ML25328A165

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Us Dept of Transportation - Nuclear Ship Savannah, Survey Unit Release Record Survey Unit STR-105-02 Reactor Compartment - Lower Level (5-23) Port-side Half
ML25328A165
Person / Time
Site: NS Savannah
Issue date: 11/20/2025
From: Roberson D
US Dept of Transportation, Maritime Admin, Nuclear Ship Support Services
To:
Office of Nuclear Reactor Regulation
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U.S. Department of Transportation Maritime Administration Office of Ship Operations Nuclear Ship Savannah Survey Unit Release Record Survey Unit STR-105-02 Reactor Compartment - Lower Level (5' - 23') Port-side Half Approved:

Senior Technical Advisor Prepared by:

Nuclear Ship Support Services, LLC

SAVANNAH Technical Staff Survey Unit Release Record PREPARED BY /DATE:

PEER REVIEW/ DATE:

DECOMMISSIONING PROGRAM MANAGER REVIEW/ DATE:

INDEPENDENT REVIEW/

DATE:

FSS MANAGER REVIEW/ DATE:

LICENSING COMPLIANCE MANAGER REVIEW/ DATE:

SAFETY REVIEW COMMITTEE SUBMITTED/ APPROVED Survey Unit STR-105-02 D. Roberson Douglas Roberson Pete Hollenbeck Pete Hollenbeck, CHP Soeuth Caleb Soeun Soeuth C. Soeun James Reese, CHP, RRPT James Reese Digitally signed by D. Roberson Date: 2025.04.28 12:49:07 -05'00' Date Digitally signed by Pete Hollenbeck Date: 2025.04.28 15:16:24 -04'00' Date Digitally signed by Soeuth Caleb Soeun Date: 2025.04.29 07:50:03 -04'00' Date Digitally signed by James Reese, CHP, RRPT Date: 2025.04.30 07:51 :28 -07'00' Date Dan

  • 1 e I R M
  • 1 ha 1
  • 1 k Digitally signed by Daniel R. Mihalik Date: 2025.04.30 15:19:43 -04'00' Daniel Mihalik Date John Osborne ~~~allysignedby: JohnOsbome ON: CN = John Osborne LCM email LCM

= jmosbome@nsss.llc C = AD Date: 2025.05.20 08:31 :07 -05'00' John Osborne Date 5/12/2025 5/20/2025 Submitted Approved Page 2 of33 Reactor Compartment Lower Level (5' - 23') Port-Side Half

SAVANNAH Technical Staff Survey Unit Release Record TABLE OF CONTENTS

1.

EXECUTIVE SUMM.ARY.................................................................................................... 6

2.

SURVEY UNIT DESCRIPTION.......................................................................................... 6

3.

CLASSIFICATION BASIS................................................................................................... 7

4.

DATA QUALITY OBJECTIVES......................................................................................... 7 S.

SURVEY DESIGN............................................................................................................... 10

6.

SURVEY IMPLEMENTATION......................................................................................... 13

7.

SURVEY RESULTS............................................................................................................. 14

8.

QUALITY CONTROL........................................................................................................ 16

9.

INVESTIGATIONS AND RESULTS................................................................................ 16

10. REMEDIATION AND RESUL TS...................................................................................... 16
11. CHANGES FROM THE FINAL STATUS SURVEY PACKAGE................................. 17
12. DATA QUALITY ASSESSMENT (DQA)......................................................................... 17
13. ANOMALIES........................................................................................................................ 17
14. CONCLUSIONS................................................................................................................... 17
15. REFERENCES..................................................................................................................... 17
16. ATTACHMENTS................................................................................................................. 19 Survey Unit STR-105-02 Page 3 of33 Reactor Compartment Lower Level (5' - 23') Port-side Half

SAVANNAH Technical Staff Survey Unit Release Record LIST OF TABLES Table 4 Radionuclide Fractions and Normalized Fractions............................................... 8 Table 4 15 mrem/y DCGLs for ROC and Ni-63.................................................................. 8 Table 4 Re-normalized Co-60 and Cs-137 Fractions.......................................................... 9 Table 4 Operational DCGLs................................................................................................ 10 Table 5 STR-105-02 Systematic Measurement Designations........................................... 12 Table 5 Scanning Coverage................................................................................................ *. 12 Table 5 Investigation Levels................................................................................................ 13 Table 7 Summary of Systematic, Judgmental, and QC Static Measurements................ 14 Table 7 Basic Statistical Properties of Static Measurement Population.......................... 15 Table 7 Scan Measurement Summary................................................................................ 16 Survey Unit STR-105-02 Page 4 of33 Reactor Compartment Lower Level (5' - 23') Port-side Half

SAVANNAH Technical Staff Survey Unit Release Record LIST OF ACRONYMS AND ABBREVIATIONS ALARA As Low As Reasonably Achievable DQA Data Quality Assessment DQO Data Quality Objective DCGL Derived Concentration Guideline Level FSS Final Status Survey HSA Historical Site Assessment IC Insignificant Dose Contributors LBGR Lower Bound of the Gray Region LTP License Termination Plan MARAD Maritime Administration MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual MDC Minimum Detectable Concentration MDCR Minimal Detectable Count Rate NSS Nuclear Ship Savannah QC Quality Control RASS Remedial Action Support Survey ROC Radionuclides of Concern SOF Sum-of-Fraction TEDE Total Effective Dose Equivalent UBGR Upper Bound of the Gray Region USNRC United States Nuclear Regulatory Commission Survey Unit STR-105-02 Reactor Compartment Lower Level (5' - 23') Port-side Half Page 5 of33

SAVANNAH Technical Staff Survey Unit Release Record

1.

EXECUTIVE

SUMMARY

This Survey Unit Release Record for survey unit STR-105-02, Reactor Compartment -

Lower Level (5' - 23') Port-side Half, has been generated in accordance with Maritime Administration (MARAD) procedure STS-005-035, Preparation of Survey Unit Release Records and FSS Final Reports [ 1] and satisfies the requirements of Section 5.10 of the Nuclear Ship SAVANNAH (NSS) License Termination Plan, STS-004-003 [2].

A Final Status Survey (FSS) survey package for this survey unit was developed in accordance with MARAD procedure STS-005-030, Preparation of Final Status Survey Packages [3 ], the NSS License Termination Plan (LTP), and with guidance from NUREG-1575, Revision 1, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) [4].

This survey unit has a MARS SIM classification of 1. A survey package was designed based upon the use of the Sign Test as the nonparametric statistical test for compliance. Both the Type I (a.) and Type II (~) decision error rates were set at 0.05. As a systematic measurement population, fifteen (15) static beta measurements were acquired from the survey unit. In addition, two judgmental static beta measurements were acquired. Surface scanning was performed on 100% of the accessible total surface area in the survey unit.

The data assessment results for survey unit STR-105-02 show that the maximum gross activity concentration among systematic and judgmental measurements is equal to 1,471.72 dpm/100 cm2, which is 2. 81 % of the operational Derived Concentration Guideline Level (DCGLw) value of 52,300 dpm/100 cm2. Therefore, the null hypothesis of the Sign Test is rejected, and survey unit STR-105-02 is acceptable for unrestricted release. The mean gross activity concentration among the systematic and judgmental measurements is equal to 630.75 dpm/100 cm2, which is 0.90% of the 15 mrem/y gross activity DCGLw of 69,700 dpm/100 cm2. The mean gross activity concentration is equal to 0.14 mrem/y for the survey unit.

2.

SURVEY UNIT DESCRIPTION STR-105-02 is an impacted Class 1 survey unit. The reactor compartment where the containment vessel is located extends from 5' Elevation (Tanktop) to above the A Deck level. The reactor compartment contains support systems for the reactor plant.STR-105-02 is the Port-side of the reactor compartment lower level, 5' - 23' elevation. Based upon Computer Aided Design drawings, the deck surface area is approximately 99.30 square meters (99.30 m2); the total surface area, including the bulkheads and overhead, is approximately 340.60 m2; this includes the surfaces above 2 meters. Refer to Attachment 1 of this report for figures and maps depicting survey unit STR-105-02.

