Text

Final Status Survey (FSS) Final Report - Phase VII
	ML071730427
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	05/17/2007
From:	Gerard van Noordennen; Connecticut Yankee Atomic Power Co
To:	; Document Control Desk, NRC/FSME
References
	CY-07-077
	Download: ML071730427 (65)
	v • d • e

P CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT 362 INJUN HOLLOW ROAD *EAST HAMPTON, CT 06424-3099 MAY 17 2007 Docket No. 50-213 CY-07-077 Re: 10 CFR 50.82(a)(1 1)

U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555-0001 Haddam Neck Plant Final Status Survey (FSS) Final Report - Phase VII The Haddam Neck Plant (HNP) License Termination Plan (LTP) (Section 1.4) describes the process of releasing land from the HNP Operating License. The HNP LTP Section 5.9.2 states that the ESS Final Report will be prepared and submitted ina phased approach.

CYAPCO ishereby submitting the FSS Final Report - Phase VII (Attachment 1).

This Phase VII FSS Final Report addresses fifteen (15) land area survey units comprising most of the former plant location and the main parking lot areas. The report also addresses three (3) subsurface survey units covering the same areas as the surface units. This report contains a compilation of all 18 Survey Unit Release Records that are within the Phase VII scope. Table 1-1 of the report provides a listing of all the survey units including the classification and general description for each unit.

A request to release the NRC license from FSS areas covered under Phases Ill through VII will be submitted under separate cover.

CYAPCO hereby requests the NRC review this Phase VII FSS Final Report for acceptance of this portion of the HNP site final radiological survey by July 31, 2007.

U.S. Nuclear Regulatory Commission CY-07-077/ Page 2 If you should have any questions regarding this submittal, please contact me at (860) 267-3196.

Si nce rely, G. P. van Noordennen Date Director, Regulatory Affairs and Quality Assurance : Final Status Survey (FSS) Final Report - Phase VII cc: S. J. Collins, NRC Region 1 Administrator T. B. Smith, NRC Project Manager, Haddam Neck Plant R. Lorson, Chief, Decommissioning Branch, NRC Region 1 E. L. Wilds, Jr., Director, CT DEP Radiation Division

Docket No. 50-213 CY-07-077 Attachment 1 Haddam Neck Plant Final Status Survey (FSS) Final Report - Phase VII May 2007

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May 2007 Prepared By: Date: -,/O2-t2 7 Dale Randall- FSS E-ng-ineer Reviewed By: Date: 51/i0 /0-7

- FSS Engineer Approved By: Date: SI4Z/

Clyde Newson -Technical Support Manager

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 TABLE OF CONTENTS 1.0 Introduction............................................................................... 3 1.1 Executive Summary................................................................... 3 1.2 Phased Submittal Approach .......................................................... 7 2.0 Final Status Survey Program Overview .............................................. 10 2.1 Survey Planning...................................................................... 12 2.2 Survey Design........................................................................ 17 2.3 Survey Implementation.............................................................. 20 2.4 Survey Data Assessment............................................................. 21 2.5 Quality Assurance and Quality Control Measures................................ 22 3.0 Site Information ........................................................................ 25 3.1 Site Description ...................................................................... 25 3.2 Survey ArealUnit Description ...................................................... 27 3.3 Summary of Historical Radiological Data......................................... 31 3.4 Conditions at the Time of Final Status Survey.................................... 35 3.5 Identification of Potential Contaminants .......................................... 35 3.6 Radiological Release Criteria ...................................................... 36 4.0 Final Status Survey Protocol........................................................... 36 4.1 Data Quality Objectives............................................................. 36 4.2 Survey Unit Designation and Classification....................................... 42 4.3 Background Determination ......................................................... 42 4.4 Final Status Survey Plans ........................................................... 42 4.5 Survey Design........................................................................ 43 4.6 Instrumentation ...................................................................... 44 4.7 Survey Methodology ................................................................ 49 4.8 Quality Control Surveys ............................................................ 51 5.0 Survey Findings ........................................................................ 52 5.1 Survey Data Conversion ............................................................ 52 5.2 Survey Data Verification and Validation .......................................... 53 5.3 Evaluation of No. of Sample and Measurement Locations in SUs.............. 54 5.4 Comparison of Findings with Derived Concentration Guideline Levels ......55 5.5 USNRC/Independent Verification Team Findings ............................... 55 6.0 Summary ................................................................................ 56 7.0 References............................................................................... 56 8.0 Appendices .............................................................................. 60 1

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 LIST OF TABLES 1-1 Phase VII Survey Unit Classification and Description List ........................ 5 2-1 Derived Concentration Guideline Levels for Soil................................. 14 2-2 HNP LTP Compliance Equation 5-1 Values and Actual Soil Dose ................. 15 2-3 FSS Area Classifications ........................................................ 17 2-4 Easy-to-Detect (ETD) and Hard-to-Detect (HTD) Radionuclides.................. 19 4-1 Action Levels.................................................................. 40 4-2 Number of Samples for FSS.................................................... 43 4-3 SPA-3 Technical Details and Specifications ...................................... 45 4-4 Ambient Background Count Rates, Associated MDCR's and Investigation Levels 46 4-5 Scan Coverage ................................................................. 49 4-6 Summary of Total Area Scanned ............................................... 50 5-1 Summary of Statistical Analysis for Soil Samples................................ 53 LIST OF FIGURES 1-1 Phase VII Submittal ........................ /....................................

6 1-2 FSS Final Report Phased Submittal Areas....................................... 9 2-1 FSS Organizational Chart ...................................................... 11 2

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007

1.0 INTRODUCTION

1.1 Executive Summary The purpose of this Final Status Survey (FSS) Final Report is to provide a summary of the survey results and the overall conclusions, which demonstrate that the Connecticut Yankee Atomic Power Company's Haddam Neck Plant (HNP) site, or portions of the site, meets the established criteria for release for unrestricted use. The FSS results provided herein only address the dose component due to soil as provided in the HNP License Termination Plan (LTP) (Reference 7.1) compliance Equation 5-1. The remaining two components, present and future groundwater, were bounded on an individual survey unit basis as discussed in section 2-1 of this report and Integrated Site Closure (ISC) memo 06-024, "Initial Target Operational DCGLs / Dose Targets for CY" (Reference 7.2).

This report also documents that the FSS activities were performed consistent with the guidance provided in the HNP LTP; NUREG-l 575, "Multi-Agency Radiation Survey and Site Investigation Manual" (MARSSIM) (Reference 7.3); HNP program document ISC-GQP-0000l-003, "Final Status Survey Quality Assurance Plan" (Reference 7.4); HNP procedure GPP-GGGR-R5 120-002, "Final Status Survey Program (RPM5.1-00)" (Reference 7.5); and, various station implementing procedures.

This FSS Final Report has been written consistent with the guidance provided in NUREG-1757, Vol. 2, "Consolidated NMSS Decommissioning Guidance-Characterization, Survey, and Determination of Radiological Criteria" (Reference 7.6); MARSSIM; and the requirements specified in GPP-GGGR-R5 122-001, "Preparation of Final Status Survey Reports (RPM 5.1-22)" (Reference 7.7).

To facilitate the data management process, as well as overall project management, FSS Final Reports will incorporate multiple Survey Unit Release Records. Survey Unit Release Records are complete and unambiguous records of the as-left radiological status of specific survey units. Sufficient data and information are provided in each Survey Unit Release Record to enable an independent re-creation and evaluation at some future time of both the survey activities and the derived results.

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Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 This report contains a compilation of eighteen (18) Survey Unit Release Records that are within the Phase VII scope. The Phase VII FSS Final Report specifically addresses fifteen (15) surface soil areas of the HNP site that total approximately fifteen (15) surface acres in size (61,159 in 2 ).

In addition Phase VII encompasses three (3) sub surface soil survey units, with an area of approximately seventeen (17) acres (69,565 in 2 ). Table 1-1 provides a listing of all survey units addressed in this report including the classification and general description for each. Figure I1-I depicts the locations of the survey units in relation to the HNP site, as well as survey unit boundaries.

All FSS activities essential to data quality have been implemented and performed under approved procedures. Trained individuals, using appropriate sampling equipment and laboratory equipment that is sensitive to the suspected contaminants, performned the FSS of the Phase VII survey units.

The survey data for all Phase VII survey units demonstrate that the dose from residual radioactivity in soil is less than the dose target set for the soil portion of the maximum annual dose criterion for license termination for unrestricted use specified in 10CFR2O. 1402 (see Table 2-2). The additional requirement of 10CFR2O. 1402 that all residual radioactivity be reduced to levels that are As Low As Reasonably Achievable (ALARA) has also been satisfied.

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Connecticut Yankee Atomic Power Company Haddam Neck Plant Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey FinalReport - Phase VII May, 2007 9302 0000 3 Northwest Protected Area Grounds (3,490 2 in )

9306 0000 2 Southwest Protected. Area Grounds (5,878m')

9312 0001 1 Containment (Former Radiologically Controlled

________ _____Area) (1,975M 2 )

9312 0002 1 Spent Fuel Building (SFB) (Former

_______Radiologically Controlled Area) (1,975 2 in )

9312 0003 1 Southwest I115kV Switchyard ( Former

______Radiologically Controlled Area) (1,486 in2 )

9312 0004 1 Former Radiologically Controlled Area North of the Primary Auxillary Building and Tank Farm (1,586 in) 9312 005 1 Former Radiologically Controlled Area Tank 9312 005 1 Farm (1,460 in2 )

9312 006 1 Primary Auxiliary Building (PAB) (Former 9312 006 1 Radiologically Controlled Area) (1,754 in2 )

9312 0007 1 Radiologically Controlled Area /RRF Bldg./ 115 kV East Footprint (1,566 in2 )

9312 0008 1 115 kV West Side GW Treatment Facility (Former Radio logically Controlled Area) 2

______ _____(1,351 mn )

9312 0009 1 Former Radiologically Controlled Area East 2

_______Trench North (1,511 in )

9312 0010 1 Radiologically Controlled Area, East Trench 2

____South!/ MWST A&B (1,365 in )

9313 0000 2 Central Site Grounds (8,266 M2) 9514 0000 3 West Primary Parking Lot (18,757 2 in )

9514 0001 2 East Primary Parking Lot (8,739 in 2 )

9801 001 A Subsurface Soils in the Radiologically Controlled 9801_0001 _ Area (15,788 2 in )

9802 0002 B Subsurface Area Associated with the West Industrial Site Grounds (non-protected area)

(18,292, in 2 )

9803 000 C Subsurface Area Associated with the North 9803___ 0000_1__ Grounds (non-protected area) (35,485 2 in )

(1) Refer to Section 3.2 for a more detailed description.

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Connecticut Yankee Atomic Power Company Haddam Neck Plant Connecticut Yankee Atomic Power Company Haddam Neck Plant FinalStatus Survey FinalReport - Phase VII May, 2007 6

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 1.2 Phased Submittal Approach To minimize the incorporation of redundant historical assessment and other FSS program information, and to facilitate potential phased releases from the current license, FSS Final Reports will be prepared and submitted in a phased approach.

I-NP estimates that a total of seven (7) FSS Final Reports will be submitted during the decommissioning project (see Figure 1-2 for locations of phased submittal areas).

Phase I FSS Final Report On April 29, 2004, HNP submitted a request to release a portion of the HNP site (Reference 7.8) from the I1OCFR50 License (DPR-61). Specifically, the request addressed the removal and release of the East Site Grounds (Survey Area 9532), a non-impacted area, from the Part 50 License. In accordance with Section 1.4.2 of the HNP LTP, and the USNRC Safety Evaluation dated November 25, 2002 (Reference 7.9), HNP determined the proposed action would have no adverse impact on the ability of the site in aggregate to meet 10CFR2O, Subpart E, criteria for unrestricted release. The request did not contain a FSS Final Report for Survey Area 9532, because this area was classified as non-impacted. The site release and removal of Survey Area 9532 from the site was approved by the USNRC on September 01, 2004 (Reference 7.10).

Phase 11 FSS Final Report On March 8, 2005, 1-NP submitted a request to release a portion of the HNP site (Reference 7.11) from the I1OCFR50 License (DPR-6 1). Specifically, the request addressed the removal and release of the fourteen (14) surface survey units, and one (1) subsurface survey unit, which collectively made up the area defined as Phase 11. In accordance with Section 1.4.2 of the HNP LTP, and the USNRC Safety Evaluation dated October 5, 2005 (Reference 7.12), HNP determined the proposed action would have no adverse impact on the ability of the site in aggregate to meet 10CFR2O, Subpart E, criteria for unrestricted release. The request contained an FSS Final Report covering all of the areas involved. The site release and removal of Phase 11 from the site was approved by the USNRC on February 28, 2006 (Reference 7.13).

Phase III FSS Final Report On May 4, 2006, HNP submitted the Phase III FSS Report (Reference 7.14). This submittal included the FSS release records for a total of seven (7) surface survey units. In response to 'verbal comments and communications with the USNRC staff, four (4) survey unit release records were revised to further clarify specific technical issues. Revision 1 of the Phase III report and the associated revised release records were submitted to the USNRC on September 9, 2006 (Reference 7.15).

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Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 Phase IV FSS Final Report On November 29, 2006, HNP submitted the Phase IV FSS Report (Reference 7.16). This submittal comprised the FSS release records for a total of sixteen (16) surface survey units, and included the pond and discharge canal survey areas.

