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| number = ML17208A122
| number = ML17208A122
| issue date = 02/27/2017
| issue date = 02/27/2017
| title = Zion Ltp Ch 2 Rev 1 022017 L
| title = LTP Ch 2 Rev 1 022017 L
| author name =  
| author name =  
| author affiliation = EnergySolutions, Inc, ZionSolutions, LLC
| author affiliation = EnergySolutions, Inc, ZionSolutions, LLC
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{{#Wiki_filter:ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN CHAPTER 2, REVISION 1 SITE CHARACTERIZATION ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-i  TABLE OF CONTENTS 2. SITE CHARACTERIZATION 2-1 2.1. Historical Site Assessment .................................................................................................. 2-2 2.1.1. Objectives .................................................................................................................... 2-2 2.1.2. Methodology ................................................................................................................ 2-3 2.1.2.1. Preliminary Classification ...................................................................................... 2-4 2.1.2.2. Documents Reviewed ............................................................................................ 2-5 2.1.2.3. Licenses, Permits and Authorizations .................................................................... 2-5 2.1.2.4. Personnel Interviews .............................................................................................. 2-6 2.1.3. Operational History ...................................................................................................... 2-6 2.1.4. Incidents ....................................................................................................................... 2-7 2.1.4.1. Radiological Spills ................................................................................................. 2-8 2.1.4.2. Chemical Spills ...................................................................................................... 2-8 2.1.4.3. Loss of Radioactive Material Control .................................................................... 2-9 2.1.4.4. System Cross-Contamination ................................................................................ 2-9 2.1.5. Findings and Conclusions ............................................................................................ 2-9 2.1.6. Initial Survey Units and Classification ...................................................................... 2-11 2.1.6.1. Survey Areas ........................................................................................................ 2-11 2.1.6.2. Survey Units......................................................................................................... 2-11 2.2. Characterization Approach ................................................................................................ 2-15 2.2.1. Data Quality Objectives ............................................................................................. 2-16 2.2.2. Survey Design ............................................................................................................ 2-17 2.2.2.1. Number of Static Measurements and/or Samples ................................................ 2-18 2.2.2.2. Determination of Static Measurement or Sample Locations ............................... 2-18 2.2.2.3. Scan Coverage ..................................................................................................... 2-18 2.2.2.4. Types of Measurements or Samples .................................................................... 2-18 2.2.3. Instrumentation Selection, Use and Minimum Detectable Concentrations (MDCs) . 2-20 2.2.3.1. Instrument Calibration ......................................................................................... 2-21 2.2.3.2. Instrument Use and Control ................................................................................. 2-21 2.2.4. Laboratory Instrument Methods And Sensitivities .................................................... 2-21 2.2.5. Quality Assurance ...................................................................................................... 2-21 2.3. Summary of Characterization Survey Results .................................................................. 2-23 2.3.1. Background Studies ................................................................................................... 2-23 2.3.1.1. EnergySolutions Background Study .................................................................... 2-24 2.3.1.2. Crib House Concrete Study ................................................................................. 2-25 2.3.1.3. ZionSolutions Soil Background Study ................................................................. 2-25 2.3.1.4. Technical Support Document Regarding Cs-137 Global Fallout ........................ 2-26 2.3.2. Potential Radionuclides of Concern........................................................................... 2-26 2.3.3. Impacted Structures and Systems .............................................................................. 2-27 2.3.3.1. Unit 1 and Unit 2 Containments .......................................................................... 2-28 2.3.3.2. Auxiliary Building ............................................................................................... 2-31 2.3.3.3. Fuel Handling Building........................................................................................ 2-33 2.3.3.4. Turbine Building .................................................................................................. 2-34 2.3.3.5. Service Water Intake and Discharge Structure .................................................... 2-36 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-ii  2.3.3.6. Support Buildings and Miscellaneous Structures ................................................ 2-37 2.3.3.7. Embedded or Buried Pipe .................................................................................... 2-38 2.3.4. Non-Impacted Open Land Areas ............................................................................... 2-39 2.3.4.1. Surface Soils ........................................................................................................ 2-40 2.3.4.2. Subsurface Soils ................................................................................................... 2-41 2.3.5. Impacted Open Land Areas ....................................................................................... 2-42 2.3.5.1. Surface Soils and Paved Areas ............................................................................ 2-43 2.3.5.2. Subsurface Soils ................................................................................................... 2-45 2.3.6. Surface and Groundwater .......................................................................................... 2-47 2.3.6.1. Area Groundwater Use ........................................................................................ 2-47 2.3.6.2. Groundwater Flow ............................................................................................... 2-47 2.3.6.3. Previous Investigations ........................................................................................ 2-47 2.3.6.4. On-Going Investigations ...................................................................................... 2-48 2.3.6.5. Summary of Analytical Results in Groundwater ................................................. 2-49 2.3.6.6. Summary of Analytical Results in Surface Water ............................................... 2-49 2.4. Hazardous Material Characterization ................................................................................ 2-50 2.5. Continuing Characterization ............................................................................................. 2-51 2.6. References ......................................................................................................................... 2-54 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-iii  LIST OF TABLES Table 2-1 Operational History .................................................................................................... 2-57 Table 2-2 Historical Incidents/Occurrence................................................................................. 2-61 Table 2-3 Initial List of Structural Survey Units ........................................................................ 2-88 Table 2-4 Initial List of Open Land Survey Units.................................................................... 2-102 Table 2-5 Scan Coverage Guidelines for Characterization ...................................................... 2-106 Table 2-6 Instrument Types and Nominal MDC...................................................................... 2-107 Table 2-7 Typical Vendor Laboratory Standard MDC Values ................................................ 2-108 Table 2-8 EnergySolutions Background Study Results ........................................................... 2-109 Table 2-9 Crib House Concrete Core Sample Analysis Results .............................................. 2-111 Table 2-10 Hosah Park Background Assessment Sample Analysis .......................................... 2-112 Table 2-12 Initial Suite of Radionuclides................................................................................... 2-115 Table 2-13 Nominal Radiological Data - Structural Survey Units ............................................ 2-116 Table 2-14 Unit 1 Containment 568 Foot Elevation Concrete Core Sample  Analysis Summary .................................................................................................. 2-125 Table 2-15 Unit 1 Bio-Shield Concrete Core Samples Gamma Spectroscopy Analysis ........... 2-126 Table 2-16 Unit 2 Containment 568 Foot Elevation Concrete Core Sample  Analysis Summary .................................................................................................. 2-127 Table 2-17 Unit 1 Containment 541 Foot Elevation Concrete Core Sample  Analysis Summary .................................................................................................. 2-128 Table 2-18 Unit 2 Containment 541 Foot Elevation Concrete Core Sample Analysis  Summary ................................................................................................................. 2-129 Table 2-19 Unit 1 Containment Concrete Core Samples - Eberline Laboratory Analysis ........ 2-130 Table 2-20 Unit 2 Containment Concrete Core Samples - Eberline Laboratory Analysis ........ 2-131 Table 2-21 Radionuclide Distributions for Unit 1 and Unit 2 Containments ............................ 2-132 Table 2-22 Auxiliary Building 542 Foot Elevation Concrete Core Sample  Analysis Summary .................................................................................................. 2-134 Table 2-23 Auxiliary Building Concrete Core Samples - Eberline Laboratory Analysis ......... 2-135 Table 2-24 Radionuclide Distribution for the Auxiliary Building ............................................. 2-136 Table 2-25 Turbine Building 560 Foot and 570 Foot Elevation Concrete Core  Sample Analysis Summary ..................................................................................... 2-137 Table 2-27 Non-Impacted Open Land Survey Units - Characterization Survey Summary ...... 2-147 Table 2-28 Recommended Judgmental Sample Population Size ............................................... 2-151 Table 2-29 Impacted Class 3 Open Land Survey Units - Characterization Survey Summary .. 2-152 Table 2-30 Impacted Class 2 Open Land Survey Units - Characterization Survey Summary .. 2-162 Table 2-31 Impacted Class 1 Open Land Survey Units - Characterization Survey Summary .. 2-164 Table 2-32 Surface and Subsurface Soil Samples - Eberline Laboratory Analysis .................. 2-167 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-iv  LIST OF FIGURES Figure 2-1 Zion Nuclear Power Station Owner Controlled Area .............................................. 2-169 Figure 2-2 Zion Nuclear Power Station Radiologically Restricted Area (RRA) ...................... 2-170 Figure 2-3 Zion Nuclear Power Station Security Restricted Area ............................................ 2-171 Figure 2-4 Non-Impacted Open Land Survey Units.................................................................. 2-172 Figure 2-5 Class 3 Open Land Survey Units Outside of "Radiologically-Restricted Area" ..... 2-173 Figure 2-6 Class 3 Open Land Survey Units Inside of "Radiologically-Restricted Area" ....... 2-174 Figure 2-7 Class 1 and Class 2 Open Land Survey Units.......................................................... 2-175 Figure 2-8 Unit 1 Containment 568 foot el. Class 1 Survey Units ............................................ 2-176 Figure 2-9 Unit 1 Containment 541 foot el. Class 1 Survey Units ............................................ 2-177 Figure 2-10 Unit 2 Containment 568 foot el. Class 1 Survey Units ........................................... 2-178 Figure 2-11 Unit 2 Containment 541 foot el. Class 1 Survey Units ........................................... 2-179 Figure 2-12 Auxiliary Building 542 foot el. Class 1 Survey Units ............................................. 2-180 Figure 2-13 Auxiliary Building 560 foot el. Class 1 Survey Units ............................................. 2-181 Figure 2-14 Auxiliary Building 579 foot el. Class 1 Survey Units ............................................. 2-182 Figure 2-15 Turbine Building 560 and 570 Foot Elevations Class 2 Survey Units .................... 2-183 Figure 2-16 Crib House Suction Forebay Class 2 Survey Units ................................................. 2-184 Figure 2-17 Independent Spent Fuel Storage Installation ........................................................... 2-185 Figure 2-18 Vertical Concrete Cask Construction Area ............................................................. 2-186 Figure 2-19 Energy Solutions Background Study Locations ...................................................... 2-187 Figure 2-20 Zion City Park District's "Hosah Park" Background Study Location .................... 2-188 Figure 2-21 Unit 1 Containment 568 foot el. Concrete Core Sample Locations ........................ 2-189 Figure 2-22 Unit 1 Containment 541 foot el. Concrete Core Sample Locations ........................ 2-190 Figure 2-23 Unit 2 Containment 568 foot el. Concrete Core Sample Locations ........................ 2-191 Figure 2-24 Unit 2 Containment 541 foot el. Concrete Core Sample Locations ........................ 2-192 Figure 2-25 Auxiliary Building 542 foot el. Concrete Core Sample Locations ......................... 2-193 Figure 2-26 Turbine Building 560 foot el. and Steam Tunnel 570 foot el. Concrete  Core Sample Locations ........................................................................................... 2-194 Figure 2-27 Turbine Building 560 foot el. Floor Drain System Sediment Sample Locations .... 2-195 Figure 2-28 Non-Impacted Open Land Survey Units Measurement and Sample Locations ...... 2-196 Figure 2-29 Class 3 Open Land Survey Units Located Outside of the  "Radiologically-Restricted Area"Measurement and Sample Locations ................. 2-197 Figure 2-30 Class 3 Open Land Survey Units Located Inside of the  "Radiologically-Restricted Area" Measurement and Sample Locations ................ 2-198 Figure 2-31 Class 2 Open Land Survey Units Measurement and Sample Locations ................. 2-199 Figure 2-32 Class 1 Open Land Survey Units Measurement and Sample Locations ................. 2-200 Figure 2-33 ZNPS Locations of Outfalls, Groundwater Monitoring Wells and Surface Water Sampling Locations ......................................................................... 2-201 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-i  LIST OF ACRONYMS AND ABBREVIATIONS 1 ALARA As Low As Reasonably Achievable 2 BFM  Basement Fill Model 3 ComEd Commonwealth Edison 4 CR  Condition Reports  5 CRA  Conestoga-Rovers & Associates 6 CVS  Contamination Verification Survey 7 DCGL  Derived Concentration Guideline Level 8 DOE  Department of Energy 9 DQO  Data Quality Objective  10 ENC  Engineering and Construction 11 EPA  Environmental Protection Agency  12 ESCSG Energy Solutions Commercial Services Group 13 Exelon  Exelon Generation Company  14 FOV  Field of View 15 FRS  Final Radiation Survey 16 FSS  Final Status Survey  17 GPS  Global Positioning System 18 HSA  Historical Site Assessment 19 HTD  Hard to Detect 20 IDNS  Illinois Department of Nuclear Safety 21 ISOCS  In Situ Object Counting System 22 IRSF  Interim Radioactive Waste Storage Facility 23 ISFSI  Independent Spent Fuel Storage Installation 24 LCPWD Lake County Public Water District 25 LER  Licensee Event Reports  26 LTP  License Termination Plan 27 MARLAP Multi-Agency Radiological Laboratory Analytical Protocols Manual 28 MARSAME Multi-Agency Radiation Survey and Assessment of Materials and Equipment Manual 29 MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual 30 MDC  Minimal Detectable Concentrations 31 MDCR  Minimum Detectable Count Rate 32 MGD  million gallons per day 33 MWe  Megawatts electric 34 MWhr  Megawatt hour 35 MWth  Megawatts thermal 36 NaI  Sodium Iodide 37 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-ii  NGET  Nuclear General Employee Training 38 NIST  National Institute of Standards and Technology 39 NPDES Illinois Environmental Protection Agency - National Pollutant Discharge Elimination 40 System  41 NRC  Nuclear Regulatory Commission  42 ODCM Off-site Dose Calculation Manual 43 PWST  Primary Water Storage Tank 44 QAPP  Quality Assurance Project Plan for Characterization and FSS  45 QA/QC Quality Assurance and Quality Control 46 RCA  Radiologically Controlled Area  47 REMP  Radiological Environmental Monitoring Program 48 RGPP  Radiological Groundwater Protection Program 49 ROC  Radionuclides of Concern 50 ROR  Radiological Occurrence Reports  51 SAFSTOR SAFeSTORe 52 SFP  Spent Fuel Pool 53 S/G  Steam Generator 54 STS  Source Term Survey 55 SST  Secondary Condensate Storage Tank 56 TSD  Technical Support Document 57 VCC  Vertical Concrete Cask 58 WDHS  Wisconsin Department of Health Services 59 WWTF Waste Water Treatment Facility 60 ZNPS  Zion Nuclear Power Station 61 ZSRP  Zion Station Restoration Project 62  63  64 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-1  2. SITE CHARACTERIZATION 65 In accordance with the requirements of 10 CFR 50.82 (a)(9)(ii)(A) and the guidance of 66 Regulatory Guide 1.179, "Standard Format and Contents for License Termination Plans for 67 Nuclear Power Reactors" (Reference 2-1), this chapter provides a description of the radiological 68 characterization performed at the Zion Nuclear Power Station (ZNPS) site. The purpose of site 69 characterization is to ensure that the Final Radiation Status Survey (FRSFSS) will be conducted 70 in all areas where contamination existed, remains, or has the potential to exist or remain. The 71 results of the characterization survey, including the "Zion Station Historical Site Assessment" 72 (HSA) (Reference 2-2), demonstrate that it is unlikely that significant quantities of residual 73 radioactivity have gone undetected. There are areas known to potentially contain contamination 74 that were inaccessible during the initial characterization which will be surveyed during 75 continuing characterization as access is gained (see section 2.45).The term "Final Radiation 76 Survey" is from 10 CFR 50.82(9)(ii)(D) and is used in this License Termination Plan (LTP) in 77 order to acknowledge the distinction between the two types of compliance surveys that will be 78 performed by the Zion Station Restoration Project (ZSRP). These surveys are; 1) a Final Status 79 Survey (FSS) for open land areas based on guidance provided in NUREG-1575, "Multi-Agency 80 Radiation Survey and Site Investigation Manual (MARSSIM)" (Reference 2-2) and 2) a Source 81 Term Survey (STS) for below ground structures. See LTP Chapter 5 for a description of the 82 FRS. 83 The site characterization incorporates the results of investigations and surveys conducted to 84 quantify the extent and nature of contamination at the ZNPS site. In addition, the results of site 85 characterization surveys and analyses have been and continue to be used to identify areas of the 86 site that will require remediation, as well as to plan remediation methodologies, develop waste 87 classification and volumes, and estimate costs. 88 The characterization survey was designed and executed using the guidance provided in  89 NUREG-1575, "Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM)" 90 (Reference 2-3)NUREG-1575 (MARSSIM) and NUREG-1757, Volume 2, Revision 1, 91 "Consolidated Decommissioning Guidance - Characterization, Survey, and Determination of 92 Radiological Criteria, Final Report", (Reference 2-34). In addition, surveys were designed and 93 executed in accordance with the ZionSolutions ZS-LT-02, "Characterization Survey Plan" 94 (Reference 2-45), and ZS-LT-01, "Quality Assurance Project Plan (for Characterization and 95 FSS)" (QAPP) (Reference 2-56) which describes policy, organization, functional activities, the 96 Data Quality Objectives (DQO) process, and measures necessary to achieve quality data. The 97 information obtained from the characterization provides guidance for decontamination and 98 remediation planning. Materials which were shown to be contaminated with radioactive material 99 at concentrations greater than the unrestricted release criteria have been and will continue to be 100 removed and properly packaged for shipment and disposal. 101 The site characterization of ZNPS includes the information requirements listed in NUREG-1700, 102 Standard Review Plan for Evaluating Nuclear Power Reactor License Termination Plans 103 (Reference 2-7) and NUREG-1757. Measurements and samples were taken in each accessible 104 area, along with the historical information, to provide a clear picture of the residual radioactive 105 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-2  materials and its vertical and lateral extent at the site. Using appropriate DQOs, monitoring well 106 water samples, surface soil, sediment, concrete cores and sub-surface soil were collected to 107 provide a profile of the residual radioactivity at the site. Samples were analyzed for the 108 applicable radionuclides with detection limits that provided the level of detail necessary for 109 decommissioning planning. Based upon the volume of characterization data collected and an 110 assessment of the characterization results, the characterization survey is considered adequate to 111 demonstrate that it is unlikely that significant quantities of residual radioactivity have gone 112 undetected. 113 Section 8.5 of Exhibit C, Lease Agreement, titled "Removal of Improvements; Site Restoration" 114 integral to the "Zion Nuclear Power Station, Units 1 and 2 Asset Sale Agreement"  115 (Reference 2-68) requires the demolition and removal of all on-site buildings, structures, and 116 components to a depth of at least 3 feet below grade. Consequently, the only structures that will 117 remain at license termination are the exposed steel lined walls and floorliner and Under-Vessel 118 concrete in the Unit 1 and Unit 2 Containment Buildings (after all other interior concrete is 119 removed) and the below-grade structural concrete outside of the liner, the reinforced concrete 120 basement floor and outer walls of the Auxiliary Building and Turbine Building (after all internal 121 walls and floors are removed), the reinforced concrete floor and walls of the Spent Fuel Pool 122 (SFP) and Fuel Transfer Canal (after the steel liner is removed), the concrete floor and walls of 123 the Crib House, the Waste Water Treatment Facility (WWTF), the Forebay and the Circulating 124 Water Intake and Discharge Piping below the 588 foot elevation. 125 All systems, and components, as well as all structures above the 588 foot elevation will be 126 removed during the decommissioning process and disposed of as a waste stream. The 127 switchyard, which belongs to Commonwealth Edison, will also remain. As part of the 128 decommissioning process, all reactor fuel and greater than Class C waste will bewas loaded into 129 casks and transferred to an Independent Spent Fuel Storage Installation (ISFSI). The fuel will 130 remain on-site in dry storage within the ISFSI until it is transferred to the Department of Energy 131 (DOE). The ISFSI has been constructed in the southwest corner of the ZNPS site, immediately 132 south of the switchyard. 133 2.1. Historical Site Assessment 134 In accordance with guidance provided in MARSSIM, section 3.0, a "Zion Station Historical Site 135 Assessment" (HSA) (Reference 2-7) was issued in August of 1999. Historical information, 136 including any 10 CFR 50.75(g) files, employee interviews, radiological incident reports, pre-137 operational survey data, spill reports, special surveys (e.g., site aerial surveys, marine fauna and 138 sediment surveys), operational survey records, and Annual Radiological Environmental Reports 139 (including sampling of air, groundwater, estuary water, milk, invertebrates, fish and surface 140 vegetation) to the Nuclear Regulatory Commission (NRC) were reviewed and compiled for this 141 investigation. 142 2.1.1. Objectives 143 The HSA was a detailed investigation to collect existing information (from the start of ZNPS 144 activities related to radioactive materials or other contaminants) for the site and its surroundings. 145 The HSA focused on historical events and routine operational processes that resulted in 146 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-3  contamination of plant systems, onsite buildings, surface and subsurface soils within the 147 Radiologically Controlled Area (RCA). It also addressed support structures, open land areas and 148 subsurface soils outside of the RCA but within the owner controlled area. The information 149 compiled by the HSA was used to establish initial area survey units and their MARSSIM 150 classifications. This information may also bewas used as input into the development of site-151 specific Derived Concentration Guideline Levels (DCGL), remediation plans and the design of 152 the FSS. The scope of the HSA included potential contamination from radioactive materials, 153 hazardous materials, and other regulated materials. 154 The objectives of the HSA were to: 155  Identify potential, likely, or known sources of radioactive and chemical contaminants based 156 on existing or derived information. 157  Distinguish portions of the site that may need further action from those that pose little or no 158 threat to human health. 159  Provide an assessment of the likelihood of contaminant migration. 160  Provide information useful to subsequent continuing characterization surveys. 161  Provide an initial classification of areas and structures as non-impacted or impacted. 162  Provide a graded initial classification for impacted soils and structures in accordance with 163 MARSSIM guidance. 164  Delineate initial survey unit boundaries and areas based upon the initial classification. 165 At the time that the HSA was performed, the facility was in a SAFSTOR condition. As noted in 166 the NRC public meeting in June 1998, the decommissioning approach for the facility specified 167 that the units would remain in a SAFSTOR condition through 2010, when decontamination and 168 dismantlement activities would begin for the structures, systems and components not required for 169 maintenance of the nuclear spent fuel. The intended purpose of the Zion HSA was to provide a 170 compilation and "road-map" of data and documents relating to the contaminant makeup of the 171 site. This road-map would aid subsequent detailed site characterizations to be conducted in 172 support of decommissioning planning which were anticipated to begin in approximately 2010. 173 During the SAFSTOR period, no scoping or initial characterization surveys as defined by 174 MARSSIM, sections 5.2 and 5.3 were performed. 175 2.1.2. Methodology 176 The objective of the HSA records search and interview process was the identification of those 177 events posing a significant probability of impacting the hazardous material or radiological status 178 of ZNPS site land areas and structures. These included system, structure, or area contamination 179 from system failures resulting in airborne releases, liquid spills or releases, or the loss of control 180 over solid material. Depending upon previous site operations and processes, the potential for 181 residual contamination varies by area. In order to facilitate effective characterization surveys to 182 guide future decontamination activities and provide sufficient data for the design of FSS, land 183 areas and structures are classified based upon their potential for contamination. 184 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-4  Each incident identified that posed a realistic potential to impact the characterization of the site 185 was further investigated. This investigation focused on the scope of contaminant sampling and 186 analysis, any remedial actions taken to mitigate the situation, and any post-remedial action 187 sampling, survey, and analysis in an attempt to identify the "as left" condition of the incident 188 location. Historical records archives provided the source of a vast majority of the documents 189 inspected. 190 Also included in the research associated with the development of the HSA were: 191  Relevant excerpts from written reports and correspondences; 192  Personnel interviews, including the use of questionnaires, of current, former and retired plant 193 personnel to confirm documented incidents and identify undocumented incidents; and 194  Site inspection, utilizing historic site drawings, photographs, prints, and diagrams to identify, 195 locate, confirm, and document areas of concern. 196 Information from this research was used in the HSA development, including the compilation of 197 data, evaluation of results, documentation of findings, and the identification of initial Survey 198 Units. 199 2.1.2.1. Preliminary Classification 200 The HSA investigation was designed to obtain sufficient information to provide initial 201 classification of the site land areas and structures as impacted or non-impacted. Impacted areas 202 have a potential for contamination (based on historical data) or contain known contamination 203 (based on past or preliminary radiological surveillance). Non-impacted areas are identified 204 through knowledge of site history or previous survey information and are those areas where there 205 is no reasonable possibility for residual radioactive contamination. Areas were classified as 206 impacted from a radiological perspective. Potential chemical hazards incidents on owner-207 controlled areas were also documented including the confirmed presence of petroleum products, 208 asbestos or other hazardous materials. 209 If a land area or structure was classified as impacted, then a determination of the initial impacted 210 area classification (e.g. Class 1, Class 2 or Class 3) in accordance with MARSSIM, section 2.2 211 was made based upon the information obtained. 212 Initial classification of ZNPS areas was based on historical information and available historical 213 radiological survey data. Classifying a survey area has a minimum of two stages: (1) initial 214 classification and (2) final classification. Initial classification of most areas is performed at the 215 time of identification of the survey area using the information available when the HSA was 216 prepared. Final classification is performed and verified as a DQO during FSS design. 217 Radiological survey data from characterization surveys, operational surveys in support of 218 decommissioning, routine surveillance, and any other applicable survey data may cause an 219 increase in survey area classifications (for example, from Class 3 to Class 2 and from Class 2 to 220 Class 1) until the time of commencement of the FSS. 221 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-5  2.1.2.2. Documents Reviewed 222 Records maintained to satisfy the requirements of 10 CFR Part 50.75(g)(1) provided a major 223 source of documentation for the HSA records review process. During the conduct of the HSA 224 for ZNPS, many record types were evaluated including paper, microform, and electronic media. 225 In total, over 29,000 records were reviewed for applicability for the HSA. A complete listing of 226 documents reviewed is provided in Appendix 3 of the HSA. A summary of the types of records 227 reviewed include: 228  License and Technical Specification reports, 229  Annual operational and environmental reports, 230  Environmental investigations performed by independent entities, 231  Regulatory actions against the site, 232  Documentation from interviews conducted with currently employed and retired/separated site 233 personnel, 234  Radiological and environmental survey documents, 235  Site inspection and surveillance documents associated with identified events, 236  Annual Environmental and Operational documents, 237  Licensee Event Reports (LERs), 238  Radiological Occurrence Reports (RORs), 239  Condition Reports (CRs), 240  Quality Control /Quality Assurance findings. 241 2.1.2.3. Licenses, Permits and Authorizations 242 ZNPS was operated in accordance with several Federal and State of Illinois licenses and permits. 243 The NRC Operating Licenses for Units 1 and 2 and supporting Technical Specifications allowed 244 Commonwealth Edison and subsequent license holders to use any quantity of radioactive 245 material at the site, to support operations during its operating lifetime, and to implement 246 decommissioning activities. 247 The US Environmental Protection Agency (EPA) and applicable State of Illinois agencies 248 maintain files on a variety of environmental programs that are applicable to ZNPS. These 249 include permit applications and monitoring results with information on specific waste types and 250 quantities, sources, type of site operations, and operating status of the facility or site. 251 The following denotes the licenses and permits relevant to the development of the HSA: 252  US Nuclear Regulatory Commission - Docket Number 50-295, Facility Operating License 253 Number DPR-39 (for Unit 1) (Reference 2-89) 254  US Nuclear Regulatory Commission - Docket Number 50-304, Facility Operating License 255 Number DPR- 48 (for Unit 2) (Reference 2-910) 256 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-6  Illinois Environmental Protection Agency - National Pollutant Discharge Elimination 257 System (NPDES) Permit Number IL0002763 (Reference 2-1011) 258 2.1.2.4. Personnel Interviews 259 Interviews with current or previous employees were performed to collect first-hand information 260 about the site and to verify or clarify information gathered from the records that were reviewed. 261 The personnel interviews included a combination of questionnaires completed by a majority of 262 the participants as well as individual and group interviews with several of the participants. Key 263 personnel were chosen due to their knowledge of and association with the systems and source 264 terms being investigated for the assessment. A number of the personnel interviewed possessed 265 site knowledge and experience that ranged from the site construction period to shutdown. 266 Two types of interview questionnaires were used in the conduct of the Zion HSA. The first type 267 of questionnaire was designed for permanent site production personnel. The second type of 268 interview questionnaire was used during the personnel exit process (permanent and contractor 269 staff). Typically, individuals were provided the questionnaire as a part of the standard station 270 exit process. These exit interviews/questionnaires were obtained more as a quality check on 271 information obtained during permanent staffing interviews. During the conduct of the Zion 272 HSA, over 300 personnel interviews occurred with current and previous Zion personnel. With 273 few exceptions, the personnel observations were corroborated by either the observations of other 274 interviewees or documentation discovered during the records search. 275 2.1.3. Operational History 276 The ZNPS is located in Northeast Illinois on the west shore of Lake Michigan. The site is 277 approximately 40 miles north of Chicago, Illinois, and 42 miles south of Milwaukee, Wisconsin. 278 The site is in the extreme eastern portion of the city of Zion, (Lake County) Illinois, on the west 279 shore of Lake Michigan approximately 6 miles NNE of the center of the city of Waukegan, 280 Illinois, and 8 miles south of the center of the city of Kenosha, Wisconsin. 281 The station is comprised of two essentially identical pressurized water reactors with supporting 282 facilities. Each unit's primary coolant system consists of a pressurized water reactor system 283 designed by the Westinghouse Corporation and is comprised of the reactor vessel and four heat 284 transfer loops. Each loop contains a reactor coolant pump, steam generator, and associated 285 piping and valves. In addition, each unit includes a pressurizer, a pressurizer relief tank, 286 interconnecting piping, and the instrumentation necessary for operational control. All major 287 components of each unit's reactor coolant system are located in their respective containment 288 building. The design reactor thermal power level was 3250 Megawatts thermal (MWth). The 289 corresponding electrical output was approximately 1,085 Megawatts electric (MWe) for both 290 Units 1 and 2. 291 The initial construction of the station was authorized on December 26, 1968. Unit 1 and Unit 2 292 achieved initial criticality on June 19, 1973 and December 24, 1973 respectively. Next, Unit 1 293 was synchronized to the grid for the first time on June 28, 1973 and Unit 2 on 294 December 26, 1973. Finally, Unit 1 and Unit 2 began commercial operation on 295 December 31, 1973 and September 19, 1974 respectively. Between the two units, Zion operated 296 for approximately 248,238,983 effective MWhrs over the course of its operating lifetime. 297 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-7  On January 15, 1998, Commonwealth Edison (ComEd) announced the permanent shutdown of 298 both Zion reactors. The shutdown decision was based on the corporation's economic 299 determination that neither Zion reactor would be able to produce competitively priced electricity 300 in a deregulated marketplace over the facility's remaining useful life. 301 On February 13, 1998, ComEd certified the permanent cessation of operation of ZNPS Units 1 302 and 2 to the NRC. On March 9, 1998, ComEd certified to the NRC that all fuel assemblies had 303 been permanently removed from both ZNPS reactor vessels and placed in the SFP. Both units at 304 ZNPS were subsequently placed in a SAFSTOR condition (a period of safe storage of the 305 stabilized and defueled facility) until eventual final decommissioning and dismantlement. 306 Upon docketing of the certification for permanent cessation of operation and permanent removal 307 of fuel from the reactor vessels, the 10 CFR Part 50 license no longer authorizes operation of the 308 reactors or emplacement or retention of fuel in the reactor vessels. In addition, the operating 309 licenses scheduled to expire in April 2013 for Unit 1 and November 2013 for Unit 2 continue to 310 remain in effect until the NRC notifies ZionSolutions that the licenses have been terminated. 311 The reactors at Zion remained in a SAFSTOR condition until September of 2010. At this point, 312 the license for the facility was transferred from Exelon Generation Company (Exelon) (the 313 licensee at that time) to ZionSolutions LLC. This was accomplished to allow ZionSolutions to 314 begin the process of the physical decommissioning of the ZNPS. 315 A synopsis of the operational history is provided in Table 2-1. 316 2.1.4. Incidents 317 Based on the review of existing plant records (e.g. annual and semi-annual reports, licensee 318 notifications, Occurrence Description Reports, and Personnel Data Questionnaire) approximately 319 305 incidents with radiological or hazardous material implications occurred between the 320 commencement of plant operation in 1974 and placing both reactor units in a SAFSTOR 321 condition in 1999. A majority of these incidents took place within the "Security-Restricted 322 Area" and, while contributing to the radiological contamination and potential contamination of 323 the structures and soils directly related to the operation of the reactors, were generally contained 324 within the RCA, which is already known to be "impacted". Those incidents occurring outside of 325 the "Security-Restricted Area" have contributed to the "impacted" classification of other 326 supporting structures and surrounding open land areas. These include: 327  Spills outside of the RCA or incidents involving potential contamination based on leakage 328 from systems that had been historically contaminated by primary to secondary leaks, 329  Loss of control of radioactive materials resulting in the potential for contamination outside of 330 the RCA, 331  Spills of plant liquid radioactive effluents resulting in soil contamination, 332  Hazardous material spills or losses of control, and 333  Contamination of systems not originally designed as radioactive systems. 334 A synopsis index of these incidents is presented in Table 2-2. 335 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-8  2.1.4.1. Radiological Spills 336 The HSA indicates that between 1973 and 1997, 64 documented spills occurred at the facility. 337 Of those, 18 spills occurred either inside of Unit 1 or Unit 2 Containment, 21 occurred inside of 338 the Auxiliary Building and two occurred inside of the Fuel Handling Building. These spill 339 incidents, while contributing to the radiological contamination of these buildings, were generally 340 contained within the radiologically controlled drains and waste systems of the structures. 341 Of the remaining 23 documented spill incidents, 14 occurred either inside the Rad Waste Annex 342 trackways or just outside of the trackway doors in the open land areas between the Containment 343 structures and the Turbine Building. The prevalence of these incidents causes concern for the 344 potential contamination of ground coverings (concrete and asphalt) as well as surface and 345 subsurface soils in these two areas. The HSA specifically refers to these two areas as the most 346 extensively contaminated open land areas on the site. Substantial spills of spent resins and 347 contaminated water were documented. Most significant spills occurred prior to 1980 which 348 preceded the construction of the Rad Waste Annex. The Annex was constructed to provide an 349 enclosure to the area where spent resins were sluiced and solidified for shipment and disposal. 350 Prior to the construction of the Annex, these activities were conducted in the open on a concrete 351 pad. It is estimated that over 100 gallons of spent resin may have leaked into the soils at these 352 locations. 353 Other significant spills and releases are summarized as follows; 354  Overflow of both Unit 1 and Unit 2 Primary Water Storage Tank (PWST) as well as Unit 1 355 Secondary Condensate Storage Tank (SST) 356  Unmonitored release of potentially contaminated liquids through the normal effluent release 357 pathway to Lake Michigan from the Unit 2 Condenser hotwell, the Turbine Building Fire 358 Sump and the Turbine Building drain system. 359  Spill of potentially contaminated water to the 560 ft. elevation of the Turbine Building. 360 These spills resulted in the affected areas being designated as "impacted". 361 2.1.4.2. Chemical Spills 362 Between 1973 and 1997, the HSA documented 67 incidents involving the unplanned spill or 363 release of chemicals and/or potentially hazardous liquids to the environment. These incidents 364 ranged from spills of acids and caustics used in the plant's various systems to the spill of diesel 365 and fuel oil from systems and storage tanks. A majority of the incidents occurred inside of 366 impacted buildings. There were also several instances where caustics and acids exceeding 367 Technical Specification requirements were discharged through the plant WWTF. In addition, 368 significant spills of mercury occurred in the Turbine Building and Crib House. 369 These spills were controlled and remediated in accordance with the station policies and 370 procedures for identification, control and remediation of hazardous material releases. 371 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-9  2.1.4.3. Loss of Radioactive Material Control 372 The HSA documents 132 incidents involving the loss of control of radioactive material between 373 1973 and 1997. Of those incidents, 61 involve the identification of radioactive material in non-374 posted areas inside of the RCA, such as the Maintenance Shop or the Tool Crib. Twenty-375 two (22) incidents involve the identification of radioactive material in trash piles or dumpsters 376 located in non-posted areas inside the RCA. Twenty-four (24) incidents involve the 377 identification of radioactive material in the trash segregation area located in the Unit 1 Turbine 378 Building trackway. Four (4) incidents pertained to the loss of control of radioactive material 379 while shipping or receiving radioactive material packages. Seven (7) incidents involved 380 personnel leaving site with radioactive material on their person or in their vehicle and 381 14 incidents involved the loss of control of radioactive material where the material was 382 discovered and recovered outside of the RCA. Areas affected by these incidents were classified 383 as "impacted." 384 2.1.4.4. System Cross-Contamination 385 Starting in 1981 and expanding dramatically in 1984, the Unit 1 Steam Generators (S/G) 386 exhibited significant primary to secondary leaks. Unit 2 Steam Generators also exhibited 387 primary to secondary leaks, but not to the extent exhibited by Unit 1. On September 10, 1984, 388 Unit 1 was shut down as primary to secondary leakage exceeded the Technical Specification 389 limit of 500 gallons per day. Due to the extensive primary to secondary leakage, secondary 390 systems not originally expected to contain radioactivity became contaminated. The level of 391 contamination varied from system to system. 392 In addition, many other secondary systems had the potential for cross contamination including 393 open cycle and closed cycle cooling systems, auxiliary systems, and storage tanks. Following 394 the guidance in NRC Bulletin 80-10, "Contamination of Nonradioactive Systems and Resulting 395 Potential for Unmonitored Release of Radioactivity to Environment" (Reference 2-1112), non-396 contaminated systems was routinely monitored to identify contamination events in a timely 397 fashion. When normally non-contaminated systems became contaminated, they were evaluated 398 against 10 CFR Part 50 Appendix I criteria. In addition, systems already contaminated were 399 monitored according to plant chemistry and surveillance procedures to measure and trend the 400 levels of activity within the systems. 401 Based on the HSA investigation, several additional secondary systems besides the Main Steam, 402 Condensate and Feedwater systems were identified as contaminated. These systems included the 403 Auxiliary Boiler, Unit 1 and Unit 2 Oil Separators and the Turbine Building equipment and floor 404 drain systems. The structures associated with these systems are classified as "impacted." 405 2.1.5. Findings and Conclusions 406 The ZNPS was designed with multiple boundaries to control and contain the radioactive contents 407 within its many systems, components, and structures. Many of these systems and structures have 408 been impacted due to routine operations and maintenance activities during the operational and 409 post operational history of the plant. Structures classified as "impacted" by the operation of the 410 facility include Unit 1 and Unit 2 Containments, the Auxiliary Building, the Fuel Handling 411 Building, the Turbine Building, the Service Building, the Crib House and system storage tanks 412 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-10  located outdoors adjacent to the Crib House. Secondary systems, components and structures that 413 were not originally anticipated to be contaminated have been impacted as the result of system 414 cross contamination between the primary coolant system and secondary steam systems due to the 415 failure of tubes within both unit's S/Gs. In addition to the structures, the soils surrounding these 416 building have also been deemed to be directly impacted by the operation of this facility. This 417 area is defined by the surrounding double-security fence and has been designated as the 418 "Security-Restricted Area". 419 The area surrounding the "Security-Restricted Area" area has been designated as the 420 "Radiologically-Restricted Area". This area encompasses the ancillary support buildings such as 421 the Engineering and Construction (ENC) Building, the Gate House, the Interim Radioactive 422 Waste Storage Facility (IRSF), the Switchyard and various warehouses and storage buildings. 423 Based on the findings documented in the HSA, these structures along with the soils within the 424 "Radiologically-Restricted Area" fence has also been deemed as "impacted."  425 In addition to the area within the "Radiologically-Restricted Area" area, several additional areas 426 have been deemed as "impacted". These include the site parking lot, the open land area along 427 the south site boundary, the beach adjacent to the site and the area along Shiloh Boulevard 428 designated as the West Training area. The parking lot was designated as impacted as it is a 429 major path for radioactive material movement onto and off of the site. The West Training area 430 was the former location of the Zion Training Building. This building housed a Westinghouse 431 training reactor from 1980 to 1987. The reactor was decommissioned in 1988 and the license 432 was terminated. The building itself was dismantled shortly following the permanent shutdown of 433 the facility. 434 Figure 2-1 illustrates the "Owner-Controlled Area" that is under the management of the licensee. 435 The "Radiologically-Restricted Area" area is illustrated in Figure 2-2 and the "Security-436 Restricted Area" area is illustrated in Figure 2-3. 437 Based on current and historic sample results from the ZNPS Radiological Environmental 438 Monitoring Program (REMP), there is no indication that surface waters on or near the facility or 439 the ground water beyond the site have been affected by the licensed operation of the facility. 440 However, further evaluations of the groundwater directly below the licensed facility have been 441 conducted. The initial findings of this study are presented in section 2.3.6. The normal effluent 442 release pathway for the facility is the Circulating Water Discharge Piping Tunnel that discharges 443 to Lake Michigan approximately 870 feet from the lakeshore. During operation, effluent 444 discharges contained measurable amounts of radioactive material resulting from liquid releases 445 conducted in accordance with the license and permit requirements. 446 There were periods of liquid effluent releases during operation of the plant where it was 447 determined that calculated dose to a maximally exposed individual via the liquid effluent 448 pathway exceeded the design objective of 10 CFR Part 50, Appendix I. However, it was also 449 determined that these liquid effluent releases did not exceed the concentration limits of 450 10 CFR Part 20 or the EPA fuel cycle dose limit in 40 CFR Part 190. The dose from liquid 451 effluents has already been accounted for in accordance with the regulations governing 452 radioactive effluent from power plants and no remediation is required. 453 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-11  2.1.6. Initial Survey Units and Classification 454 As part of the HSA process, the ZNPS facilities and grounds were divided into preliminary 455 survey areas and assigned initial area classifications based on the operational history and the 456 incidents and processes documented for that survey unit. 457 2.1.6.1. Survey Areas 458 The entire 331 acre site was divided into survey areas. Survey areas are typically larger physical 459 sections of the site that may contain one or more survey units depending on their classification. 460 Survey area size was determined based upon the specific area and the most efficient and practical 461 size needed to bound the lateral and vertical extent of contamination identified in the area. 462 Survey areas that have no reasonable potential for residual contamination were classified as 463 "non-impacted". These areas have no radiological impact from site operations and are identified 464 in the HSA. Survey areas with reasonable potential for residual contamination were classified as 465 "impacted." 466 2.1.6.2. Survey Units 467 The classified survey areas established by the HSA were further divided into survey units. A 468 survey unit is a portion of a structure or open land area that is surveyed and evaluated as a single 469 entity following FSS. Survey units were delineated to physical areas with similar operational 470 history or similar potential for residual radioactivity to the extent practical. To the extent 471 practical, survey units were established with relatively compact shapes and highly irregular 472 shapes were avoided unless the unusual shape was appropriate for the site operational history or 473 the site topography. 474 The survey units established by the HSA were used as initial survey units for characterization. 475 Prior to characterization, survey unit sizes for Class 1 open land survey units were adjusted in 476 accordance with the guidance provided in MARSSIM, section 4.6 for the suggested physical area 477 sizes for survey units for FSS. 478 The decommissioning approach that will be implemented by the ZSRP calls for the complete 479 segmentation, removal and disposal of all impacted systems and above-grade structures. With 480 the exception of structure basement floors and walls that reside 3 feet below grade, and concrete 481 structures that are candidates for the potential reuse of concrete as hard fill, no portion of any 482 structure will remain at site closure and consequently, be subjected to FRSFSS. However, 483 survey units have been established for structures to facilitate other characterization objectives. 484 These objectives include providing survey data for remediation planning, estimating the waste 485 volume contained onsite, and disposition options for the waste. 486 In addition, the survey units established for structures that are 3 feet below grade are intended for 487 the purpose of characterization planning and do not correspond to the survey units that will be 488 used for the FRS FSS of remaining below grade structures (designated as Source Term Surveys 489 [STS] and discussed in section 5.5.2 of Chapter 5). 490 The non-impacted open land survey units for the site are depicted in Figure 2-4. The impacted 491 Class 3 open land survey units are depicted in Figures 2-5 and 2-6. The impacted Class 1 and 492 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-12  Class 2 open land survey units are depicted in Figure 2-7. A summary of the initial survey unit 493 classifications are presented as follows. 494 2.1.6.2.1. Class 1 Structures 495 The following is a list of some of the major buildings that were initially classified as impacted 496 Class 1 structures in the HSA. The complete list of all initial structural survey units is provided 497 in Table 2-3. These structures contain the nuclear reactors, primary reactor systems, reactor 498 support systems, radioactive waste systems, and nuclear fuel handling and storage systems. 499 During operations, radioactive material was routinely handled, transferred, and stored within 500 these buildings. A majority of the current radioactive material inventory at Zion resides in these 501 structures: 502  Unit 1 Containment Building 503  Unit 2 Containment Building 504  Fuel Handling Building 505  Radioactive Waste Building 506  Auxiliary Building 507 Throughout facility operations, these structures were subjected to spills of radioactive liquids, the 508 spread of loose surface contamination, and airborne radioactive material. Structural surfaces 509 were routinely posted as contaminated areas. The decommissioning approach for these 510 structures involves the complete segmentation, removal, and disposal of all systems and 511 structural material as waste. With the exception of structural floors and walls that reside 3 feet 512 below grade, and concrete structures that are candidates for the potential reuse of concrete as 513 hard fill, no portion of these structures will remain at site closure and are therefore not subjected 514 to FSS. The Class 1 structural survey units for building basements below the 588 foot elevation 515 are depicted in Figures 2-8 and 2-9 for Unit 1 Containment, Figures 2-10 and 2-11 for Unit 2 516 Containment and Figures 2-12, 2-13 and 2-14 for the Auxiliary Building. 517 2.1.6.2.2. Class 2 and 3 Structures 518 The following is a list of some of the major buildings that were initially classified as impacted 519 Class 2 or 3 structures by the HSA. All are located within the "Radiologically-Restricted Area" 520 of ZNPS. The complete initial list of all structures and survey units is provided in Table 2-3. 521 The primary function of these structures is to house the secondary side steam systems or 522 electrical generating systems, or to provide office and/or warehouse space. The primary basis for 523 the initial classification of secondary side systems and structures as impacted is due to a series of 524 primary to secondary side leaks through the S/Gs during plant operations. 525  Turbine Building 526  Crib House 527  Unit 1 Main Steam Valve Houses 528  Unit 2 Main Steam Valve Houses 529 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-13  Waste Water Treatment Facility (WWTF) 530  Warehouse/Mechanical Maintenance Training Area  531  Station Construction Building 532  Illinois Department of Nuclear Safety (IDNS) Building 533  Gate House 534  North Warehouse 535  South Warehouse 536 These structures did not routinely house radioactive systems or materials during operations. 537 However, it was possible, due to their physical proximity to effluent release pathways, 538 radioactive contamination of secondary side systems, temporary storage and transport of 539 radioactive materials in and through these buildings, and past incidents involving the loss of 540 control of radioactive material, that residual radioactive material could be found in and on, and 541 around these structures. Consequently, this justified their initial classification as impacted 542 Class 2 or Class 3. As with the Class 1 impacted structures, the decommissioning approach calls 543 for the complete segmentation, removal, and disposal of all Class 2 or 3 systems and structural 544 material as waste or salvage. With the exception of structural below-grade foundations and 545 concrete structures that are candidates for the potential reuse of concrete as hard fill, no portion 546 of these structures will remain at site closure and therefore will not be subjected to FRSFSS. The 547 Class 2 structural survey units for building basements below the 588 foot elevation are depicted 548 in Figures 2-15 for the Turbine Building and Figure 2-16 of the Forebay for the Circulating 549 Water system under the Crib House. There are no Class 3 structures that will remain in the final 550 site configuration. 551 2.1.6.2.3. Class 1 Open Land Areas 552 The following open land areas have been initially classified as impacted Class 1. The basis for 553 this initial classification is due to a series of documented incidents of the contamination of soil 554 by radioactive material in these areas during facility operations. These incidents include spills of 555 radioactive liquids and resins, radioactive system leakage, and storage of radioactive packages 556 and containers. The complete list of all initial open land survey units is provided in Table 2-4. 557  Sludge Drying Bed Area 558  WWTF Area 559  Unit 1 PWST/SST Area 560  Unit 2 PWST/SST Area 561  South Yard Area Northeast of the Gate House 562  Yard Between Unit 1 Containment and Turbine Building 563  Yard Between Unit 2 Containment and Turbine Building 564 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-14  Sub-slab Soils under and around the Unit 1 Containment, Unit 2 Containment, the Fuel 565 Handling Building and the Auxiliary Building 566 Based on an assessment of historical incidents and events, it was anticipated that the surface and 567 subsurface soils in these areas could possibly contain residual radioactive material in excess of 568 the unrestricted release criteria. Class 1 open land survey units are illustrated on Figure 2-7. 569 2.1.6.2.4. Class 2 Open Land Areas 570 The following open land areas were initially classified as impacted Class 2. Based upon a 571 review of the historical information and operational radiation and contamination surveys 572 performed in these areas as documented in the HSA, there was a potential for residual 573 radioactive contamination to exceed the unrestricted release criteria. The complete list of all 574 initial open land survey units is provided in Table 2-4. 