ML19295G699

Revised Final Status Survey (FSS) Report - Phase 2, Unit 2 Containment Basement Survey Units 02100/02110

ML19295G699
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	09/30/2019
From:	ZionSolutions
To:	Office of Nuclear Material Safety and Safeguards
Shared Package
ML19295G627	List: ML19295G587 ML19295G611 ML19295G612 ML19295G617 ML19295G621 ML19295G625 ML19295G670 ML19295G674 ML19295G699 ML19295G702 ML19295G705 ML19295G726 ML19295G728 ML19295G734 ML19295G738 ML19295G742 ML19295G747 ML19295G751 ML19295G758 ML19295G764 ML19295G768 ML19295G788 ML19295G791 ML19295G795 ML19295G816 ML19295G818 ML19295G820 ML19295G822 ML19295G826 ML19295G828 ML19295G831 ML19295G837 ML19295G841 ML19295G843 ML19295G846 ML19295G850 ML19295G853 ML19295G855 ML19295G857 ML19295G859 ML19295G863 ML19295G866 ML19295G870 ZS-2019-0090, Revised Final Status Survey (FSS) Report - Phase 2, Release Record - Waste Water Treatment Facility Survey Unit 09100
References
ZS-2019-0090
Download: ML19295G699 (190)

Text

ZION STATION RESTORATION PROJECT FINAL STATUS SURVEY RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100/02110

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 PREPARED BY / DATE: 2019-09-01 David Montt, Radiological Engineer REVIEWED BY / DATE: 2019-09-01 Robert Massengill, Radiological Engineer APPROVED BY / DATE: 2019-09-01 D. Wojtkowiak, C/LT Manager

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 TABLE OF CONTENTS

1. EXECUTIVE

SUMMARY

................................................................................................ 8

2. SURVEY UNIT DESCRIPTION ...................................................................................... 9

3. CLASSIFICATION BASIS.............................................................................................. 16

4. DATA QUALITY OBJECTIVES (DQO) ...................................................................... 37

5. SURVEY DESIGN ............................................................................................................ 41

6. SURVEY IMPLEMENTATION ..................................................................................... 65

7. SURVEY RESULTS ......................................................................................................... 68

8. QUALITY CONTROL..................................................................................................... 90

9. INVESTIGATIONS AND RESULTS ............................................................................. 90

10. REMEDIATION AND RESULTS .................................................................................. 91

11. CHANGES FROM THE FINAL STATUS SURVEY PLAN ....................................... 91

12. DATA QUALITY ASSESSMENT (DQA) ..................................................................... 94

13. ANOMALIES .................................................................................................................... 94

14. COMPLIANCE EQUATION .......................................................................................... 94

15. CONCLUSION ................................................................................................................. 97

16. REFERENCES .................................................................................................................. 98

17. ATTACHMENTS ............................................................................................................. 98 ATTACHMENT 1 .............................................................................................................. 99 ATTACHMENT 2 ............................................................................................................ 107 ATTACHMENT 3 ............................................................................................................ 152 ATTACHMENT 4 ............................................................................................................ 158 ATTACHMENT 5 ............................................................................................................ 171 ATTACHMENT 6 ............................................................................................................ 189 ATTACHMENT 7 ............................................................................................................ 190

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 LIST OF FIGURES Figure 1 - Containment Layout ....................................................................................................... 11 Figure 2 - Unit 2 Containment 565 Elevation ................................................................................ 12 Figure 3 - Unit 2 Containment Under Vessel ................................................................................. 13 Figure 4 - Unit 2 Containment Incore Tunnel ................................................................................ 14 Figure 5 - Unit 2 Containment Sloped Tunnel................................................................................ 15 Figure 6 - Unit 2 Containment 568 Foot Elevation Concrete Core Sample Locations .................. 22 Figure 7 - Unit 2 Containment 541 Foot Elevation Concrete Core Sample Locations .................. 23 Figure 8 - Unit 2 Containment Continuing Characterization Concrete Core Sample Locations... 25 Figure 9 - Unit 2 Containment FSS Confirmatory Concrete Core Sample Locations.................... 47 Figure 10 - Unit 2 Under Vessel Incore Tunnel Remediation ........................................................ 67 Figure 11 - ISOCS Measurements of Unit 2 Containment Above 565 Foot Elevation.................. 70 Figure 12 - Unit 2 Containment Above 565 Foot Elevation FSS Floor Measurement Locations .. 71 Figure 13 - Unit 2 Containment Above 565 Foot Elevation FSS Wall Measurement Locations ... 72 Figure 14 - Unit 2 Under Vessel Concrete H-3 Concrete Remediation Area ................................. 82 Figure 15 - Unit 2 Containment Under Vessel FSS Measurement Locations ................................ 83 Figure 16 - Unit 2 Containment Under Vessel ORISE FSS Confirmatory Locations.................... 88 LIST OF TABLES Table 1 - Unit 2 Containment 568 Foot Elevation Concrete Core Sample Analysis Summary ..... 19 Table 2 - Unit 2 Containment 541 Foot Elevation Concrete Core Sample Analysis Summary ..... 20 Table 3 - Unit 2 Containment Concrete Core Samples - Eberline Laboratory Analysis ............... 21 Table 4 - Unit 2 Containment Continuing Characterization Concrete Core Samples - On-Site Analysis ........................................................................................... 26 Table 5 - Unit 2 Containment Continuing Characterization Concrete Core Samples - Eberline Laboratory Analysis ....................................................................... 34 Table 6 - HTD Ratios Based on Continuing Characterization Concrete Core Samples ................. 35 Table 7 - Dose Significant Radionuclides and Mixture .................................................................. 38 Table 8 - Base Case DCGLs for Containment Basements (BcDCGLB) from LTP Chapter 5, Table 5-3 ............................................................................................... 40 Table 9 - Operational DCGLs (OpDCGLB) for Containment Basements (pCi/m2) from LTP Chapter 5, Table 5-4 ............................................................................................... 40 Table 10 - Number of ISOCS Measurements per FSS Unit based on Areal Coverage .................. 42 Table 11 - Adjusted Minimum Number of ISOCS Measurements per FSS Unit........................... 43 Table 12 - Surrogate Ratios for Containment ................................................................................. 44 Table 13 - FSS Confirmation Concrete Core Sample Analysis - Grade to 0.5 inch Depth ........... 48 Table 14 - FSS Confirmation Concrete Core Sample Analysis - Concentrations at Depth ........... 55

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 15 - FSS Confirmation Concrete Core Sample Analysis Surrogate Ratios .......................... 58 Table 16 - Unit 2 Containment Under Vessel Concrete Area, Volume and Dimensions ............... 59 Table 17 - Unit 2 Containment Under Vessel Concrete HTD Inventory and Dose Based on FSS Confirmatory Core Samples .................................................................. 60 Table 18 - Unit 2 Containment Under Vessel FSS Confirmatory Core Samples Measured HTD Concentrations and SOF ..................................................................... 63 Table 19 - Investigation Levels....................................................................................................... 64 Table 20 - Synopsis of Survey Design ............................................................................................ 65 Table 21- Unit 2 Containment Above 565 ft. Elevation - Measured Concentrations of ROC for FSS ............................................................................................................. 73 Table 22 - Unit 2 Containment Above 565 ft. Elevation - Statistical Quantities - Systematic Measurement Population .............................................................................................. 79 Table 23 - Unit 2 Containment Under Vessel Area - Measured Concentrations of ROC for FSS .......................................................................................................................... 84 Table 24 - Unit 2 Containment Under Vessel Area - Statistical Quantities - Systematic Measurement Population .............................................................................................. 87 Table 25 - Unit 2 Containment Under Vessel Area - Post H-3 Concrete Removal Concrete Core Results................................................................................................... 89

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 LIST OF ACRONYMS AND ABBREVIATIONS ALARA As Low As Reasonably Achievable AMCG Average Member of the Critical Group BcDCGL Base Case Derived Concentration Guideline Level BcSOF Base Case Sum of Fractions BFM Basement Fill Model C/LT Characterization/License Termination CP Circular Plane DCGL Derived Concentration Guideline Level DQA Data Quality Assessment DQO Data Quality Objective DRL Depth Relaxation Length EMC Elevated Measurement Comparison ECP Exponential Circular Plane FOV Field-of-View FSS Final Status Survey GW Groundwater IC Insignificant Contributor ISOCS In Situ Object Counting System HTD Hard-to-Detect LTP License Termination Plan LBGR Lower Bound of the Gray Region MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual MDC Minimum Detectable Concentration NRC Nuclear Regulatory Commission OpDCGL Operational Derived Concentration Guideline Level OpSOF Operational Sum of Fractions QAPP Quality Assurance Project Plan

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 QC Quality Control RE Radiological Engineer ROC Radionuclides of Concern SOF Sum of Fractions ORISE Oak Ridge Institute for Science and Education TEDE Total Effective Dose Equivalent TSD Technical Support Document UBGR Upper Bound of the Gray Region UCL Upper Confidence Level ZNPS Zion Nuclear Power Station ZSRP Zion Station Restoration Project

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110

1. EXECUTIVE

SUMMARY

This Final Status Survey (FSS) Release Record for survey units 02100 and 02110, Unit 2 Containment Basement, has been generated for the Zion Station Restoration Project (ZSRP) in accordance with ZionSolutions procedure ZS-LT-300-001-005, Final Status Survey Data Reporting (Reference 1) and satisfies the requirements of Section 5.11 of the Zion Station Restoration Project License Termination Plan (LTP) (Reference 2).

The FSS package for the Unit 2 Containment Basement includes FSS design and FSS results for the following;

• B1-02100AF Unit 2 Containment above 565 foot

• B1-02110AF Unit 2 Containment Under Vessel Area Final Status Survey (FSS) sample plans for each of these survey units were developed in accordance with ZionSolutions procedure ZS-LT-300-001-001, Final Status Survey Package Development (Reference 3), the ZSRP LTP, and guidance from NUREG-1575, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM)

(Reference 4).

In accordance with ZSRP LTP Chapter 5, section 5.5.2.1.2 and Table 5-19, the Unit 2 Containment basement survey units have a MARSSIM classification of 1. Survey plans were designed based upon use of the Sign Test as the nonparametric statistical test for compliance. Both the Type I () and Type II () decision error rates were set at 0.05. The Canberra In Situ Object Counting System (ISOCS) was selected as the primary instrument used to perform FSS of the Containment basement survey units. As Class 1 survey units, ISOCS measurement locations were designated to ensure 100% areal coverage of all accessible structural surfaces within the survey units.

Based on a measurement Field-of-View (FOV) of 28 m2 for each ISOCS measurement, it was determined that one hundred and fifty-five (155) ISOCS measurements were required to ensure 100% areal coverage of the Containment above the 565 foot elevation (survey unit 02100) and nineteen (19) ISOCS measurements were identified to provide 100% areal coverage of the Under Vessel area (survey unit 02110).

Modifications to the designed sample plan were required based on the location of measurement center-points. It was determined that some measurement locations were not feasible due to physical constraints and alternate measurement locations were added.

After making those adjustments to the sample plan, a total of one hundred and sixty-four (164) ISOCS measurements were taken; sixty-eight (68) on the lower wall above 565 foot and ninety-six (96) on the floor (metal liner) and in the Cavity Flood Sump and the Recirculation Sump. In the Under Vessel area, additional measurements were required due to physical constraints caused by the limited space in the Incore Tunnel Area. A 3-

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 meter stand-off distance between the detector and the surface undergoing survey was not possible in all cases. Consequently, a total of fifty four (54) ISOCS measurements were required to ensure 100% areal coverage of the wall and floor surfaces in the Under Vessel and Incore Tunnel Area.

The final Radionuclides of Concern (ROC) for the decommissioning of Zion Nuclear Power Station (ZNPS) are Co-60, Cs-134 and Cs-137 (as well as Eu-152 and Eu-154 for Containment), which are gamma emitters and Ni-63, Sr-90 and H-3 (applicable only to Containment), which are Hard-to-Detect (HTD) radionuclides. LTP section 5.1 states that HTD concentrations will be inferred using a surrogate approach and that the maximum ratios from LTP Chapter 5, Table 5-15 will be used unless area-specific ratios as determined by actual survey data are derived.

The results for all ISOCS measurements taken in both survey units indicate that the Sum-of-Fractions (ee) for each measurement, considering the concentration of all applicable ROC, either by direct measurement or by inference, is less than one (1) when applying the respective Operational Derived Concentration Guideline Levels (OpDCGL) for the Containment Basements (ZionSolutions Technical Support Document (TSD)17-004, Operational Derived Concentration Guideline Levels for Final Status Survey

[Reference 5]). Therefore the null hypothesis is rejected and both of the Unit 2 Containment Basement survey units # 02100 and 02110 are acceptable for unrestricted release.

2. SURVEY UNIT DESCRIPTION The Unit 2 Containment Basement survey units 02100 and 02110 are impacted Class 1 basement FSS units. A basement FSS unit is comprised of the combined internal wall and floor surfaces of each remaining building basement below the 588 foot elevation following demolition. The FSS of the penetrations in the Unit 2 Containment Basement is documented in the Release Record for Survey Unit 02112. The Unit 2 Containment Basement structure is located within Class 1 open land survey units 12201, 12104 and 12105.

The basic decommissioning end-state configuration for the Unit 2 Containment Building is the walls and floors below 588 foot elevation. All concrete was removed from the interior side of the steel liner above the 565 foot elevation, leaving only the remaining exposed liner below the 588 foot elevation, the concrete in the Incore Instrument Shaft leading to and including the area under vessel (or Under Vessel area), and the structural concrete outside of the liner. The exposed metal liner was cleaned to levels below the OpDCGLs for basement structures (LTP Chapter 5, Table 5-4).

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 The large components inside each structure such as the Reactor Vessel, Pressurizer, Steam Generators, Reactor Coolant Pumps, primary piping and all associated systems were removed and disposed of as radioactive waste. The upper steel containment liner, the refuel cavity and all interior walls above the 588 foot elevation were also removed and disposed of as radioactive waste. The outer containment shells above the 588 foot elevation were surveyed and demolished. All waste material was packaged and sent offsite for disposal at approved disposal facilities for radioactive waste.

In accordance with the planned end-state configuration, the concrete floor of the 568 foot elevation was removed to expose the 1/2-inch steel liner. In this end-state configuration, FSS unit 02100 consisted of the interior side of the steel liner walls below the 588 foot elevation and the 565 foot elevation liner floor. The survey unit also contained the Cavity Flood Sump and the Recirculation Sump. The bottoms of both sumps were located at the 559 foot elevation.

Prior to remediation, the configuration of FSS unit 02110 included the concrete and embedded, 1/2-inch steel support rings interior to the steel liner below the 565 foot elevation of the Unit 2 Containment Building. The Under Vessel Area walls were 1 foot 11.5 inches thick, and the floor concrete was 2 foot 6 inches thick. The access tunnel had 1 foot 3 inch thick walls, floor, and roof. The embedded steel rings had supported equipment present in the Under Vessel area.

The Zion Station Restoration Project (ZSRP) performed extensive remediation of the concrete located in the Under Vessel area below the 565 foot elevation in Unit 2 Containment. Scabbling and hammering demolition techniques were used to remove at least six inches of concrete from the floor and walls located directly under the reactor vessel and at least six inches of concrete from the walls and sloped floor of the access tunnel. In some places, sufficient concrete was removed to expose the steel liner. Parts of the 1/2-inch steel support rings were also removed.

Also, during remediation, Pipe #P325, the Unit 2 Containment Incore Sump Drain header, which was embedded in the concrete of the tunnel walls, was completely removed and disposed of as radioactive waste. In the LTP, the Unit 2 Containment Incore Sump Drain header was to remain in the end-state however, due to the extensive amount of remediation of the concrete in the sloped tunnel, it became more cost effective to completely remove the pipe. Therefore, no dose will be assigned to the Unit 2 Containment Basement from embedded pipe 02111.

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Figure 1 - Containment Layout

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Figure 2 - Unit 2 Containment 565 Foot Elevation

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Figure 3 - Unit 2 Containment Under Vessel

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Figure 4 - Unit 2 Containment Incore Tunnel

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Figure 5 - Unit 2 Containment Sloped Tunnel

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110

3. CLASSIFICATION BASIS The Unit 2 Containment housed numerous systems containing primary coolant as well as radioactively contaminated support systems. System leakage and maintenance activities over the operating life of the reactor resulted in the radiological contamination of most of the interior surfaces of the structures. Some components, equipment, structural steel and concrete became radioactive due to neutron activation. Based on the building design basis and the operating history, all internal survey units in Unit 2 Containment Building were given an initial classification of Class 1 in accordance with the Zion Station Historical Site Assessment (HSA) (Reference 6).

Final Status Survey unit 02100 encompassed the Unit 2 Containment above the 565 foot elevation. The Unit 2 Containment structure housed the Unit 2 Reactor Vessel, Steam Generators and Pressurizer. The HSA noted several occasions of radioactive liquid spill events during plant operation.

Final Status Survey unit 02110 housed the Unit 2 Incore flux monitoring tubes and associated supports. This survey unit was the concrete structure around and beneath the reactor void space (565 foot elevation and below). It provided personnel access to the area under the reactor vessel and housed the Incore sump for collection and recovery of liquids released into the area.

The following summary of processes and incidents was obtained from the HSA:

• May 1980: Due to a valve connection error, a freeze seal was applied to a line connected to the Unit 2 refueling cavity. The freeze seal blew out, causing the spillage of ~2000 gallons of refueling cavity water into the lower portion of Unit 2 Containment (NRC IR 80-12/80-12).

• 08/24/1996 to 10/4/1996 Inspection: Discussion of unplanned spraying of ~3000 gallons of demineralized water into Unit 2 568 foot IMB (NRC IR 96-14/96-14).

• January 1997: 25-100 mR/hr General Area, 80,000 dpm/100cm2.

• 12/28/1976 to 03/08/1977: Inspection noted flaking paint in Unit 2 Containment (NRC IR -/77-11).

• 08/14/1984: The Containment exceeded the tech spec limit of 120 degrees F. Actual level reached 120.48 degrees F (LER 2-84-020).

• 06/09/1986: Flooding was noted in the Unit 2 Tendon Tunnels from a possible water main problem. On 06/13/1986, Tendon Tunnel drains backed up, supposedly from high lake water level (Zion RP/Decon Logs).

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110

• 06/27/1986: Unit 2 tripped due to lightning strike on one or more of the Containment lightning rods. The surge followed a path from Containment liner to ground via the electrical penetrations (LER 2-86-016 and NRC 86-13/86-12).

• 05/07/1990: During refueling, a piece of grid strap was observed falling from the assembly. All cladding appeared to remain intact (LER 2-90-006).

• 05/13/1992: Approximately 4200 gallons of RCS water was inadvertently sprayed into Containment though the 2A CS header - A GSEP was declared (NRC IR 92-10/92-10 and Zion RP/Decon Log).

• November 1996: 40-50% of concrete floor coatings in Unit 2 Containment showed extensive failure. Unqualified coatings (~1200 ft2) were observed on various components including instrument racks, struts, filter housings, valve bodies, and piping (NRC IEN 97-24).

During the time that initial characterization was performed, all radioactive systems and components were still located inside Containment. Consequently, ambient radiation dose rates inside the Containment prohibited the direct assessment of concrete and steel structural surfaces below the 588 foot elevation by scanning or direct measurement.

On 11/09/2010, an initial characterization survey of the Incore surfaces was conducted (Survey #2980). Fourteen (14) out of twenty (20) smears collected in the area were greater than 1,000 dpm/100cm2; the highest loose surface contamination indication was 127,000 dpm/100cm2. The maximum dose rate recorded in the area was 35 mR/hr.

From June of 2012 through January of 2013, site characterization was performed in Unit 2 Containment. The characterization survey consisted of a series of concrete core samples taken in the 568 foot concrete floor, the 541 foot Incore Tunnel floor and Incore Tunnel walls. The locations selected for the concrete core sampling were biased toward locations where physical or observed radiological measurements indicated the presence of fixed and/or volumetric contamination of the concrete media. When possible, locations were determined based upon elevated observed contact dose rates or count rates. In addition, visual observations of floor and wall surfaces were used to identify potential locations of surface contamination, such as discoloration or standing water. The goal was to identify, to the extent possible, the locations that exhibited the highest potential of representing the worst case bounding radiological condition for concrete in each survey unit. This judgmental sampling approach also ensured there was sufficient source term in the cores to achieve the sensitivities required to determine the radionuclide distributions of gamma emitters as well as HTD radionuclides.

Sixteen (16) concrete core samples were taken on the 568 foot elevation of the Unit 2 Containment, eight inside the missile shield and eight outside of the missile shield.

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Three (3) concrete core samples were obtained from each of the Incore Tunnel Under Vessel areas. Two (2) concrete core samples were taken from the 541 foot elevation floor and one was taken from the wall directly under each reactor vessel.

The results of the site characterization surveys performed from 2010 to 2013 are documented in ZionSolutions Technical Support Document (TSD)14-028, Radiological Characterization Report (Reference 7) and in Chapter 2 of the LTP. A summary of the on-site gamma spectroscopy results for the analysis of the concrete cores taken from the Unit 2 Containment 568 foot elevation is presented in Table 1. A summary of the on-site gamma spectroscopy results for the analysis of the concrete cores taken from the Containment Incore Tunnel areas are presented in Table 2. A summary of the analysis of select concrete cores for the full suite of radionuclides by an off-site laboratory is presented in Table 3. The locations where the core samples were taken are illustrated in Figures 6 and 7.

For the Unit 2 568 foot elevation, the sample analysis indicated that the majority of the radionuclide source inventory resided within the first 1/2-inch of concrete and that Cs-137 was the dominant radionuclide. For the Unit 2 Under Vessel area, the maximum dose rate recorded was 15 mR/hr and the maximum loose surface contamination smear indicated 90,000 dpm/100cm2, which was taken at the plate that supports the Incore tubes (Survey

1. 2013-0046). Sample B1-02110-CJF-CCV-001 showed the majority of activity above Minimum Detectable Concentration (MDC) for Co-60, Cs-137, and Eu-152 was to a depth of 14 inches (entire core). The majority of Eu-154 source term was in the first 10 inches.

Sample B1-02110-CJF-CCV-002 showed the majority of activity above MDC for Co-60, Eu-152, and Eu-154 was to a depth of 4.5 inches (entire core). The majority of Cs-137 source term was in the first 1/2-inch. Sample B1-02110-CJW-CCV-003 showed the majority of activity above MDC for Co-60, Cs-137, Eu-152, and Eu-154 was to a depth of 5.5 inches (entire core).

The top 1/2-inch puck from eight (8) of the nineteen (19) cores from Unit 2 were sent to Eberline Laboratories for gamma spectroscopy and HTD analyses for radionuclides such as H-3, C-14, Tc-99, Ni-63, Sr-90, and alpha emitters. Significant HTD radionuclides identified by the analysis of the concrete core samples included Ni-63, H-3 and Sr-90.

The other radionuclides positively detected at concentrations greater than their respective MDC included; C-14, Tc-99, Pu-238, Pu-239/240, Am-241, Am-243 and Cm-243/244.

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 1 - Unit 2 Containment 568 Foot Elevation Concrete Core Sample Analysis Summary Co-60 Cs-137 Core Avg. Avg.

Surface Surface Location Sample ID# Depth Subsurface Subsurface Activity (1) Activity (1)

(inches) Activity (2) Activity (2)

(pCi/g) (pCi/g) (pCi/g) (pCi/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 (1) Represents surface activity of floor following removal of loose contamination (2) Represents average of activity over entire depth of core sample minus the surface activity

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 2 - Unit 2 Containment 541 Foot Elevation Concrete Core Sample Analysis Summary Co-60 Cs-137 Eu-152 Eu-154 Core Avg. Sub- Avg. Sub- Avg. Sub- Avg. Sub-Surface Surface Surface Surface Location Sample ID# Depth (1) surface (1) surface (1) surface (1) surface Activity Activity Activity Activity (inches) Activity (2) Activity (2) Activity (2) Activity (2)

(pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/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 (1) Represents surface activity of floor following removal of loose contamination (2) Represents average of activity over entire depth of core sample minus the surface activity

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 3 - Unit 2 Containment Concrete Core Samples - Eberline Laboratories Analysis B102102- B102103- B102103- B102105- B102105- B102106- B102106- B102107- B102110- B102110-CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJFCCV- CJFCCV-Radionuclide(1) 001 001 002 001 002 001 002 001 001 002 (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (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 (1) Bold values indicate concentration greater than MDC. Italicized values indicate MDC value. NA indicates no analysis

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Figure 6 - Unit 2 Containment 568 Foot Elevation Concrete Core Sample Locations

[22]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Figure 7 - Unit 2 Containment 541 Foot Elevation Concrete Core Sample Locations

[23]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 On 07/20/16, the last routine surveys were conducted in Unit 2 Containment, before heavy demolition started and access was no longer possible. Survey 2016-2226, conducted in the Outer Missile Barrier (OMB) area of Unit 2, showed that all smears were less than 1,000 dpm/100cm2 and that the maximum dose rate was 1.5 mR/hr. Survey 2016-2224, conducted in the Inner Missile Barrier (IMB) area of Unit 2, showed a maximum loose contamination level of 6,400 dpm/100cm2 and a maximum dose rate of 5.1 mR/hr.

Following demolition and prior to attempting FSS, continuing characterization was performed on the concrete walls and floor of the Under Vessel area in Unit 2 Containment and to assess the radiological condition of the exposed steel liner above the 565 foot This work was required in accordance with LTP Chapter 5, section 5.3.4.4. The continuing characterization of the steel liner above the 565 foot elevation consisted of sufficient smear samples and beta scans of accessible surfaces to ensure that the liner was adequately decontaminated prior to FSS. This survey was performed in December 2017. The result of smear samples indicated no detectable loose surface contamination greater than 1,000 dpm/100cm2 on exposed building surfaces above the 565 foot elevation.

Continuing characterization was performed in the Under Vessel are between November 11, 2017 and November 22, 2017. The objective of the continuing characterization survey was to assess the depth of activation in the concrete in order to guide the remediation necessary to meet OpDCGL for Containment and, to ensure the correct geometry was used for the ISOCS measurements. The survey consisted of scanning the exposed concrete surfaces and the acquisition of sixteen (16) concrete core samples with four (4) of those samples taken on the upper walls, eight (8) samples taken on the lower walls and four (4) samples taken on the floor. In addition, three (3) samples were taken from the metal in the embedded steel support ring. See Figure 8 for a graphic depiction of the sample locations.

To the extent possible, the locations selected for concrete core samples were identified by the scan measurement on the surface that exhibited the highest activity. The concrete core samples were taken through the layer of concrete from the exposed grade to the underlying steel liner where possible. Each core was segmented into 1/2-inch pucks, which were then analyzed by the on-site gamma spectroscopy system for gamma-emitting radionuclides. The results of the analysis of continuing characterization concrete core samples are presented in Table 4.

On November 16, 2017, the two concrete pucks (as well as one metal sample) that contained the highest gamma-emitting radionuclide activity were sent to Eberline Laboratories to be analyzed for the full suite of radionuclides from Table 5-1 from LTP Section 5.1. The results of the concrete core analyses are presented in Table 5. The ratios for H-3, Ni-63 and Sr-90, based on the two continuing characterization samples that were analyzed for HTDs are presented in Table 6.

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Figure 8 - Unit 2 Containment Continuing Characterization Concrete Core Sample Locations

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 4 - Unit 2 Containment Continuing Characterization Concrete Core Samples - On-Site Analysis B1-02110C-JWC-001-CV B1-02110C-JWC-002-CV B1-02110C-JWC-003-CV B1-02110C-JWC-004-CV Depth Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 (in) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) 0 15.5 0.15 11900 50.8 3.84 6.14 0.314 1040 37.4 2.92 3.93 0.0292 9.76 46.2 3.66 10.4 0.0751 2060 67 4.35 0.5 14 0.321 9290 50 3.49 5.83 0.0636 754 38.5 2.62 3.39 0.119 4.24 49.1 3.54 10.3 0 1110 64.4 3.97 0.5 6.05 0.352 1150 50.6 3.65 7.92 0 96.8 11.1 0.577 3.05 0.112 0 45.4 2 6.56 0 47.7 70.2 4.28 1 6.01 1.53 879 466 2.52 3.22 0 0 45.1 2.51 6.05 0.148 28 65.8 3.69 1 8.8 0.206 334 48.7 3.44 2.67 0 0.223 51.7 2.65 5.59 0 0 71.6 4.06 1.5 9.07 0.276 363 49.5 2.96 2.5 0 0.333 54.1 2.61 5.86 0.279 0.335 69.4 3.41 1.5 5.77 0.139 49 43.5 1.6 2.59 0.0765 0 49.2 0 4.91 0.0808 0 64.2 3.61 2 5.81 0.398 38.5 45.3 3.23 8.68 0.318 73.6 9.18 2.01 2.81 0.123 0 50.1 2.55 4.72 0 0 63.8 3.25 2 3.54 0.0176 8.04 39.5 1.54 4.52 0.147 719 31 1.34 3.32 0.525 0 49.7 2.71 3.82 0.159 0.232 62.6 3.32 2.5 3.6 0 7.83 38.4 1.69 4.55 0 830 31 2.02 3.5 0.119 0 49.3 2.99 4.2 0 0 59.7 44.9 2.5 3.05 0.777 1.84 43.9 2.39 3.86 0.328 287 36.6 2.28 3.13 0 0 50.2 2.67 3.78 0 0.185 52.4 2.57 3 3.23 0.0701 1.88 44.1 2.36 3.93 0 213 35.6 1.96 3.63 0.0426 0 50.7 2.44 4.13 0.346 0 54.3 2.73 3 3.33 0.227 0.674 46.2 2.72 2.96 0.0638 83.7 32.9 0.583 3.21 0 0.445 39.6 1.84 2.95 0.0348 0.203 43.7 2.7 3.5 2.87 0.0532 0.966 43.3 2.89 3.25 0.35 86.2 32.4 0.556 3.15 0.53 0 38.1 0 2.95 0.415 0.0491 41.1 2.02 3.5 4.11 0.106 1.38 41.7 1.87 3.2 0.241 44.2 32.8 1.65 2.16 0.478 0 28.8 1.26 2.86 0.2 0 37 1.94 4 3.8 0 1.49 40.7 2.49 3.29 0.078 35.5 34.3 1.25 2.07 0.284 0.0757 27.7 0.752 3.03 0.414 0 36.9 0.974 4 4.12 0.0563 0.605 38.9 2.56 4.67 0 9.62 12.5 1.56 3.6 0.125 0 26.8 1.65 2.72 0.208 0 41.6 2.19 4.5 3.58 0.103 0.466 37.6 2.07 3.09 0.0309 0.0238 27.4 1.32 2.78 0.423 0 41.9 2.11 4.5 1.75 0 0 22.7 17 1.43 0.0707 0.166 23.4 0.84 2.11 0.122 0 34.7 1.68 5 1.58 0.0995 0.026 21.2 15.6 1.47 0.324 0.292 21.4 1.04 2 0.216 0.322 32.6 2.33 5 4.66 0 0.0403 2.47 0.0135 1.05 0 0 17.4 0.612 1.59 0.0555 0 22.1 1.27 5.5 5.78 0 7.06 10.8 0.94 0.967 0.234 0.43 17.1 0.835 1.42 0 0.018 21.9 0.825 5.5 2.15 0 22.1 24.6 0.907 0.817 0.173 0 15.2 10.4 1.38 0 0.162 16.9 0.628 6 1.82 0.0005 24.3 25.2 9.97 0.822 0 0.208 14.3 0.621 1.26 0.163 0.0985 16.5 0.929 6 2.24 0.163 18.6 31.8 0.434 0.77 0.113 0.102 10.9 0.534 1.03 0.218 0.18 14 0.858 6.5 3.68 0.0356 0.175 1.9 0.162 2.43 0 17.8 29.8 0.923 0.662 0 0 10.8 0.508 0.88 0.11 0 13.7 1.07 6.5 0.783 0.0128 0.346 12.6 8.89 2.66 0.0623 12.2 21.3 0.401 0.67 0.0145 0 11.1 0.728 0.759 0 0 12.3 0.782 7 0.948 0.18 0.326 11.9 1.33 2.87 0.11 10.3 20.4 0.616 0.82 0.196 0.249 11.4 0.152 0.732 0.0144 0 11.8 0.0476 7 0.961 0.215 0.106 11.1 0.891 1.2 0.101 3.84 15.4 0.976 0.318 0 0 7.12 0.479 0.823 0.0195 0 12.9 9.43 7.5 0.737 0.21 0.195 11.4 0.248 1.15 0 2.58 16.1 1.45 0.596 0 0 8.02 0 0.844 0 0 11.2 1.15 7.5 0.947 0.0598 0.337 10.6 0.228 1.1 0.113 0.276 13.9 0.32 0.458 0 0 7.34 5.07 0.613 0.0389 0.319 9.61 0.133 8 0.935 0.0721 0.2 11 0.235 1.22 0.0207 0.294 14.2 0.701 0.367 0 0 7.32 5.59 0.792 0.0174 0 11.2 0 8 0.558 0.0563 0.0931 7.51 0.591 0.933 0 0 11 0.176 0.532 0.0633 0 5.57 3.97 0.518 0 0.205 8.85 0.53 8.5 0.589 0 0.23 7.67 0.683 0.83 0.089 0.112 10.6 1.15 0.462 0.0183 0.111 5.56 0 0.49 0.0199 0.05 8.27 0.823 8.5 0.621 0.0474 0 6.77 0.841 0.708 0 0 9.05 2.29 0.842 0.0154 0 5.68 0.248 0.438 0 0 6.8 0.702 9 0.461 0.101 0.0546 6.49 0 0.619 0 0.105 8.14 0.292 0.657 0.0087 0.0098 5.26 0 0.542 0.0446 0.06 6.15 0.59 9 0.535 0.145 0.0766 6.47 0.321 0.75 0 0 9.27 0.0038 0.474 0.0343 0.0386 4.32 0.0064 0.325 0 0.0984 4.6 3.3 9.5 0.494 0 0.323 5.92 4.63 0.609 0.137 0 8.57 0.0394 0.619 0.276 0 4.07 0.386 0.361 0.0104 0 4.56 0.219

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 4 (continued) - Unit 2 Containment Continuing Characterization Concrete Core Samples - On-Site Analysis B1-02110C-JWC-001-CV (cont) B1-02110C-JWC-002-CV (cont) B1-02110C-JWC-003-CV (cont) B1-02110C-JWC-004-CV (cont)

Depth Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 (in) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) 9.5 0.422 0.143 0.24 6.04 0.659 0.453 0 0.09 5.92 0.0264 0.285 0 0 2.95 2.31 0.303 0.0777 0 3.98 0.238 10 0.398 0.113 0.195 5.64 0.457 0.443 0 0.294 5.75 0.285 0.204 0 0 3.12 2.52 0.312 0.091 0.136 3.69 0.151 10 0.349 0 0 4.99 0.104 0.116 0 0.0771 2.29 0 0.25 0 0.11 3.11 0.327 10.5 0.444 0.0866 0.0335 4.34 1.89 0.119 0.0082 0.305 2.31 0.155 0.261 0.222 0 2.77 0 10.5 0.347 0.0504 0.217 5.03 0.492 0.263 0.0308 0.0425 3.67 0.464 0.328 0 0.229 2.3 0 0.203 0 0 2.48 1.67 11 0.376 0 0.203 4.51 0.534 0.279 0.0849 0.0433 3.5 0.203 0.286 0 0.0382 1.95 0 0.219 0.0164 0.0162 2.67 1.84 11 0.438 0.0473 0.23 3.93 0.0867 0 0.147 0 4.04 0.492 0.139 0.0502 0 1.46 0.0408 0.212 0 0 2.43 1.57 11.5 0.489 0.0355 0.0316 3.96 0.0264 0.101 0 0.0646 3.77 0.103 0.172 0.0396 0.0399 1.48 0 0.19 0 0.16 2.26 1.68 11.5 0.284 0.0514 0.127 3.63 0.321 0.305 0.0751 0.139 2.97 0.505 0.18 0.166 0.0738 1.08 0.719 0.169 0.0017 0 1.9 0 12 0.357 0.157 0.111 3.31 0.241 0.168 0.0422 0 2.76 0.438 0.157 0.0156 0.0341 1.32 0.343 0.18 0.139 0 1.92 1.32 12 0.419 0 0.302 3.57 0.706 0.252 0 0 2.14 0.739 0.0447 0 0.0924 1.05 0.77 0.273 0.0111 0 1.26 1.32 12.5 0.318 0.0182 0.122 3.35 0.416 0.251 0 0.132 2.49 0.648 0.0874 0 0.0148 0.828 0.654 0.194 0 0 1.34 0.846 12.5 0.285 0.101 0.149 2.13 0.11 0.216 0.0485 0.0772 2.29 0.0005 0.141 0.135 0 0.523 0.0316 0.149 0.0723 0 0.878 0 13 0.195 0.0564 0.227 2.29 0.0995 0.162 0 0 2.3 0.0414 0.0619 0.0151 0 0.557 0.469 0.146 0.145 0 1.13 0 13 0.34 0.22 0.155 1.42 0 0.335 0 0.0454 2.17 0.404 0.102 0 0 0.759 0.373 0.172 0.0296 0.0269 0.688 0.0005 13.5 0.334 0 0.333 1.45 0.0623 0.198 0 0.148 1.73 0.165 0.0922 0 0 0.697 0.559 0.161 0.179 0.165 0.771 0.441 13.5 0.164 0 0.252 1.37 0.922 0.1 0.0683 0 1.32 0.531 0.157 0.0345 0.0521 0.681 0.343 0.213 0.042 0 0.458 0.601 14 0.185 0.0479 0.226 0.981 0.0575 0.188 0.159 0.136 1.14 0.441 0.0846 0.0206 0.0799 0.0429 0.442 0.149 0 0.0291 0.717 0.0406 14 0.139 0.0166 0.233 1.09 0.229 0.0679 0.0091 0 0.905 0.254 0.191 0 0.0226 0.399 0.366 0.108 0 0.0815 0.45 0 14.5 0.232 0.0866 0.321 1.06 0.165 0.17 0 0 0.911 0.221 0.0090 0.0891 0 0.359 0.369 0.111 0 0 0.347 0.274 14.5 0.433 0.138 1.21 1.17 0.734 0.17 0 0 0.659 0.402 0.0371 0.0288 0.0214 0.237 0.318 0.14 0.149 0 0.0114 0.181 15 0.22 0.02 1.49 0.987 0.32 0.123 0.0241 0.0619 0.624 0.0126 0.122 0.0157 0.0124 0.141 0.111 0.0282 0.0463 0.109 0.43 0.0308 15 0.0751 0.0067 0.13 0.562 0.222 0.21 0 0 0.638 0.0153 0 0 0.0577 0.298 0.154 0.102 0 0.0059 0.112 0.196 15.5 0.118 0 0.0446 0.291 0.177 0.0613 0.0726 0.102 0.735 0.184 0.183 0.0648 0.159 0.189 0.0112 0.123 0 0 0.184 0.289 15.5 0.0561 0.0167 0.192 0.466 0.313 0.111 0.0907 0.0281 0.591 0 0.111 0 0.0183 0.197 0.196 0.126 0 0.173 0.232 0.125 16 0.0543 0.0469 0.104 0.296 0.145 0.101 0 0 0.629 0 0.0444 0.016 0 0.426 0.154 0.0616 0 0.0127 0.318 0.006 16 0.12 0.0307 0.174 0.294 0 0.0651 0.0651 0.0703 0 0.0048 0.118 0.0351 0.0444 0.214 0.129 16.5 0.148 0.159 0.0898 0.385 0 0.0992 0.0142 0 0.0984 0.096 0.226 0 0 0.0578 0.149 16.5 0.0613 0.189 0.003 0.12 0.107 0.0366 0 0 0.319 0 0.0592 0 0.0188 0.327 0 0.109 0.0444 0.163 0.101 0.234 17 0.179 0.123 0.219 0.589 0.0352 0 0 0 0.324 0 0.0971 0 0.056 0.117 0.0682 0.0628 0 0.0624 0.157 0.0389 17 0.0565 0 0.28 0.259 0.186 0.0107 0.0060 0.0083 0.0088 0 0.0557 0.0517 0.112 0.112 0.0564 17.5 0.056 0 0.323 0.617 0.0387 0 0.0155 0.0165 0.204 0 0.153 0.0894 0.0599 0.227 0.173 17.5 0.134 0.083 0.727 0.264 0.244 18 0.145 0.102 1.07 0.0867 0.0487 18

