B. Watson Ltr. Re: Report No. 1: Independent Confirmatory ...Energy Commission (AEC) granted an operating license, DPR-9, to the Power Reactor Development Company (PRDC), a consortium

Enrico Fermi Atomic Power Plant, Unit 1 2018-SR-01-0

INDEPENDENT CONFIRMATORY SURVEY SUMMARY AND RESULTS FOR THE ENRICO FERMI ATOMIC POWER PLANT, UNIT I

NEWPORT, MICHIGAN

Prepared by

E. M. Harpenau

Independent Environmental Assessment and Verification Program Oak Ridge Institute for Science and Education

Oak Ridge, Tennessee 37831-0017

Prepared for the U.S. Nuclear Regulatory Commission

FINAL REPORT

OCTOBER 2010 Prepared by the Oak Ridge Institute for Science and Education, under interagency agreement (NRC FIN No. F1008) between the U.S. Nuclear Regulatory Commission and the U.S. Department of Energy. The Oak Ridge Institute for Science and Education performs complementary work under contract number DE-AC05-06OR23100 with the U.S. Department of Energy.


ACKNOWLEDGMENTS

The author would like to acknowledge the significant contributions of the following staff members:

FIELD AND SUPPORT

T. J. Vitkus E. Montalvo A. M. Hood

LABORATORY

R. D. Condra

J. S. Cox W. P. Ivey

W. F. Smith

ADMINISTRATIVE

J. L. Clary R. M. Fink

K. M. Moore A. Ramsey

EDITORIAL

D. J. Steger

ILLUSTRATORS

A. M. Hood

Enrico Fermi Atomic Power Plant, Unit 1 i 2018-SR-01-0

TABLE OF CONTENTS

PAGE LIST OF FIGURES ......................................................................................................................................... iii

LIST OF TABLES ........................................................................................................................................... iv

ABBREVIATIONS AND ACRONYMS ..................................................................................................... v

1.0 INTRODUCTION .................................................................................................................................... 1

2.0 SITE DESCRIPTION ............................................................................................................................... 1

3.0 OBJECTIVES ............................................................................................................................................. 2

4.0 DOCUMENT REVIEW........................................................................................................................... 2

5.0 PROCEDURES .......................................................................................................................................... 2

5.1 REFERENCE SYSTEM ......................................................................................................................... 3

5.2 SURFACE SCANS ................................................................................................................................. 3

5.2.1 Interior Survey Units ................................................................................................................ 4

5.2.2 Exterior Survey Areas .............................................................................................................. 4

5.3 SURFACE ACTIVITY MEASUREMENTS ............................................................................................. 4

5.4 SOIL AND MISCELLANEOUS MATERIAL SAMPLING ...................................................................... 5

5.5 SURFACE ACTIVITY DATA COMPARISON ....................................................................................... 5

6.0 SAMPLE ANALYSIS AND DATA INTERPRETATION .............................................................. 5

7.0 APPLICABLE SITE GUIDELINES ..................................................................................................... 5

8.0 FINDINGS AND RESULTS .................................................................................................................. 6

8.1 DOCUMENT REVIEW ......................................................................................................................... 6

8.2 SURFACE SCANS ................................................................................................................................. 7

8.2.1 Interior Survey Units ................................................................................................................ 7

8.2.2 Exterior Grounds and Roofs .................................................................................................. 7

8.3 SURFACE ACTIVITY MEASUREMENTS ............................................................................................. 7

8.4 SURFACE ACTIVITY DATA COMPARISON ....................................................................................... 8

8.5 RADIONUCLIDE CONCENTRATIONS IN SOIL AND ROOF SAMPLES ........................................... 9

9.0 COMPARISON OF RESULTS WITH GUIDELINES ..................................................................... 9

10.0 SUMMARY ................................................................................................................................................ 9

11.0 REFERENCES ....................................................................................................................................... 11

APPENDIX A FIGURES

APPENDIX B TABLES

Enrico Fermi Atomic Power Plant, Unit 1 ii 2018-SR-01-0

TABLE OF CONTENTS (cont.)

PAGE APPENDIX C MAJOR INSTRUMENTATION

C.1 SCANNING AND MEASUREMENT INSTRUMENT/DETECTOR COMBINATIONS .................... C-1

C.1.1 Gamma .................................................................................................................................. C-1

C.1.2 Alpha and Alpha Plus Beta ................................................................................................. C-1

C.2 LABORATORY ANALYTICAL INSTRUMENTATION .................................................................... C-1

APPENDIX D SURVEY AND ANALYTICAL PROCEDURES

D.1 PROJECT HEALTH AND SAFETY ................................................................................................. D-1

D.2 CALIBRATION AND QUALITY ASSURANCE ................................................................................ D-1

D.3 SURVEY PROCEDURES .................................................................................................................. D-2

D.3.1 Surface Scans ........................................................................................................................ D-2

D.3.2 Surface Activity Measurements .......................................................................................... D-2

D.3.3 Soil Sampling ........................................................................................................................ D-3

D.4 RADIOLOGICAL ANALYSIS .......................................................................................................... D-3

D.4.1 Gamma Spectroscopy ......................................................................................................... D-3

D.5 DETECTION LIMITS ...................................................................................................................... D-4

Enrico Fermi Atomic Power Plant, Unit 1 iii 2018-SR-01-0

LIST OF FIGURES

PAGE Figure A-1: Location of the Detroit Edison Enrico Fermi Atomic Power Plant,

Units 1 and 2 ........................................................................................................................................... A-1

