ML070450170

to Final Status Survey Plan for the Plum Brook Reactor Facility. Cover Through Page C2-14

ML070450170
Person / Time
Site:	Plum Brook
Issue date:	02/28/2007
From:	US National Aeronautics & Space Admin (NASA), John H. Glenn Research Ctr at Lewis Field
To:	NRC/FSME
References
Download: ML070450170 (454)

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NDMISIO SAFTY SAFETY AND MISSION ASSURANCE DIRECTORATE Plum Brook Reactor Facility Final Status Survey Plan for the Plum Brook Reactor Facility (Rev 1)

February 2007

NASA PBRF DECOMMISSIONING PROJECT ROUTING AND S. . . APPROVAL SHEET Document

Title:

. Final Status SurveyPlan for the Plum Brook Reactor Facility Document Number: N/A Revision Number: 1 ROUTING D;i ic

• Procedure Originator/ to.....nerS7"';*,/ " ....... .......

.]NASA Project.RS0 IW. Stoner/ .,.. *"

• A NASA Project Safety Officer H. Bayes . - , 7,/ 2 NASA Project Construction Manager C. Fellhauer/ -

HM anagerProject... Environmental NASA ..... . .Kb_____, * . .. , .*

NASA Project QA Manager P. Kolb I NASA Senior Project Engineer K. Peecook I

• W A IMPLEMENTING APPROVAL: K?

14JAz,ýýý (EP~ct Safety Committee Chairman Date EFFECTIVE DATE: ospedn 2zo]

NASA PBRF DECOMMISSIONING PROJECT CHANGE/CANCELLATION RECORD DOCUMENT TITLE: DOCUMENT NO: N/A REVISION NO: 1 Final Status Survey Plan for the Plum (February 2007)

Brook Reactor Facility Revision 0: Initial issue of Document Revision 1: Section 5.3 on page 5-3 was revised to incorporate a more detailed description of the background reference area.

LIST OF EFFECTIVE PAGES DOCUMENT NO: N/A (FSSP) REVISION NO: 1 Page No. Revision Level Page No. Revision Level Page No. Revision Level Cover Page 1 Attachment B B-1 through B-26 Routing Page 1 Attachment C C-1 through C-16 Change Page Attachment C-Addendum 1 Cl-i through C1-256 LOEP Attachment C - Addendum 2 C2-1 through C2-14 i through viii Attachment C - Addendum 3 C3-1 through C3-51 Attachment D 1-1 D1 through D-33 2-1 through 2-14 0 3-1 through 3-7 0 4-1 0 5-1 through 5-2 0 5-3 through 5-7 1 6-1 through 6-6 0 7-1 through 7-6 0 8-1 through 8-5 0 9-1 through 9-3 0 10-1 through 10-5 0 11-1 through 11-2 0 12-1 through 12-7 0 13-1 through 13-2 0 Attachment A 0 A-I through A-27 Attachment A-Addendum 1 0 7-Pages Attachment A-Addendum 2 0 16-Pages Attachment A-Addendum 3 0 3-Pages Attachment A-Addendum 4 0 2-Pages I _

u B/

plum Brook Reactor Facility FinalStatus Survey Plan Revision]1 TABLE OF CONTENTS

1.0 INTRODUCTION

10 ITO CTO ..................................... ...........................

°........ ° 1-1 1.1 P urp o se ................................................................................................................- 1-1 1.2 Final Status Survey Plan Overview ................................................................... 1-1 2.0 CLASSIFICATION OF AREAS 2-1 2.1 Impacted and Non-Impacted Areas ................................................................... 2-1 2.2 PBRF Classifications------------------------------------ 2-2 2.2.1 Changes in Classification -------------------------------------------- 2-2 3.0 RADIOLOGICAL CONTAMINANTS AND DCGL 3-1

°°*....... ........ .......

°.... .. °... .....

°...

3.1 Site-Specific DCGL Values for Soil ............................................................... 3-1 3.2 Site-Specific DCGL Values for Structure -------------------------------------- 3-1 3.3 Embedded Piping DCGL Values ...................................................................... 3-2 3.4 DCGL for Other Media 3-3 3.5 Radionuclide Mixture for FSS------------------------------ 3-3 3.6 Surrogate DCGL, Gross Beta Activity and the Unity Rule--------------------------- 3-4 3.6.1 Surrogate Equation ................................................................................ 3-5 3.6.2 Gross Beta Equation ......... -............................................................... 3-5 3.6.3 Unity Rule Equation ----------------------------------------------- 3-6 3.7 Area Factors---------------------------------------- 6 4.0 ESTABLISHING SURVEY UNITS 4-1 4.1 Survey U nit ................................... ................................................................... 4-1 4.1.1 Survey Unit Size ------------------------------------------------------------------------  ;........... 4-1 4.1.2 Site Reference Coordinate System (Reference Grid) -------------------------- 4-1 5.0 SURVEY DESIGN 5-1 5.1 Scan Survey Coverage ....................................................................................... 5-1 5.2 Sample Size D etermination ............................................................................... 5-1 5.2.1 Determining Which Test To Be Used .................................................. 5-1 5.2.2 Establish Decision Errors2..................................................................... 5-2 5.2.3 Relative Shift 5-2 i

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 1 TABLE OF CONTENTS (continued) 5.2.4 Number of Measurements ---------------------------- 5-3 5.2.5 Elevated Measurement Comparison (EMC) Sample Size A djustm ent ......................................................... ......................... 5-3 5.3 Background Reference Areas ............................................................................. 5-3 5.3 .1 S election-... .. .. .. ... .. .. .. .. ... .. .. .. ... .. .. .. . 5-4 5.3.2 Different Survey Unit Material Backgrounds ...................................... 5-4 5.3.3 Different Background Reference Areas ................................................ 5-5 5.3.4 Background Level Determinations -------------------------------------- 5-5 5.4 Measurement Locations----------------------------------- 5-5 5.4.1 Class 3 Survey U nits-.............................................................................. 5-5 5.4.2 Class 1 and 2 Survey Units ------------------------------------------- 5-6 5.5 FSS Design Package ---------------------------------------------------- 5-7 6.0 RADIOLOGICAL INSTRUMENTATION ......................... 6-1 6.1 Instrumentation Selection--------------------------------- 6-1 6.2 Instrumentation Calibration-------------------------------- 6-2 6.3 R esponse Checks ..................... 6.....................................

6-3 6.4 Minimum Detectable Concentration (MDC) .................................................... 6-3 6.5 Detection Sensitivity.------------------------------------------

- 6-5 6.5.1 Structure Static Measurements ------------------------- 6-5 6.5.2 Structure Scan Measurements 6-5 6.5.3 Soil Scan Measurements 6-5 oluVm tric ateri ls .. .........................................................................

6.5.4 -

6.5.4 Volumetric Materials-----------------6-5 6.5.5 Embedded and Buried Piping_ .----------------------..................................... 6-6 7.0 RADIOLOGICAL SURVEY METHODS .......................... 7-1 7.1 Structures -------------------------------------------- 7-1 7.1.1 Surface Scans ------------------------------------ 7-1 7.1.2 Static Measurements-------------------------------- 7-1 7.1.3 Activated Concrete --------------------------------- 7-2 7.1.4 Volumetric Concrete Measurements --------------------- 7-2 ii

Plum Brook Reactor Facility FinalStatus Survey Plan Revision ]

TABLE OF CONTENTS (continued) 7.1.5 Loose Surface Contamination Surveys ................................................ 7-2 7.1.6 Cracks, Crevices, Wall-Floor Interfaces and Small Holes .................. 7-3 7.1.7 P aint C overed Surfaces,.......................................................................... 7-3 7.2 Surface Soil 7-3 7.2.1 Surface Scans ..................................... 7-3 7.2.2 Surface Sam pling .................................................................................. 7-4 7.3 Subsurface Soil 7-4 7.3.1 Subsurface Sampling ----------------------------------------------- - -------- 7-4 7.4 Stored Excavated Soil 7-5 7.5 Embedded and Buried Piping .................--........................................................ 7-5 7.6 Pavement Covered Areas---------------------------------- 7-5 8.0 INVESTIGATION LEVELS AND ELEVATED AREAS TEST 8-1 8.1 Investigation Levels ........................................................................................... 8-1 8.2 Investigation Process .......................................................................................... 8-1 8.3 Elevated Measurement Comparison (EMC) ------------------------------------- 8-2 8.4 Remediation and Reclassification 8-4 9.0 DATA COLLECTION AND PROCESSING ........................ 9-1 9.1 Sample Handling and Record Keeping ---------------------------------------- 9-1 9.2 D ata M anagem ent .............. 9-1 1..................................

9.3 Data Verification and Validation 9-1 9.4 Graphical Data Review -------------------------------------------------- 9-2 9.4.1 Posting Plots ........................................................................................... 9-2 9.4.2 Frequency Plots -------------------------------------------------- 9-3 10.0 DATA ASSESSMENT AND COMPLIANCE 10-1 10.1 Data Assessment Including Statistical Analysis .....................................-....... .10-1 10.1.1 Interpretation of Sample Measurement Results ................................... 10-1 10.1.2 Wilcoxon Rank Sum Test 10-2 10.1.3 Sign T est................................................................................................. 10-3 10.1.4 U nity Rule ..............................-................................................................ 10-4 iii

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 1 TABLE OF CONTENTS (continued) 10.2 Data Conclusions 10-4 10 .3 C o mp lian ce...............................................................................................---......... 10 -5 11.0 REPORTING FORMAT.......................................11-1 11.1 H isto ry F ile ----------.----------------------------------------------- 11-1 11.2 Survey Unit Release Record ............................................................................ 11-1 11.3 Final Status Survey Report ................................................................................ 11-1 12.0 FSS QUALITY ASSURANCE & QUALITY CONTROL (QA/QC) ................... 12-1 12.1 Project Management and Organization ---------------------------------------- 12-1 12.1.1 NASA Project Radiation Safety Officer (RSO) ................................... 12-1 12.1.2 FSS/Characterization Manager ...................................-------------------------- 12-1 12.1.3 FS S/Characterization Engineers ........................................................... 12-2 12.1.4 FSS/Characterization Supervisors ........................................................ 12-2 12.1.5 Radiological Laboratory Manager -------------------------------------- 12-2 12.1.6 FSS/Characterization Technicians 12-2 12.2 Training .............................................................---------------................................. 12-3 12.3 Written Procedures -------------------------------------- 12-3 12.4 Access Control of Surveyed Areas and Systems,................-............................ 12-3 12.5 Chain-of-Custody ............................................................................................... 12-4 12.6 Instrumentation Selection, Calibration and Operation ..................................... 12-4 12.7 Quality Control Surveys and Samples .............................................................. 12-4 12.7.1 Replicate Field M easurem ents .............................................................. 12-4 12.7.2 Replicate Sample Analyses . ----------........................................................ 12-5 12.7.3 Control of Vendor-Supplied Services.................................................. 12-6 12.7.4 Database Control -------------------------------------------------- 12-6 12.7.5 Assessm ent and Oversight .................................................................... 12-6 12.7.5.1 Assessments------------------------------- 12-6 12.7.5.2 Corrective Action Process 12-6 12.7.6 Data Validation----------------------------------- 12-6 12.7.7 NRC Confirmatory Measurements ....................................................... 12-7 iv

Plum Brook Reactor Facility Final Status Survey Plan Revision 1 TABLE OF CONTENTS (continued) 13.0 R E FERE NC E S ............................................................................................................. 13-1 A TTACHMENTA 1.0 P urp ose ........................................................................................................................... A -1 2.0 References A-1 3.0 Assumptions and General Information ................................................................ A-1 3.1 Nuclides A-1 3.2 RESRAD and RESRAD-BUILD A-1 4.0 Discussion A-1 5.0 Historical Overview A-2 5.1 Assessment of Historical and Operational Factors --------------------------------- -- -----.

A-4 6.0 Sam ple C ollection and A nalysis .................................................................................. A -5 6.1 Sm ear Sam ples of Structural Surfaces ----------------------------------------- A -5 6.2 Concrete Core Sampling ------------------- .............................----------------------------------- -A-7 6.3 Soil Sam pling .................................................................................................. - A -16 7.0 Evaluation of Sample Results and Elimination of Insignificant Radionuclides.A-19 7.1 Minimum Detectable Activity (MDA) ............................................................ A- 19 7.2 Mean Distribution Evaluation A- 19 7.3 Application of the 10% Rule ............................................................................. A-23 8.0 Conclusion ................................................. A-26 9.0 Addendums ................................................. A-27 Addendum 1, Result of Isotopic Analysis of Smear Samples (7 Pages)

Addendum 2, Preliminary Analysis of Concrete Core "Puck" Samples by the On-Site Laboratory (16 Pages)

Addendum 3, Results of Isotopic Analysis of Concrete Core Samples (3 Pages)

Addendum 4, Results of Isotopic Analysis of Surface Soil Samples (2 Pages)

A TTACHMENT B 1.0 P u rp ose ........................................................................................................................... B -1 2.0 References ...................................................................................................................... B -1 3.0 D C G L A pproach ........................................................................................................... B -2 4.0 D C G L M ethodology .................................................................................................... B -3 V

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 1 TABLE OF CONTENTS (continued) 5.0 DCGL BASES B-4 5.1 Residual Contamination in Surface Soils B-4 5.2 Residual Contamination in Buildings.............................. ................................. B-11 5.3 Residual Contamination in Subsurface Structures ----------------- B-18 6.0 Area Factors ................................................ B-25 A TTA CHMENT C 1.0 P urp ose ........................................................................................................................... C-1 2.0 References .................................................. C-1 3.0 Discussion C-1 3.1 Industrial Safety ------------------------------------------------------ C-2 3.2 Waste Generation --------------------------------------- C-2 3.3 Cost C-2 4.0 Embedded Piping Versus Buried Piping .................................................................. C-3 4.1 Embedded Piping DCGL Values ............................................--- ....................... C-3 4.2 Buried Piping DCGL Values ---------------------------------------------- C-3 5.0 Embedded Piping Conceptual Dose Model .............................................................. C-4 6.0 Dose Calculations for 9-Pipe Cluster ......................................................................... C-5 7.0 Em bedded Piping DCGL Values ................................................................................ C-7 8.0 Evaluation of Alternative Exposure Scenario .......................................................... C-8 9.0 Area Factors ................................................ C-10 Addendum 1, MicroShield Case Run Reports for Canal F- Pump Room Walkway Pipe Cluster (256 Pages)

Addendum 2, MicroShield Case Run Reports for Pump Room Trench Pipe Cluster (14 Pages)

Addendum 3, MicroShield Case Run Reports for Area Factor Calculations (51 Pages)

A TTA CHMENT D Illustrationsof Survey Area Classification(33 Pages)

Vi

Plum Brook Reactor Facility FinalStatus Survey Plan Revision I Plum Brook Reactor Facility Final Status Survey Plan Revision 1 LIST OF ACRONYMS (c Alpha ALARA As Low As Reasonable Achievable AF Area Factor AMCG Average Member of the Critical Group Beta CFR Code of Federal Regulations CoC Chain-of-Custody cm 2 Centimeters cm Square Centimeters cpm Counts per Minute DCGL Derived Concentration Guideline Levels DCGLEMC DCGL for small areas of elevated activity, used with the Elevated Measurement Comparison (EMC)

DCGLES Effective Surface DCGL DCGLFSS Final Status Survey DCGL DCGLv Volumetric DCGL DCGLw DCGL for average concentrations over a large area, used with statistical tests EMC Elevated Measurement Comparison EP Embedded Pipe EPA Environmental Protection Agency ERB Emergency Retention Basin FSS Final Status Survey FSSP Final Status Survey Plan FSSR Final Status Survey Report ft Feet 7 Gamma GRC Glenn Research Center HTD Hard To Detect Kd Distribution Coefficient LBGR Lower Boundary of the Gray Region m2 Square Meters MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual MDC Minimum Detectable Concentration mrem Millirem NASA National Aeronautics and Space Administration NRC Nuclear Regulatory Commission ODNR Ohio Department of Natural Resources OEPA State of Ohio Environmental Protection Agency NIST National Institute of Standards and Technology PBRF Plum Brook Reactor Facility PBS Plum Brook Station pCi/g Picocuries per Gram PDF Parameter Distribution Function PRCC Partial Rank Correlation Coefficient QA Quality Assurance QC Quality Control vii

Plum Brook Reactor Facility FinalStatus Survey Plan Revision I LIST OF ACRONYMS (continued)

ROLB Reactor Office and Laboratory Building RPD Relative Percent Difference SEB Reactor Service Equipment Building TBD Technical Basis Document TEDE Total Effective Dose Equivalent WEMS Water Effluent Monitoring Station WRS Wilcoxon Rank Sum Test viii

Survey Plan Revision 0 Plum Reactor Facility Plum Brook Reactor Facility FinalStatus Final Status Survey Plan Revision 0

1.0 INTRODUCTION

1.1 Purpose The purpose of this Final Status Survey Plan (FSSP) is to describe the methodology and approach to performing the Final Status Survey of the Plum Brook Reactor Facility. This plan replaces the description of the FSS methodology provided in the Decommissioning Plan and provides the description of the planned final radiation surveys as required by IOCFR50.82(b)(4)(iii). The survey program described by this plan will demonstrate that the facility has been decontaminated to the levels required for release of the facility for unrestricted use as prescribed by 10CFR20, subpart E. The report of Final Status Survey results will provide the basis for requesting termination of NRC Licenses TR-3 and R-93 in accordance with 10CFR50.82(b)(6).

The FSSP is based on guidance provided in NUREG-1575, "Multi-Agency Radiation Survey and Site Investigation Manual" (MARSSIM); NUREG 1757, "Consolidated NMSS Decommissioning Guidance"; NUREG-1 727, "NMSS Decommissioning Standard Review Plan"; and DG-4006, "Demonstrating Compliance with the Radiological Criteria for License Termination". The graded approach described in NUREG-1575 (MARSSIM) is followed to ensure that survey efforts are maximized in those areas having the greatest potential for residual contamination. The FSSP was developed to work in conjunction with the programmatic plans that are currently in place to safely and effectively decontaminate and dismantle the Plum Brook Reactor Facility (PBRF) as described in the Decommissioning Plan.

1.2 Final Status Survey Plan Overview This plan describes the scope and methodology of the PBRF final status survey (FSS) process. It includes specifics for classification of areas, DCGL development, establishment of survey units, survey design, radiological instrumentation, survey methods, investigation levels, data collection and processing, data assessment and compliance, reporting, and quality control.

Specific details of this plan will be incorporated into site procedures for implementation of the FSS.

• 1-1

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 2.0 CLASSIFICATION OF AREAS 2.1 Impacted and Non-Impacted Areas Area classification ensures that the number of measurements and the scan coverage are commensurate with the potential for residual contamination to exceed the unrestricted use criterion. Areas that have no reasonable potential for residual contamination from site operations are classified as non-impacted areas.

These areas are not required to be surveyed beyond what has already been completed as a part of site characterization to confirm the area's non-impacted classification. Areas with some potential for residual contamination are classified as impacted areas. Based on the levels of residual radioactivity present, impacted areas are further divided into Class 1, Class 2, or Class 3 designations as described below:

• Class 1 Areas - Areas that have, or had prior to remediation, a potential for radioactive contamination (based on site operating history) or known contamination (based on previous radiation surveys) above the DCGLw.

Examples of Class 1 areas include: 1) site areas previously subjected to remedial actions, 2) locations where leaks or spills are known to have occurred, 3) former burial or disposal sites, 4) waste storage sites, and 5) areas with contaminants in discrete solid pieces of material and high specific activity.

• Class 2 Areas - Areas that have, or had prior to remediation, a potential for radioactive contamination or known contamination, but are not expected to exceed the DCGLw. To justify changing the classification from Class 1 to Class 2, there should be measurement data that provides a high degree of confidence that no individual measurement would exceed the DCGLw.

Examples of areas that might be classified as Class 2 for the final status survey include: 1) locations where radioactive materials were present in an unsealed form, 2) potentially contaminated transport routes, 3) areas downwind from stack release points, 4) upper walls and ceilings of buildings or rooms subjected to airborne radioactivity, 5) areas handling low concentrations of radioactive materials, and 6) areas on the perimeter of former contamination control areas.

• Class 3 Areas - Any impacted areas that are not expected to contain any residual radioactivity, or are expected to contain levels of residual radioactivity at a small fraction of the DCGLw, based on site operating history and previous radiation surveys. Examples of areas that might be classified as Class 3 include buffer zones around Class 1 or Class 2 areas, and areas with very low potential for residual contamination but insufficient information to justify a non-impacted classification.

2-1

Plum Brook Reactor Facility Fýinal Status Survey Plan Revision 0 2.2 PBRF Classifications Section 2.2 of the PBRF Decommissioning Plan describes the operational history and radiological status of the PBRF. The plan also discusses routine and non-routine events that occurred during the PBRF's operational history that contributed to facility radioactivity and contamination levels as well as presenting information from a characterization survey conducted in 1985 and confirmatory survey conducted in 1998. This information was used to develop initial PBRF classifications which are listed in Table 4-2 of the Decommissioning Plan. After approval of the Decommissioning Plan, additional characterization data was collected throughout the site. This information revealed that some site areas were assigned overly conservative classifications and some areas were under classified.

The current classifications and summary of characterization results are provided in Tables 2-1 and 2-2. Illustrations of structure and land area impacted areas are provided in Attachment D.

2.2.1 Changes in Classification Changes in classification are based on survey data and other relevant information that indicates a different area classification is more appropriate. Changes in classifications which decrease an area classification (i.e., impacted to non-impacted; Class 1 to Class 2; Class 2 to Class 3; or Class 1 to Class 3) will not be performed without prior NRC approval per license condition requirements.

2-2

Plum Brook.Reactor Facility FinalStatus Survey Plan. Revision 0 Table 2 Survey Area Classifications Estimated Fre Floor Total FSS Initial Mean Net Maximum Net 2

Facility or Survey Area (ft ) Area Surface Classification Classification Total Beta Total Beta (a)

(a) (Mi) Area (b) (c) (dpm/100 cm2 ) (dpm/100 cm 2 )

(m2)

Reactor Building (Building 1111):

Inside Containment Vessel

- Area 2 - Work Space Inside CV @ 0' 4,019 374 2244 Class 1 Class 1 <5,000 <5,000 (Cl110 106Cx) ,1 322laa15050

• Area 17 - Test Area Inside CV at -25' 1,350 126 756 Class 1 Class 1 88,284 100,832 (C110 105Cx)

• Area 18 -Canal E (C1110 111Cx) 1,281 120 720 Class 1 Class 1 23,235 297,000

• Area 23 - Quad A (C110 107Cx) 803 75 450 Class 1 Class 1 18,644 116,000

• Area 24 - Quad B (Cl 110 108Cx) 813 76 456 Class 1 Class 1 4733 14,000

• Area 25 - Quad C (C1110 109Cx) 803 75 450 Class 1 Class 1 48,406 337,000

• Area 26 - Quad D (Cl110 1 1OCx) 637 60 360 Class 1 Class 1 13,811 60,000

• Area 29 - Sub-Pile Room (Cl 110 101Cx) 157 15 90 Class 1 Class 1 38,108 78,775 Area 30-Elevator Pit and Stair Well 210 20 120 Class 1 Class 1 3,286 8,153 (C1110 102Cx/103Cx/104Cx) 10,073 941 5,646 Reactor Building (Building 1111):

Outside Containment Vessel

- Area 1 - General Floor Area @ grade 9, 1 878 5,268 Class 1/2 Class 2 <15,000 300000 (Cl111 207Cx) 9 878 5,268 Class_1/2 Cass_2 <15,000300,00

• Area 3 - Canals Canal F (Cl 111 104Cx) 382 36 216 Class 1 Class 1 117,040 995,000 Canal G (Cl111 105Cx) 580 54 324 Class 1 Class 1 50,738 426,000 o Canal H (Cl 111 103Cx) 455 43 258 Class 1 Class 1 27,500 39,000

• Area 4 - Shop Area (Cl 111 203Cx) o Rooms 102 &103, Exp Ctrl Annex 806 75 450 Class 3 Class 2 o Room 104, Office 400 38 228 Class 3 Class 2 144 551 Room 105, Office 441 41 246 Class 3 Class 2

• Count Rooms (C111i 204Cx) oRoom 5, Experiment Control Room 1,156 108 648 Class 2 Class 2 o Room 6, Counting 80 8 48 Class 2 Class 2 Room 7, Janitor Closet 124 12 72 Class 2 Class 2 Room 8, Restroom 498 47 282 Class 2 Class 2 Room 9, Locker 197 19 114 Class 2 Class 2 o Room 10, Personnel Decontamination 120 12 72 Class 2 Class 2

• Area 11 - Office Area Mezzanine (C1111 208Cx) o Room 15, Reactor Control Room 872 82 492 Class 2 Class 2 o Room 16, Restroom, +12 Elevation 80 8 48 Class 2 Class 2 o Room 28, Storage 87 9 54 Class 2 Class 2 2,957 17,749 Rooms 202/203, Elec Equip & Parts Storage 806 75 450 Class 2 Class 2 o Room 204, Office 400 38 228 Class 2 Class 2 2-3

Plum Brook Reactor Facility FinalStatus Survey Plan Revision'0" Table 2 Survey Area Classifications Floor Floo Floor Estimated Total FSS Initial Mean Net Maximum Net Facility or Survey Area (ft) Area Surface Classification Classification Total Beta Total Beta I (M) Area (b) (c) (dpm/100 cm 2 ) (dpmll00 cm 2)

(a) (Mi) o Room 205, Office 441 41 246 Class 2 Class 2 o Room 206, Office 171 16 96 Class 2 Class 2 o Room 207, Office 171 16 96 Class 2 Class 2 Room 208, Office 171 16 96 Class 2 Class 2 2,957 17,749 Room 209, Office 171 16 96 Class 2 Class 2 Pipe Chase 46 5 30 Class 2 Class 2

• Area 20 - Work Area @ -15' (Cl111 202Cx) 7,790 724 4,344 Class 1 Class 2 850 38,000

• Reactor Bldg Sub-basement (C1111 201Cx) oArea 21 - Work Area @ -25' 3,013 280 1,680 Class 1 Class 2 6,280 Area 22 - Pump Room Area + Roof 1,366[ 127 762 Class 1/2 Class 2 , 25,058

• Penthouse Areas (Cl 111 209Cx) o Room 31, East Penthouse N/A N/A N/A N/AA(CO Class 2 o Room 32, West Penthouse (d) N/A N/A N/A N/A (CO Class 2 N/A N/A

• Area 33 - Air Lock 1 &2 (Cl 111 206Cx) 121 12 72 Class 1 Class 1 <1,000 <1,000 30,840 2,878 17,268

• Building Exterior (Cl 111 301Cx) o Building Roof 28,084 2,609 2,609 Class 2 (e) 658 Building Exterior Walls 13,110 1,218 1,218 Class 3 (e) 5,188 Additional Information

- Reactor Bldg Loose and Fixed Equipment (Cl111 101Cx) 1,061 148,117

-(c1Rx111 Bldg106cx)

&Canal E Loose and Fixed Equip 217 766 2,4 252,936 13,079,207

_________________________________ 82,107 I 7,646 I 26,741 Hot Laboratory (Building 1112):

" Hot Cells (Cl112 107Cx)

Room 1, Hot Cell #1 342 32 192 Class 1 (e)

Room 2, Hot Cell #2 138 13 78 Class 1 (e) o Room 3, Hot Cell #3 96 9 54 Class 1 (e) o Room 4, Hot Cell #4 64 6 36 Class 1 (e) 1,547,828 11,664,262 o Room 5, Hot Cell #5 64 6 36 Class 1 (e) o Room 6, Hot Cell #6 64 6 36 Class 1 (e) o Room 7, Hot Cell #7 64 6 36 Class 1 (e)

"Mezzanine above Hot Cells 1-2 1,000 93 558 Class 1 Class 1/2 151,979 597,660 (C1112 109Cx) 1,000 _9 558 Cass_1 Class_1/2 151,979 597,660

( Mezzanine above Hot Cells 37 1,005 94 564 Class 1 Class 1/2 989,411 4,462,502 (Cii112 ii OCx)_________ _________________

• Cold Work Areas (Cl 112 203Cx) 2-4

Plum Brook Reactor Facility FinalStatus Survey Plan Revisian 0:

Table 2 Survey Area Classifications oArea Floor Estimated Total FSS Initial MeanNet Maximum Net Facility or Survey Area Area Surface Classification Classification Total Beta Total Beta (fta) (m ) Area (b) (c) (dpm/l00 cm 2) (dpm/l00 2 (a) cm )

_(m2) o Room 8, Cold Work Area + Air Lock 2,219 207 1,242 Class 1 Class 2 o Room 8A, Vestibule 44 5 30 Class 2 Class 2 11,398 288,801 o Room 9, Manipulator Repair Shop 409 38 228 Class 1 Class 2 o Room 10, Office 117 11 66 Class 2 Class 2

• _Lavatory Areas (C1112 205Cx) o Room 11, LockerArea 217 21 126 Class 1 (e) o Room 12, Cold Lavatory 142 14 84 Class 1 (e) oArea 13 - Pipe Space 61 6 36 Class 1 (e) 11,834 78,234

- Room 14, Change Room 183 18 108 Class 1 (e) o Room 15, Hot Lavatory 279 26 156 Class 1 (e) o Room 15A, Closet 24 3 18 Class 1 (e)

• Room 16, Hot Work Area (C1112 202Cx) 2,155 201 1,206 Class 1 (e) 628,257 1,667,274

• Hot Handling Area (Cl 112 106Cx) oRoom 17, Hot Handling Room oArea 26 - Valve Pit 692 184 I 65 18 [

390 108

[ class 1 __

Class 1 Class 1/2 (e) 628,257 1,667,274

• Area 18 - Canal J (Cl112 105Cx) 435 41 246 Class 1 Class 1 175,662 1,192,000

• Hot Dry Storage (Cl 112 103Cx) oRoom 19, Hot Dry Storage 900 84 504 Class 1 (e) o Room 19A, Off-Gas Clean-up 174 17 102 Class 1 (e) 4,400 2,160,000

• Room 19, Removable Slabs & area above 74 444 Class 1 (e)

HDS (C1112 111Cx) Class_1 (e)

• Area 20 - Canal K (Cl 112 104Cx) 799 75 450 Class 1 Class 1 156,519 2,298,000

• Decontamination Areas (Cl 112 204Cx)

Room 21, Storage + Roof 246 23 138 Class 1 Class 1/2 o Room 22, Repair Shop 646 61 366 Class 1 Class 1/2 396,111 1,602,360 o Room 23, Decontamination Room 387 36 216 Class 1 Class 1/2 o Room 24, Storage 591 55 330 Class 1 Class 1/2

• _Hot Pipe Tunnel (C1112 108Cx) oArea 25A - Hot Pipe Tunnel 1,413 132 792 Class 1 Class 1 I oArea 25B - Hot Pipe Tunnel oArea 25C - Hot Pipe Tunnel

• Room 27, Mezzanine (Cl 112 1:12Cx) 1,474 1,112 1,412 137 104 132 822 624 792 Class 1 Class 1 Class I Class 1 Class 1 Class 1/2 30,000 2,000 I 3,000,000 5,000

• Building Exterior (Cl 112 301Cx) oBuilding Roof 14,134 1,313 1,313 Class 2 (e) o Building Exterior 14,047 1,305 1,305 Class 3 (e) 9 Additional Information

-Hot Cells Loose Equipment &.Material 1 (C0112 101Cx) 10,691,780 61,910,893 2-5

Plum Brook Reactor.Facility Final Status Survey Plan- Revision!0-Table 2 Survey Area Classifications Estimated FloAr Floor Total FSS Initial Mean Net Maximum Net Fclt Area Surface Classification Classification Total Beta Total Beta (a) (a)__ (M 2) Area (m2) _ _ _ (b)_ _ _ _ _ _(c) _ _ _ _ (dpm/100 2

_cm_ ) (dpmll00

_ _ _ cm 2

_ _)

- Hot Lab Loose Equipment & Material 412,081 33,401,830 (C1112 201Cx) 60,008 205,752 48,126 1 4,487 13,832 Reactor Service Equipment Building (1131)

• SEB First Floor Areas (D1131 403Cx) o Area 1 - Shop & Equipment 2,218 207 1,242 Class 1/3 Non-Impacted o Room 1, Chem. Lab & Record 394 37 222 Class 2/3 Non-Impacted Room 2, Counting 143 14 84 Class 2/3 Non-Impacted o Room 3, Office 173 17 102 Class 2/3 Non-Impacted o Room 4, Corridor 104 10 60 Class 2/3 Non-Impacted o Room 5, Office 87 9 54 Class 2/3 Non-Impacted o Room 6, Locker 162 16 96 Class 2/3 Non-Impacted

- Room 7, Janitor's Closet 28 3 18 Class 2/3 Non-Impacted o Room 8, Restroom Vestibule 16 2 12 Class 2/3 Non-impacted 545 1,134 Room 9, Vestibule 52 5 30 Class 2/3 Non-Impacted o Room 10, Corridor 195 19 114 Class 2/3 Non-Impacted o Room 11, Control Room 1,083 101 606 Class 2/3 Non-Impacted o Room 12, Chlorine 105 10 60 Class 2/3 Non-Impacted o Room 13, Water Treatment 3,752 349 2,094 Class 2/3 Non-Impacted o Room 15, Boiler 1,667 155 930 Class 2/3 Non-Impacted o Room 16, Parts and Storage 290 27 162 Class 2/3 Non-Impacted

" Room 17, Vertical Lift 149 14 84 Class 2/3 Non-Impacted

" Room 18, Engine Room 5,372 500 3,000 Class 2/3 Non-Impacted _ _

• SEB Mezzanine Areas (D1131 404Cx) o Room 1A, Instrument Repair 221 21 126 Class 3 Non-Impacted o Room 2A, Instrument Repair 270 26 156 Class 3 Non-Impacted o Room 3A, Instrument Repair 320 30 180 Class 3 Non-Impacted 1,564 4,859 o Area 14 - Mezzanine 358 34 204 Class 2/3 Non-Impacted o Room 19, Chemical Storage 1,526 142 852 Class 2/3 Non-Impacted

" Room 19A, Chemical Storage 393 37 222 Class 1/3 Non-Impacted 12,791 91,375

• Cold Pipe Tunnel (D1131 406Cx) o Area 23 - CPT (under SEB) 1,890 176 1,056 Class 1 Class 3 o Area 23 - CPT (from 1131 to 1152) 1,098 103 618 Class 1 Class 3 o Area 23 - CPT (under 1152) 570 53 318 Class 1 Class 3 21,824 92,897 o Area 23 - CPT (from 1151 to 1152) 366 35 210 Class 1 Class 3 o Area 23 - CPT (under 1151) 111 11 66 Class 1 Class 3 o Area 23 - CPT (from 1111 to 1131) 2,347 219 1,314 Class 1 Class 3

• SEB Basement Areas (D1131 402Cx) o Room 20, Auxiliary Equipment 1,020 95 1 570 Class 3 Non-Impacted I 501W 1,021 2-6

• Plum Brook ReactorFacility FinalStatus Survey Plan RevisionO,0 Table 2 Survey Area Classifications Floo Floor Estimated Total FSS Initial Mean Net Maximum Net aor Area Surface Classification Classification Total Beta Total Beta (a) (a)(in(M 2 ) 2 Area ) (b) (C) (dpm/100 cm 2 ) (dpmll00 cm 2) o Room 21, Water Treatment Pump 1,543 144 864 Class 3 Non-Impacted o Area 22 - Clear Well 423 40 240 Class 3 Non-Impacted o Area 24 - Generator/Comrpressor Pit 460 43 258 Class 3 Non-Impacted 501 1,021 o Room 25, Electrical &Batteries 914 85 510 Class 2/3 Non-Impacted "Area 26 - Pit 88 9 54 Class 3 Non-impacted

" Closet, Basement 40 4 24 Class 3 Non-Impacted

• Building Exterior (D1131 405Cx) o Building Roof 16,985 1,578 1,578 Class 2 (e) 467 699 o Building Exterior Walls 4,123 383 383 Class 3 (e)

Additional Information

- SEB Loose Equipment & Material 294 74,070 (D1131 401Cx) 75 2,071 51,056I 4,763I 18,773 Fan House Building (1132):

" First Floor Operating Area (C1132 201 Cx) o Room 1, Operating Area 2,772 258 1,548 Class 1 Class 1/2 o Room 2, Restroom 94 9 54 Class 1 Class 1/2 o Room 3, Janitor's Closet 55 6 36 Class 1 Class 1/2 10,868 108,396 o Room 4, Deionizer 155 15 90 Class 1 Class 1/2 o Room 5, Office 64 6 36 Class 1 Class 1/2

" Basement Areas (C1132 102Cx) o Room 6, Air Monitor 174 17 102 Class 1 Class 1 o Room 7, Sump Room 217 21 126 Class 1 Class 1 o Room 8, Equipment Room 2,906 270 1,620 Class 1 Class 1

- Area 9, Tunnel to Rx Bldg 1111 420 40 240 Class 1 Class 1 35,363 652,565 oArea 10, Stairwell 96 9 54 Class 1 Class 1 "Resin Pit 136 13 78 Class 1 Class 1 oPipe Trench 183 18 108 Class 1 Class 1

• Building Exterior (C1132 301Cx) o Building Roof 3,897 362 362 Class 2 (e) 99 580 "Building Exterior Walls 4,445 413 413 Class 2 (e) 15,614 1,457 4,867 Waste Handling Building (1133):

• Operating Areas (Cl 133 104Cx) o Room 1, Operating Area 1,951 182 1,092 Class 1 Class 1/2 o Room 2, Decontamination 414 39 234 Class 1 Class 1/2 3,062 26,221

" Area 16 - Stair Housing 97] 10 60 Class 1 (e)

• Laundry Area (C1133 201Cx) o Room 3, Laundry 222 21 126 Class 1 Class 1/2 2,957 17,749 2-7

Plum Brook ReactornFacility FinalStatus: Survey Plan RevisionO" Table 2 Survey Area Classifications Estimated Floo Floor Total FSS Initial Mean Net Maximum Net aor Area Surface Classification Classification Total Beta Total Beta (ft)

(a) (Mi) Area (b) (c) (dpm/100 cm 2) (dpm/100 cm2)

(m2) o Room 4, Clean Clothing 171 16 96 Class 1 Class 1/2 o Room 5, Storage 85 8 48 Class 1 Class 1/2 o Room 6, Laboratory 155 15 90 Class 1 Class 1/2 o Room 7, Office 150 14 84 Class 1 Class 1/2 o Room 8, Corridor 121 12 72 Class 1 Class 1/2 o Room 9, Janitor's Closet 19 2 12 Class 1 Class 1/2 2,957 17,749 o Room 10, Closet 15 2 12 Class 1 Class 1/2 o Room 11, Contaminated Change 122 12 72 Class 1 Class 1/2 o Room 12, Clean Restroom 120 12 72 Class 1 Class 1/2

" Room 13, Corridor 127 12 72 Class 1 Class 1/2 o Pipe Chase 21 2 12 Class 1 Class 1/2

• Room 14, Boiler Room (1133 202Cx) 411 39 234 Class 1 Class 1/2

• Basement Work Areas (C1133 102Cx) o Room 15, Access & Work Area 1,563 146 876 Class 1 Class 1 54,900 6,092,674

- Room 19, Access Tunnel 347 33 198 Class 1 Class 1

• _Evaporator Work Areas (Cl 133 103Cx) o Room 17, Preparation 406 38 228 Class 1 Class 1 o Room 18, Evaporator 406 38 228 Class 1 __ Class 1 7,582 201,885

• Mezzanine (C1133 105Cx) 1,350 126 756 Class I (e)

• Building Exterior (C1133 301 Cx) o Building Roof 4,726 439 439 Class 2 (e) 16 349 o Building Exterior Walls 3,821 355 355 Class 2 (e) 14,869 1,391 4,376 Primary Pump House (1134)

• Interior Rooms (C1134 201 Cx) oRoom 1, Pump 171 16 96 Class 1 Class 2 oRoom 2, Pump 171 16 96 Class 1 Class 2 Room 3, Pump 171 16 96 Class 1 Class 2 1,052,432 5,288,932 o Room 4, Heat Exchanger 1,073 100 600 Class 1 Class 2 1,046,611 4,986,792 o Room 5 149 14 84 Class 1 Class 2 oRoom 6, Bypass Deionizer 257 24 144 Class 1 Class 2

• Exterior Rooms (Cl 134 202Cx) oRoom 7 636 60 360 Class 1 Class 2 o Room 8 990 92 552 Class 1 Class 2 6,998 275,028 o Mezzanine 544 51 306 Class 1 Class 2

• Resin Pit (Cl134 203Cx) 136 13 78 Class 1 Class 2

• Building Exterior (Cl 134 301Cx) o Building Roof 5,220 485 485 Class 1 (e) 115 713 o Building Exterior Walls 4,316 406 406 Class 1 (e) 2-8

Plum.Brook Reactor Facility FinalStatus Survey Plan- Revision 0 Table 2 Survey Area Classifications Floo Floor Estimated Total FSS Initial Mean Net Maximum Net Facility or Survey Area Area Surface Classification Classification Total Beta Total Beta (a) 2 (m ) Area (b) (c) (dpmll00 cm 2) (dpmll00 cm 2 )

(a) 2 (M )

13,834 1,293 3,303 Reactor Office and Laboratory Building (1141)

• Area 1, Northeast Stair Hall (C1141 203Cx) 291 28 168 Class 2 Class 2 818 1,575

• Elevator Areas (C1141 202Cx) oArea 2, Elevator & Shaft 60 6 36 Class 2 Class 2 249 941 oArea 3, Elevator Machinery 143 14 84 Class 2 Class 2

• Vault Areas (Cl 141 206Cx) oArea 4, Cold Test Area 2,491 232 1,392 Class 1 Class 2 oArea 5, Airway 700 66 396 Class 1 Class 2 oArea 8, Vestibule 99 10 60 Class 1 Class 2 oArea 9, Restroom 82 8 48 Class 1 Class 2

- Area 10, Janitor's Closet 38 4 24 Class 1 Class 2 3,204 38,865 oArea 11, Building Service Equipment 1,767 165 990 Class 2 Class 2 586 2,155 oArea 14, Tool Crib 265 25 150 Class 2 Class 2 oArea 15, General Shop Area 813 76 456 Class 2 Class 2 oArea 16, Telephone Exchange 303 29 174 Class 2 Class 2 oArea 17, Vault 188 18 108 Class 1 Class 2

• Area 6, Sump (Cl 141 208Cx) 530 50 300 Class 1 Class 2 209 781

• Area 7, Crawl Space (Cl 141 21OCx) 3,782 352 2,112 Class 3 Class 2 450 608

• Instrument Areas (C1141 207Cx)

Area 12, Counting Rooms 357 34 204 Class 2 Class 2 oArea 13, Electronic Shop 317 30 180 Class 2 Class 2 715 2,589 Area 13A, Calibration Room 177 17 102 Class 2 Class 2

• Utility Tunnel (C1141 209Cx) 2,064 192 192 Class 1 (e) 1,500 1,700 First Floor Offices (C1141 211Cx)

Lobby 505 47 282 Class 3 Class 2 Room 100, Office 214 20 120 Class 3 Class 2 o Room 101, Office 214 20 120 Class 3 Class 2 o Room 102, Office 214 20 120 Class 3 Class 2 o Room 103, Office 209 20 120 Class 3 Class 2 o Room 104, Office 176 17 102 Class 3 Class 2 o Room 105, Office 191 18 108 Class 3 Class 2 106, Office 176 17 102 Class 3 Class 2664 SRoom o Room 107, Office 214 20 120 Class 3 Class 2 o Room 108, Office 197 19 114 Class 3 Class 2 o Room 109/110/111, Classroom 653 61 366 Class 2/3 Class 2 o Room 121, Conference 484 45 270 Class 2/3 Class 2 o Room 122, Office 300 28 168 Class 2/3 Class 2 o Room 123, Office 197 19 114 Class 2/3 Class 2 2-9

Plum Brook ReactorFacility FinalStatus Survey.Plan Revision 0 Table 2 Survey Area Classifications Floo Floor Estimated Total FSS Initial Mean Net Maximum Net aor Area Surface Classification Classification TotalBeta Total Beta (a)

(a) (m ) Area (b) (dpm/100 cm 2)

(M=) (c) (dpm/100 cm 2 )

o Room 124, Office 200 19 114 Class 2/3 Class 2 o Room 125, Office 200 19 114 Class 2/3 Class 2 Room 126, Office 212 20 120 Class 2/3 Class 2 o Restroom, Men's, +0 Elevation 177 17 102 Class 2 Class 2 o Restroom, Women's +0 Elevation 158 15 2 Class 2 Class 2 263 1,664 Lavatory, +0 Elevation 32 3 18 Class 2 Class 2 Janitor's Closet, +0 Elevation 30 3 18 Class 2 Class 2 Pipe Chase, +0 Elevation 39 4 24 Class 2 Class 2 o Hallways, +0 Elevation North/South 307 29 174 Class 3 Class 2

• First Floor Work Areas (C1141 212Cx) o Room 112, First Aid 303 29 174 Class 2 Class 2

- Room 113, Office 100 10 60 Class 2 Class 2 o Room 114, Health & Safety Operations 406 38 228 Class 2 Class 2 o Room 115, Office 341 32 192 Class 2 Class 2

. Room 116, Receiving 209 20 120 Class 2 Class 2 o Room 117/118, Electronic Laboratory 768 72 432 Class 1/2 Class 2 o Room 119/120, Electronic Laboratory 642 60 360 Class 1/2 Class 2 o Hallways, +0 Elevation East/West 1,725 161 966 Class 2 Class 2

• Middle Stairwell (Cl 141 204 Cx) 196 19 114 Class 2 Class 2 497 1,527

• Southeast Stairwell (Cl141 205Cx) 196 19 114 Class 2 Class 2 1,490 6,438

• Second Floor Offices (Cl 141 213Cx) o Room 200, Office 202 19 114 Class 3 Class 2 o Room 201, Office 214 20 120 Class 3 Class 2 o Room 202, Office 214 20 120 Class 3 Class 2 o Room 203, Office 214 20 120 Class 3 Class 2 o Room 216, Office 214 20 120 Class 3 Class 2 o Room 217, Library 480 45 270 Class 3 Class 2 o Room 218, Office 214 20 120 Class 3 Class 2 o Room 219, Office 214 20 120 Class 3 Class 2 o Room 220, Office 214 20 120 Class 3 Class 23,564 o Room 221, Office 214 20 120 Class 3 Class 2 o Room 222, Office 523 49 294 Class 3 Class 2 o Room 223, Office 214 20 120 Class 3 Class 2 o Restroom, Men's, +12 Elevation 134 13 78 Class 2 Class 2 o Restroom, Women's +12 Elevation 45 5 30 Class 2 Class 2 Janitor's Closet 1, +12 Elevation 28 3 18 Class 3 Class 2 o Hallways, +12 Elevation North/South 727 68 408 Class 3 Class 2 2-10

• Plum.Brook Reactor Facility Final-StatusSurvey Plan Revision 0:,

Table 2 Survey Area Classifications Floo Floor Estimated Total FSS Initial Facility Srvey AreaAreaFS nta Mean Net Maximum Net Facility or Survey Area (ft2) Area Surface Classification Classification Total Beta Total Beta 2 2 2 (a) (M ) Area (M') (b) (c) (dpm/100 cm ) (dpm/100 cm )

• Second Floor Work Areas (C1141 214Cx)

Room 204, Materials Laboratory 345 33 198 Class 1 Class 2 o Room 205, Materials Laboratory 301 28 168 Class 1 Class 2 o Room 206, Materials Laboratory 345 33 198 Class 1 Class 2 o Room 207, Chem. Lab Storage 352 33 198 Class 1 Class 2 o Room 207A, Counting 160 15 90 Class 1 Class 2 o Room 208, Office 164 16 96 Class 1 Class 2 o Room 208A, Darkroom 133 13 78 Class 1 Class 2 o Room 208B, Darkroom 133 13 78 Class 1 Class 2 Room 209, Chem. Laboratory 312 29 174 Class 1 Class 2 39,099 293,254 Room 210, Chem. Laboratory 312 29 174 Class 1 Class 2 626a 4,878a o Room 211/212, Chem. Laboratory 695 65 390 Class 1 Class 2 o Room 213, Chem. Laboratory 349 33 198 Class 1 Class 2 o Room 213A, Chem. Laboratory 362 34 204 Class 1 Class 2 o Room 214/215, Chem. Laboratory 417 39 234 Class 1 Class 2 o Janitor's Closet 2, +12 Elevation - 23 3 18 Class 1 Class 2 o Pipe Chase, +12 Elevation 33 4 24 Class 1 Class 2 o Hallways, +12 Elevation East-West 855 80 480 Class 1 Class 2

• Building Exterior (Cl 141 215Cx) o Building Roof 11,540 1,072 1,072 Class 2 (e) o Building Exterior Walls 18,675 1,735 1,735 Class 3 (e) 595 1,093 Hot Retention Area (1155)

• AllAreas (Cl155 102Cx) 4,050 377 2,262 Class 1 Class 1 22,973 41,197 Reactor Security Building (1191)

• All Areas (D1191 401Cx)

• Room 100, Visitor Control 470 44 264 Class 3 Non-Impacted

• Room 101, Utility 28 3 18 Class 3 Non-Impacted 177 523

" Room 102, Furnace 52 5 30 Class 3 Non-Impacted

" Lavatory 34 4 24 Class 3 Non-Impacted

• Building Exterior (C1191 402Cx) 1,701 158 158 Class 3 Non-Impacted -12 138 1 2.285 I 214 I 494 I i

Table 2-1 Notes:

(a) Floor Area - The majority of numerical values provided in the floor areas (ft ) column were taken from "Plans of Buildings and Structures, Lewis Research Center, Plum Brook Station, June 1974". In locations where that document did not provide numerical values for the floor areas, drawings were used to estimate the floor surface areas.

2-11

Plum Brook Reactor Facility FinalStatusSurveyPlan Revision:O (b) FSS Classification - The current classification to be used for the FSS. Class X/Y designates the floors and lower walls as Class X while the upper walls and ceilings are Class Y.

(c) Initial Classification - The initial classifications derived from Table 4-2 of the Decommissioning Plan (d) Structure was demolished and removed. No FSS will be performed.

(e) Classification not specifically listed in Table 4-2 of the Decommissioning Plan 2-12

Plum Brook ReactorFacility FinalStatus Survey Plan Revision-0..

.'Co 1.120 16.65

- Pentolite Ditch & Environs (A2300 101Cx) 574,000 53,327 Class 1 Class 1 137Cs 37.51 1,019 Environmental Areas .* , -_ ,

60 Co 0.05172 0.08278 137 Cs 0.29297 0.48578 60

• South Southwest Unit (A2400 301Cx) 125,000 11,613 Class 2/3 Class 3 co 0.11662 0.87453 1Cs 0.21873 0.44134 60 Co 0.04291 0.06650 137

• South Southeast Corner (A2400 302Cx) Cs 0.23082 0.36748 Note: Contains the WEMS Spill area, the south ERB 60 122,891 11,417 Class 1/2 Class 1/3 Co berm and portions of the east and west ERB berm. 137 1.8708 37.151 Cs 15.327 217.90 60 Co 0.04259 0.04662 37

- Southwest Unit (A2400 303Cx) TCs 19.657 150.58 60 Note: Contains portions of the WHB Spill Area and the 125,000 11,613 Class 1/2/3 Class 1/3 Co 0.09689 0.22770 Waste Storage Pad.0.980270 137 Cs 110.51 207.50

- Southeast Unit (A2400 304Cx) 60 Co 0.04558 0.06258 Note: Contains the north ERB berm and portions of the 105,895 9,838 Class 1/2 Class 3 east and west ERB berm. 137 Cs 0.26198 0.42556 60

- Northwest Unit (A2400 305Cx) Co 0.05054 0.10171 Note: Contains the HRA, WHB, FH, portions of the Hot 108,608 10,091 Class 1/2 Class 1/3 137 Lab, and portions of the WHB spill area. Cs 0.51620 1.5203 60

- Northeast Unit (A2400 306Cx) Co 0.04701 0.07637 Note: Contains the CRA's and ERB Spill Areas 137 117,542 10,921 Class 1/2 Class 3 Cs 0.23683 0.38934 60 Co 0.03420 0.03973 37

- North Northwest Unit (A2400 307Cx) 1 Cs 0.26071 0.49599 Note: Contains the Rx Bldg, ROLB, PPH, portions of the 60 74,626 6,933 Class 1/2 Class 1/3 Co Hot Lab, and PPH resin spill area. 137 0.03369 0.05632 Cs 0.05655 0.12184 2-13

Plum Brook Reactor Facility FinalStatus.Survey Plan Revision 0 Table 2 Environmental SurveyArea Classification Survey FSS Initial Mean Maximum 2

PBRF Survey Area Area (ft ) Survey Classification Classification Isotope Measurement Measurement (a) Area (b) (c) (pCilg) (pCi/g) 60

• North Northeast Unit (A2400 308Cx) Co 0.04431 0.05089 Note: Contains the SEB, and portions of the Sludge 121,072 11,248 Class 1/2 Class 3 7

Basins and Precipitator. 3 Cs 0.26315 0.43784 60 Northern Unit (A2400 309Cx) Co 0.04560 0.07090 Note: Contains portions of the Precipitator and portions 110,287 10,246 Class 1/2/3 Class 3 137 of the Sludge Basins. Cs 0.23966 0.39998 60

- Far Northern Unit (A2400 31OCx) Co 0.04903 0.06385 Note: Contains the Compressor Bldg, Gas Storage 89,817 8,345 Class 3 Class 3 137 Structure and Cryogenic and Gas Supply Farm. Cs 0.30677 0.61130 60

- Open land areas outside the PBRF Fence Co 0.6339 4.567 137 Note: Areas to serve as buffer zones to impacted areas 1,524,748 141,649 Class 1/3 (d) Cs inside the fence (estimated) 2.0630 19.080 M 1,216,450 113,015 * -- - * .

Table 2-2 Notes:

(a) Survey Area - This area was estimated using facility drawings.

(b) FSS Classification - The current classification to be used for the FSS. Refer to the illustrations in Attachment D of this plan for a classification layout.

(c) Initial Classification - The initial classifications derived from Table 4-2 of the Decommissioning Plan.

(d) Classification not specifically listed in Table 4-2 of the Decommissioning Plan 2-14

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 3.0 RADIOLOGICAL CONTAMINANTS AND DCGL The goal of the PBRF decommissioning project is to release the site for unrestricted use in compliance with the NRC's annual dose limit of 25 mrem/yr plus ALARA. The NRC dose limits apply to residual radioactivity that is distinguishable from background. The DCGL values established within this FSSP will not be increased without prior NRC approval.

Site-specific dose assessments were performed to calculate the DCGL for surface soil, structures, and embedded pipe. RESRAD 6.21, RESRAD 6.0, RESRAD-BUILD 3.22, and the Microshield code were used for these dose assessments. Model input parameters were developed and justified for each assessment.

The dose assessments and DCGL calculations for surface soil, building reuse and subsurface structures are described in detail in Attachment B, "Approach and Basis for Development of Site-Specific Derived Concentration Guideline Levels (DCGL)" of this FSSP. The dose assessment and DCGL calculations for embedded piping are described in detail in Attachment C, "Dose Assessment and DCGL Calculation for Embedded Pipe".

3.1 Site-Specific DCGL Values for Soil The surface soil DCGL values are listed in Table 3-1. The DCGL values are the volumetric activity of the first 6 inches of soil, in pCi/g, that will be used during FSS to determine compliance with the 25 mrem/yr unrestricted use criterion.

Table 3-1 DCGL Values for Surface Soil DCGL Radionuclide (CGL (pCi/g)

Co-60 3.8 Sr-90 5.4 Cs-137 14.7 3.2 Site-Specific DCGL Values for Structures The structure DCGL values are listed in Table 3-2. The DCGL values are the surface activity level in dpm/100 cm 2 that will be used during FSS to determine compliance with the 25 mrem/yr unrestricted use criterion.

3-1

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Table 3-2 DCGL Values for Structures Radionuclide DCGL (dpm/100 cm2)

Co-60 11,000 Sr-90 33,100 Cs-137 40,500 Eu-154 4,500 H-3 9.1E+06 1-129 14,900 U-234 31,500 U-235 27,100 U-236 33,200 The current decommissioning strategy for PBRF calls for the removal of activated portions of the concrete bio-shield and disposition of the activated concrete as radioactive waste. Any potentially activated concrete remaining in place will be evaluated for residual radioactive contamination volumetrically using the subsurface structure DCGL values provided in Attachment B, Table B-14.

Volumetric sampling of contaminated concrete, as opposed to surface measurements may be necessary if gross activity measurements are insufficient or subsurface activity greater than the DCGLw is suspected. The results will either be evaluated by 1) calculating the derived total gross beta dpm/ 100 cm 2 in the sample and comparing the gross beta results directly to the gross beta DCGL or,

2) compare results to the volumetric DCGL values (Attachment B, Table B-14) for subsurface structures coupled with application of the unity rule.

3.3 Embedded Piping DCGL Values The PBRF contains a number of pipe runs that are embedded in concrete.

Embedded piping (EP) is any pipe situated below the minus three (-3) foot elevation that is totally encased in concrete or piping directly beneath building floors that may not be totally encased in concrete, but contained within the structural foundation of the building. Examples include the Containment Vessel Quadrant and Canal drain piping and remaining sections of the Primary Cooling Loop. The EP DCGL values are listed in Table 3-3. These values represent surface activity concentrations that correspond to an annual dose of 1 mrem/yr to a future building occupant. In order to utilize the EP DCGL values, piping must be grouted prior to license termination.

3-2

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 The PBRF dose goal for EP is 1 mrem!yr. However, at the discretion of PBRF, different dose goals could be applied in different areas as long as the residual contamination on the structure surface in the survey unit containing the given EP is sufficiently low to allow for the selected dose goal. For example, if the FSS results indicate that the residual contamination level in Hot Dry Storage is 0.5 times the DCGL, the dose from the two drains in this survey unit could be as high as 12.5 mrem/yr.

Table 3-3 DCGL Values for Embedded Piping Radionuclide DCGL (dpm/100 cm 2 per mrem/yr)

Co-60 2.408E+05 Eu-154 5.325E+05 Eu-152 7.352E+05 Nb-94 9.082E+05 Ag-108m 1.312E+06 Cs-137 3.785E+06 3.4 DCGL for Other Media Other media that will undergo FSS include subsurface soil, concrete foundation pads, and buried pipes. The DCGL for foundation pads and buried piping will be the same as the structure DCGL values. Buried piping is any pipe buried in soil and situated outside the structural foundation of a building, such as storm drains.

The DCGL for sediment (e.g., stream or ditch silt) will be the same as the surface soil. The DCGL for subsurface soil will be the same as surface soil.

3.5 Radionuclide Mixture for FSS The radionuclides listed in Tables 3-1, 3-2 and 3-3 were selected after a detailed evaluation of the current characterization data including concrete core samples, smears, and media samples collected for analyses. The evaluations of radionuclide mixtures for soil and structure DCGL development are contained in Attachment A, "Radionuclide Distribution Basis for DCGL Determination, and FSS of the PBRF". The evaluation of radionuclide mixtures for embedded piping is contained in Attachment C, "Dose Assessment and DCGL Calculation for Embedded Pipe". Current and representative sample data are used to determine the final radionuclide mixtures for FSS.

Per NUREG-1757, the Nuclear Regulatory Commission (NRC) staff considers radionuclides and exposure pathways that contribute no greater than 10% of the 3-3

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 25 mrem/yr dose criteria to be insignificant contributors. This 10% limit for insignificant contributors is an aggregate limitation only. That is, the sum of the dose contributions from all radionuclides and pathways considered insignificant will be no greater than 10% of the dose criteria of 25 mremlyr per 10 CFR Part 20, Subpart E.

The dose from the insignificant radionuclides will be accounted for in demonstrating compliance, but may be eliminated from further detailed evaluations. The lowest total aggregate dose from the remaining radionuclides for PBRF structures was evaluated at 90% of the 25 mrem/yr criterion, which means that radionuclides potentially representing a dose of 2.5 mrem/yr were eliminated.

To ensure the 25 mrem/yr criterion is met, any structural survey unit where the mean of FSS results indicates that the dose may be greater than 22.5 mrem/yr (including dose from embedded pipe in the given survey unit, if applicable) shall be reviewed for compliance with the unrestricted use limit.

For PBRF soil, the doses from all radionuclides other than Cs-137, Co-60, and Sr-90 totaled 0.5 mrem/yr. Because this dose is 2% of the 25 mrem/yr limit, all radionuclides other than Cs-137, Co-60, and Sr-90 were eliminated from further consideration. To ensure the 25 mrem/yr criterion is met, any open land survey unit where the mean of FSS results indicates that the dose may be greater than 24.5 mrem/yr will be reviewed for compliance with the unrestricted use limit.

The only exposure pathway that is operative for PBRF embedded piping is direct dose from gamma-emitting radionuclides. All radionuclides that may be present in piping residual contamination are fixed in place by the grout and are not available for transport to ground water or to ingestion or inhalation pathways to a future building occupant.

3.6 Surrogate DCGL, Gross Beta Activity and the Unity Rule Hard-to-detect radionuclides (non-gamma emitters for soil and non-beta emitters for structures) will be addressed by using a surrogate relationship to another detectable radionuclide. A common example would be to relate a specific radionuclide, such as Cs-137, to one or more radionuclides of similar characteristics such as Sr-90. This directly applies to PBRF as gamma spectroscopy will be used to assess volumetric soil samples in comparison against the DCGL for soil. In such cases, to demonstrate compliance with the release criteria for the survey unit, the DCGL for the surrogate radionuclide, in this case Cs- 137 must be scaled to account for the fact that it is being used as an indicator for an additional radionuclide, Sr-90. The result is referred to as the surrogate DCGL.

For structural surfaces, the final DCGL for FSS design and implementation will be a gross beta DCGL that represents the unrestricted use criterion of 25 mrem/yr.

There are two steps required to determine the gross beta DCGL; 1) perform a surrogate calculation to account for radionuclides that cannot be readily measured 3-4

Final Status Survey Plan Revision 0 Plum Brook Reactor Facility Plum Facility Final Status Survey Plan Revision 0 by a beta detector (e.g., plastic beta scintillation, gas proportional) with typical efficiency; and, 2) perform a gross activity DCGL calculation on the surrogate DCGL values and other beta emitting radionuclides determined to be present in significant fractions. The equations to be used were derived from NUREG-1505, "A Nonparametric Statistical Methodology for the Design and Analysis of Final Status Decommissioning Surveys" and are listed below.

3.6.1 Surrogate Equation The surrogate DCGL is computed based on the distribution ratio between the hard-to-detect radionuclides and the easy-to-detect radionuclides. The surrogate DCGL is calculated using the following equation:

1 Surrogate~c =I 1___ + R2 +( R' L=[()DCGL,+ DCGL2 DCGL3 . DCGL.Jj Where: DCGLsur = Surrogate radionuclide DCGL DCGL2, 3... n = DCGL for radionuclides to be represented by the surrogate Rn = Ratio of concentration (or nuclide mixture fraction) of radionuclide "n" to surrogate radionuclide 3.6.2 Gross Beta Equation Where multiple radionuclides are present, the gross beta DCGL may be developed. This approach enables field measurements of gross activity rather than the determination of individual radionuclide activity for comparison to the radionuclide-specific DCGL. The gross beta DCGL is calculated using the following equation:

1 D.{DGLcJ Where: DCGLGB = gross beta DCGL fn = mixture fraction of radionuclide "n" and DCGLn = DCGL of radionuclide "n".

Note 1: The gross beta equation may also be used to calculate a gross alpha DCGL for application in areas where DCGL values are established for alpha emitters.

Note 2: If a surrogate radionuclide is used, the "fn" is equal to the surrogate radionuclide fraction.

3-5

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Note 3: The value of 1 in the numerator is replaced by the actual fraction of beta (or alpha) emitters if less than 100% of the mixture.

3.6.3 Unity Rule Equation The unity rule is typically used as the first test to evaluate compliance with radiological criteria for license termination when more than one radionuclide has been determined to be potentially present. In lieu of a single gross beta (or alpha) DCGL, a unity rule calculation is used to demonstrate compliance with the structure surface unrestricted use limit.

The unity rule is typically used as the first test to demonstrate compliance with surface soil limits. A surrogate DCGL, if applicable, would be used in the unity rule calculation. The unity rule is:

C1 +

+ C-2 ...... C 11,, <1 DCGL1 DCGL 2 DCGL, Where: Cn = concentration of radionuclide n and DCGL = DCGL of radionuclide n.

If two adjusted gross activity DCGL values (one for alpha and one for beta) are used, the unity rule must be applied to demonstrate compliance.

In the event that the unity rule test fails, i.e., the calculated sum of fractions is > 1, then evaluation of individual radionuclide concentrations against their DCGL values may be performed.

3.7 Area Factors The area factor is the multiple of the DCGL that is permitted in the area of elevated residual radioactivity without requiring remediation. The area factor is related to the size of the area over which the elevated residual radioactivity is distributed. That area, denoted AEMC, is generally bordered by levels of residual radioactivity below the DCGL, and is determined by the investigation. The area factor is the ratio of dose per unit area or volume for the default surface area for the applicable dose modeling scenario to that generated using the area of elevated residual radioactivity, AEMC. Area factors for surface soil, building reuse (structures), and embedded pipe are provided in Tables 3-4, 3-5, and 3-6, respectively. Area factor assumptions and calculations are provided in Attachments B and C.

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FinalStatus Survey Plan Revision 0 Brook Reactor Plum Brook Pl.um Facility Reactor Facility Final Status Survey Plan Revision 0 Table 3-4 Surface Soil Area Factors Elevated Area 1 2 3 5 10 15 25 100 250 2,000 (m2)

Area Fa 10.4 6.2 4.7 3.4 2.3 1.9 1.6 1.2 1.1 1 Factor Table 3-5 Building Reuse Area Factors (Structures)

Elevated Area 0.25 0.50 1 2 4 6 8 10 15 25 50 75 (m2 Area Fa 40.2 20.8 11.1 6.2 3.6 2.8 2.4 2.1 1.7 1.4 1.1 Factor 1 Table 3-6 Embedded Pipe Area Factors Pipe Length (ft) Total Dose from Pipes of Area Factor specified Length (mrem/h) 1 3.013E-10 5.9 2 5.834E-10 3.0 5 1.197E-09 1.5 10 1.531E-09 1.2 3-7

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 4.0 ESTABLISHING SURVEY UNITS 4.1 Survey Unit Survey areas listed in Tables 2-1 and 2-2 will be divided into discrete survey units. Survey units are areas that have similar characteristics and contamination levels. Survey units are assigned only one classification. The site and facility are surveyed, evaluated, and released on a survey unit basis.

4.1.1 Survey Unit Size Survey units are typically limited in size to ensure each area is assigned an adequate number of data points. The survey unit sizes for PBRF are provided in Table 4-1.2 Note that the maximum survey2 unit size for Class 1 structures is 75 m2, which is smaller than the 100 m recommended in NUREG-1575 (MARSSIM). The 75 m2 maximum was required to be consistent with the site-specific building reuse dose assessment assumptions.

Table 4-1 Recommended Survey Unit Areas for FSS Class Structures Land 1 up to 75 m 2* up to 2000 m 2 2 up to 1000 m 2 up to 10,000 m 2 3 up to 10,000 m2 up to 100,000 m 2

• Includes floor only 4.1.2 Site Reference Coordinate System (Reference Grid)

A reference coordinate system is used for impacted areas to facilitate the identification of the location of measurements and samples within the survey unit. The reference coordinate system is basically an X-Y plot of the site area referenced to an established fixed point monument. Once the reference point is established, grids may be overlaid parallel to lines of latitude and longitude.

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Plum Brook Reactor Facility Final Status Survey Plan Revision 0 5.0 SURVEY DESIGN This section describes the methods and data required to determine the number and location of measurements or samples in each survey unit, the coverage fraction for scan surveys, and requirements for measurements in background reference areas. The applicable design activities described in this section will be documented in a Survey Design Package for each survey unit.

5.1 Scan Survey Coverage The area covered by scan measurement is based on the survey unit classification.

A 100% accessible area scan of Class 1 survey units will be required. The emphasis will be placed on scanning the higher risk areas of Class 2 survey units such as soils, floors and lower walls. The percentage of scan coverage in Class 2 areas will be proportional to the potential for finding contamination that is close to the DCGL. Scanning percentage of Class 3 survey units will be performed on, likely areas of contamination based on the judgment of the FSS/Characterization Engineer. Minimum scan survey coverage requirements for the PBRF are provided in Table 5-1.

Table 5-1 Minimum Scan Survey Coverage Scan Measurements Class 1 Class 2 Class 3 Scan Coverage 100% 10 to 100% Minimum of 10%

5.2 Sample Size Determination This section describes the process for determining the number of survey measurements necessary to ensure that a data set is sufficient for statistical analysis. Sample size is based on the relative shift, the Type I and II errors, and the specific statistical test used to evaluate the data.

5.2.1 Determining Which Test Will Be Used Statistical tests will be used to determine if the FSS results are below the DCGLw. The Sign Test or Wilcoxon Rank Sum (WRS) Test will be implemented using unity rules, surrogate methods, or combinations of unity rules and surrogates.

The Sign Test is expected to be the most appropriate test for PBRF FSS results because background is expected to constitute a small fraction of the DCGL. If a situation is encountered where background is a significant fraction of the DCGL, the Wilcoxon Rank Sum (WRS) Test may be used.

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Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 5.2.2 Establish Decision Errors A decision error is the probability of making an error in the decision on a survey unit, either passing a survey unit that should fail or failing a survey unit that should pass. The first decision error, passing a survey unit that should fail, is referred to as a false positive or TYPE I decision error. The probability of making this error is denoted by "a". Setting a high value for a results in a higher risk of passing a survey unit that should fail. Setting a low value for a lowers the risk of passing a survey unit that should fail.

The a for the PBRF will be set at 0.05 and will not be increased without prior NRC approval.

The second decision error, failing a survey unit that should pass, is referred to as a false negative or TYPE II decision error and is denoted by "03". Selecting a high value for 03results in a higher risk of failing a survey unit that should pass and subjecting it to fuirther investigation. Selecting a low value for 03lowers the risk and minimizes these investigations. The P3 for the PBRF will initially be set at 0.10, or 10 percent probability based on site-specific considerations. Since the P3 is the licensee's risk, the PBRF project may choose to vary this value from 0.25, or 25 percent to 0.05 or 5 percent after evaluating the resulting change in the number of required survey measurements and the risk of unnecessarily investigating and/or remediating survey units that are truly below the release criteria.

5.2.3 Relative Shift The number of measurements needed depends on a ratio involving the concentration to be measured relative to the variability in the concentration. This ratio is called the relative shift (A / T)and is calculated as follows:

A _ (DCGLW-LBGR)

Where: Delta (A) = DCGLw minus the Lower Boundary of the Gray Region (LBGR)

Sigma (a) = Standard deviation of contaminant measurements collected within the survey unit LBGR = The concentration to which the survey unit must be remediated in order to have acceptable probability of passing the statistical test for meeting the site release criteria.

NOTE 1: The LBGR is initially set at 0.5 times the DCGLw, but may be adjusted to obtain an optimal value for the relative shift between 1 and 3.

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Plum Brook Reactor Facility FinalStatus Survey Plan Revision 1 NOTE 2: Use of a relative shift greater than 3 must be approved by the FSS/Characterization Manager.

5.2.4 Number of Measurements The number of background reference area or survey unit data points N is determined using Table 5.3 or Table 5.5 (as applicable) ofNUREG-1575 (MARSSIM). The tables include the recommended minimum 20%

adjustment to ensure an adequate sample size. Computer programs (i.e.,

CompassTM and VSPTM) may also be used to calculate N.

Special considerations may be necessary for survey units with structure surface areas less than 10 m22 or land areas less than 100 m2.2 In these cases, the number of data points obtained from the statistical tests may be unnecessarily large and not appropriate for smaller survey unit areas.

Instead, professional judgment may be used to determine the specified level of survey effort.

5.2.5 Elevated Measurement Comparison (EMC) Sample Size Adjustment If the scan Minimum Detectable Concentration (MDC) in a Class 1 survey unit is greater than the DCGLw, the sample size will be calculated using the equation provided below. No adjustment is required in a Class 2 or 3 survey unit. If NEMc exceeds the statistically determined sample size N, NEMC will replace N.

A Nrmc A' FMc Where: NEMC = elevated measurement comparison sample size A= survey unit area AEMC = area corresponding to the area factor calculated using the MDCsc, concentration 5.3 Background Reference Areas Background reference areas are used if either (a) the residual radioactivity contains a radionuclide of concern that also occurs in background or (b) the sample measurements to be made are not radionuclide-specific. Background reference areas are not needed when radionuclide-specific measurements are used to measure concentrations of a radionuclide that is not present in background.

They also are not needed when one or more radionuclides are present in background at such small fractions of the DCGL as to be considered insignificant.

Surveys are conducted in one or more background reference areas to determine background levels for comparison with the conditions determined in specific survey units. Background studies may be performed on any materials to be 5-3

Plum Brook Reactor Facility Final Status Survey Plan Revision I surveyed during the FSS including, but not limited to, soil, concrete, drywall, metals, glass, tile, brick, asphalt, and petroleum product wastes. In order to minimize systematic bias in the comparison, the same sampling procedure, measurement techniques, and type of instrumentation (e.g., detection sensitivity and accuracy) should be used at both the survey unit and the reference area.

5.3.1 Selection Background reference areas are selected in areas that have similar physical, chemical, radiological, and biological characteristics as the survey unit being evaluated. They are usually selected from near site non-impacted areas, but are not limited to natural areas undisturbed by human activities. Each background reference area should have an area at least as large as the survey unit in order to include the full potential spatial variability in background concentrations.

For materials present on site, either in buildings or as non-soil materials present in outdoor survey units (e.g., concrete, brick, drywall, petroleum product wastes, etc.), background reference areas of non-impacted materials that are as similar as possible to the materials on site are used.

In those situations where such materials are not available, a good faith effort is made to find either the most similar materials readily available or appropriate published estimates are used.

For soils, reference areas should have a soil type as similar to the soil type in the survey unit as possible. If there is a choice of possible reference areas with similar soil types, consideration will be given to selecting reference areas that are most similar in terms of other physical, chemical, geological, and biological characteristics.

5.3.2 Different Survey Unit Material Backgrounds Survey units may contain a variety of materials with markedly different backgrounds such as a room with concrete walls and floor, glass windows, metal doors, wood trim, and plastic fixtures. A separate survey unit is not necessarily established for each material. If one material is predominant or if there is not too great a variation in background among materials, a background reference area comprised of the predominant material may be appropriate. In this situation, PBRF will demonstrate that the selected reference area will not result in a significant underestimate of the residual radioactivity on other materials.

When there are different materials with substantially different backgrounds in a survey. unit, a non-impacted room with roughly the same mix of materials may be used as a background reference area. Alternately, measured backgrounds for the different materials or for groups of similar materials may be used. In this case, it is acceptable to perform the Sign 5-4

Plum Brook Reactor Facility FinalStatus Survey Plan Revision ]

Test on the difference between the paired measurements from the survey unit and from the appropriate background material.

5.3.3 Different Background Reference Areas If significant differences in background measurements among background reference areas are identified, a value of three times the standard deviation of the mean between the background reference areas is added to the mean background for all background reference areas to define a background concentration. The value of three times the standard deviation of the mean is chosen to minimize the likelihood that a survey unit that contains only background would fail the statistical test for release. The WRS test is then used to test whether the survey unit meets the radiological criteria for license termination.

5.3.4 Background Level Determinations In general, background levels will be established (as needed) for each type of instrument used for total surface contamination measurements, removable contamination measurements, and gamma exposure rate measurements. In addition, backgrounds will be determined for specialized detectors and detector systems (e.g., gamma spectroscopy systems and detectors used for surveying interiors of piping) on an as needed basis.

Volumetric material samples of soil, sediment, and concrete are collected in designated background reference areas and are analyzed for gamma activity using a gamma spectroscopy system. Additionally, laboratory analysis for other non-gamma emitting radionuclides will be performed, as necessary.

Background determinations will be performed in accordance with approved procedures and work instruction documents. Background values will be evaluated in accordance with MARSSIM (NUREG-1575) guidance.

5.4 Measurement Locations 5.4.1 Class 3 Survey Units Measurements locations in Class 3 survey units and background reference areas are taken in random locations. Random means that each measurement location in the survey unit has an equal probability of being selected. The random selection process uses random numbers that correspond to a survey unit's reference coordinate system to establish the measurement locations within the survey unit. The random numbers are generated using a random number generator. Measurement locations selected that do not fall within the survey unit area or cannot be surveyed due to site conditions may be replaced using the same random process.

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Plum Brook Reactor Facility Final Status Su~rey Plan Revision 1 5.4.2 Class 1 and 2 Survey Units For Class 1 and Class 2 survey units, a systematic pattern (triangular or rectangular grid) is used to establish measurement locations. After the spacing L is determined, a starting point is identified using the random selection process as described in section 5.4.1. Beginning at the random starting point, a row of measurement locations or points is identified parallel to the X axis at intervals of L. For a triangular grid, a second row of points is then developed parallel to the first row, at a distance of 0.866 x L from the first row. Points identified along that second row are midway between the points on the first row on the X-axis. For a rectangular grid, the points are identified around the random starting point in a perpendicular manner at intervals of L. The physical spacing of measurement locations are calculated as follows:

Triangular Grid L- A 0.866N Where: A = Survey unit Area N = Number of data points required based on statistical tests Rectangular Grid

)NW Where: A = Survey unit Area N = Number of data points required.

To simplify the designation of data points while assuring a sufficient number of data points are obtained for statistical purposes, the value of L is rounded down to the nearest distance easily measured in the field. If a point falls outside the survey unit or'at locations that cannot be surveyed, additional points may be determined using the random selection process as described in section 5.4.1.

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Plum Brook Reactor Facility FinalStatus Survey Plan Revision ]

5.5 FSS Design Package A FSS Design Package is produced for each survey unit or group of survey units, at the discretion of PBRF. Instructions for package development, implementation, and closure will be described in an approved PBRF procedure.

Each FSS Design Package will contain the following information, as applicable:

" A brief overview of the survey unit history

" A description of the survey unit

" A summary of statistical tests to be used to evaluate survey results

• A description of the background reference areas and materials and justification for their selection (required only if WRS Test is selected)

• A summary of static measurements or sample data used to both evaluate the success of remediation and to estimate the survey unit variability

• A description of radiological field instruments to be used and sensitivity

• For in-situ measurements made by field instruments, a description of the instruments, calibration, operational checks, sensitivity, and sampling methods, with a demonstration that the instruments and methods have adequate sensitivity

• Survey Area Maps showing the Survey Unit(s) and Measurement/Sample locations

• Specific survey and sampling instructions

" FSS investigation levels

• Justification for radionuclide mixture used to acquire gross activity and surrogate DCGL values

" DCGL values (i.e., DCGLw, DCGLEMC, etc.)

• Supporting documentation (e.g., Compass TM and VSPTM) 5-7

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 6.0 RADIOLOGICAL INSTRUMENTATION Proper selection and use of instrumentation will ensure that sensitivities are sufficient to detect radionuclides at the minimum detection requirements specified by the survey design which will assure the validity of the survey data. Commercially available portable and laboratory instruments and detectors are typically used to perform the three basic survey measurements: 1) surface scanning; 2) static measurements; and 3) spectroscopy of soil and other bulk materials, such as concrete. Specific implementing procedures control the issuance, use, and calibration of instrumentation.

6.1 Instrumentation Selection Radiation detection and measurement instrumentation is selected based on the type and quantity of radiation to be measured and the detection sensitivity.

Detection sensitivity requirements are specified in section 6.5.

A listing of typical radiological instrumentation that may be used for FSS are provided in Table 6-1. As the project proceeds, other measurement instruments or technologies, such as in-situ gamma spectroscopy, may be found to be more efficient or appropriate than the survey instruments proposed in this plan. The acceptability of such an instrument or technology for use in the final survey program must be justified and documented in a Technical Basis Document (TBD) or equivalent PBRF document. The TBD should include the following: (1) a description of the conditions under which the method would be used; (2) a description of the measurement method, instrumentation and criteria; (3) justification that the technique would provide acceptable MDCs; and (4) a demonstration that the method provides data that has a Type I error (falsely concluding that the survey unit is acceptable) equivalent to 5% or less.

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Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Table 6-1 Typical Radiological Instrumentation and Nominal MDC Nominal Detection Sensitivity Detector Model2 Meter Model Application MDCscI MDCstatiC' (dpm/100 cm2) (dpm/100 cm2)

Ludlum 44-9 Ludlum 2350-1 f3 static & scan 2900 985 Ludlum 43-5 Ludlum 2350-1 a static & scan 150 75 Ludlum 43-68 P3 mode Ludlum 2350-1 f3 static & scan 1050 330 Ludlum 43-68 a mode Ludlum 2350-1 a static & scan 170 70 Ludlum 44-116 Ludlum 2350-1 1 static & scan 1300 415 Ludlum 43-90 Ludlum 2350-1 a static & scan 130 55 3.5 pCi/g Ludlum 44-10 Ludlum 2350-1 y scan 60Co 6.5 N/A pCi/g 137Cs Ludlum 43-37 Ludlum 2350-1 f3 scan 1000 N/A Packard Tri-Carb 2900 N/A 13smear N/A 40 (Tritium)

TR LSC Canberra S5XLB or N/A a and/or 13N/A 18 Protean IPC-9025 smear HPGe Spe GammaSyste N/A y Analysis N/A Varies Spectroscopy System

1. Based on 1-minute count time; and default values for surface efficiencies,Es, as specified in Internal Standard, ISO 7503-1.

2. Functional equivalent instrumentation may be used.

6.2 Instrumentation Calibration All instrumentation used for FSS, including the gamma spectroscopy system, will be calibrated for normal use under typical field conditions and for the radiation types and energies of interest at least annually not to exceed 15 months.

Calibration typically includes:

• High Voltage Calibration

" Discriminator/Threshold Calibration

• Window Calibration 6-2

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0

• Alarm Operation Verification

• Scaler Calibration Verification

• Operating Voltage Determination

" Calibration Constant Determination

• Dead Time Correction Determination Calibrations will be performed in accordance with approved procedures. If vendor services are used, the vendor QA program is subject to approval of the PBRF. Radioactive sources will be traceable to the National Institute of Standards and Technology (NIST) or equivalent standards.

Calibration labels showing the instrument identification number, calibration date and calibration due date will be attached to all portable field instruments.

Calibration records will be maintained in accordance with PBRF record retention requirements.

6.3 Response Checks Instrumentation response checks are conducted to assure proper instrument response and operation. An acceptable response for field instrumentation is an instrument reading within +/-20% of the established check source value.

Laboratory instrumentation standards will be within +/- 3 sigma and not to exceed

+/- 20% as documented on a control chart. Response testing of portable radiological instrumentation and/or detectors used for FSS shall be performed prior to use and following use. If an instrument and/or detector are to be used for a continuous time frame greater than a standard work shift, the instrument and/or detector will be subjected to a response test prior to the end of that shift. If an instrument fails a response check, it is labeled appropriately and is removed from service until the problem is corrected in accordance with applicable procedures.

Data obtained with that instrument since its previous acceptable performance check, will be evaluated for acceptability. The results of this evaluation will be documented.

6.4 Minimum Detectable Concentration (MDC)

Minimum Detectable Concentration (MDC) is defined as the smallest amount or concentration of radioactive material that will yield a net positive count with a 5%

probability of falsely interpreting background responses as true activity from contamination and a 5% probability of interpreting a result at the MDC level as being background. The MDC is dependent upon the counting time, geometry, sample size, detector efficiency and background count rate. There are two different MDCs that will be used, one for direct alpha or beta surface 6-3

Survey Plan Revision 0 Brook Reactor Facility Plum Brook Facility FinalStatus Final Status Survey Plan Revision 0 contamination measurements, MDCstatic and one for field alpha or beta scanning of surfaces, MDCsCan. These are calculated differently and each will be incorporated into the operating procedures. The equation to be used for calculating the MDCstatic for direct alpha or beta surface measurements is as follows:

3 +3.29ýB,-t B (I+

MDCstatic - A 100 Where: MDCstatic = Minimum Detectable Concentration (dpm/100 cm 2),

BR = Background Count Rate (cpm),

tb = Background Count Time (min),

t= Sample Count Time (min),

A = Detector Area (cm 2) and Etot = Total Efficiency.

Total Efficiency (Etot) is equal to Detector Efficiency (Ei) multiplied by the applicable Surface Efficiency (Es).

The equation that will be used to calculate MDCscan for beta surface scan measurements is as follows:

d ,* -

• 60 MDCscan =

100 Where: MDCscan = Minimum Detectable Concentration (dpm/1 00 cm2) d' = Decision error taken from Table 6.5 of NUREG -1575 (MARSSIM) i = Observation counting interval (scan speed divided by the detector width) bi= Background count per observation interval E = Detector Efficiency (c/d) 6-4

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0

(- = Surface Efficiency (typically 25% for alpha and 50% for beta (ISO 7503-1, Table 2))

p = Surveyor Efficiency (typically 50%)

2 A = Detector Area (cm )

6.5 Detection Sensitivity The nominal detection sensitivity of some of the detectors that may be used for surface contamination surveys has been determined and is provided in Table 6-1.

Count times and scanning speed are calculated and selected to ensure that the measurements are sufficiently sensitive for the DCGL.

6.5.1 Structure Static Measurements Instruments used to perform beta and alpha static measurements of structures should be capable of detecting the radiation of concern to a MDC of less than 50% of the applicable DCGLw. Although, any value below the DCGL is acceptable.

6.5.2 Structure Scan Measurements Instruments used to perform beta and alpha scan measurements of structures should be capable of detecting the radiation of concern to a MDC of less than the DCGLw. If the MDCscan exceeds the DCGLw, additional static measurements may be required.

6.5.3 Soil Scan Measurements For scanning soil with a sodium iodide gamma detector, the MDCsoan values presented in Table 6.7 of NUREG -1575 (MARSSIM) will typically be used. According to NUREG- 1727, these values provide an acceptable estimate of MDCsca for the survey. Individual MDCsca* values may be calculated for sodium iodide detectors configured and calibrated to detect specific radionuclides such as Cs-137. If the MDCscan exceeds the DCGLw, additional soil samples may be required.

6.5.4 Volumetric Materials The MDC for gamma spectral analysis of soil, concrete, and other volumetric materials will be based on sample count times sufficient to detect 10% of the applicable DCGL values for the radionuclides of concern or best sensitivity achievable. The MDC for the beta counter for analysis of smears will be based on sample count times sufficient to detect 6-5

Survey Plan Revision 0 Plum Brook Reactor Facility Facility FinalStatus Final Status Survey Plan Revision 0 10% or less of the adjusted gross beta DCGL for the radionuclide mix appropriate for the survey area or best sensitivity achievable.

6.5.5 Embedded and Buried Piping Beta or gamma sensitive pipe probes are used for surveys of embedded and buried piping. Instruments used to perform static measurements should be capable of detecting the radiation of concern to a MDC of less than 50% of the applicable DCGLw. Although, any value below the DCGL is acceptable. Instruments used to perform scan measurements should be capable of detecting the radiation of concern to a MDC of less than the DCGLw. If the MDCscal exceeds the DCGLw, additional static measurements may be required.

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Plum Brook Reactor Facility Final Status Survey Plan Revision 0 7.0 RADIOLOGICAL SURVEY METHODS Trained and qualified personnel will perform survey measurements and collect samples.

FSS measurements include surface scans, static measurements, gamma spectroscopy of volumetric materials, and in-situ gamma spectroscopy. The surveying and sampling techniques are specified in approved procedures.

7.1 Structures Structures will receive scan surveys, static measurements and, when necessary, volumetric sampling.

7.1.1 Surface Scans Surface scanning is performed in order to locate small areas of residual activity above the investigation level. Beta scans will be performed over accessible floor, wall and ceiling interior and exterior surfaces, asphalt, and concrete paved areas. In general, beta scans are performed with the detector held at less than 2 cm from the surface and moved at a rate such that residual radioactivity can be detected at or below the investigation level. Alpha scans may be performed in areas where alpha contamination has been observed and if a surrogate is not used. In general, alpha scans are performed with the detector held as close to the surface as possible and moved at a rate such that there is a high probability of detecting elevated residual activity.

Technicians will respond to indications of elevated areas while surveying.

Upon detecting an increase in visual or audible response, the technician will reduce the scan speed or pause and attempt to isolate the elevated area. If the elevated activity is verified to exceed the established investigation level, the area is bounded (e.g., marked and measured to obtain an estimated affected surface area). Representative static measurements are obtained as determined by the FSS/Characterization Engineer. The collected data is documented on a Radiological Survey Form.

If surface conditions prevent scanning at the specified distance, the detection sensitivity for an alternate distance will be determined and the scanning technique adjusted accordingly. Whenever possible, technicians will monitor the audible response to identify locations of elevated activity that require further investigation and/or evaluation.

7.1.2 Static Measurements Static measurements are performed to detect total surface activity levels.

Static measurements are conducted by placing the detector on or very near 7-1

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 the surface to be counted and acquiring data over a pre-determined count time. A count time of one minute is typically used and generally provides an acceptable DCGLstatic. Measurements will be performed at designated locations and at locations of elevated activity identified by surface scans within each survey unit. Static measurements will be performed in pairs of shielded and non-shielded measurements.

7.1.3 Activated Concrete The current decommissioning strategy for PBRF calls for the removal of activated portions of the concrete bio-shield and disposition of the activated concrete as radioactive waste. Any potentially activated concrete remaining in place will be evaluated for residual radioactive contamination volumetrically using the subsurface structure DCGL values provided in Attachment B, Table B-14.

7.1.4 Volumetric Concrete Measurements Volumetric sampling of contaminated concrete, as opposed to static measurements may be necessary if gross beta measurements are insufficient or subsurface activity greater than the DCGLw is suspected.

Volumetric concrete samples will be analyzed by gamma spectroscopy and for hard to detect radionuclides, as necessary. The results will either be evaluated by 1) calculating the derived total gross beta dpm/100 cm 2 in the sample and comparing the gross beta results directly to the gross beta DCGL or, 2) compare results to the volumetric DCGL values for subsurface structures coupled with application of the unity rule. Use of the unity rule may require the use of a surrogate calculation to account for the radionuclides in the mixture not identified by gamma spectroscopy.

This will be accomplished using the appropriate nuclide mixture for the applicable survey unit.

7.1.5 Loose Surface Contamination Surveys Loose surface contamination (smear) surveys will be performed to verify contamination is 10% or less of the DCGLw consistent with assumptions made during dose modeling for structural DCGL development. A smear will be collected at each static measurement location. This process is performed by wiping 100 cm of surface area with a circular cloth or paper filter using moderate pressure. Smear samples will be evaluated for gross beta activity and gross alpha for areas known to contain alpha contamination. Each survey unit with smear results exceeding the building reuse 10% modeling assumption will be evaluated on a case-by-case basis to determine if the 25 mrem/yr limit is met (see Attachment B).

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Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 7.1.6 Cracks, Crevices, Wall-Floor Interfaces and Small Holes Surface contamination on irregular structure surfaces (e.g., cracks, crevices, and small holes) is difficult to survey directly. Where no remediation has occurred and residual activity has not been detected above background, these surface blemishes may be assumed to have the same level of residual activity as that found on adjacent surfaces. The accessible surfaces are surveyed in the same manner as other structural surfaces and no special corrections or adjustments have to be made.

In situations where remediation has taken place or where residual activity has been detected above background, representative volumetric samples of the crack, crevice, or small hole may be obtained and evaluated per section 7.1.4. Other methods of evaluation may include adjustment of the instrument efficiency (ifjustifiable) or surveying the imperfection with a smaller detector (i.e., sodium iodide detector) and estimating the surface activity.

7.1.7 Paint Covered Surfaces Surfaces painted to fix loose contamination are remediated before FSS activities begin. For other surfaces painted after site start-up, representative samples are collected in areas where it is suspected that elevated levels of residual radioactivity could have been covered over.

Detection sensitivities are adjusted or remediation is performed as directed by the analysis results. NUREG 1507, "Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions" provides additional guidance.

7.2 Surface Soil Surface soil refers to outdoor areas where the soil is, for purposes of dose modeling, considered to be uniformly contaminated from the surface down to a depth of 15 cm (6 in). These areas will be surveyed through combinations of sampling, scanning, and in-situ measurements, as appropriate.

7.2.1 Surface Scans Gamma scanning will be performed over land surfaces to identify locations of residual surface activity. The gamma emitters are used as surrogates for the hard-to-detect radionuclides. NaI gamma scintillation detectors (typically 2" x 2") will be used for these scans. Scanning is generally performed by moving the detector in a serpentine pattern within 15cm (6 in) from the surface, while advancing at a rate not to exceed 0.5 m (20 in) per second. Audible signals should be monitored.

