ML072080391

Revision 2 to Final Status Survey Final Report Phase V, Book 1 of 13

ML072080391
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	07/12/2007
From:	Wojtkowiak D Connecticut Yankee Atomic Power Co
To:	NRC/FSME
References
CY-07-106
Download: ML072080391 (62)

Text

BoW JA Final Status Survey Final Report Phase V Connecticut Yankee Atomic Power Company Haddam Neck Plant v.s Haddam, Connecticut July 29.007 so Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Report -Phase V July 2007-Prepared-By:, Reviewed By: Approved By: Clyde Newson -Technical Support Manager chard McGrath -Radiaion Protection Manager-Date:- -- I cr_ .Date: 7///7 Date: -7/1 /9 Connecticut Yankee Atomic Power Company Haddam Neck Plant Ft tal Status Survey Final Report -Phase V July 2007 TABLE OF CONTENTS 10 Introduction 3 1 1 Executive Summary 3 1 2 Phased Submittal Approach 7 2 0 Final Status Survey Program Overview 11 2 1 Survey Planning 13 22 Survey Design 18 2 3 Survey Implementation 22 2 4 Survey Data Assessment 23 2 5 Quality Assurance and Quality Control Measures 24 3 0 Site Information 26 3 1 Site Description 26 3 2 Survey Area/Unmt Description 28 3 3 Summary of Historical Radiological Data 31 34 Conditions at the Time of Final Status Survey 34 35 Identification of Potential Contaminants 35 36 Radiological Release Criteria 37 40 Final Status Survey Protocol 37 41 Data Quality Objectives 37 42 Survey Unit Designation and Classification 43 43 Background Determination 43 44 Final Status Survey Plans 43 45 Survey Design 43 4 6 Instrumentation 45 4 7 Survey Methodology 50 48 Quality Control Surveys 51 5 0 Survey Findings 52 5 1 Survey Data Conversion 53 52 Survey Data Verification and Validation 54 5 3 Evaluation of No of Sample and Measurement Locations in SUs 55 5 4 Comparison of Findings with Derived Concentration Guideline Levels 55 5 5 USNRC/Independent Verification Team Findings 56 6 0 Summary 56 7 0 References 56 8 0 Appendices 60 Rev 2 I Connect c t Yankee Atomic Power Company Haddam Neck Plant F nal Status Su vey Final Report -Phase V July 2007 LIST OF TABLES 1 1 Phase V Su-rvey Unit Classificatitn and Derilption List 5-2 1 Derived Concentration Guideline Levels for Soil 15 2 2 HNP LTP Compliance Equation 5 1 Values and Actual Soil Dose 16 2 3 FSS Area Classifications 18 2 4 Easy to Detect (ETD) and Hard to Detect (HTD) Radionuchdes 20 4 1 Action Levels 40 42 Number of Samples for FSS 44 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 50 4 6 Summary of Total Area Scanned 50 5 1 Summary of Statistical Analysis for Soil Samples 53 LIST OF FIGURES 1 1 Phase V Submittal 6 1 2 FSS Final Report Phased Submittal Areas 10 2 1 FSS Orgamnzational Chart 12 Rev 2 2 Co ect t Ya kee Atom c Pow r Compa y Haddam Neck Plant Final Status Survey Final Report -Ph se V July 2007 10 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 d uot tte ". t', Con' tcu v Atom c Po Ner Comppay s Haddam Neck Plant (HNP) site or portions of the site meets 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 Integrated Site Closure (ISC) memo 06 024 Initial Target Operational DCGLs 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 1575 Multi Agency Radiation Survey and Site Investigation Manual (MARSSIM) (Reference 7 3) HNP program document ISC GQP 00001 003 Final Status Survey Quality Assurance Plan (Reference 7 4) HNP procedure GPP GGGR R5120 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 Decommissiomng Guidance Characterization Survey and Determination of Radiological Criteria (Reference