Figure A-2: Enrico Fermi Atomic Power Plant, Unit 1 Plot Plan ......................................................... A-2

Figure A-3: Turbine Building, Fourth Floor—Alpha plus Beta Radiation Floor Scans .................... A-3

Figure A-4: Turbine Building, Fifth Floor—Alpha plus Beta Radiation Floor Scans ........................ A-4

Figure A-5: Turbine Building, Sixth Floor—Alpha plus Beta Radiation Floor Scans ........................ A-5

Figure A-6: Steam Generator Building, Upper Level—Alpha plus Beta Radiation

Floor Scans .............................................................................................................................................. A-6

Figure A-7: Steam Generator Building, Basement—Alpha plus Beta Radiation Floor Scans .......... A-7

Figure A-8: Fermi 1—External Gamma Radiation Scans of Open Land Areas ................................. A-8

Figure A-9: Turbine Building, Fifth Floor Roof—Exterior Gamma Radiation Scans ....................... A-9

Figure A-10: Turbine Building, Seventh Floor Roof—Exterior Gamma Radiation Scans ............. A-10

Figure A-11: Turbine Building, Fourth Floor—Alpha plus Beta Direct

Measurement Locations ...................................................................................................................... A-11

Figure A-12: Turbine Building, Fifth Floor—Alpha plus Beta Direct


Figure A-13: Turbine Building, Sixth Floor—Alpha plus Beta Direct


Figure A-14: Steam Generator Building, Upper Level—Alpha plus Beta Direct


Figure A-15: East Sodium Gallery—Alpha plus Beta Direct Measurement Locations ................... A-15

Figure A-16: Waste Gas Building—Alpha plus Beta Direct Measurement Locations ..................... A-16

Figure A-17: West Sodium Gallery—Alpha plus Beta Direct Measurement Locations .................. A-17

Figure A-18: Fermi 1—Exterior Soil and Turbine Roof Samples ....................................................... A-18

Enrico Fermi Atomic Power Plant, Unit 1 iv 2018-SR-01-0

LIST OF TABLES

PAGE Table 1: Confirmatory Structural Survey Units ............................................................................................. 4

Table 2: Surface Activity Range Summary ..................................................................................................... 8

Table B-1: Surface Activity and Soil Concentration DCGLs ..................................................................B-1

Table B-2: ESG01-01comparative Direct Measurement Results ...........................................................B-2

Table B-3: Fermi 1 Radionuclide Surface Activity Levels .......................................................................B-3

Table B-4: Fermi 1 Radionuclide Concentrations for Activation and Fission Products

in Soil and Building Media (pCi/g) .......................................................................................................B-5

Table D-1: MDC Derived from Total Absorption Peak ....................................................................... D-4

Enrico Fermi Atomic Power Plant, Unit 1 v 2018-SR-01-0

ABBREVIATIONS AND ACRONYMS

AEC Atomic Energy Commission cm centimeter cpm counts per minute DCGLW derived concentration guideline level DCGLGA gross activity derived concentration guideline level DOE U.S. Department of Energy DTE Detroit Edison Company dpm disintegrations per minute ESG East Sodium Gallery Fermi 1 Enrico Fermi Atomic Power Plant, Unit 1 Fermi 2 Enrico Fermi Atomic Power Plant, Unit 2 FSS final status survey FSSP Final Status Survey Package FSSR Final Status Survey Report gal gallon GPS global positioning system IEAV Independent Environmental Assessment and Verification Program ITP Intercomparison Testing Program kg kilogram MAPEP Mixed Analyte Performance Evaluation Program MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual MDC Minimum Detectable Concentration MeV million electron volts m2 square meter MW megawatt mrem millirem NAD North American Datum NaI sodium iodide NIST National Institute of Standards and Technology NRC U.S. Nuclear Regulatory Commission NRIP NIST Radiochemistry Intercomparison Program ORAU Oak Ridge Associated Universities ORISE Oak Ridge Institute for Science and Education pCi/g picocuries per gram PRDC Power Reactor Development Company

Enrico Fermi Atomic Power Plant, Unit 1 vi 2018-SR-01-0

ABBREVIATIONS AND ACRONYMS (cont.)

ROC Radionuclide of Concern SGB Steam Generator Building TAP Total Absorption Peak TBN Turbine Building WGB Waste Gas Building WSG West Sodium Gallery yr year


FINAL INDEPENDENT CONFIRMATORY SURVEY SUMMARY

AND RESULTS FOR THE ENRICO FERMI ATOMIC POWER PLANT, UNIT I

NEWPORT, MICHIGAN

1.0 INTRODUCTION

Enrico Fermi Atomic Power Plant, Unit 1 (Fermi 1) was a fast breeder reactor design that was

cooled by sodium and operated at essentially atmospheric pressure. On May 10, 1963, the Atomic

Energy Commission (AEC) granted an operating license, DPR-9, to the Power Reactor

Development Company (PRDC), a consortium specifically formed to own and operate a nuclear

reactor at the Fermi 1 site. The reactor was designed for a maximum capability of 430 megawatts

(MW); however, the maximum reactor power with the first core loading (Core A) was 200 MW. The

primary system was filled with sodium in December 1960 and criticality was achieved in

August 1963.

