ML21067A219

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Restoration Project, Final Status Survey Release Record Unit 1 Containment Incore Sump Discharge Pipe, Survey Unit 01111 (No. P125), Revision 1
ML21067A219
Person / Time
Site: Zion  File:ZionSolutions icon.png
Issue date: 02/10/2021
From: Yetter R
ZionSolutions
To:
Office of Nuclear Material Safety and Safeguards
Shared Package
ML21067A225 List:
References
ZS-2021-0001
Download: ML21067A219 (36)
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Text

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= ZIONSOLUTIONSLLC-An EnergySolutions Company ZION STATION RESTORATION PROJECT FINAL STATUS SURVEY RELEASE RECORD UNIT 1 CONTAINMENT INCORE SUMP DISCHARGE PIPE SURVEY UNIT 01111 (No. P125)

REVISION 1

FSS RELEASE RECORD REV. 1

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SURVEY UNIT 01111 (P125)

An E,-gySolutlona Company Robert F. Yetter III Nov 11 2020 11 :02 AM PREPARED BY / DATE: Robert Yetter III cosign Final Status Survey Specialist Robert F. Yetter 9lo..&,tt fJ. ~ Nov 11 2020 12:27 PM REVIEWED BY / DATE: Robert Yetter cosign Director, Radiological Site Closure Sarah Roberts Sarah Roberts Nov 1120201:05 PM cosign APPROVED BY / DATE: Sarah Roberts Vice President, Radiological Programs

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MEnergySdu6c,rn,Q:mpany TABLE OF CONTENTS

1. EXECUTIVE

SUMMARY

................................................................................................... 5

2. SURVEY UNIT DESCRIPTION ......................................................................................... 6
3. CLASSIFICATION BASIS .................................................................................................. 6
4. DATA QUALITY OBJECTIVES ........................................................................................ 6
5. SURVEY DESIGN ................................................................................................................. 9
6. SURVEY IMPLEMENTATION ........................................................................................ 14
7. SURVEY RESULTS ............................................................................................................ 15
8. QUALITY CONTROL........................................................................................................ 19
9. INVESTIGATIONS AND RESULTS................................................................................ 19
10. REMEDIATION AND RESULTS ..................................................................................... 19
11. CHANGES FROM THE SURVEY PLAN........................................................................ 19
12. DATA QUALITY ASSESSMENT ..................................................................................... 19
13. ANOMALIES ....................................................................................................................... 20
14. CONCLUSION .................................................................................................................... 20
15. REFERENCES..................................................................................................................... 20
16. ATTACHMENTS ................................................................................................................ 21 ATTACHMENT 1 - FIGURE 1 ............................................................................................. 22 ATTACHMENT 2 - SAMPLE DATA .................................................................................... 24 ATTACHMENT 3 - SIGN TEST ........................................................................................... 30 ATTACHMENT 4 - QC DATA ............................................................................................ 32 ATTACHMENT 5 - GRAPHICAL PRESENTATIONS ............................................................ 34 LIST OF TABLES Table 1 - Dose Significant Radionuclides and Mixture .................................................................... 8 Table 2 - Base Case and Operational DCGLs (pCi/m2) ................................................................... 9 Table 3 - Surrogate Ratios for Containment ..................................................................................... 9 Table 4 - Typical FSS Instrument Detection Sensitivities .............................................................. 12 Table 5 - Synopsis of Survey Design .............................................................................................. 13 Table 6 - Survey Data Collected ..................................................................................................... 15 Table 7 - Instrument and Detector .................................................................................................. 15 Table 8 - Unit 1 Incore Sump Discharge Pipe (P125) - Measurement Results .............................. 16 Table 9 - Unit 1 Incore Sump Discharge Pipe (P125) - Statistical Quantities - Systematic Measurement Population ................................................................................................. 17

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MEnergySdu6c,rn,Q:mpany LIST OF ACRONYMS AND ABBREVIATIONS ALARA As Low As Reasonably Achievable AMCG Average Member of the Critical Group CsI Cesium Iodide DQA Data Quality Assessment DQO Data Quality Objective DCGL Derived Concentration Guideline Level EMC Elevated Measurement Comparison FSS Final Status Survey HSA Historical Site Assessment IC Insignificant Contributor ID Internal Diameter LTP License Termination Plan MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual MDC Minimum Detectable Concentration OpDCGL Operational Derived Concentration Guideline Level OpSOF Operational Sum of Fraction QAPP Quality Assurance Project Plan QC Quality Control SOF Sum of Fractions TEDE Total Effective Dose Equivalent UCL Upper Confidence Level ZNPS Zion Nuclear Power Station ZSRP Zion Station Restoration Project

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MEnergySdu6c,rn,Q:mpany

1. EXECUTIVE

SUMMARY

This Final Status Survey (FSS) Release Record for survey unit 01111, Unit 1 Containment Incore Sump Discharge Pipe (No. P125) 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).

Final Status Survey Sample Plan S1-01111AF was 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).

Final Status Survey is conducted to demonstrate that the concentrations of residual radioactivity are equal to or below site-specific Derived Concentration Guideline Levels (DCGL) corresponding to the dose criterion in 10 CFR 20.1402. The Unit 1 Containment Incore Sump Discharge Pipe (P125) is classified as MARSSIM Class 1.

Measurements were collected at 1 foot intervals inside the pipe which has a 1.61 inch Internal Diameter (ID). The Ludlum 2350-1 Data Logger paired with a Ludlum Model 44-159 Cesium Iodide (CsI) gamma detector was selected to survey 26.74 linear feet with a surface area of 1.05 m2 to provide 100% coverage requirement for a Class 1 survey unit.

Due to an obstruction (90 degree elbow), 22 measurements were taken to achieve 100%

areal coverage of the accessible internal surface which equated to a surface area of 0.86 m2.

For the FSS of the Incore Sump Discharge Pipe, 22 readings were obtained. Twenty-one (21) readings were below a Sum of Fractions (SOF) of 1.0 when compared against the Operational DCGL for embedded pipe (OpDCGLEP) with a mean Operational SOF (OpSOF) of 0.363. Compared against the Base Case DCGL for embedded pipe (BcDCGLEP), the mean Base Case SOF (BcSOF) was 0.049, which equated to a dose of 1.221 mrem/yr.

With the exception of a single measurement, evaluation of the data showed that none of the remaining concentration values exceeded the OpDCGL for embedded pipe or any investigational level. The single measurement that exceeded the OpDCGLEP could exceed an OpSOF of one without remediation as long as the survey unit passed the Sign Test and, the mean OpSOF for the survey unit did not exceed one, which was the case in survey unit 01111. Therefore, the null hypothesis was rejected and the Unit 1 Containment Incore Sump Discharge Pipe (No. P125) survey unit 01111 was acceptable for unrestricted release.

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MEnergySdu6c,rn,Q:mpany

2. SURVEY UNIT DESCRIPTION The Unit 1 Containment Incore Sump Discharge Pipe is 1.61 inch ID embedded pipe located in the concrete of the Incore Access Tunnel in Unit 1 Containment. The incore area extends below the containment slab and consists of a cylindrical area directly under the reactor vessel biological shield and a sloped tunnel. The incore area walls are 1 foot, 11.5 inches thick (23.5 inches) with a 2 foot, 6 inch under vessel area floor thickness.

There is also an access tunnel with 15 inch thick walls, floor and roof. The sump is 2 ft. x 2 ft. x 2 ft. approximately 1 foot from the bend line. The pipe enters the wall at the floor above the sump making the opposite of the triangle 17 feet plus 9.5 feet or 22.5 feet. The base is 43 feet minus 30 feet and 9-inches making the hypotenuse length 25.74 feet, assuming the pipe enters the wall approximately 1 foot before sloping upward results in an estimated length of 26.74 feet (8.15 meters) and a 1.05 m2 surface area. Twenty-seven (27) measurements were planned to be taken but only 22 feet of the pipe was accessible for survey.

3. CLASSIFICATION BASIS Survey unit 01111 is the Unit 1 Incore Sump Discharge embedded pipe No. P125 was classified in accordance with ZionSolutions procedure ZS-LT-300-001-002, Survey Unit Classification (Reference 5).

Based on information from the Zion Station Historical Site Assessment (HSA),

(Reference 6), the Incore Sump Discharge Pipe is located in a Class 1 area. The Under Vessel Incore area was subjected to operational conditions as well as the exercising of the incore detectors. The Unit 1 Incore Sump Discharge Pipe contained radioactive material and was classified as a Class 1 system.

4. DATA QUALITY OBJECTIVES 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 will be 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

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MEnergySdu6c,rn,Q:mpany 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 unit 01111 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).

LTP Chapter 6, section 6.5.2 discusses the process used to derive the ROC for the decommissioning of ZSRP, including the elimination of insignificant dose contributors (IC) from the initial suite. In accordance with LTP Chapter 6, Table 6-2, the ROC for Containments include: H-3, Co-60, Ni-63, Sr-90, Cs-134, Cs-137, Eu-152 and Eu-154.