Two (2) of the sixteen (16) survey units were permanent wetland areas, the balance were water covered locations. Sediments were sampled in these areas by performing direct push sample coring to the appropriate depths to meet the dose model.

Phase V FSS Final Report On December 7, 2006, I-NP submitted the Phase V FSS Report (Reference 7.17).

This submittal comprised the FSS release records for a total of nine (9) surface survey units, and two (2) subsurface survey units, which collectively made up the area defined as Phase V. This area covered the northern portion of the peninsula, as indicated in Figure 1-2.

Phase VI FSS Final Report On February 20, 2007, HNP submitted the Phase VI FSS Report (Reference

7.1 8). This submittal comprised the FSS release records for a total of sixteen (16) surface survey units, and one (1) subsurface survey units, which collectively made up the area defined as Phase VI. This area generally surrounded the industrialized areas of the site, as indicated in Figure 1-2.

Phase VI1 FSS Final Report The subject of this report.

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Connecticut Yankee Atomic Power CompanyHaamNcPln Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 Figure 1-2, FSS Final Report Phased Submittal Areas CONNECTICUT YANKEE ATOMIC POWER COMPANY.

GENERAL ARRANGEMENT DRAWING Final Status Survey Final Report Phased Submittals 9

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII may, 2007 2.0 FINAL STATUS SURVEY PROGRAM OVERVIEW The FSS Program consists of the methods used in planning, designing, conducting, and evaluating FSS activities at the I-NP site to demonstrate that the premises are suitable for release in accordance with the criteria for decommissioning in Title 10CFR2O, Subpart E. The actual FSS serves as a key element to demonstrate that:

" Dose from residual radioactivity is less than the maximum annual dose criterion for license termination for unrestricted use as specified in Title 10CFR2O. 1402 - that is, the residual radioactivity that is distinguishable from background radiation results in a Total Effective Dose Equivalent (TEDE) to an average member of a critical group that does not exceed twenty five (25) millirem per year (25 mremlyr); and,

" All residual radioactivity at the site is reduced to levels that are As Low as Reasonably Achievable (ALARA) in accordance with Title 10CFR20. 1402.

To implement the FSS Program as provided in Reference 7.5, and MARSSIM, HNP established an organization within the Integrated Site Closure group with sufficient management and technical resources to fulfill project objectives and goals. The FSS organization was responsible for the safe completion of all activities related to FSS necessary to obtain the radiological release for unrestricted use of the IiNP site. Approved site procedures directed this process to ensure consistent implementation and adherence to applicable requirements.

Figure 2-1 provides an organizational chart of the FSS organization and its relationship within the Site Closure Directorate.

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Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey FinalReport - Phase VIIJ May, 2007 Figure 2-1 FSS Organizational Chart Director of Site Closure r--------

R/FSS Manager Technical Support 1[ FSS Project Lead 1RCRA/H Group Manager J _ _ _ _JGround WaterPl FSS Engineers FSS Supervisors FSS Technicians ]

Integrated Site Closure Group

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Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 2.1 Survey Planning After termination of commercial operations, the initial development and planning phase started in 1997 with the characterization and Historical Site Assessment (HSA) processes that continued until submittal of-the License Termination Plan in 2000. The HSA consisted of a review of site historical records regarding plant incidents, radiological survey documents, operations and maintenance records, plant modification documents, and both routine and special reports submitted by HNP to various regulatory agencies. Along with the HSA, inter-views with site personnel, both past and present, reviews of historical site photos and extensive area inspections were performed to meet the following objectives:

" To develop the information to support FSS design including the development of Data Quality Objectives (DQOs) and survey instrument performance standards;

" To develop the initial radiological information to support decommissioning planning including building decontamination, demolition, and waste disposal;

" To identify any unique radiological or health and safety issues associated with decommissioning;

" To identify the potential and known sources of radioactive contamination in systems, on structures, in surface or subsurface soils, and in ground water;

To divide the HNP site into manageable areas or units for survey and classification purposes; and,

To determine the initial classification of each survey area or unit as non-impacted or impacted Class 1, 2, or 3 as defined in MARSSIM or Class A, B, or C for subsurface soils (below 15 cm) as described in the HNP LTP.

DQOs developed and implemented during the initial phase of planning directed all data collection efforts. The DQOs are qualitative and quantitative statements derived from the DQO process that clarify technical and quality objectives, define the appropriate type of data, and specify tolerable levels of potential decision errors used as the basis for establishing the quality and quantity of data needed to support decisions.

This process, described in MARSSIM, and procedure GGGR-R5 111-002, "Preparation of Final Status Survey Plans (RPM 5. 1-11 )" (Reference 7.19), is a series of graded, planning steps found to be effective in establishing criteria for data quality and developing survey plans.

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Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 Used extensively during FSS, the DQO approach consists of the following seven steps:

" State the Problem;

Identify the Decision;

Identify the Inputs to the Decision;

" Define the Boundaries of the Decision;

Develop a Decision Rule;

Specify Tolerable Limits on Decision Errors;

" Optimize the Design for Obtaining Data.

A fundamental precursor to survey design is to establish a relationship between the release criteria and some measurable quantity. This is done through the development of Derived Concentration Guideline Levels (DCGLs). The DCGLs represent average levels of radioactivity, above background levels, presented in terms of surface or mass activity concentrations. Chapter 6 of the I-NP LTP describes in detail the modeling used to develop the DCGLs for soil (called Base Case Soil DCGL), existing groundwater radioactivity, and future groundwater radioactivity from building basements and footings.

A reduction to the Base Case Soil DCGLs provided in Chapter 6 of the IiNP LTP must be performed to ensure compliance with the release criteria of twenty five (25) mremlyr TEDE when all three pathways (soil, existing groundwater and fuiture groundwater) are potentially present.

Chapter 5 of the FINP LTP shows a compliance formula, Equation 5-1, for including the total dose from the three pathways. The reduced quantity becomes the Operational DCGL, whose relationship to the Base Case Soil DCGL is shown by Equation 5-3 of the HNP LTP. Table 2-1 provides a listing of the Base Case and required MDC values.

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Connecticut Yankee Atomic Power Company Haddam Neck Plant Yankee Atomic Power Company Connecticut Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 C-14 5.66E+00 2.26E-0OI Mn-54 1.74E+01 6.96E-0OI Fe-55 2.74E+04 1.1 OE+03 Co-60 3.8 1E+00 1.52E-01 Ni-63 7.23E+02 2.89E+01 Sr-90 1.55E+00 6.20E-02 Nb-94 7.12E+00 2.85E-01 Tc-99 11.26E+01 5.04E-0OI Ag-108m 7.14E+00 2.86E-01 Cs-134 4.67E+00 1.87E-01 Cs-137 7.9 1E+00 3.16E-0OI Eu-152 LI.OE+OI 4.04E-0OI Eu-154 9.29E+00 3.72E-0OI Eu-155 3.92E+02 1.57E+01 Pu-238 2.96E+Ol1 1.18E+00 Pu-239/240 2.67E+01 1.07E+00 Pu-241 8.70E+02 3.48E+O I Amn-241 2.5 8E+O1I 1.03E+00 Cm-243/244 2.90E+O 1 1.16E+00 (1) Bold indicates those radionuclides considered to be Hard-to-Detect (HTD).

The compliance equation of the HNP LTP Equation 5-1, equates the total dose to three (3) components, soil dose, existing groundwater dose and future groundwater dose. This report contains only the results of the FSS that addresses the dose due to soil. To calculate DCGLs, dose models were developed to relate levels of residual radioactivity to potential dose.

In the HNP LTP, Equation 5-1 expresses the total dose (HTotal) from all three (3) media, which is shown below:

HToal can be expressed as:

H7,010I = Hs01 + HIxisfigGW + HFIiIreGW (HNP LTP Equation 5-1) 14

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 The total dose, HTotal, under the LTP criteria is twenty five (25) mremlyr TEDE from all three (3) components. The allowable total dose under the Connecticut Department of Enviromnmental Protection (CTDEP) radiological remediation standard for the HINP is nineteen (19) mrem/yr TEDE. Therefore, the value for HTotai is effectively nineteen (19) mremlyr for all survey units. To determine the Hs0 1j (the dose equivalent for the Operational DCGLs) one must subtract the existing and future groundwater dose values as shown below.

H Soil =HT'o,, -HLY~i~vi,,g G-Hl, uiuireGW (Operational DCGL dose equivalent)

The present and future groundwater terms were bounded on an individual survey unit basis as discussed in Integrated Site Closure (ISC) memo 06-024, "Revised Target Operational DCGLs/Dose Targets for CY" (Reference 7.2). Table 2-2 summarizes the HNP Equation 5-1 values for each of the survey units discussed in this report. Table 2-2 also shows the actual soil dose equivalent based on the survey unit data analyses.

Tble

'_j ?2-2 ffINP LTPComplianceeEuto5- Valuesindea Soi Dose~eI'

<Existin gfround future~Giou id ~&Ai I ~ab Actual

~S urve-%

CN 'Wa ter Dose ~Waiter Dose Soi D5Iose Soil Dose' 9302-0000 2 2 15 0.20 9306-0000 2 2 15 0.17 9312-0001 2 2 15 0.10 9312-0002 2 2 15 0.06 9312-0003 2 2 15 0.07 9312-0004 2 2 15 0.96 9312-0005 2 2 15 4.11 9312-0006 2 2 15 0.21 9312-0007 2 2 15 0.17 9312-0008 2 2 15 0.54 9312-0009 2 2 15 3.42 9312-0010 2 __ 2 15 1.20 9313-0000 2 2 15 0.14 9514-0000 2 0 17 0.25 9514-0001 2 0 17 1.43 9801-0000 2 2 15 0.52 19802-0000 2 2 15 0.09 9803-0000 2 0 17 0.14 (1) These bounding values were taken from ISC memo 06-024, "Target Operational DCGLs/Dose Targets for CY" (Reference 7.2); the maximum allowable groundwater dose is 8 mrem/yr to meet the H-NP LTP release criteria for unrestricted use.

(2) The Operational DCGL dose equivalent meets the release criteria for unrestricted use, as 15

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 agreed to with the CTDEP, of 19 mrem/yr plus ALARA.

(3) The average dose based on the average residual radioactivity in soil following FSS.

The development of information to support decommissioning planning and execution was accomplished through a review of all known site radiological and environmental records. Much of this information was consolidated in the "Results of Scoping Surveys" (Reference 7.20);

"Augmented Characterization Survey Report" (Reference 7.21);

"Characterization Report" (Reference 7.22); "Historical Site Assessment Supplement (HSA)" (Reference 7.23); and, in files containing copies of records maintained pursuant to Title I1OCFR5O.75(g)(1). These documents are discussed further in applicable sections of this report.

An initial objective of site characterization and HSA was to correlate the impact of a radiological event to a physical location on the plant site and to provide a means to correlate subsequent survey data. To satisfy these objectives, the FSS organization divided the site into large, manageable areas and assigned a unique four digit System Survey Code (e.g. Survey Area 9528) to each area. The area designations form the basis for the survey units presented in Table 1-1 of this report. Physically, survey area boundaries made use of logical physical boundaries and site landmarks (paved roads, fences, stone walls) or were determined through the integration of Global Positioning System (GPS) equipment with commercially available mapping software using coordinates consistent with the Connecticut State Plane System, North American Datum (NAD) 1927.

Upon completion of survey area assignment, the FSS organization began the task of initial classification and establishing the initial set of survey units. Classification, as described in MARS SIM, is the process by which an area or survey unit is described according to its radiological characteristics and potential for residual radioactivity. Not all areas of the site had the same potential for residual radioactivity. Residual radioactivity could be evenly distributed over a large area, appear as small areas of elevated activity or a combination of both. In some cases, there may be no residual radioactivity in a survey unit. Therefore, the adequacy and effectiveness of the FSS process depends upon properly classified survey units to ensure that areas with the highest potential for contamination receive a higher degree of survey effort.

A survey area may consist of one or more survey units. A survey unit is a physical area consisting of structures or land areas of a specified size and shape that would be subjected to a FSS. Survey units were limited in size based on classification, exposure pathway modeling assumptions, and site-specific conditions. Particular attention was given to survey unit 16

Connecticut Yankee Atomic Power Company Haddam Neck Plant Yankee Atomic Power Company Connecticut Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 boundaries and surface areas to ensure building foundation footprint coverage. Utilization of this method of classification and size limitation ensures that each area was assigned an adequate number of data points.

The surface area limits provided in MARS SIM were used to establish the initial set of survey units for the HNP LTP. For identification, survey units were assigned the area four-digit code and a sub-code to designate the unit within the survey area (e.g. Survey Unit 9528-0002). Table 2-3 provides an outline for classification and area limits.

~~ ~. 2TTable2-3 FSSAreica Cl'sific'atioiisCntiaio

~Surveys U;nit Sur-face.Area-Limit' Cotmnto ClassificationPteta Structures: U o10M Class I (floor area) Up toi100st Land Area: Up to 2,000 m ihs

ýClass A Subsrae No limi Structures: 100 rm 2 to 1,000 m2 Class 2 (floor area) M o1,0 2Mdrt Land Area: 2,000 2 t1000m Class B Subsurface: No limit Structures:

Class 3 (floor area) No limit Lowest Land Area:

Class C Subsurface Several survey units have undergone reclassification prior to FSS.