The reactor was tested at low power during the first couple years of operation. Power ascension

testing above 1 MW commenced in December 1965 immediately following the receipt of a

high-power operating license. In October 1966, during power ascension, zirconium plates at the

bottom of the reactor vessel became loose and blocked sodium coolant flow to some fuel

subassemblies. Two subassemblies started to melt and the reactor was manually shut down. No

abnormal releases to the environment occurred. Forty-two months later; after the cause had been

determined, cleanup completed, and the fuel replaced, Fermi 1 was restarted. However, in

November 1972, PRDC made the decision to decommission Fermi 1 as the core was approaching

its burn-up limit. The fuel and blanket subassemblies were shipped off-site in 1973. Following that,

the secondary sodium system was drained and sent off-site. The radioactive primary sodium was

stored on-site in storage tanks and 55 gallon (gal) drums until it was shipped off-site in 1984. The

initial decommissioning of Fermi 1 was completed in 1975. Effective January 23, 1976, DPR-9 was

transferred to the Detroit Edison Company (DTE) as a “possession only” license (DTE 2009).

2.0 SITE DESCRIPTION

Fermi 1 is located in Monroe County near the town of Newport, Michigan on the western bank of

Lake Erie (Figures A-1 and A-2). Fermi 1 and Enrico Fermi Atomic Power Plant, Unit 2 (Fermi 2)

are located in the same controlled area on the same site. Fermi 1, however, stands beyond the

Enrico Fermi Atomic Power Plant, Unit 1 2 2018-SR-01-0

protected operational area of Fermi 2. The Fermi 1 License Termination boundary is made up of

27,200 square meters (m2) including roads, a railroad spur, buildings and land areas; a portion of

which is occupied by an oily waste bin (DTE 2009). Figure A-2 shows the plot plan and associated

building identifications.

3.0 OBJECTIVES

The objectives of the confirmatory surveys were to provide independent contractor field data

reviews and to generate independent radiological data for use by the U. S. Nuclear Regulatory

Commission (NRC) in evaluating the accuracy and adequacy of the licensee’s procedures and Final

Status Survey (FSS) results.

4.0 DOCUMENT REVIEW

Prior to on-site activities, the Oak Ridge Institute for Science and Education (ORISE) was tasked

with reviewing the Enrico Fermi Atomic Power Plant, Unit 1 Final Status Survey Report (FSSR) and

the Final Status Survey Package (FSSP) in DTE’s Fermi 1 License Termination Plan (LTP). The

FSSP was specifically reviewed to identify the site’s Radionuclides of Concern (ROC)s and the

associated derived concentration guideline levels (DCGLW), ORISE also reviewed the licensee’s

survey design and data quality objectives, instrumentation and calibration, and survey measurement

methods to be used during the FSS (DTE 2009). All documents and data were reviewed for

adequacy and appropriateness taking into account the LTP and Multi-Agency Radiation Survey and

Site Investigation Manual (MARSSIM) guidance (DTE 2009 and NRC 2000).

5.0 PROCEDURES

The ORISE survey team visited the Fermi 1 site from July 12 through 15, 2010, to perform visual

inspections, confirmatory measurements and sample collection along with side-by-side measurement

comparisons of the ongoing decommissioning activities. The confirmatory survey activities were

conducted in accordance with a site-specific plan, the ORISE/(Independent Environmental

Assessment and Verification) IEAV Survey Procedures Manual and Quality Program Manual

(ORISE 2010a, ORISE 2008 and ORAU 2009).

Survey units are classified based on contamination potential, as either Class 1, 2, or 3 in accordance

with MARSSIM (NRC 2000). A description of each is as follows:


Class 1: Buildings or land areas that have a significant potential for radioactive contamination (based

on site operating history) or known contamination (based on previous radiological surveys) that

exceeds the expected DCGLW value.

Class 2: Buildings or land areas, often contiguous to Class 1 areas that have a potential for

radioactive contamination but at levels less than the expected DCGLW.

Class 3: Remaining impacted buildings and land areas that are not expected to contain residual

contamination, or are expected to contain levels of residual contamination at a small fraction of the

DCGLW.

Confirmatory surveys were conducted in the Class 3 Turbine Building (TBN), Class 3 Steam

Generator Building (SGB), Class 2 West Sodium Gallery (WSG), Class 2 Waste Gas Building

(WGB), and the open land areas within the Fermi 1 footprint. An in-process inspection was

conducted in the Class 2 East Sodium Gallery (ESG). Table 1, provides the list of structures, their

associated survey unit identifications and the scan coverage of accessible surfaces each received

when the survey units were evaluated.

5.1 REFERENCE SYSTEM

Indoor measurements and sampling locations were referenced to prominent site features and

documented on site drawings provided by the licensee. Exterior survey results and sample locations

were referenced to prominent site features and/or Global Positioning System (GPS) coordinates.

The coordinate reference system used for the confirmatory survey was: North American

Datum (NAD) 1983 UTM Zone 17N with units represented in meters.

5.2 SURFACE SCANS

The licensee’s FSS results were considered when determining the level of confirmatory survey effort

required to adequately represent each survey unit. Interior scans covered floors, lower walls, and

accessible upper surfaces while exterior scans focused on soil areas. The surface scan coverage of the

areas selected for confirmatory surveys varied based on the size and accessibility of the areas. The

total area covered was dependent upon the results as the survey progressed. Scans were focused in

areas with the highest potential for contamination (i.e. cracks and joints in the floor and walls, other

horizontal surfaces, surface run-off pathways, etc.).


