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Us Dept of Transportation - Nuclear Ship Savannah, Survey Unit Release Record Survey Unit SYS-117-02 Fuel Transfer Tank, Retained Walls
	ML25328A173
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: ML25328A173 (0)
	v • d • e

U.S. Department of Transportation Maritime Administration Office of Ship Operations Nuclear Ship SAVANNAH Survey Unit Release Record Survey Unit SYS-117-02 Fuel Transfer Tank, Retained Walls Senior Technical Advisor Prepared by:

Nuclear Ship Support Services, LLC

S AVANNAH 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 SYS-117-02 Fuel Transfer Tank, Retained Walls Pete HO 11 en bee k Digitally signed by Pete Hollenbeck Date: 2025.04.17 16:35:59 -04'00' Pete Hollenbeck, CHP D. Roberson Douglas Roberson Date Digitally signed by D. Roberson Date: 2025.04.21 07:47:24-05'00' Date Soeuth Caleb Soeun DigitallysignedbySoeuthCalebSoeun Date: 2025.04.23 09:29:57 -04'00' Soeuth C. Soeun James Reese, CHP, RRPT James Reese Date Digitally signed by James Reese, CHP, RRPT Date: 2025.04.23 11 :34:16

-07'00' Date Dan

1 e I R M

1 ha 1

1 k Digitally signed by Daniel R. Mihalik Date: 2025.04.24 10:14:40 -04'00' Daniel Mihalik John Osborne LCM John Osborne 4/24/2025 Submitted Eric Darois Date Digitally signed by: John Osborne LCM DN: CN = John Osborne LCM email =

jmosborne@nsss.llc C = AD Date: 2025.05.13 11 :37:45 -05'00' Date 5/2/2025 Approved 9/2/2025 Date Page 2 of 30

S AVANNAH Technical Staff Survey Unit Release Record TABLE OF CONTENTS l - --- a f

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................................................................................................................... 17

15. REFERENCES..................................................................................................................... 18

16. ATTACHMENTS................................................................................................................. 18 Survey Unit SYS-117-02 Page 3 of30 Fuel Transfer Tank, Retained Walls

S AVANNAH Technical Staff Survey Unit Release Record LIST OF TABLES l - - -- d 1 rt Table 4 Radionuclide Fractions and Normalized Fractions............................................... 8 Table 4 15 mrem/y DCGLs for ROC and Ni-63.................................................................. 8 Table 4 Re-normalized Co-60 and Cs-137 Fractions........................................................ 10 Table 4 Operational DCGLs................................................................................................ 10 Table 5 SYS-117-02 Systematic Measurement Designations............................................ 12 Table 5 Scanning Coverage................................................................................................. 12 Table 5 Investigation Levels................................................................................................ 13 Table 7 Summary of Systematic, Judgmental, and QC Static Measurements................ 15 Table 7 Basic Statistical Properties of Static Measurement Population.......................... 15 Table 7 Scan Measurement Summary................................................................................ 16 Survey Unit SYS-I I 7-02 Page 4 of30 Fuel Transfer Tank, Retained Walls

S AVANNAH Technical Staff Survey Unit Release Record LIST OF ACRONYMS AND ABBREVIATIONS ALARA As Low As Reasonably Achievable CR Contractor Report DQO Data Quality Objective DCGL Derived Concentration Guideline Level ETD Easy-to-Detect FSS Final Status Survey HTD Hard-to-Detect JC 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 NST Neutron Shield Tank QC Quality Control ROC Radionuclides of Concern TEDE Total Effective Dose Equivalent UBGR Upper Bound of the Gray Region VSP Visual Sample Plan Survey Unit SYS-117-02 Fuel Transfer Tank, Retained Walls l - --- i rt Page 5 of30

SAVANNAH Technical Staff Survey Unit Release Record

1.

EXECUTIVE

SUMMARY

This Survey Unit Release Record for survey unit SYS-117-02, Fuel Transfer Tank, Retained Walls, 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 [L TP], STS-004-003, Revision I, 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 (MARSSIM), Reference (d).

This survey unit has a MARSSIM classification of Impacted. 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 approximately I 00% of the total surface area in the survey unit. The data assessment results for survey unit SYS-117-02 show that the maximum gross activity concentration among all the final systematic and judgmental measurements is equal to 18,486.73 dpm/100 cm2, which is 35.3% 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 SYS-117-02 is acceptable for unrestricted use. The mean gross activity concentration among all the final systematic and judgmental measurements is equal to 5,426.19 dpm/100 cm2, which is 7.8%

of the 15 mrem/y gross activity DCGLw of 69,700 dpm/100 cm 2. The mean gross activity concentration is equal to 1.17 mrem/y for the survey unit.