Verification and change to increase the class (more restrictive) can be performed at anytime prior to FSS. New sample results or emergent data may require evaluation and reclassification to more restrictive criteria.

Final classification was performed in conjunction with the preparation of the FSS plan, thus indicating all issues of classification are resolved.

2.2 Survey Design Final Status Surveys for the HNP surface soils and structures are designed following I-NP procedures, Section 5 of the HNP LTP and MARSSIM guidance using an integrated approach and combinations of fixed measurements, traditional scanning surveys, and other advanced survey methods, as appropriate, to evaluate survey units relative to their applicable release criteria.

Another important facet of the DQO' process is to identify the radionuclides of concern and determine the concentration variability.

During characterization and in preparation for FSS, the HNP 17

Connecticut Yankee Atomic Power Company Haddam Neck Plant Finial Status Survey Final Report - Phase VII May, 2007 Radiochemistry Lab, using gamma spectroscopy, analyzed soil samples collected from random and biased locations in the survey units for Easy-to-Detect (ETD) radionuclides (Table 2-4). The on-site results were augmented, in most cases, by analyses performed by an off-site laboratory for both ETD radionuclides and Hard-to-Detect (HTD) radionuclides (Table 2-4). Characterization indicated that Cs-137 and/or Co-60 would be the primary radionuclides of concern for survey design and FSS for a majority of the areas submitted in this report. Applied statistically, this data were used to determine the number of samples required to achieve adequate sample design.

Although the HNP LTP only required a minimum of 5% (for subsurface soil samples), typically 10% of all the soil samples, and in some cases a higher percentage, were analyzed for HTD by the off-site laboratory. Sr-90 was the most prevalent HTD radionuclide identified in samples.

Most radionuclides could be screened out or excluded from the survey design under I-NP LTP Section 5.4.7.2. Radionuclide screening or de-selection is a process where an individual radionuclide or aggregate may be considered insignificant and eliminated from the FSS. The criteria for de-selection are concentrations less than 5% of the applicable operational DCGL for individual radionuclides and less than 10% for aggregates of the combined DCGLs. Consistent with Equation 5-7 of the HNP LTP, the 5% rule for single radionuclides or 10% rule for multiple radionuclides is conservative relative to the process presented in Title IOCFR20 in which radionuclides that contribute less than 10% to dose, and where the aggregate does not exceed 30%, are not required to be included in dose assessments.

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Connecticut Yankee Atomic Power Company Haddam Neck Plant Yankee Atomic Power Company Connecticut Haddam Neck Plant Final Status Survey FinalReport - Phase VII May, 2007 Table 2-4 Eayt-Dtc Hard-to-De~tecIt(UD) Radimiuchides SRadionuclide (1 Type~ When AnalyreId Analysis ~

11-3 HTD AS NEEDED Liquid Scintillation C-14 HTD AS NEEDED Liquid Scintillation Mn-54 ETD ALWAYS Gamma Spectroscopy Fe-55 HTD AS NEEDED Liquid Scintillation Co-60 ETD ALWAYS Gamma Spectroscopy Ag-108m ETD ALWAYS Gamma Spectroscopy Ni-63 HTD AS NEEDED Liquid Scintillation Sr-90AS NEDED Gas Flow Proportional Sr90HTD ANEDDCounting Nb-94 ETD ALWAYS Gamma Spectroscopy Tc-99 HTD AS NEEDED Liquid Scintillation Cs- 134 ETD ALWAYS Gamma Spectroscopy Cs-137 ETD ALWAYS Gamma Spectroscopy Eu-152 ETD ALWAYS Gamma Spectroscopy Eu- 154 ETD ALWAYS Gamma Spectroscopy Eu-I 55 ETD ALWAYS Gamma Spectroscopy Pu-238 HTD AS NEEDED Alpha Spectroscopy Pu-239/240 HTD AS NEEDED Alpha Spectroscopy Pu-241 HTD AS NEEDED Liquid Scintillation Am-21 ED ALAYS Gamma Spectroscopy

_______ ____________ Alpha Spectroscopy Cm-243/244 HTD AS NEEDED Alpha Spectroscopy (1) Bold indicates those radionuclides considered to be Hard-to-Detect (HTD).

(2) Americium-241 can be analyzed by gamma and alpha spectroscopy and is considered to be Easy to Detect (ETD); the preferred result is the alpha spectroscopy's when both analyses are performed.

Soil sample locations were determined randomly for Class 3 survey units, or by a triangular systematic grid with a random starting point for Class 1 and 2 survey units using commercially available software. Similarly, for sub-surface units, locations were determined randomly for Class C survey units, or by a triangular systematic grid with a random starting point for Class A and B survey units.

Soil sample locations were identified in North American Datum (NAD) 1927 coordinates and were loaded into the GPS software. Each FSS plan provides a map and GPS positions to FSS field super-vision for reference.

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Connecticut Yankee Atomic Power Company Haddam Neck Plant Yankee Atomic Power Company Connecticut Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 In each survey unit, a minimum of five (5) percent of the samples were collected for quality control analysis such as "splits" or duplicates. All survey units passed the quality control acceptance criteria.

Off-site laboratories were chosen to perform ETD and HTD analysis of samples collected during FSS. Laboratory analysis results were reported as actual calculated results. Results reported as <MDC (i.e., less than minimum detectable concentration) were not accepted for FSS. Sample report summaries included unique sample identification, analytical method, radioisotope, result and uncertainty of two (2) standard deviations, laboratory data qualifiers, units and required MDC.

A consideration of survey design was the need to use "surrogates." In lieu of analyzing every sample for HTDs, the development and application of surrogate ratio DCGLs is an accepted industry practice to assay HTD radionuclides. Surrogate ratios allow for expedient decision making in characterization, remediation planning or FSS design.

Briefly described, a surrogate is a mathematical ratio where an ETD radionuclide concentration is related to a HTD radionuclide concentration, such as Cs-137 to Sr-90. From the analytical data, a ratio is developed and applied in the survey scheme for samples taken in the area. The result is referred to as the surrogate DCGL. Details and applications of this method are provided in Section 5.4.7.3 of the HNP LIP. Surrogates were not used for any of the survey units covered by this FSS Final Report.

Some portion of the Cs-137 and Sr-90 found in the soil samples is certainly attributed to "background" or fallout. However, as an added conservatism, it was decided that background subtraction would not be applied during the survey of the land areas included in this submittal.

A very conservative approach was adopted with respect to the design of Final Status Surveys. Examples of this would include the inclusion of direct analyses of Sr-90 for each sample taken in Survey Area 9312, while it was determined to be a radionuclide of concern for only one (1) of the ten (10) Survey Units. Also, in the design of sub-surface Survey Unit 980 1-0000, each sample was measured for the full suite of FSS nuclides, while only a limited number of these were actually required.

2.3 Survey Implementation Starting in November 2001, FSS plans were developed to guide the physical work of FSS implementation for each survey unit. Some of the tasks included in the implementation were:

20

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007

" Verification and validation of personnel training as required by procedure GPP-GGGR-R5400-000 "Site Closure Training Program (RPM 5.4-0)" (Reference 7.24);

Implementation of a work control process including applicable health and safety procedures under GGGC-O0001-004, "Work Plan and Inspection Record" (Reference 7.25);

Determination of the amount of samples required to meet survey DQOs as described in GGGR-R5 112-001, "Determination of the Number Samples for Final Status Survey (RPM 5.1-12)" (Reference 7.26);

Determination of the overall survey design and objectives including where measurements or samples are to be made or collected, generation of detailed maps of the survey area showing the measurement and~sample locations, and investigation levels and corrective actions under procedure GGGR-R5 111-002, "Preparation of Final Status Survey Plans" (RPM 5. 1-11) (Reference 7.19);

Maintaining Quality Assurance and Quality Control requirements (e.g., replicate measurements or samples) in accordance with procedure GPP-GGGR-R5124-000, "Split Sample Assessment for Final Status Survey (RPM 5.1-24)" (Reference 7.27) and the FSSQAP;

Providing accountability and sample integrity for sample submission to approved laboratories as provided in procedure GPP-GGGR-R5104-003, "Chain of Custody for Final Status Survey Samples (RPM 5.1-5)"

(Reference 7.28); and,

Application of the Operational DCGLs in conjunction with the unity rule, when applicable, to sample results in accordance with the Data Quality Assessment (DQA) process as detailed in procedure GGGR-R123-000, "Data Quality Assessment (DQA) (RPM 5.1-23)"

(Reference 7.29).

The FSS implementation and completion process resulted in the generation of field logs, and radionuclide specific analysis. Data were stored electronically on the I-NP network server.

2.4 Survey Data Assessment Prior to proceeding with data evaluation and assessment, the assigned FSS Engineer resolves and documents discrepancies between the data quality or the data collection process and the applicable requirements.

The DQA process is an evaluation method used during the assessment phase of FSS to ensure the validity of FSS results and demonstrate achievement of the survey plan objectives. The first step in the data 21

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report -Phase VII May, 2007 assessment process converts all of the survey results to DCGL units. The individual measurements and sample concentrations are compared to the Operational DCGL in conjunction with the unity rule, when applicable, for evidence of small areas of elevated activity or results that are statistical outliers relative to the rest of the measurements. When practical, graphical analyses of survey data that depicts the spatial correlation of the measurements were used.

To demonstrate that survey data fulfills the radiological release criteria, FSS planning incorporated hypothesis testing and probabilistic sampling distributions to control decision errors during data analysis. Hypothesis testing is a process based on the scientific method that compares a baseline condition to an alternate condition. The baseline condition is technically known as the null hypothesis. Hypothesis testing rests on the premise that the null hypothesis is true and that sufficient evidence must be provided for rejection. In designing the survey plan, the underlying assumption, or null hypothesis was that residual activity in the survey unit exceeded the release criteria. Rejection of the null hypothesis would demonstrate that residual activity was at or below the release' criteria objective of the FSS.

Hypothesis testing was performed by applying the Sign Test on the sample data associated with the survey unit. The Sign Test is considered a one-sample statistical test that compares sample data directly to the release criteria. Combined with an effective sampling scheme, passing the Sign Test constitutes satisfying the release criteria. Selection of the Sign Test is prudent and conservative in the assumption that the radionuclides being considered are not present in background or are at levels at a small fraction of the applicable release criteria. Reference areas and reference samples are not needed, thus simplifying the FSS. Furthermore, any background contribution (e.g., Cs-137 from atmospheric weapons testing) in the sample increases the likelihood of failing the survey unit, or requiring investigation, which is conservative. If the release criteria were exceeded, or if results indicated the need for additional data points, appropriate further actions were implemented usually through the issue of an addendum to the FSS plan.

Probabilistic sampling was the preferred method to select a sample so that each item in the population being studied had a known likelihood of being included in the sample. Probabilistic sampling included simple random sampling, where every sample had the same chance of being included, or systematic random sampling, where samples were arranged in order and a random starting point was selected.

2.5 Quality Assurance and Quality Control Measures Quality assurance and control measures were employed throughout the Final Status Survey process to ensure that all decisions were based on data 22

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 of acceptable quality. Quality assurance and control measures were applied to ensure:

The plan was correctly implemented as prescribed;

DQOs were properly defined and derived;

All data and samples were collected by individuals with the proper training following approved procedures;

All collected data were validated, recorded, and stored in accordance with approved procedures;

All required documents were properly maintained; and,

Corrective actions were prescribed, implemented and tracked as necessary.

The off-site laboratories used for analysis of the samples collected during FSS maintain Quality Assurance Plans designed for their facility. I-NP reviews these plans, as required by the "Quality Assurance Program for the Haddam Neck Plant (CYQAP)," (Reference 7.30) and the FSSQAP, prior to selection of a laboratory for FSS sample analysis to ensure standards are acceptable. The on-site laboratory was not used to analyze FSS samples used for non-parametric statistical sampling.

The Integrated Site Closure organization maintains a formal, stand alone training program for FSS technicians and FSS Supervision. The training program relates to, but is independent of, the Health Physics Department training program. All FSS technicians met the requirements of the American National Standards Institute, ANSI N18.1-1971, "Selection and Training of Nuclear Plant Personnel", or were junior technicians working under the direct supervision of an ANSI N18.1-1971 qualified Technician and/or FSS supervision. Supervisory and technical support personnel had sufficient education, experience and certification to qualify personnel and perform assigned duties. Some lead Site Closure personnel have had additional training in MARSSIM implementation; and some were certified by the American Board of Health Physics.

The Site Closure Group has established a Curriculum Advisory Committee (CAC) - a training committee - that is comprised of Site Closure Management, a Training Coordinator and Site Closure lead personnel. The CAC is responsible for department training implementation, including review and approval of new training such as required reading (knowledge measures) and On-the-Job (OJT) training and Task Qualification Records (performance measures), revision of existing training, and designation of personnel as OJT Trainers, Evaluators and Subject Matter Experts. The objective of the CAC is to establish effective 23

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 training and qualifications programs and ensure the appropriate design, development and implementation of the Site Closure training program.

Quality Surveillance activities are ongoing in 2007, the following is a summary of Quality Surveillance activities for 2006 & 2007.

