ML25328A163

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Us Dept of Transportation - Nuclear Ship Savannah, Survey Unit Release Record Survey Unit STR-103 Containment Vessel (Cv) - 3rd Level (D Deck)
ML25328A163
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-103 Containment Vessel (CV) - 3rd Level (D Deck)

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 and COMPLIANCE MANAGER REVIEW/ DATE:

SAFETY REVIEW COMMITTEE SUBMITTED/ APPROVED LICENSE TERMINATION PLAN MANAGER REVIEW/ DATE:

Survey Unit STR-103 Containment Vessel (CV) - 3rd Level (D Deck)

D. Roberson Douglas Roberson Digitally signed by D. Roberson Date: 2025.03.12 11 :18:36 -05'00' Date Pete Hollen beck Digitally signed by Pete Hollenbeck Date: 2025.03.12 14:28:34-04'00' Pete Hollenbeck, CHP Date Soeuth Caleb Soeun Soeuth C. Soeun James Reese, CHP, RRPT James Reese Digitally signed by Soeuth Caleb Soeun Date: 2025.03.17 13:00:43 -04'00' Date Digitally signed by James Reese, CHP, RRPT Oate: ~Q~S.Q!.18 Q9:~S:Q8 Q7'QQ' Date I

Digitally signed by Daniel R.

Danie R. Mihalik Mihalik Date: 2025.03.19 15:46:11 -04'00' Daniel Mihalik Date JO h n Os b Orne ~~~ally signed by: John Osborne DN: CN = John Osborne LCM email LCM

= jmosborne@nsss.llc C = AD Date: 2025.04.29 15:53:55 -05'00' John Osborne Date 3/19/2025 3/28/2025 Submitted Approved 9/2/2025 Date Page 2 of 32

SAVANNAH Technical Staff Survey Unit Release Record TABLE OF CONTENTS l - - -- d

  • krl
1.

EXECUTIVE

SUMMARY

.................................................................................................... 6

2.

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

3.

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

4.

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

5.

SURVEY DESIGN............................................................................................................... 11

6.

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

7.

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

8.

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

9.

INVESTIGATIONS AND RESULTS................................................................................ 17

10. REMEDIATION AND RESULTS...................................................................................... 17
11. CHANGES FROM THE FINAL STATUS SURVEY PACKAGE................................. 17
12. DATA QUALITY ASSESSMENT...................................................................................... 17
13. ANOMALIES........................................................................................................................ 17
14. CONCLUSIONS................................................................................................................... 18
15. REFERENCES..................................................................................................................... 18
16. ATTACHMENTS................................................................................................................. 19 Survey Unit STR-103 Page 3 of32 Containment Vessel (CV) - 3rd Level (D Deck)

SAVANNAH Technical Staff Survey Unit Release Record LIST OF TABLES l - --- i f t Table 4 Radionuclide Fractions and Normalized Fractions............................................... 8 Table 4 15 mrem/y DCGLs for ROC and Ni-63.................................................................. 9 Table 4 Re-normalized Co-60 and Cs-137 Fractions........................................................ 10 Table 4 Operational DCGLs................................................................................................ 10 Table 5 STR-103 Systematic Measurement Designations................................................. 12 Table 5 Scanning Coverage................................................................................................. 12 Table 5 Investigation Levels................................................................................................ 13 Table 7 Summary of Systematic, Judgmental, and QC Static Measurements................ 15 Table 7 Basic Statistical Properties of Static Measurement Population.......................... 15 Table 7 Scan Measurement Summary................................................................................ 16 Survey Unit STR-103 Page 4 of32 Containment Vessel (CV) - 3rd Level (D Deck)

S AVANNA H Technical Staff Survey Unit Release Record LIST OF ACRONYMS AND ABBREVIATIONS ALARA As Low As Reasonably Achievable CV Containment Vessel CR Contractor Report DQO Data Quality Objective DCGL Derived Concentration Guideline Level ETD Easy-to-Detect FSS Final Status Survey HSA Historical Site Assessment HTD Hard-to-Detect IC Insignificant Dose Contributors LBGR Lower Bound of the Gray Region LTP License Termination Plan MARAD Maritime Administration MARLAP Multi-Agency Radiological Laboratory Analytical Protocols MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual MDC Minimum Detectable Concentration NSS Nuclear Ship SA VANNA H QC Quality Control RASS Remedial Action Support Survey ROC Radionuclides of Concern TEDE Total Effective Dose Equivalent UBGR Upper Bound of the Gray Region VSP Visual Sample Plan Survey Unit STR-103 Containment Vessel (CV) - 3rd Level (D Deck)

Page 5 of32

SAVANNAH Technical Staff Survey Unit Release Record

1.

EXECUTIVE

SUMMARY

This Survey Unit Release Record for survey unit STR-103, Containment Vessel (CV) -

3rd Level (D Deck), has been generated in accordance with Maritime Administration (MARAD) procedure STS-005-035, Preparation of Survey Unit Release Records and FSS Final Reports, Reference (a) and satisfies the requirements of Section 5.10 of the Nuclear Ship SAVA AH (NSS) License Termination Plan [L TP], STS-004-003, Revision 1, Reference (b ).

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, Reference (c), the NSS LTP, and with guidance from NUREG-1575, Revision 1, Multi-Agency Radiation Survey and Site Investigation Manual (MARS SIM), Reference (d).

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 (P) 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 (2) 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-103 show that the maximum gross activity concentration among all the final systematic and judgmental measurements is equal to 9,197.32 dpm/100 cm2, which is 17.59% 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-103 is acceptable for unrestricted use.

The mean gross activity concentration among all the final systematic and judgmental measurements is equal to 1,819.93 dpm/100 cm2, which is 2.61% ofthe 15 mrem/y gross activity DCGLw of 69,700 dpm/100 cm2. The mean gross activity concentration is equal to 0.39 mrem/y for the survey unit.

2.