2.

SURVEY UNIT DESCRIPTION SYS-117-02 is an impacted system survey unit. The Fuel Transfer Tank surrounds the reactor vessel head above the hot legs and is normally empty. It has no lead shielding.

During refueling operations before the reactor vessel head is lifted, the Fuel Transfer Tank is filled with water to 36 inches above the lower reactor vessel flange to reduce dose during refueling. The survey unit consists of interior and exterior walls. The total surface area is approximately 62 square meters (62 m2), based upon Computer Aided Design drawings.

Refer to Attachment 1 of this report for figures and maps depicting survey unit SYS-I 17-

02.

Survey Unit SYS-117-02 Page 6 of30 Fuel Transfer Tank, Retained Walls

SAVANNAH Technical Staff Survey Unit Release Record

3.

CLASSIFICATION BASIS f -

5t *- - bat No scoping survey was performed for the Fuel Transfer Tank. The Neutron Shield Tank (NST) scoping survey #042020231100 performed on 04/20/23 shows the NST system to be up to twice background. Based upon review of the historical information, the results of the NST scoping survey data, and completion of a final Survey Unit Classification Worksheet, the correct final classification of survey unit SYS-117-02 is an Impacted system.

4.

DATA QUALITY OBJECTIVES FSS planning and design relies on a properly executed Data Quality Objective (DQO) process to ensure, through compliance with explicitly defined inputs and boundaries, that the primary objective of the survey is satisfied. The DQO process is described in the NSS L TP. 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 SYS-I I 7-02 did 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 (e), established the basis for an initial suite of potential Radionuclides of Concern (ROC) for decommissioning. Insignificant dose contributors (IC) were determined consistent with the guidance contained in Section 3.3 of NUREG-

1757, Volume 2,

Revision 1,

Consolidated Decommissioning Guidance Characterization, Survey, and Determination of Radiological Criteria, Reference (f). In all analyses, Cs-137 and Co-60 contribute nearly I 00% 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.

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SAVANNAH Technical Staff Survey Unit Release Record 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 3.37£-02 5.61E-03 Co-60 9.78E-02 1.63£-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 1.27£-04 2.1 IE-05 Ag-108m 8.30E-04 l.38E-04 Cs-I 37 4.57E-01 7.61 E-02 7.61 E-02 H-3 1.93£-03 3.21 E-04 Fe-55

8. l0E-03 1.35E-03 Am-241 5.79£-07 9.66E-08 Pu-239/240 4.81£-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 presents the 15 mrem/y DCGLw for Co-60, Ni-63 and Cs-137 from Chapter 6 of the L TP.

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

Co-60 2.37E+04 Ni-63 2.53£+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.

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SAVANNAH Technical Staff Survey Unit Release Record The surrogate DCGL is computed as:

DCGLsurrogate = DCGLETD X DCGLHTD (f HTD:ETDXDCGLErv)+ DCGLHTD Where:

DCGLETD DCGLHTD the DCGL for the easy-to-detect radionuclide the DCGL for the hard-to-detect radionuclide Equation I FHTD: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 I 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.

C 2.53E+08 2

D GLco-60 surrogate= 2.37E + 04 X (

)

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

Where:

fn n

DCGLn 1

Gross Activity DCGLw = ti 1z In DCGL1 + DCGL2 +***vcGLn 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 have to be re-normalized for use in Equation 2.

Table 4-3, located on the next page, presents the re-normalized fractions for each radionuclide. Remainder of this page left blank intentionally.

Survey Unit SYS-117-02 Page 9 of 30 Fuel Transfer Tank, Retained Walls

SAVANNAH 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 5.61 E-03 Co-60 1.63E-02 1.63E-02 1.76E-01 Ni-63 9.00E-01 Sr-90 1.54E-06 Tc-99 2.11 E-05 Ag-108m 1.38E-04 Cs-137 7.61E-02 7.61E-02 8.24E-01 H-3 3.21E-04 Fe-55 1.35£-03 Am-241 9.66£-08 Pu-239/240 8.0IE-08 Totals 1.00E+00 9.24E-02 1.00E+00 Solving Equation 2, using the re-normalized Co-60 and Cs-137 fractions and the Co-60 surrogate DCGL, is shown below.

