ML051950120

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Final Status Survey Report for Saxton Nuclear Experimental Corporation Open Land Area Survery Units OL11-1 and OL11-2
ML051950120
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 06/22/2005
From: Kuehn G
GPU Nuclear Corp
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
E910-05-025
Download: ML051950120 (22)


Text

ONpU NUCLEAR GPU Nuclear, Inc.

Three Mile Island Nuclear Station Route 441 South Post Office Box 480 Middletown, PA 17057-0480 Tel 717-948-8461 June 22, 2005 E910-05-025 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen, Subject Saxton Nuclear Experimental Corporation (SNEC)

Operating License No., DPR-4 Docket No. 50-146 FSS Report for Open Land Area OL11 The purpose of this letter is to submit for your review the attached FSS Report for Open Land Area OL1 1. One CD-ROM is included in this submission. The CD-ROM labeled: UFSS Report for Open Land Area OL11 - Publicly Available" contains the following 5 files:

Document Title File Name File Size (Mbytes)

Main Report 001 FSS Report-OL11.pdf 1.05 Appendix A (pages 1 to 9) 002 OLI I - Appendix A (1-9).pdf 33.8 Appendix A (attachments 1-1 to 4-3) 003 OL11 -Appendix A 37.9 Appedix(attachments 1 -1 to 4-3).pdf ApedxA (attachment 5-1 to 9-2) 004 OLI I - Appendix A 4.

Appendix A(attachments 5-1 to 9-2).pdf Appendix B to Appendix C 005 OLA e -Appendix B to 20.8 AppendixC.pdf__

If you have any questions on this information, please contact Mr. Art Paynter at (814) 635-4384.

Program Director, SNEC cc:

NRC Project Manager NRC Project Scientist, Region I Mr. Tim Bauer, ORISE Project Leader 1,O2V

Final Status Survey Report For Saxton Nuclear Experimental Corporation Open Land Area Survey Units, OLII-1 and OL11-2 IL<

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4L4 The Saxton Coal Fired Steam Generating Station - Photo from Operational Period Showing Approximate Location of the OL.111 and OL11-2 Open Land Area Survey Units Prepared by GPU Nuclear, Inc.

June 2005

Final Status Survey - OLI I Open Land Area Table of Contents Section No.

Page Executive Sum m ary.....................................................

1.0 Purpose and Scope

3 2.0 Survey Area Description.

3 3.0 Operating History...........................................................................................

3 3.1 OLI I Area Use 3

3.2 OLII Remediation Status 4

3.3 SNEC Facility Operating History..........................................

4 4.0 Site Release Criteria 5

4.1 OL1 IArea Specific DCGLw Values 5

5.0 Final Status Survey Design/DQO Process 6

5.1 Description of Survey Unit.8 5.2 Survey Design for the OL11 Open Land Area 8

6.0 Final Status Survey Results 8

6.1 Summary of Survey Results for OL11.......................................................

8 6.2 Survey and Sample Locations.1.1 7.0 Data Asessment,,,,,,,,,....................................................................................... l 7.0 Data Assessment 12 7.1 Assessment Criteria 12 7.2 Survey Variations (Design, Survey Request, LTP),..........................,,,,,,,,,,,,,,,,, 13 7.3 Quality Control Measurements.15 7.4 Assessment Summary.....................................

1 5 8.0 Final Status Survey Conclusions 1 6 9.0 References 17 10.0 Appendices 10.1 Appendix A - SNEC Calculation No. E900-05-021, 'OL11 & Remaining OL12 Open Land Area - Survey Design", April 8, 2005.

10.2 Appendix B - Survey Request Results Summary'for SR-0209 (OL11-1), May 31, 2005.

10.3 Appendix C - Survey Request Results Summary for SR-0210 (0L11-2), May 31, 2005.

i

Final Status Survey Report - OLI I Open Land Area List of Figures.

Figure No.

Title Page 1

Photo of the Saxton Steam Generating Station Showing OL11 Area Cover 2

SNEC Facility site area grid map showing the location of OL 1-1 & OL1 1-2 1

3 Random Start, Triangular Grid, Systematic Spacing Sample Points 12 ii

Final Status Survey Report - O11 Open Land Area List of Tables Table No.