Survey Unit STR-105-02 Page 6 of33 Reactor Compartment Lower Level (5' - 23') Port-side Half

SAVANNAH Technical Staff Survey Unit Release Record

3.

CLASSIFICATION BASIS Based on the NSS Historical Site Assessment [HSA] [5], survey unit STR-105-02, identified as survey unit 109Al in the HSA, was identified as a Class 1 structure survey unit. The HSA states primary coolant leaks were experienced from time to time, as was typical of nuclear power plants of the era. In the spring of 1976, the primary and secondary systems were drained, and the

  • removed liquid was transported to the Chem-Nuclear disposal site in Barnwell, South Carolina, for processing and disposal. The three primary system demineralizers were removed from the reactor compartment and shipped to Chem-Nuclear for disposal. Based upon a review of the historical information, the results of the characterization survey data, the 2024 Remedial Action Support Survey (RASS) STR-105-RASS-01-Rev 0, and the completion of a final Survey Unit Classification Worksheet, the correct final classification of survey unit STR-105-02 met the requirements of Class 1.
4.

DATA QUALITY OBJECTIVES FSS planning and design relies on a properly executed 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 NSS L TP in accordance with MARS SIM. The appropriate design for a given survey was developed using the DQO process as outlined in Appendix D ofMARSSIM.

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 package, 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 is to demonstrate that the level of residual radioactivity in survey unit STR-105-02 did not exceed the release criteria specified in the L TP and that the potential dose from residual radioactivity is As Low As Reasonably Achievable (ALARA).

MARAD Contractor Report CR-13 9, Calculations to Support NSS Surface Contamination DCGLs [ 6] established the basis for an initial suite of potential Radionuclides of Concern (ROC) for decommissioning. Insignificant dose contributors (IC) were determined consistent with the guidance contained in Section 3.3 of NUREG-1757, Volume 2, Revision 1, Consolidated Decommissioning Guidance - Characterization, Survey, and Determination of Radiological Criteria [7]. In all analyses, Cs-137 and Co-60 contribute Survey Unit STR-105-02 Page 7 of33 Reactor Compartment Lower Level (5' - 23') Port-side Half

SAVANNAH Technical Staff Survey Unit Release Record nearly 100% of the total dose. The remaining radionuclides were designated as IC. Because Ni-63 comprises approximately 90% of the total activity, it is accounted for as a surrogate to Co-60. Therefore, the final ROCs for final status surveys are Cs-137 and Co-60surrogate-LTP Chapter 6, Section 6.13 discusses the process used to derive the Radionuclides of Concern (ROC) for the decommissioning of the NSS, including the elimination of insignificant dose contributors from the initial suite. Table 4-1 presents the initial suite of ROC for the decommissioning of the NSS, and the normalized mixture fractions based on the radionuclide mixture.

Table 4-1-Radionuclide Fractions and Normalized Fractions Normalized Sum of Sum of Only Co, Ni Nuclide Fractions Fractions and Cs C-14 3.37E-02 5.61E-03 Co-60 9.78E-02 1.63E-02 l.63E-02 Ni-63 5.40E+00 9.00E-01 9.00E-01 Sr-90 9.22E-06 l.54E-06 Tc-99 l.27E-04 2.llE-05 Ag-108m 8.30E-04 l.38E-04 Cs-137 4.57E-01 7.61E-02 7.61E-02 H-3 l.93E-03 3.21E-04 Fe-55 8.l0E-03 l.35E-03 Am-241 5.79E-07 9.66E-08 Pu-239/240 4.81E-07 8.0lE-08 Totals 6.00E+00 l.00E+00 9.93E-0l Each radionuclide-specific DCGLw 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 15 mrem/yr to an Average Member of the Critical Group (AMCG). Table 4-2 presents the 15 mrem/y DCGLw for Co-60, Ni-63 and Cs-137 from Chapter 6 of the L TP.

Table 4 15 mrem/y DCGLs for ROC and Ni-63 Radionuclide DCGLw (dpm/100cm2)

Co-60 2.37E+04 Ni-63 2.53E+o8 Cs-137 l.20E+05 Survey Unit STR-105-02 Page 8 of33 Reactor Compartment Lower Level (5' - 23') Port-side Half

SAVANNAH Technical Sta ff rd Survey Unit Release Reco Nickel-63 is a Hard-to-Detect (HTD) radionuclide. To account for Ni-63, the Easy-To-radionuclide Co-60 will be used as a surrogate.

Detect (ETD)

The surrogate DCGL is computed as:

DC GL DCGLETD X DCGLHTD surrogate =

(f HTD:ETvxDCGLETv)+DCGLHTD Where:

DCGLETD DCGLHTD

= the DCGL for the easy-to-detect radionuclide

= the DCGL for the hard-to-detect radionuclide Equation 1 FHTD:ETD

= the activity ratio of the hard-to-detect radionuclide to the easy-to-detect radionuclide Using the dat a in Table 4-1, the Ni-63/Co-60 ratio equals 55.3. Solving Equation 1 using r Co-60 and Ni-63 in Table 4-2 and the Ni-63/Co-60 ratio of 55.3 is shown the DCGLs fo below.

DCGLco-60 2.53E+08 2

surrogate= 2.37E + 04 X (

)

= 2.36E+04 dpm/100 cm 55.3 X 2.37E+04 +2.53E+08 A gross activi ty DCGLw has been established, based on the representative radionuclide ws:

mix, as follo Where:

fn n

DCGLn 1

Gross Activity DCGLw =

11 1z tn DCGL1 + DCGL2 +"*ocGLn

= fraction of the total activity contributed by radionuclide n the number of radionuclides

= DCGL for the Radionuclide of Concern (ROC)

Equation 2 Of the three measurements radionuclides, only Co-60 and Cs-137 can be detected by gross activity

. The normalized fractions for both radionuclides in Table 4-1 must be re-r use in Equation 2. Table 4-3 presents the re-normalized fractions for each normalized fo radionuclide.

T able 4-3-Re-normalized Co-60 and Cs-137 Fractions Normalized Only Co-60 Re-sum of and Cs-137 normalized Nu elide fractions Fractions Fractions C-1 4 5.61E-03 Co -60 1.63E-02 l.63E-02 l.76E-01 Ni-63 9.00E-01 Sr-90 l.54E-06 Tc-99 2.1 lE-05 Survey Unit STR-105-02 Page 9 of33 Reactor Compartment Lo wer Level (5' - 23') Port-side Half

SAVANNAHTechnical Staff Survey Unit Release Record Nuclide Ag-108m Cs-137 H-3 Fe-55 Am-241 Pu-239/240 Totals Normalized sum of fractions l.38E-04 7.61E-02 3.21E-04 1.35E-03 9.66E-08 8.0lE-08 1.00E+00

-r - -. -- -

OnlyCo-60 Re-and Cs-137 normalized Fractions Fractions 7.61E-02 8.24E-01 9.24E-02 1.00E+00 Solving Equation 2 using the re-normalized Co-60 and Cs-137 fractions and the Co-60 surrogate DCGL is shown below.

1 Gross Activity DCGLw = 1.

7 6 E - l +

8

_ 24E - l = 6.97E+04 dpm/100 cm 2

2.36E+o4 1.20E+os The DCGLs are reduced to a fraction of the 15 mrem/yr dose limit. The reduced DCGLs, or operational DCGLw is then used as the DCGL for the FSS design of the survey unit (investigations levels, etc.). The operational DCGLs are set at 75% of the 15 mrem/y DCGLw. The operational DCGLs are provided in Table 4-4.

Table 4 Operational DCGLs Radionuclide Operational DCGL (dpm/100cm2)

Co-60 l.77E+04 Cs-137 9.00E+04 Gross Activity 5.23E+04 Instrument DQOs included a verification of the ability _of the survey instrument to detect the radiation(s) of interest relative to the operational DCGLw. Survey instrument response checks were required prior to issuance and after the instrument had been used. Control and accountability of survey instruments was required to ensure the quality and prevent the loss of data. MARS SIM states that a Minimum Detectable Concentration (MDC) below 10%

of the DCGL is preferable and up to 50% is acceptable. Because the background is low on the NSS, the MDC for most static and scan measurements were less than 10% of the DCGL and in all cases the MDCs were less than 50% of the DCGL.