The residual radioactivity in embedded piping located below the 588 foot grade that will remain and be subjected to FSS is discussed in LTP Chapter 2, section 2.3.3.7 and TSD 14-016, Description of Embedded Piping, Penetrations, and Buried Pipe to Remain in Zion End State (Reference 7). The DCGLs for embedded piping are listed in LTP Chapter 5, sections 5.2.7 and 5.2.8.

For the Unit 1 Incore Sump Discharge Pipe (P125), the suite of ROC and radionuclide mixture derived for the Containment concrete was considered as a reasonable and conservative mixture to apply to the Unit 1 Incore Sump Discharge Pipe (P125) for FSS planning and implementation. Table 1 reproduces the ROC from LTP Chapter 5, Table 5-2.

Final Status Survey is conducted on the interior surfaces of embedded piping to demonstrate that the concentrations of residual activity are equal to or below DCGLs corresponding to the dose criterion in 10CFR20.1402 (DCGLEP). DCGLEP were calculated for each of the remaining embedded pipe systems. The DCGLEP values for the Unit 1 Incore Sump Discharge Pipe (P125) embedded pipe system from LTP Chapter 6, section 6.13 are referred to as Base Case DCGLs.

At Zion Nuclear Power Station (ZNPS), compliance is demonstrated through the summation of dose from four distinct source terms for the end-state (basements, soils, buried pipe and groundwater). Each radionuclide-specific Base Case DCGL 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).

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MEnergySdu6c,rn,Q:mpany Table 1 - Dose Significant Radionuclides and Mixture Containment Radionuclide  % of Total Activity (normalized)(1)

H-3 0.075%

Co-60 4.72%

Cs-134 0.01%

Cs-137 68.17%

Ni-63 26.50%

Sr-90 0.05%

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.

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 OpDCGLs derived for each dose component and the basis for the applied a priori dose fractions are provided in ZionSolutions TSD 17-004, Operational Derived Concentration Guideline Levels for Final Status Survey (Reference 8).

The Base Case and Operational DCGLs for the Incore Sump Discharge Pipe are listed in Tables 5-11 and 5-12 of the LTP and are reproduced in Table 2 below.

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MEnergySdu6c,rn,Q:mpany Table 2 - Base Case and Operational DCGLs (pCi/m2)

Base Case Operational Unit 1 & Unit 2 Unit 1 & Unit 2 Radionuclide Containment Incore Sump Containment Incore Sump Embedded Drain Pipe Embedded Drain Pipe H-3 8.28E+09 6.62E+08 Co-60 5.47E+09 4.38E+08 Ni-63 1.40E+11 1.12E+10 Sr-90 4.98E+07 3.98E+06 Cs-134 1.05E+09 8.40E+07 Cs-137 1.37E+09 1.10E+08 Eu-152 1.28E+10 1.02E+09 Eu-154 1.11E+10 8.88E+08

5. SURVEY DESIGN The level of effort associated with planning a survey is based on the complexity of the survey and nature of the hazards. Guidance for preparing FSS plans is provided in procedure ZS-LT-300-001-001 Final Status Survey Package Development.

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 unit 01111. 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 ZionSolutions TSD 14-019, Radionuclides of Concern for Soil and Basement Fill Model Source Terms (Reference 9) and are presented in LTP Table 5-15 and Table 3 below. The maximum ratios were to be used to infer HTD concentrations during FSS unless area specific ratios were determined.

Table 3 - Surrogate Ratios for Containment Containment Ratios Mean Max 95%UCL H-3/Cs-137 0.208 1.760 0.961 Ni-63/Co-60 30.623 442.317 193.910 Sr-90/Cs-137 0.002 0.021 0.010 Using the surrogate ratios in Table 3 and Equation 1 from LTP Chapter 5, section 5.2.11, an adjusted gross-gamma OpDCGL was calculated by applying the normalized gamma mixture for Eu-152, Eu-154, Cs-137, Cs-134 and Co-60, from Table 1.

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MEnergySdu6c,rn,Q:mpany For the FSS of survey unit 01111 (P125), the surrogate OpDCGLs for Co-60 and Cs-137 were computed using the maximum ratios from Table 3.

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 Using the OpDCGLs presented in Table 2 and the maximum ratios from Table 3, the following surrogate calculations were performed:

Equation 2 1

(60) = = 2.4007 /2 1 442

[( )+( )]

4.3808(060) 1.1210(63)

Equation 3 1

(137) = = 5.877 /2 1 1.76 0.021

[( )+( )+( )]

1.1008(137) 6.6208(3) 3.986(90)

The most limiting surrogate DCGL value was 2.40E+07 pCi/m2 (Co-60). A gross gamma activity DCGL was then calculated using Equation 4:

Equation 4 1

= f1 f2 fN

( + + )

DCGL1 DCGL2 DCGLN The normalized gamma mixture from Table 1 was applied to the surrogate OpDCGLs for the gamma-emitting nuclides as follows:

Equation 5 1

= = 5.407 /2 0.92874 0.06430 0.00013 0.0060 0.0008

( + + + + )

5.8707 2.4007 8.4007 1.0209 8.8808 A gross gamma OpDCGL of 5.40E+07 pCi/m2 was calculated as an action level for the FSS of survey unit 01111 (P125).

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MEnergySdu6c,rn,Q:mpany The Unit 1 Incore Sump Discharge Pipe (P125) is Class 1 embedded pipe. For the survey of pipe internal surfaces, areal coverage is achieved by the area of detection for each static measurement taken. Scanning, in the traditional context, is not applicable to the survey of pipe internal surfaces. For the survey of these pipes, the efficiency for the pipe detector was derived for the specific geometry of the 1.61-inch ID pipe.

The Unit 1 Incore Sump Discharge Pipe (P125) contains 26.74 linear feet of 1.61-inch ID piping, which equates to a surface area of 1.05 m2. The SeeSnakeTM camera was inserted 22 feet into the pipe. Because the entire length of the pipe was not accessible due to a 90 degree elbow, it was decided to take 22 measurements which equated to 0.86 m2 surface area. The LTP states that a FSS Class 1 survey unit shall have a minimum areal coverage of 100%. Therefore, one measurement was to be collected every 1 foot of piping traversed for a total of 22 distinct measurements over the entire accessible pathway of the piping system. For quality control (QC) purposes, a minimum of 5% of the measurements collected were to be replicated. Therefore, an additional 3 replicate measurements were collected throughout the length of the accessible surface of the piping system at locations selected at random.

Each static measurement represented the gamma activity in gross cpm for each specific measurement location. This gamma measurement value in cpm was then converted to dpm using an efficiency factor based on the calibration source in a comparable geometry.

The total activity in dpm was then adjusted for the assumed total effective surface area commensurate with the pipe/penetration diameter, resulting in measurement results in units of dpm per cm2. The total gamma surface activity for each FSS measurement was then converted to a gamma measurement result (in units of pCi/m2) for each gamma ROC based on the normalized gamma mixture from Table 1. Concentrations for HTD ROC were inferred using the surrogate approach presented earlier in this release record.

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 summation of the dose fractions for each ROC produces a SOF for the measurement.

To demonstrate that the survey unit satisfies the release criteria, the ROC concentration for each systematic measurement taken in the Unit 1 Incore Sump Discharge Pipe was divided by its applicable OpDCGLEP to derive a OpSOF for the ROC. The OpSOF for each ROC was then summed to determine the total OpSOF for all ROC that represents the measurement. The total OpSOF for each measurement was used as the summed value (Ws) for performing the Sign Test.

Embedded pipe survey units have a relatively small surface area, which results in OpDCGLs that are higher than the wall/floor OpDCGLs. The reason for this is that the

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MEnergySdu6c,rn,Q:mpany total internal surface area of the embedded pipe survey unit in a given basement is much less than the total wall/floor surface area of the basement containing them. To eliminate the potential for activity levels in embedded pipe that could lead to releases greater than surrounding walls and floors, the following remediation and grouting action levels were applied to measurements of surface activity in embedded pipe.

If maximum activity exceeds the BcDCGLEP from LTP Chapter 5, Table 5-11 (SOF

>1), then remediation was performed.

If the maximum activity in an embedded pipe exceeded the surface OpDCGLB from LTP Chapter 5, Table 5-4 in the building that contains it, but was below the BcDCGLEP from LTP Chapter 5, Table 5-11, then the embedded pipe was remediated or grouted.

If an embedded pipe was remediated and the maximum activity continues to exceed the surface OpDCGLB from LTP Chapter 5, Table 5-4, but is less than the Operational DCGLEP from LTP Chapter 5, Table 5-12, then the embedded pipe was grouted.

If the maximum activity was below the surface OpDCGLB from LTP Chapter 5, Table 5-4, then grouting of the pipe was not required.

The instrumentation used for the FSS of the Unit 1 Incore Sump Discharge Pipe (P125) was the Ludlum Model 2350-1 and the Model 44-159 detector. The typical instrumentation sensitivities are provided in Chapter 5 of the LTP and are reproduced below in Table 4.