76) MARSSIM and the requirements specified in GPP GGGR R5122 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 Umt 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 denrved results Rev 2 3 Con eet t Yankee Atom c Power Comp y Haddam Neck Plant Final Status Survey Ftual Report -Ph se V July 2007 This report contains a compilation of twelve (12) Survey Unit Release Records that are within the Phase V scope The Phase V FSS Final Report specifically addresses twelve (12) lowland survey areas of the HNP site that total approximately thirty three (33) surface acres in size (132 166 M 2) Table 1 1 provides a listing of all survey units addressed in this report including the classification and general description for each Figu e 1 1 depictq the locations of the survey unit- 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 performed the FSS of the Phase V survey units The survey data for all Phase V 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 IOCFR20 1402 (see Table 2 2) The additional requirement of 10CFR20 1402 that all residual radioactivity be reduced to levels that are As Low As Reasonably Achievable (ALARA)has been satisfied Rev 2 4 Connecticut Yankee Atom c Powe Company Final Status Survey Final Report -Phase V Haddam Neck Plant July 2007 Table 1 1 Phase V Surey Unit Classification and Description List Survey Survey Class General Description of the Survey Unit ()Area Unit 9520 0001 2 Southwest Site Storage Area surface area ( 0 m2)9520 0002 2 Southwest Site Storage Area surface area (9 720 m 2)9520 0003 2 Southwest Site Storage Area surface area (8 106 M 2)9520 0004 1 Southwest Site Storage Area surface area (1 985 mn 2)9520 0005 1 Southwest Site Storage Area surface area (1 887 M 2)9530 0001 2 Central Peninsula surface area (5 753 in 2)9530 0002 2 Central Peninsula surface area (6438 M 2)9530 0003 2 Central Peninsula surface area (6438 M 2)9530 0004 3 Central Peninsula surface area (83 777 M 2)9805 0000 C Subsurface Area Associated With The Peninsula (excluding Survey Unit 9531) subsurface area (130 380 M 2)9807 0000 B Subsurface Area Associated With The Southwest Site Storage Area subsurface area (1 983 in )9520 0006 1 Southwest Site Storage Area surface area (1 808 M 2)(1) Refer to Secti n 3 2 for a more deta led desc iption Rev 2 5 Connecticut Yankee Atomic Power Company Final Status Survey Final Report -Phase V 1-1, Phase CL&P Property--t I, V., F Haddam Neck Plant July 2007 V Submittal INITIAL CREATION DATE: 11/15/04 CREATED BY:" 3e Charleroy S1TE 1OPER1Y UNE SITE BOUNDARY REVISION DATE: N/A SURVEY AREA BOUNDAI REVISION #: 0 MAP#: 1-2 COE CONNECTICUTYANKEE ATOMIC POWER COMPANYGENERAL ARRANGEMENT DRAWING Final Status Survey r Final Report Phased V Survey Areas 6 Co ecticut Yankee Atom Powe Company Haddam Ne kPI t Final Status Survey Final Repo t -Ph se V July 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 HNP 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 IOCFR50 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 IOCFR20 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 II FSS Final Report On March 8 2005 HNP submitted a request to release a portion of the HNP site (Reference 7 11) from the 10CFR50 License (DPR61)Specifically the request addressed the removal and release of the fourteen (14) surface survey umts and one (1) subsurface survey unit which collectively made up the area defined as Phase II 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 1OCFR20 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 II 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 commumcations with the USNRC staff four (4) survey umt release records were revised to further clanfy specific techmcal issues Revision Rev 2 7 Con ect cut Yankee Atomic Power Company Haddam Neck Plant Final St tits Survey Final Report -Phase V July 2007 1 of the Phase III report and the associated revised release records were submitted to the USNRC on September 9 2006 (Reference 7 15)Phases IV 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 Phases V The subject of this report Phases V. VI and VII Final Reports As discussed above HNP anticipates at least two (2) additional FSS Final Report submittals Below is a list of the remaining survey areas grouped by phase with the approximate submittal date Details on the number description and location of survey units within each survey area can be found in Chapter 2 of the HNP LTP The schedule and identity of survey areas included in each of the remaining submittals were developed based on a review of the demolition and Final Status Survey schedule as well as in consideration of USNRC review requirements The demolition schedule including the cleanup of demolition debris to permit access for FSS is dynamic and subject to continued refinement in logic durations and completion dates It is HNP s intent to maintain the basic submittal milestone schedule provided below However because of potential changes in the decommissioning schedule it is possible that additional interim submittals will be filed with the USNRC with the goal of providing Survey Unit Release Records as soon as possible to support the agency s review as well as HNP s goals regarding the release of site lands from the license Phase VI FSS Final Report Submittal scheduled for February 2007 (15 Release Records)9304 0001 Southwest Protected Area Grounds 9304 0002 Southwest Protected Area Grounds 9504 0000 Bypass Road and Secondary Parking Lot 9506 0000 North Site Grounds (Non Protected Area)9512 0000 Northwest Site Grounds (Non Protected Area)9522 0001 Southeast Site Grounds (Non Protected Area)Rev 2 8 Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status St vey Final Report -Phase V July 2007 9522 0002 9522 0003 9522 0004 9522 0005 9522 0006 9522 0007 9539 0001 9539 0002 9804 0000 Southeast Site Grounds (Non Protected Area)Southeast Site Grounds (Non Protected Area)Southeast Site Grounds (Non Protected Area)Southeast Site Grounds (Non Protected Area)Southeast Site Grounds (Non Protected Area)Southeast Site Grounds (Non Protected Area)ISFSI Haul Road ISFSI Haul Road Subsurface Soils Associated with 9522 Phase VII FSS Final Report Submittal scheduled for May 2007 (19 Release Records)9302 0000 9306 0000 9312 0001 9312 0002 9312 0003 9312 0004 9312 0005 9312 0006 9312 0007 9312 0008 9312 0009 9312 0010 9313 0000 9514 0000 9527 0001 9527 0002 9801 0000 9802 0000 9803 0000 Northwest Protected Area Grounds South Central Protected Area Grounds Northeast Protected Area Grounds Northeast Protected Area Grounds Northeast Protected Area Grounds Northeast Protected Area Grounds Northeast Protected Area Grounds Northeast Protected Area Grounds Northeast Protected Area Grounds Northeast Protected Area Grounds Northeast Protected Area Grounds Northeast Protected Area Grounds Central site Grounds Primary Parking Lot East Mountain Side East Mountain Side Subsurface Soils in Radiologically Controlled Area Subsurface Soils Associated with 9308 Subsurface Soils Located North of Industrial Area Rev 2 9 Connecticut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Final Report- Phase V December, 2006 Rev 2 10 Connect t Yankee Atomic Powe Compa y Haddam Neck Pla t Fi tal Status Survey Fin I Repo t -P1 ase V July 2007 20 FINAL STATUS SURVEY PROGRAM OVERVIEW The FSS Program consists of the methods used in planning designing conducting and evaluating FSS activities at the INP site to demonstrate that the premises are suitable for release in accordance with the criteria for decommissioning in Title 10CFR20 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 IOCFR20 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 mrem/yr) 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 Integrated Site Closure 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 HNP 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 Project Support Directorate Rev 2 11 Co ne tcutY keeAt m Pow Comp y H ddam N k PI t Fin 1 Status Survey F nal Report -Phase V July 2007 Figure 2 1 FSS Organizational Chart Director of Project Support I RP/ FSS Maria I ~ II Ground Water RCRA 1niern Engineering Health [ Project Physics Controls Techmcal Support Group Manager I ner F FSS Engineers I Integrated Site Closure Group Rev 2 12 Connecticut Yankee Atomic Power Compa y Haddam Neck Plant F 1al St tus Surv y Final Repo I -PI ase V July 2007 2 1 Survey Planning After termination of commercial operations the imtial 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 interviews 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 imtial 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 14NP site into manageable areas or units for survey and classification purposes and To determine the imtial 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 R5111 002 Preparation of Final Status Survey Plans (RPM 5 1 11) (Reference 7 17) is a senes of graded planning steps found to be effective in establishing criteria for data quality and developing survey plans Rev 2 13 Connect e t Ya kee Atomic Powe Company Haddam Neck Plant Final Status Su ey Final Report -Phase V July 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 HNP 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 HNP LTP must be performed to ensure compliance with the release criteria of twenty five (25) mrem/yr TEDE when all three pathways (soil existing groundwater and future groundwater) are potentially present Chapter 5 of the HNP 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 2 of the HNP LTP Table 2 1 provides a listing of the Base Case and required MDC values Rev 2 14 Co nect ut Yankee Atomic Power Company Haddam Neck Plant Co nect ut Yankee Atomic Power Company Haddam Neck Plant Final Status Survey Fim I Repo t -Phase V July 2007 Table 2 1 Derived Concentration Guideline Levels for Soil Base Case Soil Required MDC (pCilg)Radionuclide DCGL (pCi/g)(25 mrem/yr) (1 0 mrem/yr)H 3 4 12E+02 1 65E+01 C 14 5 66E+00 2 26E 01 Mn 54 1 74E+01 6 96E 01 Fe-55 2 74E+04 1 I0E+03 Co 60 3 81E+00 I 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 1 26E+01 5 04E 01 Ag 108m 7 14E+00 2 86E 01 Cs 134 4 67E+00 I 87E 01 Cs 137 7 91E+00 3 16E 01 Eu 152 1 01E+01 4 04E 01 Eu 154 9 29E+00 3 72E 01 Eu 155 3 92E+02 1 57E+01 Pu 238 2 96E+01 I 18E+00 Pu 239/240 2 67E+01 1 07E+00 Pu 241 8 70E+02 3 48E+01-Am 241 2 58E+01 -1 03E+00 Cm 243/244 2 90E+01 1 16E+00 (1) Bold indicates those adionuclides cons d ed to be Ha d 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 (HT ta) from all three (3) media which is shown below HT I can be expressed as HT I = HS I + HE GW + HF GW (HNP LTP Equation 5 1)Rev 2 15 Connecticut Yankee Atom Power Compa y Haddam Neck Plant Fi tal Status Survey Final Report -Ph se V July 2007 The total dose HT t I under the LTP criteria is twenty five (25) mrem/yr TEDE from all three (3) components The allowable total dose under the CTDEP radiological remediation standard for the HNP is mneteen (19)mrem/yr TEDE Therefore the value for HT tal is effectively nineteen (19) mrem/yr for all survey units To determine the Hs I (the dose equivalent for the Operational DCGLs) one must subtract the existing and future groundwater dose values as shown below Hs -= H I -HE gGW -HF GW (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 Table 2 2 I-NP LTP Compliance Equation 5 1 Values and Actual Soil Dose Existing Ground Future Ground Allowable Actual Survey Water Dose Water Dose Soil Dose Soil Dose Unit (mrem/yr) ( i) (mrem/yr) (I) (mrem/yr)

