX5SD99267 SSGS DischargeTunnel Floor Sediment -550 l OOE+00 _ _ _ __ 1 00 6 SXCC423E SSGS Discharge Tunnel SP-3. Ceiling. Sect 1. Slice 1 1.OOE+O0 l_ _____ l 1.00 7 SXC.V3538 SSGS Discharge Tunnel 6 2. Concrete Wall Core - SR-56. Building Structure 11OE+00 IIT _ _ _ 1 1 00 8 SXCW3539 SSGS Discharge. Tunnel 6 3. Concrete Vall Core - SR-5. Building Structure l 1 OOE+00 IlII _ _ _l 1 00 9 SXCW735 SSGS Tunnel. North Wall - S-5 From Floor 1. OOE+00 l1 00 10 SXSD92a SSGS Tunnel. Rubble Q 700. SR-CO00 l 1 OOE+00 l _ ____l_1 00 4 08E-03 GOE.00 1 24E-03 3 .57E-04 5 77E-04 1 23E-02 1,02 M~eanw Sigma-*

Ilea n % c f Ota l-0 0003 0 40%

00000O 1 98 18% 1 012%

_ [1 -

0 04% { l 0 06% 1 121%

l l :

1O00%

4 cOz

Table 6 Effective DCGL Calculator for Cs-137 (dpml100 cmA2) 1 8968 _Idpml100O cm-21 6726 ldpml100 cm^2 20 mremly TEDE Limit I I !

1411eZCV.Ztf:1371L JtiWIM04-A SAMPLE lJO(s)}=Discharge Tunnel I 8807 -dpmt1OOcmA2j 6605 - dpml1OO cmA2 IMNECOALO 75%

Individual Sample Input Limits Allowed Beta dpmt10O Alpha dpm1i0O I--4---

ISDIp: {pb" r.. a, - .-

Uk.1 CGI-.J

.'VI .4 Yr4.. #A-nPd~fk -- A-)% .4flflnn -A') -rom. Tcrn mA-) .- A-)

cr I UIal jUjiiII lUVU11 IA)J UpjilJi5S PU.- m &x li lys7 I LU.c. U I T1-2 1 Am.241 1.22E-03 0.120% 27 10.77 9.97 > 10.77 Am-241 2 C-14 0.000% 3,700,000 0.00 0.00 0.00 C-14 3 Co.60 4.03E-03 0.397% 7,100 35.56 0.13 35.66 WA. Co-60 U'

4 CU1377ek i9.9aEX1i 398203% 28,OOO s88O6.'9 . 7;86WS <k-iA i8807.07 O.1 5 Eu.152 0.000%,O 13,000 0.00 0.00 0.00 Eu-152 6 H-3 0.000% 120,000,000 0.00 0.00 llotDetectable H-3 7 111-63 1.21E-02 1.191% 1,800,000 106.78 0.00 hlot Detectable Ni.63 8 Pu.238 3.50E-04 0.034% 30 3.09 2.57 .i. - 3.09 Pu.238 9 Pu-239 5.67E-04 0.056% 28 5.00 4.47 :$A8 : 5.00 Pu.239 10 Pu.241 0.000°% 880 0.00 0.00 [lot Detectable P -241 11 Sr.90 0.000% 8,700 0.00 0.00 0.00 i : . Sr.90 100. 000% 8968 25.0 8843 19 Maximum Permissible dpmt10O cmA2 5

Table 7 ll ",SNEC&ALW*+j; 15% -T- t ttfiifj DCGjv 3! 4Mi Effective DCGL Calculator for Cs-I37 (in pCllg) I 1 6.64 tpCi9g 1 4.98 CI i T I S;AMPLE HlUMBER(OZ, ~Disch.rge Tunnel I I I !

a 15.34%

L=- -: =

25.0 mremrly TEDE LUmit 6.52 IPCUC 1 4.89 jpCl1g 0.55% mremtv Drinkino Water (IRYI Limit I 17 Cled for 25 vemh1l Sample Input SfpVV e 1gvuC ' ~ 25mremy TEDE - A. Allowed pCIg for M ValueCheckedrom This Sample l san l Isotope of Total, etc.) of Total Limita (pCg) N W9 25 mremy TEDE DW Coumn A or B mremfy TEDE l emijWt I : , I -..

Am.241 0.001 0.122% 9.9 . 2:3 ' 001 001 000 f -AD 00 ' Am.241

C)

C.14 0000% 2.0 0000 ol 000 000 C.14 Co.60 0.0041 0 401% 3.5 0 03 0 03 0 03 Co.60 m- Cs-137 1.0000 98 178% 6.6 9 652 l82 379 Cs.137 Eu.152 0000% 10.1 I44 000 ! 0.0 000 0.00 Eu.152 H.3 0 000% 132 0000 ; 000 0 00 000 .H-3 Ni-63 0.0123 1 208% 747 10 0.08 2. 0 08 0.00 HM.63 Pu.238 0.0004 0 035% 1.8 0 00 ' 0006 000 0 00 Pu.238 Pu-239 0.0006 0 057% 1.6 0 0 00 01 0000 001 Pu.239 Pu.241 0 000% 86 9 8 0 000 0 00 000 Pu.241 Sr.90 _ 0 000% 1.2 ° °° 0..6i00 __ °