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 4 (continued) - Unit 2 Containment Continuing Characterization Concrete Core Samples - On-Site Analysis B1-02110C-JFC-005-CV B1-02110C-JWC-001-CV B1-02110C-JFC-007-CV B1-02110C-JFC-008-CV Depth Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 (in) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) 0 49 0 7730 44.1 3.41 37.5 0.0064 5200 85.9 5.41 14.20 0.0597 2000 14 1.52 7.41 0.00 306.00 40.30 6.13 0.5 35 0.505 4590 44.8 3.35 33 2.98 4320 87.3 9.16 13.50 0.694 1750 14.3 0.91 6.15 0.04 292.00 42.30 2.10 0.5 10.7 0.429 287 52.8 3.15 20.5 0.711 1140 106 7.43 21.10 0 798 43.7 3.5 4.42 0.11 121.00 55.90 3.36 1 9.48 0.508 187 54.6 3.09 21.2 0.699 1040 112 7.94 19.10 0.0051 703 44.3 2.51 4.94 0.03 88.40 57.80 3.09 1 5.49 0.0119 7.76 75 4.17 13.9 11.4 202 136 7.44 14.10 0.261 291 47.9 2.48 3.70 0.00 6.47 56.10 3.68 1.5 6.46 0.709 8.08 80.9 4.08 15.6 0.151 277 142 7.79 13.60 0.865 250 47.8 2.99 3.53 0.17 5.96 54.50 3.45 1.5 6.16 0 6.34 77.3 3.88 12.6 7.13 35.6 135 7.43 11.00 0 107 43.5 2.56 5.22 0.23 2.82 59.50 3.93 2 4.46 0 3.16 66.3 3.53 12.2 0.337 37.3 132 8.3 11.40 0.126 108 46.5 2.66 5.66 0.58 2.69 62.80 3.55 2 6.18 0.0435 6.08 76.9 3.52 10.8 0.42 50.4 201 10.1 9.46 0.0635 94.4 54.7 2.54 7.76 0.00 1.66 72.00 4.13 2.5 5.38 0.244 6.98 72.2 4.48 11.7 0.862 55.9 232 13.9 9.52 0.199 79.4 53.7 2.54 7.76 0.00 1.95 70.50 3.56 2.5 6.67 0.104 7.76 83 4.46 12 1.25 24.9 215 11.2 8.41 0.627 68.9 61.9 3.59 5.31 0.67 0.32 61.40 4.10 3 5.02 0.533 3.28 67.5 3.6 11.7 0.174 17.7 189 8.66 7.94 0.0525 56.8 62.4 2.98 4.94 0.00 0.00 66.00 3.27 3 4.26 0.197 0.213 65.9 3.56 8.31 0.305 0.592 110 5.58 7.76 0.13 16.8 51.5 2.55 6.43 0.36 0.00 65.10 3.87 3.5 3.83 0 0.403 58.7 3.53 8.51 0.0050 0.478 113 4.96 7.31 0 14.9 47.6 2.73 7.68 0.96 0.00 65.10 2.13 3.5 21.4 0.138 0.186 10.3 9.62 7.47 0.594 0 115 6.25 4.25 0.267 12.6 39.7 2.18 7.06 0.00 0.00 58.60 3.17 4 23.2 0.0711 0.243 7.7 0.475 8.41 14.6 0.675 116 4.98 4.48 0.119 11.1 42.1 1.89 6.61 0.06 0.04 57.00 2.79 4 6.39 0.63 1.93 55.8 2.95 8.57 0.225 0 111 5.61 4.46 0 25 37.5 2.24 4.16 0.09 0.00 53.90 3.44 4.5 8.56 0 1.61 65.2 3.99 8 0.194 0 105 4.62 4.33 0 19 38.4 1.9 4.32 0.00 0.05 50.60 1.89 4.5 3.79 0.232 0.172 46.6 2.14 5.7 0.123 0.321 88.1 4.01 2.61 0 8.79 29.5 1.33 3.67 0.00 0.00 42.80 2.18 5 3.59 0.118 0.0725 44.9 2.4 5.65 0.483 0 91 3.45 2.38 0.0517 9.32 28.3 1.84 3.07 0.46 0.00 43.20 2.07 5 5.04 0 0 49.2 3.05 5.63 0.216 0.735 88.4 4.45 2.05 0.449 6.55 26.9 1.34 2.25 0.02 0.54 37.00 1.96 5.5 5.15 0 0.443 49.8 2.65 5.68 0.0608 0 87.1 3.82 2.03 0.0266 6.34 28 1.38 2.12 0.00 0.00 37.20 1.12 5.5 4.46 1.1 0 42.5 2.21 5.38 0.97 0 81 3.05 1.60 0.0466 1.97 22.5 1.18 2.46 0.22 0.00 35.20 1.67 6 3.8 0 0.132 43 2.17 5.33 0.0783 0 80.6 3.05 1.41 0 1.59 19.7 0.731 2.60 0.16 0.31 35.60 1.77 6 2.34 0.155 0.198 33.1 1.48 4.92 0.114 0 76.9 3.4 1.27 0 1.16 21.6 1.15 2.09 0.01 0.00 29.30 1.66 6.5 2.39 0 0.103 31.8 1.62 4.85 0.386 0 72.5 4.21 1.41 0 1.01 21.5 0 1.96 0.00 0.19 29.10 1.14 6.5 3.33 0.349 0.176 31.2 0.864 3.17 0.28 0.778 49.4 2.41 1.25 0.0089 0.388 18.7 0.412 3.29 0.05 0.00 29.50 1.22 7 3.22 0.137 0 31.4 1.41 3.04 0.125 0.0616 49.9 2.51 1.28 0.292 0.313 17.5 0.478 3.51 0.00 0.17 29.20 0.94 7 3.3 0 0 31.1 0.876 3.07 0.0638 0 49.9 1.95 1.76 0 0.109 15.6 0.558 3.23 0.32 0.39 34.40 1.71 7.5 2.99 0 0.184 29.9 1.13 2.92 0.0725 0.177 47.7 2.47 1.64 0.122 0.0748 14.3 0.658 2.78 0.15 0.69 28.70 1.04 7.5 1.53 0.151 0.523 21 1.08 2.52 0.562 0.636 35.2 1.07 0.84 0 0.252 10.2 0.56 2.75 0.00 0.33 24.60 1.34 8 1.54 0.041 0.173 20.7 1.13 2.64 0.0423 0 34.7 1.74 0.73 0.0038 0.181 9.82 0.385 2.60 0.16 0.00 24.50 0.90 8 1.23 0 0 17.9 1.11 3.43 1.11 0.12 43.9 0.993 4.58 0.054 0.218 1.28 0.0618 1.29 0.15 0.02 18.60 0.57 8.5 1.47 0.0454 0.0448 18.8 1.37 3 0.168 0.648 42.9 1.75 1.23 0.00 0.00 18.20 1.02 8.5 0.708 0 0 13.3 0.0622 1.91 0.0348 0.124 23.1 0.917 1.52 0.25 0.02 25.60 0.80 9 0.773 0 0.0469 13.2 0.653 1.81 0.162 0.071 20 1.08 3.59 0 0.293 1.32 0.142 1.13 0.04 0.03 22.60 1.19 9 0.749 0.172 0.0161 12.4 0.34 2.22 0.0041 0.14 22.2 1.22 0.12 0.0649 0.327 0.026 0.0286 1.42 0.00 0.31 16.50 0.52 9.5 0.58 0.133 0 12.1 9.57 2.67 0.0289 0.407 24.7 1.26 0.10 0.0232 0.231 0.161 0.0393 1.87 0.09 0.00 17.50 0.63

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 4 (continued) - Unit 2 Containment Continuing Characterization Concrete Core Samples - On-Site Analysis B1-02110C-JFC-005-CV (cont) B1-02110C-JWC-001-CV (cont) B1-02110C-JFC-007-CV (cont) B1-02110C-JFC-008-CV (cont)

Depth Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 (in) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) 9.5 0.401 0 0.349 9.44 6.48 1.57 0.32 0 19.5 0.377 0.10 0.0134 0.17 0 0.0757 1.74 0.19 0.09 13.90 0.49 10 0.712 0 0.284 12.8 0.435 1.54 6.61 0 18.6 1.33 0.00 0.051 0.135 0.0813 0.109 1.63 0.00 0.09 13.80 0.66 10 0.719 0 0 11.8 0.995 0.887 0.138 0 12.9 1.05 0.02 0 0.0674 0.295 0.0603 0.96 0.00 0.19 15.60 0.21 10.5 0.495 0 0.169 9.18 1.73 0.96 0.228 0 13.1 0.937 0.17 0.076 0.13 0 0.144 0.78 0.12 0.00 13.40 1.02 10.5 0.533 0.107 0 7.23 0 0.905 0.0441 0 12.4 0.549 0.10 0.095 0.0228 0.396 0.0691 0.76 0.08 0.45 12.50 0.67 11 0.618 0 0.14 7.31 0.66 0.798 0.647 0.185 11.9 0.471 0.06 0 0.103 0.352 0.0172 0.56 0.00 0.51 8.95 1.63 11 0.684 0 0.154 6.1 0.463 0.984 0.125 0.332 11.2 0.582 0.00 0 0.106 0.206 0.0587 0.55 0.00 0.50 8.26 0.05 11.5 0.791 0.0276 0.0204 6.2 0.16 0.854 0.0763 0.0302 10.5 0.148 0.08 0.0298 0.145 0.0738 0.0399 0.85 0.00 0.46 9.78 0.75 11.5 0.532 0.219 0 5.51 4.47 0.566 0.0262 0.145 7.54 0.161 0.00 0 0.0955 0.379 0.113 1.27 0.31 0.24 9.29 0.82 12 0.724 0 0.154 5.58 4.44 0.492 3.56 0.101 7.28 0.0476 0.05 0 0.1 0.144 0.0574 1.47 0.00 0.06 9.12 0.48 12 0.466 0 0.0781 4.53 0.301 0.567 2.59 0.0449 7.23 0.537 0.16 0.153 0.0954 0.276 0.141 1.02 0.15 0.07 6.84 0.14 12.5 0.255 0.13 0.186 4.33 0.23 0.618 0.0772 0 7.58 5.82 0.05 0.044 0.116 0.3 0.206 1.00 0.07 0.27 6.71 0.27 12.5 0.206 0 0.176 3.4 0.115 0.31 1.48 0.109 5.91 4.39 0.12 0 0 1.33 0.764 0.29 0.02 0.02 4.84 0.53 13 0.334 0 0.106 3.37 0.224 0.271 0.0263 0.0669 5.56 0.519 0.20 0.147 0.176 1.28 0.0963 0.26 0.01 0.32 4.74 3.47 13 0.321 0.0579 2.63 3.04 0.0289 0.247 0.0012 0.0871 4.28 0.349 0.16 0.118 0.139 1.36 1.13 0.38 0.00 0.22 5.06 0.34 13.5 0.237 0.0257 3.39 2.38 0.422 0.32 0.046 0.256 4.17 0.232 0.15 0 0.153 1.61 0.375 0.50 0.00 0.12 5.14 0.40 13.5 0.3 0.0474 2.49 2.29 0.24 0.364 0.0206 0.21 3.35 2.54 0.12 0 0.0919 0.94 0.581 0.29 0.00 0.12 3.74 0.09 14 0.396 0.111 1.34 3.18 0.0991 0.328 0.0031 0 3.24 2.37 0.14 0.0182 0.127 0.816 0.0808 0.30 0.00 0.14 3.29 2.52 14 0.244 0.0447 0.0419 2.48 0 0.211 0.0741 0.098 2.62 0.0998 0.24 0.0098 0.101 0.702 0.0257 0.24 0.00 0.16 3.52 0.73 14.5 0.246 0.0286 0.0293 2.32 1.94 0.231 0.263 0.257 2.85 0.136 0.17 0.0397 0.311 0.837 0.277 0.27 0.01 0.02 3.57 0.25 14.5 0.206 0 0 2.25 0.585 0.163 1.92 0.104 2.07 1.46 0.05 0.0167 0.182 0.603 0.293 0.42 0.05 0.00 3.41 0.28 15 0.164 0 0.094 2.14 0.723 0.132 0.149 0.0936 1.87 1.4 0.14 0.129 0.269 0.746 0.521 0.32 0.35 0.00 3.26 2.04 15 0.2 0.0060 0.0984 1.61 0.0298 0.191 0.0161 0.0651 1.69 0.411 0.10 0 2.86 0.355 0.244 0.29 0.10 0.00 2.13 1.50 15.5 0.159 0.0524 0 1.61 0.0733 0.271 0.0318 0 1.98 0.225 0.18 0 1.92 0.395 0.275 0.34 0.00 0.04 2.31 0.23 15.5 0.199 0.189 0 1.26 0.847 0.137 0.044 0.0832 1.62 0.122 0.18 0.0284 0.259 0.589 0.35 0.23 0.10 0.06 2.21 1.57 16 0.072 0 0.188 0.949 0 0.0838 0.223 0.11 1.3 0.267 0.07 0.0404 0.078 0.579 0.412 0.28 0.00 0.00 2.01 1.62 16 0.225 0.0077 0.503 0.929 0.0961 0.13 0.991 0.0857 1.09 0.529 0.00 0 0.0485 0.199 0.426 0.19 0.07 0.12 1.91 0.52 16.5 0.383 0 0.437 1.14 0.417 0.0656 0.0372 0.0452 1.17 0.781 0.00 0.19 0.0998 0.47 0.214 0.17 0.01 0.22 1.86 0.21 16.5 0.193 0 0.214 1.21 0.46 0.0709 0.0546 0.199 0.896 0.669 0.19 0.0496 0.136 1.49 1.13 0.10 0.18 0.16 1.92 0.36 17 0.173 0.0396 0.0384 0.841 0.153 0.108 0.201 0.14 0.834 0.605 0.17 0 0.302 1.55 1.23 0.25 0.07 0.24 1.77 1.24 17 0.0626 0.0787 0.193 0.731 0.573 0.117 0.288 0.432 0.318 0.222 0.26 0.102 0.0702 2.24 0.114 0.20 0.17 0.08 1.14 0.88 17.5 0 0 0.0336 0.582 0.238 0.174 0.0769 0.286 0.229 0.171 0.22 0 0.0297 2.19 0.0553 0.29 0.18 0.06 1.06 0.94 17.5 0.0966 0.037 0.165 0.448 0.213 0.0123 0.0755 0.0542 0.555 0.141 0.31 0.16 0.0324 2.65 1.82 0.09 0.14 0.02 1.17 0.86 18 0.095 0 0.0113 0.527 0.263 0.0539 0.161 0.115 0.0032 0.22 0.28 0 0.0074 2.54 0.801 0.13 0.05 0.00 1.04 0.82 18 0.0793 0.0573 0.141 0.468 0.417 0 0.0949 0.17 0.28 0.212 0.20 0.0727 0.108 2.72 0.324 0.25 0.00 0.25 1.14 0.25 18.5 0.189 0 0.127 0.255 0.227 0.0837 2.09 0.106 0.224 0.248 0.21 0 0.0137 2.88 0.2 0.22 0.08 0.18 0.97 0.00 18.5 0.145 0 0.141 0.601 0.167 0.0656 0.77 0.105 0.32 0.18 0.26 0 0.0957 3.75 2.75 0.10 0.06 0.12 0.66 0.25 19 0.104 0.0604 0.219 0.321 0.165 0.0642 0.0746 0.111 0.228 0.139 0.27 0 0 3.77 0.25 0.05 0.02 0.00 0.64 0.42

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 4 (continued) - Unit 2 Containment Continuing Characterization Concrete Core Samples - On-Site Analysis B1-02110C-JWC-009-CV B1-02110C-JWC-010-CV B1-02110C-JWC-011-CV B1-02110C-JWC-015-CV Depth Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 (in) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) 0 5.35 0.0449 0.529 55.2 3.62 161 6.4 3.2 2230 117 5.49 0.179 0.977 73.9 3.75 4.51 0.723 12.8 54.7 3.82 0.5 5.21 0.0662 0.0217 54.2 4.06 180 5.24 1.09 2540 133 5.42 0.209 0 79 2.96 4.82 0.404 10.6 64.4 49.5 0.5 5.42 0.268 0 72.4 4.38 182 3.43 0 2420 122 4.47 0.0937 0 65.2 3.79 5.38 0.649 1.93 80.8 4.08 1 5.55 0.181 0 70 4.03 176 3.44 0 2380 126 4.13 0.46 0.299 65.8 3.57 5.55 0.502 1.01 72.6 4.15 1 5.51 0.38 0.216 65.8 3.57 215 4.61 0 2780 145 5.44 0.539 0 62.9 3.14 6.47 0.115 0.258 71.1 3.8 1.5 5.29 0.122 0 64.6 3.62 214 0.274 0 2700 134 5.15 0.0536 0 63 2.74 6.95 0 0.135 68.6 3.73 1.5 5.85 0 0 63.5 3.34 240 0 0 2760 132 3.76 0.253 0.207 52.8 2.81 5.39 0 0.168 57.9 2.63 2 5.5 0.141 0 62.4 3.52 233 1.24 0 2790 130 3.72 0.355 0.743 53.6 2.24 4.71 0.708 0 56.8 2.95 2 7.03 0.0743 0.018 5.32 0.421 171 3.89 3.03 2140 102 3.56 0 0 49.4 2.39 4.22 0.289 0.336 55.5 2.51 2.5 178 0 0.943 2140 97.8 3.68 0.121 0.156 50.1 2.24 4.22 0.463 0.347 57.9 3.08 2.5 153 1.76 1.4 1920 87.6 3.37 0.0564 0.219 42.3 2.09 3.94 0.2 0 54.1 2.39 3 150 2.96 0 1910 89.2 3.24 0.0247 0 41.7 1.48 3.5 0 0 51.5 2.17 3 122 1.29 0.665 1640 77.1 2.51 0 0 40 1.74 3.34 0.324 0.0424 46.3 2.56 3.5 121 0.329 2.4 1660 73.4 2.8 0.331 0.0108 40.6 1.81 3.21 0 0.386 45.4 2.17 3.5 162 2.16 6.13 1450 64.2 1.91 0.228 0.397 31.9 1.68 2.78 0.21 0.0796 36.2 1.73 4 161 0.0742 0 1520 69.1 1.97 0.266 0.161 30.7 1.41 2.97 0 0 41.4 2.04 4 67.2 3.66 0 995 40.7 1.89 0.275 0.0442 28 1.55 4 0 0 49.5 3.01 4.5 67.5 2.03 0 995 43.6 1.79 0.11 0.341 26.9 1.37 4.25 0.0273 0 45.8 1.59 4.5 132 1.6 0.22 1310 61.6 2.34 0 0 28.8 1.34 2.03 0 0 28.4 1.66 5 5.52 0.039 0.0587 2.38 0.103 136 2 0 1360 61.7 2.25 0.301 0 27.4 1.17 1.75 0.223 0.124 29.6 1.19 5 1.35 0.0137 0 20.4 1.68 64.1 0.155 0 827 34.1 1.37 0.114 0 16.9 0.0506 1.8 0.141 0.0718 27.9 0.983 5.5 14.3 0 0.0834 21.1 0.982 60.7 0.0469 0 848 34.3 1.25 0.0609 0 17.5 0.222 1.73 0.0109 0.128 27.1 1.2 5.5 2.71 0.133 0 23.2 0.901 37.7 0.331 0 591 26 1.22 0.0835 0 18.1 0.698 1.79 0.227 0.0945 22.2 1.07 6 2.91 0.174 0.0237 24.6 1.16 37.7 0 0 582 21.7 1.21 0.227 0.0583 16.5 0 1.72 0.0595 0 21.6 0.355 6 2.3 0.306 0 24.2 1.33 62.9 0.82 0 610 26.5 1.08 0.144 0.369 18.4 0.537 2.61 0 0 19.2 0.702 6.5 1.35 0.0965 0.0527 21.5 1.28 60.6 0 1.46 606 25.5 1.26 0 0.261 17.2 0.829 2.42 0 0.206 19.2 14 6.5 1.49 0 0.0528 20.1 15.8 34.2 0.319 0 459 18 1.18 0.0418 0 17.5 0.954 1.13 0.17 0.151 16 0.766 7 2.12 0.241 0.423 23.5 0.713 37.4 0 0 463 19.6 1.19 0 0 15.2 0.776 1.12 0.0556 0.0543 16.3 0.586 7 2.05 0.23 0.0245 18.5 1.19 33.2 0.305 0 405 17.1 0.875 0 0.129 10.9 0.127 1.21 0 0 15.1 0.522 7.5 1.74 0.129 0 19 1.22 31.3 0 0 398 16.9 0.843 0 0.0198 10 0.651 1.16 0 0.256 12.3 0.621 7.5 0.962 0.194 0 17.2 1.03 23.6 1.42 0.709 306 13.1 0.552 0.0315 0.173 7.9 6.16 1.36 0.339 0.0323 10.8 0.863 8 0.957 0 0 15.9 0.597 23.4 1.17 0 301 11.2 0.521 0.0348 0 7.93 0.426 0.994 0 0.11 11.3 1.3 8 0.9 0.0304 0.0578 14.8 0.771 25.3 0 0.656 303 12.1 0.589 0.0913 0.251 7.38 0.0359 0.623 0.241 0 9.82 0.329 8.5 1.06 0 0 13.2 0.297 25.3 1.2 0.225 311 13.8 0.523 0.102 0.0755 7.11 0.222 0.713 0.46 0.259 10.6 8.26 8.5 1.07 0.0446 0 12.2 0.886 22.8 0.686 0 285 11.6 0.449 0 0.0653 6 0.605 0.485 0.0498 0.259 8.07 5.45 9 1.07 0.0601 0.083 11.2 0.0896 22 0.129 0 275 11.5 0.411 0.188 0.0516 5.12 0.422 0.472 0.0561 0.0928 7.41 5.04 9 1.06 0.0418 0.32 8.68 0.156 12.2 0 0 200 8.46 0.42 0.0509 0.164 4.42 0 0.541 0 0.107 5.86 0 9.5 0.886 0 0 8.2 0.158 12.5 0.318 0.134 196 8.17 0.304 0.0194 0 4.02 0.655 0.439 0.0243 0.0497 5.91 0.418

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 4 (continued) - Unit 2 Containment Continuing Characterization Concrete Core Samples - On-Site Analysis B1-02110C-JWC-009-CV (cont) B1-02110C-JWC-010-CV (cont) B1-02110C-JWC-011-CV (cont) B1-02110C-JWC-015-CV (cont)

Depth Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 (in) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) 9.5 0.64 0 0 8.29 1.01 9.24 0 0.319 142 5.43 0.314 0.0114 0.0466 3.63 2.43 0.752 0 0.14 6.38 0.109 10 0.629 0.0796 0.0201 7.48 0.807 9.29 0.451 0.604 145 5.23 0.322 0.0246 0.0099 3.23 0.55 1.05 0 0 6.95 0.789 10 0.506 0.046 0.0469 6.28 0.605 11.9 0.465 0.195 138 5.27 0.263 0.0425 0.0844 3.09 0.366 0.366 0 0 4.78 0.264 10.5 0.398 0.046 0.159 5.95 0.309 12.1 0.113 0 135 5.33 0.377 0 0.0686 3.03 0.114 0.351 0.0556 0.0116 4.19 0 10.5 0.403 0.0486 0 6.01 0.483 21.2 0.245 0.314 142 5.77 0.284 0.0142 0.066 2.93 2.2 0.153 0 0.072 2.52 0.204 11 0.531 0.0339 0 5.64 0.527 21 0 0 136 6 0.267 0.0212 0 2.71 2.11 0.145 0.0193 0.0836 2.18 1.6 11 0.3 0 0.126 3.79 2.77 6.99 1.37 0 93.3 4.04 0.258 0 0.014 2.08 0.0256 0.165 0.0493 0.0244 1.96 0.0818 11.5 0.43 0 0 4.46 0.829 7.02 0.0318 0 91.7 4.31 0.303 0.168 0.0046 1.82 0.0357 0.176 0.0121 0.065 2.05 0 11.5 0.391 0.0031 0.183 3.19 0.232 7.69 0.57 0.448 81.4 3.13 0.188 0.219 0 1.3 0.938 0.15 0 0.132 1.43 0.0392 12 0.308 0.0466 0 3.33 0.0817 8.09 0 0.17 81.6 3.35 0.0838 0.0478 0 1.3 0.843 0.0847 0.0284 0 1.37 0.819 12 0.231 0.0007 0 2.82 1.78 6.18 0 0.182 65.5 2.93 0.143 0.0267 0.0245 1.23 0.167 0.139 0.0237 0.0895 1.69 0.0925 12.5 0.267 0 0.0821 2.39 0.0389 6.68 0.397 0.239 70.5 2.77 0.158 0 0.0946 1.04 0.053 0.178 0.14 0 1.67 1.18 12.5 0.22 0 0.0898 2.18 0.1 2.84 0 0.233 42.8 1.88 0.25 0.0427 0 0.987 0.385 0.172 0.0045 0 1.63 1.14 13 0.216 0.0618 0.0325 2.15 0.0901 2.6 0.0632 0 41.7 1.85 0 0.0494 0.111 1.15 0.756 0.129 0 0 1.48 1.02 13 0.322 0.072 0.214 1.75 0.415 3.09 0.245 0 33.7 2.28 0.11 0 0 0.866 0.736 0.0885 0 0.12 0.924 0.613 13.5 0.356 0.107 0.187 2 0.199 3.76 0.0655 0.0576 32.6 1.44 0.163 0.109 0.0607 0.8 0.599 0.0853 0.0594 0.0325 0.929 0.26 13.5 0.274 0 0.0219 1.98 1.35 2.22 0.0899 0 26.6 1.74 0.0999 0 0.0603 0.466 0.297 0.222 0 0.0623 0.924 0.583 14 0.297 0.0224 0 1.82 0.0822 2.11 0.167 0.241 27.3 19.9 0.141 0 0.0051 0.429 0.246 0.176 0 0.0073 0.912 0.689 14 0.0714 0 0 2.09 0.703 2.03 0.167 0.0761 21.4 0.359 0.0912 0.0484 0.0239 0.472 0.0664 0.126 0.0868 0 0.674 0.524 14.5 0.185 0.175 0 1.78 0.0132 2.16 0 0.184 19.7 0.856 0.163 0 0 0.491 0.386 0.109 0 0.0816 0.54 0.457 14.5 0.0866 0.0285 0.0463 0.842 0.186 1.24 0 0.121 17.8 14.2 0.182 0.165 0 0.374 0.546 0.171 0.013 0.101 0.286 0.363 15 0.13 0.11 0.133 1.13 0.401 1.39 0.12 0.241 18 1.2 0.0906 0.0416 0 0.467 0 0.119 0 0.0417 0.253 0.172 15 0.105 0.176 0.161 0.634 0.501 0.859 0.225 0.0592 14.1 0.785 0.142 0.118 0.146 0.358 0.187 0.11 0.0546 0 0.344 0.37 15.5 0.176 0.136 0 0.502 0.373 0.952 0 0.134 13.3 0.889 0.0918 0 0 0.215 0.0451 0.0161 0.042 0.0794 0.312 0.052 15.5 0.12 0 0.0717 0.512 0.26 0.777 0.0662 0.0123 9.51 0.464 0.0327 0 0 0.214 0.0673 0.0611 0.0202 0.0156 0.353 0.226 16 0.0545 0 0.132 0.62 0.409 0.689 0.0815 0.0517 8.69 0.771 0.119 0 0.0447 0.145 0.0079 0.0613 0 0 0.267 0.182 16 0.0583 0.0652 0.0802 0.282 0.314 0.415 0 15.6 4.35 0.349 0.0902 0 0 0.0376 0.181 0.103 0.055 0 0.336 0.163 16.5 0.145 0.0044 0.0759 0.233 0.405 0.393 0 26.8 4.67 0.329 0.106 0.0778 0 0.157 0.17 0.0879 0 0.0382 0.406 0.392 16.5 0.263 0.115 0.0556 0.601 0.433 0.591 0.19 0.46 6.98 0.507 0.0764 0.0069 0.0413 0.108 0.107 0.0822 0.0564 0.127 0.241 0.232 17 0.167 0.0597 0.169 0.288 0.534 0.608 0.0909 0.354 7.16 4.97 0.107 0 0.1 0.164 0.0525 0.0012 0.0054 0 0.281 0.191 17 0.111 0.0406 0.0927 0.164 0.0397 0.0115 0.0092 0.142 0.154 0.111 17.5 0.0855 0 0.0188 0.0871 0.0774 0 0.101 0.0785 0.0438 0.0573 17.5 0.0173 0.129 0.0661 0.0549 0.257 18 0.106 0.0732 0.0228 0.203 0.134 18 0.135 0 0.0502 0.246 0.163 18.5 0.074 0.0604 0.148 0.121 0.081 18.5 0 0.163 0.0398 0 0.0317 19 0.0119 0 0.0186 0.14 0.037

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 4 (continued) - Unit 2 Containment Continuing Characterization Concrete Core Samples - On-Site Analysis B1-02110C-JWC-016-CV B1-02110C-JWC-017-CV B1-02110C-JWC-018-CV B1-02110C-JWC-019-CV Depth Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 (in) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) 0 4.71 0.199 22.4 64.1 3.54 6.33 0 0.203 59 3.01 181 1.14 0 2120 121 77.8 0.942 0 1220 55.7 0.5 4.56 0.0594 12.1 62.9 4.45 6.76 0.394 0 64.6 3.67 202 0.681 4.28 2300 132 83.1 1.12 0 1300 62.4 0.5 5.07 0.258 0 66.4 3.65 5.63 0.0844 0 72.4 3.34 239 8.55 0 2510 135 92.8 0 0 1110 57.6 1 4.74 0.531 0 68.4 2.7 6.1 0.0585 0 74.9 3.87 270 0.526 0 2680 156 96.7 4.83 0 1100 49.2 1 4.28 0.339 0 61.3 3.47 5.31 0.334 0.199 66.9 3.46 296 4.14 0 2720 139 90.5 0.588 0 1620 76.2 1.5 4.47 0.19 0.0504 62.4 3.46 5.41 0.201 0 71.7 3.21 281 2.77 0 2660 126 85.9 1.13 0 1640 75.5 1.5 3.93 0.162 0 53.8 2.5 4.65 0.232 0.22 64.2 3.45 147 0.987 0 2420 118 67.2 1.94 0.536 795 37.3 2 3.56 0.0544 0.0004 52.6 3.24 4.27 0 0 62.7 2.57 142 1.33 0 2330 121 62 0 0.181 809 37 2 3.88 0 0.259 45 2.32 4.54 0.627 0 53.7 3.37 158 35 0 2240 107 44.7 1.24 0 678 28.9 2.5 3.08 0.263 0.119 41.5 1.78 4.47 0.401 0 56.7 3.07 159 0.553 0 2210 104 45.7 0.385 0.397 652 29.3 2.5 7.28 0.596 0 44.3 1.97 5.66 0 0 61.2 2.69 118 3.54 0.698 2280 112 43.9 0.245 0 514 23.8 3 6.55 0.15 0 40.7 2.36 5.62 0.603 0 60.3 2.5 116 3.93 0 2310 111 48.9 0.452 0.216 540 25.8 3 2.63 0.0176 0 40.8 1.82 2.79 0.122 0.198 39.8 1.99 127 0.81 2.13 1950 84.7 44.6 0.149 0 591 22.1 3.5 2.87 0.336 0 41.5 1.78 2.43 0.207 0 36.7 1.56 127 4.02 0 1940 89.5 44.2 0 0 592 25.1 3.5 3.27 0.29 0.0808 49.1 2.6 2.8 0.066 0.192 36.8 1.89 174 0.596 0 1820 84.1 37.1 0.131 0.334 409 16.9 4 3.42 0.0905 0.217 48.1 2.12 2.93 0 0.305 37.4 1.59 173 0 0.149 1820 87 41.7 0.65 0.607 436 18.1 4 2.2 0.09 0.0037 32.5 1.62 2.98 0.0487 0.0271 32.4 1.95 149 1.55 0 1610 71.7 32.9 0.273 0.59 328 13.9 4.5 2.25 0.107 0 32.9 1.78 2.67 0.261 0.328 29.6 0.802 142 1.5 0 1560 70.6 31.3 0.0813 0 320 14.5 4.5 4.67 0.154 0.0018 32.9 1.76 2.16 0 0.14 25.8 1.28 97.6 1.51 4.17 1270 53.3 31.7 0 0.511 299 13 5 4.04 0.26 0.0412 32.2 1.19 2.37 0.193 0.177 27 1.04 92.7 1.85 0.67 1210 59.2 31.5 0.109 0 301 14.5 5 1.66 0.256 0.0291 25.9 1.31 2.04 0.168 0.0344 20.2 0.717 78 0 0 1190 49.6 16.2 0.766 0 255 11.8 5.5 1.95 0.0858 0 25.3 1.43 1.77 0.0399 0.39 20.3 0.851 80 4.06 0 1190 57 17.2 0 0 249 10.7 5.5 1.85 0 0.169 21.2 0.969 1.37 0.0457 0 20.2 0.976 61.7 2.35 0 876 41.1 14.7 0.32 1.16 193 7.95 6 1.65 0 0 21.2 0.587 1 0.129 0 18.4 0.884 67.5 1.2 0 876 39.2 14 0 0.653 185 8.22 6 1.85 0.0383 0.233 22.1 1.27 0.866 0.0847 0 15.1 0.463 53.9 3.87 0.309 708 32.5 13.4 0.117 1.06 162 7.64 6.5 1.73 0 0.129 22.5 0.833 0.914 0.0582 0 14.4 0.138 58.6 1.12 0.754 719 30.4 12.9 0 0 159 5.75 6.5 1.6 0 0 18.7 0.783 1.12 0 0 13.9 0.607 82.3 0 0 647 27.2 8.73 0.297 0 119 5.19 7 1.5 0.56 0 18 0.842 1.22 0.0458 0 13.1 0.499 78.8 1.82 0 623 29.4 8.67 0.228 0 120 5.5 7 1.28 0.0998 0.15 13.3 0.985 0.554 0 0.0617 8.84 0.245 40.2 2.39 0 489 21.1 9.51 0.625 0.33 121 4.94 7.5 1.16 0 0.0077 13.4 0.565 0.675 0 0.0448 9.24 0.476 39.2 0 0.192 481 21.4 9.09 0.836 0 116 5.28 7.5 0.693 0.0423 0 11.5 0.663 1.08 0.0819 0.0987 9.14 0.0638 25.5 0.0165 0 356 15.3 5.83 0.039 0 87.6 3.8 8 0.661 0.0557 0.211 11.4 0.509 1.06 0.0998 0.0796 9.04 0.586 25.5 0.82 0 344 14.9 5.75 0.21 0.23 85.6 3.33 8 0.746 0.0567 0.223 9.42 0.349 0.995 0.232 0.202 7.07 0.913 20.6 1.04 0 339 15.2 7.57 0.12 0.195 78.8 3.02 8.5 0.852 0 0 8.77 0.938 0.831 0 0.0095 6.79 0.384 10.9 1.15 1.64 326 12.2 8.29 0 0 78.6 3.22 8.5 0.469 0.229 0 6.66 0.0523 0.323 0 0 5.25 1.4 13.9 0.0513 0 236 9.97 4.98 0 0 57.7 1.59 9 0.43 0.0319 0 7.48 0.292 0.417 0 0.0084 4.88 0.354 13.9 0 0.545 234 10.3 3.97 0.136 0.0244 53.4 3.45 9 0.645 0.174 0 6.88 0.639 0.216 0.0658 0.0672 4.11 0.215 14 0.212 0.159 213 8.58 3.06 0 0 45.1 1.34 9.5 0.609 0.226 0.123 6.45 0.491 0.256 0.0438 0.0647 3.98 0.0822 13.6 0.511 0 198 8.25 3.34 0 0 41.6 1.55

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 4 (continued) - Unit 2 Containment Continuing Characterization Concrete Core Samples - On-Site Analysis B1-02110C-JWC-016-CV (cont) B1-02110C-JWC-017-CV (cont) B1-02110C-JWC-018-CV (cont) B1-02110C-JWC-019-CV (cont)

Depth Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 (in) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) 9.5 0.258 0.187 0.0287 4.81 3.53 0.446 0.0374 0 3.64 0 12.5 0 0.211 200 8.52 3.41 0.273 0.102 37.1 1.75 10 0.398 0 0 5.36 0.248 0.344 0 0 3.67 0.216 12.4 0.363 1.2 199 7.95 3.29 0.421 0 36.5 1.73 10 0.41 0 0.135 4.47 1.23 0.377 0 0.186 2.57 2.06 10.7 0.66 0.293 136 5.68 2.73 0.0325 0.0837 33.5 1.4 10.5 0.331 0.0064 0 4.46 0.127 0.351 0 0.139 2.62 0.211 10.9 0 0.0209 133 4.89 2.99 0.0714 0.106 33.4 1.73 10.5 0.389 0 0.0372 4.02 0.38 0.178 0 0 2.06 0.719 10.7 0.156 0 124 5.46 1.99 0 0 28.4 1.05 11 0.298 0 0.0911 3.7 1.19 0.195 0 0 2.09 0 10.1 0.309 0 122 3.88 2.62 0 0.308 29.1 1.01 11 0.427 0.0757 0.207 2.77 0.709 0.231 0.0763 0.0675 1.96 0.412 10.8 0.156 0 106 3.81 3.16 0.147 0 23.1 1.15 11.5 0.129 0.0618 0.0008 2.3 1.74 0.252 0.0143 0 2.03 0.151 9.17 0.122 0 102 4 2.75 0.232 0 21.4 1.07 11.5 0.12 0 0 1.93 1.53 0.147 0.042 0.0731 1.61 1.52 4.32 0.847 0 75.7 2.54 1.16 0.304 0.0878 16.7 0.706 12 0.143 0 0.0019 1.87 1.41 0.115 0.026 0.0601 1.45 0.988 3.63 0.147 0 75.4 3.28 1.31 0.146 0 16.2 0.78 12 0.167 0.0014 0 2.02 0.132 0.248 0 0 1.07 0.721 3.84 0.313 0.263 57.9 2.51 1.15 0.148 0 15.6 0.964 12.5 0.301 0.0051 0 1.96 0.218 0.154 0.0334 0 1.34 0.0131 4.21 2.73 0.0973 60.1 2.34 1.22 0.214 0 14.5 0.558 12.5 0.132 0 0.0485 1.38 0.905 0.0931 0.0025 0.023 0.841 0.667 2.97 0.169 0 44.1 2.39 0.693 0 0.0080 9.21 0.638 13 0.0999 0 0.108 1.24 0.434 0.126 0 0 0.737 0 2.51 0.142 0.332 44.3 2.34 0.544 0 0 9.01 7.27 13 0.21 0 0 1.08 0.0666 0 0.185 0.0021 1.09 0.486 4.65 0.185 0 52.4 2.22 0.499 0 0.0231 8.15 5.34 13.5 0.11 0 0 1.15 0.785 0.14 0.381 0.0061 0.529 0.408 4.09 3.35 0 46.8 1.16 0.645 0.0924 0 7.26 0.438 13.5 0.123 0.0166 0.0253 0.718 0.477 0.129 0 0.0435 0.571 0.328 0.636 0.104 0 9.84 0.811 0.521 0.0731 0 5.9 0.125 14 0.144 0.0859 0 0.844 0.463 0.108 0 0 0.602 0.449 0.773 1.82 0 11.1 8.64 0.397 0 0.147 5.5 0.231 14 0.181 0.0107 0.0040 0.675 0.105 0.0014 0 0.028 0.472 0.3 1.48 0.407 0 32.4 24.3 0.323 0.0573 0 2.53 0 14.5 0.157 0.0532 0.244 0.78 0.0364 0.0873 0.0432 0 0.425 0.409 1.54 0.181 0.247 33.4 0.623 0.288 0.0359 0.0224 2.36 0.463 14.5 0.0888 0 0.0702 0.494 0.546 0.124 0 0.0436 0.32 0.278 1.43 0.89 0.257 21.4 13.8 0.372 0.062 0.0030 5.11 0.0769 15 0.286 0.0924 0 0.392 0.582 0.092 0 0 0.382 0.345 1.29 0.374 0.311 19.4 0.563 0.353 0.0448 0.169 4.35 0.275 15 0.132 0 0.0638 0.556 0 0.0873 0.11 0 0.314 0.236 1.92 0.0896 0.245 14.7 0.96 0.177 0.0845 0.043 3.15 0.344 15.5 0.096 0 0 0.444 0.286 0.0675 0 0 0.242 0.206 2.37 0.156 0.226 14.2 0.894 0.209 0 0.0191 2.99 1.87 15.5 0.146 0.0662 0 0.317 0.281 0.133 0.0678 0 0.15 0.1 1.68 0.33 0.0704 0.122 2.35 0.165 16 0.116 0 0.0648 0.429 0.327 0.115 0 0.112 0.126 0.0472 1.6 0.12 0 0.0554 2.18 0.424 16 0.0905 0 0 0.253 0.265 0.0595 0.19 0.0165 0.0701 0.284 0.201 0 0.0188 1.51 0.0695 16.5 0.0772 0 0.106 0.307 0.247 0.0367 0 0.0538 0.289 0.224 0.214 0.0679 0.128 1.67 0.515 16.5 0.0208 0 0 0.172 0.0109 0.0356 0.0102 0.018 0.0129 0.01 0.149 0.154 0.379 1.22 0.169 17 0.129 0.184 0.136 0.0131 0.189 0.0813 0 0.878 1.09 0.833 17 0.0487 0 0.0379 0.0556 0.176 0.149 0 19 0.663 0.64 17.5 0.113 0.135 0.13 0.0313 0.128 0.166 0.344 29.8 0.793 0.311 17.5 0.108 0.0717 0 0.14 0.0037 18 0.113 0.0058 0.0127 0.0611 0.146 0.0217 0 0 0.0345 0.0222 18 0.135 0.0126 0.121 0.0675 0.0443 0.105 0 0 0.171 0.127 18.5 0.107 0.0536 0.0606 0.27 0.0227 0.0428 0.0192 0.0394 0 0.089 18.5 0.105 0.0516 0 0.0393 0 0.0604 0.0278 0 0.0514 0.077 19 0.128 0.0832 0.0223 0.0503 0.248 0.126 0 0.0616 0.139 0.0523

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 5 - Unit 2 Containment Continuing Characterization Concrete Core Samples - Eberline Laboratory Analysis B102110-CJWC-001CV B102110-CJFC-005CV Nuclide Result Uncertainty MDA Result Uncertainty MDA

>MDA >MDA (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g)

H-3 6.99E+01 1.25E+01 1.84E+01 Yes 5.72E+01 1.44E+01 2.22E+01 Yes C-14 3.19E+00 2.68E+00 4.47E+00 No 1.01E+01 2.55E+00 4.02E+00 Yes Fe-55 4.05E+00 6.61E+00 1.00E+01 No 2.26E+00 6.03E+00 9.12E+00 No Ni-59 2.53E+01 8.21E+01 1.34E+02 No 1.53E+00 3.43E+01 5.50E+01 No Co-60 2.65E+00 5.07E-01 1.31E-01 Yes 7.49E+01 5.47E+00 2.23E+00 Yes Ni-63 1.15E+04 5.08E+01 8.49E+00 Yes 5.60E+02 7.38E+00 3.45E+00 Yes Sr-90 1.74E+02 3.55E+00 8.13E-01 Yes 9.38E+00 9.07E-01 8.03E-01 Yes Nb-94 0.00E+00 5.04E-01 6.65E-01 No 8.75E-01 1.23E+00 3.12E+00 No Tc-99 1.61E+00 7.55E-01 1.24E+00 Yes 1.59E+00 7.45E-01 1.22E+00 Yes Ag-108m 3.37E-01 4.36E-01 8.09E-01 No 1.49E+00 2.50E+00 3.47E+00 No Sb-125 0.00E+00 1.30E+01 1.85E+01 No 3.89E+00 3.09E+01 3.83E+01 No Cs-134 0.00E+00 2.60E+00 8.52E-01 No 0.00E+00 4.38E+00 3.18E+00 No Cs-137 1.68E+03 2.96E+02 6.66E+00 Yes 1.04E+04 1.72E+03 2.28E+01 Yes Pm-147 2.32E+00 8.88E-01 1.43E+00 Yes 1.49E+01 1.26E+00 1.65E+00 Yes Eu-152 9.24E+00 2.33E+00 1.17E+00 Yes 8.14E+01 9.68E+00 6.67E+00 Yes Eu-154 3.90E-01 4.42E-01 1.40E+00 No 2.25E+00 3.17E+00 5.55E+00 No Eu-155 0.00E+00 5.15E+00 5.32E+00 No 1.09E+01 8.21E+00 1.36E+01 No Np-237 4.64E-03 3.00E-02 8.17E-02 No 4.15E-02 5.35E-02 7.45E-02 No Pu-238 0.00E+00 4.28E-02 1.46E-01 No 3.59E-02 8.23E-02 1.60E-01 No Pu-239/240 3.39E-02 6.59E-02 1.23E-01 No 6.30E-02 8.03E-02 1.20E-01 No Pu-241 0.00E+00 5.66E+00 9.77E+00 No 0.00E+00 5.77E+00 1.00E+01 No Am-241 0.00E+00 3.46E-02 1.14E-01 No 4.33E-02 7.09E-02 1.24E-01 No Am-243 8.44E-02 8.72E-02 1.10E-01 No 3.40E-02 5.77E-02 9.79E-02 No Cm-243/244 1.53E-02 4.53E-02 9.86E-02 No 1.04E-01 8.30E-02 7.49E-02 Yes

[34]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 6 - HTD Ratios Based on Continuing Characterization Concrete Core Samples Sample ID H-3 to Cs-137 Ni-63 to Co-60 Sr-90 to Cs-137 B102110-CJWC-001CV 0.0416 4,339 0.1036 B102110-CJFC-005CV 0.0055 7.4770 0.0009 The maximum ratios from LTP Table 5-15 were exceeded by the Ni-63/Co-60 ratio of 4,339 and Sr-90/Cs-137 ratio of 0.1036. LTP section 5.2.11 states, The maximum ratios will be used in the surrogate calculations during FSS unless area specific ratios are determined by continuing characterization. Note that the 95% UCL is conservatively based in the standard deviation of the individual values as opposed to the standard deviation of the mean. Any future continuing characterization or FSS data that contains positive results for H-3, Ni-63 and Sr-90 will be reviewed. In these cases, the area specific ratios as determined by actual survey data will be used in lieu of the maximum ratios presented in Table 5-15. The area-specific ratios used and the survey data serving as the basis for the ratios will be documented in the release record for the survey unit.

