ML052140332

Survey Report, Saxton Nuclear Experimental Corp Site Areas MA3 and MA4 - Weir Discharge Area.

ML052140332
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Site:	Saxton File:GPU Nuclear icon.png
Issue date:	07/31/2005
From:	GPU Nuclear
To:	Office of Nuclear Reactor Regulation
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Download: ML052140332 (73)

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Survey Report Saxton Nuclear Experimental Corporation Site Areas MA3 and MA4 - Weir Discharge Area Removal of the SNEC WEIR Une Extension to the Raystown Branch of the Juniata River--

Prepared by GPU Nuclear, Inc.

July 2005

Site Areas MA3 and MA4 - Weir Discharge Area Table of Contents Section No. Page Executive Summary ............................................................................................................ I

1.0 Purpose and Scope

,,...............................................................................................3 2.0 Survey Area Description ............................................ 3,,,,,,,,,....

3 3.0 Operating History ............................................................................................. ,,,..4 3.1 Weir Line Use.4 3.2 Weir Line Remediation Status erLn 3~~~~~~~~~~~~.2 ....................................................

eeito bu.,,,,,,,,,,.,,,,, ,..... 5... 5 3.3 SNEC Facility Operating History ........................................................... 5 4.0 Site Release Criteria 6 4.1 Weir Line Area Specific DCGLw Values 6 5.0 Survey DesignIDQO Process.7 5.0 SureyDesgnlDQOProcess,,,,,,,,,,,,,,,,,,,,,,..............................

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5.1 Description of Survey Unit.9 5.2 Survey Design for the MA3/MA4 Area ................................................. 10 6.0 Sampling and Survey Results.1.

6.1 Summary of Survey Results from the ENERCON River Study ....... 10 6.2 REMP Sample Results 1999 to 2004.1.1 6.3 Remediation Support Survey ................................................................. 12 7.0 Data Assessment 15 7.1 Assessment Criteria 15 7.2 Survey Variations (Design, Survey Request, LTP) ........................... 16 7.3 Quality Control Measurements .................................................................. 17 7.4 Assessment Summary...................................................................................... 17 8.0 Survey Conclusions 17 9.0 References 18 10.0 Appendices 10.1 Appendix A-1 - SNEC Survey Request SR-0020, June 25, 2001.

10.2 Appendix A SNEC Survey Request SR-0028, August 28, 2001.

10.3 Appendix A SNEC Survey Request SR-0034, October 04, 2001.

10.4 Appendix A DCGLw Calculation Logic for CV Yard.

10.5 Appendix A Scan MDC for Nal Measurement of Soils.

10.6 Appendix A Scan MDC for Geiger Mueller Detector.

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Site Areas MA3 and MA4 - Weir Discharge Area List of Figures Figure No. Title Page 1 Photo of Weir Discharge Line Removal Cover 2 SNEC Grid Map Showing Weir Discharge Line and the MA3/MA4 Areas 1 3 Sketch of Weir Discharge Pipe in Raystown Branch of the Juniata River 4 4 SNEC Grid Map Showing Weir Discharge Line Remediation Support Survey 8 Area ii

Site Areas MA3 and MA4 - Weir Discharge Area List of Tables Table No. Title Page I Weir Discharge Line Samples 7 2 Weir Line - DCGLw Values 7 3 DQO/Design Parameters/Results 9 4 ENERCON Weir Area Sample Results (MA3IMA4 - SR-0034) 11 5 REMP Data from Location Al-4 (Weir Out-fall) 12 6 Soil Bed Sample Results From Below Weir Discharge line (SR-0020, June-2001) 13 7 Soil Bed Sample Results From Below Weir Discharge line (SR-0028, Sep-2001) 14 iii

Site Areas MA3 and MA4 - Weir Discharge Line Executive Summary This report summarizes information collected from the MA3 and MA4 Weir Discharge line and out-fall area. Included, in this report is information from several other reports and a remediation effort that addressed this area, and its formally connected piping. This report provides summary results from post remediation scan surveys, volumetric sampling of sediment within the Juniata River at the exit of the Weir Discharge line, and soil samples taken of the soil bed below the Weir Discharge pipe after its excavation. This survey work is an extension of previous monitoring efforts, and meets many of the requirements set forth by the SNEC License Termination Plan (LTP) (Reference 9.1). This work was conducted by GPU Nuclear, Inc. and is a part of the closeout records for the SNEC facility.

Removed Sections of Weir Drainage Syste

° 00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 00 0 0 0 / 0 ILI

,,RAYSTO* BRANCH

________ JUNIATA RIVER m °' t 0 L 0 2 X a ma 0 W W a 0 m < N . x I0 M 0 0 0 0D 0 0 CD 00 C Figure 2, Sedion of SNEC grid map showing Weir line extension as it empties to the Raystown Branch of the Juniata River Survey data was collected from the Weir Discharge line area according to data collection requirements specified in survey request SR-0020 (Appendix A-1), SR-0028 (Appendix A-2),

SR-0034 (Appendix A-3), and applicable site procedures (e.g., Reference 9.2). The following types of measurements were performed on materials found near the Weir Discharge line and out-fall area.

1. Nal scanning measurements were performed of approximately 220 m2 of soil bed below the Weir Discharge line.

2. . Subsurface soil samples were taken approximately 2 to 2.5 meters below the surface along one hundred ten (110) meters of Weir pipe out to the concrete headwall at the Raystown Branch of the Juniata river.

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Site Areas MA3 and MA4 - Weir Discharge Area

3. Sediment samples were taken in the river at the Weir Discharge line opening, within the pipe itself, and along the shoreline downstream from the exit of the Weir Discharge pipe (see Appendix A-3).

4. All samples were analyzed by gamma spectroscopy. Several samples were also sent to off-site laboratories for a more complete analysis that included all radionuclides associated with the SNEC facility decommissioning effort.

Excluding the interior of the Weir Discharge pipe, which was removed all the way to the concrete headwall', all soil and sediment samples were below the applicable DCGLw.

Therefore, this collection of data demonstrates that these survey units meet the radiological criteria for unrestricted use specified in 10 CFR 20.1402 (Reference 9.3).

Based on the results of these sampling efforts, GPU Nuclear, Inc. concludes that the MA3 and MA4 site areas and the subsurface soil bed below the Weir Discharge pipe meets the NRC requirements for release to unrestricted use.

The Weir Discharge pipe was removed in its entirety all the way to the river bed.

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Site Areas MA3 and MA4 - Weir Discharge Area

1.0 Purpose and Scope

This report presents the results and conclusions of survey and sampling work performed on the following area/item:

• Weir Discharge Area (MA3) - A Class 2 area at the mouth of the Weir Discharge line which empties to the Raystown Branch of the Juniata River.

• Weir Discharge Area (MA4) - A Class 3 area that is essentially the buffer zone around the mouth of the Weir Discharge line opening.

- Approximately one hundred ten (110) meters of the Class 3 subsurface soil bed that supported the Weir Discharge pipe from SNEC site grid number BF-127 through BQ-127. It ends at the concrete headwall on the bank of the Raystown Branch of the Juniata River.

This survey effort meets the intent of FSS information required by 10 CFR 50.82(a)(1 1)

(Reference 9.4) and SNEC's License Termination Plan (LTP) and demonstrates that this area meets the radiological criteria for unrestricted use specified in 10 CFR 20.1402.

2.0 Survey Area Description The Weir Discharge line originated in the 1.1 acre SNEC facility yard area (OL1 area) at the Weir. The Weir Discharge line was a ten (10) inch corrugated galvanized steel pipe that extended to the river discharge point about one hundred seventy (170) meters north of the SNEC Containment Vessel (CV). The pipe passed below site areas OL1, 0L2, OL10 and 0L8 on its way to the river before reaching the concrete headwall at the rivers edge. The pipe was buried about one (1) to two and one half (2.5) meters below the surface as it traversed about one hundred fifty (150) meters to the river area, and was excavated in its entirety by September 2001. The MA3 area is a small M 2 area that envelops the former Weir Discharge pipe outlet area. This location is shown on the SNEC site grid map at grid location BP-127 (Reference 9.5). The MA3 Class 2 area includes the mouth of the Weir line, and several square meters of area that surround the opening. The pipe outlet extended three to five feet beyond the concrete headwall and was embedded in the river bottom (see Figure 3 sketch). The MA4 area is an additional -200-M 2 area that is essentially a Class 3 buffer zone around the MA3 discharge point. MA4 is mostly river area.

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Site Areas MA3 and MA4 - Weir Discharge Area SNEC Weir Pipe Discharge Point Juniata River

/River Bottom , ~

Figure 3, Is a sketch of the Weir discharge pipe exit point 3.0 Operating History 3.1 Weir Line Use One of the Radioactive Waste Disposal Facility (RWDF) evaporator water release pathways was via the sewage treatment system in the OL2 area (the CV Yard area), and then on to the river north of the SNEC CV. This pathway involved the SNEC facility Weir and Weir Discharge piping system. Inaddition, the decontamination shower water from the Control and Auxiliary (C&A) building was directed to this pathway after analysis demonstrated that radioactivity levels were within limits. A respondent to the questionnaire developed for the SNEC Historical Site Assessment (Reference 9.6) indicated that the Weir sediment was contaminated during SNEC facility operation. Another respondent indicated that river sediment in the vicinity of the Weir Discharge pipe showed elevated Cs-137 concentrations.

The Weir Discharge area was sampled quarterly and the results were reported annually as location A1-4 in the Radiological Environmental Monitoring Program (REMP) report (Reference 9.7). Scoping and characterization activities at and in the Weir Discharge line also identified Cs-137 concentrations in sediment samples, but no significant levels of other SNEC related radionuclides have been identified.

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Site Areas MA3 and MA4 - Weir Discharge Area 3.2 Weir Line Remediation Status Remediation of the Weir and associated piping occurred in stages over a number of years, starting in the OLI and OL2 site areas. In the final stage, remaining sections of Weir piping extending from just outside the SNEC facility fence line (in grid BF-127) was removed. As part of the Discharge line removal effort a short three (3)to five (5)foot section of pipe that extended beyond the concrete headwall into the river was also removed. All piping systems and yard drains in the Containment Vessel (CV) Yard area were removed previously. Only the concrete headwall exists at the present time.

The Weir piping meets the definition of a Class 1-survey unit (Reference 9.1, Table 5-5) since sample analysis results from inside the pipe have shown contamination levels well above the applicable DCGLw. In addition, the pipe and Weir system have been remediated which is indicative of a Class I survey area.

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 built 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.

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Site Areas MA3 and MA4 - Weir Discharge Area 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.

4.0 Site Release Criteria The site release criteria as applied to the Weir line and surrounding 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 Weir Line Area Specific DCGLw Values The Weir Discharge line was connected to the Weir and other yard drainage systems that interconnected within the OLI and OL2 site areas, and therefore the radionuclide content for the Weir line should be well represented by a radionuclide mix from this area. Over 6

Site Areas MA3 and MA4 - Weir Discharge Area time, several samples form the Weir line internals were sent to an off-site laboratory for a more complete analysis (see Table 1).

Table 1, Weir Discharge Line Samples Decay Daft l PCUg l Je 30. 2005 SNEC Sample No LAB No. LocatloniDecaptleon Co40 CS-137 AnalystsDats SX8819601745D ERL 88237 Sedniernt-WeirPipe (-IoutTowart Riverfrom Weir), MA3& 4 ..-. 29.18

, May 7,1996 SX881960173SD ERL 88236 Sodnerdrn Weir Pipe (-77 otutTowarrl River from Weir). MA3 &4 0.15 3728 may 7. 1996 SXIOSL99012 ERL 110643. 111150 WeirDiseloRlter-30 Infrom Excvation Beyond FenceMA3 & 4 3.05 Juy 19.1999 SX12SD99285 ERL 111231 Sample 2SWeirDischarge Oufall, MA3 &4 0.33 December3, 1999 SX12SD99277 ERL 111223 Sample #21 Wer Discharge OutfIa.MA3 &4I, 4 0.36 December 3,1999 SX11S001937 BWXT, 0106103-C WeirrUna 135. Above Rlvr Outlet MA3 & 4 '. 56.05 May 24.2001 SXSD1,472 Weir Site 0 1. BP-127, Sediments MeA3&4002edbrt,20 WTt~~

SXS04717 Teledyne: L23493-3 A1-4, Weir Discharge, MA3 & 4 *! 0.15 April 15. 2004 NOTE: Samples 174, 173 and 1937 were taken from Inside the Weir pipe.

Only Co-60 and Cs-137 were positively identified in these Weir Discharge line samples.

Use of the OL1/OL2 area radionuclide listing from the CV Yard is somewhat more restrictive, but just as appropriate since this area is the origin of the effluent that entered the Weir. The applicable DCGLw values for the Weir line are tabulated in Appendix A-4 and are presented in Table 2.

Table 2, Weir Line - DCGLw Values l:.GrsActivitY DCGLw (dprnhlO cm2) ,VolumetiC DCGLN (pCIg o 1-37 44,306 (33,229 A.L.) 5.75 (4.31 A.L.)

NOTE: A.L. is the site Administrative Limit or 75% of the effective DCGLw for the area.

5.0 Survey DesignIDQO Process The Weir Discharge line post-remediation survey work was performed in June and September of 2001, with guidance provided by survey request SR-0020 and SR-0028.

These SR's required a number of samples from the soil bed below the Weir line after pipe removal between site grid markers BF-127 and BQ-127 as shown on Figure 4.

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Site Areas MA3 and MA4 - Weir Discharge Area

-o MA3 Weir Discharge Pipe Post-Remedletlon Soil Survey Area (SR-0028)

'O0 0 0 0 0 a0 0 .

he~ c ohOoOo 0eio o o 0 0 0 0

-40 m 7 m RAST0OMJ BRANCH JUNIATA RIVER Weir Discharge Pipe Post-Remedlatlon Soil Survey Area (SR-0020) 2 3 A id a a I 28 z I I 2I  !

Figure 4, is a diagram of Weir Discharge line area showing the location of post remediation survey work.