SURVEY UNIT DESCRIPTION STR-103 is an impacted Class I survey unit. The CV housed the reactor plant and some supporting systems. The 3rd level gives access to the heat exchanger steam drums manways and the platform for the pressurizer as well as the reactor coolant pumps and motors. The survey unit consists of the internal surfaces of the CV shell, ring stiffeners, and the deck/new fiberglass grating from the 23-foot to the 32-foot elevation. Based upon Computer Aided Design drawings, the 3rd level deck surface area is approximately 58.02 square meters (58.02 m2); the total surface area, including the shell, is approximately 204.90 m2; this includes the shell surface above 2 meters. Refer to Attachment 1 of this report for figures and maps depicting survey unit STR-103.

Survey Unit STR-103 Page 6 of32 Containment Vessel (CV)- 3rd Level (D Deck)

SAVANNAH Technical Staff Survey Unit Release Record

3.

CLASSIFICATION BASIS 1 rt Based on the NSS Historical Site Assessment [HSA] Reference ( e ), survey unit STR-103, identified as survey unit 101 A 1 in the HSA, was identified as a Class 1 structure survey unit. Primary coolant leaks were experienced from time to time, as was typical of nuclear power plants of the era. Coolant was released as steam condensed and drained to the bottom of the containment vessel, from which it was collected in tank PD-T4, the containment drain tank. In August of 1966, a leak produced low-level contamination in the containment vessel that was decontaminated using a detergent solution. In 1968, a primary system leak from a pressure relief system isolation valve occurred. In 1969, a primary system leak from a control rod drive buffer seal was observed. On another occasion in 1969, 3,500 gallons leaked from a primary coolant pump vent pipe. Based upon a review of the historical information, the results of the characterization survey data, the 2024 Remedial Action Support Survey (RASS) STR-103-RASS-0 1-Rev 0, and the completion of a final Survey Unit Classification Worksheet, the correct final classification of survey unit STR-103 is 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 bo_undaries, that the primary objective of the survey is satisfied. The DQO process is described in the NSS LTP. The appropriate design for a given survey was developed using the DQO process as outlined in STS-005-030, Reference (c).

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-103 does not exceed the release criteria specified in the LTP and that the potential dose from residual radioactivity is As Low As Reasonably Achievable (ALARA).

MARAD Contractor Report (CR)-139, Calculations to Support NSS Surface Contamination DCGLs, Reference (t), established the basis for an initial suite of potential Radionuclides of Concern (ROC) for decommissioning. Insignificant dose contributors Survey Unit STR-103 Page 7 of32 Containment Vessel (CV)- 3rd Level (D Deck)

SAVANNAH Technical Staff Survey Unit Release Record (IC) were determined consistent with the guidance contained in Section 3.3 of NUREG-

1757, Volume 2,

Revision I,

Consolidated Decommissioning Guidance Characterization, Survey, and Determination of Radiological Criteria, Reference (g). In all analyses, Cs-137 and Co-60 contribute 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-13 7 and Co-60surrogate-L TP Chapter 6, Section 6.13 discusses the process used to derive the 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 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 l.63E-02 l.63E-02 Ni-63 5.40E+00 9.00E-01 9.00E-01 Sr-90 9.22E-06 1.54E-06 Tc-99 l.27E-04 2.11 E-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 4.81 E-07 8.01 E-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. Table 4-2 on the next page presents the 15 mrem/y DCGLw for Co-60, Ni-63 and Cs-13 7 from Chapter 6 of the L TP.

Survey Unit STR-103 Page 8 of32 Containment Vessel (CV)- 3rd Level (D Deck)

l ---

SAVANNAHTechnical Staff Survey Unit Release Record Table 4 15 mrem/y DCGLs for ROC and Ni-63 Radionuclide DCGLw (dpm/100cm2)

Co-60 2.37E+04 Ni-63 2.53E+08 Cs-137 l.20E+05 Nickel-63 is a Hard-to-Detect (HTD) radionuclide. To account for Ni-63, the Easy-to-Detect (ETD) radionuclide Co-60 will be used as a surrogate.

The surrogate DCGL is computed as:

DCGL DCGLETD X DCGLnTD surrogate =

(f HTD:ETvxDCGLETv)+DCGLnTD Equation 1 Where:

DCGLEm DCGLHTo FHTD:ETD the DCGL for the easy-to-detect radionuclide the DCGL for the hard-to-detect radionuclide the activity ratio of the hard-to-detect radionuclide to the easy-to-detect radionuclide Using the data in Table 4-1, the Ni-63/Co-60 ratio equals 55.3. Solving Equation 1 using the DCGLs for Co-60 and Ni-63 in Table 4-2 and the Ni-63/Co-60 ratio of 55.3 is shown below.

253E+08 2

DCGLco-60 surrogate= 2.37E + 04 X (

)

= 2.36E+04 dpm/100 cm 55.3 x 2.37E+04 +2.53E+08 A gross activity DCGLw has been established, based on the representative radionuclide mix, as follows:

Where:

n DCGLn Gross Activity DCGLw =

1 fraction of the total activity contributed by radionuclide n the number of radionuclides DCGL for the ROC Equation 2 Of the three radionuclides, only Co-60 and Cs-137 can be detected by gross activity measurements. The normalized fractions for both radionuclides in Table 4-1 must be re-normalized for use in Equation 2. Table 4-3 on the next page presents the re-normalized fractions for each radionuclide.

Survey Unit STR-103 Page 9 of32 Containment Vessel (CV)- 3rd Level (D Deck)

L SAVANNA H Technical Staff Survey Unit Release Record Table 4-3-Re-normalized Co-60 and Cs-137 Fractions Normalized Only Co-60 Re-sum of and Cs-137 normalized Nuclide fractions Fractions Fractions C-14 5.61 E-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.l lE-05 Ag-108m 1.38E-04 Cs-137 7.61E-02 7.61E-02 8.24E-01 H-3 3.21E-04 Fe-55 I.35E-03 Am-241 9.66E-08 Pu-239/240 8.0lE-08 Totals l.00E+00 9.24E-02 l.00E+00 Solving Equation 2 using the re-normalized Co-60 and Cs-137 fractions and the Co-60 surrogate DCGL is shown below.