(2) (mrem/yr)

(3)9520 0001 2 0 17 0 15 9520 0002 2 0 17 032 9520 0003 2 0 17 044 95200004 2 0 17 0 15 95200005 -2 0 17- 056 9530 0001 2 0 17 035 9530 0002 2 0 17 027 9530 0003 2 0 17 078 9530 0004 2 0 17 047 9805 0000 2 0 17 008 98070000 2 0 17 047 95200006 2 0 17 038 (1) These bounding alues we e taken from ISC memo 06 024 Int al Target Operational DCGLs fo CY (Refe ence 7 2) the maximum allowable gr undwater dose is 8 mrem/yr to meet the HNP LTP release c te a for unrestricted use (2) The Operat onal DCGL dose equivalent meets the release criteria for unrestricted use as agreed to w th the CTDEP of 19 mrem/yr plus ALARA (3) The eag dos fri m d I adoa t tymsolf IlowngFSS Rev 2 16 Co ecticut Yankee Atom c Power C mpany Haddam Neck Pla t Final Status Su vey Final Repo t -P1 s V July 2007 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 Scopmg Surveys (Reference 7 18)Augmented Characterization Survey Report (Reference 7 19)Characterization Report (Reference 7 20) Historical Site Assessment Supplement (HSA) (Reference 7 21) and in files containing copies of records maintained pursuant to Title 1OCFR50 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 physical locations 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 MARSSIM 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 umts 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 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 MARSSIM were used to establish the Rev 2 17 Co necte t Yankee Atomic Power Company Haddam Ne k Pla t Fn 1 St a s Survey Final Rep I -Ph se V J ly 2007 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 Table 2 3 FSS Area Classifications Survey Unit Surface Area Limit Contamination Classification Potential Structures Class 1 (floor area) Upto10t Land Area Up to 2 000 m 2 Highest Class A Subsurface No limit Structures 100 m 2 to 1 000 m 2 Class 2 (floor area)Land Area 2 000 m 2 to 10 000 m 2 Moderate 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 22 Survey Design Final status surveys for the HNP surface soils and structures are designed following HNP 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 radionuchdes of concern and determine the concentration variability During characterization and in preparation for FSS the HNP Radiochemistry Lab using gamma spectroscopy analyzed soil samples collected from random and biased locations in the survey umts 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 Rev 2 18 Connect c t Ya kee Atomic Power Company Haddam Neck Plant F nal Status Survey Final Repo t -Ph se V July 2007 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 these 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 Strontium 90 was the most prevalent HTD radionuclide identified in samples Most radionuclides could be screened out or excluded from the survey design under HNP LTP Section 5 4 7 2 Radionuchde screemng 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/ of unity for aggregates Exceptions to this are discussed in applicable sections of this FSS Final Report and associated Survey Unit Release Records 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 1OCFR20 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 assessment Rev 2 19 Connecticut Yankee Atomic Power Company Connctiut Ynke Atoic owerComanyHaddam Neck Plant Final Status Survey F # al Repo t -Phase V July 2007 Table 2 4 Easy to Detect (ETD) and Hard to Detect (HTD) Radionuclides Radionuclide o Type When Analyzed Analysis H 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 90 HTD AS NEEDED Liquid Scintillation 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 155 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 Gamma Spectroscopy Am 241 (2) ETD ALWAYS-__ _ Alpha Spectroscopy Cm 243/244 HTD AS NEEDED Alpha Spectroscopy (1) Bold md ates those rad onucl des sidered to be Hard to Dete t (HTD)(2) Americium 241 ca be alyzed by gamma and alpha sp ctroscopy and is cons de ed to be Easy to Detect (ETD) the preferred result is the alpha spectroscopy s when both a lys are pe formed Rev 2 20 Connecticut Yankee Atom c Power Compa y Haddam Neck Plant Final Status Survey Final Report -Phase V July 2007 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 Soil sample locations were identified in North American Datum (NAD)1927 coordinates and were loaded into the GPS softwaie The FSS plan provided a map and GPS positions to FSS field supervision for reference In each survey unit a mimmum 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 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 LTP Surrogates were not required or used for 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 the DQO process assessed the application of media specific radiation background and ambient area radiation background to specific survey areas and units Based upon the DQO process the FSS planning determined that background subtraction would not be applied during the survey of the land areas included in this submittal Rev 2 21 Co ect cut Ya ke Atom c Power Company Haddam Neck Plant Fn I Status Survey Final Report -P1 ase V July 2007 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 Verification and validation of personnel training as required by procedure GPP GGGR R5400 000 Site Closure Training Program (RPM 5 4 0) (Reference 7 22)Implementation of a work control process including applicable health and safety procedures under GGGC 00001 004 Work Plan and Inspection Record (Reference 7 23)Determination of the amount of samples required to meet survey DQOs as described in GGGR R5112 001 Determination of the Number Samples for Final Status Survey (RPM 5 1 12) (Reference 7 24)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 (RPM 5 1 11) (Reference 7 17)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 25) 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 26) 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 (RPM 5 1 23) (Reference 7 27)The FSS implementation and completion process resulted in the generation of field logs and radionuclide specific analysis Data were stored electromcally on the HNP network server Rev 2 22 Connect c t Yankee Atomic Power Compa y Haddam Neck Plant Fi ial Status Survey Final Report -Phase V July 2007 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 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 appropnate further actions were implemented usually through the issue of an addendum to the FSS plan Rev 2 23 Co nect c t Yankee Atom c Powe Company Haddam Neck Pla t Final St tus Survey Fital Repo t -P1 se V July 2007 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 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 dunng FSS maintain Quality Assurance Plans designed for their facility HNP reviews these plans as required by the Quality Assurance Program for the Haddam Neck Plant (CYQAP) (Reference 7 28) 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 Rev 2 24 Connect c t Yankee Atomic Power Company Haddam Neck Plant Fm I St tus Survey Fi i 1R port -Pl ase V July 2007 The Site Closure Group has established a Curriculum Advisory Committee (CAC) a training committee