TABLE 1: CONFIRMATORY STRUCTURAL SURVEY UNITS

STRUCTURE SURVEY UNIT ID SCAN COVERAGE

Surface Alpha + Beta Gamma

Turbine Building TBN01-04 Floor High Density High Density

Lower Walls High Density High Density

Steam Generator Building SGB01-01 Floor High Density High Density

Lower Walls Low Density No Scan

West Sodium Gallery WSG01-01 Floor Medium Density High Density

Lower Walls Medium Density Medium Density

Waste Gas Building WGB01-01 Floor Medium Density High Density

Lower Walls Medium Density Medium Density

East Sodium Gallery ESG01-01 Floor Medium Density High Density

Lower Walls Medium Density High Density

5.2.1 Interior Survey Units

Interior survey unit surfaces, including floors, lower walls, and other accessible surfaces were

scanned using either large-area or hand-held gas proportional detectors for direct alpha and alpha

plus beta radiation and for gamma radiation using a sodium iodide (NaI) detector. All detectors were

coupled to ratemeter-scalers with audible indicators. Additionally, the large-area gas proportional

detector was interfaced with a robotic total station which also enabled position and count rate data

capture for floor surface scans in the nonconfined space survey units. Figures A-3 through A-7

show the interior (floor only) scan coverage.

5.2.2 Exterior Survey Areas

Medium density gamma scans of the Fermi 1 footprint land areas and three building roofs were

performed using NaI scintillation detectors for direct gamma radiation. Detectors were coupled to

ratemeter-scalers with audible indicators. NaI detectors were coupled to a GPS unit that enabled

real-time recording of both position and gamma count rates in one-second intervals. Figures A-8

through A-10 show the exterior gamma scan results for the land areas and roofs.

5.3 SURFACE ACTIVITY MEASUREMENTS

Direct measurements to quantify total alpha and/or alpha plus beta activities on interior survey units

were performed at selected licensee final status survey locations, judgmental locations, and locations

where elevated direct radiation was detected by scans. Those measurements were collected using gas

proportional detectors coupled with ratemeter-scalers. Questions and concerns were brought to the


immediate attention of the NRC representatives, the licensee, and are also noted in the Findings and

Results section of this report. Figures A-11 through A-17 show the surface activity measurements.

5.4 SOIL AND MISCELLANEOUS MATERIAL SAMPLING

One surface soil sample was collected from the exterior land areas. Two samples of miscellaneous

roofing materials, consisting of the tar and gravel build-up, were collected from rooftops of the

TBN’s fourth and seventh floors. Selected sample locations were based on the results of gamma

scans and probable migration/run-off collection pathways. Figure A-18 shows the sampled

locations.

5.5 SURFACE ACTIVITY DATA COMPARISON

ORISE performed side-by-side direct alpha plus beta measurements at six locations together with

DTE FSS personnel to enable direct data comparison. These measurements were performed in

survey unit ESG01-01.

6.0 SAMPLE ANALYSIS AND DATA INTERPRETATION

Samples were returned to the ORISE laboratory in Oak Ridge, Tennessee for analysis and

interpretation. Sample analyses were performed in accordance with the ORISE Laboratory

Procedures Manual (ORISE 2010b). Soil and miscellaneous roofing material samples were analyzed

by solid-state gamma spectroscopy for gamma-emitting ROCs. Analytical results were reported in

units of picocuries per gram (pCi/g). Direct measurement data were converted to units of

disintegrations per minute per 100 square centimeters (dpm/100 cm2). The data generated were

compared with the approved DCGLWs established for the Fermi 1 site.

7.0 APPLICABLE SITE GUIDELINES

The primary ROCs at the Fermi 1 site are beta-gamma emitters—fission and activation products—

resulting from reactor operation. The building surface and soil DCGLW values are listed below. The

DCGLW values were compared with the FSS measurements to determine compliance with the

25 millirem per year (mrem/yr) unrestricted use criterion. The average residual radioactivity above

background must be less than or equal to the DCGLW. Table B-1 provides both the surface activity

and soil concentration DCGLs.


8.2 SURFACE SCANS

Surface scan results for the interior and exterior investigated areas are discussed below.

8.2.1 Interior Survey Units

Surface scans of the selected areas within the TBN01-04, SGB01-01, WGB01-01, WSG01-01 and

ESG01-01 did not identify radiation levels distinguishable from background. Scan surveys in the

basement of the WGB01-01 identified elevated beta and gamma direct radiation from the south wall

near the southwest corner of the room. ORISE performed a detailed survey of the elevated areas

and identified four remaining pipes that had been disconnected and capped with red tape as the

source of residual activity. The elevated beta and gamma radioactivity noted, which were at levels

three times greater than background for that room, was associated with the capped end of the pipes.

The elevated activity was documented on the applicable survey map, was brought to the attention of

the attending NRC and Fermi 1 staff, and discussed in the end of the day meeting on July 14, 2010.

Figures A-3 through A-7 show the floor scan data for several of the confirmatory survey units

accessible with the robotic total station.

8.2.2 Exterior Grounds and Roofs

Exterior open land scans performed with a NaI scintillation detector coupled with a ratemeter-scaler

were at or less than two times background for areas on the south and southwest sides of Fermi 1. As

scans progressed toward the Fermi 2 reactor, located north of Fermi 1, the gamma scan count rates

increased to levels in excess of four times the typical instrument site background. Similar results

were identified for the seventh floor TBN roof survey. It was determined that the gamma radiation

“shine” from the Fermi 2 reactor caused the observed elevated direct gamma radiation. Figure A-8

shows the gamma scan coverage and the gamma radiation count rates for the Fermi 1 open land

areas.

