ML17250A539

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Westinghouse Hematite Decommissioning Project - Final Status Survey Report Volume 4, Chapter 9, Survey Release Record for Building Survey Area 04, Survey Unit 01
ML17250A539
Person / Time
Site: 07000036
(SNM-0033)
Issue date: 09/15/2017
From:
Westinghouse
To:
Office of Nuclear Material Safety and Safeguards
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ML17250A543 List:
References
HEM-17-50
Download: ML17250A539 (25)


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Attachment 2 to HEM-17-50 August 15, 2017 Final Status Survey Final Report Volume 4, Chapter 9 Survey Release Record for Building Survey Area 04, Survey Unit 01 with CD containing Appendices Westinghouse Electric Company LLC, Hematite Decommissioning Project Docket No. 070-00036

Westinghouse Non-Proprietary Class 3 2017 Westinghouse Electric Company LLC. All Rights Reserved.

8 Westinghouse Final Status Survey Report Hematite Decommissioning Project Final Status Survey Final Report Volume 4, Chapter 9 TITLE:

REVISION:

Survey Area Release Record for Building Survey Area 04, Survey Unit 01 (BSA 04-01) 0 EFFECTIVE DATE: JUL 1 9 2017 Approvals:

Author:

0 7-17_,).() f, T Kenneth E. Pallagi Date Owner/Manager:

7/li )/7 W. Clark Evers Date HDP-RPT-FSS-308

Hematite Decommissioning Project FSSFR Volume 4, Chapter 9: Survey Area Release Record for Building Survey Area 04, Survey Unit 01 (BSA 04-01)

Revision: 0 I Page i of iii Table of Contents EXECUTIVE

SUMMARY

.............................................................................................. 1 1.0 REPORT BACKGROUND.............................................................................................. 1 2.0 HDP SITE, BSA AND SURVEY UNIT DESCRIPTION............................................. 1 2.1 HDP Site Description.............................................................................................. 1 2.2 BSA Configuration................................................................................................. 1 2.3 BSA 04-01 Survey Unit Description and Configuration........................................ 2 3.0 IDSTORY OF USE........................................................................................................... 3 3.1 Radioactive Materials BSA 04-01.......................................................................... 3 3.2 Remediation and Remedial Action Support Surveys (RASS) Phase...................... 3 3.2.1 Remedial Actions BSA 04-01.................................................................... 3 3.2.2 Remedial Action Support Survey for BSA 04-01....................................... 3 3.3 Isolation and Control............................................................................................... 4 4.0 BSA RELEASE CRITERIA............................................................................................ 5 5.0 FINAL STATUS SURVEY DESIGN BSA 04-01........................................................... 5 5.1 FSS Plan Design Requirements.............................................................................. 5 5.1.1 DCGLso..................................................................................................... 5 5.1.2 Scan Coverage............................................................................................ 6 5.1.3 Instrumentation........................................................................................... 6 5.1.4 Scan Minimum Detectable Concentration (MDC)..................................... 6 5.1.5 Static Minimum Detectable Concentration................................................ 8 5.1.6 Investigation Action Level.......................................................................... 8 5.1.7 BSA 04-01 FSS Design Summary.............................................................. 9 6.0 FINAL STATUS SURVEY IMPLEMENTATION BSA 04-01............................ 9 6.1 Scan Survey Performance....................................................................................... 9 6.2 Systematic Measurements..................................................................................... 10 6.3 Biased Measurements........................................................................................... 12 6.4 Quality Control Measurements............................................................................. 12 7.0 FINAL STATUS SURVEY RESULTS BSA 04-01...................................................... 12 8.0 ALARA EVALUATION BSA 04-01.............................................................................. 14 9.0 FSS PLAN DEVIATIONS BSA 04-01.......................................................................... 14 9.1 Remedial Actions During FSS.............................................................................. 14 10.0 DATA QUALITY ASSESSMENT................................................................................ 14 10.1 Data Quality Assessment for BSA 04-01............................................................. 14

11.0 CONCLUSION

BSA 04-01............................................................................................ 19 12.0 DOSE CONTRIBUTION OF BSA 04-01 TO THE LSA SURVEY UNIT................ 19

13.0 REFERENCES

................................................................................................................ 20 14.0 APPENDICES (TO BE PROVIDED ON A SEPARATE DATA DISC)................... 20

Hematite Decommissioning Project FSSFR Volume 4, Chapter 9: Survey Area Release Record for Building Survey Area 04, Survey Unit 01 (BSA 04-01)

Revision: 0 I Page ii of iii LIST OF TABLES Table 3-1, Summary of RASS Results for BSA 04-01....................................................................4 Table 4-1, Building and Structural Surfaces Gross Radioactivity DCGLw for Small Office......... 5 Table 5-1, Total Weighted Efficiency Calculation (Ludlum Model 43-89) for BSA 04-01........... 7 Table 5-2, FSS Design Summary for BSA 04-01............................................................................ 9 Table 6-1, FSS Measurement Locations for BSA 04-01............................................................... 11 Table 7-1, FSS Data Summary for BSA 04-01.............................................................................. 13 Table 10-1, Sign Test for BSA 04-01............................................................................................ 16 Table 11-1, BSA 04-01 DCGLso and Dose Summation............................................................... 19 LIST OF FIGURES Figure 2-1, BSA 04-01 Site Pond Dam........................................................................................... 2 Figure 6-1, BSA 04-01 Measurement Locations........................................................................... 10 Figure 10-1, Data Evaluation Checklists prepared for BSA 04-01............................................... 17

Hematite Decommissioning Project ALARA bgs CFR cm cpm CSM DCGL DCGLso DCGLw DP dpm ft FSS FSSFR HDP I&C IAL LSA m

m 2 MARS SIM MDA MDC mrem NAD NRC QC Ra RASS SOF SSC SU Tc Th u

FSSFR Volume 4, Chapter 9: Survey Area Release Record for Building Survey Area 04, Survey Unit 01 (BSA 04-01)

Revision: 0 LIST OF ACRONYMS AND SYMBOLS As Low As Reasonably Achievable below ground surface Code of Federal Regulations centimeter( s) count(s) per minute Conceptual Site Model Derived Concentration Guideline Level Derived Concentration Guideline Level for Small Office

\\ Page iii of iii DCGL for average concentrations over a survey unit, used with statistical tests.

