ML25328A167

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Us Dept of Transportation - Nuclear Ship Savannah, Survey Unit Release Record Survey Unit STR-102 Containment Vessel (Cv) - 2nd Level (Flat)
ML25328A167
Person / Time
Site: NS Savannah
Issue date: 11/20/2025
From: Hollenbeck P
US Dept of Transportation, Maritime Admin, Nuclear Ship Support Services
To:
Office of Nuclear Reactor Regulation
References
Download: ML25328A167 (0)
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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-102 Containment Vessel (CV) - 2nd Level (Flat)

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-102 Containment Vessel (CV) - 2nd Level (Flat)

Pete Hollenbeck Pete Hollenbeck, CHP D. Roberson Doug Roberson Soeuth Caleb Soeun Soeuth C. Soeun Digitally signed by Pete Hollenbeck Date: 2025.03.12 13:17:24-04'00' Date Digitally signed by D. Roberson Date: 2025.03.12 12:46:33 -05'00' Date Digitally signed by Soeuth Caleb Soeun Date: 2025.03.17 12:57:49 -04'00' Date Digitally signed by James Reese, James Reese, CHP, RRPT cHP, RRPT Date: 2025.03.18 09:24:08-07'00' James Reese Date Dan

  • 1 e I R M
  • 1 ha 1
  • 1 k Digitally signed by Daniel R. Mihalik Date: 2025.03.19 15:51:11 -04'00' Daniel Mihalik John Osborne LCM John Osborne 3/19/2025 Submitted Eric Darois Date Digitally signed by: John Osborne LCM DN: CN = John Osborne LCM email

= jmosborne@nsss.llc C = AD Date: 2025.03.28 17:25:34 -05'00' Date 3/28/2025 Approved 9/2/2025 Date Page 2 of30

SAVANNAH Technical Staff Survey Unit Release Record TABLE OF CONTENTS

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................................................................................ 16

10. REMEDIATION AND RESUL TS...................................................................................... 17
11. CHANGES FROM THE FINAL STATUS SURVEY PACKAGE................................. 17
12. DATA QUALITY ASSESSMENT...................................................................................... 17
13. ANOMALIES........................................................................................................................ 17
14. CONCLUSIONS................................................................................................................... 17
15. REFERENCES..................................................................................................................... 18
16. ATTACHMENTS................................................................................................................. 18 Survey Unit STR-102 Page 3 of30 Containment Vessel (CV)- 2nd Level (Flat)

SAVANNAHTechnical Staff Survey Unit Release Record LIST OF TABLES rt 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-102 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-102 Page 4 of30 Containment Vessel (CV)- 2nd Level (Flat)

SAVANNAH 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 L TP 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 SAVANNAH 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-102 Containment Vessel (CV)- 2nd Level (Flat)

Page 5 of30

SAVANNAH Technical Staff Survey Unit Release Record

1.

EXECUTIVE

SUMMARY

1 - - -- 1 hzt This Survey Unit Release Record for survey unit STR-102, Containment Vessel (CV) -

2nd Level (Flat), 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 SAVANNAH (NSS) License Termination Plan [LTP], 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 L TP, and with guidance from NUREG-1575, Revision I, Multi-Agency Radiation Survey and Site Investigation Manual (MARS SIM), Reference (d).

This survey unit has a MARSSIM 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.

During survey implementation two (2) additional static measurements were collected in locations that were identified as exceeding the 2,500 cpm scan action level. Surface scanning was performed on 100% of the accessible total surface area in the survey unit.

The data assessment results for survey unit STR-102 show that the maximum gross activity concentration among all the final systematic and judgmental measurements is equal to 24,914.06 dpm/100 cm2, which is 47.6% 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-102 is acceptable for unrestricted use.

The mean gross activity concentration among all the final systematic and judgmental measurements is equal to 4,068.75 dpm/100 cm2, which is 5.8% of the 15 mrem/y gross activity DCGLw of 69,700 dpm/100 cm2. The mean gross activity concentration is equal to 0.88 mrem/y for the survey unit.

2.

SURVEY UNIT DESCRIPTION STR-102 is an impacted Class 1 survey unit. The CV housed the reactor plant and some supporting systems. The 2nd level gives access to the heat exchanger manways as well as the pressurizer heaters. The survey unit consists of the internal surfaces of the CV shell, ring stiffeners, and the deck/new fiberglass grating from the 14-foot to 23-foot elevation.