5.

SURVEY DESIGN The L TP specifies that the Sign Test will be used as the nonparametric statistical test for compliance with the release criteria. The number of measurements for use with the Sign Survey Unit STR-105-02 Page 10 of33 Reactor Compartment Lower Level (5' - 23') Port-side Half

SAVANNAH Technical Staff Survey Unit Release Record Test was determined in accordance with MARAD procedure STS-005-031, Calculation Of The Number of Measurements For Final Status Surveys. [8] The relative shift (Ncr) for the survey unit data set is defined as shift(~), which is the Upper Boundary of the Gray Region (UBGR), or the operational DCGLw, minus the Lower Bound of the Gray Region (LBGR),

divided by sigma ( cr ), which is the standard deviation of the data set used for survey design.

The optimal value for Ncr should range between one (1) and three (3). The largest value the Ncr can have is three (3). If the Ncr exceeds three (3), then the value of two (2) will be used for Ncr.

Remediation and RASS surveys were performed between 04/08/2024 and 05/06/2024 with an additional follow up remediation survey performed on 08/22/2024 in response to suspected Alpha concerns. A total of thirty-five (35) static measurements and 35 smears were collected, five of which were post remediation taken on 08/06/2024. On 08/22/2024 following an additional remediation, 10 additional smears were collected. Post remediation, no alpha activity was greater than the minimum detectable activity. The maximum beta activity was 91.579 dpm/100 cm2. The average total surface activity concentration and standard deviation of all static the measurements were 1,470 and 1,380 dpm/100 cm2, respectively. Because the activity concentration is low, the LBGR was set to half the operational DCGLw. The relative shift for survey unit STR-105-02 is based upon the RASS survey results and was calculated as follows:

52,300-26,150 Relative Shift=----- = 18.95 1,380 Because the calculated relative shift was greater than three (3), the value of two (2) was used as the adjusted Ncr. Both the Type I error, or a value, and the Type II error, or p value, were set at 0.05. The sample size from Table 5.5 ofMARSSIM that equates to the Type I and Type II error of 0.05 for use with the Sign Test is an N value of fifteen (15). Fifteen (15) total systematic measurements were used in the survey design for survey unit STR-105-02.

The survey unit was designated Class 1; therefore, the measurement locations were selected based on a systematic grid with a random starting point. The systematic locations of the static measurements were selected using Visual Sample Plan (VSP). Input parameters included the use of survey unit drawings, and the systematic sampling tool set with a predetermined number of measurement locations. The systematic measurement locations were identified in the field using dimension parameters provided on the survey unit map (see Attachment 1). Table 5-1 lists the systematic measurements to be collected for FSS of survey unit STR-105-02.

Survey Unit STR-105-02 Page 11 of33 Reactor Compartment Lower Level (5' - 23') Port-side Half

~--- --------

SAVANNAH Technical Staff Survey Unit Release Record Table 5 STR-105-02 Systematic Measurement Designations Label LX(m)

LY(m)

Surface STR-105-02-01

-14.27 0.59 Deck STR-105-02-02

-9.15 0.59 Deck STR-105-02-03

-4.03 0.59 Deck STR-105-02-04

-16.36

-1.18 CV Shell Overhead STR-105-02-05

-11.24

-1.18 CV Shell Overhead STR-105-02-06

-6.12

-1.18 CV Shell Overhead STR-105-02-07

-1.00

-1.18 RC Lower-Level Overhead STR-105-02-08

-13.80 3.26 CV Shell Overhead STR-105-02-09

-8.68 3.26 CV Shell Overhead STR-105-02-10

-3.56 3.26 RC Lower-Level Overhead STR-105-02-11 0.72 1.73 Bulkhead 8 STR-105-02-12 4.01 1.73 Bulkhead 6 STR-105-02-13 9.13 1.73 Bulkhead 6 STR-105-02-14 14.25 1.73 Bulkhead 6 STR-105-02-15 2.19 1.73 Bulkhead 3 The implementation of quality control (QC) measures is referenced in LTP Chapter 5, Section 5.11. A randomly chosen replicate measurement was specified in the survey package. This measurement was to be collected by either a different technician or by a different instrument. Location STR-105-02-09 was chosen for the replicate measurement.

In addition, the survey package also specified to perform QC operability checks of field instruments both prior to and after collection of the measurements.

The survey package also specified collection of two judgmental measurements to augment the systematic measurements. The locations of these two measurements were to be determined by the technicians and/or the field supervisor. Those two judgmental measurements are identified as STR-105-02-16-J and STR-105-02-17-J. Those locations would be documented on the field forms.

For this Class 1 structure survey unit, the "Scanning Coverage" are those levels specified in LTP Chapter 5, Table 5-3, and are reproduced below in Table 5-2.

Table 5 Scanning Coverage Classification Required Scanning Coverage Fraction Class 1 100%

For survey unit STR-105-02, thirteen scan areas were established SA-01 through SA-13.

The survey package stated to scan 100% of the accessible area in each scan area. Refer to for figures and maps depicting the measurement and scan locations in survey unit STR-105-02.

Survey Unit STR-105-02 Page 12 of33 Reactor Compartment Lower Level (5' - 23') Port-side Half

SAVANNAH Technical Staff Survey Unit Release Record For this Class 1 structure survey unit, the "Investigation Levels" for direct and scanning measurement results are those levels specified in LTP Chapter 5, Table 5-2, and are reproduced below in Table 5-3.

Table 5 Investigation Levels Survey Unit Fixed Measurements Scan Measurements Classification Class 1

> Operational DCGLw > Operational DCGLw and an outlier*

These investigation levels were specified in the survey package.

An additional action level was specified in the survey package. If the technician observed a count rate of2,500 cpm when scanning, approximately one-half of the investigation level, they were to stop scanning, backup and rescan the elevated location again to see if the count rate was observed again. If observed again, an additional static measurement would be collected. If not, they would continue scanning.

6.

SURVEYIMPLEMENTATION For survey unit STR-105-02, compliance with the unrestricted release criteria was demonstrated through a combination of surface scanning and surface static measurements with a Ludlum Model 43-93 ZnS detector connected to a Ludlum Model 3002 meter operating in beta mode.

Prior to performing the survey, a walkdown of the survey unit was performed per MARAD procedure STS-005-032, Survey Unit Turnover and Control. [9] No conditions prohibited the proper collection of static and scan measurements.

FSS field activities were conducted under the approved FSS Package Number NSS-FSSP-STR-105-02-00-00, which included DQOs, survey design, detailed FSS instructions, survey maps and survey forms. FSS field activities were projected to take six (6) working days to complete. A daily briefing was conducted to discuss the expectations for job performance and to review safety aspects of the job. An FSS package "Field Log" was used to document field activities and other information pertaining to the performance of the FSS.

The FSS field activities took six days to complete and were performed on December 2, 2024, through December 4, 2024, December 18, 2024 through December 19, 2024, and February 13, 2025.

Ambient background count rates were collected by taking a I-minute static measurement, while maintaining the detector waist high. This value was used to calculate the MDC for scanning and static measurements.

The fifteen (15) systematic static measurement locations were marked based on the dimensions provided on the survey map. Two (2) judgmental measurement locations were Survey Unit STR-105-02 Page 13 of33 Reactor Compartment Lower Level (5' - 23') Port-side Half

SAVANNAH Technical Staff Survey Unit Release Record selected and marked as per the sample plan. A I -minute static measurement was acquired at each location with the detector in contact with the surface.

The thirteen scan areas, SA-01 through SA-13, were scanned, resulting in 100% of the total surface area being scanned. The total scan area meets the scan coverage requirements for a Class 1 area as shown in LTP Table 5-3 and reproduced in Table 5-2 of this release record. Scanning was performed with the detector held approximately 0.75 inches from the surface while moving at a speed of one detector width per second.

The implementation of survey specific QC measures included the collection of one replicate static measurement. The random location of the replicate measurement was STR-105-02-09 and identified as STR-105-02-09-D. That measurement was collected with a different instrument but the same make and model used for all the other measurements.