Title Page 1

OL11 DCGLw Values 6

2 DQO/Design Parameters/Results 7

3 OL1 1-1 Random Start, Triangular Grid, Systematically Spaced Soil Samples 10 4

OL11-2 Random Start, Triangular Grid, Systematically Spaced Soil Samples 10 5

Alarm Point Investigation Results - Soil Samples 11 6

Grid Areas Unavailable for Scanning (M2) 14 7

O11I QC Sample Comparison (Cs-137) 15 iii

Final Status Survey - OLII Open Land Area Executive Summary This report presents the results and conclusions of the Final Status Survey (FSS) conducted by GPU Nuclear, Inc. within the SNEC facility OL11 open land area (survey units OL11-1 and OL1 1-2). This report provides summary results from volumetric scanning and sampling of soils within OL1 1. This survey work began April of 2005 and concluded May 2005. All survey work was performed in accordance with the SNEC License Termination Plan (LTP) (Reference 9.1).

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._ _5_ t.t-1 of Appe L12 A ATTACHMENT 5 -1I of Appendix A Figure 2, SNEC Facility site area grid map showing the location of survey units OLI1-1 and OL1 1-2. Each shaded grid location was selected randomly for scanning (each grid Is 100 m2).

Survey data was collected from the OL11-1 and OL11-2 survey units according to data collection requirements specified in the OLI 1 survey design (Reference 9.2 and Appendix A).

Appendix A also includes the survey design for the OL12-1 survey unit, which is not discussed in this report, but will be included in a report to follow.

'1

Final Status Survey Report - OLI I Open Land Area During FSS activities, the foliowing types of measurements were performed on materials found within the OL11 survey area.

1. Nal detector scanning measurements were performed in approximately 2,876 m2 of the OL11-1 survey unit, and in about 2,986 m2 of the OL1 1-2 survey unit. These survey units are Class 2 open land areas, which are required to have a scan coverage between 10 and 100% in accordance with Reference 9.1, Table 5-5.
2. A total of seventeen (17) soil/soil-like samples were obtained from each survey unit using the random start, triangular grid systematic spacing methodology. In addition, two (2) quality control samples were taken in each survey unit. These samples were analyzed by gamma-ray spectroscopy to determine the presence of radionuclides typical of the SNEC facility. Cs-137 is used as the surrogate radionuclide of interest.

FSS scan survey results were less than the action level for the applicable DCGLw in both survey units. All soil and soil-like material samples taken at all sampling depths were below the applicable DCGLw. Therefore, this collection of FSS data demonstrate that this survey unit meets the radiological criteria for unrestricted use specified in 10 CFR 20.1402 (Reference 9.3).

Based on the results of this final-status survey effort, GPU Nuclear, Inc. concludes that the OL11 open land area meets the NRC requirements for release to unrestricted use.

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  • Final Status Survey Report.- O11I Open Land Area 1.0 Purpose and Scone This report presents the results and conclusions of the final status survey performed on the following area:

Open Land Survey Units (OL11-1 and OL11-2) - Class 2 open land area This survey effort provides the information required by 10 CFR 50.82(a)(11) (Reference 9.4) and SNEC's License Termination Plan (LTP), and demonstrate that this area meets the radiological criteria for unrestricted use specified in 10 CFR 20.1402.

2.0 Survey Area Description The northwest open land area.(OL1I) is approximately 10,200 square meters in total area and is designated a Class 2-survey area because of location and early scoping and characterization survey results. OL11 is contained within the area enclosed by site grid markers AZ-146 and BJ-146 on the west, and on the east by grid markers AZ-137, BH-137, and BH-131 through BJ-131 (Reference 9.5).

OL11 is divided into two- (2) survey units (OL11-1 and OL11-2) which are sparsely covered with grass, trees, and small shrubs. The area soil contains a significant quantity of Saxton Steam Generating Station (SSGS) fly ash and coal dirt. An unpaved road passes through OL11 and along the PENELEC property fence line. The roadway composition is the same as the surrounding soil/soil-like materials.

3.0 Operating History 3.1 OL11 Area Use No significant historical facts are reported about the OL11 open land area in the SNEC Historical Site Assessment (HSA) (Reference 9.6). However, old photographs of the area seem to show earth moving activities in or near the area, which may have been connected with the periodic dredging of the Spray Pond. This information is however, unconfirmed.

Scoping and characterization activities have identified low levels of Cs-137 contamination in soil samples from this area at or near background levels, but no significant levels of other SNEC related radionuclides have been found.