An open window 2" by 2" Nal detector was used to scan the soil bed below the pipe. The bottom of the open trench area was scanned at 100% coverage. The open trench was approximately two (2) meters wide and one hundred ten (110) meters long (considering both SR-0020 and SR-0028). Then the total area scanned was at least two hundred twenty (220) square meters of subsurface soil.

The MA3/MA4 area has been monitored on a routine basis over several years as part of the SNEC facilities Radiological Environmental Monitoring Program (REMP). The Weir location was designated indicator station A1-4 in the REMP reports. The results from these monitoring efforts for the years 1999 through 2004 are provided in Table 5.

Sampling at or near the Weir Discharge point was also performed as a separate function by ENERCON Services, Inc. as part of the GPU Nuclear sediment sampling program for the Raystown Branch of the Juniata River (Reference 9.8). This work was previously provided to the US NRC on January 11, 2002 (Reference 9.9), and reported in Reference 9.1. The results of this work are summarized in Table 4. The ENERCON sampling effort proved that the river area adjacent to the SNEC site property is largely non-impacted (Reference 9.1), with the exception of the Discharge Tunnel and Weir Discharge line areas (MA2, MA3 and MA4). ENERCON services performed the river sampling program in accordance with applicable site procedures and guides developed specifically by ENERCON for this type of study (see Reference 9.8). All samples were collected under SNEC facility survey request SR-0034 and applicable site procedures. The sampling plan was developed for GPU in accordance with applicable sections of the SNEC License Termination Plan (LTP). All SR's are reviewed and approved by the SNEC RSO (or his 8

Site Areas MA3 and MA4 - Weir Discharge Area representative) before implementation. Data Quality Objectives (DQO's) for the Weir area are presented in the following table.

Table 3, DQO/Design Parameters/Results

E/ -1 SNEC Survey Request No. SR-0034 & REMP SR-0034 SR-0020 & SR-0028 Non classified subsurface area below MA4, OL1. 0L2, Survey Area Classification 2 3 0L8 & OLIO

-220 (assumes a -2 meter

-200 in river area, <10 for wide trench area by -110 Total Area Size (i 2) -25 headwall meters long)

Under water except for Scanning Goal (m2) N/A - under water headwall which was 100% -220 (100%)

Applicable Statistical Test N/A (non-random) NMA (non-random) N/A (non-random)

Effective Soil DCGLw (Cs-137 pCVg) 4.31 (A.L.) 4.31 (A.L) 4.31 (A.L.)

Surface Gross Activity DCGLw (dpm/100 cm2) 33,229 (A.L) 33,229 (A.L.) 33,229 (A.L)

Applicable Number of Soil or Sediment Samples Taken in 4 by ENERCON & 1Qtr 8 by ENERCON Accessible Areas' for REMP downstream of Weir out-fall 40 (SR-0020 & SR-0028)

Estimated Surface Scan MDC . _ __ -13,407 for concrete (dpm/100 cm2) N/A - under water N/A - under water headwall Estimated Scan MDC for Sediment (Cs-137 pCVg) N/A - under water N/A - under water -6.9 Scan Speed for Soil-Uke Materials (cm/sec) NMA - under water N/A - under water 50 Nal Alarm point During Scanning (FSS) N/A - under water N/A - under water > 13,000 gcpm Number of Alarm Points During NMA - under water, none for At least 3 biased samples Scanning Process N/A headwall area taken @ > 13,000 gcpm Typical Nal Background Level (cpm) N/A N/A -13,000 Typical GM Background Level (cpm) N/A N/A -40 Eberline ASP& SPA-3, 2 by 2' Nal probe for soil, HP-210 GM or equivalent Scan Survey Instrument N/A - under water N/A - under water section for pipe sections Instrument Conversion Efficiency (Nal

- cpm/mR/h) N/A N/A - 900,000 Instrument Conversion Efficiency (GM

_rnm/Hnm 5.1 Description of Survey Unit Figure 2 shows that the MA3/MA4 area as approximately 225 square meters that includes river and river bank area (concrete headwall), but is largely river bottom that is underwater except in very dry years. About forty (40) square meters of subsurface soil 9

Site Areas MA3 and MA4 - Weir Discharge Area area was also surveyed during the final remediation stage of the Weir Discharge line.

Native soil, river silt, cinders, and coal ash make up the vast majority of material types in the Weir line area.

5.2 Survey Design for the MA31MA4 Area One of the sampling efforts in the MA3/MA4 area was provided to the US NRC (Reference 9.9). From this report, a total of four (4) samples were selected from the Weir Discharge line exit point in the MA3 river area (see Reference 9.8). An additional eight (8) samples were collected within or near the MA4 area downstream from the Weir Discharge point. The results of this sampling effort are provided in Table 4. Samples were either sediment that was scooped from the river bottom, or was materials vacuumed from rocky surfaces from the river area at select locations.

The A1-4 REMP sampling area is located directly in front of the concrete bulkhead where the Weir pipe was secured at the rivers edge. These results were routinely collected on a quarterly basis every year the SNEC Decbrmrmissioning-effort was underway. These results are reported in Table 5.

During the final phase remediation effort for the final forty (40) meters of Weir line, samples and Nal scanning was performed in the vicinity of the Weir pipe as it was removed from the soil bed. In addition, a Geiger Mueller (GM) pancake probe was used to surface scan pipe sections and the concrete bulkhead at the rivers edge. The location of sample points were identified on a survey map of the Weir line area. The soil scan MDC was determined to be 6.9 pClg for Cs-137 (see Appendix A-5). The scan MDC for the GM probe was determined to be 8,024 dpml1 00 cm2CS 137 I0.5985 (Cs-1 37 fraction 2

in mix) = gross activity scan MDC 13.407 dpm/100 cm (see Appendix A-4 and A-6).

6.0 Sampling and Survey Results 6.1 Summary of Survey Results from ENERCON River Study From Reference 9.8, six (6) locations were identified for sampling in the vicinity of the Weir Discharge exit pipe. From these six locations, four (4) samples were taken at the base of the concrete headwall (MA3) (locations 1 and 2), and eight (8) additional samples were taken downstream from the Weir line in the MA4 area or beyond (locations 3 through 6). All samples were collected either by scooping up material or by vacuuming up river fines. Samples could not be located randomly and were instead 10

Site Areas MA3 and MA4 - Weir Discharge Area collected using a biased (as available) sampling approach. A complete discussion of the results of this study is provided in Reference 9.8. Actual sample results for this area are provided in Table 4.

Table 4, ENERCON Weir Area Sample Results (MA3IMA4 - SR-0034)

EbNERoN SlterDr SNEC Sample ID Sample Date: simplrgMOthf. Cs137 ( 7~gf-.6-o (pcugf Weir I (MA3)SXSDI472 10110101 Scoop 2.55 < 0.08 Weir 1 (MA3) SXSD1473 10/10/01 Scoop 1.07 <0.06 Weir 2 (MA4) SXSD1474 10110/01 Scoop <0.07 < 0.07 Weir 2 (MA4) SXSD1475 10/10101 Scoop 0.05 < 0.055 Weir 3 (MA4) SXSD1476 10110/01 Scoop < 0.039 <0.05 Weir 3 (MA4) SXSD1477 10/10/01 Scoop <0.06 < 0.05 Weir 4 (MA4) SXSDI478 10110101 Scoop <0.06 < 0.05 Weir 4 (MA4) SXSD1479 10/10/01 Scoop < 0.05 < 0.04 Weir 5 (MA4) SXSD1480 10110/01 Suction 0.15 < 0.04 Weir 5 (MA4) SXSD1481 10/10/01 Suction 0.08 < 0.04 Weir 6 (MA4) SXSD1545 10/18/01 Suction 1.8 < 0.05 Weir 6(MA4) SXSD1546 10/18/01 Suction 1.2 < 0.07 2

Data from ENERCON report (Reference 9.8). Note that Weir 3 through 6 may be out of the MA4 200 m area.

All results from the ENERCON study for the Weir area are below the applicable DCGLw for Cs-137 (as the surrogate).

6.2 REMP Sample Results 1999 to 2004 The Al -4 sample location is at the base of the concrete headwall of the Weir pipe river outlet. Samples from this area are reported annually via the Radiological Environmental Monitoring Program (REMP) process. The SNEC facility maintains a fully approved procedure (E900-ADM-4500.22) for performing this type of environmental monitoring (Reference 9.10). The results of REMP sampling at the Weir area are provide in Table 5.

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Site Areas MA3 and MA4 - Weir Discharge Area Table 5, REMP Data from Location AI-4 (Weir Out-fall)

SNEC REMP Data @ AI4 Location ii 1999 Quarter I Quarter 2 Quarter3 Quarter4 Cs-137 N/S 0.087 0.094 0.13 Co-60 NIS < 0.02 < 0.02 < 0.01d 2000 Quarter I Quarter2 Quarter3 Quarter4 Cs-137 0.034 0.03 0.25 0.43 Co-60 < 0.03 < 0.015 <0.04 <0.03 2001 Quarter I Quarter 2 Quarter 3 Quarter 4 Cs-137 0.216 < 0.02 0.5 0.17 Co-60 < 0.013 <0.02 <0.06 <0.065 2002 Quarter I Quarter2 Quarter3 Quarter4 Cs-137 0.23 0.33 0.09 0.08 Co-60 ' 0.06

< < 0.06 < 0.05 < 0.06 2003 QuarterI Quarter2 Quarter3 Quarter4 Cs-137 0.04 < 0.09 0.08 N/S l Co-60 < 0.05 < 0.1 < 0.04 N/S 2004 Quarter I Quarter2 Quarter 3 Quarter 4 Cs-137 N/S 0.17 <0.04 ' <0.11 Co-60 N/S < 0.04 4<0.04 <0.09 NIS a No sample taken.

6.3 Remediation Support Surveys (SR-0020 and SR-0028)

As previously discussed, the one hundred fifty (150) meter long Weir line was remediated over time, with the last forty (40) meters extricated in about September of 2001. Since this work was in support of the remediation effort at the SNEC facility, no survey design was developed for this work. However, a survey request was written that contained some definable Data Quality Objectives (DQO's). DQO values are summarized in Table 3, along with calculated scan MDC values for the 2" by 2" Nal open window detector, and the Geiger Mueller (pancake) probe. The DCGLw calculation logic for the Weir line is provided as Appendix A-6. Scan MDC calculations have been included with this report as Appendix A-5 and A-6. Other DQO values are provided in Table 3 (as applicable).

Samples were also taken from below the Weir Discharge line in the soil bed within the last one hundred ten (110) meters of the line to the rivers edge (see Appendix A-I and A-2). These sample results are provided in Table 6.

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Site Areas MA3 and MA4 - Weir Discharge Area Post remediation survey and sampling results indicate that no significant contamination of the surrounding soils had occurred. No sample result from the soil bed indicated the presence of contaminated soil above the applicable DCGLw. The results of this survey effort are reported in Appendix A-1, and in Table 6.

Table 6, Soil Bed Sample Results Below Weir Discharge Line (SR-0020, June-2001)

Grid No. SNEC Sample ID  :  :"

Sampilng Location Cs-I37 (pCUg) Co-60 (pCUg)

BM-127 SXSLI013 0' Removal Start Point 0.19 < 0.05 BL-127 SXSL1014 12' South of Start Point < 0.05 < 0.05 BL-127 SXSLI015 24' South of Start Point < 0.07 < 0.07 BK-127 SXSLI016 36' South of Start Point < 0.06 < 0.06 BK-127 SXSLI017 48' South of Start Point < 0.06 < 0.06 BK-127 SXSL1018 60' South of Start Point < 0.07 < 0.07 BJ-127 SXSL1I019 72' South of Start Point < 0.06 < 0.06 BJ-127 SXSL1020 84' South of Start Point < 0.05 < 0.04 BK-127 SXSL1021 62' South of Start Point < 0.07 < 0.07 BJ-1 27 SXSL1022 80' South of Start Point < 0.07 < 0.08 BJ-127 SXSL1037 96' South of Start Point < 0.07 < 0.08 BI-127 SXSLI038 108' South of Start Point < 0.06 < 0.06 BI-120 SXSL1039 120' South of Start Point 0.05 < 0.06 BH-127 SXSL1040 132' South of Start Point < 0.07 < 0.06 BH-127 SXSLIO41 144' South of Start Point 0.08 < 0.07 BH-127 SXSLI049 156' South of Start Point 0.98 < 0.06 BG-127 SXSL1050 168' South of Start Point 0.06 < 0.05 BG-127 SXSL1051 180' South of Start Point < 0.05 < 0.05 BF-127 SXSLI052 192' South of Start Point < 0.07 < 0.06 BG-127 SXSL1053 190' oc South of Start Point < 0.07 < 0.07 BF-127 SXSLI080 204' South of Start Point 0.02 < 0.05 BF-127 SXSLI081 216' South of Start Point < 0.05 < 0.05 BE-127 SXSLI082 228' South of Start Point < 0.07 < 0.06 BE-127 SXSL1083 240' South of Start Point 0.19 < 0.08 BF-127 SXSLI084 206' South of Start Point < 0.06 < 0.07 Note: Soil around the Weir Discharge line should be considered a Class 3 soil volume.

Soil bed sample results were all below the applicable DCGLw. The highest concentration found inside the Weir pipe remnants in this area was 63.2 pCi/g Cs-137 in grid BH-127.

Additional pipe intemal sample results are provided in Appendix A-1.

