Text

Enrico Fermi Atomic Power Plant, Unit 1 - License Termination Plan, Revision 4
	ML111820620
Person / Time
Site:	Fermi
Issue date:	06/29/2011
From:	Plona J; DTE Energy
To:	; Document Control Desk, NRC/FSME
References
	NRC-11-0036
	Download: ML111820620 (59)
	v • d • e

Joseph H. Plona Site Vice President 6400 N. Dixie Highway, Newport, MI 48166 Tel: 734.586.5910 Fax: 734,586.4172 DTE Energy' 10 CFR 50.90 10 CFR 50.82(a)(9) 10CFR50.71(e)

June 29, 2011 NRC-11-0036 U.S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, D.C. 20555

References:

1) Enrico Fermi Atomic Power Plant, Unit No. 1 NRC Docket No. 50-16 NRC License No. DPR-9

2) Detroit Edison Letter to NRC, "Proposed License Amendment License Termination Plan", NRC-09-0017, dated 03/25/2009

3) NUREG-1507, "Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions", 1998

Subject:

Enrico Fermi Atomic Power Plant, Unit 1 License Termination Plan, Revision 4 Please find attached the revisions to the Fermi 1 License Termination Plan. Attached is the copy of the changed pages 1-7, 1-8, 2-1 through 2-6, 2-19 through 2-28, 2-31, 2-32, 2-35 through 2-64, 5-39, 5-40, 5-47 and 5-48 for Revision 4 to the Enrico Fermi Atomic Power Plant, Unit No. 1 License Termination Plan (LTP), which was submitted to the NRC for review in Reference 2. Revisions 1, 2, and 3 to the LTP have been previously submitted to the NRC under separate transmittals. The LTP revision incorporates the deletion of maintaining worker Total Effective Dose Equivalent (TEDE) to less than 1 Rem/year in Chapter 1, changes to the License Termination Characterization data, hydrogeological discussion, and background due to fallout in Chapter 2, updated Table of Contents for Chapter 2, and correction to Table 5-11 and Section 5.4.2.5.1.

June 29, 2011 NRC-11-0036 Joseph H. Plona Site Vice President 6400 N. Dixie Highway, Newport, MI 48166 Tel: 734.586.5910 Fax: 734.586.4172 DTE Energy' 10 CFR 50.90 10 CFR 50.82(a)(9) 10CFR50.71(e) u.s. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, D.C. 20555

References:

1) Enrico Fermi Atomic Power Plant, Unit No.1

Subject:

NRC Docket No. 50-16 NRC License No. DPR-9

2) Detroit Edison Letter to NRC, "Proposed License Amendment License Termination Plan", NRC-09-0017, dated 03/25/2009

3) NUREG-1507, "Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions", 1998 Enrico Fermi Atomic Power Plant, Unit 1 License Termination Plan, Revision 4 Please find attached the revisions to the Fermi 1 License Termination Plan. Attached is the copy of the changed pages 1-7, 1-8,2-1 through 2-6,2-19 through 2-28,2-31,2-32, 2-35 through 2-64, 5-39, 5-40, 5-47 and 5-48 for Revision 4 to the Enrico Fermi Atomic Power Plant, Unit No.1 License Termination Plan (LTP), which was submitted to the NRC for review in Reference 2. Revisions 1, 2, and 3 to the LTP have been previously submitted to the NRC under separate transmittals. The L TP revision incorporates the deletion of maintaining worker Total Effective Dose Equivalent (TEDE) to less than 1 Rem/year in Chapter 1, changes to the License Termination Characterization data, hydrogeological discussion, and background due to fallout in Chapter 2, updated Table of Contents for Chapter 2, and correction to Table 5-11 and Section 5.4.2.5.1.

USNRC NRC-11-0036 Page 2 The Chapter 1 revision change removing the 1 Rem/year TEDE criteria does not affect the commitment to maintain worker TEDE "As Low As Reasonably Achievable" (ALARA). The level of specificity of 1 Rem/year does not allow for special circumstances where dose extensions are necessary to complete decommissioning work; therefore the statement pertaining to worker TEDE of less than 1 Rem/year and the reference to Fermi 2 MRP03, "Personnel Radiation Monitoring" procedure will be deleted.

The revision to Chapter 2 of the LTP incorporates changes to the License Termination Characterization data to incorporate updated instrument efficiencies calculated since the initial characterization was performed using the methodology in NUREG-1507 (Reference 3) for calculating surface beta activity. The revision addresses the efficiency calculation converting counts per minute (cpm) to disintegrations per minute (dpm).

Characterization data was reported by Final Status Survey instrumentation in counts per minute and remains unchanged.

Section 2.2, "Hydrogeological Investigations" is revised to incorporate the updated Site Conceptual Groundwater Model and additional information being separately submitted to the NRC.

Section 2.3.4, "Ambient and Background" is being revised to add information from the National Council on Radiation Protection & Measurements (NCRP) report on Cs-137 deposition from fallout and expected deposition in this region of the country.

References to the NCRP report and the updated Site Conceptual Model are being added to Section 2.6 of the LTP.

A typographical error was corrected on page 2-28 and the Table of Contents in Section 2 was revised to reflect corrected page numbers.

A revision to Chapter 5 corrects Table 5-11 source-to-detector distance from inches to centimeters in accordance with NUREG-1507 Table 4.5, "Source-to-Detector Distance Effects for P Emitters" and Table 4.6, "Source-to-Detector Distance Effects for a Emitters". Although the proposed revision reflects distances measured in centimeters, the correct stand-off distances were used in calculating efficiencies for Characterization and Final Status Survey data. The revision to Chapter 5, Section 5.4.2.5.1 changes the detector-to-ground distance for SPA-3 open land scans from within 2.5 to 5 centimeters to -6 cm or 2.5 in. to more accurately reflect the specifications in MARSSIM, Section 6.4.2.1.

USNRC NRC-11-0036 Page 2 The Chapter 1 revision change removing the 1 Rem/year TEDE criteria does not affect the commitment to maintain worker TEDE "As Low As Reasonably Achievable" (ALARA). The level of specificity of 1 Rem/year does not allow for special circumstances where dose extensions are necessary to complete decommissioning work; therefore the statement pertaining to worker TEDE of less than 1 Rem/year and the reference to Fermi 2 MRP03, "Personnel Radiation Monitoring" procedure will be deleted.

The revision to Chapter 2 of the LTP incorporates changes to the License Termination Characterization data to incorporate updated instrument efficiencies calculated since the initial characterization was performed using the methodology in NUREG-1507 (Reference 3) for calculating surface beta activity. The revision addresses the efficiency calculation converting counts per minute (cpm) to disintegrations per minute (dpm).

Characterization data was reported by Final Status Survey instrumentation in counts per minute and remains unchanged.

Section 2.2, "Hydrogeological Investigations" is revised to incorporate the updated Site Conceptual Groundwater Model and additional information being separately submitted to the NRC.

Section 2.3 A, "Ambient and Background" is being revised to add information from the National Council on Radiation Protection & Measurements (NCRP) report on Cs-137 deposition from fallout and expected deposition in this region of the country.

References to the NCRP report and the updated Site Conceptual Model are being added to Section 2.6 of the LTP.

A typographical error was corrected on page 2-28 and the Table of Contents in Section 2 was revised to reflect corrected page numbers.

A revision to Chapter 5 corrects Table 5-11 source-to-detector distance from inches to centimeters in accordance with NUREG-1507 Table 4.5, "Source-to-Detector Distance Effects for ~ Emitters" and Table 4.6, "Source-to-Detector Distance Effects for a Emitters". Although the proposed revision reflects distances measured in centimeters, the correct stand-off distances were used in calculating efficiencies for Characterization and Final Status Survey data. The revision to Chapter 5, Section 504.2.5.1 changes the detector-to-ground distance for SPA-3 open land scans from within 2.5 to 5 centimeters to ~6 cm or 2.5 in. to more accurately reflect the specifications in MARSSIM, Section 604.2.1.

USNRC NRC-11-0036 Page 3 Should you have any questions or require additional information, please contact Lynne Goodman, at (734) 586-1205.

Sincerely, Joseph H. Plona Site Vice President, Nuclear Generation JHP/NT/can Attachments (2) cc:

NRC Regional Administrator, Region III T. Smith, NRC (Washington, D.C.)

NRC Resident Inspector-Fermi 2 P. Lee, NRC Region III Michigan Department of Natural Resources & Environment (yalek@michigan.gov)

USNRC NRC-11-0036 Page 3 Should you have any questions or require additional information, please contact Lynne Goodman, at (734) 586-1205.

Sincerely, Joseph H. Plona Site Vice President, Nuclear Generation JHPINT/can Attachments (2) cc:

NRC Regional Administrator, Region III T. Smith, NRC (Washington, D.C.)

NRC Resident Inspector-Fermi 2 P. Lee, NRC Region III Michigan Department of Natural Resources & Environment (yalek@michigan.gov)

USNRC NRC-11-0036 Page 4 I, Joseph H. Plona., do hereby affirm that the foregoing statements are based on facts and circumstances which are true and accurate to the best of my knowledge and belief.

Joseph H. Plona Site Vice President, Nuclear Generation On this 6

day of U,0 7

,2011 before me personally appeared Joseph H. Plona, being first duly sworn and says that he executed the foregoing as his free act and deed.

Notary Pubic STAOY OAKE8

-'OTARY PUL=UC, STATE OF M OOUn' OF kM-RO AY COMMI88ON EXPES Jul~2 2012

CT-G 1

!COUMYOF LWMW ZOC USNRC NRC-II-0036 Page 4 I, Joseph H. Plona., do hereby affirm that the foregoing statements are based on facts and circumstances which are true and accurate to the best of my knowledge and belief.

Joseph H. Plona Site Vice President, Nuclear Generation On this Jq th.

day of J tJ V\\.t.--

, 2011 before me personally appeared Joseph H. Plona, being first duly sworn and says that he executed the foregoing as his free act and deed.

STMJY OAKES i,OTARY Pl!8UC, STATE OF I\\t.~

OOUWTY or W'.ooROE MY COMMISOON EXPIflES Jul 26, 2012

'CnNB ~\\j OOUNW OF MD JjI2.0 ~

USNRC NRC-11-0036 Page 1 Enrico Fermi Atomic Power Plant, Unit No.1 LTP Revision 4 Replacement Pages The listing below provides the replacement pages for Revision 4 of the LTP. The listing below only identifies the LTP pages that result in changes to pages from Revision 0 of the March 2009 LTP. The replacement pages are based on double-sided pages.

Chapter 1: Remove Revision 0, page 1-7 and page 1-8, and replace with page 1-7, revision 0 and page 1-8, revision 4.

Chapter 2:

Remove Revision 0, pages 2-1 through 2-6, and replace with page 2-1 through 2-5, revision 4 and page 2-6, revision 0.

Remove Revision 0, pages 2-19 through 2-28, and replace with page 2-19, revision 0, 2-20 through 2-24 revision 4, page 2-25 revision 0, pages 2-26 through 2-28 revision 4.

Remove Revision 0 pages 2-31 and 2-32, and replace with pages 2-31 and 2-32 revision 4.

Remove Revision 0 pages 2-35 through 2-64 and replace with pages 2-35 through 2-37 revision 4, page 2-38 revision 0, pages 2-39 through 2-41 revision 4, page 2-42 revision 0, page 2-43 revision 4, page 2-44 revision 0, pages 2-45 through 2-48 revision 4, page 2-49 revision 0, and pages 2-50 through 2-64 revision 4.

Chapter 3: None Chapter 4: None Chapter 5: Remove Revision 0, pages 5-39, 5-40, 5-47 and 5-48, and replace with pages 5-40 and 5-47 revision 0 and pages 5-39 and 5-48 revision 4.

Chapter 6: None Chapter 7: None Chapter 8: None Glossary of Terms: None USNRC NRC-II-0036 Page 1 Enrico Fermi Atomic Power Plant, Unit No.1 LTP Revision 4 Replacement Pages The listing below provides the replacement pages for Revision 4 of the LTP. The listing below only identifies the L TP pages that result in changes to pages from Revision ° of the March 2009 L TP. The replacement pages are based on double-sided pages.

Chapter 1: Remove Revision 0, page 1-7 and page 1-8, and replace with page 1-7, revision ° and page 1-8, revision 4.

Chapter 2:

Remove Revision 0, pages 2-1 through 2-6, and replace with page 2-1 through 2-5, revision 4 and page 2-6, revision 0.

Remove Revision 0, pages 2-19 through 2-28, and replace with page 2-19, revision 0,2-20 through 2-24 revision 4, page 2-25 revision 0, pages 2-26 through 2-28 revision 4.

Remove Revision ° pages 2-31 and 2-32, and replace with pages 2-31 and 2-32 revision 4.

Remove Revision ° pages 2-35 through 2-64 and replace with pages 2-35 through 2-37 revision 4, page 2-38 revision 0, pages 2-39 through 2-41 revision 4, page 2-42 revision 0, page 2-43 revision 4, page 2-44 revision 0, pages 2-45 through 2-48 revision 4, page 2-49 revision 0, and pages 2-50 through 2-64 revision 4.

Chapter 3: None Chapter 4: None Chapter 5: Remove Revision 0, pages 5-39, 5-40, 5-47 and 5-48, and replace with pages 5-40 and 5-47 revision ° and pages 5-39 and 5-48 revision 4.

Chapter 6: None Chapter 7: None Chapter 8: None Glossary of Terms: None

Fermi 1 License Termination Plan Revision 0 Chapter 1 General Information March 2009 Pointe Mouillee State Game Area is a 4,000 acre spit of land approximately 4 miles northeast of the Fermi 1 site at the northwest comer of Lake Erie, which jets into Lake Erie near the Huron River. It is owned by the Michigan Department of Natural Resources. Pointe Mouillee is one of the largest fresh water marsh restoration projects in the world, consisting of wetlands, diked marshes and river bayous. Most of Pointe Mouillee is open to public hunting.

Wm. C. Sterling State Park, the only Michigan state park on Lake Erie, consists of 1,300 acres of state-owned lands with recreational swimming, fishing, camping, hiking and wildlife viewing. Sterling State Park is approximately 5.2 miles southwest of the Fermi 1 site on Brest Bay. The bay sits just north of where the Raisin River spills into Lake Erie. The park is situated in Monroe County just south of Detroit Beach/Sandy Creek and north of the city of Monroe.

Bodies of Water: The Fermi 1 site sits on the western shore of Lake Erie. Lake Erie consists of 9,910 square miles of water surface area, 871 miles of shoreline.

Lake Erie provides sport fishing, recreational boating, swimming, water skiing and scuba diving for the local and surrounding population. Lake Erie empties into the Niagara River and the Welland Canal.

Farms: Monroe County has an area of about 550 square miles of which approximately 70% is farmland. The majority of crops grown on the farms in the area are corn, winter wheat and soybeans.

Water Supplies: Currently potable water is supplied to the Fermi 1 complex from the Frenchtown public water supply. Chapter 8 of the LTP discusses water use and potential impact of decommissioning on water quality. Wells in the vicinity of EF1 are depicted in Figure 1-3.

Population: Monroe County, in which Fermi 1 is located, extends about 10 miles north, 25 miles west, and 20 miles south-west of the site and has a population of about 146,000. The only substantially populated communities within a 10 mile radius are Newport, which lies within Berlin Township, located approximately 3.5 miles away with a population of about 11,000 and Monroe (consisting of Frenchtown Township, the City of Monroe and Monroe Township) located approximately 8 miles away with a population of about 54,800. The closest residence to EF1 is located approximately 0.71 mile in a straight line.

1-7 Fermi 1 License Termination Plan Chapter 1 General Information Revision 0 March 2009 Pointe Mouillee State Game Area is a 4,000 acre spit of land approximately 4 miles northeast of the Fermi 1 site at the northwest comer of Lake Erie, whichjets into Lake Erie near the Huron River. It is owned by the Michigan Department of Natural Resources. Pointe Mouillee is one of the largest fresh water marsh restoration projects in the world, consisting ofwetlarids, diked marshes and river bayous. Most of Pointe Mauillee is open to public hunting.

Wm. C. Sterling State Park, the only Michigan state park on Lake Erie, consists of 1,300 acres of state-owned lands with recreational swimming, fishing, camping, hiking and wildlife viewing. Sterling State Park is approximately 5.2 miles southwest of the Fermi 1 site on Brest Bay. The bay sits just north of where the Raisin River spills into Lake Erie. The park is situated in Monroe County just south of Detroit Beach/Sandy Creek and north of the city of Monroe.

Bodies of Water: The Fermi 1 site sits on the western shore of Lake Erie. Lake Erie consists of 9,910 square miles of water surface area, 871 miles of shoreline.

Lake Erie provides sport fishing, recreational boating, swimming, water skiing and scuba diving for the local and surrounding population. Lake Erie empties into the Niagara River and the Well and Canal.

Farms: Monroe County has an area of about 550 square miles of which approximately 70% is farmland. The majority of crops grown on the farms in the area are com, winter wheat and soybeans.

Water Supplies: Currently potable water is supplied to the Fermi 1 complex from the Frenchtown public water supply. Chapter 8 of the LTP discusses water use and potential impact of decommissioning on water quality. Wells in the vicinity ofEFl are depicted in Figure 1-3.

Population: Monroe County, in which Fermi 1 is located, extends about 10 miles north, 25 miles west, and 20 miles south-west of the site and has a population of about 146,000. The only substantially populated communities within a 10 mile radius are Newport, which lies within Berlin Township, located approximately 3.5 miles away with a population of about 11,000 and Monroe (consisting of Frenchtown Township, the City of Monroe and Monroe Township) located approximately 8 miles away with a population of about 54,800. The closest residence to EFI is located approximately 0.71 mile in a straight line.

1-7

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 1.4 Decommissioning Approach 1.4.1 Overview The objective of decommissioning EF1 is to reduce the level of residual radioactivity to levels that permit unrestricted use of the site and allow for the termination of the 10 CFR Part 50 license. The EF1 license will be terminated with the buildings remaining. Decommissioning involves the systematic removal of Systems, Structures and Components that comprise the radioactive portions of the site. DTE conducts decommissioning activities in accordance with the EF1 10 CFR Part 50 license, approved work requests, and approved procedures.

Contaminated material may be released as non-contaminated material after decontamination, shipped to a licensed offsite processor for disposition, or shipped to an offsite low-level waste (LLW) disposal site (i.e., Clive Utah site).

Qualified workers package LLW for transport and disposal in accordance with applicable NRC and Department of Transportation (DOT) regulatory requirements. EF1 continues to implement its Radiological Controls Program.

The objectives of the Radiological Controls Program are to control radiation hazards, avoid accidental radiation exposures and maintain doses to workers and the public As Low As Reasonably Achievable (ALARA). The philosophies, policies, and objectives of the Radiological Controls Program are based on federal regulations and associated regulatory guidance. EF1's ALARA policy maintains management's commitment to control exposures to workers and the public ALARA. This commitment is contained in the F1 SAR and is implemented by plant administrative procedures and Radiation Protection Department implementing procedures.

The integrated approach to decommissioning includes support from DTE employees and outside contractors, as required, to complete the project. The Decommissioning organization provides project management and has developed administrative work controls to implement decommissioning activities. The use of trained individuals, adherence to approved procedures and established institutional controls, will ensure that the risk to the public is minimal and risk to worker health and safety is minimized. Risks associated with the transportation of LLW are also minimal.

The environmental assessment, discussed in Chapter 8 of this LTP, determined that the environmental effects from decommissioning of EF1 are minimal, and there are no adverse effects outside the bounds ofNUREG-0586 "Final Generic 1-8 Fermi 1 License Termination Plan Chapter 2 Site Characterization 1.4 Decommissioning Approach 1.4.1 Overview Revision 4 June 2011 The objective of decommissioning EF1 is to reduce the level of residual radioactivity to levels that permit unrestricted use ofthe site and allow for the termination of the 10CFR Part 50 license. The EF1license will be terminated with the buildings remaining. Decommissioning invqlves the systematic removal of Systems, Structures and Components that comprise the radioactive portions of the site. DTE conducts decommissioning activities in accordance with the EF1 10 CFR Part 50 license, approved work requests, and approved procedures.

Contaminated material may be released as non-contaminated material after decontamination, shipped to a licensed offsite processor for disposition, or shipped to an offsite low-level waste (LLW) disposal site (i.e., Clive Utah site).

Qualified workers package LL W for transport and disposal in accordance with applicable NRC and Department of Transportation (DOT) regulatory requirements. EF1 continues to implement its Radiological Controls Program.

The objectives of the Radiological Controls Program are to control radiation hazards, avoid accidental radiation exposures and maintain doses to workers and the public As Low As Reasonably Achievable (ALARA). The philosophies, policies, and objectives of the Radiological Controls Program are based on federal regulations and associated regulatory guidance. EF1 's ALARA policy maintains management's commitment to control exposures to workers and the public ALARA. This commitment is contained in the F1SAR and is implemented by plant administrative procedures and Radiation Protection Department implementing procedures.

The integrated approach to decommissioning includes supp~rt from DTE employees and outside contractors, as required, to complete the project. The Decommissioning organization provides project management and has developed administrative work controls to implement decommissioning activities. The use of trained individuals, adherence to approved procedures and established institutional controls, will ensure that the risk to the public is minimal and risk to worker health and safety is minimized. Risks associated with the transportation of LL W are also minimal.

The environmental assessment, discussed in Chapter 8 of this L TP, determined that the environmental effects from decommissioning ofEFl are minimal, and there are no adverse effects outside the bounds ofNUREG-0586 "Final Generic 1-8

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 2.0 SITE CHARACTERIZATION.................................................................................

2-6 2.1 Historical Site Assessment Summary.............................................................................. 2-6 2.1.1 Introduction.....................................................................................................2.6 2.1.2 Objectives of Historical Site Assessment........................................................ 2-8 2.1.3 Property Identification....................................................................................

2-8 2.1.4 HSA Methodology............................................................................................... 2-8 2.1.4.1 Approach and Rationale....................................................................... 2-8 2.1.4.2 Documents Reviewed......................................................................... 2-9 2.1.4.3 Site Reconnaissance............................................................................ 2-9 2.1.4.4 Personnel Interviews........................................................................... 2-9 2.1.4.5 Historical Construction Photograph Reviews..................................... 2-11 2.1.5 Operational History............................................................................................ 2-11 2.1.5.1 Introduction....................................................................................... 2-11 2.1.5.2 Regulatory Overview........................................................................ 2-12 2.1.5.3 Waste Handling Procedures.............................................................. 2-13 2.1.5.4 Current Site Usage.............................................................................. 2-13 2.1.5.5 Site Dismantlement........................................................................... 2-13 2.1.5.6 Radiological Sources..................................................................... 2-14 2.1.6 E ven D escriptions.............................................................................................. 2-15 2.1.7 Survey Unit Identification and Classification.................................................... 2-15 2.1.7.1 Survey Areas.................................................................................... 2-15 2.1.7.2 Survey Units..................................................................................

2-15 2.1.7.3 Initial Designation of Areas............................................................. 2-16 2.1.8 Area Radiological Impact Summaries..................................

....................... 2-16 2.1.8.1 OOL Open Land Area Ou6tside the Controlled Area........... 2-16 2-1 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 4 June 2011 2.0 SITE CHARACTERIZATION.................................................................................... 2-6 2.1 Historical Site Assessment Summary.............................................................................. 2-6 2.1.1 Introduction........................................................................................................... 2.6 2.1.2 Objectives of Historical Site Assessment............................................................ 2-8 2.1.3 Property Identification......................................................................................... 2-8 2.1.4 HSA Methodology........ :...................................................................................... 2-8 2.1.4.1 Approach and Rationale........................................................................ 2-8 2.1.4.2 Documents Reviewed........................................................................... 2-9 2.1.4.3 Site Reconnaissance.............................................................................. 2-9 2.1.4.4 Personnel Interviews............................................................................. 2-9 2.1.4.5 Historical Construction Photograph Reviews..................................... 2-11 2.1.5 Operational History............................................................................................ 2-11 2.1.5.1 Introduction......................................................................................... 2-11 2.1.5.2 Regulatory Overview.......................................................................... 2-12 2.1.5.3 Waste Handling Procedures................................................................ 2-13 2.1.5.4 Current Site Usage.............................................................................. 2-13 2.1.5.5 Site Dismantlement............................................................................. 2-13 2.1.5.6 Radiological Sources.......................................................................... 2-14 2.1.6 Even Descriptions.............................................................................................. 2-15 2.1.7 Survey Unit Identification and Classification.................................................... 2-15 2.1.7.1 Survey Areas....................................................................................... 2-15 2.1.7.2 Survey Units........................................................................................ 2-15 2.1. 7.3 Initial Designation of Areas................................................................ 2-16 2.1.8 Area Radiological Impact Summaries............................................................... 2-16 2.1.8.1 00L Open Land Area Ou6tside the Controlled Area................ 2-16 2-1

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 2.1.8.2 SGB Steam Generator Building....................................

2-19 2.1.8.3 CTB Control Building..............................................

2-20 2.1.8.4 TBN-0l1 - Turbine Building..............................................

2-22 2.1.8.5 OFB Office Building................................................

2-24 2.1.8.6 NOL-0O1 - Open Land Area Inside the Controlled Area...............

2-27 2.1.8.7 RYB-0 1 - Reactor Building..............................................

2-30 2.1.8.8 FRB Fuel and Repair Building (FARB)...........................

2-32 2.1.8.9 TRW-0 1 - Trestleway....................................................

2-36 2.1.8.10 NAB Sodium Building..............................................

2-37 2.1.8.11 VNB-0 1 - Ventilation Building..........................................

2-40 2.1.8.12 NAT Sodium Tunnel................................................

2-42 2.1.8.13 ESG East Sodium Gallery..........................................

2-43 2.1.8.14 WSG West Sodium Gallery........................................

2-45 2.1.8.15 WGB Waste Gas Building..........................................

2-47 2.1.8.16 IGB Inert Gas Building.............................................

2-49 2.1.9 HSA Findings.........................................................................

2-50

2. 1.10 USA Conclusions....................................................................

2-51 2.2 Hydrogeological Investigations.............................................................

2-51 2.2.1 Methods...............................................................................

2-52 2.2.2 Site Geology and Hydrology........................................................

2-52 2.2.2.1 Hydrogeologic Characteristics...........................................

2-52 2.2.3 Groundwater Analytical Results....................................................

2-53 2.3 Site Characterization Survey.................................................................

2-54 2.3.1 Initial Characterization Sureys......................................................

2-54 2.3.2 Recent Characterization Surveys...................................................

2-56 2-2 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 4 June 2011 2.1.8.2 SGB Steam Generator Building................................................. 2-19 2.1.8.3 CTB Control Building................................................................ 2-20 2.1.8.4 TBN Turbine Building................................................................ 2-22 2.1.8.5 OFB Office Building.................................................................. 2-24 2.1.8.6 NOL Open Land Area Inside the Controlled Area..................... 2-27 2.1.8.7 RXB Reactor Building................................................................ 2-30 2.1.8.8 FRB Fuel and Repair Building (FARE)..................................... 2-32 2.1.8.9 TRW Trestleway......................................................................... 2-36 2.1.8.10 NAB Sodium Building.H............................................................ 2-37 2.1.8.11 VNB Ventilation Building.......................................................... 2-40 2.1.8.12 NAT Sodium Tunnel.................................................................. 2-42 2.1.8.13 ESG East Sodium Gallery.......................................................... 2-43 2.1.8.14 WSG West Sodium Gallery........................................................ 2-45 2.1.8.15 WGB Waste Gas Building.......................................................... 2-47 2.1.8.16 IGB Inert Gas Building............................................................... 2-49 2.1.9 HSA Findings..................................................................................................... 2-50 2.1.10 HSA Conclusions............................................................................................... 2-51 2.2 Hydrogeological Investigations..................................................................................... 2-51 2.2.1 Methods.............................................................................................................. 2-52 2.2.2 Site Geology and Hydrology............................................................................. 2-52 2.2.2.1 Hydrogeologic Characteristics............................................................ 2-52 2.2.3 Groundwater Analytical Results........................................................................ 2-53 2.3 Site Characterization Survey.......................................................................................... 2-54 2.3.1 Initial Characterization Sureys........................................................................... 2-54 2.3.2 Recent Characterization Surveys....................................................................... 2-56 2-2

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 2.3.2.1 Organization and Responsibilities................................................... 2-56 2.3.2.2 Characterization Data Categories....................................................

2-57 2.3.2.3 Characterization Survey Design....................................................... 2-58 2.3.2.4 Instrument Selection, Use and Minimum Detectable Concentrations (MDCs)................................................................ 2-58 2.3.2.5 Q uality A ssurance............................................................................. 2-60 2.3.2.6 Data Quality Objectives.................................................................... 2-60 2.3.3 Survey Findings and Results............................................................................ 2-61 2.3.3.1 Surfaces, Structures and Soils........................................................... 2-61 2.3.3.2 Ancillary Systems.............................................................................. 2-61 2.3.4 Ambient and Background................................................................................. 2-62 2.3.5 Waste Volumes and Activities......................................................................... 2-62 2.4 Continuing Characterization..........................................................

....... 2-62 2.5 Sum m ary..................................................................................................................

... 2-63 2.6 R eferences.............................................................................

.. 2-63 List of Tables Table 2-1 Operational/Post-operational Chronological Summary................................... 2-12 Table 2-2 List of Unplanned Events................................................................................... 2-15 Table 2-3 Survey Area Summary Information.........

............................................................. 2-16 Table 2-4 OOL-01 Characterization Data.......................................................................... 2-18 Table 2-5 SGB-01 Characterization Data......................................................................

2-20 Table 2-6 CTB-01 Characterization Data...................................................................

2-21 Table 2-7 TBN-01 Characterization Data (1st, 2nd & 3rd Floors).................................... 2-23 Table 2-8 TBN-01 Characterization Data (4th, 5th & 6th Floors)................................... 2-24 Table 2-9 OFB-01 Characterization Data....................................................................

2-26 Table 2-10 OFB-01 Characterization Data....................................................................

2-27 Table 2-11 NOL-01 Characterization Data...................................................................... 2-29 Table 2-12 RXB-01-01 Characterization Data...............................................................