Gross Activity DCGLw = 1.?6E-l 1 8_24E-l = 6.97E+04 dpm/100 cm2*

2.36E+04 + 1.20E+05 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 DCGLw (dpm/100cm2)

Co-60 1.77E+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. STS-005-030, Reference (c) states that a Minimum Detectable Concentration (MDC) below 10% of the DCGL is preferable and up to 50% is acceptable. Because the Survey Unit STR-103 Page 10 of32 Containment Vessel (CV)- 3rd Level (D Deck)

SAVANNA H Technical Staff Survey Unit Release Record l

d background is low on the NSS, the MDCs 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 Test was determined in accordance with MARAD procedure STS-005-031, Calculation of the Number of Measurements for Final Status Surveys, Reference (h). The relative shift 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 the relative shift should range between one (I) and three (3). If the relative shift is less than one (1 ), or greater than three (3), then the value of two (2) will be used for the relative shift.

A RASS survey was performed between April 10, 2024 and April 15, 2024. Thirty (30) static measurements and 30 smears were collected. No smears had alpha activity greater than the minimum detectable activity. The maximum beta activity was 135.30 dpm/100 cm2. The average total surface activity concentration and standard deviation of the measurements was 2,447 and 3,047 dpm/100 cm 2, respectively. Because the activity concentration is low, the LBGR was set to half the operational DCGLw. The relative shift for survey unit STR-103, is based upon the RASS survey results and was calculated as follows:

52,300-26,150 Relative Shift (~cr) = -----= 8.58 3,047 Because the calculated relative shift was greater than three (3), the value of two (2) was used as the adjusted relative shift. Both the Type I error, or a value, and the Type I1 error, or~ value, were set at 0.05. The sample size from STS-05-031, Reference (h), that equates to the Type I and Type II error of 0.05 for use with the Sign Test is a minimum number of fixed measurements value of fifteen (15). Fifteen (15) total systematic measurements were used in the survey design for survey unit STR-103.

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 on the next page lists the systematic measurements to be collected for FSS of survey unit STR-103.

Survey Unit STR-103 Page 11 of32 Containment Vessel (CV)- 3rd Level (D Deck)

SAVANNAH Technical Staff Survey Unit Release Record J - --- + -hrl Table 5-l -STR-103 Systematic Measurement Designations Label LX(m)

LY(m)

Surface STR-103-01

-5.66 2.28 CY Shell STR-103-02

-8.24 1.30 CV Shell STR-103-03

-11.73 1.30 CY Shell STR-103-04

-14.79 l.63 CV Shell STR-103-05

-3.09 1.22 CV Shell STR-103-06

-0.39 1.94 CV Shell STR-103-07

-21.03 0.34 CV Shell STR-103-08 2.30 0.71 CV Shell STR-103-09 19.78 2.49 CY Shell STR-103-10 5.25 1.37 CV Shell STR-103-11 8.20 0.24 CV Shell STR-103-12 11.73 0.23 CV Shell STR-103-13 15.08 0.62 CV Shell STR-103-14 17.37 2.60 CV Shell STR-103-15 13.34 1.07 Grating The implementation of Quality Control (QC) measures is referenced in L TP 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-103-12 was chosen for the replicate measurement. ln addition, the survey package also specified to perform QC operability checks of field instruments both prior to and after collection of the measurement.

The survey package also specified collection of two (2) judgmental measurements to augment the systematic measurements. The locations of these two measurements were to be determined by the technicians or the field supervisor. Those two judgmental measurements are identified as STR-103-16-J and STR-103-17-J. Those locations are documented on the field forms.

For this Class 1 structure survey unit, the "Scanning Coverage" are those levels specified in L TP 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-103, six (6) scan area was established SA-01 through SA-06. The survey package stated to scan I 00% of the accessible area in each scan area. Refer to for figures and maps depicting the measurement and scan locations in survey unit STR-103.

Survey Unit STR-103 Page 12 of32 Containment Vessel (CV)- 3rd Level (D Deck)

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 L TP 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 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.

SURVEY IMPLEMENTATION For survey unit STR-103, compliance with the unrestricted use 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 the beta mode. Surface scans were also performed utilizing the Ludlum 43-37 large area gas proportional detector connected to a Ludlum 3002 operating in the beta mode.

Prior to performing the survey, a walkdown of the survey unit was performed per MA RAD procedure STS-005-032, Survey Unit Turnover and Control, Reference (i). 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-103-00-00, which included DQOs, survey design, detailed FSS instructions, survey maps and survey forms. FSS field activities were projected to take seven (7) 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 (6) days to complete and were performed on July 15, 2024, through July 17, 2024, and July 22, 2024, through July 24, 2024. When placing the judgmental measurement locations on the survey map, based upon the recorded coordinates, the locations were not on the deck grating. On January 16, 2025, reproducible coordinates and static measurements were collected for STR-103-16-J and STR-103-17-J.

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.

Survey Unit STR-103 Page 13 of32 Containment Vessel (CY)- 3rd Level (D Deck)

SAVANNAH Technical Staff Survey Unit Release Record l

1 rt The fifteen (15) systematic static measurement locations were marked based on the dimensions provided on the survey map. Two (2) judgmental measurement locations were selected and marked as per the sample plan. A 1-minute static measurement was acquired at each location with the detector in contact with the surface.

Five of the six (6) planned scan areas, SA-0 I through SA-04 and SA-06, were scanned, resulting in 100% of the total surface area being scanned. The scan area SA-05 grating platform was removed in its entirety during decommissioning. The total scan area meets the scan coverage requirements for a Class 1 area as shown in L TP 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 (I) replicate static measurement. The random location of the replicate measurement was STR-103-12 and identified as STR-103-12-D. That measurement was collected with a different instrument but the same make and model used for the original measurement.

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-l 37 comprise the NSS fingerprint. This is documented in CR-164, Reference U).

For example, (derived from NUREG-1507) if the 41t contact Tc-99 efficiency is 0.1002 c/d and the 41t 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 I-minute count was 95 cpm and was rounded up to l 00 cpm. The painted surface contact detector weighted efficiency is equal to 0.0995 c/d and the fiberglass grating contact detector weighted efficiency is equal to 0.015 I c/d. Using L TP Equation 5-6 (derived from NUREG-1507), in which the count time and background count times are equal, results in an MDC for I-minute static measurements equal to 497.3 dpm/100 cm2 and 3,278.5 dpm/100 cm2, respectively. The value for flat surface contact is I% of the operational DCGLw and less than 1 % of the gross activity DCGLw, and the grating contact value is 6.3% of the operational DCGLw and 4.7% of the gross activity DCGLw.