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Final Status Survey Report - OL I Open Land Area 3.2 OLII Open Land Area Remediation Status Since all previous sample analysis results have been below the DCGLw, and no remediation has been performed in the area. The OL11 open land area meets the definition of a Class 2-survey area (from Reference 9.1, Section 5.4.2) 3.3 SNEC Facility Operating History The Saxton Nuclear Experimental Corporation (SNEC) facility featured a pressurized water reactor (PWR), which was licensed to operate at 23.5 megawatts thermal (23.5 MWth). The facility is owned by the Saxton Nuclear Experimental Corporation and is licensed by GPU Nuclear, Inc. The SNEC facility is maintained under a Title 10 Part 50 license and associated Technical Specifications. In 1972, the license was amended to possess but not operate the SNEC reactor.

The facility was build from 1960 to 1962 and operated from 1962 to 1972, primarily as a research and training reactor. After shutdown in 1972, the facility was placed in a condition equivalent to the current SAFSTOR status. Since then, it has been maintained in a monitored storage condition. The fuel was removed in 1972 and shipped to a (now DOE) facility at Savannah River, South Carolina, who is now the owner of the fuel. As a result of this, neither SNEC nor GPU Nuclear, Inc. has any further responsibility for the spent fuel from the SNEC facility.

The reactor, containment vessel and support buildings have all been removed from the site. The building and structures that supported reactor operation were partially decontaminated by 1974. In the late 1980's and through the 1990's, additional decontamination, disassembly and removal of the containment vessel support buildings, large and small components and other miscellaneous support equipment was complete.

By 1992 decontamination and dismantlement of the reactor support structures was

-complete. Large components such as the pressurizer, steam generator, and reactor vessel were removed in late 1998. The removal of the steel Containment Vessel (CV) (to - 4' below grade), and backfill was complete by late 2003. More recently, decontamination, disassembly and demolition of the remaining SNEC facility buildings including remnants of the coal fired Saxton Steam Generating Station (SSGS) has taken place. The SNEC facility is currently in the process of performing the Final Status Survey for unrestricted release leading to license termination.

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Final Status Survey Report - OLII Open Land Area 4.0 Site Release Criteria The site release criteria as applied to the OL11 open land area, corresponds to the radiological dose criteria for unrestricted use per 10 CFR 20.1402. The dose criteria is met

'if the residual radioactivity that is distinguishable from background radiation results in a Total Effective Dose Equivalent (TEDE) to an average member of the critical group that does not exceed 25 mrem/yr, including that from groundwater sources of drinking water, and that the residual radioactivity has been reduced to levels that are as low as reasonably achievable (ALARA)."

Levels of residual radioactivity that correspond to the allowable dose and meet site or survey unit release criteria were derived by analyses using either the building occupancy (surface area) or resident farmer (volumetric) scenarios. The dose modeling for these scenarios is explained in Chapter 6 of the SNEC LTP, Revision 3. The derived concentration guideline levels (DCGLs) determined in the LTP form the basis for satisfying the site release criteria.

As described in Chapter 6 of the SNEC LTP (Reference 9.1), a correction to the gross activity DCGLw is made to address de-listed radionuclides and provide a reasonable SNEC established safety factor. The SNEC facility has instituted an administrative limit of 75% for the allowable dose (DCGL) for all measurement results. Thus the de-listed radionuclide dose is accounted for by using the 75% administrative limit.

4.1 OLl IArea Specific DCGLw Values Not counting quality control samples (QC), at least eighty samples were taken in and near the OL11 area during the most recent characterization campaign. Most of these results were at or near background levels for Cs-137, exhibiting a mean concentration of 0.64 +/-

0.47 pCi/g (see Appendix A, Attachment 8-1). The maximum concentration found in this area during this characterization effort was 2.0 pCi/g. Samples taken during an earlier but much more limited characterization effort were.sent to an off-site laboratory for a more complete analysis. The highest concentration from this earlier sample group was reported to be 2.34 pCi/g Cs-137, which is below the DCGLw (SNEC Sample No. SXSLOO87 was sent to Teledyne, October 1999). These early analyses include all SNEC facility related radionuclides (see Appendix A, Attachment 2-1 to 2-3). Off-site analysis results of samples taken from or near the OL1I1 area were pooled to create a conservative mix for this area. Since OL11 Cs-1 37 concentrations are at or near background levels, the relative 5

Final Status Survey Report-OLII Open Land Area ratios between trace amounts of hard-to-detect radionuclides that include natural occurring radionuclides such as C-14, are not necessarily in their expected site-specific proportions.