2-31 2-3 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 4 June 2011 2.3.2.1 Organization and Responsibilities...................................................... 2-56 2.3.2.2 Characterization Data Categories....................................................... 2-57 2.3.2.3 Characterization Survey Design......................................................... 2-58 2.3.2.4 Instrument Selection, Use and Minimum Detectable Concentrations (MDCs)...................................................................... 2-58 2.3.2.5 Quality Assurance............................................................................... 2-60 2.3.2.6 Data Quality Objectives...................................................................... 2-60 2.3.3 Survey Findings and Results.............................................................................. 2-61 2.3.3.1 Surfaces, Structures and Soils............................................................. 2-61 2.3.3.2 Ancillary Syst~ms............................................................................... 2-61 2.3.4 Ambient and Background.................................................................................. 2-62 2.3.5 Waste Volumes and Activities........................................................................... 2-62 2.4 Continuing Characterization.......................................................... :............................... 2-62 2.5 Summary........................................................................................................................ 2-63 2.6 References...................................................................................................................... 2-63 List of Tables Table 2-1 OperationaVPost-operational Chronological Summary..................................... 2-12 Table 2-2 List of Unplanned Events................................................................................... 2-15 Table 2-3 Survey Area Summary Information........................................... ~....................... 2-16 Table 2-4 OOL-O 1 Characterization Data.......................................................................... 2-18 Table 2-5 SGB-01 Characterization Data.......................................................................... 2-20 Table 2-6 CTB-01 Characterization Data......................................................................... 2-21 Table 2-7 TBN-01 Characterization Data (lst, 2nd & 3rd Floors).................................... 2-23 Table 2-8 TBN -01 Characterization Data (4th, 5th & 6th Floors)..................................... 2-24 Table 2-9 OFB-01 Characterization Data.......................................................................... 2-26 Table 2-10 OFB-Ol Characterization Data.......................................................................... 2-27 Table 2-11 NOL-01 Characterization Data.......................................................................... 2-29 Table 2-12 RXB-O 1-0 1 Characterization Data..................................................................... 2-31 2-3

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 Table 2-13 RXB-01-02 Characterization Data.................................................................... 2-32 Table 2-14 FRB-01 Characterization Data........................................................................... 2-35 Table 2-15 TRW-01 Characterization Data....................................................................... 2-37 Table 2-16 NAB-01 Characterization Data...............................................

.......................... 2-39 Table 2-17 NAB-01 Characterization Data (Mezzanine)..................................................... 2-40 Table 2-18 VNB-01 Characterization Data...................................................................... 2-41 Table 2-19 NAT-01 Characterization Data........................................................................ 2-43 Table 2-20 ESG-01 Characterization Data.........................................................................

2-45 Table 2-21 WSG-01 Characterization Data....................................................................... 2-46 Table 2-22 WGB-01 Characterization Data....................................................................... 2-48 Table 2-23 WGB-01 Lower Level Characterization Data................................................. 2-48 Table 2-24 IGB-01 Characterization Data................................................................. 2-50 Table 2-25 Comparison of Ambient Levels for Beta Scans............................................... 2-56 Table 2-26 Comparison of Ambient Levels for Gamma Scans.......................................... 2-56 Table 2-27 Typical Survey Instrumentation Sensitivities.................................................. 2-59 Table 2-28 Vendor Lab. Methods and MDAs...................................................................... 2-59 2-4 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 4 June 2011 Table 2-13 RXB-01-02 Characterization Data..................................................................... 2-32 Table 2-14 FRB-01 Characterization Data........................................................................... 2-35 Table 2-15 TRW-01 Characterization Data......................................................................... 2-37 Table 2-16 NAB-01 Characterization Data.......................................................................... 2-39 Table 2-17 NAB-01 Characterization Data (Mezzanine)..................................................... 2-40 Table 2-18 VNB-01 Characterization Data.......................................................................... 2-41 Table 2-19 NAT-01 Characterization Data.......................................................................... 2-43 Table 2-20 ESG-O 1 Characterization Data........................................................................... 2-45 Table 2-21 WSG-01 Characterization Data......................................................................... 2-46 Table 2-22 WGB-O 1 Characterization Data ".".""".""""""""""""".".""""""."............... 2-48 Table 2-23 WGB-01 Lower Level Characterization Data................................................... 2-48 Table 2-24 IGB-O 1 Char~cterization Data........................................................................... 2-50 Table 2-25 Comparison of Ambient Levels for Beta Scans................................................. 2-56 Table 2-26 Comparison of Ambient Levels for Gamma Scans........................................... 2-56 Table 2-27 Typical Survey Instrumentation Sensitivities.................................................... 2-59 Table 2-28 Vendor Lab. Methods and MDAs...................................................................... 2-59 2-4

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 List of Figures Figure 2-1: EF1 License Termination Org. Chart.................................................................... 2-57 Figure 2-2: EF1 Survey Area Designations..........................................................................

2-64 Appendices Appendix 2-A: Historical Photographs Appendix 2-B: Survey Maps, Areas and Locations Appendix 2-C: 2004 Characterization Survey 2-5 Fermi 1 License Termination Plan Chapter 2 Site Characterization List of Figures Revision 4 June 2011 Figure 2-1: EF1 License Termination Org. Chart..................................................................... 2-57 Figure 2-2: EF1 Survey Area Desi~nations.............................................................................. 2-64 Appendices Appendix 2-A: Historical Photographs Appendix 2-B: Survey Maps, Areas and Locations Appendix 2-C: 2004 Characterization Survey 2-5

Fermi 1 License Termination Plan Revision 0 Chapter 2 Site Characterization May 2009 2.0 SITE CHARACTERIZATION 2.1 Historical Site Assessment Summary 2.1.1 Introduction The Historical Site Assessment (HSA) describes the site's physical configuration, identifies the radioactive constituents of site contamination, assesses the migration of contaminants, identifies contaminated media and classifies impacted areas.

Detroit Edison (DECo) has conducted the HSA of its Fermi 1 (EF1) site in accordance with the guidance of NUREG-1575, "Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM)," in support of the ultimate decommissioning and license termination of the facility. The HSA formally began in 2007, following several preliminary assessments of the impact of facility operations on the remediation required prior to the performance of the Final Status Survey(s) (FSS). These preliminary surveys were conducted beginning in 1997 with the meeting of previous employees followed by another meeting in 2002. An initial characterization survey was performed in 2004. The HSA was formally compiled in 2008. The purpose of the HSA is to document a comprehensive investigation identifying, collecting, organizing and evaluating historical information relevant to the EF1 site. The HSA focuses on open land areas and those structures that will remain at the time of final status survey.

The HSA consisted of a review of:

License and Technical Specifications

> Technical Specification Changes

> License Amendments and Revisions

> Fermi 1 Manual

> F1SAR

Original Plant Design

> Function and purpose of systems and structures

> Plant operating parameters

> Plant operating procedures

> PRDC Technical Information and Hazards Summary Report

" Original Plant Construction Drawings and Photographs

> Specifications for systems and structures

> Field Changes/as built drawings

> Site Conditions o Plant Operating History

> Reports

> Plant Operating Procedures Regarding Spills and Unplanned Releases

> Shift Supervisor Logbooks

> Radiological Environmental Monitoring Program and Golder Report on Groundwater Characterization

> Monthly Plant Operational Reports 2-6 Fermi 1 License Termination Plan Chapter 2 Site Characterization 2.0 SITE CHARACTERIZATION 2.1 Historical Site Assessment Summary 2.1.1 Introduction Revision 0 May 2009 The Historical Site Assessment (HSA) describes the site's physical configuration, identifies the radioactive constituents of site contamination, assesses the migration of contaminants, identifies contaminated media and classifies impacted areas.

Detroit Edison (DECo) has conducted the HSA of its Fermi 1 (EF1) site in accordance with the guidance ofNUREG-1575, "Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM)," in support of the ultimate decommissioning and license termination of the facility. The HSA formally began in 2007, following several preliminary assessments of the impact of facility operations on the remediation required prior to the performance of the Final Status Survey(s) (FSS). These preliminary surveys were conducted beginning in 1997 with the meeting of previous employees followed by another meeting in 2002. An initial characterization survey was performed in 2004. The HSA was formally compiled in 2008. The purpose of the HSA is to document a comprehensive investigation identifying, collecting, organizing and evaluating historical information relevant to the EFI site. The HSA focuses on open land areas and those structures that will remain at the time of fmal status survey.

The HSA consisted of a review of:

License and Technical Specifications

~ Technical Specification Changes

~ License Amendments and Revisions

~ Fermi 1 Manual

~ F1SAR Original Plant Design

~ Function and purpose of systems and structures

~ Plant operating parameters

~ Plant operating procedures

~ PRDC Technical Information and Hazards Summary Report G

Original Plant Construction Drawings and Photographs

):> Specifications for systems and structures

~ Field Changes/as built drawings

);> Site Conditions Plant Operating History

>> Reports

);> Plant Operating Procedures Regarding Spills and Unplanned Releases

);> Shift Supervisor Logbooks

~ Radiological Environmental Monitoring Program and Golder Report on Groundwater Characterization

>> Monthly Plant Operational Reports 2-6

Fermi 1 License Termination Plan Revision 0 Chapter 2 Site Characterization May 2009 2.1.8.2 SGB Steam Generator Building The Steam Generator Building is located south of the Reactor Building and north of the Detroit Edison turbine structure. The building housed the steam generators, secondary sodium pumps and piping components of the secondary coolant system. The equipment components were located at the operating floor at elevation 590'-0". The basement of the building housed the storage tanks and miscellaneous piping and equipment components of the Secondary Sodium Services System. The structure and equipment components were supported through a system of structural steel columns to a reinforced concrete base slab resting on bedrock. The basement floor of the building is divided into five sectors. An east-west concrete block firewall was installed the full length of the building extending between the basement floor and the operating floor. The remaining structure is of conventional design, that is, steel and corrugated asbestos walls.

Modes and vectors for transmigration of contaminants include:

Movement or removal of radioactive material for shipment.

Tritium in some residual sodium

Movement into and out of the RRA of personnel and equipment at the RRA entrance from the Steam Generator Building.

Survey area SGB-01 has an area footprint of approximately 1527 square meters.

Characterization data from past surveys proved to be insufficient for FSS planning activities.

A Characterization effort was implemented on August 21, 2008 to include smears, scans and fixed-point measurements in SGB-01. An ambient correction 1 was achieved by taking shielded readings at five locations on each level and the Mean of those data was calculated for each fixed-point location. Smears indicated no smear result greater than MDA.

Table 2-5 represents the results of the fixed-point readings taken on the floors, walls and ceiling during this survey effort. Smears were taken at each fixed-point location. No beta scan indicated greater than background. Gamma scans were performed in the general areas as well as locations where cracks and wall-to-floor junctures were present. No gamma scan indicated greater than background.

SAmbient readings were taken in structures to evaluate the gamma influence of the operation of Fermi 2 on the readings taken at EF1. A discussion of the methodology for taking the ambient readings is found in Section 2.3.4 2-19 Fermi 1 License Termination Plan Chapter 2 Site Characterization 2.1.8.2 SGB Steam Generator Building Revision 0 May 2009 The Steam Generator Building is located south of the Reactor Building and north of the Detroit Edison turbine structure. The building housed the steam generators, secondary sodium pumps and piping components of the secondary coolant system. The equipment componenrs were located at the operating floor at elevation 590'-0"~ The basement of the building housed the storage tanks and miscellaneous piping and equipment components of the Secondary Sodium Services System. The structure and equipment components were supported through a system of structural steel columns to a reinforced concrete base slab resting on bedrock. The basement floor of the building is divided into five sectors. An east-west concrete block firewall was installed the full length of the building extending between the basement floor and the operating floor. The remaining structure is of conventional design, that is, steel and corrugated asbestos walls.

Modes and vectors for transmigration of contaminants include:

Movement or removal of radioactive material for shipment.

Tritium in some residual sodium

Movement into and out of the RRA of personnel and equipment at the RRA entrance from the Steam Generator Building.

Survey area SGB-Ol has an area footprint of approximately 1527 square meters.

Characterization data from past surveys proved to be insufficient for FSS planning activities.

A Characterization effort was implemented on August 21,2008 to include smears, scans and fixed-point measurements in SGB-Ol. An ambient correction 1 was achieved by taking shielded readings at five locations on each level and the Mean of those data was calculated for each fixed-point location. Smears indicated no smear result greater thanMDA.

Table 2-5 represents the results of the fixed-point readings taken on the floors, walls and ceiling during this survey effort. Smears were taken at each fixed-point location. No beta scan indicated greater than background. Gamma scans were performed in the general areas as well as locations where cracks and wall-to-floor junctures were present. No gamma scan indicated greater than background.

1 Ambient readings were taken in structures to evaluate the gamma influence ofthe operation of Fermi 2 on the readings taken at EFl. A discussion of the methodology for taking the ambient readings is found in Section 2.3.4 2-19

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 Table 2-5 SGB-01 Characterization Data Wesult Result Restilt Location (dpiu/100cm)

Location (dprni/10cm2)

Location (dpin/100cin BASEMENT Is' FLOOR 2 nd FLOOR CHAR-SGB-01-001-F-M 2445 CHAR-SG13-01-016-F-M 2874 CHAR-SGB-01-031-F-M 3697 CHAR-SGB-01-002-F-M 2590 CHAR-SGB-01-017-F-M 2599 CHAR-SGB-01-032-F-M 3520 CHAR-SGB-01-003-F-M 2603 CHAR-SGB-01-018-F-M 2893 CHAR-SGB-01-033-F-M 2255 CHAR-SGB-01-0b4-F-N4 2806 CHAR-SGB-01-019-F-M 2854 CHAR-SGB-01-034-F-M 2137 CHAR-SGB-01-005-F-M 2563 CHAR-SGB-01-020-F-M 2972 CHAR-SGB-01-035-F-M 2288 CHIAR-SGB-0 1-006-F-M 2491 CHAR-SGB-0 1-021-F-M 2854 CHAR-SGB-01-036-F-M 2117 CHAR-SGB-01-007-F-M 2426 CHAR-SGB-01-022-F-M 2723 CHAR-SGB-01-037-F-M 2052 CHAR-SGB-01-008-F-M 2353 CHAR-SdB-01-023-F-M 3234 CRAR-SGB-01-038-F-M 1901 CHAR-SGB-01-009-F-M 2740 CHAR-SOB-01-024-F-M 3024 CHAR-SGB-01-039-F-M 2150 CHAR-SGB-01-010-F-M 2616 CHAR-SGB-01-025-F-M 2697 CHAR-SGB-01-040-F-M 2537 CHAR-SGB-01-011-F-M 2649 CHAR-SGB-01-026-F-M 2906 CHAR-SGB-01-041-F-M 2209 CHAR-SGB-01-012-F-M 2609 CHAR-SGB-01-027-F-M 2906 CH{AR-SGB-01-042-F-M 2124 CHAR-SGB-01-013-F-M 1672 CHAR-SGB-01-028-F-M 2946 CHAR-SGB-01-043-F-M 2550 CHAR-SGB-01-014-F-M 2694 CHAR-SGB-01-029-F-M 2546 CHAR-SGB-01-044-F-M 3081 CHAR-SGB-01-015-F-M 2360 CHAR-SGB-01-030-F-M 2684 CHAR-SGB-01-045-F-M 2603 Mean Ambient 2015 Mean Ambient 1203 Mean Ambient 1891 Ct. Mean 2508 Ct. Mean 2847 Ct. Mean 2482 Ct. Median 2590 Ct. Median 2874 Ct. Median 2255 Ct. Std. Dev.

266 Ct. Std. Dev.

176 Ct. Std. Dev.

542 F-M =Fixed measurement Based on the fixed-point measurements the average measurements in SGB-01 were -500 to 1650 dpm/100cm2 greater than the ambient levels.

These measurements are lower than the most restrictive radionuclide Derived Concentration Guideline Level (DCGL) present, (Co-GO).

Based upon the findings of materials reviewed, personnel interviews and of data acquired during characterization, SGB-0l is classified as a Class 3 area.

2.1.8.3 CTB-0l - Control Building This structure had, as its primary purpose, the protection of personnel working inside, from the elements of weather and radioactive streaming.

In addition, it served as protection for the equipment installed to control the operation of the whole plant. In order for the shielding function to be performed, the walls adjacent to the Containment Building are 40 inch thick, reinforced concrete, and the roof was designed to eliminate the effect of sky shine on the control room located on the third floor of the building.

2-20 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 4 June 2011 Table 2-5 SGB-Ol Characterization Data

........ **..\\****.c*j

.*.*** *** **ic';:::i:::*::i:i:I.~~~~*lt...,;.....

Eo:c~t:i~~

ResultC'**, ',

.. ~_.' 0.:--:.. :::...-,.:.!.

.. ;i\\.;i*

Result* *.*. ~.

Loc~tion;....*

"(dpm/l OOcmty*

.'.' "..(dpIltI100cnh i~~iflril1' (dpm/l()Ocm2)

BASEMENT

.1 51 FLOOR 2nd FLOOR CHAR-SGB-Ol-OOl-F-M 2445 CHAR-SGB-O 1-0 l6-F-M 2874 CHAR-SGB-OI-031-F-M 3697 CHAR-SGB-O 1-002-F-M 2590 CHAR-SGB-OI-017-F-M 2599 CHAR -SGB-O 1-032-F-M 3520 CHAR -SGB-O 1-003-F-M 2603 CHA.R-SGB-OI-OlS-F:M 2893 CHAR-SGB-Ol-033-F-M 2255 CHAR-SGB-O 1-OO4-F-M 2806 CHAR-SGB-Ol-019~F-M 2854 cHAR -SGB-O 1-034-F-M 2137 CHAR-SGB-Ol-005-F-M 2563 CHAR-SGB-Ol-020-F-M 2972 CHAR-SGB-Ol-035-F-M 2288 CHAR-SGB-O 1-006-F-M 2491 CHAR-SGB-Ol-02l-F-M 2854 CHAR -SGB-O 1-036-F-M 2117 CHAR-SGB-O 1-007-F-M 2426 CHAR-SGB-OI-022-F-M 2723 CHAR-SGB-Ol-037-F-M 2052 CHAR-SGB-Ol-OOS-F-M 2353 CHAR-SGB-O 1-023-F-M 3234 CHAR-SGB-O 1-038-F-M 1901 CHAR-SGB-Ol-009-F-M 2740 CHAR-SGB-O 1-024-F-M 3024 CHAR-SGB-Ol-039-F-M 2150 CHAR-SGB-OI-OIO-F-M 2616 CHAR-SGB-O 1-025-F-M 2697 CHAR-SGB-OI-040-F-M 2537 CHAR-SGB-OI-Oll-F-M 2649 CHAR-SGB-O 1-026-F-M 2906 CHAR-SGB-Ol-04l-F-M 2209 CHAR -SGB-O 1-0 12-F-M 2609 CHAR-SGB-OI-027-F-M 2906 CHAR-SGB-Ol-042-F-M 2124 CHAR-SGB-OI-013-F-M 1672 CHAR-SGB-Ol-02S-F-M 2946 CHAR-SGB-Ol-043-F-M 2550 CHAR-SGB-Ol-014-F-M 2694 CHAR-SGB-Ol-029-F-M 2546 CHAR-SGB-OI-044-F-M 3081 CHAR-SGB-Ol-015-F-M 2360 CHAR-SGB-O 1-030-F-M 2684 CHAR-SGB-Ol-045-F-M 2603 Mean Ambient 2015 Mean Ambient 1203 Mean Ambient 1891 Ct. Mean 2508 Ct. Mean 2847 Ct. Mean 2482 Ct. Median 2590 Ct. Median 2874 Ct. Median 2255 Ct. Std. Dey.

266 Ct. Std. Dey.

176 Ct. Std. Dey.

542 F-M = FIxed measurement Based on the fixed-point measurements the average measurements in SGB-01 were ~500 to 1650 dpm/100cm2 greater than the ambient levels.

These measurements are lower than the most restrictive radionuclide Derived Concentration Guideline Level (DCGL) present, (Co-60).

Based upon the findings of materials reviewed, personnel interviews and of data acquired during characterization, SGB-01 is classified as a Class 3 area.

2.1.8.3 CTB-Ol - Control Building This structure had, as its primary purpose, the protection of personnel working inside, from the elements of weather and radioactive streaming.

In addition, it served as protection for the equipment installed to control the operation of the whole plant. In order for the shielding function to be performed, the walls adjacent to the Containment Building are 40 inch thick, reinforced concrete, and the roof was designed to eliminate the effect of sky shine on the control room located on the third floor of the building.

2-20

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 Modes and vectors for transmigration of contaminants include:

eMigration of contamination from the radwaste storage area on the 3rd level of the Turbine Building to the Control Building.

Survey area CTB-0 1 has an area footprint of approximately 2,075 square meters.

Characterization data from past surveys proved to be insufficient for FSS planning activities. A Characterization effort was implemented on August 11, 2008 to include smears, scans and fixed-point measurements in CTB-0 1. An ambient correction was achieved by taking shielded readings at five locations on each floor and the Mean of those data was calculated. Table 2-6 represents the results of the fixed-point readings taken on the floors, walls and ceiling during this survey effort. Smears were taken at each fixed-point location.

Smears indicated no smear result greater than MDA. One-square meter beta scans were performed at each fixed-point location.

No beta scan indicated greater than background. Gamma scans were performed in the general areas as well as locations where cracks and wall-to-floor junctures were present. No gamma scan indicated greater than background.

Table 2-6 CTB-01 Characterization Data ReResult eut_-Result Location d in/100crn2 Location

-=-

dm/Oc 2

Location (dp mn/00CM) 1st FLOOR 2nd FLOOR 3rd FLOOR CHAR-CTB-01 -001 -F-M 2432 CHAR-MT-01-016-F-M 2605 CHAR-CTB-0 1-031 -F-M 2127 CHAR-CTB-01-002-F-M 2445 CHAR-MT-01-017-F-M 2042 CHAR-CTB-01-032-F-M 1761 CHAR-CTB-0 1-003-F-M 2334 CHAR-MT-01-018-F-M 1866 CHAR-CTB-0 1-033-F-M 1767 CHAR-CTB-01-004-F-M 1731 CHAR-MT-01-019-F-M 1983 CHAR-CTB-01-034-F-M 1748 CHAR-MT-0 1-005-F-M 2347 CHAR-CTB-01-020-F-M 1990 CHAR-CTB-01-035-F-M 1866 CHAR-CTB-01-006-F-M 2609 CHAR-MT-01-021-F-M 1833 CHAR-CTB-01-036-F-M 2284 CHAR-CTB-01-007-F-M 2367 CHAR-MT-01-022-F-M 2088 CHAR-CTB-01-037-F-M 1970 CHAR-CTB-0 1-008-F-M 2432 CHAR-CTB-0 1-023-F-M 1885 CH-AR-CTB-01-038-F-M 1833 CHAR-MT-0 t-009-F-M 2117 CHAR-CTB-0 1-024-F-M 1938 CHAR-CTB-01-039-F-M 2154 CHAR-MT-01 -01l0-F-M 2308 CHAR-CTB-01-025-F-M 1780 CHAR-CMB-0t-040-F-M 1918 CHAR-CTB-0 1-01 1-F-M 2412 CH-AR-CTB-01-026-F-M 1820 CHAR-CTB-0 1-04 1-F-M 1977 CHAR-MT-0 1-0 12-F-M 2530 CHAR-CTB-01 -027-F-M 1303 CHAR-CTB-01-042-F-M 1774 CHAR-CT13-0 1-0 13-F-M 2334 CHAR-CTB-01 -028-F-M 1172 CHAR-CTB-01 -043-F-M 1839 CHAR-CT13-01-014-F-M 2491 CHAR-CTB-01-029-F-M 2376 CHAR-CTB-01-044-F-M 1604 CHAR-CTB-0 t-01 5-F-M 2294 CHAR-CTB-01 -030-F-M 2317 CHAR-CTB-0 1-045-F-M 1990 Mean Ambient 1798 Mean Ambient 1782 Mean Ambient 1746 Ct. Mean 2346 Ct. Mean 1933 Ct. Mean 1907 Ct. Median 2367 Ct. Median 1938 Ct. Median 1866 Ct. Std. Dev.

205 Ct. Std. Dev.

365 Ct. Std. Dev.

180 F-M = Fixed measurement 2-21 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 4 June 2011 Modes and vectors for transmigration of contaminants include:

III Migration of contamination from the radwaste storage area on the 3 rd level of the Turbine Building to the Control Building.

Survey area CTB-01 has an area footprint of approximately 2,075 square meters.

Characterization data from past surveys proved to be insufficient for FSS planning activities. A Characterization effort was implemented on August 11,2008 to include smears, scans and fixed-point measurements in CTB-O 1. An ambient correction was achieved by taking shielded readings at five locations on each floor and the Mean of those data was calculated. Table 2-6 represents the results of the fixed-point readings taken on the floors, walls and ceiling during this survey effort. Smears were taken at each fixed-point location.

Smears indicated no smear result greater than MDA. One-square meter beta scans were performed at each fixed-point location.

No beta scan indicated* greater than background. Gamma scans were performed in the general areas as well as locations where cracks and wall-to-floor junctures were present. No gamma scan indicated greater than background.

Table 2-6 CTB-Ol Characterization Data

)~~:~i:6:~'JW:f *.*............

'.. Result.*.*..*....**.

L~~~ti~n;:J;i:~ll*;C:-;. ~t~W6*&~IUC~;

ResuI,t.,*\\

Loca iOri,{.j,~,......

.* (dpJ1lJI00cm2)

Hcafi*6rt****

(dpmIlOOcii?)

1st FLOOR 2nd FLOOR 3rdFLOOR CHAR-CTB-OI-OOI-F-M 2432 CHAR-CTB-OI-016-F-M 2605 CHAR-CTB-OI-031-F-M 2127 CHAR-CTB-OI-OO2-F-M 2445 CHAR-CTB-OI-017-F-M 2042 CHAR-CTB-OI-032-F-M 1761 CHAR-CTB-OI-OO3-F-M 2334 CHAR-CTB-OI-OlS-F-M 1866 CHAR-CTB-O 1-033-F-M 1767 CHAR -CTB-O 1-OO4-F-M 1731 CHAR-CTB-OI-019-F-M 1983 CHAR-CTB-OI-034-F-M 1748 CHAR-CTB-OI-OO5-F-M 2347 CHAR~CTB-OI-020-F-M 1990 CHAR-CTB-OI-035-F-M 1866 CHAR-CTB-OI-OO6-F-M 2609 CHAR-CTB-OI-021-F-M 1833 CHAR-CTB-OI-036-F-M 2284 CHAR-CTB-OI-OO7-F-M 2367 CHAR-CTB-OI-022-F-M 2088 CHAR-CTB-OI-037-F-M 1970 CHAR-CTB-OI-OOS-F-M 2432 CHAR-CTB-O 1-023-F-M 1885 CHAR-CTB-OI-03S-F-M 1833 CHAR-CTB-OI-009-F -M 2117 CHAR-CTB-OI-024-F-M 1938 CHAR-CTB-OI-039-F-M 2154 CHAR-CTB-OI-OIO-F-M 2308 CHAR-CTB-O 1-02S-F-M 1780 CHAR-CTB-OI-040-F-M 1918 CHAR-CTB-OI-OI1-F-M 2412 CHAR-CTB-OI-026-F-M 1820 CHAR-CTB-OI-041-F-M 1977 CHAR-CTB-OI-012-F-M 2530 CHAR-CTB-OI-027-F-M 1303 CHAR-CTB-OI-042-F-M 1774 CHAR-CTB-OI-013-F-M 2334 CHAR-CTB-OI-02S-F-M 1172 CHAR-CTB-OI-043-F-M 1839 CHAR -CTB-O 1-0 14-F-M 2491 CHAR-CTB-OI-029-F-M 2376 CHAR-CTB-OI-044-F-M 1604 CHAR-CTB-OI-OIS-F-M 2294 CHAR-CTB-OI-030-F-M 2317 CHAR-CTB-OI-04S-F-M 1990 Mean Ambient 1798 Mean Ambient 1782 Mean Ambient 1746 Ct. Mean 2346 ct. Mean 1933 Ct. Mean 1907 Ct. Median 2367 Ct. Median 1938 Ct. Median 1866 Ct. Std. Dev.

205 ct. Std. Dev.

365 Ct. Std. Dev.

180 F-M = Fixed measurement 2-21

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 Fixed-point measurements were at or slightly above the ambient radiation levels in the building.

Based upon the findings of materials reviewed, personnel interviews and of data acquired during characterization, CTB-01 is classified as a Class 3 area.

2.1.8.4 TBN Turbine Building Steam once produced in the three steam generators located within the Steam Generator Building passed to the adjacent Turbine Building and was used to operate the turbine. The turbine was a tandem-compound, single flow machine. Four stages of feed water heating were used. The turbine and support equipment, feedwater heaters, main condenser and associated piping and pumps are/were located in the Turbine Building.

The Turbine Building is a steel frame structure which is tied together with standard riveted or bolted connections. Steel beams support the concrete or grating floors. The exterior walls consist of a 4-foot high apron wall constructed of 8-inch cinder block except in the region behind the transformer and the hydrogen storage platform, where reinforced concrete is used to provide a positive fire barrier. Non-insulated, corrugated, asbestos-cement siding which is fastened to steel channel girts that run the full height of the building is installed above the apron wall. Open web steel joists support the standard ribbed galvanized steel roof deck.

Modes and vectors for transmigration of contaminants include:

o Movement and storage of Radwaste on the 1st and 3 rd floors of TBN-01.

Survey area TBN-01 has an area footprint of approximately 6235 square meters.

Characterization data from past surveys proved insufficient for FSS planning activities. A Characterization effort was implemented on August 13, 2008 to include smears, scans and fixed-point measurements in TBN-01. An ambient measurement was achieved by taking shielded readings at five locations on each floor and the Mean of those data was calculated. Tables 2-7 and 2-8 represent the results of the fixed-point readings taken on the floors, walls and ceiling during this survey effort.

Smears were taken at each fixed-point location. Smears indicated no smear result greater than MDA. One-square meter beta scans were performed at each fixed-point location. No beta scan indicated greater 2-22 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 4 June 2011 Fixed-point measurements were at or slightly above the ambient radiation levels in the building.

Based upon the findings of materials reviewed, personnel interviews and of data acquired during characterization, CTB-O 1 is classified as a Class 3 area.

2.1.8.4 TBN Turbine Building Steam once produced in the three steam generators located within the Steam Generator Building passed to the adjacent Turbine Building and was used to operate the turbine. The turbine was a tandem-compound, single flow machine. Four stages of feed water heating were used. The turbine and support equipment, feedwater heaters, main condenser and associated piping and pumps are/were located in the Turbine Building.

The Turbine Building is a steel frame structure which is tied together with standard riveted or bolted connections. Steel beams support the concrete or grating floors. The exterior walls consist of a 4-foot high apron wall constructed of 8-inch cinder block except in the region behind the transformer and the hydrogen storage platform, where reinforced concrete is used to provide a positive fire barrier. Non-insulated, corrugated, asbestos-cement siding which is fastened to steel channel girts that run the full height of the building is installed above the apron wall. Open web steel joists support the standard ribbed galvanized steel roof deck.

Modes and vectors for transmigration of contaminants include:

Movement and storage of Radwaste on the 1 st and 3rd floors of TBN-01.