("W" suffix denotes "Wilcoxon")

Hematite Decommissioning Plan disintegrations per minute foot (feet)

Final Status Survey Final Status Survey Final Report Hematite Decommissioning Project Isolation and Control Investigation Action Level Land Survey Area meter(s) square meter(s)

Multi-Agency Radiation Survey and Site Investigation Manual Minimum Detectable Activity Minimum Detectable Concentration milliroentgen equivalent man North American Datum U.S. Nuclear Regulatory Commission Quality Control Radium Remedial Action Support Survey Sum of Fractions Systems, Structures and Components Survey Unit Technetium Thorium Uranium

Hematite Decommissioning Project FSSFR Volume 4, Chapter 9: Survey Area Release Record for Building Survey Area 04, Survey Unit 09 (BSA 04-01)

Revision: 0 Page 1 of20 EXECUTIVE

SUMMARY

This Survey Area Release Record (SARR) presents the results of the final status radiological surveys of the Hematite Decommissioning Project (HDP) Building Survey Area (BSA) 04, Survey Unit (SU) 01 (BSA 04-01). As provided in Final Status Survey Final Report (FSSFR),

Volume 1, Chapter 1, Section 7.0 {ML15257A307}, the final report summary, FSSFR Volume 7, Final Status Survey Final Report, will be submitted at the conclusion of the post-remediation groundwater monitoring period. FSSFR Volume 7 will be submitted to demonstrate that the site has met the requirements for unrestricted release consistent with the requirements of the Title 10 Code of Federal Regulations (CFR) 20 Subpart E, "Criteria for License Termination."

As provided in FSSFR Volume 4, Chapter 1, Building Survey Areas (BSA) Overview, "There will be a number of ancillary structures that will remain at the time of license termination. These structures are primarily concrete and/or asphalt and provide an existing function. Examples are the Site Pond Dam, the Rail Scale foundation, parking lots and walkways." FSS of ancillary structures is conducted in accordance with HDP-PO-FSS-700, Final Status Survey Program.

The objective of the FSS for the SU was to obtain and document measurement results, analytical data, and other supporting information in order to demonstrate that the residual radioactivity levels in BSA 04-01 meets the criteria for unrestricted release.

This SARR was prepared as described in FSSFR Volume 4, Chapter 1, Section 8.0, Survey Area Release Record Organization, as implemented by FSS procedure HDP-PR-FSS-722.

1.0 REPORT BACKGROUND As a result of the U. S. Nuclear Regulatory Commission (NRC) feedback regarding the submittal of the FSSFR, Westinghouse and the NRC agreed that Westinghouse would develop an outline presenting the format and content of FSS documents required for NRC review. Westinghouse provided the outline to the NRC for discussion during the August 19, 2015, publicly noticed teleconference and the format was agreed upon {ML15238B032}.

FSSFR Volume 4, Chapter 1, Revision 1, Building Survey Areas (BSA) Overview provides the information common to building survey areas. This report, FSSFR Volume 4, Chapter 13, builds upon the general information provided in FSSFR Volume 4, Chapter 1, Revision 1.

2.0 HDP SITE, BSA AND SURVEY UNIT DESCRIPTION 2.1 HDP Site Description A general description of the HDP site is given in FSSFR Volume 1, Chapter l.

2.2 BSA Configuration During the development of the DP the site staff recognized that the demonstration of compliance necessary to release the site for unrestricted release would include the FSS of several structures that would potentially remain on the site after remediation was complete. Therefore discussion related to FSS was included in DP Chapter 14.

Hematite Decommissioning Project FSSFR Volume 4, Chapter 9: Survey Area Release Record for Building Survey Area 04, Survey Unit 09 (BSA 04-01)

Revision: 0 Page 2 of20 As some of the structures that remain onsite were not specifically discussed in the DP a new Survey Area Code designated BSA 04 was established to incorporate these ancillary remaining structures within the FSS program.

As such there is not a specific BSA configuration for ancillary remaining structures. Rather each BSA 04 structure is described in the section that contains the SU description and configuration.

For this Survey Area Release Record the BSA SU being addressed is the Site Pond Dam which is located within LSA 02-03.

2.3 BSA 04-01 Survey Unit Description and Configuration The BSA 04-01 SU consists of the Site Pond Dam which is constructed of concrete and is located in LSA 02-03. SU BSA 04-01 is located in the northern section of LSA SU 02-03 which is a Class 1 SU and as such BSA 04-01 has been designated a Class 1 SU. The total surface area of BSA 04-01 is 46.2 m2.

Figure 2-1 below shows the configuration of BSA 04-01.

Figure 2-1 BSA 04-01 Site Pond Dam I

I

__ _;!;~~_J1--~*~_.,--,..~_...;r-,-;:-~~--i:~=""~

Hematite Decommissioning Project FSSFR Volume 4, Chapter 9: Survey Area Release Record for Building Survey Area 04, Survey Unit 09 (BSA 04-01)

Revision: 0 Page 3 of20 3.0 HISTORY OF USE OF BSA 04-01 BSA 04-01 resides within the area of the site known as the Site Creek and Site Pond.

The Site Creek and Site Pond represent the release point for the process liquid effluent waste stream, from fuel fabrication and decommissioning operations. Prior to site operations the Site Dam and Site Pond did not exist. At that time the Site Creek was a natural free flowing spring (aka Site Spring) that ran directly to the Joachim Creek.

Following an AEC inspection conducted in 1960, Mallinckrodt determined that the Site Creek would be dammed below the point of entry for the Stormwater Drain System, such that the Site Pond, fed by the natural spring, was formed. The dam gave Mallinckrodt better control of discharges and sampling locations for liquid effluent Subsequently, site historical records indicate that the Site Pond was remediated in 1972 and the Site Dam was replaced at that time. Since installation of the dam structure in 1972 the current Site Dam remained in service up to the time of remediation and FSS.

