ML071500500

Yankee Nuclear Power Station, Site Ground Water Collection for Ynps Decommissioning Document No. DESD-TD-YR-02-001

ML071500500
Person / Time
Site:	Yankee Rowe
Issue date:	02/04/2003
From:	Bellini F, Harper G, Maher E Framatome ANP
To:	NRC/FSME
References
DESD-TD-YR-02-001, Rev 1
Download: ML071500500 (170)

Text

A TECHNICAL DOCUMENT COVER SHEET Form DPR-3.4A FRAMATOME ANP Page 1 of 1 FRAMATOMEANPD &S QA Record Type: N/A Revision 3 DOCUMENT NO.:

DESD-TD-YR-02-001 REV.:

1 Page:

1 of 26 DOCUMENT TITLE:

Site Ground Water Data Collection for YNPS Decommissioning PROJECT NAME:

YNPS Environmental Engineering Field Support PROJECT NO.:

01637.00.2002.03.00002 CLIENT: Yankee Atomic Electric Company - YNPS QA CONDITION: Non QA

• Non-QA Pagination:

Cover Sheet & Text:

26 Figures 1-8 11 w/cover page Tables 1-3 30 w/cover page 3 w/cover pg 34 w/cover pg 30 w/cover pg 33 w/cover pg 2, w/cover page DVC 1

Total 170 Revision 1 corrects the units/data used in Table 2 for gamma-emitting radionuclides and provides a few changes based on a general review of the document. Typographical errors were corrected in lab nos. 49101, 16466R, 47793, 341901 and 49113. Two verified analyses not previously reported were added to Table 2, lab nos 62623 and 62620. A general review of the report also prompted minor editorial changes, and a revision of the angle between true north and grid north on the Figures 2 and 4 through 8.

DESIGN VERIFICATION METHOD:

E Design Review El Alternate Calculation El Qualification Testing Prepared By:

F. X. Bellini 2______-13 i V:?

(First, MI, Last)

PRINTED/TYPED NAME URE

/ DATE Verified By:

E. F. Maher

___________2//os (First, MI, Last)

PRINTED/TYPED NAME SIGNATURE DATE Approved By:

G. A. Harper

___T_

_/_03_

(First, MI, Last)

PRINTED/TYPED NAME SKNATURE DATE

TABLE OF CONTENTS Page

1.0 INTRODUCTION

4 1.1 GENERAL SITE DESCRIPTION.............................................................................................

4 1.1.1 Plant Location and Local Topography........................................................................

4 1.1.2 Plant Structures..................................................................................................

5 2.0 SITE GEOLOGY....................................................................................................

6 2.1 DISTRIBUTION AND CHARACTER OF SOIL AND BEDROCK UNITS AT THE SITE....................................

6 2.2 SITE CHARACTERISTICS AND MODIFICATIONS MADE BY CONSTRUCTION.........................................8 3.0 SITE GEOHYDROLOGY..........................................................................................

8 3.1 GROUND WATER TABLE ELEVATIONS..................................................................................

9 3.2 GROUND WATER IN BEDROCK............................................................................................

9 4.0 GROUND WATER CHARACTERIZATION METHODS..................................................

11 4.1 APPROACH FOR YNPS............................................................................................

11 4.2 PRIOR DETERMINATION OF ANALYTES OF CONCERN, SURROGATES..............................................

11 4.3 INVESTIGATION METHODS: PROCEDURES AND PLANS..............................................................

12

4.4 BACKGROUND

CONSIDERATIONS.......................................................................................

13 5.0

SUMMARY

OF CHARACTERIZATION GROUND WATER INVESTIGATIONS...................

13 5.1 WELL DESIGN AND LOCATIONS.........................................................................................

15 5.2 R.EFERENCES AND DATA.................................................................................................

15 5.3 ANALYTICAL DATA.......................................................................................................

16 6.0 SITE CHARACTERIZATION RESULTS.....................................................................

17.

6.1 WATER LEVEL MEASUREMENTS........................................................................................

17 6.2 WELL DEVELOPMENT....................................................................................................

17 6.3 SAMPLE ANALYSIS RESULTS.............................................................................................

17 6.3.1 Tritium...........................................................................................................

17 6.3.2 Gamma-Emitting Radionuclides in Ground Water Samples...............................................

19 6.3.3 Gross Alpha, Gross Beta and Sr-90 Anab'ses...............................................................

20 6.3.4 Spent Fuel Pool (SFP) Leakage..............................................................................

20 6.4 WELL CLOSURES..........................................................................................................

21 6.5 SITE GROUND WATER CONDITIONS

SUMMARY

22 6.5.1 Unit Thicknesses and Lateral Extent.........................................................................

22 6.5.2 Water-Transmitting Properties, Flow Velocity Estimates, and Inferred Kds..............................

22 6.5.3 Recharge and Discharge......................................................................................

23

7.0 REFERENCES

24 Ground Water Data for YNPS Decommissioning Page 2 of 26 DESD-YR-02-001 Rev. 1

1.

2.

3A.

3B.

3C.

4.

5.

6.

7.

8.

LIST OF FIGURES Regional Topographic Map Site Structures and Areas Geologic Map Geologic Profile A-A' Geologic Profiles B-B' and C-C' Ground Water Contour for Wells in Surficial Materials Plan Map of Monitoring Wells 1999 H-3 Concentration Map 2001 H-3 Concentration Map PAB Area: H-3 in Ground Water 1998-9 LIST OF TABLES Monitoring Well Information Summary YNPS Ground Water Database Analysis Information Gross Alpha and Gross Beta data Maximum 1999 H-3 Concentrations Well Closure History Properties of Geohydrologic Units at the Site LIST OF ATTACHMENTS Radiological Profiles of Soil Graphs of H-3 Concentrations in Monitoring Well Samples Monitoring Well Configuration Sketches Monitoring Well Ground Water Levels YNPS Spent Fuel Pool: Concentration of H-3, 1997-1999 1.

2.

3.

4.

5.

6.

1.

2.

3.

4.

5.

Ground Water Data for YNPS Decommissioning DESD-YR-02-O01 Rev. 1 Page 3 of 26

1.0 INTRODUCTION

Environmental site characterization studies and surveys to support the Yankee Nuclear Power Station (YNPS) decommissioning began in late 1992 and have been carried out by Yankee Atomic Electric Co, (YAEC), Yankee Nuclear Services Division (YNSD),

Duke Engineering & Services (DE&S) and Framatome ANP DE&S (FDE&S) personnel.

This report summarizes the ground water studies performed to date for site characterization.

The goals of ground water monitoring at the site have been to evaluate the status of the site ground water following plant operation and to verify that on-site decommissioning activities are not having a negative impact on the ground water through the release of radionuclides. Ground water samples collected for site characterization have provided a very small number of results identifying elevated (compared to U. S. EPA Drinking Water Standards) levels of any radionuclide. Elevated concentrations have been principally limited to tritium in well samples from in or near the Primary Auxiliary Building (PAB) during the time period from 1998 to 2000.

Site radiological release criteria for unrestricted use are provided by 10CFR20, "Radiological Criteria for License Termination: Radiological Criteria for Unrestricted Use" (Reference 1). Dose equivalent from ground water is included in the 25 mrem/yr dose equivalent limit provided by this regulation. With one short-term exception, all sample analyses have met U. S. EPA primary drinking water standards, which are based on a 4 mrem/yr dose equivalent.

The investigation for non-radiological hazardous constituents in site ground water is based on guidance provided within Reference 2, the "Massachusetts Contingency Plan" (MCP) regulations under 310 CMR 40.00 for the release of oil or hazardous materials.

Those investigations are not addressed in this report.

1.1 General Site Description The YNPS was built in 1959-60, designed as a prototype to operate for 6 years, with a power level of 145 MW (later increased to 185 MW). In fact, YNPS operated for 32 years, safely and reliably producing low cost electric power.

Descriptions of the site, related to ground water investigations, are provided in this section.

1.1.1 Plant Location and Local Topography The YNPS plant site is located in northwestern Massachusetts in the town of Rowe, near the southern Vermont border (Figure 1). The developed area of the plant site encompasses approximately 12 acres at the northwest corner of a 2200-acre property owned by YAEC. Aside from electric transmission lines, the balance of the property area remains as undeveloped woodland.

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The YNPS site is at the east side of Berkshire Mountains situated on a portion of a river terrace on the east side of the Deerfield River. The terrace is recessed into and largely surrounded by high slopes of the river valley. In the vicinity of the plant, the sides of the river valley rise to over 1000 feet above the river elevation, creating a valley about 2 miles wide.

The YNPS plant is adjacent to Sherman Dam, owned by USGen New England, Inc., one of several dams along the Deerfield River used for hydroelectric power generation. This upper (northern) portion of the Deerfield River Valley is unique in Massachusetts for its steep topography (a product of alpine-type glacial erosion) thus providing good locations for hydroelectric generating facilities. The local gradient for this portion of the Deerfield River is quite steep at 28.4 ft/mi, as measured from the Vermont border to the gauging station at West Deerfield, Massachusetts, a distance of about 33 miles.

Sherman Pond, impounded behind Sherman Dam, has been the source of cooling water throughout plant operation. This pond is about 2 miles long, a quarter mile wide, and up to 75 feet deep along its central channel. The pond and river are directly downgradient of the site. Figure 1 provides a topographic map of the site area, showing these general features.

This report along with plant drawings and many descriptive reports base reference elevations on this arbitrary Sherman Dam datum. The Sherman Dam datum is 105.66 ft higher than mean sea level (msl) datum.

Key elevations for the site are based on the datum used for construction of Sherman Dam. These are approximately as follows:

Typical water elevation of Sherman Pond

+999 ft Deerfield River below Sherman Dam

+834 ft Ground surface at the plant site

+1014 to +1054 ft Unless otherwise noted, compass directions used to describe YNPS site locations in this report are based on a plant grid that has its north direction toward the Deerfield River, parallel to the sides of major plant structures. This grid-north direction is rotated 44.5 degrees counterclockwise from true north (Figure 2). This plant grid system is used on most original plant drawings and documents.

1.1.2 Plant Structures The YNPS consisted of 26 permanent structures and a number of separate outdoor components, especially system tanks. Figure 2 shows the location of all of these original and added structures. Structures removed as part of decommissioning are denoted with dotted lines in Figure 2.

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The plant's original Radiological Controlled Area (RCA) shown in Figure 2 represents a standard nuclear facility arrangement providing a restricted and controlled access and operations area where use and handling of radiological materials are permitted. "Summary of Excavation Volumes for YNPS Construction Projects Performed During the Time Period of Plant Operation" (Reference 3) provides a description of plant construction projects since the start of YNPS power generation. This is notable because construction included soil excavation inside the RCA for most projects. Excess soil from this work was generally placed elsewhere on the site. Radiological controls in effect at the time of these projects provided release criteria with lower thresholds than current requirements in effect for decommissioning Currently all radiological components and materials, with the exception of the spent fuel and associated support structures, have been removed from the site as part of decommissioning work. The fuel will eventually be moved to an onsite dry cask storage facility and remaining structures decommissioned.

2.0 SITE GEOLOGY Relevant site geologic data are described in detail in References 4 and 5. "YNPS Geology and Seismology" (Reference 4) is a licensing document prepared for the NRC's Systematic Evaluation Program to describe site and local geology and seismology in support of licensing of older nuclear power plants in 1979. Figures 3A, 3B, and 3C are a geologic map and two profiles taken from that document, respectively.

The document "Environmental Characterization Summary" (Reference 5) provides analysis of site characterization data collected through the year 1999. References 6, 7, 8, and 9 are the 1993-4, 1995, 1996, and 1997 "Annual Site Characterization Reports,"

respectively. These reports summarize YNPS site characterization information for those years and contain detailed data for specific characterization locations at the site where investigations were made, including soil boring information for many of the monitoring well locations.

2.1 Distribution and Character of Soil and Bedrock Units at the Site Soils at the site consist of three basic types (Figures 3A, 3B and 3C):

Fill outwash: silty sand and gravel outwash with some silt layers, generally 3 to 12 feet thick with original construction fill derived from sandy outwash and used for YNPS plant construction Till: dense, silty, sandy, gravelly bouldery glacial lodgment till, which includes some stiff clayey layers, with a total thickness of about 0 to 250 feet Ground moraine: thin till-like material present on valley slopes only Reference 4 indicates soil thickness is over 100 feet beneath the center of the plant site (Figures 3B and 3C). The thickest soil deposits are located in the Ground Water Data for YNPS Decommissioning Page 6 of 26 DESD-YR-02-O01 Rev. 1

southwest portion of the site. Soil is absent or nearly so just above the base of the valley slopes from near the northeast around to the southeast side of the site.

On the adjacent hillsides around the east, south, and west sides of the plant site, a thin layer of glacial till, essentially ground moraine, occurs intermittently over bedrock. Soil is absent and bedrock is exposed for a portion of the site just east of the RCA. A bedrock knob forms a topographic high between the site and Wheeler Brook (Figures 3A and 3C).

Close to the Deerfield River, soils include alluvial material consisting of sandy and gravelly sediment in and along the shorelines and silty sediment in the deeper sections of Sherman Pond. The contact between outwash and till or alluvium and till within the Deerfield River's south bank produces outflow of ground water as springs, as discussed in Section 3.0.