1 Gross Activity DCGLw = 1 76E-l 8 _24E-l = 6.97E+04 dpm/100 cm2.

2.~6E+04 I 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 1.77£+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 Minimum Detectable Concentration (MDC) below I 0% of the DCGL is preferable and up to 50% is acceptable. Because the Survey Unit SYS-I I 7-02 Page 10 of30 Fuel Transfer Tank, Retained Walls

S AVANNA H Technical Staff Survey Unit Release Record 1

d bri background is low on the NSS, the MDC for most static and scan measurements were less than 10% of the DCGL and in all cases the MDCs were less than 50% of the DCGL.

5.

SURVEY DESIGN The L TP specifies that the Sign Test will be used as the nonparametric statistical test for compliance with the release criteria. The number of measurements for use with the Sign Test was determined in accordance with MARAD procedure STS-005-031, Calculation of the Number of Measurements for Final Status Surveys, Reference (g). 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 (I), or greater than three (3), then the value of two (2) will be used for the relative shift.

A NST scoping survey #042020231100 was performed on 04/20/23. Twenty (20) total surface activity measurements were collected. The maximum beta activity was 1,569 dpm/100 cm2. The average activity concentration and standard deviation of the measurements was 798 and 353 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 SYS-117-02 is based upon the scoping survey results and was calculated as follows:

52,300-26,150 Relative Shift (Ncr) = ------ = 74 353 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 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 SYS-117-02.

The survey unit was designated as an Impacted system which called for judgmental measurements. However, due to decommissioning activities in the proximity of the NST in the Containment Vessel, 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 I).

Table 5-1 on the next page lists the systematic measurements to be collected for FSS of survey unit SYS-117-02.

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S AVA NA H Technical Staff Survey Unit Release Record Table 5-1-SYS-117-02 Systematic Measurement Designations Label LX(m)

LY(m)

Surface SYS-117-02-01

-2.70 0.71 Exterior Shell Port Side SYS-117-02-02

-6.18 1.45 Exterior Shell Port Side SYS-117-02-03

-3.40 2.20 Exterior Shell Port Side SYS-117-02-04 0.57 0.07 Exterior Shell Port Side SYS-117-02-05

-0.13 0.82 Interior Shell Port Side SYS-117-02-06 2.00 1.56 Interior Shell Port Side SYS-117-02-07 4.78 0.32 Interior Shell Port Side SYS-117-02-08 3.39 1.07 Interior Shell Port Side SYS-117-02-09

-2.01 1.81 Exterior Shell Starboard Side SYS-117-02-10

-5.14 0.57 Exterior Shell Starboard Side SYS-117-02-11 1.59 1.3 I Exterior Shell Starboard Side SYS-117-02-12

-1.18 2.06 Interior Shell Starboard Side SYS-117-02-13 6.08 0.16 Interior Shell Starboard Side SYS-117-02-14 1.53 0.90 Interior Shell Starboard Side SYS-117-02-15 4.04 1.65 Interior Shell Starboard Side 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 SYS-117-02-014 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 SYS-117-02-16-J, interior shell starboard side and SYS-117-02-17-J, exterior shell port side. Those locations are documented on the field forms.

For this Impacted system 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 Systems and Components Judgmental For survey unit SYS-117-02, ten (10) scan areas were established. The survey package stated to scan I 00% of the accessible area in each scan area SA-0 I through SA-I 0. An estimated 100% of the accessible surface area in SYS-117-02 was to be scanned. Refer to for figures and maps depicting the measurement and scan locations in survey unit SYS-117-02.

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SAVANNAH Technical Staff Survey Unit Release Record l - - -- d 1 rt For this Impacted system 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 Classification Direct Investigation Levels Scan Investigation Levels Systems and

> Operational DCGLw

> Operational DCGLw Components 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 SYS-117-02, 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 MA RAD procedure STS-005-032, Survey Unit Turnover and Control, Reference (h). No conditions prohibited the proper collection of static and scan measurements.

FSS field activities were conducted under the approved FSS Package Number NSS-FSSP-SYS-117-02-00-00, which included DQOs, survey design, detailed FSS instructions, survey maps and survey forms. FSS field activities were projected to take three (3) 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 four (4) days to complete and were performed between July 16, 2024, and July 23, 2024.

An ambient background count rate was collected by taking a 1-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 1-minute static measurement was acquired at each location with the detector in contact with the surface.

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SAVANNA H Technical Staff Survey Unit Release Record l - -

- - izt All planned scan areas, SA-01 through SA-10, were scanned. Approximately 100% of the total surface area was scanned. The actual total scan area exceeds the scan coverage requirements for Systems and Components 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 SYS-117-02-14 and identified as SYS-117-02-14-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 (i).