Subsequently after completion of FSS of the Site Dam and Site Pond, the natural spring flow was returned to the Site Pond and Site Dam.

3.1 Radioactive Materials BSA 04-01 The Site Dam as the designated release point for the process liquid effluent waste stream, and with the data from previous remediation and characterizations during site operations, it was expected that the radioactive material identified on the Site Dam would be from site effluent operations. As such, the radioactive materials within BSA 04-01 consist of the radionuclides of concern as provided in the DP Section 14.1.1 and reiterated in FSSFR Volume 1, Chapter 1, Section 5.1.

3.2 Remediation and Remedial Action Support Surveys (RASS) Phase The sections below provide a discussion of the remediation and the preparation of BSA 04-01 for FSS.

3.2.1 Remedial Actions BSA 04-01 The remediation of BSA 04-01 was a remediation task within the overall project of the Site Pond remediation.

To facilitate the ability to remediate the Site Pond and the Site Dam a Site Spring/Pond Diversion was installed.

The diversion directed flow from the Site Spring downstream beyond the Site Dam. Once the Site Pond Diversion was placed into service the water was removed from the Site Pond allowing full access to the Site Dam.

Remediation of the Site Dam included high pressure washing of the surface and the removal of a pass through pipe section with the surrounding concrete.

3.2.2 Remedial Action Support Survey for BSA 04-01 Remedial Action Support Surveys are conducted to determine when an area or SU had been adequately prepared for FSS, and provide updated estimates of the parameters to be used for planning the FSS. RASS of miscellaneous structures such as the remaining concrete comprising

Hematite Decommissioning Project FSSFR Volume 4, Chapter 9: Survey Area Release Record for Building Survey Area 04, Survey Unit 09 (BSA 04-01)

Revision: 0 Page 4 of20 the Site Pond Dam were performed with handheld detectors, direct total surface contamination (TSC) measurements at specified intervals, biased measurements at areas of elevated activity or special areas of interest, and smear sampling for removable activity.

The results used to develop the FSS plans for BSA 04-01 are summarized in Table 3-1 below.

Survey Unit BSA 04-0 I Notes:

Table 3-1 Summary of RASS Results for BSA 04-01 Direct (TSC) Measurements (Net Alpha + Beta-Gamma)

Average Max 680 2649 Max Removable Activity Alpha Beta

< MDA 296 I. All units are in disintegrations per 100 square centimeters (dpm/1 00 cm2)

2. Results reflect net concentrations after subtraction of ambient background.

DCGL Fraction 3.6%

3.

DCGL Fraction: mean activity of all RASS direct measurements taken within the SU/SSC DCGL ( 18,925 dpm/l 00 cm2).

All results of the RASS were a fraction of the DCGLso (18,925 dpm/l 00 cm2) and the data set was considered sufficient to support FSS design.

3.3 Isolation and Control Isolation and Control of BSA 04-01 was performed in conjunction with the Isolation and Control of the surrounding LSA 02-03. As the LSA 02-03 SU completely encompassed the BSA 04-01 SU, no additional isolation features were required specific to BSA 04-01.

Hematite FSSFR Volume 4, Chapter 9: Survey Area Release Record for Building Survey Area Decommissioning 04, Survey Unit 09 (BSA 04-01)

Project Revision: 0 Page 5 of20 4.0 BSA RELEASE CRITERIA As the release criteria for all BSA SUs is common, FSSFR Volume 4, Chapter 1, Section 3.0, Release Criteria, provides a detailed discussion on the release criteria that is applicable to BSA 04-01. Table 4-1 provides the applicable DCGLs.

Table 4-1 Building and Structural Surfaces Gross Radioactivity DCGLw for Small Office DCGLw Radioactivity Fractions Radionuclide

( dpm/100 cm2)

Based on Characterization Data a U-234 20,000 8.27E-01 U-235 + D 19,000 3.72E-02 U-238 + D 21,000 l.27E-01 Tc-99 13,000,000 2.83E-03 Th-232 + C 1,200 3.21 E-03 Np-237 + D 2,700 5.57E-05 Pu-239/240 3,500 2.03E-06 Am-241 3,400 2.68E-03 Totals:

1.0 Gross Activity DCGLso (dpm/100 cm2) b:

18,925 a Values are taken from Table 4-1 of DP Chapter 4.

b Calculated using Equation 4-4 of MARSSlM and rounded down (truncated) to two significant figures.

5.0 FINAL STATUS SURVEY DESIGN BSA 04-01 This section of the report describes the method for determining the number of measurements required for the FSS of BSA 04-01 as well as summarizing the applicable requirements of the FSS Plan. These include the DCGLso, scan survey coverage and Investigation Action level (IAL).

The radiological instrumentation used in the FSS of BSA 04-01 and the detection sensitivities are also discussed.

5.1 FSS Plan Design Requirements FSS Plan requirements for BSA 04-01 were driven by the type (Structure) and Class (Class 1) of the SU and developed in accordance with HDP procedure, HDP-PR-FSS-701, Revision 7, Final Status Survey Plan Development, June 2015.

5.1.1 DCGLso During the FSS design process a review was performed of the RASS radiological survey data for BSA 04-01. The RASS radiological survey data provided an expectation that the structure would meet the release criteria of the DCGLso.

Hematite Decommissioning Project FSSFR Volume 4, Chapter 9: Survey Area Release Record for Building Survey Area 04, Survey Unit 09 (BSA 04-01)

Revision: 0 Page 6 of20 5.1.2 Scan Coverage As a Class 1 structure SU, the scan survey requirement is a minimum of 100% of the exposed surfaces of the structure.

5.1.3 Instrumentation The chosen instrumentation to perform the FSS was a Ludlum Model 43-93 detector, paired with a Ludlum Model 2360 data logging meter.

5.1.4 Scan Minimum Detectable Concentration (MDC)

Instrument detection sensitivities depend upon the measurement geometry, instrument efficiencies, count times and scan speeds. Both scan and static measurement sensitivities for the various detectors are determined using the guidance in Chapter 14 of the DP.