Table 4 - Typical FSS Instrument Detection Sensitivities BKGD Typical Typical Count Static Instrument /Detector Radiation count time BKGD Instrument Time Scan MDC MDC (dpm/100 cm2)

(min.) (cpm) Efficiency(1)(2) (min.) 2 (dpm/100 cm )

Ludlum 2350-1/ 44-159 Gamma 1 700 0.024 I 1 I 5,250 (1) Typical calibration source used is Cs-137. The efficiency is determined by counting the source with the detector in a fixed N/A position from the source (reproducible geometry). The value is based on ISO-7503-1 and conditions noted for each detector.

(2) The efficiency varies for the pipe detectors depending on the pipe diameter used. The efficiency used for the table is the average efficiency value for the pipe diameters. The detectors and diameters are: Model 44-159: 2-4 in. dia., Model 44-157:

4-8 in. dia., Model 44-162: 8-12 in. diameter.

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.

In compliance with ZS-LT-01, Quality Assurance Project Plan (for Characterization and FSS) (Reference 10), replicate measurements were acquired at 5% of the static measurement locations.

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MEnergySdu6c,rn,Q:mpany Table 5 provides a synopsis of the survey design for the FSS of survey unit 01111.

Table 5 - Synopsis of Survey Design Feature Design Criteria Basis 1.61

[( )26.74]

Survey Unit Area 0.86 m2 12 /

10.76 2 /2 Number of Static 22 100% areal coverage, Class 1 Measurements Measurement One measurement every foot 100% areal coverage, Class 1 Spacing H 6.62E+08 Co 4.38E+08 Ni 1.12E+010 Operational DCGLs for Unit 1 Incore DCGLs Sr 3.98E+06 Sump Discharge Embedded Pipe (pCi/m2) Cs-134 - 8.40E+07 (P125), (LTP Chapter 5, Table 5-12)

Cs-137 - 1.10E+08 Eu-152 - 1.02E+09 Eu-154 - 8.88E+08 Gross Gamma DCGL adjusted for HTD ROC Analysis LTP 5.7.1.9 HTD based on the isotopic mixture Measurement

>Operational DCGLW (LTP Chapter 5, Table 5-25)

Investigation Level Scan Survey Area N/A LTP 5.7.1.9 Coverage replicate measurements will be QC performed on 5% of the static QAPP measurement locations

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MEnergySdu6c,rn,Q:mpany

6. SURVEY IMPLEMENTATION Survey instructions for this FSS were incorporated into and performed in accordance with FSS Sample Plan #S1-01111-AF, which was developed in accordance with ZionSolutions procedure ZS-LT-300-001-001, Final Status Survey Package Development. The FSS unit was inspected and controlled in accordance with ZionSolutions procedure ZS-LT-300-001-003, Isolation and Control for Final Status Survey (Reference 11).

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.

The approach used for the radiological survey of the interior surfaces of the P125 piping involved the insertion of a Ludlum Model 44-159 detector, a 1-inch x 1-inch CsI detector that was attached to the end of a fiber rod and transported through the pipe to the maximum deployment length, or to the location of an obstruction that prevented further insertion. A simple push-pull methodology was used, whereby the position of the detector in the piping system could be easily determined in a reproducible manner. Video footage was tabulated at 1-foot intervals while backing out of the pipe section.

A background value was also determined for the detector/instrument combination to be used prior to deployment. The background value was obtained at the location where the pre-use response check of the instrument was performed. The background value was primarily used to ensure that the detector had not become cross-contaminated by any previous use. Background was not subtracted from any measurement.

The detector was subjected to Pre and Post Operational Response Checks in accordance with procedure ZS-LT-300-001-006, Radiation Surveys of Pipe Interiors Using Sodium/Cesium Iodide Detectors (Reference 12). The Daily Operational Response Check compared the background response and the response to check source ranges established for normal background and detector source response to ensure that the detector was working properly.

Surveys of the Unit 1 Incore Sump Discharge Pipe (P125) were performed on 12/07/17.

The survey was completed in 1 day. The piping was accessed on the 565 foot elevation of Unit 1 Containment through the pipe opening at the top of the ladder going under-vessel.

The SeeSnakeTM camera was inserted 22 feet into the pipe. Because the entire length of the pipe was not accessible due to a 90 degree elbow, 22 measurements were taken at 1-foot intervals to obtain sufficient readings to achieve 100% areal coverage of the accessible internal surfaces of the pipe. Table 6 summarizes the data collected.

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MEnergySdu6c,rn,Q:mpany Table 6 - Survey Data Collected Length # of measurements Pipe run Comment surveyed taken P125 22 feet 22 3 QC readings taken The instrument and detector used for this survey are presented in Table 7. The instrument and detector were verified to be properly calibrated prior to use.

Table 7 - Instrument and Detector Instrument/Detect Calibration Due Serial #

or Type Date Ludlum 2350-1 304713 04/12/18 Ludlum 44-159 PR327895 04/12/18 Daily prior to use (Pre-Test) and daily upon completion of surveys (Post-Test), response checks were performed in accordance with procedure ZS-LT-300-001-006 for each detector and data logger pairing. In addition, all instruments and detectors were physically inspected for mechanical damage as part of the response check process. During the FSS, no instances were encountered where an instrument and/or detector failed a Pre or Post response check or were found to be physically damaged during the inspection.

7. SURVEY RESULTS After completion of the FSS measurements in the pipe, the sample plan was reviewed to confirm the completeness of the survey and the survey data was validated in accordance with procedure ZS-LT-300-001-004, Final Status Survey Data Assessment (Reference 13). Data processing includes converting measurement data into reporting units, validating instrument applicability and sensitivity, calculating relevant statistical quantities, and verification that all DQO have been met. In accordance with the procedure, a preliminary Data Assessment was prepared.

The primary gamma-emitting ROC for the FSS of the Unit 1 Incore Sump Discharge Pipe (P125) FSS unit are Co-60, Cs-134, Eu-152, Eu-154 and Cs-137. H-3, Ni-63 and Sr-90 are also ROC for the Unit 1 Incore Sump Discharge Pipe P125. Ni-63 is inferred from the measured concentration of Co-60, while Sr-90 and H-3 are inferred from the measured concentration of Cs-137. The results and resultant OpSOF for the measurements taken in the Unit 1 Incore Sump Discharge Pipe (P125) are presented in Table 8 below.

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U1 CONTAINMENT INCORE SUMP DISCHARGE PIPE = ZIONSOLUTIONS;:;;=

SURVEY UNIT 01111 (P125)

An Energy$olution.S Company Table 8 - Unit 1 Incore Sump Discharge Pipe (P125) - Measurement Results H-3 (1) Co-60 Ni-63 (1) Sr-90 (1) Cs-134 Cs-137 Eu-152 Eu-154 Measurement ID OpSOF (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)