However, no effort was made to remove background levels from any radionuclide concentration, and therefore the effective DCGLw for the OL11 area is conservatively derived. The effective DCGLw values are provided in Table 1 below. See Appendix A, -1 to 2-3 for the development of these effective DCGLw values.

Table 1, OLII - DCGLw VALUES Volumetric DCGLw (pCilg) for Cs-I37l 3.22 (2.41 A.L.)

NOTE: A.L. Is the site Administrative Limit (75% of the effective DCGLw for the area).

5.0 Final Status Survey DesignlDQO Process Survey Designs (SD's) (Appendix A) are developed lAW applicable sections of the SNEC License Termination Plan (LTP) and site procedures (Reference 9.7).

During development, characterization activities are reviewed along with any post-remediation survey or sampling activities (as applicable). Survey unit variability is established from the best available or most representative measurement and/or sampling result. The Compass computer program (Reference 9.8) is then used to develop MDCscan parameters (for structural surfaces), the number of survey or sampling points in each survey unit, and other DQO design parameters. For open land areas, methodology from NlJREG-1507 (Reference 9.9) is used to calculate MDCscan values that are then input to the Compass computer program. For structural surfaces, representative background values are extracted from previous measurements of non-impacted like-materials of similar age whenever possible. For open land areas, background concentrations of relevant SNEC radionuclides are not subtracted from sample data sets prior to developing individual survey unit surrogate levels (of Cs-137). Thus the effective DCGLw values for open land areas are conservatively biased.

For most survey units, the number of Compass calculated sample and/or survey locations are augmented to provide 'more than the minimum required coverage". Sample and/or survey point locations are plotted on drawings of individual survey areas using the Visual Sample Plan (VSP) computer code (Reference 9.10). Diagrams showing sample and/or survey point locations are clearly depicted on survey maps along with any necessary physical dimensions from known site area landmarks. Diagrams are then provided to 6

Final Status Survey Report - OLII Open Land Area individual survey teamsn ihrough the use of the Survey Request (SR's) procedure process (Reference 9.11). SR's are issued as field working guidance documents. All SD's and SR's are reviewed and approved by the SNEC RSO (or his representative) before implementation. Data Quality Objectives (DQO's) for the OL 1 area are presented in the following table.

Table 2, DQO/Design Parameters/Results S ye n

SNEC Design Calculation. No.

E900-05-021 (Appendix A)

SNEC Survey Request No. (for FSS work)

SR-0209 & SR-210 Survey Area Classification 2

Total Area Size (M2) 10,200 Scanning Goal (M2) 5.100 (50% of total area)

Actual Combined Area Scanned (i 2)

-5,822 (-57%)

Applicable Statistical Test Sign Type I Decision Error (ct) 0.05 Type II Decision Error (P) 0.10 Effective Soil DCGLW (Cs-1 37 pCig) 2.41 (Administrative Umit)

LBGR (Cs-137 pCVg) 1.7 (Appendix A, Attachment 6-2)

Estimated a (Cs-137 pCVg)

OA68 ala 1.52 Minimum No. of FSS Samples Required by Compass 14 (Appendix A, Attachment 6-2, OLI I-1)

Minimum No. of FSS Samples Required by Compass 14 (Appendix A, Attachment 6-5, OL1 1-2)

No. of Sample Locations Specified byVSP**.

17 (Appendix A. Attachment 7-1, OLII-1)

No. of Sample Locations Specified by VSP---

17 (Appendix A. Attachment 7-1, OL11 1-2)

No. of FSS Surface Samples taken to 1 meter depth 27 (OL1 1-1 & OLI 1-2 combined)

No. of FSS Surface Samples Taken to 6-depth (interference')

7 (OL11-2)

Highest From Either Survey Unit During FSS (pClg Cs137) 0.87 Estimated Scan MDC - Soil/Soil-Like Materials (Cs-137 pCVg)

-5.97 (Appendix A, Attachment 4-2 & 4-3)

Scan Speed for Soil and Soil-Like Materials (cm/sec) 25 Nal Action Level During Scanning (FSS)