The calculations for detection sensitivity assume a nominal background rate of 200 cpm (based on observed operational instrument background) for the Ludlum Model 43-93 probe. The Scan MDC calculation for SSC SUs given m HDP-PR-FSS-701, Final Status Survey Plan Development, Step 8.3.5.b, was applied:

1.38 x Jbkgd x 60 Scan MDC =

60 1

0 707 xeff x (Probe Area) total 100 Equation 5-1 This equation assumes the following parameters:

An index of sensitivity (1.38) corresponding to the Type I and Type II error rates of 0.05 and 0.10, respectively.

A background count performed for 60 seconds A surveyor efficiency of 0.5.

In order to calculate the Scan MDC using the above equation, the total weighted efficiency

( efftota1) must be calculated for each probe used during FSS. The method for calculating the weighted and total weighted efficiency from Appendix A ofHDP-PR-HP-415 (Equation 1) is:

Weighted Instrument Efficiency = Ei

  • Es
  • Yield
  • Activity Fraction Total Weighted Instrument Efficiency = L Weighted Instrument Efficiency (for all nuclides of concern)

Notes:

i>, = 2 pi (n) instrument efficiency for nuclide of concern c,= surface efficiency for nuclide of concern Yield = 100% for all nuclides of concern Activity Fraction = value listed on Form HDP-PR-HP-415-2 for nuclide of concern Equation 5-2

Hematite FSSFR Volume 4, Chapter 9: Survey Area Release Record for Building Survey Area Decommissioning 04, Survey Unit 09 (BSA 04-01)

Project Revision: 0 Page 7 of20 The Scan MDC calculation using the inputs of the instrumentation used for FSS are given below.

The Static MDC for a detector having an area of 100 cm2 (e.g., Ludlum Model 43-93), a nominal background rate of 200 cpm (based on observed operational instrument background), and a total weighted efficiency of 9.48% is calculated to be:

1.38 x ~

x 60 60 1

2 Scan MDC=

( 100 ) = 2,250 dprn/100 cm 0.707 x0.0948x 100 Equation 5-3 The total weighted efficiency calculation worksheet for the Ludlum Model 43-93.

1s given m Table 5-1.

Table 5-1 Total Weighted Efficiency Calculation (Ludlum Model 43-93) for BSA 04-01 Ludlum 2360 Ludlum Model Active Probe a HOP Efficiency a Cal. Efficiency fl HOP Efficiency fl Cal. Efficiency 43-93 Area 287589 PR3 12650 100 cm2 25.3%

NIA 25.5%

NIA TOTAL WEIGHTED INSTRUMENT EFFICIENCY CALCULATION Maximum Instrument Surface Yield Activity Weighted Radionuclide Radiation Energy Efficiency Efficiency 100%

Fraction Efficiency (MeV)

(E;)

(E,)

Am-241 Alpha 5.6 0.2530 0.25 1.00 2.682E-03 l.70E-04 Np-237 Alpha 5.0 0.2530 0.25 1.00 5.573E-05 3.52E-06 Pu-239 Alpha 5.2 0.2530 0.25 1.00 2.027E-06 l.28E-07 Tc-99 Beta 0.294 0.2550 0.25 1.00 2.829E-03 l.80E-04 Th-232 Alpha 4.1 0.2530 0.25 1.00 3.214E-03 2.03E-04 Ra-228 Beta 0.046 0.2550 0.00 1.00 3.2 14E-03 O.OOE+OO Ac-228 Beta 2.13 0.2550 0.50 1.00 3.214E-03

4. IOE-04 Th-228 Alpha 5.5 0.2530 0.25 1.00 3.214E-03 2.03E-04 Ra-224 Alpha 5.8 0.2530 0.25 1.00 3.214E-03 2.03E-04 U-234 Alpha 4.9 0.2530 0.25 1.00 8.270E-O I 5.07E-02 U-235 Alpha 4.7 0.2530 0.25 1.00 3.720E-02 2.80E-03 Th-23 1 Beta 0.390 0.2550 0.25 1.00
3. 720E-02 2.82E-03 U-238 Alpha 4.3 0.2530 0.25 1.00 l.270E-OI 9.23E-03 Th-234 Beta 0.270 0.2550 0.25 1.00 l.270E-01 9.3 1 E-03 Pa-234m Beta 2.20 0.2550 0.50 1.00 1.270E-01 l.86E-02 I=

9.48%

Total Weighted Instrument Efficiency= 1: Weighted Instrument Efficiency for all Nuclides of Concern Weighted Instrument Efficiency=&;

  • i:,
  • Yield* Activity Fraction

&;= 2 Pi Instrument Efficiency for Nuclide of Concern I Lud 43-93 I i:,= Surface Efficiency for Nuclide of Concern

Hematite Decommissioning Project FSSFR Volume 4, Chapter 9: Survey Area Release Record for Building Survey Area 04, Survey Unit 09 (BSA 04-01)

Revision: 0 Page 8 of20 5.1.5 Static Minimum Detectable Concentration The Static MDC for Piping and Structural Surfaces is (using Equation 14-29, Section 14.4.4.2.5 of Chapter 14 of the DP) is calculated as follows:

where:

Static MDC ( dpm I I 00 cm2) =

Rs= Background count rate (cpm);

3+3.29 j RB ts( 1 + f!)

(Et)(ts)(100 ~m2) ts =Sample or measurement count time (minutes);

tb =Background count time (minutes);

Et =Total weighted efficiency (2rc); and; A = Probe area ( cm2).

Equation 5-4 The Static MDC calculation using inputs of the instrumentation used for FSS is given below.

The Static MDC for a detector having an area of 100 cm2 (e.g., Ludlum Model 43-93), a nominal background rate of 200 cpm (based on observed operational instrument background), and a total weighted efficiency of 9.48% is calculated to be:

Static MDC (dpm I JOO cm2) =

3+3.29j2oox1(1+i) _

2 (loo) - 726 dpm/100 cm (0.0948)(1) 100 Equation 5-5 The average background count rate (in cpm) is subtracted from each gross TSC measurement prior to calculation of a dpm value, which is in turn compared to the IAL or DCGLso. The typical background values for the Ludlum Model 43-93 detectors for FSS in the SU were between 100 and 300 cpm for BSA 04-01. Negative values are treated as zero for calculating the DCGL Fraction.