S1-01111AF-SSM-001-GD 5.12E+08 2.01E+07 8.90E+09 6.11E+06 4.26E+04 2.91E+08 1.88E+06 2.56E+05 5.793 S1-01111AF-SSM-002-GD 7.75E+07 3.05E+06 1.35E+09 9.24E+05 6.46E+03 4.40E+07 2.84E+05 3.87E+04 0.877 S1-01111AF-SSM-003-GD 1.63E+07 6.42E+05 2.84E+08 1.95E+05 1.36E+03 9.27E+06 5.98E+04 8.16E+03 0.185 S1-01111AF-SSM-004-GD 7.28E+06 2.86E+05 1.27E+08 8.69E+04 6.07E+02 4.14E+06 2.67E+04 3.64E+03 0.082 S1-01111AF-SSM-005-GD 7.13E+06 2.81E+05 1.24E+08 8.51E+04 5.95E+02 4.05E+06 2.62E+04 3.57E+03 0.081 S1-01111AF-SSM-006-GD 5.65E+06 2.22E+05 9.82E+07 6.74E+04 4.71E+02 3.21E+06 2.07E+04 2.82E+03 0.064 S1-01111AF-SSM-007-GD 5.63E+06 2.22E+05 9.79E+07 6.72E+04 4.69E+02 3.20E+06 2.07E+04 2.82E+03 0.064 S1-01111AF-SSM-008-GD 5.36E+06 2.11E+05 9.32E+07 6.40E+04 4.47E+02 3.05E+06 1.97E+04 2.68E+03 0.061 S1-01111AF-SSM-009-GD 4.84E+06 1.90E+05 8.41E+07 5.77E+04 4.03E+02 2.75E+06 1.77E+04 2.42E+03 0.055 S1-01111AF-SSM-010-GD 4.17E+06 1.64E+05 7.25E+07 4.98E+04 3.48E+02 2.37E+06 1.53E+04 2.09E+03 0.047 S1-01111AF-SSM-011-GD 4.64E+06 1.83E+05 8.07E+07 5.54E+04 3.87E+02 2.64E+06 1.70E+04 2.32E+03 0.053 S1-01111AF-SSM-012-GD 3.89E+06 1.53E+05 6.76E+07 4.64E+04 3.24E+02 2.21E+06 1.43E+04 1.95E+03 0.044 S1-01111AF-SSM-013-GD 3.44E+06 1.35E+05 5.98E+07 4.10E+04 2.86E+02 1.95E+06 1.26E+04 1.72E+03 0.039 S1-01111AF-SSM-014-GD 3.39E+06 1.33E+05 5.90E+07 4.05E+04 2.83E+02 1.93E+06 1.24E+04 1.70E+03 0.038 S1-01111AF-SSM-015-GD 2.94E+06 1.16E+05 5.12E+07 3.51E+04 2.45E+02 1.67E+06 1.08E+04 1.47E+03 0.033 S1-01111AF-SSM-016-GD 2.99E+06 1.18E+05 5.20E+07 3.56E+04 2.49E+02 1.70E+06 1.10E+04 1.49E+03 0.034 S1-01111AF-SSM-017-GD 3.64E+06 1.43E+05 6.33E+07 4.35E+04 3.04E+02 2.07E+06 1.34E+04 1.82E+03 0.041 S1-01111AF-SSM-018-GD 4.01E+06 1.58E+05 6.97E+07 4.78E+04 3.34E+02 2.28E+06 1.47E+04 2.01E+03 0.045 S1-01111AF-SSM-019-GD 4.68E+06 1.84E+05 8.14E+07 5.58E+04 3.90E+02 2.66E+06 1.72E+04 2.34E+03 0.053 S1-01111AF-SSM-020-GD 3.86E+06 1.52E+05 6.71E+07 4.60E+04 3.22E+02 2.19E+06 1.41E+04 1.93E+03 0.044 S1-01111AF-SSM-021-GD 4.77E+06 1.87E+05 8.29E+07 5.69E+04 3.97E+02 2.71E+06 1.75E+04 2.38E+03 0.054 S1-01111AF-SSM-022-GD 1.75E+07 6.88E+05 3.04E+08 2.09E+05 1.46E+03 9.94E+06 6.41E+04 8.75E+03 0.198 (1) Concentrations for H-3, Ni-63 and Sr-90 are inferred based on the maximum ratios from LTP Chapter 5, Table 5-12

[16]

FSS RELEASE RECORD - REV. 1

~

U1 CONTAINMENT INCORE SUMP DISCHARGE PIPE = ZIONSOLUTIONS;:;;=

SURVEY UNIT 01111 (P125)

An Energy$olution.S Company Table 9 - Unit 1 Incore Sump Discharge Pipe (P125) - Statistical Quantities - Systematic Measurement Population Individual Measurement Metrics Total Number of Systematic Measurements = 22 Number of Quality Control Measurements = 3 Number of Judgmental/Investigational Measurements = 0 Total Number of Measurements = 25 Mean Systematic Measurement OpSOF = 0.363 Max Individual Systematic Measurement OpSOF = 5.793 Number of Systematic Measurements with OpSOF >1 = 1 Statistical Quantities - Systematic Measurement Population MEAN MEDIAN MAX MIN BcDCGL Avg Dose Avg SOF ROC per ROC (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) per ROC (mrem/yr)

H-3 3.21E+07 4.72E+06 5.12E+08 2.94E+06 1.08E+08 8.28E+09 0.004 0.097 Co-60 1.26E+06 1.86E+05 2.01E+07 1.16E+05 4.26E+06 5.47E+09 0.000 0.006 Ni-63 5.57E+08 8.21E+07 8.90E+09 5.12E+07 1.88E+09 1.40E+11 0.004 0.100 Sr-90 3.83E+05 5.63E+04 6.11E+06 3.51E+04 1.29E+06 4.98E+07 0.008 0.192 Cs-134 2.67E+03 3.94E+02 4.26E+04 2.45E+02 9.02E+03 1.05E+09 0.000 0.000 Cs-137 1.82E+07 2.68E+06 2.91E+08 1.67E+06 6.15E+07 1.37E+09 0.013 0.332 Eu-152 1.18E+05 1.73E+04 1.88E+06 1.08E+04 3.97E+05 1.28E+10 0.000 0.000 Eu-154 1.60E+04 2.36E+03 2.56E+05 1.47E+03 5.41E+04 1.11E+10 0.000 0.000 BASE CASE SOF (BcSOF) ASSIGNED TO SURVEY UNIT (SYSTEMATIC AVG.) = 0.029

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FSS RELEASE RECORD - REV. 1

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U1 CONTAINMENT INCORE SUMP DISCHARGE PIPE = ZIONSOLUTIONS;;;:=

SURVEY UNIT 01111 (P125)

MEnergySdu6c,rn,Q:mpany Twenty-one (21) of the 22 measurements had an OpSOF that was less than one. The mean OpSOF for all 22 samples was 0.363. One measurement exceeded the OpDCGLEP but was less than the BcDCGLEP. The OpSOF for a measurement may 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. The data collected passed the Sign Test (using OpDCGLs). The result of the Sign Test is provided in Attachment 3. Once the survey data set passed the Sign Test, the mean radionuclide activity (pCi/m2) for each ROC from the systematic measurements along with the identified single elevated measurement were compared against the BcDCGLs and an adjusted SOF was calculated in accordance with the following equation. Through the implementation of this equation (Equation 5 is a reproduction of Equation 5-6 from LTP Chapter 5, section 5.5.5), the mean BcSOF for the survey unit was adjusted by adding the SOF contribution from the elevated area to the mean to account for the additional dose.

Equation 6

/ ( / / )

/ = +

/

=1 [/ x ( )]

where:

SOFEP/PN = SOF for embedded pipe or penetration survey unit within a basement using BcDCGLs Mean ConcEP/PN ROCi = Mean concentration for the systematic measurements taken during the FSS of embedded pipe or penetrations in survey unit for each ROCi BcDCGLEP/PN ROCi = BcDCGL for embedded pipe or penetration for each ROCi Elev ConcEP/PN ROCi = Concentration for ROCi in any identified elevated area (systematic or judgmental)

SAElev = surface area of the elevated area SASU = surface area of FSS unit The surface area of the accessible portion of the pipe (SASU) is 0.86 m2. The surface area of the elevated area is 0.036 m2. The adjustment made to the mean BcSOF due to the one elevated measurement was 0.020.

The activity in this pipe was also compared to the OpDCGLB for the building in which it resides. According to Table 5-20 of the LTP, the Unit 1 Incore Sump Discharge Pipe (P125) will be included with the Unit 1 Containment. The results of this comparison show

[18]

FSS RELEASE RECORD - REV. 1

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U1 CONTAINMENT INCORE SUMP DISCHARGE PIPE = ZIONSOLUTIONS;;;:=

SURVEY UNIT 01111 (P125)

MEnergySdu6c,rn,Q:mpany that thirteen (13) measurements were greater than a SOF of 1 when compared to the OpDCGLB for the Unit 1 Containment Building. The pipe was grouted accordingly.

The SOF adjustment for the elevated measurement equaled 0.020. This value is then added to the mean SOF for the Unit 1 Incore Sump Discharge Pipe (P125) FSS unit of 0.029, resulting in an adjusted total mean BcSOF for the Unit 1 Incore Sump Discharge Pipe (P125) of 0.049. This SOF equates to a dose of 1.221 mrem/yr. This value is the dose assigned to the survey unit based on the average of the systematic measurements adjusted for the dose contribution of the identified elevated area.

8. QUALITY CONTROL In compliance with ZS-LT-01, Quality Assurance Project Plan (for Characterization and FSS), (QAPP) replicate measurements were performed on 5% of the survey locations chosen at random. Three (3) replicate measurements were taken. Using the acceptance criteria specified in section 4.1.2 of ZS-LT-01, there was acceptable agreement between the replicate readings and the original readings. Refer to Attachment 4 for QC analysis results.
9. INVESTIGATIONS AND RESULTS No investigations were required or performed.
10. REMEDIATION AND RESULTS No remediation was performed in this pipe.
11. CHANGES FROM THE SURVEY PLAN The actual configuration of the pipe was different than the drawings used to perform survey design. This fact was not discovered until the survey commenced. In actuality, the actual length of the pipe was 23 feet. There was one foot of pipe (1 measurement) that was not acquired as it was located on a 90 degree elbow. Only 22 feet of the piping was accessible for survey. Measurements were taken at one (1) foot intervals in the pipe to achieve 100% coverage of accessible internal surfaces.

The survey instructions called for a 44-157 detector to be used for the survey. This was a typographical error in the sample plan as the smaller 44-159 detector was used instead.