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Site Areas MA3 and MA4 - Weir Discharge Area Table 7, Soil Bed Sample Results Below Weir Discharge Line (SR-0028, Sep-2001)

Grid No. SNEC Sample ID. Samping Locaton 'Cs-I37 (pC11g) Co60 (pClIg)

BO-127 SXSL1406 North End (Headwall) 3.9 < 0.06 BP-127 SXSL1408 10' South. of North End 0.78 < 0.06 BP-127 SXSLI410 20' South. of North End < 0.08 < 0.07 BP-127 SXSLI412 30' South. of North End 0.11 < 0.08 BO-127 SXSLI414 40' South. of North End 0.06 < 0.05 BO-127 SXSL1415 45' South. of North End < 0.07 < 0.07 BO-127 SXSLI417 50' South. of North End < 0.06 < 0.06 BO-127 SXSL1419 60' South. of North End < 0.06 < 0.07 BN-127 SXSLI421 70' South. of North End < 0.07 < 0.06 BN-127 SXSL1422 75' South. of North End < 0.06 c 0.07 BN-127 SXSL1424 80' South. of North End < 0.05 < 0.05 BN-127 SXSL1426 90' South. of North End 0.06 < 0.06 BM-127 SXSL1429 100' South. of North End < 0.05 < 0.04 BM-127 SXSL1431 110' South. of North End < 0.08 < 0.07 BM-127 SXSL1433 120' South. of North End 0.05 < 0.07 Note: Sample SXSL1406 was taken below the open end of the pipe in the river area.

Soil bed sample results were all below the applicable DCGLw. The highest concentration found inside the Weir pipe remnants in this area was 4.9 pCVg Cs-137 in grid BP-127.

Additional pipe internal sample results are provided in Appendix A-2.

Scan results2 of the soil bed below the Weir pipe along the remediated sections did not detect any count rate above 15,000 cpm, while background was determined to be approximately 13,000 cpm. A corresponding sample (SXSL1 084) was taken in about the same location as the elevated count rate, and did not yield an above background Cs-137 concentration. The scan MDC for this measurement activity is estimated to be 6.9 pCi/g Cs-137. Supporting documentation for the soil scan MDC calculation is found in Appendix A-5.

Scan results of the concrete headwall area using a GM type detector did not show count rates greater than 100 net counts per minute (background was determined to be -40 cpm). The scan MDC for this measurement activity is estimated to be 8,024 dpm/100 cm2 for Cs-137, or 8,024 dpm/100 cm2 /0.5985 (see Appendix A-4) = gross activity scan MDC of 13.407 dpm/cm2 . Supporting documentation for scan MDC calculations are found in Appendix A-5 and A-6. All GM scan results of the concrete headwall are below the applicable DCGLw. All previous remediation support survey work is shown in Appendix A-1 and A-2.

2 Using a 2 by 2' Nal detector equipped with an open window 14

Site Areas MA3 and MA4 - Weir Discharge Area 7.0 Data Assessment 7.1 Assessment Criteria This 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.

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 request.

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.

15

Site Areas MA3 and MA4 - Weir Discharge Area 7.2 Survey Variations (Design, Survey Request, LTP) 7.2.1 The remediation support survey work (SR-0020 and SR-0028) was performed in accordance with an approved survey request, but lacked a reviewed survey design associated with a final status survey. Samples collected under these survey requests were biased in that they were taken from the soil bed below the Weir pipe in the area where leaks would be expected. This is a reasonable subsurface sampling approach. In addition, sampling and analysis when performed under an approved survey request is a fully qualified activity that adheres to applicable site procedures such as Reference 9.2.

7.2.2 The entire Weir line remediation effort was not covered by a similar remediation support survey process, and therefore these sections of the Weir line must be considered as representative of the entire Weir pipe length. This is not an unreasonable assumption, and while the Weir Discharge line is a Class 1 survey object, the soil volume around the pipe is not.

7.2.3 Samples taken form the river in the MA3/MA4 areas were not located using a random selection methodology, since that would have been less effective in determining if elevated Cs-137 concentrations were present in the area. Except for the immediate Weir Discharge line opening, additional samples were taken downstream form the river in deposits of sediment, and at locations where changes in the rivers direction would have deposited sediment. These natural deposition points retain higher probabilities of maintaining positive sample results than solid rock bottom surfaces which are constantly swept clean by aggressive water motion.

7.2.4 Scanning results of soils and the Weir out-let concrete headwall do not have a 5% QC re-scan documented in the survey record in accordance with the SNEC LTP.

7.2.5 No static GM measurements were taken on the concrete headwall. However, remediation support scan survey work was performed over the entire exposed headwall surface. The results yielded < 100 net counts per minute in all accessible areas. The estimated scan MDC is provided in Appendix A-6.

7.2.6 A sample of concrete from the top of the headwall structure yielded a concentration of 4.7 pCi/g for Cs-137. This relatively small location is slightly above the applicable volumetric administrative limit DCGLw of 4.3 pCilg. However, this value is well below the maximum 5.75 pCilg Cs-137 DCGLw listed in Table 2. Another sample of 16

Site Areas MA3 and MA4 - Weir Discharge Area the same concrete structure yielded a much lower concentration. It is not clear why one small location on the concrete headwall was at this elevated concentration.

7.3 Quality Control Measurements Quality Control (QC) samples are reported for each of the applicable Appendices (A-1, A-2 and A-3). All QC samples were taken in accordance with the requirements of Reference 9.1, and applicable site procedures which require that at least 5% of all samples be re-taken. However, some QC samples may have been collected at errant locations. Additionally, repeat scan surveys should have been performed in accordance Reference 9.2, but the documentation does not provide this information. Additional QC related issues are provided in the Appendix A-1 and A-2.

7.4 Assessment Summary Statistical testing of the data does not need to be performed for this survey work since the data clearly show that these survey units meets the site release criteria. This survey unit clearly meets the criterion because of the following:

1. 0 All measurements in the survey units are less than or equal to the DCGLW, or

2. E 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.

8.0 Final Status Survey Conclusions In general, the Weir Discharge line area (MA3IMA4) survey and sampling work was performed in accordance with Revision 3 of the SNEC LTP and site implementing procedures. Survey and sampling data were reviewed to determine if the data meet 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 (MA3/MA4) area is less than the assigned DCGLw.

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

17

Site Areas MA3 and MA4 - Weir Discharge Area

3. No remediation of the MA3/MA4 areas were 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 Weir Line Area (MA3/MA4) as described in this report is suitable for unrestricted release.

9.0 References 9.1 SNEC License Termination Plan 9.2 SNEC Procedure E900-IMP-4520.04, "Survey Methodology to Support SNEC License Termination" 9.3 Code of Federal Regulations, 10 CFR 20.1402.

9.4 Code of Federal Regulations, 10 CFR 50.82(a)(11).

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 Facility Radiological Environmental Monitoring Report, 1999 to 2004.

9.8 Final Report, Sediment Sampling Raystown Branch of the Juniata River for GPU Nuclear, Inc., Prepared By: ENERCON Services, Inc., November 1,2001.

9.9 GPU Nuclear Correspondence to U.S. NRC, E910-02-002, January 11, 2002, "Phase 2 and 3 Characterization Data".

9.10 SNEC Procedure E900-ADM-4500.22, Environmental Monitoring".

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

9.12 SNEC Procedure E900-ADM-4500.60 "Final Status Survey Report".

18

APPENDIX A-1 SR-0020

SURVEY REQUEST CONTINUATION SHEET SR NUMBER l 0020 l AREA/LOCATION I WEIR Piping SPECIFIC SAMPLING/SURVEY INSTRUCTIONS OR COMMENTS RESULTS

SUMMARY

FOR SR-0020 SR-0020 was issued to obtain radiological survey and sampling data to ensure adequate and correct classification of soil and materials surrounding the Weir piping. The survey unit covered under this SR is WEIR Piping (grids are listed in the SR). The SR required the following radiological measurements.

• Surface scan measurements using a Nal detector (SPA-3 or equivalent). Survey techniques will be IAW the SR.

• A minimum of 21 non-biased soil samples were required to be taken for analysis. A systematic approach to taking the samples was required to be used to ensure entire length of the trench is sampled.

• Surface Soil Samples: Using appropriate tools obtain samples as directed in the SR. Obtain a sample to a depth of 15 centimeters (6 in.)

• QC Repeat Measurements: A minimum of 5% of all surface scan measurements and sampling were required to be re-performed using identical methodology. Surface Soil sampling was performed by taking a second sample from the same drill hole or sample point.

• QC Repeat Analysis (Replicate):

• Additional sampling/surveys were not performed.

1. Summary of Results A. Surface Scan Measurements (Nal Detector)

A 100% surface scan was required of all accessible areas of the Weir pipe trench, IAW the SR. A total of 100% of this area was surveyed.

Results: The calculated ABCR for the trench was 13,000 cpm. The maximum reading seen in the trench was 15,000 cpm.

B. Surface Static Measurements No static measurements were obtained.

Results: Not Applicable.

Page l of3 7/20/2005

SURVEY REQUEST CONTINUATION SHEET SR NUNIIBER l 0020 AREAILOCATION WEIR Piping SPECIFIC SAMPLING/SURVEY INSTRUCTIONS OR COMMENTS C. Surface Soil and Sediment Sampling Thirty (30) Surface Soil samples were obtained. Five (5) Sediment samples were taken. These samples were randomly taken and spread over the length of the weir pipe trench except for 2 samples that were taken at locations of increased activity.

Results: Eighteen (18) Surface Soil and Sediment samples taken for this SR were less than MDA. MDA activity range is from 0.05 pCi/g to 0.07 pCi/g (for the surrogate isotope, Cs-137). For the seventeen (17) samples, not including QC samples, that did contain Cs-137 activity greater than the sample MDA, activities ranged from 0.02 pCi/g to 63.2 pCi/g. Co-60 was identified in the highest activity Cs-137 sample at 0.41 pCi/g and in three (3) other samples at lower concentrations..

2. Quality Control (QC) Measurements and Comparisons Repeat Scan measurements and Soil/Sediment samples were required to be performed to meet the applicable acceptance criteria established in Section 4.6 of E900-IMP-4520.04. QC scan measurements were repeated for an unknown percentage of the area scanned. Surface Soil and Sediment sample QC measurements were repeated for 0.00% of Surface Soil and Sediment samples.

(See Section #4)

3. Quality Control Sample Recounts

• Repeat QC replicate recount -Monthly, approximately five per cent (5%) of all samples counted on the gamma spectroscopy system or Tri-Carb system, lAW SNEC Procedure E900-QAP-4220.02, are required to be counted for replicate analysis. (e.g. FSS soil samples). (See Section #4)

4. Exceptions and Discrepancies

• Cs-134 was required by the SR to meet an MDA of 0.15 pCi/g. Cs-134 is not on the data base printout.

Unable to determine if this SR requirement was met.

• Field Sample Collection Sheets show that there were four (4)QC Samples taken for the Soil/Sediment The problem is that none of these uQC" samples was taken in the same location as a sample for which it was to be the QC. These can not be counted as QC samples as the closest you get to another sample point is 2 feet, unless another type of sample is taken; i.e. SL and SD at same location, both labeled QC

• Unable to tell by the survey form how much of the trench was QC surveyed, if any at all. There is no second person and/or no second instrument number on the survey form in the package.

• There was no replicate/QC done for the smears/dose rates on the weir piping boxes.

Page 2 of 3 7/20/2005

SURVEY REQUEST CONTINUATION SHEET SR NUMBER l 0020 l AREA/LOCATION I WEIR Piping SPECIFIC SAMPLING/SURVEY INSTRUCTIONS OR COMMENTS

5. Special Note(s)

• As far as the need for replicates goes, the procedure refers you to E900-QAP-4220.02 - SNEC Count Room Quality Assurance Program Print/Signature Date Page 3 of 3 7/2012005

APPENDIX A-2 SR-0028

SURVEY REQUEST CONTINUATION SHEET SR NUMBER 0028 lAREA/LOCATION I Weir Piping SPECIFIC SAMPLING/SURVEY INSTRUCTIONS OR COMMENTS RESULTS

SUMMARY

FOR SR-0028 The purpose of SR-0028 is to survey and sample below grade materials surrounding the remaining section of Weir piping on U.S. Army Corp of Engineers (Raystown Lake) property. This SR also includes surveying and sampling of the Weir concrete headwall at the bank of the Juniata river.

• Surface scan measurements were performed using an E-140N wI HP-210/260 or equivalent, an ASP-1 and a Micro Rem meter. Survey techniques will be lAW the SR and E900-IMP-4520.04 Rev 1 Survey Methodology.

• Obtain at least one (1) non-biased soil sample for approximately every 10 feet of trench length. Samples shall be representative of material that surrounded the Weir piping.

• At least two (2) non-biased concrete samples of the Weir headwall and additional samples of areas demonstrating elevated activity. Sample volume should be at least 100 cc.

• Surface Soil Samples are to be obtained at a depth of less than 15 cm (6 inches).

• Obtain representative non-biased soil samples throughout the remaining section of the Weir piping.

• Obtain additional samples of areas demonstrating elevated activity as applicable.

• QC measurements will be performed by randomly re-sampling and re-surveying at least 5% of all sampling and survey points using identical methodology contained in this SR.

• Replicate sample analysis will be performed in accordance with Reference 6.13.

1. Summary of Results A. Surface Scan Measurements A 100% surface scan was required of all accessible areas of the Weir piping, the headwall and the trench (where permissible). See 4.1.

Results: Direct frisk readings on the Weir piping and headwall showed <100 ncpm (40cpm bkg). No readings with the ASP-I or the Micro Rem exceeded action levels.

B. Surface Static Measurements No static measurements were obtained.

Results: Not Applicable.

Page 1of 3 7/13/2005

SURVEY REQUEST CONTINUATION SHEET SR NUMBER l 0028 _ AREA/LOCATION I Weir Pi in SPECIFIC SAMPLING/SURVEY INSTRUCTIONS OR COMMENTS C. Surface Soil Samples (SSS)

Thirty eight (38) SSS plus one (1)QC sample were taken. (See 4.2). These samples were spaced based on the SR requirement to sample approximately every 10' of the trench.

Results: Thirteen (13) SSS taken for this SR were less than MDA. MDA activity range is from <0.05 pCi/gm to <0.08 pCi/gm for the surrogate isotope Cs-137. For the twenty five (25) samples (not including the QC sample) that did contain Cs-137 activity greater than MDA activities ranged from 0.046 pCi/gm to 4.90 pCi/gm. No other licensed isotopes were identified for this SR.

2. Quality Control (QC) Measurements and Comparisons

• Repeat Scan measurements and SSS samples

• For QC scan measurements see 4.3.