Note that the instrument sensitives presented above are the prospective values used during the development of the FSS Plan. The actual instrument sensitivities will vary slightly based on the background and efficiency of the scanning instrumentation that was used to perform the FSS survey.

5.1.6 Investigation Action Level The Investigation Action Level was established at 50% of the DCGLso (9,463 dpm /100 cm2).

Hematite FSSFR Volume 4, Chapter 9: Survey Area Release Record for Building Survey Area Decommissioning 04, Survey Unit 09 (BSA 04-01)

Project Revision: 0 Page 9 of20 5.1.7 BSA 04-01 FSS Design Summary The complete FSS Plan for BSA 04-01 is provided in Appendix B. A summary table of the requirements in the FSS Plan for BSA 04-01 is presented in Table 5-2 below.

Table 5-2 FSS Design Summary for BSA 04-01 Portable Instrument Scannin2:

Scan Coverage 100% of BSA 04-01 total area Scan MDC 2,250 dpm I 100 cm 2 (Ludlum 43-93)

Investigation Action Level (IAL): general area 9,463 dpm I 100 cm2 (50% of the DCGL)

Total Surface Contamination (TSC) Measurements:

Surface Minimum Number of Comments Measurements A total of 11 TSC measurements Site Pond Dam, all accessible locations have been systematically surfaces 11 designed from a random start point.

Removable Activity Locations:

After each TSC measurement, at the same point as the TSC measurement, using moderate pressure swipe a cloth smear over the surface (e.g. exterior wall, roof, window, etc.) in an S-shaped pattern within an approximately 4" by 4" box.

Biased Measurement Locations:

Perform static biased measurements at those points on the north wall (delineated by blue paint) where the RASS indicated activity exceeding the DCGL and which required subsequent decontamination.

Consult FSS supervision for guidance on the amount and specific locations of biased measurements. At locations where remediation has taken place or where biased measurements exceed the instrument static MDA, adjustments to instrument efficiency or volumetric sampling may be necessary - consult FSS supervision for guidance.

Instrumentation Ludlum 2360 with 43-93 scintillation detector.

Used for scanning and to obtain static (TSC) measurements.

Lud lum 2929 with 43 1 scintillation detector.

Used for counting of swipe (smear) samples.

6.0 FINAL STATUS SURVEY IMPLEMENTATION BSA 04-01 FSS was performed in accordance with procedure HDP-PR-FSS-712, Final Status Surveys of Structures, Systems, and Components.

6.1 Scan Survey Performance As a Class 1 SU the FSS plan required that l 00% of the exposed structural surfaces be subject to scannmg. Review of the FSS scans performed confirms that 100% of the structural surfaces were scanned as prescribed by the FSS Plan (provided in Appendix C).

Hematite Decommissioning Project FSSFR Volume 4, Chapter 9: Survey Area Release Record for Building Survey Area 04, Survey Unit 09 (BSA 04-01)

Revision: 0 Page 10 of20 6.2 Systematic Measurements Based on statistical evaluations of the RASS characterization data set used for FSS planning purposes, a minimum of eleven ( 11) TSC measurements were calculated for BSA 04-01. These direct, static-count measurement locations were designed in a randomly selected pattern (See Figure 6-1 ).

Determination of the required number of TSC measurements for the SU was performed according to the requirements in Step 8.3.4 of HDP-PR-FSS-701 (and is documented in the FSS Plan in Step 7 of Appendix P-2).

Additionally, a removable smear contamination measurement was collected at each TSC location, after the initial TSC measurement was collected. The smear measurement provides the necessary information to determine how much of the TSC measurement is considered removable contamination.

Table 6-1 provides the listing of systematic measurement locations as specified in the FSS Plan (Appendix B).

Figure 6-1 BSA 04-01 Measurement Locations BSA 04-01 Site Pond Dam North Wall Surfaces South Wal l Surfaces y

S.m~ Surlau Coordin.itei Coo1tinatn LOUtlOn (lee!J (leetl y

S.m:

Suri.Ke Coord1rmt>s Coordin.ite\\

tout (lHI)

(ffftJ Top Surfaces NW.in 36.l S.8 O.imTop 7.1 4.1 N W.ill 18.S 0.S Oamlop 14.3 4.1 NWaR 2U OS O.imlop 21.5 41 N W.JI 141 OS 10 0.)mfcp 28.7 4.1 SW.Jll 36.8 S.l II O.imTop 36.0 4.1 6

o.. mTop 0.1 4.1

Hematite FSSFR Volume 4, Chapter 9: Survey Area Release Record for Building Survey Area Decommissioning 04, Survey Unit 09 (BSA 04-01)

Project Revision: 0 Page 11 of 20 No systematic location exceeded the DCGLso The highest observed systematic TSC measurement was 886 dpm/100 cm2 (5% of the DCGLso).

No removable contamination measurement exceeded the Minimum Detectable Activity (MDA). The FSS documentation for BSA 04-01 is provided in Appendix C.

Table 6-1 FSS Measurement Locations for BSA 04-01 Procedure: HDP-PR-FSS-70 I, Final Status Survey Plan Development Hematite Decommissioning Project Revision: IO Appendix P-4, Page I of I APPENDIX P-4 FSS SAMPLE & MEAS REM ENT LOCATIO S & COO RD I NA TES Survey Area:

BSA 04

==

Description:==

Structure Survel:' Unit in "Area 5" Survey Unit:

01

==

Description:==

Site Pond Dam between LSA 02-02 and LSA 02-03 Survey Type:

FSS Classification:

Class I Northing Measurement or Surface Type Start Elevation End Elevation (feet)

Easting (feet)

Remarks I Notes Sample ID or CSM (Y Axis)