Due to the fact that unreasonably high concentrations of Ni-63 and Sr-90 would be inferred using the ratios from the continuing characterization samples, an additional set of concrete core samples were acquired post-remediation to represent as end-state condition of the concrete following the removal of the source term. Concrete core samples taken during implementation of the 1st set of continuing characterization concrete core samples were determined to be not relevant due to the continuing remediation of concrete surfaces in the Under Vessel and Incore Areas after the concrete cores were collected. Additional concrete core samples were taken post-remediation and as part of the FSS for the Under Vessel Area to validate radionuclide ratios.

The secondary objective of the continuing characterization concrete core samples were to assess the depth of activation in the concrete in order to ensure the correct geometry was used for the ISOCS measurements. Based on the assessment of the analytical results of ROC concentrations at depth as presented in Table 4, an exponential circular plane geometry with a 17.8 cm depth of contamination and a depth relaxation length (DRL) of 8.6 cm was chosen as the default template.

LTP section 5.1 states, concrete cores will be collected during FSS to confirm the HTD to surrogate radionuclide ratios used for the surrogate calculation. Only HTD radionuclides included as ROC (H-3, Ni-63, Sr-90, for Containment and Ni-63 and Sr-90 for all other structures and soils) will be analyzed in the FSS confirmatory samples.

Concrete cores will be collected from the Auxiliary Building basement, Spent Fuel Pool (SFP)/Transfer Canal, and the Under-Vessel areas in Containment where concrete will

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 remain. The number of cores collected and analyzed for ROC HTD will be ten percent (10%) of the FSS ISOCS measurements. The concrete core locations will be selected from the floor and lower walls in the survey unit to alleviate safety concerns from working at heights and to focus on the areas expected to contain the majority of residual radioactivity.

The survey design for the Under Vessel concrete as specified in LTP Table 5-19, required a minimum of 19 ISOCS measurements and consequently, two additional concrete core samples were collected to meet the requirements of LTP section 5.1. As a consequence of the results of the concrete core samples taken during continuing characterization, an additional 19 concrete cores were taken from the post-remediated concrete walls and floors. These concrete core samples represented the as-left condition of the Under Vessel concrete at the time FSS was performed. The concrete surfaces that were represented by the continuing characterization concrete samples were remediated twice and the actual concrete that was sampled (original concrete surface to a depth of 1/2 inch) had been removed and disposed of as radioactive waste. At least a foot of concrete was removed from the Under Vessel floor and up to 6 inches of concrete removed from the walls. A 6-inch concrete core was obtained at the center of the FOV of every ISOCS measurement acquired in the Under Vessel region (for a total of nine) and adjacent to the location of the continuing characterization cores. The pucks representing the existing post-remediation grade of the concrete to a depth of 1/2 inch for the 19 selected locations were sent to Eberline Laboratories for analysis results for Sr-90, H-3, Ni-63 and gamma spectroscopy.

The results are presented in Attachment 7 of this Release Record.

Containment turnover also included the continuing characterization survey of the exposed steel liner above the 565 foot elevation. The objective of the survey was to assess the radiological condition of the exposed steel liner above the 565 foot elevation after the contaminated concrete has been removed. The liner was subjected to sufficient smear samples and beta scans of the accessible surfaces to demonstrate that the liner was adequately decontaminated prior to FSS. Locations for taking samples and/or measurements were biased toward locations with high potential for the presence of loose or fixed contamination. All swipe samples taken showed loose surface contamination results that were less than 1,000 dpm/100cm2.

During the removal of the concrete from the floor above the 565 foot elevation, several instances occurred where the steel liner was punctured by the ram-hoe used to break apart the concrete. During these occurrences, work was stopped and the area was surveyed for loose surface contamination. In all cases, swipe samples taken of the puncture locations showed loose surface contamination of less than 1,000 dpm/100cm2. No conditions were encountered that indicated any potential cross-contamination of media outside of the liner.

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 A patch was welded over each puncture location to prevent any future potential cross-contamination.

A Radiological Engineer (RE) performed a visual inspection and walk-down of the Unit 2 Containment Basement survey units 02100 and 02110 on January 9, 2018 as part of the initial turnover for performing FSS. The purpose of the walk-down was to assess the physical condition of the survey units, evaluate access points and travel paths and identify potentially hazardous conditions. A final classification assessment was performed in accordance with procedure ZS-LT-300-001-002, Survey Unit Classification (Reference 8) as part of the survey design for FSS.

Based upon completion of the Survey Unit Classification Basis for final classification, which included a review of the historical information, the results of the Characterization Survey data and, completion of a final Survey Unit Classification Worksheet, the correct final classification of survey units 02100 and 02110 were determined to be Class 1.

4. DATA QUALITY OBJECTIVES (DQO)

Final Status Survey planning and design hinges on coherence with the Data Quality Objective (DQO) process to ensure, through compliance with explicitly defined inputs and boundaries, that the primary objective of the survey is satisfied. The DQO process is described in the ZSRP LTP in accordance with MARSSIM. The appropriate design for a given survey is developed using the DQO process as outlined in Appendix D of MARSSIM.

The DQO process incorporated hypothesis testing and probabilistic sampling distributions to control decision errors during data analysis. Hypothesis testing is a process based on the scientific method that compares a baseline condition to an alternate condition. The baseline condition is technically known as the null hypothesis. Hypothesis testing rests on the premise that the null hypothesis is true and that sufficient evidence must be provided for rejection. In designing the survey plan, the underlying assumption, or null hypothesis was that residual activity in the survey unit exceeded the release criteria. Rejection of the null hypothesis would indicate that residual activity within the survey unit does not exceed the release criteria. Therefore, the survey unit would satisfy the primary objective of the FSS sample plan.

The primary objective of the FSS sample plan was to demonstrate that the level of residual radioactivity in survey units 02100 and 02110 did not exceed the release criteria specified in the LTP and that the potential dose from residual radioactivity was As Low As Reasonably Achievable (ALARA).

ZionSolutions TSD 11-001, Technical Support Document for Potential Radionuclides of Concern During the Decommissioning of the Zion Station (Reference 9) established the

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 basis for an initial suite of potential ROC for the decommissioning of the Zion Nuclear Power Station (ZNPS). LTP Chapter 2 provides detailed characterization data that described contamination levels in the Containment basement at the time site characterization was performed. The survey data for this basement was based on core samples obtained at biased locations with elevated contact dose rates and/or evidence of leaks/spills and analyzed for the presence of plant-derived radionuclides.

ZionSolutions TSD 14-019, Radionuclides of Concern for Soil and Basement Fill Model Source Terms (Reference 10) evaluated the results of the concrete core analysis data from the Containments and Auxiliary Building and refined the initial suite of radionuclides to potential ROC by evaluating the dose significance of each radionuclide.

LTP Chapter 6, section 6.5.2 discusses the process used to derive the ROC for the decommissioning of ZNPS, including the elimination of insignificant dose contributors (IC) from the initial suite. Table 7 presents the ROC for the Containment Basement structural surfaces and the normalized fractions based on the radionuclide mixture.

Table 7 - Dose Significant Radionuclides and Mixture

% of Total Activity Radionuclide (normalized)(1)

H-3 0.08%

Co-60 4.72%

Ni-63 26.50%

Sr-90 0.05%

Cs-134 0.01%

Cs-137 68.17%

Eu-152 0.44%

Eu-154 0.06%

(1) Based on maximum percent of total activity from Table 20 of TSD 14-019, normalized to one for the dose significant radionuclides.

A fundamental precursor to survey design is to establish a relationship between the release criteria and some measurable quantity. This is done through the development of Derived Concentration Guideline Levels (DCGL). The DCGLs represent average levels of radioactivity above background levels and are presented in terms of surface or mass activity concentrations. Chapter 6 of the LTP describes in detail the modeling used to develop the DCGLs for structures.

The end-state basements are comprised of steel and/or concrete structures that will be covered by at least three feet of clean soil and physically altered to a condition where it

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 would not realistically allow the remaining structures, if excavated, to be occupied. The exposure pathways in the Basement Fill Model (BFM) are associated with residual radioactivity in floors and walls that is released through leaching into water contained in the interstitial spaces of the fill material. The BFM assumes that the inventory of residual radioactivity in a given building is released either instantly or over time by diffusion, depending on whether the activity is surficial or volumetric, respectively. The activity released into the fill water will adsorb onto the clean fill, as a function of the radionuclide-specific distribution coefficients, resulting in equilibrium concentrations between the fill and the water. Consequently, the only potential exposure pathways after backfill, assuming the as-left geometry, are associated with the residual radioactivity in the water contained in the fill.

The final outputs of the BFM are the Basement DCGLs, in units of pCi/m2, which are calculated using the BFM Groundwater (GW) and BFM Drilling Spoils Dose Factors (LTP Chapter 6, Tables 6-24 and 6-25). DCGLs are calculated separately for the GW and Drilling Spoils scenarios and for the summation of both scenarios. The summation DCGL is designated as the (Base Case DCGL) BcDCGL and is used during FSS to demonstrate compliance (analogous to the DCGLW as defined in MARSSIM). The BcDCGLs are radionuclide-specific concentrations that represent the 10 CFR 20.1402 dose criterion of 25 mrem/yr and are calculated for each ROC and each backfilled basement.

When applied to structures, the DCGLs are expressed in units of activity per unit of area (pCi/m2). The unity rule is applied when there is more than one ROC. The measurement results for each singular ROC present in the mixture are compared against their respective DCGL to derive a dose fraction.

The BcDCGLs for the unrestricted release of the Containment basement survey units are provided in Table 8. The IC dose percentage of 10% was used to adjust the Containment basement DCGLs to account for the dose from the eliminated IC radionuclides.

Each radionuclide-specific BcDCGL is equivalent to the level of residual radioactivity (above background levels) that could, when considered independently, result in a Total Effective Dose Equivalent (TEDE) of 25 mrem/yr to an Average Member of the Critical Group (AMCG). To ensure that the summation of dose from each source term is 25 mrem/yr or less after all FSS is completed, the BcDCGLs are reduced based on an expected, or a priori, fraction of the 25 mrem/yr dose limit from each source term. The reduced DCGLs, or Operational DCGLs can be related to the BcDCGLs as an expected fraction of dose based on an a priori assessment of what the expected dose should be based on the results of site characterization, process knowledge and the extent of planned remediation. The OpDCGL is then used as the DCGL for the FSS design of the survey unit (calculation of surrogate DCGLs, investigations levels, etc.). Details of the

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 OpDCGLs derived for each dose component and the basis for the applied a priori dose fractions are provided in TSD 17-004.

Table 8 - Base Case DCGLs for Containment (BcDCGLB) from LTP Chapter 5, Table 5-3 Base Case DCGL Radionuclide (pCi/m2)

H-3 2.38E+08 Co-60 1.57E+08 Ni-63 4.02E+09 Sr-90 1.43E+06 Cs-134 3.01E+07 Cs-137 3.94E+07 Eu-152 3.66E+08 Eu-154 3.19E+08 The OpDCGLs for the unrestricted release of the Containment basement survey units 02100 and 02110 are provided in Table 9.

Table 9 - Operational DCGLs (OpDCGLB) for Containment from LTP Chapter 5, Table 5-4 Operational DCGL Operational DCGL Radionuclide (pCi/m2) (pCi/m2)

Above 565 foot Under Vessel H-3 3.25E+07 2.37E+08 Co-60 2.15E+07 1.56E+08 Ni-63 5.50E+08 4.00E+09 Sr-90 1.96E+05 1.42E+06 Cs-134 4.12E+06 2.99E+07 Cs-137 5.39E+06 3.92E+07 Eu-152 5.00E+07 3.64E+08 Eu-154 4.36E+07 3.17E+08 As part of the DQOs applied to laboratory processes, analysis results were reported as actual calculated results. The actual recorded value was used as the recorded FSS result for measurement and/or sample values that are less than MDC. Negative values were recorded as zero. For radionuclides less than MDC, the value representing the highest

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 abundance was selected. Results were not reported as less than MDC. Sample report summaries included unique sample identification, analytical method, radionuclide, result, uncertainty, laboratory data qualifiers, units, and the observed MDC.

Instrument DQOs included a verification of the ability of the survey instrument to detect the radiation(s) of interest relative to the OpDCGL. Response checks were required prior to issuance and after use. Control and accountability of ISOCS units was required to assure data quality.

In accordance with the LTP, for laboratory analysis, MDCs less than 10% of the OpDCGL were preferable while MDCs up to 50% of the OpDCGL were acceptable. The maximum acceptable MDC for measurements obtained using field instruments was 50 percent of the applicable OpDCGL.

5. SURVEY DESIGN Guidance for preparing FSS plans was provided in procedure ZS-LT-300-001-001. The FSS plan uses an integrated sample design that combines direct measurements (by ISOCS) and sampling (concrete cores).

The Canberra ISOCS was selected as the instrument of choice to perform FSS of basement surfaces because its measurements will provide results that can be used directly to determine total activity with depth in concrete, and, the surface area covered by a single ISOCS measurement is large (a nominal FOV of 10-30 m2) which essentially eliminates the need for scan surveys. In addition, after an ISOCS measurement is collected, it can be tested against a variety of geometry assumptions to address uncertainty in the source term geometry if necessary.

The source term geometry for ISOCS efficiency calibration, i.e., concentration depth profile and areal distribution of the residual radioactivity in structures, is required to generate efficiency curves (i.e., efficiency as a function of energy) for the ISOCS gamma spectroscopy measurements. The concrete cores obtained during characterization, continuing characterization and FSS provided the requisite information regarding the distribution of activity with depth for the Under Vessel concrete. The source term geometry for the Containment above the 565 foot elevation is 1/2-inch plate steel with no concrete. The basis for the chosen ISOCS efficiency calibrations for the FSS of the Under Vessel concrete and the steel liner above the 565 foot elevation are documented in ZionSolutions TSD 14-022, Use of In-Situ Gamma Spectroscopy for Final Status Survey of End State Structures (Reference 11). For the FSS of the steel liner above the 565 foot elevation, a circular plane geometry with a 1/2 inch depth of contamination was selected as the default template. For the concrete in the Unit 2 Under Vessel area, an exponential circular plane geometry with a 17.8 cm depth of contamination and a DRL

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 of 8.6 cm was chosen as the default template. The basis for the selection of this geometry was the result of concrete core samples taken during continuing characterization which were analyzed for ROC concentration at depth in concrete.

In section 5.5.2.2 of the LTP, the number of ISOCS measurements required in each FSS unit was calculated as the quotient of the ISOCS FOV divided into the surface area required for areal coverage. Table 10, which is reproduced from LTP Table 5-18, presents the FSS units for the Unit 2 Containment, the classification based on contamination potential, the surface area to be surveyed and the minimum number of ISOCS measurements based on a measurement FOV of 28 m2.

Table 10 - Number of ISOCS Measurements per FSS Unit based on Areal Coverage Minimum # of Minimum Area ISOCS FSS Unit Classification Areal Coverage Measurements (m2) (% of Area) (FOV-28 m2)

Unit 2 Containment Basement Class 1 2,465 100% 88 above 565 foot elevation Unit 2 CTMT Under-Vessel Area Class 1 294 100% 11 To ensure that the number of ISOCS measurements based on the necessary areal coverage in a basement surface FSS unit was sufficient to satisfy a statistically based sample design, a calculation was performed and documented in LTP section 5.5.2.2 to determine sample size using the standard method as presented in MARSSIM. If the sample size based on the statistical design required more ISOCS measurements than the number of ISOCS measurement required by the areal coverage, then the number of ISOCS measurements was adjusted to meet the larger sample size.

Following MARSSIM guidance, the Type I and Type II decision errors were set at 0.05.

The Upper Bound of the Gray Region (UBGR) was set at the OpDCGLB. The Lower Bound of the Gray Region (LBGR) was set at the expected fraction of 50% of the OpDCGLB. For the FSS unit in Unit 2 Containment above the 565 foot elevation, the entire concrete source term above the 565 foot elevation was removed. Consequently, the results of the concrete core samples taken above the 565 foot elevation in Unit 2 Containment were not representative of the conditions at the time of FSS. As reasonable value for sigma () could not be determined based on existing survey data, a coefficient of variation of 30% was used in accordance with the guidance in MARSSIM, section 5.5.2.2.

For the Class 1 survey unit in the Containment Under-Vessel area, the standard deviation of the cores collected during characterization were used for sigma ().

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 The relative shift (/) was calculated as discussed in LTP section 5.6.4.1.6. The relative shift (/) was greater than three for the FSS unit above the 565 foot elevation.

Consequently, a value of three was used as the adjusted relative shift (/). The relative shift (/) for the Under Vessel area was two. From Table 5-5 of MARSSIM, the required number of measurements (N) for use with the Sign Test, using a value of 0.05 for the Type I and Type II decision errors, is 14 measurements for a / value of three and 15 for a / value of 2. Consequently, the number of ISOCS measurements in the Under Vessel FSS unit was adjusted to meet the larger sample size.

As previously noted, the required areal coverage for a Class 1 basement survey unit was 100%. The LTP required that sufficient measurements be taken in a Class 1 FSS unit to ensure that 100% of the surface area was surveyed (ISOCS FOV overlapped to ensure that there were no un-surveyed corners and gaps). In cases where the physical configuration or measurement geometry makes the acquisition of a 28 m2 FOV difficult or prohibitive, then the FOV for the ISOCS measurement was reduced provided that the adjusted number of samples remained constant and the minimum areal coverage represented by the FSS unit classification was achieved. To ensure that were no unsurveyed corners and gaps, the number of measurements that were taken in both Unit 2 Containment Class 1 FSS units were adjusted by overlaying the center-point of the 28 m2 FOV for the ISOCS measurement on a 4m x 4m (16 m2) grid system. Table 11, which is reproduced from LTP Table 5-19, presents the Unit 2 Containment FSS units and the adjusted number of ISOCS measurements that will be taken in each survey unit.

Table 11 - Adjusted Minimum Number of ISOCS Measurements per FSS Unit Required Adjusted # of Adjusted Adjusted Areal ISOCS Areal Areal FSS Unit Classification Coverage Measurements Coverage Coverage (m2) (FOV-28 m2) (m2) (% of Area)

Unit 2 CTMT above Class 1 2,465 155(1) 2,465 100%

565 foot elevation Unit 2 CTMT Under Class 1 294 19(1) 294 100%

Vessel Area (1) Adjusted to ensure number of measurements that will be taken in Class 1 FSS units will ensure 100% areal coverage, including overlap to ensure that there are no un-surveyed corners and gaps (FOV based on a 4m x 4m grid system).

When the survey grids were established on the 565 foot elevation and in the Under Vessel area, obstacles and physical constraints were encountered that prompted further adjustments to the number of samples and the FOV. Some measurements were not feasible and other measurement locations were added. After adjustments to the survey design, a total of one hundred and sixty four (164) ISOCS measurements were taken above the 565 foot elevation in Unit 2 Containment; sixty eight (68) on the lower wall and

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 ninety six (96) on the floor (metal liner) and in the Cavity Flood Sump and the Recirculation Sump.

Nineteen (19) ISOCS measurements were originally planned for the Under Vessel area (FSS unit 02110), based on a stand-off distance of 3-meters for the ISOCS detector.

Additional measurements were required due to constraints caused by the limited space in the Incore Tunnel Area, which increased the total number of ISOCS measurements necessary to achieve 100% areal coverage to fifty four (54) ISOCS measurements.

The DQO process determined that H-3, Co-60, Ni-63, Sr-90, Cs-134, Cs-137, Eu-152 and Eu-154 would be the ROC in FSS Units 02100 and 02110. During FSS, concentrations for HTD ROC H-3, Ni-63 and Sr-90 were to be inferred using a surrogate approach. Cs-137 is the principle surrogate radionuclide for H-3 and Sr-90 and Co-60 is the principle surrogate radionuclide for Ni-63. The mean, maximum and 95% Upper Confidence Level (UCL) of the surrogate ratios for concrete core samples taken in the Containment Buildings were calculated in TSD 14-019 and are presented in LTP Table 5-15 and Table 12 below. The maximum ratios were to be used to infer HTD concentrations during FSS unless area specific ratios were determined.

Table 12 - Surrogate Ratios for Containment Containments Ratios Mean Max 95%UCL H-3/Cs-137 0.208 1.760 0.961 Ni-63/Co-60 30 442 193 Sr-90/Cs-137 0.002 0.021 0.010 For the FSS of survey units 02100 and 02110, the surrogate OpDCGLs for Co-60 and Cs-137 were computed based on the maximum ratios from Table 12.

The equation for calculating a surrogate DCGL is as follows:

Equation 1 1

=

1 2 3

+ + +

2 3 Where: DCGLSur = Surrogate radionuclide DCGL DCGL2,3n = DCGL for radionuclides to be represented by the surrogate Rn = Ratio of concentration (or nuclide mixture fraction) of radionuclide n to surrogate radionuclide

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Using the OpDCGLs for Unit 2 Containment above the 565 foot elevation presented in Table 9 and the maximum ratios from Table 12, the following surrogate calculations were performed for FSS unit 02100; Equation 2 1

(137) = = 2.88 + 06 /2 1 0.021 1.760

+ +

5.39 + 06(137) 1.96 + 05(90) 3.25 + 07(3)

The surrogate OpDCGL that was used for Cs-137 in FSS unit 02100 for direct comparison of sample results to demonstrate compliance is 2.88E+06 pCi/m2.

Equation 3 1

(60) = = 1.18 + 06 /2 1 442

+

2.15 + 07(60) 5.50 + 08(63)

The surrogate OpDCGL that was used for Co-60 in FSS unit 02100 for direct comparison of sample results to demonstrate compliance is 1.18E+06 pCi/m2.

Using the OpDCGLs for Unit 2 Containment Under Vessel area presented in Table 9 and the maximum ratios from Table 12, the following surrogate calculations were performed for FSS unit 02110; Equation 4 1

(137) = = 2.10 + 07 /2 1 0.021 1.760

+ +

3.92 + 07(137) 1.42 + 06(90) 2.37 + 08(3)

The surrogate OpDCGL that was used for Cs-137 in FSS unit 02110 for direct comparison of sample results to demonstrate compliance is 2.10E+07 pCi/m2.

Equation 5 1

(60) = = 8.55 + 06 /2 1 442

+

1.56 + 08(60) 4.00 + 09(63)

The surrogate Operational DCGL that was used for Co-60 in FSS unit 02110 for direct comparison of sample results to demonstrate compliance is 8.55E+06 pCi/m2.

Previous sections of this report have discussed the commitment from LTP section 5.1 to acquire concrete core samples at 10% of the locations where an ISOCS measurement was collected with the locations selected at random. Only HTD radionuclides included as ROC (H-3, Ni-63, Sr-90, for Containment) were analyzed in the FSS confirmatory

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 samples. For FSS unit 02100 which pertains to Unit 2 Containment above the 565 foot elevation, no concrete media remains. Consequently, no confirmatory concrete core samples were required as part of the FSS survey design. For FSS unit 02110 which pertains to Unit 2 Containment Under Vessel area, the survey design required a minimum of fifty-four (54) ISOCS measurements and consequently, five (5) additional concrete core samples were necessary to meet the requirements of LTP section 5.1.

As previously discussed, in response to the results of the continuing characterization concrete core samples, it was acknowledged that the concrete surfaces that were represented by the continuing characterization concrete samples were remediated twice and the actual concrete that was sampled (original concrete surface to a depth of 1/2 inch) had been removed and disposed of as radioactive waste. At least a foot of concrete was removed from the Under Vessel floor and up to 6 inches of concrete removed from the walls. Consequently, an additional 19 concrete core samples were taken on March 7, 2018 as FSS confirmatory samples. The additional 19 concrete cores represented the as-left condition of the Under Vessel concrete following concrete remediation.

A 6-inch concrete core sample was acquired at each of the 19 selected locations. If a concrete core was previously obtained at the same location (continuing characterization),

then the second core (B group) was obtained directly adjacent. In addition, a concrete core was obtained at the center of the FOV of every ISOCS measurement acquired in the Under Vessel region (for a total of nine). The pucks representing the existing post-remediation grade of the concrete to a depth of 1/2 inch for the 19 selected locations (see Figure 9) were sent to Eberline Laboratories for analysis results for Sr-90, H-3, Ni-63 and gamma spectroscopy.

The analysis results for the nineteen (19) concrete core pucks taken post remediation were received from Eberline on March 29, 2018 and the results are presented in Table 13. Each sample or 1/2-inch puck represents the concrete from the existing grade to a depth of 1/2-inch. Each of the 1st 1/2-inch concrete pucks from each of the 19 concrete core samples were analyzed for all ROC, including the HTD ROC of H-3, Ni-63 and Sr-90. In accordance with LTP section 5.1, only samples with positive results (detectable concentrations greater than MDC) were assessed for HTD ratios.

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Figure 9 - Unit 2 Containment FSS Confirmatory Concrete Core Sample Locations

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 13 - FSS Confirmation Concrete Core Sample Analysis - Grade to 0.5 Inch Depth Sample ID Nuclide Result Uncertainty MDC >MDC Ratios (pCi/g) (pCi/g) (pCi/g)

B1-02110IF-IWC-001-CV H-3 8.33E+01 1.63E+01 2.33E+01 Y H-3/Cs-137 = 33.59 Co-60 1.51E+01 1.09E+00 8.04E-01 Y Ni-63 3.36E+00 5.32E+00 8.98E+00 N Ni-63/Co-60 = N/A Sr-90 4.72E-01 3.75E-01 6.09E-01 N (Ni-63 not positively detected)

Cs-134 -4.15E-01 4.87E-01 6.74E-01 N Sr-90/Cs-137 = N/A Cs-137 2.48E+00 9.07E-01 1.32E+00 Y (Sr-90 not positively detected)

Eu-152 1.55E+02 6.36E+00 3.34E+00 Y Eu-154 6.87E+00 1.44E+00 2.55E+00 Y B1-02110IF-IWC-003-CV H-3 1.13E+02 1.48E+01 1.92E+01 Y H-3/Cs-137 = 3.01 Co-60 4.85E+00 4.77E-01 4.42E-01 Y Ni-63 2.83E+01 5.29E+00 8.02E+00 Y Ni-63/Co-60 = 5.84 Sr-90 5.50E-01 4.14E-01 6.72E-01 N Cs-134 -1.91E-02 2.59E-01 4.88E-01 N Sr-90/Cs-137 = N/A Cs-137 3.74E+01 5.90E+00 8.62E-01 Y (Sr-90 not positively detected)

Eu-152 1.05E+02 5.49E+00 2.06E+00 Y Eu-154 3.88E+00 9.23E-01 1.68E+00 Y B1-02110IF-IWC-004-CV H-3 1.20E+02 1.77E+01 2.37E+01 Y H-3/Cs-137 = N/A Co-60 1.13E+01 9.06E-01 7.32E-01 Y (Cs-137 not positively detected)

Ni-63 1.62E+01 4.90E+00 7.78E+00 Y Ni-63/Co-60 = 1.43 Sr-90 6.88E-01 5.02E-01 8.15E-01 N Cs-134 2.02E-01 3.35E-01 7.52E-01 N Sr-90/Cs-137 = N/A Cs-137 1.58E-01 6.44E-01 9.48E-01 N (Cs-137/Sr-90 not positively detected)

Eu-152 1.69E+02 7.04E+00 3.25E+00 Y Eu-154 5.51E+00 1.38E+00 2.52E+00 Y

[48]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 13 (continued) - FSS Confirmation Concrete Core Sample Analysis - Grade to 0.5 Inch Depth Sample ID Nuclide Result Uncertainty MDC >MDC Ratios (pCi/g) (pCi/g) (pCi/g)

B1-02110F-IFC-003-CV H-3 1.69E+02 2.04E+01 2.59E+01 Y H-3/Cs-137 = N/A Co-60 5.47E+00 5.99E-01 5.99E-01 Y (Cs-137 not positively detected)

Ni-63 3.11E+00 5.53E+00 9.36E+00 N Ni-63/Co-60 = N/A Sr-90 2.09E-01 5.09E-01 8.86E-01 N (Ni-63 not positively detected)

Cs-134 3.86E-03 2.12E-01 5.84E-01 N Sr-90/Cs-137 = N/A Cs-137 2.95E-02 5.64E-01 7.66E-01 N (Cs-137/Sr-90 not positively detected)

Eu-152 9.32E+01 3.89E+00 2.30E+00 Y Eu-154 3.39E+00 1.03E+00 1.17E+00 Y B1-02110F-IFC-021-CV H-3 1.29E+02 1.88E+01 2.52E+01 Y H-3/Cs-137 = N/A Co-60 4.49E+00 5.00E-01 5.34E-01 Y (Cs-137 not positively detected)

Ni-63 4.27E+00 5.09E+00 8.56E+00 N Ni-63/Co-60 = N/A Sr-90 6.83E-01 4.51E-01 7.18E-01 N (Ni-63 not positively detected)

Cs-134 -7.35E-01 4.42E-01 5.46E-01 N Sr-90/Cs-137 = N/A Cs-137 -3.20E-01 4.36E-01 6.07E-01 N (Cs-137/Sr-90 not positively detected)

Eu-152 1.02E+02 5.51E+00 2.09E+00 Y Eu-154 2.95E+00 9.60E-01 1.80E+00 Y B1-02110F-IWC-015-CV H-3 1.22E+02 1.62E+01 2.11E+01 Y H-3/Cs-137 = 109.63 Co-60 1.15E+01 8.09E-01 6.84E-01 Y Ni-63 6.91E+00 5.00E+00 8.31E+00 N Ni-63/Co-60 = N/A Sr-90 4.50E-01 4.42E-01 7.35E-01 N (Ni-63 not positively detected)

Cs-134 -1.50E-01 3.73E-01 5.31E-01 N Sr-90/Cs-137 = N/A Cs-137 1.11E+00 4.67E-01 1.10E+00 Y (Sr-90 not positively detected)

Eu-152 1.31E+02 5.86E+00 2.33E+00 Y Eu-154 6.82E+00 1.12E+00 2.02E+00 Y

[49]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 13 (continued) - FSS Confirmation Concrete Core Sample Analysis - Grade to 0.5 Inch Depth Sample ID Nuclide Result Uncertainty MDC >MDC Ratios (pCi/g) (pCi/g) (pCi/g)

B1-02110F-IWC-017-CV H-3 1.21E+02 1.52E+01 1.95E+01 Y H-3/Cs-137 = 55.95 Co-60 7.60E+00 6.76E-01 6.62E-01 Y Ni-63 -8.12E-01 5.68E+00 9.76E+00 N Ni-63/Co-60 = N/A Sr-90 5.13E-01 4.98E-01 8.27E-01 N (Ni-63 not positively detected)

Cs-134 7.41E-02 2.31E-01 6.40E-01 N Sr-90/Cs-137 = N/A Cs-137 2.17E+00 8.04E-01 1.14E+00 Y (Sr-90 not positively detected)

Eu-152 1.58E+02 5.56E+00 3.06E+00 Y Eu-154 5.91E+00 1.24E+00 2.26E+00 Y B1-02110F-IWC-019-CV H-3 3.86E+02 2.19E+01 2.02E+01 Y H-3/Cs-137 = 57.27 Co-60 8.89E+00 7.44E-01 6.22E-01 Y Ni-63 9.28E+00 5.64E+00 9.30E+00 N Ni-63/Co-60 = N/A Sr-90 9.00E-01 4.96E-01 7.74E-01 Y (Ni-63 not positively detected)

Cs-134 1.04E-02 1.63E-01 6.10E-01 N Sr-90/Cs-137 = 0.13 Cs-137 6.75E+00 1.35E+00 1.25E+00 Y Eu-152 1.53E+02 7.84E+00 2.24E+00 Y Eu-154 7.05E+00 1.32E+00 2.39E+00 Y B1-02110F-IWC-020-CV H-3 2.28E+02 2.33E+01 2.80E+01 Y H-3/Cs-137 = N/A Co-60 7.92E+00 5.99E-01 3.68E-01 Y (Cs-137 not positively detected)

Ni-63 1.51E+01 5.52E+00 8.88E+00 Y Ni-63/Co-60 = 1.91 Sr-90 5.64E-01 4.16E-01 6.72E-01 N Cs-134 -4.01E-02 3.21E-01 4.64E-01 N Sr-90/Cs-137 = N/A Cs-137 4.31E-01 4.08E-01 6.08E-01 N (Cs-137/Sr-90 not positively detected)

Eu-152 1.06E+02 3.83E+00 2.11E+00 Y Eu-154 2.91E+00 8.12E-01 1.47E+00 Y

[50]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 13 (continued) - FSS Confirmation Concrete Core Sample Analysis - Grade to 0.5 Inch Depth Sample ID Nuclide Result Uncertainty MDC >MDC Ratios (pCi/g) (pCi/g) (pCi/g)

B1-02110F-IWC-014-CV H-3 1.52E+02 1.94E+01 2.50E+01 Y H-3/Cs-137 = N/A Co-60 8.07E+00 6.91E-01 7.22E-01 Y (Cs-137 not positively detected)

Ni-63 5.61E+00 4.76E+00 7.94E+00 N Ni-63/Co-60 = N/A Sr-90 3.55E-01 4.39E-01 7.41E-01 N (Ni-63 not positively detected)

Cs-134 -2.36E-01 4.21E-01 5.93E-01 N Sr-90/Cs-137 = N/A Cs-137 5.93E-01 4.66E-01 7.55E-01 N (Cs-137/Sr-90 not positively detected)

Eu-152 1.29E+02 5.40E+00 3.03E+00 Y Eu-154 3.62E+00 1.03E+00 1.89E+00 Y B1-02110F-IWC-018-CV H-3 1.52E+02 1.82E+01 2.31E+01 Y H-3/Cs-137 = N/A Co-60 7.87E+00 7.54E-01 6.54E-01 Y (Cs-137 not positively detected)

Ni-63 3.75E+00 5.94E+00 1.00E+01 N Ni-63/Co-60 = N/A Sr-90 4.56E-01 4.55E-01 7.57E-01 N (Ni-63 not positively detected)

Cs-134 -2.17E-01 4.41E-01 6.24E-01 N Sr-90/Cs-137 = N/A Cs-137 1.17E-01 6.66E-01 9.04E-01 N (Cs-137/Sr-90 not positively detected)

Eu-152 1.10E+02 4.36E+00 3.38E+00 Y Eu-154 2.89E+00 1.26E+00 2.18E+00 Y B1-02110F-IWC-016-CV H-3 1.06E+02 1.53E+01 2.05E+01 Y H-3/Cs-137 = N/A Co-60 3.95E+00 4.32E-01 2.63E-01 Y (Cs-137 not positively detected)

Ni-63 0.00E+00 5.57E+00 9.54E+00 N Ni-63/Co-60 = N/A Sr-90 5.59E-01 5.06E-01 8.35E-01 N (Ni-63 not positively detected)

Cs-134 1.04E-01 2.63E-01 5.06E-01 N Sr-90/Cs-137 = N/A Cs-137 4.06E-01 4.60E-01 6.95E-01 N (Cs-137/Sr-90 not positively detected)

Eu-152 8.22E+01 3.27E+00 2.28E+00 Y Eu-154 2.28E+00 8.68E-01 1.66E+00 Y

[51]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 13 (continued) - FSS Confirmation Concrete Core Sample Analysis - Grade to 0.5 Inch Depth Sample ID Nuclide Result Uncertainty MDC >MDC Ratios (pCi/g) (pCi/g) (pCi/g)

B1-02110IF-IWC-019-CV H-3 2.46E+02 2.14E+01 2.42E+01 Y H-3/Cs-137 = N/A Co-60 8.42E+00 7.26E-01 4.79E-01 Y (Cs-137 not positively detected)

Ni-63 3.69E+00 5.27E+00 8.88E+00 N Ni-63/Co-60 = N/A Sr-90 1.77E-01 4.90E-01 8.54E-01 N (Ni-63 not positively detected)

Cs-134 -4.16E-01 4.66E-01 6.38E-01 N Sr-90/Cs-137 = N/A Cs-137 6.83E-01 6.30E-01 1.03E+00 N (Cs-137/Sr-90 not positively detected)

Eu-152 1.45E+02 7.66E+00 2.57E+00 Y Eu-154 2.96E+00 1.17E+00 2.06E+00 Y B1-02110IF-IFC-005-CV H-3 9.30E+01 6.31E+00 7.25E+00 Y H-3/Cs-137 = 23.12 Co-60 7.40E+00 7.64E-01 4.07E-01 Y Ni-63 4.36E+00 4.49E+00 7.53E+00 N Ni-63/Co-60 = N/A Sr-90 8.51E-01 4.07E-01 6.10E-01 Y (Ni-63 not positively detected)