Prior to plant construction a stream flowed through the south side of the site from the hills at the southwest corner of the site to the Deerfield River, downstream of the dam. This appears to have fed the so-called "unnamed tributary" that receives water from the plant's west storm drain system. This stream is shown on an original plant construction drawing for site clearing (Reference 10).. Alluvial deposits, consisting of stream terrace sands and gravels with relatively higher permeability, appear to occur along the trace of this stream.

Sherman Dam is a large earth embankment that straddles the river at the north end of the YNPS site. It consists of various types of fill originally placed in 1927 and increased in height slightly in 1964.

Reference 4 also describes outwash as thinnest at the east margin of the site where bedrock crops out at the surface along the upper (south) portion of the site (Figure 3C). Near the center of the site where the bedrock surface is very deep, Reference 4 indicates that glacial till extends to depths of over 175 feet.

Investigation for a new potable water well in 1999 showed glacial till up to 250 feet deep at the southwest corner of the plant site. Original plant construction included the placement of fill beneath and in the immediate vicinity of buildings and under the yard area of the plant.

Bedrock at the site is part of the lower Cambrian Hoosac formation. It consists of metamorphic rock described as quartz-albite-biotite gneiss and rusty gneiss in adjacent areas. Underlying these are garnet schist and a layered gneiss with some dolomitic marble belonging to the lower Cambrian or older Cavendish Formation (Reference 4). Bedrock structure consists of a south-plunging anticline, the axis of which occurs just west of the site (Figure 3B).

Reference 4 describes bedrock at the site as generally hard, fresh, internally welded metamorphic rock, without significant subaerial or other weathering features. Bedrock fracturing is not a prominent structural element. Bedrock outcrops exhibit either no joints or minor discontinuous joint surfaces. Analysis of fracture patterns for 74 joints or joint sets and 5 minor fault surfaces in the site vicinity showed no anomalously preferred orientation of fractures. These studies also suggest the absence of any through-going zones of post-metamorphic faulting or shear that is these faults are not found associated with contemporary seismicity (Reference 4).

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2.2 Site Characteristics and Modifications Made by Construction Plant structures with deep foundations that penetrate or impinge on the saturated zone include the Primary Auxiliary Building, Fuel Pool, and Ion Exchange Pit (PAB/FP/IXP). The Ash Dewatering Pit in the Waste Building is also very close to the water table level. The PAB/FP/IXP foundations are also built into a natural slope, providing a very steep local ground water gradient. The significance of this configuration is discussed in Section 3 of this Report. Underground storage tanks that held non-radiological liquids, were removed at the outset of decommissioning activities. One radiological liquid storage tank location remains as an underground concrete vault (storing drainage from a radiological lab and other radiological areas of the Service Building), while another subsurface vault, mostly filled with concrete due to internal radiological contamination also remains at the site. These are designated as nos. 35 and 36 on Figure 2.

The "Overview and Status: Environmental Characterization, Yankee Nuclear Power Plant Site" (Reference 11) describes residual contamination from water leakage to soil under the Fuel Pool, Ion Exchange Pit, PCA radiological decontamination-tub drain, and Waste Building Ash Pit. Subsurface soil at these locations is yet to be fully evaluated or remediated. However, no significant effect on ground water is apparent based on existing YNPS characterization data. A full description of soil at these locations is provided in Reference 5.

3.0 SITE GEOHYDROLOGY Prior geologic studies and YNSD decommissioning site characterization data provide a fairly complete picture of shallow ground water conditions at the site. The major portion of the data comes from monitoring wells installed as part of site characterization (Figure 5). Shallow ground water at the site is contained in fill outwash and glacial till, soil types described in Section 2.1.

Shallow ground water occurs to some extent perched in shallow soils due to the relative impermeability of the underlying till. Along slopes where the contact between these soils is exposed, such as the banks of the Deerfield River, are small, perennial and intermittent natural springs. A perennial spring, called Sherman Spring has been formally monitored for radiological constituents over many years (see Section 4.1). A second spring emanates from the Deerfield River bank to the west of Sherman Spring above the roadway to the Sherman Dam powerhouse, downgradient of the old plant septic leaching field (Reference 7).

The shallow ground water depth at the south end of the RCA is about 3 to 7 feet, depending on local soil conditions, with surface ponding occurring in isolated areas. A wetland just south of the RCA fence line highlights this shallow ground water. At the north end of the site, toward the Deerfield River, ground water is 18 to 20 feet beneath the ground surface (Figure 4).

The site's ground water is recharged primarily by precipitation, which averages 47 inches/year at YNPS based on data in the "YNPS Environmental Report" (Reference 12). Surface runoff and shallow ground water flow from the surrounding hills are directed through the plant storm drain system, ultimately discharging to the Deerfield Ground Water Data for YNPS Decommissioning Page 8 of 26 DESD-YR-02-O01 Rev. 1

River. Since the elevation of the Deerfield River below Sherman Dam is approximately 100 feet lower than average plant grade, a fairly steep average water table gradient of 0.10 ft/ft exists across of the site. This contrasts with a very steep localized ground water surface gradient of 0.15 ft/ft at the PAB/FP/IXP area. This steep gradient is due to construction of these structures along a slope and the damming effect of the deep foundations of these structures, which are extended into the glacial till.

Natural surface drainage in the YNPS site area is towards the Deerfield River and Sherman Pond. Like surface water flow, ground water flow was initially assumed to be directed toward the Deerfield River based on this practical assumption. These data can be compared to ground water elevations in wells as represented by Figure 4, described in Section 3.1. In Addition, leakage of tritium (H-3) from the plant's Fuel Pool and Ion Exchange Pit early in the plant's history in the "Yankee Nuclear Power Station Decommissioning Plan" (Appendix B of Reference 13) has provided a direct method (solubility of H-3 is not an issue) for tracing ground water movement, providing confirmation of the flow direction based on well known methods (References 14, p. 427, 15 and 16).

Ground water from surficial materials has not been used for drinking water at or nearby the site, nor is it a source of water for any purpose in the area of the plant (Reference 17, Section 3.4.2). The Deerfield River is not used for a source of drinking water downstream of the plant. The closest municipal water supply downstream of the plant is over 20 miles distant (Reference 17, Section 305). The site's potable water well, drilled into bedrock, serves as a source of drinking water for the plant. This state-licensed well is located approximately 450 feet southwest of the main plant buildings in the upgradient ground-water flow direction (Figure 2). Bedrock in the region is not a significant source of water supply, and no major ground water aquifers occur within the site area (Reference 17, Section 302).

3.1 Ground Water Table Elevations Figure 4 is a ground water contour map based on average levels of water in site monitoring wells from data compiled over the years of plant decommissioning work. Also considered were:

Topography (elevations rise sharply to the south, east and west) and toward the crest of Sherman Dam, and The shape of contour at elevation 1035 near the ISFSI structure is inferred based on the installation of a foundation drain and structural fill placed at that location per the "ISFSI Site Grading Plan" (Reference 18).

Ground water flow can be assumed to be directed perpendicular to these contour lines. Thus, in general, Figure 4 shows that ground water flow is directed towards the river, and for a small area at the northeast corner of the site, toward Sherman Pond.

3.2 Ground Water in Bedrock Ground water in bedrock has provided potable water for the plant site from two wells over the course of plant operations and decommissioning. Locations of Ground Water Data for YNPS Decommissioning Page 9 of 26 DESD-YR-02-O01 Rev. 1

both wells are shown as features 41 and 42 on Figure 2. The first plant water well, drilled in 1958 to a depth of 437 feet and with a diameter of 8 inches, had a safe yield of 5.7 gpm as documented in a report to the MA DEP (Reference 19).

Such a low yield is consistent with regional observations of yields from crystalline rock (Reference 20). That first well was decommissioned in December 1999 and grouted due to its proximity to the planned location for the YNPS ISFSI.

Stratigraphy at that location was estimated to consist of:

Unit Depths Sand and gravel fill 0-5 ft Silt and fine-grained sand outwash 5-12 ft Glacial till 12-100 ft Bedrock: Hoosac Gneiss 100-437 ft A new well was drilled in 1999 at the southwest corner of the site to a depth of 280 feet. The well was determined to have the following stratigraphy during drilling:

Unit Depths Sand and gravel outwash 0-15 ft Glacial till 15-250 ft Bedrock: Hoosac Gneiss 250-280 ft Yield estimated at the time of drilling was 60 gpm. This high yield is attributable to the well location, which was chosen based on standard geologic exploration principles:

Bedrock is deep (and consequently glacial till cover thick) and A coincident topographic inflexion line for both ground surface and bedrock surface topography occurs, and Location is along the trend of a surface drainage feature, coincident with a recognizable fracture trend in the bedrock and surface topographic and drainage lineaments Another 6-inch diameter bedrock well, 408 feet deep at the Plant's Visitor's Center, about 1/2 mile west of the site has a yield of about 8 gpm per its "1995 Annual Statistical Report" (Reference 21).

Two site monitoring wells, B-1 and CW-1 0 penetrate bedrock. The typical level of ground water in Well B-i, which has a screen that straddles the till and bedrock, is generally about 10 feet lower than that for CB-1, which is only 60 feet away and is screened in the fill-outwash. This condition demonstrates how the relative impermeability of the till perches ground water.

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4.0 GROUND WATER CHARACTERIZATION METHODS 4.1 Approach for YNPS With basic plant site geology fairly well documented in licensing plant studies and documents, the initial phase (scoping) location of monitoring wells was based on site history of spills and leaks (Reference 13, Appendix B). Some wells, installed subsequently, were located to help define a tritium (H-3) plume flow.

Based on many years of YNPS Radiological Environmental Monitoring Program (REMP) ground water analyses for radioactivity reported in the original YNPS D-Plan (Section 3 of Reference 13) it was clear that H-3 was present in the ground water at the site. Tritium acted as a tracer faithfully tracking ground water flow and provided an additional means to assess the suitability of monitoring well locations.

All pertinent descriptive information for each well and the basis for their locations are summarized in Table 1. Table 2 is a summary collection of all analyses done for characterization of ground water based on a database described in Section 5.3. A site plan showing all monitoring wells is in Figure 5.

Installed in 1993, monitoring wells, CB-1, -2, -3, -4 and CW-1, -2, -3, -4, -5, and -

6 were located just downgradient of historic spill or leak locations. At locations where there was some possibility of subsurface soil contamination, soil samples were taken and analyzed as wells were installed (wells prefixed "CB").

Analyses for H-3 from wells installed in 1993, along with REMP results for Sherman Spring (Attachment 1), provide a reasonable definition for ground water flow direction. They also served as a basis to help locate monitoring wells, CB-6,

-8, -9, CW-7, and -8, installed in 1994 to further defined general ground water flow and the H-3 plume at the site. Other monitoring wells installed upgradient or cross-gradient of the PAB/FS/IXP complex, CB-5, -7, -8, -10, -12, and CW-10 were located at places where warranted by soil conditions or site history.

4.2 Prior Determination of Analytes of Concern, Surrogates Reference 5 addressed the historical analytes of concern for site environmental characterization based largely on soil sampling data. It describes the radiological analytes of concern and for all environmental media (soil, sediment, and ground water) at the site as follows, with analytical techniques noted:

Symbol Radionuclide Analytical Technique H-3 Tritium Liquid Scintillation Counting Mn-54 Manganese 54 Gamma Spectroscopy Co-60 Cobalt 60 Gamma Spectroscopy

" Sr-90 Strontium 90 Radiochemical Separation Ag-1 08m Silver 108 metastable Gamma Spectroscopy

• Cs-134 Cesium 134 Gamma Spectroscopy

• Cs-1 37 Cesium 137 Gamma Spectroscopy Ground Water Data for YNPS Decommissioning Page 11 of 26 DESD-YR-02-O01 Rev. 1

Other radionuclides that could have been released into the environment from YNPS are transuranics, alpha-emitting radionuclides with atomic numbers greater than 92 and with half-lives greater than 20 years. These include neptunium, plutonium, americium, and curium.

No significant testing was performed for these analytes because:

The lack of evidence for their presence in characterization soil samples at the site (Appendix 6 of Reference 7)

Their very low transport rates in soils such as exist at YNPS Knowledge based on records/results of RP surveys, effluent sample analyses and radiological waste characterization analyses The use of gamma-emitting radionuclides Co-60 with Cs-1 37 as surrogates No detectable levels of these nuclides found in characterization soil samples containing the highest levels of gamma-emitting radioactivity (Appendix 6 of Reference 7)

Sr-90 was not originally considered to be a likely concern for ground water characterization. Recent interest in this radionuclide in ground water at other decommissioning plants has caused YNPS to consider a second look at the results for this analyte in YNPS ground water. Two rounds of analyses of well samples for Sr-90 are described in Section 6.3.3 of this report.

4.3 Investigation Methods: Procedures and Plans The YNPS Site Characterization process was planned and constructed based on the YNPS Plant Procedure "Administrative Program for Radiological Characterization Surveys to Support YNPS Decommissioning Planning,"

(Reference 22). Monitoring well installation was done using YNPS Plant Procedure, "Subsurface Soil Sampling and Monitoring Well Installation" (Reference 23). That procedure provided installation direction and documentation and allowed for soil samples to be taken during well installation, where needed. Wells were designed consistent with Massachusetts Department of Environmental Protection (MA DEP) guidelines for monitoring wells as recommended in MA DEP "Standard References for Monitoring Wells" (Reference 24).