7-3

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Technicians will respond to indications of elevated areas while surveying.

Upon detecting an increase in visual or audible response, the technician will reduce the scan speed or pause and attempt to isolate the elevated area. If the elevated activity is verified to exceed the established investigation level, the area is bounded (e.g., marked or flagged and measured to obtain an estimated affected surface area). Representative static measurements are obtained as determined by the FSS/Characterization Engineer. The collected data is documented on a Radiological Survey Form.

7.2.2 Surface Sampling Samples of soil (including sediment or sludge) will be obtained from designated locations and at areas of elevated activity identified by gamma scans. An appropriate volume of soil (typically 1 liter) will be collected at each sampling location using hand trowels, bucket augers, or other suitable sampling tools.

Sample processing involves removal of extraneous material and drying of the material. The sample material is then placed into a clean counting container for gamma spectroscopy analysis. All samples are tracked from time of collection through the final analysis in accordance with a chain-of-custody program.

7.3 Subsurface Soil Subsurface soil refers to residual radioactivity that is underneath structures such as building floors/foundations or material that is covered with clean soil or some other non-contaminated layer. Subsurface soil is evaluated through sampling. In accordance with DG-4006, scanning is not applicable to sub-surface activity assessments.

The historical site assessment should be reviewed to identify those survey areas where the potential exists for sub-surface radioactivity. Such areas can include, but are not limited to: soils under buildings; soils adjacent to building foundations or components where leakage was known or suspected to have occurred in the past; and areas where known spills of radioactive materials have occurred. Data from both the historical site assessment and any pertinent characterization data should be used to establish a bounding depth profile for any potential sub-surface radioactivity.

7.3.1 Subsurface Sampling Subsurface soil will be sampled by collecting core samples from 15 cm (6 in) below grade to the required depth. The number of samples required (N) is determined for the applicable statistical test applied.

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Plum Brook Reactor Facility Final Status Survey Plan Revision 0 GeoProbe, split spoon sampling or other methods may be used for the FSS unless the area has already been excavated and remediated. If remediation of the area has been conducted, and post remediation surveys and sampling indicate that the remediation is complete and the area is ready for FSS, then the. excavation will be treated as surface soil and surveyed and sampled accordingly.

Samples are segmented and homogenized over each one meter of depth.

Extraneous material is removed from each segment and is adequately dried. The material is then placed into a clean counting container for gamma spectroscopy analysis. All samples are tracked from time of collection through the final analysis in accordance with a chain-of-custody program.

7.4 Stored Excavated Soil In several areas, clean overburden soils may be removed and stockpiled on site for use as backfill materials. The primary area where this is expected to occur is the excavation of the storm drain system. These areas are primarily Class 3 areas; however the excavation and stockpile of soils from Class 1 and 2 areas is possible. Prior to the use of stockpiled excavated soils as backfill, the soil will be subjected to FSS in accordance with the classification of the area from which it had originated. Scanning requirements and soil sample frequency shall also be determined in accordance with the classification of the area where the soil had originated.

7.5 Embedded and Buried Piping Designated sections of embedded and buried piping will be remediated in place and undergo FSS. Compliance with the DCGL values, as presented in section 3.3 and Attachment C, will be assessed through the acquisition of measurements utilizing "pipe-crawling" technology and may include beta/gamma surface contamination measurements, static gamma measurements, or in-situ gamma-spectroscopy. Radiological evaluations that cannot be accessed directly will be performed via measurements made at traps and other appropriate access points where the activity levels are deemed to either bound or be representative of the interior surface activity levels. Embedded piping will be filled with grout after the FSS.

7.6 Pavement Covered Areas The survey design of parking lots, roads and other 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 structure DCGL values presented in Table 3-2 are applicable to paved areas because the dose pathways and source geometry (i.e., area source) are essentially the same as those assumed 7-5

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 in the Building Reuse scenario. In addition, the agricultural pathways are not applicable. The structure DCGL values are conservative since the direct dose from a 2000 m outdoor area is less than the dose from the Building Reuse scenario. An outdoor occupancy time of 963 hrs is used in the Surface Soil dose assessment, whereas in the Building Reuse scenario, an occupancy time of 2340 hrs is assumed. Also, dose from the re-suspension of radionuclides from paved surfaces will be less than in the Building Reuse scenario because the effective air exchange rate in an outdoor area is expected to be much higher than that seen in buildings. Scan and static beta surveys are made as determined by the survey unit design. If sub-surface contamination is possible under paved or other covered areas, sub-surface volumetric samples should be collected.

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Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 8.0 INVESTIGATION LEVELS AND ELEVATED AREAS TEST During survey unit measurements, levels of radioactivity may be identified by an increase in count rate or an elevated sample result that warrant investigation. Elevated measurements may result from discrete particles, a distributed source, or a change in background activity.

8.1 Investigation Levels Investigation levels are radioactivity levels that are based on the site release criteria, which if exceeded, initiate an investigation of the survey data.

Investigation levels also serve as quality control checks to guard against misclassification of a survey unit, identify deficiencies in the remediation process, identify a possible instrumentation failure or large variations in background. The Investigation levels are established for each area classification as shown in Table 8-1.

Table 8-1 PBRF Investigation Levels Static Measurement or Classification Sample Result Scan Investigation Levels Investigation Levels Class 1 >DCGLEMC >DCGLEMC

> DCGLW >DCGLw or >MDCsan if MDCsoan is Class 2 >greater than DCGLW Class 3 > 50 % of the DCGLw >DCGLw or >MDCscan if MDCscSn is Cs greater than DCGLw 8.2 Investigation Process Investigation levels are provided in each Survey Design Package. Locations identified by scan or static measurements with residual radioactivity that exceeds an investigation level are marked and verified true. The area around the elevated radioactivity is investigated to determine the extent and to verify that other undiscovered elevated radioactivity does not exist. If the elevated activity was identified during scanning, representative static measurements and/or samples are collected.

Investigations should consider: (1) the assumptions made in the survey unit classification; (2) the most likely or known cause of the contamination; and (3) the possibility that other areas within the survey unit may have elevated areas of 8-1

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 activity that may have gone undetected. Depending on the results of the investigation, the survey unit may require no action, may require remediation, and/or may require reclassification and resurvey. Results of the investigation process are documented. Investigation actions are shown in Table 8-2.

Table 8-2 Investigation Actions Action if Investigation Results Exceed:

Class DCGLEMc DCGLW 0.5 DCGLW Remediate and Perform statistical testing, resurvey as necessary nesar and resurvey as remediate Acceptable necessary Remediate, reclassify Increase scan coverage and 2 portions as necessary reclassify portions as Acceptable necessary Increase scan coverage and Increase scan coverage 3 Remediate, reclassify reclassify portions as and reclassify portions as portions as necessary necessary necessary 8.3 Elevated Measurement Comparison (EMC)

The elevated measurement comparison may be used for Class 1 survey units when one or more scan or static measurements exceed the investigation level if remediation is not performed. The EMC provides assurance that unusually large measurements receive the proper attention and that any area having the potential for significant dose contribution is identified. As stated in NUREG- 1575 (MARSSIM), the EMC is intended to flag potential failures in the remediation process and should not be considered the primary means to identify whether or not a survey unit meets the release criterion.

Locations identified by scan with levels of residual radioactivity which exceed the DCGLEMC or static measurements with levels of residual radioactivity which exceed the DCGLEMc are subject to additional surveys to determine compliance with the elevated measurement criteria. The size of the area containing the elevated residual radioactivity and the average level of residual activity within the area are determined. The average level of activity is compared to the DCGLw based on the actual area of elevated activity. (If a background reference area is being applied to the survey unit, the mean of the background reference area activity may be subtracted before conducting the EMC).

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Survey Plan Revision 0 Plum Brook Reactor Facility Brook Reactor Facility Final Status Final Status Survey Plan Revision 0 The initial DCGLEMc is established during the survey design and is calculated as follows:

DCGLsuc = Area Factorx DCGL The area factor is the multiple of the DCGL that is permitted in the area of elevated residual radioactivity without remediation. The area factor is related to the size of the area over which the elevated activity is distributed. That area is generally bordered by levels of residual radioactivity below the DCGL and is determined by the investigation process. The method for calculating the area factors is provided in Attachment B and the resulting area factors are listed in Tables 3-4, 3-5, and 3-6.

The actual area of elevated activity is determined by investigation surveys and the area factor is adjusted for the actual area of elevated activity. The product of the adjusted area factor and the DCGLw determines the actual DCGLEMc. If the DCGLEMC is exceeded, additional investigations are performed.

The results of the elevated area investigations in a given survey unit that are below the DCGLEMC limit are evaluated using the equation below. If more than one elevated area is identified in a given survey unit, the unity rule can be used to determine compliance. If the equation value is less than unity, no further elevated area testing is required and the EMC test (shown below) is satisfied:

S (average concentration in elevated area - 15)

• 1.0 DCGL w + (Area Factor)(DCGLw)

Where: 8 is the average residual activity in the survey unit.

When calculating 8 for use in this inequality, measurements falling within the elevated area may be excluded provided the overall average in the survey unit is less than the DCGLw.1 For embedded piping, the number of elevated areas will be limited to ensure that the total inventory remaining in each EP will be maintained at the level that would be present if the entire pipe were contaminated at the DCGL level.

Compliance with the soil DCGLEMC will be determined using the FSS gamma spectroscopy results and a unity rule approach. These general methods will also be applied to other materials where sample gamma spectroscopy is used for FSS.

The application of the unity rule to the elevated measurement comparison requires MARSSIM, NUREG-1575, Revision 1, (June 2001), Section 8.5.2, per the EPA website at www.epa.gov/radiation/marssim/docs/revision 1.

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Plum Brook Reactor Facility Final Status Survey Plan Revision 0 area factors and corresponding DCGLEMC to be calculated for Cs-137, Co-60, and any other gamma emitter identified during FSS, separately.

The methods used to calculate the nuclide specific soil area factors are presented in Attachment B. These area factors are used to determine DCGLEMC for Co-60, Cs-137, and any other identified gamma emitter, for each elevated area being evaluated during FSS. The surrogate radionuclides will be conservatively accounted for through the application of the Cs-137 area factor to the surrogate Cs-137 DCGL since the hard-to-detect radionuclides have higher area factors than Cs-137. The DCGLEMc are used as follows to determine compliance with the elevated measurement comparison. Background could be subtracted from each radionuclide concentration if necessary:

Cs-137 Co-60 RN SCs - 13 7DCGLpjc Co - 60 DCGLc) DCGLEMc, Where: Cs-137 and Co-60 are the gamma spectroscopy results from FSS, DCGLEMc, is calculated for the size of the elevated area being evaluated, RN is any other gamma emitter identified during FSS, and DCGL mc, is the DCGLEMC for radionuclide N.

8.4 Remediation and Reclassification As shown in Table 8-2, for any classification (1, 2 or 3), areas of elevated residual activity above the DCGLEMc are remediated to reduce the residual radioactivity to acceptable levels. Whenever an investigation confirms activity above an action level listed in Table 8-2, an evaluation of the historical site assessment, operational history, design information, and sample results will be performed and documented. The evaluation will consider: (1) the elevated area's location, dimensions, and sample results, (2) an explanation as to the potential cause and extent of the elevated area in the survey unit, (3) the recommended extent of reclassification, if considered appropriate, and (4) any other required actions.

Areas that are reclassified as Class 1 are typically bounded by a Class 2 buffer zone to provide further assurance that the reclassified area completely bounds the elevated area. This evaluation process is established to avoid the unwarranted reclassification of an entire survey unit (which can be quite large) while at the same time requiring an assessment as to extent and reasons for the elevated area.

If remediation is performed in a Class 1 survey unit, the survey is redesigned and re-performed accordingly. If an individual survey measurement (scan, static, or material sample) in a Class 2 survey unit exceeds the DCGL, the survey unit or a 8-4

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 portion of it shall be reclassified to a Class 1 and the survey redesigned and re-performed accordingly. If an individual survey measurement in a Class 3 survey unit exceeds 0.5 DCGL, the survey unit, or portion of a survey unit, will be evaluated, and if necessary, reclassified to a Class 2 and the survey redesigned and re-performed accordingly.

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Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 9.0 DATA COLLECTION AND PROCESSING 9.1 Sample Handling and Record Keeping A chain-of-custody record accompanies each sample from the point of collection through obtaining the final results to ensure the validity of the sample data.

Chain-of-custody records are controlled and maintained and, upon completion of the data cycle, are transferred to Document Control, in accordance with applicable procedures.

Each survey unit's Survey Design Package will be controlled in accordance with FSS implementing procedures. These procedures address the design and field implementation of the survey requirements. Survey unit records are quality records.

9.2 Data Management Measurements performed during characterization, turnover and investigation surveys can be used as FSS data if they are performed according to the same requirements as the final survey data. These requirements include: (1) the survey data is representative of the as-left survey unit condition and is not impacted by further remediation; (2) the application of isolation measures to the survey unit to prevent re-contamination and to maintain final configuration; and (3) the data collection and design were in accordance with FSS methods (e.g., MDCsca, investigation levels, survey data point number and location, statistical tests, and EMC tests).

Measurement results stored as FSS data constitute the final survey of record and are included in the data set for each survey unit used for determining compliance with the site release criteria. Measurements are recorded in units appropriate for comparison to the DCGL. The recording units for surface contamination are dpm/100 cm 2 and pCi/g for activity concentrations. Numerical values, including negative numbers, are recorded.

Document Control procedures establish requirements for record keeping.

Measurement records include, at a minimum, the surveyor's name, the location of the measurement, the instrument used, measurement results, the date and time of the measurement and any surveyor comments.

9.3 Data Verification and Validation The FSS data are reviewed before data assessment to ensure that they are complete, fully documented and technically acceptable. The review criteria for data acceptability will include at a minimum, the following items:

• Compliance with survey instructions as specified in the survey package 9-1

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0

• The instrumentation MDC for fixed or volumetric measurements was below the DCGLw or if not, below the DCGLEMC for Class 1, below the DCGLw for Class 2 and below 0.5 DCGLw for Class 3 survey units.

• The instrument calibration was current and traceable to NIST standards.

• The field instruments were source checked with satisfactory results before and after use each day data are collected or if unsatisfactory, data obtained with that instrument since its previous acceptable performance check was evaluated for acceptability.

• The MDCs and assumptions used to develop them were appropriate for the instruments and techniques used to perform the survey.

• The survey methods used to collect data were proper for the types of radiation involved and for the media being surveyed.

• "Special methods" for data collection were properly applied for the survey unit under review.

• The chain-of-custody was tracked from the point of sample collection to the point of obtaining results.

• The data set is comprised of qualified measurement results collected in accordance with the survey design, which accurately reflects the radiological status of the facility.

• The data has been properly recorded.

If the data review criteria were not met, the discrepancy will be reviewed and the decision to accept or reject the data will be documented.

9.4 Graphical DataReview Survey data may be graphed to identify patterns, relationships or possible anomalies which might not be apparent using other methods of review. A posting plot or a frequency plot may be made. Other special graphical representations of the data will be made as needed.

9.4.1 Posting Plots Posting plots may be used to identify spatial patterns in the data. The posting plot consists of the survey unit map with the numerical data shown at the location from which it was obtained. Posting plots can reveal patches of elevated radioactivity or local areas in which the DCGL is exceeded. Posting plots can be generated for background reference areas to point out spatial trends that might adversely affect the use of the data.

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Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Incongruities in the background data may be the result of residual, undetected activity, or they may just reflect background variability.

9.4.2 Frequency Plots Frequency plots may be used to examine the general shape of the data distribution. Frequency plots are basically bar charts showing data points within a given range of values. Frequency plots reveal such things as skewness and bimodality (having two peaks). Skewness may be the result of a few areas of elevated activity. Multiple peaks in the data may indicate the presence of isolated areas of residual radioactivity or background variability due to soil types or differing materials of construction. Variability may also indicate the need to more carefully match background reference areas to survey units or to subdivide the survey unit by material or soil type.

9-3

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 10.0 DATA ASSESSMENT AND COMPLIANCE An assessment is performed on the FSS data to ensure that they are adequate to support the determination to release the survey unit. Simple assessment methods such as comparing the survey data to the DCGL or comparing the mean value to the DCGL are first performed. The statistical tests are then applied to the final data set and conclusions are made as to whether the survey unit meets the site release criterion.

10.1 Data Assessment Including Statistical Analysis The results of the survey measurements are evaluated to determine whether the survey unit meets the release criterion. In some cases, the determination can be made without performing complex, statistical analyses.

10.1.1 Interpretation of Sample Measurement Results An assessment of the measurement results is used to quickly determine whether the survey unit passes or fails the release criterion or whether one of the statistical analyses must be performed. The evaluation matrices are presented in Tables 10-1 and 10-2.

Table 10-1 Interpretation of Sample Measurements When the WRS Test Is Used Measurement Results Conclusion Difference between maximum survey unit Survey unit meets concentration and minimum reference area concentration is less than the DCGLw Difference of survey unit average concentration and reference average Survey unit fails concentrations greater than the DCGLw Difference between any survey unit concentration and any reference area Conduct WRS test and concentration is greater than the DCGLw elevated measurements and the difference of survey unit average test concentration and reference area average concentration is less than the DCGLw 10-1

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Table 10-2 Interpretation of Sample Measurements When the Sign Test is Used Measurement Results Conclusion Survey unit meets All concentrations less than the DCGLw release criterion Average concentration greater than the Survey unit fails DCGLw Any concentration greater than the Conduct Sign Test and DCGLw and average concentration less elevated measurements than the DCGLw test When required, one of four statistical tests will be performed on the survey data:

• WRS Test

• Sign Test

• WRS Test Unity Rule

• Sign Test Unity Rule In addition, survey data are evaluated against the EMC criteria as previously described in section 8.3 and as required by NUREG 1727. The statistical test is based on the null hypothesis that the residual radioactivity in the survey unit exceeds the DCGL. There must be sufficient survey data at or below the DCGL to reject the null hypothesis and conclude the survey unit meets the site release criterion for dose. Statistical analyses may be performed using a computer software program or, if necessary, using hand calculations.

10.1.2 Wilcoxon Rank Sum Test The WRS test, or WRS Unity Rule (NUREG-1505, Chapter 11), may be used when the radionuclide of concern is present in the background or measurements are used that are not radionuclide-specific. In addition, this test is valid only when "less than" measurement results do not exceed 40 percent of the data set.

The WRS test is applied as follows:

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Plum Brook Reactor Facility Final Status Survey Plan Revision 0

1. The background reference area measurements are adjusted by adding the DCGLw to each background reference area measurement, Xi, Zi = Xi + DCGL

2. The number of adjusted background reference area measurements, m, and the number of survey unit measurements, n, are summed to obtain N, (N = m + n).

3. The measurements are pooled and ranked in order of increasing size from 1 to N. If several measurements have the same value, they are assigned the average rank of that group of measurements.

4. The ranks of the adjusted background reference area measurements are summed to obtain Wr.

5. The value Of Wr is compared with the critical value in Table 1.4 of NUREG-1575 (MARS SIM). If Wr is greater than the critical value, the survey unit meets the site release dose criterion. If Wr is less than or equal to the critical value, the survey unit fails to meet the criterion.

10.1.3 Sign Test The Sign Test and Sign Test Unity Rule are one-sample statistical tests used for situations in which the radionuclide of concern is not present in background, or is present at acceptable low fractions compared to the DCGLW. If present in background, the gross measurement is assumed to be entirely from plant activities. This option is used when it can be reasonably expected that including the background concentration will not affect the outcome of the Sign Test. The advantage of using the Sign Test is that a background reference area is not needed. The Sign Test may also be applied to net values after material and/or ambient background subtraction. The Sign test is conducted as follows:

1. The survey unit measurements, Xi, i = 1, 2, 3, ...N; where N the number of measurements, are listed.

2. Xi is subtracted from the DCGLw to obtain the difference Di = DCGLw - Xi , i = 1, 2, 3,..., N.

3. Differences where the value is exactly zero are discarded and N is reduced by the number of zero measurements.

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Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0

4. The number of positive differences is counted. The result is the test statistic S+. Note that a positive difference corresponds to a measurement below the DCGLw and contributes evidence that the survey unit meets the site release criterion.

5. The value of S+ is compared to the critical value given in Table 1.3 ofNUREG-1575 (MARSSIM). The table contains critical values for given values of N and a. The value of a is set at 0.05 during survey design. If S+ is greater than the critical value given in the table, the survey unit meets the site release criterion. If S+ is less than or equal to the critical value, the survey unit fails to meet the release criterion.

10.1.4 Unity Rule The Cs-137 to Co-60 ratio will vary in the final survey soil samples, and this will be accounted for using a "unity rule" approach as described in NUREG-1505 Chapter 11. Unity Rule equivalents will be calculated for each measurement result using the surrogate adjusted Cs-137 DCGL and the adjusted Co-60 DCGL, as shown in the following equation:

C1 / DCGL1 + C 2 /DCGL 2 +.... Cn/DCGLn <1 Where: Cn = concentration of radionuclide n and DCGLnI = DCGL of radionuclide n The unity rule equivalent results will be used to demonstrate compliance assuming the DCGL is equal to 1.0 using the criteria listed in Tables 10-1 and 10-2. If the application of the WRS or Sign test is necessary, these tests will be applied using the unity rule equivalent results and assuming that the DCGL is equal to 1.0. An example of a test using the unity rule is provided in NUREG- 1505.

10.2 Data Conclusions The results of the statistical tests, including application of the EMC, allow one of two conclusions. The first conclusion is that the survey unit meets the unrestricted use criterion. The data provides statistically significant evidence that the level of residual radioactivity in the survey unit does not exceed the release criterion. The decision to release the survey unit is made with sufficient confidence and without further analysis.

The second conclusion that can be made is that the survey unit fails to meet the release criterion. The data are not conclusive in showing that the residual 10-4

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 radioactivity is less than the release criterion. The data are analyzed further to determine the reason for the failure.

Possible reasons include:

1. The average residual radioactivity exceeds the DCGL, or

2. The test did not have sufficient power to reject the null hypothesis (i.e., the result is due to random statistical fluctuation).

The power of the statistical test is a function of the number of measurements made and the standard deviation in measurement data. The power is determined from 1-13 where P3 is the value for Type II errors. A retrospective power analysis will be performed using the methods described in Appendices 1.9 and 1.10 of NUREG-1 575 (MARSSIM). A greater number of measurements increase the probability of passing if the survey unit actually meets the release criterion. If failure was due to the presence of residual radioactivity in excess of the release criterion, the survey unit must be remediated and resurveyed.

10.3 Compliance The FSS is designed to demonstrate that licensed radioactive materials have been removed from PBRF facilities and property to the extent that residual levels of radioactive contamination are below the radiological criteria for unrestricted use as approved by the NRC. The site-specific radiological criteria presented .in this plan demonstrate compliance with the criteria of 10 CFR 20.1402.

If the measurement results pass the requirements of Tables 10-1 and 10-2 of section 10.1.1, and the elevated areas evaluated per section 8.3 pass the elevated measurement comparison, then the survey unit is suitable for unrestricted release.

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Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 11.0 REPORTING FORMAT Survey results are documented in history files, survey unit release records, and in the Final Status Survey Report (FSSR). Other reports may be generated as requested by the NRC.

11.1 History File A history file of relevant operational and decommissioning data should be compiled. The history file should consist of relevant historical site assessment information, Characterization Survey data and the classification basis. The purpose of the history file is to provide a substantive basis for the survey unit classification, and hence, the level of intensity of the FSS.

11.2 Survey Unit Release Record A separate release record is prepared for each survey unit. The survey unit release record is a stand-alone document containing the information necessary to demonstrate compliance with the site release criteria. This record includes:

• Description of the survey unit

• Survey unit design information

• Survey unit measurement locations and corresponding data

• Survey unit investigations performed and their results

• Survey unit data assessment results

• Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mrem/yr and dose contributions from EP and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils A check-list may be employed as part of the implementing procedure to ensure all required information and evaluations are contained within each survey unit release record. When a survey unit release record is given final approval, it becomes a quality record.

11.3 Final Status Survey Report FSS results will be described in a written report to the NRC. The actual structures, land, or system included in each written report may vary depending on the status of ongoing decommissioning activities.

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Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 The FSS report provides a summary of the survey results and the overall conclusions, which demonstrate that the PBRF facility and site meet the radiological criteria for unrestricted use. Information such as the number and type of measurements, basic statistical quantities, and statistical analysis results are included in the report. The level of detail is sufficient to clearly describe the FSS program and to certify the results. The format of the final report will contain the following topics as applicable:

" Overview of the results

" Discussion of changes to the FSS from what was proposed in the FSSP or other prior submittals

" FSS methodology

• Survey unit sample size

" Justification for sample size

• FSS Results

• Number of measurements taken

" Maps identifying measurement locations

• Sample concentrations

• Statistical evaluations, including power curves

" Judgmental and miscellaneous data sets

" Anomalous data

• Conclusion for each survey unit

• Any changes from initial assumptions on extent of residual activity 11-2

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 12.0 FSS QUALITY ASSURANCE & QUALITY CONTROL (QA/QC)

The objective of QA/QC implementation is to ensure that the survey data collected are of the type and quality required to demonstrate that the dose from residual contamination is below the 25 mremryr unrestricted use criteria and to support a decision to terminate the PBRF license. Proper application of QA/QC will ensure that: 1) the elements of the FSS plan are implemented in accordance with the approved procedures; 2) surveys are conducted by trained personnel using calibrated instrumentation; 3) the quality of the data collected is adequate; 4) all phases of survey package design and implementation are properly reviewed, and oversight is provided; and 5) corrective actions, when identified, are implemented in a timely manner and are determined to be effective.

12.1 Project Management and Organization NASA's Glenn Research Center (GRC) is responsible for overall execution of the PBRF Decommissioning Project and for public health and safety. As licensee, GRC provides oversight of the decommissioning effort and has established a team of qualified personnel to execute decommissioning of the PBRF. Complete details regarding roles and responsibilities are provided in Section 2.0 of the Decommissioning Plan.

The decommissioning team will provide the necessary personnel, materials, and subcontractors to perform all phases of decommissioning work including performance of the FSS. Trained and experienced personnel will perform the FSS in accordance with the protocols and process presented in this plan using written survey instructions and approved procedures. Specific members that are directly involved with the FSS are listed below.

12.1.1 NASA Project Radiation Safety Officer (RSO)

The NASA Project RSO is responsible for organizing, administering, and directing the radiation protection program at the PBRF during decommissioning activities, including radiation safety, environmental health, and FSS Program. Additional information is provided in Section 2.0 of the Decommissioning Plan.

12.1.2 FSS/Characterization Manager The FSS/Characterization Manager is responsible for the organization, administration, development, and implementation of the FSS program under the FSS Plan. He/she is also responsible for technical review of Survey Design Packages and development of the Final Status Survey Report. The FSS/Characterization Manager reports to the NASA Project RSO.

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Plum Brook Reactor Facility Final Status Survey Plan Revision 0 12.1.3 FS S/Characterization Engineers FSS/Characterization Engineers provide technical direction for the FSS, including development and closure of FSS Design Packages, data evaluation, procedure development, and development of survey unit release records and history files. FSS/Characterization Engineers report to the FSS/Characterization Manager.

12.1.4 FSS/Characterization Supervisors FSS/Characterization Supervisors are responsible for assisting in the control and implementation of Survey Design Packages as received from the FSS/Characterization Engineers, implementation of turnover surveys, final status surveys, survey area preparation (such as gridding and accessibility needs), implementing access controls for FSS survey areas, coordination and scheduling of FSS/Characterization Technicians to support the FSS schedule and ensuring all necessary instrumentation and other equipment is available to support survey activities.

FSS/Characterization Supervisors report to the FSS/Characterization Manager.

12.1.5 Radiological Laboratory Manager The Radiological Laboratory Manager is responsible for radiological sample analyses performed in support of FSS. These analyses include, but are not limited to, volumetric soil samples and loose surface contamination activity media. The Radiological Laboratory Manager is responsible for the operation of laboratory instrumentation in accordance with approved procedures and manufacturers' recommendations, ensuring instrument QC and MDC requirements are met which support FSS criteria. The Radiological Laboratory Manager will report to the NASA Project RSO and consult with the FSS/Characterization Manager when providing direction and support for the FSS.

12.1.6 FSS/Characterization Technicians The FSS/Characterization Technicians are responsible for performance and documentation of FSS surveys and sampling in accordance with the requirements provided in the FSS implementing procedures. Technicians are responsible for performing work according to the survey package instructions and identifying any discrepancies with performance of the survey package. Through compliance with the FSS implementing procedures, Technicians shall implement the requirements contained in this FSS Plan to ensure appropriate quality is used in the collection of data for FSS decision-making. FSS/Characterization Technicians report to the FSS/Characterization Supervisor.

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Plan Revision 0 Facility Plum Brook Reactor Facility Plum FinalStatus Survey FinalStatus Survey Plan Re~vision 0 12.2 Training Training is conducted to achieve initial proficiency and to maintain that proficiency throughout the FSS process. The training ensures that personnel have sufficient knowledge to perform work activities in accordance with the requirements of this FSSP. Specific details of the FSS training program will be included in a PBRF procedure. At a minimum, personnel assigned to acquire FSS survey data will be trained on the following:

• Initial set-up, pre and post-use performance checks, and operation of the data-logger instrument and associated detectors

" Performance of static and scan measurements

• Performance of volumetric material sampling, including sample identification and chain-of-custody

• Area isolation and control

• Sample processing and analysis

• Survey documentation 12.3 Written Procedures The FSS of the PBRF will be conducted in accordance with written, approved procedures to ensure quality. Approved procedures will describe the methods and techniques used to perform the FSS. Procedures will be developed, implemented and controlled in accordance with a written PBRF procedure.

12.4 Access Control of Surveyed Areas and Systems Prior to performing the FSS, the survey unit or area is isolated and controlled to prevent changes in radiological conditions. Routine access, material storage, and worker and material transit through the area are no longer permitted without proper controls. One or more of the following administrative and physical controls will be established to minimize the possibility of introducing radioactive material from ongoing decommissioning activities in adjacent or nearby areas.

• Personnel training

• Installation of barriers to control access

" Installation of postings with access/egress requirements

• Locking or otherwise securing entrances to the area 12-3

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 0 Installation of tamper-evident seals or labels Isolation and control measures are implemented through approved PBRF procedures and remain in place through the FSS data collection process until license termination.

12.5 Chain-of-Custody Responsibility for custody of samples from the point of collection through the determination of the final survey results is established by implementing procedures. FSS sample identification and chain-of-custody will ensure that the validity of material samples remains intact.

Samples will be accompanied by a chain-of-custody (CoC) form. Sample identification numbers will be listed on the CoC form. When transferring possession of samples, the individuals relinquishing and receiving will sign, date, and note the time on the CoC form. The CoC form documents transfer of custody of samples from the sampler to another person, to a laboratory, or to/from a secure storage area. Secure storage will be provided for archived samples.

12.6 Instrumentation Selection, Calibration and Operation Proper selection and use of instrumentation will ensure that sensitivities are sufficient to detect radioactivity at the minimum detection requirements specified by the survey design which will assure the validity of the survey data. Instrument calibration will be performed with NIST traceable sources using approved procedures. Issuance, control and operation of the survey instruments will be conducted in accordance with approved implementing procedures.

12.7 Quality Control Surveys and Samples QC replicate field measurements and replicate sample analyses will be performed to assess precision. If a replicate result falls outside the acceptance criteria, an investigation is performed. The investigation may include verification that the data set is correct, the relevant instruments were operating properly, the survey/sample points were properly identified and located, instructions and procedures were followed, and sample chain-of-custody remained intact. When deemed appropriate, additional measurements are taken. At the conclusion of the investigation, a determination is made regarding the usability of the survey or sample data. The investigation and subsequent corrective actions are documented in accordance with PBRF procedures.

12.7.1 Replicate Field Measurements Replicate field measurements will be used to monitor survey precision in the field. A minimum 5% of survey measurements will be selected for 12-4

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 performance of replicate static and scan surveys. Acceptance criteria for scan measurements are both the QC measurement and initial FSS measurement must reach the same conclusion (i.e., both measurements are either less than or greater than the investigation level). Acceptance criterion for static measurements is both measurements must reach the same conclusion and the relative percent difference (RPD) must be within 20%. RPD is calculated as follows:

RPD - _(D- D,)I x100 (D,+ D,)/ 2 Where: D1 = 1st data result D2 = 2nd data result 12.7.2 Replicate Sample Analyses Replicate sample analyses will be used to monitor sample precision. A minimum of one out of every twenty (5%) FSS samples collected will be reanalyzed or homogenized, split and submitted for independent analyses.

Similar guidance contained in NRC Inspection Manual 84750 (IP 84750) will be used for evaluation of replicate sample analyses. This evaluation is performed as follows:

1. Determine the resolution for each known nuclide concentration by dividing the initial activity by its corresponding 1a uncertainty.

2. Determine the ratio of each nuclide concentration by dividing the duplicate sample result by the initial sample result.

3. The results are acceptable if the agreement ratio falls within the values given in Table 12-1 for the corresponding resolution.

12-5

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Table 12-1 NRC Criteria for Accepting Sample Measurements Resolution Acceptable Ratio

<4 0.4-2.5 4-7 0.5-2.0 8-15 0.6-1.66 16-50 0.75-1.33 51-200 0.80-1.25

>200 0.85-1.18 12.7.3 Control of Vendor-Supplied Services Vendor-supplied services, such as instrument calibration and laboratory sample analysis, will be procured from appropriate vendors in accordance with approved quality and procurement procedures.

12.7.4 Database Control Software used for data reduction, storage or evaluation will be fully documented and certified. The software will be tested prior to use by an appropriate test data set. Programs developed to assist in calculating FSS data (i.e., Excel spreadsheets) shall also be tested to verify they are correct.

12.7.5 Assessment and Oversight 12.7.5.1 Assessments FSS assessments will be conducted in accordance with approved procedures. The findings will be tracked and trended in accordance with these procedures.

12.7.5.2 Corrective Action Process The corrective action process will be applied to all aspects of the FSS. FSS deficiencies will be fully investigated and documented in accordance with the applicable corrective action procedure.

12.7.6 Data Validation Survey data will be reviewed by FSS/Characterization management for completeness, procedural compliance, and the presence of outliers.

12-6

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Comparisons to investigation levels will be made and measurements exceeding the investigation levels will be evaluated. Procedurally verified data will be subjected to the Sign test, the Wilcoxon Rank Sum (WRS) test, Sign Unity or WRS Unity test as appropriate.

12.7.7 NRC Confirmatory Measurements PBRF anticipates that both the NRC and OEPA may choose to conduct confirmatory measurements in accordance with applicable laws and regulations. The NRC may perform confirmatory measurements to determine if FSS and associated documentation demonstrate that the facility and site are suitable for release in accordance with the criteria for decommissioning in 10 CFR Part 20, subpart E. Timely and frequent communications with these agencies will ensure that they are afforded sufficient opportunity for these confirmatory measurements prior to PBRF implementing any irreversible decommissioning actions that have an impact on FSS (e.g. backfilling open excavations, etc.).

12-7

Plum Brook Reactor Facility Final Status Survey Plan Revision 0

13.0 REFERENCES

Appendix A Technical Specifications for the License No. TR-3, National Aeronautics and Space Administration Plum Brook Station, Sandusky, Ohio, Docket No. 50-30, 1998 NUREG-1575, "Multi-Agency Radiation Survey and Site Investigation Manual" (MARSSIM), Revision 1 (June 2001)

Title 10 Code of Federal Regulations, Part 20.1402, "Radiological Criteria for Unrestricted Use" Title 10 Code of Federal Regulations, Part 20, Subpart E, "Radiological Criteria for License Termination" NUREG-1727, "NMSS Decommissioning Standard Review Plan," September 15, 2000 NUREG- 1757, "Consolidated NMSS Decommissioning Guidance", September 2003 ANL/EAD/TM-89 "Probabilistic dose analysis using parameter distributions developed for RESRAD and RESRAD-BUILD codes", Argonne National Laboratory, 2000 ANL/EAD/TM-98 "Development of probabilistic RESRAD 6.0 and RESRAD-BUILD 3.0 computer codes", Argonne National Laboratory, 2000 "Decommissioning Plan for the Plum Brook Reactor", Revision 2, October 2001 Title 10 Code of Federal Regulations, Part 50.82, "Termination of License" Draft Regulatory Guide DG-4006, "Demonstrating Compliance with the Radiological Criteria for License Termination" NUREG-1505, "A Nonparametric Statistical Methodology for the Design and Analysis of Final Status Decommissioning Surveys," Rev. 1, June 1998 draft Tetra Tech, Inc., "Final Environmental Baseline Survey Report for the Plum Brook Reactor Facility Decommissioning Project", February 2001 PBRF-CS-016, "Material Background Determination" ISO 7503-1, "International Standard, Evaluation of Surface Contamination" MW-PL-02-008, "Team Quality Control Plan" "Plans of Buildings and Structures, Lewis Research Center, Plum Brook Station, Sandusky, OH", June 1974 13-1

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 EPA/SW-846, Test Methods for Evaluating Solid Waste, Volume IA: Laboratory Manual Physical/Chemical Methods, 1986 updated 1992 United States Nuclear Regulatory Commission Inspection Manual, Inspection Procedure 84750 13-2

Final Status Survey Plan for the Plum Brook Reactor Facility Attachment A Radionuclide Distribution Basis for DCGL Determination &

Final Status Survey of the Plum Brook Reactor Facility (PBRF)

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 1.0 Purpose This attachment provides evaluations of the Plum Brook Reactor Facility (PBRF) radionuclide distribution used to determine the site structure and soil DCGL values.

Radionuclides determined to be insignificant contributors per the guidance described in NUREG-1757 (Reference 2.6) were eliminated from further consideration. Embedded piping radionuclide distribution data is provided in Attachment C of this FSSP.

2.0 References 2.1 Plum Brook Reactor Facility Decommissioning Plan 2.2 NUREG-1575, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) 2.3 NUREG/CR-3474, "Long-Lived Activation Products in Reactor Materials" 2.4 NUREG/CR-0130, "Technology, Safety and Cost of Decommissioning" 2.5 NUREG/CR-4289, "Residual Radionuclide Contamination Within and Around Commercial Nuclear Power Plants" 2.6 NUREG-1757, Vol. 2, "Characterization, Survey, and Determination of Radiological Criteria" 2.7 "An Evaluation of the Plum Brook Reactor Facility and Documentation of Existing Conditions," Teledyne Isotopes, December, 1987 3.0 Assumptions and General Information 3.1 Nuclides positively identified in a single sample were assumed to be present at their stated MDA values in all other samples in their applicable populations where the nuclides were not detected.

3.2 RESRAD and RESRAD-BUILD input values used to evaluate dose contributions from specific radionuclides employ the building reuse, subsurface structure and surface soil parameters and scenarios used for site-specific DCGL development are provided in PBRF Technical Basis Documents and are available for review, as needed.

4.0 Discussion The evaluation provided in this attachment was performed to identify the suite of radionuclides that could potentially be present in site structures and soils following completion of decommissioning activities and structure demolition. 10 CFR Part 61 waste stream characterization analyses as well as the results of the isotopic analysis of concrete core samples collected as part of the characterization survey were used to estimate radionuclide distributions.

A- 1

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 A variety of concrete structures containing residual contamination may remain after decommissioning including the walls and floors of the basements of major buildings as well as concrete demolition debris that may be used as clean fill. At PBRF, the two major sources for the radioactive contamination of the concrete were the reactor coolant water, which contained both fission and activation products, and the irradiation of experiments. The presence of low levels of fission products in some of the sample results suggests that a small clad failure or a recycling of treated water from the Hot Laboratory may have occurred.

In order to assess the possibility that more than one radionuclide distribution could apply to the concrete structures and post demolition concrete debris that will undergo FSS, both the operational history and uses of the different structures were evaluated.

5.0 Historical Overview The PBRF was used to perform nuclear irradiation testing of fueled and unfueled experiments for space program applications. Construction of the PBRF began in 1956.

Preoperational testing of the reactor was performed during 1961 and 1962 and full power operations began in April 1963. The 60 MW reactor was operated by NASA on an essentially uninterrupted basis for almost 10 years until January 1973 when it was shut down after accumulating 98,000 Mega Watt Days (MWD) of operation.

The reactor was defueled from January to July 1973. During that time, the reactor fuel element assemblies (all special nuclear material, source material, and radioactive waste generated at that time) were removed from the PBRF and preliminary decontamination was performed. The fuel assemblies were transferred and reprocessed offsite and the radioactive wastes were disposed of offsite at licensed commercial facilities. The PBRF systems and support facilities not required for safe storage were maintained (mothballed) for possible future operations. During 1997 and 1998, NASA management decided to decontaminate and decommission the PBRF to allow termination of the NRC licenses and release the PBRF for unrestricted use.

The PBRF consists of six major buildings, several subsurface "tunnels", three water holding basins and an effluent release "ditch". The major structures include the Containment Building, the Reactor Building, the Hot Laboratory, the Reactor Office and Laboratory Building, the Waste Handling Building, the Primary Pump House and the Fan House. Subsurface structures include the Hot Pipe Tunnel and the Cold Pipe Tunnel.

The holding basins include the Hot Retention Basin, the Cold Retention Basin and the Emergency Retention Basin.

Reactor fuel was constructed of uranium/aluminum alloy fuel elements clad with aluminum alloy. The reactor fuel material was uranium enriched to about 93% in the U-235 isotope in an aluminum alloy of not more than 25% uranium by weight. The maximum core loading did not exceed 6 kg of U-235. Beryllium reflector pieces surrounded the fuel along with cadmium/beryllium regulating and shim rods. The core was moderated and cooled by de-ionized water which was pressurized by the elevation of water in the head tank and the head of the primary system pumps.

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Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Most primary system piping and components are located in the Containment Building, the Reactor Building, the Primary Pump House and the Fan House. Primary systems were also present in portions of the Hot Pipe Tunnel. The primary cooling water system was subdivided into four groups, the main ioop, the by-pass clean-up loop, the instrument and test hole cooling ioop and the shutdown loop. The main loop was a closed loop, 26,000 gallon system that was routed from the reactor through 24 in. supply and return lines to the Primary Pump House where coolant water was passed through two primary heat exchangers, three primary pumps, a strainer and a flow meter and returned to the inlet supply line.

During reactor operation, the reactor tank was essentially a closed system. Experiments were inserted by means of two horizontal through tubes, six horizontal beam tubes, and two vertical experiment tubes, all of which are of aluminum alloy construction.

However, direct interface with the canal system did occur, most notably in the hydraulic "rabbit" tubes, which transferred experiment materials in and out of the reactor tank using the difference in hydraulic pressure between the reactor coolant and the canals. During shutdown, materials and fuel elements were routinely transferred between the reactor tank and the canals.

The reactor tank and concrete biological shield are surrounded by four quadrants, three (A, C, and D) of which could be flooded with water for additional biological shielding.

Quadrant B was a dry area. A system of canals was used to transfer materials or fuel assemblies to and from the reactor tank, the fuel storage area, and the adjacent Hot Laboratory. Quadrant D contained the underwater beam room. In the Hot Laboratory, materials were remotely transferred from the canals to either the hot cells or the Hot Dry Storage Area. It was here that irradiated materials were handled and tested.

The hot drain system consists of the drain collection systems for all wastewater drainage that originated directly or indirectly from a radioactively contaminated area. The system is made up of 12 collection sumps (located in the Fan House, Waste Handling Building, Reactor Office and Laboratory Building, Primary Pump House, Hot Laboratory, Reactor Building, and inside the containment vessel) along with associated pumps and valves.

Pumps were used to move liquids that had collected in the sumps to the Hot Retention Area.

The Mock-Up Reactor (MUR) was a 100OKW swimming pool type reactor located in Canal H and setup to simulate the main Plum Brook Reactor. The MUR used the same uranium enriched aluminum alloy fuel assemblies, with the exception of uranium loadings, as the larger reactor core. As such, the nuclide distribution resultant from the operation of the MUR should be essentially the same as the distribution resultant from the operation of the larger reactor.

The secondary coolant system consisted of a single loop system that took waste heat from a pair of primary to secondary heat exchangers, carried it to a cooling tower for disposal, and then returned the water to the heat exchangers located within the Primary Pump House. The secondary system piping leaves the Reactor Building (RB) and proceeds A- 3

Plum Rrnnk Reactnr Facilitv Final StatusSurvpv Plan Rev~isin 0 down the length of the Cold Pipe Tunnel that connects the RB to the Service Equipment Building (SEB) and to the cooling tower.

The Hot Retention Area, located south of the Fan House, contains eight 60,000 gal and four 7500 gal steel underground storage tanks. The larger tanks, located in an underground concrete room, received all of the radioactively contaminated water from the hot drain system. The four smaller tanks were used as holding tanks. The contaminated water was treated and the water in the holding tanks was monitored and then discharged to the Cold Retention Basins, the quadrant and canal recirculating system, or to the Water Effluent Monitoring Station.

The Cold Retention Basins are two 500,000 gal below grade storage basins in the shape of inverted pyramids. The basins were used to store low-level radioactive water primarily from the quadrants and canals in the Reactor Building. During facility operations the basins were known to leak, so a plastic liner was installed. At the time of shutdown, the Cold Retention Basins were opened to permit groundwater to enter the structures to equalize the water levels in the groundwater and basins and prevent the basins from floating in the event of a high groundwater table. Silt and sludge accumulated on the side walls and bottoms of the basins.

5.1 Assessment of Historical and Operational Factors The following conclusions were reached following an assessment of the lay-out, structures, systems and processes that were used during the operation of the PBRF. Reactor coolant systems containing reactor originated fission and corrosion products are prevalent in the Containment, the Reactor Building, the Hot Laboratory, the Primary Pump House, the Waste Handling Building, the Fan House and the Hot Pipe Tunnel. Other environmental areas were also directly impacted by exposure to either treated and/or untreated primary coolant, including the Hot Retention Area, the Cold Retention Basins, the Emergency Retention Basin, the Water Effluent Monitoring Station, the Pentolite Ditch and Drainage System. Subsequently, it was anticipated that all the areas listed above should exhibit approximately the same radionuclide mixture.

One building, the Reactor Office and Laboratory Building (ROLB) did not contain any major systems that carried primary coolant. It is believed that the source of contamination discovered in the ROLB was from the importation and analysis of reactor coolant and reactor material samples. Radiological operational surveys taken in the fuel vault and in several laboratories located in the ROLB showed significant alpha contamination that was later identified as U-234 and U-235. Subsequent radiological characterization surveys did not identify U-234 and U-235 in any other of the impacted structures at the concentrations observed in the ROLB. As such, the ROLB was evaluated as an area that could exhibit a unique mixture.

In the Hot Laboratory, a wide variety of irradiated materials were unpackaged, directly handled and tested in this area. Subsequently, it is anticipated that the A- 4

Plum Brook Reactor Facility, Final Status Survey Plan Revision 0 radionuclide distribution in the Hot Laboratory could also be significantly different from the balance of plant mixture.

6.0 Sample Collection and Analysis 6.1 Smear Samples of Structural Surfaces As part of a previous investigation performed to substantiate the nuclide distribution that would be applicable to waste disposition, twenty-two (22) smear samples were acquired and subjected to 10 CFR Part 61 analyses. The samples were as follows;

• 7 smears taken on loose equipment and materials in Hot Cells numbers 1 through 7,

• 7 smears taken on structural surfaces in Hot Cells numbers 1 through 7,

• 5 smears taken from within the Containment structure, including Quads A, Quad C, Canal E, the Lilly Pad and general area,

• 2 smears taken from the Reactor Office and Laboratory Building, and

• 1 smear taken from the Reactor Building.

In addition, alpha contamination was positively identified by direct measurement and on smear samples collected in the ROLB fuel vault and in several of the laboratories during the radiological evaluation of loose equipment in these areas for disposition and disposal. Additional smear samples were collected specifically at locations in the ROLB where positive alpha measurements were obtained. These smears were combined into composite samples and analyzed for isotopic content. To support the assessment of the nuclide mixture in the ROLB, the results from these samples were added to the Part 61 smear sample population described above. The results of the analyses of these smear samples are presented in Addendum 1 of this attachment.

A-5

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Figure A-i Part 61 Smear Populations Sample Locations NAiMA UNN IIIROANH OUIB MUN BROOK SATON SANSUK*Y, OHiO (D Quadrant A

() Quadrant C (Canal E Ully Pad (g General Containment Area

() Reactor Building Reactor Office

& Laboratory Building

( Hot Cells 1-7 A.-6

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 6.2 Concrete Core Sampling In addition to the smears, concrete core bore samples were collected at various locations throughout the PBRF structures. A plan for concrete sample collection was prepared to ensure that core bore samples were collected at representative locations from each of the primary structures designated to remain and be subjected to FSS. Core samples were collected at biased locations in the areas known to be the most exposed to radioactive contamination during plant operation. Areas in lower levels of buildings, areas housing waste processing equipment, and areas near sumps and floor trenches were chosen.

The biased location of each core bore was selected by performing a beta scan of the floor area of the targeted structure. The location with the highest total surface contamination reading was identified and assessed for the presence of loose surface contamination. If loose surface contamination was detected, the location was decontaminated. If there was appreciable fixed contamination left following the decontamination, the location was selected for obtaining a core bore sample.

By obtaining the highest activity samples from each key structure, the likelihood of detecting nuclides with low activity levels was improved and the relative fractions of the MDA values were minimized. In total, sixteen core bore samples were obtained. One core sample broke during extraction and was unusable leaving 15 samples for analysis. Of the 15 samples, thirteen were used as sent for isotopic analysis. The other two core samples were saved for possible site-specific KD analysis.

Under Characterization Survey Package Number C9000 10111, core bore samples were acquired at the following locations:

• In the Reactor Building on the 0' elevation, southern floor, a core bore sample was acquired on the floor adjacent to a removable steel hatch cover. This sample broke during extraction and was subsequently unusable for further analysis.

• In the Reactor Building on the -25' elevation in the southwest quadrant, a core bore sample was acquired on the floor adjacent to the sump in the Area #22 Pump Room.

• In the Reactor Building on the -15' elevation in the east floor area, one core bore sample was acquired on the floor adjacent to the concrete shielding for the primary water piping systems.

• In the Primary Containment on the -25' elevation at the bottom of Canal "E",

a core bore sample was acquired on the floor along the southern wall adjacent to the south canal entrance.

A-7

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" In the Primary Containment on the -25' elevation in the west area, a core bore sample was acquired on the floor adjacent to the inner wall across from the west stairwell.

" In the Waste Handling Building on the -13' elevation, a core bore sample was acquired on the floor adjacent to the north building sump.

" In the Hot Laboratory on the 0' elevation, four core bore samples were acquired, one on the floor in front of Room #2, one on the floor in front of Room #6, one in the middle of the floor adjacent to Room #5 and one at the entrance to Room #16.

" In the Hot Pipe Tunnel on the -12' elevation, two core bore samples were acquired, one in the middle of the tunnel section to the east of the corner and one on the side by the corner. Two additional core samples were acquired and placed in storage.

" In the Fan House on the -12' foot elevation, one core bore sample was acquired on the floor adjacent to the air plenum and venture located against the north wall.

" In the Primary Pump House on the 0' elevation, three core bore samples were acquired, one on the floors of Room numbers 1, 2 and 4 respectively. These samples were not included as part of the sample population due to QA concerns that could not be resolved.

• In the Reactor Office and Laboratory Building (ROLB), one core sample was acquired on the floor of the New Fuel Vault.

Structures that could potentially contain activated concrete such as the bio-shield were not sampled at the time of this study because current decommissioning plans call for the removal of activated portions of the concrete bioshield and disposition of the activated concrete as radioactive waste.

Each of the core samples was sliced and surveyed. Two 1/2 inch thick "pucks" were sliced from the top of each core. Direct alpha and beta measurements were obtained on both the tops and bottoms of each puck. A preliminary radionuclide analysis was performed on each puck using the PBRF on-site gamma spectroscopy system. This analysis was performed not to specifically assess the nuclide distribution, but rather to qualitatively evaluate the depth of contaminant migration into the concrete at each of these locations. Each 1/2 puck was analyzed twice, exposing the detector to both sides of each puck. The results of these analyses are presented in Addendum 2 of this attachment.

The data presented suggests that with the exception of the Hot Laboratory, the majority of the reactor produced radionuclides were confined to the 1 st 1/2 inch of A-8

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 concrete surface. In the Hot Lab, the contaminant migration observed went deeper, at some locations to a depth of one inch.

After the preliminary radionuclide analysis was complete, the samples were sent to an off-site laboratory for a full isotopic analysis. The top 1 inch concrete core was pulverized and analyzed for full isotopic content. Samples were prepared by transfer of the sample to a standard geometry or by removing a representative aliquot from the sample and processing the sample in accordance with the analytical technology selected. Gamma emitting isotopes were analyzed using a high purity Germanium (HPGe) gamma detector. Analysis for low energy gamma emitters used a planar, high purity germanium, low energy response gamma ray detector. Analysis for beta emitting isotopes employed beta liquid scintillation and alpha emitting isotopes were analyzed using alpha spectroscopy.

These results are presented in Addendum 4 of this attachment.

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Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Figure A-2 Concrete Core Population Sample Locations - Hot Laboratory KAM OLUNN NEUKARON CEITR PLM SP= rTATION MANDUJISY, OHIO MWT LA3OATORY MUrJNMe Mk. 1112 hayw. 4.0r A-1O

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Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Figure A-4 Concrete Core Population Sample Locations - Reactor Building P

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Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Figure A-5 Concrete Core Population Sample Locations - Fan House AJt LM MMAG OUENrT PU O STATMION AuMUwmY. 0410 P"N House MMUliM 11MIII=

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Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Figure A-6 Concrete Core Population Sample Locations - Waste Handling Building IPAILN VNO A PLUM IMMO STAnI T

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Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Figure A-7 Concrete Core Population Sample Locations - ROLB NAA MUN IUSIISAMON calNr PLUM SNOOK STATION wMANUNC, mONI OFFICE ND LADONATOMY MINLINNS UNILDING Me. 1141 Msv. 0 46,1" A-15

Plum Brook Reactor Facilitv FinalStatus Survey Plan Revision 0 6.3 Soil Sampling Surface soil samples were obtained to assess the radionuclide distribution in soils surrounding the facility. A sampling plan was developed and documented in characterization survey packages A2400 303 C2 and A2100 101 C2. Gamma scan surveys were performed using sodium iodide (Nal) detectors to ascertain the highest activity locations at the PBRF. Survey areas exhibiting scan results greater than twice the observed background were selected. At the area of highest observed scan activity, a one-liter soil sample was collected. Soil samples were sent to an off-site laboratory for processing and full isotopic analysis. Samples were analyzed for gamma emitting isotopes using a high purity germanium (HPGe) gamma detector. Analysis for low energy gamma emitters used a planar, high purity germanium, low energy response gamma ray detector. Analysis for beta emitting isotopes employed beta liquid scintillation and alpha emitting isotopes were analyzed using alpha spectroscopy.

In total, eight soil samples were obtained: four from the Emergency Retention Basin and four from a suspected spill area south of the Waste Handling Building.

Other open land areas on site also indicated elevated scan activity; however the eight locations selected were biased in order to acquire samples with relatively high isotopic concentrations in order to minimize the contribution of MDA values to the resultant nuclide distribution. Analytical results for the surface soil samples are presented in Addendum 3 of this attachment.

A-16

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Figure A-8 Surface Soil Population Sample Locations - WHB Spill Location NAMJ -lR -*

MLUM MOD= WFAON aaireina, OHIO I.

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SP 43 Y )f X SP #4 wMIO I

X X Denotes Survey Unit boundary N M1O - MIO Monument Marker a-r-u- Bod MwP 6- £2o 1001=1C4 fam. a awvev Pecsle 0 - A2100 10102 A-18

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 7.0 Evaluation of Sample Results and Elimination of Insignificant Radionuclides 7.1 Minimum Detectable Activity (MDA)

In all three sample types (smear samples, core samples and soil samples), before the nuclide distribution could be evaluated, the analysis results reported as less than MDA were considered. It was expected that several of the nuclides would be reported as less than MDA since these nuclides have a low probability of being present. Two approaches were considered for evaluating MDA results: 1) include the MDA values as representing actual concentrations, and 2) remove the less than MDA nuclides from the mixture. Removing the nuclides was considered more appropriate and representative of actual site conditions because the non-detected nuclides are believed either to not be present or to be present at negligible concentrations well below the MDA value. A nuclide was included in the "discarded" category if it was not detected at concentrations above MDA in any individual sample in the respective smear, core and/or soil sample population.

If a nuclide was detected above MDA in one or more samples in a given population, then the nuclide was retained and included in the mixture. For those radionuclides that were reported as positive in only a portion of the sample population, the MDA values were combined with the positive results to determine the mixture fraction. The MDA values were used in this case because it was conservatively assumed that if a radionuclide was positive in an individual sample then it could also be present in the remaining samples of the population. Using the MDA also has the effect of reducing the probability that a single positive radionuclide result in a given sample population will skew the overall percentage relationship between the isotopes when those percentages are normalized.

The remaining nuclides were then evaluated for the presence of naturally occurring isotopes. Naturally occurring isotopes were ignored in subsequent calculations.

7.2 Mean Distribution Evaluation Following the analysis of all nuclides identified at activities greater than their respective MDAs, an assessment was performed to ascertain the activity of radionuclides that could be attributed to background. K-40, Pb-212, Pb-214, Bi-214, Th-228, Th-230, Th-232, and Ra-226 were detected at concentrations commensurate with levels normally found in background. Subsequently, these isotopes were removed from consideration in all the sample populations.

The radionuclide distribution percentage for each remaining nuclide was then calculated by dividing the concentration for each nuclide by the sum of all remaining radionuclide concentrations in the sample population expressing the abundance of the specific nuclide compared against the total sample activity. The mean nuclide distribution was then calculated by taking the average of the individual core nuclide fractions in each sample population.

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Plum Brook Reactor Facility Final Status Survey Plan Revision 0 The smear sample mean nuclide distribution in Table A-I below contains all remaining radionuclides that were above MDA in one or more smear samples.

Table A-1 Smear Radionuclide Distribution Radionuclide Hot Laboratory Balance of Plant ROLB Ag-108m ND 0.06% ND Am-241 0.19% 0.13% 0.02%

C-14 0.20% 0.58% 0.26%

Co-57 0.03% ND ND Co-60 2.38% 5.22% 0.98%

Cm-242 ND ND 0.01%

Cm243/244 0.13% 0.02% 0.01%

Cm-245/246 ND ND ND Cs-134 0.03% ND ND Cs-137 43.69% 7.46% 16.62%

Eu- 152 ND 0.13% ND Eu- 154 0.08% 0.15% ND Eu-155 ND ND 0.12%

Fe-55 2.75% 1.98% ND H-3 8.29% 66.53% 38.87%

1-129 0.02% 0.06% 2.66%

Na-22 0.03% ND ND Nb-94 0.12% 0.03% 0.05%

Ni-59 0.33% 0.45% 1.68%

Ni-63 13.39% 13.66% 0.23%

Np-237 ND ND 0.05%

Pu-238 0.11% 0.04% ND Pu-239/240 0.13% 0.02% 0.02%

Pu-241 1.19% 0.32% 0.45%

Pu-242 0.06% ND ND Sb- 125 ND ND 0.23%

Sr-89 0.81% 0.03% ND Sr-90 25.43% 3.01% 4.03%

Tc-99 0.58% 0.12% 0.30%

U-233/234 0.03% 0.01% 31.87%

U-235/236 ND ND 1.12%

U-238 ND ND 0.42%

ND - Radionuclide Not Detected A-20

Plum Rrnnk Rpartor Fnrilitv Final Statu,ýNnrvov Phin Rovivinn 0 The nuclide distribution for the Balance of Plant (BOP) smear population indicates a nuclide distribution for H-3 of 66.53%. It is unlikely that the actual contribution of tritium to the nuclide distribution is of this magnitude. The H-3 contribution is skewed by the inherent inaccuracy of the smear sample approach for material sampling as a means to quantify H-3 activity. The core sample data analysis provides a more realistic indication of H-3 concentrations as the core bore material sampling approach results in a volumetric sample medium more appropriate for the quantification of H-3. However, as the presence of H-3 has very little effect on the calculation of the adjusted gross DCGL, the distribution of H-3 in the smear populations was not adjusted.

The concrete core samples are believed to be more representative of the mixture that will remain after license termination than the smear samples because the majority of loose contamination will be removed during remediation. The majority of the potentially contaminated surfaces that will remain following structural remediation will be concrete.

As previously stated, radionuclides that were not present in concentrations greater than their respective MDA values in any of the concrete core samples were removed from the mixture. These isotopes included Sb-125, Eu-152, Eu-154, Eu-155, Nb-95, 1-129, Np-237, Ni-59, Tc-99 and Cm-243/244. The core sample taken in the ROLB indicated no activity greater than background. Subsequently, a nuclide distribution based upon core sample analysis results can not be presented for the ROLB at this time. The concrete core sample mean nuclide distribution in Table A-2 below contains all remaining radionuclides that were above MDA in one or more core samples.

A-21

RavZ¢ion O Plum Brook Reacotr Facilitv Final ,Status~,urvev Plan RevAision 0l Table A-2 Concrete Core Radionuclide Distribution Radionuclide Hot Laboratory Balance of Plant ROLB Am-241 0.41% 0.29% ND C-14 1.97% ND ND Co-60 0.65% 1.23% ND Cm-245/246 0.07% 0.19% ND Cs-137 78.04% 34.79% ND Fe-55 ND 18.93% ND H-3 0.83% 8.46% ND Ni-63 3.09% 19.71% ND Pu-238 0.06% 0.07% ND Pu-239/240 0.59% 0.06% ND Pu-241 0.81% 2.49% ND Sr-90 13.23% 11.74% ND U-233/234 0.14% 0.98% ND U-235/236 0.01% 0.09% ND U-238 0.11% 0.97% ND ND - Radionuclide Not Detected In the surface soil samples, Th-228, Th-230, Th-232, Th-227, Ra-226, U-234, U-235 and U-238 were detected at concentrations commensurate with levels normally found in background (U-234 concentrations ranged from 0.793 pC/g to 1.876 pC/g, U-235 concentrations ranged from 0.051 pC/g to 0.197 pC/g and U-238 concentrations ranged from 0.850 pC/g to 1.861 pC/g). Subsequently, these isotopes were removed from consideration in the soil radionuclide distribution mixture. The soil nuclide distribution in Table A-3 contains all remaining radionuclides that were above MDA in one or more surface soil samples.

A-22

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Table A-3 Surface Soil Radionuclide Distribution Radionuclide Open Land Areas Am-241 0.15%

Am-243 0.16%

C-14 2.11%

Cm-245 0.22%

Co-60 1.68%

Cs-137 58.50%

Eu-155 0.76%

H-3 22.68%

1-129 0.53%

Nb-94 0.30%

Ni-63 6.96%

Pu-238 0.17%

Pu-239 0.16%

Sr-90 5.49%

U-236 0.12%

7.3 Application of the 10% Rule Based on data reviewed to date and considering the PBRF operational history, there appear to be three radionuclide mixtures for site structures and one distribution for soils. For site structures, the first applies to the Hot Laboratory, the second to the ROLB and the third to the remaining structures designated as Balance of Plant (BOP).

The final step in determining the radionuclide distribution for each of the mixtures involved the elimination of radionuclides that have insignificant dose consequences. NUREG-1757, Vol. 2, Section 3.3, states that nuclides with a combined dose of less than 10% of the 25 mremlyr unrestricted use criteria can be eliminated from further consideration. To determine which nuclides can be eliminated by the "10%" rule, a RESRAD or RESRAD-Build run was performed using the mean nuclide distribution derived for each sample population. The concentration entered for each radionuclide was the fraction listed in Tables A-i, A-2 and A-3, respectively. The RESRAD/RESRAD-Build runs used to perform the "10%" rule calculations are provided in site Technical Basis Documents and are available for review, as needed.

For the mean distribution derived from the smear samples, RESRAD-Build and RESRAD evaluations were performed for the Building Reuse and Subsurface Structure scenarios, respectively. Concrete Kd data were not available in the A-23

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 literature for three radionuclides with very low nuclide fractions; i.e. Na-22, Np-237, and Sb-125 at 0.03%, 0.00%, and 0.23%, respectively.

The RESRAD default Kd was used in the Subsurface Structure analysis for these radionuclides. Two radionuclides, Sr-89 and Cm-242, were reported as above MDA in one or more smear samples with mean fractions of 0.81% and 0.00%,

respectively. RESRAD and RESRAD-Build do not list these radionuclides.

Because of their very low fractions these nuclides were disregarded. In addition, Sr-89 is suspected to be a false positive because the half life is very short relative to the time since plant shutdown.

The radionuclides that, in aggregate, were less than 10% of the total dose for both of the scenarios were eliminated. The mixtures were readjusted to 100% based on the relative fractions of the radionuclides remaining after the insignificant radionuclides were removed.

The results of all RESRAD-Build and RESRAD runs, i.e. BOP, ROLB and Hot Lab mixtures in the Subsurface Structure and Building Reuse scenarios indicate that for the smear sample population, the aggregate dose from six radionuclides, i.e., Cs-137, Sr-90, Co-60, H-3, Eu-154 and 1-129 resulted in 94% or more of the 25 mrem/yr limit in all BOP cases, the aggregate dose from five radionuclides, i.e., Cs-137, Sr-90, Co-60, H-3, and Eu-154 resulted in 93% or more of the 25 mrem/yr limit in all Hot Lab cases and the aggregate dose from seven radionuclides, i.e., Cs-137, Sr-90, Co-60, H-3, 1-129, U-234 and U-235 resulted in 93% or more of the 25 mrem/yr limit in all ROLB cases.

For the core sample population, the aggregate dose from four radionuclides, i.e.,

Cs-137, Sr-90, Co-60 and H-3, resulted in 90% or more of the 25 mrem/yr limit in all BOP cases and the aggregate dose from three radionuclides, i.e., Cs-137, Sr-90 and Co-60 resulted in 92% or more of the 25 mrem/yr limit in all Hot Lab cases.

As previously stated, a nuclide distribution based upon core sample analysis results can not be presented for the ROLB at this time due to the fact that the only available core sample indicated only background activity.

The lowest total aggregate dose from the remaining radionuclides was 90% of the 25 mrem/yr criterion, which means that radionuclides potentially representing a dose of 2.5 mremlyr were eliminated. To ensure the 25 mrem/yr criterion is met, any structural survey unit where the mean of FSS results indicates that the dose may be greater than 22.5 mrem/yr dose (including dose from embedded pipe in the given survey unit, if applicable) shall be reviewed for compliance with the unrestricted use limit. The final normalized radionuclide distributions for structural surfaces are provided in Tables A-4 and A-5 below.

Additionally, the current decommissioning strategy for PBRF calls for the removal of activated portions of the concrete bioshield and disposition of the activated concrete as radioactive waste. Therefore, the activated concrete was not evaluated.

A-24

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Table A-4 Final Smear Radionuclide Distribution Radionuclide Hot Laboratory Balance of Plant ROLB Co-60 3.41% 6.72% 1.01%

Cs-137 53.11% 7.74% 17.29%

Eu-154 0.12% 0.17% ND H-3 10.84% 82.15% 39.71%

1-129 ND 0.08% 2.82%

Sr-90 32.52% 3.13% 4.17%

U-233/234 ND ND 33.82%

U-235/236 ND ND 1.19%

ND - Radionuclide Not Detected Table A-5 Final Concrete Core Radionuclide Distribution Radionuclide Hot Laboratory Balance of Plant Co-60 0.79% 7.84%

Cs-137 83.45% 41.45%

H-3 ND 35.35%

Sr-90 15.77% 15.36%

ND - Radionuclide Not Detected For surface soil samples, the doses from all radionuclides other than Cs-137, Co-60, and Sr-90 totaled 0.5 mrem/yr. Because this dose is 2% of the 25 mrem/yr limit, all radionuclides other than Cs-137, Co-60, and Sr-90 were eliminated from further consideration. To ensure the 25 mrem/yr criterion is met, any open land survey unit where the mean of FSS results indicates that the dose may be greater than 24.5 mremlyr shall be reviewed for compliance with the unrestricted use limit. The final normalized radionuclide distributions for soils are provided in Table A-6 below.

Table A-6 Final Soil Radionuclide Distribution Radionuclide Open Land Areas Co-60 2.56 %

Cs-137 89.08%

Sr-90 8.360/,

A-25

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 8.0 Conclusion Per NUREG-1757 (Reference 2.6), the Nuclear Regulatory Commission (NRC) staff considers radionuclides and exposure pathways that contribute no greater than 10% of the 25 mrem/yr dose criteria to be insignificant contributors. This 10% limit for insignificant contributors is an aggregate limitation only. That is, the sum of the dose contributions from all radionuclides and pathways considered insignificant will be no greater than 10%

of the dose criteria of 25 mrem/yr per 10 CFR Part 20, Subpart E.

The dose from the insignificant radionuclides will be accounted for in demonstrating compliance, but may be eliminated from further detailed evaluations. The lowest total aggregate dose from the remaining radionuclides was evaluated at 90% of the 25 mrem/yr criterion, which means that radionuclides potentially representing a dose of 2.5 mrem/yr were eliminated. To ensure the 25 mrem/yr criterion is met, any structural survey unit where the mean of FSS results indicates that the dose may be greater than 22.5 mrem/yr dose (including dose from embedded pipe in the given survey unit, if applicable) shall be reviewed for compliance with the unrestricted use limit.

For surface soil samples, the doses from all radionuclides other than Cs-137, Co-60, and Sr-90 totaled 0.5 mrem/yr. Because this dose is 2% of the 25 mrem/yr limit, all radionuclides other than Cs-137, Co-60, and Sr-90 were eliminated from further consideration. To ensure the 25 mrem/yr criterion is met, any open land survey unit where the mean of FSS results indicates that the dose may be greater than 24.5 mrem/yr will be reviewed for compliance with the unrestricted use limit.

Based on the evaluation of insignificant radionuclides as described in this attachment, soil and structural surfaces at the PBRF may contain one or more of the radionuclides listed in Table A-7. These radionuclides will be considered during the FSS design and sample analysis process.

Table A-7 PBRF Radionuclides of Concern Co-60 Cs-137 Eu-154 H-3 1-129 Sr-90 U-233/234 U-235/236 The BOP core population does not include samples from a number of BOP locations such as the primary pump house and quads. However, the cores collected are considered representative of all BOP areas because the predominant source of contamination in all areas is reactor coolant. Additional confirmatory samples and/or measurements will be A-26

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 performed in appropriate BOP areas to confirm the assumption that the cores collected are representative of all BOP areas. The final radionuclide distribution, gross activity DCGL values, and surrogate DCGL values will be determined and documented in each survey unit FSS design package.

9.0 Addendums Addendum 1 - Results of Isotopic Analysis of Smear Samples Addendum 2 - Preliminary Analysis of Concrete Core "Puck" Samples by the On-Site Laboratory Addendum 3 - Results of Isotopic Analysis of Concrete Core Samples by the Offsite Laboratory Addendum 4 - Results of Isotopic Analysis of Surface Soil Samples A-27

Final Status Survey Plan for the Plum Brook Reactor Facility Attachment A Radionuclide Distribution Basis for DCGL Determination &

Final Status Survey of the Plum Brook Reactor Facility (PBRF)

Addendum 1 Results of Isotopic Analysis of Smear Samples

Attachment A Page I of 4 Addendum I Results of Isotopic Analysis of Smear Samples HOT LABORATORY Honot CallEquipmente 1 Smear H C tHot Cell Equipment #3 Smear i5'pCl/flltsr) . . (pCl/ffltar) - o(pCl/flter)

Results MDA Used Distribution Results MDA Used Distribution Results MDA Used Distribution Am-241 7272$03 6.02+00" 7.27E+03 015% 3.00E+02 5.05E-01 3.00E+02 007% 1.35E+02 8.83E-01 1.35E+02 0.11%

C-14 9.205E202 1.37E+03 1.37E+03 0.03% 1.24E+02 6.12E+01 1.24E+02 0.03% ' 2.40E+02 6.21E+01 2.40E+02 0.20%

Co-57 0.00E+00 1.20E+02 1.20E+02 000% 0.00E+00 6.26E+01 6.26E+01 001% 0.00E+00 2.94E+01 2.94E+01 0.02%

Co-60 M 2.74E+05 1.24E+02 2.74E+05 5,73% 8.64E+03 2.25E+01 8.64E+03 1 ,94% 2.67E+03 1.27E+01 2.67E+03 2.26%

Cm-242 2.61E+00 7.82E+00 7.82E+00 0.00% 3.77E-01 7.22E-01 7.22E-01 0.00% 1.65E-01 2.47E-01 247E-01 0.00%

Cm-243/244 2.24E+02 2,25E+01 2.24E+02 0.00% 7.55E+00 7.32E-01 7.55E+00 0.00% 2.88E+00 5.50E-01 2.88E+00 0,00%

Cs-134 4.14E+02 1.71E+02 4.14E+02 0,01% 4.01E+01 6.92E+01 6.92E+01 0.02% 8.03E+00 3.01E+01 3.O1E+01 0.03%

Cs.137 8.07E+05 2.06E+02 0.07E+05 16089% 2.71E+05 6.98E+01 2,71E+05 6008/% 4.51E+04 3.22E+01 4.51E+04 38.23%

Eu-154 1.79E+03 3.00E+02 1.79E+03 0004% 0.00E+00 8.27E+01 8.27E+01 002% 1.942+02 7.49E+01 1.94E+02 0.16%

Fe-55 1.69E+05 7,5"E+01 1.69E+05 354% 3.44E+03 3.85E+03 3.85E+03 0086% 1.00E+03 4.09E+03 4.09E+03 3.47%

H-3 6.262+05 3.49E+02 6.26E+05 13 10% 4.69E+03 2.53E+02 4.69E+03 1.05% 1.73E+03 4.51E+02 1.73E+03 1.47%

1-129 -2.31E+00 2.32E+01 2.32E+01 0,00% 2.03E+00 2.14E+01 2.14E+01 0.00% 1.252-01 8.51E+00 6.51E+00 0.01%

Na-22 0.002+00 1.102+02 1.18E+02 0.00% 4.012+01 1.59E+02 1.59E+02 004% 0.00E+00 1.42E+01 1A2E+01 0,01%

Nb-94 4,99E+04 1.52E+02 4.99E+04 1.04% 1.00E+01 2.92E+01 2.92E+01 0.01% 1.18E+02 1.57E+01 1.18E+02 0.10%

NI-59 6.28E+03 2.90E+02 6.202+03 0.13% 1,86E+02 1.90E+02 1.98E+02 0.04% 2.11E+02 2.70E+02 2.70E+02 023%

NI-63 9.42E+05 1.80E+06 1.80E+06 37.67% 3.76E+04 1.80E+03 3.76E÷04 0.45% 1.56E+04 8.20E+02 1.58E+04 13.22=/.

Np-237 2.03E+00 2.65E-01 2,03E+00 0.00% 2.60E-01 2.60E-01 2.602-01 0.00% 2.58E-01 2.58E-01 2.58E-01 0,00%

Pu-238 30,256E+03 2.04E+01 3.56E+03 0074 2.17E+02 0,242+00 2.17E+02 0.05% 7.52E+01 , 5.55E+00 7.52E+01 000%

Pu-239/240 Hi' 3.65E+03 2.04E+01 3.05E+03 008% 3.11E+02 2.51E+00 3.11E+02 0.07% 1.79E+02 2.91E+00 1.79E+02 0.15%

Pu-241 3.102+04 2.372+02 3.16E+04 0.66% 2.39E+03 1.65E+02

• 2.39E+03 0.54% 0.072+02 1.83E202 8.07E+02 0.68%

Pu-242 2.56E+01 3.50E+01 3.59E+01 000% 5.07E+00 3.46E+00 5.07E+00 000% 4,24E+00 1.16E+00 4.24E+00 0.00%

Sr-89 -9.60E+04 2.20E+02 2.202+02 0'00% -2.16E+04 2.42E+02 , 2A2E+02 0.00% K/ -6.00E+03 2.70E+02 2.70E+02 0.23%

Sr-SO 8.27E+05 3.49E+02 0.27E+05 17.31% 1.15E+05 3.50E+02 1.15E+05 25.84% 4.63E+04 3.65E+02 4.63E+04 39.25%

Tc-49 1.68E+05 4.19E+02 1.68E+05 3.52% x -3.26E+00 6.12E+01 0.12E+01 0.01% 6.71E+01 4.55E+01 6.71E+01 0.06%,

U-233/234 6.69E+02 7.48E-01 6.69E+02 0.01% K-5 4.23E+01 7.00E-01 4.23E+01 0.01% 2.48E+01 3.01E-01 2.48E+01 0.02%

U-230/326 4.24E+01 7.50E-01 4.34E+01 0.00% 2.54E+00 2.75E-01 2.84E+00 0.00% 1.11E+00 3.02E-01 1.11E+00 000%

U-238 9.58E+00 9.36E-01 9.58E+00 0000% 4.57E+00 2.74E-01 4.57E+00 0.00% 8.02E-01 7.67E-01 0.02E-01 0.00%

4.702+00 100%004 4.492+05 100.00% 1.18E+05 100.00%.

4 01Hot Cell Equipment #4 Smear M-Hot Cell Equipment #5Smear Hot Cell Equipment #6 Smear 1pXCI/ller) . (pCI/Ollter) (pCI/fillter) . 0 Results MDA Used Distribution <' Results MDA Used Distribution Results . MDA Used Distribution Am-241 2.702+01 2.45E*O2. 7.78E+01 0.09% 1.03E+02 7,73E-01 1.03E+02 0.03% 1.05E+02 2.012-01 1.05E+02 0.37%

C-14 2.00E+01 3.37E+02 3.37E+02 1.11% 3.56E+00 3.59E+01 3.59E+01 0.01% 3.67E+01 3.89E+01 3.89E+01 0.14%

Co-57. 5.23E+00 1.13E+01 1.13E+01 0.04% Z. .33E+00 6.15E+01 6.15E+01 0.02% 0.00E+00 1.40E+01 1.40E+01 0.05% 0 Co-60 1.58E+03 1.23E+01 1.58E+03 520% 3.23E+02 7.08E+00 3.23E+02 0 10% 4.91E+02 7.50E+00 4.91E+02 1.74% K/

Cm-242 9 .67E-02 7.40E-01 7.40E-01 0.00% 1.912-01 2.06E-01 2.86E-01 0.00% 3.96E0-1 2.38E-01 3.96E-01 0.054 Cm-243/244 2.21E+00 7.83E-01 2.21E+00 0.01% 1,46E+00 9.96E-01 1.46E+00 0:00% 2.42E+00 2.02E-01 2.42E+00 0.01% 0 Cs-134 3.77E+00 1.47E+01 1A7E+01 0.05% 1.82E+01 6.52E+01 6.52E+01 0,02% 4.452E+00 1.542+01 1.54E+01 005%

Cs-137 3.99E+03 1.68E+01 3.99E+03 13.13% 2.85E+05 6.04E+01 2.85E+05 06.87% 1.16E+04 1.472+01 1.16E+04 41.10%

Eu-154 2.64E+01 3.99E+01 3.99E+01 0.13% 0.02E+00 3.04E+01 3.04E+01 0.01% ' 0.00E00 3.112+01 3.112+01 0114 FP-55 7.50E+02 2.90E+0t 7.50E+02 2.47% 5.17E+02 0.52E+02 8.52E+02 0 262 5.54E+02 7.98E+02 7.08E+02 2.83%

H-31.51+04 3.94+02 1.51.+04 4070% 7.612+01 2.70E+02 2.70E+02 000% 1.25E+02 2.63E+02 2.63E+02 0093%

1-129 1.642+00 1.83E+01 1.83E+01 0'06% -4.97E+00 2.33E+01 2.33E+01 0.01% -5.22E-01 6.17E+00 6.17E+00 0.02%

Na-22 9.55E+00 1.44E+01 1.44E+01 0.05% 1.33E+01 6.15E+00 1.33E+01 0500% /4 1.53E+01 0.23E+00 1.53E+01 0.05%

Nb-94 -1.25E+00 1.27E+01 1.27E+01 0.04% 2.91E+00 9.20E+00 9.20E+00 0.00% '4 3.64E+00 0.03E+01 9.03E+01 0,28%

NI-59 -4.30E+01 2.42E+02 242E+02 0.80% 1.62E+02 2.41E+02 2.41E+02 0.07% 1.17E+02 2.21E+02 2.21E+02 070%

NI-63 4.50E+03 8.73E+02 4,50E+03 14.01% 1.42E+03 3.67E+02 1.42E+03 043% 3.75E+03 4.69E+02 3.75E+03 1329%

Np-237 -1.57E-01 9.33E-01 8.33E-01 0.00% 4.30E-03 0.13E-01 8.13E-01 0.00% 3.62E-03 6.83E-01 6.83E-01 0.00%

Pu-238 1.86E+01 3.07E+00 1.00E+01 0.06% 5.51E+01 2.16E+00 5.51E+01 0.02% 5.64E+01 2.90E+00 5.64E+01 0.202 Pu-239/240 1.55E+01 2.55E+00 1.55E+01 0.054 1.04E+02 1.97E+00 1.04E+02 0.03% 4.55E+01 1.29E+00 4.55E+01 0.16%

Pu-241 1.92E+02 1.07E+02 1.92E+02 0.63% 7.390+02 2.09E+02 7.39E+02 0322 - 7.102+02 2.00E+02 7.10E+02 2.524 Pu-242 4.77E-01 2.55E+00 2.55E+00 0.01% 2.49+00 1.97E+00 2.49E+00 0.00% 3.26E-01 2.26E+00 2.262+00 0.01%

Sr-86 -2.52E+02 2.25E+02 2.850+02 0.94% -6.86E+03 2.53E+02 . 2.53E+02 0i00% -3.702+03 2.472+02 2.472+02 0.88%

Sr-90 3.18E+03 3.94E+02 3.18E+03 10.47% 3.84E+04 2.07E+02 3.84E+04 11.71% 9.70E+03 3.54E+02 9.70E+03 34:37%

To-99 i -1.45E+01 .4.05E+01 4.05E+01 0.13% 4.67E+01 1.00E+01 4.67E+01 0.01% 2.44E+01 2.44E+01 2.44E+01 0.09%

U-233/234 3.88E+00 8.24E-01 3.88E+00 0.01% 8.16E+00 1.42E+00 0.16E+00 0.00% 2.15E+00 8.95E-01 2.15E+00 0.01%

U-235/236 3.24E-01 8.26E-01 8.26E-01 0.00% 5.32E-01 3.19E-01 5.32E-01 0,00% 1 87E-01 2.81E-01 2.8115-01 0.00%

U-238 0.02-01 1.032+00 1.032+00 0004 % 2.12E-01 0.112-01 8.11E-01 0.00% 2.80E-01 2.80E-01 2.602-O1 0004 3.04E+04 100 004 3.28E+05 2.022+04 10000%-

-:4+HotCell Equipment #7 Smear .. Hot Cell #1 Surface Smear -i Hot Cell #2 Surface Smear (ppCilflter) M (pCI/fOlter) (pCl/flter)

Results MDA Used Distribution Results MDA Used Distribution Results MDA Used Distribution Am-241 2.94E+02 2.63E-01 2.94E+02 007% 1.102+03 1.89E-01 1.10E+03 0.05% 3.25E+03 6.96E+00 3.25E+03 0.86%

C-14 0.60E+02 1.42E+02 0.60E+02 0,19% 3.94E+02 8.37E+01 3.94E+02 0.02% 1.39E+02 6.93E+01 1.39E+02 0.04%

Co-57 K- 0.00E+00 4.41E+01 4A4E+01 0.01% 0.00E+00 1.14E+02 1.14E+02 000% 1.3+011 4.27E+0 4.27E+01 0.01%

Co-60 - .08E+03 2.03E+01 6.08E+03 1.35% 5.16E+04 5.16E+01 5.16E+04 2.19% 2.01E+04 3.13E+01 2.01E+04 5.31%

Cm-242 4.12E-01 3.09E-01 4.12E-01 o.00% 5 64E-01 2.11E-01 5.64E-01 000% 1.51E+00 2.322+01 2.32E+01 0.01%

Cm-243/244

• 1.93E+02 8.41E-01 1.93E+02 0504% 1 5.07E+01 8.46E-01 5.07E+01 0:00% 3.05E+01 2.53E+01 3.05E+01 0.01%

Cs-134 +. -3.15E+00 4.72E+01 4.72E+01 0.01% K" 9.78E+00 1.17E+02 1.17E+02 000% 1.41E+01 5.03E+01 5.63E+01 0.01%

C-137 1.09E+05 5.49E+01 1.09E+05 24.21% 1.202+02 0.032+05 24124 1.052+05 0.47E+01 60032+06 1.09E+05 28001%

Eu-154 0.00E+00 7.902+01 795E+01 0.02% " 1.10E+03 1.44E+02 1.18E+03 005% 4.07E+02 7.012+01 4.072+02 011%

Fe-55

• 2.36E+03 3.70E+03 , 3.70E+03 0082% 1.05E+04 4.28E+03 1.05E+04 0.45% 2.82E+03 9.04E+02 2.62E+03 0.69%

H-3 1.63E+05 6.91E+02 1.63E+05 36.20% 5.43E+04 4.01E+02 5.43E+04 2.31% 1.09E+04 5.33E+02 1.09E+04 2.88%

1-129 -3.79E-01 2.14E+01 2.14E+01 000% 0.00E+00 3.33E+01 3.33E+01 0.00% 0.05E+00 3.82E+01 3.82E+01 0.01%

Na-22 7.14E+01 1:78E+01 7.14E+01 0.02% 0.00E÷00 7.17E+01 7.17E+01 0,00% 0.05E+00 4.01E+01 4.01 E+01 0.01%

Nb-54 8.38E'01 2.30E+01 0.38E+01 0.02% 6.66E+01 7.02E+01 7.08E+01 0.00% 2.79E+01 3.64E+01 3.64E+01 0.01%

NI-59 0.00E+00 2.66E+02 2.06E+02 006% 2.21E+03 2.87E+02 2.21 E+03 0.09% 5.53E+02 2.10E+02 5.53E+02 0.15%

NI-63 4.05E+04 1.94E+03 , 4.05E+04 900%5 1.66E+05 7.70E+03 1.66E+05 7 05% 8034E+04 3.93E+03 8.34E+04 22.05%

Np-37 6,202-01 0.002-01 0.262-01 0.00% 1.01E+00 5.950-01 1.01E+00 000% 0,002-02 7.85E-01 7.05E-91 0.05%

Pu-238 1.63E+02 3.70E+00 1,63E+02 0.04% 0 9.49E+02 4.78E+00 9.49E+02 0.04% 0.75E+02 4.18E+01 8.75E+02 0.23%

Pu-239/240 "/ 3.91E+02 1.37E+00 3.91E+02 009% 3.01E+03 1.99E+00 3.01E+03 0.13% 2.01E+03 2.37E+01 2.01E+03 0.53%

Pu-241 1.02E+03 2.05E+02 1.82E+03 0.40% 7.17E+03 1.11E+02 7.17E+03 0.30% 1.64E+04 1.09E+02 1.64E+04 4.34%

Pu-242 r.. 1.79E+01 3.172+00 1.792+01 0.00% 3.402+01 1.99E+00 3.40E+01 000% 2.97E+01 4.17E+01- 4.17E+01 0,01%

Sr-89 6.70E+02 2.36E+02 6.70E+02 0.15% -1.96E+05 2.04E+02 2.04E+02 0.01% -1.97E+04 2.78E+02 2.78E+02 0.07%

Sr-SO 1.22E+05 3.472+02 1.322+05 2710% 1.25E+06 2.72E+02 1,25E+06 53.124 1.152+05 3.29E+02 1.15E+05 30.40%

Tc-9s 7.54E+01 1.00E+02 1.08E+02 0.02% -4.11E+00 6.172+01 6.17E+01 0%004 1.30E+04 1.04E+02 1.30E+04 344%

U-233/234 7.82E+02 1.02E+00 7.82E+02 0.17% 1.05E+03 6.27&-01 1.05E+03 0.04% 5.43E+01 0.26E-01 5.43E+01 0.01%

4.09E+01 0.01% 5.52E+01 6.29E-01 5.522+01 000% 3.032+00 0.62-01 3.032+00 0004 U-235/236 4,09E+01 1.422+00 U-238 1.33E+01 1.142+00 1.322+01 005% 3.112+01 246E-01 3.11E+01 0.00% 2.50E+00 9.532-01 2.50E+00 00.5%

4.02+05 10000% 2.35E+06 100 00% 3.70E+05 100.0

Attachment A Page 2 of 4 Addendum I Results of Isotopic Analysis of Smear Samples

• /Hot Cell #3 Surface Smear UHot Cell #4 Surface Smear p*Hot Cell #5 Surface Smear

ý*(pCllifltar)

{p C/f.,er) (p CI/61ter)

Result MDA Used Distribution Results MDA Used Distribution Results MDA Used Distribution Am-241 5,26E+01 6.730-01 5.26E+01 0.45% 3 .1E+01 2.42E-01 3.31E+01 0,19% 2.99E+01 2.482-01 2.50E+01 0.11%

C-14 9.05E+00 3.55E+01 3.556401 031% -1.05E+01 5.84E+01 5.84E+01 0.33% i -8.55E+00 5.48E+01 5.48E+01 0.21%

Co.57 60.00+0 7.420+00 7.4284700 006% 9.09E-01 9.59E+00 9.59E+00 0.05% 1.27E+01 1.50E+01 1.5OE+01 0.06%

Co-60 307E.02 5.70E+00 3.97E+02 3.33% 2,70E+02 5.70E+00 2.70E+02 1.54% 1.530+02 9.696+00 1.530+02 050%

Cm-242 0.00=+00 3.-0 926-01 0.00% 9.57E-02 2.07E-01 2.87E-01 0.00% -1.16E-08 7.47E-01 7A7E-01 0.00% i-<

Cm-243/244 2.06E+02 3.430E01 2.06E+02 1.70% 1.46E+00 2.43E-01 1.46E+00 0.01% 9.966-01 7.95E-01 9.96E-01 0.00%

Cs-.134 3.06E-02 1.006+01 1.0E+01 0064 -2.00+00 9.626+00 9.62E+00 005% 3.63E+00 1.82E+01 1.82E+01 0.07%

Cs.137 2.076+03 9.55E+00 3.57E+03 30.76% / 5.87E+03 1.17E+01 5.876+03 3353% 1.756+04 1.700+01 1.75E+04 6642$

Eu-154 5.3E+00 2.59E+01 2.94E+01 022% 1.76LE00 1.69E+01 1.69E+01 0.10% 2.62E+00 2.75E+01 2.75E+01 0.10%

Fe-55 4.50E+02 9.346E+02 8502 00% 6.54E+02 7.55E+02 7.55E+02 4.31% i 6.06E+02 3.326+01 7.52E+02 3.170 7.52E+02 E+702 12.85%

20.%

1:95% 6.17E+02 4.37E+02 6.17E+02 352%

H-3 1.710+01 2.2N/+02 2.26E+02 0.01%

-1.39E+00 1.53E+01 1.53E+01 0 09% 2.123+00 7.176-01 2.12E+00 1-129 N/A N/A 0 0.00% 004%

OilE+O0 0.03% 9.62 6-01 "9.9 6E+00 9.1 E+00 9.30E+00 9.3 66400 00 9 0.476-01 6.11 6+00 Na-22 1.09 0+00 0.003%/ -1.2E-+00 7.946+00 784E400 003%

0304%

5.04E+00 9.15E+00 9.15E+00 0,05% -3.24E+00 5.20+00 11 0% 1 2E+02 0.476+00 1.026E+02 Nb-94 7 20601 2 .53E+02 5.23E+0 3 0 0500% i 9,05E+02 2 .53 6+02 9 .00 0+02 3.42%

NI-59 2.7 NN/A 00+03 4.3 /A 20+02 2.78 6+03 239 04 4.32 0+03 4. 04 0+02 4.323+03 2467%

001%

NI-63 -1.416-01 0.176-01 8.17-01 0.00% -1.46E-01 2,41E+00 2.41E+00 5208E-02 7370E-01 7.787-01 0014 Np-237 . +00 .30 01 1.16E+00 3.3+01 013%

1.206+01 2.4E+00 1,29E+01 0,11% ' 7.2E0+01 0.0 0%

j 2 .200u01 3 .046+00 2.1.6+01 0 13% + 2.0 0+01 9. 006+00 2.0 6+ 01 PU-238 2.5 0 2.10E+00 4+01 2.78E+01 0 .22%

2 E0 2 142.70 +02 2 .53 E +02 0 06%

PU-239/240 3 .35 0+0 2 2.018+02 3.35 0+02 300% > 2. 00E +02 1.54 0+02 Pu-241 3.69E+00 3.0649 0 0 62 4 2.3320+00 1.03E+02 1. OE+02 0372%

2.20E+00 2.41 0+00 248 6400 002 9% 5 .01E-01 2.130+02 2.137E02 1.22% -3.706E+02 2.441E02 2.446E+0 0.93%

PU-243 6.91+02 3.2148+02 0.916+02 51959 -9.25E+02 3.006+02 4.701+03 2904% 5.66+03 3.56+02 5.050+03 21404 Sr-90 2.25E+03 3.670+02 2.24+03 19130% 4.70E+03 3 ,361+01 3.306401 0219 $ -1.15E+01 4.906E+01 4.9 E60E 1 019 1.00+01 3.8000+01 3.80E+01 032% 1.16E+01 Sr-e Tc-99 6.340-01 203 1.74E+00 0.01% 3.0 +00 2. 546-01 3.536+00 0.01%

3.35E+00 .6101+00 3. 000+00 2 1.74 6+00

.370=-01 8.376E01 0300% 9.513E02 7.27E-01 7.27.-E0 0.00%

U-233/234 2K41E-01 9.326-01 9.3E9E01 001% 5,21O-05 2.616-01 2.61E-01 000% 23.73E-01 2.40E-01 3.790-01 0.00% /

U-235/236. 1.20E-01 1.15E+00 1.15 406 02014 1.740-01 U-238 1.75 6+04" 100.00%E 2 .6 0+04 1000 1.16E+04 100,00% /

0 MEAN ST4D.70 C

uot all 00Surface smear 'HotCel I#7 urface Smear .MEAN

/1 Results 5 .6 3 E+ 0 1 MDA 0.80E -01 Used 5 .6 2 6+01 Distributuon 0 54 4 4Results

. 020+01 MDA 2 .70 0-0 t 4 . Used 026+

01 Distributiun 020 0 4 ~ - M I1 . 9 . 020+

02 0 .1 6% 0 . 23%

Am-241 4.916+01 4.915401 0.10% fC-4 2.96E+02 0.20% 0.28%

1.721+02 5.776+01 1.728+02 0.13% -3.30E+01 2.36E+01 0.04% iiCu-57 4.40E+01 0.03% 0.02%

C-14 3.26E+01 2.746+01 3.368E01 0 02% -6.570+00 2.336+01 Co-57 9.3306 5.004+02 I.03% 4 3C0-E0 2.83E+04 2.30% 1.62%

1.44iE-03 9.6 90E00 1.440+03 I05 $ ' 5.30E+02 Co-60 - 01 8 .1 1 6- hi 0 0 0% C m-24 2 2 .546+00 0 .06% 0.00 %

-1 .5 00- 0 0 1. I0 0+00 1 .1 0 04E0 0 .00 % 2 .121 E-01 8 .1 1E

.1.216400 0.00% KCm-ME/244 5.57E+01 0.13% 0.47%

Cm-242 1.0E1+00 1.015 +00 1.08E+00 0100% 1.00+00 1.216+00 2.761 +01 2.736E 01 0.00% /Cs-134 6. 036E 01 0. 03% 0. 03%

Cm-243/244 -1.16 6+01 3 .066+01 " 3.0 401 0 62 4 0.06E+00 Cs-134 2.406+01 3.900+04 76081% -'Cs-IS? 1.900+00 43,69% 22.00%

0.190+04 2.75+01 0.100+04 5002% /3.050+04 Cs-137 3.46 6+01 3.406E 01 0.07 9 Eu-154 3 .404+02 0.04% 0.06%

0+00 0 .00l+01 4.01C 4.01E 0t 0,03% / 1.31 0+01 Eu-1 54 1.506+54 2.75% 2.20%

3.400+03 0.540+03 8.564E03 6.244 4.030+02 0.200=+02 8.206402 I 50% Fe-55 Fe-55 <H-S 6.760=+04 15.26%

4.470+02 2.440+02 4.470+02 0.324 6.01E+02 2.440+02 6.010+02 1.324 .8.20%

H-3 0.62% 0.03%

-3.326+00 2.070=+01 2.07E6401 0.02% 5.416-02 1.116=+01 1.116401 0.024% 1-120 Na- fl. 1.050÷01 4.32 6+01 0.03% 0.02%

1-129 9.78E-00 1.63E+01 0.01 4 4.74 6+00 1. 320+01 1. 32 E 401 0.02 4 1.63E+01 3.006+03 0.12% 0.20%

Na-22 2.136+01 0.024% 4.42E-01 1.70-+01 1.04E+01 0024 Nb-94 2.13E+01 1.25E201 0.40 % K -NI-5 S 9. 060 +02 0.3 2% 0.3 0%

Nb-94 1.3 0+02 2.61 6E+02 2.6 4E+02 0.19% 31.673+02 2.36 6+02 2.3 06402 NI-59 5.44% 'NI-OS 1.070+05 13.39% 10.41%

5.44E0-03 5.400+02 5.440+03 3.979 2.5000+03 4.106+02 2.0601+03 7. -9E`01 0.0 9% 0.00%

NI-63 0.316E-01 0 01 000 4 Np-237

2. 66E -0 1 8.311-01 0.11%

Np-237 1. 326+01 2.0 0E+00 1.2 6E+01 0 4 §02Pu-2 S8 4.70 6+02 0.11%

4.53E+01 7.75E+00 4.53 0+01 0 53 4 0.13%

3.07E+01 1.17E÷00 3.07E+01 0.06% 7.40E+02 4u-230/240 0.13%

Pu-230 1.324402 1.30E+00 1.326+02 0104 2.70+02 3.320E+02 0 004 Pu-241 4 .066+03 1.19% 1.22%

Pu-239/240 4.47 0=+02 2.02 0+02 4.47E+02 013 2% / 3.320E+02 2 .70 6409 0 301% 4 U-242 1.2 0E+01 0.0 9% 0.19 %

Pu-2Mi - . 68E+00 1.30E+00 0.000+00 0,01% i 2 .000-0 1 2.70 6+00 3,.1 4E02 0,59% Sr-89 3 .106+02 0.01% 1 .54%

Pu-242 - 0.07 0+03 2..6+02 , 2. 464E 0 3 0 19 4 .- - 0.2 01 02 .3.01 6+02 Sr-89 2 . 05 0+02 1 6+

8.9 03 1 1 ,49 % S r- 9 O 1 . 0 06+

05 2 5 .4 3% 11 .7614

3. 75 0+ 54 2 . 00 0+02 3 .7 06 +04 2 7 .3 09 5 .9 1 6+03 Sr-S0 4.21E+01 4.086E01 000% " Tu-99 1.40E+04 0.00% 1.32%

3.44E01+01 4.0+01 4.2701 0.03% 1.81E+01 TC-99 1.25+00 7.506+00 0.01% 2.070+02 5U-232/24 0.03% 0.04%

3.916+01 0.38E-01 3.910E+01 0.039% 7.090+00 U-2331234 7. 076E0 1 7.87 6-01 0.00% U-235/13 6 1.1 00+01 0.00% 0.03%

2.97 6+00 0.410-01 2. 07E+00 0400 / 4. 116-01 U-23S51236 0.62`0- 9.826-01 0.00% U-238 5.21 6+00 0.00% 0.0 6%

1.42 0=+00 1.05E+00 1 4201+00 0.00 9 1.03 6-01 U-238 5.146+04 100.00%4 5 100.08%

1.376+05 100.00 Units oursample uu~uenaUouns are presanted 1npC<illar. Fillerin Lhiscoutext is defined as a staudard seaur sample lakeover a lO0an2 urea.