The instruments used for this survey were satisfactorily checked prior to and after performing the survey.

7.

SURVEYRESULTS The efficiencies used to convert count rates to activity are weighted efficiencies in which the Tc-99 (Co-60 surrogate) and Cs-137 efficiencies are weighted by the fraction Co-60 and Cs-137 comprise the NSS fingerprint. This is documented in CR-164 [10]. For example, if the 4n contact Tc-99 efficiency is 0.1002 c/d and the 4n Cs-137 contact efficiency is 0.1868 c/d, the weighted contact efficiency is shown below.

Weighted efficiency (c/d) = (0.1002) (0.176) + (0.1868) (0.824) = 0.1716 c/d Copies of the instrument calibration records are presented in Attachment 2.

The highest ambient background count rate from a 1-minute count was 97 cpm and was rounded up to 100 cpm. The un-painted surface contact detector weighted efficiency is equal to 0.1775 c/d. Using LTP Equation 5-6, which was derived from NUREG-1507, in which the count time and background count times are equal, results in an MDC for 1-minute static measurements equal to 278.9 dpm/100 cm2. The value for un-painted flat surface contact is less than 1% of the operational and gross activity DCGLw. Table 7-1 presents the activity concentration for all static measurements.

Table 7 Summary of Systematic, Judgmental, and QC Static Measurements Activity Concentration Measurement ID (dpm/100 cm2)

STR-105-02-01 471.21 STR-105-02-02 522.85 STR-105-02-03 497.03 STR-105-02-04 348.57 STR-105-02-05 387.29 STR-105-02-06 561.58 Survey Unit STR-105-02 Page 14 of33 Reactor Compartment Lower Level (5' - 23') Port-side Half

SAVANNAH Technical Staff Survey Unit Release Record Measurement ID STR-105-02-07 STR-105-02-08 STR-105-02-09 STR-105-02-10 STR-105-02-11 STR-105-02-12 STR-105-02-13 STR-105-02-14 STR-105-02-15 STR-105-02-16-J STR-105-02-17-J STR-105-02-09-D Activity Concentration

( dom/100 cm2) 864.91 484.12 426.02 1008.14 716.50 464.75 445.39 484.12 1471.72 522.85 1045.70 732.58 The raw static data with detector efficiencies are presented in Attachment 3.

'brl Table 7-2 presents the basic statistical properties of the static measurement population, without the duplicate measurement.

Table 7 Basic Statistical Properties of Static Measurement Population Parameter Value Units Minimum Measurement 348.57 dom/100 cm2 Maximum Measurement 1471.72 dom/100 cm2 Mean 630.75 dom/100 cm2 Median 497.03 dom/100 cm2 Standard Deviation 300.12 dom/100 cm2 Coefficient of Variation 0.48 unitless Residual activity dose rate 0.14 mrem/y The mean activity from static measurements was divided by the gross activity DCGLw to derive a mean fraction. The mean fraction was then multiplied by 15 mrem/yr to derive the dose attributed to the survey unit. For survey unit STR-105-02, the calculated dose from residual activity is 0.14 mrem/yr.

Calculation of the scan MDC uses L TP Equation 5-8, derived from NUREG-1507. scan MDC for the Ludlum 43-93 detector used the highest rounded count rate of 125 cpm, a distance of 0.75 inches, and the un-painted surface detector weighted efficiency of 0.1037 c/d. The detector width is 3.6 inches, and the detector speed is 3.6 in/second. With these parameters, the resulting observation interval is 1.234 seconds. The resulting MDC for scanning un-painted surfaces is 1,466.2 dpm/100 cm2* The value is 2.8% of the operational DCGLw and 2.1 % of the gross activity DCGLw for flat surfaces.

Table 7-3 presents activity concentrations for all scan measurements.

Survey Unit STR-105-02 Page 15 of33 Reactor Compartment Lower Level (5' - 23') Port-side Half

SAVANNAH Technical Staff Survey Unit Release Record Table 7 Scan Measurement Summary Low to High Range Average Scan ID d m/100 cm2 d m/100 cm2 SA-01 159.42 - 17612.37 8885.90 SA-02 549.48 - 1648.44 1098.96 SA-03 803.59 - 2058.19 1430.89 SA-04 485.86 - 2008.99 1247.43 SA-05 541.20 - 2603.70 1572.45 SA-06 639.60 - 1615.39 1127.50 SA-07 546.59 - 1930.33 1238.46 SA-08 224.46 - 1086.37 655.42 SA-09 179.57 -1050.46 615.02 SA-10 483.80 - 1705.59 1094.70 SA-11 305.26 - 1194.11 749.69 SA-12 356.80 - 1609.41 983.11 SA-13 639.60 - 2123.79 1381.70 The raw scan data with detector efficiencies are presented in Attachment 3.

8.

QUALITY CONTROL The implementation of survey specific QC measures included the collection of one replicate static measurement {STR-105-02-09-D) for analysis. The acceptance criteria for replicate static measurements is defined by NUREG-1576, MARLAP volume 1, Appendix C, Section C.4.2.2 Duplicate Analyses [11]. That section states that when the average of the two measurements is less than the UBGR, the control limit for the absolute difference between the two values is 4.24µMR. The value for µMR is equal to the shift divided by 10.

The shift is equal to the operational DCGLw, minus one half the operational DCGLw, or 26,150 dpm/100 cm2. Therefore, the control limit is equal to 11,087.6 dprn/100 cm2, as shown below.

Control limit= 26,150/10*4.24 = 11,087.6 dpm/100 cm2.

The results of the evaluation of the quality control measurement shows agreement between the original and duplicate measurements. See Attachment 4 for the results.

9.

INVESTIGATIONS AND RESULTS No investigation levels were triggered, and no investigations were performed as the result of the analysis of the collected data.

10.

REMEDIATION AND RESULTS No radiological remedial action was performed in this survey unit as a result of the FSS.

Survey Unit STR-105-02 Page 16 of33 Reactor Compartment Lower Level (5' - 23') Port-side Half

SAVANNAH Technical Staff Survey Unit Release Record

11.

CHANGES FROM THE FINAL STATUS SURVEY PACKAGE There were no addendums to the FSS package which was developed in accordance with STS-005-030, Preparation of Final Status Survey Packages [3].

12.

DATA QUALITY ASSESSMENT (DQA)

The DQO sample design and data were reviewed in accordance with MARAD procedure STS-005-033, Final Status Survey Data Assessment and Investigation [12] for completeness and consistency. Documentation was complete and legible. Scan surveys and the collection of static measurements were consistent with the DQOs and were sufficient to ensure that the survey unit was properly designated as Class 1.

The preliminary data review consisted of calculating basic statistical quantities ( e.g., mean, median, standard deviation). The mean and median values of the data were well below the Operational DCGLw. The survey unit data is presented graphically in a frequency plot and quantile plot presented in Attachment 6.

Although MARSSIM states that the Sign Test need not be performed in the instance that no measurements exceed the DCGL, the test was conducted to demonstrate coherence to the statistical principles of the DQO process. The Sign Test 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 results of the Sign Test are presented in Attachment 5.

13.

ANOMALIES No anomalies were observed during the performance of the survey.

14.

CONCLUSIONS Survey unit STR-105-02 has met the DQOs of the FSS package. The survey unit is properly classified as Class 1.

The sample data passed the Sign Test. The null hypothesis was rejected. Therefore, the survey unit meets the release criteria.

The dose contribution from residual activity in survey unit STR-105-02 is 0.14 mrem/yr TEDE, based on the mean activity of measurements used for non-parametric statistical sampling.

Survey unit STR-105-02 is acceptable for unrestricted release.

15.

REFERENCES

[1] "STS-005-035, Preparation of Survey Unit Release Records and FSS Final Reports".

Survey Unit STR-105-02 Page 17 of33 Reactor Compartment Lower Level (5' - 23') Port-side Half

SAVANNAH Technical Staff Survey Unit Release Record

[2] "STS-004-003, N.S. Savannah License Termination Plan".

[3] "STS-005-030, Preparation of Final Status Survey Packages".