Sketches showing the configuration of each well are included in Attachment 2.

Well development (preparation for initial sampling) was accomplished by pumping multiple well volumes (screen as well as filter pack volume) from each with pumping continued until satisfactory water clarity was obtained.

Ground water samples are obtained using YNPS Plant Procedure "Ground Water Level Measurement and Sample Collection in Observation Wells" (Reference 25) with transport to offsite labs performed in accordance with the YNPS Plant Procedure "Sample Chain of Custody" (Reference 26). Ground water samples were initially obtained from wells using bailers or a peristaltic sump. Where dedicated equipment was not used, care was taken to insure decontamination of samplers between wells. Sample acidification and filtration as needed were initially done in the laboratory but eventually these steps were provided in the field.

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The Framatome ANP DE&S Environmental Laboratory (FDESEL) typically performed analyses but the YNPS plant laboratory also performed some analyses. Analyses were done using standard environmental Minimum Detectable Concentrations (MDCs) based on the YNPS Offsite Dose Calculation Manual as guidance. For H-3, the analysis method was distillation with the distillate subject to liquid scintillation counting (Reference 27). Gamma spectroscopy analyses were performed using a shielded high purity germanium detector (Reference 28). Strontium analyses were performed using the Cerenkov method (Reference 29).

As a minimum initial survey for each well, samples were typically obtained at least quarterly for a year. Analyses included H-3 liquid scintillation counting and gamma spectroscopy.

CB-1 1A was installed in the PAB following detection of H-3 insamples from standing water exposed during concrete floor removal in that building.

Subsequent samples from that well revealed elevated H-3 concentrations in a highly localized zone. Several new monitoring wells were placed in the vicinity of that well to assure that any significant related information was uncovered.

Results of these investigations are discussed in section 6.3.1.

Soil permeability conditions were evaluated using YNPS Plant Procedure, "Field Permeability Data Collection in Observation Wells" (Reference 30). "YR Ground Water Model-Permeability and K-Summary" (Reference 31) an informal, unverified calculation, provided permeability estimates based on the field data.

The YNPS Plant "Procedure for Permanent Closure of Monitoring Wells" (Reference 32) was used to insure the safe and complete decommissioning of wells when monitoring is no longer needed. To date, five wells (shaded entries in Table 1) have been grouted for various reasons, using this procedure.

All pertinent radiological data collected for environmental characterization are documented in a database provided by YNPS Plant Procedure, "Site Characterization Environmental Radiological Database" (Reference 33).

4.4 Background Considerations Background levels of plant-related radionuclides in ground water are generally very low, well below any drinking water standards for ground water (Reference 34 p. 137-9 and Reference 35 p. 6.40). For example naturally occurring H-3 typically occurs in ground water at levels less than 10 pCi/L; slightly higher levels may occur where atmospheric weapons testing has impacted ground water (Reference 36). However, this level is not only well below drinking water standards (20,000 pCi/L), but is also below typical environmental level MDCs for H-3, which ranges from about 350 to 2000 pCi/L. Other radiological analytes of concern are expected to have even lower presence in background.

5.0

SUMMARY

OF CHARACTERIZATION GROUND WATER INVESTIGATIONS References 5 and 11 provide summaries of all radiological and non-radiological site characterization data collected through 1999. Ground water data collected Ground Water Data for YNPS Decommissioning Page 13 of 26 DESD-YR-02-O01 Rev. 1

since that time is compiled in a site characterization database per requirements of Reference 33. A summary of H-3 plume data was presented in a recent memo entitled, "H-3 Concentrations in YNPS Site Ground Water" (Reference 37).

General radiological sampling activities for ground water were last assessed in mid-1 998 (Reference 38). Reference 5, Environmental Characterization Summary describes the radiological analytes of concern for all environmental media at the site as described in Section 4.2.

With the exception of H-3, the analytes of concern listed in Section 4.4 generally have relatively low solubility in water. It is possible for them to migrate through soil when driven by water flow, but such migration is greatly inhibited by their physical state, atomic sizes, as well as the ionically charged nature of the soil column and radionuclide. Consequently, movement of these radionuclides through soil occurs very slowly or not at all when water sources (regular rainfall, or continuous leakage, e.g.) to carry them are not available. This is supported by the relatively high soil-liquid partition coefficients estimated for them by Reference 39. Thus with the exception of H-3, radionuclides inadvertently released to soils tend to remain very close to the source. This anticipated condition has been found to be the case for every instance of radioactivity investigated in YNPS site soils.

An example of this is provided in Appendix 10 of Reference 6 (Included as ). Investigations were performed at three YNPS locations where soil radioactivity was found to be the highest in surface soils:

Beside the Waste Holdup Tank Moat, In the radiological storage area north of the Old PCA, and Under the Vapor Container Hand excavation of surface soil beneath asphalt revealed very consistent profiles of diminishing radioactivity within a depth of less than 18 inches. The soil sampled is representative of the fill-outwash at the site. Pavement was added in the latter two areas in the mid-1 980s. H-3 behaves very differently compared to gamma-emitting radionuclides. H-3 moves through soils with ground water.

Historic water leakage from the Ion Exchange Pit (repaired in 1966) and the Spent Fuel Pool (prior to its lining in 1979) has introduced H-3 to the ground water at the site. The extent of this leakage is discussed and summarized in Reference 13, and the "YNPS Site Radiological Environmental History Supplement" (Reference 40). Table 2 contains a summary of H-3 values from all samples taken from wells since initiation of monitoring.

Gamma-emitting radionuclides were detected in a very few well samples, generally in samples that were not filtered. Retesting of those samples after filtration, a standard field/lab practice for ground water samples, confirmed that radioactivity was in sediment in the samples and not dissolved in the water. This implies that while there is some radioactivity at depth in soils,-these components resist dissolving in water. This is consistent with behavior the expected due to high permeability coefficients (Kd) values. Table 2 contains a summary of all detected gamma-emitting radionuclide values from all samples taken from wells since initiation of monitoring. A description of that data is provided in Section 6.3.2.

Ground Water Data for YNPS Decommissioning Page 14 of 26 DESD-YR-02-O01 Rev. 1

5.1 Well Design and Locations Figure 5 shows all site well locations and Attachment 2 contains construction sketches of all monitoring well installations. These sketches show well ground elevations, well and screen diameters, depths, materials, stratigraphic summaries, sand filter packs and bentonite seals, installation dates, drilling contractors, design engineers, and initial ground water depths.

Table 1 summarizes all information relevant to the monitoring wells including:

Date installed/grouted 0

Surface elevation Well depth Typical ground water depth Responsible engineer Well location Basis for the location of the well Characterization results summary Grid location 5.2 References and Data A number of documents were produced to address ground water monitoring results for YNPS site characterization. Key references include formally issued reports and documents in several categories as well as outside references:

The original Decommissioning Plan submitted in 1993 0 Annual Site Characterization data reports YNPS Plant Procedures used for characterization work 0 Topical reports and technical memoranda by DE&S and others Licensing documents: YNPS Final Safety Analysis Report, YNPS Environmental Report, the original License Termination Plan draft, and the SEP submittal on site geology External references on geology and geohydrology of the area There also exists a quantity of characterization data collected but for which assessment is not documented. This information is addressed in this report, as follows:

YNPS Site Characterization Database. A periodically updated, verified and validated (V&V) database of all radiological analyses done for site characterization, plant procedure DP-8600 provides for this data catalog.

Copies of the database have been provided to YNPS as new data are entered. Data are V&V through 1999. Outstanding data packages (6/01 and 12/01) have been provided to YAEC for validation check per Reference 33.

Ground Water Data for YNPS Decommissioning Page 15 of 26 DESD-YR-02-O01 Rev. 1

" A round of 1994 gross alpha and gross beta results from 12 monitoring wells.

Two rounds (1997 and 1998: 20 and 23 wells) of Sr-90 results and one round (1997: 20 wells) of Sr-89 results from monitoring wells.

Graphs of ground water depths/elevation data collected during monitoring of wells. Presented in the annual Site Characterization Annual Reports, References 6, 7, 8, and 9, these graphs have not been updated since 1998.

More recent data are included in this report in Attachment 4.

Graphs of H-3 data from the time of initiation of site monitoring in 1993.

Presented in the annual Site Characterization Annual Reports, References 6, 7, 8, and 9, these graphs have not been updated since 1999. Newer data are included in this report in Attachment 1.

YNPS REMP data for ground water samples from Sherman Spring and the site potable water well. Collected and compiled from FDESEL results, these data provide baseline information starting in 1978 to support site characterization ground water studies. Data for H-3 in Sherman Spring samples are represented in the graph in Attachment 1. No other significant detectable levels of radionuclides have been found in either Sherman Spring or in samples from the site potable water wells.

A single round of Sr-89 and Sr-90 analyses was done for 20 monitoring well samples in late 1997 and a single round of Sr-90 analyses were done for 23 YNPS monitoring well samples in early 1998. The data were not formally presented in a report. Results show no detectable Sr-90 or Sr-89 in ground water samples. MDCs for the samples were less than 20% of the U.S. EPA drinking water limits.

A single round of gross alpha and gross beta analyses was done for the 12 existing monitoring wells at YNPS in 1993. Gross beta data were presented in the original D-Plan (Reference 13, Section 3) but gross alpha data were not formally presented. Samples were unfiltered and results show no detectable gross alpha levels for samples from 12 wells. Gross beta levels were within typical background levels for environmental samples.

5.3 Analytical Data Reference 33 provides a means to formally compile, store and provide data excerpts for evaluation or analysis. The database consists of a catalog that includes all the pertinent data from sample analyses, recorded in a way that provides V&V information and ready access. Attachment 6 contains a list of the data provided in the database for each sample. Input of information has been handled both electronically and manually from lab data sheets. Currently the ground water data has 2 sets of data ready for inclusion, pending V&V completion. The V&V status of data is noted in the last column of Table 2 where, per Reference 33, a single V identifies data that is verified; VV identifies verified and validated data; X represents invalid data; and no designation represents data not yet V&Vd.

Ground Water Data for YNPS Decommissioning Page 16 of 26 DESD-YR-02-O01 Rev. 1

6.0 SITE CHARACTERIZATION RESULTS 6.1 Water Level Measurements Graphs representing ground water depths for all monitoring wells are included in. Most wells show minor seasonal fluctuations in ground water levels, as demonstrated by the data plots in Attachment 4.

Figure 4 is a ground water table hand-drawn contour based on average levels of water in site monitoring wells from data compiled over the years of plant decommissioning work. The contours show the general flow direction of ground water toward the river and Sherman Pond.

6.2 Well Development Well development was provided based on a procedure that included the initial use of driller's equipment when wells were constructed, and pumping prior to initial sampling. Well development (preparation for initial sampling) was accomplished by pumping 2 to 3 well volumes (volume of the casing as well as filter pack) from each with pumping continued until optimal water clarity was obtained.

6.3 Sample Analysis Results Radiological analytical results for site characterization ground water samples are presented in Table 2.

6.3.1 Tritium Tritium (H-3) has had a constant, though generally decreasing low-level presence in wells. These data are represented in graphical form in. The graphs show filled and open symbols to denote detectable and non-detectable (<MDC) levels, respectively. Results for wells with persistent H-3 levels are:

B-i, CB-1, -2, -6, -9, -10, -11 A, CW-11, MW-1, 2, MW-3 and its replacement, MW-5.

A few wells have had H-3 detectable intermittently in samples:

CW-7, -8 Most wells had no detectable H-3 in their samples:

CB-3, -4, -5, -7, -8, -12, CW-1, -2, -4, -5, -6, -7, -8, -9, -10, MW-6, OSR-1, NSR-1, CFW-1, -2, -3, -4, -5, -6 With the possible exception of CB-10, H-3 concentrations have trended down due partly to natural dilution and attenuation.

Decreasing H-3 Ground Water Data for YNPS Decommissioning Page 17 of 26 DESD-YR-02-O01 Rev. 1

levels in the Fuel Pool since the start of decommissioning are also a likely contributor to this trend (see Section 6.3.4).

The results from monitoring wells define a plume for the site as illustrated in Figures 6 and 7. These show:

The relatively low concentrations of H-3 insite ground water (almost all below the U. S. EPA drinking water standard of 20,000 pCi/L)

The rapid dilution of H-3 concentrations with movement toward the river, and The significant decrease of H-3 concentration with time The single exception to these conditions is the presence of elevated concentrations of H-3 in wells CB-1 1A, CW-11, MW-2 and MW-3 between early 1998 and late 1999. This appears to be a consequence of leakage from beneath the PAB, which occurred in the course of decommissioning work. Reference 41 is a memo that addressed the situation at the time.