575  Crib House Area 576  Southeast Protected Area Yard 577  The Gate House Area and the Protected Area Southwest Yard 578  North Protected Area Yard 579  Sub-slab Soils under and around the Service Building and the Turbine Building 580 Class 2 open land survey units are illustrated on Figure 2-7. 581 2.1.6.2.5. Class 3 Open Land Areas 582 The following open land areas were initially classified as Class 3. Historical information 583 contained in the HSA indicated that the presence of residual radioactivity in concentrations in 584 excess of the unrestricted release criteria was not expected. The complete list of all initial open 585 land survey units is provided in Table 2-4. 586  Northeast Corner of the Restricted Area adjacent to the Lake 587  Interim Radioactive Waste Storage Area (IRSF)/Fire Training Area 588  East Training Area 589  North Gate Area 590  Switchyard 591  In-Processing Building/Station Construction Area 592  North Warehouse Area 593  South Warehouse Area 594  Exclusion Area South of Gate House 595  Exclusion Area South of Turbine Building 596  Southeast Corner of the Restricted Area 597 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-15  Construction Parking Area 598  Area South of Switchyard 599  Owner Controlled Area South of Restricted Area 600  West Training Area 601 Class 3 open land survey units are illustrated on Figure 2-5 and Figure 2-6. 602 2.1.6.2.6. Non-Impacted Areas 603 Based on a review of the operating history of the facility, historical incidents, and operational 604 radiological surveys as documented in the HSA, the following areas have been deemed not 605 impacted by licensed activities or materials. The complete list of all initial open land survey 606 units is provided in Table 2-4. 607  Northeast Corner of the Exclusion Area 608  Power House Area 609  Owner Controlled Area North of Shiloh Boulevard 610  Owner Controlled Area West and South of the West Training Area 611  Owner Controlled Area West of the Switchyard 612  Met Tower Area 613 Non-impacted open land survey units are illustrated on Figure 2-4. 614 2.2. Characterization Approach 615 Site characterization of the ZNPS was performed in accordance with the Characterization Survey 616 Plan. It was developed to provide guidance and direction to the personnel responsible for 617 implementing and executing characterization survey activities. The Characterization Survey 618 Plan worked in conjunction with implementing procedures and survey unit specific survey 619 instructions (sample plans) that were developed to safely and effectively acquire the requisite 620 characterization data. 621 Characterization data acquired through the execution of the Plan was used to meet three primary 622 objectives: 623  Provide radiological inputs necessary for the design of FRSFSS, 624  Develop the required inputs for this License Termination Plan (LTP), and 625  Support the evaluation of remediation alternatives and technologies and estimate waste 626 volumes. 627 The decommissioning approach for the ZSRP calls for the demolition and removal of all on-site 628 buildings, structures, and components to a depth of at least 3 feet below grade. Consequently, 629 characterization efforts focused on open land areas and remaining structures that will be 630 subjected to FRSFSS. Extensive characterization of equipment, systems or structures that will 631 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-16  be removed prior to the performance of final surveys is not required in accordance with 632 NUREG-1757, Appendix O. 633 The decommissioning approach for ZSRP also calls for the beneficial reuse of concrete from 634 building demolition as clean fill. The only concrete structures that will be considered are those 635 where the probability of residual contamination is minimal. Characterization in this case will 636 consist of an in-situ assessment of the concrete under consideration to ascertain if the structure 637 concrete is an acceptable candidate. Concrete that meets the non-radiological definition of Clean 638 Concrete Demolition Debris (CCDD) and where has been deemed suitable for offsite release in 639 accordance with the site unconditional release process  FSS demonstrates that the concrete is free 640 of plant derived radionuclides above background may be used as basement fill.Demonstration 641 that plant-derived radioactive materials are not present will be accomplished with a separate 642 survey that will be designed in accordance with NUREG-1575, Supplement 1, "Multi-Agency 643 Radiation Survey and Assessment of Materials and Equipment Manual" (MARSAME) 644 (Reference 2-12). 645 A significant question that must be answered by the characterization is whether or not a survey 646 unit is classified correctly. The appropriate classification of a survey unit is critical to the survey 647 design for FRSFSS. A classification which underestimates the potential for contamination could 648 result in a survey design that does not obtain adequate information to demonstrate that the survey 649 unit meets the release criteria. In some cases, this can increase the potential for making decisions 650 errors. 651 As site-specific DCGLs were not yet established for the Zion decommissioning at the time the 652 characterization survey was performed, alternate action levels were selected. The screening 653 DCGLs presented in NUREG-1757 and the concentration values found in NUREG/CR-5512 654 Volume 3, "Residual Radioactive Contamination from Decommissioning Parameter Analysis" 655 (Reference 2-13), Table 6.91 (Pcrit = 0.10) for soils were used as alternate action levels to assess 656 the correct classification of impacted open land or soil survey units. 657 For structures, the gross screening level that was used during characterization as an action level 658 to evaluate the classification of survey units was the nuclide-specific screening value of 659 7,100 dpm/100cm2 total gross beta-gamma surface activity based on Co-60 from NUREG-1757, 660 Appendix H. Use of the Co-60 screening value was conservative as it was anticipated that the 661 radionuclide distribution for surface contamination would be principally Co-60 and Cs-137 and, 662 the more conservative approach was to assume a distribution of 100% Co-60 as the screening 663 value for Cs-137 is significantly greater. 664 2.2.1. Data Quality Objectives 665 DQOs were implemented for characterization surveys in a similar manner as anticipated for the 666 FRSFSS. However, the goal of characterization is contamination quantification and delineation 667 of the nuclide suite, whereas the FRS FSS goal is comparison of data against the unrestricted use 668 criteria to demonstrate compliance with 10 CFR 20.1402. Characterization inspections and 669 surveys of sufficient quality and quantity were performed to determine the nature, extent and 670 range of radioactive contamination in each applicable survey unit, including applicable 671 structures, residues, soils and surface water. 672 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-17  Characterization surveys were designed to gather the appropriate data using the DQO process as 673 outlined in MARSSIM, Appendix D. The seven steps in the DQO development process are: 674 1) State the problem, 675 2) Identify the decision, 676 3) Identify inputs to the decision, 677 4) Define the study boundaries, 678 5) Develop a decision rule, 679 6) Specify limits on decision errors, and 680 7) Optimize the design for obtaining data. 681 The DQOs for site characterization included identifying the types and quantities of media to 682 collect. No structures located above 3 feet below grade will remain following decommissioning 683 and be subjected to FRSFSS. Consequently, sample collection was focused on the assessment of 684 concrete basement structure materials and surrounding soils. Building concrete was sampled by 685 obtaining concrete core samples. Soils were sampled volumetrically. Sufficient measurements 686 were obtained to determine the mean and maximum activity as well as the sample standard 687 deviation. Direct measurements and scans of concrete and surface soils were also made using 688 the same instruments and Minimal Detectable Concentrations (MDC) as will be employed for 689 FSS. Volumetric samples that exhibited the highest activity were sent to an off-site laboratory 690 for analysis of Hard-to-Detect (HTD) radionuclide(s). 691 2.2.2. Survey Design 692 Characterization surveys were designed and performed in accordance with all applicable 693 approved procedures and the Characterization Survey Plan. Survey design incorporated a graded 694 approach based upon the DQOs for each survey unit. For example, an open land survey unit was 695 designated as Class 1 because it may contain levels of radiological contamination greater than 696 the unrestricted release criteria. Therefore, the characterization surveys that were performed in a 697 Class 1 survey unit focused on bounding the contamination where contamination was potentially 698 present. The survey design was based upon the number of measurements and samples required 699 to identify the lateral and vertical extent of the contamination. Areas classified as non-impacted, 700 Class 2 or Class 3 received surveys developed to include a combination of systematic and biased 701 survey measurement locations and scan areas. Biased survey designs used known information to 702 select locations for static measurements and/or samples. Systematic survey design selected static 703 measurement and/or sample locations at random or by using a systematic sampling design with a 704 random start. The decision of whether to use primarily a biased survey design or a systematic 705 approach was addressed by the DQO process for each survey unit. A biased approach was 706 warranted when the characterization effort was designed to delineate the extent of an area that 707 requires remediation. Alternatively, a systematic approach was warranted if the characterization 708 effort was designed to verify the basis for the classification of a survey unit. 709 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-18  2.2.2.1. Number of Static Measurements and/or Samples 710 The number of measurements and/or samples that were taken in each survey unit was determined 711 by assessing the sample size necessary to satisfy the DQOs. 712 For the characterization of structural survey units that would not remain at license termination 713 and not be subjected to FRSFSS, the numbers of static measurements and/or samples taken were 714 a sufficient quantity to determine the general radiological condition of the survey unit, including 715 average and maximum concentration of loose surface contamination and total surface 716 contamination if possible. 717 For the characterization of impacted Class 1 open land areas and Class 1 basement structures that 718 will remain and be subjected to FRSFSS, the sample size was based upon the necessary number 719 of samples needed to assess the lateral and vertical extent of the contamination. 720 For the characterization of impacted Class 2 open land areas and impacted Class 2 or Class 3 721 impacted basement structures that will be subjected to FRSFSS, the minimum number of static 722 measurements and/or samples that were taken in each survey unit was commensurate with the 723 probability of the presence of residual radioactive contamination in the survey unit. 724 For non-impacted and Class 3 open land survey units, the primary characterization DQO was to 725 validate the basis of the classification. Consequently, the number of systematic static 726 measurements and/or samples was sufficiently robust so that a high degree of confidence was 727 achieved to establish that only diminutive levels of licensee-generated radioactive material 728 resided in these areas. 729 2.2.2.2. Determination of Static Measurement or Sample Locations 730 For the characterization of non-impacted and impacted open land areas and Class 2 structural 731 survey units that will be subjected to FRSFSS, sample locations were primarily chosen at 732 random. Sample locations were determined by generating random pairs of coordinates that 733 corresponded to specific locations within the survey unit. The location of biased measurements 734 and/or samples that were taken in each survey unit was determined by the professional judgment 735 of the responsible Radiological Engineer during the survey design process. Consideration was 736 given to locations that exhibit measurable radioactivityexhibited measurable radiation levels 737 above background (i.e. by scanning), depressions, discolored areas, cracks, low point gravity 738 drain points, actual and potential spill locations, or areas where the ground has been disturbed. 739 Historical information from the HSA aided in the selection of biased locations. 740 2.2.2.3. Scan Coverage 741 Survey units were scanned to the extent practical in accordance with their classification. The 742 area to be scanned in each survey unit was determined during the survey design process. The 743 area scanned was contingent upon the accessibility of the surface areas in the survey unit and the 744 recommended scan coverage guidelines presented in Table 2-5. 745 2.2.2.4. Types of Measurements or Samples 746 The characterization survey of building surfaces consisted of a combination of surface scans 747 (beta and gamma); static beta measurements, material samples and smears. The characterization 748 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-19  survey of any concrete and/or asphalt-paved open land areas that will remain and be subjected to 749 FRS FSS consisted of a combination of surface scans (beta and gamma), static beta 750 measurements, and volumetric samples. The survey of the open land areas consisted of gamma 751 scans and the sampling of surface and subsurface soil, sediment and surface water for isotopic 752 analysis. The following is a description of the different types of measurements and samples that 753 were utilized. 754 2.2.2.4.1. Static Measurements 755 Static measurements were performed to detect direct levels on structural surfaces of the buildings 756 or on concrete or asphalt paved areas. These measurements were performed using primarily 757 ~126 cm2 scintillation or gas-flow proportional detectors. 758 Static measurements were conducted by placing the detector on or very near the surface to be 759 counted and acquiring data over a pre-determined count time. Instrument count times were 760 adjusted as appropriate to achieve an acceptable MDC for static measurements. 761 2.2.2.4.2. Beta Surface Scans 762 Scanning was performed in order to locate areas of residual activity above the 763 7,100 dpm/100cm2 action level. Beta scans were performed over accessible structural surfaces 764 including, but not limited to; floors, walls, ceilings, roofs, asphalt and concrete paved areas. 765 Floor monitors using large area gas-flow proportional detectors (typically with 584 cm2) were 766 used for floor and other larger accessible horizontal surfaces. Hand-held beta scintillation and/or 767 gas-flow proportional detectors (typically 126 cm2) were used for surfaces not accessible by a 768 floor monitor. 769 Beta scanning was performed with the detector position maintained within 1.27 cm (0.5 inch) of 770 the surface and with a scanning speed of one detector active window per second. If surface 771 conditions prevented scanning at the specified distance, the detection sensitivity for the alternate 772 distance was determined, and the scanning technique adjusted accordingly. Scanning speed was 773 calculated a priori to ensure that the MDC for scanning was appropriate for the stated objective 774 of the survey. 775 If not impacted by high ambient noise levels, technicians monitored the audible response of the 776 instrument to identify locations of elevated activity that require further investigation and/or 777 evaluation. Any identified areas of elevated contamination were marked or flagged for further 778 investigation and potential decontamination. 779 2.2.2.4.3. Gamma Surface Scans 780 Gamma scans were performed over open land surfaces to identify locations of residual surface 781 activity. Sodium iodide (NaI) gamma scintillation detectors (typically 2" x 2") were typically 782 used for these scans. ZionSolutions TSD 11-004, "Ludlum Model 44-10 Detector Sensitivity" 783 (Reference 2-14) examines the response and scan MDC of the Ludlum Model 44-10 NaI 784 detectors to Co-60 and Cs-137 when used for scanning surface soils. 785 Scanning was performed by moving the detector in a serpentine pattern, while advancing at a 786 rate not to exceed 0.5 m (20 in) per second. The distance between the detector and the surface 787 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-20  was maintained within 15 cm (6 in) of the surface if possible. Audible signals were monitored; 788 and, locations of elevated direct levels were flagged for further investigation and/or sampling. 789 2.2.2.4.4. Removable Surface Contamination 790 If applicable, removable beta contamination or smear surveys were performed to verify loose 791 surface contamination is less than the action level of 1,000 dpm/100cm2. A 100 cm2 surface area 792 was sampled with a circular cloth or paper filter, using moderate pressure. Smears were then 793 analyzed for the presence of gross beta activity using a proportional counting system or 794 equivalent. 795 2.2.2.4.5. Concrete Core Sampling 796 Concrete core boring and the sampling of concrete were used to assess the depth of surficial 797 contamination and the presence of volumetric contamination in concrete walls and floors that 798 will remain and be subjected to FRSFSS. Core bore sampling of concrete was accomplished 799 using a diamond bit core drill. The concrete sample produced by the coring was typically sliced 800 into    1/2-inch wide "pucks", representing a certain depth into the surface. Static measurements 801 were performed on the top and bottom of the pucks to determine contaminant intrusion depth 802 and/or the activation of the concrete matrix. Concrete pucks were also pulverized and analyzed 803 for isotopic content. 804 2.2.2.4.6. Material Sampling 805 Samples of soil, sediment, and sludge were obtained from designed judgmental and systematic 806 sample locations as well as other biased locations in areas exhibiting elevated activity that were 807 identified by scanning. Surface soil is defined as the top 15 cm (6-inch) layer of soil while 808 subsurface soil is defined as soil below the top 15 cm layer in 1 m increments. Surface soil was 809 collected using a split spoon sampling system or, by using hand trowels, bucket augers, or other 810 suitable sampling tools. 811 Subsurface soil was sampled by direct push sampling systems (e.g. GeoProbe) or by the 812 excavation of test pits. Subsurface soil sampling was performed as necessary to address the 813 DQOs for the survey unit. 814 An adequate amount of material (ranging from 0.5 liters up to 2 liters) was collected at each 815 location. Sample preparation included the removal of extraneous material and the 816 homogenization and drying of the soil for analysis. Separate containers were used for each 817 sample and each container will be accounted for throughout the analysis process using positive 818 physical control or by a chain-of-custody record. 819 2.2.3. Instrumentation Selection, Use and Minimum Detectable Concentrations (MDCs) 820 The radiation detection and measurement instrumentation for characterization was selected to 821 provide both reliable operation and adequate sensitivity to detect the Radionuclides of Concern 822 (ROC) identified for the decommissioning of the ZNPS at levels sufficiently below the 823 established action levels. Detector selection was based on detection sensitivity, operating 824 characteristics, and expected performance in the field. In all cases, the instruments and detectors 825 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-21  selected for static measurements and scanning were capable of detecting the anticipated ROC at 826 a MDC of 50% of the applicable action level. 827 Commercially available portable and laboratory instruments and detectors were typically used to 828 perform the three basic survey measurements: 1) surface scanning; 2) static measurements; and 829 3) analysis of material samples. 830 Instrumentation and nominal MDC values that were employed during characterization are listed 831 in Table 2-6. 832 2.2.3.1. Instrument Calibration 833 All data loggers, associated detectors, and all other portable instrumentation that were used for 834 characterization were calibrated on an annual basis using National Institute of Standards and 835 Technology (NIST) traceable sources. The calibration of instruments used for characterization is 836 addressed in section 5.2 of the QAPP. 837 2.2.3.2. Instrument Use and Control 838 The receipt, inspection, issue, control, and accountability of portable radiological instrumentation 839 used for characterization was performed in accordance with issue and control procedures for 840 portable radiological instrumentation. The issue and control of instruments used for 841 characterization is addressed in section 5.1 of the QAPP. 842 2.2.4. Laboratory Instrument Methods And Sensitivities 843 Gamma spectroscopy was primarily performed by the on-site radiological laboratory. Gas 844 proportional counting and liquid scintillation analysis was performed by an approved vendor 845 laboratory in accordance with approved laboratory procedures. ZionSolutions ensured that the 846 quality programs of the contracted off-site vendor laboratories that were used for the receipt, 847 preparation and analysis of characterization samples provided the same level of quality as the on-848 site laboratory under the QAPP. 849 In all cases, analytical methods were established to ensure that required MDC values are 850 achieved. The analysis of radiological contaminants used standard approved and generally 851 accepted methodologies or other comparable methodologies. Table 2-7 provides the typical 852 analytical methods employed and the laboratory MDC achieved by the off-site vendor 853 laboratories used for characterization. 854 2.2.5. Quality Assurance 855 MARSSIM, section 2.2 discusses the need for a quality system to ensure the adequacy of data 856 used to demonstrate that site conditions are acceptable for unrestricted release. Laboratory 857 quality for sample analysis taken to support characterization and FRS FSS is discussed in 858 NUREG-1576, "Multi-Agency Radiological Laboratory Analytical Protocols Manual 859 (MARLAP)" (Reference 2-15) and Regulatory Guide 4.15, "Quality Assurance of Radiological 860 Monitoring Programs (Inception through Normal Operations to License Termination) - Effluent 861 Streams and the Environment" (Reference 2-16). Further, MARSSIM and MARLAP both 862 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-22  indicate that a Quality Assurance Project Plan may be used in addition to, or in lieu of, existing 863 quality systems to ensure data quality is achieved. 864 The QAPP was prepared and implemented to ensure the adequacy of data being developed and 865 used during the site characterization and FRS FSS process. The QAPP describes policy, 866 organization, functional activities, the DQO process, and measures necessary to achieve quality 867 data. It supplements the quality requirements and quality concepts presented in ZS-QA-10, 868 "Quality Assurance Project Plan - Zion Station Restoration Project" (Reference 2-17) which 869 adequately encompass other risk-significant decommissioning activities. 870 All characterization activities essential to data quality were implemented and performed using 871 approved procedures. The effective implementation of characterization was verified through 872 audit and surveillance activities, including field walk-downs by ZionSolutions 873 Characterization/License Termination management and radiological engineering staff and 874 program self-assessments, as appropriate. Corrective actions were prescribed, implemented, and 875 verified when deficiencies were identified. These measures applied to any applicable services 876 provided by off-site vendors, as well as on-site sub-contractors. 877 The Characterization Survey Plan was developed according to the essential elements of the 878 quality assurance and quality control (QA/QC) program for the decommissioning of the ZNPS 879 and is subject to the QAPP. The QA/QC program elements applicable to characterization are as 880 follows: 881  Establishment/implementation of plans, procedures, and protocols for the field operations. 882  Actions to ensure that the procedures are understood and followed by the implementing staff. 883  Documentation of the data collected. 884 Details of the QA/QC elements specific to characterization are presented in the QAPP, as well as 885 the procedures and sample plan instructions. The characterization operations and the associated 886 data acquisition and recording was guided and conducted in compliance with these QA/QC 887 requirements. The specific QA/QC program components for site characterization are as follows: 888  Personnel qualifications, experience, and training. 889  Execution in accordance with approved procedures. 890  Proper documentation of survey data and sample analyses. 891  Selection of appropriate instruments to perform the surveys. 892  Proper instrument calibration and daily functional checks. 893  Management oversight of characterization activities relative to the adherence to procedures, 894 protocols, and documentation requirements. 895 All characterization activities were conducted in accordance with the Characterization Survey 896 Plan, the QAPP, all applicable implementing procedures, and approved sample plan instructions. 897 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-23  2.3. Summary of Characterization Survey Results 898 The site characterization of the ZNPS site commenced on November 2, 2011 with the 899 characterization of the open land survey units encompassing the proposed site for the future 900 ISFSI facility. At the time this survey was performed, the site-specific ZionSolutions 901 characterization plans and procedures were still under development. Consequently, due to 902 schedule constraints, ZionSolutions contracted the EnergySolutions Commercial Services Group 903 (ESCSG) to perform characterization of the ISFSI location, the location where the Vertical 904 Concrete Cask (VCC) Construction Area was to be located and the pathway for the new rail 905 tracks. These locations are illustrated on Figures 2-17 and 2-18. These surveys were performed 906 on a turnkey basis using ESCSG technicians, procedures and instrumentation. A survey-specific 907 characterization plan was developed and approved for these areas, survey packages were 908 prepared and executed in accordance with ESCSG procedures and a final report 909 "Characterization of the Zion Station Independent Spent Fuel Storage Facility (ISFSI) 910 (Reference 2-18) dated July 30, 2012 was prepared by ESCSG and approved by ZionSolutions. 911 The results of these surveys were validated and integrated into the subsequent site-specific 912 characterization program and the results are reported in this chapter as valid characterization data 913 for the affected survey units. 914 In February 2012, the site-specific ZionSolutions site characterization program was approved. In 915 addition, all required personnel, equipment and instrumentation necessary to implement the 916 characterization program were procured. Characterization activities, self-performed by 917 ZionSolutions in accordance with the ZionSolutions characterization program commenced on 918 April 10, 2012 with the acquisition of concrete core samples from the 542 foot elevation of the 919 Auxiliary Building. The initial scheduled site characterization effort concluded on 920 November 11, 2013. 921 Throughout 2012 and 2013, characterization activities were performed in parallel with 922 radioactive commodity removal and radioactive waste shipment activities at ZNPS. 923 Consequently, the removal and movement of radioactive material directly impacted the ability to 924 access certain structural survey units and open land areas and obtain meaningful characterization 925 survey data. In several specific areas, characterization has been deferred until such time that 926 radiological or physical conditions would allow access for characterization. ZionSolutions 927 intends to continue characterization throughout the decommissioning process, including 928 following the submittal of this LTP. This is discussed further in section 2.5. In these cases, 929 characterization has been deferred until such time that radiological or physical conditions would 930 allow the survey of these survey units. It is the intention of the ZSRP to continue 931 characterization throughout the decommissioning process, including following the submittal of 932 this LTP. In the case where significant additional characterization data is obtained, this chapter 933 of the LTP will be updated by revision or addendum as a part of the required 2 year update of the 934 approved LTP. 935 2.3.1. Background Studies 936 Several background studies were performed on the ZNPS site to assess background for soils and 937 concrete. The first study was performed in February of 2012 by ESCSG as an integral part of the 938 work scope pertaining to the characterization of the ISFSI and VCC construction area. During 939 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-24  this study, soil, concrete and asphalt was assessed though surface scanning and volumetric 940 sampling and analysis. In March and April of 2012, ZionSolutions conducted a comprehensive 941 background study of non-contaminated concrete by acquiring and analyzing concrete core 942 samples taken from the 559 foot elevation and 594 foot elevation of the Crib House. This study 943 was conducted to support the eventual evaluation of concrete demolition debris as clean hard fill. 944 In July of 2012, an additional study was performed to evaluate background for soils. Additional 945 scanning and acquisition and analysis of volumetric soil samples were performed. 946 2.3.1.1. EnergySolutions Background Study 947 The primary purpose of the EnergySolutions background study was to identify and quantify the 948 levels of natural activity, including fallout, within soils and construction materials. This effort 949 included support of the unconditional release and potential re-use of concrete originating from 950 ZNPS as potential backfill material. The surveys were performed using the same instruments 951 and survey techniques that will were to be used during characterization. 952 This background study was performed through the selection of reference background areas 953 known to be unaffected by plant operations to ensure any measured radioactivity would be of 954 natural origin. It was determined that the best location for measuring background would be 955 outside the restricted area boundary toward the north as based in part on "Annual Report on the 956 Meteorological Monitoring Program at Zion Nuclear Power Station for 2010" (Reference 2-19), 957 which demonstrated that winds are predominately from the west and northwest at the site. As a 958 result, locations north and northwest of the restricted area were less likely to be impacted by 959 airborne particulate and gaseous effluents from past plant operations. 960 To ensure that the data is was relevant, it was necessary to ensure the background reference areas 961 selected were representative of the materials and areas to be surveyed at the facility. This 962 included soils of similar geology and construction materials of similar age and content. 963 Consequently, the reference area(s) selected were located as near to the facility as possible and 964 representative of the construction of the plant. It was determined, based upon this selection 965 criterion, that the area around the former Visitors Center would be representative of background 966 at the site. Figure 2-19 represents the background survey locations used during the 967 EnergySolutions background assessment. 968 Surface scans and direct surface activity measurements were performed for gross beta activity on 969 both asphalt and concrete surfaces within the background reference areas. In addition, gamma 970 walkover scans and direct measurements were performed over soil and vegetation. The scans 971 were distributed evenly over each background reference area. One-minute static measurements 972 were also collected. 973 In addition to the surface scans and direct measurements, samples were collected for volumetric 974 analysis by gamma spectroscopy analysis. Fifteen (15) samples were taken of asphalt, concrete 975 and surface soils and were analyzed by a qualified off-site vendor laboratory. 976 To account for any potential difference in geology, subsurface samples were also collected at 977 each surface sampling location to assess for any differences in background if present. 978 Subsurface samples were collected at depths between 6 inches below grade down to a depth of 979 about 4 feet using GeoProbe&#x17d;. Subsurface soil samples were composited over the depth of the 980 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-25  sampled soil column. As with the surface soils, all composite subsurface samples were also 981 analyzed by a qualified off-site vendor laboratory. 982 The results of the Energy Solutions background study was presented in CS-RS-PN-028, 983 "Background Reference Area Report - Zion Nuclear Power Station" (Reference 2-20). A 984 summary of the background survey results from this assessment is provided in Table 2-8. Based 985 upon a review of the sample analysis results for asphalt, concrete and soils, only natural activity 986 expected in background was detected. No other licensed materials were identified in the 987 samples. Additionally, based upon the activities of the daughter products within the decay chain, 988 in approximate equilibrium, the background reference area(s) and samples were deemed 989 representative of background and were not impacted by site activities. A review of both the 990 surface and subsurface soil sample results concluded that there appears to be no difference 991 between the surface and subsurface radionuclide distribution. 992 2.3.1.2. Crib House Concrete Study 993 In March of 2012, ZSRP commenced an assessment of the concrete 594 foot and 559 foot 994 elevation floors and lower walls of the Crib House. The DQOs established for this survey were 995 to establish a background threshold range for volumetric concrete at ZNPS, evaluate the 996 basement foundations and floors of the Crib House for the presence of volumetric radiological 997 contamination and to provide a sufficient quantity and quality of uncontaminated concrete media 998 representative of the "Basement Fill" concrete to an off-site vendor for the derivation of 999 distribution coefficients for the radionuclides of concern. 1000 On each floor (594 foot and 559 foot elevations), 16 six-inch concrete core samples were taken 1001 from the floors and 4 six-inch concrete core samples were taken from the lower walls for a total 1002 of 40 concrete core samples. Sample locations were selected at random. Prior to acquiring the 1003 core samples, the area was scanned to ensure the absence of surficial radioactive contamination 1004 at each sample location. Scans were performed with a Ludlum 43-93 100 cm2 alpha-beta 1005 scintillator detector. Gross beta background ranged from 150 cpm to 300 cpm. No activity 1006 greater than background was observed at each selected sample location. 1007 All concrete core samples were analyzed by the on-site gamma spectroscopy system for gamma 1008 emitting radionuclides. Only natural activity expected in background was detected during the 1009 analysis. No other licensed materials were identified in the samples. A summary of the survey 1010 results from the assessment of the Crib House concrete is provided in Table 2-9. 1011 2.3.1.3. ZionSolutions Soil Background Study 1012 In July of 2012, a survey was performed of non-impacted soils adjacent to the ZNPS owner 1013 controlled area with the objective of determining background radioactivity concentrations in 1014 soils. The area chosen for the survey was the Zion City Park District's "Hosah Park", located 1015 north of the ZNPS at the end of Shiloh Boulevard. The park consists of open land areas covered 1016 with native grasses and low lying brush. While there did appear to be evidence of soil 1017 disturbance on the property, the evidence suggested that this occurred in the past and the land has 1018 been undisturbed for a number of years. Figure 2-20 illustrates the location of the area chosen 1019 for the survey. 1020 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-26  The survey was designed to determine the radionuclide activity concentrations of key naturally 1021 occurring and man-made radionuclides, particularly Cs-137, in surface and subsurface soils. The 1022 survey design included surface and subsurface soil samples as well as static gamma 1023 measurements. Thirty (30) sample locations were chosen, biased towards soils that appeared to 1024 be undisturbed with minimal vegetation. At each location, a static one-minute measurement was 1025 taken using a sodium iodide detector, a sample was taken from the soils within the first 15 cm of 1026 grade and a composite soil sample was taken from soils between 15 cm below grade to 60 cm 1027 below grade. All soil samples were analyzed by a qualified off-site vendor laboratory. 1028 The results of the survey were presented in a report titled "Determination of Radionuclide 1029 Activity Concentrations in Soils in Non-Impacted Soils Adjacent to the Zion Nuclear Station" 1030 (Reference 2-21). In both surface and subsurface soil populations, the only radionuclide 1031 identified, with the exception of naturally occurring radionuclides, was Cs-137. In the surface 1032 soil sample population, Cs-137 was positively identified in concentrations greater than MDC in 1033 26 of the 30 samples. In the subsurface soil population, Cs-137 was positively identified in 1034 concentrations greater than MDC in five (5) of the 30 samples obtained. Based upon the 1035 concentrations observed and the distribution, it was postulated that the presence of Cs-137 was 1036 due to global fallout. The results of the sample analysis are presented in Table 2-10. 1037 2.3.1.4. Technical Support Document Regarding Cs-137 Global Fallout 1038 In order to establish an investigation action criteria indicative of Cs-137 contamination levels in 1039 soil that are distinguishable from background levels, ZionSolutions TSD 13-004, "Examination 1040 of Cs-137 Global Fallout In Soils At Zion Station" (Reference 2-22) was prepared to document 1041 ZionSolutions soil sample results for Cs-137 in soils to date and compare the results to those 1042 anticipated from world-wide fallout. The TSD established the technical basis for the anticipated 1043 soil concentrations attributable to fallout and established criteria for investigating soil samples 1044 due to observed Cs-137 concentrations. 1045 The soil sample data compiled in the TSD concludes that the majority of the soil samples taken 1046 for the background studies were from disturbed soils. The Hosah Park data as well as the data 1047 obtained during the ESCSG study corresponded with documented fallout levels from disturbed 1048 soil at sites in Massachusetts, New York and Pennsylvania. Consequently, predicted ranges for 1049 background concentrations of Cs-137 were established for disturbed soils as well as undisturbed 1050 soils based on literature. These ranges are presented in Table 2-11. The upper Cs-137 1051 concentration for each category was used as the action level for the characterization of non-1052 impacted open land survey units. The upper Cs-137 concentration for disturbed, non-drainage 1053 soil in Table 2-11 was used as the action level for the characterization of Class 2 and 3 open land 1054 area survey units.The upper Cs-137 concentration for each category was used as the investigation 1055 levels for non-impacted open land survey units. The upper Cs-137 concentration for disturbed, 1056 non-drainage in Table 2-11 was used as the investigation level for Class 2 and 3 open land area 1057 survey units. 1058 2.3.2. Potential Radionuclides of Concern 1059 ZionSolutions TSD 11-001, "Potential Radionuclides of Concern during the Decommissioning 1060 of Zion Station" (Reference 2-23) was prepared and approved in November 2011. The purpose 1061 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-27  of this document was to establish the basis for an initial suite of potential ROCs for the 1062 decommissioning. Industry guidance was reviewed as well as the analytical results from the 1063 sampling of various media from past plant operations. Based on the elimination of some of the 1064 theoretical neutron activation products, noble gases and radionuclides with a half-life less than 1065 2 years, an initial suite of potential ROC for the decommissioning of the ZNPS was prepared. 1066 The list of potential radionuclides is listed in Table 2-12. 1067 2.3.3. Impacted Structures and Systems 1068 The decommissioning approach for the ZSRP requires the demolition and removal of all 1069 impacted buildings, structures, systems and components to a depth of at least 3 feet below grade. 1070 In addition, all systems and exposed metal below 3 feet below grade will also be removed. The 1071 accepted elevation for grade at ZNPS is the 591 foot elevation. The only structures that will 1072 remain and be subjected to STS FSS are the exposed steel lined walls and floor from the Unit 1 1073 and Unit 2 Containment Buildings (after all interior concrete is removed) and the below-grade 1074 structural concrete outside of the liner, the reinforced concrete basement floor and outer walls of 1075 the Auxiliary Building and Turbine Building (after all internal walls and floors are removed), the 1076 reinforced concrete floor and walls of the SFP and Fuel Transfer Canal (after the steel liner is 1077 removed), the concrete floor and walls of the Crib House, the WWTF, the Forebay and 1078 Circulating Water Intake Piping and Discharge Piping Tunnel below the 588 foot elevation. 1079 Consequently, all systems and components and structural surfaces above the 588 foot elevation 1080 will be remediated, disassembled and/or demolished, segregated by waste classification and 1081 disposed of as clean demolition debris, clean salvage or radioactive waste. No extensive 1082 characterization was or will be performed of equipment, systems or structures that will be 1083 removed prior to the performance of FRSFSS. 1084 The current decommissioning approach for ZSRP also calls for the beneficial reuse of concrete 1085 from building demolition as clean fill. The only concrete structures that will be considered are 1086 those where the probability of the presence of residual contamination is minimal. Only concrete 1087 that has been demonstrated to be free of detectable plant-derived radionuclides and hazardous 1088 painted surfaces will be used. Characterization in this case will consist of an in-situ assessment 1089 of the concrete under consideration to ascertain if the structure concrete is an acceptable 1090 candidate. Only concrete that meets the non-radiological definition of CCDD and has been 1091 deemed suitable for offsite release in accordance with the site unconditional release process 1092 where FSS demonstrates that the concrete is free of plant derived radionuclides above 1093 background may be used as basement fill.Compliance with the unrestricted release criteria will 1094 be demonstrated with a separate survey that will be designed in accordance with MARSAME. 1095 Radiological surveys of the interiors of structures at the ZNPS are routinely performed to ensure 1096 compliance with 10 CFR 20 requirements regarding the posting of areas and to identify 1097 radiological conditions for the implementation of controls for the protection of workers in these 1098 areas. The radiological information from these surveys will provide the basis for the 1099 disassembly and removal of systems and the demolition of impacted structures at the site. When 1100 remediation has adequately reduced radiological conditions to levels suitable for controlled 1101 demolition, the impacted structures will be demolished, packaged and properly disposed of as 1102 waste. 1103 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-28  After commodity removal is complete, the structures that will remain at license termination, i.e., 1104 3 feet below grade, will be re-surveyed to determine the concentrations of the residual 1105 radioactivity and the extent of additional remediation required, if any, to meet the unrestricted 1106 use criteria. 1107 2.3.3.1. Unit 1 and Unit 2 Containments 1108 The Unit 1 and Unit 2 Containment buildings house numerous systems containing primary 1109 coolant as well as radioactively contaminated support systems. Physically, both units are 1110 basically mirror images of the other. System leakage and maintenance activities over the 1111 operating life of both units have resulted in the radiological contamination of most of the interior 1112 surfaces of both structures. Some components, equipment, structural steel and concrete have 1113 become radioactive due to neutron activation. Based on the building design basis, the operating 1114 history as well as the present status of areas that are controlled as contaminated areas, all internal 1115 survey units in both the Unit 1 and Unit 2 Containment Buildings are considered to be Class 1 1116 areas. 1117 General area radioactive dose rates within the buildings range from 1 mrem/hr to over 1118 250 mrem/hr. Loose radioactive contamination ranges from <1,000 dpm/100 cm2 to over 1119 110 mrad/swipe. The general radiological conditions within the Unit 1 and Unit 2 Containment 1120 buildings are presented per survey unit in Table 2-13. 1121 The basic decommissioning end-state for each Containment building will consist of the walls and 1122 floors below 588 foot elevation. In both Containment basements, all concrete will be removed 1123 from the interior side of the steel liner above the 565 foot elevation, leaving only the remaining 1124 exposed liner below the 588 foot elevation, the concrete in the In-core Instrument Shaft leading 1125 to and including the area under vessel (or Under-Vessel area), and the structural concrete outside 1126 of the liner. Interior concrete walls and floors except for the 568 foot elevation floor and the 1127 under-vessel incore walls and floor will be removed. In addition, the 3 feet of concrete on the 1128 568 foot elevation floor will be removed to expose the metal liner. The exposed metal liner will 1129 be remediated cleaned to levels commensurate with inventory limits in the Basement Fill Model 1130 (BFM) that represent the annual dose criterion for unrestricted release specified in 1131 10 CFR 20.1402.below DCGLs for basement structures (Chapter 5, Table 5-3). It is anticipated 1132 that only activity remaining on the steel liner after concrete removal will be loose dust from the 1133 demolition of the concrete. Following completion of a STS FSS in accordance with section 5.5.3 1134 4 of this LTP, the basements will be backfilled with clean fill, clean concrete debrisCCDD, 1135 grout, or a combination of the three materials. 1136 The large components inside each structure such as the Reactor Vessel, Pressurizer, Steam 1137 Generators, Reactor Coolant Pumps, primary piping and all associated systems will be removed 1138 and properly disposed of as radioactive waste. Several sections of pipe that is located below the 1139 588 foot elevation that are embedded in concrete may remain as part of the final configuration of 1140 the structure. An embedded pipe is defined as a pipe that runs vertically through a concrete wall 1141 or horizontally through a concrete floor and is contained within a given building. A penetration 1142 is defined as a pipe (or remaining pipe sleeve, if the pipe is removed, or concrete, if the pipe and 1143 pipe sleeve is removed) that runs through a concrete wall and/or floor, between two buildings, 1144 and is open at the wall or floor surface of each building. A penetration could also be a pipe that 1145 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-29  runs through a concrete wall and/or floor and opens to a building on one end and the outside 1146 ground on the other end. The list of penetrations and embedded piping to remain is provided in 1147 ZionSolutions Technical Support Document (TSD) 14-016, "Description of Embedded Pipe, 1148 Penetrations, and Buried Pipe to Remain in Zion End State" (Reference 2-24).In most cases, 1149 these sections of pipe will consist of penetrations through the concrete structure, however 1150 sleeved sections of embedded sump discharge piping that originate in the Unit 1 and Unit 2 1151 Cavity Flood and Recirculation sumps and end in the Auxiliary building Equipment Drain 1152 Collection Tank room could also remain. 1153 The upper steel containment liner, the refuel cavity and all interior walls above the 588 foot 1154 elevation in both units will also be removed and disposed of as radioactive waste. The outer 1155 containment shells above the 588 foot elevation will be surveyed and demolished. If the exterior 1156 concrete is free of detectable plant-derived radioactive material, it may be used as clean hard 1157 fillCCDD or disposed of as clean demolition debris. All waste material will be packaged and 1158 sent offsite for disposal at approved disposal facilities for radioactive waste or clean demolition 1159 debris. 1160 It is anticipated that the most highly activated concrete in either Containment will be the internal 1161 radius of the Bio-Shield concrete that surrounded the vessel as it was closest to the active core 1162 region. The concrete inside the liner in the underUnder-vessel Vessel incore area is also 1163 activated. Unit 1 and 2 Containment have interior concrete walls 23.5 inches thick in the under 1164 Under-Vvessel incore area and 30 inch thick concrete floors inside the liner. Consequently, the 1165 potential for activation outside the liner is minimal. 1166 During the time that initial characterization was performed, all radioactive systems and 1167 components were still located inside each Containment. Consequently, ambient radiation dose 1168 rates inside the Containments prohibited the direct assessment of concrete and steel structural 1169 surfaces below the 588 foot elevation by scanning or direct measurement. Once commodity 1170 removal is complete in both of these structures, additional characterization will be performed by 1171 scan and direct measurement to identify the lateral and vertical extent of surficial contamination 1172 and the extent of any remediation that will be necessary on the structural steel and concrete that 1173 will remain in the final configuration of the Containments. All continuing Characterization Plans 1174 will be provided to the NRC for information and continuing Characterization Reports will be 1175 provided to the NRC for evaluation. 1176 From June of 2012 through January of 2013, a series of concrete core samples were taken in the 1177 568 foot concrete floor, 541 foot In-coreincore tunnel floor and In-coreincore tunnel walls in 1178 both Containment buildings. In addition, a single concrete core sample was taken from the 1179 reactor centerline location of Unit 1 Bio-Shield. A total of 39 concrete core samples were 1180 collected, 20 in Unit 1 Containment and 19 in Unit 2 Containment. 1181 The locations selected for the concrete core sampling were biased toward locations where 1182 physical or observed radiological measurements indicated the presence of fixed and/or 1183 volumetric contamination of the concrete media. When possible, locations were determined 1184 based upon elevated observed contact dose rates or count rates. In addition, visual observations 1185 of floor and wall surfaces were used to identify potential locations of surface contamination, 1186 such as discoloration or standing water. The goal was to identify, to the extent possible, the 1187 locations that exhibited the highest potential of representing the worst case bounding radiological 1188 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-30  condition for concrete in each survey unit. This judgmental sampling approach also ensured 1189 there was sufficient source term in the cores to achieve the sensitivities required to determine the 1190 radionuclide distributions of gamma emitters as well as HTD radionuclides. 1191 Sixteen (16) concrete core samples were taken on the 568 foot elevation of both the Unit 1 1192 Containment and the Unit 2 Containment, eight inside the missile shield and eight outside of the 1193 missile shield. Three (3) concrete core samples were obtained from each of the In-coreincore 1194 tunnel underUnder-vessel Vessel areas in both Unit 1 and Unit 2 Containments. Two (2) 1195 concrete core samples were taken from the 541 foot elevation floor and one was taken from the 1196 wall directly under each reactor vessel. A single concrete core sample was obtained from the 1197 Unit 1 Bio-Shield. Since the Bio-Shields in both Containments will not remain in the end-state 1198 configuration and the concrete is to be removed as waste, this was the only core sample taken of 1199 Bio-Shield. No Bio-Shield core was obtained in Unit 2. 1200 A summary of the on-site gamma spectroscopy results for the analysis of the concrete cores 1201 taken from the Unit 1 Containment 568 foot elevation is presented in Table 2-14. A summary of 1202 the on-site gamma spectroscopy results for the analysis of the concrete cores taken from the 1203 Unit 1 Bio-Shield is presented in Table 2-15. A summary of the on-site gamma spectroscopy 1204 results for the analysis of the concrete cores taken from the Unit 2 Containment 568 foot 1205 elevation is presented in Table 2-16. A summary of the on-site gamma spectroscopy results for 1206 the analysis of the concrete cores taken from the Containment In-coreincore tunnel areas are 1207 presented in Table 2-17 for Unit 1 Containment and Table 2-18 for Unit 2 Containment. The 1208 locations where the core samples were taken are illustrated in Figures 2-21 and 2-22 for Unit 1 1209 Containment and Figures 2-23 and 2-24 for Unit 2 Containment. 1210 ZionSolutions TSD 14-028, "Radiological Characterization Report" (Reference 2-2425) 1211 presents additional detail on the concrete sampling methodology and results of the radiological 1212 analysis of each concrete core sample obtained from the Containment Building basements. In 1213 addition, an in-depth analysis of the results of the concrete core samples taken in the 1214 Containment are presented in ZionSolutions TSD 13-006, "Reactor Building Units 1 & 2 End 1215 State Concrete and Liner Initial Characterization Source Terms and Distributions" 1216 (Reference 2-2526). 1217 With the exception of one (1) core sample where Eu-154 was positively identified, Co-60,        1218 Cs-137 and Cs-134 were the only plant-derived gamma emitting radionuclides identified by the 1219 analysis of the concrete core samples taken from the 568 foot elevation. The on-site gamma 1220 spectroscopy results identified Co-60, Cs-134, Cs-137, Eu-152 and Eu-154 in the concrete core 1221 samples taken from the In-coreincore tunnel areas. 1222 For both Unit 1 and Unit 2 568 foot elevations, the sample analysis indicated that the majority of 1223 the radionuclide source inventory resides within the first 1/2-inch of concrete and that Cs-137 is 1224 the dominant radionuclide. Co-60 is significantly more prevalent in Unit 2 verses Unit 1. In 1225 addition, the analysis also indicates that the overall source inventory in Unit 2 is much lower 1226 than Unit 1. 1227 An examination of the underUnder-vessel Vessel In-coreincore area profiles show diminishing 1228 activation at depth. In Unit 1, the source inventory is dominated by the presence of Cs-137 in the 1229 first 1/2-inch of concrete, which contains approximately 63% of the overall source inventory. In 1230 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-31  Unit 2, the    Cs-137 concentrations are significantly less and the source inventory is dominated 1231 by Eu-152, which accounts for approximately 74% of the calculated total source inventory. 1232 Analysis of the core taken from Unit 1 Bio-Shield indicates that Eu-152 and Eu-154, which are 1233 indicators of the neutron activation of concrete was not detected in concentrations greater than 1234 their respective MDC until a depth of 47.5 inches. This supports the postulation that neutrons 1235 were successfully attenuated prior to traversing the Bio-Shield and consequently, there is 1236 minimal potential for the activation of concrete in areas outside the Bio-Shield. 1237 The top 1/2-inch puck from nine (9) of the 20 cores from Unit 1 and the top 1/2-inch puck from 1238 eight (8) of the 19 cores from Unit 2 were sent to Eberline Laboratory for gamma spectroscopy 1239 and HTD analyses for radionuclides such as H-3, C-14, Tc-99, Ni-63, Sr-90, and alpha emitters. 1240 The results of the analysis are presented in Table 2-19 for Unit 1 Containment and Table 2-20 for 1241 Unit 2 Containment. The radionuclide distribution for Unit 1 and Unit 2 Containments that is 1242 based on this sample population is presented in Table 2-21. Significant HTD radionuclides 1243 identified by the analysis of the concrete core samples include Ni-63, H-3 and Sr-90. The other 1244 radionuclides positively detected at concentrations greater than their respective MDC include;  1245 C-14, Tc-99, Pu-238, Pu-239/240, Am-241, Am-243 and Cm-243/244. 1246 2.3.3.2. Auxiliary Building 1247 The Auxiliary Building is located between the Unit 1 and Unit 2 Containments and the Turbine 1248 Building. The structure is designed to house support systems for the operation of both reactors. 1249 Major support systems that are located in the Auxiliary Building include Containment Spray, 1250 Residual Heat Removal, Reactor Water Cleanup, Reactor Water Charging and Safety Injection 1251 systems. In addition, the Auxiliary Building contains various filters and tanks designed to batch 1252 and/or process gaseous, liquid and solid wastes resulting from reactor operation. With the 1253 exceptions of the service water, primary de-ionized water, control air, fire protection, nitrogen 1254 gas and service air, all of the systems within the Auxiliary Building are radiologically 1255 contaminated internally. The structure itself is designed to contain and control leakage from 1256 these systems during normal operation as well as unusual events. System leakage and 1257 maintenance activities over the operating life of the facility have resulted in the radiological 1258 contamination of most of the interior surfaces of the Auxiliary Building. Most of the cubicles 1259 that contain major systems are posted as contaminated areas identifying removable radioactive 1260 material. Based on the building design basis, the operating history, as well as the present status 1261 of areas that are controlled as contaminated, all internal survey units within the Auxiliary 1262 Building are considered to be Class 1 areas. 1263 General area radioactive dose rates within the Auxiliary Building range from 1 mrem/hr to 1264 60 mrem/hr with contact dose rates on specific components in excess of 1000 mrem/hr. Loose 1265 radioactive contamination ranges from <1,000 dpm/100 cm2 to over 250 mrad/swipe. The 1266 general radiological conditions within the Auxiliary Building are presented per survey unit in 1267 Table 2-13. 1268 The basic decommissioning end-state for the Auxiliary Building will consist of the foundation 1269 concrete walls below 588 foot elevation and the 542 foot elevation concrete floor. All systems 1270 and components contained within the Auxiliary Building will be disassembled and/or 1271 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-32  demolished, packaged and properly dispositioned as either a radioactive or non-radioactive 1272 waste. The list of penetrations and embedded piping to remain is provided in TSD 14-016. 1273 During the time that initial characterization was performed, all radioactive systems and 1274 components were still located inside the Auxiliary Building. Consequently, ambient radiation 1275 dose rates inside most of the cubicles on the 542 foot elevation prohibited the direct assessment 1276 of concrete surfaces by scanning or direct measurement. Once commodity removal is complete, 1277 a contamination verification survey (CVS) will be performed to identify areas requiring 1278 remediation to meet the open air demolition limits. Prior to demolition, all structural surfaces 1279 that will remain after demolition will be remediated to levels that will ensure that an individual 1280 ISOCS measurement will not exceed the DCGLs from Chapter 5, Table 5-3 during FSS. 1281 Following completion of a FSS in accordance with section 5.5.4 of this LTP, the basements will 1282 be backfilled with clean fill, CCDD, grout, or a combination of the three materials.additional 1283 characterization will be performed by scan and/or direct measurement to identify the lateral and 1284 vertical extent of surficial contamination of the concrete surfaces and the extent of any 1285 remediation of concrete that will be necessary. 