> 350 gcpm

-6 pCig Cs-1 37 at 200 cpm bkgnd No. of Alarm Points During Scanning Process One (1) In OLI1-2 No. of Samples Taken During Characterization In or Near Area

> 80 Typical Nal Background Level (cpm)

-200 to 300 Survey Instrument Type (narrow window optimized for Cs-137)**

Ludlum 2350-1 w/44-10 Nal probe Instrument Conversion Efficiency (cpm/iR/h) 2 209, 000 (Cs-137 window)

Measurement Protocol 2-by 2 Nal scans and samDles

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Final Status Survey Report -OLI1 Open Land Area 5.1 Description of Survey Unit Figure 2 shows that the OL11 area is approximately 10,200 square meters in total area.

Native soil, cinders, coal ash, with some small quantities of building debris make up the composition of material in this area. The OLI 1 area borders the PENELEC Switch Yard on the west and northern sides and a dirt road, which runs along the perimeter of the PENELEC fence line passes through this area. The area is accurately depicted as a Class 2 survey unit.

5.2 Survey Design for the OLI 1 Open Land Area The survey design for OL11 is provided as Appendix A. Since OLI I is a Class 2 open land area, the initial scanning goal was set at 50% of the total area. Therefore, fifty one (51) 100 nM 2 grid areas were randomly chosen yielding 5,100 square meters scan area.

Eight (8) additional randomly chosen grid areas were provided in the survey design in event one or more of the original set of fifty one (51) were not accessible because of existing obstructions. 100% of each grid was to be scanned. This assignment is in accordance with Reference 9.1, Table 5-5.

The number of random start, triangular grid, systematically spaced sample points were determined using the COMPASS computer program. The minimum number of sample points selected by Compass was fourteen (14) for each survey unit. Each sample was to be one meter in depth to match the site area dose model discussed in Chapter 6 of the SNEC LTP (Reference 9.1).

All sample points were placed on survey maps of the OL 1I area using the Visual Sample Plan (VSP) computer code (Reference 9.10).

6.0 Final Status Survey Results 6.1 Summary of Survey Results for OL11 From Appendix B and C, approximately 57% of the total OLI 1 area was scanned during FSS activities. This scanning effort exceeded the requirements of the survey design, and since FSS scanning requirements for a Class 2 open land area are typically 10 to 100%,

the total scanned area in OL11 is considered adequate. Instrument response above 350 gcpm was used as the action level during the FSS scanning effort. One (1) instrument alarm was encountered in grid BD-138 with a stationary count rate of about 370 gcpm. A sample at the alarm point yielded a Cs-137 concentration of 0.15 pCi/g. Three additional 8

Final Status Survey Report - OLI I Open Land Area samples taken to bound the approximately 0.1 m2 area alarm point, yielded < 0.072, < 0.2 and 0.11 pCi/g Cs-1 37. These results show that the areas natural occurring radionuclides elevate background levels in the Cs-137 window setting of the survey instrument.

Therefore, there was no sample analysis result from any sampling effort (scoping, characterization or FSS), that yielded a value above the DCGLw in either survey unit.

Worth noting is that during characterization activities in this area, the action level was set at 300 gross counts per minute (gcpm), which is at or near background levels. This resulted in a number of samples being taken based on exceeding an alarm point driven solely by background levels. As expected, sample results from these alarm points were all below the applicable DCGLw, and alarms were attributed to elevated concentrations of naturally occurring radionuclides.

In all, well over one hundred (100) characterization and FSS samples have been taken in the OL11 area. During one early scoping survey result a Cs-137 concentration of 2.34 pCi/g was identified (SNEC sample SXSL0087, assayed by Teledyne, October 1999).

However, all sample analysis results, including scoping, characterization and the current FSS sampling effort have been below the effective DCGLw for Cs-1 37.

FSS sample data are provided in Table 3 and 4 below. The variability of the samples identified in Table 3 and 4 are below the initial variability estimate used during the survey-planning phase (see Table 2 initial sigma value).