______° 000 Sr-9D 1.02E400 100.000% 1I 6.64 I 183.!

53-. 6.64 3.835 r 0.022 Maximum Permissible Maximum l To Use This Information, (2 ?Q, PermIssible pCi/g Sample Input Units Must Be In (26 mremty) (4mremly) I DUCO nor%of rotal I 6

Nal Scan MDC Calculation - Concrete Surface

-- -7 S. IS SR,1-5 d :1.38 Cony :-208.' MS I :5u.10 HS d

- = 6.096 ObservationInterval (seconds)

SR

°Oi := HS ObservationInterval (seconds)

(b-o i) 60 MDCR i := (d-J)i 60 MDCR `43.294j,1 net counts per minute MDCR MDCR surveyor r MC ii-, <surveyor,,7>,

>-, , '" Mj--i12

.*; r net counts per minute MDCR surveyor MDER:=

Conv MY-REI-F-Ma"12U fLR/h MDC scan MDER scnMS output'1 l o3

7 KN-j ]j,- i,. " pCilg 117-11,Lll172-- -.

4 -' r rAn Df AA m , ,9 c ATTACHMEW. N-L,

Nal Scan MDC Calculation - Concrete Surface

1. rr" OO

.48' SR=S 1

'117.. 865 10 Ale HS d

-S = 6.096 ObservationInterval (seconds)

SR HS d (b Oi) 0i := - ObservationInterval (seconds) 60 i MDCR1i := (d . i MDCR i -- 61.228 e net counts per minute __

.X ;-

MDCRIMDCR i MDCR surveyor MDCRF P!

MDCR ~ 86.58-9 :~J net counts per minute

.r :

MDCR surveyor MDER:=

Conv 8_ BgR/h MDC scan MDER MS output' lo MDCI pCi/g z.can In in ATTACHMENT. J- 2-

Nal Scan MDC Calculation - Surface Deposition

= 100 Hs.'5 30.48

. __S.JT=

Conv:= 208.

- I ~._' II.. 4- . .- .

M-~I I1 0.- j..

..... I . 1 -

S.,,

r, 0 i = 6.096 ObservationInterval (seconds)

_ (b-O i) 60 MDCRi := (d-lbi)-o MiDCR

,~~~<

i -43.294

_ a:I

., net counts per minute MDCR; MDCR surveyor = Lr P;

MDCR.-"yo q Z< -uveo

r= 61.22 8 - . net counts per minute

.7_.-

.<., ; 4' MDCR surveyor MDER: =

Conv MIDER.- . 94fl jiLR/h MDC scan : MDER scn-Ms output' 1 -10 3 J~mc9 r.~can~,~~--'-§ . i!.' PCi/cm 2

w-_._:ne MDC .. ;-.-iscan+.

a-222 45.7

<*.. dpm/1OO cm2 eI flA A ,S f ATTACHMENEjlT 3

where:

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

MDCSCm = Minimum Detectable Concentrationforscanning (pCi/cm2)

MDCR1 = Minimum Detectable Count Rate (ncpm)

MDCRw,,,Vj, = MDCR, correctedby humanperformancefactor(ncpm) _ _ __

MDER = Minimum Detectable Exposure Rate (uR/h)

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

Oi = obervationInterval(seconds) p = humanperformancefactor SR = scan rate in centimeters per second __

aN.Df A C - C ATTACHMENT I - q

MicroShield v5.05 (5.05-00121)

GPU Nuclear Page :1 File Ref:

DOS File: 12SLAB.MS5 Date:

Run Date: May 9, 2004 By:

Run Time: 8:06:59 AM Checked:

Duration : 00:00:01 Case

Title:

12" Diameter

Description:

Slab - 1" Thick, Cs-137 Source Term Geometry: 8 - Cylinder Volume - End Shields Y

Source Dimensions Height 2.54 cm 1.0 in Radius 15.24 cm 6.0 in Dose Points X Y z

1 0cm 10.16 cm 0 cm 0.0 in 4.0 in 0.0 in z

Shields Shield Name Dimension Material Density Source 1853.333 cm? Concrete 2.35 Air Gap Air 0.00122 Source Input Grouping Method : Actual Photon Energies Nuclide curies becquerels uCi/cm3 Ba/cm 3 Ba-137m 4.1201e-009 1.5245e+002 2.2231e-006 8.2255e-002 Cs-137 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 Enermy Activitv Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cn-?sec MeV/cm2/sec mR/hr mR/hr 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 1I.196e-07 0.0364 2.119e+00 6.726e-06 8.749e-06 3.821e-08 4.971 e-08 0.6616 1.372e+02 3.202e-02 4.057e-02 6.207e-05 7.865e-05 ATTACHMENT 9 - 6

rdt: .e DOS File: 12SLAB.MS5 Run Date: May 9, 2004 Run Time: 8:06:59 AM Duration : 00:00:01 Energy Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photonsfsec MeV/crrIsec MeV/cm 2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup TOTALS: 1.483e+02 3.204e-02 4.060e-02 6.226e-05 7.888e-05 ATTACHMENT q *6

MicroShield v5.05 (5.05-00121)

GPU Nuclear Page :1 File Ref:

DOS File: PLATE.MS5 Date:

Run Date: May 10, 2004 By:

Run Time: 11:03:01 AM Checked:

Duration : 00:00:00 Case

Title:

Steel Surface

Description:

12 Inch Diameter, 1/8" Layer of Oxide Geometry: 3 - Disk NY Source Dimensions Radius 15.24 cm 6.0 in X Dose Points X Y z

1 7.9375 cm 0 cm 0cm SIN 3.1 in 0.0 in 0.0 in Shields Shield Name Dimension Material Density Shield I .318 cm Iron Oxide 5.1 Air Gap Air 0.00122 Source Input Grouping Method : Actual Photon Energies Nuclide curies becquerels uCilcm2 Bq/cm2 Ba-137m 6.9026e-010 2.5540e+001 9.4600e-007 3.5002e-002 Cs-137 7.2966e-010 2.6997e+001 1.00OOe-006 3.7000e-002 Buildup The material reference is : Shield I Integration Parameters Radial 40 Circumferential 40 Results Enernv Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cmrlsec MeV/cm2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.0318 5.287e-01 5.790e-1 0 6.708e-1 0 4.823e-12 5.588e-1 2 0.0322 9.755e-01 1.437e-09 1.670e-09 1.157e-11 1.344e-1 1 0.0364 3.550e-01 7.253e-09 8.719e-09 4.121e-1 1 4.954e-11 0.6616 2.298e+01 6.714e-03 7.745e-03 1.302e-05 1.501 e-05 TOTALS: 2.484e+01 6.714e-03 7.745e-03 1.302e-05 1.501 -p5 ATTACHMENTU 9 - Z.

Williamsburg Concrete Background Measurements 37122N21 Instrurnent 95348 RLM6220 Time Detector Counts Count Time (sec) lModo Desianator FSS-001 BHB 0 BKGND 114102 08:52 1 7.26E+03 1800 SCL Inital Background B Correction Factor I Source Check 1/4102 09:07 1 1.79E+05 60 SCL Source 0 1 40 2 BKGND 1/4102 10:05 2 4.40E+01 1800 SCL Inital Background a 14 Source Check 1/4102 10:39 2 1.51E+05 60 SCL Source a Shielded Unshlelded 15 CON AlS 1/4102 13:00 1 2.78E+02 60 SCL Shielded 0 12.78E+021 16 CON A1U 1/4102 13:02 1 3.88E+02 60 SCL Unshielded 3.48E+02 17 CON A2S 1/4102 13:20 1 2.39E+02 60 _ __SCL .- Shielded _ 2.39E+02 _

18 CON A2U 1/4102 13:21 1 2.22E+02 60 SCL Unshielded 1.82E+02 19 CON A3S 1/4102 13:28 1 2.39E+02 60 SCL Shielded 2.39E+02 20 CON A3U 1/4102 13:30 1 2.62E+02 60 SCL Unshielded 2.22E+02 21 CON A4S 1/4/02 13:36 1 2.45E+02 60 SCL Shielded 2.45E+02 22 CON A4U 1/4/02 13:38 1 2.71 E+02 60 SCL Unshielded _ __ 2.31 E+02 23 CON A5S 1/4/02 13:58 1 2.00E+02 60 SCL Shielded 2.00E+02 24 CON A5U 1/4/02 14:00 1 2.82E+02 60 SCL Unshielded B I 2.42E+02 25 CON A6S 1/4/02 14:03 1 1.84E+02 60 SCL Shielded 1.84E+02 26 CON A6U 1/4102 14:05 1 3.102+02 60 SCL Unshielded p I 2.70E+02 27 CON A7S 1/4/02 14:09 1 1.98E+02 60 SCL Shielded 1.98E+02 28 CON A7U 1/4102 14:10 1 3.15E+02 60 SCL Unshielded n 2.75E+02 29 CON A85 1/4/02 14:19 1 2.34E+02 60 SCL Shielded 2.34E+02 30 CON A8S 114/02 14:22 1 2.31E+02 60 SCL Shielded 2.31 E+02 31 CON A8U 114/02 14:24 1 2.88E+02 - - 60 - - SCL Unshielded - - 2.48E+02 32 CON A9S 1/4/02 14:31 1 2.65E+02 60 SCL Shielded B 2.65E+02 33 CON A9U 1/4102 14:33 1 2.89E+02 60 SCL Unshielded B 2.49E+02 34 CON A10S 1/4102 14:42 1 2.46E+02 - 60 SCL Shielded 2.46E+02 I -__

35 CON A1OU 114102 14:43 1 3.16E+02 60 SCL Unshielded n 2.76E+02 36 CONA11S 1/4102 15:10 1 1.95E+02 60 SCL Shielded 1.95E+02 37 CONA11U 1/4102 15:12 1 2.94E+02 60 SCL Unshielded f 2.54E+02 38 CONA125 114102 15:13 1 2.21 E+02 60 SCL Shielded B 2.21E+02 _

39 CON A12U 114102 15:14 1 2.84E+02 60 SCL Unshielded _ 2.44E+02 40 CON A135 1/4102 15:23 1 1.74E+02 60 SCL Shielded _ 1.74E+02 ___

41 CONA13U 1/4102 15:24 1 2.94E+02 60 SCL Unshlelded H 2.54E+02 42 CON A145 1/4102 15:25 1 1.96E+02 60 SCL Shielded 1.96E+02 43 CON A14U 1/4r02 15:26 1 3.33E+02 60 SCL Unshielded ._

I 2.93E+02 44 CON A15S 1/4102 1528 1 2.16E+02 60 SCL Shielded 2.16E+02 45 CON A15U 1/4102 15:29 1 3.45E+02 60 SCL Unshielded f 3.05E+02 46 CON A16S 1/4102 15:30 1 1.83E+02 60 SCL Shielded 1.83E+02 ..