• One (1) SSS sample was taken for 2.6% of SSS samples. See 4.2

3. Quality Control Sample Recounts

• Repeat QC replicate recount- See 4.4

4. Exceptions and Discrepancies

• 4.1 E900-IMP-4520.04 Rev 1 4.3.2 states that all survey instruments will have an established ABCR (4.3.2-3) prior to scanning. No written documentation could be found to establish that this step had been performed for this SR.

• 4.2 Although four (4)QC samples were listed on the field collection data sheet only one (1)qualified as a QC sample. The other three (3)QC samples were obtained from unique locations and therefore must be considered a sample and not a QC.

• 4.3 E900-IMP-4520.04 Rev 1 states that at least 5% of all scanned areas shall have a repeat QC scan. No written documentation could be found to establish that this step had been performed for this SR.

• 4.4 E900-IMP-4520.04 Rev I requires that at least 5% of all samples taken have a replicate count performed. No written documentation could be found to establish that step had been performed for this SR.

Page 2 of 3 7/13/2005

SURVEY REQUEST CONTINUATION SHEET SR NUMBER 0028 l AREA/LOCATION Weir Piping SPECIFIC SAMPLING/SURVEY INSTRUCTIONS OR COMMENTS S. Special Note(s)

NIA N/A Bill Horton 07-13-05 Print/Signature Date Page 3 of 3 7/13/2005

APPENDIX A-3 SR-0034

'7'1ri -,'n re. ! I Q! 1L:Ul ldiWrvl)A1-SURVEY REQUEST FORM

-SR NUMBER SR-0034 DATE OF REQUEST 10/04/01 TYPE OF SR El FSS 0 CHARACTERIZATION 0 OTHER:

AREA/LOCATION Raystown Branch of the Juniata River - Sediment Sampling

- The purpose of this SR is to obtain sediment samples from the Juniata River bottom in PURPOSE accordance with the attached ENERCON Services work procedure. See attached map for SUREYsampling locations.

-UVYUI#N/A GRID# N/A

• SURVEYUNIT# N/A GRID# N/A SURVEY UNIT# N/A GRID# N/A SAMPLE TYPE El SURFACE SOIL SAMPLE:

. SUB-SURFACE SOIL SAMPLE:

El SEDIMENT SAMPLE: See specific sampling instructions on page 2 of this SR.

a CORE SAMPLE:

o WATER SAMPLE:

. E-OTHER:

• .:., :;__ -- SURVEY TYPE 0EA INST. SCAN RATE&

SURFACE TP DETECTOR

-',SCAN oo GAMMA ALPHA PROBE TYPE DISTANCE FROM SURFACE FACE BETA TA INST.

TYPE. SCAN RATE &

DETECTOR SCAN 3 GAMMA PROBDISTANCE

_ ALPHA OTYPE FROM SURFACE UINST.

STATIC a BETA TYPE COUNT TIME &

DETECTOR MEASURE- E GAMMA DISTANCE MEASRE PROBE

_ . ALPHA TYPE FROM SURFACE

- INST. COUNT TIME &

E M

'STATIC 0 EASURE- GAMMA

~~ MENT BETA

~

TYPE ________

PROBEDITNE DETECTOR Di TANCE.

• ALPHA PEFROM SURFACE

.TYP I . :OTHER L.,SURVEY, I TYPES OR ICOMMENTS Page 1 of 3

SRNUMBER SR-0034 DATE OF REQUEST 1010401 SPECIFIC SAMPLING I SURVEY INSTRUCTIONS General Requirements

1. All personnel working under this Survey Request (SR) (including support personnel) shall comply with the ENERCON Services Health and Safety Plan titled 'Sediment Sampling Raystown Branch of the Juniata River".

2. If possible, obtain photographs of the sampling areas. Photographs should be attached to this SR as part of the record data.

Sediment Samples

1. Obtain samples in accordance with the applicable procedural steps stated in section 4.2.4 of SNEC procedure E900-IMP-4520.04, 'Survey Methodology to Support SNEC License Termination' and attached ENERCON Services procedure.

2. Ensure that each sample container is labeled with the following information:

A. SR Number B. Sample Number C. Sample Date and Time D. Sample Location E. Samplers Initials

3. Record the sampling location of all samples on an approved map or drawing.

4. Document all discrepancies or deviations from this SR on a SR Continuation Sheet or Field Sample Collection Sheet (Sediment Sampling Data Form).

5. Consult the SNEC Project Manager for Juniata River Sampling and responsible GRCS before processing any sample. Samples may be composited, processed as a whole, processed in sections, or other method as determined by SNEC Project Manager and GRCS.

6. Sample processing methodology shall be performed in accordance with SNEC Procedure E900-IMP-4520.02,

'Preparation of Sample Materials for Analysis".

.. ,.._ _._ .. .. APPROVAL SIGNATURES SR COORDINATOR William Stoner / DATE 10/04/01 RTR - A. Paynter /( DATE q 4 CZ\

ISR N DATE

. CONCURRENCE' N/A DATE

.:RSO APPROVAL A. Paynter I DATE SR kLO -OUT  ;

GRCS'.. DATE CLAO DATE

-SRCOORDINATOR DATE RSO DATE COMMENTS Page 2 of 3

- I-

.; r -I.