12. DATA QUALITY ASSESSMENT (DQA)

In accordance with procedure ZS-LT-300-001-004, the DQOs, sample design, and data were reviewed for completeness, accuracy and consistency. Documentation was complete and legible. The FSS unit was properly classified as Class 1. All measurement results were individually reviewed and validated. The number of measurements was sufficient to

[19]

FSS RELEASE RECORD - REV. 1

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U1 CONTAINMENT INCORE SUMP DISCHARGE PIPE = ZIONSOLUTIONS;;;:=

SURVEY UNIT 01111 (P125)

MEnergySdu6c,rn,Q:mpany meet the requirement of 100% areal coverage of accessible surfaces. The instrumentation used to perform the FSS was in calibration, capable of detecting the activity with an adequate minimum detectable concentration (MDC) and successfully response checked prior to and following use. An adequate number of replicate measurements were taken and the results met the acceptance criteria as specified in the QAPP.

The data for Gross Gamma Activity 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. CONCLUSION Twenty-two (22) static measurements were taken in the Unit 1 Incore Sump Discharge Pipe (P125), at 1-foot intervals. The accessible length of pipe was 22 feet; therefore 100%

areal survey coverage was achieved.

The Sign Test was passed, and the Null Hypothesis was rejected. Twenty-one (21) of the 22 measurements had an OpSOF that was less than one. The mean OpSOF for all 22 samples was 0.363. One measurement exceeded the exceeded the OpDCGLEP but was less than the BcDCGLEP. The SOF adjustment for the elevated measurement equals 0.020. This value is then added to the mean BcSOF for the Unit 1 Incore Sump Discharge Pipe (P125) FSS unit of 0.029 resulting in an adjusted total SOF for the Unit 1 Incore Sump Discharge Pipe (P125) of 0.049. This SOF equates to a dose of 1.221 mrem/yr.

Survey unit 01111 is acceptable for unrestricted release.

15. 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 procedure ZS-LT-300-001-002, Survey Unit Classification
6. Zion Station Historical Site Assessment
7. ZionSolutions TSD 14-016, Description of Embedded Piping, Penetrations, and Buried Pipe to Remain in Zion End State

[20]

FSS RELEASE RECORD - REV. 1

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U1 CONTAINMENT INCORE SUMP DISCHARGE PIPE = ZIONSOLUTIONS;;;:=

SURVEY UNIT 01111 (P125)

MEnergySdu6c,rn,Q:mpany

8. ZionSolutions TSD 17-004, Operational Derived Concentration Guideline Levels for Final Status Survey
9. ZionSolutions TSD 14-019 Radionuclides of Concern for Soil and Basement Fill Model Source Terms
10. ZionSolutions procedure ZS-LT-01, Quality Assurance Project Plan (for Characterization and FSS)
11. ZionSolutions procedure ZS-LT-300-001-003, Isolation and Control for Final Status Survey
12. ZionSolutions procedure ZS-LT-300-001-006, Radiation Surveys of Pipe Interiors Using Sodium/Cesium Iodide Detectors
13. ZionSolutions procedure ZS-LT-300-001-004, Final Status Survey Data Assessment
16. ATTACHMENTS Attachment 1 - Figure 1 Attachment 2 - Sample Data Attachment 3 - Sign Test Attachment 4 - QC Data Attachment 5 - Graphical Presentations

[21]

ATTACHMENT 1 FIGURE 1

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FSS RELEASE RECORD - REV. 1

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U1 CONTAINMENT INCORE SUMP DISCHARGE PIPE = ZIONSOLUTIONS;:;;=

SURVEY UNIT 01111 (P125)

An Eni,rgySolufic,n,s Campany FIGURE 1

- ~ ~ - .J-@-- +---- - - -- - - - ~ ;.,,; ----,:;=======:cl

....,J:=====::::;:::==I=======:--:: 43*3* - - - - - - - - , - --------1

... * - :c..

~l"l\\,S,c::, ... ~ ..... , ur-*

  • [loT 0 ,,. ~"'"'"' u.. Si1 f'J,"

~-- 1t&.r**.,. (6.- 41 k J

- - -- ">.r:i_**- ='-'- - - - - -- -

~

ZION SOLUTIONS Not to Scale Survey Unit S1-01111 Containment Unit 1 1" pipe (P125)

Date: 11/02/2017

[23]

ATTACHMENT 2 - SAMPLE DATA

[24]

FSS RELEASE RECORD - REV. 1

~

U1 CONTAINMENT INCORE SUMP DISCHARGE PIPE = ZIONSOLUTIONS;:;;=

SURVEY UNIT 01111 (P125)

An Eni,rgySolufic,n,s Campany Unit 1 Incore Sump Discharge Pipe (embedded - 1.5 in diameter)

Feet Gamma Gamma Activity per CTMT CTMT Nuclide Nuclide Sample ID into Result ROC Mixture/HTD ROC OpDCGLEP OpSOFEP BcDCGLEP BcSOF BcSOFEP OpSOF Pipe (pCi/m2) Ratio (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)

H-3 1.76 5.12E+08 6.62E+08 0.773 8.28E+09 0.062 Co-60 0.06431 2.01E+07 4.38E+08 0.046 5.47E+09 0.004 Ni-63 442.00 8.90E+09 1.12E+10 0.794 1.40E+11 0.064 Sr-90 0.021 6.11E+06 3.98E+06 1.534 4.98E+07 0.123 S1-01111AF-SSM-001-GD 0 3.13E+08 5.793 0.464 Cs-134 0.00014 4.26E+04 8.40E+07 0.001 1.05E+09 0.000 Cs-137 0.92875 2.91E+08 1.10E+08 2.643 1.37E+09 0.212 Eu-152 0.00599 1.88E+06 1.02E+09 0.002 1.28E+10 0.000 Eu-154 0.00082 2.56E+05 8.88E+08 0.000 1.11E+10 0.000 H-3 1.76 7.75E+07 6.62E+08 0.117 8.28E+09 0.009 Co-60 0.06431 3.05E+06 4.38E+08 0.007 5.47E+09 0.001 Ni-63 442.00 1.35E+09 1.12E+10 0.120 1.40E+11 0.010 Sr-90 0.021 9.24E+05 3.98E+06 0.232 4.98E+07 0.019 S1-01111AF-SSM-002-GD 1 4.74E+07 0.877 0.070 Cs-134 0.00014 6.46E+03 8.40E+07 0.000 1.05E+09 0.000 Cs-137 0.92875 4.40E+07 1.10E+08 0.400 1.37E+09 0.032 Eu-152 0.00599 2.84E+05 1.02E+09 0.000 1.28E+10 0.000 Eu-154 0.00082 3.87E+04 8.88E+08 0.000 1.11E+10 0.000 H-3 1.76 1.63E+07 6.62E+08 0.025 8.28E+09 0.002 Co-60 0.06431 6.42E+05 4.38E+08 0.001 5.47E+09 0.000 Ni-63 442.00 2.84E+08 1.12E+10 0.025 1.40E+11 0.002 Sr-90 0.021 1.95E+05 3.98E+06 0.049 4.98E+07 0.004 S1-01111AF-SSM-003-GD 2 9.98E+06 0.185 0.015 Cs-134 0.00014 1.36E+03 8.40E+07 0.000 1.05E+09 0.000 Cs-137 0.92875 9.27E+06 1.10E+08 0.084 1.37E+09 0.007 Eu-152 0.00599 5.98E+04 1.02E+09 0.000 1.28E+10 0.000 Eu-154 0.00082 8.16E+03 8.88E+08 0.000 1.11E+10 0.000 H-3 1.76 7.28E+06 6.62E+08 0.011 8.28E+09 0.001 Co-60 0.06431 2.86E+05 4.38E+08 0.001 5.47E+09 0.000 Ni-63 442.00 1.27E+08 1.12E+10 0.011 1.40E+11 0.001 Sr-90 0.021 8.69E+04 3.98E+06 0.022 4.98E+07 0.002 S1-01111AF-SSM-004-GD 3 4.45E+06 0.082 0.007 Cs-134 0.00014 6.07E+02 8.40E+07 0.000 1.05E+09 0.000 Cs-137 0.92875 4.14E+06 1.10E+08 0.038 1.37E+09 0.003 Eu-152 0.00599 2.67E+04 1.02E+09 0.000 1.28E+10 0.000 Eu-154 0.00082 3.64E+03 8.88E+08 0.000 1.11E+10 0.000 H-3 1.76 7.13E+06 6.62E+08 0.011 8.28E+09 0.001 Co-60 0.06431 2.81E+05 4.38E+08 0.001 5.47E+09 0.000 Ni-63 442.00 1.24E+08 1.12E+10 0.011 1.40E+11 0.001 Sr-90 0.021 8.51E+04 3.98E+06 0.021 4.98E+07 0.002 S1-01111AF-SSM-005-GD 4 4.36E+06 0.081 0.006 Cs-134 0.00014 5.95E+02 8.40E+07 0.000 1.05E+09 0.000 Cs-137 0.92875 4.05E+06 1.10E+08 0.037 1.37E+09 0.003 Eu-152 0.00599 2.62E+04 1.02E+09 0.000 1.28E+10 0.000 Eu-154 0.00082 3.57E+03 8.88E+08 0.000 1.11E+10 0.000