During 2006, three (3) Quality Surveillance Reports (QSR) were produced on activities related to FSS. In general, these reports were performed to evaluate the adequacy of the implementation of regulatory and I-NP LTP and FSS requirements.

QSR-06-0 1-CY (Reference 7.3 1) performed during January of 2006, concluded that a sampling of the Survey Unit Release Records to be submitted in Phase III met the I-NP LTP and FSS programmatic requirements.

QSR-06-007 (Reference 7.32) performed during November of 2006, concluded that a sampling of the Survey Unit Release Records to be submitted in Phase IV were consistent with the HNP LTP and FSS programmatic requirements.

QSR-06-008 (Reference 7.33) performed from November of 2006, to December of 2006, concluded that a sampling of the Survey Unit Release Records to be submitted in Phase V was consistent with the ITNP LTP and FSS programmatic requirements.

During 2006, one (1) Quality Assurance Audit was performed covering activities specific to the FSS/CY LTP. The purpose of the audit and associated surveillances was to verify that the licensee was appropriately implementing the programs, processes and procedures which satisfy the requirements of the License Termination Plan and associated regulatory requirements.

AUDIT CY-06-A06-01 (Reference 7.34) performed during May of 2006 covered FSS activities including a sampling of the implementation of FSS activities covered in Release Records to be submitted in Phase IV. The audit concluded that all areas examined met applicable requirements and were satisfactory.

The Integrated Site Closure Group has performed three Self Assessments for 2006. As required by the FSSQAP (Reference 7.4) Self Assessments are performed on a periodic basis to ensure that the FSS program conforms to the requirements of the LTP and implementing procedures.

SCA-06-01 (Reference 7.35), performed in April 2006, was performed as a follow-up to Condition Report (CR)05-781 (Reference 7.36). The issues identified involved soil sample collection, particularly samples used for quality control. The Self Assessment provided recommendations for improvement.

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Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 SCA-06-02 (Reference 7.37) performed in August, 2006, noted that personnel and staffing changes had been implemented since major FSS field activities were last performned. In anticipation of an increase in FSS field activities going forward, the Self Assessment sought to determine what lessons could be learned from recent FSS field activities, identify and correct deficiencies and further ensure Site Closure readiness for FSS.

SCA-06-03 (Reference 7.38) performed in November, 2006, was performed as an investigation of the cause of Condition Report (CR) 06-0223 (Reference 7.39). The CR identified an issue with split sample agreement. The Self Assessment observed that media homogenization for samples from the pond and discharge canal were made more difficult due to the large and varying quantities of clay to fine grained media collected from coring at these locations. In addition, moisture content, aliquot size and varying organic content further hampered the sample homogenization efforts. Recommendations for improvement included improving the briefing process with regards to split sample processing and employing the use of a mechanical sieve. The recommendations for improvement were implemented as of November 2006.

Additionally, each of the Phase VI and Phase VII Release Records were reviewed for adequacy during the spring of 2007.

All findings from the QSRs, audits and assessments have been corrected and systematic controls implemented.

3.0 SITE INFORMATION 3.1 Site Description Haddam Neck Plant, owned by Connecticut Yankee Atomic Power Company, is located on the east bank of the Connecticut River, approximately twenty-one (2 1) miles south-southeast of Hartford.

The site consists of approximately five hundred twenty five (525) acres, with a minimum distance overland from the reactor containment to the site boundary of one thousand seven hundred and forty feet (1,740 ft), and the distance to the nearest residence is over two thousand feet (2,000 ft).

The plant incorporated a 4-loop closed-cycle pressurized water type Nuclear Steam Supply System (NSSS); a turbine generator and electrical systems; engineered safety features; radioactive waste systems; fuel handling systems; instrumentation and control systems; the necessary auxiliaries; and structures to house plant systems and other on-site facilities. HNP was designed to produce 1,825 MW of thermal power and 590 MW of gross electrical power.

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Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 Westinghouse Electric Corporation was responsible for design and fabrication of all nuclear steam supply and auxiliary systems and equipment, as well as design and supply of all secondary plant mechanical and electrical equipment, which it normally manufactures. Stone and Webster Engineering Corporation was responsible for site development, design of buildings and secondary systems, and all plant construction.

Each of these contractors were responsible to HNP for tasks performed in their respective areas of design and construction. Pre-operational plant checkout, core loading, plant start-up and operation were the responsibility of HNP.

On December 4, 1996, I-NP permanently shut down after approximately 28 years of operation. On December 5, 1996, I-NP notified the USNRC of the permanent cessation of operations at the HNP site and the permanent removal of all fuiel assemblies from the Reactor Pressure Vessel and their placement in the Spent Fuel Pool. Following the cessation of operations, I-NP began the decommissioning of the site. The Post Shutdown Decommissioning Activities Report (PSDAR) (Reference 7.40) was submitted, in accordance with Title 10CFR5O.82 (a)(4), on August 22, 1997, and was accepted by the USNRC. On January 26, 1998, HNP transmitted an Updated Final Safety Analysis Report (UFSAR)

(Reference 7.41) to reflect the plant's permanent shutdown status, and on June 30, 1998, the USNRC amended the I-NP Facility Operating License to reflect the plant condition. On October 19, 1999, the lIMP Facility Operating License was amended to reflect the decommissioning status of the plant and long-term storage of the spent fuel in the spent fuel pool.

Additional licensing basis documents were also rex~ised and submitted to reflect long-term fuel storage in the spent fuel pool (Defueled Emergency Plan, Security Plan, QA program, and Operator Training Program).

After extensive analyses and comparison of fuel pool and dry cask storage, CY chose the dry cask option for storing its 1019 spent fuel assemblies.

The location for the new Independent Spent Fuel Storage Installation (ISFSI), which is on CY's 500-plus acres about three-quarters of a mile from the reactor site, was selected from eight carefully researched areas.

In 1997, in accordance with NUREG/CR-5 849 (Reference 7.42) initial site characterization was implemented. In 1999, following the guidelines of MARS SIM, initial characterization was completed. The information developed during the initial I-IP characterization program represented a radiological assessment based on the knowledge and information available at the end of 1999.

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Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 3.2 Survey Area/Unit Description The following information is a description of each survey unit at the time of FSS from December 2006 through April 2007 (additional detail is provided in the Survey Unit Release Records). During this period, the approximately twenty-three and one half (23.5) acres of open land areas of the HNP site received a FSS.

The I-NP site maintains a reference coordinate system based on GPS coordinates consistent with the Connecticut State Plane System. A benchmark was established as an origin for documenting survey efforts and results. The benchmark, located in the main parking lot, was established during the setup and calibration of the base station for the GPS receiver. The benchmark is also provided on Figure 1 of the attached survey unit Release Records to this FSS Final Report.

Each of the attached survey unit Release Records references the distance from a survey unit's nearest point to a North American Datum 1927 (NAD 1927) location. To support decommissioning activities, this datum location has been relocated to a permanent fixed location at coordinates Northing 237370.20, Easting 667394.57. The distances shown in the descriptions reflect the distance of the nearest portion of a survey unit to this datum location.

Survey Unit 9302-0000 Survey Unit 93 02-0000, is an open land surface soil survey area located in the northwestern portion of the former protected area and outside of the former Radiologically Controlled Area (RCA). Survey Unit 9302-0000 is designated as Final Status Survey (FSS) Class 3 and consists of approximately three thousand four hundred and ninety (3,490) square meters of open land and is located approximately one thousand one hundred and twenty-five (1,125) feet from the reference coordinate system benchmark.

Survey Unit 9306-0000 Survey Unit 93 06-0000, which encompasses the south central portion of the protected area grounds outside the Radiologically Controlled Area (RCA) and is designated as Final Status Survey (FSS) Class 2 and consists of approximately five thousand eight hundred seventy-eight (5,878) square meters of open land and is located approximately one thousand four hundred three (1,403) feet from the reference coordinate system benchmark. The survey unit consists of open land areas with no obstructions from trees and brush. Topography is fairly level throughout Survey Area 9306 with a slight slope from east to west, toward the Connecticut River.

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Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 Survey Unit 9312-0001 Survey Unit 9312-0001 (Containment) is designated as Final Status Survey (FSS) Class 1 and consists of approximately one thousand nine hundred-seventy five (1,975) square meters of open land and is located approximately one thousand four hundred eighty feet (1,480 ft) to the southeast of the site benchmark. As a result of demolition and remediation activities, the area topography is mostly flat and de-vegetated. The survey unit has a moderate slope running from east to west.

Survey Unit 9312-0002 Survey Unit 9312-0002 (Spent Fuel Building) is designated as Final Status Survey (FSS) Class 1 and consists of approximately one thousand nine hundred seventy-five (1,975) square meters and is located approximately one thousand five hundred-one feet (1,501 ft) to the southeast of the site benchmark. As a result of demolition and remediation activities, the area topography is mostly flat and de-vegetated. The survey unit has a moderate slope running from east to west.

Survey Unit 9312-0003 Survey Unit 9312-0003 (Southwest 115 kV Switchyard) is designated as Final Status Survey (FSS) Class 1 and consists of approximately one thousand four hundred eighty-six (1,486) square meters of open land and is located approximately one thousand four hundred seventy-seven feet (1,477 ft) to the southeast of the site benchmark. As a result of demolition and remediation activities, the area topography is mostly flat and de-vegetated. The survey unit has a moderate slope running from east to west Survey Unit 9312-0004 Survey Unit 9312-0004 (northern portion of the former Radiologically Controlled Area (RCA)) is designated as Final Status Sur-Vey (FSS) Class 1 and has an area of approximately fifteen hundred-eighty six (1,586) square meters and is located approximately five hundred-six feet (506 ft) to the southeast of the site benchmark. As a result of demolition and remediation activities, the area topography is mostly flat and de-vegetated. The survey unit has a moderate slope running from east to west.

Survey Unit 9312-0005 Survey Unit 9312-0005 Tank Farm (RCA) is designated as Final Status Survey (FSS) Class 1 and has an area of approximately one thousand four hundred sixty (1,460) square meters of open land and is located approximately one thousand three hundred fifty nine feet (1,359 ft) to the 28

Connecticut Yankee Atomic Power Company Haddam Neck Plant Yankee Atomic Power Company Connecticut Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 southeast of the site benchmark. As a result of demolition and remediation activities, the area topography is mostly flat and de-vegetated. The survey unit has a moderate slope running from east to west.

Survey Unit 9312-0006 Survey Unit 9312-0006 (Primary Auxiliary Building) is designated as Final Status Survey (FSS) Class 1 and consists of approximately one thousand seven hundred fifty-four (1,754) square meters of open land and is located approximately one thousand three hundred forty-seven (1,347) feet to the southeast of the site reference coordinate system benchmark.

As a result of demolition and remediation activities, the area topography is mostly flat and de-vegetated. The survey unit has a moderate slope running from east to west.

Survey Unit 93 12-0007 Survey Unit 9312-0007 (Radiologically Controlled Area, Radwaste Reduction Facility (RRF), 115 kV East Footprint) is designated as Final Status Survey (FSS) Class 1 and consists of approximately'one thousand five hundred sixty six square meters (1,566 in2 ) of uninhabited land and is located approximately sixteen hundred ninety four feet (1,694 ft) from the reference coordinate system benchmark. As a result of demolition and remediation activities, the area topography is mostly flat and de-vegetated; Survey Unit 93 12-0008 Survey Unit 9312-0008 (115kV West Side GW Treatment Facility) is designated as Final Status Survey (FSS) Class 1 and consists of approximately one thousand three hundred fifty-one (1,35 1) square meters of open land and is located approximately six hundred sixty-eight (668) feet to the southeast of the site reference coordinate system benchmark.

As a result of demolition and remediation activities, the area topography is mostly flat and de-vegetated. The survey unit has a moderate slope running from east to west.

Survey Unit 9312-0009 Survey Unit 9312-0009 (East Trench North) is designated as Final Status Survey (FSS) Class 1 and has an area of approximately one thousand five hundred eleven (1,511) square meters of open land and is located approximately one thousand three hundred twenty six feet (1,326 ft) to the southeast of the site benchmark. Survey Unit 9312-0009 includes all portions of the RCA that have the steep topography of the rock face and hillside. A smaller flat level gravel covered area is also located within the survey unit at the northwest boundary.

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Connecticut Yankee Atomic Power Company Haddam Neck Plant final Status Survey Final Report - Phase VII May, 2007 Survey Unit 9312-0010 Survey Unit 9312-0010 (Radiologically Controlled Area, East Trench South / MWST A&B) is designated as Final Status Survey (FSS) Class 1 and consists of approximately one thousand three hundred sixty five square meters (1,365 in2 ) of uninhabited land and is located approximately fifteen hundred twenty nine feet (1,529 ft) from the reference coordinate system benchmark. The survey unit is located along the east boundary of Survey Area 9312. It is comprised of flat gravel terrain. The eastern boundary is bordered by a steep rock cliff that transitions to a steep soil bank from north to south.

Survey Unit 93 13-0000 Survey Unit 9313-0000 (Central Site Grounds) is designated as Final Status Survey (FSS) Class 2 and consists of approximately eight thousand two hundred sixty-six square meters (8,266 mn 2

) of open land and is located approximately one hundred ten feet (1 10 ft) to the southeast of the site reference coordinate system benchmark. As a result of demolition, the area topography is mostly flat and de-vegetated. The survey unit has a shallow drainage ditch along the East Mountainside running from south to north.