Based upon Computer Aided Design drawings, the 2nd level grating surface area is approximately 40.71 square meters (40.71 m2); the total surface area, including the shell, is approximately 176.97 m2; this includes the shell surface above 2 meters. Refer to of this report for figures and maps depicting survey unit STR-102.

Survey Unit STR-102 Page 6 of30 Containment Vessel (CV) - 2nd Level (Flat)

SAVANNAHTechnical Staff Survey Unit Release Record

3.

CLASSIFICATION BASIS l - - -- d

  • 1 rt Based on the NSS Historical Site Assessment [HSA], Reference (e), survey unit STR-102, identified as survey unit 101 A I 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. The coolant was released as steam condensed and drained to the bottom of the CV, 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 CV 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-102-RASS-0 I-Rev 0, and the completion of a final Survey Unit Classification Worksheet, the correct final classification of survey unit STR-102 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 boundaries, 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-05-030, 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-102 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 (f) established the basis for an initial suite of potential Radionuclides of Concern (ROC) for decommissioning. Insignificant dose contributors Survey Unit STR-102 Page 7 of30 Containment Vessel (CV) - 2nd Level (Flat)

SAVANNAH Technical Staff Survey Unit Release Record l --ri --d - i r1 (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, 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-137 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 ofROC 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 1.63£-02 1.63E-02 Ni-63 5.40E+00 9.00E-01 9.00E-01 Sr-90 9.22E-06 1.54E-06 Tc-99 I.27E-04 2.1 lE-05 Ag-108m 8.30E-04 1.38E-04 Cs-137 4.57E-0I 7.61E-02 7.61£-02 H-3 1.93E-03 3.21E-04 Fe-55 8.1 0E-03 1.35£-03 Am-241 5.79E-07 9.66£-08 Pu-239/240 4.81E-07 8.0lE-08 Totals 6.00E+00 1.00E+00 9.93£-01 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 I 5 mrem/y DCGLw for Co-60, Ni-63 and Cs-137 from Chapter 6 of the LTP.

Survey Unit STR-102 Page 8 of30 Containment Vessel (CV) - 2nd Level (Flat)

SAVANNA H Technical 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 1.20E+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 DCGLHTD surrogate =

(/ HTD:ETDXDCGLETv)+ DCGLHTD Where:

DCGLETo the DCGL for the easy-to-detect radionuclide DCGLHTo = the DCGL for the hard-to-detect radionuclide Equation I F HTD:ETD 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 1

Gross Activity DCGLw = ti 1z In DCGL1 + DCGL2 +***DCGLn

=

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-102 Page 9 of30 Containment Vessel (CV)- 2nd Level (Flat)

SAVANNA H Technical Staff Survey Unit Release Record Table 4 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 5.61E-03 Co-60 l.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 l.38E-04 Cs-137 7.61E-02 7.61E-02 8.24E-0l H-3 3.21 E-04 Fe-55 l.35E-03 Am-241 9.66E-08 Pu-239/240 8.01 E-08 Totals l.00E+00 9.24E-02 1.00E+00 1 - --- rl i rt 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 76E-l 8 _24E-l = 6.97E+04 dpm/100 cm2.

2.~6E+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 DCGLw (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. STS-05-030, 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-102 Page 10 of30 Containment Vessel (CV)- 2nd Level (Flat)

I L

SAVANNAH Technical Staff Survey Unit Release Record 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 (d), 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 (1) 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 17, 2024 and May 16, 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 85.3 dpm/100 cm2.

The average total surface activity concentration and standard deviation of the measurements was 3,769 and 7,317 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-102 is based upon the RASS survey results and was calculated as follows:

52,300-26,150 Relative Shift (d/cr) = ----- = 3.57 7,317 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 II error, or p value, were set at 0.05. The sample size from STS-05-031, Reference (h) that equates to the Type I and Type ll 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-102.

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-102.