Attachment A Page 3 of 4 Addendum I t

Results of Iso opic Analysis of Smear Samples BALANCE OF PLANT KQuad A Smear +,Quad C Smear Canal E Smear

,(pCI6ilter) (pCi/t~ter) (pCl/foiltr)

Results MDA Used Distribution Results MDA Used Distribution Results MDA Used Distribution Aglo08m 5.63+01 7.241200 5.63E+01 0,06% 4.44E+01 7.67E+00 4.44E+01 007% 0% 1.98E+02 9.21E+00 1.98E+02 0.22%

Am-241 1.43E+00 1.02E+00 1.43E+00 0,00% 1.62E+00 8.09E-01 1.62E+00 0,O-% 3.48E+00 3.60E-01 3.48E+00 C-14 1.08E+03 4.47E+01 1.08E+03 1.08% 7.60E+02 4.89E+01 7.60E+02 1.20% t 7.92E+02 4.42E+01 7.92E+02 0.87%

Co-60 3.78E+03 7.072+00 3.78E+03 3.78% 4.50E+03 7.40E+00 4.50E+03 7.10% 7.61E+03 9.32E+00 7.61E+03 8936%

Cm-243(244. 1 .70E+01 1.28E+00 1.70E+01 0.02% 2.18E+01 2.80E-01 2:181+01 0,03% 1.79E+01 3.62E-01 1.79E+01 0,02%

Cm-245/246 9.732-01 7.22E-01 0.73E-01 0.00% 1.40E+00 3.23E-01 11.401+00 0.00% 2.23E+00 4.18E-01 2.23E+00 0.00%

Cs-137 1.22E+02 9.49E+00 1.22E+02 0 12% 7.44E+01 1.02E+01 7.44E+01 0.12% 1.44E202 1.23E+01 1.44E+02. 0.16%

Eu-152 4.37E+01 2.01E+01 4.37E+01 0,04% 5.17E+01 2.11E+01 5.17E+01 0.08% 6.52E+01 2.58E+01 6.52E+01 0.07%

Eu-154 0.00E+00 2.31E+01 2.31E+01 0.02% 0.O9E+00 2.63E+01 2.63E+01 0.04% 0.09E+00 2.77E+01 2.77E+01 0.03%

Fe-55 8.58E+02 3.79E+01 8.58E+02 0.86% 9.090+02 3.80E+01 9.00E+02 1.42% 8"08E+02 3.79E+01 8.08E+02 0.89%

H-3 8 .07E+04 5.22E+02 8.07E+04 8007951' 3.90E+04 3.57E+02 3.90E+04 61.57% 4.81E+04 4.14E+02 4.81E+04 5282%4 1-129 5.06E+00 1.57E+01 1.57E+01 0.02% 3.62E+00 1.35E+01 1.35E+01 0.02% 3.74E+00 1.88E+01 1.88E+01 0.02%

8.66E+00 001% -6.07E-01 9.26E+00 9.26E+00 0.01% 1.44E+00 1.11E+01 1.11E+01 0.01%

Nb-94 2.29E+00 8.66E+00 2.20E+02 0.22% 2.190E+02 6.56E+01 2.19E+02 0.35% 2.58E+02 7.98E+01 2.58E+02 0.28% ýY NI-59 2.20E+02 4.46E+01 36021/%

NI-63 1.28E+04 8.64E+01 1.28E+04 12.81% 1.76E+04 9.97E+01 1.76E+04 27.79% 3.28E+04 1.30E+02 .3.28E+04 Pu-238 2.92E+00 6.23E-01 2.92E+00 0.00% 1.74E+00 1.16E+00 1.74E+00 0.00% 3.68E+00 1.64E+00 3.68E+00 0.00%

Pu-239/240 1.28E+00 9.49E-01 1.28E+00 0.00% 7.240-01 7.03E-01 7.24E-01 0.00% 1.84E+00 7.07E-01 1.84E+00 Pu-241 1.02E+01 2.64E+01 2.64E+01 0.03% 5.87E+00 2.50E+01 2.50E+01 0.04% 2.13E+01 2.82E+01 2.82E+01 0.03%

Sr-89 1.39E+01 8.86E+00 1.39E+01 0.01% 7.220+00 1.46E+01 1.46E+01 0.02% -1.38E+01 1.18E+01 1.18E+01 0.01%

Sr-90 7.93E+01 8.56E+00 7.93E+01 0.08% 4.27E+01 0.20E+00 4.27E+01 0.07% 1.02E+02 8.25E+00 1.02E+02 0.11%

Tc-99 3.20E+01 3.04E+01 3.20E+01 0.03% . 3.160+01 3.02E+01 3.16E+01 0.05% 5.911+01 4.30E+01 5.91E+01 0,06%

0.00%

U 233/234 " 1.94E-01 9.43E-01 9.43E-01 0.00% 7.96E-01 7.62E-01 7.96E-01 0.00% 4.65E-01 8.95E-01 8.95E-01 9.99E+04 100.00% 6.33E+04 100.00%K , 9.11E+04 100.00%>

4 0Ully pad Smear CTMT General Area Smear Rx Building Smear i(pCI/filter)

'+

/ (pCI/filtsr) (pC[ifilter)

Results MDA Used Distribution Results MDA Used Distnbution ý. Results MDA Used Distribution '

Ag-108m 4.70E+00 3.63E+00 4.70E+00 0.05% 8.69E+01 7.47E+00 8.69E+01 003% K N/A N/A 0 0.06%

Am-T41 . .25E-01 7.17E-01 7.17E-01 0 01% 3.01E+00 7.24E-01 3.61E+00 0500% 7.84E+01 1.471+01 7.54E+01 0.42%

C-14 5.30E+01 2.38E+01 5.30E+01 0 59% 2.90E+02 4.53E+01 2.90E+02 0:11% 2.09E+01 1,37E+01 2.09E+01 0.11%

Coal0 2.53E+02 4.03E+00 2.53E+02 2081% 3.57E+03 6.77E+00 3.57E+03 1.36% 2.38E+02 8.51E+00 2.38E+02 1.,29%

Cm-2431244 2.05E+00 8.75E-01 2.05E+00 0502% 4.71E+01 8.82E-01 4.71E+01 0 02% 2.39E+00 2 4.021-01 2.39E+00 0.01%Y Cm-245/246 6.60E-01 3.96E-01 6.60E-01 0.01% 9.33E-01 4.02E-01 9.33E-01 0.00% N/A N/A . 0 0.00%

Cs-137 1.39E+01 4.05E+00 1.39E+01 0.15% 3.64E+02 9.38E+00 3.64E002 0.14% 4.64E+03 1,02E+01 4.64E+03 25.15%

0.01% 6.50E+01 3.70E+01 6.50E÷01 0.35%

0063% $K:

Eu-152 2.26E+00 1.07E+01 1.07E+01 0.12% 1.40E+01 2.06E+01 2.06E+01 Eu-154 143E+00 1.04E+01 1.04E+01 0.12% 0.00E+00 2.08E+01 2.08E+01 0.01% 7.18E+01 1.75E+01 7.18E+01 0.10%

Fe-5S , 7.910+02 3.82E+01 7.9iE+02 8.80% 4.43E+03 4.02E+01 4.43E+03 1 0.% -1.59E+01 1.79E+01 1.79E+01 5800%

H-3 6.42E+03 3.09E+02 6.42E+03 71.40/. 2.42E+05 9.07E+02 2.42E+05 91.95% ' 1.07E+04 2.89E+01 1.07E+04 1-129 1.54E+01 2.21E+01 2.21 E+01 0 20% -5.02E+00 1.500E+01 1.00E+01 0,00% 1.02E+01 8.17E+00 1.02E+01 0.06%

Nb-94 80.05E-01 3.91E+00 3.91 E+00 0:04% 1.73E+01 8.20E+00 1.73E+01 0.01% ' -3.06E-01 9.12E+00 9.12E+00 0.05%

NI-59 8 0.000E00 7.98E+01 7.98E+01 0.89% 9.04E+01 7.67E+01 9.04E+01 0.03% 2.36E+02 2.31E+01 2.36E+02 1.28%

NI-63 1.24E+03 I" 2.68E+01 1.24E+03 13.79% 1.19E+04 8.27E+01 1.19E+04 4.524% 3.27E+01 6.59E+01 6.59E+01 0.36%

Pu-2383 '.' 2.24E-01 7.25E-01 7.25E-01 001% 6.51E-01 9.05E-01 9.052-01 0.00% 2.86E+01 3.50E+00 2.86E+01 016%

Pu-239/240 4.33E-01 4.14E-01 4.33E-01 0.00% 2.16E+00 1.04E+00 2.16E+00 0.00% 1.48E+01 2.71E+00 1.48E+01 0.08%

Pau-241 2.56E+00 3.08E+01 3.08E+01 0 .34% 2.71E+01 2.37E+01 2.71E+01 0.01% 1.78E+02 1.43E+02 1.78E+02 0.96%

Sr-89 1'- -6.02E-01 8.76E+00 8.76E+00 0.10% 2.99E+01 7.18E+00 2.99E+01 0.01% N/A N/A 0 0.00%

Sr-SO . 9.77E+00 8.11E+00 9.77E+00 0 11% 2.42E+02 8.64E+00 2.42EO2 0.09% 2.04E+03 1.44E+01 2.04E+03 11.06%'/

Tc-99 1.02E+01 3.39E+01 3.39E+01 0338% 9.06E+00 3.36E+01 3.36E+01 0.01% 0,00E+00 2.81E+01 2.81E+01 0.15%

U-233/134 3.14E-01 1.01E+00 1.01 E+00 0.01% 3.73E-01 9.00E-01 9a.OE-01 0.00% 4.38E+00 4.43&+00 4.43E+00 0.02%

8.99E+03 100.00%-- 2.63E+05 100.00% 1.34E+04 100.00%

Rx Building Smear Duplicate S(pCll6flter) MEAN MEAN STD DEV Results MDA Used Distribution (pCI/gm) (%)

Ag-1 08m N/A N/A 0 0.00% ,$ýAgq-108m 5.58E÷01 0.06% 0.07%

Am-241 1.01E+02 1.55E+01 1.01E+02 0.47% ' Am-41 2.72E+01 0.13% 0.22%

C-14 2.09E+01 1.37E+01 2.09E+01 0.10%/ *!::ii c-t4 4.31E+02 0.58% 0.48%

Co-60 2.53E+03 7.07E+00 2.53E+03 1105% C..o-6o 3.21 E+03 5.22% 3.99%

Cm-243/244 2.31E+00 7.91E-01 2.31E+00 001% >+tCm-243/244 1.58E+01 0.02% 0.01%

Cm-245/246 N/A N/A 0 0.00% /i- Cm-245/246 8.85E-01 0.00% 0.00%

Cs-137 5.63E+03 1.01E+01 5.63E+03 2360.22% 'ii 2636% +*' Eu-1 Cs-137 52 1.57E+03 7.46% 12.50%

Eu-152 3.29E+01 4.62E+01 4.62E+01 4.33E+01 0.13% 0.12%

Eu-1 54 9.62E+01 1.50E+01 9.62E÷01 0.45% -:':Eu-154 3.95E+01 0.15% 0.19%

Fe-55 -9.63E+00 2.00E+01 2.02E+01 0.09% 'i.4 F.-5 1.12E+03 1.98% 3.07%

H-3 1 1.05E+04 2,84E+01 1.05E+04 40.16% .i!H.-3 6.25E+04 66.53%/ 15.60%

1o129 1.94E+01 1.09E+01 1.94E+01 0.09%  ?t1.129 1.57E+01 0.06% 0.09%

Nb-94 4-1.29E+00 8.60E+00 0.60E+00 0.04%

0.i0% ..'.Nb-94

• !iNl-s9 4

9.71E+00 0.03% 0.02%

NI-59 -1.65E+01 2.03E+01 2.03E+01 1.611+02 0.45% 0.46%

NI-63 6.79E+01 6.83E+01 6.83E+01 0.32%

• NI-63 1.09E+04 13.66% 13.78%

Pu-236 ' 2.86E+01 3.50E+00 2.86E+01 0.13% 'tPu-236 9.601+00 0.04% 0.07%

Pu-2391240 1.48E+01 2.71E+00 1.48E+01 0 07% + <Pu-239/240 5.151+00 0.02% 0.04%

Pu-241 1,78E+02 1.43E+02 1.78E+02 0o34 ,iiýPu-241 7.05E+01 0.32% 0.41%

Sr-89 N/A N/A 0 o.00%

01 9.55%  :.:s,-89

$Sr-90 1.131+01 0.03% 0.03%

Sr-90 U, 2.04E+03 1.44E+01 2.04E+03 6.51E+02 3.01% 3.80%

Tc-99 "-1.21E+01 2.81E+01 2.81 E+01 0,13% "i Tc-99 3.52E+01 0.12% 0.13%

U-2331234 4.38E+00 4.43E+00 4.43E+00 0.02% .U+u-233/234 1.91E+00 0.01% 0.01%

2.14E+04 100.00% 100.00%

Units for sample concentratons are presented in pCifilter. Filter in this context Is defined as a standard smear sanple take ovar a I o0cm2 area.

Attachment A Page 4 of 4 Addendum I Results of Isotopic Analysis of Smear Samples Reactor Operations & Laboratory Building 0 0

'ROLB Smear Duplicate (ROLB Smaer 2 ROLB Smear 4'(p~l/filtsr) (p~l/filler)

(pCi/flilter)

Results MDA Used Distribution Results Used Distribution Results MDA Used Distribution MDA 1.64E+00 1.82E+00 0.01% 1.82E+00 1.64E+00 1.82E+00 0.01% 6.07E+00 1.70E+00 6.07E+00 0.3%"

Amn-241 ..,. 1.82E+00 1.05E+01 0.04% -4.69E+01 00G% 1t.05E+01 1.03E+01 8.61E+01 8.61E0+01 0.47%

1C-t4 11.55E+01 1.53E+01 1.55E+01 4.09E+02 1:45% 4.09E+02 1.16E+01 4.09E+02 1.45% 8.90E+01 8.81E+00 8.90E+01 0.48%

Co-60 4.09E+02 t.16E+01 3.27E+00 -2.54E-01 3.27E+00 3.27E+00 0.01%Y 8.22E-01 1.53E+00 1.53E+00 0.01%

Cm-242 -2.54E-01 3.27E+00 001%

3.04E+00 001% 3.04E+00 1.54E+00 3.041+00 0.01% 5.60E-01 2.09E+00 2.09E+00 0.01%

Cm.243/244 3.04E+00 1,64E+00 4.77E+03 15.96% 4.77E+03 1.37E+01 4.77E+03 16*9W6 2.97E+03 1.14E+01 2.97E+03 16.18%

Cs.137 4,77E+03 1.37E+01 0.07% 1,26E+01 1.86E+01 1.86E+01 0.07% 1.46E+02 3.23E+01 3.23E+01 0.18 Eu-155 1.26E+01 1.00E+01 1.66E+01 5.30E+01 2.08E+04 73,96% -498E+02 6.84E+02 6.84E+02 3.73%

H.3 2.08E+04 5.30E+01 2.08E+04 73.93% 2.08E+04 1.67E+01 0.06% 1.67E+01 1.20E+01 1.67E+01 0.06% 9063+02 1.04E+01 9.63E+02 5.24%

1-129 K.$ 1.67E+01 1.20E+01 IAIE+01 0.05% 6.74E+00 1.41E+01 1.41E+01 0.05% 1.910+02 8.11E+00 8.11E+00 0.04%

Nb-94 6.74E+00 1.41E+01 2.56%

1.95E+02 0.69% 5.16E+01 1.95E+02 1.95E+02 0069% -4.30E+02 4.71E+02 4.71E+02 NI-50 5 16E+01 1.95E+02 0.24%

6.30E001 0.22% 3.13E+01 6.30E+01 6.30E+01 0.22% 1.70E+02 4.47E+01 4.47E+01 NI-63 3.13E+01 6.30E+01 1I.00E+01 0:04% 7.94E-01 4.43E+00 443E+00 0.02% 3.65E+00 1.74E+01 1.74E+01 0,09%

Np-237 4.93E+00 1.00E+01 5.64E+00 1.08E+01 004% 1.88E+00 1.53E+00 1.88E+00 0.01%

Pu-232/240 5 .64E+00 1.95E+00 002% 1.08E+01 3.19E+00 947E+01 0.34% 9.32E+01 1.50E+02 1.50E+02 0053% 8.80E+01 7.57E+01 7.57E+01 0.41%

Pu-241 5.88E+01 9.47E+01 5.26E+01 0 19% -1.24E+00 5.26E+01 5.26E+01 0.19% = 5.92E+00 4.82E+01 4.83E+01 0.26%

Sb-125 -1.24E+00 5.26E+01 1.48E+03 1.39E+01 1.48E+03 5026% 4.81E+02 1.23E+01 4.81E+02 2.62%

Sr-S0 1.53E+03 1.48E+01 1.53E+03 5.44%

2.80E+01 0.10% 5.96E-01 2.80E+01 2.80E+01 0.10% 9.04E+01 8.89E+01 8.89E+01 0.48%

Tc`-9 5.96E-01 2.*0E+01 8.52E0+1 0.30% 1 .181+04 4.93E+00 1.16E+04 64.02%

U.233/234 t .15E001 3.97E+00 9.15E+01 033% ,.52E0+0 1.01E+00 3.94E+02 2.14%

U-235/236 U-238 5.82E+00 4.81E+00 2.84E+00 2.85E+00 5.82E+00 4.81E+00 0.02%

0.02%

4.42E+00 4.46E+00 2.24E+00 2.18E+00 4.42E+00

.446E+00 0.02%

0.02%

3.94E+02 1.42E+02 3.35E+00 2.71E+00 1.42E+02 0.77% ~

2.81E+04 100.00%, 1.84E+04 100%4 2.81E+04 100.00%

ROLB Smear 2 Duplicate MEAN MEAN STD DEV (pCI/gm) (%)

(pCtiflter)

R' Results MDA Used Distribution 0 2.90E+00 0'02% +'/Amn-241 3.15E+00 0.02% 0.01%

Am-241 :Ks 2.35E+00 2.90E+00 8.51E+01 8.51 E+01 0.48% OC-14 4.93E+01 0.26% 0.25%

C-14 -2.04E+01 0.54% .-xCo-60 2.51E+02 Co-SO 9.58E+01 7.77E+00 9.58E+01 0.98% 0.54%

Cm-242 -6.70E-03 2.230+00 2.23E+00 0,01% Cm-242 2.58E+00 0.01% 0.00%

2.11E+00 0.01% ' Cm-243/244 2.57E+00 0,01% 0.00%

Cm-243W244 6.50E-01 6 2.110+00 1.17E+01 2.90E+03 16.40% Cs-137 3.85E+03 16.62% 0.40%

C-137 I2..0E+03 3.18E+01 0.18% Eu-155 2.53E+01 0.12% 0.06%

Ee-10 - 2.77E+01 3.18E+01 6.85E+02 3087% H-3 1.07E+04 38.87% 40.50%

H-3 -4.15E+02 6.35E+02

-129

• 9.32E+02 1.05E+01 9.32E+02 5.27% 1-129 4.82E+02 2.66% 3.00%

1.94E+02 7.77E+00 7.77E+00 0 :04,Nb-94 -1.10E+01 0.05% 0.00%

Nb`64 0 NI-59 K 4.21E+01 4.93E+02 4.93E+02 2.79% KNI59 3.38E+02 1.68% 1.15%

4.36E+01 0 30% N1-63 5.36E+01 0.23% 0.01%

NI-63 1.68E+02 4.36E+01 8.72E+00 8.72E+00 0.05% Np-237 1.01E+01 0.05% 0.03%

Np-237 -1.58E+00 2,00E+00 9,05E-01 2.00E+00 0,01% ýPu-239/240 5.08E+00 0.02% 0.01%

Pu-239/240 N 5.34E+01 9.19E+01 9.19E+01 0.52% :0-P.-241 1.03E+02 0.45% 0.09%

Pu-241 4.69E+01 4.69E+01 0.27% 'Sb-125 5.01E+01 0.23% 0.04%

Sb-125 -5.72E+00 Sr-90 4.97E+02 1.26E+01 4.97E+02 2.81% Sr-90 9.97E+02 4.03% 1.6%

Tc-99 4.51E+01 8,87E+01 8.87b,01 0.50% Tc-99 5.84E+01 0.30% 0.23%

U-233/234 1.11E+04 5.04E+00 1.11E+04 62.820/ U-233/234 5.76E+03 31.87% 36.44%

4,08E+02 2.30% U-235/236 2.03E+02 1.12% 1.27%

U-2351236 4.08E+02 3.28E+00 0.86% U-238 7.58E+01 U-238 1.52E+02 4.58E+00 1-52E+02 0.42% 0.46%

1.77E+04 100% 100.00%

Units for sample cencentratiols are presented in pCVfllter. Filter in this context is defined as a standard snear sample take over a 100=cn2 area.

Attachment A Page I of 3 Addendum I Results of Isotopic Analysis of Smear Samples (100%Rule Normalized)

HOT LABORATORY aiiiHot Cell Equipment #11 Smear Hot Cell Equipment #2 Smear Not Cell Equlpment #3 Smear lr (pCIflterl) Msu (pClifllter) :I (pCLifilter)

Results MDA Used Distribution Results MDA Used Distribution Results MDA Used Distribution C a60 2.74E+05 1.24E+02 2.74E+05 10.81% 8.664E03 2.25E+01 8.6.E403 2.16% 2.67E+03 1.27E+01 2.67E+03 2.78%

C8137 8.07E+05 2.06E+02 8.07E+05 31.82% 2.71E+05 6.98E+01 2.71E+05 67.5% 4.512E04 3.22E+01 4.51E+04 46898/.

Eu 154 iii 1.7E+03 3.689+02 1.79E+03 0.07% .O00OE+008.27E+01 1.275+01 0.02% 1.94E+02 7.49E+01 1.94E+02 0.20%

H-3 6.26E+05 3.49E+02 6.26E+05 24 69% 4.69E+03 2.53E+02 4.69E+03 1.17% 1.73E+03 4.51E+02 1.73E+03 1.80%

Sr-90 8.27E+05 3.49E+02 8.27E+05 32.61% 1.15E+05 3.50E+02 1.15E+05 28.79% 4.63E+04 3.65E+02 4.63E+04 48.23%

2.54E+06 100.00% 3.99E+05 100.00% 9.60E+04 100 00%

Ceo Eqalpment#4 Smear ali-0t Hot CellEquapment 15 Smear Hot Cel Eqaupment#6 Smear X.

"p C li flt srl (pC lXllter

ýii(pC itfiltler)

Resuets MDA Used Distribution Results MDA Used Distrlbution Results MDA Used Distribution Co-60 1.58E+03 1.232+01 1.58E+03 6.61% 3.23E+02 7.08E+00 3.23E+02 0.10% 4.91E+02 7.50E+00 4.91E+02 2.22%

c.892E03 1.12+01 3.88+03 16.70%0.17 2.85E+05 6.04E-01 2.05E+05 87.86 1182+04 1472+01 1t6+0 8282k Eu- 154 264+01 3 +01 .E01 17% .0 0 3.04E+01 3.04E+01 0.01% 006E+00 3.11E+01 3.1E+01 0.14%

1.51E+04 3.94E+02 1.51E+04 63.21% 7.61E+01 2.70E+02 2.70E+02 080% 1.95*+02 2.63E+02 2.63E+02 119%

Sr,-90 3.18E+03 3.84E+02 3.18E+03 13.316/6 3 3.84+04 2.876+02 3.042+04 116 A 8.70E+03 3.54E+02 9.70E+03 43.92%

. 2.39E+04 100.00%::% 3.24E+05 100.00%k ::: 2.21E+04 100.00%

Hot ai Cell Equipment #7 Smear "*.a".HotCell #1 Surface Smear  :..'.Hot Cell #2 Surface Smear

iipCI/Slterl iý (pC~fllter) (pWtt~~lterl X. Results MDA Used Distribution !! Results MDA Used Distributlon  : Results MDA Used Distribution Coa68 8:i 6.086+03 2.032+01 6.08E+03 1.52% 5.162-04 5.18 +01 5.16E+04 2.39% 2.01E,04 3.13E+01 2.01E+04 7.87%

C.-137 1.09E+05 5.49E+01 1.09E+05 27.24% 8.03E+05 1.25E+02 8.03E+05 37.17% 1.09E+05 6.47E+01 1.09E+05 42.68%

Es 154 005+00 O. 7.95E+01 7.95E+01 002% 1.185+03 1.44E+02 1.18*+03 0.05% 4.076+02 7.91E201 4.07E+02 016%

1.636+08 8.01E+02 1.63E+05 40.73% 5.43E+04 4.01E+02 5,43E+04 2.51% 1.09E+04 5.33E+02 1.09E+04 4.27%

Sr- 8 1.222+08 3.472+02 1.22E+0 304% .25E+06 2.72E+02 1.25E+06 5757% 1.800 2.9+02 1182+08 4503%

4.00E+05 100.00% 2.16E+06 100.00%",.': 2.55E+05 100.00%

aotCell83 Srface Smear tCell 4 Surface Smear Hot Ceolt5 Surface Smear (pCOfllter) iiii pCfller) pClfllter Results MDA Used, Distrlbution Reselts MDA Used Distributao Results MDA Used Distribution Ca 65 3.872+02 870E+00 3.872:02 5ý0 061A 2.702+02 5.70E+05 2.70E+02 2.35%A 1.53E+02 8.692+00 1.532+02 0.65%

Cs-137 2.57E+03 9.55E+00 3.57E+03 5536k 5.87E+03 1.17E+01 5.87E+03 51.16% 1.75E+04 1.70E+01 1.75E+04 73.97%

Eu-104 5.35E+00 2.59E+01 2.59E+01 0.40% 1.76E+00 1.69E+01 1.692+01 0.15% 2.62E+00 2.75E+01 2.75E201 0.12%

-3 1.71E÷01 2.26E+02 2.26E+02 2 6.17E+02 4.37E+02 6.17E+02 5.38% 3.32E+01 3.17E+02 3.17E+02 1.34%

Sr-98 2.24E+03 3.67E+02 2.24E+03 34.73% 4.70E+03 3.00E+02 4.70E+03 40.96% 5.66E+03 3.56E+02 .5.66E+03 23.92%

8.45E603 100.00%' 1.152+04 10000% 2.376+04 100.00%

Hot Cell #6 Surae Smear Hot Cell 67 Surface Smear MEAN MEAN STD DEV xll (p ClIflter) l:pCI/flltsrn) (l)Com 1 Resuets MDA Us.d Distibution Resuets MDA Used Distrbutonf Co-60 1.44E+03 9.69E+00 1.44E+03 1.19% 5.30E+02 9.30E+00 5.30E+02 1.14% 0+-SO . 2.83E+04 3.41% 3.15%

Cs-137 .t89E+04 2.75E+01 8.19E+04 67.50% 3.95E+04 2.40E+01 3.95E+04 84.66% :lCs-137 1.98E+05 53.11% 21.35%

Eu-154 0.006+00 4.01E+01 4.01E+01 0,03% 1.31E+01 3.48E+01 3A8E+01 0.07 Eu-154 3.042+02 0.12% 0.10%

H-3 4.47E+02 2.44E+02 4.47E+02 0.37% 6.51E+02 2.442+02 6.81E+02 1.46% H-3 6.76E+04 10.84% 19.01%

Sr-90 3.75E+04 2.89E+02 3.75E+04 30.91% 5.91E+03 2.95E+02 5.91E+03 12867% Sr-90 1.98E+05 32.52% 13.97%

1.21E+05 100.00% 4.67E+04 100.00% 100.00%

Units for sernple concentrations are presented in pCi/filter. Filter in this context Is definedas a standard smear sample take over a 100cm2 area.

Attachment A Page 2 of 3 Addendum I Results of Isotopic Analysis of Smear Samples (10% Rule Normalized)

BALANCE OF PLANT

X.Quad A Smear Quad C Smear i i Canal E Smear lpCitfllter) iiii (p Clfl lerl l](pClI/lter)

Results MDA Used Distrlbutlon a Results MDA -Used Distrlbuton Results MDA Used Distribution Ce-60 3.702+03 7.07E+00 3.78E+03 4.46% 4.50E+03 7.40E+00 4.50E+03 10.31% 7.61E+03 9.32E+00 7.61E+03 13.59%

Cs-137 1.22E+02 0.49E+00 1.22Et02 0.14% 7.44E+01 1.02E+01 7.44E+01 0.17% 1.44E+02 1.23E+01 1.44E+02 02604 000200o 2.31+01 2.310+01 0034 0002+00

. 2.63E+01 2.63E+01 0.06% 00j)joooE+00 277E+01 2.77E401 005 Eu-154 H-3 8.07E+04 5.22E+02 0.07E+04 95.25% 3.90E+04 3.57E+02 3.90E+04 89.33% 4.01E+04 4.14E+02 4.81E+04 8509%

1-129 5.00E+00 1.57E+01 1.57E+01 0.02%  :: 3.62E+00 1.35E+01 1.352+01 0.03% 3.74E+00 1.88E+01 1.881+01 0.03%

Sr-90 7.903+01 8.56E+00 7.93E+01 0.0% 4.271+01 9.20E+00 4272+01 0.10% 1.02+02 8.25E400 1.02E+02 0A18%0 8.47E+04 100.00%/a 4.37E+04 100.00%: 5.60E+04 100.004 Ully Pad Smear i i CTMT General Area Smear RX Building Smear XI"(pClfilter) iio pCWfillter) l lujipCl/filterl Results MDA Used DLtibutsonI Results MDA Used Distributon Results MDA Used Distribution Co-60 2.53E+02 4.03E+00 2.53E+02 3.706%4 3 57E+03 6.77E+00 3.57E+03 1.45% 2.38E+02 8.51E+00 2.30E+02 1.34%

Cs-137 1.39E+01 4.05E+00 1.39E+01 0.21% 3.64E+02 9.38E+00 3.64E+02 0.15% 4.64E+03 1.02E+01 4.64E+03 26.21%

Eu-154 143E+00 1.04E+01 1.040+01 0.14% 0.00O+00 2.00+01 2.080+01 0014 7.18E+01 1.70E+01 7.18E+01 0.41%

H-3 0.42E+03 3.09E+02 6.42E+03 95.41% 2.42+05 9.07E+02 2.42200 00.209 1.07E+04 2.9 +01 1.07E+04 60.45%

1-129 1.540+01 2.212+01 2.21 0+01 033% -0.020+00 1002+01 1000001 .00% 102E+01 .17E+00 1,02E+01 0.06%

Sr-S0 9.77E+00 8.11E+00 9.77E+00 0.15% 2.42E+02 8.64E+00 2.42E+02 0.10% 2.04E+03 1.44E+01 2.04E+03 11.53%

6.73E+03 100.00% ::' 2.46E+05 100.00%::, 1.77E+04 100004%

O!RX Building Smear Duplicate MEAN MOAN STD DEV Results MDA Used Ditribution ibi:i (pCvgm) cO-60 2.53E+03 7.07E+00 2.53E+03 12.15% Co-60 3.21E+03 6.72% 5.17%

5.630+03 1,01E+01 CS-137 5.63E+03 27.05% Cs-I 37 1.57E+03 7.74% 12.91%

Eu-1 54 9.62E+01 1.59E+01 9.62E+01 0.46% Eu-154 3.95E+01 0.17% 0.19%

H-3 1.05E+04 2.84E+01 1.05E+04 50.44% H-3 6.25E+04 82.15% 10.93%

1-129 1.94E+01 1.00E+01 1.94E+01 0.09% *l-120 1.57E+01 0.08% 0.11%

Sr-S0 2.04E+03 1.44E÷01 2.04E+03 9.80% Sr-90 6.51E+02 3.13% 3.88%

2.08E+04 100.00% 100.00%

Units for sample concentratons are presented in pCi/filter. Filter in this context is defined as a standard smear sanile take over a 100-2 area.

Attachment A Page 3 of 3 Addendum I Results of Isotopic Analysis of Smear Samples (10% Rule Normalized)

Reactor Operations & Laboratory Building jý ROLB Smear .i. ROLB Smear Duplicate i-ii:ROLB Smear 2 c

i: (pCitiltr(ler: I fltur) lpcllter)

Results MDA Used Dlstrlbutalo  ::j:: Results MDA Used Distribution 4: Results MDA Used Distribution co60as 4.09E-02 1.16E+01 4.0eE,02 1.45% i~ii 4.009E02 1.16E+01 4.00E+02 1.40% 8.90E+01 e.81Eo00 5.80. 01 0.51%

4.7-10 3770 4.7+03 17.274 4.770.03 1.37E-01 4.77E+03 17.30% 2.97E+03 1.14E+01 2.e7E++031 17.14%

H-3 ii 2.08E+04 5.30E+01 2.08E+04 75.30% 2.08E+04 5.30E+01 2.08E+04 75.46% -4.98E+02 6.84E+02 6.84E+02 3.95%

1.129 1.67E+01 1.20E+01 1.67E+01 0.05%  :: 1.67E+01 120E+01 1.67E+01 0.06% ii* 9.63E+02 1.04E+01 9.53E+02 5.55%

Sr-90 1.53+03 1.45+01 1.53E+03 5.54% / i: 1.48E+03 139E501 1.48E+03 5.37%/ i, 4.81E+02 1.23E+01 4.015+02 2774 U-233/234 9.15E+01 3.97E+00 . 0 30 8.525+01 00 8.52E+01 0.31% 1.18E+04 4.93E+00 1.18E+04 67.51%

U-235/23, 5.82E+00 2.94E+00 5.825+00 0.02% 4.25.00 2245+00 20400 0524 3.94E+02 3.35E000 354.402 2.274A 2.76E+04 15005%:. 2.76E04 '1500.0% 1.73E+04 10 ROLSSmear 2 Duplicate MEAN MEAN STD DEV (pClfiltper) (pCi/gm) (%)

ii Results MDA Used Distribution Co-60 0.K 9.58E+01 7.77E+00 9.58E+01 0.50% c0-6o 2.51 E+02 1.01% 0.54%

C.-137 2.90E+03 1.17E+01 2.90E+03 17.44% Cs-1 37 3.85E+03 17.29% 0.13%

H-3 -4.15E+02 6.55E+02 6.85E+02 4.12% H-3 1.07E+04 39.71% 41.19%

1-129 9.32E+02 1,05E+01 9.32E+02 5.60% 1-129 4.82E+02 2.82% 3.19%

Sr-90 4575E+02 1.25E+01 , 4.97E+02 2.59% Oi!i!Sr-90 9.97E+02 4.17% 1.49%

U-233/234 1.11E+04 5,04E+00 1.11E÷04 65024 U-2331234 5.76E+03 33.82% 38.60%

U-235123 4.050+02 3.205+00 4.08-02 20.5% 4  ::WU-235/236 2.03E+02 1.19% 1.35%

1.66E+04 " 100% 100.00%

Units for sanpla concentrations are presented In pCi/filter. Filter in this context is defined as a standard smear sample take over a 00crr2 area.

Final Status Survey Plan for the Plum Brook Reactor Facility Attachment A Radionuclide Distribution Basis for DCGL Determination &

Final Status Survey of the Plum Brook Reactor Facility (PBRF)

Addendum 2 Preliminary Analysis of Concrete Core "Puck" Samples by the On-Site Laboratory

Attachment A Page 1 of 16 Addendum 2 Preliminary Analysis of Concrete Core "Puck" Samples by the On-Site Laboratory CORE BORE #5, Reactor Building -25 ft., Area 22 C900010111FLICI L0505-01 1ST PUCK C900010111FLICILOSOS- 01A 1ST PUCK C900010111FLICILOS06-02 2CND PUCK C900010111FLICILO505-02A 2CND PUCK 04NCH DEPTH 112-INCH DEPTH 1124NCH DEPTH 14NCH DEPTH Results MDA Used %Results MDA Used  % Results MDA Used  % Results MDA Used  %

K-40 5.26E+00 1.94E+00 5.26E+00 12+35% 7.10E+00 1.94E +00 7.10E+00 22.27% 7.41E+00 2.02E+00 7.41E+00 93.01% 7.95E+00 2.02E+00 7.95E+00 88.66%

CO-60 2.77E+01 1.97E-01 2.77E+01 64.98% 1.81E+01 1.97EE-01 1.81E+01 56.81% ND 0 ND 0 Nb-94 ND ND ND ND Ag-108m 6.61E-01 3.21E-01 6.61E-01 1+55% ND 0 ND 0 ND 0 Cs-137 7.74E+00 3.34E-01 7.74E+00 18.17% 456E+00 3.71E -01 4.56E+00 14.31% ND 0 3.93E-01 2.04E-01 3.93E-01 4.39%

Eu-152 ND ND ND ND Eu-154 ND ND ND ND TI-208 ND ND ND ND Pb-212 ND ND 5,57E-01 3.76E-01 5.57E-01 6.99% 6.24E-01 3.91E-01 6.24E-01 6.95%

Pb-214 ND 1.21E+00 7.07E-01 1.21E+00 3.79% ND 0 ND 0 Bi-212 ND ND ND ND Bi-214 1,26E+00 5.26E-01 1.26E+00 2.95% 9.00E-01 5.24E-01 9.00E-01 2.82% ND 0 ND 0 Ra-226 ND ND ND ND Ac-228 ND ND ND ND Th-234 ND ND ND ND U-235 ND ND ND ND Am-241 ND ND ND ND Cmn-243 ND ND ND ND CM-245 ND ND ND ND 4.26E+01 100.00% 3.19E+01 100.00% 7.96E+00 100.00% 8,97E+00 100.00%

0 inch 1/2 inch 1/2 inch 1 inch

!1/2 INCH 1/2 INCH 3.00.E01 2 50E+01 2 000001 - K-40 E -C1137 1 500.01 - -- __Pb-2412

-Pbý-214

-Bi-214 50OE000 1/2 1/2 t

Dep h

Attachment A Page 2 of 16 Addendum 2 COR IMl nayssofnm cW tCo."Puck" Samples by the On-Site Laboratory C900010111FLIC31506-061 1ST PUCK C900010111FLIC3LO5-06B1A 1ST PUCK C900010111FLIC3L.050-2 2CNDPUCK C900OI0111FLICILOSO$-02A 2CND PUCK 04NCH DEPTH 112-INCHDEPTH 12-INCH DEPTH 1-4NCHDEPTH Results MDA Used Results MDA Used  % Results MDA Used  % Results MDA Used  %

K-40 1.24E+01 2.96E+00 1+24E+01 5.23% ND 0 ND 0 ND 0 Co-60 ND 0 6.61EE+00 3.00E-01 6.61E+00 2.23% ND 0 ND 0 Nb-94 ND ND ND ND Ag-108m ND ND ND ND Cs-137 2.22E+02 9.47E-01 2.22E+02 93.43% 2-70E+02 8.92E-01 2.70E+02 91.10% ND 0 2.58E-01 1.36E-01 2.58E-01 6.23%

Eu-152 ND ND ND ND Eu-154 ND 0 3.42E+00 1.62E+00 3.42E+00 1.15% ND 0 ND 0 Tt-208 ND 0 ND 0 ND 0 3.29E-01 1.64E-01 3.29E-01 7.96%

Pb-212 ND 0 ND 0 ND 0 6.33E-01 4.58E-01 6,33E-01 15.31%

Pb-214 ND 0 ND 0 1.48E+00 4.98E-01 1.48E+00 17.26% 1.26E+00 4.76E-01 1.26E+00 30,55%

Bi-212 ND 0 6.54E+00 7.08E+00 6.54E+00 2.21% ND 0 ND 0 Bi-214 ND 0 3.10E+00 1.67E+00 3.10E+00 1.04% 1.52E+00 2.34E-01 1.52E+00 17.77% 1.65E+00 4.49E-01 1.65E+00 39.96%

Ra-226 ND 0 ND 0 5.57E+00 3.89E+00 5.57E+00 64.97% ND 0 Ac-228 ND ND ND ND Th-234 ND ND ND ND U-235 ND ND ND ND Am-241 3+17E+00 1.95E+00 3.17E+00 1.33% 6.75E+00 2.23E+00 6.75E+00 2.27% ND 0 ND 0 Crn-243 ND ND ND ND Cm-245 ND ND ND ND 2.38E+02 100.00% 2.97E+02 100.00% 8.58E+00 100.00% 4.13E+00 100.00%

0 inch 1/2 inch 1/2 inch 1 inch i112 INCH 1/2 INCH 300 14 12 250 -K-40 0K-.D 10 -coon0 200 -G-137

-Eo 154

-Eo 45 8 -T6208 E - TI-208 95-Pb 212 15 - Pb212 o -Pb 214

-Pb 214 6 - -8k212

-B.212 100__ -B____-

ý214 4 -Re226 Rý-22fl

-A-l241

-A-,241 son 2 ___

05 0.5 05 05 D.pth D.pth with Cs-1137 without Cs-137 CORE BORE #7, Reactor Building -15 ft, SE Area

Attachment A Page 3 of 16 Addendum 2 Preliminary Analysis of Concrete Core "Puck" Samples by the On-Site Laboratory C900010111FLICILO507-01 1ST PUCK C900010111FLICILO507-01A 1ST PUCK C900010111FLICIL0507-02 2CND PUCK C900010111FLICILO507-02A 2CND PUCK 04NCH DEPTH 112-NCH DEPTH 1124NCH DEPTH 14NCH DEPTH 0 i.38E~0 Results 3.25E.00 MDA Used 1.39E~00 % 11.09% 1 1124NCH0

.00 DEPTEHO Results MDA Used Results MDA Used Results MDA Used  %

K-40 1.38E+00 3.25E+00 1.38E+00 1.04% 1.30E+01 2.13E+00 1.30E+01 49.03% ND C0 ND 0 4.04% 3.83E-01 2+17E-01 3.83E-01 0 Co- -60 1 5.02E-01 2.17E-01 5.02E--01 1.44% ND C ND 0 Nb-94 ND ND ND ND Ag-i08m ND ND ND ND Cs-137 1.69E+00 2.58E-01 1.69E+00 13.57% 1.28E+00 2.06E-01 1.28E+00 4.83% ND C0 ND 0 Eu-i 52 ND ND ND ND Eu-i 54 ND ND ND ND TI-208 ND ND ND ND Pb-212 ND 0 7.15E-01 4.35E-01 7.15E-01 2.69% 4.37E-01 4.09E-01 4.37E-01 13.84% 5.28E-01 4.38E-01 5.28E-01 4.19%

Pb-214 1.79E+00 4.03E-01 1.79E+00 14.39% 1.50E+00 4.96E-01 1.50E+00 5.64% 1,60E600 4.90E-01 1.60E+00 50,72% 1,62E+00 4.79E-01 1.62E+00 12.88%

Bi-212 5.35E+00 1.97E+00 5.35E+00 43.02% ND 0 ND 0 ND 0 B1-214 1.73E+00 4.87E-01 1.73E+00 13.90% 1.67E*00 5.16E-01 1.67E+00 6.27% 1.12E+00 3.47E-01 1.12E+00 35.44% 1.28E+00 3.81E-01 1.28E+00 10.20%

Ra-226 ND 0 8.00E+00 5.84E+00 8.OOE+00 30.10% 6.03E+00 0 916E+00 4.41 E+00 9.16E+00 72.72%

Ac-228 ND ND ND ND Th-234 ND ND ND ND U-235 ND ND ND ND Amn-24i ND ND ND ND Cm-243 ND ND ND ND Cmn-245 ND ND ND ND 1.24E+01 100.00% 2.66E+01 100.00% 3.16E+00 100.00% 1.26E+01 100.00%

0 inch 112 inch 1/2 inch Mlee- 1 inch S112INCH 112 INCH 14.

12-10- 10 K-40

-K-40

59. -c-137

-Pb-212

-Pb-214

-B4214

-RS,226 4- 4. Bi-212 2-

+1 !1 -

05 05 Depth CORE BORE#9, Containment -25 ft, Area 18

Attachment A Page 4 of 16 Addendum 2 Prelimin "VWej6f-g C%'*Jjc"Samples by I V.o1A LAA R25 1ST PUCK C900010111FLIC1L0509-02 2CNO PUCK C900010111FLICIL0509-02A 2CND PUCK 0N4NCH DEPTH 112INCH DEPTH 1124NCH DEPTH 14NCH DEPTH Results MDA Used  % Results MDA Used Results MDA Used Results MDA Used KA 0 ND ND ND ND Co -60 ND ND ND ND Nb--94 ND ND ND ND Ag--108m ND ND ND ND 7.11E-01 2+34E-01 7.11 E-0'1 8.52% 1.40E-01 0 ND 0 Cs- 137 1.35E+00 2 34E-01 1.35E+00 9.81%

Eu- 152 ND ND ND ND Eu- 154 ND ND ND ND TI-2 ND ND ND 208 ND Pb-21 5.40E-01 4.27E-01 5.40E-01 3.91% 5.62E-01 4.40E-O1 5.62E-01 6.74% 5.58E-01 4.55E-01 5.58E-01 18.70% 6.56E-01 3.42E-01 6.56E-01 20.58%

Pb-212 11.07% 1.25E+00 5.50E-01 1.25E+00 14.95% 1.22E+00 3.51E-01 1.22E+00 40.80% 1.39E+00 4.03E-01 1.39E+00 43.57%

1.53E+00 4.04E-01 1.53E+00 Bi-212 ND 0 4.48E+00 1.94E+00 4.48E+00 53.72% ND 0 ND 0 Bi-214 1.59E+00 3.98E-01 1.59E+00 11.53% 1.34E+00 3.44E-01 1.34E+00 16.07% 1.21E+00 4.01E-01 1.21E+00 40.50% 1.14E+00 3.22E-01 1.14E+00 35.85%

Ra-226 8.78E*00 6.08E÷00 8.78E+00 63.68% ND 0 ND 0 ND 0 AC-228 ND ND ND ND Th-234 ND ND ND ND U-235 ND ND ND ND Amn-241 ND ND ND ND Cmn-243 ND ND ND ND Cmn-245 ND ND ND ND 1.38E+01 100.00% 8.34E+00 100.00% 2.98E+00 100.00% 3.19E+00 100.00%

0 inch 1/2 inch 1/2 inch 1 inch 0

S112 INCH 1/2 INCH 10 9

8 7

cs 1337 C

6 E B-P,2121 9 5 Ru226 4

3 2

1 0

05 0.5 Depth CORE BORE #10, Waste Handling Building -15ft MC900010111FLIC3LO510-01 1ST PUCK §C900010111FLIC3LO5IO-01A 1ST PUCK IC i00010111FLICIL0510-02 2CND PUCK MC900010111FLIClLOSIO-02A 2CNDPUCK a

Attachment A Page 5 of 16 Addendum 2 Prelimin A.Wl6%gf Concrete Core "Puck" Samples by t

,kJ.*hiA**)rato rY 1124NCH DEPTH 1I4NCH DEPTH Results MDA Used  % Results MDA Used Results MDA Used  % Results MDA Used  %

K-4-60 ND N0 0 ND 0 1.20E+01 2.10E+00 1+20E+01 78.10% 1.11E+01 2.10E+00 1.11E+01 87.04%

ND ND ND ND Nb-94 ND ND ND ND Ag -108m ND ND ND ND Cs- 137 8.17E-03 3.85E-00 8.17E+03 100.00% 4.37E+03 3.40E+00 4.37E+03 100.00% 5.09E-01 2.48E-01 5+09E-01 3.32% 3.21E-01 1.39E-01 3.21E-01 2.51%

Eu-152 ND ND ND ND Eu -154 ND ND ND ND TI- 208 ND 0 ND 0 3.77E-01 1.26E-01 3.77E-01 2.46% ND 0 Pb--212 ND 0 ND 0 5.12E-01 4.16E-01 5.12E-01 3.34% ND 0 Pb.-214 ND 0 ND 0 8.54E-01 5.05E-01 8.54E-01 5.57% ND 0 Bi-2212 ND ND ND ND Bi- 214 ND 0 ND 0 1.11E+00 2,40E-01 1.11E+00 7.22% 1.34E+00 2.40E-01 1.34E+00 10.45%

Ra- -226 ND ND ND ND Ac-228 ND ND ND ND Th- -234 ND ND ND ND U-235 ND ND ND ND Amnm241 ND ND ND ND CM-243 ND ND ND ND Crm-245 ND ND ND ND 8.17E+03 10000% I 4.37E+03 100.00% 1+53E+01 100.00% 1.28E+01 100.00%

0 inch 112 inch 1/2 inch 1 inch A

i1/2 INCH 1/2 INCH 9000 8noo 7000 6000 E 5000 ssoon 01200

K-40 noc

- K-40 -Pb-212 4000 Pb-212

-Pb-214 3000 3000 P-B214 5,-214 9.214 2000 1000 05 0.5 05 0,5 DS.Pt D.pth with Cs-137 without Cs-137 CORE BORE #11, Hot Laboratory 0 ft (0 Inch to I inch)

I C90001011tFLiCILO1 1-01 1ST PUCK C C00010111FLICILOS1 1-OIA 1ST PUCK C900010111FLICILO511-02 I

2CND PUCK CS00010111FLICILO511-02A 2CND PUCK 0-INCH DEPTH 12-4NCH DEPTH 11I2-NCH DEPTH l 14NCH DEPTH

Attachment A Page 6 of 16 Addendum 2 Prelimin A jiysis oWJ~ncrete CeW'Puck" Sgmples by I .2&iteLab lory Used Results MDA Used Results MDA Used K-40 6r34E+00 1.87E+00 6r34E+00 0.48% 7.61 E+00 1.87E+00 7.61E+00 1.13% 9.76E+00 2.25E+00 9r76E+00 37.03% 1.34E+01 2.25E+00 1.34E+01 49.33%

CO-80 2.83E+00 1.90E-01 2.83E+00 0,21% 1.36E+00 1.90E-01 1.36E+00 0.20% ND 0 ND 0 Nb-94 ND ND ND ND Ag-108m ND ND ND ND Cs-137 1.29E+03 1.46E+00 1.29E+03 97.38% 6.59E+02 1.22E+00 6.59E+02 98.18% 1.39E+01 2,72E-01 1.39E+01 52.67% 1.18E+01 3.31E-01 1.18E+01 43.44%

Eu-152 ND ND ND ND Eu-154 4.71E+00 3.67E+00 4.71E+00 0.36% ND 0 ND 0 ND 0 TI-208 ND ND ND ND Pb-212 2.79E+00 0 ND 0 ND 0 9.33E-01 5,29E-01 9.33E-01 3.43%

Pb-214 3.69E+00 0 ND 0 1.45E+00 5+13E-01 1.45E+00 5.52% 1.03E+00 7.41E-01 1.03E+00 3.80%

Bi-212 ND 0 ND 0 ND 0 ND 0 Bi-214 2.10E+00 0 ND 0 1.26E+00 4.12E-01 1.26E+00 4.78% ND 0 Ra-226 ND ND ND ND Ac-228 ND 0 ND 0 ND 0 ND Th-234 ND ND ND ND U-235 ND ND ND ND Am-241 2.08E+01 3.25E+00 2.08E+01 1.58% 3.26E+00 2.04E+00 3.26E+00 0.49% ND 0 ND Cm-243 ND ND ND ND Cm-245 ND ND ND ND 1.32E+03 100.00% 6.71E+02 100.00% 2.64E+01 100.00% 2.72E+01 100.00%

0 inch 112 inch 1/2 inch 1 inch 1/2 INCH 1/I2 INCH 1400 1200

-K40

-CS-137 E 800 6 600Pb-212 600 _Pb-214

~*

600 6-212 0,8414 4O00 400 Ac-228

-An,-241 200 0

DEPTH with Cs-137 CORE BORE #11, Hot Laboratory 0 ft (1 inch to 2 inch)

C900010111FLICIL05I1-03 3RD PUCK C900010111 FLIC1LO511-03A 3RD PUCK C9000101IFLIcILO8i11-04 4TH PUCK C9000101,1FLICIL0611-04A 4TH PUCK 14NCH DEPTH I 1/124NCHDEPTH 1 1124NCH DEPTH 24NCH DEPTH Results MDA Used  % Results MDA Used  % Results MDA Used  % Results MDA Used

Attachment A Page 7 of 16 Addendum 2

_9 K.40Prlimin Analysis of Concrete Core "Puck"oSamples by 1 *O'lgSVg+10b°rm ÷oo 8.38E+00 47.91%

0 0 0 0 0 Co-60 0 Nb-94 Ag-108m Cs-137 3.22E+00 2.02E-01 3.22E+00 63+95% 3.29E+00 1.41E-01 3.29E+00 18.82% 1.52E+00 2.06E-01 1.52E+00 47.92% 1.27E+00 2.46E-01 1.27E+00 37.25%

Eu-152 Eu-154 0 0 0 0 TI-208 Pb-212 0 0 5.03E-01 3.84E-01 5.03E-01 15.87% 0 Pb-214 1.02E+00 5.60E-01 1.02E+00 20.32% 1.31E+00 4.586-01 1.31E+00 7.51% 1.15E+00 4.16E-01 1.15E+00 36.21% 1.15E+00 5.19E-01 1.15E+00 31.59%

Bi-212 0 2.94E+00 1+97E+00 2 94E+00 16.80% 0 0 Bi-214 7r92E-01 2+43E-01 7.92E-01 15.73% 7.48E-01 4.09E-01 7.48E-01 4.27% 0 9.96E-01 3.17E-01 9.96E-01 29.17%

Ra-226 Ac-228 0 8.22E-01 6.06E-01 8.22E-01 4.70% 0 0 Th-234 U-235 Am-241 0 0 0 Cm-243 Cm-245 5.03E+00 100.00% 1.75E+01 100.00% I 3.17E+00 100.00% 3.41E+00 100.00% I 1 inch 1 112 inch 1 112 inch sm-_ 2 inch A

11ICH' K-40

-Co-60

-Eu-i 54

-Pb-212 E

-Pb-214

-8,212 8.W214

-AC-228

-AM-241 0.5 0.5 1.5 1.5 DEPTH without Cs-137 CORE BORE #12, Hot Laboratory 0 ft 0-4NCH C900010111FLIC3LO512-01 t DEPTH 2.12NCH 1ST PUCK C900010111FLICIL0512-O1A DEPTH 1ST PUCK- CSU0*01011FLIClLO512-02 112-4NCH DEPTH 2CND PUCK 1.4NCH DEPTH Csc00010111FLCIL012-02A 2CND PUCK K0 Results MOA Used  % Results MOA Used  % Results MDA Used %Results MDA Used9.16E+00 %

K-0 I 1.31E+01 2 626+00 1.31E+01 4.161% 1.49E+01 3.83E+00 1.49E+01 7.13% 11.00E+01 2.11E+00 1.006+0.1% 71.84% 9.16E+00 2A16+00 7901

Attachment A Page 8 of 16 Addendum 2 coZrelimin AnXtpf CoqWFore 1P7Vpt'lSamplegXlo On171.Tbora 6E_01 1.26E+01 6.02%

2A15E-01 0 ND 0 Nb-94 ND 0 5.38E-01 1.85E-01 5.38E-01 0.26% 1.49E-01 0 ND 0 Ag-108m ND ND ND ND Cs-137 2.81E+02 9.32E-01 2.81E+02 89.02% 1.76E+02 9.92E-01 1.76E+02 84.37% 2.84E-01 1.40E-01 2.84E-01 2.04% ND 0 Eu-152 ND ND ND ND Eu-154 ND ND ND ND TI-208 ND ND ND ND Pb-212 ND 0 ND 0 5.61E-01 3.46E-01 5.61E-01 4.02% ND 0 Pb-214 ND 0 2.87E+00 2.26E+00 0 1.38E+00 5.84E-01 1.38E+00 9.88% 1-06E+00 4.13E-01 106E+00 9.13%

Bi-212 ND ND ND ND Bi-214 ND 0 2.54E+00 1.24E+00 2.54E+00 1.21% 1.71E+00 4.24E-01 1.71E+00 12.22% 1,37E+00 4.06E-01 1.37E+00 11,81%

Ra-226 ND ND ND ND Ac-228 ND ND ND ND Th-234 ND ND ND ND U-235 ND ND ND ND Am-241 3.92E+00 1.73E+00 3.92E+00 1.24% 2.11E+00 1.53E+00 2.11E+00 1.01% ND ND 0 Cm-243 ND ND ND ND Cm-245 ND ND ND ND 3.16E+02 100.00% 2.09E+02 100.00% 1.40E+01 100.00% 1.16E+01 100.00%

0 inch 1/2 inch 112inch 1 inch A

S1/2 INCH 1/2 INCH 300 2500

-K-40

-C.-60

-Nb-04 E -Cn.137 E S150 - - ___ Pb-212

-P0212

-Pb-214

-P5-214

-B-214 100 _______8-214 -B_ -Mo.241

-An-24 1 0' 0.5 as 05 D.pth Depth with Cs-137 without Cs-1 37 CORE BORE #13, Hot Laboratory 0 ft (0 inch to I inch) c90O0o1oII1FLIc3LO5I13-01 1ST PUCK Ic90oOIOIIIFLIcI1.o5I3-0IA 1ST PUCK JC90001011I1FLICIL0613-02 2cND PUCK c000IIIIFLOCILO6I3-02A 2cND PUCK 0-INCH DEPTH 1124NCH DEPTH Ih/2-4NCH DEPTH l-INCH DEPTH Results MDA Used  % Results MDA Used  % Results MDA Used  % Results MDA Used  %

K-40 1.287E+01 2.70E+00 1.87E+01 0.54% 1.28E+01 2.70E+00 128E+01 0.53% 9,42E+00 2.24E+00 9242E+00 6189%ICD 790E+00 2024E+00 7N90E+00 63.50%1 Co-60 I 1.28E+00 2.75E-01 1.28E+00 0.04% 8.12E-01 2.75E-01 8.12E-01 0.03% ND 0 ND0

Attachment A Page 9 of 16 Addendum 2 Nb_9p4relimin &nalysis of Concrete Core "Puck"oSamples by' n-Slte Laboratory 0 2.37E-01 1.58E-01 2.37E-01 1.61% ND 0 Ag-1 08m ND ND ND ND Cs-137 3.41E+03 2.92E+00 3.41E+03 99.17% 2.40E+03 2.77E+00 2.40E+03 99W44% 1.75E+00 1.48E-01 1 75E+00 11.87% 1.09E+00 1.48E-01 1.09E+00 8.73%

Eu-152 ND ND ND ND Eu-154 ND ND ND ND TI-208 ND 0 ND 0 ND 0 ND 0 Pb-212 ND 0 ND 0 ND 0 7,OOE-01 4.55E-01 7.00E-01 5.63%

Pb-214 ND 0 ND 0 1.56E+00 6.OOE-01 1.56E+00 10.55% 1.16E+00 6.05E-01 1.16E+00 9.31%

Bi-212 ND ND ND ND Bi-214 ND 0 ND 0 1.78E+00 4.04E-01 1.78E+00 12.08% 1.60E+00 2.56E-01 1.60E+00 12.83%

Ra-226 ND 0 ND 0 ND 0 ND 0 Ac-228 ND ND ND ND Th-234 ND ND ND ND U-235 ND ND ND ND Ar'-241 8.58E+00 4.49E+00 8.58E+00 0.25% ND 0 ND ND 0 Cm-243 ND ND ND ND Cm-245 ND ND ND ND 3.44E+03 100.00%

II 2.42E+03 100.00% I 1.48E+01 100.00% I 1.24E+01 100.00% I 0 inch 112 inch 1/2 inch 1 inch 1%

S1/2 INCH 12H 3500 3000* 30K-40

-Co-60 2500- 2Nb-94

-C.-137

-TI-208 E 2000

-Pb-212 1Pb-214 15000

-Bi-214

- Ra-226 oAm-241 500-0.5 0.5 1 1 15 1.5 DEPTH with Cs-137 CORE BORE #13, Hot Laboratory 0 ft (1 inch to 2 inch)

C900010111FLIC3LO613-03 3RDPUCK lC900010i11FLIC1L013-03A 3RDPUCK C900010111FLIClLO513-04 4THPUCK C90001011IFLICILO513-04A 4TH PUCK 1-INCH DEPTH 1I124NCH DEPTH I 1124NCH DEPTH 124NCH DEPTH Results MDA Used  % Results MDA Used  % Results MDA Used  % Results MDA Used  %

K-40 1,33E+01 2.18E+00 1.33E+01 78.43%11 1,33E+01 2.18E+00 1.33E+01 60.81%11 1.17E+01 2. 11E+00 1.17E+01 73.601 9.16E+00 2.11E+00 9.16E+00 74.59%1 CO-60 0I 0I 0I 0 Nb-94 10 0 0 0

Ag,1 Attachment A Addendum 2 Cs-137 Eu-152 ilmin Analysis of Concrete Core "Puck" Samples by I 6.01E-01 2.20E-01 6.01E-01 3.54%

F On-Site Laboratory 5.39E-01 1.97E-01 5.39E-01 2.46% 7+21E-01 1A40E-01 7.21E-01 4.52%

Page 10 of 16 Eu-154 TI-208 0 4.18E-01 1.79E-01 4.18E-01 1.91% 0 0 Pb-212 6.15E-01 4.66E-01 6.15E-01 3.62% 8.76E-01 3.98E-01 8.76E-01 4.00% 6.91E-01 4.76E-01 6.91E-01 4.33% 5.92E-01 3.27E-01 5.92E-01 4.82%

Pb-214 1.34E+00 4.85E-01 1.34E+00 7.91% 9.67E-01 4.27E-01 9.67E-01 4.42% 9.57E-01 5.26E-01 9.575-01 6.00% 1.49E+00 4A4E-01 1.49E+00 12.17%

Bi-212 Bi-214 1.10E+00 4.55E-01 1.10E+00 6,50% 1.84E+00 0,4177 1.84E+00 11.55% 1.04E+00 3r21E-01 1.04E+00 8.43%

Ra-226 0 5.78E+00 4.30E+00 5.78E+00 26.40% 0 0 Ac-228 Th-234 U-235 Am-241 0 0 0 0 Crm-243 Crm245 1.70E+01 100+00% 2,19E+01 100.00% 1.60E+01 100.00% 1+23E+01 100+00%

1 inch 11111. 1 112 inch 1 1/2 inch 2 inch A

112 INCH 112INCH 18 16 14 . . - C.........

-K-4 8 -TI-208 10 8ib-214

-An-241 05 ---.-- 1.

0 0.5 0.5 1 1.5 1.5 2 DEPTH without Cs-137 CORE BORE #14, Hot Laboratory 0 ft "0 IN000101IFLIC3L0514-01 1ST PUCK C900010111FLIClL0514-OIA 1ST PUCK C900010111FLICIL0514-02 2CND PUCK c900010111FLlCIL0514-02A 2CNDPUCK 0-4NCHDEPTH 1/24INCH DEPTH 11124NCHDEPTH 1-4NCHDEPTHI K-40 1.77E+01 2.29E+00 1.77E+01 0.82% 7+58E+00 0 1.54E+01 2.18E+00 1.54E+01 61.13% 9.77E+00 2.18E+00 9.77E+00 77.26%

Co-60 7.49E+00 2.32E-01 7.49E+00 0.35% 4.73E+00 232E-01 4.73E+00 0.37% 2.23E-01 0 2+98E-01 2.22E-01 2+98E-01 2.36%

Nb-94 8.98E-01 5.26E-01 8.98E-01 0+04% 8.63E-01 3.77E-01 863E-01 0.07% 1.89E-01 0 1.54E-01 0 Ag-108m ND ND IND IND I

Attachment A Page 11 of 16 Addendum 2 Cs,_,felimin AnrpI t f Co tCore qj3SampI O"°nWi4boPa','+oo 1.286E03 99.56% 1.82E-01 1.44E-01 0 Eu-152 ND ND ND ND Eu-154 ND ND ND ND TI-208 ND ND ND ND Pb-212 ND 0 ND 0 4.99E-01 3.44E-01 4.99E-01 1.98% 3.72E-01 0 Pb-214 ND 0 ND 0 1.39E+00 3.34E-01 1.39E+00 5.51% 1.11E+00 6.14E-01 1.11E+00 8.78%

Bi-212 ND ND ND ND Bi-214 ND 0 ND 0 1.68E+00 3.49E-01 1.68E+00 6.66% 1.47E+00 0.14E-01 1.47E+00 11.60%

Ra-226 ND 0 ND 0 6.22E-00 4.76E+00 6.22E+00 24.71% 6.19E+00 0 Ac-228 ND ND ND ND Th-234 ND ND ND ND U-235 ND ND ND ND Arn-241 ND ND ND ND Cm-243 ND ND ND ND Cm-245 ND ND ND ND 2.17E+03 100.00% II 1.26E+03 100,00% I 2.52E+01 100.00% I 1.26E+01 100.00% I 0 inch 1/2 inch 112 inch 1 inch S1/2 INCH 1IH 2500 2000

-K-40 1500 N5-Cý0.

Co-00K-4G 1500 5

oO Cn.137Nb-94 Pb-212Pb-212 15000 Pb-21-P55214 5.214 8 214 Rn.22-R.-226 500 0,5 Depth with Cs-137 without Cs-137 CORE BORE #15, Hot Laboratory 0 ft (0 inch to I inch)

C900010111FLICILOSI5-01 I1STPUCK C890001O0111FLI C11.061-01A I1STPUCK C9000IOIIIFLICILO8I5-2 2CND PUCK C900010111FL1CILOS16-02A 2CND PUCK 0-4NCHDEPTH 112-4NCH DEPTH 11/2-INCH DEPTH 14-NCHDEPTH K-40 1.29E+01 2.50E+00 1.29%+01 0.13% 1.76E+01 2.49E+00 1.76E+01 0.22%% 1.40E+01 2.10+00 1.40E+01 46.13%% 1.33+01 2.105+00 1.33E+01 5 R-401.29E+01 25.02E0 U .29E+01 % R Est MA UsE 0 0 R Es 1 2 0 UsEd 4 R Est 2 0 UsEd 5 Co-60 7.20E+01 5.02E-01 7.20E+01 0.72% 5.36E+01 2.53E-01 5.36E+01 0.68% 8.69E-01 2.13E-01 8.69E-01 2.87% 8.64E-01 2.13E-01 8.84E-01 3.57%

Nb-94 ND 0 1.10E+00 8.53E-01 1.10E+00 0.01% ND 0 ND 0 Ag-108m ND ND ND ND Cs-137 9.87E+03 5.11E+00 9.87E+03 99.05%1 7.79E+03 4.90E+00 7.79E+03 98.99% 1.40E+01 4.53E-01 1.40E+01 48.41% 8.28E+00 2.94E-01 8.28E+00 33.40%

Attachment A Page 12 of 16 Addendum 2 Eu-l*eimin Analysis of Concrete Core "Puck" Samples by I Wn-Site Laboratory ND ND Eu-154 ND ND ND ND TQ208 ND 0 ND 0 ND 0 ND 0 Pb-212 ND 0 ND 0 ND 0 ND 0 Pb-214 ND 0 ND 0 1,39E+00 6.27E-01 1.39E+00 4.59% 1.24E+00 7.66E-01 1.24E+00 4.99%

Bi-212 ND ND ND ND Bi-214 ND 0 ND 0 ND 0 1.06E+00 6,65E-01 1.06E+00 4.26%

Ra-226 ND ND ND ND Ac-228 ND ND ND ND Th-234 ND ND ND ND U-235 ND ND ND ND Arm-241 9.63E+00 6.17E+00 9.63E+00 0.10% 7.10E+00 6.51 E +00 7.10E+00 0.09% ND 0 ND 0 Cm-243 ND ND ND ND Cm-245 ND ND ND ND 9.96E+03 100.00% 7.87E+03 100.00% 3.03E+01 100.00% 2.48E+01 100.00%

0 inch 112inch 112 inch 1 inch A

0 S112 INCH 1112 INCH 12000 10000 KO40 8000 0Co-60 1Nb-94 1Cs-137 6000 0TI-208 1Pb-212 Pb-214 4000 14 214 Arn-241 2000 0.5 0.5 1 1 1.5 1.5 DEPTH with Cs-1 37 CORE BORE #15, Hot Laboratory 0 ft (1 inch to 2 inch)

I-4NCH DEPTH I 112-INCH DEPTH *1112-4NCH DEPTH 2-INCH DEPTH K-40 1 9.23E+00 1.79E+00 9.23E+00 79.00% ND 0 1.15E+00 2.36E+00 1.15E+00 21.46% 1.15E+00 2.36E+00 1.15E+00 21.46%

Co-60 ND 0 ND 0 ND 0 ND 0 Nb-94 ND 0 ND 0 ND 0 ND 0 Ag-1083 ND N3 N1 N3 Cs-137 N.31E-01 3.22E-01 1,18E-011 3.22E-01 2.75% 5,31E-01 1.18E-01 21.71% 5.95E-01 1.DE-01 5.95E-01 11,05% 5.95E-01 1.5E-01 5.95E-01 11.05%

Eu-152 NDND ND IND

Attachment A Page 13 of 16 Addendum 2 Eu.l-pellmin L&nalysis of Concrete Core "Puck" Samples by , kqn-Slte Laboratory ND ND TI-208 ND 0 2.53E-01 1.70E-01 2.53E-01 10.35% ND 0 ND 0 Pb-212 ND 0 ND 0 7.17E-01 5.33E-01 7.17E-01 13.32% 7,17E-01 5.33E-01 7.17E-01 13.32%

Pb-214 1.24E+00 4.83E-01 1.24E+00 10.61% 1.25E+00 3.18E-01 1.25E+00 51.11% 1.19E+00 6.04E-01 1.19E+00 22.18% 1.19E+00 6.04E-01 1.19E+00 22.18%

Bi-212 ND ND ND ND Bi-214 8.92E-01 2.93E-01 8.92E-01 7.63% 4.11E-01 2.04E-01 4.11E-01 16,83% 1.72E+00 2,70E-01 1.72E+00 31.98% 1.72E+00 2.70E-01 1.72E+00 31.98%

Ra-226 ND ND ND ND Ac-228 ND ND ND ND Th-234 ND ND ND ND U-235 ND ND ND ND Am-241 ND 0 ND 0 ND 0 ND 0 Cm-243 ND ND ND ND Cm-245 ND ND ND ND 1.17E+01 100.00% Ll 2.44E+00 100.00% 5.38E+00 100.00% I 5.38E+00 100.00%

1 inch 1 1/2 inch 1 1/2 inch 2 inch A A i1/2 INCH ' 112INCH I 70 60

-K-40 50- 50Co-60 E -Nb-94

-TI-208 T 40 UPb-212 30 30 Pb-214 8Bi-214

-Am-241 20 10 0

0.5 0.5 1 1 1.5 1.5 DEPTH without Cs-137 CORE BORE #16, Hot Pipe Tunnel, -12 ft C900IDOD1111FLICILOII-6-O1 1ST PUCK C9000ID111FLlClLO516-OIA 1ISTPUCK C9OO1I(1011FLICILO05I6-2 2CND PUCK 3C9000I101FLICILOS16-02A 2CND PUCK K-40 1.32E+01 1.95E+00 1.32E+01 2.15% 9.26E+00 1.95E+00 9.26E+00 2.46% 8.84E+00 2.1OE+00 8.84E+00 70.20% 1.17E+01 2.10E+00 1.17E+01 7773%

Co-60 2.10E+01 1.98E-01 2+10E+01 3.41% 1.28E+01 1.98E-01 1.28E+01 3.39% 2.14E-01 0 2.14E-01 0 Nb-94 NODONON Ag-108m NDO ND ND ND Cs-137 5.82E+02 1.398+00 5.82E+02 94.45% 3.53E+02 8+79E-01 3.53E+02 93.47% 6.17E-01 2.54E-01 6.17E-01 4.89% 8.12E-01 2.27E-01 8.12E-01 5.39%

Eu-152 ND ND ND ND Eu-1 54 IND IND IND IND

Attachment A Page 14 of 16 Addendum 2 TI-2 &relimin Pnalysis of Concrete Core "Puck" Samples by I %qn-Site Laboratory ND ND Pb-212 ND 0 ND 0 6.82E-01 4.07E-01 6.82E-01 5.42% &.55E-01 0 Pb-214 ND 0 ND 0 8.59E-01 5.50E-01 8.59E-01 6.82% 1.37E+00 5.43E-01 1.37E+00 9.12%

Bi-212 ND ND ND ND Bi-214 ND 0 2.57E+00 1.35E+00 2.57E+00 0.68% 1.60E+00 2.40E-01 1.60E+00 12.67% 1.17E+00 3.58E-01 1.17E+00 7.76%

Ra-226 ND ND ND ND Ac-228 ND ND ND ND Th-234 ND ND ND ND U-235 ND ND ND ND Am-241 ND ND ND ND Cm-243 ND ND ND ND Cm-245 ND ND ND ND 6.16E+02 100.00% 3.77E+02 100.00% 1.26E+01 100.00% I 1.50E+01 100.00% I 0 inch 112 inch 112 inch 1 inch i112 INCH 1/2 INCH 700 600 4-500 4a S400- 400. -Cý60 C0-60 Co-80 Is S Cs-137 E 137 P6-212Pb-212 O300-  ::C112 '- , 2 300. -111146-214 Pb.214

-..- 211 6,-214-D-214 200 100.

0i ,

0 a's 05 I Depth Depth with Cs-1 37 without Cs-1 37 CORE BORE #17, Fan House, -12 ft C900010111FLICILOL17-01 1ST PUCK C900010111FLICIL0517-OIA 1ST PUCK C900010111FLICIL0617-02 2CND PUCK C900010111FLICILO516-02A 2CND PUCK 04NCH DEPTH 1124NCH DEPTH 1124NCH DEPTH 14NCH DEPTH Results MDA Used Results MDA Used  % Results MDA Used  % Results MDA Used  %

K40 1.70E+01 2.46E+00 1.70E+01 65.69% 1.54E+01 2.46E+00 1.54E+01 74.32% 1+39E+01 2,27E+OO 1.39E+01 46.03% 1.57E+01 2.27E+00 1.57E+01 89.44%

Co-60 ND ND ND ND Nb-94 IND ND ND ND I

Ag-108m ND ND 1.90E-01 ND Cs-137 9.95E-01 1.63E-01 9.95E-01 3.83% 885E-01 1.63E-01 8.85E-01 4.28% N 4.48E-01 1.50E-01 4.48E-01 1.49% 3.68E-01 O Eu-152 ND ND Eu-154 ND ND ND ND ND ND TI-208 ND ND ND ND

Attachment A Page 15 of 16 Addendum 2 Pb.2Wlimin An +pf Coi.%.pore 1 PO n l*itb° r9t08UE.01 8.81E-01 4.26% 4.13%

6.52E-01 5.11E-01 6.52E-01 2.17% 7.25E-01 5.56E-01 7.25E-01 Pb-214 1.87E-00 7.01E-01 1.87E+00 7.21% 1.79E+00 6.30E-01 1.79E+00 8.65% 1.34E+00 5.27E-01 1.34E+00 4.46% 9.64E-01 4.77E-01 9.64E-01 5.49%

Bi-212 3.71E+00 2.28E+00 3.71E+00 14.29% ND 0 ND 0 ND 0 Bi-214 1.66E+00 6.27E-01 1.66E+00 6.40% 1.76E+00 2.81E-01 1.76E+00 8.49% 9.61E-01 4.09E-01 9.61E-01 3.19% 1.65E-01 2.59E-01 1.65E-01 0.94%

Ra-226 ND 0 ND 0 5.65E+00 5.38E+00 5.65E+00 18.77% ND 0 Ac-228 ND 0 ND 0 1.12E+00 6.45E-01 1.12E+00 3,70% ND 0 Th-234 ND 0 ND 0 6.08E+00 6.OOE+00 6.08E+00 20.20% ND 0 U-235 ND ND ND ND Am-241 ND ND ND ND Cm-243 ND ND ND ND Cm-245 ND ND ND ND 2.60E+01 100.00% 2.07E+01 100.00% I 3.01E+01 100.00% I 1.76E+01 100.00% I 0 inch 112 inch 1/2 inch 1 inch A

i112 INCH -1/2INCH 18 16 14

-K40 12 4- -C.137

-P5-212

-P6-14 10 -B 212

-B.214

-Ro226 6 -Ae-228

-Th-234 4

2'1.

Al -..- ~------ II 0 0.5 05 D.pth CORE BORE #21, ROLB Fuel Vault C900010111FLICILO521"1 1ST PUCK C900010111FL1ClLO521-OIA 1ST PUCK CS0010111 FLCIL0821-02 2CND PUCK C90010111FLICIL0521-02A 2CND PUCK 04NCH DEPTH 1124NCH DEPTH 1124NCH DEPTH 14NCH DEPTH Results MDA Used  % Results MDA Used  % Results MDA Used  % Results MDA Used  %

K40 1.50E+01 2.21E+00 1.50E+01 84.76% 1.59E+01 2.21E+00 1.59E+01 81.31% 1.33E+01 208E+00 1.33E+01 84.59% 9.65E+00 2.98E+00 9.65E+00 87.04%

Co-60 ND ND ND ND Nb-94 ND ND ND ND Ag-108m ND ND ND ND Cs-1 37 ND 0 2.38E-01 1.46E-01 2.38E-01 1.22% ND 0 3.05E-01 1.93E-01 3.05E-01 2.75%

Eu-152 ND ND ND ND Eu-154 ND ND ND ND T1-208 ND 0 3.49E-01 2.66E-01 3.49E-01 1.78% ND 0 ND 0 Pb-212 I ND 0 6.53E-01 5.68E-01 6.53E-01 3.34% 5.26E-01 4.71E-01 5.26E-01 3.35% ND 0

Attachment A Page 16 of 16 Addendum 2 I

13gtoSampleý.t I I Pb21elimin Arf%,f CoTsFoire0 qihn0 o.ora . E.01 1.06E*00 5+43% 1.02E+00 5.06E-01 1.02E+00 6.51% ND 0 Bi-212 ND ND ND ND Bi-214 1.31E+00 4.05E-01 1.31E+00 7.39% 1.35E+00 5.85E-01 1.35E+00 6.92% 8.70E-01 4.55E-01 8.70E-01 5.55% 1.13E+00 3.62E-01 1.13E+00 10.21%

Ra-226 ND ND ND ND Ac-228 ND ND ND ND Th-234 ND ND ND ND U-235 ND ND ND ND Arn-241 ND ND ND ND Cm-243 ND ND ND ND Cm-245 ND1 ND ND ND 1.77E+01 100.00%

I 1.95E+01 100.00% 1.57E+01 100.00% 1.11E+01 100.00%

0 inch 1/2 inch 1/2 inch 31 inch A

S1/2 INCH 1/2 INCH 16 14 - _ _

12 -K-40 Cs-137 iTb-208 10 a8 Pb-212

.Pb-214 6 8+3214 4

2 . . ......... . .. ....

0 I 0 0.5 0.5 1 DEPTH

Final Status Survey Plan for the Plum Brook Reactor Facility Attachment A Radionuclide Distribution Basis for DCGL Determination &

Final Status Survey of the Plum Brook Reactor Facility (PBRF)

Addendum 3 Results of Isotopic Analysis of Concrete Core Samples

Attachment A, Page 1 of 3 Addendum 3 Results of Isotopic Analysis of Concrete Core Samples Rx Bldg -25Ht, Area 22 :CTMT -25 ft, Canal E Rx Bldg 15 ft. SE Area

!? Core Location #5  ::::::Core Location #6 Core Location #7 C9000101 IFL1 CI L0505-01 C9000101 IFLI C3L0506-01 C90001 IFLI CI L0507-01 Result MDC Used Disribution ::::: Result MDC Used Disribution Result MDC Used Disribuiob.utlo "

pCi/gm */I pCi/gm pCi/gm pCi/gm pCi/gm pCi/gm pCi/gm °AV, i::

pCi/gm pCi/gm o/I H-3 4.90E+00 5.20E+00 5.20E+00 2.60% 6.40E+00 5.10E+00 6.40E+00 4.07% 3. 00E+00 5.20E+00 5.20E+00 15.33%

Cs-137 2.86E+00 .1.70E-01 2.86E+00 1.43% 1.17E+02 2.OOE-01 1.17E+02 74.32% 7.20E-01 1.10E-01 7.20E-01 2.12%

Co-60 1.13E+01 1.00E-01 1.13E+01 5.65% 2.21E+00 1.20E-01 2.21E+00 1.40% 1.40E-01 2,40E-01 2.40E-01 0.71%

Fe-55 1.70E+01 6.70E+01 6.70E+01 33.48%: 1.80E+00 1,20E-01 1.20E+01 7.62% 4.40E-01 1.30E+01 1.30E+01 38.33%

Ni-63 1.07E+02 2.70E+01 1.07E+02 53.47%/ 1.19E+01 1.30E+01 1.30E+01 8.26% 8.30E+00 9.80E+00 9.80E+00 28.89%

Sr-90 2.07E+00 6.40E-01 2.07E+00 1.03%/ 4.60E-01 4.40E-01 4.60E-01 0.29% 4.00E-02 5.70E-01 5.70E-01 1.68%

Pu-238 iii 4.10E-02 6.90E-02 6.90E-02 0.03% : 8.50E-02 2.90E-02 8.50E-02 0.05% 6.00E-03 5.30E-02 5.30E-02 0.16%

Pu-239/240 2.70E-02 5.40E-02 5.40E-02 0.03% I 1.90E-02 4.70E-02 4.70E-02 0.03% : 1.00E-02 2.80E-02 2.80E-02 0.08%

Pu-241 6.80001 2.60E+00 2.60E+00 1.30%  : 1.20E+00 2.80E+00 2.80E+00 1.78% `::i:! -200E-01 2.50E+00 2.50E+00 7.37%

Ann-241 6.00E-02 2.10E-01 2.10E-01 0.10% 1.67E+00 3.OOE-01 1.67E+00 1.06% 0.00E+00 1.00E-01 1.00E-01 0.29%

Cm-245/246 5000-02 390E-1 3.906-01 0.19%/ 1.60E-02 8.70E-02 8.70E-02 0.06%/ 1.00E-01 1.30E-01 1.30E-01 0.38%

U-234 6.40E-01 9.OOE-02 6.40E001 0.32% 7.50E-01 3,OOE-02 7.50E-01 0.48% 7.20E-01 4.00E-02 7.20E-01 2.12%

U-235 i1.10E-01 7.70E-02 1.10E-01 0.05% 1.30E-02 3.40E-02 3.40E-02 0.02% 2.90E-02 7.70E-02 7.70E-02 0.23%

U-238 6.20E-01 4.OOE-02 6.20E-01 0.31% 8.80E-01 3.00E-02 8.80E-01 0.56% 7.80E-01 6.00E-02 7.80E-01 2.30%

2.00E+02 100% 1.57E+02 100% 3.39E+01 100%

CTMT -25 fl. Area 18  ::::::Waste Handling Bldg -1 ft Hot Pipe Tunnel, -12 ft Core Location #9  :::..:Core Location #10 .......Core Location #15 C9000101 IFL1 C310509-01 X::::::C9000101 IFLIC3L0507-01 C9000101 IFLI Cl L051 5-01 Result MDC Used Disributionx: Result MDC Used Disribution Result MDC Used Dis ribut io n ::i:::

pCi/gm pCi/gmn pCi/gmn A/ iPCi/gmn pCi/gm pCi/gmn I/ pCi/gmn pCi/gmn pCi/gm' H-3 1.11E+01 5.10E+00 1.11E+01 28.99% 2.70E+00 5.30E+00 5 .30E+00 0.17% 1.60E+00 5.30E+00 5.30E+00 0.09%

Cs-137 6.10E-01 8.00E-02 6.10E-011 1.59%, 3,15E+03 8.00E-01 3 .15E+03 98.90%, 4.43E+03 1.O0E+00 4.43E+03 76.87%

Co-60 2.32E-01 2.10E-01 2.32E-01 0.61% -3.30E-02 1.10E-01 1 .10E-01 0.00% 2.69E+01 3.00E-01 2.69E+01 0.47%

Fe-55 3.10E+00 1.30E+01 1.30E+01 33,96% 3.30E+00 1.40E+01 1.40E+01 044%, 1.90E+01 1.70E+01 1.90E+01 0.33%

Ni-63 -4.10E+00 110E+01 1.10E+01 28.73% 1 00E+00 1 00E+01 1.00E+01 0.31% 1.61E+02 2.00E+01 1.61E+02 2.79%

Sr-90 X, -3.00E-01 "4.50E-01 4.50E-01 1.18% 1.20E+00 4.80E-02 1.20E+00 0.04%. 1.01E+03 1.00E+00 1.01E+03 17.52%

Pu-238 0.00E+00 0.00E+00 0.00E+00 0.00%, 1.90E-02 4.80E-02 4.802-02 0.00% 6.59E+00 5.00E-02 6.59E+00 0.11%

Pu-239/240 0.00E+00 6.00E-02 6.00E-02 0.16% 1.10E-02 3.00E-02 3.00E-02 0.00% 7.58E+00 3.00E-02 7.58E+00 0.13%

Pu-241 X -2.00-02 3.000-02 3.006-02 008% -5.00E-01 2.90E+00 2

.90E+00 009% 747E+01 2.70E+00 1.30%

7A7E+01 Am-241 0.00E+00 2.00E-01 2.00E-01 0.52%, 6.00E-03 1.00E-01 1.0OE-01 0+00%, 1.30E+01 3.00E-01 1.30E+01 0.23%

Crn-245/246 1.55E-01 9.40E-02 1.55E-01 0.40% 4.40E-02 8.70E-02 8.70E-02 0.00% 6.95E+00 1.60E-01 6.95E+00 0.12%

U-234 7.00E-01 4.00E-02 7.00E-01 1.83% 5.50E-01 8.00E-02. 5.50E-01 0.02% 1.28E+00 7.00E-02 1.28E+00 0.02%

U-235 1.70E-02. 4.70E-02 4.70E-02 0-12% i,6: 5.30E-02 4.80E-02 5.30E-02 0.00% 9.90E-02 9.10E-02 9.10E-02 0.00%

.00E-01 0.02% 9 -100-017.00E-02 U-238 7.00E-01 4.OOE-02 7.00E-01 1.83% 5,00E-01 4.00E-02 5 9.10E-01 0.02%

3.83E+01 100% 3..18E+03 1OA% 5.76E+03 100%

Hot Pipe Tunnel, -12 ft  ::::::Fen House -12 ft

.Core Location #16  ::::::Core Location #17 BALANCE OF PLANT CORE RESULTS C9000101 IFLI C1 LO516-01  ::::::C9000101 IFLI Cl L0517-01 Result MDC Used Disribution:..:.' Result MDC Used Disribution:: MEAN MEAN STD DEV pCi/gm pCi/gm pCi/gm A pCi/gmn pCi/gmn pCi/grn A .. (pCi/gm) (O)

H-3 2.10E+00 . 5.20E+00 5.20E+00 0.44% 6.20E+00 5.30E+00 6.20E+00 15.99% ,6i:i::H-3 6.24E+00 8.46% 10.57%

Cs-137 2.60E+02 4.00E-01 2.60E+02 2204%, 4.10E-01 9.00E-02 4.10E-01 1.06% :x6: Cs-137 9.95E+02 34.79% 41 .45%

Co-60 8.97E+00 2.40E-01 8.97E+00 0.76% -2.70E-02 1.10E-01 1.10E-01 0.28% :::C:::::Co -60 6.26E+00 1.23% 1.83%

Fa-S5 8.20E+00 1.40E+01 1.40E+01 1.19% -2.40E+00 1.40E+01 1.40E+01 36.11% . Fe-55 2.08E+01 18.93% 17.89%

Ni-63 5.00E+01 2.50E+01 5.00E+01 4.24% -3.0OE+00 1.20E+01 1.20E+01 30.95%, Hi 63 4.67E+01 19.71% 18.76%

Sr-90 8.36E+02 2.00E+00 8.36E+02 70.87% O.90E+00 5.00E-01 5.00E-01 1.29%, Sr 90 2.31E+02 11.74% 24 .60%

Pu-238 1.70E-02 5.60E-01 5.60E-01 0.05% 6.00E-03 5.90E-02 5.90E-02 0.15%, Pu 238 9.33E-01 0.07% 0.06%

Pu-239/240 7.30E-02 5.80E-02 7.30E-02 0.01% 1.10E-02 3.10E-02 3.10E-02 0.08%, P -239/240 9.88E-01 0.06% 0 .06%

Pu-241 1.90E+00 2.70E+00 2.70E+00 0.23%, 9.00E-01 3.OOE+00 3.00E+00 7.74%, Pu-241 1.14E+01 2.49% 3 .19%

Arn-241 4.60E-02 6.70E-02 6.70E-02 0.01% 9.00E-03 5.30E-02 5.30E-02 0.14%  :::::::Am-241 1.93E+00 0.29% 0 .35%

Cm-245/246 0.00E+00 1.00E-01 1.002-01 0.01%I 1.20E-01 1.40E-01 1.40E-01 0.36% C rn-2451246 1.00E+00 0.19% 0 .17%

U-234 9.10E-01 6.00E-02 9.10E-01 0.08% 1.14E+00 4.00E-02 1.14E+00 2.94% U-234 8.36E-01 0.98% 1.15%

U-235 6.50E-02 9.30E-02 9.30E-02 0.01%, 5.80E-02 1.10E-01 1.10E-01 0.28% '.::::.U-235 7,69E-02 0.09% 0 .11%

U-238 9.10E-01 6.00E-02 9.10E-01 0.08% 1.02E+00 4.OOE-02 1.02E+00 2.63% U-238 7.90E-01 0.97% 1.10%

1.18E+03 100% 3.88E+01 100% . 100.00%

Attachment A, Page 2 of 3 Addendum 3 Results of Isotopic Analysis of Concrete Core Samples Hot Laboratory 0 ft  ::::::Hot Laboratory 0 ft .......