Survey Unit 9514-0000 Survey Unit 9514-0000 (West Primary Parking Lot) is designated as a Final Status Survey (FSS) Class 3 survey unit and consists of eighteen thousand seven hundred fifty-seven square meters (18,757 in 2 ) or 4.63 5 acres of uninhabited open land located approximately five hundred and sixty-five feet (565 ft) south of the reference coordinate system benchmark. The survey unit is comprised of predominantly flat disturbed open land that gently slopes from east to west toward the Connecticut River.

Survey Unit 9514-0001 Survey Unit 9514-0001 (East Primary Parking Lot) is designated as a Final Status Survey (FSS) Class 2 survey unit and consists of eight thousand seven hundred thirty-nine square meters (8,739 in 2 ) or 2.159 acres of uninhabited open land located approximately five hundred and eighty-four feet (584 ft) south of the reference coordinate system benchmark used at Haddamn Neck Plant (HNP). The survey unit is comprised of predominantly flat disturbed open land that gently slopes from east to west toward the Connecticut River. The eastern portion of the survey unit contains a small stream that collects water from the hillside to the south and east of the survey unit and flows from south to north through the survey unit until it discharges into the onsite retention pond (Survey Unit 9508-0000).

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Connecticut Yankee Atomic Power Company Haddam Neck Plant final Status Survey Final Report - Phase VII May, 2007 Survey Unit 9801-0000 The subsurface Survey Unit 9801-0000 is a designated as a Final Status Survey Class A survey unit and corresponds to the surface Survey Units 9312-0001 through 9312-0010. Survey Units 9312-0009 & 9312-0010 include the rock wall on the east side of the former RCA. All of the aforementioned surface survey units are classified as Class 1. The survey unit is located approximately one thousand two hundred and seventy-one (1,271) feet (ft) to the southeast of the site benchmark. It has a total surface area of approximately fifteen thousand seven hundred and eighty-eight (15,788) square meters (in 2 ).

Survey Unit 9802-0000 Survey Unit 9802-0000 (Subsurface Area Associated with the West Industrial Site Grounds (non-protected area) is designated as Final Status Survey (FSS) Class "B" subsurface soils area and consists of approximately eighteen thousand two hundred and ninety two (18,292 in2 )

square meters of area under uninhabited land and-is located approximately eleven hundred and eighty eight feet (1,188 ft) from the reference coordinate system benchmark. Survey Unit 9802-0000 includes the subsurface soils located under open land area Survey Units 9304-0001, 93 04-0002 and 93 06-0000. Additionally parts of survey areas 9302, 9313 and 9512 are located over the footprint of Survey Unit 9802-0000. The southeast quadrant of the survey unit is comprised mostly of rock outcroppings, rock ledge, underbrush and trees.

Survey Unit 9803-0000 Survey Unit 9803-0000 (Subsurface Area associated with the North Site Grounds (non-protected area) is designated as Final Status Survey (FSS)

Class "C" subsurface soils area and consists of approximately thirty-five 2

thousand four hundred eighty-five square meters (35,485 mn ) of area under uninhabited land associated with the parking lot, Warehouse #s 1 & 2 and the Steam Generator Mockup Building, which have been demolished and is located approximately five hundred sixty five feet (565 ft) from the reference coordinate system benchmark. Survey Unit 9803-0000 includes the subsurface soils located under open land area Survey Units 9504-0000, 9514-0000, 9514-0001, 9313-0000, 9302-0000 and 9512-0000. The surface topography consists of relatively flat open land that is void of all vegetation with a gentle slope toward the onsite pond (Survey Area 9508) to the north (called north as oriented with the north to south flow of the Connecticut River) of the survey area.

3.3 Summary of Historical Radiological Data The site historical radiological data for HNP includes the results of the scoping surveys completed in 1998, augmented characterization surveys in 31

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 1999, a characterization report in 2000, a historical site assessment supplement in 2001, characterization surveys, and remedial action surveys performed up to the time of FSS.

3.3.1 Scoping Surveys The purpose of the scoping survey was to establish early in the decommissioning process, the necessary areas requiring remediation and to what extent. Details of the scoping surveys are provided in the Reference 7.20. The scoping survey identified 140 events that could have potentially contaminated the facility outside of the Radiological Control Area (RCA). From the 140 identified events, the scoping survey report listed those events most likely to have impacted the HNP site outside the RCA. These events were:

" Leak from the Refueling [sic] Water Storage Tank (RWST) heater valve in November 1973 that contaminated the storm drain system;

" Multiple waste gas tank rupture disc actuations in the 70's;

Various leaks in the steam generator blowdown waste discharge line and the service water effluent line under the Primary Auxiliary Building (PAB) floor in the 1976 to 1980 time period;

" Contamination of the yard area around the B orated Water Storage Tank (BWST) from leaks in the circulating water heater line in 1978;

" Unplanned radioactive release from the degasifier through the plant stack in December 1979;

" Leak from a cracked weld seam in the auxiliary building exhaust duct to the main stack in September 1981;

" Draining of the Spent Fuel Pool (SFP) heat exchanger to an uncontrolled drain that emptied into the 115 kV switchyard trench in April 1984;

" Resin liner overflows in 1984;

Sediment dredged out of discharge canal was stored in boneyard burm [sic] area [dredge spoils area] in 1986;

" Drain hose spill of contaminated water to yard area in August 1987;

Contaminated water from radioactive waste processing dumped into an uncontrolled drain that emptied into the 115 kV switchyard trench in February 1989; 32

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phtase VII May, 2007

" Spill of component cooling water to the storm drain in March 1990;

" Leak from the refuieling water storage tank in September 1990;

Spill from the reactor coolant system to the pipe trench in August 1991; and,

Waste material disposed of at on-site permitted landfill in south east corner of site starting in 1974.

3.3.2 Characterization Surveys The characterization of the radiological and hazardous materials conditions of all areas of the HNP site, an initial task in the plant decommissioning and license termination process, centered around four main objectives:

Determine the nature and extent of contamination;

" Provide the basis for the initial classification of areas;

" Provide a basis for remediation planning, including recommendations for additional surveys or samples; and

" Provide input into the FSS design.

Following plant shutdown at the end of 1996, it was determined that there was a need for additional surveys to better define the scope of radioactivity or "characterization" in several on-site areas.

To fill this gap, surveys were conducted in plant areas along with the sampling and analysis of environmental media that included ground water, paved surfaces outside the RCA and soils suspected of containing radioactive materials. The coalescence of this data, as well as all available site data, occurred during the development of the HSA. The HSA consisted of a review of plant operational records since initial license approval, a review of events that have potential impact on decommissioning activities compiled in accordance with Title 10CFR5O.75(g)(l), and interviews with present and former employees regarding events and activities that impact license termination.

The results of the HSA identified radiological conditions or events that impacted the HNP. These events fall into several categories:

Normal plant operation that affected systems, components and building surfaces that are designed to contain radioactive material. Examples of these are the reactor coolant system, residual heat removal pumps and building areas such as sumps and pipe vaults; 33

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007

" The discharge and runoff of radiological effluents to the canal;

" Operational events that occurred in which radioactive materials were released from ventilation, and waste processing systems.

Examples are elevated readings on the Primary Auxiliary Building roof and owner controlled hillside locations east of the plant; and,

" Leakage of water containing radioactive material that was documented historically. Incidents of this nature included leaking lines under the PAB drumming room floor, overflowing of a manhole just east of the Service Building and leakage from radioactive liquid storage tanks.

The summary information developed during the HSA process was evaluated concurrently with the informnation provided in the "NRC Historical Review Team Report - Radiological Control and Area Contamination Issues at Haddam Neck" (Reference 7.43), dated March 26, 1998, to assure completeness of the historical data.

The Characterization Report provided an assessment of the radiological and hazardous material conditions for each of the site buildings and subsections of the site grounds at a specific point in time. A listing of the areas was provided in the table of contents, along with the area identification number(s) and the area's initial classification in accordance with the criteria established in MARSSIM. Site maps were provided to locate the areas and the respective survey area number(s). A report for each area contained a description (boundaries) of the area, known radiological and hazardous material information, impacted systems within an area and recommendations for further samples or surveys. Buildings assumed to remain in support of spent fuel storage activities, were not included (i.e. not considered at that time to be part of the HNP LTP as they would remain under license, to store the spent fuel).

As suggested in the Characterization Report, and discussed in the applicable I-NP LTP and Survey Unit Release Records, additional characterization surveys would be needed to aid in the FSS plan design.

3.3.3 Remedial Action Surveys All survey areas submitted in this FSS Final Report were evaluated in accordance with Health Physics Department Technical Support Document (TSD) BCY-HP-0078, "ALARA Evaluation of Soil Remediation in Support of Final Status Survey (Reference 7.44). " This evaluation determined that remediation beyond that required to satisfy the release criteria to be 34

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 unnecessary, and that the remaining residual radioactivity in soil was ALARA.

During the phase of decommissioning and surveying covered by this FSS Final Report, remedial action and a Remedial Action Survey (RAS) was performed in survey units 93 12-0009 and 93 12-0010 prior to the commencement of FSS activities. In addition, some sub-surface radiological remediation was performed in Class 1 survey units of Survey Area 9312. However, the remedial work performed in Survey Area 9312 was done in response to activity found to be in excess of the ground water screening criteria as opposed to being required for compliance with soil DCGL limits.

The surveys associated with this work were performed and documented in accordance with station procedures. It was determined that the remediation was completed when the concentrations of residual radioactivity within the survey unit were below the ground water screening values which are much less than the soil operational DCGLs.

3.4 Conditions at the Time of Final Status Survey The survey areas discussed in this FSS Final Report are open land areas.

Construction activities were complete, and the areas were turned over to Integrated Site Closure for the implementation of isolation and controls.

Prior to FSS, areas rea dy for survey were isolated and controlled under procedure GGGR-R5 116-002, "Area Preparation for Final Status Survey Activities" (RPM 5.1-16) (Reference 7.45) This included posting of the areas as well as notifications to site personnel. Permission to enter and work in these areas had to be obtained from FSS Supervision. Obvious postings of the boundaries in the areas controlled public access; however, the impact of public access to the final radiological condition of the areas was considered minimal to nonexistent.

3.5 Identification of Potential Contaminants In general, the identification of potential contaminants was accomplished through the review of plant operating records, radiological surveys and laboratory analysis for ETD and HTD radionuclides. During characterization, a portion of the soil samples collected from areas that would undergo FSS were sent to an off-site laboratory for HTD analysis.

The HTD analysis usually included chemical separation or other advanced methods of detection not available at HNP.

The radiological assessments and characterization surveys identified Cs-137 and Co-60 as the primary radionuclides of concern. Other radionuclides, from both the ETD and HTD list provided in Table 2-4, 35

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report -Phase VII May, 2007 have been identified in survey areas covered under this FSS Final Report.

It is very likely that many of these are false positives and were counted as positive detects because the criterion used at HNP is highly conservative.

The HNP criterion for accepting as a positive detection was any reported result greater than two (2) standard deviations uncertainty. In almost every case, radionuclides that were considered detected by the HNP criterion, were reported in concentrations that were less than the MDC value. All the radionuclides listed in Table 2-4 were considered in the DQO process when designing an FSS plan and during the DQA when reviewing the adequacy of the FSS plan.

3.6 Radiological Release Criteria The radiological release criteria is based on 10CFR2O, Subpart E, where dose from residual radioactivity that is distinguishable from background radiation results in a TEDE to an average member of a critical group that does not exceed twenty five (25) mremlyr; and, all residual radioactivity is reduced to levels that are ALARA. The HNP LTP had established DCGLs (e.g., Base Case Soil DCGLs) to demonstrate compliance with the release criterion of less than or equal to twenty five (25) mremlyr.

A reduction to the Base Case Soil DCGLs had to be performed to ensure compliance with the release criterion of 25 mrem/yr TEDE when all three (3) pathways (soil, existing groundwater and future groundwater) are potentially present. The reduced quantity is the Operational DCGL which was administratively set in accordance with the values listed in Table 2-2.

4.0 FINAL STATUS SURVEY PROTOCOL 4.1 Data Quality Objectives The DQO process as outlined in Section 2.1 of this report was applied for each FSS Plan and contains basic elements common to all FSS plans at HNP. A general outline of those elements presented in the I-NP FSS plans are as follows:

STATE THE PROBLEM The problem: To demonstrate that the level of residual radioactivity in a survey unit including any areas of elevated activity does not exceed the release criterion.

Stake holders: The primary stakeholders interested in the answer to this problem are HNP, the CTDEP and the USNRC.

The Planning Team: The planning team consisted of the Site Closure personnel. The primary decision maker was the assigned FSS Engineer. The FSS Engineer obtained input from I-NP Project Support on issues relating to schedule and costs.

36

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase V'II May, 2007 Schedule: The approximate time to complete an FSS plan and collect field data. Constraints and other activities that may have limited access to areas or hamper survey and sampling were also addressed.

Resources: The primary resources needed to determine the answer to the problem were ANSI N18.1-1971 qualified Health Physics Technicians to perform fieldwork, FSS Engineers to prepare the plan, generate maps, coordinate field activities and evaluate data. An off-site laboratory would be needed to analyze the samples and provide quality radionuclide specific results.