1286 In May and June of 2012, a characterization survey was performed of the Auxiliary Building 542 1287 foot elevation and Auxiliary Building exterior walls. The characterization survey consisted of 1288 surface scans and the acquisition of a series of concrete core samples were taken in the 542 foot 1289 elevation concrete floor and exterior lower walls. In March of 2013, two (2) additional concrete 1290 cores were taken in the Auxiliary Building elevator shaft and the Hold-Up tank Cubicle floors as 1291 these areas became accessible. 1292 During the characterization of the Auxiliary Building basement, extensive beta gamma scan 1293 surveys were performed on the floors and lower walls of the 542 foot elevation in an effort to 1294 determine the locations representing the worst case radiological condition for concrete in each 1295 survey unit. These scans were performed of accessible walls surfaces to the extent practicable 1296 while standing on the 542 foot elevation, to a nominal elevation of approximately six feet up the 1297 wall from the floor. The scan surveys indicated that, for a majority of the lower wall surfaces on 1298 the Auxiliary Building 542 foot elevation, the residual radioactivity on the wall was 1299 indistinguishable from ambient background. This was particularly true for all the outer wall 1300 surfaces in the east portion of the Auxiliary Building 542 foot elevation, including the Waste Gas 1301 Decay Tank area, the Lake Discharge Tank area, the Blowdown Monitor Tank area and the areas 1302 adjacent to the Cavity Fill Pump cubicles. Residual contamination at concentrations greater than 1303 the ambient background was only detected on the outer walls of the Unit 1 and Unit 2 Pipe 1304 Chases, the Unit 1 and Unit 2 ABEDCT cubicles and the outer walls of the HUT cubicles. 1305 However, with the exception of the HUT cubicles, the contamination identified on the walls in 1306 the Pipe Chases and ABEDCT cubicles was not uniform. The contamination on the walls in 1307 these cubicles was primarily from valve leakage and gland seal spray from primary system 1308 pumps. 1309 A total of 20 concrete core samples were collected. The locations selected were biased toward 1310 locations where physical or observed radiological measurements indicated the presence of fixed 1311 and/or volumetric contamination of the concrete media. When possible, locations were 1312 determined based upon elevated observed contact dose rates or count rates from scans. In 1313 addition, visual observations of floor and wall surfaces were used to identify potential locations 1314 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-33  of surface contamination, such as discoloration or standing water. The goal was to identify to the 1315 extent possible, the locations that exhibited the highest potential of representing the worst case 1316 radiological condition for concrete in each survey unit. This judgmental sampling approach also 1317 ensured that there was sufficient source term in the cores to achieve the sensitivities required to 1318 determine the radionuclide distributions of gamma emitters as well as HTDhard to detect 1319 radionuclides. 1320 The locations where the core samples were taken are illustrated in Figure 2-25. The concrete 1321 pucks were analyzed on the on-site gamma spectroscopy system. A summary of the on-site 1322 gamma spectroscopy results for the analysis of the concrete cores taken from the 542 foot 1323 elevation of the Auxiliary Building is presented in Table 2-22. Co-60, Cs-134 and Cs-137 were 1324 the only plant-derived gamma emitting radionuclides identified. ZionSolutions TSD 14-028 1325 presents additional detail on the concrete sampling methodology and results of the radiological 1326 analysis of each concrete core sample obtained from the Auxiliary Building basement. 1327 Analyses of the concrete core samples taken from the Auxiliary Building 542 foot elevation 1328 indicate that there is extensive radiological contamination at depth. This is most likely due to the 1329 fact that the 542 foot elevation was routinely flooded with contaminated water during operations. 1330 In the first 1/2-inch of floor, Co-60 concentrations averaged 46 pCi/g with a maximum 1331 concentration of 456 pCi/g and Cs-137 concentrations averaged 3,352 pCi/g with a maximum 1332 concentration of 25,100 pCi/g. In both Unit 1 and Unit 2 Pipe Chase Tunnel rooms, Cs-137 1333 concentrations of 530 pCi/g and 1,740 pCi/g were observed at depths of 4 and 5 inches 1334 respectively. In addition, sample analysis indicated a Cs-137 concentration of 56.80 pCi/g at a 1335 depth of 2 inches in the central common area, a Cs-137 concentration of 31.10 pCi/g at a depth 1336 of 3.5 inches in the east floor area and a Cs-137 concentration of 63.10 pCi/g at a depth of 1337 2.5 inches in the Unit 1 Equipment Drain Collection Tank room. 1338 The top 1/2-inch puck from six (6) of the 20 cores from the Auxiliary Building were sent to 1339 Eberline Laboratory for gamma spectroscopy and HTD analyses for radionuclides such as H-3, 1340 C-14, Tc-99, Ni-63, Sr-90, and alpha emitters. The results of the analysis are presented in 1341 Table 2-23. The mixture percentages for the initial suite of radionuclides for the Auxiliary 1342 Basement concrete were developed in TSD 14-019, "Radionuclides of Concern for Soil and 1343 Basement Fill Model Source Terms" (Reference 2-27) using the results of all core sample 1344 analyses, including the cores sent to Eberline as well as those analyzed onsite, andThe 1345 radionuclide distribution for the Auxiliary Building that is based on this sample population is 1346 presented in Table 2-24. Significant HTD radionuclides identified by the analysis of the 1347 concrete core samples include Ni-63 and H-3. The other radionuclides positively detected at 1348 concentrations greater than their respective MDC include; C-14, Tc-99, Sr-90, Ag-108m, Pu-1349 238, Pu-239/240, Am-241 and Am-243. 1350 2.3.3.3. Fuel Handling Building 1351 The Fuel Handling Building is located between the Unit 1 and Unit 2 Containments and adjacent 1352 to the Auxiliary Building. The structure is designed for the storage of new and spent fuel. Major 1353 support systems that are located in the Fuel Handling Building include the SFP Heat Exchangers 1354 and SFP Skimmer Pumps. The SFP is a 63 ft. long by 33 ft. wide by 40 ft. deep pool located in 1355 the east half of the building. The pool is filled with borated water and contains storage racks for 1356 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-34  the storage of spent fuel assemblies. Spent nuclear fuel, highly irradiated reactor components 1357 and other highly radioactive debris are were stored in the pool. A new fuel storage area and a 1358 fuel unloading area are located in the western portion of the building. A cask decontamination 1359 pit is located adjacent to the pool. With the exceptions of the service water, de-ionized water, 1360 control air, fire protection, nitrogen gas and service air, all of the systems within the Fuel 1361 Handling Building are radiologically contaminated internally. The SFP, the decontamination pit, 1362 and the equipment cubicles are all posted as "Contaminated Areas."  The potential for residual 1363 contamination exists throughout the building. Based on the building design basis, the operating 1364 history, as well as the present status of areas that are controlled as contaminated, all internal 1365 survey units within the Fuel Handling Building are considered to be Class 1 areas. 1366 General area radioactive dose rates within the Fuel Handling Building range from 1 mrem/hr to 1367 25 mrem/hr. Loose radioactive contamination ranges from <1,000 dpm/100 cm2 to 1368 37,000 dpm/100 cm2. The general radiological conditions within the Fuel Handling Building are 1369 presented per survey unit in Table 2-13. 1370 The spent fuel located in the SFP will was be packaged into dry cask storage and transferred to 1371 the ISFSI facility. All systems, components and materials located in the Fuel Handling Building 1372 will be removed and dispositioned as radioactive or non-radioactive waste as appropriate. A 1373 majority of the Fuel Handling Building structure is located above the 588 foot elevation. 1374 Consequently, the basic decommissioning end-state for the Fuel Handling Building is the 1375 complete removal of the current accessible structure. The only portion of the building that 1376 resides below the 588 foot elevation is the bottom 12 feet of the SFP and adjoining Transfer 1377 Canal. As part of the building demolition, the steel liner will be removed from the SFP and 1378 Transfer Canal. Once the liner is removed and the underlying concrete is exposed, additional 1379 characterization surveys will be performed to assess the radiological condition of the underlying 1380 concrete pad and remaining pool walls. Following an assessment of the results of the survey, a 1381 cost benefit analysis will be performed to determine if the concrete will be remediated and 1382 abandoned in place or removed. Once commodity removal is complete, a contamination 1383 verification survey (CVS) will be performed on the concrete surfaces to identify areas requiring 1384 remediation to meet the open air demolition limits. Prior to demolition, all concrete surfaces that 1385 will remain will be remediated to levels that will ensure that an individual ISOCS measurement 1386 will not exceed the DCGLs from Chapter 5, Table 5-3 during FSS. Any remaining concrete 1387 surfaces will be remediated to levels commensurate with inventory  limits developed with the 1388 BFM that represent the dose criterion for unrestricted release specified in 10 CFR 20.1402. 1389 Following completion of a STS FSS in accordance with section 5.5.3 4 of this LTP, any 1390 remaining remnant of the SFP and Transfer Canal below the 588 foot elevation will be backfilled 1391 with clean fill, clean concrete debrisCCDD, grout, or a combination of the three materials. 1392 2.3.3.4. Turbine Building 1393 The Turbine Building houses the steam turbines and generators for both reactor units as well as 1394 secondary steam systems, circulating water systems, lubrication and fuel oil systems and 1395 emergency diesel generators. The steam and support systems in the Turbine Building are 1396 designed to be operated as non-radioactive systems. However, from 1981 through the facility 1397 shutdown in 1998, both Zion units experienced significant primary system to secondary side 1398 leakage from leaking Steam Generator tubes. From 1981 to 1984, primary to secondary side 1399 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-35  leakage was recorded at levels exceeding 500 gallons per day. Consequently, primary to 1400 secondary side leakage has resulted in measurable radioactivity in portions of the secondary 1401 system piping, primarily in the high-pressure steam components, the condensate re-heaters, the 1402 Auxiliary Boiler and the system, equipment and floor drain systems. In addition, several 1403 areas/components adjacent to the fire sump have detectable radioactive contamination. In the 1404 late 1970's (prior to fire sump modifications), the Turbine Building Equipment Drain Analysis 1405 Tank had exposure rates up to 200 mR/hr on contact. 1406 General area radioactive dose rates within the Turbine Building are <1 mrem/hr. Loose 1407 radioactive contamination ranges from <1,000 dpm/100 cm2 to 18,000 dpm/100 cm2 located in 1408 the Auxiliary Boiler room. The general radiological conditions within the Turbine Building are 1409 presented per survey unit in Table 2-13. 1410 The Turbine Building systems and structural surfaces above the 588 foot elevation will be 1411 surveyed and released for unrestricted access under the operational "free-release" program at 1412 Zionunconditional use. The concept is to allow a contractor to disassemble, salvage and 1413 demolish the Turbine Building as "non-radiological". To allow this process to occur, the "high-1414 risk" systems within the Turbine Building, such as Main Steam, Condensate, Auxiliary Steam, 1415 Feedwater and liquid waste systems will be removed and properly dispositioned as radioactive 1416 waste. The remaining systems, as well as the Turbine Building structure will be remediated as 1417 necessary and surveyed for unrestricted release using a graded survey approach in accordance 1418 with MARSAMEunconditional use. The drain system embedded in the concrete floor of the 1419 560 foot elevation, which is currently radiologically contaminated, will be surveyed in 1420 accordance with Chapter 5, section 5.5.6as a STS and then grouted in place. The results for the 1421 characterization of the Turbine Building floor drains is presented in section 2.3.3.7. 1422 Once the Turbine Building has been verified as meeting the unrestricted releaseunconditional 1423 release criteria in accordance with the operational material release program at ZNPS, then the 1424 building will be gutted and demolished to the 588 foot elevation. Prior to demolition, all 1425 concrete surfaces that will remain will be remediated to levels that will ensure that an individual 1426 ISOCS measurement will not exceed the DCGLs from Chapter 5, Table 5-3 during 1427 FSS.Remaining concrete surfaces will be remediated to levels commensurate with inventory 1428 limits developed with the BFM that represent the dose criterion for unrestricted release specified 1429 in 10 CFR 20.1402. Following completion of a STS FSS in accordance with section 5.5.3 4 of 1430 this LTP, the basement void below the 588 foot elevation will be backfilled with clean fill, clean 1431 concrete debrisCCDD, grout, or a combination of the three materials. 1432 In November of 2012, a series of concrete core samples were taken in the 560 foot elevation 1433 Turbine Building concrete floor as well as the 570 foot elevation Steam Tunnel concrete floors. 1434 The locations where the core samples were taken are illustrated in Figures 2-26. 1435 A total of 10 concrete core samples were collected, three (3) in the Turbine Building 560 foot 1436 elevation floor, five (5) in the Unit 1 Steam Tunnel floor and two (2) in the Unit 2 Steam Tunnel 1437 floor. The locations selected were biased toward locations where physical or observed 1438 radiological measurements indicated the presence of fixed and/or volumetric contamination of 1439 the concrete media. When possible, locations were determined based upon elevated observed 1440 contact dose rates or count rates. In addition, visual observations of floor and wall surfaces were 1441 used to identify potential locations of surface contamination, such as discoloration or standing 1442 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-36  water. The goal was to identify to the extent possible, the locations that exhibited the highest 1443 potential of representing the worst case radiological condition for concrete in each survey unit. 1444 A summary of the gamma spectroscopy results for the concrete cores obtained from the Turbine 1445 Building 560 foot elevation and the 570 foot elevation Steam Tunnels are provided in      1446 Table 2-25. ZionSolutions TSD 14-028 presents additional detail on the concrete sampling 1447 methodology and results of the radiological analysis of each concrete core sample obtained from 1448 the Turbine Building. Cs-137 was the only plant-derived gamma emitting radionuclides 1449 identified. Concentrations for Co-60 were less than the MDC for all samples from the Turbine 1450 Building and the Steam Tunnels. 1451 Analyses of the concrete core samples taken from the Turbine Building 560 foot elevation show 1452 the presence of Cs-137 at concentrations greater than the MDC of the instrument at two (2) of 1453 the three (3) sample locations, and only in the 1st 1/2-inch of concrete. Observed Cs-137 1454 concentrations ranged from 0.55 pCi/g to 46.7 pCi/g. At depths greater than 1/2-inch, 1455 concentrations for Cs-137 was less than MDC. In the Steam Tunnels, Cs-137 concentrations in 1456 the 1st 1/2-inch on concrete ranged from 6.60 pCi/g to 46.70 pCi/g in Unit 1 and 0.29 pCi/g to 1457 18.60 pCi/g in Unit 2. At depths greater than 1/2-inch, concentrations for Cs-137 was less than 1458 the MDC of the instrument used. 1459 Between March 21, 2013 and March 27, 2013, all accessible surfaces of the 560 foot elevation 1460 floor in the Turbine Building were scanned using a Ludlum Model 43-37 floor monitor. The 1461 average background of the instrument was 900 cpm. The alarm set-point was set at the observed 1462 background plus the Minimum Detectable Count Rate (MDCR) for the instrument. The mean 1463 observed count rate was 1,493 cpm with a maximum observed count rate of 3,922 cpm. 1464 Three (3) instrument alarms were observed, primarily around a posted radiological area adjacent 1465 to the elevator. 1466 2.3.3.5. Service Water Intake and Discharge Structure 1467 The Service Water intake and discharge structure is composed of several different components, 1468 including the Crib House, which houses the Circulating Water and Fire Pump motors and 1469 impeller housings, the Forebay, which acts as the intake pool for the pumps, the Circulating 1470 Water Intake Headers, which funnels the Circulating Water Pump discharge flow to the Main 1471 Condenser and the Circulating Water Discharge PipingTunnels, which directs the heated 1472 circulating water back to Lake Michigan. The Circulating Water Discharge Piping Tunnels is 1473 were also the main authorized effluent release pathway for the discharge of treated and filtered 1474 radioactive liquid waste to Lake Michigan. During plant operations and following shut-down, 1475 the liquid effluent release pathway was monitored and the results presented in the annual REMP 1476 report in accordance with the Off-site Dose Calculation Manual (ODCM). 1477 As previously described in section 2.3.1.2, a scan survey and a total of 40 concrete core samples 1478 were taken from the floors and lower walls of the Crib House 594 foot and 559 foot elevations. 1479 No activity greater than background was observed by either scan or the isotopic analysis of the 1480 concrete samples. The Crib House above the 588 foot elevation will be surveyed and released 1481 for unrestricted accessunconditional release under the operational "free-release" program at the 1482 same time as the Turbine Building. Once it has been demonstrated that the Crib House is 1483 suitable for unrestricted unconditional release under the Zion Station operational "free-release" 1484 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-37  program, a "non-radiological" demolition contractor will salvage materials out of the Crib 1485 House. The Crib House structural concrete and cinder block will be surveyed to demonstrate 1486 that the material is free of plant-derived radionuclides at concentrations greater than background, 1487 demolished and used as "clean-hard fillCCDD."  1488 At the time of LTP submittal, the Forebay is completely underwater. The Forebay walls will be 1489 demolished to elevation 588 foot. The circulating Circulating water Water suction Intake piping 1490 that runs from the Forebay to the Main Condenser will be isolated and drained. When 1491 accessible, the remaining lower portions of the Crib House and the Forebay structure below the 1492 588 foot elevation and the Circulating Water Intake piping circulating water suction piping will 1493 be remediated to levels that will ensure that an individual ISOCS measurement will not exceed 1494 the DCGLs from Chapter 5, Table 5-3 during FSS.commensurate with inventory  limits 1495 developed with the BFM that represent the dose criterion for unrestricted release specified in 1496 10 CFR 20.1402. Following completion of a STSFSS, the Forebaypiping will be filled with 1497 grout and the remaining void below the 588 foot elevation will be backfilled with clean fill, clean 1498 concrete debris, grout, or a combination of the three materials. The Circulating Water Intake 1499 piping will be filed with grout. 1500 The Circulating Water Discharge Piping Tunnels is a tunnel that runs under the Forebay and 1501 discharges to Lake Michigan approximately 870 feet from the lakeshore. The current 1502 decommissioning approach is to leave the Circulating Water Discharge Piping Tunnels in place. 1503 The interior surfaces of the Circulating Water Discharge Tunnels will be remediated to levels 1504 that will ensure that an individual ISOCS measurement will not exceed the Turbine Building 1505 DCGLs from Chapter 5, Table 5-3 during FSS. As it is difficult to isolate the majority of the 1506 tunnel from Lake Michigan, the tunnel may be characterized by collecting a series of sediment 1507 samples from the lake bottom at the tunnel discharge location and extrapolating the results to the 1508 activity inside the tunnel. Another option is to perform underwater surveys or sampling of the 1509 tunnel by diver or remote methods. The characterization (and STS) approach will be finalized 1510 after the elimination of the Circulating Water Discharge Piping as the normal effluent release 1511 pathway for ZSRP. 1512 2.3.3.6. Support Buildings and Miscellaneous Structures 1513 The major support buildings and miscellaneous structures include the Service Building, Gate 1514 House, Waste Water Treatment Facility, IRSF, ENC Building, NGET Building, Unit 1 and 1515 Unit 2 Valve Houses, and several warehouses. The location of these buildings and structures are 1516 illustrated on Figures 2-2 and 2-3. The general radiological conditions within these buildings are 1517 presented per survey unit in Table 2-13. 1518 As previously stated, the Asset Sale Agreement requires the demolition and removal of all on-1519 site buildings, structures, and components to a depth of at least 3 feet below grade. All support 1520 buildings and miscellaneous structures are categorized as structures located above the 588 foot 1521 elevation. Consequently, all support buildings and miscellaneous structures within the "security-1522 restricted" and "radiologically-restricted" areas at ZNPS will be demolished and dispositioned as 1523 a radioactive or non-radioactive waste stream. Several minor structures such as the Switchyard 1524 as well as all roadways and rail lines, will remain at license termination as requested by 1525 Exelon.Several structures such as the switchyard, the ISFSI warehouse, the microwave tower, 1526 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-38  and the Sewage Lift Station, as well as all roadways and rail lines, will remain at license 1527 termination as requested by Exelon. The switchyard was characterized as a Class 3 open land 1528 survey unit. The result of the switchyard characterization is presented in section 2.3.5. 1529 2.3.3.7. Embedded or Buried Pipe 1530 The End State will also include a range of buried piping, embedded piping and penetrations. 1531 Buried piping is defined as pipe that runs through soil. An embedded pipe is defined as a pipe 1532 that runs vertically through a concrete wall or horizontally through a concrete floor and is 1533 contained within a given building. A penetration is defined as a pipe (or remaining pipe sleeve, 1534 if the pipe is removed, or concrete, if the pipe and pipe sleeve is removed) that runs through a 1535 concrete wall and/or floor, between two buildings, and is open at the wall or floor surface of each 1536 building. A penetration could also be a pipe that runs through a concrete wall and/or floor and 1537 opens to a building on one end and the outside ground on the other end. The list of buried 1538 piping, penetrations and embedded piping to remain is provided in ZionSolutions TSD 14-016. 1539 Several sections of embedded and buried piping located below the 588 foot elevation have been 1540 designated to remain following demolition as part of the end-state condition for the structures in 1541 which they reside. At the time of LTP submittal, the interior surfaces of most of these sections 1542 of pipe were not accessible. As decommissioning progresses and access is achieved, radiological 1543 surveys will be performed to assess if any remediation is necessary, to confirm the radiological 1544 distribution inside of the pipe and to assess the dose from residual radioactivity remaining in the 1545 pipes. 1546 For pipe embedded in concreteembedded pipe and penetrations, the pipe interiors will be 1547 remediated to levels commensurate with inventory limits developed with the BFM that represent 1548 the dose criterion for unrestricted release specified in 10 CFR 20.less than the embedded pipe 1549 and penetration specific DCGLs discussed in sections 5.2.4 and 5.2.5 of this LTP1402. In most 1550 cases, these sections of pipe will consist of mostly penetrations through the remaining concrete 1551 walls of the structure. A list of penetrations that is anticipated to remain as part of the end-state 1552 condition of Unit 1 and Unit 2 Containment is presented in Table 2-26. As decommissioning 1553 progresses and access is achieved to the interior of these pipe sections, STS FSS will be 1554 performed in accordance with section 5.5.5 6 of this LTP. 1555 For pipe buried in soil, the pipe interiors will be remediated to levels less than the site-specific 1556 DCGLs presented in section 5.2.3Table 5-6 of this LTP. FSS surveys will be performed as 1557 described in section 5.57.1.8. A list of the sections of buried piping that will be abandoned in 1558 place and surveyed during FSS is presented in Table 2-27. 1559 In April of 2013, several sediment samples were collected from the floor drain system embedded 1560 in the Turbine Building 560 foot elevation. Three (3) sediment samples were collected from the 1561 floor drains in the south portion, six (6) sediment samples were collected from the floor drains in 1562 the central portion, and seven (7) sediment samples were collected from the floor drains in the 1563 north portion of the Turbine Building 560 foot elevation. In addition, two (2) large area wipes 1564 were collected and analyzed from the drain pipe interiors of floor drains in the central and north 1565 sections. The locations where the sediment samples were taken are illustrated in Figure 2-27. 1566 All sediment and wipe samples were weighed and analyzed using the on-site gamma 1567 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-39  spectroscopy system. The gamma spectroscopy results for the sediment samples from the 1568 Turbine Building 560 foot elevation drain system piping are provided in Table 2-2826. 1569 Analysis of the sediment samples indicates the presence of Cs-137 in concentrations greater than 1570 the instrument MDC in 12 of the 16 sediment samples, ranging from 0.11 pCi/g to 17.7 pCi/g. 1571 Co-60 was present in three (3) of the 16 samples, ranging from 0.28 pCi/g to 0.44 pCi/g. The 1572 large area wipe taken in drain pipes in the central portion of the 560 foot elevation indicated Cs-1573 137 at a concentration of 77.9 pCi/g. The analysis of the large area wipe taken in the north 1574 section did not show Cs-137 or Co-60 at concentrations greater than the instrument MDC. 1575 2.3.4. Non-Impacted Open Land Areas 1576 Based upon the information compiled in the Zion HSA, several large outlying open land survey 1577 units received an initial classification as "non-impacted."  Non-impacted areas have no 1578 reasonable potential for residual contamination because historical information indicates there 1579 was no known impact from site operations. These include the outlying open land areas of the 1580 site as well as contiguous areas that have no impact from site operations based upon the 1581 location(s) of licensed operations, site use, topography, site discharge locations, and other site 1582 physical characteristics. These areas are not required to be surveyed for demonstrating 1583 compliance beyond any characterization surveys performed to provide a basis for the 1584 classification. 1585 For ZNPS, the non-impacted open land areas includes most of the surrounding Exelon owned 1586 land outside of the footprint of the 87 acre, fence-enclosed "Radiologically-Restricted Area" as 1587 well as tracts of land that are owned by the Town of Zion and adjacent businesses. With the 1588 exception of operational surveys performed at the perimeter of the RCA to establish compliance 1589 with non-occupational exposure limits, no radiological survey data was available to support this 1590 basis. 1591 From June to September 2013, characterization surveys were performed in the non-impacted 1592 open land areas of the site. To facilitate data collection, review and evaluation, the non-impacted 1593 open land areas were surveyed as designated survey units. A sample plan was prepared for each 1594 survey unit in accordance with procedure ZS-LT-100-001-001, "Characterization Survey 1595 Package Development" (Reference 2-2628). The objective of the survey was to perform a 1596 sufficient radiological characterization to establish the empirical basis for the "non-impacted" 1597 classification and to establish a reasonable assurance that the survey units in question were free 1598 of detectable radioactive material resulting from the operation of the reactors. 1599 Within each of the survey units specified, the survey focused primarily on surface (0 to 15 cm) 1600 soils. Subsurface (15 to 100 cm) soil samples were included in the survey design only if the 1601 analysis of surface soil samples indicated the presence of detectable plant-derived radioactivity. 1602 The sample and static measurement locations were based on a random design to ensure an 1603 unbiased survey. 1604 The characterization survey of each survey unit consisted of both qualitative evaluations and 1605 quantitative analysis results. The qualitative evaluation consisted of static measurements using 1606 the Canberra In Situ Object Counting System (ISOCS). Investigative and verification gamma 1607 scans using a Ludlum Model 2350-1 and a Model 44-10 NaI detector were also performed. 1608 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-40  MDC and gamma scanning sensitivities were estimated based on the assumed geometry and the 1609 potential plant-derived gamma-emitting radionuclides that may be present. Quantitative analysis 1610 results were obtained from radionuclide specific analysis of surface soil media using a calibrated 1611 counting geometry. Analysis times were set to achieve the required MDCs that were based on 1612 the expected Cs-137 background due to global fallout as set forth in TSD 13-004 and reproduced 1613 in Table 2-11. The results of the ISOCS and soil sample measurements were compared to the 1614 appropriate background value commensurate with the soil type. Any measurements exceeding 1615 these values would be indicative of the presence of plant-derived radioactivity. 1616 The minimum number of random-based direct measurements was adjusted to approximate 1617 one (1) measurement location for every 2,000 m2 of land area. This survey frequency was in 1618 accordance with the Characterization Survey Plan and procedure ZS-LT-100-001-001. Surface 1619 scanning using a NaI detector was performed in the vicinity of each static measurement location 1620 and for investigations of elevated results. Surface soil samples were taken at 25% of the 1621 measurement locations. 1622 Specific ISOCS measurement locations were determined by generating random pairs of 1623 coordinates that corresponded to specific locations within each survey unit. If a randomly 1624 selected location was found to be either inaccessible or unsuitable (e.g. a portion of the surface 1625 area in the instruments "Field-of-View" (FOV) was covered in standing water), then the location 1626 was adjusted to the closest adjacent suitable location. 1627 The ISOCS detector was oriented downward and perpendicular to the ground. The exposed face 1628 of the detector was positioned at a height of 3 meters above the ground. With the 90-degree 1629 collimation shield installed, this orientation corresponded to a nominal FOV of 28 m2. The 1630 ISOCS geometry evaluated soil activity to a depth of 15 cm (6 inches below grade) over the 1631 geometric FOV. Measurement count times were adjusted to achieve a MDC of 0.40 pCi/g for 1632 Cs-137. 1633 The investigation action level was set at any detectable activity greater than the actual 1634 measurement MDC for any potential plant-derived gamma emitting radionuclide or the Cs-137 1635 background values. If any measurement would have identified a plant-derived gamma emitting 1636 radionuclide that was not found in background or, if the observed activity exceeded the expected 1637 background activity concentration, then an investigation would have been performed. 1638 2.3.4.1. Surface Soils 1639 The owner-controlled non-impacted open land areas at Zion totaled 874,041 square meters of 1640 surface area. The non-impacted surface area was broken into 11 survey units in accordance with 1641 the area descriptions, sizes and boundaries presented in the HSA. The non-impacted survey units 1642 are illustrated by Figure 2-4. Of the 874,041 square meters, 182,127 square meters was deemed 1643 as "inaccessible". In this context, "inaccessible" is defined as an area where personnel or vehicle 1644 transit was inhibited by the presence of standing water, marsh or wet-lands, thick underbrush, 1645 trees or natural grasses where clearing would be prohibitive. The total surface area deemed 1646 "accessible" was 691,913 square meters. 1647 Of the 691,913 square meters of surface area, 9,378 square meters were scanned by a 1648 Model 2350 paired with a Model 44-10 NaI detector. Alarm set-points for the instrument were 1649 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-41  set at the observed background plus the MDCR of the instrument. With an average background 1650 of 4,337 cpm, the average observed scan result was 4,677 cpm. Twenty-four (24) instrument 1651 alarms were logged with a maximum observed scan reading of 9,550 cpm. All alarms were 1652 investigated and soil samples were taken at locations where the elevated reading was verified. 1653 Two hundred and thirty-six (236) static measurements were taken with the ISOCS. This equated 1654 to a coverage area of 6,608 square meters using a 28 square meter FOV. Of the total 1655 measurements taken, 75 measurement results indicated the presence of Cs-137 in concentrations 1656 greater that the MDC of the instrument. No other potential plant-derived radionuclides were 1657 positively identified. Cs-137 concentrations identified by ISOCS measurements averaged 1658 0.17 pCi/g with a maximum observed Cs-137 concentration of 0.34 pCi/g. 1659 One hundred and sixty-six (166) surface soil sample were taken to verify ISOCS results or as 1660 investigations. Of the total number of surface soil samples taken and analyzed, Cs-137 was 1661 identified at concentrations greater than the MDC of the instrument in 106 surface soil samples. 1662 No other potential plant-derived radionuclides were positively identified. The average Cs-137 1663 concentration observed in the analysis of the surface soil samples was 0.24 pCi/g with a 1664 maximum observed concentration of 0.57 pCi/g. 1665 Additional detail on the survey and sampling methodology and results of the radiological 1666 analysis of each measurement and soil sample obtained during the characterization of non-1667 impacted open land survey units are presented in ZionSolutions TSD 14-028. The scope and 1668 extent of the surveys performed in the non-impacted classified open land areas were sufficient to 1669 demonstrate that the non-impacted classification was appropriate for the open land areas in 1670 question and that it is highly unlikely, based upon the findings and conclusions of the HSA, 1671 combined with the results of the characterization, that plant-derived radioactivity resides in these 1672 areas. Based upon the results of the characterization surveys performed of the non-impacted 1673 open land areas, it can be concluded that a non-impacted classification for these areas are 1674 appropriate. Cs-137 was the only radionuclide positively identified that could potentially be 1675 classified as plant-derived. However, the concentrations observed are well within the range of 1676 activity defined as background due to global fallout illustrated in Table 2-11. The locations of 1677 ISOCS measurements and surface soil samples are illustrated on Figure 2-28. A summary of the 1678 findings of the survey for each individual survey unit are presented in Table 2-2927. 1679 2.3.4.2. Subsurface Soils 1680 The survey design for the characterization of the non-impacted open land survey units required 1681 the acquisition of subsurface soil samples only if an investigation was required prompted by the 1682 discovery of plant-derived radionuclides in concentrations greater than background in a surface 1683 soil sample or an ISOCS measurement. In addition, a subsurface soil sample would be taken if 1684 physical indications would suggest the potential presence of a burial area. Based upon the results 1685 of the characterization survey, no investigation was prompted by the discovery of plant-derived 1686 radionuclides in concentrations greater than background. In addition, no suspected burial areas 1687 were identified during the walkdowns of the survey units. Consequently, no subsurface soil 1688 samples were acquired in the non-impacted survey units. 1689 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-42  2.3.5. Impacted Open Land Areas 1690 The Zion HSA identified the open land area inside the single fenced "Radiologically-Restricted 1691 Area" as "impacted" by reactor operations. The approximate area of the footprint is 87 acres. In 1692 addition, a majority of the open land area inside the double-fenced "Security-Restricted Area" 1693 was primarily classified as Class 1. 1694 Characterization of the impacted open land areas began in November 2011 with the 1695 characterization of the Class 3 open land survey units encompassing the proposed site for the 1696 future ISFSI facility, the "non-impacted" location where the Vertical Concrete Cask 1697 Construction Area was to be located and the pathway for the new rail tracks. The remaining 1698 balance of the "impacted" open land areas were surveyed between November 2012 and 1699 October 2013. 1700 Initial survey units were established by the HSA. A sample plan was prepared for each survey 1701 unit in accordance with procedure ZS-LT-100-001-001. Survey techniques were employed to 1702 determine the lateral and vertical extent of any contamination identified and the radionuclide 1703 concentrations in the soil. 1704 A reference grid was established in each impacted survey unit. The reference grid consisted of a 1705 grid coordinate system that can be accessed using a Global Positioning System (GPS) system. 1706 Survey units were scanned in accordance with their initial classification or the anticipated 1707 classification based on historical knowledge. Recommended scan coverage guidelines for 1708 characterization for each class of survey unit is presented in Table 2-5. 1709 A combination of random and judgmental survey locations were established in each survey unit 1710 in accordance with the survey unit classification. The size of the judgmental sample population 1711 was determined using the recommended judgmental sample population sizes stated in procedure 1712 ZS-LT-100-001-001 and presented in Table 2-3028. The locations of judgmental measurements 1713 and/or samples were determined by the professional judgment of the responsible Radiological 1714 Engineer. Consideration was given to locations that exhibit measurable radioactivity, 1715 depressions, discolored areas, low point gravity drain areas, actual and potential spill locations, 1716 or areas where the ground had been disturbed. The number of random-based survey locations 1717 was also determined by area classification. Random-based measurements were not required in 1718 an open land areas designated as Class 1. In a Class 2 survey unit, a minimum of 15 random-1719 based locations were recommended. In Class 3 open land survey units, the minimum number of 1720 random-based survey locations were adjusted to approximate one (1) measurement location for 1721 every 2,000 m2 of land area. 1722 A surface soil sample was taken at each selected judgmental and random-based survey location. 1723 Sub-surface soil samples were acquired at a minimum of 10% of the surface soil sample 1724 locations identified. Additional subsurface soil samples were acquired if surface soil sample 1725 analysis or surface scans indicated elevated activity. Depending on the location, subsurface soil 1726 samples were taken from 0.15 cm to depths ranging from 1 to 3 m below grade and composited 1727 over 1 m intervals. 1728 Each surface soil and composite subsurface soil sample was analyzed by the on-site radiological 1729 laboratory by gamma-spectroscopy for plant-derived gamma emitting radionuclides. Analysis 1730 count times were adjusted as necessary to achieve an isotopic MDC equal to or less than 1731 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-43  0.18 pCi/gm for Cs-137 and Co-60. In a majority of the survey units, the surface and subsurface 1732 composite samples were initially analyzed without drying the sample media. If the initial on-site 1733 gamma spectroscopy analysis indicated that no plant-derived radionuclides were detected at a 1734 concentration greater than their respective MDC, then the sample was dried and reanalyzed, 1735 again using the on-site gamma spectroscopy system. If the initial on-site gamma spectroscopy 1736 analysis indicated the presence of plant-derived radionuclides greater than their respective MDC, 1737 then a portion of the sample was segregated into a separate container for further analysis and the 1738 remainder of the sample was dried and reanalyzed, again using the on-site gamma spectroscopy 1739 system. Several soil samples that exhibited concentrations of plant-derived gamma emitting 1740 radionuclides greater than MDC were shipped to an approved off-site vendor for full isotopic 1741 analysis (HTD radionuclides). 1742 2.3.5.1. Surface Soils and Paved Areas 1743 The "Radiologically-Restricted Area" is illustrated in Figure 2-2. In this area, there are 22 1744 Class 3 open land survey units. The survey unit boundaries are illustrated on Figure 2-6. 1745 Seven (7) Class 3 open land survey units reside outside of the "Radiologically-Restricted Area". 1746 These areas include the "West Training Area" along Shiloh Boulevard, the beach outside of the 1747 fenced area along the lakefront (broken into three (3) Class 3 survey units), survey unit 10220C 1748 along the south boundary and two (2) areas initially classified as non-impacted in the HSA but 1749 reclassified as Class 3 due to current and expected decommissioning activities. These areas 1750 include the VCC area and the site parking lot. The Class 3 survey units situated outside of the 1751 "Radiologically-Restricted Area" are illustrated in Figure 2-5. 1752 The Class 3 open land survey units at Zion have a total surface area of 401,042 square meters. 1753 49,116 square meters of the total Class 3 area was deemed as "inaccessible" due to obstacles. 1754 The total surface area deemed "accessible" was 351,926 square meters. Of this area, 1755 104,350 square meters or approximately 30% of the surface area were scanned using a 1756 Model 2350 paired with a Model 44-10 NaI detector. This area included asphalt paved surfaces. 1757 Alarm set-points for the instrument were set at the observed background plus the MDCR of the 1758 instrument. With an average background of 3,713 cpm, the average observed scan result was 1759 3,753 cpm. Three hundred-seventeen (317) instrument alarms were logged with a maximum 1760 observed scan reading of 12,193 cpm. All alarms were investigated and soil samples were taken 1761 at locations where an elevated reading was verified. 1762 In the "West Training Area", forty-six (46) static measurements were taken with the ISOCS. 1763 This equated to a coverage area of 1,288 square meters using a 28 square meter FOV. Of the 1764 total measurements taken, seven (7) measurement results indicated the presence of Cs-137 in 1765 concentrations greater that the MDC of the instrument. No other potential plant-derived 1766 radionuclides were positively identified. Cs-137 concentrations identified by ISOCS 1767 measurements averaged 0.18 pCi/g with a maximum observed Cs-137 concentration of 1768 0.25 pCi/g. 1769 Seven hundred-eighteen (718) surface soil sample were taken at judgmental, random-based and 1770 investigation locations. The locations of random and judgmental surface soil samples taken in 1771 Class 3 open land survey units located outside of the "Radiologically-Restricted Area" are 1772 illustrated on Figure 2-29. The locations of random and judgmental surface soil samples taken in 1773 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-44  Class 3 open land survey units located inside of the "Radiologically-Restricted Area" are 1774 illustrated on Figure 2-30. Of the total number of surface soil samples taken and analyzed,      1775 Cs-137 was identified at concentrations greater than the MDC of the instrument in 142 surface 1776 soil samples and Co-60 was identified at concentrations greater than the MDC of the instrument 1777 in one (1) sample. No other potential plant-derived radionuclides were positively identified. The 1778 average Cs-137 concentration observed in the analysis of the surface soil samples was 0.12 pCi/g 1779 with a maximum observed concentration of 1.14 pCi/g. The one sample where Co-60 was 1780 positively identified had a Co-60 concentration of 0.13 pCi/g. 1781 Additional detail on the survey and sampling methodology and results of the radiological 1782 analysis of each measurement and soil sample obtained during the characterization of Class 3 1783 open land survey units are presented in ZionSolutions TSD 14-028. Based upon the results of 1784 the characterization surveys performed of the Class 3 open land areas, strong evidence is 1785 provided to conclude that minimal residual plant-derived radioactivity is present in these areas. 1786 A summary of the findings of the survey for each individual Class 3 open land survey unit are 1787 presented in Table 2-3129. 1788 The "Security-Restricted Area" is illustrated in Figure 2-3. In this area, there are 13 Class 1 1789 open land survey units and five (5) Class 2 open land survey units. The survey unit boundaries 1790 are illustrated on Figures 2-7. The area of each survey units complies with the recommended 1791 survey unit sizes for open land survey units specified in MARSSIM, section 4.6. Additional 1792 detail on the survey and sampling methodology and results of the radiological analysis of each 1793 measurement and soil sample obtained during the characterization of Class 2 and Class 1 open 1794 land survey units are presented in ZionSolutions TSD 14-028. 1795 The Class 2 open land survey units at Zion total 39,747 square meters of surface area. 1796 9,085 square meters of the total Class 2 area was deemed as "inaccessible", mostly due to the 1797 presence of buildings (Turbine Building, Crib House, Service Building and Gate House). The 1798 total surface area deemed "accessible" was 30,622 square meters. Of this area, 22,559 square 1799 meters or approximately 74% of the surface area were scanned by a Model 2350 paired with a 1800 Model 44-10 NaI detector. This area included asphalt paved surfaces. Alarm set-points for the 1801 instrument were set at the observed background plus the MDCR of the instrument. With an 1802 average background of 3,005 cpm, the average observed scan result was 3,012 cpm. One-1803 hundred-eighteen (118) instrument alarms were logged with a maximum observed scan reading 1804 of 11,264 cpm. All alarms were investigated and soil samples were taken at locations where 1805 elevated readings were verified. 1806 Fifty-nine (59) surface soil samples were taken at judgmental, random-based and investigation 1807 locations in Class 2 open land survey units. The locations of random and judgmental surface soil 1808 samples are illustrated on Figure 2-31. Of the total number of surface soil samples taken and 1809 analyzed, Cs-137 was identified at concentrations greater than the MDC of the instrument in 1810 12 surface soil samples. No other potential plant-derived radionuclides were positively 1811 identified. The average Cs-137 concentration observed in the analysis of the surface soil 1812 samples was 0.14 pCi/g with a maximum observed concentration of 0.21 pCi/g. A summary of 1813 the findings of the survey for each individual Class 2 open land survey unit are presented in 1814 Table 2-3230. 1815 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-45  There are thirteen (13) open land survey units classified as Class 1 at Zion totaling 24,759 square 1816 meters of surface area. Of the 13 Class 1 open land survey units, the surface soils in four (4) 1817 survey units, totaling 7,740 square meters of surface area were deemed as "inaccessible". A 1818 majority of the inaccessible surface area is obstructed by the presence of buildings, namely the 1819 two Containment Buildings, the Fuel Handling Building and the Auxiliary Building. However, 1820 due to the fact that all the asphalt and concrete ground coverings inside of the "Security-1821 Restricted Area" will be disposed of as waste, surface soil was also deemed inaccessible if the 1822 area was paved. In addition, stored radioactive material in the vicinity of some areas prevented 1823 the ability to perform surface scanning due to high background. These surfaces were deemed as 1824 "inaccessible" as well. 1825 The Class 1 surface area deemed "accessible" was 17,019 square meters. Of this area, 1826 9,444 square meters or approximately 55% of the surface area was scanned by a Model 2350-1 1827 paired with a Model 44-10 NaI detector. Alarm set-points for the instrument were set at the 1828 observed background plus the MDCR of the instrument. With an average background of 1829 2,690 cpm, the average observed scan result was 3,361 cpm. Five-hundred forty-six (546) 1830 instrument alarms were logged with a maximum observed scan reading of 35,962 cpm. All 1831 alarms were investigated and soil samples were taken at locations where an elevated reading was 1832 verified. 1833 Ninety-four (94) surface soil samples were taken at locations biased toward observed elevated 1834 scan measurements and known spill locations. The locations of surface soil samples taken in 1835 Class 1 open land survey units are illustrated in Figure 2-32. Of the 111 surface soil samples 1836 taken, Co-60 was positively identified in concentrations greater than the instrument MDC in 14 1837 samples and Cs-137 was positively identified in concentrations greater than the instrument MDC 1838 in 58 samples. No other potential plant-derived gamma-emitting radionuclides were positively 1839 identified. The average Co-60 concentration observed in the analysis of the surface soil samples 1840 was 0.13 pCi/g with a maximum observed concentration of 1.04 pCi/g. The average Cs-137 1841 concentration observed in the analysis of the surface soil samples was 0.12 pCi/g with a 1842 maximum observed concentration of 3.39 pCi/g. A summary of the findings of the survey for 1843 each individual Class 1 open land survey unit are presented in Table 2-3331. 1844 Nine (9) surface soil samples taken from Class 1 open land survey units were sent to Eberline 1845 Laboratory for gamma spectroscopy and HTD analyses for radionuclides such as H-3, C-14,  1846 Tc-99, Ni-63, Sr-90, and alpha emitters. The results of the analysis are presented in Table 2-1847 3432. Co-60 and Cs-137 were the only potential plant-derived radionuclide identified in a 1848 concentration greater than the analysis MDC. No other plant-derived radionuclides were 1849 positively identified by these analyses. 1850 2.3.5.2. Subsurface Soils 1851 The HSA was consulted to identify those survey areas where the potential existed for subsurface 1852 radioactivity. Such areas include, but are not limited to, areas under buildings, building 1853 floors/foundations, or outside components where leakage was known or suspected to have 1854 occurred in the past and on-site storage areas where radioactive materials have been identified. 1855 Soil data from both the HSA and any pertinent surface characterization data were used to 1856 establish locations and potential depth for any potential sub-surface radioactivity. 1857 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-46  A total of 723 composited subsurface soil samples were collected and analyzed during the site 1858 characterization. Inside the "Security-Restricted Area", subsurface soil samples were typically 1859 taken to a depth of approximately 3 m below grade. In the Class 3 survey units, subsurface soil 1860 samples were typically taken to a depth of approximately 1 m below grade. 1861 Two-hundred eighty-three (283) subsurface soil samples were taken in Class 1 open land survey 1862 units. Cs-137 was positively identified in concentrations greater than the instrument MDC in 1863 14 samples and Co-60 was positively identified in concentrations greater than the instrument 1864 MDC in one (1) sample. No other potential plant-derived gamma-emitting radionuclides were 1865 positively identified. The average Cs-137 concentration observed in the analysis of the surface 1866 soil samples was 0.18 pCi/g with a maximum observed concentration of 0.70 pCi/g. The one 1867 sample where Co-60 was positively identified had a Co-60 concentration of 0.10 pCi/g. A 1868 summary of the results of the subsurface soil sample analysis by Class 1 open land survey unit 1869 are presented in Table 2-3331. 1870 One (1) subsurface soil sample taken from a Class 1 open land survey unit was sent to Eberline 1871 Laboratory for gamma spectroscopy and HTD analyses for radionuclides such as H-3, C-14,  1872 Tc-99, Ni-63, Sr-90, and alpha emitters. The results of the analysis are presented in Table 2-1873 3432. Cs-137 was the only potential plant-derived radionuclide identified in a concentration 1874 greater than the analysis MDC. No other plant-derived radionuclides were positively identified 1875 by these analyses. 1876 Sixty (60) subsurface soil samples were taken in Class 2 open land survey units. Cs-137 was 1877 positively identified in concentrations greater than the instrument MDC in three (3) samples. No 1878 other potential plant-derived gamma-emitting radionuclides were positively identified. The 1879 average Cs-137 concentration observed in the analysis of the surface soil samples was 0.11 pCi/g 1880 with a maximum observed concentration of 0.15 pCi/g. A summary of the results of the 1881 subsurface soil sample analysis by Class 2 open land survey unit are presented in Table 2-3432. 1882 Three-hundred eighty (380) subsurface soil samples were taken in Class 3 open land survey 1883 units. Cs-137 was positively identified in concentrations greater than the instrument MDC in 1884 32 samples. No other potential plant-derived gamma-emitting radionuclides were positively 1885 identified. The average Cs-137 concentration observed in the analysis of the surface soil 1886 samples was 0.09 pCi/g with a maximum observed concentration of 0.15 pCi/g. A summary of 1887 the results of the subsurface soil sample analysis by Class 2 open land survey unit are presented 1888 in Table 2-3230. 1889 In October of 2013, a single soil sample was acquired from the soil under the Turbine Building 1890 560 foot floor slab. The basis for the selection of the location assumed groundwater flow from 1891 west toward Lake Michigan to the east. The Turbine Building is located between Lake Michigan 1892 and four potential sources of radiological contamination (the two Containment Buildings, the 1893 Auxiliary Building and the Fuel Handling Building). Other considerations for the selection of 1894 the sample location included the accessibility for the GeoProbe equipment and the thickness of 1895 the concrete floor slab that must be drilled through in order to access the underlying soils. 1896 A hole was drilled through the concrete floor slab, exposing the underlying soil. The soil 1897 consistency found was hard-packed clay. A single sample of the soil was acquired, representing 1898 a depth of approximately 38 feet below grade. The sample was analyzed on the on-site gamma 1899 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-47  spectroscopy system. No plant-derived radionuclides at concentrations greater than the 1900 instrument MDC were detected. 1901 The assessment of potential subsurface soil contamination is not currently complete. Soil in 1902 difficult to access areas such as under building foundations and surrounding buried structures 1903 will be deferred until later in the decommissioning process, when access will be more readily 1904 available. 1905 2.3.6. Surface and Groundwater 1906 Section 8.5 in Chapter 8 of this LTP contains a summary description of the geology, 1907 hydrogeology and hydrology of ZNPS and environs. The information contained in this section 1908 was derived directly from ZionSolutions TSD 14-003, Conestoga Rovers & Associates (CRA) 1909 Report, "Zion Hydrogeologic Investigation Report" (Reference 2-2729) and presents a summary 1910 of studies that have been performed to investigate radiological groundwater contamination 1911 resulting from the operation of ZNPS. TSD 14-003, documents the results of hydrogeologic 1912 investigations completed by Conestoga-Rovers & Associates (CRA), Exelon, and ZionSolutions 1913 from August 2006 through September 2013. 1914 2.3.6.1. Area Groundwater Use 1915 ZNPS is connected to the Zion municipal water supply and does not use groundwater in its 1916 operations. The City of Zion provides municipal water to City residents and the surrounding 1917 area. The City purchases water from the Lake County Public Water District (LCPWD). The 1918 LCPWD obtains its water from Lake Michigan by means of an intake pipe located approximately 1919 1 mile north of the Site and extending 3,000 feet into the Lake. The City of Zion municipal code 1920 requires all improved properties to be connected to the City's water supply. The code states that 1921 it is "unlawful for any person to construct, permit or maintain a private well or water supply 1922 system within the City which uses groundwater as a potable water supply". There is an 1923 exception for some existing wells constructed prior to March 2, 2004. However, it is unlikely 1924 that any private well or water supply system exists within the City which uses groundwater as a 1925 potable water supply. 1926 2.3.6.2. Groundwater Flow 1927 The shallow groundwater in the upper sand unit flows to the east toward Lake Michigan. The 1928 sheet pile wall installed along the lakeshore and the building foundations restrict the groundwater 1929 flow in the upper sand unit, which causes the groundwater to flow around ZNPS. The shallow 1930 water table intercepts the stormwater drainage ditches in the west area of the ZNPS property, but 1931 does appear to affect the flow of groundwater to the east and toward Lake Michigan. If the 1932 buildings and sheet pile wall are left intact (not perforated for flow) during the decommissioning, 1933 then a localized stagnation of groundwater around these barriers will occur since groundwater is 1934 prevented from flowing through these structures toward the Lake. 1935 2.3.6.3. Previous Investigations 1936 In 2006, CRA prepared a report titled "Hydrogeologic Investigation Report, Fleetwide 1937 Assessment, Zion Station", Revision 1 (Reference 2-2830) to determine whether groundwater at 1938 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-48  and in the vicinity of ZNPS has been adversely impacted by any releases of radionuclides. With 1939 the exception of H-3 and total strontium, no radionuclides were detected above the MDC during 1940 the 2006 investigation. 1941 In 2011, the Wisconsin Department of Health Services (WDHS) conducted environmental 1942 radiation monitoring around the ZNPS site. This investigation was documented in a report titled, 1943 ""Zion Environmental Radioactivity Survey-2001" (Reference 2-2931). In this report, the 1944 WDHS concluded: 1945  Air particulate analysis shows no evidence of influence by ZNPS on air quality. 1946  The average yearly exposure of ambient gamma radiation is at background levels and is 1947 comparable to other areas within Wisconsin. 1948  The surface water samples showed no unusual concentrations of gross beta, gross gamma, 1949 tritium, and strontium. 1950  The gamma isotopic analysis for surface water indicated radioisotopes below their respective 1951 minimum detectable concentration. 1952  The gamma isotopic analysis on vegetation detected only a small amount of the naturally 1953 occurring elements K-40 and Be-7. 1954  The gamma isotopic analysis for soil detected naturally occurring K-40 and Cs-137, which is 1955 attributable to fallout from previous atmospheric nuclear tests (these were also detected in 1956 previous years). 1957  Doses of radiation as a result of gaseous and liquid effluent are less than the limits allowed 1958 for an average individual as stated in Federal Regulations. 1959 2.3.6.4. On-Going Investigations 1960 Ongoing monitoring of surface water and groundwater at ZNPS include REMP, Radiological 1961 Groundwater Protection Program (RGPP) and NPDES Monitoring. 1962 2.3.6.4.1. Radiological Environmental Monitoring Program (REMP) 1963 The REMP at ZNPS was initiated in 1973. The REMP includes the collection of various media 1964 samples including air, surface water, groundwater, fish, sediment, vegetation, clams, and crabs. 