Survey area TBN -01 has an area footprint of approximately 6235 square meters.

Characterization data from past surveys proved insufficient for FSS planning activities. A Characterization effort was implemented on August 13, 2008 to include smears, scans and fixed-point measurements in TBN-O 1. An ambient measurement was achieved by taking shielded readings at five locations on each floor and the Mean of those data was calculated. Tables 2-7 and 2-8 represent the results of the fixed-point readings taken on the floors, walls and ceiling during this survey effort.

Smears were taken at each fixed-point location. Smears indicated no smear result greater than MDA. One-square meter beta scans were performed at each fixed-point location. No beta scan indicated greater 2-22

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 than background. Gamma scans were performed in the general areas as well as locations where cracks and wall-to-floor junctures were present.

No garmma scan indicated greater than background with the exception of the areas on the 3 rd floor that were attributed to the presence of waste boxes awaiting shipment.

Table 2-7 TBN-01 Characterization Data (1st, 2nd & 3rd Floors) eutResult Result Location (dpiu/100cn)

Location d

/Oc 2

Location _

dpra/l00cm)

I1st FLOOR 2nd FLOOR 3rd FLOOR CHAR-TBN-01-001-F-M 2799 CHAR-TBN-0 1-0 16-F-M 2203 CHAR-TBN-0 1-03 1-F7-M 2439 CHAR-TBN-01-002-F-M 2485 CHAR-TBN-0 1-017-F-M 2465 CHAR-TBN-0 1-032-F-M 2190 CHAR-TBN-01-003-F-M 2216 CHAR-TBN-0 1-018-F-M 2996 CHAR-TBN-01-033-F-M 2530 CHAR-TBN-0 1-004-F-M 2334 CHAR-TBN-0 1-019-F-M 2806 CHAR-TBN-0 1-034-F-M 2773 CHAR-TBN-01-005-F-M 2124 CHAR-TBN-01-020-F-M 2196 CH-AR-TBN-0 1-035-F-M 2806 CHAR-TBN-01-006-F-M 2426 CHAR-TBN-01-021-F-M 2439 CHAR-TBN-01-036-F-M 2826 CHAR-TBN-01-007-F-M 2203 CHAR-TBN-0 1-022-F-M 2465 CHAR-TBN-01-037-F-M 2570 CHAR-TBN-01-008-F-M 2288 CHAR-TBN-01-023-F-M 2583 CHAR-TBN-01-038-F-M 2839 CHAR-TBN-01-009-F-M 2321 CHAR-TBN-0 1-024-F-M 2150 CH-AR-TBN-01-039-F-M 3114 CHAR-TBN-01-010-F-M 2268 CHAR-TBN-01-025-F-M 3697 CHAR-TBN-01-040-F-M 3153 CHAR-TBN-01-01 I-F-M 1927 CHAR-TBN-0 1-026-F-M 3370 CHAR-TBN-01-041-F-M 2819 CHAR-TBN-01-012-F-M 2393 CHAR-TBN-01-027-F-M 2924 CHAR-TBN-01-042-F-M 2688 CHAR-TBN-01-013-F-M 2465 CHAR-TBN-0 1-028-F-M 2996 CHAR-TBN-0 1-043-F-M 2793 CH-AR-TBN-01-014-F-M 2406 CHAR-TBN-0 1-029-F-M 1809 CHAR-TBN-0 1-044-F-M 2550 C-HAR-TBN-0 1-01 5-F-M 2262 CHAR-TBN-01-030-F-M 1744 CHAR-TBN-0 1-045-F-M 2603 Mean Ambient 1648 Mean Ambient 1525 Mean Ambient 2213 Ct. Mean 2328 Ct. Mean 2590 Ct. Mean 2713 Ct. Median 2321 Ct. Median 2465 Ct. Median 2773 Ct. Std. Dev.

194 Ct. Std. Dev.

548 Ct. Std. Dev.

247 F-M Fixed measurement 2-23 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 4 June 2011 than background. Gamma scans were performed in the general areas as well as locations where cracks and wall-to-floor junctures were present.

No gamma scan indicated greater than background with the exception of the areas on the 3 rd floor that were attributed to the presence of waste boxes awaiting shipment.

Table 2-7 TBN-01 Characterization Data (1st, 2nd & 3rd Floors) f~Ht;in..*.. ::!.. " !!C.-'*:I(~W~Yi&b~JIll~:'

r,l~~ti(ly*'**..... >';i;:,

~Reslllf';*'*'\\'

.,.i.'

e.,

. Result'....**

T

- - (dp'lrijl()()~ni2) Locatiori

'CdpmllOOcIll2j..

1st FLOOR 2nd FLOOR 3rdFLOOR CHAR-TBN-OI-OOI-F-M 2799 CHAR-TBN-OI-016-F-M 2203 CHAR-TBN-OI-031-F-M 2439 CHAR-TBN-OI-002-F-M 2485 CHAR-TBN-OI-017-F-M 2465 CHAR-TBN-OI-032-F-M 2190 CHAR-TBN-OI-003-F-M 2216 CHAR-TBN-OI-OlS-F-M 2996 CHAR-TBN-OI-033-F-M 2530 CHAR-TBN-OI-004-F-M 2334 CHAR-TBN-O 1-0 19-F-M 2806 CHAR-TBN-OI-034-F-M 2773 CHAR-TBN-OI-OOS-F-M 2124 CHAR-TBN-O 1-020-F-M 2196 CHAR-TBN-OI-03S-F-M 2806 CHAR-TBN-OI-006-F-M 2426 CHAR-TBN-OI-021-F-M 2439 CHAR-TBN-OI-036-F-M 2826 CHAR-TBN-OI-007-F-M 2203 CHAR-TBN-OI-022-F-M 2465 CHAR-TBN-OI-037-F-M 2570 CHAR-TBN-OI-OOS-F-M 2288 CHAR-TBN-OI-023-F-M 2583 CHAR-TBN-OI-03S-F-M 2839 CHAR-TBN-OI-009-F-M 2321 CHAR-TBN-OI-024-F-M 2150 CHAR-TBN-OI-039-F-M 3114 CHAR-TBN-O 1-0 1 O-F-M 2268 CHAR-TBN-OI-02S-F-M 3697 CHAR-TBN-OI-040-F-M 3153 CHAR-TBN-OI-OII-F-M 1927 CHAR-TBN-OI-026-F-M 3370 CHAR-TBN-OI-041-F-M 2819 CHAR-TBN-OI-012-F-M 2393 CHAR-TBN-OI-027-F-M 2924 CHAR-TBN-OI-042-F-M 2688 CHAR-TBN-OI-013-F-M 2465 CHAR-TBN-OI-02S-F-M 2996 CHAR-TBN-OI-043-F-M 2793 CHAR-TBN-OI-014-F-M 2406 CHAR-TBN-OI-029-F-M 1809 CHAR-TBN-OI-044-F-M 2550 CHAR-TBN-OI-OlS-F-M 2262 CHAR-TBN-OI-030-F-M 1744 CHAR-TBN-OI-04S-F-M 2603 Mean Ambient 1648 Mean Ambient 1525 Mean Ambient 2213 Ct. Mean 2328 Ct. Mean 2590 Ct. Mean 2713 Ct Median 2321 Ct Median 2465 Ct. Median 2773 Ct. Std. Dey.

194 Ct. Std. Dey.

548 ct. Std. Dey.

247 F-M = Ftxed measurement 2-23

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 Table 2-8 TBN-01 Characterization Data (4th, 5th & 6th Floors)

Result Result

-Result Location

[,dpmI100cm2)

Location (dpn/

m/lOCm2 Location (dp In/O0CM) 4th FLOOR 5th FLOOR 6th FLOOR CHAR-TBN-01 -046-F-M 2649 CHAR-TBN-01-061 -F-M 3081 CHAR-TBN-0 1-076-F-M 3048 CHAR-TBN-01-047-F-M 2419 CHAR-TBN-01-062-F-M 3042 CHAR-TBN-01-077-F-M 2826 CHAR-TBN-01-048-F-M 2819 CHAR-TBN-01-063-F-M 2996 CHAR-TBN-01-078-F-M 2865 CHAR-TBN-01l-049-F-M 2537 CHAR-TBN-01-064-F-M 2865 CHAR-TBN-01-079-F-M 3212

-CHAR-TBN-*0l-050-F-M 2491 CHAR-TBN-0 1-065-F-M 3330 CHAR-TBN-0 1-080-F-M 2773 CHAR-TBN-01-05 1-F-M 2288 CHAR-TBN-0 1-066-F-M 3330 CHAR-TBN-01-081-F-M 2878 CHAR-TBN-01-052-F-M 2419 CHAR-TBN-01-067-F-M 3193 CHAR-TBN-01-082-F-M 2845 CHAR-TBN-01-053-F-M 2360 CHAR-TBN-01-068-F-M, 3068 CHAR-TBN-01 -083-F-M 2963 CHAR-TBN-01-054-F-M 2649 CHAR-TBN-01-069-F-M 2891

'CH-AR-TBN-01-084-F-M 3048 CHAR-TBN-0 1-055-F-M 2563 CHAR-TBN-0 1-070-F-M 3278 CHAkR-TBN-0 1-085-F-M 2930 CHAR-TBN-01-056-F-M 2563 CH{AR-TBN-01-071-F-M 3225 CHAR-TBN-01-086-F-M 3193 CHAR-TBN-01 -05 7-F-M 2262 CHAR-TBN-01-072-F-M 2917 CHAR-TBN-01-087-F-M 3153 CH{AR-TBN-01-058-F-M 2360 CHAR-TBN-01-073-F-M 3081 CHAR-TBN-01-088-F-M 3363 CHAR-TBN-01-059-F-M 2399 CHAR-TBN-0 1-074-F-M 3199 CHAR-TBN-01-089-F-M 2812 CHAR-TBN-01-060-F-M 2393 CHAR-TBN-0 1-075-F-M 2858 CHAR-TBN-01 -090-F-M 3003 Mean Ambient 1766 Mean Ambient 1996 Mean Ambient 1976 Ct. Mean 2478 Ct. Mean 3090 Ct. Mean 2994 Ct. Median 2419 Ct. Median 3081 Ct. Median 2963 Ct. Std. Dev.

152 Ct. Std. Dev.

164 Ct. Std. Dev.

174 F-M =Fixed measurement Fixed-point measurements were slightly above the ambient radiation levels in the building. Based upon the findings of information reviewed, personnel interviews and data acquired during characterization, TBN-0 1 is classified as a Class 3 area. The radwaste storage area on the 3 rd floor and the rollup door area on the I"t floor are classified as Class 1 areas because of the presence of stored radwaste.

2.1.8.5 OFB Office Building The Office Building is located on the west side of the Control Building and is outside the confines of the Controlled Area. This structure housed the offices, conference rooms and dining room for the project. The structure is of reinforced concrete and structural steel design. The outer walls are made of lightweight concrete block and the remainder of corrugated cement asbestos siding backed up by gypsum board and hard board.

2-24 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 4 June 2011 Table 2-8 TBN-Ol Characterization Data (4th, 5th & 6th Floors)

'ioc~ti6n',Ii ;,]~_',."

Result./,::,"C

.,-;: .'.-cc

,'nJ,'",

. Result',

Ldc~~ion '1.. Result

, (dpriili()Oc'1ll2y' L()g~~16ri' ' "

'lr(dprflJi'Olkfu2) ii,',(dpmt100cm2) 4th FLOOR 5th FLOOR 6th FLOOR CHAR-TBN-OI-046-F-M CHAR-TBN-OI-047-F-M CHAR-TBN-O 1-048-F-M CHAR-TBN-O 1-049-F-M CHAR-TBN~Ol-050-F-M CHAR-TBN-OI-051-F-M CHAR-TBN-O 1-OS2-F-M CHAR-TBN-O 1-053-F-M CHAR-TBN-OI-054-F-M CHAR-TBN-O 1-055-F-M CHAR-TBN-OI-056-F-M CHAR-TBN-OI-057-F-M CHAR-TBN-OI-058-F-M CHAR-TBN-OI-059-F-M CHAR-TBN-OI-060-F-M Mean Ambient Ct. Mean Ct. Median Ct. Std. Dev.

F-M = Fixed measurement 2649 CHAR-TBN-OI-061-F-M 3081 CHAR-TBN-OI-076-F-M 3048 2419 CHAR-TBN-O 1-062-F-M 3042 CHAR-TBN-OI-077-F-M 2826 2819 CHAR-TBN-O 1-063-F-M 2996 CHAR-TBN-OI-078-F-M 2865 2537 CHAR-TBN-OI-064-F-M 2865 CHAR-TBN-OI-079-F-M 3212 2491 CHAR-TBN-OI-065-F-M 3330 CHAR-TBN-OI-080-F-M 2773 2288 CHAR-TBN-OI-066-F-M 3330 CHAR-TBN-OI-081-F-M 2878 2419 CHAR-TBN-OI-067-F-M 3193 CHAR-TBN-O 1-082-F-M 2845 2360 CHAR-TBN-O 1-068-F-M.

3068 CHAR-TBN-OI-083-F-M 2963 2649 CHAR-TBN-OI-069-F-M 2891

. CHAR-TBN-O 1-084-F-M 3048 2563 CHAR-TBN-OI-070-F-M 3278 CHAR-TBN-OI-085-F-M 2930 2563 CHAR-TBN-OI-071-F-M 3225 CHAR-TBN-OI-086-F-M 3193 2262 CHAR-TBN-O l-072-F-M 2917 CHAR-TBN-OI-087-F-M 3153 2360 CHAR-TBN-O l-073-F-M 3081 CHAR-TBN-OI-088-F-M 3363 2399 CHAR-TBN-OI-074-F-M 3199 CHAR-TBN-OI-089-F-M 2812 2393 CHAR-TBN-OI-07S-F-M 2858 CHAR-TBN-OI-090-F-M 3003 1766 Mean Ambient 1996 Mean Ambient 1976 2478 ct. Mean 3090 Ct. Mean 2994 2419 Ct. Median 3081 Ct. Median 2963 152 Ct. Std. Dev.

164 Ct. Std. Dev.

174 Fixed-point measurements were slightly above the ambient radiation

'\\

levels in the building. Based upon the findings of information reviewed, personnel interviews and data acquired during characterization, TBN-01 is classified as a Class 3 area. The radwaste storage area on the 3rd floor and the rollup door area on the 1 st floor are classified as Class 1 areas because of the presence of stored radwaste.

2.1.8.5 OFB-Ol - Office Building The Office Building is located on the west side of the Control Building and is outside the confines of the Controlled Area. This structure housed the offices, conference rooms and dining room for the project. The structure is of reinforced concrete and structural steel design. The outer walls are made of lightweight concrete block and the remainder of corrugated cement asbestos siding backed up by gypsum board and hard board.

2-24

Fermi 1 License Termination Plan Revision 0 Chapter 2 Site Characterization May 2009 Characterization data from past surveys proved insufficient for FSS planning activities. A Characterization effort was implemented on October 28, 2008 to include smears, scans and fixed-point measurements in OFB-01. This characterization was performed to the rigors of FSS so the data could be utilized for survey area release if the result supported the release. An ambient measurement was achieved by taking shielded readings at five locations on each floor and five locations on the roof; and the Mean of those data was calculated. Tables 2-9 and 2-10 represent the results of the fixed-point readings taken on the floors, walls and ceiling during this survey effort. Smears were taken at each fixed-point location.

Smear results indicated no smear result greater than MDA. One-square meter beta scans were taken at each fixed-point location. No beta scan indicated results greater than background. Gamma scans were taken in the general areas as well as locations where cracks and wall-to-floor junctures were present. No gamma scan indicated results greater than background.

2-25 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 0 May 2009 Characterization data from past surveys proved insufficient for FSS planning activities. A Characterization effort was implemented on October 28,2008 to include smears, scans and fixed-point measurements in OFB-01. This characterization was performed to the rigors ofFSS so the data could be utilized for survey area release if the result supported the release. An ambient measurement was achieved by taking shielded readings at five locations on each floor and five locations on the roof; and the Mean of those data was calculated. Tables 2-9 and 2-10 represent the results of the fixed-point readings taken on the floors, walls and ceiling during this survey effort. Smears were taken at each fixed-point location.

Smear results indicated no smear result greater than MDA. One-square meter beta scans were taken at each fixed-point location. No beta scan indicated results greater than background. Gamma scans were taken in the general areas as well as locations where cracks and wall-to-floor junctures were present. No gamma scan indicated results greater than background.

2-25

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 Table 2-9 OFB-01 Characterization Data Result Result Lucation j

dpru/100em')

Location (dPH/1OOcU12 Ist FLOOR 1 st FLOOR (Cont'd)

CHAR-OFB-01 -003 -F-M 1211 CHAR-OFB-01-032-F-M 1656 CHAR-OFB-01-004-F-M 1316 CHAR-OFB-01-033-F-M 2972 CHAR-OFB-Of -005 -F-M 1892.

CHAR-OFB-01-034-F-M 1826 CHAR-OFB-01-006-F-M 1211 CHAR-OFB-01-035-F-M 1708 CHAR-OFB-01-007-F-M 1578 CHAR-OFB-01-036-F-M 1558 CHAR-OFB-01-008-F-M 1519 CHAR-OFB-01-037-F-M 1623 CH{AR-OFB-01-009-F-M 1466 CHAR-OFB-01-038-F-M 2232 CHAR-OFB-01-010-F-M 1362 CHAR-OFB-01-039-F-M 1538 CHAR-OFB-01 -01 1-F-M 1735 CHAR-OFB-01-040-F-M 1630 CH{AR-OFB-0 1-012-F-M 1532 CHAR-OFB-01-041-F-M 1951 CH{AR-OFB-0 1-013-F-M 1512 CHAR-OFB-01-042-F-M 1434 CHAR-OFB-0 1-014-F-M 2612 CHAR-OFB-01-043-F-M 3129 CHAR-OFB-01-015-F-M 1303 CHAR-OFB-01-044-F-M 1839 CH{AR-OFB-0 1-016-F-M 2232 CHAR-OFB-01l-045-F-M 1375 CH-AR-OFB-01-017-F-M 1636 CHAR-OFB-01-046-F-M 2010 CHAR-OFB-01-018-F-M 1918 CHAR-OFB-01-047-F-M 1244 CHAR-OFB-01-019-F-M 1918 CHAR-OFB-01-048-F-M 1257 CHAR-OFB-01-020-F-M 1460 CHAR-OFB-01-049-F-M 1617 CHAR-OFB-01-021-F-M 2736 CHAR-OFB-01-050-F-M 1571 CH{AR-OFB-01-022-F-M 3037 CHAR-OFB-01-051-17-M 1525 CHAR-OFB-0 1-023-F-M 2121 CHAR-OFB-01-052-F-M 1892 CHAR-OFB-01-024-F-M 2396 CHAR-OFB-01-053-F-M 2121 CHAR-OFB-0 1-025-F-M 3090 CHAR-OFB-01-054-F-M 1669 CHAR-OFB-0 1-026-F-M 1852 CHAR-OFB-01-055-F-M 1722 CHAR-OFB-01-027-F-M 2494 CHAR-OFB-01-056-F-M 1708 CHAR-OFB-01-028-F-M 2088 CHAR-OFB-01-057-F-M 1682 CHAR-OFB-01-029-F-M 1676 CHAR-OFB-01-058-F-M 1434 CHAR-OFB-01-030-F-M 1283 CHAR-OFB-01-059-F-M 1532 CHAR-OFB-01-03 1-F-M 1257 CH{AR-OFB-01-060-F-M 1918

__________Mean Ambient 1664

_________Ct.

Mean 1807

_________Ct.

Median 1672

_________Ct._Std._Dev.

487 F-M Fixed measurement 2-26 Fermi 1 License Termination Plan Chapter 2 Site Characterization Table 2-9 OFB-Ol Characterization Data

~;:!lf~.ii ***Result\\.'.,.. '....

T.o,,~tln

'.J.*........* (d'pniJioOcII6

)~~tin:~::l't Result iy.~, inn

~,-->*i;....

(dpill!IOO~n8 1st FLOOR 1st FLOOR (Cont'd)

CHAR-OFB-O l-003-F-M 1211 CHAR-OFB-OI-032-F-M 1656 CHAR-OFB-OI-OO4-F-M 1316 CHAR-OFB-OI-033-F-M 2972 CHAR-OFB-OI-OO5-F-M 1892 CHAR-OFB-OI-034-F-M.

1826 CHAR-OFB-OI-OO6-F-M 1211 CHAR-OFB-OI-035-F-M 1708 CHAR-OFB-OI-OO7-F-M 1578 CHAR-OFB-OI-036-F-M 1558 CHAR-OFB-OI-OOS-F-M 1519 CHAR-OFB-OI-037-F-M 1623 CHAR-OFB-OI-OO9-F-M 1466 CHAR-OFB-O 1-03S-F-M 2232 CHAR-OFB-OI-OIO-F-M 1362 CHAR-OFB-O 1-039-F-M 1538 CHAR-OFB-OI-Oll-F-M 1735 CHAR-OFB-OI-040-F-M 1630 CHAR-OFB-OI-012-F-M 1532 CHAR-OFB-OI-041-F-M 1951 CHAR-OFB-OI-013-F-M 1512 CHAR-OFB-OI-042-F-M 1434 CHAR-OFB-OI-014-F-M 2612 CHAR-OFB-OI-043-F-M 3129 CHAR-OFB-OI-015-F-M 1303 CHAR-OFB-OI-044-F-M 1839 CHAR-OFB-OI-016-F-M 2232 CHAR-OFB-O 1-045-F-M 1375 CHAR-OFB-OI-017-F-M 1636 CHAR-OFB-OI-046-F-M 2010 CHAR-OFB-OI-OlS-F-M 1918 CHAR-OFB-OI-047-F-M 1244 CHAR-OFB-OI-019-F-M 1918 CHAR-OFB-OI-04S-F-M 1257 CHAR-OFB-OI-020-F-M 1460 CHAR-OFB-OI-049-F-M 1617 CHAR-OFB-OI-021-F-M 2736 CHAR-OFB-OI-050-F-M 1571 CHAR-OFB-OI-022-F-M 3037 CHAR-OFB-OI-OSI-F-M 1525 CHAR-OFB-O 1-023-F-M 2121 CHAR-OFB-OI-052-F-M 1892 CHAR-OFB-OI-024-F-M 2396 CHAR-OFB-OI-053-F-M 2121 CHAR-OFB-O 1-025-F-M 3090 CHAR-OFB-OI-054-F-M 1669 CHAR-OFB-O 1-026-F-M 1852 CHAR-OFB-OI-055-F-M 1722 CHAR-OFB-O 1-027-F-M 2494 CHAR-OFB-OI-056-F-M 1708 CHAR-OFB-O 1-02S-F-M 2088 CHAR-OFB-OI-057-F-M 1682 CHAR-OFB-OI-029-F-M 1676 CHAR-OFB-OI-05S-F-M 1434 CHAR-OFB-O 1-030-F-M 1283 CHAR-OFB-OI-059-F-M 1532 CHAR-OFB-OI-031-F-M 1257 CHAR-OFB-OI-060-F-M 1918 Mean Ambient 1664 Ct. Mean 1807 ct. Median 1672 Ct. Std. Dev.

487 F-M Fixed measurement 2-26 Revision 4 June 2011

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 Table 2-10 OFB-01 Characterization Data ResultResult Result Location dIlOm)

Location (dp M/1OC1m12 Location d IlOcj 2nd FLOOR 2nd FLOOR (Cont'd)

ROOF CHAR-OFB-0 1-001-F-M 1957 CHAR-OFB-0 1-01 8-F-M 2710 CHAR-OFB-01I-001-F-M 2291 CHAR-OFB-01-002-F-M 2252 CHAR-OPB-01-019-F-M 2036 CHAR-OFB-01-002-F-M 2690 CHAR-OFB-01-003-F-M 1689 CHAR-OFB-01-020-F-M 1970 CHAR-OFB-01-003-F-M 2749 CHAR-OFB-01-004-F-M 1447 CHAR-OFB-01-021-F-M_

1551 CHAR-OFB-01-004-F-M 2337 CHAR-OFB-01-005-F-M 2075 CHAR-OFB-01-022-F-M 1767 CHAR-OFB-01-005-F-M 3063 CHAR-OFB-01-006-F-M 2010 CHAR-OFB-01-023-F-M 1767 CHAR-OFB-01-006-F-M 3581 CHAR-OFB-01-007-F-M 2350 CHAR-OFB-01-024-F-M 1708 CHAR-OFB-0 1-007-F-M 3031 CHAR-OFB-01-008-F-M 1892 CHAR-OFB-01-025-F-M 1270 CHAR-OFB-01-008-F-M 2782 CHAR-OFB-01-009-F-M 2265 CHAR-OFB-01-026-F-M 1905 CHAR-OFB-01-009-F-M 3116 CHAR-OFB-01-010-F-M 1492 CHAR-OFB-0 1-027-F-M 2494 CHAR-OFB-01-010-F-M 2926 CHAR-OFB-01-01 1-F-M 1623 CHAR-OFB-0 1-028-F-M 1826 CHAR-OFB-01-012-F-M 1656 CHAR-OFB-01-029-F-M 1879 CHAR-OFB-01-013-F-M 2612 CHAR-OFB-01-030-F-M 1578 CHAR-OFB-01-014-F-M 2180 CHAR-OFB-01-03 1-F-M 1872 CHAR-OFB-01 -015-F-M 2219 CHAR-OFB-0 1-032-F-M 1794 CHAR-OFB-01-016-F-M 1708 CHAR-OFB-01-033-F-M 2527 CHAR-OFB-01-017-F-M 1761 Mean Ambient 2129 Mean Ambient 2413 Ct. Mean 1935 Ct. Mean 2857 Ct. Median 1879 Ct. Median 2854

_______________________Ct. Std. Dev.

349 Ct. Std. Dev.

381 F-M Fixed measurement Fixed-point measurements were at, slightly below or slightly above the ambient radiation levels in the office building.

Based upon the findings of information reviewed, personnel interviews and of data acquired during characterization, OFB-O01 is classified as a Class 3 area. Based upon the result of the Data Quality Assessment (DQA) this characterization may be used as part of the FSS for this survey area.

2.1.8.6 NOL Open Land Area Inside the Controlled Area Survey Area NOL-0OI consists of the open land area inside the EFF1 Controlled Area. Survey area NOL-0l contains about 2392 square meters of surface area made up of soils, asphalt, gravel and concrete.

NOL-0O1 is bounded by the Controlled Area fence and OOL-0OI on the north and west and a portion of the eastern boundary. FRB-0Ol forms a 2-27 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 4 June 2011 Table 2-10 OFB-01 Characterization Data

......Result.

'a'~ati'Jrid' ResuU.'..

n[~

'..'

Result..*.* '

Location

(dIlIDIIOOcm 2

)

(dpmliOOcn?). Locati()n

"(dpfu/l00tm1) 2nd FLOOR 2nd FLOOR (Cont'd)

ROOF CHAR-OFB-Ol-OOI-F-M CHAR-OFB-OI-OO2-F-M CHAR-OFB-OI-OO3-F-M CHAR-OFB-OI-OO4-F-M CHAR-OFB-OI-OOS-F-M CHAR-OFB-OI-OO6-F-M CHAR-OFB-OI-OO7-F-M CHAR-OFB-OI-OOS-F-M CHAR-OFB-OI-OO9-F-M CHAR-OFB-OI-OIO-F-M CHAR-OFB-OI-Oll-F-M CHAR-OFB-OI-012-F-M CHAR-OFB-O 1-0 13-F-M CHAR-OFB-OI-014-F-M CHAR-OFB-OI-OIS-F-M CHAR-OFB-OI-016-F-M CHAR-OFB-OI-017-F-M F-M = Fixed measurement 1957 CHAR-OFB-OI-OlS-F-M 2710 CHAR-OFB-OI-OOI-F-M 2291 2252 CHAR-OFB-OI-019-F-M 2036 CHAR-OFB-OI-OO2-F-M 2690 1689 CHAR-OFB-O 1-020-F-M 1970 CHAR-OFB-OI-OO3-F-M 2749 1447 CHAR-OFB-OI-021-F-M 1551 CHAR-OFB-OI-OO4-F-M 2337 2075 CHAR-OFB-OI-022-F-M 1767 CHAR-OFB-OI-OOS-F-M 3063 2010 CHAR-OFB-OI-023-F-M 1767 CHAR-OFB-OI-OO6-F-M 3581 2350 CHAR -OFB-O 1-024-F-M 1708 CHAR-OFB-OI-OO7-F-M 3031 1892 CHAR-OFB-O 1-02S-F-M 1270 CHAR-OFB-OI-OOS-F-M 2782 2265 CHAR-OFB-OI-026-F-M' 1905 CHAR-OFB-O 1-OO9-F-M 3116 1492 CHAR-OFB-O 1-027-F-M 2494 CHAR-OFB-OI-OIO-F-M 2926 1623 CHAR-OFB-OI-02S-F-M 1826 1656 CHAR-OFB-OI-029-F-M 1879 2612 CHAR-OFB-OI-030-F-M 1578 2180 CHAR-OFB-OI-031-F-M 1872 2219 CHAR-OFB-O 1-032-F-M 1794 1708 CHAR-OFB-OI-033-F-M 2527 1761 Mean Ambient 2129 Mean Ambient 2413 Ct. Mean 1935 Ct. Mean 2857 Ct. Median 1879 Ct. Median 2854 Ct. Std. Dev.

349 Ct. Std. Dev.

381 Fixed-point measurements were at, slightly below or slightly above the ambient radiation levels in the office building.

Based upon the findings of information reviewed, personnel interviews and of data acquired during characterization, OFB-Ol is classified as a Class 3 area. Based upon the result of the Data Quality Assessment (DQA) this characterization may be used as part ofthe FSS for this survey area.

2.1.8.6 NOL-Ol-Open Land Area Inside the Controlled Area Survey Area NOL-Ol consists of the open land area inside the EFl Controlled Area. Survey area NOL-Ol contains about 2392 square meters of surface area made up of soils, asphalt, gravel and concrete.

NOL-Ol is bounded by the Controlled Area fence and OOL-Ol on the north and west and a portion ofthe eastern boundary. FRB-O 1 forms a 2-27

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 portion of the eastern boundary and NAB-01, IGB-01 form a portion of the western boundary. NOL-01 lies entirely within the open land Class 3 survey area OOL-01. Survey Area NOL-01 is designated a Class 2 area acting as a buffer between the Class 1 and Class 3 areas.