47 CON A16U 1/4102 15:31 1 3.13E+02 60 SCL Unshielded _ . 2.73E+02 48 CON A175 1/4102 15:33 1 1.82E+02 60 SCL Shielded 1.82E+02 ___I 49 CON A17U 1/4102 15:34 1 3.22E+02 60 SCL Unshielded A ,: 2.82E+02 50 CON A18S 1/4/02 15:35 1 1.84E+02 60 SCL Shielded 1.84E+02 51 CON A18U 1/4102 15:36 1 3.24E+02 60 SCL Unshielded _ 2.84E+02 52 CON A195 1/4/02 15:37 1 1.91E+02 60 SCL Shielded 1.91E+02 . -

53 CONA19U 1/4/02 15:39 1 3.07E+02 60 SCL Unshielded 2.67E+02 54 CON A205 1/4102 15:40 1 1.94E+02 60 SCL Shielded 1.94E+02 ;______

55 CON A20U 1/4/02 15:41 1 3.33E+02 60 SCL Unshielded _ 2.93E+02 56 CON A215 1/4/02 15:57 1 2.23E+02 60 SCL Shielded 2.23E+02 .

57 CON A21U 1/4/02 15:58 1 2.92E+02 60 SCL Unshielded B 2.52E+02 58 CON A225 1/4102 15:59 1 1.72E+02 60 SCL Shielded 1.72E+02 59 CON A22U 1/4102 16:00 1 2.80E+02 60 SCL Unshielded A 2.40E+02 60 CON A23S 1/4/02 16:01 1 1.94E+02 60 SCL Shielded 1.94E+02 _-_-

61 CON A23U 1/4102 16:02 1 3.29E+02 60 SCL Unshielded A .___ I 2.89E+02 62 CON A245 1/4/02 16:04 1 1.87E+02 60 SCL Shielded 1.87E+021 63 CON A24U 1/4102 16:05 1 3.48E+02 60 SCL Unshielded _ 3.08E+02 -

64 CON A255 1/4/02 16:06 1 2.07E+02 60 SCL Shielded 2.07E+02 65 CON A25U 1/4102 16:07 1 3.72E+02 60 SCL Unshielded I 3.32E+02 66 CON A265 1/4/02 16:09 1 2.09E+02 60 SCL Shielded 2.09E+02 _

67 CON A26U 1/4102 16:10 1 3.26E+02 60 SCL Unshielded _ 2.86E+02 68 CON A275 1/4102 16:11 1 2.07E+02 60 SCL Shielded 2.07E+02 69 CON A27U 1/4102 16:12 1 3.30E+02 60 SCL Unshielded J5 2.90E+02 70 CON A28S 1/4/02 16:14 1 2.30E+02 60 SCL Shielded 2.30EtO21 71 CON A28U 1/4102 16:15 1 3.06E+02 60 SCL Unshielded B 2.66E+02 72 CON A29S 1/4102 16:20 1 2.13E+02 60 SCL Shielded _ 2.13E+02 73 CON A29U 1/4102 16:21 1 2.58E+02 60 SCL Unshielded 2.18E+02 74 CON A30S 1/4102 16:24 1 2.33E+02 60 SCL Shielded 2.33E+02 75 CON A30U 1/4/02 16:25 1 2.89E+02 60 SCL Unshielded _ 2.49E+02 76 CON A31S 1/4/02 16:28 1 1.84E+02 60 SCL Shielded 1.84E+02 _

77 CONA31U 1/4/02 16:29 1 2.63E+02 60 SCL Unshielded B 2.23E+02

- Source Check 1/4/02 17:27 1 1.70E+05 60 SCL - 1 Minimum => 1.72E+02l 1.82E+02 Max/mum - 2.78E+02l 3.48E+02 Mean