Initial samples from well CB-1 1A, installed (12/18/97) inside the PAB through its concrete foundation mat, contained H-3 at levels near 80,000 pCi/L. In addition, this well exhibited an artesian condition with water flowing from the hole at a rate of 1/2/2 to 3/4 gpm. The initial water level was about 2 to 3 inches above the top of the concrete foundation slab of the PAB cubicle corridor pipe trench. This condition supports the belief that the foundation of the PAB along with those of the Ion Exchange Pit and the Fuel Pool, all deep structures extending beneath the ground water table and into the top of glacial till, are providing a "dam" impeding flow of ground water from beneath the PAB. Dewatering of the PAB to facilitate building cleanup effectively removed a very large percentage of the trapped ground water. The result was an effective remediation of the tritium. Water produced by this process was collected and processed through the plant evaporator and released to surface drainage in keeping with regulatory release permits. The consequences of residual concentrations of H-3 in the ground water beneath the PAB were investigated by installation of several new and existing wells, as described below.

Soil samples taken during installation of CB-11 A contained very low levels of gamma-emitting radioactivity. Ground water samples from CB-11 A have contained no detectable gamma-emitting radionuclides.

Additional monitoring wells were installed downgradient (MW-2 and MW-

3) and upgradient (MW-1) of this location in early April 1998. These new wells supplemented existing downgradient wells CB-1, -2, -6, and CB-9.

During the period between early 1998 and early 2000, samples from downgradient wells showed some increase in H-3 levels compared with prior results. These data is illustrated for the two closest wells, CW-11 and MW-2 in Figure 8 and in graphs for wells in Attachment 2. After early 2000 the trend of decreasing H-3 resumed for downgradient wells.

The H-3 plume maps in Figures 6 and 7 provide a comparison of H-3 concentrations in the vicinity of the PAB for yearsl 999 and 2000. These Ground Water Data for YNPS Decommissioning Page 18 of 26 DESD-YR-02-O01 Rev. 1

show that H-3 concentrations decrease rapidly downgradient of the PAB.

In Figure 6, for example, maximum H-3 1999 concentrations were as listed in Table 4.

Table 4. Maximum 1999 H-3 Concentrations Well Downgradient Maximum 1999 H-3 Distance from Concentration, pCi/L CW-11 MW-5 30 5610 CB-9 75 4010 CB-2 350 1280 CB-6 500 666 Figure 7 shows that by the year 2001 the highest H-3 concentration in any of the wells was just over 4000 pCi/L in MW-5.

6.3.2 Gamma-Emitting Radionuclides in Ground Water Samples Routine tests for gamma-emitting radionuclides have been done for all site monitoring wells. Samples that were found to have detectable levels are highlighted in Table 2. This includes eight samples from CB-1 (and two reanalyses of those samples), and one sample each from wells CB-6, CW-5 and MW-3. Almost all of these have been in unfiltered samples.

Detected levels in all samples are all well below U. S. EPA Drinking Water Standards levels (based on a 4 mrem/yr dose equivalent).

Follow-up samples or results from filtering of samples have shown that the radioactivity in CB-1 samples appears to have been in suspended particulate matter in samples, and not dissolved in the water itself. Since field filtration of samples was initiated in 1996, no samples from that well have contained detectable levels of gamma-emitting radionuclides.

Single samples from wells CW-5 (unfiltered) and MW-3 (filtered) contain detectable Co-60 and Cs-1 34, respectively. In both cases concentrations were very low and no subsequent samples from those wells contained gamma-emitting radionuclides above MDC levels. During the sampling episode for the CW-5 sample demineralized water used for decontamination of sampling equipment was found to contain gamma-emitting radioactivity and that is the suspected source for that sample.

The sample from well CB-6, filtered in the lab, retested with no detectable gamma activity.

Fifteen samples from seven wells taken in early March 1999 were found to be contaminated by Co-60 due to field and/or laboratory error.

Subsequent resampling of these wells provided Co-60 results below detectable levels (Reference 42).

Ground Water Data for YNPS Decommissioning Page 19 of 26 DESD-YR-02-O01 Rev. 1

6.3.3 Gross Alpha, Gross Beta and Sr-90 Analyses As discussed in Section 4.2 testing of ground water for gross alpha, gross beta, strontium and transuranics has not been a major component of YNPS site characterization. Data were collected at the outset of the project in 1993 for gross alpha and gross beta (Table 3). Strontium analyses were done for two sets of samples (Table 2).

Samples from 12 wells were analyzed for gross beta as both unfiltered and filtered through a 40-micron screen (Table 3). Results for both filtered and unfiltered samples showed detectable gross beta in all samples with levels consistent with those found in ground water for samples in YNPS REMP analyses, that is detectable but low (based on U. S. EPA criteria discussed below) levels of gross beta. The U.S. EPA defines a gross beta screening level for "vulnerable" locations (such as near a nuclear facility) at 50 pCi/L. All results for filtered samples and all but two results from filtered samples were well below that threshold. The two unfiltered samples that exceeded that guideline, from CB-3 and CW-4, had values of 74 and 79 pCi/L, respectively. Subsequent filtering and reanalysis of these samples resulted in concentrations of 5.20 and 1.70 pCi/L for CB-3 and CW-4, respectively. Thus the high values for the unfiltered samples are attributable to radioactivity in the suspended fraction of the sample and thus not contributing to internal dose. Most if not all gross beta in these samples is likely to be attributable to naturally-occurring radioactivity.

Samples from 12 wells were analyzed for gross alpha with all samples filtered prior to analysis. All sample results were less than detectable levels (<MDC). The MDC for those analyses was generally between 1 and 4 pCi/L, sufficient to analyze against the U. S. EPA drinking water standard of 15 pCi/L.

Sr-90 analyses were done for 20 wells in 1997 and 24 wells in 1998. The 1997 work included analyses for Sr-89 as well. None of the samples showed detectable levels of either nuclide. MDC values were all below the U. S. EPA drinking water standards of 8 and 20 pCi/L for Sr-90 and Sr-89, respectively (based on a 4 mrem/yr dose equivalent).

6.3.4 Spent Fuel Pool (SFP) Leakage "YNPS Condition Report CR 1999-036" was issued on 5/17/99 (Reference 43) and addressed leakage from the upgradient Spent Fuel Pool (SFP) wall into the Ion Exchange Pit (IXP). The CR was prompted by analysis of standing water in the Ion Exchange Pit, which contained H-3 at a concentration of 50,000 pCi/L. Subsequent inspections and analyses of standing water from IXP provided information confirming that the leak to the IXP was less than 10 gallons per year. H-3 concentrations in water on the IXP floor, sump and in upgradient well CB-10 showed decreasing concentrations based on data reported in YNPS memoranda (References 44 through 48).

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A chart showing the average concentration of H-3 in SFP water was included with these references and is included in this report as. This graph shows a significant decrease in H-3 concentration from 1/97 to 12/98 due mostly to evaporation (approximately 90% of the decrease) and the balance to H-3 decay (approximately 10% of the decrease). The significance of this condition to ground water monitoring is high. First, if there is leakage from the SFP to the IXP, there appears to be a reasonable likelihood that leakage occurs through the floor, the other walls and/or the joints between them.

Thus, it seems likely that leakage from the SFP is the source of H-3 found in ground water monitoring wells. The general decreasing levels of H-3 in wells like CB-1, -9, -2, and -6, and B-1 would appear to be consistent with a decreasing source term like the SFP water.

A "blister" (water penetration) in the New Fuel Vault was noted as a leakage location. A water sample taken at the blister contained low levels of Co-60, Cs-1 34 and Cs-1 37. It was indicated that the Cs-1 34/Cs-1 37 ratio, compared to that of the SFP water, suggested a 4-year migration-rate through the SFP wall (Reference 48).

Removal of the fuel from the SFP in the near future will allow it to be drained. Levels of H-3 in ground water should then reflect the extent to which the SFP is the source of H-3 insite ground water.

6.4 Well Closures Five YNPS monitoring wells have been closed since the start of monitoring.

These are noted with shading in Table 1. Closure was accomplished in keeping with Reference 32. The procedure is based on Reference 24. The wells closed are as shown in Table 5.

Table 5. Well Closure History Well No.

Date Closed Reason for Closure B-3 2-Jan-97 Well used for prior geotechnical investigation was small diameter and difficult to sample, replaced with CB-3 CW-1 7-Jul-00 Replaced by CW-9 to confirm isolated contamination with paint chips CW-9 7-Jul-00 Replaced with MW-6 to confirm isolated contamination with paint chips MW-3 7-Jul-00 Bent casing made sampling difficult, results from adjacent well, MW-2, appeared more conservative NSR-1 7-Jul-00 Offsite location: non-radiological investigation completed Ground Water Data for YNPS Decommissioning DESD-YR-02-O01 Rev. 1 Page 21 of 26

6.5 Site Ground Water Conditions Summary This section presents a review and evaluation of conditions at the YNPS site relevant to ground water. It addresses the three potentially water-bearing units:

fill outwash, glacial till and bedrock and their measured or inferred water transmitting and water bearing properties, and their potential for radionuclide transport. Key properties of the geohydrologic units at the site are estimated as shown in Table 6 based on study done for site characterization (Reference 31) and estimated done using site geotechnical data.

Unit Thicknesses and Lateral Extent The thicknesses of key geologic units related to ground water at the YNPS site are as follows:

Fill-Outwash 3-12 feet 6.5.1 Glacial Till 0-250 feet The limits of the fill-outwash and the till are generally defined by site topography as shown in Figures 3A and 3B.

6.5.2 Water-Transmitting Properties: Estimated Coefficients of Permeability Values for coefficients of permeability for site soils were obtained in two ways: 1) estimates based on soil description using a standard chart and 2) based on computations using field testing results. Table 6 shows these data.

Table 6. Properties of Geohydrologic Units at the Site Unit Description Silt and Estimated Computed Clay Permeability Permeability Fill Silty sand and 5-25%

5.0 x 10-1 to 2.5 x 101 to outwash gravel with some silt; 5% or 1.0 x 101 4.6 x 101 (sandy silt layers, 3 to less clay g/d/ft2 g/d/ft2

portion, 12 feet thick.

(Equivalent (Equivalent excludes Original plant to 2.0 x 10-2 to 1.0 x 100 silt layer) construction fill to 4.0 x 10-1 to 1.8 x 100 was derived from m/d) m/d) sandy outwash Glacial till Dense, silty, 30% to 1.0 X 10-3 to 5.0 x 10-2 to sandy, gravelly 40% silt, 1.0 x 101 4.0 x 100 bouldery glacial 8% to g/d/ft2 g/d/ft2 lodgment till, 20% clay (Equivalent (Equivalent which includes to 4.0 x 10.5 2.0 x 10-3 to some stiff clayey to 4.0 x 10-3 1.6 x 10-1 layers (till), from m/d) m/d) 0 to about 250 feet Ground Water Data for YNPS Decommissioning DESD-YR-02-O01 Rev. 1 Page 22 of 26

Table 6. Properties of Geohydrologic Units at the Site, continued Bedrock Quartz-albite-Estimates 1.0 X 10-7 to No measure-biotite gneiss based on 1.0 x 10-ments made and a rusty low yields g/d/ft2 gneiss, generally for drilled (Equivalent hard, fresh, low wells 4.0 x 10-9 to fracture 4.0 x 10-7 frequency m/d) metamorphic rock, and without significant weathering Estimated permeabilities were based on grain size distribution data from References 49 and 50, geotechnical studies done for the YNPS site and site characterization data. Key properties of the various units are noted in Table 6, in particular the abundance of fines (silt and clay) in soils and fracture frequency in the bedrock. Permeability of the fill-outwash soil is estimated to be moderate.

Till and bedrock permeabilities are both estimated to be low. These data were used to make estimates based on a standard chart describing permeabilities for the range soil and rock deposits in Reference 14 p. 29.

Specific ground water inputs to RESRAD (Reference 51) were presented for the YNPS site in Reference 52 with some revisions provided in Reference 53. These are the results of site-specific judgments made by personnel familiar with characterization data and these dose codes. Those data represent one of the principal products of site characterization work.

6.5.3 Recharge and Discharge Ground water recharge for the YNPS site is described in Section 3.0. It is provided by rainfall as well as by ground water flow from the steep hills adjacent to the site.

Ground water discharge from the site is to the Deerfield River surface water via springs or to underlying river deposits via ground water flow. Minimal ground water discharge occurs from the site soils to the underlying bedrock.

Ground Water Data for YNPS Decommissioning DESD-YR-02-O01 Rev. 1 Page 23 of 26

7.0 REFERENCES

1. "Radiological Criteria for License Termination: Radiological Criteria for Unrestricted Use," 10CFR20.1402, 1/1/01.

2. "The Massachusetts Contingency Plan" (MCP), 310 CMR 40.0000, Massachusetts Department of Environmental Protection, Bureau of Waste Site Cleanup, October 29, 1999.

3. "Summary of Excavation Volumes for YNPS Construction Projects Performed During the Time Period of Plant Operation," Memo to: E. Cumming from F. Bellini ESG 97-082, 2/27/98.

4. "Geology and Seismology Yankee Rowe Nuclear Power Plant," Prepared for Yankee Atomic Electric Company, Weston Geophysical, 1979, Docket No. 50-29, 67p.

5. "Environmental Characterization Summary," Yankee Nuclear Power' Plant Site, DE&S, June 2000.

6. "Summary Report of Site Characterization Activities (1993-4)," Environmental Engineering Department, September 1995, YAEC-1924.