Subsurface systems that traverse or connect within NOL-01 include:

Health Physics/Chemistry Building drain system

Underground vent ducts

Waste gas lines

Sump pump system Survey area NOL-01 represents the secondary travel path for personnel and equipment entering and leaving EF1. NOL-01 included the primary travel path for personnel and equipment until approximately 10 years ago when the existing path was created. Systems present in survey area NOL-01 that may contain residual radioactivity are the Health Physics/Chemistry Building waste discharge, vent lines, gas lines and the FARB liquid discharge line. Contamination of survey area NOL-01 may have resulted from traffic of contaminated personnel, equipment and material.

Events and activities that may have contaminated survey area NOL-01 include:

Leak in Waste Gas drain line (8/01/67).

o Leak in Waste Gas discharge line (4/30/68).

Fire in the Reactor Building Basement (5/20/08).

Characterization data from past surveys proved insufficient for FSS planning activities. Few soil samples had been taken in this survey area and no samples were analyzed for HTD radionuclides.

Characterization plan EF1-CHAR-NOL-01 was implemented on June 25, 2008. Seventeen samples were collected with two split samples sent to an off-site lab to be analyzed for HTD radionuclides. Table 2-11 represents the sample results for NOL-01. Because of ambient levels associated with the operation of Fermi 2, gamma scans were not performed in survey area NOL-01 at the time of the characterization survey.

2-28 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 4 June 2011 portion of the eastern boundary and NAB-Ol, IGB-Ol form a portion of the western boundary. NOL-Ollies entirely within the open land Class 3 survey area OOL-Ol. Survey Area NOL-Ol is designated a Class 2 area acting as a buffer between the Class 1 and Class 3 areas.

Subsurface systems that traverse or connect within NOL-Ol include:

It Health Physics/Chemistry Building drain system It Underground vent ducts It Waste gas lines

" Sump pump system Survey area NOL-Ol represents the secondary travel path for personnel and equipment entering and leaving EFl. NOL-Ol included the primary travel path for personnel and equipment until approximately 10 years ago when the existing path was created. Systems present in survey area NOL-Ol that may contain residual radioactivity are the Health Physics/Chemistry Building waste discharge, vent lines, gas lines and the FARB liquid discharge line. Contamination of survey area NOL-Ol may have resulted from traffic of contaminated personnel, equipment and material.

Events and activities that may have contaminated survey area NOL-Ol include:

Leak in Waste Gas drain line (8/01/67).

It Leak in Waste Gas discharge line (4/30/68).

Fire in the Reactor Building Basement (5/20/08).

Characterization data from past surveys proved insufficient for FSS planning activities. Few soil samples had been taken in this survey area and no samples were analyzed for HTD radionuclides.

Characterization plan EFI-CHAR-NOL-Ol was implemented on June 25, 2008. Seventeen samples were collected with two split samples sent to an off-site lab to be analyzed for HTD radionuclides. Table 2-11 represents the sample results for NOL-O 1. Because of ambient levels associated with the operation of Fermi 2, gamma scans were not performed in survey area NOL-Ol at the time ofthe characterization survey.

2-28

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 HTD radionuclides with the focus on Co-60, Cs-137, Sr-90 and H-3.

Additional characterization was performed in September through October of 2008 to include smears, scans and fixed-point measurements on the operating floor (590' elevation) of RXB-01. An ambient correction was achieved by taking shielded readings at five locations around the inner annulus and operating floor (on the floor and up to 6 feet on the walls) and the Mean of those data was calculated. Table 2-12 provides a summary of the survey results for the fixed-point readings taken on the floors and walls during this survey effort. Smears were taken at each fixed-point location. Smears indicated no smear result greater than MDA. One-square meter beta scans were performed at each fixed-point location. No beta scan indicated greater than background.

Gamma scans were performed in the general areas as well as locations where cracks and wall-to-floor junctures were present. No gamma scan indicated results greater. than background.

Table 2-12 RY-B-01-01 Characterization Data Result RTesMult Result Location (dpm/lOOcm 2)

Location I dpm/100cmn)

Location (dprn/100cm'_

590' FLOOR 590' <6' WALLS 590' >6' WALLS CHAR-RXB-01-01-001-F-M 2163 CHAR-RXB-01-01-01 1-F-M 1259 CHAR-RXB-01-01-021-F-M 1200 CHAR-R,XB-01-01-002-F-M 2098 CHAR-RXB-01-01-012-F-M 1156 CHAR-RXB-01-01-022-F-M 1600 CHAR-RXB-01-01-003-F-M 7237 CH{AR-RXB-01-01-0 13-F-M 1207 CHAR-RXB-01-01-023-F-M 1403 CHAR-RXB-01-01-004-F-M 2285 CHAR-RXB-01-01-0 14-F-M 1194 CHAR-RXB-01-01-024-F-M 1305 CHAR-RXB-01-01-005-F-M 1821 CHAR-RXB-01-01-015-F-M 1369 CHAR-RXB-01-01-025-F-M 1265 CHAR-RXB-01 006-F-M 3151 CHAR-RXB-01-01-016-F-M 1311 CHAR-RXB-01-01 -026-F-M 1527 CHAR-RXB-01-01 -007-F-M 2544 CHAR-RXB-01-01-017-F-M 1291 CHAR-RXB-01-01-027-F-M 1718 CHAR-RX,B-01 008-F-M 2460 CHAR-RXB-01-01-018-F-M 1091 CHAR-RXB-01-01-028-F-M 1514 CHAR-RYXB-01-01-009-F-M 2214 CHAR-RXB-01-01-019-F-M 1149 CHAR-RXB-01-01-029-F-M 1554 CHAR-RXB-01-01-010-F-M 2402 CHAR-RXB-01 020-F-M 1394 CHAR-RXB-01-01~-030-F-M 1560

___________CHAR-RXB-01-01-031-F-M 1318

__________CHAR-RXB-01-01-032-F-M 1475 CHAR-RXB-01-01-033-F-M 1390 CHAR-RXB-01-01-034-F-M 1580 CHAR-RXB-01-01-035-F-M 1737 Mean Ambient 1814 Mean Ambient 1814 Mean Ambient 1767 Ct. Mean 2837 Ct. Mean 1242 Ct. Mean 1476 Ct. Median 2344 Ct. Median 1233 Ct. Median 1514 Ct. Std. Dev.

1585 Ct. Std. Dev.

99 Ct, Std. Dev.

160 F-M =Fixed measurement Characterization plan EF 1-CH-JAR-RXB-0O1-02 was implemented on October 20, 2008 to survey the reactor building 552' elevation annulus, Table 2-13 provides a summary of the survey results for the fixed-point readings taken on the floors and walls during this survey effort. Smears were taken at each fixed-point location. Smears indicated no smear result greater than MDA. One-square meter beta scans were performed 2-31 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 4 June 2011 Location...,. " *.,.,....

590' FLOOR CHAR-RXB-OI-OI-OOI-F-M CHAR-RXB-OI-OI-OO2-F-M CHAR-RXB-OI-OI-OO3-F-M CHAR-RXB-OI-OI-OO4-F-M CHAR-RXB-OI-OI-OOS-F-M CHAR-RXB-OI-OI-OO6-F-M CHAR-RXB-OI-OI-OO7-F-M CHAR-RXB-OI-OI-OO8-F-M CHAR-RXB-OI-OI-OO9-F-M CHAR-RXB-OI-OI-OlO-F-M Mean Ambient Ct. Mean Ct. Median Ct. Std. Dev.

F-M = Fixed measurement BTD radionuclides with the focus on Co-60, Cs-137, Sr-90 and B-3.

Additional characterization was perfonned in September through October of 2008 to include smears, scans and fixed-point measurements on the operating floor (590' elevation) ofRXB-Ol. An ambient correction was achieved by taking shielded readings at five locations around the inner annulus and operating floor (on the floor and up to 6 feet on the walls) and the Mean of those data was calculated. Table 2-12 provides a summary of the survey results for the fixed-point readings taken on the floors and walls during this survey effort. Smears were taken at each fixed-point location. Smears indicated no smear result greater than MDA. One-square meter beta scans were perfonned at each fixed-point location. No beta scan indicated greater than background.

Gamma scans were perfonned in the general areas as well as locations where cracks and wall-to-floor junctures were present. No gamma scan indicated results greater than background.

Table 2-12 RXB-01-01 Characterization Data Result..

I....,,<

Result Result (dpm/lOOcm2) I'Location

.. (dpllihOOcm2)

Location

( dpm/lOOcm2) 590' <6' WALLS 590' >6' WALLS 2163 CHAR-RXB-OI-OI-OII-F-M 1259 CHAR-RXB-OI-OI-021-F-M 1200 2098 CHAR-RXB-OI-OI-012-F-M 1156 CHAR-RXB-OI-OI-022-F-M 1600 7237 CHAR-RXB-OI-OI-013-F-M 1207 CHAR-RXB-OI-OI-023-F-M 1403 2285 CHAR-RXB-OI-OI-014-F-M 1194 CHAR-RXB-OI-OI-024-F-M 1305 1821 CHAR-RXB-OI-OI-OlS-F-M 1369 CHAR-RXB-OI-OI-02S-F-M 1265 3151 CHAR-RXB-OI-OI-016-F-M 1311 CHAR-RXB-OI-OI-026-F-M 1527 2544 CHAR-RXB-OI-OI-017-F-M 1291 CHAR-RXB-OI-OI-027-F-M 1718 2460 CHAR-RXB-OI-O 1-0 1 S-F-M 1091 CHAR-RXB-OI-OI-02S-F-M 1514 2214 CHAR-RXB-OI-OI-019-F-M 1149 CHAR-RXB-OI-OI-029-F-M 1554 2402 CHAR-RXB-OI-OI-020-F-M 1394 CHAR-RXB-OI-OI-030-F-M 1560 CHAR-RXB-OI-OI-031-F-M 1318 CHAR-RXB-OI-OI-032-F-M 1475 CHAR-RXB-OI-OI-033-F-M 1390 CHAR-RXB-OI-OI-034-F-M 1580 CHAR-RXB-OI-OI-03S-F-M 1737 1814 Mean Ambient 1814 Mean Ambient 1767 2837 Ct. Mean 1242 Ct. Mean 1476 2344 Ct. Median 1233 Ct. Median 1514 1585 Ct. Std. Dev.

99 ct. Std. Dev.

160 Characterization plan EF1-CHAR-RXB-01-02 was implemented on October 20, 2008 to survey the reactor building 552' elevation annulus.

Table 2-13 provides a summary of the survey results for the fixed-point readings taken on the floors and walls during this survey effort. Smears were taken at each fixed-point location. Smears indicated no smear result greater than MDA. One-square meter beta scans were perfonned 2-31

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 at each fixed-point location. No beta scan indicated greater than background. Gamma scans were performed in the general areas as well as locations where cracks and wall-to-floor junctures were present. No gamma scan indicated results greater than background.

Table 2-13 RXB-01-02 Characterization Data Result Location (dpim/100cmrn)

ANNULUS CHAR-RXB-01-02-001-F-M 2098 CHAR-RXB-01-02-002-F-M 846 CHAR-RXB-01-02-003-F-M 2163 CHAR-RXB-01-02-004-F-M 983 CHAR-RXB-01-02-005-F-M 2727 CHAR-RXB-01-02-006-F-M 2622 CHAR-RXB-01-02-007-F-M 2432 CHAR-RXB-01-02-008-F-M 2353 CHAR-RXB-01-02-009-F-M 1121 CHAR-RXB-01-02-010-F-M 1842 CHAR-RXB-01-02-011-F-M 1311 CHAR-RXB-01-02-012-F-M 1101 CHAR-RXB-01-02-013-F-M 1724 CHAR-RXB-01-02-014-F-M 1010 CHAR-RXB-01-02-015-F-M 1731 Mean Ambient 1042 Ct. Mean 1738 Ct. Median 1731 Ct. Std. Dev.

644 F-M = Fixed measurement Fixed-point measurements were at, slightly above or below the ambient radiation levels in the floor areas and walls to a height of 6 feet on the 590' elevation, however, since considerable decommissioning work has yet to be completed-(reactor vessel removal) the basement, floor and walls up to a height of 6' on the 590' elevation remain Class 1 areas.

The fixed-point readings on the walls 6' and above on the 590' elevation were at approximately ambient levels and therefore are classified as Class 2 areas. Characterization survey performed in the reactor annulus provided data at approximately ambient levels. Therefore, the results show the annulus was minimally impacted during operations and decommissioning activities. The reactor building 552' annulus is classified as a Class 3 area.

2.1.8.8 FRB Fuel and Repair Building (FARB) 2-32 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 4 June 2011 at each fixed-point location. No beta scan indicated greater than background. Gamma scans were performed in the general areas as well as locations where cracks and wall-to-floor junctures were present. No gamma scan indicated results greater than background.

Table 2-13 RXB-01-02 Characterization Data 12T'*I':~;i"t::::!:lili:;~~E'.':: h~e~ult*..*.*.*. <..

..'" *...'(dphili OOcm2).

ANNULUS CHAR -RXB-O 1-02-00 1-F-M 2098 CHAR -RXB-O 1-02-002-F-M 846 CHAR-RXB-01-02-003-F-M 2163 CHAR-RXB-01-02-004-F-M 983 CHAR-RXB-01-02-005-F-M 2727 CHAR-RXB-O 1-02-006-F-M 2622 CHAR-RXB-01-02-007-F-M 2432 CHAR -RXB-O 1-02-008-F-M 2353 CHAR-RXB-O 1-02-009-F-M 1121 CHAR-RXB-01-02-010-F-M 1842 CHAR-RXB-01-02-011-F-M 1311 CHAR-RXB-O 1-02-0 12-F-M 1101 CHAR-RXB-01-02-013-F-M 1724 CHAR-RXB-O 1-02-0 14-F-M 1010 CHAR-RXB-01-02-015-F-M 1731 Mean Ambient 1042 Ct. Mean 1738 Ct. Median 1731 Ct. Std. Dev.

644 F-M = Fixed measurement Fixed-point measurements were at, slightly above or below the ambient radiation levels in the floor areas and walls to a height of 6 feet on the 590' elevation, however, since considerable decommissioning work has yet to be completecL(reactor vessel removal) the basement, floor and walls up to a height of 6' on the 590' elevation remain Class 1 areas.

The fixed-point readings on the walls 6' and above on the 590' elevation were at approximately ambient levels and therefore are classified as Class 2 areas. Characterization survey performed in the reactor annulus provided data at approximately ambient levels. Therefore, the results show the annulus was minimally impacted during operations and decommissioning activities. The reactor building 552' annulus is classified as a Class 3 area.

2.1.8.8 FRB-Ol-Fuel and Repair Building (FARB) 2-32

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 Table 2-14 FRB3-01 Characterization Data Reslt

-Residt Locationi (d Pm/IOOCUm2 Locationi (dpw/100ei)

MAINTENANCE PIT 590' <6' FLOORS AND WALLS CHAR-FRB-01-00 1-F-M 2169 CHAR-FRB-01-016-F-M 4458 CHAR-FRB-01-002-F-M 9038 CHAR-FRB-01-017-F-M 3711

-CHAR-FRB-01-003-F-M 2118 CHAR-FRB-01-018-F-M 4904 CHAR-FRB-01 -004-F-M 3357 CHAR-FRB-01-019-F-M 2583 CHAR-FRB-01-005-F-M 2137 CHAR-FRB-01 -020-F-M 3081 CHAR-FRB-01-006-F-M 3906 CHAR-FRB-01-021-F-M 2747 CHAR-FRB-01-007-F-M 2182 CHAR-FRB-01-022-F-M 3901 CHAR-FRB-01-008-F-M 3506 CHAR-FRB-01-023-F-M 2845 CH-AR-FRB-01-009-F-M 2260 CHAR-FRB-01 -024-F-M 2871 CHAR-FRB-01-010-F-M 2750 CHAR-FRB-01-025-F-M 2655 CHAR-FRB-01-01 1-F-M 1930 CHAR-FRB-01 -026-F-M 2176 CHAR-FRB-01-012-F-M 2569 CHAR-FRB-01-027-F-M 3081 CHAR-FRB-01-013-F-M 1976 CHAR-FRB-01-028-F-M 2406 CHAR-FRB-01-014-F-M 2473 CH-AR-FRB-01 -029-F-M 3219 CHAR-FRB-01-015-F-M 1846 CHAR-FRB-01-030-F-M 8713 Mean Ambient 1246 Mean Ambient 3443 Ct. Mean 2948 Ct. Mean 3557 Ct. Median 2260 Ct. Median 3081 Ct. Std. Dev.

1795 Ct. Std. Dev.

1616 MEZZANINE 590' >6' WALLS CHAR-FRB-01-03 1-F-M 3912 CHAR-FRB-01-046-F-M 2557 CH{AR-FRB-01-032-F-M 4545 CHAR-FRB-01-047-F-M 2616 CHAR-FRB-01-033-F-M 5171 CHAR-FRB-01-048-F-M 3625 CHAR-FRB-01-034-F-M 4132 CHAR-FRB-01-049-F-M 3186 CHAR-FRB-01-035-F-M 3874 CHAR-FRB-01-050-F-M 2773 CHAR-FRB-01-036-F-M 2931 CHAR-FRB-01-05 1-F-M 2753 CHAR-FRB-01-037-F-M 3719 CHAR-FRB-01-052-F-M 4943 CHAR-FRB-01-038-F-M 3958 CHAR-FRB-01-053-F-M 4268 CHAR-FRB-0t-039-F-M 6082 CHAR-FRB-01-054-F-M 8116 CHAR-FRB-01-040-F-M 3757 CHAR-FRB-01-055-F-M 5546 CHAR-FRB-01 -041-F-M 5952 CHAR-FRB-01 -056-F-M 2163 CHAR-FRB-01-042-F-M 10420 CHAR-FRB-01l-057-F-M 2596 CHAR-FRB-01-043-F-M 6178 CHAR-FRB-01-058-F-M 3193 CHAR-FRB-01-044-F-M 4506 CHAR-FRB-01-059-F-M 2393 CHAR-FRB-01 -045-F-M 3583 CHAR-FRB-0 1-060-F-M 2445 Mean Ambient 3769 Mean Ambient 3443 Ct. Mean 4848 Ct. Mean 3545 Ct. Median 4132 Ct. Median 2773 Ct. Std. Dev.

1827 Ct. Std. Dev.

1605 F-M =Fixed measurement 2-35 Fermi 1 License Termination Plan Chapter 2 Site Characterization Table 2-14 FRB-01 Characterization Data Result

....,/.'

llesulf ~.i'c...* ~~.

Location

( dpm/lOOcn?Y:?; L()cation.... :..**..*.*...

(dpmilOOcm2)

MAINTENANCE PIT 590' <6' FLOORS AND WALLS CHAR-FRB-OI-OOI-F-M 2169 CHAR-FRB-OI-016-F-M 4458 CHAR-FRB-OI-OO2-F-M 9038 CHAR-FRB-OI-017-F-M 3711 CHAR-FRB-O 1-003-F-M 2118 CHAR-FRB-OI-OlS-F-M 4904 CHAR-FRB-OI-004-F-M 3357 CHAR-FRB-O 1-0 1 9-F-M 2583 CHAR-FRB-OI-OO5-F-M 2137 CHAR-FRB-OI-020-F-M 3081 CHAR-FRB-OI-006-F-M 3906 CHAR-FRB-OI-021-F-M 2747 CHAR-FRB-OI-007-F-M 2182 CHAR-FRB-OI-022-F-M 3901 CHAR-FRB-OI-OOS-F-M 3506 CHAR-FRB-OI-023-F-M 2845 CHAR-FRB-OI-OO9-F-M 2260 CHAR-FRB-O 1-024-F-M 2871 CHAR-FRB-OI-OIO-F-M 2750 CHAR-FRB-OI-025-F-M 2655 CHAR-FRB-O 1-0 ll-F-M 1930 CHAR-FRB-OI-026-F-M 2176 CHAR-FRB-OI-012-F-M 2569 CHAR-FRB-OI-027-F-M 3081 CHAR-FRB-OI-013-F-M 1976 CHAR-FRB-OI-02S-F-M 2406 CHAR-FRB-OI-014-F-M 2473 CHAR-FRB-OI-029-F-M 3219 CHAR-FRB-OI-015-F-M 1846 CHAR-FRB-OI-030-F-M 8713 Mean Ambient 1246 Mean Ambient 3443 Ct. Mean 2948 Ct. Mean 3557 Ct. Median 2260 Ct. Median 3081 Ct. Std. Dey.

1795 Ct. Std. Dey.

1616 MEZZANINE 590' >6' WALLS CHAR-FRB-OI-031-F-M 3912 CHAR-FRB-OI-046-F-M 2557 CHAR-FRB-OI-032-F-M 4545 CHAR-FRB-OI-047-F-M 2616 CHAR-FRB-OI-033-F-M 5171 CHAR-FRB-OI-04S-F-M 3625 CHAR-FRB-OI-034-F-M 4132 CHAR-FRB-OI-049-F-M 3186 CHAR-FRB-OI-035-F-M 3874 CHAR-FRB-OI-050-F-M 2773 CHAR-FRB-OI-036-F-M 2931 CHAR-FRB-OI-051-F-M 2753 CHAR-FRB-OI-037-F-M 3719 CHAR-FRB-OI-052-F-M 4943 CHAR-FRB-OI-03S-F-M 3958 CHAR-FRB-OI-053-F-M 4268 CHAR-FRB-OI-039-F-M 6082 CHAR-FRB-OI-054-F-M 8116 CHAR-FRB-OI-040-F-M 3757 CHAR-FRB-OI-055-F-M 5546 CHAR-FRB-OI-041-F-M 5952 CHAR-FRB-OI-056-F-M 2163 CHAR-FRB-OI-042-F-M 10420 CHAR-FRB-OI-057-F-M 2596 CHAR-FRB-OI-043-F-M 6178 CHAR-FRB-OI-05S-F-M 3193 CHAR-FRB-OI-044-F-M 4506 CHAR-FRB-OI-059-F-M 2393 CHAR-FRB-OI-045-F-M 3583 CHAR-FRB-OI-060-F-M 2445 Mean Ambient 3769 Mean Ambient 3443 Ct. Mean 4848 Ct. Mean 3545 ct. Median 4132 Ct. Median 2773 Ct. Std. Dey.

1827 Ct. Std. Dev.

1605 F-M = FIxed measurement 2-35 Revision 4 June 2011

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 Based upon the information reviewed, personnel interviews and data acquired during characterization, the classifications of FRB-01 are as follows:

1. The floor and walls of the decay and cut-up pools are Class 1 areas.

2. The floors, walls and ceiling of the transfer tank room and steam cleaning chamber are Class 1 areas.

3. The floors and walls, up to a height of 6 feet, in all other areas of FRB-01 are Class 1 areas.

4. The walls greater than 6 feet in the areas referenced in #3 are Class 2 areas.

2.1.8.9 TRW Trestle way The trestle way is located to the north and adjacent to the Reactor Building and functioned as a connection between the Reactor Building and the FARB. The substructure consists of reinforced concrete. The superstructure consists of structural steel with corrugated asbestos siding and a corrugated steel roof. The fuel transport machine, or cask car, unloaded irradiated fuel from the reactor via the transfer rotor, transported the irradiated fuel in finned pots from the Reactor Building to the FARB via the trestle way and unloaded the pots into the transfer tank rotor.

Modes and vectors for transmigration of contaminants include:

Transport of radioactive material associated with decommissioning of the trestle way and adjacent buildings.

Sodium fire that occurred on May 2 0 th 2008 in the basement of the Reactor Building.

Minor leaks in the Trestle way which occurred at unknown dates during operation.

Characterization data from past surveys proved insufficient for FSS planning activities.

A Characterization effort was implemented on September 15, 2008 to include smears, scans and fixed-point measurements in TRW-01. An ambient correction was achieved by taking shielded readings at five locations in the Trestle way, and the Mean of the data was calculated.

Table 2-15 represents the results of the fixed-point readings taken on the floors, walls and ceiling during this survey effort. Smears were taken at each fixed-point location. Smears indicated no result greater than MDA.

One-square meter beta scans were performed at each fixed-point location. No beta scan indicated greater than background. Gamma scans were performed in the general areas as well as locations where cracks and wall-to-floor junctures were present. No gamma scan 2-36 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 4 June 2011 Based upon the infOlmation reviewed, personnel interviews and data acquired during characterization, the classifications of FRB-O 1 are as follows:

1. The floor and walls of the decay and cut-up pools are Class 1 areas.

2. The floors, walls and ceiling of the transfer tank room and steam cleaning chamber are Class 1 areas.

3. The floors andwalls, up to a height of 6 feet, in all other areas of FRB-O 1 are Class 1 areas.

4. The walls greater than 6 feet in the areas referenced in #3 are Class 2 areas.

2.1.8.9 TRW-Ol - Trestle way The trestle way is located to the north and adjacent to the Reactor Building and functioned as a connection between the Reactor Building and the F ARB. The substructure consists of reinforced concrete. The superstructure consists of structural steel with corrugated asbestos siding and a corrugated steel roof. The fuel transport machine, or cask car, unloaded irradiated fuel from the reactor via the transfer rotor, transported the irradiated fuel in finned pots from the Reactor Building to the F ARB via the trestle way and unloaded the pots into the transfer tank rotor.

Modes and vectors for transmigration of contaminants include:

Transport of radioactive material associated with decommissioning of the trestle way and adjacent buildings.

Sodium fire that occurred on May 20th 2008 in the basement of the Reactor Building.

Minor leaks in the Trestle way which occurred at unknown dates during operation.

Characterization data from past surveys proved insufficient for FSS planning activities.

A Characterization effort was implemented on September 15,2008 to include smears, scans and fixed-point measurements in TRW-Ol. An ambient correction was achieved by taking shielded readings at five locations in the Trestle way, and the Mean of the data was calculated.

Table 2-15 represents the results of the fixed-point readings taken on the floors, walls and ceiling during this survey effort. Smears were taken at each fixed-point location. Smears indicated no result greater than MDA.

One-square meter beta scans were performed at each fixed-point location. No beta scan indicated greater than background. Gamma scans were performed in the general areas as well as locations where cracks and wall-to-floor junctures were present. No gamma scan 2-36

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 indicated results greater than background. There is a section of the TRW-01 where there is contamination that is painted over. This section will require the paint removed and that area surveyed.

Table 2-15 TRW-01 Characterization Data Result Result Location (dpm/100cm')

Location (dpim/100cm )

CHAR-TRW-01-001-F-M 3841 CHAR-TRW-01-013-F-M 2976 CHAR-TRW-01-002-F-M 3564 CHAR-TRW-01-014-F-M 2085 CHAR-TRW-01-003-F-M 2944 CHAR-TRW-01-015-F-M 2208 CHAR-TRW-01-004-F-M 4151 CHAR-TRW-01-016-F-M 2092 CHAR-TRW-01-005-F-M 3441 CHAR-TRW-01-017-F-M 2130 CHAR-TRW-01-006-F-M 3467 CHAR-TRW-01-018-F-M 2253 CHAR-TRW-01-007-F-M 3054 CHAR-TRW-01-019-F-M 2479 CHAR-TRW-01-008-F-M 2950 CHAR-TRW-01-020-F-M 2531 CHAR-TRW-01-009-F-M 3654 CHAR-TRW-01-021-F-M 2195 CHAR-TRW-01-010-F-M 3467 CHAR-TRW-01-022-F-M 2692 CHAR-TRW-01-011-F-M 3990 CHAR-TRW-01-023-F-M 3499 CHAR-TRW-01-012-F-M 4435 CHAR-TRW-01-024-F-M 6004 Mean Ambient 1713 Ct. Mean 3171 Ct. Median 3015 Ct. Std. Dev.

929 F-M = Fixed measurement Based on the information reviewed, personnel interviews and data acquired during characterization, the floors and walls up to a height of 6 feet are Class 1 areas and the walls greater than 6 feet are Class 2 areas.

2.1.8.10 NAB Sodium Building The Sodium Building is adjacent to the Reactor Building and is connected by an underground concrete tunnel. The Sodium Building housed the equipment used for storing and purifying the primary sodium. The Sodium Building, Waste Gas Building and the Inert Gas Building form one structural complex. The Sodium Building is divided into four sections:

1. The primary sodium storage tank room is a concrete structure comprised of 30 inch thick cast concrete walls and a 30 inch thick combination pre-cast and poured concrete roof. The room contains the three 15,000 gallon primary sodium storage tanks.

2-37 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 4 June 2011 indicated results greater than background. There is a section of the TRW -01 where there is contamination that is painted over. This section will require the paint removed and that area surveyed.

Table 2-15 TRW-Ol Characterization Data It~Cllh~l1::!:::j:~.*******.........** :...* ;.:

!(.!

~Resulf!.!***c:.

'(dpllijfoo~hi*2):.; !*£~~~ti~l:.*:*i.::* *.*.*.* ::~:Gi:r.: Reslllf'!'!'!> ** '

(dpfulloocril2)

CHAR-TRW-01-001-F-M 3841 CHAR-TRW-01-013-F-M 2976 CHAR-TRW-01-002-F-M 3564 CHAR-TRW-01-014-F-M 2085 CHAR-TRW-01-003-F-M 2944 CHAR-TRW-01-015-F-M 2208 CHAR-TRW-01-004-F-M 4151 CHAR-TRW-O 1-0 16-F-M 2092 CHAR-TRW-01-005-F-M 3441 CHAR-TRW-01-017-F-M 2130 CHAR-TRW-O 1-006-F-M 3467 CHAR-TRW-01-018-F-M 2253 CHAR-TRW-01-007-F-M 3054 CHAR-TRW-01-019-F-M 2479 CHAR-TRW-01-008-F-M 2950 CHAR-TRW-01-020-F-M 2531 CHAR-TRW-01-009-F-M 3654 CHAR-TRW-01-021-F-M 2195 CHAR-TRW-01-01O-F-M 3467 CHAR-TRW 022-F-M 2692 CHAR-TRW-01-011-F-M 3990 CHAR-TRW-01-023-F-M 3499 CHAR-TRW-01-012-F-M 4435 CHAR-TRW-01-024-F-M 6004 Mean Ambient 1713 Ct. Mean 3171 Ct. Median 3015 Ct. Std. Dev.

929 F-M = Fixed measurement Based on the information reviewed, personnel interviews and data acquired during characterization, the floors and walls up to a height of 6 feet are Class 1 areas and the walls greater than 6 feet are Class 2 areas.

2.l.8.10 NAB-O 1 - Sodium Building The'Sodium Building is adjacent to the Reactor Building and is connected by an underground concrete tunnel. The Sodium Building housed the equipment used for storing and purifying the primary sodium. The Sodium Building, Waste Gas Building and the Inert Gas Building form one structural complex. The Sodium Building is divided into four sections:

1. The primary sodium storage tanle room is a concrete structure comprised of 30 inch thick cast concrete walls and a 30 inch thick combination pre-cast and poured concrete roof. The room contains the three 15,000 gallon primary sodium storage tanles.