Hot Laboratory 0 ft

Core Location #11 Core Location #12 Core Location #13 SC90001oo010IFL CL051 1-01  :::i90 01 IFLI CI L0512-01 C90001 01 FLI C3LO51 3-01 Result MDC Used Disribution:::::... Result MDC Used Disribution Result MDC Used Disribution pCi/gm pCi/gm pCi/gm X.. pCi/gm pCi/gm pCi/gm

• pCi/grm pCi/gm pCi/gm  :

H-3 -9.OOE-02 5.20E+00 5.20E+00 0 50% 6.00E-01 5.20E+00 5.20E+00 1+82% 7.20E+00 5.40E+00 7.20E+00 0.37%

C-14 -5.30E-01 8.80E-01 8.80E:01 0.09% 2,16E+01 1.30E+00 2.16E-01 7.57% 4.10E-01 1.20E+00 1.20E+00 0.06%

Cs-137 9.45E+02 5.00E-01 9.45E+02 91.64% 1.13E+02 3.00E-01 1.13E+02 39.60%: 1.71E+03 6.00E-01 1.71E+03 88.43%

Co-so X:X.1.82E+00 1.70E-01 1.82E+00 0.18% 5.79E+00 1.30E-01 5.79E+00 2.03% 2.70E-01 1.70E-01 2.70E-01 0.01%

NI-63 2.50E+01 5.20E+01 5.20E+01 5.04%  : 1.42E+01 1.20E+01 1.42E+01 498/ -3002+00 1.10E+01 11.10E+01 0.57%

Sr-90 1.18E+01 5.00E-01 1.18E+01 1.14% 1.08E+02 5,00E-01 1.08E+02 37.84,% 193E+02 6.00E-01 1.93E+02 9.98%

Pu-238 3.90E-01 5.00E-02 4.80E-01 0.17% 6.50E-01 9.00E-02 6.50E-01 0.03%

3.90E-01 0.04% 4.80E-01 3.00E-02 Pu-239/240 2.05E-01 2.90E-02 2.05E-01 0.02% 6.39E+00 6.00E-02 6.39E+00 2.24% 5.00E-01 4.00E-02 5.00E-01 .0.03%

Pu-241 2.20E+00 2.90E+00 2.90E+00 0.28% 6.80E+00 3.10E+00 6.80E+00 2.38%, 4.70E+00 3.70E+00 4.70E+00 0.24%

Am-241 9.90E+00 9.00E-01 9.90E+00 0.96%/ 1.40E+00 1.90E-01 1.40E+00 0.49%/ 2.90E+00 1.00E+00 2.90E+00 0.15%

Cm-245/246 1.90E-01 8.OOE-02 1.90E-01 0.02% 6.00E-01 1.20E-01 6.00E-01 0.21% 3.80E-01 1.20E-01 3.80E-01 0.02%

U-234 3.60E-01 6.005-02 3.60E-01 0.03%  : 1.04E+00 3,00E-02 1.04E+00 0 36% 9.60E-01 4.00E-02 9.60E-01 0.05%

U-235 9.00E-03 8.90E-02 8.90E-02 0.01% 2.80E-02 3.80E-02 3.80E-02 0.01% 5:102-02 4.60E-02 5.10E-02 0.00%

U-238 4.40E-01 6.00E-02 4.402-01 0.04% 8.50E-01 5.00E-02 8.50E-01 0.30% 8.20E-01 4.00E-02 8.20E-01 0.04%

1.03E+03 100%/ 2.85E+02 100%/ .93E+03 100%

Hot Laboratory 0 ft

,Core Location #14 HOT LAB CORE RESULTS C9000101 IFLI C3L0514-0 Result MDC Used Disribution ii:: MEAN MEAN STD DEV PCt/gm pCi/gm pCi/gm A (pCi/gm) IN, H-3 1.70E+00 5.20E+00 5.20E+00 0.62% H--3 5.70E+00 0.83% 0.67%

C-14 -6.00E-01 1.30E+00 1.30E+00 0.16% C-14 6.25E+00 1.97% 3.73%

Cs-137 7.75E+02 5.00E-01 7.75E+02 92.48%/ Cs-137 8.86E+02 78.04% 25.69%

Co-60 3.12E+00 1.20E-01 3.12E+00 0.37% Co-60 2.75E+00 0.65% 0.93%

Ni-63 1.10E+00 1.50E+01 1.50E+01 1.79%, i::::Ni-63 2.31E+01 3.09% 2.27%

Sr-90 3.30E+01 4.00E-01 3.30E+01 3.94% r:::::::sr-90 8.65E+01 13.23% 16.82%

Pu-238 9.70E-02 4.90E-02 9.70E-02 001% P -238 4.04E-01 0.06% 0.07%

Pu-239/240 5.901-01 3.00E-02 5.90E-01 0.07%  ::::::Pu-239/240 1.92E+00 0.59% 1.10%

Pu-241 7.002-01 2.80E+00 2.80E+00 0.33% Pu -241 4.30E+00 0.81% 1.05%

Ar-241 3.20E-01 3.00E-02 3.20E-01 0.04% Arn-241 3.63E+00 0.41% 0.41%

Cm-245/246 1.07E-01 8.90E-02 1.07E-01 0.01%  ::::::Crm-245/246 3.19E-01 0.07% 0.10%

U-234 8.10E-01 7.00E-02 8.10E-01 0.10% U-234 7.93E-01 0.14% 0.15%

U-235  :: 5.90E-02 7.40E-02 7.40E-02 0.01% 6 -235 6.30E-02 0.01% 0.00%

U-238  : 6.40E-01 6.00E-02 6.40E-01 0.08% U-238 6.88E-01 0.11% 0.12%

8.38E+02 100,% 100.00%

Attachment A, Page 3 of 3 Addendum 3 Results of Isotopic Analysis of Concrete Core Samples ROLB Fuel Vault Core Location #21 C90O01 01 IFLI C1 L0521 -01 Result MDC Used Disribution ..'.

PCif/m pCilgm pCi/gm A Cs-137 1.30E-02 1.00E-01 1.O0E-01 6.67%

Co 60 4.70E-02 1.30E-01 1.30E-01 8 67%

U-234 6.O0E-01 6.00E-02 6.OOE-01 40.00%

U-238 670E-01 3.OOE-02 6.70E-01 44.67%  :'ii' I .50E+00 100%

Final Status Survey Plan for the Plum Brook Reactor Facility Attachment A Radionuclide Distribution Basis for DCGL Determination &

Final Status Survey of the Plum Brook Reactor Facility (PBRF)

Addendum 4 Results of Isotopic Analysis of Surface Soil Samples

Attachment A, Page 1 of 2 Addendum 4 Results of Isotopic Analysis of Surface Soil Samples Sample CS013004-004 Sample CS013004-005 Spill Area 2400303C1 Spill Area 2400303C1 Surface Soils (1st 6") Surface Soils (1st 6")

(pCi/gm) (pCi/gm)

Result MDA Used Result MDA Used AM-241 1.822E-02 4.936E-02 4.94E-02 0.02% AM-241 1.648E-02 1.354E-01 1.35E-01 0.20%

AM243 1.347E-01 1.567E-01 1.57E-01 0.06% AM243 9.944E-02 8.982E-02 9.94E-02 0.14%

C-14 1.377E+00 1.401E+00 1.40E+00 0.58% C-14 1.435E+00 1.051E+00 1.44E+00 2.07%

CM-245 1.659E-01 1.590E-01 1.66E-01 0.07% CM-245 9.517E-02 1.556E-01 1.556E-01 0.22%

CO-60 9.387E-02 2.641E-01 2.641E-01 0.11% CO-60 2.277E-01 . 2.486E-01 2.486E-01 0.36%

CS-137, 2.075E+02 4.241E-01 2.08E+02 85.26% CS-137 5.081E+01 2.355E-01 5.08E+01 73.42%

EU-155 1.052E-01 9.603E-01 9.603E-01 0.39% EU-155 6.000E-01 5.594E-01 6.00E-01 0.87%

H-3 7.497E+00 1.012E+01 1.012E+01 4.16% H-3 1.043E+00 9.755E+00 9.755E+00 14.10%

1-129 8.993E-01 6.558E-01 8.99E-01 0.37% 1-129 3.374E-01 3.883E-01. 3.883E-01 0.56%

NB-94 3.835E-02 1.926E-01 1.926E-01 0.08% NB-94 -3.178E-02 1.259E-01 1.259E-01 0.18%

NI-63 5.589E-01 1.563E+00 1.563E+00 0.64% NI-63 1.970E+00 1.836E+00 1.97E+00 2.85%

PU-238 4.512E-02 1.092E-01 1.092E-01 0.04% PU-238 1.932E-02 5.234E-02 5.234E-02 0.08%

PU-239 1.811E-02 4.909E-02 4.909E-02 0.02% PU-239 9.464E-03 1.165E-01 1.165E-01 0.17%

SR-90 1.990E+01 5.885E-01 1.99E+01 8.17% SR-90 3.200E+00 6.905E-01 3.20E+00 4.62%

U-236 1.795E-02 4.866E-02 4.866E-02 0.02% U-236 1.482E-02 1.121E-01 1.121E-01 0.16%

2.43E+02 100.00% 6.92E+01 100.00%

Sample CS013004-006 Sample CS013004-007 Spill Area 2400303C1 Spill Area 2400303C1 Surface Soils (1st 6") Surface Soils (1st 6")

(pCi/gm) (pCi/gm)

Result MDA Used Result MDA Used AM-241 4.326E-02 3.908E-02 4.33E-02 0.02% AM-241 0.000E+00 6.228E-02 6.23E-02 0.24%

AM243 6.588E-02 8.926E-02 8.93E-02 0.04% AM243 3.134E-02 7.924E-02 7.92E-02 0.31%

C-14 6.130E-01 1.378E+00 1.38E+00 0.67% C-14 1.277E+00 1.379E+00 1.38E+00 5.34%

CM-245 7.752E-02 2.188E-01 2.188E-01 0.11% CM-245 2.589E-02 1.048E-01 1.05E-01 0.41%

CO-60 3.030E-02 2.529E-01 2.529E-01 0.12% CO-60 3.570E-02 1.939E-01 1.939E-01 0.75%

CS-137 1.744E--02 4.606E-01 1.74E+02 84.55% CS-137 9.349E+00 1.823E-01 9.35E+00 36.21%

EU-155 4.207E-01 9.052E-01 9.052E-01 0.44% EU-155 1.401E-01 3.895E-01 3.895E-01 1.51%

H-3 -1,411E-01 9.899E+00 9,899E+00 4.80% H-3 8.951E+00 1.029E+01 1.029E+01 39.87%

1-129. 1.256E+00 6.032E-01 1.26E+00 0.61% 1-129 -9.881E-03 3.125E-01 .3.125E-01 1.21%

NB-94 -1.763E-02 1.544E-01 1.544E-01 0.07% NB-94 -8.472E-03 1.630E-01 1.630E-01 0.63%

NI-63 1.173E+00 1.641E+00 1.641E+00 0.80% NI-63 2.145E+00 1.499E+00 2.14E+00 8.31%

PU-238 8.891E-02 1.074E-01 1.074E-01 0.05% PU-238 -1.245E-02 1.471E-01 1.471E-01 0.57%

PU-239 1.856E-01 6.289E-02 1.86E-01 0.09% PU-239 2.025E-02 1.129E-01 1.129E-01 0.44%

SR-90 1.566E+01 6.545E-01 1.57E+01 7.59% SR-90 1.041E+00 6.891E-01 1.04E+00 4.03%

U-236 2.698E-02 6.822E-02 6.822E-02 0.03% U-236 3.381E-02 4.581E-02 4.581E-02 0.18%

2.06E+02 100.00% 2.58E+01 100.00%

Sample CS013004-008 Sample CS013004-009 Emergency Retention Basin Emergency Retention Basin Surface Soils (1st 6") Surface Soils (1st 6")

(pCi/gm) (pCi/gm)

Result MDA Used Result MDA Used AM-241 1.708E-02 1.403E-01 1.40E-01 0.20% AM-241 6.563E-02 9.722E-02 9.72E-02 0.19%

AM243 5.986E203 1.224E-01 1.22E-01 0.17% AM243 1.550E-01 5.999E-02 1.55E-01 0.30%

C-14 1.121E+00 1.445E+00 1.44E+00 2.02% C-14 7.087E-01 1.331E+00 1.33E+00. 2.59%

CM-245 -3.809E-04 1.406E-01 1.41E-01 0.20% CM-245 1.759E-01 1.039E-01 1.76E-01 0.34%

CO-60 7.355E-01 2.409E-01 7.36E-01 1.03% CO-60 8.647E-01 2.417E-01 8.65E-01 1.68%

CS-137 2.129E+01 2.536E-01 2.13E+01 29.76% CS-137 3.240E+01 2.798E-01 3.24E+01 63.03%

EU-155 1.728E-01 4.628E-01 4.628E-01 0.65% EU-155 3.470E-01 5.541E-01 5.541E-01 1.08%

H-3 4.298E-+01 9.814E+00 4.30E+01 60.08% H-3 3.006E+00 1.054E+01 1.054E+01 20.51%

1-129 1.526E-02 2.837E-01 2.837E-01 0.40% 1-129 -1.874E-02 2.716E-01 2.716E-01 0.53%

NB-94 7.072E-02 2.582E-01 2.582E-01 0.36% NB-94 5.722E-02 2.256E-01 2.256E-01 0.44%

NI-63 2.700E+00 1.510E+00 2.70E+00 3.77% NI-63 3.210E+00 1.496E+00 3.21E+00 6.24%

PU-238 1.485E-02 1.220E-01 1.220E-01 0.17% PU-238 4.426E-02 1.445E-01 1.445E-01 0.28%

PU-239 2.250E-02 6.098E-02 6.098E-02 0.09% PU-239 -4.532E-03 1.233E-01 1.233E-01 0.24%

SR-90 7.010E-01 6.790E-01 7.01E-01 0.98% SR-90 1.161E+00 6.452E-01 1.16E+00 2.26%

U-236 4.074E-02 9.868E-02 9.868E-02 0.14% U-236 1.475E-01 4.995E-02 1.48E-01 0.29%

7.15E+01 100.00% 5.14E+01 100.00%

Attachment A, Page 2 of 2 Addendum 4 Results of Isotopic Analysis of Surface Soil Samples Sample CS013004-010 Sample CS013004-011 Emergency Retention Basin Emergency Retention Basin Surface Soils (1st 6") Surface Soils (1st 6")

(pCi/gm) (pCi/gm)

Result MDA Used  % Result MDA Used  %

AM-241 6.704E-03 1.371E-01 1.37E-01 0.12% AM-241 1.765E-01 1.437E-01 1.77E-01 0.24%

AM243 5.310E-02 1.343E-01 1.34E-01 0.12% AM243 1.039E-01 9.952E-02 1.04E-01 0.14%

C-14 1.210E+00 1.427E+00 1.43E+00 1.24% C-14 1.734E+00 1.524E+00 1.73E+00 2.34%

CM-245 3.384E-02 2.060E-01 2.062-01 0.18% CM-245 1.124E-01 1.527E-01 1.53E-01 0.21%

CO-60 5.665E+00 2.814E-01 5.67E+00 *4.91% CO-60 3.335E+00 2.693E-01 3.34E+00 4.50%

GS-137 5.424E+01 3.064E-01 5.42E+01 47.00% CS-137 3.616E+01 2.683E-01 3.62E+01 48.74%

EU-155 8.057E-02 5.829E-01 5.829E-01 0.51% EU-155 4.595E-02 4.476E-01 4.476E-01 0.60%

H-3 2.845E+01 1.008E+01 2.851+01 24.66% H-3 3.441E+00 9.854E+00 9.854E+00 13.28%

1-129 6.859E-02 2.777E-01 2.777E-01 0.24% 1*-129 8.316E-02 2.687E-01 2.687E-01 0.36%

NB-94 1.336E-01 3.152E-01 3.152E-01 0.27% NB-94 2.923E-01 2.079E-01 2.92E-01 0.39%

NI-63 1.648E+01 1.396E+00 1.65E+01 14.28% NI-63 1.397E+01 1.395E+00 1.40E+01 18.83%

PU-238 9.437E-02 1.140E-01 1.140E-01 0.10% PU-238 7.927E-02 7.159E-02 7.93E-02 0.11%

PU-239 9.854E-02 6.676E-02 9.85E-02 0.09% PU-239 1.321E-01 7.159E-02 1.32E-01 0.18%

SR-90 7.192E+00 6.492E-01 7.19E+00 6.23% SR-90 7.437E+00 6.639E-01 7,44E+00 10.03%

U-236 4.707E-02 7.696E-02 7.696E-02 "0.07% U-236 4.962E-02 4.482E-02 4.96E-02 0.07%

1.15E+02 100.00% 7.42E+01 100.00%

STANDARD MEAN DEVIATION AM-241 0.15% 0.09%

AM243 0.16% 0.10%

C-14 C 2.11% 1.51%

CM-245 0.22% 0.11%

CO-60 1.68% 1.94%

CS-137 58.50% 21.34%

EU-155 0.76% 0.38%

H-3 22.68% 19.00%

1-129 0.53% 0.30%

NB-94 0.30% 0.19%

NI-63 6.96% 6.56%

PU-238 0.17% 0.18%

PU-239 0.16% 0.13%

SR-90 5.49% 3.08%

U-236 0.12% 0.09%

Final Status Survey Plan for the Plum Brook Reactor Facility Attachment B Approach and Basis for Development of Site-Specific Derived Concentration Guideline Levels (DCGL)

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 1.0 Purpose Document the approach, methodology and bases for the establishment of site-specific Derived Concentration Guideline Levels (DCGL) and to document the actual DCGL(s) and area factors to be used during the performance of Final Status Survey of the Plum Brook Reactor Facility (PBRF).

2.0 References 2.1 Title 10, Code of Federal Regulations, Part 20 "Standards for Protection Against Radiation" 2.2 Draft Regulatory Guide DG-4006, "Demonstrating Compliance with the Radiological Criteria for License Termination" (NRC 1998a) 2.3 NUREG-1549, "Decision Methods for Dose Assessment to Comply with Radiological Criteria for License Termination" (NRC 1998b) 2.4 PBRF Decommissioning Plan 2.5 NUREG-1757 Vol. 2, "Consolidated NMSS Decommissioning Guidance, Characterization, Survey, and Determination of Radiological Criteria" (NRC 2003) 2.6 NUREG-5512, Vol. 3, "Parameter Analysis" (NRC 1999) 2.7 NUREG/CR-6697, "Development of Probabilistic RESRAD 6.0 and RESRAD-BUILD 3.0 Computer Codes" (NRC 2000) 2.8 Federal Guidance Report No. 11 (FGR 11), "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion and Ingestion" 2.9 Federal Guidance Report No. 12 (FGR 12), "External Exposure to Radionuclides in Air, Water and Soil" 2.10. NUREG/CR-6377 (PNL-11408), Krupka, K.M., and R.J. Seme. 1998. "Effects on Radionuclide Conecentrations by Cement/Groundwater Interactions in Support of Performance Assessment of Low-Level Radioactive Waste Disposal Facilities" 2.11 Mattigod, S.V., et. al., 2002. "Radionuclide Desorption and Leaching Tests for Concrete Cores from Haddam Neck Nuclear Plant Facilities. Final Letter Report, Battelle, Pacific Northwest Laboratory" 2.12 Fuhrmann, M., Sullivan, T, 1999. "Leaching and Sorption of Radionuclides:.

Structural Concrete from Maine Yankee Nuclear Power Station. Final Letter Report, Brookhaven National Laboratory" 2.13 Clapp, R.B., and Hornberger, G.M., 1978. "Empirical Equations for Some Soil Hydraulic Properties", Water Resources Research 14:601-604.

2.14 Fetter, C.W., 1988. Applied Hydrology, Merrill Publishing Company, Columbus OH.

2.15 Freze, R.A. and Cherry, J.A., 1981. Groundwater, Prentice-Hall, Inc. Englewood Cliffs, NJ.

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Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 2.16 Gray, D.M., 1970. Handbook on the Principles of Hydrology, Water Information Center, Inc. Port Washington, NY.

2.17 McWorter, D.B. and Sunada, D.K. 1977. Groundwater Hydrology and Hydraulics, Water Resources Publication, Fort Collins, CO.

2.18 National Climactic Data Center, NCDC, http://www.ncdc.noaa.gov/oa/ncdc.html.

2.19 Teledyne Isotopes, 1987. "An Evaluation of the Plum Brook Reactor Facility and Documentation of Existing Conditions, Volume 3: Physical Characterization of Radioactive/Contaminated Areas of the PBRF."

2.20 US Army Corps of Engineers, 2004. "Hydrogeologic Report Plum Brook Reactor Facility, Sandusky, OH."

2.21 US Department of Energy, 2001. User's Manual for RESRAD Version 6. Office of Scientific and Technical Information, Oak Ridge, TN.

3.0 DCGL Approach Consistent with 10 CFR Part 20, decommissioning means reducing residual radioactivity to a level that permits termination of the license and release of the site for unrestricted use.

The PBRF license would be terminated after NASA demonstrates that the site meets the criteria for decommissioning specified in 10 CFR Part 20, Subpart E, "Radiological Criteria for License Termination." The two radiological criteria for unrestricted use specified in 10 CFR 20.1402 are: (1) the TEDE from residual radioactivity that is distinguishable from background radiation must not be greater than 25 mrem/yr to the Average Member of the Critical Group (AMCG) and (2) residual radioactivity levels must be ALARA.

According to NUREG-1549, "Decision Methods for Dose Assessment to Comply with Radiological Criteria for License Termination" (NRC 1998b), a licensee can demonstrate compliance with the dose criterion either by using a generic screening model or by using site-specific analyses. As recommended by Draft Regulatory Guide DG-4006, "Demonstrating Compliance with the Radiological Criteria for License Termination" (NRC 1998a), this attachment presents the methodology and approach used for the development of site-specific DCGLs. This document also presents the estimated DCGLs for surface soils, building surfaces, and subsurface structures at the PBRF. The DCGLs will be used during the final radiation survey to demonstrate compliance with the two unrestricted use criteria previously specified.

The Decommissioning Plan for the PBRF presents the proposed methodology for demonstrating that residual contamination levels are ALARA. The methodology follows the guidance in DG-4006 and involves comparing the costs and benefits of postulated decommissioning actions. The Decommissioning Plan also presents options for using DCGLs for specific portions of the PBRF and the timing of the final status survey, including the identification of the criteria that will be used for selecting DCGLs for specific portions of the PBRF.

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Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 4.0 DCGL Methodology This section presents the methodology used in the calculation of DCGLs (the level of residual contamination that would produce a TEDE of 25 mrem/yr to the AMCG).

DCGLs were estimated using existing characterization data. DCGL estimates are based on the analysis of scenarios that could reasonably be expected to occur if a site is released for unrestricted use. A scenario is defined as a set of release modes, receptor metabolic and behavioral characteristics, environmental transport pathways, and exposure modes that result in dose to an individual or population. The dose analysis performed assumes the PBRF site is released for unrestricted use and evaluates the case of members of the public using the site. In actuality, NASA has no plans to sell this property after license termination, so realistic receptors would be members of the public located offsite and NASA employees working onsite after license termination. Thus, unrestricted use of the PBRF site is conservative and bounds the realistically expected scenario.

NRC has published guidance on methods for dose analysis supporting license termination under 10 CFR Part 20 (NUREG/CR-5512 [Kennedy and Strenge 1992], DG-4006, NUREG- 1549, and NUREG- 1757 Vol. 2, "Consolidated NMSS Decommissioning Guidance, Characterization, Survey, and Determination of Radiological Criteria" [NRC 2003]). The guidance allows using either generic screening or site-specific dose assessment in the decision framework. Under the generic screening approach, NRC has identified pathways, scenarios, models, and model parameter values, and has provided analysis results in the form of levels of contamination consistent with the 10 CFR Part 20, Subpart E, dose criteria. The pathways and scenarios constitute the residential farmer and building reuse scenarios. The NRC generic screening analysis of the residential farmer scenario is based on the assumption that all contamination has been distributed into the upper 15 cm (6 in.) of soil. Among the options presented for site-specific analysis is the use of site-specific parameter values and existing models other than the generic NRC model. The guidance recommends that the licensee provide information supporting use of site-specific data or models, other than the generic NRC model.

Because the generic screening model addresses subsurface contamination through assumed redistribution to surface soil, it is very conservative for the case of residual contamination of subsurface structures. To provide a consistent level of analysis for the contamination of surface soil, building surface, and subsurface structures, a site-specific analysis approach was used for the PBRF.

The dose model selected for analyzing residual soil contamination, RESRAD Version 6.0 (Yu et al. 2000), has been formally accepted by the NRC for analysis of residential farmer scenarios. The dose model selected for analyzing residual building surface contamination, RESRAD-BUILD Version 3.22 (Yu et al. 2000), addresses pathways discussed in NRC guidance and is widely used by the U.S. Department of Energy (DOE) and the U.S.

Department of Defense when analyzing building reuse scenarios. These two site-specific models include all pathways and exposure modes included in the NRC generic screening models. No conditions outside those incorporated in the site-specific models are expected to occur at the PBRF. The residential farmer scenario presumes that both the residence and garden are located on contaminated soil. Thus, the site-specific modeling is appropriate for assessing doses because of contamination of soil and building surfaces.

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Survey Plan Revision 0 Facility Reactor Facility Plum Brook Reactor Final Status Final Status Survey Plan Revision 0 The RESRAD Version 6.21 (Yu et al. 2002) model was used to analyze residual subsurface structure contamination to allow a sensitivity analysis to be conducted for the concrete Kd values. In this case, concrete Kd is the most sensitive parameter. No conditions outside those incorporated in the site-specific model are expected to occur at the PBRF, and no pathways have been eliminated. Thus, the site-specific model is appropriate for assessing dose because of residual contamination associated with subsurface structures.

Using existing characterization information, site-specific pathway scenarios were used to calculate DCGLs and to develop estimates of dose over time for the AMCG at the PBRF.

The site-specific DCGLs were developed by considering PBRF soils and hydrology.

5.0 DCGL Bases 5.1 Residual Contamination in Surface Soils NRC regulatory guidance (DG-4006) recommends analysis of a residential farmer scenario as the basis for the DCGLs for residual contamination in site-wide surface soil. In the residential farmer scenario, an individual could contact residual contamination by establishing a home and garden on contaminated soil or by using groundwater that comes in contact with the residual contamination. The primary release modes are partitioning of contaminants from soil into infiltrating water and resuspension by wind. The environmental transport pathways include ground water transport; translocation into plants, animals, and fish; and atmospheric dispersion. Exposure modes include ingestion of water, crops, animal products, and fish; direct external exposure from the ground; inhalation of airborne material; and inadvertent ingestion of soil.

NUREG-1549 identifies DCGLs (i.e., soil concentrations that would result in a TEDE of 25 mrem/yr to the AMCG) for a generic, screening-level exposure scenario. More realistic site-specific DCGLs for the PBRF were developed using RESRAD Version 6.21, a computer code developed by DOE and commonly used to estimate residual contamination in soils. The site-specific DCGLs were calculated based on many variables that characterize the receptors; environmental pathways, and modes of exposure. The estimates of physical, behavioral, and metabolic parameter values were developed from either site measurements or literature review.

In support of the PBRF project and resident farmer DCGL development, available hydrogeologic information was consolidated in a report by the US Army Corps of Engineers entitled "Hydrogeological Report Plum Brook Reactor Facility Sandusky, Ohio". This report summarized available information about the geologic and hydrogeologic conditions that exist both regionally and within the PBRF. The following excerpts from the hydrogeologic report were used to develop site-specific RESRAD inputs as shown in Tables B-1 through B-4.

Note that surface soil dose is insensitive to the hydrogeological parameters but site specific values are provided for completeness.

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Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Bedrock that subcrops at the PBRF consists of Devonian Delaware Limestone and the overlying Devonian Plum Brook Shale Member of the Olentangy Shale. The majority of the site is underlain by Olentangy Shale, with the subcrop of DelawareLimestone limited to the northern and southeasternportion of the PBRF. Underlying the DelawareLimestone is a thick section ofpredominantly carbonate bedrock consisting of the Columbus Limestone and the DetroitRiver Formation.

The bedrock surface at the PBS generallyslopes toward the north, although the PBS is located in an area where an apparent bowl-shapedfeature is present. In-filling of the bedrock depression has resulted in a similar thickening of unconsolidateddeposits at the PBRF.

Unconsolidateddeposits consist mostly ofglacialtill that occurs as a thin veneer over the bedrock surface. The thickness of these materials at the PBRF is typically about 25ft. Native surficialdeposits at the PBRF have been extensively disturbed. Boringlogs for the PBRFtest borings and monitoringwells show that the unconsolidateddeposits consistpredominantly of cohesive soil, with some relatively thin, discontinuousgranularunits interbedded. The pro-glaciallacustrine depositionalenvironment in which these depositsformed tends to homogenize the deposits through wave reworking. While localized lenses of granularmaterialsdo exist, it does not appearthat these lenses are continuous across the site, and these units should not be consideredto be indicative of the typical site stratigraphy.

The United States DepartmentofAgriculture,NaturalResources Conservation Service (2002) has recently revised the Soil Survey of Erie County, Ohio. The soil within the 27-acre PBRF is mapped as Udorthents, disturbedsoil that has been affected by construction activities. Review of the soils surroundingthe PBRFprovides insight regardingwhat was likely presentpriorto disturbance. The soils in the immediate vicinity of the PBRFconsist of Colwood Loam, 0-1 percent slopes (CmA); Elnora loamy fine sand, 0-4 percent slopes.

(EnA); Gilfordfine sandy loam, 0-1 percent slopes (GdA); Oakville loamy fine sand, 0-6 percent slopes (Oab), and Udorthents, loamy, 0-6 percent slopes (UdB). These undisturbedsoils are composed of loam, loamy fine sand,fine sandy loam, and loamy fine sand, respectively.

The surficial soil at the PBRF has been extensively disturbed. In addition, the entire site was reportedly regradedto promote surface water to flow to the southeast corner of the PBRF. These excavation and gradingactivities have resulted in the entire PBRF being mapped by NaturalResources Conservation Service as Udorthents.

Photographsduring construction show stockpiled soil that was B-5

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 presumably used to backfill around the structures and to support the regradingactivity. Therefore, it is likely that the surficialmaterials at the PBRF are a mixture of variablethickness composed of the entire section of unconsolidateddeposits, which at depth predominantly consists of cohesive soils.

Hydraulic conductivityfor the mixed unconsolidateddeposits ranges from 49 to 270 meters/year (m/yr), gradientrangesfrom 0. 005 to

0. 006ft/fi, and the porosity is expected to rangefrom about 0.35 to

0. 70 (Freeze and Cherry, 1979). The hydraulic conductivity of the DelawareLimestone rangesfrom 3 to 188 m/yr, and the gradient rangesfrom 0. 002 to 0. 003 ft/ft. The site-specific effective porosity of the DelawareLimestone has not been established. Therefore, a published value for limestone must be used to calculategroundwater flow velocity: 0.01 to 0.3 (Fetter,1988).

All the other parameters used in the dose analysis were generic screening values or a most conservative value was chosen. These parameters were estimated based on NRC and DOE guidance for generic screening (i.e., the NUREG-1549 analysis and the RESRAD computer code) and are considered to be prudently conservative. Using a water table drop rate of 0 m/yr is also prudently conservative because it minimizes travel time through the unsaturated zone for the observed thickness of the zone. Using observed values for other site-specific parameters is reasonable because it is consistent with existing conditions and does not introduce a judgment bias that may be conservative or non-conservative depending on the intricacies of pathway analysis for individualradionuclides.

Wherever possible, NRC-recommended parameter values were used unless site-specific data were available. In the absence of either site-specific and NRC-recommended values, RESRAD default values were used. The parameter values used in the analysis of the PBRF residential farmer scenario are presented in Tables B-1 through B-8. The generic values used for the most dose-sensitive parameter (i.e., the distribution coefficient), are relatively high. This results in retaining radionuclides in soil rather than removing them by groundwater, which produces conservative dose estimates through the external exposure pathway for the radionuclides controlling dose at the PBRF. The radiation dose limit and time for calculations are 25 mrem/yr and 1000 years, respectively, as specified in 10 CFR 20.1401 and 20.1402.

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Plum Brook.Reactor Facility FinalStatus Survey Plan Revision 0 Table B-1. Residential Farmer Scenario: Contaminated Zone Parameters Parameter Parameter Value Source Area of contaminated zone 109100 m2 for controlled Teledyne Isotopes, 1987.

area including:

1102400 m2 for PBRF

• 6700 m2 for Pentolite Ditch Thickness of contaminated zone 1m Conservative thickness to maximize dose Length parallel to aquifer flow 365 m Teledyne Isotopes, 1987.

Radiation dose limit 25 mrem/yr 10 CFR 20.1402 Time since placement of material 0 years Distribution coefficients available Time for calculations Through 1000 years 10 CFR 20.1402 Table B-2. Resident Farmer Scenario: Cover and Contaminated Zone Hydrologic Data Parameter Parameter Value Source Density of contaminated zone 1.522 g/cm3 Hydrogeologic Report PBRF, 2004.

Average value used unconsolidateddeposits.

Contaminated zone erosion rate 0.001 m/yr RESRAD Contaminated zone total porosity 0.45 Groundwater Hydrology and Hydraulics, 1977.

Contaminated zone field capacity 0.20 RESRAD Contaminated zone hydraulic 270 rn/yr Hydrogeologic Report PBRF, 2004. Most conductivity conservative value unconsolidateddeposits.

Contaminated zone b parameter 7.12 "Empirical Equations for Some Soil Hydraulic Properties", 1978. Sandy clay loam Evapotranspiration coefficient 0.5 RESRAD Precipitation 0.86 m/yr National Climactic Data Center - Ohio Irrigation 1.04 mr/yr NUREG 1549 Irrigation mode Overhead RESRAD Runoff coefficient 0.3 Handbook on the Principles of Hydrology, 1970.

Watershed area for stream or pond 1 x 106mM RESRAD B-7

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Table B-3. Residential Farmer Scenario: Saturated Zone Hydrologic Data Parameter Parameter Value Source Density of saturated zone 1.522 g/cm 3 Hydrogeologic Report PBRF, 2004.

Average value used unconsolidateddeposits.

Saturated zone total porosity 0.45 Groundwater Hydrology and Hydraulics, 1977.

Saturated zone effective porosity 0.20 Groundwater Hydrology and Hydraulics, 1977.

Saturated zone hydraulic 270 mn/yr Hydrogeologic Report PBRF, 2004. Most conductivity conservative value unconsolidated deposits.

Saturated zone hydraulic gradient 0.005 m/m Hydrogeologic Report PBRF, 2004.

Saturated zone b parameter NA Water table drop rate 0.0 m/yr Most conservative - minimizes transport time Well pump intake depth 8 (m below water table) Hydrogeologic Report PBRF, 2004 Mixing model Nondispersion RESRAD Individual use of groundwater 118 m3/yr NUREG 1549 Table B-4. Residential Farmer Scenario: Uncontaminated and Unsaturated Zone Hydrologic Data Parameter Parameter Value Source Number of unsaturated zone strata 1 Hydrogeologic Report PBRF, 2004.

Unsaturated zone thickness 3.0 m Hydrogeologic Report PBRF, 2004.

3 Unsaturated zone soil density 1.522 g/cm Hydrogeologic Report PBRF, 2004.

Average value used unconsolidateddeposits.

Unsaturated zone total porosity 0.45 Groundwater Hydrology and Hydraulics, 1977.

Unsaturated zone effective 0.20 Groundwater Hydrology and Hydraulics, porosity 1977.

Unsaturated zone b parameter 7.12 "Empirical Equations for Some Soil Hydraulic Properties", 1978. Sandy clay loam Unsaturated zone hydraulic 270 rn/yr Hydrogeologic Report PBRF, 2004. Most' conductivity conservative value unconsolidateddeposits.

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Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Table B-5. Residential Farmer Scenario: Distribution Coefficients Element Parameter Value*

(mL/g)

C 21 Fe 891 Co 1,000 Ni 37 Sr 32 Tc 7 Cs 447 Eu 955

• Source: NUREG-1549.

Table B-6. Residential Farmer Scenario: Dust Inhalation and External Gamma Parameters Parameter Parameter Value Source Inhalation rate 8400 m3/yr NUREG-1549a 3

Mass loading for inhalation 6 x 10.6 g/m NIJREG-1549' Dilution length for airborne dust 3m RESRADc Exposure duration 365.25 days NUREG-1549 Shielding factor, inhalation 0.40 RESRAD Shielding factor, external gamma 0.47 NUREG- 1549d Fraction of time indoors, onsite 0.66 NUREG- 1549 Fraction of time outdoors, onsite 0.11 NUREG-1549 Shape factor, external gamma 1 RESRAD Fraction of annular areas 0 RESRAD

a. NUREG-1549.

b. Activity and time average of NUJREG-1549 values.

c. RESRAD.

d. Sum of the product of the means for the fraction of time and shielding factor for outdoor and indoor exposure.

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Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 Table B-7. Residential Farmer Scenario: Ingestion Pathway, Data Dietary Parameters Parameter Parameter Value Source Fruit, vegetable, and grain consumption 78 kg/yr NUREG-1549a'b rate Leafy vegetable consumption rate 15 kg/yr NUREG-1549 Milk consumption 118 L/yr NUREG- 1549 Meat and poultry consumption 52 kg/yr NUREG-1549c Fish consumption 16 kg/yr NUREG-1549 Soil ingestion rate 18.3 g/yr NUIREG-1549 Drinking water intake 478 L/yr NUREG-1549 Fraction of drinking water from site. 1 RESRADd Fraction of aquatic load from site 0.5 RESRAD

a. Sum of individual means for other vegetables, fruit, and grain.

b. NUREG-1549.

c. Sum of individual means for meat and poultry.

d. RESRAD.

Table B-8. Residential Farmer Scenario: Ingestion Pathway Data, Nondietary Parameters Parameter Parameter Value Source Livestock fodder intake for meat 8.5 kg/day NUIREG- 1549a Livestock fodder intake for milk 17 kg/day NUREG- 154 9 b Livestock water intake for meat 50 L/day RESRADc Livestock water intake for milk 160 L/day RESRAD Livestock soil intake 0.5 kg/day RESRAD Mass loading for foliar deposition 4 x 10-4 g/m 3 NUREG-1 54 9 d Depth of soil mixing layer: 0.15 m NUREG-1549 Depth of roots 0.9 m RESRAD Drinking water fraction from groundwater 1 RESRAD Livestock water fraction from groundwater 1 NUREG-1549 Irrigation fraction from groundwater 1 RESRAD

a. NUREG-1549.

b. Sum of individual medians for forage, hay, and grain.

c. RESRAD.

d. Value for gardening.

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Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 The parameters identified in Tables B-I through B-8 were used in the RESRAD code to determine the corresponding radionuclides concentrations in soil (i.e., DCGLs). Table B-9 presents the DCGLs for the radionuclides that may present at PBRF.

Table B-9. DCGLs for Surface Soils Site-Specific DCGLa Radionuclide (pCi/g)

Co-60 3.8 Cs-137 14.7 Eu-152 8.8 Eu-154 8.2 Fe-55 7.1 E+04 Ni-59 1.4 E+04 Ni-63 5.4 E+03 Sr-90 5.4

a. Calculated by RESRAD using the parameters specified in Tables B-1 through B-8.

5.2 Residual Contamination in Buildings The PBRF buildings that were largely uncontaminated by past operations may be demolished during decommissioning and may be used as clean, hard fill to backfill the subsurface structures. The PBRF buildings having residual contamination may be decontaminated, surveyed, and demolished. If used as a source of fill material, the FSS survey will determine that the buildings meet the criteria for unrestricted release. After a survey of the subsurface structures demonstrates that these areas are suitable for free release, the demolition debris will be placed in the below grade cavities of the buildings. The building reuse scenario was used to develop DCGLs supporting release of PBRF buildings, such as the Reactor Office and Laboratory Building (Building 1141), which is known to have low levels of residual contamination.

In the building reuse scenario, residual contamination is assumed to be located on' building surfaces (i.e., walls, floors, and ceilings). Exposure modes include direct external exposure, inhalation, and ingestion.

To analyze residual contamination in PBRF buildings, a site-specific analysis was conducted using RESRAD-BUILD 3.22. The RESRAD-BUILD parameters were selected in accordance with the methods recommended in NUREG- 1757 Vol. 2.

The parameters were categorized as behavioral, metabolic, or physical. The B-11

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 behavioral and metabolic parameters selected were the default values from NUREG-5512, Vol. 3 or the NRC screening code DandD 2.1.0. Because of differences between the RIESRAD-BUILD and NUREG-5512 dose assessment models, some parameters required by the RESRAD-BUILD code are not provided in NUREG-5512 Vol. 3. The RESRAD-BUILD specific parameters were derived from NUREG/CR-6697. The average or most likely value was selected to represent the average member of the critical group.

Physical parameters that were not site specific, such as the assumed room dimensions, or selected to be consistent with NUREG/CR-5512 model assumptions (such as evaluating one room for the building occupancy scenario) were selected to be conservative. Physical parameters that did not have a clearly conservative value were evaluated using the probabilistic module of RESRAD-BUILD to determine whether the dose was sensitive to the parameter. The only parameter requiring a sensitivity analysis was the "Lifetime or Time of Source Removal" (Source Lifetime). This represents the time over which surface contamination is removed.

The default parameter distribution function (PDF) from NUREG/CR-6697, Attachment C, Section 8.8, was used for the sensitivity analysis of the Source Lifetime parameter. The PDF was a triangular distribution defined by a 1000 day minimum, 100,000 day maximum, and 10,000 day most likely value. The RESRAD-BUILD output for the Partial Rank Correlation Coefficient (PRCC) was used to evaluate the sensitivity of dose to the parameter. The PRCC is one of the recommended methods in NUREG-1757 Section 1.7.5. In addition, precedence has been set for the use of PRCC in other previously submitted and approved decommissioning plans. If the PRCC exceeded the absolute value of 0.10, then the dose was considered sensitive to the parameter and either the 2 5 th or 75th quantile of the PDF was selected as the deterministic parameter. The 25th quantile was used if the dose was negatively correlated, i.e., dose increased as the parameter decreased.

The 75' quantile was used if the dose was positively correlated, i.e., dose increased as the parameter increased. A negative correlation was indicated by a negative PRCC result and a positive correlation by a positive PRCC. The 25tf quantile for source lifetime was 18,200 days and the 75th quantile was 52,700 days. All of the nuclides were sensitive to the Source Lifetime parameter. Table B-10 lists the nuclides according to whether the dose was positively or negatively correlated. In general, a nuclide was positively correlated if the primary dose pathway was direct radiation and negatively correlated if the direct radiation dose was not significant.

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Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 Table B-10. Results of Sensitivity Analysis for Source Lifetime Parameter Positive Negative PRCC PRCC 7 5 th Quantile 2 5 Quantile th C-14 Fe-55 Co-60 Ni-59 Cs-137 Ni-63 Eu-152 Sr-90 Eu-154 Tc-99 1-129 H-3 Nb-94 Pu-241 Pu-238 Cm-243 Am-241 Eu-155 Pu-239 U-234 U-235 U-236 U-238 Table B-Il lists all of the parameters used in the site-specific RESRAD-BUILD analysis and provides the reference and justification as appropriate. The room dimensions of 15 m [49 ft] long, 5 m [16 ft] wide, and 3 m [10 ft] high represent the largest room expected to have residual contamination and is considered prudently conservative since it maximizes direct radiation from the floor and the largest wall because of the relative narrowness of the room. The bases provided in Table B-1 1 for the parameter selections are self-explanatory with one exception, i.e., Direct Ingestion.

The Direct Ingestion parameter of 4.07E-07 hr - was selected to ensure consistency with the NRC recommended Effective Transfer Rate for Ingestion provided in NUREG/CR-5512 Vol. 3, Section 5.2.3. The recommended Effective Transfer Rate is 1.1E-04 m2ih and applies to loose source surface contamination. RESRAD-BUILD does not have a direct analogy to the Effective Transfer Rate from the source. However, the Direct Ingestion parameter can be modified to result in the same ingestion intake as would occur using the NUREG/CR-5512 model and the Effective Transfer rate. This is accomplished by dividing the 1.1E-04 m2/h value by the total source area for the room, i.e., 270 in 2 . RESRAD-BUILD calculates the ingestion intake for each of the six sources (4 walls, floor, and ceiling) by calculating the total inventory (activity/area multiplied by the area). of each source and then multiplying by the Direct Ingestion parameter. The 4.07E-07 hf1 B-13

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 parameter will result in an ingestion rate equal to 1. 1E-04 m 2/hr when the results of all six sources are summed.

The RESRAD-BUILD dose assessment results are contained in three reports that are available for review as needed. The first contains the nuclides requiring a Source Lifetime parameter of 52,700 days, the second those requiring a Source Lifetime of 18,200 days, and a third containing the results for H-3. The DCGLs were calculated by dividing the 25 mrem/yr criteria by the nuclide specific unitized dose factors. The term unitized dose factor was used because the source term was 1 dpm/100 cm 2 for each radionuclide.

Table B-12 provides the DCGLs for the Building Reuse scenario.

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Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Table B-1I. Building Reuse Scenario: Parameter Values No Parameter (unit) Typea Value/Distribution Source Comments/Justification 1 Exposure duration (days) B 365.25 NUREG/CR-5512, V3 S5.2.1 Accounts for leap year 2 Indoor fraction B 0.267 NUREG/CR-5512, V3 S5.2.2 Equal to 97.5 day/year, or 45 hour/week; average value 3 Evaluation time (year) P 0 4 Number of rooms P 1 NUREG/CR-5512, V1 Building occupancy scenario assumes only one contaminated room 5 Deposition velocity (m/sec) P 2.7E-06 NUREG/CR-6697, C, 7.5 Minimum value selected to maximize airborne concentration 6 Resuspension Rate (sec') P 1.4E-05 NUREG/CR-6697, C, 7.2 Maximum value selected to maximize airborne concentration 7 Air exchange rate for building and room (hr 1 ) B 0.8 NUREG/CR-6697, C, 7.4 Most likely value 2

8 Room area (M ) P 75 Site-specific model Largest unit expected at PBRF 9 Room height (m) P 3 Site-specific model Largest unit expected at PBRF 10 Time fraction B NUREG/CR-5512, V1 Building occupancy scenario assumes all time is spent at one receptor 1.0 location 3

11 Breathing rate (m /day) B 33.6 NUREG/CR-5512, V3 S5.3 Equal to 1.4 m 3/hr which is median value and DandD V2.1 default 12 Indirect ingestion rate (m2/hr) B 0.OOE+00 NUREG/CR-5512, V3 S5.2.3 Indirect ingestion not modeled in building occupancy scenario 13 Receptor location: x,y,z (m) B 7.5, 2.5, 1 Site-specific model Occupant located at center of room area with exposure at Im height 14 Shielding thickness (cm) P 0 Site-specific model No shielding is assumed 15 Shielding density (g/cc) P 0 Site-specific model No shielding is assumed 16 Shielding material P None Site-specific model No shielding is assumed 17 Number of sources. P 6 Site-specific model All room surfaces assumed to be equally and uniformly contaminated RESRAD-BUILD 18 External dose conversion factor (mrem/yr)/(pCi/m 2) FGR 12 Mdefaults Air submersion dose conversion factor M RESRAD-BUILD FGR 12 19 ((mremfyr)/(pCi/m 3 ) defaults 20 Inhalation dose conversion factors (mrem/pCi) M RESRAD-BUILD FGR 11 defaults 21 Ingestion dose conversion factors (mrem/pCi) RESRAD-BUILD defaults FGR 11 22 P Area Site-specific model 23 Direction P X Site-specific model 24 Location of center of source: x,y,z (m) P 0,2.5,1.5 Site-specific model 25 Area (M2 ) P 15 Site-specific model Wall area is 5 m by 3 m 26 Air fraction for H-3 B 1.00 NUREG/CR-6697, C, 8.6 Recommended value for gaseous form of H-3 Air fraction (for all radionuclides except H-3) B 0.07 NUREG/CR-6697, C, 8.6 Upper bound for contaminated noncombustible solids 2 2

27 Direct ingestion (hr 1 ) B 4.07E-07 NUREG/CR-5512, V3 S5.2.3 Equal to 1.1 E-4 m /hr divided by total source area of 270 M 28 Removable fraction P 0.1 NUREG-1757, V2 SI.6.3.1 Default parameter value for loose fraction from DandD 2.1 29 Lifetime or time for source removal (days) P Nuclide Specific NUREG/CR-6697, C, 8.8 30 Radionuclide Concentration (pCi/m 2 ) P 45 Site-specific model Initial concentration is unit sourceof 1 dpm/1 00 cm 2 to allow for B-15

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 No Parameter (unit) Typea Value/Distribution Source Comments/Justification proportional DCGL calculation 31 P Area Site-specific model 32 Direction P X Site-specific model 33 Location of center of source: x,y,z (m) P 15,2.5,1.5 Site-specific model 34 Area (Mi) P 15 Site-specific model Wall is 5 m by 3 m 35 Air fraction for H-3 B 1.00 NUREG/CR-6697, C, 8.6 Recommended value for gaseous form of H-3 Air fraction (for all radionuclides except H-3) B 0.07 NUREG/CR-6697, C, 8.6 Upper bound for contaminated noncombustible solids 2 2 36 Direct ingestion (hr 1 ) B 4.07E-07 NUREG/CR-5512, V3 S5.2.3 Equal to 1.1E-4 m /hr divided by total source area of 270 M 37 Removable fraction P 0.1 NUREG-1757, V2 SI.6.3.1 Default parameter value for loose fraction from DandD 2.1 38 Lifetime or time for source removal (days) P Nuclide Specific NUREG/CR-6697, C, 8.8 39 Radionuclide Concentration (pCi/m 2 ) P 45 Site-specific model Initial concentration is unit source to allow for proportional DCGL calculation 40 Type P Area Site-specific model 41 Direction P Y Site-specific model 42 Location of center of source: x,y,z (m) P 7.5, 0, 1.5 Site-specific model 43 Area (Mi) P 45 Site-specific model Wall area is 15 m by 3 m 44 Air fraction for H-3 B 1.00 NUREG/CR-6697, C, 8.6 Recommended value for gaseous form of H-3 Air fraction (for all radionuclides except H-3) B 0.07 NUREG/CR-6697, C, 8.6 Upper bound for contaminated noncombustible solids 2 2 45 Direct ingestion (hr 1 ) B 4.07E-07 NUREG/CR-5512, V3 S5.2.3 Equal to 1.1E-4 m /hr divided by total source area of 270 m 46 Removable fraction P 0.1 NUREG-1757, V2 SI.6.3.1 Default parameter value for loose fraction from DandD 2.1 47 Lifetime or time for source removal (days) P Nuclide Specific NUREG/CR-6697, C, 8.8 48 Radionuclide Concentration (pCi/m2 ) P Initial concentration is unit source to allow for proportional DCGL 45 Site-specific model calculation Site-specific model 49 Type P Area Site-specific model 50 Direction P Y 5 . Site-specific model 51 Location of center of source: x,y,z (m) . P 7.5, 5, 1.5 Site-specific model 52 Area (Mi) P 45 Wall area is 15 m by 3 m NUREG/CR-6697, C, 8 53 Air fraction for H-3 B 1.00 NUREG/CR-6697, C, 81.6 Recommended value for gaseous form of H-3 Air fraction (for all radionuclides except H-3) B 0.07 1.6 Upper bound for contaminated noncombustible solids 2 54 Direct ingestion (hr 1) B 4.07E-07 NUREG/CR-5512, V3 S5 i.2.3 Equal to 1.1 E-4 m2/hr divided by total source area of 270 m 55 Removable fraction P 0.1 NUREG-1757, V2 SI.6. 3.1 Default parameter value for loose fraction from DandD 2.1 56 Lifetime or time for source removal (days) P Nuclide Spe cific NUREG/CR-6697, C, 81.8 57 Radionuclide Concentration (pCi/m 2 ) Initial concentration is unit source to allow for proportional DCGL P 45 Site-specific model calculation

. . -. , ... . ... .. ,. .c .1 58 Type P Area Site-specific model B-16

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 No Parameter (unit) Typea Value/Distribution Source Comments/Justification 59 Direction P Z Site-specific model 60 Location of center of source: x,y,z (m) P 7.5, 2.5, 0 Site-specific model 61 Area (M 2 ) P 75 Site-specific model Floor area is 5 m by 15 m 62 Air fraction for H-3 B 1.00 NUREG/CR-6697, C, 8.6 Recommended value for gaseous form of H-3 Air fraction (for all radionuclides except H-3) B 0.07 NUREG/CR-6697, C, 8.6 Upper bound for contaminated noncombustible solids 2 1 2 63 Direct ingestion (hr ) B 4.07E-07 NUREG/CR-5512, V3 S5.2.3 Equal to 1.1E-4 m /hr divided by total source area of 270 m 64 Removable fraction P 0.1 NUREG-1757, V2 S1.6.3.1 Default parameter value for loose fraction from DandD 2.1 65 Lifetime or time for source removal (days) P Nuclide Specific NUREG/CR-6697, C, 8.8 2 Initial concentration is unit source to allow for proportional DCGL 66 Radionuclide Concentration (pCi/m ) P 45 Site-specific model calculation 67 Type P Area " Site-specific model 68 Direction P Z Site-specific model 69 Location of center of source: x,y,z (m) P 7.5, 2.5, 3 Site-specific model 70 Area (Mi) P 75 Site-specific model Ceiling area is 15 m by 5 m 71 Air fraction for H-3 B 1.00 NUREG/CR-6697, C, 8.6 Recommended value for gaseous form of H-3 Air fraction (for all radionuclides except H-3) B 0.07 NUREG/CR-6697, C, 8.6 Upper bound for contaminated noncombustible solids 72 Direct ingestion (hr') B 4.07E-07 NUREG/CR-5512, V3 S5.2.3 Equal to 1.1E-4 M2/hr divided by total source area of 270 m2 73 Removable fraction P 0.1 NUREG-1757, V2 SI.6.3.1 Default parameter value for loose fraction from DandD 2.1 74 Lifetime or time for source removal (days) P Nuclide Specific NUREG/CR-6697, C, 8.8 Initial concentration is unit source to allow for proportional DCGL 75 Radionuclide Concentration (pCi/in 2 ) P 45 Site-specific model calculation Notes:

P = physical, B = behavioral, M = metabolic; [NUREG/CR-6676, App. B, Table B.3]

B-1 7

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Table B-12. DCGLs for Building Reuse Scenario Radionuclide DCGL (dpm/100 cm2)

C-14 1.OE+07 Fe-55 4.OE+07 Co-60 11,000 Ni-59 9.9E+07 Ni-63 3.6E+07 Sr-90 136,200 Tc-99 1.4E+07 Cs-137 40,500 Eu-152 24,300 Eu-154 4500 H-3 3.2E+08 Pu-241 228,000 Pu-238 4900 Cm-243/244 6100 Am-241 4300 Eu-155 395,000 1-129 67,800 Nb-94 15,800 Pu-239 4400 U-234 31,500 U-235 27,100 U-236 33,200 U-238 32,900 5.3 Residual Contamination in Subsurface Structures Decontamination and decommissioning of below grade PBRF structures (e.g., the Reactor Building [Building 1111 ]) will include decontamination of surfaces to building reuse DCGLs and offsite disposal of decontamination waste, removing decontaminated above grade and below grade structures down to 1 m (3 ft) below grade, backfilling belowground cavities with rubble generated from demolishing.

decontaminated above grade and below grade structures, and installing a cover over the backfilled area.

B-18

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Residual activity in the belowground portions of the various structures could be from several sources: in crushed concrete from aboveground structures, in remaining portions ofthe biological shield, on the surfaces of the canals and quadrants.

The resident farmer scenario was used for the Subsurface Structure dose assessment. RESRAD 6.21 was used for the assessment with certain parameter modifications, as listed below, to model the source in the saturated zone. The area used in the dose assessment was a 70-m (230-ft) cylinder (the approximate diameter of the subsurface structures), which extended vertically downward a distance of 3 m (10 ft) placing the contaminated zone directly on top of the saturated zone. The thickness of the contaminated zone is taken as 3 m (10 ft) to maximize dose through the external exposure and crop pathways. The well could be conceptualized as either in the center of the contaminated zone or located on the down gradient edge of the 70-m (230 ft.) diameter cylinder because the mass balance (MB) water transport model was used. The MB model eliminates the inappropriate dilution found in the Non-Dispersion Model that does not apply to the saturated zone equilibrium assumption of the Subsurface Structure fill model. Note that the hydrological parameters used were those provided in the Decommissioning Plan, which in some cases differ slightly from the final parameters listed in Tables B-1 through B-3. However, these parameters have no effect on the resulting water concentrations from the Subsurface Structure model because the model was designed to simulate concrete in an equilibrium saturated condition and not flow through an unsaturated contaminated zone.

The dose assessment and DCGL development for the Subsurface Structure scenario was performed using RESRAD 6.21 and the deterministic parameters from the surface soil scenario with seven changes as listed below. The unsaturated zone depth, time since material placement, and contaminated zone hydraulic conductivity parameters were selected to allow RESRAD to model a saturated condition.

1. MB water transport model used,

2. unsaturated zone depth 0 m,

3. contaminated zone 3 m,

4. contaminated zone area 3850 M2 ,

5. time since material placement 1 yr,

6. contaminated zone hydraulic conductivity 0.86 m/y, and

7. concrete Kds used in place of soil Kds.

A dose assessment was also performed assuming a lm cover is in place, which is the actual planned end state for the site. The "no cover" condition was assumed to be conservative for all radionuclides. The 1m cover analysis was performed to ensure that this assumption was correct. As shown in Table B-14, the 1m cover assumption results in a lower DCGL for one radionuclide, i.e., H-3.

B-19

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Concrete Kds were used to model the concrete debris to be placed in the subsurface structures. Table B-13 provides the range of concrete Kds for each of the radionuclides that were reported as above detection limits in smear samples of PBRF concrete and represent greater than 0.05% of the smear radionuclide mixture. The final list of radionuclides considered for FSS will include only those radionuclides considered significant per NIJREG-1757, Vol. 3.

The K-d ranges were derived from the following three references:

1. Krupka, K.M., and R.J. Serne. 1998. Effects on Radionuclide Conecentrations by Cement/GroundwaterInteractionsin Support ofPerformanceAssessment ofLow-Level Radioactive Waste DisposalFacilities. NJREG/CR-6377 (PNL- 11408).

2. Mattigod, S.V., et. al., 2002. Radionuclide Desorption and Leaching Tests for Concrete Coresfrom Haddam Neck Nuclear PlantFacilities.Final Letter Report, Battelle, Pacific Northwest Laboratory.

3. Fuhrmann, M., Sullivan, T, 1999. Leaching and Sorption ofRadionuclides:

StructuralConcretefrom Maine Yankee Nuclear Power Station. Final Letter Report, Brookhaven National Laboratory.

K 3 parameter distribution functions (PDFs) were developed for each radionuclide based on the range of potential values. Table B-13 provides the PDFs and defining numerical parameters. NUREG/CR-6697, Appendix A states that the uniform or loguniform distribution is useful if little is known about the distribution except the minimum and maximum, which is the condition arising from compiling the data from the above references. The loguniform is more appropriate when there is a wide range between the minimum and maximum.

Accordingly, the loguniform PDF was selected if the range exceeded a factor of

10. Otherwise, the uniform distribution was used. The three exceptions were Sr-90, Cs-137, and Tc-99. Because the Kd ranges were numerically low, i.e., 10, 18, and 21 for Sr-90, Cs-137, and Tc-99, respectively, the uniform distribution was used.

Consistent with the recommendations in NUREG-1757, Vol. 2, an uncertainty analysis was performed to determine if the calculated dose was sensitive to the concrete K4. The uncertainty analysis was performed using the probabilistic module of RESRAD 6.21 with radionuclide specific PDFs. The RESRAD output report of the Partial Rank Correlation Coefficient (PRCC) for the peak of the mean dose was reviewed. A decision criterion of the absolute value of 0.25 was selected for the PRCC test. The 0.1 and 0.25 values were found acceptable by the NRC through the approval of the Connecticut Yankee License Termination Plan (LTP). The results showed that the PRCC was less than -0.25 for all radionuclides indicating that the parameter was sensitive and the dose negatively correlated to the K4 (i.e., the dose went up as the K1 went down). Because the dose was negatively correlated, the 2 5 th quantile value of each PDF was used as the deterministic K1 parameter in the subsurface structure dose model. See Table B-13 for the 25h quantile t(4 values.

B-20

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 The dose assessment was performed with and without a 1 meter cover. As expected, the dose was higher with no cover with the exception of H-3 where the dose was higher with the cover in place. This is due to the unique characteristics of H-3 and the corresponding unique RESRAD environmental transport model.

The highest H-3 dose was used for the PBRF DCGL calculation as shown in Table B-14, Column 4.

RESRAD output report for the Subsurface Structure dose assessments are contained in a separate report available for review as needed. The RESRAD output report contains the maximum dose results (at t = Oy). The RESRAD output report also contains the RESRAD dose results for the evaluation with 1 m cover at the time of maximum dose (t = Oy).

Table B-13. Concrete Kds (mUg) for Subsurface Structure Model Dose Assessment Radionuclide Literature' CY 2 Maine 3 Plum Brook Kd PDF 2 5 th Quantile Kd C 10-500 10 - 500 Loguniform 4 26 Fe 10-100 7-18 7 - 100 Loguniform 13 Co 10-100 180-32500 10 - 100 Loguniform 17 Ni 10-100 10-61 10 - 100 Uniform5 32 Sr 1-3 10-111 0.7-1.3 1 - 11 Uniform 3.5 To 0-100 6-21 0 - 21 Uniform 5.2 Cs 2-20 34-26800 2.9-3.3 2 - 20 Uniform 6.5 Eu 200 - 1000 200 - 1000 Uniform 400 Pu 500-5000 500 - 5000 Uniform 1625 Cm 200-1000 200 - 1000 Uniform 400 Am 200-5000 >230 - 200 - 5000 Loguniform 445

>1750 I 1-10 1 -10 Uniform 3.2 Nb 100-1000 100 - 1000 Uniform 325 U 100-2000 100 - 2000 Loguniform 212 Footnotes:

1. Krupka 1998 and Bradbury 1998

2. Mattigod 2002

3. Fuhrman 1999

4. Minimum and maximum values of distribution

5. Minimum and maximum of distribution 1CY Kd value for Sr-90 was confirmed by an independent review by Brookhaven National Laboratory B-21

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 The DCGL calculation was performed by dividing 25 mrem/y by the unitized dose factors from the RESRAD output report (and the corresponding output page for the 1 m cover evaluation). The term unitized dose factor is used because the source term was 1 pCi/g for each radionuclide. The DCGLs are listed in Table B-

14. The radionuclides listed in Table B-14 represent all radionuclides that were reported as above detection limits in smear samples of PBRF concrete.

The final list of radionuclides considered for FSS will include only those that are considered significant per NUREG-1757, Vol. 3.

Table B-14. DCGLs for Subsurface Structures Radionuclide DCGL DCGL PBRF No Cover 1 m Cover DCGL (pCi/g) (pCi/g) (pCi/g)

C-14 17 85 17 Fe-55 685 691 685 Co-60 3.3 17 3.3 Ni-59 2134 2,495 2134 Ni-63 779 911 779 Sr-90 0.6 0.7 0.6 Tc-99 25 87 25 Cs-137 2.2 2.6 2.2 Eu-152 9.4 2,074 9.4 Eu-154 8.6 1,426 8.6 H-3 357 166 166 Pu-241 472 552 472 Pu-238 13 17 13 Cm-243/244 4.8 5.3 4.8 Am-241 3.8 4.0 3.8 Eu-155 354 9,184 354 1-129 0.27 0.27 0.27 Nb-94 6.6 1,504 6.6 Pu-239 12 15 12 U-234 22 24 22 U-235 18 25 18 U-236 23 25 23 U-238 22 25 22 B-22

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 The last step in the subsurface structure DCGL calculation is the conversion of the pCi/g volumetric DCGL. to an Effective Surface DCGL (DCGLEs). This allows the FSS to be performed using surface activity measurements and the inclusion of the source term that is present on the subsurface structure surfaces.

The DCGLEs is calculated using the following basic relationship:

DCGLv (pCi/g) Radionuclide Inventory / Concrete Debris Mass Where:

Inventory = (SA m )(10,000 cm 2/m2 )(DCGLts dpm/100 cm 2)(l pCi/2.22 dpm)

Concrete Debris Mass = (V mB)(lE+06 cm 3/m 3)(1-rl)(2.4 g/cm 3)

SA = Structure surface area requiring FSS (internal surfaces above and below grade) (M2) 1= porosity (0.41)

V = Volume of fill required (in 3)

Combining conversion factors and rearranging terms results on the following equation for calculating the DCGLEs:

DCGLEs dpmlO00 cm 2 = 31,435 (DCGLv pCilg) (V m3/SA in)

The vast majority of the structure contamination is in the Reactor Building (1111), Reactor Hot Lab (1112), Reactor Primary Pump House (1134), and Reactor Office and Lab Building (1141). These buildings are essentially connected and during demolition the debris from these structures will be expected to mix together. Because of the aforementioned, the V/SA ratio will be based on an average of these four buildings. The DCGLEs values calculated using this V/SA ratio will conservatively apply to all subsurface structures. The result is conservative because it is very unlikely the actual inventory of residual radioactivity'remaining on any structure surfaces will approach the calculated inventory assuming uniform contamination at the DCGLEs level. This ensures with high confidence that the Subsurface Structure volumetric DCGL will not be exceeded. The V/SA ratios are listed in Table B-15.

B-23

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Table B-15. Structure V/SA ratios Structure V/SA Ratio (m3/m 2)

Reactor Building (1111) 2.91 Hot Laboratory Building (1112) 1.19 Primary Pump House (1134) 1.27 Reactor Office and Laboratory Building (1141) 1.65 Average 1.76 Table B-16 lists the DCGLEs and the Building Reuse DCGL values for each radionuclide that was reported as above detection limits in smear samples of PBRF concrete. The final list of radionuclides considered for FSS will include only those that have a significant dose per NUREG-1757, Vol. 3.

The DCGLEs values were compared to the Building Reuse DCGLs and the more conservative of the two values designated as DCGLFss as shown in Column 4 of Table B-16. The DCGLFSS is the surface activity level that will be used during FSS to determine compliance with the 25 mrem/yr unrestricted use criteria.

The use of the DCGLFss value is a conservative approach when the DCGLEs is limiting because the radionuclide inventory expected to actually to be present on building surfaces at the time of demolition is much lower than that used in either the DCGL or the DCGLES calculations, which assume uniform contamination at either level.

If deemed necessary, the Building Reuse DCGLs could be applied for radionuclides where the DCGLEs is limiting. This would require a separate calculation to be performed, based on actual FSS measurement results, to confirm that the radionuclide specific inventory divided by the fill volume is less than the Subsurface Structure volumetric DCGL. For the four structures listed in Table B-15, this confirmation would be based on the average residual surface radioactivity level in the four structures (and the combined subsurface structure volumes). For all other structures the confirmation would be structure specific.

B-24

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Table B-16. Building Reuse DCGLs, Subsurface Structure Effective Surface DCGLs, and DCGLFSS Values Building Reuse Subsurface Structure DCGL Effective Surface DCGLFss Radionuclide (dpm/100 cm 2) DCGLES (dpm/l 00 cm 2)

(from Table B-12) (dpm/100 cm 2)

C-14 1.0E+07 940,500 940,500 Fe-55 4.0E+07 3.7E+07 3.7E+07 Co-60 11,000 182,500 11,000 Ni-59 9.9E+07 8.OE+07 8.OE+07 Ni-63 3.6E+07 4.3E+07 3.6E+07 Sr-90 136,200 33,100 33,100 Tc-99 1.4E+07 1.3E+06 1.3E+06 Cs-137 40,500 121,700 40,500 Eu-152 24,300 520,000 24,300 Eu-154 4,500 475,800 4,500 H-3 3.2E+08 9.1E+06 9.1E+06 Pu-241 228,000 2.6E+07 228,000 Pu-238 4,900 719,200 4,900 Cm-243/244 6,100 265,500 6,100 Ami-241 4,300 210,200 4,300 Eu-155 395,000 1.9E+07 395,000 1-129 67,800 14,900 14,900 Nb-94 15,800 365,100 15,800 Pu-239 4,400 663,900 4,400 U-234 31,500 1.2E+06 31,500 U-235 27,100 995,800 27,100 U-236 33,200 1.2E+06 33,200 U-238 32,900 1.2E+06 32,900 6.0 Area Factors Area factors (AFs) were developed for the Surface Soil and Building Reuse scenarios.

The Building Reuse AFs also apply to the Subsurface Structure DCGLEs values. The AFs were calculated using Co-60 to ensure the values are conservative for all radionuclides. The AF for the direct exposure pathway is lower than that for the ingestion and inhalation pathways and Co-60 generates the highest direct exposure per pCi/g.

The AFs for Surface Soil were calculated by first running the RESRAD code with the Surface Soil parameters and a source area of 2000 m2. The 2,000 in 2 source area was selected since this is the maximum survey unit size for a Class 1 area. RESRAD was then run using source areas ranging from 1 m2 to 250 M2 to represent the elevated area sizes. RESRAD dose reports used for the calculations are available for review as needed.

B-25

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 The AFs were calculated by dividing the dose result for the 2,000 m2 source area by the dose results for the smaller elevated areas. The Surface Soil AFs are shown in Table B-17.

The AFs for Building Reuse were calculated in an analogous manner except that an initial source area of 75 m 2 was selected to represent the floor area for the room size used in the RESRAD-BUILD modeling for the Building Reuse scenario. The elevated areas evaluated ranged from 0.25 m 2 to 50 M2 . The RESRAD-BUILD dose reports used for the calculations are available for review as needed. The Building Reuse AFs are listed in Table B- 18.

Table B-17 Surface Soil Area Factors Elevated Area 1 2 3 5 10 15 25 100 250 2000 (m2)

Area Fa 10.4 6.2 4.7 3.4 2.3 1.9 1.6 1.2 1.1 1 Factor Table B-18 Building Reuse Area Factors Elevated Area 0.250.50 1 2 4 6 8 10 15 25 50 75 (m2)

Area Fa 40.2 20.8 11.1 6.2 3.6 2.8 2.4 2.1 1.7 1.4 1.1 Factor 1 B-26

Final Status Survey Plan for the Plum Brook Reactor Facility Attachment C Embedded Piping Dose Assessment & DCGL Calculation

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 1.0 Purpose This attachment provides a discussion on the decision to leave selected sections of Plum Brook Reactor Facility (PBRF) embedded and buried piping in place, describes the conceptual dose model, and presents the Derived Concentration Guideline Level (DCGL) values and area factors to be used during final status surveys.

2.0 References 2.1 NUREG-1757, Volume 2, Consolidated NMSS Decommissioning Guidance, Characterization, Survey, and Determination of Radiological Criteria 2.2 MWH Constructors, Radionuclide Composition and Activity Ratios in Primary Coolant Piping, Transmittal-No. PBRF-05-0285, March 24,2005 2.3 Grove Software Inc., MicroShield User's Manual, Version 7, 2005 2.4 IAEA, Engineering Compendium on Radiation Shielding, Vol. 1, Springer-Verlag New York, 1968.

2.5 NASA Plum Brook Station Drawing PF-00375, Reactor Building Process Piping North Half- Plan -25 ft. Elevation, 08/27/56 2.6 NASA Plum Brook Station Drawing PF-00376, Reactor Building Process Piping, South Half- Plan -25 ft. Elevation, 08/27/56 2.7 NASA Plum Brook Station Drawing PF-003 85, Reactor Building Process Piping, Pump Room Plan & Sections. Revised 04/03/67 2.8 NASA Plum Brook Station Drawing PF-04645, Process Piping Tunnel Header &

Drains Below First Floor - Plan & Sections, 09/09/57 2.9 ICRP, Publication 74, Conversion Coefficients for Use in Radiological Protection against External Radiation, Elsevier, 1997 (Also ICRU Report No. 51, 1987 2.10 Portland General Electric Co., Final Survey Report, Embedded Piping, December, 2004 3.0 Discussion PBRF has performed an assessment of safety, radioactive waste generation, and cost associated with the removal of embedded and buried piping. PBRF has concluded that the increased risk from industrial safety, time and physical logistics of removing the piping, and cost would justify leaving some piping in place. Therefore, designated sections of embedded and buried piping will be remediated in place and undergo FSS.

C-1

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 3.1 Industrial Safety A study was performed to determine the industrial safety risks associated with removal of embedded and buried piping. A summary of the activities which elevate the safety risks during removal of embedded and buried piping outside those traditionally associated with reactor decommissioning projects include:

A large percentage of piping is located fifteen (15) to thirty-five (35) feet below grade. Working beneath the ground, the site labor forces must rely on the soil stabilization system to prevent a cave-in or a sudden onrush of groundwater into the work area.

The removal of piping in many areas entails the use of large hydraulic hammers (hoe-rams) for extended periods of time. The utilization of hoe-rams has the potential to increase fugitive dust emissions potentially creating silica exposures to labor forces, significantly increases noise levels throughout the facility, increase the risk to injury by flying debris, building collapse and worker becoming pinched by heavy equipment.

• Piping and rebar will have to be cut using torches which increases the risk of a fire.

• The packaging and handling of large quantities of waste debris and operation of heavy equipment increases the risk of an industrial accident.

3.2 Waste Generation The removal of the. embedded and buried piping will generate significant quantities of potential radioactive waste. The waste will have to be surveyed and sampled and either staged for backfill, if the material meets the release limits, or packaged and shipped to a waste processor. An estimated 3,565,100 pounds. of potential radioactive waste, including soil, concrete, and steel will be generated during removal of just the Primary Cooling Loop and Quadrant and Canal piping.

3.3 Cost The cost of removing the piping is high and far more costly than justified by the Nuclear Regulatory Commission (NRC) $2000/person-rem ALARA standard.

The operational phase of removing the Primary Cooling Loop was estimated to consume fifty-nine (59) weeks of schedule duration at an estimated cost of eight million to ten million dollars ($8,000,000-$ 10,000,000). The addition of removing the embedded Quadrant and Canal piping would have further increased that cost by approximately one million to one million, two hundred fifty thousand dollars

(-$1,000,000-$1,250,000). In total, the estimated costs associated with removing the PBRF's embedded piping systems would have ranged, more or less, from nine million dollars to eleven million, two hundred fifty thousand dollars ($9,000,000-

• $11,250,000).

C-2

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Once the preliminary estimates of costs associated with the removal of the PBRF embedded systems were thoroughly evaluated, it was decided that the more prudent and logical course of action would be that of surveying the embedded piping conduits, decontaminating the same as necessary to either meet the DCGL values or ALARA, and subsequently leave the embedded piping in place. The costs associated with the in-situ decontamination of the embedded Primary Cooling Loop, Quadrant and Canal piping, and some sections of buried piping was estimated to range from two million to four millions dollars ($2,000,000-

$4,000,000), depending upon the number of access points that need to be cut into the concrete to gain access to piping through floor traps and piping connected by "Tee"s and mitered elbows.

4.0 Embedded Piping versus Buried Piping Embedded piping (EP) is any pipe situated below the minus three (-3) foot elevation that is totally encased in concrete or piping directly beneath building floors that may not be totally encased in concrete, but contained within the structural foundation of the building.1 Examples include Containment Vessel Quadrant and Canal drain piping and remaining sections of the Primary Cooling Loop. Buried piping is any pipe buried in soil and situated outside the structural foundation of a building, such as storm drains.

4.1 Embedded Piping DCGL Values Embedded piping DCGL values were derived by developing a conservative conceptual model of piping layouts based on an extensive review of PBRF drawings and facility walk-downs. The calculations were performed using the dose calculation software MicroShield. Individual DCGL values were calculated for PBRF gamma-emitting radionuclides observed in PBRF embedded piping surface deposits. The DCGL values represent surface activity concentrations that correspond to an annual dose of one millirem per year (1 mrem/yr) to a future building occupant assuming that an individual occupies the facility and is exposed for 2340 hours0.0271 days <br />0.65 hours <br />0.00387 weeks <br />8.9037e-4 months <br /> per year. The PBRF methodology for determining DCGL values is provided in Sections 5.0 through 8.0. The EP DCGL values are provided in Table C-4.

4.2 Buried Piping DCGL Values The DCGL values for buried piping will be the same as the structure DCGL values. Refer to Attachment B of the FSSP.

1 The Trojan Decommissioning Project followed a similar approach for disposition of piping that was located beneath structures, but not necessarily embedded in concrete. This piping was inspected, cleaned, surveyed to embedded piping DCGL values and grouted in place after regulatory review and inspection/surveys of selected piping. (See Reference 2.10)

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Plum Brook Reactor Facility Final Status Survey Plan Revision 0 5.0 Embedded Piping Conceptual Dose Model The EP configuration that delivers the highest dose to a future building occupant was used in the dose model. This individual is assumed to occupy the walkway between Canal F and the Pump Room at the Reactor Building -25 ft. elevation and is exposed to a group of pipes (a pipe cluster) embedded in the concrete beneath the walkway. Plant drawings were reviewed and inspections performed to confirm that the pipe cluster located beneath the Canal F - Pump Room Walkway represents the most conservative case. That is, this pipe cluster is the highest concentration of embedded pipe's to which a future building occupant could be exposed while occupying a single location in the facility. Table C-i1 describes the piping layout used in the dose model. Figures C- I and C-2 provide views of the piping model layout and location of the dose point (one meter above the walkway floor) relative to the piping.

Table C-i Description of Pipe Cluster in Canal F - Pump Room Walkway Pipig I LegthHorizontal Offset Pipe CL Pipe Top Surf PipngI Description enth From Dose Point (f Depth Depth Below floor Ru I (n. (t)CL (ft) (in.) (in.)

1.21 Canal H Drain 6 81 1.5 16 13.25 1.23 Canal GDrain 6 42 1.5 16 13.25 1.24 Canal GPurge 3 39 3 16 14.75 1.25 Canal F Drain 6 20 4.5 16 13.25 1.26 Canal FPurge 3 19.5 .6 16147 1.641 Canal F&GOF Header (1) 8 125 3 38 34.25 1.81 Canal KFloor Drain 6 25 6. 25 22.25 2

1.82 Canal J& DS Riser () 3 25 4.5 25 23.75 1.83T EDS Floor Drain 4 25 7 38 36.25 Average Dimensions => 5.0 33.5 22.9 20.6 Table C-i Notes:

1. Overflow Header

2. Hot Drain System R'iser A review was conducted to identifyi other piping configurations that could represent potential exposures comparable to or possibly greater than the 9-pipe cluster described above. Plum Brook Reactor Facility drawings were reviewed and walk-downs conducted to identify locations with potential for exposure to clusters of embedded pipes, which

• terminate at wall surfaces in areas of the facility that could be occupied. A cluster of 1.0 pipes that terminate in a pipe trench located in the Reactor Building, -25 foot elevation was identified. During facility operation, these pipes emerged from concrete and were C-4

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 connected to a drain manifold in a trench (Quad & Canal Drains). After shutdown, the exposed piping has been removed and the pipe-ends cut flush with the trench wall. The trench is of such dimensions that an individual could occupy the trench and be exposed to gamma radiation emanating from the pipes (piping end-view exposure geometry). The layout of the conceptual model used to calculate doses from end-view exposure.to the former drain manifold piping is shown in Figures C-3 and C-4.

6.0 Dose Calculations for 9-Pipe Cluster All dose calculations reported herein were performed using MicroShield Version 5.04.

For the primary DCGL dose calculations, MicroShield geometry option 10 was used for the 9-pipe cluster Canal F - Pump Room Walkway. model.2 This is a cylindrical surface source with external dose point. The following assumptions were used to establish the MicroShield case runs and for determination of DCGL values:

• The dose receptor (dose point) is located one meter above the walkway floor surface on the longitudinal centerline of the pipe cluster and at a distance midway between the pipe ends.

• The 9 pipes lie in parallel runs (parallel to each other and to the floor surface) at the same elevation. Per review of PBRF drawings (References 2.5, 2.6, 2.7, &

2.8), the actual pipe centerline depths range from 16 to 38 inches and the average depth is 22.9 inches.

• The concrete in which the piping is embedded is modeled as a concrete slab shield (density 2.4 g/cc), 12 in. thick, placed between the top pipe surface and the floor elevation.

• All the pipes are cleaned by vacuuming and pressure blasting or mechanical means to remove loose scale and loosely adherent surface contamination. The pipes are filled with grout (concrete) with density 1.8 g/cc.,

• The pipes are all assumed to be 25 ft. in length. Note that the pipe lengths vary from 19.5 to 81 ft. with average length of 33.5 ft. It is found that the calculated dose is not sensitive to pipe length as the length is increased beyond 20 ft.

The pipe wall is modeled as a 1/4 in. thick (0.65 cm) cylindrical shield. This corresponds to Schedule 40 piping wall thickness for 5 in. piping, the average ID of the 9-pipe cluster. Note that the actual piping is all Schedule 80 (0.95 cm. wall thickness) [Reference 2.5, PF-00375].

2 The MicroShield code has several standard options for combinations of source and shield configurations. These are called "geometries". The geometry used for the default case, Geometry 10 is suitable for dose-receptor points external to the piping and located at positions that lie between the pipe ends (within the two planes perpendicular to the pipe longitudinal axis).

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Plum Brook Reactor Facility Final Status Survey Plan Revision 0

• The "buildup" medium for the MicroShield dose calculations is selected as the grout-filled pipe core.

• The model includes a piping corrosion layer surrounding the cylindrical surface source, modeled as "cladding" of 0.025 cm thickness.

• The only exposure pathway that is operative for embedded piping is direct dose from gamma-emitting radionuclides. All the radionuclides that may be present in piping residual contamination are fixed in place by the grout and are not available for transport to ground water or to ingestion or inhalation pathways to a future building occupant.

• This DCGL calculation uses MicroShield case run ou. ut dose rates in units of mSv/Ih (Deep Dose Equivalent Rate). The MicroShield code uses dose conversion factors from ICRP Publication 74, 1997 (Reference 2.9). The output dose rates are then converted to mrem/hr (100 mrem/hr per mSv/h).

The MicroShield source, dose point coordinates and shield dimensions are summarized in Table C-2.

Table C-2 Dose Calculation .Model Dimensions Source Dimensions Dose Point Coordinates Shields (cm) (cm) (cm)

Pipe Radius (1) X (2) y (3) Z (4) Wall Pipe Concrete Length Clad Wall 762 Pipe- Pipe- 381 Pipe- 0.025 0.65 30.48 (25 ft.) specific specific (12.5 ft.) specific (1 fit)

Table C-2 Notes:

1. This is the radius in cm. corresponding to each pipe ID.

2. The x coordinate is the total distance from the center axis of each pipe to the dose point. This includes the pipe radius, wall clad, pipe wall-shield thickness, the 12 in. concrete slab-shield thickness and the 1-meter distance from floor surface to the dose point (receptor center-height above the floor).

3. The y coordinate places the dose point at the center of the pipe lengths.

4. The z coordinate is the offset distance from the centerline of each pipe to the pipe cluster centerline (the dose point is located directly above the pipe cluster centerline).

The dose from each pipe was calculated individually for seven gamma-emitting radionuclides found to be present in primary cooling water piping in 2005 (Reference 2.2).

The dose was calculated for unit activity (one dpm/100-cm 2 or 4.5E-09 *Ci/cm 2). The dose to the receptor from each radionuclide is obtained as the sum of the contributions from each C-6

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 piping run in the 9-pipe cluster. The results are shown in Table C-3. The MicroShield case run reports are provided in Addendum 1.

It is noted that DCGL values for radionuclides that emit only beta particles are not calculated for embedded piping, even though several have been measured in piping deposits. They do not contribute to the dose to future building occupants because the piping that remains in place is filled with grout. However their presence must be accounted for when direct beta surface activity measurements are used for FSS of embedded piping.

Table C-3 Calculated Doses from Principal Gamma Emitting Radionuclides Canal F - Pump Room Walkway 9-pipe Cluster 2

Piping mremihr per dpm/100-cm Line No. Co-60 Cs-137 Eu-152 Eu-154 Ag-108m Nb-94 1.21 5.54E-10 3.90E-11 1.82E-10 2.50E-10 1.11E-10 1.58E-10 1.23 5.54E-10 3.90E-l1 1.82E-10 2.50E-10 1.11E-10 1.58E-10 1.24 1.79E-10 1.08E-11 5.84E-11 8.08E-11 3.13E-11 4.60E-11 1.25 8.64E-11 3.60E-12 2.79E-11 3.95E-11 1.10E-11 1.74E-11 1.26 1.76E-11 5.33E-13 5.68E-12 8.19E-12 1.71E-12 2.87E-12 1.641 2.90E-10 1.64E-11 .9.42E-11 1.31E-10 4.79E-11 7.11E-11 1.81 2.43E-11 7.02E-13 7.87E-12 1.14E-11 2.27E-12 3.83E-12 1.82 6.12E-11 2.70E-12 1.97E-11 2.79E-11 8.16E-12 1.28E-11 1.83 8.29E-12 1.87E-13 2.71E-12 3.97E-12 6.32E-13 1.11E-12 Total 1.77E-09 1.13E-10 5.81E-10 8.03E-10 3.25E-10 4.71E-10 Table C-3 Notes:

The dose rates from 1-129 (9.89E-35 mrem/hr), Sn-126 (1.45E-17 mrem/hr) and Eu-155 (4.10E-16 mrem/hr) were calculated, but are found to be at least 5 orders of magnitude below the dose rates from the other gamma emitting radionuclides. They are of no consequence and are eliminated from further consideration.

7.0 Embedded Piping DCGL Values To obtain individual radionuclide DCGL values, the dose rate for each radionuclide is converted to annual dose by multiplying by 2340 h/y, the exposure-hours for the occupant in the building occupancy scenario. The DCGL values are then obtained as the I C- 7

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 reciprocal of the annual dose. The results of these calculations are provided in Table C-4.

The individual radionuclide DCGL values range from 2.408E05 dpm/100-cm2 for Co-60 to 3.785E06 dpm/1 00-cm 2 for Cs-137. The calculated doses and DCGL values are strongly dependent on the thickness of concrete shielding that surrounds the embedded piping. The concrete typically provides a minimum of 12 to 14 inches of shielding for the piping.

Table C-4 Individual Radionuclide DCGL Values for Embedded Piping Annual Dose to DCGL Radionuclide Dose from all Pipes Building Occupant (dpm/100-cm 2 per (mrem/hr) (mrem/yr) mrem/yr)

Co-60 1.77E-09 4.17E-06 2.408E+05 Eu-154 8.03E-10 1.89E-06 5.325E+05 Eu-152 5.81E-10 1.37E-06 7.352E+05 Nb-94 4.71E-10 1.11E-06 9.082E+05 Ag-108m 3.25E-10 7.60E-07 1.312E+06 Cs-137 1.13E-10 2.64E-07 3.785E+06 8.0 Evaluation of Alternative Exposure Scenario The potential dose to a future building occupant was evaluated for the cluster of 10 pipes with pipe-ends terminating at the face of the Reactor Building Pump Room trench. The layout shown in Figures C-3 and C-4 were used to set up the MicroShield dose calculation model. The piping dose model and assumptions are very similar to the approach followed in calculating dose rates to a future building occupant from the 9-pipe cluster beneath the Canal F - Pump Room walkway. The specific assumptions for this scenario are:

e The dose receptor is located one meter above the Pump Room trench floor and one meter from the trench wall where the piping runs terminate. With reference to Figure C-3, the distance from the pipe cluster horizontal centerline to the elevation of the dose point is 67 cm.

• The 10 pipes are all horizontal and their centerlines are at an elevation of 13 inches (33 cm.) above the trench floor. The pipe centerline separation distance is 1 ft. 9 inches (53.3 cm.).

C-8

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 The pipes are modeled as 10 ft long cylindrical surface sources using MicroShield Geometry 10, Cylinder Surface with external dose point.

The shielding provided by the concrete surrounding each pipe is modeled as a cylindrical annular shield that surrounds the surface source. In MicroShield, when the external dose point lies outside the space between the ends of a cylindrical source (a pipe), compromises are required. The code does not accommodate more than one cylindrical material surrounding the source. Thus, the concrete replaces the steel pipe wall in the model setup. This is conservative, because the calculated doses would be lower, if the shielding effect of the piping wall could be accounted for.

To demonstrate that this exposure scenario does not yield limiting case DCGL values, it is sufficient to show that the dose rate for Co-60 is less than from the Canal F - Pump Room Walkway embedded pipe cluster. This result is shown in Table C-5. It is seen that the calculated dose rate is 3.06E-12 mrem/hr is much less than the Co-60 dose rate obtained from the Walkway floor Co-60 dose rate of 1.77E-09 mrem/hr.