For example, (derived from NUREG-1507) if the 41t contact Tc-99 efficiency is 0.1002 c/d and the 41t Cs-13 7 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 ambient background count rate from a I -minute count was 148 cpm. Rounding up the count rate to 150 cpm, using the contact detector weighted efficiency of 0.0849 for painted surfaces and 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 a 1-minute static measurement equal to 706.5 dpm/100 cm2 on painted surfaces. That value equals 1.4% of the operational DCGLw and 1.0% of the gross activity DCGLw.

Table 7-1, located on the next page, presents the activity concentration for all final static measurements. Remainder of this page left blank intentionally.

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S AVANNAH Technical Staff Survey Unit Release Record Table 7 Summary of Systematic, Judgmental, and QC Static Measurements Activity Concentration Measurement ID (dpm/100 cm2)

SYS-117-02-01 1448.32 SYS-117-02-02 1248.15 SYS-117-02-03 1295.25 SYS-117-02-04 1224.60 SYS-117-02-05 883.12 SYS-117-02-06 18015.73 SYS-117-02-07 9090.29 SYS-117-02-08 7547.77 SYS-117-02-09 1283.47 SYS-117-02-10 2143.05 SYS-117-02-11 1201.05 SYS-117-02-12 2366.77 SYS-117-02-13 12481.48 SYS-117-02-14 1448.32 SYS-117-02-15 4804.19 SYS-117-02-16-J 18486.73 SYS-117-02-17-J 7276.94 SYS-117-02-14-D 813.73 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 883.12 dpm/100 cm2 Maximum Measurement 18486.73 dpm/100 cm2 Mean 5426.19 dpm/100 cm2 Median 2143.05 dpm/100 cm2 Standard Deviation 5917.15 dpm/100 cm2 Coefficient of Variation 1.09 unitless Residual activity dose rate 1.17 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 SYS-117-02, the calculated dose from residual activity is 1.17 mrem/yr.

The scan MDC for the Ludlum 43-93 detector was calculated using the same rounded count rate of 150 cpm, the detector weighted efficiency on painted surfaces of 0.0582 c/d at a distance of 0.75 inches and using L TP Equation 5-8 (derived from NUREG-1507). The Survey Unit SYS-117-02 Page 15 of30 Fuel Transfer Tank, Retained Walls

S AVANNA H Technical Staff Survey Unit Release Record elevated area was assumed to be a 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 2,864.5 dpm/100 cm2. That value is 5.5% of the operational DCGLw and 4.1 % of the gross activity DCGLw.

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

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

(dom/100 cm2)

SA-01 1099.73 - 60141.59 30620.66 SA-02 3316.38 - 24056.64 13686.51 SA-03 2938.35 - 13866.93 8402.64 SA-04 5189.36 - 10842.67 8016.02 SA-05 3574.13 - 7629.39 5601.76 SA-06 2010.45 - 11151.97 6581.21 SA-07 2216.65 - 11048.87 6632.76 SA-08 1185.65 -14313.70 7749.68 SA-09 5687.68 - 13334.25 9510.96 SA-10 4570.76 - 39521.62 22046.19 The raw scan data with detector efficiencies are presented in Attachment 3.

One (1) static measurement was collected on July 23, 2024, in SA-01 due to a positive indication during scanning which triggered the 2,500 cpm action level. The follow-up static measurement, SA-01-01, resulted in an activity concentration of22,725.72 dpm/100 cm2, which is below the investigation level.

8.

QUALITY CONTROL The implementation of survey specific QC measures included the collection of one (I) replicate static measurement (SYS-117-02-0 I 4-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 G). 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 = 1 I,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.

Survey Unit SYS-117-02 Page 16 of30 Fuel Transfer Tank, Retained Walls

S AVANNAH Technical Staff Survey Unit Release Record

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 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 (k) 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 an Impacted system.

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 SYS-117-02 has met the DQOs of the FSS survey package. The survey unit is properly classified as an lmpacted system.

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.

Survey Unit SYS-117-02 Page 17 of30 Fuel Transfer Tank, Retained Walls

S AVANNAH Technical Staff Survey Unit Release Record l - -

- i rt

15.

(a)

(b)

(c)

(d)

(e)

(f)

(g)

(h)

(i)

G)

(k)

16.

The dose contribution from residual activity in survey unit SYS-117-02 is 1.17 mrem/yr TEDE, based on the mean activity of all the final measurements.

Survey unit SYS-117-02 is acceptable for unrestricted use.