" IDENTIFY THE DECISION PrincipalStudy Question: Does the average concentration of residual radioactivity in the survey unit exceed the release criteria?

Alternate Actions. Alternative actions include failure of the survey unit, remediation, reclassification and no action.

The Decision: If the survey unit fails to demonstrate compliance with the release criteria, then the survey unit is not ready for release for unrestricted use.

" IDENTIFY THE INPUTS TO THE DECISION Information Needed: New measurements of sample media would be needed to determine the concentration and variability of the radionuclides present at the site at the time of final status survey, the extent of any areas of elevated activity, and the results of statistical outliers relative to the rest of the measurements.

Source of the Information. A review of historical information, 10CFR5O.75(g)(l) files, and radiological surveys providing an indication of the potential for contamination.

Sampling and Analysis Methods to Meet the Data Requirements:

The media consisted of surface soil, that is, the soil collected to 15 cm (6 inches) depth for fifteen (15) of the eighteen (18) survey units.

The samples were collected with new or decontaminated tools to minimize cross-contamination between sampling. Judgmental samples were taken in the vicinity of locations where remedial action had occurred or as otherwise deemed necessary by the FSS Engineer based on past events and process knowledge. Samples were sent to an approved off-site laboratory. Results exceeding the investigation level were verified and evaluated as necessary.

The media included subsurface soil, that is, the soil below the top 15 cm (6 inches) depth up to a depth of 3 meters or bedrock, whichever was reached first, for three (3) of the eighteen (18) survey units.

Subsurface soil was collected using direct push equipment to obtain 37

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 cores to the required depth. The media was removed from the core on-site, was homogenized and a sample was obtained from the mixture. The cores were collected with new or decontaminated tools to minimize cross-contamination between sampling.

Analyses included radionuclide specific measurements to identify and quantify the ETD and HTD radionuclides listed in Table 2-4.

Laboratory analysis results included actual calculated results.

Results reported as <MDC were not accepted for FSS. Results included reporting error, observed MDC and data qualifiers as appropriate.

Determining the Operational DCCL: Table 2-1 lists twenty (20) radionuclides potentially present at the site. DCGLs were calculated for each of the radionuclides listed based on a limit of twenty five (25) mrem/yr USNRC dose limit and a CTDEP dose limit of nlineteen (19) mremlyr. To calculate DCGLs, dose models were developed to relate levels of residual radioactivity to potential dose. The DCGLs were developed for exposures from three (3) potential media, which is residual radioactivity in soil, existing groundwater contribution, and future groundwater contribution. In the I-NP LTP, Equation 5-1 expresses the total dose (HTota!) from all three (3) media, which is shown below:

HToal can be expressed as:

H 7 ;910, =HSoi + Hilisfi,,gGW + HI;,lureGW (HINP LTP Equation 5-1)

The dose contribution from the existing groundwater and future groundwater contamination, the second and third components of I-NP LTP Equation 5-1, are addressed on a survey unit basis as shown in Table 2-2.

Following characterization, the data was evaluated to determine if any of the twenty listed radionuclides would be present in quantities greater than 5% of the applicable individual Operational DCGL or an aggregate concentration exceeding 10%. If multiple radionuclides were assumed present (e.g., Cs-137, Co-60) then the individual Operational DCGLs would be used in conjunction with the unity rule to demonstrate compliance.

As verification, a minimum of 5% of the samples required for compliance were analyzed for all radionuclides listed in Table 2-4.

Any radionuclides listed in Table 2-4 verified present in FSS samples were included in the assessment of data and incorporated into the decision process as necessary.

38

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report -Phase VII May, 2007 A decision to use or not use surrogate DCGLs was evaluated based on radionuclide analysis. During Phase VII FSS surrogates were not used to evaluate sample results.

Survey and Analysis Methods to Meet the Data Requirements: The H~NP LTP requires that MDCs for fixed measurements (samples are considered fixed measurements) be as far below the DCGL as possible. A value of 10% is the desired level of sensitivity with up to 50% of the DCGL being acceptable. The MDCs for soil samples were typically less than 10% of the Operational DCGL.

All activities fall under the FSSQAP. This plan requires, among other things, the use of trained technicians, calibrated instruments and procedures. In addition to these requirements, a minimum of 5%

of the required number of samples were selected for QC evaluation which consisted of field replicate splits.

Based on survey unit class, an elevated measurement comparison test (EMC) was sometimes applicable. The EMC test is applicable and was designed for all Class I survey units. For each Class I survey unit, direct measurements above the Operational DCGL were bounded for area extent and evaluated using the EMC test.

The EMC test does not apply for Class 2 or Class 3 units.

Basis for Determining the Action Level: The Action Level provides the criterion used during the decision process for choosing among alternative actions (e.g., whether to take action or not to take action or whether to choose Action 1 versus Action 2). The Action Levels associated with implementing the 1HNP LTP are based on regulatory requirements and are linked to the evaluation of FSS data.

The first step in evaluating FSS data for a given survey unit was to draw simple comparisons between the measurement results and the release criterion, which for FSS, is identified with the Operational DCGL used in conjunction with the unity rule, when applicable. The result of these comparisons would be one (1) of four (4) conclusions shown in Table 4-1.

39

Connecticut Yankee Atomic Power Company Haddam Neck Plant Yankee Atomic Power Company Connecticut Haddam Neck Plant Final Status Survey Finial Report - Phase VII May, 2007 A plant-related radionuclide other Re-evaluate the Operational than those planned for has been DCGL detected.

All reported concentrations are less No further action required, the than the Operational DCGL ' survey unit meets the release criterion The average concentration is less than the Operational DCGL (1)but anCodcthSinTs individual sample exceeds Operational CodcthSgnTs DCGL (')

The average concentration exceeds Implement alternative actions, Operational DCGL ()the survey unit does not meet the release criterion (1)Used in conjunction with the unity rule, when applicable.

DEFINE THE BOUNDARIES OF THE SURVEY.

Boundaries of the survey: The actual physical boundaries as stated for each survey unit.

Temporal boundaries: Estimated times and dates for the survey.

Sampling in a survey unit was normally performed only during daylight and dry weather.

Constraints: The most common constraints were the weather, water level, fall protection and overgrowth that limited personnel access to survey and some sample locations.

DEVELOP A DECISION RULE The following decision rule was developed to define a logical process for choosing among alternative actions for the principal study questions associated with each survey unit. The decision rule is based on the Action Levels listed in Table 4-1.

The Decision: If the average concentrations for the radionuclides of interest exceed the Operational DCGLs or the Sign Test fails, then the survey unit is not ready for release for unrestricted use.

SPECIFY TOLERABLE LIMITS ON DECISION ERRORS The Null Hypothesis: Residual radioactivity in the survey unit exceeds the release criteria.

Type I Error: This is the (x error. This is the error associated with incorrectly concluding that the null hypothesis was rejected. The 40

Connecticut Yankee Atomic Power Company Haddam Neck Plant Yankee Atomic Power Company Connecticut Haddam Neck Plant Final Status Survey Final Report - Phase VII IMay, 2007 HNP LTP has set the cc error at 0.05 (5%) unless prior approval is granted from the USNRC to use a less restrictive value. Therefore, a value of 0.05 (5%) was used for survey planning and data assessment for FSS.

Type II Error: This is the P3error. This is the error associated with incorrectly concluding that the null hypothesis was accepted. A value of 0.05 (5%) was used for survey planning and data assessment for these survey units.

The Lower Bound of the Gray Region (LBGR).- The LBGR is set or adjusted during the optimization phase of the DQO process.

Relative Shpif (Ala): The relative shift will be maintained within the range of 1.0 and 3.0 by adjusting the LBGR in accordance with Reference 7.14.

OPTIMIZE DESIGN Type of statistical test: The Sign Test was selected as the statistical test for FSS.

The Sign Test is conservative as it increases the probability of incorrectly accepting the null hypothesis (i.e., the conclusion would have been the survey unit does not meet the release criteria) and would not require the selection or use of a background reference area. This approach was also conservative since it included background Cs- 137 as part of the sample set (Reference 7.48).

Number of samples for non-parametric statistical sampling: The number of samples for non-parametric statistical sampling was determined using Reference 7.26. The LBGR was set to obtain a relative shift in the range of 1 and 3. The locations of the samples were determined using Visual Sample Plan (VSP) software in accordance with procedure (RPM 5.1-14), "Identifying and Marking Locations for Final Status Survey" (Reference 7.49) and the appropriate grid spacing for the assigned class (i.e. random or systematic). VSP was created by Pacific Northwest National Laboratory (PNNL) for the United States Department of Energy.

Number of judgmental samples and locations: The selection of judgmental or biased samples was at the discretion of the FSS Engineer. Locations chosen for sampling were usually areas of interest (obvious disturbance of soil, collection points from run-off and erosion, small piles, trenches, etc).

Number of scan areas and location: Scan survey areas locations were based on the conditions found during the area inspection or historic evaluation. The amount of scan coverage was based on the 41

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report -Phase VII May, 2007 potential for small areas of elevated radioactivity. The LTP does not require scanning of subsurface survey units.

Number of samples for Quality Control: The number of quality control samples usually exceeded 5% percent of the sample set. The locations for split samples was selected randomly from the set of samples for non-parametric statistical testing using the Microsoft Excel RAND function.

Invest'igat'ion Levels: Investigation levels are established in the HNP LTP for the various classifications. Investigation levels prompted additional survey and analysis to identify areas of elevated activity and ensure proper classification. The investigation level for a soil sample measurement includes individual radionuclide results greater than the Operational DCGL used in conjunction with the unity rule.

For scan measurements, the investigation level is determined as a function of ambient background level.

Power Curve. A Prospective Power Curve was generated using COMPASS, a software package developed under the sponsorship of the USNRC for implementation of the MARSSIM in support of the decommissioning license termination rule (10 CFR 20, Subpart E).

The result of the COMPASS computer run showed adequate power for all the Phase VII FSS designs.

4.2 Survey Unit Designation and Classification The procedure "Survey Unit Classification (RPM 5.1-10)" (Reference 7.50) defines the decision process for classifying an area in accordance with the I-TNP LTP and MARSSIM. During the FSS of areas submitted for Phase VII FSS Final Report Survey Unit 9514 was subdivided and reclassified, creating Survey Units 9514-0000 and 9514-0001, these were classified as class 3 and class 2 respectively.

4.3 Background Determination During FSS area scanning, ambient backgrounds were determined and the "elevated" reading limit for that scan area was established by the FSS Supervisor. Each Survey Unit Release Record discusses scan area readings (instrument readings for each scan area is enclosed with each release record in the appendixes).

4.4 Final Status Survey Plans The level of effort associated with planning a survey is based on the complexity of the survey and nature of the hazards. To assist the Site Closure FSS Engineers when preparing survey plans to support FSS, guidance is provided in Reference 7.14.

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Connecticut Yankee Atomic Power Company Haddam Neck Plant Yankee Atomic Power Company Connecticut Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 4.5 Survey Design 4.5.1 Determination of Number of Data Points The number of samples was determined in accordance with Reference 7.26. A summary of survey design data points is provided in Table 4-2.

Tabe -2 Nmbr f amle for FSS S~urvey Unit Survey D~esign Bise nvsigation Sam plesM'~ Samle(2 ) sample's 9302-0000 15 3 1 9306-0000 15 4 1 9312-0001 ____15 4 7 9312-0002 ____15 3 0 9312-0003 15 3 0 9312-0004 15 0 6 9312-0005 15 4 4 9312-0006 15 4 0 9312-0007 15 0 0 9312-0008 15 0 3 9312-0009 21 0 24 9312-0010 18 5 3 9313-0000 15 0 8 9514-0000 15 3 1 9514-0001 15 5 6 9801-0000 32 6 0 19802-0000 25 1 4 0 9803-0000 1 15 0 1 0 (1) The number of statistical samples taken for performing the Sign Test.

(2) The number of biased samples was determined during the DQO process and augmented as necessary by addendumns to the FSS plan.

4.5.2 Sample Locations Locations of the samples were determined using VSP in accordance with Reference 7.49. VSP was verified and validated by Health Physics Technical Support Document (TSD) BCY-HP-0079, "Use and Verification of Visual Sample Plan" (Reference 7.52). The TSD contains documentation including a user's manual for VSP Version 2.0 and verification documentation.

VSP software imports a topographical map of the selected survey area and, once provided with the number of required samples, type of grid pattern (triangular or square), and the starting point for the grid pattern (random starting point), then develops the survey design and designates the sample location coordinates based on the Connecticut State Plane System. The coordinates 43

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report -Phase VII May, 2007 are then imported into the GPS for use in finding the sample location in the field.

For those locations where access was impractical or unsafe, the location was either moved within a fixed radius of the original point (e.g., 3 meters) or an alternate random sample location was generated. In either case, the decision to relocate a sample location was documented in the Daily Survey Journal (a detailed log of field activities) or in an addendum of the FSSP.

4.6 Instrumentation The DQO process evaluates the ability of the instrument to measure radioactivity at levels below the applicable DCGL. Referred to by the FSS plan, this evaluation is documented in Reference 7.54. Detector sensitivities are also discussed in Section 5.7 of the HNP LTP.

4.6.1 Detector Efficiencies The Eberline E-600 survey instrument coupled with the SPA-3 high sensitivity gamma detector was selected as the primary radiation detection instrumentation for FSS surveys at I-NP.