Table 7-1 on the next page presents the activity concentration for all final static measurements.

Survey Unit STR-103 Page 14 of 32 Containment Vessel (CV)- 3rd Level (D Deck)

SAVANNAH Technical Staff Survey Unit Release Record Table 7 Summary of Systematic, Judgmental, and QC Static Measurements Activity Concentration Measure ment ID d m/100 cm2 STR-1 03-01 843.86 STR-1 03-02 763.50 STR-1 03-03 572.62 STR-1 03-04 683.13 STR-1 03-05 592.71 STR-1 03-06 733.36 STR-1 03-07 602.76 STR-1 03-08 652.99 STR-1 03-09 723.31 STR-1 03-10 823.77 STR-1 03-11 843.86 STR-1 03-12 1044.78 STR-1 03-13 884.05 STR-1 03-14 773.54 STR-1 03-15 4570.02 STR-10 3-16-J 9197.32 STR-10 3-17-J 6633.22 STR-10 3-12-D 989.12 The raw static data with detector efficiencies are presented in Attachment 3.

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

Table 7 Basic Statistical Properties of Static Measurement Population Paramet er Value Units Minimum Meas urement 572.62 d m/100 cm2 Maximum Mea surement 9197.32 d m/100 cm2 Mean 1819.93 d m/100 cm2 Median 773.54 d m/100 cm2 Standard Dev iation 2516.48 d m/100 cm2 Coefficient of Variation 1.38 unitless Residual activity dose rate 0.39 mrem/

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-103, the calculated dose from residual activity is 0.39 mrem/yr.

The scan MDC for the Ludlum 43-37 detector was calculated using the rounded count rate of 500 cpm, at a distance of 0.75 inches, and the fiberglass grating detector weighted efficiency of 0.0113 c/d, and using L TP Equation 5-8, ( derived from NUREG-1507). The Survey Unit STR-103 Page 15 of32 Containment Vessel (CV) - 3rd Level (D Deck)

SAVANNAH Technical Staff Survey Unit Release Record rt elevated area is an assumed 100 cm 2 circular source. The detector width is 6.25 inches, and thus the detector speed is 6.25 in/second. With these parameters, the resulting observation interval is 0. 711 seconds. The resulting MDC for scanning is 6,103.85 dpm/100 cm 2. This value is 11.67% of the operational DCGLw and 8.76% of the gross activity DCGLw.

The scan MDC for the Ludlum 43-93 detector was calculated using the highest rounded count rate of 100 cpm, at a distance of 0. 75 inches, and the painted surface detector weighted efficiency of 0.0711 c/d, or the fiberglass grating surface detector weighted efficiency of0.0135 c/d, and using LTP Equation 5-8, (derived from NUREG-1507). The elevated area is an assumed 100 cm2 circular source. The detector width is 3.6 inches, and thus the detector speed is 3.6 in/second. With these parameters, the resulting observation interval is 1.234 seconds. The resulting MDC for scanning painted surfaces is 1,915.1 dpm/100 cm 2, and the MDC for scanning fiberglass gratings is 10,073.7 dpm/100 cm 2. The respective values are 3.66% of the operational DCGLw and 2.75% of the gross activity DCGLw for flat surfaces or 19.26% of the operational DCGLw and 14.45% of the gross activity DCGLw for grating surfaces.

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

Table 7 Scan Measurement Summary Scan ID SA-01 SA-02 SA-03 SA-04 SA-06 Low to High Range (dpm/100 cm2) 478.42 - 2617.21 2516.58 - 7253.67 3848.89 - 8956.06 2072.48 - 6957.60 5066.15 - 7637.26 Average d m/100 cm2 1547.82 4885.12 6402.48 4515.04 6351.70 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 (1) replicate static measurement (STR-103-12-O) for analysis. The acceptance criteria for replicate static measurements is defined by NUREG-1576, Multi-Agency Radiological Laboratory Analytical Protocols Manual (MARLAP) Volume I, Appendix C, Section C.4.2.2 Duplicate Analyses, Reference (k). 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 required method uncertainty (µMR) is a control limit formula value that is equal to the shift divided by ten (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 dpm/100 cm2, as shown below.

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

Survey Unit STR-103 Page 16 of32 Containment Vessel (CV)- 3rd Level (D Deck)

SAVANNAH Technical Staff Survey Unit Release Record 1-*jf

  • - - 1 rt The results of the evaluation of the QC measurement show 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.

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.

A field change was initiated to the FSS package. As described in Section 6, Scan Area SA-05, a grating platform, had not been replaced following decommissioning; therefore, it did not exist at the time of this survey.

12.

DATA QUALITY ASSESSMENT The DQO sample design and data were reviewed in accordance with MARAD procedure STS-005-033, Final Status Survey Data Assessment and Investigation, Reference (I). 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.

All fifteen systematic/unbiased measurements did not require remediation and were less than the DCGLw. Although MARSSIM states that the Sign Test need not be performed in the instance that no measurements exceed the DCGLw, 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 use 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.

Survey Unit STR-103 Page 17 of32 Containment Vessel (CV) - 3rd Level (D Deck)

SAVANNAH Technical Staff Survey Unit Release Record 1 - -

- t b zt

14.

CONCLUSIONS

15.

(a)

(b)

(c)

(d)

(e)

(f)

(g)

(h)

(i)

(j)

(k)

(I)

Survey unit STR-103 has met the OQOs of the FSS package. The survey unit is properly classified as Class I.

All final measurements are less than the DCGLw. 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-103 is 0.39 mrem/yr TEDE, based on the mean activity of all the final measurements.

Survey unit STR-103 is acceptable for unrestricted use.

REFERENCES STS-005-035, Preparation of Survey Unit Release Records and FSS Final Reports.

STS-004-003, NS SAVANNAH License Termination Plan, Revision 1.

STS-005-030, Preparation of Final Status Survey Packages.

NUREG-1575, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM), Revision I, August 2000.

CR-003, STS-109, Historical Site Assessment, Revision 1, 2023.