2.1_ E+021l 2.66E+02 Sigma = 2.69E+01 I 3.45E+01 ATTACHMENT_1 L2 .- /

Discharge Tunnel Concrete Variability Measurements - 2 Instrument 80500 BB7173 Time Detector Counts Count Tlime (sec) Mode Designator FSS-178 BHB 2 DTUNL FP1S 7115103 08:47 1 1.59E+02 60 SCL Shielded 1.59E+02 3 DTUNL FP1U 7115103 08:48 1 3.97E+02 60 SCL Unshielded 3.97E+02 4 DTUNL FP2S 7115103 08:51 1 1.82E+02 60 SCL Shielded 1.82E+02 5 DTUNL FP2U 7115103 08:52 1 2.10E+02 60 SCL Unshielded I2.IOE+02 6 DTUNLFP3S 7/15103 08:55 1 1.73E+02 60 SCL Shielded 1.73E.02 7 DTUNL FP3U 7/15/03 09:00 1 2.75E+02 60 SCIL Unshielded 2.75E+02 8 DTUNLFP4S 7/15/03 09:02 1 1.82E+02 60 SCL Shielded 1.82E+02 9 DTUNL FP4U 7115103 09:03 1 2.87E+02 60 SCL Unshielded e 2.87E+02 10 DTUNL FP5S 7115/03 09:06 1 1.71E+02 60 SCL Shielded 1.71E+02 11 DTUNL FPSU 7/15103 09:07 1 2.45E+02 60 SCL Unshielded 2.45E+02 12 DTUNL FP6S 7/15/03 09:09 1 1.69E+02 60 SCL Shielded 1.69E+02 13 DTUNL FP6U 7/15103 09:10 1 3.23E+02 60 SCL Unshielded 3.23E+02 14 DTUNL FP7S 7/15/03 09:13 1 1.95E+02 60 SCL Shielded 1.95E+02 15 DTUNL FP7U 7/15103 09:14 1 2.90E+02 60 SCL Unshielded 2.90E+02 16 DTUNL FP8S 7115/03 09:16 1 1.82E+02 60 SCL Shielded 1.82E+02 17 DTUNL FP8U 7/15/03 09:17 1 2.89E+02 60 SCL Unshielded 2.89E+02 18 DTUNL FP9S 7115/03 09:20 1 1.63E+02 60 SCL Shielded 1.63E+02 19 DTUNL FP9U 7/1503 09:21 1 2.83E+02 60 SCL Unshielded 2.83E+02 20 DTUNL FP1OS 7115103 09:23 1 1.64E+02 60 SCL Shielded 1.64E+02 21 DTUNL FP1OU 7115103 09:24 1 3.09E+02 60 SCL Unshielded 3.09E+02 24 DTUNLFP11S 7115/03 09:30 1 1.52E+02 60 SCL Shielded 1.52E+02 25 DTUNLFPIIU 7115103 09:31 1 1.76E+02 60 SCL Unshielded . 1.76E+02 26 DTUNL FP12S 7115/03 09:33 1 1.26E+02 60 SCL Shielded 1.26E+02 27 DTUNLFP12U 7115/03 09:34 1 1.91E+02 60 SCL Unshielded . 1.91E+02 28 DTUNL FP13S 7115/03 09:35 1 1.33E+02 60 SCL Shielded 1.33E+02 29 DTUNL FP13U 7115/03 09:36 1 2.30E+02 60 SCL Unshielded 2.30E+02 30 DTUNL FP14S 7115103 09:38 1 1.50E+02 G0 SCL Shielded 1.50E+02 31 DTUNLFP14U 7115/03 09:39 1 1.90E+02 60 SCL Unshelded 1.90E+02 32 DTUNL FP15S 7/15/03 09:41 1 1.47E+02 60 SCL Shielded 1.47E+02 33 DTUNL FP15U 7/15/03 09:42 1 2.48E+02 60 SCL Unshielded a 2.48E+02 34 DTUNL FP16S 7/15/03 09:45 1 1.69E+02 60 SCL Shielded 1.69E+02 35 DTUNL FP16U 7115/03 09:47 1 2.39E+02 60 SCL Unshielded 2.39E+02 36 DTUNL FP17S 7115/03 09:51 1 1.86E+02 60 SCL Shielded 1.86E+02 37 DTUNL FP17U 7115103 09:53 1 3.25E+02 60 SCL Unshielded 3.25E+02 38 DTUNL FP18S 7115/03 09:55 1 1.81E+02 60 SCL Shielded 1.81E+02 -;

39 DTUNL FP18U 7115/03 09:56 1 3.29E+02 60 SCL Unshielded r . : . 3.29E+02 40 DTUNL FP19S 7115/03 09:59 1 1.53E+02 60 SCL Shielded 1.53E+02 41 DTUNL FP19U 7/15103 10:00 1 3.15E+02 60 SCL Unshielded . 3.15E+02 42 DTUNL FP20S 7/15/03 10:02 1 1.81E+02 60 SCL Shielded 1.81E+02 -

43 DTUNL FP20U 7/15103 10:04 1 3.43E+02 60 SCL Unshielded .. . 3.43E402 44 DTUNLFP21S 7115/03 10:07 1 1.94E+02 60 SCL Shielded 1.94E+02 45 DTUNLFP21U 7115/03 10:08 1 3.53E+02 60 SCL Unshielded 3.53E+02 46 DTUNL FP22S 7/15103 10:10 1 1.88E+02 60 SCL Shielded 1.88E+02 47 DTUNLFP22U 711503 10:11 1 3.53E+02 60 SCL Unshielded ..-. 3.53E+02 48 DTUNL FP23S 7/15/03 10:14 1 1.64E+02 60 SCL Shielded 1.64E+02 49 DTUNL FP23U 7115/03 10:15 1 3.77E+02 60 SCL Unshielded 3.77E+02 50 DTUNL FP24S 7/15103 10:17 1 1.54E+02 60 SCL Shielded 1.54E+02 .-

51 DTUNLFP24U 7115/03 10:18 1 3.18E+02 60 SCL Unshielded I . 3.18E+02 52 DTUNLFP25S 7/15/03 10:20 1 1.71E+02 60 SCL Shielded 1.71E+02 .

53 DTUNL FP25U 7/15/03 10:22 1 3.24E+02 e0 SCL Unshielded . 3.24E+02 56 DTUNL FP26S 7/1503 10:32 1 1.92E+02 60 SCL Shielded 1.92E+02 57 DTUNL FP26U 7/15/03 10:33 1 2.30E+02 60 SCL Unshielded - 2.30E+02 58 DTUNL FP27S 7/15/03 10:35 1 1.93E+02 60 SCL Shielded 1.93E+02 59 DTUNL FP27U 7115103 10:36 1 2.70E+02 60 SCL Unshielded . 2.70E+02 60 DTUNL FP28S 7115103 10:38 1 2.15E+02 60 SCL Shielded 2.15E+02 61 DTUNL FP28U 7115/03 10:39 1 3.85E+02 60 SCL Unshielded 3.85E+02 62 DTUNL FP29S 7/15/03 10:41 1 1.99E+02 60 SCL Shielded 1.99E+02 63 DTUNL FP29U 7115/03 10:42 1 3.20E+02 60 SCL Unshielded . .3.20E+02 64 DTUNL FP30S 7115103 10:44 1 1.80E+02 60 SCL Shielded 1.80E+02 . -,