Efficiencies for the SPA-3 Sodium Iodide probe are demonstrated during calibration as the ability to respond as expected when exposed to a gamma radiation field from a National Institute of Standards and Technology (NIST) traceable Cs-137 source. If the response is within an acceptable range, then the detector is placed in service; otherwise, the instrument is considered "Out of Service" and sent for evaluation and repair. This method is described in procedure GGGR-R4206-003 RPM 4.2-14, "Calibration of the Eberline SPA-3 Smart Probe" (Reference 7.55).

4.6.2 Detector Sensitivities Instrument DQOs include a verification of the ability of the survey instrument to detect the radiation(s) of interest relative to the Operational DCGL. DQOs established that the E-600 with the SPA-3 scintillation probe, operated in the data-logging, rate-meter mode, set to audio response, met the detection criteria needed to perform FSS surveys. Table 4-3 provides specifications for the SPA-3 detector.

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Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 Table 4-3 - SPA-3 Technical Deal an I~cfcain Application High sensitivity gamma measurements ype2-inch Detetor diameter by 2-inch thick NaI(TI)

Detetor ype(5.1 centimeter x 5.1 centimeter)

Operating 1,000 volt nominal Voltage Dead Time 14 Rs nominal Background -1.2 Mcpm/mR/h Sensitivity (Cs-I 37)

Energy Range -60 keV to 2 MeV Operating -220 to + 1400 F Temperature (-30' to +60' C)

Housing Aluminum body Connector CJ- I Size 2.63 inch diameter x 11.13 inch long (6.7centimeter x 28.3 centimeter)

Weight 3.4 lbs. (1.5 kg)

Detector sensitivity, or the ability to detect radionuclides of interest at levels acceptable for FSS, is derived as a function of the application of the DQO process, from vendor specifications, instrument calibration, survey technique and a determination of background and Minimum Detectable Count Rate (MDCR).

Unless noted otherwise in the Survey Unit Release Records, before performing FSS of land areas, a scanning investigation level was established for each sample location and judgmental scan area based upon the ambient background levels at the location. The investigation level was determined using Reference 7.54, which provided the MDCR and investigation level relative to the ambient background count rate. The scanning investigation level was equal to the MDCR plus the ambient background count rate for class 2 and class 3 survey units. For class 1 Survey Units this limit could have been set as high as an instrument count rate equivalent of the DCGLEMC, but in general, more conservative values were used.

For some Class I Survey Units, Technical Guidance Document BCY-HP-0239 was used to calculate Action levels of 2,000 cpm plus background (Reference 7.56). The methodology was consistent with guidance provided in NUREG- 1507, "Minimum Detectable Concentrations with Typical Radiation Survey 45

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 Instruments for Various Contaminants and Field Conditions" (Reference 7.57).

The background level was determined by holding the detector at arms length and at waist height near the scan location and the reading logged. The investigation level was determined and scanning was performed. An instrument response above the investigation level required investigation and additional sampling.

Typical ambient background levels and corresponding investigation levels are provided in Table 4-4.

Table 4-4-- Ambiient Backgr-ound _Count Rates, Associated ~MDCR's and Investigation Levels Backgrouznd (cprni) MDCR (epm)~ Investigation Level 2500 714 3214 3000 782 3782 3500 845 4345 4000 903 4903 4500 958 5458 5000 1010 6010 5500 1059 6559 6000 1106 7106 6500 1152 7652 7000 1195 8195 7500 1237 8737 8000 1278 9278 8500 1317 9817 9000 1355 10355 9500 1392 10892 10000 1428 11428 10500 1464 11964 11000 1498 12498 11500 1532 13032 12000 1565 13565 12500 1597 14097 13000 1629 14629 13500 1660 15160 14000 1690 15690 14500 1720 16220 46

Connecticut Yankee Atomic Power Company Haddam Neck Plant Yankee Atomic Power Company Connecticut Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 15500 1778 17278 16000 1807 17807 16500 1835 18335 17000 1862 18862 17500 1890 19390 18000 1916 19916 18500 1943 20443 19000 1969 20969 19500 1995 21495 20000 2020 22020 20500 2045 22545 21000 2070 23070 21500 2094 23594 22000 2119 24119 22500 2143 24643 23000 2166 25166 23500 2190 25690 24000 2213 26213 24500 2236 26736 25000 2259 27259 25500 2281 27781 26000 2303 28303 26500 2325 28825 27000 2347 29347 27500 2369 29869 28000 2390 30390 28500 2411 30911 29000 2433 31433 29500 2453 31953 30000 2474 32474 30500 2495 32995 31000 2515 33515 31500 2535 34035 47

Connecticut Yankee Atomic Power Company Haddam Neck Plant Yankee Atomic Power Company Connecticut Haddam Neck Plant Final Status Survey FinalReport - Phase VII May, 2007 Table 4-4 -AmbietBcgon Coun Raes Aso ia~eNl)R's~

iand InvestigationLevels<

Backg7round (cpmn) NMLDCR (cpm) Investigation Level~

32000 2555 34555 32500 2575 35075 33000 2595 35595 33500 2614 36114 34000 2634 36634 34500 2653 37153 35000 2672 37672 35500 2691 38191 36000 2710 38710 36500 2729 39229 37000 2748 39748 37500 2766 40266 38000 2785 40785 38500 2803 41303 39000 2821 41821 39500 2839 42339 40000 2857 42857 4.6.3 Instrument Maintenance and Control Control and accountability of survey instruments were maintained to assure the quality and prevent the loss of data. Health Physics Technicians performing field survey activities and assessing the data collected were trained in the use and control of the instruments applicable to the tasks they were performing. Training consisted of reading required procedures and On-the-Job Training.

The E-600 remained in the custody of assigned technicians, and positive control was maintained, until collected data had been downloaded. Log sheets and other forms used to record field data remained in the custody of the responsible individual, and positive control was maintained, until the instrument was returned to secure storage. Procedure RPM 5.2-1, "Setup and Operation of the E-600 Digital Survey Instrument for Scoping, Characterization and Final Status Surveys," (Reference 7.58) provided details on the instrument for field use.

48

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 4.6.4 Instrument Calibration Instruments were calibrated using NIST (National Institute of Standards and Technology) traceable sources using approved procedures and instructions. Instrument calibration and repair history were documented for each instrument and probe.

Instrument integrity and operation was checked prior to use and issue. Only trained and qualified personnel repaired, calibrated or tested FSS instrumentation.

Instrument response checks were performed prior to use, at the completion of the survey, and prior to data download. An instrument failing a response check was removed from service. In addition, an investigation was performed to determine if collected data was corrupt. Instrument source and performance checks were documented for each instrument.

4.7 Survey Methodology 4.7.1 Scan Surveys The HNP LTP specifies the minimum amount of scanning required for each class (See Table 4-5). The total fraction of scanning coverage was determined for each survey unit during the DQO process with the amount, and location(s) based on the likelihood of finding elevated activity during FSS.

~si~~

nitRequired Scanning CoveragIfe Sur~%

CassricaionFraction Uit Class 1 100%

Class 2 10% tol100%

Class 3 Judgmental Class A (subsurface) None Class B (subsurface) None Class C(subsurface) None Scan areas were walked down and marked out grid fashion using paint or flags. The scan areas were staked out using GPS in most cases. In general, the scan areas were divided into manageable 1-meter wide strips with variable lengths depending on the size of the scan area and the location. The strips are then mapped, flagged as a row 1-meter wide by the strip length long, and scanned 100%

of the available area. The instrument was operated in the rate 49

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 meter mode with the audio response enabled. During the scan, the probe was positioned as close to the ground as possible and was moved at a scan speed of about 0.5 meters per second. Areas with elevated readings were marked and evaluated, and in most cases additional sampling was performed. Table 4-6 provides a summary of the area scanned during FSS.

9306-0000 2 5,878 1,500 25 9312-0001 1 1,975 1,975 100 9312-0002 1 1,975 1,975 100 9312-0003 1 1,486 1,486 100 9312-0004 1 1,586 1,586 100 9312-0005 1 1,460 1,460 100 9312-0006 1 1,754 1,754 100 9312-0007 1 1,566 1,566 100 9312-0008 1 1,351 1,351 100 9312-0009 1 1,511 1,511 100 9312-0010 1 1,365 1,365 100 9313-0000 2 8,266 1,400 17 9514-0000 3 18,757 1,900 10 9514-0001 2 8,739 2,200 25 9801-0000 A 15,788 N/A N/A 9802-0000 B 18,292 N/A N/A 9803-0000 C 35,485 N/A N/A For random and biased sample locations, the scan area for samples was a circle of one (1) meter radius around the sample flag. The instrument was operated in the rate meter mode with the audio response enabled. During the scan, the probe was positioned as close to the ground as possible and was moved at a scan speed of about 0.5 meters per second. When applicable, the sample location was moved, and the sample was collected, from the area exhibiting elevated readings.

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Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 During the scanning, the technician recorded data in the Daily Survey Journal. This log documented field activities and other information pertaining to the FSS.

The LTP does not require scanning for subsurface survey units.

4.7.2 Soil Sampling Measurement locations were identified in North American Datum (NAD) 1927 coordinates that were supplied to the FSS field supervisor. Surface soil samples were collect by hand, using radiologically clean equipment between samples. Subsurface core samples were collected using direct push technology to collect composite samples up to a depth of three (3) meters.

4.7.3 Total Surface Contamination Measurements "Total Surface Contamination Measurements" refers to the FSS of structural surfaces such as walls, floors and ceilings. During this phase of FSS and submittal, no areas containing structures subject to FSS were surveyed.

4.8 Quality Control Surveys Reference 7.27 establishes a method for evaluating QC split samples collected in support of FSS. QC split sample data was assessed on criteria taken from the USNRC Inspection Manual, Inspection Procedure 84750, "Radioactive Waste Treatment and Effluent and Environmental Monitoring," March 1994 (Reference 7.53).

A minimum of five percent (5%) of the sample locations used in the FSS design were selected randomly using the Microsoft Excel "RANDBETWEEN" function and submitted as "splits." All splits taken during FSS were field replicates, that is, samples obtained from one location, homogenized, divided into separate containers and treated as separate samples. These samples were used to assess errors associated with sample heterogeneity, sample methodology and analytical procedures. It was desirable that when analyzed, there would be agreement between the splits resulting in data acceptance. When there is not agreement between the samples, the FSS Engineer evaluated the magnitude and impact on FSS plan design, and the need to perform confirmatory sampling. When the FSS Engineer has determined that the discrepancy affects quality or is detrimental to the FSS program then the discrepancy warranted the issuance of a Condition Report (Reference 7.27).

To maintain the quality of the FSS, isolation and control measures are implemented until there is no risk of recontamination from 51

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 decommissioning or the survey area has been released from the license.

Following FSS, until the area is released, a semi-annual surveillance will be performed on the survey units covered by this FSS Final Report. The surveillance will include an inspection of area postings, inspection of the area for signs of dumping or disturbance and some sampling from selected locations, when warranted. In the event that isolation and control measures are compromised, a follow-up survey may be performed after evaluation.

5.0 SURVEY FINDINGS Reference 7.29 provides guidance to Site Closure personnel to interpret survey results using the DQA process during the assessment phase of FSS. Although intended for FSS activities, the DQA process could be used for other radiological data collection activities (e.g., characterization and remedial action surveys). The extent to which of the DQA process was applied to these surveys was commensurate with the objectives of the particular survey.

The DQA process is the primary evaluation tool to determine whether data are of the right type, quality and quantity to support the objectives of the sample plan (e.g., FSS Plan and the requirements of the I-NP LTP). The five steps of the DQAs process are:

" Review the sample plan Data Quality Objectives (DQOs) and the survey design;

" Conduct a preliminary data review;

Select the statistical test;

" Verify the assumptions of the statistical test, and,

" Draw conclusions from the data.

Data validation descriptors described in MARSSIM Table 9.3 were used during the DQA process to verify and validate collected data as required by the FSSQAP.

5.1 Survey Data Conversion During the data conversion, the FSS Engineer will evaluate raw data for problems or anomalies encountered during the FSS plan activities (sample collection and analysis, handling and control, etc.) including the following:

" Recorded data;

Missing values;

" Deviation from established procedure; and,

" Analysis flags.

52

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 Once resolved, initial data conversion, which is part of preliminary data review was performed and consists of converting the data into units relative to the release criteria (i.e., pCi/g), and calculating basic statistical quantities (e.g., mean, median, standard deviation). Table 5-1 provides a summary of the data analysis for each survey unit of Phase VII. The individual FSS Release Records covered by this FSS Final Report provide additional detail.