CR-139, TSO 21-089, Calculations to Support NSS Surface Contamination DCGLs, Revision 1, September 2022.

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

STS-005-031, Calculation of the Number of Measurements for Final Status Surveys.

STS-005-032, Survey Unit Turnover and Control.

CR-164, TSO 23-126, Calculation of Weighted Efficiencies and MDCs of Ludlum Detectors for Final Status Surveys on the NS SAVANNAH, Rev O I.

NUREG-1576, Multi-Agency Radiological Laboratory Analytical Protocols Manual, (MARLAP), July 2004.

STS-005-033, Final Status Survey Data Assessment and Investigation.

Survey Unit STR-103 Page 18 of32 Containment Vessel (CV)- 3rd Level (D Deck)

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-103 Containment Vessel (CV)- 3rd Level (D Deck) 1 - -

- + b zt Page 19 of32

SAVANNAH Technical Staff Survey Unit Release Record - Figures and Maps Location of the Containment Vessel (CV)- 3rd Level (D Deck) r Survey Unit STR-103 Containfnent Vessel (CV) - 3rd Level (D Deck) t Page 20 of32

SAVANNAH Technical Staff Survey Unit Release Record j

Containment Vessel (CV)- 3rd Level (D Deck) Systematic and Judgmental Static Locations

'30 Survey Unit STR-103

~TR-103-10 LEGEND:

Containment Vessel (CV) - 3rd Level (D Deck)

~R-103-13 j

  1. TR-103-03 TR-103-04 NOTES:

CV SHELL SHOWN IN FLATTENED VIEW (23' 10 32")

SAMPLE LOCATIONS CREATED IN VISUA_ SAMPLE PLAN NUMBER OF SAMPLES 15 PLACEMENT METHOD SYSTEMATIC STAAT LOC' RANootl TR-103-1 4 95 VSP Origin Point in Ship Coordinates:

Frame 123 On Centerline 23 'O" above baseline BOW tr Page 21 of32

AVANNAH Technical Staff Survey Unit Release Record Containment Vessel (CV)- 3rd Level (D Deck) Scan Areas NOTE:

Shell curvature was flattened out for sampling position placement.

Survey Unit STR-103 Containment Vessel (CV) - 3rd Level (D Deck)

SA-01 SA-03 SA-06 SA-01 BOW b Page 22 of32

SAVANNAH Technical Staff Survey Unit Release Record - Calibration Records ca111>ra11on cenlflcate

  • ID Number: 25035112000
  • 20240606

Customer: Scott Ginter Roo*atIon Safety & Control services, Inc.

93 Ledge Road Seabrook NH 0367 4 Instrument Luclum MOClel 3002 Probe Model LUdlum 43-93 Precision Check Serial Number 25035112 Serial Number 421417 Test1 Tesl2 Test3 Mean Results 5.00kcpm 4.99 kcpm 4.99 kcpm 4.99 kcpm Accuracy Check Ra e

T et Value As Found As Len AUTO 500 Kcpm #

500 Kcpm #

AUTO 50 Kcpm #

50 Kcpm #

AUTO 5 Kcpm II 5 Kcpm #

500Kcpm#

50Kcpmll 5Kcpm#

AUTO 0.5 K 0 499 Kcpm II 0.499 K II Readings with

  • Indicate ranges l'Alere As-Found readings are >20% of Target vatue.

Readings with** IndlcateAs-Ien read ngs are >10'- Of Target value Readings with # Indicate ranges were calibrated uSlng a pulser Prol>e Isotope 43-93 421417 Cs-137(Beta) 43-93 421417 Tc-99 43-93421417 Tc-99 43-93421417 Cs-t 37(Beta) 43-93 421417 Cs-137(Beta) 43.93 421417 Tc-99 43.93 421417 Tc-99 43-93 421417 CS*137(Beta)

Physical Checks Light Ched< or Santltation Probes Pass Outer Physical Check Pass Tap Test Pass Audio Function Cheek Pass Coro cheek Pass Calibration Date Set: Pass Efficiency

0. 1901 CID (4 Pi) 0 1028 CID (4 Pi) 0.0699 CID (4 Pl) 0 I 360 CID (4 Pl) 0.0167 CID (4 Pl) 0 0076 CID (4 PI) 0 0056 CID (4 Pl) 0.0152 CID (4 Pl)

NIST source ID 127357 Cs-137(Beta) 127356 Tc-99 127356 Tc-99 127357 cs-137(Beta) 127357 Cs-137(Beta) 127356 Tc-99 127356 Tc-99 127357 Cs-137(Beta)

I Electronics Checks High VOltllge Comments Elrioenoes done using 1.5" thick t,l>ergtass grate as requested Customer Equ,pment ID:

Geometry Flat surface Flat surtace Flat SUrtace Flat SUrtace Flat surtace Flat surtace Flat surface Flat SUrtace As Found 704 Volts Pass Source ID PUiser 98756 Pulser 98756 Pulser 98756 PUlser98756 com-m On Contact On Contact 3/4" Above Source 3/4" >JxNe Source On Grate On Grate 3/4" Above Grate 3/4

  • Above Grate As Left 704 Volts Calibrated By Nicole WedIg QC Review By Matthew Hunter Date: Jun 06, 2024 Expires. Jun 06, 2025 QC Date Jun 06 2024 Atm05pt,enc CondlLons - Temperature 71 0 'F humldtr 52.0 % Ba=tne Pressure:29.62 dl/ll9 In toler.111ce condltlons are based on tesl results fa ing with n specified l1111J1S with no reduction by the uncerta,nry of the meJSuren-ent The resutts conto,ned herein ielate coif 10 e item c:i bfateo Unless rw se 513teo this cal brotioo was perfolme<! by RSCS at 93 Ledge Rd, 5e:lb<'ook NH iZlnO the ronow ng NIST Traceable sources Pulser 98756 - (Cal Due: Oct 31 2024)

\\ort;ed on cal >r.raon, N*cole Wed,g The reported expanded uncertalnrt ol n>!osuremen,s sta:ed as the s:.and3rd uncert:>Jnry of measurement lll.lltiplled by the ooveraoe ractor k such the coverage prob3bl'rty correspondS to ~ro m31e'Y 95~.