Survey Unit STR-102 Page 11 of30 Containment Vessel (CV)- 2nd Level (Flat)

SAVANNAH Technical Staff Survey Unit Release Record Table 5 STR-102 Systematic Measurement Designations Label LX(m) LY(m)

Sample Area STR-102-01

-5.07 0.86 CV Shell STR-102-02

-8.67 0.43 CV Shell STR-102-03

-12.47 0.54 CV Shell STR-102-04

-15.05 2.49 CV Shell STR-102-05

-17.54 2.63 CV Shell STR-102-06 1.38 1.93 CV Shell STR-102-07 16.77 0.91 CV Shell STR-102-08 4.03 2.32 CV Shell STR-102-09 6.75 0.98 CV Shell STR-102-10 10.62 0.97 CV Shell STR-102-11 13.78 1.73 CV Shell STR-102-12 2.23

-1.31 Grating Area I STR-102-13 4.18 2.07 Grating Area l STR-102-14 8.40

-2.17 Grating Area 3 STR-102-15 10.35 1.21 Grating Area 3 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-102-12 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 (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-102-16-J and STR-102-17-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-102, four (4) scan areas were established, SA-01 through SA-04. 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-102.

Survey Unit STR-102 Page 12 of30 Containment Vessel (CV)- 2nd Level (Flat)

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

SAVANNAH Technical Staff Survey Unit Release Record 1

J t 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.

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

> 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-102, 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 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, 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-102-00-00, 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 seven (7) days to complete and were performed between July 29, 2024, through August 7, 2024.

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 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.

Survey Unit STR-102 Page 13 of30.

Containment Vessel (CV)- 2nd Level (Flat)

SAVANNAH Technical Staff Survey Unit Release Record 1 - - -- 1 rt All four planned scan areas, SA-01 through SA-04, 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. Two (2) locations were identified that exceeding the 2,500 cpm scan action level. Both locations were marked and static measurement SA-01-01 and SA-01-02 were collected as follow-up static measurements. One (I) static measurement, SA-01-02, triggered the Investigation Level of 52,300 dpm/100 cm2. Static measurement location SA-01-02 was remediated. After remediation a follow-up static measurement was collected with the resulting value of less than the operational DCGLw.

The implementation of survey specific QC measures included the collection of one (1) replicate static measurement. The random location of the replicate measurement was STR-102-12 and identified as STR-102-12-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-137 comprise the NSS fingerprint. This is documented in CR-164, Reference U).

For example, (derived from NUREG-1507) if the 4n 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 1-minute count was 85 cpm and was rounded up to 100 cpm. The painted surface contact detector weighted efficiency is equal to 0.0995 c/d and the non-painted fiberglass grating contact detector weighted efficiency is equal to 0.0151 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 1-minute static measurements equal to 497.3 dpm/100 cm 2 and 3,278.5 dpm/100 cm 2, respectively. The value for flat surface contact is less than 1 % of the operational DCGLw and 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-102 Page 14 of30 Containment Vessel (CV) - 2nd Level (Flat)

SAVANNAH Technical Staff Survey Unit Release Record 1 - - -- t i rt Table 7 Summary of Systematic, Judgmental, and QC Static Measurements Activity Concentration Measurement ID (dpm/100 cm2)

STR-102-01 1074.92 STR-102-02 602.76 STR-102-03 763.50 STR-102-04 783.59 STR-102-05 693.17 STR-102-06 743.40 STR-102-07 853.91 STR-102-08 823.77 STR-102-09 612.81 STR-102-10 904.14 STR-102-11 683.13 STR-102-12 5232.34 STR-102-13 5762.20 STR-102-14 5364.81 STR-102-15 5894.66 STR-102-16-J 13461.63 STR-102-17-J 24914.06 STR-102-12-D 4662.77 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 Parameter Value Units Minimum Measurement 602.76 dpm/100 cm2 Maximum Measurement 24914.06 dpm/100 cm2 Mean 4068.75 dpm/100 cm2 Median 853.91 dpm/100 cm2 Standard Deviation 6380.73 dpm/100 cm2 Coefficient of Variation 1.57 unitless Residual activity dose rate 0.88 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-102, the calculated dose from residual activity is 0.88 mrem/yr.