Cs-134 -1.50E-02 4.49E-01 8.63E-01 N Sr-90/Cs-137 = 0.21 Cs-137 4.02E+00 1.02E+00 1.17E+00 Y Eu-152 1.54E+02 8.50E+00 2.83E+00 Y Eu-154 5.56E+00 1.63E+00 3.10E+00 Y B1-02110IF-IFC-006-CV H-3 2.04E+02 1.21E+01 1.32E+01 Y H-3/Cs-137 = N/A Co-60 1.74E+01 1.30E+00 8.79E-01 Y (Cs-137 not positively detected)

Ni-63 4.94E+00 4.47E+00 7.47E+00 N Ni-63/Co-60 = N/A Sr-90 5.76E-01 4.50E-01 7.32E-01 N (Ni-63 not positively detected)

Cs-134 -3.18E-01 7.02E-01 1.00E+00 N Sr-90/Cs-137 = N/A Cs-137 -2.16E-02 8.65E-01 1.26E+00 N (Cs-137/Sr-90 not positively detected)

Eu-152 2.36E+02 8.46E+00 4.41E+00 Y Eu-154 8.68E+00 1.82E+00 3.37E+00 Y

[52]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 13 (continued) - FSS Confirmation Concrete Core Sample Analysis - Grade to 0.5 Inch Depth Sample ID Nuclide Result Uncertainty MDC >MDC Ratios (pCi/g) (pCi/g) (pCi/g)

B1-02110IF-IFC-008-CV H-3 2.64E+01 9.04E+00 1.43E+01 Y H-3/Cs-137 = N/A Co-60 2.32E+00 4.53E-01 3.77E-01 Y (Cs-137 not positively detected)

Ni-63 5.99E+00 4.59E+00 7.63E+00 N Ni-63/Co-60 = N/A Sr-90 8.11E-01 4.91E-01 7.80E-01 Y (Ni-63 not positively detected)

Cs-134 1.27E-01 2.15E-01 5.26E-01 N Sr-90/Cs-137 = N/A Cs-137 -6.01E-01 5.17E-01 6.30E-01 N (Cs-137/Sr-90 not positively detected)

Eu-152 4.80E+01 2.42E+00 2.48E+00 Y Eu-154 8.13E-01 8.90E-01 1.65E+00 N B1-02110IF-IWC-010-CV H-3 5.01E+01 9.74E+00 1.46E+01 Y H-3/Cs-137 = N/A Co-60 9.17E+00 9.70E-01 6.78E-01 Y (Cs-137 not positively detected)

Ni-63 4.94E+01 6.24E+00 8.89E+00 Y Ni-63/Co-60 = 5.39 Sr-90 3.23E-01 5.36E-01 9.20E-01 N Cs-134 1.04E-01 3.24E-01 9.28E-01 N Sr-90/Cs-137 = N/A Cs-137 8.54E-01 8.59E-01 1.43E+00 N (Cs-137/Sr-90 not positively detected)

Eu-152 1.64E+02 6.91E+00 3.96E+00 Y Eu-154 4.92E+00 1.64E+00 3.21E+00 Y B1-02110IF-IWC-011-CV H-3 3.16E+00 7.44E+00 1.27E+01 N H-3/Cs-137 = N/A Co-60 6.31E-02 1.96E-01 3.08E-01 N (Cs-137 not positively detected)

Ni-63 1.01E+01 5.12E+00 8.38E+00 Y Ni-63/Co-60 = N/A Sr-90 4.96E-01 6.11E-01 1.03E+00 N (Ni-63 not positively detected)

Cs-134 -4.12E-03 6.81E-02 2.79E-01 N Sr-90/Cs-137 = N/A Cs-137 -3.59E-02 1.56E-01 2.32E-01 N (Cs-137/Sr-90 not positively detected)

Eu-152 3.64E+00 4.34E-01 8.63E-01 Y Eu-154 -3.80E-02 2.11E-01 5.58E-01 N

[53]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 13 (continued) - FSS Confirmation Concrete Core Sample Analysis - Grade to 0.5 Inch Depth Sample ID Nuclide Result Uncertainty MDC >MDC Ratios (pCi/g) (pCi/g) (pCi/g)

B1-02110IF-IWC-018-CV H-3 1.65E+02 1.26E+01 1.52E+01 Y H-3/Cs-137 = N/A Co-60 1.34E+01 9.82E-01 1.02E+00 Y (Cs-137 not positively detected)

Ni-63 1.32E+01 5.71E+00 9.28E+00 Y Ni-63/Co-60 = 0.98 Sr-90 1.61E+00 6.17E-01 9.09E-01 Y Cs-134 -1.39E-02 3.37E-01 7.68E-01 N Sr-90/Cs-137 = N/A Cs-137 4.94E-02 6.40E-01 9.34E-01 N (Cs-137 not positively detected)

Eu-152 2.23E+02 7.75E+00 4.54E+00 Y Eu-154 7.20E+00 1.47E+00 2.62E+00 Y

[54]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 14 - FSS Confirmation Concrete Core Sample Analysis - Concentrations at Depth B1-02110IF-IWC-003-CV H-3 Co-60 Ni-63 Sr-90 Cs-134 Cs-137 Eu-152 Eu-154 Depth (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g)

Surface to 0.5 inch 1.13E+02 4.85E+00 2.83E+01 5.50E-01 -1.91E-02 3.74E+01 1.05E+02 3.88E+00 0.5 to 1 inch 1.48E+01 5.83E+00 1.48E+01 3.32E-01 6.40E-03 1.85E+01 1.20E+02 3.91E+00 1 to 1.5 inch 1.17E+01 5.44E+00 1.17E+01 7.35E-01 5.91E-02 2.27E+00 1.17E+02 4.81E+00 1.5 to 2 inch 1.21E+00 1.49E+01 1.21E+00 3.85E-01 8.86E-02 -7.21E-02 2.01E+01 4.18E-01 2 to 2.5 inch 2.10E-01 3.12E+00 2.10E-01 3.23E-01 -1.77E-01 9.10E-02 5.42E+01 2.49E+00 2.5 to 3 inch 2.46E+01 2.95E+00 2.46E+01 5.49E-01 7.12E-02 -2.66E-01 5.74E+01 1.68E+00 3 to 3.5 inch 2.20E+00 1.65E+00 2.20E+00 4.51E-01 -1.26E+00 -4.89E-01 3.95E+01 3.24E+00 3.5 to 4 inch 9.53E-01 4.30E+00 9.53E-01 4.98E-02 6.66E-03 -2.22E-02 1.35E+01 6.10E-01 4 to 4.5 inch 1.23E+00 1.24E+00 1.23E+00 1.57E-01 1.67E-02 2.07E-01 2.70E+01 -6.97E-03 4.5 to 5 inch 1.27E+00 1.49E+00 1.27E+00 4.25E-01 -4.74E-01 -9.51E-02 2.21E+01 2.33E+00 5 to 5.5 inch 7.04E-01 6.68E-01 7.04E-01 2.56E-01 3.90E-02 -3.46E-03 2.09E+01 5.88E-01 B1-02110F-IWC-014-CV H-3 Co-60 Ni-63 Sr-90 Cs-134 Cs-137 Eu-152 Eu-154 Depth (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g)

Surface to 0.5 inch 1.52E+02 8.07E+00 5.61E+00 3.55E-01 -2.36E-01 5.93E-01 1.29E+02 3.62E+00 0.5 to 1 inch 5.12E+01 4.64E+00 3.34E+00 3.11E-01 4.53E-02 1.72E-01 8.23E+01 2.67E+00 1 to 1.5 inch 4.16E+01 5.65E+00 -4.55E-01 1.60E+00 1.79E-01 4.41E-02 8.14E+01 2.64E+00 1.5 to 2 inch 2.10E+01 4.50E+00 -9.45E-01 9.81E-01 2.26E-01 -1.51E-01 1.27E+02 4.06E+00 2 to 2.5 inch 1.05E+01 3.83E+00 1.73E+00 2.55E-01 2.11E-02 -2.18E-01 5.28E+01 1.55E+00 2.5 to 3 inch 1.37E+01 1.70E+00 1.52E+00 1.57E-01 1.79E-01 2.31E-01 3.48E+01 1.75E-01 3 to 3.5 inch 1.65E+01 1.16E+00 -1.01E+00 4.42E-01 -5.31E-02 4.69E-02 2.57E+01 9.10E-01 3.5 to 4 inch 4.54E+01 1.61E+00 -1.37E+00 1.05E+00 -1.13E-03 5.18E-03 2.64E+01 5.25E-01 4 to 4.5 inch 3.10E+01 1.38E+00 -9.19E-01 3.79E-01 -2.55E-02 1.18E-01 2.36E+01 4.67E-01 4.5 to 5 inch 4.05E+01 1.04E+00 1.12E+00 -2.97E-02 2.20E-02 1.34E-02 2.02E+01 9.21E-01 5 to 5.5 inch 3.16E+01 1.17E+00 -2.09E+00 1.09E+00 -5.97E-01 3.04E-01 1.82E+01 4.27E-01 5.5 to 6 inch 2.91E+01 7.26E-01 -2.88E+00 6.88E-01 -8.13E-02 8.10E-02 1.76E+01 -1.64E-02

[55]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 14 (continued) - FSS Confirmation Concrete Core Sample Analysis - Concentrations at Depth B1-02110F-IWC-015-CV H-3 Co-60 Ni-63 Sr-90 Cs-134 Cs-137 Eu-152 Eu-154 Depth (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g)

Surface to 0.5 inch 1.22E+02 1.15E+01 6.91E+00 4.50E-01 -1.50E-01 1.11E+00 1.31E+02 6.82E+00 0.5 to 1 inch 5.36E+01 7.92E+00 0.00E+00 6.06E-01 1.25E-01 -1.11E-01 1.55E+02 8.19E+00 1 to 1.5 inch 1.15E+02 7.81E+00 4.61E-01 8.23E-01 -5.70E-02 8.07E-02 1.42E+02 3.75E+00 1.5 to 2 inch 1.30E+02 7.80E+00 -1.85E-01 4.89E-01 -1.79E-02 3.96E-01 1.49E+02 7.04E+00 2 to 2.5 inch 1.39E+02 6.32E+00 -5.44E-01 3.35E-01 -4.34E-01 -2.06E-01 1.29E+02 4.67E+00 2.5 to 3 inch 1.23E+02 9.62E+00 3.60E-01 7.49E-01 1.65E-01 -3.14E-01 1.09E+02 4.32E+00 3 to 3.5 inch 1.05E+02 5.37E+00 8.46E-01 6.09E-01 9.23E-02 3.08E-01 9.54E+01 2.72E+00 3.5 to 4 inch 9.97E+01 1.14E+01 1.84E+00 4.70E-01 1.19E-01 -4.06E-02 1.01E+02 5.14E+00 4 to 4.5 inch 7.70E+01 5.09E+00 1.18E+00 -4.41E-01 6.46E-02 1.67E-02 7.37E+01 2.52E+00 4.5 to 5 inch 7.76E+01 3.77E+00 2.54E+00 2.29E-01 1.44E-02 2.41E-01 6.60E+01 1.86E+00 5 to 5.5 inch 5.78E+01 5.49E+00 1.57E+00 4.52E-01 1.12E-01 2.84E-01 8.37E+01 2.50E+00 B1-02110F-IWC-016-CV H-3 Co-60 Ni-63 Sr-90 Cs-134 Cs-137 Eu-152 Eu-154 Depth (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g)

Surface to 0.5 inch 1.06E+02 3.95E+00 0.00E+00 5.59E-01 1.04E-01 4.06E-01 8.22E+01 2.28E+00 0.5 to 1 inch 1.72E+02 4.17E+00 2.25E+00 6.63E-01 -2.76E-01 -1.74E-01 7.08E+01 2.52E+00 1 to 1.5 inch 1.41E+02 2.49E+00 1.59E+00 4.15E-02 -2.01E-02 -1.02E-01 4.12E+01 1.77E+00 1.5 to 2 inch 1.14E+02 2.26E+00 1.41E+00 -7.12E-02 -8.33E-02 9.99E-02 4.49E+01 1.06E+00 2 to 2.5 inch 1.03E+02 2.23E+00 -2.95E-01 6.52E-01 -5.81E-02 6.67E-03 4.87E+01 1.30E+00 2.5 to 3 inch 8.10E+01 2.98E+00 1.65E-01 4.51E-01 -2.23E-01 -2.06E-01 3.64E+01 1.37E+00 3 to 3.5 inch 6.25E+01 1.42E+00 3.14E-01 3.24E-01 -6.03E-02 -5.34E-02 3.28E+01 7.25E-01 3.5 to 4 inch 6.10E+01 1.84E+00 1.09E+00 1.14E-01 -3.45E-02 4.33E-03 3.01E+01 9.56E-01 4 to 4.5 inch 5.06E+01 1.71E+00 9.50E-01 2.97E-01 -6.53E-02 4.78E-01 2.71E+01 6.05E-01 4.5 to 5 inch 4.05E+01 9.95E-01 1.66E-01 2.06E-01 4.17E-02 1.91E-01 1.77E+01 3.69E-01 5 to 5.5 inch 3.08E+01 1.08E+00 8.72E-02 2.21E-01 -5.68E-01 1.03E-01 1.51E+01 3.09E-01 5.5 to 6 inch 3.05E+01 6.01E-01 8.11E-02 9.41E-01 -4.50E-03 8.64E-02 9.46E+00 1.77E-01

[56]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 14 (continued) - FSS Confirmation Concrete Core Sample Analysis - Concentrations at Depth B1-02110F-IWC-017-CV H-3 Co-60 Ni-63 Sr-90 Cs-134 Cs-137 Eu-152 Eu-154 Depth (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g)

Surface to 0.5 inch 1.21E+02 7.60E+00 -8.12E-01 5.13E-01 7.41E-02 2.17E+00 1.58E+02 5.91E+00 0.5 to 1 inch 6.67E+01 5.74E+00 7.70E-01 4.94E-01 2.25E-02 -1.11E-01 1.13E+02 4.04E+00 1 to 1.5 inch 7.70E+01 6.41E+00 2.09E+00 6.79E-01 1.95E-02 -2.83E-01 1.17E+02 4.95E+00 1.5 to 2 inch 6.47E+01 7.35E+00 7.29E-02 4.96E-02 3.18E-01 3.46E-01 1.60E+02 6.98E+00 2 to 2.5 inch 5.89E+01 5.96E+00 5.95E-01 3.77E-01 -8.67E-02 1.56E-01 1.04E+02 3.93E+00 2.5 to 3 inch 5.13E+01 6.64E+00 -7.10E-02 6.17E-01 6.95E-01 -2.04E-01 1.09E+02 2.73E+00 3 to 3.5 inch 7.75E+01 5.90E+00 6.50E-01 3.17E-01 -1.09E-01 -2.28E-01 1.15E+02 3.93E+00 3.5 to 4 inch 8.58E+01 4.96E+00 1.25E+00 1.24E-01 -2.00E-01 4.84E-01 7.75E+01 3.33E+00 4 to 4.5 inch 8.39E+01 2.49E+00 -3.20E-01 2.63E-01 -3.00E-01 1.09E-01 5.75E+01 1.34E+00

[57]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 In accordance with the process described in LTP section 5.1, the HTD to surrogate ratio was derived for concrete cores with positive results for both the HTD ROC and the corresponding surrogate (Cs-137 or Co-60). The HTD ratios from the analysis of the 1st 1/2-inch of the nineteen (19) FSS confirmatory concrete cores are presented in Table 15.

Table 15 - FSS Confirmation Concrete Core Sample Analysis Surrogate Ratios Containment Ratios Mean Max 95%UCL H-3/Cs-137 47.10 109.63 96.54 Ni-63/Co-60 3.11 5.84 5.75 Sr-90/Cs-137 0.17 0.21 0.21 A review of the post-remediation concrete core data indicates that almost all of the ratios for H-3/Cs-137 exceeded 1.76 and all the positive results for Sr-90/Cs-137 exceeded 0.021, both representing the maximum ratios from LTP section 5.2.11, Table 5-15. A review of the pre-remediation results (Table 4) and the post remediation results (Table 13 and Table 14) clearly showed that the cause could be attributed to the fact that the majority of the less soluble source term activity for Cs-137 was contained with the near surface concrete that was remediated and removed (within a minimum of 6 inches) while the more soluble ROC (H-3 and Sr-90), while present in lesser concentrations than present in the pre-remediated concrete, had become the dominant radionuclide in the relationship with Cs-137. Due to the significant reduction in the concentrations of the gamma-emitting ROC (many at MDC), the H-3 and Sr-90 concentrations were not well correlated with Cs-137 and the use of a ratio with Cs-137 to infer a concentration for the HTD was no longer defensible.

LTP Chapter 5, section 5.1 states. Survey unit-specific surrogate ratios, in lieu of the maximum ratios from section 5.2.11 Table 5-15, may be used for compliance if sufficient radiological data exists to demonstrate that a different ratio is representative for the given survey unit. In these cases, the survey unit-specific radiological data and the derived surrogate ratios will be submitted to the Nuclear Regulatory Commission (NRC) for approval. If approved, then the survey unit-specific ratios used and the survey data serving as the basis for the surrogate ratios will be documented in the release record for the survey unit. Accordingly, ZSRP submitted a document to the NRC titled Request for Regulatory Approval for Area Specific Hard to Detect (HTD) Approach for the Zion Nuclear Station Unit 1 Containment Undervessel Area on April 10, 2018 While this document was specific to Unit 1 Containment, the situation and the proposed solution were applicable to both Unit 1 and Unit 2 Containments. In this document, ZSRP presented evidence that the use of surrogate ratios to infer concentrations of HTD ROC in the Under Vessel concrete was no longer defensible. ZSRP proposed an alternate approach to use the actual measured concentration of each HTD ROC to derive HTD

[58]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 concentrations for demonstrating compliance in the end-state concrete.

In the document, ZSRP stated that a sufficient number (19) of post-remediation concrete core samples were taken on the Under Vessel concrete to demonstrate compliance based on actual analysis results. As previously stated, of the nineteen (19) samples taken, nine (9) were taken directly at the center-point of the FOV of the ISOCS FSS measurement.

The other ten (10) were taken adjacent to continuing characterization concrete core locations that were selected based on elevated scan results (i.e. biased to areas exhibiting highest activity).

To ensure that the measured values were limiting, the following calculations were performed to assess the dose consequence of the inventory of each HTD in the Under Vessel concrete if present at the measured concentration. The measurements and dimensions presented in Table 16 (which were taken from ZionSolutions TSD 13-005, Unit 1 & 2 Reactor Building Estimated End State Concrete and Liner Volumes and Surfaces Areas [Reference 12]) were used to quantify the volume of concrete in the Unit 2 Containment Under Vessel area.

Table 16 - Unit 2 Containment Under Vessel Concrete Area, Volume and Dimensions Total Surface Total Length Width Thickness Volume Surface Section Area Number Volume Area (in) (in) (in) (ft2) (ft3) (ft2) (ft3)

Sloped Tunnel Floor 320 90 15 200 250 1 200 250 Sloped Tunnel Ceiling 168 90 15 105 131 1 105 131 Sloped Tunnel Walls 319.9 94 15 209 344 2 418 688 Tunnel Ceiling 196 90 15 123 153 1 123 153 Sump Area Floor 87 90 30 70 128 1 70 128 Sump Area Walls 87 123 15 74 127 2 149 254 Fan Shaped Floor 179.5 126 30 157 393 1 157 393 Fan Shaped Walls 157 123 15 134 229 2 268 458 Under Vessel Floor N/A 102.5 30 229 573 1 229 573 Under Vessel Walls 348 102.5 23.5 1443 3150 1 1443 3150 3161 ft2 6178 ft3 294 m2 175 m3 1.75E+08 cm3 For the assessment, the concrete thickness was reduced by 20% to account for the volume of concrete removed during remediation. The concentrations in units of pCi/g were multiplied by the affected mass of concrete in units of grams resulting in the actual inventory of each measured HTD ROC in units of mCi. The dose consequence was derived using the dose factors from LTP Chapter 6, Tables 6-19 and 6-20. The dose bounding calculations for each HTD ROC based on the measured concentrations of each HTD ROC from the 1st 1/2-inch puck from each of the nineteen (19) FSS confirmatory concrete core samples are presented in Table 17.

[59]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 17 - Unit 2 Containment Under Vessel Concrete HTD Inventory and Dose Based on FSS Confirmatory Core Samples Concrete Representative Concrete Concrete Result Activity Dose Sample ID Description of Location Nuclide Thickness Area Volume Mass (pCi/g) (cm) (cm2) (cm3) (g) (mCi) (mrem/yr)

B1-02110IF-IWC-001-CV Lower Under Vessel wall adj to tunnel H-3 8.33E+01 47.752 9.57E+04 4.57E+06 1.07E+07 0.8950 0.03 B1-02110IF-IWC-003-CV Lower Under Vessel wall adj to tunnel H-3 1.13E+02 47.752 9.57E+04 4.57E+06 1.07E+07 1.2109 0.04 B1-02110IF-IWC-004-CV Lower Under Vessel wall adj to tunnel H-3 1.20E+02 47.752 9.57E+04 4.57E+06 1.07E+07 1.2924 0.04 B1-02110F-IFC-003-CV Under Vessel Floor center-point H-3 1.69E+02 60.96 4.26E+04 2.60E+06 6.10E+06 1.0288 0.03 B1-02110F-IFC-021-CV Under Vessel Floor @ tunnel H-3 1.29E+02 60.96 4.26E+04 2.60E+06 6.10E+06 0.7843 0.02 B1-02110F-IWC-015-CV Under Vessel Floor north H-3 1.22E+02 47.752 9.57E+04 4.57E+06 1.07E+07 1.3061 0.04 B1-02110F-IWC-017-CV Upper Under Vessel east H-3 1.21E+02 47.752 9.57E+04 4.57E+06 1.07E+07 1.3035 0.04 B1-02110F-IWC-019-CV Lower Under Vessel wall adj to tunnel H-3 3.86E+02 47.752 9.57E+04 4.57E+06 1.07E+07 4.1494 0.13 B1-02110F-IWC-020-CV Mid Under Vessel wall east H-3 2.28E+02 47.752 9.57E+04 4.57E+06 1.07E+07 2.4446 0.07 B1-02110F-IWC-014-CV Mid Under Vessel wall west H-3 1.52E+02 47.752 9.57E+04 4.57E+06 1.07E+07 1.6327 0.05 B1-02110F-IWC-018-CV Upper Under Vessel west H-3 1.52E+02 47.752 9.57E+04 4.57E+06 1.07E+07 1.6280 0.05 B1-02110F-IWC-016-CV Upper Under Vessel east H-3 1.06E+02 47.752 9.57E+04 4.57E+06 1.07E+07 1.1378 0.03 B1-02110IF-IWC-019-CV Upper Under Vessel east H-3 2.46E+02 47.752 9.57E+04 4.57E+06 1.07E+07 2.6404 0.08 B1-02110IF-IFC-005-CV Under Vessel Floor west wall H-3 9.30E+01 60.96 4.26E+04 2.60E+06 6.10E+06 0.5672 0.02 B1-02110IF-IFC-006-CV Under Vessel Floor north wall H-3 2.04E+02 60.96 4.26E+04 2.60E+06 6.10E+06 1.2461 0.04 B1-02110IF-IFC-008-CV Under Vessel Floor east wall H-3 2.64E+01 60.96 4.26E+04 2.60E+06 6.10E+06 0.1609 0.00 B1-02110IF-IWC-010-CV Upper undervessel east H-3 5.01E+01 47.752 9.57E+04 4.57E+06 1.07E+07 0.5381 0.02 B1-02110IF-IWC-011-CV Mid undervessel wall adj to tunnel H-3 3.16E+00 47.752 9.57E+04 4.57E+06 1.07E+07 0.0339 0.00 B1-02110IF-IWC-018-CV Mid undervessel wall adj to tunnel H-3 1.65E+02 47.752 9.57E+04 4.57E+06 1.07E+07 1.7745 0.05 Avg. of Tunnel Adj Cores (1) Tunnel H-3 1.43E+02 47.752 1.39E+06 6.62E+07 1.56E+08 22.2313 0.67 Constants Total H-3 Activity Inventory in Under Vessel Concrete 48.01 mCi Concrete Density = 2.35 g/cm3 H-3 Dose Factor (2) = 3.02E-02 mrem/yr per mCi Total Dose from H-3 Inventory in Concrete 1.45 mrem/yr Conversion Factor = 1.00E-09 mCi/pCi Notes No concrete cores were taken in the Tunnel. Result for H-3 concentration in Tunnel is the average of the concrete cores taken closest to and adjacent to the Tunnel (1) opening. These cores included 001, 003, 004, 011, 018, 019 and 021 The Dose Factor for H-3 is the sum of the Dose Factor for Groundwater from LTP Chapter 6, Table 6-19 and the Dose Factor for Drilling Spoils from LTP Chapter 6, (2)

Table 6-20. The value was then adjusted by dividing by 0.9 to account for the Insignificant Contributor (IC) Dose Adjustment Factor

[60]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 17 (continued) - Unit 2 Containment Under Vessel Concrete HTD Inventory and Dose Based on FSS Confirmatory Core Samples Concrete Representative Concrete Concrete Result Activity Dose Sample ID Description of Location Nuclide Thickness Area Volume Mass (pCi/g) (cm) (cm2) (cm3) (g) (mCi) (mrem/yr)

B1-02110IF-IWC-001-CV Lower Under Vessel wall adj to tunnel Ni-63 3.36E+00 47.752 9.57E+04 4.57E+06 1.07E+07 0.0361 0.0001 B1-02110IF-IWC-003-CV Lower Under Vessel wall adj to tunnel Ni-63 2.83E+01 47.752 9.57E+04 4.57E+06 1.07E+07 0.3044 0.0005 B1-02110IF-IWC-004-CV Lower Under Vessel wall adj to tunnel Ni-63 1.62E+01 47.752 9.57E+04 4.57E+06 1.07E+07 0.1737 0.0003 B1-02110F-IFC-003-CV Under Vessel Floor center-point Ni-63 3.11E+00 60.96 4.26E+04 2.60E+06 6.10E+06 0.0190 0.0000 B1-02110F-IFC-021-CV Under Vessel Floor @ tunnel Ni-63 4.27E+00 60.96 4.26E+04 2.60E+06 6.10E+06 0.0261 0.0000 B1-02110F-IWC-015-CV Under Vessel Floor north Ni-63 6.91E+00 47.752 9.57E+04 4.57E+06 1.07E+07 0.0742 0.0001 B1-02110F-IWC-017-CV Upper Under Vessel east Ni-63 0.00E+00 47.752 9.57E+04 4.57E+06 1.07E+07 0.0000 0.0000 B1-02110F-IWC-019-CV Lower Under Vessel wall adj to tunnel Ni-63 9.28E+00 47.752 9.57E+04 4.57E+06 1.07E+07 0.0997 0.0002 B1-02110F-IWC-020-CV Mid Under Vessel wall east Ni-63 1.51E+01 47.752 9.57E+04 4.57E+06 1.07E+07 0.1625 0.0003 B1-02110F-IWC-014-CV Mid Under Vessel wall west Ni-63 5.61E+00 47.752 9.57E+04 4.57E+06 1.07E+07 0.0603 0.0001 B1-02110F-IWC-018-CV Upper Under Vessel west Ni-63 3.75E+00 47.752 9.57E+04 4.57E+06 1.07E+07 0.0403 0.0001 B1-02110F-IWC-016-CV Upper Under Vessel east Ni-63 0.00E+00 47.752 9.57E+04 4.57E+06 1.07E+07 0.0000 0.0000 B1-02110IF-IWC-019-CV Upper Under Vessel east Ni-63 3.69E+00 47.752 9.57E+04 4.57E+06 1.07E+07 0.0396 0.0001 B1-02110IF-IFC-005-CV Under Vessel Floor west wall Ni-63 4.36E+00 60.96 4.26E+04 2.60E+06 6.10E+06 0.0266 0.0000 B1-02110IF-IFC-006-CV Under Vessel Floor north wall Ni-63 4.94E+00 60.96 4.26E+04 2.60E+06 6.10E+06 0.0301 0.0001 B1-02110IF-IFC-008-CV Under Vessel Floor east wall Ni-63 5.99E+00 60.96 4.26E+04 2.60E+06 6.10E+06 0.0365 0.0001 B1-02110IF-IWC-010-CV Upper Under Vessel east Ni-63 4.94E+01 47.752 9.57E+04 4.57E+06 1.07E+07 0.5306 0.0009 B1-02110IF-IWC-011-CV Mid Under Vessel wall adj to tunnel Ni-63 1.01E+01 47.752 9.57E+04 4.57E+06 1.07E+07 0.1087 0.0002 B1-02110IF-IWC-018-CV Mid Under Vessel wall adj to tunnel Ni-63 1.32E+01 47.752 9.57E+04 4.57E+06 1.07E+07 0.1417 0.0003 Avg. of Tunnel Adj Cores (1) Tunnel Ni-63 1.21E+01 47.752 1.39E+06 6.62E+07 1.56E+08 1.8843 0.0034 Constants Total Ni-63 Activity Inventory in Under Vessel Concrete 3.7943 mCi Concrete Density = 2.35 g/cm3 Ni-63 Dose Factor (2) = 1.79E-03 mrem/yr per mCi Total Dose from Ni-63 Inventory in Concrete 0.0068 mrem/yr Conversion Factor = 1.00E-09 mCi/pCi Notes No concrete cores were taken in the Tunnel. Result for Ni-63 concentration in Tunnel is the average of the concrete cores taken closest to and adjacent to the Tunnel (1) opening. These cores included 001, 003, 004, 011, 018, 019 and 021 The Dose Factor for Ni-63 is the sum of the Dose Factor for Groundwater from LTP Chapter 6, Table 6-19 and the Dose Factor for Drilling Spoils from LTP Chapter 6, (2)

Table 6-20. The value was then adjusted by dividing by 0.9 to account for the Insignificant Contributor Dose Adjustment Factor

[61]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 17 (continued) - Unit 2 Containment Under Vessel Concrete HTD Inventory and Dose Based on FSS Confirmatory Core Samples Concrete Representative Concrete Concrete Result Activity Dose Sample ID Description of Location Nuclide Thickness Area Volume Mass (pCi/g) (cm) (cm2) (cm3) (g) (mCi) (mrem/yr)

B1-02110IF-IWC-001-CV Lower Under Vessel wall adj to tunnel Sr-90 4.72E-01 47.752 9.57E+04 4.57E+06 1.07E+07 0.0051 0.0254 B1-02110IF-IWC-003-CV Lower Under Vessel wall adj to tunnel Sr-90 5.50E-01 47.752 9.57E+04 4.57E+06 1.07E+07 0.0059 0.0296 B1-02110IF-IWC-004-CV Lower Under Vessel wall adj to tunnel Sr-90 6.88E-01 47.752 9.57E+04 4.57E+06 1.07E+07 0.0074 0.0370 B1-02110F-IFC-003-CV Under Vessel Floor center-point Sr-90 2.09E-01 60.96 4.26E+04 2.60E+06 6.10E+06 0.0013 0.0064 B1-02110F-IFC-021-CV Under Vessel Floor @ tunnel Sr-90 6.83E-01 60.96 4.26E+04 2.60E+06 6.10E+06 0.0042 0.0209 B1-02110F-IWC-015-CV Under Vessel Floor north Sr-90 4.50E-01 47.752 9.57E+04 4.57E+06 1.07E+07 0.0048 0.0242 B1-02110F-IWC-017-CV Upper Under Vessel east Sr-90 5.13E-01 47.752 9.57E+04 4.57E+06 1.07E+07 0.0055 0.0276 B1-02110F-IWC-019-CV Lower Under Vessel wall adj to tunnel Sr-90 9.00E-01 47.752 9.57E+04 4.57E+06 1.07E+07 0.0097 0.0484 B1-02110F-IWC-020-CV Mid Under Vessel wall east Sr-90 5.64E-01 47.752 9.57E+04 4.57E+06 1.07E+07 0.0061 0.0304 B1-02110F-IWC-014-CV Mid Under Vessel wall west Sr-90 3.55E-01 47.752 9.57E+04 4.57E+06 1.07E+07 0.0038 0.0191 B1-02110F-IWC-018-CV Upper Under Vessel west Sr-90 4.56E-01 47.752 9.57E+04 4.57E+06 1.07E+07 0.0049 0.0245 B1-02110F-IWC-016-CV Upper Under Vessel east Sr-90 5.59E-01 47.752 9.57E+04 4.57E+06 1.07E+07 0.0060 0.0301 B1-02110IF-IWC-019-CV Upper Under Vessel east Sr-90 1.77E-01 47.752 9.57E+04 4.57E+06 1.07E+07 0.0019 0.0095 B1-02110IF-IFC-005-CV Under Vessel Floor west wall Sr-90 8.51E-01 60.96 4.26E+04 2.60E+06 6.10E+06 0.0052 0.0260 B1-02110IF-IFC-006-CV Under Vessel Floor north wall Sr-90 5.76E-01 60.96 4.26E+04 2.60E+06 6.10E+06 0.0035 0.0176 B1-02110IF-IFC-008-CV Under Vessel Floor east wall Sr-90 8.11E-01 60.96 4.26E+04 2.60E+06 6.10E+06 0.0049 0.0248 B1-02110IF-IWC-010-CV Upper Under Vessel east Sr-90 3.23E-01 47.752 9.57E+04 4.57E+06 1.07E+07 0.0035 0.0174 B1-02110IF-IWC-011-CV Mid Under Vessel wall adj to tunnel Sr-90 4.96E-01 47.752 9.57E+04 4.57E+06 1.07E+07 0.0053 0.0267 B1-02110IF-IWC-018-CV Mid Under Vessel wall adj to tunnel Sr-90 1.61E+00 47.752 9.57E+04 4.57E+06 1.07E+07 0.0173 0.0866 Avg. of Tunnel Adj Cores (1) Tunnel Sr-90 7.71E-01 47.752 1.39E+06 6.62E+07 1.56E+08 0.1200 0.6015 Constants Total Sr-90 Activity Inventory in Under Vessel Concrete 0.2262 mCi Concrete Density = 2.35 g/cm3 Sr-90 Dose Factor (2) = 5.01E+00 mrem/yr per mCi Total Dose from Sr-90 Inventory in Concrete 1.1338 mrem/yr Conversion Factor = 1.00E-09 mCi/pCi Notes No concrete cores were taken in the Tunnel. Result for Sr-90 concentration in Tunnel is the average of the concrete cores taken closest to and adjacent to the Tunnel (1) opening. These cores included 001, 003, 004, 011, 018, 019 and 021 The Dose Factor for Sr-90 is the sum of the Dose Factor for Groundwater from LTP Chapter 6, Table 6-19 and the Dose Factor for Drilling Spoils from LTP Chapter 6, (2)

Table 6-20. The value was then adjusted by dividing by 0.9 to account for the Insignificant Contributor Dose Adjustment Factor

[62]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 13 presents the measured concentrations of each HTD ROC in units of pCi/g from grade to a depth of 1/2-inch for each of the nineteen (19) sample locations. In Table 14, five (5) of the 19 concrete core samples are further analyzed at depths greater than the 1st 1/2-inch. In the April 10th document, it was proposed to convert the measured concentrations of each HTD ROC from units of pCi/g to units of pCi/m2, assuming a depth of 1/2-inch (1.27 cm) and a concrete density of 2.35 g/cm3. The concentration for each HTD ROC could then be directly compared against its respective OpDCGL to derive an Operational Sum of Fractions (OpSOF) for each. Table 18 shows the results of converting positively identified measured concentrations of H-3, Ni-63 and Sr-90 from the concrete core samples to units of pCi/m2 and then converting to SOF.

Table 18 - Unit 2 Containment Under Vessel FSS Confirmatory Core Samples Measured HTD Concentrations and SOF H-3 H-3 Ni-63 Ni-63 Sr-90 Sr-90 Sample ID 2 2 2 (pCi/m ) OpSOF (pCi/m ) OpSOF (pCi/m ) OpSOF B1-02110IF-IWC-001-CV 2.49E+06 0.010 B1-02110IF-IWC-003-CV 3.37E+06 0.014 8.46E+05 0.000 B1-02110IF-IWC-004-CV 3.59E+06 0.015 4.83E+05 0.000 B1-02110F-IFC-003-CV 5.03E+06 0.021 B1-02110F-IFC-021-CV 3.84E+06 0.016 B1-02110F-IWC-015-CV 3.63E+06 0.015 B1-02110F-IWC-017-CV 3.62E+06 0.015 B1-02110F-IWC-019-CV 1.15E+07 0.049 2.69E+04 0.019 B1-02110F-IWC-020-CV 6.79E+06 0.029 4.52E+05 0.000 B1-02110F-IWC-014-CV 4.54E+06 0.019 B1-02110F-IWC-018-CV 4.52E+06 0.019 B1-02110F-IWC-016-CV 3.16E+06 0.013 B1-02110IF-IWC-019-CV 7.34E+06 0.031 B1-02110IF-IFC-005-CV 2.77E+06 0.012 2.54E+04 0.018 B1-02110IF-IFC-006-CV 6.10E+06 0.026 B1-02110IF-IFC-008-CV 7.87E+05 0.003 2.42E+04 0.017 B1-02110IF-IWC-010-CV 1.50E+06 0.006 1.47E+06 0.000 B1-02110IF-IWC-011-CV 3.02E+05 0.000 B1-02110IF-IWC-018-CV 4.93E+06 0.021 3.94E+05 0.000 4.80E+04 0.034 Samples = 18 Samples = 6 Samples = 4 Mean = 0.019 Mean = 0.019 Mean = 0.022 Max = 0.049 Max = 0.049 Max = 0.034 Min = 0.003 Min = 0.003 Min = 0.017 SD = 0.010 SD = 0.010 SD = 0.008 95%URL = 0.034 95%URL = 0.034 95%URL = 0.032 Max Operational SOF (OpSOF) from HTDs= 0.083 95%UCL OpSOF from HTDs= 0.066

[63]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 To demonstrate compliance with the unrestricted release criteria in FSS unit 02100 and FSS unit 02110, the Sign Test was selected as the non-parametric statistical test. The use of the Sign Test did not require the selection or use of a background reference area, which simplified survey design and implementation.

It was proposed to sum the maximum SOF for each HTD ROC to derive a SOF that represented the worst-case dose consequence from the presence of HTD ROC. While the depth of contamination for the HTD ROC is greater than 1/2 inch, use of the maximum concentration compensated for the additional source term at depth. ZSRP also conservatively proposed using the maximum SOF as opposed to the mean or 95%UCL SOF to account for any additional, unspecified variability.

The summation of the maximum SOF resulted in a value of 0.083 which equates to a dose of 2.071 mrem/yr. This value corresponds closely with the calculated dose from total inventory of 2.591 mrem/yr from Table 17 (1.45 mrem/yr from H-3 plus 0.007 mrem/yr from Ni-63 plus 1.114 mrem/yr from Sr-90). It was then proposed to add this worst-case SOF to each of the measured OpSOF for the gamma emitting ROC. The combined OpSOF (including the addition of the maximum SOF for HTD) for each measurement would then be used as the sum value for the Sign Test. Passing the Sign Test with the combined OpSOF would then demonstrate that the mean activity for each ROC was less than the OpDCGLB at a Type 1 decision error of 0.05. The mean measured concentration for each HTD ROC would then be compared to their respective Base Case DCGLs to calculate dose in mrem/yr.

The Elevated Measurement Comparison (EMC) did not apply to this survey unit. At ZSRP, EMC only applies to soils as all other media (structural surfaces, embedded pipe, buried pipe and penetrations) will be remediated to their applicable BcDCGL.

A Prospective Power Curve was generated using MARSSIM 2000, a software package developed for implementation of MARSSIM. The result showed adequate power for the survey design.

For this Class 1 basement structure survey unit, the Investigation Levels for ISOCS measurement results are those levels specified in LTP Chapter 5, Table 5-25 and are reproduced below in Table 19.

Table 19 - Investigation Levels Classification Direct Measurement Class 1 >Operational DCGL Table 20 provides a synopsis of the survey designs for FSS unit 02100 and FSS unit 02110.

[64]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 20 - Synopsis of Survey Design FEATURE DESIGN CRITERIA BASIS Under Vessel 294 m2 Survey Unit Surface Areas LTP Ch. 5, Table 5-19 Above 565 foot 2,465 m2 Under Vessel 19(1)

Number of ISOCS Measurements LTP Ch. 5, Table 5-19 Above 565 foot 155(1)

• UBGR = SOF of 1

• LBGR = SOF of 0.01

• Type I error = 0.05

• Type II error = 0.05 LTP Chapter 5, Sec.

Survey Design

• / = 3 (adjusted) (above 5.5.2.2 565 foot)

• / = 2 (Under Vessel)

• MARSSIM Table 5.5 100% Areal Coverage LTP Chapter 5, Sec.

Grid Spacing (Planned for 28 m2 FOV) 5.5.2.2 LTP Chapter 5, Tables DCGLs See Tables 3 and 4 above 5-3 and 5-4 LTP Chapter 5, Table Investigation Level >Operational DCGL 5-25 5 % Replicate ISOCS LTP Chapter 5, Sec.