1965 The samples are analyzed for beta and gamma emitters, H-3, Sr-90 and other radiological 1966 constituents. The samples were collected at established locations, identified as stations, so that 1967 trends in the data could be monitored. The data for the REMP is collected quarterly and reported 1968 annually. The data has consistently supported a conclusion that the operation of ZNPS has and 1969 continues to have no adverse environmental impact on the environment. 1970 2.3.6.4.2. Radiological Groundwater Protection Program (RGPP) 1971 Since the fall of 2006, routine monitoring has been completed through the sampling and analysis 1972 of groundwater from 11 permanent monitoring wells and surface water from one established 1973 sampling location. The location of groundwater monitoring wells and the surface water sample 1974 location is presented in Figure 2-33. 1975 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-49  2.3.6.4.3. National Pollutant Discharge Elimination System (NPDES) 1976 ZNPS has an NPDES permit that was issued by the Illinois EPA. The NPDES permit covers 1977 discharge limitations, monitoring and reporting requirements for station discharges to Lake 1978 Michigan through two approved outfalls (#001 and #002). In addition, ZNPS has a General 1979 NPDES Permit for Storm Water Discharges from Construction Site Activities. The locations of 1980 the outfalls are presented in Figure 2-33. 1981 2.3.6.5. Summary of Analytical Results in Groundwater 1982 H-3 was detected in monitoring well MW-ZN-01S (located just south of the WWTF) in May of 1983 2006. The analysis of groundwater samples collected from both the upper and lower portions of 1984 the screened intervals in MW-ZN-01S resulted in H-3 concentrations of 261  124 pCi/L and 1985 506  141 pCi/L respectively. Well MW-ZN-01S was re-sampled in June of 2006, and the 1986 analysis of the samples resulted in H-3 concentrations of 220  123 pCi/L and <200 pCi/L for 1987 the upper and lower screened intervals respectively. Since the initial sample results noted above, 1988 tritium has not been observed in MW-ZN-01S or any other ZNPS monitoring well greater than 1989 the MDC of 200 pCi/L. It was noted that following the initial sampling in June of 2006 the 1990 tritium analysis method was changed to include distillation of the samples for tritium. It should 1991 also be noted that even though the level of H-3 was greater than the detection limit, the reported 1992 values were significantly less than the EPA drinking water standard of 20,000 pCi/L. 1993 Sr-90 was also detected during the May 2006 sampling event, specifically at monitoring wells 1994 MW-ZN-05S (located south of the Service Building parking lot) and MW-ZN-06S (located near 1995 the access road west of the Switchyard and up-gradient of ZNPS). The Sr-90 concentrations 1996 were respectively, 1.93  0.8  pCi/L (MDC: 1.3 pCi/L) and 1.77  0.72 pCi/L, (MDC: 1997 1.15 pCi/L). Based on the uncertainty and associated MDC both samples are very near the 1998 detection limit. These concentrations were less than the EPA drinking water standard of 8 pCi/L. 1999 Both of these locations are up-gradient from the groundwater flow direction and should not be 2000 impacted by ZNPS activities. 2001 Between 2006 and 2013, other radionuclides have been detected in groundwater at the Facility at 2002 concentrations greater than their respective detection limits. These include the natural 2003 radionuclides associated with the soils, silts and clays. These radionuclides were K-40, Th-228, 2004 Ra-226 and Ac-228. These naturally occurring radionuclides are expected to be within the soils 2005 and detected during sample analyses. Appendix D of TSD 14-003 presents the 2006 through 2006 2011 analytical data for groundwater analysis. Table 6.2 of TSD 14-003 presents the 2012 2007 through 2nd Quarter 2014 analytical results for groundwater analysis. 2008 2.3.6.6. Summary of Analytical Results in Surface Water 2009 Between 2006 and 2014, H-3 and site-derived radionuclides has not been detected in surface 2010 water at ZNPS at concentrations greater than the respective detection limit. Gross Beta was 2011 detected within background range. K-40 was detected in a surface soil sample in May 2006 at a 2012 concentration of 106.8 pCi/L. Appendix D of TSD 14-003 presents the 2006 through 2011 2013 analytical data for surface water. Table 6.2 of TSD 14-003 presents the 2012 through 2nd Quarter 2014 2014 analytical results for surface water analysis. 2015 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-50  2.4. Hazardous Material Characterization 2016 The decommissioning approach for ZSRP calls for the beneficial reuse of concrete from building 2017 demolition as clean fill. A sampling plan was developed and implemented for testing of paints 2018 and coatings on structures and concrete. ZionSolutions evaluated the use of Clean Construction 2019 or Demolition Debris (CCDD) for the end-state of the basements and submitted a "Request for 2020 Concurrence for Basement Fill End-State" to the Illinois EPA in August of 2014. This request 2021 included the results of a sampling plan for concrete candidate fill material to be used for the 2022 basement fill end-state. On October 3, 2014, ZionSolutions received a "Letter of Concurrence" 2023 from the Illinois EPA for the use of CCDD for the basement fill end-state. In accordance with 2024 Section 3.160(b) of the Illinois Environmental Protection Act, CCDD is defined as 2025 uncontaminated broken concrete without protruding metal bars, bricks, rock, stone, reclaimed or 2026 other asphalt pavement or soil generated from construction or demolition activities. Only 2027 concrete debris that meets the definition of CCDD will be considered for use as clean hard fill 2028 and only when surveys have demonstrated that the concrete is free of detectable residual 2029 radioactivity. Concrete debris that is surveyed and found contaminated with detectable residual 2030 radioactivity will be disposed of as low-level radioactive waste. 2031 Integral to the decommissioning process, ZionSolutions has undertaken a comprehensive 2032 asbestos abatement project. Asbestos containing material that is identified on equipment and 2033 structures is remediated prior to demolition. Lead and PCB surveys are also performed on 2034 structures and remediation actions identified prior to demolition. 2035 A sampling program has been developed to assess potential impacts to the environment. Non-2036 radiological site characterization activities focus on areas of interest that have been identified 2037 based on the HSA and current site conditions. Characterization activities have included surface 2038 and subsurface soil sampling as well as groundwater sampling, with primary constituents of 2039 concern including, but not limited to: volatile organic compounds, semi-volatile organic 2040 compounds, polychlorinated biphenyls, metals, and dioxins. A preliminary list of areas of 2041 interest has been developed and will be evaluated for potential impacts to the environment. The 2042 areas of interest include the following: 2043  Fire Training, IRSF, and Mechanical Maintenance Training Warehouse Area 2044  Underground Fuel Oil Tanks (2 locations) 2045  Crib House 2046  East Yard Above Ground Storage Tanks (4 locations) 2047  Aboveground 150,000 gallon Fuel Oil Tank  2048  Transformer Areas  2049  Unit 1 Containment Tendon Area  2050  Used Oil Storage Pad 2051  Aboveground Diesel Fuel Tank north of ENC 2052  North Parking Lot 2053 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-51  Site Warehouses 2054  Oil/Water Separators 2055  Wastewater Treatment Facility 2056  Compactor and Dumpster Areas 2057 Initial characterization activities have been completed at the Fire Training, IRSF, Mechanical 2058 Maintenance Training Warehouse Area, the Crib House, and the above ground 150,000 gallon 2059 Fuel Oil Tank. Environmental sampling completed for the areas of interest identified elevated 2060 poly-nuclear aromatic hydrocarbon (PAH) results in surface soils in the fuel oil tank area. A 2061 remediation plan will be required to address the impacted soils to reach closure of this area under 2062 IEPA regulations. Characterization activities will be completed at the remaining areas of interest 2063 as site decommissioning activities allow. Site closure activities will comply with applicable 2064 USEPA and IEPA regulatory requirements. 2065 2.5. Continuing Characterization 2066 The survey of many inaccessible or not readily accessible subsurface soils or surfaces has been 2067 deferred. All continuing Characterization Plans will be provided to the NRC for information and 2068 all continuing Characterization Reports will be provided to the NRC for evaluation. Examples of 2069 areas where surveys are deferred include soils under structures, soils under concrete or asphalt 2070 coverings, structural wall and floor surfaces in the basements of structures that will remain and 2071 be subjected to FRS, the remaining surfaces of the SFP and Transfer Canal after liner removal, 2072 the interiors of embedded and/or buried pipe that may remain and the interior and exterior of 2073 both Containment domes. The following are areas at Zion where additional or "continuing" 2074 characterization will occur. These areas are; 2075  The underlying concrete of the SFP/Transfer Canal below the 588 foot elevation after the 2076 steel liner has been removed. Continuing characterization will consist of scanning of the 2077 exposed concrete surfaces and the acquisition of concrete core sample(s) at the location of 2078 highest activity. The number and location of the additional concrete core sample(s) will be 2079 determined by DQO during survey design. 2080  The concrete walls and floor of the Under-Vessel areas in Unit 1 and Unit 2 Containments. 2081 Continuing characterization will consist of the acquisition of additional concrete core 2082 sample(s). The number and location of the additional concrete core samples will be 2083 determined by DQO during survey design. 2084  The floors and walls of the Hold-Up Tank (HUT) cubicle. Continuing characterization will 2085 consist of the acquisition of additional concrete core sample(s). The number and location of 2086 the additional concrete core samples will be determined by DQO during survey design. 2087  The floor of the Auxiliary Building 542 foot elevation Pipe Tunnel floors. Continuing 2088 characterization will consist of the acquisition of additional concrete core sample(s). The 2089 number and location of the additional concrete core samples will be determined by DQO 2090 during survey design. 2091 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-52  The floor and lower walls of the 542 foot elevation of the Auxiliary Building to augment the 2092 existing characterization data. The number and location of the additional concrete core 2093 samples will be determined by DQO during survey design. 2094  The subsurface soils in the "keyways" between the Containment Buildings and the Turbine 2095 Building once subsurface utilities have been removed and the removal of subsurface 2096 structures in this area create access (e.g., Waste Annex Building). Continuing 2097 characterization will consist of the scanning of soils exposed by the demolition and building 2098 removal, the acquisition of soil sample(s) of the exposed soil and the acquisition of additional 2099 subsurface soil samples using test pits or soil borings. The number and location of the 2100 additional subsurface soil samples will be determined by DQO during survey design. 2101  The soils under the basement concrete of the Containment Buildings, the Auxiliary Building 2102 and the SFP/Transfer Canal once commodity removal and building demolition have 2103 progressed to a point where access can be achieved. Continuing characterization will consist 2104 of soil borings at the nearest locations along the foundation walls that can be feasibly 2105 accessed, angled soil bores to access the soils under the concrete, and deep cores from 2106 building floors, but not entirely through the foundation, at bias locations to assess migration 2107 potential from building interiors to soils under basement concrete. The number and location 2108 of the additional subsurface soil samples will be determined by DQO during survey design. 2109 Additional investigations and sampling will be performed in accordance with a sample plan 2110 if activity is positively identified. 2111  When the interior surfaces become accessible, several potentially contaminated embedded 2112 and buried pipe systems that will be abandoned in place. Continuing characterization will 2113 consist of direct measurements on pipe openings and the acquisition of sediment and/or 2114 debris samples (if available) for analysis. 2115  The Containment basements after concrete removal. Continuing characterization of the steel 2116 liner will consist of beta gamma scans and swipe samples. 2117 All surface soil at ZNPS has been adequately characterized and additional characterization of 2118 surface soil is not anticipated during continuing characterization. Radiological Assessment (RA) 2119 surveys will be performed in currently inaccessible soil areas that are exposed after removal of 2120 asphalt or concrete roadways and parking lots, rail lines, or building foundation pads (slab on 2121 grade). 2122 The decision to defer the characterization of a soil or structure was based on one or more of the 2123 following conditions: 2124  ALARA considerations (e.g., the area is either a high radiation or high contamination area 2125 and additional data would likely not change the survey area or area classification of the 2126 location or surrounding areas), 2127  Safety considerations (e.g., difficulty of access to the upper reaches of the Containments due 2128 to height), 2129  Historical data shows that the area could be classified without further characterization, 2130 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-53  Access for characterization would require significant deconstruction of adjacent systems, 2131 structures or other obstacles where the removal could result in an unsafe condition or 2132 interfere with continued operation of operating systems, or 2133  The ability to use engineering judgment in assigning the area a classification based on 2134 physical relationship to surrounding areas and the likelihood of the area to have radiological 2135 conditions represented by the conditions in these adjacent areas. 2136 Continuing characterization surveys as specified will be performed when these areas become 2137 accessible. Characterization survey plans will be generated for each using the approved 2138 characterization survey procedures. All additional characterization data will be collected as 2139 necessary, evaluated, documented in a Characterization report and stored with previous 2140 characterization survey data in a survey history file for the survey unit. As access is gained to 2141 areas that were previously inaccessible, additional characterization data will be collected, 2142 evaluated and stored with-other radiological survey data in a survey history file for the survey 2143 unit. This data will be used along with existing data to update the types of radionuclides present 2144 and update the variability in the radionuclide mix for both gamma-emitting and HTD 2145 radionuclides. In addition, as the decommissioning progresses, data from operational events 2146 caused by equipment failures or personnel errors, which may affect the radiological status of a 2147 survey unit(s) will be captured. These events will be evaluated and, when appropriate, stored in 2148 the characterization database. This additional characterization data will be used in validating the 2149 initial classification and in planning for the FSS. 2150 There are several previously inaccessible soils and buried pipe where historical information, 2151 process knowledge or operational survey data indicate that no significant concentrations of 2152 residual radioactivity is identified or anticipated and, that the soil or pipe is classified correctly. 2153 In these cases, survey design for FSS will be use a coefficient of variation of 30% as a 2154 reasonable value for sigma    2155 As decommissioning proceeds, areas will, as necessary, be decontaminated to remove loose 2156 surface decontamination (as well as fixed contamination) to levels that will meet the conditions 2157 for controlled demolition or unrestricted release conditions for demolition. When a structure is 2158 ready for demolition, a documented survey and a formal turnover will be made by the 2159 Radiological Protection group for the group preforming demolition, validating that the 2160 radiological conditions in the structure are suitable. 2161 Following the demolition and/or remediation, and when an area is believed to be ready for 2162 FRSFSS, a "turnover assessment" will be performed. If the results of this assessment indicate 2163 that the FRS FSS acceptance criteria will be met, then physical and administrative control of the 2164 area will be transferred to Characterization/License Termination group personnel for preparation, 2165 design, and performance of the FRSFSS. Otherwise, additional remediation may be required. 2166 This assessment may include a "turnover survey," primarily for Class 1 and 2 areas within the 2167 "Security-Restricted Area". 2168 The "turnover survey" process, together with any additional characterization and remediation 2169 survey performed, represent at least one, but possibly several, opportunities to collect additional 2170 survey data prior to conducting the FRSFSS. For each type of survey (characterization, 2171 remediation, turnover, and FRSFSS), a documented survey plan will be developed using the 2172 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-54  DQO process. These survey plans will contain the appropriate data assessment to ensure that 2173 several objectives are met. These objectives include; 2174  Appropriate instrument selection to ensure the proper sensitivity relative to the applicable 2175 action level and/or release criteria, 2176  Appropriate instrument quality control measures to ensure operability, 2177  Appropriate survey techniques to ensure that the field measurement techniques are consistent 2178 with the calibration methodologies, 2179  Appropriate sample collection and analysis to determine spatial variability and variability in 2180 radionuclide ratios, 2181  Data analysis criteria to identify follow-up actions such as remediation and the collection of 2182 additional samples and, 2183  Appropriate classification of the survey area. 2184 2.6. References 2185 2-1 U.S. Nuclear Regulatory Commission Regulatory Guide 1.179, "Standard Format and 2186 Content of License Termination Plans for Nuclear Power Reactors" - January 1999 2187 2-12-2 "Zion Station Historical Site Assessment" (HSA) - September 2006 2188 2-22-3 U.S. Nuclear Regulatory Commission NUREG-1575, Revision 1, "Multi-Agency 2189 Radiation Survey and Site Investigation Manual (MARSSIM)," - August 2000 2190 2-32-4 U.S. Nuclear Regulatory Commission NUREG-1757, Volume 2, Revision 1, 2191 "Consolidated Decommissioning Guidance - Characterization, Survey, and 2192 Determination of Radiological Criteria, Final Report" - September 2003 2193 2-42-5 ZionSolutions ZS-LT-02, "Characterization Survey Plan" 2194 2-52-6 ZionSolutions ZS-LT-01, "Quality Assurance Project Plan (for Characterization and 2195 FSS)" (QAPP) 2196 2-7 U.S. Nuclear Regulatory Commission NUREG-1700, "Standard Review Plan for 2197 Evaluating Nuclear Power Reactor License Termination Plans" 2198 2-62-8 "Zion Nuclear Power Station, Units 1 and 2 Asset Sale Agreement" - December 2007 2199 2-7 "Zion Station Historical Site Assessment" (HSA) - September 2006 2200 2-82-9 U.S. Nuclear Regulatory Commission Docket Number 50-295, "Facility Operating 2201 License Number DPR-39 (for Unit One)" 2202 2-92-10 U.S. Nuclear Regulatory Commission Docket Number 50-304, "Facility 2203 Operating License Number DPR-48 (for Unit Two)" 2204 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-55  2-102-11 Illinois Environmental Protection Agency - National Pollutant Discharge 2205 Elimination System (NPDES) Permit Number IL0002763 2206 2-112-12 U.S. Nuclear Regulatory Commission IE Bulletin 80-10, "Contamination of 2207 Nonradioactive Systems and Resulting Potential for Unmonitored Release of 2208 Radioactivity to Environment", - May 1960 2209 2-12 U.S. Nuclear Regulatory Commission NUREG-1575, Supplement 1, "Multi-Agency 2210 Radiation Survey and Assessment of Materials and Equipment Manual" (MARSAME) - 2211 December 2006 2212 2-13 Sandia National Laboratories, NUREG/CR-5512, Volume 3, "Residual Radioactive 2213 Contamination From Decommissioning Parameter Analysis" - October 1999 2214 2-14 ZionSolutions Technical Support Document 11-004, "Ludlum Model 44-10 Detector 2215 Sensitivity" 2216 2-15 U.S. Nuclear Regulatory Commission NUREG-1576, "Multi-Agency Radiological 2217 Laboratory Analytical Protocols Manual" (MARLAP) - August 2001 2218 2-16 U.S. Nuclear Regulatory Commission Regulatory Guide 4.15, "Quality Assurance or 2219 Radiological Monitoring Programs (Inception Through Normal Operations to License 2220 Termination) - Effluent Streams and the Environment" - July 2007 2221 2-17 ZionSolutions ZS-QA-10, "Quality Assurance Project Plan - Zion Station Restoration 2222 Project" 2223 2-18 Energy Services Commercial Services Group Report, "Characterization of the Zion 2224 Station Independent Spent Fuel Storage Facility (ISFSI)" - July 2012 2225 2-19 "Annual Report on the Meteorological Monitoring Program at Zion Nuclear Power 2226 Station for 2010", Murray and Trettel, Inc. - February 2011 2227 2-20 Energy Services Commercial Services Group Report CS-RS-PN-028, "Background 2228 Reference Area Report - Zion Nuclear Power Station", - February 2012 2229 2-21 ZionSolutions Report, "Determination of Radionuclide Activity Concentrations in Soils 2230 in Non-Impacted Soils Adjacent to the Zion Nuclear Station", - July 2012 2231 2-22 ZionSolutions Technical Support Document 13-004, "Examination of Cs-137 Global 2232 Fallout in Soils at Zion Station" 2233 2-23 ZionSolutions Technical Support Document 11-001, "Potential Radionuclides of Concern 2234 during the Decommissioning of Zion Station" 2235 2-232-24 ZionSolutions Technical Support Document 14-016, "Description of Embedded 2236 Piping and Penetrations to Remain in Zion End State" 2237 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-56  2-242-25 ZionSolutions Technical Support Document 14-028, "Radiological 2238 Characterization Report" 2239 2-252-26 ZionSolutions Technical Support Document 13-006, "Reactor Building Units 1 & 2240 2 End State Concrete and Liner Initial Characterization Source Terms and Distributions" 2241 2-27 ZionSolutions Technical Support Document 14-019, "Radionuclides of Concern for Soil 2242 and Basement Fill Model Source Terms" 2243 2-262-28 ZionSolutions Procedure ZS-LT-100-001-001, "Characterization Survey Package 2244 Development" 2245 2-272-29 ZionSolutions Technical Support Document 14-003, Conestoga Rovers & 2246 Associates (CRA) Report, "Zion Hydrogeologic Investigation Report" 2247 2-282-30 Conestoga-Rovers and Associates, "Hydrogeologic Investigation Report, 2248 Fleetwide Assessment, Zion Station, Zion Illinois", Revision 1 - September 2006. 2249 2-292-31 Wisconsin Department of Health Services, "Zion Environmental Radioactivity 2250 Survey" - 2001 2251 2-32 International Standard ISO 7503-1, Part 1, "Evaluation of Surface Contamination, Beta-2252 Emitters (maximum beta energy greater than 0.15 MeV) and Alpha-Emitters" - August 2253 1998 2254 2-30  2255 2-31 U.S. Nuclear Regulatory Commission Regulatory Guide 4.8, "Environmental Technical 2256 Specifications for Nuclear Power Plants" - December 1975 2257  2258 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-57  Table 2-1 Operational History 2259 DATE(S) EVENT 02/10/67 ComEd announced intent to build Unit 1 07/11/67 ComEd announced intent to build Unit 2 07/12/67 ComEd dockets applications and PSAR to build both Units 1 and 2 11/25/70 ComEd dockets FSAR for both Units 1 and 2 04/06/73 ComEd receives license to operate Unit 1 11/14/73 ComEd receives license to operate Unit 2 06/19/73 Unit 1 Reactor achieves initial criticality 12/24/73 Unit 2 Reactor achieves initial criticality 12/31/73 Commercial operation begins for Unit 1 09/17/74 Commercial operation begins for Unit 2 03/05/76 to 06/19/76 Unit 1 Spring 1976 Refueling Outage 06/25/76 License received to operate both Units 1 and 2 at 100% power 01/07/77 to 03/27/77 Unit 2 Spring 1977 Refueling Outage  09/09/77 to 12/04/77 Unit 1 Fall 1977 Refueling Outage 02/04/78 to 04/12/78 Unit 2 Spring 1978 Refueling Outage 09/21/78 to 11/02/78 Unit 1 Fall 1978 Refueling Outage 03/09/79 to 04/18/79 Unit 2 Spring 1979 Refueling Outage  10/06/79 to 02/19/80 Unit 1 Fall 1979 Refueling Outage 05/02/80 to 07/26/80 Unit 2 Summer 1980 Refueling Outage 01/15/81 to 04/22/81 Unit 1 Spring 1981 Refueling Outage 09/11/81 to 12/01/81 Unit 2 Fall 1981 Refueling Outage  02/13/82 to 07/07/82 Unit 1 Spring 1982 Refueling Outage 02/24/83 to 05/27/83 Unit 2 Spring 1983 Refueling Outage 09/07/83 to 02/09/84 Unit 1 Fall 1983 Refueling Outage  03/27/84 to 07/10/84 Unit 2 Spring 1984 Refueling Outage 01/30/85 to 06/18/85 Unit 1 Spring 1985 Refueling Outage 09/05/85 to 02/04/86 Unit 2 Fall 1985 Refueling Outage  2260 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-58  Table 2-1 Operational History (continued) 2261 DATE(S) EVENT 09/04/86 to 03/20/87 Unit 1 Fall 1986 Refueling Outage 02/03/87 to 02/04/87 Unit 2 Reactor Shutdown for 2D Main Steam Isolation Valve Oil Leak 04/25/87 to 05/05/87 Unit 1 Shutdown due to H-2 leak from Generator 03/25/87 to 08/08/87 Unit 2 Spring 1987 Refueling Outage 05/10/87 to 05/15/87 Unit 1 Shutdown due to High Vibrations in Generator 10/02/87 to 10/06/87 Unit 2 Reactor Forced Outage for Pressurizer Spray Valve Leakage 02/24/88 to 05/09/88 Unit 1 Spring 1988 Refueling Outage 07/13/88 to 07/16/88 Unit 1 Reactor Trip due to S/G Steam-flow/Feed-flow mismatch 07/23/88 to 07/26/88 Unit 1 Reactor Offline due to Extraction Steam leak in 16 heaters 08/09/88 to 08/12/88 Unit 2 Reactor Shutdown for 2A & 2D S/G Handhole Repairs 10/08/88 to 10/09/88 Unit 2 Reactor Trip during PT-1 10/12/88 to 12/28/88 Unit 2 Fall 1988 Refueling Outage 10/25/88 to 11/04/88 Unit 1 Reactor Shutdown due to Station Blackout 01/15/89 to 02/01/89 Unit 2 Reactor Shutdown to Repair 2A Steam Generator Tube Leak 01/27/89 to 01/29/89 Unit 1 Turbine Trip During EM Troubleshooting 02/06/89 to 03/03/89 Unit 1 Outage for Primary S/G Manway Gasket Replacement  02/20/89 to 02/22/89 Unit 2 Reactor Shutdown Due to Excess Pzr Spray Valve Leakage 03/08/89 to 03/09/89 Unit 1 Reactor Shutdown due to Inoperable RPI's / Sola Transformer 04/22/89 to 04/24/89 Unit 2 Reactor Shutdown due to Excess RCS Leakage - 2SS-9351A 08/21/89 to 08/23/89 Unit 1 Forced Outage due to loss of EHC Fluid from Broken Piping 08/27/89 to 08/31/89 Unit 1 Reactor Shutdown due to Inoperable S/G Safety Valves 09/07/89 to 01/25/90 Unit 1 Fall 1989 Refueling Outage  12/01/89 to 12/04/89 Unit 2 Reactor Forced Outage due to RCS Leak 01/18/90 to 01/19/90 Unit 2 Reactor Forced Outage due to Loss of EHC Control 01/27/90 to 01/28/90 Unit 1 Reactor Trip due to 1D S/G High Level alarm  03/01/90 to 06/13/90 Unit 1 and Unit 2 Reactor Forced Outage due to Diesel Failure 03/21/90 to 08/30/90 Unit 2 Spring 1990 Refueling Outage  2262 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-59  Table 2-1 Operational History (continued) 2263 DATE(S) EVENT 08/13/90 to 08/17/90 Manual Trip of Unit 1 Turbine due to Operator Error 09/07/90 to 09/22/90 Unit 2 Turbine/Reactor Trip on loss of Condenser Vacuum 09/22/90 to 11/03/90 Unit 2 Turbine/Reactor Trip on 2W Main Transformer Failure 11/06/90 to 11/12/90 Shutdown of Unit 1 due to inoperable Diesel Generators 11/11/90 to 11/13/90 Unit 2 Turbine Trip Block Diaphragm Rupture 11/18/90 to 11/19/90 Unit 2 Heater Drain Tank Rupture Disk Repair 12/04/90 to 05/14/91 Unit 1 Reactor Shutdown due to excessive RCS Leakage 01/04/91 to 01/11/91 Unit 2 2A & 2B Safety Injection Pump Failure  03/21/91 to 06/11/91 Fire in the Unit 2 System Auxiliary Transformer 06/08/91 to 06/10/91 Unit 1 Reactor Shutdown required by abnormal 1C RCP Indications 06/11/91 to 06/13/91 Unit 2 Seal Leakoff Flow Transmitter Failed 07/28/91 to 07/30/91 Unit 2 Heater Drain Recirculation Line Rupture 09/27/91 to 11/11/91 Unit 2 1992 Surveillance Outage 12/07/91 to 01/02/92 Hydrogen Leak from Unit 1 Main Generator 02/27/92 to 08/13/92 Unit 1 1992 Refueling Outage  04/04/92 to 06/19/91 Unit 2 System Auxiliary Transformer Replacement  09/17/92 to 10/03/92 Shutdown of Unit 1 Reactor to repair the 1A Aux Feedwater Pump 11/12/92 to 02/22/93 Unit 2 1992 Refueling Outage 02/24/93 to 02/25/93 Unit 2 Main Turbine Overspeed Test 07/07/93  to 07/09/93 Unit 1 Reactor Trip due to trip of 1B RCP  07/10/93 to 07/11/93 Unit 1 Heater Drain Tank Disk Rupture  10/07/93 to 04/18/94 Dual Unit 2 Service Water/Refueling Outage 10/21/93 to 04/03/94 Dual Unit 2 Service Water/Refueling Outage 04/03/94 to 06/14/94 Unit 1 Reactor Trip due to fire at Generator Bus Duct 07/02/94 to 07/16/94 Unit 1 Reactor Trip due to fire at under Main Generator Bus Duct 10/21/94 to 10/23/94 Excessive Secondary Leak on 1A S/G Handhold  01/06/95 to 04/19/95 Unit 2 Refueling Outage  2264 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-60  Table 2-1 Operational History (continued) 2265 DATE(S) EVENT 05/11/95 to 05/14/95 Unit 1 1995 Maintenance Outage 12/07/95 to 12/10/95 Unit 2 EHC Leak Due To Cracked Weld Near Accumulators 01/13/96 to 02/03/96 Unit 2 Maintenance Outage to repair Main Condenser Tubes 02/19/96 to 03/16/96 Unit 1 Shutdown to locate a loose item in the 1B S/G 03/16/96 to 03/22/96 Unit 1 Reactor Scram due to "1C" S/G Hi Level alarm 04/17/96 to 04/26/96 Automatic Scram of Unit 1 Reactor caused by Trip Of "C" Loop Flow 05/19/96 to 05/23/96 Shutdown of Unit 2 due to inoperable Diesel Generators 08/18/96 to 08/22/96 Automatic Trip of Unit 1 due to Failed Limit Switch On "1D" MSIV 08/27/96 to 09/18/96 Unit 1 Forced Outage To Repair Block Valve 1MOV-RC8000B 9/19/96 Last Day of Power Operations for Unit 2 9/19/96 to 01/15/98 Unit 2 Extended Refuel Outage 02/21/97  Last day of power operations for Unit 1 02/21/97 to 02/28/97 Unit 1 Forced Outage due to "1C" Core Spray Pump Inoperability 03/01/97 to 03/30/97 Unit 1 Maintenance Outage 03/31/97 to 01/15/98 Unit 1 Spring Refuel Outage 01/15/98 Decision to Permanently Shutdown Zion Unit 1 and Unit 2 02/13/98 Certification of Permanent Cessation of Operations for both Units 03/09/98 Certification of Permanent Defueled Status for both Units 03/10/98 to 01/25/08 Zion Units 1 and 2 maintained in a SAFSTOR condition 02/14/00 Exelon (formally ComEd) submits PSDAR to NRC. 01/25/08 Exelon submits application to NRC to transfer license to ZionSolutions 02/02/09 Zion NRC Licenses formally transferred to ZionSolutions pending confirmatory orders 09/01/09 Confirmatory orders issued allowing ZionSolutions to begin decommissioning 10/13/10 Physical Decommissioning of Zion Units 1 and 2 commences  2266  2267 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-61  Table 2-2 Historical Incidents/Occurrence 2268 Date Incident/Occurrence Citation 07/24/73 RCS spill from pressurizer spray valves. (ROR - No #) 12/27/73 Approximately 12,000 gallons of S/G water of pH 9.7 was released to the lake. Also approximately 2800 pounds of boric acid was also released to the lake.  (NRC IR      74-17/74-17) 02/1974 to 10/1974 During this period, forty-six liquid releases were made to the discharge canal from the waste neutralization tank. Two releases had detectable tritium and Co-58. In addition, two liquid releases were made from the Unit 2 Condenser Hotwell to the discharge canal which exhibited detectable tritium. (NRC IR 74-14/74-13) 02/07/74 Spill of approximately 15 ft3 of spent resin from "2B" CVCS mixed resin bed demineralizer (ROR 74-01) 04/25/74 Valve leak in Unit 2 Containment leading to >10 gpm RCS leak. (NRC IR                    74-07/74-07) 07/26/74 Overflow of both Unit 1 and Unit 2 PWSTs. Unit 1 overflowed approximately 500 gallons and Unit 2 overflowed approximately 100 gallons. The top one-inch of soil in both spill areas was collected and disposed of as radioactive material. (NRC IR                  74-13/74-12 and 74-14/74-13) 07/30/74 A Rad Waste shipment to Sheffield arrived with 2 spots of liquid and some resin beads on the floor of the tractor trailer.  (NRC IR 74-11/74-10) 08/27/75 Spent resin spill in the Rad Waste Annex Truckbay 592 ft.
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elevation (ROR 75-30) 09/08/75 Contaminated tools were discovered in the storeroom. (ROR 75-34) 09/12/75 1000 to 2000 gallons of RWST water sprayed through Core Spray into Unit 1 containment. (NRC IR              75-13/75-12) 01/22/76 Approximately 300 gallons of RCS water spilled from "2A" S/G manway. (ROR 76-001) 01/26/76 Approximately 3,000 gallons of RCS water spilled from an open check valve on loop "2D". (ROR 76-003) 03/18/76 Legal overexposure of 8.05 Rem occurred in the Unit 1 Incore area. (NRC IR              76-12/)  2269 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-62  Table 2-2 Historical Incidents/Occurrence (continued) 2270 Date Incident/Occurrence Citation 03/24/76 The Unit 1 RWST overflowed through the vent line contaminating the Unit 1 Auxiliary Building adjacent to the Unit 1 Containment between the 640 ft. to the 592 ft. and into the soil. Contamination levels on the wall were reading up to 3000 cpm/ft2 and direct reading on the soil indicated up to 10,000 cpm. (ROR 76-018) 04/20/76 Contaminated water leaking from the "1" Boric Acid Evaporator tank leaked into the "1B" Charging pump room and into the Laundry Drain Tank area on the 560 ft. elevation of the Auxiliary Building (ROR 76-032) 05/05/76 A rope contaminated was discovered in the Tech Staff area of the Service Building (ROR 76-39) 06/24/76 Contaminated clothing with readings up to 4,500 cpm was discovered in the Shift Engineer office. (ROR 76-044) 08/14/76 Due to leakage from valve 0VC8264, a gaseous release occurred which exceeded the tech spec limit of 60,000 uCi/sec. The maximum release rate was 100,000 uCi/sec, with a total activity released of 31.8 Ci.  (LER 2-76-029 and NRC IR 76-31/76-27) 09/19/76 The PRT rupture disc failed due to a trip of Unit 2 Reactor. Approximately 2,500 gallons of PRT water spilled into Unit 2 Containment. (NRC IR              76-28/76-24) 09/19/76 A fire occurred when operating the "2A" Diesel Generator (NRC IR 76-28/76-24) 10/01/76 The Turbine Building Floor Drain Analysis Tank (TBFDAT) was found with 5K cpm direct and adjacent pipes up to 175 cpm/ft2 (ROR 76-53) 10/02/76 Contaminated tools were discovered in the Tech Staff area of the Service Building (ROR 76-51) 10/02/76 Contaminated tools were discovered in the storeroom. (ROR 76-52) 10/20/76 An unmonitored release (~ 5000 gallons) occurred from the TBFDAT to the fire sump. (ROR 76-56 and LER 1-76-084) 02/15/77 Contaminated protective clothing with readings up to 2,500 cpm was discovered outside of the Gate House (ROR 77-07)  2271 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-63  Table 2-2 Historical Incidents/Occurrence (continued) 2272 Date Incident/Occurrence Citation 03/07/77 Radiological surveys performed on the 560 ft. and 592 ft. elevations of the Unit 2 Turbine Building identify loose surface contamination. (ROR - No #) 06/03/77 Fire hoses were found draining the TBFDAT to the Fire Sump. (ROR 77-27 and ROR 77-28) 06/30/77 Water which had collected in the Unit 1 Electrical Conduit Sump in the Turbine Building was discharged through the normal discharge path to Lake Michigan. The water in this sump is from ground seepage and has been assumed to be non-radioactive and discharged as such. It was discovered after the release that it was contaminated with low level radioactivity.
The activity released was estimated to be 0.00614 Ci of beta/gamma emitters and 0.0274 Ci of tritium.  (LER 2-77-038) 06/1977 Release via an unauthorized unmonitored effluent pathway of about 5000 gallons from the Turbine Building Floor Drain Analysis Tank via the Turbine Building Fire Sump. Samples indicated concentrations of 2E-5 uCi/ml of fission products and an H-3 concentration of 2E-3 uCi/ml. This incident also resulted in the contamination of the Unit 1 and Unit 2 Oil Separators. The leakage containing H-3 from a Feedwater pump was being collected and routed via a drain to the Waste Neutralization tank. (NRC IR 77-15/77-18) 10/19/77 Contaminated tools were discovered in the IM "Hot Shop" in an un-posted area. (ROR 77-47) 11/09/77 Contaminated line was discovered in a desk located in the MM Shop. (ROR 77-61) 11/12/77 Carpet in the control room was identified as radiologically contaminated. (ROR 77-63) 02/25/78 A pipe wrench with contamination up to 500 cpm direct was discovered in the MM Shop tool crib. (ROR 78-20) 02/25/78 A document that was discovered to be radiologically contaminated was discovered in the Tech Staff area of the Service Building. A follow-up survey of the area identified 35 additional contaminated documents in the area. (ROR 78-61) 03/23/78 Contaminated shoe covers and coveralls with readings up to 1,000 cpm direct were discovered in a station pickup truck. (ROR 78-36)  2273 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-64  Table 2-2 Historical Incidents/Occurrence (continued) 2274 Date Incident/Occurrence Citation 04/15/78 Pipes by the TBFDAT and the Turbine Building Equipment Drain Analysis Tank (TBEDAT) found to have exposure rates up to 200 mR/h on contact. (ROR 78-15) 06/06/78 Contamination up to 200,000 cpm direct was found on the ground outside the Rad Waste annex.  (ROR 78-43) 06/20/78 Spill of approximately 16 gallons of spent resin spill in the Rad Waste Annex area. Incident contaminated a truck and a concrete pad (DVR 22-1-78-107) 07/23/78 During the transfer of S/G blowdown resin to an HN-150 cask, the cask was overfilled, causing contaminated resin to fall on the cask, trailer, and onto the ground outside the loading area.  (ROR 78-46) 02/01/79 During the transfer of the 2A mixed bed to an HN-200 cask, an overflow occurred, spilling approximately 25 gallons of the water/resin mixture onto the cask exterior, truck-bed, and onto the pavement around truck. Dose rates on the spilled mixture ranged from 180 - 310 mR/h.  (ROR 79-01) 03/05/79 A contaminated trailer was found parked outside the Fuel Building trackway door. Although wrapped in plastic, the trailer still had contamination up to 300,000 cpm and a hot spot of 120 mR/h. The trailer was successfully decontaminated and released on 10/25/1979. (ROR 79-08) 03/30/79 A spill occurred during the filling of a resin cask for solidification and shipment. An estimated 25 gallons of line flush water containing some resins overflowed the cask, contaminating it, the trailer, and the concrete pad outside of the Rad Waste Truckbay where the transfer took place. The occurrence was blamed on failure of a high liquid level alarm together with a frozen overflow line designed to handle such an occurrence. (NRC IR                  79-04/79-04) 04/09/79 Surveys conducted outside the fenced area by the Rad Waste loading area noted soil contamination up to 3000 cpm.  (ROR 79-12) 06/05/79 After the Rad Waste loading area had been remediated, a large amount of plastic was found in the area with up to 20,000 cpm removable contamination. A wall in the area was found with up to 25,000 cpm/ft2 contamination.  (ROR 79-25)  2275 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-65  Table 2-2 Historical Incidents/Occurrence (continued) 2276 Date Incident/Occurrence Citation 08/07/79 During the transfer of resin into an HN-600 cask, a hose became disconnected from a sight-glass, spraying a resin/water mixture into the area. Due to the ventilation configuration, most of the spill was contained in the Rad Waste Truckbay and Auxiliary Building, but some radioactive material spread to the area outside of the Truckbay door. (ROR 79-36A) 10/26/79 pH of WWTF discharge to Lake Michigan was observed at 8.1 which are above the limit of 8.0. (LER 1-79-085) 12/1979 A spill occurred during the filling of a resin cask for solidification and shipment. An estimated 25 gallons of line flush water containing some resins overflowed the cask, contaminating it, the trailer, and the concrete pad outside of the Rad Waste Annex where the transfer took place. The occurrence was blamed on failure of a high liquid level alarm together with a frozen overflow line designed to handle such an occurrence. Temperature at the time of the transfer was said to be 10-15 degrees F. A rather extensive cleanup was performed. The tractor was cleaned and released; the trailer moved to the Fuel Handling Building loading area, where it was stored until final disposition.  (NRC IR 79-04/79-04) 12/27/79 The WWTF effluent pH ranged from 4.1 to 4.77 (lower than the Tech spec minimum of 6.0). A total of 5,760 gallons of the acidic solution was discharged to the condenser cooling water, where it was further diluted prior to discharge to Lake Michigan. (LER 1-79-094) 03/20/80 A hose from the Auxiliary Building Floor Drain Analysis Tank (ABFDAT) and Equipment Drain Analysis Tank (ABEDAT) to a portable demineralizer ruptured and spilled approximately 20 gallons of contaminated water from the 617 ft. elevation to the 562 ft. elevation. Contamination ranged from 1,000 to 2,000 cpm/ft2. (ROR 80-16) 03/21/80 While using a portable demineralizer system in the Rad Waste Annex, a hose failure resulted in the spill of approximately 30 to 40 gallons of radioactive water to the floor. (NRC IR                80-05/80-04) 04/17/80 Spent resin was spilled in the non-posted portion of the Fuel Handling Building 617 ft. elevation mezzanine (ROR 80-20)  2277 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-66  Table 2-2 Historical Incidents/Occurrence (continued) 2278 Date Incident/Occurrence Citation 05/1980 Due to a valve connection error, a freeze seal that was applied was applied to a RCS pipe system failed, causing the spill of approximately 2,000 gallons of refueling cavity water to the basement of the Unit 2 Containment. (NRC IR 80-12/80-12) 05/21/80 Contamination up to 1,000 cpm/ft2 was discovered on the cask overflow liner outside of the posted "Contaminated Area". (ROR 80-31) 06/09/80 A spill of contaminated water occurred during the solidification of an HN-100 demineralizer. The spill contaminated the floor in the Fuel Handling Building outer track-way (Car-Shed) up to 35,000 cpm/ft2.  (ROR 80-35) 07/08/80 The WWTF effluent pH ranged from 4.0 to 6.0 (lower than the Tech spec minimum of 6.0). A total of 317,430 gallons of the acidic solution was discharged to the condenser cooling water, where it was further diluted prior to discharge to Lake Michigan. (LER 1-80-033) 07/20/80 The WWTF effluent pH ranged from 4.0 to 6.0 (lower than the Tech spec minimum of 6.0). Approximately 70,200 gallons of the acidic solution with a pH of 5.86 was discharged to the condenser cooling water, where it was further diluted prior to discharge to Lake Michigan. (LER 1-80-035) 10/24/80 A basic solution from the Waste Neutralization Tank drained to the Fire Sump and the resulting effluent pH to the WWTF was 8.49. Approximately 8,600 gallons of caustic water was discharged to the condenser cooling water, where it was further diluted prior to discharge to Lake Michigan. (LER 1-80-045) 10/30/80 A contaminated metal pipe with readings up to 100,000 cpm was found in a dumpster.  (ROR 80-64) 11/01/80 The WWTF effluent pH was measured at 4.45 with a tech spec allowed range of 6 - 8. Approximately 27,000 gallons of acidic wastewater was discharged to the condenser cooling water, where it was diluted by a factor of 8200 to 1. (LER 1-80-047) 11/02/80 A contaminated black hose and plastic with readings up to 1,500 cpm was discovered outside the Unit 2 Containment Emergency hatch. (ROR 80-56) 11/18/80 A contaminated vent duct (up to 3,000 cpm/ft2) was found in a dumpster.  (ROR 80-74)  2279 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-67  Table 2-2 Historical Incidents/Occurrence (continued) 2280 Date Incident/Occurrence Citation 11/20/80 A contaminated vent duct (up to 800 cpm/ft2) was found in a dumpster.  (ROR 80-77) 01/15/81 to 01/31/82 Primary to Secondary leakage discovered on the "1B" S/G and "1C" S/G prior to outage. Leakage observed at 45 gpd. After outage completion, leakage again noted in "1B" S/G at ~ 4 to 32 gpd.  (NRC IR 81-03 and NRC IR 81-09/81-05) 02/08/81 Contaminated water was sprayed into the Rad Waste Annex when a hose from a liner ruptured. (ROR 81-25) 02/26/81 A rug contaminated with readings up to 50,000 cpm direct was discovered adjacent to the old Service Building elevator and a chair contaminated with readings up to 300 cpm direct was discovered in the MM Shop office area. (ROR 81-31) 03/21/81 An individual carrying personal clothing alarmed the Gate House portal monitor. The individual refused to bag the clothing and return to Radiation Protection. The individual left the clothing in the Gate House and left site.  (ROR 81-33) 04/05/81 Four bags containing contaminated materials (up to 80,000 cpm) was found in a dumpster.  (ROR 81-35) 04/14/81 A bag containing contaminated Out-Of-Service cards (up to 200,000 cpm) was found in a dumpster.  (ROR 81-39) 04/14/81 A contaminated individual was inadvertently released from site resulting in the low level contamination of passenger vehicles and the individual's home with identified readings up to 700 cpm direct. The total offsite activity released was estimated to be less than 0.5 uCi.  (ROR 81-37, NRC IR 81-15/81-11 and ComEd response) 04/15/81 A contaminated hammer with readings up to 500,000 cpm direct was discovered in the Gate House (ROR 81-40) 04/16/81 Three bags containing contaminated materials (up to 2,500 cpm) was found in a dumpster.  (ROR 81-38A) 08/20/81 A contaminated tool with readings up to 1,200 cpm fixed was discovered in the Tech Staff office area of the Service Building. (ROR 81-49)  2281 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-68  Table 2-2 Historical Incidents/Occurrence (continued) 2282 Date Incident/Occurrence Citation 08/21/81 A dry active waste (DAW) shipment from Zion was found to be leaking water upon its arrival at the Richland Washington disposal site. Approximately 2 pints of water containing 20 to 80 pCi of activity was found on the truck bed. The DAW container was found to have been damaged.  (NRC IR 81-20/81-16) 09/1981 In September 1981, the leakage from "1B" S/G averaged 118 gpd. (NRC IR                  81-20/81-16) 09/11/81 During Unit 2 outage, a fuel assembly was damaged (missing spring clip, torn grid strap and a loose rod). The fuel assembly was removed and repaired. Subsequent debris from the failure was observed in "2B" and "2C" S/Gs.  (NRC IR                  81-26/81-22) 10/1981 In 4th qtr of 1981, primary to secondary leakage observed was "1A"  S/G (~12 gpd), "1B"  S/G (~240 gpd), "1C"  S/G (~20 gpd), and "1D"  S/G (~19 gpd) (NRC IR 81-26/81-22) 10/27/81 A "bellows" contaminated with readings up to 1,000 cpm direct was discovered in the EM Shop (ROR 81-57) 10/29/81 A contaminated teletector with loose contamination up to 20,000 cpm/ft2 was discovered in the respirator issue room. (ROR 81-54) 12/01/81 Noted RCS leak from Unit 2 RVLIS fitting upon reaching operating pressure. Due to leak, the upper reactor head was saturated with steam and condensed reactor coolant. (NRC IR                      81-26/81-22) 12/01/81 to 01/15/82 Due to increasing activity in the secondary system of Unit 1 due to primary to secondary leaks in all four S/G at flow rates exceeding 500 gpd, several areas in the Unit 1 Turbine Building were posted as Radiologically Controlled Areas (NRC IR 81-29/81-27) 12/19/81 to 01/19/82 Primary to secondary leakage observed was "1B" S/G (218 to 431 gpd) and "1C" S/G (8 to 56 gpd) (NRC IR                      81-29/81-27) 02/28/82 Contaminated protective clothing was discovered in the clean trash staging area in the Unit 1 Turbine Building Trackway (ROR 82-35) 03/03/82 A health physicist intentionally released approximately 20 people who had alarmed the gate house portal monitor. One individual was noted to have 500 cpm on a shoe.  (ROR 82-53 and ROR 82-54) 03/09/82 A pair of contaminated rubber gloves reading up to 300 cpm was discovered during a daily survey of a trash pile at the dumpster area. (ROR 82-88B)  2283 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-69  Table 2-2 Historical Incidents/Occurrence (continued) 2284 Date Incident/Occurrence Citation 03/21/82 Contaminated tools and scrap materials with direct readings up to 900 cpm was discovered in the clean trash staging area in the Unit 1 Turbine Building Trackway (ROR 82-30 and ROR 82-32) 03/24/82 Leakage from the Unit 1 refueling cavity occurred due to gasket failure of a nuclear instrument well cover. The leakage increased beyond the capacity of the installed containment and cavity sump systems. The reactor cavity filled up and overflowed about 2,000 gallons onto the containment floor. (NRC IR                      82-04/82-04) 03/25/82 A portable demineralizer in the Rad Waste Annex overflowed, resulting in the spill of an indeterminate amount of radioactive water spilled to floor (ROR 82-40) 03/25/82 Legal overexposure of 3.88 Rem occurred in the Unit 1 Incore area. (NRC IR 82-09/) 04/04/82 A bag of contaminated trash reading 200 cpm was discovered in the clean trash staging area in the Unit 1 Turbine Building Trackway (ROR 82-47) 04/18/82 Contaminated protective clothing with readings up to 300 cpm was discovered in the clean trash staging area in the Unit 1 Turbine Building Trackway (ROR 82-56) 04/21/82 Contaminated gloves reading up to 300 cpm was discovered in the clean trash staging area in the Unit 1 Turbine Building Trackway (ROR 82-60) 04/29/82 A bag containing contaminated material (200 cpm) was found in a dumpster during daily survey. (ROR 82-63) 05/09/82 A contaminated surgeon's cap with readings up to 1,500 cpm was discovered on the ground between the Gate House and the NRC Building (ROR 82-64) 05/25/82 A bag containing contaminated material (400 cpm) was found in a dumpster during daily survey. (ROR 82-69) 06/08/82 A piece of radiologically contaminated waste was discovered in the office area by the control room. (ROR 82-71) 06/17/82 A piece of contaminated pipe reading 45,000 dpm direct was discovered in the dumpster (ROR 82-73)  2285 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-70  Table 2-2 Historical Incidents/Occurrence (continued) 2286 Date Incident/Occurrence Citation 06/17/82 A barrel from the Unit 1 steam tunnel was transferred to the clean trash compactor and found to have contaminated oil/dirt/grease in bottom. (up to 62,500 dpm). Some material spilled onto the asphalt and was subsequently cleaned. (ROR 82-74) 06/25/82 Unit 2 Reactor tripped from full power due to a ground on the Main Power Transformer. Fire-fighting exercises to the north of the Turbine Building resulted in the Main Power Transformer being covered with a residue of the fire-fighting chemical ("purple K"). A sudden rain interacted with the chemical causing a conducting solution and the busses arced to ground. (NRC IR 82-14/82-13) 07/17/82 to 08/31/82 RCS to CC water system leak in the Unit 1 Pzr Steam Space Sample Cooler (NRC IR                82-19/82-17) 08/11/82 A fire occurred in the "0" Diesel Generator due to a failure of the turbo charger lube oil filter gasket. The oil sprayed on an exhaust manifold where it ignited. An additional 10-15 gallons of lube oil spilled on the floor.  (NRC IR                        82-19/82-17) 11/17/82 Trash bags containing contaminated material (up to 100K dpm) were discovered at the trash compacting area. While moving the bags, material spilled which contaminated the asphalt. The surface was subsequently decontaminated. An investigation concluded that the material originated from steam tunnel work areas. (ROR 83-81) 01/31/83 A severe oil leak occurred on the "2B" Diesel Generator (NRC IR              83-02/83-02) 04/14/83 Unit 1 shutdown due to severe weather when 4 of 6 incoming 4KV lines were lost. This resulted in a surge on the Unit 1 Main Transformer resulting in an insulator for one phase of the east transformer to explode.  (NRC IR 83-04/83-04) 07/13/83 RCS leakage of ~ 1.6 gpm was identified (source from BIT inlet valves) (LER 1-83-020) 08/04/83 Hydrazine spill by Unit 1 Hydrazine Tank on the Turbine Building 560 ft. elevation (NTS 29520193 CAT4-0673) 08/17/83 Fire in the "1A" Diesel Generator room due to the failure of the turbocharger oil filter gasket which allowed oil to spray directly onto the turbocharger manifold. (NRC IR 83-17/83-18)  2287 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-71  Table 2-2 Historical Incidents/Occurrence (continued) 2288 Date Incident/Occurrence Citation 10/16/83 Contaminated slings reading up to 50,000 dpm was discovered in the clean trash staging area in the Unit 1 Turbine Building Trackway (ROR 83-67) 11/02/83 High noble gas levels in Unit 1 resulted in the contamination of 65 persons (NRC IR              83-21/83-22 and  83-27/83-28 and ROR 83-97) 11/09/83 A bag containing contaminated material (20,000 cpm) was found in a dumpster during daily survey. (ROR 83-78) 11/22/83 An individual alarmed the gate house portal monitor due to contaminated tape stuck to shoe. The investigation led to a probable location of source as outside the east DAW Building. (ROR 83-87) 01/15/84 A contaminated flashlight with readings up to 3,000 cpm direct was discovered at the Gate House. (ROR 84-07) 01/20/84 While performing repairs in the seal table room, a fitting broke causing an RCS leak of ~ 18 gpm. Approximate 700 gallons of RCS spilled before the leak was stopped. (LER 1-84-005, and NRC IR 83-26/83-27) 03/14/84 The Hot Lab and office areas were contaminated during a Na-24 moisture carryover test. (ROR 84-20) 05/1984 Caustic accidentally entered the RW system, releasing radioactive contaminants which had plated out on the piping and caused higher levels of contaminants in the liquid waste effluents. (LER 1-85- 035) 05/09/84 Contaminated material with readings up to 1,250,000 dpm direct was discovered in the dumpster (ROR 84-41) 05/11/84 Drained down ~ 3000 gallons of 30% NaOH from the Unit 2 Spray Add tank. The majority of the caustic ended up in the ABEDAT room through vents in the Containment Spray pumps.  (Letter re: high Na concentration in Unit 2 RCS) 05/12/84 Materials with loose surface contamination was discovered in the east DAW Building (ROR 84-42) 05/30/84 Found a fire extinguisher in the Turbine Building with fixed contamination up to 1,250 dpm (ROR 84-47)  2289 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-72  Table 2-2 Historical Incidents/Occurrence (continued) 2290 Date Incident/Occurrence Citation 06/16/84 A contractor who set off the gate house portal monitor allegedly decontaminated his shoe in a puddle outside the gate house. (ROR 84-54) 08/14/84 The Unit 2 Containment exceeded the Technical Specification limit of 120 degrees F. Actual maximum temperature was 120.48 degrees. (LER 2-84-020) 08/26/84 A "teletector" located in the IM Shop was discovered to be internally contaminated. (ROR 84-76) 09/10/84 Unit 1 was shutdown due to excessive primary to secondary leakage of > 500 gpd (calculated at 1,050 gpd). Unusual Event declared (NRC Log, LER 1-84-029, NRC IR 84-17/84-18) 09/14/84 A pipe wrap contaminated with readings up to 7,500 cpm direct was discovered in the MM Shop. (ROR 84-104) 09/27/84 Contaminated material with readings up to 7,500 dpm direct was discovered in the dumpster (ROR 84-80) 10/06/84 Contaminated material with readings up to 7,500 dpm direct was discovered in the dumpster (ROR 84-88) 11/12/84 RCS leakage reached 10-12 gpm due to packing leaks from valve 2FCV-121. The valve is located in the "2B" Charging Pump room. (NRC IR 84-23/84-22) 12/07/84 A U.S. Flag was found to be contaminated with readings up to 2,500 cpm direct. The contamination was later found to be naturally occurring materials.  (ROR 84-102) 12/10/84 Discovered contaminated material with readings up to 375,000 dpm in an uncontrolled storage cage on the Unit 1 Turbine Building 617 ft. elevation (ROR 84-103) 01/03/85 Radiological surveys discovered contaminated material up to 2,500 cpm fixed in the trash segregation area located in Unit 1 Turbine Building Trackway. Investigations concluded that the material originated in the secondary sample room (ROR 85-02) 01/19/85 During testing, a fuel oil supply line leaked an indeterminate amount of fuel oil to the Turbine Building floor  (LER 1-85-002)  2291 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-73  Table 2-2 Historical Incidents/Occurrence (continued) 2292 Date Incident/Occurrence Citation 02/05/85 Contaminated trash reading up to 2,500 dpm was discovered in the clean trash staging area in the Unit 1 Turbine Building Trackway (ROR 85-18) 03/02/85 Contaminated trash reading up to 2,000 dpm was discovered in the clean trash staging area in the Unit 1 Turbine Building Trackway (ROR 85-40) 02/16/85 to 05/17/85 2 component cooling water leaks identified in relief valves, the first one on 02/16/85 on 1CC-9427 (total of ~ 1710 gallons of water), and the second on 05/17/85 on 1CC-9428. A total of ~ 10,000 gallons of component coolant water was discharged to the containment floor (NRC IR                85-12/85- 13 and NRC IR                            85-20/85-21) 03/16/85 Contaminated trash reading up to 3,700 dpm was discovered in the clean trash staging area in the Unit 1 Turbine Building Trackway (ROR 85-46) 04/06/85 Contaminated material with readings up to 18,750 dpm fixed was discovered in the Tech Staff area of the Service Building (ROR 85-49) 04/24/85 Contaminated tools with fixed contamination up to 5,000 dpm direct was discovered in the EM Shop (ROR 85-53) 05/13/85 A radiological survey of Unit 1 Steam Tunnel identified contaminated material up to 1250 dpm by direct frisk. (ROR 85-61) 08/23/85 A contaminated Rad Waste cask with 200,000 dpm fixed and 3,750 dpm smearable was identified as it was being unloaded inside the north security gate. (ROR 85-74) 09/14/85 A contaminated ladder with readings up to 7,500 dpm direct was discovered leaning against the Unit 1 Discharge Valve house. (ROR 85-80) 09/14/85 Contaminated hoses with readings up to 75,000 dpm direct were discovered in the Crib House. (ROR 85-81) 09/14/85 Contaminated white crystals (up to 2500 dpm) were found under the evergreens outside the Service Building and in the storage shed near the WWTF. Isotopic analysis results showed all activity was due to naturally occurring potassium in the crystals (fertilizer). (ROR 85-82)  2293 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-74  Table 2-2 Historical Incidents/Occurrence (continued) 2294 Date Incident/Occurrence Citation 12/10/85 Contaminated plywood reading up to 18,500 dpm was discovered in the clean trash staging area in the Unit 1 Turbine Building Trackway (ROR 85-101) 12/17/85 Contaminated trash reading up to 7,500 dpm was discovered in the clean trash staging area in the Unit 1 Turbine Building Trackway (ROR 85-104) 12/18/85 Contaminated wood pallet reading up to 1,000 dpm was discovered in the clean trash staging area in the Unit 1 Turbine Building Trackway (ROR 85-106) 01/30/86 Contaminated rubber gloves with readings up to 12,500 dpm direct was discovered in a trash can outside of the Auxiliary Building elevator. (ROR 86-05) 01/31/86 During a resin sluice, a hose broke spilling contaminated liquid into the Rad Waste Annex 592 ft. elevation floor. Floor was contaminated to levels up to 675,000 dpm/100cm2 smearable. (ROR 86-06) 02/11/86 Contaminated protective clothing with readings up to 6,250 dpm was discovered in the clean trash staging area in the Unit 1 Turbine Building Trackway (ROR 86-08) 05/16/86 Observed RCS leakage in excess of Technical Specification limit. Source was Pzr spray valve 1PCV-RC06 (NRC IR              86-11/86-10) 06/09/86 Flooding was noted in the Unit 2 Tendon tunnels (Zion RP/Decon Log) 06/26/86 Pieces of contaminated metal with readings up to 1,250 dpm direct was discovered in the dumpster (ROR 86-18) 09/16/86 Contaminated protective clothing with readings up to 7,500 dpm was discovered in the clean trash staging area in the Unit 1 Turbine Building Trackway (ROR 86-23) 09/30/86 Spill from the Unit 1 SST following weld repairs on the tank. (Zion RP/Decon Log) 11/17/86 Transportation incident with the shipment of the 1A RCP motor to Westinghouse as the package was damaged in-route. No loss of contamination control occurred.  (NRC IR 86-28/86-28) 12/04/86 Contaminated material with readings up to 12,500 dpm was discovered in the clean trash staging area in the Unit 2 Turbine Building Trackway (ROR 86-46)
ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-75  Table 2-2 Historical Incidents/Occurrence (continued) 2295 Date Incident/Occurrence Citation 02/09/87 A spill of approximately 60 gallons of fuel oil occurred in the Turbine Building (Zion RP/Decon Log) 03/27/87 Minor fire in the Turbine Building 560 ft. elevation (NRC IR                        87-06/87-06) 03/27/87 Contaminated trash with readings up to 10,000 dpm was discovered in the clean trash staging area in the Unit 1 Turbine Building Trackway (ROR 87-10) 04/29/87 Discovered a contaminated step stool with readings up to 2,500 dpm direct in an outside trash pile (ROR 87-15) 05/21/87 Service water flood into the "2A" and "2B" Diesel Fuel Oil Storage tank rooms as well as the Turbine Building 560 ft.