The scan MDC for the Ludlum 43-93 detector was calculated using L TP Equation 5-8

( derived from NUREG-1507), with the highest rounded count rate of 100 cpm, a distance of 0.75 inches, the painted surface detector weighted efficiency of 0.0711 c/d, and the non-Survey Unit STR-102 Page 15 of30 Containment Vessel (CV) - 2nd Level (Flat)

SAVANNAH Technical Staff Survey Unit Release Record rt painted fiberglass grating surface detector weighted efficiency of 0.0135 c/d. 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 flat surfaces is 1,914.2 dpm/100 cm 2, and the MDC for scanning gratings is 10,081.5 dpm/100 cm2

  • The respective values are 3.7% of the operational DCGLw and 2.7% of the gross activity DCGLw for flat surfaces and 19.3% of the operational DCGLw and 14.5% of the gross activity DCGLw for grating surfaces.

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

Table 7 Scan Measurement Summary Low to High Range Average Scan ID (dpm/100 cm2)

(dpm/100 cm2)

SA-01 211.07 - 49811.45 25011.26 SA-02 3552.82 - I 0658.46 7105.64 SA-03 2220.51 - 7105.64 4663.08 SA-04 3552.82 - 63654.67 33603.75 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-102-12-D) for analysis. The acceptance criteria for replicate static measurements is defined by NUREG-1576, Multi-Agency Radiological Laboratory Analytical Protocols Manual (MARLAP) Volume 1, 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.

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 Two locations triggered the scan action level of 2,500 cpm, requiring a confirmatory measurement at each location. One of those two static measurements, SA-01-02, also triggered the investigation level equal to the operational DCGLw of 5.23E+04 dpm/100 cm2. Its activity concentration was 7.59E+04 dpm/100 cm2. The other location, SA-01-01, had an activity concentration of3.29E+04 dpm/100 cm 2. Neither of these two (2) locations were part of the fifteen systematic/unbiased measurement locations.

Survey Unit STR-102 Page 16 of30 Containment Vessel (CV)- 2nd Level (Flat)

SAVANNA H Technical Staff Survey Unit Release Record

10.

REMEDIATION AND RESULTS 1

- - }rt Remediation was performed on both locations. The post remediation survey result for SA-O I-I is 1.43E-04 dpm/100 cm2 and SA-01-02 is l.69E+04 dpm/100 cm2. These values are less than the operational DCGLw.

11.

CHANGES FROM THE FINAL STATUS SURVEY PACKAGE There were no addendums or field changes to the FSS package which was developed in accordance with STS-005-030.

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 I.

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 MARSSJM 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.

14.

CONCLUSIONS Survey unit STR-102 has met the DQOs of the FSS package. The survey unit is properly classified as Class 1.

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-102 is 0.88 mrem/yr TEDE, based on the mean activity of all the final measurements.

Survey Unit STR-102 Page 17 of30 Containment Vessel (CV)- 2nd Level (Flat)

SAVANNAH Technical Staff Survey Unit Release Record

15.

(a)

(b)

(c)

(d)

(e)

(f)

(g)

(h)

(i)

(j)

(k)

(I)

16.

Survey unit STR-102 is acceptable for unrestricted use.

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

STS-004-003, N.S. SA VANNAH License Termination Plan, Revision I.

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

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

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

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

NUREG-1757, Vol 2, Rev l, 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, TSD 23-126, Calculation of Weighted Efficiencies and MDCs of Ludlum Detectors for Final Status Surveys on the NS SAVANNAH, Rev 01.

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

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

ATTACHMENTS - Figures and Maps - Calibration Records - Static and Scan Data - Quality Control Assessment - Sign Test - Graphical Presentations Survey Unit STR-102 Page 18 of30 Containment Vessel (CV)- 2nd Level (Flat)

SAVANNAH Technical Staff Survey Unit Release Record Survey Unit STR-102 - Figures and Maps Location of the Containment Vessel (CV)- 2nd Level (Flat)

Containment Vessel (CV) - 2nd Level (Flat) t Page 19 of30

SAVANNAH Technical Staff Survey Unit Release Record t

Containment Vessel (CV) - 2nd Level (Flat) Systematic and Judgmental Static Locations o~o r.-o,

~TR-1

/

VSP Origin Point in Ship Coordinates:

5" Forward of Frame 123 On Centerline 14'6" above baseline LEGEND NOTES BOW Survey Unit STR-102 Containment Vessel (CV) - 2nd Level (Flat)

CV SHELLSHO,WI ltl FLATTEt ED IIEWC14' 10 :l't SA. tPLE LOCATI~-'S CREATED IN 'ISUAL SA~Pl.E PLA.tl t.UMSER Of SAMPLES IS PLACEMEl'-lT METHOD SYSTEl C