65 DTUNL FP30U 7115/03 10:45 1 3.17E+02 60 SCL Unshielded .I . 3.17E+02 66 DTUNL FP31S 7115/03 10:46 1 1.69E+02 60 SCL Shielded 1.69E+02 67 DTUNL FP31U 7/15103 10:48 1 2.91 E+02 60 SCL Unshielded . 2.91 E+02 68 DTUNL FP32S 7/15103 10:49 1 1.57E+02 60 SCL Shielded 1.57E+02 69 DTUNL FP32U 7/15103 10:50 1 3.07E+02 60 SCL Unshielded .. 3.07E+02 70 DTUNL FP33S 7/15/03 10:52 1 1.55E+02 60 SCL Shielded 1.55E+02 71 DTUNL FP33U 7115103 10:54 1 2.39E+02 60 SCL Unshilded . 2.39E+02 72 DTUNL FP34S 7/15/03 10:56 1 1.59E+02 60 SCL Shielded 1.59E+02 73 DTUNL FP34U 7/15/03 10:57 1 4.12E+02 60 SCL Unshielded 4.12E+02 74 DTUNL FP35S 7/15/03 10:59 1 1.89E+02 60 SCL Shielded 1.89E+02 75 DTUNLFP35U 7/15/03 11:00 1 4.11E+02 60 SCL Unshielded . .- . 4.11E+02 Shielded Unshielded MAlnmum = 1.26E+02 1.76E+02 Maxrmum = 2.1SE+02 4.12E+02 Mean = 1.71 E+02 2.97E+02 Slama = 1.93E+01 6.21 E+01 ATTACHMENT IlL..- L

Number aSaxton Nuclear Exper imerital Corporation

. k- SAXTON NUCLEAR Facility Policy and FProcedure Manual E900-IMP-4520.06 Tite Revision No.

Survey Unit Inspection in Support of FSS Design o0 i~..

EXHIBIT I Survey Unit Inspection Check Sheet I .

_--I,' .

'TiOS. 1-SUR2E

... Ut¶V U NIliNSPECTIONDESC PTION ;.:

Survey Unit X 5 Survey Unit Location I% 0 T Cctu elUt ILST t ,sc Date Time l Inspection I Team Members SECTION 2 SURVEY UNIT.INSPECTION SCOPE Inspection Requirements (Check the appropriate Yes/No answer.) Yes No IN!A

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

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

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

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

5. Are the survey surfaces relatively free of loose debris (i e.. dirt, concrete dust, metal filings, etc.)7

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

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 established7 (Refer to Exhibit 2 for instructions.)

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

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

11. Is lighting adequate to perform the FSS?

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

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

14. Have all unsatisfactory conditions been resolved?

. Is 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.

.1; Comments: G goC.L'j,44 . -f4C (-ISZVJ 6Act 4

A I

Survey Unit Inspector (print/sign)

. Survey Designer (prinrtsign) I yp, 6

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 - -O- -

EXHIBIT 3 Surface Measurement Test Area (SMTA) Data Sheet SMTANumber SM - - Survey Unit Num be lSurvey Unit Number SMTA Number I SMTA -

SMTA Location I Survey Unit Inspector W

55q 5

TziusV-14V CTu vve)

I CC`LwA F\(iST s'j lDate

1 3.n~dm11`4 .i';;SE-TiN,,2 -. ALIPER iNFdkMAf16N 8&PERSO-N-NEl CaliperManufacturer i Al4 #Iv}

Caliper Serial Number Rad Con Technician I Survey Unit Inspector Approval i r l

3 MESECTA SMTA Grid Map & Measurement Results in Units of mm Comments (Insert Results in White Blocks Below) ar [.7Ii 13 ' i' 26 31 ~9V T4 4

g0Pf=Ic-1 tzzvt0-1tr75 UtA. -

1-W#W '-;Gl: 6!l',S@F;22 C;. 28 : 3.

4 8 3 Z7 I)3 .7-U 13 IE W

A~verage Measurement ZA 6' mm Additional Measurements Required (1Iv i-I0- OtA;-°° Li (ajj 46 c5Y4 < sYUZ')

~*(ri-($I

.sj-z00L14~Z~ q~ zwSAO,^J ss CIA-A? l *5 5 L4-00oO (IsA I $7 t55Lf...vO3 3 Z~ £rq-of00 erA 1(67-k -

53qt/vLt >JL /$4 SS4-00 5 3~Ar6A4 s 5 5&j-oO7 Its&iU 6l373

-+s o.q Ms2 roA 5,55L00gv 5 J u* ) 5-147j zrS 1 d f5 ',i'. Y2 9

Number Saxton Nuclear Experimental Corporation SAXTON NUCLEAR I Facility Policy and Procedure Manual E900-4MP-4520.06 Title Revision No.

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

FiirJ; URE INSPECTION DESCRkIPTION ;-."vw.'n~

IJ4T ~ ~

g!, t~gI ,;,, SECTIOs I -_SURVtEKY,, iSE IgP@, l i Survey Unit# Survey Unit Location l)qSC 6-GTutih-el FL4>x,, T f5b Date Time 1s Inspection Team Members

~~ E.~~t SECTION 2SREUJT.NPCIN~OE' '~~~

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

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

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

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

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

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

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

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.)