Unless o*

rwse stated caLbrat.ons perforrred,n contom,:,nce 10 e fo1ohiog documena: ANSI N323AB-20t3, RSCS New Hampshire RadlCl3CWa Ma:ena LJcense NumDer 381R RSCS ca brabon seN ces ore performed,n acoord ce Nith the RSCS Radla:lon Protection ProQram Manual and Ru.acnS.Nly&CaWCISr.iott '"'

a..-.Rmo. s.JtncaN,,,(Olc**

111 ht' Survey Unit STR-103 Page 23 of32 Containment Vessel (CV)- 3rd Level (D Deck)

SAVANNAH Technical Staff nit Release Record Survey U I

jf -- -

C.illbr.itlon Certific.ite

  • ID Number: 25035118000
  • 20240606

V &. O' Customer:

RadiaUon Safety & control Services, Inc 93 Ledge Road Instrument Ludlum Model 3002 Probe MOdel Ludlum 43-37 Seri.ii Number 25035 118 Strl.il Number Seabrook NH 03874 Precision Check Test!

Test2 Test3 Mean 4.99 kcpm 5.01 kcpm 5.00 kcpm 5.00 kcpm Accuracy Check Ra e

Tar et Value As Found As Len AUTO 500 Kcpm #

500 Kcpm #

AUTO 50 Kcpm #

49.9 Kcpm #

AUTO 5 Kcpm #

4.99 Kcpm #

AUTO 0.5 K m #

0.50 1 Kcpm #

500Kcpm#

499Kcpm#

4.99Kcpm#t 0.50 1 K m#

R R

eadlngs w1111

  • Indicate ranges v.tiere As-Found readings are >20% of Target value eadlngs w1111 ** indicate As-left readings are > I0°'o of Target value.

R eadings with # Indicate ranges were calibrated using a pulser Probe Isotope 43-37 281043 Tc-99 43-37 281043 Cs-137(Beta) 43-37 281043 Tc-99 43-37 281043 Cs-137(Beta) 43-37 281043 Tc-99 43-37 281043 Cs-137(Beta) 43-37 281043 Tc-99 43-37 281043 Cs-137(Beta)

Ph sic.ii Checks 0 uter Physical Check: Pass apTest: Pass T

A udio Fl.llctlOn Cheek Pass Cord cheek. Pass C alibratlon Date Set Pass Efficiency 0.1071 CID (4 Pl) 0.1345 CID (4 Pl) 0 0073 CID (4 Pl) 0.0121 CID (4 Pl) 0.1544 CID (4 Pi) 0.1751 CID (4 Pl) 0 0 113 CID (4 Pl) 0.0136 CID (4 Pl)

NIST Source ID 127356 Tc-99 127357 Cs-137(Beta) 127356 Tc-99 127357 Cs-137(Beta) 127356 Tc-99 127357 Cs-137(Beta) 127356 Tc-99 127357 Cs-137(Beta)

Electronics Checks Hi ll Volta e C omments EffiaencleS performed using I 5" fiberglass grate as requested.

C ustomer Equ*pment ID:

Geometry Flat surface Flat surface Flat surface Flat surface Flat surface Flat SUrtace Flat surtace Flat surface As Found 1751 Volts 281043 Results P.iss Source ID Pulser 98756 Pulser 98756 Pulser 98756 Pulser 98756 Comment 3'4" Above Source 3'4" Above source 3/4" Above Grate 3/4" Above Grate On Source On Source On Grate On Grate As Left 1800 Volts Calibrated By Nicole

~edlg V

OC RevieW By Matthew Hunter ate Jun 06, 2024 D

Exp a

ires: Jun 06, 2025 c Date Jun 06. 2024 A tmosp~erlc Cond :ions - emperature 71 0 ' F. 1-'umid1ty 52.0 %, Barome:nc PressUfe:29.62 n/hg.

In tolerance conditions :n b3sed on test results 13 1111(1 with n specmed llm:ts W1tll no reduction by the uncertainty or the me contained herein relate on!'/ to the.:em ca rated Un less O r;., se stated S calibration was performed by RSCS at 93 Ledge Rd Seabroek, NH 112_.ng the follow ng NIS Pu Iser 98756 - {Cal Due: Oct 31 2024) w orked on carbra:ion: N cole Weo1g asurement The resultS T Traceable sources.

T he reported expanded uncertainty ol measuremen Is sta:ed as the standard uncertainty ol measuren,ent mJltiplied by the coverage factor ~ such th e coverage probabl 1ty corresponds to appro~Imately 95%.

Un less o*

rv, se stated cal b<a~ons perfOlllled In conformance to e lollowtng docurrents: ANSI N323AB-2013. RSCS Ne atena l.Jcense Number 381 R RSCS ca br3bon serw:es are perf0!!1'ed in accordance wilh the RSCS Radl3:lon Protectlon w Hamps Ire Raoioacwe M

Standard Operabng Procedures Ca \\,bratlon Laborato~, IS operated n accordance wrth ANSI/NCSL 2540-1-1994.

~cn~lt.cnrol~ft g;)i...:sg.~ Gutroc.,,...03,S.-,

800*'2~

,~Dl-'i-4-C:3

-"°'"'"'Y=

Program Manual and 11 bri t

Survey U nit STR-103 Page 24 of32 Containm ent Vessel (CV)- 3rd Level (D Deck)

SAVANNAH Technical Staff Survey Unit Release Record C.illbr.itlon Ctnlficat* -10 Number: 25035134000 - 20240606 - 1 RSCS Customer: Scott Ginter Radiation Safety & Control Services, Inc.

93 Ledge Road Seabrook NH 03874 Instrument Ludurn Model 3002 Probe Modtl Ludlum 43-93 Precision Check Serial Number 25035134 Stria! Number 421368 Test1 I

Test2 I

Test3 I

Mean I

Resuns 49.90 kcpm I

49.90 kcpm I

49.90 kcpm I

49.90 kcpm I

Accuracy Check Ranqe Tarqet Value As Found As Lett AUTO 500 Kcpmll 500Kcpmit 500Kcpm#

AUTO 50 Kcpm#

49 9 Kcprn #

49 9 Kcprn #

AUTO 5 Kcpm#

5Kcpm#

AUTO 0.5 Kcpm#

0.5 Kcorn #

Readings with

  • Ind.cate ranges Where As-Found readings are >20% of Target value.