elevation. Approximately 181,000 gallons of water was discharged (NRC IR                  87-09/87-11 and                NRC IR                        87-16/87-16) 05/31/87 Contaminated metal with direct readings up to 8,750 dpm was discovered in the scrap metal dumpster (ROR 87-21) 06/21/87 Found contaminated protective clothing and tape (up to 2500 dpm direct) near Primary Storage Tank Pumps (ROR 87-25) 08/04/87 Contaminated protective clothing with readings up to 10,000 dpm direct was discovered in a trash pile north of the Crib House. (ROR 87-36) 10/01/87 Observed RSC leakage in Unit 2 Containment from Pzr Spray valve. (NRC IR                        87-26/87-27) 10/09/87 Discovered contaminated material with readings up to 25,000 dpm in Tech Staff storage cage on the Unit 1 Turbine Building 617 ft. elevation (ROR 87-41) 03/1988 to 12/1988 Report denotes a 1200 gallon spill of diesel fuel in March 1988, a 500 gallon diesel fuel spill in April 1988 and a 300 gallon turbine oil spill in May of 1988. In addition, a Bulk Acid Tank rupture in December of 1988 resulted in the discharge of 92%
sulfuric acid to the WWTF for processing. (1988 WWTF Report) 03/01/88 An oil spill was identified in Unit 1 Turbine Building that deposited oil along the wall and on the floor of the insulator workshop in the south Condenser Bay (Zion RP/Decon Log)  2296 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-76  Table 2-2 Historical Incidents/Occurrence (continued) 2297 Date Incident/Occurrence Citation 04/01/88 Contaminated tool with fixed contamination up to 12,500 dpm direct was discovered in the MM tool crib (ROR 88-33) 04/16/88 Discovered contaminated drums of waste oil with smearable levels up to 2,500 dpm on the outside of the drums located in the posted "High Radiation Area" between the Unit 2 Containment and the Fuel Handling Building (ROR 88-47) 05/1988 Spill of approximately 300 gallons of oil in the Turbine Building. (1988 WWTF Report) 05/03/88 Radiological surveys identified surface contamination up to 10,000 cpm fixed on materials found in an outside trash pad. An investigation concluded that the material originated in the Unit 2 Steam Tunnel Valve House. (ROR 88-54) 05/04/88 Diesel fuel oil spill in the Unit 1 Containment Spray cubicle in the Auxiliary Building. (Zion RP/Decon Log) 05/27/88 Contaminated material, up to 375,000 dpm direct was discovered in a trash pile located outside of the RCA. (ROR 88-59) 10/22/88 Hydrazine spill by the Unit 1 Chemical Addition area on the Turbine Building 560 ft. elevation. (Zion RP/Decon Log) 10/27/88 License termination order for the Westinghouse Training reactor housed in the West Training Center received  (NRC License #
R-119, Docket # 50-87) 11/19/88 Contaminated tools with readings up to 25,000 dpm fixed were discovered in the contractor office trailer located adjacent to the Unit 2 trackway. (ROR 88-85) 12/07/88 Discovered a contaminated hand radio with fixed readings up to 40,000 dpm direct in the IM Shop. (ROR 88-88) 12/19/88 Bulk Acid Tank rupture caused 1,228 gallons of 92% sulfuric acid to be sent to the WWTF for processing. (1988 WWTF Annual Report) 12/19/88 Discovered spill of sulfuric acid in the Unit 2 Turbine Building Trackway. The acid flowed down an floor penetration and deposited acid on the 560 ft. elevation floor (NRC IR 88-23/88-23) 02/12/89 The Rad Waste conveyor system broke down during the removal and shipment of some of the drums. As a result, some drum with spent resins was spilled outside. (Zion RP/Decon Log)  2298 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-77  Table 2-2 Historical Incidents/Occurrence (continued) 2299 Date Incident/Occurrence Citation 02/21/89 Rad Waste conveyor system broke during the removal and shipment of 55 gallon drums of waste. Spent resin was spilled outside the Truckbay door when several barrels broke open (Zion RP/Decon Log) 03/16/89 Contaminated insulating blankets (up to 37,500 dpm direct) were found in the Unit 2 Turbine Building trackway trash area. These blankets were determined to have come from the "2C" East MSR Reheat Stop Valve. (ROR 89-21) 03/22/89 Discovered contaminated wood with fixed contamination up to 37,500 dpm direct in the Unit 2 Turbine Building Trackway trash segregation area (ROR 89-24) 05/08/89 Unplanned release of radioactive noble gas and spill of approximately 300 gallons of RCS water during a fill of the CVCS demineralizer. (NRC IR            89-20/89-18) 07/18/89 Discovered contaminated tool with fixed contamination up to 20,000 dpm direct in the Shift Engineer office. (ROR 89-24) 07/28/89 Discovered contaminated metal with readings up to 75,000 dpm direct in the dumpster trash area. (ROR 89-31) 10/01/89 Identified flooding in Unit 1 Containment through the open manway openings in all four S/G (Zion RP/Decon Log) 01/03/90 Observed RCS leakage of ~ 20 gpm from valve 1MOVRH8702 (LER 1-90-001) 01/16/90 The overflow of the "0A" Lake Discharge Tank (LDT) resulted in a substantial contamination of the Auxiliary Building 542 ft. elevation floor. (ROR 90-02) 01/23/90 Zion became aware of a condenser cooling water leakage from Unit 2 discharge piping approximately 60 feet off shore. It was determined that a 20 foot section of the 14 foot diameter pipe had shifted slightly, resulting in the top portion of the discharge piping's bell spigot joint to be misaligned. This translated to a four inch gap at one construction joint and an 8 inch gap on the other. The estimate at the time was that 10% of the discharge volume was escaping the normal discharge location of 870 feet into Lake Michigan. The intent was to continue operations in this mode until late March 1990.  (NRC IR          90-03/90-03)  2300 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-78  Table 2-2 Historical Incidents/Occurrence (continued) 2301 Date Incident/Occurrence Citation 03/05/90 A loss of Main Turbine oil of approximately 3,000 gallons from the Unit 2 Turbine Oil reservoir was identified and observed as an oil slick in the Screen-house afterbay. The leak was isolated and the oil was removed from the afterbay. No detectable oil was observed in Lake Michigan by the Coast Guard.  (NRC IR 90-03/90-03 and ESD Spill Summary) 03/06/90 Black sand was discovered on the beach adjacent to the site.
Analysis indicated that the "black sand" from lake shore was not oil/grease, but ferrotitanium. Oil and grease were less than 40 ug/g.  (SMAD black sand analysis) 03/22/90 A contaminated wire with readings up to 3,750 dpm direct was discovered under the stairs in on the Service Building 592 ft.
elevation (ROR 90-05) 03/29/90 Water leakage and system overflow in both Unit 1 and Unit 2 Containment Spray pump cubicles (Zion RP/Decon Log) 04/08/90 Contaminated chairs with readings up to 7,500 dpm direct was discovered in the Gate House (ROR 90-48) 04/02/90 Contaminated material up to 7,500 dpm/100cm2 smearable was discovered in the Fuel Handling Building Car-Shed (ROR 90-07) 04/26/90 Instruments contaminated with readings up to 150,000 dpm direct was discovered in the IM Shop (ROR 90-18) 04/26/90 A contaminated instrument component with readings up to 10,000 dpm fixed was discovered in the trash awaiting compaction at the Crib House (ROR 90-19) 05/04/90 A contaminated clipboard with readings up to 18,750 dpm fixed was discovered in the contractor trailer. (ROR 90-24) 05/07/90 During the refueling of Unit 2, a piece of grid strap was observed falling from a fuel assembly during movement. The cladding on the assembly remained intact (LER 2-90-006) 07/02/90 The overflow of the "0A" Lake Discharge Tank (LDT) resulted in a substantial contamination of the Auxiliary Building 542 ft. elevation floor. (ROR 90-35) 07/31/90 Discovered a bucket containing contaminated concrete with readings up to 57,500 dpm fixed in the outside trash area. It was identified that the bucket originated from the 642 ft.
elevation of the Turbine Building. (ROR 90-38) 2302 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-79  Table 2-2 Historical Incidents/Occurrence (continued) 2303 Date Incident/Occurrence Citation 08/22/90 Spill of approximately 200 gallons of radiologically contaminated water from the vendor laundry trailer located at the north missile door entrance to Auxiliary Building. The water spilled onto concrete into the adjacent subsurface soil.
The affected area was approximately 80 feet by 80 feet. (ROR 90-41) 09/10/90 Notification of flooding in the Crib House. Flooding reached levels approximately 2 feet above the basement floor. An unusual event was declared. (NRC IR 90-21/90-23) 09/22/90 The Unit 2 Main Power Transformer exploded and burned, resulting in a spill of approximately 300 gallons of transformer oil to the pavement adjacent to the transformer. (NRC IR 90-21/90-23) 09/29/90 Discovered nitrogen tanks with fixed contamination up to 5,000 dpm direct in the Unit 1 Turbine Building trackway (ROR 90-43) 10/16/90 Both LDTs overflowed resulting in the discharge of approximately 16,000 gallons of contaminated water to the Auxiliary Building 542 ft. elevation floor. (Zion RP/Decon Log) 02/25/91 Discovered contaminated fittings and flanges with readings up to 25,000 dpm direct on a truck leaving the Protected Area. (ROR 91-04) 04/17/91 Due to a leaking valve, the SFP overflowed. Water accumulated in and overflowed the ABEDAT (500 to 1000 gallons) causing the backup of water through the bedplate drains in the Unit 1 and Unit 2 Containment Spray pump rooms and the Unit 1 Safety Injection pump room. The areas outside the rooms and the level below were contaminated.  (NRC IR 91-10/91-10) 06/26/91 Break in a temporary PVC pipe for a temporary demineralizer skid created a flood on the Turbine Building 560 ft. elevation. (Zion RP/Decon Log) 08/01/91 The Boric Acid Mix Tank (BAMT) overflowed, contaminating Auxiliary Building areas from the 617 ft. elevation to the 562 ft.
elevation. (Zion RP/Decon Log) 05/13/92 Approximately 4,200 gallons of RCS water was inadvertently sprayed into Unit 2 Containment through the "2A" Containment Spray header (NRC IR 92-10/92-10) 05/17/92 A grass fire was reported adjacent to the West Training area. No citation  2304 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-80  Table 2-2 Historical Incidents/Occurrence (continued) 2305 Date Incident/Occurrence Citation 05/19/92 to 07/06/92 A weld failure in the RWST system resulted in a leak of approximately 1 gpm to the Unit 1 Equipment Drain Tank Collector room. (NRC IR 92-14/92-14) 07/15/92 A failure of the "2A" Diesel Generator was attributed to zebra mussels in the lube oil system. Zebra mussels were later also found in "2B" Diesel Generator coolers. (LER 2-92-004 and Zion RP/Decon Log) 10/24/92 Overflow of the "0B" Blow Down Monitor Tank (BDMT) resulted in the contamination of approximately 5,000 ft2 of floor on the Auxiliary Building 542 ft. elevation. (NTS 2952019 208401) 11/04/92 During a cleanup of the two oil/water separators, the station discovered oil containing PCBs (5 ppm on Unit 1 and 11 ppm on Unit 2). These were the only positive results for PCBs. After the separators were cleaned, water and sludge samples were taken and indicated <0.5 ppb and < 1.0 mg/kg PCB respectively. (NTS 29555492 CAT3-087) 03/29/93 An oil leak was identified that leak approximately 80 gallons of oil to the floor near the "2C" Feed Water pump (NTS 30420193 CAT4-0258) 06/01/93 Unit 1 and Unit 2 oil separator sludge found to be contaminated (NTS 29520193 CAT4-0456) 07/15/93 Underground oil storage tanks for the CS Diesel was identified as leaking (NTS 29520193 CAT4-0586) 11/18/93 A temporary hose rupture in the Circ. Water bay resulted in the spill of sodium hypochlorite. (NTS 29520193 CAT4-1339) 11/18/93 Mercury spill occurred outside the Unit 2 Turbine Building trackway adjacent to the Unit 2 Main Transformer on the asphalt. NTS 30420193 CAT4-1340) 11/27/93 Overflow of the Unit 1 ABEDT resulted in back-leakage into the Containment Spray and Safety Injection cubicles in the Auxiliary Building (NTS 29520193 CAT4-1381) 12/04/93 Contaminated scaffolding with readings up to 20K dpm fixed was used to repair the temporary Auxiliary Boiler located outside of the Service Building.  (NTS 29520093 CAT3-202)  2306 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-81  Table 2-2 Historical Incidents/Occurrence (continued) 2307 Date Incident/Occurrence Citation 01/06/94 A mercury spill occurred while removing a hydrogen purity meter. The material spilled at the base of the panel on 617 ft. elevation of the Unit 1 Turbine Building. While transporting the device to the IM shop, mercury was spilled on the Turbine Building elevator, on the 592 ft. elevation outside the elevator, inside and outside of the MM shop, outside of the north Service Building elevator, hallway to the IM shop, and in the IM shop. All areas were cleaned and released. (NTS 29520194 CAT4-0019) 01/15/94 Oil was observed leaking from the 1E and 1W Main Transformers.  (NTS 29520194 CAT4-0110) 01/17/94 Oil spill from the Unit 1 Turbine Oil reservoir seeped through the floor to the 560' elevation of the Turbine Building (NTS-29520194 CAT4-0111) 02/16/94 Contaminated material found in decontamination technician trailer (NTS 29520094 CAT3-038) 03/16/94 A contractor laborer was found to have contaminated clothing with readings up to 24,000 dpm fixed in a hotel room off-site. The hotel room and vehicle were surveyed and not contaminated. (NTS 29510094008, NTS 29520094 CAT3-074 and NRC IR        94-08/94-08) 04/03/94 A fire occurred in the Unit 1 Main Generator Lead Box which subsequently cause a trip of the Unit 1 Reactor (LER 1-94-005, NRC IR 94-09/94-09 and NRC IR          94-12/94-12) 03/07/94 A failure of the "2B" Diesel Generator was attributed to zebra mussels in the lube oil and jacket water coolers.  (LER 2-94-002) 03/22/94 Two abandoned transformers were found in the owner-controlled fields west of the facility. One had fallen over and was leaking oil onto the ground. The oil was tested and did not contain PCBs.  (NTS 29520194 CAT4-0790) 05/31/94 While performing a flush of the Turbine Oil seals, approximately 200 gallons of turbine oil overflowed into the Unit 1 Main Generator (NTS 29520194 CAT4-1206)  2308 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-82  Table 2-2 Historical Incidents/Occurrence (continued) 2309 Date Incident/Occurrence Citation 07/02/94 A fire occurred in the three bus duct phases for Unit 1 Main Generator. The fire resulted in a shutdown of Unit 1 Reactor.  (LER 1-94-010 and NRC IR    94-17/94-17) 08/19/94 Oil was observed leaking from the #9 cooler on the 1W Main Transformer. (NTS 29520194 CAT4-1844) 08/24/94 The SFP overflowed, resulting in the spill of approximately 1,250 gallons of borated water through the Unit 1 Containment Spray pump and the Unit 1 Safety Injection pump bedplates. (NRC IR          94-19/94-19 and (NTS 29520094 CAT3-204) 09/03/94 A contaminated cart with readings up to 55,000 dpm fixed was discovered in the Radiation Protection office. (NTS 29520094 CAT3-211) 09/06/94 Oil was observed leaking from the #7 cooler on the 1W Main Transformer. (NTS 29520194 CAT4-1985) 03/09/95 Contaminated tool with fixed contamination up to 53,000 dpm fixed found in the MM tool crib (NTS29520095 CAT3-044) 04/1995 "Cleansweep Project" implemented at Zion site. Project implemented the comprehensive survey of site facilities and grounds to identify uncontrolled radioactive material. The following findings were identified; The survey was conducted between 04/25/95 through 05/04/95. 61 items found with fixed contamination up to 80,000 dpm direct, and 3 items with smearable contamination up to 6,000 dpm/100cm2. Eleven items were discovered in the Bechtel warehouse, one in the east MM training area, one in the decontamination trainer, one in the paint shed and one item on the 4th floor of the Service Building (NTS29520095 CAT3-044) 04/05/95 The Hydrazine Addition Tank overflowed approximately 6 gallons of 35% solution hydrazine to the floor in the Turbine Building during Auxiliary Boiler layup. (NTS 29520095 CAT3-071) 04/21/95 Spill of caustic liquid in the Unit 1 Containment Spray pump cubicle. (NTS 29520195 CAT4-1310) 04/29/95 Resin spill in the "2A" De-Borating demineralizer cubicle left approximately 6 inches of spent resin on the floor of the cubicle. (Zion RP/Decon Log) 05/10/95 Contaminated materials discovered in the IM Shop (NTS 29520095 CAT3-090)  2310 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-83  Table 2-2 Historical Incidents/Occurrence (continued) 2311 Date Incident/Occurrence Citation 06/12/95 A mercury spill occurred inside the Unit 1 Screen Wash panel in the Crib House. (NTS 29520195 CAT4-1629) 08/15/95 Contamination discovered on the internals of the Auxiliary Boiler (NTS 29520195 CAT4-2208 09/11/95 to 10/25/95 Contaminated resin (up to 7.15E-7 uCi/g Co-60 and 4.94E-7 uCi/g  Cs-137) found in 3 barrels of used resin from non-rad systems (only one barrel was identified as Unit 1 stator water). Additional contaminated resin was also found in cardboard drums in the same area. (NTS 29520095  CAT3-160 and NTS29520195            CAT4-3148) 09/22/95 Fire in the Unit 1 Refueling Cavity (NTS 29520195 CAT4-2663) 11/13/95 Diesel fuel spill on the floors of both Unit 1 and Unit 2 Containment Spray pump cubicles (Zion RP/Decon Log and NTS 29520195 CAT4-3351) 12/04/95 Contaminated tools and rigging slings with fixed contamination up to 109,000 dpm fixed was discovered in the MM tool crib. (NTS 29520095 CAT3-219) 01/22/96 The Lake Discharge Tank (LDT) overflowed, resulting in the contamination of approximately 11,000 ft2 of the Auxiliary Building 542 ft. elevation being contaminated. (Zion RP/Decon Log) 01/22/96 Three contaminated clipboards with readings up to 31,000 dpm fixed were discovered in the Chemistry Offices. (NTS 29520096 CAT3-010) 02/02/96 Approximately 100 gallons of hydrazine spilled near the "2D" Condensate and Condensate Booster Pump (NTS 30420196 CAT4-0296) 02/18/96 Approximately 1 gallon of hydrazine and approximately 100 gallons of an ammonia/hydrazine mixture spilled on the 560 ft. elevation of the Unit 2 Turbine Building. (PIF 96-4846 and spill log 96-007) 04/15/96 Barrels which contained oil cleaned up from a spill of Turbine oil was knocked over by high winds, resulting in a spill of oil to the concrete storage pad. (NTS 29520196 CAT4-0850) 04/20/96 The "0B" LDT overflowed, resulting in approximately 560 gallons of slightly contaminated water discharged to the Auxiliary Building 542 ft. elevation floor. (NRC IR 96-07/96-07)  2312 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-84  Table 2-2 Historical Incidents/Occurrence (continued) 2313 Date Incident/Occurrence Citation 05/22/96 Contaminated ISI block reading 2,000 dpm fixed discovered on the Turbine Building 617 ft. elevation by the generator seal oil unit. (NTS 29520096 CAT2-008) 06/27/96 Five clothing bins with fixed contamination were discovered stored in an un-posted area on the 592 ft. elevation of Unit 2 Turbine Building. (NTS 2950096 CAT2008 and PIF 96-1405) 07/15/96 The sludge removed from the Unit 1 and Unit 2 Oil Separators was discovered to be contaminated. (Zion RP/Decon Log) 07/18/96 An unspecified volume of hydraulic oil was spilled into the Spent Fuel transfer canal. (PIF 96-1670) 07/27/96 Radiological survey of Turbine Building identified fixed contamination up to 3,800 dpm direct on the MS Stop valve (Zion RP/Decon Log) 08/17/96 The "0B" LDT overflowed, resulting in approximately 7,000 gallons of slightly contaminated water discharged to the Auxiliary Building 542 ft. elevation floor. (NRC IR            96-10/96-10) 08/24/96 Approximately 3,000 gallons of demineralized water was inadvertently sprayed into the Unit 2 Containment 568 ft. elevation. (NRC IR 96-14/96-14) 10/01/96 Scaffolding, delivered to the Zion site was discovered to be contaminated with readings up to 100,000 dpm fixed on various pieces. (PIF 96-2936) 10/12/96 to 12/06/96 An out-of-service component (2RH-8734A) resulted in the spill of approximately 400 gallons of contaminated water to the floor of the Auxiliary Building 542 ft. elevation floor. (NRC IR 96-17/96-17) 10/17/96 A spill of approximately 10 gallons of oil occurred on the "2C" RCP pump deck and on the 568 ft. elevation under the pump. (PIF 96-3505) 10/23/96 An oil leak was identified from the #1 cooler on the 2E Main Transformer. (PIF 96-3672) 10/25/96 Contaminated scaffolding with readings up to 2,000 dpm fixed was discovered adjacent to the missile doors to the Auxiliary Building near Unit 2 Containment. (PIF 96-3724)  2314 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-85  Table 2-2 Historical Incidents/Occurrence (continued) 2315 Date Incident/Occurrence Citation 10/28/96 Received a notice of violation from the North Shore Sanitary District for discharges with too high levels of Total Suspended Solids and ammonia. Additional violations for same parameters were identified on 11/20/1996. (PIF 96-4585 and PIF 96-4994) 10/30/96 Spill of approximately 30 gallons of ethylene glycol occurred in the Auxiliary Building heating coil room. (PIF 96-3816) 11/01/96 Miscellaneous tools with fixed contamination were discovered in the IM Shop on the Service Building 592 ft. elevation. (PIF 96-3954 and PIF 97-0310) 11/16/96 Approximately 1,000 gallons of turbine oil was spilled into the Fire Sump and pumped to the WWTF (PIF 96-4665) 11/18/96 Spill of approximately 10 gallons of ethylene glycol occurred in the Auxiliary Building heating coil supply plenum room. (Spill incident log 96-005) 11/19/96 Approximately 145 gallons of glycol spilled in the bermed area above Unit 2 VCT valve aisle. (Spill incident log 96-006) 11/19/96 Contaminated material was discovered in the IM Shop (PIF 96-4351,  NTS 29520096 CAT2-0802) 12/06/96 Approximately 100 gallons of turbine oil was spilled into the Fire Sump and pumped to the WWTF (PIF 96-4264) 12/25/96 Spill of ethylene glycol on the 617 ft. and 642 ft. elevations of the Auxiliary Building (PIF 96-4986) 01/29/97 Approximately 27 gallons of 40% NaOH from the CS system entered the Unit 2 RWST during CS pump testing.  (PIF 97-0497) 02/01/97 Approximately 1 gallon of diesel fuel spilled at the CS Day Tank fill location. (PIF 97-0672 and Spill/Incident Log 97-006) 02/24/97 Spill of approximately 1.5 gallons of hydrazine on the Unit 1 Turbine Building 560 ft. elevation. (PIF 97-0997 and NTS 29520097SCAQ 0997 03/21/97 A LSA barrel containing non-contaminated sand and water was discovered outside the RCA. (PIF 97-1461)  2316 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-86  Table 2-2 Historical Incidents/Occurrence (continued) 2317 Date Incident/Occurrence Citation 03/29/97 A mercury spill (~ 7 grams) occurred in the Crib House by the Unit 1 Traveling Screens (Spill/Incident Log 97-006) 04/02/97 A grass fire occurred in the open land areas adjacent to the reactor site. (NTS 29520197 CAQS-1632) 04/03/97 During semi-annual air quality checks, found 2 Service Air valves (on the 560' Turbine Building E-23 and F-8) leaking considerable amount of oil/water mixture.  (NTS 29520197 CAQD-2143 and PIF 97-2143) 04/08/97 Individual left site after successfully passing Gate House portal monitor. Upon return to the site, a single particle reading 110,000 dpm contact was found in pants pocket.  (NTS 29520097 SCAQ-1725 and PIF 97-1725) 04/12/97 The Fuel Handling Building roof leaked rainwater into the SFP (NTS 29520197 CAQS-1810) 04/18/97 An empty LSA barrel was discovered in a dumpster north of the Construction Building.  (PIF 97-1928 & NTS 29520097 SCAQ-1928) 04/22/97 Four rusty 55 gallon drums and one 30 gallon drum were found on property east of the BAT warehouse and south of Shiloh Blvd. The barrels were in poor condition and contained a black non-radioactive solid.  (PIF 97-2040) 04/23/97 A spill of approximately 10 to 15 gallons of hydraulic oil spilled in the Unit 2 A/C MSIV room (Spill/Incident Log 97-007) 05/01/97 An oil spill of approximately 15 gallons occurred on the ground south of the Crib House south doors. The area covered approximately 4 feet by 10 feet. Some of the material went into the storm drains. (NTS 29520197 CAQD-2166 and PIF 97-2166) 05/03/97 A contaminated posting stanchion with a reading of 135,000 dpm fixed was discovered on the Unit 1 Turbine Building 617 ft. elevation (NTS 29520097 SCAQ-2192 and PIF 97-2192) 05/06/97 A contaminated stanchion (40K dpm fixed) was found in the contractor fab shop. (NTS 29520197 CAQD-2298 and PIF 97-2298)  2318 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-87  Table 2-2 Historical Incidents/Occurrence (continued) 2319 Date Incident/Occurrence Citation 05/07/97 A contaminated stanchion (10K dpm fixed) was found in the contractor fab shop. (NTS 29520197 CAQD-2297 and PIF 97-2297) 05/14/97 Contaminated materials with readings up to 10,000 dpm fixed was discovered in the West Training Center (NTS 29520197 CAQD-2407) 05/24/97 Flash fire in the Unit 1 Refueling Cavity during the cleaning of stud plugs (NTS 29520097 SCAQ-2561,  PIF 97-2561, and Tech Alert   
#97-21) 05/27/97 A spill of approximately 5 gallons of diesel fuel occurred in the Auxiliary Boiler Storage Tank area. (NTS 29520197 CAQD-2577 and                PIF 97-2577) 07/26/97 Contaminated materials (up to 1,600 dpm fixed) found in a dumpster. The material is believed to have originated from work on the Auxiliary Boiler (NTS 29520197 CAQD-0536 and PIF                Z1997-00906 08/05/97 A spill of sodium hypochlorite occurred on concrete by hypochlorite tank. (Spill incident log 97-009) 09/30/97 A spill of approximately 1 gallon of sodium hypochlorite occurred on concrete by hypochlorite tank. (Spill incident log 97-010) 10/09/97 A spill of approximately 10 gallons of transformer oil occurred near the north gate on gravel. (Spill incident log 97-011) 10/17/97 A spill of approximately 3 gallons of diesel fuel occurred in the Turbine Building (Spill incident log 97-013) 12/11/97 Approximately 13 grams of mercury was spilled in the Cold Lab. (Spill/Incident Log 97-016) 12/18/97 An oil spill of approximately 1 quart occurred into the southwest corner of the fore-bay. (Spill/Incident Log 97-017) 12/11/98 A small diesel oil spill occurred outside the Gate House (PIF 96-4731)  2320  2321 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-88  Table 2-3 Initial List of Structural Survey Units 2322 Survey Unit ID # Survey Unit Description 01000 Unit 1 Containment (All Interior Surfaces are Class 1)  100  568 Ft Elevation  01  Vessel Bio-Shield  02  Inside Missile Barrier - "A" Loop  03  Inside Missile Barrier - "B" Loop  04  Inside Missile Barrier - "C" Loop  05  Inside Missile Barrier - "D" Loop  06  Outside Missile Barrier - "A" Loop  07  Outside Missile Barrier - "B" Loop  08  Outside Missile Barrier - "C" Loop  09  Outside Missile Barrier - "D" Loop  10  Incore Area 543 Ft Elevation  200  592 Ft and 603 Ft Elevation  01  Cavity Area  02  Inside Missile Barrier - "A" Loop  03  Inside Missile Barrier - "B" Loop  04  Inside Missile Barrier - "C" Loop  05  Inside Missile Barrier - "D" Loop  06  Outside Missile Barrier - "A" Loop  07  Outside Missile Barrier - "B" Loop  08  Outside Missile Barrier - "C" Loop  09  Outside Missile Barrier - "D" Loop  10  Incore Drive Area/Seal Table Room 603 Ft Elevation  300  617 Ft Elevation  01  Cavity Area  02  "A" and "C" Loop Area  2323 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-89  Table 2-3 Initial List of Structural Survey Units (continued) 2324 Survey Unit ID # Survey Unit Description  03  "B" and "D" Loop Area  04  Outside Missile Barrier - "A" Loop  05  Outside Missile Barrier - "B" Loop  06  Outside Missile Barrier - "C" Loop  07  Outside Missile Barrier - "D" Loop  400  Exterior Surfaces & Roof (All Exterior Surfaces are Class 2)  01  Roof  02  Exterior Walls 02000 Unit 2 Containment (All Interior Surfaces are Class 1)  100  568 Ft Elevation  01  Vessel Bio-Shield  02  Inside Missile Barrier - "A" Loop  03  Inside Missile Barrier - "B" Loop  04  Inside Missile Barrier - "C" Loop  05  Inside Missile Barrier - "D" Loop  06  Outside Missile Barrier - "A" Loop  07  Outside Missile Barrier - "B" Loop  08  Outside Missile Barrier - "C" Loop  09  Outside Missile Barrier - "D" Loop  10  Incore Area 543 Ft Elevation  200  592 Ft and 603 Ft Elevation  01  Cavity Area  02  Inside Missile Barrier - "A" Loop  03  Inside Missile Barrier - "B" Loop  04  Inside Missile Barrier - "C" Loop  05  Inside Missile Barrier - "D" Loop  2325 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-90  Table 2-3 Initial List of Structural Survey Units (continued) 2326 Survey Unit ID # Survey Unit Description  06  Outside Missile Barrier - "A" Loop  07  Outside Missile Barrier - "B" Loop  08  Outside Missile Barrier - "C" Loop  09  Outside Missile Barrier - "D" Loop  10  Incore Drive Area/Seal Table Room 603 Ft Elevation  300  617 Ft Elevation  01  Cavity Area  02  "A" and "C" Loop Area  03  "B" and "D" Loop Area  04  Outside Missile Barrier - "A" Loop  05  Outside Missile Barrier - "B" Loop  06  Outside Missile Barrier - "C" Loop  07  Outside Missile Barrier - "D" Loop  400  Exterior Surfaces & Roof (All Exterior Surfaces are Class 2)  01  Roof  02  Exterior Walls 03000 Fuel Handling Building (All Interior Surfaces are Class 1)  100  592 Ft Elevation  01  Trackway/Cars Shed/Open Area  02  Spent Fuel Pit Heat Exchangers  03  Spent Fuel Pit Pump Rooms  04  Decon Pit  200  617 Ft Elevation  01  New Fuel Storage Area and 602 Ft Elevation Mezzanine  02  Spent Fuel Pool  03  Cross-town Area and SPING Gallery  2327 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-91  Table 2-3 Initial List of Structural Survey Units (continued) 2328 Survey Unit ID # Survey Unit Description  300  Exterior Surfaces & Roof (All Exterior Surfaces are Class 2)  01  Roof  02  Exterior Walls 04000 Radwaste Building (All Interior Surfaces are Class 1)  100  579 Ft Elevation  01  Crystallizer  200  592 Ft Elevation  01  Dry Active Waste Storage Area  02  Drum Fill Area  03  Radwaste Annex Truck Loading Zone  300  Exterior Surfaces & Roof (All Exterior Surfaces are Class 2)  01  Roof  02  Exterior Walls 05000 Auxiliary Building (All Interior Surfaces are Class 1)  100  542 Ft Elevation  01  Unit 1A RHR Pump Room  02  Unit 1B RHR Pump Room  03  Unit 2A RHR Pump Room  04  Unit 2B RHR Pump Room  05  Unit 1 Pipe Chase  06  Unit 2 Pipe Chase  07  Hold Up Tanks  08  Central Area  09  South Area  10  North Area  11  West Area  2329 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-92  Table 2-3 Initial List of Structural Survey Units (continued) 2330 Survey Unit ID # Survey Unit Description  12  Gas Decay Tanks  13  Unit 1 Equipment Drain Collection Tank  14  Unit 2 Equipment Drain Collection Tank  15  HUT Recirculation and BAE Feed Pumps  16  Aux Building Equipment Drain Tank and Pumps  17  Aux Building Sump A  18  Aux Building Sump B  200  560 Ft Elevation  01  Unit 1A Safety Injection Pump  02  Unit 2A Safety Injection Pump  03  Unit 1B Safety Injection Pump  04  Unit 2B Safety Injection Pump  05  Unit 1A RHR Heat Exchanger  06  Unit 2A RHR Heat Exchanger  07  Unit 1B RHR Heat Exchanger  08  Unit 2B RHR Heat Exchanger  09  Unit 1 Containment Spray Pump  10  Unit 2 Containment Spray Pump  11  South Area  12  Central Area  13  North Area  14  West Area  15  Equipment Drain Tank  16  Chemical Drain Tank  17  Unit 1 Vertical Pipe Chase  18  Unit 2 Vertical Pipe Chase  2331 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-93  Table 2-3 Initial List of Structural Survey Units (continued) 2332 Survey Unit ID # Survey Unit Description  19  Blowdown Heat Exchangers  20  Waste Gas Compressor Area  21  Unit 1 RHR Heat Exchanger Pipe Chase  22  Unit 2 RHR Heat Exchanger Pipe Chase  300  579 Ft Elevation  01  Unit 1A Centrifugal Charging Pump  02  Unit 2A Centrifugal Charging Pump  03  Unit 1B Centrifugal Charging Pump  04  Unit 2B Centrifugal Charging Pump  05  Unit 1C Reciprocating Charging Pump  06  Unit 2C Reciprocating Charging Pump  07  Unit 1 Refueling Water Storage Tank  08  Unit 2 Refueling Water Storage Tank  09  South Area  10  Central Area  11  North Area  12  West Area  13  Unit 1 Horizontal Pipe Chase  14  Unit 2 Horizontal Pipe Chase  15  #1 HUT  16  #0 HUT  17  #2 HUT  18  Anion/Cation Valve Aisle  19  Unit 1 Vertical Pipe Chase  20  Unit 2 Vertical Pipe Chase  400  592 Ft Elevation  01  Unit 1 Letdown Heat Exchanger  2333 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-94  Table 2-3 Initial List of Structural Survey Units (continued) 2334 Survey Unit ID # Survey Unit Description  02  Unit 2 Letdown Heat Exchanger  03  Unit 1 Seal Water Heat Exchanger  04  Unit 2 Seal Water Heat Exchanger  05  Unit 2 Future Diesel Generator  06  Primary Sample Room  07  Calibration Facility  08  South Area  09  Central Area  10  North Area  11  West Area  12  Unit 1 Vertical Pipe Chase  13  Unit 2 Vertical Pipe Chase  14  Unit 1 BAT and Pumps  15  Unit 2 BAT and Pumps  500  617 Ft Elevation  01  Unit 1 Volume Control Tank  02  Unit 2 Volume Control Tank  03  Unit 1 Pipe Chase  04  Unit 2 Chase  05  Radiation Protection Offices  06  Unit 1 Containment Purge Air Equipment Room  07  Unit 2 Containment Purge Air Equipment Room  08  Tool Crib  09  Waste Evaporator Monitor Tank  10  Radwaste Evaporator  11  Spent Resin Storage Area  12  Laboratory  2335 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-95  Table 2-3 Initial List of Structural Survey Units (continued) 2336 Survey Unit ID # Survey Unit Description  13  West Area  14  East Area  600  630 Ft Elevation  01  Unit 1 Cable Spreading Room  02  Unit 2 Cable Spreading Room  03  Unit 1 Cable Penetration Room  04  Unit 2 Cable Penetration Room  700  642 Ft Elevation  01  642 Ft Elevation  800  654 Ft Elevation  01  654 Ft Elevation  900  Exterior Surfaces & Roof (All Exterior Surfaces are Class 2)  01  Roof  02  Exterior Walls 06000 Turbine Building (All Interior Surfaces are Class 2)  100  560 Ft Elevation  01  Oil Room  02  South Area  03  Central Area  04  North Area  200  570 Ft Elevation  01  Unit 1 Diesel Fuel Oil Storage 1B  02  Unit 2 Diesel Fuel Oil Storage 2B  03  Unit 1 Diesel Fuel Oil Storage 1A  04  Unit 2 Diesel Fuel Oil Storage 2A  05  Unit 1 Diesel Fuel Oil Storage 0A  06  Unit 2 Future Diesel Fuel Oil Storage 0B  2337 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-96  Table 2-3 Initial List of Structural Survey Units (continued) 2338 Survey Unit ID # Survey Unit Description  07  Unit 1 Steam Pipe Tunnel  08  Unit 2 Steam Pipe Tunnel  300  592 Ft Elevation  01  Unit 1 Diesel Generator 1A  02  Unit 2 Diesel Generator 1B  03  Unit 1 Diesel Generator 0  04  Unit 2 Diesel Generator 2A  05  Unit 1 Diesel Generator 2B  06  Battery and Charger Room  07  Technical Support Center  08  Secondary Sample Room  09  Auxiliary Heating Boiler  10  South Area  11  Central Area  12  North Area  400  609 Ft Elevation  01  609 Ft Elevation  500  617 Ft Elevation  01  Switchgear Rooms 17, 18 &19  02  Switchgear Rooms 27, 28 &29  03  Air Conditioning Equipment Room  04  QA Records Area  05  South Area  06  Central Area  07  North Area  600  625 Ft Elevation  01  625 Ft Elevation  2339 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-97  Table 2-3 Initial List of Structural Survey Units (continued) 2340 Survey Unit ID # Survey Unit Description  700  642 Ft Elevation  01  Unit 1 Nonessential Switchgear and Rod Drive MG Set  02  Unit 2 Nonessential Switchgear and Rod Drive MG Set  03  Main Control Room Complex  04  Control Room Annex South  05  Control Room Annex North  06  Unit 1 Auxiliary Electric Equipment Room  07  Unit 2 Auxiliary Electric Equipment Room  08  South Area  09  Central Area  10  North Area  800  656 Ft Elevation  01  656 Ft Elevation  900  Exterior Surfaces & Roof (All Exterior Surfaces are Class 2)  01  Roof  02  Exterior Walls 07000 Service Building (All Interior Surfaces are Class 2)  100  592 Ft Elevation  01  East  02  West  200  608 Ft Elevation  01  East  02  West  300  624 Ft Elevation  01  East  02  West  400  636 Ft Elevation  2341 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-98  Table 2-3 Initial List of Structural Survey Units (continued) 2342 Survey Unit ID # Survey Unit Description  01  East  02  West  500  648 Ft Elevation  01  East  600  660 Ft Elevation  01  East  700  Exterior Surfaces & Roof (All Exterior Surfaces are Class 2)  01  East Roof  02  West Roof  03  Exterior Walls 08000 Crib House (All Interior Surfaces are Class 2)  100  552 Ft Elevation  01  552 Ft Elevation  200  594 Ft Elevation  01  594 Ft Elevation  300  Exterior Surfaces & Roof (All Exterior Surfaces are Class 2)  01  Roof  02  Exterior Walls 09000 Outbuildings  100  WWTF  01  1st Floor Interior Surfaces (Class 2)  02  2nd Floor Interior Surfaces (Class 2)  03  Roof (Class 2)  04  Exterior Surfaces (Class 2)  200  North Valve House  01  1st Floor Interior Surfaces (Class 2)  02  Roof (Class 2)  2343 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-99  Table 2-3 Initial List of Structural Survey Units (continued) 2344 Survey Unit ID # Survey Unit Description  03  Exterior Surfaces (Class 2)  300  North Chlorination/Dechlorination Building  01  1st Floor Interior Surfaces (Class 2)  02  Roof (Class 2)  03  Exterior Surfaces (Class 2)  400  Warehouse/Mechanical Maintenance Training Center  01  1st Floor Interior Surfaces (Class 3)  02  Roof (Class 3)  03  Exterior Surfaces (Class 3)  500  Interim Radwaste Storage Facility (IRSF) Building  01  1st Floor Interior Surfaces (Class 2)  02  Mezzanine (Class 2)  03  Roof (Class 2)  04  Exterior Surfaces (Class 2)  600  Fire Training Building  01  1st Floor Interior Surfaces (Class 3)  02  Roof (Class 3)  03  Exterior Surfaces (Class 3)  700  Contractor Break Building  01  1st Floor Interior Surfaces (Class 3)  02  Roof (Class 3)  03  Exterior Surfaces (Class 3)  800  East Training Center  01  1st Floor Interior Surfaces (Class 3)  02  Roof (Class 3)  03  Exterior Surfaces (Class 3)  900  In-Processing Building  2345 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-100  Table 2-3 Initial List of Structural Survey Units (continued) 2346 Survey Unit ID # Survey Unit Description  01  1st Floor Interior Surfaces (Class 3)  02  2nd Floor Interior Surfaces (Class 3)  03  Roof (Class 3)  04  Exterior Surfaces (Class 3)  110  Station Construction Building  01  1st Floor Interior Surfaces (Class 3)  02  Roof (Class 3)  03  Exterior Surfaces (Class 3)  120  Illinois Department of Nuclear Safety (IDNS) Building  01  1st Floor Interior Surfaces (Class 2)  02  Roof (Class 2)  03  Exterior Surfaces (Class 2)  130  Security Offices  01  1st Floor Interior Surfaces (Class 2)  02  Roof (Class 2)  03  Exterior Surfaces (Class 2)  140  Gate House  01  1st Floor Interior Surfaces (Class 2)  02  2nd Floor Interior Surfaces (Class 2)  03  Roof (Class 2)  04  Exterior Surfaces (Class 2)  150  North Warehouse  01  1st Floor Interior Surfaces (Class 3)  02  Roof (Class 3)  03  Exterior Surfaces (Class 3)  160  South Warehouse  01  1st Floor Interior Surfaces (Class 3)  2347 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-101  Table 2-3 Initial List of Structural Survey Units (continued) 2348 Survey Unit ID # Survey Unit Description  02  Roof (Class 3)  03  Exterior Surfaces (Class 3)  170  South Valve House  01  1st Floor Interior Surfaces (Class 2)  02  Roof (Class 2)  03  Exterior Surfaces (Class 2)  180  South Chlorination/Dechlorination Building  01  1st Floor Interior Surfaces (Class 2)  02  Roof (Class 2)  03  Exterior Surfaces (Class 2)  190  West Training Building  01  1st Floor Interior Surfaces (Class 3)  02  2nd Floor Interior Surfaces (Class 3)  03  Roof (Class 3)  04  Exterior Surfaces (Class 3)  2349  2350 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-102  Table 2-4 Initial List of Open Land Survey Units 2351 Survey Unit ID # Survey Unit Description Initial Classification Approximate Survey Unit Area (m2) 12000 Security Restricted Area Grounds  12101 WWTF Sludge Drying Bed Area Class 1 2,036  12102 WWTF Facility Class 1 2,024  12103 Unit 2 PWST/SST Area Class 1 2,034  12104 Area Under Around the North Half of Unit 2 Containment Class 1 1,940  12105 Area AroundUnder the South Half of Unit 2 Containment Class 1 1,938  12106 Area AroundUnder the North Half of Fuel Handling and Auxiliary Buildings Class 1 1,936  12107 Area AroundUnder the South Half of Fuel Handling and Auxiliary Buildings Class 1 1,934  12108 Area AroundUnder the North Half of Unit 1 Containment Class 1 1,932  12109 Area AroundUnder the South Half of Unit 1 Containment Class 1 1,931  12110 Yard Between Unit 1 Containment and Turbine  Class 1 1,740  12111 South Yard Area Northeast of Gate House Class 1 1,964  12112 Unit 1 PWST/SST Area West Class 1 1,658  12113 Unit 1 PWST/SST Area East Class 1 1,693  12201 North Protected Area Yard Class 2 9,610  12202 Gate House and Southwest Yard Class 2 7,562  12203 Soils AroundUnder  the Service Building and South East Yard Class 2 7,569  12204 Crib House Area Class 2 5,909  12205 Area AroundUnder  the Turbine Building Class 2 9,085 10200 Radiological Restricted Area Grounds  10201 NE Corner of Restricted Area - Lakeshore Class 3 8,530  10202 IRSF/Fire Training Area Class 3 7,799 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-103  Survey Unit ID # Survey Unit Description Initial Classification Approximate Survey Unit Area (m2)  10203 East Training Area Class 3 11,761  10204 North Gate Area Class 3 7,230  10205 Switchyard Class 3 55,432 Table 2-4 Initial List of Open Land Survey Units (continued) 2352 Survey Unit ID # Survey Unit Description Initial Classification Approximate Survey Unit Area (m2)  10206 Station Construction Area Class 3 10,539  10207 North Warehouse Area Class 3 10,284  10208 South Warehouse Area Class 3 12,381  10209 Restricted Area South of Gate House Class 3 5,664  10210 Restricted Area South of Turbine Building Class 3 5,048  10211 Southeast Corner of Restricted Area - Lakeshore Class 3 6,472  10212 North Restricted Area Fence line - Lakeshore Class 3 36,714  10213 Power House Area Class 3 44,471  10214 Construction Parking Area Class 3 29,681  10215 Area Northwest of Switchyard Non-Impacted 26,008  10216 Area West Northwest of Switchyard Non-Impacted 31,171  10217 Area Southwest of Switchyard Non-Impacted 45,984  10218 Area Near South of Switchyard Class 3 17,822  10219 Area Far South of Switchyard Class 3 12,185  10220 Adjacent to South Restricted Area - lakeshore Class 3 46,964  10221 Owner Controlled Area South of Restricted Area Class 3 27,297 10300 Owner Controlled Area Grounds (included in Final Safety Analysis Report [FSAR])  10301 West Training Area Class 3 55,942  10302 Northwest Corner of FSAR Area Non-Impacted 35,162  10303 Southwest Corner of FSAR Area Non-Impacted 61,955  10304 Southern Area of FSAR Non-Impacted 34,387 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-104  Survey Unit ID # Survey Unit Description Initial Classification Approximate Survey Unit Area (m2)  10305 Area West of Survey Unit #10217 Non-Impacted 121,535  10306 Area West of Survey Unit #10216 Non-Impacted 85,268 10400 Owner Controlled Area Grounds (not included in FSAR)  10401 Northeast Corner of Owner Controlled Property Non-Impacted 76,118  10402 MET Tower Area Non-Impacted 107,618  2353 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-105  Table 2-4 Initial List of Open Land Survey Units (continued) 2354 Survey Unit ID # Survey Unit Description Initial Classification Approximate Survey Unit Area (m2)  10403 Area North of West Training Non-Impacted 139,282  10404 Northwest Corner of Owner Controlled Property Non-Impacted 100,075  2355  2356 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-106  Table 2-5 Scan Coverage Guidelines for Characterization 2357 Area Classification Recommended Characterization Scan Coverage Class 1 No scanning required unless compelled by a specific survey objective. Class 2 50% to 100%, concentrating on areas with an increased probability of exhibiting elevated activity (such as Class 1 boundaries, vehicle transit routes, etc.). Class 3 10% to 50%, with emphasis on areas that were used for plant activities during operation and areas downwind or downstream of known effluent release points. Non-Impacted 1% to 5%, with emphasis on areas adjacent to impacted areas. 