START LOC; RANDOM Page 20 of30

SAVANNAH Technical Staff Survey Unit Release Record Containment Vessel (CV)- 2nd Level (Flat) Scan Areas Note: SA-OJ is a flattened view of the CV shell (14' to 23')

Survey Unit STR-102 Containment Vessel (CV) - 2nd Level (Flat)

BOW b Page 21 of30

SAVANNAH Technical Staff Survey Unit Release Record - Calibration Records C31lbr.itlon Cenlflc;ite

  • ID Number: 25035112000
  • 20240606
  • 0 RSCS Customer: Scott Ginter Instrument LUClum Moelel 3002 Probe Model LlKllum 43-93 I Number Serla 250 Serla 4

Ra<11ation Safety & Control Services, Inc.

93 ledge Road Seabrook NH 03874 Tesl2 5.00 kcpm 4.99 kcpm Ra e T

etValue Precision Check Test3 Mean 4.99 kcpm 4.99 kcpm Accuracy Check As Found As Len AUTO AUTO AUTO AUTO 500 Kcpm#

50 Kcpm#

5Kcpm#

0.5 Kcpm-.

500Kcpm#

50 Kcpm#

5Kcpm#

500Kcpm#

50 Kcpm#

5 Kcpm#

0.499 K 0499K m#

Readings v.rth

  • indicate ranges v.tlere As-Found readings are >20% of Target value.

Readings wttn ** I00IcateAs-Ien reoo ngs are >10% Of Target value Readings wttn # tndlcate ranges were calibrated using a pulser Probe Isotope 43-93 421417 Cs-137(Beta) 43-93421417 Tc-99 43-93 421417 Tc-99 43-93 421417 Cs-I37(Beta) 43-93 421417 Cs-137(Beta) 43-93421417 Tc-99 43-93 421417 Tc-99 43-93 421417 Cs-137(Beta)

Pllyslc;il Checks Light Check of Scrntilalion Probes Pass Outer Pllys1cal Check Pass Tap Test Pass Audio Function Cheek Pass Cord Cheek Pass Calibration Date Set: Pass Efficiency 0.1901 CID (4 Pl) 0 1028 CID (4 Pl) 0.0699 CID (4 Pl) 0 1360 CID (4 Pl) 0.0167 CID (4 Pi) 0.0076 CID (4 PI) 0 0056 CID (4 Pi) 0.0152 CID (4 Pl)

NIST source ID 127357 Cs-137(Beta) 127356 Tc-99 127356 Tc-99 127357 Cs-I37(Bela) 127357 Cs-137(Beta) 127356 Tc-99 127356 Tc-99 127357 Cs-137(Beta)

I Elec:tronlcs Checks High VoltJge Comments Eflte1enoes done using 1.5" tnick fiberglass grate as requested Customer Equ pment ID:

o.-1ry Flat Surface Flat Surface Flat Surface Flat Surface Flat Surface Flat Surface Flat Surface Flat Surface As Founel 704 Volts 35112 I Number 21417 Results Pass source 10 Pulser 98756 Pulser 98756 Pulser 98756 Pulser 98756 comment On Cont.:ict On Contact 3/4" Above Source 3/4" Above Source On Grate On Grate 3/4" Above Grate 3/4" Above Grate As Left I

704 Volts Calibrated By Nicole Wed19 QC Review By Matthew Hunter e: Jun 06. 2024 Oat Expl QC res. Jun 06, 2025 Date Jun 06 2024 Atmospr,ertc ConcL:,c,ns - Temperatu e 71 O 'F Humic!rty 52.0 "-* Borome!IIC Pte,sute:29.62 tn/hg In tolerance condition* are b:lsea on test results lo 11n9 wilh n specified hnuts wilh no reducbon by the uncertainty of the meosu reme.nt The re.suits conto,ned herein relate 00110 w item calbrated Unless o*

1W se Sl.'.lted

  • s cal bratlon W3S p&lformed b, RSCS at 93 Ledge Rd Se;illrook. NH tr. !ZlnQ the folloW,ng NIST T rateable sources Pulser 98756 * (Cal Due: Oct 31 2024)

Wort.eel on cal.bra:.on. N,cole Vedio eraoe factor k s ch that The reponed e~nded uncertainty of meas remen* is su:ed as stand.ml uncena,nr1 of measurement 111Jlliplled by the =

the coverage probab ty correspond$ to 3Ppro,imai y 95"-.