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

STS-004-003, N.S. 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-139, TSD 21-089, Calculations to Support NSS Surface Contamination DCGLs, Revision I, 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, 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 SYS-117-02 Page 18 of30 Fuel Transfer Tank, Retained Walls

SAVANNAH Technical Staff Survey Unit Release Record

-_:._.. r - Figures and Maps Location of the Fuel Tran sf er Tank, Retained Walls H

- I Fuel Transfer Tank Wall I-~----~.-

DJ Survey Unit SYS-117-02 Fuel Transfer Taruc, Retained Walls Page 19 of30

SAVANNAH Technical Staff Survey Unit Release Record Fuel Transfer Tank, Retained Walls Systematic and Judgmental Static Locations SY 17 2-0 SYS-17_0

..Q4 VS-117-02-07

'------------__..J'----.....,=---'

'---------- --~-------------'

~

YS-117-02-01 Extenor Shel Port Side Interior Shell Port Side t

VSP Origin Point in Ship Coordinates: Exterior 1 '5" Aft ofFrame I 15

?onSod<Ope,ing VSP Origin Point in Ship Coordinates: Interior 1'4" AftofFrame 115 5 '2" to the Port of Centerline 26'9" above baseline 1 '0" Aft of Frame 110 5' IO" to the Starboard of Centerline 26'9" above baseline

~

YS-1 17-D2-t0 I

$-SYS-117--02-1 5' 1.5" to the Port of Centerline 26'9" above baseline 1 '0" Aft ofFrame 110 5'9" to the Starboard of Centerline 26'9" above baseline

~

i:

SYS-117-02-12~--,,'-.:....' ------~

Ext-=nor Shel Start>o d Side lntenor Shel starboard Side LEGEND:

& VSP SJ.mru Loe.:ttion Surface-Ongin Po,m Survey Unit SYS-117-02 NOTES:

SAMPLE LOCATIONS CREATED IN VISUAL SAMPLE PLAN NUMBER OF SAMPLES: 15 PLACEMENT METHOD: RANDOM START LOC: RANDOM Fuel Transfer Tank, Retained Walls BOW tr Page 20 of30

SAVANNAH Technical Staff Survey Unit Release Record Fuel Transfer Tank, Retained Walls, Scan Areas Interior Shell Exterior Shell Survey Unit SYS-117-02 Fuel Transfer Tank, Retained Walls Page 21 of30

S AVANNA H Technical Staff Survey Unit Release Record - Calibration Records Calibration Certificate

10 Number: 25035102000

20240305

1 RSCS 11 S

'¥' & Co Customer: Matthew G Hunter Instrument Serial Number Radiation Safety & Control Services Inc.

Ludlum Model 3002 25035102 93 Ledge Road Probe Model Serial Number Seabrook NH 03874 Ludlum 43-93 Precision Check Tes11 I

Test2 I

Test3 I

Mean I

4.98 kcpm I

Accuracy Check Range Target Value As Found As Left AUTO 500 Kcpm#

497 Kcpm#

AUTO SO Kcpm #

49.8 Kcpm #

AUTO 5 Kcpm#

4.98 Kcpm #

AUTO 0.5 Kcpm #

0.501 Kcpm #

Readings with

Indicate ranges where As-Found readings are >20% of Target value Readings with ** Indicate As-left readings are > 10% of Target value.

Readings with # Indicate ranges were calibrated using a pulser Probe Isotope 43-93 421410 Tc-99 43-93 421410 Cs-137(Beta) 43-93 421410 Tc-99 43.93 421410 Cs-137(Beta) 43-93 421410 Cs-137(Beta) 43.93 421410 Tc-99 43-93 4214 t 0 Cs-137(Beta) 43-93 4214 10 Tc-99 Physical Checks Light Check of Sclntilation Probes: Pass Outer Physical Check: Pass Tap Test. Pass Audio Function Check: Pass Cord check: Pass Calibration Date Set: Pass Efficiency 0.0269 C/D (4 Pl) 0.0552 CID (4 Pl) 0.0176 CID (4 Pl) 0.0389 CID (4 Pl) 0.1599 C/D (4 Pl) 0.1164 CID (4 Pl) 0.1100 CID (4 Pl) 0.0744 CID (4 Pl)

Comments: Calibrated with 20' C to C cable.