2-37

Fermi 1 License Termination Plan Revision 0 Chapter 2 Site Characterization May 2009

2. The cold trap room has 6-foot thick external concrete walls as well as a 6-foot thick concrete ceiling. Additionally, the cell has a 4-foot thick internal wall separating it from the storage tank room. This room contained the equipment necessary to determine and maintain the purity of the primary sodium.

3. The sodium-potassium (NaK) room is comprised of reinforced concrete floor, walls and ceiling and access is provided via a steel door located in the west wall of the room and a stairway on the east side. The NaK room contained the ventilation equipment and the air-to-NaK heat exchanger equipment for the cold trap.

4. The valve control room occupies the second story region of the Sodium Building and is constructed of concrete block walls and a steel roof deck structure. The valve control room contained the sodium service hand wheels and motors for the valves, electric panels supporting the induction heating for the piping, and the control panel.

Additionally, the mezzanine level and secondary portion of the Inert Gas Building are covered in this section since they are open to the Sodium Building areas and are separate from the Inert Gas Tank Room Survey area NAB-01 has an area footprint of approximately 1,116 square meters.

Modes and vectors for transmigration of contaminants include:

Transport of radioactive material associated with decommissioning of the Sodium Building.

Processing activities performed in the cold trap room.

Characterization data from past surveys proved insufficient for FSS planning activities.

A Characterization effort was implemented on September 23, 2008 to include smears, scans and fixed-point measurements in NAB-01. An ambient correction was achieved by taking shielded readings at five locations in each room and the Mean of those data was calculated.

Tables 2-16 and 2-17 represent the results of the fixed-point readings taken on the floors, walls and ceiling during this survey effort. Smears were taken at each fixed-point location. Smears indicated no result greater than MDA. One-square meter beta scans were performed at each fixed-point location. No beta scan indicated greater than background. Gamma scans were performed in the general areas (except 2-38 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 0 May 2009

2. The cold trap room has 6-foot thick external concrete walls as well as a 6-foot thick concrete ceiling. Additionally, the cell has a 4-foot thick internal wall separating it from the storage tank room. This room contained the equipment necessary to determine and maintain the purity of the primary sodium.

3. The sodium-potassium(NaK) room is comprised of reinforced concrete floor, walls and ceiling and access is provided via a steel door located in the west wall of the room and a stairway on the east side. The NaK room contained the ventilation equipment and the air-to-NaK heat exchanger equipment for the cold trap.

4. The valve control room occupies the second story region of the Sodium Building and is constructed of concrete block walls and a steel roof deck structure. The valve control room contained the sodium service hand wheels and motors for the valves, electric panels supporting the induction heating for the piping, and the control panel.

Additionally, the mezzanine level and secondary portion of the Inert Gas Building are covered in this section since they are open to the Sodium Building areas and are separate from the Inert Gas Tank Room Survey area NAB-O 1 has an area footprint of approximately 1,116 square meters.

Modes and vectors for transmigration of contaminants include:

8 Transport of radioactive material associated with decommissioning of the Sodium Building.

CD Processing activities performed in the cold trap room.

Characterization data from past surveys proved insufficient for FSS planning activities.

A Characterization effort was implemented on September 23,2008 to include smears, scans and fixed-point measurements in NAB-O 1. An ambient correction was achieved by taking shielded readings at five locations in each room and the Mean of those data was calculated.

Tables 2-16 and 2-17 represent the results of the fixed-point readings taken on the floors, walls and ceiling during this survey effort. Smears were taken at each fixed-point location. Smears indicated no result greater than MDA. One-square meter beta scans were performed at each fixed-point location. No beta scan indicated greater than background. Gamma scans were performed in the general areas (except 2-38

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 the tank, room) as well as locations where cracks and wall-to-floor junctures were present. No gamma scan indicated results greater than background.

Because of ambient levels associated with the sodium storage tanks, gamma, scan surveys were not performed in the tank room at the time of the characterization survey.

Table 2-16 NAB-01 Characterization Data ResuI t Result Resut Location (dpni/100enm*

Location (dpi/100cm2)

Location

(

/Oc 2

TANK ROOM NaK ROOM VALVE ROOM CHAR-NAB-C01-001-F-M 2767 CHAR-NAB-0 1-021-F-M 3586 CHAR-NAB-01-041 -F-M 3331 CHAR-NAB-01-002-F-M 9093 CHAR-NAB-01-022-F-M 5389 CHAR-NAB-01-042-F-M 2912 CHAR-NAB-C01-003-F-M 8450 CHAR-NAB-01t-023-F-M 2708 CHAR-NAB-01-043-F-M 3202 CHAR-NAB-C01-004-F-M 10528 CHAR-NAB-01-024-F-M 3219 CHAR-NAB-0 1-044-F-M 3170 CHAR-NAB-01-005-F-M 7683 CHAR-NAB-01-025-F-M 2399 CHAR-NAB-01-045-F-M 3092 CHAR-NAB-01-006-F-M 30890 CHAR-NAB-01-026-F-M 2432 CHAR-NAB-01-046-F-M 2925 CHAR-NAB-01-007-F-M 16370 CHAR-NAB-01-027-F-M 3566 CHAR-NAB-01-047-F-M 2860 CHAR-NAB-01-008-F-M 40750 CHAR-NAB-01-028-F-M 4366 CHAR-NAB-01-048-F-M 3176 CHAR-NAB-0l1-009-F-M 13374 CHAR-NAB-01l-029-F-M 2537 CHAR-NAB-01l-049-F-M 3041 CHAR-NAB-C01-010-F-M 23653 CHAR-NAB-01-030-F-M 2314 CHAR-NAB-C01-050-F-M 3176 CHAR-NAB-Cl-Oil1-F-M 11958 CHAR-NAB-C01-031l-F-M 2039 CHAR-NAB-C01-051l-F-M 3254 CHAR-NAB-01-012-F-M 35335 CHAR-NAB-01-032-F-M 3062 CHAR-NAB-01-052-F-M 2963 CHAR-NAB-Cl1-013-F-M 12508 CHAR-NAB-C01-033-F-M 2380 CHAR-NAB-C01-053-F-M 2214 CHAR-NAB-C01-014-F-M 20513 CHAR-NAB-01-034-F-M 2662 CHAR-NAB-C01-054-F-M 2440 CHAR-NAB-C01-015-F-M 13557 CHAR-NAB-01-035-F-M 2471 CHAR-NAB-C01-055-F-M 2453 CHAR-NAB-01-016-F-M 27999 CHAR-NAB-01-036-F-M 2196 CHAR-NAB-01-056-F-M 2163 CHAR-NAB-C01-017-F-M 13610 CHAR-NAB-01-037-F-M 2353 CHAR-NAB-01-057-F-M 2234 CHAR-NAB-C01-Cl18-F-M 34562 CHAR-NAB-Cl1-038-F-M 3370 CHAR-NAB-01-058-F-M 1737 CHAR-NAB-01-019-F-M 9991 CHAR-NAB-01-039-F-M 2471 CHAR-NAB-C01-059-F-M 2350 CHAR-NAB-C01-020-F-M 9912 CHAR-NAB-C01-040-F-M 2839 CHAR-NAB-01-060-F-M 2879 Mean Ambient 11112 Mean Ambient 2040 Mean Ambient 2138 Ct. Mean 17675 Ct. Mean 2918 Ct. Mean 2779 Ct. Median 1346ý5 Ct. Median 2599 Ct. Median 2918 Ct. Std. Dev.

10807 Ct. Std. Dev.

821 Ct. Std. Dev.

454 F-M Fixed measurement 2-39 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 4 June 2011 the tanle room) as well as locations where cracks and wall-to-floor junctures were present. No gamma scan indicated results greater than background.

Because of ambient levels associated with the sodium storage tanks, gamma scan surveys were not performed in the tanle room at the time of the characterization survey.

Table 2-16 NAB-Ol Characterization Data

~;" "

....*.*., Result Locati~~'.~"C\\

Result'

'.~

~.

.L';*'\\;'*<'."

Result Location

~.

~.'

(dprn/l00c~2)

(dpmIIOOcm2),

~ Location C,

( dpmJI00cni2)

TANK ROOM NaKROOM VALVE ROOM CHAR-NAB-OI-OOI-F-M 2767 CHAR-NAB-Ol-021-F-M 3586 CHAR-NAB-O 1-041-F-M 3331 CHAR-NAB-O 1-OO2-F-M 9093 CHAR-NAB-OI-022-F-M 5389 CHAR-NAB-OI-042-F-M 2912 CHAR-NAB-O 1-OO3-F-M 8450 CHAR-NAB-OI-023-F-M 2708 CHAR-NAB-O 1-043-F-M 3202 CHAR-NAB-OI-OO4-F-M 10528 CHAR-NAB-OI-024-F-M 3219 CHAR-NAB-O 1-044-F-M 3170 CHAR-NAB-O l-OOS-F-M 7683 CHAR-NAB-OI-02S-F-M 2399 CHAR-NAB-O 1-04S-F-M 3092 CHAR-NAB-O 1-OO6-F-M 30890 CHAR-NAB-OI-026-F-M 2432 CHAR-NAB-O 1-046-F-M 2925 CHAR-NAB-OI-OO7-F-M 16370 CHAR-NAB-OI-027-F-M 3566 CHAR-NAB-OI-047-F-M 2860 CHAR-NAB-O l-OOS-F-M 40750 CHAR-NAB-OI-02S-F-M 4366 CHAR-NAB-OI-04S-F-M 3176 CHAR-NAB-O 1-OO9-F-M 13374 CHAR-NAB-OI-029-F-M 2537 CHAR-NAB-OI-049-F-M 3041 CHAR-NAB-OI-OIO-F-M 23653 CHAR-NAB-OI-030-F-M 2314 CHAR-NAB-OI-OSO-F-M 3176 CHAR-NAB-OI-Oll-F-M 11958 CHAR-NAB-OI-031-F-M 2039 CHAR-NAB-OI-OSI-F-M 3254 CHAR-NAB-OI-012-F-M 35335 CHAR-NAB-OI-032-F-M 3062 CHAR-NAB-O 1-052-F-M 2963 CHAR-NAB-OI-013-F-M 12508 CHAR-NAB-O 1-033-F-M 2380 CHAR-NAB-O 1-OS3-F-M 2214 CHAR-NAB-OI-014-F-M 20513 CHAR-NAB-OI-034-F-M 2662 CHAR-NAB-OI-OS4-F-M 2440 CHAR-NAB-OI-OlS-F-M 13557 CHAR-NAB-OI-03S-F-M 2471 CHAR-NAB-OI-OSS-F-M 2453 CHAR-NAB-OI-016-F-M 27999 CHAR-NAB-O 1-036-F-M 2196 CHAR-NAB-O 1-OS6-F-M 2163 CHAR-NAB-OI-017-F-M 13610 CHAR-NAB-OI-037-F-M 2353 CHAR-NAB-OI-OS7-F-M 2234 CHAR-NAB-OI-OlS-F-M 34562 CHAR-NAB-OI-03S-F-M 3370 CHAR-NAB-OI-OSS-F-M 1737 CHAR-NAB-OI-019-F-M 9991 CHAR-NAB-OI-039-F-M 2471 CHAR-NAB-O 1-059-F-M 2350 CHAR-NAB-O 1-020-F-M 9912 CHAR-NAB-OI-040-F-M 2839 CHAR-NAB-OI-060-F-M 2879 Mean Ambient 11112 Mean Ambient 2040 Mean Ambient 2138 Ct. Mean 17675 ct. Mean 2918 Ct. Mean 2779 Ct. Median 13465 Ct. Median 2599 Ct. Median 2918 Ct. Std. Dey.

10807 ct. Std. Dey.

821 Ct. Std. Dey.

454 F-M = Fixed measurement 2-39

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 Table 2-17 NAB-01 Characterization Data (Mezzanine)

LocationI (dpdm/10oocm MEZZANINE CHAR-NAB-01-061-F-M 2649 CHAR-NAB-01-062-F-M 2878 CHAR-NAB-01-063-F-M 2681 CHAR-NAB-01-064-F-M 2629 CHAR-NAB-01-065-F-M 2688 CHAR-NAB-01-066-F-M 2727 CHAR-NAB-01-067-F-M 2386 CHAR-NAB-01-068-F-M 2327 CHAR-NAB-01-069-F-M 2550 CHAR-NAB-01-070-F-M 2314 Mean Ambient 1724 Ct. Mean 2583 Ct. Median 2639 Ct. Std. Dev.

186 F-M = Fixed measurement The cold trap room is still posted as a contaminated area and has a great deal of equipment removal left, therefore the cold trap room has not been surveyed. Therefore, based upon the information reviewed, personnel interviews and data acquired during characterization the classifications for NAB-01 are as follows:

1. The cold trap room and also the storage tank room are classified as Class 1.

2. The valve room, NaK room and the mezzanine are classified as Class 2.

2.1.8.11 VNB Ventilation Building The Ventilation Building consists of a steel reinforced concrete floor with concrete block walls. The roof consists of a structural steel framework covered by corrugated steel. The Ventilation Building housed equipment for the Reactor Building Ventilation System including the supply and exhaust blowers, valves for water supply to the under floor cooling heat exchangers, a control panel, Freon refrigeration equipment for above floor cooling, and space for future equipment additions, such as dehumidifiers. The restricted area fence has been modified to extend past the east doors of the building.

2-40 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 4 June 2011 2.1.8.11 Table 2-17 NAB-01 Characterization Data (Mezzanine)

~:,o'~~;fl~,~:,-;,~:,)ii:i',Result;,:

'(dpili710()cm2r,/

MEZZANINE CHAR-NAB-01-061-F-M 2649 CHAR-NAB-01-062-F-M 2878 CHAR-NAB-OI-063-F-M 2681 CHAR-NAB-OI-064-F-M 2629 CHAR-NAB-01-065-F-M 2688 CHAR-NAB-O 1-066~F-M 2727 CHAR-NAB-O 1-067-F-M 2386 CHAR-NAB-01-068-F-M 2327 CHAR-NAB-01-069-F-M 2550 CHAR-NAB-01-070-F-M 2314 Mean Ambient 1724 ct. Mean 2583 Ct. Median 2639 Ct. Std. Dev.

186 F-M = Fixed measurement The cold trap room is still posted as a contaminated area and has a great deal of equipment removal left, therefore the cold trap room has not been surveyed. Therefore, based upon the information reviewed, personnel interviews and data acquired during characterization the classifications for NAB-01 are as follows:

1. The cold trap room and also the storage tank room are classified as Class 1.

2. The valve room, N aK room and the mezzanine are classified as Class 2.

VNB Ventilation Building The Ventilation Building consists of a steel reinforced concrete floor with concrete block walls. The roof consists of a structural steel framework covered by cOlTugated steel. The Ventilation Building housed equipment for the Reactor Building Ventilation System including the supply and exhaust blowers, valves for water supply to the under floor cooling heat exchangers, a control panel, Freon refrigeration equipment for above floor cooling, and space for future equipment additions, such as dehumidifiers. The restricted area fence has been modified to extend past the east doors of the building.

2-40

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 Modes and vectors for transmigration of contaminants include:

Transport of radioactive material associated with decommissioning of the adjoining structures.

Sodium fire that occurred on May 2 0 th 2008 in the basement of the Reactor Building.

Characterization data from past surveys proved insufficient for FSS planning activities.

A Characterization effort was implemented on September 16, 2008 to include smears, scans and fixed-point measurements in VNB-01. An ambient correction was achieved by taking shielded readings at five locations within the survey area and the Mean of those data was calculated. Table 2-18 represent the results of the fixed-point readings taken on the floors, walls and ceiling during this survey effort. Smears were taken at each fixed-point location. Smears indicated no result greater than MDA. One-square meter beta scans were performed at each fixed-point location. No beta scan indicated greater than background. Gamma scans were performed in the general areas as well as locations where cracks and wall-to-floor junctures were present. No gamma scan indicated results greater than background.

Table 2-18 VNB-01 Characterization Data Result Result l

Location (dpm/100cm)

Location (dpm/100cm 2)

CHAR-VNB-01-001-F-M 2609 CHAR-VNB-01-011-F-M 2026 CHAR-VNB-01-002-F-M 1947 CHAR-VNB-01-012-F-M 2537 CHAR-VNB-01-003-F-M 3035 CHAR-VNB-01-013-F-M 3153 CHAR-VNB-01-004-F-M 2406 CHAR-VNB-01-014-F-M 2708 CHAR-VNB-01-005-F-M 2649 CHAR-VNB-01-015-F-M 2104 CHAR-VNB-01-006-F-M 2288 CHAR-VNB-01-016-F-M 2249 CHAR-VNB-01-007-F-M 2190 CHAR-VNB-01-017-F-M 1986 CHAR-VNB-01-008-F-M 1967 CHAR-VNB-01-018-F-M 2865 CHAR-VNB-01-009-F-M 2609 CHAR-VNB-01-019-F-M 2563 CHAR-VNB-01-010-F-M 2065 CHAR-VNB-01-020-F-M 2485 Mean Ambient 2005 Ct. Mean 2422 Ct. Median 2445 Ct. Std. Dev.

360 F-M = Fixed measurement Based upon information reviewed, personnel interviews and data acquired during characterization the floor 2-41 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 4 June 2011 Modes and vectors for transmigration of contaminants include:

Transport of radioactive material associated with decommissioning of the adjoining structures.

Sodium fire that occurred on May 20th 2008 in the basement ofthe Reactor Building.

Characterization data from past surveys proved insufficient for FSS planning activities.

A Characterization effort was implemented on September 16, 2008 to include smears, scans and fixed-point measurements in VNB-Ol. An ambient correction was achieved by taking shielded readings at five locations within the survey area and the Mean of those data was calculated. Table 2-18 represent the results of the fixed-point readings taken on the floors, walls and ceiling during this survey effort. Smears were taken at each fixed-point location. Smears indicated no result greater than MDA. One-square meter beta scans were performed at each fixed-point location. No beta scan indicated greater than background. Gamma scans were performed in the general areas as well as locations where cracks and wall-to-floor junctures were present. No gamma scan indicated results greater than background.

Table 2-18 VNB-Ol Characterization Data

r.;:;.~;c*~'**)n.,;~:t!;.'.

ReSlJ@i,', **,i;,

I£bgll'i~'~ ** :i.* ",::* :_ li

'.Resul('***"

I '.i,.. ~c'F~t.~g,.,.,\\,":

'Cdp nViOOcln~)

- - - c dpm'itO(jcm~r*

CHAR-VNB-01-001-F-M 2609 CHAR-VNB-01-011-F-M 2026 CHAR-VNB-OI-002-F-M 1947 CHAR-VNB-OI-012-F-M 2537 CHAR-VNB-O 1-003-F-M 3035 CHAR-VNB-01-013-F-M 3153 CHAR-VNB-01-004-F-M 2406 CHAR-VNB-01-014-F-M 2708 CHAR-VNB-01-005-F-M 2649 CHAR-VNB-01-015-F-M 2104 CHAR-VNB-01-006-F-M 2288 CHAR-VNB-01-016-F-M 2249 CHAR-VNB-01-007-F-M 2190 CHAR-VNB-01-017-F-M 1986 CHAR-VNB-01-008-F-M 1967 CHAR-VNB-O 1-0 18-F-M 2865 CHAR-VNB-01-009-F-M 2609 CHAR-VNB-01-019-F-M 2563 CHAR-VNB-01-010-F-M 2065 CHAR-VNB-01-020-F-M 2485 Mean Ambient 2005 Ct. Mean 2422 Ct. Median 2445 Ct. Std. Dev.

360 F-M = Fixed measurement Based upon information reviewed, personnel interviews and data acquired during characterization the floor 2-41

Fermi 1 License Termination Plan Revision 0 Chapter 2 Site Characterization May 2009 and walls up to a height of 6 feet are Class 1. The walls above 6 feet are Class 2.

2.1.8.12 NAT Sodium Tunnel The Sodium Tunnel consists of a subsurface reinforced concrete structure lined with a /4" thick carbon steel plate. The tunnel runs from the northwest corner of the Reactor Building annulus to the Cold Trap Room of the Sodium Building. The structure contained some of the primary sodium service system piping and was heated by a 60 cycle induction heating system replacing heat losses when the piping was at 400 degrees Fahrenheit with a 100 degree Fahrenheit ambient temperature. Access to this tunnel is via one of two manholes located between the Cold Trap Room and the Trestleway.

The area of the footprint of NAT-01 is approximately 50 square meters.

Modes and vectors for transmigration of contaminants include:

Any contamination encountered during the removal or modification of piping within NAT-01.

Characterization data from past surveys proved insufficient for FSS planning activities.

A Characterization effort was implemented on October 6, 2008 to include smears, scans and fixed-point measurements in NAT-01. An ambient correction was achieved by taking shielded readings at five locations in the sodium tunnel and the Mean of those data was calculated. Table 2-19 represent the results of the fixed-point readings taken on the floors, walls and ceiling during this survey effort. Smears were taken at each fixed-point location. Smears indicated no result greater than MDA. One-square meter beta scans were performed at each fixed-point location. No beta scan indicated greater than background. Gamma. scans were performed in the general areas as well as locations where cracks and wall-to-floor junctures were present. No gamma scan indicated results greater than background.

2-42 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 0 May 2009 2.1.8.12 and walls up to a height of 6 feet are Class 1. The walls above 6 feet are Class 2.

NAT Sodium Tunnel The Sodium Tunnel consists of a subsurface reinforced concrete structure lined with a 1'4" thick carbon steel plate. The tunnel runs from the northwest comer of the Reactor Building annulus to the Cold Trap Room of the Sodium Building. The structure contained some of the primary sodium service system piping and was heated by a 60 cycle induction heating system ~eplacing heat losses when the piping was at 400 degrees Fahrenheit with a 100 degree Fahrenheit ambient temperature. Access to this tunnel is via one of two manholes located between the Cold Trap Room and the Trestleway.

The area ofthe footprint ofNAT-01 is approximately 50 square meters.

Modes and vectors for transmigration of contaminants include:

Any contamination encountered during the removal or modification of piping within NAT -01.

Characterization data from past surveys proved insufficient for FSS planning activities.

A Characterization effort was implemented on October 6, 2008 to include smears, scans and fixed-point measurements in NAT-01. An ambient correction was achieved by taking shielded readings at five locations in the sodium tunnel and the Mean of those data was calculated. Table 2-19 represent the results of the fixed-point readings taken on the floors, walls and ceiling during this survey effort. Smears were taken at each fixed-point location. Smears indicated no result greater than MDA. One-square meter beta scans were performed at each fixed-point location. No beta scan indicated greater than background. Gamma scans were performed in the general areas as well as locations where cracks and wall-to-floor junctures were present. No gamma scan indicated results greater than background.

2-42

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 Table 2-19 NAT-01 Characterization Data

.- !Result Result Location (dpm/100cm2)

Location

_(dpm/100cm1 2)

CHAR-NAT-01-001-F-M 4877 CHAR-NAT-01-011 -F-M 9603 CHAR-NAT-01-002-F-M 2860 CHAR-NAT-01-012-F-M 7534 CHAR-NAT-01-003-F-M 2906 CHAR-NAT-01-013-F-M 8359 CHAR-NAT-01-004-F-M 1977 CHAR-NAT-01-014-F-M 3594 CHAR-NAT-01-005-F-M 1591 CHAR-NAT-01-015-F-M 6212 CHAR-NAT-01-006-F-M 1139 CHAR-NAT-01-016-F-M 3600 CHAR-NAT-01-007-F-M 4039 CHAR-NAT-01-017-F-M 6736 CHAR-NAT-01-008-F-M 6408 CHAR-NAT-01-018-F-M 3155 CHAR-NAT-01-009-F-M 4680 CHAR-NAT-01-019-F-M 6264 CHAR-NAT-01-010-F-M 2906 CHAR-NAT-01-020-F-M 3338 Mean Ambient 5365 Ct. Mean 4589 Ct. Median 3819 Ct. Std. Dev.

2337 F-M = Fixed measurement As a result of historical information, decommissioning activities performed and planned, and characterization data, NAT-01 is classified as a Class 2 area.

2.1.8.13 ESG-01 -East Sodium Gallery The east sodium gallery consists of three chambers (North, Center and South) which held the secondary sodium lines. Access to the three east sodium gallery chambers is via horizontal steel doors just above ground level. The east sodium gallery's walls and base slab are of conventional reinforced concrete construction resting on concrete filled pilasters. The roof is constructed of an 8 inch thick precast concrete slab covered with a 10 inch thick concrete layer all of which is beneath approximately 5 feet of earth. Included in this area is the Fission Product Detector (FPD) Building. The FPD building is located due east of the reactor building, directly above the East Sodium gallery (north chamber). This is a small partially buried room; a portion of it below ground level, which contained the gaseous fission product detector and piping. Access to the FPD building is through a manhole in the roof of the building. The building is constructed of steel reinforced concrete.

The area of the footprint of ESG-01, including the FPD building, is approximately 98 square meters.

2-43 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 4 June 2011 Table 2-19 NAT -01 Characterization Data Locatiof:

--c'.'

." *.ResuIL'.. *'

'L Result~o":L (dl))ri7:10(icrn2)

.... Location

.*. x.

(dplIlI100cIll2)

CHAR-NAT-O 1-00 I-F-M 4877 CHAR-NAT-OI-OII-F-M 9603 CHAR-NAT-OI-002-F-M 2860 CHAR-NAT-OI-012-F-M 7534 CHAR-NAT-OI-003-F-M 2906 CHAR-NAT-OI-013-F-M 8359 CHAR-NAT-OI-004-F-M 1977 CHAR-NAT-OI-014-F-M 3594 CHAR-NAT-OI-005-F-M 1591 CHAR-NAT-01-015-F-M 6212 CHAR-NAT-OI-006-F-M 1139 CHAR-NAT-OI-016-F-M 3600 CHAR-NAT-OI-007-F-M 4039 CHAR-NAT-OI-017-F-M 6736 CHAR-NAT-OI-008-F-M 6408 CHAR-NAT-OI-018-F-M 3155 CHAR-NAT-O 1-009-F-M 4680 CHAR-NAT-OI-019-F-M 6264 CHAR-NAT-OI-0I0-F-M 2906 CHAR-NAT-OI-020-F-M 3338 Mean Ambient 5365 ct. Mean 4589 Ct. Median 3819 Ct. Std. Dev.

2337 F-M = FIxed measurement As a result of historical information, decommissioning activities performed and planned, and characterization data, NAT -01 is classified as a Class 2 area.

2.1.8.13 ESG-OI-East Sodium Gallery The east sodium gallery consists of three chambers (North, Center and South) which held the secondary sodium lines. Access to the three east sodium gallery chambers is via horizontal steel doors just above ground level. The east sodium gallery's walls and base slab are of conventional reinforced concrete construction resting on concrete filled pilasters. The roof is constructed of an 8 inch thick precast concrete slab covered with a 10 inch thick concrete layer all of which is beneath approximately 5 feet of earth. Included in this area is the Fission Product Detector (FPD) Building. The FPD building is located due east of the reactor building, directly above the East Sodium gallery (north chamber). This is a small patiially buried room; a portion of it below ground level, which contained the gaseous fission product detector and piping. Access to the FPD building is through a manhole in the roof of the building. The building is constructed of steel reinforced concrete.

The area of the footprint ofESG-Ol, including the FPD building, is approximately 98 square meters.

2-43

Fermi 1 License Termination Plan Revision 0 Chapter 2 Site Characterization May 2009 Modes and vectors for transmigration of contaminants include:

Any contamination encountered during the removal of piping within ESG-01.

Characterization data from past surveys proved insufficient for FSS planning activities.

A Characterization effort was implemented on October 13, 2008 to include smears, scans and fixed-point measurements in ESG-01. An ambient correction was achieved by taking shielded readings at five locations inside the east sodium gallery and the Mean of those data was calculated. Additionally, an ambient correction was achieved by taking shielded readings at five locations in the FPD building and the Mean of those data was calculated. Table 2-20 represent the results of the fixed-point readings taken on the floors and walls during this survey effort.

Smears were taken at each fixed-point location. Smears indicated no result greater than MDA. One-square meter beta scans were performed at each fixed-point location. No beta scan indicated greater than background. Gamma scans were performed in general areas as well as locations where cracks and wall-to-floor junctures were present. No gamma scan indicated results greater than background.

2-44 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 0 May 2009 Modes and vectors for transmigration of contaminants include:

Any contamination encountered during the removal of piping within ESG-Ol.

Characterization data from past surveys proved insufficient for FSS planning activities.

A Characterization effort was implemented on October 13,2008 to include smears, scans and fixed-point measurements in ESG-Ol. An ambient correction was achieved by taking shielded readings at five locations inside the east sodium gallery and the Mean of those data was calculated. Additionally, an ambient correction was achieved by taking shielded readings at five locations in the FPD building and the Mean of those data was calculated. Table 2-20 represent the results of the fixed-point readings taken on the floors and walls during this survey effort.

Smears were taken at each fixed-point location. Smears indicated no result greater than MDA. One-square meter beta scans were performed at each fixed-point location. No beta scan indicated greater than background. Gamma scans were performed in general areas as well as locations where cracks and wall-to-floor junctures were present. No gamma scan indicated results greater than background.

2-44

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 Table 2-20 ESG-01 Characterization Data SResult Resuilt Location (dpm/100cm 2)

Location (dp m/lOcm2)

EAST SODIUM GALLERY FISSION PRODUCT DETECTOR (FPD) BLDG.

CHAR-ESG-01-001-F-M 1990 CHAR-ESG-01-021-F-M 1790 CHAR-ESG-01-002-F-M 1944 CHAR-ESG-01-022-F-M 1744 CHAR-ESG-01-003-F-M 1852 CHAR-ESG-01-023-F-M 1711 CHAR-ESG-01-004-F-M 1826 CHAR-ESG-01-024-F-M 1973 CHAR-ESG-01-005-F-M 1682 CHAR-ESG-01-025-F-M 1809 CHAR-ESG-01-006-F-M 1846 CHAR-ESG-01-026-F-M 1750 CHAR-ESG-01-007-F-M 2154 CHAR-ESG-01-027-F-M 1370 CHAR-ESG-01-008-F-M 2599 CHAR-ESG-01-028-F-M 2176 CHAR-ESG-01-009-F-M 2370 CHAR-ESG-01-029-F-M 2340 CHAR-ESG-01-010-F-M 2402 CHAR-ESG-01-030-F-M 2635 CHAR-ESG-01-011-F-M 2114 CHAR-ESG-01-012-F-M 1892 CHAR-ESG-01-013-F-M 2042 CHAR-ESG-01-014-F-M 2127 CHAR-ESG-01-015-F-M 1957 CHAR-ESG-01-016-F-M 2101 CHAR-ESG-01-017-F-M 2802 CHAR-ESG-01-018-F-M 2415 CHAR-ESG-01-019-F-M 2127 CHAR-ESG-01-020-F-M 2140 Mean Ambient 1962 Mean Ambient 1263 Ct. Mean 2119 Ct. Mean 1930 Ct. Median 2108 Ct. Median 1800 Ct. Std. Dev.