Unless otherwse stated cal.bfa:.ons pe!fOITT'ed In conformance to 1he fo lo~ing documentl: ANSI N323AB-20t3, RSCS Ne-N M3:ena l.Jcense "-umller 381 R RSCS ca braUon ser,*ces are pMorrned m accoroance witn the RSCS Rad!

  • Protecuon Pr Hampshire Rodl03d1Ve ogram Manu:11 and Fw.alonSftly&Conw'CISr.G-t Inc m~Roaasu.d!NriOlc.-,

111 1st Survey Unit STR-I 02 Page 22 of30 Containment Vessel (CV)- 2nd Level (Flat)

/

SAVANNA H Technical Staff Survey Unit Release Record Calibration Certificate

  • ID Numbtr: 25035118000
  • 20240606

., & o tro Radi.Jtlon Safety & Control Services, Inc 93 Ledge Road Seabrook NH 03874 lnstrumtnt Ludlum Model 3002 Probe Model Ludlum 43-37 Precision Check serial Numbtr 25035118 Strlal Numbtr 281043 Test1 I

Test2 I

Test3 I

Mean I

Results 4.99 kcpm I

5.01 kcpm I

5.00 kcpm I

Accuracy Check Ranae Target Value As Found AUTO 500Kcpm#

500Kcpm#

AUTO 50 Kcpmll 49.9Kcpm#

AUTO 5 Kcpmtl 4.99Kcpm#

AUTO 0.5 Kcom#

0.501 Kcpm#

Readings with

  • Ind cate ranges where As-Found readings are >20% of Target value Readings with ** indicate As-len readings are > 10% of Target value.

Readings with ti indicate ranges were calibrated using a pulser Probe Isotope Efficiency NIST Source ID 43-37 28 I 043 Tc-99 0.1 071 CID (4 Pl) 127356 Tc-99 5.00 kcpm I

As Len 500 Kcpm#

499Kcpm#

4.99Kcpm#

0.501 Kcpm#

Gtometry Flat surface 43-37 281043 cs-137(Beta) 0.1345 CID (4 Pl) 127357 Cs-137(Betl)

Flat SUrface 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(6etl)

Physie.1I Checks Outer Physical Check: Pass Tap Test Pass Auctio Function Check Pass Cord check. Pass Calibration Date Set Pass 0 0073 CID (4 Pl) 127356 Tc-99 0.0121 CID (4 Pl) 127357 Cs-137(Beta) 0.154-1 CID (4 Pl) 127356 Tc-99 0 1751 CID (4 Pl) 127357 Cs-137(Beta) 0 0113 CID (4 Pl) 127356 Tc-99 0.0136 CID (4 Pl) 127357 Cs-137(Beta)

Electronics Checks Hi h Volta e Commenls Etroencles performed using I 5" fiberglass grale as requested.

Customer Equipment ID:

Flat surface Flat SUrface Flat SUrface Flat surface Flat surface Flat SUrface As Found 1751 Vons P.1ss Source ID Pulser 98756 Pulser 98756 Pulser 98756 Pulser 98756 Comment 314" Above Source 314" 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 Wedig QC Review By Matthew Hunter Date Jun 06. 2024 Expires: Jun 06, 2025 QC Date Jun 06, 2024 Atmosphertc Cond-JOOs - Temperature 71 0 'F humidity. 52 O %, E!aromet11c Pressure*29.621Ml9.

In toler:ince condltlons 3re b3sed on test results ta 11110 with n speclfie<l ll'll11S v.nh no re<luctoo by !Ile uncertaInr1 of !Ile measurement The resuns contained herein reiate onl'/ to

.em ca rated Unless O @IW se Sl:lted S cal ration W3S pe1orrned by RSCS 31 93 Ledge Rd Seabrook NH U'.JbnlJ !he follow no NIST Traceable sources Pulser 98756 - (Cal Due: Oct 31 2024)

Wo!1<ed on cal bra:ion: N cole WeoI0 The reported expanded urcertalnty of measurement Is s!3:ed as !Ile S!3ndard uncertainty of measurement multipheer 381 R RSCS ca,bra~on serv,ces are perfonned in accord ce wnh !Ile RSCS Radla:lon Protection PrQ1Jram M:inUJl and Stand3rd Opera no Procedures Caf.bralion Laboratory,s operated n accordance,'1lll ANSIINCSL 2540-1-1994.