[25]

FSS RELEASE RECORD - REV. 1

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U1 CONTAINMENT INCORE SUMP DISCHARGE PIPE = ZIONSOLUTIONS;:;;=

SURVEY UNIT 01111 (P125)

An Eni,rgySolufic,n,s Campany Unit 1 Incore Sump Discharge Pipe (embedded - 1.5 in diameter) (continued)

Feet Gamma Gamma Activity per CTMT CTMT Nuclide Nuclide Sample ID into Result ROC Mixture/HTD ROC OpDCGLEP OpSOFEP BcDCGLEP BcSOF BcSOFEP OpSOF Pipe (pCi/m2) Ratio (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)

H-3 1.76 5.65E+06 6.62E+08 0.009 8.28E+09 0.001 Co-60 0.06431 2.22E+05 4.38E+08 0.001 5.47E+09 0.000 Ni-63 442.00 9.82E+07 1.12E+10 0.009 1.40E+11 0.001 Sr-90 0.021 6.74E+04 3.98E+06 0.017 4.98E+07 0.001 S1-01111AF-SSM-006-GD 5 3.45E+06 0.064 0.005 Cs-134 0.00014 4.71E+02 8.40E+07 0.000 1.05E+09 0.000 Cs-137 0.92875 3.21E+06 1.10E+08 0.029 1.37E+09 0.002 Eu-152 0.00599 2.07E+04 1.02E+09 0.000 1.28E+10 0.000 Eu-154 0.00082 2.82E+03 8.88E+08 0.000 1.11E+10 0.000 H-3 1.76 5.63E+06 6.62E+08 0.009 8.28E+09 0.001 Co-60 0.06431 2.22E+05 4.38E+08 0.001 5.47E+09 0.000 Ni-63 442.00 9.79E+07 1.12E+10 0.009 1.40E+11 0.001 Sr-90 0.021 6.72E+04 3.98E+06 0.017 4.98E+07 0.001 S1-01111AF-SSM-007-GD 6 3.45E+06 0.064 0.005 Cs-134 0.00014 4.69E+02 8.40E+07 0.000 1.05E+09 0.000 Cs-137 0.92875 3.20E+06 1.10E+08 0.029 1.37E+09 0.002 Eu-152 0.00599 2.07E+04 1.02E+09 0.000 1.28E+10 0.000 Eu-154 0.00082 2.82E+03 8.88E+08 0.000 1.11E+10 0.000 H-3 1.76 5.36E+06 6.62E+08 0.008 8.28E+09 0.001 Co-60 0.06431 2.11E+05 4.38E+08 0.000 5.47E+09 0.000 Ni-63 442.00 9.32E+07 1.12E+10 0.008 1.40E+11 0.001 Sr-90 0.021 6.40E+04 3.98E+06 0.016 4.98E+07 0.001 S1-01111AF-SSM-008-GD 7 3.28E+06 0.061 0.005 Cs-134 0.00014 4.47E+02 8.40E+07 0.000 1.05E+09 0.000 Cs-137 0.92875 3.05E+06 1.10E+08 0.028 1.37E+09 0.002 Eu-152 0.00599 1.97E+04 1.02E+09 0.000 1.28E+10 0.000 Eu-154 0.00082 2.68E+03 8.88E+08 0.000 1.11E+10 0.000 H-3 1.76 4.84E+06 6.62E+08 0.007 8.28E+09 0.001 Co-60 0.06431 1.90E+05 4.38E+08 0.000 5.47E+09 0.000 Ni-63 442.00 8.41E+07 1.12E+10 0.008 1.40E+11 0.001 Sr-90 0.021 5.77E+04 3.98E+06 0.015 4.98E+07 0.001 S1-01111AF-SSM-009-GD 8 2.96E+06 0.055 0.004 Cs-134 0.00014 4.03E+02 8.40E+07 0.000 1.05E+09 0.000 Cs-137 0.92875 2.75E+06 1.10E+08 0.025 1.37E+09 0.002 Eu-152 0.00599 1.77E+04 1.02E+09 0.000 1.28E+10 0.000 Eu-154 0.00082 2.42E+03 8.88E+08 0.000 1.11E+10 0.000 H-3 1.76 4.17E+06 6.62E+08 0.006 8.28E+09 0.001 Co-60 0.06431 1.64E+05 4.38E+08 0.000 5.47E+09 0.000 Ni-63 442.00 7.25E+07 1.12E+10 0.006 1.40E+11 0.001 Sr-90 0.021 4.98E+04 3.98E+06 0.013 4.98E+07 0.001 S1-01111AF-SSM-010-GD 9 2.55E+06 0.047 0.004 Cs-134 0.00014 3.48E+02 8.40E+07 0.000 1.05E+09 0.000 Cs-137 0.92875 2.37E+06 1.10E+08 0.022 1.37E+09 0.002 Eu-152 0.00599 1.53E+04 1.02E+09 0.000 1.28E+10 0.000 Eu-154 0.00082 2.09E+03 8.88E+08 0.000 1.11E+10 0.000

[26]

FSS RELEASE RECORD - REV. 1

~

U1 CONTAINMENT INCORE SUMP DISCHARGE PIPE = ZIONSOLUTIONS;:;;=

SURVEY UNIT 01111 (P125)

An Eni,rgySolufic,n,s Campany Unit 1 Incore Sump Discharge Pipe (embedded - 1.5 in diameter) (continued)

Feet Gamma Gamma Activity per CTMT CTMT Nuclide Nuclide Sample ID into Result ROC Mixture/HTD ROC OpDCGLEP OpSOFEP BcDCGLEP BcSOF BcSOFEP OpSOF Pipe (pCi/m2) Ratio (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)

H-3 1.76 4.64E+06 6.62E+08 0.007 8.28E+09 4.64E+06 Co-60 0.06431 1.83E+05 4.38E+08 0.000 5.47E+09 1.83E+05 Ni-63 442.00 8.07E+07 1.12E+10 0.007 1.40E+11 8.07E+07 Sr-90 0.021 5.54E+04 3.98E+06 0.014 4.98E+07 5.54E+04 S1-01111AF-SSM-011-GD 10 2.84E+06 0.053 0.004 Cs-134 0.00014 3.87E+02 8.40E+07 0.000 1.05E+09 3.87E+02 Cs-137 0.92875 2.64E+06 1.10E+08 0.024 1.37E+09 2.64E+06 Eu-152 0.00599 1.70E+04 1.02E+09 0.000 1.28E+10 1.70E+04 Eu-154 0.00082 2.32E+03 8.88E+08 0.000 1.11E+10 2.32E+03 H-3 1.76 3.89E+06 6.62E+08 0.006 8.28E+09 3.89E+06 Co-60 0.06431 1.53E+05 4.38E+08 0.000 5.47E+09 1.53E+05 Ni-63 442.00 6.76E+07 1.12E+10 0.006 1.40E+11 6.76E+07 Sr-90 0.021 4.64E+04 3.98E+06 0.012 4.98E+07 4.64E+04 S1-01111AF-SSM-012-GD 11 2.38E+06 0.044 0.004 Cs-134 0.00014 3.24E+02 8.40E+07 0.000 1.05E+09 3.24E+02 Cs-137 0.92875 2.21E+06 1.10E+08 0.020 1.37E+09 2.21E+06 Eu-152 0.00599 1.43E+04 1.02E+09 0.000 1.28E+10 1.43E+04 Eu-154 0.00082 1.95E+03 8.88E+08 0.000 1.11E+10 1.95E+03 H-3 1.76 3.44E+06 6.62E+08 0.005 8.28E+09 3.44E+06 Co-60 0.06431 1.35E+05 4.38E+08 0.000 5.47E+09 1.35E+05 Ni-63 442.00 5.98E+07 1.12E+10 0.005 1.40E+11 5.98E+07 Sr-90 0.021 4.10E+04 3.98E+06 0.010 4.98E+07 4.10E+04 S1-01111AF-SSM-013-GD 12 2.10E+06 0.039 0.003 Cs-134 0.00014 2.86E+02 8.40E+07 0.000 1.05E+09 2.86E+02 Cs-137 0.92875 1.95E+06 1.10E+08 0.018 1.37E+09 1.95E+06 Eu-152 0.00599 1.26E+04 1.02E+09 0.000 1.28E+10 1.26E+04 Eu-154 0.00082 1.72E+03 8.88E+08 0.000 1.11E+10 1.72E+03 H-3 1.76 3.39E+06 6.62E+08 0.005 8.28E+09 3.39E+06 Co-60 0.06431 1.33E+05 4.38E+08 0.000 5.47E+09 1.33E+05 Ni-63 442.00 5.90E+07 1.12E+10 0.005 1.40E+11 5.90E+07 Sr-90 0.021 4.05E+04 3.98E+06 0.010 4.98E+07 4.05E+04 S1-01111AF-SSM-014-GD 13 2.07E+06 0.038 0.003 Cs-134 0.00014 2.83E+02 8.40E+07 0.000 1.05E+09 2.83E+02 Cs-137 0.92875 1.93E+06 1.10E+08 0.018 1.37E+09 1.93E+06 Eu-152 0.00599 1.24E+04 1.02E+09 0.000 1.28E+10 1.24E+04 Eu-154 0.00082 1.70E+03 8.88E+08 0.000 1.11E+10 1.70E+03 H-3 1.76 2.94E+06 6.62E+08 0.004 8.28E+09 2.94E+06 Co-60 0.06431 1.16E+05 4.38E+08 0.000 5.47E+09 1.16E+05 Ni-63 442.00 5.12E+07 1.12E+10 0.005 1.40E+11 5.12E+07 Sr-90 0.021 3.51E+04 3.98E+06 0.009 4.98E+07 3.51E+04 S1-01111AF-SSM-015-GD 14 1.80E+06 0.033 0.003 Cs-134 0.00014 2.45E+02 8.40E+07 0.000 1.05E+09 2.45E+02 Cs-137 0.92875 1.67E+06 1.10E+08 0.015 1.37E+09 1.67E+06 Eu-152 0.00599 1.08E+04 1.02E+09 0.000 1.28E+10 1.08E+04 Eu-154 0.00082 1.47E+03 8.88E+08 0.000 1.11E+10 1.47E+03