Customer Equipment ID NIST Source 10 127356 Tc-99 127357 Cs-137(Beta) 127356 Tc-99 127357 Cs-t37(Beta) 127357 Cs--137(Beta) 127356 Tc-99 127357 Cs-137(Bela) 127356 Tc-99 Electronics Checks High Voltage Geometry Flat Surface Flat Surface Flat Surface Flat Surface Flat Surface Flat Surface Flat Surface Flat Surface As Found 675 Volts 421410 Results Pass Source ID Pulser 98756 Pulser 98756 Pulser98756 Pulser98756 Comment On Grate On Grate 3/4" Above Grate 3/4" Above Grate On Contact On Contact 3/4

Above Source 3/4

Above Source As Left 795 Votts Calibrated By Nicole Wedlg QC Review By Matthew Hunter Date: Mar OS. 2024 Expires: Mar OS, 2025 QC Date: Mar OS. 2024 Au>>osphenc Conditions. Temperolure 71 I ' F Humodny 36 0 ~,. Barometn<: Pressure 30 29 10-llg In 1oleronce conditions ere bosed on lest results foling within SC)8Clfl8d limilS with no reducUon by the uncerw1n1y or lhe meosurernenl Unless otherwise stoled, thlS coltirobon wos performed by RSCS ot 93 Ledge Rd Seabrook, NH ulil121ng lhe following NIST Traceable sources Pulser 98756 (Cal Due Ocl 31. 2024)

WO<ked on cohbm~on N1cote Wed1g The reported expanded uncerui1111y ol measurement 1s staled os the slandard uncenomty ol measurement mult1p~ed by the coverage foct<< k such lhol the coverage probobllity cooesponds to opproxmotely 95*,,

Unless olhefw,se stated, calibrations pertormed,n conformance 10 the lollowing documents ANSI N323AB-2013: RSCS New Hompshl"e RlldooCb e Motenol License Number 381 R RSCS colibrooon services ore perfooned,n occordonce with the RSCS Rlld,ooon ProtectJoo Program Monual ood Standard Operobng Procedures R.1$kln!.afety&C0Nr0s<<vk.-W tlL.ootl'tON s......,J-10!74 (KIO; ~}S.tl!I t60l1 *74~7:l~

I 2 izt Survey Unit SYS-117-02 Page 22 of30 Fuel Transfer Tank, Retained Walls

SAVANNAH Technical Staff Survey Unit Release Record

~1 b t1011 c.,rtmc 10 l*mb r* 250)5112000 202'40306 1 RSCS Customer:

l.,11 5,00 Cpm Ra A 0 AUTO A

0 Al/TO Readin;;s. wttn

tr Ir.ate range11 vmere A!

R d~1g1 w,111 ** lml1¢:1, A r

ead1n;s wrth It lnd,ce:e ranges were cslI Pro

-43 93 42141i 4 9 421 17 43-3 21q 17 Cs-7(Beta1 43.93 421417 Tc-99 43 93 421~17 c~ 13 ca taJ 43-9 2 1 ' 7 Tc 9S 43-2 " 7 Cs-13/(Bet.a) 0 !.l65 0 1086 C 0 447 I)

I),,

1)

I) (4

'I ln1trument Ludl 111

.I 3002 rrobeUodel La a '3-93 1ST Source ID 127~7 Cs.-*:mBcta) 127356 Tc-9 127 7C,:meet 127356 c-9 127357 Cs-* 37( Bcto I 73!>6 lc* 9 127357 C

7(Bet 1 Sc I um r

2 03 1 2

~ri I Nun~ber 421.017 u

987!5~

Pu~r9B7 ij P

r 8756

..;.....:;..;.=:..,_ ___ C= cmment ISur'a,:;c I Su~zee 1 Surl

~~t Surf 0~ Grat On Grate 43.93 42141 1 le 9 0 Of.99 CID (4 P 1 177355 Tc-99 r 1 Surfr-e F".al Surface

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

_ _,::.._.:....::::.==--==~

AE. Found ____

.....:.A$

.=...L=fl.;.__~

1---=-=~=:.:ll:,__ __

__;7.;,0,;.1.;,V.:.,I::..1 :,__ ___

..!.701 V II Ct,51,orr r Equ 11ent I OC RG*icw B :ilatt.,ev, H n. r 4*

ssvre 30211, *r I

.-1 1,-,,;111, llh ltO,ea bon tir "* UI"

,ty a1 u, Survey Unit SYS-117-02 d b ledg.. fld f,

cr,I.

~ I mng I

"' *Ir rml>d 111 wrwn r, 10 lr,,.,n m;t,01 ;er.ces are r.e~

n ac

~

, ** ~~ /\\hSl/tlCSL Z5'10 1 1,li4 Fuel Transfer Tank, Retained Walls

fl '"

Page 23 of30

SAVANNAH Technical Staff Survey Unit Release Record Calibration Certificate

ID Number: 25035132000

20240305. 1 RSCS Customer: Matthew G Hunter Radiation Safety & Control Services, Inc.