-that is complised 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 training and qualifications programs and ensure the appropriate design development and implementation of the Site Closure training program During 2006 one (1) Quality Surveillance Report (QSR) was produced on activities related to FSS In general these reports were performed to evaluate the adequacy of the implementation of regulatory and HNP LTP and FSS requirements QSR 06 01 CY (Reference 7 29) performed during January of 2006 concluded that a sampling of the Survey Unit Release Records to be submitted in Phase III met the HNP 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 A05 01 (Reference 7 30) 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 As of early December the Integrated Site Closure 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 31) performed in April 2006 was performed as a follow up to Condition Report (CR) 05 781 (Reference 7 32) The issues identified involved soil sample collection particularly samples used for quality control The Self Assessment provided recommendations for Improvement Rev 2 25 Connectic t Yankee Atom c Power Company Haddam Neck Plant Final Status Survey Fi 1 I Repo t -Phase V July 2007 SCA 06 02 (Reference 7 33) performed in August 2006 noted that personnel and staffing changes had been implemented since major FSS field activities were last performed 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 34) performed in November 2006 was performed as an investigation of the cause of Condition Report (CR) 06 0223 (Reference 7 35) The CR identified an issue with split sample agreement The Self Assessment observed that media homogenization for samples from the pond and discharge canal was 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 homogemzation 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 QSR 06 007 (Reference 7 36) performed during November of 2006 into concluded that a sampling of the Survey Unit Release Records to be submitted in Phase III and Phase IV was consistent with the HNP LTP and FSS programmatic requirements QSR 06 008 (Reference 7 37) 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 HNP LTP and FSS programmatic requirements All findings from the QSRs audits and assessments were corrected and systematic controls implemented as of the publication date of this report 3 0 SITE INFORMATION 3 1 Site Description Haddam Neck Plant owned by Connecticut Yankee Atonuc Power Company is located on the east bank of the Connecticut River approximately twenty one (21) miles south southeast of Hartford The site consists of approximately five hundred twenty five (525) acres with a mimmum distance overland from the reactor containment to the site boundary of one thousand seven hundred and forty feet (1 740 fi) and the distance to the nearest residence is over two thousand feet (2 000 ft)Rev 2 26 Connect cut Y k e Atomic Powe Comp ny Haddam Neck P1 nt Fit I Status Survey Fit 1 Repo t -Phase V July 2007 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 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 mechamcal and electrical equipment which it normally manufactures Stone and Webster Engineering Corporation were responsible for site development design of buildings and secondary systems and all plant construction Each of these contractors was 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 HNP permanently shut down after approximately 28 years of operation On December 5 1996 HNP notified the USNRC of the permanent cessation of operations at the HNP site and the permanent removal of all fuel assemblies from the Reactor Pressure Vessel and their placement in the Spent Fuel Pool Following the cessation of operations HNP began the decommissiomng of the site The Post Shutdown Decommissiomng Activities Report (PSDAR) (Reference 7 38) was submitted in accordance with Title 1OCFR50 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 39) to reflect the plant s permanent shutdown status and on June 30 1998 the USNRC amended the HNP Facility Operating License to reflect the plant condition On October 19 1999 the HNP 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 revised and submitted to reflect long term fuel storage in the spent fuel pool (Defueled Emergency Plan Security Plan QA program and Operator Traimng Program)In 1997 in accordance with NUJREG/CR 5849 (Reference 7 40) imtial site characterization was implemented In 1999 following the guidelines of MARSSIM initial characterization was completed The information developed during the initial HNP characterization program represented a radiological assessment based on the knowledge and information available at the end of 1999 Rev 2 27 Co e t c t Y nkee Atom c Power Company Haddam Neck Pla t Final Status Sui vey Final Repo I -Phase V July 2007 3 2 Survey Area/Unit Description The following information is a description of each survey unit at the time of FSS from August through July 2007 (additional detail is provided in the Survey Unit Release Records) During this period the approximately thirty three (33) acres of open land areas of the HNP site received a FSS The HNP 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 an accessible iron pin 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 Release Records to this FSS Final Report Survey Unit 9520 0001 Survey Unit 9520 0001 (Southwest Site Storage Area) is designated as Class 2 and consists of 8 062 m 2 (2 0 acres) of uninhabited open land located approximately 1 804 feet from the reference coordinate system benchmark used at HNP The survey umt is relatively level open space in the north end of the peninsula The restoration of the peninsula for FSS had removed most of the surface interference in the survey unit Survey Unit 9520 0002 Survey Unit 9520 0002 (Southwest Site Storage Area) is designated as Class 2 and consists of 9 720 m 2 (2 4 acres) of uninhabited open land located approximately 1 167 feet from the reference coordinate system benchmark used at HNP The survey unit is relatively level open space in theiiorth-end of the peninsula The restoration of the pemnsula for FSS had removed most of the surface interference (small trees dense brush and invasive phragmite