!z.- s SURVEY REQUEST - SAMPLE ANALYSIS SHEET

'SR NUMBER SR-0034 ..DATE OF REQUEST - 10/04/01 REQUESTED SAMPLE ANALYSIS SAMPLE TYPE I

RADIONUCUDE

~~~TYPE OF ANALYSIS R

RQIE COUNTING COMMENTS

-. ';

____ .SYSTEM ': _ MDA Cs-1 37 Gamma Scan 0.18 pCi/g Other analysis (i.e., TRU, HTD, etc.) may be Sediment and Scrape Samples performed as requested by the SNEC Co-60 Gamma Scan 0.15 pCilg Project Manager for Juniata River 4 4 4-Sampling, RSO, or SR Coordinator.

t 1-4 4 4-4 t 4-t 1 1-4 4 4-4 4 4-4 4 +

4 4 +

4 4- 4 I ~ II SIGNATURES SR COORDINATOR William Stoner/ DATE 10/04/01 RSO'APPROVAL A. Paynter I DATE l LJ~O4k\

Page 3 of 3

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Work Procedure Sediment Sampling Raystown Branch of the Juniata River for GPU Nuclear, Inc.

Saxton Nuclear Experimental Corporation Facility Saxton, Pennsylvania Prepared For:

GPU Nuclear, Inc.

300 Madison Avenue Post Office Box 1911 Morristown, NJ 07962-1911 Prepared By:

ENERCON Services, Inc.

4115 William Penn Highway Suite 202 Murrysville, PA 15668 October 2, 2001

Work Procedure Sediment Sampling Raystown Branch of the Juniata River for GPU Nuclear, Inc.

Saxton Nuclear Experimental Corporation Facility Saxton, Pennsylvania 1.0 Purpose This plan has been prepared by ENERCON Services, Inc. (ENERCON) and Marion Hill Associates, Inc.

(Marion Hill) at the request of GPU Nuclear, Inc. (GPU) to assure that sediment sampling activities on the Raystown Branch of the Juniata River are conducted in a safe manner.

2.0 Applicability/Scope This procedure applies to all sediment sampling activities performed on the Raystown Branch of the Juniata River. The goal of this Work Procedure is to describe proper general procedures for sediment sampling and the use of sediment sampling equipment. Sound sediment sampling techniques that are followed for all sampling efforts on this project will improve the quality of data received from sediment surveys. Effective and proper use and cleaning of sampling equipment is important to the safety of field staff and quality assurance and control of samples Study goals may require that additional or alternate equipment or procedures be used than are discussed here. Any procedure changes will be based on sound scientific and practical reasons and should ultimately help further the goals of the study, without the loss of quality assurance and control.

3.0 Definitions R.S.O.: GPIJ Radiation Safety Officer 4.0 Equipment

• Global Positioning System (GPS) unit

• Recording fathometer

• Personal protective clothing

• Sampling Vessels

- Modified sediment sampling vessel (14 feet)

- 13 x 16 feet sediment sampling barge (if needed) 1

Or i

12 or 14 feet tender boat (if needed)

Back up safety boat to be located near Guard Station USCIG Safety Equipment on Each Vessel

• 4

• Personal Flotation Devices for each individual I

• Throwable device

• Fire extinguisher (if flammable fuel on board)

• Oars and/or paddles

• Signaling device capable of being heard for one-half mile 4.2

• VHF-FM marine radio

• Outboard engine (optional)

L.m

• Anchoring device (optional)

• Registration 4.3 Coriiig Equipment

• Two and three inch OD steel tubes - two and four foot lengths

• Plastic liners (if practicable), nose cones and catchers (if needed)

• Slide hammer

• Hoisting boom or tripod

• Winch

. 4.2

• Lines and/or cables

• Pulleys

• Liner holders (if needed)

• Containers to composite samples

• Spoons Alternative Devices - General

• Split spoons two and three inch outside diameter 2

l

• Ponar grab samples p

• Containers to composite samples 1 4.4

• Spoons Alternative Device - Suction (NOTE: Due to the lack of suitable depositional areas, an alternative suction method may be used.)

• Two-inch trash pump with adequate lengths of intake and discharge hose

• Modified nose cone to collect finer particles and to keep out the very coarse material iI that would clog the pump I

• Holding containers to permit small particles to drop out of solution (50 gallon plastic I containers that can be stacked for ease of transport)

I II

• Draining device and/or submersible pump to remove excess water from holding containers I I... .

• Container to composite sediment samples I,

i.

• Spoons I

4.5 Decontamination Gear i

• Processing table to provide a clean surface for equipment

• Wash and rinse containers for solvent (Ivory liquid soap and water) and wash water (4iver..watr) i o/8/cc

• Containers for used solvent and concentrated rinse water with lids

• Submersible pump or buckets

• Brushes

• Aluminum foil and/or plastic bags

i. .

• Solid waste containers (e.g. garbage bags) for trash 3

5.0 Procedure 5.1 Limits and Precautions See ENERCON Health and Safety Plan.

5.2 Site Reconnaissance 5.2.1 The survey team will perform site reconnaissance activities prior to sampling to verify that selected site locations are in viable sediment deposition areas. A deposition area will be considered viable for core sampling if a significant accumulation of fine-grained sediments exists at that location 5.2.2 Record the findings of reconnaissance activities in a field notebook including, date, time, water depth, substrate characteristics, flow conditions, site location, conclusions regarding site viability, and proposed sampling approach.

5.3 Preparation for Sampling 5.3.1 Field Staff - All field staff working at a site will understand the basic goals of the study, use of the samples, and the basic methods to be used to assure that quality samples are collected.

5.3.2 Safety - All field staff will be aware of and fully understand the possible safety hazards posed by the site Precautions will be taken to prevent exposure to contaminated sediments (See Site Specific Health and Safety Plan.).

5.3.3 Cleaning Equipment - All equipment will be cleaned before going into the field and between sites to prevent contaminating sediment samples. Equipment will be washed with clean scrub brushes using Ivory liquid and river water. To properly clean equipment, wash apparatus thoroughly with detergent, then rinse 5-6 times with hi-ff.water. Rinse the apparatus with site water before taking the first sediment sample. Al /0/Bl/a 5.4 General Procedures in the Field 5.4.1 Make sure all equipment is clean and ready to use.

5.4.2 When working from a boat, two or three anchors or spuds driven into the sediment in shallow water will help stabilize boat in breezy, open water conditions (if needed).

5.4.3 Each grab or core attempt should be taken from undisturbed sediment at the site. Avoid disturbing sediments with a boat motor or by walking on the site. Approach sites from downstream to avoid suspending sediment into the water column over the site.

4

I 5.4.4 Have container ready to accept entire sample quickly upon retrieval.

5.4.5 Label every sample container with a permanent marker on labeling tape on the side of the jar or wherever the label will not come off accidentally. Information on the label will be that required for SNEC facility samples.

5.4.6 Record all site information in a field notebook or on field sheets (Exhibit I attached) before leaving site. Information usually includes: field measurements, time and date, persons collecting samples, number and types of samples taken including field blanks, etc., labels assigned to each sample, and any general observations. Keep records of all samples, how they were labeled and any blanks or duplicates that are submitted for analysis.

5.5 Collecting Composite Samples (if necessary).

5.5.1 Composite samples may required to generate sufficient sample volume for all analyses. Multiple grabs or cores for a composite sample should be taken from a relatively homogeneous sediment deposit (i.e., all grabs should be of similar sand/silt content). It is best to know the rough boundaries of the sediment deposit or "site" before sampling.

5.5.2 Place each grab or core into a single mixing bowl, remove any large objects such as sticks, leaves or stones, etc. and stir thoroughly with a spoon to homogenize. A single grab or core should be mixed at least two minutes. Multiple grab or core samples should be mixed five minutes or longer if necessary.

5.5.3 Fill sample jars with the sediment mixture by placing one spoonful sequentially into each jar until the jars are full (see section on sample containers). This subsampling system assures that each sample container contains a sample as similar as possible to the other containers.

5.6 Quality Control Measurements 5.6.1 Quality control measurements will be performed by randomly re-sampling 5% of all sampling points using identical methodology.

5.6.2 The locations of quality control samples will be determined by the R.S.O.

5.7 Collecting Replicate Samples 5.7.1 Replicate samples will be collected at each sampling site.

5.7.2 Each replicate sample will be taken from an undisturbed area of sediment.

5.7.3 Equipment will rinsed with site water between replicate samples.

5.8 Core Sampling 5

5.8.1 To prepare for collecting a sample, the survey team will begin by measuring water depth. The corer will then be assembled and lowered to the river bottom.

5.8.2 The survey team will utilize a slide hammer to drive 2 or 3 inch outside diameter stainless steel sampling tubes with plastic liners (is appropriate) connectable in 2 or 4 foot lengths into river substratum and bottom sediments.

5.8.3 The slide hammer will be used to drive the sampling tube into the river bottom. Once the desired depth of drive or refusal is achieved, the sampler will be removed from the river bottom by using a winch system (if appropriate) and brought to the surface for removal and processing.

5.8.4 More than one core sample may be required at each sampling location to achieve the required volume.

5.8.5 The survey team will conduct this sediment sampling effort using an aluminum workboat modified for the collection of sediments and/or a mobile workbarge capable of being assembled on site. Shallow areas may be sampled using waders or hip boots.

5.8.6 Heavy-duty anchors with long lines may be used to hold position on sampling locations. The workboat may also be anchored to land bound anchor points (e.g. trees, rocks) where appropriate.

5.8.7 The survey team will have available stainless steel Ponar samplers, 2 or 3 inch outside diameter sampling tubes, split spoon samplers and all the necessary sediment sampling equipment to collect the sediments from the river. The survey team will also provide the solvents and/or wash water used for decontamination of the equipment. These spent fluids will be containerized and their disposal will be the responsibility of the client.

5.8.8 The survey team will identify the sample location using Global Position System (GPS), transport samples to the processing station, containerize the sediments, decontaminate sampling equipment, maintain chain-of-custody, and handle delivery of the samples.

5.9 Grab Samplers (Ponar).

5.9.1 Scope Based on the river morphology of the area, cobble, gravel and sand are likely to be encountered.

Therefore, recovery of soft sediments in the core sampler may be difficult to achieve. Cobble and gravel size of greater than 1.5 inches may impede any recovery by the corer. Therefore, it may be difficult to recover the required sample volume. In these cases use a Ponar grab sampler may be used if (if practicable).

6

5.9.2 Collection Procedure 5.9.2.1 Set closing mechanism and lower grab slowly to substrate, being careful to avoid a shock wave caused by too rapid of a descent near the sediment.

5.9.2.2 Initiate closure mechanism of grab. This is usually a sharp pull on the rope.

5.9.2.3 When it feels like the grab has closed and contains sediment, raise grab at a steady rate and immediately position over large bucket.

5.9.2.4 Empty entire contents of grab into mixing bowl if sample needs to be mixed.

5.9.2.5 Place appropriate volume of sediment into sample container.

5.10 Suction Devices.

5.10.1 Scope: In areas where a sample should/must be taken (e.g. weir and discharge areas) and suitable areas of deposition does not exist, a suction method may be attempted.

5.10.2 Collection Procedure.

5.10.2.1 The trash pump will be started and permitted to warm-up and generate an adequate flow rate and suction.

5.10.2.2 River water being pumped during this start up phase will be recirculated back into the river.

5.10.2.3 For sediment sampling, the modified suction head will be placed in contact with the river bottom and forced among the larger cobbles and boulders.

5.10.2.4 Once sediment starts flowing through the hoses, this slurry will be directed into the 50-gallon settling containers. It may take several 50 gallon containers to collect enough sediment for one sample.