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Final Status Survey Report - OLI I Open Land Area Table 3, Random Start, Triangular Grid, Systematically Spaced Soil Samples OL11-1 Samnle Results Sample No. Grid No. Sample Point Cs-137W(pCI/g) Sample Depth SXSLI0236 AZ-145 SP-1 0.08 1 meter SXSL10237 BA-146 SP-3 0M6O 1 meter SXSL10238 BA-144 SP-4 0.10 1 meter SXSL10239 AZ-143 SP-2 0.23 1 meter SXSLI0240 AZ-143 SP-2 (QC)

[iD0Ol 7 1 meter SXSLI0241 BA-142 SP-5 Dl OiN 1 meter SXSL10242 BC-145 SP-6 0.23 1 meter SXSL10243 BC-143 SP-7 0.13 1 meter

_ BD-146 SP-8

o:ogrn 1 meter BD-144 SP-9 0.17 1 meter BD-142 SP-10 0.12 1 meter BF-145 SP-11 0.26 1 meter BF-143 SP-12 0.21 1 meter BH-146 SP-13 0.18 1 meter SP-14 0.14 1 meter SP-15 1Ai0.091_

1 meter SP-16 0.07 1 meter SP-17 0.11 1 meter SP-17 (QC) 0.24 1 meter NI Average=*

0.15 11 Slgma:*

0.06 Maximum:*

0.26 Table 4, Random Start, Triangular Grid, Systematically Spaced Soil Samples OL11-2 Sample Results Sampll.N6.I Grid No. -Sample Polnt' Cs'137(pCUg )[Sample' Dopth SXSL10191 BH-132 SP-17 4

0.19 6" Deep SP-16

. 0.70 6" Deep

'1 SP-15 I

0.28 1

6" Deep 36 SP-14 0.87 6" Deep 36 SP-14 QC 0.61 6" Deep 137 SP-13 0.19 6' Deep 38 SP-12 0.14 1 meter 40 SP-11 0.07 1 meter 139 SP-10 0.69 1 meter 141 SP-9 nO Mtil_

1 meter 138 SP-8 0.27 6" Deep 140 SP-7 0.18 1 meter 140 SP-7 QC 0.08 1 meter SP-5 0.07J1111M SP-6 Q110.1m 5 SP-4 0.30 SP-3 0.86 SP-2

  1. 0=

151M SP-1 0.13 i

l Average=-

0.32 iM I

Slggma=

0.28 I

tI Maximum=

-0.87 I

Note: Shaded results were reported as 'Less Than" values.

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Final Status Survey Report - O11 Open Land Area One alarm point was reached in the OL1 1-2 survey unit. The alarm was reported to be about 370 gcpm, which is only slightly above the alarm set-point of 350 gcpm. The alarm point was investigated by sampling the elevated area and several other locations at a one (1) meter radius around the alarm point. The sample results are provided below in Table 5.

Table 5, Alarm Point Investigation Results - Soil Samples OL11-2 Alarm Point Investigation Results

[ Sample.Nol.Grid No.l Sample Point [ Csr137i(pCUgl Sample Depth1 SXSL10492 BD-138 SP-A l

0.11 1 meter SXSL10493 BD-138 SP-2 M0.211W 1 meter SXSL10494 1BD-138 SP-3 15-oijOW 7

1 meter

[SXSL10495 jBD-138 AP-1 1 0.15 l

1 meter Note: Shaded results were reported as 'Less Than' values.

Since all analysis results for Cs-137 were below the DCGLw, and are more characteristic of typical background Cs-1 37 concentrations, no additional samples were taken.

6.2 Survey and Sample Locations Scanning was conducted in randomly selected grid locations. A goal of 50% of the total area was assigned in the survey design, and additional grid locations were provided in the event that some or parts of other grid areas were not accessible to survey team personnel.

Figure 2 provides the randomly selected grid locations for OLI 1.

From the VSP computer code output (Reference 9.10), seventeen sample points were placed in each survey unit as shown on the diagram of Figure 3. Each location, with the exception of four (4), eight (8), and sample point thirteen (13) through five (17) in OL1 1-2, were sampled to a depth of one (1) meter. However, the PENELEC Switch Yard area contains a grounding mat at an original depth of about sixteen (16") inches below the surface (over time this depth has changed up or down in some areas). SNEC personnel were not permitted to disrupt or damage this important component of the Switch Yard grounding circuit. Therefore, sampling in the region of the grounding mat was limited to the upper few inches of sample material available. Figure 3 on the following page provides the locations selected for sampling using a triangular grid systematic spacing methodology.

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Final Status Survey Report - OLI 1 Open Land Area Figure 3, Random Start, Triangular Grid, Systematic Spacing Sample Points BK BJ _

B' BH BG BF BE BD BC BB BA AZ AY_.