(X Axis)*

804-01-01-S-W-S-OO w

s NA NA 5.8 36.3 North Wall 804-01-02-S-W-S-OO w

s NA NA 0.5 28.5 North Wall 804-01-03-S-W-S-OO w

s NA NA 0.5 21.3 North Wall 804-01-04-S-W-S-OO w

s NA NA 0.5 14.1 North Wall 804-01-05-S-W-S-OO w

s NA NA 5.3 36.8 South Wall 804-01-06-S-W-S-OO w

s NA NA 4.1 0.1 Dam Top 804-01-07-S-W-S-OO w

s NA NA 4.1 7.1 Dam Top 804-01-08-S-W-S-OO w

s NA NA 4.1 14.3 Dam Top 804-01-09-S-W-S-OO w

s NA NA 4.1 21.5 Dam Top 804 1 O-S-W-S-00 w

s NA NA 4.1 28.7 Dam Top 804-01-1 1-S-W-S-OO w

s NA NA 4.1 36.0 Dam Top B04-0l-12-S-W-B-OO w

s NA NA 0.5 21.3 Dam Top B04-0l -1 3-S-W-B-OO w

s NA NA 0.5 28.5 Dam Top

  • X and Y coordinates are provided using Missouri - East State Plane Coordinates [North American Datum (NAO) 1983) (Open Land Area)

Surface: Floor = F; Wall = W; Ceiling = C; Roof = R CSM:

Three-Layer (Surface-Root-Deep) or Uniform Type:

Systematic= S, Biased = B; QC =Q; Investigation = I Quality Record

Hematite Decommissioning Project FSSFR Volume 4, Chapter 9: Survey Area Release Record for Building Survey Area 04, Survey Unit 09 (BSA 04-01)

Revision: 0 Page 12of20 6.3 Biased Measurement Two biased measurements were collected from BSA 04-01 at areas where scan surveys indicated elevated count rates. The maximum biased reading encountered in BSA 04-01 was 5,500 dpm/100 cm2 (29% ofthe DCGLso).

6.4 Quality Control Measurements For the purpose of FSS ancillary structure SUs are treated as "normal" structure SUs, and as such the Quality Control (QC) requirement found in HDP-PR-FSS-703, Final Status Survey Quality Control states that at least 5% of the total number of structural SU s undergoes a complete replicate survey by a different Health Physics Technician from that which was used in the original FSS of the selected structural SU. As there are 17 ancillary SUs in total identified for FSS, one QC replicate survey will be performed (5.8%). BSA 04-14 was randomly selected as the BSA to undergo a QC replicate survey, and as such, no QC measurements were necessary for BSA 04-01.

7.0 FINAL STATUS SURVEY RESULTS BSA 04-01 During the performance of FSS in BSA 04-01, only two small areas were identified by scan measurement to exceed the Scan MDC of 2,458 dpm /100 cm2. Biased measurements were collected at both locations, and the results found to be acceptable. No static measurement exceeded the IAL of 9,463 dpm I 100 cm2 (50% of the DCGLs0 ). No removable contamination measurement exceeded MDA, therefore no removable measurement exceeded 10% of the DCGLso. The highest observed systematic TSC measurement was 886 dpm /100 cm2 (5% of the DCGLso), and the average residual radioactivity based on all systematically collected measurements is 515 dpm/100 cm2 (3% of the DCGLso).

The analytical data sheets used to evaluate the BSA 04-01 FSS data are provided in Appendix A.

A summary table of the FSS results is presented below in Table 7-1.

Hematite FSSFR Volume 4, Chapter 13: Survey Area Release Record for Building Survey Area 04, Survey Unit 09 (BSA 04-01)

Decommissioning Project Revision: 0 Page 13of20 Table 7-1 FSS Data Summary for BSA 04-01 GROSS cpm BKG cpm Net cpm (a Combined Net Corrected Net Fraction of MEASUREMENT ID MEASUREMENT LOCATION DATE MEAS MEASUREMENT (a+l3)

(a+b)

+ 13) dpm/100 cm 2 (a+l3) dpm/100cm2 DCGL 804-01-01 -S-W-S-OO North Wall 8/8/2016 alpha + beta TSC 309 267 42.333 425 425 2%

804-01-02-S-W-S-OO North Wall 8/8/2016 alpha + beta TSC 278 267 11.333 114 114 1%

804-01-03-S-W-S-OO North Wall 8/8/2016 alpha + beta TSC 250 267

-16.67

-167 0

0%

804-01-04-S-W-S-OO North Wall 8/8/2016 alpha + beta TSC 313 267 46.333 465 465 2%

804-01-05-S-W-S-OO South Wall 8/8/2016 alpha + beta TSC 314 267 47.333 475 475 3%

804-01-06-S-W-S-OO Dam Top 8/8/2016 alpha + beta TSC 337 267 70.333 705 705 4%

804-01-07-S-W-S-OO Dam Top 8/8/2016 alpha + beta TSC 320 267 53.333 535 535 3%

804-01-08-S-W-S-OO Dam Top 8/8/2016 alpha + beta TSC 301 267 34.333 344 344 2%

804-01-09-S-W-S-OO Dam Top 8/8/2016 alpha + beta TSC 324 267 57.333 575 575 3%

804-01-1 O-S-W-S-00 Dam Top 8/8/2016 alpha + beta TSC 380 267 113.33 1137 1137 6%

804-01-11-S-W-S-OO Dam Top 8/8/2016 alpha + beta TSC 355 267 88.333 886 886 5%

804-01-12-S-W-8-00 Dam Top 8/8/2016 alpha + beta TSC 815 267 548.33 5500 5500 29%

804-01-13-S-W-8-00 Dam Top 8/8/2016 alpha + beta TSC 468 267 201.33 2019 2019 11%

  • NOTE: Differences from documented survey results are due to rounding in Excel Min 0

3%

Max 1137 Mean 515 DCGLso Median 475 0.75 Stdev 321.3 mrem

Hematite Decommissioning Project FSSFR Volume 4, Chapter 13: Survey Area Release Record for Building Survey Area 04, Survey Unit 09 (BSA 04-01)

Revision: 0 Page 14of20 8.0 ALARA EVALUATION BSA 04-01 All measurements collected within BSA 04-01 were evaluated against the DCGLso-For BSA 04-01 no measurement result exceeded the DCGLso.