7. "Summary Report of Site Characterization Activities (1995)", Environmental Engineering Department May, 1996, YAEC-1934.

8. "Summary Report of 1996 Site Characterization Activities," Environmental Engineering Department, October 1997, YAEC-1945.

9. "Summary Report of 1997 Site Characterization Activities," Environmental Engineering Department, August 1999.

10. "Site Clearing," YNPS Plant Drawing 9699-FY-1C, 8/22/57.

11. "Overview and Status: Environmental Characterization," Yankee Nuclear Power Plant Site, DE&S, Feb. 2000.

12. "YNPS Decommissioning Environmental Report," December 1993.

13. "Yankee Nuclear Power Station Decommissioning Plan," Revision: 0.0, Yankee Atomic Electric Co., 1993.

14. "Groundwater," R.A. Freeze and J. A. Cherry. Prentice-Hall, 1979.

15. "Isotope Tracers in Catchment Hydrology," Chapter 2, Fundamentals of Isotope Geochemistry, Carol Kendall and Eric A. Caldwell, 1998, Elsevier Science B.V.,

Amsterdam, 839 p.

16. "Introduction to Ground Water Tracers," Dept of Hydrology and Water Resources, University of Arizona for the U. S. EPA, EPA/600/2-05/022 March 1985.

17. "YNPS Final Safety Analysis Report," 1999.

18. "ISFSI Rough Site Grading and Earthwork, Plan," Sheet 1, YNPS Drawing ISFSI-FY-010, 3/23/00.

19. "Comprehensive Compliance Evaluation: Sanitary Survey Stage 1," Letter to Yankee Atomic Electric Co. from MA DEP, NYR 96-047, 4/24/96.

Ground Water Data for YNPS Decommissioning Page 24 of 26 DESD-YR-02-O01 Rev. 1

20. Ground Water Atlas Of The United States: Connecticut, Maine, Massachusetts, New Hampshire, New York, Rhode Island, Vermont, Crystalline-rock aquifers," HA 730-M, 1995.

21. Submittal of 1995 Annual Statistical Report," Letter to Massachusetts DEP Division of Water Supplies from W. J. Meyers, YNPS, BYR 96-055, 11/25/96.

22. "Administrative Program for Radiological Characterization Surveys to Support YNPS Decommissioning Planning," YNPS Procedure, AP-0831, Rev. No. 1.

23. "Subsurface Soil Sampling and Monitoring Well Installation," YNPS Procedure, OP-8122, Rev. No. 0, Issue Date, 4/93.

24. "Standard Reference for Monitoring Wells," Section 4.6, "Decommissioning of Monitoring Wells," Massachusetts Department of Environmental Protection, Publication WSC-310-91, November 1993.

25. "Ground Water Level Measurement and Sample Collection in Observation Wells,"

YNPS Procedure, DP-9745, Rev. No. 1, 9/96.

26. "Sample Chain of Custody," YNPS Procedure, DP-8123, Rev No. 8, 5/02.

27. "Determination of Tritium in Environmental and Bioassay Matrices," FDESEL Procedure No. 371, Rev 19, 1/25/02.

28. 'The Determination of Gamma-Ray Emitting Radionuclides In Environmental/Bioassay and Effluent/Waste Media," FDESEL Procedure.No. 450, Rev. 15, 2/21/00.

29. "The Determination of Sr-89, 90 in Environmental Media via Cerenkov Counting,"

FDESEL Procedure No.368, Rev. 10, 3/1/02.

30. "Field Permeability Data Collection in Observation Wells," YNPS Procedure, DP-9747 10/94.

31. "YR Ground Water Model-Permeability and K Summary," informal unverified calculation: F. X. Bellini and G. A. Harper, YNDS, February 1996.

32. "Procedure for Permanent Closure of Monitoring Wells at YNPS," YNPS Procedure, OP-8125.

33, "Site Characterization Environmental Radiological Database," YNPS Procedure, DP-8600, Rev 0, 5/00.

34, "Hydrogeology," S. N. Davis and R. J. M. DeWeist, John Wiley & Sons, Inc., 1966

35. "Handbook of Hydrology," D. R. Maidment (editor), McGraw-Hill, Inc., 1993.

36. "Determining Background Radiation Levels In Support of Decommissioning Nuclear Power Facilities": Contributing author: soil and ground water sampling plan designs and river sediment case studies, EPRI Report No. TR-1 003030, December 2001.

37. "H-3 Concentrations in YNPS Site Ground Water," Letter to K. W. Dow from Daniel L Magnarelli, DSF 2002-034, 2/19/02.

38, "Assessment of Ground Water Sampling Activities," Memo to E. M. Heath from F. X.

Bellini/D. R. Orlowski, ESG 98-061, 6/2/98.

39. "Default Soil Solid/Liquid Partition Coefficients, Kds, for Four Major Soil Types: A Compendium," M.I. Sheppard and D.H. Thibault, Health Physics. Oct 1990, v.59 (4),

p.471-482.

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40. "YNPS Site Radiological Environmental History: Supplemental Information," Memo to E. M. Heath from F. X. Bellini, ESG 98-100, 12/22/98.

41. "Evaluation of Tritium in Ground Water at YNPS PAB," Memo to E. M. Heath from F.

X. Bellini, ESG 98-045, 3/25/98.

42. "Co-60 results from 7 Ground Water Observation Wells for 3/99 and 5/99," Memo to E. M. Heath from F. X. Bellini, ESG 99-11, 6/10/99.

43. "Possible Spent Fuel Pool in-leakage to the Ion Exchange Pit," YNPS Condition Report CR-1 999-036, Issued: 5/24/99, Closed 2/7/00.

44. "CR-1999-036 - Possible Spent Fuel Water In-Leakage to the Ion Exchange Pit (5/18/99)," Memo to Management Review Team from J. Gedutis, CHM 99-012, 11/22/99.

45. "Reference CR-1999-036"' CHM 99-015," Memo to Rick Williams from J. Gedutis, 12/1/99.

46. "Ion Exchange Pit Inspection Report," Memo to Rick Williams from J. Gedutis, CHM 00-005, 5/17/00.

47. "Surveillance for Spent Fuel Pit Wall Leakage," Memo to Rick Williams from J.

Gedutis, CHM 01 -008, 6/14/01.

48. "Surveillance for Spent Fuel Pit Wall Leakage," Memo to Greg Babineau/Rick Williams from J. Gedutis, CHM 02-009, 5/12/02.

49. "Project Plan: Preliminary Geotechnical Studies for the Proposed Expansion of Spent Fuel Facility (Draft)," Dames & Moore, 1978. YAEC Microfilm # 1000010.

50. "Report on Foundation Investigation, Fire Water Tank, Rowe Atomic Plant, Rowe, MA," Geotechnical Engineers, Inc, 1980, Prepared for Yankee Atomic Electric Company, Docket No. 50-29.

51. "Manual for Implementing Residual Radioactivity Materials Guidelines Using RESRAD, Version 5.0," Yu, C., Zielen, A.J., Cheng, J.-J., Yuan, Y.C., Jones, L.C.,

LePoire, D.J., Wang, Y.Y., Loueiro, C.O., Gnanapragasam, E., Faillace, E., Wallo III A., Williams, W.A., and Peterson, H., September 1993, Environmental Assessment Division, Argonne National Laboratory.

52. "YNPS Soil and Ground Water Inputs for Dose Models," Memo to J. W. Bisson from F. X. Bellini, ESG 98-025, Rev. 1, 3/24/98.

53. "YNPS Soil and Ground Water Inputs for Dose Models," Memo to J. W. Bisson from F. X. Bellini, ESG 00-001, 1/20/00.

Ground Water Data for YNPS Decommissioning Page 26 of 26 DESD-YR-02-O01 Rev. 1

DESD-TD-YR-02-001 Rev. 1 Site Ground Water Data Collection for YNPS Decommissioning Page 1 of 11 Figures

M---

M-

-I MM m

Approximate Scale 4000 8000 1

1 0

meters L 12000 160oo 0

miles i 4.0 1

8.01 Figure 1. Site Location Map DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning Figures: Page 2 of I I

Site Structures and Area Designations Yankee Nuclear Power Station Legend (Dotted structures are removed)

1.

Abandoned Septic Leaching Field

2.

Operating Septic Leaching Field

3.

Sherman Dam Powerhouse (USGen)

4.

CW Discharge Structure

5.

CW Intake Pumphouse

6.

Gatehouse and Security Generator

7. Former Office Building

8.

Turbine Building

9.

Service Building

10. Stores Warehouse

11. Modular Office Building

12. Office Trailers

13. Office Building

14. Vapor Container

15. Decon Rooms (N.

& S.)

16. Spent Fuel Pool

17. New Fuel Vault

18. Diesel Generator Building

19. Safety Injection Building

20.

Primary Auxiliary Building

21.

Ion Exchange Pit

22.

Fuel Oil Tank

23.

Compactor Building

24. Waste Disposal Building

25. Tanks Area (ADD & WH Tanks)

26. Safe Shutdown Building

27. Fire Water Tank and Pumphouse

28.

PCA Warehouse

29. Old PCA Building (#I)

30. New PCA Building (#2)

31. Outdoor Rad Storage Areas

32.

ISFSI (Dry Fuel Storage)

33.

SE Construction Fill Area

34. Gas Drum Decay Area

35. Fuel Chute Lock Valve Access

36. Service Bldg. Drain Tank Pit

37. Former Clean-Side Incinerator

38.

Old (N.) and New (S.)

SI Tanks

39.

E&W Storm Drain Discharges

40. Circulating Water System Pipe

41.

Former Potable Water Well

42.

New Potable Water Well DESD-TD-YR-02-001 Rev. I Site Ground Water Data Collection for YNPS Decommissioning Figure 2 Figures: Page 3 of 11

=

M-i

=

M I

I, M

l, M

m m

-m OR Mm M

so DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning U

OUIU Approx. Scale Contour interval 6 meters Figures: Page 4 of 11I Figure 3A. Geologic Map See Figs 3B and 3C for profiles

IIIm mmM m

m N

A See Fig 3A for Location SITS SHERMAN DAM

-- 2000' 1500I 1000' 500' Northwest Ccg ICcsf Ch Southeast O' MSL GLACIAL SEDIMENTS h

HOOSAC ALBITE GNEISS h

HOOSAC RUSTY GNEISS c

CAVENDISH GARNET SCHIST

-cg--

CAVENDISH EVENLY-LAYERED GNEISS 0*

1000' I

2000' 3000' NO VERTICAL EXAGGERATION Site Locale Geologic Profile I

Figure 3B. Geologic Profile From Reference 4 DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning Figures: Page 5 of 11

-M m m

-ý M M m IM am

-s -n M, M -s M

See Fig 3A for Locations B Northwest 1 CONTAINMENT I Southeast B' 0

0.

-'0CN Ch

~'

~

>N'N

<.N N

K NXN' N

N, INortheast

.0*.

.j 0

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OUTWASH: BROWN SAND AND GRAVEL, SILT TILL: COMPACT, FINE, WITH GRAVEL AND BOULDERS VARVED CLAY-SILT: COMPACT, MINOR SAND SAND: FINE TO COARSE, VERY COMPACT BEDROCK t HOOSAC FORMATION, ALBITE GNEISS 0I.I.

50' 100' I

l 200' i

300' NO VERTICAL EXAGGERATION Site Locale Geologic Profiles Figure 3C.

Geologic Profiles from Reference 4 DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning Figures: Page 6 of 11

Yankee Nuclear Power Station CB-4 968 CO 0

Sherman Spring 997 0S I

S I

OCB-6 on Average Water Levels in for Well in Surficial Materials Grid NYi N(True) 4"44.5 Deg.

Elevations based on YNPS Plant/Sherman Dam Datum Estirmate Contours are Hand-Drawn E-stimates N-7 Ground Water Contour Based 9%5-

-t 1000 1000 1005 1010 0 C0 CW-6 1015

'"1007

-7 1026 0

\\

___1030 0000000001 0 5 o

oo00000000o 0

200 ft I

I SI Approx. Scale A040 OSR-1 0 1043 CB-5 1044 0

DESD-TD-YR-02-001 Rev. I Site Ground Water Data Collection for YNPS Decommissioning Figure 4 Figures: Page 7 of 1

- -,nI na m

I I_

m Plan of Monitoring Wells Yankee Nuclear Power Station Fall, 2001 Deer 0 C0-4 3

ShE Well No.

Location CB-1 NW of Fuel Pit CB-2 NW of Office Bldg CB-3 E of Fire Tk CB-4 Old Leaching Field CB-5 Misc Fill Area CB-6 Sherman Spring Area CB-7 PCA Warehouse at WDG wall CB-8 Storage Area behind old PCA CB-9 VC Equipment Hatch CB-10 IX Pit CB-11A PAB Cubicle Corridor Trench CB-12 WDB Ash Dewatering Pit B-1 NE side Fuel Bldg B-3*

NE side Fire Pumphouse CW-I*

NW of DG Bldg CW-2 NW of SI Tks CW-3 SE of Ion Exch Pit CW-4 NW of Plant Whse CW-5 SE of Service Bldg CW-6 SW of Turbine Bldg CW-7 W. of Service Bldg CW-8 SW comer Turb Bldg CW-9*

5' N of CW-1 CW-1 0 Down-Gradient of old gas UST CW-11 PAB Down-Gradient of CB-11 A MW-1 Up-Gradient of PAB MW-2 Down-Gradient of PAB MW-3*

Down-Gradient of PAB MW-5 Adjacent to MW-3 MW-6 Adjacent to CW-1 & 9 NSR-I*

New Shooting Range OSR-1 Old Shooting Range

• Well Decommissioned. Grouted OCB-6

= C 0 CB-2

• rman Pond NSR-1

)S O Monitoring Well Decommissioned Well 0

300 ft Approximate Scale CFW-6 0 n

Grid N e44.5 Deg.