-a tall common plant that grows in large colonies)in the survey unit Survey Unit 9520 0003 Survey Unit 9520 0003 (Southwest Site Storage Area) is designated as Class 2 and consists of 8 106 m 2 (2 0 acres) of uninhabited open land located approximately 1 661 feet from the reference coordinate system benchmark used at HNP The survey unit is relatively level open space in the north end of the peninsula The restoration of the peninsula for FSS had removed most of the surface interference (small trees dense brush and invasive phragmite) in the survey unit Survey Unit 9520 0004 Survey Unit 9520 0004 (Southwest Site Storage Area) is designated as Class 1 and consists of 1 985 m 2 (0 5 acres) of uninhabited open land located approximately 1 860 feet from the reference coordinate system Rev 2 28 Connecticut Yankee Atom c Powe Company Haddam Neck Plant Final Status Surv y Fin I Repo t -Ph se V July 2007 benchmark used at HNP The survey unit was initially included in Survey Unit 9520 0003 a Class 2 survey unit However in March of 2006 Co 60 and Cs 137 were identified in subsurface soils in sufficient quantities to warrant radiological remediation Radiological remediation was performed in July 2006 A new Class 1 survey unit Survey Unit 9520 0004 was established to bound the area of remediation The survey unit is relatively level open space in the north end of the peninsula The restoration of the peninsula for FSS had removed most of the surface interference (small trees dense brush and invasive phragmite) in the survey unit Survey Unit 9520 0005 Survey Unit 9520 0005 (Southwest Site Storage Area) is designated as Class 1 and consists of 1 887 m 2 (0 5 acres) of uninhabited open land located approximately 1 661 feet from the reference coordinate system benchmark used at HNP The survey unit was initially included in Survey Unit 9520 0003 a Class 2 survey unit In October of 2006 Co 60 was identified in soil in sufficient concentrations to warrant a Class 1 designation for a new Survey Unit 9520 0005 within the original boundaries of 9520 0003 The survey unit is relatively level open space in the north end of the peninsula The restoration of the peninsula for FSS had removed most of the surface interference (small trees dense brush and invasive phragmite) in the survey unit Survey Unit 9530 0001 Survey Unit 9530 0001 (Central Peninsula) is designated as Class 2 and consists of 5 753 m2 (1 4 acres) of uninhabited open land located approximately 2 294 feet from the reference coordinate system benchmark used at HNP The survey unit is set within Survey Unit 9530 0004 a Class 3 survey unit The survey unit is relatively level open space in the middle of the peninsula The restoration of the peninsula for FSS had removed most surface interference in the survey unit however there were some trees and brush remaining in the area Survey Unit 9530 0002 Survey Unit 9530 0002 (Central Peninsula) is designated as Class 2 and consists of 6 438 m2 (1 6 acres) of uninhabited open land located approximately 2 900 feet from the reference coordinate system benchmark used at HNP The survey unit is set within Survey Unit 9530 0004 a Class 3 survey unit The survey unit is relatively level open space in the middle of the peninsula The restoration of the peninsula for FSS had removed most of the surface interference (invasive phragmite) in the survey unit Rev 2 29 Co nectlc t Yankee Atom c Powe Company Haddam Ne k Plant FD al Status Survey Final Report -Phase V July 2007 Survey Unit 9530 0003 Survey Unit 9530 0003 (Central Peninsula) is designated as Class 2 and consists of 6 438 m 2 (16 acres) of uninhabited open land located approximately 3 160 feet from the reference coordinate system benchmark used at HNP The survey unit is set within Survey Unit 9530 0004 a Class 3 survey unit The survey unit is relatively level open space in the middle of the peninsula The restoration of the peninsula for FSS had removed most of the surface interference (invasive phragmite) in the survey unit Survey Unit 9530 0004 Survey Unit 9530 0004 (Central Peninsula) is designated as Class 3 and consists of 83 777 m2 (21 acres) of uninhabited open land located approximately 2 100 feet from the reference coordinate system benchmark used at HNP The survey unit is relatively level open space in the middle of the peninsula The restoration of the peninsula for FSS has removed some surface interference in the survey unit Survey Unit 9805 0000 Survey Unit 9805 0000 (Subsurface Area Associated With The Peninsula) is designated as Class C (subsurface classification) and consists of 130 380 m 2 (32 acres) of uninhabited open land located approximately 750 feet from the reference coordinate system benchmark used at HNP The subsurface survey unit is within the physical boundary of surface Survey Unit 9520 0004 The survey unit does not include the 1 983 m2 associated with the land area of Survey Unit 9807 0000 a separate subsurface area which is located within Survey Area 9805 The restoration of the peninsula for FSS has removed some of the surface interference in the survey unit Survey Unit 9807 0000 Survey Unit 9807 0000 (Subsurface Area associated with the Southwest Site Storage Area) is designated as Class B (subsurface) and consists of 1 983 mn (0 5 acres) of uninhabited open land located approximately 1 860 feet from the reference coordinate system benchmark used at HNP The surface land unit that resides above this subsurface survey unit is relatively level open space of the peninsula The restoration of the peninsula for FSS has removed all of the surface interference in the survey unit Survey Unit 9520 0006 Survey Unit 9520 0006 (Southwest Site Storage Area) is designated as Class 1 and consists of 1 808 m 2 (0 5 acres) of uninhabited open land located approximately 1 804 feet from the reference coordinate system benchmark used at HNP The survey unit was initially included in Survey Rev 2 30 Con ect cut Yankee Atomic Power Comp ny Haddam Neck Plant Final Status Survey Final Repo t -P1 se V July 2007 Unit 9520 0001 a Class 2 survey unit Following the completion of FSS the area was used to stockpile radiologically clean rubblized asphalt intended to be used to pave the ISFSI access road after final site grading was complete In June of 2007 a surveillance survey was performed on the surface soils under the asphalt pile following the removal of the pile Removal of the pile had removed additional soil below the original grade and exposed additional buried commodities In addition two elevated areas were identified at the same location On site analysis of soil samples indicated the presence of Co 60 and Cs 137 in sufficient concentrations to warrant remediation and a Class 1 designation for this new survey unit The FSS of this survey unit occurred after the submittal of Revision I to the Phase V Final Report Inclusion of this survey unit into Phase V resulted in Revision 2 to the Phase V submittal The survey unit is relatively level open space in the north end of the peninsula Remediation activities had removed most of the surface interference (small trees dense brush and invasive phragmite) in the survey unit 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 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 18 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 Radioactive 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 Rev 2 31 Connect c t Ya kee Atom c Power Company Haddam Neck Pla t Fiual Status Survey Fulal Repo I -Phase V July 2007 Contamination of the yard area around the Borated 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" Spill of component cooling water to the storm dram in March 1990* Leak from the refueling 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 comer of site starting in 1974 3 3 2 Characterization Surveys The characterization of 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 initial classification of areas" Provide a basis for remediation planmng including recommendations for additional surveys or samples and Provide input into the FSS design Rev 2 32 Conne t cut Yankee Atom c Power Company Haddam Neck Plant Final St I s Survey Fm I Repo I -Ph se V July 2007 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 1OCFR50 75(g)(1) 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 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 ownier dontrolled hillside locationis east of the plant and Leakage of water containing radioactive material that was documented historically Incidents of this nature included lealkng 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 information provided in the NRC Historical Review Team Report -Radiological Control and Area Contamination Issues at Haddam Neck (Reference 7 41) dated March 26 1998 to assure completeness of the historical data The Characterization Report provided an assessment of the radiological and hazardous matenal 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 Rev 2 33 Co nect c t Yankee Atom c Power Comp y Haddam Neck Pla t Fm I St tit Survey Fi ial Rep t- Plase V July 2007 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 HNP 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 42) This evaluation determined that remediation beyond that required to satisfy the release criteria to be 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) were performed on three (3) survey units (9520 0005 9807 0000 and 9520 0006) It was determined that the remediation was completed when the concentrations of residual radioactivity within the survey unit were below the 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 Clearing of heavy brush and invasive phragmite was performed prior to FSS to improve safety and facilitate survey and sampling Prior to FSS areas ready for survey were isolated and controlled under procedure GGGR R5116 002 Area Preparation for Final Status Survey Activities RPM 5 1 16 (Reference 7 43) This included posting of the areas as well as notifications to site personnel Permission to enter and Rev 2 34 Co ect c t Ya kee Atom c Powe Company Haddam Neck Plant Co ect C t Ya kee Atom c Powe Company Haddam Neck Plant Fatal Status Survey Final Repo I -Phase V July 2007 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 Removal of material and restoration of the peninsula for FSS has been ongoing since 2000 starting with the radiological release of the South Access Point and several abandoned trailers The collapse of the Radioactive Material(s)