Quality Control (QC)

Measurements 5.9.3.1 (1) The number of ISOCS measurements designated in the survey designs is greater than the minimum number required for these survey units per Chapter 5 of the LTP, Table 5-19. Fifty four (54) measurements were required to achieve 100% coverage of the Under Vessel. One hundred and sixty four (164) measurements were required for 100% coverage of the 565 foot

6. SURVEY IMPLEMENTATION For FSS unit 02100 and FSS unit 02110, compliance with the unrestricted release criteria was demonstrated through a combination of direct measurements using the ISOCS and the analysis of concrete core samples obtained from the Under Vessel area.

Field Logs (ZS-LT-300-001-001 Attachment 14) were used to document field activities and other information pertaining to the performance of the FSS. Daily briefings were conducted to discuss the expectations for job performance and to review safety aspects of the job.

ZionSolutions TSD 14-022 provided the initial justification for the selection of reasonably conservative geometries for efficiency calibrations for the ISOCS based on the physical conditions of the remediated surface and the anticipated depth and distribution of activity.

All ISOCS measurements were acquired using approved geometries. Various stand-off distances were utilized due to space constraints in the Incore Tunnel area. Graphics

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 containing the details of those geometries are attached to this Release Record. The number and locations of the ISOCS shots were adjusted to ensure 100% coverage of the surfaces of the steel liner above the 565 foot elevation, the Under Vessel and Incore Tunnel area.

Between 2014 and 2017, decommissioning activities involved the removal of all radioactive systems and components from the interior of the Unit 2 Containment, including major components such as the Reactor Vessel, the Steam Generators, the Pressurizer, the Reactor Coolant Pumps as well as all contaminated primary and secondary pipe. In 2017, all contaminated concrete was removed from the interior of the Containment above the 565 foot elevation, leaving only the exposed 1/2-inch steel liner and several penetrations.

Initial remediation of the Under Vessel concrete was performed between November 27, 2017 and December 21, 2017. Remediation techniques included the scabbling and hammering of the concrete surface using hydraulic hoe-rams. Concrete debris was then removed through load-out of waste skids. Approximately 2 to 4 inches of concrete was removed from the walls and floor directly below where the Reactor Vessel was located and approximately 1 to 2 inches of concrete was removed from the walls and floor of the sloped tunnel.

Both the interior above the 565 foot elevation and the Under Vessel area of Unit 2 Containment were initially turned over to the Characterization/License Termination (C/LT) Group on December 22, 2017 anticipating that the remediation performed was sufficient to meet the unrestricted release criteria.

On January 12, 2018, the C/LT group attempted to perform FSS. FSS failed due to several ISOCS measurements exceeding a SOF of one. The area was rejected and turned back over for additional remediation on January 13, 2018.

Between January 13, 2018 and January 28, 2018, an additional 4 inches of concrete was removed from the floor of the Under Vessel area and from the floor of the sloped tunnel.

On January 29, 2018, C/LT took turnover of the Unit 2 Containment Under Vessel area for the second time. Additional ISOCS measurements indicated contaminated concrete around the Incore sump that exceeded the OpDCGL for Cs-137. Again, the area was rejected and turned back over for additional remediation on February 2, 2018.

On February 3, 2018, the decommissioning contractor re-commenced remediation of Under Vessel concrete. Emphasis was placed on removing concrete around sump and concrete at the seams of the floor and lower wall where scans indicate elevated gamma activity.

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Figure 10 - Unit 2 Under Vessel Incore Tunnel Remediation On February 12, 2018, C/LT took turnover of the Unit 2 Containment Under Vessel area for the third time. ISOCS measurements continued to indicate contaminated concrete around the Incore sump and along the seams in the floor that exceeded the OpDCGL for Cs-137. Again, the area was rejected and turned back over for additional remediation on February 15, 2018.

On February 15, 2018, remediation re-commenced of the Under Vessel concrete. Project management provided direction to remove another 6 to 12 inches of concrete from the floor and walls and to remove all concrete down to the liner in the sloped tunnel area at the locations that failed FSS.

Remediation was completed on April 5, 2018. The area was cleaned and turned over to the C/LT group for FSS. A walkdown and turnover survey was satisfactorily performed in

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 both FSS units in accordance with the Isolation and Control requirements of procedure ZS-LT-300-001-003, Isolation and Control for Final Status Survey (Reference 13). The turnover surveys consisted of surveys for loose surface contamination as well as the acquisition of several ISOCS measurements in areas that had previously failed FSS. All smear results were less than 1,000 dpm/100 cm2 and all ISOCS measurements indicated a SOF of less than one for all ROC. The Unit 2 Containment was deemed acceptable for turnover and FSS commenced in the Under Vessel area on April 6, 2018.

The ISOCS detector was positioned horizontal or vertical to the surface at the center-point of each selected measurement location. In most cases, the exposed face of the detector was positioned at a distance of 3 meters from the surface with the 90- degree collimation shield installed; this orientation corresponded to a nominal FOV of 28 m2. The detector to source distance was reduced even further to accommodate physical constraints or encountered obstructions. In this case, the FOV was reduced and the number of measurements increased to ensure 100% areal coverage was achieved.

The measured activity for each gamma-emitting ROC (and any other gamma-emitting radionuclide that was positively detected by ISOCS) was recorded (in units of pCi/m2).

Background was not subtracted from any measurement. A OpSOF calculation was performed for each measurement by dividing the reported concentration of each ROC by the OpDCGL for each ROC to derive an individual ROC fraction. The individual ROC fractions were then summed to provide a total OpSOF value for the measurement.

Nine (9) replicate measurements were taken with the ISOCS above the 565 foot elevation and three (3) replicate measurements were taken with the ISOCS in the Under Vessel area.

Above the 565 foot elevation, the locations selected for taking replicate measurements were at locations 045, 050, 060, 100, 115, 119, 139, 150 and 165. In the Under Vessel area, the locations selected for taking replicate measurements were at locations 016, 017 and 051. These locations were randomly selected using the Microsoft Excel RANDBETWEEN function. The number of replicate measurements satisfies the requirement that a minimum of 5% percent of the number of measurements that will be used for non-parametric statistical testing be selected for additional QC evaluation.

7. SURVEY RESULTS The SOF or unity rule is applied to the data used for the survey planning, data evaluation and statistical tests for basement surfaces since multiple radionuclide-specific measurements were performed and the concentrations inferred based on known relationships. The application of the unity rule served to normalize the data to allow for an accurate comparison of the various data measurements to the release criteria. When the unity rule is applied, the DCGLw (used for the nonparametric statistical test) becomes

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 one (1). The BcDCGLB are directly analogous to the DCGLW as defined in MARSSIM.

The use and application of the unity rule was performed in accordance with section 4.3.3 of MARSSIM.

As described in LTP Chapter 5, section 5.10.3.2, the Sign Test was used to evaluate the measured residual radioactivity against the dose criterion. The SOF for each measurement was used as the sum value for the Sign Test. The Sign Test then demonstrated that the mean activity for each ROC was less than the OpDCGLB at a Type I decision error of 0.05.

For building surfaces, areas of elevated activity were defined as any area identified by measurement/sample (systematic or judgmental) that exceeded the OpDCGL but was less than the BcDCGL. Any area that exceeded the BcDCGL would have required remediation. The OpSOF for a systematic or a judgmental measurement/sample(s) can exceed one without remediation as long as the survey unit passes the Sign Test and, the mean OpSOF for the survey unit does not exceed one. Once the survey data set passes the Sign Test (using OpDCGLs), then the mean radionuclide activity (pCi/m2) for each ROC from systematic measurements along with any identified elevated areas from systematic and judgmental measurements can be used with the BcDCGLs to perform a mean (Base Case Sum of Fractions Basement) BcSOFB calculation. The dose from residual radioactivity assigned to the FSS unit is the mean BcSOFB multiplied by 25 mrem/yr.

Unit 2 Containment above the 565 foot Elevation Direct measurement locations were denoted on the steel liner above the 565 foot elevation by marking an approximate 4 meter by 4 meter grid pattern using a random start point that was overlaid over the exposed surface, providing sufficient overlap between locations to ensure 100% areal coverage. See Figures 12 and 13 for a depiction of all measurement locations.

The systematic sample population consisted of one hundred and sixty four (164) direct measurements that were acquired using the ISOCS. A summary of the results of the 164 ISOCS measurements taken for non-parametric statistical testing results is provided in Table 21. The concentrations for H-3, Ni-63 and Sr-90 were inferred based on the maximum ratios as specified in LTP Chapter 5, Table 5-15. The complete ISOCS gamma spectroscopy reports are presented in Attachment 6. The basic statistics for the systematic measurements are summarized in Table 22.

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Figure 11 - ISOCS Measurements of Unit 2 Containment Above 565 foot Elevation

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Figure 12 - Unit 2 Containment Above 565 foot Elevation FSS Floor Measurement Locations

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Figure 13 - Unit 2 Containment Above 565 foot Elevation FSS Wall Measurement Locations

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 21- Unit 2 Containment Above 565 foot Elevation - Measured Concentrations of ROC for FSS H-3(2) Co-60(1) Ni-63(2) Sr-90(2) Cs-134 Cs-137(1) Eu-152 Eu-154 Measurement ID OpSOF (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)

B1-02100DF-SWM-001-GD 6.35E+04 3.65E+04 1.62E+07 7.58E+02 2.17E+03 3.61E+04 0.00E+00 2.76E+04 0.045 B1-02100DF-SWM-002-GD 3.51E+04 7.75E+04 3.43E+07 4.19E+02 0.00E+00 2.00E+04 5.73E+04 2.75E+04 0.075 B1-02100DF-SWM-003-GD 4.68E+04 3.86E+04 1.71E+07 5.58E+02 7.99E+03 2.66E+04 2.40E+04 8.61E+03 0.045 B1-02100DF-SWM-004-GD 6.54E+04 4.66E+04 2.06E+07 7.81E+02 0.00E+00 3.72E+04 1.89E+04 7.79E+02 0.053 B1-02100DF-SWM-005-GD 1.29E+05 2.92E+04 1.29E+07 1.53E+03 2.64E+04 7.31E+04 3.37E+04 1.89E+04 0.058 B1-02100DF-SWM-006-GD 7.33E+04 2.72E+04 1.20E+07 8.75E+02 7.25E+03 4.17E+04 4.61E+03 8.65E+03 0.040 B1-02100DF-SWM-007-GD 3.54E+04 2.44E+04 1.08E+07 4.23E+02 0.00E+00 2.01E+04 4.47E+04 3.09E+04 0.029 B1-02100DF-SWM-008-GD 6.58E+04 3.22E+04 1.42E+07 7.85E+02 5.15E+03 3.74E+04 2.67E+04 0.00E+00 0.042 B1-02100DF-SWM-009-GD 5.83E+04 2.78E+04 1.23E+07 6.96E+02 0.00E+00 3.32E+04 2.11E+04 2.57E+04 0.036 B1-02100DF-SWM-010-GD 3.92E+04 2.89E+04 1.28E+07 4.67E+02 1.89E+04 2.23E+04 2.30E+04 0.00E+00 0.037 B1-02100DF-SWM-011-GD 9.02E+04 2.46E+04 1.09E+07 1.08E+03 4.88E+03 5.12E+04 8.28E+04 9.68E+03 0.042 B1-02100DF-SWM-012-GD 1.11E+05 2.84E+04 1.25E+07 1.33E+03 2.19E+04 6.33E+04 2.40E+04 8.04E+02 0.052 B1-02100DF-SWM-013-GD 1.04E+05 3.99E+04 1.76E+07 1.24E+03 3.20E+03 5.89E+04 2.13E+04 7.15E+03 0.056 B1-02100DF-SWM-014-GD 6.34E+04 2.88E+04 1.27E+07 7.57E+02 1.02E+04 3.60E+04 6.68E+03 1.45E+04 0.040 B1-02100DF-SWM-015-GD 1.04E+05 6.39E+04 2.83E+07 1.24E+03 9.43E+03 5.90E+04 2.32E+03 2.77E+04 0.078 B1-02100DF-SWM-016-GD 1.22E+05 4.02E+04 1.78E+07 1.45E+03 0.00E+00 6.93E+04 5.58E+04 3.56E+03 0.059 B1-02100DF-SWM-017-GD 1.83E+05 4.30E+04 1.90E+07 2.18E+03 2.62E+03 1.04E+05 5.73E+04 9.19E+03 0.075 B1-02100DF-SWM-018-GD 3.63E+05 9.22E+04 4.08E+07 4.34E+03 2.36E+03 2.07E+05 2.45E+03 1.42E+04 0.151 B1-02100DF-SWM-019-GD 6.62E+05 2.36E+05 1.04E+08 7.90E+03 0.00E+00 3.76E+05 5.00E+04 4.64E+03 0.332 B1-02100DF-SWM-020-GD 3.44E+05 3.21E+04 1.42E+07 4.11E+03 1.46E+04 1.96E+05 1.49E+04 0.00E+00 0.099 B1-02100DF-SWM-021-GD 3.40E+05 3.62E+04 1.60E+07 4.05E+03 1.08E+04 1.93E+05 8.38E+03 0.00E+00 0.100 B1-02100AF-SWM-022-GD 8.78E+04 1.76E+04 7.80E+06 1.05E+03 4.42E+03 4.99E+04 3.81E+04 1.23E+04 0.034 B1-02100DF-SWM-023-GD 8.64E+04 1.49E+03 6.59E+05 1.03E+03 0.00E+00 4.91E+04 1.34E+04 1.49E+04 0.019 B1-02100DF-SWM-024-GD 2.08E+05 2.00E+04 8.84E+06 2.49E+03 0.00E+00 1.18E+05 6.55E+04 3.90E+04 0.060 B1-02100DF-SWM-025-GD 1.83E+05 2.74E+04 1.21E+07 2.18E+03 2.11E+04 1.04E+05 4.25E+04 2.39E+04 0.066 B1-02100DF-SWM-026-GD 1.84E+05 3.38E+04 1.50E+07 2.20E+03 4.99E+03 1.05E+05 2.31E+04 3.67E+04 0.068 B1-02100DF-SWM-027-GD 7.87E+04 2.62E+04 1.16E+07 9.39E+02 8.00E+03 4.47E+04 0.00E+00 2.07E+04 0.040 B1-01200DF-SWM-028-GD 9.18E+04 3.29E+04 1.46E+07 1.10E+03 3.24E+04 5.22E+04 2.33E+04 1.20E+04 0.055 B1-02100DF-SWM-029-GD 1.84E+05 3.97E+04 1.75E+07 2.20E+03 7.21E+03 1.05E+05 1.99E+04 9.37E+03 0.072 B1-02100DF-SWM-030-GD 1.58E+05 3.83E+04 1.69E+07 1.88E+03 0.00E+00 8.95E+04 4.98E+04 0.00E+00 0.065 B1-02100DF-SWM-031-GD 6.57E+04 3.02E+04 1.33E+07 7.84E+02 8.59E+03 3.73E+04 3.87E+04 8.38E+03 0.042 B1-02100DF-SWM-032-GD 1.57E+05 3.00E+04 1.32E+07 1.88E+03 7.46E+03 8.94E+04 1.51E+04 6.12E+04 0.060

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 21 (continued) - Unit 2 Containment Above 565 foot Elevation - Measured Concentrations of ROC for FSS H-3(2) Co-60(1) Ni-63(2) Sr-90(2) Cs-134 Cs-137(1) Eu-152 Eu-154 Measurement ID OpSOF (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)

B1-02100DF-SWM-033-GD 1.23E+05 3.51E+04 1.55E+07 1.46E+03 1.46E+03 6.97E+04 3.76E+04 4.67E+03 0.055 B1-02100DF-SWM-034-GD 7.59E+04 2.55E+04 1.13E+07 9.05E+02 0.00E+00 4.31E+04 2.99E+04 6.30E+03 0.037 B1-02100DF-SWM-035-GD 3.55E+04 2.86E+04 1.26E+07 4.24E+02 1.87E+04 2.02E+04 7.19E+04 0.00E+00 0.037 B1-02100DF-SWM-036-GD 1.53E+05 4.32E+04 1.91E+07 1.82E+03 9.30E+03 8.68E+04 0.00E+00 1.54E+04 0.069 B1-02100DF-SWM-037-GD 8.33E+04 2.97E+04 1.31E+07 9.93E+02 7.65E+03 4.73E+04 1.81E+04 1.29E+04 0.044 B1-02100DF-SWM-038-GD 3.28E+04 2.29E+04 1.01E+07 3.92E+02 1.48E+04 1.86E+04 5.73E+04 1.85E+04 0.031 B1-02100DF-SWM-039-GD 5.44E+04 3.94E+04 1.74E+07 6.49E+02 0.00E+00 3.09E+04 0.00E+00 4.02E+04 0.045 B1-02100DF-SWM-040-GD 9.18E+04 4.51E+04 2.00E+07 1.10E+03 7.51E+03 5.22E+04 4.97E+04 1.72E+04 0.060 B1-02100DF-SWM-041-GD 9.63E+04 7.02E+04 3.10E+07 1.15E+03 1.00E+04 5.47E+04 1.76E+04 3.69E+04 0.082 B1-02100DF-SWM-042-GD 1.16E+05 4.13E+04 1.83E+07 1.39E+03 0.00E+00 6.62E+04 2.52E+04 0.00E+00 0.059 B1-02100DF-SWM-043-GD 8.80E+04 3.47E+04 1.54E+07 1.05E+03 1.59E+04 5.00E+04 5.13E+04 2.30E+04 0.052 B1-02100DF-SWM-044-GD 5.57E+04 3.45E+04 1.52E+07 6.64E+02 8.04E+03 3.16E+04 5.90E+04 1.74E+04 0.044 B1-02100DF-SWM-045-GD 2.95E+04 2.23E+04 9.84E+06 3.52E+02 8.02E+03 1.67E+04 5.43E+03 2.18E+04 0.027 B1-02100DF-SWM-046-GD 6.60E+04 2.33E+04 1.03E+07 7.87E+02 2.06E+04 3.75E+04 4.83E+04 2.47E+04 0.039 B1-02100DF-SWM-047-GD 4.88E+04 2.55E+04 1.13E+07 5.82E+02 0.00E+00 2.77E+04 8.28E+04 6.33E+04 0.034 B1-02100DF-SWM-048-GD 3.51E+04 3.75E+04 1.66E+07 4.19E+02 2.98E+03 1.99E+04 2.20E+04 2.07E+04 0.040 B1-02100DF-SWM-049-GD 5.51E+04 3.09E+04 1.36E+07 6.57E+02 1.22E+03 3.13E+04 4.01E+04 1.45E+04 0.039 B1-02100DF-SWM-050-GD 3.48E+04 1.54E+04 6.80E+06 4.15E+02 1.67E+04 1.97E+04 0.00E+00 8.38E+02 0.024 B1-02100DF-SWM-051-GD 5.39E+04 5.51E+04 2.44E+07 6.43E+02 4.45E+03 3.06E+04 1.86E+04 0.00E+00 0.059 B1-02100DF-SWM-052-GD 5.39E+04 3.33E+04 1.47E+07 6.43E+02 9.03E+03 3.06E+04 1.63E+04 8.37E+03 0.042 B1-02100DF-SWM-053-GD 3.13E+04 3.31E+04 1.46E+07 3.73E+02 0.00E+00 1.78E+04 2.02E+04 1.16E+04 0.035 B1-02100DF-SWM-054-GD 4.43E+04 3.14E+04 1.39E+07 5.28E+02 3.08E+03 2.52E+04 1.33E+04 1.89E+04 0.037 B1-02100DF-SWM-055-GD 6.77E+04 3.62E+04 1.60E+07 8.08E+02 2.03E+04 3.85E+04 6.77E+03 1.20E+04 0.049 B1-02100DF-SWM-056-GD 5.17E+04 4.32E+04 1.91E+07 6.17E+02 0.00E+00 2.94E+04 4.09E+04 4.30E+04 0.049 B1-02100DF-SWM-057-GD 8.06E+04 4.05E+04 1.79E+07 9.62E+02 8.83E+03 4.58E+04 1.09E+04 2.23E+04 0.053 B1-02100DF-SWM-058-GD 5.26E+04 3.48E+04 1.54E+07 6.28E+02 0.00E+00 2.99E+04 1.40E+04 0.00E+00 0.040 B1-02100DF-SWM-059-GD 6.57E+04 3.94E+04 1.74E+07 7.84E+02 7.94E+02 3.74E+04 1.86E+04 1.59E+04 0.047 B1-02100DF-SWM-060-GD 7.05E+04 4.32E+04 1.91E+07 8.41E+02 3.67E+02 4.01E+04 1.37E+04 6.71E+03 0.051 B1-02100DF-SWM-061-GD 5.60E+04 5.57E+04 2.46E+07 6.68E+02 0.00E+00 3.18E+04 1.68E+03 2.53E+04 0.059 B1-02100DF-SWM-062-GD 6.30E+04 3.66E+04 1.62E+07 7.51E+02 0.00E+00 3.58E+04 1.68E+04 7.63E+03 0.044 B1-02100DF-SWM-063-GD 4.34E+04 5.57E+04 2.46E+07 5.18E+02 4.77E+03 2.47E+04 8.52E+04 8.33E+03 0.059

[74]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 21 (continued) - Unit 2 Containment Above 565 foot Elevation - Measured Concentrations of ROC for FSS H-3(2) Co-60(1) Ni-63(2) Sr-90(2) Cs-134 Cs-137(1) Eu-152 Eu-154 Measurement ID OpSOF (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)

B1-02100DF-SWM-064-GD 7.74E+04 1.02E+05 4.50E+07 9.24E+02 1.54E+04 4.40E+04 2.09E+03 1.01E+04 0.106 B1-02100DF-SWM-065-GD 2.26E+04 7.67E+04 3.39E+07 2.69E+02 0.00E+00 1.28E+04 4.49E+04 7.21E+03 0.071 B1-02100DF-SWM-066-GD 4.22E+04 2.90E+04 1.28E+07 5.03E+02 4.40E+03 2.40E+04 2.68E+04 8.63E+03 0.035 B1-02100DF-SWM-067-GD 4.43E+04 5.57E+04 2.46E+07 5.28E+02 2.40E+03 2.52E+04 4.45E+04 1.37E+03 0.058 B1-02100DF-SWM-068-GD 3.06E+04 8.89E+04 3.93E+07 3.65E+02 2.91E+02 1.74E+04 2.01E+04 8.65E+03 0.082 B1-02100DF-SFM-076-GD 1.15E+05 3.87E+04 1.71E+07 1.37E+03 0.00E+00 6.51E+04 1.17E+04 0.00E+00 0.056 B1-02100DF-SFM-077-GD 5.55E+04 4.00E+04 1.77E+07 6.62E+02 9.77E+03 3.15E+04 3.47E+04 2.05E+04 0.049 B1-02100DF-SFM-078-GD 5.71E+04 2.48E+04 1.10E+07 6.81E+02 0.00E+00 3.24E+04 1.57E+04 1.22E+04 0.033 B1-02100DF-SFM-079-GD 4.54E+04 1.77E+04 7.84E+06 5.42E+02 1.89E+03 2.58E+04 1.36E+04 5.98E+03 0.025 B1-02100DF-SFM-080-GD 6.97E+04 4.48E+04 1.98E+07 8.32E+02 5.13E+03 3.96E+04 5.95E+04 2.75E+04 0.055 B1-02110AF-SWM-083-GD 1.36E+05 2.72E+04 1.20E+07 1.62E+03 8.49E+03 7.71E+04 3.71E+04 1.62E+04 0.053 B1-02100DF-SFM-084-GD 3.27E+04 2.29E+04 1.01E+07 3.90E+02 0.00E+00 1.86E+04 6.38E+04 4.10E+03 0.027 B1-02100AF-SFM-085-GD 7.80E+04 1.81E+04 7.98E+06 9.31E+02 3.04E+03 4.43E+04 5.73E+04 1.65E+04 0.033 B1-02100DF-SFM-086-GD 2.23E+05 2.17E+04 9.59E+06 2.66E+03 5.20E+03 1.27E+05 8.58E+03 1.23E+04 0.064 B1-02100DF-SFM-087-GD 4.36E+04 2.64E+04 1.17E+07 5.20E+02 7.14E+03 2.48E+04 3.09E+04 1.15E+04 0.034 B1-02100DF-SFM-088-GD 4.83E+04 2.02E+04 8.91E+06 5.76E+02 1.45E+04 2.74E+04 2.79E+04 0.00E+00 0.031 B1-02100DF-SFM-089-GD 6.68E+04 2.85E+04 1.26E+07 7.97E+02 1.06E+04 3.79E+04 1.72E+04 4.52E+04 0.041 B1-02100DF-SFM-090-GD 1.28E+05 3.22E+04 1.42E+07 1.52E+03 2.59E+03 7.25E+04 1.69E+04 2.30E+04 0.054 B1-02100DF-SFM-092-GD 9.06E+04 3.19E+04 1.41E+07 1.08E+03 5.13E+03 5.15E+04 4.46E+04 4.90E+04 0.048 B1-02100DF-SFM-093-GD 5.01E+04 2.55E+04 1.13E+07 5.97E+02 3.39E+03 2.84E+04 1.86E+04 6.65E+04 0.034 B1-02100DF-SFM-094-GD 8.41E+04 1.99E+04 8.81E+06 1.00E+03 5.18E+03 4.78E+04 6.82E+04 2.36E+04 0.037 B1-02100DF-SFM-095-GD 6.80E+04 2.12E+04 9.37E+06 8.11E+02 5.41E+03 3.86E+04 1.12E+05 4.44E+04 0.036 B1-02100DF-SFM-096-GD 1.50E+05 2.29E+04 1.01E+07 1.79E+03 2.12E+04 8.54E+04 1.85E+04 0.00E+00 0.055 B1-02100DF-SFM-097-GD 5.41E+04 1.97E+04 8.69E+06 6.46E+02 9.77E+03 3.07E+04 1.05E+05 1.73E+03 0.032 B1-02100DF-SFM-098-GD 3.82E+04 1.90E+04 8.42E+06 4.56E+02 1.41E+04 2.17E+04 5.33E+04 6.19E+03 0.028 B1-02100DF-SFM-099-GD 4.19E+04 1.85E+04 8.17E+06 5.00E+02 0.00E+00 2.38E+04 1.15E+05 1.78E+04 0.027 B1-02100DF-SFM-100-GD 6.41E+04 3.68E+04 1.63E+07 7.65E+02 1.71E+04 3.64E+04 2.77E+04 1.46E+04 0.049 B1-02100DF-SFM-102-GD 3.77E+04 2.74E+04 1.21E+07 4.50E+02 1.14E+04 2.14E+04 3.45E+04 1.75E+04 0.035 B1-02100DF-SFM-103-GD 4.56E+04 1.76E+04 7.79E+06 5.45E+02 5.54E+03 2.59E+04 3.59E+04 1.27E+04 0.026 B1-02100DF-SFM-104-GD 1.84E+05 1.00E+04 4.43E+06 2.19E+03 1.27E+04 1.04E+05 8.45E+03 1.30E+04 0.048 B1-02100DF-SFM-105-GD 6.34E+04 2.27E+04 1.00E+07 7.56E+02 1.69E+04 3.60E+04 2.22E+04 3.14E+04 0.037 B1-02100DF-SFM-106-GD 4.29E+04 3.28E+04 1.45E+07 5.12E+02 2.75E+04 2.44E+04 1.67E+04 1.98E+04 0.044

[75]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 21 (continued) - Unit 2 Containment Above 565 foot Elevation - Measured Concentrations of ROC for FSS H-3(2) Co-60(1) Ni-63(2) Sr-90(2) Cs-134 Cs-137(1) Eu-152 Eu-154 Measurement ID OpSOF (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)

B1-02100DF-SFM-107-GD 6.72E+04 2.68E+04 1.18E+07 8.02E+02 0.00E+00 3.82E+04 9.25E+04 0.00E+00 0.038 B1-02100DF-SFM-108-GD 7.95E+04 3.25E+04 1.44E+07 9.49E+02 0.00E+00 4.52E+04 2.27E+04 1.92E+04 0.044 B1-02100DF-SFM-109-GD 8.42E+04 2.13E+04 9.43E+06 1.01E+03 1.07E+04 4.79E+04 3.25E+04 5.44E+03 0.038 B1-02100DF-SFM-110-GD 6.23E+04 2.52E+04 1.11E+07 7.43E+02 1.82E+04 3.54E+04 2.03E+04 5.09E+04 0.040 B1-02100DF-SFM-111-GD 1.68E+05 4.78E+04 2.11E+07 2.01E+03 4.68E+03 9.56E+04 4.13E+03 7.88E+03 0.075 B1-02100DF-SFM-112-GD 1.47E+05 5.55E+04 2.46E+07 1.76E+03 8.36E+04 8.36E+04 6.26E+04 4.44E+04 0.099 B1-02100DF-SFM-113-GD 4.25E+04 2.17E+04 9.57E+06 5.07E+02 9.99E+03 2.41E+04 4.76E+03 1.88E+04 0.030 B1-02100DF-SFM-114-GD 6.95E+04 2.76E+04 1.22E+07 8.30E+02 1.04E+04 3.95E+04 5.94E+04 8.41E+03 0.041 B1-02100DF-SFM-115-GD 7.23E+04 3.29E+04 1.45E+07 8.63E+02 4.88E+03 4.11E+04 9.35E+03 3.29E+03 0.044 B1-02100DF-SFM-116-GD 2.18E+05 1.19E+05 5.28E+07 2.61E+03 8.96E+03 1.24E+05 6.60E+05 3.62E+05 0.168 B1-02100DF-SFM-117-GD 6.21E+05 4.88E+05 2.16E+08 7.41E+03 7.44E+04 3.53E+05 2.67E+06 1.89E+05 0.613 B1-02100DF-SFM-118-GD 4.02E+04 2.74E+04 1.21E+07 4.80E+02 1.28E+04 2.29E+04 4.04E+04 1.32E+04 0.035 B1-02100DF-SFM-119-GD 4.96E+04 2.76E+04 1.22E+07 5.91E+02 7.75E+03 2.82E+04 8.60E+04 2.87E+04 0.038 B1-02100DF-SFM-120-GD 3.15E+04 2.73E+04 1.21E+07 3.76E+02 1.64E+04 1.79E+04 2.92E+04 4.78E+04 0.035 B1-02100DF-SFM-121-GD 7.32E+04 2.46E+04 1.09E+07 8.74E+02 1.80E+04 4.16E+04 5.52E+04 3.30E+04 0.042 B1-02100DF-SFM-122-GD 6.81E+04 2.68E+04 1.19E+07 8.12E+02 0.00E+00 3.87E+04 2.33E+04 1.44E+04 0.037 B1-02100DF-SFM-123-GD 4.59E+04 1.76E+04 7.78E+06 5.47E+02 1.70E+03 2.61E+04 9.04E+03 3.07E+04 0.025 B1-02100DF-SFM-124-GD 3.43E+04 1.76E+04 7.78E+06 4.10E+02 0.00E+00 1.95E+04 1.61E+04 2.80E+04 0.023 B1-02100DF-SFM-125-GD 4.25E+04 2.98E+04 1.32E+07 5.07E+02 0.00E+00 2.41E+04 5.06E+04 4.01E+04 0.036 B1-02100DF-SFM-126-GD 9.33E+05 8.23E+05 3.64E+08 1.11E+04 1.49E+04 5.30E+05 4.70E+06 1.82E+05 0.985 B1-02100DF-SFM-128-GD 3.44E+05 2.23E+05 9.85E+07 4.10E+03 1.63E+04 1.95E+05 1.29E+06 4.79E+04 0.288 B1-02100DF-SFM-129-GD 7.75E+04 2.40E+04 1.06E+07 9.25E+02 2.26E+03 4.40E+04 1.04E+04 1.05E+04 0.037 B1-02100DF-SFM-130-GD 5.27E+04 2.66E+04 1.18E+07 6.29E+02 1.09E+04 3.00E+04 9.23E+04 1.06E+04 0.038 B1-02100DF-SFM-131-GD 5.20E+04 1.35E+004 5.97E+06 6.21E+02 2.38E+03 2.96E+04 1.78E+04 6.86E+03 0.023 B1-02100DF-SFM-132-GD 2.67E+05 3.99E+4 1.76E+07 3.18E+03 1.85E+04 1.52E+05 7.10E+02 1.99E+04 0.091 B1-02100DF-SFM-133-GD 4.77E+05 3.68E+04 1.62E+07 5.69E+03 9.44E+03 2.71E+05 1.62E+04 2.24E+04 0.128 B1-02100DF-SFM-134-GD 2.68E+04 1.57E+04 6.92E+06 3.19E+02 2.66E+03 1.52E+04 1.58E+04 5.14E+04 0.021 B1-02100DF-SFM-135-GD 7.18E+04 3.63E+04 1.60E+07 8.56E+02 1.01E+03 4.08E+04 1.01E+04 1.31E+04 0.046 B1-02100DF-SFM-136-GD 5.30E+04 2.45E+04 1.08E+07 6.33E+02 1.31E+04 3.01E+04 4.52E+04 2.37E+04 0.036 B1-02100DF-SFM-137-GD 6.88E+04 3.28E+04 1.45E+07 8.21E+02 1.16E+04 3.91E+04 8.45E+04 5.75E+04 0.047 B1-02100DF-SFM-138-GD 3.66E+05 1.12E+05 4.94E+07 4.37E+03 7.73E+03 2.08E+05 5.93E+05 3.58E+05 0.189 B1-02100DF-SFM-139-GD 1.62E+05 8.10E+04 3.58E+07 1.93E+03 1.11E+04 9.20E+04 3.78E+05 2.06E+05 0.116

[76]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 21 (continued) - Unit 2 Containment Above 565 foot Elevation - Measured Concentrations of ROC for FSS H-3(2) Co-60(1) Ni-63(2) Sr-90(2) Cs-134 Cs-137(1) Eu-152 Eu-154 Measurement ID OpSOF (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)

B1-02100DF-SFM-140-GD 5.32E+04 2.08E+04 9.18E+06 6.34E+02 5.19E+03 3.02E+04 3.16E+04 2.37E+04 0.031 B1-02100DF-SFM-141-GD 3.99E+04 1.61E+04 7.12E+06 4.76E+02 1.89E+04 2.27E+04 9.55E+04 1.86E+04 0.028 B1-02100DF-SFM-142-GD 3.76E+04 1.03E+04 4.57E+06 4.49E+02 4.56E+03 2.14E+04 1.05E+04 0.00E+00 0.018 B1-02100DF-SFM-143-GD 4.24E+04 2.88E+04 1.27E+07 5.06E+02 2.07E+04 2.41E+04 4.55E+04 2.32E+04 0.039 B1-02100DF-SFM-144-GD 5.05E+04 2.16E+04 9.53E+06 6.03E+02 1.18E+04 2.87E+04 2.10E+04 7.79E+03 0.032 B1-02100DF-SFM-145-GD 4.95E+04 1.16E+04 5.13E+06 5.90E+02 1.34E+04 2.81E+04 1.19E+03 1.12E+04 0.023 B1-02100DF-SFM-146-GD 4.24E+04 2.35E+04 1.04E+07 5.05E+02 1.01E+04 2.41E+04 5.72E+04 4.02E+04 0.033 B1-02100DF-SFM-147-GD 6.62E+04 2.14E+04 9.46E+06 7.90E+02 7.10E+03 3.76E+04 2.79E+04 1.74E+04 0.034 B1-02100DF-SFM-148-GD 1.03E+05 2.16E+04 9.53E+06 1.23E+03 0.00E+00 5.87E+04 7.69E+04 2.06E+04 0.041 B1-02100DF-SFM-149-GD 7.56E+04 1.53E+04 6.78E+06 9.02E+02 5.08E+03 4.29E+04 2.37E+04 1.71E+04 0.030 B1-02100DF-SFM-150-GD 8.21E+04 2.21E+04 9.78E+06 9.80E+02 1.02E+04 4.67E+04 6.36E+04 3.32E+04 0.040 B1-02100DF-SFM-151-GD 5.41E+04 1.61E+04 7.09E+06 6.45E+02 1.20E+04 3.07E+04 3.58E+04 2.73E+04 0.029 B1-02100DF-SFM-152-GD 1.49E+05 1.97E+04 8.70E+06 1.78E+03 2.40E+03 8.46E+04 0.00E+00 2.28E+03 0.047 B1-02100DF-SFM-153-GD 3.40E+05 3.45E+04 1.52E+07 4.06E+03 0.00E+00 1.93E+05 5.29E+04 2.36E+04 0.098 B1-02100DF-SFM-154-GD 9.79E+04 3.42E+04 1.51E+07 1.17E+03 0.00E+00 5.56E+04 0.00E+00 1.72E+04 0.049 B1-02100DF-SFM-155-GD 5.18E+04 1.92E+04 8.48E+06 6.18E+02 1.32E+04 2.94E+04 6.69E+04 2.08E+04 0.032 B1-02100DF-SFM-156-GD 5.87E+04 2.49E+04 1.10E+07 7.01E+02 2.63E+03 3.34E+04 8.32E+03 1.70E+03 0.034 B1-02100DF-SFM-157-GD 8.92E+04 2.28E+04 1.01E+07 1.06E+03 3.27E+03 5.07E+04 2.40E+03 0.00E+00 0.038 B1-02100DF-SFM-158-GD 3.18E+04 1.71E+04 7.55E+06 3.79E+02 4.05E+03 1.81E+04 3.22E+03 1.80E+04 0.022 B1-02100DF-SFM-159-GD 5.26E+04 3.00E+04 1.33E+07 6.27E+02 1.38E+04 2.99E+04 1.57E+04 1.77E+04 0.040 B1-02100DF-SFM-160-GD 3.73E+04 1.95E+04 8.62E+06 4.45E+02 3.44E+03 2.12E+04 1.64E+04 7.03E+03 0.025 B1-02100DF-SFM-161-GD 5.21E+04 2.58E+04 1.14E+07 6.22E+02 2.03E+04 2.96E+04 3.79E+04 3.43E+04 0.039 B1-02100DF-SFM-162-GD 8.56E+04 2.71E+04 1.20E+07 1.02E+03 5.42E+03 4.86E+04 3.74E+02 1.41E+04 0.042 B1-02100DF-SFM-163-GD 9.05E+04 2.91E+04 1.28E+07 1.08E+03 1.60E+04 5.14E+04 7.56E+04 4.37E+03 0.048 B1-02100DF-SFM-164-GD 4.82E+04 1.69E+04 7.45E+06 5.75E+02 0.00E+00 2.74E+04 0.00E+00 1.18E+03 0.024 B1-02100DF-SFM-165-GD 4.49E+04 1.57E+04 6.93E+06 5.36E+02 1.97E+04 2.55E+04 7.99E+03 6.75E+03 0.027 B1-02100DF-SFM-166-GD 6.80E+04 2.38E+04 1.05E+07 8.12E+02 0.00E+00 3.87E+04 3.47E+04 1.94E+04 0.035 B1-02100DF-SFM-167-GD 7.48E+04 2.39E+04 1.06E+07 8.92E+02 0.00E+00 4.25E+04 4.80E+03 2.33E+04 0.036 B1-02100DF-SFM-168-GD 1.40E+05 4.42E+04 1.95E+07 1.66E+03 0.00E+00 7.93E+04 3.29E+04 1.58E+04 0.066 B1-02100DF-SFM-169-GD 7.65E+04 5.80E+04 2.56E+07 9.13E+02 3.02E+03 4.35E+04 1.92E+05 1.94E+04 0.069 B1-02100DF-SFM-170-GD 1.34E+05 3.21E+04 1.42E+07 1.60E+03 5.12E+03 7.62E+04 3.10E+04 2.08E+03 0.056

[77]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 21 (continued) - Unit 2 Containment Above 565 foot Elevation - Measured Concentrations of ROC for FSS H-3(2) Co-60(1) Ni-63(2) Sr-90(2) Cs-134 Cs-137(1) Eu-152 Eu-154 Measurement ID OpSOF (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)

B1-02100DF-SFM-171-GD 1.72E+05 4.30E+04 1.90E+07 2.05E+03 1.79E+03 9.75E+04 3.10E+04 3.51E+04 0.072 B1-02100DF-SFM-172-GD 1.48E+05 3.40E+04 1.50E+07 1.77E+03 2.23E+04 8.42E+04 4.21E+04 2.11E+04 0.065 B1-02100DF-SFM-173-GD 8.50E+04 5.04E+04 2.23E+07 1.01E+03 5.53E+03 4.83E+04 2.33E+04 3.03E+04 0.062 B1-02100DF-SFM-174-GD 2.80E+05 1.62E+05 7.15E+07 3.34E+03 9.69E+02 1.59E+05 6.66E+04 1.19E+04 0.195 B1-02100DF-SFM-175-GD 2.15E+05 4.09E+04 1.81E+07 2.56E+03 2.67E+03 1.22E+05 5.63E+04 6.54E+04 0.080 B1-02100DF-SFM-176-GD 3.25E+05 1.86E+05 8.21E+07 3.88E+03 1.72E+04 1.85E+05 7.54E+05 4.79E+05 0.252 (1) The surrogate OpDCGL for Cs-137 (inferring both H-3 and Sr-90 at the maximum ratios from LTP Table 5-15) is 2.88E+06 pCi/m2 (Equation 2) and the surrogate OpDCGL for Co-60 (inferring Ni-63 at the maximum ratio from LTP Table 5-15) is 1.18E+06 pCi/m2 (Equation 3). No ISOCS measurement result for Cs-137 or Co-60 exceeded its respective surrogate OpDCGL value.