Readings with - Indicate As-felt read ngs are >10% of Target value.

Readings with # Indicate ranges were calibrated using a pulser Probe Isotope 43-93 421368 Cs-137(Beta) 43-93 421368 Tc-99 43-93 421368 Cs-I37(Beta) 43-93 421368 Tc-99 43-93 421368 Cs-I37(Beta) 43-93 421368 Tc-99 43-93 421368 Cs-137(Beta) 43-93421368 Tc-99 Physic.ii Checks Light Chee of Sc111tilation Probes Pass outer Physical Check: Pass Tap Test: Pass Audio Function Check Pass Cord check Pass Efficiency 00158 C/D(4 Pl) 0.0162 CID (4 Pl) 0.0160 CID (4 Pl) 0 0055 CID (4 Pl) 0.1755 CID (4 Pl) 0.0975 CID (4 Pl) 0 1238 CID (4 Pl) 0.0658 CID (4 Pl)

NIST Source ID 127357 Cs-137(Beta) 63963 (Beta) Tc-99 127357 Cs-137(Beta) 127356 Tc-99 127357 Cs-137(Beta) 127356 Tc-99 127357 Cs-137(Beta) 127356 Tc-99 Electronics Checks HI 11 Votta e Comments* Efficiencies performed using I 5" fiberglass grate as requested.

customer Equipment ID:

5 Kcpm#

0.5 Kcprn#

GtOlllttry Flat Surface Flat SUrface Flat SUrface Flat SUrface Flat surface Flat SUrface Flat surface Flat SUrface As Found 700 Vons P.iss source ID Pulser 66 151 Pulser 66151 Pulser 66151 Pulser 66151 Comment On Grate On Grate 3/4" Above Grate 3/4" Above Grate On Contact On Contact 314" Above Source 3/4" Above Source As Left 700 Volts Calibrated By N cote Wedig 1-S)

QC Review By Matthe\\l Hunter Date: Jun 06, 2024 Expires: Jun 06, 2025 oc Date Jun 06, 2024 Atmospheric Cond..ons - Temperature 71 o 'F, humid 52 o %, Barome c Pressure:29.62 n/hg.

In tolerance condr.ions :ire based on test res 115 fa lln\\l "'ilh n specified llm, "'ilh no reauctJon by Ille unceft:linty of the measurement The resuns contailled here111 relate onty to e :em cal.brated.

Unless otherw-se s131ed 1s cal.brauon was peJformed by RSCS at 93 Ledge Rd, Seabrook NH U'ult! no the ro11o-N ng NIST Traceable sources Pulser 66151 * (Cal Due Apr 05 2025)

WOll<ed on calibrat,on. C ris Pirie\\ Nicole Wed g The reported expanded uncertainty of meas remem 1s sta:ed as !he sl3ndard uncert31nty of measurement n1J1t1p!led by the coverage factor k such that the coverage probabl 1ty corresponds to approXlma1eJy 95'!4.

Unless ex MiSe sbted cal tira* ons perton,,ed In conformance to e lo IOWlrlg documents. ANSI N323AB-2013: RSCS New Hampshlre Radioact e M3.en31 L,cense "umber 381 R RSCS ca 11Jrauon setv,ces are pertocmed in accord:ince with Ille RSCS Rad1:mon Protection Program ManU31 and Stand3fd Operaur19 Procedures Gallirallon Laboratory Is operated.n 3CCOrclance With ANSIINCSL 2540- 1-1994.

~JtonS-7.tCy&Ccrw-olStn,,ots Inc

~t...dgllRoac Sutwook~!Ui.""4

'.eOO! ~~~

t6J3j C4-~"."Zl Survey Unit STR-103 Containment Vessel (CV)- 3rd Level (D Deck) 1 :!

Page 25 of32

SAVANNAH Technical Staff Survey Unit Release Record Calibration Certificate - ID Number: 25035147000. 20240708. O RSCS Customer: Scott Ginter Radiation Safety & Control 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 5 Kcpm #

5 Kcpm #

AUTO 0.5 Kcpm #

0.5 Kcpm #

Readings with

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

Readings with ** indicate As-left readings are >1 0% of Target value.

Readings with # Indicate ranges were calibrated using a pulser Probe Isotope 43-93 421411 Cs-137(Beta) 43-93 421411 Tc-99 43-93 421411 Cs-137(Beta) 43-93 421411 Tc-99 43-93 421411 Cs-137(Beta) 43.93 421411 Tc-99 43-93 421411 Cs-137(Beta) 43-93 421411 Tc-99 Physical Checks Light Check of Sclntilatlon Probes: Pass Outer Physical Check: Pass Tap Test: Pass Audio Function Check: Pass Cord check: Pass Efficiency NIST Source ID 0.1 940 CID (4 Pl) 127357 Cs-137(Beta) 0.1 231 CID (4 Pl) 127356 Tc-99 0.1435 CID (4 Pl) 127357 Cs-137(Beta) 0.0766 CID (4 Pl) 127356 Tc-99 0.0197 CID (4 Pl) 127357 Cs*137(Beta) 0.0097 CID (4 Pl) 127356 Tc-99 0.0170 CID (4 Pl) 127357 Cs-137(Beta) 0.0064 CID (4 Pl) 127356 Tc-99 Electronics Checks High Voltage Comments: Efficiencies Using 1 112" Fiberglass Grate Provided.

Customer Equipment ID:

Calibrated By Jarod Fagan QC Review By Matthew Hunter Atmospheric Conditions - Temperature 71 6 "F, Humidity 46 0 %, Borometnc Pressure29 88 mlhg 50 Kcpm #

Pulser 66151 5 Kcpm #

Pulser 66151 0.5 Kcpm #

Pulser 66151 Geometry Comment Flat Surface On Source Flat Surface On Source Flat Surface 314" Above Source Flat Surface 314

  • Above Source Flat Surface On Grate Flat Surface On Grate Flat Surface 314" Above Grate Flat Surface 314" Above Grate As Found As Left 682 Volts 682 Volts Date: Jul 08, 2024 Expires: Jul 08, 2025 QC Data: Jul 08. 2024 In tolerance conditions ore based on lest results folffng within specified limits with no reduct,on by the uncertomty of the measurement The results contmned herein relate only to the item cofibraled.