Area (RMA) boundary and removal of subsurface commodities has produced a large data set that has helped characterize the radiological contaminants of concern and extent of contamination In 2006 utilities were being removed as part of the decommissiomng effort on the Upper Pemnsula Construction debris including Asbestos Containing Material (ACM) was identified and remediated Radiological assessments were performed on the excavated soil and debris In addition to the ACM several objects were also identified that had detectable radioactivity Two pieces of angle iron were located in a water utility trench in adjacent Survey Umt 9530 0004 Most of the work involved two areas adjacent to Survey Umt 9530 0001 Some of the excavated spoils from these areas were temporarily stored in Survey Umt 9530 0001 during the investigation To assess the extent of this condition supplemental characterization consisting of geophysical (electro magnetic high resolution metal detection) surveys and test pitting was conducted on the peninsula Most of the geophysical survey data was collected from the upper and central portion of the peninsula as tlus is where the majority of industrial support and storage activities were known to have taken place However portions of the lower peninsula were surveyed to confirm that this area was not used for equipment storage or debris burial The geophysical survey was meant to screen for the presence or absence of buried metallic objects Geophysical surveying was completed in four separate phases during the spring of 2006 Following the geophysical survey suspect areas were targeted for test pitting to confirm the presence of metal and characterize the nature of the geophysical responses (e g objects that could be the size Rev 2 35 Connect cut Yankee Atom c Power Compa y Haddam Neck Plant Final St lus Survey Fi al Repo I -Phase V July 2007 of a portion of a 55 gallon drum) Chemical samples were collected based on observations made during test pitting and radiological assessment surveys were performed on all encountered debris and test pit soils A total of 130 test pit locations were performed on the peninsula thirty four (34) test pits completed during the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) program (Reference 7 44)eighty eight (88) test pits to characterize the geophysical survey anomalies and eight (8) additional test pits at the request of the CTDEP (Reference 7 45)The radiological assessments and characterization surveys identified Cs 137 and Co 60 as the primary radionuchdes of concern Other radionuchdes from both the ETD and HTD list provided in Table 2 4 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 standard deviations uncertainty In almost every case radionuclides that were considered detected by the IINP criterion were reported in concentrations that were less than the MDC All the radionuclides listed in Table 2 4 were included in the DQO process when desigmng an FSS plan and during the DQA when reviewing the adequacy of the FSS plan Rev 2 36 Co ect cut Yanke Atom c Powe Comp ny Hadd m Neck Pla t Fi I Stat; s Survey Final Report -Phase V July 2007 3 6 Radiological Release Criteria The radiological release criteria is based on Title 1OCFR20 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) mrem/yr 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 twenty five (25)mrem/yr 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 HNP 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 Stakeholders 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 Integrated Site Closure personnel The primary decision maker was the assigned FSS Engineer The FSS Engineer obtained input from HNP Project Support on issues relating to schedule and costs 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 11971 qualified Health Physics Technicians to perform fieldwork FSS Engineers to prepare the plan generate maps coordinate field activities and evaluate data An off Rev 2 37 Connect cut Ya kee Atom c Power Company Haddam Neck Pla t F I Stt S rveyFinal Rp t -P1 se V July 2007 site laboratory would be needed to analyze the samples and provide quality radionuclide specific results IDENTIFY THE DECISION Pt incipal Study 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 unrestnicted 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 IOCFR50 75(g)(1) 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 ten (10) of the twelve (12) survey umits The samples were collected with new or decontaminated tools to----mimimize cross contamination between sampling Judgmental samples were taken in the area where remedial action had occurred or 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 two (2) of the twelve (12) survey units Subsurface soil was collected using direct push equipment to obtain 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 Rev 2 38 Connect cut Yankee Atomic Power Company Haddam Neck Plant Fiual Status Su vey Final Report -Ph s V July 2007 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 DCGL Table 2 1 lists twenty (20)radionuchdes potentially present at the site Derived Concentration Guideline Levels (DCGLs) were calculated for each of the radionuchdes listed based on a limit of twenty five (25) mrem/yr USNRC dose limit and a CTDEP dose limit of nineteen (19) mrem/yr 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 HNP LTP Equation 5 1 expresses the total dose (HT tal) from all three (3) media which is shown below HT I can be expressed as H I=Hst+Ha GW +HF GW (HNP LTP Equation 5 1)The dose contribution from the existing groundwater and future groundwater contamination the second and third components of HNP 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 radionuchdes 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 minmum of 5/ of the samples required for compliance were analyzed for all radionuclides listed in Table 2 4 Any radionuchdes 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 A decision to use or not use surrogate DCGLs was evaluated based on radionuchde analysis During Phase V FSS no surrogates were used Survey and Analysis Methods to Meet the Data Requirements The HNP LTP requires that MDCs for fixed measurements (samples are considered fixed measurements) be as far below the DCGL as Rev 2 39 Connecticut Yankee Atom c Power Company Haddam Neck Plant Final St tit Survey Fi tal Repo I -Ph se V July 2007 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 1 survey units For each Class 1 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 HNP 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 Table 4-1 Action Levels Evaluation Result Conclusion 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 () but an individual sample exceeds Operational DCGL I')Rev 2 40 Con ecticut Yankee Atom c Powe Compa y Haddam Neck Plant Final Status Survey Final Report -Ph se V July 2007 Table 4 1 Action Levels Evaluation Result Conclusion The average concentration exceeds Implement alternative actions Operational DCGL (1) the survey unit does not meet the release criterion (1) Used in conjunction w th the un ty 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 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 radionuchdes of interest exceed the Operational DCGLs or the Sign Test falls 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 error This is the error associated with incorrectly concluding that the null hypothesis was rejected The HNP LTP has set the at error at 0 05 (5/) unless prior approval is granted from the USNRC to use a less restnctive value Therefore a value of 0 05 (5/) was used for survey planning and data assessment for FSS Type II Error This is the P3 error This is the error associated with incorrectly concluding that the null hypothesis was accepted A value of 0 05 (5/) was used for survey planmng and data assessment for these survey umts The Lower Bound of the Gray Region (LBGR) The LBGR is set or adjusted during the optimization phase of the DQO process Rev 2 41 Co ect c t Yankee Atomic Power Company Haddam Neck Pla t Final St tus Survey Fit al Rep t -P1 ase V July 2007 Relative Shift (A/a) 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 46)Number of samples for non parametric statistical sampling The number of samples for non parametric statistical sampling was determined using Reference 7 24 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 47) 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 samphng 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 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 10/ 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 Investigation 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 In two (2) instances an Rev 2 42 Connecticut Ya kee Atomic Power Company Haddam Neck Plant Final Status Survey Fin I Repo t -Phase V July 2007 investigation resulted in the creation of new Class I survey units Survey Unit 9520 0005 and 9520 0006 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 V FSS designs 4 2 Survey Unit Designation and Classification Procedure RPM 5 1 10 Survey Unit Classification (Reference 7 48)defines the decision process for classifying an area in accordance with the HNP LTP and MARSSIM During the FSS of areas submitted for Phase V FSS Final Report two (2) survey units were subdivided and reclassified 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 technician 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 4 5 Survey Design 4 5 1 Determination of Number of Data Points The number of samples was determined in accordance with Reference 7 24 A summary of survey design data points is provided in Table 4 2 Rev 2 43 Co et cut Yank e Atom c Power Company Hadd mn Neck Pla t Final Status Survey Fit iI Report -Phase V July 2007 Table 4 2 Number of Samples for FSS Survey Unit Sun ey Design Biased Investigation Samples Samples (1) Samples 95200001 15 0 0 95200002 15 5 4 95200003 15 5 4 9520 0004 15 2 9520 0005 15 3 14 9530 0001 15 2 1 9530 0002 15 2 9530 0003 15 1 9530 0004 15 3 7 9805 0000 15 5 9807 0000 25 95200006 15 6 0 (1) The n mbe of biased samples was determin d d ring the DQO p ocess and augmented as necessary by addendums to th FSS plan 4 52 Sample Locations Locations of the samples were determined using VSP in accordance with Reference 7 47 VSP was verified and validated by Health Physics Techmcal Support Document (TSD) BCY HP 0079 Use and Verification of Visual Sample Plan (Reference 7 50) The TSD contains documentation including a user s manual for VSP Version 2 0 and venfication 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 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)