5.10.2.5 Once enough water sediment slurry has been collected, this would be permitted to settle. The excess water would be decanted off and the remaining sediment would be placed in the sample container.

6.0 Responsibilities Responsibilities are as stated in Section 4.0.

7.0 Exhibits Exhibit 1 - Sediment Sampling Data Form 7

EXHIBIT 1 I

SEDIMENT SAMPLING DATA FORM DATE/TIME SAMPLE NO.

SAMPLE AREA:

TITLE OF STUDY LOCATION LONG. LAT.

SAMPLE SIZE/CONTAINER SAMPLING METHOD (DESCRIPTION) -

VISUAL CHARACTERIZATION ANALYZE FOR:

REMARKS:

PERSONNEL:

PHOTOGRAPH NOS.

SAMPLER'S SIGNATURE: DATE/TIME:

CAWINDOWSTEIwt P\Sampling Proce(

Table I Sediment Sampling Locations Sample Sample Sample Site Identification Identification Latitude Longitude Date Time Sample Type Weir1 SXSD1472 400 13'42.539' 78014'33.429" 10/10/01 855 Scoop Weir 1 SXSD1473 400 13' 42.539" 78°14' 33.429' 10/10/01 900 Scoop Weir 2 SXSD1474 40°13'43.417' 780 14'30.996' 10/10/01 1205 Scoop Weir 2 SXSD1475 400 13'43.417' 78" 14'30.996' 10/10/01 1215 Scoop Weir 3 SXSD1476 40°13'43.491' 780 14'31.384' 10110/01 1226 Scoop Weir 3 SXSD1477 40" 13' 43.491' 780 14' 31.384- 10/10/01 1232 Scoop Weir 4 SXSD1478 400 13' 43.676' 78014'32.104- 10/10101 1240 Scoop Weir 4 SXSD1479 400 13' 43.676" 78014' 32.104' 10110/01 1245 Scoop Weir 5 SXSD1480 400 13' 42.832- 78014' 32.382' 10110/01 1415 Suction Weir 5 SXSDI481 400 13'42.832- 78014'32.382- 10110/01 1420 Suction Weir 6 SXSD1545 400 13' 42.597" 780 14' 33.435' 10/18/01 817 Suction Weir 6 SXSD1546 40° 13' 42.597' 78014.33.435. 10/18/01 823 Suction Discharge Tunnel I SXSD1482 40" 13'43.548' 78014'34.806' 10/10101 1502 Scoop Discharge Tunnel 1 SXSD1483 400 13' 43.548' 780 14' 34.806- 10/10/01 1508 Scoop Discharge Tunnel 2 SXSD1484 400 13' 43.561" 780 14' 35.097' 10/10/01 1525 Scoop Discharge Tunnel 2 SXSD1485 400 13'43.561' 780 14' 35.097- 10/10/01 1535 Scoop Discharge Tunnel 3 SXSD1486 400 13'42.284' 78014'34.657' 10/10/01 1515 Ponar Discharge Tunnel 3 SXSD1487 400 13' 42.284' 78 14' 34.657" 10/10/01 1530 Ponar Discharge Tunnel 4 SXSD1488 400 13' 42.440' 78 14'36.302' 10/10/01 1555 Ponar Discharge Tunnel 4 SXSD1489 400 13' 42.440" 780 14' 36.302' 10/10/01 1605 Ponar Discharge Tunnel 5 SXSD1490 40° 13' 42.116' 78014' 36.419' 10/10/01 1612 Scoop Discharge Tunnel 5 SXSD1491 400 13'42.116' 78014'36.419' 10110/01 1615 Scoop Spray Pond Lagoon SXSD1498 400 13' 27.614' 78°14'40.116' 10/11/01 1130 Core Spray Pond Lagoon SXSD1499 400 13' 27.614" 78" 14'40.116' 10/11/01 1155 Core Spray Pond Bog SXSD1500 400 13'28.015' 78014'39.220- 10/11/01 1240 Ponar Spray Pond Bog SXSD1501 40° 13' 28.015" 780 14'39.220' 10/11/01 1242 Ponar Site 1 SXSD1502 40" 13'20.197' 78014'35.441- 10/11/01 1310 Scoop Site 1 SXSD1503 400 13' 20.197' 78" 14' 35.441" 10/11/01 1313 Scoop Site 2 SXSD1496 40" 13'30.559' 78° 14'43.783" 10/11/01 1018 Scoop Site 2 SXSD1497 400 13' 30.559' 78014' 43.783' 10/11/01 1022 Scoop Site 3 SXSD1494 40° 13'32.130' 78014'45.129' 10/11/01 1007 Ponar Site 3 SXSX1495 400 13'32.130' 78 14'45.129' 10/11/01 1010 Ponar Site 4 SXSD1492 400 13'36.644' 78014'46.519" 10/11/01 947 Scoop Site 4 SXSD1493 400 13'36.644" 78°14'46.519" 10/11/01 954 Scoop Site 5 Deleted due to redu dancy with disch rge tunnel sampling.

Site 6 SXSD1506 40" 13' 56.499" 78013' 53.996" 10/15/01 1415 Core Site 6 SXSD1507 40° 13' 56.499' 78°13'53.996' 10/15/01 1430 Core Site 7 SXSD1508 400 13' 59.081" 78013'48.768' 10/15/01 1510 Core Site 7 SXSD1509 400 13' 59.081" 78" 13' 48.768' 10/15/01 1532 Core Site 8 SXSD1535 400 14'01.520' 78013'39.818' 10/16/01 946 Core Site 8 SXSD1536 40" 14' 01.520" 78013' 39.818' 10/16/01 1014 Core Site 9 SXSD1 504 400 13' 57.580' 78° 13'24.309' 10/16/01 1200 Core Site 9 SXSD1505 400 13' 57.580' 78013'24.309' 10/16101 1216 Core Site 10 SXSD1470 400 14' 16.367' 78013' 15.900' 10/9/01 1530 Core Site 10 SXSD1471 40" 14' 16.367' 78°13' 15.900' 10/9/01 1600 Core Site 11 SXSD1547 400 14'54.757' 78013'49.096' 10/18/01 1116 Core Site 11 SXSD1548 400 14'54.757" 780 13'49.096' 10/18/01 1200 Core BKG - I SXSD1537 40" 09' 25.063" 780 15' 22.185" 10/17/01 940 Core BKG - 1 SXSD1538 40" 09' 25.063' 78015'22.185' 10/17/01 955 Core BKG - 2 SXSD1539 400 12' 12.494' 78015'46.467' 10/17/01 1300 Ponar BKG - 2 SXSD1540 40" 12' 12.494' 78"15' 46.467' 10/17/01 1315 Ponar BKG - 3 SXSD1543 40" 11'47.708' 78015'04.959' 10/17/01 1355 Ponar BKG-3 SXSD1544 40° 11' 47.708' 78°15'04.959' 10/17/01 1405 Ponar

Table 2 Juniata River Sediment Gamma Spec Results Y Y - - -- ¶- --

us-lit SAMPLE ID l HpGeID# l SAMPLE TIME DESCRIPTION/LOCATION (pCilg) (Pci/g)

- 14728; ; 3-9330 10/10/01 855 t-. WEI8. SITE1 9C 2.55 < 0.08 1473 2-9329 10/10/01 900 WEIR SITE #1 1.07 < 0.06 1474 3-9327 10/10/01 1205 WEIR SITE #2 < 0.07 < 0.07 1475 2-9326 10/10/01 1215 WEIR SITE #2 0.05 < 0.055 1476 1-9325 10/10/01 1226 WEIR SITE #3 < 0.039 < 0.05 1477 1-9338 10/10/01 1232 WEIR SITE #3 < 0.06 < 0.05 1478 2-9339 10/10/01 1337 WEIR SITE #4 < 0.06 < 0.05 1479 1-9328 10/10/01 1245 WEIR SITE #4 < 0.05 < 0.04 1480 1-934 10/10101 1415 WEIR SITE #5 0.15 < 0.04 1481 1-9345 10/10101 1420 WEIR SITE #5 0.08 < 0.04 1545 1-9412 10118/01 817 WEIR SITE #6 1.8 < 0.05 1546 2-9413 10/18/01 823 WEIRSITE#6 1.2 < 0.07 1482 2-9346 10/10/01 1502 DISCHARGETUNNEL#1 0.07 < 0.06 1483 2-9354 10/10/01 1508 DISCHARGE TUNNEL #1 < 0.07 < 0.07 1484 3-9352 10/10/01 1525 DISCHARGETUNNEL#2 < 0.09 < 0.07 1485 2-9366 10/10101 1535 DISCHARGE TUNNEL #2 < 0.04 < 0.07 1486 3-9356 10110101 1515 DISCHARGE TUNNEL #3 < 0.05 < 0.06 1487 2-9348 10/10/01 1530 DISCHARGETUNNEL#3 < 0.045 < 0.06 1488 1-9371 10/10/01 1555 DISCHARGE TUNNEL #4 < 0.05 < 0.04 1489 2-9372 10110/01 1605 DISCHARGETUNNEL#4 < 0.06 < 0.06 1490 3-9349 10110/01 1612 DISCHARGETUNNEL#5 < 0.06 < 0.06 1491 2-9351 10/10/01 1615 DISCHARGETUNNEL#5 < 0.06 < 0.06 1498 1-9369 10/11/01 1130 SPRAY POND LAGOON < 0.06 < 0.05 1499 2-9364 10/11/01 1155 SPRAY POND LAGOON < 0.06 < 0.07 1500 1-9367 10/11/01 1240 SPRAY POND BOG < 0.06 < 0.06 1501 1-9363 10/11/01 1242 SPRAY POND BOG < 0.14 < 0.12 1502 1-9365 10/11101 1310 RIVER SITE #1 < 0.04 < 0.05 1503 1-9361 10/11/01 1313 RIVER SITE #1 < 0.05 < 0.05 1496 3-9358 10/11/01 1018 RIVER SITE #2 < 0.05 < 0.08 1497 3-9362 10/11/01 1022 RIVER SITE #2 < 0.1 < 0.1 1494 3-9360 10/11101 1007 RIVER SITE #3 < 0.1 < 0.09 1495 2-9357 10/11101 1010 RIVER SITE #3 < 0.1 < 0.09 1492 2-9370 10/11/01 947 RIVER SITE#4 < 0.08 < 0.07 1493 1-9347 10/11/01 954 RIVER SITE#4 < 0.047 < 0.057 1506 1-9397 10115101 1415 RIVER SITE #6 0.07 < 0.04 1507 2-9399 10115/01 1430 RIVER SITE #6 < 0.053 < 0.055 1508 1-9390 10/15/01 1510 RIVER SITE #7 < 0.05 < 0.04 1508-B 2-9403 10115/01 1510 RIVER SITE #7 < 0.06 < 0.05 1509 2-9391 10/15101 1532 RIVER SITE #7 < 0.06 < 0.06 1509-B 1-9402 10115/01 1532 RIVER SITE #7 < 0.04 < 0.03 1535 2-9386 10/16/01 946 RIVER SITE #8 0.09 < 0.06 1536 1-9387 10/16/01 1014 RIVER SITE #8 0.11 < 0.05 lM504 g 1-9392 10/15/01 1200 izM>2tRIVER 'SITE #9 4, 0.16 < 0.04 1505 2-9393 10/15/01 1216 RIVER SITE #9 < 0.06 < 0.06 1470 1-9333 10/9/01 1530 RIVER SITE #10 0.13 < 0.037 1471 2-9334 10/9/01 1600 RIVER SITE #10 < 0.044 < 0.04 1547 1-9420 10/18/01 1116 RIVER SITE #11 < 0.03 < 0.04 1548 2-9416 10/18/01 1200 RIVER SITE #11 < 0.049 < 0.063 1537 6' n.: 2-9419 10117101 940 .BKG4#1RIDDLESBURGtI.. 0.08 < 0.07 1538 2-9421 10/17/01 955 8KG #1 RIDDLESBURG < 0.07 < 0.07 1539 2-9423 10/17/01 1300 8KG #2 WARRIORS PATH 0.07 < 0.06 1540 1-9418 10/17/01 1315 BKG #2 WARRIORS PATH 0.09 < 0.05 1543 1-9422 10/17/01 1355 8KG #3 WARRIORS PATH 0.01 < 0.04 1544 1-9414 10/17/01 1405 BKG #3WARRIORS PAT- < 0.04 < 0.05 Areaswith a <symbol are less than MDA.

TRU analyses performed on these samples (Ref. BWXT Report #0110089).

Table 3 Juniata River Sediment TRU HTD Results Reference BWXT Report# 0110089, November 13, 2001 Results (pCilg)

Isotope Weir #1 River Site #9 Bkg #1 (Riddlesburg)

H-3 < 1.02E+01 < 1.01E+01 < 9.62E+00 C-14 < 4.58E+o0 < 4.82E+00 < 4.94E+00 Fe-55 < 1.19E+00 < 3.21 E-01 < 1.61 E-01 Ni-59 < 5.20E+00 < 1.34E+01 < 5.74E+0O Ni-63 < 7.46E+00 < 6.94E+00 < 7.98E+o0 Sr-90 < 1.40E-02 < 1.OOE-02 < 1.OOE-02 Tc-99 < 5.56E-01 < 2.05E+00 < 1.25E+00 1-129 < 1.35E+00 < 1.46E+00 < 1.27E+00 Np-237 < 3.41 E-03 < 5.45E-03 < 1.03E-02 Pu-242 < 3.41 E-03 < 4.35E-03 < 3.56E-03 Pu-239/240 < 3.41E-03 < 3.12E-03 < 3.56E-03 Pu-238 < 3.41 E-03 < 3.48E-03 < 3.56E-03 Pu-241 < 9.60E-01 < 1.06E+00 < 1.15E+00 Am-243 < 5.13E-03 < 2.83E-03 < 3.50E-03 Am-241 < 4.89E-03 < 2.83E-03 < 3.50E-03 Cm-244 < 3.70E-03 < 3.16E-03 < 3.50E-03 Cm-242 < 5.72E-03 < 3.02E-03 < 3.72E-03 U-234 t

_ -4.-:k0EaQj1ii~ _ -* 29EEipr1 _ 77 ~ E E 1.

EU-235 _ Z230EiO2~'{ _ < -f<5j1x.1St2trJ-

,2E0s U-238 j34'ERjjif -4Xr412E-O1' " , 4i 95E-O1 [-'

Co-60 _ f2'00E02* <I 2.74E-02 < 1.37E-02 Nb-94 < 1.08E-02 < 2.36E-02 < 1.13E-02 Sb-125 < 3.83E-02 < 5.90E-02 < 3.11 E-02 Cs-1 34 < 1.57E-02 < 3.86E-02 < 2.04E-02 Cs-137 _ t2.87E+/-00 i;54EjO I.

I_:1 .6 2EO.2Et02, Ce-144 < 8.78E-02 < 1.32E-01 < 8.73E-02 Eu-152 < 6.24E-02 < 1.39E-01 < 6.86E-02 Eu-154 < 4.20E-02 < 9.41 E-02 < 4.66E-02 Eu-155 4.69E-02 _< 6.98E-02 < 3.26E-02 Shaded areas denote positive results.

Areas with a < symbol are less than MDA.

APPENDIX A-4 DCGLw Calculation Logic for CV Yard

DCGL Calculation Logic-CV Yard Soil & Boulders (Decay Update)

Survey Unit: SNEC Containment Vessel (CV) Yard Soil and Boulders

11.

Description:

The purpose of this calculation is to determine a representative isotopic mix for the CV Yard Soil and associated Boulders from available sample analyses. The effective surface 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. Table explanation is as follows.

Table 1: Reduced Listing - This table, which has been extracted from a larger database, provides a list of the most representative sample analyses. Results are from scoping, characterization, and pre/post remediation surveys. The samples consist of soil and soil-like media that was 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 MDA values are noted in the gray shaded fields.

Values in red typeface are on-site analysis results.

Table 2: Reduced Listinq - Decayed - This table decays the data from Table 1. Half-life values (days) are listed above each respective nuclide column. Samples are decayed from the respective analysis date to December 15, 2004. Positive results are denoted in a yellow background field while MDA values are noted in the gray shaded fields. Values in red typeface are on-site analysis results.

Table 3: Reduced Listing Decayed - MDAs Removed - This table provides the best overall representation of the data. Non-positive nuclide columns have been removed as well as all the MDA values. Therefore, 11 nuclides have been reduced to four (4).

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.

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 mean percent values were averaged using only the positive sample results in each column. In some cases only a single nuclide value (e.g. Sr-90) had a positive result. This value is listed as the value in the mean result field, and results in higher "mean percent of total" values for single positive radionuclides in the mix, which is a 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 mean percent values were averaged using only the positive sample results in each column. In some cases only a single nuclide value (e.g. Sr-90) had a positive result. This value is listed as the value in the mean result field. 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.

Table 6: Effective DCGL Calculator for Cs-I 37 (in dpm/100 cm2 ) - This table provides the surface gross activity DCGLW calculation results from data derived from Table 4.

1

Table 7: Effective DCGL Calculator for Cs-1 37 (in pCig) - This table provides the surrogate volumetric modified Cs-1 37 DCGLW calculation results from data derived from Table 5.

IV. Summary - Since the CV Yard and Boulders are volumes of soil or rock material, existing in place or in a pile, the release limit is primarily based on the volumetric DCGLW. Using the above data selection logic tables the calculated Cs-137 volumetric DCGLW is 5.75 pCi/g (previous value was 5.73 pCig due to earlier decay date of January 15, 2004). The updated value will be reduced by 25% as part of SNEC's requirement to apply an administrative limit as discussed in the License Termination Plan (LTP).

Using the above data selection logic tables the calculated gross activity DCGLwfor surface area is 44,306-dpm/100 cm2 (previous value of 44,434-dpm/100 cm2 due to earlier decay date of January 15, 2004). The updated value will be reduced by 25% as part of SNEC's requirement to apply an administrative limit as discussed in the License Termination Plan (LTP).

2

TAI F 41.PntfiClm i Wn.n LAMl. IL- gtA Co22 C-427 A.1. Pua-m P-a Pu41 C.14 1 EU-152 Anluin Ode 2

S 3

4 B

a I

S I