Table C-5 Summary of Dose .Calculations for Pump Room Trench Occupancy Scenario Dose Point X Dose Point Z Dose Rate Pipe Run No. Pipe ID (in) Dimension Dimension DosemRate (cm) (cm) (mrem/hr) 1.36 10 53.3 0 4.225E-13 1.35 3 62.2 53.3 1.305E-12 1.34 10 53.3 106.6 5.920E-15 1.33 3 62.2 160 8.646E-15 1.32 10 53.3 214 8.157E-19 1.31 3 62.2 266.5 1.113E- 17 1.37 3 62.2 53.3 1.305E-12 1.38 10 53.3 106.6 5.920E-15 1.39 3 62.2 160 8.646E-15 1.395 10 53.3 214 8.157E-19 3.062E-12 Total 3.062E-12 C-9

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 The MicroShield case-run reports for the Pump Room Pipe Trench cluster are provided in Addendum 2. It is noted that due to the symmetry of the piping layout, it is necessary to calculate the doses for only 6 of the 10 pipes. As shown in Figure C-3, there are four pairs of pipes with identical diameters and separation distance on either side of the cluster centerline.

9.0 Area Factors Area factors provide a method to evaluate localized areas encountered in the Final Status Survey of embedded piping that exceed the DCGL (i.e., the elevated area comparison).

A working definition of area factor is the multiple of the DCGL that may be permitted in a localized area of specified dimensions such that the basic dose criterion (25 mrem/yr) is not exceeded. The area factors derived in this attachment are based on several assumptions. They are:

• A run of piping is considered to be a survey unit.

" The length of piping that contains elevated activity is analogous to the area containing elevated activity in a structural survey unit.

" The dose from Co-60 per unit activity in embedded piping exceeds that from any of the other gamma-emitting radionuclides observed in PBRF embedded piping.

Thus, area factors that are based on the dose from Co-60 will be conservative.

That is, the use of area factors derived on this basis will not result in doses that are greater than the dose criterion regardless of the radionuclide mixture that is present.

Area factors are calculated using the conceptual dose model described in Section 5.0 and using the same method for calculating doses as described in Section 6.0. It is seen from the dose calculation results in Table C-4, that most of the dose to the future building occupant is received from four of the 9 pipes in the pipe cluster, approximately 85%.

Therefore, it is a reasonable approximation to calculate the dose delivered from various lengths of these four pipes in the derivation of embedded piping area factors. Area factors are calculated for lengths of 1, 2, 5, and 10 feet. They are obtained as ratios of the dose rate from the four pipes of lengths 1, 2, 5, and 10 feet to the total dose rate from the entire length of all the pipes (1.77E-09 mrem/hr from Co-60).

The results of the area factor calculations are presented in Table C-6. Figure C-5 shows area factor versus length of elevated section of piping.3 The MicroShield case run reports for area factors are provided in Addendum 3.

3 An additional conservatism in the area factors is from the use of the combined dose from four pipe runs in the calculation. From physical principles, the average dose contribution from a single pipe of the specified lengths could be used, rather that the sum of the dose contributions.

C-]0

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Table C-6 Embedded Piping Area Factors Total Dose from Pipes Pipe Length (ft) of Specified Length Area Factor (mrem/hr) 1 3.013E-10 5.9 2 5.834E-10 3.0 5 1.197E-09 1.5 10 1.531E-09 1.2 Total dose rate 1.77E-09 ,

from all EP =>

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Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 Figure C-1 Conceptual Model for Embedded iping DCGL- Dose Calculation Canal F- Pump Fbom V\blkway 9-ipe Cluster Cross-section Mew Dose Fbint 0 100cm Canal F- Pomp Room Walkway Roor 4/

I. t Average depth to pipe CLis 20.6" Minimum depth to pipertop is 13 1/4 in 12 in shielding thickness assumed forall pipes 4-----0 0-6>

Line 1.26 Line 1.25 line ,1.24 Line 1.23 Line 1.21 Line 1.641 Line 1.82 Line 1.81 Line 1.83 3 in ID 6 in ID 3 in ID 6 in ID 6 in ID 8 in ID 3 in ID 6 in.ID 4 in ID 3' 3' 4.5' 4.5' -

4 6' 01 6'.

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C-12

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Figure C-2 Canal F- Prmp Rrnm .V\alkway 9-Rpe Cluster Conceptual Dose Model - Ran View m

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Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Figure C-3 Layout for Dose Model of Fbactor Building Pump Fbom Quad and Canal Drain Manifold Rpe Trench (Section View at Trench Wall showing ipe-Ends)

Rpe Cluster Center line FRBdg Pump Fbom Roor- 25 ft.

¶ Rpe CL2 ft 6 in below - 25 ft el.

Dose'Fbint lm 53.3 cm 67 cm 62.2 cm 1.33 3 in ID Rpe CL 1.39 3 in ID 1.37 3 in ID

-o 1.31 3 in ID 13 in above floor Trench Poor- 28 ft7 3/ in C-14 C- 14

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Figure C Pump Fbom Quad & Canal Drain Manifold Fpe Trench Conceptual Dose:Model - Ran View

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.4 4.' 10" Trench Sbuth wall Dose' Fbint C-15

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Figure C-5 Embedded Piping Area Factors 7.0 6.0 5.0 4.0 I-3.0 2.0 1.0 0.0 0 2 4 6 8 10 12 Length of Piping Elevated Area (ft.)

C-16

Final Status Survey Plan For the Plum Brook Reactor Facility Attachment C Embedded Piping Dose Assessment & DCGL Calculation Addendum 1 MicroShield Case Run Reports for Canal F Pump Room Walkway Pipe Cluster

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield Case Run Reports for Canal F - Pump Room Walkway Pipe Cluster Index Case Title Description File Name Result Run Date (mrem/hr) 12/19/2005 Line 1.21 A2 Revised ActModel DCGL w sched 40 & Calc - Co-60 12 in shid Unit PB121903 5.54E-10 12/21/2005 Line 1.21 B Revised Model Cale - Gs-137 Unit Act w PB122101 3.90E- 11 Sched 40 & 12 in cone shield 12/21/2005 Line 1.21 C Revised Model Calc - Eu-152 Unit Act w PB122102 1.82E-10 Sched 40 & 12 in cone shield 12/21/2005 Line 1.21 D Revised Model Calc - Eu-154 Unit Act w PB122103 2.50E-10 Sched 40 & 12 in cone shield 12/21/2005 Line 1.21 E Revised Model40Calc w Sched & 12- Ag-108m Unit Act PB122104 in cone shield 1.11E10 12/21/2005 Line 1.21 F Revised Model Calc Sched 40 & 12 -inNb-94 Unit Act w PB122105 cone shield 1.58E-10 Revised Model Calc 129 Unit Act w PB122901 2.10E-35 12/29/2005 Line 1.21 G Sched 40 & 12 in cone shield 1/4/2006 Line 1.21 H Revised Model Sched 40 Catc

& 12- in Sn-126 Unit Act w PBO10401 cone shield 5.551-18 12/29/2005 Line 1.211 Revised Model Calc - Zr-95 Unit Act w PB122903 6.42E-1 1 Sched 40 & 12 in conc shield 12/29/2005 Line 1.21 J Revised Model w Sched 40 Cale

& 12- inEu- 155 shield cone Unit Act PB122904 1.84E-16 12/19/2005 Line 1.23 A2 Revised Model DCGL Act w sched 40 &Cale - Co-60 Unit PB 121907 12 in shld 5.54E-10 Revised Model Calc - Cs-137 Unit Act w PB122106 3.90E-11 12/21/2005 Line 1.23 B Sched 40 & 12 in cone shield 12/21/2005 Line 1.23 C Revised Model Calc - Eu-152 Unit Actw PB122107 1.82E-10 Sched 40 & 12 in cone shield Line 1.23 D Revised Model Calc - Eu-154 Unit Act w PB122108 2.50E-10 Sched 40 & 12 in cone shield 12/21/2005 Line 1.23 E Revised Model Calc - Ag-108m Unit Act PB122109 1.1 E-l1 w Sched 40 & 12 in cone shield 12/21/2005 Line 1.23 F Revised Model Calc - Nb-94 Unit Act w PB122110 1.58E-10 Sched 40 & 12 in conc shield 12/29/2005 Line 1.23 G 12/29/2005_Line_1.2 G Revised Model Calc 129 Unit Act w PB122905 2.10E-35 Sched 40 & 12 in conc shield Revised Model Catc - Sn-126 Unit Act w 1/4/2006 Line 1.23 H Sched 40 & 12 in cone shield PBO10402 5.55E-18 12/29/2005 Line 1.23 1 Revised Model Cale 12 -inZr-95 Unit Act w PB122907 6.42E-1 Sched 40 & cone shield PB122907 6.42E-111 Revised Model Cale - Eu-155 Unit Act PB122908 1.84E-16 12/29/2005 Line 1.23 J w Sched 40 & 12 in conc shield PB12908 1.8E _1 12/19/2005 Line 1.24 A2 Revised ActModel DCGL w sched 40 &Cale12 -inCo-60 shld Unit PB121909 1.79E-10 12/21/2005 Line 1.24 B Revised Model Sched 40 Cale

& 12 -inCs-137 Unit Act w PB122111 conc shield* 1.08E-1 1 Revised Model Cale - Eu-152 Unit Act w PB122112 5.84E-1 12/21/2005__ L 14Sched 40 & 12 in conc shield I I C1-]

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield Case Run Reports for Canal F - Pump Room Walkway Pipe Cluster Index Run Date Result Case Title Description File Name (mrenmhr) 12/21/2005 Line 1.24 D Revised Model Cale =Eu-154 Unit Act w PB 122113 8.08E-1 1 Sched 40 & 12 in cone shield 12/21/2005 Line 1.24 E Revised Model40Cale w Sched & 12- Ag-108m Unit Act PB122114 in cone shield 3.13E-11 12/21/2005 Line 1.24 F Revised Model Cale Sched 40 & 12 -inNh-94 Unit Act w PB122115 conc shield 4.60E- 11 12/29/2005 Line 1.24 G Revised Model Cale 129 Unit Act w PB122909 9.09E-36 Sched 40 & 12 in cone shield 12/29/2005 Line 1.24 H Revised Model Calc - Sn-126 Unit Act w PB122910 2.89E-19 Sched 40 & 12 in cone shield Revised Model Cale - Zr-95 Unit Act w 12/29/2005 Line 1.24 1 Reied Md40 &

Sched G 112 in conc shield UnitsActlw PB122911 1.83E-1 1 1/4/2006 Line 1.24J Revised Model Gale - EU-155 Unit Act w PB010403 1.53E-17 Sched 40 & 12 in cone shield 12/19/2005 Line 1.25 A2 Revised Model DCGL Cale - Co-60 Unit PB121911 8.64E-11 Act w sched 40 & 12 in shld 12/21/2005 Line 1.25 B Revised Model Cale - Cs-137 Unit Act w PB122116 3.60E-12 Sched 40 & 12 in cone shield 12/21/2005 Line 1.25 C Revised Model Cale - Eu-152 Unit Act w PB 122117 2.79E-1 1 Sched 40 & 12 in cone shield 12/21/2005 Line 1.25 D Revised Model Cale - Eu-154 Unit Act w Sched 40 & 12 in cone shield PB122118 3.95& 11 12/21/2005 Line 1.25 E Revised Model40Cale w Sched & 12- Ag-108m Unit Act PB122119 in cone shield 1.10E-11 12/21/2005 Line 1.25 F Revised Model Cale - Nb-94 Unit Act w PB122120 1.74E-11 Sched 40 & 12 in cone shield 12/29/2005 Line 1.25 G Revised Model Cale 129 Unit Act w PB122913 1.43E-35 n1.25 Sched 40 & 12 in cone shield 1/4/2006 Line 1.25 H Revised Model Cale - Sn-126 Unit Act w PBO10404 1.04E-20 Sched 40 & 12 in cone shield 12/29/2005 Line 1.251 Revised Md Reied Model GCale - Z-Zr-95 UnitsActl Unit Act w PB122915 6.58E-12 Sched140 & 12 in cone shield 12/29/2005 Line 1.25 J Revised Model Cale - Eu-155 Unit Act PB 122916 9.69E-19 w Sched 40 & 12 in cone shield 12/19/2005 Line 1.26 A2 Revised Model Calc . Co-60 Unit Act w PB121913 1.76E-1 I Sched 40 & 12 in cone shield 12/21/2005 Line 1.26 B RRevised Model 12/21/2005_ LSched 40 Cale

& 12 -inCs-137 Unit Act w PB122121 cone shield 5.33E-13 12/21/2005 Line 1.26 C Revised Model Cale - Eu-152 Unit Act w PB 122122 5.68E-12 Sched 40 & 12 in cone shield 12/21/2005 Line 1.26 D Revised Model Cale - Eu-154 Unit Act w PB122123 8.19E-12 12/1/00 Lne1.6_ Sched 40 & 12 in cone shield 12/21/2005 Line 1.26 E Revised Model Cale - Ag-108m Unit Act PB122124 1.71E-12 w Sched 40 & 12 in cone shield 121/2005 Line 1.26F Revised Model Cale - Nb-94 Unit Act w PB122125 2.87E-12 Sched 40 & 12 in cone shield C1-2

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield Case Run Reports for Canal F - Pump Room Walkway Pipe Cluster Index Case Title Description File Name Result Run Date (mrem/hr) 12/29/2005 Line 1.26 G Revised Model 40 &Calc Unit Act W PB122917 5.78E-36 Sched 12 -in1-129 cone shield 1/4/2006 Line 1.26 H Revised Model Sched 40 Cale

& 12 -inSn-126 Unit Act w PB010405 cone shield 1.08E-22 12/29/2005 Line 1.26 1 Revised Model Galc - Zr-95 UnitActw PB122919 1.03E-12 Sched 40 & 12 in cone shield 12/29/2005 Line 1.26 J Revised Model Cale - Eu-155 Unit Act PB122920 2.04E-20 w Sched 40 & 12 in conc shield

• 12/19/2005 Line 1.641 A2 Revised Model Calc - Co-60 Unit Act w PB121915 2.90E-10 Sched 40 & 12 in conc shield 12/21/2005 Line 1.641 B Revised Model Caic - Gs-137 Unit Act w PB122126 1.64E-11 Sched 40 & 12 in conc shield 12/21/2005 Line 1.641 C Revised Model Calc - Eu-152 Unit Act w PB122127 9.42E-11 Sched 40 & 12 in cone shield 12/21/2005 Line 1.641 D Revised Model Sched 40 Cale

& 12 -inEu-154 Unit Act w PB122128 1.31E-10 cone shield 12/21/2005 Line 1.641 E Revised Model Cale - Ag-108m Unit Act PB122129 4.79E-11 w Sched 40 & 12 in cone shield 12/21/2005 Line 1.641 F RevisedModel Gale - Nb-94 Unit Act w PB122130 7.1 1E-1 I Sched 40 & 12.in cone shield 12/29/2005 Line 1.641 G Revised Model Gale 129 Unit Act w PB 122921 2.33E-35 Sched 40 & 12 in cone shield Revised Model Cale - Sn-126 Unit Act w 1/4/2006 Line 1.641 H Sched 40 & 12in cone shield PBO10406 4.96E-19 12/29/2005 Line 1.6411 Revised Model Cale - Zr-95 Unit Act w PB 122923 2.81E-11 Sched 40 & 12 in cone shield 12/29/2005 Line 1.641 J Revised Model w Sched 40 Calc

& 12 -in Eu-155 Unit Act cone shield PB 122924 2.49E-17 12/19/2005 Line 1.81 A2 Revised Model Cale Sched 40 & 12 -inCo-60 Unit Act w PB121917 cone shield 2.43E-11 12/21/2005 Line 1.81 B Revised Model 12/2/205_Le181 _ Sched 40 Cale

& 12 -inCs-137 Unit Act w PB122131 cone shield 7.02E-13 12/21/2005 Line 1.81 C Revised Model Sched 40 &Calc 12 -inEu-152 Unit Act w PB122132 cone shield 7.87E-12 12/21/2005 Line 1.81 D Revised Model Cale - Eu-154 Unit Act w PB122133 1.14E-11 1.81 D Sched 40 & 12 in cone shield 12/21/2005 Line

_2/2_/205___ n 1.81 E Revised 1.81___________

E Model40Calem Ag-108m Unit Act PB122134 w Sched & 12 in cone shield 2.27E-12 12/21/2005 Line 1.81 F Revised Model Calc Sched 40 & 12 -inNb-94 Unit Act w PB122135 cone shield 3.83E-12 12/29/2005 Line 1.81 G Revised Model Cale 129 Unit Act w PB 122925 1.14E-35 12/29/2005__ Line_____.81__G Sched 40 & 12 in cone shield PB12925 1.1E-3 1/4/2006 Line 1.81 H Revised Model Cale - Sn-126 Sb-126) PBO10407 1.35E-22 Unit Act w Sched 40 & 12 in cone shield 12/29/2005 Line 1.811 Revised Model Cale - Zr-95 Unit Act w PB122927 1.37E-12 Sched 40 & 12 in cone shield

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield Case Run Reports for Canal F - Pump Room Walkway Pipe Cluster Index File Name Result Run Date Case Title Description (mrem/hr) 12/29/2005 Line 1.81 J Revised Model w Sched 40 Cale

& 12-inEu-155 Unit Act conc shield PB122928 2.56E-20 12/19/2005 Line 1.82 A2 Revised ModelCale - Co-60 Unit Act w PB121919 6.12E-1 1 Sched 40 & 12 in conc shield 12/21/2005 Line 1.82 B Revised Model Gale - Gs-137 Unit Act w PB 122136 2.70E- 12 Sched 40 & 12 in conc shield 12/21/2005 Line 1.82GC Revised Model Cale - Eu-152 Unit Act w PB122137 1.97E-1 1 Sched 40 & 12 in conc shield 12/21/2005 Line 1.82 D Revised Model Calc - Eu-154 Unit Act w PB122138 2.79E-11 Sched 40 & 12 in conc shield 12/21/2005 Line 1.82 E Revised Model40Calc w Sched & 12- Ag-I08m Unit Act PB122139 in conc shield 8.16E-12 12/21/2005 Line 1.82 F Revised Model Cale - Nb-94 Unit Act w PB122140 1.28E-11 Sched 40 & 12 in cone shield 12/29/2005 Line 1.82 G Revised Model Gale 129 Unit Act w PB3 122929 7.29E-36 Sched 40 & 12 in cone shield Revised Model Cale - Sn-126 Unit Act w 12/29/2006 Line 1.82 H Sched 40 & 12 in cone shield PBO10408 7.29E-36 12/29/2005 Line 1.82 1 Revised Model Cale - Zr-95 Unit Act w PB122931 4.871E-12 Sched 40 & 12 in cone shield 12/29/2005 Line 1.82 J Revised Model Gale - Eu-155 Unit Act PB 122932 7.31E-19 w Sched 40 & 12 in cone shield Revised Model Cale - Co-60 Unit Act w wSched 40 & 12 in cone shield 12/21/2005 Line 1.83 B Revised Model Cale - Cs-137 Unit Act w PB122141 1.87E-13 Sched 40 & 12 in cone shield 12/21/2005 Line 1.83 G Revised Model Cale - Eu-152 Unit Act w PB122142 2.71E-12 Sched 40 & 12 in cone shield 12/21/2005 Line 1.83 D Revised Model Cale - Eu-154 Unit Act w 3.7E-12 Sched 40 & 12 in cone shield PB 122143 1/2/2006 Line 1.83 E Revised Model40Cale WSched & 12- Ag-15m4Unit in cone shield Act PB 122144 6.32E-13 12/21/2005 Line 1.83 F Revised Model Cale - Nb-94 Unit Act w P1122145 1. 1E-12 Sched 40 & 12 in cone shield 12/29/2005 Line 1.83 G Revised Model Cale 129 UnitActw PB122933 6.59E-36 Sehed 40 & 12 in cone shield 1/4/2006 Line 1.83 H Revised Model Cale - Sn-126 Unit Act w PBO10409 5.32E-24 Sched 40 & 12 in cone shield .

Revised Model Cale - Zr-95 Unit Act w 12/29/2005 Line 1.83 1 Sched 40 & 12 in cone shield 12/29/2005 Line 1.83 J Revised Model Gale - Eu-155 Unit Act PB122936 1.67E-21 w Sched 40 & 12 in cone shield C1-4

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Paa' :1 File Ref:

DX. ile ' PB121903.MS5 Date:

Rur te: December 19, 2005 By:

Run 'rime: 10:34:32 AM Checked:

Duration : 00:00:01 Case

Title:

Line 1.21 A2

Description:

Revised Model Calc. - Co-60 Unit Act w Sched 40 & 12 in shid Geometry: 10 - Cylinder Surface - External Dose Point Sour ce Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in x lose Points Y z

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in Shields Shield Name Dirtnension Mate rial Density Cyl. Core 7. 62 cm2 Conc rete 1.8 Shield 1 .65 cm Iro n 7.86 Transition Concrete 2.4 Shield 3 30..48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .0 25 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies Nucide curies becquerels Co.60 1.6417e-010 6.0744e+000 4.5000e-009 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cml/sec MeV/cmY/sec mR/hr No Buildup With Buildup No Buildup With Buildup 0.6938 9.909e-04 3.041e-13 5.389e- 12 5.872e-16 1.040e-14 1.1732 6.074e+00 1.656e-08 1.527e-07 2.959e- 11 2.728e-10 1 3325 6.074e+00 2.723e-08 2.17le-07 4.723e- 11 3.766e-10 1 ALS: 1.215e+01 4.378e-08 3.697e.07 7.682e- 11 6.494e.10 Cl-s

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/19/05 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB121903.MS5 Case

Title:

Line 1.21 A2 This case was run on Monday, December 19, 2005 at 10:34:32 AM Dose Point # 1 - (138.78,381,45.7) cm Results (Summed over energies) Units Without Buildup Buildup Photon Fluence Rate (flux) Photons/cm 2/sec 3.454e-008 2.930e-007 Photon Energy Fluence Rate MeV/cm 2/sec 4.378e-008 3.697e-007 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 7.682e-011 6.494e-010 Absorbed Dose Rate in Air mGy/hr 6.707e-013 5.670e-012 mrad/hr 6.707e-011 5.670e-010 Deep Dose Equivalent Rate (ICRP 51 -. 1987) o Parallel Geometry mSv/hr 7.614e-013 6.438e-012 o Opposed 6.558e-013 5.542e-012 o Rotational 6.558e-013 5.542e-012 o Isotropic 5.858e-013 4.950e-012 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 8.105e-013 6.854e-012 o Opposed 7.804e-013 6.598e-012 o Rotational 7.804e-013 6.598e-012 o Isotropic 6.206e-013 5.246e-012 Effective Dose Equivalent Rate (ICRP 51

• 1987) o Anterior/Posterior Geometry mSv/hr 6.856e-013 5.797e-012 o Posterior/Anterior 6.316e.013 5.339e-012 o Lateral 5.024e-013 4.244e-012 o Rotational 5.687e-013 4.807e-012 o Isotropic 5.034e.013 4.253e-012 Page 1 C1-6

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File : PB122101.MS5 Date:

Ru ate: December 21, 2005 By:

Rurf-Time: 1:04:33 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.21 B

Description:

Revised Model Calc - Cs-137 Unit Act w Sched 40 & 12 in shid Geometry: 10 - Cylinder Surface - External Dose Point urce Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in Dose Points x Y z

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in I ft 6.0 in 0 Shields Shield Name D:

)imension Mate Den sity Cyl. Core 7.62 cm 2 Conc rete 1.8 Shield 1 .65 cm Iro)n 7.86 Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies Nuclide becqueres Ci/cm BQ/nam Ba-137m 1.5531e-010 5.7464e+000 4.2570e.009 1.5751e.004 Cs-137 1.6417e-010 6.0744e+000 4.5000e.009 1 .6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Fluence Rate EUga=3at Exoosure Rate Exposure Rate MeV photons/sec MeV/cm 2/sec MeV/cm-2/sec mR/hr No Buildup WithBildu No Buildup With Buildup 0.0318 1.190e-01 8.159e-60 1.246e-34 6.796e-62 1.038e-36 0.0322 2.195e-01 4.883e-58 2.389e-34 3.930e-60 1.923e,36 0 f)364 7.987e-02 1.780e-45 1.33 le-34 1.012e-47 7.564e-37 316 5.171 e+00 1.291e-09 2.43le-08 2.503e-12 4.713e-11 C1-7

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Page :2 DOS File : PB122101.MS5 Run Date: December 21, 2005 Run Time: 1:04:33 PM Duration : 00:00:01 Energy Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm-'/sec MeV/cmz/sec mR/hr mRihB No Buildup With Buildup No Buildup TOTALS: 5.589e+00 1.291e-09 2.431e-08 2.503e.12 4.713e-1 1 C]-8

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 M.icroShield v5.04 (5.04-00362) 12/21/05 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122101.MS5.

Case

Title:

Line 1.21 B This case was run on Wednesday, December 21, 2005 at 1:04:33 PM Dose Point # 1 - (138.78,381,45.7) cm Results (Summed over energies) Unit Without With Buildup2 Buildup)

Photon Fluence Rate (flux) Photons/cml/sec 1.952e-009 3.674e-008 Photon Energy Fluence Rate MeV/cm 2/sec 1.291e*009 2.431e-OO8 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 2.503e-012 4.713e-011 Absorbed Dose Rate in Air mGy/hr 2,186e-014 4.114e-013 mrad/hr 2.186e-012 4.114e-011 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 2.588e-014 4.871e-0.13 o Opposed 2.072e-014 3.900e-013 o Rotational 2.072e-014 3.900e-013 o Isotropic 1.832e.014 3.449e-013 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 2.750e-014 5.177e-013 o Opposed 2.612e-014 4.917e-013 o Rotational 2.612e.014 4.917e-013 o Isotropic 1.958e.014 3.687e-013 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 2.288e-014 4.307e-013 o Posterior/Anterior 2.020e-014 3.802e-013 o Lateral 1.498e-014 2.819e-013 o Rotational 1.805e-014 3.397e-013 o Isotropic 1.536e-014 2,892e-013 Page 1 C1-9

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File : PB122102.MS5 Date:

RL. ate: December 21, 2005 By:

Runi Time: 1:09:19 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.21 C

Description:

Revised Model Calc - Eu-152 Unit Act w Sched 40 & 12 in shid Geometry: 10 - Cylinder Surface - External Dose Point urce Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in Dose Points Y z n

1. 1 138,78 cn 381 cm 45.7 cm 4 ft 6.6 ir 12 ft 6.0 in 1 ft 6.0 in Shields z

Shield Name Dimension Material Density Cyl. Core 7.62 cm 2 Concrete 1.8 Shield 1 .65 cm Iron 7.86 Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Standard Indices Number of Groups 25 Lower Energy Cutoff 0.015 Photons < 0.015 : Excluded Library : Grove Nuclide curies becauerels pCi/cm_ *Ba/cm 2 Eu-152 1,6417e- 010 6.0744e+000 4.5000e-0l09 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Ac~ti~i~t Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV/cm 2/sec M-eV/cm 2'/sec mR/hr mR/hr No Build=8 With Buildup No Builduo With Buildup D4 3.594e+00 1.418e-36 8.333e-33 6.272e-39 3.686e-35 c0-1o

Plum Brook Reactor Facility FinalStatus Survey Plan , Revision 0 Page :2 DOS File : PB122102.MS5 Run Date: December 21, 2005 Run Time: 1:09:19 PM Duration : 00:00:01 Energy Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate pho-tons/sec MeV/cm 2/sec MeV/cm 2/sec mR/hr mR/hr No Buildun With Buildup No Buildup With Buildup 0.05 8.987e-01 3.132e-26 2.928e-25 8.342e-29 7.80le-28 0.1 1.727e+00 4.074e-15 2.024e- 13 6.233e-18 3.096e-16 0.2 4.552e-01 3.440e- 13 2.243e- 11 6.072e-16 3.959e- 14 0.3 1.642e+00 1.054e-11 5.126e-10 1.999e-14 9.723e-13 0.4 3.817e-01 9.797e-12 3.474e-10 1.909e-14 6.769e- 13 0.5 3.426e-02 2.465e- 12 6.636e. 11 4.839e-15 1.303e-13 0.6 2,576e-01 4.189e-11 8.937e-10 8.176e.14 1.744e- 12 0.8 1.082e+00 6&109e-10 9.029e-09 1.162e-12 1.717e-11 1.0 2.599e+00 3.719e-09 4.152e-08 6.855e-12 7.654e-11

.1.5 1.409e+00 9.875e-09 6.928e-08 1.66le.11 1.166e-10 TOTALS: 1.408e+01 1.427e-08 1.217e-07 2.476e. 1I 2.138e- 10 Cl-))

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 HicroShield v5.04 (5.04-00362) 12/21/05 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122102.MS5 Case

Title:

Line 1.21 C This case was run on Wednesday, December 21, 2005 at 1:09:19 PM Dose Point # 1 - (138.78,381,45.7) cm Results (Summed over energie_) Without With Buildup Buildup-Photon Fluence Rate (flux) Photons/cm 2 1.120e-008 1.033e-007

/sec 1.217e-007 Photon Energy Fluence Rate MeV/cm 2/sec 1.427e.008 Exposure and Dose Rates: 2.138e-010 Exposure Rate in Air mR/hr 2.476e-011 mGy/hr 2.161e-013 1.867e-012 Absorbed Dose Rate in Air mrad/hr 2,161e-01 1 1.867e-010 Deep Dose Equivalent Rate -.-- '(lCRP-5r- -1987)--

o Parallel Geometry mSv/hr 2.459e-013 2.131e-012 o Opposed 2,120e-013 1.824e-012 o Rotational 2.120e-013 1.824e-012 o Isotropic 1.895e-013 1.628e-012 Shallow Dose Equivalent Rate (ICRP 51 . 1987) o Parallel Geometry mSv/hr 2,610e-013 2.265e-01 2 2,517e-013 2.180e-012 o Opposed 2.517e-013 2.180e-012 o Rotational 2.002e-013 1.724e-012 o Isotropic Effective Dose Equivalent Rate (ICRP 51 - 1987) mSv/hr 2.212e-013 1.914e-012 o Anterior/Posterior Geometry 1.757e-012 o Posterior/Anterior 11 2,039e-013 1.626e-013 1.392e-012 o Lateral 1,837e-013 1.582e-012 o Rotational 1.396e-012 o Isotropic 1.627e-013 Page C1-12

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File : PB122103.MS5 Date:

RL )ate: December 21, 2005 By:

Ru- rime: 1:12:29 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.21 D

Description:

Revised Model Calc - Eu-154 Unit Act w Sched 40 & 12 in shld Geometry: 10 - Cylinder Surface - External Dose Point urce Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3,0 in Dose Points x y z

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6,6 in 12 ft 6.0 in 1 ft 6.0 in z Shields Shield Name D)imension Mate Cyl. Core 7.62 cm 2 Conc rete 1.8 Shield 1 .65 cm iron 7.86 Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff 0.015 Photons < 0.015 : Excluded Library : Grove becquerels uci/cm2 B./cm-Eu-154 1.6417e- 010 6.0744e+000 4.5000e-OC )9 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy .ActivitIy Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm 2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup

)4 1.236e+00 4.878e-37 2.866e-33 2.158e,39 1.268e-35 CJ-13

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Page :2 DOS File : PB122103.MS5 Run Date: December 21, 2005 Run Time: 1:12:29 PM Duration : 00:00:01 Inergy Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV ohotons/sec MeV/cmI/sec MeV/cm2/sec mR/hr mR/hr No Buildup- Withl uI du No Buildup With Buildup 0.05 3.140e-01 1.094e.26 1.023e.25 2.915e-29 2.726e-28 0.1 2.458e+00 5.798e-15 2.880e-13 8.871e-18 4.406e-16 0.2 4.148e-01 3.136e-13 2.044e-11 5.534e. 16 3.608e-14 0.4 4.334e-02 1.112e-12 3.944e-11 2.167e-15 7.685e-14 0.5 1.315e-02 9.463e- 13 2.547e-11 1.857e-15 5.000e-14 0.6 4.900e-01 7.968e-11 1.700e-09 1.555e-13 3.318e-12 0.8 2.369e+00 1 .338e-09 1.978e-08 2.545e-12 3.761e-11 1.0 1.869e+00 2.674e.09 2.985e-08 4.929e-12 5.503e- 11 1.5 2.370e+00 1.661e-08 1. 165e-07 2.795e-11 1.961e-10 TOTALS: 1.158e+01 2.070e-08 1.679e-07 3.558e-11 2.922e-10 C1-14

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 icroShield v5.04 (5.04-00362) 12/21/05 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122103.MS5 Case

Title:

Line 1.21 D This case was run on Wednesday, December 21, 2005 at 1:12:29 PM Dose Point # 1 - (138.78,381,45.7) cm Results (Summed over energies) Units Without With Buildup Build~up_

Photon Fluence Rate (flux) Photons/cm 2/sec 1.556e-008 1.353e-007 Photon Energy Fluence Rate MeV/cm 2/sec 2.070e-008 1.679e.007 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 3.558e-0 11 2.922e.010 Absorbed Dose Rate in Air mGy/hr 3.106e-013 2.551e-012 II mrad/hr 3.106e-0 11 2.551e-010 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 3.528e.013 2.906e.012 o Opposed 3.053eý-013 2.499e-012 o Rotational 3.053e-013 2.499e-012 o Isotropic 2.733e-013 2.233e-012 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 3.741e-013 3.085e-012 o Opposed 3.613e-013 2.974e-012 o Rotational 3.613e-013 2.974e-012 o Isotropic 2.883e-013 2.361e-012 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 3.176e-013 2.612e-012 o Posterior/Anterior 2.934e-013 2.405e.012 o Lateral. 2.35le-013 1.915e-012 o Rotational 2.646e-013 2.167e-012 o Isotropic 2.349e-013 1.916e-012 Page 1 CI-I5

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File : PB122104.MS5 Date:

RL 'ate: December 21, 2005 By:

Rurf-l-ime: 1:21:22 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.21 E

Description:

Revised Model Calc- Ag-108m Unit Act w Sched 40 & 12 in shl Geometry: 10 - Cylinder Surface - External Dose Point urce Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in Dose Points I Z

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in Shields Shield Name C_

)imension Mate rial Density Cyl. Core 7.62 cm 2 Conc rete 1.8 Shield 1 .65 cm Iro n 7.86 Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Library : Grove Ncde curi es becuerelci/cm Ag-108m 1.6417 e-010 6,0744e+000 4.5000e-009 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Atvt Fluence Rate Fluence Rate Exposure Rate Exposure Rate Mev photons/Le MeV/cmz/sec MeV/cm 2/sec mr/hr mR/h No Buildup With Buildup No Buildup With Buildup D2 3.984e+00 3.590e- 187 1 .575e-33 1.244e- 188 5.457e.35 ICl-1 6

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Page :2 DOS File : PB122104.MS5 Run Date: December 21, 2005 Run Time: 1:21:22 PM Duration : 00:00:01 EnergV Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV/cm2 /sec MeV/cm 2/sec mR/hr mR/hr M.eM photons/sec No Buildup With Buildup No Buildup With Buildup 0.03 1.290e-06 3.735e-73 1. 128e-39 3.702e-75 1.118e-41 0.08 4.305e-01 2.032e-17 6.656e-16 3.216e-20 1.053e-18 0.4 5.460e+00 1.401e-10 4.969e-09 2.730e-13 9.681e-12 0.6 5.491e+00 8.929e-10 1.905e-08 1.743e-12 3.719e- 11 0.8 5.497e+00 3.105e-09 4.589e-08 5.906e-12 8.729e- 11 TOTALS: 2.086e+01 4.138e-09 6.991e-08 7.922e-12 1.342e-10 Cl-17

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 licroShield v5.04 (5.04-00362) 12/21/05 MicroShield v5.04 (5.04-00362)

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Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122104.MS5 Case

Title:

Line 1.21 E This case was run on Wednesday, December 21, 2005 at 1:21:22 PM Dose Point # 1 - (138.78,381,45.7) cm Results (Summed over energies) tUnita Without With Buildup Photon Fluence Rate (flux) Photons/cm 2 /sec 5.720e-009 1.015e-007 Photon Energy Fluence Rate MeV/cm 2/sec 4.138e-009 6.991e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 7.922e-012 1.342e-010 Absorbed Dose Rate in Air mGy/hr 6.916e-014 I.171e-012 mrad/hr 6.916e-012 1.17le-010 Deep DoseEquivalent Rate (ICRP 51 - 1987) o Parallel Geometry. mSv/hr 8.125e-014 1.382e-012 o Opposed 6.590e-014 1.114e-012 o Rotational 6.590e-014 1.114e-012 o Isotropic 5.826e-014 9.850e-013 Shallow Dose Equivalent Rate (ICRP 51.- 1987) o Parallel Geometry mSv/hr 8.661e-014 1.470e-012 o Opposed 8.249e-014 1,399e-012 o Rotational 8.249e-014 1.399e-012 o Isotropic 6,233e-014 1.054e-012 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 7.214e.014 1.225e-012 o Posterior/Anterior 6.419e-014 1.087e-012 o Lateral 4.818e-014 8.119e-013 o Rotational 5.739e-014 9.708e-013 o Isotropic 4.914e.014 8.297e-013 Page 1

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

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Page :1 File Ref:

DOS File : PB122105.MS5 Date:

RL ate: December 21, 2005 By:

Run-Time: 1:23:24 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.21 F

Description:

Revised Model Calc- Nb-94 Unit Act w Sched 40 & 12 in shl Geometry: 10 - Cylinder Surface - External Dose Point Sourc:e Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in Ri.!1'Man D ose Points Y z

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in Shields

.z Shield Name Dim ension Density Material Cyl. Core 7.6i2 cm 2 Concrete 1.8 Shield I 65 cm Iron 7.86 Transition Concrete 2.4 Shield 3 30. 48 cm Concrete 2.4 Air Gap Air 0.00122 7.86 Wall Clad .0 25 cm Iron Source Input Grouping Method : Actual Photon Energies curies becouerels w~i/cm 1 q/cm0 Nb-94 1.6417e.010 6.0744e+000 4.5000e-009 1 .6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Fluence Rate Fluence Rate Exposure Rate Exposure Rate photons/sec MeV/cm 2 /sec MeV/CM 2/sec mR/hr mR/hr No Bu~ildlup With Buildup No Buildup With Buildup 0.0174 2.148e-03 2.567e-278 6.819e-37 1.386e-279 3.681e-38 0.0175 4.115e-03 1.690e-273 1.319e-36 8.95le-275 6.984e-38 0.0196 1.209e-03 3.203e-201 4.633e-37 1. 182e-202 1.710e-38 0 7026 6.074e+00 1.969e-09 3.433e-08 3.797e-12 6.621e11 711 6.074e+00 4.910e-09 6.5 13e-08 9.241e.12 1.226e-10 CJ-19

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Page :2 DOS File : PB122105.MS5 Run Date: December 21, 2005 Run Time: 1:23:24 PM Duration : 00:00:01 E~r Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm 2/sec MeVV/cm 2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup TOTALS: 1.216e+01 6.879e-09 9.946e-08 1.304e- 11 1.888e-10 C1-20

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 icroShield v5.04 (5.04-00362) 12/21/0!

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Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122105.MS5 Case

Title:

Line 1.21 F This case was run on Wednesday, December 21, 2005 at 1:23:24 PM Dose Point # 1 - (138.78,381,45.7) cm Results (Summed over energies) Units WLithouti With Buildu Buildup2 Photon Fluence Rate (flux) Photons/cm2 /sec 8.439e-009 1 .236e-007 Photon Energy Fluence Rate MeV/cm 2/sec 6.879e-009 9.946e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 1.304e-01 1 1.888e-010 Absorbed Dose Rate in Air mGy/hr 1.138e-013 1.648e-012 mrad/hr 1.138e-011 1.648e-010 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.325e-013 1.920e-012 o Opposed 1.090e-013 1.577e-012 o Rotational 1.090e-013 1.577e-012 o Isotropic 9.639e-014 1.395e-012 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.416e-013 2.052e-012 o Opposed 1.35le-013 1.958e-012 o Rotational 1.35le-013 1.958e-012 o Isotropic 1.031e-013 1,492e-012 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 1.181e-013 1.710e-012 o Posterior/Anterior 1.059e-013 1.532e-012 o Lateral 8.040e-014 1.162e-012 o Rotational 9.477e-014 1.37le-012 o Isotropic 8.163e-014 1.180e-012 Page 3 C1-21

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

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Page :1 File Ref:

DOS File : PB122901.MS5 Date:

RL ate: December 29, 2005 By:

Run rime: 2:03:16 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.21 G

Description:

Revised Model Calc- 1-129 Unit Act w Sched 40 & 12 in shl Geometry: 10 - Cylinder Surface - External Dose Point urce Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in OWF x-Dose Points x Y z

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in

• z a Shields Shield Name )imension D: Matetrial Density Cyl. Core 7.62 cm 2 Conc rete 1.8 Shield 1 .65 cm Iro)n 7.86 Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies Nuclide curies becauerels pCi/cmz Ba/cm-1-129 1.6417e-010 6.0744e+000 4.5000e-009 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activity Fluence Rate EbL-oceRate Exposure Rate Exposure Rate MeV photons/sec MeV/cm z /sec MeV/CM 2/sec mR/hr mR/hB No Buildup No Buildup 0.0295 1.212e+00 4.389e-70 1.007e-33 4.593e-72 1.054e-35 0.0298 2.249e+00 4.520e-68 1 .925e-33 4.579e-70 1.951e-35 0.0336 7.995e-01 2.067e-52 1.005e-33 1.47le-54 7.150e-36 0 0396 4.568e-01 3.486e-38 1.022e-33 1.584e-40 4.643e-36 C1-22

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page :2 DOS File : PB122901.MS5 Run Date: December 29, 2005 Run Time: 2:03:16 PM Duration : 00:00:01 Energy Activity Fluence Rate Fluence Rate Exposure Rate MeV photons/sec MeV/cm 2/sec MeV/cm 2/sec mR/hr mR/hr No Buildup With Buildup With Buildup TOTALS: 4.718e+00 3.486e-38 4.959e-33 1.584e-40 4.184e-35 C]-23

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/29/05 MicroShield v5.04 (5.04-00362)

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Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122901.MS5 Case

Title:

Line 1.21 G This case was run on Thursday, December 29, 2005 at 2:03:16 PM Dose Point # 1 - (138.78,381,45.7) cm Results (Summed over energies) Units With Buildup Photon Fluence Rate (flux) Photons/cm2/sec 8.807e-037 1.546e-031 Photon Energy Fluence Rate MeV/cm 2/sec 3.486e-.038 4.959e-033 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 1.584e-040 4.184e-035 Absorbed Dose Rate in Air mGy/hr 1.383e-042 3.652e-037 i1 mrad/hr 1,383e-040 3.652e-035 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.979e-042 4.181e-037 o Opposed 9.969e-043 2.097e-037 o Rotational 9.026e-043 1.789e-037 o Isotropic 8.635e-043 1.662e-037 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.991e-042 4.557e-037 o Opposed 1.375e.042 3.134e-037 o Rotational 1.375e-042 3.134e-037 o Isotropic 1.009e-042 2.316e-037 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 1.154e-042 1.875e-037 o Posterior/Anterior 6.976e-043 9.692e-038 o Lateral 3.854e-043 5.231 e-038 o Rotational 6.273e-043 9.630e-038 o Isotropic 5.142e-043 7.979e-038 Page 1 CJ-24

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

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Page :1 File Ref:

DOz File : PBO1O401.MS5 Date:

Ru ate: January 4, 2006 By:

Run Time: 7:40:17 AM Checked:

Duration : 00:00:01 Case

Title:

Line 1.21 H

Description:

Revised Model Calc- Sn-126 Unit Act w Sched 40 & 12 in shld Geometry: 10- Cylinder Surface - External Dose Point urce Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in Dose Points

_x Y z

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in I ft 6.0 in z

a Shields Shield Name Dfimension Mate rial De~nsity Cyl. Core 7.62 cm 2 Conc rete 1.8 Shield 1 .65 cm lro n 7.86 Tra nsition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .025 cm iron 7.86 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff 0.015 Photons < 0.015 : Excluded Library : Grove Nuclide curies becquerels 2 moilcm Bq/c*

Sn- 126 1.6417e-' 010 6.0744e+000 4.5000e.0()9 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Enerv Activity Fluence Rate Fluence Rate Exposure Rate MeV photons/sec MeV/cm 2/sec MeV/cm 2/SeC mR/h No Buildup With Buildup) With Buildup

.02 4.702e-01 4.237e.188 1 .859e-34 1 .468e* 189 6.440e-36 C1-25

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0.

Page :2 DOS File : PBO1O401.MS5 Run Date: January 4, 2006 Run Time: 7:40:17 AM Dur-tion : 00:00:01 Ehergy Activ/it Fluence Rate Fluence Rate Exposure Rate Exposure MeV/cmz/sec MeV/cmz/sec . mR/hrRate e photons/sec . mR/hr No Buildup With Buildup With Buildup 0.03 1 .779e+00 5.151e-67 1.555e.33 5.105e-69 1.541e-35 7

0.04 3.034e-02 1. 197e-38 .035e-35 5.295e-41 3.111e-37 0.06 5.82le-01 1.833e-21 3.141e-20 3.640e-24 6.240e-23 0.08 2.789e+00 1.317e.16 4.313e-15 2.084e-19 6.825e-18 TOTALS: 5.650e+00 1.317e.16 4.313e-15 2.084e-19 6.825e. 18 C1-26

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 01/04/0 MicroShield v5.04 (5.04-00362)

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Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PBO1O401.MS5 Case

Title:

Line 1.21 H This case was run on Wednesday, January 4, 2006 at 7:40:17 AM Dose Point # 1 - (138.78,381,45.7) cm Results (Summed over energies) Withou Buildup Photon FluenceRate (flux) Photons/cm 2/sec 1.646e-015 5.391e.014 Photon Energy Fluence Rate MeV/cm 2/sec 1.317e-016 4.313e.015 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 2,084e-019 6.825e-018 Absorbed Dose Rate in Air mGy/hr 1.819e-021 5.958e-020 mrad/hr 1.819e-019 5.958e-018 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 3.182e-021 1.042e-019 o Opposed 1.695e-021 5.55 le.020 o Rotational 1.647e-021 5.395e-020 o Isotropic 1.636e-021 5.357e-020 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel, Geometry mSv/hr 3.153e-021 1.033e-019 o Opposed 2.317e-021 7. 589e-020 o Rotational 2.317e.021 7. 589e.020 o Isotropic 1.70le-021 .5.570e-020 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 2.673e-021 8.753e-020 o Posterior/Anterior 2.039e-021 6.676e-020 o Lateral 1.256e-021 4.115e-020 o Rotational 1.736e-021 5.687e-020 o Isotropic 1.404e-021 4.600e-020 Page CJ-27

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

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Page :1 File Ref:

DO" Pile : PB122903.MS5 Date:

Ru ..-,ate: December 29, 2005 By:

Run Time: 2:10:45 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.21 I

Description:

Revised Model Calc- Zr-95 Unit Act w Sched 40 & 12 in shid Geometry: 10 - Cylinder Surface - External Dose Point Sourcce Dimensions Height 762.0 cm 25ft Radius 7.62 cm 3.0 in 1'k-FXA91 xx Dose Points Z

1. 1i 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in Shields Shield Name Dim ension Material Density Cyl. Core 7. 62 cm 2 Concrete 1.8 Shield 1 65 cm Iron 7.86 Transition Concrete 2.4 Shield 3 30. 48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .0 25 cm lron 7.86 Source Input Grouping Method : Actual Photon Energies Nuclide curies becquerels _C_/cm? B1/cm-Zr-95 1.6417e-010 6.0744e+000 4.50OOe-009 1.6650e-004 Buildup The material reference is "Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 ResulIts Enem Activity Fluence Rate Fluence Rate Exposure Rate Expoure Rate V photons/sec MeV/cm 2/sec MeV/cm 2/gec mR/hr No Buildup With Buildup No Builduo With Buildup 0.7242 2.652e+00 9.792e-10 1.643e-08 1.883e-12 3.159e-11 0.7567 3.362e+00 1.499e-09 2.378e-08 2.869e-12 4.551e- 11 T^IALS: 6.014e+00 2.478e-09 4.020e-08 4.75le-12 7.709e- II C]-28

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicrcShield v5.04 (5.04-00362) 12/29/05 MicroShield v5.04 (5.04-00362)

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Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122903.MS5 Case

Title:

Line 1.21 I This case was run on Thursday, December 29, 2005 at 2:10:45 PM Dose Point # 1 - (138.78,381,45.7) cm Results (Sunnmed over energips) Units Without Buildup Buildup Photon Fluence Rate (flux) Photons/cm 2/sec 3.333e-009 5.410e-008 Photon Energy Fluence Rate MeV/cm 2/sec 2.478e-009 4.020e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 4.751eo012 7.709e-011 Absorbed Dose Rate in Air mGy/hr 4.148e-014 6.730e-013 mrad/hr 4.148e,012 6.730e-011

.Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 4.862e-014 7.890e-013 o Opposed 3.954e-014 6.416e-013 o Rotational 3.954e-014 6.416e-013 o Isotropic 3.495e-014 5.671e-013 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 5.19le-014 8.423e-013 o Opposed 4.947e.014 8.026e-013 o Rotational 4.947e-014 8.026e-013 o Isotropic 3.740e.014 6.069e-013 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 4.319e-014 7.007e-013 o Posterior/Anterior 3.846e-014 6.241e-013 o Lateral 2.892e-014 4.692e-013 o Rotational 3.440e-014 5.582e-013 o Isotropic 2.947e-014 4.782e-013 Page 1 C1-29

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Page :1 File Ref:

DOS File : PB122904.MS5 Date:

Ru ate: December 29, 2005 By:

Run--rime: 2:13:27 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.21 J

Description:

Revised Model Calc- Eu-155 Unit Act w Sched 40 & 12 in shid Geometry: 10 - Cylinder Surface - External Dose Point

'urce Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in Dose Points g Y- z

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in Shields Shield Name I)imension Mat(erial De~nsity Cyl. Core 7.62 cm 2 Conc rete 1.8 Shield 1 .65 cm Irc)n 7.86 Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 - Excluded Library : Grove Nuclide curies becquerels uCi/cm2 B1/cm-Eu.155 1.6417e- 010 6.0744e+000 4.5000e-0C)9 1 .6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Fluence Rate FWuenmce R-ate Exposure Rate Exposure Rate MeV photons/sec MeV/cm 2 /sec MeV/cm 2/sec mR/hr mR/h No Buildurp No Buildup With Buildup 1.933e-02 5.599e-69 1.690e-35 5.549e-71 1.675e-37 CJ-30

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page :2 DOS File : PB122904.MS5 Run Date: December 29, 2005 Run Time: 2:13:27 PM Duration : 00:00:01 Fluence Rate Fluence Rate Exposure Rate MeV MeV/cm2/sec MeV/cm 2 /sec mR/hr No Buildup With Buildup No Buildup '

WithB~uidu 0.04 1.101e+00 4.345e-37 2.553e-33 1.922e-39 1.129e-35 0.05 3.58 le-02. 1.248e-26 1.167e-25 3.324e-29 3.109e-28 0.06 7.878e.02 2.480e-22 4.251e,21 4.926e-25 8.444e-24 0.08 .1.886e+00 8.905e-17 2.917e-15 1.409e-19 4.615e-18 0.1 1.256e+00 2.962e-15 1.471e-13 4.532e-18 2.251e. 16 TOTALS: 4.699e+00 3.051e-15 1.50le-13 4.673e-18 2.297e-16 CI-31

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/29/05 MicroShield v5.04 (5.04-00362)

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Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122904.MS5 Case

Title:

Line 1.21 J This case was run on Thursday, December 29, 2005 at 2:13:27 PM Dose Point # 1 - (138.78,381,45.7) cm Rp-,iilt- (Ru;immel nver Pneroies) Units Without Buildlup Buildup

• Photon Fluence Rate (flux) Photons/cm 2/sec 3.074e-014 1l.508e-012 Photon Energy Fluence Rate MeV/cm 2/sec 3.05le-015 1.501e-013 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 4.673e-018 2.297e-016 Absorbed Dose Rate in Air mGy/hr 4.079e.020 2.006e-018 mrad/hr 4.079e-0 18 2.006e-016 Deep Dose Equivalent Rate (ICRP 51 -1987) o Parallel Geometry mSv/hr 6.827e-020 3.355e-018 o Opposed 3.740e-020 1.839e-018 o Rotational 3.737e-020 1.838e-018 o Isotropic 3.6 19e-020 1.779e-018 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 6.782e-020 3.333e-018 o Opposed 5.254e-020 2.583e-018 o Rotational 5.254e-020 2.583e-018 o Isotropic 3.826e-020 1.88Ie-018 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 5.865e-020 2.883e-018 o Posterior/Anterior 4.595e-020 2.259e-Oi8 o Lateral 2.836e-020 1.394e-018 o Rotational 3.925e-020 1.930e-018 o Isotropic 3. 124e.020 1.535e-018 Page 1 C1-32

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

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Pa--I :1 File Ref:

DC. ile : PB121907.MS5 Date:

Rur te: December 19, 2005 . By:

Run lime: 10:58:55 AM Checked:

Duration : 00:00:01 Case

Title:

Line 1.23 A2

Description:

Revised Model Calc. - Co-.60 Unit Act w Sched 40 & 12 in ShId Geometry: 10 - Cylinder Surface - External Dose Point Sour ce Dimensions Height 762.0 cm 25ft Radius 7.62 cm 3.0 in lose Points 1 x Y z

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in Shields Shield Name Dirt nension Mate Density Cyl. Core 7. 62 cm 2 Conc rete 1.8 Shield 1 .65 cm Iron 7.86 Transition Concrete 2.4 Shield 3 30. 48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .0 25 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies Nuclide curies becauerels pCi/cm2 .6/cm-Co-60 1.6417e-010 6.0744e+000 4.5000e-009 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm 2/sec MeV/cm 2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.6938 9.909e-04 3.041e-13 5.389e-12 5.872e-16 1.040e-14 1.1732 6.074e+00 1.656e-08 1.527e-07 2.959e.11 2.728e-10

' 3325 6.074e+00 2.723e-08 2.17le-07 4.723e- 11 3.766e.10 T ýLS: 1.215e+01 4.378e-08 3.697e-07 7.682e-11 6.494e-10 CI-33

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/19/05 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB121907.MS5 Case

Title:

Line 1.23 A2 This case was run on Monday, December 19, 2005 at 10:58:55 AM Dose Point # I - (138.78,381,45.7) cm Results (Summed over energies) .nit Without With Buildup Buildup)

Photon Fluence Rate (flux) Photons/cm 2/sec 3.454e-008 2.930e-007 Photon Energy Fluence Rate MeV/cm 2/sec 4.378e-008 3.697e-007 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 7.682e-01 1 6.494e-010 Absorbed Dose Rate in Air mGy/hr 6.707e-013 5.670e-012 mrad/hr 6.707e-01 1 5.670e-010 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 7.614e-013 6.438e-012 o Opposed 6.558e-013 5.542e-012 o Rotational 6.558e-013 5.542e-012 o Isotropic 5.858e-013 4.950e-012 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 8.105e-013 6.854e-012 o Opposed 7.804e-013 6.598e-012 o Rotational 7.804e-013 6.598e-012 o Isotropic 6.206e-013 5.246e-012 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 6.856e-013 5.797e-012 o Posterior/Anterior 6.316e-013 5.339e-012 o Lateral 5.024e-013 4.244e-012 o Rotational 5.687e-013 4.807e-012 o Isotropic 5.034e-013 4.253e-012 Page 1 CI-34

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File : PB122106.MS5 Date:

RL ate: December 21, 2005 By:

Ruff-rime: 1:29:02 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.23 B

Description:

Revised Model Calc - Cs-137 Unit Act w Sched 40 & 12 in ShId Geometry: 10 - Cylinder Surface - External Dose Point urce Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in Dose Points x Y z

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in 4 Shields Shield Name I)imension Mate Cyl. Core 7.62 cm 2 Conc rete 1.8 Shield 1 .65 cm Iro n 7.86 Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies 2

Nuclide cures becquerels WCi/CM BQ/cm 2 Ba-137m 1.5531e-010 5.7464e+000 4.2570e-009 1.5751e-004 Cs-137 1.6417e-010 6.0744e+000 4.5000e-009 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activity Fluence Rate Fluence Rate Exposure Rate Exoosure Rate MeV photons/sec MeV/cm 2/sec MeV/cm 2/sec mR/hr mR/hrgZ No Buildup No Buildup With Buildup 0.0318 1.190e-01 8.159e-60 1 .246e-34 6.796e-62 1.038e-36 0.0322 2.195e-01 4.883e.58 2.389e-34 3.930e-60 1.923e-36 0.0364 7.987e-02 1.780e-45 1 .331e-34 1.012e-47 7.564e.37 316 5.171e+00 1.291e.09 2.431 e.08 2.503e-12 ,4.713e-11 C]-35

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Page  : 2.

DOS File : PB122106.MS5 Run Date: December 21, 2005 Run Time: 1:29:02 PM Duration : 00:00:01 L, tr-ay Activity Fluence Rate Fluence Rate Exmosure Rate Exposure Rate MeV photons/sec MeV/cm 2/sec MeV/cm 2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup2 TOTALS: 5.589e+00 1.291e-09 2.431e-08 2.503e-12 4.713e.11 CI-36

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/21/05 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122106.MS5 Case

Title:

Line 1.23 B This case was run on Wednesday, December 21, 2005 at 1:29:02 PM Dose Point # 1 - (138.78,381,45.7) cm Results (Summed over energies) Units Without With Buildup Buildu""

Photon Fluence Rate (flux) Photons/cm 2/sec 1.952e-009 3.674e-008 Photon Energy Fluence Rate MeV/cm 2/sec 1.291e-009 2.431e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 2.503e-012 4.713e-011 Absorbed Dose Rate in Air mGy/hr 2.186e-014 4.114e-013 mrad/hr 2.186e-012 4.114e-011 Deep Dose Equivalent Rate (ICRP 51 -1987) o Parallel Geometry mSv/hr 2.588e-014 4.871e-013 o Opposed 2.072e-014 3.900e-013 o Rotational 2.072e-014 3.900e-013 o Isotropic 1.832e-014 3.449e-013 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 2.750e.014 5.177o-013 o Opposed 2.612e-014 4.917e-013 o Rotational 2.612e-014 4.917e-013 o Isotropic 1.958e-014 3.687e-013 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 2.288e-014 4.307e-013 o Posterior/Anterior 2.020e-014 3.802e-013 o Lateral 1.498e-014 2.819e-013 o Rotational 1.805e-014 3.397e-013 o Isotropic 1.536e-014 2.892e.013 Page 1 C1-37

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File : PB122107.MS5 Date:

RL ate: December 21, 2005 I By:

Run rime: 1:30:33 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.23 C

Description:

Revised Model Calc - Eu-152 Unit Act w Sched 40 & 12 in Shld Geometry: 10 - Cylinder Surface - External Dose Point urce Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in Dose Points X Y z

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in 0 Shields Shield Name I)imension Mate rial Density Cyl. Core 7.62 cm 2 Conc rete 1.8 Shield I .65 cm Iro )n 7.86 Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff 0.015 Photons < 0.015 : Excluded Library : Grove Nuclide curies becquerels WCI/CM 2 09 Eu-152 1.6417e-(010 6.0744e+000 4.5000e-0( 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm 2/sec MeV/CM2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 04 3.594e+00 1.418e-36 8.333e-33 6.272e-39 3.686e.35 CI-38

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page :2 DOS File : PB122107.MS5 Run Date: December 21, 2005 Run Time: 1:30:33 PM Duration : 00:00:01 Activity Fluence Rate Exposure Rate Exposure Ra~te MeV photons/sec MeV/cm 2/sec MeV/cm 2/sec mR/hr mR/hr With Buildup No Buildup With Buildup 0.05 8.987e-01 3.132e-26 2.928e-25 8.342e-29 7.80 le-28 0.1 1.727e+00 4.074e- 15 2.024e. 13 6.233e- 18 3.096e. 16 0.2 4.552e-01 3.440e. 13 2.243e-11 6.072e-16 3.959e- 14 0.3 1.642e+00 1.054e-11 5.126e-10 1.999e-14 9.723e-13 0.4 3.817e-01 9.797e- 12 3.474e- 10 1.909e-14 6.769e-13 0.5 3.426e-02 2.46o5e-12 6.636e-11 4.839e- 15 1.303e-13 0.6 2.576e-01 4.189e-11 8.937e-10 8.176e-14 1.744e. 12 0.8 1.082e+00 6.1096-10 9.029e-09 1.162e-12 1.7717e- 11 1.0 2.599e+00 3.719e-09 4.152e-08 6.855e.12 7.654e-11 1.5 1.409e+00 9.875e-09 6.928e-08 1.661e-11 1.166e-10 TOTALS: 1.408e+01 1.427e-08 1.217e-07 2.476e.11 2.138e-10 C1-39

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroSlhield v5.04 (5.04-00362) 12/21/05 MicroShield v5.04 (5.04-00362)

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Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122107.MS5 Case

Title:

Line 1.23 C This case was run on Wednesday, December 21, 2005 at 1:30:33 PM Dose Point # 1 - (138.78,381,45.7) cm Results (Summed over energies) Units Withou With Buildluo Buildup Photon Fluence Rate (flux) Photons/cm2/sec 1.120e-008 1.033e-007 Photon Energy Fluence Rate MeV/cm 2/sec 1.427e-008 1.217e-007 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 2.476e-011 2.138eO010 Absorbed Dose Rate in Air mGy/hr 2.16le-013 1.867e-012 mrad/hr 2.161e-011 1.867e-o10 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 2.459e-013 2.131e-012 o Opposed 2.120e-013 1.824e-012 o Rotational 2.120e-013 1.824e-012 o Isotropic 1.895e-013 1.628e-012 Shallow Dose Equivalent Rate (ICRP 51 -1987) o Parallel Geometry mSv/hr 2.610e-013 2.265e-012 o Opposed 2.517e-013 2.180e-012 o Rotational 2.517e-013 2.180e-012 o Isotropic 2.002e-013 1.724e-012 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 2.212e-013 1.914e-012 o Posterior/Anterior 2.039e-013 1.757e-012 o Lateral 1.626e-013 1.392e-012 o Rotational 1,837e-013 1.582e-012 o Isotropic 1.627e-013 1.396e-012 Page 1 CJ-40

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :I File Ref:

DOS File : PB122108.MS5 Date:

RL 'ate: December 21, 2005 By:

Rut,. ime: 1:32:17 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.23 D

Description:

Revised Model Calc - Eu-154 Unit Act w Sched 40 & 12 in Shid Geometry: 10 - Cylinder Surface - External Dose Point wurce Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in I ~ t X Dose Points Y Z

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in Shields Dimension Mate Shield Name Z Lrial Density Cyl. Core 7.62 cm 2 Conc rete 1.8 Shield 1 .65 cm Iro)n 7.86 Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Library : Grove Nuclid- curies becquerels p'i/cm2 Eu-154 1.6417e-010 6.0744e+000 4.5000e-009 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activity Fluence Rate FLuence Rate Exposure Rate Exposure Rate mev ohotons/sec MeV/cm 2/sec MeV/cm 2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 04 1.236e+00 4.878e-37 2.866e-33 2.158e-39 1.268e-35 CI-41

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Page :2 DOS File : PB122108.MS5 Run Date: December 21, 2005 Run Time: 1:32:17 PM Duration : 00:00:01 Activity Fluence Rate Fluence Rate Exposure Rate. Exposure Rate MeV photons/sec MeV/cm 2/sec MeV/cm 2/sec mR/hr mR/hr No Buildur) With Buildup No Buildup) With Buildup 0.05 3.140e-01 1.094e-26 1.023e-25 2.915e-29 2.726e-28 0.1 2.458e+00 5.798e-15 2.880e.13 8.87le-.18 4.406e- 16 0.2 4.148e-01 3.136e-13 2.044e- 11 5.534e-16 3.608e-14 0.4 4.334e-02 1.112e-12 .3.944e-11 2.167e-15 7.685e-14 0.5 1.315e-02 9.463e-13 2.547e-11 1.857e.15 5.000e-14 0.6 4.900e-01 7.968e.-I 1.700e-09 1,555e-13 3.318e-12 0.8 2.369e+00 1.338e-09 1.978e.08 2.545e-12 3.761e-11 1.0 1.869e+00 2.674e-09 2.985e-08 4.929e-12 5.503e-11 1.5 2.370e+00 1.661e-08 1.165e-07 2.795e- 11 1.961e-10 TOTALS: 1.158e+01 2.070e-08 1.679e-07 3.558e-11 2.922e-10 C1-42

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/21/05 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122108.MS5 Case

Title:

Line 1.23 D This case was run on Wednesday, December 21, 2005 at 1:32:17 PM Dose Point # 1 - (138.78,381,45.7) cm Results (Summed over energies) withou Buildup Builduo Photon Fluence Rate (flux) Photons/cm 2/sec 1.556e-008 1.353e-007 Photon Energy Fluence Rate MeV/cm 2/sec 2.070e-008 1.679e-007 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 3.558e-01 1 2.922e-010 Absorbed Dose Rate in Air mGy/hr 3.106e-013 2.551e-012 mrad/hr 3.106e-01 1 2.55le-0to Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 3.528e-013 2.906e-012 o Opposed 3.053e-O13 2.499e-012 o Rotational 3.053e-013 2.499e-O12 o Isotropic 2.733e-013 2.233e-012 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 3.741e-013 3.085e-012' o Opposed 3.613e-013 2.974e-O12 o Rotational 3.613e-013 2.974e.012 o Isotropic 2.883e-013 2.361e-012 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 3.176e.013 2.612e-012 o Posterior/Anterior 2.934e-013 2.405e-012 o Lateral 2.35le-013 1.915e-012 o Rotational 2ý646e-O13 2.167e-012 o Isotropic 2.349e-O13 1.916e-012 Page 1 C1-43

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File : PB122109.MS5 Date:

Ru ate: December 21, 2005 By:

RurF rime: 1:33:55 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.23 E

Description:

Revised Model Caic - Ag-108m Unit Act w Sched 40 & 12 in Shl Geometry: 10 - Cylinder Surface - External Dose Point Source Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in Dose Points x Y z

1. 1 138.78 c zm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in a Shields 2

Shield Name Dimension Material Density Cyl. Core 7.62 cm 2 Concrete 1.8 Shield 1 .65 cm Iron 7,86 Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .025 cm iron 7.86 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Library : Grove Nucliide curi es becuerels CI/cm Ag- 108m 1.6417i e-010 6.0744e+000 4.5000e-0'09 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm 2/sec MeV/cm2/sec mR/hr mR/h No Builduo With Buildup No Buildup With Buildup

)2 3.984e+00 3.590e. 187 1.575e.33 1.244e-188 5.457e-35 C]-44

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 Page  : 2 DOS File : PB122109.MS5 Run Date: December 21, 2005 Run Time: 1:33:55 PM Duration : 00:00:01 Entergy Activity Fluence Rate Fuence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm 2/sec MeV/cm 2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.03 1.290e-06 3.735e-73 1.128e.39 3.702e-75 1.118e-41 0.08 4.305e-01 2.032e-17 6.656e-16 3.216e-20 1,053e-18 0.4 5.460e+00 1.401e-10 4.969e-09 2.730e-13 9.681e-12 0.6 5.491e+00 8.929e.10 1.905e.08 1.743e-12 3.719e- 11 0.8 3.105e-09 4 5.497e+00 .589e-08 5.906e- 12 8.729e-11 TOTALS: 2.086e+01 4.138e-09 6.991e-08 7.922e-12 1.342e-10 C1-45

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 VlicroShield v5.04 (5.04-00362) 12/21/0!

MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122109.MS5ý Case

Title:

Line 1.23 E This case was run on Wednesday, December 21, 2005 at 1:33:55 PM Dose Point # 1 - (138.78,381,45.7) cm Results (Summed over energies) Units Without With Photon Fluence Rate (flux) Photons/cm2/sec 5.720e-009 1.015e-007 Photon Energy Fluence Rate MeV/cm 2/sec 4.138e-009 6.991e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 7.922e-012 1.342e-010 Absorbed Dose Rate in Air mGy/hr 6.916e-014 1.17le-012 mrad/hr 6.916e-012 1.171e-010 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 8.125e-014 1.382e-012.

o Opposed 6.590e.014 1.11 4e-0 12 o Rotational 6.590e-014 1.114e-012 o Isotropic 5.826e.014 9.850e-013 Shallow Dose Equivalent Rate (ICRP 51 . 1987) o Parallel Geometry mSv/hr 8.66 1e-014 1.470e-012 o Opposed 8.249e-014 1.399e-012 o Rotational 8.249e-014 1.399e-012 o Isotropic 6.233e-014 1,054e-012 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 7.214e-014 1.225e-012 o Posterior/Anterior 6.419e-014 1.087e-012 o Lateral . 4.818e,014 8.119e-013 o Rotational 5.739e-0 14 9.708e-013 o Isotropic 4.914e-014 8.297e-013 Page C]-46

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOR File : PB122110.MS5 Date:

Ru ate: December 21, 2005 By:

Run Time: 1:35:45 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.23 F

Description:

Revised Model Calc - Nb-94 Unit Act w Sched 40 & 12 in Shl Geometry: 10 - Cylinder Surface - External Dose Point Sourice Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in

4. X Dose Points x Y z

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in Shields Shield Name Dim ension Material Density Cyl. Core 7.( 52 cm 2 Concrete 1.8 Shield 1 65 cm Iron 7.86 Transition Concrete 2.4 Shield 3 30. 48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .0 25 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies Nuclide becouerels wci/CM2 Nb-94 1.6417e-010 6.0744e+000 4.5000e-009 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Fluence Rate Ftuence Rate Exposure Rate Exposure Rate photons/sec MeV/cm 2/sec MeV/cm 2'/sec mR/h mR/hr No Buildup With Buildup No Buildup With Buildup 0.0174 2.148e-03 2.567e-278 6.819e-37 1.386e-279 3.681e-38 0.0175 4.115e-03 1.690e-273 1.3 19e-36 8.951e-275 6.984e-38 0.0196 1.209e-03 3.203e.201 4.633e-37 1. 182e-202 1.710e-38 0 7026 6.074e+00 1.969e-09 3.433e-08 3.797e-12 6.621e-11 711 6.074e+00 4.910e-09 6.513e-08 9.241e-12 1.226e-10 CJ-4 7

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 Page :2 DOS File : PB122110,MS5 Run Date: December 21, 2005 Run Time: 1:35:45 PM Duration : 00:00:01 Energy Fluence Rate Fluence Rate Exposure Rate .Exposure Rate photons/sec MeV/cml/sec MeV/cml/sec NmR/hr mR/hr No Buildup With Buildup No Buildup With Buildup TOTALS: 1.216e+01 6.879e-09 9.946e-08 1.304e-11 1.888e-10 C]-48

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/21/05 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122110.MS5 Case

Title:

Line 1.23 F This case was run on Wednesday, December 21, 2005 at 1:35:45 PM Dose Point # 1 - (138.78,381,45.7) cm Results (Summed over energies) Units Without With Builidup Buildup Photon Fluence Rate (flux) Photons/cm2 /sec 8.439e-009 1.236e-007 Photon Energy Fluence Rate MeV/cm 2/sec 6.879e-009 9.946e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 1.304e-011 1.888e-010 Absorbed Dose Rate in Air mGy/hr 1.138e-013 1.648e-012 mrad/hr 1.138e-011 1.648e-010 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.325e-013 1.920e-012 o Opposed 1.090e-013 1.577e-012 o Rotational 1.090e-013 1.577e-012 o Isotropic 9.639e-014 1.395e-012 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.416e.013 2.052e-012 11 o Opposed 1.351e-013 1.958e-012 o Rotational 1.35le-013 1.958e-012 o Isotropic 1.031e-013 1.492e-012 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 1.18le-013 1.710e.012 o Posterior/Anterior 1.059e-013 1.532e-012 o Lateral 8.040e-014 1.162e-012 o Rotational 9.477e-014 1.37le-012 o Isotropic 8.163e-014 1.180e-012 Page 1 C1-49

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File : PB122905.MS5 Date:

RL ate: December 29, 2005 By:

Rur-Time: 2:22:38 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.23 G

Description:

Revised Model Calc 129 Unit Act w Sched 40 & 12 in Shid Geometry: 10 - Cylinder Surface - External Dose Point Sour ce Dimensions Height 762.0 cm 25ft Radius 7.62 cm 3.0 in lose Points x Y z

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in I Shield Name Shields Dirt nension Material Density Cyl. Core 7. 62 cm 2 Concrete 1.8 Shield 1 .65 cm Iron 7.86 Transition Concrete 2.4 Shield 3 30 .48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .0125 cm iron 7.86 Source Input Grouping Method : Actual Photon Energies Nuclide curies becquerels uji/CM2 Ba/cm2 k129 1.6417e-010 6.0744e+000 4.5000e-009 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm 2/sec M~eV/CM 2/sec mR/hr mR/hr No Buildup No Buildup With Buildup 0.0295 1.212e+00. 4,389e-70 1 .007e-33 4.593e-72 1.054e-35 0.0298 2.249e+00 4.520e-68 1.925e-33 4.579e-70 1.951e-35 0.0336 7.995e-01 2.067e-52 1.005e-33 1.471e-54 7.150e.36 0 0396 4.568e-01 3.486e-38 1.022e-33 1.584e-40 4.643e-36 Cl-50

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page - : 2 DOS File : PB122905.MS5 Run Date: December 29, 2005 Run Time: 2:22:38 PM DurAtion : 00:00:01 Energy Activity Fluence Rate FlecnRate Exposure Rate Exposure Rate MeV photons/sec MeV/cm 2/sec MeV/cm-'/sec mR*/hr mR/hr No Buildup With Buildup No Buildup With Buildup TOTALS: 4.718e+00 3.486e.38 4.95ge-33 1.584e-40 4.184e-35 Ct-51

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/29/05 MicroShield v5.04 (5.04-00362)

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Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122905.MS5 Case

Title:

Line 1.23 G This case was run on Thursday, December 29, 2005 at 2:22:38 PM Dose Point # 1 - (138.78,381,45.7) cm Results (Summed over energies) Units Without uidupth Buildup Photon Fluence Rate (flux) Photons/cm2/sec 8.807e-037 1.546e-031 Photon Energy Fluence Rate MeV/cm2/sec 3.486e-038 4.959e.033 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 1.584e-040 4.184e-035 Absorbed Dose Rate in Air mGy/hr 1.383e-042 3,652e-037 mrad/hr 1.383e-040 3.652e-035 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.979e-042 4.181e-037 o Opposed 9.969e-043 2.097e-037 o Rotational 9.026e.043 1.789e-037 o Isotropic 8.635e-043 1.662e-037 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.991e-042 4.557e-037 o Opposed 1.375e.042 3.134e-037 o Rotational 1.375e-042 3.134e-037 o Isotropic 1.009e-042 2.316e-037 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 1,154e-042 1.875e-037 o Posterior/Anterior 6,976e-043 9.692e-038 o Lateral 3.854e-043 5.231e-038 o Rotational 6.273e-043 9.630e-038 o Isotropic 5.142e.043 7.979e-038 Page 1 C1-52

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File : PBO10402.MS5 Date:

Rt )ate: January 4, 2006 By:

Rurf Time: 7;55:14 AM Checked:

Duration : 00:00:01 Case

Title:

Line 1.23 H

Description:

Revised Model Calc - Sn-126 Unit Act w Sched 40 & 12 in ShId Geometry: 10 - Cylinder Surface - External Dose Point urce Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3,0 in Dose Points x Y

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in 0 Shields

.Shield Name I ]imension Mt *rial Density Cyl. Core 7.62 cm 2 Conc rete 1.8 Shield 1 .65 cm Iro 7.86 Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff 0.015 Photons < 0.015 : Excluded Library : Grove Nuclide curies

• becquerels LC.JiLni Bg/CM 2 Sn-126 1.6417e- 010 6.0744e+000 4.5000e-0C39 1 .6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activity Fluence Rate FlUenqe Rate Exposure Rate MeV photons/sec MeV/cmt/.sec MelfV/Cr 2/-SeC mR/hr No Buildup With Buildup With Buildup 32 4.702e-01 4.237e-188 1.859e-34. 1.468e-189 6.440e-36 CJ-53

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Page :2 DOS File : PBO10402.MS5 Run Date: January 4, 2006 Run Time: 7:55:14 AM Duration : 00:00:01 Energy Fluence Rate Fluence Rate Exposure Rate Exposure Rate photons/sec MeV/cm 2/sec MeV/cm 2/sec mR/hr mR/hr No Buildup, With Buildup No Buildup With Buildup 0.03 1.779e+00 5.151e-67 1.555e-33 5.105e-69 1.541e-35 0.04 3.034e-02 1.197e-38 7.035e-35 5.295e-41 3.111e-37 0.06 5.82le-0O 1.833e-21 3.141e-20 3.640e-24 6.240e-23 0.08 2.789e+00 1.317e-16 4.313e-15 2.084e-19 6.825e-18 TOTALS: 5.650e+00 1.317e-16 4.313e-15 2.084e-19 6.825e- 18 C]-54

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 01/04/06 MicroShield v5.04 (5.04-00362)

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Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PBO10402.MS5 Case

Title:

Line 1.23 H This case was run on Wednesday, January 4, 2006 at 7:55:14 AM Dose Point # 1 - (138.78,381,45.7) cm Results (Summed over energies) Units Without With Buildup Photon Fluence Rate (flux) Phiotons/cm 2/sec 1.646e-015 5.391e-014 Photon Energy Fluence Rate MeV/cm 2/sec 1.317e-016 4.313e-015 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 2.084e-019 6.825e-018 Absorbed Dose Rate in Air mGy/hr 1.819e-021 5.958e-020 mrad/hr 1.819e-019 5.958e-018 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 3.182e.021 1.042e.019 o Opposed 1.695e-021 5.551e-020 o Rotational 1.647e-021 5.395e-020 o Isotropic 1.636e-021 5,357e-020 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 3.153e-021 1.033e-019 o Opposed 2.317e-021 7.589e-020 o Rotational 2.317e-021 7.589e-020 o Isotropic 1.701e-021 5.570e-020 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 2.673e-021 8.753e-020 o Posterior/Anterior 2.039e.021 6.676e.020 o Lateral 1.256e-021 4.115e-020 o Rotational 1.736e.021 5.687e.020 o Isotropic 1.404e-021 4,600e-020 Page I C1-55

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File : PB122907.MS5 Date:

RL ate: December. 29, 2005 By:

RunhTime: 2:27:29 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.23 I

Description:

Revised Model Calc - Zr-95 Unit Act w Sched 40 & 12 in Shid Geometry: 10 - Cylinder Surface. External Dose Point Sour ce Dimensions Height 762,0 cm 25 ft Radius 7.62 cm 3.0 in D

ose Points z

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in Shields S$hield Name Dinm

• ensioniMtra Density Cyl. Core 7. 62 cm 2 Concrete 1.8 Shield 1 65 cm Iron 7.86 Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .0 25 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies Nuclide curies becquerels ui/M Zr-95 1.6417e-010 6.0744e+000 4.5000e-009 1.6650e.004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activity Fluence Rate FLuence, Rate Exposure Rate Exposure Rate MeV hotons/sec MeV/cm 2/sec MeV/cm 2/sec mR/hr mR/hr No Buildup With Buildu No Buildup With Buildup 0.7242 2.652e+00 9.792e.10 1.643e-08 1.883e-12 3.159e-11 0.7567 3.362e+00 1.499e-09 2,378e-08 2.869e- 12 4.551e- 11 TOTALS: 6.014e+00 2.478e.09 4.020e-08 4.751e-12 7.709e-11 CI-56

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/29/05 MicroShield v5.04 (5.04-00362)

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Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122907.MS5 Case

Title:

Line 1.23 I This case was run on Thursday, December 29, 2005 at 2:27:29 PM Dose Point # 1 - (138.78,381,45.7) cm ppýlllfq (15,11mnmed over energies) Without With Buildup Photon Fluence Rate (flux) Photons/cm 2/sec 3.333e-009 5.410e-008 Photon Energy Fluence Rate MeV/cm 2/sec 2.478e-009 4.020e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 4.75le-012 7.709e-011 Absorbed Dose Rate in Air mGy/hr 4.148e-014 6.730e-013 mrad/hr 4.148e-012 6.730e-01 1 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 4.862e-014 7.890e-013 o Opposed 3.954e-014 6.416e-013 o Rotational 3.954e-014 6.416e-013 o Isotropic 3.495e-014 5.67le-013 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 5.19le-014 8.423e-013 o Opposed 4.947e-014 8.026e-013 o Rotational 4.947e.014 8.026e-013 o Isotropic 3.740e-014 6.069e-013 Effective Dose Equivalent Rate (ICRP 51 . 1987) o Anterior/Posterior Geometry mSv/hr 4.319e-014 7.007e-013 o Posterior/Anterior 3.846e-014 6.24le-013 o Lateral 2.892e-014 4.692e-013 o Rotational 3.440e-014 5.582e,013 o Isotropic 2.947e-014 4.782e-013 Page 1 Cl-57

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File : PB122908.MS5 Date:

Rt late: December 29, 2005 By:

Run- Time: 2:29:31 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.23 J

Description:

Revised Model Calc - Eu-155 Unit Act w Sched 40 & 12 in Shid Geometry: 10 - Cylinder Surface - External Dose Point iurce Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in Vý X Dose Points Y z

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in a Shields Shield Name Dimension Material Density Cyl. Core 7.62 cm2 Concrete 1.8 Shield 1 .65 cm Iron 7.86 Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff: 0.015 Photons < 0.015 : Excluded Library : Grove Nuclide curie becguerels pCi/cm Eu-155 1.6417e- 010 6.0744e+000 4.5000e-0( )9 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Eneray ActiLty Fluence Rate Fluence Rate Exposure Rate Exposu re Rate MeV ohotons/sec MeV/cm 2/sec MeV/cm 2/sec mR/hr mR/hr No Buildup With Buildup2 No Buildup With Buildup

)3 1.933e-02 5.599e-69 1 .690e.35 5.549e-71 1.675e-37 CJ-58

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 Page :2 DOS File : PB122908.MS5 Run Date: December 29, 2005 Run Time: 2:29:31 PM Duration : 00:00:01 Ehergy Activity FluenceRate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm 2/sec MeV/cm 2/sec mR/hr With Buildup No Buildup With Buildup 0.04 1.101e+00 4.345e-37 2.553e-33 1.922e-39 1.129e-35 0.05 3.581e-01 1 .248e.26 1.167e.25 3.324e-29 3.109e-28 0.06 7.878e-02 2.480e-22 4.25le-21 4.926e-25 8.444e-24 0.08 1.886e+00 8.905e- 17 2.917e-15 1.409e- 19 4.615e.18 0.1 1.256e+00 2.962e-1 5 1.471e-13 4.532e-18 2.25le-16 TOTALS: 4.699e+00 3.051e-15 1.501e-13 4.673e-18 2.297e-16 C1-59

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/29/05 MicroShield v5.04 (5.04-00362)

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Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122908.M55 Case

Title:

Line 1.23 J This case was run on Thursday, December 29, 2005 at 2:29:31 PM Dose Point # 1 - (138.78,381,45.7) cm Results (Summed over energies) Unuts Without Wtith Buildup Buildup Photon Fluence Rate (flux) Photons/cm 2/sec 3,074e-014 1.508e-012 Photon Energy Fluence Rate MeV/cm 2/sec 3.05le-015 1.50le-013 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 4.673e.018 2.297e-016 Absorbed Dose Rate in Air mGy/hr 4.079e-020 2.006e-018 mrad/hr 4.079e-018 2.006e-016 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 6.827e-020 3.355e-018 o Opposed 3.740e-020 1.839e-018 o Rotational 3.737e-020 1.838e-018 o Isotropic 3.619e-020 1.779e-018 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 6.782e-020 3.333e-018 o Opposed 5.254e-020 2.583e-018 o Rotational 5.254e-020 2.583e.018 o Isotropic 3.826e.020 1.881e-018 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 5.865e-020 2.883e-018 o Posterior/Anterior 4..595e-020 2.259e-018 o Lateral 2.836 e-020 1.394e-018 o Rotational 3.925e-020 1.930e-018 o Isotropic 3.1 24e-020 1.535e-018 Page 1 CI-60

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Pawe :1 File Ref:

D( Tile : PB121909.MS5 Date:

Rue te: December 19, 2005 By:

Run -time: 11:05:13 AM Checked:

Duration : 00:00:01 Case

Title:

Line 1.24 A2

Description:

Revised Model Calc. - Co-60 Unit Act w Sched 40 & 12 in Shld Geometry: 10 - Cylinder Surface - External Dose Point V-+ x Source Dimensions Height 762.0 cm 25 ft Radius 3.81 cm 1.5 in x lose Points Y z

1. 1 134.97 cm 381 cm 91.44 cm 4 ft 5.1 in 12 ft 6.0 in 3 ft Shields Shield Name Dirm*ension Material Density Cyl. Core 3, 31 cm 2 Concrete 1.8 Shield 1 65 cm Iron 7.86 Transition Concrete 2.4 Shield 3 30. 48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .0 25 cm iron 7.86 Source Input Grouping Method : Actual Photon Energies Nuclide curies becquerels pCi/cmZ Co-60 8.2087e-01 1 3.0372e+000 4:5000e-009 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm 2/sec MeV/cm'/sec mR/hr No Buildup With Buildup No Buildup With Buildup 0.6938 4.954e-04 7.277e-14 1.510e-12 1.405e-16 2.916e-15 1.1732 3.037e+00 4.717e-09 4.857e-08 8.429e-12 8.679e-11 1 3325 3.037e+00 8.038e-09 7.095e-08 1.395e- 11 1.23le-10 T \LS: 6.075e+00 1.275e-08 1.195e-07 2.237e- 11 2.099e-10 CJ-61

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/19/05 MicroShield v5.04 (5.04-00362)

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Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB121909.MS5 Case

Title:

Line 1.24 A2 This case was run on Monday, December 19, 2005 at 11:05:13 AM Dose Point # 1 - (134.97,381,91.44) cm Results (Summed over energies) Units Without With Buildup Buildup Photon Fluence Rate (flux) Photons/cm2/sec 1.005e-008 9.464e-008 Photon Energy Fluence Rate MeV/cm 2/sec 1.275e-008 1.195e-007 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 2.237e-01.1 2.099e-010 Absorbed Dose Rate in Air mGy/hr 1.953e-013 1.832e-012 mrad/hr 1.953e-01 1 1.832e-010 Deep Dose Equivalent Rate (ICRP 51 -1987) o Parallel Geometry mSv/hr 2.217e-013 2.080e-012 o Opposed 1.910e-013 1.791e-012 o Rotational 1.910e-013 1.79le-012 o Isotropic 1.706e-013 1.600e-012 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 2.360e-013 2.215e-012 o Opposed 2.273e-013 2.132e-012 o Rotational 2.273e-013 2.132e-012 o Isotropic 1.808e-013 1.695e-012 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 1.997e-013 1.873e-012 o Posterior/Anterior 1.840e-0 13 1.725e-012 o Lateral 1.463e-013 1.372e-012 o Rotational 1.657e-013 1.554e-012 o Isotropic 1.466e-013 1.375e-012 Page 1 Cl-62

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File : PB122111.MS5 Date:

Ru te: December 21, 2005 By:

Run-i ime: 1:45:09 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.24 B

Description:

Revised Model Caic. - Cs-137 Unit Act w Sched 40 & 12 in Shl Geometry: 10 - Cylinder Surface- External Dose Point urce uimensiorns Height 762.0 cm 25 ft Radius 3.81 cm 1;5 in Dose Points Y

1. 1 134.97 cm 381 cm 91.44 cm 4 ft 5.1 in 12 ft 6.0 in 3ft Shields Shield Name Dimension Mate Density Cyl. Core 3.81 cm2 Conc rete 1:8

-X Shield 1 .65 cm Iro n 7.86 Lz Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies Nucli~de curies becquerels wCi/cm 2 Bg/cm 2

Ba-137m 7.7654e-0 11 2.8732e+000 4.2570e-009 1.5751e-004 Cs-137 8.2087e-0 11 3.0372e+000 4.5000e-009 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy .Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate photons/sec MeV/cm 2/sec MeV/cm 2/sec MeV mR/hr mR/hr No Buildup With Buildup No Buildup With Builduo 0.0318 5.948e-02 1.933e-65 5.403e-35 1.610e-67 4.5004-37 0.0322 1.097e-01 1.659e-63 1.036e-34 1.335e-65 8.337e-37 0 n364 3.994e-02 1.318e-49 5.773e-35 7.489e-52 3.280e-37 i16 2.585e+00 3.035e-10 6.72 le.09 5.884e-13 1.303e.11 C]-63

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Page :2 DOS File : PB122111.MS5 Run Date: December 21, 2005 Run Time: 1:45:09 PM Duration : 00:00:01 Activity Flence Rat Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm 2/sec MeV/cm 2/sec rnR/hr No Buildup With Buildup No Buildup With Buld1up TOTALS: 2.794e+00 3.035e-10 6.72le-09 5.884e- 13 1.303e. 11 C]-64

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/21/05 MicroShield v5.04 (5.04-00362)

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Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122111.MS5 Case

Title:

Line 1.24 B This case was run on Wednesday, December 21, 2005 at 1:45:09 PM Dose Point # 1- (134.97,381,91.44) cm Results (Summed over energies) Units Without with Buildup Buildup Photon Fluence Rate (flux) Photons/cm 2/sec 4.587e-010 1.016e-008 Photon Energy Fluence Rate MeV/cm 2/sec 3.035e-010 6.721e-009 Exposure and Dose Rates:

Exposure Rate in Air mR/hr *5.884e-013 1.303e-011 Absorbed Dose Rate in Air mGy/hr 5.137e-015 1.137e-013 mrad/hr 5.137e-013 1.137e.011 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 6.082e-015 1.347e.013 o Opposed 4.869e-015 1.078e-013 o Rotational 4.869e-015 1.078e-013 o Isotropic 4.306e-015 9.534e-014 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 6.464e-015 1.43le-013 o Opposed 6.139e-015 1.359e-013 o Rotational 6.139e-015 1.359e-013 o Isotropic 4.603e-015 1.019e-013 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 5.378e-015 1.191e-013 o Posterior/Anterior 4.747e-015 1.05le-013 o Lateral 3.520e-01 5 7.794e-014 o Rotational 4.242e-015 9.392e-014 o Isotropic 3.6 lle-015 7.996e-014 Page 1 Cl-65

Plum Brook Reactor Facility . Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

D10 File : PB122112.MS5 Date:

RL. te: December 21, 2005 By:

Run time: 1:48:57 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.24 C

Description:

Revised Model Caic. - Eu-152 Unit Act w Sched 40 & 12 in Shl Geometry: 10 - Cylinder Surface - External Dose Point Source Dimensions Height 762.0 cm 25 ft Radius 3.81 cm 1.5 in Dose Points X Y z

1. 1 134.97 cr n 381 cm 91.44 cm 4ft 5.1i n 12 ft 6.0 in 3ft Shields Shield Name Dimension Material Cyl. Core 3.81 cm 2 Concrete 1.8 Shield 1 .65 cm Iron 7.86 Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff 0.015 Photons < 0-015 : Excluded Library : Grove Nuclide curies . WCi/crn 2 B1 !-cm 4 Eu-152 8.2087e-011 3.0372e+000 4.5000e-009 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Actuvity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cmz/sec MeV/cm 2/sec mR/hr mR/hr No Buildup With Buildup No Build=e With Buildup

)4 1.797e+00 5.750e-40 3.614e-33 2.543e-42 1.598e-35 C]-66

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 Page :2 DOS File : PB122112.MS5 Run Date: December 21, 2005 Run Time: .1:48:57 PM Dur-tion : 00:00:01

[Energy Activity Fluence Rate Fluence Rate Exposure Rate MeV photons/sec MeV/cm 2/sec MeV/cm 2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Butildup 0.05 4.493e-01 1 .622e-28 1.584e-27 4.320e-31 4.220e.30 0.1 8.635e-01 2.796e- 16 1.693e-14 4.278e-19 2.591e-17 0.2 2.276e-01 4.533e-14 3.792e- 12 8,00le-17 6.693e- 15 0.3 8.212e.01 1.744e. 12 1.067e.10 3.309e- 15 2.025e- 13 0.4 1.909e-01 1.864e-12 8.121e- 11 3.632e- 15 1.582e-13 0.5 1.713e-02 5.178e-13 1.678e- 11 1.016e-15 3.293e-14

.0.6 1.288e-01 9.480e- 12 2.399e-10 1.850e-14 4.682e-13 0.8 5.408e-01 1.539e-10 2.629e-09 2.927e-13 5.00le.12 1.0 1.300e+00 1.009e-09 1.275e-08 1.860e.12 2.350e- 11 1.5 7.046e-01 3.006e-09 2.317e-08 5.058e-12 3.898e- 1I TOTALS: 7.040e+00 4.183e-09 3.899e-08 7.238e-12 6.835e-11 C]-67

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 M*icroShield v5.04 (5.04-00362) 12/21/0!