The average result, based on all systematically collected measurements was 3% of DCGLso for BSA 04-01. The average of all measurements equates to residual activity contribution from the SU area of 0.75 rnrem/year for BSA 04-01. As the estimated Total Effective Dose Equivalent for LSA 04-01 including the dose contribution of BSA 04-01 is below the regulatory release criterion of 25 rnrern/year, the conclusion of the ALARA evaluation is that the FSS of BSA 04-01 was successful and that there would be no discemable benefit to the health and safety of the public in discounting the results of FSS and performing remediation of BSA 04-01.

9.0 FSS PLAN DE VIA TIO NS BSA 04-01 There were no deviations from the FSS Plan as written.

9.1 Remedial Actions During FSS As the measurement results of the FSS indicated the results were below the DCGLso no remedial actions during FSS were necessary.

10.0 DATA QUALITY ASSESSMENT The DQO process is thoroughly integrated within the DP and Hematite FSS procedures. The steps of the DQO process specific to FSS of structures are presented in HDP-PO-FSS-700 Section 9.0 and correspond to the DQO steps described in Chapter 14, Section 4.2.1 of the DP.

The HDP DQO process reflects the recommendations given in MARSSIM, Chapter 2, Figure 2-2.

10.1 Data Quality Assessment for BSA 04-01 The Data Quality Assessment of the survey methodology, measurement and analysis results to ascertain the validity of the conclusion for BSA 04-01 (see Figure 10-1) provides the following:

The field and laboratory instruments utilized were capable of detecting activity at an MDC less than the appropriate investigation level, and were verified to be operable prior to and after use in accordance with HDP-PR-HP-415 (Operation of the Ludlum 2360 for Final Status Survey), and HDP-PR-HP-411 (Radiological Instrumentation).

The calibration of all instruments that were used to measure or analyze data was current at the time of use and the calibrations of the instruments were performed using a NIST traceable source. The instruments used were successfully source checked prior to and after use.

The TSC systematic samples that were collected (on a random-start triangular grid) and the scan surveys that were conducted were performed in accordance with procedure HDP-PR-FSS-712, Final Status Surveys of Structures, Systems and Components.

Hematite Decommissioning Project FSSFR Volume 4, Chapter 13: Survey Area Release Record for Building Survey Area 04, Survey Unit 09 (BSA 04-01)

Revision: 0 Page 15 of20 Quality Control sample results were not necessary for BSA 04-01. However a Quality Control Replicate Survey was performed for BSA 04-14, and the results were found to be acceptable, satisfying the requirement that a minimum of 5% of structure surveys undergo a successful QC Replicate Survey.

BSA 04-01 survey and sample results were independently reviewed and validated in accordance with HDP-PR-FSS-721 Final Status Survey Data Validation.

Eleven (11) systematic measurements were collected in BSA 04-01. None of the 11 measurements exceeded the DCGLso resulting in a systematic average result of 3% of the DCGLso. As such performance of the Sign Test is not required, but was still performed for illustrative purposes and is provided in Table 10-1. The Sign Test was successful as the total number of systematic measurements (11 ),

exceeded the minimum requirement of 8 measurements.

Smear samples were collected at each TSC measurement location after the initial TSC measurement was collected. No removable smear sample exceeded MDA, and therefore no removable activity exceeding 10% of the DCGLso was identified.

The maximum observed result in BSA 04-01 was 29% of the DCGLso. The average residual radioactivity concentration fraction based on the systematically collected measurements was 3% of the DCGLso, resulting in a residual dose contribution of 0.75 mrem/year.

No FSS measurement result in BSA 04-01 exceeded the DCGLso, therefore an elevated measurement comparisons or hot spot averaging was not required.

HDP staff ensured that a visual inspection of the SU configuration and of the Isolation & Control measures for BSA 04-01 (within LSA 02-03) was completed prior to and after the performance of the FSS. BSA 04-01 remained isolated after the completion of FSS field activities ensuring SU isolation, until all Field FSS activities for the Site Pond were completed.

Hematite FSSFR Volume 4, Chapter 13: Survey Area Release Record for Building Survey Area 04, Survey Unit 09 (BSA 04-01)

Decommissioning Project Revision: 0 Page 16of20 Table 10-1 Sign Test for BSA 04-01 Sign Test MARSSIM Table 1-3 MARSSIM Table 1-3 Critical Values for Gross TSC I Adj.

Difference Corrected Critical Values for the the Sign Test SAMPLE ID SAMPLE ID Gross TSC Gross DCGL (W.)

(1-W.)

Difference Sign Test Statistic S+

Statistic S+

Alpha=

Alpha=

804-01-01 -S-W-S-OO North Wall 425 0.022 0.978 0.978 a= 0.05 N

0.05 N

0.05 804-01 S-W-S-OO North Wall 114 0.006 0.994 0.994 4

4 28 18 804-01 S-W-S-OO North Wall 0

0.000 1.000 1.000 5

4 29 19 804-01 S-W-S-OO North Wall 465 0.025 0.975 0.975 6

5 30 19 804-01 S-W-S-OO South Wall 475 0.025 0.975 0.975 7

6 31 20 804-01 S-W-S-OO Dam Top 705 0.037 0.963 0.963 8

6 32 21 804-01-07-S-W-S-OO Dam Top 535 0.028 0.972 0.972 9

7 33 21 804-01-08-S-W-S-OO Dam Top 344 0.018 0.982 0.982 10 8

34 22 804-01-09-S-W-S-OO Dam Top 575 0.030 0.970 0.970 11 8

35 22 804-01 -1 O-S-W-S-00 Dam Top 1137 0.060 0.940 0.940 12 9

36 23 804-01 -1 1-S-W-S-OO Dam Top 886 0.047 0.953 0.953 13 9

37 23 Number of Positive Differences (S+)

11 14 10 38 24 Sign Test Critical Value (MARSSIM Table 1-3) 8 15 11 39 25 16 11 40 25 TEST:

PASS 17 12 41 26 If every measurement in the systematic sample population is <= the DCGL, a statistical test is not reQuired.