,c..w.,s.-.an1nc

',3 ~

... 03o-,

ilXl) s:!-&n.l

~* -~4-t~

Survey Unit STR-102

'll#W~CCll"'I Containment Vessel (CV)- 2nd Level (Flat) l.1 Page 23 of30

SAVANNA H Technical Staff Survey Unit Release Record Co11ibration Certifico1te

  • ID Number: 25035134000
  • 20240606
  • 1 RSCS Customer: Scott Ginter Rad ation Safety & Control SeMces, Inc.

93 Ledge Road Seabrook NH 03874 Instrument Ludlum Model 3002 Probe Model Llldlum 43-93 Precision Check Serial Number 25035134 Serial Numbtr 421368 Test!

I Test2 I

Test3 I

Mean I

ResultS 49.90 kcpm I

49.90 kcpm I

49.90 kcpm I

49.90 kcpm I

Accuracy Check Range TarQet Value As Found As Left AUTO 500 Kcpmll 500Kcpm1t 500Kcpm/i AUTO 50 Kcpm#

49 9 Kcpm #

49 9 Kcpm #

AUTO 5 Kcpml/.

5Kcpm#

AUTO 0.5 Kcpm#

0.5 Kcpm#

Readings with

  • indicate ranges wtiere As-Found readings are >20% ofTarget value.

Readings with - Indicate As-left read,ngs are >10% or Target value.

Readings with # indicate ranges were calibrated using a pulser Probe Isotope 43.93 421368 Cs-I37(Beta) 43-93 421368 Tc-99 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-t37(Beta) 43-93 421368 Tc-99 Physic.ii Checks Light Chee or Saitilation Probes Pass Outer Physical Clleck: Pass Tap Test: Pass Audio Function Cheek Pass Cord check Pass Efficiency 0 0158 CID (4 Pi) 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-t37(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 H h VOita e Comments* Emaencles performed using 1.5" fiberglass grate as requested Customer Equipment ID:

5 Kcpm#

0.5Kcom#

GtOIMtry Flat Surface Flat Surface Flat Surface Flat Surface Flat Surface Flat Surface Flat Surface Flat Surface As Found 700Votts Pass source ID Pulser 66 151 Pulser66151 Pulser 66151 Pulser 66151 Comment On Grate On Grate 3/4" Above Grate 3/4" Above Grate On Contact On Contact 314" Above Source 314" Above Source As Left 700 Volts Calibrated By N*cote Wedlg OC Review By Matthew Hunter Date: Jun 06, 2024 Expires: Jun 06, 2025 QC Date Jun 06, 2024 Atmospheric Cond :.ons - Temper3ture 71 0 'F Humlcfrty 52 0 ~. Barometric Pressure:29.62 n/hg.

In oter3nce conartlons are baSed on test results fa lr,g wilh n specified lim ts "'ith no reoucuon by tne unceltalfl!Y of !he measurement The results contained herein relate only to

.t~m cal brated.

Unless 0:

fW se stated s cal br3t1011 \\'13S pe1ormed by RSCS 31 93 Ledge Rd Seabroot<. N U izlng the ro110v, ng NIST Tr3Ce3ble sources Pulser66151- (Cal Due Apr05 2025)

WoJl<ed on colibr31,011: Chris Pirie\\ Nlcote Wed,g The repolted expanded unceltoln y of measureme11t is st3:ed as tile stan0Jrd uncertainty of measurement multiplied b:,, !he coverage factor k s ch t

!he coverage prob3bi1ty corresponds 10 appro mate,y 95111 Unless Oll>ewse stated cal bratJ011s pertorn-ed In coorormance to the roJJowlng doa.ments. ANSI N323'18-2013, RSCS New h31l\\PSl\\lre Rad,oacwe Matena License 1'umber 381 R RSCS ca 1br:luon sen, ces are perforn-ed In accord:ince \\\\1th the RSCS Radiaoon ProteClion Progr3m Manual and standard Opera~no Procedures Cal bratlon L3b0r3tory Is oper3ted n accordance wrth ANSI/NCSL Z540-l-1994.