(2) The concentrations for H-3, Ni-63 and Sr-90 were inferred based on the maximum ratios as specified in LTP Chapter 5, Table 5-15

[78]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 22 - Unit 2 Containment Above 565 foot Elevation - Statistical Quantities - Systematic Measurement Population Individual Measurement Metrics Total Number of Systematic Measurements = 164 Number of Quality Control Measurements = 9 Number of Judgmental/Investigational Measurements = 0 Total Number of Measurements = 173 Mean Systematic Measurement OpSOF = 0.063 Max Individual Systematic Measurement OpSOF = 0.985 Number of Systematic Measurements with OpSOF >1 = 0 Statistical Quantities - Systematic Measurement Population MEAN MEDIAN MAX MIN ST. DEV. BcDCGL Avg Dose per Avg BcSOF ROC ROC (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) per ROC (mrem/yr)

H-3 1.07E+05 6.80E+04 9.33E+05 2.26E+04 1.18E+05 2.38E+08 0.000 0.011 Co-60 4.49E+04 2.92E+04 8.23E+05 1.49E+03 7.74E+04 1.57E+08 0.000 0.007 Ni-63 1.99E+07 1.29E+07 3.64E+08 6.59E+05 3.42E+07 4.02E+09 0.005 0.123 Sr-90 1.28E+03 8.11E+02 1.11E+04 2.69E+02 1.41E+03 1.43E+06 0.001 0.022 Cs-134 8.34E+03 5.30E+03 8.36E+04 0.00E+00 1.06E+04 3.01E+07 0.000 0.007 Cs-137 6.08E+04 3.86E+04 5.30E+05 1.28E+04 6.71E+04 3.94E+07 0.002 0.039 Eu-152 9.91E+04 2.68E+04 4.70E+06 0.00E+00 4.36E+05 3.66E+08 0.000 0.007 Eu-154 2.82E+04 1.64E+04 4.79E+05 0.00E+00 5.84E+04 3.19E+08 0.000 0.002 BASE CASE SOF (BcSOF) ASSIGNED TO SURVEY UNIT (SYSTEMATIC AVG.) = 0.009 DOSE ASSIGNED TO SURVEY UNIT (SYSTEMATIC AVG.) = 0.219 mrem/yr.

[79]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 The analytical results of all measurements taken above the 565 foot elevation were less than a SOF of one.

Unit 2 Containment Under Vessel Area Direct measurement locations were denoted on the remaining concrete and/or on the exposed steel liner in the Unit 2 Containment Under Vessel area by marking an approximate 4 meter by 4 meter grid pattern using a random start point that was overlaid over the exposed surface, providing sufficient overlap between locations to ensure 100%

areal coverage. See Figure 15 for a depiction of all measurement locations.

The systematic sample population consisted of fifty-four (54) direct measurements that were acquired using the ISOCS. A summary of the results of the 54 ISOCS measurements taken for non-parametric statistical testing results is provided in Table 23.

Concentrations of HTD ROC were not inferred. However, The surrogate OpDCGL for Cs-137 (inferring both H-3 and Sr-90 at the maximum ratios from LTP Table 5-15) equaled 2.10E+07 pCi/m2 (Equation 4) and the surrogate OpDCGL for Co-60 (inferring Ni-63 at the maximum ratio from LTP Table 5-15) equaled 8.55E+06 pCi/m2 (Equation 5). No ISOCS measurement result for Cs-137 or Co-60 exceeded its respective surrogate OpDCGL value.

As stated in the April 10, 2018 letter to the NRC, ZSRP presented evidence that the use of surrogate ratios to infer concentrations of HTD ROC in the Under Vessel concrete was no longer defensible. Demonstrating compliance based on dose consequence from the actual measured concentrations for HTD ROC was a more reasonable approach as the spatial distribution of the concrete cores is representative and due to the extensive remediation and removal of source term, particularly Cs-137, the ratios used to infer H-3 and Sr-90 using the Cs-137 as a surrogate were no longer consistent or reasonably correlated. ZSRP proposed an area-specific alternate approach to use the actual measured concentration of each HTD ROC to derive HTD concentrations for demonstrating compliance in the end-state concrete. This is allowed under LTP Chapter 5, section 5.2.11 which states, the area specific ratios as determined by actual survey data will be used in lieu of the maximum ratios presented in Table 5-15. The area-specific ratios used and the survey data serving as the basis for the ratios will be documented in the release record for the survey unit.

The maximum SOF derived for each measured HTD ROC was summed to provide a SOF that represented the worst-case dose consequence from the presence of HTD ROC at the measured concentrations in the concrete core samples. Use of the maximum concentration compensated for the additional source term at depth and accounted for any additional, unspecified variability. The summation of the maximum SOF resulted in a value of 0.083.

This value was then added to each of the measured OpSOF for the gamma-emitting ROC.

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 The combined OpSOF (including the addition of the maximum SOF for HTD) for each measurement was then used as the sum value for the Sign Test. The mean measured concentration for each ROC was then compared to their respective BcDCGLs to calculate dose in mrem/yr.

The complete ISOCS gamma spectroscopy reports are presented in Attachment 6. A summary of the results of the 54 ISOCS measurements taken for non-parametric statistical testing results is provided in Table 23. The basic statistics for the systematic measurements are summarized in Table 24.

On May 21, 2018, the NRC commenced a confirmatory survey of the Unit 2 Containment basement FSS unit through Oak Ridge Institute for Science and Education (ORISE). The confirmatory survey consisted of several ISOCS measurements and additional concrete core samples. Upon review of the results, the NRC had questions pertaining to measured activity for H-3 in certain concrete core samples extrapolated over a 6-inch depth verses a 1/2-inch depth and the potential to exceed the BcDCGL in that scenario. For Unit 2, the concrete core of concern was Zion location 03.

To address the NRCs concerns, ZSRP agreed to remove a minimum of 1 to 4 inches of additional concrete from around the location of this core. For Unit 2 Containment, the area was designated as ISOCS location 15 (inclusive of the 1 ORISE sample). See Figure 16 for a depiction of the ORISE concrete core sample locations.

ZSRP commenced removal of the additional concrete commencing on 07/02/18. Due to the location of where the concrete was physically located, it was more effective to remove all the concrete exposing the steel liner in and around the upper circular wall.

Consequently, the concrete was completely removed down to the steel liner in ISOCS location #s 014, 018 and 020. In area #15, only 1/2-inch to 2-inches of concrete remained.

During the execution of this evolution, ZSRP controlled the spread of concrete dust, wiped down adjacent areas after concrete removal and performed an extensive post-work contamination survey. All survey results indicted no detectable loose surface contamination.

[81]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Figure 14 - Unit 2 Under Vessel Concrete H-3 Concrete Remediation Area Following the completion of this evolution, it was agreed to acquire and analyze two concrete core samples from each of the ISOCS zones that were remediated. As no concrete remained in location #s 014, 018 and 020, no concrete core samples were acquired in these locations. In location #15, two concrete core samples were acquired on 07/17/18 under NRC observation. The results are presented in Table 25. Upon completion of the sampling, the NRC provided concurrence to backfill the Unit 2 Containment.

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Figure 15 - Unit 2 Containment Under Vessel FSS Measurement Locations

[83]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 23 - Unit 2 Containment Under Vessel Area - Measured Concentrations of ROC for FSS Co-60(2) Cs-134 Cs-137(2) Eu-152 Eu-154 Measurement ID OpSOF(1)

(pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)

B1-02110DF-SFC-001-GD 1.03E+05 3.03E+04 4.18E+06 2.03E+05 1.77E+05 0.192 B1-02110DF-SFC-002-GD 3.16E+05 5.47E+04 2.26E+06 1.34E+06 1.23E+06 0.152 B1-02110DF-SFC-003-GD 4.60E+06 1.67E+05 1.11E+07 1.90E+07 7.82E+05 0.457 B1-02110DF-SCC-004-GD 6.90E+05 6.93E+04 1.68E+05 3.68E+06 2.18E+05 0.105 B1-02110DF-SWC-005-GD 1.00E+06 6.23E+04 2.03E+05 4.39E+06 2.55E+05 0.109 B1-02110DF-SWC-006-GD 6.14E+05 6.80E+04 2.30E+05 3.39E+06 2.13E+05 0.105 B1-02110DF-SWC-007-GD 5.28E+05 0.00E+00 2.61E+05 2.10E+06 9.56E+04 0.099 B1-02110DF-SWC-008-GD 3.29E+05 2.09E+04 6.79E+05 1.66E+06 1.05E+05 0.108 B1-02110DF-SWC-009-GD 1.67E+06 1.92E+05 1.91E+06 8.75E+06 4.08E+05 0.174 B1-02110DF-SWC-010-GD 1.66E+06 1.20E+04 2.33E+06 9.32E+06 5.27E+05 0.181 B1-02110DF-SWC-011-GD 4.74E+05 1.25E+05 8.27E+05 2.12E+06 1.30E+06 0.121 B1-02110DF-SWC-012-GD 2.45E+05 2.70E+04 2.17E+06 8.30E+05 6.03E+05 0.145 B1-02110DF-SFC-013-GD 2.58E+04 0.00E+00 2.15E+06 5.39E+03 3.08E+04 0.138 B1-02110DF-SWC-014-GD 3.47E+06 0.00E+00 1.71E+06 2.97E+07 1.17E+06 0.234 B1-02110DF-SWC-015-GD 3.32E+06 5.06E+04 8.28E+06 2.10E+07 1.09E+06 0.378 B1-02110DF-SWC-016-GD 2.88E+06 1.40E+05 8.43E+05 2.50E+07 9.92E+05 0.199 B1-02110DF-SWC-017-GD 4.37E+06 2.97E+04 4.14E+06 2.33E+07 1.23E+06 0.285 B1-02110DF-SWC-018-GD 4.48E+06 5.70E+04 2.71E+06 3.71E+07 1.39E+06 0.289 B1-02110DF-SWC-019-GD 3.40E+06 3.60E+04 4.48E+06 2.13E+07 1.06E+06 0.282 B1-02110DF-SWC-020-GD 4.00E+06 8.72E+04 4.29E+06 3.30E+07 1.48E+06 0.316 B1-02110DF-SFC-021-GD 1.24E+06 9.50E+03 2.59E+06 6.83E+06 4.18E+05 0.177 B1-02110DF-SFC-022-GD 2.09E+05 2.46E+04 5.29E+06 6.24E+05 4.48E+05 0.223 B1-02110DF-SCC-023-GD 3.60E+05 2.74E+04 2.35E+05 1.84E+06 6.28E+04 0.097 B1-02110DF-SCC-024-GD 1.08E+06 1.11E+04 2.24E+05 6.71E+06 2.91E+05 0.115

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 23 (continued) - Unit 2 Containment Under Vessel Area - Measured Concentrations of ROC for FSS Co-60(2) Cs-134 Cs-137(2) Eu-152 Eu-154 Measurement ID 2 2 2 2 OpSOF(1)

(pCi/m ) (pCi/m ) (pCi/m ) (pCi/m ) (pCi/m2)

B1-02110DF-SWC-025-GD 2.22E+04 8.79E+03 7.09E+04 5.25E+04 1.21E+04 0.085 B1-02110DF-SWM-026-GD 2.07E+04 2.44E+04 2.04E+05 0.00E+00 2.16E+04 0.089 B1-02110DF-SWM-027-GD 1.39E+04 1.66E+04 1.48E+05 4.05E+04 2.76E+04 0.087 B1-02110DF-SWM-028-GD 9.48E+03 3.25E+04 9.30E+04 5.23E+04 0.00E+00 0.087 B1-02110DF-SWM-029-GD 2.86E+04 1.07E+04 2.04E+05 9.16E+04 2.27E+04 0.089 B1-02110DF-SWM-030-GD 4.96E+04 6.37E+03 1.07E+06 1.35E+05 1.21E+04 0.111 B1-02110DF-SWM-031-GD 2.15E+04 0.00E+00 9.28E+04 1.81E+04 2.00E+04 0.085 B1-02110DF-SWM-032-GD 6.27E+03 1.80E+03 5.34E+05 3.53E+04 5.19E+04 0.097 B1-02110DF-SWM-033-GD 1.68E+04 7.88E+03 6.35E+05 3.07E+04 0.00E+00 0.100 B1-02110DF-SWM-034-GD 2.68E+04 7.29E+03 4.20E+05 4.76E+04 2.73E+04 0.094 B1-02110DF-SWM-035-GD 4.54E+04 0.00E+00 1.11E+06 1.64E+02 6.74E+03 0.111 B1-02110DF-SWM-036-GD 6.45E+04 4.74E+03 3.60E+06 1.82E+05 7.10E+03 0.176 B1-02110DF-SFM-037-GD 1.89E+04 1.99E+03 3.40E+04 2.93E+04 3.52E+03 0.084 B1-02110DF-SFM-038-GD 1.02E+04 1.27E+04 2.00E+04 1.68E+04 6.28E+03 0.084 B1-02110DF-SFM-039-GD 1.82E+03 6.90E+03 2.63E+04 4.56E+04 1.53E+04 0.084 B1-021100DF-SFM-040-GD 8.35E+03 6.21E+03 2.25E+04 0.00E+00 1.26E+04 0.084 B1-02110DF-SFM-041-GD 2.11E+04 1.18E+04 3.14E+04 0.00E+00 2.75E+04 0.084 B1-02110DF-SFM-042-GD 1.42E+04 8.59E+03 9.25E+04 5.70E+03 2.37E+04 0.086 B1-02110DF-SCC-043-GD 8.73E+04 1.29E+04 4.12E+06 0.00E+00 1.40E+05 0.189 B1-02110DF-SCC-044-GD 1.03E+05 4.25E+03 4.52E+06 1.20E+05 1.53E+05 0.200 B1-02110DF-SCC-045-GD 2.06E+05 4.90E+04 4.11E+06 7.99E+05 7.61E+04 0.083 B1-02110DF-SWC-046-GD 4.72E+05 0.00E+00 7.90E+05 2.30E+06 6.94E+04 0.113 B1-02110DF-SWC-047-GD 1.01E+06 1.06E+04 5.89E+05 5.05E+06 2.47E+05 0.119 B1-02110DF-SWC-048-GD 5.68E+05 1.35E+05 1.28E+06 2.81E+06 1.05E+05 0.132 B1-02110DF-SWC-049-GD 6.12E+05 8.42E+04 4.75E+05 3.74E+06 1.86E+05 0.113

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 23 (continued) - Unit 2 Containment Under Vessel Area - Measured Concentrations of ROC for FSS Co-60(2) Cs-134 Cs-137(2) Eu-152 Eu-154 Measurement ID 2 2 2 2 OpSOF(1)

(pCi/m ) (pCi/m ) (pCi/m ) (pCi/m ) (pCi/m2)

B1-02110DF-SWC-050-GD 2.70E+05 1.08E+04 3.09E+06 1.05E+06 6.00E+05 0.168 B1-02110DF-SWC-051-GD 5.45E+05 1.64E+04 2.44E+05 2.41E+06 1.34E+05 0.100 B1-02110DF-SWC-052-GD 3.05E+05 6.86E+03 3.27E+05 1.83E+06 9.76E+05 0.101 B1-02110DF-SWC-053-GD 4.51E+05 4.58E+04 7.07E+05 2.04E+06 1.09E+05 0.111 B1-02110DF-SFM-054-GD 1.62E+04 9.44E+03 2.64E+05 6.21E+04 1.91E+03 0.090 Note (1) OpSOF increased by a value of 0.083 to account for the presence of HTD ROC (2) The surrogate OpDCGL for Cs-137 (inferring both H-3 and Sr-90 at the maximum ratios from LTP Table 5-15) is 2.10E+07 pCi/m2 (Equation 4) and the surrogate OpDCGL for Co-60 (inferring Ni-63 at the maximum ratio from LTP Table 5-15) is 8.55E+06 pCi/m2 (Equation 5). No ISOCS measurement result for Cs-137 or Co-60 exceeded its respective surrogate OpDCGL value.

[86]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 24 - Unit 2 Containment Under Vessel Area - Statistical Quantities - Systematic Measurement Population Individual Measurement Metrics Total Number of Systematic Measurements = 54 Number of Quality Control Measurements = 3 Number of Judgmental/Investigational Measurements = 0 Total Number of Measurements = 57 Mean Systematic Gamma Measurement OpSOF = 0.147 Max Individual Systematic Gamma Measurement OpSOF= 0.457 Number of Systematic Measurements with OpSOF >1= 0 Max OpSOF from HTD ROC = 0.083 Statistical Quantities - Systematic Measurement Population MEAN MEDIAN MAX MIN ST. DEV. BcDCGL Avg Dose per Avg SOF per ROC ROC (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) ROC (mrem/yr)

H-3 4.42E+06 3.73E+06 1.15E+07 7.87E+05 2.44E+06 2.38E+08 0.019 0.464 Co-60 8.54E+05 2.87E+05 4.60E+06 1.82E+03 1.33E+06 1.57E+08 0.005 0.136 Ni-63 6.58E+05 4.67E+05 1.47E+06 3.02E+05 4.41E+05 4.02E+09 0.000 0.004 Sr-90 3.11E+04 2.61E+04 4.80E+04 2.42E+04 1.13E+04 1.43E+06 0.022 0.544 Cs-134 3.43E+04 1.28E+04 1.92E+05 0.00E+00 4.45E+04 3.01E+07 0.001 0.029 Cs-137 1.71E+06 6.93E+05 1.11E+07 2.00E+04 2.23E+06 3.94E+07 0.043 1.084 Eu-152 5.30E+06 1.20E+06 3.71E+07 0.00E+00 9.36E+06 3.66E+08 0.014 0.362 Eu-154 3.46E+05 1.21E+05 1.48E+06 0.00E+00 4.48E+05 3.19E+08 0.001 0.027 BASE CASE SOF (BcSOF) ASSIGNED TO SURVEY UNIT (SYSTEMATIC AVG.) = 0.106 DOSE ASSIGNED TO SURVEY UNIT (SYSTEMATIC AVG.) = 2.650 mrem/yr.

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Figure 16 - Unit 2 Containment Under Vessel ORISE FSS Confirmatory Locations

[88]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Table 25 - Unit 2 Containment Under Vessel Area - Post H-3 Concrete Removal Concrete Core Results B1-02110A-IRW-C001-CV H-3 Co-60 Ni-63 Sr-90 Cs-134 Cs-137 Eu-152 Eu-154 Depth (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g)

Surface to 0.5 inch 8.05E+01 5.90E+00 1.37E+00 6.97E-02 -9.87E-03 8.98E-01 9.35E+01 4.07E+00 0.5 to 1 inch 1.15E+02 5.53E+00 2.36E+00 4.04E-01 1.19E-01 4.87E-01 9.42E+01 3.85E+00 1 to 1.5 inch 1.18E+02 4.27E+00 1.95E+00 1.90E-01 8.79E-02 6.41E-02 8.05E+01 2.99E+00 1.5 to 2 inch 9.03E+01 6.92E+00 7.06E-01 2.81E-01 -4.93E-02 1.19E-02 1.16E+02 4.30E+00 2 to 2.5 inch 6.70E+01 4.92E+00 8.72E-01 2.16E-01 -2.02E-02 4.99E-01 1.02E+02 4.09E+00 2.5 to 3 inch 6.51E+01 3.01E+00 1.29E+00 -4.75E-02 -1.34E-02 -2.05E-01 5.24E+01 1.90E+00 3 to 3.5 inch 6.10E+01 2.27E+00 7.75E-01 3.68E-01 -1.20E-02 -2.39E-01 4.07E+01 1.80E+00 3.5 to 4 inch 5.65E+01 2.38E+00 1.52E+00 7.73E-02 2.34E-01 -1.24E-01 7.27E+01 2.12E+00 4 to 4.5 inch 4.55E+01 1.94E+00 1.88E+00 2.24E-01 8.85E-02 2.24E-01 3.06E+01 1.80E+00 4.5 to 5 inch 3.91E+01 1.95E+00 5.16E-01 3.49E-01 -5.07E-01 -7.41E-02 2.79E+01 1.50E+00 B1-02110A-IRW-C002-CV H-3 Co-60 Ni-63 Sr-90 Cs-134 Cs-137 Eu-152 Eu-154 Depth (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g)

Surface to 0.5 inch 1.48E+02 5.13E+00 8.35E+00 5.25E-01 -4.18E-02 3.73E-01 1.10E+02 4.12E+00 0.5 to 1 inch 1.49E+02 6.02E+00 5.59E+00 4.21E-01 -9.09E-02 -3.66E-01 1.32E+02 5.31E+00 1 to 1.5 inch 1.42E+02 6.19E+00 6.95E+00 4.70E-01 -3.00E-01 -1.74E-01 1.17E+02 4.25E+00 1.5 to 2 inch 1.11E+02 6.41E+00 4.80E+00 2.95E-01 1.07E-01 1.16E-01 1.30E+02 3.61E+00 2 to 2.5 inch 1.35E+02 3.86E+00 3.57E+00 4.53E-01 -5.41E-02 4.85E-02 8.13E+01 3.30E+00 2.5 to 3 inch 4.24E+01 3.27E+00 2.32E+00 6.35E-02 -9.21E-03 2.15E-01 6.49E+01 2.49E+00 3 to 3.5 inch 1.12E+02 3.12E+00 2.76E+00 1.95E-01 -4.18E-01 -9.44E-02 5.50E+01 2.07E+00 3.5 to 4 inch 7.57E+01 2.91E+00 1.85E+00 -1.28E-01 7.89E-02 -1.02E-01 8.20E+01 2.27E+00 4 to 4.5 inch 7.38E+01 2.31E+00 1.94E+00 -1.60E-01 1.01E-02 -1.25E-01 4.05E+01 1.61E+00 4.5 to 5 inch 6.46E+01 1.38E+00 1.50E+00 1.48E-01 -9.81E-03 -7.11E-02 2.97E+01 1.23E+00 5 to 5.5 inch 4.51E+01 1.20E+00 2.33E+00 -2.12E-01 -2.28E-02 4.20E-01 2.99E+01 4.56E-01

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110

8. QUALITY CONTROL The implementation of required QC measures included the collection of three (3) additional ISOCS measurements in the Under Vessel area (survey unit 02110) and nine (9) additional ISOCS measurements in the 565 foot elevation (survey unit 02100) for replicate measurement analysis. The complete ISOCS gamma spectroscopy reports for the replicate measurements are presented in Attachment 6. All replicate ISOCS measurements met the required acceptance criteria. The completed Replicate Sample Assessment Forms are included in Attachment 4 of this Release Record.

9. INVESTIGATIONS AND RESULTS The Unit 2 Containment Building was initially turned over to C/LT for performance of FSS on January 9, 2018. A walkdown by C/LT and the decommissioning contractor was conducted on that date. Following completion of the initial turnover surveys, the Unit 2 Containment was deemed to be ready for FSS. As previously stated in the Survey Implementation section of this Release Record, the C/LT group attempted to perform FSS on January 12, 2018. Several ISOCS measurement on the floor of the Under Vessel area indicated a SOF greater than one (1) when compared against the Base Case DCGLs. The elevated area was bounded and an investigation was initiated on January 12, 2018. The investigation concluded that further remediation was required in the Under Vessel area and a recommendation was made to remove approximately four (4) inches of concrete from the floor and walls of the Under Vessel and Incore Tunnel area. Remediation commenced on January 13, 2018.

Following remediation, C/LT was notified by the decommissioning contractor on January 28, 2018 that the Unit 2 Containment Building was again ready for FSS. On January 29, 2018, investigational ISOCS measurements indicated contaminated concrete at concentrations exceeding the Base Case DCGL. A second investigation was initiated on January 30, 2018 for FSS failure. Following the investigation, further remediation was recommended. On February 3, 2018, the decommissioning contractor re-commenced remediation of Under Vessel concrete.

On February 12, 2018, C/LT took turnover of the Unit 2 Containment Under Vessel area for the third time. As part of the turnover survey, investigative ISOCS shots were performed at the locations where elevated measurements were identified previously in the Under Vessel area. The results of several shots indicated SOF results greater than one (1).

The area was rejected and turned back over for additional remediation on February 15, 2018.

The C/LT Manager was notified by the decommissioning contractor on February 22, 2018 that the Unit 2 Containment Building was again ready for FSS. Investigational ISOCS

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 measurements were taken at Under Vessel locations #007 and #012 on February 24, 2018.

Again, measurement results indicated a SOF greater than one at those locations and so the Unit 2 Containment Building was not acceptable for turnover. The area was rejected and turned back over for additional remediation on February 25, 2018.

Remediation was completed on April 5, 2018. The area was cleaned and turned over to the C/LT group for FSS. A walkdown and turnover survey was satisfactorily performed in both FSS units. Following the successful completion of the turnover surveys, the radiological conditions were deemed acceptable and the area was posted for FSS isolation and control.

10. REMEDIATION AND RESULTS As noted in Section 9 above, repeated cycles of extensive remediation and re-survey were required in the Under Vessel area prior to performance of FSS. Following remediation, FSS was conducted successfully and met all acceptance criteria for release of the survey units.

Chapter 4 of the ZSRP LTP states that remediation beyond that required to meet the release criteria is unnecessary and that the remaining residual radioactivity in structures was ALARA.

11. CHANGES FROM THE FINAL STATUS SURVEY PLAN In accordance with the LTP, compliance with the unrestricted release criteria is demonstrated though a series of static measurements taken with an ISOCS. LTP section 5.5.2.2, Table 5-19 lists the Unit 2 Containment Under Vessel area as a Class 1 basement structure survey unit with a total surface area of 294 m2 and the Unit 2 Containment above the 565 foot elevation as a Class 1 basement structure survey unit with a total surface area of 2,465 m2. The FSS design specified to demonstrate compliance required a minimum of 155 static ISOCS measurements above the 565 foot elevation, 19 static ISOCS measurements in the Under Vessel area and areal coverage of 100% in both survey units.

One hundred and sixty four (164) static ISOCS measurements and fifty-four (54) static ISOCS measurements were taken in the Unit 2 Containment above the 565 foot elevation and the Under Vessel structural survey units respectively to ensure that 100% of the surface area was surveyed (the ISOCS FOV was overlapped to ensure that there were no un-surveyed corners and/or gaps). No judgmental measurements were taken. Replicate measurements were taken at nine (9) locations above the 565 foot elevation and three (3) locations in the Under Vessel area that were selected at random (LTP section 5.9.3.1). In addition, a concrete core was required to be taken at 10% of the locations selected for an FSS ISOCS measurement (LTP section 5.1) which would require the acquisition of a

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 minimum of six (6) FSS confirmatory concrete cores in the Under Vessel area. All concrete was removed above the 565 foot elevation. Consequently, no concrete core samples were acquired.

The LTP assumes that HTD concentrations will be inferred. Section 5.2.11 of the LTP states, During FSS, HTD concentrations will be inferred using a surrogate approach. Cs-137 is the principle surrogate radionuclide for H-3 and Sr-90 and Co-60 is the principle surrogate radionuclide for Ni-63. The maximum ratios used to infer HTD concentrations during compliance are presented in Table 5-15 from LTP section 5.2.11.

As previously stated, a concrete core was required to be taken at 10% of the locations selected for an FSS ISOCS measurement in the Unit 2 Containment Under Vessel area (LTP section 5.1) for a minimum of 6 concrete cores to be taken as part of the FSS. The purpose of the core samples was to ensure that the ratios used to infer the HTD concentrations remained valid. During the remediation process, it was acknowledged that the concrete surfaces that were represented by the continuing characterization concrete samples were remediated twice and the actual concrete that was sampled (original concrete surface to a depth of 1/2 inch) had been removed and disposed of as radioactive waste. At least a foot of concrete was removed from the Under Vessel floor and up to 6 inches of concrete removed from the walls.

Due to the amount of remediation that occurred on the Under Vessel concrete, ZSRP took an additional 19 concrete cores that represented the as-left condition of the Under Vessel concrete following concrete remediation. A review of the analysis of the post-remediation concrete core data indicated that almost all of the ratios to Cs-137 for H-3 exceeded 1.76 and all the positive results for Sr-90 exceeded 0.021, which are the maximum ratios from LTP section 5.2.11, Table 5-15. A review of the results clearly show that the cause can be attributed to the fact that the majority of the less soluble source term activity for Cs-137 was contained with the near surface concrete that was remediated and removed (within a minimum of 6 inches) while the more soluble ROC (H-3 and Sr-90), while present in lesser concentrations than present in the pre-remediated concrete, have become the dominant radionuclide in the relationship with Cs-137. Due to the significant reduction in the concentrations of the gamma-emitting ROC (many at MDC),

the H-3 and Sr-90 concentrations are not well correlated with Cs-137 and the use of a ratio with Cs-137 to infer a concentration for the HTD was no longer defensible.

On April 10, 2018, ZSRP submitted a proposal to the NRC for an alternate approach to use the actual HTD concentrations from the 19 end-state cores to demonstrate compliance as opposed to surrogate ratios. ZSRP proposed to use measured concentrations of each HTD ROC in units of pCi/g for each of the nineteen (19) locations and, assuming a depth of 1/2 inch (1.27 cm) and a concrete density of 2.35 g/cm3, converting the concentrations to

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 units of pCi/m2. While it was acknowledged that the depth of contamination for the HTD ROC was greater than 1/2 inch, it was also proposed to use the maximum concentration to conservatively compensate for the additional source term at depth. The concentration is then divided by its respective OpDCGL to derive an OpSOF.

For the FSS of the Unit 2 Containment Under Vessel concrete, the maximum measured concentrations of H-3, Ni-63 and Sr-90 in the 19 concrete core samples were used to extrapolate a worst-case OpSOF of 0.083 from the presence of HTD ROC. As before, a SOF was calculated for each of the 54 ISOCS measurements taken Under Vessel however, only the gamma results were included. Instead of inferring concentrations for the HTD SOF using a surrogate, the maximum measured SOF of 0.083 for HTD ROC was added to the OpSOF for the gamma results. Of the 54 measurements taken, no measurement exceeded a SOF of one. The OpSOF (including the addition of the maximum SOF of 0.083 from HTD) for each measurement was used as the sum value for the Sign Test.

Passing the Sign Test demonstrates that the mean activity for each ROC is less than the OpDCGLB at a Type I decision error of 0.05. The sample data passed the Sign Test. The null hypothesis was rejected. Compliance with the dose-based unrestricted release criteria was again demonstrated in accordance with the process presented in the LTP as well as the proposed approach for accounting for the presence of HTD ROC.

The actual measured concentrations for HTD ROC were used in conjunction with the 54 ISOCS measurements taken on the Under Vessel concrete in Unit 2 Containment to demonstrate compliance. It should also be noted that the surrogate OpDCGL for Cs-137 (inferring both H-3 and Sr-90 at the maximum ratios from LTP Table 5-15) equaled 2.10E+07 pCi/m2 (Equation 4) and the surrogate OpDCGL for Co-60 (inferring Ni-63 at the maximum ratio from LTP Table 5-15) equaled 8.55E+06 pCi/m2 (Equation 5). No ISOCS measurement result for Cs-137 or Co-60 exceeded its respective surrogate OpDCGL value.

Demonstrating compliance based on dose consequence from the actual measured concentrations for HTD ROC is a reasonable approach as the spatial distribution of the concrete cores is representative and, due to the extensive remediation and removal of source term, particularly Cs-137, the ratios used to infer H-3 and Sr-90 using the Cs-137 as a surrogate are no longer consistent or reasonably correlated.

There were no addendums to the FSS plan, however, there were changes to the ISOCS survey plans as noted earlier in this Release Record. Those changes were required due to constraints on placement of ISOCS detectors that were not obvious when the FSS plan was first written. The changes in ISOCS measurement locations were made to ensure 100% areal coverage of the survey units.

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 In the 565 foot elevation, the floor and lower walls were gridded using available plant drawings. In practice, some of the identified ISOCS measurement locations were not usable, and some additional locations were required. Adjustments were made to ensure 100% coverage of the surface of the survey unit.

Corrected drawings for both survey units, showing final locations of all ISOCS measurements are included in Attachment 1 of this Release Record.

12. DATA QUALITY ASSESSMENT (DQA)

The DQO sample design and data were reviewed in accordance with ZionSolutions procedure ZS-LT-300-001-004, Final Status Survey Data Assessment (Reference 14) for completeness and consistency. Documentation was complete and legible. Surveys and the collection of measurements were consistent with the DQOs and were sufficient to ensure that the survey unit was properly designated as Class 1. The survey design had adequate power as indicated by the Retrospective Power Curve (see Attachment 5).

The analytical results of all ISOCS measurements were less than a SOF of one. Although MARSSIM states that the Sign Test need not be performed in the instance that no measurements surpass the DCGL, the test was conducted to demonstrate coherence to the statistical principles of the DQO process. The Sign Test (Attachment 3) was performed on the data and compared to the original assumptions of the DQOs. The evaluation of the Sign Test results clearly demonstrates that the survey unit passes the unrestricted release criteria, thus, the null hypothesis is rejected.

The preliminary data review consisted of calculating basic statistical quantities (e.g.,

mean, median, standard deviation). All data was considered valid including negative values, zeros, values reported below the MDC, and values with uncertainties that exceeded two standard deviations. The mean and median values for each ROC were well below the respective OpDCGLs. Also, the retrospective power curve shows that a sufficient number of samples were collected to achieve the desired power. Therefore, the survey unit meets the unrestricted release criteria with adequate power as required by the DQOs.

The data for Co-60 and Cs-137 is represented graphically through a frequency plot and a quantile plot. All graphical representations are provided in Attachment 5.

13. ANOMALIES No anomalies were observed during the performance or analyses of the survey.

14. COMPLIANCE EQUATION There are four distinct source terms for the end-state at Zion: backfilled basements, soil, buried piping and groundwater. Demonstrating compliance with the dose criterion

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 requires the summation of dose from the four source terms (see Equation 6-11 from LTP Chapter 6, section 6-17).

The final compliance dose will be calculated using LTP Equation 6-11 after FSS has been completed in all survey units. The results of the FSS performed for each FSS unit will be reviewed to determine the maximum dose from each of the four source terms (e.g.,

basement, soil, buried pipe and existing groundwater if applicable) using the mean BcSOF of FSS systematic results plus the dose from any identified elevated areas. The compliance dose must be less than 25 mrem/yr. The dose contribution from each ROC is accounted for using the BcSOF to ensure that the total dose from all ROC does not exceed the dose criterion.

The term for each basement includes the dose contributions from wall and floor surfaces within the basement, the dose contribution from embedded pipe within the basement, the dose contribution from penetrations within the basement and the dose contribution from concrete fill in the basement when clean concrete debris was used as fill. Each (structural surfaces, embedded pipe and penetrations) are surveyed separately during FSS. The dose from clean concrete fill is predetermined in accordance with LTP Chapter 5, Table 5-16, which is conservatively based on a maximum allowable MDC of 5,000 dpm/100cm2. The dose from fill assigned to the Unit 2 Containment basement is 1.775 mrem/yr, which equates to a SOF of 0.071.

After the FSS of all dose components in a given basement is complete and all dose component survey units pass the Sign Test, the BcSOF for each dose component is calculated using Equations 5-5 or 5-6 as applicable from LTP Chapter 5, section 5.5.4.

For both the Unit 2 Containment FSS unit above the 565 foot elevation and the Unit 2 Containment FSS unit in the Under Vessel area, there were no elevated area identified by the compliance survey (elevated areas are defined as areas exceeding the OpDCGL but less than the BcDCGL). The mean BcSOF for the Unit 2 Containment above the 565 foot elevation is 0.009, which equates to a dose of 0.219 mrem/yr, and the mean BcSOF for the Unit 2 Containment Under Vessel area is 0.106, which equates to a dose of 2.650 mrem/yr. As the DCGLs for both FSS units in Unit 2 Containment were derived on an area-weighted basis, the total mean BcSOF for Unit 2 Containment is a summation of the mean BcSOF for the area above the 565 foot elevation and the mean BcSOF for the area Under Vessel area, which equates to a total BcSOF for the Unit 2 Containment structure of 0.115 or a dose of 2.875 mrem/yr.

Basement surface area adjustments (i.e. increases) were applied to the DCGL calculation for certain basements to ensure that the DCGLs accounted for the contribution of residual radioactivity from basements/structures that cannot, on their own, support a water supply well but, were hydraulically connected to a basement that could support a well. In

[95]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 accordance with LTP section 5.5.6.1, this adjustment must be made to the Containment structural BcSOF due to its hydraulic conductivity with the SFP/Transfer Canal FSS unit.

Equation 5-8 from LTP Chapter 5, section 5.5.6.1 was used to sum the residual activity in the Unit 2 Containment structure and the SFP/Transfer Canal structure on an area-weighted basis. The mean BcSOF for the SFP/Transfer Canal is 0.039. The derivation of this value is documented in the Release Record for the SFP/Transfer Canal structure. LTP Chapter 5, section 5.5.6.1, Table 5-23 states that the total area for the Unit 2 Containment plus the area of the SFP/Transfer Canal is 3,482 m2 and the stand-alone area of the SFP/Transfer Canal is 723 m2. The result is provided in Equation 7.

Equation 7 723 (0.039) = 0.008 3482 The SOF of 0.008 is added to the mean BcSOF for the Unit 2 Containment to derive the adjusted BcSOF of 0.123 for the Unit 2 Containment basement structure. This equates to a dose of 3.075 mrem/yr. The adjusted BcSOF for the Unit 2 Containment structure is then used in the following equation to calculate BcSOFBASEMENT for the Unit 2 Containment.

Equation 8

= + + +

where:

SOFBASEMENT = SOF (mean of FSS systematic results plus the dose from any identified elevated areas) for backfilled basements SOFB = SOF for structural survey unit(s) within the basement (mean of FSS systematic results plus the dose from any identified elevated areas)

SOFEP = SOF for embedded pipe survey unit(s) within the basement (mean of FSS systematic results plus the dose from any identified elevated areas)

SOFPN = SOF for penetration survey unit(s) within the basement (mean of FSS systematic results plus the dose from any identified elevated areas)

SOFCF = SOF for clean concrete fill (if applicable) based on maximum MDC during unrestricted release survey

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 The variable for BcSOFPN for the Unit 2 Containment penetrations is 0.008. The derivation of this value is documented in the Release Record for the Unit 2 Containment penetrations.

The value for embedded pipe in the Unit 2 Containment is from the Unit 2 Tendon Tunnel 547 foot Embedded Floor Drain Pipe. From the Release Record for the Unit 2 Tendon Tunnel Floor Drain Pipe, the BcSOFEP value is 0.000. As previously stated in section 2 of this record, the Unit 2 Containment Incore Sump Drain was completely removed and disposed of as radioactive waste during decommissioning. Therefore, no dose will be assigned to the Unit 2 Containment Basement from embedded pipe 02111.

The BcSOFBASEMENT value for the Unit 2 Containment is then derived as follows; Equation 9

= 0.123 + 0.008 + 0.000 + 0.071 = 0.202 The BcSOFBASEMENT for the Unit 2 Containment basement is 0.202. This SOF equates to a dose of 5.062 mrem/yr TEDE to an AMCG from residual radioactivity in the Unit 2 Containment basement.

15. CONCLUSION Survey Units 02100 and 02110 have met the DQOs of the FSS plan. The ALARA criteria as specified in Chapter 4 of the LTP were achieved. The EMC is not applicable to structural surfaces and remediation was successfully implemented.

All identified ROC were used for statistical testing to determine the adequacy of the survey unit for FSS. Evaluation of the data shows that none of the ROC concentration values exceed the Operational DCGL or any investigational levels; therefore, in accordance with the LTP Section 5.10, the survey units meet the release criterion.

The sample data passed the Sign Test. The null hypothesis was rejected. The Retrospective Power Curve showed that adequate power was achieved. The survey units are properly classified as Class 1.

The total mean BcSOF for the Unit 2 Containment basement structure is 0.123, which is the sum of mean BcSOF from survey unit above 565 foot elevation plus the mean SOF from the Under Vessel area and adjusted to account for residual radioactivity in the SFP/Transfer Canal on an area-weighted basis. The total dose contribution from the Unit 2 Containment basement structure, including dose from penetrations, embedded pipe and fill is 5.062 mrem/yr TEDE (BcSOFBASEMENT = 0.202).

Survey Units 02100 and 02110 are acceptable for unrestricted release.