Ta~ble 5 Summary of Stati~stical Analysis for Soil Samples 1 NMean~3 Standard~

Suve Cass Cocnrto Deito Actual Soil Dose V ni(Untizd)(" (Untize) (reni/yr) 9302-0000 3 8.55E-03 2.50E-01 0.20 9306-0000 2 1.14E-02 1.53E-02 0.17 9312-0001 1 3.11 E-03 1.71 E-02 0.10 9312-0002 1 1.38E-03 1.39E-02 0.06 9312-0003 1 1.36E-06 1.71 E-02 0.07 93 12-0004 1 6.39E-02 4.74E-02 0.96 9312-0005 1 2.74E-01I 9.76E-0 1 4.1H 9312-0006 1 1.38E-02 1.69E-02 0.21 9312-0007 1 6.69E-03 9.47E-03 0.17 93 12-0008 1 3.38E-02 8.07E-02 0.54 9312-0009 1 2.28E-01 3.62E-01 3.42 9312-0010 1 6.92E-02 1.16E-0 1 1.20 9313-0000 2 9.34E-03 1.3 1E-02 0.14 9514-0000 3 1.71E-02 1.24E-02 0.25 9514-0001 2 8.03E-02 1.66E-01 1.43 9801-0000 A 3.03E-02 6.46E-02 0.52 9802-0000 B 4.75E-03 7.23E-03 0.09 9803-0000 C 8.01 E-03 1.57E-02 0.14 (1) This value represents the sum of each radionulcide of concern divided by its applicable soil DCGL.

5.2 Survey Data Verification and Validation Items supporting DQO sample design and data were reviewed for completeness and consistency. This includes:

Classification history and related documents;

Site description;

Survey design and measurement locations; 53

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007

Analytic method, detection limit and that the required analytical method(s) were adequate for the radionuclides of concern;

" Sampling variability has been provided for the radionuclides of interest;

QC measurements have been specified;

Survey and sampling result accuracy has been specified;

" MDC or Minimum Detectable Activity (MDA) limits have been provided;

Field conditions for media and environment are assessed.

Documentation, as listed, was reviewed to verify completeness and that it is legible:

" Field and analytical results;

Chain-of-Custodies;

" Daily Survey Journals;

Instrument downloads; and,

" Measurement results relative to measurement location.

After completion of these previously mentioned tasks, a Preliminary Data Review record was initiated. This record serves to verify that all data are in standard units in relation to the DCGLs and requires the calculation of the statistical parameters needed to complete data evaluation. Included at a minimum are the following parameters:

The number of samples or measurements;

" The range of observations (i.e., minimum and maximum values);

" Mean;

Median; and,

" Standard deviation.

Considerations as an optional aid to evaluate the data set are the coefficient of variation, measurements of relative standing, such as percentile and other statistical applications as necessary (frequency distribution, skew etc.). Finalization of the data review consists of graphically displaying the data in distributions and percentiles plots.

5.3 Evaluation of Number of Sample and Measurement Locations in Survey Units 54

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 An effective tool utilized to evaluate the number of samples collected in the sampling scheme is the Retrospective Power Curve generated by COMPASS. The Retrospective Power Curve shows how well the survey design achieved the DQOs. For reporting purposes, all Survey Unit Release Records included a Retrospective Power Curve analysis indicating that the sampling design had adequate power to pass FSS release criteria (i.e. adequate number of samples were collected).

The Sign Test was the selected statistical test for all Survey Unit Release Records covered under this FSS Final Report. This test was performed in accordance with procedure RPM 5.1-21, "Applying the Sign Test,"

(Reference 7.59). All the data for the survey units covered under this FSS Final Report passed the Sign Test and the null hypothesis was rejected.

The FSS design has been satisfied.

During this FSS, the need to apply the Elevated Measurement Comparison (EMC) Test was required to evaluate locations in Survey Units 9312-0004, 93 12-0005 and 93 12-0009.

5.4 Comparison of Findings with Derived Concentration Guideline Levels In conjunction with performing the Sign Test, and the generating of a Retrospective Power Curve, the data were compared to the Table 4-1 criteria and the decision rule provided in the FSS plan. Based on the comparison, and non-parametric statistical sampling (i.e., the Sign Text),

the survey unit may either fail or pass.

Investigations are typically addressed in the FSS plan and may require the issue of an addendum to provide additional instruction and information.

When the investigational criteria are exceeded, additional evaluation is done to understand the extent and mechanism for the apparent elevated response. Several actions may occur which include bounding the elevated area with multiple samples. Information collected from this type of plan provides additional information for statistical analysis and may stimulate further considerations to reclassify, remediate and resurvey. It should be noted that one (1) or more samples exceeding the Operational DCCL may not constitute failure of the survey unit and a viable option is to do nothing more in this area.

5.5 USNRCflndependent Verification Team Findings The USNRC/ORISE has performed independent verification work in several of the Phase VII Survey Units. This work included independent scan surveys and soil sampling within these areas.

55

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 6.0

SUMMARY

The eighteen (18) survey units covered under this FSS Final Report have met the criteria of the applicable FSS plans. However, the FSS results provided herein only address the dose component from soil as provided in the HNP LTP Equation 5-1. Refer to Table 2-2 and Table 5-1 for the dose component for soil in each survey unit. The second component of HNP LTP Equation 5-1, dose contribution due to existing groundwater, is bounded by either 2 mremlyr or 0 mremlyr per note (1) of Table 2-2. The dose contribution from the third component of HNP LTP Equation 5-1, future groundwater, is bounded by either 2 mremlyr or 0 mremlyr depending on whether there are not underground building foundations or footings containing residual radioactive material within the groundwater saturated zone in the survey areas.

7.0 REFERENCES

7.1 Haddam Neck Plant License Termination Plan 7.2 ISC 06-024, "Initial Target Operational DCGLs/Dose Targets for CY",

August 2, 2006.

7.3 NUREG- 15 75, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) 7.4 ISC-GQP-0000 1-003, "Final Status Survey Quality Assurance Plan" (FSSQAP) 7.5 GPP-GGGR-R5 120-002, "Final Status Survey Program (RPM 5. 1-00)"

7.6 NUREG- 1757, Volume 2, Consolidated NMSS Decommissioning Guidance-Characterization, Survey, and Determination of Radiological Criteria 7.7 GPP-GGGR-R5122-001, "Preparation of Final Status Survey Reports (RPM 5.1-22)"

7.8 W. Norton (I-NP) to USNRC, "Letter of Intent Concerning the Release of the East Site Grounds from the Part 50 License", dated April 29, 2004 (CY-04-069 / Docket No. 50-2 13) 7.9 J. D. Donahue (USNRC) to K. Heider (HNP), "Haddam Neck Plant -

Issuance of Amendment RE: Approval of License Termination Plan",

dated November 25, 2002 7.10 T. Smith (USNRC) to W. Norton (HNP), "Haddam Neck Plant - Release of East Site Grounds from Part 50 License", dated September 01, 2004 7.11 J. Bourassa (HNP) to USNRC, "Final Status Survey (FSS) Final Report Phase 11", March 8, 2005 (CY-05-040/ Docket No. 50-2 13) 56

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report -Phase VII May, 2007 7.12 W. Norton (HNP) to USNRC, "Letter of Intent Concerning the Phased Release (Phase 11 Release Area) from the Part 50 License", dated October 5, 2005 (CY-05-194 / Docket No. 50-2 13) 7.13 T. Smith (USNRC) to W. Norton (HNP), "Haddam Neck Plant - Release of Phase 11 from Part 50 License", dated February 28, 2006 7.14 "Final Status Survey Report - Phase 111", May 04, 2006 7.15 "Final Status Survey Report - Phase 111", Revision 1 September 9, 2006 7.16 "Final Status Survey Report - Phase IV", November 29, 2006 7.17 "Final Status Survey Report - Phase V", December 7, 2006 7.18 "Final Status Survey Report - Phase VI", February 20, 2007 7.19 GGGR-R5 111-002, "Preparation of Final Status Survey Plans" (RPM 5.1 -

I11)"

7.20 "Results of Scoping Surveys", September 1998 7.21 "Augmented Characterization Survey Report", January 1999 7.22 "Characterization Report", January 2000 7.23 "Historical Site Assessment Supplement" August 2001 7.24 GPP-GGGR-R5400-000, "Site Closure Training Program (RPM 5.4-00)"

7.25 GGGC-0000 1-004, "Work Plan and Inspection Record" 7.26 GGGR-R5 112-00 1, "Determination of the Number of Samples for Final Status Surveys (RPM 5.1-12)"

7.27 GPP-GGGR-R5124-000, "Split Sample Assessment for Final Status Survey (RPM 5.1-24)"

7.28 GPP-GGGR-R51004-003, "Chain of Custody for Final Status Survey Samples (RPM 5.1-5)"

7.29 GGGR-R5123-000, "Data Quality Assessment (DQA), (RPM 5.1-23)"

7.30 "Quality Assurance Program for Haddam Nuclear Plant," (QAP HNP) 7.31 CY Quality Surveillance Report QSR 06-001 -CY 7.32 Quality Surveillance Report QSR 06-007 7.33 Quality Surveillance Report QSR 06-008 7.34 CY Quality Assurance Audit CY-06-A06-01 7.35 Self Assessment 06-01 "Final Status Survey Field Activities" 7.36 CY Condition Report (CR) 05-78 1 7.37 Self Assessment 06-02 "Final Status Survey Field Activities" 57

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 7.38 Self Assessment 06-03 "Final Status Survey Field Activities" 7.39 Condition Report (CR) 06-0223 7.40 Post Shutdown Decommissioning Activities Report (PSDAR) 7.41 Updated Final Safety Analysis Report (UFSAR) 7.42 US NRC NUREG CR-5 849 "Manual for Conducting Radiological Surveys in Support of License Termination" 7.43 "NRC Historical Review Team Report - Radiological Control and Area Contamination Issues at Haddam Neck" USNRC, dated March 26, 1998 7.44 HNP Health Physics Department Technical Support Document BCY-HP-0078, "ALARA Evaluation of Soil Remediation in Support of Final Status Survey 7.45 24265-000-GPP-GGGR-R5 116-002, "Area Preparation for Final Status Survey Activities (RPM 5.1-16)"

7.46 RCRA Facility Investigation Report, April 2006 7.47 Peninsula Area Investigation Report, July 2006 7.48 Health Physics Technical Support Document (TSD) BCY-HP-0063, "Background Cs- 137 Concentration in Soil."

7.49 GGGR-R5 114-001, "Identifying and Marking Locations for Final Status Survey (RPM 5.1-14)".

7.50 GPP-GGGR-R51 10-00 1, "Survey Unit Classification (RPM 5. 1-10) 7.51 EPRI Technical Report 1003030, "Determining Background Radiation Levels in Support of Decommissioning Nuclear Power Plants."

7.52 Health Physics Technical Support Document (TSD) BCY-HP-0079, "Use and Verification of Visual Sample Plan" 7.53 USNRC Inspection Manual, Inspection Procedure 84750, "Radioactive Waste Treatment and Effluent and Environmental Monitoring," March 1994.

7.54 Health Physics Technical Support Document BCY-HP-0081, "Scan MDC of Land Areas using a 2-inch by 2-inch Sodium Iodide Detector."

7.55 GGGR-R4206-003 RPM, "Calibration of the Eberline SPA-3 Smart Probe (RPM 4.2-14)"

7.56 Health Physics Technical Support Document BCY-HP-0239, "Guidance on Setting the Investigation Level for SPA-3 Scans of soil for Class 1 Final Status Survey Units" 58

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 7.57 NUREG-15507, "Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions" December 1997.

7.58 GPP-GGGR-RPM 5.2-1, "Setup and Operation of the E-600 Digital Survey Instrument for Scoping, Characterization and Final Status Surveys,"

7.59 GPP-GGGR-R512 1-001, "Applying the Sign Test (RPM 5.1-2 1)"

59

Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 8.0 Appendices Al Survey Unit Release Record 93 02-0000, Northwest Protected Area Grounds A2 Survey Unit Release Record 9306-0000, Southwest Protected Area Grounds A3 Survey Unit Release Record 9312-0001, Containment (Former Radiologically Controlled Area)

A4 Survey Unit Release Record 9312-0002, Spent Fuel Building (SFB) (Former Radiologically Controlled Area)

A5 Survey Unit Release Record 9312-0003, Southwest 11I5kV Switchyard (Radiologically Controlled Area)

A6 Survey Unit Release Record 9312-0004, Former Radiologically Controlled Area North of the Primary Auxillary Building and Tank Farm A7 Survey Unit Release Record 9312-0005, Former Radiologically Controlled Area Tank Farm A8 Survey Unit Release Record 9312-0006, Primary Auxiliary Building (PAB)

(Former Radiologically Controlled Area)

A9 Survey Unit Release Record 9312-0007, Radiologically Controlled Area /RRF Bldg.! 115 kV East Footprint Al 0 Survey Unit Release Record 9312-0008, 115 kV West Side GW Treatment Facility (Former Radiologically Controlled Area)

All Survey Unit Release Record 9312-0009, Former Radiologically Controlled Area East Trench North Al12 Survey Unit Release Record 93 12-0010, Radiologically Controlled Area, East Trench South! MWST A&B Al13 Survey Unit Release Record 9313-0000, Central Site Grounds A 14 Survey Unit Release Record 9514-0000, West Primary Parking Lot A15 Survey Unit Release Record 95 14-0000, East Primary Parking Lot A16 Survey Unit Release Record 9801 -0000, Subsurface Soils in the Radiologically Controlled Area 60

.Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report - Phase VII May, 2007 Al17 Survey Unit Release Record 9802-0000, Subsurface Area Associated with the West Industrial Site Grounds:

Al18 Survey Unit Release Record 9803-0000, Subsurface Area Associated with the North Grounds (non-protected area) 61

CY-07-077, Final Status Survey (FSS) Final Report - Phase VII

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SUMMARY

7.0 REFERENCES

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CY-07-077, Final Status Survey (FSS) Final Report - Phase VII

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