8.3 SURFACE ACTIVITY MEASUREMENTS

Total surface activity levels are provided in Table B-3. The reported surface activities represent gross

levels that have not had background contributions subtracted, per the DTE FSS data reporting

procedure. Table 2 provides a summary of the confirmatory measurement data for each survey unit.


TABLE 2: SURFACE ACTIVITY RANGE SUMMARY

SURVEY UNIT ID Alpha (dpm/100 cm2) Beta (dpm/100 cm2) TBN01-04 9 to 53 790 to 1,500

SGB01-01 18 to 53 1,100 to 1,600

WSG01-01 NAa 570 to 700

WGB01-01 NAa 990 to 1,600

ESG01-01 NAa 1,000 to 1,300 aMeasurements were not collected for corresponding survey unit.

8.4 SURFACE ACTIVITY DATA COMPARISON

The in-process side-by-side measurements ORISE collected in conjunction with DTE’s FSS for the

survey unit ESG01-01 are provided in Table B-2. The instrument/detector combinations used were:

• ORISE—Ludlum Model 2221 ratemeter-scaler coupled to a Ludlum Model 43-68 gas

proportional detector

• DTE—Model 2350-1 data-logger coupled to a Ludlum Model 43-68 detector. DTE also

used an acrylic spacer that provided a 0.803 cm stand-off from the surface being surveyed

The total efficiencies for the instrument and detector combinations were 0.09 for DTE and 0.21 for

ORISE. Prior to receiving the NSEF-10-0027 Fermi 1 Final Status Survey DCGL Selection for

Survey Units document, there was a systematic nonconservative bias between the reported results

where DTE’s results were consistently reported an average of 40 percent below the ORISE result

(DTE 2010). This document illustrates how DTE applied a weighted surface efficiency factor of

0.437 accounting for radionuclide fractions and their respective surface efficiencies. The complete

DTE total weighted efficiency calculation was:

Where 0.2682 = instrument efficiency; 0.803 = correction for instrument stand-off from surface;

0.437 = weighted surface efficiency. With the appropriate efficiencies, these comparative

measurements were re-evaluated. The results are shown in Table B-2. The DTE:ORISE ratio

averaged 1.2, an acceptable and conservative systematic bias.


8.5 RADIONUCLIDE CONCENTRATIONS IN SOIL AND ROOF SAMPLES

Individual sample results for the gamma-emitting fission/activation products that DTE has

identified as site-related contaminants are presented in Table B-4. Sample 2018M0001 had a

cesium-137 concentration of 1.78 pCi/g—above typical background concentrations of less than

1 pCi/g. The sample was collected from a low spot where natural accumulation may have occurred

due to surface run off. Additional investigations are recommended once FSS activities of the exterior

survey units commence. Roof samples did not indicate the presence of any elevated concentrations

of site-related contaminants.

9.0 COMPARISON OF RESULTS WITH GUIDELINES

The total surface activity values were directly compared with the survey unit-specific gross activity

DCGLGA values developed by the licensee. All values were less than the corresponding DCGLGA.

Laboratory analysis of the soil, tar, and gravel were less than 10% of the respective DCGLW values.

10.0 SUMMARY

At the request of the NRC, ORISE conducted confirmatory surveys of the Fermi 1 facility during

the period of July 12 through 15, 2010. The survey activities included visual inspections and

measurement and sampling activities. Confirmatory activities also included the review and

assessment of the licensee’s project documentation and methodologies.

The licensee was forthcoming with information regarding the direct measurement variations

identified during the in-process, side-by-side survey of the ESG. DTE resolved the surface activity

discrepancy between ORISE and DTE. DTE provided to ORISE a revised survey plan and the

NSEF-10-0027 Fermi 1 “Final Status Survey DCGL Selection for Survey Units” document. These

documents revised the radionuclide fractions, and the corresponding efficiency, within the

confirmatory survey units evaluated. The beta surface activity range in Table 2; DTE and ORISE

activities and ratios in Table B-2; and the alpha plus beta activity in Table B-3 reflect the efficiency

modifications. DTE’s total efficiency calculation has also been updated to reflect the weighted

surface efficiency correction.

The FSS data packages that were reviewed accurately and adequately described the sequence of FSS

activities and the radiological conditions at the site. All confirmatory measurement results were

below the respective DCGLGA values for the ROCs as specified in the FSSP. Soil, tar, and gravel


sample activities were below 10% of the DCGLW values. ORISE’s survey data verifies that the

radiological conditions of the confirmatory survey units are below the DCGLGA value requirements

stated in the licensee’s Final Status Survey Plan (DTE 2009). Confirmatory survey activities validated

the licensee’s classifications, radiological status and satisfaction of the guidelines.


11.0 REFERENCES

Detroit Edison Energy (DTE). Enrico Fermi Atomic Power Plant, Unit 1 License Termination Plan, Revision 2. Newport, MI; March 23, 2009.

DTE. NSEF-10-0027 Fermi 1 Final Status Survey DCGL Selection for Survey Units. Newport, MI;

July 29, 2010. Oak Ridge Associated Universities (ORAU). Quality Program Manual for the Independent Environmental

Assessment and Verification Program. Oak Ridge, TN; June 30, 2009. Oak Ridge Institute for Science and Education (ORISE). Survey Procedures Manual for the Independent

Environmental Assessment and Verification Program. Oak Ridge, TN; May 1, 2008. ORISE. Survey Project-Specific Plan for the Decommissioning of the Enrico Fermi Atomic Power Plant, Unit 1.

Oak Ridge, TN; May 28, 2010a. ORISE. Laboratory Procedures Manual for the Independent Environmental Assessment and Verification Program.