7.0 Data Assessment 7.1 Assessment Criteria Final status survey data has been reviewed to verify authenticity, appropriate documentation, quality, and technical acceptability. The review criteria for data acceptability are:

1) The instruments used to collect the data were capable of detecting the radiation of the radionuclide of interest at or below the investigation levels.
2) The calibration of the instruments used to collect the data was current and radioactive sources used for calibration were traceable to recognized standards or calibration organizations.
3) Instrument response was checked before, and when required, after instrument use each day data was collected.

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Final Status Survey Report - OLI I Open Land Area

4) Survey team personnel were properly trained in the applicable survey techniques and training was documented.
5) MDC values and the assumptions used to develop them were appropriate for the instruments and the survey methods used to collect the data.
6) The survey methods used to collect the data were appropriate for the media and types of radiation being measured.
7) Special instrument methods used to collect data were applied as warranted by survey conditions, and were documented in accordance with an approved site Survey Request procedure.
8) The custody of samples that were sent for off-site analysis was tracked from the point of collection until final results were provided.
9) Final status survey data consists of qualified measurement results representative of current facility status and were collected in accordance with the applicable survey design package.

r If a discrepancy existed where one or more criteria were not met, the discrepancy was reviewed and corrective action taken (as appropriate) in accordance with site procedures.

7.2 Survey Variations (Design, Survey Request, LTP) 7.2.1 5,100 square meters of the OL11 area were randomly selected for scanning.

About 400 square meters of survey area were inaccessible in the randomly selected primary grid areas. However, supplemental randomly selected grid locations were provided in the survey design and in some cases, these supplemental grid areas were included in the scan coverage for the area.

Therefore, about 57% of the OL11 open land area was scanned, which is well within coverage requirements for a Class 2-survey unit in accordance with the SNEC LTP, Table 5-5 (Reference 9.1).

7.2.2 The following Table provides a list of grid numbers that were partially scanned.

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Final Status Survey Report - O11 Open Land Area Table 6, OLi11 Grid Areas Unavailable for Scanning Survey (i 2)

,Grid No.'(OL11-1)

Approximate'Area-Size Obstructlo-5 AZ-142 1.2 m2 Standing Trees AZ-144 0.8 m2 Standing Trees AZ-146 0.5 m2 Standing Trees BA-146 1 m2 Standing Trees BA-143 3 m2 Standing Trees BE-145 1.1 m2 Standing Trees BE-146 1 m2 Standing Trees BF-143 0.3 m2 Standing Trees BF-144 0.6 M2 Standing Trees BF-145 0.8 m2 Standing Trees, Brush BF-146 1.9 m2 Standing Trees, Fallen Trees, Brush & Stones BG-143 2 m2 Standing Trees BG-144 0.2 m2 Standing Trees & Brush BH-143 2.1 m2 Standing Trees & Brush BH-146 1.8 m2 Standing Trees, Fallen Trees, Brush & Stones Bl-143 2 m2 Standing Trees, Brush & Stones BI-144 02 m2 Trees & Brush Bl-145 2.8 m2 Standing Trees, Fallen Trees, Brush & Stones BI-146 0.7 m2 Trees & Brush

.Grild No. (OLI1-2)5 Approxirate Aea' Size Obstriuctioni BA-139 1 m2 Standing Trees BA-141 1.8 m2 Standing Trees BC-139 0.4 m2 Standing Trees BG-138 1 M2 Rocks BG-141 1.5 M2 Standing Trees BH-139 I M2 Standing Trees BH-140 1.8 M2 Standing Trees BH-141 1.2 M 2

Standing Trees Bl-133 0.01 m2 Standing Trees BI-135 0.04 m2 Concrete Wall B -137 0.4 rr2 Standing Trees BI-139 3.1 m2 Standing Trees BI-141 1.2 M2 Standing Trees NOTE: Each grid Is 100m 2 in total area.

7.2.3 Sample points four (4), eight (8), and thirteen (13) through seventeen (17) were sampled to a depth of only six (6) inches because of the presence of the PENELEC Switch Yard grounding mat. These sample locations were not relocated because there was no other reasonable points of relief in the area, away from the grounding mat. However, the OL11 survey units did not show any indications of Cs-137 contamination above the DCGLw, and the actual sample depth for these samples is considered representative of deeper soil 14

Final Status Survey Report - OLI I Open Land Area and soil-like materials at their selected locations. Thus the sampling effort is adequate.