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Radiological Services, Inc.

Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122112.MS5 Case

Title:

Line 1.24 C This case was run on Wednesday, December 21, 2005 at 1:48:57 PM Dose Point # 1 - (134.97,381,91.44) cm Results (Summed over energies) Units WiLthout1 With Buildup Photon Fluence Rate (flux) Photons/cm 2/sec 3.233e-009 3.249e-008 Photon Energy Fluence Rate MeV/cmz/sec 4.183e-009 3.899e.-008

• Exposure and Dose Rates:

Exposure Rate in Air mR/hr 7.238e-012 6.835e-011 Absorbed Dose Rate in Air mGy/hr 6.319e-014 5.967e-013 mrad/hr 6.319e-01 2 5.967e-011 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 7.183e-014 6.805e-013 o Opposed 6.20le-014 5.835e-013 o Rotational 6.201e-014 5.835e-013 o Isotropic 5.545e-014 5.209e-013 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 7.624e-014 7.232e-013 o Opposed 7.355e-014 6.963e.013 o Rotational 7.355e-014 6.963e-013 o Isotropic 5.858e-014 5.515e-013 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 6.464e-014 6.116e-013 o Posterior/Anterior 5.963e-014 5.620e-013 o Lateral 4.764e-014 4.458e-013 o Rotational 5.375e-014 5.060e-013 o Isotropic 4.764e-014 4.468e-013 Page C1-68

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File : PB122113.MS5 Date:

RL te: December 21, 2005 By:

Run rime: 1:50:31 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.24 D

Description:

Revised Model Calc. - Eu-154 Unit Act w Sched 40 & 12 in Shl Geometry: 10 - Cylinder Surface - External Dose Point Source Dimensions Height 762.0 cm 25 ft Radius 3.81 cm 1.5 in Dose Points X Y

1. 1 134.97 cr r 381 cm 91.44 cm 4 ft 5.1 in 12 ft 6.0 in 3ft Shields Shield Name Dimension Mat Density 2

Cyl. Core 3.81 cm Con crete 1.8 Shield 1 .65 cm Ir 7.86 Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff 0.015 Photons < 0;0-1-5 : Excluded Library : Grove Nuclide curie-3 becquerels pCi/cm 2 B1/cm 2 Eu .154 8.2087e- 011 3.0372e+000 4.5000e-0C39 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Enery Activity Ftuence Rate FluneRt Exposure Rate Exoosure Rate MeV photons/sec MeV/cm 2/sec MeV/cm 2/sec mR/hr naR/hr No Buildup With Buildup No Buildup With Buildup

)4 6.181e-01 1.978e-40 1.243e-33 8.748e.43 5.497e-36 C1-69

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page :2 DOS File : PB122113.MS5 Run Date: December 21, 2005 Run Time: 1:50:31 PM Duration : 00:00:01 Energy Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm 2/sec MeV/cm 2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.05 1.570e-01 5,666e.29 5.536e-28 1.509e-31 1.475e-30 0.1 1.229e+00 3.980e- 16 2.410e-14 6.089e-19 3.687e-17 0.2 2.074e-01 4.131e-14 3.456e-12 7.292e-17 6.099e-15 0.4 2.167e-02 2.117e-13 9.220e-12 4.124e-16 1.796e-14 0.5 6.576e-03 1.988e-13 6.440e-12 3.901e-16 1.264e-14 0.6 2.450e.01 1.803e- 11 4.563e.10 3.519e-14 8.906e-13 0.8 1.184e+00 3,37le,10 5.759e-09 6.411e-13 1.095e- 11 1.0 9.343e-01 7.256e-10 9.166e-09 1.337e-12 1.690e-11 1.5 1.185e+00 5.057e-09 3.897e-08 8.508e-12 6.557e-1 1 TOTALS: 5.789e+00 6.138e-09 5.437e-08 1.052e- 11 9.434e-11 C]-70

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 licroShield v5.04 (5.04-00362) 12/21/0 MicroShield v5.04 (5.04-00362)

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Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122113.MS5 Case

Title:

Line 1.24 D This case was run on Wednesday, December 21, 2005 at 1:50:31 PM Dose Point # 1 - (134.97,381,91.44) cm Results (Summed over energies) Units Without With Qilidup Photon Fluence Rate (flux) Photons/cm2/sec 4.549e-009 4.316e-008 Photon Energy Fluence Rate MeV/cm 2/sec 6.138e-009 5.437e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 1.052e-011 9.434e-011 Absorbed Dose Rate in Air mGy/hr 9.186e-014 8.236e-013 mrad/hr 9.186e-012 8.236e-011 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.043e-013 9.376e-013 o Opposed 9.036e-014 8.075e-013 o Rotational 9.036e-014 8.075e-013 o Isotropic 8.090e-014 7.218e-013 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.106e-013 9.952e-013 o Opposed 1.068e-013 9.598e-013 o Rotational 1.068e-013 9.598e-013 o Isotropic 8.533e-014 7.628e-013 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 9.389e-014 8.432e-013 o Posterior/Anterior 8.680e-014 7.767e-013 o Lateral 6.966e-014 6.193e-013 o Rotational 7.83le-014 7.00le-013 o Isotropic 6.957e-014 6.197e-013 Page CI-71

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

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Page :1 File Ref:

DOS File : PB122114.MS5 Date:

Ru ate: December 21, 2005 By:

Runr-rime: 2:10:25 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.24 E

Description:

Revised Model Calc Ag-108m Unit Act w Sched 40 & 12 in ShIld Geometry: 10 - Cylinder Surface - External Dose Point

~~II +

Source Dimensions Height 762.0 cm 25 ft Radius 3.81 cm 1.5 in Dose Points X Y z

1. 1 134.97 crmn 381 cm 91.44 cm 4 ft 5.1 n 12 ft 6.0 in 3 ft Shields Shield Name Dimension Mat erial Density Cyl. Core 3.81 cm 2 Conc:rete 1.8 Shield 1 .65 cm It on 7.86 z Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Standard Indices Number of Groups 25 Lower Energy Cutoff : 0.015 Photons.< 0.015 : Excluded Library : Grove Nuclide curi es becguerels mi/gf2i gq/cm 2 Ag-108m 8.2087 e-011 3.0372c+000 4.5000e-0 09 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm 2/sec M eV/CM 2/sec mR/hr mR/hr No Buildup withLaW1 Buildu No Buildup With Buildup

)2 1.992e+00 1.913e-206 6.83 le-34 6.626e-208 2.366e-35 CJ-72

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Page :2 DOS File : PB122114.MS5 Run Date. December 21, 2005 Run Time: 2:10:25 PM Duration : 00:00:01 Energy Activty Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm 2/sec MeV/cm 2/sec mR/hr mR/hr No Buildup With uildup No Buildup With Buildup 0.03 6.449e-07 1.192e-79 4.890e-40 1.182e-81 4.846e-42 0.08 2.152e.01 9.096e-19 3.469e- 17 1.439e-21 5.489e-20 0.4 2.730e+00 2.666e- 11 1.161e.09 5.195e-14 2.263e-12 0.6 2.745e+00 2.021e-10 5.113e-09 3.944e-13 9.98le-12 0.8 2.749e+00 7.822e.10 1.336e-08 1.488e-12 2.542e-1 1 TOTALS: 1.043e+01 1.0 l1e-09 1.964e-08 1.934e-12 3.766e-1 1 C1-73

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Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122114.MS5 Case

Title:

Line 1.24 E This case was run on Wednesday, December 21, 2005 at 2:10:25 PM Dose Point # 1 - (134.97,381,91.44) cm Results (Summed over energies) Units Without Buildup Photon Fluence Rate (flux) Photons/cm /sec 1.381e-009 2.813e.008 Photon Energy Fluence Rate MeV/crr 2/sec 1.011 e-009 1.964e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 1.934e-012 3.766e-01 1 Absorbed Dose Rate in Air mGy/hr 1.689e-014 3.288e-013 mrad/hr 1.689e-012 3.288e-011 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1,.982e-014 3.875e-013 o Opposed 1.610e.014 3.129e-013 o Rotational 1 .610e.014. 3.129e-013 o Isotropic *1.423e-014 2.767e-013 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 2.114e-014 4.125e-013 o Opposed 2.013e-014 3.926e-013 o Rotational 2.013e-014 3.926e,013 o Isotropic 1.523e-014 2.960e-013 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 1 .760e-014 3.436e-013 o Posterior/Anterior 1.567e-014 3.051e-013 o Lateral 1.178e-014 2.282e-013 o Rotational 1.402e-014 2.726e-013 o Isotropic 1.20le-014 2.331e-013 Page 1 C1-74

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File : PB122115.MS5 Date:

Ru ate: December 21, 2005 By:

Ruh--Time: 2:04:46 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.24 F

Description:

Revised Model CaIc. - Nb-94 Unit Act w Sched 40 & 12 in Sh Geometry: 10 - Cylinder Surface - External Dose Point Sour ce Dimensions Height 762.0 cm 25 ft Radius 3.81 cm 1.5 in Dlose Points

• x z

1. 1 134.97 cm 381 cm 91.44 cm 4 ft 5.1 in 12 ft 6.0 in 3ft Shields Shield Name Din: enein Material Density Cyl. Core 3. 31 cm 2 Concrete 1.8 Shield 1 65 cm Iron 7.86 Transition Concrete 2.4 Shield 3 30. 48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .0)25 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies Nuclide curies becauerels uci/cm2 B1/cm 2 Nb-94 8.2087e-011 3.0372e+000 4.5000e-009 1 .6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activity. Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm 2/sec MeV/cm 2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.0174 1.074e-03 4.704e-307 2.957e-37 2.539e.308 1.596e-38 0.0175 2.057e-03 9.585e-302 5.718e-37 5.076e.303 *3.028e-38 0.0196 6.044e-04 1.268e-221 2.009e.37 4.682e.223 7.416e-39 0 7026 3.037e+00 4.733e-10 9.655e-09 9.128e-13 1.862e-11 711 3.037e+00 1.274e-09 1.937e-08 2.397e- 12 3.646e-11 C1- 75

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Page :2 DOS File : PB122115.MS5 Run Date: December 21, 2005 Run Time: 2:04:46 PM Duration : 00:00:01 MnergV Fluence Rate Fluence Rate Exposure Rate Exposure Rate photons/sec MeV/cm 2/sec MeV/cm 2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup TOTALS: 6.078e+00 1.747e-09 2.903e-08 3.310e.12 5.508e- 11 C1-76

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 VlicroShield v5.04 (5.04-00362) 12/21/05 MicroShleld v5.04 (5.04-00362)

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Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122115.MS5 Case

Title:

Line 1.24 F This case was run on Wednesday, December 21, 2005 at 2:04:46 PM Dose Point # 1 - (134.97,381,91.44) cm Results (Summed over energies) Without With Buildup Photon Fluence Rate (flux) Photons/cm 2/sec 2.136e-009 3.598e-008 Photon Energy Fluence Rate MeV/cm 2/sec 1.747e-009 2.903e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 3.310e-012 5.508e-011 Absorbed Dose Rate in Air mGy/hr 2.890e-014 4.808e-013 mrad/hr 2.890e-012 4.808e-011 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 3.362e-014 5.600e-013 o Opposed 2.768e-014 4.602e-013 o Rotational 2.768e-014 4.602e-013 o Isotropic 2.447e-014 4.069e-013 Shallow Dose Equivalent Rate (ICRP 51 -1987) o Parallel Geometry mSv/hr 3.595e-014 5.986e-013 o Opposed 3.430e-014 5.710e-013 o Rotational 3.430e-014 5.710e-013 o Isotropic 2.619e-014 4.354e-013 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 2.996e-014 4.989e-013 o Posterior/Anterior 2.688e-014 4.470e.013 o Lateral 2.042e-014 3.391e-013 o Rotational 2.406e-014 4.002e-013 o Isotropic 2.073e-014 3.445e-013 Page 1 C1-77

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

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Page :1 File Ref:

DO.q File : PB122909.MS5 Date:

RL ate: December 29, 2005 By:

Run-Time: 2:36:06 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.24 G

Description:

Revised Model Calc. 129 Unit Act w Sched 40 & 12 in Shid Geometry: 10 - Cylinder Surface - External Dose Point SX Source Dimensions Height 762.0 cm 25 ft Radius 3.81 cm 1.5 in E)ose Points x y z

1. 1 134.97 cm 381 cm 91.44 cm 4 ft 5.1 in 12 ft 6.0 in 3 ft Shields Shield Name Din nension Material Density Cyl. Core 3. 81 cm 2 Concrete 1.8 Shield 1 .65 cm Iron 7.86 Transition Concrete 2.4 Shield 3 30 .48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad 'C125 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies Nuclide curies becquerels "Ci/cmZ 6q/cm2 1-129 8.2087e-01 1 3.0372e+000 4.5000e-009 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activity Fluence Rate FLuence Rate Exoosure Rate Exlposure Rate MeV phoonsse MeV/cm 2/sec mR/hr mR/hr No Buildup No Buildup) withffIcu With Buildup 0.0295 6.061e-01 6.977e-77 4.366e-34 7.301e.79 4.569e-36 0.0298 1. 124e+00 1.092e-74 8.349e-34 1.107e-76 8.458e-36 0.0336 3.998e-01 2.344e-57 4. 359e. 34 1.667e-59 3.100e.36 0 0396 2.284e-01 1.196e-41 4.431 e-34 5.435e-44 2.013e-36 01C-78

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 Page :2 DOS File : PB122909.MS5 Run Date: December 29, 2005 Run Time: 2:36:06 PM Duration : 00:00:01 Energy Activity Fluence Rate Fluence Rate Exposure Rate Exoosure Rate TTL 2hotons/sec MeV/cm2/sec MeV/cm 2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup TOTALS: 2.359e+00 1. 196e-41 2.150e-33 5.435e-44 1.814e-35 Cl-79

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/29/05 MicroShield v5.04 (5.04-00362)

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Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122909.MS5 Case

Title:

Line 1.24 G This case was run on Thursday, December 29, 2005 at 2:36:06 PM Dose Point # 1 - (134.97,381,91.44) cm Units Without With Buildup QuilduI Photon Fluence Rate (flux) Photons/cm 2/sec 3.022e-040 6.702e-032 Photon Energy Fluence Rate MeV/cm 2/sec 1.196e-041 2.150e-033 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 5.435e-044 1.814e-035 Absorbed Dose Rate in.Air mGy/hr 4.745e-046 1.584e-037 mrad/hr 4.745e-044 1.584e-035 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 6.792e-046 1.813e-037 o Opposed 3.42le-046 9.094e-038 o Rotational 3.097e-046 7.757e-038 o Isotropic 2.963e-046 7.205e-038 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 6.834e-046 1.976e-037 o Opposed 4.717e-046 1.359e-037 o Rotational 4.717e-046 1.359e-037 o Isotropic 3.462e-046 1.004e-037 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 3.960e-046 8,128e-038 o Posterior/Anterior 2.394e-046 4,203e-038 o Lateral 1.322e-046 2.268e-038 o Rotational 2.153e-046 4.176e-038 o Isotropic 1.764e-046 3.460e-038 Page 1 C1-80

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShleld v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File : PB122911.MS5 Date:

RL ate: December 29, 2005 By:

Run -fime: 2:42:27. PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.24 I

Description:

Revised Model Calc - Zr-95 Unit Act w Sched 40 & 12 in ShId Geometry: 10 - Cylinder Surface - External Dose Point Source Dimensions Height 762.0 cm 25 ft Radius 3.81 cm 1.5 in C)ose Points y z

1. 1 134.97 cm 381 cm 91.44 cm 4 ft 5.1 in 12 ft 6.0 in 3ft Shields Shield Name Dirnnension M~ate.ral Density Cyl. Core 3. 81 cm 2 Concrete 1.8 Shield 1 .65 cm Iron 7.86 Transition Concrete 2.4 Shield 3 30 .48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad '0125 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies N becauerels MCI/=

Zr-95 8.2087e-011 3.0372e+000 4.5000e-009 1.6650e-004 Buildup The material reference is : Cyl. Core integration Parameters Y Direction (axial) 20 Circumferential 20 Results Ene*gy Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV 1ohotons/sec MeV/cm 2/sec MeV/crML 2

/seC mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.7242 1.326e+00 2.380e-10 4.659e-09 4.577e-13 8.958e-12 0,7567 1.681e+00 3.702e-10 6.824e-09 7.085e-13 1.306e-11 TOTALS: 3.007e+00 6.082e-10 1.-148e08 1.166e-12 2.202e- 11 CI-81

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 icroShleld v5.04 (5.04-00362) 12/29/0e MicroShield v5.04 (5.04-00362)

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Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122911.MS5 Case

Title:

Line 1.24 1 This case was run on Thursday, December 29, 2005 at 2:42:27 PM Dose Point # 1 - (134.97,381,91.44) cm Results (Summed over energies) Unila Without With Builduo2 Photon Fluence Rate (flux) Photons/cm 2/sec 8.178e-010 1.545e-008 Photon Energy Fluence Rate MeV/cm 2/sec 6.082e-010 1. 148e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 1.166e-012 2.202e-01 1 Absorbed Dose Rate in Air mGy/hr 1.018e-014 1.922e-013 mrad/hr 1.018e-012 1.922e-011 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.193e-014 2.254e-0 13 o Opposed 9.705e-015 1.832e-013 o Rotational 9.705e-015 1.832e-013 o Isotropic 8.578e-015 1.620e-013 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.274e-014 2.406e-013 o Opposed 1.214e-014 2.292e-013 1*

o Rotational 1.214e-014 2.292e-013 o Isotropic 9.181e-015 1.733e-013 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 1.060e-014 2.00le-013 o Posterior/Anterior 9.441e-015 1.783e-013 o Lateral 7.098e-015 1.340e-013 o Rotational 8.444e-015 1.594e-013 o Isotropic 7.233e-015 1.366e.013 Page 1 C]-82

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

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Page :1 File Ref:

DOS File : PBO10403.MS5 Date:

RL. ate: January 4, 2006 By:

Run-Time: 7:59:23 AM Checked:

Duration : 00:00:01 Case

Title:

Line 1.24 H

Description:

Revised Model Calc - Sn-126 Unit Act w Sched 40 & 12 in ShId Geometry: 10 - Cylinder Surface - External Dose Point Source Dimensions Height 762.0 cm 25 ft Radius ' 3.81 cm 1.5 in Dose Points x Y z

1. 1 134.97 crmn 381 cm 91.44 cm 4 ft 5.1i n 12 ft 6.0 in 3ft Shields Shield Name Dimension Mat erial Density Cyl. Core 3.81 cm 2 Con crete 1.8 Shield 1 .65 cm Ir on 7.86 7

Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Library : Grove Nuclide curigss be30 uerels 4.50 0e B1/CM 2 Sn-126 8.2087e- Oil 3.0372e+000 4.5000e-0(09 1.6650e.004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results EnerActivity Fluence Rate Fluence Rate Exposure Rate Exposure RatC.

MeV photons/sec MeV/cm 2/sec MeV/cm 2/sec mR/hr mR/hr

.No Buildup With Buildup No Buildup With Buildup

)2 2.351e-01 2.258e.207 8.062e-35 7.820e-209 2.792e-36 C]-83

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Page :2 DOS File :.PBO10403.MS5 Run Date: January 4, 2006 Run Time: 7:59:23 AM Duration : 00:00:01 Enrgy Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV MeV/cm 2 /sec MeV/cm 2/sec naR/hr No Buildp With Buildup No Buildup With Buildup 0.03 8.893e-01 1.644e-73 6.743e-34 1.630e-75 6.683e-36 0.04 .1.517e-02 4.854e-42 3.051e-35 2.147e-44 1.349e-37 0.06 2.911 e-01 3.017e-23 5.881e-22 5.993e-26 1.168e-24 0.08 1.395e+00 5.894e-18 2.247e-16 9.326e-21 3.557e-19 TOTALS: 2.825e+00 5.894e-18 2.247e-16 9.327e-21 3.557e-19 CI-84

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 01/04/06 MicroShield v5.04 (5.04-00362)

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Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PBO10403.MS5 Case

Title:

Line 1.24 H This case was run on Wednesday, January 4, 2006 at 7:59:23 AM Dose Point # 1 - (134.97,381,91.44) cm Results (Summed over energies) Units Without With Photon Fluence Rate (flux) Photons/cm 2/sec 7.367e-017 2.809e-015 Photon Energy Fluence Rate MeV/cm 2/sec 5.894e-018 2.247e-016 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 9.327e-021 3.557e-019 Absorbed Dose Rate in Air mGy/hr 8.142e-023 3.105e-021 mrad/hr 8.142e-021 3.105e-019 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.424e-022 5.431e.021 o Opposed 7.585e-023 2.893e-02 1 o Rotational 7.373e-023 2.812e-021 o Isotropic 7.320e-023 2.791e-021 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.41 le-022 5.380e-021 o Opposed 1.037e-022 3.954e-021 o Rotational 1.037e-022 3.954e-021 o Isotropic 7.612e-023 2.903e-021 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 1.196e-022 4.561e-021 o Posterior/Anterior 9.123e-023 3.479e-021 o Lateral 5.623e-023 2.144e-021 o Rotational 7.77le-023 2.963e-021 o Isotropic 6.286e-023 2.397e-021 Page 1 C1-85

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

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Page :1 File Ref:

DOS File : PB122912.MS5 Date:

RL ate: December 29, 2005 By:

Run-Time: 2:45:53 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.24 J

Description:

Revised Model Calc - Eu-155 Unit Act w Sched 40 & 12 in Shid Geometry: 10 - Cylinder Surface - External Dose Point

-I- x Source Dimensions Height 762.0 cm 25 ft Radius 3.81 cm 1.5 in Dose Points Z

1. 1 134.97( 381 cm 91.44 cm 4 ft 5.1 in 12 ft 6.0 in 3 ft Shields Shield Name Dimension Mate*ria* Density Cyl. Core 3.81 cm 2 Conc rete 1.8 Shield 1 .65 cm Ira 7.86 z

Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method ; Standard Indices Number of Groups : 25 Lower Energy Cutoff 0.015 Photons < 0.015 : Excluded Library : Grove Nuclide curies becauerels wCi/cm Eu.155 8,2087e- 011 3.0372e+000 4.5000e.OC )9 1.6650e.004 Buildup The material reference is Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm 2/sec MeV/cml/sec mR/hr No Buildua With Buildup No Builduo With Buildup

)3 9.667e.03 1.787e-75 7.330e-36 1.771e-77 7.264e-38 CJ-86

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page :2 DOS File : PB122912.MS5 Run Date: December 29, 2005 Run Time: 2:45:53 PM Duration : 00:00:01 Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm2/sec MeV/cmz/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.04 5.505e-01 1.762e-40 1.107e-33 7.79le-43 4.896e-36 0.05 1.791e-01 6.462e-29 6.313e-28 1.721e-31 1.682e-30 0.06 3.939e-02 4.083e-24 7.960e-23 8.110e-27 1.581e-25 0.08 9.43!e-01 3.986e-18 1.520e-16 6.307e-21 2.405e-19 0.1 6.279e.01 2.033e-16 1.231e-14 3.11 le-19 1.884e- 17 TOTALS: 2.350e+00 2.073e-16 1.246e-14 3.174e- 19 1.908e-17 CJ-87

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/29/05 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122912.MS5 Case

Title:

Line 1.24 J This case was run on Thursday, December 29, 2005 at 2:45:53 PM Dose Point # 1 - (134.97,381,91.44) cm Repsuits (Summed over enerpiesp Unit Without With Buildlug Buildup Photon Fluence Rate (flux) Photons/cm 2/sec 2.083e-015 1.250e-013 Photon Energy Fluence Rate MeV/cm 2/sec 2.073e-016 1.246e-014 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 3.174e-019 1.908e-017 Absorbed Dose Rate in Air mGy/hr 2.77le-021 1.665e-019 mrad/hr 2.77le-019 1.665e-01 7 Deep Dose Equivalent Rate (ICRP 51 . 1987) o Parallel Geometry mSv/hr 4.635e-021 2.785e-019 o Opposed 2.540e-021 1.526e-019 o Rotational 2.539e-021 1.526e-019 o Isotropic 2.458e-021 1,477e-019 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 4.604e-021 2.767e-019 o Opposed 3.569e-021 2.145e-019.

o Rotational 3.569e-021 2.145e-019 o Isotropic 2.599e-021 1.562e-019 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 3.982e-021 2.393e-019 o Posterior/Anterior 3.121e-021 1.876e-019 o Lateral 1.926e-021 1.158e-019 o Rotational 2.666e-021 1.602e-019 o Isotropic 2.12le.021 1.275e-019 Page 1 C1-88

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File : PB121911.MS5 Date:

Rt )ate: December 19, 2005 By:

Run"Time: 11:14:14 AM Checked:

Duration : 00:00:01 Case

Title:

Line 1.25 A2

Description:

Revised Model Catc. - Co-60 Unit Act w Sched 40 & 12 in Shid Geometry: 10 - Cylinder Surface - External Dose Point ource Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in Dose Points X Y z

1. 1 138.78 cm 381 cm 137.16 cm 4 ft 6.6 in 12 ft 6.0 in 4 ft 6.0 in Shields Shield Name Dimension Material Density Cyl. Core 7.62 cm 2 Concrete., 1.8 Shield 1 .65 cm Iron 7.86 a

z transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energ ies Nuclide curies becuerels im Co-60 1.6417e-010 6,0744e+000 4.5000e-OC)9 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm2/sec MeV/cm 2/sec mR/hr r-R/hr No Buildup With Buildup No Buildup WithiBuildup 0.6938 9.909e.04 1.9516.14 5.213e-13 3.766e-17 1.006e-15 1,1732 6,074e+00 1,764e.09 2.250e-08 3.151e-12 4.022e- 11 1.3325 6.074e+00 3.243e-09 3.513e-08 5.627e-12 6.095e- 11

.'ALS: 1.215e+01 5.007e-09 5.764e-08 8.778e-12 1.012e-10 C1-89

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/19/05 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB121911.MS5 Case

Title:

Line 1.25 A2 This case was run on Monday, December 19, 2005 at 11:14:14 AM Dose Point # 1 - (138.78,381,137.16) cm Results (Summed over energies) Units Without Buildup With Photon Fluence Rate (flux) Photons/cm 2/sec 3.937e-009- 4.555e-008 Photon Energy Fluence Rate MeV/cm./sec 5.007e-009 5.764e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 8.778e-012 1.012e-010 Absorbed Dose Rate in Air mGy/hr 7,663e-014 8.832e-013 mrad/hr 7.663e-012 8.832e-011 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 8.699e-014 1.003e-012 o Opposed 7.495e-01 4 8.636e-013 o Rotational 7.495e-014 8.636e-013 o Isotropic 6.696e-014 7.714e-013 Shallow Dose Equivalent Rate (ICRP 51 -1987) o Parallel Geometry mSv/hr 9.259e-014 1.067e-012 o Opposed 8.91 6e-01 4 1.028e-012 o Rotational 8.916e-014 1.028e-012 o Isotropic 7.093e-014 8.173e-013 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 7.834e-014 9.030e-013 o Posterior/Anterior 7.218e-014 8.318e-013 o Lateral 5.743e-014 6.614e-013 o Rotational 6.500e-014 7.489e-013 o Isotropic 5.754e-014 6.628e-013 Page 1 C]-90

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page  : 1 File Ref:

DO" rile : PB122116.MS5 Date:

Ru ate: December 21, 2005 By:

Run Time: 2:17:24 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.25 B Descri ption: Revised Model Calc - Cs-137 Unit Act w Sched 40 & 12 in Shid Geometry: 10 - Cylinder Surface - External Dose Point lwý iX "-

Sour ce Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in Dlose Points x Y_ z

1. 1 138.78 cm 381 cm 137.16 cm 4 ft 6.6 in 12 ft 6.0 in 4 ft 6.0 in Shields Shield Name Din"nension Mat eria IDest Cyl. Core 7.162 cm 2 Conc :ret(e 1.8 Shield 1 65 cm Ire Dn 7.86 Transition Concret e 2,4 Shield 3 30. 48 cm Concret e 2.4 Air Gap Air 0,00122 Wall Clad .0'25 cm Iron 7,86 Source Input Grouping Method : Actual Photon Energies Nuclide curies becquerels$ Ci/cm 2 Ba-137m 1.5531e-010 5.7464e+000 4.2570e-009 1.5751e-004 Cs-137 1.6417e-010 6.0744e+000 4.5000e-009 1.6650e.004 Buildup The material .reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Fne riz Activity Fluence Rate Flu once Ra to Exp2osure Rate Exposure Rate MeV photons/sec MeV/cm2/sec MeV/hm./sL mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.0318 1.190e-01 2.257e-73 8.498e-35 1.880e-75 7.078e-37 0.0322 2.195e-01 3.354e-71 1.629e-34 2.699e-73 1.311e-36 P '1364 7.987e-02 2.920e-55 9.080e-35 1.659e-57 5.159e-37

,_316 5.171e+00 7.886e- I1 2.257e-09 1.529e-13 4.375e-12 CJ-9]

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Page :2 DOS File : PB122116.MS5 Run Date: December 21, 2005 Run Time: 2:17:24 PM Duration : 00:00:01 E~nergv Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm2/sec MeV/c2m/sec mR/hr No Buildup With Buildup No Buildup With Buildup TOTALS: 5.589e+00 2.257e-09 7.886e' 11 1.529e-13 4.375e-12 C1-92

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/21/05 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122116.MS5 Case

Title:

Line 1.25 8 This case was run on Wednesday, December 21, 2005 at 2:17:24 PM Dose Point # 1 - (138.78,381,137.16) cm Results (Summed over energies) units Withou With Buildup2 Buildup Photon Fluence Rate (flux) Photons/cma/sec 1.192e-010 3.411e-009 Photon Energy Fluence Rate MeV/cm 2/sec 7.886e-011 2.257e-009

• Exposure and Dose Rates:

Exposure Rate in Air mR/hr 1.529e-013 4.375e-012 Absorbed Dose Rate in Air mGy/hr 1.335e-015 3.819e-014 mrad/hr 1.335e-013 3.819e-012 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.580e-015 4.522e-014 o Opposed 1.265e-015 3.620e-014 o Rotational 1.265e-015 3.620e-014 o Isotropic 1.119e-015 3.201e-014 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.680e-015 4.806e-014 o Opposed 1.595e-015 4.565e-014 o Rotational 1.595e-015 4.565e-014 o Isotropic 1.196e-015 3.422e-014 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 1.397e-015 3.998e-014 o Posterior/Anterior 1.233e-015 3.529e-014 o Lateral 9.146e-016 2.617e-014 o Rotational 1.102e-015 3.154e-014 o Isotropic 9.383e-016 2.685e-014 Page 1 C1-93

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 MicroShield V5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File : PB122117.MS5 Date:

RL ate: December 21, 2005 By:

Rurf Time: 2:23:34 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.25 C

Description:

Revised Model Calc Eu-152 Unit Act w Sched 40 & 12 in Shld Geometry: 10 - Cylinder Surface - External Dose Point I~*~Ij x ource Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in Dose Points X Y z

1. 1 138.78 cm 381 cm 137.16 cm 4 ft 6.6 in 12 ft 6.0 in 4ft 6.0 in Shields Shield Name Dimension Mate.rialI Density Cyl. Core 7.62 cm2 Conc retee 1.8 Shield 1 .65 cm fro)n 7.86 Transition Concretee 2.4 Shield 3 30.48 cm Concretee 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Library : Grove Nucide curie5 becquerels WCi/cm B1/cm-Eu.152 1.6417e- 010 6.0744e+000 4.5000e-0(09 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Ene~rgy. Activity Fluence Rate Flue~nce Rate Exposure Rate Exposure Rate MeV ohotons/sec MeV/cm 2/sec MeV/cm 2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 34 3,594e+00 1.705e-44 5.683e-33 7.540e-47 2.514e-35 CJ-94

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Page :2 DOS File : PB122117.MS5 Run Date: December 21, 2005 Run Time: 2:23:34 PM Duration : 00:00:01 Mnerg Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm 2/sec MeV/cm 2/sec mR/hr mR/hr No Buildup With Buildup No Quildun With Buildup 0.05 8.987e-01 2.286e-31 2.318e-30 6.091e-34 6.175e-33 0.1 1.727e+00 1.425e-17 1.080e- 15 2.179e-20 1.653e- 18 0.2 4.552e-01 5.009e-15 5.689e-13 8.840e-18 1.004e.15 0.3 1.642e+00 2.624e-13 2.178e-II 4.978e- 16 4.132e-14 0.4 3.817e-01 3.443e-13 2.007e-11 6.708e-16 3.911e-14 0.5 3.426e-02 1.1 16e-13 4.775e-12 2.190e-16 9.372e- 15 0.6 2.576e.-01 2.309e-12 7.607e-11 4.506e-15 1.485e- 13 0.8 1.082e+00 4.526e-1 1 9.859e- 10 8.608e- 14 1.875e-12 1.0 2.599e+00 3.419e-10 5.424e-09 6.302e- 13 9.998e-12 1.5 1.409e+00 1.299e-09 1.218e-08 2.185e-12 2.050e- 11 TOTALS: 1.408e+01 1.689e-09 1.872e-08 2.907e-12 3.261e-11 C1-95

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/21/05 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122117.MS5 Case

Title:

Line 1.25 C This case was run on Wednesday, December 21, 2005 at 2:23:34 PM Dose Point # 1 - (138.78,381,137.16) cm Results (Summed over energies) Units- Without With Buildup Buildup Photon Fluence Rate (flux) Photons/cm 2/sec 1,270e-009 1.504e-008 Photon Energy Fluence Rate MeV/cm 2/sec 1.689e-009 1.872e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 2.907e-012 3.261e-011 Absorbed Dose Rate in Air mGy/hr 2.538e-014 2.847e-013 mrad/hr 2.538e-012 2.847e-O011 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 2.882e-014 3.242e-013 o Opposed 2.494e-014 2.789e-013 o Rotational 2.494e-014 2.789e-013 o Isotropic 2.232e-014 2.491e-013 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geomotry mSv/hr 3.058e-014 3.443e-013 o Opposed 2.952e-014 3.318e-013 o Rotational 2.952e-014 3.318e-013 o Isotropic 2.356e-014 2.635e-013 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 2.595e-014 2.915e-013 o Posterior/Anterior 2.397e-014 2.684e-013 o Lateral 1.920e-014 2.136e-013 o Rotational 2.162e-014 2.418e-013 o Isotropic 1.919e-014 2.139e-013 Page 1 CI-96

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File : PB122118.MS5 Date:

Ru ate: December 21, 2005 By:

Run Time: 2:24:58 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.25 D

Description:

Revised Model Calc - Eu-154 Unit Act w Sched 40 & 12 in ShId Geometry: 10 - Cylinder Surface - External Dose Point I --41tL~iA-1 X ---- ---

ource Dimensions Height 762.0 cm 25ft Radius 7.62 cm 3.0 in Dose Points Y z

1. 1 138.78 cm 381 cm 137.16 cm 4 ft 6.6 in 12 ft 6.0 in 4 ft 6.0 in Shields Shield Name Dimension Mate ria I Density Cyl. Core 7.62 cm 2 Conciret e 1.8 Shield 1 .65 cm Iro n 7.86 0

Transition Concret e 2.4 Shield 3 30.48 cm Concret e 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Library : Grove Nuclide curi es becquerels Li/Lm Eu-154 1.6417e- 010 6.0744e+000 4.5000e-0C)9 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Eneriz Ac[tivi Fluence Rate Fluence Rate Exposure Rate Exposure Rate Mev photons/sec MeV/cm 2/sec MeV/cm 2/sec mR/hr mR/hr o.8a6ildup4 With -BuiLd Lip N-oBuiLdtup_ With Buildup

)34 1.236e+00 5.864e-45 1.955e-33 2,593e.47 8.646e-36 C]-97

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page :2 DOS File : PB122118.MS5 Run Date: December 21, 2005 Run Time: 2:24:58 PM Duration : 00:00:01 EVer hoton/ivity Fluence Rate f1wenceRat Exposure Rate Exposure Rate MV photons/sec MeV/cml/sec MeV/cm 2/sec mR/hr No Buildup WithBildu No Buildup With Buildup) 0.05 3.140e-01 7.989e-32 8.099e-31 2.128e-34 2.158e-33 0.1 2.458e+00 2.027e-17 1.538e-15 3.102e-20 2.352e-18 0.2 4.148e-01 4.565e-15 5.184e-13 8.056e-18 9.150e-16 0.4 4.334e-02 3.909e-14 2.279e-12 7.616e-17 4.440e.15 0.5 1.315e-02 4.282e-14 1.833e-12 8.405e-17 3.597e-15 0.6 4.900e-01 4,391e-12 1 .447e- 10 8.571e.15 2.824e- 13 0.8 2.369e+00 9.912e-11 2.159e-09 1.885e-13 4.107e-12 1.0 1.869e+00 2.458e- 10 3.900e-09 4.531e-13 7.188e-12 1.5 2.370e+00 2.185e-09 2.049e-08 3.675e-12 3.448e- 11 TOTALS: 1.158e+01 2.534e-09 2,670e-08 4.326e.12 4.607e- 11 CI-98

Plum Brook ReactorFacility Final Status Survey Plan Revision 0

/licroShield v5.04 (5.04-00362) 12/21/01 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Conversion of calculated exposure in air to dose FILE: C: \MS5\DATA\PB122118.MS5 Case

Title:

Line 1.25 D This case was run on Wednesday, December 21, 2005 at 2:24:58 PM Dose Point # 1 - (138.78,381,137.16) cm Results (Summed over energies) Units Withopt Buildup Mldwit Photon Fluence Rate (flux) Photons/cm 2/sec 1.834e-009 2.051e:008 Photon Energy Fluence Rate MeV/cmr/sec 2.534e-009 2.670e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 4.326e-012 4.607e-011 Absorbed Dose Rate in Air mGy/hr 3.777e-014 4.022e-013 mrad/hr 3.777e-0.12 4.022e-O1 1 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 4.283e.014 4.572e-013 o Opposed 3.719e-014 3.949e-013 o Rotational 3.719e-014 3.949e-013 o Isotropic 3.331e-014 3.533e-013 Shallow Dose Equivalent Rate (ICRP 51 . 1987) o Parallel Geometry mSv/hr 4.539e-014 4.850e-013 o Opposed 4,387e-014 4.681e-013 o Rotational 4.387e-014 4.68le-013 o Isotropic 3.51le.014 3.730e-013 Effective Dose Equivalent Rate (ICRP 51 11987) o Anterior/Posterior Geometry mSv/hr 3.858e-o14 4.114e-013 o Posterior/Anterior 3.571e-014 3.796e-013 o Lateral 2.872e.014 3.036e-013 o Rotational 3.222e-014 3.423e-013 o Isotropic 2.866e-014 3.035e-013 Page 3 C1-99

Survey Plan Revision 0 Facility Reactor Facility Plum Brook Reactor FinalStatus Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File : PB122119.MS5 Date:

Ru ate: December 21, 2005 By:

RurfTime: 2:28:46 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.25 E

Description:

Revised Model CaIc- Ag-108m Unit Act w Sched 40 & 12 in Shid Geometry: 10 - Cylinder Surface - External Dose Point ource Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in Dose Points X Y z

1. 1 138.78 cm 381 cm 137.16cm 4 ft 6.6 in 12 ft 6.0 in 4ft 6.0 in Shields Shield Name Dimension Material Density Cyl. Core 7.62 cm 2 Concrete 1.8 Shield 1 .65 cm Iron 7.86 0

z Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Standard Indices Number of Groups 25 Lower Energy Cutoff : 0.015 Photons <0.015 : Excluded Library : Grove Nuclide 1curl es becquerels i/CM2 Bq/cm 2 Ag-108m 1.6417 e-010 6.0744e+000 4.5000e.0' 09 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/crn2/sec LLeYLQML5se aLbrL mRlhr No Buildup With Buildup No Buildup With Buildup 32 3.984e+00 3.279e-235 1.074e-33 1.136e-236 3.722e-35 C.1-100

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 Page :2 DOS File : PB122119.MS5 Run Date: December 21, 2005 Run Time: 2:28:46 PM Duration : 00:00:01 Eiiergy Activity Fluence Rate Fluence Rate Exposure Rate Exloosure Rate MeV photons/sec MeV/cm 2/sec MeV/cm2/sec nR/hr mR/hr No Buildup With Buildup No Buildup With Buildup2 0.03 1.290e-06 6.584e-89 7.691e-40 6.525e-91 7.622e-42 0.08 4.305e-01 2.739e-20 1.249e- 18 4.335e-23 1.976e-21 0.4 5.460e+00 4.924e- 12 2.87le-10 9.595e-15 5.594e-13 0.6 5.491e+00 4.921e-11 1.621e.09 9.606e. 14 3.165e-12 0.8 5.497e+00 2.300e-10 5.01 le-09 4.375e-13 9.531e-12 TOTALS: 2.086e+01 2.842e-10 6.920e-09 5.432e- 13 1.326e.11 C.-I10

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/21/05 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Conversion of calculated exposure in air to dose FILE: C:\MSS\DATA\PB122119.MS5 Case

Title:

Line 1.25 E This case was run on Wednesday, December 21, 2005 at 2:28:46 PM Dose Point # 1 - (138.78,381,137.16) cm Results (Summed over energies) Units Without With Buildup Buildup Photon Fluence Rate (flux) Photons/cm 2/sec 3.819e-010 9.684e-009 Photon Energy Fluence Rate MeV/cm 2/sec 2.842e.010 6.920e-009 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 5.432e-013 1.326e-01 1 Absorbed Dose Rate in Air mGy/hr 4.742e-0 15 1.157e-013 mrad/hr 4.742e-013 1.157e-011 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 5.557e-015 1.36le-013 o Opposed 4.523e-015 1.102e-013 o Rotational. 4.523e-015 1.102e-013 o Isotropic 3.998e-015 9.744e-014 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 5.93le-015 1.450e-013 o Opposed 5.65le-015 1.38le-013 o Rotational 5.65le-015 1.38le-013 o Isotropic 4.278e-015 1.042e-013 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 4.939e-015 1.208e-013 o Posterior/Anterior 4.402e-015 1.074e-013 o Lateral 3.313e-015 8.05le-014 o Rotational 3.937e-015 9.600e-014 o Isotropic 3.375e.015 8.215e-014 Page 1 C1-102

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File : PB122120.MS5 Date:

Ru ate: December 21, 2005 By:

Ruh Time: 2:32:47 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.25 F

Description:

Revised Model Calc- Nb-94 Unit Act w Sched 40 & 12 in Shld Geometry: 10 - Cylinder Surface - External Dose Point Sour ce Dimensions Height 762.0 cm 25ft Radius 7.62 cm 3.0 in Dlose Points Y z

1. 1 138.78 cm 381 cm 137.16 cm 4ft 6.6 in 12 ft 6.0 in 4 ft 6.0 in Shields Shield Name Din lension Mat( ~ria 2

Cyl. Core 7. 62 cm Conc retie 1.8 Shield 1 65 cm Irc3n 7.86 Transition Concret e 2.4 Shield 3 30. 48 cm Concret e 2.4 Air Gap Air 0.00122 Wall Clad .0'25 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies Nuclide curies becquerels W~i/CM2 Bq/cm2 Nb-94 1.6417e-010 6.0744e+000 4.5000e-009 1 .6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Mnerg h Activity Fluence Rate fluneRt .Exiposure Rate Exposure Rate MV photons/sec MeV/cml/sec MeV/cm 2/sec mR/hr mR/hr No Buildup With Buildup2 No Buildup With Buildup 0,0174 2.148e-03 0.O00e+00 4.650e-37 0.O00e+00 2.5 10e-38 0.0175 4.115e-03 0.O00e+00 8.994e-37 0.O00e+00 4.763e-38 0.0196 1.209e-03 4.082e-252. 3. 160e-37 1.507e-253 1.166e-38 0 7026 6.074e+00 1.279e-10 3.358e-09 2.467e-13 6.475e- 12 711 6.074e+00 3.955e-10 7.629e-09 7.444e- 13 1.436e-11 C]-103

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page :2 DOS File : PB122120.MS5 Run Date: December 21, 2005 Run Time: 2:32:47 PM Duration : 00:00:01 Ener FliuenceRate Fluence Rate Exposure Rate Exposure Rgate photons/sec MeV/CM 2/SeC MeV/cm 2/sec mR/hr mR/hr No Buildup With Buildup No Buildup2 With Buitdup TOTALS: 1.216e+01 5.235e-10 1.099e-08 9.911e-13 2.083e- 11 C1-104

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/21/05 MicroShield v5.04 (5.04-00362)

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Conversion of calculated exposure in air to dose FILE: CA\MS5\DATA\PB122120.MS5 Case

Title:

Line 1.25 F This case was run on Wednesday, December 21, 2005 at 2:32:47 PM Dose Point # 1 - (138.78,381,137.16) cm Results (Summed over energies) Units Without With Buildup Buildup Photon Fluence Rate (flux) Photons/cm2/sec 6.362e-010 1.354e.008 Photon Energy Fluence Rate MeV/cmz/sec 5.235e-010 1.099e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 9.911e-013 2.083e-011 Absorbed Dose Rate in Air mGy/hr 8.653e-015 1.819e-013 mrad/hr 8.653e-013 1.819e-011 Deep Dose Equivalent Rate (ICRP 51 -1987) o Parallel Geometry mSv/hr 1.006e-014 2.117e-013 o Opposed 8.289e-015 1.741e.013 o Rotational. 8.289e-015 1.741e-013 o Isotropic 7.330e-015 1.540e-013 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.076e-014 2.264e-013 o Opposed 1,027e-014 2.160e-013 o Rotational 1.027e-014 2.160e-013 o Isotropic 7.844e-01 5 1.648e-013 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 8.970e-015 1.887e-013 o Posterior/Anterior 8.049e015 1.691e-013 o Lateral 6.119e-015 1.284e-013 o Rotational 7.207e-015 1.514e-013 o Isotropic 6.210e-015 1.304e.013 Page 1 C1-105

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :I File Ref:

DOS File : PB122913.MS5 Date:

RL ate: December 29, 2005 By:

Rur-Time: 2:49:38 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.25 G

Description:

Revised Model Calc- 1-129 Unit Act w Sched 40 & 12 in Shid Geometry: 10 - Cylinder Surface - External Dose Point I- I I-ource Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in Dose Points X z

1. 1 138.78 cm 381 cm 137.16 cm 4 ft 6.6 in 12 ft 6,0 in 4 ft 6.0 in Shields Shield Name Dimension Mate Cyl. Core 7.62 cm? Conc ret e 1.8 Shield 1 .65 cm lrcrn 7.86 9

Transition Concret e 2.4 Shield 3 30.48 cm Concretee 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies Nuclide curiiicm beccuerels B1/cm-1.129 1.6417e-010 6.0744e+000 4.50O0e-009 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV ohotons/sec MeV/cm 2/sec MeV/cm 2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.0295 1.212e+00 1.333e-86 6.866e-34 1.395e-88 7.186e-36 0.0298 2.249e+00 3.950e-84 1 .313e-33 4.002e-86 1.330e-35 0.0336 7.995e-01 2.970e-64 6.856e-34 2.113e-66 4.876e-36 00396 4.568e.01 2.750e-46 6.969e-34 1,249e-48 3.167e-36 Cl -106

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 Page :2 DOS File : PB122913.MS5 Run Date: December 29, 2005 Run Time: 2:49:38 PM Duration : 00:00:01

,Fn rA c ivity Fluence Rate Exposure Rate Exposure Rate MeV ohotons/sec MeV/cm 2/sec MeV/cm2/sec mR/hr mR/hr With Buildup NO Buildup With Buildup TOTALS: 4.718e+00 2.750e-46 3.382e-33 1.249e-48 2.853e-35 C1-107

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/29/05 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122913.MS5 Case

Title:

Line 1.25 G This case was run on Thursday, December 29, 2005 at 2:49:38 PM Dose Point # 1 - (138.78,381,137.16) cm Results (Sur mied over energies) Units Without With Buildup Photon Fluence Rate (flux) Photons/cm2 /sec 6.947e-045 1.054e-031 Photon Energy Fluence Rate MeV/cm 2/sec 2.750e-046 3.382e-033 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 1.249e-048 2.853e-035 Absorbed Dose Rate in Air mGy/hr 1.091e-050 2.491e-037 n

mrad/hr 1.09le-048 2.491e-035 Deep Dose Equivalent Rate (ICRP,51 - 1987) o Parallel Geometry mSv/hr 1.561e-050 2.852e-037 o Opposed 7.864e-051 1.430e-037 o Rotational 7.120e-051 1.220e-037 o Isotropic 6.81 le-051 1.133e-037 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.57le-050 3.108e-037 o Opposed 1.084e-050 2.137e.037 o Rotational 1.084e-050 2.137e-037 o Isotropic 7.958e.051 1.580e-037 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 9.103e-051 1.278e-037 o Posterior/Anterior 5.503e-051 6.610e.038 o Lateral 3.040e-051 3.568e-038 o Rotational 4.948e-051 6.568e-038 o Isotropic 4.056e-051 5.441e-038 Page 1 CJ-108

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DO.q File : PBO10404;MS5 Date:

R. ate: January 4, 2.006 By:

Run Time: 8:04:03 AM Checked:

Duration : 00:00:01 Case

Title:

Line 1.25 H

Description:

Revised Model Calc- Sn-126 Unit Act w Sched 40 & 12 in Shid Geometry: 10- Cylinder Surface - External Dose Point

[

iz Source Dimensions Height 762.0 cm 25ft Radius 7.62 cm 3.0 in i

Dose Points x Y z

1. 1 138.78 c m 381 cm I 37.16 cm 4 ft 6.6 in 12 ft 6.0 in 4ft 6.0 in Shields Shield Name Dimension Material Density Cyl. Core 7.62 cm 2 Concrete 1.8 Shield 1 .65 cm Iron 7.86 z Transition Concrete 2.4 Shield 3. 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Library : Grove 2 Nuclide curies becauerels uC/*Cm Bg/cm2 Sn-126 1.6417e- 010 6.0744e+000 4.5000e-OC )9 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy A.Qtivity Fluence Rate Exposure Rate Exposure Rate MeVL photon s/sec MeV/cm 2/sec rnR/hr mR/hr No Buildup With Buildup No Buildup With Buildup

)2 4.702e-01 3.869e-236 1 .268e-34 1.340e-237 4.392e-36 C.1-]09

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page :2 DOS File : PBO10404.MS5 Run Date: January 4, 2006 Run Time: 8:04:03 AM Duration : 00:00:01 Energ Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate phot~ons/sec MeV/cm 2/sec MeV/cm 2/sec rnR/hr mR/hr No Buildup With Buildup No Buildup With Builduo 0.03 1.;779e+00 9.079e-83 1.061e-33 8.997e-85 1.05le-35 0.04 3.034e-02 1.439e-46 4.798e-35 6.365e-49 2.122e-37 0.06 5.82le-01 2.323e-25 5.459e-24 4.615e-28 1,084e-26 0.08 2.789e+00 1.775e-19 8.092e-18 2.809e-22 1.281e-20 TOTALS: 5.650e+00, 1.775e-19 8.092e-18 2.809e-22 1.281e-20 C.-ll0

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 01/04/06 MicroShield v5.04 (5.04-00362)

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Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB0O0404.MS5 Case

Title:

Line 1.25 H This case was run on Wednesday, January 4, 2006 at 8:04:03 AM Dose Point # 1 - (138.78,381,137.16) cm Results (Sum-nmed over energies) Units Without BuidII2 Photon Fluence Rate (flux) Photons/cm2 /sec 2.219e.018 1.012e-016 Photon Energy Fluence Rate MeV/cm 2/sec 1.775e-019 8.092e-018 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 2.809e.022 1.281e-020 Absorbed Dose Rate in Air mGy/hr 2.452e-024 1.118e-022 mrad/hr 2.452e-022 1.118e-020 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 4.289e-024 1.955e-022 11 o Opposed 2.284e-024 1.041e-022 o Rotational. 2.220e-024 .1.012e-022 o Isotropic 2.204e-024 1.005e-022 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 4.249e-024 1.937e-022 II o Opposed 3.123e-024 1.424e-022 o Rotational 3.123e-024 1.424e-022 o Isotropic 2.292e-024 1.045e-022 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 3.602e-024 1.642e-022 o Posterior/Anterior 2.747e-024 1.253e-022 o Lateral 1.693e-024 7.720e-023 o Rotational 2.340e-024 1.067e-022 o Isotropic 1.893e-024 8.630e-023 Page 1 CI-]ll

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File : PB122915.MS5 Date:

RL )ate: December 29, 2005 By:

Rurf-ime: 2:53:47 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.25 I

Description:

Revised Model Calc- Zr-95 Unit Act w Sched 40 & 12 in Shid Geometry: 10 - Cylinder Surface - External Dose Point ource Dimensions Height 762.0 cm 25ft Radius 7.62 cm 3.0 in Dose Points x Y z

1. 1 138.78 cm 381 cm 137.16 cm 4 ft 6.6 in 12 ft 6.0 in 4 ft 6.0 in Shields Shield Name Dimension Mate I Density Cyl. Core 7.62 cm 2 Conc ret e 1.8 Shield 1 .65 cm Irc)n 7.86 a Transition Concret e 2.4 z

Shield 3 30.48 cm Concret e 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies Iulide curies becquerels lCi/cM2 Bq/nam Zr-95 1.6417e-010 6.0744e+000 4.5000e-009 1.6650e.004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm 2 /sec MeV/cm 2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildlu 0.7242 2.652e+00 6.562e- 11 1.649e-09 1.262e-13 3.170e-12 0.7567 3.362e+00 1.050e-10 2.477e-09 2.010e-13 4.742e- 12 TOTALS: 6.014e+00 1.706e-10 4.126e-09 3.27le-13 7.912e-12 Cl-1 12

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 kticroShield v5.04 (5.04-00362) 12/29/05 MicroShield v5.04 (5.04-00362)

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Conversion of calculated exposure in air to dose FILE: C:\MS5 \DATA\PB122915.MS5 Case

Title:

Line 1.25 I This case was run on Thursday, December 29, 2005 at 2:53:47 PM Dose Point # 1 - (138.78,381,137.16) cm Results (Summed over energies) Units Without With Buildup Photon Fluence Rate (flux) Photons/cm 2/sec 2.294e-010 5.551e-009 Photon Energy Fluence Rate MeV/cm 2/sec 1.706e-010 4.126e-009 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 3.27le-013 7.912e-012 Absorbed Dose Rate in Air mGy/hr 2.856e-015 6.907e-014 mrad/hr 2.856e-013 6.907e-012 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 3.348e-015 8.097e-014 o Opposed 2.723e-015 6.584e-014 o Rotational 2.723e-015 6.584e-014 o Isotropic 2.406e-015 5.820e-014 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 3.574e.015 8.644e-014 o Opposed 3.406e-015 8.237e.014 o Rotational 3.406e-015 8.237e-014 o Isotropic 2.576e-015 6.229e-014 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 2.973e.015 7.191e-014 o Posterior/Anterior 2.648e-015 6.405e-014 o Lateral 1.99le-015 4.816e-014 o Rotational 2.369e-015 5.729e-014 o Isotropic 2.029e-015 4.907e-014 Page 1 CI-1l3

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File : PB122916.MS5 Date:

RL 'ate: December 29, 2005 By:

Run Time: 2:55:49 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.25 J

Description:

Revised Model CaIc- Eu-155 Unit Act w Sched 40 & 12 in ShId Geometry: 10 - Cylinder Surface - External Dose Point

(~i~I .+ x ource Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in Dose Points x z

1. 1 138.78 cm 381 cm 137.16 cm 4 ft 6.6 in 12 ft 6.0 in 4ft 6.0 in Shields Shield Name Dimension Mate.ria I Density Cyl. Core 7.62 cm 2 Conc ret e 1.8 Shield 1 .65 cm Ire }n 7.86 z Transition Concret e 2.4 Shield 3 30.48 cm Concret e 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff 0.015 Photons < 0.015 : Excluded Library : Grove Nuclide curies* becuerels pCi/cm 2 Eu-155 1.6417e- 010 6.0744e+000 4.500Oe-0C)9 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 ResulIts Energ Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cmz/sec MeV/cm 2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 03 1.933e-02 9.868e-85 1.153e-35 9.780e-87 1.143e-37 0l-]14

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 Page :2 DOS File PB122916.MS5 Run Date: December 29, 2005 Run Time: 2:55:49 PM Duration : 00:00:01 Efnergv .Activity Fluence Rate Ffuence Rate Exposure Rate Exposure Rate Me* photons/sec. MeV/cml/sec MeV/cml/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.04 1.lOle+00 5.223e-45 1.741e.33 2.310e-47 7.701e-36 0.05 3.581e-01 9.11 le-32 9.238e-31 2.427e-34 2.461e-33 0.06 7.878e-02 3.144e-26 7.387e-25 6.245e-29 1.467e-27 0.08 1.886e+00 1.200e-19 5.472e- 18 1.899e-22 8.660e-21 0.1 1.256e+00 1.036e-17 7.855e- 16 1.585e-20 1.202e-18 TOTALS: 4.699e+00 1.048e-17 7.910e-16 1.604e-20 1.210e-18 C1-115

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 1icroShield v5.04 (5.04-00362) 12/29/0 MicroShield v5.04 (5.04-00362)

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Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122916.MS5 Case

Title:

Line 1.25 J This case was run on Thursday, December 29, 2005 at 2:55:49 PM Dose Point # 1 - (138.78,381,137.16) cm Results (Summed over energies) Units Without With Buildup Photon Fluence Rate (flux) Photons/cm2/sec 1.05le,016 7.924e-015 Photon Energy Fluence Rate MeV/cm 2/sec 1.048e-017 7.910e-016 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 1.604e-020 1.210e-018 Absorbed Dose Rate in Air mGy/hr 1.400e-022 1.057e-020 mrad/hr 1.400e.020 1.057e-018 Deep Dose Equivalent Rate (ICRP 51

• 1987) o Parallel Geometry mSv/hr 2.341e-022 1.767e-020 o Opposed 1.283e-022 9.685e-021 o Rotational 1.283e-022 9.683e-021 o Isotropic 1.242e-022 9.372e-021 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 2.326e-022 1.755e-020 o Opposed 1.803e-022 1,361e-020 o Rotational 1.803e-022 1.361e-020 o Isotropic 1.313e-022 9.912e-021 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 2.012e.022 1.518e-020 o Posterior/Anterior 1,577e-022 1.19le-020 o Lateral 9.735e-023 7.348e-021 o Rotational 1.347e-022 1.017e-020 o Isotropic 1.072e-022 8.090e-021 Page CI-1]6

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref' DOS File : PB121913.MS5 Date:

RL ate: December 19, 2005 By:

Ruri-rime: 11:24:57 AM Checked:

Duration : 00:00:01 Case

Title:

Line 1.26 A2

Description:

Revised Model Calc. - Co-60 Unit Act w Sched 40 & 12 in ShId Geometry: 10 - Cylinder Surface - External Dose Point C

Source Dime nsions Height 762.0 cm 25 ft Radius 3.81 cm 1.5 in Dose Points.

x Y

1. 1 134.97 cm 381 cm 182.88 cm 4ft 5.1 in 12 ft 6.0 in 6 ft Shields Shield Name Dim iension Matf aet I Density Cyl. Core 3. 31 cm2 Conc;ret :e 1.8 Shield 1 65 cm Irc3n 7.86 Transition Concret :e 2.4 Shield 3 30. 48 cm Concret .e 2.4 Air Gap Air 0.00122 Wall Clad .0 25 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies Nuclide curies becquerels wCi/cm 2 Bq/cm2 Co-60 8.2087e-011 3.0372e+000 4.5000e.009 1.6650e-004 Buildup The material, reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm 2/sec MeV/cm 2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.6938 4.954e-04 2.365e-15 7.879e-14 4.566e- 18 1.521e-16 1.1732 3.037e+00 2.935e-10 4.432e-09 5.246e- 13 7.920e-12 1.3325 3.037e+00 5.773e-10 7.308e-09 1.002e-12 1.268e-11

- ALS: 6.075e+00 8.708e-10 1.-174e-08 1.526e-12 2.060e. II Cl-117

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/19/05 MicroShield v5.04 (5.04-00362)

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Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB121913.MS5 Case

Title:

Line 1.26 A2 This case was run on Monday, December 19, 2005 at 11:24:57 AM Dose Point # 1 - (134i97,381,182.88) cm Results (Sur nmed over energies) U4ni.t WiSthou Buildup Buildup Photon Fluence Rate (flux) Photons/cm 2/sec 6.834e-010 9.262e-009 Photon Energy Fluence Rate MeV/cma/sec 8.708e-010 1.174e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 1.526e-012 2.060e-01 1 Absorbed Dose Rate in Air mGy/hr 1.332e-014 1.798e-013 mrad/hr 1.332e-012 1,798e-01 1 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.512e-014 2.042e-013 o Opposed 1.303e-014 1.758e-013 o Rotational 1.303e-014 1.758e-013 o Isotropic 1.164e.014 1.57le-013 Shallow Dose Equivalent Rate (ICRP 51 1987) o Parallel Geometry mSv/hr 1.609e-014 2.173e-013 o Opposed 1.550e-014 2.093e-013 o Rotational 1.550e-0 14 2.093e-013 o Isotropic 1.233e-014 1.664e-013 Effective Dose Equivalent Rate .(ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 1.,362e-014 1.838e-013 o Posterior/Anterior 1 .255e-014 1.694e-013 o Lateral 9.987e-015 1.347e-013 o Rotational 1.130e-014 1,525e-013 o Isotropic 1 .OOle-O14 1.350e-013 Page 1 CI-118

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

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Page :1 File Ref:

DOS File : PB122121.MS5 Date:

RL late: December 21, 2005 By:

Run-rime: 3:45:18 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.26 B

Description:

Revised Model Calc - Cs-137 Unit Act w Sched 40 & 12 in ShId Geometry: 10 - Cylinder Surface - External Dose Point 0=9X Durce Dimensions Height 762.0 cm 25 ft Radius 3.81 cm 1.5 in Dose Points x Y z

1. 1 134.97 cm 381 cm 182.88 cm 4 ft 5.1 in 12 ft 6.0 in 6ft Shields Shield Name Dimension Mate I Density Cyl: Core 3.81 cm2 Conc ret.e 1.8 Shield 1 .65 cm Iro n 7.86 a

Transition Concret e 2.4 Shield 3 30.48 cm Concret.e 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies curies becquerels UCi/cm 2 Bg/CM 2 Ba-137m 7.7654e-01 1 2.8732e+000 4.2570e-009 1.5751e-004 Cs- 137 8.2087e-011 3.0372e+000 4.5000e.009 1.6650e.004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Activity Fluence Rate Flue ceRate Exposure Rate Exposure Rate MeV photons/sec MeV/cm2 /sec MeV/cm 2/sec mR/hr mR/hr No Buildup2 Wit Bilu No Buildup With Buildup 0.0318 5.948e-02 2.447e-82 3.48le-35 2.038e-84 2.858e-37 0.0322 1.097e-01 6.519e-80 6.579e-35 5.246e-82 5.295e-37 0.0364 3.994e-02 8.36 le-62 3.666e-35 4.750e-64 2.083e-37 516 2.585e+00 9.264e-12 3.324e-10 1.796e-14 6.443e- 13 cl-i 19

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Page :2 DOS File : PB122121.MS5 Run Date: December 21, 2005 Run Time: 3:45:18 PM Duration : 00:00:01 tnOrMe Fluence Rate Fluence Rate Exposure Rate Exposure Rate Mev photons/sec MeV/cm 2/sec MeV/cm 2 /sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup TOTALS: 2.794e+00 9.264e-12 3.324e-10 1.796e-14 6.443e- 13 C1-120

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 licroShield v5.04 (5.04-00362) 12/21/C MicroShield v5.04 (5.04-00362)

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Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122121.MS5 Case

Title:

Line 1.26 B This case was run on Wednesday, December 21, 2005 at 3:45:18 PM Dose Point # I - (134.97,381,182.88) cm Results (Summed over energies) Units* Without With Photon Fluence Rate (flux) Photons/cm 2 /sec 1.400e-011 5.023e-010 Photon Energy Fluence Rate MeV/cm 2/sec 9.264e-012 3.324e-010 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 1.796e-014 6.443e-013 Absorbed Dose Rate in Air mGy/hr 1.568e-016 5.625e-015 mrad/hr 1.568e.014 5.625e-013 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.856e-016 6.660e-015 o Opposed 1.486e-016 5.332e-015 o Rotational 1.486e-016 5.332e-015 o Isotropic 1.314e-016 4.715e-015 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.973e-016 7.078e-015 o Opposed 1.874e-016 6.723e-015 o Rotational 1.874e-016 6.723e-015 o Isotropic 1.405e-016 5.041e-015 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 1.64le-016 5.889e-015 1.

o Posterior/Anterior 1.449e-016 5.198e-015 o Lateral 1.074e-016 3.854e-015 fl 6 Rotational IZ 1.295e-016 4.645e-015 o Isotropic 1.102e-016 3.954e-015 Page C1-121

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

D05' File : PB122122.MS5 Date:

Ru ate: December 21, 2005 By:

Run-Time: 3:50:53 PM Checked:

Duration : 00:00:01 Case

Title:

Line 1.26 C

Description:

Revised Model Calc - Eu-152 Unit Act w Sched 40 & 12 in Shid Geometry: 10 - Cylinder Surface - External Dose Point u

X ource Dimensions Height 762.0 cm 25 ft Radius 3.81 cm 1.5 in Dose Points x Y z

1. 1 134.97 cm 381 cm 182.88 cm 4 ft 5.1 in 12 ft 6.0 in 6 ft Shields Shield Name Dimension Mate I Densit Cyl. Core 3.81 cm 2 Conc ret:e 1.8 Shield 1 .65 cm Iro n 7.86 2- Transition Concret :e 2.4 Shield 3 30.48 cm Concret :e 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Library : Grove Nuclide curie s becquerels 4.500_O Eu-152 8.2087e--011 3.0372e+000 4.5000e-00)9 1.6650e.004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Ener_, Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV p-hotons/sec MeV/cm 2/sec MeV/cm 2/sec mR/hr mR/h No Buildup With Buildup No Buildup With Buildup 04 1.797e+00 7.689e.50 2.295e-33 3.401e-52 1.015e-35 CJ-122

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Page :2 DOS File : PB122122.MS5 Run Date: December 21, 2005 Run Time: 3:50:53 PM Durntion : 00:00:01 Energy Activit Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cmI/sec MeV/cm 2/sec mR/hr mR/h No Buildup With Buildup No Buildup With Buildup 0.05 4.493e-01 6.370e,35 2.389e-33 1.697e-37 6.365e-36 0.1 8.635e-01 2.353e-19 2.288e-17 3.600e-22 3.501e-20 0.2 2.276e-01 2.237e.16 3.535e- 14 3.947e- 19 6.238e- 17 0.3 8.212e-01 1.694e-14 1.920e-12 3.214e-17 3.642e- 15 0.4 1.909e-01 2.807e-14 2.175e-12. 5.470e- 17 4.239e-15 0.5 1.713e-02 1.077e. 14 5.981e-13 2.114e-17 1.174e-15 0.6 1.288e-01 2.537e-13 1.061e-11 4.952e-16 2.07le.14 0.8 5.408e-01 6.015e.12 1.608e-10 1.144e.14 3.058e- 13 1.0 1.300e+00 5.202e. 11 9.920e-10 9.589e- 14 1.829e-12 1.5 7.046e-01 2.451e.10 2.658e.09 4.123e- 13 4.472e-12 TOTALS: 7.040e+00 3.034e.10 3.826e-09 5.203e- 13 6.636e- 12 C1-123

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MlIcra~ide'Jd Y5404,(5,04-00362) 12/21/O0 M~icro~hield v5.04 (5.04-00362)

Ra~i~c'kaISei~~ee, Irtc.

Converion of cakulated ex~posure rinair to dosei FILE.- C.AMIVI\DAMAP6l22122.MS5 This case was rum om Wednesday, Deceimber 21, 2009 at 3.50:93 PM 151ie P~inlf $1 - 134VOt$ýM em ifUaR, Wi thUg~

Photamscrn-*sec 2.996eý.009 Mev/Cri9sec 3,.034e-010 3,826e-009

Expo~sure and D~ot Ratcis, Exposure I.are in Air nMflhr 5 .2030-01 3 6.636e-012 Abawre Po Rate in Air rnGy/h r 4-S4Že-OI 5 5.7944e-0:14 Mr~d/li 4 542c-01 3 5 .794o-01 2 a Parall~el Geanietry rn!.vhr 6.59We-01 4

-IOppQ."ýd 54154,@-D1 5 5-682,e-0i1 4 a Rotational 4.C6ae-01 6 5.672-A04 ai I %elrLopic 5.07%~-01 4 5.468e'Dl 5 ShalIow ose Equivialent Rate .ICRP 51 287) ciParpili"I Gwrnotry~ G.6.7e-01 4 r0up"Posed 6-747e-D1 4 5.2 78e- G1 5i o Roitational C.747v-014 4.21 9e-D1 S 5-368e-01 4 o Arnterior/Posterior -Gernetre m~y/hr 4.64 leC01 5 59.929e-01 4 t) P,,.-ericr/Ar;1ericir 4,292e-0-1 5 9469e-01 4 aiLateral 4,3~61 e-ID1 4 a Ro~tational 1~8729-0 15 4.926.e-014 d Iq10tpic 3.440e-0 19 4.363e-01 4 Page 1 C1-124

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Micro~hie~ld v5.04 (5.040062.)

Radiological Seyvices, In~c.

Page :1 'IlC Rof:___ ____

005. File P81,21l23.M.S5 Date:

Ru ate: Deembw 21,2cMS RurfTjmne: 3:53:07 PW Checked:

Dura'tion 0cO:C0O01 Caso Me.r~ Line 1.26 D Oisrlpthon: Revised Model Caic Eu-IS4 Unit Act w Schad 40 & 12 In Sthtd Geormutryr: 10 -Cyllnder Surface External D*ow Point

(

I l~adius 4 'N5.1 in Dose Points5 381 ern 12 ft 5.0 in Shields z

2s rt 1.5 in 1E92.88~

eft 5iý4Icd Name ri GO, Core~ 31M~ CM m ~e 1.8 Shield 1 -65=,- Ire*n e~ 2,4 Shield 3 ~e '2.4 Air Cap Air Q()IU 22

.0,25 Cm Iron Somme Input 01youpling Method -Standard Itidlees Nu~mboT off Groups 25 LOW&~i tEwgy ctiloll t 30015 PhojonSO Qý.15:.Excluded Library rGrove Eu-154 8.20837e-01 1 3.037 2e-t{00 4.5C'cON-C'9 1 ./gr0.04 Buildup The iiaterlal Ireferenc* Is Cyl, Care Integra~tIor Paramiete~rs 20 Ci rcunmfri~tia eslh 20 Efi=Activ'it' Fluence Ratie Kl::i tqO LIIA IE 1-5Ci 7 894., e 1-1709-52 3.491 e-36 C]-125

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 Page ;2 DOS File :P8122123.MS5 Run Date; Deciernbor 2;~, 2005

'Ru~n lime: 1:5107 PM Duration: 0DO00i.'O1 Ener "I Mev MeVICM,1150'r 0.05 1, 57Oe-01 Z2 269-35 5ý 929e-,38 01 1-.229e+00 3.34ge-19 3.267e-. 7 5.124e-22 0,2 2,074-c-1 I%97g.1 5,8917 0.4 2.1 67e-.02 3,19879-15 2.470e. 13 6.210e-18 4.812e-1 6 0,5 4.5q&f, i5 0.6 2.450"..1 4;82CSe-13 2-0188-1 1 9.41 9e-16 3,939e. 14 0.8 1. 184E~400 1.3 17e-11 3.R2,1 e - 2.506e. 14 6.697e- 13 1.0 3.740epg 1. 7.1 321e, 1.3150,12 1s:; 1. 185e.OO 4.122e- 1 4,47 le09 .6.9359-~13 7.5239-12.

TOTALS: 5, 789c+00 4,633i, 10 5,557e-09 7.985e.13 9.547e-12 C1-126

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 Vlkr*$hl~eld &IDO4(50--32 12/2110S Micco~hicd v5,04 (S,"00O362)

Conwewrsi~or of Cacuatwed expesiire in air toos FIILL CA.MS5\OATA\P~1322123.MS5

'This~case 'was rwn cco Wednesday, Osiac*I'iber 21, 2005 aft 3 -. 3:07 PHI Mh~ton FimcRate (flux) Photons./cmnl/sec 3.295e-0i 10 4. 1 ge-QON Iawtor) Erneg fIiuenc-E Rate MaVICM11-58C 4,633e-0 10 5,55 7e-D09 Exposure aind DDos Rates.

zxxsuc Plate in1Air m R/hr 7 -Me- 13 5,5474:OI 2 Abisrbitd Dose Rate in Air mnGy/bir 6~.8849-015 mitadl.hr 8.335c--012 Dvep Dcsc Equivalf.-nt Rate 7 202e-~O 15 a Paral lei GearnntP/ M~v.(hr 6. IM e,015 9.466e-O04 o Opppsf-4d 6.714e-0 15 a Rotational 6.080e.0 15 n lf;1j~fpic 7.334e.-014 Shllw C,,is Equivalent Rate o Para!kIel G~e mSV/hr 8 .264-e-0 15 1 W~4e-01 3 7.q41eO015 9'.6 4v--014 o Rotaftn~l 7,99119-015 SP.634~-014 6 .40Se.-Ol 5 (Imp 51 -7 . 7-738e-014 a An~tedior/f'o5Terior GeomEtry' m~v/hr 7.OR9rQ] 5 p

6.512e-015 S.2464 015 7-83e-14 aiRotati~rial 518~76C.015 7.101e-014 aiI satoptc 5 .233e.0.O5 6-305e-Dl 4 Page I C1-127

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 McroShleled S.Ok4 (5o44-00362 Radiological Servricers, Inc.

Flap ;I file Ref______

DOS He~:PR22124AS5 IDate:___ ___

RiL ale:December Z1,, 2005 B~Y; Ru rý rme: S: 4: 55 PM Checked: ______

Duration ;=00 Case Tltieý Line 1.26 E Desriptlort; Rloiod NT~dl COW- Ag. 108thk Unil A4t W Uhe 40 & 12- ImShMl Geomtetry Cyflinde~r Surfa~ce - External Dose Point

1<1Heigm 762.0 cm 25 ft fIadiu U1 -;m 1.5 in 381 ernl 1152,88 cmT 4 ft 5.1 6t Cyl, Core 3.~8. cmn' Gonc ret Shield 1 .65 ornm r n 61 Trusi~ori i Shield 3 XPOS cm Conervt

• 2A4 Air Ga,: Air 0,00122 WaIg Oad Source Input Grouiping Method .Standard Indices.

Numbeg of, Groups ,25 LoWert Este~g- Cia0111 A-6015 t~hotons -e 1.015 : Exciuded Library .Groe~~

be2gecell2ic ;BL/cIT Ag- 108m 8.2C087 e-01 1 3.D372ce-rOOO 4-50COe-0 09 1,6.650cr34 SuiIdup The material rederence is -Cyl. Core tntegration Paramneters Y irwufritn(aial 20 Re sults Cray Activity Flturnr.e Ra"A Flyorict Rajt-v Exi.;gro Rate Exprqsura Rate 24vln~Ll 32 1;992c+00 4,33c.34- 5.2309-2&3 1-5703e. 35 CI-128

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 Paig DOS Fire P8122124.MSS F~un. Date; N~cr.mber 21, 2005 Huni Titrne: 3:54:55 PM Bubiata U~na 0.03 3. I 06e-940 0.08 2.152'e-01 2,348e-22 :3.7 16e-2:5 0.6 4.01 Se,13 3.1 12e4I1 '7.824e-16 6.063e-1 4 2, 74.5-00O 5,409'e-12 2.262e 1 k 4,414t~.13 0.8 2. 749 c t 0 3. 57;.- 11 8.171e.10~ 17056c.14 TOTALS: 1.0'434+01 3.638e- 11 1,074e.09 6.949e-14 C1-129

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 12/21/05 Mic-roStiield w5..0.4 (5404-0362)

RadboinogkaI Services, Inc.

Convvrsiin ofrlciulatid expostare in~ air to dose FILE. C.-\?IS~\DATA\P8122-124hIUS5 This case was nin on Wednesday. December 21, 2005 at 3:54:55 PM Dm5,Ijj5(§aMd y er eneqjieý j1CI Wjftt MuLaw Pbokon Fluenre i~ Ylru(fLJ45 Photons/cmrI~serc 4.823e-C 111 1.476e-009 Photon Energy Flhuence Rate 3.6359-0 111 1.0749-009 1E1xpo~ure amd Do"e Rates-Exp.osire'Rae Ini Air mR/hr 6.94ge-0 14 2.0%e.012 Abscirted Dose Rate in Air MiGY / hr 6,0156ewO 16S 1, 795e.O014 rnrad/~hr 6.066e.0 14 1. 79se-O12

,,,Deep Dose Equiva~nt Rate jo F'ara~Iel G'webxty 7.1I02e-0 16 2.108ae.014 a

5 .790e,016 o3Rotational S .79Oe.02.6 1,711 f.,O 14 5.1.16e-016 1.53 2e-O 14 ShplwC)Dsp Etquiy-,jIont. Rote (IC.RP 51 %7) io Parallel Geometry mSv/hr 7-582e-M16 ý247eOý04 7.~2270r_016 2-14 le-.01.4 G Ronaticonal 7 2;17e-01 6 2.141e-014 S ,4 76Cn-016 1 .6I B-014 iICRP ~

aýAriterior/'Postert.Dr CGeometiy m~y/hr 6ý314,z-016 1 .872e-02 4

-5633e-0 16 "1 6 Oxe-D04 4-245e-9U 16 .2,5 le-Di 4 o Rotationat ,5-039e--016 I -400e-Dl 4 a O~Oi 4ýý20-Q 115 1.276Q-CD1 4.

Paige 1 C1-130

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Miicro~hlld1 -60'(," 6-2 Rtadiological Services,1 In~c.

Page ;I Fle, Ref______

00Oý Fit,& P312Z1.25.MS,5 Date:

By:

Ruri'Tme: 3.56:.,37 PM Duratiuqp ; 0QW Cas~e Titleý Line 1-26 F Descriptiion: Reviised FUode Cialc Nb-94 Unit Act w Sched 4-0 & 12 in ShI~d Geomietry: 10 - Cylinder Surfa~ce - Externbal Dose Point Sour' ce ~imensions Hqig'It 25 It IFadiu~s 1.5 in,

~ose Points C-z

w1 $4.97 em 182.88. cm 4 ft 5..1 in 12 ft G.!; 8 (t Shielids.

31. cln Cono ret Transitiion Concret e 2.4 Shqd3, 31) S2.4 AIr'( a 2Q.Qi 22 Yiall Cla'd 25o M. Io T86 sourcoInput Groupilng Method :Actul~ Piftcton Energies 4

mlri-i j~jfW-!n za~,I- ý Nb.94 B8 7ZO 724,'O'1 4, 50 .1(L,0 1, 1-65 N,-N4 The m,aewizal teleierence Is -!Cyl. Core YIntDirectionParamaiu's 20 1C:-rc.u mferzr ti a, 20 Results 0).0 I7,1 1.0 14e,38 0.Oc(LDe-4.OO 3.6'32e-37 O0I00e+ao 1.9~23e- 38 0'2.0 196 I25. -I5I 1.2-6e-37 9.584e-287

-3 C447 e tO -5.1 Q;o.1 - .3.016e.14 9,85-3913 71 72 5.5I4.3eI- 11 1.t043(:13 2.414ge.12 C1-131

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Page  :.2 L)) File PB1322125-NSS Ron Date:. Dercember 2,1< 2005 Dura~tion : 00:00:0 Fluence Rare Fluence Rair Exý2F..5rR Rt mR&1h Eurum-ai U2 audilwo

, Mf?1i4L TOTALS: 6.078e+0O 7.107e 11 1,812e.oý L345e-13 3.434e.12 C1-132

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 rdicrogh414et w5-04 (5J3O4-00362) M/21/V05 MicroShidd vS.04 54OX"362)

R'adlio4agical Services, rInc.

rILE-. C:\MSM\-ATA\.PMi212~5.S QMS-e TkwI L2rS6 F Mile

'Ths cas~e was run am Wednesiday, December 21, 2M0 at 3:56:37 PM~

Des Padatt 1I - .7a18s)4¶ ftultsSuWmgu d over qnerg~gs JM Mhotonscmi/sec 2, 22.1e-DO9 HMotan Enefg IFicence Rate 7.1.07e-01 1 Exposure aind Dose ROOF~

Egposure Rae Ini Air imRfhr 1 345c-01 3 3.434e-01 2 Abs.orbed Dose Rate' in Air mGylhr 1. 174e-01 a

rb~r.O11hr L I74ir,-O 13 2 .9913e-01 2 a Para.91el Gm-e~rtry 3-488~-O1 4 o Rotafonal rnSv/hr 1 .125e.015 2-.871.e-01 4,

'ý%43e'o 16 2. 39e.014 1.460ee*O15 3. 730e.0 14 o Oppo~csed 1..3938-015 3.559e-0 14 o Rotatilarial 3. 5.5ge* 14 rn~.v/hr 2.7 1-1uO 14 O Ifotrkpi.- 00Cuvac-tRt

-3,Anternorlcsteri-or G1eo-fntri 1,2179-015 3.100e.034

2. 788e*O014 to LD~ter.Ef a.309e-.WO~6 a3 Rotational I 9,780o.0O1 6 2.4-96e-014 tj I Sa tiArapi 8,430e-016 Page 1 CI-133

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 f*1kvoShbieid Y&O.4 (&W03~f62)

Page :1I File Ref: _____ _

DGS FI~e : P,822917.NS5 W. aWmnenbr29,200-5 By:

IRjn- frime: 3:04:12 PIM Checked:6 Duratio-n 0000O:03 C~ase

Title:

Line 1,2Z Q Description.: Revised m*OdeI 4Cak, tI125 UnImt Act w ScIhed 40 & 12 in Shid Qeom~etryý. 10 - Cytiider Silace - Extoirmvl Do Point1

• f Ource Dimensions Height 762.0 c:mv 25 ft Radius 1.5 In~

Doise Point

• 1 134.97 cm 192.88 cm 1 t5, 1 iih 12 4t LrJ Sh ields cyll C-ore 3~.81 =m .fl

ý'hiirki .ýi5q (vir

-W Transi,-on oncriet e 2.4 Ahr i3 .31a413 c~m C~lc~t%3t S2.4 Air C. C'1~22 G23 -,m !D :7.M siouscx: imppt G-roupIrig Ntethod ,Actual Pho~ton Energies

ý-cueps 6zL, Ltic 5c..N3 1.129 8. 2051-7',, -1 ZQ72u,+GC(X 4,5Gflix-., )9 The matied&I tedevence is 4.Cyl. Cate InTegration Paramneters 20 Circ;umin4,e r.-!it i,3 20 Resuft~

0.02M, E .06 1 e-0 I 1 887e-99 2,9&2e.36 1.O69e*ý96 5..372e. 36 4-GZ7(.L72 I-34 172.o :Z84u 74 1.969e.36 0.0396 2,.2.84,e*0 9 6.3c $2 4.30-0e. 54 1.2713e,36

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Paac  ; 2.

DOS Fite - P8122927JA55 ftwo Date: Decernber 29,,, 2005 R~pn Time; 3:04:12, PM Duraticoit 003:00-D ExiapsLre Rate ExrasUids,-

F9.463j EW.5 1I~~g

.R&6e*3 TOTALS: ,2~359c+00 4,300s 1.152e- 35 C1-135

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 12/29/05 MicroShitld Y&O4 (5.04-00362)

Radogical Serull, esIn.

~E cku~I~d zp~ur~int air to dosi IRLE; C.AMS.5\DATA\PB122927-,MS5 Case Tifle- Urie L.26S 0 This cas& wans run on Thursday, December 29, 20-05 at 31.D4,12 PM Dose PoIint 0 1 - 0134.9 31 4 1ý.) cm R-esults %'Summedomer erier.&iea, MWf h PhGtons/crW/sec 2 .3g1 e0.5~0 4.25f6e-032 Phtrion Eniergy 'Flarence Rate 9.4,63o,52 1..366e-33 Exposure anud Doso Rate-Eyposure Rate tIn Aie .mR/hr 4i300"5O4 1.16:2e.035 Ab'sirbed Dose Rate in Air myf hr 3.7-54c,056 1 ,0068-037 mrad/hr 3. 754e.054 D~eep Dozo Ed1~iai,-~~4nt Ratc a Paral lel Ge~em-ery mrlv/hr 1. 151e-0$7 a :5.776e.038 o Ro'tationasl 2 .450e.066 4.926e.038s 2 .344e.051 Sha~llow DceSE Equ-,-aierit Rate ( dcRP 51 M~7) a Parall~el Guretry irnSv/hr 5 .406e-066 1.2-55e-037 N

a O.p0o--ý 3 .732,--Q56 6.6.30e038 o Rotationail 3,732e-056 B.6aCi038o 617&*-38 EO Ifivo Ormt (ICRP r.1 - 9.-T o Anterior/Posterior G-rietr>y MS-v/hr 551452e-038 us.iPoseriotFiAnerior R A.S4-e-056 o Latorobl 1 44 1le-038 o R~tational 1 .703e-056 2 .652,e-O3$

2,.1974-038 PaelI C1-136

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Microghield i5.04 (S.40032)

Radiological Seri'vces, Iinc.

Page  ;:1 File Ref: _ ---------

U File !P8O10405.AS5 P&. ate; Jarnuary 4, 20r By:

gunTr 'nme: 8!09: 1 AM Checked:

Duration . 00ODCO;0 Case Titlei: Line 1.26 H Dw.scription;* Rew~i-st iMoel Coleý Sm~426 Uniit Act w Slthed 40 & 12 in Shtd G~eomietry, 10 - Cyllinder Surface - External DowftPiwt Source Dimension~s

[HWght 7,62.0 cm 25 ft 1.5 in 2

1a2.88 cm 611 Shields Shiel dd-a J Shield .3 .30.48 cm Ooncreti e 2.4 Air ý;ano Q,)001 025 m l-SourceinIrput Grouping Msihod ;Standaird Inic~ies nre.-of Groups 2 Lcwel Uiergy Cutoff (]-(]I fPhotons < 01 Excluded Library . G~rove Sn 1.26 9.ŽCT870j, 1*.0372c+0Q0

_'1 4,5CO~io-C( 9 1,,5650e Q034 The makeral veletehee [s CYL. Cote Intaggation, Pauamernes 20 Ci rcurniur'um bwj 20 Flmupau MeV/cn1:"/eC 2..3m

1. 82.e 2,7 5.120e-35 6.172e-269 1 7739-H C]-137

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Pap 2 DOS Fiie P80104-95.0S5 Fh~ri Onto: .nuary 4. 2006n Rtan Ti~me- O8!0:18 AM~

Durqtico 00:1 M2LbL 0.03 8-893e601 3.81 1893 4.280-3 3.7 770-5 41244063 0.04 1.51,74-02 6.491e-S2 1.9-37e-35 6, 5 8 "3 6 0.08 9110;0 4,132o28 9.20i8e..31 2.404e-29 0.08 1.395e*OO 1.52219-21 1.2 e,26 2,~408e-24 1.326e-22 TOTALS. 2.825e+00 8,380e-20 2.408e;24 1.326e,22 Cl-138

Plum Brook Reactor Facility FinalStatus Survey Plan. Revision 0 11croWeld v5.04 (5.044M362) OY431141 MicAra~hkid Y5.04 (.5.041-362) ftadkiodlecal Servicers Inc.

Cooversion OA~IC116 e~po$ore ji ape ta dose.

FILE: C:.\1S5\DATA\Pfl020405.M55 Cse rife- UnLm 26 It.

This carte was rm on Wednes~day, Januar 4, 2006 at 8:08:2~8 AN ft~e PFb¶~t # 1, om, Eglilts ('Summed y~ear energfies Uim~I Without Mb~

Pho~ons/wl/siec 1.902e-020 1.048e-:)!8 rmtAon Eaweiy Fluence Rate MeVY/cm2/se

'Expo~sure a'nd Dos Riatms-Exposure Rate in Air mnR/hr 2 .408e.024 Abw- rb--. Dw Rib in Air mnGy/hr 2.102e-0261 1.1 W8eD24 rnvarj/hr 2 -I 0e,024 (ICRP 51

• 1987) a Para Ie 1 iEY:4net ry m~vhr 3 ,67 7e,025 1 .958e-0)26 1.079e-024 o Rotational 1.04!Se. .24 1 .890"-26 1,041 c-2 StaIlvo Case Equivalent Rate (IMRP 51

• 1987) m5v/hr 2.0-01145M a

a OJpposed 2.677e.9O2M. 1,474e.024 o RotatilonEat 2.6 7e--06 1 .474e.024t 0 1Iwiaopic 1 ;9G59-026 -1,M -0 4 Efflectivp, Dos5e 11 L2iVwIr1& Rat (ICRP 51 oj Anterg-or/Postehacr &&eorrietry ,3tO889*Q2' 1 7G1 e-O24 o Pob~i./nsi) 2..356a-026 a Lateral 1,~452o.026 7 .99~59-025 o Rota ionaE 2-006e.02.6 1.10e.02O4.

UsoIlf~pic  ; 194 1P Page I C1-139

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MNicrDShiO.Id w5.04,(5.04..G362)

Radiological Setrives, Inc.

File Reti______

DOS File P8122919.MS5 RL ate: Deember 29, 2005 By:

hrrFrnThe- 3:09:53 PMA Check~ed: ______

Case TRWe Line 1.26 1 Descriptioni: lRewied Modei CafQ- Lr-S Unih Ac w Scheir 40 & 12 in ShId Gearnetry.10'- Cylind~er Surfae Ertarnal Des4e Point source Dimensiaons 25 ft l Radius 3.81 cm DO-SIB Painis z

41 1 -497 on 3.81 cm 182,80 cm 4 ft 5.1I in, 12ftt6.0 fin 6 t shold Na' J 3.8cm Conc. rot Shield w

Trafisitirn 2A4 Shield 3 30.413 orm Coricret e 2.4 AirCa 0,00122 Wall - akd .025 cm Irm~ 7.86 GroupLuiI Method :Actual! ftoton LEergies uw&L" 1.BQL-Q" zr-a.N, 628Q- 1 JAV721:+QCQ 4,5000r,-09 The mateirlaI .redef euce lis Cyl Core IWniiation Pararnei5r 20 20 Results 8.18e.12 Rt 0.7242 1 ~26e+OO 2. 55e.10 3-57~3e.*14. 7,507c'~du.1 0.75, 7 1 681ei4~O I14 37 e,- 11 2.57ge'- 14, T4,1TAU~;: .Q!,P,+w ý,165e-1I 4.15,e14 1,241c.12 6,-47e10 CJ-140

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 12/2906 r~~Microshiell 4.04 (5.04-00302))

Rtadiological fiervioes, Inc.

VILE: C:\MS6\DATA\P0222919.M95 Cas Title Line 1-2$ 1 This carve was rum oni Thursfay 1 December 29, 200 at &0V913 PM Dose Po~int # 1 (1.34.97814182.88)c Roults 4(Sumnmod gryar arle~i~

Ei.1"dikp P~wAon F'itc4 Ra~te (flux)

Me V/onscmZJpc 2-910e.01 1 8, 704-01 0 Iftbotonf Ene.¶r/ Fluiencie Rate 2AG65e 011 6.472e-0~1

~Expos~ure aind Dose~ Ratos

~axpasure Rate In Air mR/hr 1 24le-0M 2 Abwrbad De' Rztr, in Air mr.'y/hir I -M l 14-irnradfhr 3.624e*014 1 .08.39-012 (lCRP 51 -1987) to Parallel Geometry mn:V/hr 1.270r,.O 14 IV00p30V 1 .033e.0 14

-oRotational .3.45Se-02i 6 1.01332!o 14 in -f1igp ý.:054,e -Q 6 -%.12&.015

!Stvallcfv Dose .Equ~va lent Rate (lCRP 51 -1987) 0 P~RN311 RI 'M~try mn~yhr 4. 53Ee-Dl 6 1.356e_0.14 a ppse 1292,e2ý14 a Rotational 4.3221e-0Q16 1.292~e-O14 3-0!ý~ 15 9;,770a.015

('ICRP 51 -1987) a Anter-iorlPasterior GeorrRtry rm:v/hr 3.6773e-01 6 2-12&e--014 o Posteror/An~terrior 11 3.361 e-016 J..O5-e-04 o LatcrtI 7-554Q-OIL5 a Roitatona'r 300GEe-O 16G a1g6e-cKE S a I gotVopDi 2.57 5e-0 16 7-0 1,-0 5

page I cC-141

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 WicroUkt~id v$,* (B."4-00362)

RUNH~o~gicaI S-OrdceG, OInc Pag Fe !2.22 MS; FdoRo_-

K.,~

af!O.$¶ iw29 W Case Thk Lne 1-26 J criptiowt Rovised Mondel Cafc- Eu4155 Unil Act . Selld 40 & 12:1n ShI~d Gvon'i~riy;)ý 10 CylI nmdrt Surace - External Dose Poinit d

T I.