Oak Ridge, TN; May 28, 2010b. U.S. Nuclear Regulatory Commission (NRC). Multi-Agency Radiation Survey and Site Investigation Manual

(MARSSIM), NUREG-1575; Revision 1. Washington, DC; August 2000.


APPENDIX A

FIGURES

Enrico Fermi Atomic Power Plant, Unit 1 A-1 2018-SR-01-0

Figure A-1: Location of the Detroit Edison Enrico Fermi Atomic Power Plant, Units 1 and 2


Figure A-2: Enrico Fermi Atomic Power Plant, Unit 1 Plot Plan


Figure A-3: Turbine Building, Fourth Floor—Alpha plus Beta Radiation Floor Scans


Figure A-4: Turbine Building, Fifth Floor—Alpha plus Beta Radiation Floor Scans


Figure A-5: Turbine Building, Sixth Floor—Alpha plus Beta Radiation Floor Scans


Figure A-6: Steam Generator Building, Upper Level—Alpha plus Beta Radiation Floor Scans


Figure A-7: Steam Generator Building, Basement—Alpha plus Beta Radiation Floor Scans


Figure A-8: Fermi 1—External Gamma Radiation Scans of Open Land Areas


Figure A-9: Turbine Building, Fifth Floor Roof—Exterior Gamma Radiation Scans


Figure A-10: Turbine Building, Seventh Floor Roof—Exterior Gamma Radiation Scans


Figure A-11: Turbine Building, Fourth Floor—Alpha plus Beta Direct Measurement Locations


Figure A-12: Turbine Building, Fifth Floor—Alpha plus Beta Direct Measurement Locations


Figure A-13: Turbine Building, Sixth Floor—Alpha plus Beta Direct Measurement Locations


Figure A-14: Steam Generator Building, Upper Level—Alpha

plus Beta Direct Measurement Locations


Figure A-15: East Sodium Gallery—Alpha plus Beta Direct Measurement Locations


Figure A-16: Waste Gas Building—Alpha plus Beta Direct Measurement Locations


Figure A-17: West Sodium Gallery—Alpha plus Beta Direct Measurement Locations


Figure A-18: Fermi 1—Exterior Soil and Turbine Roof Samples


APPENDIX B TABLES

Enrico Fermi Atomic Power Plant, Unit 1 B-1 2018-SR-01-0

TABLE B-1: SURFACE ACTIVITY AND SOIL CONCENTRATION DCGLS

Radionuclide Building Surfacea

(dpm/100cm2) Soila

(pCi/g) Ag-108m 1.8E+04 7.8

Am-241 5.0E+03 130

C-14 1.0E+07 450

Cm-242 3.1E+05 7,700

Cm-243 7.2E+03 78

Co-60 1.1E+04 5.1

Cs-134 1.7E+04 8.3

Cs-137 3.9E+04 17

Eu-152 2.2E+04 11

Eu-154 2.0E+04 11

Eu-155 3.6E+05 400

Fe-55 4.1E+07 34,000

H-3 2.9E+08 31,000

Na-22 1.3E+04 6.2

Nb-94 1.5E+04 7.9

Ni-59 6.0E+05 11,000

Ni-63 3.6E+07 4,000

Pu-238 5.7E+03 160

Pu-239 5.0E+03 140

Pu-240 5.0E+03 140

Pu241 2.7E+05 5,200

Sb-125 5.9E+04 34

Sr-90 1.4E+05 12

Tc-99 1.4E+07 20 aDCGLW values correspond to an annual dose of 25 mrem.


TABLE B-2: ESG01-01 COMPARATIVE DIRECT MEASUREMENT RESULTS

DTE Data ORISE Data DTE:ORISE

Ratio Location cpm dpm/100cm2

εtotal (0.10) cpm

dpm/100cm2

εtotal (0.21)

ESG01-01-21 174 1,600 273 1,000 1.6

ESG01-01-22 134 1,300 304 1,100 1.2

ESG01-01-23 162 1,500 331 1,300 1.2

ESG01-01-24 147 1,400 334 1,300 1.1

ESG01-01-25 119 1,200 292 1,100 1.1

ESG01-01-26 141 1,300 296 1,100 1.2


TABLE B-3: FERMI 1 RADIONUCLIDE SURFACE ACTIVITY LEVELS

Building/Area Measurement ID Surface Alpha plus Beta

Gross Activity (dpm/100cm2)