7.3 Quality Control Measurements 7.3.1 Two (2) Quality Control (QC) samples were taken in each OL11 survey unit.

The SNEC LTP requires gamma-ray spectrometry scans of sample splits at a minimum frequency of at least 1 QC sample for every 20 samples collected (5%). Results for the two- (2) samples collected per survey unit are in reasonably good agreement, and represent normal background variations between sample volumes from the site. All QC sample results are below the assigned O11 DCGLw. See Table 7 below.

Table 7, OL11 QC Sample Comparison (Cs-137)

Grid No.

Survey Unit Sample Location ID Initial pCU9g Q.pCCg AZ-143 OL11-1 SXSL10239 SP-2 0.23 ISXSLI10240

SP-2 QC 0.17 B-143 OLII-1 SXSL10253 SP-17 0.11 SXSL10254:

SP-17 QC -:;

0.24 Bl-136 OL 1-2 SXSLI 0194 SP-14 0.87 SXSL1 0195 -ax SP-14 QC 0.61 BF-140 OL112 SXSL10202 SP-71 0.18 5XL10195 SP QC :.--.,;:;10.08- ¢. -:<-

7.3.2 Sections of sixteen (16) grids were re-scanned in OL11-1, and seventeen (17) grid sections were re-scanned in OL11-2 as QC duplicates. In all, QC scanning covered approximately 330 m2 of the OL11 area. All scan results were below the alarm point assigned by the survey design. Since the total amount of scanned area in OL11 in about 5,862 i 2, the percent of re-scanned QC area was greater than 5% (330 m2/5,862 M2 x 160%).

Therefore, the amount of re-scanned area is adequate and meets the requirements of the SNEC LTP (> 5% of the area re-surveyed/re-sampled).

7.4 Assessment Summary Statistical testing of the data does not need to be performed for this final status survey since the 'data clearly show that the survey unit(s) meet the site release criteria. These survey units clearly meet the criterion because of the following:

1. E All measurements in the survey units are less than or equal to the DCGLW, or
2. El A background reference area was used, and the difference between the maximum survey unit measurement and the lowest background reference area measurement are less than or equal to the DCGL.

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Final Status Survey Report - OLI I Open Land Area 8.0 Final Status Survey Conclusions The FSS for the OL1 i open land area (OL11) was performed in accordance with Revision 3 of the SNEC LTP and site implementing procedures. Final status survey data were collected to meet and/or exceed the quantity and quality specified for this survey unit as prescribed by the applicable survey design. The survey data for each survey unit met the following conditions:

1.

The average residual radioactivity within the OL11 area is less than the assigned DCGLw.

2.

Since all measurements were less than the DCGLw, no DCGLEMC criteria need be applied.

3.

No remediation was performed to reduce levels of residual radioactivity below concentrations necessary to meet DCGLw values.

These conditions satisfy the release criteria established in the SNEC LTP and the radiological criteria for unrestricted use given in 10 CFR 20.1402. Therefore, it is concluded that the SNEC OL11 Area (OL-11) as described in this report is suitable for unrestricted release.

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Final Status Survey Report - OLI I Open Land Area 9.0 References 9.1 SNEC License Termination Plan 9.2 SNEC Calculation E900-05-021, OL11 & Remaining OL12 Open Land Area -

Survey Design".

9.3 Code of Federal Regulations, 10 CFR 20.1402.

9.4 Code of Federal Regulations, 10 CFR 50.82(a)(1 1).

9.5 SNEC Facility Site Area Grid Map - Drawing Number SNECRM-020.

9.6 SNEC Facility Historical Site Assessment Report, March 2000.

9.7 SNEC Procedure E900-IMP-4500.59, "Final Site Survey Planning and DQA" 9.8 COMPASS computer program, Version 1.0.0, Oak Ridge Institute for Science and Education.

9.9 NUREG-1507, 'Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions".

9.10 Visual Sample Plan computer program, Version 3.0, Battelle Memorial Institute.

9.11 SNEC Procedure E900-IMP-4520.04, "Survey Methodology to Support SNEC License Termination" 9.12 SNEC Procedure E900-ADM-4500.60 "Final Status Survey Report".

9.13 NUREG 1575 "Multi-Agency Radiation Survey and Site Investigation Manual" (MARSSIM), revision 1 August 2000 17