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

11. Is lighting adequate to perform the FSS?

,j 1 12. Is the area Industrially safe to perform the FSS? (Evaluate potential fall & trip hazards, confined spaces, etc.) G

1,

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

I 14. Have all unsatisfactory conditions been resolved?

n.?

'Is NOTE: If a No answer is obtained above, the inspector should immediately correct the problem or initiate corrective actions through the

.-.11 responsible site department, as applicable. Document actions taken and/or justifications in the Comments section below. Attach additional A.

I -i sheets as necessary.

I Commentsq oa S2t4 i {APEoV LELa Mol.S40,_ rpf

.1

.A 4V b-0-4u C-0 4cA ccsr-c, ,4'r-toJL A51 z~ ok¢\

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N Survey Unit Inspector (print/sign) i...... Date i71a3h)

Survey Designer (print/sign) l .- ,j Date g° 6

Number SN Saxton Nuclear Experimental Corporation SAXTON NUCLEARI Facility Policy and Procedure Manual E900-IMP-4520.06 Title Revision No.

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

.. * . SECTION 1-DESCRIPTiON' -

SMTA Number SMTA - 55 1-} Survey Unit Number S5 I SMTA Location 5Cv 9p- _ F tZS T 15- tFS Survey Unit Inspector i .)bueslL\'J c.. Date 7/3/a3 l Time lZSo

.SECTION 2 - CAlOERMFORMATION & PERSONNEL INVOLVED Caliper Manufacturer l %4A A 0 -o Caliper Model Number ICj-4' CS Caliper Serial Number 0 763 3173 Calibration Due Date (as applicable) I D°5 Rad Con Technician l&,s i Date I ,4/ f Time / I Survey Unit Inspector Approval /Date 137o)

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

1 7 13 '19 26 31 L4.q I-I 07 Ly (

6 Dy 5' rS'-f 5_i

_1 r Sve c) -IS xC 2 5 14 20 26 32 6,3 5,2- o.qe o,'L o I1 9 .- 1 21 27 i4 10o ' 18 22 28 34 m2,7 I- 3,-

26 5, iy1 17*T . 23 29 35 1,7 ; lO

(- l3 lS 42 1i8 24 30 36' 2 V57i 0,-6 G , .7 Average Measurement I mm Additional Measurements Required P44e OV1-i 401 k 4t

,Ir-1 Ayrl1 bcPw- COgk. " es S-4 31l°°IA~{I' 3*£i'" m, -8g1 y~'sl .1 55l-aoq't 3cf-m It;At2/ 7 1.4jlimtL ll6 3 5 0 r

6Z3,{-As4,,

ssl-Oo A WA 7 0" Y5 3-InIL t S51-o'ns'- OA ' 32'")c' I3&4 27, 9

Number Saxton Nuclear Experimental Corporation Facility Policy and Procedure Manual E900-IMP-4520.06 Survey Unit Inspection in Support of FSS Design l 0 EXHIBIT 1 Survey Unit Inspection Check Sheet

.tp; ~SECTIONIS 1 URVEY UNIT INSPECTION DESCRiPTlO;N, .' L',.-r.;.3/4 Survey Unit# . l ..2 Survey Unit Location _T)I \k)-JL_,W TrT ,FjrS-TjtFT Date "73 0 l Time l143c, - Inspection Team Members 5 4u5. 1 J Srt j

.2: SECTION 2 . SURVE? UNIT INSPECTION SCOPE *. ,*.. *.

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

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

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

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

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

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

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

7

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.) Cz-)

9. Have the Surface Measurement Test Areas (SMIVTA) data been collecled? (Refer to Exhibit 2 for instructions.)

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

11. Is lighting adequate to perform the FSS?

12. Is the area Industrially safe to perform the FSS7 (Evaluate potential fall & trip hazards. confined spaces. etc.)

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

wi

14. Have alt 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 1 heets as necessary.

Comments: hD *j I .t'i ;4 t 24 5. $,rte i g F J L 4 4

u. -v8tJ9 24 P -A ' U \ F bJj ++ " 'olG 4 V-4. :H r:

i r

., .5. I . _

Survey Unit Inspector (print/sign) \Dt Date 7131

. ,Survey Designer (print/sign) ,.;.. Date 3 0 6

N.u,me rst. - " '

I Number SAXTON NUCLEAR Title I Saxton Nuclear Experimental Corporation Facility Policy and Procedure Manual E900-IMP-4520.06 Revision No.

Survey Unit Inspection in Support of FSS Design 0 EXHIBIT 3 Surface Measurement Test Area (SMTA) Data Sheet eitcQ:&I,-;,: ', *' . SECTION 1 -.DESCRIPTiON . ' * * ..