Turbine Building TBNa / 4th Floor TBN01-04-01 Concrete Floor 1,400

TBNa / 4th Floor TBN01-04-02 Concrete Floor 1,200

TBNa / 4th Floor TBN01-04-03 Metal I-beam 790

TBNa / 4th Floor TBN01-04-04 Metal 910



TBNa / 5th Floor TBN01-04-07 Corrugated Transite 1,400

TBNa / 5th Floor TBN01-04-08 Metal Ledge 1,200




TBNa / 6th Floor TBN01-04-12 Corrugated Transite 1,500

Steam Generator Building SGBa / 1st Floor SGB01-01-01 Cinder Block 1,600

SGBa / 1st Floor SGB01-01-02 Concrete Floor 1,100



West Sodium Gallery WSGa WSG01-01-01 Concrete Floor 700

WSGa WSG01-01-02 Concrete Wall 600

WSGa WSG01-01-03 Concrete Floor 570

Waste Gas Building WGBb / Valve Room WGB01-01-01 Concrete Wall 1,300

WGBb / Valve Room WGB01-01-02 Concrete Floor 1,300

WGBb / Valve Room WGB01-01-03 Concrete Wall 1,200

WGBb / Basement WGB01-01-04 Concrete Floor 990

WGBb / Basement WGB01-01-05 Concrete Wall 1,000

WGBb / Basement WGB01-01-06 Concrete Wall 1,000

WGBb / Tank Room 2 WGB01-01-07 Concrete Wall 990

WGBb / Tank Room 2 WGB01-01-08 Concrete Floor 1,300

WGBb / Tank Room 2 WGB01-01-09 Concrete Wall 1,300

WGBb / Tank Room 1 WGB01-01-10 Concrete Floor 1,100




TABLE B-3: FERMI 1 RADIONUCLIDE SURFACE ACTIVITY LEVELS

Building/Area Measurement ID Surface Alpha plus Beta

Gross Activity (dpm/100cm2)

East Sodium Gallery ESGc ESG01-01-21 Concrete Floor 1,000

ESGc ESG01-01-22 Concrete Floor 1,100




ESGc ESG01-01-26 Concrete Ceiling 1,100 aDTE FSS documents did not provide sufficient data for ORISE to calculate a total weighted efficiency for the Turbine Building,

Steam Generator Building, or West Sodium Gallery.

bThe total weighted efficiency for the Waste Gas building was calculated based on the concentrations DTE provided for cesium-137, cobalt-60 and strontium-90.

cThe total efficiency for the measurements collected in the East Sodium Gallery was based on cobalt-60.


TABLE B-4:

FERMI 1 RADIONUCLIDE CONCENTRATIONS FOR ACTIVATION AND FISSION PRODUCTS IN SOIL AND BUILDING MEDIA (pCi/g)

ORISE Sample IDa Eu-155 Eu-152 Eu-154 Cs-137 Co-60 Am-241 U-235 Th-234

2018M0001 0.05 ± 0.10b 0.01 ± 0.12 -0.3 ± 0.18 1.78 ± 0.14 0.03 ± 0.04 0.15 ± 0.09 0.38 ± 0.04 2.78 ± 0.47

2018M0002 -0.02 ± 0.10 -0.21 ± 0.13 0.09 ± 0.17 0.08 ± 0.04 0.00 ± 0.04 0.00 ± 0.06 0.17 ± 0.04 0.57 ± 0.39

2018S0001 0.01 ± 0.04 -0.08 ± 0.05 -0.02 ± 0.08 0.11 ± 0.02 0.02 ± 0.03 -0.01 ± 0.04 0.13 ± 0.01 1.38 ± 0.21 aSee Figure A-18 bUncertainties represent the 95% confidence interval based on total propagated uncertainties.


APPENDIX C

MAJOR INSTRUMENTATION

Enrico Fermi Atomic Power Plant, Unit 1 C-1 2018-SR-01-0

The display of a specific product is not to be construed as an endorsement of the product or its manufacturer by the author or his employer.

C.1 SCANNING AND MEASUREMENT INSTRUMENT/DETECTOR COMBINATIONS

C.1.1 Gamma

Ludlum NaI Scintillation Detector Model 44-10, Crystal: 5.1 cm x 5.1 cm (Ludlum Measurements, Inc., Sweetwater, TX) coupled to: Ludlum Ratemeter-scaler Model 2221 (Ludlum Measurements, Inc., Sweetwater, TX) coupled to: Trimble GeoXH Receiver and Data Logger (Trimble Navigation Limited, Sunnyvale, CA)

C.1.2 Alpha and Alpha Plus Beta

Ludlum Gas Proportional Detector Model 43-68, 126cm2 physical area coupled to: Ludlum Ratemeter-scaler Model 2221 (Ludlum Measurements, Inc., Sweetwater, TX) Ludlum Gas Proportional Detector Model 43-37, 582cm2 physical area coupled to: Ludlum Ratemeter-scaler Model 2221 (Ludlum Measurements, Inc., Sweetwater, TX) coupled to: Trimble S3 Total Station with TSC2 controller (Trimble Navigation Limited, Sunnyvale, CA)

C.2 LABORATORY ANALYTICAL INSTRUMENTATION

High Purity Extended Range Intrinsic Detector CANBERRA/Tennelec Model No: ERVDS30-25195 (Canberra, Meriden, CT) Used in conjunction with: Lead Shield Model G-11 (Nuclear Lead, Oak Ridge, TN) and Multichannel Analyzer Canberra’s Apex Gamma Software Dell Workstation (Canberra, Meriden, CT)

Enrico Fermi Atomic Power Plant, Unit 1 C-2 2018-SR-01-0

LABORATORY ANALYTICAL INSTRUMENTATION (CONTINUED)

High Purity Extended Range Intrinsic Detector Model No. GMX-45200-5 (AMETEK/ORTEC, Oak Ridge, TN) used in conjunction with: Lead Shield Model SPG-16-K8 (Nuclear Data) Multichannel Analyzer Canberra’s Apex Gamma Software Dell Workstation (Canberra, Meriden, CT)

High-Purity Germanium Detector Model GMX-30-P4, 30% Eff. (AMETEK/ORTEC, Oak Ridge, TN) Used in conjunction with: Lead Shield Model G-16 (Gamma Products, Palos Hills, IL) and Multichannel Analyzer Canberra’s Apex Gamma Software Dell Workstation (Canberra, Meriden, CT)


APPENDIX D SURVEY AND ANALYTICAL PROCEDURES

Enrico Fermi Atomic Power Plant, Unit 1 D-1 2018-SR-01-0

D.1 PROJECT HEALTH AND SAFETY

The proposed survey and sampling procedures were evaluated to ensure that any hazards inherent to

the procedures themselves were addressed in current job hazard analyses. Additionally, upon arrival

on site, a walk-down of the site was performed to identify hazards present and a pre-job integrated

safety management checklist was completed and discussed with field personnel. All survey and

laboratory activities were conducted in accordance with ORISE health and safety and radiation

protection procedures.