~Saf<<v&CcnrolSt,v,ots Inc

l)UdftRoao ~N-40
.6.7.&

aaa,~

.~.,-~;z Survey Unit STR-102 Containment Vessel (CY) - 2nd Level (Flat) l 2 Page 24 of30

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

(c/d)

STR-102-01 107 0.0995 STR-102-02 60 0.0995 STR-102-03 76 0.0995 STR-102-04 78 0.0995 STR-102-05 69 0.0995 STR-102-06 74 0.0995 STR-102-07 85 0.0995 STR-102-08 82 0.0995 STR-102-09 61 0.0995 STR-102-10 90 0.0995 STR-102-11 68 0.0995 STR-102-12 79 0.0151 STR-102-13 87 0.0151 STR-102-14 81 0.0151 STR-102-15 89 0.0151 STR-102-16-J 1340 0.0995 STR-102-17-J 2480 0.0995 STR-102-12-D 74 0.0159 Note: Meter IDs 25035112 and 25035134 are connected to a Ludlum model 43-93 detector with an area of 100 cm2.

st Survey Unit STR-102 Page 25 of30 Containment Vessel (CV)- 2nd Level (Flat)

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

(cpm)

SA-01 31/1560 795.5 SA-01 32/1800 916 SA-01 15/3540 1777.5 SA-01 40/138 89 SA-02 48/144 96 SA-03 30/96 63 SA-04 48/860 454 J - - -- d 1

Total Weighted Eff (c/d) 0.0711 0.0711 0.0711 0.0711 0.0135 0.0135 0.0135 Note: Meter ID 25035112 is connected to a Ludlum model 43-93 detector with an area of 100 cm2.

Survey Unit STR-102 Page 26 of30 Containment Vessel (CV)- 2nd Level (Flat)

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

Initial measurement 5232.34 Replicate measurement 4662.77 Average 4947.555 Absolute Value of the difference 569.57 Condition Absolute value of the Control Limit (dpm/100 cm2) difference (dpm/100 cm2)

Average < 52,300 569.57 11087.6 Survey Unit STR-102 Containment Vessel (CY)- 2nd Level (Flat) t Result Pass Page 27 of30

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

(dpm/100 cm2)

STR-102-01 1074.92 68625.08 STR-102-02 602.76 69097.24 STR-102-03 763.5 68936.50 STR-102-04 783.59 68916.41 STR-102-05 693.17 69006.83 STR-102-06 743.4 68956.60 STR-102-07 853.91 68846.09 STR-102-08 823.77 68876.23 STR-102-09 612.81 69087.19 STR-102-10 904.14 68795.86 STR-102-11 683.13 69016.87 STR-102-12 5232.34 64467.66 STR-102-13 5762.2 63937.80 STR-102-14 5364.81 64335.19 STR-102-15 5894.66 63805.34 STR-102-16-J 13461.63 56238.37 STR-102-17-J 24914.06 44785.94 Parameter Result Number of Measurements 17 Number of S+

17 Critical Value 12 Meets I Doesn't Meet Acceptance Criteria Meets Survey Unit STR-102 Containment Vessel (CV)- 2nd Level (Flat)

J d tzt Sign

+1

+1

+1

+1

+1

+1

+1

+1

+l

+l

+l

+1

+1

+.l

+1

+l

+1 Page 28 of30

SAVANNAH Technical Staff Survey Unit Release Record - Graphical Presentations Quantile Plot of Gross Activity Concentration 30300 25300 N,....

~ 20300 0

E

_g-15300

(.)

s:;

0 10300 u

(.)

5300 300 * * * * * * * * * *

  • 0%

10%

20%

30%

40%

70%

80%

Survey Unit STR-102 Containment Vessel (CV)- 2nd Level (Flat) r r 90%

100%

Page 29 of 30

SAVANNAH Technical Staff Survey Unit Release Record Histogram Survey Unit Number: STR-102 C)

C Containment Vessel (CV)

Survey Unit Name: - 2nd Level (Flat) 12 10 8

~ 6 er Q) u..

4 2

0 3642 668 1 9719 12758 15797 18836 Upper end Yalue (dpm/100 cm2)

Survey Unit STR-102 Containment Vessel (CV)- 2nd Level (Flat) rt 2 1875 24914 Page 30 of30

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