2358  2359 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-107  Table 2-6 Instrument Types and Nominal MDC 2360 Detector Model b Meter Model Application Typical Detection Sensitivity MDCscan (dpm/100cm2) MDCstatica (dpm/100cm2) Ludlum 44-9 Ludlum 2350-1  static & scan 2900 985 Ludlum 43-5 Ludlum 2350-1  static & scan 150 75 Ludlum 43- mode Ludlum 2350-1  static & scan 1050 330 Ludlum 43- mode Ludlum 2350-1  static & scan 170 70 Ludlum 44-116 Ludlum 2350-1  static & scan 1300 415 Ludlum 43-90 Ludlum 2350-1  static & scan 130 55 Ludlum 44-10 Ludlum 2350-1  scan 3.5 pCi/g 60Co 6.5 pCi/g 137Cs N/A Ludlum 43-37 Ludlum 2350-1  scan 1000 N/A Tennelec LB5100 proportional counting system N/A and/or smear N/A 18 HPGe Gamma Spectroscopy System c N/A  Analysis N/A ~0.15 pCi/g for Co-60 and Cs-137 a Based on 1-minute count time; and default values for surface efficiencies s) as specified in International 2361 Standard, ISO 7503-1 (Reference 2-3032). 2362 b Functional equivalent instrumentation may be used 2363 c MDC Requirements per Regulatory Guide 4.8 (Reference 2-3133) 2364  2365  2366 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-108  Table 2-7 Typical Vendor Laboratory Standard MDC Values 2367 Test Technique Method Solid (pCi/g) Water (pCi/L) Gamma radionuclides Gamma Spectroscopy LANL EM-9 0.1 10 Alpha Gas Flow Proportional EPA 900.0 4.0 5.0 Beta Gas Flow Proportional EPA 900.0 10.0 5.0 H-3 Liquid Scintillation EPA 906.0 Mod 6.0 700 C-14 Liquid Scintillation EPA EERF C 2.0 50.0 Fe-55 Liquid Scintillation DOE RESL Fe-1 5.0 100.0 Ni-59 Low Energy Gamma Spectroscopy DOE RESL Ni-1 10.0 20.0 Ni-63 Liquid Scintillation DOE RESL Ni-1 4.0 50.0 Sr-90 Gas Flow Proportional EPA905.0 Mod 2.0 2.0 Tc-99m Liquid Scintillation DOE EML HASL 300 5.0 50.0 Pm-147 Liquid Scintillation EPA EERF PM-1-1 10 10 Np-237 Alpha Spectroscopy DOE EML HASL 0.5 1.0 Pu-238-240 Alpha Spectroscopy DOE EML HASL 300 0.5 1.0 Pu-241 Liquid Scintillation DOE EML HASL 300 15.0 15.0 Am-241 & 243 Alpha Spectroscopy DOE EML HASL 300 0.5 1.0 Pu-242 Alpha Spectroscopy DOE EML HASL 300 0.5 1.0 Cm-242-246 Alpha Spectroscopy DOE EML HASL 300 0.5 1.0  2368  2369 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-109  Table 2-8 EnergySolutions Background Study Results 2370 Asphalt Results Measurements Results in dpm/100cm2 Min Max Average St. Dev 95% UCLa 25 101 393 257 77 284 a 95% Upper Confidence Level on the average based on 25 measurements or 24 (n-1) degrees of freedom. Nuclide Results in pCi/g Average Std. Dev 95% UCLa K-40 4.64E+00 9.26E-01 5.06E+00 Cs-137 1.23E-03 1.05E-02 6.02E-03 Tl-208 1.57E-01 5.56E-02 1.82E-01 Pb-212 1.77E-01 3.81E-02 1.95E-01 Bi-214 1.19E-01 4.01E-02 1.37E-01 Pb-214 1.55E-01 3.68E-02 1.72E-01 Ac-228 1.60E-01 6.55E-02 1.90E-01 Th-234 8.60E-02 3.65E-01 2.52E-01 U-235 3.51E-03 4.11E-02 2.22E-02 a 95% Upper Confidence Level on the average based on 15 measurements or 14 (n-1) degrees of freedom. b Bold values indicate concentration greater than MDC. Italicized values indicate MDC value. Concrete Results Measurements Results in dpm/100cm2 Min Max Average St. Dev 95% UCLa 25 141 541 356 100 391 a 95% Upper Confidence Level on the average based on 25 measurements or 24 (n-1) degrees of freedom. Nuclide Results in pCi/g Average Std. Dev 95% UCLa K-40 5.55E+00 2.63E+00 6.74E+00 Cs-137 1.21E-02 1.82E-02 2.03E-02 Tl-208 2.60E-01 8.74E-02 3.00E-01 Pb-212 3.01E-01 1.15E-01 3.54E-01 Bi-214 3.00E-01 6.51E-02 3.30E-01 Pb-214 3.03E-01 6.57E-02 3.32E-01 Ac-228 3.08E-01 1.03E-01 3.55E-01 Th-234 3.48E-01 3.27E-01 4.96E-01 U-235 8.78E-02 9.81E-02 1.32E-01 a 95% Upper Confidence Level on the average based on 15 measurements or 14 (n-1) degrees of freedom. b Bold values indicate concentration greater than MDC. Italicized values indicate MDC value. 2371  2372 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-110  Table 2-8 EnergySolutions Background Study Results (continued) 2373 Surface Soil Results Surface Scanning Measurements Results in cpm (gross) Min Max Average St. Dev 95% UCL 8,955 2,520 9,240 5,192 832 5,206 Static Measurements Measurements Results in cpm (gross) Min Max Average St. Dev 95% UCLa 30 4,530 6,362 5,718 543 5,886 a 95% Upper Confidence Level on the average based on 30 measurements or 29 (n-1) degrees of freedom. Nuclide Results in pCi/g Average Std. Dev 95% UCLa K-40 1.40E+01 2.00E+00 1.49E+01 Cs-137 6.61E-03 2.15E-02 1.64E-02 Tl-208 4.45E-01 8.78E-02 4.85E-01 Pb-212 5.30E-01 8.94E-02 5.70E-01 Bi-214 5.44E-01 1.10E-01 5.94E-01 Pb-214 5.43E-01 9.21E-02 5.85E-01 Ac-228 5.20E-01 1.02E-01 5.66E-01 Th-234 6.05E-01 4.68E-01 8.18E-00 U-235 9.83E-02 1.16E-01 1.51E-01 a 95% Upper Confidence Level on the average based on 15 measurements or 14 (n-1) degrees of freedom. b Bold values indicate concentration greater than MDC. Italicized values indicate MDC value. Sub-Surface Soil Results Nuclide Results in pCi/g Average Std. Dev 95% UCLa K-40 1.36E+01 2.89E+00 1.49E+01 Cs-137 -1.95E-03 1.83E-02 6.35E-03 Tl-208 4.42E-01 9.56E-02 4.85E-01 Pb-212 4.98E-01 1.68E-01 5.74E-01 Bi-214 6.06E-01 1.76E-01 6.86E-01 Pb-214 6.10E-01 1.92E-01 6.97E-01 Ac-228 4.87E-01 1.14E-01 5.39E-01 Th-234 5.74E-01 4.87E-01 7.95E-00 U-235 5.26E-02 7.70E-02 8.76E-02 a 95% Upper Confidence Level on the average based on 15 measurements or 14 (n-1) degrees of freedom. b Bold values indicate concentration greater than MDC. Italicized values indicate MDC value. 2374 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-111  Table 2-9 Crib House Concrete Core Sample Analysis Results 2375 Concrete Core Sample Analysis Results Nuclide Results in pCi/g Average Max Std. Dev K-40 1.39E+01 2.18E+01 2.86E+00 Co-60 1.20E-01 1.44E-01 1.84E-02 Cs-137 7.00E-02 9.24E-02 1.07E-02 Bi-212 1.82E-01 1.90E-01 1.20E-02 Pb-212 2.38E-01 4.20E-01 6.13E-02 Bi-214 4.00E-01 6.53E-01 9.16E-02 Pb-214 4.36E-01 7.07E-01 1.30E-01 Ra-226 1.46E+00 2.64E+00 4.89E-01 Ac-228 6.93E-01 4.79E-01 9.76E-02 U-235 8.30E-02 1.60E-01 3.59E-01 a Sample population consisted of 40 samples with 32 taken on the floor and 8 taken on lower walls b Bold values indicate concentration greater than MDC. Italicized values indicate MDC value. 2376  2377 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-112  Table 2-10 Hosah Park Background Assessment Sample Analysis 2378 Surface Soil Sample Analysis Results Nuclide Results in pCi/g Average Max Std. Dev K-40 6.62E+00 8.59E+00 9.49E-01 Co-60 4.56E-02 6.09E-02 8.20E-03 Sr-90 5.65E-02 9.76E-02 2.10E-02 Cs-137 6.26E-02 2.41E-01 4.95E-02 Th-228 1.38E-01 4.50E-01 1.05E-01 Th-230 3.31E-01 8.11E-01 2.05E-01 Th-232 1.26E-01 4.05E-01 9.08E-02 U-234 1.46E-01 7.36E-01 1.43E-01 U-235 5.63E-02 1.10E-01 2.76E-02 U-238 1.48E-01 6.65E-01 1.34E-01 a Bold values indicate concentration(s) greater than MDC. Italicized values indicate MDC value. 2379 Surface Soil Sample Analysis Results Nuclide Results in pCi/g Average Max Std. Dev K-40 6.96E+00 8.95E+00 9.01E-01 Co-60 -3.19E-02 2.87E-02 1.88E-01 Sr-90 -6.03E-04 5.26E-02 2.41E-02 Cs-137 2.11E-01 6.51E-01 1.48E-01 Th-228 1.72E-01 4.30E-01 1.18E-01 Th-230 3.45E-01 2.07E+00 3.55E-01 Th-232 1.53E-01 5.11E-01 1.04E-01 U-234 2.03E-01 1.74E+00 3.23E-01 U-235 1.40E-02 1.37E-01 3.24E-02 U-238 2.11E-01 1.86E+00 3.24E-01 Subsurface Soil Sample Analysis Results Nuclide Results in pCi/g Average Max Std. Dev K-40 6.62E+00 8.59E+00 9.49E-01 Co-60 3.72E-04 3.79E-02 1.38E-02 Sr-90 4.40E-03 5.30E-02 2.16E-02 Cs-137 2.64E-02 2.41E-01 6.00E-02 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-113  Th-228 1.26E-01 4.50E-01 1.14E-01 Th-230 3.28E-01 8.11E-01 2.09E-01 Th-232 1.21E-01 4.05E-01 9.54E-02 U-234 1.25E-01 7.36E-01 1.57E-01 U-235 1.05E-02 1.10E-01 2.43E-02 U-238 1.31E-01 6.65E-01 1.47E-01 a Bold values indicate concentration(s) greater than MDC. Italicized values indicate MDC value. 2380  2381  2382  2383 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-114  Table 2-11 Investigative Levels for Cs-137 Based on Background Studies 2384 Condition and Depth Measured Range                (pCi/g) Range for 95% Distribution (pCi/g) Drainage Areas  Surface 0-10 cm Undisturbed 0.00 to 2.80 0.45 to 3.63 Disturbed 0.00 to 1.67 0.35 to 2.86 Non-Drainage Areas Surface 0-10 cm Undisturbed 0.23 to 0.66 0.15 to 0.77 Disturbed 0.27 to 0.34 0.23 to 0.42  2385  2386 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-115  Table 2-12 Initial Suite of Radionuclides 2387 Radionuclide Half Life (years)  Radionuclide Half Life (years) H-3 1.24 E 01  Pm-147 2.62 E 00 C-14 5.73 E 03  Sm-146 1.03 E 08 Fe-55 2.70 E 00  Sm-151 9.00 E 01 Ni-59 7.50 E 04  Eu-152 1.33 E 01 Co-60 5.27 E 00  Eu-154 8.80 E 00 Ni-63 9.60 E 01  Eu-155 4.96 E 00 Sr-90 2.91 E 01  Pu-238 8.77 E 01 Mo-93 3.50 E 03  Pu-239/240 2.41 E 04 Nb-94 2.03 E 04  Pu-241 1.44 E 01 Tc-99 2.13 E 05  Np-237 2.14 E 06 Sb-125 2.77 E 00  Am-241 4.32 E 02 Cs-134 2.06 E 00  Am-243 7.38 E 03 Cs-137 3.00 E 01  Cm-244 1.81 E 01  2388 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-116  Table 2-13 Nominal Radiological Data - Structural Survey Units 2389 Survey HSA Class Radiation Levels    (mr/hr) Contamination Levels (dpm/100cm2) Major Systems & Components Comments Area ID Area Description Unit ID Unit Description Total Loose G/A Max G/A Max G/A Max 01100 Unit 1 CTMT 568 ft. el. 01101 Unit 1 Vessel Bio-Shield Class 1 (NOT SURVEYED - INACCESSIBLE)  Not Accessible  01102 A Loop I/S Missile Barrier Class 1 5 6 548K 2.2M 5200 10000 1A Reactor Coolant Pump    01103 B Loop I/S Missile Barrier Class 1 6 8 226K 500K 19000 40000 1B Reactor Coolant Pump    01104 C Loop I/S Missile Barrier Class 1 4 7 684K 2.3M 4400 10000 1C Reactor Coolant Pump    01105 D Loop I/S Missile Barrier Class 1 5 10 213K 450K 5000 10000 1D Reactor Coolant Pump    01106 A Loop O/S Missile Barrier Class 1 1.3 5 152K 400K 3000 5000    01107 B Loop O/S Missile Barrier Class 1 2 10 368K 1.5M 3000 1000    01108 C Loop O/S Missile Barrier Class 1 0.2 0.4 150K 490K 3000 1000    01109 D Loop O/S Missile Barrier Class 1 1 5 53K 145K 1000 1000    01110 543 ft. el. Incore Tunnel Class 1 5 10 (not taken) 21K 40K Incore Sump Under Reactor Vessel 01200 Unit 1 CTMT 592 ft. el. 01201 Cavity Area Class 1 100 187 (210 mrad) 500K 1M Unit 1 Reactor Cavity filled with water  01202 A Loop I/S Missile Barrier Class 1 11 20 (not taken) 1600 40K 1A Steam Generator (S/G)    01203 B Loop I/S Missile Barrier Class 1 16 20 (not taken) 1600 40K 1B Steam Generator (S/G)    01204 C Loop I/S Missile Barrier Class 1 11 22 (not taken) 1600 40K 1C Steam Generator (S/G)    01205 D Loop I/S Missile Barrier Class 1 11 18 (not taken) 1600 40K 1D Steam Generator (S/G)    01206 A Loop O/S Missile Barrier Class 1 0.6 1 84K 345K 1600 3000    01207 B Loop O/S Missile Barrier Class 1 0.2 0.3 49K 136K 1200 2000    01208 C Loop O/S Missile Barrier Class 1 0.4 1 83K 198K 1200 2000    01209 D Loop O/S Missile Barrier Class 1 0.2 0.2 21K 46K 2000 5000    01210 603 ft. Seal Table/Incore Drives Class 1 0.5 1.6 359K 780K 4200 5000  HRA Not Accessible 01300 Unit 1 CTMT 617 ft. el. 01301 Cavity Area Class 1 .06 1 32K 55K <1000 <1000 Unit 1 Reactor Upper Area Only  01302 "A" & "C" Loop Area Class 1 37 70 (not taken) <1000 <1000 1A & 1C S/G    01303 "B" & "D" Loop Area Class 1 13 18 (not taken) <1000 <1000 1B & 1D S/G, Pressurizer    01304 A Loop O/S Missile Barrier Class 1 0.5 0.7 23K 48K <1000 <1000    01305 B Loop O/S Missile Barrier Class 1 0.5 0.7 13K 28K 1500 2000    01306 C Loop O/S Missile Barrier Class 1 2 10 30K 80K 1000 1500    01307 D Loop O/S Missile Barrier Class 1 0.4 2 80K 300K 1000 1000  01400 Unit 1 CTMT Exterior 01401 Roof Class 2 (NOT SURVEYED - INACCESSIBLE)  Not surveyed - safety    01402 Exterior Walls Class 2 40 120 225 272 <300 <300  Accessible walls only 02100 Unit 2 CTMT 568 ft. el. 02101 Unit 2 Vessel Bio-Shield Class 1 (NOT SURVEYED - INACCESSIBLE)  Not Accessible  02102 A Loop I/S Missile Barrier Class 1 8 25 1.1M 2.5M 20K 60K 2A Reactor Coolant Pump    02103 B Loop I/S Missile Barrier Class 1 5 10 600K 2.1M 4000 12K 2B Reactor Coolant Pump    02104 C Loop I/S Missile Barrier Class 1 7 30 500K 1.3M 3500 6000 2C Reactor Coolant Pump    02105 D Loop I/S Missile Barrier Class 1 5 20 550K 1.4M 4000 10K 2D Reactor Coolant Pump    2390 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-117  Table 2-13 Nominal Radiological Data - Structural Survey Units (continued) 2391 Survey HSA Class Radiation Levels    (mr/hr) Contamination Levels (dpm/100cm2) Major Systems & Components Comments Area ID Area Description Unit ID Unit Description Total Loose G/A Max G/A Max G/A Max  02106 A Loop O/S Missile Barrier Class 1 0.1 1 90K 270K <1000 1000    02107 B Loop O/S Missile Barrier Class 1 0.3 10 80K 240K <1000 1000 Rx Coolant Drain Tank    02108 C Loop O/S Missile Barrier Class 1 0.1 0.2 19K 50K 1000 2000    02109 D Loop O/S Missile Barrier Class 1 0.1 0.1 120K 350K <1000 1000    02110 543 ft. el. Incore Tunnel Class 1 3 6 (not taken) 25K 900K Incore Sump Under Reactor Vessel 02200 Unit 2 CTMT 592 ft. el. 02201 Cavity Area Class 1 40 250 (not taken) (110 mrad) Unit 2 Reactor Cavity filled with water  02202 A Loop I/S Missile Barrier Class 1 3 6 14K 40K <1000 <1000 2A Steam Generator (S/G)    02203 B Loop I/S Missile Barrier Class 1 5 7.5 14K 20K <1000 <1000 2B Steam Generator (S/G)    02204 C Loop I/S Missile Barrier Class 1 3.2 6 12K 20K <1000 <1000 2C Steam Generator (S/G)    02205 D Loop I/S Missile Barrier Class 1 4 7.5 24K 80K <1000 <1000 2D Steam Generator (S/G)    02206 A Loop O/S Missile Barrier Class 1 0.3 0.3 53K 200K <300 531    02207 B Loop O/S Missile Barrier Class 1 0.2 0.2 9000 40K <300 506    02208 C Loop O/S Missile Barrier Class 1 0.3 0.3 3000 9000 <300 1000    02209 D Loop O/S Missile Barrier Class 1 0.3 0.6 900 2000 <300 367    02210 603 ft. Seal Table/Incore Drives Class 1 2.6 6 62K 200K 2000 5000  02300 Unit 2 CTMT 617 ft. el. 02301 Cavity Area Class 1 40 250 (not taken) (110 mrad) Unit 2 Reactor Cavity filled with water  02302 "A" & "C" Loop Area Class 1 0.8 1 4500 7000 2000 5000 2A & 2C S/G    02303 "B" & "D" Loop Area Class 1 1.4 4 2000 3000 <1000 <1000 2B & 2D S/G, Pressurizer    02304 A Loop O/S Missile Barrier Class 1 0.5 0.7 1000 4000 <1000 1000    02305 B Loop O/S Missile Barrier Class 1 0.7 1.6 10000 30000 1000 2000    02306 C Loop O/S Missile Barrier Class 1 0.5 2.2 2000 5000 <1000 <1000    02307 D Loop O/S Missile Barrier Class 1 10 24 10000 30000 <1000 <1000  02400 Unit 2 CTMT Exterior 02401 Roof Class 2 (NOT SURVEYED - INACCESSIBLE)  Not surveyed - safety  02402 Exterior Walls Class 2 11 15 764 764 <300 <300  Accessible walls only 03100 Fuel Handling Bldg. 592 ft. el. 03101 Trackway/Cars Shed/Open Area Class 1 0.2 0.2 7900 37000 <300 <300    03102 Spent Fuel Pit Heat Exchangers Class 1 0.3 0.6 <634 1790 <300 <300    03103 Spent Fuel Pit Pump Rooms Class 1 0.3 0.6 8700 34000 <300 <300    03104 Decon Pit Class 1 5.7 25 (not taken) 3000 10000  Hot Work during Survey 03200 Fuel Handling Bldg. 617 ft. el. 03201 New Fuel Storage & Mezzanine Class 1 0.2 0.4 1254 2276 <300 <300    03202 Spent Fuel Pool Class 1 <0.2 <0.2 2479 5304 <300 <300 Spent Nuclear Fuel Filled with water  03203 Cross-town & SPING Gallery Class 1 <0.2 0.2 8591 29039 <300 569  03300 Fuel Bldg. Exterior & Roof 03301 Roof Class 2 0.022 0.022 2057 2210 <300 <300    03302 Exterior Walls Class 2 11 14 613 660 <300 <300  04100 Radwaste Bldg. 579 ft. el. 04101 Crystallizer Class 1 0.3 0.5 17K 96K 306 2709  04200 Radwaste Bldg. 592 ft. el. 04201 Dry Active Waste Storage Area Class 1 10 50 (floor covered) <300 <300 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-118  Table 2-13 Nominal Radiological Data - Structural Survey Units (continued) 2392 Survey HSA Class Radiation Levels    (mr/hr) Contamination Levels (dpm/100cm2) Major Systems & Components Comments Area ID Area Description Unit ID Unit Description Total Loose G/A Max G/A Max G/A Max  04202 Drum Fill Area Class 1 4 40 20K 178K <300 <300    04203 Radwaste Annex Truck Loading Class 1 1 4.1 5400 22K <300 426  04300 Radwaste Bldg. Exterior & Roof 04301 Roof Class 2 0.34 0.36 1429 1581 <300 <300    04302 Exterior Walls Class 2 300 600 513 597 <300 <300  Max DR @ RW Truckbay 05100 Auxiliary Bldg. 542 ft. el. 05101 1A RHR Pump Room Class 1 3 10 64K 35K <1000 <1000 1A RHR Pump    05102 1B RHR Pump Room Class 1 2 5 16K 35K <1000 <1000 1B RHR Pump    05103 2A RHR Pump Room Class 1 0.7 1.2 101K 800K <1000 3000 2A RHR Pump    05104 2B RHR Pump Room Class 1 0.7 1 21K 80K <1000 <1000 2B RHR Pump    05105 Unit 1 Pipe Chase Class 1 5 15 60K 240K <1000 3000    05106 Unit 2 Pipe Chase Class 1 2 5 300K 1.7M 8000 50000    05107 Hold Up Tanks Cubicle Class 1 (ACCESSED FROM THE 579 FT. ELEVATION) Hold Up Tanks    05108 Central Area Class 1 <0.2 0.2 3726 31.0K <300 1000    05109 South Area Class 1 0.2 1 1110 3400 <300 <300    05110 North Area Class 1 0.2 0.6 5018 38K <300 <300    05111 West Area Class 1 0.2 0.6 4447 20K <300 <300    05112 Gas Decay Tanks Class 1 <0.2 <0.2 5000 1 mrad <300 <300    05113 Unit 1 EDCT Class 1 1 1.5 120K 13 mrad <300 <300 Equip Drain Collection Tk    05114 Unit 2 EDCT Class 1 0.4 0.5 38K 6 mrad <300 <300 Equip Drain Collection Tk    05115 HUT Recirc & BAE Feed Pmps Class 1 0.5 1 (270 mrad) 50K 300K  Hi Contamination Drains  05116 EDT and Pumps Class 1 10 20 15K 70K <1000 1000 Equipment Drain Tank    05117 Sump A Class 1 0.3 0.4 36K 140K 1000 1000    05118 Sump B Class 1 1.7 2 66K 150K 2000 4000  05200 Auxiliary Bldg. 560 ft. el. 05201 Unit 1A Safety Injection Pump Class 1 0.75 1 23K 200K <300 1696    05202 Unit 2A Safety Injection Pump Class 1 0.4 0.4 45K 400K <1000 3000    05203 Unit 1B Safety Injection Pump Class 1 0.5 0.5 2000 42K <300 <300    05204 Unit 2B Safety Injection Pump Class 1 0.4 0.4 41K 400K <1000 2000    05205 Unit 1A RHR Heat Exchanger Class 1 1.8 5 2000 4000 <300 <300 1A RHR Heat Exchanger    05206 Unit 2A RHR Heat Exchanger Class 1 0.8 1.3 2000 4000 <300 <300 2A RHR Heat Exchanger    05207 Unit 1B RHR Heat Exchanger Class 1 1.9 5 2000 3000 <300 <300 1B RHR Heat Exchanger    05208 Unit 2B RHR Heat Exchanger Class 1 0.5 1 1000 2000 <300 <300 2B RHR Heat Exchanger    05209 Unit 1 Containment Spray Pump Class 1 0.4 1.2 11K 60K <300 <300    05210 Unit 2 Containment Spray Pump Class 1 0.3 0.5 84K 222K <300 607    05211 South Area Class 1 0.6 1 17K 61K <300 417 Laundry Drain Tanks    05212 Central Area Class 1 0.3 0.4 9000 15K <1000 15000 Component Cooling Pmps    05213 North Area Class 1 0.3 0.5 7013 61K <300 <300    05214 West Area Class 1 0.3 0.5 26K 227K <300 455 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-119  Table 2-13 Nominal Radiological Data - Structural Survey Units (continued) 2393 Survey HSA Class Radiation Levels    (mr/hr) Contamination Levels (dpm/100cm2) Major Systems & Components Comments Area ID Area Description Unit ID Unit Description Total Loose G/A Max G/A Max G/A Max  05215 Equipment Drain Tank Class 1 4 10 47K 170K <300 1329    05216 Chemical Drain Tank Class 1 16 40 124K 700K <1000 250K  Pump Base contaminated  05217 Unit 1 Vertical Pipe Chase Class 1 (ACCESSED FROM THE 579 FT. ELEVATION)    05218 Unit 2 Vertical Pipe Chase Class 1 (ACCESSED FROM THE 579 FT. ELEVATION)    05219 Blowdown Heat Exchangers Class 1 0.1 0.1 <690 2617 <300 <300    05220 Waste Gas Compressor Area Class 1 0.1 0.1 <690 8413 <300 <300    05221 Unit 1 RHR HE Pipe Chase Class 1 30 60 (20 mrad) 12K 30K  Boric Acid on Floor  05222 Unit 2 RHR HE Pipe Chase Class 1 5 5 (12 mrad) 7000 18K  05300 Auxiliary Bldg. 579 ft. el. 05301 Unit 1A Charging Pump Class 1 0.4 0.5 1902 3606 <300 <300 1A Centrifugal Charging    05302 Unit 2A Charging Pump Class 1 0.2 0.2 12K 50K <300 <300 2A Centrifugal Charging    05303 Unit 1B Charging Pump Class 1 0.4 0.7 32K 165K <300 <300 1B Centrifugal Charging    05304 Unit 2B Charging Pump Class 1 0.4 0.4 230K 1.3M <300 <300 2B Centrifugal Charging    05305 Unit 1C Charging Pump Class 1 1.3 4 70K 342K <300 <300 1C Reciprocating    05306 Unit 2C Charging Pump Class 1 0.2 0.3 74K 255K <300 784 2C Reciprocating    05307 Unit 1 RWST Class 1 (NOT SURVEYED - INACCESSIBLE) Refueling Wtr Storage Tk    05308 Unit 2 RWST Class 1 (NOT SURVEYED - INACCESSIBLE) Refueling Wtr Storage Tk    05309 South Area Class 1 0.3 0.7 13K 45K <300 <300    05310 Central Area Class 1 1 2 760K 2.9M 560 1860    05311 North Area Class 1 0.2 0.5 17.5K 81K 520 1392    05312 West Area Class 1 <0.2 0.2 760 1280 <300 <300    05313 Unit 1 Horizontal Pipe Chase Class 1 1.6 5 326K 2.5M 4000 30K    05314 Unit 2 Horizontal Pipe Chase Class 1 0.4 0.5 345K 1.6M <1000 <1000    05315 #1 Hold Up Tank Class 1 10 20 (250 mrad) 50K 150K    05316 #0 Hold Up Tank Class 1 5 5 (160 mrad) 50K 110K    05317 #2 Hold Up Tank Class 1 5 40 (125 mrad) 50K 150K    05318 Anion/Cation Valve Aisle Class 1 <0.2 0.2 1380 5700 <300 <300    05319 Unit 1 Vertical Pipe Chase Class 1 5 20 (not taken) 50K 500K    05320 Unit 2 Vertical Pipe Chase Class 1 5 20 (not taken) 4000 20K  05400 Auxiliary Bldg. 592 ft. el. 05401 Unit 1 Letdown Heat Exchanger Class 1 20 40 380K 1.4M 4000 10K    05402 Unit 2 Letdown Heat Exchanger Class 1 1 2 15K 136K <1000 <1000    05403 Unit 1 Seal Water HE Class 1 5 15 48K 220K <300 556 Seal Wtr Heat Exchanger    05404 Unit 2 Seal Water HE Class 1 0.4 0.8 6680 24K <300 1278 Seal Wtr Heat Exchanger    05405 Unit 2 Future Diesel Generator Class 1 <0.2 <0.2 <300 320 <300 <300    05406 Primary Sample Room Class 1 0.25 0.3 19K 60K 10K 30K    05407 Calibration Facility Class 1 0.5 0.6 <300 674 <300 <300    05408 South Area Class 1 0.2 0.3 710 1900 <300 <300 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-120  Table 2-13 Nominal Radiological Data - Structural Survey Units (continued) 2394 Survey HSA Class Radiation Levels    (mr/hr) Contamination Levels (dpm/100cm2) Major Systems & Components Comments Area ID Area Description Unit ID Unit Description Total Loose G/A Max G/A Max G/A Max  05409 Central Area Class 1 0.2 0.4 144K 5.6M 340 556    05410 North Area Class 1 0.2 0.3 463 696 <300 <300    05411 West Area Class 1 0.2 0.5 8000 30K <300 <300    05412 Unit 1 Vertical Pipe Chase Class 1 (ACCESSED FROM THE 579 FT. ELEVATION)    05413 Unit 2 Vertical Pipe Chase Class 1 (ACCESSED FROM THE 579 FT. ELEVATION)    05414 Unit 1 BAT and Pumps Class 1 0.5 1.5 <300 <300 <300 <300    05415 Unit 2 BAT and Pumps Class 1 <0.2 <0.2 6500 15.9K <300 <300  05500 Auxiliary Bldg. 617 ft. el. 05501 Unit 1 Volume Control Tank Class 1 9 15 153K 740K <300 632    05502 Unit 2 Volume Control Tank Class 1 1 2 3800 19K <300 <300    05503 Unit 1 Pipe Chase Class 1 0.6 2 3629 19K <300 1075 U1 CTMT Hatch    05504 Unit 2 Chase Class 1 0.2 0.5 5600 20K <300 <300 U2 CTMT Hatch    05505 Radiation Protection Offices Class 1 0.013 0.06 953 5319 <300 <300    05506 Unit 1 CTMT Purge Room Class 1 <0.2 0.3 60 300 <300 <300 CTMT Purge Air Equip    05507 Unit 2 CTMT Purge Room Class 1 10 40 360 1000 <300 <300 CTMT Purge Air Equip    05508 Tool Crib Class 1 0.3 0.3 8911 47K <300 <300    05509 Waste Evaporator Monitor Tank Class 1 0.3 4 92K 117K <300 734    05510 Radwaste Evaporator Class 1 0.6 2 69K 195K <300 367  Areas not accessible  05511 Spent Resin Storage Area Class 1 (NOT SURVEYED - LOCKED HI RAD AREA)  Posted LHRA >15 R/hr  05512 Laboratory Class 1 0.01 0.014 444 1213 <300 <300    05513 West Area Class 1 <0.2 <0.2 8300 26K <300 <300    05514 East Area Class 1 0.3 1 552 1204 <300 <300  05600 Auxiliary Bldg. 630 ft. el. 05601 Unit 1 Cable Spreading Room Class 1 0.007 0.008 905 1031 <300 <300    05602 Unit 2 Cable Spreading Room Class 1 0.007 0.008 760 1031 <300 <300    05603 Unit 1 Cable Penetration Room Class 1 0.006 0.007 763 849 <300 <300    05604 Unit 2 Cable Penetration Room Class 1 0.006 0.007 530 731 <300 <300  05700 Auxiliary Bldg. 642 ft. el. 05701 642 ft. elevation Class 1 0.2 0.3 <658 <658 <300 <300  05800 Auxiliary Bldg. 654 ft. el. 05801 654 ft. elevation Class 1 0.2 0.3 <658 989 <300 <300 Vent Filter Banks  05900 Auxiliary Bldg. Exterior & Roof 05901 Roof Class 2 0.028 0.035 1886 2114 <300 <300    05902 Exterior Walls Class 2 600 300 764 764 <300 <300  Max DR @ RW Truckbay 06100 Turbine Bldg. 560 ft. el. 06101 Oil Room Class 2 0.006 0.007 <514 699 <300 <300    06102 South Area Class 2 0.005 0.006 <366 1383 <300 <300    06103 Central Area Class 2 0.008 0.015 3700 27K <300 <300    06104 North Area Class 2 0.005 0.006 1752 7257 <300 <300  06200 Turbine Bldg. 570 ft. el. 06201 1B Diesel Fuel Oil Storage Class 2 0.005 0.006 <528 787 <300 <300    06202 2B Diesel Fuel Oil Storage Class 2 0.006 0.007 <539 721 <300 <300    06203 1A Diesel Fuel Oil Storage  Class 2 0.005 0.005 <465 915 <300 <300 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-121  Table 2-13 Nominal Radiological Data - Structural Survey Units (continued) 2395 Survey HSA Class Radiation Levels    (mr/hr) Contamination Levels (dpm/100cm2) Major Systems & Components Comments Area ID Area Description Unit ID Unit Description Total Loose G/A Max G/A Max G/A Max  06204 2A Diesel Fuel Oil Storage  Class 2 0.006 0.007 <539 <539 <300 <300    06205 0A Diesel Fuel Oil Storage  Class 2 0.004 0.005 <521 <521 <300 <300    06206 Unit 2 Future Fuel Oil Storage Class 2 0.007 0.008 <606 664 <300 <300    06207 Unit 1 Steam Pipe Tunnel Class 2 0.008 0.04 17K 104K <300 <300  Reclassified to Class 1  06208 Unit 2 Steam Pipe Tunnel Class 2 0.006 0.01 1500 6200 <300 <300  Reclassified to Class 1 06300 Turbine Bldg. 592 ft. el. 06301 Unit 1 Diesel Generator 1A Class 2 0.004 0.004 <433 752 <16 <16    06302 Unit 2 Diesel Generator 1B Class 2 0.004 0.005 <354 638 <16 <16    06303 Unit 1 Diesel Generator 0 Class 2 0.005 0.007 <302 505 <16 <16    06304 Unit 2 Diesel Generator 2A Class 2 0.003 0.004 <353 641 <16 <16    06305 Unit 1 Diesel Generator 2B Class 2 0.004 0.004 <575 <575 <16 <16    06306 Battery and Charger Room Class 2 0.005 0.005 <460 807 <16 <16    06307 Technical Support Center Class 2 0.006 0.006 <442 <442 <16 <16    06308 Secondary Sample Room Class 2 0.007 0.011 <312 819 <300 <300    06309 Auxiliary Heating Boiler Class 2 0.006 0.008 3233 18K <300 <300    06310 South Area Class 2 0.009 0.015 <510 648 <16 <16    06311 Central Area Class 2 0.005 0.008 <670 1048 <300 <300    06312 North Area Class 2 0.006 0.007 <455 1028 <16 <16  06400 Turbine Bldg. 609 ft. el. 06401 609 ft. elevation Class 2 0.004 0.005 <353 589 <16 <16  06500 Turbine Bldg. 617 ft. el. 06501 Switchgear Rooms 17, 18 &19 Class 2 0.006 0.008 <522 738 <16 <16    06502 Switchgear Rooms 27, 28 &29 Class 2 0.006 0.007 <654 928 <16 <16    06503 Air Conditioning Equipment Rm Class 2 0.016 0.025 <553 682 <16 <16    06504 QA Records Area Class 2 0.005 0.005 <539 862 <17 <17    06505 South Area Class 2 0.005 0.008 <438 785 <16 <16    06506 Central Area Class 2 0.005 0.006 <596 1028 <16 <16    06507 North Area Class 2 0.005 0.007 <595 983 <16 <16  06600 Turbine Bldg. 625 ft. el. 06601 625 ft. elevation Class 2 0.005 0.005 661 862 <16 <16  06700 Turbine Bldg. 642 ft. el. 06701 Unit 1 Switchgear & Rod Drive  Class 2 0.007 0.009 <690 1171 <16 <16    06702 Unit 2 Switchgear & Rod Drive  Class 2 0.005 0.005 <612 873 <16 <16    06703 Main Control Room Complex Class 2 0.005 0.006 <476 <476 <16 <16    06704 Control Room Annex South Class 2 0.004 0.005 <353 <589 <16 <16    06705 Control Room Annex North Class 2 0.004 0.005 <393 1048 <16 <16    06706 Unit 1 Aux Electric Equipment Class 2 0.005 0.006 <416 752 <16 <16    06707 Unit 2 Aux Electric Equipment Class 2 0.005 0.005 <429 674 <16 <16    06708 South Area Class 2 0.007 0.01 <334 600 <16 <16    06709 Central Area Class 2 0.005 0.005 <448 796 <16 <16    06710 North Area Class 2 0.008 0.01 <410 641 <16 <16 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-122  Table 2-13 Nominal Radiological Data - Structural Survey Units (continued) 2396 Survey HSA Class Radiation Levels    (mr/hr) Contamination Levels (dpm/100cm2) Major Systems & Components Comments Area ID Area Description Unit ID Unit Description Total Loose G/A Max G/A Max G/A Max 06800 Turbine Bldg. 656 ft. el. 06801 656 ft. elevation Class 2 0.005 0.006 <507 848 <16 <16  06900 Turbine Bldg. Exterior & Roof 06901 Roof Class 2 0.015 0.016 2490 2790 <300 <300    06902 Exterior Walls Class 2 10 30 <300 <300 <300 <300  Max DR @ Truckbay 07100 Service Bldg. 592 ft. el. 07101 East Class 2 0.008 0.012 <596 789 <17 <17    07102 West  Class 2 0.009 0.013 312 705 <16 <16  07100 Service Bldg. 608 ft. el. 07201 East Class 2 0.008 0.012 <716 804 <16 <16    07202 West  Class 2 0.009 0.012 1867 473 <16 <16  07100 Service Bldg. 624 ft. el. 07301 East Class 2 0.008 0.012 <716 792 <17 <17    07302 West  Class 2 0.013 0.01 222 1067 <17 <17  07100 Service Bldg. 636 ft. el. 07401 East Class 2 0.008 0.012 872 2846 <300 <300    07402 West  Class 2 0.011 0.012 160 286 <16 <16  07100 Service Bldg. 648 ft. el. 07501 East Class 2 0.007 0.01 181 343 <16 <16  07600 Service Bldg. 660 ft. el. 07601 East Class 2 0.009 0.013 184 457 <16 <16  07700 Service Bldg. Exterior & Roof 07701 East Roof Class 2 0.017 0.018 890 1000 <300 <300    07702 West Roof Class 2 0.044 0.046 2267 2438 <300 <300    07703 Exterior Walls Class 2 20 30 319 461 <300 <300  Elevated DR waste  08100 Crib House 559 ft. el. 08101 552 ft. elevation Class 2 0.006 0.007 <615 849 <300 <300 Circ Water Pumps 1990 -552 ft flooded 08200 Crib House 594 ft. el. 08201 594 ft. elevation Class 2 0.006 0.007 <702 <702 <300 <300 Fire Pumps, Pmp Motors  08300 Crib House Exterior & Roof 08301 Roof Class 2 0.006 0.007 2412 2504 <300 <300    08302 Exterior Walls Class 2 0.006 0.007 <615 658 <300 <300  09100 Waste Water Treatment Facility 09101 1st Floor Class 2 0.008 0.025 <683 <683 <300 <300 Pits & drying area HSA SU ID# 09101  09102 2nd Floor Class 2 0.008 0.025 <683 <683 <300 <300  HSA SU ID# 09201  09103 Roof Class 2 0.006 0.007 <677 <677 <300 <300  HSA SU ID# 09301  09104 Exterior Walls Class 2 0.008 0.025 <683 <683 <300 <300    09200 North Valve House 09201 1st Floor Class 2 0.006 0.007 1049 1826 <300 <300  HSA SU ID# 09102  09202 Roof Class 2 0.006 0.007 2803 2861 <300 <300  HSA SU ID# 09202  09203 Exterior Walls Class 2 0.006 0.007 737 1266 <300 <300  HSA SU ID# 09302 09300 North Chlor/Dechlor Bldg. 09301 1st Floor Class 2 0.004 0.005 <606 <606 <300 <300  HSA SU ID# 09103  09302 Roof Class 2 0.006 0.007 1165 1276 <300 <300  HSA SU ID# 09203  09303 Exterior Walls Class 2 0.004 0.005 <606 <606 <300 <300  09400 Warehouse/Maint. Training Ctr 09401 1st Floor Class 3 0.006 0.01 <554 1240 <16 <16    09402 Roof Class 3 0.006 0.007 <623 <623 <300 <300    09403 Exterior Walls Class 3 0.006 0.007 <623 <623 <300 <300  09500 IRSF 09501 1st Floor Class 2 0.006 0.007 <680 1964 <300 <300    09502 Mezzanine Class 2 0.006 0.007 <554 575 <300 <300    09503 Roof Class 2 0.006 0.007 927 962 <300 <300 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-123  Table 2-13 Nominal Radiological Data - Structural Survey Units (continued) 2397 Survey HSA Class Radiation Levels    (mr/hr) Contamination Levels (dpm/100cm2) Major Systems & Components Comments Area ID Area Description Unit ID Unit Description Total Loose G/A Max G/A Max G/A Max  09504 Exterior Walls Class 2 0.006 0.007 <554 853 <300 <300  09600 Fire Training Building 09601 1st Floor Class 3 <0.1 <0.1 <607 1306 <300 <300  Fire Pit - 20    09602 Roof Class 3 0.006 0.007 888 1011 <300 <300    09603 Exterior Walls Class 3 <0.1 <0.1 <607 <607 <300 <300  09700 Contractor Break Building 09701 1st Floor Class 3 0.006 0.007 <642 667 <300 <300  HSA SU ID# 09107  09702 Roof Class 3 0.006 0.007 <677 <677 <300 <300  HSA SU ID# 09207  09702 Roof Class 3 0.006 0.007 <677 <677 <300 <300  HSA SU ID# 09207  09703 Exterior Walls Class 3 0.006 0.007 <642 <642 <300 <300  09800 East Training Center 09801 1st Floor Class 3 0.006 0.007 <650 1110 <300 <300  Old N-GET Bldg  09802 Roof Class 3 0.006 0.007 652 864 <300 <300    09803 Exterior Walls Class 3 0.006 0.007 <650 933 <300 <300  09900 In-Processing Building 09901 1st Floor Class 3 0.008 1.3 <717 <717 <300 <300 Laboratory (sources) Also known as ENC Bldg  09902 2nd Floor Class 3 0.006 0.008 <717 <717 <300 <300    09903 Roof Class 3 0.006 0.007 864 953 <300 <300    09904 Exterior Walls Class 3 0.006 0.007 <717 <717 <300 <300  09010 Station Construction Building 09011 1st Floor Class 3 0.006 0.006 <569 1188 <300 <300    09012 Roof Class 3 0.006 0.007 <623 714 <300 <300    09013 Exterior Walls Class 3 0.006 0.006 <569 <569 <300 <300  09030 Security Offices 09031 1st Floor Class 2 0.04 0.07 <768 1011 <300 <300  HSA SU ID# 09116  09032 Roof Class 2 0.048 0.048 1495 1649 <300 <300  HSA SU ID# 09216  09033 Exterior Walls Class 2 0.04 0.07 <768 <768 <300 <300  09040 Gate House 09041 1st Floor Class 2 0.15 0.5 <749 2209 <300 <300  HSA SU ID# 09117  09042 2nd Floor Class 2 0.15 0.5 <749 <749 <300 <300  HSA SU ID# 09217  09043 Roof Class 2 0.041 0.042 894 1128 <300 <300  HSA SU ID# 09317  09044 Exterior Walls Class 2 0.15 0.5 <749 <749 <300 <300  09050 North Warehouse 09051 1st Floor Class 3 0.006 0.007 <663 697 <663 <663    09052 Roof Class 3 0.006 0.007 <623 <623 <300 <300    09053 Exterior Walls Class 3 0.006 0.007 <623 <623 <300 <300  09060 South Warehouse 09061 1st Floor Class 3 0.006 0.007 <623 137 <300 <300  RAM stored in warehouse  09062 Roof Class 3 0.006 0.007 652 744 <300 <300    09063 Exterior Walls Class 3 0.006 0.007 <609 <609 <300 <300  09070 South Valve House 09071 1st Floor Class 2 0.006 0.007 716 1149 <300 <300  HSA SU ID# 09121  09072 Roof Class 2 0.006 0.007 2856 3074 <300 <300  HSA SU ID# 09221  09073 Exterior Walls Class 2 0.006 0.007 <586 943 <300 <300  09080 South Chlor/Dechlor Bldg. 09080 1st Floor Class 2 0.004 0.005 <492 156 <300 <300    09081 Roof Class 2 0.006 0.007 1846 1926 <300 <300 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-124  Table 2-13 Nominal Radiological Data - Structural Survey Units (continued) 2398 Survey HSA Class Radiation Levels    (mr/hr) Contamination Levels (dpm/100cm2) Major Systems & Components Comments Area ID Area Description Unit ID Unit Description Total Loose G/A Max G/A Max G/A Max  09082 Exterior Walls Class 2 0.004 0.005 <492 <492 <300 <300  09210 Temp Rad Waste Liner Storage 09211 1st Floor Class 3 0.006 0.007 630 2211 <300 <300 Concrete Liners Not included in HSA  09212 Roof Class 3 0.006 0.007 2266 2558 <300 <300  Not included in HSA  09213 Exterior Walls Class 3 0.006 0.007 (not taken) <300 <300  Not included in HSA 09220 Warehouse #13 09221 1st Floor Class 3 0.004 0.005 <672 <672 <300 <300 ISFSI Warehouse Not included in HSA  09222 Roof Class 3 0.006 0.007 <492 <492 <300 <300  Not included in HSA  09223 Exterior Walls Class 3 0.004 0.005 <672 <672 <300 <300  Not included in HSA  2399 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-125  Table 2-14 Unit 1 Containment 568 Foot Elevation Concrete Core Sample Analysis Summary 2400 Location Sample ID# Core Depth (inches) Co-60 Cs-137 Surface Activity (a) Avg. Subsurface Activity (b) Surface Activity (a) Avg. Subsurface Activity (b) (pC/g) (pC/g) (pC/g) (pC/g) "A" Loop I/S Missile Barrier B101102-CJFCCV-001 1.5 9.69E+01 1.40E+01 3.46E+04 4.76E+03 "A" Loop I/S Missile Barrier B101102-CJFCCV-002 5.0 1.91E+02 1.90E+01 4.04E+05 1.65E+04 "B" Loop I/S Missile Barrier B101103-CJFCCV-001 4.0 2.18E+02 2.55E+01 3.05E+05 3.10E+04 "B" Loop I/S Missile Barrier B101103-CJFCCV-002 4.5 7.97E+03 3.64E+02 9.86E+04 1.00E+04 "C" Loop I/S Missile Barrier B101104-CJFCCV-001 4.5 1.25E+02 1.69E+01 4.93E+05 6.71E+04 "C" Loop I/S Missile Barrier B101104-CJFCCV-002 4.0 4.63E+02 2.86E+01 4.40E+05 2.09E+04 "D" Loop I/S Missile Barrier B101105-CJFCCV-001 3.5 3.66E+04 6.54E+03 2.56E+03 2.09E+02 "D" Loop I/S Missile Barrier B101105-CJFCCV-002 5.0 1.04E+03 5.88E+01 3.07E+04 5.79E+03 "A" Loop O/S Missile Barrier B101106-CJFCCV-001 3.0 1.84E+01 1.20E+00 1.39E+03 6.42E+01 "A" Loop O/S Missile Barrier B101106-CJFCCV-002 1.0 2.66E+01 6.16E+00 8.03E+01 1.23E+01 "B" Loop O/S Missile Barrier B101107-CJFCCV-001 1.0 2.04E+01 3.36E+00 3.68E+02 5.21E+01 "B" Loop O/S Missile Barrier B101107-CJFCCV-002 1.0 1.92E+01 3.56E+00 2.41E+02 3.40E+01 "C" Loop O/S Missile Barrier B101108-CJFCCV-001 2.5 1.50E+01 2.10E+00 8.70E+03 4.71E+02 "C" Loop O/S Missile Barrier B101108-CJFCCV-002 1.5 6.16E+01 1.16E+01 6.08E+04 8.50E+03 "D" Loop O/S Missile Barrier B101109-CJFCCV-001 1.0 1.02E+01 1.93E+00 1.94E+02 3.21E+01 "D" Loop O/S Missile Barrier B101109-CJFCCV-002 1.0 1.18E+02 1.84E+01 7.32E+03 9.08E+02 (a) Represents surface activity of floor following removal of loose contamination 2401 (b) Represents average of activity over entire depth of core sample minus the surface activity 2402 (c) Italicized values indicate MDC value. 2403 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-126  Table 2-15 Unit 1 Bio-Shield Concrete Core Samples Gamma Spectroscopy Analysis 2404 Sample ID Sample Date Puck Depth Co-60 a Cs-137 a Eu-152 a Eu-154 a (inches) (pCi/g) (pCi/g) (pCi/g) (pCi/g) B101101-CJWCCV-001 - 1st Core Section 01/10/13 1 11.5 9.15E-02 1.33E-01 2.26E-01 1.22E-01 12 1.46E-01 1.06E-01 1.76E-01 1.42E-01 B101101-CJWCCV-001 - 2nd Core Section 01/17/13 2 23.5 1.85E-01 1.89E-01 1.80E-01 1.54E-01 24 1.43E-01 1.67E-01 2.40E-01 1.09E-01 B101101-CJWCCV-001 - 2nd Core Section 01/17/13 3 35.5 1.28E-01 1.02E-01 2.27E-01 1.82E-01 36 8.28E-02 1.02E-01 2.06E-01 1.76E-01 B101101-CJWCCV-001 - 2nd Core Section 01/17/13 4 47.5 2.76E-01 1.95E-01 1.53E+00 2.48E-01 48 2.67E-01 1.49E-01 1.25E+00 2.29E-01 B101101-CJWCCV-001 - 3rd Core Section 02/21/13 5 59.5 1.94E+00 2.77E-01 2.04E+01 8.55E-01 60 1.94E+00 2.77E-01 2.04E+01 8.95E-01 B101101-CJWCCV-001 - Rebar Metal Piece 02/21/13 Rebar 63 1.76E+01 1.92E-01 4.10E-01 2.53E-01 B101101-CJWCCV-001 - 3rd Core Section 02/21/13 6 71.5 1.50E+01 4.22E-01 1.55E+02 6.49E+00 72 1.52E+01 4.12E-01 1.63E+02 7.04E+00 a Bold values indicate concentration greater than MDC. Italicized values indicate MDC value. 