D.2 CALIBRATION AND QUALITY ASSURANCE

Calibration of all field and laboratory instrumentation was based on standards/sources, traceable to

National Institute of Standards and Technology (NIST).

Analytical and field survey activities were conducted in accordance with procedures from the

following documents of the Independent Environmental Assessment and Verification Program:

• Survey Procedures Manual (ORISE 2008)

• Laboratory Procedures Manual (ORISE 2010b)

• Quality Program Manual (ORAU 2009)

The procedures contained in these manuals were developed to meet the requirements of

Department of Energy (DOE) Order 414.1C and the U.S. Nuclear Regulatory Commission Quality

Assurance Manual for the Office of Nuclear Material Safety and Safeguards and contain measures to assess

processes during their performance.

Quality control procedures include:

• Daily instrument background and check-source measurements to confirm that equipment

operation is within acceptable statistical fluctuations.

• Participation in Mixed Analyte Performance Evaluation Program (MAPEP), NIST

Radiochemistry Intercomparison Program (NRIP), and Intercomparison Testing Program

(ITP) Laboratory Quality Assurance Programs.


• Training and certification of all individuals performing procedures.

• Periodic internal and external audits.

D.3 SURVEY PROCEDURES

D.3.1 Surface Scans

A sodium iodide (NaI) scintillation detector was used to scan for elevated gamma radiation.

Identification of elevated radiation levels was based on increases in the audible signal from the

recording and/or indicating instrument. Additionally, the detectors were coupled to global

positioning system (GPS) units with data loggers enabling real-time recording in one- or two-second

intervals of both geographic position and the gamma count rate. Position and gamma count rate

data files were transferred to a computer system, positions differentially corrected, and the results

plotted on geo-referenced aerial photographs. Positional accuracy was within 0.5 meters at the 95th

percentile.

The scan minimum detectable concentration for the NaI scintillation detectors was approximately

3.4 pCi/g for cobalt-60 and 6.4 pCi/g for cesium-137, as provided in NUREG-1507.

D.3.2 Surface Activity Measurements

Measurements of total activity levels were performed using gas proportional detectors with portable

ratemeter-scalers. Surface activity measurements were performed on floors, lower walls and at

locations of elevated direct radiation.

Count rates (cpm), which were integrated over one minute with the detector held in a static position,

were converted to activity levels (dpm/100cm2) by dividing the count rate (in counts per minute) by

the physical detector area of 126 cm2, and by the total efficiency (εi ×εs). Individual building material

background measurements were not subtracted for the confirmatory surveys performed at the

Fermi 1 site in order to match the DTE Final Status Survey procedure. Therefore, confirmatory

measurement data represent gross activity levels for the remaining structures and surfaces.

The 2π instrument efficiencies (εi) were as follows: 0.38 for the gas proportional detectors calibrated

to thorium-230; 0.37 for carbon-14; 0.46 for technetium-99; 0.59 for thalium-204 and 0.56 for

strontium-90. The source efficiency factor (εs) was 0.25 for alpha measurements. Both 0.25 and 0.50


were used for the beta measurements, dependent upon the beta energy level of the contaminant(s)

within specific survey units. The total beta efficiency in survey unit ESG01-01 was 0.11 based on the

Tc-99 εi of 0.46 and εs of 0.25 representing the beta energy distribution of Co-60. Survey units

TBN01-04, SGB01-01, WSG01-01 and WGB01-01 have a DCGLGA for radionuclides including

cesium-137 and cobalt-60.

The total efficiency for direct measurements varied based on the applicable ROCs per survey unit.

Sufficient data were not provided to calculate a total weighted efficiency for the TBN01-04,

SGB01-01 and WSG01-01 survey units. The total efficiency for technetium-99 was used to calculate

the gross activity in these survey units. The total weighted efficiency for the WGB01-01 survey unit

was calculated using the concentrations for the ROCs provided in the DTE survey packages. That

efficiency was calculated using the following formula:

The total efficiency for technetium-99 was used to calculate the gross activity of cobalt-60 in the

ESG01-01 survey unit.

D.3.3 Soil Sampling

Approximately 0.5 to 1 kilogram (kg) of soil/tar and gravel was collected at each sample location.

Collected samples were placed in a plastic bag, sealed, and labeled in accordance with ORISE survey

procedures.

D.4 RADIOLOGICAL ANALYSIS

D.4.1 Gamma Spectroscopy

Samples were dried, mixed, crushed, and/or homogenized as necessary, and a portion sealed in a

0.5-liter Marinelli beaker or other appropriate container. The quantity placed in the beaker was

chosen to reproduce the calibrated counting geometry. Net material weights were determined and

the samples counted using intrinsic germanium detectors coupled to a pulse height analyzer system.

Background and Compton stripping, peak search, peak identification, and concentration calculations

were performed using the computer capabilities inherent in the analyzer system. All Total

Documents

B. Watson Ltr. Re: Report No. 1: Independent Confirmatory ...Energy Commission (AEC) granted an operating license, DPR-9, to the Power Reactor Development Company (PRDC), a consortium