[4] "NUREG-1575, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM), Revision 1, August 2000".

[5] "CR-003, STS-105-02, Historical Site Assessment, 2008".

[6] "CR-139, TSD 21-089, Calculations to Support NSS Surface Contamination DCGLs, Rev 01, September 2022".

[7] "NUREG-1757, Vol 2, Rev 1, Characterization, Survey, and Determination of Radiological Criteria".

[8] "STS-005-031, Calculation of The Number of Measurements For Final Status Surveys".

[9] "STS-005-032, Survey Unit Turnover and Control".

[10] "CR-164, TSD 23-126, "Calculation of Weighted Efficiencies and MDCs of Ludlum Detectors for Final Status Surveys on the NS Savannah", Rev 0 1 ".

[11] "NUREG-1576, Multi-Agency Radiological Laboratory Analytical Protocols Manual, MARLAP, July 2004".

[12] "STS-005-033, Final Status Survey Data Assessment and Investigation".

Survey Unit STR-105-02 Page 18 of33 Reactor Compartment Lower Level (5' - 23') Port-side Half

SAVANNAH Technical Staff Survey Unit Release Record

16.

ATTACHMENTS - Figures and Maps - Calibration Records - Static and Scan Data - Quality Control Assessment - Sign Test - Graphical Presentations Survey Unit STR-105-02 Reactor Compartment Lower Level (5' - 23') Port-side Half Page 19 of33

SAVANNAJ-1 Technical Staff Survey Unit Release Record - Figures and Maps Location of the Reactor Compartment-Lower Level (5' -23') Port-side Half Survey Unit STR-105-02 Reactor Compartment Lower Level (5' - 23') Port-side Half Page 20 of33

SA VANNA /I Technical Staff Survey Unit Release Record Reactor Compartment - Lower Level (5' - 23 ') Port-side Half Systematic and Judgmental Static Locations ad6

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=::===d 5=:: ~ '-------=--=--=--=--=--=--=--=--=--=--=--=--=--=--=--=--=--=--=--=--:::'.~==

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I

-$-STR-105-02-12 -$-STR-105-02-13

-$-STR-105-02-16-J B

ad3

-$-STR-105-02-01 #TR-105-02-02 -$-STR-105-02-0 G

D

_t:&STR-105-0 -15

~

TR-105-0 -17 D

6 lM!ad VSP Origin Point in Ship Coordinates:

Frame 100 6'9" Port of Centerline 5'0" above baseline NOTES:

"-R-105-02-0S.-:WTR-105-02~TR-105-02-10 RC L..,., le""I Ch M

TR-105-02-04 1h5TR-105-02-05 ~ STR-105-02-06 _th.

-W W

W STR-105-02-0t-+"

LEGEND:

-& VI>

!'iA IPLE LOCATI NS CREATE IN VISUAL, MIPLE PLAN NU~lBER OF SAMPLC 15 BOW b PLACFl,IENT l,IETHOD SYSTEIIIATIC sunacc Onq<1 Pont START LOC RANDOii!

0 2 5 s

C::::::j~==:3 1.1 I Survey Unit STR-105-02 Page21 of33 Reactor Compartment Lower Level (5' - 23') Port-side Half

SA VANNA/-1 Technical Staff Survey Unit Release Record Reactor Compartment-Lower Level (5' - 23') Port-side Half Scan Areas

~ !II B

5

.,nl SAJ.ll!

I I SMlli

~

LZ2J Survey Unit STR-105-02 D

eu """ o Reactor Compartment Lower Level (5' - 23') Port-side Half SA-t:'

D Page22 of33

S-1vANNA11 Technical Staff Survey Unit Release Record - Calibration Records l - -- d Calibration Certificate - ID Number: 25035102000. 20240305 -1 RSCS Customer: Matthew G Hunter Rodla~on Safety & Control Services Inc 93 Ledge Road Seabrook NH 03874 Instrument Ludlum Model 3002 Probe Model Ludlum 43-93 Precision Check Serial Number 25035102 Serial Number 421410 Test1 I

Test2 I

Test3 I

Mean I

Results 4.98 kcpm I

4.98 kcpm I

4.98 kcpm I

4.98 kcpm I

Accuracy Check Range Targ*J Value As Found As Left AUTO 500 Kcpm" 497 Kcpm" 497 Kcpm #

AUTO 50 Kcpm#

49.8 Kcpm#

49 8 Kcpm #

AUTO

!5 Kcpm #

4.98 Kcpm #

4.98 Kcpm" AUTO 0.5 Kcpm #

0.501 Kcpmll 0.501 Kcpm ~

Readings with

  • Indicate ranges where As-Found readings are >20'!1, o!Target value_

Readings with *

  • Indicate As-left readings are >10% of Target value Readings With # Indicate ranges were calibrated usrng a pulser Probe Isotope 43-93 421410 Tc-99 43-93 421410 Cs-137(Beta) 43-93 421410 Tc-99 43-93 421410 Cs-137(Bela) 43.93 421410 Cs-137(Beta) 43-93 421410 Tc-99 43-93 4214 10 Cs-137(Beta) 43-93 421410 Tc-99 Physical Checks Llghl Check of Sclnh atlon Probes Pass Outer Physical Check. Pass Tap Test Pass Audio Function Check Pass Cord check. Pass Cahbrallon Date Set Pass Efficiency 0.0269 C/0 (4 Pl) 0.0552 C/0 (4 Pl) 0.0176 C/0 (4 Pl) 0.0389 C/0 (4 Pl) 0.1 599 CID (4 Pl) 0 1164 C/0 (4 Pl) 0 1100 C/0 (4 Pl) 0 0744 C/0 (4 Pl)

Comments Calibrated with 20' C to C cable Customer Equipment 10 NIST Source 10 127356 Tc-99 127357 Cs*137(Beta) 127356 Tc-99 127357 Cs-137(Beta) 127357 Cs-137(Beta) 127356 Tc-99 127357 Cs-137(Beta) 127356 Tc-99 Electronics Checks High Voltage Geometry Flat Sul1ace Flat Sul1ace Flat Surface Flat Sul1ace Flat Surface Flat Surface Flat Surface Flat Sul1ace As Found 675 Volts Pass Source 10 Pulser 98756 Pulser 98756 Pulser 98756 Pulser 98756 Comment On Grate On Orate 3/4" Above Grate 314" Above Gra1e On Contact On Contact 314* Above Source 3/4" Aoove Source As Len 795 Volts Callbratod By Nico*

Wadlg QC Revl By Matthew Hunter Date Mar 05 2024 Expires Mar 05. 2025 QC Cate: Mar 05. 2024 A'JOOSpl\\t:IIC Coodn1<.-is T tn tokJh.1nce m tK>ns 01e bo.:..oct on tr sols f ino w,&hm $pecll kmlts v. 1th no 1educt.10n by the uncortJinty ol tho m :..uromont u~ olherw,se SIO'.ed this co~bfO!IOll was perfonned by RSCS Ol 93 Ledge Rd Seoblootc. NI~ Uta1.Z1119 foloMng NIST Tra b1e sources Pulse, '*M'.fl tent l, Oct 31 ?W)

Wll!ked on rn,t.rollon Nicole W I ho reported xpot1do<I uncennrnty 01 meosuromenl rs s l!ICJ os I slandonl unc.ertmnty 01 moosuromo,. mllltlj)l1'l<I by Ille CO\\lom<)e raaor k such !hot U covr.rtlQtt probnbll1ty ccnos1JOOO<t to opprounot ty pr.~

Unless ollleMise 5111181!

l,bfotJOOs per10mled,n coolormance IO tile followino documenb ANSI N323AB-2013 RSCS New 11 1pshire R Clive MoIenol Lac nse Num 38 IR RSC rolihnnon SOf\\lOC or performf>d in occordonce,..,,.ho RSC~ RoMllOl'I Pr $Cllon Program Manu, ond 1:ind1rd 0pem1,ng PtotOOur f yr Survey Untt STR-105-02 Page 23 of33 Reactor Compartment Lower Level (5' - 23') Port-side Half

S1vANNAJJ Technical Staff Survey Unit Release Record Calibration Certificate - ID Number: 25035110000. 20240305 -1 RSCS Customer: Manha" G Hunter Instrument Serial Number R11dl11tIon Safety & Control Services Inc Ludlum Model 3002 25035110 93 Ledge Road Seabrook NH 03874 Probe Model Serlat Number Ludlum 4 3-93 Precision Check Test1 Test2 Test3 Mean 4.98 kcpm 4.99 kcpm 4.99 kcpm 4.99 kcpm Accuracy Check Range Target Value As Found As Len AUTO 500 Kcpm#

498 Kcpm #

498 Kcpm #

AUTO 50 Kcpmi.