279 Ct. Std. Dev.

364 F-M= Fixed measurement As a result of historical information, decommissioning activities performed and planned, and characterization surveys performed, ESG-01 is classified as a Class 2 area.

2.1.8.14 WSG West Sodium Gallery The west sodium gallery consists of two chambers (north and south) which held the secondary sodium lines. The west gallery supplied the No. 3 steam generator. Access to the south compartment of the west sodium gallery chamber is via a horizontal steel door just above ground level. Access to the north compartment is via a tunnel from the Reactor Building annulus or a horizontal door which was sealed with a steel plate, concrete and stone fill to prevent water intrusion. The west sodium gallery's walls and base slab are of conventional concrete resting on concrete filled pilasters.

2-45 Fermi 1 License Termination Plan Chapter 2 Site Characterization Table 2-20 ESG-Ol Characterization Data Revision 4 June 2011

)}Resulf'},::>'

t,ocation "',',;

2:

I"'""",,', "

.--c;;* __,-- *. **.*

Resll-t""<,,

""i(dpm/10()ciIlh ",

Locati()n

\\

(dprii./IQOcm\\,

EAST SODIUM GALLERY FISSION PRODUCT DETECTOR (FPD) BLDG.

CHAR-ESG-OI-00I-F-M 1990 CHAR-ESG-OI-021-F-M 1790 CHAR-ESG-OI-002-F-M 1944 CHAR-ESG-OI-022-F-M 1744 CHAR-ESG-O 1-003-F-M 1852 CHAR-ESG-O 1-023-F-M 1711 CHAR-ESG-O 1-004-F-M 1826 CHAR -ESG-O 1-024-F-M 1973 CHAR-ESG-OI-005-F-M 1682 CHAR-ESG-OI-025-F-M 1809 CHAR-ESG-O 1-006-F-M 1846 CHAR-ESG-OI-026-F-M 1750 CHAR-ESG-OI-007-F-M 2154 CHAR-ESG-OI-027-F-M 1370 CHAR-ESG-OI-008-F-M 2599 CHAR-ESG-OI-028-F-M 2176 CHAR-ESG-OI-009-F-M 2370 CHAR-ESG-O 1-029-F-M 2340 CHAR-ESG-O 1-0 1 O-F-M 2402 CHAR-ESG-OI-030-F-M 2635 CHAR-ESG-OI-0II-F-M 2114 CHAR-ESG-OI-012-F-M 1892 CHAR-ESG-OI-013-F-M 2042 CHAR-ESG-Q1-014-F-M 2127 CHAR-ESG-OI-015-F-M 1957 CHAR-ESG-OI-016-F-M 2101 CHAR-ESG-OI-017-F-M 2802 CHAR-ESG-OI-018-F-M 2415 CHAR-ESG-OI-019-F-M 2127 CHAR-ESG-OI-020-F-M 2140 Mean Ambient 1962 Mean Ambient 1263 Ct. Mean 2119 Ct. Mean 1930 Ct. Median 2108 Ct. Median 1800 Ct. Std. Dev.

279 Ct. Std. Dev.

364 F-M = Fixed measurement As a result of historical information, decommissioning activities performed and planned, and characterization surveys performed, ESG-01 is classified as a Class 2 area.

2.1.8.14 WSG-Ol-West Sodium Gallery The west sodium gallery consists of two chambers (north and south) which held the secondary sodium lines. The west gallery supplied the No.3 steam generator. Access to the south compartment of the west sodium gallery chamber is via a horizontal steel door just above ground level. Access to the north compartment is via a tunnel from the Reactor Building annulus or a horizontal door which was sealed with a steel plate, concrete and stone fill to prevent water intrusion. The west sodium gallery'S walls and base slab are of conventional concrete resting on concrete filled pilasters.

2-45

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 The area of the footprint of WSG-01 is approximately 67 square meters.

Modes and vectors for transmigration of contaminants include:

Any contamination encountered during the removal of piping within WSG-01.

Characterization data from past surveys proved insufficient for FSS planning activities.

A Characterization effort was implemented on October 16, 2008 to include smears, scans and fixed-point measurements in WSG-01. An ambient correction was achieved by taking shielded readings at five locations inside the west sodium gallery and the Mean of those data was calculated. Table 2-21 represent the results of the fixed-point readings taken on the floors, walls and ceiling during this survey effort.

Smears were taken at each fixed-point location. Smears indicated no result greater than MDA. One-square meter beta scans were performed at each fixed-point location. No beta scan indicated results greater than background. Gamma scans were performed in the general areas as well as locations where cracks and wall-to-floor junctures were present. No gamma scan indicated results greater than background.

Table 2-21 WSG-01 Characterization Data Result

-Result LEocationi (dpm/100cm')

Location (dpm/100cm)

CHAR-WSG-01-001-F-M 2075 CHAR-WSG-01-011-F-M 1846 CHAR-WSG-01-002-F-M 2180 CHAR-WSG-01-012-F-M 1852 CHAR-WSG-01-003-F-M 2036 CHAR-WSG-01-013-F-M 1964 CHAR-WSG-01-004-F-M 2108 CHAR-WSG-01-014-F-M 2121 CHAR-WSG-01-005-F-M 2271 CHAR-WSG-01-015-F-M 2239 CHAR-WSG-01-006-F-M 2239 CHAR-WSG-01-016-F-M 1610 CHAR-WSG-01-007-F-M 2219 CHAR-WSG-01-017-F-M 2042 CHAR-WSG-01-008-F-M 2193 CHAR-WSG-01-018-F-M 1754 CHAR-WSG-01-009-F-M 1951 CHAR-WSG-01-019-F-M 1911 CHAR-WSG-01-010-F-M 1872 CHAR-WSG-01-020-F-M 2088 Mean Ambient 1160 Ct. Mean 2029 Ct. Median 2059 Ct. Std. Dev.

180 F-M = Fixed measurement Based on the information reviewed, personnel interviews and data acquired during characterization, WSG-01 is classified as a Class 3 area.

2-46 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 4 June 2011 The area of the footprint ofWSG-Ol is approximately 67 square meters.

Modes and vectors for transmigration of contaminants include:

Any contamination encountered during the removal of piping within WSG-O 1.

Characterization data from past surveys proved insufficient for FSS planning activities.

A Characterization effort was implemented on October 16,2008 to include smears, scans and fixed-point measurements in WSG-01. An ambient correction was achieved by taking shielded readings at five locations inside the west sodium gallery and the Mean of those data was calculated. Table 2-21 represent the results of the fixed-point readings taken on the floors, walls and ceiling during this survey effort.

Smears were taken at each fixed-point location. Smears indicated no result greater than MDA. One-square meter beta scans were performed at each fixed-point location. No beta scan indicated results greater than background. Gamma scans were performed in the general areas as well as locations where cracks and wall-to-floor junctures were present. No gamma scan indicated results greater than background.

Table 2-21 WSG-Ol Characterization Data

L~l~t~i~~J,l~**;:j~*.;:.*.**** [~~ Ifa~~lkoiJ~t2{.} ;ir;~~l~J~.(: ;;.,..**::.:::::~fa~~fi60r;~2)

CHAR-WSG-01-001-F-M 2075 CHAR-WSG-01-011-F-M 1846 CHAR-WSG-OI-002-F-M 2180 CHAR-WSG-01-012-F-M 1852 CHAR-WSG-01-003-F-M 2036 CHAR-WSG-OI-013-F-M 1964 CHAR-WSG-O 1-004-F-M 2108 CHAR-WSG-01-014-F-M 2121 CHAR-WSG-01-005-F-M 2271 CHAR-WSG-O 1-0 15-F-M 2239 CHAR-WSG-O 1-006-F-M 2239 CHAR-WSG-01-016-F-M 1610 CHAR-WSG-O 1-007 -F-M 2219 CHAR-WSG-01-017-F-M 2042 CHAR-WSG-O 1-008-F-M 2193 CHAR-WSG-01-018-F-M 1754 CHAR-WSG-O 1-009-F-M 1951 CHAR-WSG-01-019-F-M 1911 CHAR -WSG-O 1-01 O-F -M 1872 CHAR-WSG-O 1-020-F-M 2088 Mean Ambient 1160 Ct. Mean 2029 Ct. Median 2059 Ct. Std. Dev.

180 F-M = Fixed measurement Based on the information reviewed, personnel interviews and data acquired during characterization, WSG-01 is classified as a Class 3 area.

2-46

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 2.1.8.15 WGB Waste Gas Building The Waste Gas Building housed the waste gas disposal system that removed waste gases from the plant by a process which included storage until the gases decayed to a suitable level, dilution below the maximum permissible concentration in air and dispersion into the atmosphere through a stack. Piping, valves, and mechanical equipment were housed in chambers below grade; the holdup tanks were housed above grade in shielded cells of the building. Piping transported the waste gas to the FARB where it exited to the atmosphere via a waste gas stack. The holdup tank chambers are inside the Fermi 1 Controlled Area, while the below grade chamber and the grade level valve operating room are outside the Fermi 1 Controlled Area boundary.

Construction of the Waste Gas Building includes reinforced concrete walls 12-18 inches thick, with the exception of the concrete block walled valve room. The roof is constructed of reinforced concrete 2 feet thick.

The area of the footprint of WGB-01 is approximately 303 square meters.

Modes and vectors for transmigration of contaminants include:

Any contamination encountered during the removal of piping within WGB-01.

Characterization data from past surveys proved insufficient for FSS planning activities.

A Characterization effort was implemented on October 1, 2008 to include smears, scans and fixed-point measurements in WGB-01. An ambient correction was achieved by taking shielded readings at five locations in each room and the Mean of those data was calculated.

Tables 2-22 and 2-23 represent the results of the fixed-point readings taken on the floors, walls and ceiling during this survey effort. Smears were taken at each fixed-point location. Smears indicated no results greater than MDA. One-square meter beta scans were performed at each fixed-point location. No beta scan indicated greater than background. Gamma scans were performed in the general areas as well as locations where cracks and wall-to-floor junctures were present. No gamma scan indicated results greater than background.

2-47 Fermi 1 License Termination Plan Chapter 2 Site Characterization 2.1.8.15 WGB Waste Gas Building Revision 4 June 2011 The Waste Gas Building housed the waste gas disposal system that removed waste gases from the plant by a process which included storage until the gases decayed to & suitable level, dilution below the maximUll} permissible concentration in air and dispersion into the atmosphere through a stack. Piping, valves, and mechanical equipment were housed in chambers below grade; the holdup tanks were housed above grade in shielded cells of the building. Piping transported the waste gas to the F ARB where it exited to the atmosphere via a waste gas stack. The holdup tank chambers are inside the Fermi 1 Controlled Area, while the below grade chamber and the grade level valve operating room are outside the Fermi 1 Controlled Area boundary.

Construction of the Waste Gas Building includes reinforced concrete walls 12-18 inches thick, with the exception of the concrete block walled valve room. The roof is constructed of reinforced concrete 2 feet thick.

The area of the footprint ofWGB-Ol is approximately 303 square meters.

Modes and vectors for transmigration of contaminants include:

Any contamination encountered during the removal of piping within WGB-01.

Characterization data from past surveys proved insufficient for FSS planning activities.

A Characterization effort was implemented on October 1,2008 to include smears, scans and fixed-point measurements in WGB-Ol. An ambient correction was achieved by taking shielded readings at five locations in each room and the Mean of those data was calculated.

Tables 2-22 and 2-23 represent the results of the fixed-point readings taken on the floors, walls and ceiling during this survey effort. Smears were taken at each fixed-point location. Smears indicated no results greater than MDA. One-square meter beta scans were performed at each fixed-point location. No beta scan indicated greater than background. Gamma scans were performed in the general areas as well as locations where cracks and wall-to-floor junctures were present. No gamma scan indicated results greater than background.

2:-47

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 Table 2-22 WGB-01 Characterization Data Result Result Result.

Location

ýdpam/lOem 2)

Location (dpra/100croj Location (d n/100CM2

)

TANK ROOM 1 TANK ROOM 2 VALVE ROOM CHAR-WGB-01 -021-F-M 2786 CHAR-WGB-01-03 1-F-M 2834 CHAR-WGB-01-041-F-M 2409 CHAR-WGB-01-022-F-M 2957 CHAR-WGB-01-032-F-M 2847 CHAR-WGB-01-042-F-M 2769 CHAR-WGB-01-023-P-M 2891 CHAR-VVGB-0 l-033-F-M 2841 CHAR-WGB-0 1-043-F-M 2278 CHAR-WGB-01 -024-F-M' 2891 CHAR-WGB-01 -034-F-M

2991, CHAR-WGB-01 -044-F-M 2494 CHAR-WGB-0l -025-F-M 2819 CHAR-WGB-01-035-F-M 2782 CHAR-WGB-01-045-F-M 2180 CHAR-WGB-01 -026-F-M 2727 CHAR-WGB-01-036-F-M 2684 CHAR-WCTB-01-046-F-M 1983 CHAR-WGB-01 -027-F-M 3029 CHAR-WGB-01-037-F-M 2572 CHAR-WGB-01-047-F-M 2147

-CHAR-WGB-01-028-F-M 2983 CHAR-WGB-01-038-F-M 2651 CHAR-WGB-01-048-F-M 2278 CHAR-WGB-01-029-F-M 1999 CHAR-WGB-01-039-P-M 2769 CHAR-WGB-01-049-F-M 2180 CHAR-WGB-0 1-030-F-M 2445 CHAR-WGB-01-040-F-M 2743 CHAR-WGB-01-050-F-M 2173 Mean Ambient 1701 Mean Ambient 1678 Mean Ambient 1506 Ct. Mean 2753 Ct. Mean 2771 Ct. Mean 2289 Ct. Median 2855 Ct. Median 2775 Ct. Median 2229 Ct Sd Dy 32Ct.

Std. Dev.

118 Ct. Std. Dev.

221 F-M Fixed measurement Table 2-23 WGB-01 Lower Level Characterization Data Result.

.Result Location

ýId

=mrltooem 2

oain.:dmlOm 572' ROOM 1 572' ROOM 2 CHAR-WGB-01-001-F-M 2229 CHAR-WGB-01-01 1-F-M 2432 CHAR-WGB-01-002-F-M 2294 CHAR-WGB-01-012-F-M 2419 CHAR-WGB-017003-F-M 2327 CHAR-WGB-01-013-F-M 2465 CRAR-WGB-01-004-F-M 2163 CHAR-WGB-01-014-F-M 2445 CHAR-WGB-01-005-F-M 2203 CHAR-WGB-01-015-F-M 2150 CHAR-WGB-01-006-F-M 2255 CHAR-WGB-01-016-F-M 2399 CHAR-WGB-01-007-F-M 2170 CHAR-WGB-01-017-F-M 2026 CHAR-WGB-01-008-F-M 1777 CHAR-WGB-01 -018-F-M 1960 CHAR-WGB-01-009-F-M 2052 CHAR-WGB-01-019-F-M 2393 CHAR-WGB-01-0 10-F-M 2176 CHAR-WGB-01-020-F-M 2242 Mean Ambient 1489 Mean Ambient 1672 Ct. Mean 2165 Ct. Mean 2293 Ct. Median 2190 Ct. Median 2396 Ct. Std. Dev.

157 Ct. Std. Dev.

187 F-M Fixed measurement As a result of historical information, decommissioning activities performed and planned, and characterization survey results, WGB-01 is classified as a Class 2 area.

2-48 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 4 June 2011 Table 2-22 WGB-Ol Characterization Data Result

- - - - llj~l~.'*.'..........

...,'L ~atio~Si.**!;*ll*;.\\ ** ***<.Result>,":.}:".*

thc~tio~-::

~.--.' ** '.*.~~~Yioocm2r

'( dpmll OOcm2)

~oc~

'.. '(dp'ml1oociu2) ideation".......... -*.*.. --....... - '.

TANK ROOM 1 TANK ROOM 2 VALVE ROOM CHAR-WGB-OI-021-F-M 2786 CHAR-WGB-OI-031-F-M 2834 CHAR-WGB-OI-041-F-M 2409 CHAR-WGB-OI-022-F-M 2957 CHAR-WGB-OI-032-F-M 2847 CHAR-WGB-OI-042-F-M 2769 CHAR-WGB-OI-023-F-M 2891 CHAR-WGB-OI-033-F-M 2841 CHAR-WGB-O 1-043-F-M 2278 CHAR-WGB-OI-024-F-M 2891 CHAR-WGB-OI-034-F-M 2991 CHAR-WGB-OI-044-F-M 2494 CHAR-WGB-OI-025-F-M 2819 CHAR-WGB-OI-035-F-M 2782 CHAR-WGB-OI-045-F-M 2180 CHAR-WGB-O 1-026-F-M 2727 CHAR-WGB-OI-036-F-M 2684 CHAR-WGB-OI-046-F-M 1983 CHAR-WGB-O l-027-F-M 3029 CHAR-WGB-OI-037-F-M 2572 CHAR-WGB-OI-047-F-M 2147 CHAR-WGB-O 1-028-F-M 2983 CHAR-WGB-OI-03S-F-M 2651 CHAR-WGB-OI-04S-F-M 2278 CHAR-WGB-OI-029-F-M 1999 CHAR-WGB-OI-039-F-M 2769 CHAR-WGB-OI-049-F-M 2180 CHAR-WGB-O 1-030-F-M 2445 CHAR-WGB-OI-040-F-M 2743 CHAR-WGB-OI-050-F-M 2173 Mean Ambient 1701 Mean Ambient 1678 Mean Ambient 1506 Ct. Mean 2753 Ct. Mean 2771 Ct. Mean 2289 Ct. Median 2855 Ct. Median 2775 Ct. Median 2229 Ct. Std. Dey.

312 Ct. Std. Dey.

118 Ct. Std. Dey.

221 F-M = Fixed measurement Table 2-23 WGB-Ol Lower Level Characterization Data

.~; -":-"~

Result,.:~"l:*;: l.*

lioc~tilik':

i[:~:I~!lStltt ***..,.*..*..*

Location:..>

. *(dl)iriho(fcm~) **

. (dpmIlOOcm2) 572' ROOM 1 572' ROOM 2 CHAR-WGB-OI-OOI-F-M 2229 CHAR-WGB-OI-OII-F-M 2432 CHAR -WGB-O I-002-F-M 2294 CHAR-WGB-OI-012-F-M 2419 CHAR-WGB-Olc003-F-M 2327 CHAR-WGB-OI-O 13-F-M 2465 CHAR-WGB-OI-004-F-M 2163 CHAR-WGB-OI-014-F-M 2445 CHAR-WGB-OI-005-F-M 2203 CHAR-WGB-O 1-0 1 5-F-M 2150 CHAR -WGB-O 1-006-F-M 2255 CHAR-WGB-O 1-0 1 6-F-M 2399 CHAR-WGB-OI-007-F-M 2170 CHAR-WGB-OI-017-F-M 2026 CHAR-WGB-OI-OOS-F-M 1777 CHAR-WGB-OI-O 18-F-M 1960 CHAR-WGB-OI-009-F-M 2052 CHAR-WGB-OI-O 19-F-M 2393 CHAR-WGB-OI-OlO-F-M 2176 CHAR-WGB-OI-020-F-M 2242 Mean Ambient 1489 Mean Ambient 1672 Ct. Mean 2165 Ct. Mean 2293 ct. Median 2190 Ct. Median 2396 ct. Std. Dey.

157 Ct. Std. Dey.

187 F-M = Fixed measurement As a result of historical information, decommissioning activities performed and planned, and characterization survey results, WGB-Ol is classified as a Class 2 area.

2-48

Fermi 1 License Termination Plan Revision 0 Chapter 2 Site Characterization May 2009 2.1.8.16 IGB Inert Gas Building The Inert Gas Building housed the compressors, vapor trap, hold-up and vacuum tanks, valves, piping and other associated equipment for the purification and distribution of the argon cover gas system to the primary, secondary, and FARB cover gas systems. The Inert Gas Building has a first story of concrete construction and a second story of cinder block construction located immediately adjacent to the Sodium Service Building valve room. The Inert Gas Tunnel is part of this Survey Area.

The area of the footprint of IGB-01 (including the tunnel) is approximately 466 square meters.

Modes and vectors for transmigration of contaminants include:

SAny contamination encountered during the removal of piping and components within IGB-01.

Characterization data from past surveys proved insufficient for FSS planning activities.

A Characterization effort was implemented on October 7, 2008 to include smears, scans and fixed-point measurements in IGB-01. An ambient correction was achieved by taking shielded readings at five locations in the tank room and the Mean of those data was calculated.

Additionally, an ambient correction was achieved by taking shielded readings at five locations inside the tunnel and the Mean of those data was calculated. Table 2-24 represent the results of the fixed-point readings taken on the floors, walls and ceiling during this survey effort.

Smears were taken at each fixed-point location. Smears indicated no result greater than background. One-square meter beta scans were performed at each fixed-point location. No beta scan indicated greater than background. Gamma scans were performed in general areas (with the exception of the tunnel areas where gamma scans were inaccessible) as well as locations where cracks and wall-to-floor junctures were present. No gamma scan indicated results greater than background.

2-49 Fermi 1 License Termination Plan Chapter 2 Site Characterization 2.1.8.16 IGB-OI-Inert Gas Building Revision 0 May 2009 The Inert Gas Building housed the compressors, vapor trap, hold-up and vacuum tanks, valves, piping and other associated equipment for the purification and distribution of the argon cover gas system to the primary, secondary, and F ARB cover gas systems. The Inert Gas Building has a first story of concrete construction and a second story of cinder block construction located immediately adjacent to the Sodium Service Building valve room. The Inert Gas Tunnel is part ofthis Survey Area.

The area of the footprint ofIGB-O 1 (including the tunnel) is approximately 466 square meters.

Modes and vectors for transmigration of contaminants include:

Any contamination encountered during the removal of piping and components within IGB-OI.

Characterization data from past surveys proved insufficient for FSS planning activities.

A Characterization effort was implemented on October 7, 2008 to include smears, scans and fixed-point measurements in IGB-01. An ambient correction was achieved by taking shielded readings at five locations in the tank room and the Mean of those data was calculated.

Additionally, an ambient correction was achieved by taking shielded readings at five locations inside the tunnel and the Mean of those data was calculated. Table 2-24 represent the results of the fixed-point readings taken on the floors, walls and ceiling during this survey effort.

Smears were taken at each fixed-point location. Smears indicated no result greater than background. One-square meter beta scans were performed at each fixed-point location. No beta scan indicated greater than background. Gamma scans were performed in general areas (with the exception of the tunnel areas where gamma scans were inaccessible) as well as locations where cracks and wall-to-floor junctures were present. No gamma scan indicated results greater than background.

2-49

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 Table 2-24 IGB-01 Characterization Data Result

-Rsl Location dPRm/1O0c1112 Location d

/c 2)

TANK ROOM TUNhNEL CHAR-IGB-0 1-00 1-F-M 3638 CHAR-IOB-0 1-021 -F-M 2363 CHAR-IGB-01-002-F-M 3507 CHAR-IGB-01-022-F-M 2101 CHAR-IGB-01 -003-F-M 2163 CHAR-IGB-0 1-023-F-M 2239 CHAR-IGB-01 -004-F-M

'2144 CHAR-IGB-01-024-F-M 2193 CHAR-IGB-0 1-005-F-M 2229 CHAR{-IGB-01-025-F-M 2317 CHAR-IGB-01-006-F-M 2124 CHAR-IGB-01-026-F-M 2088 CHAR-IGB-0 1-007-F-M 2570 CHAR-IGB-01-027-F-M 2330 CHAR-IGB-01-008-F-M 2249 CHAR-IGB-01-028-F-M 2212 CHAR-IGB-01 -009-F-M 3114 CHAR-IGB-01 -029-F-M 2239 CHAR-IGB-0 1-0 10-F-M 3350 CHAR-IGB3-0 1-030-F-M 2402 CH{AR-IGB-01-01 1-F-M 2190 CHAR-IGB-01-03 1-F-M 2134 CHIAR-IGB-01-0 12-F-M 2058 CHAR-IGB-01-032-F-M 1990 CH{AR-IGB-0 1-013-F-M 2196 CHAR-IGB-01 -033-F-M 2271 CHAR-IGB-01-014-F-M 1973 CHAR-IGB-01-034-F-M 2049 CEAR-IGB-01-015-F-M 2249 CHAR-IGB-01-035-F-M 2487 CHAR-IGB-0 1-01 6-F-M 2281 CHAR-IGB-0 1-03 6-F-M 1990 CHAR-IGB-01 -0 17-F-M 2255 CHIAR-IGB-01-037-F-M 2625 CHAR-IGB-01 -01 8-F-M 2334 CHAR-IGB-01 -03 8-F-M 2108 CHAR-IGB-01 -0 19-F-M 2098 CHAR-IGB-01-039-F-M 2461 CHAR-IGB-01-020-F-M 2412 CHAR-IGB-01 -040-F-M 2127 Mean Ambient 1994 Mean Ambient 1762 Ct. Mean 2457 Ct. Mean 2236 Ct. Median 2249 Ct. Median 2226 Ct. Std. Dev.

509 Ct. Std. Dev.

172 F-M =Fixed measurement Fixed-point measurements inside the Inert Gas Building and tunnel were less than the most restrictive site-specific DCGL. As a result of historical information, decommissioning activities performed and planned and characterization surveys performed, IGB-O01 is classified as a Class 2 area.

2.1.9 HSA Findings EFl1, like all commercial U.S. nuclear power plants, was designed with multiple boundaries to contain the unit's radioactive contents within its many systems, components, and structures. Many of these systems and structures have been impacted due to routine operations and maintenance activities during the operational and post-operational history of the plant. All structures at EF1 have been impacted, however, due to the nature of a sodium cooled plant; the structures were minimally impacted during plant operations. Ancillary systems (feedwater, condensate, steam and oil) were essentially isolated from the primary sodium system by a double boundary during plant operations. Portions of these systems 2-50 Fermi 1 License Termination Plan Chapter 2 Site Characterization Table 2-24 IGB-Ol Characterization Data

-....... '< *. '/.;.

Lri~~tion

- - IN~~liI~'o~;~i)\\' ~ocati~Il *..* ::;' **,..*...

TANK ROOM TUNNEL CHAR-IGB-OI-00I-F-M 3638 CHAR-1GB-OI-021-F-M CHAR-IGB-O 1-002-F-M 3507 CHAR -IGB-O 1-022-F-M CHAR-IGB-01-003-F-M 2163 CHAR-IGB-OI-023-F-M CHAR-IGB-OI-004-F-M 2144 CHAR-IGB-OI-024-F~M CHAR-IGB-OI-005-F-M 2229 CHAR-1GB-OI-025-F-M CHAR-IGB-OI-006-F-M 2124 CHAR -I GB-O 1-026-F-M CHAR-IGB-01-007-F-M 2570 CHAR-1GB-01-027-F-M CHAR-IGB-OI-008-F-M 2249 CHAR-IGB-01-028-F-M CHAR-IGB-OI-009-F-M 3114 CHAR-IGB-01-029-F-M CHAR-IGB-01-010-F-M 3350 CHAR-IGB-01-030-F-M CHAR-IGB-OI-011-F-M 2190 CHAR-1GB-OI-031-F-M CHAR-IGB-OI-012-F-M 2058 CHAR-1GB-01-032-F-M CHAR-IGB-O 1-0 13-F-M 2196 CHAR-IGB-01-033-F-M CHAR-IGB-01-014-F-M 1973 CHAR-IGB-01-034-F-M CHAR-IGB-OI-015-F-M 2249 CHAR-1GB-OI-035-F-M CHAR-IGB-01-016-F-M 2281 CHAR-IGB-OI-036-F-M CHAR-IGB-01-017-F-M 2255 CHAR-IGB-OI-037-F-M CHAR-IGB-01-01 8-F-M 2334 CHAR-1GB-01-038-F-M CHAR-IGB-OI-019-F-M 2098 CHAR-IGB-01-039-F-M CHAR-IGB-OI-020-F-M 2412 CHAR-IGB-0l-040-F-M Mean Ambient 1994 Mean Ambient Ct. Mean 2457 Ct. Mean Ct. Median 2249 Ct. Median Ct. Std. Dev.

509 Ct. Std. Dev.

F-M = Fixed measurement R¢sjllt>,*:':*........

(dprri/l00Cin~).'.

2363 2101 2239 2193 2317 2088 2330 2212 2239 2402 2134 1990 2271 2049 2487 1990 2625 2108 2461 2127 1762 2236 2226 172 Revision 4 June 2011 Fixed-point measurements inside the Inert Gas Building and tunnel were less than the most restrictive site-specific DCGL. As a result of historical information, decommissioning activities performed and planned and characterization surveys performed, IGB-01 is classified as a Class 2 area.

2.1.9 HSA Findings EF1, like all commercial u.s. nuclear power plants, was designed with multiple boundaries to contain the unit's radioactive contents within its many systems, components, and structures. Many of these systems and structures have been impacted due to routine operations and maintenance activities during the operational and post-operational history of the plant. All structures at EF1 have been impacted, however, due to the nature of a sodium cooled plant; the structures were minimally impacted during plant operations. Ancillary systems (feedwater, condensate, steam and oil) were essentially isolated from the primary sodium system by a double boundary during plant operations. Portions of these systems 2-50

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 were surveyed and found to have no plant related activity; therefore these systems are classified as non-impacted and require no further survey effort. Since there is little evidence to suggest that plant-related activity is present in the interior areas of the structures above 6 feet in height (reinforced by the historical analysis and characterization surveys), the MARSSIM classification of these areas will be less restrictive.

2.1.10 HSA Conclusions The EF1 HSA provides sufficient evidence to support an Impacted Area classification for all structures and open land areas. EF1 ancillary systems shall be classified as Non-Impacted Areas and excluded from further investigation and survey actions. Table 2-3 summarizes the classifications for each area.

2.2 Hydrogeological Investigations The information contained in Section 2.2 of the LTP contains a brief summary description of the Conestoga-Rover & Associates report, "Site Conceptual Model Fermi 1, Rev. 1", the Golder Associates report "Report on Groundwater Characterization, Enrico Fermi 1 License Termination" and additional information being docketed in response to questions.

Detailed information on the Golder Report can be found in NRC Agency Document and Management System (ADAMS) ML081080041 and ML081080043.

2.2.1 Methods From November 2003 through December 2006, Golder Associates Inc. (Golder) and the Detroit Edison Company conducted a groundwater characterization program to test for possible historical radiological contamination in groundwater within Areas of Concern (AOC) at EF1. The characterization efforts included the following:

installation of monitor wells;

measurement of the hydraulic conductivity of the fill and natural geologic Sformations in which the monitor wells are set; measurements of groundwater elevations, and

collection and analysis of groundwater samples for possible radionuclides of concern.