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110

16. REFERENCES

1. ZionSolutions procedure ZS-LT-300-001-005, Final Status Survey Data Reporting

2. Zion Station Restoration Project License Termination Plan

3. ZionSolutions procedure ZS-LT-300-001-001, Final Status Survey Package Development

4. NUREG-1575, Multi-Agency Radiation Survey and Site Investigation Manual

5. ZionSolutions TSD 17-004, Operational Derived Concentration Guideline Levels for Final Status Survey

6. Zion Station Historical Site Assessment

7. ZionSolutions TSD 14-028, Radiological Characterization Report

8. ZionSolutions procedure ZS-LT-300-001-002, Survey Unit Classification

9. ZionSolutions TSD 11-001, Technical Support Document for Potential Radionuclides of Concern During the Decommissioning of the Zion Station

10. ZionSolutions TSD 14-019, Radionuclides of Concern for Soil and Basement Fill Model Source Terms

11. ZionSolutions TSD 14-022, Use of In-Situ Gamma Spectroscopy for Final Status Survey of End State Structures

12. ZionSolutions TSD 13-005, Unit 1 & 2 Reactor Building End State Concrete and Liner Volumes and Surfaces Areas

13. ZionSolutions procedure ZS-LT-300-001-003, Isolation and Control for Final Status Survey

14. ZionSolutions procedure ZS-LT-300-001-004, Final Status Survey Data Assessment

17. ATTACHMENTS Attachment 1 - Additional Figures and Maps Attachment 2 - ISOCS Geometry Attachment 3 - Sign Test Attachment 4 - QC Measurement Assessments Attachment 5 - Graphical Presentations Attachment 6 - ISOCS Analytical Reports Attachment 7 - Eberline Reports

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ATTACHMENT 1 ADDITIONAL FIGURES AND MAPS

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Figure 1 - Under Vessel ISOCS Grid Locations - Under Vessel Wall

[100]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Figure 2 - Under Vessel ISOCS Grid Locations - Incore Floor

[101]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Figure 3 - Under Vessel ISOCS Grid Locations - Incore Tunnel Ceiling

[102]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Figure 4 - Under Vessel ISOCS Grid Locations - Incore Tunnel North Wall

[103]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Figure 5 - Under Vessel ISOCS Grid Locations - Incore Tunnel South Wall

[104]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Figure 6 - Under Vessel ISOCS Grid Locations - Sloped Tunnel Floor

[105]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Figure 7 - Under Vessel ISOCS Grid Locations - Sloped Tunnel Ceiling

[106]

ATTACHMENT 2 ISOCS Geometry

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 TSD 14-022, Use of In-Situ Gamma Spectroscopy for Source Term Survey of End State Structures The efficiency calibration methods and results for the use of in-situ gamma spectroscopy (ISOCS) to perform FSS of the ZSRP end state structure basements is presented in ZionSolutions TSD 14-022, Use of In-Situ Gamma Spectroscopy for Source Term Survey of End State Structures. The following is relevant information pertaining to ISOCS geometry for FSS of the Containment basements that is reproduced from the TSD.

For survey planning purposes and the assessments provided in the TSD, the assumed configuration of the ISOCS system during FSS is a three meter distance from the surface to be measured with a 90 degree, 50 mm lead collimator. This results in a 28.3 m2 FOV. The source term geometry, concentration depth profile and areal distribution of the residual radioactivity in structures are required to generate efficiency curves (i.e., efficiency as a function of energy). The concrete cores obtained during characterization, continuing characterization and FSS confirmatory phase provide the necessary information regarding the distribution of activity with depth for each structure. The areal distribution is assumed to be uniform for the efficiency calibration.

Containment Above 565 foot Elevation ISOCS Geometries For Final Status Surveys Section 3.7 of TSD 14-022 acknowledges the decommissioning approach for the Containment basements above the 565 foot elevation to remove all concrete inside the liners in both Containments. The source term geometry for the containment basements above the 565 ft/

elevation will be a thin layer of surface contamination on the remaining exposed steel liner. The geometry used on the Containment steel liner walls and floors will be a circular plane (CP) geometry with a thin source thickness. A source thickness of 0.153 cm provides a bounding and conservative depth of contamination for the liner model.

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110

• • • • • G A M M A S P E C T R U M A N A L Y S I S ***

Filename: C:\GENIE2K\CAMFILES\10216-012 7-31-13.CNF Report Generated On  : 5/14/2015 10:14:45 AM Sample Title  : CP_Containment_0.153_Steel Sample Description  :

Sample Identification  :

Sample Type  : Steel Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 50 - 8192 Peak Area Range (in channels)  : 50 - 8192 Identification Energy Tolerance  : 1.000 keV Sample Size  : 1.000E+000 M^2 Sample Taken On  :

Acquisition Started  : 7/31/2013 @ 12:36:59 PM

[109]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Live Time  : 900.0 seconds Real Time  : 902.5 seconds Dead Time  : 0.28 %

Energy Calibration Used Done On  : 5/13/2013 Efficiency Calibration Used Done On  : 5/11/2015 Efficiency ID  : U1CT_.153_051115

• • • • • P E A K A N A L Y S I S R E P O R T **

Detector Name: 5452 Sample Title: CP_Containment_0.153_Steel Peak Analysis Performed on: 5/14/2015 @ 10:14:44 AM Peak Analysis From Channel: 50 Peak Analysis To Channel: 8192 ROI Energy FWHM Net Peak Peak Net Peak Continuum Area No. start end centroid (keV) (keV) Area Counts Uncert.

1 336 345 340.40 84.83 1.14 3.61E+01 40.33 1.64E+02 2 946 961 954.82 238.59 1.15 8.72E+01 32.59 5.88E+01 3 2327 2336 2331.97 583.12 0.53 1.90E+01 16.02 2.00E+01 4 2639 2654 2644.80 661.36 0.86 4.23E+01 17.98 1.27E+01 5 5830 5852 5841.95 1460.50 1.21 2.08E+02 31.75 1.15E+01 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

• • • • • N U C L I D E I D E N T I F I C A T I O N R E P O R T ***

Sample Title: CP_Containment_0.153_Steel Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion_LiB.NLB

....................IDENTIFIED NUCLIDES.....................

Nuclide ID Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/m2) Uncertainty

[110]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 K-40 0.985 1460.81* 10.67 8.89E+05 1.55E+05 Cs-137 0.986 661.65* 85.12 1.50E+04 6.63E+03 Tl-208 0.999 583.19 84.50 6.37E+03 5.42E+03 Pb-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 3.43E+04 1.40E+04 300.09 3.41 Th-231 0.983 26.64 18.70 84.21* 8.00 7.05E+04 7.99E+04 89.95 1.25

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

[111]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110

• • • • • I N T E R F E R E N C E C O R R E C T E D R E P O R T ***

Nuclide Nuclide ID Weighted Mean Weighted Mean Name Confidence Activity Activity (pCi/m2) Uncertainty K-40 0.985 8.89E+05 1.55E+05 Cs-137 0.986 1.50E+04 6.63E+03 Tl-208 0.999 6.37E+03 5.42E+03 Pb-212 1.000 3.43E+04 1.40E+04 Th-231 0.983 7.05E+04 7.99E+04

? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis

@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma

• • • • • • • • • • • • • • • • U N I D E N T I F I E D P E A K S****************

Peak Locate Performed on: 5/14/2015 @ 10:14:44 AM Peak Locate From Channel: 50 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide All peaks were identified.

• • • • • N U C L I D E M D A R E P O R T **

Detector Name: 5452 Sample Geometry:

Sample Title: CP_Containment_0.153_Steel Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion_LiB.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)

+K-40 1460.81 10.67 1.06E+05 1.06E+05 8.89E+05 4.71E+04 Mn-54 834.83 99.97 6.62E+03 6.62E+03 1.88E+03 2.85E+03 Co-60 1173.22 100 3.76E+03 3.76E+03 -5.06E+03 1.33E+03 1332.49 100 8.45E+03 4.95E+03 3.64E+03 Nb-94 702.63 100 6.07E+03 5.78E+03 1.13E+03 2.61E+03 871.10 100 5.78E+03 1.92E+01 2.42E+03

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 SN-113 255.12 1.93 3.03E+05 9.00E+03 6.53E+04 1.40E+05 391.69 64.90 9.00E+03 -2.70E+03 4.02E+03 Cs-134 475.35 1.46 3.61E+05 6.47E+03 8.19E+04 1.57E+05 563.23 8.38 6.47E+04 -2.48E+04 2.78E+04 569.32 15.43 3.97E+04 7.38E+03 1.74E+04 604.70 97.60 7.40E+03 2.96E+02 3.30E+03 795.84 85.40 6.47E+03 -2.91E+03 2.71E+03 801.93 8.73 8.56E+04 1.64E+04 3.76E+04 1038.57 1.00 5.70E+05 -1.04E+05 2.34E+05 1167.94 1.80 3.16E+05 -1.42E+05 1.28E+05 1365.15 3.04 1.34E+05 9.04E+03 4.76E+04

+Cs-137 661.65* 85.12 8.21E+03 8.21E+03 1.50E+04 3.63E+03

+Tl-208 583.19* 84.50 8.32E+03 8.32E+03 6.37E+03 3.71E+03 Bi-211 72.87 1.20 1.06E+06 6.96E+04 -4.79E+05 5.08E+05 351.10 12.20 6.96E+04 2.96E+04 3.24E+04 404.80 4.10 1.48E+05 2.16E+03 6.62E+04 426.90 1.90 3.04E+0 -8.13E+03 1.35E+05 831.80 3.30 1.71E+0 -4.11E+04 7.17E+04 Pb-211 404.80 3.00 2.02E+0 2.02E+05 2.96E+03 9.04E+04 427.10 1.40 4.21E+0 2.48E+04 1.87E+05 831.80 2.80 2.02E+0 -4.11E+04 8.45E+04 Bi-212 39.86 1.10 5.05E+0 5.88E+04 -1.74E+06 2.45E+06 727.17 11.80 5.88E+0 1.56E+04 2.58E+04 785.42 2.00 2.87E+0 -2.06E+05 1.21E+05 1620.56 2.75 1.64E+0 -3.10E+04 5.82E+04 Pb-212 74.81 9.60 1.42E+05 1.84E+04 1.52E+05 6.86E+04 77.11 17.50 6.24E+04 3.00E+03 2.99E+04 87.20 6.30 1.44E+05 2.78E+04 6.87E+04 89.80 1.75 4.21E+05 -1.53E+05 1.99E+05 115.19 0.60 1.15E+06 2.65E+05 5.44E+05 238.63* 44.60 1.84E+04 3.43E+04 8.65E+03 300.09 3.41 1.73E+05 -3.33E+04 7.88E+04 Bi-214 609.31 46.30 2.33E+04 2.33E+04 2.49E+04 1.08E+04 768.36 5.04 1.26E+05 4.90E+04 5.42E+04 806.17 1.23 5.62E+05 9.23E+04 2.45E+05 934.06 3.21 1.78E+05 2.03E+04 7.37E+04 1120.29 15.10 7.14E+04 2.33E+04 3.56E+04 3.22E+04 1155.19 1.69 3.11E+05 -7.60E+04 1.24E+05 1238.11 5.94 1.27E+05 -9.08E+03 5.41E+04 1280.96 1.47 5.03E+05 -2.89E+03 2.12E+05 1377.67 4.11 2.10E+05 1.40E+05 9.02E+04 1385.31 0.78 8.02E+05 -1.61E+05 3.24E+05 1401.50 1.39 5.10E+05 1.33E+05 2.11E+05 1407.98 2.48 2.71E+05 -5.15E+03 1.11E+05 1509.19 2.19 2.79E+05 2.66E+04 1.11E+05 1661.28 1.15 3.99E+05 0.00E+00 1.41E+05 1729.60 3.05 2.35E+05 3.74E+04 9.48E+04 1764.49 15.80 6.74E+04 2.88E+04 2.93E+04

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 1847.44 2.12 3.00E+05 9.99E+04 1.62E+05 2118.54 1.21 0.00E+00 0.00E+00 0.00E+00 Pb-214 74.81 6.33 2.15E+05 2.42E+04 2.30E+05 1.04E+05 77.11 10.70 1.02E+05 4.91E+03 4.89E+04 87.20 3.70 2.45E+05 3.88E+04 1.17E+05 89.80 1.03 7.16E+05 -2.59E+05 3.38E+05 241.98 7.49 7.41E+04 -8.92E+03 3.39E+04 295.21 19.20 3.61E+04 1.32E+04 1.67E+04 351.92 37.20 2.42E+04 2.38E+04 1.13E+04 785.91 1.10 5.43E+05 -1.31E+05 2.31E+05 Ra-226 186.21 3.28 2.11E+05 2.10E+05 8.24E+04 9.88E+04 89.95 2.10 3.47E+05 3.67E+04 -1.98E+05 1.64E+05 93.35 3.50 2.39E+05 1.35E+05 1.14E+05 129.08 2.80 2.15E+05 1.98E+04 1.01E+05 209.28 4.40 1.46E+05 3.45E+04 6.81E+04 270.23 3.60 1.75E+05 7.57E+04 8.03E+04 327.64 3.20 2.01E+05 7.23E+04 9.19E+04 Ac-228 338.32 11.40 5.82E+04 1.83E+04 2.66E+04 409.51 2.13 2.96E+05 -1.32E+04 1.33E+05 463.00 4.40 1.77E+05 4.55E+04 8.07E+04 794.70 4.60 1.36E+05 -1.43E+04 5.81E+04 911.60 27.70 3.67E+04 3.26E+04 1.66E+04 964.60 5.20 1.46E+05 2.42E+04 6.33E+04 969.11 16.60 5.63E+04 3.01E+04 2.52E+04 1587.90 3.71 1.83E+05 7.77E+04 7.38E+04 Pa-234M 766.36 0.29 2.29E+06 6.68E+05 4.08E+05 9.97E+05 1001.03 0.84 6.68E+05 -1.95E+05 2.74E+05 Th-234 92.38 2.81 2.76E+05 2.76E+05 -1.33E+05 1.31E+05 92.80 2.77 2.94E+05 3.01E+04 1.40E+05 112.81 0.28 2.28E+06 -1.30E+06 1.07E+06 U-235 89.96 1.50 4.63E+05 1.23E+04 -2.78E+05 2.30E+05 93.35 2.50 3.35E+05 1.89E+05 2.30E+05 105.00 1.00 6.99E+05 3.07E+05 1.59E+05 109.14 1.50 4.81E+05 2.97E+05 3.30E+05 143.76 10.50 6.20E+04 7.46E+03 2.28E+05 163.35 4.70 1.03E+05 -7.82E+04 4.74E+04 185.71 54.00 1.23E+04 7.78E+02 5.76E+03 202.12 1.00 5.15E+05 -7.04E+04 2.36E+05 205.31 4.70 1.26E+05 1.03E+04 5.83E+04 59.54 36.30 4.04E+04 4.04E+04 -1.48E+04 1.94E+04

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region or the region is outside the spectrum

@ = Half-life too short to be able to perform the decay correction

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Containment Sump Geometries: Zion Reactor Building Cavity Flood Sump Efficiency The Unit 1 and Unit 2 Containment sumps located on the 565 foot elevation that were modeled using Geometry Composer are mirror images of each other and separate geometries were not required. The sumps modeled were the Reactor Cavity Flood Sump and the Reactor Building Recirculation Sump. The sumps were modeled using the Room templates consisting of four sides and a bottom. The contamination was modeled as surface contamination where 10 percent of the surface activity was assumed to be associated with each of the four walls and 60 percent was expected to be contained on the floor of the sumps. A single geometry and source to detector distance was used for each sump model.

The Geometries are titled:

• Zion Reactor Bldg Cavity Flood Sump

• Zion Reactor Bldg Recirc Sump

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Containment Under Vessel (Incore) ISOCS Geometries For Final Status Surveys General At the time that TSD 14-022 was developed, the decommissioning approach for the Under Vessel concrete for both Containment basements was complete removal. Consequently, the document assumed conditions similar to the exposed liner above the 565 foot elevation. The approach was altered in late 2016 and it was decided to attempt to leave all concrete below the 565 foot elevation in the Under Vessel area with residual radioactivity less than the DCGL as the end-state.

Additional remediation and subsequent core sampling was required to quantify the remaining residual radioactivity (including both gamma emitting and HTD ROC). The core sampling also defined the depth of contamination associated with the Under Vessel concrete and augments the information required for developing the geometry and subsequent efficiency for the ISOCS measurements.

Discussion For both Unit 1 and Unit 2 Containment Under Vessel concrete, the gamma and HTD results of the continuing characterization core sampling (see Tables 4 and 5 of this Release Record for data used for Unit 2 Containment) were examined to develop initial geometries for the ISOCS. These initial geometries were based on the available data and were conservative. The geometries used were modeled using the Exponential Circular Plane (ECP) template included as part of the Canberra Geometry Composer software and is described in TSD 14-022. The initial Under Vessel (Incore) geometry parameters are provided in Table A below.

Table A - Under Vessel Initial Exponential Circular Plane Geometry Parameters Unit Analysis Depth of DRL*

Contamination (cm) (cm) 2 Total Average Activity 14.0 6.4 2 Weighted Fraction Average 17.8 8.6 1 Total Average Activity 16.5 8.1 1 Weighted Fraction Average 21.6 21.6

• Depth Relaxation Length as described in TSD 14-022.

Based on Table A data, the more conservative geometry parameters were selected for the Unit 2 Under Vessel FSS Sample Plan. These included the Depth of Contamination at 17.8 cm and a DRL of 8.6 cm.

While surveys were being conducted in Unit 2 Under Vessel area, the data used to develop the parameters in Table A were reviewed. In order to be consistent with TSD 14-022, the depth of contamination is determined by examining the average activity and converting the lambda ()

value generated by curve fitting exponential functions to the core data and subsequently, into the

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 contamination depth and DRL value used with the ISOCS Exponential Circular Plane Template in Geometry Composer. TSD 14-022 (equation 3) defines lambda where:

ln(0.368) = = 1 1

=

This activity examination was performed using the most recent Under Vessel core data and the associated spreadsheets and graphs (see Under Vessel A2-1 and A2-2) present both the data and results. The curve fit activity was used to develop a chart of total activity over depth and the cumulative value at the 90 percentile activity was used to select the depth of contamination.

As shown in the spreadsheets in 2A-1 and 2A-2, the evaluation resulted in a depth of contamination for Containment Units 1 and 2 under vessel of 15.24 cm and a DRL of 6.9 cm.

Table B below presents the new parameter values based on using the total activity as described above.

Table B - Revised Under Vessel Exponential Circular Plane Geometry Parameters Depth of DRL Unit Analysis Contamination (cm) (cm) 1 Total Average Activity 15.24 6.9 2 Total Average Activity 15.24 6.9 It was decided that instead of using the new parameter values in Table B to continue using the parameter values of 17.8 cm contamination depth and DRL of 8.6 cm in that the values are conservative, reasonable and prudent. Table C compares the Under Vessel geometry to the geometry created using the parameters in Table B for Co-60, Cs-137, Eu-152, Eu-154 and Eu-155. Table D compares the two geometries using the Sum of Fractions which is the approach used for data assessment and the final acceptance of FSS data.

For Under Vessel ISOCS measurements, four variations of the current geometry were used. The geometries variation is the source to detector distance of 1.0, 1.5, 2.0 and 3.0 meters. 2A-5 presents the Geometry Composer parameters and efficiency associated with each of the geometries. The geometries are files used for Genie2000 Spectrum Analysis Software are named as followed:

• 3M90D_ECP_17.8cm.geo

• 2M90D_ECP_17.8cm.geo

• 1.5M90D_ECP_17.8cm.geo

• 1M90D_ECP_17.8cm.geo

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 In addition to the above geometries another was created for the Under Vessel sump. This geometry was designed using Geometry Composers Rectangular Plane template. The contamination was distributed over a depth of 17.8 centimeters and 10 layers. The first 7.62 cm was divided into 1.27 cm segments (6) and the remaining 10.16 cm was divided into 4 segments (layers 2.54 cm thick). The associated concrete puck(s) activity for each layer was included as the Relative Concentration.

Table C - Difference Between the Under Vessel (UV) Geometry Used and Table B Geometry Nuclides UV Geometry* Geometry From (pCi/m2) Table B

(pCi/m2)

Co-60 3.10E+06 2.80E+06 0.097 (9.7%)

Cs-137 4.14E+06 3.69E+06 0.109 (10.9%)

Eu-152 1.10E+07 9.70E+06 0.118 (11.8%)

Eu-154 4.30E+05 3.86E+05 0.102 (10.2%)

Eu-155 7.87E+05 6.75E+05 0.142 (14.2%)

• Where current geometry parameter for depth is 17.8 cm and DRL is 8.6 cm; the file analyzed is from under vessel The Gamma Spectrum Analysis Reports used to create Table C are found in Attachment A2-3.

Table D - Difference Between Under Vessel (UV) and Table B Geometry SOF UV Geometry* Geometry From SOF Table B SOF

0.597 0.536 0.102 (10.2%)

The SOF spreadsheet used to create Table D is found in Attachment A2-4.

As noted in both Tables C and D, the UV geometry which using a thicker depth of contamination (17.8 cm) and larger DRL (8.6 cm) is ten percent more conservative than the Table B geometries.

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Attachment 2A-1 Unit 2 --Under Vessel Core Results for Contamination Depth and DRL Parameters

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Attachment 2A-2 Unit 2 --Under Vessel Core Results for Contamination Depth and DRL Parameters

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Attachment 2A-3 Gamma Spectrum Analysis Reports for Table C

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Attachment 2A-4 Under Vessel Sum Of Fractions for Current and Activity Derived Geometry for Table D SYSTEMATIC ISOCS MEASUREMENTS FSS Unit B1-02110B-F Description Unit 2 Containment Under Vessel Classification 1 Type Structural Surface Area 294 m2 Location Measured Inferred Activity Operational FOV Fraction of Sample ID ID# ROC Activity Ratio Activity per ROC DCGL OpSOF 2 OpDCGL (Grid No.) (m ) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)

B1-01110AF-SFC-003-GD 003 28 H-3 1.76 7.29E+06 7.29E+06 2.37E+08 3.08E-02 0.597 Co-60 3.10E+06 3.10E+06 1.56E+08 1.99E-02 Ni-63 442 1.37E+09 1.37E+09 4.00E+09 3.42E-01 Original Geometry Sr-90 0.021 8.70E+04 8.70E+04 1.42E+06 6.13E-02 3M90D 17.8cm 8.6cm Cs-134 1.64E+05 1.64E+05 2.99E+07 5.48E-03 Cs-137 4.14E+06 4.14E+06 3.92E+07 1.06E-01 Eu-152 1.10E+07 1.10E+07 3.64E+08 3.01E-02 Eu-154 4.30E+05 4.30E+05 3.17E+08 1.36E-03 B1-01110AF-SFC-003-GD 003 28 H-3 1.76 6.48E+06 6.48E+06 2.37E+08 2.74E-02 0.536 Co-60 2.80E+06 2.80E+06 1.56E+08 1.80E-02 Ni-63 442 1.24E+09 1.24E+09 4.00E+09 3.10E-01 Sr-90 0.021 7.74E+04 7.74E+04 1.42E+06 5.45E-02 3M90D 15.24cm 6.9cm Cs-134 1.45E+05 1.45E+05 2.99E+07 4.85E-03 Cs-137 3.68E+06 3.68E+06 3.92E+07 9.40E-02 Eu-152 9.70E+06 9.70E+06 3.64E+08 2.66E-02 Eu-154 3.86E+05 3.86E+05 3.17E+08 1.22E-03

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Attachment 2A-5 Under Vessel (Incore) Geometries (3M90D_ECP_17.8.geo)

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Attachment 2A-6 Under Vessel Geometries (Zion Unit 2 Incore Tunnel Sump)

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ATTACHMENT 3 SIGN TEST

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Sign Test - Unit 2 Containment Basement Above 565 foot Elevation Survey Area 02100 Description Unit 2 Containment Basement Survey Unit B1-02100A-F Description Area Above 565 foot Elevation Classification 1 Type I Error 0.05 # of Measurements 164 SOF SOF

1. 1-Ws Sign # 1-Ws Sign (Ws) (Ws) 1 0.045 0.96 +1 83 0.034 0.97 +1 2 0.075 0.93 +1 84 0.037 0.96 +1 3 0.045 0.96 +1 85 0.036 0.96 +1 4 0.053 0.95 +1 86 0.055 0.95 +1 5 0.058 0.94 +1 87 0.032 0.97 +1 6 0.040 0.96 +1 88 0.028 0.97 +1 7 0.029 0.97 +1 89 0.027 0.97 +1 8 0.042 0.96 +1 90 0.049 0.95 +1 9 0.036 0.96 +1 91 0.035 0.97 +1 10 0.037 0.96 +1 92 0.026 0.97 +1 11 0.042 0.96 +1 93 0.048 0.95 +1 12 0.052 0.95 +1 94 0.037 0.96 +1 13 0.056 0.94 +1 95 0.044 0.96 +1 14 0.040 0.96 +1 96 0.038 0.96 +1 15 0.078 0.92 +1 97 0.044 0.96 +1 16 0.059 0.94 +1 98 0.038 0.96 +1 17 0.075 0.93 +1 99 0.040 0.96 +1 18 0.151 0.85 +1 100 0.075 0.92 +1 19 0.332 0.67 +1 101 0.099 0.90 +1 20 0.099 0.90 +1 102 0.030 0.97 +1 21 0.100 0.90 +1 103 0.041 0.96 +1 22 0.034 0.97 +1 104 0.044 0.96 +1 23 0.019 0.98 +1 105 0.168 0.83 +1 24 0.060 0.94 +1 106 0.613 0.39 +1 25 0.066 0.93 +1 107 0.035 0.96 +1 26 0.068 0.93 +1 108 0.038 0.96 +1 27 0.040 0.96 +1 109 0.035 0.96 +1 28 0.055 0.95 +1 110 0.042 0.96 +1 29 0.072 0.93 +1 111 0.037 0.96 +1 30 0.065 0.94 +1 112 0.025 0.97 +1 31 0.042 0.96 +1 113 0.023 0.98 +1 32 0.060 0.94 +1 114 0.036 0.96 +1 33 0.055 0.94 +1 115 0.985 0.01 +1

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Sign Test - Unit 2 Containment Basement Above 565 foot Elevation (continued)

SOF SOF

1. 1-Ws Sign # 1-Ws Sign (Ws) (Ws) 34 0.037 0.96 +1 116 0.288 0.71 +1 35 0.037 0.96 +1 117 0.037 0.96 +1 36 0.069 0.93 +1 118 0.038 0.96 +1 37 0.044 0.96 +1 119 0.023 0.98 +1 38 0.031 0.97 +1 120 0.091 0.91 +1 39 0.045 0.95 +1 121 0.128 0.87 +1 40 0.060 0.94 +1 122 0.021 0.98 +1 41 0.082 0.92 +1 123 0.046 0.95 +1 42 0.059 0.94 +1 124 0.036 0.96 +1 43 0.052 0.95 +1 125 0.047 0.95 +1 44 0.044 0.96 +1 126 0.189 0.81 +1 45 0.027 0.97 +1 127 0.116 0.88 +1 46 0.039 0.96 +1 128 0.031 0.97 +1 47 0.034 0.97 +1 129 0.028 0.97 +1 48 0.040 0.96 +1 130 0.018 0.98 +1 49 0.039 0.96 +1 131 0.039 0.96 +1 50 0.024 0.98 +1 132 0.032 0.97 +1 51 0.059 0.94 +1 133 0.023 0.98 +1 52 0.042 0.96 +1 134 0.033 0.97 +1 53 0.035 0.97 +1 135 0.034 0.97 +1 54 0.037 0.96 +1 136 0.041 0.96 +1 55 0.049 0.95 +1 137 0.030 0.97 +1 56 0.049 0.95 +1 138 0.040 0.96 +1 57 0.053 0.95 +1 139 0.029 0.97 +1 58 0.040 0.96 +1 140 0.047 0.95 +1 59 0.047 0.95 +1 141 0.098 0.90 +1 60 0.051 0.95 +1 142 0.049 0.95 +1 61 0.059 0.94 +1 143 0.032 0.97 +1 62 0.044 0.96 +1 144 0.034 0.97 +1 63 0.059 0.94 +1 145 0.038 0.96 +1 64 0.106 0.89 +1 146 0.022 0.98 +1 65 0.071 0.93 +1 147 0.040 0.96 +1 66 0.035 0.97 +1 148 0.025 0.97 +1 67 0.058 0.94 +1 149 0.039 0.96 +1 68 0.082 0.92 +1 150 0.042 0.96 +1 69 0.056 0.94 +1 151 0.048 0.95 +1 70 0.049 0.95 +1 152 0.024 0.98 +1 71 0.033 0.97 +1 153 0.027 0.97 +1

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Sign Test - Unit 2 Containment Basement Above 565 foot Elevation (continued)

SOF SOF

1. 1-Ws Sign # 1-Ws Sign (Ws) (Ws) 72 0.025 0.98 +1 154 0.035 0.97 +1 73 0.055 0.95 +1 155 0.036 0.96 +1 74 0.053 0.95 +1 156 0.066 0.93 +1 75 0.027 0.97 +1 157 0.069 0.93 +1 76 0.033 0.97 +1 158 0.056 0.94 +1 77 0.064 0.94 +1 159 0.072 0.93 +1 78 0.034 0.97 +1 160 0.065 0.94 +1 79 0.031 0.97 +1 161 0.062 0.94 +1 80 0.041 0.96 +1 162 0.195 0.81 +1 81 0.054 0.95 +1 163 0.080 0.92 +1 82 0.048 0.95 +1 164 0.252 0.75 +1 Number of positive differences (S+) 164 Critical Value 93 The Survey Unit MEETS the Acceptance Criteria

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Sign Test - Unit 2 Containment Basement Under Vessel Area Survey Area 02100 Description Unit 2 Containment Basement Survey Unit B1-02110A-F Description Under Vessel Area Classification 1 Type I Error 0.05 # of Measurements 54 HTDs Inferred Using Table 5-15 Ratios Addition of Measured Max HTD of 0.083 SOF SOF

1. 1-Ws Sign # 1-Ws Sign (Ws) (Ws) 1 0.214 0.79 +1 1 0.192 0.81 +1 2 0.154 0.85 +1 2 0.152 0.85 +1 3 1.129 (0.13) -1 3 0.457 0.54 +1 4 0.102 0.90 +1 4 0.105 0.90 +1 5 0.142 0.86 +1 5 0.109 0.89 +1 6 0.095 0.91 +1 6 0.105 0.90 +1 7 0.080 0.92 +1 7 0.099 0.90 +1 8 0.076 0.92 +1 8 0.108 0.89 +1 9 0.319 0.68 +1 9 0.174 0.83 +1 10 0.333 0.67 +1 10 0.181 0.82 +1 11 0.109 0.89 +1 11 0.121 0.88 +1 12 0.137 0.86 +1 12 0.145 0.86 +1 13 0.106 0.89 +1 13 0.138 0.86 +1 14 0.572 0.43 +1 14 0.234 0.77 +1 15 0.846 0.15 +1 15 0.378 0.62 +1 16 0.453 0.55 +1 16 0.199 0.80 +1 17 0.777 0.22 +1 17 0.285 0.71 +1 18 0.762 0.24 +1 18 0.289 0.71 +1 19 0.674 0.33 +1 19 0.282 0.72 +1 20 0.771 0.23 +1 20 0.316 0.68 +1 21 0.289 0.71 +1 21 0.177 0.82 +1 22 0.281 0.72 +1 22 0.223 0.78 +1 23 0.059 0.94 +1 23 0.097 0.90 +1 24 0.157 0.84 +1 24 0.115 0.88 +1 25 0.006 0.99 +1 25 0.085 0.91 +1 26 0.013 0.99 +1 26 0.089 0.91 +1 27 0.009 0.99 +1 27 0.087 0.91 +1 28 0.007 0.99 +1 28 0.087 0.91 +1 29 0.014 0.99 +1 29 0.089 0.91 +1 30 0.058 0.94 +1 30 0.111 0.89 +1 31 0.007 0.99 +1 31 0.085 0.91 +1 32 0.027 0.97 +1 32 0.097 0.90 +1 33 0.033 0.97 +1 33 0.100 0.90 +1

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Sign Test - Unit 2 Containment Basement Under Vessel Area (continued)

SOF SOF

1. 1-Ws Sign # 1-Ws Sign (Ws) (Ws) 34 0.058 0.94 +1 34 0.111 0.89 +1 35 0.180 0.82 +1 35 0.176 0.82 +1 36 0.004 1.00 +1 36 0.084 0.92 +1 37 0.003 1.00 +1 37 0.084 0.92 +1 38 0.002 1.00 +1 38 0.084 0.92 +1 39 0.002 1.00 +1 39 0.084 0.92 +1 40 0.004 1.00 +1 40 0.084 0.92 +1 41 0.006 0.99 +1 41 0.086 0.91 +1 42 0.208 0.79 +1 42 0.189 0.81 +1 43 0.229 0.77 +1 43 0.200 0.80 +1 44 0.224 0.78 +1 44 0.083 0.92 +1 45 0.099 0.90 +1 45 0.113 0.89 +1 46 0.161 0.84 +1 46 0.119 0.88 +1 47 0.140 0.86 +1 47 0.132 0.87 +1 48 0.108 0.89 +1 48 0.113 0.89 +1 49 0.184 0.82 +1 49 0.168 0.83 +1 50 0.083 0.92 +1 50 0.100 0.90 +1 51 0.060 0.94 +1 51 0.101 0.90 +1 52 0.094 0.91 +1 52 0.111 0.89 +1 53 0.015 0.99 +1 53 0.090 0.91 +1 54 0.058 0.94 +1 54 0.111 0.89 +1 Number of positive differences (S+) 54 Number of positive differences (S+) 54 Critical Value 33 Critical Value 33 The Survey Unit MEETS the Acceptance Criteria

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ATTACHMENT 4 QC MEASUREMENT ASSESSMENTS

[158]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Replicate Measurement Assessment Survey Unit # 02100 Survey Unit Name Unit 2 Containment Above 565 foot Sample Plan # B1-02100A-F Sample

Description:

Comparison of replicate ISOCS measurements collected from measurement location #45. The standard measurement was B1-02100DF-SWM-045-GD, the comparison sample was B1-02100DF-QWM-045-GD.

STANDARD COMPARISON ROC Activity Standard Resolution Agreement Activity Standard Compariso Acceptable Value Error Range Value Error n Ratio (Y/N)

Cs-137 1.67E+04 1.07E+04 1.57 N/A 2.58E+04 1.03E+04 1.54 N K-40 6.39E+05 1.53E+05 4.18 0.5 - 2.0 5.94E+05 1.50E+05 0.93 Y Comments/Corrective Actions: The resolution when Table is provided to show acceptance criteria using Cs-137 was insufficient. Comparison was used to assess split samples.

then made using K-40. There was acceptable agreement between the standard measurement and the replicate measurement. No further action is necessary.

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FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Replicate Measurement Assessment Survey Unit # 02100 Survey Unit Name Unit 2 Containment Above 565 foot Sample Plan # B1-02100A-F Sample

Description:

Comparison of replicate ISOCS measurements collected from measurement location #50. The standard measurement was B1-02100DF-SWM-050-GD, the comparison sample was B1-02100DF-QWM-050-GD.

STANDARD COMPARISON ROC Activity Standard Resolution Agreement Activity Standard Compariso Acceptable Value Error Range Value Error n Ratio (Y/N)

Cs-137 1.97E+04 9.31E+03 2.12 N/A 2.18E+04 9.40E+03 1.11 N K-40 6.45E+05 1.50E+05 4.30 0.5 - 2.0 5.48E+05 1.59E+05 0.85 Y Comments/Corrective Actions: The resolution when Table is provided to show acceptance criteria using Cs-137 was insufficient. Comparison was used to assess split samples.

then made using K-40. There was acceptable agreement between the standard measurement and the replicate measurement. No further action is necessary.

[160]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Replicate Measurement Assessment Survey Unit # 02100 Survey Unit Name Unit 2 Containment Above 565 foot Sample Plan # B1-02100A-F Sample

Description:

Comparison of replicate ISOCS measurements collected from measurement location #60. The standard measurement was B1-02100DF-SWM-060-GD, the comparison sample was B1-02100DF-QWM-060-GD.

STANDARD COMPARISON ROC Activity Standard Resolution Agreement Activity Standard Compariso Acceptable Value Error Range Value Error n Ratio (Y/N)

Cs-137 4.01E+04 1.34E+04 2.99 N/A 3.66E+04 1.40E+04 0.91 N K-40 5.59E+05 1.48E+05 3.78 N/A 5.60E+05 1.44E+05 1.00 N Comments/Corrective Actions: The resolution when Table is provided to show acceptance criteria using Cs-137 and K-40 while using the acceptance used to assess split samples.

criteria from NRC Inspection Procedure, No. 84750 was not comparable. IAW section 4.2.2 of the QAPP, agreement is ultimately determined when the same conclusion is reached for each compared result in the professional opinion of the RE. No further action is necessary.

[161]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Replicate Measurement Assessment Survey Unit # 02100 Survey Unit Name Unit 2 Containment Above 565 foot Sample Plan # B1-02100A-F Sample

Description:

Comparison of replicate ISOCS measurements collected from measurement location #100. The standard measurement was B1-02100DF-SFM-100-GD, the comparison sample was B1-02100DF-QFM-100-GD.

STANDARD COMPARISON ROC Activity Standard Resolution Agreement Activity Standard Compariso Acceptable Value Error Range Value Error n Ratio (Y/N)

Cs-137 3.64E+04 1.20E+04 3.04 N/A 2.41E+04 1.20E+04 0.66 N K-40 6.79E+05 1.54E+05 4.41 0.5 - 2.0 5.45E+05 1.47E+05 0.80 Y Comments/Corrective Actions: The resolution when Table is provided to show acceptance criteria using Cs-137 was insufficient. Comparison was used to assess split samples.

then made using K-40. There was acceptable agreement between the standard measurement and the replicate measurement. No further action is necessary.

[162]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Replicate Measurement Assessment Survey Unit # 02100 Survey Unit Name Unit 2 Containment Above 565 foot Sample Plan # B1-02100A-F Sample

Description:

Comparison of replicate ISOCS measurements collected from measurement location #115. The standard measurement was B1-02100DF-SFM-115-GD, the comparison sample was B1-02100DF-QFM-115-GD.

STANDARD COMPARISON ROC Activity Standard Resolution Agreement Activity Standard Compariso Acceptable Value Error Range Value Error n Ratio (Y/N)

Cs-137 4.11E+04 2.64E+04 1.56 N/A 4.17E+04 1.38E+04 1.02 N K-40 7.37E+05 1.57E+05 4.69 0.5 - 2.0 6.10E+05 1.48E+05 0.83 Y Comments/Corrective Actions: The resolution when Table is provided to show acceptance criteria using Cs-137 was insufficient. Comparison was used to assess split samples.

then made using K-40. There was acceptable agreement between the standard measurement and the replicate measurement. No further action is necessary.

[163]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Replicate Measurement Assessment Survey Unit # 02100 Survey Unit Name Unit 2 Containment Above 565 foot Sample Plan # B1-02100A-F Sample

Description:

Comparison of replicate ISOCS measurements collected from measurement location #119. The standard measurement was B1-02100DF-SFM-119-GD, the comparison sample was B1-02100DF-QFM-119-GD.

STANDARD COMPARISON ROC Activity Standard Resolution Agreement Activity Standard Compariso Acceptable Value Error Range Value Error n Ratio (Y/N)

Cs-137 2.82E+04 1.12E+04 2.51 N/A 3.20E+04 1.20E+04 1.14 N K-40 6.48E+05 1.55E+05 4.18 0.5 - 2.0 6.49E+05 1.68E+05 1.00 Y Comments/Corrective Actions: The resolution when Table is provided to show acceptance criteria using Cs-137 was insufficient. Comparison was used to assess split samples.

then made using K-40. There was acceptable agreement between the standard measurement and the replicate measurement. No further action is necessary.

[164]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Replicate Measurement Assessment Survey Unit # 02100 Survey Unit Name Unit 2 Containment Above 565 foot Sample Plan # B1-02100A-F Sample

Description:

Comparison of replicate ISOCS measurements collected from measurement location #139. The standard measurement was B1-02100DF-SFM-139-GD, the comparison sample was B1-02100DF-QFM-139-GD.

STANDARD COMPARISON ROC Activity Standard Resolution Agreement Activity Standard Compariso Acceptable Value Error Range Value Error n Ratio (Y/N)

Cs-137 9.20E+04 2.33E+04 3.95 N/A 9.53E+04 2.29E+04 1.04 N K-40 5.75E+05 1.51E+05 3.81 N/A 6.06E+05 1.56E+05 1.05 N Comments/Corrective Actions: The resolution when Table is provided to show acceptance criteria using Cs-137 and K-40 while using the acceptance used to assess split samples.

criteria from NRC Inspection Procedure, No. 84750 was not comparable. IAW section 4.2.2 of the Quality Assurance Project Plan (QAPP), agreement is ultimately determined when the same conclusion is reached for each compared result in the professional opinion of the RE. No further action is necessary.

[165]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Replicate Measurement Assessment Survey Unit # 02100 Survey Unit Name Unit 2 Containment Above 565 foot Sample Plan # B1-02100A-F Sample

Description:

Comparison of replicate ISOCS measurements collected from measurement location #150. The standard measurement was B1-02100DF-SFM-150-GD, the comparison sample was B1-02100DF-QFM-150-GD.

STANDARD COMPARISON ROC Activity Standard Resolution Agreement Activity Standard Compariso Acceptable Value Error Range Value Error n Ratio (Y/N)

Co-60 2.21E+04 6.33E+03 3.49 N/A 2.74E+04 6.70E+03 1.24 N K-40 6.74E+05 1.61E+05 4.19 0.5 - 2.0 5.61E+05 1.57E+05 0.83 Y Comments/Corrective Actions: The resolution when Table is provided to show acceptance criteria using Cs-137 was insufficient. Comparison was used to assess split samples.

then made using K-40. There was acceptable agreement between the standard measurement and the replicate measurement. No further action is necessary.