49.8 Kcpm;;

49.8 Kcpm #

AUTO 5 Kcpm#

4.98 Kcpm;;

4.98 Kcpm #

AUTO 05 Kcpm #

0.499 Kcpm #

0499 Kcpm #

Readings With

  • Indicate ranges "'here As-Found readings are >20°4 of Target value Readings with** indicate As-left readings are >1 0% of Target value Readings With # lndlcoto rongos wero collbroted us ng o pulser Probe lsoto e 43.93 421346 Tc-99 43.93 421346 Cs* 137(Beta) 43-93 421346 Tc-99 43-93 421346 Cs-137(Beta) 43-93 421346 Cs* 137(Beta) 43-93 421346 Tc-99 43-93 421346 Cs-137(Beta) 43-93 421346 Tc-99 Physical Cheeks Light Check of Scinblatlon Probes Pass Outer Physical Check Pass Audio Function Check* Pas Calibration Date Sel Pass Comments*

Customer Equipment ID Efflcienc 0.0299 C/0 (4 Pl) 0 0540 CID (4 Pl) 0 0199 C/0 (4 Pl) 0.0517 C/0 (4 Pl) 0.2075 CID (4 Pl )

0 1156 C/0 (4 Pl) 0 1326 C/0 (4 Pl) 0.0721 C/0 (4 Pi)

NIST Source ID 127356 Tc-99 127357 Cs-137(Beta) 127356 Tc-99 127357 Cs-137(Beta) 127357 Cs-137(Beta) 127356 Tc-99 127357 Cs-137(Beta) 127356 Tc-99 Electronics Checks High Volta e Oeomet Flat Surface Flat Surface Flat Surface Flat Surface Flat sunace Flat Surface Flat Surface Flat Surface As Found 677 Volts 421346 Results Pass Source 10 Pulsor 98756 Pulser 98756 Pulser 98756 Pulser 98756 Comment On Grate On Grate 314

  • Above Grate 314* Above Grate On contact On Contact 3/4" Above Source 314
  • Above Source As Len 715 Votts Calibrated By Nico e Wedlg jJ QC Revie 11 By Matthew Hunter Date Mar 05. 2024 Expires: Mar 05. 2025 QC Dote Mar 05, 2024 Atmosphe11c Cond T ampe, lure 7 I I F Humidity 36 0
  • B 1omeu1c Pr ssuIc 30 29 11, hQ In l<Jlofonc:e COfld,t,ons er on t t r su f,ng v,t111n poclfi 111,tt1 no r luc:IIOn by uncei n1y of II Unless otheJW st led

)IS a,\\blotJon was p,,rtormed by RSCS ot 93 Ledge Rd

, bJOOI.. NH uuhzmg the lollow,ng NI sou,ces Pulser 98750 - (Cai Due Oct 3 t 2024)

Wotke<I on 1b101100 N,cote Wodlg The reported xponded uncenJ11nty of m&asurement 1s stated os the standard uncerumiy of meosuremem mul11pb8d by th co emg loctor ~ such that tho covOIOQo probob11t corresponds lo opproXlfOOtoty 05*.

Unie<s Otherwise 8d c.1llbm1J011s l)l'rformed,n conformance 10 tile fotlOI nq documen ANSI N373A8-7013 RSCS New HampShor Rod ctJve Mll18t1JI I.I

,is. Num "l81R RS 5 I

011011 < MC S Of po 11000 Ill crord.inc *illh the RSC Ro *~lion PIO!.,~,n PrO!JI m Manuol orld Slondmd Operotong Procedures Cuhbruhm l.ubo!uuy r., 0JJ1!Iul8d In uccurdanc~ wiu, AN:sV