Awl1in

• wfe i m*?flo Don igirl-ptL frr

?iTRQCrl z6 ft b hl Iik

.Air 'II i,:,

Sour~ce hiput oro44pJllgblathod ,,Slp'daed Indilces

• Mnmbei of Ovmips ý25 Lower' Eiwrg Ctduff 0.01-5 LUbmev Grwe'V iaU.011 t~erc, ~

rl flQ-fcM Gl1 3.c03720i'oao 4 5O00O0eO( 19 Eýj ýI55i e, Vi'3 7 Dvidup Imelraikii&,n~ tr Circumferc-Aial R9o1alts UW" r1fignagg F.Milti E3",ur-q Mai.

~~Luz~aaa Ey a 7-r M=L tk.&IIIJI191 w1b nuddus, Iffir -

4,.3 42. -4.5 4.CU@ý-M C1-142

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Page, :2 DO$ FPh~ A9122920.MSS Ruzn Date: l~cember 29, 2005 Ro Time! 3:11:41 PfA

• Duretign;M U rwiýi 0.04 S.505e-0 1 2.356e,.5 7,031 e.34 1,042e-52 0,05 1.791evO1. 9.522e.34 2.537e.3$

0.06 3.93ge-02 5.69d3429 1 638e.27 11 lle-3 I 3,254o.30 0,08 9,43190 1 q.&ý. 1.62$e 24-0.1 6,~279a.01 1.7 110.19 1 M-49-.17 2.618e*22 2,545e-20 TOTAIZ; 2.ý5OQ+OQ 1.72 1a-19 2.634e.22 2.554e.20 CI-143

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 11J2-9/05 MicroShield Y404 (5.04-003G2)

Convrsion of, ~alculatd expoaurc in air to dose MEi: C:\MS5\DATA\P6i22M2.1MSS Cee roleI- Lrime L.26 J

~Thin, case was run,an Thursday'. Decernber 29, 2005 at 3:21.41 PM Dos Point 9 e.(1C73a I em Results (%urmmd over energ'ies) WJJm Pkoton Flug-i.e Rate M¶ltO Phatoms/cm 1 /sec 1.724e.018 1.671e-016 frho[arf EnesIgy Fhience Rate 3,721c.019 1,669o.017

~Ewpstre and, Dose Rates Exposiure Rate in Air mRfhr 2.634e.022 2.S~e-020 Absorbed Dose Rate fri Air ml~y/hr 2,299c.024 2,230e.022 a

mrad/~ir 2..2~9e-022 2-2%le-02 Deep Do~se Equf"ýIcni RRato to Parallel Gewre~try mSv/hr 3.844e-024 3.727C-022 UiOPPO*Cd 2Z 107e-024 2,.044ýe 022 fa Rotkiionat 2.107"-24 2.OW4e022 0 Ioi~rtpic 2,039c-024 1.978e.022 Shal~ip- Dose Equivalent Rate~

m~;v/hr 3,81 9c-24 c Qoposed 2.962e-024 2.973e-022 o Rototionad o totropic 2. I57eA024 2.092e.-022 E ve r-Gd D (JCRP 51 - n87) io Ariteri-Dr/Pcstterior Gietrrar mSv/hr 3.304e-024 3.a-204-L2 to Pos-erlaviAnterior  !..5qge!O24 2-12*-022 io Liptora 11599 a-024 1.551e-022 io Rotationial 2.213Se-024 2. 146&,022 0i ý(J~fow 17N~xg?4, 1;7Q7-;-022 Page I C1-144

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Micro~hiald Y5..04 (5.04-00362)

Radiological Services, Me,.

Page :1I File Ref; DCFile:P.1ý 1.$ C ate:

RL. ate: December 19, 2CO5 Ru~n Tome: 1.-09:20 Mol Chocked:

Duration. :0D G;02 Case Tift.e Line 1.641 A2 P"CrHpOO: R~evised WONe Cýak. -CO-60 Unmit Act w $Ce 40 & W~ in $bf Geometry. 10 - Cy~l rder Surface - Externad Dose Point.

Sour, ce Dnimensions

- ' Height 762,0 cm 25 ft Radiius 10.16 CM 4.0 in

'Q~a Pukrib z

1. 1 141.32 cm 383 cn-e 91.44 cm 4 ft 7.6 in 12 ft 6.0in 3ft Sh~fft 1,64cm' 'Concrief ShieWdy Ir -65 Isakn 7.86 Cor'crotu 2.4 Shield 3 30~.48 cmn Conc~rete* 2.4 Air r~ap Air G0.0122 WalI Clad, ý ~25,,j. brof 7.86 sauree Input Grouping Method .Arctual Photon Enrgies

~Lainfik 4 ,50U00e,009 Co-60 2.1890rA I1G 8,:0992t+00J0 1.15650ae.004-Buildup The malerfaI releifenice Is - Cyl. Care Integration Par~n- etefs 20 YCliFFrtiur1fr~ 20 Exrasurs Rate Ma/hr Nu BUldun 2 65 13 2.302e.,12 2.035e- 16 4,444o. 15 14.M30- 11 1A.732 8.0999 4 C' 7,292-a-09 7.786e-08 1.1)1e.1')

1.3325 6.09%~4-00 1.1-54,07 2.OG2e. 10 TALS3: 1,6~20e+01 I .!M7e.0a 1-145 a.3940-10 C]-145

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 W19/06.Q Mihmghlod (5.44-00361 vSM ftdlalingkal gervieft, Il¶C.

Cowwivrvior ol i foi~slO expetwur In Or~ to doza MgtE C;\MM~OATA\PO1.219MSS Caim THiCli Mooi 1.641 AZ flIS.COSO was nwi Magidyi Ton Oteiiber 19,2005 at 1.O9,20 PMI 0054 Point # 1 (141,321381,91,44) a'i Reumits f~wumrnd ox~w riarlw ='r lý,om Flepw Rale C06i*u rlruvon EsEe~ Fl- ýeRate Me~kw/sec 1.987e-008 1.933a-007 if'pa&ura and ~DowRib ZkgidiuriE Rate InAir r-AFUN, Ab.;ta Dpse Rats iq Air mGyhr 3 0430413 2,9639-012 atead-ft 3.0434-011 2,96-e010 Deep Pose~ Equiviterwt Raft-3.364412 a Rotati onat 2-M.O012 Iirnihr 2 £,6580013 2. -9ft 012 Shak-avo Ditse Equ`?a~r-: 7-'Il 2. W9-0D12 3.677e-10,1 3

'0 plair.all fWnor 3. 54,0eý 1-3 3.448e-0.12 3.,540Je-013 Cs AtfriiP~ o'~Gaecrvetry 2..'%0o 1e 2.5 12eý0.1 2.284e.0 13 2.223r,-012 Pare I C1-146

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 VlcrogSihefd w9,04 (SA4.4OG262)

Radiological Senviks, Inc.

Page~ -I File, _Ref:

001t~ Pile -,PB122126.MS5 Ro ate, D~'crhber 21, 2005 ByC:_

RuhTlme; 5,32:49 PM Checked*:_______

Duration . 00:;01 Case Titte: Line MAIE4 B Dsriptifri; Revised WWWe Ci~alt Cs-lal UoIt Act w Sched 40 & 12- IMOldd Ge~Foty: 10e - Cyllinder Siu'fce - xtemli Dorse Point

e 01men~sfans Height or 762,0 cm 25 ft Radius 10-16 cm 4-0 im1

1. 1141.32 cm $81 L-M 4 ft 7,6 in 12 ft 6.13in 3 ft Shiellds Cyi. GCorc 1;G, 118 Shivid 1 16, Mco rc Irate 3n ý.t conc.rut 2A4 Shiavd 3 30.48 crn Conre~rte 2.4 Air 0=1 O2:2

~2.5 rm Ion 7.86 Source Input Grouiping Me.thod ; Atual, Photon Ervergjes

____ beapes UCir/CjM,2 2, l7U-T $-,OOý0 1 .63e4 4-1151e.4XY' 1.57-5le-W~4 Cs 137 2.1 &q0B .010 8 .09,2e,0C0 4-50Oc'e-C0Q9 1,65&5G-0,04 The miaer~i~i teletemce Is tCyt. Care Iiflegratilon Pairamnete 20 QCrcurnfere~tia? 20 Results 1EAM Fluence Qate With BvildwD 0,0318 2.I95e,*67. 1.3a~eK34 2 .a2,8e.67 0.0322 2.926 5e-0 Is 1.924o-63 Z62e-2,34, 1.54ge-65 2. 134e-36 1.819e,49 1.478eý-34 37 316 6. 8944 '0 0 4.517c.10 u-21/208 &758-4-13 1.979e* II C1-147

Plum Brook ReactorFacility ' Final Status Survey Plan Revision 0 Page :2 DOS File 'P'2z-S Run Date:, Decembtei 21, 2006 Dur-fion ODOMa~

rJuence Rate 1 1k bkx=!4=.

E~isure With Ri I..Idl4p TOTAULS: '0.45'N+00 4,517e,1.0 1.979e-l 1 C1-148

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MN~ii~~keld 6,0O4 (5.04-00362)

Micreftiold Y5.04 (5.11"0362)

RadIololocal Servileei Inc, Conversion of calculated expasur In air to dose FILE- C:\VS5\DATAkPfl122126.M36 C44e Titli: Lift t-641 0, This case was aim (m Wednesday, December 21, 2006 at 5-32:40 PM.I Omse Paoint 9 1 - (14La2j381,9i44" :n EgpWiIts {Surmmgd over n W&t uladu~

Pbotn Filuoem Rate MUiN5 Photon~fr1cmsqu 6.8279-0110 1.54l-Piiroton Enef.@y Fluence Raite MeV/CM*/seC 4.$7e-01 0 1.021ae-008

Expt~ur. anid Doso Rotes-

'Eposure Rate in Air mR/hr 8.758e.0 13 1.97ge*011 Ab.rl;t~d Dom Rate in Air mGy/hr 7.6$4eO15 1,7289-013 mrnrd/hr 7.64,5a.0 13 1.728e.0i1 N'CR Dos Equviwtcnt pftc fIC.PP 51 - lg7) aoParafiei Geometry mS'v/hr 9,O52e.0 15 7 ,247e0O 15 2-0466-013 Qpmj 7.247e-0 15 1.~630" 13 640J98-015 1.448eO13 Shallo~w Dose Equivalent Rate o Paraflol aewicry 9,21e0-015 2.174E-013 aoOppos.ed a RotationalI 9,1389.O015 2.065e.0 13ý o Isolopic mnSv/hr 1,5Q8.013 0

$8.004-015 c Ariteriar/Posterlor Qeoiietay 1.80ge-O13 7.065e-0 15 a.Lateral 7.313e.015. 1. 184e-013 0 o~o~

5.$75ie-.Q5 C1-149

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 VIqvro~hlq~d W50 (5~.0440362)

RadiofogIcall Seticivs4 Inc.

Page :1 Filc Rrof; _ _ _ _ _

DOA File :.PB122127-MS5 Date:______

Rl3b  ; Dftamer 211,200 Rw kii m~e; $ASAO P1I¶ Checked: ______

Duratigm ; O Case

Title:

Line 1.641 C Description. Hirvised Model C!!14: Ei-6 Wilt AVI WUhecl 40' & 12 in 5hMd G~eon~etry.: 10 - Cylider Sutface - ExternalI Dose Point Height 762-0 cm 25ft G- Radius 4,0 in Do~se Poirtqs X

1. 114-32 1 91,44 cm 4 ft 7,6 an 12 ft 6.0in $ III Shiel ds

(

.6 CM If rntte 1.2 Shieid L ShielId .9 30.48. cm Cc.-ricete OD.86; Air rlao aAM Wi1 1' t 025- cm Iro n GaroupiUng, thod , Standard findles Lower E1tetley Cuitolf t iOj[115 Phutons -, 0.015, Excluded Libraty , rove buwa~l.k u~i~ml E.u152 2,1990c- 8,10'49 2,e+ 00 4;500 u0VvC' 15 /5'crO0 BuilJdup The material referience is CytI Care Integration Parameters 20 Ci rCLmcum~r,,iti lhwha E2!r&%gro Rat-o 4,79afig~ix M&bL N-, Buildup

&,,F94ie-4 3.645e-42 4.091e* 3,5 Ci-150

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page 2 DO$ File P BI22127.MS5 Run Date Dwcembar 21. 2005 RFun Time: 5,.35:40 PM Dur-tior : 00:00:01 FIlnc. Rate

,VtrnI, lhr 0.05 I. 1*9Be+D 2.72"e-27 7.410c,31 7,2489.30 O.-1 2,303e+00 4.62e- 16 7.OM le-1 9 4.221e*-

0-.2. G.O*e-01 6-925e, 14 5,617e.12 I .:W4i, 115 9,914e. 15 2,579e.12 3.57le-lO 4.893e. 15 2.979e.13 0.4 5.&90e-01 2.747e.12 5.352e.15 2,342c,13; 0-5 4.56ge-02 7.SA*.15 1.500e, 15 43921e.14, 0.6 3,434e.0] 11460, 11 3.621e-10 Z 744c. 14 7.67e, 1 0-9 1.442e+t'Q 2.312e- 10 4.398e. 13 7.7139-12!

1.55 09 1=1*5-00 2.37t-,12 $Jt7O4e, II, 1.5 1.879ei-00 4.762e-09 8.01 2e- 12 6.430e- 11 TOTAL!5; 1,877e+Q1 6.303e-08 1.133e.11. 1.1 M e.10 C1-151

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 MikroStibeld vS.04 (S.,04-00362) 12(21/05 MicrvShioIld vS .04 C5.04-0OD&52 RadloIogimal Services1 In~c.

Covtfr *f callulated exiufo!~~ Wit to~das FILE: C-:\MS5A\OATA\P8122127.M.S5 C*s4 Titis., Lain L~$41 C:

This, c3&u was runi an Wadne~day, Uvgcibgq 21, 2005 at 5:3!M40 Phi

.Dose Poita I ý (1-  :ý UIt3

- 19t44) c m

-Wrtbou -%I 0411141ý Photo1~nsCrW/Sc 5.21 Se-DOS Pho~ton Eneiergy Fluence Rate MefV/cm2/`see 6.303eOQB 9.8$0e,0104 Expeure Rate In Air mR/hr 1. 1,03e-010 Abwrbe Clue Rate in Air ra~y/h r 9.633e-01 3 mradih~r 9-633e-01 1 (ICRP 51 R87) a Parallel Ge'ormetry rn~v/hr 9i424eo0 13 o ot~taional o 1iS01hropivc 8.4 14eýO 13 1.0123e-0 13 ShaIow- Dose Equiva lent Rate. 9.134e,014 mS'y/hr 1.167e.0 12 ac Opposed 1.1 24e.0 12 7 .460o.014 o IRCotationa 1.124c,.012

~8.41e-014 8,906e-O 13 caArnten or/Posterior Geometry m~v/hr ai~iPf~rir 9,074e-0 13~

aoaea 7.204e-013 oi Rotational 7.4"qQ014 a lp~

Page L C1-152

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 Mlcroftiie¶d 0e.04 (S."40362)

Radfolagicall Ser~ices9 Inc.

Page ;I File Ref; MIA~ Flle : P9ia2212&aMS5 Deate:

Sy:.. _ . ..

Chocked; =---.

Run'Time; :~4823 PM Duratiop ; 00;00:01

.Case, Title, Line 1,641 D Discription:i Rgwisd M49del Malt. Evi.164 Uirt Att w Sched 40 & 12 in Shfa Geottiett-yi 10 - Cylinder Sutface - External ODse Pointt Source Dimensions Heightt 762.0 cm 25 ft Radius 10.16. cm 4.O in Dqu rufTb z

Ak1 141.32 c 'M ý$! CMY 91.44 cm i ft Urin ~It ShicIds DIMbE Li~oJa Ma 10, 16 zniý o rtee 1.8 I

• Shield TI .s CM Ilic 0C"nc~reto 7.*6 2,4 Shiel.d 3 30.48 ocm Concirete 2.4 Ale Gap Q.QQi2z Wall QIad 7,ý15

'Q25 GM Irg, t Source Input Grouping NMthod - Standefrd Inidces Hunibe.T of Gitoups t2 Lowet Eniergy OuIol -ul iphDIons -90.015: Exdiuded Library ,.Grove Eu-.154 2. 189Ce- 1C1 &0992#+000 4,5=e00eG *9 1 gam!

Buildup The miatef lal regerence Is :Cyl. Core ha~egratimoI1 Pairameteq'si 20 Cirgmorita 20 Resuhts M Activity ILMQU29k Exwsue Rzte leý rjbo12naZ5z MAýLýc r No au ji= E4225w Bat

)4 1.ý4842+00 2.99le-40 3,1020-331 .323e.42 C1-153

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Pri~c -2 DOS File :PB1221-:S.MSS Rtin Date - De-em ber 21, 20C 5 Run Time: 58!$ PNI Duraition : 00:00:01 flijVInMR/s~

0.05 4. 1 87e-01 9.7 1ge-2,9 0,1 6,5870-16 1.008e. 18 0.2 5,~778c-02 6.2 20e- 14 1.5 7~e 8 1.N-Se.16 26-00e- I1I 0,4 3.1 196-13 6.0-77s*16 0.5 1. 65e-.11 1 .754e-0~2 2.934e-:,3 5.760--.16 1I8aBe,14 0.6 6.1.5-e.O01 2.7e II 6.8876- 102 5,2 1 ft 14 1.3-44g.12:

0,8 3, 158a+00 54.0644.0 8.88 1e-O94 9.633e- 13 1.689e-1 1 1.0 2.49~2e+001 I .1O7e,(19 2.0 4* 12. 2.663t I]

1,5 3. 16Oc+oQ -8.0108.09 6.42:8e-06 L.08k*1c.

T-OTAOLS: 1.54e+D1I 9.$50e.09 8.833e-08 1, *- 11 I.53 1. 10 CJ-154

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Mwwruhies v5,04 (Sz04-0032)

MIkro9Iulod v540~4 (10440O3)

PRadle~ftkial vc*,t Coo~inve of cakIculmd expesure If#a31r to ds Ca"*~T~tf; Vitto 1,641 D

~This caso wait ro an Wircsp. Owmoion 21, 2OOM al 5:4B,21 PIP

$ ~63e~Q~3~

Pht~V/c-m~o P-tnEneifgy fThienoe Rarte 9 65O.~OO~ ~5~23~ ~

apsead Dow Rat Epgare Kwff A~i mR/hf 1AUC-011 1,531c.O3O l~sa Rate in%

Dz~ Air M~yltv ].W4e-01 3 1.336f-012 msad/Ow~ I.44ae01 I Deep Dos Equivaa 1174 QICP GI - mr o P~ara! lei Geom-vfy mSvihr L 1.31"012 o OPP~O 1:.420e-013 1.311 e-012 o Ro'tational I .42Ge-013 1,172t!012 (C'AP 61 -1M7) mS'dhr I .73170,01 1.614e!012 U

I.678e-013 1.557s-012 o Rotational 1 .67&e-013 1.557e-0 12 0 Ilictropit 1-3i41t.013 I .238e~o 12 Uiv 51-1"7 Al4?eCO,1,1 1.368O I )

c Po~eririAntriur 1.364,0321 l216164 1 cýL fv ', L095eý013 2I.2316,33 1.1~36e,012~

1,9*013 L.00e~o 12 Pap I C1-155

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Mi~croShle~d v5,04 (5,0440i362)

Radiological Services, Inc.

Page ;1I F;Ic Ref,; _____

ID 0'-Ffi~ Pz:FB12212~9.1S,5 Da te 1____

Ru ate: Onernber 21, 20Q5 By:

Checked: ______

Duratio~n : 000O:01 Case 1fltle;I Lne 1.641 E Descriptio~n; Revisod Modiel Citk- A LOFW imit A4tt w Sched 40 & 12 'am Sh~d Geoffleory 10 - Cylinde.F Surface - External Dose Point Sorce Dimiensions 25 ft 4,0 irn

1. 1 141.32 1 ýM 381 ern 91.44 c 4 ft 7-, 3 t Shiklds Cyl, Coro a Shield '1 .65cCM Ircrct 7.86 Trar~ili¶ion 2.4 Shield .3 ~30.48 cm QCDricrete 2.4 Air Gap 0.00122 WalIIGiad r.C25 GM Iru-. 7.86 Sorce Inpuit G~rouping Method .Standard IridIca!%

Num~ber of Groups :25 Lowee Energy Culoll,0.1 Library Grv Uzi 1.1r Cu~rl Aý- 108M 2.1890 2~992e+&30D

&01Q 4.50009.0I09 1.66.50e- 004 The malerial reference Is : Cyl. Core Iritegatian Parameters 20 Ci rcurnierential 20 Results EF-6urn Rafr 1lj n-ý mP./hr

)z 5-312e+00 1 817se-2Q7 ,6-04e-2U9 CI-156

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 DOS File ,PB122129.MS5 Ran Date: De~orniber 21, 2005 Duration : 00-:00:01 Atiavitj Flugng.Ee2*.

mR/Ihr 0108 1J720e.06 1,197ie-79 1.1"se.81 5-74N-0O1 1.$72e. 18 1,41.41Oe~

I0.4 7,2BOei-00 3.3506-12 7-121 e4-00 7,7 18009 7,33-0e+00 1.1758-09 2.061 e-08 2.23-5e-12 12~*

!0e!

TQTAL5,i 2.78e.2+QI 1.514e9-9 3005e,08 2,8970.-12 5.762e-Il Cl-157

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 NlicroSlihie v5.04 0.0O4-00362) 12/21/05 Mi rdgShield 4~.04,(SA~4.OI2)

RedolleglcaI Setvlcet Inca COCgn;i0 V Cawllau9d expasiurv ini air fl d MlE CA.,M9MDATA\8122129A1S5 This case was run an Wednesday, Decmnber 21, 2009 al 5-40,37 PWM base Polni # 1 - (14132S,ý9144) cm~

Results 4Surmmed over enrges [IniL M61 it MLb cull-4ua' Pl~oton Fluence Rate~ (ittim) 2.0679-009 4..292e-OO&

Ph~oton, Ewegy Flutance Rate MeV~cn/cfW i.514eO~9 Oc~oO&

Exposure and Dose Rates-f~xrAurt ae in.Ale mR/hr 2.89 7e-012 5.71&2e.0 11 Abwted D~ Rate in Air rnay/lft ý,25t-014 5,030e*O013 mrad/hr 2.52%e-012 S.03Oe.0 I11 IDeop DUos Equjiv~ont Ratv (ICFP 51 - 1987) a Paradiel G~eiwretry mSv/hr 2,96Ek-014 &.9268-013 2-41 le-014 a Roitalional 4.787e-013 2-41 le-014 2-131e-014 4,787e.013 Shallw Dime Equivale~nt Rate (ICRP 51 . 1987) 4.233emO1,3 mSv/hr 3. 165c-014 a Oppciad 3,.1 5e-014 o Rotational 3 " 1 e-ni 4 6,309e-013 a ljcteapic 2-280~-c-14 4M5eO13 a AnterioriPasterior Gome-tri m~v.hr 2.636e.0 14.

9-347e-O 14 4. 667e-0d 3 o Lateral 1,764o.0 14 3,492e-01 3 ci Rotat onal 2..09ge.O14 4.1 7le-013 0 1zllTo~ir 'I- " 14 Page I C1-158

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MticroShale¶d v§.04 (S."00~362)

Radiological Semrices, Inc.

Page I File Ref:______

DGCý File P8122130.M55 By:

Ru i4 nwime 5-43:37 PM Chocked:_

Duration :00;00;01 Case Title- Line 1,641 F Descriptirori RevisedWO NCfI ale N11-94 Unit AOI w Schad AO & 12 in~ S$bW Geomietry Cy I inder Surffce - External Dose Po~id

'urce Dinienions Height 762.G cm 25ft F~adius 10.16 CM 4.0 in

~77~

9 141.32 cm 3131 cmn 1.44 cm 4 ft 7.6 in, 1,2 ft 6.0 16 3ft Shieulds a.=5cm 990 deI 1.86

!hield I S

el 2*,4 Shield 3 30.48 cm Comrcrete 2.4 AirGa Ait XC25 cm Iron 7.86 Groutping Method : Actuat Phaitom EAejgle-.

No -94 2,199N)-L11G 8.139920~+000 4,5D0000019 L665Oe*-004 Buildup The, material reference is : Cyl. Care y ~r~:~on I r7Iiuration Parameters ,20 Ci rcumi'erentiM 2,O N~o REjillu 0,0174 21.864e-03 7.1g30 Empwc Ra 4.07950--A 0.0175 1.464e-36 7i752e~.39 0.0 1 ý6 1.612e.03 9.99e22.3 5.142e-37 1.0se.3a

'1.7026 sia9sc.+Go 1.47.3cý048 2,w4h- 1

.2I1i 8.'099et00 192 4 e-0'9 3,011 e-018 3L62 L8-12 5.667e. 11 C1-159

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 P3,3 :2 DOS File - PB122130D.MSS Run D~ate; D~ccrnber 21, 2005 Runi T~ime,, 9,413Ok PM Dur'+ion . 00;0:01

ýAF.HVI Fluence Rate EMasgre Rd2 ExPoure Rid&

I&h2Lr&VAA= MR/hr MLhr MeclUse Wif h 61 MAIO No Buildup Mfb bildug TOTAL!5 1,6210+01 2.63N-09 4.484e-08 .983c-12 Cl-160

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 12/21/05 MicroShisld vS.04 (5,04-003432)

Con'vtsion of 611vulatid txpiouirv in Wr 11 g &

FILE. C:\MSSATA\PB122l130.1VSS Cawe Titlo L~io 1,641 F This. case was. rni an Wednesday, December 21, 2005 at 5:.43.~37 PM pos P*OLrtt # 1 14.2 1 94)Cm RCMl (S.U-MIM d ovar ignacgiW Lab~ Mih 5,553e-cxJB PIfboton Erw~gy Flue'nce Rate MeVA~m~/sec 2.630e.OMg Exjxc~sure and Dose Rates.

lxour ate fin Air mnR/hr 4.9 83e.O012 Abj~orbd Dose Rate in A~ir mGy/ht 4,350c,014 7,427e-013 mfod/hr 4.360e.0 12 7-.427e-011i Deep Dose~ Eq~Wlvalnt Rate (ICRP 51 - 1987) oaParallel 11--cT*etry mSv/hr 5-061c-0O14

':0OPPO*Cd 4,.1 Ne-O 14 7,109e-0l13 PoRotat i nal 4.166eeO 14 3.64c.0 14 612879.013 Sahalra Dose Equivalent Rate (ICRP 51 - 1987) 0 Paralle Gt~m.,rnry mSv/hr 5.4 l2eQ 14 9-247e-0 13

r. 1649-014 8.821c.013 o Ralational S. 164e.0 14 8-82le-013 If 3,942c;Q14 6. 727e*O013 (ICRP 51 *1,987) o .Antanor/PastenDr Gelorniry m~v/hr 4.5 Ile*O14 7. 706e.0i13 N

4.046b,014 6.900oO 1.3 o Lateral 304r014 5.240e'.013 a Rotafionak' 3.622e-014 6.182e.01.3

ý11t(1~Q4 page I CI-161

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 M icro~held w50 (5.04-00362)

Radi~ogoicall Services., In~c.

Page ;1I File Ref;____

DQX23 Fitt PS1~22-32LvtS5 D'ate:____ __

Rt Ma., Owemba 29. 2OG5 8hy;_____

Ruhn-fime: 317: 5.3 PM Duraitiga ; MQO;Q1 I ase

Title:

Line 1.641 G Dwet8ipim Revis~ed Model Caic- l1-129 Unklt Act w Sched 40 & 12 In SWtd Geometry; 20 - Cylfrk'or Surfut~ - Wanalli Das fthiw wrce Dimnieisions Height 762.0 cm 25 ft Radius 4-0 in z

N1 141.32 cm 91,44 M

-t it17.6 in' 12 ft 6-0 in ShI*cds 1

CAL Core I r 3 6 cmal Oc4mete 1.8 Shield 1. .65 cm Iran 1.85 Trari'iion Cc~ncjretu 2,4 Shield 3 30.48 cm Ccncrete 2.4 Air 6ap IAir 0.00122 wpI! --.!d 1;2M Jrqn 7. E Glimupling MNethod -Ac~tuai Photwn nE wgles 1-12S 2,16SNOIO US52e,000 4.5Oci0e-00 )..665oe-0o4 The material reference, Is ý I.', Care I rrtgratloii Pafarneters 20 i~rcurnferen~tial P.0 1.169Rake 6Z-99%*77 1.117@-33 7.01lle.79 1.07ae-74 2. 137e. 33 1ý052- 76 2-1 4ý$7 2.073~e59 0.0396 6.09 e-ci1 1.i7931641 1.134e-33 8.1I46o.44 Cl-162

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 page 2 DOS File PS12292 1.MS5 Min Date; Dtcc.mrbor 29, 200~5 fb~n '?rme: 3:17:53 PM Duration MEL~j~gLEa" ExasLgBai fIV1WJe; f4iLT/h TOTALS: 6,2909-00O 5 .504P-33 8. 146e-44 Cl-163

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 hM~crShleld w5.04 (5.04-00362), 12/29t05 MImr~hield v50 6.4O 2 Conversioni of cakulated exposure -on air to dose FI~LE: CA\MSS\dDATA\P8122921.MSS This case wrar rmn on Thursday,1 Decemnhr 119, 2OC5 at 1~17-93 PM base Poklo 0 ILý 14t Maflýk~44) 1 cmt With gUillclug Pftoton Fkgqmr~e Raft, (f~lux) PhotonLc'IT,/sec 4. 529e-040 1.7,15c.0-31 Pfhoton Enetgy Fluerice Rate MeV~emlI/%" I ?9 0O41 &50549-033 Exposure and~ r~os Rates-Exposwre Rate in Ale mRfhr &146e-044 4.644e-C35 Absorbed Dose Rate in Air MGY/hr 7,11i40463 4MU54-O37 M

mracl/hr 7;.1 ie-044 4.034e-039 a Parallel (cometry m5-Y/hr I.Q]~eQ45 4,1641 e-0~37 o Oppos~1 5. 127e.04.6 2.328e.037 a Rotational 4.642e*C'4 1.flel~,37 1.844e-0:37 o P~aralel Geenrn~tfy m~vhr 1.O~4e-045 5.05&.037 a Opposed 3.47ge.037 a RotationalI 7 .070e-046 3.478-e-03 a Isotropic 5.E1BO41001 2 ,57 Ie.O37 a Arrterdor/)Posterior Geornnqy mWn /hr 5,.935o.046 *Q7.06e37 IS.e.041 o Lateral 1191329-046 5-807e-038 a Rotatponai 3 .226e-046 1 09I-O 0 I~cw¶supie ý:WC.44;Q4 Page I Cl- 164

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroSJield v5414 (5,4-00362) 1Radiollogicall SejvIces,, Inbc..

page :1I Fatle r;____ ___

Date:______

Rt. ate: Ja nary 4,. 2006 By:

Rwn' Time4 : 1i3! 8 AM Chec-lied:___ ____

Durationm :00:00:01, Case

Title:

Line 1.641 H ReviU~t~ised M4oclel Ce~g. Stb-12 lljodit Act w Sched 40 & 12 in SIl~d Go~m~etry; 10 - Cylinder Swuac~e - ExtienalI Dose Polne Source Dnuunsioos Heigt 762.0 cm 25 ft Radius 10.16 crm 4.0 in Dose Pointis z

1. 1 141.32.c 'M 381 en. 9 1.44 cm 4 ft 7.6 3 t ShieIdr, iii.. Cyi. Cc eree Shield I .0cr Ito 2,4 Shield 3 30.48 cm Ccno Lte 2.4 Air Gap Aii Wall -Clad .02.5-cm Iro-n 7.86 Sommec Input, Groepling M~etlod : Stan~dard InidIces Mwib~er of Groups ,,25 (Ldwet Uea Cwtll U 0,01$

Library:.. Grovei Sn- 126 21139N~.-rn o & 0920g-000O 4,50000,001 9 1.6165011c-004-awildup The material irefeieence Is -.Cyl Care

. ErAegrairion Pwaiiefers 20 Ci r'umfortnitial 20 Results PAUCm'IMCe Fluctire Rate~

02 6.269e.0 1 221 Go-2~08 7.676e.210 7.145e-36 C/-165

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 Paige -:2

)O~S File :P80 10406.0M5 Run Date- )anuary 4, 2006 Riun Timpre: 13: 18 AM Dur-ticon : WOO:01 DmeL E&L 0.04 I 1,61073 1.71 le35 0.04 7.340e-42 3.246e-44 7.76le-01 1,042r,,1 2.070c. 24 0,08 5.345-237 3,857e* 16 1,~612a.20 TOTALS: 7.534<640 I1.019e17 3.857e.16 1,612e-20 61034-19 Cl-166

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 Mirra~hield i5.AO4 (S.O4-WIG2 0210 4/019 M1k095i~4d vLO4 (51.04403Q21 FILL" CA5SSOATANIM104MMS Case TfuethiaLn 641L It This case was~ runwi Wodd Jauaury 4., 26 at &13:2M AM Dese IQtMid (4I31,A4) cm Re-1S ('Sa~~ tye enerzes~iUL j_6_ Without P1%AOqVc"1ý-(Stc 1.273e-G t 4.&2le-015 Mevlblw/sac ai.0I1 %L1 I 3.5tQ

f. rciur Rato InAir m1~r I .512.e.20 6, 103e-Ol19 Abvw ose Rate inAir rnc~rIi ) ;407e!022 S3~28o 021 i~i~8,~/hv L.OUe-= $,1284-010 (IC-ýP 51 . 1:R37) a Paraiai ~e..r-etri 2 .4~652) .022 4,964e021

~~1,3e-022 4.84g-02 1, o otar onai 4 .790e-02 1 1.274e-022 (ICRP 51 - 1M, 6..7&*02 oI iifjlpc~ 4.981e-O2 rn9hr 79.7i3e T.92Th.021 Ci Lateral 5.0&%--02t 1.087e. 022 Par I CI-167

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 fti1rfzShield 0i.04 (5,0400362)

Radiob~ical Sef vices~, Inc.

Page ,I Fii.t Rc~f;_____

DOS Floe :P1B122-923-1095 Date:______

Rh f t Dx vmtw 9 a, 15 FI3y:______

Chw-:e _______

Case Title. Line 1.6411I Descriptiow Reviise OTdeI VCalt- Zr Unit ACII w 5lihcd 4G & 12 in Sbid Geomietry-, 10 aCyllindet.5Surface - External Dose Poinit Sou we Dimensions Height 762.0 cm 25 ft Radius 10,16cM 4.0 in 381 em z Al 141.32 cm 91.44*crn 4 ft 7.Fj in. 12 ft 6.0 in 3ft Shields L~*I"" MikLiA i1.*

• Shie~d I 2A4 Shield 3 30..48 crn ,,onesete 2.4 AiwGAP AirT 0,00122 WallI Clad ' ~25 cm IrcT. 7.86 Source rInput Gircuping M~ethod . Actuall -Plitori Eneiieee Zr-95 2. 1B690e-i01 G &C992e+000 4,5000e.O009 The maler~al reference Is :,CyL, Core Intay~aliori Parameters 20 Cir~cumrferential 20 Re sults MeV./mllsec

0. 7242 3.5368+00 3.5~57e-10 7,125Ai.09 -6.940e-13 0,75V 4,483@+00 $,544e, 10 1.047015 ICM10.12 2.00~e,1 11 T41TALS: 8.0188+OCA .10G1e.1O 1.76C0-CS 1.745e.12 $,375t.1 1 Cl-1]68

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MkraShbold v5-04 (5.O-4.U0GZ) 12/29/05 MicroShlold Y5.04 (5ý04-0036Z)

Radlo~gicall Services., Imc.

FILE. C:\MS5\DATA\P612ZZ2LMSS C444 T110ec Ll- i"14411 This cas.e was vim on Thurs~day, Decembef 29, 200 at 3,21-.15 PM R&i4itl ISummad 2ver energi-s ~i. Withou+/- With PbotonsJcmVlser, 1,.224e-009 2.36&e-008 Plvton Ertaf y F1 uence Rat~e MeVICV/2 See 9-10101010 Exposure and Dos R~att; Exposure Rate in Air rnft~lhr 1.74$e-012 1375c-D 1 Absocrbed Dosea Ra~ke in Air 1.523"-O14 2.946,e-01 3 rUrad/hr 1,5230,012 2.946-Dl I Deep Do~se Equiivalnt Ratc a Paralilei C-reu-aetr/ m~y/hr 1.78~6e-14 3.454e-013 1 .452e-0 14 a Rotational 1 ,462"-14 a I'sa.Ifopic 1.28Ae-014. 2.BO~e-D1 3 ni Parallel Ge"Et~ry m5-/hr 1ZI 7e-014

-3.513e-013 o-f se Eotl 1.3 74e-01,4 2.657e-01 3 Elfective Co~E iivalen' Rat ai An~te ritir/Po9sterior Oejom.ietry mS-v/hr -31,067"i'O 3 1.4130-014 2.732e-01 3 1,062e-.014 2,054e-01 3 a R~otaoionaý 1-.264e--0314 2.444e'DI$

aiIrIpL 1,082~-u414 2.093"~1 3 Page 1 Cl-169

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MictwShield w5.04 (5.04-00362)

Radooicr~al Services., Inc.

Page ý1. File Ref: ,,

DOS File ý.PB122'924.MS F;4 aw-D.cer~. 29, 200' By:

Runm fame: 3:44:47 FRi Checked:

Dura~tiGM : 00:00:01, Care Tiflw. Lime 1.641 1 M~scription: Reirisgd M0101CODe8 wEO*-5 Un~it AO W$ChecI 40 & 12 in Sluic Gem~etry.ý 10 - Cytirvder Surface - External Dose PONo 25 t1 Radius 10.16 Cm 4.0 in Dose Poinzts t1.4 1.i32 c 381 cin 91.44 cm 4 It 7.6 in 12 ft &0in Shfalds rial 1O0.16 cml Concf 1.8.

Shield I 65 ci n

Tronl~iiior Concrete 2,4 Shield 3 3,048 cm. Concrete 2.4 Air Gp Air ,OG122 WaI!] Clad .025 crr; Irrin 7.86 Soiurce Iniput Gre"Ipng Methad -Stanidard Indices Nuibtw of Gr~ups 25 Lowo~r Efu*y OAizil 00-Pbuotons < 0.015 zExcluded Librar).:Q'rate Eu-L55 218~~ o'lt 8.0992t+000O 4MO5000eO 19 I '6650eý00O4 Buildujp The inatertial relerence Is :Cyl. Care Frtgratibn Parameter s 20 Ci rcumfere-itial EneM, Z-'LW=&.aLa.

M^.Y Me-VICMV56s 'MeV/cm'/ sec 257ctiit With Ewildwo With Buiffur) 1.794 .75 1ý876it,3 5 1,778e-77 I iO-9o3 CI-170

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Pace .2 DOS File -6PB'122924,MS5 Rurn Dale: De-cernber 29, 2005 Run 'rme; 3,44:47 PM Dura~tion ; MQQ:;I Lne Acflwij,ý

~+/-Flugo iIt NDBuildup a .C4 1-46$e+.00 1.1 7&-42 1,~253-1 0.05 4,775e.01 1.108e-28 1L.64e-27 2.953e-31 .2.888e-30 0-06 7, 2341-24 1.411e*222 1.43?e-2S6 .2.802e-25 0-08 21 51500 6.8%9e- 18 2 .60ge* 16 1,09-0e-20 4,127e. 19 0.I 1.6.74e+00 3.36e1 2-006e. 14 5. 1480e~9 .3.06ge-17 TOCTALS. 6-266e++/-0 3-A344,16 2,032e, 14 5,257e-19 $.1Oe-1 CI-1 71

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 12/29105.

MicroShield wiS04- M0-02 RaIcodogleal Sernikes, Inc.

pynvrsiloo oif c~cutalld exposure In air to doseo FILE: C:\MSM\DATA\P8hI2224.M.S Case Mite; Liveo L642 J This case was run on Thurslay, Decem~ber 2.9. 200S at 3:44,-47 P14 Dose Poinit # 1 (14LU,3,81.91A44) CM mbr Photons/cm~lsoc- 3.45le-015 2.0aL-013 Ptoton Elbei Fluenc Rate MO/w/cfsoc 3A4s4-01 2,032e.014 Expcoure anid Dose Rates:

Expasure Rate in Air rn~Rhr 5.257e-0 19 3-11 0eýOI 7 Ab~bdDm Rate ;jfl Air m~yA-!r 4.58ge*021 .2-71 5e-019 mad/hr 4. 589e.0,19 2171 5k-,O 7 Clew Dose Equ iva~ci; Rate (ICRP 51 - 1M7) mSv/hr 9

7,6779e-021 4.54le-019 4.207e.021 2.489eý01 9 ci Rotational 2:48&4O19 1*Is1

$1pie 4.07 1e-021 2.408e-01 9 Shalgaw Dotse Equivalent: Rate!

ai P'arallel G~eometry mS~v/hr 7.627o~.02,1 4, 511e-O0 9 a

5;9 12e.021, 3.4 98e-01 9 o Rotationat 5.912e-021 1.4-9&01 9 o Iwtrapic -4,30-50-021 2,547e-O1 9 Efibctive:Dose Equ~iv~alent Rato (ICRP 51 - 1967) o Anterorlilasterio'r Geormelty m&SY/hr ,6.597e.021i *3.902e-01 9 e Pose ior/Antwior N 5.170C.091 1O-Mee1 9 o LWoro1 4.419l-O21 o Rotational' 2.613e.0 19 131sojlropic page I CI-172

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 Fie Ref; _ _ _ _ _

Rwitiftke: 12J h Checiked: ______

Case

Title:

Llo 1.81 A2

&Gegmfei: 10 -Cylind~er Surface- Exlernmi Do". PoWp

",ighl7 62.Uvm Rm~diu3 7.62, z

N1 1,30i78 cm381Cn 4 ft66 sin 1Zlt0in

'I Cyl.. Cgfe 7,62 on' Cikncrr.

Shield 1 ~ 65 om Io T8$6 to 2,4 30,48c Cana*e ~2A Air Ggp Air 0100,122

.0250 n~ 7.86 Grouplrng MethM - ActialPa w n L IZ,=i ruck" i.1 h-010 fkO 1 .6&50e-004~

The ffawet~l feI6wence Is : Cyl. Car~e 20 20~

FRu11rii

~t~n~Ic~c

'NO uljý V14th BwUdkLi Elumus IU ' :X4 M 0,&r, CA 1.ItL7 32 38 15W: 4@41

,ALS: I1.

J75e.09 ý2 45e, 1.1.

CCI-173

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 OlKwo~hicid 4-04 (9ý04-fl3612) 12/19/05 Mikrogbioed 4.04 (S4W Radiologlea I Servkes, Inc.

Conversion ofW callullawd .epo.ure In air to dose VIFI+/-E 1:A-M55\bAMTPB1219174MS5 Case Title; Lino L.A1 A2 This case was fun an Monday, Deceniber 19., 2009 al 1.-18,19 PH 00sos POWu # 1 (1571-8)~~

QeU1lst5.451mnww$ ime W&4Wto Photm/crk/sec 921 9c,010 1-279e-008 Pitoton Efwgy Fhieneie Rate MO1*1rn4W'sec 1.A75e.-OO'9 I -621e.008 Exposuro and Dote Rate-

~Expoure Rate inAir .mR/hr 2ionefol 2 2,845c-01 1 Abs~zrbed Dose Rate in Air m,Gy/hr 1.798Ek4014 2-483pa-013 rnraAd/hr 2,483e-OI 1 o Para~ieI Geosn-etry m.Sv/hr 2.04 N-O0 4 2,81196c,013 0iOppmed 1.75ge-O 4 2.42ge-01 3 o~ Rcgtatonal 1-7,5U.014 2.42ft-013 1.571-e-014

$haIlrw Dose Equivallent Rate (ICRP 51 - 987) o P.zratkI Gmmmryidr mS'v/hr 2. 172e04 3.Wle~-01 3 o Opposed 2.091ae-G1 4 2,B90e-01 3 2,091e-14 2.90C'1 3 o IcctiwRose. 1,6&4e-0 14 2-.29ge-0 3 I

o A.ntarhoPosrteri or G~eometry 1,8371g-014 2.53ge-0 13 1.693e.014 2..31eaU 11 a Lateral 1 3489-014 1Z60e-01 3 oi Rotaionri; 1 52 se-0 14 2JO06e-J ii 1,.350a.O014 1,5864-c-0 13 Pajo IL CI-174

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MlcroShl~d v5O.N (5.04-00362)

Radiologicat Services,. Inc.

Page :1 -File Ret:

D08- FiNý PE1122i13iMS5 By:

Rvifýunrn: t~: j 04A' Cho~cked: ______

Duraticon 00:0O0-,0 Case, Title-, Linie LII B Derscription; Revised Model Cakv Cs-37 Wiit Act, w Sched 40 & 1Z on $W4~

Gco7Ktm 10-USovStae xeil 0*e Palm~i~o Heigitt 25 It Radiug 7,62 tmr 3.0 in Dose Point 12.885 cm in 12 ft 6.0 in IQ5ft 01 13.c 7,632 cml Conc r-t sheied :i .66 ern gIro 'I) i Concret a2.4 Sie!dC3 3.acm: Concret 124 Air lap Air 01001 22 Wall Clad .02-5cm tron 7.86 1.5S3100 .7464.e,400- 4_25'?Oe.0fl as-13711 1.15417e;0 N 6.07441,-000 4,5000o.00U9 I .6650e-004 The materlal referen~ce is CyL. Care iFalegraffori Paraiinetws, 20 Ci rcumnicrwitidl 20 Recsuka Flu4ncrc Poic woq9 A-gildutp 0.0318 &0900.83 6-739e*8F.

0.0322 1.298e-34 1,8.34o.82 1.044e-36 D.0364 7.97e,02 4.644c*62 2.63$e-64 5;1714D*00 1.200e-1 I 4.374-.. 10 2,.326e-14 8.479e. 13 C1-175

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 Pap :2

, 1 DOYS FRe :PIB122131.MS5 R~un Oat Do.crnber 21, 20D5 Run ¶sme: ý5A7:30 PM Duration~ QOn.;QQ:O MO~rY paos fLCxQL&-IiQ Rxng rr M1 Exp2sure Rat

-MeV(j-rn2/sjj MeV/crn~sec zl&ýL

&, wildu flL~L~ IýUb gWqýdWp TVTALý.- 5i;9,, 1.200e-II 4.374-*10 Z.3260-14 8.479e- 13 4

C1-176

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 M~icro~hield Y5.04 (5,04-0036Z) 12/ 21/06

&IficroShuield Y5.04 (5.04-00362)

Radlilo1goeall servicasi Inc.

Convwsrsur of c~alulated exposuire In air to dose FLLEL C-XMS5XtDATA\P81Z2131.MS6 Casmq TRtIC: Lhq 1,81 This case was run an Wednesday, Dlemmbe~r 21,.2005 at 5: 57:30 PM PeSIjlks Qimmed over eau~rgie Uik Mhoton Fiveimco FRato (Flux)

MeVICMI/sec L-20Oe'0.O 1 4.374"103 Exposure~ Orid Do~se Rate$7 Ex~posure Rate in Air mRihr 2.326ie-O14 8.47'9ý- 13 Absorbed Dow Rivto in Air rnl~y/hr 2.-0. 16 7,403s.O015 a

imriad/hr 2,0309-014 7.4a3e.O1 3 Deep Dos*e Equiva'Unt Raie a Paralilei Geomnetry rnSv/hr 2.404e-016 S. 64.e-O2l5 a Rotatio~nal 13.,25e-016 7.0114e-015 a Isotiropic 1-702e-01 6 6.20l59-0115 SbaIlaftj Cc~se Equivalent Rate

- a, Paralflel G~nr~utr' rnSv/hr 2.555e-01 6 o flPpo-e &8$47e-02 5 a Rotational 2.427e-01 6 8.47e-03:5 (ICRP 51 - Mq7) o .nteiorP~-Gt~cnrty- mn-v/hr 1 qq1A-MF. 63840e-016 o Lateral 1,.42'7ei-01 !5.20O4e-01 65 Pa"o 1 CI-177

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 MicroSheied v5.04 (5.04,0036,2)

Pa &e -,1 DSFile ,PR12-2132.MSS R-adiologicall Seqices, Inc.

HeRef By-lRumrfi me: 6:r01: *15PM Checkted: ______

Ouratign;Q0;Qn1 ICase Ti'tio, Lin~o 131 C p4-cripiorn: RoyisecI Mde -rc.Eu.152 U~nit Agt w Sched 40 & 12 in $hW Gecomelry: 10 - Cylinder Surface AExtoinal Dose Mait T Heig'nt SOU Me DImenlshrns 762.0 cm 7.62 erni 25 ft Radius 3.0 in VuePgpuv z

J1 138-.78c rn 381 cm 182.81 cm in 12 ft6.0 in 6ft Shtields Shield Name Dlimesin M t rit I. DelsitV Cyl4 CMr 7.62 cml Gonciret e Lý8

$hlelcd I .65 cmy Iro 786 Trans i~on Concret e 2.4 Shield 3 30.48 cm C-oncret e 2.4 Air Gap Wa.WI Qa;d .025 cm Iroi 7.86 Group~ing Method -Stamdard hIdlce&

Nvmiber of Grmqupi 25 Lower Ener~gy Ctftff,, 0,01S$

,Library: Girove Eu -152 1,6417.0-01 6,0744e+UOC, 4,5C00G'009 14 66509-004.

B~uildu~p The rmaterial reference [s -Cyl. Care I ftegraflon Parameters YDirectijon (ax~ial) 20 Ci rcumtorvnfiti 20 Rurrullis Flumnra, Qnkir Exnanur MR~

99ý4ý-' ý a' th al life'.1.0 2&I Ell 2WULL'U

4 3.5949+-00 5 454-50 4i 525e-a-3 2.QQ29-35 CI-178

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Page :2 fJ0$ Fil~e . PB1221322AS.5 Run Date: Dvernbcr 21, 2OU-5 Time,. 6--1,15 PM aRun Duration -00:00:401 FRuanre. Rate 0.0,5 3.1387e-0 I 6.*4 2&B-35 4AJ64-33 1,712e37 0,1 4.5S35p-22 4.352e.20 3

0.2 4.552e.0 1 2,821 e-16 4.979e-19 7,85~8e.17 1-4eQ"QD 21 46e-34 2.443e.12 4.O071e-3 7 4.634e, 15 0.4 3,817e.O1 3,67 5e-i 4 2,794e, 12 i6,96e-] 7 5,444e. 15 0.5  !..380e-'!4 7. 755e. 13 1.522e. 15.

.2.7C6e4?7 0,6 2.576C~.01 3.272o' 13 1,388c,11I 2,71 0t.14-0.8 1-082e4O00 7.865e* 2 1.40,e-1 4 4.073e. 13:

3.0 2. 59f+00 $- e I1 2.476e. 1Z~

1 .5 1-409e+00 3.350e. 10 .3.726e..09 5,636e-13 '52ýe 12a TOTA1,5; 1.4Q;Oo+g I 4,1 Ž2e-10 5,3033.09 7.065e-13 9.1oe.12 Cl-i 79

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MIjrm~ttel vL04 (S..04--0362) 12/21/06 ftadlataglcll Sevvlces, Inc.c

• Conversion ovf catculated exposure In air to (JS FILE C.",HISMATA\P812213111VI Casc Tite: Uric 14 C This case was tun an Wednesday, Dece.inbr 21. 2005 aot G.-O1k1 PM MeP oin 9 1 - 2 S C1~S)i1 M

Uh , SWilh Pho~ton Fluence Riito, (ilw) Photonsl/cmz/sec 3.0 Zge-01 0 4.135iq0 Mw~tof Em.egy Fluence Rate 4.122e-010 5.3034-009 Exposure and Dose Rates Upa~sLure Rate In AIr mR/hr 7,065e-01 3 9-190e-01 2 Abs~rbed Dose Rate in Air rvGy/he B-Z0L14 rrirad/hr 6.167ewO1 3 8.023"-1 2 Deep Dose Equiva~nk Rate (ICRP 51 -1%-7) a IPeraflef Gecmetry mSv/hr 6.997e-0 15 ,9.2e014 6.068G-0 15 7,4870e1 014 o Rotafional T7,09.0~14 5,432e.015 7-036e.014 Shaltow 'Cvse Equwivalnt Ra'kW m*$v/hr 7.4 lge-01 S.

7.167e-015 9.3429-014

• Rotational 7. 167e-0D~1 9.42e.014

• lwotropic. 5.73-70e . 15 7.4.35c.014

• Efiecti-we Dose Equ~iva~lonit Raitý (iICRP 51 - lad7) a Anterior /Posteruor C~eormetiry m$vlhr 6.30le.,015 5,828e.0 15 7.5699-014 a Lateral 4.680e,(315 6-042e01 4.

a Rotiatkira., 5.258e.0 15 6.822c,014 41§740 ,915 E;.0449-0 14 Page 1 C1-180

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 N lcmShleld v5.04 (5.0400362)

Radiookgical Servilces, Inc.

Page :1I FilP Rcrf; p$et Nie F-B122.133-M35 Date,.___________._

RL a~teDtlember 21,20D5 Byh

'Chaced;:td .

PýTirme: 6:08:42 PM Duration 0OQD;QQ-Q

.Case

Title:

, Line tBI ll Dac~ripti*n; Rowlsed O~Id Oak.- Ew!64 Unit Act w ScIhod 40 & 12 In $h~d Geonuietty: 10 -Cylinder Surface - Exter'nal Do'se Poini Durce Dimlensions Height. 762,0 cmn 25ft 3.0 in Date Points z

1. 1 138.78 cm 182.83 cm 4 ft 6.6 in 12 RS.0 in aml:

Shield%

CyrI, Corez Xe.t e 1.8 shipeid I~ .65 cm Irc ft I'll.86 Tr~jrv,3i1i ýonvrA,rte 2,4 Shielci :3 30.48 cm C.onc ret e 2.4 Air Gap Aiir 0.-0o02?1 Wad'"C lad ,0325 crn, Iro': 7.86 Source Input Grpng ethod :Stanidard Inidices Wumber of Grroups 25 Photons < 0.015 : Excluded Library: Growe au.1k Q, 21-Eu -164 1,6417t, 01 60744e,+OOO 4,50O0a*G( *9 1.665GA-004 Buildup Tiw matriarIl ireforence, is ; Cyt, Carv' I'degra'tion Parameters 20 Ci rcumtlerentiaR Rervuhrm r1tjr..nrn Bate Emu= -Rah M4VArM2/z;Or PlionrA5 M "I 6.886e-36R;4 italug= Ug Quil2la L41236ie+00 1. 557Q-31-3 83120-53 CI-181

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 D06 Rie : FB,122133AAS5 ftu i 11ime: 6.08-,42 P A EuELLIk 3.1409-01 24 2e-35 1 .455o.33 5.9.838-38 3,8769-36 0.1 4.219e-)A 4,0869-17 6-455e22 6.281e-20 4, 1489-01 4 ,05U,~ 14 0,2 2,5-71e-16 4ý30 19 7,162o-17 0.4 4.334e*02Z 4;0599-I 5 3,1729-13 7.908e-1 B 6,181e-'16 0.5 I McM~0 $.29'6c, .5 2 "977-e-13 1.040e. 17 5,843t. 16 0,6 4.900.e.01 6.2239.13 2,64le- ii 1.ý2159-.15 5,154e..14 0.8 2,369+O0 1.723e, -ý 4A9§t--10 3.276e- 14 9.920e, 13 1.0 1.86ge-iOO 4,957e, 11 94ý57e. 10~ 9-138Ac 14 1,78Qro.12 1.5 2.3 70e+00 5.63,5e.10O 6.267e-09 ,4a1e-13 1.054-.1.1 TOTALS: 1.168e-01 6. 30ge-10 7,728e 09 1-073-o-12 1,327. 11 C1-182

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 croSlielid v5.04 (5.04-00O362) 22/21/05 M*icroShuied Y5.04 (5,"00362-)

Radiabgkeal Sftvkces Inc.

Convw~sion of cakulatm! exposure ini air lo dEos FI~LE. C.AMS5'\.CATA\P812.2133,MS.S C~se TitleU0 LIX 1,l This case was run am Wednesday, OKeumei~r 21, 2006 aft &.09-42 PfA Doise Point 0 1 (13&78,391,82Ms) to ag 'k. Srnrned over engrgies an-Lt.,itL PF-*&jtor Flu~e~ce Rato (flux) Photorns/CmyhseC 4.47'$-01 0 5, 775e-0G09 Piifoton Env&~ Fl wence Rate MeV/cm1'/5ec 6.30%e-010 7.728e-009

&P~v~sure aind Dose. Rkct.

1,;psijr4, Rate in Air m.Rlhlr 1.07,3e*0 12 3V3Z-e011 Abs-rbed Dose Rate in Air 9 37 1o;0.15 1.1 -S8*O013 mrad/hr 9.371le.013 1.16see-11 141e~p Doso Eqiain. Ra~to a Parallel Gewietry rn5v1hr 1 .06,2e,014 0 Opposed 9,237e-.015 1,1399-013 o RoDtational 9.237L-015 a IsalTopic: ( HP5

-197 5,28i*.01 5 1.020e.-013 Shallumi £C~se Equiv~alernt Rate a Paratlel C-4rmetry- 1 .125c-014 1.395e *O013 a Opposed1 1.088e*0,14 1.341e.013 o R-otational 1.OMe-O 14 1.34-7e..013 o lsac~opic 8,720e-01 5 1 .076e--013 a Antenlor./Posterior Tioret!,y mS'dhr 1)58c- 5 j .184,e-013 a

&866emM01 1 .094e-013 o Lwterv3 7. 143e-035 8.7 75cý-0 4 a Rotational 4-002t-01 5 9.117 le-014 0 1I*t-.0 ;r 7.125e-03,5 9-765e-01 4 Pap 1 Cl-183

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicraShiield w5.04 (5.04-OOL362)

Radbological Services, Inc.

Page :1I FiIe Pei;_____

D06 File, PS122134AS-5 D~ate: ______

RL at oiie 21, 2005 By; IRu Kftme, 6:,04:26 PM& Checked: ______

Dwratigp;QP ?W; Case Tiite; Line 1.91 E Dacsriptivn; Revised WYdel Cak-C A97g-1,f4 Unti t Act w $ched 4(0 & 1.2 in Shtd Geo~metry: 10 - Cyllider Surface3 - Exteruiil Dose Po~int Source Wbimensions 25 ft Hadius 7.62 rrn 30 in Dam~ Poimnu 182.88 cm 4 ft 6.6 n 12 (t Uin 6ft shidd

.Difl1-risio inkrI*

7,65-2 c~m' -D: e 1.8

.65 cm Ircvl O-2,4 2 Shiel-d 3 WC.48 cm Cowet~~ S2.4, Air Gap Ai! 7,86t 2 5V0I1 V?10 Somm~e Inpwi Gr~ouping M~ethod -Slandard lnodlc Number of Groups ;25 PhOtons < D.015 .Extluded L~brary ;,Grove Aff-1081" 1,,F417~ *9 Z141;121!~O The material referemea Is Cyl. Core Integration Paramete,'s 20 C2ircumbferential Resufts; aw ~ 4e~ With RiiHI&tM

.3.5 1 e 269 6,5~70.4 1.216~e-270 2.96'4935 CJ-184

Plum Brook Reactor Facility Final Status Survey Plan 'Revision 0 pag Fie ; 1213,S Ru-n Date; Decu,-ber 21,.2005 IRur Nme: 6.04-,26.PM Duration :00:00:O01 Activit 0.03 1.290e-06 6.ý93e- 100 6.633c.102 6,0709-42 90.6 4,3058*O 1 2.,g~ie22 4.637e.25, 1A%& 13p 0.4 5,11.3e- 13 7.797e. 14-5.440"e00 0.8 6,97-5P - 2.9$qe* 10 1.3fie124-5 .491e+OD.

3.9979-1 1 7.6G,79* 14, 25Q777&ý.J TQTA.L5; ZQQ~+QI 4.746e. 11 1.424e.09 0,064e.]4 2.726e- 12 C1-185

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 Mlenodtlheld vS.04 (SX.0-00362) 12121/05 MicraShield v5.M4 S4,4-00362)

Radiological S~Ietws line, Conwer;Om of cakiulated wpsr In oir la doo4 FILE. CAMS5\OSATA\P8122134,M55 Cas rill; Line 1..81 E This case was rwn ani Wedhnesday, Decjgmbei' 21, 2005 at C:04.26 PM#

mm0 Paoin 1 -(1378P30B1i281" CM Results (qumrnmad over esEgies) WithoL yuitdu Plhotonsi/emnsec 6,2137c-011 1.954100O9 114ton Enea'gy Flue~nc~e Rate MOeIGm 1 ,sec 4. 746e.0 I1I 1.424e-009 Ex posure and Dose Rates-EiAPO-sure Rate in Air mR/'hr 9.064e.0 14. 2.726e.o12 Absorbed Dose Rate in.Air rnay/hr 7.913a.016 2.380e.O014 mradthr 7.913e-014 2.380a*O 12 Deep flc'e Equiv~e~nt Rate (ICRP 51

• 187) a Parallel Geomretry m~v/hr 9.263e.016 2. 7!9.4. 14 o Opposci 7,5529-016 2.268e.0 14 o R-otational 7.552e.0 16 Z25Sc.O 14 0 1.561fpic Ith 2.005e-0 14 t,ICLRP 51,.1987) o ParatIeI CGeornetri rnýv,/hr 9,890e*01'S 2.91ge!-O14 o OjpP &11d 9.42~O6e. 2,837e.O014 o Rotatýonal 9.42'S9.01- 2.8$7e-014 7.144eiO16 2.1459-014 (ICRP 51'- 1987) o Arytereor./Posterior Geomietry m.$v/hr 2,481lc.014 a

7.347e.016 2.20&e-014 o Laferail 5430,06 1.,65%u-014 a Rotabonwl 6..57-3E-016 1.975e014 a lnolyopic 516374-106 1.69le-014 Page 1 C1-186

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 Micro~bleld w5.4 (5.04-0032)

Radiological Sermimks, Inc.

Paige ;I File Rerf:

rDO1$ File. _,P8Ml35_MS5 RA Ste. DOCOMber21,V05 BY:

R~jN rime:. 6.136:00 PM Checked. ______

Duration~ 0: MOM]

Ca~se T~te. Line 1.11 F Dqosrlptfiq: Revi~ed Nl~deI taic- Ub9 UtnIt Att w Selied 40, & 12 Iii Sht-d Geomietry, 10 Cyl~imndr Surface. Exterinll Dose Poinit Source Dimensions Height 7e52.0 cM~ 25ft 30in Dose Points X

~a138.78 r ri 381 cne ri 22 ft U -i 6ft Shields 7M ým Con crfi

.66 cin IFOf) 4 Shield I 4! 2,4 30,48 cm Concret :e2.4 Ale Gap Air CO122 Wall -lIpd 025 cm Iron 7.816 Source Input grouping Merthod ;.twial; Photo~n Energies hu~d"L, Lux WZL 1 ,5CM-1j The materiaI reference is ý-Cyl. Core

.Inllagxaton Farameters Y Directon .(axial) 20 Ci rcumlerwiti~a 20 R'lu~nr& E "I zww AQU nrLaaal 0.0174 2,148c 03 0'c>000400 D.0175 4. 11Se-03 7.1 63e-37 .OC,Owe'i 3,79,3e-38 D.0196 1.20go-03 0.031e-] 1 2,S1~e-27 0 7026 6.074eO00 4.72-,-,M 6, 748c. I C0740+000 1.743e-,09 1.3719.13 3.2ale. 12 C1-187

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 Page :2 Run Nte: D~ecemnber 21, 2005 Runt ?ime: 6:06,OO PM Dur~itian : 00:0:0 FNuence Rate Fmaw rimP.wf A LAOWML-119 Fýuncg;it#u mR/h TOTAL$ 1,1W0 9,314e-11 2A1 B9-0O L.762e-13 4.582e,12 C1-188

Plum Brook Reactor Facility Final Status Survey.Plan Revision 0 MI-croS.b*et v5,04 (10O4-00362) 12/21/05 Mlcru~hliold 0.04 (5.044)0362)

.Radbaogtcall Services, inc.

Convr~woI of caiwuLated exposuio in air tG dose FllLE, C-kMS~s\ATAXP812213S5JM95 Cuei Tit~e4 LUo 1.81 F Thk I casea was run on Weduesday, Decernber 21, 2005 at G.-O6:0 PM owe, Point N1 (1t,8,8-S)'r Rejults (Suimmed over ensr1~ Mffh Phoitons/crnlfsec 1,125e-010 2-962e-00!;

Pi~un Eirwgy Fluence Rate Mevicn t s~ec 2.41&-009 E~xpo'sure and D~ose R~s-E.mpoure Rate In Air me/hr 1,762"13 May/hr 4OOO2e-01 2 Abworbd Dose Rafte in Air 1. 53ge-0 1 Mrnrchr 4-.OO~e*O1 2

1. 538'O 13 Deep iOcs Equiva~nt R~tr, o Parallel Geam-try mSv/hr 4ý,665e*Q14 0 1,474" 15~ 3.8$.ie-Oij 4.

o Rotatioanal 1.474eO15 0 1s la i 1 .304"-15 Shalgovi Dose Equivajkari Rptru (]CRP 51 - HM7) a Paralef G~eometry' nS-v/hr 4.9~77e-0,14 c,C~pposed M 4.349e,,014 a Rotational 4.74ge-0 14 3.125eO 141-Eflectrve Ds quvlntRt (ICRP 51 -1987) r) Antet~r./orIcteror Ge#netfy mS-v/hr 165~95".O15 4. k49e*Ol14 a Pos~terixr/Aikarior M 1-43ieý01 CLatea 1.0890e-015 2.8269-014 o ata~a 1.282eD19 3.331 e-014 0 ýJ o f 1.1050-015.

Pag~e 1 CI-189

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShleld v§.0D4 (5LO4-00362)

.RadiooIgical Sexvicui., Inc.

Page :I Fiit Rot ______

DO~c Fifle -,PB1.22925-MS5 13y:

RainýOrtw 1129:02 FPm Checked: ______

Dur-atign; QWQ Case Title- Line 1.81 Q Desc~ript~on: R~vii.d Model, e O1c. P ikLh

.. A0t w SeW@ 40 & 1.2 in Shi1d

~inwetry: 10 - Cyllnder SiurI.ce ExtwnaIl Dose PoWn r:,*  :

• ource Dimieloms Hleight 762.0 cm 25 ft Radius 7,62 cm  :ý,O in z

381 cm 182.8$ cm

.4 ft 6.6 in 12 ft 5.0 in 6 ft Sh*Ids IF*

CYL. Core 7.62 cm2' Convcii'ei 1 Shield I 3 C~>Jch'A4c 2.4 S3hield 3 0.48 corn Conctretc- 2.4, Air Giap Air, 04,0)122 Wall Clad .0 2 5 om Irn 7.86 Groupi~ng Method :Actual Pltomb Energle&

11,29 1.'64179-010 6i0744e44J00 4.5000e.OCG9 1.6650e-0O4 Builduip The EmaterliaI reference Is : Cyl. Core Integration Parametas Y Direction (axial) 2 Oircumnfervitiag 20 Resuhs Enara 'Acivity Fluenre Ratto Fluvacte Raite E .~sr Rzte!

4..096e.,100 0.0295 1ý21I2e+0O 3.3 149- 98 !5.4,69e-34

2. 249e+00 2.447e4)5 1.046e-33 2,479e9-9 1.05<)e-35 7-995e-*01 1,708cm72 5,4604-3~4 0 n 396 4.568clo 1 6.56,58-52 5.9-.50e-34 2.9.8-3e-54. 2,5229-36 C]-190

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Page :2 DOS File P8122925AVMS5 Rtun Date: December 291. 2005 Run' Time: 3:29WQ2 PM9 Dur;;tiosi ;07OD:OO:1 Fluent-tx Riam MpV TOTALS; 4,718etO~d 2,694-~33 .8 -5 2,2720-35 CI-191

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 12/29/1(!

M~Mcrrohhici (IO4-OOM v5.04 ComeUsigno3t WM& e~~wwdowire Iin air to dose rILE:- C:\MS5ATAXPI112~292SMSS This case. was ruumon~ Thursday, Dewdior 29, 2005 at 3:29.02 PHA base Point 4i 1 (130uM30,~14140.8) cm Restilt 4&.mrnmed over ene" Lb feou wit Phioton Fluewce Rate (fux) Photonsfcm/selc 1.65%e-05D B.35eO032 Ptotan Emeigy F~enc*e Rate 6.65-052 2,104.033 Expcsure aind Dose Rates:

Exposure fiate inAIr mR/hr 2.983e-054 Ab~crbtd Dm lite in Air Mciylhr 1,594t-037 mracifhr 2.605e-054 Naop D~os Eq ivwi~ant Rafe (ICRP 51 - 9~87) o F'aral let CGeni~Etiy mSylhr 2.27 1e-037T 1.M7e-056 oRotational 1-700c,056 9.717o-038; 0 lileopic 1.626"O56 9.025e-038:

Sitallcow Dose Ec.ui'alent Raite (ICRP 51 -1987) o Paisliele Geomne"r mSv/hr 3, 751 o;5 21475e-03T o Qpproc 2.58ge.O036 1.702e-037 a FRotation~l 2.58ge-056 1.7O2ctWT7 o llotI!0pkt 14,258e-037 2114-056 o Anterior/Posterior Geoirntry m5yh a Postef toy/Anterior .1,314e.056 5.264e-0~38 o Latemr .

o Rr'tatoonal 1.1 82e*056 52,9 le-038.

o lsotfopr~c 9.68-1e.057t Page I.

C1-192

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MICrDShiled v5.04 (5,044MJ362)

Radiological Sewices,, Inc.

Par~ ;I File RO1; DOS Fite :PBO10407,MS5 Date:_______

Rh ate; Jahwary 4-, 2W.~ 13y:

Rurrfime: 8:13:21 AM Duratiop : 00:00:01 C-as9 Thle.: Line 1A81 H U~riceptlarl. pev40e1 mooet 0*11c $it~-12 Om It Act w kheO~ 40 A 12 imShfd Geomietry: 10 - Cylinder Surface Externl Dose Point Source Dimnimsions Height. 762.0 cm 25 It Radius 7,62 cm 3.0 in z

a i acko m J04s Cjr 182.88 cm 4ft 6.6in 12ft &.0in 6 t Shields J

Cylý @C 7.62 cma ýConcrel te 1.8 Shield I .65 CM Ilro 7.86 9

Transibon Coc'nret :e 2.4 Shield 3 3.408 ern Conciet :e 2.4 Air Oap Air 0001 22 WaIl Vad 7M8 Source Input Oroupping. Method -.Standard Indices tNumban of Groups ,25

?Photans < D.015 fue LUbrary :Grave Sn- 126 1-6417e. -30 6,0744"N00 4,5300Oe.0C 1.665W-0e~4 Billdoip

'The material[ r~eFerence Is: Cyl. Coreo Inlegraifion.Paramnetes Y Direction (axial) 20 Circ umfrential1 20O Me'/sen~ MeV/-,rn/sec MnUTER-271 4.702s.01 4.14-Se.270 L103-r~34 &.498E,-36 CI-193

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Page ;2 POS File : PEIOlO47.MS5 Run Date: Ja.nuary 4, 200C, aTime: &M-21 AM Run Duratio. 00:.00:01 Wilix9+0 No 1Mgi!Su6, 9.229.e-,!ý4 6,446e-34 8.37le.36 0.04 3.034e-02 4,613e-52 2,0409-54 0.06 4. 7ge-28 1.4 10e-26 1 9.111e 2.801eý29 0.06 23.899+00 1899e.21 1.045919 1.654e-22 TOTALS.: 5-65Oe*~00 1.89ge-2 1-0Se-19 31005e,24 1 .654a.22 Cl-194

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 NicraghleIdvA.64 (S.UO-MM 01/04/06 MicroShied v5.04 (5.04-00392) lRadkidoglcal Seiiilcs, Inc.

Covrsioil Of[r*auIlld e"poswr INV air to does FILE: C.%MS5\DATA\PBO1OAO.MS5 Case rulhle- Lhiff 1,01 N This case was. run oni Wed nesdary, January 4.ý 200 at 3:18M2 AM Dose Pkont a I~ {f&.fl.8 b~wijs 4iammed racage.4TP LUIS ithou Builduio P'htoin Flu~emce Rate 'Tiux3 Pbonslo~Wlsd 2.373ea-020 1.307e-018 Photon Erneigy Frtuenc'e Rate MewenW1sec 3,.045c-019 E~x psuroand Do~e Rgitov Exposure Rate in Alf mR/hr 3.005e-024 1 .654e-022 Absorbed Dose Rate in Air mnGy/hr 1.444e-024 w

rnrad/hr 2.623e-024 A.4e4-I022

!j~cep D'ose Equin4!ent Rate! (ICRP 51

• 1987) a Parallel Geo~metry mrnv/hr 4. 5S8e,026 2-526Se-624 C)oppprfd I 2,444"026 i ý345a-024 a Ro'tational 2. 37802 1.-308e-024 0 1golfopic 2,38c.02,6 1.298Ea-024 Shaitfow D'ose Equ k;alent Rate (ICRP 51

• 1987) o Paraillel Goomu.c ry rnmv/hr II

4. 545e,026 2.502e-024 o Oppos-ed 3.341 e-M4 1,.839a-024 o Rotjutionz~i 3.341 e.026 1-83sge-t424, a Isatrop.ic 1.350v*024 rfeb~-o~eruvlu- (ilp 51 51 a Anteri~or/Povterior Geornetry. mnv/hr ft 3,8539-026 2.121,9.024 ej Po,.o,ýia-T/Areriar 2.939e-026 3 .61 e.oM4 o Laterat 3.811 e-02,6 9-972e-02 5 a Rotational 2 $0e,0215 1,~378se024 o IQsobvook 2 .025e- 026 1-116e-024 page 1 C1-195

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Micro~held Y5.04 (5.04-00362) ladiologlcal Sw'~jces, Inc.

Page~ :I Filc Ref:

DOQ~Fije , PBI22927-tS5 ,Date:

B~y" Ri. *ate; Decwnbcr 29, ZOGS ft 6Time' i3-'-!53 PM Ch¢ied ;I Durati~n . 00;00;01 Case Title. Line 1.811I V~e~tfilodm: Roiftd Mod-9 Wek. Ztr-95 Unit A41 w 59hed 40 & 12 in SW4

___ eomeotr 10 - CylInder Surface -Exierrnal Dos~e Polint Sam ce Dimensionis Height 762..0cm 25 ft Radius 7,62 cm 1)Ogg P01nis z

ml 138.78 cm 361 cm 4 ft6.6 in 12I~t 6.0in 6 ft Sh~elds

-e1 52 =21 Conc' ShieldI1 65 cm IFO 2.46 convort Shield 3 30 48 cm Conads e2A 0.001?2 INa ll Oa I d 25:cn' irc 7S86 5G4rYCO rII~put Grouptrg btethod : Actual PhIioon Eniergles Zr.95 1.641.74-010 6-0744e+000 4-5000e.00-9 1.465Cme-0X4, Buildup The narterlal ref eremce Is: Cyf. Care Iniegratfon Parameters Resuhs EMUrg 6"Wty Elueincq Elace-atUremR Ogmin5iýiec, MeV/cmM.L.=, MevcW/3miY0c ______

No ul I WWL'da Wn Ruidury 0, 7242 2.652e400~ 1.064eý11 .3.374a-10 2.046'e'-14 1.3 0.7567 3,362c~-00 1 i755, I1 52001.6 tli TnTALS: 6.0 144~00 2.2Oe-. 11 8.5790-10 5.407e.14 L645e-12 C1-196

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShl~ed v5A.04 (5.04-ID362) 12129/05 MicroShield v5.04 (5.04-OO362)

Rl41g10008 senllto Inc, Camersloii of aiculltiml exposure, in air to dosue FILE: C:\MS6\OATAkPR122927MSS Ca$4 7ThJ4: LiMM LS~n I This~ case was run oni Thursclay, Decemibr 29, 2005 at 3:33:53 PM~

base PoIMl 0 1 - (138a7391a2=$ cm SmuligOM-0-O M 0er Witho> Wfit Phoon Fluemc Ratce (fux) Photons/cm2 /sec 3-790e-01 1 1.1 54e.()0

.Photon Ernengy Fluence Rate MGV/cm 2/sec 2,920e-O1 1 &579e-O01 E.xposure and Dose Rates-ECg*p$urge Rate in Air mR/hr 5.407e-01 4 1-649e-012 Absorbed Dose Rate in Air mvyflhr 4,7219-016 1.4,36e-014 F1 mrad/hi- 4.72le-01 4 1.436e.,01 (ICRvP 51 - 1987) oParal lel Geometry mg%/hr 5,6349-016S 1,6S3e.O1 4 io Oppo*# 4..5c0e*O 16 1.36ge-014 c Rotafional I .369clG14 ioIsotropic 3,9789-0 16 1.210e.010o Shelaivowse Equivalent Rate jo Pprallei G~evrmetry mnSv/hr 1.7979-0 14 inOppos~ed 5.630e.0 16 1 .713e-014 to Rotatibnal 5.630e.0 16 117113c.014 4,2570-016 1.295e.0 14 (ICRP 51 - 1967) ooAnteri~or/Postarior Gecmtr/ 1.495e.0 14 c Pa evioa'/Anlerior 4.37ge,-016 3-292L1016 IO01..001 14 io Rotational 3.91 6e-016 1.191e-014 cIQk~r $3--54~e-,O 6 Pao C1-197

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Microgido4d vS05.0L4-00362)

Radiological Seavices~, Inc.

FPig9 ;1 Fi!

• Ref;__ ____

DOS FILe : PIB122928.14S.5 Date:_____ __

Ri. at. e:Dcerber2a 2005 13y:__ _ _ _ _

Run- Time: 3:85.35 PMV Choekd ______

Duratior : 00:00:01 Case

Title:

, Line ti. J Description. Reirlsed MixW Cai~c- Eas155 Lhttt Act w Schod 4.0 & 1Z in Shfd Geomuetry: 10 - Cylinder Suirf-ace - ExternaJ1 Dose Point C Source Dimnsie~ons 25 ft Hecight 762.0 cm 3-0 in Ra.~dius 7..&2 CM z

1 138.78 c~n 381 cr 182.88 cri 12 tt UOin 6fIt ShWle[dri flLTLQ, M CAl Oure 7.62 cm2' Con Crot Shield I .65 C-m Ii 7.86 Trarisbi#~n it 2.4 Shield 3L 30.48 u~n Crnctret e 2.4 Air Gasp Air Q.0012'2 Waill Clad .025 crm Iron 7286 So~urce Input Grtwtpllng Me'thod -.Standard Ifrdlceet Number of Groups 2 Lorwi~ Ewafy Cutoff 0.015 Photos,i -90.015 : Excluded Library: Grove NAXI& aui Eu-155 1.64,17,3-010 5,07440+000 4.50008-09 1.6650e-004 Builiduip The material reference Is :Cyl, Cor'e Iliegraiion Pararneucs 20 Y ircurn (axdial 20 Resuft.

Fluence 13:02 EjUorggc R-iite YAVXmeýse; 1IL 5ý10 2gja Ejji4dýM

1-003eý55 9.1810-36 9-.943e-913 9090 C1-198

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 P~as :2 DOS File PSI 2~292.MSS Run Date; Newmber 29, 2005 fOun' Time: 3!36.-35 PM Dur.qtian ; M:OMO 0.04 1-10 le+-00 1.387e-33 7.403.353 4.421 e.36 7,.878e-02 .6.467e-2-9 1.90go-27 1,285e-31 3,7919~-30 1.$8i56.+IX 1-240"1 7.068e-20 .1. Ige,22 O01 2,1 55e-19 Z,057@-17 3,2.,7e-22 :3,1 93e-20 TOTALS: 4,699e+00 2.168e. 19 2,094-17 3.-318e,22 3.204e-20 Cl-199

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 M~icnaSbleld wS.04 (104s'N362) 12/29105, MicrofteldI w5.04 (5.04.-.O62)

RzdkAqOJca1 Servieem, Inc,c Couivesr~1on of caIculiatud exposure in air to dose FILE: C:%MS5\DATMkPR1t2928,MSS C~$se Th111 UiW 1-Ba J This.case war, rnn an Thursdays, OemonbwrZ 29,200 at 3.35MS PVA Dose Pohbt 0 1.- ~1 7l3~8.)cm EL-slts (SuImmed over ~rresn U-OdA Without Phot4on Fluence Rate Cf1lL*,% 2.17Je.0U18g 2..0964L.O2iS Photon Energy Flue-me Rate Me/cml'/sec 2.094e.O17

~Expo~sure aind Dos'o Ratwr Expquro Rate in Ai! rnR/hr 3,3 18e-022 3-204e-020 Absiorbed Dose Rate in Air rnOGY/hi 2.8%*,024 A

rrwd/hr 2,896e-022 2.798e-020' (ICRP 51 - 1987) a Parallel G~ecretry rnSv/hr 4.$42c.024 4,676e-02Z 0 OPPOSPd 2,655e.024 2.564e-022-o Rotational 2.654e-024 2,481"-22:

Shali'y).Dose Equivwalent Rate CICRP 51 - 197)

-o Parallel Gsaetm-/ mrndhr 4.810e.1024 4,f'4m-022, a 3.73 1o*024 3.604e-022, c Rotatilonal 3.73Sle.024 2,.62 4 e-022 Effective Dose Equivalent Rate a A &trvor/fitsterlarentr M5$Ythr 4. 1629-024 4..O1ge-022 o PostericriAnterior 3,152e-022 a Lateral 2.0 149-024 1-1345e-0~22 o Rotaticnal 2. 787e-024 2,692c'O22 a Isotropý,t 2.2179-024 2.1 42e. M, Page I CI-200

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield Y5.04 (5.04.-0362)

Radiologcal Sen'Ices, I1C.

Pap :1I File Ref1:

Dotý Flie : PB21919-M&5 Date:

&~ ate. 04cemnbor 19, 200~5 By:_

Ch%*,t.d- .__,___

Duration : OGO:O-01 Case Thils Line 1.82 A2 Utscription-R~evised Model -ic - Co-6 OlUt Act w Sched 40 & 12 in Whd Goiiery: 10 - Cylinder Swdace - External Dese Point Durce Dlimeslons; Heighit 762.0 cm 25 ft Radiu~s 3.81 cm I Z5in 381 em z 41 134.97 cm 137.16 em 4 ft 5,1 in 12 It 6.0 in 4 ft 6.0in Shields

'" ield Narnp ,

Cy!, Core 181 crm' Concrete Shield I ,655 cm ran 7S6 9

Transition Ctoncroto 24 Shield 3 30.48 cm Cancrete 2-4 Air G~p Air 0.00O. 22 Wall COad .025m CM I= ?Ao sourto h'pijt GroupipngMethiod :Actual Ph~ton Efer~

es cm Bacn Buildup TRmiatevial feeimence Is - tyl. Care Wrvegration Paramewsi Y Direcfion (axial) 20 Ci rcumnfereqtial 20 Results Fk~ienre'Rate C,.693B bW.47.1d= 2.856e 17 7,4132e. 16

,3.037Pt-;OD 1;79*- 14O 1,1732 2.310e.12 :2.869e. 11 1.3325 3,037e-00 4,8e 12 4.2"999. 11

."ALS: 6.0759t00 3,6460-09 4-083,.08 6,39 .12 7,1t6he11 C1-201

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 12/19/10$

Mirro~hiud wS.04 (5.0O4-00362)

Radiological, Services, rIme, COOWwr910h 01 Cakwfaltd OVOWOmr INair to dote FILE,- C.-\MS5\I)A1\PB1.2191gJ,MSS This cas~e was ruin on,M~onday, Decemiber 1.9, 2005 al 2,26.:48 P141 ag;Wjhj 4:sfnrT1Ad rtygor mocgaa UL Wth Aitt P~botofl Fluea-ee R~ato (Ikix) MxK~ons~cm 1 /sec 2.86;8e-009 P~tion Eaer& Flitene Rate 3,6469-OO9 4.083e-008 Expo'sure -and Dose RMeW:

fiposwre%Rate inl Aie mR/hr 6. 3030.1:2 7,167C-01 1 Absorbed Dose Rate~ in Air mGylhK 5.5819-0 14 6-257e-013 mvtad/hr 6,257c~Q 1 NcpDor q " ctRt (ICRP 51 1,87) a Parallel Geowtetry rnSv/hr 6;336e-01 4 O'Oppo*Od 5,.45&8-Ol 4 a Rotat~ional 5,458a.01 4 o Isotropkc 4-876e-01 4 Sh~allkw.,Ozse EqiurYa'ent Rate (ICRP 51. 1987) o ParailkI Gerc*mv',V rnS¢v/hr 6.743e-01 4 7.563e-01 3.

- a Opposed 6-.4~-91-04 6,493a-014 7..281e-013.

5. 16F6e-1 4.

Ei'.Cr1iVC rý5 FqUiVaUcrit Ratc (ICRP 51 - 1987) a Anteri or/Post.erior GEL-rntryf mSv/hr 5.705e-014 6, 397c.0 13, U 5,256c.0 14 5.8929-01 3 o Liptorai 4.182e.014 4.686e.0 13 o Rotational it.73,3eO014 5..3O60-013 0 isotropic 4.1 909-014 4.695a.0 13 Page I C1-202

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 NlcrGS~ileld w5.04 (5.04-003621 Radiological Sefvlces, Inc.

Page -.1 File Re~f:__ _ _ _ _

DO F~ile - PS122,136.MSS Date! _____

Ru ate;Decembe.r 2,2005 13y; Rui~ri~Mc. 6'2:30 I'M Checrlted:______

DwratiQn ;(00;0010 Case

Title:

Line 1.82 B DOSCHOOOMr~ RO~iSed Modell We-1 CS-17 Unit Aict w SChed 40 & 12 in Shid Cieoetry: 10 Cylinder Surface - Extarnal Dose Poilmt aI-,I - ..

762.0 cm 25 ft Radio~ 3,1 orr1 1,5 in DGse poiffts z

137.N cm 12 ft 6.0 in 4 ft 6-0in 4 ft 5,.1 in Icyl! QW0 3 31 cm2' Conc~rete 1.8 Shield I 65 cm Iroa, 7.85 Concrete 2.4 Shield 3 30. 48&cm Concrete 2.4 Air 0.00122 25 o~rn. Ircrý 7.86 source Input Grouping Method : Actual Photon Dwtrigles b~tr31Jrnt_, niiliro-sa-137m 7-7654e-0~11 2.8732e+0003 4.2570e.OO4 Cs. 137 8.2087o.01 1 3,037-29+000 4.50GOe-009 1 .665C'e-004 Hui Idup The material reference is Cyll. Care Inftegruation Paramieters Y 'DirKction (axial) 20 Ci rcumnferhdltial 20 3.402c.73 0.0318 6;948e-02 4.329G-35 2,330-75 .3.606e.37 0.0322 1.00~7e-0'1 4.917e-71 8.2-94--35S 3.9579-*73 6. 67ge-3 7 010 364 3.994c 02 4.6,250-35; 1.8!48e.57 51.6 2.585sei-00 3.34 15 2.2-r 2 1.1 F,2@ 13 C1-203

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Pg,,:2 DOS File -PB31221M.MS5 Rwrl Oita: Oftesooer 21,*2005 Run Time-. 4522930 PM4 Duration .00:0010 1 ArH-W& rlimnra P,%Aq F~ufenc Rat LUMMArIlL2 ghfjlgng/gecý Lt'Ohretel&-e ynR/he mEx UlbRid UO BUil&w MVV/ertIb~

Up Bij=L, TOTALS; 2,7949+00 5,994e 11 1.693.009 1.162e-13 3-262oe 12 CI-204.

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 Micrgo1iield vi.04 (5,04-00562)

RadialloglcaIl Services, Inc.

Conwasi~oi of CaclakuId ft~uft ~ifair t0 doic FILE~ C\MSS5DATA\081223.3GMSS C'"oTItIec U110 Lez B Thils case was nmn ce Wednesday, DOcember 21, 2Q05 at 6:22:30 PfA nose Ftazlft # 1 - 7~117~C~M 8glj1-K&ummned over eneris L='ou Pho~torns/cW/s~er 9.059*.031 2,5Z.43e.009 Phvoton Enefgy Fluenc~e Rat& MsOcV/ijec 5-994e-01 1 1.683e.009 j~pisure Rate In Air I. .162e.0 13 3.262e.O012 Absorbed Dosie Rate in Air I .014e.0 15 2.848e,0 14 mrad/hr 1 .014-01O3 2,M4e.012 IDCP 1)0s5 EQV]YaI~rit Me (IC.RP 51 - 1967)

-oParallel C-eamitry m:v/hr I

1.20le-015 3.3720,-014 g3 fl~ppuaed 916661-016 2.6996-014 fc,Rotational 9.61 6e-016 2.611e-0 14 8-503C01 6 2,387e-014 Sh l'~0cse Equi a~ent Rate (ICRP 51. 1g97) io Parallel Gooim-etry m/hr 0!

1.2 77O1e,1 e) O~pposed 1.2 12e-015 3,404-0O14 io Roatitwnal 1.2 12e-GIS 3 .404e-014 M9009,0V15 2;.552e-014 E-fi~rgtive D0,5 Eiuivafv'it RC-n' (ICRP 51 -1987) a Ante'riorIPc'sterior Geometry rn$v/hr 1.0O62e-0 15 2.98 le-Ol 4 9.374e-0 16 2.631c,01 4 io Lateral 6,9510.016& 1.95Ie-01 4 io Rottational 8.37 7e9016 2. 352e-0I 4 10lsaurboprt 2.1 32-eQ 1ý Page 1 Cl-205

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5fl4 (B."4362)

Radiological Sarvices, Inc.

Pa&D I1 FiIt Ref;__ ____

t)08 File 1`B,221.37.MVS5 Date:____ __

B~Y; Cho Owd-. ____

Duration ;000:0~1 Case Title, Line 1.82 C Doacriotlia: Reit mad ell Cok.. Eu4$2 Olt Act wSched 40 & 12 in 5Wtd

- eomtrt: 10 zClyfiuudef Suifice - Extenal Dose Poin~t a= Durce Dimensions Heig1& 762.0 cm 2.5 tt Radius 3.81 cm L5 in VaE Poirtu z

41 134,97 cm 381 cm 131.6 Cm 4ft 5.1 in 12 ft 6.0 in 4 ft 6,0 in Shletlds 3,81 cM, C*nc re*t 4

Shieid I -65 cm roi 7.86 Transivori 2.4 Shield 3 30.48 or Con atie 2.4 Air Gap O.OD122 Wal I O1nd ,025 cr Ir~i, 7.86 500wo~ input Groupin fethod ,Standlaid 1idi~ces Humbrof roups ;26 LOWW Etetgy Cliloll ý .,,

IPhotonsi O.015 : [xcluded idbrary : ýromre Eu-152 132C,87c -011 3.0372c+000 4,15*00ia.C 91.6650e-0O4 Builduip The matetlal relareiice Is : Cyl, Care IrIM.graftloT Parumeters YDirection (axial) 20 20 He5wits L=MLIIQ No Buildup 7.474e-4 1.2809-35 Cl -206

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 P49 ;2 006 File ! P8122137.MS5 Ru:n Date; December 21, 2005 Run lme: 6:2$:23 PM Durvtiga ; Q,0;Q0.,

Ex~lure Rate S ghotons/se rnR/hr 0.09 4.4903e.01 1.845o-31 1,8680-30 4o5t1,P-34 0.1 8.6350,01 1.066e-I 7 8.1!50e-16 1.6310,20 1.247e.18 3.876e- 3_5 4.44~e,13 0,2 2.2769.01 6.B429- 18 0.3 8.212e.01 2,035e-. 3 1,6830.11 3,660ii., 16 3,192e.14 0,4 2.661 e- 3 1.536e. 11 5.184e,.16 2.993e-14 0.5 1.713e.02 8.573e, 4 3 70--.12 1.683e- 16 71.*00c"15 0.6 1.2w&e-0 1 1,762eI12 5,705eB1 1 3,40,e15 1,114e-13 0,8 5A408.01 3.40-5e-. 1 7.258e. 10 6.477e- 14 1.3380e. 12 1.0 1.3O0e+00 2,5 31, . 0 ,9W4,,Q9 4.757- 1 3 7,23O, 12 1,5 7,046$e0 1  %,3300-100 1.570L-12 1.430e-11 TOTALS: 7,040e+00 1.2 31009 2.824~-M 2,1 Me. 12 2.30ge. 11 C1-207

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 M~ico~hicid v5-04 (SA.040362). 12/21/0I MrcroShieId v5.04 OS."302)

Radlalog~l Services, !Re.