SMTA Number SMTA - 7.-OD-L l SurveyUnitNumber 5S6-- -

SMTA Location £5$L3/4 Alvf2th vvI)

Survey Unit Inspector l Z<1ZS li Date I 2zS Timel //1o SECTION 2 - CALIPER INFORMATION & PERSONNEL INVOLVED Caliper Manufacturer l Jl ( JCaliper Model Number I C 0-6 C'5 Caliper Serial Number l 76 3 3l Calibration Due Date (as applicable) 1/0703 Rad Con Technician I r -. Date I rl Time Survey Unit Inspector Approval l)/ iDate SECTION 3 - MEASUREMENT RESULTS SMTA Grid Map & Measurement Results in Units of mm Comments (Insert Results in White Blocks Below) Comments 7' 13 19 25 31

- 13 I1 S c.2. o.3 5 7 SM T LPJ T I2(s&iE' -

- -' - - - gZvc'.[Ar(. OJ A-. 4 c-.A-$

2 ' 14 20 26 32 0 S--'-- - u 43, 9 IL*5 .21 6.7 3 ,

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fx2 10, 18 22 28 34 i

. t 1i' 17 23 29 35 i

{ls7 54 I.t(0 - 1, o, 6.

1 .2 18 ..:;' 24 '30 36 15is7to A O~f AI o.'

Average Measurement S mm Additional Measurements Required 556S.7-DI A 700 / (7 )10 D "' ( 556-2-0C°14 61)(11'16661-1" ) 8 1-aX 5S56.-L47- Iq 1t (1Cf-T1nt),). 5-Z-&oo,4 31"zz2"(6;6m) el f S <^sSY1(103,1.1) 13.3m &$s -IJ Q,(64),1 till 76-ToS/ lC 74"X (7f0- 10,) ,W

.vm 5*2-W l4 3 43"1L lS 7r 71193e 1z3014-,) q,Sm 2e S%- L-o;A 4 Iyg51 11.7 NM l>,-.l5 3ATm 556 - I - O07 U711 24" / (plo 11)Il-3AM 6A l Si 2 t1-0)5z(zS 7. 2,-

9 e

Number Saxton Nuclear Experimental Corporation Facility Policy and Procedure Manual E900-IMP-4520.06 Survey Unit Inspection in Support of FSS Desii EXHIBIT I Survey Unit Inspection Check Sheet

. ;.. SEC R N CTION DESCRIPTION C, ; '

I ...

Survey Unit# Survey Unit Location piscIvuz&Tuj sa4xvAfi-arsJ I&Z)T Date 113j Time 13 Inspection Team Members SECTION 2 - SURVEYUMMTINSPECTION'tCOPE . <*'." -

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

1. Have sufficient surveys (i.e.. post remediation, characterization, etc.) been obtained for the survey unit?7 I -

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

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

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

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

I-

6. Are the survey surfaces relatively free of liquids (i.e . water, moisture, oil, etc.) 7

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

8. Have the Surface Measurerrent 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.)

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

11. Is lighting adequate to perform the FSS?

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

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

14. Have all unsatisfactory conditions been resolved?

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

Comments:

.: 041OAh'0- O SUjPC;-WAS r0 Po~tlJ 4c.6- cccpw (4-ti(Su~wT AddS Survey Unit Inspector (print/sign) r Date 1311

,SurveyDesigner(print/sign) t' Date 6' v.3 6

Number*

Saxton Nuclear Experimental Corporation r SAXTON NUCLEAR Facility Policy and Procedure Manual E900-MP-4520.06 Title Revision No.

Su~rvey Unit Inspection in Support of FSS tDes!g O EXHIBIT 3 r Surface Measurement Test Area (SMTA) Data Sheet A- k I

l Caliper Model Number I CD-(,'

Calibration Due Date (as applicable)

Survey Unit Inspector Approval I . s!,Y-w sl Wi2Z AL1

~S, 3,;Yl.i!}ti.,-. S i 3 - Md,&$REMElT RtESULTS; .. i: ii SMTA Grid Map & Measurement Results in Units of mm Comments (Insert Results in White Blocks Below)

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Average Measurement '1 1 mm Additional Measurements Required SSL~~- \7II 00sl^wzs-'.q A" 56,-1-0V tiq~

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Exhibit I Survey Unit Inspect.on Check Sheet

.. , ,-, ..; .XH SECTION1-SURVEY UNU INSPECTION'DESCRIPTIONW -

Survey Unit # SS1 , 4, SS6-12 Survey Unit Location SSGS Discharge Tunnel (Entrance to 150 ft)

Date l 5/10/04 l Time l 1400 l Inspection Team MembersI D. Sarge

' '" , " -' .. ... '.:'- - -. . - :- - . . . .. . t . .-- , . :-'-, '.: -. - . . .- tllz ... .I-I-- -.1 .-."- . ,.."'% .

.- - - , '4".- I...- '- -SECTION 2 "SURAW

-, - IFEY UNIT INSPECTION SCOPE: '- .-..

?' ...... _,. _... -:,z Inspection Requirements (Check the appropriate Yes/No answer.)

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

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

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

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

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

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

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.)

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

11. Is lighting adequate to perform the FSS?

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

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

14. Have all unsatisfactory conditions been resolved?

a't NOTE: If a 'No answer Is obtained above, the Inspector should Immediately correct the problem or Initiate corrective actions through the responsible ste department, as applicable. Document actions taken andlorjustifications In the Comments section below. Attach additional sheets as necessary.

Comments:

Response to Question 6 - Water present on majority of floor areas. Must be removed prior to performance of survey.

Response to Question 10 - Scaffolding will be installed to allow access to higher elevations of the walls and 1-ceiling.

Response to Question 11 - Lighting will be improved prior to start of survey.

Response to Question 12 - Discharge Tunnel access is controlled under the Confined Space Program.

Survey Unit Inspector (print/sign) David Sarge / Date 5/11/04 Survey Designer (print/sign) I'. S0 8k M - 4ED f Aa l Date

ML052140065

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