Rev 2 44 Connecticut Ya kee Atomic Powe Company Haddam Neck Plant F ISt tu SurvyF 1Rp t-PhaseV July 2007 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 52 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 HNP 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 53)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 Table 4 3 SPA 3 Technical Details and Specifications Application High sensitivity gamma measurements 2 inch diameter by 2 inch thick NaI(TI)(5 1 centimeter x 5 1 centimeter)

Operating 1 000 volt nominal Voltage Dead Time 14 jts nominal Background

-1 2 Mcpm/mRfh Sensitivity (Cs 137)Energy Range 60 keV to 2 MeV Operating 22 to +140 F Temperature (30 to +60 C)Rev 2 45 Connecticut Yankee Atom e Power Company Haddam Neck Plant F n I Statis Su ey Fn iR po t- PI e V July 2007 Table 4 3 SPA 3 Technical Details and Specifications Application High sensitivity gamma measurements 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 52 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 The methodology was consistent with guidance provided m NUREG 1507 Mimmum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions (Reference 7 54)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 -Ambient Background Count Rates Associated NIDCR s and Investigation Levels Background (cpm) MDCR (cpm) Investigation Level 2500 714 3214 3000 782 3782 3500 845 4345 4000 903 4903 4500 958 5458 Rev 2 46 Conn t cut Ya k Atom Power Company Haddam Neck Pla t Conn t cut Va k Atom Power Company Haddam Neck Pla t Final Status Survey Final Report -P1 ase V July 2007 Table 4 4 -Ambient Background Count Rates Associated MIDCR s and Investigation Levels Background (cpm) MDCR (cpm) Investigation Level 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 -15000 1749 16749 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 Rev 2 47 Co nect ut Ya kee Atom c Power Company Haddam Ne k PI nt Co nect at Ya kee Atom c Power Company Haddam Ne k P1 nt Final Status Survey Final Repo I -Phase V July 2007 Table 4 4 -Ambient Background Count Rates Associated MDCR s and Investigation Levels Background (cpm) MDCR (cpm) Investigation Level 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 -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 Rev 2 48 Co ecticut Ya kee Atom c Power Company Haddam Ne k Plant Fi tal Status Su vey Fin I Report -Ph V July 2007 Table 4 4 -Ambient Background Count Rates Associated MDCR s and Investigation Levels Background (cpm) MDCR (cpm) Investigation Level 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 55) provided details on the instrument for field use 4 6 4 Instrument Calibration Instruments were calibrated using NIST 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 Rev 2 49 Connect c t Yankee Atom c Power Comp ny Haddam Neck Plant Connect c t Yankee Atom c Power Comp fly Haddam Neck Plant Finaal Statuts Survey Fin~al Repo t -Phase V July 2007 47 Survey Methodology 4 71 Scan Surveys The L-INP 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 Table 4 5 Scan Coverage Survy Uit Cassficaion Required Scanning Coverage Survy Uit CassficaionFraction Class 1 100/Class 2 10/ to 100/Class 3 Judgmental 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 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 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 Table 4 6 -Smayo oa Area Scanned Survey Area in Area Survey Unit Unit Square Scanned in Percentage Classification Meters Square Scanned Meters 95200001 2 8062 1408 17 9520 0002 2 9 720 3 888 40 9520 0003 2 8 106 1 621 20 9520 0004 1 1 985 1 985 100 9520 0005 1 1 887 1 887 100 9530 0001 2 5753 863 15 Rev 2 50 Connect cut Yankee Atom c Power Company Haddam Neck Plant Fm 1 Status Su vey Final Report -Phase V July 2007 Table 4 6 -Summary of Total Area Scanned Area Survey Unit Unie Area In Scanned in Percentage SuvyUt Unit Square Square Scanned Classification Meters Meters 95300002 2 6438 773 12 9530 0003 2 6 438 773 12 9530 0004 3 83 777 4 189 5 9805 0000 B N/A N/A N/A 9807 0000 C N/A N/A N/A 9520 0006 1 1 808 1 808 100 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 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 72 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 25 establishes a method for evaluating QC split samples collected in support of FSS QC split sample data was assessed on criteria Rev 2 51 Con ecticut Ya kee Atom c Powe Company Haddam Ne k Plant F nal Status Survey Final Repo t -P1 se V July 2007 taken from the USNRC Inspection Manual Inspection Procedure 84750 Radioactive Waste Treatment and Effluent and Environmental Monitoring March 1994 (Reference 7 51)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 as ess 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 25)To maintain the quality of the FSS isolation and control measures are implemented until there is no risk of recontamination from decommissiomng 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 measure-sare compromised--a follow up suirvey may be perf0rinmd after evaluation 5 0 SURVEY FINDINGS Reference 7 27 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 applies for these surveys would be commensurate with the objectives of the particular survey The DQA process is the primary evaluation tool to determine that 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 HNP LTP) The five steps of the DQAs process are Review the sample plan Data Quality Objectives (DQOs) and the survey design Rev 2 52 Co nect cut Yankee Atom c Powe Company Haddam Neck Plant Co nect cut Yankee Atom c Powe Company Haddam Neck Plant Final Status Survey Final Repo I -Phase V July 2007 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 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 V The individual FSS Release Records covered by this FSS Final Report provide additional detail Table 5 1 Summary of Statistical Analysis for Soil Samples Mean Standard Actual Soil Survey Class Concentration Deviation Dose from Cs (pCilg) (pCilg) 137 (mrem/yr)9520 0001 2 4 72E 02 5 50E 02 0 15 9520 0002 2 1 03E 01 8 16E 02 032 9520 0003 2 9 32E 02 5 88E 02 044 9520 0004 1 4 64E 02 2 79E 02 0 15 9520 0005 1 8 08E 02 5 34E 02 056 9530 0001 2 1 09E 01 5 40E 02 035 9530 0002 2 8 63E 02 5 20E 02 027 9530 0003 2 2 48E 01 1 18E 01 078 9530 0004 3 1 48E 01 1 07E 01 047 Rev 2 53 Co necticut Yankee Atom c Power Company Haddam Ne k Pla t Final St tus Survey F n I Repo I -Phase V July 2007 Table 5 1 Summary of Statistical Analysis for Soil Samples Mean Standard Actual Soil Survey Class Concentration Deviation Dose from Cs (pCl/g) (pCilg) 137 (mrem/yr)9805 0000 B 2 72E 02 2 64E 02 008 9807 0000 C 1 49E 01 6 98E 01 047 95200006 1 1 21E 01 1 71E 01 038 5 2 Survey Data Verification and Validation Items supporting DQO sample design and data were reviewed for completeness and consistency This includes Classification hustory and related documents Site description Survey design and measurement locations 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 Rev 2 54 Connecticut Yankee Atomic Power Comp ny Haddam Neck Plant Final Status Su y Funal Repo t- P1 ase V July 2007 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 umts 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 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 was collected)