The work was performed in accordance with the "Work Plan for Groundwater Characterization", through Revision 2, August 2005 (Golder, 2005). The work plan specifies the following:

Areas of Concern (AOC) with respect to possible historical releases of radioactive fluids and other possible contaminants to the subsurface based on former EF1 operations and waste routing systems.

2-51 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 4 June 2011 were surveyed and found to have no plant related activity; therefore these systems are classified as non-impacted and require no fUliher survey effort. Since there is little evidence to suggest that plant-related activity is present in the interior areas of the structures above 6 feet in height (reinforced by the historical analysis and characterization surveys), the MARSSIM classification of these areas will be less restrictive.

2.1.10 HSA Conclusions The EF1 HSA provides sufficient evidence to support an Impacted Area classification for all structures and open land areas. EF1 ancillary systems shall be classified as Non-Impacted Areas and excluded from further investigation and survey actions. Table 2-3 summarizes the classifications for each area.

2.2 Hydrogeological Investigations The information contained in Section 2.2 of the L TP contains a brief summary description of the Conestoga-Rover & Associates report, "Site Conceptual Model Fermi 1, Rev. I", the Golder Associates report "Report on Groundwater Characterization, Enrico Fermi 1 License Termination" and additional information being docketed in response to questions.

Detailed information on the Golder Report can be found in NRC Agency Document and Management System (ADAMS) ML081080041 and ML081080043.

2.2.1 Methods From November 2003 through December 2006, Golder Associates Inc. (Golder) and the Detroit Edison Company conducted a groundwater characterization program to test for possible historical radiological contamination in groundwater within Areas of Concern (AOC) at EF1. The characterization efforts included the following:

e installation of monitor wells; e

measurement of the hydraulic conductivity of the fill and natural geologic formations in which the monitor wells are set; e

measurements of groundwater elevations, and collection and analysis of groundwater samples for possible radionuclides of concern.

The work was performed in accordance with the "Work Plan for Groundwater Characterization", through Revision 2, August 2005 (Golder, 2005). The work plan specifies the following:

e Areas of Concern (AOC) with respect to possible historical releases of radioactive fluids and other possible contaminants to the subsurface based on former EF1 operations and waste routing systems.

2-51

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011

Locations of monitor wells in relation to the AOC.

Field methods that included drilling, well installation, hydraulic testing, and groundwater sampling.

The Quality Assurance and Quality Control methods that were used to conduct the characterization.

Schedule.

In 2010, an updated site conceptual groundwater model was developed by Conestoga-Rover & Associates, which was documented in Reference 2.6.17.

2.2.2 Site Geology and Hydrology 2.2.2.1 Hydrogeologic Characteristics

1. The pre-construction geological profile at EF1 consists of the following unconsolidated native sediments and the bedrock sequence:

o 575 feet datum to 568 feet datum (0 -7 feet): Soft black muck and peat.

568 feet datum to 563 feet datum (7 - 12 feet): Glaciolacustrine laminated gray clay and silt, with traces of humus (Glacial Lake Clay).

563 feet datum to 557 feet datum (12 - 18 feet): Hard gray to yellowish sandy clay (Glacial Till).

< 557 feet datum (>18 feet): Dolomitic bedrock of the Bass Islands Group.

During construction of the reactor building in 1956, approximately 27 feet of clay and crushed stone fill was added to the top of the bedrock in order to bring the ground up to elevation of near 590 feet MSL.

Outside the Controlled Area, approximately 10 feet of fill was added, bringing the existing ground elevation up to approximately 583.5 feet.

2-52 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 4 June 2011 Locations of monitor wells in relation to the AOC.

Field methods that included drilling, well installation, hydraulic testing, and groundwater sampling.

1\\1 The Quality Assurance and Quality Control methods that were used to conduct the characterization.

1\\1 Schedule.

In 2010, an updated site conceptual groundwater model was developed by Conestoga-Rover & Associates, which was documented in Reference 2.6.17.

2.2.2 Site Geology and Hydrology 2.2.2.1 Hydrogeologic Characteristics

1. The pre-construction geological profile at EFI consists of the following unconsolidated native sediments and the bedrock sequence:

o 575 feet datum to 568 feet datum (0 -7 feet): Soft black muck and peat.

e 568 feet datum to 563 feet datum (7 - 12 feet): Glaciolacustrine laminated gray clay and silt, with traces of humus (Glacial Lake Clay).

'" 563 feet datum to 557 feet datum (12 - 18 feet): Hard gray to yellowish sandy clay (Glacial Till).

It < 557 feet datum (>18 feet): Dolomitic bedrock ofthe Bass Islands Group.

During construction of the reactor building in 1956, approximately 27 feet of clay and crushed stone fill was added to the top of the bedrock in order to bring the ground up to elevation of near 590 feet MSL.

Outside the Controlled Area, approximately 10 feet of fill was added, bringing the existing ground elevation up to approximately 583.5 feet.

2-52

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011

2. Outside the major building structures, the current geologic units at the Station, in descending order, are approximately as follows:

586 to 566 feet datum: Clay Fill

566 to 563 feet datum: Glacial Lake Clay

563 to 557 feet datum: Glacial Till

< 557 feet datum: Dolomite bedrock (Bass Islands Group)

3. Immediately around major Station structures, more Permeable Fill is present. Fermi 1 drawings indicate the designed placement of Permeable Fill materials, including sand and crushed stone, from the surface to depths below the top of bedrock adjacent to some of the deeper structures such as the FARB and Reactor Building.

4. Groundwater elevations (and conversely, the periodic occurrence of dry wells) in the shallow wells indicate that the groundwater table in the shallow zone is perched on top of the clay fill. As such, continuous lateral flow does not occur in the shallow zone. Overall, the shallow zone groundwater elevations are higher than Lake Erie's and the site bedrock wells' water levels, indicating that the potential is for shallow groundwater to slowly penetrate downward.

5. The flow of groundwater is primarily downward percolation in the permeable fill surrounding Station structures.

6. Groundwater flow in the bedrock changes. It varies from being towards the south-south-east to being towards the south-south-west quadrant as described in Reference 2.6.17.

2.2.3 Groundwater Analytical Results

1. Based on a review of radionuclide concentrations detected in water samples collected at sumps, monitoring wells and background wells, impacts from Station operations are not likely present in waters beneath the Station.

2. Three intermediate wells and two additional deep wells were installed in 2011 to obtain additional data, since little monitoring was performed to the south-southwest of the facility or in the intermediate zone (e.g., Glacial Till or Glacial Lake Clay). Initial onsite laboratory analysis of new samples did not detect plant isotopes.

2-53 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 4 June 2011

2. Outside the major building structures, the CUlTent geologic units at the Station, in descending order, are approximately as follows:

586 to 566 feet datum: Clay Fill III 566 to 563 feet datum: Glacial Lake Clay CD 563 to 557 feet datum: Glacial Till III

< 557 feet datum: Dolomite bedrock (Bass Islands Group)

3. Immediately around major Station structures, more Permeable Fill is present.. Fermi 1 drawings indicate the designed placement of Permeable Fill materials, including sand and crushed stone, from the surface to depths below the top of bedrock adjacent to some of the deeper structures such as the F ARB and Reactor Building.

4. Groundwater elevations (and conversely, the periodic OCCUlTence of dry wells) in the shallow wells indicate that the groundwater table in the shallow zone is perched on top of the clay fill. As such, continuous lateral flow does not occur in the shallow zone. Overall, the shallow zone groundwater elevations are higher than Lake Erie's and the site bedrock wells' water levels, indicating that the potential is for shallow groundwater to slowly penetrate downward.

5. The flow of groundwater is primarily downward percolation in the permeable fill sUlTounding Station structures.

6. Groundwater flow in the bedrock changes. It varies from being towards the south-south-east to being towards the south-south-west quadrant as described in Reference 2.6.17.

2.2.3 Groundwater Analytical Results

1. Based on a review of radionuclide concentrations detected in water samples collected at sumps, monitoring wells and background wells, impacts from Station operations are not likely present in waters beneath the Station.

2. Three intermediate wells and two additional deep wells were installed in 2011 to obtain additional data, since little monitoring was performed to the south-southwest of the facility or in the intermediate zone (e.g., Glacial Till or Glacial Lake Clay). Initial onsite laboratory analysis of new samples did not detect plant isotopes.

2-53

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 2.3 Site Characterization Survey 2.3.1 Initial Characterization Surveys In support of the decommissioning activities at the Fermi 1 facility, radiological characterization surveys were contracted for selected areas in and around the facility, and performed during the months of October and November 2004. The purposes of these surveys were as follows:

a) evaluating the increase in ambient background radiation levels caused by Fermi 2 power operation and the resulting impact on detection levels and ability for performing decommissioning survey with Fermi 2 in operation, and b) characterizing radiological conditions for selected areas in and around Fermi 1 that were more likely to exhibit little to no contamination, commonly referred to as non-impacted or Class 3 MARSSIM areas.

An initial set of surveys were performed at Fermi 1 in late October with Fermi 2 at essentially full power operations. This set of data was to baseline the levels that reflected the influence from Fermi 2, predominantly from the 16N sky shine component. Following the Fermi 2 shutdown on November 6, 2004, follow-up surveys were performed for the same areas. These two data sets - one reflecting the impact from Fermi 2 operations and the second without - provide meaningful data for evaluating the overall impact that the increase in ambient radiation levels from Fermi 2 operations may have on performing the decommissioning surveys at Fermi 1. The type of surveys performed were those typical for a decommissioning project. Surface beta scans were performed for floor and roof areas. These scans predominantly examine surface contamination (within top few mm of the surface). Where volumetric contamination is the primary source of interest (such as top 15 cm for surface soil contamination), gamma walkover scans were performed. Outside grassy and gravel areas were surveyed for gamma radiation levels.

The areas included in the surveys were:

o Fuel and Repair Building (FARB) roofs (three total, beta surface scans),

Steam Generator Building roof (beta surface scans)

" Waste Gas Decay Tank Room (general floor area beta surface scans)

Sodium Building roof (beta surface scans)

Turbine Building roof (beta surface scans)

Outside areas, within the Radiologically Restricted Area (RRA) (gamma walkover scans)

Outside areas, outside the RRA (gamma walkover scans)

Turbine Building (general floor area beta surface scans)

Fuel and Repair Building Interior

Fuel Pools (general floor area beta surface scans) 2-54 Fermi 1 License Termination Plan Chapter 2 Site Characterization 2.3 Site Characterization Survey 2.3.1 Initial Characterization Surveys Revision 4 June 2011 In support of the decommissioning activities at the Fermi 1 facility, radiological characterization surveys were contracted for selected areas in and around the facility, and performed during the months of October and November 2004. The purposes of these surveys were as follows:

a) evaluating the increase in ambient background radiation levels caused by Fermi 2 power operation and the resulting impact on detection levels and ability for performing decommissioning survey with Fermi 2 in operation, and b) characterizing radiological conditions for selected areas in and around Fermi 1 that were more likely to exhibit little to no contamination, commonly referred to as non-impacted or Class 3 MARSSIM areas.

An initial set of surveys were performed at Fermi 1 in late October with Fermi 2 at essentially full power operations. This set of data was to baseline the leyels that reflected the influence from Fermi 2, predominantly from the 1~ sky shine component. Following the Fermi 2 shutdown on November 6, 2004, follow-up surveys were performed for the same areas. These two data sets - one reflecting the impact from Fermi 2 operations and the second without - provide meaningful data for evaluating the overall impact that the increase in ambient radiation levels from Fermi 2 operations may have on performing the decommissioning surveys at Fermi 1. The type of surveys performed were those typical for a decommissioning project. Surface beta scans were performed for floor and roof areas. These scans predominantly examine surface contamination (within top few mm of the surface). Where volumetric contamination is the primary source of interest (such as top 15 cm for surface soil contamination), gamma walkover scans were performed. Outside grassy and gravel areas were surveyed for gamma radiation levels.

The areas included in the surveys were:

., Fuel and Repair Building (F ARB) roofs (three total, beta surface scans),

@ Steam Generator Building roof (beta surface scans) o Waste Gas Decay Tank Room (general floor area beta surface scans) o Sodium Building roof (beta surface scans)

~ Turbine Building roof (beta surface scans)

(1) Outside areas, within the Radiologically Restricted Area (RRA) (gamma walkover scans) q) Outside areas, outside the RRA (gamma walkover scans)

(} Turbine Building (general floor area beta surface scans) o Fuel and Repair Building Interior II Fuel Pools (general floor area beta surface scans) 2-54

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011

Truck Bay (general floor area beta surface scans)

Trestle-way (cast car corridor between reactor building and FARB, general floor area beta surface scans)

Warm Room (Radiation Protection count room) exterior walls (beta surface scans)

Vent Room interior walls (beta surface scans)

Tables 2-25 and 2-26 provide a summary of the results of this characterization effort.

Appendix 2-C provides detailed results of this survey effort.

2-55 Fermi 1 License Termination Plan Chapter 2 Site Characterization III Truck Bay (general floor area beta surface scans)

Revision 4 June 2011 III Trestle-way (cast car corridor between reactor building and F ARB, general floor area beta surface scans)

III Warm Room (Radiation Protection count room) exterior walls (beta surface scans)

III Vent Room interior walls (beta surface scans)

Tables 2-25 and 2-26 provide a summary of the results of this characterization effort.

Appendix 2-C provides detailed results of this survey effort.

2-55

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 Table 2-25 Comparison of Ambient Levels for Beta Scans Fermi-2 Net Increase Building/Surface Operating Fermi-2 Shutdown (power over shutdown)

(cpm)

(cpma)

(percent)

FARB 1st Floor Roof 4773 +/- 542 3285 304 1488 +/- 621 45 +/-19%

FARB 2 nd Floor Roof 6371 +/- 783 3257 275 3114 +/- 830 96 25%

FARB3rd Floor Roof 6429 845 2964 392 3465 +/- 932 117 +31%

Steam Generator Bldg.

Roof 3660 294 1741 +/- 112 1910 315 110 18%

Waste Gas Tank Room Floor 2160 +/- 147 1952 +/- 121 208 190 11 9.7%

Sodium Bldg. Roof 3874 465 2685 +/- 217 1189 513 44 + 19%

Turbine Bldg. Roof 2802 227 1955 +/- 129 847 261 43 +/- 13%

Turbine Bldg.

Driveway 2347 227 1249 +/- 180 1098 290 88 +/- 23%

Turbine Bldg. 3rd Floor, HP Turbine 1963 +/- 114 1571 145 392 184 25%+ 12%

FARB East Fuel Pool Area 2602 +/- 335 2530 244 72 414 2.8 16%

FARB West Fuel Pool Area 2407 139 2344 161 63 +/- 213 2.7 9.1%

FARB Truck Bay 4006 767 2867 +/-1039 1139 +/-1291*

40 45%

Trestle-way 3430 353 2987 1430 443 +/- 1473*

15 +/- 49%

The area with elevated measurements for the shutdown survey results in a relatively high standard deviation value. These elevated measurements were not detected during the at-power survey. Removing these elevated measurements would provide a better dataset for comparison.

Table 2-26 Comparison of Ambient Levels for Gamma Scans Net Increase Fermi-2 Operating Fermi-2 Shutdown (power over shutdown)

Outside Area (cpm)

(cpm)

(percent)

East Courtyard 23,245 +/- 4734 4824 +/- 813 18,421 +/- 4803 380 +/- 96%

Turbine Bldg. Lawn 19,667 +/- 1797 6670 + 945 12,997 +/- 6908 190 +/- 100%

2.3.2 Recent Characterization Surveys 2.3.2.1 Organization and Responsibilities The site Radiation Protection Technicians, under the direction of the License Termination Manager, performed the site characterization. The Characterization Surveys were preformed in accordance with EF1 "Radiological Site Characterization Plan". The EF1 Health Physicist is 2-56 Fermi 1 License Termination Plan Chapter 2 Site Characterization Table 2-25 Revision 4 June 2011 Comparison of Ambient Levels for Beta Scans

,1

~,

'Fermi":2

',NetIncrease Building/Surface'.:, *..*..

()per~ting Fermi-2 Shutdown (power over shutdown),

(cpm)'

. (cpm)h, (cpm)

(percent)

F ARB 1 SI Floor Roof 4773 +/- 542 3285 +/- 304 1488 +/- 621 45 +/-19%

F ARB 2 na Floor Roof 6371 +/- 783 3257 +/- 275 3114+/-830 96 +/-25%

F ARB 3ra Floor Roof 6429 +/- 845 2964 +/- 392 3465 +/- 932 117 +/- 31%

Steam Generator Bldg.

Roof 3660 +/- 294 1741+/-112 1910 +/- 315 110 +/- 18%

Waste Gas Tank Room Floor 2160 +/- 147 1952 +/- 121 208 +/- 190 11 +/- 9.7%

Sodium Bldg. Roof 3874 +/- 465 2685 +/- 217 1189 +/- 513 44+/- 19%

Turbine Bldg. Roof 2802 +/- 227 1955 +/- 129 847 +/- 261 43 +/- 13%

Turbine Bldg.

Driveway 2347 +/- 227 1249 +/- 180 1098 +/- 290 88 +/-23%

Turbine Bldg. 3ra Floor, HP Turbine 1963 +/- 114 1571 +/- 145 392 +/- 184 25%+/- 12%

F ARB East Fuel Pool Area 2602 +/- 335 2530 +/- 244 72 +/- 414 2.8 +/- 16%

F ARB West Fuel Pool Area 2407 +/- 139 2344+/- 161 63 +/- 213 2.7+/-9.1%

F ARB Truck Bay 4006 +/- 767 2867 +/- 1039 1139+/- 1291*

40+/-45%

Trestle-way 3430 +/- 353 2987 +/- 1430 443 +/- 1473*

15 +/-49%

The area with elevated measurements for the shutdown survey results In a relattvely high standard deViatIOn value. These elevated measurements were not detected during the at-power survey. Removing these elevated measurements would provide a better dataset for comparison.

Table 2-26 Comparison of Ambient Levels for Gamma Scans Net Increase Fermi-2 Operating Fermi-2 Shutdown (power over shutdown)

Outside Area (cpm)

(cpm)

(percent)

East Courtyard 23,245 +/- 4734 4824 +/- 813 18,421 +/- 4803 380 +/-96%

Turbine Bldg. Lawn 19,667 +/- 1797 6670 +/- 945 12,997 +/- 6908 190 +/- 100%

2.3.2 Recent Characterization Surveys 2.3.2.1 Organization and Responsibilities The site Radiation Protection Technicians, under the direction of the License Telmination Manager, performed the site characterization. The Characterization Surveys were preformed in accordance with EF1 "Radiological Site Characterization Plan". The EF1 Health Physicist is 2-56

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 responsible to ensure that the Characterization Survey Plan is supported and implemented by the EF1 employees. The EF1 Health Physicist is responsible for ensuring that all decommissioning survey activities are performed by qualified personnel in accordance with approved procedures and implemented in coordination with, and support of, ongoing decommissioning activities. The Decommissioning Superintendent supplies the craft to support the Decommissioning Survey effort and coordinates activities with the Radiation Protection Supervisor (Operations). Figure 2-1 Depicts the EF1 Organizational Chart as it applies to the Characterization Survey.

EF1 Custodian EF1 Decommissioning Health Phyiscist Superintendant License Termination RP Supervisor Craft Manager FSS Engineer RP Technicians FSS Technicians Figure 2-1 EF1 License Termination Org. Chart 2.3.2.2 Characterization Data Categories One of the objectives of the characterization surveys was to be able to classify survey areas. As shown in Table 2-3 in Section 2.1.7.3 of this chapter, areas have been designated as: 1) Class 1 if residual radioactivity was greater than the DCGL or would likely be present based upon historical information, 2) Class 2 if residual radioactivity was present but less than the DCGL, and 3) Class 3 if residual radioactivity was not present or present at a small fraction of the DCGL.

2-57 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 4 June 2011 responsible to ensure that the Characterization Survey Plan is supported and implemented by the EF1 employees. The EF1 Health Physicist is responsible for ensuring that all decommissioning survey activities are performed by qualified personnel in accordance with approved procedures and implemented in coordination with, and support of, ongoing decommissioning activities. The Decommissioning Superintendent supplies the craft to support the Decommissioning Survey effort and coordinates activities with the Radiation Protection Supervisor (Operations). Figure 2-1 Depicts the EF1 Organizational Chart as it applies to the Characterization Survey.

EFl Custodian I

I EFl Decommissioning Health Phyiscist Superintendant J

I I

License Termination RP Supervisor -

Craft Manager FSS Engineer

.... RP Technicians FSS Technicians Figure 2-1 EF1 License Termination Org. Chart 2.3.2.2 Characterization Data Categories One of the objectives ofthe characterization surveys was to be able to classify survey areas. As shown in Table 2-3 in Section 2.1.7.3 of this chapter, areas have been designated as: 1) Class 1 if residual radioactivity was greater than the DCGL or would likely be present based upon historical information, 2) Class 2 if residual radioactivity was present but less than the DCGL, and 3) Class 3 if residual radioactivity was not present or present at a small fraction of the DCGL.

2-57

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 2.3.2.3 Characterization Survey Design The EF1 FSS Engineer designed the characterization surveys based on the Site Characterization Data Quality Objectives (DQOs) (see Appendix 2-B for the survey maps and results). Instrumentation used was identical to that which is planned to be used during FSS with similar MDCs. Gas proportional detectors were used for most of the surface measurements and scans. The detectors have a MylarTM window which is sensitive to the average beta energy emitted from the radionuclide mixture found in the various media. Additionally, volumetric samples of soil and concrete were also collected and counted using HPGe detectors with MDCs set at 10% of the DCGLs. Nal detectors were used to perform scans and direct measurements of soil, asphalt and some concrete areas. These surveys were used to identify regions of potentially contaminated soil and surfaces.

The actual dispositioning of systems at EF1 occurs on a case-by-case basis, with additional data collected when necessary during dismantlement activities to support the dispositioning decision-making.

This method of real-time waste management has proven to be cost-effective, much more so at EF1 than if an extensive characterization effort had been undertaken prior to beginning dismantlement. The decision was also made to begin the characterization effort to support the license termination process (remediation and eventually Final Status Survey) when areas were more accessible and could be directly surveyed (after system removal). Remediation and dismantlement tasks are scheduled and reviewed by EF1 personnel. Current and past radiological conditions that could affect the dismantlement or remediation processes are examined. Additionally, the area physical conditions that have or could have been affected radiologically are examined. Instructions and survey objectives are provided for adequate documentation of the characterization surveys and performance of dismantlement activities. The process data quality objectives include but are not limited to, instructions that delineate the types of surveys, samples and action levels for the tasks, and instructions and guidance for the remediation or dismantlement activities.

2.3.2.4 Instrument Selection, Use and Minimum Detectable Concentrations (MDCs)

Instrumentation used for characterization surveys were the same type that are planned to be used for FSS. Count times and scan rates were the same as those that will be used during FSS thus ensuring adequate MDCs. Table 2-27 lists the types of instruments that were used for characterization surveys along with the MDCs achieved. Table 2-28 provides the vendor laboratory minimum detectable activity (MDA) values.

2-58 Fermi 1 License Termination Plan Chapter 2 Site Characterization 2.3.2.3 Characterization Survey Design Revision 4 June 2011 The EF1 FSS Engineer designed the characterization surveys based on the Site Characterization Data Quality Objectives (DQOs) (see Appendix 2-B for the survey maps and results). Instrumentation used was identical to that which is planned to be used during FSS with similar MDCs. Gas proportional detectors were used for most of the surface measurements and scans. The detectors have a Mylar' window which is sensitive to the average beta energy emitted from the radionuclide.

mixture found in the various media. Additionally, volumetric samples of soil and concrete were also collected and counted using HPGe detectors with MDCs set at 10% of the DCGLs. NaI detectors were used to perform scans and direct measurements of soil, asphalt and some concrete areas. These surveys were used to identify regions of potentially contaminated soil and surfaces.

The actual dispositioning of systems at EF1 occurs on a case-by-case basis, with additional data collected when necessary during dismantlement activities to support the dispositioning decision-making.

This method of real-time waste management has proven to be cost-effective, much more so at EF1 than if an extensive characterization effort had been undertaken prior to beginning dismantlement. The decision was also made to begin the characterization effort to support the license termination process (remediation and eventually Final Status Survey) when areas were more accessible and could be directly surveyed (after system removal). Remediation and dismantlement tasks are scheduled and reviewed by EF1 personnel. Current and past radiological conditions that could affect the dismantlement or remediation processes are examined. Additionally, the area physical conditions that have or could have been affected radiologically are examined. Instructions and survey objectives are provided for adequate documentation of the characterization surveys and performance of dismantlement activities. The process data quality objectives include but are not limited to, instructions that delineate the types of surveys, samples and action levels for the tasks, and instructions and guidance for the remediation or dismantlement activities.

2.3.2.4 Instrument Selection, Use and Minimum Detectable Concentrations (MDCs)

Instrumentation used for characterization surveys were the same type that are planned to be used for FSS. Count times and scan rates were the same as those that will be used during FSS thus ensuring adequate MDCs. Table 2-27 lists the types of instruments that were used for characterization surveys along with the MDCs achieved. Table 2-28 provides the vendor laboratory minimum detectable activity (MDA) values.

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Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 Table 2-27 Typical Survey Instrumentation Sensitivities Instruments

Background

Count and Count Time

Background

Instrument Time Static Scan Detectors Radiation minutes)

(cpm)

Efficiency (minutes)

MDC MDC Model 43-68 Alpha 1

2 0.087 1

26 N/A Beta-Model 43-68 Gamma 1

243 0.2705 1

454 1082 Beta-Model 43-37 Gamma 1

607 0.2399 1

204 635 Beta-LN-177 Gamma N/A N/A 0.10 N/A N/A N/A Model SPA-3 Gamma 1

8000 0.62 0.04 N/A 4.73 0.15-0.30 0.40 0.05 pCi/g pCi/g HPGe Gamma Up to 60 N/A relative 10-60 volumetric vol.

Tennelec Low Bkg.

Alpha 10 0.1 0.35 11 N/A Counter Beta 10 1.0 0.48 1-10 16 N/A Table 2-28 Vendor Lab. Methods and MDAs MDA Test Technique Method (pCi/g)

Gamma radionuclides Gamma Spectroscopy LANL EM-9 0.1 Alpha Gas Flow Proportional EPA 900.0 4.0 Beta Gas Flow Proportional EPA 900.0 10.0 H-3 Liquid Scintillation EPA 906.0 Mod 11-55 C-14 Liquid Scintillation EPA EERF C 1.2-6.0 Fe-55 Liquid Scintillation DOE RESL Fe-1 1000-5000 Low Energy Gamma Ni-59 Spectroscopy DOE RESL Ni-1 1100-5500 Ni-63 Liquid Scintillation DOE RESL Ni-1 210-1050 Sr-90 Gas Flow Proportional EPA905.0 Mod 0.17-0.85 Tc-99 Liquid Scintillation DOE EML HASL 300 1.90-9.50 Pu-238-240 Alpha Spectroscopy DOE EML HASL 300 0.23-1.25 Pu-241 Liquid Scintillation DOE EML HASL 300 7.2-36.00 Am-241 Alpha Spectroscopy DOE EML HASL 300 0.21-1.05 Cm-242&243 Alpha Spectroscopy DOE EML HASL 300 16-80 Cm-243 Alpha Spectroscopy DOE EML HASL 300 0.32-1.60 2-59 Fermi 1 License Termination Plan Chapter 2 Site Characterization Table 2-27 Revision 4 June 2011 Typical Survey Instrumentation Sensitivities Instruments

Background

Count and Count Time

Background

Instrument Time Static Scan Detectors Radiation (minutes)

(cpm)

Efficiency (minutes)

MDC MDC Model 43-68 Alpha 1

2 0.087 1

26 N/A Beta-Model 43-68 Gamma 1

243 0.2705 1

454 1082 Beta-Model 43-37 Gamma 1

607 0.2399 1

204 635 Beta-LN-l77 Gamma N/A N/A 0.10 N/A N/A N/A Model SPA-3 Gamma 1

8000.

0.62 0.04 N/A 4.73 0.15-0.30 0040 0.05 pCi/g pCi/g HPGe Gamma Up to 60 N/A relative 10-60 volumetric vol.

Tennelec Low Bkg.

Alpha 10 0.1 0.35 11 N/A Counter Beta 10 1.0 0048 1-10 16 N/A Table 2-28 Vendor Lab. Methods and MDAs MDA Test Technique Method (pCi/g)

Gamma radionuclides Gamma Spectroscopy LANLEM-9 0.1 Alpha Gas Flow Pwportional EPA 900.0 4.0 Beta Gas Flow Proportional EPA 900.0 10.0 H-3 Liquid Scintillation EPA 906.0 Mod 11-55 C-14 Liquid Scintillation EPAEERFC 1.2-6.0 Fe-55 Liquid Scintillation DOE RESL Fe-1 1000-5000 Low Energy Gamma Ni-59 Spectroscopy DOE RESL Ni-l 1100-5500 Ni-63 Liquid Scintillation DOE RESL Ni-l 210-1050 Sr-90 Gas Flow Proportional EPA905.0 Mod 0.17-0.85 Tc-99 Liquid Scintillation DOE EML HASL 300 1.90-9.50 Pu-238-240 Alpha Spectroscopy DOE EML HASL 300 0.23-1.25 Pu-241 Liquid Scintillation DOE EML HASL 300 7.2-36.00 Am-241 Alpha Spectroscopy DOE EML HASL 300 0.21-1.05 Cm-242&243 Alpha Spectroscopy DOE EML HASL 300 16-80 Cm-243 Alpha Spectroscopy DOE EML HASL 300 0.32-1.60 2-59

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 2.3.2.5 Quality Assurance Instrumentation used for characterization surveys was calibrated by an off-site vendor using NIST-traceable sources of energies similar to those emitted by the nuclide fractions for the various media surveyed.

Instrumentation was source checked before and after survey measurements were made in accordance with approved site procedures.

The FSS Engineer, prior to accepting the data for characterization, evaluated instruments not passing a source check. Laboratory instruments were calibrated following the approved Fermi 2 Radiation Protection procedures. A fraction of the volumetric samples were collected as split samples for quality control purposes. 10% of the volumetric samples were designated as recounts. Split sampling and sample recounts were in accordance with EF1 procedure MEF201, "Final Status Survey Quality Assurance Project Plan (QAPP)."