2405 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-127  Table 2-16 Unit 2 Containment 568 Foot Elevation Concrete Core Sample Analysis Summary 2406 Location Sample ID# Core Depth (inches) Co-60 Cs-137 Surface Activity (a) Avg. Subsurface Activity (b) Surface Activity (a) Avg. Subsurface Activity (b) (pC/g) (pC/g) (pC/g) (pC/g) "A" Loop I/S Missile Barrier B102102-CJFCCV-001 3.0 7.56E+02 1.78E+02 1.10E+05 1.66E+04 "A" Loop I/S Missile Barrier B102102-CJFCCV-002 6.0 9.40E+04 1.65E+03 1.75E+03 5.65E+01 "B" Loop I/S Missile Barrier B102103-CJFCCV-001 5.5 5.64E+02 2.31E+01 4.57E+04 1.57E+03 "B" Loop I/S Missile Barrier B102103-CJFCCV-002 4.0 1.91E+02 8.11E+00 6.39E+03 2.27E+02 "C" Loop I/S Missile Barrier B102104-CJFCCV-001 5.5 3.55E+02 1.22E+01 1.94E+04 6.59E+02 "C" Loop I/S Missile Barrier B102104-CJFCCV-002 1.5 1.40E+02 4.05E+00 1.45E+04 1.73E+02 "D" Loop I/S Missile Barrier B102105-CJFCCV-001 4.5 1.11E+03 4.39E+01 2.88E+03 8.77E+01 "D" Loop I/S Missile Barrier B102105-CJFCCV-002 4.0 1.11E+02 4.05E+00 1.25E+04 3.82E+02 "A" Loop O/S Missile Barrier B102106-CJFCCV-001 5.0 5.59E+01 1.75E+00 8.13E+02 1.70E+01 "A" Loop O/S Missile Barrier B102106-CJFCCV-002 1.5 2.71E+01 1.20E+01 1.40E+04 2.93E+03 "B" Loop O/S Missile Barrier B102107-CJFCCV-001 4.5 6.61E+01 8.16E+00 4.10E+03 7.06E+00 "B" Loop O/S Missile Barrier B102107-CJFCCV-002 1.5 3.57E+01 3.86E+00 2.09E+03 1.82E+02 "C" Loop O/S Missile Barrier B102108-CJFCCV-001 2.0 1.30E+01 1.17E+00 2.55E+02 1.77E+01 "C" Loop O/S Missile Barrier B102108-CJFCCV-002 2.0 1.89E+01 1.64E+00 3.97E+02 2.64E+01 "D" Loop O/S Missile Barrier B102109-CJFCCV-001 4.0 1.13E+03 4.61E+01 6.07E+03 2.15E+02 "D" Loop O/S Missile Barrier B102109-CJFCCV-002 2.5 8.62E+01 7.46E+00 4.65E+03 3.09E+02 (a) Represents surface activity of floor following removal of loose contamination 2407 (b) Represents average of activity over entire depth of core sample minus the surface activity  2408 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-128  Table 2-17 Unit 1 Containment 541 Foot Elevation Concrete Core Sample Analysis Summary 2409 Location Sample ID# Core Depth (inches) Co-60 Cs-137 Eu-152 Eu-154 Surface Activity (a) Avg. Sub-surface Activity (b) Surface Activity (a) Avg. Sub-surface Activity (b) Surface Activity (a) Avg. Sub-surface Activity (b) Surface Activity (a) Avg. Sub-surface Activity (b) (pC/g) (pC/g) (pC/g) (pC/g) (pC/g) (pC/g) (pC/g) (pC/g) Incore Tunnel Floor B101110-CJFCCV-001 15.5 2.79E+01 5.97E+00 5.27E+01 4.07E+00 6.97E+01 3.34E+01 5.23E+00 1.86E+00 Incore Tunnel Floor B101110-CJFCCV-002 4.0 3.48E+02 5.91E+01 2.71E+03 3.28E+02 6.30E+01 9.15E+01 4.35E+00 5.72E+00 Incore Tunnel Wall B101110-CJWCCV-003 3.5 1.12E+01 7.64E+00 3.72E+01 2.61E+00 5.60E+01 6.67E+01 4.19E+00 3.73E+00 (a) Represents surface activity of floor following removal of loose contamination 2410 (b) Represents average of activity over entire depth of core sample minus the surface activity  2411 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-129  Table 2-18 Unit 2 Containment 541 Foot Elevation Concrete Core Sample Analysis Summary 2412 Location Sample ID# Core Depth (inches) Co-60 Cs-137 Eu-152 Eu-154 Surface Activity (a) Avg. Sub-surface Activity (b) Surface Activity (a) Avg. Sub-surface Activity (b) Surface Activity (a) Avg. Sub-surface Activity (b) Surface Activity (a) Avg. Sub-surface Activity (b) (pC/g) (pC/g) (pC/g) (pC/g) (pC/g) (pC/g) (pC/g) (pC/g) Incore Tunnel Floor B102110-CJFCCV-001 14.0 2.35E+01 9.15E+00 6.74E+02 1.08E+01 1.14E+02 7.71E+01 8.45E+00 4.33E+00 Incore Tunnel Floor B102110-CJFCCV-002 4.5 1.42E+01 1.37E+01 1.74E+01 9.43E-01 1.13E+02 1.22E+02 8.61E+00 7.38E+00 Incore Tunnel Wall B102110-CJWCCV-003 5.5 1.35E+01 8.45E+00 5.01E+01 1.99E+00 7.08E+01 6.27E+01 5.12E+00 3.56E+00 (a) Represents surface activity of floor following removal of loose contamination 2413 (b) Represents average of activity over entire depth of core sample minus the surface activity 2414  2415 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-130  Table 2-19 Unit 1 Containment Concrete Core Samples - Eberline Laboratory Analysis 2416 Radionuclide B101102-CJFCCV-002 (pCi/g) B101103-CJFCCV-002 (pCi/g) B101104-CJFCCV-001 (pCi/g) B101105-CJFCCV-001 (pCi/g) B101105-CJFCCV-002 (pCi/g) B101106-CJFCCV-002 (pCi/g) B101107-CJFCCV-002 (pCi/g) B101108-CJFCCV-002 (pCi/g) B101109-CJFCCV-001 (pCi/g) B101110-CJFCCV-001 (pCi/g) B101110-CJFCCV-002 (pCi/g) H-3 1.91E+01 2.60E+01 3.75E+01 2.71E+01 1.19E+02 8.11E+01 5.05E+01 7.61E+01 5.40E+01 1.33E+02 2.20E+02 C-14 2.50E+00 3.62E+00 4.40E+00 2.46E+01 2.71E+00 1.51E+00 1.12E+00 9.52E+00 1.09E+00 9.89E-01 3.30E+00 Co-60 8.12E+01 7.09E+03 8.69E+01 3.35E+04 9.77E+02 4.36E+01 1.50E+01 8.67E+01 8.50E+00 4.45E+01 3.60E+02 Ni-63 1.81E+04 2.26E+03 6.29E+03 2.81E+03 1.14E+01 3.02E+01 5.48E+00 2.39E+01 1.13E+01 1.40E+02 2.98E+01 Sr-90 4.75E+01 7.60E+00 1.63E+02 1.45E+01 7.08E+00 3.97E-01 5.67E-01 8.46E+00 4.74E-01 3.16E-01 6.01E-01 Nb-94 8.56E+01 1.56E+01 5.13E+01 2.56E+01 7.85E+00 6.01E-01 3.03E-01 9.30E+00 2.37E-01 1.47E+00 1.97E+00 Tc-99 2.25E+01 1.22E+00 3.46E+01 9.31E-01 9.35E-01 2.96E-01 2.60E-01 1.13E+00 2.66E-01 2.63E-01 1.33E+00 Ag-108m 2.39E+02 1.72E+01 5.72E+01 2.05E+01 9.25E+00 4.50E-01 2.35E-01 1.19E+01 2.09E-01 1.45E+00 1.91E+00 Sb-125 1.92E+02 5.54E+01 1.23E+02 3.88E+01 4.78E+01 1.86E+00 1.65E+00 5.62E+01 2.96E-02 NA NA Cs-134 5.47E+01 1.61E+01 3.68E+01 1.53E+01 9.47E+00 4.45E-01 3.31E-01 3.92E+01 3.54E-01 6.39E-01 1.61E+00 Cs-137 1.45E+05 9.44E+04 1.22E+05 2.72E+03 4.27E+04 1.38E+02 1.60E+02 5.91E+04 1.43E+02 8.83E+01 2.84E+03 Pm-145 1.49E+04 1.38E+04 3.49E+03 2.75E+02 5.26E+03 1.42E+01 1.74E+00 8.49E+03 2.02E+00 1.63E+01 3.94E+02 Eu-152 4.52E+02 7.31E+01 2.52E+02 1.25E+02 2.29E+01 1.82E+00 8.56E-01 1.95E+01 1.06E+00 1.64E+02 1.08E+02 Eu-154 2.26E+02 3.58E+01 1.29E+02 5.16E+01 1.48E+01 9.41E-01 5.26E-01 1.76E+01 5.44E-01 1.29E+01 8.69E+00 Eu-155 5.39E+01 2.37E+01 3.54E+01 1.70E+01 1.68E+01 6.24E-01 6.11E-01 1.89E+01 6.41E-01 3.69E+00 3.52E+00 Np-237 9.15E-02 9.56E-02 7.24E-02 9.82E-02 7.93E-02 2.40E-02 3.62E-02 1.01E-01 2.56E-02 NA NA Pu-238 1.25E-01 2.35E-01 3.05E-01 3.18E+00 1.31E-01 5.39E-02 1.03E-01 1.65E-01 9.33E-02 5.21E-02 1.22E-01 Pu-239/240 9.84E-02 1.11E-01 1.12E-01 2.30E+00 7.62E-02 5.24E-02 1.64E-01 1.05E-01 5.88E-02 4.50E-02 1.09E-01 Pu-241 8.17E+00 7.08E+00 8.54E+00 1.24E+01 7.86E+00 5.60E-01 4.53E-01 9.36E+00 4.79E-01 4.21E-01 7.28E+00 Am-241 3.58E-01 1.39E+00 4.25E-01 5.15E+01 2.68E-01 1.67E-01 8.80E-02 1.01E-01 5.40E-02 4.36E-02 2.15E-01 Am-243 8.37E-02 1.36E-01 6.05E-03 5.33E-01 8.36E-02 3.80E-02 4.49E-02 7.63E-02 2.96E-02 3.04E-02 9.33E-02 Cm-243/244 8.70E-02 3.34E-01 1.27E-01 1.01E+01 1.43E-01 4.35E-02 4.04E-02 7.26E-02 6.46E-02 6.35E-02 1.56E-01 a Bold values indicate concentration greater than MDC. Italicized values indicate MDC value. NA indicates "no analysis"  2417 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN REVISION 1 2-131  Table 2-20 Unit 2 Containment Concrete Core Samples - Eberline Laboratory Analysis 2418 Radionuclide B102102-CJFCCV-001 (pCi/g) B102103-CJFCCV-001 (pCi/g) B102103-CJFCCV-002 (pCi/g) B102105-CJFCCV-001 (pCi/g) B102105-CJFCCV-002 (pCi/g) B102106-CJFCCV-001 (pCi/g) B102106-CJFCCV-002 (pCi/g) B102107-CJFCCV-001 (pCi/g) B102110-CJFCCV-001 (pCi/g) B102110-CJFCCV-002 (pCi/g) H-3 1.27E+02 7.61E+01 5.57E+00 9.18E+00 2.06E+02 1.12E+01 5.19E+01 7.26E+00 2.41E+02 3.29E+01 C-14 2.80E+00 5.80E+00 1.17E+00 3.94E+00 1.23E+00 2.72E+00 2.51E+00 4.44E+00 9.72E-01 1.84E+00 Co-60 9.96E+02 6.91E+02 2.59E+02 1.09E+03 1.83E+02 8.01E+01 4.35E+01 7.57E+01 4.95E+01 2.27E+01 Ni-63 4.35E+03 1.23E+03 2.72E+02 4.85E+03 1.08E+02 9.98E+00 1.07E+02 3.11E+02 7.31E+01 4.73E+01 Sr-90 4.84E+00 1.41E+00 1.46E+00 1.76E+01 8.33E-01 4.17E-01 3.79E+00 2.08E+00 3.71E-01 3.35E-01 Nb-94 1.92E+01 1.77E+01 1.77E+01 3.50E+00 5.97E+00 1.06E+00 7.04E+00 1.25E+00 3.22E+00 2.48E+00 Tc-99 2.86E-01 2.22E+00 6.85E-01 3.97E-01 2.54E-01 2.95E-01 3.96E-01 2.80E-01 2.60E-01 2.50E-01 Ag-108m 6.85E+01 2.29E+01 1.88E+00 2.93E+00 7.03E+00 8.09E-01 9.72E+00 1.08E+00 4.17E+00 2.08E+00 Sb-125 2.39E+02 1.00E+02 1.00E+02 2.93E+00 5.56E+01 6.51E+00 6.41E+01 1.52E+01 NA NA Cs-134 6.09E+01 2.10E+01 8.27E+00 3.10E+00 8.75E+00 1.26E+00 1.12E+01 1.68E+01 1.30E+00 8.19E-01 Cs-137 2.14E+05 5.58E+04 8.45E+03 2.49E+03 2.09E+04 1.13E+03 2.66E+04 4.51E+03 1.05E+03 1.56E+01 Pm-145 1.23E+04 8.75E+02 1.08E+03 3.31E+01 2.62E+03 1.28E+02 1.12E+03 3.88E+02 4.78E+01 2.79E+01 Eu-152 3.98E+01 5.08E+01 5.08E+01 9.27E+00 1.22E+01 3.28E+00 1.11E+01 3.58E+00 3.97E+02 2.53E+02 Eu-154 2.70E+01 3.35E+01 3.35E+01 5.45E+00 9.97E+00 1.43E+00 1.21E+01 1.75E+00 2.58E+01 2.17E+01 Eu-155 7.97E+01 3.55E+01 6.12E+00 4.05E+00 2.00E+01 2.32E+00 2.39E+01 4.58E+00 7.02E+00 5.98E+00 Np-237 2.74E-02 2.85E-02 2.85E-02 2.96E-02 3.68E-02 3.84E-02 2.90E-02 3.17E-02 NA NA Pu-238 4.15E-02 3.99E-02 2.59E-02 1.64E-01 4.71E-02 2.85E-02 4.43E-02 3.67E-02 3.18E-02 2.71E-02 Pu-239/240 4.40E-02 5.00E-02 4.74E-02 1.54E-01 4.48E-02 2.86E-02 4.04E-02 2.56E-02 2.78E-02 2.36E-02 Pu-241 3.38E+00 4.01E+00 2.79E+00 6.17E+00 4.65E+00 3.45E+00 4.20E+00 3.09E+00 3.30E+00 2.70E+00 Am-241 2.49E-01 1.24E-01 1.27E-01 6.28E+00 5.08E-02 4.55E-02 4.48E-02 4.25E-02 4.95E-02 1.94E-02 Am-243 4.86E-02 3.28E-02 3.92E-02 3.80E-01 3.58E-02 7.19E-02 5.63E-02 3.94E-02 5.18E-02 3.61E-02 Cm-243/244 9.04E-02 4.54E-02 5.56E-02 1.19E-00 3.50E-02 3.98E-02 4.60E-02 3.66E-02 4.96E-02 2.86E-02 a Bold values indicate concentration greater than MDC. Italicized values indicate MDC value. NA indicates "no analysis"2419 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-132  Table 2-21 Radionuclide Distributions for Unit 1 and Unit 2 Containments 2420 Unit 1 Containment 568 foot elevation  Unit 1 Containment 541 foot elevation H-3 0.10%  H-3 3.25% C-14 0.01%  C-14 0.04% Fe-55 0.07%  Fe-55 0.27% Ni-59 0.01%  Ni-59 0.51% Co-60 2.88%  Co-60 8.22% Ni-63 2.04%  Ni-63 3.61% Sr-90 0.05%  Sr-90 0.01% Nb-94 0.01%  Nb-94 0.07% Tc-99 0.01%  Tc-99 0.01% Ag-108m 0.02%  Ag-108m 0.07% Sb-125 0.10%  Sb-125 0.09% Cs-134 0.03%  Cs-134 0.41% Cs-137 94.30%  Cs-137 27.28% Eu-152 0.19%  Eu-152 51.89% Eu-154 0.10%  Eu-154 2.82% Eu-155 0.03%  Eu-155 1.36% Np-237 0.00%  Np-237 0.00% Pu-238 0.00%  Pu-238 0.00% Pu-239 0.00%  Pu-239 0.00% Pu-240 0.00%  Pu-240 0.00% Pu-241 0.01%  Pu-241 0.07% Am-241 0.01%  Am-241 0.00% Am-243 0.00%  Am-243 0.00% Cm-243 0.00%  Cm-243 0.00% Cm-244 0.00%  Cm-244 0.00%  2421  2422 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-133  Table 2-21 Radionuclide Distributions for Unit 1 and Unit 2 Containments (continued) 2423 Unit 2 Containment 568 foot elevation  Unit 2 Containment 541 foot elevation H-3 0.06%  H-3 1.13% C-14 0.00%  C-14 0.01% Fe-55 1.14%  Fe-55 0.70% Ni-59 0.24%  Ni-59 1.55% Co-60 13.70%  Co-60 7.84% Ni-63 45.02%  Ni-63 12.94% Sr-90 0.00%  Sr-90 0.00% Nb-94 0.29%  Nb-94 0.05% Tc-99 0.00%  Tc-99 0.00% Ag-108m 0.46%  Ag-108m 0.67% Sb-125 0.07%  Sb-125 0.03% Cs-134 0.06%  Cs-134 0.34% Cs-137 38.90%  Cs-137 4.40% Eu-152 0.02%  Eu-152 65.28% Eu-154 0.01%  Eu-154 3.72% Eu-155 0.02%  Eu-155 1.31% Np-237 0.00%  Np-237 0.00% Pu-238 0.00%  Pu-238 0.00% Pu-239 0.00%  Pu-239 0.00% Pu-240 0.00%  Pu-240 0.00% Pu-241 0.00%  Pu-241 0.02% Am-241 0.00%  Am-241 0.00% Am-243 0.00%  Am-243 0.00% Cm-243 0.00%  Cm-243 0.00% Cm-244 0.00%  Cm-244 0.00%  2424 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-134 Table 2-22 Auxiliary Building 542 Foot Elevation Concrete Core Sample Analysis Summary 2425 Location Sample ID# Core Depth (inches) Co-60 Cs-137 Surface Activity (a) Avg. Subsurface Activity (b) Surface Activity (a) Avg. Subsurface Activity (b) (pC/g) (pC/g) (pC/g) (pC/g) 1A RHR Pump Room  B105101-CJFCCV-001 5.5 6.11E+01 1.06E+01 3.74E+03 3.06E+02 2A RHR Pump Room B105103-CJFCCV-001 4.0 4.56E+02 2.04E+02 2.51E+04 4.92E+03 2B RHR Pump Room B105104-CJFCCV-001 1.0 4.08E-01 4.20E-01 9.44E+00 1.79E+00 Unit 1 Hot Pipe Chase B105105-CJFCCV-001 5.0 7.00E+00 8.89E-01 9.83E+03 2.65E+03 Unit 2 Hot Pipe Chase B105106-CJFCCV-001 4.5 3.86E+00 1.51E+00 2.77E+03 1.05E+03 Unit 2 Hot Pipe Chase  B105106-CJFCCV-002 1.0 1.75E+01 3.60E+00 3.09E+03 4.14E+02 Hold-up Tank Cubicles  B105107- CJFCCV-002 14.0 1.18E+01 3.71E-01 1.17E+02 2.26E+00 Central Common Area  B105108-CJFCCV-001 4.5 4.32E-01 1.74E-01 1.92E+03 2.18E+02 Central Common Area B105108-CJFCCV-002 4.0 2.80E+00 1.28E+00 1.13E+02 1.53E+01 Central Common Area B105108-CJFCCV-003 3.0 3.03E+01 1.65E+00 1.67E+03 7.26E+01 Central Common Area Elevator Shaft B105108-CJFCCV-004 4.0 4.05E+00 2.71E-01 1.51E+02 4.92E+00 South Common Area B105109-CJFCCV-001 1.0 4.22E+00 8.22E-01 1.43E+03 2.13E+02 North Common Area B105110-CJFCCV-001 1.0 8.09E+00 1.81E+00 2.11E+03 3.50E+02 North Common Area B105110-CJFCCV-002 1.5 3.28E-01 7.85E-02 6.37E+01 5.17E+00 East Common Area B105111-CJFCCV-001 3.5 2.06E+00 7.66E-01 1.13E+03 1.99E+02 East Common Area Wall B101111-CJWCCV-002 0.5 1.94E-01 2.85E-01 9.52E-01 4.25E-01 Unit 1 ABEDCT Room  B105113-CJFCCV-001 5.5 1.96E+02 1.33E+01 5.69E+03 1.54E+02 Unit 1 ABEDCT Room  B105113-CJFCCV-002 5.5 3.76E+01 6.98E+00 1.79E+03 1.50E+02 Unit 1 ABEDCT Room Wall B105113-CJWCCV-003 1.0 6.71E+02 1.69E+02 1.66E+04 3.77E+03 (a) Represents surface activity of floor following removal of loose contamination 2426 (b) Represents average of activity over entire depth of core sample minus the surface activity 2427 (c) Bold values indicate concentration greater than MDC. Italicized values indicate MDC value. 2428  2429 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-135 Table 2-23 Auxiliary Building Concrete Core Samples - Eberline Laboratory Analysis 2430 Radionuclide B105101-  CJFCCV-001 (pCi/g) B105103-  CJFCCV-001 (pCi/g) B105105-  CJFCCV-001 (pCi/g) B105106-  CJFCCV-002 (pCi/g) B105108-  CJFCCV-003 (pCi/g) B105113-CJWCCV-003 (pCi/g) H-3 1.12E+01 1.68E+01 6.98E+00 2.96E+01 5.61E+00 4.71E+00 C-14 9.56E-01 4.88E+00 9.98E-01 1.48E+00 1.19E+00 3.10E+00 Fe-55 1.20E+01 3.16E+01 1.81E+01 1.12E+01 8.17E+00 1.73E+01 Ni-59 1.59E+01 2.08E+01 1.81E+01 1.74E+01 1.67E+01 1.75E+01 Co-60 2.62E+01 2.28E+02 3.20E+00 1.01E+01 1.83E+01 2.03E+02 Ni-63 1.52E+02 3.38E+03 2.91E+02 9.18E+01 8.59E+01 1.65E+03 Sr-90 1.07E+00 5.44E+00 1.52E+00 4.04E-01 3.29E-01 8.82E+00 Nb-94 2.29E-01 8.17E-01 6.19E-01 2.13E-01 3.02E-01 6.57E-01 Tc-99 1.45E+00 9.61E-01 6.70E-01 4.73E-01 9.09E-01 5.81E-01 Ag-108m 2.06E-01 1.66E+00 8.06E-01 2.53E-01 1.82E-01 5.96E-01 Sb-125 2.27E+00 7.79E+00 4.39E+00 2.46E+00 1.99E+00 4.57E+00 Cs-134 4.53E-01 1.47E+00 8.63E-01 8.11E-01 2.90E-01 1.23E+00 Cs-137 1.35E+03 1.33E+04 5.29E+03 1.88E+03 1.05E+03 4.19E+03 Pm-147 1.43E+01 8.17E-01 9.63E-01 5.30E+00 9.57E+00 7.19E+00 Eu-152 7.57E-01 2.58E+00 1.05E+00 6.75E-01 7.10E-01 1.80E+00 Eu-154 4.00E-01 1.38E+00 1.19E+00 3.95E-01 3.21E-01 1.05E+00 Eu-155 5.76E-01 1.76E+00 1.16E+00 6.33E-01 4.84E-01 1.05E+00 Np-237 2.04E-02 2.13E-02 2.39E-02 2.10E-01 1.92E-02 3.20E-02 Pu-238 1.77E-02 3.43E-01 1.32E-02 1.37E-02 1.78E-02 1.39E-02 Pu-239/240 1.77E-02 2.74E-01 1.06E-02 1.37E-02 1.33E-02 1.35E-02 Pu-241 2.48E+00 2.46E+00 1.79E+00 2.36E+00 1.73E+00 1.72E+00 Am-241 3.03E-02 2.29E-01 4.38E-02 2.72E-02 4.29E-02 3.17E-02 Am-243 2.89E-02 1.09E-01 6.01E-02 3.62E-02 3.36E-02 3.18E-02 Cm-243/244 3.91E-02 4.41E-02 3.95E-02 3.89E-02 4.02E-02 4.29E-02 a Bold values indicate concentration greater than MDC. Italicized values indicate MDC value.2431 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-136  Table 2-24 Radionuclide Distribution for the Auxiliary Building 2432 Auxiliary Building 542 foot elevation H-3 0.21174% C-14 0.044% Fe-55 0.38106% Ni-59 0.44498% Co-60 1.660.908% Ni-63 2123.69480% Sr-90 0.051% Nb-94 0.013% Tc-99 0.016% Ag-108m 0.02017% Sb-125 0.06017% Cs-134 0.06010% Cs-137 7574.27597% Eu-152 0.02017% Eu-154 0.01009% Eu-155 0.02008% Np-237 0.0004% Pu-238 0.001% Pu-239 0.0005% Pu-240 0.00001% Pu-241 0.03028% Am-241 0.001% Am-243 0.001% Cm-243 0.0003% Cm-244 0.0003%  2433  2434 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-137  Table 2-25 Turbine Building 560 Foot and 570 Foot Elevation Concrete Core Sample Analysis Summary 2435 Location Sample ID# Core Depth (inches) Co-60 Cs-137 Surface Activity (a) Avg. Subsurface Activity (b) Surface Activity (a) Avg. Subsurface Activity (b) (pC/g) (pC/g) (pC/g) (pC/g) TB 560 el. North @ Grid F8  B206104-CJFCCV-001 5.5 1.14E-01 8.57E-02 1.27E-01 1.30E-01 TB 560 el. North @ Grid F11  B206104-CJFCCV-002 5.0 2.11E-01 1.07E-01 1.65E+00 1.76E-01 TB 560 el. North @ Grid F12  B206104-CJFCCV-003 4.0 2.73E-01 1.10E-01 4.67E+00 1.37E+00 Unit 1 Steam Tunnel @ Grid L32  B206207-CJFCCV-001 2.0 1.04E-01 1.18E-01 4.67E+00 2.98E+00 Unit 1 Steam Tunnel @ Grid K31  B206207-CJFCCV-002 2.0 1.30E-01 6.86E-02 4.52E+01 3.02E+00 Unit 1 Steam Tunnel@ Grid M32  B206207-CJFCCV-003 2.0 1.06E-01 9.61E-02 1.49E+01 1.03E+00 Unit 1 Steam Tunnel o/s West Valve Room B206207-CJFCCV-004 2.0 1.66E-01 7.57E-02 3.97E+01 2.44E+00 Unit 1 Steam Tunnel @ End of Tunnel B206207-CJFCCV-005 1.5 6.56E-02 1.22E-01 1.74E+01 1.70E+00 Unit 2 Steam Tunnel o/s West Valve Room B206208-CJFCCV-001 2.0 1.50E-01 1.17E-01 6.72E+00 5.95E-01 Unit 2 Steam Tunnel o/s West Valve Room B206208-CJFCCV-002 5.0 1.35E-01 8.93E-02 1.86E+01 1.97E-01 (e) Represents surface activity of floor following removal of loose contamination 2436 (f) Represents average of activity over entire depth of core sample minus the surface activity 2437 (g) Italicized values indicate MDC value. 2438  2439 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-138  Table 2-26 Inventory of Embedded Penetrations 2440 Unit 1 Containment Embedded Penetrations (Sleeves) 2441 System Description a Elevation Sleeve Size b  (inches) Pipe Size c  (inches) Length d          (feet) Fire Protection 577.5 ft. 10 4 4 Spare Penetration (no system pipe) 577.5 ft. 6 N/A 4 Boron Injection Tank to Cold Legs 577.5 ft. 8 3 4 Main Steam 579.5 ft. 50 34 4 Main Steam 579.5 ft. 50 34 4 Main Steam 579.5 ft. 50 35.5 4 Main Steam 579.5 ft. 50 35.5 4 Feed Water 584.6 ft. 32 16 4 Feed Water 584.6 ft. 32 16 4 Feed Water 584.6 ft. 32 16 4 Feed Water 586.8 ft. 32 16 4 RCS No.1 loop to RHR 584.3 ft. 28 14 4 Cavity Fill pump 1A discharge 584.3 ft. 18 10 4 Component Cooling Header to RCP's 586.8 ft. 12 6 4 Cavity Fill pump 1B discharge 584.3 ft. 18 10 4 Spare Penetration (no system pipe) 584.3 ft. 28 N/A 4 RHR Exchanger to RC loop Cold Legs 580.1 ft. 28 12 4 RC pumps to CC suction 586.8 ft. 12 6 4 CTMT sump discharge 577.5 ft. 6 1.5 4 RC Drain Discharge to Hold-up Tank 580.1 ft. 8 3 4 Fuel Transfer Tube e 578.5 ft. 24 N/A 8 Spare Penetration (no system pipe) 580.1 ft. 10 N/A 4 CTMT Pressure 586.8 ft. 6 2 4 Filtered Vents 580.1 ft. 8 2 4 Spare Penetration (no system pipe) 586.8 ft. 10 N/A 4 RC pump Seal Water Supply lines 580.1 ft. 14 8 4 Spare Penetration (no system pipe) 584.3 ft. 18 N/A 4 Aux FW to S/G 1C 577.5 ft. 14 3 4 Aux FW to S/G 1A 577.5 ft. 14 3 4 Cavity Drain to Purification pump 577.5 ft. 14 3 4 Spare Penetration (no system pipe) 584.3 ft. 18 N/A 4 Aux FW to S/G 1D 586.8 ft. 14 3 4 RCS Hot Leg sample 586.8 ft. 10 0.1 4 Prez. Relief Tank to Gas Analyzer 586.8 ft. 10 0.1 4 Dead wt. Calibration from Prez. 586.8 ft. 10 0.1 4 S/G Blowdown sample 586.8 ft. 10 0.1 4 Spare Penetration (no system pipe) 584.3 ft. 10 N/A 4  2442 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-139  Table 2-26 Inventory of Embedded Penetrations (continued) 2443 System Description a Elevation Sleeve Size b  (inches) Pipe Size c  (inches) Length d          (feet) Heating System Hot Water supply 586.8 ft. 12 2 4 Heating System Hot Water return 586.8 ft. 12 2 4 Spare Penetration (no system pipe) 584.3 ft. 10 N/A 4 Blowdown S/G 1A 584.6 ft. 16 2.5 4 Blowdown S/G 1A 584.6 ft. 16 2 4 Blowdown S/G 1C 584.6 ft. 16 2 4 Blowdown S/G 1C 584.6 ft. 16 2.5 4 Blowdown S/G 1A 580.3 ft. 14 2 4 Blowdown S/G 1C 580.3 ft. 14 2 4 Blowdown S/G 1D 580.3 ft. 14 2 4 Blowdown S/G 1B 580.3 ft. 14 2 4 Spare Penetration (no system pipe) 577.5 ft. 8 N/A 4 SIM to Aux FS pumps 580.1 ft. 24 6 4 RHR Exchanger to RCS Hot Legs 580.1 ft. 18 10 4 S/G blowdown sample 580.1 ft. 16 0.1 4 S/G blowdown sample 580.1 ft. 15 0.1 4 Blowdown S/G 1D 584.6 ft. 16 2.5 4 Blowdown S/G 1D 584.6 ft. 16 2 4 Blowdown S/G 1B 584.6 ft. 16 2 4 Blowdown S/G 1B 584.6 ft. 16 2.5 4 Steam to Aux FW pumps 578.1 ft. 16 6 4 Steam to Aux FW pumps 578.1 ft. 16 6 4 Recirculating Sump suction 561.3 ft. 24 20 4 Recirculating Sump suction 561.3 ft. 24 20 4 Cavity Flood sump suction  561.3 ft. 24 20 4 Cavity Flood sump suction  561.3 ft. 24 20 4 a. Description of system pipe that transited concrete wall through the embedded sleeve. 2444 b. Outer diameter size of metal sleeve embedded in concrete wall. Only the sleeve will remain and be subjected to FSS. 2445 c. Outer diameter size of the system pipe that transited concrete wall through the embedded sleeve. System pipe will be 2446 removed and dispositioned as waste stream. 2447 d. Length of embedded sleeve in concrete. Assumes pipe sleeve is cut flush with concrete wall on both sides. 2448 Unit 2 Containment Embedded Penetrations (Sleeves) 2449 System Description a Elevation Sleeve Size b  (inches) Pipe Size c  (inches) Length d          (feet) Fire Protection 577.5 ft. 10 4 4 Spare Penetration (no system pipe) 577.5 ft. 6 N/A 4 Boron Injection Tank to Cold Legs 577.5 ft. 8 3 4 Main Steam 579.5 ft. 50 34 4  2450 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-140  Table 2-26 Inventory of Embedded Penetrations (continued) 2451 System Description a Elevation Sleeve Size b  (inches) Pipe Size c  (inches) Length d          (feet) Main Steam 579.5 ft. 50 34 4 Main Steam 579.5 ft. 50 35.5 4 Main Steam 579.5 ft. 50 35.5 4 Feed Water 584.6 ft. 32 16 4 Feed Water 584.6 ft. 32 16 4 Feed Water 584.6 ft. 32 16 4 Feed Water 586.8 ft. 32 16 4 RCS No.1 loop to RHR 584.3 ft. 28 14 4 Cavity Fill pump 1A discharge 584.3 ft. 18 10 4 Component Cooling Header to RCP's 586.8 ft. 12 6 4 Cavity Fill pump 1B discharge 584.3 ft. 18 10 4 Spare Penetration (no system pipe) 584.3 ft. 28 N/A 4 RHR Exchanger to RC loop Cold Legs 580.1 ft. 28 12 4 RC pumps to CC suction 586.8 ft. 12 6 4 CTMT sump discharge 577.5 ft. 6 1.5 4 RC Drain Discharge to Hold-up Tank 580.1 ft. 8 3 4 Fuel Transfer Tube e 578.5 ft. 24 N/A 8 Spare Penetration (no system pipe) 580.1 ft. 10 N/A 4 CTMT Pressure 586.8 ft. 6 2 4 Filtered Vents 580.1 ft. 8 2 4 Spare Penetration (no system pipe) 586.8 ft. 10 N/A 4 RC pump Seal Water Supply lines 580.1 ft. 14 8 4 Spare Penetration (no system pipe) 584.3 ft. 18 N/A 4 Aux FW to S/G 2C 577.5 ft. 14 3 4 Aux FW to S/G 2A 577.5 ft. 14 3 4 Cavity Drain to Purification pump 577.5 ft. 14 3 4 Spare Penetration (no system pipe) 584.3 ft. 18 N/A 4 Aux FW to S/G 2D 586.8 ft. 14 3 4 Non-filtered vents 580.1 ft. 8 2 4 RCS Hot Leg sample 586.8 ft. 10 0.1 4 Prez. Relief Tank to Gas Analyzer 586.8 ft. 10 0.1 4 Dead wt. Calibration from Prez. 586.8 ft. 10 0.1 4 S/G Blowdown sample 586.8 ft. 10 0.1 4 Spare Penetration (no system pipe) 584.3 ft. 10  4 Heating System Hot Water supply 586.8 ft. 12 2 4 Heating System Hot Water return 586.8 ft. 12 2 4 Spare Penetration (no system pipe) 584.3 ft. 10  4 Blowdown S/G 2A 584.6 ft. 16 2.5 4 Blowdown S/G 2A 584.6 ft. 16 2 4 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-141  Table 2-26 Inventory of Embedded Penetrations (continued) 2452 System Description a Elevation Sleeve Size b  (inches) Pipe Size c  (inches) Length d          (feet) Blowdown S/G 2C 584.6 ft. 16 2 4 Blowdown S/G 2C 584.6 ft. 16 2.5 4 Blowdown S/G 2A 580.3 ft. 14 2 4 Blowdown S/G 2C 580.3 ft. 14 2 4 Blowdown S/G 2D 580.3 ft. 14 2 4 Blowdown S/G 2B 580.3 ft. 14 2 4 Spare Penetration (no system pipe) 577.5 ft. 8  4 SIM to Aux FS pumps 580.1 ft. 24 6 4 RHR Exchanger to RCS Hot Legs 580.1 ft. 18 10 4 S/G blowdown sample 580.1 ft. 16 0.1 4 S/G blowdown sample 580.1 ft. 15 0.1 4 Blowdown S/G 2D 584.6 ft. 16 2.5 4 Blowdown S/G 2D 584.6 ft. 16 2 4 Blowdown S/G 2B 584.6 ft. 16 2 4 Blowdown S/G 2B 584.6 ft. 16 2.5 4 Steam to Aux FW pumps 578.1 ft. 16 6 4 Steam to Aux FW pumps 578.1 ft. 16 6 4 Recirculating Sump suction 561.3 ft. 24 20 4 Recirculating Sump suction 561.3 ft. 24 20 4 Cavity Flood sump suction  561.3 ft. 24 20 4 Cavity Flood sump suction  561.3 ft. 24 20 4 a. Description of system pipe that transited concrete wall through the embedded sleeve. 2453 b. Outer diameter (OD) size of metal sleeve embedded in concrete wall. Only the sleeve will remain and be subjected to 2454 FSS. 2455 c. OD size of the system pipe that transited concrete wall through the embedded sleeve. System pipe will be removed and 2456 dispositioned as waste stream. 2457 d. Length of embedded sleeve in concrete. Assumes pipe sleeve is cut flush with concrete wall on both sides. 2458  2459 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-142 Table 2-27 Inventory of Buried Piping/Conduit 2460 Survey Unit(s) a Structure/System Description Elevation b Pipe Size c (inches) Pipe Length d (feet) 10202/12101 IRSF to Turbine Bldg. Buried Conduit 584 ft. 1 185 10202/12101 IRSF to Turbine Bldg. Buried Conduit 584 ft. 3 185 10202/12101 IRSF to Turbine Bldg. Buried Conduit 584 ft. 3 185 12112 Unit 1 CST 400MCM grounding cable 587 ft. 1 130 12103 Unit 2 CST 400MCM grounding cable 587 ft. 1 130 12113 Unit 1 PWST 400MCM grounding cable 587 ft. 1 71 12103 Unit 2 PWST 400MCM grounding cable 587 ft. 1 71 12203 Fuel oil tank berm sump 400MCM grounding cable 587 ft. 1 125 12112 Unit 1 CST Cable duct package 586 ft. 42 x 20 200 12113 Unit 1 PWST Cable duct package 586 ft. 42 x 20 30 12203 Fuel Oil Tank Cable duct package 586 ft. 18 x 140 89 12103 Unit 2 CST Cable duct package 586 ft. 42 x 20 200 12103 Unit 2 PWST Cable duct package 586 ft. 42 x 20 30 12204 Crib House to Turbine Building Unit 1 Circulating Water supply 552 ft. 17 100 12204 Crib House to Turbine Building Unit 2 Circulating Water supply 552 ft. 17 100 12204 Crib House  Unit 1 Circ. Water supply drain 540 ft. 14 20 12204 Crib House Unit 2 Circ. Water supply drain 540 ft. 14 20 12204 Crib House Unit 1 Circ. Water inlet pipe drain  537 ft. 8 15 12204 Crib House Unit 2 Circ. Water inlet pipe drain 537 ft. 8 15 12204 Crib house Unit 1 Discharge Tunnel drain  537 ft. 8 142 12204 Crib House Unit 2 Discharge Tunnel drain 537 ft. 8 142 12204 Crib House Unit 1 Service Water supply 579 ft. 48 40 12204 Crib House Unit 2 Service Water supply 579 ft. 48 40 12204 Crib house Circ. Water intake to Forebay 558 ft. 16 150 12204 Forebay area Unit 1 Forebay Ice Melting pipe 558 ft. 12 65 12204 Forebay area Unit 2 Forebay Ice Melting pipe 558 ft. 12 65  2461 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-143 Table 2-27 Inventory of Buried Piping/Conduit (continued) 2462 Survey Unit(s) a Structure/System Description Elevation b Pipe Size c (inches) Pipe Length d (feet) 12204 Forebay area Unit 1 Forebay Ice Melting pipe 558 ft. 8 20 12204 Forebay area Unit 2 Forebay Ice Melting pipe 558 ft. 8 20 12106/12107 Auxiliary Building Service Water to D/G Heat Exch. 555 ft. 12 45 12106/12107 Auxiliary Building Service Water to D/G Heat Exch. 553 ft. 12 45 12106/12107 Auxiliary Building Service Water to D/G Heat Exch. 555 ft. 12 45 12106/12107 Auxiliary Building Service Water to D/G Heat Exch. 553 ft. 12 45 12106/12107 Auxiliary Building Service Water supply header 550 ft. 48 60 12106/12107 Auxiliary Building Service Water supply header 550 ft. 48 60 12106/12107 Auxiliary Building Safety Injection 570 ft. 24 20 12106/12107 Auxiliary Building Component Cooling 570 ft. 10 20 12106/12107 Auxiliary Building Component Cooling 570 ft. 10 20 12106/12107 Auxiliary Building Aerated Drain 571 ft. 1.5 20 12106/12107 Auxiliary Building Aerated Drain 571 ft. 1.5 20 12106/12107 Auxiliary Building Aerated Drain 571 ft. 1.5 20 12106/12107 Auxiliary Building Service Water 570 ft. 2 20 12106/12107 Auxiliary Building Fire protection 570 ft. 4 20 12106/12107 Auxiliary Building Instrument Air 570 ft. 1.5 20 12106/12107 Auxiliary Building Aerated drain 569 ft. 4 20 12106/12107 Auxiliary Building Service Air 569 ft. 1.5 20 12106/12107 Auxiliary Building Spent Fuel Pool Cooling 569 ft. 3 20 12106/12107 Auxiliary Building Spent Fuel Pool Cooling 569 ft. 2 20 12106/12107 Auxiliary Building Safety Injection 570 ft. 24 20 12106/12107 Auxiliary Building Component Cooling 570 ft. 10 20 12106/12107 Auxiliary Building Component Cooling 570 ft. 10 20 12106/12107 Auxiliary Building Aerated Drain 571 ft. 1.5 20 12106/12107 Auxiliary Building Aerated Drain 571 ft. 1.5 20  2463 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-144 Table 2-27 Inventory of Buried Piping/Conduit (continued) 2464 Survey Unit(s) a Structure/System Description Elevation b Pipe Size c (inches) Pipe Length d (feet) 12106/12107 Auxiliary Building Aerated Drain 571 ft. 1.5 20 12106/12107 Auxiliary Building Waste Disposal  570 ft. 2.5 20 12106/12107 Auxiliary Building Demineralized Water 570 ft. 3 20 12106/12107 Auxiliary Building Aerated Drain 569 ft. 4 20 12106/12107 Auxiliary Building Service Water 569 ft. 2 20 12106/12107 Auxiliary Building Spent Fuel Pool cooling 569 ft. 3 20 12106/12107 Auxiliary Building Spent Fuel Pool cooling 569 ft. 3 20 12106/12107 Auxiliary Building Spent Fuel Pool cooling 569 ft. 2 20 12106/12107 Auxiliary Building Service Air 569 ft. 1.5 20 12106/12107 Auxiliary Building Demineralized Water 569 ft. 3 20 12106/12107 Auxiliary Building Waste Drain 569 ft. 3 20 12106/12107 Auxiliary Building Demineralized Water 570 ft. 24 20 12106/12107 Auxiliary Building Feedwater  570 ft. 4 20 12102 WWTF Force Main 586 ft. 8 80 12102 WWTF Roof Drain Lines 578 ft. 6 53 12204 WWTF to Forebay WWTF discharge to Forebay 587 ft. 8 342 12204 Forebay area Unit 1 Ice melting pipe  569 ft. 8 25 12204 Forebay area Unit 1 Ice melting pipe  569 ft. 12 71 12204 Forebay area Unit 2 Ice melting pipe  569 ft. 8 25 12204 Forebay area Unit 2 Ice melting pipe  569 ft. 12 71 12107 Fuel Handling Building Unit 1 Component Cooling 570 ft. 10 4 12107 Fuel Handling Building Unit 1 Component Cooling 570 ft. 10 4 12107 Fuel Handling Building Unit 1 Aerated Drain 572 ft. 2 4 12107 Fuel Handling Building Unit 1 Aerated Drain 572 ft. 2 4 12107 Fuel Handling Building Unit 1 Aerated Drain 572 ft. 2 4 12107 Fuel Handling Building Unit 1 Safety Injection 569 ft. 24 4  2465 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-145 Table 2-27 Inventory of Buried Piping/Conduit (continued) 2466 Survey Unit(s) a Structure/System Description Elevation b Pipe Size c (inches) Pipe Length d (feet) 12107 Fuel Handling Building Drain Line to Unit 1 569 ft. 2 4 12107 Fuel Handling Building Spent Fuel Pool Cooling to Unit 1 569 ft. 3 4 12107 Fuel Handling Building Spent Fuel Pool Cooling to Unit 1 569 ft. 2 4 12107 Fuel Handling Building Fuel Pool Drain to Unit 1 570 ft. 4 4 12107 Fuel Handling Building Unit 1 Service Water 570 ft. 2 4 12107 Fuel Handling Building Unit 1 Instrument Air 570 ft. 2 4 12107 Fuel Handling Building Unit 1 Aerated Drain 569 ft. 4 4 12107 Fuel Handling Building Unit 1 Service Air 569 ft. 2 4 12107 Fuel Handling Building Unit 2 Component Cooling 570 ft. 10 4 12107 Fuel Handling Building Unit 2 Component Cooling 570 ft. 10 4 12107 Fuel Handling Building Unit 2 Aerated Drain 572 ft. 1.5 4 12107 Fuel Handling Building Unit 2 Aerated Drain 572 ft. 1.5 4 12107 Fuel Handling Building Unit 2 Safety Injection 570 ft. 24 4 12107 Fuel Handling Building Spent Fuel Pool Cooling to Unit 2 569 ft. 3 4 12107 Fuel Handling Building Spent Fuel Pool Cooling to Unit 2 569 ft. 3 4 12107 Fuel Handling Building Spent Fuel Pool Cooling to Unit 2 569 ft. 2 4 12107 Fuel Handling Building Drain Line to Unit 2 570 ft. 2.5 4 12107 Fuel Handling Building Fuel Pool Drain to Unit 2 570 ft. 3 4 12107 Fuel Handling Building Unit 2 Aerated Drain 570 ft. 4 4 12107 Fuel Handling Building Unit 2 Service Water 570 ft. 3 4 12107 Fuel Handling Building Unit 2 Service Air 569 ft. 1.5 4 12107 Fuel Handling Building Fuel Pool Drain to Unit 2 569 ft. 3 4 12107 Fuel Handling Building Instrument to Unit 2 569 ft. 2 4 a. Denote open land survey unit affected by presence of pipe. 2467 b. Elevations are approximate. 2468 c. Pipe diameter is OD. 2469 d. Pipe lengths are approximate. 2470 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-146 Table 2-26 Turbine Building 560 Foot Elevation Floor Drain System Sediment Samples Gamma Spectroscopy Analysis 2471 Location Sample ID b Sample Date Analysis Date Co-60 a Cs-137 a (pCi/g) (pCi/g) Turbine Bldg. 560 ft. South S1-00333-CJSMSM-A001 04/01/13 04/22/13 1.92E-01 1.08E-01 S1-00333-CJSMSM-A002 04/02/13 04/22/13 2.61E-01 6.37E-01 S1-00333-CJSMSM-A004 04/10/13 04/11/13 1.88E-01 6.03E-01 Turbine Bldg. 560 ft. Central S1-00333-CJSMSM-B001 04/03/13 04/09/13 3.18E-01 1.24E+01 S1-00333-CJSMSM-B002 04/03/13 04/10/13 2.29E-01 5.44E+00 S1-00333-CJSMSM-B003 04/03/13 04/09/13 1.67E-01 2.05E+00 S1-00333-CJSMSM-B004 04/03/13 04/09/13 3.02E-01 1.04E+01 S1-00333-CJSMSM-B006  (LAW) 04/17/13 04/18/13 8.22E+00 7.79E+01 S1-00333-CJSMSM-B007 04/17/13 04/18/13 1.50E-01 1.77E+01 S1-00333-CJSMSM-B008 04/17/13 04/18/13 1.43E-01 9.46E-01 Turbine Bldg. 560 ft. North S1-00333-CJSMSM-C001 04/04/13 04/10/13 2.77E-01 1.38E+00 S1-00333-CJSMSM-C002 04/04/13 04/16/13 4.38E-01 4.72E+00 S1-00333-CJSMSM-C003 04/04/13 04/11/13 1.36E-01 2.21E-01 S1-00333-CJSMSM-C004 04/16/13 04/17/13 2.67E-01 3.38E-01 S1-00333-CJSMSM-C005 04/16/13 04/16/13 1.88E-01 1.99E-01 S1-00333-CJSMSM-C006 04/16/13 04/17/13 2.09E-01 2.51E-01 S1-00333-CJSMSM-C007 04/16/13 04/17/13 3.11E-01 2.74E-01 S1-00333-CJSMSM-C008  (LAW) 04/16/13 04/16/13 2.24E+01 2.87E+01 a Bold values indicate concentration greater than MDC. Italicized values indicate MDC value. 2472 b. "LAW" indicates Large Area Wipe 2473  2474 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-147 Table 2-27 Non-Impacted Open Land Survey Units - Characterization Survey Summary 2475 Survey Unit 10215 10216 10217 Surface Area  26,007.80 m2  31,171.10 m2  50,880.20 m2 Description Area Northwest of Switchyard Area West of Switchyard Area Southwest of Switchyard Surface Soil Samples Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Samples  4  4  4  4  7  7  # >MDC  0  0  0  3  0  7  Mean <0.06 pCi/g <0.09 pCi/g <0.04 pCi/g 0.23 pCi/g <0.05 pCi/g 0.41 pCi/g Median <0.05 pCi/g <0.09 pCi/g <0.04 pCi/g 0.23 pCi/g <0.05 pCi/g 0.43 pCi/g Max <0.09 pCi/g <0.10 pCi/g <0.05 pCi/g 0.26 pCi/g <0.06 pCi/g 0.52 pCi/g Min <0.04 pCi/g <0.08 pCi/g <0.01 pCi/g 0.20 pCi/g <0.05 pCi/g 0.26 pCi/g Standard Deviation N/A  N/A  N/A  0.03  N/A  0.09  ISOCS Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Measurements  14  14  16  16  27  27  # >MDC  0  1  0  8  0  10  Mean <0.04 pCi/g 0.05 pCi/g <0.04 pCi/g 0.19 pCi/g <0.04 pCi/g 0.20 pCi/g Median <0.04 pCi/g 0.05 pCi/g <0.04 pCi/g 0.27 pCi/g <0.04 pCi/g 0.21 pCi/g Max <0.05 pCi/g 0.05 pCi/g <0.05 pCi/g 0.27 pCi/g <0.06 pCi/g 0.30 pCi/g Min <0.02 pCi/g 0.05 pCi/g <0.03 pCi/g 0.07 pCi/g <0.04 pCi/g 0.04 pCi/g Standard Deviation N/A  N/A  N/A  0.07  N/A  0.08  Surface Scans    % Scanned 1%  1%  1%  # of Alarms 0  0  0  Mean Scan 3,995 cpm 4,828 cpm 4,563 cpm Max Scan 4,725 cpm 5,389 cpm 5,070 cpm Notes    1) 9 of 14 samples in west section of survey unit were relocated as area was deemed as inaccessible. 2) Additional ISOCS measurement (#14) was taken on discovered debris pile. 1) 9 of 16 samples in west section of survey unit were relocated as area was deemed as inaccessible. 1) 3 additional judgmental ISOCS measurement locations were added to account for additional area. 2) 1 additional ISOCS measurement added for discovered abandoned drain pipe. 2476 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-148 Table 2-2927 Non-Impacted Open Land Survey Units - Characterization Survey Summary (continued) 2477 Survey Unit 10302 10303 10304 Surface Area  64,739.50 m2  68,847.10 m2  34,009.70 m2 Description Northwest Corner of FSAR Area Southwest Corner of FSAR Area Southern Area of FSAR Surface Soil Samples Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Samples  11  11  25  25  5  5  # >MDC  0  9  0  13  0  3  Mean <0.05 pCi/g 0.30 pCi/g <0.06 pCi/g 0.17 pCi/g <0.05 pCi/g 0.26 pCi/g Median <0.06 pCi/g 0.27 pCi/g <0.06 pCi/g 0.15 pCi/g <0.06 pCi/g 0.23 pCi/g Max <0.08 pCi/g 0.46 pCi/g <0.10 pCi/g 0.39 pCi/g <0.07 pCi/g 0.35 pCi/g Min <0.02 pCi/g 0.12 pCi/g <0.02 pCi/g 0.06 pCi/g <0.02 pCi/g 0.21 pCi/g Standard Deviation N/A  0.11  N/A  0.10  N/A  0.08  ISOCS Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Measurements  19  19  18  18  17  17  # >MDC  0  7  0  9  0  8  Mean <0.05 pCi/g 0.25 pCi/g <0.05 pCi/g 0.21 pCi/g <0.04 pCi/g 0.17 pCi/g Median <0.05 pCi/g 0.22 pCi/g <0.05 pCi/g 0.23 pCi/g <0.04 pCi/g 0.16 pCi/g Max <0.06 pCi/g 0.34 pCi/g <0.06 pCi/g 0.30 pCi/g <0.05 pCi/g 0.27 pCi/g Min <0.04 pCi/g 0.20 pCi/g <0.03 pCi/g 0.09 pCi/g <0.02 pCi/g 0.09 pCi/g Standard Deviation N/A  0.06  N/A  0.07  N/A  0.06  Surface Scans    % Scanned 1%  1%  1%  # of Alarms 0  7  4  Mean Scan 4,951 cpm 5,858 cpm 4,456 cpm Max Scan 7,474 cpm 9,550 cpm 5,704 cpm Notes    1) 33 designed locations reduced to 22 due to accessibility. 2) 3 of 22 locations scanned with NaI & soil sample only. 3) 6 of 18 ISOCS taken at height of 1 meter due to obstructions - FOV = 3 m2. 1) 35 designed locations reduced to 18 due to accessibility. 2) 5 of 18 locations scanned with NaI & soil sample only. 3) 17 additional random and 3 additional judgmental soil samples taken. 1) 16 of 17 random locations relocated due to accessibility. 2478 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-149 Table 2-2927 Non-Impacted Open Land Survey Units - Characterization Survey Summary (continued) 2479 Survey Unit 10305 10306 10402 Surface Area  121,535.20 m2  85,267.80 m2  133,565.00 m2 Description Area West of Survey Unit #10217 Area West of Survey Unit #10216 MET Tower Area Surface Soil Samples Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Samples  17  17  4  4  41  41  # >MDC  0  4  0  4  0  31  Mean <0.05 pCi/g 0.19 pCi/g <0.05 pCi/g 0.26 pCi/g <0.04 pCi/g 0.20 pCi/g Median <0.05 pCi/g 0.18 pCi/g <0.04 pCi/g 0.23 pCi/g <0.04 pCi/g 0.18 pCi/g Max <0.08 pCi/g 0.33 pCi/g <0.08 pCi/g 0.40 pCi/g <0.07 pCi/g 0.42 pCi/g Min <0.01 pCi/g 0.07 pCi/g <0.02 pCi/g 0.20 pCi/g <0.01 pCi/g 0.04 pCi/g Standard Deviation N/A  0.14  N/A  0.09  N/A  0.10  ISOCS Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Measurements  61  61  18  18  39  39  # >MDC  0  10  0  14  0  5  Mean <0.04 pCi/g 0.19 pCi/g <0.04 pCi/g 0.17 pCi/g <0.05 pCi/g 0.10 pCi/g Median <0.04 pCi/g 0.20 pCi/g <0.04 pCi/g 0.17 pCi/g <0.05 pCi/g 0.11 pCi/g Max <0.06 pCi/g 0.30 pCi/g <0.06 pCi/g 0.27 pCi/g <0.08 pCi/g 0.12 pCi/g Min <0.03 pCi/g 0.08 pCi/g <0.01 pCi/g 0.08 pCi/g <0.03 pCi/g 0.07 pCi/g Standard Deviation N/A  0.06  N/A  0.05  N/A  0.02  Surface Scans    % Scanned 1%  1%  1%  # of Alarms 9  0  0  Mean Scan 5,473 cpm 4,407 cpm 4,835 cpm Max Scan 7,343 cpm 5,337 cpm 5,543 cpm Notes      1) 43 designed ISOCS measurement locations reduced to 18 due to accessibility. 2) 4 of 18 locations scanned with NaI & soil sample only. 1) 67 designed ISOCS measurement locations reduced to 39 due to accessibility. 2) 30 additional random locations designated for NaI scanning and surface soil samples. 2480 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-150 Table 2-2927 Non-Impacted Open Land Survey Units - Characterization Survey Summary (continued) 2481 Survey Unit 10403 10404 Surface Area  139,282.00 m2  118,735.00 m2 Description Area North of West Training NW Corner of Owner Controlled Property Surface Soil Samples Co-60 Cs-137 Co-60 Cs-137 # of Samples  18  18  30  30  # >MDC  0  12  0  20  Mean <0.04 pCi/g 0.18 pCi/g <0.04 pCi/g 0.20 pCi/g Median <0.04 pCi/g 0.17 pCi/g <0.04 pCi/g 0.20 pCi/g Max <0.07 pCi/g 0.39 pCi/g <0.06 pCi/g 0.57 pCi/g Min <0.01 pCi/g 0.05 pCi/g <0.01 pCi/g 0.02 pCi/g Standard Deviation N/A  0.09  N/A  0.14  ISOCS Co-60 Cs-137 Co-60 Cs-137 # of Measurements  7  7  0  0  # >MDC  0  3  0  0  Mean <0.04 pCi/g 0.19 pCi/g N/A pCi/g N/A pCi/g Median <0.04 pCi/g 0.19 pCi/g N/A pCi/g N/A pCi/g Max <0.05 pCi/g 0.23 pCi/g N/A pCi/g N/A pCi/g Min <0.03 pCi/g 0.14 pCi/g N/A pCi/g N/A pCi/g Standard Deviation N/A  0.04  N/A  N/A  Surface Scans  % Scanned <1%  1%  # of Alarms 4  0  Mean Scan 3,959 cpm 3,391 cpm Max Scan 5,310 cpm 6,964 cpm Notes    1) Approximately 90% of area was inaccessible to the ISOCS. 2) 70 ISOCS measurements reduced to 7. 3) 4.8% of accessible 13,928 m2 of land area scanned. 4) 16 additional random locations designated for NaI scanning and surface soil samples. 1) 60 ISOCS locations were designed. Entire area was inaccessible to the ISOCS. To compensate, additional scan and soil sample locations were evenly distributed in areas that were accessible. The total area scanned equates to 1,200 m2, or approximately 1%.
ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-151 Table 2-28 Recommended Judgmental Sample Population Size 2482 The following are the recommended judgmental sample population sizes for impacted 2483 survey units that will be subjected to FSS. The judgmental sample population should be 2484 taken in addition to any random-based sample population. These are recommended 2485 minimum sample population sizes. 2486 Area Classification Structure Land Class 1 8 judgmental samples per survey unit 8 judgmental samples per survey unit Class 2 30 judgmental samples per survey unit 30 judgmental samples per survey unit Class 3 13 judgmental samples per survey unit 13 judgmental samples per survey unit  2487 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-152 Table 2-29 Impacted Class 3 Open Land Survey Units - Characterization Survey Summary 2488 Survey Unit 10201 10202 10203 Surface Area  6,028.20 m2  6,843.90 m2  9,997.80 m2 Description NE Corner Restricted Area - Lakeshore IRSF/Fire Training Area East Training Area Surface Soil Samples Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Samples  17  17  17  17  20  20  # >MDA  0  0  0  0  0  5  Mean <0.05 pCi/g <0.07 pCi/g <0.04 pCi/g <0.06 pCi/g <0.08 pCi/g 0.11 pCi/g Median <0.06 pCi/g <0.06 pCi/g <0.05 pCi/g <0.06 pCi/g <0.08 pCi/g 0.11 pCi/g Max <0.09 pCi/g <0.11 pCi/g <0.08 pCi/g <0.10 pCi/g <0.11 pCi/g 0.16 pCi/g Min <0.02 pCi/g <0.02 pCi/g <0.02 pCi/g <0.01 pCi/g <0.02 pCi/g 0.06 pCi/g Standard Deviation N/A  N/A  N/A  N/A  N/A  0.04  Subsurface Soil Samples Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Measurements  2  2  2  2  2  2  # >MDC  0  0  0  0  0  0  Mean <0.05 pCi/g <0.07 pCi/g <0.06 pCi/g <0.06 pCi/g <0.06 pCi/g <0.08 pCi/g Median <0.05 pCi/g <0.07 pCi/g <0.06 pCi/g <0.06 pCi/g <0.06 pCi/g <0.08 pCi/g Max <0.06 pCi/g <0.08 pCi/g <0.06 pCi/g <0.06 pCi/g <0.06 pCi/g <0.10 pCi/g Min <0.05 pCi/g <0.05 pCi/g <0.05 pCi/g <0.06 pCi/g <0.06 pCi/g <0.07 pCi/g Standard Deviation N/A  N/A  N/A  N/A  N/A  N/A  Surface Scans    % Scanned 25%  27%  25%  # of Alarms 0  0  4  Mean Scan 1,224 cpm 1,681 cpm 2,977 cpm Max Scan 1,967 cpm 2,379 cpm 8,706 cpm Notes    1) 13 judgmental locations. 2) Subsurface soil samples taken to 1-meter. 1) 13 judgmental locations. 2) Subsurface soil samples taken to 1-meter. 1) 13 judgmental and 2 investigative locations. 2) Subsurface soil samples taken to 1-meter. 2489 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-153 Table 2-3129 Impacted Class 3 Open Land Survey Units - Characterization Survey Summary (continued) 2490 Survey Unit 10204 10205 10206 Surface Area  7,228.10 m2  54,573.00 m2  10,529.10 m2 Description North Gate Area Switchyard Station Construction Area Surface Soil Samples Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Samples  18  18  32  32  19  19  # >MDC  0  1  0  0  0  0  Mean <0.07 pCi/g 0.11 pCi/g <0.05 pCi/g <0.07 pCi/g <0.04 pCi/g <0.05 pCi/g Median <0.05 pCi/g 0.11 pCi/g <0.05 pCi/g <0.07 pCi/g <0.05 pCi/g <0.05 pCi/g Max <0.46 pCi/g 0.11 pCi/g <0.08 pCi/g <0.09 pCi/g <0.12 pCi/g <0.08 pCi/g Min <0.02 pCi/g 0.11 pCi/g <0.05 pCi/g <0.05 pCi/g <0.02 pCi/g <0.01 pCi/g Standard Deviation N/A  N/A  N/A  N/A  N/A  N/A  Subsurface Soil Samples Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Measurements  2  2  0  0  2  2  # >MDC  0  0  0  0  0  0  Mean <0.05 pCi/g <0.08 pCi/g N/A pCi/g N/A pCi/g <0.05 pCi/g <0.05 pCi/g Median <0.05 pCi/g <0.08 pCi/g N/A pCi/g N/A pCi/g <0.05 pCi/g <0.05 pCi/g Max <0.06 pCi/g <0.11 pCi/g N/A pCi/g N/A pCi/g <0.06 pCi/g <0.05 pCi/g Min <0.05 pCi/g <0.06 pCi/g N/A pCi/g N/A pCi/g <0.05 pCi/g <0.05 pCi/g Standard Deviation N/A  N/A  N/A  N/A  N/A  N/A  Surface Scans    % Scanned 26%  10%  27%  # of Alarms 2  1  2  Mean Scan 2,071 cpm 2,594 cpm 3,386 cpm Max Scan 5,437 cpm 6,246 cpm 7,406 cpm Notes    1) All samples were dried prior to analysis. 2) Subsurface soil samples taken to 1-meter. 1) Initial survey design called for 25% scan coverage. Scan suspended at 10% due to safety concerns. 2) Additional surface samples taken to compensate for loss of scan coverage. 1) All samples were dried prior to analysis. 2) Subsurface soil samples taken to 1-meter. 2491 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-154 Table 2-3129 Impacted Class 3 Open Land Survey Units - Characterization Survey Summary (continued) 2492 Survey Unit 10207 10208 10209 Surface Area  10,273.80 m2  11,821.00 m2  5,970.80 m2 Description North Warehouse Area South Warehouse Area Protected Area South of Gate House Surface Soil Samples Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Samples  19  19  33  33  13  13  # >MDA  0  0  0  0  0  1  Mean <0.05 pCi/g <0.07 pCi/g <0.04 pCi/g <0.05 pCi/g <0.05 pCi/g 0.12 pCi/g Median <0.05 pCi/g <0.07 pCi/g <0.04 pCi/g <0.05 pCi/g <0.05 pCi/g 0.12 pCi/g Max <0.09 pCi/g <0.12 pCi/g <0.06 pCi/g <0.08 pCi/g <0.11 pCi/g 0.12 pCi/g Min <0.02 pCi/g <0.02 pCi/g <0.01 pCi/g <0.01 pCi/g <0.03 pCi/g 0.12 pCi/g Standard Deviation N/A  N/A  N/A  N/A  N/A  N/A  Subsurface Soil Samples Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Measurements  2  2  3  3  2  2  # >MDC  0  0  0  0  0  0  Mean <0.06 pCi/g <0.06 pCi/g <0.06 pCi/g <0.08 pCi/g <0.07 pCi/g <0.07 pCi/g Median <0.06 pCi/g <0.06 pCi/g <0.06 pCi/g <0.09 pCi/g <0.07 pCi/g <0.07 pCi/g Max <0.07 pCi/g <0.07 pCi/g <0.07 pCi/g <0.10 pCi/g <0.09 pCi/g <0.08 pCi/g Min <0.05 pCi/g <0.06 pCi/g <0.06 pCi/g <0.04 pCi/g <0.06 pCi/g <0.07 pCi/g Standard Deviation N/A  N/A  N/A  N/A  N/A  N/A  Surface Scans    % Scanned 29%  34%  26%  # of Alarms 6  10  2  Mean Scan 5,688 cpm 3,274 cpm 2,281 cpm Max Scan 12,193 cpm 6,464 cpm 3,006 cpm Notes    1) All samples were dried prior to analysis. 2) Subsurface soil samples taken to 1-meter. 3) Elevated scan readings due to the presence of packaged radioactive material in vicinity during scan performance. 1) 8 judgmental and 3 investigative locations. 2) Subsurface soil samples taken to 1-meter. 1) 5 judgmental and 2 investigative locations. 2) Subsurface soil samples taken to 1-meter. 2493 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-155 Table 2-3129 Impacted Class 3 Open Land Survey Units - Characterization Survey Summary (continued) 2494 Survey Unit 10210 10211 10212A Surface Area  5,593.90 m2  3,198.30 m2  12,225.70 m2 Description Protected Area South of Turbine Building SE Corner Protected Area - Lakeshore North Protected Area Fence - Lakeshore Surface Soil Samples Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Samples  17  17  16  16  32  32  # >MDC  0  0  0  1  0  6  Mean <0.04 pCi/g <0.05 pCi/g <0.04 pCi/g 0.02 pCi/g <0.04 pCi/g 0.11 pCi/g Median <0.04 pCi/g <0.05 pCi/g <0.04 pCi/g 0.02 pCi/g <0.04 pCi/g 0.10 pCi/g Max <0.05 pCi/g <0.07 pCi/g <0.06 pCi/g 0.02 pCi/g <0.10 pCi/g 0.14 pCi/g Min <0.01 pCi/g <0.02 pCi/g <0.01 pCi/g 0.02 pCi/g <0.01 pCi/g 0.09 pCi/g Standard Deviation N/A  N/A  N/A  N/A  N/A  0.02  Subsurface Soil Samples Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Measurements  3  3  2  2  32  32  # >MDC  0  0  0  0  0  1  Mean <0.07 pCi/g <0.08 pCi/g <0.04 pCi/g <0.08 pCi/g <0.04 pCi/g 0.08 pCi/g Median <0.07 pCi/g <0.08 pCi/g <0.04 pCi/g <0.08 pCi/g <0.04 pCi/g 0.08 pCi/g Max <0.08 pCi/g <0.09 pCi/g <0.05 pCi/g <0.09 pCi/g <0.06 pCi/g 0.08 pCi/g Min <0.06 pCi/g <0.07 pCi/g <0.02 pCi/g <0.07 pCi/g <0.01 pCi/g 0.08 pCi/g Standard Deviation N/A  N/A  N/A  N/A  N/A  N/A  Surface Scans    % Scanned 26%  30%  25%  # of Alarms 40  0  9  Mean Scan 2,686 cpm 2,619 cpm 5,363 cpm Max Scan 4,585 cpm 3,327 cpm 9,014 cpm Notes    1) High number of scan alarms due to improper set-point -area rescanned with no alarms. 2) 13 judgmental and 1 investigation sample location. 3) All subsurface samples taken to 1-meter depth, sample #01 - taken to 2-meter depth. 1) 13 judgmental and 1 investigative locations. 2) Subsurface soil samples taken to 1-meter. 1) 5 judgmental and 5 investigative locations. 2) Subsurface soil samples taken to 1-meter. 3) All judgmental samples analyzed for H-3, no activity detected greater than MDA. 2495 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-156 Table 2-3129 Impacted Class 3 Open Land Survey Units - Characterization Survey Summary (continued) 2496 Survey Unit 10213A 10214 10218A Surface Area  12,255.30 m2  33,551.40 m2  11,559.00 m2 Description Power House Area Construction Parking Lot ISFSI Area East Surface Soil Samples Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Samples  24  24  31  31  32  32  # >MDA  0  6  0  4  0  11  Mean <0.05 pCi/g 0.17 pCi/g <0.04 pCi/g 0.09 pCi/g <0.04 pCi/g 0.06 pCi/g Median <0.05 pCi/g 0.10 pCi/g <0.04 pCi/g 0.10 pCi/g <0.04 pCi/g 0.05 pCi/g Max <0.08 pCi/g 0.29 pCi/g <0.09 pCi/g 0.11 pCi/g <0.08 pCi/g 0.12 pCi/g Min <0.01 pCi/g 0.09 pCi/g <0.01 pCi/g 0.07 pCi/g <0.02 pCi/g 0.03 pCi/g Standard Deviation N/A  0.08  N/A  0.02  N/A  0.03  Subsurface Soil Samples Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Measurements  24  24  3  3  31  31  # >MDC  0  2  0  0  0  9  Mean <0.04 pCi/g 0.07 pCi/g <0.05 pCi/g <0.04 pCi/g <0.04 pCi/g 0.05 pCi/g Median <0.04 pCi/g 0.07 pCi/g <0.04 pCi/g <0.04 pCi/g <0.04 pCi/g 0.05 pCi/g Max <0.06 pCi/g 0.08 pCi/g <0.09 pCi/g <0.04 pCi/g <0.07 pCi/g 0.08 pCi/g Min <0.01 pCi/g 0.07 pCi/g <0.03 pCi/g <0.04 pCi/g <0.02 pCi/g 0.03 pCi/g Standard Deviation N/A  0.01  N/A  N/A  N/A  0.02  Surface Scans    % Scanned 25%  10%  50%  # of Alarms 3  2  29  Mean Scan 5,459 cpm 2,145 cpm 4,315 cpm Max Scan 9,798 cpm 3,798 cpm 7,440 cpm Notes    1) Subsurface soil samples taken to 1-meter. 1) Subsurface soil samples taken to 1-meter. 1) Area survey by ESCSG as stand-alone survey. 2) Scan alarms due to bkgd from adjacent radioactive material, area rescanned - no alarms. 3) Several samples analyzed for H-3, Fe-55, Ni-63 and Sr-90, no positive results > MDC. 2497 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-157 Table 2-3129 Impacted Class 3 Open Land Survey Units - Characterization Survey Summary (continued) 2498 Survey Unit 10218B 10218F 10219A Surface Area  11,559.00 m2  3,151.70 m2  2,433.20 m2 Description ISFSI Area East Area Near South of Switchyard Area Far South of Switchyard (Part A) Surface Soil Samples Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Samples  30  30  4  4  25  25  # >MDA  0  16  0  0  0  4  Mean <0.05 pCi/g 0.08 pCi/g <0.04 pCi/g <0.06 pCi/g <0.06 pCi/g 0.19 pCi/g Median <0.04 pCi/g 0.07 pCi/g <0.04 pCi/g <0.06 pCi/g <0.05 pCi/g 0.15 pCi/g Max <0.08 pCi/g 0.31 pCi/g <0.04 pCi/g <0.09 pCi/g <0.12 pCi/g 0.34 pCi/g Min <0.02 pCi/g 0.03 pCi/g <0.03 pCi/g <0.04 pCi/g <0.01 pCi/g 0.11 pCi/g Standard Deviation N/A  0.07  N/A  N/A  N/A  0.11  Subsurface Soil Samples Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Measurements  31  31  0  0  25  25  # >MDC  0  10  0  0  0  2  Mean <0.04 pCi/g 0.05 pCi/g N/A pCi/g N/A pCi/g <0.05 pCi/g 0.14 pCi/g Median <0.04 pCi/g 0.05 pCi/g N/A pCi/g N/A pCi/g <0.05 pCi/g 0.14 pCi/g Max <0.08 pCi/g 0.08 pCi/g N/A pCi/g N/A pCi/g <0.08 pCi/g 0.15 pCi/g Min <0.03 pCi/g 0.01 pCi/g N/A pCi/g N/A pCi/g <0.01 pCi/g 0.13 pCi/g Standard Deviation N/A  0.03  N/A  N/A  N/A  0.02  Surface Scans    % Scanned 50%  13%  50%  # of Alarms 21  0  27  Mean Scan 4,883 cpm 1,507 cpm 6,468 cpm Max Scan 6,897 cpm 1,964 cpm 7,671 cpm Notes    1) Area survey by ESCSG as stand-alone survey. 2) Scan alarms due to increase in ambient bkgd from adjacent radioactive material, area rescanned - no alarms. 3) Several samples analyzed for H-3, Fe-55, Ni-63 and Sr-90, no positive results > MDC. 1) Majority of surface area in survey unit occupied by ISFSI warehouse. 1) High number of scan alarms due to improper adjustment of set-point -readjusted and area rescanned with no alarms. 2) Subsurface soil samples taken to 1-meter. 3) Surface & subsurface biased samples analyzed for H-3, no activity detected > MDC. 2499 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-158 Table 2-3129 Impacted Class 3 Open Land Survey Units - Characterization Survey Summary (continued) 2500 Survey Unit 10219B 10220A 10220B Surface Area  7,515.70 m2  8,192.00 m2  8,271.20 m2 Description Area Far South of Switchyard (Part B) SE Corner of Exclusion Area - Lake Shore SE Corner of Exclusion Area - Inland Surface Soil Samples Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Samples  25  25  28  28  31  31  # >MDA  0  15  1  4  0  4  Mean <0.05 pCi/g 0.24 pCi/g 0.13 pCi/g 0.15 pCi/g <0.05 pCi/g 0.15 pCi/g Median <0.06 pCi/g 0.25 pCi/g 0.13 pCi/g 0.14 pCi/g <0.05 pCi/g 0.12 pCi/g Max <0.09 pCi/g 0.41 pCi/g 0.13 pCi/g 0.24 pCi/g <0.12 pCi/g 0.27 pCi/g Min <0.01 pCi/g 0.09 pCi/g 0.13 pCi/g 0.06 pCi/g <0.01 pCi/g 0.08 pCi/g Standard Deviation N/A  0.09  N/A  0.08  N/A  0.09  Subsurface Soil Samples Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Measurements  0  0  28  28  31  31  # >MDA  0  0  0  1  0  2  Mean N/A pCi/g N/A pCi/g <0.04 pCi/g 0.11 pCi/g <0.05 pCi/g 0.12 pCi/g Median N/A pCi/g N/A pCi/g <0.04 pCi/g 0.11 pCi/g <0.04 pCi/g 0.12 pCi/g Max N/A pCi/g N/A pCi/g <0.07 pCi/g 0.11 pCi/g <0.09 pCi/g 0.12 pCi/g Min N/A pCi/g N/A pCi/g <0.01 pCi/g 0.11 pCi/g <0.01 pCi/g 0.11 pCi/g Standard Deviation N/A  N/A  N/A  N/A  N/A  0.01  Surface Scans    % Scanned 11%  50%  50%  # of Alarms 3  2  18  Mean Scan 4,926 cpm 6,766 cpm 5,089 cpm Max Scan 6,355 cpm 9,830 cpm 10,221 cpm Notes    1) No subsurface soil samples taken in this survey unit. 2) 21 random and 4 investigation surface soil samples taken. 1) Subsurface soil samples taken to 1-meter. 2) Investigation samples taken in "wet-land" area. 3) Investigation samples analyzed for H-3, no activity detected greater than MDC. 1) Subsurface soil samples taken to 1-meter. 2) Investigation samples analyzed for H-3, no activity detected >MDC. 3) Sample location #12 not sampled due to safety concerns. 2501 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-159 Table 2-3129 Impacted Class 3 Open Land Survey Units - Characterization Survey Summary (continued) 2502 Survey Unit 10220C 10221A 10221B Surface Area  25,560.00 m2  6,273.60 m2  6,374.00 m2 Description SE Corner of Exclusion Area - Inland South of Protected Area - Lakeshore South of Protected Area - Inland Surface Soil Samples Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Samples  55  55  30  30  26  26  # >MDC  0  41  0  3  0  2  Mean <0.05 pCi/g 0.33 pCi/g <0.04 pCi/g 0.16 pCi/g <0.04 pCi/g 0.06 pCi/g Median <0.05 pCi/g 0.26 pCi/g <0.04 pCi/g 0.13 pCi/g <0.05 pCi/g 0.06 pCi/g Max <0.18 pCi/g 1.14 pCi/g <0.08 pCi/g 0.23 pCi/g <0.07 pCi/g 0.07 pCi/g Min <0.01 pCi/g 0.09 pCi/g <0.01 pCi/g 0.12 pCi/g <0.01 pCi/g 0.05 pCi/g Standard Deviation N/A  0.25  N/A  0.06  N/A  0.01  Subsurface Soil Samples Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Measurements  0  0  30  30  3  3  # >MDC  0  0  0  1  0  0  Mean N/A pCi/g N/A pCi/g <0.03 pCi/g 0.04 pCi/g <0.04 pCi/g <0.07 pCi/g Median N/A pCi/g N/A pCi/g <0.04 pCi/g 0.04 pCi/g <0.02 pCi/g <0.07 pCi/g Max N/A pCi/g N/A pCi/g <0.05 pCi/g 0.04 pCi/g <0.08 pCi/g <0.09 pCi/g Min N/A pCi/g N/A pCi/g <0.01 pCi/g 0.04 pCi/g <0.02 pCi/g <0.05 pCi/g Standard Deviation N/A  N/A  N/A  N/A  N/A  N/A  Surface Scans    % Scanned 14%  50%  26%  # of Alarms 9  0  2  Mean Scan 6,037 cpm 5,053 cpm 3,053 cpm Max Scan 8,418 cpm 9,970 cpm 6,464 cpm Notes    1) Extensive investigation of Bull Creek, where elevated Cs-137 soil sample was located. 2) Investigation concluded that elevated Cs-137 due to concentration of global fallout. 3) Investigation samples 10 thru 20 taken outside of survey unit. 1) Portion of survey unit surveyed by ESCSG as part of "rail spur" survey. 2) Subsurface soil samples taken to 1-meter. 1) Portion of survey unit surveyed by ESCSG as part of "rail spur" survey. 2) Subsurface soil samples taken to 1-meter. 3) Subsurface sample #12 labeled as "QC" sample when actually taken as random sample. 2503 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-160 Table 2-3129 Impacted Class 3 Open Land Survey Units - Characterization Survey Summary (continued) 2504 Survey Unit 10222 10223 10224 Surface Area  21,777.80 m2  12,371.40 m2  14,607.70 m2 Description North Beach Area Power Block Beach Area South Beach Area Surface Soil Samples Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Samples  30  30  20  20  22  22  # >MDC  0  0  0  0  0  0  Mean <0.05 pCi/g <0.06 pCi/g <0.06 pCi/g <0.06 pCi/g <0.04 pCi/g <0.07 pCi/g Median <0.05 pCi/g <0.06 pCi/g <0.06 pCi/g <0.06 pCi/g <0.05 pCi/g <0.07 pCi/g Max <0.08 pCi/g <0.09 pCi/g <0.07 pCi/g <0.08 pCi/g <0.07 pCi/g <0.08 pCi/g Min <0.02 pCi/g <0.03 pCi/g <0.02 pCi/g <0.02 pCi/g <0.02 pCi/g <0.04 pCi/g Standard Deviation N/A  N/A  N/A  N/A  N/A  N/A  Subsurface Soil Samples Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Measurements  45  45  21  21  24  24  # >MDC  0  0  0  0  0  1  Mean <0.04 pCi/g <0.05 pCi/g <0.04 pCi/g <0.05 pCi/g <0.04 pCi/g 0.03 pCi/g Median <0.04 pCi/g <0.05 pCi/g <0.04 pCi/g <0.05 pCi/g <0.04 pCi/g 0.03 pCi/g Max <0.06 pCi/g <0.07 pCi/g <0.06 pCi/g <0.08 pCi/g <0.07 pCi/g 0.03 pCi/g Min <0.01 pCi/g <0.03 pCi/g <0.02 pCi/g <0.03 pCi/g <0.01 pCi/g 0.03 pCi/g Standard Deviation N/A  N/A  N/A  N/A  N/A  N/A  Surface Scans    % Scanned 56%  50%  52%  # of Alarms 102  0  0  Mean Scan 2,139 cpm 1,788 cpm 2,744 cpm Max Scan 4,316 cpm 2,277 cpm 3,400 cpm Notes    1) "Black Beauty" sand-blasting sand cause of elevated scans alarms investigation soil samples taken. 2) Analysis of investigation samples indicate natural U & Th 3) Subsurface soil samples taken to 3-meters. 1) Subsurface soil samples taken to 3-meters. 1) Subsurface soil samples taken to 3-meters. 2505 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-161 Table 2-3129 Impacted Class 3 Open Land Survey Units - Characterization Survey Summary (continued) 2506 Survey Unit 10301 VCC Surface Area  55,941.60 m2  15,364.00 m2 Description West Training Area Vertical Concrete Cask Construction Area Surface Soil Samples Co-60 Cs-137 Co-60 Cs-137 # of Samples  22  22  30  30  # >MDA  0  11  0  7  Mean <0.05 pCi/g 0.17 pCi/g <0.04 pCi/g 0.04 pCi/g Median <0.06 pCi/g 0.14 pCi/g <0.04 pCi/g 0.04 pCi/g Max <0.08 pCi/g 0.39 pCi/g <0.08 pCi/g 0.08 pCi/g Min <0.02 pCi/g 0.06 pCi/g <0.03 pCi/g 0.03 pCi/g Standard Deviation N/A  0.12  N/A  0.02  Subsurface Soil Samples ISOCS Cs-137 Co-60 Cs-137 # of Measurements    46  30  30  # >MDC    7  0  3  Mean  0.18 pCi/g <0.05 pCi/g 0.04 pCi/g Median  0.19 pCi/g <0.04 pCi/g 0.03 pCi/g Max  0.25 pCi/g <0.10 pCi/g 0.06 pCi/g Min  0.11 pCi/g <0.02 pCi/g 0.03 pCi/g Standard Deviation  0.05  N/A  0.02  Surface Scans  % Scanned 14%  20%  # of Alarms 23  0  Mean Scan 5,433 cpm 5,192 cpm Max Scan 9,499 cpm 9,240 cpm Notes    1) No subsurface soil samples taken in this survey unit. 2) 46 ISOCS measurements acquired. 1) Area survey by ESCSG as stand-alone survey - documented in separate report. 2) Subsurface soil samples taken to 1-meter. 3) Following survey, area was paved for use as VCC Construction Area. 2507 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-162 Table 2-30 Impacted Class 2 Open Land Survey Units - Characterization Survey Summary 2508 Survey Unit 12201 12202 12203 Surface Area  9,610.40 m2  7,573.90 m2  7,568.70 m2 Description North Restricted Area Yard Gate House and Southwest Yard Under Service Building and South East Yard Surface Soil Samples Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Samples  15  15  16  16  15  15  # >MDC  0  2  0  1  0  3  Mean <0.06 pCi/g 0.15 pCi/g <0.06 pCi/g 0.12 pCi/g <0.06 pCi/g 0.15 pCi/g Median <0.07 pCi/g 0.15 pCi/g <0.06 pCi/g 0.12 pCi/g <0.06 pCi/g 0.18 pCi/g Max <0.10 pCi/g 0.17 pCi/g <0.09 pCi/g 0.12 pCi/g <0.10 pCi/g 0.18 pCi/g Min <0.02 pCi/g 0.12 pCi/g <0.02 pCi/g 0.12 pCi/g <0.02 pCi/g 0.08 pCi/g Standard Deviation N/A  0.04  N/A  N/A  N/A  0.06  Subsurface Soil Samples Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Measurements  9  9  9  9  6  6  # >MDC  0  0  0  0  0  1  Mean <0.06 pCi/g <0.06 pCi/g <0.06 pCi/g <0.08 pCi/g <0.04 pCi/g 0.15 pCi/g Median <0.06 pCi/g <0.06 pCi/g <0.06 pCi/g <0.07 pCi/g <0.04 pCi/g 0.15 pCi/g Max <0.07 pCi/g <0.07 pCi/g <0.10 pCi/g <0.14 pCi/g <0.08 pCi/g 0.15 pCi/g Min <0.02 pCi/g <0.05 pCi/g <0.02 pCi/g <0.05 pCi/g <0.02 pCi/g 0.15 pCi/g Standard Deviation N/A  N/A  N/A  N/A  N/A  N/A  Surface Scans    % Scanned 66%  26%  45%  # of Alarms 4  12  1  Mean Scan 2,132 cpm 4,805 cpm 2,541 cpm Max Scan 3,611 cpm 11,264 cpm 5,677 cpm Notes    1) Subsurface soil samples taken to 3-meters. 1) Subsurface soil samples taken to 3-meters. 2) Elevated scans from RAM & systems in vicinity. 3) Sample #11 labeled as "QC" when actually random sample. 4) Scans performed under 2 sample plans. 1) Subsurface soil samples taken to 3-meters. 2) ~50% of surface area either obstructed or covered. 2509 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-163 Table 2-3230 Impacted Class 2 Open Land Survey Units - Characterization Survey Summary (continued) 2510 Survey Unit 10204 Surface Area  5,908.70 m2 Description Crib House Area Surface Soil Samples Co-60 Cs-137 # of Samples  13  13  # >MDC  0  6  Mean <0.08 pCi/g 0.15 pCi/g Median <0.08 pCi/g 0.14 pCi/g Max <0.10 pCi/g 0.21 pCi/g Min <0.07 pCi/g 0.12 pCi/g Standard Deviation N/A  0.04  Subsurface Soil Samples Co-60 Cs-137 # of Measurements  36  36  # >MDC  0  2  Mean <0.05 pCi/g 0.08 pCi/g Median <0.05 pCi/g 0.08 pCi/g Max <0.09 pCi/g 0.12 pCi/g Min <0.01 pCi/g 0.04 pCi/g Standard Deviation N/A  0.06  Surface Scans  % Scanned 30%  # of Alarms 102  Mean Scan 2,569 cpm Max Scan 6,203 cpm Notes  1) Subsurface soil samples taken to 3-meters. 2) Elevated scans from RAM & contaminated systems in vicinity. 2511 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-164 Table 2-31 Impacted Class 1 Open Land Survey Units - Characterization Survey Summary 2512 Survey Unit 12101 12102 12103 Surface Area  2,035.70 m2  2,024.50 m2  2,033.60 m2 Description WWTF Sludge Drying Bed Area WWTF Facility Unit 2 PWST/SST Area Surface Soil Samples Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Samples  13  13  13  13  13  13  # >MDC  0  2  0  4  0  2  Mean <0.05 pCi/g 0.19 pCi/g <0.04 pCi/g 0.32 pCi/g <0.06 pCi/g 0.39 pCi/g Median <0.06 pCi/g 0.19 pCi/g <0.05 pCi/g 0.25 pCi/g <0.07 pCi/g 0.39 pCi/g Max <0.09 pCi/g 0.21 pCi/g <0.06 pCi/g 0.70 pCi/g <0.09 pCi/g 0.46 pCi/g Min <0.02 pCi/g 0.17 pCi/g <0.02 pCi/g 0.09 pCi/g <0.03 pCi/g 0.33 pCi/g Standard Deviation N/A  0.03  N/A  0.28  N/A  0.09  Subsurface Soil Samples Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Measurements  38  38  38  38  39  39  # >MDC  0  1  0  0  1  0  Mean <0.06 pCi/g 0.08 pCi/g <0.06 pCi/g <0.08 pCi/g 0.10 pCi/g <0.06 pCi/g Median <0.06 pCi/g 0.08 pCi/g <0.06 pCi/g <0.08 pCi/g 0.10 pCi/g <0.06 pCi/g Max <0.13 pCi/g 0.08 pCi/g <0.10 pCi/g <0.16 pCi/g 0.10 pCi/g <0.09 pCi/g Min <0.02 pCi/g 0.08 pCi/g <0.02 pCi/g <0.04 pCi/g 0.10 pCi/g <0.03 pCi/g Standard Deviation N/A  N/A  N/A  N/A  N/A  N/A  Surface Scans    % Scanned 100%  100%  100%  # of Alarms 27  83  232  Mean Scan 3,293 cpm 2,767 cpm 3,320 cpm Max Scan 35,962 cpm 10,759 cpm 30,660 cpm Notes    1) Subsurface soil samples taken to 3-meters. 2) Elevated scans from RAM & contaminated systems in vicinity. 3) No HTD analysis performed. 1) Subsurface soil samples taken to 3-meters. 2) Elevated scans from RAM &
contaminated systems in vicinity. 3) Surface soil sample #s 5, 7 & 8 sent to Eberline for HTD analysis. 1) Subsurface soil samples taken to 3-meters. 2) Elevated scans from RAM &
contaminated systems in vicinity. 3) Surface soil sample #s 12 & 13 and subsurface sample # 8 sent to Eberline for HTD analysis. 2513 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-165 Table 2-3331 Impacted Class 1 Open Land Survey Units - Characterization Survey Summary (continued) 2514 Survey Unit 12104 12109 12110 Surface Area  1940.3 m2  1930.5 m2  1739.7 m2 Description Area Under and North of Unit 2 CTMT Area Under and South of Unit 1 CTMT Yard Between U1 CTMT and TB Surface Soil Samples Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Samples  1  1  16  16  13  13  # >MDC  0  0  14  16  0  6  Mean <0.10 pCi/g <0.05 pCi/g 0.13 pCi/g 0.18 pCi/g <0.05 pCi/g 0.12 pCi/g Median <0.10 pCi/g <0.05 pCi/g 0.06 pCi/g 0.14 pCi/g <0.05 pCi/g 0.11 pCi/g Max <0.10 pCi/g <0.05 pCi/g 1.04 pCi/g 0.59 pCi/g <0.08 pCi/g 0.27 pCi/g Min <0.10 pCi/g <0.05 pCi/g 0.02 pCi/g 0.05 pCi/g <0.03 pCi/g 0.03 pCi/g Standard Deviation N/A  N/A  0.26  0.13  N/A  0.08  Subsurface Soil Samples Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Measurements  9  9  15  15  24  24  # >MDC  0  0  0  1  0  2  Mean <0.06 pCi/g <0.07 pCi/g <0.05 pCi/g 0.08 pCi/g <0.07 pCi/g 0.27 pCi/g Median <0.06 pCi/g <0.07 pCi/g <0.05 pCi/g 0.08 pCi/g <0.07 pCi/g 0.27 pCi/g Max <0.10 pCi/g <0.09 pCi/g <0.08 pCi/g 0.08 pCi/g <0.09 pCi/g 0.30 pCi/g Min <0.02 pCi/g <0.05 pCi/g <0.03 pCi/g 0.08 pCi/g <0.03 pCi/g 0.24 pCi/g Standard Deviation N/A  N/A  N/A  N/A  N/A  0.05  Surface Scans    % Scanned On date, April 16, 2013, survey unit was not scanned due to prohibitive background from adjacent systems and stored RAM. Soil sample locations were biased based upon visual cues & opportune accessibility Survey unit was not scanned. On date, April 14, 2013, area posted as "Radiation Area" for loading RAM on rail cars. Radiation area will remain until commodity removal is complete. Soil sample locations were biased based upon visual cues & accessibility. Survey unit was not scanned. On date, April 25, 2013, area posted as "Radiation Area" for loading RAM on rail cars. Radiation area will remain until commodity removal is complete. Soil sample locations were biased based upon visual cues & accessibility. # of Alarms Mean Scan Max Scan  Notes    1) Subsurface soil samples taken to 3-meters. 2) No surface soil samples were taken at locations 2 and 3 as surface was covered with concrete. 1) Subsurface soil samples taken to 3-meters. 2) No surface soil samples were taken at locations 1 thru 4 as surface was covered with concrete. 3) SS #5 sent to Eberline for HTD analysis. 1) Subsurface soil samples taken to 3-meters. 2) SB sample #5 - no soil, SB sample #7 limited to 1-meter and SB sample #4 limited to 2-meter due to refusal. 3) No samples collected at 11, 12 & 13 due to potential ACM. 2515 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-166 Table 2-3331 Impacted Class 1 Open Land Survey Units - Characterization Survey Summary (continued) 2516 Survey Unit 12111 12112 12113 Surface Area  1964.3  1692.6 m2  1,657.60 m2 Description South Yard Area NE of Gate House Unit 1 PWST/SST Area East Unit 1 PWST/SST Area West Surface Soil Samples Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Samples  13  13  14  14  15  15  # >MDC  0  10  0  9  0  9  Mean <0.07 pCi/g 0.15 pCi/g <0.08 pCi/g 0.82 pCi/g <0.08 pCi/g 0.12 pCi/g Median <0.10 pCi/g 0.14 pCi/g <0.08 pCi/g 0.23 pCi/g <0.08 pCi/g 0.10 pCi/g Max <0.10 pCi/g 0.20 pCi/g <0.12 pCi/g 3.39 pCi/g <0.11 pCi/g 0.22 pCi/g Min <0.05 pCi/g 0.12 pCi/g <0.02 pCi/g 0.07 pCi/g <0.06 pCi/g 0.06 pCi/g Standard Deviation N/A  0.03  N/A  1.19  N/A  0.06  Subsurface Soil Samples Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 # of Measurements  42  42  39  39  39  39  # >MDC  0  1  0  2  0  0  Mean <0.05 pCi/g 0.04 pCi/g <0.05 pCi/g 0.45 pCi/g <0.07 pCi/g <0.07 pCi/g Median <0.05 pCi/g 0.04 pCi/g <0.05 pCi/g 0.45 pCi/g <0.07 pCi/g <0.07 pCi/g Max <0.08 pCi/g 0.04 pCi/g <0.07 pCi/g 0.70 pCi/g <0.10 pCi/g <0.12 pCi/g Min <0.03 pCi/g 0.04 pCi/g <0.02 pCi/g 0.19 pCi/g <0.03 pCi/g <0.04 pCi/g Standard Deviation N/A  N/A  N/A  0.36  N/A  N/A  Surface Scans    % Scanned Survey unit was not scanned. On date, April 1, 2013, area posted as "Radiation Area" for loading RAM on rail cars. Radiation area will remain until commodity removal is complete. Soil sample locations were biased based upon visual cues & accessibility. 100%  100%  # of Alarms 98  106  Mean Scan 3,483 cpm 3,943 cpm Max Scan 5,225 cpm 7,562 cpm        Notes    1) Subsurface soil samples taken to 3-meters. 2) SS #s 11, 12 & 13 - asphalt. 3) SS #s 1, 3 7 4, additional        1-meter sample taken. 4) No SS samples collected at 13, 14 & 15 due to safety concerns. 1) Subsurface soil samples taken to 3-meters. 2) Elevated scans from RAM & contaminated systems in vicinity. 3) SS #s 1 & 2 - asphalt. 4) SS #s 4 & 6 sent to Eberline for HTD analysis. 1) Subsurface soil samples taken to 3-meters. 2) Elevated scans from RAM & contaminated systems in vicinity. 2517 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-167 Table 2-32 Surface and Subsurface Soil Samples - Eberline Laboratory Analysis 2518 Radionuclide L1-12102-CJGSSS-0510 (pCi/g) L1-12102-CJGSSS-0710 (pCi/g) L1-12102-CJGSSS-0810 (pCi/g) L1-12102-CQGSSS-0810 (pCi/g) L1-12103-CJGSSS-1210 (pCi/g) L1-12103-CJGSSS-1310 (pCi/g) L1-12109-CJGS-050-SS (pCi/g) L1-12112-CJGSSS-0410 (pCi/g) L1-12112-CJGSSS-0610 (pCi/g) L1-12103-CJGSSB-0821 (pCi/g) H-3 2.51E+00 2.73E+00 2.54E+00 2.48E+00 2.50E+008.39E-01 2.51E+00 3.96E+00 3.56E+00 3.61E+00 2.69E+00 C-14 8.52E-01 8.10E-01 9.49E-01 8.76E-01 8.39E-013.36E+00 8.51E-01 1.01E+00 1.07E+00 9.26E-01 9.56E-01 Fe-55 3.53E+00 3.19E+00 3.24E+00 3.47E+00 3.36E+007.40E+00 3.06E+00 N/A 7.16E+00 6.34E+00 3.24E+00 Ni-59 7.28E+00 7.23E+00 6.65E+00 6.30E+00 7.40E+004.29E-02 6.30E+00 N/A 6.12E+00 7.71E+00 5.69E+00 Co-60 4.82E-02 4.52E-02 3.00E-02 3.22E-02 4.29E-026.21E-01 4.29E-02 2.43E-01 8.80E-02 1.22E-01 3.98E-02 Ni-63 6.22E-01 7.06E-01 6.24E-01 6.41E-01 6.21E-012.67E-01 6.26E-01 1.77E+00 8.36E-01 7.95E-01 6.10E-01 Sr-90 2.90E-01 3.15E-01 2.35E-01 2.99E-01 2.67E-012.92E-02 3.33E-01 4.70E-01 3.76E-01 3.59E-01 2.95E-01 Nb-94 3.35E-02 2.64E-02 2.21E-02 2.40E-02 2.92E-024.43E-01 2.85E-02 5.35E-02 7.05E-02 7.16E-02 2.83E-02 Tc-99 4.03E-01 4.38E-01 4.20E-01 3.95E-01 4.43E-012.97E-02 4.18E-01 2.61E-01 2.61E-01 2.62E-01 6.39E-01 Ag-108m 2.95E-02 3.05E-02 2.03E-02 2.21E-02 2.97E-028.03E-02 2.91E-02 4.89E-02 7.14E-02 7.52E-02 2.62E-02 Sb-125 9.26E-02 8.40E-02 6.11E-02 6.35E-02 8.03E-022.78E-02 8.44E-02 1.68E-01 2.19E-01 2.90E-01 7.13E-02 Cs-134 2.92E-02 2.91E-02 2.24E-02 2.41E-02 2.78E-022.63E-02 2.85E-02 6.04E-02 7.72E-02 9.92E-02 2.72E-02 Cs-137 6.98E-01 3.85E-01 7.98E-02 8.86E-02 3.15E-01 4.57E-01 1.57E-01 2.30E+00 3.39E+00 3.31E-02 Pm-147 5.09E-01 5.06E-01 5.03E-01 5.04E-01 4.90E-011.67E-01 5.00E-01 N/A 2.74E-01 2.63E-01 5.02E-01 Eu-152 1.84E-01 2.13E-01 1.61E-01 1.83E-01 1.67E-018.26E-02 1.76E-01 1.60E-01 6.27E-01 4.74E-01 2.27E-01 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-168 Eu-154 1.16E-01 9.27E-02 7.38E-02 7.90E-02 8.26E-027.11E-02 1.10E-01 8.00E-02 2.23E-01 2.66E-01 9.19E-02 Eu-155 7.42E-02 8.00E-02 6.40E-02 6.32E-02 7.11E-022.01E-02 7.83E-02 1.43E-01 1.87E-01 2.12E-01 7.41E-02 Np-237 2.43E-02 2.42E-02 2.37E-02 3.22E-02 2.01E-023.83E-02 2.35E-02 N/A 7.80E-02 7.14E-02 2.58E-02 Pu-238 5.78E-02 3.45E-02 3.33E-02 3.34E-02 3.83E-023.83E-02 4.30E-02 9.30E-02 7.45E-02 3.95E-02 4.52E-02 Pu-239/240 6.53E-02 4.71E-02 3.33E-02 3.02E-02 3.83E-026.56E+00 3.88E-02 6.25E-02 6.87E-02 4.49E-02 4.52E-02 Pu-241 8.31E+00 6.13E+00 5.20E+00 5.05E+00 6.56E+003.57E-02 6.55E+00 N/A 4.89E-01 5.10E-01 7.84E+00 Am-241 6.19E-02 2.91E-02 4.90E-02 3.78E-02 3.57E-027.03E-02 3.45E-02 4.61E-02 8.29E-02 5.50E-02 4.58E-02 Am-243 3.33E-02 3.90E-02 3.80E-02 4.10E-02 7.03E-023.44E-02 4.30E-02 N/A 4.51E-02 5.67E-02 4.10E-02 Cm-243/244 5.74E-02 5.40E-02 2.80E-02 4.09E-02 3.44E-028.39E-01 5.40E-02 N/A 1.22E-01 6.94E-02 3.80E-02 a Bold values indicate concentration greater than MDC. Italicized values indicate MDC value.2519 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-169  Figure 2-1 Zion Nuclear Power Station Owner Controlled Area 2520  2521 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-170  Figure 2-2 Zion Nuclear Power Station Radiologically Restricted Area (RRA) 2522  2523 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-171  Figure 2-3 Zion Nuclear Power Station Security Restricted Area 2524  2525 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-172  Figure 2-4 Non-Impacted Open Land Survey Units 2526 2527 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-173  Figure 2-5 Class 3 Open Land Survey Units Outside of "Radiologically-Restricted Area" 2528 2529 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-174  Figure 2-6 Class 3 Open Land Survey Units Inside of "Radiologically-Restricted Area" 2530 2531 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-175  Figure 2-7 Class 1 and Class 2 Open Land Survey Units 2532 2533 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-176  Figure 2-8 Unit 1 Containment 568 foot el. Class 1 Survey Units 2534 2535 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-177  Figure 2-9 Unit 1 Containment 541 foot el. Class 1 Survey Units 2536 2537 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-178  Figure 2-10 Unit 2 Containment 568 foot el. Class 1 Survey Units 2538 2539 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-179  Figure 2-11 Unit 2 Containment 541 foot el. Class 1 Survey Units 2540 2541 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-180  Figure 2-12 Auxiliary Building 542 foot el. Class 1 Survey Units 2542 2543 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-181  Figure 2-13 Auxiliary Building 560 foot el. Class 1 Survey Units 2544 2545 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-182  Figure 2-14 Auxiliary Building 579 foot el. Class 1 Survey Units 2546 2547 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-183  Figure 2-15 Turbine Building 560 and 570 Foot Elevations Class 2 Survey Units 2548  2549 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 0 2-184 Figure 2-16 Crib House Suction Forebay Class 2 Survey Units 2550 2551 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-185  Figure 2-17 Independent Spent Fuel Storage Installation 2552 2553 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-186  Figure 2-18 Vertical Concrete Cask Construction Area 2554 2555 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-187  Figure 2-19 Energy Solutions Background Study Locations 2556 2557 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-188  Figure 2-20 Zion City Park District's "Hosah Park" Background Study Location 2558 2559 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-189  Figure 2-21 Unit 1 Containment 568 foot el. Concrete Core Sample Locations 2560 2561 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-190  Figure 2-22 Unit 1 Containment 541 foot el. Concrete Core Sample Locations 2562 2563 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-191  Figure 2-23    Unit 2 Containment 568 foot el. Concrete Core Sample Locations 2564 2565 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-192  Figure 2-24 Unit 2 Containment 541 foot el. Concrete Core Sample Locations 2566 2567 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-193  Figure 2-25 Auxiliary Building 542 foot el. Concrete Core Sample Locations 2568 2569 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-194  2570 Figure 2-26 Turbine Building 560 foot el. and Steam Tunnel 570 foot el. Concrete Core Sample Locations 2571  2572 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-195 Figure 2-27 Turbine Building 560 foot el. Floor Drain System Sediment Sample Locations 2573 2574 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-196 Figure 2-28 Non-Impacted Open Land Survey Units Measurement and Sample Locations 2575 2576 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-197 Figure 2-29 Class 3 Open Land Survey Units Located Outside of the  2577 "Radiologically-Restricted Area"Measurement and Sample Locations 2578 2579 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-198 Figure 2-30 Class 3 Open Land Survey Units Located Inside of the  2580 "Radiologically-Restricted Area" Measurement and Sample Locations 2581 2582 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-199 Figure 2-31 Class 2 Open Land Survey Units Measurement and Sample Locations 2583  2584 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-200 Figure 2-32 Class 1 Open Land Survey Units Measurement and Sample Locations 2585 2586 ZION STATION RESTORATION PROJECT LICENSE TERMINATION PLAN  REVISION 1 2-201 Figure 2-33 ZNPS Locations of Outfalls, Groundwater Monitoring Wells and Surface Water Sampling Locations 2587  2588 
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Latest revision as of 16:20, 8 January 2025

LTP Ch 2 Rev 1 022017 L
ML17208A122
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Site: Zion  File:ZionSolutions icon.png
Issue date: 02/27/2017
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