IS 14 Is le If Is Is 21 22 I TABLE 2-REDUCED LISTNG . DECAYED T12 T1/2 T7112 T12 T7112 T1/2 T 112 T112 7112 7112 71 D064WOM 2 I 3

S 4

a IS 5

11 17 II 14 16 I Ii Is II I?

It 22 23

. Z Ydow BSakgri.d

• Posilve Resul Shaded -ud

• MDA XXX RedVu es- On-SleArtysis 3

CON

TABLI 3 - REDUCED LISTIN5 DECAYED -MD/'s E*MOVED 51EC Supl No LAB No. ermrlptkC H-3 HLo-3n r-N 1 To pOO CY Twzvu rmy, 6162SR"S CY TuW §g~adyurCompab. CU B.BiE40 7.6i,1E-1.14E.O 1154.7 SX9sL992t9 111074 S abeS e RS (0-59,AY-128,OL1 S0S3 SXSL1063 T 9 ; 1131- h CV Yard sq BA-127. 81Z El.Saob 95, OL2 }:8: _ _ 8 4.82 SXS1089 TeIMge2- L#I*4-2 thCV Yard Sol AY-127, el OBt8R  : 3,E4O0 E9 0O. 1.0 35 SXSL115 T ue l L1.S4-3 NocthCV Yard Sol AY-128 804' , SmnipseD2 OL7 OL 4.25E-2 1 _ 5 95 SXS11122 T!I.*6 21; L116W4 North CV Ywd Sri AY-129, 79' H. $uSb 2, OL 2. 9E 10 _. 4.51E40 75q SXSLI130 Tsbdn-W22; 1110164 North CY Yard Sdl AX-129, 802 B. S5p 4, CL1 4.34E p0 2.15E-02 Z14E+01 25.73 SXSL1 132 ToloeL4*r1931U84 Norh CV Yard Soi AZ.I 30, S5W t S5,O1 2,59E400 2._4_00 5.04 SXSL1270 OwT,311-62AM 29,3-3,Sol,CYSE Skbde 6ProqCV, 000'B. ouI 2.14E4O1 21 37-SXSLI 281 OWCT,ai1U541 AM- 28,3-4, Sol, CY TwIe EWg6 FromCY, OW B. 011 _ _ ___ 4.0E400 4.05 SXSL2649 LsW-T322t; L1U77-2 AA W. A-2, 5to M10 D.h, OLI ME 51 Om SX52871 Todyne-71MR L17M6-1I CY Am. .g! Yord Url Pbi - l, 1R Wn LW Up I S_ 01 0L53 SXSL2872 Tolane718g L7iSie CV Am- EeslYard 04t Pb - Sutom (Lo top 2ert)r, OL 9.3E402 oos SXSL3140 llT4IS-6S-8w" EU* CV Yg,Sd Ela Q6 on WaI Splo t6 qpth);, 01 7.3E01 0.78 SXSL3142 T u 1L262-3 Sd Pie, CV Yard, Th1!. FM on East Sik, SR-37, OL1 ___ 5. 057 SXSL3145 inWMTl82S-U-1W Ea CV Yard, Sol Ple p 3' on Eam Sie OP DPh). 0LI 1_20E40 120 SXS1-3149 Tab"S L2320-4 Sol Pb, CV Yard. Ek Fed onEWt Sde, SR-37,OL1 __ 2AME41 o28 SXSL3153 OWT.I8U-m11S-h1 Eed CV Yard. Si Pk i Top (8 Dqpth), COL 2.85E-01 028 SXSL4142 Taiedpie L22187-2 CY Yard Sol - Wst SIde, API -7, OLI _.75EJ1 0.8 SXSL4143 Tabfel4 L22187-3 CV Yard Sol- Wm Sis. API-7, CLI _ 4.86ES1 0.49 SXSL4149 T dns; L22187-4 CY Yard Sol -Wat Side, AP1-7, OL 597ES2 3.79E4 385 TABLE 4- MEAWJ PERCENT OF TOTAM. FOR POSITIVE NUCLIDES WSIEC Sanple No UB M& Locan~flAiUbWW H-3 Sr-U Co-U C-137 TOWg CV Twurel gmXT, SINS-m CY TuWalSur4 CMpoIS, OL1 0.76% 0.07% 99.17% 1W.0%

SX9SL99219 111074 S~ibac. S0 t29 (0-5S),AY-1 2d, 011 100.00% 100.0%

SXSL1063 Tabdbne- fti L131114-i North CY Yard Sl BA-127,81? El, Sur* 115,OL2 82.64% 17.38% 100.0%

5XS11089 TOKLmre4U6 1.1184-2 Noth CVY Yard Sol AY-1 27. 510SON*e B 3, 3, OL1 58.38% 31.62% 100.0%

SXS(111 S Telkmiu-22 1191U-3 North CV Yard Sd AY-1 28, 04' El.Swrpb t 2. OL1 71.40% 23.60% 1W.0%

SXSL1122 Tebbp.4nM;L13.1844 NdthCY Yard Sol AY-129, 798 l, Swob t 2, O1. 39.91% 60.09% 100.0%

S1(511130 T c*bsr-UN L131S45 Noith CV Yard Sol AX 1298803' S. Sw* t 4. OL1 16.89% 0.08% 83.03% 100.%o S1(511132 T 2dya L U231131644 Nor1hCV Yard Soi AZ-I30, S t5. OL1 S1ph. 51.45% 49.55% 100.0%

SXSL1270 WIXT, *19UlffJ2 l-129,33, Sol, CY SE Sde S'From CV, 8' El., 011 100.00% 100.0%

SXSUt281 OlrXi, 81138n 01 AXM28, 3S, Sol, CV Twrel Eag 5' From CV, 8W B, OL1 1.00% 100%

SXSL2849 Te7ed 73229 L177-2 AWMolW1, A-2, Sto 10 Depth, OLI _ 1iD4% 100.0%

S(.w2871 Tpobbno-7194; L171I11 CY Am - Et Yard Drt Ple - Mdkk, 1t2 Way Lp, OL = lool13% 100.0%

SXS1(2872 Tleyne-7IS4t 14713-I CVAM - E&g YordttPkb - eOlom (an tlop cart), OLI -_ __M. 1 0D%

SXSL3140 WAT,4IMN3-1W1 EastCV Yard. Sol Pb M 8 on WeanSbde(EDth), COL 100.00% 100.0%

SXSL3142 Tebne; 121325-3 SdI Plb, C Yard, Three Fet onEst Side, SR-37,0OL1 _ 100% 100.0%

SX(SL3145 11MT,18S63-IU1 Ea. CV Yard, SollF 3' eon Eaa Side Or OL1 l) . 1.0% 100.0%

SXSL3149 Tafetdyn; L2 -4 Sol Plb, CV Yard, Six Fed on Eat Side, SR-37, O11 1000 100.0%

SXSL3153 BWT,IS314WWSU-81 ft. CY Yard, Sd Pb a Top (O Deph), O100.0%01 100.0%

SXSL4142 T.14no; L22187-2 CY Yard Sol - Wet Side, API -7, OL1 _ 10 0 100.0%

SX1S(4143 TeoeiS¶m L22187-3 CY Yard Sol - Wed Side, API-7, OLI I 101311.%100.09 SXSL4149 Tde*ma; L22187-4 CY Yord Sd - Wet Side, AM -7, OL __ _ 1.55% 98.45% 1 00.0%

Metr- 0.561113 I nM7E I n0 .05 In fRAI I 1 A41 Mwo*

0.241 0.009 0.282 Mmw % of Totul- 39.20% 0.54% 0.40% 59.85% 10.00%

2 Sigm + Memw 1.03E+00 7.63E-03 2.27E-02 1 .E-O 2.47

% of Tobtl- 41.86% 0.31% 0.92% 56.91% 100.00%

4 Co_-

TABLE 5 - RATIO TO Cs-137 FOR POSITIVE NUCLIDES SIIEC Sample Ho LAB Ho. Locatlonifeserlptlon H-3 Sr-90 Co-SO Ce-137 Total 1 CV Tunnel BWXT, 01020S9-01 CV Tunnel Sedimert Composle, OL1 7.70E-03 6.65E-04 1.OOE400 1.01 2 SX9SL99219 111074 Subsuface Sample t29 (0-5'), AY-128, OLI 1.0OE+00 1.oo 3 SXSL1063 Teledyne-80018; 1191841 North CV Yard Sol BA-1 27, 817Z B, Sample t5, OL2 4.76E400 41.002005.76 4 SXSL1089 Teledyne-80019; L19184-2 North CV Yard Sol AY-127, 810' E, Sample # 3, OL1 2.16E400 1.00E400 3.16 5 SXSL1115 Teledyne-80020; 1191843 North CV Yard Sol AY-128, 804' El, Sample t2, O1 2.50E400 1.00E400 3.50 S SXSL1122 Teledyne-80021; L191844 North CV Yard Sol AY-129, 788 B, Sample 2, OL1 6.64E-01 1.OOE400 1.6S 7 SXSL1 30 Teledyne-80022; L191845 North CV Yard Sol AX-I 29, 80 El, Sample t4, OL1 2.03E-01 1.01 E-03 1.00E4O 1.20 8 SXSL1 132 Teledyne-80023; L191848 North CV Yard Sol AZ-130, Sample 5, OL1 1.06E400 1.0E400 2.06 9 SXSL1 270 BWXT, 0108055-02 AX- 29,3-3, Sol, CV SE Side 5 From CV, 8W El., OL1 1.OOE+OO 1.o 10 SXSL 281 BUXT, 0108055-01 AX-I 28, 3-1, Sol, CV Tunnel East 5SFrom CV, 800 El OL1 1.OOE400 1i.oo 11 SXSL2649 Teledyne-73220; 118077-2 mAnsWell, A-2, 5to 10' Depth, OL1 _ 1.OE00 1.00 13 SXSL2871 Teledyne-71949; L17838-11 CV Area - East Yard Dirt Pie . Mddle, 1Q2 Way Up, OL1 1.00E+D0 1.00 14 SXSL2872 Teledyne-71948; L17838-10 CV Area - East Yard Dirt Pie - Botom (also top careter), OL1 1.00E+00 1.oo is SXSL3140 BWXT,1030-003-10-01 Esst CV Yard, Sol Pie C V on West Side (6 Depth), OU 1.00E400 1.oo 16 SXSL3142 Teledyne; L20326-3 SoN Ple, CV Yard, Three Feet on East Side, SR-37, OL 1.00E+00 1.00 17 SXSL3145 BWXT,1030-003-10-01 East CV Yard, Sol Pilep3 on East Side (6" Depth), OL 1.OOE+00 1.0o 18 SXSL3149 Teledyne; L20326-4 So! Pile, CV Yard, Six Feet on East Side, SR-37, OL 1.00E+00 1.00 19 SXSL3153 BWXT,1030-003-10-01 East CV Yard, Sol Pile ( Top W Depth), OL 1 1.00E400 1.o 21 SXSL4142 Teledyne; L22187-2 CV Yard Sod -West Side, API-7, OL1 1.00 E00 1.00 22 SXSL4143 Teledyne; L22187-3 CV Yard Sol -West Side, AP1-7, OLI 1 .OOE00 1.00 23 SXSL4149 Teledyne; L22187-4 CV Yard Sol -West Side, AP1-7, OL.. _____._ .57E.02 1.00E+00 1.02 Meanw. 1.890991 10.007699 10.005808 1 2.90 Slgma-. 13.47091 1.656 0.009 0.1279 0.00708 0.000 1604 2.90 Mean % of Total- 65.11% 0.27% 0.20% 34.43% 100.00%

2 Sigma +Mean-6 5.20E4W 7.70E-03 2.30E-02 1.E0400 6.23

% of Total-s 83.47% 0.12% 0.37% 16.04% 100.00%l l:

5

Table 6

, . . v . !s .

Effective DCGL Calculator for Cs-137 (dpml100 cMA2)

. . g . .

I I T=81 Limit 9dlita1v-44306 jdpmM00.- em^ 33229 d~pmM00 2m -

[ 25.0mremtyTEDE Limit i I j WW.EQS~~~~~~~~~~Iiilt & lwCiAdi iiK{s.

SAMPLE HO(s)-* CV Yard Soil & Boulder Samples - Oeac 12.15-04 26517 Idpmii00 cm^21 19888 ldpmMl0O cm^2 JkSNECALVI 75% l Individual Sample Input Limits Allowed Beta dpmMO00 Alpha dpmM00 Isotope (pCIg, uCI, etc.)  % of Total (dpmM0O cmA2) dpmM100 cmA2 mremfyTEDE cmA2 cmA2 i Am-241 0.000% 27 0.00 0.00 Am-241 2 C-14 0.000% 3,700,000 0.00 0.00 0.00 C-14 3 Co-60 5.67E-03 0.403% 7,100 178.64 0.63 178.64 .. - Co-60 4 01 ,17'0k81E 59.850% ItAmk!4i28 ,000i ~2 157,03tt 23.88l!,,f ;',26517.0 6¶ W -3 s Eu-152 0 .000% 13,000 0.00 0.00 0.00 Eu-152 6 H.3 5.51E-01 39.203% 120,000,000 17369.23 0.00 Not Detectable  ::iA H3 7 Ni-63 ___ ___ 0.000% 1,800,000 0.00 0.00 Ilot Detectable WA Ni 863 8 Pu-238 0.000% 30 0.00 0.00  !$? : - 0.00 Pu.238 9 Pu-239 0.000% 28 0.00 0.00 .. 0.00.Pu.239 10 Pu-241 0.000% 880 0.00 0.00 Hot Detectable .

• i .:Pu.241 11 Sr-90 7.64E-03 0.543% 8,700 240.63 0.69 240.63 ........W h Sr-90 100.0W0% 44306 25.0 26936 .

Maximum Permissible dpmMO cmA2 6

Table 7 I

7

APPENDIX A-5 Scan MDC for Nal Measurement of Soils

Analog Smart Portable Model ASP- 1

• OPERATES WITH EBERLINE DETECTOR PROBES TO MEASURE ALPHA, BETA, GAMMA, X-RAY AND NEUTRON RADIATION

• OFFERS EXTENDED RANGE WITH AUTOMATIC DEAD-TIME CORRECTION

• RADIATION UNITS EASILY SELECTED BY THE USER

• FUNCTIONS AS A RATE METER AND INTEGRATOR

• BATTERY-SAVING CMOS MICROCOMPUTER

• OPTIONAL SINGLE-CHANNEL PULSE-HEIGHT ANALYZER (PHA) AND INTERNAL G-M DETECTOR AVAILABLE Z _, ,.s.c^I. =;:

- Th ermo Eberline FW Electron C 0 MP C PATIOI N ASP-1

Model ASP-1, Analog Smart Portable GENERAL DESCRIPTION The Eberline Analog Smart Portable (ASP-1) is our time based on the count rate from the detector and most versatile, metered survey instrument. Designed the range switch position. Normal response time for use with G-M, scintillation and proportional ranges from one to ten seconds with a standard detectors, it is capable of measuring alpha, beta, deviation (SD) no greater than five percent over the gamma, x-ray and neutron radiation. top three decades of the useful range. Longer response times, and better precision, can be The ASP-1 functions as a rate meter and an in- selected.

tegrator, and displays the present radiation rate or the integrated total radiation received. Inventory savings can be significant by using the ASP-1. This instrument will perform the functions of Microcomputer-based, the ASP-1 corrects for coin- many other radiation survey instruments when cidence loss so that the upper limit of the range of coupled with detector probes available as ac-each detector is increased by a factor of ten or cessories. One detector probe can be used to more. When the useful range is exceeded, an over- measure gamma exposure rate, another to range alarm is given. The ASP-1 has built-in measure beta-gamma contamination, another to speaker and a head-set is provided for use in noisy measure alpha contamination, and another to areas. measure neutron dose equivalent. With appropriate detectors, the ASP-1 performs all functions of When the ASP-1 is used as a rate meter, the CMOS Eberline's E-120, E-130A, E-140, E-520, E-530, microcomputer selects the appropriate response PNR-4, PRM-6 and PRM-7, combined.

SPECIFICATIONS Operating Modes The ASP-1 continually computes the detector pulse Meter (lighted): rate and the total integrated count from the detector.

Upper scale: 0 to 1.0, 50 divisions (range deter- When the response switch is set at SLOW or FAST, mined by detector used) the meter displays the count rate in the calibrated Lower scale: 0 to 2500 V,50 divisions units (mR/h, rem/min, cpm, etc.). When INTE-Scale lengths: 7.6 cm (3 in.) GRATE is selected, the meter displays the total radi-ation received (in the same units of calibration, mR, High Voltage Output: From 300 to 2500 V with no rem, counts, etc.) since integration was last reset.

load and up to 1600 V with a 100 MQ load.

Battery Input Sensitivity:Adjustable from 1 to 50 mV, Six C-cell size batteries are used. The life of six negative pulse. carbon-zinc batteries is variable from about 150 to 250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br />, depending on the high voltage power Detector Dead-Time Compensation:Up to 255 ps. required, the speaker usage and the light usage.

Alkaline batteries will last more than twice as long External Control under the same operating conditions. The BAT A nine-position rotary switch turns the ASP-1 on, position of the range switch checks the battery checks the batteries, displays the high voltage and condition.

selects the range of operation. Three toggle switch-es control the speaker, the meter light, the reset function, the response time and the operating mode (rate or integrate).

OTHER SPECIFICATIONS Dimensions: 4.2 in. wide x 7.9 in. long x 6.2 in. high Weight:2.8 lbs. (1.3 kg)

(10.7 cmx 20 cm x 15.7 cm)

Connector:MHV for detector input Temperature Range: -400 F to +122 0 F (-40 0C to

+50 0C). Use alkaline or nickel cadmium batteries below 00 F (-180C)

DETECTOR PROBES RECOMMENDED FOR USE WITH ASP-1*

Model No. Type Measurement Useful Range with ASP-1 HP-270 Exposure or Exposure Rate Bkg to 3000 mR/h HP-290 Exposure or Exposure Rate 0.0005 to 40 R/h HP-210L Beta-Gamma Contamination Bkg to 20,000 counts/s HP-260 AC-3 Alpha Contamination Bkg to 40,000 counts/s NRD Neutron Dose Equivalent or 0.001 to 50 rem/h Dose Equivalent Rate LEG-1 Low Energy Gamma or X-Ray Bkg to 40,000 counts/s SPA-3 High Sensitivity Gamma Bkg to 35,000 counts/s

• When ordering the ASP-I with a detector, please specify the preferred radiation rate units. When order-ing the ASP-1 without a detector, or with more than one detector, please specify the first detector to be used and the preferred radiation units so that Eberline can set up the ASP-1 accordingly. If no detector is specified, the ASP-1 will be configured for use with a Model HP-270 detector; calibrated in mR/h.