[27]

FSS RELEASE RECORD - REV. 1

~

U1 CONTAINMENT INCORE SUMP DISCHARGE PIPE = ZIONSOLUTIONS;:;;=

SURVEY UNIT 01111 (P125)

An Eni,rgySolufic,n,s Campany Unit 1 Incore Sump Discharge Pipe (embedded - 1.5 in diameter) (continued)

Feet Gamma Gamma Activity per CTMT CTMT Nuclide Nuclide Sample ID into Result ROC Mixture/HTD ROC OpDCGLEP OpSOFEP BcDCGLEP BcSOF BcSOFEP OpSOF Pipe (pCi/m2) Ratio (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)

H-3 1.76 2.99E+06 6.62E+08 0.005 8.28E+09 0.000 Co-60 0.06431 1.18E+05 4.38E+08 0.000 5.47E+09 0.000 Ni-63 442.00 5.20E+07 1.12E+10 0.005 1.40E+11 0.000 Sr-90 0.021 3.56E+04 3.98E+06 0.009 4.98E+07 0.001 S1-01111AF-SSM-016-GD 15 1.83E+06 0.034 0.003 Cs-134 0.00014 2.49E+02 8.40E+07 0.000 1.05E+09 0.000 Cs-137 0.92875 1.70E+06 1.10E+08 0.015 1.37E+09 0.001 Eu-152 0.00599 1.10E+04 1.02E+09 0.000 1.28E+10 0.000 Eu-154 0.00082 1.49E+03 8.88E+08 0.000 1.11E+10 0.000 H-3 1.76 3.64E+06 6.62E+08 0.006 8.28E+09 0.000 Co-60 0.06431 1.43E+05 4.38E+08 0.000 5.47E+09 0.000 Ni-63 442.00 6.33E+07 1.12E+10 0.006 1.40E+11 0.000 Sr-90 0.021 4.35E+04 3.98E+06 0.011 4.98E+07 0.001 S1-01111AF-SSM-017-GD 16 2.23E+06 0.041 0.003 Cs-134 0.00014 3.04E+02 8.40E+07 0.000 1.05E+09 0.000 Cs-137 0.92875 2.07E+06 1.10E+08 0.019 1.37E+09 0.002 Eu-152 0.00599 1.34E+04 1.02E+09 0.000 1.28E+10 0.000 Eu-154 0.00082 1.82E+03 8.88E+08 0.000 1.11E+10 0.000 H-3 1.76 4.01E+06 6.62E+08 0.006 8.28E+09 0.000 Co-60 0.06431 1.58E+05 4.38E+08 0.000 5.47E+09 0.000 Ni-63 442.00 6.97E+07 1.12E+10 0.006 1.40E+11 0.000 Sr-90 0.021 4.78E+04 3.98E+06 0.012 4.98E+07 0.001 S1-01111AF-SSM-018-GD 17 2.45E+06 0.045 0.004 Cs-134 0.00014 3.34E+02 8.40E+07 0.000 1.05E+09 0.000 Cs-137 0.92875 2.28E+06 1.10E+08 0.021 1.37E+09 0.002 Eu-152 0.00599 1.47E+04 1.02E+09 0.000 1.28E+10 0.000 Eu-154 0.00082 2.01E+03 8.88E+08 0.000 1.11E+10 0.000 H-3 1.76 4.68E+06 6.62E+08 0.007 8.28E+09 0.001 Co-60 0.06431 1.84E+05 4.38E+08 0.000 5.47E+09 0.000 Ni-63 442.00 8.14E+07 1.12E+10 0.007 1.40E+11 0.001 Sr-90 0.021 5.58E+04 3.98E+06 0.014 4.98E+07 0.001 S1-01111AF-SSM-019-GD 18 2.86E+06 0.053 0.004 Cs-134 0.00014 3.90E+02 8.40E+07 0.000 1.05E+09 0.000 Cs-137 0.92875 2.66E+06 1.10E+08 0.024 1.37E+09 0.002 Eu-152 0.00599 1.72E+04 1.02E+09 0.000 1.28E+10 0.000 Eu-154 0.00082 2.34E+03 8.88E+08 0.000 1.11E+10 0.000 H-3 1.76 3.86E+06 6.62E+08 0.006 8.28E+09 0.000 Co-60 0.06431 1.52E+05 4.38E+08 0.000 5.47E+09 0.000 Ni-63 442.00 6.71E+07 1.12E+10 0.006 1.40E+11 0.000 Sr-90 0.021 4.60E+04 3.98E+06 0.012 4.98E+07 0.001 S1-01111AF-SSM-020-GD 19 2.36E+06 0.044 0.003 Cs-134 0.00014 3.22E+02 8.40E+07 0.000 1.05E+09 0.000 Cs-137 0.92875 2.19E+06 1.10E+08 0.020 1.37E+09 0.002 Eu-152 0.00599 1.41E+04 1.02E+09 0.000 1.28E+10 0.000 Eu-154 0.00082 1.93E+03 8.88E+08 0.000 1.11E+10 0.000

[28]

FSS RELEASE RECORD - REV. 1

~

U1 CONTAINMENT INCORE SUMP DISCHARGE PIPE = ZIONSOLUTIONS;:;;=

SURVEY UNIT 01111 (P125)

An Eni,rgySolufic,n,s Campany Unit 1 Incore Sump Discharge Pipe (embedded - 1.5 in diameter) (continued)

Feet Gamma Gamma Activity per CTMT CTMT Nuclide Nuclide Sample ID into Result ROC Mixture/HTD ROC OpDCGLEP OpSOFEP BcDCGLEP BcSOF BcSOFEP OpSOF Pipe (pCi/m2) Ratio (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)