2.3.2.6 Data Quality Objectives Data Quality Objectives (DQOs) were implemented for Characterization surveys in a similar manner as anticipated for Final Status Surveys, however, the goal of the characterization is contamination quantification and delineation of the nuclide suite, whereas the FSS goal is comparison of data against the Null Hypothesis. Characterization surveys were designed to gather the appropriate data using the DQO process as outlined in MARSSIM, Appendix D. The seven steps in the DQO development process are:

1) State the problem,

2) Identify the decision,

3) Identify inputs to the decision,

4) Define the study boundaries,

5) Develop a decision rule,

6) Specify limits on decision errors, and

7) Optimize the design for obtaining data.

The DQOs for site characterization included identifying the types and quantities of media to collect. Since the scenarios used for dose modeling were the Building Occupancy and Resident Farmer scenarios, sample collection was concentrated on structure materials and surrounding soils. Building concrete was sampled by obtaining volumetric samples (additional volumetric sampling will be performed when the areas of interest become available). Soils were also sampled volumetrically. Enough measurements (typically 10 to 15 measurements per area) were obtained to achieve statistically significant results so that the mean and maximum activity as well as the sample standard deviation could be determined. Direct measurements and scans of concrete surfaces were also made using the same instruments and MDCs as those that are planned to be used for FSS. A percentage of samples of each 2-60 Fermi 1 License Termination Plan Chapter 2 Site Characterization 2.3.2.5 Quality Assurance Revision 4 June 2011 Instrumentation used for characterization surveys was calibrated by an off-site vendor using NIST -traceable sources of energies similar to those emitted by the nuclide fractions for the various media surveyed.

Instrumentation was source checked before and after survey measurements were made in accordance with approved site procedures.

The FSS Engineer, prior to accepting the data for characterization, evaluated instruments not passing a source check. Laboratory instruments were calibrated following the approved Fermi 2 Radiation Protection procedures. A fraction ofthe volumetric samples were collected as split samples for quality control purposes. 10% of the volumetric samples were designated as recounts. Split sampling and sample recounts were in accordance with EFI procedure MEF201, "Final Status Survey Quality Assurance Project Plan (QAPP)."

2.3.2.6 Data Quality Objectives Data Quality Objectives (DQOs) were implemented for Characterization surveys in a similar manner as anticipated for Final Status Surveys, however, the goal of the characterization is contamination quantification and delineation of the nuclide suite, whereas the FSS goal is comparison of data against the Null Hypothesis. Characterization surveys were designed to gather the appropriate data using the DQO process as outlined in MARSSIM, Appendix D. The seven steps in the DQO development process are:

1) State the problem,

2) Identify the decision,

3) Identify inputs to the decision,

4) Define the study boundaries,

5) Develop a decision rule,

6) Specify limits on decision errors, and

7) Optimize the design for obtaining data.

The DQOs for site characterization included identifying the types and quantities of media to collect. Since the scenarios used for dose modeling were the Building Occupancy and Resident Farmer scenarios, sample collection was concentrated on structure materials and surrounding soils. Building concrete was sampled by obtaining volumetric samples (additional volumetric sampling will be performed when the areas of interest become available). Soils were also sampled volumetrically. Enough measurements (typically 10 to 15 measurements per area) were obtained to achieve statistically significant results so that the mean and maximum activity as well as the sample standard deviation could be determined. Direct measurements and scans of concrete surfaces were also made using the same instruments and MDCs as those that are planned to be used for FSS. A percentage of samples of each 2-60

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June2011 type of media were sent for HTD radionuclide analysis. Samples were also collected from the interior surfaces of ancillary piping.

2.3.3 Survey Findings and Results Survey categories consist of surfaces, structures and environs present at EF1.

Several areas of the site were specifically targeted for detailed sampling and surveys. The areas were either'known or suspected to have been contaminated by plant operations or decommissioning. The remainder of the site received general sampling and surveys to determine whether structures or soils were contaminated and to what extent. Appendix 2-B illustrates the survey areas and locations described in this chapter.

2.3.3.1 Surfaces, Structures and Soils Surfaces and structures include building interiors and exteriors of the associated structures and if applicable, the exterior surfaces of systems or components because these surfaces have the same potential for residual levels of radioactive material as the building surfaces in which they are located. Land areas were surveyed and sampled to detect the presence and extent of soil contamination.

Over 1332 beta scan and direct measurements have been taken in EF1 during the 2008 characterization survey.

40 soil samples were taken from open land areas within and outside of the EF1 Controlled Area. Five of these samples were sent off-site to a laboratory for analysis of HTD radionuclides.

A concrete sample taken from the inner Biowall concrete was sent off-site for analysis of HTD nuclides as well as counted on site for activation.

All samples submitted to the vendor laboratory were analyzed for the entire nuclide suite. The nuclide suite includes those nuclides found in Chapter 6 of this LTP.

Groundwater analysis results from the site monitoring wells were provided in Section 2.2.4.

2.3.3.2 Ancillary Systems Due to the nature of a Liquid Metal Fast Breeder Reactor (LMFBR) ancillary systems such as the feedwater, condensate, steam, and lubricating oil systems are not expected to be impacted by plant operations. In an effort to verify the non-impacted classification of these systems, a survey was performed consisting of scans, volumetric sampling and smears. The ancillary systems were accessed at various 2-61 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 4 June 2011 type of media were sent for HTD radionuclide analysis. Samples were also collected from the interior surfaces of ancillary piping.

2.3.3 Survey Findings and Results Survey categories consist of surfaces, structures and environs present at EF1.

Several areas of the site were specifically targeted for detailed sampling and surveys. The areas were either 'known or suspected to have been contaminated by plant operations or decommissioning. The remainder of the site received general sampling and surveys to determine whether structures or soils were contaminated and to what extent. Appendix 2-B illustrates the survey areas and locations described in this chapter.

2.3.3.1 Surfaces, Structures and Soils Surfaces and structures include building interiors and exteriors of the associated structures and if applicable, the exterior surfaces of systems I

or components because these surfaces have the same potential for residual levels of radioactive material as the building surfaces in which they are located. Land areas were surveyed and sampled to detect the presence and extent of soil contamination.

Over 1332 beta scan and direct measurements have been taken in EF1 during the 2008 characterization survey.

40 soil samples were taken from open land areas within and outside of the EF1 Controlled Area. Five of these samples were sent off-site to a laboratory for analysis of HTD radionuclides.

A concrete sample taken from the inner Biowall concrete was sent off-site for analysis of HTD nuclides as well as counted on site for activation.

All samples submitted to the vendor laboratory were analyzed for the entire nuclide suite. The nuclide suite includes those nuclides found in Chapter 6 of this L TP.

Groundwater analysis results from the site monitoring wells were provided in Section 2.2.4.

2.3.3.2 Ancillary Systems Due to the nature of a Liquid Metal Fast Breeder Reactor (LMFBR) ancillary systems such as the feedwater, condensate, steam, and lubricating oil systems are not expected to be impacted by plant operations. In an effort to verify the non-impacted classification of these systems, a survey was performed consisting of scans, volumetric sampling and smears. The ancillary systems were accessed at various 2-61

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 locations throughout the turbine building. No scan or volumetric sample identified the presence of plant-related contamination.

2.3.4 Ambient and Background The National Council on Radiation Protection & Measurements (NCRP) addresses deposition of Cs-137 from fallout in Reference 2.6.16, Section 3.2.

Using the values in the NCRP report, with conservative assumptions, the expected mean deposition of Cs-137 in this region of the country is 0.35 pCi/g to 1.2 pCi/g, depending on depth of the sample.

Additionally, Big Rock Point (BRP) performed a study in northern Michigan which would be reasonably representative of the levels found at EF1. As a result of the 2000 BRP study, Cs-137 average activity 0.48 pCi/g to 0.54 pCi/g with a log-normal standard deviation of 0.79 pCi/g would be expected in Michigan.

Adjusting the reported data for radioactive decay to 2008 results in current background values of 0.39 pCi/g to 0.44 pCi/g.

Soil samples collected and analyzed during site characterization within or adjacent to the Controlled Area showed a mean Cs-137 activity 0.11 pCi/g and a maximum Cs-137 activity 0.45 pCi/g. For purposes of decommissioning, background Cs-137 activities in soil should be considered to be approximately 0.39 pCi/g to 1.2 pCi/g.

Ambient radiation levels are present at EF1 due to the operation of Fermi 2. As can be seen by the data comparison shown in section 2.3.1, the ambient influence due to Fermi 2 operation can contribute significantly to the readings taken at EF1.

Readings within the interior of buildings are not impacted as significantly as the reading taken exterior to the structures. As a result of this ambient contribution from Fermi 2 operation, beta scans and fixed-point measurements will be compensated by the use of ambient correction. A series of shielded beta readings will be taken at various locations within a room or building and the mean value will be subtracted from the unshielded readings taken. For gamma scans (with SPA-3 sodium iodide detector), portable shielding or other methods of reducing the ambient levels will be utilized as needed. Ambient gamma radiation from the operation of Fermi 2 and the methodology for the ambient correction are further explained in Section 5.4.3.1 of this LTP.

2.3.5 Waste Volumes and Activities Chapter 3 of this LTP presents the waste volumes and activities.

2.4 Continuing Characterization As previously stated, characterization data will be collected as necessary throughout the project. Results of future characterization sample analyses will be evaluated to determine the impact, if any, on the radionuclide identities, nuclide fractions and the classification of structures, soils and other site media.

2-62 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 4 June 2011 locations throughout the turbine building. No scan or volumetric sample identified the presence of plant-related contamination.

2.3.4 Ambient and Background The National Council on Radiation Protection & Measurements (NCRP) addresses deposition ofCs-137 from fallout in Reference 2.6.16, Section 3.2.

Using the values in the NCRP report, with conservative assumptions, the expected mean deposition ofCs-137 in this region ofthe country is 0.35 pCi/g to 1.2 pCi/g, depending on depth of the sample.

Additionally, Big Rock Point (BRP) performed a study in northern Michigan which would be reasonably representative of the levels found at EF 1. As a result of the 2000 BRP study, Cs-137 average activity 0.48 pCi/g to 0.54 pCi/g with a log-normal standard deviation of 0.79 pCi/g would be expected in Michigan.

Adjusting the reported data for radioactive decay to 2008 results in current background values of 0.39 pCi/g to 0.44 pCi/g.

Soil samples collected and analyzed during site characterization within or adjacent to the Controlled Area showed a mean Cs-137 activity 0.11 pCi/g and a maximum Cs:'137 activity 0.45 pCi/g. For purposes of decommissioning, background Cs-13 7 activities in soil should be considered to be approximately 0.39 pCi/g to 1.2 pCi/g.

Ambient radiation levels are present at EFI due to the operation of Fermi 2. As can be seen by the data comparison shown in section 2.3.1, the ambient influence due to Fermi 2 operation can contribute significantly to the readings taken at EF1.

Readings within the interior of buildings are not impacted as significantly as the reading taken exterior to the structures. As a result of this ambient contribution from Fermi 2 operation, beta scans and fixed-point measurements will be compensated by the use of ambient correction. A series of shielded beta readings will be taken at various locations within a room or building and the mean value will be subtracted from the unshielded readings taken. For gamma scans (with SPA-3 sodium iodide detector), portable shielding or other methods of reducing the ambient levels will be utilized as needed. Ambient gamma radiation from the operation of Fermi 2 and the methodology for the ambient correction are further explained in Section 5.4.3.1 ofthis LTP.

2.3.5 Waste Volumes and Activities Chapter 3 of this L TP presents the waste volumes and activities.

2.4 Continuing Characterization As previously stated, characterization data will be collected as necessary throughout the project. Results of future characterization sample analyses will be evaluated to determine the impact, if any, on the radionuclide identities, nuclide fractions and the classification of structures, soils and other site media.

2-62

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 2.5 Summary The characterization data collected and analyzed to date are of sufficient quantity and quality to provide the basis for the initial classification of survey areas, planning remediation activities, estimating radiological waste types and volumes, and for the development of DCGLs. However, characterization is an ongoing process that will continue as necessary during decommissioning.

2.6 References 2.6.1 Big Rock Point Nuclear Plant, License Termination Plan, Section 2.3.3, April 2003 2.6.2 C&M Department Maintenance 2.6.3 Chesapeake Nuclear Services, Inc., Fermi 1 Radiological Characterization Surveys, March 2005 2.6.4 Enrico Fermi Atomic Power Plant, Unit 1, Fermi 1 Safety Analysis Report, November 2006 2.6.5 Enrico Fermi Atomic Power Plant, Unit 1, Fermi 1 Manual 2.6.6 Enrico Fermi Atomic Power Plant, Unit 1, Historical Site Assessment 2.6.7 Fermi 1 Decommissioning Evaluation Report, June 1997 2.6.8 Fermi 1 Shift Logs, August 1963 to September 1995 2.6.9 Fermi 1 Operating Reports, August 1963 to December 1975 2.6.10 Golder Associates, Inc., Report on Groundwater Characterization, June 2007 2.6.11 Power Reactor Development Company, Technical Information and Hazards Summary Report 2.6.12 Technical Based Document, (TBD) NESF-08-0018, Radionuclide Selection for DCGL Development 2.6.13 U.S. Nuclear Regulatory Commission NUREG-1575, Revision 1, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM), August 2000 2.6.14 U.S. Nuclear Regulatory Commission NUREG/CR-2082 - Monitoring for Compliance with Decommissioning Termination Survey Criteria 2.6.15 U.S. Nuclear Regulatory Commission NUREG-0586, Final Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities (FGEIS),

August 1988 2.6.16 National Council on Radiation Protection & Measurements, NCRP Report No.

154, Cesium-137 in the Environment: Radioecology and Approaches to Assessment and Management, 2007 2.6.17 Conestoga-Rovers & Associates, Site Conceptual Model Fermi 1, Revision 1, January 2011 2-63 Fermi 1 License Termination Plan Chapter 2 Site Characterization 2.5 Summary Revision 4 June 2011 The characterization data collected and analyzed to date are of sufficient quantity and quality to provide the basis for the initial classification of survey areas, planning remediation activities, estimating radiological waste types and volumes, and for the development of DCGLs. However, characterization is an ongoing process that will continue as necessary during decommissioning.

2.6 References 2.6.1 Big Rock Point Nuclear Plant, License Termination Plan, Section 2.3.3, April 2003 2.6.2 C&M Department Maintenance 2.6.3 Chesapeake Nuclear Services, Inc., Fermi 1 Radiological Characterization Surveys, March 2005 2.6.4 Enrico Fermi Atomic Power Plant, Unit 1, Fermi 1 Safety Analysis Report, November 2006 2.6.5 Enrico Fermi Atomic Power Plant, Unit 1, Fermi 1 Manual 2.6.6 Enrico Fermi Atomic Power Plant, Unit 1, Historical Site Assessment 2.6.7 Fermi 1 Decommissioning Evaluation Report, June 1997 2.6.8 Fermi 1 Shift Logs, August 1963 to September 1995 2.6.9 Fermi 1 Operating Reports, August 1963 to December 1975 2.6.10 Golder Associates, Inc., Report on Groundwater Characterization, June 2007 2.6.11 Power Reactor Development Company, Technical Information and Hazards Summary Report 2.6.12 Technical Based Document, (TBD) NESF-08-0018, Radionuelide Selectionfor DCGL Development 2.6.13 U.S. Nuclear Regulatory Commission NUREG-1575, Revision 1, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM), August 2000 2.6.14 U.S. Nuclear Regulatory Commission NUREG/CR-2082 - Monitoringfor Compliance with Decommissioning Termination Survey Criteria 2.6.15 U.S. Nuclear Regulatory Commission NUREG-0586, Final Generic Environmental Impact Statement on Decommissioning ofNuelear Facilities (FGEISj, August 1988 2.6.16 National Council on Radiation Protection & Measurements, NCRP Report No.

154, Cesium-137 in the Environment: Radioecology and Approaches to Assessment and Management, 2007 2.6.17 Conestoga-Rovers & Associates, Site Conceptual j\\lfodel Fermi 1, Revision 1, January 2011 2-63

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 Figure 2-2 EF1 Survey Area Designations 2-64 Fermi 1 License Termination Plan Chapter 2 Site Characterization Figure 2-2 EFI Survey Area Designations 2-64 Revision 4 June 2011

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 surface activity DCGLs. Direct measurements can then be performed on the underlying surface after removal of the coating.

The thickness of the layer of building surface to be removed as a sample should be consistent with the development of the EF1 site model and the DCGLs (i.e. <10mm in depth).

5.4.2.5 Soils Soil will receive scan surveys at the coverage level described in Table 5-4 and volumetric samples will be taken at designated locations. Surface soil samples will normally be taken at a depth of 0 to 15 cm. Samples will be collected and prepared in accordance with approved procedures.

5.4.2.5.1 Scans Open land areas are scanned for gamma emitting nuclides. The gamma emitters are used as surrogates for the HTD radionuclides. Sodium iodide detectors are typically used for scanning. For detectors such as the SPA-3, the detector is held close to the ground surface (-6 cm or 2.5 in.) and is moved at a speed of 0.5 m/sec, traversing each square meter 3 times. The area covered by scan measurements is based on the survey unit classification as described in Section 5.3.2.

5.4.2.5.2 Volumetric Samples Soil materials are analyzed by gamma spectroscopy. Soil samples of approximately 1,500 grams are normally collected from the surface layer (top 15 cm). Sample preparation includes removing extraneous material, homogenizing, and drying the soil for gamma isotopic analysis. Separate containers are used for each sample and each container is moved through the analysis process following site procedures.

Samples are split when required by the applicable quality control procedures. If a survey area has already been excavated and remediated to the soil DCGL, this area will be treated as surface soil, and the FSS will be performed on the excavated area. Soil samples will be collected to depths at which there is high confidence that deeper samples will not result in higher concentrations. Alternatively, a sodium-iodide detector of sufficient sensitivity to detect DCGL concentrations may be utilized to identify the presence or absence of subsurface contamination, and the extent of such contamination. If the detector identifies the presence of contamination at a significant fraction of the DCGL, confirmatory investigation and analyses of soil samples of the suspect areas will be 5-39 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 4 June 2011 surface activity DCGLs. Direct measurements can then be performed on the underlying surface after removal of the coating.

The thickness of the layer of building surface to be removed as a sample should be consistent with the development ofthe EFI site model and the DCGLs (i.e. <10mm in depth).

5.4.2.5 Soils Soil will receive scan surveys at the coverage level described in Table 5-4 and volumetric samples will be taken at designated locations. Surface soil samples will normally be taken at a depth of 0 to 15 cm. Samples will be collected and prepared in accordance with approved procedures.

5.4.2.5.1 Scans Open land areas are scanned for gamma emitting nuclides. The gamma emitters are used as surrogates for the HTD radionuclides. Sodium iodide detectors are typically used for scanning. For detectors such as the SPA-3, the detector is held close to the ground surface (~6 cm or 2.5 in.) and is moved at a speed of 0.5 m/sec, traversing each square meter 3 times. The area covered by scan measurements is based on the survey unit classification as described in Section 5.3.2.

5.4.2.5.2 Volumetric Samples Soil materials are analyzed by gamma spectroscopy. Soil samples of approximately 1,500 grams are normally collected from the surface layer (top 15 cm). Sample preparation includes removing extraneous material, homogenizing, and drying the soil for gamma isotopic analysis. Separate containers are used for each sample and each container is moved through the analysis process following site procedures.

Samples are split when required by the applicable quality control procedures. If a survey area has already been excavated and remediated to the soil DCGL, this area will be treated as surface soil, and the FSS will be performed on the excavated area. Soil samples will be collected to depths at which there is high confidence that deeper samples will not result in higher concentrations. Alternatively, a sodium-iodide detector of sufficient sensitivity to detect DCGL concentrations may be utilized to identify the presence or absence of subsurface contamination, and the extent of such contamination. If the detector identifies the presence of contamination at a significant fraction of the DCGL, confirmatory investigation and analyses of soil samples of the suspect areas will be 5-39

Fermi 1 License Termination Plan Revision 0 Chapter 2 Site Characterization May 2009 performed. All subsurface sampling will be performed in accordance with the guidance in Section G.2.1 of NUREG-1757, Volume 2. The sample size for subsurface samples will be determined using the same methods described for surface soil. Per NUREG-1757, Volume 2, scanning is not applicable to subsurface areas; however, EF1 Final Status Surveys will employ scanning techniques commensurate with the survey unit classification. Scanning subsurface soils, where accessible, as an excavated surface, will demonstrate compliance with site release criteria.

5.4.3 Specific Survey Area Considerations 5.4.3.1 Pavement-Covered Areas Survey of paved areas will be required along the roadways providing ingress and egress to EF1 (e.g. FARB, west yard entrance, turbine building entrance, etc.). The survey design of paved areas will be based on soil survey unit sizes since they are outdoor areas where the exposure scenario is most similar to direct radiation from surface soil. The applicable DCGL will be the soil DCGL. Scan and static gamma and beta-gamma surveys are determined by the survey unit design. Samples will be obtained of not only the asphalt, but of the soil present under the asphalt. Paved areas may be separate survey units or they may be incorporated into surveys of adjacent open land areas of like classification.

5.4.3.2 Stored Bulk Materials Excavated soil may be reused onsite. Prior to reuse, excavated soil will be characterized to determine its suitability. Any surface scanning or volumetric analyses will be directly compared with DCGL values.

Controls will be instituted to prevent mixing of soils from more restrictive survey area classifications (e.g., Class 2 material could be used in either Class 1 or 2 areas and Class 1 material could only be used in Class 1 areas). Soils satisfying the criteria for unrestricted release may be stockpiled for use as EF1 onsite backfill material.

The one area that would need to be separately evaluated is if the decision is made to leave sand, steel shot or other materials within or outside of existing structures. There are no plans to dispose of concrete building rubble onsite as part of Fermi 1 decommissioning, since the buildings will remain standing. However, there are materials such as sand and steel shot that were sealed behind walls or in penetrations during plant operations. Some needed to be removed to gain access to areas for equipment removal. Sand will need to be removed because the walls it 5-40 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 0 May 2009 performed. All subsurface sampling will be performed in accordance with the guidance in Section G.2.1 ofNUREG-1757, Volume 2. The sample size for subsurface samples will be determined using the same methods described for surface soil. Per NUREG-1757, Volume 2, scanning is not applicable to subsurface areas; however, EF1 Final Status Surveys will employ scanning techniques commensurate with the survey unit classification. Scanning subsurface soils, where accessible, as an excavated surface, will demonstrate compliance with site release criteria.

5.4.3 Specific Survey Area Considerations 5.4.3.1 Pavement-Covered Areas Survey of paved areas will be required along the roadways providing ingress and egress to EF1 (e.g. F ARB, west yard entrance, turbine building entrance, etc.). The survey design of paved areas will be based on soil survey unit sizes since they are outdoor areas where the exposure scenario is most similar to direct radiation from surface soil. The applicable DCGL will be the soil DCGL. Scan and static gamma and beta-gamma surveys are determined by the survey unit design. Samples will be obtained of not only the asphalt, but of the soil present under the asphalt. Paved areas may be separate survey units or they may be incorporated into surveys of adjacent open land areas oflike classification.

5.4.3.2 Stored Bulk Materials Excavated soil may be reused onsite. Prior to reuse, excavated soil will be characterized to determine its suitability. Any surface scanning or volumetric analyses will be directly compared with DCGL values.

Controls will be instituted to prevent mixing of soils from more restrictive survey area classifications (e.g., Class 2 material could be used in either Class 1 or 2 areas and Class 1 material could only be used in Class 1 areas). Soils satisfying the criteria for unrestricted release may be stockpiled for use as EF 1 onsite backfill material.

The one area that would need to be separately evaluated is if the decision is made to leave sand, steel shot or other materials within or outside of existing structures. There are no plans to dispose of concrete building rubble onsite as part of Fermi 1 decommissioning, since the buildings will remain standing. However, there are materials such as sand and steel shot that were sealed behind walls or in penetrations during plant operations. Some needed to be removed to gain access to areas for equipment removal. Sand will need to be removed because the walls it 5-40

Fermi 1 License Termination Plan Revision 0 Chapter 5 Final Status Survey Plan March 2009 1.38V4 MDCstructural surface scan(dpm/100cm2) =

Equation 5-8 where:

B = number of background counts during the count interval t,

p = surveyor efficiency, ei = instrument efficiency for the emitted radiation (cpm per dpm),

es = source efficiency (intensity) in emissions per disintegration, A = sensitive area of the detector (cm2), and t = time interval of the observation while the probe passes over the source (minutes).

The numerator in Equation 5-8 represents the minimum detectable count rate that the observer would "see" at the performance level represented by the sensitivity index. The surveyor efficiency (p) will be taken to be 0.5, as recommended by Section 6.7.1 of NUREG-1507. The factor of 100 corrects for probe areas that are not 100 cm 2. In the case of a scan measurement, the counting interval is the time the probe is actually over the source of radioactivity. This time depends on scan speed, the size of the source, and the fraction of the detector's sensitive area that passes over the source; with the latter depending on the direction of probe travel. The source efficiency term (es) in Equation 5-8 may be adjusted to account for effects such as self absorption, as appropriate.

5.4.4.4.3 Total Efficiency (et) and Source Efficiency (e,) for Concrete Contamination The source term inventory on contaminated concrete appears to be primarily located within the top few millimeters of the concrete surface. The practical application of choosing the proper instrument efficiency may be determined by averaging the surface variation (peaks and valleys narrower than the length of the detector) and adding 0.5 inches, the spacing that should be maintained between the detector and the highest peaks of the surface. Selection of the source to detector distance is based on Table 5-11 that best reflects the predetermined geometry.

5-47 Fermi 1 License Termination Plan Chapter 5 Final Status Survey Plan Revision 0 March 2009 5.4.4.4.3 2

1.3S{B MDCstructuralsur/acescanCdpm/l00cm ) -

A fP ei es (100) t Equation 5-8 where:

B = number of background counts during the count interval t,

p = surveyor efficiency, ei = instrument efficiency for the emitted radiation (cpm per dpm),

es = source efficiency (intensity) in emissions per disintegration, A = sensitive area of the detector (cm2), and t = time interval of the observation while the probe passes over the source (minutes).

The numerator in Equation 5-8 represents the minimum detectable count rate that the observer would "see" at the performance level represented by the sensitivity index. The surveyor efficiency (P) will be taken to be 0.5, as recommended by Section 6.7.1 ofNUREG-1507. The factor of 100 corrects for probe areas that are not 100 cm2* In the case of a scan measurement, the counting interval is the time the probe is actually over the source of radioactivity. This time depends on scan speed, the size of the source, and the fraction of the detector's sensitive area that passes over the source; with the latter depending on the direction of probe travel. The source efficiency term (es) in Equation 5-8 may be adjusted to account for effects such as self absorption, as appropriate.

Total Efficiency (el) and Source Efficiency (es) for Concrete Contamination The source term inventory on contaminated concrete appears to be primarily located within the top few millimeters of the concrete surface. The practical application of choosing the proper instrument efficiency may be determined by averaging the surface variation (peaks and valleys narrower than the length of the detector) and adding 0.5 inches, the spacing that should be maintained between the detector and the highest peaks of the surface. Selection of the source to detector distance is based on Table 5-11 that best reflects the predetermined geometry.

5-47

Fermi 1 License Termination Plan Revision 4 Chapter 2 Site Characterization June 2011 Table 5-11 Sources to Detector Distance Effects on Instrument Efficiencies for Ua/P Emitters Source to Detector Instrument Efficiency e Distance (cm)

Tc-99 Distributed Th-230 Distributed Contact (1)(2n eff)

(1) (27t eff) 0.5 cm (0.803) (2n eff)

(0.761) (2t eff) 1 cm (0.701) (27t eff)

(0.579) (2n eff) 2 cm (0.503) (27t eff)

(0.099) (27t eff)

Source efficiency (es), reflects the physical characteristics of the surface and any surface coatings. The source efficiency is the ratio between the number of particles emerging from surface and the total of particles released within the source.

The source efficiency accounts for attenuation and backscatter. Source efficiency (e,), is nominally 0.5 (no self-absorption/attenuation, no backscatter) backscatter increases the value, self-absorption decreases the value. Source efficiencies may either be derived empirically or simply selected from the guidance contained in ISO 7503-1. ISO 7503-1 takes a conservative approach by recommending the use of factors to correct for alpha and beta self-absorption/attenuation when determining surface activity.

However, this approach may prove to be too conservative for radionuclides with max beta energies that are marginally lower than 0.400 MeV, such as Co-60 with a

,max of 0.3 14 MeV. In this situation, it may be more appropriate to determine the source efficiency by considering the energies of other beta emitting radionuclides. Using this approach it is possible to determine weighted average source efficiency.

For example, a source efficiency of 0.375 may be calculated based on a 50/50 mix of Co-60 and Cs-137. The source efficiencies for Co-60 and Cs-137 are 0.25 and 0.5 respectively, since the radionuclide fraction for Co-60 and Cs-137 is 50% for each, the weighted average source efficiency for the mix may be calculated in the following manner:

(.25)(.50) + (.50)(.50) = 0.375 5-48 Fermi 1 License Termination Plan Chapter 2 Site Characterization Revision 4 June 2011 Table 5-11 Sources to Detector Distance Effects on Instrument Efficiencies for a/p Emitters Contact 0.5 cm 1cm 2cm (1 )(2n eft)

(1) (2n eft)

(0.803) (2n eft)

(0.761) (2n eft)

(0.701) (2n eft)

(0.579) (2n eft)

(0.503) (2n eft)

(0.099) (2n eft)

Source efficiency (es), reflects the physical characteristics of the surface and any surface coatings. The source efficiency is the ratio between the number of particles emerging from surface and the total of particles released within the source.

The source efficiency accounts for attenuation and backscatter. Source efficiency (es), is nominally 0.5 (no self-absorption/attenuation, no backscatter) backscatter increases the value, self-absorption decreases the value. Source efficiencies may either be derived empirically or simply selected from the guidance contained in ISO 7503-1. ISO 7503-1 takes a conservative approach by recommending the use of factors to correct for alpha and beta self-absorption/attenuation when determining surface activity.

However, this approach may prove to be too conservative for radionuclides with max beta energies that are marginally lower than 0.400 MeV, such as Co-60 with a Pma'{ of 0.3 14 MeV. In this situation, it may be more appropriate to determine the source efficiency by considering the energies of other beta emitting radionuclides. Using this approach it is possible to determine weighted average source efficiency.

For example, a source efficiency of 0.375 may be calculated based on a 50/50 mix ofCo-60 and Cs-137. The source efficiencies for Co-60 and Cs-137 are 0.25 and 0.5 respectively, since the radionuclide fraction for Co-60 and Cs-137 is 50% for each, the weighted average source efficiency for the mix may be calculated in the following manner:

(.25)(.50) + (.50)(.50) = 0.375 5-48

NRC-11-0036, Enrico Fermi Atomic Power Plant, Unit 1 - License Termination Plan, Revision 4

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