ACCESSORIES Audio Headset:Part No. ADHS4 Carrying Strap:ZP10125099 Any of the following Eberline detectors can be used with the ASP- 1:

Detector Probe Cable Check Sources Probe Holder/Bracket AC-3 CA-12-60 CS-1, CS-10, CS-12, CS-15 HP-190A CA-16-60 CS-7A ZP10434029 HP-210AL CA-16-60 CS-13 HP-210L CA-16-60 CS-13 HP-210T CA-16-60 CS-13 HP-220A CA-16-60 CS-7A HP-230A CA-16-60 CS-13 ZP10434029 HP-260 CA-16-60 CS-13 ZP10434029 HP-270 CA-16-60 CS-7A ZP10434029 HP-280 CA-15-36 HP-290 CA-16-60 CS-7A ZP10434029 LEG-1 CA-12-60 NRD CA-15-60 YP11358000 PG-2 CA-12-60 SPA-3 CA-12-60 CS-7B SPA-6 CA- 15-36 CS-7B

Scintillation Probe Model SPA-3 A:

• HIGH GAMMA SENSITIVITY

• 2-INCH X 2-INCH Nal(TI) CRYSTAL

• RUGGED CONSTRUCTION A DIVISION OF

- Thermo Eberline 7/ Electron CORPOPATION SPA-3

Model SPA-3, Scintillation Probe GENERAL DESCRIPTION The Model SPA-3 scintillation probe is a The SPA-3 contains a 2-inch-diameter, 2-inch-rugged, waterproof gamma detector designed long Nal(TI) crystal, a 2-inch, 10-stage for high sensitivity of pulse-height applica- photomultiplier tube, tube socket with a tions. dynode resistor string, and a magnetic shield.

SPECIFICATIONS AVAILABLE ACCESSORIES Crystal: Nal(TI), 2-inch-diameter x 2 inches Instruments Cables long (5.1 cm x 5.1 cm). PRM-6 CA-1 2-60 Photomultiplier Tube: _ 2-inch-dlameter, ESP-1 CA-12-60 RM-20 CA-1 2-60 10-dynode, end-window with S-11 RM-21 CA-12-60 photocathode. MS-2 CA-12-60 MS-3 CA-12-60 Operating Voltage: Variable dependent upon SAM-2 CA-12-60 application.

Maximum Voltage: + 1600 V Sensitivity: =1200k cpm per mR/h with "13Cs Current Drain: =120 MQ resistance string yields 10 zA at 1200 V.

Wall Material: Aluminum Wall Thickness: 11s-inch (0.32 cm), 'Ii-inch (0.16 cm) at crystal Connector: Mates with Eberline CP-1 Finish: Enameled body with chrome-plated connector Size: 25/a-inch-diameter x 111/i inches long (6.7 cm x 28.3 cm)

Weight: 3.25 pounds (1.5 kg)

A DIVISION OF

- Thermo Eberline AE ElectronCO R PO PATIO N P.O. Box 2108 Santa Fe, New Mexico 87504-2108 (505) 471-3232 TWX: 910-985-0678 10-85

NUREG 1507 Table 6.4 PagelI of 2 NUREG 1507 Table 6.4 Nal Scintillation Detector Scan .MDCs for Common Radiological Contaminantsa The estimates of the scan MDCs provided in this table should be evaluated to determine the appropriateness of using these estimated scan MDCs for implementation in the final status survey. 1 1.25" x 1.5" Nal Detector 2" x 2" Nal Detector Radionuclide/Radioactive Scan MDC Weighted Scan MDC Weighted Material (pCilg) cpm/gRPh (pCilg) cpmljgR/h Am-241 44.6 5,830 31.5 13,000 Co-60 5.8 160 3.4 430 Cs-137 10.4 350 6.4 900 Th-230 3,000 4,300 2,120 9,580 Ra-226 (In equilibrium with 4.5 300 2.8 760 progeny)

Th-232 decay series (Sum of all radionuclides in 28.3 340 18.3 830 thorium decay series, in equilibrium)

Th-232 aloneb (In equilibrium with 2.8 340 1.8 830 progeny in decay series)

Depleted Uraniumc 80.5 1,680 56.0 3,790 (0.34% U-235) 8. ,8 Processed Natural 115 1,770 80.0 3,990 Uraniumc 3% Enriched UraniumC 137 2,010 95.7 4,520 20% Enriched Uraniumc 152 2,210 107 4,940 50% Enriched Uraniumc 168 2,240 118 5,010 75% Enriched Uraniumc 188 2,250 132 5,030 a Refer to text for complete explanation of factors used to calculate scan MDCs. For example, the background level for the 1.25" x 1.5" Nal detector was assumed to be 4,000 cpm and 10,000 cpm for the 2" x 2" Nal detector.

The observation interval was 1 second and the level of performance was selected to yield d' of 1.38.

mk:(-,)MSITStore:C:\Program%20Files\COMPASS\COMPASS.chm::/TechnicalGuidanc ... 7/21/2005

Nal Scan MDC Calculation - Weir Une Nal Scan MDC Calculation - Weir Line Soils

, Z b -3000 1- p : O0 HS - 56.i2 SW!

1 "50-1. i1':'-!"1.38

.. _ .90ob m"~4 HS d

- = 1.128 ObservationInterval (seconds)

SR HSd 0i  := HS ObservationInterval (seconds)

_ (b O i) 60 MDCRi:= (d-lb i 60 1DcR j 1.147:o 3 A:; net counts per minute MDCRR M)CR surveyor := Cr Al

- , - net counts per minute MDCR surveyor MDER:=

Conv MDER; 803s .R/h MDC MDER M;'; 0 pci/g 4 of S 7/21/2005 40of 5

Nal Scan MDC Calculation - Weir Line where:

b = backgroundin counts per minute b= backgroundcounts in observation interval Conv =Nal manufacturersreported response to energy ofcontaminant(cpm/uRfh) d = index ofsensitivity (Table 6.5 MARSSIM), 1.38 = 95% of correct detection's, 60%false positives HSd = hot spot diameter (in centimeters)

MDCSC0, = Minimum Detectable Concentrationforscanning fpCi/g)

MDCRI = Minimum Detectable Count Rate (ncpm)

MDCRSUwyr = MDCR1 correctedby human performancefactor(ncpm)

MDER = Minimum Detectable Exposure Rate (uR/h)

MSOp. = MicroShieldoutput exposure ratefor 1 pCilgof contaminant (mR/h)

°i = obervation Interval (seconds) p = human performancefactor SR = scan rate in centimetersper second 5 of 5 7/21/2005 7/21/2005 5 of 5

MicroShield v5.05 (5.05-00121)

GPU Nuclear Page :1 File Ref:

DOS File: SOIL.MS5 Date:

Run Date: July 21, 2005 By:

Run Time: 3:22:53 PM Checked:

Duration : 00:00:08 Case

Title:

Soil

Description:

Soil Density 1.5 glcc, 6" Cylinder @ 6 cm from Surface

_.Gmetry: 8 - Cylinder Volume - End Shields Source IDimensions Height 15 .24 cm 6.0 in Radius 28 .21 cm 11.1 in Doswe Points X Y z

1. 1 0cm 23.78 cm 0 cm 0.0 in SI 9.4 in 0.0 in hields Shield Name Dimenision Material Density Source 3.81e+CF4 cm 3 Concrete 1.5 Air Gap Air 0.00122 Source Input Grouping Method : Actual Photon Energies Nuclide curies becquerels uCi/cm3 Bqlcm3 Ba-1 37m 5.4066e-008 2.0004e+003 1.4190e-006 5.2503e-002 Cs-137 5.7152e-008 2.1146e+003 1.5000e-006 5.5500e-002 Buildup The material reference is : Source Integration Parameters Radial 60 Circumferential 60 Y Direction (axial) 60 Results Energy Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeVlcm 2/sec MeV/cm 2/sec mR/hr mR/hr No Buildup With Buildup No Buildun With Buildup 0.0318 4.142e+01 8.226e-06 9.957e-06 6.852e-08 8.294e-08 0.0322 7.641e+01 1.582e-05 1.927e-05 1.273e-07 1.551 e-07 0.0364 2.781 e+01 8.770e-06 1.146e-05 4.983e-08 6.508e-08 0.6616 1.800e+03 7.609e-02 1.347e-01 1.475e-04 2.612e-04 TOTALS: 1.946e+03 7.613e-02 1.348e-01 1.478e-04 2.615e-04

APPENDIX A-6 Scan MDC for Geiger Mueller Detector

GM Survey Meter Model E-14ON

• BUILT-IN SPEAKER W 500, 5k, 50k cpm SCALES

• RUGGEDIZED, SPLASH PROOF PACKAGE A DIVISION OF Eberline FE Thermo Electron CORPORATION E-1401

Model E-140N, Geiger-Mueller Survey Meter GENERAL DESCRIPTION The Model E-140N Survey Meter combines the A single printed circuit board contains most proven reliability of Geiger-Mueller (GM) components, resulting in a minimum of solder detectors with reliable electronics to provide Joints which enhances reliability. The PC an instrument with outstanding operational board connects to the cover, which permits characteristics in a compact, lightweight an operational unit to be removed from the package. case for ease of calibration.

The ruggedized meter gives exceptional The E-140N is equipped with a built-in-speaker readability and linearity with a variable and a mounted probe holder which will response time. Calibration stability results accommodate the HP-210 type (DT-304/PDR) from temperature compensation and voltage hand probe.

regulation. High efficiency circuits extend battery life.

SPECIFICATIONS AVAILABLE ACCESSORIES Range: Three linear ranges, covering 0 to Hand probe assemblies 50k cpm. Model Display: Ruggedized meter with 0-500 cpm HP-210T (tungsten) scale. HP-210AI (aluminum)

Response Time: Variable from 2 to HP-210L (lead) 10 seconds for 0-90 percent of final value. Connecting Cables Linearity: Within +/- 5 percent of full scale (Instrument to Probe) when driven with a repetitive signal. Model Battery Complement: Two "D" cells. CA-18-60, 60-inch ruggedized cable (standard)

Battery Life: Nominal 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> C-Zn, CA-1-36, 36-inch coaxial 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> Alkaline. Built-in battery check. CA-1-60, 60-inch coaxial Voltage Coefficient: Reading changes

<10 percent from new battery to end point.

Connectors: BNC for detector input. Audio Headset Assembly: Model BA201M No. 5501 MP for headphones. Carrying Strap: Model ZP10125099 Construction: Splashproof, all metal case, enamel finish. Radioactive Check Source: CS-7A, gamma Temperature: Operational from -40 'C to source

+ 60 'C (-40 OF to 140 OF).

Dimensions: 5 inches wide, 81/2 inches long, 71/ inches high (including handle) (12.7 cm x 21.6 cm x 18.1 cm).

Weight: 3.6 pounds (1.64 kg) with C-Zn batteries.

Detectors: The Model E-140N is compatible A OIVISION OF with all Eberline GM hand probes (+900 V).

DThermo Eberline Mr/=Electron COPPORATICN P.O. Box 2108 Santa Fe, New Mexico 87504-2108 (505) 471-3232 TWX: 910-985.0678 7-84

Hand Probe Model HP-210

-Ae z4,

.0 HP-210AL HP-21OT r2 t!.

A-1_

IT18

• THIN WINDOW "PANCAKE" GM M HIGH BETA SENSITIVITY X WINDOW PROTECTIVE SCREEN A DIVISION OF Thermo Eberline -

E Electron CC ROPATION HP-210

Model HP-210, Hand Probe GENERAL DESCRIPTION The Model HP-210 series hand probes provide a The HP-210T, with a high density tungsten shield, sensitive beta detector featuring a "Pancake" GM permits relatively low-level beta monitoring in a tube with a thin mica window. The open window, gamma background. Also available is the HP-210L which is protected by a sturdy wire screen, permits with a lead shield which has the same specifica-useful beta sensitivities down to 40 keV. The detec- tions as the tungsten shield. When low-level beta tor is alpha sensitive (above 3 MeV). monitoring is required in a low background area, the HP-210AL with an aluminum housing may be The HP-210 is designed for contamination surveys used.

on personnel, table tops, floors, equipment, etc.

SPECIFICATIONS HP-210T (DT-304) HP-210AL HP-210L Operating Voltage: 900 +/-50V 900 +50V Plateau Length: 100 V minimum 100 V minimum Plateau Slope: 0.1 percent per V maximum 0.1 percent per V maximum Dead Time: 50 ;s maximum 50 ps maximum Temperature Range: -220 F to +167OF -22 0 Fto +1670 F

(-3 0 0C to +750C) (-3 0°C to +750C)

Mica Window Thickness: 1.4 to 2.0 mg/cm 2 1.4 to 2.0 mg/cm2 Mica Window Size: 1.75 in. diameter 1.75 in. diameter (4.45 cm) 2.4 in2 (4.45 cm) 2.4 in2 Series Resistor: 3.3 mQ (in probe) 3.3mQ (in probe)

Gamma Sensitivity: -3600 cpm/mR/h (137Cs) -3600 cpmlmR/h (137Cs)

(into window)

Shielding Ratio: ? eiw _4:1 (6 0Co) ~1:1 (window: back) (,

• Beta Efficiency: -45 percent 9OSr-90Y S45 percent 90 Sr- 90Y

-30 percent 99Tc =30 percent 99Tc

-10 percent 14C -10 percent 14C Alpha Sensitivity: 3 MeV at window 3 MeV at window Connector: BNC series coaxial BNC series coaxial Size: 6.5 in. long x 3.5 in. wide 6.5 in. long x 3.5 in. wide x 3.8 in. high (16.2 cm x 3.8 in. high (16.2 cm x 8.8 cm x 9.6 cm) x8.8 cm x 9.6 cm)

Weight: 4.25 lbs. (1.9 kg) 1.5 lbs. (0.7 kg)

• Efficiencies with screen in place. Screen removal will increase efficiency by 45 percent of stated value. Efficiencies listed as percentage of 2ii emission rate from a one inch diameter source.

AVAILABLE ACCESSORIES Instruments Cables E-120 CA-1-36 E-140 CA-1-36 E-140N CA-18-60 E-520 CA-1 -36 ESP-1 CA-16-60 RM-14 CA-1 -60 RM-20 CA-16-60 RM-21 CA- 16-60 MS-3 CA- 16-60 A DIVISION OF Sample Holder: SH-4A - Thermo Eberline !E Electron COPPORATION P.O. Box 2108 Santa Fe, New Mexico 87504-2108 1-87 (505) 471*3232 TWX: 910-985-0678

Beta Scan Measurement MDC Calculation Weir Concrete Headwall Scan Parameters - HP-2 10 Probe e 1 :=.1 a :=1 p -p -j 4r% S := 7.62 d:i LAi 5.6

_J

1 -:;;" ...IS.

=fd b> -;W dd

-=0.583 ObservationInterval (seconds) sr 0 -- ,.S: j ObservationInterval (seconds) 60 .7-- ...;--

70 .1 fii.x-,!

b= 0.4 Counts in observation Interval

._ e 1 C = 90.655 MDCRi:=(d-i) ~60 oi MDCR I - 88.5 _ net counts per minute

~..... . . . -X . .... .. , ._ .4 MDC =i285n Tff g-b gross counts per minute

. tv;.. ..-.

MfDCRI))

= 151.7 net counts per minute in observation interval Oi MDCscan :=C-MDCR i MDCsc,' ,an 8,0624 .10 dpm per 100 cm2 Parametersfrom Post Remediation Surveys 900-01-2477,900-01-2476, 700-01-1763, 700-01-1764, 305-01-1751, 305-01-1752 MARSS. Paf318 643 Eq6-9 6-9a640-.A NUREG-157. PoSs6-1S t 6-17 3 7/21/200

where:

b = backgroundcounts per minute b1= backgroundcounts in observation interval p = humanperformancefactor J~d = detectorwidth in centimeters Sr = scan rate in centimetersper second d = index ofsensitivity (Table 6.5 MARSSIM), 1.38 = 95% of correctdetection's, 60%false positives MDCJCa , = Minimum Detectable Concentrationforscanning (dpm/100 square centimeters)

C = constant used to convert MDCR to MDC

• Instrument efficiency (counts/emission)

En =source efficiency (emissions/disintegration)

A = instrumentphysicalprobe area (in squarecentimeters)

MARSS!Mt Pga 6432to2673 Fruta 6£9A 6.10.andNUREG-S1 Pa 6-1Sto6-17 4 7121/200