18 12 42 26 19 13 43 27 20 14 44 27 21 14 45 28 22 15 46 29 23 15 47 29 24 16 48 30 25 17 49 30 26 17 50 31 27 18

Hematite Decommissioning Project FSSFR Volume 4, Chapter 13: Survey Area Release Record for Building Survey Area 04, Survey Unit 09 (BSA 04-01)

Revision: 0 I Page 17 of20 Figure 10-1 Data Evaluation Checklists prepared for BSA 04-01 (page 1 of 2)

Hematite Procedure: l-IDP-PR-FS -721. Final Statu Survey Data Evaluation Decommissioning 1

1 Project Westinghouse on-Proprietary Class 3 Revision: 9 Appendix G-1. Page I of 2 APPEN DIX G-1 FINAL STAT SS RVEY DATA Q UALITY OBJECTI VES REVIEW CHECKLIST Survey Area:

BSA 04 01

==

Description:==

Structure Survey Unit in "Area 5" Survey Unit:

==

Description:==

Site Pond Dam between LSA 02-02 and LSA 02-03 I.

Have all measurements and/or analysis results that will be subjected to data analysi for FSS been individually reviewed and validated in accordance with Section 8.1 of this procedure?

2.

Have all systematic measurements and/or amples been taken or acquired at the locations specified in the FSSP and the FSS ample Instructions?

3.

Have all scans surveys been perfo1med of the area specified as required in the F SP and the FS San1ple Instructions?

4.

Have all biased measurements and/or samples been taken or acquired at the locations specified in the FSSP & the FSS Sample Instructions?

5.

Have duplicate and/or split samples or measurements been taken or acquired at each location designated as a QC sample?

6.

Were the instruments used to measure or analyze the survey data capable of detecting the ROCs or gross activity at a MDC less than the appropriate investigation level?

7.

Was the calibration or all instrnments that were used to mea ure or analyze data. cunent at the time of use and were those calibrations performed using a I T traceable source?

8.

Were the instruments successfully response-checked before use and.

where required. after use on the day the data wa measured?

9.

Do the samples match those identified on the chain of custody?

I 0.

Do the QC ample Results meet the acceptance criteria as specified in HDP-PR-F

-703. Final Status Survey Quality Control?

11. Are all Laboratory QC parameters within acceptable limits?

Yes [gj No 0 Ye [gj o 0 Yes [gj o 0 Yes [gj No 0 NA D Yes D No D NA [gj Yes [gj No 0 Yes~ NoO Yes [gj No D Yes D No D A [gj Yes D No D NA [gj Yes D o D NA [gj If "No'* was the response to any of the questions above. then document the discrepancy as well as any corrective actions that were taken to resolve the discrepancy.

Comments: NA Quality Record

Hematite FSSFR Volume 4, Chapter 13: Survey Area Release Record for Building Survey Area 04, Decommissioning Survey Unit 09 (BSA 04-01)

Project Revision: 0 I Page 18 of 20 Figure 10-1 Data Evaluation Checklists prepared for BSA 04-01 (page 2 of 2)

Hematite Procedure: HDP-PR-FSS-721, Final Status urvey Data Evaluation Decommissioning Westinghouse Non-Proprietary Class 3 I Revision: 9 l Appendix G-1. Page 2 of 2 Project APPENDIX G-1 FINAL STATUS SURVEY DATA QUALITY OBJECTIVES REVIEW CHECKLIST Survey Area:

BSA 04

==

Description:==

Structure Survey Unit in "Area 5" Survey Unit:

01

==

Description:==

Site Pond Dam between LSA 02-02 and LSA 02-03 Discrepancy:

NA Corrective Actions Taken:

NA

11.

Have the corrective actions resolved the discrepancy with the data')

YesO No DNA IZJ

a. Jf **No'". then forward this fonn to the RSO.
12. The following questions will be answered by the RSO.
a. If the answer to question 11 was** o'*. then is the affected data YesO No DNA JZl still valid?
b. If **No'*, tben are the existing valid measurements or samples YesD No0 NA~

sufficient to demonstrate compliance for the survey unit?

c. If **No'". then direct the acquisition of additional measurements or samples as necessary to demonstrate compliance for the survey unit.

Prepared by (HP taff):

Ellen C. Jakub CZ~~-<

t 111 11 £.>

(Prinl NamcJ I

(D~tc )

Approved by (RSO):

W. Clark Evers lJ (!/-/-:______

/1/i~(p (Prinl Nume)

(Sig.nature)

Quality Record

Hematite Decommissioning Project FSSFR Volume 4, Chapter 13: Survey Area Release Record for Building Survey Area 04, Survey Unit 09 (BSA 04-01)

Revision: 0 I Page 19 of20

11.0 CONCLUSION

BSA 04-01 An adequate quantity and quality of radiological surveys and measurements has been performed, evaluated and documented to demonstrate that the dose associated with the structures designated as BSA 04-01 of 0.75 mrem/year does not to exceed the dose criterion for unrestricted release in accordance with 10 CFR 20.1402 of25 mrem/year.

Table 11-1 BSA 04-01 DCGLso and Dose Summation A VE. SU RESIDUAL RADIOACTIVITY DCGLso Dose 3%

0.75 mrem/year 12.0 DOSE CONTRIBUTION OF BSA 04-01 TO THE LSA SURVEY UNIT The 0.75 mrem/year dose contribution determined for the structure designated as BSA 04-01 will be added to the total dose determination for SU LSA 02-03.

Hematite Decommissioning Project FSSFR Volume 4, Chapter 13: Survey Area Release Record for Building Survey Area 04, Survey Unit 09 (BSA 04-01)

Revision: 0 I Page 20 of 20

13.0 REFERENCES

13.1 D0-08-004, Hematite Decommissioning Plan {ML092330123}

14.0 APPENDICES (To Be Provided On A Separate Data Disc)

APPENDIX A:

Analytical Data Evaluation Spreadsheets for BSA 04-01 APPENDIX B:

FSS Plan Development for BSA 04-01 APPENDIX C:

FSS Documentation for BSA 04-01