The Sign Test was the selected statistical test for all Survey Unit Release Records covered under tlus FSS Final Report This test was performed in accordance with procedure RPM 5 1 21 Applying the Sign Test (Reference 7 56) 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 not required to evaluate areas 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 Rev 2 55 Connecticut Yankee Atomic Powe Company Haddam Neck Pla t Final Status Su vey Fin I Repo I -Phase V July 2007 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 DCGL may not constitute failure of the survey unit and a viable option is to do nothing more in this area 5 5 USNRC/Independent Verification Team Findings The USNRC/ORISE has not performed independent verification work in the Phase V survey areas as of the submittal date of Revision 1 of this document USNRC/ORISE has subsequently performed independent verification work in the Phase V survey areas and their reports are pending as of the date of this revision 60

SUMMARY

The twelve (12) 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 m each survey unit The second component of HNP LTP Equation 5 1 dose contribution due to existing groundwater is bounded by either 2 mrem/yr or 8 mrem/yr per note (1) of Table 2 2 The dose contribution from the third component of HNP LTP Equation 5 1 future groundwater is zero (0) since there are no underground structures systems or components containing residual radioactive matenal within the groundwater saturated zone in the survey areas 70 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 1575 Multi Agency Radiation Survey and Site Investigation Manual (MARSSIM)7 4 ISC GQP 00001 003 Final Status Survey Quality Assurance Plan (FSSQAP)Rev 2 56 Co ecticut Ya kee Atom c Powe Company Haddam Neck Plant Final Status Su vey Final Report -Phase V July 2007 7 5 GPP GGGR R5120 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 (HNP) 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 50 213)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 II March 8 2005 (CY 05 040/ Docket No 50 213)7 12 W Norton (HNP) to USNRC Letter of Intent Concerning the Phased Release (Phase II Release Area) from the Part 50 License dated October 5 2005 (CY 05 194 / Docket No 50 213)7 13 T Smith (USNRC) to W Norton (HNP) Haddam Neck Plant -Release of Phase II from Part 50 License dated February 28 2006 7 14 Final Status Survey Report Phase III May 04 2006 7 15 Final Status Survey Report -Phase III Revision 1 September 9 2006_7 16 Final Status Survey Report -Phase IV November 29 2006 7 17 GGGR R5111 002 Preparation of Final Status Survey Plans (RPM 5 1 11)7 18 Results of Scoping Surveys September 1998 7 19 Augmented Characterization Survey Report January 1999 7 20 Characterization Report January 2000 7 21 Historical Site Assessment Supplement August 2001 7 22 GPP GGGR R5400 000 Site Closure Training Program (RPM 5 4 00)7 23 GGGC 00001 004 Work Plan and Inspection Record 7 24 GGGR R5112 001 Determination of the Number of Surface and Subsurface Samples for FSS of Open Land Areas (RPM 5 1 12)7 25 GPP GGGR R5124 000 Split Sample Assessment for Final Status Survey (RPM 5 1 24)Rev 2 57 Co ect cut Ya k e Atomic Pow Company Haddam N k Plant Final Status Survey Funal Repo t -P1 ase V July 2007 7 26 GPP GGGR R51004 003 Chain of Custody for Final Status Survey Samples (RPM 5 1 5)7 27 GGGR R5123 000 Data Quality Assessment (DQA) (RPM 5 1 23)7 28 Quality Assurance Program for Haddam Nuclear Plant (QAP HNP)7 29 CY Quality Surveillance Report QSR 06 001 CY 7 30 CY Quality Assurance Audit CY 06 A06 01 7 31 Self Assessment 06 01 Final Status Survey Field Activities 7 32 CY Condition Report (CR) 05 781 7 33 Self Assessment 06 02 Final Status Survey Field Activities 7 34 Self Assessment 06 03 Final Status Survey Field Activities 7 35 Condition Report (CR) 06 223 7 36 Quality Surveillance Report QSR 06 007 7 37 Quality Surveillance Report QSR 06 008 7 38 Post Shutdown Decommissiomng Activities Report (PSDAR)7 39 Updated Final Safety Analysis Report (UFSAR)7 40 US NRC NUREG CR 5849 Manual for Conducting Radiological Surveys in Support of License Termination 7 41 NRC Historical Review Team Report -Radiological Control and Area Contamination Issues at Haddam Neck USNRC dated March 26 1998 7 42 HNP Health Physics Department Technical Support Document BCY HP 0078 ALARA Evaluation of Soil Remediation m Support of Final Status Survey 743 24265 000 GPP GGGR R5116 002 Area Preparation for Final Status Survey Activities (RPM 5 1 16)7 44 RCRA Facility Investigation Report April 2006 7 45 Peninsula Area Investigation Report July 2006 7 46 Health Physics Technical Support Document (TSD) BCY HP 0063 Background Cs 137 Concentration in Soil 7 47 GGGR R5114 001 Identifying and Marking Locations for Final Status Survey (RPM 5 1 14)7 48 GPP GGGR R5 110 001 Survey Unit Classification (RPM 5 1 10)7 49 EPRI Technical Report 1003030 Determining Background Radiation Levels in Support of Decommissiomng Nuclear Power Plants Rev 2 58 Co t t Y k e Atom Pow Compa y H ddam Neck P1 t Final Status Sit ey Fmial Report -Phase V July 2007 7 50 Health Physics Technical Support Document (TSD) BCY HP 0079 Use and Verification of Visual Sample Plan 7 51 USNRC Inspection Manual Inspection Procedure 84750 Radioactive Waste Treatment and Effluent and Environmental Monitoring March 1994 7 52 Health Physics Technical Support Document BCY HP 0081 Scan MDC of Land Areas using a 2 inch by 2 inch Sodium Iodide Detector 7 53 GGGR R4206 003 RPM Calibration of the Eberline SPA 3 Smart Probe (RPM 4 2 14)7 54 NUREG 1507 Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions December 1997 7 55 GPP GGGR RPM 5 2 1 Setup and Operation of the E 600 Digital Survey Instrument for Scoping Characterization and Final Status Surveys 7 56 GPP GGGR R5121 001 Applying the Sign Test (RPM 5 1 21)Rev 2 59 Co nect cut Ya kee Atom c Pow r Compa y Final Status Survey Final Report -Phase V 8 0 Appendices Al Survey Unit Release Record 9520 0001 A2 Survey Unit Release Record 9520 0002 A3 Survey Unit Release Record 9520 0003 A4 Survey Unit Release Record 9520 0004 A5 Survey Unit Release Record 9520 0005 A6 Survey Unit Release Record 9530 0001 A7 Survey Unit Release Record 9530 0002 A8 Survey Unit Release Record 9530 0003 A9 Survey Unit Release Record 9530 0004 AlO Survey Umt Release Record 9805 0000 the Pemnsula Haddam Neck Plant July 2007 Southwest Site Storage Area Southwest Site Storage Area Southwest Site Storage Area Southwest Site Storage Area Southwest Site Storage Area Central Peninsula Central Peninsula Central Peninsula Central Peninsula Subsurface Area associated with Al1 Survey Unit Release Record 9807 Subsurface Area associated with the Southwest Site Storage Area A12 Survey Unit Release Record 9520 0006 Southwest Site Storage Area Rev 2 60