- L Z!>40- l-19'J4 RSC Inc hos b<>on O'\\""'se<I by ANAB ond m<>ets the req,nrement, of I. 0 I C 1107~ ;>O 1 I wh,le demons uog techn,cal coml)f' 1 e,~ lhe toeld of rot lllll1,on Ref 10 tile Sro of Armldotnuon AC-7079 tor,ntollll/lnon on th tvr>P of mlil,,m11)11 10 "'"'rl1 u1 orrred,1 *,on rpt,

~~~~ & C.,_Sef't il'IC I 1 1,.J LeOQlr lllMCS Nt,..,_.

4800 !-::--tut Cti0l1,:._,... :1 Survey Unit STR-105-02 Page24 of33 Reactor Compartment Lower Level (5' - 23') Port-side Half

S1 vANNA11 Technical Staff Survey Unit Release Record Calibration C*rtlflcate -10 Number: 25035147000 - 20240708. 0 RSCS Customer: Scott Ginter Redla on Safety & Contro Services Inc 93 Ledge Road Seabrook NH 03874 Instrument Ludlum Model 3002 Probe Model Ludlum 43-93 Serial Number 25035147 Serial Number 421411 Precision Check Test1 I

Test2 I

Test3 I

Mean I

Results 5.00 kcpm I

5.00 kcpm I

5.00 kcpm I

5.00 kcpm I

Pass Accuracy Check Range Target Value As Found As Left Source ID AUTO 500 Kcpm =

500 Kcpm ;;

500 Kcpm =

Pulser 66151 AUTO 50 Kcpm #

50 Kcpm;:

AUTO 5Kcpm :

5 Kcpm #

AUTO 0.5 Kcpm 11 0.5 Kcpm #

Readings with

  • Indicate ranges where As-Found readings are >20~ of Target value.

Readings with ** Indicate As-left readings are > 10% of Target value.

Readings with # Indicate ranges were calibrated using II pulser Probe lsot"""

43-93 421411 Cs-137(Beta) 43.93 4214 11 Tc-99 43-93 42141 t Cs-1 37(Beta) 43-93 421 411 Tc-99 43-93 421411 Cs-137(Beta) 43-93 4214 11 Tc-99 43-93 42 1411 Cs-1 37(Be1a) 43-93 4214 11 Tc-99 Physical Ch*cks Light Check of Scintllat,on Probes Pass Outer Physical Check* Pass Tap Tast Pass Audio Function Check* Pass Cord check. Pass Efficiency 0.1940 CID (4 Pl) 0.1231 CID (4 Pl) 0.1435 C/D (4 Pl) 0 0766 CID (4 Pl) 0.0 197 CID (4 Pl) 0.0097 CID (4 Pl) 0.0170 CID (4 Pl) 0.0064 CID (4 Pl)

Comments* Efficiencies Using 1 112* Fiberglass Grate Prollfded.

Customer Equipment ID NIST Source ID 127357 Cs-137(Beta) 127356 Tc-99 127357 Cs-1 37(Beta) 127356 Tc-99 127357 Cs-137(Beta) 127356 Tc-99 127357 Cs--1 37(Beta) 127356 Tc-99 Electronics Checks High Votage Calibrated By Jarod Fagan OC RevieN By Matthew Hunter Atm0Sphe11c Condiboffi 1 empemtu1e I 1 ti F 1 lum,d ty 4 0 % !!arome1nc f'1essur 29 88., Ilg 50 Kcpm,;

Pulser 66 151 5 Kcpm#

Pulser 66151 0.5Kcpm11 Pulser 66151 Geometry Comment Flat Surface On Source Flat Surface On Source Flat Surface 3/4" Above Source Fial Surface 3/4" Above Source Flat Surface On Grate Flat Surface On Grate Flat Surface 314" Above Grate Flat Surface 3/4" Above Grate As Found As Len 682 Votts 682 Volts Date Jul 08 2024 Expires* Jul 08. 2025 OC Date: Jul 08. 2024 In 101 cOOdl on,; re

<AC1 on 1 I rt>SU la ng 111ltn spoc1fi mits w th no mducl,on by unc

~

I too fl1'l ur nr The f conu, ~

her n relate only to the rtem cohbm!l!tl Unless othe,wise sto:ed this cohbraoon wos p,,rtonnoo by RSCS 93 LedQe Rd Soobrook. Nii tnA1zmg I~

NIST Traceable sources Pulsel 151 * (C Due Ap1 05 2025)

Workod oo

,bf uon J od F 1g Th reported exparded uncertau1ty ol I asuremem 1s s ted as the slllnda1d uncertainty of measurement mullJpbed by lhe w rage factor k such that the cover e probab1<ty corresponds to approxwnately Q5*

Unlessolhem,se stated colibrauons performed 11 confomumce to the lollowmg documents ANSI N323AB-2013 R C ew ltompshtre RodlOOC e

Malenol l.Jceose Nl.mbe1 38 IR RSCS obmtion seMC85 ore pertonned,n occordance w,u, the R C!:>

,ntion PIO!ecuon Program Monuol ond tanda!d Opemhng Procedures Cohblouon Lobomtory is operoted., occordJnce,-,th ANSI L 2!>40 1994 I 2 f ri Survey Umt STR-105-02 Page 25 of33 Reactor Compartment Lower Level (5' - 23') Port-side Half

S1 v ANNAJ, Technical Staff Survey Unit Release Record l

Calibration Certlflcahl

  • ID Number: 25017648000
  • 2024070\\J
  • 0 RSCS Customer: Scott Gonlef Instrument Serial Number

, Inc Ludlum Mod I 3002 25017648 Rad,aUon Sar ty & Control Serv 93 Ledge Road Seabrook NH 03874 Probe Modal Serial Number Ludlum 3 -93 Precision Check Te 11 Test2 Test3 Mean 50.00kcpm 49.80 kcpm 49.80 kcpm 49.87 kcpm Accuracy Check Re 0

Ta et Value Aa Found As left AUTO 500Kcpm#

499Kepm#

499Kcpm#

AUTO 50 Kcpm#I 50 Kcpm#

50Kcpm#

AUTO SKcpm#

4 99 Kcpm#

4 99 Kcpm #

AUTO OSK 0.505 0505 Kcpm#

Reading with

  • indicate ranges where As-Found readings are >20'-' of Target value.

R&adlngs with ** Indicate A *I n readings are >10% or Target value Readings. with # lnd,Cllt ranges were caffbrated using a pul Probe lsoto e 43-93 379676 Cs 137(Beta) 43-93 379676 Tc-99 43 93 379676 Cs-137(Beta) 43-93 379676 Tc-99 43-93 379676 Cs-137(Beta) 43.93 379676 Tc-99 43.93 379676 Cs-137(Bete) 43.93 379676 Tc-99 43-93 379676 Sr/Y-90 43-93 379676 Th-228 Physical Checks Light Check of Sci-,til Uon Probes. Pass Outer Physical Chee

  • Pass Tap T st PaH Audio Fu-,c-tlon Check: Pass Cord Check. Pes.s Commen Cu tamer Equipment ID:

Etflclenc 0.1916 C/0 (4 P1) 0.1103 CJD (4 Pt) 0 1351 C/0 (4 Pt) 0.0733 CID ( Pi) 0.0196 CJD (4 Pl) 0.0093 CJD( Pl) 0.0152 CID (4 Pl) 0.0063 CJD (4 Pl) 0.2165 CID (4 Pl) 0.0962 CID (4 Pi r

NIST Source ID 127357 Cs-137(Beta) 127356 Tc-99 127357 Cs-137(Beta) 27356 Tc-99 127357 Cs-137(Beta) 127356 Tc-99 127357 Cs-137(8 le) 127356 Tc-99 TB-173 Sr/Y-90 T6-691 Th-230 Eloctronlcs Checks HI h Voltage Geomet Flat SI.Wface Flot Surface Flat Surface Flat Surface Flat Surf cc Fiat Surfeco Flat Surface Flat Surface 1 cm 1 cm Found 640 VOita 379676 Results Pass Source 10 Pulser 98756 Pulser 98756 Pul6er 98756 Pulsor 98756 Comment On Source On Source 3/4' Abav &ource 3/4' Abave Source On Grate OnGrel 3/4

  • Above Grat 3/4" Abov Grat As Left 765 Vons C hbrated By Jarod Fagen QC Rev w By Matthew Hunter Dal Jul 09, 2024 Explfes; Jul 09, 2025 QC Dat : Jul 09, 2024 Alrro pherlc Cond"too,
  • lempeiature, 71.1 ' F, Humklrty 42 O *,., BIIIOmOITIC PretllU'e:29.96 lnhlg In lol<<ance cond ons are based on leSI resutts 11-r,g v.1 n apeo '" Im w'h no r-.cll an by the unr:erlalnty of th IUretllffll TIM ra...C cx,-,lained here!* ral1 orly 10 tho c:al,bra\\ed Unlen olhen,lse r.ated. this cal lnt!OII w s performed by RSCS et 93 Ledge Rd.

abrook. NH uti1z,ng the followwlg NIST Tri blUO\\lteel P"8er 98758 - (Cal Due: Oct 31 2024)

WO!lied on callbnllJon J1,od Fagan The raponed JCl)llnded uneena.,ty of meaturement lo lllttd 1N mn<ard uncert ty of measurement m iphed by coverage facto< k ouch tnat

!hi coverage p,obab y ~po,,ds to app,o>drnat 'Y 95 Uni olherw,ge MIiied ~lib<ll~on* pcrlorned In conlormanc:e to

  • folowng documenlJ ANSI N323AB-2013, RSCS New H mpehl*e RadlOIICtlvw 1/2 J rt Survey Umt STR-105-02 Page 26 of33 Reactor Compartment Lower Level (5' - 23') Port-side Half

S1vANNA11 Technical Staff Survey Unit Release Record Calibration Certlllcate - ID Number: 25017651000. 20240305.1 RSCS Customer: Matthew G Hunter Instrument Serial Number Radiation Safety & Control Services Inc Ludlum Model 3002 25017651 93 Ledge Road Probe Model Serial Number Seabrook NH 03874 Ludum 43.93 312635 Precision Check Test1 Test2 Test3 Mean Resuits 5.00 kcpm 5.01 kcpm 5.00 kcpm 5.00 kcpm Pess Accuracy Check Ran e Tar et Value As Found As Left Source ID AUTO 500 Kcpm:

500 Kcpm ti 500 Kcpm #

Pulser 98756 AUTO so Kcpm=

49.9 Kcpm #

49 9 Kcpm #

Pulnr98756 AUTO 5 Kcpm#

5 Kcpm;;

AUTO 0.5Kcpm;:

05Kcpmti Readings with

  • Indicate ranges where As-Found readings are >20% of Target value.

Readings with *

  • Indicate As-left readings are > 10% of Target value.

Readings with ti Indicate ranges were calibrated using a pulser Probe lsoto e 43.93 312635 Tc-99 43.93 312635 Cs-137(Beta) 43.93 312635 Cs-137(Beta) 43.93 312635 Tc-99 43.93 312635 Cs-137(Beta) 43.93 312635 Tc-99 43-93 312635 Cs-137(BetaJ 43.93 312635 Tc-99 Physical Checks Light Check of Scintila on Probes* Pass Outer Phys cal Check Pass Tap Test Pass Audio Funcbon Check Pass Comments:

Customer Equipment ID Calibrated By Nicole Wedlg Efficlenc NIST Source ID 0.0249 CID (4 Pl) 127356 Tc-99 0.0546 C/D (4 Pl) 127357 Cs-137(Beta) 0.0471 CID (4 Pl) 127357 Cs-137(Beta) 0.0193 CID (4 Pl) 127356 Tc-99 0.1693 CID (4 Pl) 127357 Cs-137(Bela) 0.0876 CID (4 Pl) 127356 Tc-99

0. 1237 CD (4 Pl) 127357 Cs-137(Beta) 0.0537 CID (4 Pl) 127356 Tc-99 Electronics Checks Hlgh Voltage OC Rev1e,y By Matthe"'

Hunter All ph!:11(; COl'llhtoun

  • Ten I tu, 71 I F Hun,ty ~ 0 8-11on1Cl11C Pl

"' '.lO 29 101,g 5 Kcpm #

Pulser 98756 05Kcpm#

Pulser 98756 Geomet Comment Fial Surface On Grate Flat Surface On Grate Flat Surface 314" Above Grate Flat Surface 314" Above Grate Fial Surface On Contact Flat Surface On Contact Flat Surface 314* Above Source Flat Surface 314" Above Source As Found 710 Volts 775 Volts Date Mar 05, 2024 Expires Mar 05. 2025 QC Date Mar 05. 2024 In tolerance condluons re ba"8d on test results I ng,_,thin spec.died i1mts wnh no reducuon by the uncenatnty el U,e me

,emenl Unless other.,,se SI *ed, thrs calibration -,as pertormed by RSC 93 Ledqe Rd Seabrook NI I uulmng the follow llQ NIST T mcenble sources Pul 96756

(

  • Due Oct 31 2024)

Worked on Cllllbm on

,cole Wedlg The repor1ed xponded uncenoIn1Y of meosurement 1s stoled os th stondord unceru,niy of meosurement mull,pl,ed by coverooe loctor k such !hot tho ctN rn<J prnl 1)11,!y car r<*r>l, lo opp1oxwnolnly n~*

ll> l)Uflonnod on ANSI N323AB 2013 RSCS Now H m h*O RoJ11 cuve SCS cehbr !inn RSC'S Radnhnn P1 h,-., Plogmm Monool ond C fibrat, 1n. ccor.1nc v.11h AN I c;1 Z'40-1-lfl!J4 I scs In ANABondmeetsthereQUl(001AfllSOflS01[

l7025l017v.tule mon trD toctnailcompet nce,nlhelieldol ro!1hmt1on Refer to the Scope ol Accrf'dItnt,on AC-:>o79 lor il\\tormnuon on the IYl'8'i of 1obrar,ons to which this ccred,1011011 Dl)plI I~

b t Survey Umt STR-105-02 Page 27 of33 Reactor Compartment Lower Level (5' - 23') Port-side Half

SAVANNAHTechnical Staff Survey Unit Release Record - Static Data Count Rate Total Weighted Eff Meter ID Measurement ID (cpm)

(c/d) 25017651 STR-105-02-01 73 0.1549 25017651 STR-105-02-02 81 0.1549 25017651 STR-105-02-03 77 0.1549 25017651 STR-105-02-04 54 0.1549 25017651 STR-105-02-05 60 0.1549 25017651 STR-105-02-06 87 0.1549 25035147 STR-105-02-07 157 0.1815 25017651 STR-105-02-08 75 0.1549 25017651 STR-105-02-09 66 0.1549 25035147 STR-105-02-10 183 0.1815 25017651 STR-105-02-11 111 0.1549 25017651 STR-105-02-12 72 0.1549 25017651 STR-105-02-13 69 0.1549 25017651 STR-105-02-14 75 0.1549 25017651 STR-105-02-15 228 0.1549 25017651 STR-105-02-16-J 81 0.1549 25017651 STR-105-02-17-J 162 0.1549 25017648 STR-105-02-09-D 130 0.1775 Note: Meter ID 25035147, Meter ID 25017648, and Meter ID 25017651 are connected to a Ludlum model 43-93 detector with an area of 100 cm2.

Survey Unit STR-105-02 Page 28 of 33 Reactor Compartment Lower Level (5' - 23') Port-side Half

SAVANNAH Technical Staff Survey Unit Release Record Meter ID 25017651 25035147 25017651 25035147 25035147 25035102 25035110 25035147 25035110 25017651 25035110 25035110 25017651 25035147 25017651 25017651 25035110 25017651 25035147 25035147 25035110 - Scan Data Min/Max Range Average Location (cpm)

(cpm)

SA-01 83/1600 841.50 SA-01 64/1400 732.00 SA-01 59/188 123.50 SA-01 21/141 81.00 SA-01 100/2320 1210.00 SA-02 57/171 114.00 SA-03 98/251 174.50 SA-04 64/220 142.00 SA-04 85/245 165.00 SA-05 76/290 183.00 SA-05 66/290 178.00 SA-06 78/197 137.50 SA-07 64/215 139.50 SA-07 72/228 150.00 SA-08 25/121 73.00 SA-09 20/117 68.50 SA-10 59/208 133.50 SA-11 34/133 83.50 SA-12 61/212 136.50 SA-12 47/208 127.50 SA-13 78/259 168.50 l - ---

-+ tr Total Weighted eff (c/d) 0.1114 0.1317 0.1114 0.1317 0.1317 0.1037 0.1220 0.1317 0.1220 0.1114 0.1220 0.1220 0.1114 0.1317 0.1114 0.1114 0.1220 0.1114 0.1317 0.1317 0.1220 Note: Meter ID 25035102, Meter ID 25035110, Meter ID 25035147, and Meter ID 25017651 is connected to a Ludlum model 43-93 detector with an area of 100 cm2.

Survey Unit STR-105-02 Page29 of33 Reactor Compartment Lower Level (5' - 23') Port-side Half

SAVANNAHTecbnical Staff Survey Unit Release Record 1 - - -- 1 t - Quality Control Assessment Measurement Initial measurement Replicate measurement Avera~e Absolute Value of the difference Condition d m/100 cm2 Avera e < 52 300 Survey Unit STR-105-02 Absolute value of the difference 306.56 Reactor Compartment Lower Level (5' - 23') Port-side Half Value ( dpm/100 cm2) 426.02 732.58 579.30 306.56 Control Limit d m/100 cm2 11087.6 Result --

Pass Page 30 of33

SAVANNAHTechnical Staff Survey Unit Release Record - Sign Test Measurement Result DCGLw - Result ID

( dpm/100 cm2)

(dpm/100 cm2)

STR-105-02-01 471.21 69228.79 STR-105-02-02 522.85 69177.15 STR-105-02-03 497.03 69202.97 STR-105-02-04 348.57 69351.43 STR-105-02-05 387.29 69312.71 STR-105-02-06 561.58 69138.42 STR-105-02-07 864.91 68835.09 STR-105-02-08 484.12 69215.88 STR-105-02-09 426.02 69273.98 STR-105-02-10 1008.14 68691.86 STR-105-02-11 716.50 68983.50 STR-105-02-12 464.75 69235.25 STR-105-02-13 445.39 69254.61 STR-105-02-14 484.12 69215.88 STR-105-02-15 1471.72 68228.28 STR-105-02-16-J 522.85 69177.15 STR-105-02-17-J 1045.70 68654.30 Parameter Result Number of Measurements 17 NumberofS+

17 Critical Value 12 Meets I Doesn't Meet Acceptance Criteria Meets Survey Unit STR-105-02 Reactor Compartment Lower Level (5' - 23') Port-side Half 1 - - -- b Yi Sign

+1

+1

+1

+1

+1

+1

+1

+1

+1

+1

+1

+1

+1

+1

+1

+1

+1 Page 31 of33

SAVANNAH Technical Staff Survey Unit Release Record - Graphical Presentations Quantile Plot of Gross Activity Concentration 1750 1500

"' § 1250 0

0......

8

.g. 1000 u c::

0 u 750

(.)

500 250 0%

10%

20%

30%

40%

50%

60%

70%

80%

Survey Unit STR-105-02 Reactor Compartment Lower Level (5' - 23') Port-side Half l -- -- d 1 Yi 90%

100%

Page 32 of33

SAVANNAH Technical Staff Survey Unit Release Record Histogram Survey Unit Number: STR-105-02 Reactor Compartment -

Survey Unit Name: Lower Level (5' - 23')

Port-side Half 9

8 7

6 3

2 0

489 629 770 910 1051 1191 Upper end value (dpm/100 cm2)

Survey Unit STR-105-02 Reactor Compartment Lower Level (5' - 23') Port-side Half 1331 1472 Page 33 of33

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