Unless otherwise stoled, this colibrotion wos performed by RSCS ot 93 Ledge Rd, Seabrook, NH utilizing the following NIST Traceable sources Pulser 66151- (Cot Due Apr 0S, 2025)

Worked on calibration Jarod Fogonl Nicole Wedig The reponed expanded uncertointy of measurement is stated os the stondord uncertointy of measurement multiplied by the coverage factor k such !hot the coverage probobihty corresponds to opproximotely 95%

Unless otherwlS8 stated, colibrotions perfomled,n conformance 10 the following documents* ANSI N323AB-2013; RSCS New Hompsh,re Rod1ooctJve Moteriol License Number 38 1 R. RSCS colibrotion services ore performed,n occordonce with the RSCS Rodiobon Protection Program Manual ond Standard Operating Procedures.

Colibrotion Laboratory is operated in occordonce with ANSI/NCSL 2540 1994 Radi:IINWIS.ftty&Contn>s<<vka IN 9l 1..e0Qe f\\o.c:I S.at:niol M-t C3&74 fi!OO) SJS--t339 (6031474~7.l,

....,,,.ua-'e"OOtl'l l 2 rat Survey Unit STR-103 Page 26 of32 Containment Vessel (CV)- 3rd Level (D Deck)

SAVANNAH Technical Staff Survey Unit Release Record Meter ID 25035112 25035112 25035112 25035112 25035112 25035112 25035112 25035112 25035112 25035112 25035112 25035112 25035112 25035112 25035112 25035147 25035147 25035134 - Static Data Count Rate Total Weighted Eff Measurement ID (cpm)

(c/d)

STR-103-01 84 0.0995 STR-103-02 76 0.0995 STR-103-03 57 0.0995 STR-103-04 68 0.0995 STR-103-05 59 0.0995 STR-103-06 73 0.0995 STR-103-07 60 0.0995 STR-103-08 65 0.0995 STR-103-09 72 0.0995 STR-103-10 82 0.0995 STR-103-11 84 0.0995 STR-103-12 104 0.0995 STR-103-13 88 0.0995 STR-103-14 77 0.0995 STR-103-15 69 0.0151 STR-103-16-J 165 0.0179 STR-103-17-J 119 0.0179 STR-103-12-O 91 0.0920 Note: Meter ID 25035112, 25035147, and 25035134 are connected to a Ludlum model 43-93 detector with an area of 100 cm2.

i' Survey Unit STR-103 Page 27 of32 Containment Vessel (CY)- 3rd Level (D Deck)

SAVANNA H Technical Staff Survey Unit Release Record Meter ID 25035112 25035112 25035112 25035112 25035112 25035112 25035118 - Scan Data Min/Max Range Average Location (cpm)

(cpm)

SA-01 42/186 114 SA-01 34/146 90 SA-01 46/149 97.5 SA-02 34/98 66 SA-03 52/121 86.5 SA-04 28/94 61 SA-06 333/502 417.5 Total Weighted Eff (c/d) 0.0711 0.0711 0.0711 0.0135 0.0135 0.0135 0.0113 Note: Meter ID 25035118 is connected to a Ludlum model 43-37 detector with an area of 584 cm2. Meter ID 25035112 is connected to a Ludlum model 43-93 detector with an area of 100 cm2.

Survey Unit STR-103 Page 28 of32 Containment Vessel (CV)- 3rd Level (D Deck)

SAVANNAHTechnical Staff Survey Unit Release Record - Quality Control Assessment Measurement Value (dpm/100 cm2)

Initial measurement 1044.78 Replicate measurement 989.12 Average 1016.95 Absolute Value of the difference 55.66 Condition Absolute value of the Control Limit (dpm/100 cm2) difference (dpm/100 cm2)

Average < 52,300 55.66 11087.6 Survey Unit STR-103 Containment Vessel (CV)- 3rd Level (D Deck)

Result Pass Page 29 of32

SAVANNAH Technical Staff Survey Unit Release Record - Sign Test Measurement Result DCGLw - Result ID (dpm/100 cm2)

(dpm/100 cm2)

STR-103-01 843.86 68856.14 STR-103-02 763.50 68936.50 STR-103-03 572.62 69127.38 STR-103-04 683.13 69016.87 STR-103-05 592.71 69107.29 STR-103-06 733.36 68966.64 STR-103-07 602.76 69097.24 STR-103-08 652.99 69047.01 STR-103-09 723.31 68976.69 STR-103-10 823.77 68876.23 STR-103-11 843.86 68856.14 STR-103-12 1044.78 68655.22 STR-103-13 884.05 68815.95 STR-103-14 773.54 68926.46 STR-103-15 4570.02 65129.98 STR-103-16-J 9197.32 60502.68 STR-103-17-J 6633.22 63066.78 Parameter Result Number of Measurements 17 Number ofS+

17 Critical Value 12 Meets I Doesn't Meet Acceptance Criteria Meets Survey Unit STR-103 Containment Vessel (CV)- 3rd Level (D Deck)

Sign

+1

+]

+l

+1

+l

+]

+l

+1

+1

+1

+1

+1

+I

+1

+1

+1

+1 Page 30 of32

SAVANNAH Technical Staff Survey Unit Release Record - Graphical Presentations uan ile P f ross A --rivi *co

~

C 0 El( ()

N roo E:

u

... 00

---£ 5~00

" --- ~*oo 1 00 0

0 20~.

70 Survey Unit STR-103 Containment Vessel (CY)- 3rd Level (D Deck) ll C

,oy*

Page 31 of32

SAVANNAH Technical Staff Survey Unit Release Record Histogram Survey Unit Number: STR-103

i J p Containment Vessel (CV)

Survey Unit Name: - 3rd Level (D Deck)

.6 L

10 8

6 1651

so-488 5963

-o 1 Upper end luc: d m l 00 cm_)

Survey Unit STR-103 Containment Vessel (CV) - 3rd Level (D Deck) t SIL Page 32 of32

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