\\.............-.......

OSR-1 0

CFW-3 00 CFW-4 CFW-2 0

0 CFW-5 CB-5 0

Figure 5.

Ground Water Monitoring Wells CFW-l 0 DESD-TD-YR-02-001 Rev. 1 Site Ground Water Data Collection for Figures: Page 8 of 1I

O Sherman Spring

-- S 0 CB YNPS 1999 Maximum Concentration/Annual Dose Equivalent due to H-3 in Ground Water (mrem/yr)

Grid N Y

N(True) e44.5 Deg.

o CW-7",li 0

Li czj C:13-2 Well H-3 No.

pCi/L 0

CW-6 0

CB-1 CB-2 CB-3 CB-6 CB-7 CB-8 CB-9 CB-10 CB-11A CB-12 CW-2 CW-3 CW-4 CW-5 CW-6 CW-7 CW-8 CW-10 CW-1 1 MW-1 MW-2 MW-5 MW-6 B-1 4210 1280

<MDC 666

<MDC

<MDC 4010 2330 2030

<MDC

<MDC

<MDC

<MDC

<MDC

<MDC

<MDC 360

<MDC 11600 1290 11470 5610

<MDC 2830 MW-6 CW-5 Legend o

Monitoring Wells (x are grouted) 0

_....J CB-8 0

O CW-4 CB-3 D-]

Site Structures Fence line Note: All contours are approximate D 300-3000 pCi/L MDC to 0.6 mrem/yr Lii 3000-6000 pCi/L

-0.6 to 1.2 mrem/yr E] 6000-9000 pCi/L 1.2 to 1.8 mrem/yr 9000-12000 pCi/L 1.8 to 2.4 mrem/yr Sherman Spring

<MDC 0

200 ft I

I S Approximate Scale LI DESD-TD-YR-02-001'Rev. I Site Ground Water Data Collection for YNPS Decommissioning Figure 6 Figures: Page 9 of 11

0 Sherman Spring, YNPS Fall 2001 Concentration/Annual Dose Equivalent due to H-3 in Ground Water (mrem/yr) 0CB-6 Grid NYN(T 44.5 Deg.

0 200 ft Approximate Scale ELZ

.0CB-2 0

CW-6 0 CW-10 Well H-3 No.

pCi/L

'S CB-I CB-2 CB-3 CB-6 CB-7 CB-8 CB-9 CB-10 CB-11A CB-12 CW-2 CW-3 CW-4 CW-5 CW-6 CW-7 CW-8 CW-10 CW-11 MW-I MW-2 MW-5 MW-6 B-I 2820 1370

<MDC 430

<MDC

<MDC 2330 3270 410

<MDC

<MDC

<MDC

<MDC

<MDC

<MDC

<MDC

<MDC

<MDC 2260 620 2250 4180

<MDC 1710 I

.I

,*, t 0 i CW-5 OjI Legend O

Monitoring Wells (x are grouted)

E-]

Site Structures Fence line E 300-3000 pCi/L MDC to 0.6 mrem/yr Li 3000-6000 pCi/L 0.6 to 1.2 mrem/yr Note: All contours are approximate CW-4 0+/-1 1

I I

000000o Sherman Spring

<MDC DESD-TD-YR-02-001 Rev. 1 Site Ground Water Data Collection for YNPS Decommissioning Figure 7 Figures: Page 10 of 11

MMM -M M

m-mM-PAB Area: H-3 in Ground Water 1998-9 80000 70000 60000 50000 G

L. 40000 S30000 CB-11A (4-gal purge)

--o--CB-11A(30-gal purge)

MW-2

--x-CW-11 20000 10000 0

0o 00

)

0 Date O0 C.,

0 DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning Figure 8 Figures: Page I I of 11

U I

I I

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i I

DESD-TD-YR-02-001 Rev. 1 Site Ground Water Data Collection for YNPS Decommissioning Page l of 30 Tables

m

-~

rn Table 3. YNPS 1993 Gross Alpha and Gross Beta Results Page 1 of 1 Gross Gross Beta Beta Filtered Unfiltered Concentration Concentration Date Well LSN pCi/L Error MDC Detected? Date Well LSN pCi/L Error MDC Detected?

6/28/1993 B-1 11726 4.70 0.80 2.30 Y

6/28/1993 B-1 11115 16.0 1.3 3.5 Y

6/28/1993 B-3 11725 6.80 0.80 2.20 Y

6/28/1993 B-3 11114 11.9 2.0 5.9 Y

6/18/1993 CB-1 11717 17.60 1.00 2.50 Y

6/18/1993 CB-1 11101 17.2 2.1 6.0 Y

6/18/1993 CB-2 11718 13.90 0.99 2.50 Y

6/18/1993 CB-2 11102 16.9 2.1 6.0 Y

6/28/1993 CB-3 11466 5.20 0.48 1.30 Y

6/28/1993 CB-3 1111-2 74.0 3.7 8.4 Y

6/28/1993 CB-4 11724 4.90 1.30 3.90 Y

6/28/1993 CB-4 11113 12.1 1.4 3.9 Y

6/28/1993 CW-1 11722 12.30 0.95 2.50 Y

6/28/1993 CW-1 11109 11.4 1.4 4.1 Y

6/28/1993 CW-2 11723 6.20 1.80 5.60 Y

6/28/1993 CW-2 11110 43.6 3.2 8.1 Y

6/18/1993 CW-3 11719 26.80 2.50 6.50 Y

6/18/1993 CW-3 11103 25.4 4.3 13.0 Y

6/28/1993 CW-4 11465 1.70 4.30 13.00 Y

6/28/1993 CW-4 11111 79.0 11 31 Y

6/18/1993 CW-5 11720 25.30 2.30 5.90 Y

6/18/1993 CW-5 11104 35.1 3.0 8.1 Y

6/18/1993 CW-6 11721 13.30 0.95 2.40 Y

6/18/1993 CW-6 11105 15.4 1.3 3.5 Y

Gross Alpha Filtered Concentration Date Well LSN pCi/L Error MDC Detected?

6/28/1993 B-1 11726 1.27 0.46 1.20 N

6/28/1993 B-3 11725

-0.17 0.92 3.60 N

6/18/1993 CB-1 11717 4.30 1.60 4.10 N

6/18/1993 CB-2 11718 2.40 1.50 4.10 N

6/28/1993 CB-3 11466

-0.70 0.37 1.50 N

6/28/1993 CB-4 11724

-0.77 0.88 2.70 N

6/28/1993 CW-1 11722 0.89 0.46 1.30 N

6/28/1993 CW-2 11723 1.32 0.97 2.90 N

6/18/1993 CW-3 11719

-1.50 3.20 1.10 N

6/28/1993 CW-4 11465

-0.30 2.10 7.10 N

6/18/1993 CW-5 11720

-0.30 3.00 1.00 N

6/18/1993 CW-6 11721 3.00 1.40 3.90 N

DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning Tables: Page 30 of 30

DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning : Page 1 of 3 Radiological Profiles of Surface Soil

M a-I o

O mEft w-K *m w

-o Distribution of Cobalt-60 with Depth, (pCi/kg wet)

TS-155 TS-158 TS-171 Depth (Beside WHT Moat)

(Storage Area)

(Under VC)

Asphalt 183 414 0-2" 18,600 9880 264 2-4" 5290 8880

< 99 4-6" 1270 866

< 93 6-8" 201 17.5 137 8-10" 95 201

< 104 10-12" 215 124

< 98 12-14"

<96 781 14-16"

<45 Distribution of Silver-108M with Depth, (pCi/kg wet)

TS-155 TS-158 TS-171 Depth (Beside WHT Moat)

(Storage Area)

(Under VC)

Asphalt

<56

<55 0-2" 37,400 20,600

< 66 2-4" 5030 3940

< 44 4-6" 1100 149

< 51 6-8" 425

< 61

< 52 8-10" 187

< 59

< 51 10-12" 157 226

< 42 12-14"

< 61

< 53 14-16"

<60 Ground Water Data for YNPS Decommissioning DESD-YR-02-001 Rev. 0 : Page 2 of 3

-¸

-In m

m m

Distribution of Cesium-137 with Depth, (pCi/kg wet)

TS-155 TS-158 TS-171 Depth (Beside WHT Moat)

(Storage Area)

(Under VC)

Asphalt 428 582 0-2' 18,400 7780 1490 2-4" 6070 9970 173 4-6" 1200 1660 84 6-8" 263 515 87 8-10" 115 336

<87 10-12"

< 105 167

< 81 12-14" 145 251 14-16"

< 79 Ground Water Data for YNPS Decommissioning DESD-YR-02-001 Rev. 0 : Page 3 of 3

DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning : Page 1 of 34. H-3 Well Graphs

M

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DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning : Page 1 of 30 Monitoring Well Configuration Sketches

DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning :

Page 2 of 30 SCHEMATIC FOR WELL INSTALLATION B-I New Fuel Vault DEPTH (fi) 0-10-ground depth 20-30 -

ground surface elevation: +1128.34 (1022.68) pipe PVC riser pipe water

18.

F 5' bentonite seal filter pack sand 40 -

6" dia borehole Top of Bedrock 44 -

49.0' -

4 in. dia schedule 40 PVC slotted well screen Borehole depth: 78.5' Bottom of well screen: 49.0' Top of well screen: 39.0' Top of filter sand: 23' Top of bentonite seal: 18' Installation date: 12/30/77 Sampled Subsurface Materials:

0-8' Fill 8-44' Till 44'-78.5' Bedrock Contractor: Guild Drilling Engineer: Dames & Moore

DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning :

Page 3 of 30 SCHEMATIC FOR WELL INSTALLATION CB-I N. of Fuel Building DEPTH (ft) 0-5-

10-ground water depth 11.7' 15-20-25-N

[ ground surface elevation: +1126.80 (1021.15) 16" deep road box metal cover N

2.5 in. dia schedule 40 PVC riser pipe grout 2' bentonite seal filter pack sand

\\1 2.5 in. dia schedule 40 PVC slotted well screen 5" dia borehole Sampled Subsurface Materials:

0-0.5' Asphalt 0.5-3.5' Fill 3.5'-13.5' Bouldery Till 13.5'-25.5' Till Contractor: Guild Drilling Engineer: Yankee Atomic Borehole depth: 25.5' Bottom of well screen: 25' Top of well screen: 15' Top of filter sand: 14' Top of bentonite seal: 12' Installation date: 4/26-27/93

DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning :

Page 4 of 30 SCHEMATIC FOR WELL INSTALLATION CB-2 N. of Office Building D

ground surface DEPTH (ft)

F I..

ý;...