[166]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Replicate Measurement Assessment Survey Unit # 02100 Survey Unit Name Unit 2 Containment Above 565 foot Sample Plan # B1-02100A-F Sample

Description:

Comparison of replicate ISOCS measurements collected from measurement location #165. The standard measurement was B1-02100DF-SFM-165-GD, the comparison sample was B1-02100DF-QFM-165-GD.

STANDARD COMPARISON ROC Activity Standard Resolution Agreement Activity Standard Compariso Acceptable Value Error Range Value Error n Ratio (Y/N)

Cs-137 2.55E+04 9.90E+03 2.58 N/A 1.27E+04 8.05E+03 0.50 N K-40 5.93E+05 1.51E+05 3.93 N/A 6.48E+05 1.52E+05 1.09 N Comments/Corrective Actions: The resolution when Table is provided to show acceptance criteria using Cs-137 and K-40 while using the acceptance used to assess split samples.

criteria from NRC Inspection Procedure, No. 84750 was not comparable. IAW section 4.2.2 of the QAPP, agreement is ultimately determined when the same conclusion is reached for each compared result in the professional opinion of the RE. No further action is necessary.

[167]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Replicate Measurement Assessment Survey Unit # 02110 Survey Unit Name Unit 2 Containment Under Vessel Area Sample Plan # B1-02110A-F Sample

Description:

Comparison of replicate ISOCS measurements collected from measurement location #16. The standard measurement was B1-02110DF-SWC-016-GD, the comparison sample was B1-02110DF-QWC-016-GD.

STANDARD COMPARISON ROC Activity Standard Resolution Agreement Activity Standard Compariso Acceptable Value Error Range Value Error n Ratio (Y/N)

Cs-137 8.43E+05 1.94E+05 4.34 0.5 - 2.0 5.65E+05 1.73E+05 0.67 Y Comments/Corrective Actions: There was Table is provided to show acceptance criteria acceptable agreement between the standard used to assess split samples.

measurement and the replicate measurement. No further action is necessary.

[168]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Replicate Measurement Assessment Survey Unit # 02110 Survey Unit Name Unit 2 Containment Under Vessel Area Sample Plan # B1-02110A-F Sample

Description:

Comparison of replicate ISOCS measurements collected from measurement location #17. The standard measurement was B1-02110DF-SWC-017-GD, the comparison sample was B1-02110DF-QWC-017-GD.

STANDARD COMPARISON ROC Activity Standard Resolution Agreement Activity Standard Compariso Acceptable Value Error Range Value Error n Ratio (Y/N)

Cs-137 4.14E+06 5.37E+05 7.70 0.6 - 1.66 4.17E+06 5.40E+05 1.01 Y Comments/Corrective Actions: There was Table is provided to show acceptance criteria acceptable agreement between the standard used to assess split samples.

measurement and the replicate measurement. No further action is necessary.

[169]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Replicate Measurement Assessment Survey Unit # 02110 Survey Unit Name Unit 2 Containment Under Vessel Area Sample Plan # B1-02110A-F Sample

Description:

Comparison of replicate ISOCS measurements collected from measurement location #51. The standard measurement was B1-01110AF-SWC-051-GD, the comparison sample was B1-02110DF-QWC-051-GD.

STANDARD COMPARISON ROC Activity Standard Resolution Agreement Activity Standard Compariso Acceptable Value Error Range Value Error n Ratio (Y/N)

Cs-137 2.44E+05 6.37E+04 3.83 N/A 2.50E+05 6.79E+04 1.03 N K-40 1.52E+06 3.77E+05 4.03 0.5 - 2.0 1.84E+06 4.02E+05 1.21 Y Comments/Corrective Actions: The resolution when Table is provided to show acceptance criteria using Cs-137 was insufficient. Comparison was used to assess split samples.

then made using K-40. There was acceptable agreement between the standard measurement and the replicate measurement. No further action is necessary.

[170]

ATTACHMENT 5 GRAPHICAL PRESENTATIONS

[171]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 QUANTILE PLOT FOR Co-60 Survey Unit: 02100 Survey Unit Name: Unit 2 Containment Above 565 ft 2

Mean: 4.49E+04 pCi/m Quantile Plot For Co-60 9.00E+05 8.00E+05 7.00E+05 Concentration (pCi/m2) 6.00E+05 5.00E+05 4.00E+05 3.00E+05 2.00E+05 1.00E+05 0.00E+00 0% 20% 40% 60% 80% 100%

Percentage RANK Co-60  % RANK Co-60  % RANK Co-60  % RANK Co-60  % RANK Co-60  % RANK Co-60  %

1 1.49E+03 0% 31 2.13E+04 19% 61 2.64E+04 37% 91 3.19E+04 55% 121 3.87E+04 73% 151 7.67E+04 92%

2 1.00E+04 1% 32 2.14E+04 19% 62 2.66E+04 38% 92 3.21E+04 56% 122 3.94E+04 74% 152 7.75E+04 92%

3 1.03E+04 2% 33 2.16E+04 20% 63 2.68E+04 38% 93 3.21E+04 56% 123 3.94E+04 75% 153 8.10E+04 93%

4 1.16E+04 2% 34 2.16E+04 20% 64 2.68E+04 39% 94 3.22E+04 57% 124 3.97E+04 75% 154 8.89E+04 94%

5 1.35E+04 3% 35 2.17E+04 21% 65 2.71E+04 39% 95 3.22E+04 58% 125 3.99E+04 76% 155 9.22E+04 94%

6 1.53E+04 3% 36 2.17E+04 22% 66 2.72E+04 40% 96 3.25E+04 58% 126 3.99E+04 77% 156 1.02E+05 95%

7 1.54E+04 4% 37 2.21E+04 22% 67 2.72E+04 41% 97 3.28E+04 59% 127 4.00E+04 77% 157 1.12E+05 95%

8 1.57E+04 5% 38 2.23E+04 23% 68 2.73E+04 41% 98 3.28E+04 59% 128 4.02E+04 78% 158 1.19E+05 96%

9 1.57E+04 5% 39 2.27E+04 23% 69 2.74E+04 42% 99 3.29E+04 60% 129 4.05E+04 78% 159 1.62E+05 97%

10 1.61E+04 6% 40 2.28E+04 24% 70 2.74E+04 42% 100 3.29E+04 61% 130 4.09E+04 79% 160 1.86E+05 97%

11 1.61E+04 6% 41 2.29E+04 25% 71 2.74E+04 43% 101 3.31E+04 61% 131 4.13E+04 80% 161 2.23E+05 98%

12 1.69E+04 7% 42 2.29E+04 25% 72 2.76E+04 44% 102 3.33E+04 62% 132 4.30E+04 80% 162 2.36E+05 98%

13 1.71E+04 8% 43 2.29E+04 26% 73 2.76E+04 44% 103 3.38E+04 63% 133 4.30E+04 81% 163 4.88E+05 99%

14 1.76E+04 8% 44 2.33E+04 27% 74 2.78E+04 45% 104 3.40E+04 63% 134 4.32E+04 81% 164 8.23E+05 100%

15 1.76E+04 9% 45 2.35E+04 27% 75 2.84E+04 45% 105 3.42E+04 64% 135 4.32E+04 82%

16 1.76E+04 9% 46 2.38E+04 28% 76 2.85E+04 46% 106 3.45E+04 64% 136 4.32E+04 83%

17 1.76E+04 10% 47 2.39E+04 28% 77 2.86E+04 47% 107 3.45E+04 65% 137 4.42E+04 83%

18 1.77E+04 11% 48 2.40E+04 29% 78 2.88E+04 47% 108 3.47E+04 66% 138 4.48E+04 84%

19 1.81E+04 11% 49 2.44E+04 30% 79 2.88E+04 48% 109 3.48E+04 66% 139 4.51E+04 84%

20 1.85E+04 12% 50 2.45E+04 30% 80 2.89E+04 48% 110 3.51E+04 67% 140 4.66E+04 85%

21 1.90E+04 13% 51 2.46E+04 31% 81 2.90E+04 49% 111 3.62E+04 67% 141 4.78E+04 86%

22 1.92E+04 13% 52 2.46E+04 31% 82 2.91E+04 50% 112 3.62E+04 68% 142 5.04E+04 86%

23 1.95E+04 14% 53 2.48E+04 32% 83 2.92E+04 50% 113 3.63E+04 69% 143 5.51E+04 87%

24 1.97E+04 14% 54 2.49E+04 33% 84 2.97E+04 51% 114 3.65E+04 69% 144 5.55E+04 88%

25 1.97E+04 15% 55 2.52E+04 33% 85 2.98E+04 52% 115 3.66E+04 70% 145 5.57E+04 88%

26 1.99E+04 16% 56 2.55E+04 34% 86 3.00E+04 52% 116 3.68E+04 70% 146 5.57E+04 89%

27 2.00E+04 16% 57 2.55E+04 34% 87 3.00E+04 53% 117 3.68E+04 71% 147 5.57E+04 89%

28 2.02E+04 17% 58 2.55E+04 35% 88 3.02E+04 53% 118 3.75E+04 72% 148 5.80E+04 90%

29 2.08E+04 17% 59 2.58E+04 36% 89 3.09E+04 54% 119 3.83E+04 72% 149 6.39E+04 91%

30 2.12E+04 18% 60 2.62E+04 36% 90 3.14E+04 55% 120 3.86E+04 73% 150 7.02E+04 91%

[172]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 HISTOGRAM FOR Co-60 Survey Unit: 02100 Survey Unit Name: Unit 2 Containment Above 565 ft Mean: 4.49E+04 pCi/m2 Median: 2.92E+04 pCi/m2 ST DEV: 7.74E+04 Skew: 7.71E+00 Frequency Plot For Co-60 100%

90%

80%

70%

Frequency 60%

50%

40%

30%

20%

10%

0%

8.38E+04 2.48E+05 4.13E+05 5.78E+05 7.42E+05 Upper End Value (pCi/m2)

Upper Value Observation Observation Frequency  %

8.38E+04 153 93%

1.66E+05 6 4%

2.48E+05 3 2%

3.31E+05 0 0%

4.13E+05 0 0%

4.95E+05 1 1%

5.78E+05 0 0%

6.60E+05 0 0%

7.42E+05 0 0%

8.25E+05 1 1%

TOTAL 164 100%

[173]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 QUANTILE PLOT FOR Cs-137 Survey Unit: 02100 Survey Unit Name: Unit 2 Containment Above 565 ft 2

Mean: 6.08E+04 pCi/m Quantile Plot For Cs-137 6.00E+05 5.00E+05 Concentration (pCi\m2) 4.00E+05 3.00E+05 2.00E+05 1.00E+05 0.00E+00 0% 20% 40% 60% 80% 100%

Percentage RANK Cs-137  % RANK Cs-137  % RANK Cs-137  % RANK Cs-137  % RANK Cs-137  % RANK Cs-137  %

1 1.28E+04 0% 31 2.48E+04 19% 61 3.15E+04 37% 91 4.16E+04 55% 121 5.89E+04 73% 151 1.27E+05 92%

2 1.52E+04 1% 32 2.52E+04 19% 62 3.16E+04 38% 92 4.17E+04 56% 122 5.90E+04 74% 152 1.52E+05 92%

3 1.67E+04 2% 33 2.52E+04 20% 63 3.18E+04 38% 93 4.25E+04 56% 123 6.33E+04 75% 153 1.59E+05 93%

4 1.74E+04 2% 34 2.55E+04 20% 64 3.24E+04 39% 94 4.29E+04 57% 124 6.51E+04 75% 154 1.85E+05 94%

5 1.78E+04 3% 35 2.58E+04 21% 65 3.32E+04 39% 95 4.31E+04 58% 125 6.62E+04 76% 155 1.93E+05 94%

6 1.79E+04 3% 36 2.59E+04 22% 66 3.34E+04 40% 96 4.35E+04 58% 126 6.93E+04 77% 156 1.93E+05 95%

7 1.81E+04 4% 37 2.61E+04 22% 67 3.54E+04 41% 97 4.40E+04 59% 127 6.97E+04 77% 157 1.95E+05 95%

8 1.86E+04 5% 38 2.66E+04 23% 68 3.58E+04 41% 98 4.40E+04 59% 128 7.25E+04 78% 158 1.96E+05 96%

9 1.86E+04 5% 39 2.74E+04 23% 69 3.60E+04 42% 99 4.43E+04 60% 129 7.31E+04 78% 159 2.07E+05 97%

10 1.95E+04 6% 40 2.74E+04 24% 70 3.60E+04 42% 100 4.47E+04 61% 130 7.62E+04 79% 160 2.08E+05 97%

11 1.97E+04 6% 41 2.77E+04 25% 71 3.61E+04 43% 101 4.52E+04 61% 131 7.71E+04 80% 161 2.71E+05 98%

12 1.99E+04 7% 42 2.81E+04 25% 72 3.64E+04 44% 102 4.58E+04 62% 132 7.93E+04 80% 162 3.53E+05 98%

13 2.00E+04 8% 43 2.82E+04 26% 73 3.72E+04 44% 103 4.67E+04 63% 133 8.36E+04 81% 163 3.76E+05 99%

14 2.01E+04 8% 44 2.84E+04 27% 74 3.73E+04 45% 104 4.73E+04 63% 134 8.42E+04 81% 164 5.30E+05 100%

15 2.02E+04 9% 45 2.87E+04 27% 75 3.74E+04 45% 105 4.78E+04 64% 135 8.46E+04 82%

16 2.12E+04 9% 46 2.94E+04 28% 76 3.74E+04 46% 106 4.79E+04 64% 136 8.54E+04 83%

17 2.14E+04 10% 47 2.94E+04 28% 77 3.75E+04 47% 107 4.83E+04 65% 137 8.68E+04 83%

18 2.14E+04 11% 48 2.96E+04 29% 78 3.76E+04 47% 108 4.86E+04 66% 138 8.94E+04 84%

19 2.17E+04 11% 49 2.96E+04 30% 79 3.79E+04 48% 109 4.91E+04 66% 139 8.95E+04 84%

20 2.23E+04 12% 50 2.99E+04 30% 80 3.82E+04 48% 110 4.99E+04 67% 140 9.20E+04 85%

21 2.27E+04 13% 51 2.99E+04 31% 81 3.85E+04 49% 111 5.00E+04 67% 141 9.56E+04 86%

22 2.29E+04 13% 52 3.00E+04 31% 82 3.86E+04 50% 112 5.07E+04 68% 142 9.75E+04 86%

23 2.38E+04 14% 53 3.01E+04 32% 83 3.87E+04 50% 113 5.12E+04 69% 143 1.04E+05 87%

24 2.40E+04 14% 54 3.02E+04 33% 84 3.87E+04 51% 114 5.14E+04 69% 144 1.04E+05 88%

25 2.41E+04 15% 55 3.06E+04 33% 85 3.91E+04 52% 115 5.15E+04 70% 145 1.04E+05 88%

26 2.41E+04 16% 56 3.06E+04 34% 86 3.95E+04 52% 116 5.22E+04 70% 146 1.05E+05 89%

27 2.41E+04 16% 57 3.07E+04 34% 87 3.96E+04 53% 117 5.22E+04 71% 147 1.05E+05 89%

28 2.41E+04 17% 58 3.07E+04 35% 88 4.01E+04 53% 118 5.47E+04 72% 148 1.18E+05 90%

29 2.44E+04 17% 59 3.09E+04 36% 89 4.08E+04 54% 119 5.56E+04 72% 149 1.22E+05 91%

30 2.47E+04 18% 60 3.13E+04 36% 90 4.11E+04 55% 120 5.87E+04 73% 150 1.24E+05 91%

[174]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 HISTOGRAM FOR Cs-137 Survey Unit: 02100 Survey Unit Name: Unit 2 Containment Above 565 ft Mean: 6.08E+04 pCi/m2 Median: 3.86E+04 pCi/m2 ST DEV: 6.71E+04 Skew: 3.83E+00 Frequency Plot For Cs-137 90%

80%

70%

60%

Frequency 50%

40%

30%

20%

10%

0%

6.82E+04 1.74E+05 2.80E+05 3.86E+05 4.92E+05 Upper End Value (pCi/m2)

Upper Value Observation Observation Frequency  %

6.82E+04 125 76%

1.21E+05 23 14%

1.74E+05 5 3%

2.27E+05 7 4%

2.80E+05 1 1%

3.33E+05 0 0%

3.86E+05 2 1%

4.39E+05 0 0%

4.92E+05 0 0%

5.45E+05 1 1%

TOTAL 164 100%

[175]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 QUANTILE PLOT FOR Eu-152 Survey Unit: 02100 Survey Unit Name: Unit 2 Containment Above 565 ft 2

Mean: 9.91E+04 pCi/m Quantile Plot For Eu-152 5.00E+06 4.50E+06 4.00E+06 Concentration (pCi/m2) 3.50E+06 3.00E+06 2.50E+06 2.00E+06 1.50E+06 1.00E+06 5.00E+05 0.00E+00 0% 20% 40% 60% 80% 100%

Percentage RANK Eu-152  % RANK Eu-152  % RANK Eu-152  % RANK Eu-152  % RANK Eu-152  % RANK Eu-152  %

1 0.00E+00 0% 31 9.35E+03 19% 61 1.86E+04 37% 91 3.10E+04 55% 121 5.06E+04 73% 151 9.23E+04 92%

2 0.00E+00 1% 32 1.01E+04 19% 62 1.89E+04 38% 92 3.16E+04 56% 122 5.13E+04 74% 152 9.25E+04 92%

3 0.00E+00 2% 33 1.04E+04 20% 63 1.99E+04 38% 93 3.25E+04 56% 123 5.29E+04 75% 153 9.55E+04 93%

4 0.00E+00 2% 34 1.05E+04 20% 64 2.01E+04 39% 94 3.29E+04 57% 124 5.33E+04 75% 154 1.05E+05 94%

5 0.00E+00 3% 35 1.09E+04 21% 65 2.02E+04 39% 95 3.37E+04 58% 125 5.52E+04 76% 155 1.12E+05 94%

6 0.00E+00 3% 36 1.17E+04 22% 66 2.03E+04 40% 96 3.45E+04 58% 126 5.58E+04 77% 156 1.15E+05 95%

7 0.00E+00 4% 37 1.33E+04 22% 67 2.10E+04 41% 97 3.47E+04 59% 127 5.63E+04 77% 157 1.92E+05 95%

8 0.00E+00 5% 38 1.34E+04 23% 68 2.11E+04 41% 98 3.47E+04 59% 128 5.72E+04 78% 158 3.78E+05 96%

9 3.74E+02 5% 39 1.36E+04 23% 69 2.13E+04 42% 99 3.58E+04 60% 129 5.73E+04 78% 159 5.93E+05 97%

10 7.10E+02 6% 40 1.37E+04 24% 70 2.20E+04 42% 100 3.59E+04 61% 130 5.73E+04 79% 160 6.60E+05 97%

11 1.19E+03 6% 41 1.40E+04 25% 71 2.22E+04 43% 101 3.71E+04 61% 131 5.73E+04 80% 161 7.54E+05 98%

12 1.68E+03 7% 42 1.49E+04 25% 72 2.27E+04 44% 102 3.76E+04 62% 132 5.73E+04 80% 162 1.29E+06 98%

13 2.09E+03 8% 43 1.51E+04 26% 73 2.30E+04 44% 103 3.79E+04 63% 133 5.90E+04 81% 163 2.67E+06 99%

14 2.32E+03 8% 44 1.57E+04 27% 74 2.31E+04 45% 104 3.81E+04 63% 134 5.94E+04 81% 164 4.70E+06 100%

15 2.40E+03 9% 45 1.57E+04 27% 75 2.33E+04 45% 105 3.87E+04 64% 135 5.95E+04 82%

16 2.45E+03 9% 46 1.58E+04 28% 76 2.33E+04 46% 106 4.01E+04 64% 136 6.26E+04 83%

17 3.22E+03 10% 47 1.61E+04 28% 77 2.33E+04 47% 107 4.04E+04 65% 137 6.36E+04 83%

18 4.13E+03 11% 48 1.62E+04 29% 78 2.37E+04 47% 108 4.09E+04 66% 138 6.38E+04 84%

19 4.61E+03 11% 49 1.63E+04 30% 79 2.40E+04 48% 109 4.21E+04 66% 139 6.55E+04 84%

20 4.76E+03 12% 50 1.64E+04 30% 80 2.40E+04 48% 110 4.25E+04 67% 140 6.66E+04 85%

21 4.80E+03 13% 51 1.67E+04 31% 81 2.52E+04 49% 111 4.45E+04 67% 141 6.69E+04 86%

22 5.43E+03 13% 52 1.68E+04 31% 82 2.67E+04 50% 112 4.46E+04 68% 142 6.82E+04 86%

23 6.68E+03 14% 53 1.69E+04 32% 83 2.68E+04 50% 113 4.47E+04 69% 143 7.19E+04 87%

24 6.77E+03 14% 54 1.72E+04 33% 84 2.77E+04 51% 114 4.49E+04 69% 144 7.56E+04 88%

25 7.99E+03 15% 55 1.76E+04 33% 85 2.79E+04 52% 115 4.52E+04 70% 145 7.69E+04 88%

26 8.32E+03 16% 56 1.78E+04 34% 86 2.79E+04 52% 116 4.55E+04 70% 146 8.28E+04 89%

27 8.38E+03 16% 57 1.81E+04 34% 87 2.92E+04 53% 117 4.83E+04 71% 147 8.28E+04 89%

28 8.45E+03 17% 58 1.85E+04 35% 88 2.99E+04 53% 118 4.97E+04 72% 148 8.45E+04 90%

29 8.58E+03 17% 59 1.86E+04 36% 89 3.09E+04 54% 119 4.98E+04 72% 149 8.52E+04 91%

30 9.04E+03 18% 60 1.86E+04 36% 90 3.10E+04 55% 120 5.00E+04 73% 150 8.60E+04 91%

[176]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 HISTOGRAM FOR Eu-152 Survey Unit: 02100 Survey Unit Name: Unit 2 Containment Above 565 ft Mean: 9.91E+04 pCi/m2 Median: 2.68E+04 pCi/m2 ST DEV: 4.36E+05 Skew: 8.70E+00 Frequency Plot For Eu-152 120%

100%

80%

Frequency 60%

40%

20%

0%

4.70E+05 1.41E+06 2.35E+06 3.29E+06 4.23E+06 Upper End Value (pCi/m2)

Upper Value Observation Observation Frequency  %

4.70E+05 158 96%

9.40E+05 3 2%

1.41E+06 1 1%

1.88E+06 0 0%

2.35E+06 0 0%

2.82E+06 1 1%

3.29E+06 0 0%

3.76E+06 0 0%

4.23E+06 0 0%

4.70E+06 1 1%

TOTAL 164 100%

[177]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 QUANTILE PLOT FOR Eu-154 Survey Unit: 02100 Survey Unit Name: Unit 2 Containment Above 565 ft 2

Mean: 2.82E+04 pCi/m Quantile Plot For Eu-154 6.00E+05 5.00E+05 Concentration (pCi/m2) 4.00E+05 3.00E+05 2.00E+05 1.00E+05 0.00E+00 0% 20% 40% 60% 80% 100%

Percentage RANK Eu-154  % RANK Eu-154  % RANK Eu-154  % RANK Eu-154  % RANK Eu-154  % RANK Eu-154  %

1 0.00E+00 0% 31 5.44E+03 19% 61 1.19E+04 37% 91 1.78E+04 55% 121 2.47E+04 73% 151 2.47E+04 73%

2 0.00E+00 1% 32 5.98E+03 19% 62 1.20E+04 38% 92 1.80E+04 56% 122 2.53E+04 74% 152 2.53E+04 74%

3 0.00E+00 2% 33 6.19E+03 20% 63 1.20E+04 38% 93 1.85E+04 56% 123 2.57E+04 75% 153 2.57E+04 75%

4 0.00E+00 2% 34 6.30E+03 20% 64 1.22E+04 39% 94 1.86E+04 57% 124 2.73E+04 75% 154 2.73E+04 75%

5 0.00E+00 3% 35 6.71E+03 21% 65 1.23E+04 39% 95 1.88E+04 58% 125 2.75E+04 76% 155 2.75E+04 76%

6 0.00E+00 3% 36 6.75E+03 22% 66 1.23E+04 40% 96 1.89E+04 58% 126 2.75E+04 77% 156 2.75E+04 77%

7 0.00E+00 4% 37 6.86E+03 22% 67 1.27E+04 41% 97 1.89E+04 59% 127 2.76E+04 77% 157 2.76E+04 77%

8 0.00E+00 5% 38 7.03E+03 23% 68 1.29E+04 41% 98 1.92E+04 59% 128 2.77E+04 78% 158 2.77E+04 78%

9 0.00E+00 5% 39 7.15E+03 23% 69 1.30E+04 42% 99 1.94E+04 60% 129 2.80E+04 78% 159 2.80E+04 78%

10 0.00E+00 6% 40 7.21E+03 24% 70 1.31E+04 42% 100 1.94E+04 61% 130 2.87E+04 79% 160 2.87E+04 79%

11 0.00E+00 6% 41 7.63E+03 25% 71 1.32E+04 43% 101 1.98E+04 61% 131 3.03E+04 80% 161 3.03E+04 80%

12 0.00E+00 7% 42 7.79E+03 25% 72 1.41E+04 44% 102 1.99E+04 62% 132 3.07E+04 80% 162 3.07E+04 80%

13 0.00E+00 8% 43 7.88E+03 26% 73 1.42E+04 44% 103 2.05E+04 63% 133 3.09E+04 81% 163 3.09E+04 81%

14 0.00E+00 8% 44 8.33E+03 27% 74 1.44E+04 45% 104 2.06E+04 63% 134 3.14E+04 81% 164 3.14E+04 81%

15 0.00E+00 9% 45 8.37E+03 27% 75 1.45E+04 45% 105 2.07E+04 64% 135 3.30E+04 82%

16 7.79E+02 9% 46 8.38E+03 28% 76 1.45E+04 46% 106 2.07E+04 64% 136 3.32E+04 83%

17 8.04E+02 10% 47 8.41E+03 28% 77 1.46E+04 47% 107 2.08E+04 65% 137 3.43E+04 83%

18 8.38E+02 11% 48 8.61E+03 29% 78 1.49E+04 47% 108 2.11E+04 66% 138 3.51E+04 84%

19 1.18E+03 11% 49 8.63E+03 30% 79 1.54E+04 48% 109 2.18E+04 66% 139 3.67E+04 84%

20 1.37E+03 12% 50 8.65E+03 30% 80 1.58E+04 48% 110 2.23E+04 67% 140 3.69E+04 85%

21 1.70E+03 13% 51 8.65E+03 31% 81 1.59E+04 49% 111 2.24E+04 67% 141 3.90E+04 86%

22 1.73E+03 13% 52 9.19E+03 31% 82 1.62E+04 50% 112 2.30E+04 68% 142 4.01E+04 86%

23 2.08E+03 14% 53 9.37E+03 32% 83 1.65E+04 50% 113 2.30E+04 69% 143 4.02E+04 87%

24 2.28E+03 14% 54 9.68E+03 33% 84 1.71E+04 51% 114 2.32E+04 69% 144 4.02E+04 88%

25 3.29E+03 15% 55 1.01E+04 33% 85 1.72E+04 52% 115 2.33E+04 70% 145 4.30E+04 88%

26 3.56E+03 16% 56 1.05E+04 34% 86 1.72E+04 52% 116 2.36E+04 70% 146 4.44E+04 89%

27 4.10E+03 16% 57 1.06E+04 34% 87 1.74E+04 53% 117 2.36E+04 71% 147 4.44E+04 89%

28 4.37E+03 17% 58 1.12E+04 35% 88 1.74E+04 53% 118 2.37E+04 72% 148 4.52E+04 90%

29 4.64E+03 17% 59 1.15E+04 36% 89 1.75E+04 54% 119 2.37E+04 72% 149 4.78E+04 91%

30 4.67E+03 18% 60 1.16E+04 36% 90 1.77E+04 55% 120 2.39E+04 73% 150 4.79E+04 91%

[178]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 HISTOGRAM FOR Eu-154 Survey Unit: 02100 Survey Unit Name: Unit 2 Containment Above 565 ft Mean: 2.82E+04 pCi/m2 Median: 1.64E+04 pCi/m2 ST DEV: 5.84E+05 Skew: 5.53E+00 Frequency Plot For Eu-154 160 140 120 Frequency 100 80 60 40 20 0

4.79E+04 1.44E+05 2.39E+05 3.35E+05 4.31E+05 Upper End Value (pCi/m2)

Upper Value Observation Observation Frequency  %

4.79E+04 149 91%

9.57E+04 9 5%

1.44E+05 0 0%

1.91E+05 2 1%

2.39E+05 1 1%

2.87E+05 0 0%

3.35E+05 0 0%

3.83E+05 2 1%

4.31E+05 0 0%

4.79E+05 1 1%

TOTAL 164 100%

[179]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 QUANTILE PLOT FOR Co-60 Survey Unit: 02110 Survey Unit Name: Unit 2 Under Vessel 2

Mean: 8.54E+05 pCi/m Quantile Plot For Co-60 5.00E+06 4.50E+06 4.00E+06 Concentration (pCi/m2) 3.50E+06 3.00E+06 2.50E+06 2.00E+06 1.50E+06 1.00E+06 5.00E+05 0.00E+00 0% 20% 40% 60% 80% 100%

Percentage RANK Co-60  % RANK Co-60  % RANK Co-60  %

1 1.82E+03 1% 19 4.96E+04 34% 37 5.68E+05 68%

2 6.27E+03 3% 20 6.45E+04 36% 38 6.12E+05 69%

3 8.35E+03 5% 21 8.73E+04 38% 39 6.14E+05 71%

4 9.48E+03 6% 22 1.03E+05 40% 40 6.90E+05 73%

5 1.02E+04 8% 23 1.03E+05 42% 41 1.00E+06 75%

6 1.39E+04 10% 24 2.06E+05 44% 42 1.01E+06 77%

7 1.42E+04 12% 25 2.09E+05 45% 43 1.08E+06 79%

8 1.62E+04 14% 26 2.45E+05 47% 44 1.24E+06 81%

9 1.68E+04 16% 27 2.70E+05 49% 45 1.66E+06 82%

10 1.89E+04 18% 28 3.05E+05 51% 46 1.67E+06 84%

11 2.07E+04 19% 29 3.16E+05 53% 47 2.88E+06 86%

12 2.11E+04 21% 30 3.29E+05 55% 48 3.32E+06 88%

13 2.15E+04 23% 31 3.60E+05 56% 49 3.40E+06 90%

14 2.22E+04 25% 32 4.51E+05 58% 50 3.47E+06 92%

15 2.58E+04 27% 33 4.72E+05 60% 51 4.00E+06 94%

16 2.68E+04 29% 34 4.74E+05 62% 52 4.37E+06 95%

17 2.86E+04 31% 35 5.28E+05 64% 53 4.48E+06 97%

18 4.54E+04 32% 36 5.45E+05 66% 54 4.60E+06 99%

[180]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 HISTOGRAM FOR Co-60 Survey Unit: 02110 Survey Unit Name: Unit 2 Under Vessel Mean: 8.54E+05 pCi/m2 Median: 2.87E+05 pCi/m2 ST DEV: 1.33E+06 Skew: 1.83E+00 Frequency Plot For Co-60 70%

60%

50%

Frequency 40%

30%

20%

10%

0%

4.61E+05 1.38E+06 2.30E+06 3.22E+06 4.14E+06 Upper End Value (pCi/m2)

Upper Value Observation Observation Frequency  %

4.61E+05 32 59%

9.21E+05 8 15%

1.38E+06 4 7%

1.84E+06 2 4%

2.30E+06 0 0%

2.76E+06 0 0%

3.22E+06 1 2%

3.68E+06 3 6%

4.14E+06 1 2%

4.60E+06 3 6%

TOTAL 54 100%

[181]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 QUANTILE PLOT FOR Cs-137 Survey Unit: 02110 Survey Unit Name: Unit 2 Under Vessel 2

Mean: 1.71E+06 pCi/m Quantile Plot For Cs-137 1.20E+07 1.00E+07 Concentration (pCi\m2) 8.00E+06 6.00E+06 4.00E+06 2.00E+06 0.00E+00 0% 20% 40% 60% 80% 100%

Percentage RANK Cs-137  % RANK Cs-137  % RANK Cs-137  %

1 2.00E+04 1% 19 2.61E+05 34% 37 2.15E+06 68%

2 2.25E+04 3% 20 2.64E+05 36% 38 2.17E+06 69%

3 2.63E+04 5% 21 3.27E+05 38% 39 2.26E+06 71%

4 3.14E+04 6% 22 4.20E+05 40% 40 2.33E+06 73%

5 3.40E+04 8% 23 4.75E+05 42% 41 2.59E+06 75%

6 7.09E+04 10% 24 5.34E+05 44% 42 2.71E+06 77%

7 9.25E+04 12% 25 5.89E+05 45% 43 3.09E+06 79%

8 9.28E+04 14% 26 6.35E+05 47% 44 3.60E+06 81%

9 9.30E+04 16% 27 6.79E+05 49% 45 4.11E+06 82%

10 1.48E+05 18% 28 7.07E+05 51% 46 4.12E+06 84%

11 1.68E+05 19% 29 7.90E+05 53% 47 4.14E+06 86%

12 2.03E+05 21% 30 8.27E+05 55% 48 4.18E+06 88%

13 2.04E+05 23% 31 8.43E+05 56% 49 4.29E+06 90%

14 2.04E+05 25% 32 1.07E+06 58% 50 4.48E+06 92%

15 2.24E+05 27% 33 1.11E+06 60% 51 4.52E+06 94%

16 2.30E+05 29% 34 1.28E+06 62% 52 5.29E+06 95%

17 2.35E+05 31% 35 1.71E+06 64% 53 8.28E+06 97%

18 2.44E+05 32% 36 1.91E+06 66% 54 1.11E+07 99%

[182]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 HISTOGRAM FOR Cs-137 Survey Unit: 02110 Survey Unit Name: Unit 2 Under Vessel Mean: 1.71E+06 pCi/m2 Median: 6.93E+05 pCi/m2 ST DEV: 2.23E+06 Skew: 2.14E+00 Frequency Plot For Cs-137 70%

60%

50%

Frequency 40%

30%

20%

10%

0%

1.14E+06 3.37E+06 5.59E+06 7.82E+06 1.01E+07 Upper End Value (pCi/m2)

Upper Value Observation Observation Frequency  %

1.14E+06 33 61%

2.25E+06 5 9%

3.37E+06 5 9%

4.48E+06 6 11%

5.59E+06 3 6%

6.71E+06 0 0%

7.82E+06 0 0%

8.94E+06 1 2%

1.01E+07 0 0%

1.12E+07 1 2%

TOTAL 54 100%

[183]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 QUANTILE PLOT FOR Eu-152 Survey Unit: 02110 Survey Unit Name: Unit 2 Under Vessel 2

Mean: 5.30E+06 pCi/m Quantile Plot For Eu-152 4.00E+07 3.50E+07 Concentration (pCi/m2) 3.00E+07 2.50E+07 2.00E+07 1.50E+07 1.00E+07 5.00E+06 0.00E+00 0% 20% 40% 60% 80% 100%

Percentage RANK Eu-152  % RANK Eu-152  % RANK Eu-152  %

1 0.00E+00 1% 19 9.16E+04 34% 37 2.81E+06 68%

2 0.00E+00 3% 20 1.20E+05 36% 38 3.39E+06 69%

3 0.00E+00 5% 21 1.35E+05 38% 39 3.68E+06 71%

4 0.00E+00 6% 22 1.82E+05 40% 40 3.74E+06 73%

5 1.64E+02 8% 23 2.03E+05 42% 41 4.39E+06 75%

6 5.39E+03 10% 24 6.24E+05 44% 42 5.05E+06 77%

7 5.70E+03 12% 25 7.99E+05 45% 43 6.71E+06 79%

8 1.68E+04 14% 26 8.30E+05 47% 44 6.83E+06 81%

9 1.81E+04 16% 27 1.05E+06 49% 45 8.75E+06 82%

10 2.93E+04 18% 28 1.34E+06 51% 46 9.32E+06 84%

11 3.07E+04 19% 29 1.66E+06 53% 47 1.90E+07 86%

12 3.53E+04 21% 30 1.83E+06 55% 48 2.10E+07 88%

13 4.05E+04 23% 31 1.84E+06 56% 49 2.13E+07 90%

14 4.56E+04 25% 32 2.04E+06 58% 50 2.33E+07 92%

15 4.76E+04 27% 33 2.10E+06 60% 51 2.50E+07 94%

16 5.23E+04 29% 34 2.12E+06 62% 52 2.97E+07 95%

17 5.25E+04 31% 35 2.30E+06 64% 53 3.30E+07 97%

18 6.21E+04 32% 36 2.41E+06 66% 54 3.71E+07 99%

[184]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 HISTOGRAM FOR Eu-152 Survey Unit: 02110 Survey Unit Name: Unit 2 Under Vessel Mean: 5.30E+06 pCi/m2 Median: 1.20E+06 pCi/m2 ST DEV: 9.36E+06 Skew: 2.11E+00 Frequency Plot For Eu-152 80%

70%

60%

Frequency 50%

40%

30%

20%

10%

0%

3.71E+06 1.11E+07 1.86E+07 2.60E+07 3.34E+07 Upper End Value (pCi/m2)

Upper Value Observation Observation Frequency  %

3.71E+06 39 72%

7.43E+06 5 9%

1.11E+07 2 4%

1.49E+07 0 0%

1.86E+07 0 0%

2.23E+07 3 6%

2.60E+07 2 4%

2.97E+07 0 0%

3.34E+07 2 4%

3.71E+07 1 2%

TOTAL 54 100%

[185]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 QUANTILE PLOT FOR Eu-154 Survey Unit: 02110 Survey Unit Name: Unit 2 Under Vessel 2

Mean: 3.46E+05 pCi/m Quantile Plot For Eu-154 1.60E+06 1.40E+06 1.20E+06 Concentration (pCi/m2) 1.00E+06 8.00E+05 6.00E+05 4.00E+05 2.00E+05 0.00E+00 0% 20% 40% 60% 80% 100%

Percentage RANK Eu-154  % RANK Eu-154  % RANK Eu-154  %

1 0.00E+00 1% 19 3.08E+04 34% 37 2.91E+05 68%

2 0.00E+00 3% 20 5.19E+04 36% 38 4.08E+05 69%

3 1.91E+03 5% 21 6.28E+04 38% 39 4.18E+05 71%

4 3.52E+03 6% 22 6.94E+04 40% 40 4.48E+05 73%

5 6.28E+03 8% 23 7.61E+04 42% 41 5.27E+05 75%

6 6.74E+03 10% 24 9.56E+04 44% 42 6.00E+05 77%

7 7.10E+03 12% 25 1.05E+05 45% 43 6.03E+05 79%

8 1.21E+04 14% 26 1.05E+05 47% 44 7.82E+05 81%

9 1.21E+04 16% 27 1.09E+05 49% 45 9.76E+05 82%

10 1.26E+04 18% 28 1.34E+05 51% 46 9.92E+05 84%

11 1.53E+04 19% 29 1.40E+05 53% 47 1.06E+06 86%

12 2.00E+04 21% 30 1.53E+05 55% 48 1.09E+06 88%

13 2.16E+04 23% 31 1.77E+05 56% 49 1.17E+06 90%

14 2.27E+04 25% 32 1.86E+05 58% 50 1.23E+06 92%

15 2.37E+04 27% 33 2.13E+05 60% 51 1.23E+06 94%

16 2.73E+04 29% 34 2.18E+05 62% 52 1.30E+06 95%

17 2.75E+04 31% 35 2.47E+05 64% 53 1.39E+06 97%

18 2.76E+04 32% 36 2.55E+05 66% 54 1.48E+06 99%

[186]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 HISTOGRAM FOR Eu-154 Survey Unit: 02110 Survey Unit Name: Unit 2 Under Vessel Mean: 3.46E+05 pCi/m2 Median: 1.21E+05 pCi/m2 ST DEV: 4.48E+05 Skew: 1.29E+00 Frequency Plot For Eu-154 60%

50%

40%

Frequency 30%

20%

10%

0%

1.48E+05 4.44E+05 7.40E+05 1.04E+06 1.33E+06 Upper End Value (pCi/m2)

Upper Value Observation Observation Frequency  %

1.48E+05 29 54%

2.96E+05 8 15%

4.44E+05 2 4%

5.92E+05 2 4%

7.40E+05 2 4%

8.88E+05 1 2%

1.04E+06 2 4%

1.18E+06 3 6%

1.33E+06 3 6%

1.48E+06 2 4%

TOTAL 54 100%

[187]

FSS RELEASE RECORD UNIT 2 CONTAINMENT BASEMENT SURVEY UNITS 02100 AND 02110 Retrospective Power Curve for Survey Unit

[188]

ATTACHMENT 6 ISOCS ANALYTICAL REPORTS (See Separate File for ISOCS Reports)

[189]

ATTACHMENT 7 EBERLINE REPORTS (See separate file for Eberline Analytical Reports)

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