93 Ledge Road Seabrook NH 03874 Instrument Ludlum Model 3002 Probe Model Ludlum 43-93 Serial Number 25035132 Serial Number 421425 Precision Check Test1 I

Test2 I

Test3 I

Mean I

Results 5.00 kcpm I

4.!l!lkcpm I

4.!l!I kcpm 1

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

499 Kcpm #

Pulser 98756 AUTO 50 Kcpm #

50 Kcpm #

Pulser 98756 AUTO 5 Kcpm#

5 Kcpm#

Pulser 98756 AUTO 0.5 Kcpm#

0.498 Kcpm #

Pulser 98756 Readings with

Indicate ranges where As-Found readings are >20% ofTarget value.

Readings with *

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

Readings with # indicate ranges were calibrated using a pulser Probe Isotope 43.93 421425 Tc-99 43-93 421425 Cs-137(Beta) 43-93 421425 Cs-137(Beta) 43-93 421425 Tc-99 43-93 421425 Cs-137(Beta) 43-93 421425 Tc-99 43-93 421425 Cs-137(Beta) 43-93 421425 Tc-99 Physical Checks Light Check of Sclntllatlon Probes: Pass Outer Physical Check: Pass Tap Test: Pass Audio Function Check: Pass Cord check: Pass Calibration Date Set: Pass Efficiency 0.0243 CID (4 Pl) 0.0505 C/D (4 Pl) 0.0398 C/D (4 Pl) 0.0177 C/D (4 Pl) 0.1 620 C/D (4 Pl) 0.1108 C/D (4 Pl) 0.1193 C/D (4 Pl) 0.0821 C/D (4 Pl)

Comments: Calibrated with 20' C to C cable.

Customer Equipment ID:

NIST Source ID 127356 Tc-99 127357 Cs-137(Beta) 127357 Cs-137(Beta) 127356 Tc-99 127357 Cs-137(Beta) 127356 Tc-99 127357 Cs-137(Beta) 127356 Tc-99 Electronics Checks High Voltage Calibrated By Nicole Wedlg QC Review By Matthew Hunter Atmospheric Cond1bons - Temperature 71 I ' F Hum1d1ty 36 0 "* Borometnc Pressure.30 29 In/hg Geometry Comment Flat Surface On Grate Flat Surface On Grate Flat Surface 3/4" Above Grate Flat Surface 314" Above Grate Flat Surface On Contact Flat Surface On Contact Flat Surface 3/4" Above Source Flat Surface 3/4" Above Source As Found As Left 678 Volts 780 Volts Date: Mar 05, 2024 Expires: Mar 05. 2025 QC Date: Mar 05. 2024 In tolerance condibons ore based on test results fnlhng within specified !units with no reduction by the uncertainty or the measurement Unless othe,wIse stoled, this calibroboo was pe!formed by RSCS ot 93 Ledge Rd Seabrook. NH uti,zmg the following NIST Traceable sources Pulser 98756 - (Col Due Oct 31, 2024)

Worked on colibrabon. Nicole Wedtg The reponed expanded unceruunty ol measurement Is stoled os the standard uncertainty of measurement multiplied by the coverage factor k such that the coverage probability cooesponds to approximately 95'-.

Unless othe,w1se stated, calibrations pe!formed in confo,monce to the following documents ANSI N323AB-2013; RSCS New t-ompshire RodIoactive Material License Number 381 R RSCS calibration services ore perto,med in accordance wllh the RSCS Radiation Protecuon Program Manual and Standard Operabng Procedures

~~'->OOfl S.~fY I Cotttro Ser,IUI Inc tl LedQe f\\OMI Se~ Nt1 0.3174 (800 5~S4lli

(&031 47'-6723 I 2 WWW,.OU.!l!ny con brl Survey Unit SYS-117-02 Page 24 of30 Fuel Transfer Tank, Retained Walls

S AVANNAH Technical Staff Survey Unit Release Record - Static Data Count Rate Total Weighted Eff Meter ID Measurement ID (com)

(c/d) 25035102 SYS-117-02-01 123 0.0849 25035102 S YS-117-02-02 106 0.0849 25035102 SYS-117-02-03 110 0.0849 25035102 SYS-117-02-04 104 0.0849 25035102 SYS-117-02-05 75 0.0849 25035102 SYS-117-02-06 1530 0.0849 25035102 SYS-117-02-07 772 0.0849 25035102 SYS-117-02-08 641 0.0849 25035102 SYS-117-02-09 109 0.0849 25035102 SYS-117-02-10 182 0.0849 25035102 SYS-117-02-11 102 0.0849 25035102 SYS-117-02-12 201 0.0849 25035102 SYS-117-02-13 1060 0.0849 25035102 SYS-117-02-14 123 0.0849 25035102 SYS-117-02-15 408 0.0849 25035102 SYS-117-02-16-J 1570 0.0849 25035102 SYS-117-02-17-J 618 0.0849 25035112 SYS-117-02-14-D 81 0.0995 25035102 SA-01-01 1930 0.0849 Note: Meter IDs 25035102 and 25035112 are connected to a Ludlum model 43-93 detector with an area of 100 cm 2.