1 In Q,7 IlI A

,)I eLIVGLIUII. "-r1 on

.01 kIU 1.C.1 0-5-

10-ground water depth 13.7

-V-15-20---

Borehole depth: 25' Bottom of well screen: 24.5' Top of well screen: 14.5' Top of filter sand: 13.5' Top of bentonite seal: 12' 2.5 in. dia schedule 40 PVC riser pipe grout seal filter pack sand slotted well screen 5" dia borehole Sampled Subsurface Materials:

0-0.5' Asphalt 0.5-15.5' Fill/Outwash 15.5-25' Bouldery Till Contractor: Guild Drilling Engineer: Yankee Atomic Installation date: 4/20-21/93

DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning :

Page 5 of 30 SCHEMATIC FOR WELL INSTALLATION CB-3 E. of Fire Water Tank DEPTH (ft) 0-16" deep road box metal cover ground water depth 4.2' 5-10-15-L-

ground surface elevation: +1139.97 (1034.31) 4 grout 1' bentonite seal 2.5 in. dia schedule 40 PVC riser pipe filter pack sand 2.5 in. dia schedule 40 PVC slotted well screen 5" dia borehole Borehole depth: 15.0' Bottom of well screen: 13.0' Top of well screen: 3.0' Top of filter sand: 5.0' Top of bentonite seal: 2' Installation date: 4/29/93 Sampled Subsurface Materials:

0-0.5' Asphalt 0.5-10' Silty Outwash 10-15' Till Contractor: Guild Drilling Engineer: Yankee Atomic

DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning :

Page 6 of 30 SCHEMATIC FOR WELL INSTALLATION CB-4 Old Septic Leaching Field Top of casing elevation: 1087.21 (981.55) ground surface elevation: 1084.5 (978.8)

DEPTH (ft) 0-5-

riser pipe F' bentonite seal 10-ground water depth 11.3' 15-2.5 in. dia schedule 40 PVC slotted well screen 20--

5" dia borehole Borehole depth: 20.0' Bottom of well screen: 19.0' Top of well screen: 9.0' Top of filter sand: 8.0' Top of bentonite seal: 7.0' Installation date: 5/4-5/93 Sampled Subsurface Materials:

0-0.5' Asphalt 0-2' Fill 2'-7'Sand 7-9' Gravel 9-13' Sand 13-15' Gravel 15-20' Alluvium Contractor: Guild Drilling Engineer: Yankee Atomic

DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning :

Page 7 of 30 SCHEMATIC FOR WELL INSTALLATION CB-5 Southeast Construction Fill Area DEPTH (ft) 0 10 -

20 -

ground water v depth: 26' 30 -

40-50-60-Borehole depth: 60'6" Bottoms of well screen: 59' Top of well screens: 29' Top of filter sand: 18' Top of bentonite seal: 16' L

ground surface elevation: 1070+-

24" deep metal riser box 3/4 grout 2'bentonite seal filter pack sand 2.5 'dia. schedule 40 PVC slotted well screen W5" dia. borehole Sampled subsurface materials:

0-0.2' Topsoil 0.2'-25' Fill 25'-60'6" Till Contractor: Guild Drilling Engineer: Yankee Atomic Installation date: 9/9/94

DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning :

Page 8 of 30 SCHEMATIC FOR WELL INSTALLATION CB-6 Southeast of Sherman Dam DEPTH (ft) 0 10

/

Top of casing elevation: +1113.79 (1008.13) ground surface eelevation: +1110.6 (1004.9)

.- 24" deep metal riser box g grout 2'bentonite seal filter pack sand 2.5' dia. schedule 40 PVC slotted well screen X" 5 dia. borehole Sampled subsurface materials:

0-0.2' Topsoil 0.2'-20'SSand and gravel 20'-26 Till ground water depth: 15' V

20 Borehole depth: 26' Bottom of well screen: 25' Top of well screen: 15' Top of filter sand: 14' Top of bentonite seal: 12' Contractor: Guild Drilling Engineer: Yankee Atomic Installation date: 9/13/94

DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning :

Page 9 of 30 SCHEMATIC FOR WELL INSTALLATION CB-7 PCA Warehouse near Waste Building DEPTH (ft) floor surface elevation: +1141.34 (1035.67) 0-ground water depth: 10' 10 17 -

4 Flush metal road box grout 1' bentonite seal 1' fine sand seal filter pack sand 2.5 'dia. schedule 40 PVC slotted well screen 5" dia. borehole Well depth: 17' Bottom of well screen: 17' Top of well screen: 7' Top of filter sand: 5.5' Top of fine sand seal: 4.5' Top of bentonite seal: 3.5' Sampled subsurface materials:

0-1' Concrete 1'-6' Sand and Gravel Fill 6'-11' Boulder, Cobbles 11 -17' Boulders (Till?)

Contractor: Guild Drilling Engineer: Yankee Atomic Installation date: 1/7/97

DESD-TD-YR-02-00l Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning :

Page 10 of 30 SCHEMATIC FOR WELL INSTALLATION CB-8 Rad Storage Area East of Old PCA DEPTH (ft) 0 ground water depth: 5' 10 20-Well depth: 19' Bottom of well screen: 19' Top of well screen: 14' Top of filter sand: 13' Top of bentonite seal: 11.5' fl ground surface elevation: +1140.83 (1035.17) lush metal road box grout 1.5' bentonite seal filter pack sand 5" dia. borehole 2.5 'dia. schedule 40 PVC slotted well screen Sampled subsurface materials:

0-.5' Asphalt 0.5'-3' Sand fill (till?)

3'-19' Till Contractor: Guild Drilling Engineer: Yankee Atomic Installation date: 9/20/94

DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning :

Page 11 of 30 SCHEMATIC FOR WELL INSTALLATION CB-9 Beneath VC Equipment Hatch DEPTH (ft) ground surface elevation: +1126.84 (1021.18) 0 ground water depth: 8' V

10 20 24 Well depth: 24' Bottom of well screen: 24' Top of well screen: 14' Top of filter sand: 13' Top of bentonite seal: 11.5' Flush metal road box

• grout 1.5' bentonite seal

- filter pack sand 2.5 ' dia. schedule 40 PVC slotted well screen 5" dia. borehole Sampled subsurface materials:

0-2" Asphalt 2"-9.5' Sand fill 9.5'-24' Till Contractor: Guild Drilling Engineer: Yankee Atomic Installation date: 9/19/94

DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning :

Page 12 of 30 SCHEMATIC FOR WELL INSTALLATION CB-10 NW. Comer of Ion Exchange Pit DEPTH (ft) 0-slab surface elevation: +1127 (1021) ground water depth 2.5' F bentonite seal 5 -

10-2.0 in. dia schedule 40 PVC riser pipe 5" dia borehole 2.0 in. dia schedule 40 PVC slotted well screen Borehole depth: 11.5' Bottom of well screen: 11.5' Top of well screen: 6.5' Top of filter sand: 5.5' Top of bentonite seal: 4.5' Sampled Subsurface Materials:

0-1.5' Concrete 1.5-10' Brown silty gravelly widely-graded sand Installation date: 12/19/97 Contractor: Geosearch Engineer: Duke Engineering & Services

DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning :

Page 13 of 30 SCHEMATIC FOR WELL INSTALLATION CB-1 1A PAB Pipe Trench DEPTH (ft) 0 ground water depth 3'*

7 5

10 15 20 Top of casing elevation: 1023.5 (1129) ground surface elevation: 1020.5 (1126) 16" deep covered metal riser pipe 2.0 in. dia schedule 40 PVC K

riser pipe grout 1' bentonite seal filter pack sand 2.0 in. dia schedule 40 PVC slotted well screen 5" dia borehole

• Initial ground water depth +0.2 ft above floor Borehole depth: 20' Bottom of well screen: 19' Top of well screen: 9' Top of filter sand: 8' Top of bentonite seal: 7' Installation date: 12/18/97 Sampled Subsurface Materials:

0-1.5' Concrete 1.5-19.5' Brown silty gravelly widely-graded sand: loose 19.5-20.0' Clayey silt Contractor: Geosearch Engineer: Duke Engineering & Services

DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning :

Page 14 of 30 SCHEMATIC FOR WELL INSTALLATION CB-12 NW Comer of Waste Disposal Building Ash Dewatering Pit DEPTH (ft) 0-grout,,'

ground water depth 3.5' 5-6-

5" dia borehole F

floor slab surface elevation: +1134.3 (1028.6) 16" deep road box metal cover F1' bentonite seal 2.0 in. dia schedule 40 PVC slotted well screen filter pack sand Borehole depth: 7' Bottom of well screen: 6.6' Top of well screen: 1.6' Top of filter sand: 1.6' Top of bentonite seal: 0.6' Installation date: 12/10/97 Sampled Subsurface Materials:

0-0.5' Asphalt 0.5-10' Silty Outwash 10-15' Till Contractor: Geosearch Engineer: Duke Engineering & Services Installation date: 12/10/97

DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning :

Page 15 of 30 SCHEMATIC FOR WELL INSTALLATION CW-1 N. of Diesel Generator Building DEPTH (ft) 0-5-

ground water depth 7.2' 10-15-20-g ground surface elevation: +1126.49 (1020.83) 16" deep road box metal cover 2.5 in. dia schedule 40 PVC riser pipe grout 1' bentonite seal filter pack sand I'-

2.5 in. dia schedule 40 PVC slotted well screen 4" dia borehole Borehole depth: 21.0' Bottom of well screen: 21.0' Top of well screen: 11.0' Top of filter sand: 9.0' Top of bentonite seal: 8' Installation date: 4/28/93 Inferred Subsurface Materials:

0-0.5' Asphalt 0.5-12' Bouldery Till 12-21' Till Contractor: Guild Drilling Engineer: Yankee Atomic

DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning :

Page 16 of 30 SCHEMATIC FOR WELL INSTALLATION CW-2 N. of old SI Tank DEPTH (ft)

/-

ground surface elevation: +1 136i.57 k032.9) 0-5-

10-ground water

-2 depth 12.4' 15-20-Borehole depth: 21.0' Bottom of well screen: 20.0' Top of well screen: 9.0' Top of filter sand: 9.0' Top of bentonite seal: 8.0' Installation date: 4/29/93 2.5 in. dia schedule 40 PVC riser pipe grout 1' bentonite seal filter pack sand 2.5 in. dia schedule 40 PVC slotted well screen 5" dia borehole Inferred Subsurface Materials:

0-0.5' Asphalt 0.5-15' Fill/Outwash 15'-21Fill Contractor: Guild Drilling Engineer: Yankee Atomic

DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning :

Page 17 of 30 SCHEMATIC FOR WELL INSTALLATION CW-3 SE of Ion Exchange Pit DEPTH (ft) 0 -

5-ground water depth 8.3' 10-15-20-I ground surface elevation: 1140.20 (1034.54) 16" deep road box metal cover 2.5 in. dia schedule 40 PVC riser pipe I\\

grout 1.5' bentonite seal K,

filter pack sand 2.5 in. dia schedule 40 PVC slotted well screen 5" dia borehole Borehole depth: 23.0' Bottom of well screen: 23.0' Top of well screen: 8.0' Top of filter sand: 7.0' Top of bentonite seal: 5.5' Installation date: 5/3/93 Inferred Subsurface Materials:

0-0.5' Asphalt 0.5-7.5' Fill/Outwash 7.5-19' Till 19-23' Bedrock Contractor: Guild Drilling Engineer: Yankee Atomic

DESD-TD-YR-02-001 Rev. '0 Site Ground Water Data Collection for YNPS Decommissioning :

Page 18 of 30 SCHEMATIC FOR WELL INSTALLATION CW-4 Between PCA Storage Buildings DEPTH (ft) 0-5 -

ground water.a7 depth 7.7' 10-15-ground surface elevation: +1141.17 (1035.5) 16" deep road box metal cover grout 2.5 in. dia schedule 40 PVC riser pipe 1 bentonite seal K,filter pack sand 2.5 in. dia schedule 40 PVC slotted well screen 5" dia borehole Inferred Subsurface Materials:

0-0.5' Asphalt 0.5-17' Till Contractor: Guild Drilling Engineer: Yankee Atomic Borehole depth: 17.0' Bottom of well screen: 17.0' Top of well screen: 7.0' Top of filter sand: 5.0' Top of bentonite seal: 5' Installation date: 5/3-4/93

DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning :

Page 19 of 30 SCHEMATIC FOR WELL INSTALLATION CW-5 S. of Service Building DEPTH (ft) 0-5 ground water depth 8.1'

-F.

10 -

15 -

20 -

T ground surface elevation: +1126.70 (1021.04) 16" deep road box metal cover 2.5 in. dia schedule 40 PVC Sriser pipe N

grout 1' bentonite seal I,,

filter pack sand 2.5 in. dia schedule 40 PVC slotted well screen 5" dia borehole Borehole depth: 21.5' Bottom of well screen: 16.5' Top of well screen: 6.5' Top of filter sand: 5.5' Top of bentonite seal: 4.5' Installation date: 4/27/93 Inferred Subsurface Materials:

0-0.5' Asphalt 0.5-12' Fill/Outwash 13'-21.5' Bedrock Contractor: Guild Drilling Engineer: Yankee Atomic

DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning :

Page 20 of 30 SCHEMATIC FOR WELL INSTALLATION CW-6 W. of Turbine Building DEPTH (ft) 0-5-

10-ground water depth 11.4' 15 -

20 -

L ground surface elevation: +1124.44 (1018.78) 16" deep road box metal cover 2.5 in. dia schedule 40 PVC riser pipe grout 2' bentonite seal K,

filter pack sand K

2.5 in. dia schedule 40 PVC slotted well screen 5" dia borehole Borehole depth: 24' Bottom of well screen: 22' Top of well screen: 12' Top of filter sand: 11' Top of bentonite seal: 10' Installation date: 4/22-23/93 Inferred Subsurface Materials:

0-0.5' Asphalt 0.5-14' Fill/Outwash 12'-24' Till Contractor: Guild Drilling Engineer: Yankee Atomic

DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning :

Page 21 of 30 SCHEMATIC FOR WELL INSTALLATION CW-7 West of Service Building near former Used Oil UST DEPTH (ft) 0 10 4

ground surface elevation: +1127.89 (1022.23) k"_

16" metal road box grout ground water depth: 19' 1 bentonite seal V__

x_"

20 30 Borehole depth: 31' Bottom of well screen: 31' Top of well screen: 21' Top of filter sand: 20' Top of bentonite seal: 19' filter pack sand 2.5 'dia. schedule 40 PVC slotted well screen 5" dia. borehole Sampled subsurface materials:

0-5' Silt with sand 5'-6' Fine-grained sand 6'-8' Cobbles 8'-31' Till (top depth uncertain)

Contractor: Guild Drilling Engineer: Yankee Atomic Installation date: 9/13/94

DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning :

Page 22 of 30 SCHEMATIC FOR WELL INSTALLATION CW-8 Southwest Bay of Turbine Building DEPTH (ft) 0 10 ground surface elevation: +1128.25 (1022.59)