H-3 1.76 2.99E+06 6.62E+08 0.005 8.28E+09 0.001 Co-60 0.06431 1.18E+05 4.38E+08 0.000 5.47E+09 0.000 Ni-63 442.00 5.20E+07 1.12E+10 0.005 1.40E+11 0.001 Sr-90 0.021 3.56E+04 3.98E+06 0.009 4.98E+07 0.001 S1-01111AF-SSM-021-GD 20 2.92E+06 0.054 0.004 Cs-134 0.00014 2.49E+02 8.40E+07 0.000 1.05E+09 0.000 Cs-137 0.92875 1.70E+06 1.10E+08 0.015 1.37E+09 0.002 Eu-152 0.00599 1.10E+04 1.02E+09 0.000 1.28E+10 0.000 Eu-154 0.00082 1.49E+03 8.88E+08 0.000 1.11E+10 0.000 H-3 1.76 1.87E+05 4.38E+08 0.000 8.28E+09 0.002 Co-60 0.06431 8.29E+07 1.12E+10 0.007 5.47E+09 0.000 Ni-63 442.00 5.69E+04 3.98E+06 0.014 1.40E+11 0.002 Sr-90 0.021 3.97E+02 8.40E+07 0.000 4.98E+07 0.004 S1-01111AF-SSM-022-GD 21 1.07E+07 0.198 0.016 Cs-134 0.00014 2.71E+06 1.10E+08 0.025 1.05E+09 0.000 Cs-137 0.92875 1.75E+04 1.02E+09 0.000 1.37E+09 0.007 Eu-152 0.00599 2.38E+03 8.88E+08 0.000 1.28E+10 0.000 Eu-154 0.00082 1.75E+07 6.62E+08 0.026 1.11E+10 0.000 H-3 1.76 5.43E+06 6.62E+08 0.008 8.28E+09 0.001 Co-60 0.06431 2.14E+05 4.38E+08 0.000 5.47E+09 0.000 Ni-63 442.00 9.44E+07 1.12E+10 0.008 1.40E+11 0.001 Sr-90 0.021 6.48E+04 3.98E+06 0.016 4.98E+07 0.001 S1-01111AF-QSM-007-GD 6 3.32E+06 0.061 0.005 Cs-134 0.00014 4.53E+02 8.40E+07 0.000 1.05E+09 0.000 Cs-137 0.92875 3.09E+06 1.10E+08 0.028 1.37E+09 0.002 Eu-152 0.00599 1.99E+04 1.02E+09 0.000 1.28E+10 0.000 Eu-154 0.00082 2.72E+03 8.88E+08 0.000 1.11E+10 0.000 H-3 1.76 3.48E+06 6.62E+08 0.005 8.28E+09 0.000 Co-60 0.06431 1.37E+05 4.38E+08 0.000 5.47E+09 0.000 Ni-63 442.00 6.06E+07 1.12E+10 0.005 1.40E+11 0.000 Sr-90 0.021 4.16E+04 3.98E+06 0.010 4.98E+07 0.001 S1-01111AF-QSM-013-GD 12 2.13E+06 0.039 0.003 Cs-134 0.00014 2.90E+02 8.40E+07 0.000 1.05E+09 0.000 Cs-137 0.92875 1.98E+06 1.10E+08 0.018 1.37E+09 0.001 Eu-152 0.00599 1.28E+04 1.02E+09 0.000 1.28E+10 0.000 Eu-154 0.00082 1.74E+03 8.88E+08 0.000 1.11E+10 0.000 H-3 1.76 6.81E+06 6.62E+08 0.010 8.28E+09 0.001 Co-60 0.06431 2.68E+05 4.38E+08 0.001 5.47E+09 0.000 Ni-63 442.00 1.18E+08 1.12E+10 0.011 1.40E+11 0.001 Sr-90 0.021 8.12E+04 3.98E+06 0.020 4.98E+07 0.002 S1-01111AF-QSM-021-GD 21 4.17E+06 0.077 0.006 Cs-134 0.00014 5.68E+02 8.40E+07 0.000 1.05E+09 0.000 Cs-137 0.92875 3.87E+06 1.10E+08 0.035 1.37E+09 0.003 Eu-152 0.00599 2.50E+04 1.02E+09 0.000 1.28E+10 0.000 Eu-154 0.00082 3.41E+03 8.88E+08 0.000 1.11E+10 0.000

[29]

ATTACHMENT 3 SIGN TEST

[30]

FSS RELEASE RECORD - REV. 1

~

U1 CONTAINMENT INCORE SUMP DISCHARGE PIPE = ZIONSOLUTIONSLLC-SURVEY UNIT 01111 (P125)

""' EnergySolufKlr!s Company Sign Test - Unit 1 Containment Basement Under Vessel Area Survey Area 01111 Survey Area Unit 1 Containment Under Vessel Survey Unit P125 Survey Unit Incore Sump Discharge Pipe (embedded)

Classification 1 Type I Error 0.05 Number of Measurements 22 SOF

  1. 1-Ws Sign (Ws) 1 5.793 (4.79) -1 2 0.877 0.12 +1 3 0.185 0.82 +1 4 0.082 0.92 +1 5 0.081 0.92 +1 6 0.064 0.94 +1 7 0.064 0.94 +1 8 0.061 0.94 +1 9 0.055 0.95 +1 10 0.047 0.95 +1 11 0.053 0.95 +1 12 0.044 0.96 +1 13 0.039 0.96 +1 14 0.038 0.96 +1 15 0.033 0.97 +1 16 0.034 0.97 +1 17 0.041 0.96 +1 18 0.045 0.95 +1 19 0.053 0.95 +1 20 0.044 0.96 +1 21 0.054 0.95 +1 22 0.198 0.80 +1 Number of positive differences (S+) 21 Critical Value 15 The Survey Unit MEETS the Acceptance Criteria

[31]

ATTACHMENT 4 QC DATA

[32]

FSS RELEASE RECORD - REV. 1

~

U1 CONTAINMENT INCORE SUMP DISCHARGE PIPE = ZIONSOLUTIONS;:;;;=.

SURVEY UNIT 01111 (P125)

An Erw,rgySo/uticnt: Campany Unit 1 Incore Sump Discharge Pipe (P125) - QC Agreement Duplicate Sample Assessment Form Survey Unit #: 01111A Survey Unit # P125 Survey Unit Name: U1 In Core Sump Discharge Pipe Sample Plan#: S101111A-F I

Sample

Description:

Comparison of replicate measurements collected from measurement location #s 6, 12 and 20. The standard measurements were S1-01111A-FSSM-006-GD, S1-01111A-FSSM-012-GD and S1-01111A-FSSM-020-GD. The comparison measurments were S1-01111A-FQSM-006-GD, S1-01111A-FQSM-012-GD and S1-01111A-FQSM-020-GD.

Standard Measurement Duplicate Activity Activity Acceptable

+20% -20%

ID Value ID Value (Y/N)

(pCi/m 2 ) (pCi/m 2 ) (pCi/m 2 ) (pCi/m 2 )

S1-01111A-FSSM-006-GD 3.45E+06 4.13E+06 2.76E+06 S1-01111A-FQSM-006-GD 3.32E+06 Y S1-01111A-FSSM-012-GD 2.10E+06 2.52E+06 1.68E+06 S1-01111A-FQSM-012-GD 2.13E+06 Y S1-01111A-FSSM-020-GD 2.92E+06 3.50E+06 2.33E+06 S1-01111A-FQSM-020-GD 4.17E+06 Y Comments/Corrective Actions: The 1st two replicate measurement The acceptance criteria for replicate static measurements results (S1-01111A-FQSM-006-GD and S1-01111A-FQSM-012- and scan surveys is that the same conclusion is reached GD) are in acceptable agreement (within -+ 20%). The 3rd replicate for each measurement. This is defined as -+ 20% of the measurement S1-01111A-FSSM-020 result is outside of the standard acceptance range (+30%). This is expectedly due to the detector not being positioned exactly over the original location resulting in the higher value. In accordance with section 4.1.2 of the QAPP, a replicate measurement is in agreement if, based on the professional judgment of the Radiological Engineer, that the same conclusion is reached for the replicate measurement location as with the standard. In the case of S1-01111A-FQSM-020-GD, this is true. No further investigation is necessary.

Performed by: Date: Reviewed by: Date:

9/18/2018

[33]

ATTACHMENT 5 GRAPHICAL PRESENTATIONS

[34]

FSS RELEASE RECORD - REV. 1

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U1 CONTAINMENT INCORE SUMP DISCHARGE PIPE = ZIONSOLUTIONS;;:;=

SURVEY UNIT 01111 (P125)

An Eni,rgySoluficns Company QUANTILE PLOT FOR GROSS GAMMA ACTIVITY Survey Unit: S101111A Survey Unit Name: Unit 1-In-Core Sump Drain Pipe (No. P125)

Mean: 1.96E+07 pCi/m2 Quantile Plot for Gross Gamma Activity 3.50E+08 3.00E+08 Activity in pCi/m2 2.50E+08 2.00E+08 1.50E+08 1.00E+08 5.00E+07 0.00E+00 0% 20% 40% 60% 80% 100% 120%

Percentage Point Gross Gamma Rank Percent 15 1.80E+06 22 0%

16 1.83E+06 21 5%

14 2.07E+06 20 10%

13 2.10E+06 19 14%

17 2.23E+06 18 19%

20 2.36E+06 17 24%

12 2.38E+06 16 29%

18 2.45E+06 15 33%

10 2.55E+06 14 38%

11 2.84E+06 13 43%

19 2.86E+06 12 48%

21 2.92E+06 11 52%

9 2.96E+06 10 57%

8 3.28E+06 9 62%

7 3.45E+06 8 67%

6 3.45E+06 7 71%

5 4.36E+06 6 76%

4 4.45E+06 5 81%

3 9.98E+06 4 86%

22 1.07E+07 3 90%

2 4.74E+07 2 95%

1 3.13E+08 1 100%

[35]

FSS RELEASE RECORD - REV. 1

~

U1 CONTAINMENT INCORE SUMP DISCHARGE PIPE = ZIONSOLUTIONS;;:;=

SURVEY UNIT 01111 (P125)

An Eni,rgySoluficns Company HISTOGRAM FOR GROSS GAMMA ACTIVITY Survey Unit: S101111A Survey Unit Name: Unit 1 In-Core Sump Drain Pipe (P125)

Mean: 1.96E+07 pCi/m2 Median: 2.89E+06 pCi/m2 ST DEV: 6.62E+07 Skew: 4.54E+00 Histogram 25 21 20 Frequency 15 10 Frequency 5

1 0 0 0 0 0

5.37E+07 5.37E+07 5.37E+07 5.37E+07 1.06E+08 More Bin pCi/m2 Bin Frequency 5.37E+07 21 5.37E+07 0 5.37E+07 0 5.37E+07 0 1.06E+08 0 More 1

[36]

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