Covmlo of cukuicated eipqtrc ~in air lo dose~

FILE.- C:\t4S5\DATA.\P8122137.PISS c~ase itIle: Line i.-

This case was run ant Wednesday, Decemnher 21, 2N5 at C-25:23 PM Dv~se Pairin # I1 (iU,9 7 381'.1a7zM M~

Withou Mith Photon Fluvenmc Rate m'u* Photonm/cmI/sex. 9-226e-010 1.070e.00LB PIwitn Energy Fldence Rate I-Me-009 1,3249-008 1x~osure and Dose ROPW Ex~posure Rate ini Air, vmR/hr 2ý.106e-012 2.-Mse.O 1]

Absorbed Dose Rate in Air mGy/hr I A~39*-014 a.Q!'6cOQi mrard/IIr L8.390-012 2,016e.0Q11 Cucp Dose Equivagent Ra'te (ICRP 51 ,1987)

GParagIel Geomnetry mýW~hr 2..069FA-014 2,96. 1a N

1.,B07ewlD14 1.974e.0 13 o Rotational 1,974,O 13 1.617e,-014 1.764e-013 Shall-ow Dose Equivalent Rate lCICP 51-IM7 a Pa~rallel Geometrf 2.216e.O014 24$9gtV 13~

21 39re.O 14 2.35Oe.O 13 o Rotationail 2.13ge-0,14 2,350e.0i 13 1.85c,13~

Sflectiye Dose Equivalent Ralo a Anterior/Postefior GCearnetry mSv/hr 1..880e-014 a.Posterior/Antwior 1,737o-014 219000-013 a Lateral 1.-391e-014 1.612e-0 13 a Rotational 1.56150-014 1,71 2v,-013 a Isotropic 1. 390e-014 1.51 4e-0 13 Page I C]-208

Plum.Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShIeOd w5..04 (5.04-00362)

Radbologicall SeM.ces,.Inc.

Page :1 File Ref;_______

DDS File P1322138,14S5 Ctate:_____ __

RL aie: tDeCOMber 21.- 20a5 B3y:

Rki-irn~e: 6:26-,42 PM Checked:_______

Duration~ : 00:00:01 Case Thitei Line 1.82 D 00oscriptro~n; R0ytWd Me-dot Cole. Ew-164 Unit AC~t WSkhed 40 & 12; in Shold Gemevy, 10 -Cyllt~er Surfce - EneriI DOne Point

'urc Dimensions Height 762.0 cm 25 ft 3,81 cm 1,5 in Dose Paints z

381.cm 13T716 cm 4ft 5.1 in. 12*A .0 ri 4 It 15,Q in Shiuo~ds Shield,Mg 3.81 cm' Conc ret ,e 1.8

.65 Cm . iro,n 7.86 Shield I CGri'ret l 2.4

§0.4 em COncat 2-4 Air G~eal Air 0,00122 Wah Clad .025 cm Wron 7,86 Sommet Input Grou~plma Moethod Standard Indttcei Numnbeirof Groups -2 Lower Eaer-gy CulafI : CAO1S Photons 9~ 0.015 : Em~Ju~ded Li~brary -Grove Bo.km'~

Eu- 154 8.2087v- OIL -~3.0372c+400O 4%5000o-0C 19 1.6650e~C~I4 BuiIIdup The m lI roference Is.- Cyll. Care Prilegraton Parannete'rs 20 Circumferential 20 Results Engi 6.15.1*01 6,61-3e 45 9.9-59-34 2-5719-47 4;4049.36 C1-209

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 DCGS Fite .P8122138.MSS Rujn We~ - Demmnber 21, 2005 Nun Tmcte, 62642. PM Owaa 0.05 Na ewwwn 5270-31 2,070-01 6.4$ov33i1 Wt~#1 1.170e-1.5 6 2 Wi 1-31 e-.5

.2,1670-2 12.775e-18 0.6 1.MAC! 12 6*5.9o 17 0.2 2.45~0e-0 1 11O859-10 6;543e-15 1.0 1.184efoo 1.590e-09, 1.ý41 W-13 9-43 1 2.820e..O.9 3,36~ ~ ZY.~'se-J1 1.5 L1.e'-QOx 1;430e.08 TOTALS: 5 Me+00 1,83e-09 1.8teO 3.1 25e-12 1.249R.11I CI-210

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicraShieW 44~4 (114-OO362) 12121005, MkoShfeld v5.04 (5.04-00362)

Radido~gkeI Servkai., Int.-

Copw'wlon, of cakialated exposuren ini air to dose FILE CA MS5SbATA\P81+/-221I9.M95 Casern itle:, Line L82 D

~This, case was rtuas on Wednesday, Decembur 21, 20M at 6-2~4,4 Phi 0"0s Pointf # 1 (UL0-7,31,137,M) 4,i W~uIt~i MSillxd gaer coz -Wieso Mfih Rudiip Pi"vton Fjvwvc Pato Mfwux notMong/cMl/59C 1 3269-009 1 .453e-008 RPioton Ereirgy FIuenee Rate Mev/cml/sec 1.S82-01008 Expcesure and Dose Rates-,

F.vp*r-eRt in Air mR/hr 3,.12,5e*O012 3.249e-O- 11 Absorbed Do-se Rate in Air mG-y/hr 2. 728e-014 2,837*O013 mrad/hr 2,728@.0. 12 2,.37e-01 1 C'cep D'ose Equivient Rate (ICRP 51 -1967) o, Parallel Gecwrietry mS--v/hr 3.094e-01 4 c Oppomcd 2 M610-014 2.785e-01 3 0 o talonaI 2.686.e014 2.785c.,01 3 a Isat-raic 2.406e-01 4 2..4g1e-01 3 Shallwi~Dose Equi~alent Rate

,3.274eG-&I 4 3.4 22e-Dl3.1

$- 16%-OD14 1.3038-01 3 io Rotea anat (!CRP 51 - 187) -q-169e-014 3-303e-01 3 m~.v/hr Z53-414 2M3Oe .01 3 a Anteriorfosterior G~ecmetry 2. 787e-0 14 23902e.0 13 2.5 7ge-0 14 2.67 7e-0 13~

a Late~ral 2.074o.0 14 2,141e-0 13 o Rotaqqonat 2. 328e-0 14 2.4 14eO 13ý a I garopic 2,070c.O014 2, 1409-0 13 Page 1 C1 -211

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield w5.04 (L (*00362)

Radoiolgical Ser'iicas, Inc.

Page :I File R*of; _____

D09 Fife PKt22139AOS D~ate:____ __

Rtl. ab;ecermbervl200~5 R~in7Tme: 6,28-,54 PMP Duration . 00400;01 Case Tit*,Line 1.82 E Desc~ltipors R~evised MIodel COC.- Ag-1080 Unit Ad-w Sched 40 & 12 in 51111 geomietry Cylinder Suffacea Extermia Dose Pn~nt 717Height X

Source D-iniersions i

2Sft Radius 762.0 cm 3.81 cm 115 in~

41 134.97 cr n 381 cm z

137.16 cm 4 ft 5.11 nj 22 ft U in 4 ft6,0 in S~hields 3,81 cmz' Cor icret

..6s CM I Transition~ e2.4

.Shield 3 W.48 cm Conrcre -a 44 Air G20 o1o0012.2 Wall Clad .025 cm Iron 7M6 Source Input Grouping M'ethod :Standard Indices Numb-of of Groups ý2 Photons < C0.G15 : E~xcluied Libraqr: Groves..

A~g-liO8m 8. 20567 aiO21 3.Oa72e+O0J0 4,5000*ý D9 1 ,6650t'.004 Buildup The mateiial' refl~ence is : Cyl Care In~tegration~ Parametefs Circum~forwotiel 210 Flurence R-ato M&V 1,992e~+00 2.76%42214 5.473e-34 9.5~9 3o-236 1.fl968-35 CJ-212

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 Page~ : 2 bOdS Fife P8122139.M~SS Run Date; Oicerber 21.. 20C05 Run Time: 6:28:54 P~M Duration 00-M-1 D:

121=12Actixit MplyWou4g 0.03 6.44ge*O7 1,1496-88: SeB. 40 3, 1.1 3E-90 3.8a3e-42 2.1 52e.01 2.02l e-20 9.24.3e. i9 3. 198e-23 19.453o-2 1 0.4 .3.8C068-2 2.1 97e. 10 7.41 5e-1-5 4.M81 e.13 0.6 2.745e+400 3.757e. 11 1.2 16e-0~ 7AS33eK 14 Z.74e- 12 0.8 2,7499e+O0 1,73$e10~ 3.689e.09 3,292e- 13 7-.01 7e..12 TIDTALS: 2.043e+01 2.145e-10 5.1 25e-09 4.100e..13 C1-213

Plum Brook ReactorFacility . FinalStatus Survey Plan Revision 0 Mlkro$lheld wS.04 (544430362) 12/221/05 Mkcro~hfld ~O .~032 RaciokIcall Services, Inc.

Conveirsioi Of Caklw~aed exposuirv Inair Ila dose ME,~ C.XSS\DATA\PB1221l9,MS5 This case was run ani Wednesday. Decemiber 21, 2005 mt 6:2014 P*I Dose Point $ 1 -1M.7311$2)

Pfbot-on Fluecgo Roat. (ifLow) Photons/cmnl/sec 2,885o-010 7 -17e-009 Fl.nt'ton Eniw../ Fluence Rate NMeVI/c/Sec 2-14$61010 5.1259-009 Exposure and Dose Rates:

Expo~sure. gale lei Air mR/hr 4. 1O~e-O13 9.819e*012 AbsoDrbed Dose Rate3 in Air mGy/thr 3,57ft-0I 5 8,572e-014 mrakd/hF 3. 5799-01 3 8.57 2-e-0,12 Na Close Ewvln Rwfo a Parallel Geomne~tr m$vlhr 4. 195e-01 5 1,0 8d- 0 13 Q Ovpo0e 3,4 14e-01 5 a. 164e-014 o Rotational 3.4 14e-01 5 8. 164e,-Oll 4 7,217s-014 Sha~lkw ,Dose Equiiva~ent Rate 0 P-arallcl Ge~ometry m$iV1 hr 1 .Q74e.-0'j3 4,265a*0O15 1.023e-01 3 o,Rotationual 4.265e-0 1$ I .023p-O1i 3 0 I'Sotropic 3,2299-015 7.72 lc-O1 4

,o AnterioriP~osterior Gemmetry mnSy/hr ý1.728*.O15 8,9147e-0314 in Pors.eriof/AngIericar 3.3229-015 7-954e-01i4 loL trf 21500e.015 7. 11 e-01 4i ooRotational 2,9729-015 0n di 2.S4 7e.Q 115 CW c-14 Page I C1-214

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield Y5.04 (5.04-00362)

Rad!.ologicaIl Services, Iric.

Page ;1I File Ref:

DOt File --%I2214O.MOS5 Riu ate: Decembstr 21, 200.5 By:

Rvnýime. 6-30:33 PM Checked:

Duration :00:00:01 Carse Title; Line 1.52 F D-O;criptiorw; R0030d M~odel Oala. W!9-4 Utnit Art w Schad 40)& 12 Iii SIld G~eomietry: 10-"Cylinder Surfios AExteiial Doss PoWn G1~

$Duni e, Dnimensions Height 762.0cm 25 ft Radius 3.81 CM 1.5 ii 0 *se paifts z

~1 134:97c 381 cty 137.16 em 12 ft 6.0 irl 4 ft 6.0 in shields ension Wlaf rit

~1 cm' Oonc e 1.8 Shield I 65 orn Iro.

e 2.4 Shietd 3 4$Cm Concret 2.40022 Air ".6P Ar 25 ur lrqji 7,;56 Source inplwt Grou~ing Mwthod , Actual Phorton Energi-es 1e5a/cmO4 Nb,94 514,87o,11 3,10372e+000 4. 5000.OG9 Buildup The niatew~aI teleirence [a CyI. Cato (axial)

Integratlonon Results Fluecg! R-,tt 0.0174 1.074e-03 2,369e-37 0.OO0e.OO0 1.279o.3M 0-0175 2.057e-0O3 O.cG30e300 4.58Ie-2k, O-e0CVe+Dx) 2.42b6e38 0.0196 6.0"9e-04 1.60%.-37 1 .446e.2,52 5-941 e-39 el 7026 3.037e+00 128708.13, 4.809o-12a 1711 3-03 7eit-0 2.9cle- 10 5. 5&Oe-G9 r-,573c. 13 1.050e* 11 C1-215

Plum Brook ReactorFacility Final Status Survey Plan .Revision 0 F'ase 2 DOS File '.PB122140.MS5 ft,n Daite-, Dnobcr 22, 2005 fkun Time- 6:30:3.3 PM Dur-*ion :00:00:01 Actiwiht. Fluence Rate phrAws/sec No uildu~

TQTAt$:ý U*78a+00 8,074e,09 7.443e-13 1ý531e-ll C1-216

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 M~icroShteld 6'S04 (S.,04-=062) 12/21105 Mcu~shk~Id VSMG 0,0400362)

Radiological Services, Inc.

Conwws*gm~r ~*cak'd**4aI p~ Al I* do-e Inv~

FILE, CAMS5\ATANP1312214O.MSO C*aie Thite LineL~

Trhis case was5run ain Wednesday, Dsciwber 21, 2005 3t 6:3033 PM Dose Point 9 1 - CM4.7a1~a.6 i

ýffib Photon Flwsr~e eafte Mfus) Photow,~crnl/sec 4.,779eO1O 9,9550,009 Photon E.nefgWif, enc~e Rate tM9V/crn/sec 3.93le.O1O 8.074e-009 Eximsure and1 Dose Rates:

Exposare Rate ini Air mR/li: 7,443e,013 1,531e-01 1 Absorbed Dose Rate in Air ma~y/hr 6.497a.0 15 1.337e-013 mradft. 6.497cO 13 1,.337e.01 1 Oeep Dose Equrivaent RNdto (ICRP 51 .1987) alParallel G~eometry rnSv/hr 7.556e-015 1.-1556e 01 3 o,Opposgd E

6.2-24eO 15 I.2o00ei :3 a R~tat'moal 6,224eo.15 1.280e-013 5.504e.0 15 1.1 32e.01 3 Shaltow Dose Equi4va~rnt Rift (ICAP 51 -. 7 i9 parallel Georeatfy rnSvfhr 8.0918-015 1.664e.O1 3

- oOpposed a 7.711e-015 1,587e,013 7 ,711e,015 1,587e-01 3 o RotationalI 0 1istrcopic 5.8909-015 1,2 lle-013 Eifrectiye Docse Equiv.derlt Rate o Att ten:)r/P-osterior Geo-rdetry rnSv/hr !6736c.015 1. a~e,01 3 o P*isterior/Anterior 6.044e.0 18 1,~2439-01 3 ci Lott~r-1 4.595.41 5 9,05e,01 4 oi Ro~tatoa 5A412e.0 15 1.113e-013 9,581 e01 4 Page 1 C]-217

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 10rbc~5kMt VS-04 (Sý044$O) ftd~ait~al 5.wvket Inc, Page 1: file "r DOO'N -~t 'R8122929AMS5 RiIl 1O: flcernbeif 29. 2005 Run T~ime ý;42:46 PDA Oweatloo Q: 0:O:01 4:4* TIV*e Uie 2.82:0 View~ tpucin ftakus Model Wt.- 11429 Unit Act w Schad4 40 &L12 in "-Id Gc~vtvy )@- filnd'er Su4zie .Cmtpr -I Doe Pa~n NH4Iht X-2.0 c~h 25 tt Radtvt 1I 134.9 cm .381 em 4 ht 5.1 In 12 I't COin ShIelds 4. 1108 i ALOL M91904 I1cmn' Cosncre 65 cmr Iei Sh~ek 1 S2A4 48 cm Cwwwk 2A 0700 1 25 em Iron sawce Niput GQporipg Miethod 'AetuPI Pl*toM Eirg~jeS 1-1,29 8.2O~081.0 30372eo000 415000.009 1.66SOec004 The matzria reeente Is - CIL Cor 20 Resulta wfl/br 3.660e-.36

'0:0295 3 &02* 34 6. 7 76e,315 7-026e-84 21910,66 D.0336 16 5t-34 2,484e-36 2'.284-c-01 23 64-46 12%o46~

Cl-218

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page :2 DOS File M1~22929 ASS Run Da1c; 'amber 2ý. 200O5 R-un Time, 3:42-.4 PM Du~r-hQ,¶on -~J f.ýCIerw fiuenceate MRY TOTALS: 2Z3594too 2.764e.0$ 1,7239-33 1.2~.4S 1.4-53e-IS

.C1-219

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MkragSletO 40A4 (S.O4OOM W229IOS McraShIsId w&,04 (&.04-00362)

Cmawsiwofi@ cakulated cipmuro inair to dms CM. ?10 Ltni LaZ G Mhs. case was maon Thundaj Dsumber 29. 2M at 3A2:46 PAI Results tsumre ovr nr j& WkMf Photont Fluence Rate (flux) Photons/cmlisec 6.9W;045- S.369"'O22 FPotOn Energy fluen* Rot 2,764,9-46 I .7,39-033 Exposure and Dose Rates:

Expaw~re Ract in Air mR/hr I .25&e 048 1,453e-035 Absorb~ed Dase Rate in Air m~y./hr 1.2696-057 mraid~lh 1.976O48 1-269e.035 Dowp Clow Eqaivalert Rate (ICRP 51 - 1987)

'0Op"SedG~ne~ 1,4.3c-0.37 7;90Ue.O5I 7,2V*.038 a Roa-ttional 7.1S80,051 61215e-038 o Isotropoc 5.772-c-038 Shallow Dose Equivalen Rate (tCRP 51 - 1987) o Parallel Geometry 1 583e-037 o Roatiosiai 0 I1Sotropic Elfctive Dow Equivalent Rate (ICRP 51 - 1987) 3.i056e0 o Anterior/Posteirior Geometry mS~hr 6,512t,038 13Z67e'.038 1.817e.038 o Robtierial 4197$0.051 3.34-50-03 o ISMOtWo 440o78@051 2:772e4038 Pago I C1-220

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MitroubIell44 Y544 (64440.368)

Radibogiqcal Bervims Inc.

Pftg  ; File Ifte ______

00-- -r1% PBO04O&IIS DA:, ý k4. ale, JAnrusty ~ 0 Run Time: 8:24:59 AM bu~ration ooo Cates Pilot Une 1.111 H bosicriptiln: Revised Model Cat 5r,'126 Unki Act w Schod 40 IL12 rin ShId O4omnery !10 Cy~r~do7 Surface - Exlermna Da Point I4Set DimensIion Height 762.0 cm Riafts 81cmr 25 in Obse Poins I.

M 1 trm .391 crm 4 t5 f! 12 11 b.0 in

'K Cy, Core shtelds wastfii 3,81 rm'

.65cm Carti 'e1*

ivbri Z4 4.

O:W2.8 Shim 3l 3)*#-. Camret Air Wall Clad .025 Cm I-a 126 5ouvro input avcmupIlg Mothad Stamdard Ivricos, Luww Eewra, Watfl : O015 S~,1. 2 a2i7e oil 3,0372a0,P00 4.5O00060 19 1.66~QO4 Ue. mitoilall reference Is -Cyl. Core V 1OW46aI Parameters 20 20 Results 2.351e-01 3,266c-235 6.4&,9 35 1. 132e.236 2.237e-M C1-221

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Page .. '.2 P3Q5 Hie -P9BOW&405,MS Run Mae: January 4 . 2006 Run Time! 81:5 AM~

Dkir'-tion ; O;W0i1 Rpem-a Ra No Ewiidu~

0.04 I 54e,82 5.4,02s-34 0.04 1,.427946 2."44.-35 6.3 10*49 1 01e-37 2.911041 1,747e.25 3,470o.28 0.06 4,ID2a-24 8.1~27e-27 L054,00 I .309c 19 2.072.o,22 q.4789.21 ro'rAvs! .25~Q 1.309e- 1i, 5.989048 2,072@,22 9.478e.21 C] -222

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 Mic-ra5bf*d 0544 504-00362) 0o/iooe MlcreSheled wG.4 (6.0440O302)

Cooversi ofc~alculated expo.ture Imn air to doum FILE-. C+/-XMS5-\OA1A\fpBO1O,4CO6f Cam TRIu Lri UPA 1H9 Thisi case was run on Wedmeda~y, Jariuury 4, 2MO at 8:24:59 AM Daseftlm 9#1 (u* 1 8i1-e Cm C&Imeoer energios) Ch.

EýUildu 1.4370-0 1S 7,486e-017 P6Wvkmýb meg 1,30C,019 5.98e-O18 Fup"sg'o ANt4Wse Rates Exposvr gme Jii Air 9-478e-021I ArbwcbM Ov Rate in Air ~Gy/hr 140%2022 B8.2,74e-M3

.inr.~/Iv 8,274-021 b)eep E'ajentf LDosalqi Rate, oPae 11e4 GCme~ry 3.1 64-.0R4 1,66,5a3.024 7.708E-023 7.4,92t;023 1,626O24 1.438c-023 Sh~w o Equivalet Rate 0 Parallel O-armay 1,.434e-022 2 3O~e4~. 1.054e-022 aiRoattional 2.304-9,024 1.0542p,22

m. w/hr 7.735aý023 ElfedI~we~ 0 .quivalent Rate o t~ierP~st ienetty uean 1.21 5e-02-2 2 02 a-024' 9.,2 71e-02 5.7 14a-.Q2.3 T8971q-023 1ý3fto 024 6. 387e-023 Pose I C1-223

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 IftraShlield 4404 (S."-0 Radiological swV1446, Oft-No Rof;_____

Dtr itde J43122931 JA~5 Date.:_ __

,PL i1t: Dicrmpbw 29, 2005 Run Timv ~.55:0 FIA Durston ý 00; Caise Tltiu Lime 1.82 Dvicriptlariu RevisdaI Ofdol (;Wc- Zr-95 Um It ct w Sehed 40& 1~2 Ito $id Gemaulry: WL-Cy4indef Surface E1~Ntarm Doss Point ff, C0 Din naIleqs

76. con, 25 ft kne PW@fti I , 134.97 cm I ~ 37,~6r~12 4 ft5.1 inl W~IT cm 4 ft 6.0 in SI,2 ds L*Auipn Material LDej yA cyt. 0&0 3. 51 crri, Concxete 1.8 65 Ifl

[ta 7.86

,C~rete 2.4 4.8 Vm C-Wwcri 2.4 Aoir G~p 44 0.001 Z2 Wa.il Clad 025 ern Wonr 7.85 Gm~ziirug ftTnhod AcMtual Phwoton Enariefgef Mud3 8 2087-61011 3.0372~0+00 4.5O00Gc-09 L6G 004 The matariI rqfteofte is- ILC 1,BInMvatI6 PNOM91Mnr 20 CQrcurnifurati~aI .20 Exnamse-McI~nt EKXWLMLO"i

,M!Recrnz;.rc MIME, Reut witIiiAua 0-7242 13269+00 9.5460,14 21350e- 11 0,7567 1.681eO00 7,926e,-I1 I.5114-13 3.SDO4e.12 TOlTALS; 3.0070400 1.289e. 10 C3 13e-29 2,472.0-13 5.85 4 e. 12 Cl -224

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Micvoghleld vl.04 (5,04-03i42)

Mkclshleld VC04 .45'"0032)

Rad kgklo S4"wvIcps. Inc.

Canfersin Qf ltkdto to Ongt

• 0~sv FILK; OWMAA112,3.

Case THN~: k~ne I -, I ibis cbse w"s ni" on Thr"".4 DwombOr 29. Wi5 at I3".5~;03 PM DO owtItU t14.7.llL.1S) cu a 1-97n with Nolonz/wcriWVwe 1-733oe-01O 4I,?0.OOM Phtotat EfmIy FIuenoe Rate MOV/cffwswc Exposuro an inAir c v mRthr 2.472o'Q]I3 AErbOIUF R)ae Ritn~ Air llft1y/i fr 5,U11*.014 J¶rNax/hr (PONP 51 ,1987) 2.152%OM oý b Doso W in Ai 2 V570-01 ý Ch~~hh 4Ui Equn~idrwlt Rog, 2,057e..01 S 0 PiaraIIk Gaamrye m,.Whr 605. e-014 aiOpp'ou-hd 4.739c,014 2-573e-01 S M0r 1639-0~14 v AnlwioeiPatedo4 Geamdry 2.247e,0 15 6 orA~i 1,505e.015 1790e.0 1 4.230e.014 C1-225

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5,04-00362)

Ralofogcal Savivces, Inc.L page ;1I Fitc Ro;_

DO', File !PB122932-M&5 Date:

11% ate; Deomber 29o Z)05 By; Rvn Tome-. 3: 57;38 PM Qhoeld.

Duratiom : 00:00:01 Case Title., Line 1.82 J

~ Rv9$e Model COIC- Fw-1$5 Un¶ i~tAdW $4d~ 40 & 12 fio hl geomietry: 10 - CylInmder Surfface - External Doese Point lFt0,Jz w-,*. - . .. . . . . .

ource Dimnen~sions Height 7 62.0 cm 25 ft Radius 3.81 cm 1,5 in z

1. 1 134,97Cm 38~em 137.16 cm 4it 5.1 in 12 ft 6.0 in 4 ft 6.0 In Shields Sh~ield Name I CAi, Core 1#1i cm?2 Conc rot 2.84 Shield I .'65 CM tro n Tran!Witon ie 2,4 Shield 3 304Acm Concrat e 2.4 Air Cap 0.00,i22

.026 an fronr 7.86 5vur" Input caep~ing Metlwd .stafiidwd IndkIBs Numnbeif of Groups 25 Lowet tEmW VI:UjlI t 6.3.

Polons,9~0.015 .Ecue lLibrary::Grove.

Eu- 155 8.208e- Oil1 .,0372@-+000 4,50000~Oe 1.650eC004

.The malarial reference Is , Cyl. Cere Integration Paramieters 20 Ci~curnftoren tiat 20 Ad ". Zwr'ah'PLl gaaal mtU 1.wOwl MIL 03 9.667e.03 527 2s-36 5.820o.38 C1-226

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 PW~ .2 DOS Fit~e - P122932.MS5

~IRn Date: VoCember 29, 2005 Run Time: 3:57:38 PM ur-tioll i; c .O 0,04 5. 505e~o 1 S. 17 i-45 aSZGWe34 2,2909-47 3,92.29-36 0.05 1.791"g~1 7. 354e-32 '7.449e-3 1 1.49S9e*34- 1.a98e-33 0.06 3.-99e-02 2,364e-26 -.5~39e-25 4,6969-29 1,1009-27 0,08 9,431a.301 $.$54ev 20 ý44,OOe-18~ I .40le-2Z~ SAe2 0.1 6.27ge-0 1 7,75,39-18 -5,9216e.1i6 1,1868-20 9.06819 TOTALS: 2,,350t+60 7.841c,18 53960-16 1.200e,20 9,13N-19 C1-227

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Iikjo~hiswld V5.04 0,04)OU3Z) 12/29/

MicreShield vS.O4 (SAM4021 Radlelogilem Servuices, It Comejsrsion of calcul~add expasure in air to, dose ME:L C-.\MS5kOATAkPR122932.MSS This case was~run on Thursday, Decemvber 2.9,2005 at 3.67.:38 PM4 Dose. Point # I1- 9, 1, CM16 Wiidha Photons/c-=N2 sec 7.96 3L-01 7 5-976e-0 15 fototn Er~eigy Fluenrce Rate MeV/C~m2/SeC 7-B4 le-DI B 5-966e.0 16 txposure anrd Doso Rates-Exposurt Rate In Air snR/ho- I .200e-D20 9.130e-019 Absorbed Dose Rarte in Air mnGy/hr 1-.048e- 022 7,970e.021 rnrad/hgr 1- L48e- 020 7.970e,0 19 NIOP Dose Equivalent Rafe~ QICRP 51 - 1987) a Parallel Gkkametry rnSv/hr I -ý32e,020 a Oppo%'d 9,603e-023 7,30'5e.021I o Rotational 7.-304e.02 1 9,292e-023 7,069i6.02 1 S1-3H-w0 Dose Equivalent Rate c~ PafaIA& Geometry 1.74,09-022 1.324e.020 10 Opposed 1.3&e-022 1.027e:-020 1-350C.02 1.027-e-020 olsouapic Ui 9.827-e-023 7.4764,-,01, (ICRP 51

• 1987)

F-irftif Dez E-quivi4dnt Ile. r*;S/hr I

o Arrerior/rPosrerior 3ec~n-ietrr 2 .506e.022 a Poserlair/Ant~erior 1, 1 80e,022 8.980e-02 1 o Latorall 7 .285e.023 5.42)e-02 1 a Rotational 1 .008e-022 a Isoaopic 1Q1 QRI Page C1-228

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield Y5.0-4 (5.04-00362)

Page  ;

Eit1S File : B1i,2i,2MS5 Date:_____ __

Pa ate; Deerriber 19, 200!5 Ro6-1-Time: 2:-43:03 PM Checked~:_______

D~uration 0O0-.0:01 Case Title, Line L8B3 A2 P"iCripffork: Po*ised M60 dal~c Co4I) Valt Ai~t w Sieho 40~ 4 12 -it $.h1t Geometry Cylinder Suirfce -Externial Dose Pofnt 1***Heigh~t Radius 762.0 cm 5.08 cm 25 ft 2.o in D054 1 cmIL i~1 136-24 er 213.36 cm 4 ft 5.6 i n 12 ft6.0 in 7 ft 00 in ShieIfds Dimerns~pn Maer qL Densi1t

'CyJ Care, 5M8 CM Ccomcte te 1.8 Shield I .6 C Im tort 7.86 Transi!Fon to 2.4 Shield 3 .30.48 om Coni'cer te 2.4 Air Ca A~ir 70=12

ýsalI Clad .025 Drnm lrcc 7,86 sourca Input re~iprr~ Mothod ;Actuali Photon I~Emu~ies Niiciidi~ ~~urE4s a r 15 b~o Uci/c,rn

~ 4 J..094~.0~0 - ,496v-+OC 4.5~0000-9 1.6650e.00Y4 Buildup The material referomw~ is. Cyl. GCair Prntegj'affm Parameters 20 Ci rnfmerential1 20 0.&93 2Z821P;,1A4 5,447e. 17 1-1732 1.4166e. 10 2,020e.09 2.08.4e-13; 1.3325 4.0ý4e+0 .3..513e.09 4.226e ~3 3.09~e,12 2.36e;i~ 10 ALS: ~AOC~+OO 5.6S3,0-09 &3100.13 9.;'5Oeo12 C1-229

Plum Brook ReactorFacility FinalStatusSurvey Plan Revision 0 kro$Fiield vS.04 (B.D"0362) 01/02/C MkiroShield vS.04 ISA445019 Cagversion ol "ikIwu!M w~pusw in imir to dose FILE: C:\MSS\DATAkPB12192t1MS5 Cos* TRIO- Limae X.a AZ This casea was run an Monday, Decwnber 1, 2W05 at 2:43:03 PM 0000 ftiffit 4 1 (.&21,3.) c~m VIdb Photons/carr 2 /sec 2.-82 2e-0100 Phiotoni Emerg Fl it4nce Rate 3a6o2e-01 0 5.633900D9 Expo~sure and Dose Rates--

Exoure Rale In Alk fnR/hr 6..31Oe-013 9.70,5e-0 12 Abwvrbed D~ Rimto in Air MGY/hr 5. 5090-01 5 8.472e-.014 m-.rad/hr Cw .Dose Equ ivaigont Rato (ICRP 51 . 19i87) a Parallel Gecawtry m~v/hr 6-252e-01 5 ,9,61 F~e.Q 14 8,285~e-0 14 o Rcttatic'nal 8-285e-014 4.91 4e-01 S ShaIfbw Ciose Equiyalent Rate (ICRP 51 - 1987) a Paraliel Gei-nc-rftre rn,5vhr 6,654c.0 15 1.024e.-013 6.4CY~e.(O 15 9.858e.0 114 o Rcitati-onal 6.409e'O 15 9,858e-014 6ibvlos 5.O09ge.O15 7.841 e.014 Eff ective Case E~quivaIeit at (1CRP 51 -1987) a Antesior/Posterior Gecinetry m$'v/hr !5.63le-4J15 8..661e-014 0 oPslerior/Antgrior 7.9ne-01 4 o Lateral 4.1 30e-015 6.,348e-014 oiRttaflori~l 4.673e.015S U 'o p. 4.133e-015 6.360e-D1 4 Page C1-230

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShrield Y5.04 (5.04-00O362)

Radiological Servicerp Imc.

file Ref:______

DOS File : P'3122141.MS5 By:

Ruri-1ime: 6&38:11 RM Duration : 0:00:01 Case

Title:

Line 1.83 B Descriptifo, Reviset! mideI t*Ie. cs~-117 Ualt Act w $ohed 40 & 12 In SWt Gemnetry: 10 ,Cyl ader Sufface , External ftse Polint 11.1 ~ SomTe DireIans 25 ft Reight Raiu 5.08cm 2.0 in z

41 13624 er c1m 4 ft5.6in 12 t 15.0in CYL Core 6, 8 crn2 Conc ret Shield I 65 eryi Ir 2.4 Transition Concret Shield 3 30, 48 cm Concret Air 1ýi Ali 0,00122 VWalI Clad 0,25Gr Imm 7.86 Grctuping Miethod Actual PhDoton Eiterges

=i= .11AQ=QL-- tg?'i=3m Ba-137m 1.054e-010 3.8309e+000 4.2S7Ce-00 1.5751e-CO4 Cs. 137 1.094-5o010 4.496c,+00 4;5XCC9-NC1 1.6650~e-00I4 SWiIldup The, mate fat, referenice Is : Cyl. Core Integrition Parameters Y Direclion (ax~ial) 20 Circumtorwitial 20 1=1 U, 1.931e-02 1.5cm'ser8 31515-35 0.0322 1.4 634,-,Q 7106e-35 1,239c-~88 6.0e1 e-37 0 )364 5.3254e-02 4.181t 35 6.124e,69 2.37 le!37 31$ 3.447e+00 N.37e-12 1-163e-10 5R.3cze-15 2.2~55e.13 C1-231

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Page :2 Ru'n Date: Diceiber 21, 2005 Ru n T i Me,.5 19-1.,1 F3M Dur.4tion : 003:00-01 fluenro Rall ..~RLtAk Mty E1sue at TOTALS: 137Neg+00 2.7375-12 1,1 63e I0 5,306e-15 2.255e-13 C1-232

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MI-Croojieid W&04 (5.04-030362) QJOZI/06 101r05bield v5.04 (5.04-00362) tadlatgical $e~vkice, Inc.

Conversionu of cal'ulated exposwu 9Ini air to dose FILE, C,-NMSS\OATA\P812214i.MS85 Case 7tio. Line 1.83 8 This cas~e was rwn an Wednesday, De'emiber 21, 2005 at 6-111,1 PMA 0068 Poinht 4 2 - (12C4,38M13.3) t~

UMM-tLýMEQ pynr energies, wathaut V-dhdU Photons/cml/sec 4.1 379-012 Phioton Eiwgy A weene Rate MeWcM'/Sec 1.1 53,.OIO 2, ?7376,012 Exposure and Dose Rates,-

Lxpur- Rat In Air mR/hr 5.3069-015 2. 2S5e-013 Absorbed Dose Rate in Air im~y/hrt 4-3UO 7 1.96%1~01 mra'i/hr 4,6329-015 1.960e-013 Dcp Doco Equivalent Rate (ICRP 51 -19~87) a Paragilel G~eometry m&v/hr 5.44Me-017, 439 li-017 a Rotational 4-39 1c.017 3.883e-01 7 Mk~allow C~es Equiva lent Rate QICRP 51 .M7 o ParidoeI Gcow1&y 5.82gkL-OI 7 2 .477e-0~1$

a Opposed 5,5.36001 7 2.353e-O15S a Rotational 5.!&6e-01 7 o Ialosipic 4. 15le-017 1.76'4e-015 o Aritenor/Postehor Gec-roatni m.S'vhr 4-Nge-ti 7 ý-( 14-.0,1, a Poteir/orAnteril0r 4.280c,' 017 1.819e-015 a L.6torioI ~3, 174e-01 7 1.34%,.015 o Rota~ionaO 3.92'5e.,017 L.626e.015 0 Isotropic 3.2-56" 17 Page I C1-233

Plum Brook Rea'ctorFacility FinalStatus Survey Plan Revision 0 MicroShield Y5.0.4 (5.04-00362)

R~adiolo~gical Services, Inc.

Page :1 File Ref; _____

DOS~ File , PB=2242.MS5 By:

mphrTire: 6;,93$ PIM Checked: ______

Duratic~n .-00:00:01 Case Title-. Line 1.83 C Newilsed Model Catc.ý EU-152 U~nit Act w Schad 40 & 12 on Shtd mm Desclpion Gooriwvtry; 10 - Cylinder Surfaca Extmaiil Des@ Poinvt Heigbt Source7-62.0 Diniemlons cm 25f1 Ridius 5.08 cm 2.0 In Dose Points x

1. 1 136,24 c 21336 cm 4:ft 5.6 i 12ft 6.0 in 7 ft0.0 in Shiel~ds Denit Cyl, Core 5.013 cml Conc rette 1,1 Shleld I m G6 Ir.ý)n 7,86 Tramn.*it.,o Concre~:e 2.4 i

Shield 3 3DM = Cowet :e2.4 Ait rtp 0.O00122 Wall Clad 7186 Source luinpii GrouIngh "holid ,Stamdavid loidIco Numbw- of Groups 2 Low"t Eft.,erg Culoll - 0.015 Pholons < 0.015 . xfjuded Lrbrary: Girv hluraW curL"A 1

Eu-152 1,09445e.e0 ý.0 4,0496o+Vo0 4,5000e.OC 9* 1.6650e-004

.Buildup

'The mateilal tefeteiice i~s -Cyt, Cove Integrationi Parameters Y.Direc on (~~l 20 Ci rcumicrential 20 Results EunrgUL Pn ARn.ita Wi~th auiIdflg 3M~bz5 2.3'9~+0O 9.024e-54 2.6 180,113 1.158e-35 C1-234

Plum Brook ReactorFacility Final.StatusSurvey Plan Revision 0 DOS File; P8122142.MS5 Ron Date! Cecemrber 21, 20O5 Dur~ltion :00:00O:01 Activity Fh'tsnr~p RE& Fliuoflc Raite 0.05 5,9'91t-01 59. 3*4$0 0-1 1.1.61e+00 1,6510420 6 2272e-15 2;525e-23 0.2 3.17,5e-17 -..604e-20 1.098e- I 0.3 1.0958*00 41414-13 5,9808-18 0.4 2-94&.401 6,228e* 15 ~5-881e-13 1.2 13e-17 0.5 2,.284t-12 2.722e- 15 1448Že-1 3 3.572e- 16 0.6 1-717e-01 a35399-12 1,3JE1e 16 7-2 10e-01 1 .967e. 112 6.1.57e-I 1 3.742e-15 Li07.c15~1 0A 1.0 1. 7339*00 1 ~1 4.21~.3,40 3$.$C9,14 7.766.-te,1 i.5 Q-3,94e-O 1 1-34le-09 1,8MQ-13 2.256e-12 TOTALS: 9.387e+00 1303e-10 1,828C.09 2.227o-.13 3,159*-12 C1-235

Plum*Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5,04-00362) 01/0~2/06 Micro ~hibod v5.04 (5,04-0362)

Radlo~gicall Services, In~c.

Conver~Own of caftulated vitpeure I-n air 11a dose FILE: C.-kNIMS\AMMP822142.11VSS Cahsc TWOI: LIJMO 1,3 C.

This case was run an Wednesday, December 21, 200S at 6:39,33 PM 11:4 mmat nui n Pa~uiIk Ferint # 1C Buteu Pboton Flu~enc Rate Oltux) Ph~o~tonsm~sec 9-446e-O1 1 1.401 e.009 INwiton Enbergy Fliijce Rate MeQiCm1/sM 1,3039-010 1,8289.OD9 Eapc.ure anrd Dose Ratus; ExW. ure Ralle In Air m-Rlhr 2-.22 7e-.1 3 Absorbed Dose Rate in Air MGY/h r 1,.944e-01 5 2. 7589-014 imrad/hr 1.944e-01 3 2. 758e. 12 Nsep Does Equivailont Rate (ICRP 51

• 1987) a FParailer' Geo1?etry mSv/hr 2,205s.015 3.134o.014 0 GO;Ipo~A'd n 1.914e-01 5 2. 707e*O014 anRotationat I .914efOI 2, 707c, 14 1,7349-O15 2,4219-014

$ýkqflicw Dose Equiia lent Rate (ICRP 51 1987) m~v/hr o Parallel Gaornsry -3326r,.014 2,2599-015 3.20ge-O 14 o R-otati'onal 2.2gie.O1 5 1.2One.O14 0 lsoropie 21557s.0 14 Effective Ocss E~qui-walcnt Ratc (ýCRP 51 1987) o A.M1terior/ftsterior etf mS'v/hr 1.986e-015 2.820e.014 a RDsoi~fr/Arotrior 9 2,60J3c.014 o Lateral 1.478e-015 2.081 e0 14 o Rotational 1.655e-03 5 2.34,7*,014 0 10oi 1.475e,-015 2. 081 a -014 Page I C1-236

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 M~icroShie~d Y5.04 (5,04-00362)

Radiologcall Servles, Inc.

Page :1I File Ref; ____

DC!; Fie ; P12,2143,10S5 RL, at@.: D'e~embe: 21, 20M By:

Run-Time: 6:40:51 PMA Checked:____ ___

Duration : OG:00:01i Case

Title:

Lline 1.83 D Descrlptiwn;.Rc~1svd M~di (alc* Eu-25-4 Unit Ad w uhed-40 & 2 in 5Shl~d Gieometry- 10 -Cylinder Surface - ternall Dose Point G2CZ--

$owrce Dlmnensimn Height 762.0 cm 25 ft Radius 5US8 cm 2.0 in z

01 136.24 cr ii 381 CM 213,36 cm 4 ft 5.6 in 12 ft6.0onr 7 ft 0.0 in Shiields Cyt! COTO 5,08 cml Gon crelte 1,8 Shield I .65icCM i ,on 7.86 a Tran.*illion to 2A4 Shield 3 30.48 em ComV~~

Air (Glp 0.001 Z2 Wal',i Clad ..025 cm Irun 7.26 Groupipng Ntethod - Slauidard Indices-N4umber ot Groups 25 Lower Ener~gy Cutoff,: 0.015 Photoans it 0,015 -.fcluded Library -.Gmim 1.04-45e. 010 4,0496t+000 4,50~00e-0 1 ,650otO

,Eu-154 9 Buildup The material relersuce Is : Cyl. Core Integtrrin Paramneter's; Y Direcfion (axial) 20 Cifrcum~rnoretial 20 Rusulis flkiouc E 9.oc~Je R34 La.L X~ 42Q .3.104e-54 1.3739-56 CI-237

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 Paige  ;

DOS File P8 122143.MS5 Run~ Date: Decemtber 21, 2L*5, Run Time; M;O-15 PM Dur-tion 0,0:01 J:

0-05 2. 093401 7,419c.34 0,11 1,63'9e+00 2,349,e.20 2,665e.18 3-5949-23 4.07 79-21 0.2 2. 766e-D1 199~4e.17 5.672e,15 1.0(%g-17 0.4 7.07 lo.16 6,6763. 14 1,3769-18 0.5 8.7613e-03 1.1045~e-15 6..95e. 14 1.371e.16 1,351-t-13 6.73le12 0.8 1,246e-ýo1 4.309e- 12 1..34ge.10 8. 196e. 15 2.565e. 13 1.0 1 57M0840 1.3721 I -3,029e-'10 5.wea 13 1.5 1 86-10 2.2 55e .09 ý.~7a4e-12 TOiTALS: 7.718e4ý00 2.0 18e, 10 2.,'00c.09 3,427e-13 4-623e- 12 C1-238

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 litro~h4ld 514. (5<.04,00162) 01/02/I Microahleld v5.04 (."4032)

Corwerrvioq ovf cauluateid expe~suria In air lo dose FI LE- C. A5\DS\ATMAPf122143.MS5S Case Tilek; Line 1,83 D This case was run an Wednesday.. Deembtner 21. 2005 ENO6:40.51 PM OPOa Po~int# I - (33.2,9,2336 n With Ph'oton Flvenbc Rauto (R~um) Pholans/cm-k/s~ec L~4170-010 I ,987t-09 Photon Enefgy fluenc-i Rate Melv/m'heic 2. 01 Be-OlO 2-.700e-009~

Exposurea nd Doue Ra tes EUpoure R~ate In Air mrR/ht 3A427e;.013 4-623e-01 2 Absorbed Dose Rate in Air m~ylhr 2.991e,01 $ 4.Q.360-D1 4 mrad/hT 2.2919e-01 3 4,06-12 Deep Dc~e Equiv~t~v-t IRMO, e'ICRp 51 -1,go) o Parallel Geom~etry mS'dlhr 3-389e-01 5 4. 0c-14

2. 950e-01 5 3-g7Ie01 4 o Ro~tati~onal 215C0,1 5 1~971e-014 q I-0ra i 2. 644e-01 5 3.55e01 4

ýhsfi~vi aose Equi~alent Rate IcP51 -119 487) o Para Ile-4 Georrne-try mSv/hr 3.589e-01 5 &.a5ge-01 4 0 p-cV 3.47le-01 5 4.9*J4 ro Rotational -3471ic-01 5 4ý690e-O 14 o0Isatrropf'r 2. 785e-131 6 3.750e-0-14 C]CRP 51, 10987) ci Anterior/Pcoskerior Gaecrnwtry rnSY/hr -$;054k-u 5 4i 24c-0l)4 ra Plosterlar/Anterior 2.831c-131 5 3-814e-01.4 io LplfraI 2. 283a-D1 5 3.063e-014 oi Ro~tational 2. 5-5e-.

ISM-05 3,441cVO14

2. 277e-D1 5 3. 05HS&-0 14 Pagg C-1-239.

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 Microftl eld Y5.04 (5,04-00362)

RadleolglcaE Services, Inc.

Pap  ;:1 Filt Per: ______

Q(1t File, ! FBI22144.MSS RL , ate: Janua~ry 2.' 20M~

Ruý Time: 8!0,957 AM Checked: ______

Duratic-P =00-401 Case Title., Lino 1.9! E De~scr]Ptior: Revised Model Calc, Ag.1O;1m Uait Act w SdIw 40 & 12 In S1114 Geometer I0C Cyi~der~wrtuw, EfL~rmaUlOie ~ar I x iiarce Dimensioni Height 25 ft Radius 5.08 CM 2,0 in Dose Porinis Al 1.36.24 ern ~1m 213,36 cm 4 ft 5.6 in 22 ft Uin 7 ft D.0 in Shields

• liield Name )Ienlon Mate 5X4~ On' OCnri rctt* 1.8 Shield 1 .65 ern Ira 7.86 Tran!ijiori te 2,4 Shield 3 30.48 Mb cCmcre4e 2.4 Air Gap Air 0,001 22

'Nall Clad .025CM Iro-! 7.86 Source Input Grouping. Metho~d - Slandard indices Number ýof Groups ; 25 LO wer Egwegy ~itU1 1 001 IPhotons -9G.O15 , Ucuded Library :Grove A,- 108m I .Q94~ L-010' 4.M49~+QQ 4.VQ Dý 1~~Qi-~Q4 BuilIdup The maiewlaJ reference is, CyL. Care Iivlegratiori Paramieters V D'irecton' Owki~l) 20 Civcum'fereaitial 20 MFlggir La~ MeV/rW/seQ 2.656v4lO Me3irn2s-29 1 1.367e-292 131 5e-35 Cl -240

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 Page -2 DOS File : P6122144.MS5 Runn Tome: 8:09:57 AM Enffug activity 0103 S. 59geQ7 3.04e- 107 .3543,u4 0 3.0139-109 3.5129-42 0.08 2.870e-01 1 G290-23 6.373e-22 1,628cý26 1.009e.24 0.4. 3.64Oe4OO 8.908e-14 8.41 g.] 2 1.736e-16 O6 B6399-14 3a66~1e+O0 1.5 ]14ft 12 7.$43e.] 1 1.472e.13 0.8 3.66se4oo L.OONe-11 3.130e-10 1.902@-.15 5.953a.13 TOTALS: 1.3,418+01 I 1O160, II 3.968C.10 2.2154--14 7Y589e-13 C1-241

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Mlcro~Iled Y5.04 (5-04OO362) 0 1/(122/6 MicroShiuI4 v5.04 (5.04-O03M)

"RadioJegocalSovidsm, Inc.

Conrsion ofIicalculated expomrar ini air to~ dose FILE: C:\MSS\DA1TAkPB122UALMSS C~asio

Title:

Line 1.9$ E This case was run mon~Iwday, Janiuary 2. 2006 at 8,09- 7 AM Dose Point 4 1 - (136.2A Ot1213aU) cm EA,5UIrs ISuMn edovrn efgjer Uw Phioton Fluemce Rate (i uix) Photons/cunV/sec 1.525"-1 1 5-380e-010 Phioton Ezbtdgy Fiernce Rate MeWCOW16/&C E~xposure an oe ae-Eximaute Rate I-V Ai~r mR/hr 2,2150-014 7.589,-GI3 Abs~orbed Dose Rate in Air mn~y/br 1.934e.0 16 al mrad~hr 1.9ý4o.O14 6.625e-01 3 Deep rCQe Equiy'atent Ra~te (lCRP 51 - 1987.)

a FPirarie'! Ge'ornefty m.~y/hr 1,846e*016 a Rotational 1.846e.0 16 6.3 1Se-DIS 1 .6320,16 5. 585a*015 Sihaitc Dose Equi'vailent Rate (IC"RP S1 -. 7 a Parallel Gvcrmoi~y mSv/hr Z2U.4e16 8.289e.0 15 a Opposed 7,857m.0 15 o Rotatiorpl 2,.303e.016 7.8g7e*O019 a lsalropqc 5.975e.O015 (iCRP 51 - w Eflodiive Ciose Eqivaeni Patei a Anterior/Postenior Geomriary m~vhr, 1-7962e-016 C)Paslerior/Ant~eri--n 6.1500-015 o LateralI 1-6076e-G16 4,625o.01 5 o Rotarional S5 so oe*O01 5 a I"'0if0cipC 1.378e-016 4,7134-015 Page 1 C1-242

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Mkiro$~ibeld Y5-4 (5-044KW362)

OdhiowskcaI $WwIces, Inc.

Page ,I F~ile RIO: ______

D~O'SFt P8122145MS5 Oate:____

FIX 't.;DO421,ZO00 By.,

%bjrf T1me, 6:43-:57 P)A Checr kd :______

Duratiao -0;00 Case

Title:

Line 1.83 F posotpti~m: Rvised Model~ "c-k tNb-94 UniIt Act w Sched 40 4 12 Im$-It Geomnetry: 10 - CylInder Surface - xternial Dose Point Heig-tt 762.0 cm 25 rt Radlus 5.08 cm 2,0 in Dose Point y

S136.24 cM 8ci 213.36 crrn 4 ft5rain 12 ft 6,Qin 7 ft GQ inl Shields aU, tdiAM&. Dirrnemsion Mae et 7 .86 S hield 1 .65 am.~ Irati z e~ 2,4 Shield 3 309,48 cmn Cowre e 2.4 A~ir Gap Air 0,00,122 Srim Irgn Sourto Input Gmw4I~ng Metchod 4Actwl~ "on Eftmrg1%

Nucl idl u~ilmlea em I41 palc

~Nb-94 LO 94 5e- 11 4AO496o+000 4ý5.00 O9Q 1.-6650a.004 The materhal rei~fer eme Is :C14. Core Integration Parawieters 20 Ci rcumlerentiad 20 Results 0,01,74 1-432e-0O3 2.142eý37 1,15SQ!38 0.000ic+D 0.0175 274 3e-C' 4i.1 430-37 0.000,8+0( 2,19~4e-38 0,0196 4-05 0e-C-1.466e-3~7 6.374e.39 0,7026 4.050e+00

,4:774,4. 12 1,641c,1 ~0 711 1,69~56, 21 5.,1859-10 .3.56'5e-14 978e13 C1-243

Plum Brook Reactor Facility Final.Status Survey Plan Revision 0 Page. ;2 RMin Date; Chcember 21, 2005 Run Timne, 6,.43:7 PMO IDuraticki :00-00.01 A~vi1y Flu2nGLE.=. FlunmrAt PaIn Msuu.cwl rxQ1j' au g 2ahiudd=

TOTALS: 8,104e+00 2,3739-1 1 7,O6e.O10 4.4882e.14 1,331e-22 C1-244

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Mlct)v$1iel~d YS.04 (5.N0"0362) 01/ii206 Microhileld v6.04 (5.04,00362) ftadloiJgkal $enieft, lIme, Corwersioi of calculated exporpure In air to dew0 PILE: C-MMI)\AMAPB12145,10155 COse TOW~ MOrO L83 lF "Thiscaure was nmi on Wednoesday, becembgr 21, 2005 at 6:4197 P#A Dose Point a 1 - On$4O12336)~

EQW=%'=sumed ga'r angrim-M. Units M=tou M, h Pi-4oton rlgezce Rate (1111J Photo s/cm;'/sec 2 .855e*o 11 815720,010 Photon Enmgy Fluence Rate Mit'1CM 2/sec 2-373e-011 7.026e--010 Exposure aind Dose Rates-,

Expysure Rate in Ale mR/hr 4.488e.O014 1-3314012 Absorbed Dosae Rate in Air mGy/hr :3 91 8.O016 1-162e-014 mrad/thr 3.918e.014 1-16~2e-1 N D t~~we~Eqw ya'nt Rat!, (ICRP 51 197 o Paral lei Geometry r~iSv/hr 4.553e-026 1.351e.0,14 3-755elOI6 1411i3e-01 4 o Rotational 3-755---016 1.11 3e-01 4 a ISAolSpic 3.:921&-026 9,840o- 015 Shallow Dose Equivalent Rate (ICRP 51 1987) mSy/hr 4.870e-01 6 1.445e.0 14 GOpposed 4-648e-01 6 1,379e-C 14 a~ Rotational 4,64,Bg.Oj 6 1.37ge-014 o lsotropit 1.05.3e.0 14

'E~fictive. Dose Euialent Rate o AnterloriPosterlor CGeomnetiy mf(hr 4.06'Oe*O1CS 2.20rm.O 14 c Porstmor/44dcrior 3.646e.Q 1 11,081eO014 a Lateral 2,774e-0 16 8-212~e-015 o Rsot~icga 3.264e.0 16 9-5759-035 2,8150,016 8.3315e-015 Page I C1-245

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShleld Y5.04 (5.04-00362>

Radiological Segyices., Inc.

Page :I File Ref; DOS Fle : a122933.MS5 W)te:

R 3ate! -anuary 2,20O6 By_____.

Rtib 7-smo 8:03:0$ AM Case Tide, Line 1.83 Q Descriptien: Revised Mdlud9 Calc. [ý-122 U"It Wt w Sched 40 & 12 in S~dd GQeon~etry: 10 Cylinder!5wrlape kztirna1 ~Pmgirnt Durrev Dimensioui 762.0 CM 25 ft RaIdius 5.08 CM 2,Q in case Poiffts

1. 1 136,24-cm 213,36 crm 4 ft 5-6 in 12 ft 6.0in 7 ft ý,Q in cyl. Cexe 5,08 cmn C'On' rot te 1,8 Shield I 7.86

.65 cM gro rt 13 2,4 Shield 3 30,48 cm Concýret e 2.4 Air C,&D Al 0.00122 7,N6 sourcl; Inputc Weepling Mtethod :Ac~tuat P~hotoni Ertesrgesi 1-129 1.0945e.ri .'O 4.04 eg+6O00 .0*00 1. ~4 Buildu4p The material reference Is . Cyl. Core Inteprationr Parameters 20 C; rcurrnfereatial 20 itosulls k~ti Fluanco Raite mr /hr 0.0295 3,407c.1033 3.3100-36 0.0298 1 .&89e+C00 8-C-A-e- 103 6.43e-f34 6.12-ge. 36 5 3.3- 0f~010i 3.2 L 5e.34 21.459e.-N 0.0396 8.943e-56 4.0364e.,58 C1-246

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Pagb ;2 IDGS File P~i 22933.MS5 Nun DaN~ January 2. 2006 Nun Time! 8:03:05 AM Duratign;0M0 IiumLawEt Flugaý2 Rate Empuma M2 Exosmaafp MML

~butidýM Ataw&a TOTALS: 3.145e*00 8.943e.56 4,064e-58 1.3 14e.35 C1-247

Plum Brook.Reactor Facility FinalStatus Survey Plan Revision 0 O1/VOVO Microgbiiuld w5.04 (5.04)03682) fud~eqc1al Seruk", Inc.

Owworshm of a 4culwted e~OVOW Ini air to dat FIU4. CMSSDATAPEU22933.MS3 This ca"e wnr oun Jatuay 2, 2006 at DI3S.0 AM OViia, Dom. Poin! 1 .(136.2V8,31213,5) cm Biu Ph~oton Flutrce Rate 0440~ Phctcypsu/yWsp 2,259904M 4.856e-032 Ptwotan 'rlffgy Fiuerice Rate MecW~en-lw 8.943a.OSG 1$5043 Epseand Dowi Rotov e",~irCe ft~ ~i Aifr Iiifthr 1.314e-035

.Absarbsd Dose Rite rn Air 3.5~4$0,060~ 1.148403Q7 Mfadihr 3,548a.058 1.1 489-035 DampDoe ivalnt Rift 0 ftae G.-W"ry F-.07&e.060 oj qctaboval 2 316eloeo 5,621 D,038 M'S.fti 2,2 15e.060 5.22 1"38 p.;, . ~pow .

51 1C9O606 1.432aeO37 3,527a.060 9.846Le*03B

• Ratatior¶;l 9 846e-038

• 4stropic 2.588e.060 7'.277e..036 oi & eieifPse r~erWfIn m~w/hr 2.9618.O6O a

1.7-90e.060 3-804e-039 oi~~ ne 1 04S-035 ro1 Iro k- ft.6W% 060 3.026a-038 I .31geO.60 Par I C1-248

Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield 0.04 (5.04-0062)

Radiologicall Servilces, Inc.

Page :1 File*Ref;___ ._

DOS File ; PBO6100*,M$S W*te:

k ate: January 4, 2006 By.

lrnrffme: 8:29-50 AM Chec1kad:______

Duration . 00,00:01 Case Thitl: Liii. 1 HB

Description:

Revised Model Calc- Sa-226 Unit Act w Sched 40 & 12 in Shild Gsarmgivy. 10 - Cyi nder Surf ace - ExternaIl Dose Point M-eight 762 .0CM 2$It Z2, in Date Points 2

1. 1 136,24 On 381 CM 2i3.36 cm 4 It 5.6 in 12 ft 5.0 in 7 ft .0 in Shields E )irrnsi MaYj

• Dyl, CaTre 5.08 cm 2' Cenc ret te 1.8 Shield I .65er lrg T1 co~ncet e 2.4 Shield 3 30.48 cmn Conefret e 2.4 Air iCop Air 0,00122 7M*

sma~rco Input 0youping Method -Standard Iidkce$

Number of Growps :25 Lawer EmerW CuIloI 0.025 Phliioons 9 0.015 , Ex-duded Library : Grov'e Nuctie Q1121,UQi=

Sn-126 1.094U-010 4,04-95e+000 4,50000-0.09 i-6650e.004.

The moallerlal referemc is,: Cyl. Care.

Integration Parameters YDiroz~on faxiWl) 20 Cir~umeren tiai uui 20 32 3,135e.01 4.557 o-292 5,B4le-35 1.613e- 293 2.023e,36 C1-249

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 Page -2 DOS File :PSO 10409. MS5 Riu.n Date; Januai#Y 4, 20($

Run Time: 8:29:50 AM Dur~ktiar, 0O0!0"1 N6 ildu~

0.03 1.1$e+C-O 4.192e-101l 4.886e-34 4,1 55e-103 4,842e.36 0104 0,06. 2,.023o.02 7.t 1go56 .2-21,0e-35 3ý698-S8 9.776e-,38 0.0's 3m88e-01 5. 534e-30 1 920c,28 1.8-59e4+30 &.664e-23 41 Z90' 21 .1.055e-25 6.535e.24 TOTALS; 3.767e'+00 6.664e-23 4.129e.21 1.055e-25 CI-250

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Mlera~leled vg..4 (LG4-OO262) 01/c414' MicreShi~eld wS.04 (S.044O=62)

Radlellogical Servi m-a,Inc, COAVUSriOm 0f CakIate3d SXpGSUre in air to &,Se FILE: C:\MS5\DATA\PO01040?iIS5 001W T11101 Lnin 1,3 H This case was run an Wedn~esda~y. Jauiuary 4l 200 at &29:50 AM Raodse (SuMi (as 81hou)a W Photon Flueswx Rate (flux) Photons/cm-t/see 8.331 e422 5,162e-020 Ph~oton Emigy Flixenc~e Rate Mev/cmz/sec 6.664".23 4-12e9*-02 Expsure and Dose Rartesw-Ex~posure Rate In Air mR/tkr 1 .05se,025 6.535c-024 Ab~unbed Dose R~ate in Air rnGy/hr 9,207e-028 S .705EL-026 a

mrad/hr 9.207e.026 5..705c.024 Cleep. C-e Equivaliont Rate (IC¶RP 51 - 1,987) a Parallel Geronrtry 9-97ge-026 QOppost" $.57 7e,028 5,3154-026 a Rotational 8.337e.028 5.166e-026 0 cIsavpie MýV~hr 8,27 7e028 5. 129e-026 Shallow D)o*e Equ y.iwalont RM',

-oParallel Geormertry 9.886,e-026 o) Oppow~ 1.173e-027 c Rotational' (ICRP 61 - 1987) 1.17:**0Z7 7.266e-0'26 cinI~ro 8.60 7e-028 Eftertiyo Does Equivalent Ratc 5,3.3c1 026 a Anterior./Posterior Geowmetry m.Sv/hr 1,353e-027 o Pnstmriorf.Aintrcrior a 1.032e-O'27 6.392e.026 o Lateral 3,9399-026 0 Rotatponai 8,787 e-028 5.445e.026 o Isctropic 7. 10e-M~ 4.4DUý026 Page 1 C1-251

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MIcraShleld Y5O41 (5.04-W362)

Radiolokigcall S~erices Inc.

File Ref; DOS~ File : RB122935-MS5 R law,: December 29. 2005 By:..___ .. ,_..

Ri, Thime: 4:09:22 Pto Chocked:_

D~uration O; 60 Case Title. iLine 1,93 1 Desriptfm: Revis* "~el "ek. Zrr-9 Unit Act w Sched 40 &12 In SW~

Geometryr 10 -Cyllindef Surface - External Dorse Point SoQurve Vimun5Wn5, Heiht 762.0)cm 25 ft Radi us 5.08 cm Dose poinrts z

1. 1

1. 1-3.24 cm 381 cm 213.36 CM 7 ft IM in Shields I enFbi a 1.8 Shield 1 .GS C cm 1ran 7.86 et e, 2,4 Shield :3 WC 48 c~m Conoret e 2.4 Air Oap Ait 0.o00122 Wq lI il1ad

?I 7, i Souce rnput Grouping Method : Attual Photon E~nergles&

Zr-9'5 1,0945e-1)10 4:0496e+000 4.,0o-5576b 1n.irm,~'O The miaterial reference Is CV1. Clore lrrtegrafion Parameters 20 0i rcumferevitia 20 Flsuhsof~t U&SWIMEl 1iý la4~1 0-7242 4-.F31 t-ý15 212ax~

Q175V. 2.24le;+00 4.27EIP-1.2 lJa9e'-1 5 TOTALS,' 4,009e+0.0 6,817e.12 1,3070-14 4,5930.13 C12526~1 C]-252

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MIVSh Icd Y5.04 (5-4O O0345 01/02M06 Uk, huid p5.04M(M.5A 6a Ccimwesk M calklated eqmwe In al! to dose FILL C4ASSWATANP8222935.MS5 Case Tl~e- LIw 1.83 1 This me was rum 0Tbwvy, wmbfr 29 2005 at 4-00:22 PM Dow Point 1 - (23&24,381,223.16) m mm .arlmr Pnluziu%. IWIau Pbtwitum Cle- Rate (flum Potnslcml/sec* 9.159e-012 3.221e.010

. MeV/err/set 6.8170.012, 2,3960.010 Exoasrt and DýwRts tcueR6te in A.A  !¶MwhV 1.3074-014 4.593e,013 Abs,,ted U

Dose Rate ýn A.r 1,141o-016 4.010Oo*015 1.14te-014 4.010e.013 (ICRP 51 - D.

cn Par~ie4 eA! r mrr/hr 1.337e.016 I t088.0016 in-Roiticarea 3.B23e-015 9.$14e.O] 7 3-3790-015 Sh3Aýt Dose Eqiiv-jilent Rate (ICRP 51 - 7W mn*/hr 1.42&e-016 5.018-r,015 o2,1Faia;lre I ,.5e0 6 4.782e-01 5 I.36le-016 4.*82-Dl 5 1,616e-015 E~ffc.ýic Do~c Euiicni RwIc (ICRP 51-197 c4 r ri Gr I 4,1 75- 015 I Q,.8-016 3719*,015 Eaet* 2.796e.01 5 7.957e.01 7 9.4 64e.O 17 3.326e-015 8.O8e..017 Page I Cl-253

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v§.04 (5.04-00362)

Radii oloicall Sefvces, Inc.

Page :1 Fih Rf;il DOS 510 ; Pei 220~6NOS Oate:

R Date., December 29, 2)05 Rimn TimeR: 4:10:54 PM Checked:

DuratiGri -:00:00;01 Case ride: line L93 J Dcsc~riptbowi; Rmnlsacl WTdeI 0014--**.1 I hoit Am wSched 40 & 12 in Wltd Qooniotry: 10 - Cyrinder Sufface - External Dose Point Height 762,0 cm 25 ft Radius 6.U8 ork 2.0 in Dose Pohits z

213,36 cm 4 ft 5.6in 12 ft U in 7 ft Q.O in I Shields Itte 1.8

'CYI. Core 5.08 7,$6 Shie'ld 1 .65 cmn' cm Ooncre trod co 2,4 Shield 3 30A cin Concorette 2.4 Air Gap .Aie 0,00122 Wal 1Vod *OU OM Irv 7,86-Source Inpui Grouping Method . Standard Indices Numbef of, Groups ; 25 Lowet taetigy Cuiof I S Lfibrary Grove Eu-1 55 1 ,0945o01 0 4,0496o+000 4,5000o.009 1.6650eI004 Buildup The materialt feletence is : Cyi. Core Integration Paramneiars 20 Ci rcumfrenrtial 20 Results E=Urr Upou're B&

Z&U,

=114=1 1.289e42 4,557e.103 5.31 le-36 4,5169-105. 5164-311 C] -254

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 PaED :2 DOS Firt ; PB122936,MS5 RVM Date: Neeembier A9 2005 Run Time: 4:10:54 PM Duration ; DOXOM 61M., 89LV 0-04 7.341e-01 2-765e.54 8,0229,34 1,223e-56 ,548o.36 0.V05 7.971C.3 2.124.4t) 2.272e.36 0.06 5,.252e.02, 7.489e.31 2.598e-29 1.4889-33 516l6e-32 0.08 4,507oi.?3 4.41ge-24

0.1 L836e-23

2,0839-2 1 TOTALS: 3.133a+GO 1o2Z5#:20 1,364e-18 ].64U-23 2,087e.,21 C1-255

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Micras-hielId vSA4 (9.04.0W362) OVIO21OG MlcroSbiield vS.04 (5.04-003~62)

Otdiaogbeal Servtcesi Inc-Cotwer~iovu of catculatad exposure Ini air to idose FILE, C4NDA OTA\P8129315.S5 Case,

Title:

Lina 1.8 J This cas was twit on Thr~ay. Diccrnbr 29, 2005 at 4;]Wh4 PM1 Dose Polint al I - (1A.4tSI 3 m6 M;5It5 (Summed meir arnecgrais UJias Xjithou Ph'oto~n Flu&hce Rate (flux) Phoaoamsfcmn:/sec 1 .2Oe- 1! 1,365e.0 17 Pmcton E.rwer Flu~eicie Rate MOVAW/sa5c 1.205e-020- 1.364e-0 18 Ex~posure anid Dose Rates-Exposure Rate In Aie MR/hr I .Me3s023 2 "067e-021 Abw.rb'cd Dow Ratiten Air rnGy/hr I .60-ge*025 Mrnrdlhr 1.&1090-023 1.1122e-02 1

• Parallel' Geornetry rnSv/ehr 2G89e.025 0

1.479e*0.S I ..670cwG'On 1.475e-025 1.670ewO23 a-I stropic 1 .427e-02.5 Sh~allow Dose Equ iva lent Rate 0 panodel Geco'nettf' mS-v./hr 2',073oNý.025 2..348e-023 o Rotational a-.073e-Q2S 2.$48e-023 o l't4ropic 1 Z5Q9-O25 1.70ge-023 (ICRP 51 1-9087)

c. Anterjor!Pcster~or Gecrwetr mnSv/hr 2..312e-025 2.618e-023 c Posexi6'r/knten~rj 2.053eo023 a Latoral I 119e,025 1 .267e.023 a Rotat4onal 1.648e-026 1. 5e03 a I uSrorpic 1 .JD'5'o23 Page 1 C1-256

Final Status Survey Plan for the Plum Brook Reactor Facility Attachment C Embedded Piping Dose Assessment & DCGL Calculation Addendum 2 MicroShield Case Run Reports for Pump Room Trench Pipe Cluster

MicroShield Case Run Reports for Pump Room Trench Pipe Cluster Index Result Reslt Run Date Case Title Description File Name (mrem/hr) 2/3/2006 Line 1.36 A PBRF Pump Room Trench with Co-60, PB020301 4.225E-13 1 ft. concrete wall shield 2/3/2006 Line 1.35 A PBRF Pump Room Trench with Co-60, PB020302 1.305E-12 1 ft. concrete wall shield PBRF Pump Room Trench with Co-60, 2/3/20061 ft. concrete wall shieldPB020303 5.920E-15 2/3/2006 Line 1.33 A PBR.F Pump Room Trench with Co-60, PB020304 8.646E-15 1 ft. concrete wall shield 2/3/2006 Line 1.*33 A PBRF Pump Room Trench with Co-60, PB020305 8.157E-19 1 ft. concrete wall shield 2/3/2006 Line 1.31 A PBRF Pump Room Trench with Co-60, PB020306 1.113E-17 1 ft, concrete wall shield C2-1

MicroSh~ec v5.05 (5.05-$2 Radk~ogqicaI Sarvycb. w c Pago :1 File Ref:

DOS$File : PiB020301 JASS Date, RUfl Dat-h FObWW~Y 3, 20C6 By:

P Time: 7:07:06 PM Ctlh1~______

DLaio~din :00:00:00 CaseridJe, Line 1.30A DascripfiorL: PBRF Pnip Rm Trench Co-80 w I ft cone wall shield ILconc core Geomery~ 10 - CylrIndEr Surfface - Extenrn4 Dome Point Saurce Oimnsl~fom Ieight 304,1 Om 10 ft 0.0 in RadiuS 12.7cm 5.0 in Dgq 1'1 1 -1. - z

1. 1 53.3 cmn 404. 8 csm Ocm 1ft3.4 in '0.0 in mbn jme~a Cy'1. Comr 12.7 Cmz, Concret 1.8 Transftkion 2.4 Air Gap Air 0.00122 Waib Clad 30.4 Ocm Concret 2.4 lmmembin Cowcete 2.4 SOaTwO Input N~uclde irupilng Mothad -Actual Pht~oln Energilus CO-50 I.0,4.5e-411 0 4.0496e4O0O 4.5NO"00eV ienal-oo Buildup!

The mhaterbil reforafta.1! ;sGyI.ý Cam hItegratton Parmaneteru Y Direclion (axial) 20 Circumferenvtial 20 Rluence Rate Fluonoe Rate ExpouoRt xaueRt bgii= With Buildup No Buildup With Buibdup 0.6938 ego~e-04 8,5e1 a 6etNi691 6e-20 1-074,0-1 j 1,1732 4 '050e+00 1.3325 4.05(1+00 9.1,29-12 1.9138-10 f.5EB4-14 3-31 Se-13; TOTALS- 8. 100e+00 1.268e, II 2.824e-10 2.21 $e114 4.947e-13 C2-2

Mcrofieb v64 J&H406.O3G) JtO 02T0*g0 Micruglhied v&.Cg (&05-003621 Radolaigical Service%. thu Corwersion of culcubde~d exposure [a air to dose FILE-. C.MNS51IATA1131=1030ItMS8 Case Tiffl Line 1.31 A Thfie cas4 was run an Fridtay, Fabrmray 3, 2006 at 7TATO5 PM 0"ao Poikit gI1 (53.3^08,0) Cm gab~ With~out With~

Fhaton Fbienoe Ride (flux) Photonscm2 /see 9,878e-01 2 2,212e-010 Phatom Eneqy Flumeo Rate 1.268"-i11 2.82,4"10O Expo~sure mid Dose Rates:

Exposure Rai* in Air mnRihr 2.21 S.-O 14 4..g47e-C-1,3 Absorbed Dose Rate InAkr mayffli 1.937e-016 4.319e*015 mrad~if I .937e-DI4 4-31ge-01 Deep Dose Equivolen Rate (ICRP 51 - 1987) c0Parsailei Geomietry mSwt4br 420O20-015 o Opposed 1.0959-016 4,2~2 Se-Q 1.695"-16 4.225e-015 olsalmtpic 3,77$e--01$

Shaflow Dose Equiva1ent R.Abe (ICRP 61 - 0957) o Par~lel r*OMGiry 5-2 17eý.015 o-Opposed 2.253e-0,16 5-G25"-O15 o Rotational 2.253em-G16 5-025"4J 5 0 150froPiG 1,703e.O016 3ý998"eOI5 Effez4ive Dose Equivalani Rate (IC-RP 51 - 190B7) ai An~ridorPoterioT Geometry mSvlhr 1.979ge-01 4Al15e-0 M o PostericriArnt-brIC 1,025e-016 4.069"V15 oLasraJ 1-.463e-016 3-239e4 $8 oRolOiaftta 1.~64U-01 6 3.064"-O15 oIs~otropic 1 Afi~e-01 6 3-244e-015 C2-3

MicroshfoId 4AU5 (A54POO621 Radkiogoicall Ssrvioe 1 be i.

Pago '1 File Ref_____

Do$ Fite :P110203012.MSS Run Data' February 3, 2006 BY:

R Tim'e: 7 33:25 PM Chwcked:____

Du, A1ion 06:00:00 Case rTie. LUne I.M A

,Dss~dptian PURF Pnip Witn Tvo"Ih Co-80 W1 ft,eone wall shielEd & cDI'bc core G~ometry 10 - Cylifinde SurfAde - Extarnall Docss Point Hteight 30418 am~ 10 ft 0.0 in Radius I

DMa~ Pohftw x z

1. ~62.2dm 40-4.8 cm 53.3 cm 2it 0,5 in 13 ft 3.4 in *It 9,0 In Whelds

.t 1m

.8 TransItIon Conc :re*e 2,4 Air Gap ir 0.00122 Wall Clad 30.46 cmn Conc rsle 2.4 lmmmricin Conc rcle 2.4 6MurM Input Grouping Mothodl Actuall Phorton EnaroGes Nudd 21c kwouems uCcrn Co-80 3-2a350a-011 1,214,90+000 4-5000"GC9 1.6650e-004 Isildup The ma4eriall rsfsrsm, e is: Cyl. G~r&

fritagratlon Par-umatafm Y Diection (axiol 20 Cirumferential 20 Wih Bild&

Noaffdu No9didim With Bui~dup 0.6938 1.9820-04 7'.447e-1 7 1410- -5 '1.48-In65l 1.1732 1.211$e+00 3A85e-1l I 5.642e-10 6.047e-1 4 9.Ma8-113 TOTALS. 2-430e+00 5.058e-I I 8.21L-10 8.857e-1 4 1.529e-12 C2-4

MicroShlotd v&.05 (5.06-00362)

MieroShleld vg.45 (5A05-MS32J)

Radibilogical Services, fnem CanvmmioM of calculatud expewam Ini mir to da FILE. GMS5MDATMPB0203O2J1S5 Case rift. U-na 1.35 A This case was run an Friday, Feb~ruary 3, 2006 at 7-33.2.5 PIN 00".F~int 0 1-ý (62.Z44J852.3) em ISuksut O'Sum med gw gerepie Without Wdht Mdup Ph~ton Fluernoa Rate (flux) 3.966a-01 I 6-058e-010 Photon Energy Ftuence Rate lpotnsvoisýMe 5.058e-011 E17216-010l Exposure and Dose Rak-o:

EXpoeure Ra2te in Air mIfAit 1,62!ýe.ol 2 Atngftd 0060 Rate in Air mGyihr 7.*732e-010B 1.33'5e-014 mrad/hr 7.732&-014 1.~3350-012 Deep Dose Equi~ua~nt Rate QICRP 51 - 1987) mSvhlhr e Opposed 7.W8e-0115 1.305e-014 a Rotationial 7.5fSle-O1 6 1.30$e-014 0 Iotropic, 1.1lef-014 88sltbw Does Equivaleml Rate ([CRP 51 - 1987) o Parallel Geomnetry rn~vlhr 9.33ge-01 0 1.6130-014 0 0pposwd 01

-1.553e.014 0oRdtsional 8.99ge-01 6 1.663e-014 7.1$8e-01 S -1.236e-014 Effective Dowe Equivalent Rate- (ICRP 51 - 1987.)

o Afteriwor.Pterlor Geornefty mrnva'hr 7.903e-01 6 1.3659-014 o Posterjorliftrior 7.284e-01 6 1.267e-014 o Ufteral 5.799"-1 B I ZOO0e-O14 o RolalioqmI 6.5~ea-01 6 1.,132a-014 0 iWa~pic: 1.902V-014 Pap I C2-5

MicroShled A5OS (6.054M3&)

Rad~aiogcall Services, Ince.

Page :1I File Ref. ____

DOS File: P020303,MSS Ron, Date; Febfury a, 2,006 By:___

R Tirme:7:2118 PM Durdticof : 00~:0.0-0 Case Mels Line 1,34 A Deacription: PBRF Pmnp Rm Trench Ca-60 w I Rconec wall shikid &cone core GdomeW.y 10 -Cylindeor Surface - External Dose Point ource Dimnslnelw Height 10 ft 0.0 in Radius 12.7 Cm 5.0 in a

x Dose Point _z 404,8on, 106.6 cm I ft 9.0in 13 R34 in 3 ft6.0 i Shigld Name Dime nsion Mati frial De"flu

-617.'aF-Transitin in oncM% 2.4 Air Gap Alr 0.00122 Wall Ciad 30.4i8cm Conc rek- 2.4 Conc ref 2.4 Scmaw Input Grouping Method ;Adtua Photon Energies NLucido Curies bmmra wudr? 11 C040, 1.0O45~-0O1 0 0496~ 4.59oooe-0ct 19W~~-O Oulhdu Th - mawrial ta~rane is Cyl, Care bntgration Parametars YDirecfibn (wdal) 20 Girturnfere~1lal 20 Mence Rate Epuug xosr Rt MeWkaN/se MeV/crmisec mRthr mRl'hr 1,90102 2.W11 3770Z 4,01 Go-21 1.1732 4.0509400 2.70e-14 1,070e,12 4.9a3e-17 1.912.e-16 9.437e-14 2,893e-12 1.637e-165119-1 TOTALS; 8.1.00e+00 1.223e-13 3.96.3-12 2.136e-16 ,6930e-15 C2-6

Page :2 DOS File: PB: 0MMSS Run Dawe February 3,200$

Run Time: 6:40:40 PM Dur*fl Q 00Ima a* I '~,

C2- 7

Mleo~h-Idd v6.06 (&CU0362) OZ'l)3m, MicroSel~d vAiS (5.05-g02)

Radfalkoical garvices Inc.

Comwrshmoa f calculabd auposIro Inair to dose FILE: C.W$bIDATAV'5O2UW3.MS5 Cm.TI~eo Um*, tS4 ThI~ isacm waa rn an Frbday, Pebnr~my 3,2M.I t T.21,18 P11 Do"e PoWc $11.1513^3448,FIGt cm Resulfts LSummed ove enews Un~ Buldu Photon Fluence Rate (flux) Pboofl~k/i~= 9.459s-014 3.08W-1 2 Fhotbn Energy Flueiocc Rato MeVk*i~/se~ 1-2230-013 3AM"e-12 Expasure and Dowe Rates:

EVosum Rata inl At mR/hr 2.136e-016 M9oea-i 5 Absfteid Dose Rate inAir mGy!Ir I .8s~-018 1,004e010 DeOP D088 Equivalert RaiD (ICRP 51 - ISM7 pParaltel Geometry M5lI~'hr 2.1 50-015 8.865".1 7 oOPP~Od l..825e418B 0 R048110nal 1.825"1O a 5.920af`1 7 o IWrvpic I .O3ie-01 Shallowv Dose Equivalent Rate fICRP 51 - 1987) 0 ParameI Geomfelry mSvlhr 2.260e-M o Opposed 2 5~-168B1 7.037"17i o R0,121l0'nM 2.1 $Be-01 8 7.W~e41 7 0so tmorpic 1.727"-18 5.803"-1 7 Effedive Dose 2quivalunt Rat. (ICRP 51-1987) o AfiterIvAWosterlor Geometry rnSvilhr I ý9e5e-ol $ 8e-01 7 M

o PotiorArtarior 91 1.757e-018 5.701 "017 otateral 1Ve~OW 8 0~41e-017 o Rolafioaft 1.683e-018 5.1t344-1I7 o15mtopic 1.402e.018 4.50e-01 7 Pao I C2-8

McroSoWel v 5,05PAGP62)

Radiaok~JaaI Sevioei hc Page :1 File Ref._

DOS File, P1302004.MS5 Date:

Run We ; February 3,2006 By:_ _

P Time: 7:34:4 PM Cheked:_

Duration :00:00:00 hieUne 1111A ma Me.

caripfion, PBRF Pmp Rm Trench CoMw ift onc iNWI hbehi & Cortcce Geometry,, 10 -Cylinder Surkeac - External nose Point SoUrMO Dimembmi Hight 304. OM M0ft.0 in Raftes~ 3.51CM 1.5 in Dose Points 7

_z i 6 22Ca 180 ini 2 ft 05 in 13 ft 3.4 ini 5 ft 3.0 in shwseo Sh~ied Namg Isc Material acp Cyl. Cora 3.81 cm2 Concrete 1.8-Transition Concrete 2.4 Air 0.00122 W3111Cw ~ 30A48 cm Concret 2.4 Immerriin Source input Grouping Melbod ;Acthial Phoaton Enarglis Nuclide curies beoguerala wCi/cm COM 3?2VW-Ol I 1.2149W+QQ 4MU00-009 S.8685(e-004 wiidup.

The materiail wlrefurei is -,Cyl. Coft Integaton pwimnters YDirection (axial) 20 20 Resufts acgivib&

04e~kMn~tsc 0,6938 1M2V 1.92i*-04 5.287o -20 4.814e-1 8 I .02le-22 9.2r4e-21 1,2!5e.+00 1.6606-1 2 8.82B001a7 1,3325 1.2 1ý5e+00 4.116o-12 2.6358-16; 7.141 e'- 15~

1.01 ge-1 3 TOTALS: 2.430eL+00 5784e-12 3.51 8e16 1.012e-04 C2-9

US=~iO Mievoghiakl 405l (U4OO3S2)

RadION9ioat 8.MICSO, 4W.

CortW~qbw of cabotiated exipure in air to do..

FU.,~ C. fOTAWM- UKRO4MS Came This: Lin I .M3A Thin cam was run an Friday, Febru"r 3,2006 at 7.-34-.4 PFA Daow Powt#I- (97.2,04.0,M) am NCUh I-SME Photon Fluenop Rate (flux)  ?,*et"SWOO I M6e-13 4.511 "e12 PhOton Eniergyr FlrIMiio Raft Z.01X-013 5.7846-012 AbsuorbeudOme RateinPi mRfv 1.012e-014 MI3Yfiw 828360.17 mM"Ih Deep Doss Eq alvie~ RaL-0 Parallel Geometry I OO'3e-O1&

o Opposed 3.57218.-

o R(olaowa 0 Irootropic mSvfhr a' 3.572"Q18 SheflW Dase Equivalent Rime o~ Paraltin Geomolry 0 Opplosed 6 463e.017 o Isalrapic 3.138"181 7.498e-017 Effvive Dow Equivildnt Rata (lCRP 51 - 109T) o Ant-erioristerior CGe-mettry tOZ8e-01T o.P00iWoItefot r o Latergl 23.106e-013 cisatopic Pap I C2-10

MIvroWel4d ADS J56OAM)

Page :1 File Ref:

D)O$ F110 . P50203OMMS5 Rijn Dat: Felbruary 3, 2006 By:

R- Time. 7:30:54 PM D61r-ijw 1 0011010 Case Tife:, Urtt 1.32 A Dsscription. PBRF Pmnp Rm Trench Ca-60 w I ft canc wal shish] I&conc core Geometry 10 -CylindesrSurface- External Dow Point Swfze, Dimonrrims Height 304.8ram 0 R0.0in I Radiv 12.7 CM 5.0 in IC DamePokfts

/ x y Z

1. 1 53.3 CM 404.8 oiri 214 an I ft 94in 13 ft 3.4 Mi 1ft 0.3 In Shields Concr*e 2,4 Air Gap Air 0,00122 Wall Clad 30.4 8 cm Con cre*

Concrete 2.4 2.4 Source Input Grouplng 1tM*Mod AcduP Ptlotn Ertries 1,665oV,-o24 OD-60 1.0945e-010 4iG49&e+090 4.50DOe-009 Bulildup Ebe maeerfaT rue~wo is;: Cyl. C"r 16ýfriion Puaruluter Y Meotln (wadai) 20 Cthumforonuai 20 Rwni~tv

___ Fluenoe Rate Fluence Rate Evsr ae xoueRt Noa Buildu With Buildup !Ntob BulduP Writh 8uildUR Dv 6.0$eO 6803e-26 I 547e-23 1,314e-28296e2 1,1732 -4.050e+00 1.36ge-1IB 9.626e-17 2.444e-21 1.720e-19 1,3325 4,0$0e.'00 B.273e-18 4.5O&e-16 1.436e-20 7.822o-19 TOTALS: 8.100e+0l0 9,64le-1 8 5,47Ce-16 1,680e-20 ,9.542e-19 C2-11

MWcroghiellI v3405 (S.05-=9~2) 0I$

WIM6 MicroSMiud MS~0 (S.0"0362)

Radiological Sarvto6 IM commresWofcalculMW exosu24re ý air to daso FILE- C41639MATAIPS020I306,MS5 Case Title, Line 1,32 A This case was run on Friday, February 3, 2006 at 7130:54 P.M Do"o Point # 1 - 153,404.B2141 cm Resutb (Summned ovier enernies~ Ul" WitJffimt Wish Photon Fluence Rate (flux) PhonskznWIse 7.374e-01 8 4.204e-D1O Phocton Energy Ftuwice Rath MeV~onfisec Exposure and~ Dose Rates:

Exposure Rafte inAir mR~r 1.680".20 9.542"-19 Absorbed.Dose Rate inAir MGY/tnr 1.466e-422 8,330e-,021 mradthr 1.4660-020 8.330"-19 Deep Dose Equivalmnt Rate (QCRP61 - 07 a Parallel Geomntry miyWhr 1.$63 "-22 9,448e.021 a Opposed 1.4369tO22 8.157e-021 0 Rotational 1.46e-022 8.1570-021 oa [SotroPIG I .2ýWe,-O22 Shallow Dose Equivalent Rate (tCRP 61 - 1087) oParaleI Geome"r rnSvlhr a Opposed 1.705"-22 9.606e-021 o Rotational I .7fl5e-O22 olsdrpic 1.359"~f22 7.71 80-021 E-faedv' Doze ýqugvalen4 RabV (ICRP 51 - 1987) c6 Atedor4~osterlor Geomeiry M$Yffir 1.08e-022 0 P"OVtioI~nterlot 1.382"-22 7.8529-0~21 a Laterat 1,103e422 6,203e.021 0 Ro4~iornal 1.245"022 7.0749-021 o lsotropt 1,10e4022 $,270e-OM1 pap I C2-12

Nicro~h~i~d v5US (540"0O362)

Radk~o~ogl Siaru'kaa Inc.

Page :1 Fil Ref:_____

DOS Fft P11020306.MS5 IJato:_____

Run Dwte: February 3,2008 By:

R Tone: 7:46:12PM Checked:

D~uiain OA 00:00:O Case 1Tib Line ili A Descriplifon PERF Pinp Rm Trenich Co-60 w 1 ft conec watl shield & conec ore IGeaom~Iry 10 - Cytltider Surface - Extermal Dose Point Source Ohmenslora Heigmt M.50M 10ftOA-0inu

• Rathus 3.51 m 1.5 Jri

/z Dose Poliils

1. 1 x cm 62.2 Z 2'66.5 a*

2 A O.5 In 13 ft3.4 ini BSft 8.9 in' Whelds 2 gaa Densit Cyl. Coare 3.81 cmz Concrele 1.8 Transitin C-on cr1el 24 Air Gap Air 0.00122 WaltM Ciad 30.44 ~cm Cioricrme- 2.4 2.4 Source Input Grouping MetiKWd ; Actual Phioton Erber gim Mulie ý2 bcueul uikm Co-SO 3.2835o-0 11 1.21490+000 4.500e-009 Buildup The naitarfa ftrafow 1 1~ Cyl. Core btrtAwitlon Parsumeture Y Dieawn(axdal) 20 20 REOuib Fluenc" Rates FuwRj j E t No Buildup Vfit Bu=NogiJIM 1.902e-04 4,1 9Ue24 7.230*'.22 0,0950-27 1.3960-24 1.215e+i00 2.,817e-17 1.683e~-15 ý.034e-20 2.829e-1 $

1i3325 1.2150+09 1.01$0-17 TOTALS: 2A30e+00 1,618e416 7AS9e-t 5 2,822e-l9 13*2e-.17 C2-13

Acroshlhe4 4505 (5,05-O0362) O*

12VJ McreShalak! v6.05 (5SO5-003112)

Radilological 8Srvicim, Inc.

Convasioon of 9aicukWuexpoeie Inairto dme FILE. C:MSfIRDATAIPB102MIS5MS5 Ca* Mmfu Lins 1.31 A Thib GiSo Wva runl on Mriay. Feiruiy 3, 2006 at 7:45:112 -PM D8ose Poilt #1 -(62.2AN04.826&5) cmn REaukIt M m nemiffý LS udoe mWU Photon FluencQ Rate (flux) Phatowc/mz/sec Photonl Erpergy Flujce Rate Nk3V/crn'sec 1.618e-G16 7.450e-015 Expaure arid DowS Rats:

Exposure Rate inAir 2;822eao1 g 1.302e-01?

Absoft~d Dms Rate hn Air .m6yhr 2.463e-021 -1.1 37e-01 g in 1,1 370-017 Deep Dowe Equivialenit Ratu' (ICU~ 51 - 07 o ParalleI Geonelr~y mSv/bir 2,794e-021 1,290e-019 o Opposed 2.41 2e-021 1.1-13e-019 o RollilofalI 11113e019 o Imtwopdc 2.11570-021 9.,949e-020 Sballow Dose Equivabent Rate IICRZP 51 - 1W)7 10 Parfilui Geometry mSv.~hr 2.972"021 1.372e-019 0OppOSed- 2.864e-~i2 1-322e-01 9 oRoakalofI UW54e-21 1.3220-019 o W&orOpiC. 2.28Ue-021 1.053,8_019 Effective Dowe Equivalent Rate3 (ICRP 51 -1W7 o~Anterior/Posterior Gearnelry m~ythr 2,51 76-021 1.1020-019 0 P00bricIA mtoriot n 2.-322e-021 1.07e.01 9 0 Latrera 8.542e-020 o RolallonaI 2.092e-021 9.6520-029 0 WsctrpiC I .85Ae-Or2I 8.5u4O20O pap l C2-14