SFlush metal road box grout 1.5 bentonite seal Sfilter pack sand 2.5'dia. schedule 40 PVC slotted well screen S5" dia. borehole ground water depth: 18' 20 V

Well depth: 26' Bottom of well screen: 26' Top of well screen: 16' Top of filter sand: 14.5' Top of bentonite seal: 13' Sampled subsurface materials:

0-1.4' Concrete 1.4'-5' Sand 5'-10' Cobbles 10'-26' Till (top depth uncertain)

Contractor: Guild Drilling Engineer: Yankee Atomic Installation date: 9/14/94

DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning :

Page 23 of 30 SCHEMATIC FOR WELL INSTALLATION CW-9 N. of Diesel Generator Building DEPTH (ft) 0-grout 5-ground water.

depth 7' 10-15-20-Borehole depth: 17.0' Bottom of well screen: 17.0' Top of well screen: 4.0' Top of filter sand: 3.0' ground surface elevation: +1126 (1020) 1' bentonite seal 2.0 in. dia schedule 40 PVC riser pipe filter pack sand (#2) 2.0 in. dia schedule 40 PVC slotted well screen (0.010")

6" dia borehole Observed Subsurface Materials:

0-0.5' Asphalt 0.5-17' Brown dense c.sandy

f. gravelly, cobbley silt: Till Contractor: Geosearch Engineer: Duke Engineering & Services Top of bentonite seal: 2' Installation date: 6/8/98 Method: Hollow Stem Auger DESD-TD-YR-02-001 Rev. 0 Page 24 of 30 Site Ground Water Data Collection for YNPS Decommissioning SCHEMATIC FOR WELL INSTALLATION CW-10 N. of Former Gasoline UST Location ground surface ft)

/

elevation: +1120 (1014)

DEPTH 0-grout 5-Top of Bedrock 10. 4" dia borehole in bedrock 15 -,,

20-ground wate-depth 21' 25-30-Contractor: Geosearch Engineer: Duke Engineering & Servi 16" deep road box metal cover 1' bentonite seal 2.0 in. dia schedule 40 PVC riser pipe 6" dia borehole in soil filter pack sand (#2) 2.0 in. dia schedule 40 PVC slotted well screen (0.010")

Borehole depth: 30.5' Bottom of well screen: 30.0' Top of well screen: 15.0' Top of filter sand: 14.0' Top of bentonite seal: 13' Installation date: 6/8/98 Method: Hollow Stem Auger Observed Subsurface Materials:

0-0.5' Asphalt 0.5-10.2' Brown silty gravelly f. sand 10.2-30.5' Bedrock: dry to 23,'

where fractures occur

DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning :

Page 25 of 30 SCHEMATIC FOR WELL INSTALLATION CW-I1 PAB at LP Cooling Pump Area 16" deep road box, metal cover DEPTH (11) floor slab surface grout elevation: +1128.5 (1022.5)

A*

go,,*_

V ground water V depth 3' "Z

5-2.0 in. dia schedule 40 PVC slotted well screen (0.101")

filter pack sand (#2) 10 -

Borehole depth: 9.5' Bottom of well screen: 9' Top of well screen: 2' Top of filter sand: 1.6' Top of bentonite seal: 0.6' Installation date: 6/11/98 Sampled Subsurface Materials:

0-1.5' Concrete Slab 1.5-9.5' Sand & gravel fill Contractor: Geosearch Engineer: Duke Engineering & Services

DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning :

Page 26 of 30 DEP']

0 5

10 SCHEMATIC FOR WELL INSTALLATION MW-I S. of PAB H

Ift-ground surface elevation: 1140 (1034) 16" deep road box metal covei 2.0 in. dia carbon steel pipe riser pipe ground water depth 13.5' 15-2.0 in. dia carbon steel slotted well screen (0.01.5")

20-1' sediment sump Borehole depth: 21' Bottom of well screen: 20' Top of well screen: 10' Installation date: 4/24/98 Inferred Subsurface Materials:

0-0.5' Asphalt 0.5-21' Clay/silt?

Contractor: Geosearch Engineer: Duke Engineering & Services

DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning :

Page 27 of 30 SCHEMATIC FOR WELL INSTALLATION MW-2 N. of PAB DEPTH (ft) ground surface elevation: + 1126' (1021')

0-16" deep road box metal cover ground water depth 4' 5-2.0 in. dia carbon steel pipe riser pipe 10-2.0 in. dia carbon steel 15-slotted well screen (0.015")

1' sediment sump 20-Borehole depth: 18' Bottom of well screen: 17' Top of well screen: 7' Installation date: 4/24/98 Inferred Subsurface Materials:

0-0.5' Asphalt 0.5-11' Fill 10'-18.5' Till 18.5' Refusal Contractor: Geosearch Engineer: Duke Engineering & Services

DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning :

Page 28 of 30 SCHEMATIC FOR WELL INSTALLATION MW-3 N. of PAB (ft) r ground surface

/elevation:

+1126' (1021 ')

DEPTH 0-5-

gr1 dl 10--

16" deep road box metal cover ound water epth 5' 2.0 in. dia carbon steel pipe riser pipe 2.0 in. dia carbon steel slotted well screen (0.015")

15-20-1' sediment sump Borehole depth: 21' Bottom of well screen: 20' Top of well screen: 10' Installation date: 4/24/98 Note: Casing bent on installation causing sampling difficulty Inferred Subsurface Materials:

0-0.5' Asphalt 0.5-11' Fill 11-21' Till Contractor: Geosearch Engineer: Duke Engineering & Services

DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning, Page 29 of 30 ERM SITE MAP 399 Bo~ylton St-eet, 6th Hoor DRILLING LOG for Well #- NSR-1 iR Bogo SMA 02116 Prjc Yankee Nuclear Power SL-Rowe Proet Number 468.01 NSR-1 @

Client Yanke-Atomic Electric Company Logged by:

Joe Fanco Drilling Cox Geosearch Drille.

Pat Goodale Date Started:

22-Oct-97 Data Finished 22-0ct-97 Shooting Location:

Rowe, Massachusetts Drinlng Metho&

4 1/4" ID HSA& & 3 7/8" Air Hammer ane Screen Dlame 2.5" L

10y Slot Siz 0.01" Casng Diam; 2.5" Length:

l3 Type PVC Firing Line Boring___

________wll___t 23 Boring Mauin 9" (0-201/4" C20-231)

Surface KP.

Depth to GW:

-18" Notes:

Til"s boring was MP Blev-completed in two attempts

bSple, (ppm)

Lab Smp#le sLog pn6t y

Split Spoon Description/SoilClassification

&Depth spoonlHS

&Analyses I Sand 2-2 12" Brown, fine to medium SAN, trace fine gravel, piece S-1 1.0 Fill 3-5 of wood in tip of spoon, well sorted, loose, dry 0-2'

.4 Misc.

8-9 12" Greyish-brown, rock fragments, some fine to medium S-2 900 NSR-I/S-2/

6 Fill 10413 sand and wood fragments, poorly sorted, loose, dry; 5-7" 5-7 ft the wood pieces have a strong chemical odor VOCs (8260)

VOCs (8270) 9 Sand 13-13 10" Brown, fine to medium SAND, trace coarse sand and S-3 5.3 15-17 fine gravel, well sorted, loose, damp 10-12' Note

air hammered through a boulder from 11-13 feet 1in second boring Note: encountered water table at 18 feet Note: top of bedrock at 20 feet; air hammered to 23 feet Bottom of Borehole: 2T

-17.

.19 Well construction:

-3' - 2': Steel protective standpipe 0 - 11Y: Portland cement/bentorilte grout 10 - 12': Bentonite chip seal 24 12 -23': #1 silica sand filter pack 13 -23': 2.5" 11, 0.010"-slotted PVC well sceen Foonoe for BoiiV unM=

(1) 140 b. tammer (2) 300 lo. Hammer MIi sii.,H--

Bentonite Seal Cement

DESD-TD-YR-02-001 Rev. 0, Page 30 of 30 Site Ground Water Data Collection for YNPS Decommissioning, ERM SITE MAP 399 Boylston Street, 6th Root DRILLING LOG for Well #:

OSR-1

&RM Boston MA 02116 ERM Bston MA 02116 Project Yankee Nucclear Power St-Rowe Project Number.

468.01 Client; Yankee Atomic Mectric Company Logged bY Joe Macco Drilling Co:

Geose Is Driller.

Pat Goodale Date Started.

22-Oct-97 Date Firnahed:

22-Oct-97 Shooting Location:

Rowe, Massachusetts Drilling Method:

4 1/4" ID HSAs Range Screen DiaaL 25" Length:

10 Slot Size:

0.01" Casing Diam-2-5 Length:

3' Type PVC F

Line Boring, Deth,~:

33 w,,u Dp,*

is.

Boring Di, m.-

w" Surface Elev.:

MR Depth toGW:

-7 NIotes MP Elev.:

Bb-ftSample (ppm)

Lab Sample#

Depth Well iog sea h ja kid,- R-Split Spoon Description/Soil Classification

&Depth spoon/HS

&Analyses Sand 3-5 24" Brown, fine SAND, some coarse sand and fine gravel, S-1 13.8

.2.

Fill 10-12

-moderately well sorted, loose, dry 0-2'

.3

.4

.5 1

1 Sand 4-4 12 Top 6" of spoon: Brown, fine SAND, well sorted, loose, S-2 502 Fill 5-6 damp; Middle of spoon: 2r thick piece of wood (no odor);

5-7

-. 8 Bottom 4" of spoonr Grey, fine to very fine SAND, well sorted, loose, damp Sand 9-9 10" Brown, fine SAND, some coarse sand and fine gravel, S-3 6.2 23-50/31 moderately well sorted, loose, wet 10-12' Bottomn of Borehole. 13' 13 -

.14

.15. 17-

-18

-19.

Well Constructiow

.20.

m

.21

-3Y - 2': Steel protective standpipe 0 - 1s5: Portland cement surface seal 1.5 -2.5': Bentonite chip seal 2.5 - 13': #1 silica sand filter pack

.25.1-3

- 13': 25" ID, 0.01O"-slotted PVC well screen (1) 140 Lb.

Hammer (2) 30o Lb. Hammer (M cAd. "--e..

Key to Well Constructio El Sandpack Wll Screen Grout M Bentonite Seal Cement

DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning : Page 1 of 33 Monitoring Well Ground Water Levels

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DESD-TD-YR-02-OO1 Rev. 0DESDTD-Y-02-01 Rv.

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DESD-TD-YR-02-001 Rev. 0 Site Ground Water Data Collection for YNPS Decommissioning : Page 1 of 2 YNPS Spent Fuel Pool: Concentration of H-3, 1997-1999

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DESIGN VERIFICATION CHECKLIST Form DPR-3.9A FRAMATOME ANP DE&S QA Record Type N/A Revision 4 Document No.:

DESD-TD-YR-02-001 Rev.:

1 Page:

1 of 1 Document

Title:

Site Ground Water Data Collection for YNPS Decommissioning

1.

Were the inputs correctly selected and incorporated into design?

El Y

EL N

0 N/A

2.

Are assumptions necessary to perform the design activity adequately El Y

Li N

0 N/A described and reasonable? Where necessary, are the assumptions identified for subsequent reverifications when the detailed design activities are completed?

3.

Are the appropriate quality and quality assurance requirements specified?

E Y

EL N

EL N/A

4.

Are the applicable codes, standards and regulatory requirements, Li Y EL N

N N/A including issue and addenda properly identified, and are their requirements for design met?

-5.

Have applicable construction and operating experience been considered?

EL Y

L il N 0 N/ N/A

6.

Have the design interface requirements been satisfied?

EL Y

Li N

0 N/A

7.

Was an appropriate design method used?

El Y

[L N

O N/A

8.

Is the output reasonable compared to inputs?

EL Y

Li N

Z N/A

. 9.

Are the specified parts, equipment and processes suitable for the required EL Y

EL N

0 N/A application?

10.

Are the specified materials compatible with each other and the design EL Y

Li N

E N/A environmental conditions to which the material will be exposed?

11.

Have adequate maintenance features and requirements been specified?

EL Y

EL N

0_ N/A

12.

Are accessibility and other design provisions adequate for performance of

[I Y EL N

0 N/A needed maintenance and repair?

13.

Has adequate accessibility been provided to perform the inservice EL Y

[Li N

0 N/A inspection expected to be required during the plant life?

14.

Has the design properly considered radiation exposure to the public and EL Y

EL N

0E N/A plant personnel?

.15.

Are the acceptance criteria incorporated in the design documents Li Y

EL N

0 N/A sufficient to allow verification that design requirements have been satisfactorily accomplished?

16.

Have adequate pre-operational and subsequent periodic test EL Y

EL N

0 N/A requirements been appropriately specified?

17.

Are adequate handling, storage, cleaning and shipping requirements EL Y

EL N

0 N/A specified?

18.

Are adequate identification requirements specified?

EL Y

EL N

0 N/A

19.

Are requirements for record preparation review, approval, retention, etc.,

0 Y

Li N

Li N/A adequately specified?

Comments:

Verified By:

E. F. Maher

.71____'$1/_2._'01P_

(First, MI, Last)

PRINTED/TYPED NAME SIGNATURE DATE