Survey Unit SYS-117-02 Page 25 of30 Fuel Transfer Tank, Retained Walls

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

(cpm)

SA-01 64/3500 1782.0 SA-02 193/1400 796.5 SA-03 l 71 /807 489.0 SA-04 302/631 466."5 SA-05 208/444 326.0 SA-06 117/649 383.0 SA-07 129/643 386.0 SA-08 69/833 451.0 SA-09 331/776 553.5 SA-10 274/2300 1287.0 SA-06 223/501 362.0 SA-07 289/477 383.0 SA-08 313/676 494.5 SA-09 345/599 472.0 SA-10 266/640 453.0 Total Weighted Eff (c/d) 0.0582 0.0582 0.0582 0.0582 0.0582 0.0582 0.0582 0.0582 0.0582 0.0582 0.0582 0.0582 0.0582 0.0582 0.0582 Note: Meter ID 25035102 is connected to a Ludlum model 43-93 detector with an area of 100 cm2.

Survey Unit SYS-117-02 Page 26 of30 Fuel Transfer Tank, Retained Walls

SAVANNAH Technical Staff Survey Unit Release Record - Quality Control Assessment Measurement Initial measurement Absolute Value of the difference Condition d m/100 cm2 Avera e < 52,300 Survey Unit SYS-117-02 Absolute value of the difference 634.59 Fuel Transfer Tank, Retained Walls Value d m/100 cm2 1448.32 813.73 1131.025 634.59 Control Limit d m/100 cm2 11087.6 t

Result Pass Page 27 of30

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

(dpm/100 cm2)

SYS-117-02-01 1448.32 68251.68 SYS-117-02-02 1248.15 68451.85 SYS-117-02-03 1295.25 68404.75 SYS-117-02-04 1224.60 68475.40 SYS-117-02-05 883.12 68816.88 SYS-I I 7-02-06 18015.73 51684.27 SYS-117-02-07 9090.29 60609.71 SYS-117-02-08 7547.77 62152.23 SYS-117-02-09 1283.47 68416.53 SYS-117-02-10 2143.05 67556.95 SYS-117-02-11 1201.05 68498.95 SYS-117-02-12 2366.77 67333.23 SYS-117-02-13 12481.48 57218.52 SYS-117-02-14 1448.32 68251.68 SYS-117-02-15 4804.19 64895.81 SYS-117-02-16-J 18486.73 51213.27 SYS-117-02-17-J 7276.94 62423.06 Parameter Result Number of Measurements 17 Number of S+

17 Critical Value 12 Meets/ Doesn't Meet Acceptance Criteria Meets Survey Unit SYS-117-02 Fuel Transfer Tank, Retained Walls t

Sign

+l

+1

+]

+I

+1

+l

+]

+l

+]

+l

+]

Page 28 of30

S AVANNAH Technical Staff Survey Unit Release Record - Graphical Presentations Quantile Plot of Gross Activity Concentration 20,000

,,...._ 18.000 N

E u 16,000 0

0 14.000

~

_g-12,000 C 10.000 0

ro 8.000 C:

Q) u 6,000 C

0 u

4,000

--u < 2,000 0

I - --- A \\ rt 0°,o I0~o 20°0 30%

40%

50%

60%

70%

80%

90%

I00~o Survey Unit SYS-117-02 Page 29 of30 Fuel Transfer Tank, Retained Walls

SAVANNAH Technical Staff Survey Unit Release Record Histogram Survey Unit Number:

SYS-117-02

<.)

C:

u 0-u,_

w...

Fuel Transfer Tank, Survey Unit Name: Retained Walls 12 10 8

6

,t 2

0 --

308-l 5284 7-184 9685 I 1885 1-1086 l lpper end, alue (dpm/ 100 crn2)

Survey Unit SYS-117-02 Fuel Transfer Tank, Retained Walls t

16286 18487 Page 30 of30

ML25328A173

Text

SUMMARY

SUMMARY

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